|
---|
Category:E-Mail
MONTHYEARML23248A2612023-09-0505 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) 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 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 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 ML19065A0962019-03-0606 March 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19058A0742019-02-26026 February 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19056A2212019-02-25025 February 2019 NRR E-mail Capture - Brunswick Draft 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 2023-09-05
[Table view] |
Text
NRR-PMDAPEm Resource From: Saba, Farideh Sent: Thursday, July 19, 2012 12:33 PM To: Thorpe, April
Subject:
FW: Brunswick spent fuel pool petition Hi April, Have I asked before to add the following email to ADAMS. I think I did, but let me know. If not, I will send you another email with the following email attached.
- Thanks, Farideh Farideh E. Saba, P.E.
Senior Project Manager NRC/ADRO/NRR/DORL 301-415-1447 Mail Stop O-8G9A Farideh.Saba@NRC.GOV From: Dave Lochbaum [1]
Sent: Monday, July 16, 2012 12:54 PM To: Saba, Farideh Cc: Mensah, Tanya; Brown, Eva; Billoch, Araceli; Banic, Merrilee
Subject:
RE: Brunswick spent fuel pool petition
Dear Mr. Saba:
Thank you for your response and its background on the 2.206 vs. allegations processes.
Yes, I concur with the NRC's proposal to treat our petition under its 2.206 process.
Yes, I would like to address the PRB, both to answer any clarifying questions from the NRC staff regarding the petition and also to emphasize our concern about the status quo at Brunswick - in other words, the reasons we believe the actions sought in the petition are needed to ensure adequate protection.
Because I work in Chattanooga, TN, it is most likely that my interaction with the PRB would be via telephone.
However, I am currently scheduled to be in Washington DC on August 7th for a presentation to the NRC Commissioners. If the PRB meeting could be arranged on the afternoon of August 7th or early morning of August 8th, I could participate in person. I'm equally comfortable with either arrangement - phone or in-person.
- Thanks, David Lochbaum Director, Nuclear Safety Project Union of Concerned Scientists PO Box 15316 Chattanooga, TN 37415 (423) 468-9272 office 1
(423) 488-8318 cell dlochbaum@ucsusa.org From: Saba, Farideh [Farideh.Saba@nrc.gov]
Sent: Thursday, July 12, 2012 4:34 PM To: Dave Lochbaum Cc: Mensah, Tanya; Brown, Eva; Billoch, Araceli; Banic, Merrilee
Subject:
RE: Brunswick spent fuel pool petition
Dear Mr. Lochbaum,
I have been assigned as the Petition Manager for the 10 CFR 2.206 petition you submitted to the Nuclear Regulatory Commission (NRC) on July 10, 2012, regarding your concerns on safety of the irradiated spent fuel assemblies stored in the Brunswick Steam Electric Power Units 1 and 2 (Brunswick) spent fuel pools.
Section 2.206 of Title 10 of the Code of Federal Regulations describes the petition process - the primary mechanism for the public to request enforcement action by the NRC in a public process. This process permits anyone to petition NRC to take enforcement-type action related to NRC licensees or licensed activities. Depending on the results of its evaluation, NRC could modify, suspend or revoke an NRC-issued license or take any other appropriate enforcement action to resolve a problem. The NRC staffs guidance for the disposition of 2.206 petition requests is in Management Directive 8.11, which is publicly available.
The 2.206 process provides a mechanism for any member of the public to request enforcement action against NRC licensees. Therefore, because you specifically requested in your letter that the NRC takes enforcement action in the form of an order either modifying the Brunswick operating licenses or requiring the licensee to submit amendment requests for these licenses to address the technical specifications changes detailed in the Specific Actions Requested section of your petition, it was referred to the 2.206 process. The 2.206 process is separate from the allegations process which affords individuals who raise safety concerns a degree of protection of their identity. In the 2.206 process, all of the information in your letter will be made public, including your identity.
In addition, in accordance with NRC Management Directive 8.11 (which I have attached for your reference), you have the opportunity to address the NRC Petition Review Board (PRB) to further discuss your petition, either in person at the NRC Headquarters in Rockville, MD, or by telephone conference.
I would appreciate if you could advise me by July 16, 2012, if you agree to the NRCs processing your request under the 2.206 process. In addition, please advise me if you would like to address the PRB. If you would like to meet in person, I will need to schedule a formal public meeting at the NRC Headquarters. If you would prefer to address the PRB via phone, I will also work with you to coordinate a date/time during the upcoming weeks.
Thank you, Farideh E. Saba, P.E.
Senior Project Manager NRC/ADRO/NRR/DORL 301-415-1447 Mail Stop O-8G9A Farideh.Saba@NRC.GOV From: Dave Lochbaum [2]
Sent: Tuesday, July 10, 2012 12:11 PM To: Borchardt, Bill Cc: Jim Warren; maryo@nirs.org; McCree, Victor; Ledford, Joey; Hannah, Roger; Leeds, Eric; Saba, Farideh; Musser, 2
Randy; Phil.OBryan@nrc.gobv; Alexander, Donna
Subject:
Brunswick spent fuel pool petition
Dear Mr. Borchardt:
Attached is an electronic copy of a petition per 10 CFR 2.206 seeking revisions to the technical specifications for Brunswick Units 1 and 2 to better manage the risk of irradiated fuel stored in the spent fuel pools. I do not intend to also mail in a hard copy, but would be glad to do so upon request.
The existing technical specifications essentially only require preventative or mitigative measures when recently discharged irradiated fuel is being moved in a spent fuel pool. Otherwise, virtually all these measures are not required, even as basic as requiring the spent fuel pool to contain water.
The root cause of this situation likely dates back to the fuel handling accident being the only scenario within the design and licensing bases leading to fuel damage outside primary containment. As the orders issued by the NRC earlier this year to all licensees, including Brunswick's, other credible scenarios affecting the safety of irradiated fuel in spent fuel pools include loss of water inventory from the pools or loss of cooling of that water.
Yet the technical specifications fail to recognize these other scenarios.
Our petition seeks to remedy those shortcomings.
The actions requested in the petition are neither onerous nor far-fetched. For example, the technical specifications for the Pilgrm nuclear plant - a BWR/4 with a Mark I containment like Brunsick - require water level to be maintained in the spent fuel pool whenever it contains irradiated fuel, not just when irradiated fuel is being moved. Pilgrim has technical specification requirements like those we seek in this petition and yet is able to conduct operations seemingly unfettered from undue burden.
Sincerely, David Lochbaum Director, Nuclear Safety Project Union of Concerned Scientists PO Box 15316 Chattanooga, TN 37415 (423) 468-9272 office (423) 488-8318 cell dlochbaum@ucsusa.org 3
Hearing Identifier: NRR_PMDA Email Number: 416 Mail Envelope Properties (36CF286628C20846A68047F2463233098597A02809)
Subject:
FW: Brunswick spent fuel pool petition Sent Date: 7/19/2012 12:33:15 PM Received Date: 7/19/2012 12:33:16 PM From: Saba, Farideh Created By: Farideh.Saba@nrc.gov Recipients:
"Thorpe, April" <April.Thorpe@nrc.gov>
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 7040 7/19/2012 12:33:16 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: