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Category:E-Mail
MONTHYEARML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24179A1292024-06-24024 June 2024 Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1 ML24066A0132024-03-0505 March 2024 Bru 2024-002 Radiation Safety Baseline Inspection Information Request ML23248A2612023-09-0505 September 2023 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of License Amendment Request to Revise the 10 CFR 50.69 Categorization Process ML23202A0652023-07-19019 July 2023 NRR E-mail Capture - Request for Additional Information - Brunswick Steam Electric Plant, Units 1 and 2, Torus Liner Inspection Alternative Request (L-2022-LLR-0089) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23032A2472023-01-26026 January 2023 Document Request Letter for Brunswick Upcoming RP Inspection 2023002 ML23018A1892023-01-17017 January 2023 Document Request for RP Inspection at Brunswick Inspection Report 2023-01 ML23006A0642023-01-0606 January 2023 NRR E-mail Capture - Acceptance Review Results for Brunswick, Unit Nos. 1 and 2 - Proposed Alternative Request RA-22-0308 ML23006A1892023-01-0606 January 2023 NRR E-mail Capture - Corrected - Acceptance Review Results for Brunswick, Unit Nos. 1 and 2 - Proposed Alternative Request RA-22-0308 NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML21357A0472021-12-23023 December 2021 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of License Amendment Request Regarding Adoption of TSTF-580 ML21361A0122021-12-23023 December 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21277A0952021-10-0101 October 2021 NRR E-mail Capture - Request for Additional Information - Brunswick Exemption Request from 10CFR 55.47 License Operator Exam Two-year Waiver Limit ML21200A1582021-07-16016 July 2021 NRR E-mail Capture - Accepted for Review - Brunswick License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery ML21168A0042021-06-17017 June 2021 Notification of Inspection and Request for Information ML21137A1622021-04-26026 April 2021 NRR E-mail Capture - Accepted for Review - Brunswick License Amendment Request to Adopt TSTF-505 Risk-Informed Completion Time (L-2021-LLA-0060) ML21082A0162021-03-22022 March 2021 Accepted for Review - Brunswick License Amendment Request to Change Tech Spec Limit for Standby Liquid Control System Boron Solution Storage Tank Volume L-2021-LLA-0022 ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21019A3772021-01-13013 January 2021 002 Radiation Safety Baseline Inspection Information Request ML21007A3722021-01-0707 January 2021 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-19-0352 - Proposed Alternative for Reactor Vessel Close Stud Examinations (L-2020-LLR-0156) ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20309A5212020-10-29029 October 2020 Request for Additional Information - Brunswick License Amendment Request to Modify Its Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of SSC Categorization Process ML20294A0642020-10-20020 October 2020 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Adopt TSTF-582 RPV Water Inventory Control Enhancements(L-2020-LLA-0218) ML20297A3102020-10-13013 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0191 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 (L-2020-LLR-0126) ML20297A3082020-10-0707 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0263 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI for Repair/Replacement (L-2020-LLR-0124) ML20297A3092020-10-0606 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0262 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-4540(b) (L-2020-LLR-0125) ML20275A2972020-10-0101 October 2020 NRR E-mail Capture - Request for Additional Information - Brunswick Request for Alternate Examination of Reactor Vessel Nozzles ML21033A8562020-08-0505 August 2020 NRR E-mail Capture - Accepted for Review - Brunswick Relief Request for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements EPID-L-2020-LLR-0091 ML20121A1262020-04-29029 April 2020 Radiation Safety Baseline Inspection Information Request ML20111A1212020-04-20020 April 2020 NRR E-mail Capture - Accepted for Review - Brunswick Request for Alternative to Examination Category B-N-1 (VT-3) Visual Examination of Accessible Areas of the Reactor Vessel Interior - EPID: L-2020-LLR-0048 ML20017A1602020-01-17017 January 2020 E-mail Notification of Inspection and Request for Additional Information ML19283D0852019-10-0909 October 2019 Request for Additional Information - Brunswick Atrium 11 LAR ML19252A4572019-09-0808 September 2019 (FEMA Email 09-08-19) Tentative Notification of Brunswick Preliminary Capability Assessment Results ML19252A4092019-09-0606 September 2019 (E-mail to FEMA 09-06-19) FEMA Notification for Planned Restart of Brunswick Units 1 and 2 ML19219A2132019-08-0707 August 2019 NRR E-mail Capture - Duke Energy Fleet - Acceptance of Requested Licensing Action Amendment Requests to Relocate the TSs Staff Qualification Requirements to the Duke Energy Corporation QAPD ML19179A1312019-06-27027 June 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19177A0122019-06-25025 June 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19162A3912019-06-11011 June 2019 NRR E-mail Capture - Duke Energy Fleet - Acceptance of Requested Licensing Action Relief Request (19-GO-001) Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19162A3902019-06-11011 June 2019 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Fourth 10-Year Inservice Inspection Interval ISI-12 ML19092A1152019-04-0101 April 2019 NRR E-mail Capture - Brunswick Steam Electric Plant, Unit Nos. 1 and 2 - Acceptance of Requested Licensing Action Amendment Request to Modify Surveillance Requirements for Safety Relief Valves (L-2019-LLA-0043) ML19092A1142019-04-0101 April 2019 NRR E-mail Capture - Brunswick Plant, Unit 1 and 2 - Acceptance of Requested Licensing Action Amendment Request to Modify TS 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (L-2019-LLA-0031) ML19067A2712019-03-0707 March 2019 NRR E-mail Capture - Brunswick 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 2024-09-04
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NRR-PMDAPEm Resource From: Wyman, Stephen Sent: Tuesday, June 23, 2015 6:55 PM To: Philip.Ballard@duke-energy.com; Bill.Murray@duke-energy.com; Lee.Grzeck@duke-energy.com Cc: Paul.Guill@duke-energy.com; Devlin-Gill, Stephanie; DiFrancesco, Nicholas
Subject:
Brunswick ESEP Clarification Question Mr. Grzeck, In follow-up to my phone conversation with Paul Guill today, as part of the NRC review of the Brunswick ESEP report, the staff would appreciate clarification on the following technical item:
The following clarification questions are raised in the context of the NRC evaluation of the ESEP submittals only and licensees responses will be reviewed by NRC staff only to the extent the use of this information affects the elements and outcomes of the ESEP evaluation. As many licensees have used information from their ongoing SPRA analyses, the current review will not evaluate methods or results as they pertain to the SPRA. They will be reviewed later at the time of SPRA review.
- 1. Section 5.2 of the ESEP report states: The ISRS for the ESEP were developed by linearly scaling the existing BSEP ISRS by the ESEP specified maximum ratio of two times the SSE. For the Containment, the A-46 response spectra were used in place of the design basis SSE spectra. For Control Building and Diesel Generator Buildings, the original design basis SSE spectra are used.
Since the licensee defined the ESEP RLGM as two times the SSE in Section 5.1 of the ESEP report, the ESEP ISRS should be established as two times the SSE-based ISRS. The licensee should explain why the A-46 spectra, instead of the SSE, are used in developing the ESEP ISRS for the Containment. Also, since the A-46 spectrum comparison to the RLGM at the same control point location was not presented, please provide this information.
- 2. The results of the screened-out ESEL items for Units 1 and 2 are presented in Attachment B of the ESEP report. However, for two of the items that were screened out (ESEL items 130 and 133 corresponding to DC power supply for EGM control for Units 1 and 2, respectively) no entry was identified in the HCLPF Capacity column of the table. Therefore, please provide the HCLPF capacity for these components.
- 3. Section 7 of the ESEP report identifies ESEL items inaccessible for walkdowns. The licensee provided various ways of dispositioning these items and referred to maintenance and testing schedules, installation drawings, photographic evidence and other ways to account for these items.
In order for the staff to assess the current condition or state of the inaccessible items, please address the following:
- a. If photographic evidence was used as part of the SRT review to safely disposition the inaccessible items, as stated in various instances in Section 7 (i.e. MCC, distribution panels, torus temperature elements, switchgear transformers, etc) please provide dates or range of dates said pictures were taken.
- b. Motor Control Centers and Distribution Panels, :
- i. Provide date or range of dates the items were externally inspected ii. Identify other documentation and calculations, as stated in subsection 7.1.2, used in the SRT review
- c. Switchgear Transformers:
- i. Identify and provide dates of previous walkdowns, inspections and engineering packages, stated in subsection 7.1.4, used in the SRT review.
1
An email response will likely be sufficient to support the ESEP report review, however, please be aware that your email response will be made publicly available in ADAMS. A response around July 14, if practicable, would be greatly appreciated to support the planned review schedule.
Please let me or Nick DiFrancesco (at 301-415-1115) know if you would like to schedule a clarification call or have any questions and concerns.
- Thanks, Steve Stephen M. Wyman USNRC/NRR/JLD/HMB Office: O-13G9 MS: O-13C5 301-415-3041 (Voice) 301-415-8333 (Fax)
Stephen.Wyman@nrc.gov 2
Hearing Identifier: NRR_PMDA Email Number: 2289 Mail Envelope Properties (6389e94bf84c41a39160dd632e2b3754)
Subject:
Brunswick ESEP Clarification Question Sent Date: 6/23/2015 6:54:48 PM Received Date: 6/23/2015 6:54:49 PM From: Wyman, Stephen Created By: Stephen.Wyman@nrc.gov Recipients:
"Paul.Guill@duke-energy.com" <Paul.Guill@duke-energy.com>
Tracking Status: None "Devlin-Gill, Stephanie" <Stephanie.Devlin-Gill@nrc.gov>
Tracking Status: None "DiFrancesco, Nicholas" <Nicholas.DiFrancesco@nrc.gov>
Tracking Status: None "Philip.Ballard@duke-energy.com" <Philip.Ballard@duke-energy.com>
Tracking Status: None "Bill.Murray@duke-energy.com" <Bill.Murray@duke-energy.com>
Tracking Status: None "Lee.Grzeck@duke-energy.com" <Lee.Grzeck@duke-energy.com>
Tracking Status: None Post Office: HQPWMSMRS02.nrc.gov Files Size Date & Time MESSAGE 3937 6/23/2015 6:54:49 PM Options Priority: Standard Return Notification: Yes Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: