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EPID:L-2019-LLR-0062, Relief Request RV-03 Related to Pressure Isolation Valve Testing Frequency (Approved, Closed) |
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Category:Code Relief or Alternative
MONTHYEARML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23262B4442023-09-26026 September 2023 Authorization and Safety Evaluation for Alternative Request No. I4R-14 ML22194A9152022-07-15015 July 2022 Proposed Alternative I4-R13 for Repair of Recirculation Flow Control Valves RS-22-032, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0202 March 2022 Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques RS-19-066, Relief Request RV-03 Related to Pressure Isolation Valve Testing Frequency2019-06-28028 June 2019 Relief Request RV-03 Related to Pressure Isolation Valve Testing Frequency ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19121A3172019-05-20020 May 2019 Relief Request 13R-15, Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&Pv) Code, Section X1, Rules for Inservice Inspection (EPID-L-2018-LLR-0123) ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds RS-18-112, End of Interval Relief Request Associated with the Third Ten-Year Inservice Inspection (ISI) Interval2018-09-19019 September 2018 End of Interval Relief Request Associated with the Third Ten-Year Inservice Inspection (ISI) Interval JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 ML18011B1112018-01-23023 January 2018 Relief from the Requirements of the ASME Code and OM Code Relief Requests I4R-04, Proposed Alternatives to Various Inservice Inspection Interval (ISI) Requirements of the American Society of Mechanical Engineers, Section XI, 2007 Edition ML18003A2472018-01-0808 January 2018 Relief from the Requirements of the ASME Code and OM Code Relief Requests I4R-01 (CAC Nos. MF9758 and MF9759; EPID L-2017-LLR-0057) ML17354A8542018-01-0303 January 2018 Approval of Alternative to the ASME Code Regarding Inspection of Hydrogen Recombiner System Piping - Relief Request I4R-08 (CAC Nos. MF9772 and MF9773; EPID L-2017-LLR-0036) RA17-086, County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-012017-11-10010 November 2017 County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-01 ML17261A0782017-10-12012 October 2017 Request for Additional Information Regarding Relief Request I4R-01 (CAC Nos. MF9758 and MF9759; EPID L-2017-LLR-0057) ML17171A3202017-07-0505 July 2017 Relief from the Requirements of the ASME Code Regarding Relief Request I4-R-10, Proposed Alternative to Utilize Code Case N-513-4 ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML17059C5832017-03-0101 March 2017 Relief from ASME Code for OM Code Re. RR RV-01 Proposed Alternative to Inservice Testing Requirement of ASME Code for OM Code ML17047A5862017-02-22022 February 2017 Letter to Licensee, Approvals of Relief Requests-RP-02, and RP-03 for the Fourth 10-Year Inservice Testing Intervals (CAC Nos. MF8494 - MF8497) ML17024A2652017-02-22022 February 2017 Letter to Licensee, Approvals of Relief Requests-G-01, RP-01, and RP-04 for the Fourth 10-Year Inservice Testing Intervals (MF8490, MF8491, MF8492, MF8493, MF8498, and MF8499) ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML15226A4122015-10-30030 October 2015 MF5654 & MF5655, Letter to Licensee -Authorization of RR-I3R14 (MF5654 & MF5655-Lasalle RRI3R14(08-14-2015) ML12121A6372012-05-10010 May 2012 Request to Use Code Case N-789 ML0925703212009-09-21021 September 2009 Relief Request CR-26, Inservice Inspection Program Relief Regarding Examination Coverage for the Second 10-Year Inservice Inspection Interval, MD9817 - MD9818 ML0809301222008-05-0707 May 2008 Request for Relief from ASME OM Code for the Third Inservice Testing Interval ML0809803112008-04-30030 April 2008 Relief Request to Use Boiling Water Reactor Vessel & Internals Project Guidelines.. ML0736105872008-01-30030 January 2008 Request for Relief Nos. I3R-03, I3R-04, I3R-08, I3R-09 and I3R-10: Third 10-Year Interval Inservice Inspection Program Plan ML0333001472004-01-28028 January 2004 Relief Request, Shell Weld Inspection, TAC No MB9755 and MB9756 ML0219800132002-07-29029 July 2002 Code Relief, Relief Request RV-13 to Delay Sr/V Setpoint Testing 2023-09-26
[Table view] Category:Letter type:RS
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023 Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-22-085, Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-01-12012 January 2023 Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-23-006, Supplemental Information Regarding License Amendment Request – Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report2023-01-10010 January 2023 Supplemental Information Regarding License Amendment Request – Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-083, Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical2022-06-17017 June 2022 Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical RS-22-051, Constellation Energy Generation, LLC - 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Cover Letter2021-06-30030 June 2021 License Amendment Request Re New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies - Cover Letter RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements 2024-09-12
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4300 Winfield Road Exelon Generation Warrenville, IL 60555 630 657 2000 Office 10 CFR 50.55a RS-19-066 June 28, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
Relief Request RV-03 Related to Pressure Isolation Valve Testing Frequency In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (z)(1), Exelon Generation Company, LLC (EGC), hereby requests NRC approval of the attached relief request associated with the fourth inservice testing (IST) interval for LaSalle County Station (LSCS),
Units 1 and 2.The fourth 10-year interval of the LSCS, Units 1 and 2, IST Program began on October 12, 2017, and complies with the American Society of Mechanical Engineers (ASME)
Code for Operation and Maintenance of Nuclear Power Plants (OM Code) - 2004 Edition with Addenda through OMb-2006.
There are no regulatory commitments contained within this letter.
EGC requests approval of this relief request by January 31, 2020.
Should you have any questions concerning this letter, please contact Mr. Jason Taken at (630) 657-3660.
Dwi Murray Manager - Licensing Exelon Generation Company, LLC Attachments:
- 1. 10 CFR 50.55a Relief Request RV-03 Related to PIV Testing Frequency
- 2. Leakage History of LSCS Unit 1 and Unit 2 PIVs
U.S. Nuclear Regulatory Commission June 28, 2019 Page 2 cc: USNRC Region Ill, Regional Administrator USNRC Senior Resident Inspector, LSCS USNRC Project Manager, LSCS Illinois Emergency Management Agency - Division of Nuclear Safety
Attachment 1 10 CFR 50.55a Relief Request RV-03 Related to PIV Testing Frequency Proposed Alternative In Accordance with 10 CFR 50.55a(z)(1)
- 1. ASME Code Component(s) Affected All Pressure Isolation Valves (PIVs) in the Reactor Coolant System (RCS), as listed in the attached Table, RR-RV-03:
Table RR-RV-03 RCS Pressure Isolation Valve Component List Valve Number System OM Category ASME Code Class Units 1and2 1(2)E21-F006 Low Pressure Core Spray A/C 1 1(2)E21-F005 Low Pressure Core Spray A 1 1(2)E22-F005 High Pressure Core Spray A/C 1 1(2)E22-F004 High Pressure Core Spray A 1 1(2)E12-F041A Residual Heat Removal A/C 1 1(2)E12-F041 B Residual Heat Removal A/C 1 1(2)E12-F041 C Residual Heat Removal A/C 1 1(2)E12-F042A Residual Heat Removal A 1 1(2)E12-F042B Residual Heat Removal A 1 1(2)E12-F042C Residual Heat Removal A 1 1(2)E12-F050A Residual Heat Removal A/C 1 1(2)E12-F050B Residual Heat Removal A/C 1 1(2)E12-F053A Residual Heat Removal A 1 1(2)E12-F053B Residual Heat Removal A 1 1(2)E12-F009 Residual Heat Removal A 1 1(2)E12-F008 Residual Heat Removal A 1 1(2)E51-F066 Reactor Core Isolation Cooling A/C 1 1(2)E51-F065 Reactor Core Isolation Cooling A/C 1
2. Applicable Code Edition and Addenda
The fourth 10-year interval of the LaSalle County Station (LSCS) , Units 1 and 2, lnservice Testing (IST) Program is based on the American Society of Mechanical Engineers (ASME)
Code for Operation and Maintenance of Nuclear Power Plants (OM Code) - 2004 Edition with Addenda through OMb-2006.
3. Applicable Code Requirement
ISTC-3522, "Category C Check Valves," requires licensees to exercise Category C check valves to verify obturator travel with methods in ISTC-5221 during power operation, during cold shutdown if not practicable during power operation, or during refueling outages if not practicable during power and cold shutdowns.
Page 1 of 5
Attachment 1 10 CFR 50.55a Relief Request RV-03 Related to PIV Testing Frequency Proposed Alternative In Accordance with 10 CFR 50.55a(z)(1)
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 are 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," requires licensees to conduct these leakage rate tests at least once every two years.
4. Reason for Request
Pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (z)(1 ), relief is requested from the requirements of ASME OM Code ISTC-3630(a) for the subject valves . The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.
ISTC-3630 requires that leakage rate testing for PIVs be performed at least once every two years. Pressure Isolation Valves are not specifically included in the scope for performance-based testing as provided for in 10 CFR 50 Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors ," Option B, "Performance-Based Requirements." These motor-operated and check valve PIVs are, in some cases, Containment Isolation Valves (CIVs), but are not within the Appendix J scope since the Reactor Shutdown Cooling System valves are considered water-sealed.
The LSCS Technical Specification Section 5.5.13 contains a requirement to establish the leakage rate testing program in accordance with the guidelines contained in NEI 94-01, Revision 3-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," dated July 2012.
The concept behind the Option B alternative for CIVs is that licensees should be allowed to adopt cost effective methods for complying with regulatory requirements. Additionally, NEI 94-01 describes the risk-informed basis for the extended test intervals under Option B. That justification shows that for CIVs which have demonstrated good performance by the successful completion of two consecutive leakage rate tests over two consecutive cycles may increase their test frequencies. Furthermore, it states that if the component does not fail within two operating 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 conclusion that "the risk impact associated with increasing [leak rate]
test intervals is negligible (i.e., less than 0.1 percent of total risk) ."
The valves identified in this relief request are all in water applications. Testing is currently performed with water pressurized to pressures between 950 psig and 1050 psig as required by Technical Specification Surveillance Requirement (SR) 3.4.6.1. This relief request is intended to provide for a performance-based scheduling of PIV tests at LSCS. The reason for requesting this relief is to allow for divisional outages to reduce the required resources and dose required for testing.
Page 2 of 5
Attachment 1 10 CFR 50.55a Relief Request RV-03 Related to PIV Testing Frequency Proposed Alternative In Accordance with 10 CFR 50.55a(z)(1)
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-1985 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 with the valve in a closed condition. Typical PIV testing does not identify functional problems which may inhibit the valves ability to reposition from open to closed. For check valves, functional testing is accomplished in accordance with ASME OM Code Section ISTC-3520, "Exercising Requirements," and Section ISTC-3522, "Category C Check Valves." For power-operated valves , testing is full stroke testing in accordance with the ASME OM Code to ensure their functional capabilities. For the Category C Check Valves, the closed functional testing is credited to the PIV leak rate test. Performance of the separate two-year PIV leak rate testing provides assurance that the Category C PIV Check Valves are capable of closing but otherwise does not contribute any additional assurance of functional capability.
- 5. Proposed Alternative and Basis for Use LSCS proposes to perform PIV testing at intervals ranging from every refueling outage to every third refueling outage. The specific interval for each valve would be a function of its performance and would be established in a manner consistent with the CIV process under 10 CFR 50 Appendix J, Option B. A conservative control will be established such that if any valve fails the PIV test, the test interval for the test will be reduced consistent with Appendix J, Option B requirements until good performance is reestablished .
The primary basis for this relief request is the historically good performance of the PIVs.
The functional capability of the check valves is demonstrated by the open and close exercise test. The open testing is separate and distinct from PIV testing and is performed at a refuel outage frequency in accordance with Section ISTC-3522 of the ASME OM Code.
The closed testing takes credit for the PIV leak rate testing and will be on the same frequency as the PIV leak rate testing. The fact that the PIVs have had good historical performance shows that the Category C Check Valves are exhibiting the required obturator movement to close and remain closed .
Note that NEI 94-01 is not the sole basis for this relief request, given that NEI 94-01 does not address seat leakage testing with water. This document was cited as an approach that was similar to the requested alternative method.
If the proposed alternative is authorized and the valves exhibit good performance, there is the possibility that the PIV test frequency could be extended so that the test would not be required each refueling outage.
Testing history of the LSCS PIVs for past three outages on each unit has shown that 1E12-F050A and 2E12-F050A failed their leakage test requiring maintenance to correct excessive leakage. All other PIVs had satisfactory leakage of less than 1 gpm .
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Attachment 1 10 CFR 50.55a Relief Request RV-03 Related to PIV Testing Frequency Proposed Alternative In Accordance with 10 CFR 50.55a(z)(1)
The extension of test frequencies will be consistent with the guidance provided for Appendix J, Type C leak rate tests as detailed in NEI 94-01, Revision 3-A, Paragraph 10.2.3.2, "Extended Test Interval," (as approved by letter dated June 8, 2012 (ADAMS Accession No. ML121030286)) which states:
Test intervals for Type C valves may be increased based upon completion of two consecutive periodic as-found Type C tests where the result of each test is within a licensee's allowable administrative limits. Elapsed time between the first and last tests in a series of consecutive passing tests used to determine performance shall be 24 months or the nominal test interval (e.g. refueling cycle) for the valve prior to implementing Option B to Appendix J. Intervals for Type C testing may be increased to a specific value in a range of frequencies from 30 months up to a maximum of 75 months. Test intervals for Type C valves should be determined by the licensee in accordance with Section 11 .0.
Additional basis for this relief request is provided below:
- The low likelihood of valve mispositioning during power operations (e.g., procedures, interlocks).
- Relief valves in the low pressure (LP) piping - these relief valves may not provide Inter-System Loss of Coolant Accident (ISLOCA) mitigation for inadvertent PIV mispositioning but their relief capacity can accommodate conservative PIV seat leakage rates.
- Alarms that identify high pressure (HP) to LP leakage - Operators are highly trained to recognize symptoms of the presence of a ISLOCA and to take appropriate actions.
- 6. Duration of Proposed Alternative Relief is requested for the fourth 10-year IST interval for LSCS, Units 1 and 2, beginning October 12, 2017 and ending October 11, 2027.
- 7. Precedents
- 1. Letter from R. J. Pascarelli (U.S . Nuclear Regulatory Commission) to J. M. Davis (Detroit Edison), "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 (ADAMS Accession No. ML102360570).
- 2. Letter from J. Wiebe (U.S. Nuclear Regulatory Commission) to M. J. Pacilio (Exelon Nuclear), "Quad Cities Nuclear Power Station, Units 1 and 2 - Safety Evaluation in Support of Request for Relief Associated with the Fifth 10 Year Interval lnservice Testing Program (TAC Nos. ME7981, ME7982, ME7983, ME7984, ME7985, ME7986, ME7987, ME7988, ME7990, ME7991, ME7992, ME7993, ME7994, and ME7995)," dated February 14, 2013 (ADAMS Accession No. ML13042A348).
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Attachment 1 10 CFR 50.55a Relief Request RV-03 Related to PIV Testing Frequency Proposed Alternative In Accordance with 10 CFR 50.55a(z)(1)
- 3. Letter from T. L. Tate (U.S. Nuclear Regulatory Commission) to B. Hanson (Exelon Generation, LLC), "Dresden Nuclear Power Station, Units 2 and 3 - Relief Request to Use An Alternative from the American Society of Mechanical Engineers Code Requirements (CAC Nos. MF5089 AND MF5090)," dated October 27, 2015 (ADAMS Accession No. ML15174A303).
- 4. Letter from D. A. Broaddus (U .S. Nuclear Regulatory Commission) to B. Hanson (Exelon Generation, LLC), "Peach Bottom Atomic Power Station, Units 2 and 3 - Safety Evaluation of Relief Request GVRR-2 Regarding the Fourth 10-Year Interval of the lnservice Testing Program (CAC Nos. MF7630 and MF7631 ),"dated September 21, 2016 (ADAMS Accession No. ML16235A340).
- 5. Letter from J. G. Danna (U.S . Nuclear Regulatory Commission) to B. Hanson (Exelon Generation, LLC), "Nine Mile Point Nuclear Station, Units 1 and 2 - Re : Alternative to the Requirements of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (CAC Nos. MF9073 and MF9074)," dated May 30, 2017 (ADAMS Accession No. ML17136A112).
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Attachment 2 Leakage History of LSCS Unit 1 and Unit 2 PIVs Historical PIV Leakage The tables below show the leakage history for LSCS Unit 1 and Unit 2 PIVs for the last three tests. Tables 1 through 4 have the PIV leakage history for Unit 1 and Tables 5 through 8 have the PIV leakage history for Unit 2.
The PIV leakage of some valves were derived by using Air-to-Water correlations that were based on the results of the Appendix J Type C Local Leak Rate Tests (LLRTs) which is allowed by ASME OM Code , Section ISTC-3630(b)(4). However, all the subject valves have been removed from the Append ix J Program as part of the Append ix J Scope Reduction .
Table 1: Unit 1 Historical Leak Rate Test Performance for Low Pressure Core Spray (System E21) PIVs Measured Value Required Action Component Date of Test Comments (gpm) Limit Caom) 2/16/2014 < 1 5 1E21-F006 2/18/2016 < 1 5 2/23/2018 < 1 5 2/16/2014 < 1 5 1E21-F005 2/18/2016 < 1 5 2/23/2018 < 1 5 Table 2: Unit 1 Historical Leak Rate Test Performance for High Pressure Core Spray (System E22) PIVs Measured Value Required Action Component Date of Test Comments (gpm) Limit Caom) 2/12/2014 < 1 5 1E22-F005 3/1/2016 < 1 5 2/20/2018 < 1 5 2/12/2014 < 1 5 1E22-F004 6/26/2017 < 1 5 2/20/2018 < 1 5 Table 3: Unit 1 Historical Leak Rate Test Performance for Residual Heat Removal (System E12) PIVs Measured Value Required Action Component Date of Test Comments (gpm) Limit Caom) 2/16/2014 < 1 5 1E12-F041A 3/3/2016 < 1 5 2/23/2018 < 1 5 2/21/2014 < 1 5 1E12-F041 B 2/25/2016 < 1 5 2/26/2018 < 1 5 Page 1 of 7
Attachment 2 Leakage History of LSCS Unit 1 and Unit 2 PIVs Measured Value Required Action Component Date of Test Comments (gpm) Limit (apm) 2/21/2014 < 1 5 1E12-F041C 2/23/2016 < 1 5 2/27/2018 < 1 5 2/16/2014 < 1 5 1E12-F042A 3/3/2016 < 1 5 2/23/2018 < 1 5 Leakage based on Air-to-Water Correlation as allowed by the 2001 2/21/2014 < 1 5 Edition with 2003 1E12-F042B Addenda of the ASME OM Code, Subsection ISTC-3630(b)(4).
2/25/2016 < 1 5 2/26/2018 < 1 5 2/21/2014 < 1 5 1E12-F042C 2/23/2016 < 1 5 2/27/2018 < 1 5 2/16/2014 < 1 5 Valve failed to pressurize during 1E12-F050A 3/4/2016 < 1 5 initial test. Valve was rebuilt and tested SAT.
2/22/2018 < 1 5 2/20/2014 < 1 5 1E12-F050B 2/25/2016 < 1 5 2/21/2018 < 1 5 Leakage based on Air-to-Water Correlation as allowed by the 2001 1E12-F053A 2/13/2014 < 1 5 Edition with 2003 Addenda of the ASME OM Code, Subsection ISTC-3630(b)(4).
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Attachment 2 Leakage History of LSCS Unit 1 and Unit 2 PIVs Measured Value Required Action Component Date of Test Comments (gpm) Limit (apm) 3/3/2016 < 1 5 2/22/2018 < 1 5 Leakage based on Air-to-Water Correlation as allowed by the 2001 2/22/2014 < 1 5 Edition with 2003 1E12-F053B Addenda of the ASME OM Code, Subsection ISTC-3630(b )(4 ).
2/25/2016 < 1 5 2/21/2018 < 1 5 2/21/2014 < 1 5 1E12-F009 2/27/2016 < 1 5 2/22/2018 < 1 5 Leakage based on Air-to-Water Correlation as allowed by the 2001 2/22/2014 < 1 5 Edition with 2003 1E12-F008 Addenda of the ASME OM Code, Subsection ISTC-3630(b )(4 ).
2/27/2016 < 1 5 2/22/2018 < 1 5 Table 4: Unit 1 Historical Leak Rate Test Performance for Reactor Core Isolation Cooling (System E51) PIVs Measured Value Required Action Component Date of Test Comments (a pm) Limit laom) 2/13/2014 < 1 3 1E51-F066 2/21/2016 < 1 3 3/5/2018 < 1 3 2/13/2014 < 1 3 1E51-F065 2/22/2016 < 1 3 3/5/2018 < 1 3 Page 3 of 7
Attachment 2 Leakage History of LSCS Unit 1 and Unit 2 PIVs Table 5: Unit 2 Historical Leak Rate Test Performance for Low Pressure Core Spray (System E21) PIVs Measured Value Required Action Component Date of Test (gpm) Comments Limit (aom) 2/15/2015 < 1 5 2E21-F006 2/11/2017 < 1 5 3/3/2019 < 1 5 Leakage based on Air-to-Water Correlation as allowed by the 2001 2/14/2015 < 1 5 Edition with 2003 2E21-F005 Addenda of the ASME OM Code, Subsection ISTC-3630(b)(4).
2/11/2017 < 1 5 3/3/2019 < 1 5 Table 6: Unit 2 Historical Leak Rate Test Performance for High Pressure Core Spray (System E22) PIVs Measured Value Required Action Component Date of Test Comments (gpm) Limit (aom) 2/7/2015 < 1 5 2E22-F005 2/8/2017 < 1 5 2/18/2019 < 1 5 Leakage based on Air-to-Water Correlation as allowed by the 2001 2/4/2015 < 1 5 Edition with 2003 2E22-F004 Addenda of the ASME OM Code, Subsection ISTC-3630(b)(4) 2/8/2017 < 1 5 2/18/2019 < 1 5 Table 7: Unit 2 Historical Leak Rate Test Performance for Residual Heat Removal (System E12) PIVs Measured Value Required Action Component Date of Test Comments (gpm) Limit (aom) 2/13/2015 <1 5 2E12-F041A 2/18/2017 <1 5 Page 4 of 7
Attachment 2 Leakage History of LSCS Unit 1 and Unit 2 PIVs Measured Value Required Action Component Date of Test Comments (gpm) Limit (apm) 2/22/2019 < 1 5 2/12/2015 < 1 5 2E12-F041 B 2/10/2017 < 1 5 2/22/2019 < 1 5 2/10/2015 < 1 5 2E12-F041C 2/11/2017 < 1 5 2/22/2019 < 1 5 Leakage based on Air-to-Water Correlation as allowed by the 2001 2/8/2015 < 1 5 Edition with 2003 2E12-F042A Addenda of the ASME OM Code, Subsection ISTC-3630(b)(4) 2/18/2017 < 1 5 3/2/2019 < 1 5 Leakage based on Air-to-Water Correlation as allowed by the 2001 2/7/2015 < 1 5 Edition with 2003 2E12-F042B Addenda of the ASME OM Code, Subsection ISTC-3630(b)(4) 2/10/2017 < 1 5 2/22/2019 < 1 5 2/10/2015 < 1 5 2E12-F042C 2/11/2017 < 1 5 2/22/2019 < 1 5 2/12/2015 < 1 5 Valve failed to pressurize during 2E12-F050A 2/22/2017 < 1 5 initial test. Valve was rebuilt and tested SAT.
2/20/2019 < 1 5 Page 5 of 7
Attachment 2 Leakage History of LSCS Unit 1 and Unit 2 PIVs Measured Value Required Action Component Date of Test Comments (gpm) Limit (apm) 2/6/2015 < 1 5 2E12-F050B 2/9/2017 < 1 5 2/20/2019 < 1 5 Leakage based on Air-to-Water Correlation as allowed by the 2001 2/8/2015 < 1 5 Edition with 2003 2E12-F053A Addenda of the ASME OM Code, Subsection ISTC-3630(b)(4) 2/19/2017 < 1 5 2/20/2019 < 1 5 Leakage based on Air-to-Water Correlation as allowed by the 2001 2/5/2015 < 1 5 Edition with 2003 2E12-F053B Addenda of the ASME OM Code, Subsection ISTC-3630(b)(4) 2/9/2017 < 1 5 2/20/2019 < 1 5 Leakage based on Air-to-Water Correlation as allowed by the 2001 2/7/2015 < 1 5 Edition with 2003 2E12-F009 Addenda of the ASME OM Code, Subsection ISTC-3630(b)(4) 2/9/2017 < 1 5 2/21/2019 < 1 5 Leakage based on Air-to-Water Correlation as 2E12-F008 2/7/2015 < 1 5 allowed by the 2001 Edition with 2003 Addenda of the ASME OM Code, Page 6 of 7
Attachment 2 Leakage History of LSCS Unit 1 and Unit 2 PIVs Measured Value Required Action Component Date of Test Comments (gpm) Limit (apm)
Subsection ISTC-3630(b)(4) 2/9/2017 <1 5 2/21/2019 <1 5 Table 8: Unit 2 Historical Leak Rate Test Performance for Reactor Core Isolation Cooling (System E51) PIVs Measured Value Required Action Component Date of Test Comments (gpm) Limit (aom) 2/7/2015 <1 3 2E51-F066 2/16/2017 <1 3 2/21/2019 <1 3 2/7/2015 <1 3 2E51-F065 2/16/2017 <1 3 2/21/2019 <1 3 Page 7 of 7