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Category:E-Mail
MONTHYEARML24285A1682024-10-11011 October 2024 Email Response: LTR-24-0212 David Lochbaum Letter - Public Access to Advisory Committee on Reactor Safeguards Materials - Seabrook ASR ML24149A3532024-05-24024 May 2024 Change in Estimated Review Schedule for Nextera Common Emergency Plan Amendment ML24122C6922024-05-0101 May 2024 NextEra Fleet EP Amendment - Demonstration Drill ML24115A2362024-03-28028 March 2024 Acceptance Review: Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23156A3042023-05-31031 May 2023 Acceptance of Requested Licensing Action Amendment Request to Remove Period of Applicability from Pressure Temperature Limits and Low Temperature Over Pressure Protection Curves ML23109A1862023-04-19019 April 2023 and Turkey Point Acceptance of Requested Licensing Action Proposed Alternative to Asme Section XI Authorizing Implementation of Asme Code Case N-752-1 ML23066A1892023-03-0303 March 2023 OEDO-22-00419: Email Dated 3-3-2023 to Petitioner on Seabrook ASR Petition ML23066A0892023-02-24024 February 2023 OEDO-22-00419 - Email Dated 02/24/2023 to Petitioner on Seabrook Unit 1 ASR Petition ML23020A9392023-01-19019 January 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Cooling Tower Service Water Loop or Cell Requirements (EPID L-2022-LLA-0183) (Email) ML23011A3082023-01-11011 January 2023 Request for Additional Information Regarding Relief Request 4RA-22-001 (L-2022-LLR-0074) ML22341A0012022-12-0606 December 2022 Acceptance of Requested Licensing Action Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) ML22333A7452022-11-22022 November 2022 OEDO-22-00419 - Email: C-10 Response on PRB Initial Assessment - C-10 Petition on Seabrook ASR Concrete Degradation ML22287A1472022-10-13013 October 2022 2.026 Petition Screen-in Email ML22228A0552022-08-15015 August 2022 Request for Additional Information Steam Generator Tube Inspection Report Review ML22200A1082022-07-19019 July 2022 Acceptance Review for TSTF-577 Amendment ML24285A2022022-07-0202 July 2022 Email Response - LTR-24-0212 - Patricia Skibbee - President C-10 Board of Directors - David Lochbaum ML22153A4152022-05-31031 May 2022 Request for Additional Information Re 120V Inverter LAR from TS Branch - Final ML22116A2442022-04-26026 April 2022 Acceptance of Requested Licensing Action Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage ML22048B5522022-02-17017 February 2022 LTR-22-0010 Reply to Geoff Gilbert Email Concern About Seabrook Station Concrete Degradation ML22062B6642022-02-0707 February 2022 Request for Additional Information 120V Inverter LAR from the Electrical Branch ML22063A0002022-01-25025 January 2022 Requests for Additional Information from Risk Branch Regarding 120V Inverter LAR ML22020A2542022-01-20020 January 2022 LTR-22-0010 Geoff Gilbert, E-mail Concern About Seabrook Station Concrete Degradation ML21097A2512021-04-0707 April 2021 Request for Additional Information Regarding Steam Generator Tube Inspection Report Review for RFO 20 (EPID L-2020-LRO-0066) (Email) ML21054A0482021-02-23023 February 2021 Request for Additional Information Regarding Heat Flux Hot Channel Requirement Amendment Request ML20343A0942020-12-0303 December 2020 Request for Additional Information Regarding Seabrook (COVID-19) Part 73 Force-on-Force Exemption Request (L-2020-LLE-0219) ML20273A2812020-09-22022 September 2020 Acceptance of Requested Licensing Action License Amendment Request to Resolve Non-Conservative Heat Flux Hot Channel Factor Requiments ML20258A1502020-09-14014 September 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding One-Time Change to the AC Sources Operating TS ML20260H4932020-09-11011 September 2020 NRR E-mail Capture - Comanche Peak - Acceptance of Requested Licensing Action - Request to Use Later Code Edition of ASME OM Code ML20230A2962020-08-14014 August 2020 Acceptance of Requested Licensing Action License Amendment Request to Allow a One-Time Change to the AC Sources Operating TS ML20167A1842020-06-11011 June 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding TSTF-411 and TSTF-418 (L-2019-LLA-0237) ML20124A0012020-05-0101 May 2020 Cancellation of Call with Seabrook on Steam Generator Tube Inspections ML20114E1592020-04-23023 April 2020 Email and Request for Additional Information Related to Seabrook License Amendment Request to Degraded Voltage Time Delay Setpoint (L-2020-LLA-0012) ML20101L0402020-04-10010 April 2020 Acceptance of Requested Licensing Action Relief Request to Use Code Case OMN-13 with 2012 Edition of the OM Code ML20101N0932020-04-10010 April 2020 Acceptance of Requested Licensing Action Re Relief Request to Defer ASME Inspections Due COVID-19 (EPIDs L-2020-LLR-0055, -56, and -57) ML20101H3912020-04-0808 April 2020 Verbal Authorization for Seabrook Relief Request 3IIR-7 ML20087K8262020-03-27027 March 2020 Upcoming Steam Generator Tube Inservice Inspection ML20063J9792020-02-28028 February 2020 Acceptance of Requested Licensing Action Amendment Request to Revise Degraded Voltage Time Delay Setpoint ML19347C6732019-12-13013 December 2019 Acceptance of Requested Licensing Action Amendment Request to Adopt TSTF-418 ML19296D9122019-10-23023 October 2019 NRR E-mail Capture - Request for Additional Information Related to Seabrook Inverter Amendment (L-2019-LLA-0216) ML19295F5422019-10-15015 October 2019 NRR E-mail Capture - Seabrook Station, Unit No. 1 - Acceptance of Requested Licensing Action Amendment Request to Revise Onsite Power Distribution Requirements ML19275G7832019-10-0101 October 2019 Limited Appearance Statement from New Hampshire State Representative, Robert Harb Regarding the Seabrook Station Unit 1 License Amendment Application ML19270E6512019-09-27027 September 2019 Limited Appearance Statement from Joanna Hammond Regarding the Seabrook Station Unit 1 License Amendment Application ML19270E6542019-09-26026 September 2019 Limited Appearance Statement from Brian Campbell Regarding the Seabrook Station Unit 1 License Amendment Application ML19196A3592019-07-15015 July 2019 NRR E-mail Capture - Seabrook Station, Unit No. 1 - Acceptance of Requested Licensing Action Amendment Request to Revise the Emergency Core Cooling System Accumulator Technical Specifications ML19169A2412019-06-13013 June 2019 NRR E-mail Capture - Seabrook Station, Unit No. 1 - Acceptance of Requested Licensing Action Relief Requests for the Containment Building Spray Pump Flow and Vibration Testing (Epids L-2019-LLR-00 and L-2019-LLR-00) ML19162A0662019-06-0404 June 2019 Reply to Mr. Rick Jakious'S E-mail of 5-29-2019 to Stephen B. Comley Sr., We the People with Attachments ML19112A1782019-04-22022 April 2019 NRR E-mail Capture - Point Beach; Seabrook; Turkey Point - Acceptance of Requested Licensing Action Amendment Request to Revise Technical Specifications to Adopt TSTF-563 ML19101A4042019-04-11011 April 2019 NRR E-mail Capture - Point Beach; Seabrook; St. Lucie; Turkey Point - Acceptance of Licensing Action Relief Request to Use Encoded Phased Array Ultrasonic Examination Techniques for Ferritic and Austenitic Welds ML19070A2382019-03-10010 March 2019 LTR-19-0088 Maura Healey, Attorney General, the Commonwealth of Massachusetts, Ltr NextEras Requests for a License Amendment and Twenty-year Extension Prior to Issuance of a Final Decision in Adjudicatory Hearing on Concrete Degradation at 2024-05-24
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NRR-PMDAPEm Resource From: Poole, Justin Sent: Monday, January 30, 2017 4:25 PM To: Browne, Kenneth
Subject:
Verbal Authorization for Seabrook Relief Request RA-17-001 Attachments: Seabrook verbal authorization 1-30-2017.docx Mr. Browne, In accordance with NRR Office Instruction LIC-102, Relief Request Reviews, the NRR staff has provided verbal authorization for Seabrook Station, Unit 1 relief request RA-17-001 as described in your letter to the NRC dated January 27, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17028A010).
The script read this afternoon that provides verbal authorization is attached. The NRC staff intends to follow-up this verbal authorization with a written safety evaluation within approximately 150 days.
Please let me know if you have any questions. A copy of this email and attached verbal authorization will become publicly available in ADAMS.
Justin C. Poole Project Manager NRR/DORL/LPL I U.S. Nuclear Regulatory Commission (301)415-2048 1
Hearing Identifier: NRR_PMDA Email Number: 3301 Mail Envelope Properties (Justin.Poole@nrc.gov20170130162400)
Subject:
Verbal Authorization for Seabrook Relief Request RA-17-001 Sent Date: 1/30/2017 4:24:44 PM Received Date: 1/30/2017 4:24:00 PM From: Poole, Justin Created By: Justin.Poole@nrc.gov Recipients:
"Browne, Kenneth" <Kenneth.J.Browne@nexteraenergy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 808 1/30/2017 4:24:00 PM Seabrook verbal authorization 1-30-2017.docx 22150 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
1 VERBAL AUTHORIZATION BY THE OFFICE NUCLEAR REGULATION FOR RELIEF REQUEST RA-17-001 TEMPORARY REPAIR OF SERVICE WATER PIPING SEABROOK STATION UNIT 1 NEXTERA ENERGY SEABROOK LLC DOCKET NO. 50-443 JANUARY 30, 2017 Technical Evaluation read by David Alley, Chief of the Component Performance, Non-Destructive Examination, and Testing Branch, NRR By letter dated January 27, 2017, NextEra Energy Seabrook LLC (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWA-4412, at Seabrook Station Unit 1.
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee submitted Relief Request RA-17-001 for a temporary repair of leaking service water piping on the basis that complying with the specified ASME Code requirement to repair the degraded piping would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The affected piping is on the discharge side of the A train service water system piping. The through wall flaw is located at weld FW1818-F0602, which connects a 24-inch elbow to straight pipe downstream of check valve 1-SW-V-53. The licensee proposed to install a 6-inch encapsulation which consists of a weldolet, weld neck flange and blind flange, on the leaking flaw which was caused by seawater corrosion. The licensee demonstrated the structural integrity of the subject pipe in accordance with ASME Code Case N-513-3 Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping,Section XI, Division 1. The licensee also demonstrated that considering the flaw growth rate, the 6-inch encapsulation will maintain the structural integrity of the pipe up to the end of the next refueling outage (OR18) in Spring 2017. In addition, the licensee will perform daily walkdowns and ultrasonic inspections of the affected area at a frequency of no more than 30 days. As a defense-in-depth measure, the licensee stated that the relief request would expire if the ongoing ultrasonic testing identify that the flaw progresses outside the encapsulated area to the point that the ASME Code minimum thickness of 0.105 inch is challenged. The NRC staff finds that the licensee has provided adequate hardship justification.
The NRC staff finds that the proposed encapsulation has sufficient margin with respect to the predicted growth of the flaw at the end of next refueling outage in Spring 2017 and is designed to support all the loadings of the pipe. Therefore, the NRC finds that Relief Request RA-17-001 will provide reasonable assurance that the structural integrity of the subject service water piping and its intended safety function will be maintained up to the end of the next refueling outage (OR18) in Spring 2017.
Authorization read by Rick Ennis, Acting Chief of the Plant Licensing Branch I, NRR As Acting Chief of the Plant Licensing Branch I, Office of Nuclear Reactor Regulation, I agree with the conclusions of the Component Performance, Non-Destructive Examination, and Testing Branch.
2 The NRC staff concludes that the proposed alternative provides reasonable assurance of structural integrity of the subject service water piping. The NRC staff finds that complying with IWA-4412 of the ASME Code,Section XI, 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, as of January 30, 2017, the NRC authorizes the use of Relief Request RA-17-001 at Seabrook Station Unit 1 until the end of the next refueling outage (OR18) in Spring 2017, or until the flaw progresses outside the encapsulated area such that the pipe wall thickness is below 0.105 inch, whichever occurs first.
All other requirements in ASME Code,Section XI, for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding the Relief Request while preparing subsequent written safety evaluation.