|
|
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:Dominion Nuclear Connecticut, Inc.5000 Dominion Boulevard, Glen Allen, VA 23060 7J DominionWeb Address: www.dom.comProprietary Information -Withhold Under 10 CFR 2.390March 7, 2013U. S. Nuclear Regulatory Commission Serial No. 12-578AAttention: Document Control Desk NSSL/WDC ROWashington, DC 20555 Docket No. 50-336License No. DPR-65DOMINION NUCLEAR CONNECTICUT. INC.MILLSTONE POWER STATION UNIT 2SUPPLEMENT TO RESPONSE TO REQUEST FOR ADDITIONAL INFORMATIONREGARDING THE 30-DAY REPORT FOR EMERGENCY CORE COOLING SYSTEMMODEL CHANGES (TAC NO. ME7881)By letter dated January 25, 2012, Dominion Nuclear Connecticut, Inc. (DNC) submittedthe Millstone Power Station Unit 2 (MPS2) 30-Day Report for Emergency Core CoolingSystem Model Changes. The report documented changes to, or errors discovered in,an acceptable Small Break Loss of Coolant Accident (SBLOCA) evaluation model (EM)application for the emergency core cooling system for MPS2, in accordance with 10CFR 50.46(a)(3)(ii). By letter dated August 28, 2012, the NRC transmitted a request foradditional information (RAI) to DNC related to the report. DNC responded to the RAI ina letter dated November 1, 2012.In a telephone call between NRC and DNC on November 20, 2012, DNC agreed toperform additional sensitivity studies which would combine the effects of certainmodeling assumptions for the MPS2 SBLOCA. Attachment 1 provides the summaryreport of the sensitivity studies. The report contains proprietary AREVA information.The non-proprietary version of the report is provided in Attachment 2. It is respectfullyrequested that Attachment 1 be withheld from public disclosure in accordance with 10CFR 2.390. The AREVA application for withholding and affidavit is provided inAttachment 3.As shown in the attached report, the SBLOCA current licensing basis peak cladtemperature of 1801°F remains conservative. Since the MPS2 SBLOCA currentlicensing basis peak clad temperature is conservative and consistent with the Reference1 NRC approved methodology, no additional reporting under 10 CFR 50.46(a)(3)(ii) iswarranted.DNC understands that Supplement 1 of the Reference 1 AREVA S-RELAP5 basedPWR SBLOCA evaluation model is currently with the NRC for review and approval. Asstated in the DNC letter dated November 1, 2012, within one year of NRC approval ofSupplement 1 of Reference 1, DNC plans to submit a reanalysis of the SBLOCA eventusing Supplement 1 of Reference 1.Attachment I contains information that is being withheld from publicdisclosure under 10 CFR 2.390. Upon separation from Attachment 1, thisletter is decontrolled.-- | | {{#Wiki_filter:Dominion Nuclear Connecticut, Inc.5000 Dominion Boulevard, Glen Allen, VA 23060 7J Dominion Web Address: www.dom.com Proprietary Information |
| Serial No. 12-578ADocket No. 50-336Page 2 of 2If you have any questions regarding this submittal, please contact William D. Bartron at(860) 444-4301.Sincerely,Eugene S. GrecheckVice President -Nuclear Engineering and Development | | -Withhold Under 10 CFR 2.390 March 7, 2013 U. S. Nuclear Regulatory Commission Serial No. 12-578A 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 SUPPLEMENT TO RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING THE 30-DAY REPORT FOR EMERGENCY CORE COOLING SYSTEM MODEL CHANGES (TAC NO. ME7881)By letter dated January 25, 2012, Dominion Nuclear Connecticut, Inc. (DNC) submitted the Millstone Power Station Unit 2 (MPS2) 30-Day Report for Emergency Core Cooling System Model Changes. The report documented changes to, or errors discovered in, an acceptable Small Break Loss of Coolant Accident (SBLOCA) evaluation model (EM)application for the emergency core cooling system for MPS2, in accordance with 10 CFR 50.46(a)(3)(ii). |
| | By letter dated August 28, 2012, the NRC transmitted a request for additional information (RAI) to DNC related to the report. DNC responded to the RAI in a letter dated November 1, 2012.In a telephone call between NRC and DNC on November 20, 2012, DNC agreed to perform additional sensitivity studies which would combine the effects of certain modeling assumptions for the MPS2 SBLOCA. Attachment 1 provides the summary report of the sensitivity studies. The report contains proprietary AREVA information. |
| | The non-proprietary version of the report is provided in Attachment |
| | : 2. It is respectfully requested that Attachment 1 be withheld from public disclosure in accordance with 10 CFR 2.390. The AREVA application for withholding and affidavit is provided in Attachment 3.As shown in the attached report, the SBLOCA current licensing basis peak clad temperature of 1801°F remains conservative. |
| | Since the MPS2 SBLOCA current licensing basis peak clad temperature is conservative and consistent with the Reference 1 NRC approved methodology, no additional reporting under 10 CFR 50.46(a)(3)(ii) is warranted. |
| | DNC understands that Supplement 1 of the Reference 1 AREVA S-RELAP5 based PWR SBLOCA evaluation model is currently with the NRC for review and approval. |
| | As stated in the DNC letter dated November 1, 2012, within one year of NRC approval of Supplement 1 of Reference 1, DNC plans to submit a reanalysis of the SBLOCA event using Supplement 1 of Reference 1.Attachment I contains information that is being withheld from public disclosure under 10 CFR 2.390. Upon separation from Attachment 1, this letter is decontrolled.-- |
| | Serial No. 12-578A Docket No. 50-336 Page 2 of 2 If you have any questions regarding this submittal, please contact William D. Bartron at (860) 444-4301.Sincerely, Eugene S. Grecheck Vice President |
| | -Nuclear Engineering and Development |
|
| |
|
| ==References:== | | ==References:== |
| : 1. AREVA Report EMF-2328(P)(A), Revision 0, "PWR Small Break LOCAEvaluation Model, S-RELAP5 Based," March 2001.Attachments:1. Millstone Unit 2 Small Break LOCA Sensitivity Study Summary Report(Proprietary)2. Millstone Unit 2 Small Break LOCA Sensitivity Study Summary Report (Non-Proprietary)3. AREVA application for withholding and affidavitCommitments made in this letter: Nonecc: U.S. Nuclear Regulatory CommissionRegion I2100 Renaissance Blvd.Suite 100King of Prussia, PA 19406-2713J. S. KimProject Manager -Millstone Power StationU.S. Nuclear Regulatory CommissionOne White Flint North11555 Rockville PikeMail Stop 08 C2ARockville, MD 20852-2738NRC Senior Resident InspectorMillstone Power Station | | : 1. AREVA Report EMF-2328(P)(A), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," March 2001.Attachments: |
| }} | | : 1. Millstone Unit 2 Small Break LOCA Sensitivity Study Summary Report (Proprietary) |
| | : 2. Millstone Unit 2 Small Break LOCA Sensitivity Study Summary Report (Non-Proprietary) |
| | : 3. AREVA application for withholding and affidavit Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd.Suite 100 King of Prussia, PA 19406-2713 J. S. Kim Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2A Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station}} |
Letter Sequence Supplement |
---|
|
|
MONTHYEARML12236A1442012-08-28028 August 2012 Request for Additional Information Regarding 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.45 Project stage: RAI ML12311A0292012-11-0101 November 2012 Response to Request for Additional Information Regarding the 30-Day Report for Emergency Core Cooling System Model Changes Project stage: Response to RAI ML13074A7952013-03-0707 March 2013 Supplement to Response to Request for Additional Information Regarding 30-Day Report for Emergency Core Cooling System Model Changes Project stage: Supplement ML13071A1022013-03-13013 March 2013 Request for Withholding Information from Public Disclosure for Millstone Power Station, Unit No. 2 Project stage: Withholding Request Acceptance ML13080A3062013-03-28028 March 2013 Request for Withholding Information from Public Disclosure for Millstone Power Station, Unit No. 2 Project stage: Withholding Request Acceptance ML13192A1022013-07-18018 July 2013 Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 Project stage: Other 2013-03-13
[Table View] |
|
---|
Category:Letter
MONTHYEARML24317A2562024-11-12012 November 2024 Core Operating Limits Report, Gycle 30 IR 05000245/20240012024-11-12012 November 2024 Safstor Inspection Report 05000245/2024001 IR 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) ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 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) 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) 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 ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 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 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 ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 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) ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating 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 2024-09-04
[Table view] |
Text
Dominion Nuclear Connecticut, Inc.5000 Dominion Boulevard, Glen Allen, VA 23060 7J Dominion Web Address: www.dom.com Proprietary Information
-Withhold Under 10 CFR 2.390 March 7, 2013 U. S. Nuclear Regulatory Commission Serial No. 12-578A 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 SUPPLEMENT TO RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING THE 30-DAY REPORT FOR EMERGENCY CORE COOLING SYSTEM MODEL CHANGES (TAC NO. ME7881)By letter dated January 25, 2012, Dominion Nuclear Connecticut, Inc. (DNC) submitted the Millstone Power Station Unit 2 (MPS2) 30-Day Report for Emergency Core Cooling System Model Changes. The report documented changes to, or errors discovered in, an acceptable Small Break Loss of Coolant Accident (SBLOCA) evaluation model (EM)application for the emergency core cooling system for MPS2, in accordance with 10 CFR 50.46(a)(3)(ii).
By letter dated August 28, 2012, the NRC transmitted a request for additional information (RAI) to DNC related to the report. DNC responded to the RAI in a letter dated November 1, 2012.In a telephone call between NRC and DNC on November 20, 2012, DNC agreed to perform additional sensitivity studies which would combine the effects of certain modeling assumptions for the MPS2 SBLOCA. Attachment 1 provides the summary report of the sensitivity studies. The report contains proprietary AREVA information.
The non-proprietary version of the report is provided in Attachment
- 2. It is respectfully requested that Attachment 1 be withheld from public disclosure in accordance with 10 CFR 2.390. The AREVA application for withholding and affidavit is provided in Attachment 3.As shown in the attached report, the SBLOCA current licensing basis peak clad temperature of 1801°F remains conservative.
Since the MPS2 SBLOCA current licensing basis peak clad temperature is conservative and consistent with the Reference 1 NRC approved methodology, no additional reporting under 10 CFR 50.46(a)(3)(ii) is warranted.
DNC understands that Supplement 1 of the Reference 1 AREVA S-RELAP5 based PWR SBLOCA evaluation model is currently with the NRC for review and approval.
As stated in the DNC letter dated November 1, 2012, within one year of NRC approval of Supplement 1 of Reference 1, DNC plans to submit a reanalysis of the SBLOCA event using Supplement 1 of Reference 1.Attachment I contains information that is being withheld from public disclosure under 10 CFR 2.390. Upon separation from Attachment 1, this letter is decontrolled.--
Serial No. 12-578A Docket No. 50-336 Page 2 of 2 If you have any questions regarding this submittal, please contact William D. Bartron at (860) 444-4301.Sincerely, Eugene S. Grecheck Vice President
-Nuclear Engineering and Development
References:
- 1. AREVA Report EMF-2328(P)(A), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," March 2001.Attachments:
- 1. Millstone Unit 2 Small Break LOCA Sensitivity Study Summary Report (Proprietary)
- 2. Millstone Unit 2 Small Break LOCA Sensitivity Study Summary Report (Non-Proprietary)
- 3. AREVA application for withholding and affidavit Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd.Suite 100 King of Prussia, PA 19406-2713 J. S. Kim Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2A Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station