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MONTHYEARML0226207122002-09-23023 September 2002 Facsimile Transmission, Issues to Be Discussed in an Upcoming Conference Call Project stage: Other ML0312005372003-04-17017 April 2003 Request for Additional Information: Licensing Basis Document Change Request 2-12-02, Unit 2 Technical Specification Change - Operation with Main Steam Line Code Safety Valves Inoperable Project stage: Request ML0312805212003-05-0707 May 2003 Technical Specification Pages to Amendment 275, Millstone Power Station, Unit 2 Project stage: Other ML0309903402003-05-0707 May 2003 Issuance of Amendment No. 275, Revising Technical Specification 3.7.1.1, to Reflect Results of a Reanalysis of Overpressurization Events to Allow Plant Operation, at Corresponding Reduced Power Levels as Listed Project stage: Approval 2003-04-17
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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
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I - 7 Dominion Nudear Connecticut, Inc.
Millstone Power Station W-Dominion-Rope Ferry Road Waterford, CT 06385 t ,
- ', Of: ; :
.. , I APR I 7 2003 Docket No. 50-336 B18881 RE: 10 CFR 50.90 U.S. Nuclear Regulatory Cbrhmissiton .
Attention: Document Control Desk -. -
Washington, DC 20555 Millstone Power Station, Unit No. 2 Request for Additional Information: Licensing Basis Document Change Request 2-12-02, Unit No. 2 Technical Specification Change - Operation With Main Steam Line Code Safety Valves Inoperable (TAC NO. MB5799)
In a letter dated August 1, 2002('), Dominion Nuclear Connecticut, Inc. (DNC) proposed changes to the Millstone Unit No. 2 Technical Specifications relating to the Main Steam Line Code Safety Valves technical specifications. On September 19, 2002(2), a request for additional information (RAI) was received from the NRC. On October 18, 2002(3),
DNC provided a response to the September 19, 2002 RAI. During a conference call on April 2, 2003, the NRC indicated that a clarification is required for the response to Question (3) included in our submittal dated October 18, 2002.
The purpose of this submittal is to clarify the response to Question 3 of the October 18, 2002 submittal.
The original response to Question 3 states in part:
"Based on the above results it has been concluded that plant operation in accordance with the proposed Technical Specification Table 3.7.1 power levels will assure that pressure relief capacities are sufficient to limit the primary and (1) J. A. Price letter to U.S. NRC, "Millstone Power Station, Unit No. 2, Licensing Basis Document Change Request 2-12-02, Unit No. 2 Technical Specification Change -
Operation With Main Steam Line Code Safety Valves Inoperable," dated August 1, 2002.
(2) Facsimile from R. Ennis, U.S. NRC to R. Joshi, DNC, Inc., "Issues for Discussion in Upcoming Telephone Conference Regarding Proposed Amendment to Technical Specifications, Operation with Main Steam Line Code Safety Valves Inoperable," dated September 19, 2002.
(3) J. A. Price letter to U.S. NRC, "Millstone Power Station, Unit No. 2, Request for Additional Information: Licensing Basis Document Change Request 2-12-02, Unit No. 2 Technical Specification Change Operation with Main Steam Line Code Safety Valves Inoperable,"
dated October 18, 2002.
U.S. Nuclear Regulatory Commission B18881/Page 2 secondary system pressures to less than 110% of their design limits of 2750 and 1100 psia respectively."
The revised response is as follows:
"Based on the above results it has been concluded that plant operation in accordance with the proposed Technical Specification Table 3.7.1 power levels will assure that pressure relief capacities are sufficient to limit the primary system pressures to less than 110% of the plant design limit (Design Limit is 2500 psia) and the secondary system pressure to less than 110% of the Chapter 14 analyses limit of 1000 psia. It should be noted that the Chapter 14 analyses limit is more conservative than the secondary plant component and piping design limit of 1000 psig."
The clarification provided above will not affect the conclusions of the Safety Summary and Significant Hazards Consideration discussion provided in the DNC August 1, 2002 submittal.
There are no regulatory commitments contained within this letter.
If you should have any questions on the above, please contact Mr. Ravi Joshi at (860) 440-2080.
Very truly yours, DOMINION NUCLEAR CONNECTICUT, INC.
J. a Price Sit ice President - Millstone Subscribed and sworn to before me this I day of f , 2003.
N aryp My Commission Expires:)//
cc: See next page Lorrie AArzamarski Notary Public Commission Expires February 28, 2006
-Uv U.S. Nuclear Regulatory Commission B1 8881/Page 3 cc: H. J. Miller, Region 1 Administrator R. B. Ennis, NRC Senior Project Manager, Millstone Unit No. 2 Millstone Senior Resident Inspector Director Bureau of Air Management Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127