Letter Sequence Approval |
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TAC:ME9733, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B (Approved, Closed) |
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MONTHYEARML12284A2132012-10-0404 October 2012 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 Project stage: Request ML12307A3032012-11-0202 November 2012 Acceptance Review for TS Amendment to Adopt TSTF-425 Project stage: Acceptance Review ML13008A3282013-01-0404 January 2013 Response to Request for Additional Information Regarding Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Project stage: Response to RAI ML13059A3292013-03-0808 March 2013 Second Request for Additional Information to Support Review of Millstone Power Station Unit 3 Amendment Application Regarding Risk Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Control Project stage: RAI ML13113A3442013-04-17017 April 2013 Response to Request for Additional Information Regarding Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Project stage: Response to RAI ML13122A1602013-04-29029 April 2013 Response to Request for Additional Information Regarding Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Project stage: Response to RAI ML13115A0182013-04-30030 April 2013 Summary of the Audit to Support the Review of the Technical Specification Task Force-425 License Amendment Request Project stage: Approval ML13281A8332013-10-0909 October 2013 Request for Additional Information to Support Review of Millstone Power Station Unit 3 Application for Technical Specification Change Regarding Risk Informed Justification for the Relocation of Specific Surveillance Frequency Requirements t Project stage: RAI ML13309A7522013-10-30030 October 2013 Response to Request for Additional Information Regarding Relocation of Specific Surveillance Frequency Requirements to a License Controlled Program Project stage: Response to RAI ML14023A7482014-02-25025 February 2014 Issuance of Amendment Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) Project stage: Approval 2013-10-09
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Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 30, 2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT 3 -
SUMMARY
OF THE AUDIT TO SUPPORT THE REVIEW OF THE TECHNICAL SPECIFICATION TASK FORCE-425 LICENSE AMENDMENT REQUEST (TAC NO. ME9733)
Dear Mr. Heacock:
The Millstone Power Station Unit 3 (MPS3) submitted a license amendment request (LAR),
dated October 4, 2012 (Agencywide Documents Access and Management Systems Accession Number ML12284A213), to relocate technical specification surveillance frequencies to a licensee controlled program with the adoption of Technical Specification Task Force (TSTF) 425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - Risk-Informed Technical Specification Task Force (RITSTF) Initiative 5b." The Office of Nuclear Reactor Regulation, Division of Risk Analysis, Probabilistic Risk Assessment Licensing Branch (APLA) performed a regulatory audit for its review of the LAR.
The audit was performed at the request of the licensee, and was conducted at the Dominion Federal Affairs office in Washington, D.C. on January 29 and 30, 2013. Specifically, the scope of the audit was to review closed findings and observations (F&Os) for the internal events probabilistic risk assessment model used in support of the application. The list of participants is provided in Enclosure 1.
The audit was conducted by APLA staff. An entrance meeting was held on January 29,2013, and during the audit period, documents were reviewed. The list of documents reviewed is provided in Enclosure 2. The audit reviewed the closed F&Os, and concluded that there was no need for any follow-on request for additional information on them since they had been appropriately addressed. However, some potential follow-on questions on open F&Os (related to gap numbers 3 and 9 of the LAR) were discussed. Any additional information needed to support the LAR review will be formally requested by the staff utilizing the request for additional information process in accordance with Office of Nuclear Reactor Regulation Office Instruction L1C-101, "License Amendment Review Procedures." APLA staff re-capped its review of the closed F&Os, and noted the two potential questions noted above on open F&Os, at the exit meeting held on January 29, 2013 with MPS3 staff.
D. Heacock -2 Please contact me at (301) 415-4125 if you have any questions on this issue.
Sincerely, James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
As stated cc w/encl: Distribution via Listserv
List of Participants U.S. Nuclear Regulatory Commission Team
- Donnie Harrison APLA Chief
- Daniel O'Neal APLA Reliability and Risk Analyst Millstone Power Station Unit 3 Staff (Dominion)
- Wanda Craft Nuclear Licensing and Operations Support Enclosure 1
list of Documents Reviewed During Millstone Power Station Unit 3 TSTF425 Audit Appendix B - Quality Summary - ASME Standard SR status - 2012 SAIC Focused Scope Peer Review F&Os - 1999 WOG Peer Review F&Os Appendix A 1 - Internal Events Self-Assessment NFAA-PRA-1 01-2051, Probabilistic Risk Assessment Procedure and Methods: PRA Human Reliability Analysis - Human Failure Events, Attachment 2: "Review of Components, Procedures and Practices for the Pre-Initiator HRA."
IF_2, "Flood Scenarios Development" IF_2, Table 5, "Scenarios" Enclosure 2
D. Heacock -2 Please contact me at (301) 415-4125 if you have any questions on this issue.
Sincerely, Ira!
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
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