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| ==Subject:== | | ==Subject:== |
| Millstone Unit 3 - DRAFT Request for Additional Information - License Amendment Request to Revise Battery Surveillance Requirements (EPID: L-2020-LLA-0094) | | Millstone Unit 3 - DRAFT Request for Additional Information - License Amendment Request to Revise Battery Surveillance Requirements (EPID: L-2020-LLA-0094) |
| : Shayan, By letter dated April 30, 2020, (ADAMS Accession No. ML20121A217), Dominion Energy Nuclear Connecticut, Inc., (the licensee), submitted a license amendment request to Renewed Facility Operating License No. NPF-49 for Millstone Power Station Unit 3 (MPS3). The proposed changes would revise MPS3 Technical Specifications (TS) Surveillance Requirement (SR) 4.8.2.1.b and 4.8.2.1.c by adding a new acceptance criterion to verify the total battery connection resistance is within pre-established limits to ensure that the intended design functions are met. | | : Shayan, By {{letter dated|date=April 30, 2020|text=letter dated April 30, 2020}}, (ADAMS Accession No. ML20121A217), Dominion Energy Nuclear Connecticut, Inc., (the licensee), submitted a license amendment request to Renewed Facility Operating License No. NPF-49 for Millstone Power Station Unit 3 (MPS3). The proposed changes would revise MPS3 Technical Specifications (TS) Surveillance Requirement (SR) 4.8.2.1.b and 4.8.2.1.c by adding a new acceptance criterion to verify the total battery connection resistance is within pre-established limits to ensure that the intended design functions are met. |
| The NRC staff has determined that additional information is needed to complete its review, as described in the request for additional information (RAI) shown below. This RAI is identified as DRAFT at this time to confirm your understanding of the information needed by the NRC staff to complete its evaluation. If youd like to have a clarification call, please let me know and I will coordinate availabilities w/the NRC technical staff. I intend to send out the questions below as official by August 28th, if possible. | | The NRC staff has determined that additional information is needed to complete its review, as described in the request for additional information (RAI) shown below. This RAI is identified as DRAFT at this time to confirm your understanding of the information needed by the NRC staff to complete its evaluation. If youd like to have a clarification call, please let me know and I will coordinate availabilities w/the NRC technical staff. I intend to send out the questions below as official by August 28th, if possible. |
| : Thanks, | | : Thanks, |
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| REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE BATTERY SURVEILLANCE REQUIREMENTS MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 (EPID: L-2020-LLA-0094) | | REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE BATTERY SURVEILLANCE REQUIREMENTS MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 (EPID: L-2020-LLA-0094) |
| By letter dated April 30, 2020, (Agencywide Documents Access and Management System (ADAMS) | | By {{letter dated|date=April 30, 2020|text=letter dated April 30, 2020}}, (Agencywide Documents Access and Management System (ADAMS) |
| Accession No. ML20121A217), Dominion Energy Nuclear Connecticut, Inc. (the licensee) submitted a license amendment request (LAR) to Renewed Facility Operating License No. NPF-49 for Millstone Power Station Unit 3 (MPS3). The proposed changes would revise MPS3 Technical Specifications (TS) Surveillance Requirement (SR) 4.8.2.1.b and 4.8.2.1.c by adding a new acceptance criterion to verify the total battery connection resistance is within pre-established limits to ensure that the intended design functions are met. | | Accession No. ML20121A217), Dominion Energy Nuclear Connecticut, Inc. (the licensee) submitted a license amendment request (LAR) to Renewed Facility Operating License No. NPF-49 for Millstone Power Station Unit 3 (MPS3). The proposed changes would revise MPS3 Technical Specifications (TS) Surveillance Requirement (SR) 4.8.2.1.b and 4.8.2.1.c by adding a new acceptance criterion to verify the total battery connection resistance is within pre-established limits to ensure that the intended design functions are met. |
| The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in the submittal and has determined that additional information as requested below is needed to complete its review. | | The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in the submittal and has determined that additional information as requested below is needed to complete its review. |
Letter Sequence RAI |
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EPID:L-2020-LLR-0094, Relief Request I4R-23 Associated with Pandemic Related Issues - Examination of Containment Surfaces Requiring Augmented Examination (Category E-C) (Approved, Closed) |
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Category:E-Mail
MONTHYEARML24032A4702024-02-0101 February 2024 Change in Estimated Review Schedule Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC ML24024A0202024-01-24024 January 2024 Correction to Safety Evaluation Associated Wit Amendment No. 288 - Revision to Applicability Term for RCS Heat-Up and Cooldown Pressure-Temperature Limitations Figures ML24024A2452024-01-24024 January 2024 1/24/2024 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in SE for Amendment No. 288 - Revision to Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures ML23326A0132023-11-22022 November 2023 Acceptance Review Determination LAR to Support Implementation of Framatome Gaia Fuel ML23318A0952023-11-14014 November 2023 Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel ML23317A0732023-11-13013 November 2023 Acceptance Review Determination - License Amendment Request Modification of TS SR 4.3.6.a ML23297A2312023-10-24024 October 2023 E-mail to File - Summary of September 13, 2023, Meeting with Dominion to Discuss Proposed LAR to Support Cycle Reloads Using Framatome Gaia Fuel ML23265A2302023-09-22022 September 2023 Acceptance Review Determination - License Amendment Request Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC ML23258A0552023-08-31031 August 2023 Setup of Online Reference Portal and Audit Plan for the NRC Staff'S Review of LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies (08/31/2023 e-mail) ML23199A2832023-07-18018 July 2023 Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits ML23172A0752023-06-21021 June 2023 Acceptance Review Determination LAR to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23145A0052023-05-25025 May 2023 Acceptance Review Determination Exemption to Use Framatome Gaia Fuel Assemblies Containing Fuel Rods Fabricated with M5 Fuel Rod Cladding ML23145A0042023-05-25025 May 2023 Acceptance Review Determination LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies ML23115A3022023-04-24024 April 2023 4/24/2023 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in Issuance of Amendments Adoption of TSTF-359, Increase Flexibility in Mode Restraints ML23089A1882023-03-29029 March 2023 Request for Additional Information (E-mail Dated 3/29/2023) Spring 2022 Steam Generator Tube Inspection Report ML23067A2162023-03-0707 March 2023 NRR E-mail Capture - RAI for North Anna, 1 & 2, Surry 1 & 2, Millstone, 2 & 3, Request for Approval of App. F Fleet Report DOM-NAF-2-P, Qual of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion VIPRE-D Computer Code ML23038A0152023-02-0707 February 2023 Acceptance Review Determination LAR to Revise the Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures ML23024A1522023-01-24024 January 2023 Acceptance Review Determination LAR to Supplement Burnup Credit of Criticality Safety Analysis ML23018A0352023-01-17017 January 2023 NRR E-mail Capture - Acceptance Review for Fleet Report Re Appendix F of DOM-NAF-2-P (L-2022-LLT-0003) ML22320A5752022-11-16016 November 2022 E-mail to File - Summary of October 18, 2022, Meeting with Dominion to Discuss Requested Actions for Implementing Framatome Gaia Fuel ML22298A2052022-10-25025 October 2022 Acceptance Review Determination for Alternative Request for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles ML22292A3212022-10-19019 October 2022 Acceptance Review Determination for Alternative Request for Containment RSS Pump Periodic Verification Testing Program ML22297A1802022-10-0707 October 2022 Email Acknowledgement to Dominion Energy Nuclear Decommissioning Trust Fund Disbursement 30 Day Notification for Millstone Power Station Unit 1: Docket No 50-245 ML22278A0932022-10-0505 October 2022 E-mail to File - Summary of September 7, 2022, Meeting with Dominion to Discuss Proposed Supplement to the Spent Fuel Pool Criticality Safety Analysis (EPID L-2022-LRM-0059 ML22272A0332022-09-29029 September 2022 Memo E-mail to File - Summary of August 29, 2022, Meeting with Dominion to Discuss Proposed Alternative Request Post-peening follow-up Volumetric Exam of RPV Head Penetration Nozzle ML22252A1772022-09-0909 September 2022 Memo E-mail to File - Summary of August 9, 2022, Meeting with Dominion to Discuss Proposed Alternative Reqeust Recirculation Spray Pump Flow Testing (EPID L:2022-LRM-0057) ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) ML22174A3552022-06-23023 June 2022 NRR E-mail Capture - Acceptance Review for Dominion Fleet LAR to Implement TSTF-554 (L-2022-LLA-0078) ML22123A0812022-05-0303 May 2022 Acceptance Review Determination for Proposed LAR for TS Change Applicable to TSTF-359, Increase Flexibility in Mode Restraints ML22069A7192022-03-10010 March 2022 E-mail from R. Guzman to S. Sinha - Millstone Unit 3 Steam Generator Outage Conference Call ML22020A4122022-01-11011 January 2022 1/11/2022 State Consultation E-mail, R. Guzman to J. Semancik Millstone Power Station, Unit 3 Planned Issuance of Amendment to Clarify Shutdown Bank TS and Add Alternate Control Rod Position Monitoring Requirements ML21348A7392021-12-14014 December 2021 E-mail - Acceptance Review Determination Alternative Request IR-4-09 for Use Alternative Brazed Joint Assessment Methodology for Class 3 Moderate Energy Piping ML21347A9412021-12-13013 December 2021 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in Safety Evaluation for Amendment No. 280 Measurement Uncertainy Recapture Power Uprate ML21334A1922021-11-30030 November 2021 NRR E-mail Capture - Audit Plan for Reactor Core Thermal-Hydraulics Using the VIPRE-D Appendix E Review ML21326A1502021-11-22022 November 2021 NRR E-mail Capture - Acceptance Review for Relocation of Unit Staff Requirements to the QAPD LAR (L-2021-LLA-0195) ML21306A3302021-11-0202 November 2021 NRR E-mail Capture - Acceptance Review for TSTF-569 LAR ML21297A0072021-10-19019 October 2021 E-mail from R. Guzman to S. Sinha - Acknowledgemnt of Error in SE for Millstone Power Station, Unit 3, Amendment No. 279 Addition of Analytical Methodology to the COLR for LBLOCA ML21286A7372021-10-13013 October 2021 Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR ML21223A3042021-08-11011 August 2021 Request for Withholding Information from Public Disclosure Proposed LAR to Add an Analytical Methodology to the COLR for a Large Break LOCA ML21200A2562021-07-19019 July 2021 7/19/2021 E-mail Pressurizer Steam Space Line Classification 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 ML21147A2982021-05-27027 May 2021 Correction to Projected Review Completion Date, ASME Section XI Inservice Inspection Program Relief Requests, Limited Coverage Examinations, Third Period, 3rd 10-year Inservice Inspection Interval (EPID L-2020-LLR-0081 to LLR-0088) ML21141A0482021-05-18018 May 2021 5/18/2021 E-mail Proposed License Amendment Request Measurement Uncertainty Recapture Power Uprate 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 ML21103A0532021-04-13013 April 2021 NRR E-mail Capture - Millstone Unit No. 3 - Acceptance Review Determination: Request for Alternative Frequency to Supplemental Valve Position Indication Verification Testing Requirement ML21084A0042021-03-25025 March 2021 3/25/2021 E-mail, Acceptance Review Determination, Proposed License Amendment Request to Revise Shutdown Bank TS Requirements and Add Alternate Control Rod Position Monitoring Requirements 2024-02-01
[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] |
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{{#Wiki_filter:From: Guzman, Richard To: Shayan Sinha
Subject:
Millstone Unit 3 - REQUEST FOR ADDITIONAL INFORMATION re: License Amendment Request to Revise Battery Surveillance Requirements (EPID: L-2020-LLA-0094)
Date: Monday, August 31, 2020 1:21:31 PM
- Shayan, On August 18, 2020, the U.S. Nuclear Regulatory Commission (NRC) staff sent Dominion Energy Nuclear Connecticut, Inc. (DENC) the subject Request for Additional Information (RAI) as a draft (via e-mail shown below).This RAI relates to the license amendment request submitted by DENC dated April 30, 2020, (ADAMS Accession No. ML20121A217), proposing to revise Technical Specifications (TS)
Surveillance Requirement (SR) 4.8.2.1.b and 4.8.2.1.c by adding a new acceptance criterion to verify the total battery connection resistance is within pre-established limits to ensure that the intended design functions are met.
On August 27, 2020, the NRC staff conducted a conference call with the licensee staff to clarify the request. Following the discussion, you indicated that DENC will provide a response to this RAI within 30 days from the issuance of the RAI; therefore, the NRC staff expects DENCs formal response by September 30, 2020. Updated below is the official (final) RAI. A publicly available version of this e-mail and RAI will be placed in the NRCs ADAMS system. Please contact me should you have any questions in regard to this request.
Sincerely, Rich Guzman Sr. PM, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov From: Guzman, Richard <Richard.Guzman@nrc.gov>
Sent: Tuesday, August 18, 2020 9:56 AM To: Shayan Sinha <Shayan.Sinha@dominionenergy.com>
Subject:
Millstone Unit 3 - DRAFT Request for Additional Information - License Amendment Request to Revise Battery Surveillance Requirements (EPID: L-2020-LLA-0094)
- Shayan, By letter dated April 30, 2020, (ADAMS Accession No. ML20121A217), Dominion Energy Nuclear Connecticut, Inc., (the licensee), submitted a license amendment request to Renewed Facility Operating License No. NPF-49 for Millstone Power Station Unit 3 (MPS3). The proposed changes would revise MPS3 Technical Specifications (TS) Surveillance Requirement (SR) 4.8.2.1.b and 4.8.2.1.c by adding a new acceptance criterion to verify the total battery connection resistance is within pre-established limits to ensure that the intended design functions are met.
The NRC staff has determined that additional information is needed to complete its review, as described in the request for additional information (RAI) shown below. This RAI is identified as DRAFT at this time to confirm your understanding of the information needed by the NRC staff to complete its evaluation. If youd like to have a clarification call, please let me know and I will coordinate availabilities w/the NRC technical staff. I intend to send out the questions below as official by August 28th, if possible.
- Thanks,
~~~~~~~~~~~
Rich Guzman Sr. PM, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov
===================================================================
REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE BATTERY SURVEILLANCE REQUIREMENTS MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 (EPID: L-2020-LLA-0094)
By letter dated April 30, 2020, (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML20121A217), Dominion Energy Nuclear Connecticut, Inc. (the licensee) submitted a license amendment request (LAR) to Renewed Facility Operating License No. NPF-49 for Millstone Power Station Unit 3 (MPS3). The proposed changes would revise MPS3 Technical Specifications (TS) Surveillance Requirement (SR) 4.8.2.1.b and 4.8.2.1.c by adding a new acceptance criterion to verify the total battery connection resistance is within pre-established limits to ensure that the intended design functions are met.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in the submittal and has determined that additional information as requested below is needed to complete its review.
Regulatory Basis The following NRC requirements are applicable to the NRC staffs review of the LAR:
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A, General Design Criterion (GDC) 17, General Design Criteria for Nuclear Power Plants, requires, in part, that nuclear power plants have onsite and offsite electric power systems to permit the functioning of structures, systems, and components that are important to safety. The onsite system is required to have sufficient independence, redundancy, and testability to perform its safety function, assuming a single failure.
10 CFR 50, Appendix A, GDC-18, Inspection and testing of electric power systems, requires that electric power systems that are important to safety must be designed to permit appropriate periodic inspection and testing.
10 CFR 50.36(c)(3), Technical Specifications, requires that TSs include SRs, which are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
Additionally, the following guidance document as referenced by the licensee is applicable for conformance to the regulatory requirements:
Institute of Electrical and Electronics Engineers (IEEE) Standard 450-1980 and IEEE Standard 450-1975 IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations.
The NRC staff also applied the 2002 edition of IEEE Standard 450 as it illustrates methods for measuring battery connection resistance.
Request for Additional Information (RAI)
The licensee proposed adding new acceptance criterion to TS SR 4.8.2.1.b and 4.8.2.1.c to verify that the total battery connection resistance is within pre-established limits, which ensures that the batteries can perform their specified safety functions by maintaining required battery terminal voltage under design-basis load conditions.
Section 3.2.1, Battery Resistance Evaluation, of the LAR states that Batteries 301A-1 and 301B-1 are model number NCN-27 and Batteries 301A-2 and 301B-2 are model number NCN-11. The LAR further states:
However, because surveillance procedure C SP 760, "Battery Discharge Test" (Reference 6.7) monitors only the plate-to-post and inter-cell connections and does not include the resistance from the inter-tier and inter-rack cabling (which have a total calculated impedance of 870 micro-ohm), the new calculated bounding acceptance criteria value is 3894 micro-ohm.
To determine the acceptability of the proposed TS total battery connection resistance limits, the NRC staff requests the following additional information:
RAI-1
The manufacturers data sheets indicate that NCN 11 battery cells have two posts per cell and NCN 27 cells have four posts per cell. Therefore, there are differences in the type and number of intercell connections. Section 3.2.1 of the LAR states that resistance sources in the MPS3 battery setup include plate-to-post connections, inter-cell connections, and cabling connections. The LAR also states that because MPS3 surveillance procedure for the battery discharge test monitors only the plate-to-post and inter-cell connections, the conductor resistance for inter-tier and inter-rack cables is not included in the bounding resistance value of 3894 micro-ohm.
The NRC staff notes that in addition to plate to post intercell connections, there are cabling connections, such as external/terminal cable lug to battery post and inter-tier or inter-rack cable lug to cell post. These cabling connections are also subjected to resistance changes due to acid related corrosion, loose connection fittings, improper mating surfaces, or material degradation. The LAR does not differentiate between the allowable resistance values for the different types of cell connections for the NCN-11 and NCN-27 cells. Annex F of IEEE Standard 450-2002 provides examples of methods for performing connection resistance measurements for various cell configurations.
Please provide a discussion on any differences between industry accepted guidance (e.g. Annex F of IEEE 450-2002) for measuring intercell connections for the different types of batteries and methods used at MPS3. In the discussion, confirm that the resistance of the cabling connections (i.e.,
connections between inter-tier cable lugs, inter-rack cable lugs, terminal cable lugs, multiple posts and battery posts) is included in the bounding resistance value of 3894 micro-ohm.
RAI-2
Section 3.1.2, Class 1E Batteries, of the LAR discusses the ampere-hour capacity of the battery systems and the 2-hour sizing criterion. Section 3.2.1, Battery Resistance Evaluation, states:
To ensure full functionality of the battery and associated loads with the new total allowable battery inter-cell impedance of 4764 micro-ohm, the most conservative battery draw and associated voltage drop was verified against the load profiles to ensure all battery minimum voltage requirements would be met. The primary bounding event for batteries is Loss of Onsite Power (LOP), but the calculations supporting the technical evaluation (Reference 6.6) also reviewed the normal and emergency operation loading
as part of the sizing verification.
Please provide a discussion on the calculation which demonstrates that LOP event is the bounding event for the proposed TS total connection resistance of 3700 micro-ohm. In the discussion please provide:
- a. A summary of assumptions, design basis and margins considered for total circuit resistances (battery internal resistance, battery system connection resistance, external conductor and conductor connection resistance, etc.) when evaluating battery load profiles for postulated operational conditions such as LOP. Please include a summary of load profile for other events such as station blackout and LOP coupled with an accident.
- b. Examples of equipment with limiting (minimum) terminal voltage and current conditions required to operate, as the battery terminal voltage approaches 1.75V per cell at the end of 2 hours.
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