FITNESS FOR SERVICE ASSESSENENT FOR CRYSTALLIZERS WITH CRACK LIKE FLAWS

Similar documents
Advances In ILI Allow Assessing Unpiggable Pipelines. By Lisa Barkdull and Ian Smith, Quest Integrity Group, Houston

COMPARISON BETWEEN DUCTILE TEARING ANALYSIS AND LINEAR ELASTIC FRACTURE MECHANICS ANALYSIS

Evaluation of Pipe Weld NDE Indications

Steam Turbine Critical Crack Evaluation and Ranking Cracks to Prioritize Inspection

BODY OF KNOWLEDGE API-653 ABOVEGROUND STORAGE TANK INSPECTOR CERTIFICATION EXAMINATION

Ductile Tearing Instability Assessment of a Cracked Reactor Pressure Vessel Nozzle for Larger Critical Crack Size Compared to the FAD Method

PVP PVP EFFECTS OF WELD OVERLAYS ON LEAK-BEFORE BREAK MARGINS

PROPOSED ASME SECTION III CODE CASE REDUCTION OF NDE WELD REPAIRS

BACKGROUND TO PROCEDURES IN SECTION XI OF THE ASME CODE FOR EVALUATION OF FLAWS IN NUCLEAR PIPING

Fatigue Testing and Life Estimates of Welded Flat Head Pressure Vessel Joints. Chris Hinnant Paulin Research Group Houston, TX

OBSERVATIONS ON FLAW TOLERANCE AND BRITTLE FRACTURE: THE EFFECT OF POST WELD HEAT TREATMENT

SECTION 2.0 REFERENCES

A practical appraisal method for through-wall cracks in tubular structures

Fitness-for-Service Evaluation of a Pipe with an Incomplete Penetration Flaw

Failure Assessment Diagram Constraint Used for Integrity Analysis of Cylindrical Shell with Crack

Utilizing acoustic emission testing to detect high-temperature hydrogen attack (HTHA) in Cr-Mo reformer reactors and piping during thermal gradients

PRESSURE-TEMPERATURE LIMIT CURVES

API 653 Training Course

PVP Proceedings of the ASME 2014 Pressure Vessels & Piping Conference PVP2014 July 20-24, 2014, Anaheim, California, USA

Limits of NDT. Michael Kröning

Stress Evaluation of a Typical Vessel Nozzle Using PVRC 3D Stress Criteria: Guidelines for Application

GLOBAL RATCHETING BY ELASTIC-PLASTIC FEA ACCORDING TO ASME SECTION VIII RULES

PART 2 REPAIR WELDING CONSIDERATIONS FOR Cr-Mo STEEL PRESSURE VESSELS ARTICLE 2.15 Guide for Selection of Repair Technique. Local wall Pitting

Common Operating Problems

Convection Section Failure Analysis and Fitness-for-Service Assessment*

ULTRASONIC MEASUREMENT OF RESIDUAL STRESSES IN WELDED SPECIMENS AND STRUCTURES

Pressurized Water Reactor Materials Reliability Program (QA)

Technical Presentation PVP

Detection of In-service Wet H 2 S Cracking at Reboiler Shell Weldment using Phased Array Ultrasonic Testing (PAUT)

Stress Corrosion Cracking in a Dissimilar Metal Butt Weld in a 2 inch Nozzle. Master of Engineering in Mechanical Engineering

DOUBLE WALLED PIPING SYSTEMS

POWER TURBINE STEAM CHEST LIFE ASSESSMENT. Proceedings of the ASME Power Conference POWER2010 July 13-15, 2010, Chicago, Illinois, USA

Assessment of critical defects in a PSA pressure vessel subjected to cyclical loading using BS-7910 procedures

MATERIALS OF CONSTRUCTION FOR PROCESS EQUIPMENT AND PIPING SYSTEMS

STRESS ANALYSIS USING ACTUAL COKE DRUM BULGE PROFILES A CASE STUDY. Daryl K. Rutt, Richard D. Clark. CIA Inspection Inc.

Development and Validation of an Automated Ultrasonic System for the Non- Destructive Evaluation of Welded Joints in Thermoplastic Storage Tanks

Can Today s Fracture Mechanics address Future Pipelines Integrity?

Increased plastic strains in containment steel liners due to concrete cracking and discontinuities in the containment structure

Sulfur Unit Equipment Problems and Low Silicon Carbon Steel Corrosion Gerald W. Wilks Lemont Refinery CITGO Petroleum

Module 4 Design for Assembly

TFC KAOHSIUNG FACTORY 30 KMT AMMONIA STORAGE TANK INSPECTION REPORT. By: Jackson Yang (TFC R&D Department) 01 Oct 2016

Latest SCC Issues of Core Shroud and Recirculation Piping in Japanese BWRs

API 579/ASME FFS-1 FITNESS FOR SERVICE PART 1 (LEVEL 1 & 2)

Why the Gusset Plates of I-35W Bridge Are Undersized? The Potential Risk in Today and A Proposed Bridge Safety Monitoring System *

ALLOY 600 REACTOR VESSEL HEAD PENETRATION ISSUES. Dudenstrasse 44, Mannheim, Germany. Post Office Box 355 Pittsburgh, PA ABSTRACT

Failure analysis of a structural weld using BEM

Development and validation of an automated ultrasonic system for the non-destructive evaluation of welded joints in thermoplastic storage tanks

THE EFFECTS OF FLAW SIZE AND IN-SERVICE INSPECTION ON CASS PIPING RELIABILITY

Innovations in the Integrity Management of Seam Welds in Cyclic Service

Mechanical Engineering Journal

TECHNICAL JUSTIFICATION FOR ASME CODE SECTION XI CRACK DETECTION BY VISUAL EXAMINATION

Investigation of Leakage on Water Wall Tube in a 660 MW Supercritical Boiler

LABORATORY EXPERIMENTS FOR ASSESSING THE DETECTABILITY OF SPECIFIC DEFECTS BY ACOUSTIC EMISSION TESTING

Advance Analysis of Gasket Pressure Vessel Closure System

Review of ASME Guidance Articles on Repair Strategies

Claude FAIDY, EDF (France) Overview of EDF ageing management program of safety class components

International Journal of Advance Engineering and Research Development

FAILURE ANALYSIS OF A STORAGE PUMP SHAFT

Non Destructive Inspection Technology for Thermal Power Plants

GN01 DEAERATOR CRACKING

Higher Harmonic Imaging of Crack Surfaces of SCC in Dissimilar Metal Weld with Ni-based Alloy and Fatigue Crack in Cast Stainless Steel

FRACTURE UNDER COMBINED PRIMARY AND SECONDARY STRESSES. Bob Ainsworth EDF Energy, Barnwood, Gloucester GL4 3RS, UK;

Structural Integrity and NDE Reliability I

HYBRID COMPOSITE REPAIR for OFFSHORE RISERS

PVP ALTERNATIVE ACCEPTANCE CRITERIA FOR FLAWS IN FERRITIC STEEL COMPONENTS OPERATING IN THE UPPER SHELF TEMPERATURE RANGE

ASME BPVC.CC.BPV.S Approval Date: October 7, 2015

Engineering Critical Assessment of Vintage Girth Welds

PART I PERFORMANCE OF MATERIALS IN SERVICE. Materials and Process Selection for Engineering Design: Mahmoud Farag

Appendix. Publications Effectivity Sheet For API 653 Exam Administration: 21 September 2011

Maintenance Technologies for SCC which Support Stable Operations of Pressurized Water Reactor Power Plants

Updated Design Methods for HPHT Equipment Kenneth Young, Chris Alexander, Richard Biel, Stress Engineering Services; Earl Shanks, DTC International

NAVIGATING ASME SECTION VIII (DIV.1): MANAGING YOUR PRESSURE VESSELS - PART 1 FEATURING:

Introduction to Joining Processes

A Review of Suitability for PWHT Exemption Requirements in the Aspect of Residual Stresses and Microstructures

NDE Based Finite Element Modeling & Analysis of Wall Thinning in CANDU Feeders

Welding simulations: assessment of welding residual stresses and post weld heat treatment

Standard Recommended Practice

STRESS ANALYSIS OF A 46-INCH REACTOR FEED/EFFLUENT EXCHANGER

Reducing the Risk of High Temperature Hydrogen Attack (HTHA) Failures

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION OFFICE OF NEW REACTORS WASHINGTON, DC

Bulging Assessment and Long- Term Repair of Coke Drums

RESULTS OF FEA ANALYSES AT NOZZLE/SHELL JUNCTIONS SUBJECTED TO EXTERNAL LOADS

Monitoring of Lack of Bond in a Cladded (Alloy 825) Carbon Steel Vessel by Ultrasonic Phased Array Longitudinal Waves.

CHAPTER 9 INFLUENCE OF RESIDUAL STRESSES ON THE FAILURE PRESSURE OF CYLINDRICAL VESSELS

SAMPLING AND RISK ASSESMENT METHOD FOR METALLURGICAL INSPECTION OF PIPES AND TANKS

COMPARISON OF LIMIT LOAD, LINEAR AND NONLINEAR FE ANALYSES OF STRESSES IN A LARGE NOZZLE-TO-SHELL DIAMETER RATIO APPLICATION

VERIFICATION ANALYSES FOR NEWLY DEVELOPED AUTOMATIC 3D FINITE ELEMENT CRACK PROPAGATION SYSTEM

For ASME Committee use only.

Three Dimensional Plastic Stress Analysis of Reactor Pressure Vessel Nozzle Belt

FEA & Experimental Approach for Weld Fatigue Stress Evaluation of Pressure Vessel Nozzle Joint

Condition Assessment. By Robert S. Vecchio, Ph.D., P.E.

SAFETY ASSESMENT OF PRESSURE VESSELS

Fitness for Service: Using NDT and Inspection

GENERAL CONTENTS SECTION I - NUCLEAR ISLAND COMPONENTS

ADVANCING THE STATE OF PRACTICE IN STEEL BRIDGE EVALUATION: APPLICATION OF THE MASTER CURVE AND FITNESS-FOR- SERVICE FOR EXISTING STRUCTURES

GAINS WITH ADVANCED DATA ASSESSMENT IN ILI: LEVERAGING PIPELINE DATA TO ELIMINATE RISK, PRIORITIZE AND SCHEDULE NECESSARY REPAIRS

Available online at ScienceDirect. Procedia Engineering 86 (2014 )

C. PROCEDURE APPLICATION (FITNET)

OIL TECH SERVICES, INC.

Abstract. 1. Introduction. 2. Literature Review

Transcription:

FITNESS FOR SERVICE ASSESSENENT FOR CRYSTALLIZERS WITH CRACK LIKE FLAWS Morteza K. Jafari 1, PE, Steve Wickerson 1, PE 1 MISTRAS Group, Inc., 4000 Underwood Rd., La Porte, Texas 77571 Abstract Since 2001, API 579-1/ASME FFS-1, Fitness For Service (FFS) document has been utilized by many professionals in the chemical and petroleum industry to mitigate the risk of operating process equipment with possible anomalies. A FFS assessment is an engineering analysis of equipment to determine whether it is fit for continued service. The equipment may contain flaws, may not meet current design standards, or may be subject to more severe operating conditions than the design conditions. The product of an FFS assessment is a decision to safely operate the equipment as is, or to alter, repair, monitor, or replace the equipment. Keywords: Fitness For Service, Crack Like Flaws, Crystallizer, Engineering Analysis 1. Introduction In 1990 s petrochemical plants in the United State of America and especially in Texas experienced a few catastrophic failures. These failures caused plant personnel s lives and damaged and destroyed process equipment. These failures initiated several investigations by the Occupational Safety and Health Administration (OSHA). OSHA officials were looking for processes to prevent occurrences of such accidents in the future. The results of these investigations caused OSHA to mandate the OSHA 1910.119, Process Safety Management of Highly Hazardous Chemicals. Paragraph j of this Code of Federal Regulations required that each facility under the regulations to have a formal mechanical integrity program for safe guarding against occurrence of such accidents. Many petrochemical companies had difficulties in writing the mechanical integrity program for their facilities because a document that provided rules for the evaluation of in service equipment did not exist. In 1994, American Petroleum Institute (API) formally established the Fitness For Service (FFS) committee with API 579 designation. Members from owner-user groups and technical professionals from chemical and petroleum industries and international groups from Europe, Japan, and China participated in the meetings and discussions. API released Recommended Practice RP 579 for determining FFS of pressure vessels and piping in early 2000. Later a joint committee of the American Society of Mechanical Engineers (ASME) and API worked together to release API 579-1/ASME FFS-1 in 2004. FFS assessments are quantitative engineering evaluations that are performed to demonstrate the structural integrity of an in-service component that may contain a flaw or damage. This Standard provides guidance for conducting FFS assessments using methodologies specifically prepared for pressurized equipment. These guidelines provides Standard that can be used to make run-repairreplace decisions to help determine if pressurized equipment containing flaws that have been Page 1 of 7

identified by inspection can continue to operate safely for some period of time. These FFS assessments are currently recognized and referenced by the API Codes and Standards (510, 570, & 653), and by National Board-23 as suitable means for evaluating the structural integrity of pressure vessels, piping systems and storage tanks where inspection has revealed degradation and flaws in the equipment. 2. Required Data for the Assessment The required data for the assessment of the Crystallizer vessel shell in this study was as follows: Equipment Type Pressure Vessel Material of Construction Nominal Thickness Corrosion Allowance Diameter Joint Efficiency Design Pressure Design Temperature SA 240-304 0.500 in. 0.062 in. 102 in. 85% 25 psi 500 F The vessel was externally insulated. The product inside this vessel was a mixture of Dimethyl Naphthalene Isomer. The chilled water utilized in the jacket side was about 50/50 mixture of De-Ionized Water and Ethylene until 9-12 months before the assessment and about 50/50 mixture of De-Ionized Water and Glycol Propylene Glycol since then. The vessel is heated up to 300 F for de-riming every 14 days. Other operating conditions consisted of: Item Process In Temperature Process Out Temperature* Operating Pressure Internal Vessel 165º F- 175º F 140º F - 145º F 5 psig 10 psig Vessel Jacket 70º F Chilled Water 110º F - 120º F 100 psig 110 psig * Internal vessel process out temperature is about 270º F during de-rime The vessel was fabricated in 1994 and placed in service upon construction. During a period between 1997 and 2002 cooling water was injected in the jacket. Cooling water contained chloride and the possibility of chloride stress corrosion of the jacket and shell were realized. In 2001, after removal of insulations, an inspector performed a visual examination and found through wall cracks on the jacket side of the vessel. These cracks were thought to be chloride Stress Corrosion Cracking (SCC) from the chilled cooling water. An ultrasonic shear wave examination was performed in the inner vessel wall at eight elevations. The result of this examination noted no significant indication at the time of the examination. Further internal visual examination and an API 510 internal inspection was performed on this vessel and no sign of cracking was detected. However, in October 2011 a Phased Array Scan on the inside diameter wall of this vessel was performed. The intent of the Phased Array Scan was to locate any SCC type indications that may be propagating into the vessel walls from spot welds connecting the outer jacket to the vessel. Each vessel was assigned four quadrants at 0, 90, 180, and 270 degrees. A manual raster scan was performed on areas 6 W x 2 L in each quadrant at multiple levels of scaffolding in the vessel. Scans in this vessel were performed at the bottom two levels and the top level of scaffolding at all four quadrants. A scan was also performed at the 0º quadrant on the sixth level. Numerous SCC type indications were found in these areas and each indication was assigned a number and the depth of penetration into the vessel was recorded. Depths of SCC type indications range from a low of 0.082 to a high of 0.244 with an average of approximately 0.165. Page 2 of 7

Furthermore, on November 2011 a follow up examination was performed to provide more detailed information about the nature of the flaws. The scans were performed at elevations 0-2, 19-22, and 22-26 at the 0, 90, 180, and 270 degree quadrants; also at elevations 29-32 at the 0 and 90 degree quadrants. The readings in these areas were found to be consistent to those of the previous scans performed. Depths of the SCC type indications range from 0.085 to 0.292 from the outside wall of the pressure envelope. Indications were found to have a length ranging from 0.350 to 0.800. Indications were found only in areas where spot welds have been deposited and appeared to be separated by approximately 2 vertically and horizontally. In an effort to provide as much detail as possible, it was also requested to perform a Computed Radiography inspection in an area where the insulation had been removed at the 300 to 0 degree quadrant at elevation 26. One radiographic exposure was taken covering the entire exposed area of the vessel. The radiograph provided a visual reference of the linear indications. It was found that the majority of the spot welds in the exposed areas contain indications and numerous spot welds contain multiple indications. Linear indications in exposed areas were found to be approximately 0.250 to 0.450 in length. Furthermore, a liquid penetrant examination was performed on the internal surfaces of the vessel. The result of the examination indicated that no internal surface cracks are present at the time of examination. 3. FFS Engineering Assessment A FFS assessment based on the criteria in API 579-1/ASME FFS-1 Part 9, Assessment of Crack-Like Flaws was conducted. The entire vessel shell plates were assessed. No openings, nozzles, appurtenances, or structural supports were included in the assessment. No supplemental loads were considered. Page 3 of 7

The assessment requires grouping of the crack-like flaws together in this case per figure below: The evaluation has been performed for a number of different scenarios for each vessel shell course. The effect of the depth and the length of the crack-like flaw on this vessel is documented. It is assumed that fatigue is not a factor and no active crack growth exists in the vessels. To perform FFS assessment two Finite Element Analysis (FEA) models were created. One model is a slice of the entire vessel and the other is a small section of a representative part of the vessel with a size of about 21 x 21. Both models use studs attached with roller/sliding fixtures to represent where the end of the studs are welded to the jacket. For both models the internal vessel pressure used was 25 psig and the external vessel pressure used was 175 psig. Vessel FEA Models and slice stresses A mesh around a central stud is created and a 0.050 radius where this central stud is attached to the shell for both models were allowed. The models and hand calculations indicate that the highest stressed part is where each stud is welded to the vessel. The procedure outlined in API 579 Annex D Paragraph D.2.2.3 was utilized to determine the equivalent membrane and bending stress distribution across the wall thickness of the vessel. These values were used in the crack analysis to determine the risk of failure per following: Page 4 of 7

Stress, psi y = 257472x 4-547499x 3 + 382556x 2-101073x + 10043 R² = 0.9494 Series1 Poly. (Series1) x/t in inches y = -6902.1x + 6463.8 R² = 0.4505 Plot of Stress Distribution The FEA results were utilized to calculate the Failure Assessment Diagram (FAD) detail. The FAD is used for the evaluation of crack-like flaws in components. The FAD approach was adopted because it provides a convenient, technically based method to provide a measure for the acceptability of a component with a crack-like flaw when the failure mechanism is measured by two distinct criteria: unstable fracture and limit load. Unstable fracture usually controls failure for small flaws in components fabricated from a brittle material and plastic collapse typically controls failure for large flaws if the component is fabricated from a material with high toughness. In a FFS analysis of crack-like flaws, the results from a stress analysis, stress intensity factor and limit load solutions, the material strength, and fracture toughness are combined to calculate a toughness ratio, Kr and load ratio, Lr. These two quantities represent the coordinates of a point that is plotted on a two dimensional FAD to determine acceptability. If the assessment point is on or below the FAD curve, the component is suitable for continued operation. The load ratio based on primary stress, L P r, is calculated using the reference stress for primary stress, σ P ref, and the yield strength of the material, σ ys : L P r = σ P ref / σ ys The reference stress based on primary stress, σ P ref, is based on the modified primary stress distribution and modified flaw size, and utilizes reference stress solutions based on crack-like flaw geometries. Yield strength values, σ ys, utilize either actual material test values, or nominal values based on the material specification. They are chosen at the assessment temperature. The toughness ratio, K r, is calculated using the applied stress intensity due to the primary stress distribution, K P I, the applied stress intensity due to the secondary and residual stress Page 5 of 7

distributions, K SR I, the plasticity correction factor, Ф, and the modified material toughness value, K mat : K r = ( K P I + ФK SR I ) / K mat The applied stress intensity due to the primary stress distribution, K P I, is calculated utilizing modified primary stress distributions and modified flaw sizes, and stress intensity factor solutions. The applied stress intensity due to the secondary and residual stress distributions, K SR I, is calculated using secondary and residual stress distributions, the modified flaw size, and stress intensity factor solutions. The plasticity correction factor, Ф is calculated using the stress intensity attributed to secondary and residual stresses, or load ratios. The modified material toughness value, K mat, is the mean value of the material fracture toughness modified with the partial safety factor for fracture toughness. 4. Conclusion The results of the assessment indicated that this Crystallizer vessel was fit for service at the time of evaluation. However, when considering the extend of the cracking around all the stud welds it becomes apparent that any further sharp temperature and pressure cycle should be avoided. The maximum crack length recorded is 0.800 at this time which means that there could be areas in the vessel where the defect free distance between the adjacent stud welds is only about 0.150. Furthermore, the maximum depth of crack recorded is 0.292 at this time. It is emphasized that controlling the rate of growth of these cracks is the most important factor in continuous utilization of the vessel. Therefore, it is strongly recommended to perform online monitoring of the growth of these cracks by Acoustic Emission or other instrumentation. Page 6 of 7

5.0 References: 1. Fitness-For-Service, API 579-1/ASME FFS-1, June 5, 2007 (API 579 Second Edition), The American Society of Mechanical Engineers. 2. Anderson, T.L., Fracture Mechanics Fundamentals and Applications, 3nd Edition, CRC Press, Boca Raton, Florida, 2005. 3. Anderson, P., Bergman, M., Brickstad, B., Dahlberg, L. A Procedure for Safety Assessment of Components with Cracks Handbook, 3rd Edition, SAQ/FoU-Report 96/08, SAQ Kontroll AB, Sweden, 1997. 4. Anderson, T.L., Merrick, R.D., Yukawa, S., Bray, D.E., Kaley, L. And Van Scyoc, K., Fitness-For- Service Evaluation Procedures For Operating Pressure Vessels, Tanks, And Piping In Refinery And Chemical Service, FS-26, Consultants Report, MPC Program On Fitness-For-Service, Draft 5, The Materials Properties Council, New York, N.Y., October, 1995. 5. Anderson, T.L. and Osage, D.A., API 579: A Comprehensive Fitness-For-Service Guide, International Journal of Pressure Vessels and Piping 77 (2000), pp 953-963. 6. Ainsworth, R.A., The Treatment of Thermal and Residual Stresses in Fracture Assessments, Engineering Fracture Mechanics, Vol. 24, No. 1, pp. 65-76, 1986. 7. Bloom, J.M., Deformation Plasticity Failure Assessment Diagram (DPFAD) For Materials With Non-Ramberg-Osgood Stress-Strain Curves, Journal Of Pressure Vessel Technology, American Society Of Mechanical Engineers, Vol. 117, November 1995. 8. Bloom, J.M., Deformation Plasticity Failure Assessment Diagram (DPFAD) Approach / A Fitness- For-Purpose Fracture Mechanics Based Methodology for Use in the Petrochemical Industry, PVP- Vol. 315, Fitness-for-Service and Decisions for Petroleum and Chemical Equipment, ASME, pp. 131-144, 1995. 9. Dong, P., Rahman, S., Wilkowski, G., Brickstad, B., Bergman, M., Effects Of Weld Residual Stresses On Crack Opening Area Analysis Of Pipes For LBB Applications, LBB95; Specialist Meeting On Leak-Before-Break In Reactor Piping And Vessels, Lyon, France, October, 1995. 10. Ewing, D.J.F., Simple Methods For Predicting Gas Leakage Flows Through Cracks, Paper C376/047 In Proceedings Of International Conference On Pipework Engineering And Operation, I. Mech. E., London, 21-22, Pp. 307-314, February, 1989. 11. Hazelton, W.S., Technical Report On Material Selection And Processing Guidelines For BWR Coolant Pressure Boundary Piping (Draft Report), NUREG -0313, Rev. 2, June, 1986. Page 7 of 7

FITNESS FOR SERVICE ASSESSENENT FOR VESSEL WITH CRACK LIKE FLAWS Morteza K. Jafari 1, PE, Steve Wickerson 1, PE 1 MISTRAS Group, Inc., 4000 Underwood Rd., La Porte, Texas 77571 Abstract Since 2001, API 579-1/ASME FFS-1, Fitness For Service (FFS) document has been utilized by many professionals in the chemical and petroleum industry to mitigate the risk of operating process equipment with possible anomalies. A FFS assessment is an engineering analysis of equipment to determine whether it is fit for continued service. The equipment may contain flaws, may not meet current design standards, or may be subject to more severe operating conditions than the design conditions. The product of an FFS assessment is a decision to safely operate the equipment as is, or to alter, repair, monitor, or replace the equipment. Keywords: Fitness For Service, Crack Like Flaws, Crystallizer, Engineering Analysis 1. Introduction In 1990 s petrochemical plants in the United State of America and especially in Texas experienced a few catastrophic failures. These failures caused plant personnel s lives and damaged and destroyed process equipment. These failures initiated several investigations by the Occupational Safety and Health Administration (OSHA). OSHA officials were looking for processes to prevent occurrences of such accidents in the future. The results of these investigations caused OSHA to mandate the OSHA 1910.119, Process Safety Management of Highly Hazardous Chemicals. Paragraph j of this Code of Federal Regulations required that each facility under the regulations to have a formal mechanical integrity program for safe guarding against occurrence of such accidents. Many petrochemical companies had difficulties in writing the mechanical integrity program for their facilities because a document that provided rules for the evaluation of in service equipment did not exist. In 1994, American Petroleum Institute (API) formally established the Fitness For Service (FFS) committee with API 579 designation. Members from owner-user groups and technical professionals from chemical and petroleum industries and international groups from Europe, Japan, and China participated in the meetings and discussions. API released Recommended Practice RP 579 for determining FFS of pressure vessels and piping in early 2000. Later a joint committee of the American Society of Mechanical Engineers (ASME) and API worked together to release API 579-1/ASME FFS-1 in 2004. FFS assessments are quantitative engineering evaluations that are performed to demonstrate the structural integrity of an in-service component that may contain a flaw or damage. This Standard provides guidance for conducting FFS assessments using methodologies specifically prepared for pressurized equipment. These guidelines provides Standard that can be used to make run-repairreplace decisions to help determine if pressurized equipment containing flaws that have been Page 1 of 7

identified by inspection can continue to operate safely for some period of time. These FFS assessments are currently recognized and referenced by the API Codes and Standards (510, 570, & 653), and by National Board-23 as suitable means for evaluating the structural integrity of pressure vessels, piping systems and storage tanks where inspection has revealed degradation and flaws in the equipment. 2. Required Data for the Assessment The required data for the assessment of the vessel shell in this study was as follows: Equipment Type Pressure Vessel Material of Construction Nominal Thickness Corrosion Allowance Diameter Joint Efficiency Design Pressure Design Temperature SA 240-304 0.500 in. 0.062 in. 102 in. 85% 25 psi 500 F The vessel was externally insulated. The chilled water utilized in the jacket side was about 50/50 mixture of De-Ionized Water and Ethylene until 9-12 months before the assessment and about 50/50 mixture of De-Ionized Water and Glycol Propylene Glycol since then. The vessel is heated up to 300 F for de-riming every two weeks. Other operating conditions consisted of: Item Process In Temperature Process Out Temperature* Operating Pressure Internal Vessel 165º F- 175º F 140º F - 145º F 5 psig 10 psig Vessel Jacket 70º F Chilled Water 110º F - 120º F 100 psig 110 psig * Internal vessel process out temperature is about 270º F during de-rime The vessel was fabricated in 1994 and placed in service upon construction. During a period between 1997 and 2002 cooling water was injected in the jacket. Cooling water contained chloride and the possibility of chloride stress corrosion of the jacket and shell were realized. In 2001, after removal of insulations, an inspector performed a visual examination and found through wall cracks on the jacket side of the vessel. These cracks were thought to be chloride Stress Corrosion Cracking (SCC) from the chilled cooling water. An ultrasonic shear wave examination was performed in the inner vessel wall at eight elevations. The result of this examination noted no significant indication at the time of the examination. Further internal visual examination and an API 510 internal inspection was performed on this vessel and no sign of cracking was detected. However, in 2011 a Phased Array Scan on the inside diameter wall of this vessel was performed. The intent of the Phased Array Scan was to locate any SCC type indications that may be propagating into the vessel walls from spot welds connecting the outer jacket to the vessel. Each vessel was assigned four quadrants at 0, 90, 180, and 270 degrees. A manual raster scan was performed on areas 6 W x 2 L in each quadrant at multiple levels of scaffolding in the vessel. Scans in this vessel were performed at the bottom two levels and the top level of scaffolding at all four quadrants. A scan was also performed at the 0º quadrant on the sixth level. Numerous SCC type indications were found in these areas and each indication was assigned a number and the depth of penetration into the vessel was recorded. Depths of SCC type indications range from a low of 0.082 to a high of 0.244 with an average of approximately 0.165. Furthermore, on fourth quarter of 2011 a follow up examination was performed to provide more detailed information about the nature of the flaws. The scans were performed at elevations 0-2, Page 2 of 7

19-22, and 22-26 at the 0, 90, 180, and 270 degree quadrants; also at elevations 29-32 at the 0 and 90 degree quadrants. The readings in these areas were found to be consistent to those of the previous scans performed. Depths of the SCC type indications range from 0.085 to 0.292 from the outside wall of the pressure envelope. Indications were found to have a length ranging from 0.350 to 0.800. Indications were found only in areas where spot welds have been deposited and appeared to be separated by approximately 2 vertically and horizontally. In an effort to provide as much detail as possible, it was also requested to perform a Computed Radiography inspection in an area where the insulation had been removed at the 300 to 0 degree quadrant at elevation 26. One radiographic exposure was taken covering the entire exposed area of the vessel. The radiograph provided a visual reference of the linear indications. It was found that the majority of the spot welds in the exposed areas contain indications and numerous spot welds contain multiple indications. Linear indications in exposed areas were found to be approximately 0.250 to 0.450 in length. Furthermore, a liquid penetrant examination was performed on the internal surfaces of the vessel. The result of the examination indicated that no internal surface cracks are present at the time of examination. 3. FFS Engineering Assessment A FFS assessment based on the criteria in API 579-1/ASME FFS-1 Part 9, Assessment of Crack-Like Flaws was conducted. The entire vessel shell plates were assessed. No openings, nozzles, appurtenances, or structural supports were included in the assessment. No supplemental loads were considered. The assessment requires grouping of the crack-like flaws together in this case per figure below: Page 3 of 7

The evaluation has been performed for a number of different scenarios for each vessel shell course. The effect of the depth and the length of the crack-like flaw on this vessel is documented. It is assumed that fatigue is not a factor and no active crack growth exists in the vessels. To perform FFS assessment two Finite Element Analysis (FEA) models were created. One model is a slice of the entire vessel and the other is a small section of a representative part of the vessel with a size of about 21 x 21. Both models use studs attached with roller/sliding fixtures to represent where the end of the studs are welded to the jacket. For both models the internal vessel pressure used was 25 psig and the external vessel pressure used was 175 psig. Vessel FEA Models and slice stresses A mesh around a central stud is created and a 0.050 radius where this central stud is attached to the shell for both models were allowed. The models and hand calculations indicate that the highest stressed part is where each stud is welded to the vessel. The procedure outlined in API 579 Annex D Paragraph D.2.2.3 was utilized to determine the equivalent membrane and bending stress distribution across the wall thickness of the vessel. These values were used in the crack analysis to determine the risk of failure per following: Page 4 of 7

Stress, psi y = 257472x 4-547499x 3 + 382556x 2-101073x + 10043 R² = 0.9494 Series1 Poly. (Series1) x/t in inches y = -6902.1x + 6463.8 R² = 0.4505 Plot of Stress Distribution The FEA results were utilized to calculate the Failure Assessment Diagram (FAD) detail. The FAD is used for the evaluation of crack-like flaws in components. The FAD approach was adopted because it provides a convenient, technically based method to provide a measure for the acceptability of a component with a crack-like flaw when the failure mechanism is measured by two distinct criteria: unstable fracture and limit load. Unstable fracture usually controls failure for small flaws in components fabricated from a brittle material and plastic collapse typically controls failure for large flaws if the component is fabricated from a material with high toughness. In a FFS analysis of crack-like flaws, the results from a stress analysis, stress intensity factor and limit load solutions, the material strength, and fracture toughness are combined to calculate a toughness ratio, Kr and load ratio, Lr. These two quantities represent the coordinates of a point that is plotted on a two dimensional FAD to determine acceptability. If the assessment point is on or below the FAD curve, the component is suitable for continued operation. The load ratio based on primary stress, L P r, is calculated using the reference stress for primary stress, σ P ref, and the yield strength of the material, σ ys : L P r = σ P ref / σ ys The reference stress based on primary stress, σ P ref, is based on the modified primary stress distribution and modified flaw size, and utilizes reference stress solutions based on crack-like flaw geometries. Yield strength values, σ ys, utilize either actual material test values, or nominal values based on the material specification. They are chosen at the assessment temperature. The toughness ratio, K r, is calculated using the applied stress intensity due to the primary stress distribution, K P I, the applied stress intensity due to the secondary and residual stress Page 5 of 7

distributions, K SR I, the plasticity correction factor, Ф, and the modified material toughness value, K mat : K r = ( K P I + ФK SR I ) / K mat The applied stress intensity due to the primary stress distribution, K P I, is calculated utilizing modified primary stress distributions and modified flaw sizes, and stress intensity factor solutions. The applied stress intensity due to the secondary and residual stress distributions, K SR I, is calculated using secondary and residual stress distributions, the modified flaw size, and stress intensity factor solutions. The plasticity correction factor, Ф is calculated using the stress intensity attributed to secondary and residual stresses, or load ratios. The modified material toughness value, K mat, is the mean value of the material fracture toughness modified with the partial safety factor for fracture toughness. 4. Conclusion The results of the assessment indicated that this vessel was fit for service at the time of evaluation. However, when considering the extend of the cracking around all the stud welds it becomes apparent that any further sharp temperature and pressure cycle should be avoided. The maximum crack length recorded is 0.800 at this time which means that there could be areas in the vessel where the defect free distance between the adjacent stud welds is only about 0.150. Furthermore, the maximum depth of crack recorded is 0.292 at this time. It is emphasized that controlling the rate of growth of these cracks is the most important factor in continuous utilization of the vessel. Therefore, it is strongly recommended to perform online monitoring of the growth of these cracks by Acoustic Emission or other instrumentation. Page 6 of 7

5.0 References: 1. Fitness-For-Service, API 579-1/ASME FFS-1, June 5, 2007 (API 579 Second Edition), The American Society of Mechanical Engineers. 2. Anderson, T.L., Fracture Mechanics Fundamentals and Applications, 3nd Edition, CRC Press, Boca Raton, Florida, 2005. 3. Anderson, P., Bergman, M., Brickstad, B., Dahlberg, L. A Procedure for Safety Assessment of Components with Cracks Handbook, 3rd Edition, SAQ/FoU-Report 96/08, SAQ Kontroll AB, Sweden, 1997. 4. Anderson, T.L., Merrick, R.D., Yukawa, S., Bray, D.E., Kaley, L. And Van Scyoc, K., Fitness-For- Service Evaluation Procedures For Operating Pressure Vessels, Tanks, And Piping In Refinery And Chemical Service, FS-26, Consultants Report, MPC Program On Fitness-For-Service, Draft 5, The Materials Properties Council, New York, N.Y., October, 1995. 5. Anderson, T.L. and Osage, D.A., API 579: A Comprehensive Fitness-For-Service Guide, International Journal of Pressure Vessels and Piping 77 (2000), pp 953-963. 6. Ainsworth, R.A., The Treatment of Thermal and Residual Stresses in Fracture Assessments, Engineering Fracture Mechanics, Vol. 24, No. 1, pp. 65-76, 1986. 7. Bloom, J.M., Deformation Plasticity Failure Assessment Diagram (DPFAD) For Materials With Non-Ramberg-Osgood Stress-Strain Curves, Journal Of Pressure Vessel Technology, American Society Of Mechanical Engineers, Vol. 117, November 1995. 8. Bloom, J.M., Deformation Plasticity Failure Assessment Diagram (DPFAD) Approach / A Fitness- For-Purpose Fracture Mechanics Based Methodology for Use in the Petrochemical Industry, PVP- Vol. 315, Fitness-for-Service and Decisions for Petroleum and Chemical Equipment, ASME, pp. 131-144, 1995. 9. Dong, P., Rahman, S., Wilkowski, G., Brickstad, B., Bergman, M., Effects Of Weld Residual Stresses On Crack Opening Area Analysis Of Pipes For LBB Applications, LBB95; Specialist Meeting On Leak-Before-Break In Reactor Piping And Vessels, Lyon, France, October, 1995. 10. Ewing, D.J.F., Simple Methods For Predicting Gas Leakage Flows Through Cracks, Paper C376/047 In Proceedings Of International Conference On Pipework Engineering And Operation, I. Mech. E., London, 21-22, Pp. 307-314, February, 1989. 11. Hazelton, W.S., Technical Report On Material Selection And Processing Guidelines For BWR Coolant Pressure Boundary Piping (Draft Report), NUREG -0313, Rev. 2, June, 1986. Page 7 of 7