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MONTHYEARML0415604642004-05-27027 May 2004 Proposed Technical Specification Changes Implementation of Alternate Source Term Project stage: Other ML0423304632004-08-20020 August 2004 Facsimile Transmission, Draft RAI to Be Discussed in an Upcoming Conference Call Project stage: Draft RAI ML0426602502004-09-22022 September 2004 Facsimile Transmission, Draft Request for Additional Information (RAI) to Be Discussed in an Upcoming Conference Call Project stage: Draft RAI ML0435100392004-12-29029 December 2004 Request for Additional Information Regarding Use of Alternate Source Term Project stage: RAI ML0500402642005-02-0909 February 2005 RAI, Use of Alternate Source Term Project stage: RAI ML0515400932005-04-25025 April 2005 Summary of Meeting with Dominion Nuclear Connecticut, Inc.,Surry & North Anna, Units 1 & 2, & Millstone, Units 2 & 3, Discuss Current Licensing Issues with Dominion. Enclosure 3 - Top Ten Millstone Licensing Tasks Project stage: Meeting ML0530704822005-11-18018 November 2005 RAI Regarding Use of Alternate Source Term Project stage: RAI ML0619901352006-09-15015 September 2006 Issuance of Amendment Alternate Source Term Project stage: Approval 2004-09-22
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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:Request for Additional Information (RAI)
MONTHYEARML23318A0952023-11-14014 November 2023 Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel ML23199A2832023-07-18018 July 2023 Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23089A1882023-03-29029 March 2023 Request for Additional Information (E-mail Dated 3/29/2023) Spring 2022 Steam Generator Tube Inspection Report ML23073A1802023-03-14014 March 2023 Notification of Commercial Grade Dedication Inspection (05000336/2023010 and 05000423/2023010) and Request for Information ML22251A1292022-09-0909 September 2022 Request for Additional Information Related to Response to Generic Letter 2004-04 ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) ML21225A5022021-08-13013 August 2021 Request for Additional Information for North Anna Power Station, Units 1 and 2, Surry Power Station, Units 1 and 2, and Millstone Power Station, Units 2 and 3, Appendix E of Fleet Report Com-Naf-2 (EPID:L02021-LLT-0000) Public Version ML21195A2442021-07-13013 July 2021 NRR E-mail Capture - Draft RAI Appendix E to Topical Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21182A2902021-07-0101 July 2021 7/1/2021 E-mail - Request for Additional Information Alternative Frequency to Supplemental Valve Position Verification Testing Requirements ML21112A3082021-04-22022 April 2021 Request for Additional Information (E-mail Dated 4/22/2021) License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML21105A1152021-04-15015 April 2021 Request for Additional Information (e-mail Dated 4/15/2021) Proposed LAR for Addition of Analytical Methodology to the Core Operating Limits Report for a LBLOCA ML21078A0332021-03-18018 March 2021 NRR E-mail Capture - Millstone Power Station, Unit 2 - Request for Additional Information - Proposed LAR to Revise TSs for Steam Generator Inspection Frequency ML21076A4622021-03-17017 March 2021 NRR E-mail Capture - Draft RAI for Versatile Internals and Component Program for Reactors Vipre Code Review (L-2021-LLT-0000) ML21077A1652021-02-26026 February 2021 (02/26/2021 E-mail) Draft Request for Additional Information LAR to Revise Technical Specifications for Steam Generator Inspection Frequency ML21034A5762021-02-0303 February 2021 Request for Additional Information (e-mail Dated 1/3/2021) Alternative Request RR-05-06 Inservice Inspection Interval Extension for Steam Generator Weld Inspections ML20246G5612020-09-0202 September 2020 Request for Additional Information (E-mail Dated 9/2/2020) License Amendment Request for a One-Time Deferral of the Steam Generator Inspections ML20244A2902020-08-31031 August 2020 Request for Additional Information (E-mail Dated 8/31/2020) License Amendment Request to Revise Battery Surveillance Requirements ML20231A7172020-08-18018 August 2020 Request for Additional Information (e-mail Dated 8/18/2020) License Amendment Request to Revise TS Table 3.3-11 Accident Monitoring Instrumentation ML20184A0052020-07-0202 July 2020 Request for Additional Information (E-mail Dated 7/2/2020) Relief Request IR-3-33 for Limited Coverage Examiniations ML20075A0322020-03-15015 March 2020 Request for Additional Information (E-mail Dated 3/15/2020) Alternative Request IR-4-03 for Use of an Alternative Non-Code Methodology to Demonstrate Structural Integrity ML20050F9212020-02-19019 February 2020 Request for Additional Information (E-mail Dated 2/19/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating ML20023D0372020-01-23023 January 2020 Request for Additional Information (E-mail Dated 1/23/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating ML19361A0382019-12-23023 December 2019 12/23/19 E-mail from R.Guzman to S. Sinha - Draft Request for Additional Information Planned Audit of LAR to Revise TS 3.8.1.1 ML19277B9082019-10-0707 October 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time ML19248D7552019-09-0505 September 2019 Request for Additional Information Via E-mail from R.Guzman to S. Sinha Proposed License Amendment Request to Adopt 10 CFR 50.69 ML19169A0962019-06-17017 June 2019 NRR E-mail Capture - Request for Additional Information Emergency Action Level Scheme Change for Millstone Power Station - Units 1, 2, and 3, North Anna Power Station - Units 1 and 2, and Surry Power Station - Units 1 and 2 ML19162A0052019-06-10010 June 2019 NRR E-mail Capture - Draft RAIs for Dominion EAL Scheme Change ML19042A1822019-02-11011 February 2019 Request for Additional Information LAR for TS Changes to Spent Fuel Storage and New Fuel Storage, 02/11/2019 E-mail from R. Guzman to S. Sinha ML18291B3262018-10-18018 October 2018 Request for Additional Information LAR Regarding Proposed Technical Specification Changes for Spent Fuel Pool Storage and New Fuel Storage, E-mail from R.Guzman to S.Sinha ML18277A1762018-10-0404 October 2018 Request for Additional Information LAR to Revise TS Action Statement for Loss of Control Building Inlet Ventilation Rad Monitor Instrumentation Channels (e-mail from R.Guzman to M.Whitlock, EPID: L-2018-LLA-0099) ML18213A1152018-08-0101 August 2018 Request for Additional Information Alternative Request P-06 'C' Charging Pump (08/01/2018 E-mail from R. Guzman to M. Whitlock) ML18171A1532018-06-20020 June 2018 Request for Additional Information Via E-mail from R.Guzman to W.Craft Alternative Requests for Inservice Testing Program (E-mail from R.Guzman to W.Craft) (EPID: L-2018-LLR-0012-LLR-0022) ML18137A3132018-05-17017 May 2018 Request for Additional Information Via E-mail from R.Guzman to W.Craft Proposed License Amendment Request to Revise ILRT Type a and Type C Test Intervals ML17297A8472017-10-27027 October 2017 Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools (CAC No. MF9430; EPID L-2016-LRC-0001) ML17033B6142017-02-0202 February 2017 Request for Additional Information, 2017/02/02 E-mail from R.Guzman to W.Craft Proposed Alternative RR-04-24 and IR-3-30 for the Elimination of Reactor Pressure Vessel Threads in Flange Examination (CAC Nos. MF8468/MF8469) ML17005A3282017-01-0505 January 2017 MPS2 EOC-23 and MPS3 EOC-17 Steam Generator Tube Inspection Reports - Requests for Additional Information ML16260A0062016-09-16016 September 2016 2016/09/16 E-mail from R. Guzman to W. Craft Request for Additional Information - License Amendment Request Realistic Large Break Loss of Coolant Accident Analysis (MF7761) ML16267A0022016-09-12012 September 2016 2016/09/12 E-mail from R.Guzman to W.Craft Request for Additional Information - LAR to Revise ECCS TS and FSAR Ch. 14 to Remove Charging (MF7297) ML16133A3562016-05-12012 May 2016 E-mail from R. Guzman to C. Sly Request for Additional Information Supporting License Amendment Request to Remove Charging Credit ML16068A4142016-03-0808 March 2016 Request for Additional Information - Relief Request RR-04-19 Examination Cat R-A, Risk-Informed Piping Examinations (MF6569) ML16055A5302016-02-24024 February 2016 2016/02/24 E-mail from R.Guzman to W.Craft Request for Additional Information - LAR to Adopt Dominion Core Design and Safety Analysis Methods (MF6251) ML16047A1712016-02-16016 February 2016 2016/02/16 E-mail from R.Guzman to M. Whitlock Request for Additional Information - Small Break Loss of Coolant Accident Re-Analysis (MF6700) ML16043A5232016-02-12012 February 2016 Request for Additional Information 2016/02/12 E-mail from R. Guzman to M.Whitlock Relief Requests IR-3-22 and IR-3-23 (CAC Nos. MF6573 and MF6574) ML16013A4772016-01-13013 January 2016 NRR E-mail Capture - Millstone Power Station, Units 2 and 3 - Request for Additional Information License Amendment Request for Removal of Severe Line Outage Detection (Slod) from the Offsite Power System - (MF6430, MF6431) ML16011A5172016-01-11011 January 2016 NRR E-mail Capture - Millstone Power Station, Unit 3, Reactor Vessel Surveillance Capsule Withdrawal Schedule - Request for Additional Information ML15349A8312016-01-0808 January 2016 Request for Additional Information License Amendment Request to Adopt Dominion Core Design and Safety Analysis Methods ML15337A1512015-12-0303 December 2015 NRR Email Capture - Millstone Unit 2 Request for Additional Information ML15279A1092015-10-0606 October 2015 NRR e-mail Capture - Millstone Power Station, Unit 3, NRC Staff Request for Additional Information - Relief Request Nos. IR-3-19,3-20,3-21 ML15275A1432015-10-0202 October 2015 2015/10/02 E-mail from R.Guzman to W.Craft - Follow-up Request for Additional Information TSTF-523, Revision 2, GL 2008-01, Managing Gas Accumulation 2023-07-18
[Table view] |
Text
December 29, 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 - REQUEST FOR ADDITIONAL INFORMATION REGARDING USE OF ALTERNATE SOURCE TERM (TAC NO.
MC3333)
Dear Mr. Christian:
By letter dated May 27, 2004, you requested an amendment to the technical specifications for the Millstone Power Station, Unit No. 3. The proposed amendment would allow the use of an alternate source term.
The Nuclear Regulatory Commission staff has determined that the enclosed questions must be addressed before we can complete our review. These questions were forwarded electronically to Mr. Paul Willoughby of your staff on December 6, 2004. Additionally, they were discussed in a telephone call with Mr. Willoughby and other members of your staff on December 14, 2004. I understand that you intend to respond to this request for additional information within 30 days of the date of this letter. If you have any questions, I can be reached at (301) 415-1494.
Sincerely,
/RA/
George F. Wunder, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423 cc: See next page
Enclosure:
Request for Additional Information
REQUEST FOR ADDITIONAL INFORMATION MILLSTONE POWER STATION, UNIT NO. 3 USE OF ALTERNATE SOURCE TERM Regulatory Guide (RG) 1.52 establishes the criterion for penetration in the laboratory testing of engineered safety feature filter systems. In Revision 2 of RG 1.52, the allowable penetration for a 2-inch bed filter is less than 1 percent. In Revision 3 of RG 1.52, some relaxation was allowed and the penetration criterion for a 2-inch bed during a laboratory test was increased to less than 2.5 percent, based in part on maintaining a safety factor of 2. The current Millstone Power Station, Unit No. 3 technical specification (TS) for the control room emergency ventilation filter allows 2.5 percent penetration and is in compliance with RG 1.52, Revision 3.
The submittal requests a TS surveillance change to allow a 5-percent penetration test criteria.
The Nuclear Regulatory Commission staff does not have sufficient information on filter performance for test penetration criteria lower than specified in your existing TSs.
The fact that lower filter efficiencies were assumed in the design basis analysis does not necessarily support reducing filter efficiency test requirements. The surveillance requirement is based on system parameters for a 2-inch deep filter considering residence time and other parameters using clean carbon adsorbers.
In addition, consideration is given to the change in efficiency over time so that there will be reasonable assurance that the filter will have the required efficiency at the end of the test interval, as well as at the beginning of the test interval. Performance of carbon adsorbers at other efficiencies as a result of depletion of adsorber sites over the time of the test interval have not been evaluated. Please justify the acceptability of reducing the testing criteria in your existing TS.
Enclosure
Millstone Power Station, Unit No. 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 Terry's Plain Road Simsbury, CT 06070
Millstone Power Station, Unit No. 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
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 - REQUEST FOR ADDITIONAL INFORMATION REGARDING USE OF ALTERNATE SOURCE TERM (TAC NO.
MC3333)
Dear Mr. Christian:
By letter dated May 27, 2004, you requested an amendment to the technical specifications for the Millstone Power Station, Unit No. 3. The proposed amendment would allow the use of an alternate source term.
The Nuclear Regulatory Commission staff has determined that the enclosed questions must be addressed before we can complete our review. These questions were forwarded electronically to Mr. Paul Willoughby of your staff on December 6, 2004. Additionally, they were discussed in a telephone call with Mr. Willoughby and other members of your staff on December 14, 2004. I understand that you intend to respond to this request for additional information within 30 days of the date of this letter. If you have any questions, I can be reached at (301) 415-1494.
Sincerely,
/RA/
George F. Wunder, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423 cc: See next page
Enclosure:
Request for Additional Information DISTRIBUTION:
PUBLIC CRaynor ACRS PDI-2 R/F GWunder GMatakas DRoberts OGC DLPM DPR ADAMS Accession Number: ML043510039 OFFICE PDI-2/PM PDI-2/LA PDI-2/SC NAME GWunder CRaynor DCollins for DRoberts DATE 12/28/04 12/27/04 12/29/04 OFFICIAL RECORD COPY