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| | number = ML12062A069 | | | number = ML12062A069 |
| | issue date = 02/24/2012 | | | issue date = 02/24/2012 |
| | title = Millstone Power Station - Response to Request for Additional Information Regarding License Amendment Request to Revise the Snubber Technical Specification Surveillance Requirements | | | title = Response to Request for Additional Information Regarding License Amendment Request to Revise the Snubber Technical Specification Surveillance Requirements |
| | author name = Hartz L N | | | author name = Hartz L N |
| | author affiliation = Dominion Nuclear Connecticut, Inc | | | author affiliation = Dominion Nuclear Connecticut, Inc |
Letter Sequence Response to RAI |
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Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 ML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A2162024-04-0101 April 2024 Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits 2024-09-04
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Dominion Nuclear Connecticut, Inc.5000 Dominion Boulevard, Glen Allen, Virginia 23060 J Dom inion Web Address: www.dom.com February 24, 2012 U. S. Nuclear Regulatory Commission Serial No.12-086 Attention:
Document Control Desk NSSL/WDC RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT.
INC.MILLSTONE POWER STATION UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE THE SNUBBER TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS (TAC NO. ME7221)By letter dated September 21, 2011, Dominion Nuclear Connecticut, Inc. (DNC)submitted a license amendment request (LAR) for Millstone Power Station Unit 2 (MPS2) to revise Technical Specification (TS) 3/4.7.8, Snubbers.
The proposed amendment would revise the TS for snubbers to conform to the revised MPS2 inservice inspection program. In a letter dated February 9, 2012, the NRC transmitted a request for additional information (RAI) to DNC related to the LAR. DNC agreed to respond to the RAI by March 7, 2012.Attachment 1 provides DNC's response to the NRC's RAI.If you have any questions regarding this submittal, please contact Wanda Craft at (804)273-4687.Sincerely, L. N. H artz ~Vice President
-Nuclear Support Services
Attachment:
- 1. Response to Request for Additional Information Regarding License Amendment Request to Revise the Snubber Technical Specification Surveillance Requirements Commitments made in this letter: 1. None 4ooI Serial No.12-086 Docket No. 50-336 RAI Response for Revision to TS 3/4.7.8, Snubbers Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 C. J. Sanders Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08-B3 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Serial No.12-086 Docket No. 50-336 RAI Response for Revision to TS 3/4.7.8, Snubbers ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE THE SNUBBER TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 2 Serial No.12-086 Docket No. 50-336 RAI Response for Revision to TS 3/4.7.8, Snubbers Attachment 1, Page 1 of 2 By letter dated September 21, 2011, Dominion Nuclear Connecticut, Inc. (DNC)submitted a license amendment request (LAR) for Millstone Power Station Unit 2 (MPS2) to revise Technical Specification (TS) 3/4.7.8, Snubbers.
The proposed amendment would revise the TS for snubbers to conform to the revised MPS2 inservice inspection (ISI) program.-
In a letter dated February 9, 2012, the NRC transmitted a request for additional information (RAI) to DNC related to the LAR. This attachment provides DNC's response to the NRC's RAI.
References:
- 1. Dominion Nuclear, Connecticut, Inc. (Dominion), letter to NRC, "Licensee Amendment Request (LAR) to Revise Snubber Surveillance Requirements," for Millstone Power Station, Unit 2, Docket No. 50-336, dated September 21, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11270A051).
- 2. Millstone Power Station Unit 2 (MPS2),. Fourth 10-Year Interval Inservice (ISI)Inspection Program and Associated Proposed Alternatives and Relief Requests, July, 2010 (ADAMS Accession No. ML102580204).
- 3. Millstone Power Station Unit 2, Fourth 10-Year Interval Inservice Inspection Program, August 5, 2010 (ADAMS Accession No. ML 102220527).
In Reference 1, Attachment 1, Page 1 of 7, Section 3.0, "Background", the first paragraph states that "MPS2 is currently in the fourth 10-year ISI interval.
The fourth 10-year interval at MPS2 began on April 1, 20,10 (References 2 and 3). Currently, snubber testing and examination are performed in accordance with the specific requirements of Technical Specification (TS) 3/4.7.8 and the requirements contained in American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), 2004 Edition." On Page 1-16, Section 1.8.25 and Page 2-34, Note 4, of References 2 and 3, it is noted that the snubber examination and testing of snubbers is performed in accordance with the 2004 Edition of the ASME OM Code, ISTD.RAI 1: Please state whether examination and testing of snubbers is performed per TS 3/4.7.8 and the ASME OM Code requirements as described in Reference I or only in accordance with ASME OM Code, ISTD requirements as noted in References 2 and 3.If MPS2 is performing examination and testing of snubbers per TS 3/4.7.8 and the ASME OM Code, please explain how Dominion is meeting both sets of requirements at MPS2.
Serial No.12-086 Docket No. 50-336 RAI Response for Revision to TS 3/4.7.8, Snubbers Attachment 1, Page 2 of 2 DNC Response MPS2 is currently meeting the requirements of both TS 3/4.7.8 and ASME OM Code, ISTD, 2004 Edition (ISTD).Consistent with the guidance in NRC Regulatory Issue Summary 2010-06, "Inservice Inspection and Testing Requirements of Dynamic Restraints (Snubbers)," DNC submitted a LAR (Reference
- 1) to revise the TS for snubbers to conform to the requirements of ISTD, which is MPS2's code of record for the fourth 10-year ISI interval (References 2 and 3). Consequently, until the LAR is approved by the NRC, DNC has and will continue to meet the requirements of TS 3/4.7.8 and ISTD for examination and testing of snubbers.During the first refueling outage in the fourth 10-year ISI interval (2R20), snubber testing was performed to the requirements of both the TS and ISTD. Comparison of the MPS2 TS and ISTD show that the snubber requirements are very similar, with some differences in snubber grouping and scope expansion.
While the requirements of the TSs were met using existing surveillance procedures and work orders, the additional requirements of ISTD were addressed using newly created work orders. This will continue until approval of the LAR by the NRC.RAI 2: Attachment 5 of Reference 1 contains the MPS2 Snubber Program, Rev. 0, dated July 21, 2011. Please indicate what snubber program was being used at MPS2 from April 1, 2010 through July 21, 2011, and provide a copy of this snubber program, if it is different than Attachment 5.DNC Response From April 1, 2010 through July 21, 2011, the program plan for examination and testing of snubbers was delineated in the MPS2 Fourth 10-Year Interval ISI Program update (References 2 and 3). In the program update, DNC committed to the requirements of ISTD for examination and testing of snubbers.
Until the TS is revised, DNC has and will continue to meet the requirements of both the TS and ISTD. Upon approval of the LAR, the snubber program provided in Attachment 5 of Reference 1 will be implemented.