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MONTHYEARML1025802042010-07-29029 July 2010 Fourth 10-Year Interval Inservice Inspection Program and Associated Proposed Alternatives and Relief Request Project stage: Request ML1022205272010-08-0505 August 2010 Fourth 10-Year Interval Inservice Inspection Program Project stage: Request ML1107005072011-03-16016 March 2011 Request for Additional Information Regarding Pressure Testing Requirements for Service Water System Buried Piping Systems Project stage: RAI ML1110902622011-04-18018 April 2011 Response to Request for Additional Information Relief Request RR-04-05 Alternate Pressure/Flow Testing for Service Water Buried Piping Project stage: Response to RAI ML1118706002011-07-22022 July 2011 Issuance of Relief Request RR-04-05 Regarding Use of Alternative Pressure Testing Requirements Project stage: Approval 2011-03-16
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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 Web Address: www.dom.com April 18, 2011 U. S. Nuclear Regulatory Commission Serial No.11-166 Attention: Document Control Desk NSSLl\NDC RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2 REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST RR-04-05 ALTERNATE PRESSURE/FLOW TESTING FOR SERVICE WATER BURIED PIPING, (T AC NO. ME4472)
Dominion Nuclear Connecticut, Inc. (DNC) submitted the Millstone Power Station Unit 2 (MPS2) fourth 10-year lSI program and associated proposed alternatives and relief requests in a letter dated July 29, 2010 and supplemental letter dated August 5, 2010. ONC requested the use of alternatives to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI requirements. Included in the submittal was Relief Request RR 05, which requests the use of alternative pressure testing requirements for service water system buried piping segments. In a letter dated March 16, 2011, the NRC transmitted a request for additional information (RAI) related to RR 05. ONC agreed to respond to the RAI by April 27, 2011.
Attachment 1 provides ONC's response to the NRC RAI.
If you have any questions regarding this submittal, please contact Wanda Craft at (804) 273-4687.
Sincerely,
Serial No.11-166 Docket No. 50-336 RAI Response for RR-04-05 Page 2 of 2
Attachment:
- 1. Response to Request for Additional Information Regarding Relief Request RR-04-05 Alternate Pressure/Flow Testing for Service Water Buried Piping Commitments made in this letter:
- 1. None cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 J. 0 Hughey Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08-B1A Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.11-166 Docket No. 50-336 ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST RR-04-05, "ALTERNATE PRESSURE/FLOW TESTING FOR SERVICE WATER BURIED PIPING" DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2
Serial No.11-166 Docket No. 50-336 RAI Response for RR-04-05 Attachment 1, Page 1 of 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST RR-04-05. "ALTERNATE PRESSUREIFLOW TESTING FOR SERVICE WATER BURIED PIPING" Dominion Nuclear Connecticut, Inc. (DNC) submitted the Millstone Power Station Unit 2 (MPS2) fourth 10-year lSI program and associated proposed alternatives and relief requests in a letter dated July 29, 2010 and supplemental letter dated August 5, 2010.
ONC requested the use of alternatives to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI requirements.
Included in the submittal was Relief Request RR-04-05, which requests the use of alternative pressure testing requirements for service water system buried piping segments. In a letter dated March 16, 2011, the NRC transmitted a request for additional information (RAI) related to RR-04-05. This attachment provides DNC's response to the NRC RAI.
Question 1 The Piping and Instrument Diagram (P&ID) that is included with the relief request shows buried piping and four flow elements in grid coordinate C-13.
a) Is the buried piping indicated in grid coordinate C-13 the only piping being covered in this relief request, or is the 24"-KE-1 piping (flagged on the P&ID) in tunnels also being covered?
b) Are the flow elements downstream of the buried piping in grid coordinate C-13 the flow elements used for pump inservice testing (1ST) surveillance?
c) Are there piping segments, covered by this relief request, that are downstream of the flow elements used for pump 1ST surveillance and, if so, what means will be used to detect pipe leakage in these segments?
DNC Response a) The buried piping in grid C-13 is the only piping covered in this request. The 24"-
KE-1 piping in the pipe tunnel is accessible and receives a visual VT-2 examination in accordance with the requirements of the ASME Section XI Code.
The line number 24"-KE-1 that is flagged on the P&IO (two places) was only meant to highlight the line number, not to indicate relief request coverage for that portion of piping.
b) Yes, the flow elements downstream of the buried piping in grid coordinate C-13 are the flow elements used for pump 1ST surveillance.
c) The piping downstream of the flow elements used for pump 1ST surveillance is not covered by this relief request. The piping downstream of the flow elements
Serial No.11-166 Docket No. 50-336 RAI Response for RR-04-05 Attachment 1, Page 2 of 2 receives a visual (VT-2) examination in accordance with the requirements of the ASME Section XI Code.
Question 2 What is the total length of 24"-KE-1 piping considered in this relief request?
ONC Response The total length of 24"-KE-1 piping subject to this relief request is approximately 494 feet.
Question 3 Provide a brief summary of the 24"-KE-1 lining inspection results and pipe leak history.
ONC Response Internal visual inspections of the lining of the buried piping segments of 24"-KE-1 has identified no significant degradation of the liner. There is no history of leakage for the buried piping segments of line 24"-KE-1.