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Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024
Technical Specification Bases Pages
IR 05000336/20234022024-01-30030 January 2024
Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only)
ML23341A0172024-01-12012 January 2024
Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures
IR 05000336/20234402024-01-11011 January 2024
Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only)
ML24004A1052024-01-0404 January 2024
Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010
ML23361A0942023-12-21021 December 2023
Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report .
ML23283A3052023-12-20020 December 2023
Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary)
ML23361A0312023-12-20020 December 2023
Intent to Pursue Subsequent License Renewal
ML23352A0202023-12-18018 December 2023
Senior Reactor and Reactor Operator Initial License Examinations
ML23334A2242023-11-30030 November 2023
Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation
ML23324A4222023-11-20020 November 2023
Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13
ML23324A4302023-11-20020 November 2023
Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15
ML23317A2702023-11-13013 November 2023
Core Operating Limits Report, Cycle 23
IR 05000336/20230032023-11-0606 November 2023
Integrated Inspection Report 05000336/2023003 and 05000423/2023003
ML23298A1652023-10-26026 October 2023
Requalification Program Inspection
IR 05000336/20234202023-10-0404 October 2023
Security Inspection Report 05000336/2023420 and 05000423/2023420
ML23230A0502023-10-0202 October 2023
5 of the Quality Assurance Topical Report - Review of Program Changes
ML23226A0052023-09-26026 September 2023
Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis
IR 05000245/20230012023-09-19019 September 2023
Safstor Inspection Report 05000245/2023001
IR 05000336/20230102023-09-0808 September 2023
Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010
IR 05000336/20230052023-08-31031 August 2023
Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005)
ML23248A2132023-08-30030 August 2023
Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature.
ML23242A0142023-08-30030 August 2023
Operator Licensing Examination Approval
ML23223A0552023-08-18018 August 2023
Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel
ML23223A0482023-08-18018 August 2023
Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits
IR 05000336/20230022023-08-0909 August 2023
Integrated Inspection Report 05000336/2023002 and 05000423/2023002
ML23188A0432023-07-31031 July 2023
Authorization and Safety Evaluation for Alternative Request No. IR-04-11
ML23208A0922023-07-26026 July 2023
Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response
ML23188A0202023-07-26026 July 2023
Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML23207A1102023-07-26026 July 2023
NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
IR 05000336/20234012023-07-17017 July 2023
Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only)
ML23175A0052023-07-12012 July 2023
Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps
ML23193A8562023-06-28028 June 2023
Submittal of Updates to the Final Safety Analysis Reports
ML23178A1682023-06-26026 June 2023
2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46
ML23153A1732023-06-16016 June 2023
Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement
ML23151A0742023-06-12012 June 2023
Review of the Spring 2022 Steam Generator Tube Inspection Report
ML23159A2202023-06-0808 June 2023
Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes
IR 07200047/20234012023-06-0808 June 2023
NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401
2024-01-04
[Table view]
Category:Technical Specifications
MONTHYEARML23341A0172024-01-12012 January 2024
Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures
ML23072A0892023-05-0101 May 2023
(Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements
ML21280A3282021-10-0707 October 2021
Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions
ML20275A0002020-10-14014 October 2020
Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections
ML20237H9952020-09-29029 September 2020
Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program
ML20261H5982020-09-17017 September 2020
Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation
ML20191A0042020-08-0707 August 2020
Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity
ML19126A0002019-05-28028 May 2019
Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage
ML19042A2772019-03-21021 March 2019
Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels
ML18100A0552018-04-0404 April 2018
License Amendment Request to Revise Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels
ML17038A0062017-02-0101 February 2017
Technical Specifications 2016 Annual Report
ML17025A2182017-01-24024 January 2017
Issuance of Amendment Realistic Large Break Loss-of-Coolant Accident Analysis
ML16354A4242016-12-14014 December 2016
License Amendment Request to Revise Technical Specification Surveillance Requirement 4.1.3.1.2 for Control Element Assembly 39 for the Remainder of Cycle 24
ML16208A0512016-07-26026 July 2016
Clean Technical Specifications (TS) Pages for Millstone Power Station 1 (Docket No. 05000245), Administrative Changes for TS (L53121)
ML16068A3122016-03-31031 March 2016
Issuance of Amendment No. 326 to Revise Technical Specifications for Containment Leak Rate Testing
ML16011A4002016-01-29029 January 2016
Issuance of Amendments Nos. 325 and 267 to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation
ML15288A0042015-11-30030 November 2015
Issuance of Amendment No. 266: Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times
ML15280A2422015-10-29029 October 2015
Issuance of Amendment No. 324 Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, Adoption of TSTF-425,Rev 3
ML15245A4822015-10-0707 October 2015
Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses
ML15225A0102015-08-28028 August 2015
Issuance of Amendment No. 264 Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves
ML15225A0082015-08-26026 August 2015
Issuance of Amendment No. 322 Revision to the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds
ML15187A3262015-07-29029 July 2015
Issuance of Amendment No. 321, Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C
ML15187A1862015-07-28028 July 2015
Issuance of Amendment No. 263, Regarding Technical Specification Changes to Auxiliary Feedwater System (MF4692)
ML15187A0112015-07-27027 July 2015
Issuance of Amendment No. 262, Refueling Water Storage Tank Allowable Temperatures
ML15209A7292015-07-21021 July 2015
Response to Second Request for Additional Information Regarding Proposed Technical Specification Change for Spent Fuel Storage
ML15098A0342015-05-20020 May 2015
Issuance of Amendment No. 261, Delete Technical Specification Index and Make Other Editorial and Administrative Changes
ML15093A0022015-05-20020 May 2015
Issuance of Amendment No. 320, Delete Technical Specification Index and Make Other Editorial and Administrative Changes
ML15093A4412015-05-18018 May 2015
Issuance of Amendment No. 319, Use of Areva M5 Alloy Clad Fuel Assemblies
ML15044A0442015-02-0909 February 2015
Revised Response to Request for Additional Information Regarding License Amendment Request for Proposed Technical Specification Changes of the Refueling Water Storage Tank Allowable Temperatures
ML15021A1282015-01-15015 January 2015
Proposed License Amendment Requests to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation
ML14301A1122014-10-22022 October 2014
License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3
ML14154A0912014-05-28028 May 2014
Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink.
ML14073A0552014-04-0808 April 2014
Issuance of Amendment Calculated Containment Internal Pressure
ML13346A7672013-12-18018 December 2013
Correction Letter to License Amendment Nos. 256 and 257
ML13155A1402013-05-28028 May 2013
Response to Request for Additional Information Regarding Proposed Technical Specifications Changes for Spent Fuel Storage
ML13133A0322013-05-0303 May 2013
License Amendment Request for Changes to Technical Specification 3/4.7.5 Ultimate Heat Sink.
ML13133A0332013-05-0303 May 2013
License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink.
ML12284A2132012-10-0404 October 2012
License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3
ML12250A6642012-08-28028 August 2012
Correction to Proposed Technical Specifications to Adopt TSTF-510
ML12220A0122012-07-31031 July 2012
Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
ML12219A0732012-07-31031 July 2012
Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
ML12202A0402012-07-17017 July 2012
License Amendment Request Regarding Removal of a License Condition, Proposed Technical Specifications Bases Change and FSAR Change for Ultimate Heat Sink Temperature Measurement
ML12110A1142012-04-12012 April 2012
License Amendment Request for Permanent Alternate Repair Criteria for Steam Generator Tube Inspection and Repair
ML12097A2002012-04-0202 April 2012
License Amendment Request to Revise Snubber Surveillance Requirements
ML12032A2242012-01-25025 January 2012
License Amendment Request to Relocate TS Surveillance Frequencies to License Controlled Program in Accordance with TSTF-425, Revision 3
ML11329A0032011-11-17017 November 2011
Proposed License Amendment and Exemption Request for Use of Optimized Zirlo Rod Cladding
ML11193A2242011-07-0505 July 2011
License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 3 Through Attachment 6, Marked-up TS Pages and TS Bases Pages
ML11193A2232011-07-0505 July 2011
License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 1 Through Attachment 3, Marked-up TS Page Changes 3/4 6-22
ML1102802082011-01-20020 January 2011
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 Temporary Alternate Repair Criteria (H*)
ML1022400642010-07-21021 July 2010
License Amendment Request to Revise Technical Specification 3/4.9.3.1, Decay Time
2024-01-12
[Table view] |
Text
February 26, 2004 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 - CORRECTION TO TECHNICAL SPECIFICATIONS PAGES 3/4 8-23 THROUGH 3/4 8-37
Dear Mr. Christian:
During the comparison review of the U.S. Nuclear Regulatory Commission (NRC) Technical Specification (TS) Authority File to a copy of the Millstone Power Station, Unit No. 3 TSs provided by your staff, it was identified that pages 3/4 8-23 through 3/4 8-37 were deleted from your TSs but were still included in the NRC Authority File.
By application dated July 24, 1990, you had requested the deletion of pages 3/4 8-24 through 3/4 8-37 because previous text is being moved forward and pages which were left intentionally blank were being removed. Amendment No. 64, dated March 9, 1992, was issued to address this application and moved TS 3.8.4.2.1 from page 3/4 8-28 to 3/4 8-21, TS 3.8.4.2.2 from page 3/4 8-32 to 3/4 8-22, and TS 3.8.4.3 from page 3/4 8-37 to 3/4 8-23; however it did not discuss the removal of pages 3/4 8-24 through 3/4 8-37. Page 3/4 8-23 was subsequently removed by Amendment No. 121, dated November 29, 1995.
This letter is issued to provide a record for the removal of pages 3/4 8-24 through 3/4 8-37. It is understood that the Millstone Power Station, Unit No. 3 TSs already indicated that these pages have been removed. We apologize for any inconvenience this may have caused.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423 cc w/encls: See next page
Millstone Power Station Unit 3 cc:
Lillilan M. Cuoco, Esquire Senior Resident Inspector Senior Counsel Millstone Power Station Dominion Resources Services, Inc. c/o U.S. Nuclear Regulatory Commission Rope Ferry Road P. O. Box 513 Waterford, CT 06385 Niantic, CT 06357 Edward L. Wilds, Jr., Ph.D. Mr. G. D. Hicks Director, Division of Radiation Director - Nuclear Station Safety Department of Environmental Protection and Licensing 79 Elm Street Dominion Nuclear Connecticut, Inc.
Hartford, CT 06106-5127 Rope Ferry Road Waterford, CT 06385 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Ms. Nancy Burton 475 Allendale Road 147 Cross Highway King of Prussia, PA 19406 Redding Ridge, CT 00870 First Selectmen Mr. William D. Meinert Town of Waterford Nuclear Engineer 15 Rope Ferry Road Massachusetts Municipal Wholesale Waterford, CT 06385 Electric Company Moody Street Mr. P. J. Parulis P.O. Box 426 Manager - Nuclear Oversight Ludlow, MA 01056 Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Mr. J. Alan Price Waterford, CT 06385 Site Vice President Dominion Nuclear Connecticut, Inc.
Mr. W. R. Matthews Rope Ferry Road Senior Vice President - Nuclear Operations Waterford, CT 06385 Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Mr. Chris Funderburk Waterford, CT 06385 Director, Nuclear Licensing and Operations Support Mr. John Markowicz Dominion Resources Services, Inc.
Co-Chair 5000 Dominion Boulevard Nuclear Energy Advisory Council Glen Allen, VA 23060-6711 9 Susan Terrace Waterford, CT 06385 Mr. David W. Dodson Licensing Supervisor Mr. Evan W. Woollacott Dominion Nuclear Connecticut, Inc.
Co-Chair Rope Ferry Road Nuclear Energy Advisory Council Waterford, CT 06385 128 Terrys Plain Road Simsbury, CT 06070
Millstone Power Station Unit 3 cc:
Mr. S. E. Scace Assistant to the Site Vice President Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. M. J. Wilson Manager - Nuclear Training Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. A. J. Jordan, Jr.
Director - Nuclear Engineering Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. S. P. Sarver Director - Nuclear Station Operations and Maintenance Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
February 26, 2004 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 - CORRECTION TO TECHNICAL SPECIFICATIONS PAGES 3/4 8-23 THROUGH 3/4 8-37
Dear Mr. Christian:
During the comparison review of the U.S. Nuclear Regulatory Commission (NRC) Technical Specification (TS) Authority File to a copy of the Millstone Power Station, Unit No. 3 TSs provided by your staff, it was identified that pages 3/4 8-23 through 3/4 8-37 were deleted from your TSs but were still included in the NRC Authority File.
By application dated July 24, 1990, you had requested the deletion of pages 3/4 8-24 through 3/4 8-37 because previous text is being moved forward and pages which were left intentionally blank were being removed. Amendment No. 64, dated March 9, 1992, was issued to address this application and moved TS 3.8.4.2.1 from page 3/4 8-28 to 3/4 8-21, TS 3.8.4.2.2 from page 3/4 8-32 to 3/4 8-22, and TS 3.8.4.3 from page 3/4 8-37 to 3/4 8-23; however it did not discuss the removal of pages 3/4 8-24 through 3/4 8-37. Page 3/4 8-23 was subsequently removed by Amendment No. 121, dated November 29, 1995.
This letter is issued to provide a record for the removal of pages 3/4 8-24 through 3/4 8-37. It is understood that the Millstone Power Station, Unit No. 3 TSs already indicated that these pages have been removed. We apologize for any inconvenience this may have caused.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423 cc w/encls: See next page DISTRIBUTION:
PUBLIC OGC PDI-2 R/F VNerses GHill (2)
CRaynor BMcDermott, RI Tech Branch DRoberts ADAMS Accession Numbers: Letter: ML040300171 OFFICE PDI-2/PM PDI-2/LA PDI-2/(A)SC NAME VNerses CRaynor DRoberts DATE 02/17/04 02/17/04 02/18/04 OFFICIAL RECORD COPY
CORRECTIONS TO TECHNICAL SPECIFICATION PAGES BASED ON NRC STAFF REVIEW OF THE LICENSE AUTHORITY FILE FOR MILLSTONE POWER STATION, UNIT 3 DOCKET 50-423 Remove the following pages in the technical specifications.
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