NRC-17-0051, Submittal of Revised Relief Requests Nos. VRR-012 and VRR-013 for the Inservice Testing Program Third 10-Year Interval

Submittal of Revised Relief Requests Nos. VRR-012 and VRR-013 for the Inservice Testing Program Third 10-Year Interval

ML17216A015
Person / Time
Site:	Fermi
Issue date:	08/04/2017
From:	Polson K DTE Electric Company, DTE Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-17-0051, TAC ME2556, TAC ME2557, TAC ME2558
Download: ML17216A015 (32)

Text

August 4, 2017 10 CFR 50.55a NRC-17-0051 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

References:

1) Fermi 2

NRC Docket No. 50-341 NRC License No. NPF-43

2) DTE Electric Company Letter to NRC, "Submittal of the Inservice Testing Program Relief Requests for Pumps and Valves - Third Ten-year Interval," NRC-09-0064, dated November 3, 2009 (ML093140302)

3) DTE Electric Company Letter to NRC, "Response to Request for Additional Information Regarding Relief Request VRR-012 for the Inservice Testing Program Third Ten-Year Interval," NRC-10-0037, dated May 19, 2010 (ML101400550)

4) NRC Letter to DTE Electric Company, "Fermi 2 - Evaluation of In-Service Testing Program Relie f Requests VRR-011, VRR-012, and VRR-013 (TAC No. ME2558, ME2557, and ME2556)," dated September 28, 2010 (ML102360570)

5) NRC Letter to DTE Electric Company, "Fermi 2 Nuclear Power Plant - Issuance of Amendment to Extend Containment Leakage Test Frequency (CAC No. MF7534)," dated March 9, 2017 (ML16351A460)

6) Nuclear Energy Institute (NEI)

Topical Report, 94-01, Revision 3-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," dated July 2012 (ML12221A202)

Subject:

Submittal of Revised Relief Requests Nos. VRR-012 and VRR-013 for the Inservice Testing Program Third 10-Year Interval

USNRC NRC-17-0051

Page 2 Pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (z)(1), DTE Electric Company (DTE) hereby requests NRC approva l of the enclosed revision to relief requests, VRR-012 and VRR-013, for the Fermi 2 Power Plant. The third interval of the Fermi 2 IST Program began on February 17, 2010, and complies with the American Society of Mechanical Engi neers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), 2004 Edition, no addenda.

In Reference 2, DTE submitted relief requests for the third Inservice Testing (IST) Program 10-year interval at Fermi 2 for NRC review and approval. Specifically, VRR-012 requested relief for subject valves from the requirement of ASME OM Code ISTC-3700, which requires the Position Indication Verification Test (PIT) be performed once every 2 years, and VRR-013 requested relief from the requirement of ASME OM Code ISTC-3630(a), which requires that leakage rate testing (water) for Pressure Isolation Valves (PIVs) be performed once every 2 years. DTE provided additional information for Relief Requ est VRR-012 in Reference 3. The NRC's approval of Relief Requests VRR-012 and VR R-013 in Reference 4 stated that the proposed alternatives in the requests pr ovide reasonable assurance that the 32 PIT valves and the 15 PIVs will remain operationally ready. The approved alternatives aligned the PIT frequency and the PIV test frequency with the Fermi 2 performance-based leakage-test program outlined in 10 CFR 50 Appendix J, Option B, which allowed testing to be performed once every 60 months for components with established good performance.

In Reference 5, the NRC issued Fermi 2 a license amendment to revise TS Section 5.5.12, "Primary Containment Leakage Rate Testing Program," to reference the guidance in NEI 94-01, Revision 3-A, and conditions and limitations specified in NEI 94-01, Revision 2-A. The license amendmen t also allowed the extension of the containment isolation valve leakage test (i.e., Type C tests) from 60 months to 75 months in accordance with NEI 94-01, Revi sion 3-A for components with established good performance in the 10 CFR 50 Appendix J, Option B performance-based leakage-testing program. However, the NRC's approval of Relief Requests VRR-012 and VRR-013 (Reference 4) to align the PIT frequency and the PIV test frequency with the Fermi 2 performance-based leakage-test program outlined in 10 CFR 50 Appendix J, Option B specified that the program interval shall not exceed 60 months. Therefore, DTE is hereby submitting a revision to Relief Requests VRR-012 (see ) and VRR-013 (see Enclosure 2) to realign the testing frequency with the 10 CFR 50 Appendix J, Option B program, which now specifies an interval limit of 75 months. NRC approval of the proposed alternative is requested for the remaining duration of the Fermi 2 Third Inservice Tes ting (IST) 10-Year Interval, which started on February 17, 2010.

DTE requests NRC approval of these relief requests within one calendar year of the date of this letter.

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Page 1

C5100F002A 2 A TIP Channel A Ball Valve C5100F002B 2 A TIP Channel B Ball Valve C5100F002C 2 A TIP Channel C Ball Valve C5100F002D 2 A TIP Channel D Ball Valve C5100F002E 2 A TIP Channel E Ball Valve E11F412 2 A RHR Div II Pri. Containment Monitoring Isolation Valve E11F413 2 A RHR Div II Pri. Containment Monitoring Isolation Valve E11F414 2 A RHR Div I Pri. Containment Monitoring Isolation Valve E11F415 2 A RHR Div I Pri. Containment Monitoring Isolation Valve E41F400 2 A Pri. Containment Mon itoring (PCM) - Suppression Pool E41F401 2 A Pri. Containment Mon itoring (PCM) - Suppression Pool E41F402 2 A Pri. Containment Mon itoring (PCM) - Suppression Pool E41F403 2 A Pri. Containment Mon itoring (PCM) - Suppression Pool P34F401A 1 A Post Accident Sampling (PAS) V13-7360 P34F401B 1 A Post Accident Sampling (PAS) V13-7361 P34F403A 2 A Post Accident Sampling (PAS) V13-7364 P34F403B 2 A Post Accident Sampling (PAS) V13-7365 P34F404A 2 A Post Accident Sampling (PAS) V13-7374 P34F404B 2 A Post Accident Sampling (PAS) V13-7375 P34F405A 2 A Post Accident Sampling (PAS) V13-7366 P34F405B 2 A Post Accident Sampling (PAS) V13-7367 P34F406A 2 A Post Accident Sampling (PAS) V13-7376 P34F406B 2 A Post Accident Sampling (PAS) V13-7377 P34F407 2 A Post Accident Sampling (PAS) V13-7368 P34F408 2 A Post Accident Sampling (PAS) V13-7369 P34F409 2 A Post Accident Sampling (PAS) V13-7378 P34F410 2 A Post Accident Sampling (PAS) V13-7379 T50F412A 2 A Pri. Containment Torus Level Monitoring Division 1 T50F412B 2 A Pri. Containment Torus Level Monitoring Division 2 T50F450 2 A Pri. Containment Radiation Monitoring System Inlet Isolation Valve T50F451 2 A Pri. Containment Radiation Monitoring System Outlet Isolation

Valve T50F458 2 A Pri. Cont Atmospheric Monitori ng (PCAM) Division 2 Penetration X-27F Remote Manual Solenoid Valve to NRC-17-0051

Page 2 ASME OM Code 2004 Edition, no Addenda ISTC-3700 "Position Verification Testing," states that "Valves with remote position indicators shall be observed locally at l east once every 2 years to verify that valve operation is accurately indicated."

Pursuant to 10 CFR 50.55a, "Code s and Standards", paragraph (z)(1), relief is requested from the requirement of ASME OM Code ISTC-3700 for the subject valves. The proposed alternative will provide an acceptable level of quality and safety. Reducing the number of tests involving set-up of Leak Rate Monitors, tubing, etc. every two years will reduce overall dose.

Relief is requested from performing the posit ion indication verification test (PIT) on a two year frequency. Recent historical data was used to identify that PIT alone each refuel outage (each 18 months) incurs a total dose of approximately 700 mRem. The NRC's approval of the proposed alternative in VRR-012, Revision 0, re sulted in the PIT frequency being aligned with the Fermi 2 performance-based leakage-test program outlined in 10 CFR 50 Appendix J, Option B with a test interval limit of 60 months.

VRR-012, Revision 1, proposes that position indication verification will be performed at a frequency commensurate with the 10 CFR 50 Appendix J, Option B performance-based leakage testing program at Fermi 2, wh ich incorporates NEI 94-01, Revision 3-A (ADAMS Accession No. ML12221A202), and the conditions and limitations specified in NEI 94-01, Revision 2-A.

The Fermi 2 program which implements 10 CFR 50 Appendix J, Option B requires individual containment isolation valves to be good performers before they can be placed on extended seat leakage testing frequency. Assuming all of the PIT valves are classified as good performers, the extended test inte rvals would provide for a savings of approximately 2100 mRem (700 mRem above the 1400 mRem savings realized through the previously approved test interval limit of 60 months in VRR-012, Revision 0) over a 75-month period.

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Page 3 In accordance with ISTC-3700, where local observation is not possible, other indications shall be used to verify valve position. The method used at Fermi 2 is a pressure test using

the local leakage rate testing equipment. This method involves pressurizing the containment penetration volume to approximately 56.5 psig [pounds per square inch gauge], and verifying the penetration remains pressurized while the valve is indicating closed on the main control room board. Th e valve is then opene d using the control switch in the main control room. A decrease in pressure is then verified along with valve position indicating open in the main control room. This method satisfies the requirement for position indication verification and ensures that the indicating system accurately reflects the valve position.

The subject valves are all in category A and are all containment isol ation valves per the plant safety analysis. All of the subject valves have a safety function to close in order to isolate containment during a Loss of Cool ant Accident (LOCA) when required.

Since these valves are containment isolation valves, they are each individually seat leakage tested in accordance with 10 CFR 50 Appendix J, Option B.

The subject valves are designed such that the position of the va lve is not locally observable. The design of these valves is such that the coil position is internal to the valve body and not observable in either the energized or de-energized state. See Attachment 1 - Typical Solenoid Valve Arrangement, which is typical for the subject valves.

For the subject valves, Fermi 2 will perform the position indication verification in conjunction with the seat leakage test at a frequency in accordance with 10 CFR 50 Appendix J, Option B. This interval may be adjusted to a frequency of testing commensurate with the Option B of 10 CF R 50 Appendix J Type C leakage testing, which is based on valve seat leakage performance.

Each of these valves are seat leakage tested using local leakage rate testing equipment (i.e., Local Leakage Rate Monitors (LRMs)), and the current leakage rate tests have been modified to also perform the position indication verification test at the same time. The individual valve being tested must have its system properly draine d, vented, and aligned correctly prior to performing the seat leakag e test or the position indication verification, per code requirements. The radiation exposure and the Operations/Test personnel time/labor involved will be significantly reduced by performing th e position indication verification test at the same interval (fre quency) as the 10 CFR 50 Appendix J, Option B to NRC-17-0051

Page 4 seat leakage test. A sample of PIT historical data has been provided in Attachment 2 and a sample of Local Leakage Rate Test historic al data has been provided in Attachment 3.

In addition, each of these subject valves are exercised on a quarterly or refueling frequency and their stroke times are measured and compared to the ASME OM Code ISTC-5152 "Stroke Test Acceptance Criteria," which states "Test results shall be compared to referenced values establishe d in accordance with ISTC-3300, ISTC-3310, or ISTC-3320." By continuing this valve exercising, the performance of the position indication verification, and the seat leakage test in accordance with 10 CFR 50 Appendix J, Option B, an adequate assessment of valve health may be determined. A sample of the stroke time history for each valve has been provided in Attachment 4.

These PIT valves are also subject to Preven tive Maintenance program coverage, in which preventive maintenance activities are performed periodically to satisfy Environmental Qualifications (EQ) Program criteria. Any maintenance that is performed on these valves which might affect position indication will be followed by applicable Post Maintenance Testing (PMT) including PIT. EQ Program maintenance information has been provided in Attachment 5.

In 1996, Fermi 2 received a Safety Evaluation (Technical Specification Amendment No. 108) with approval to implement Option B of the 10 CFR 50 Appendix J Program. This program permits the extension of the A ppendix J seat leakage testing to a frequency corresponding to the specific valve performance. Valves whose leakage test results indicate good performance may have their interv al of testing increased based on these test results.

On March 9, 2017, Fermi 2 received a Safe ty Evaluation (Technical Specification Amendment No. 205) with approval to implement NEI 94-01, Revision 3-A (ADAMS accession No. ML12221A202) and the conditions and limitations specified in NEI 94-01, Revision 2-A, to implement the performance-based leakage-testing program in accordance with 10 CFR 50 Appendix J, Option B. This Amendment increased the containment isolation valves leakage test intervals (i.e., Type C tests) from 60 months to 75 months. The Fermi 2 program which implements 10 CFR 50 Appendix J, Option B requires individual containment isolation valves to be good performers before they can be placed on extended seat leakage testing frequency. Based on the data contained in Attachment 3, all the listed valves have passed their last three PIT Local Leakage Rate Tests.

In conclusion, the ability to detect degradation and ensure the operational readiness of the subject valves to perform th eir intended function is not jeopardized by performing the position indication verification test at the same frequency as specified by 10 CFR 50 to NRC-17-0051

Page 5 Appendix J, Option B. This frequency of te sting provides reasonab le assurance of the operational readiness of the subject valves a nd provides an acceptable level of quality and safety.

This proposed alternative is for the remaining duration of the Femi 2 Third Inservice Testing (IST) 10-Year Interval, which started February 17, 2010.

NRC Safety Evaluation Report: Kewaunee Nuclear Power Plant - Fourth 10-Year Inservice Testing Interval Program Requests for Relief (TAC Nos. MC4182, MC4183, MC4184, and MC4185), dated March 4, 2005 (ML050380305) NRC Safety Evaluation Report: Fermi 2 - Ev aluation of In-Servi ce Testing Program Relief Requests VRR-011, VRR-012, and VRR-013 (TAC No. ME2558, ME2557, and ME2556), dated September 28, 2010 (ML102360570) Attachment 1 - Typical Solenoid Valve Arrangement Attachment 2 - Position Indication Test History Sample (Last Three Tests) Attachment 3 - Position Indication Test Valve Local Leakage Rate Test History Sample (Last Three Tests) - Stroke Time History Sample - Position Indication Test EQ Program Maintenance to NRC-17-0051

Page 6 Attachment 1 - Typical Solenoid Valve Arrangement

1 Cover Bolts 10 Seal 2 Locknu t 11 Nameplate 3 Cove r 12 Strap 4 O-Ring 14 Buckle 5 Bol t 15 Bol t 6 Lockwashe r 16 Lockwashe r 8 Switch Block Assy.17Space r 9 Coil Shell Assy.

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Page 7 Attachment 2 - Position Indication Test History Sample (Last Three Tests)

C5100F002A 4/10/2017 PASS 43.401.338 4/15/2012 PASS 4/15/2009 PASS C5100F002B 4/10/2017 PASS 43.401.337 4/15/2012 PASS 4/15/2009 PASS C5100F002C 4/10/2017 PASS 43.401.339 4/15/2012 PASS 4/15/2009 PASS C5100F002D 4/10/2017 PASS 43.401.341 4/15/2012 PASS 4/15/2009 PASS C5100F002E 4/10/2017 PASS 43.401.340 4/15/2012 PASS 4/15/2009 PASS E11F412 4/2/2017 PASS 43.401.331 4/20/2012 PASS 4/12/2009 PASS E11F413 4/2/2017 PASS 43.401.332 4/23/2012 PASS 4/12/2009 PASS E11F414 3/21/2017 PASS 43.401.350 4/7/2012 PASS 4/5/2009 PASS E11F415 3/21/2017 PASS 43.401.351 4/7/2012 PASS 4/5/2009 PASS E41F400 3/25/2017 PASS 43.401.379 4/8/2012 PASS 4/6/2009 PASS to NRC-17-0051

Page 8 Attachment 2 - Position Indication Test History Sample (Last Three Tests)

E41F402 4/11/2017 PASS 43.401.378 4/21/2012 PASS 4/9/2009 PASS P34F401A 11/3/2015 PASS 43.401.329 11/3/2010 PASS 4/10/2009 PASS P34F401B 11/15/2015 PASS 43.401.346 11/4/2010 PASS 4/10/2009 PASS P34F403A 3/5/2014 PASS 43.401.324 4/11/2012 PASS 6/30/2009 PASS P34F403B 3/5/2014 PASS 43.401.359 4/11/2012 PASS 7/16/2009 PASS P34F404A 3/12/2014 PASS 43.401.324 3/5/2014 PASS 4/11/2012 PASS P34F404B 3/5/2014 PASS 43.401.359 4/11/2012 PASS 7/16/2009 PASS P34F405A 3/4/2014 PASS 43.401.387 4/11/2012 PASS 3/4/2009 PASS P34F405B 3/17/2014 PASS 43.401.386 4/11/2012 PASS 3/4/2009 PASS P34F406A 9/28/2015 PASS 43.401.387 3/4/2014 PASS 4/11/2012 PASS to NRC-17-0051

Page 9 Attachment 2 - Position Indication Test History Sample (Last Three Tests)

P34F406B 3/17/2014 PASS 43.401.386 4/11/2012 PASS 3/4/2009 PASS P34F408 3/2/2014 PASS 43.401.383 2/24/2010 PASS 4/30/2008 PASS P34F410 3/2/2014 PASS 43.401.383 9/18/2013 PASS 2/24/2010 PASS T50F450 1/21/2015 PASS 43.401.354 1/14/2015 PASS 1/19/2011 PASS T50F451 4/14/2015 PASS 43.401.383 1/19/2011 PASS 1/22/2009 PASS T50F458 3/5/2013 PASS 43.401.389 3/12/2010 PASS 3/11/2008 PASS E41F403 4/11/2017 PASS 43.401.400 4/16/2012 PASS 4/10/2009 PASS E41F401 3/25/2017 PASS 43.401.401 4/8/2012 PASS 4/5/2009 PASS P34F407 3/5/2014 PASS 43.401.405 1/6/2010 PASS 1/9/2008 PASS P34F409 3/5/2014 PASS 43.401.405 1/6/2010 PASS 1/9/2008 PASS to NRC-17-0051

Page 10 Attachment 2 - Position Indication Test History Sample (Last Three Tests)

T50F412A 3/24/2017 PASS 43.401.402 4/27/2012 PASS 4/13/2012 PASS T50F412B 3/5/2014 PASS 43.401.403 4/11/2012 PASS 4/13/2009 PASS to NRC-17-0051

Page 11 Attachment 3 - Position Indication Test Valve Local Leakage Rate Test (LLRT) History Sample (Last Three Tests)

C5100F002A 4/10/2017 2.00 0.05 SAT 43.401.338 4/15/2012 0.05 SAT 10/19/2007 0.05 SAT C5100F002B 4/10/2017 2.00 0.05 SAT 43.401.337 4/15/2012 0.05 SAT 10/19/2007 0.05 SAT C5100F002C 4/10/2017 2.00 0.05 SAT 43.401.339 4/15/2012 0.05 SAT 10/19/2007 0.05 SAT C5100F002D 4/10/2017 2.00 0.05 SAT 43.401.341 4/15/2012 0.05 SAT 10/19/2007 0.05 SAT C5100F002E 4/10/2017 2.00 0.05 SAT 43.401.340 4/15/2012 0.05 SAT 10/19/2007 0.05 SAT E11F412 4/2/2017 2.00 0.13 SAT 43.401.331 4/20/2012 0.05 SAT 10/3/2007 0.05 SAT E11F413 4/2/2017 2.00 0.14 SAT 43.401.332 4/23/2012 0.09 SAT 10/3/2007 0.05 SAT E11F414 3/21/2017 2.00 0.11 SAT 43.401.350 4/7/2012 0.08 SAT 10/20/2007 0.05 SAT E11F415 3/21/2017 2.00 0.10 SAT 43.401.351 4/7/2012 0.07 SAT 10/20/2007 0.11 SAT to NRC-17-0051

Page 12 Attachment 3 - Position Indication Test Valve Local Leakage Rate Test (LLRT) History Sample (Last Three Tests)

E41F400 3/25/2017 2.00 0.05 SAT 43.401.379 4/8/2012 0.05 SAT 10/20/2007 0.15 SAT E41F402 4/11/2017 2.00 0.11 SAT 43.401.378 4/21/2012 0.17 SAT 10/11/2007 0.20 SAT P34F401A 11/3/2015 1.00 0.05 SAT 43.401.329 11/3/2010 0.05 SAT 4/3/2006 0.05 SAT P34F401B 11/15/2015 1.00 0.05 SAT 43.401.346 11/4/2010 0.05 SAT 4/10/2009 0.05 SAT P34F403A 3/5/2014 1.00 0.16 SAT 43.401.324 4/11/2012 0.05 SAT 4/2/2007 0.08 SAT P34F403B 3/5/2014 1.00 0.07 SAT 43.401.359 4/11/2012 0.05 SAT 4/17/2007 0.08 SAT P34F404A 3/5/2014 1.00 0.05 SAT 43.401.324 4/11/2012 0.05 SAT 4/4/2007 0.08 SAT P34F404B 3/5/2014 1.00 0.14 SAT 43.401.359 4/11/2012 0.17 SAT 4/17/2007 0.13 SAT P34F405A 3/4/2014 1.50 0.68 SAT 43.401.387 4/11/2012 0.18 SAT 5/16/2007 0.20 SAT to NRC-17-0051

Page 13 Attachment 3 - Position Indication Test Valve Local Leakage Rate Test (LLRT) History Sample (Last Three Tests)

P34F405B 3/17/2014 1.00 0.14 SAT 43.401.386 4/11/2012 0.12 SAT 5/16/2007 0.18 SAT P34F406A 9/28/2015 1.00 0.49 SAT 43.401.387 3/4/2014 0.61 SAT 4/11/2012 0.05 SAT P34F406B 3/17/2014 1.00 0.15 SAT 43.401.386 4/11/2012 0.10 SAT 5/16/2007 0.17 SAT P34F408 3/2/2014 1.00 0.22 SAT 43.401.383 4/30/2008 0.18 SAT 1/31/2006 0.20 SAT P34F410 3/2/2014 1.00 0.09 SAT 43.401.383 9/18/2013 0.11 SAT 10/14/2007 0.05 SAT T50F450 1/14/2015 2.00 0.05 SAT 43.401.354 1/19/2011 0.05 SAT 1/23/2007 0.05 SAT T50F451 4/14/2015 2.00 0.05 SAT 43.401.383 1/19/2011 0.21 SAT 1/23/2007 0.05 SAT T50F458 3/5/2013 2.00 0.05 SAT 43.401.389 3/11/2008 0.05 SAT 3/16/2004 0.05 SAT to NRC-17-0051

Page 14 Attachment 3 - Position Indication Test Valve Local Leakage Rate Test (LLRT) History Sample (Last Three Tests)

ValveNumberAcceptanceCriteria(mL/min)MeasuredValue(mL/min)StatusProcedureNumberE41F403 4/11/2017 3785.00 0.00 SAT 43.401.400 4/16/2012 0.00 SAT 10/11/2007 0.00 SAT E41F401 3/25/2017 3785.00 0.00 SAT 43.401.401 4/8/2012 0.00 SAT 10/20/2007 0.00 SAT P34F407 3/5/2014 500.00 0.00 SAT 43.401.405 1/9/2008 0.00 SAT 1/14/2004 41.80 SAT P34F409 3/5/2014 500.00 0.00 SAT 43.401.405 1/9/2008 0.00 SAT 1/14/2004 34.80 SAT T50F412A 3/24/2017 3785.00 19.30 SAT 43.401.402 4/13/2012 16.24 SAT 10/20/2007 0.00 SAT T50F412B 3/5/2014 3785.00 0.00 SAT 43.401.403 4/11/2012 2.32 SAT 10/12/2007 0.00 SAT Legend: SAT is Satisfactory SCFH is Standard Cubic Feet per Hour mL/min is milliliters per minute to NRC-17-0051

Page 15 Attachment 4 - Stroke Time History Sample C5100F002A Closed 2 Sec. 4/29/20170.5 1/22/20170.5 10/22/20160.2 C5100F002B Closed 2 Sec. 4/29/20170.3 1/22/20170.4 10/22/20160.3 C5100F002C Closed 2 Sec. 4/29/20170.4 1/22/20170.4 10/22/20160.3 C5100F002D Closed 2 Sec. 4/29/20170.4 1/22/20170.5 10/22/20160.3 C5100F002E Closed 2 Sec. 4/29/20170.4 1/22/20170.4 10/22/20160.2 E11F412 Closed 2 Sec. 4/8/2017 0.7 11/8/20160.6 10/12/20150.9 E11F413 Closed 2 Sec. 4/8/2017 0.7 11/8/20160.6 10/12/20150.5 E11F414 Closed 2 Sec. 3/24/20170.4 11/8/20160.5 10/31/20150.5 E11F415 Closed 2 Sec. 3/24/20170.2 11/8/20160.4 10/31/20150.3 E41F400 Open 2 Sec. 6/18/20170.2 5/18/20170.5 4/21/2017 0.2 E41F400 Closed 2 Sec. 6/18/20170.3 5/18/20170.4 4/21/2017 0.2 E41F401 Open 2 Sec. 6/18/20170.3 5/18/20170.3 4/21/2017 0.2 E41F401 Closed 2 Sec. 6/18/20170.4 5/18/20170.4 4/21/2017 0.2 E41F402 Open 2 Sec. 5/28/20170.3 3/16/20170.3 11/29/20160.3 E41F402 Closed 2 Sec. 5/28/20170.4 3/16/20170.3 11/29/20160.5 E41F403 Open 2 Sec. 5/28/20170.4 3/29/20170.2 11/29/20160.5 E41F403 Closed 2 Sec. 5/28/20170.4 3/29/20170.2 11/29/20160.4 P34F401A Closed 2 Sec. 5/8/2017 0.8 2/6/2017 0.4 11/18/20160.9 P34F401B Closed 2 Sec. 7/10/20170.4 6/5/2017 0.5 5/8/2017 0.4 P34F403A Closed 2 Sec. 5/8/2017 0.5 2/6/2017 0.4 11/8/2016 0.3 P34F403B Closed 2 Sec. 5/8/2017 0.4 2/6/2017 0.3 11/8/2016 0.3 P34F404A Closed 2 Sec. 5/8/2017 0.4 2/6/2017 0.3 11/8/2016 0.3 P34F404B Closed 2 Sec. 5/8/2017 0.3 2/6/2017 0.3 11/8/2016 0.2 P34F405A Closed 2 Sec. 5/8/2017 0.4 2/6/2017 0.2 11/8/2016 0.2 P34F405B Closed 2 Sec. 5/8/2017 0.3 2/6/2017 0.3 11/8/2016 0.3 P34F406A Closed 2 Sec. 5/8/2017 0.3 2/6/2017 0.3 11/8/2016 0.2 to NRC-17-0051

Page 16 Attachment 4 - Stroke Time History Sample

P34F406B Closed 2 Sec. 5/8/2017 0.3 2/6/2017 0.3 11/8/2016 0.3 P34F407 Closed 2 Sec. 5/8/2017 0.3 2/6/2017 0.3 11/8/2016 0.4 P34F408 Closed 2 Sec. 5/8/2017 0.3 2/6/2017 0.3 11/8/2016 0.3 P34F409 Closed 2 Sec. 5/8/2017 0.3 2/6/2017 0.3 11/8/2016 0.3 P34F410 Closed 2 Sec. 5/8/2017 0.3 2/6/2017 0.3 11/8/2016 0.3 T50F412A Open 2 Sec. 6/18/20170.4 5/18/20170.6 4/21/2017 0.4 T50F412A Closed 2 Sec. 6/18/20170.8 5/18/20170.6 4/21/2017 0.7 T50F412B Open 2 Sec. 6/26/20170.5 5/28/20170.4 5/1/2017 0.5 T50F412B Closed 2 Sec. 6/27/20170.4 5/28/20170.7 5/1/2017 0.6 T50F450 Closed 2 Sec. 4/21/20170.5 1/19/20170.3 10/19/20160.5 T50F451 Closed 2 Sec. 4/21/20170.4 1/19/20170.3 10/19/20160.5 T50F458 Open 2 Sec. 5/28/20170.4 3/16/20170.3 11/29/20160.3 T50F458 Closed 2 Sec. 5/28/20170.4 3/16/20170.3 11/29/20160.5 to NRC-17-0051

Page 17 Attachment 5 - Position Indication Test EQ Program Maintenance E11F412 E156 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 4/19/2012 Q011 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/16/2003 E11F413 E157 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 4/26/2012 E011 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/22/2003 E11F414 E158 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 4/5/2012 E088 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/5/2003 E11F415 E159 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 4/5/2012 E090 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/5/2003 E41F400 E436 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 4/6/2012 E093 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/11/2003 E41F402 E437 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 4/20/2012 E099 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/8/2003 P34F401A H185 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 10/25/2015 E160 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 10/25/2015 P34F401B P237 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 11/1/2015 E161 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 11/1/2015 P34F403A H189 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 3/6/2014 H176 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 2/11/2005 to NRC-17-0051

Page 18 Attachment 5 - Position Indication Test EQ Program Maintenance

P34F403B H190 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 2/20/2014 H184 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 11/16/2004 P34F404A H191 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 3/2/2014 E191 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 2/11/2005 P34F404B H200 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 2/20/2014 E192 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 1/31/2005 P34F405A H201 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 3/6/2014 E194 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/8/2005 P34F405B H202 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 2/25/2014 E195 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 5/27/2005 P34F406A H203 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 3/2/2014 H193 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/8/2005 P34F406B H204 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 2/20/2014 H196 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 5/27/2005 P34F408 P284 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 2/16/2014 H198 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 5/5/2005 P34F410 H208 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 2/16/2014 E202 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 5/5/2005 to NRC-17-0051

Page 19 Attachment 5 - Position Indication Test EQ Program Maintenance

T50F450 U367 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 1/13/2015 U360 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/28/2005 T50F451 U368 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 4/14/2015 U362 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/28/2005 P34F407 H205 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 3/6/2014 H197 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/15/2005 P34F409 H207 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 3/6/2014 E199 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/15/2005 T50F412A T608 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 4/12/2012 E208 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 4/9/2003 T50F412B T610 Replace 10 Year Components Required by NE-6.6-EQMS.070 Y 10 3/5/2014 E217 Replace 20 Year Components Required by NE-6.6-EQMS.070 Y 20 11/20/2004 Note: Valves C5100F002A through E, E41F401, E41F403, and T50F458 are EQ Cat 2C, therefore no periodic EQ part replacements are specified.

to NRC-17-0051

Page 1

Valve No.

Description Appendix J, Option B Air Tested Code Class E1100F050A RHR Div. 1 Inbd Isolation Testable Check Valve N 1 E1100F050B RHR Div. 2 Inbd Isolation Testable Check Valve N 1 E1150F008 RHR Div. 1 & 2 Shutdown Cooling Outboard

Cont. Isol. Valve Y 1 E1150F009 RHR Div. 1 & 2 Shutdown Cooling Inbd Cont.

Isol. Valve Y 1 E1150F015A RHR Div. 1 Low Pressure Coolant Injection (LPCI) Inbd Isolation Valve N 1 E1150F015B RHR Div. 2 Low Pressure Coolant Injection (LPCI) Inbd Isolation Valve N 1 E1150F608 RHR Shutdown Cooling Inbd Inlet Isolation

Bypass Valve Y 1 E2100F006A Core Spray (CS) Div. 1 Inbd Primary Containment (PC) Check Valve Y 1 E2100F006B Core Spray (CS) Div. 2 Inbd Primary Containment (PC) Check Valve Y 1 E2150F005A Core Spray (CS) Div.1 Inbd Isolation Valve Y 1 E2150F005B Core Spray (CS) Div.2 Inbd Isolation Valve Y 1 E4150F006 HPCI Main Pump Outlet to Feedwater Isolation

Valve Y 1 E4150F007 HPCI Main Pump Discharge Isolation Valve N 2 E5150F012 Reactor Core Isolation Cooling (RCIC) Pump

Discharge Isolation Valve N 2 E5150F013 Reactor Core Isolation Cooling (RCIC) Pump

Supply To Feedwater Header Isolation Valve Y 1 ASME OM Code 2004 Edition, no Addenda

to NRC-17-0051

Page 2 ISTC-3630, "Leakage Rate for other than Containment Isolation Valves," states that "Category A valves with a leakage requirement not based on an Owner's 10 CFR 50, Appendix J program, shall be tested to verify their seat leakages within acceptable limits. Valve closure before seat leakage testing shall be by using the valve operator with no additional closing force applied."

ISTC-3630(a), "Frequency," stat es that "tests shall be c onducted at least once every 2 years."

Pursuant to 10 CFR 50.55a, "Code s and Standards," paragraph (z)(1), relief is requested from the requirement of ASME OM Code ISTC

-3630(a). The basis of this relief request is that the proposed alternative would provide an acceptable level of quality and safety.

ISTC-3630(a) requires that leakage rate testi ng (water) for pressure isolation valves (PIV) be performed at least once ev ery two years. The radia tion exposure and the personnel time involved will be significantly reduced by performing the PIV test at the same interval (frequency) as the 10 CFR 50 Appendix J "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," Option B "Performance-Based Requirements," seat leakage test. Recent histor ical data was used to identify that PIV testing alone each refuel outage (each 18 months) incurs a total dose of approximately 900 mRem. The reason for this relief request is to reduce outage dose and to align the PIV test frequency to the Appendix J, Option B test frequency.

The NRC's approval of the proposed alternativ e in VRR-013, Revision 0, resulted in the PIV test frequency being aligned with the Fermi 2 performance-based leakage-test program outlined in 10 CFR 50 Appendix J, Option B but with a test interval limit of 60 months. VRR-013, Revision 1, proposes that PIV testing will be performed at a frequency commensurate with the 10 CFR 50 Appendix J, Option B performance-based leakage testing program at Fermi 2, wh ich incorporates NEI 94-01, Revision 3-A (ADAMS Accession No. ML12221A202), and the conditions and limitations specified in NEI 94-01, Revision 2-A.

The Fermi 2 program which implements 10 CFR 50 Appendix J, Option B requires individual containment isolation valves to be good performers before they can be placed on extended seat leakage testing frequency. Assuming all of the PIVs are classified as good performers, the extended test interv als would provide for a savings of to NRC-17-0051

Page 3 approximately 2700 mRem (900 mRem above the 1800 mRem savings realized through the previously approved test interval limit of 60 months in VRR-013, Revision 0) over a 75-month period. Pressure Isolation Valves (P IVs) are not included in the scope for performance-based testing as provided for in 10 CFR 50 Appe ndix J, Option B. The concept behind the Option B alternative for containment isolation valves is that licensees should be allowed to adopt cost effective methods for complying with regulatory requirements. NEI 94-01 describes the risk-informed basis for the extended test intervals under Option B. That justification shows that for valves which have demonstrated good performance by passing their leak rate tests for three consecutive cycles, further failures appear to be governed by the random failure rate of the component. NEI 94-01 also presents the results of a comprehensive risk analysis, including the statement that "the risk impact associated with increasing [leakrate] test intervals is negligible (less than 0.1% of total risk)." The valves identified in this relief request are all in water applications. The PIV testing is performed with water pressurized to normal plant operating pressures. This relief request is intended to provide for a performance-based scheduling of PIV tests at Fermi 2.

NUREG-0933, "Resolution of Generic Safety Issues," Issue 105, "Interfacing Systems

LOCA at LWRs," discussed the need for PIV leak rate testing based primarily on three pre-1980 historical failures of applicable valves industry-wide. These failures all involved human errors in either operations or maintenance. None of these failures involved inservice equipment degradation. The performance of PIV leak rate testing provides assurance of acceptable seat leakage wi th the valve in a closed position. Typical PIV testing does not identify functional problems which may inhibit the valves ability to re-position from open to closed. For ch eck valves, such functional testing is accomplished per ASME OM Code Section ISTC-3522 "Category C check Valves" and Section ISTC-3520 "Exercising Requirements."

Power-operated valves are routinely full stroke tested in accordance with ASME OM Code Section ISTC-5100, "Power Operated

Valves," to ensure their functional capabilities. At Fermi 2, thes e functional tests for PIVs are performed only at a Cold Shutdown or refuel outage frequency. Such testing is not performed online in order to prevent any possibility of an in advertent Interfacing System Loss of Coolant Accident (ISLOCA) condition. The 18-month functional stroke testing of the PIVs is adequate to identify any abnormal condition that might affect closure capability. Performance of the separate 18-month PIV leak rate testing does not

contribute any additional assura nce of functional capability as it only verifies the seat tightness of the closed valves. to NRC-17-0051

Page 4

Fermi 2 proposes to perform PIV testing at intervals (frequ encies) ranging from every 30 months up to every 75 months. The specific interval for each valve would be a function of its seat leakage performance and would be established in a manner consistent with the Containment Isol ation valves (CIVs) pro cess under 10 CFR 50 Appendix J Option B. Thirteen of the fifteen valves listed are classified as CI Vs and nine of those valves are leak rate tested with air at intervals determined by 10 CFR 50 Appendix J, Option B (hereto referred to as Option B). IST Leak Rate Program guidance will be established such that if any of those nine valves fail either their CIV test or their PIV test, the test interval for both tests will be reduced to every 30 months until they can be re-classified as good performers per the 10 CFR 50 Appendix J, Option B requirements.

The test intervals for the valves with a PIV-only function will be determined in the same manner as is done for CIV testing under Option B. That is, the test interval may be extended up to every four refueling outages (not to exceed 75 months) upon completion of three consecutive periodic PIV tests with re sults within prescribed acceptance criteria.

Any PIV test failure will require a return to the initial (every 30 months) interval until good performance can be re-established.

The primary basis for this relief request is the historically good performance of the PIVs. There have been no PIV failures due to seating surface condition of the valves. Several of the valves covered by this relief request have passed the as f ound PIV water test but experienced failures of as found CIV air leakage tests due to seat imperfections. There is industry-wide consensus that CIV air-test ing is a more challenging and accurate measurement of seat condition, and more likely to identify any seat condition degradation. A sample of PIV leak rate test performance has been provided in Attachment 1.

NUREG/CR-5928, "Final Report of the NRC-sponsored ISLOCA Research Program", evaluated the likelihood and poten tial severity of ISLOCA ev ents in BWRs and PWRs. The BWR design used as a reference for this analysis was a BWR-4 with a Mark 1 containment. Fermi 2 was listed in Section 4.1 of the document as one of the applicable plants. The applicable BWR systems were individually analyzed and in each case this report concluded that the system was not at risk with respect to ISLOCA risk. Section 4.3 concluded the BWR portion of the analysis by saying "ISLOCA is not a risk concern for the BWR plant examined here."

On March 9, 2017, Fermi 2 received a Safe ty Evaluation (Technical Specification Amendment No. 205) with approval to implement NEI 94-01, Revision 3-A (ADAMS accession No. ML12221A202) and the conditions and limitations specified in NEI 94-01, Revision 2-A, to implement the performance-based leakage-testing program in to NRC-17-0051

Page 5 accordance with 10 CFR 50 Appendix J, Option B. This Amendment increased the containment isolation valves leakage test intervals (i.e., Type C tests) from 60 months to 75 months. Valves whose leakage test results indicate good performance may have their interval of testing increase d based on these test results. The Fermi 2 program which implements 10 CFR 50 Appendix J, Option B requires individual containment isolation valves be good performers before they can be placed on extended seat leakage testing frequency. Based on the data contained in Attachment 1, the majority of the listed valves have passed their last three PIV Leak Rate Tests.

Summary of bases and rationale for this relief request: Performance-based PIV testing would yield a dose reduction of approximately 2700 mRem over a 75-month period. Performance of functional stroke testing of PIVs every 18 months per ASME Code. Excellent historical performance results from PIV testing for all the applicable

valves. Very low likelihood of valve mispositioning during power operations (procedures, interlocks). Air testing versus water testing - degrading seat conditions are identified much sooner with air testing. Relief valves in the low pressure piping - these relief valves may not provide ISLOCA mitigation for inadvertent PIV mispositioning (gross leakage) but their relief capacity can easily accommodate conservative PIV seat leakage rates. Alarms that identify high pressure to low pressure leakage - Operators are highly trained to recognize symptoms of a present or incipi ent ISLOCA and to take appropriate actions.

The intent of this relief request is to allow a performance-based approach to the scheduling of PIV leakage testing. Fermi 2 PIVs have an excellent performance history in terms of seat leakage testing. The risks a ssociated with extending the leakage test interval to a maximum of 75 months are extremely low. This relief will provide significant reductions in radiation dose.

This proposed alternative is for the remaining duration of the Femi 2 Third Inservice Testing (IST) 10-Year Interval, which started February 17, 2010. to NRC-17-0051

Page 6 NRC Safety Evaluation Report: Limerick Generating Station, Units 1 and 2 -

Proposed Relief Request GVRR-8 Regarding Inservice Testing Program Third 10-Year Interval (CAC Nos. MF8787 and MF8788), dated February 7, 2017 (ML17004A063) NRC Safety Evaluation Report: Fermi 2 - Ev aluation of In-Servi ce Testing Program Relief Requests VRR-011, VRR-012, and VRR-013 (TAC No. ME2558, ME2557, and ME2556), dated September 28, 2010 (ML102360570) - Historical Pressure Isolation Valves Leakage Test Performance (Last Three Tests) to NRC-17-0051

Page 7 Attachment 1 - Historical Pressure Isolation Valves Leakage Test Performance (Last Three Tests) E1100F050A 2/15/2014 10.00 0.00 3/29/2009 0.211 10/17/2007 0.22 E1100F050B 4/4/2017 10.00 Unsat** 10/6/2015 0.077 2/27/2014 Unsat*** E1150F008 3/12/2014 5.00 0.14 4/17/2009 0.06 10/20/2007 0.003 E1150F009 and E1150F608* 3/12/2014 5.00 0.12 4/17/2009 0.002 10/20/2007 0.012 E1150F015A 2/14/2014 0.40 0.002 3/29/2009 0.021 10/17/2007 0.001 E1150F015B 2/27/2014 0.40 0.00 4/8/2009 0.003 10/2/2007 0.00 E2100F006A 3/21/2017 5.00 0.00 4/18/2012 0.00 11/5/2010 0.00 E2100F006B 4/3/2017 5.00 0.00 4/6/2012 0.00 11/13/2010 0.001 E2150F005A 2/13/2014 5.00 0.00 3/30/2009 0.00 10/9/2007 0.014 to NRC-17-0051

Page 8 Attachment 1 - Historical Pressure Isolation Valves Leakage Test Performance (Last Three Tests)

E2150F005B 2/24/2014 5.00 0.008 4/6/2009 0.00 10/1/2007 0.003 E4150F006 2/19/2014 5.00 0.00 4/1/2009 0.00 10/5/2007 0.06 E4150F007 2/19/2014 5.00 0.001 4/1/2009 0.00 10/5/2007 0.00 E5150F012 2/15/2014 3.00 0.00 4/1/2009 0.00 10/5/2007 0.018 E5150F013 2/15/2014 3.00 0.00 4/1/2009 0.00 10/5/2007 0.007 Legend: gpm is gallons per minute

• Group tested together ** Unable to pressurize E1100F050B (04/04/2017). This was due to actuator shaft, indicator shaft and bushing found to be mechanically bound together. In addition, the brass indicator shaft bushing found mechanically bound to the valve body. Corrective Actions: actuator shaft, indicator shaft and bushing, and actuator stuffing box were replaced, and proper clearance was obtained.

• • • Unable to pressurize E1100F050B (02/27/14). This was due to mechanical binding and sticking of the actuator or linkage (hinge/bearing). Corrective Actions: Performed check valve internal inspection, cleaned and machined swing arm and created Preventive Maintenance (PM) events for internal inspection and/or maintenance of the E1100F050A and E1100F050B.