Letter Sequence Supplement |
---|
TAC:MD6115, Control Room Habitability (Approved, Closed) TAC:MD6116, Control Room Habitability (Approved, Closed) |
|
MONTHYEARML0732402752007-11-21021 November 2007 Request for Additional Information Regarding Control Room Habitability Project stage: RAI ML0734106512007-12-0707 December 2007 Application for Technical Specification Improvement Regarding Control Habitability Lbdcrs 07-MP2-013 and 07-MP3-033 Response to Request for Additional Information Project stage: Response to RAI ML0800203002008-01-28028 January 2008 Request for Additional Information Regarding Control Room Habitability (TAC Nos. MD6115 and 6116) Project stage: RAI ML0806606502008-03-0505 March 2008 Response to Request for Additional Information Regarding Control Room Habitability Technical Specification Improvement Project stage: Response to RAI ML0808508432008-03-25025 March 2008 Amended Response to Request for Additional Information Regarding Control Room Habitability Project stage: Response to RAI ML0812001362008-04-28028 April 2008 Significant Hazards Consideration Control Room Habitability - Recently Irradiated Fuel Project stage: Request ML0811904562008-05-0909 May 2008 FRN: Notice of Consideration of Issuance of Amendment to Millstone Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing Concerning Control Room Habitability Project stage: Acceptance Review ML0811904302008-05-0909 May 2008 Individual Notice of Consideration of Issuance of Amendment Concerning Control Room Habitability Project stage: Other ML0816202432008-06-0909 June 2008 Supplemental Information Regarding Control Room Habitability Project stage: Supplement ML0817900112008-06-26026 June 2008 Supplemental Information Regarding Control Room Habitability Project stage: Supplement ML0821102802008-07-28028 July 2008 Transmittal of Response to Request for Additional Information Regarding Control Room Habitability Program Amendment Request Project stage: Response to RAI ML0822706792008-09-18018 September 2008 Issuance of Amendments 305 and 243 Technical Specifications Regarding Control Room Habitability Project stage: Approval ML0822706892008-09-18018 September 2008 Technical Specifications, Amendment No. 305 to DPR-65, Control Room Habitability Project stage: Other ML0822706982008-09-24024 September 2008 Technical Specifications, Amendment No. 243 to NPF-49, Control Room Habitability Project stage: Acceptance Review 2008-04-28
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000245/20240012024-11-12012 November 2024 Safstor Inspection Report 05000245/2024001 ML24317A2562024-11-12012 November 2024 Core Operating Limits Report, Gycle 30 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 ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification 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 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) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code 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 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 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) 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) 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 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 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 ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) 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.
'i(lOO Dominion Boulevard, Glen Allen, Virginia 2.1060
'X,*b Address: www.dorn.com June 26, 2008 U. S. Nuclear Regulatory Commission Serial No. 08-0050C Attention: Document Control Desk NL&OS/GAW R1 Washington, DC 20555-0001 Docket Nos. 50-336 50-423 License Nos. DPR-65 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS 2 AND 3 SUPPLEMENTAL INFORMATION REGARDING CONTROL ROOM HABITABILITY (TAC NOS. MD6115 AND MD6116)
On July 13, 2007, Dominion Nuclear Connecticut, Inc. (DNC) submitted a request for an amendment to the Technical Specifications (TSs) for Millstone Power Station Units 2 and 3 (MPS2 and MPS3)
(Serial No. 07-0440). The proposed amendment would revise TS requirements related to control room envelope habitability consistent with the intent of NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-448, "Control Room Habitability," Revision 3. The NRC sent DNC requests for additional information (RAls) in letters dated November 21, 2007 and January 28, 2008. DNC responded to the RAls in letters dated December 7, 2007 (Serial No. 07-0790), March 5, 2008 (Serial No.08-0050), March 25, 2008 (Serial No. 08-0050A) and June 9, 2008 (Serial No. 08-00508).
As discussed in a conference call between NRC staff and DNC on June 17, 2008, DNC is providing additional clarification for its June 9, 2008 response to Question 3 in the attachment to this letter.
Question 3 was included in the NRC RAI dated January 28,2008. Specifically, NEI 99-03, Revision 1 is not relied upon in claiming any exceptions to the ASTM E741 test method.
Should you have any further questions in regard to this submittal, please contact Mr. Geoffery A.
Wertz at (804) 273-3572.
Sincerely,
,~Z~7~D Vice President - Nuclear Engineering COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Gerald T. Bischof, who is Vice President - Nuclear Engineering of Dominion Nuclear Connecticut, Inc.
He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.
iJ!
Acknowledged before me this~G? (fay otJiL.nL, 2008.
My Commission Expires: MAy 31 I ,lola
/f;it* L/ILILL Notary Public VICKI L. HULL NotaIy PublIc I...,
COIIIInOnWNIItI Of VIIgInIa COfNnIuIon ...... May '1. 101'
Serial No. 08-0050C Docket No. 50-336 50-423 Control Room Habitability Supplemental Information Page 2 of 2 Attachments: (1)
Control Room Habitability (TAC Nos. MD6115 and MD6116) - Supplemental Information Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. J. D. Hughey Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 B3 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring and Radiation Division CT Department of Environmental Protection 79 Elm St.
Hartford, CT 06106-5127
Serial No. 08-0050C Docket No. 50-336 50-423 Control Room Habitability Supplemental Information ATTACHMENT CONTROL ROOM HABITABILITY (TAC NOS. MD6115 AND MD6116)
SUPPLEMENTAL INFORMATION MILLSTONE POWER STATION UNITS 2 AND 3 DOMINION NUCLEAR CONNECTICUT, INC.
Serial No. 08-0050C Oocket Nos. 50-336 50-423 Control Room Habitability Supplemental Information Attachment, Page 1 of 1 CONTROL ROOM HABITABILITY SUPPLEMENTAL INFORMATION This supplement further clarifies the intent of ONC's application of the ASTM E741 testing methodology to nuclear power plant control room envelope integrity. Specifically, as discussed in a conference call between NRC staff and ONC on June 16, 2008, ONC is providing an amended response to Question 3. Question 3 was included in the NRC request for additional information dated January 28, 2008.
NRC Question ONC references NEI 99-03, Revision 1, Appendix EE, in Attachment 1, Page 7 of 11 under I Exceptions.'
The NRC staff has not reviewed NEI 99-03, Revision 1. Therefore, exceptions used in Appendix EE of NEI 99-03, Revision 1, have not been reviewed by the NRC staff. Please identify alternate plant-specific ASTM E741 exceptions and provide a detailed explanation justifying the acceptability of these exceptions.
ONC Response The ASTM E741 test method was not written specifically for use in nuclear power plant control room envelope tests. Exceptions referenced in ONC's submittal on July 13, 2007 (Serial No.
07-0440) are limited to those exceptions necessary to meet the intent of the ASTM E741 methodology when applying it to nuclear power plant control room envelope testing. These exceptions are typically taken by test vendors and documented in test reports, as is the case for MPS3.
When CRE testing is performed at MPS2 without the use of a vendor, ONe will document the steps taken to appropriately apply the ASTM E741 test methodology in the surveillance.
NEI 99-03, Revision 1 is not relied upon in claiming any exceptions to the ASTM E741 test method.