Letter Sequence Other |
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EPID:L-2021-LLR-0011, 10 CFR 50.55a Request Number VR-4, Revision 0, Exercising Test Frequency, VR-6, Revision 0, Position Verification Testing, and VR-8, Revision 0, Valve Test Frequency Extension (Approved, Closed) |
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MONTHYEARL-21-045, 10 CFR 50.55a Request Number VR-4, Revision 0, Exercising Test Frequency, VR-6, Revision 0, Position Verification Testing, and VR-8, Revision 0, Valve Test Frequency Extension2021-02-0808 February 2021 10 CFR 50.55a Request Number VR-4, Revision 0, Exercising Test Frequency, VR-6, Revision 0, Position Verification Testing, and VR-8, Revision 0, Valve Test Frequency Extension Project stage: Request ML21054A1802021-02-16016 February 2021 NRR E-mail Capture - Perry Nuclear Power Plant - Acceptance of Relief Requests Regarding VR-4, VR-6, and VR-8 Valve Testing Extensions Project stage: Acceptance Review ML21050A1112021-02-18018 February 2021 NRR E-mail Capture - Perry Nuclear Power Plant - Request for Additional Information for Proposed Alternative Requests VR-4, Rev. 0 and VR-6, Rev. 0 Project stage: RAI L-21-080, Response to Requests for Additional Information Re 10 CFR 50.55a Request Numbers VR-3. VR-4. VR-5, VR-61 and VR-7 (EPID Numbers L-2021-LLR-0007, L-2021-LLR-0008, L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011)2021-02-22022 February 2021 Response to Requests for Additional Information Re 10 CFR 50.55a Request Numbers VR-3. VR-4. VR-5, VR-61 and VR-7 (EPID Numbers L-2021-LLR-0007, L-2021-LLR-0008, L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011) Project stage: Response to RAI ML21063A1982021-03-0404 March 2021 NRR E-mail Capture - Perry Nuclear Power Plant - Verbal Authorization of Request VR-8, Revision 0 Project stage: Other ML21063A1952021-03-0404 March 2021 NRR E-mail Capture - Perry Nuclear Power Plant - Verbal Authorization of Request VR-6, Revision 0 Project stage: Other ML21063A1922021-03-0404 March 2021 NRR E-mail Capture - Perry Nuclear Power Plant - Verbal Authorization of Request VR-4, Revision 0 Project stage: Other ML21077A0012021-03-17017 March 2021 NRR E-mail Capture - Perry Nuclear Power Plant - Correction to Acceptance of Relief Requests Regarding VR-3 VR-4, VR-5, VR-6, VR-7, and VR-8 Valve Testing Extensions (Epids: L-2021-LLR-0007 Through L-2021-LLR-0012) Project stage: Acceptance Review ML21123A2172021-05-0505 May 2021 Issuance of Relief Requests Vr 4, Revision 0, Vr 6, Revision 0, and Vr 8, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L 2021 Llr 0010, L 2021 Llr 0011, L 2021 Llr 0012 COVID-19 Project stage: Approval 2021-02-08
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Text
From: Wall, Scott Sent: Thursday, March 4, 2021 9:37 AM To: Lashley, Phil H (EH); Morgan, Jeffrey D.
Cc: Dickson, Billy; Ospino, Ty; Ruiz, Robert
Subject:
Perry Nuclear Power Plant - Verbal Authorization of Request VR-6, Revision 0 (EPID No. L-2021-LLR-0011)
Dear Mr. Lashley:
By telephone conversation on March 3, 2021, the U.S. Nuclear Regulatory Commission (NRC) staff provided a verbal authorization to Energy Harbor Nuclear Corp (the licensee) for the alternative VR-6, Revision 0, for Perry Nuclear Power Plant (Perry) proposing one-time extensions of testing for certain Perry valves scheduled for the upcoming spring 2021 refueling outage. The NRC staffs evaluation and verbal authorization is repeated at the end of this e-mail.
The following NRC and licensee personnel participated in the conference call:
NRC Nancy Salgado - Chief, Plant Licensing Branch III Angela Buford - Chief, Mechanical Engineering and Inservice Testing Branch Bob Wolfgang - Senior Mechanical Engineer Yuken Wong - Senior Mechanical Engineer Gurjendra Bedi - Mechanical Engineer Ian Tseng - Mechanical Engineer Jason Huang - Mechanical Engineer Michael Farnan - Mechanical Engineer Nicholas Hansing - Mechanical Engineer Scott Wall - Senior Project Manager Energy Harbor Nuclear Corp Rod Penfield - Site Vice President Darin Benyak - Senior Vice President, Fleet Nuclear Support Alexandra Zelaski - Manager, Nuclear Work Control Dave Olderman - Supervisor, Nuclear Engineering Programs Justin Truxall - Nuclear Engineer Jacob Zbiegien - Nuclear Engineer Jeff Morgan - Licensing Engineer Dave McCreary - Licensing Engineer Ken McMullen - Licensing Engineer Phil Lashley - Fleet Licensing Manager Please contact me if you have any questions.
Scott P. Wall, LSS BB, BSP Senior Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301.415.2855 Scott.Wall@nrc.gov
VERBAL AUTHORIZATION BY THE NRC OFFICE OF NUCLEAR REACTOR REGULATION FOR 10 CFR 50.55a REQUEST VR-6, REVISION 0 POSITION VERIFICATION TESTING EXTENSION ENERGY HARBOR NUCLEAR CORP.
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 EPID NO. L-2021-LLR-0011 MARCH 3, 2021 Technical Evaluation read by Angela Buford, Chief, Mechanical Engineering and Inservice Testing Branch, Division of Engineering and External Hazards, NRC Office of Nuclear Reactor Regulation By letter dated February 8, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21039A409), as supplemented by , L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011)|letter dated February 22, 2021]] (ADAMS Accession No. ML21053A010), [Energy Harbor Nuclear Corp.] the licensee proposed to the [U.S. Nuclear Regulatory Commission] NRC, an alternative to specific inservice testing requirements in the [American Society of Mechanical Engineers] ASME [Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST] OM Code, 2012 Edition, for [Perry Nuclear Power Plant, Unit No. 1] Perry, 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 VR-6, Revision 0, requesting NRC authorization to extend the performance of position verification testing for 35 valves at Perry listed in the request from the upcoming refueling outage 1RF18, scheduled to begin on March 7, 2021, to the next refueling outage 1RF19, scheduled to occur in the spring of 2023. The NRC staffs evaluation described in this Verbal Authorization applies only to the 35 valves at Perry listed in the submittal dated February 8, 2021, as supplemented by , L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011)|letter dated February 22, 2021]].
In those documents, 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-3700, Position Verification Testing, and compliance with the 10 CFR 50.55a(b)(3)(xi) OM Condition: Valve Position Indication as incorporated by reference in 10 CFR 50.55a, to verify obturator position testing of 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 obturator position verification testing of valves at this time would represent a hardship during this [Coronavirus Disease 2019] COVID-19 outbreak, because the licensee intends to reduce the number of personnel on site to prevent the spread of COVID-19 at Perry.
This reduction would include qualified testing contractors who perform the obturator position verification tests.
In its February 22, [2021,] supplement, the licensee provided the results of the recent tests conducted to satisfy the obturator position verification for the 35 valves within the scope of its alternative request. The licensee clarified the test methods used to verify the obturator position and emphasized that the tests will be conducted to the requirement in ASME OM Code paragraph ISTC-3700. The NRC staff notes that the valve position verification testing is also required to be supplemented by the condition in 10 CFR 50.55a(b)(3)(xi). The licensee also
explained the basis for the classification of four specific valves within the scope of its request as passive. The NRC staff determined that the licensees classification of those four valves as passive does not impact the NRC staff review of the licensees alternative request with respect to the requirements of ASME OM Code, Subsection ISTC, paragraph ISTC-3700.
Based on the information described above for the 35 valves at Perry identified in the licensees request, the NRC staff finds that (1) previous 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) a hardship exists for the performance of obturator position verification testing of these 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, applicable to the extension of the obturator position testing interval for the 35 specified valves, submitted in accordance with 10 CFR 50.55a(z)(2), will provide reasonable assurance that these valves at Perry will be operationally ready to perform their safety functions until the next refueling outage, scheduled for the spring of 2023. 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 February 8, 2021, as supplemented by , L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011)|letter dated February 22, 2021]], remain applicable. If the licensee identifies a performance issue with any of these 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 Perry, scheduled for the spring of 2023. The licensees obturator position verification testing plans for these valves may be adjusted as appropriate by any subsequent NRC-authorized alternative requests.
Authorization read by Nancy Salgado, Chief of the Plant Licensing Branch III, Office of Nuclear Reactor Regulation As Chief of the Plant Licensing Branch III, Office of Nuclear Reactor Regulation, I agree with the conclusions of the Mechanical Engineering and Inservice Testing Branch.
The NRC staff concludes that the licensees proposed alternative, under Request Number VR-6, Rev. 0, for Perry will provide reasonable assurance of adequate safety until the next refueling outage, scheduled for the spring of 2023 when position verification testing for the 35 specific valves will be performed.
The NRC staff finds that complying with the valve position verification requirements of the ASME OM Code, Subsection ISTC, as required by 10 CFR 50.55a, for the valves within the scope of this alternative request 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 March 3, 2021, the NRC authorizes the use of Request Number VR-6, Rev.
0, until completion of the next refueling outage, scheduled for the spring of 2023. All other requirements in ASME OM Code for which relief or an alternative was not specifically requested and approved in this alternative request remain applicable.
This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding Request Number VR-6, Rev. 0, while subsequently preparing the written safety evaluation.
Hearing Identifier: NRR_DRMA Email Number: 1055 Mail Envelope Properties (SA0PR09MB6058D74FFD3DAA15E540ABA492979)
Subject:
Perry Nuclear Power Plant - Verbal Authorization of Request VR-6, Revision 0 (EPID No. L-2021-LLR-0011)
Sent Date: 3/4/2021 9:36:45 AM Received Date: 3/4/2021 9:36:47 AM From: Wall, Scott Created By: Scott.Wall@nrc.gov Recipients:
"Dickson, Billy" <Billy.Dickson@nrc.gov>
Tracking Status: None "Ospino, Ty" <Tyrone.Ospino@nrc.gov>
Tracking Status: None "Ruiz, Robert" <Robert.Ruiz@nrc.gov>
Tracking Status: None "Lashley, Phil H (EH)" <phlashley@energyharbor.com>
Tracking Status: None "Morgan, Jeffrey D." <jdmorgan@energyharbor.com>
Tracking Status: None Post Office: SA0PR09MB6058.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 8963 3/4/2021 9:36:47 AM Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: