Letter Sequence Approval |
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EPID:L-2020-LLR-0027, ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Second Period of the Third 10-Year Inspection Interval (Approved, Closed) |
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MONTHYEARML20049A0882020-02-17017 February 2020 ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Second Period of the Third 10-Year Inspection Interval Project stage: Request ML20079M6752020-03-19019 March 2020 Acceptance Review Determination (E-mail Dated 3/19/2020) ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations (EPID L-2020-LLR-0027 to LLR-0032) Project stage: Acceptance Review ML20184A0052020-07-0202 July 2020 Request for Additional Information (E-mail Dated 7/2/2020) Relief Request IR-3-33 for Limited Coverage Examiniations Project stage: Request ML20209A5362020-07-27027 July 2020 Response to Request for Additional Information Regarding Relief Request IR-3-33 for Limited Coverage Examinations Performed in the Second Period of the Third 10-Year Inspection Interval Project stage: Response to RAI ML20312A0022020-12-10010 December 2020 Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0027 Through L-2020-LLR-0032) Project stage: Approval ML21102A2602021-04-12012 April 2021 One-Time Interval Extension for Supplemental Position Indication Testing Project stage: Request ML21109A2092021-04-19019 April 2021 R. E. Ginna Nuclear Power Plant, Additional Information - One-Time Interval Extension for Supplemental Position Indication Testing Project stage: Supplement ML21246A1062021-09-22022 September 2021 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Alternative Request GR-03, Valve Position Verification Testing Extension Sixth 10-Year Inservice Testing Program Interval Project stage: Approval 2020-07-02
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Similar Documents at Ginna |
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Category:Code Relief or Alternative
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Ginna Nuclear Power Plant Relief Requests VR-1, VR-2 and VR-13 for the Fourth 10-Year Interval of the Pump and Valve Inservice Testing Program ML0330401202003-11-21021 November 2003 R. E. Ginna Nuclear Power Plant, Relief Request Review, Inservice Testing Program Relief Requests VR-4 and VR-8 ML0329603222003-10-20020 October 2003 Submittal of Relief Request VR-4 Related to the Requirements of 10CFR50.55a(f), Inservice Testing Requirements. ML0304202642003-02-10010 February 2003 R. E. Ginna Nuclear Power Plant, Relief, Inservice Testing Program Relief Request PR-2, MB7232 ML0314205202003-01-0909 January 2003 Enclosure - R.E. Ginna, Inservice Testing Program Relief Request PR-2 2024-07-23
[Table view] Category:Letter
MONTHYEARIR 05000244/20244022024-12-20020 December 2024 R. E. Ginna Nuclear Power Plant - Cyber Security Inspection Report 05000244/2024402 (Cover Letter Only) RS-24-077, Application to Revise Technical Specifications for Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2024-12-0909 December 2024 Application to Revise Technical Specifications for Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process IR 05000244/20244012024-11-20020 November 2024 R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2024401 IR 05000244/20240032024-11-0808 November 2024 Integrated Inspection Report 05000244/2024003 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000244/20243012024-10-22022 October 2024 Initial Operator Licensing Examination Report 05000244/2024301 ML24286A0022024-10-11011 October 2024 Core Operating Limits Report Cycle 45, Revision 0 RS-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 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing RS-24-092, Revised Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-09-25025 September 2024 Revised Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000244/20245012024-09-24024 September 2024 LLC - Emergency Preparedness Biennial Exercise Inspection Report 05000244/2024501 IR 05000244/20240052024-08-29029 August 2024 Updated Inspection Plan for R.E. 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IR 05000244/20230032023-10-25025 October 2023 LLC - Integrated Inspection Report 05000244/2023003 ML23292A0282023-10-19019 October 2023 LLC - Notification of Conduct of a Fire Protection Team Inspection 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 2024-09-25
[Table view] Category:Safety Evaluation
MONTHYEARML24170A3852024-07-16016 July 2024 R. E. Ginna Nuclear Power Plant - Alternative Associated with Inservice Testing of B Auxiliary Feedwater Pump - PR-03 ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23191A0592023-07-21021 July 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23073A3682023-03-16016 March 2023 Authorization and Safety Evaluation for Proposed Alternative I6R-10, Revision 0 Related to the Steam Generators, ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML23005A1762023-02-23023 February 2023 R. E. 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Ginna Nuclear Power Plant - Issuance of Amendment No. 137 to Revise Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) ML19325D8242019-12-23023 December 2019 R. E. Ginna Nuclear Power Plant Issuance of Amendment No. 136 to Revise Technical Specification 5.5.15, Containment Leakage Rate Testing Program, to Extend Containment Integrated Leak Rate Test Frequency ML19318E0802019-12-0202 December 2019 R. E. Ginna Nuclear Power Plant - Safety Evaluation of Alternative Request SR-1 Related to Snubber Program Aligned with Sixth 10-Year Inservice Testing Interval Program ML19252A2462019-10-29029 October 2019 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 134 to Revise the Emergency Response Organization Staffing Requirements ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19205A4532019-08-0505 August 2019 R. E. 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Ginna - Issuance of Amendment Nos. 327, 305, 232, 173, and 133, Respectively, Eliminating the Nuclear Advisory Committee Requirements ML18213A3692018-11-13013 November 2018 Issuance of Amendment No. 132 Revise Technical Specifications 3.3.1, Reactor Trip System Instrumentation, and 3.3.2, Engineered Safety Feature Actuation System Instrumentation ML18295A6302018-10-31031 October 2018 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 131 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF 547, Clarification of Rod Position Requirements ML18214A1762018-08-31031 August 2018 Issuance of Amendment No. 130, Revise Technical Specification Surveillance Requirement 3.8.4.3, DC (Direct Current) Sources - Modes 1, 2, 3, and 4 ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18190A4722018-07-12012 July 2018 R.E Ginna - Correction to Amendment No. 127 Related to Request to Delete a Modification Associated with the Risk-Informed, Performance Based Fire Protection Program in Accordance with 10 CFR 50.48(c) (CAC No. MF9948; EPID L-2017-LLA-0253) 2024-07-16
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September 22, 2021 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT - ISSUANCE OF ALTERNATIVE REQUEST GR-03, VALVE POSITION VERIFICATION TESTING EXTENSION SIXTH 10-YEAR INSERVICE TESTING PROGRAM INTERVAL (EPID L-2020-LLR-0027)
Dear Mr. Hanson:
By letter dated April 12, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21102A260), as supplemented by a revision dated April 19, 2021 (ADAMS Accession No. ML21109A209), Exelon Generation Company, LLC (Exelon, the licensee) submitted Alternative Request GR-03 to the U.S. Nuclear Regulatory Commission (NRC) regarding specific Inservice Testing (IST) Program requirements in the 2012 Edition of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code) as incorporated by reference in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a at R.E. Ginna Nuclear Power Plant (Ginna) associated with the sixth 10-year IST program interval.
Specifically, pursuant to 10 CFR 50.55a(z)(2), the licensee requested to use the proposed alternative in request GR-03, on the basis that complying with the requirements of the OM Code would result in hardship without a compensating increase in the level of quality and safety. On April 26, 2021, the NRC provided a verbal authorization (ADAMS Accession No. ML21117A031) of Alternative Request GR-03 for Ginna. The verbal authorization documentation provides a summary of the NRC staff evaluation for this proposed alternative. Although the licensee submitted its request under 10 CFR 50.55a(z)(2), the staff evaluated this alternative request under 10 CFR 50.55a(z)(1) consistent with review precedent.
The NRC staff finds that the implementation of Alternative Request GR-03 at Ginna provides an acceptable level of quality and safety until December 28, 2021. Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, the NRC authorizes the use of Alternative Request GR-03 at Ginna until December 28, 2021.
All other ASME OM Code requirements for which relief was not specifically requested and approved remain applicable.
If you have any questions, please contact the Limerick Project Manager, V. Sreenivas, at 301-415-2597 or V.Sreenivas@nrc.gov.
Sincerely, James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Safety Evaluation cc: Listserv James G.
Danna Digitally signed by James G. Danna Date: 2021.09.22 08:44:08 -04'00'
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ALTERNATIVE REQUEST GR-03, VALVE POSITION VERIFICATION TESTING EXTENSION SIXTH 10-YEAR INSERVICE TESTING PROGRAM INTERVAL EXELON GENERATION COMPANY, LLC R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244
1.0 INTRODUCTION
By letter dated April 12, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21102A260), as supplemented by a revision dated April 19, 2021 (ADAMS Accession No. ML21109A209), Exelon Generation Company, LLC (Exelon, the licensee) submitted Alternative Request GR-03 to the U.S. Nuclear Regulatory Commission (NRC) regarding specific Inservice Testing (IST) Program requirements in the 2012 Edition of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code) as incorporated by reference in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a at R.E. Ginna Nuclear Power Plant (Ginna) associated with the Sixth 10-Year IST Program interval.
Specifically, pursuant to 10 CFR 50.55a(z)(2), the licensee requested to use the proposed alternative in request GR-03, on the basis that complying with the requirements of the OM Code would result in hardship without a compensating increase in the level of quality and safety.
Although the licensee submitted its request under 10 CFR 50.55a(z)(2), the staff evaluated this alternative request under 10 CFR 50.55a(z)(1) consistent with review precedent.
On April 26, 2021, the NRC provided a verbal authorization (ADAMS Accession No. ML21117A031) of Alternative Request GR-03 for Ginna. The verbal authorization documentation provides a summary of the NRC staff evaluation for this proposed alternative.
This safety evaluation (SE) provides the details of the NRC staff review of Alternative Request GR-03 for Ginna.
2.0 REGULATORY EVALUATION
The NRC regulations in 10 CFR 50.55a(f), "Inservice Testing Requirements," require, in part, that inservice testing of certain ASME Code Class 1, 2, and 3 components meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraph 10 CFR 50.55a(z)(1) or 10 CFR 50.55a(z)(2).
The NRC regulations in 10 CFR 50.55a(b)(3)(xi), OM condition: Valve Position Indication, state the following:
When implementing paragraph ISTC-3700, Position Verification Testing, in the ASME OM Code, 2012 Edition through the latest edition and addenda of the ASME OM Code incorporated by reference in paragraph (a)(1)(iv) of this section, licensees shall verify that valve operation is accurately indicated by supplementing valve position indicating lights with other indications, such as flow meters or other suitable, to provide assurance of proper obturator position for valves with remote position indication within the scope of Subsection ISTC including its mandatory appendices and their verification methods and frequencies.
In proposing alternatives, a licensee must demonstrate that the proposed alternatives provide an acceptable level of quality and safety (10 CFR 50.55a(z)(1)) or compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety (10 CFR 50.55a(z)(2)).
3.0 TECHNICAL EVALUATION
3.1 Licensees Alternative Request GR-03 The IST requirements of the ASME OM Code as incorporated by reference in 10 CFR 50.55a related to this alternative request are as follows:
ASME OM Code, Subsection ISTC-3700, Position Verification Testing, states, in part, that:
Valves with remote position indicators shall be observed locally at least once every 2 yr [years] to verify that valve operation is accurately indicated. Where practicable, this local observation should be supplemented by other indications such as use of flow meters or other suitable instrumentation to verify obturator position. These observations need not be concurrent. Where local observation is not possible, other indications shall be used for verification of valve operation.
In its submittal dated April 12, 2021, as supplemented by a revision dated April 19, 2021, the licensee requested a one-time extension of the testing interval for the following 15 valves at Ginna:
Valve ID Description Code Class Category Type 310 Excess Letdown Loop A Cold to Heat Exchanger Valve 1
B AOV 371 Letdown Isolation Valve Residual Heat Removal to Non-Regenerative Heat Exchanger 2
A AOV 386 Reactor Coolant Pump A and B Seal Bypass Valve 2
B AOV 5392 Instrument Air to Containment Isolation Valve 2
A AOV 835A Safety Injection Accumulator A Fill Valve 2
B AOV 835B Safety Injection Accumulator B Fill Valve 2
B AOV 839A Safety Injection Accumulator A Test Valve 2
B AOV 840A Safety Injection Accumulator B Test Valve 2
B AOV 844A Safety Injection Accumulator A Drain Valve 2
B AOV 844B Safety Injection Accumulator B Drain Valve 2
B AOV 875A Upper Containment Spray Charcoal Filter Dousing Valve 2
B MOV 875B Upper Containment Spray Charcoal Filter Dousing Valve 2
B MOV 876A Lower Containment Spray Charcoal Filter Dousing Valve 2
B MOV 876B Lower Containment Spray Charcoal Filter Dousing Valve 2
B MOV 966A Pressurizer Steam Space Sample Containment Isolation Valve 2
A AOV
=
Reason for Request===
In its submittal, the licensee proposed that compliance with the provisions in ASME OM Code, Subsection ISTC, paragraph ISTC-3700, as incorporated by reference in 10 CFR 50.55a and supplemented by 10 CFR 50.55a(b)(3)(xi), to perform obturator position verification testing of specific valves during the spring 2021 at Ginna would result in a hardship without a compensating increase in the level of quality and safety in accordance with 10 CFR 50.55a(z)(2). The most-limiting supplemental position indication (SPI) testing interval for these valves would end on April 28, 2021, based on the 2-year interval that came into effect on January 1, 2020, and considering the use of the 6-month interval extension allowed by ASME OM Code Case OMN-20, Inservice Test Frequency. The ISTC-3700 position verification requirement as supplemented by 10 CFR 50.55a(b)(3)(xi) requires the valves to be exercised in the open and closed direction and the valve obturator position verified by other indications, such as use of flow meters or other suitable instrumentation. The licensee stated that the position verification testing would require a forced plant shutdown at Ginna.
Although the licensee submitted its request under 10 CFR 50.55a(z)(2), the staff evaluated this alternative request under 10 CFR 50.55a(z)(1) consistent with review precedent. In its request dated April 12, 2021, as supplemented by a revision dated April 19, 2021, the licensee proposed a one-time extension of eight months (to December 28, 2021) for position verification testing of 15 valves listed above at Ginna to allow the testing to be performed during the next refueling outage, which is scheduled to begin on October 4, 2021.
3.2
NRC Staff Evaluation
As incorporated by reference in 10 CFR 50.55a, ASME OM Code (2012 Edition), Subsection ISTC-3700, requires, in part, that valves with remote position indicators shall be observed locally at least once every 2 years to verify that valve operation is accurately indicated. Where practicable, this local observation should be supplemented by other indications such as use of flow meters or other suitable instrumentation to verify obturator position. The NRC regulations in 10 CFR 50.55a(b)(3)(xi) require that licensees implementing the ASME OM Code (2012 or later Editions) verify that valve operation is accurately indicated by supplementing valve position indicating lights with other indications, such as flow meters or other suitable instrumentation to provide assurance of proper obturator position for valves with remote position indication within the scope of Subsection ISTC including its mandatory appendices and their verification methods and frequencies.
In lieu of performing the ASME OM Code valve position testing requirements as supplemented by 10 CFR 50.55a(b)(3)(xi), the licensee requested a one-time extension of eight months to the next refueling outage currently scheduled for October 2021 for the valve position testing of the 15 valves listed in the above table. The eight-month extension includes the six-month grace period allowed by ASME OM Code Case OMN-20. The NRC staff notes that ASME OM Code Case OMN-20 is accepted in Regulatory Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, as incorporated by reference in 10 CFR 50.55a.
In its request dated April 12, 2021, the licensee stated that these valves have demonstrated exceptional performance and reliability, and have satisfactorily passed their IST tests for the past 10 years. Additionally, the licensee indicated that these valves have no history of stem-disk separation. In a revision dated April 19, 2021, the licensee provided additional information regarding the specific tests or operations that have been performed on the individual valves listed in its submittal to provide confidence in the open or closed obturator positions. For example, the open position of some of the 15 valves has been verified by flow during normal operation or IST testing, while the closed position of some of these valves has been verified by maintaining system pressure or water level during normal operations or IST testing.
Based on the information described above for these 15 valves, the NRC staff finds that (1) previous IST testing including position verification testing of these valves indicates their acceptable historical performance; (2) no current concerns with the performance of these valves have been identified; (3) periodic maintenance activities are not modified by this request; and (4) the alternative provides an acceptable level of quality and safety for the short extension of the valve position indication testing interval requested in the licensees submittal.
4.0 CONCLUSION
On April 26, 2021, the NRC provided a verbal authorization of Alternative Request GR-03 for Ginna. As described in this SE, the NRC staff finds that the implementation of Alternative Request GR-03 for the 15 valves at Ginna will provide an acceptable level of quality and safety until December 28, 2021. Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, the NRC authorizes the use of Alternative Request GR-03 at Ginna until December 28, 2021.
All other ASME Code requirements for which relief or an alternative was not specifically requested, and granted or authorized (as appropriate), in the subject request remain applicable.
Principal Contributors: M. Farnan T. Scarbrough Y. Wong Dated: September 22, 2021
ML21246A106
- by e-mail OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DEX/EMIB/BC/(A)*
NAME VSreenivas KZeleznock YTseng DATE 09/02/2021 09/09/2021 08/09/2021 OFFICE NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME JDanna VSreenivas DATE 9/22/21 9/22/21