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MONTHYEARML13133A0322013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.5 Ultimate Heat Sink. Project stage: Request ML13170A4772013-06-26026 June 2013 Millstone Power Station, Unit Nos. 2 and 3 - Acceptance Review Results Regarding Ultimate Heat Sink License Amendment Request (TAC Nos. MF1779 and MF1780) Project stage: Acceptance Review ML13192A2402013-07-30030 July 2013 Acceptance Review Results Regarding Ultimate Heat Sink License Amendment Requests Project stage: Acceptance Review ML13347B0932013-12-19019 December 2013 Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.7.5 Ultimate Heat Sink Project stage: RAI ML14023A6462014-01-15015 January 2014 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink. Project stage: Response to RAI ML14139A1002014-05-19019 May 2014 LAR Ultimate Heat Sink Project stage: Other 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. Project stage: Response to RAI ML14178A5992014-07-11011 July 2014 Issuance of Amendment Proposed Changes to Technical Specification 3/4 7.5, Ultimate Heat Sink (Tac MF1780) Project stage: Approval 2013-07-30
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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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. lnnsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 December 19, 2013 SUBJECT: MILLSTONE POWER STATION, UNIT 3-REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3/4.7.5 "ULTIMATE HEAT SINK" (TAC NO. MF1780) Dear Mr. Heacock: By letter dated May 3, 2013 (Agencywide Documents Access and Management System Accession No. ML 13133A032), Dominion Nuclear Connecticut, Inc. (the licensee), submitted a License Amendment Request to revise Technical Specification 3/4.7.5, Ultimate Heat Sink. The U.S. Nuclear Regulatory Commission staff has reviewed the information provided by the licensee and has determined that the enclosed request for additional information (RAI) is needed in order to complete the review. A response to this RAI is requested to be provided by January 31, 2014. If you have any questions regarding this matter, please contact me at 301-415-4125. Docket No. 50-423 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST PROPOSED TECHNICAL SPECIFICATIONS AND BASES AMENDMENT TS AND BASES 3/4.7.5, ULTIMATE HEAT SINK MILLSTONE POWER STATION, UNIT 3 DOCKET NUMBER 50-423 1. Vendor data sheet [Figure 6 of Millstone Power Station, Unit 3 (MPS3) letter dated July 2, 2013] for recirculation spray heat exchangers (3RSS*E1A, E1 B, E1 C, E1 D) specifies approximate service water flow of 6500 GPM at 75°F for a heat load of 184,534,533 BTU/Hr. But Table 5.2 of MPS3 letter dated May 3, 2013 lists a minimum flow of 5400 GPM at 80°F. a.) Explain why the licensee's minimum required flow is significantly less than the vendor sheet specified flow for the same heat removal duty. b.) Explain why the flow rates specified in Table 5.2 for the recirculation spray heat exchangers (3RSS*E 1 A, E 1 B, E 1 C, E 1 D) are identical for both the 75°F and 80°F analyses of record. 2. Table 5.2 of the MPS3 letter dated May 3, 2013 lists calculated minimum available flow for all the safety related heat exchangers cooled by Service Water (SW). In order to provide validity to the proposed increase in SW temperature to 80°F, calculated flow rates from the SW model should match actual flow rates as determined by measurement in the field. a.) Describe the accuracy of calculated SW flow values provided in Table 5.2 as compared to field measured testing of flow rates and provide justification that the calculated flow rates are valid. b.) Provide assurance that calculated flow rates are accurate for the various SW lineups including the "DBA COINCIDENT WITH LOSS OF OFFSITE POWER" and "LOSS OF POWER WITH TRAIN FAILURE" lineups as specified in Table 9.2-2 of the Final Safety Analysis Report (FSAR) by comparing calculated values to measured values in the field. 3. MPS3 letter dated May 3, 2013, paragraphs 5.3.2.4 and 5.3.2.5, for the Residual Heat Removal Pump Ventilation Units and the Containment Recirculation Pump Cubicle Ventilation Units, respectively, and Table 5.2 list identical required minimum flow rates for 75°F and 80°F SW temperatures. The stated reason is the limit was based on "downstream piping analysis temperature limitation. Re-evaluation of the piping system Enclosure
-2 -at an increased outlet temperature has increased this limitation such that the required flow is unchanged from the 75°F Analysis Of Record." Explain the downstream temperature limitation and how this limitation was increased for the 80°F analysis. 4. Tables in the MPS3 letter dated July 2, 2013, for ESF Air Conditioning Unit Heat Exchangers 3HVQ*ACUS1A, 1 B, 2A and 2B list Figure 4 as the vendor data sheet. The vendor data sheet shows a SW flow rate of approximately 65 GPM at 80°F for a heat load of 510,000 BTU/hr. The tables in the July 2 letter list design heat loads of 360,600 BTU/hr and 396,400 BTU/hr with required minimum SW flow rates of 25 GPM and 33.2 GPM respectively, for these heat exchangers. Using a linear heat transfer relationship on the water side of the heat exchangers, the listed flow rates of 25 GPM and 33.2 GPM are much lower than flow rates needed for transfer of 360,600 BTU/hr and 396,400 BTU/hr, since 65 GPM at 80°F is needed to absorb 510,00 BTU/hr. Please explain the seeming inconsistency. 5. Vendor data sheet (Figures 2(a) and 2(b) of MPS3 letter dated July 2, 2013) for the emergency diesel generator heat exchangers (3EGS*E 1 A, E 1 B, E2A, E2B) specify SW flow of 1900 GPM at 80°F. But Table 5.2 of MPS letter dated May 3, 20131ists a minimum flow of 1444 GPM at 80°F. Explain and justify why the licensee's minimum required SW flow is significantly less than the vendor sheet specified flow for similar heat load removal duty. 6. Paragraph 5.3.2.8 titled "EDG Heat Exchangers (3EGS*E1AIB and 3EGS*E2AIB)," states that the analysis of record was performed using an overly conservative heat load assumption and that when the calculation was revised for an Ultimate Heat Sink (UHS) temperature of 80°F using the design basis heat load, the minimum required flow rate did not change from the calculation performed at 75°F. Describe the aforementioned overly conservative heat load assumption and justify the assumption(s) used in its place. 7. The list of regulatory commitments in Attachment 4 of the May 3, 2013 letter list calculations/analysis [Commitment numbers 4, 7, 8, 9, 10, 11, and 13] that the licensee plans to complete upon implementation of the NRC approved License Amendment Request (LAR). The NRC cannot approve an LAR unless all pertinent safety related calculations/analysis are complete in accordance with the licensee's approved quality assurance program that meets the requirements of 10 CFR 50 Appendix B. The licensee is requested to complete all calculations/analysis associated with the commitments listed above and report the status of completion of those items and any
-3 -effect of the completed calculations/analysis on the LAR to the NRC before NRC staff approval of the LAR. 8. The vendor data sheet for the Reactor Plant Closed Cooling Water (RPCCW) heat exchangers (Figure 1 of the July 2, 2013 letter) show that the heat exchanger's capability is 76 E+6 BTU/hr with a SW flow rate of 4,000,000 lb/hr (8000GPM) at 75°F. This does not apparently correlate with the information provided in Enclosure 2 page 1 of the July 2, 2013 letter which shows a design heat load of 117.8 E+6 Btu/hr. Neither data sheet correlate with the heat transfer requirements listed in Table 9.2-2 of the FSAR. The licensee is requested to explain the seeming lack of agreement in the above listed documents and justify the proposed UHS/SW temperature limit of 80°F for the RPCCW heat exchangers. 9. Table 5.2 of the MPS3 letter dated May 3, 2013 lists similar minimum SW flow requirements at 75°F and 80°F for the control building air conditioning water chillers (3HVK*CHL 1NB) with no justification given for why the required flow has not increased for 80°F. Provide justification as to why the required SW flow at 80°F has not increased when compared to the required flow for 75°F.
Mr. David A Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. lnnsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 December 19, 2013 SUBJECT: MILLSTONE POWER STATION, UNIT 3-REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3/4.7.5 "ULTIMATE HEAT SINK" (TAC NO. MF1780) Dear Mr. Heacock: By letter dated May 3, 2013 (Agencywide Documents Access and Management System Accession No. ML 13133A032), Dominion Nuclear Connecticut, Inc. (the licensee), submitted a License Amendment Request to revise Technical Specification 3/4.7.5, Ultimate Heat Sink. The U.S. Nuclear Regulatory Commission staff has reviewed the information provided by the licensee and has determined that the enclosed request for additional information (RAI) is needed in order to complete the review. A response to this RAI is requested to be provided by January 31, 2014. If you have any questions regarding this matter, please contact me at 301-415-4125. Docket No. 50-423 Enclosure: Sincerely, Ira/ James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Request for Additional Information cc w/encl: Distribution via Listserv Distribution: PUBLIC RidsAcrsAcnw_MaiiCTR Resource RidsNrrDssSbpb Resource RidsNrrDssSrxb Resource LPLI-1 R/F RidsNrrDoriDpr Resource RidsNrrLKGoldstein Resource RidsRgn1 Mail Center Resource GPurciarello, NRR RidsNrrDorllpl1-1 Resource RidsNrrPMMillstone Resource ADAMS Accession No.: ML13347B093 *via memo dated December 6 2013 ' OFFICE LPL 1-1/PM LPL 1-1/LA DSS/SBPB/BC LPL 1-1/BC LPL1-1/PM NAME JKim KGoldstein GCasto* BBeasley JKim DATE 12/17/13 12/17/13 12/6/13 12/18/13 12/19/13 OFFICIAL RECORD COPY