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MONTHYEARML0924503332009-08-28028 August 2009 Vogtle - Submittal of Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9, Steam Generator (SG) Program and TS 5.6.10, Steam Generator Tube Inspection... Project stage: Response to RAI NL-09-1265, Response to RAI Related to License Amendment Request to Revise TS Sections 5.5.9, Steam Generator (SG) Program and TS 5.6.10,Steam Generator Tube Inspection Report for Permanent Alternate Repair Criteria2009-08-28028 August 2009 Response to RAI Related to License Amendment Request to Revise TS Sections 5.5.9, Steam Generator (SG) Program and TS 5.6.10,Steam Generator Tube Inspection Report for Permanent Alternate Repair Criteria Project stage: Response to RAI NL-09-1317, Supplemental Information for License Amendment Request to Revise Technical Specification Sections 5.5.9, Steam Generator (SG) Program and TS 5.6.10, Steam Generator Tube Inspection Report for Permanent Alternate Repair Criteria2009-08-28028 August 2009 Supplemental Information for License Amendment Request to Revise Technical Specification Sections 5.5.9, Steam Generator (SG) Program and TS 5.6.10, Steam Generator Tube Inspection Report for Permanent Alternate Repair Criteria Project stage: Supplement NL-09-1411, License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9, Steam Generator (SG) Program and TS 5.6.10, Steam Generator Tube Inspection Report for Interim Alternate Repair Criteria2009-09-11011 September 2009 License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9, Steam Generator (SG) Program and TS 5.6.10, Steam Generator Tube Inspection Report for Interim Alternate Repair Criteria Project stage: Request ML0936200852009-11-23023 November 2009 License Amendment Request to Revise Technical Specification (TS) 6.8.4.g, Steam Generator (SG) Program, and TS 6.9.1.7, Steam Generator Tube Inspection Report for One-Time Alternate Repair Criteria (H*) Project stage: Request ML1011904172010-04-22022 April 2010 Westinghouse Electric Co., LLC, LTR-SGMP-10-50 NP-Attachment Assessment of the Effect of the Location of the Bottom of the Expansion Transition on H. Project stage: Request ML1011804732010-04-28028 April 2010 Response to Query on MPS3 Tube Inspection Results Project stage: Request ML1007703582010-05-0303 May 2010 Issuance of Amendment Changes to the Steam Generator Inspection Scope and Repair Requirements Project stage: Approval ML1015405582010-06-11011 June 2010 Request for Withholding Information from Public Disclosure for Millstone Power Station, Unit 3 Project stage: Withholding Request Acceptance ML1021607492010-09-22022 September 2010 Request for Withholding Information from Public Disclosure for Millstone Power Station, Unit No. 3 Project stage: Withholding Request Acceptance ML1028504382010-09-30030 September 2010 Attachments 2, 3, 5, 7, 8 & 9, to 10-579A, Westinghouse Electric Co. LLC, WCAP-17071-NP, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F), Revision 2, Dated Sep Project stage: Other ML1027308602010-09-30030 September 2010 Extension Request for Resubmittal of Westinghouse Documentation Supporting License Amendment 249, Changes to the Steam Generator Inspection Scope & Repair Requirements Project stage: Request ML1028504352010-10-0707 October 2010 Resubmittal of Westinghouse Documentation Supporting License Amendment 249, Changes to the Steam Generator Inspection Scope and Repair Requirements Project stage: Other ML1103906642011-02-28028 February 2011 Request for Withholding Information from Public Disclosure for Millstone Power Station, Unit No. 3 Project stage: Withholding Request Acceptance 2010-04-28
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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 ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations 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) 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 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 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 ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 2024-09-04
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Dominion R eso rceServices, Innsbrook Technical Center Inc.
5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 October 7, 2010 oiil U.S. Nuclear Regulatory Commission Serial No. 10-579A Attention: Document Control Desk NSSL/MLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 RESUBMITTAL OF WESTINGHOUSE DOCUMENTATION SUPPORTING LICENSE AMENDMENT 249, "CHANGES TO THE STEAM GENERATOR INSPECTION SCOPE AND REPAIR REQUIREMENTS (TAC NO. ME2978)"
In a letter dated November 23, 2009, and supplemented by a letter dated April 26, 2010, Dominion Nuclear Connecticut, Inc. (DNC) submitted a request for a one-time revision to Facility Operating License NPF-49 for Millstone Power Station Unit 3 (MPS3). This amendment request proposed to revise Technical Specification (TS) 6.8.4.g, "Steam Generator (SG) Program," and TS 6.9.1.7, "Steam Generator Tube Inspection Report,"
to incorporate the one-time alternate repair criteria (H*). On May 3, 2010, in response to this request, the Nuclear Regulatory Commission (NRC) issued License Amendment (LA) 249 for Refueling Outage 13 and the subsequent operating cycle.
During the NRC's administrative processing of the supporting documentation for LA 249, the NRC discovered discrepancies with proprietary markings in some of the Westinghouse documents supporting the license amendment request dated November 23, 2009. On September 22, 2010, the NRC issued a letter to DNC requesting affected documents be revised and resubmitted to meet the requirements of 10 CFR 2.390(b)(1)(i). The specific discrepancies, which are administrative in nature, are detailed in Attachment 1. The revised documents and affidavits (as applicable), are provided in Attachments 2 through 9.
Attachments 4 and 6 contain proprietary information. Classification of these attachments as proprietary is supported by the affidavits provided in Attachments 3 and 5; therefore, it is respectfully requested that this information be withheld from public disclosure in accordance with 10 CFR 2.390.
If you have any questions regarding this submittal, please contact Mr. William D.
Bartron at (860) 444-4301.
Sincerely, C. L. Funderburk Director, Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Dominion Nuclear Connecticut, Inc.
AooI
Serial No. 10-579A Docket No. 50-423 Page 2 of 3 Attachments:
- 1. Administrative Discrepancies in Westinghouse Documents Supporting License Amendment 249.
- 2. Westinghouse Electric Company LLC, WCAP-17071-NP, "H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F)," Revision 2, dated September 2010. (Non-Proprietary)
- 3. Westinghouse Electric Company LLC, CAW-10-2966, "Application forWithholding Proprietary Information from Public Disclosure," for WCAP-17071-P, Revision 2, dated September 28, 2010. (Non-Proprietary)
- 4. Westinghouse Electric Company LLC, WCAP-17071-P, "H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F)," Revision 2, dated September 2010. (Proprietary)
- 5. Westinghouse Electric Company LLC, CAW-1 0-2948, "Application for Withholding Proprietary Information from Public Disclosure," for LTR-SGMP-09-100 P-Attachment, Rev. 1, dated September 9, 2010. (Non-Proprietary)
- 6. Westinghouse Electric Company LLC, LTR-SGMP-09-100 P-Attachment, Rev. 1, "Response to NRC Request for Additional Information on H*; Model F and Model D5 Steam Generators, dated September 7, 2010. (Proprietary)
- 7. Westinghouse Electric Company LLC, LTR-SGMP-09-1100 NP-Attachment, Rev. 1, "Response to NRC Request for Additional Information on H*; Model F and Model D5 Steam Generators," dated September 7, 2010. (Non-Proprietary)
- 8. Westinghouse Electric Company LLC, LTR-RCPL-09-131, WCAP-17071-P, Rev. 0 Proprietary Information Clarification, dated August 27, 2009. (Non-Proprietary)
- 9. 'Westinghouse Electric Company LLC, LTR-SGMP-09-121, Replacements for Illegible Pages in Prior RAI Response (Reference 1), dated August 27, 2009. (Non-Proprietary)
Commitments made in this letter: None
Serial No. 10-579A Docket No. 50-423 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 C. J. Sanders, Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08-B3 Rockville, MD 20852-2738 NRC Senior Resident Inspector (w/o attachments)
Millstone Power Station
Serial No. 10-579A Docket No. 50-423 ATTACHMENT I ADMINISTRATIVE DISCREPANCIES IN WESTINGHOUSE DOCUMENTS SUPPORTING LICENSE AMENDMENT 249 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 2
Serial No. 10-579A Docket No. 50-423 Attachment 1 Page 1 of 3 Administrative Discrepancies in Westinghouse Documents Supporting License Amendment 249 In a letter dated November 23, 2009, and supplemented by a letter dated April 26, 2010, Dominion Nuclear Connecticut, Inc. (DNC) submitted a request for a one-time revision to Facility Operating License NPF-49 for Millstone Power Station Unit 3 (MPS3). This amendment request proposed to revise Technical Specification (TS) 6.8.4.g, "Steam Generator (SG) Program," and TS 6.9.1.7, "Steam Generator Tube Inspection Report," to incorporate the one-time alternate repair criteria (H*). On May 3, 2010, in response to this request, the Nuclear Regulatory Commission (NRC) issued License Amendment (LA) 249 for Refueling Outage 13 and the subsequent operating cycle.
During the NRC's administrative processing of the supporting documentation for LA 249, the NRC discovered discrepancies with proprietary markings in some of the Westinghouse documents supporting the license amendment request dated November 23, 2009. On September 22, 2010, the NRC issued a letter (Agencywide Document Access and Management System (ADAMS) Accession No. ML102160749) to DNC requesting affected documents be revised and resubmitted to meet the requirements of 10 CFR 2.390(b)(1)(i). The specific discrepancies, which are administrative in nature, are detailed below:
- 1) Sections 9 and 10 of Enclosure 10, WCAP-17071-NP, "H*.: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generatorswith Hydraulically Expanded Tubes (Model F)," (Non-Proprietary),,are marked "Westinghouse ProprietaryClass 2," at the top of each page although DNC clearly indicates that the document is non-proprietaryon page 6 of its November 23, 2009, letter.
Additionally, DNC identified the following:
Appendix A and the first page of Appendix B of WCAP-17071-NP, Revision 0, contain Proprietary Class 2 markings at the top of the page. These pages are non-proprietary and therefore should not be marked as Proprietary Class 2.
Appendix B of WCAP-1 7071 -P, Revision 0 (except for the first page), is not marked Proprietary Class 2 at the top of each page although the document is proprietary.
DNC Response Westinghouse documents WCAP-17071-NP and WCAP-17071-P have been revised to correct the discrepancies identified above. These corrected documents are provided as Revision 2 in Attachments 2 and 4, respectively. No new technical information is provided in Revision 2 to these documents.
a
Serial No. 10-579A Docket No. 50-423 Attachment 1 Page 2 of 3 The proprietary information contained in WCAP-17071-P, Revision 2, is supported by the affidavit, CAW-10-2966, contained in Attachment 3. It is respectfully requested that this information be withheld from public disclosure in accordance with 10 CFR 2.390.
- 2) There is no non-proprietaryversion of Enclosure 8, LTR-RCLP-09-131, "WCAP-I 7071-P, Rev. 0 ProprietaryInformation Clarification."Also, the letter contains no basis for proposingthe information be withheld.
Note: The correct Westinghouse letter designation is LTR-RCPL-09-1 31.
DNC Response Westinghouse transmittal letter, LTR-RCPL-09-131, is marked Proprietary Class 2 by Westinghouse policy because it transmits a proprietary document. There is no information in the cover letter or in Attachment 1 to the letter that is proprietary.
Therefore, DNC is resubmitting LTR-RCPL-09-1 31 and Attachment 1, without the Proprietary Class 2 markings at the top of these pages. See Attachment 8.
- 3) There are no markings at the top of page 74 of Enclosure 6, LTR-SGMP-09-100, "Response to NRC Request for Additional Information on H*: Model F and Model D5 Steam Generators."
DNC Response Westinghouse document LTR-SGMP-09-100 P-Attachment, Revision 0, has been revised to add a Proprietary Class 2 marking and page number to page 74. These changes are contained in Revision 1. See Attachment 6. The proprietary information contained in LTR-SGMP-09-1 00 P-Attachment, Revision 1, is supported by the affidavit, CAW-1 0-2948, contained in Attachment 5. It is respectfully requested that this information be withheld from public disclosure in accordance with 10 CFR 2.390.
- 4) Page 78 of Enclosure 6, and its non-proprietarycounterpart (Enclosure 11), included bracketed information without providing a basis for proposingthe information be withheld.
DNC Response Westinghouse document, LTR-SGMP-09-100 NP-Attachment, Revision 0, has been revised to correct the erroneous deletion of non-proprietary information on page 78.
Additionally, Westinghouse document, LTR-SGMP-09-100 P-Attachment, Revision 0, has been revised to correct symbols on pages 46, 68, and 85 that did not transfer
Serial No. 10-579A Docket No. 50-423 Attachment 1 Page 3 of 3 properly to the .pdf version. These symbols were replaced with words or the symbol corrected.
LTR-SGMP-09-100 P-Attachment, Revision 1, and LTR-SGMP-09-100 NP-Attachment, Revision 1, are provided in Attachments 6 and 7, respectively. No new technical information is provided in Revision 1 to these documents.
The proprietary information contained in Attachment 6 is supported by the affidavit, CAW-10-2948, contained in Attachment 5. It is respectfully requested that this information be withheld from public disclosure in accordance with 10 CFR 2.390.
- 5) There is no non-proprietaryversion of Enclosure 9, LTR-SGMP-09-121, "Replacementsfor Illegible Pages in PriorRAI Response (Reference 1). Also, the letter contains no basis for proposing the information be withheld.
DNC Response Westinghouse transmittal letter, LTR-SGMP-09-121, is marked Proprietary Class 2 by Westinghouse policy because it transmits a proprietary document. There is no information in the cover letter that is proprietary. Therefore, DNC is resubmitting LTR-SGMP-09-121 without the Proprietary Class 2 markings at the top of that page. See Attachment 9.
There is no non-proprietary version of the replacement pages provided by Westinghouse transmittal letter LTR-SGMP-09-121. These illegible figuires were redacted in the non-proprietary version of LTR-SGMP-09-100, which is the reference document identified in LTR-SGMP-09-121, and therefore the corresponding pages did not require replacement.