JAFP-11-0085, Proposed Relief Request Nos. VRR-07 & VRR-08, Fourth Interval In-Service Testing Program
| ML111890199 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/07/2011 |
| From: | Eugene Dorman Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| JAFP-11-0085 | |
| Download: ML111890199 (18) | |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 JAFP-11-0085 July 7, 2011 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
Subject:
Proposed Relief Request Nos. VRR-07 and VRR-08 for the James A.
FitzPatrick Nuclear Power Plant Fourth Interval In-Service Testing Program Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant Docket No.
50-333 License No.
Dear Sir or Madam:
In accordance with 10 CFR 50.55a(a)(3)(i), this letter requests relief from the testing requirements of ASME OM Code-2001 including 2003 addenda, ISTC-3630(a) Leakage Test Frequency, [Enclosure 1] and ISTC-3700 Position Verification Testing [Enclosure 2].
ASME OM Code, ISTC-3630(a), requires that leakage rate testing of Category A valves, with a leakage requirement that is not based on 10 CFR 50 Appendix J, be conducted at least once every 2 years. James A. FitzPatrick Nuclear Power Plant (JAF) Fourth Interval Inservice Testing (IST) Valve Relief Request VRR-07 [Enclosure 1] proposes a performance-based approach to the scheduling of Pressure Isolation Valve (PIV) leakage testing. This alternative will provide an acceptable level of quality and safety; and, it is consistent with 10 CFR 50.55a(a)(3)(i).
ASME OM Code, ISTC-3700, requires local valve position verification at least once every 2 years. JAF Fourth IST Interval Valve Relief Request VRR-08 [Enclosure 2] proposes using the position indication verification test frequency specified in 10 CFR 50 Appendix J, Option B in lieu of the ASME OM Code, ISTC-3700 test frequency. This alternative will provide an acceptable level of quality and safety; and, it is consistent with 10 CFR 50.55a(a)(3)(i).
The fourth interval began October 1, 2007, and these reliefs will be applicable for the duration of the fourth interval. JAF requests approval of the enclosed relief request by July 31, 2012.
Eugene Dorman Acting Licensing Manager
JAFP-11-0085 Page 2 of 2 There are no commitments made in this letter.
Should you have any questions, please contact Mr. Eugene Dorman at (315) 349-6810.
Very truly yours,
/~L,.~ --
Eugene Dorman Acting Licensing Manager ED:mh
Enclosures:
1:
10 CFR 50.55a Valve Relief Request VRR-07 Performance-Based Scheduling of Pressure Isolation Valve Leakage Tests 2:
10 CFR 50.55a Valve Relief Request VRR-08 Performance-Based Scheduling of Position Indication Verification Tests cc:
Mr. William Dean Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8-C2A Washington, DC 20555-0001 Resident Inspector's Office U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, New York 13093 Document Components:
001 JAFP-11-0085 with Enclosures
JAFP-11-0085 10 CFR 50.55a Valve Relief Request VRR-07 Performance-Based Scheduling of Pressure Isolation Valve Leakage Tests (6 Pages with Index)
JAFP-11-0085 ENCLOSURE 1 Index Valve Relief Request VRR-07 2 Pages : Pressure Isolation Valve Leakage History 3 Pages
10 CFR 50.55a Valve Relief Request VRR-07 Performance-Based Scheduling of Pressure Isolation Valve Leakage Tests Page 1 of 2 Systems Residual Heat Removal Low Pressure Core Spray ASME Code Components Affected Valve Description Appendix J Option B Air Tested Code Category 10AOV-68A Loop A Low Pressure Coolant Injection Testable Check Valve No A/C 10MOV-25A Loop A Low Pressure Coolant Injection Inboard Injection Valve Yes A
10AOV-68B Loop B Low Pressure Coolant Injection Testable Check Valve No A/C 10MOV-25B Loop B Low Pressure Coolant Injection Inboard Injection Valve Yes A
14AOV-13A Loop A Low Pressure Core Spray Testable Check Valve No A/C 14MOV-12A Loop A Low Pressure Core Spray Inboard Isolation Valve Yes A
14AOV-13B Loop B Low Pressure Core Spray Testable Check Valve No A/C 14MOV-12B Loop B Low Pressure Core Spray Inboard Isolation Valve Yes A
10MOV-17 Residual Heat Removal Shutdown Cooling Outboard Isolation Valve Yes A
10MOV-18 Residual Heat Removal Shutdown Cooling Inboard Isolation Valve No A
=
Applicable Code Edition and Addenda===
ASME OM Code 2001 including 2003 addenda Applicable Code Requirements ISTC-3630(a) - Frequency - Tests shall be conducted at least once every 2 years.
Reason for Request
Pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (a)(3), relief is requested from the requirement of ASME OM Code ISTC-3630(a). ISTC-3630(a) requires that leakage rate testing of Category A valves with a leakage requirement that is not based on 10CFR50 Appendix J be conducted at least once every 2 years. At James A. FitzPatrick, Pressure Isolation Valves (PIVs) are Category A valves within the scope of ISTC-3630. The basis of this relief request is that the proposed alternative would provide an acceptable level of quality and safety.
Proposed Alternative and Basis for Use 10CFR50 Appendix J was amended to improve the focus of the body of regulations by eliminating prescriptive requirements that are marginal to safety and provide licensees greater flexibility for cost-effective implementation methods for regulatory safety objectives. Consistent with this approach, 10CFR50 Appendix J, Option B is less prescriptive, utilizes risk-based insights, and allows licensees to adopt cost-effective methods, including setting test intervals, for implementing safety objectives underlying the requirements of Appendix J.
NEI 94-01, as modified by the positions in Regulatory Guide 1.163, describes the risk-informed basis for extended test intervals under Option B. NEI 94-01 justifies that valves with demonstrated good leakage rate performance over two consecutive cycles are subject to future failure predominantly 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 test intervals is negligible (less than 0.1% of total risk)."
PIV testing is performed with water pressurized to normal plant operating pressures in accordance with ISTC-3630. This relief request applies performance-based scheduling of PIV tests in an identical manner as performance-based Type C tested components as described in NEI 94-01, and as modified by the positions in Regulatory Guide 1.163.
NUREG 0933, Issue 105 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
10 CFR 50.55a Valve Relief Request VRR-07 Performance-Based Scheduling of Pressure Isolation Valve Leakage Tests Page 2 of 2 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 with the valve in a closed condition. Typical PIV testing does not identify functional problems which may inhibit the valves ability to re-position from open to close. For check valves, such functional testing is accomplished per ASME OM Code ISTC-3522 and ISTC-3520. Power-operated valves are routinely full-stroke tested per ASME OM Code to ensure their functional capabilities. The functional tests for PIVs are performed only at Refuel Outage frequency. Such testing is not performed online in order to prevent any possibility of an inadvertent Interfacing System Loss of Coolant Accident (ISLOCA) condition. The functional testing of the PIVs is adequate to identify any abnormal condition that might affect closure capability. Performance of the separate PIV leak rate testing does not contribute any additional assurance of functional capability; it verifies the seat tightness of the closed valves. JAF proposes to perform PIV testing at intervals specified in NEI 94-01. The specific interval for each valve would be a function of its performance and would be established in a manner consistent with the Containment Isolation valve (CIV) process under 10CFR50 Appendix J, Option B. Program guidance will be established such that if any of the valves fail either the CIV test or PIV test, the test interval for both tests will be reduced to once every 30 months until they can be re-classified as good performers per the performance evaluation requirements of Appendix J, Option B. 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 upon completion of two consecutive periodic PIV tests with results within prescribed acceptance criteria. Any PIV test failure will require a return to the initial interval until good performance can again be established.
The intent of this relief request is to allow for a performance-based approach to the scheduling of PIV leakage testing. It has been shown that ISLOCA represents a small risk impact to BWRs such as James A. FitzPatrick. NUREG/CR-5928, "Final Report of the NRC-sponsored ISLOCA Research Program" (ADAMS Accession No. ML072430731), evaluated the likelihood and potential severity of ISLOCA events in Boiling Water Reactors (BWR) and Pressurized Water Reactors (PWR). The BWR design used as a reference for this analysis was a BWR-4 with Mark I containment. James A.
FitzPatrick is listed as an applicable plant. The BWR systems were individually analyzed and in each case the report concluded that the system was "...judged to not be an important consideration with respect to ISLOCA risk." Section 4.3 of the report concluded the BWR portion of the analysis by saying "ISLOCA is not a risk concern for the BWR plant examined here."
The PIVs have an excellent performance history in terms of seat leakage testing. Since the receipt of Technical Specification Amendment 234, which approved the implementation of 10 CFR 50 Appendix J Option B, 91 pressure isolation valve leakage tests have been performed on the subject valves, with 3 failures. All 3 of the failures were on the same valve during a one month period, and were attributed to improper valve operation and mechanical cycling. Since November of 2000, no pressure isolation valve leakage test failures have occurred on the subject valves. The risks associated with extending the leakage test interval to a maximum of 60 months are extremely low. The basis for this relief request is the historically good performance of the PIVs. This relief will also provide significant reductions in radiation dose. The last refueling outage radiation exposure was used to identify that PIV testing alone each refuel outage incurs a total dose of approximately 800 mRem.
Duration of Proposed Alternative This proposed alternative will be utilized for the Fourth Ten-Year Interval at JAF.
Precedents FERMI 2 -EVALUATION OF IN-SERVICE TESTING PROGRAM RELIEF REQUESTS VRR-011, VRR-012, AND VRR-013 (TAC NOs. ME2558, ME2557, AND ME2556), dated September 28, 2010.
Attachments - Pressure Isolation Valve Leakage History
10 CFR 50.55a Valve Relief Request VRR-07 Performance-Based Scheduling of Pressure Isolation Valve Leakage Tests Page 1 of 3 - Pressure Isolation Valve Leakage History 10AOV-68A Leakage History Test Date Test Type Test Result Leakage Leakage Limit Leakage Units 11/2/1996 LKO Sat 0.575 10 GPM 10/31/1998 LKO Sat 0
10 GPM 10/20/2000 LKO Sat 3.76 10 GPM 10/10/2002 LKO Sat 0.5 10 GPM 10/9/2004 LKO Sat 0
10 GPM 10/29/2006 LKO Sat 0
10 GPM 9/29/2008 LKO Sat 0
10 GPM 9/19/2010 LKO Sat 0
10 GPM 10MOV-25A Leakage History Test Date Test Type Test Results Leakage Leakage Limit Leakage Units 7/10/1998 LJ-C Sat 0.008 5.893 SLM 10/20/2000 LJ-C Sat 0.073 5.893 SLM 9/3/2002 LKO Sat 0
5 GPM 10/10/2004 LJ-C Sat 1.184 16 SLM 8/30/2006 LKO Sat 0
5 GPM 9/30/2008 LJ-C Sat 5.96 16 SLM 9/10/2010 LKO Sat 0.24 5
GPM 10AOV-68B Leakage History Test Date Test Type Test Results Leakage Leakage Limit Leakage Units 11/2/1996 LKO Sat 0.104 10 GPM 10/27/1998 LKO Sat 0
10 GPM 10/12/2000 LKO Sat 0
10 GPM 3/28/2001 LKO Sat 0.2075 10 GPM 10/17/2002 LKO Sat 0
10 GPM 9/29/2004 LKO Sat 8.5 10 GPM 10/29/2006 LKO Sat 0
10 GPM 9/21/2008 LKO Sat 0
10 GPM 9/29/2010 LKO Sat 0
10 GPM (Continued)
10 CFR 50.55a Valve Relief Request VRR-07 Performance-Based Scheduling of Pressure Isolation Valve Leakage Tests Page 2 of 3 - Pressure Isolation Valve Leakage History 10MOV-25B Leakage History Test Date Test Type Test Results Leakage Leakage Limit Leakage Units 7/10/1998 LJ-C Sat 0
5.893 SLM 9/3/1998 LJ-C Sat 0
5.893 SLM 10/28/1998 LJ-C Sat 2.97 5.893 SLM 10/12/2000 LJ-C Unsat 9.95 5.893 SLM 10/13/2000 LJ-C Unsat 9.51 5.893 SLM 10/15/2000 LJ-C Sat 5.02 5.893 SLM 10/23/2000 LJ-C Unsat 10.99 5.893 SLM 11/11/2000 LJ-C Sat 0.37 5.893 SLM 9/3/2002 LKO Sat 0
5 GPM 10/2/2002 LJ-C Sat 2.84 16 SLM 10/5/2004 LJ-C Sat 3.85 16 SLM 9/3/2006 LKO Sat 0
5 GPM 10/26/2006 LJ-C Sat 8.85 16 SLM 9/16/2008 LJ-C Sat 1.53 16 SLM 9/23/2008 LJ-C Sat 4.88 16 SLM 8/29/2010 LKO Sat 0
5 GPM 14AOV-13A Leakage History Test Date Test Type Test Results Leakage Leakage Limit Leakage Units 11/3/1996 LKO Sat 0.112 10 GPM 11/15/1998 LKO Sat 0
10 GPM 10/21/2000 LKO Sat 3.34 10 GPM 10/8/2002 LKO Sat 0
10 GPM 10/9/2004 LKO Sat 0
10 GPM 10/14/2006 LKO Sat 0
10 GPM 9/22/2008 LKO Sat 0
10 GPM 9/20/2010 LKO Sat 0
10 GPM 14MOV-12A Leakage History Test Date Test Type Test Results Leakage Leakage Limit Leakage Units 11/7/1996 LJ-C Sat 0.009 1.473 SLM 11/11/1996 LJ-C Sat 0.126 1.473 SLM 11/15/1998 LJ-C Sat 0.1256 1.473 SLM 10/22/2000 LJ-C Sat 0.016 1.473 SLM 10/8/2002 LKO Sat 0
5 GPM 10/9/2004 LJ-C Sat 0.019 16 SLM 10/14/2006 LKO Sat 0
5 GPM 9/25/2008 LJ-C Sat 0.113 16 SLM 9/13/2010 LJ-C Sat 0.351 16 SLM (Continued)
10 CFR 50.55a Valve Relief Request VRR-07 Performance-Based Scheduling of Pressure Isolation Valve Leakage Tests Page 3 of 3 - Pressure Isolation Valve Leakage History 14AOV-13B Leakage history Test Date Test Type Test Results Leakage Leakage Limit Leakage Units 11/12/1996 LKO Sat 0
10 GPM 10/26/1998 LKO Sat 0.10375 10 GPM 10/9/2000 LKO Sat 0
10 GPM 10/17/2002 LKO Sat 0
10 GPM 10/1/2004 LKO Sat 0.75 10 GPM 10/29/2006 LKO Sat 0.1044 10 GPM 9/18/2008 LKO Sat 0.11 10 GPM 9/29/2010 LKO Sat 0
10 GPM 14MOV-12B Leakage History Test Date Test Type Test Results Leakage Leakage Limit Leakage Units 11/13/1996 LJ-C Sat 0.093 1.473 SLM 11/17/1996 LJ-C Sat 0.002 1.473 SLM 10/24/1998 LJ-C Sat 0.002 1.473 SLM 10/9/2000 LJ-C Sat 0.12 1.473 SLM 10/17/2002 LKO Sat 0
5 GPM 10/3/2004 LJ-C Sat 0.007 16 SLM 10/28/2006 LKO Sat 0
5 GPM 9/15/2008 LJ-C Sat 0.722 16 SLM 9/29/2010 LJ-C Sat 0.38 16 SLM 10MOV-17 Leakage History Test Date Test Type Test Results Leakage Leakage Limit Leakage Units 11/2/1996 LJ-C Sat 0.26 4
SLM 11/3/1998 LJ-C Sat 0.1715 4
SLM 10/17/2000 LJ-C Sat 0.002 4
SLM 10/20/2002 LJ-C Sat 0.409 16 SLM 10/4/2004 LJ-C Sat 0.002 16 SLM 10/19/2006 LKO Sat 0.105 5
GPM 9/19/2008 LJ-C Sat 1.04 16 SLM 9/20/2010 LJ-C Sat 0.256 16 SLM 10MOV-18 Leakage History Test Date Test Type Test Results Leakage Leakage Limit Leakage Units 7/11/1998 LKO Sat 0
5 GPM 7/10/2000 LKO Sat 0.25 5
GPM 7/10/2002 LKO Sat 0
5 GPM 7/11/2004 LKO Sat 0.25 5
GPM 10/20/2004 LKO Sat 0
5 GPM 7/7/2006 LKO Sat 0.5 5
GPM 10/31/2006 LKO Sat 0.255 5
GPM 10/9/2008 LKO Sat 0
5 GPM 8/20/2010 LKO Sat 0.26 5
GPM Notes:
- 1. LKO is a leak test for other than a containment isolation valve. It is a Water Leakage Test
- 2. LJ-C is a Leak test per 10 CFR 50 Appendix J.
JAFP-11-0085 10 CFR 50.55a Valve Relief Request VRR-08 Performance-Based Scheduling of Position Indication Verification Tests (8 Pages with Index)
JAFP-11-0085 ENCLOSURE 2 Index Valve Relief Request VRR-08 3 Pages : Position Indication Test Historical Sample 1 Page : Local Leak Rate Test Historical Sample 1 Page : Stroke Time Historical Sample 1 Page : Preventive Maintenance and Environmental Qualification Information 1 Page
10 CFR 50.55a Valve Relief Request VRR-08 Performance-Based Scheduling of Position Indication Verification Tests Page 1 of 3 Systems Traversing In-Core Probe System (07)
Containment Atmosphere Dilution System (27)
ASME Code Components Affected Valve Description Class Code Category 07SOV-104A TIP Channel A Guide Tube Ball Valve 2
A 07SOV-104B TIP Channel B Guide Tube Ball Valve 2
A 07SOV-104C TIP Channel C Guide Tube Ball Valve 2
A 27SOV-119E1 Containment Analyzer A Torus Sample Outer Isolation Valve 2
A 27SOV-119E2 Containment Analyzer A Torus Sample Inner Isolation Valve 2
A 27SOV-119F1 Containment Analyzer B Torus Sample Inner Isolation Valve 2
A 27SOV-119F2 Containment Analyzer B Torus Sample Outer Isolation Valve 2
A 27SOV-120E1 Containment Analyzer A Drywell 310 Foot Elevation Sample Outer Isolation Valve 2
A 27SOV-120E2 Containment Analyzer A Drywell 310 Foot Elevation Sample Inner Isolation Valve 2
A 27SOV-120F1 Containment Analyzer B Drywell 310 Foot Elevation Sample Outer Isolation Valve 2
A 27SOV-120F2 Containment Analyzer B Drywell 310 Foot Elevation Sample Inner Isolation Valve 2
A 27SOV-122E1 Containment Analyzer A Drywell 343 Foot Elevation Sample Outer Isolation Valve 2
A 27SOV-122E2 Containment Analyzer A Drywell 343 Foot Elevation Sample Inner Isolation Valve 2
A 27SOV-122F1 Containment Analyzer B Drywell 343 Foot Elevation Sample Outer Isolation Valve 2
A 27SOV-122F2 Containment Analyzer B Drywell 343 Foot Elevation Sample Inner Isolation Valve 2
A 27SOV-123E1 Containment Analyzer A Drywell 276 Foot Elevation Sample Outer Isolation Valve 2
A 27SOV-123E2 Containment Analyzer A Drywell 276 Foot Elevation Sample Inner Isolation Valve 2
A 27SOV-123F1 Containment Analyzer B Drywell 276 Foot Elevation Sample Outer Isolation Valve 2
A 27SOV-123F2 Containment Analyzer B Drywell 276 Foot Elevation Sample Inner Isolation Valve 2
A 27SOV-124E1 Containment Analyzer A Post Accident Sampling Return Header Outer Isolation Valve 2
A 27SOV-124E2 Containment Analyzer A Post Accident Sampling Return Header Inner Isolation Valve 2
A 27SOV-124F1 Containment Analyzer B Post Accident Sampling Return Header Outer Isolation Valve 2
A 27SOV-124F2 Containment Analyzer B Post Accident Sampling Return Header Inner Isolation Valve 2
A 27SOV-125A Drywell Radiation Monitor 17-04-1 Sample Return Inner Isolation Valve 2
A 27SOV-125B Drywell Radiation Monitor 17-04-2 Sample Return Inner Isolation Valve 2
A 27SOV-125C Drywell Radiation Monitor 17-04-1 Sample Return Outer Isolation Valve 2
A 27SOV-125D Drywell Radiation Monitor 17-04-2 Sample Return Outer Isolation Valve 2
A 27SOV-135A Drywell Radiation Monitor 17-04-1 Sample Supply Outer Isolation Valve 2
A 27SOV-135B Drywell Radiation Monitor 17-04-2 Sample Supply Outer Isolation Valve 2
A 27SOV-135C Drywell Radiation Monitor 17-04-1 Sample Supply Inner Isolation Valve 2
A 27SOV-135D Drywell Radiation Monitor 17-04-2 Sample Supply Inner Isolation Valve 2
A 27SOV-141 Drywell PCV and instrument Air or Normal N2 Cross-Tie Valve 2
A 27SOV-145 Drywell Instrument Nitrogen Backup Supply Isolation Valve 2
A
=
Applicable Code Edition and Addenda===
ASME OM Code 2001 including 2003 addenda.
Applicable Code Requirements ISTC-3700 Position Verification Testing, states Valves with remote position indicators shall be observed locally at least once every 2 years to verify that valve operation is accurately indicated.
10 CFR 50.55a Valve Relief Request VRR-08 Performance-Based Scheduling of Position Indication Verification Tests Page 2 of 3
=
Reason for Request===
Pursuant to 10 CFR 50.55a, Codes and Standards, paragraph (a)(3). Relief is requested from the requirement of ASME OM Code ISTC-3700, for the subject valves, to perform the position indication verification test (hereby referred to as PIT) on a 2 year frequency. PIT will be performed at the same frequency as the 10 CFR 50 Appendix J, Option B test. 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. By review of the radiation exposure for the latest PIT for each valve, each two year test cycle incurs a total dose of approximately 200 mR.
Proposed Alternative and Basis for Use In accordance with ISTC-3700, where local observation is not possible, other indications shall be used to verify valve position. The method used at JAF is a pressure test using the local leakage rate testing equipment. This method involves pressurizing the containment penetration volume between 45 and 48 psig, and verifying the penetration remains pressurized while the valve is indicating closed on the main control room board.
The valve is then opened using the control switch in the main control room and the penetration is verified to depressurize and the local leak rate testing equipment is verified to have high flow. This method satisfies the PIT requirement and ensures that the indicating system accurately reflects the valve position. This method also verifies that both valve stem and obturator are moving acceptably, and there is no separation of the two.
The subject valves are all categorized as A and are all containment isolation valves. All of the subject valves have a safety function to close in order to isolate containment during a Loss of Coolant Accident. Since these valves are containment isolation valves, they are each individually seat leakage tested in accordance with 10 CFR 50 Appendix J, Option B. Each of these valves is a solenoid operated valve designed in a way that the position of the valve is not locally observable. The coil position is internal to the valve body and not observable in either the energized or de-energized state.
For the subject valves, JAF will perform the PIT in conjunction with the Type C valve seat leakage test at a frequency in accordance with 10 CFR 50 Appendix J, Option B.
Since each of these valves is seat leakage tested using local leakage rate testing equipment, the current leakage rate tests have been modified to also perform the PIT at the same time. The individual valve being tested must have its system properly drained, vented, and aligned correctly prior to performing the seat leakage test or PIT. Currently, this must be done every two years, due solely to the PIT two-year interval requirement.
Based on seat leakage test results, the testing frequency may be adjusted to a maximum of 60 months in accordance 10 CFR 50 Appendix J, Option B. Radiation exposure and Operations/Test personnel time involved will be significantly reduced by performing the PIT at the same interval as the Appendix J seat leakage test. A sample of PIT historical data has been provided in Attachment 1 and a sample of Local Leak Rate Test (LLRT) historical data has been provided in Attachment 2.
In addition, each of these subject valves is exercised on a quarterly frequency and their stroke times are measured and compared to the ASME OM Code acceptance criteria.
By continuing this valve exercising, and performance of the PIT and seat leakage test in accordance with 10 CFR 50 Appendix J. Option B, an adequate assessment of valve
10 CFR 50.55a Valve Relief Request VRR-08 Performance-Based Scheduling of Position Indication Verification Tests Page 3 of 3 health may be determined. A sample of the stroke time history for each valve is shown in.
The subject valves are also subject to Preventive Maintenance tasks. Many of these SOVs are periodically replaced to satisfy Environmental Qualification program requirements. Any maintenance that is performed on these valves which might affect position indication will be followed by applicable post-work testing, including a PIT.
Preventive Maintenance and Environmental Qualification information has been provided in Attachment 4.
On October 4, 1996, JAF received a Safety Evaluation (Technical Specification Amendment 234) with approval to implement Option B of the 10 CFR 50 Appendix J Program. This program permits the extension of the Appendix J seat leakage testing to a frequency based on specific valve performance. Valves whose leakage test results indicate good performance may have their interval of testing increased. The JAF program which implements 10 CFR 50 Appendix J Option B requires individual containment isolation valves to pass two consecutive successful seat leakage tests before it can be placed on extended seat leakage testing frequency. All of the subject valves are currently in good performer status, requiring a seat leakage test every 60 months.
In conclusion, the ability to detect degradation and ensure the operational readiness of the subject valves to perform their intended function is not adversely affected by performing the PIT at the same frequency as specified by 10 CFR 50 Appendix J Option B. This frequency of testing provides assurance of the operational readiness of the subject valves and provides an acceptable level of quality and safety.
Duration of Proposed Alternative This proposed alternative will be utilized for the Fourth Ten-Year Interval at JAF.
Precedents Fermi 2-Evaluation of In-Service Testing Program relief requests VRR-011, VRR-012, and VRR-013 (TAC Nos. ME2558, ME 2557, and ME2556), dated September 28, 2010.
Kewaunee-Fourth 10-Year Inservice Testing interval program requests for relief (TAC NOs. MC4182, MC4183, MC4184, and MC4185). Accession No. ML050380305, dated 3/4/2005.
Attachments
- Position Indication Test Historical Sample (Latest 2 Tests) - Local Leak Rate Test Historical Sample (Latest test) - Stroke Time Historical Sample (Latest Test) - Preventive Maintenance and Environmental Qualification Information
10 CFR 50.55a Valve Relief Request VRR-08 Performance-Based Scheduling of Position Indication Verification Tests Page 1 of 1 - Position Indication Test Historical Sample (Latest 2 Tests)
Position Indication Historical Sample Valve Test Date Test Result Test Date Test Result Test Frequency Procedure 07SOV-104A 9/12/2010 Sat 10/12/2008 Sat 2 Year ST-41K 07SOV-104B 9/12/2010 Sat 10/12/2008 Sat 2 Year ST-41K 07SOV-104C 9/12/2010 Sat 10/12/2008 Sat 2 Year ST-41K 27SOV-119E1 1/18/2011 Sat 5/7/2010 Sat 2 Year ST-41D 27SOV-119E2 1/18/2011 Sat 5/4/2010 Sat 2 Year ST-41D 27SOV-119F1 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-119F2 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-120E1 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-120E2 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-120F1 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-120F2 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-122E1 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-122E2 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-122F1 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-122F2 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-123E1 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-123E2 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-123F1 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-123F2 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-124E1 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-124E2 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-124F1 1/18/2011 Sat 1/27/2009 Sat 2 Year ST-41D 27SOV-124F2 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-125A 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-125B 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-125C 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-125D 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-135A 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-135B 1/18/2011 Sat 1/29/2010 Sat 2 Year ST-41D 27SOV-135C 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-135D 1/18/2011 Sat 1/29/2010 Sat 2 Year ST-41D 27SOV-141 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D 27SOV-145 1/18/2011 Sat 11/3/2008 Sat 2 Year ST-41D Legend:
Sat is Satisfactory
10 CFR 50.55a Valve Relief Request VRR-08 Performance-Based Scheduling of Position Indication Verification Tests Page 1 of 1 - Local Leak Rate Test Historical Sample (Latest test)
LLRT Historical Sample Valve Date Result Leakage (SLM)
Procedure 07SOV-104A 9/20/2010 Sat 0.024 ST-39B-X35 07SOV-104B 9/20/2010 Sat 0.004 ST-39B-X35 07SOV-104C 9/20/2010 Sat 0.015 ST-39B-X36 27SOV-119E1 5/7/2010 Sat 0.0426 ST-39B-X203A 27SOV-119E2 5/4/2010 Sat 0.0449 ST-39B-X203A 27SOV-119F1 10/8/2007 Sat 0.411 ST-39B-X216 27SOV-119F2 7/18/2009 Sat 0.002 ST-39B-X216 27SOV-120E1 1/11/2008 Sat 0.003 ST-39B-X26A/B 27SOV-120E2 5/24/2010 Sat 0.002 ST-39B-X26A/B 27SOV-120F1 5/13/2010 Sat 0.00217 ST-39B-X58C 27SOV-120F2 5/13/2010 Sat 0.0593 ST-39B-X58C 27SOV-122E1 1/11/2008 Sat 0.021 ST-39B-X26A/B 27SOV-122E2 5/24/2010 Sat 0.01926 ST-39B-X26A/B 27SOV-122F1 5/12/2010 Sat 0.0106 ST-39B-X58B 27SOV-122F2 5/13/2010 Sat 0.0162 ST-39B-X58B 27SOV-123E1 7/27/2007 Sat 0.0184 ST-39B-X59 27SOV-123E2 7/27/2007 Sat 0.0207 ST-39B-X59 27SOV-123F1 5/13/2010 Sat 0.00343 ST-39B-X58D 27SOV-123F2 5/13/2010 Sat 0.0212 ST-39B-X58D 27SOV-124E1 1/11/2008 Sat 0.014 ST-39B-X203B 27SOV-124E2 1/11/2008 Sat 0.014 ST-39B-X203B 27SOV-124F1 11/22/2010 Sat 4.4 ST-39B-X203B 27SOV-124F2 11/22/2010 Sat 0.693 ST-39B-X203B 27SOV-125A 2/15/2008 Sat 0.0762 ST-39B-X52A 27SOV-125B 11/29/2007 Sat 0.0795 ST-39B-X55B 27SOV-125C 2/15/2008 Sat 0.0872 ST-39B-X52A 27SOV-125D 11/29/2007 Sat 0.0435 ST-39B-X55B 27SOV-135A 3/14/2008 Sat 0.002 ST-39B-S31Ad 27SOV-135B 3/24/2008 Sat 0.003 ST-39B-S31Bd 27SOV-135C 3/14/2008 Sat 0.002 ST-39B-S31Ad 27SOV-135D 3/24/2008 Sat 0.003 ST-39B-S31Bd 27SOV-141 9/23/2010 Sat 0.001 ST-39B-X22 27SOV-145 9/17/2010 Sat 0.002 ST-39B-X57C Legend:
Sat is Satisfactory SLM is Standard Liters per Minute
10 CFR 50.55a Valve Relief Request VRR-08 Performance-Based Scheduling of Position Indication Verification Tests Page 1 of 1 - Stroke Time Historical Sample (Latest Test)
Stroke Time Historical Sample (Latest Test)
Valve Stroke Direction Stroke Time Reference Value Stroke Time Code Action Limit (S)
Test Date Stroke Time (S) 07SOV-104A Closed 11
<8.3 and >13.8 5/5/2011 11.46 07SOV-104B Closed 11
<8.3 and >13.8 5/5/2011 10.78 07SOV-104C Closed 11
<8.3 and >13.8 5/5/2011 10.96 27SOV-119E1 Closed 2
>2 5/5/2011 2
27SOV-119E2 Closed 2
>2 5/5/2011 2
27SOV-119F1 Closed 2
>2 5/5/2011 2
27SOV-119F2 Closed 2
>2 5/5/2011 2
27SOV-120E1 Closed 2
>2 5/5/2011 2
27SOV-120E2 Closed 2
>2 5/5/2011 2
27SOV-120F1 Closed 2
>2 5/5/2011 2
27SOV-120F2 Closed 2
>2 5/5/2011 2
27SOV-122E1 Closed 2
>2 5/5/2011 2
27SOV-122E2 Closed 2
>2 5/5/2011 2
27SOV-122F1 Closed 2
>2 5/5/2011 2
27SOV-122F2 Closed 2
>2 5/5/2011 2
27SOV-123E1 Closed 2
>2 5/5/2011 2
27SOV-123E2 Closed 2
>2 5/5/2011 2
27SOV-123F1 Closed 2
>2 5/5/2011 2
27SOV-123F2 Closed 2
>2 5/5/2011 2
27SOV-124E1 Closed 2
>2 5/5/2011 2
27SOV-124E2 Closed 2
>2 5/5/2011 2
27SOV-124F1 Closed 2
>2 5/5/2011 2
27SOV-124F2 Closed 2
>2 5/5/2011 2
27SOV-125A Closed 2
>2 5/5/2011 2
27SOV-125B Closed 2
>2 5/5/2011 2
27SOV-125C Closed 2
>2 5/5/2011 2
27SOV-125D Closed 2
>2 5/5/2011 2
27SOV-135A Closed 2
>2 5/5/2011 2
27SOV-135B Closed 2
>2 5/5/2011 2
27SOV-135C Closed 2
>2 5/5/2011 2
27SOV-135D Closed 2
>2 5/5/2011 2
Closed 2
>2 5/5/2011 2
27SOV-141 Open 2
>2 5/5/2011 2
Closed 2
>2 5/5/2011 2
27SOV-145 Open 2
>2 5/5/2011 2
Legend:
S is Seconds
10 CFR 50.55a Valve Relief Request VRR-08 Performance-Based Scheduling of Position Indication Verification Tests Page 1 of 1 - Preventive Maintenance and Environmental Qualification Information Preventive Maintenance Information Valve EQ Frequency (Days)
Description Last Completion PMRQ 07SOV-104A No 1460 PM - PERFORM TIP BALL VALVE MAINTENANCE.
9/26/2008 50047679-01 07SOV-104B No 1460 PM - PERFORM TIP BALL VALVE MAINTENANCE.
9/26/2008 50047680-01 07SOV-104C No 1460 PM - PERFORM TIP BALL VALVE MAINTENANCE.
9/26/2008 50047681-01 27SOV-119E1 Yes 1825 PM-Replace valve (Note 1) 5/6/2010 50057122-02 27SOV-119E2 Yes 1825 PM-Replace valve (Note 1) 5/10/2010 50057123-02 27SOV-119F1 Yes 1825 PM-Replace valve (Note 1) 4/1/2004 50057124-02 27SOV-119F2 Yes 1825 PM-Replace valve (Note 1) 8/17/2004 50057125-02 27SOV-120E1 Yes 6570 EQ PM - Replace solenoid valve assembly 10/25/1988 50057126-02 27SOV-120E2 Yes 6570 EQ PM - REPLACE EPR O-RINGS 2/10/2005 50057127-02 27SOV-120F1 Yes 6570 EQ PM - REPLACE EPR O-RINGS 5/25/2005 50057128-02 27SOV-120F2 Yes 6570 EQ PM - REPLACE EPR O-RINGS 9/7/1988 50049654-01 27SOV-122E1 Yes 6570 EQ PM - REPLACE EPR O-RINGS 9/3/1988 50057129-02 27SOV-122E2 Yes 6570 EQ PM - REPLACE EPR O-RINGS 2/10/2005 50057130-02 27SOV-122F1 Yes 6570 EQ PM - REPLACE EPR O-RINGS 3/23/2005 50057131-02 27SOV-122F2 Yes 6570 EQ PM - REPLACE EPR O-RINGS 3/23/2005 50057132-02 27SOV-123E1 Yes 6570 EQ PM - REPLACE EPR O-RINGS 12/10/1994 50057133-02 27SOV-123E2 Yes 6570 EQ PM - REPLACE EPR O-RINGS 12/10/1994 50057134-02 27SOV-123F1 Yes 6570 EQ PM - REPLACE EPR O-RINGS 5/23/2005 50057135-02 27SOV-123F2 Yes 6570 EQ PM - REPLACE EPR O-RINGS 5/23/2005 50057136-02 27SOV-124E1 Yes Note 2 27SOV-124E2 Yes Note 2 27SOV-124F1 Yes 6570 EQ PM - REPLACE EPR O-RINGS 10/23/2002 50057139-02 27SOV-124F2 Yes 6570 EQ PM - REPLACE EPR O-RINGS 3/22/2005 50057140-02 27SOV-125A Yes Note 2 27SOV-125B Yes Note 2 27SOV-125C Yes Note 2 27SOV-125D Yes Note 2 27SOV-135A Yes Note 2 27SOV-135B Yes Note 2 27SOV-135C Yes Note 2 27SOV-135D Yes Note 2 27SOV-141 Yes Note 3 27SOV-145 Yes Note 3 Notes:
- 1. These PM tasks are not labeled as EQ PM tasks, however are more conservative in nature. Every 5 years the valve is replaced per the PM. Per QDR 35.02, the JAF Qualification Documentation Report for Target Rock Model 1015005 Solenoid Operating Globe Valves Revision 4, the most limiting life of the valve is 22.87 years.