Letter Sequence Other |
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EPID:L-2020-LLR-0052, CFR 50.55a Request Number: VRR4, Revision 0, Containment Isolation Valve Test Frequency (Approved, Closed) |
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MONTHYEARL-20-060, CFR 50.55a Request Number: VRR4, Revision 0, Containment Isolation Valve Test Frequency2020-04-0202 April 2020 CFR 50.55a Request Number: VRR4, Revision 0, Containment Isolation Valve Test Frequency Project stage: Request L-20-127, Supplement to 10 CFR 50.55a Request Number VRR4, Revision 0, Containment Isolation Valve Test Frequency2020-04-0606 April 2020 Supplement to 10 CFR 50.55a Request Number VRR4, Revision 0, Containment Isolation Valve Test Frequency Project stage: Request ML20099K2152020-04-0808 April 2020 Verbal Relief for CIVs - Delivered 4/8/2020 at 10:00 A.M Project stage: Other ML20099B2572020-04-0808 April 2020 Verbal Relief Unit 2 CIV Project stage: Other ML20153A0142020-07-16016 July 2020 Relief from the Requirements of the American Society of Mechanical Engineers Code Regarding Request VRR4 (EPID L-2020-LLR-0052 (COVID-19)) Project stage: Approval ML22153A5212022-04-15015 April 2022 Email Error in Energy Harbor Submittal and Associated SE for Beaver Valley 1 & 2 - Containment Isolation Valve Relief Request Project stage: Approval 2020-04-08
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Category:Code Relief or Alternative
MONTHYEARML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 ML22082A2532022-03-29029 March 2022 Correction Letter - Issuance of Authorization of Proposed Alternative to Use ASME OM Code Case OMN-27 ML22012A2972022-01-21021 January 2022 Proposed Alternative to Use ASME OM Code Case OMN-27 L-20-256, Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-09-28028 September 2020 Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML20223A0142020-08-20020 August 2020 Issuance of Relief Request SSR-1, Revision 0, from the Requirements of the ASME Code (EPID L-2020-LLR-0050 (COVID-19)) ML20206K8652020-08-0707 August 2020 Relief Requests 2-TYP-4-RV-06 and 2-TYP-4-RV-07 from the Requirements of the ASME Code (EPID L-2020-LLR-0053 and EPID L-2020-LLR-0054 (COVID-19)) ML20145A0002020-06-0303 June 2020 Relief from the Requirements of the ASME Code for Requests VRR6 and VRR5 (EPID L-2020-LLR-0049 and EPID L-2020-LLR-0051 (COVID-19)) ML20100N3222020-04-0909 April 2020 Verbal Relief for Penetration Evaluation and Hot Leg Nozzles - Delivered 4/9/2020 at 10:00 Am ML20099B2572020-04-0808 April 2020 Verbal Relief Unit 2 CIV ML20098F3012020-04-0707 April 2020 Verbal Relief for Appendix I Safety Relief Valves ML20095J2192020-04-0404 April 2020 Email Beaver Valley Power Station, Unit 2 - Verbal Relief for MOVs - Delivered 4/4/2020 at 4:00 Pm ML20095J0992020-04-0404 April 2020 Email Beaver Valley Power Station, Unit 2 - Verbal Relief for Snubbers - Delivered 4/4/2020 at 4:00 P.M L-20-117, 10 CFR 50.55a Request Number 2-TYP-4-RV-06, Hardship for Hot Leg Nozzle Inspections2020-04-0303 April 2020 10 CFR 50.55a Request Number 2-TYP-4-RV-06, Hardship for Hot Leg Nozzle Inspections L-20-118, CFR 50.55a Request Number SRR-1, Revision 0, Snubber Testing2020-04-0303 April 2020 CFR 50.55a Request Number SRR-1, Revision 0, Snubber Testing L-20-060, CFR 50.55a Request Number: VRR4, Revision 0, Containment Isolation Valve Test Frequency2020-04-0202 April 2020 CFR 50.55a Request Number: VRR4, Revision 0, Containment Isolation Valve Test Frequency L-20-116, CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency2020-04-0101 April 2020 CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency ML20079F8162020-03-26026 March 2020 Relief Requests 1-TYP-4-C2.21-1 and 1-TYP-4-RA-1 Regarding Weld Examination Coverage for the Fourth Inservice Inspection Interval ML19275E2942019-10-16016 October 2019 Issuance of Relief Request Proposed Alternative to Reactor Vessel Nozzle Weld Examination Frequency Requirements in Lieu of Specific ASME Code Requirements L-19-107, Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2019-08-27027 August 2019 Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements ML19051A1082019-02-20020 February 2019 Request Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds (Request 2-TYP-4-RV-05, Revision 0) ML18227A7332018-08-27027 August 2018 Request for Relief from the Requirements of the ASME Code ML18004A1222018-01-22022 January 2018 FENOC-Beaver Valley, Davis-Besse, and Perry - Alternative for the Use of ASME Code Case N-513-4 (CAC Nos. MG0120, MG0121, MG0122, and MG0123; EPID L-2017-LLR-0088) L-17-317, Request to Extend Certain Reactor Vessel Inspections from 10 to 20 Years (Request 1-TYP-4-BN-01)2017-11-15015 November 2017 Request to Extend Certain Reactor Vessel Inspections from 10 to 20 Years (Request 1-TYP-4-BN-01) L-17-308, 10 CFR 50.55a Request for Alternate Reactor Vessel Nozzle Flaw Depth Sizing Criteria (Request 2-TYP-4-RVSE-2)2017-10-25025 October 2017 10 CFR 50.55a Request for Alternate Reactor Vessel Nozzle Flaw Depth Sizing Criteria (Request 2-TYP-4-RVSE-2) ML17167A0672017-06-26026 June 2017 Requests for Alternatives and Requests for Relief Fourth 10-Year Inservice Test Program Interval (CAC Nos. MF8333-MF8356). Note: Correction Safety Evaluation See ML17255A526 ML17159A4422017-06-26026 June 2017 Requests for Alternatives and Requests for Relief Fifth 10-Year Inservice Testing Program Interval (CAC Nos. MF8332 Through MF8357). Note: Correction Safety Evaluation See ML17255A508 ML17047A6102017-03-0202 March 2017 Relief from the Requirements of the American Society of Mechanical Engineers Code ML17041A1852017-03-0202 March 2017 Relief from the Requirements of the ASME Code ML17048A0042017-03-0202 March 2017 Relief from the Requirements of the ASME Code ML16328A1252017-01-23023 January 2017 Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) (TAC No. MF7780 - MF7783) ML16190A1332016-12-27027 December 2016 Relief from the Requirements of the ASME Code ML16319A0572016-12-0101 December 2016 Acceptance of Requested Licensing Action Relief Request for Proposed Alternative to Perform As-Found Set-Pressure Test ML16257A6212016-11-21021 November 2016 Relief Request BV2-PZR-01, Regarding Alternative to Requirements for Components Connected to the Steam Side of the Pressurizer ML16228A4082016-10-21021 October 2016 Correction to Relief Request 2-TYP-3-RV-04, Revision 0, Regarding Repair Activities for Reactor Vessel Head Penetration Nozzles and Associated J-Groove Welds ML16147A3622016-06-17017 June 2016 Relief Request No. 2-TYP-3-RV-04, Revision 0, Regarding Repair Activities for Reactor Vessel Head Penetration Nozzles and Associated J-Groove Welds ML14363A4092015-01-28028 January 2015 Relief Request No. 1-TYP-4-RV-04 Regarding the Examination Requirements of Code Case N-729-1 ML1202702982012-02-0707 February 2012 Relief Request VRR3 Regarding Solenoid Operated Valve Remote Position Verification Frequency ML1131304282011-11-22022 November 2011 Relief Request VRR5 Regarding Turbine Driven Auxiliary Feedwater Valve Test Frequency for the 10-Year Inservice Testing Program Interval ML1126404122011-09-20020 September 2011 Acceptance Review Results for VC Summer Relief Request (ME6879) ML1107705512011-04-26026 April 2011 Relief Request VRR2 Regarding the 10-Year Inservice Testing Program Interval ML1104705572011-02-25025 February 2011 Relief Request Regarding an Alternative Weld Repair Method for Reactor Vessel Head Penetrations J-Groove Welds ML1006807812010-03-12012 March 2010 Third 10-Year ISI Interval Relief Request (ME2608) L-08-362, Beaver, Units 1 and 2, Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Paragraph IWA-5244 Examination Requirements2008-12-0202 December 2008 Beaver, Units 1 and 2, Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Paragraph IWA-5244 Examination Requirements L-08-207, Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Inspection Period Extension Requirement2008-09-24024 September 2008 Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Inspection Period Extension Requirement L-08-069, Impractical American Society of Mechanical Engineers Code Section XI Weld Examination Requirements (Request Nos. 1-TYP-3-RA-1, 1-TYP-3-RA-2, 1-TYP-3-RA-3)2008-04-0909 April 2008 Impractical American Society of Mechanical Engineers Code Section XI Weld Examination Requirements (Request Nos. 1-TYP-3-RA-1, 1-TYP-3-RA-2, 1-TYP-3-RA-3) ML0720504882007-09-17017 September 2007 Relief Request No. BV1-PZR-01 Regarding Weld Overlay Repairs on Pressurizer Nozzle Welds ML0705905552007-04-30030 April 2007 Relief, Relief Request No. BV2-PZR-01 Regarding Weld Overlay Repairs on Pressurizer Nozzle Welds L-07-056, Requests Approval of Proposed Alternatives and Relief for Inservice Testing Program Ten-Year Update2007-03-28028 March 2007 Requests Approval of Proposed Alternatives and Relief for Inservice Testing Program Ten-Year Update ML0625801202006-10-0202 October 2006 (BVPS-1 and 2), Inservice Inspection (ISI) Program, Alternative Examination of Reactor Coolant Pipe Welds, Request for Relief No. BV3-RV-2 L-06-042, Proposed Alternative to American Society of Mechanical Engineers Code Section XI Examination Requirements2006-04-0707 April 2006 Proposed Alternative to American Society of Mechanical Engineers Code Section XI Examination Requirements 2023-09-18
[Table view] Category:E-Mail
MONTHYEARML23129A3122023-05-0909 May 2023 NRR E-mail Capture - Beaver Valley Unit 2 - Verbal Authorization of Alternative Request, 2-TYP-4-RV-06 ML23128A1612023-05-0808 May 2023 NRR E-mail Capture - Comanche Peak Nuclear Power Plant, Units 1 and 2, Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit No. 1 - Acceptance of Requested Licensing ML23125A1462023-05-0505 May 2023 NRR E-mail Capture - Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23125A1602023-05-0505 May 2023 NRR E-mail Capture - Correction to Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23122A0342023-05-0202 May 2023 NRR E-mail Capture - Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report ML23089A1252023-03-30030 March 2023 NRR E-mail Capture - Beaver Valley Upcoming Steam Generator Tube Inservice Inspection ML23079A1202023-03-20020 March 2023 NRR E-mail Capture - Acceptance Review for Beaver Valley 1 & 2 Exemption from Specific Provisions in 10 CFR 50 Appendix H ML23065A0782023-03-0303 March 2023 Final RAIs Regarding the Beaver Valley Emergency LAR (EPID L-2023-LLA-002) - Email ML22321A2392022-11-17017 November 2022 NRR E-mail Capture - (External_Sender) Beaver Valley Power Station, Units 1&2 - Clarification on LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22312A5912022-11-0808 November 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1&2 - Request for Additional Information LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22273A1132022-09-30030 September 2022 NRR E-mail Capture - Acceptance of Requested Licensing Action to Add Full Spectrum LOCA Methodology to COLR ML22277A5122022-09-19019 September 2022 NRR E-mail Capture - (External_Sender) Eh Response to Corrected SE Associated with Beaver Valley Amendments 315 and 205 Changes to the EPP ML22238A2812022-08-25025 August 2022 Request for Additional Information for Beaver Valley Unit 2 - 2R22 Steam Generator 180 Day Report ML22202A4642022-06-29029 June 2022 Emergency Plan Safety Evaluation ML22178A1322022-06-24024 June 2022 Request for Additional Information for Beaver Valley Unit 2 Steam Generator Inspection Report - Fall 2021 Refueling Outage ML22173A0402022-06-21021 June 2022 NRR E-mail Capture - Acceptance of Requested Licensing Action Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22147A0392022-05-27027 May 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley, Units 1 & 2 Amendment - Revise TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Separation Instrumentation ML22129A0122022-05-0606 May 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Unit 2 Amendment - Correct TS 3.1.7 Change Made by TSTF-547 ML22123A0232022-05-0202 May 2022 NRR E-mail Capture - Acceptance of Requested Licensing Action for Beaver Valley Power Station, Units 1 and 2 - Adoption of TSTF-501, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML22153A5212022-04-15015 April 2022 Email Error in Energy Harbor Submittal and Associated SE for Beaver Valley 1 & 2 - Containment Isolation Valve Relief Request ML22101A0122022-04-0808 April 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Units 1 and 2 Amendment - Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR) ML22087A1302022-03-28028 March 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Units 1 and 2 Amendment - Adopt TSTF-577 ML22080A2512022-03-18018 March 2022 NRR E-mail Capture - (External_Sender) ASME OM Code Case OMN-27, Alternative Requirements for Testing Category a Valves (Non- Piv/Civ) ML22068A1822022-03-0909 March 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1 & 2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5 ML21344A0392021-12-0909 December 2021 NRR E-mail Capture - Beaver Valley TSTF-577-A Acceptance Review ML21321A3782021-11-16016 November 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSEL Unit 1 - Acceptance of License Amendment Request Adoption of TSTF-554 EPID-L-2021-LLA-0193 ML21286A7892021-10-0707 October 2021 NRR E-mail Capture - Beaver Valley Acceptance Review for LAR Regarding TS 3.1.7.2 to Correct a Logic Error (L-2021-LLA-0160) ML21266A2222021-09-23023 September 2021 NRR E-mail Capture - Beaver Valley Loss of Power Diesel Generator Start and Bus Separation Instrument ML21259A1642021-09-16016 September 2021 NRR E-mail Capture - Request for Additional Information Regarding the LAR for Core Operating Limits ML21225A0362021-08-12012 August 2021 NRR E-mail Capture - Beaver Valley Unit Nos. 1 and 2 - Acceptance Review Determination Emergency Plan Amendment Request ML21197A0242021-07-15015 July 2021 NRR E-mail Capture - Beaver Valley No. 1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action Emergency Plan Amendment Request ML21137A0082021-05-14014 May 2021 Acceptance of License Amendment Request: Beaver Valley COLR TS LAR ML21119A2152021-04-28028 April 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSE Unit 1 - Acceptance of Relief Request Proposed Alternative to Use ASME OM Code Case OMN-27 ML21102A1542021-04-0909 April 2021 Request for Additional Information (2nd Round) - Steam Generator Tube Sleeve LAR ML21082A4942021-03-23023 March 2021 Final RAIs for GL 04-02 Closure (Email) ML21068A3502021-03-0909 March 2021 Final Request for Additional Information for Reactor Coolant System (RCS) and Pressure and Tempature Limits Report(Ptlr) TS LAR ML21053A0252021-02-20020 February 2021 NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing ML21032A2582021-02-0101 February 2021 Acceptance of License Amendment Request: Beaver Valley Steam Generator Inspection Deferral ML21015A5762021-01-14014 January 2021 Final RAIs for Steam Generator 180 Day Tube Inspection Report ML21014A1142021-01-12012 January 2021 Correction Letter Notification from Licensee ML21007A3732021-01-0707 January 2021 NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, ML21004A1442020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff ML20329A4562020-11-24024 November 2020 Acceptance of License Amendment Request: Beaver Valley RCS and PTLR TS Changes ML20325A2312020-11-20020 November 2020 Request for Additional Information - Beaver Valley Request for Exemption - Part 73 Force-on-Force Exemption ML20324A0872020-11-19019 November 2020 Acceptance of Requested Licensing Action: Beaver Valley Unit 2 Capsule Pull ML20323A0452020-11-17017 November 2020 2.206 Petition ML20310A1632020-11-0404 November 2020 Acceptance of Requested Licensing Action: Beaver Valley One-time Exemption App. B Sect. VI.C.3.(I)(1) Force on Force (COVID-19) ML20307A5762020-11-0202 November 2020 Acceptance of Requested Licensing Action: Beaver Valley Adv Non-Conservative TS LAR ML20297A3222020-10-22022 October 2020 Final Request for Additional Information - Steam Generator Tube Sleeve LAR ML20283A7722020-10-0909 October 2020 Submittal of Pennsylvania Letter Requesting Exemption from Biennial Exercise Requirements for Pennsylvania Nuclear Power Plants in Calendar Year 2020 2023-05-09
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From: Tobin, Jennifer To: "rpenfield@firstenergycorp.com" Cc: "Lashley, Phil H (EH)"; "McCreary, Dave M (EH)"
Subject:
Verbal Relief for CIVs - Delivered 4/8/2020 at 10:00 am Date: Wednesday, April 08, 2020 10:21:00 AM Good afternoon Mr. Penfield, Please find below a written documentation of the verbal relief that NRC provided this morning (4/8/2020). This email will be made publicly available.
Please contact me with questions or concerns.
Thanks!
-Jenny VERBAL AUTHORIZATION BY THE NRC OFFICE OF NUCLEAR REACTOR REGULATION FOR 10 CFR 50.55a REQUEST L-20-127-VRR4, REVISION 0, ISOLATION VALVE TEST FREQUENCY BEAVER VALLEY POWER STATION, UNIT 2 ENERGY HARBOR DOCKET NO. 50-412 APRIL 8, 2020 Technical Evaluation read by Thomas G. Scarbrough, Acting Chief, Mechanical Engineering and Inservice Testing Branch, Division of Engineering and External Hazards, NRC Office of Nuclear Reactor Regulation By letter dated April 6, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20097C373), Energy Harbor (the licensee) proposed an alternative to specific requirements in the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), 2004 Edition through 2006 Addenda, for Beaver Valley Power Station (BVPS), Unit 2, pursuant to Title 10 of the Code of Federal Regulations, Part 50, Section 55a (10 CFR 50.55a).
In particular, the licensee submitted 10 CFR 50.55a Request L-20-127-VRR4, Revision 0, Containment Isolation Valve Test Frequency, on April 6, 2020, requesting NRC authorization to extend the performance of leakage testing for 35 specific isolation valves at Beaver Valley Unit 2 listed in the submittal. The licensee submitted the request on April 6, 2020, as a supplement to a previous request dated April 2, 2020, (ADAMS Accession No. ML20093C288) that had proposed an alternative to the ASME OM Code requirements for the isolation valve leakage testing program at BVPS. The NRC staffs evaluation described in this Verbal Authorization applies only to the 35 specific isolation valves at Beaver Valley Unit 2 listed in the submittal dated April 6, 2020.
In its submittal dated April 2, 2020, the licensee provided justification that compliance with the provisions in ASME OM Code, Subsection ISTC, Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants, paragraph ISTC-3630, Leakage Rate for Other Than Containment Isolation Valves, subparagraph (a), Frequency, as incorporated by reference in 10 CFR 50.55a, to conduct leakage testing of isolation valves every 2 years 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), if performed at this time. For example, the licensee indicated that the performance of leakage testing of isolation valves at this time would represent a hardship during this COVID-19 outbreak, because the licensee intends to reduce the amount of personnel on site to prevent the spread of COVID-19 at BVPS.
The licensee is also contingency planning in case some of its workforce becomes
unavailable due to the COVID-19 outbreak.
In its submittal dated April 2, 2020, the licensee reported that its review of the leakage test results for the specific isolation valves at Beaver Valley Unit 2 showed that the valves maintained a history of excellent performance, with the exception of a reactor coolant system loop fill header flow control valve that failed its leakage test in 2012 but, after adjustments, has demonstrated acceptable performance since then. The licensee considers that the performance of these isolation valves with acceptable results for at least two consecutive outages prior to submittal of its request supports an extension of the leakage test interval for these valves.
Based on the information described above for the 35 isolation valves at Beaver Valley Unit 2 identified in the licensees submittal, the NRC staff finds that (1) previous leakage testing of these isolation valves indicates their acceptable historical performance; (2) no current concerns with the performance of these isolation valves have been identified; (3) periodic maintenance activities are not modified by this request; and (4) a hardship exists for the performance of team-oriented leakage testing of these isolation valves at this time that would be contrary to the health and safety of plant personnel.
Therefore, the NRC finds that the licensees proposed alternative, submitted in accordance with 10 CFR 50.55a(z)(2), will provide reasonable assurance that the specified 35 isolation valves at Beaver Valley Unit 2 will be operationally ready to perform their safety functions until the next refueling outage in the fall of 2021. All other ASME OM Code requirements as incorporated by reference in 10 CFR 50.55a for which relief or an alternative was not specifically requested and approved in this request dated April 6, 2020, remain applicable.
If the licensee identifies a performance issue with any of these isolation valves, the licensee will be expected to take action to implement the requirements of its Technical Specifications. This authorization will remain in effect until restart from the next refueling outage for Beaver Valley Unit 2 in the fall of 2021. This Verbal Authorization is applicable to the extension of the leakage testing interval for the 35 isolation valves specified in the licensees request dated April 6, 2020, from the upcoming refueling outage (2R21) scheduled to begin in April 2020, to the following refueling outage (2R22) planned for the fall of 2021. The NRC staff review of the proposal in the licensees submittal dated April 2, 2020, to modify the isolation valve leakage testing program at BVPS will be conducted through a separate safety evaluation. The licensees leakage testing plans for these isolation valves may be adjusted as appropriate by any subsequent NRC-authorized alternative requests.
Authorization read by James Danna, Chief of the Plant Licensing Branch I, Office of Nuclear Reactor Regulation As Chief of the Plant Licensing Branch I, Office of Nuclear Reactor Regulation, I agree with the conclusions of the Mechanical Engineering and Inservice Testing Branch.
The NRC staff concludes that the proposed relief for Beaver Valley, Unit 2 will provide reasonable assurance of adequate safety until the next scheduled refueling outage in the fall of 2021 when leakage testing for the 35 specific isolation valves may be performed.
The NRC staff finds that complying with the requirements of the ASME OM Code, Subsection ISTC, as required by 10 CFR 50.55a, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2).
Therefore, effective April 8, 2020, the NRC authorizes the use of the proposed alternative at Beaver Valley, Unit 2 until completion of the next scheduled refueling outage, scheduled
for the fall of 2021. All other requirements in ASME OM Code for which relief was not specifically requested and approved in this relief request remain applicable.
This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding the proposed relief while subsequently preparing the written safety evaluation.