Letter Sequence RAI |
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TAC:ME9733, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B (Approved, Closed) |
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MONTHYEARML12284A2132012-10-0404 October 2012 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 Project stage: Request ML12307A3032012-11-0202 November 2012 Acceptance Review for TS Amendment to Adopt TSTF-425 Project stage: Acceptance Review ML13008A3282013-01-0404 January 2013 Response to Request for Additional Information Regarding Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Project stage: Response to RAI ML13059A3292013-03-0808 March 2013 Second Request for Additional Information to Support Review of Millstone Power Station Unit 3 Amendment Application Regarding Risk Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Control Project stage: RAI ML13113A3442013-04-17017 April 2013 Response to Request for Additional Information Regarding Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Project stage: Response to RAI ML13122A1602013-04-29029 April 2013 Response to Request for Additional Information Regarding Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Project stage: Response to RAI ML13115A0182013-04-30030 April 2013 Summary of the Audit to Support the Review of the Technical Specification Task Force-425 License Amendment Request Project stage: Approval ML13281A8332013-10-0909 October 2013 Request for Additional Information to Support Review of Millstone Power Station Unit 3 Application for Technical Specification Change Regarding Risk Informed Justification for the Relocation of Specific Surveillance Frequency Requirements t Project stage: RAI ML13309A7522013-10-30030 October 2013 Response to Request for Additional Information Regarding Relocation of Specific Surveillance Frequency Requirements to a License Controlled Program Project stage: Response to RAI ML14023A7482014-02-25025 February 2014 Issuance of Amendment Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) Project stage: Approval 2013-10-09
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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 NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 March 8, 2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 MILLSTONE POWER STATION UNIT 3 -SECOND REQUEST FOR ADDITIONAL INFORMATION TO SUPPORT REVIEW OF AMENDMENT APPLICATION REGARDING RISK INFORMED JUSTIFICATION FOR THE RELOCATION OF SPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTS TO LICENSEE CONTROLLED PROGRAM (TAC NO. ME9733)
Dear Mr. Heacock:
The Millstone Power Station Unit 3 submitted a license amendment request to adopt Technical Specification Task Force -425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control-Risk-Informed Technical Specification Task Force (RITSTF) Initiative 5b" (Agencywide Documents Access Management Systems (ADAMS) ML12284A213), dated October 4, 2012. The staff issued a request for additional information (RAI) letter (ADAMS ML12342A380), dated December 18, 2012, and has reviewed the licensee's responses to the RAI provided in a letter (ADAMS ML13008A328), dated January 4,2013. The U.S. Nuclear Regulatory Commission staff's review of the RAI responses has determined that further information is necessary to evaluate the technical adequacy of the licensee's submittal.
The second RAI on the licensee's submittal is provided in the enclosure.
A response to this RAI is requested to be provided within 45 days. If you have any questions regarding this matter, please contact me at 301-415-4125.
Sincerely, James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
As stated cc w/encl: Distribution via Listserv SECOND REQUEST FOR ADDITIONAL INFORMATION RELATED TO AN AMENDMENT TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TREVELLER TSTF-425, REVISION 3, TO RELOCATE SPECIFIC SURVEILLANCE FREQUENCIES TO A LICENSEE CONTROLLED PROGRAM MILLSTONE POWER STATION UNIT 3 DOCKET NO. 50-423 Question 1 The response to Question 5 of the request for additional information (RAI), dated January 4, 2013, discussed a process and noted a procedure.
However, the response is future-looking, and the question is related to what has been done to-date to support the application.
The original question is repeated:
Gap #2. The disposition of this supporting requirements states this is a documentation issue only; however, no discussion is provided on the plant walkdowns and interviews mentioned in the supporting requirement.
Please discuss these walkdowns and interviews which address this supporting requirement (SR). Question 2 The response to Question 6 of the RAI, dated January 4,2013, states that Gap #3 (HR-G5) is based on outdated (circa 2006) talk-through documentation with Operations, and proposes to perform a sensitivity analysis on human error probabilities (HEPs) in lieu of updating operator survey information to support the basis for revised or new human failure events. The license amendment request proposes to use a sensitivity analysis using an a-prior multiple of 10; however, this a-prior approach cannot be known to represent a bounding sensitivity analyses for the HEPs. Therefore, since the last update to the HEPs which considered operator survey information was performed a long time ago, either complete the talk-throughs or provide assurance that the HEPs will be treated in a bounding manner. Question 3 In response to Question 7 of the RAI, dated January 4,2013, it is noted that the MPS3 probabilistic risk assessment (PRA) Internal Flooding notebook states: "Thus, only equipment within the area that may be affected by spray or jet impingement damage are assumed to fail, and there is no propagation to other areas and no damage due to submersion." Provide justification for the assumption that action can be taken such that there is no propagation or submersion.
Enclosure
-2 Question 4 Gap #9 is related to the potential for flood barrier unavailability and flood pathways through floor drain check valves. Please discuss your assessment and the risk significance of the flood barrier unavailability and the floor drain check valves for the application in more detail, as well as planned updates, if necessary, to the flood PRA model based on the assessment.
Question 5 For fire events and external events risk assessment, responses to Questions 10 and 11 of the RAI, dated January 4,2013, state that information from the Millstone Individual Plant Examination of External Events (IPEEE) report will be screened.
In addition, the responses to Questions 10 and 11 of the previous RAI indicate that the IPEEE information will be qualitatively assessed.
- a. Please clarify which methods (e.g., an IPEEE method or other) would be used if a bounding analysis is to be performed for fire events or external events. b. If a bounding analysis is to be performed for fire events or external events, discuss steps of your analysis process which help to ensure the analysis is bounding and considers the current plant configuration and operation Question 6 SR 4.2.4.2 is only performed if >75% power AND one power range channel is inoperable (Frequencies that are related to specific condition) and cannot be relocated to the Surveillance Frequency Control Program (SFCP). Also Table 4.7.1, Secondary Coolant System Specific Activity Sample and Analysis Program, proposes to relocate a "Program Frequency" to the SFCP. This is prohibited because it is a program requirement (Frequencies that reference other approved programs for the specific interval).
And even if they could be relocated, note that 2(a} and (b) are conditional (SR performance is dependent upon on (1) Gross Radioactivity Determination SR results. I had a similar issue with the Oconee TSTF-425 license amendment request where the licensee proposed relocating an Oconee TS Chapter 5 component "test interval," that is located in the Standard Technical Specification (Section 3, Surveillance), to the SFCP. Question 7 The response to Question 13 of the RAI, dated January 4, 2013, is unacceptable.
The Frequency (the "when") can be located in the SFCP -NOT the Surveillance Requirement
("what" is being tested) i.e., "each train shall be tested," This is very clearly identified in the FR Notice for Availability.
The frequency (62 days) and the reference to the staggered test basis can be replaced by "the frequency specified in the Surveillance Frequency Control Program," as the licensee identified in the RAI response.
March 8, 2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut.
Inc. Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 MILLSTONE POWER STATION UNIT 3 -SECOND REQUEST FOR ADDITIONAL INFORMATION TO SUPPORT REVIEW OF AMENDMENT APPLICATION REGARDING RISK INFORMED JUSTIFICATION FOR THE RELOCATION OF SPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTS TO LICENSEE CONTROLLED PROGRAM (TAC NO. ME9733)
Dear Mr. Heacock:
The Millstone Power Station Unit 3 submitted a license amendment request to adoptTechnical Specification Task Force -425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control-Risk-Informed Technical Specification Task Force (RITSTF) Initiative 5b" (Agencywide Documents Access Management Systems (ADAMS) ML12284A213), datedOctober 4,2012. The staff issued a request for additional information (RAI) letter (ADAMSML12342A380), dated December 18,2012 ,and has reviewed the licensee's responses to theRAI provided in a letter (ADAMS ML13008A328), dated January 4, 2013. The U.S. Nuclear Regulatory Commission staff's review of the RAI responses has determined that further information is necessary to evaluatethe technical adequacy of the licensee's submittal.
The second RAI on the licensee's submittal is provided in the enclosure.
A response to this RAI is requested to be provided within45 days. If you have any questions regarding this matter, please contact me at 301415-4125.
Sincerely, I RAJ James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
As stated cc w/encl: Distribution via Listserv Distribution:
PUBLIC RidsNrrLKGoldstein Resource LpLl-1 r/f RidsNrrPMMilistone Resource RidsAcrsAcnw
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3/8/13 2/14/13 OFFICIAL RECORD COpy