IEEE 382 Standard for Qualification of Safety Related Actuators for Nuclear Power Generating Stations REVIEW

Transcription

1 IEEE 382 Standard for Qualification of Safety Related Actuators for Nuclear Power Generating Stations REVIEW Ed Mohtashemi GE Hitachi Nuclear November 2, 2015

2 Purpose Updates to make IEEE Std consistent with RG 1.73 R1, as applicable. Updates based on Industry needs and parent Standard updates

3 Background NRC endorsed IEEE Std with some modifications per RG 1.73 R1

4 Updates per RG 1.73 R1 Modifications ; RG Modification 1 Section 1.2 of IEEE Std references IEEE Std IEEE Standard for Quality Class 1E Equipment for Nuclear Power Generating Stations (Ref. 14) which provides guidance for demonstrating the qualification of safety related equipment including components of any interface whose failure could adversely affect the performance of safety related systems and electric equipment. As of the date of this RG, the NRC staff does not endorse IEEE Std or IEEE Std as acceptable means of meeting regulatory requirements for qualifying equipment for operations in harsh environment.

5 Standard Suggested Update No update necessary. IEEE Standard call out/version per plant specific licensing design basis in Final Safety Analysis Report (FSAR).

6 Updates per RG 1.73 R1 Modifications ; RG Modification 2 To the extent practical, auxiliary equipment (e.g. Limit Switches) that are not integral with the actuator mechanism but will be part of the installed actuator assembly should be tested in accordance with guidelines in IEEE Std

7 Standard Suggested Update No update necessary. IEEE Std , section 4.1 General includes interfaces; Safety related actuators with their interfaces

8 Updates per RG 1.73 R1 Modifications ; RG Modification 3 The applicants and licensees should perform environmental qualification of safety related actuators using the guidance in RG This testing includes a combination of type testing, operating experience, and analysis rather than just type testing and operating experience, ongoing qualification, or a combination thereof. Type testing is the preferred method of equipment qualification because other methods may be based on older or dissimilar equipment that may not be comparable to the equipment being qualified

9 Standard Suggested Update No update necessary. IEEE Std , section 5.2 Selection of actuator units for type testing includes qualification by analysis and similarity analysis of tested units and others.

10 Updates per RG 1.73 R1 Modifications ; RG Modification 4 The radiological source term for qualification tests in a nuclear radiation environment should be based on the source term methodology used in RG 1.89 or RG The containment size should be taken into account in each case. For expose organic materials, calculations should take into account both beta and gamma radiation.

11 Standard Suggested Update No update necessary. The radiological source term calculation and methodology per plant specific licensing design basis in Final Safety Analysis Report (FSAR).

12 Updates per RG 1.73 R1 Modifications ; RG Modification 5 Section 2, Normative References of IEEE Std , lists additional applicable IEEE standards. The specific applicability or acceptability of these referenced standards is discussed in the paragraphed titled Documents Discussed in Staff Regulatory Guidance in Section B of this RG

13 Standard Suggested Update No update necessary. IEEE Standard call out/version per plant specific licensing design basis in Final Safety Analysis Report (FSAR).

14 Updates per RG 1.73 R1 Modifications ; RG Modification 6 The environmental qualification criteria described in Section 6, Qualification Testing of Selected Actuators in Generic Actuator Group, and Section 7, Qualification of Actuator for Specific Application, of IEEE Std should be used to qualify actuators in generic and specific applications, respectively, unless anticipated actual service operating sequence for the actuator is expected to create a more severe impact than described in Section 6.3.2, Test Sequence and Requirements. In such case, the actual service sequence should be used in the test

15 Standard Suggested Update No update necessary. IEEE Std section identifies; An alternative sequence may be used if it is shown to be as severe or more severe than this sequence

16 Updates per RG 1.73 R1 Modifications ; RG Modification 7 Section 12.3, Test Conduct, of IEEE Std for Cycle Aging Tests, provides a representative number of cycles for the valve application. The applicant or licensee will be responsible for qualifying the actuator for its qualified life including its design cycle as specified in the design requirements for new nuclear power plants, or plants receiving license renewal for plant life extension

17 Standard Suggested Update No update necessary. Valve actuation cycles per plant specific licensing design basis in Final Safety Analysis Report (FSAR).

18 Updates per RG 1.73 R1 Modifications ; RG Modification 8 Section 14, Vibration Aging Test, of IEEE Std states that the vibration aging test is intended to provide a vibratory environment that is representative of normal plant induced vibration including system operating transients and other dynamic vibratory environments. The environmental qualification for power operated valves should also address flow induced vibration caused by acoustic resonance and hydraulic loading in the reactor, steam, and feed water systems.

19 Standard Suggested Update No update necessary; RG 1.20 Comprehensive Vibration Assessment Program For Reactor Internals During Preoperational and Initial Start up Testing in conjunction with plant system vibration test provide vibration assessment against flow induced acoustics load per plant specific licensing design basis in Final Safety Analysis Report (FSAR).

20 Updates per RG 1.73 R1 Modifications ; RG Modification 9 (9.1) Section 15.3 (b) of IEEE Std states, Each sweep shall be from 2 Hz to 35 Hz to 2 Hz, or other enveloping frequency range specified by the user. This requirement should be replaced with the following Each sweep shall be from 2 Hz to 64 Hz to 2 Hz or, if the Required Response Spectra (RRS) has a frequency range 0f exceeding 64 Hz, then the frequency sweep should be consistent with the RRS of the specific plant equipment

21 Standard Suggested Update (9.1) No update necessary; Seismic qualification of power operated valve actuator including RRS and frequency sweep requirement per plant specific licensing design basis in Final Safety Analysis Report (FSAR).

22 Updates per RG 1.73 R1 Modifications ; RG Modification 9 (9.2) Section 15.3 (c) of IEEE Std states, for HRHF site plants, at one third octave interval test frequencies indicated on Figure 1. This should be replaced with the following:.the frequency interval should be one sixth octave to adequately identify resonance frequencies. The users of IEEE Std need to address the other aspects of the qualification process (such as seismic and functional qualification) for power operated valves as described in RG

23 Standard Suggested Update (9.2) Suggested update; (Commensurate with IEEE Std ) When performing Safe Shutdown Earthquake (SSE) Required Input Motion Seismic test at HRHF (Hard Rock High Frequency) site plants, testing shall be performed as follows; Actuator SSE qualification for line mounted application at HRHF site plants should be based on performing a single frequency test by exposing the actuator to a series of sine beat tests at one third octave intervals over the frequency range of 2 Hz to 32 Hz and at one sixth octave interval over the frequency range of 32 Hz to 64 Hz or to cut off frequency whichever is higher.

24 Updates per RG 1.73 R1 Modifications ; RG Modification 10 To ensure that the actuator is tested under an environment of sufficient severity, the magnitude of the environmental conditions (e.g. temperature, pressure, radiation, humidity) that simulate the conditions to which the actuator is expected during and following a DBE (section17, DBE environment test of IEEE Std ) should be based on conservative calculations. The equipment needs to be qualified for the duration of its operational performance requirement for each applicable DBE condition, including any required post DBE operability.

25 Standard Suggested Update No update necessary; The magnitude of environmental conditions (e.g. temperature, pressure, radiation, humidity) that simulate the conditions to which the actuator is expected to be exposed during and following a DBE including post DBE operability are per plant specific licensing design basis in Final Safety Analysis Report (FSAR).

26 Schedule Review at SC 2 (15 02) Fall 2015 PAR 2015 SC 2 Approval Fall 2016 Complete Revision update Fall 2016 NPEC Approval Jan Ballot Pool Mid 2017 MEC Review Mid 2017 Re Ballot As Required TBD White paper Mid 2017 REVCom Approval Jan 2018

27 Q & A