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Category:E-Mail
MONTHYEARML24149A3532024-05-24024 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 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) 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) 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 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 ML19056A4602019-02-25025 February 2019 Comment from Lisa Conti Regarding the Emergency Petition Filed by C-10 on February 13, 2019 ML19056A4582019-02-25025 February 2019 Comment from Deborah A. Jones Regarding the Emergency Petition Filed by C-10 on February 13, 2019 2024-05-24
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NRR-PMDAPEm Resource From: Poole, Justin Sent: Tuesday, August 30, 2016 4:07 PM To: Browne, Kenneth
Subject:
DRAFT RAIs on SG Inspection Report for RFO 17 Attachments: MF7686 DRAFT RAIs.docx
- Ken, By letter dated April 22, 2016, (ADAMS Accession Numbers ML16120A203), NextEra Energy Seabrook, LLC (NextEra), submitted its Steam Generator Tube Inspection Report for refueling outage 17. In reviewing NextEras report, the NRC staff has developed the attached DRAFT request for additional information (RAI).
Please review to ensure that the RAI questions are understandable, the regulatory basis is clear, there is no proprietary information contained in the RAI, and to determine if the information was previously docketed. If further clarification is needed, and you would like to discuss the questions in a conference call, let us know.
This email does not convey a formal NRC staff position, and it does not formally request for additional information.
Justin C. Poole Project Manager NRR/DORL/LPLI-2 U.S. Nuclear Regulatory Commission (301)415-2048 1
Hearing Identifier: NRR_PMDA Email Number: 3023 Mail Envelope Properties (Justin.Poole@nrc.gov20160830160600)
Subject:
DRAFT RAIs on SG Inspection Report for RFO 17 Sent Date: 8/30/2016 4:06:57 PM Received Date: 8/30/2016 4:06:00 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 880 8/30/2016 4:06:00 PM MF7686 DRAFT RAIs.docx 27479 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION 2015 STEAM GENERATOR TUBE INSPECTIONS SEABROOK STATION DOCKET NUMBER 50-443 By letter dated April 22, 2016, (Agencywide Documents Access and Management System (ADAMS) Accession Number ML16120A203), NextEra Energy Seabrook, LLC (the licensee) submitted information summarizing the results of the 2015 steam generator tube inspections at Seabrook Station. These inspections were performed during refueling outage 17. In order to complete its review of the document listed above, the staff requests the following additional information:
- 1. Section A: The last sub-bullet on page 1 contains a statement regarding the augmented inspections performed after the bobbin coil inspections, to improve the probability of detection (POD) of axial outside diameter stress corrosion cracking (ODSCC) flaws at tube support plates. The sub-bullet appears to indicate that approximately 68 percent of hot-leg tubes were inspected (from three inches above the top-of-the-tubesheet to the H*
depth) in targeted zones that are prone to sludge deposition, using the +Point' probe.
A bullet on page 2 indicates that for the ODSCC indication, the inspection scope was increased from 68 percent to 100 percent of the hot-leg tubes (from three inches above to three inches below the top-of-the-tubesheet) in the affected SG (SG-C). Please clarify the scope of the examinations in the tubesheet and at the top of the tubesheet. Were 68 percent of all tubes (not just tubes in the targeted zones) inspected from +3 inches to the H* depth in all four SGs? Were 100 percent of all tubes in SGs A and C inspected from
+3 to -3 inches on the hot-leg?
- 2. In reviewing the reported volumetric indications in Table 4, it appears that the indication in the tube in row 22 column 97 in SG B was present in 2009 with a 32 percent through-wall depth, but was not reported (since Table 4 also states that the indication is a newly reported TSP indication). Please confirm and discuss why the indication was not reported previously, or clarify the information in the table (since normally a 32 percent through-wall wear flaw would be readily detectible with a high probability of detection).
- 3. The report states on page 9 that all tube plugs were inspected and classified as Category 1, Westinghouse procedure MRS 2.4.2 Gen-44, Revision 1; Visual Inspection of Plugs. The U.S. Nuclear Regulatory Commission staff is not familiar with the characteristics of a Category 1 plug. Please clarify whether any degradation was noted on the plugs during the visual inspection.
- 4.Section I on page 11 states, Since there is no observed operating leakage from the remaining SGs (SG-A, SG-C and SG-D), the predicted accident induced leakage for each of these is zero. Please clarify this statement. Please confirm that since there was no observed operational leakage from SGs A, C, and D, the predicted accident-induced leakage from the tubesheet expansion region is zero, from these three SGs. Also, please confirm that there were no other sources of accident-induced leakage (other than the expansion region in SG B) in all four SGs.
ENCLOSURE