ML21054A182
| ML21054A182 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/23/2021 |
| From: | Scott Wall NRC/NRR/DORL/LPL3 |
| To: | Schultz K Michigan Safe Energy Future |
| Wall S | |
| References | |
| Download: ML21054A182 (3) | |
Text
From:
Wall, Scott Sent:
Tuesday, February 23, 2021 10:26 AM To:
Kraig D Schultz Cc:
Kraig Schultz; Bette Pierman; Bette P; B. Iris Potter; bruce5050@comcast.net; Maynard Kaufman
Subject:
Regarding Public Comment on Palisades request for relief RR 5-8 Attachments:
[External_Sender] Re: Palisades Request for Relief RR 5-8 Dear Mr. Schultz By emails dated September 28, 2020, and January 6, 2021, Michigan Safe Energy Future expressed concern regarding granting relief associated with the reactor vessel closure head at Palisades Nuclear Plant (Palisades). On October 1, 2020 (ADAMS Accession No. ML20275A343), the U.S. Nuclear Regulatory Commission (NRC) staff verbally authorized the use of relief request RR 5-8 at Palisades for one cycle of operation, not to exceed 20 months of operation or May 31, 2022, when Palisades will permanently cease power operations (See letters from Entergy Nuclear Operations, Inc. (Entergy, or the licensee) dated September 28, 2017 and October 19, 2017 (ADAMS Accession Nos. ML17271A233 and ML17292A032)). On January 19, 2021, the NRC staff issued a written safety evaluation supporting the verbal authorization (ADAMS Accession No. ML20365A001). To operate Palisades with the repairs outlined in RR 5-8 beyond the approved period, the licensee must submit, and the NRC must approve, an additional relief request under Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.55a.
As discussed in the NRC staffs January 19, 2021 safety evaluation, the licensee is required to meet certain requirements in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) related to the repair of degraded reactor vessel closure head. Regarding the surface stress relief process, based upon the information provided to the staff in the relief request, the licensee did not perform or take credit for peening, a process by which a metals surface is conditioned to create compressive surface stresses, of the repairs as part of obtaining the staffs approval of the proposed alternative for one cycle of operation.
Therefore, the NRC staff reviewed the adequacy of the repair in the relief request without the licensee performing the peening activity and found the repair method to be acceptable for one cycle of operation.
The NRC requires licensees to provide reasonable assurance of adequate protection in the operation of their facilities and comply with the conditions in its license and all applicable NRC regulations. The licensees and the nuclear industry may voluntarily seek additional information from each other pertaining to the subject weld repairs, as they deem appropriate.
Regarding the status of the capsules in the Palisades Reactor Pressure vessel, by letter dated December 2, 2019 (ADAMS Accession No. ML19318E394), the NRC staff authorized revisions to the reactor vessel material surveillance capsule withdrawal schedules for Palisades.
Specifically, the NRC approved the licensees proposal to withdraw Capsule W-80 (the fifth capsule) from Palisades in accordance with American Society for Testing and Materials Standard Practice (ASTM) E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels" (ASTM E 185-82 or Standard Practice).
This altered the withdrawal schedule for Capsule W-80 from 31.96 to 35.2 effective full power years of operation from plant startup. 10 CFR 50.60, Acceptance Criteria For Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation, states, in
part, that all light-water nuclear power reactors, other than reactor facilities for which the certifications required under § 50.82(a)(1) have been submitted, must meet the fracture toughness and material surveillance program requirements for the reactor coolant pressure boundary set forth in appendices G and H to this part. Once Palisades submits the certifications required under 10 CFR 50.82(a)(1) and ceases power operations, the licensee is no longer subject to the requirements of Appendices G and H to 10 CFR Part 50 for removal and testing of the surveillance capsule per 10 CFR 50.60.
Sincerely, 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
Hearing Identifier:
NRR_DRMA Email Number:
1040 Mail Envelope Properties (MN2PR09MB5019B4BF8F88CBBCDF679E7492809)
Subject:
Regarding Public Comment on Palisades request for relief RR 5-8 Sent Date:
2/23/2021 10:26:00 AM Received Date:
2/23/2021 10:26:03 AM From:
Wall, Scott Created By:
Scott.Wall@nrc.gov Recipients:
"Kraig Schultz" <kraigschultz@gmail.com>
Tracking Status: None "Bette Pierman" <bettebgv@yahoo.com>
Tracking Status: None "Bette P" <bette49022@yahoo.com>
Tracking Status: None "B. Iris Potter" <b.irispotter@gmail.com>
Tracking Status: None "bruce5050@comcast.net" <bruce5050@comcast.net>
Tracking Status: None "Maynard Kaufman" <maynard.kaufman@wmich.edu>
Tracking Status: None "Kraig D Schultz" <kraig@schultzengineering.us>
Tracking Status: None Post Office:
MN2PR09MB5019.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 4114 2/23/2021 10:26:03 AM
[External_Sender] Re: Palisades Request for Relief RR 5-8 61649 Options Priority:
Normal Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date: