Letter Sequence Response to RAI |
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EPID:L-2018-LLA-0126, License Amendment Request Regarding Proposed Technical Specifications Changes for Spent Fuel Storage and New Fuel Storage (Approved, Closed) |
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MONTHYEARML18128A0492018-05-0303 May 2018 License Amendment Request Regarding Proposed Technical Specifications Changes for Spent Fuel Storage and New Fuel Storage Project stage: Request ML18163A1732018-06-12012 June 2018 Acceptance Review Determination (E-mail 6/12/2018), LAR Regarding Proposed TS Changes to Spent Fuel Storage and New Fuel Storage Project stage: Acceptance Review ML18173A1582018-06-29029 June 2018 Request for Withholding Information from Public Disclosure for Millstone Power Station Unit 3 (Holtec) Project stage: Withholding Request Acceptance ML18172A2352018-06-29029 June 2018 Request for Withholding Information from Public Disclosure for Millstone Power Station Unit 3 (Westinghouse) Project stage: Withholding Request Acceptance 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 Project stage: RAI ML18340A0282018-11-29029 November 2018 Response to Request for Additional Information for Proposed Technical Specifications Changes for Spent Fuel Pool Storage and New Fuel Storage Project stage: Response to RAI 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 Project stage: RAI ML19092A3322019-03-27027 March 2019 Response to Request for Additional Information for Proposed Technical Specification Changes for Spent Fuel Pool Storage and New Fuel Storage Project stage: Response to RAI ML19126A0002019-05-28028 May 2019 Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage Project stage: Approval ML19159A0022019-06-0606 June 2019 06/06/09 E-mail from R. Guzman to M. Calderone Discrepancies Identified in SE for License Amendment No. 273 Project stage: Other 2018-06-29
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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:Response to Request for Additional Information (RAI)
MONTHYEARML23361A0942023-12-21021 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 . 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. 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 L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information ML23124A3642023-04-20020 April 2023 Response to Request for Additional Information for Spring 2022 Steam Generator Tube Inspection Report ML23096A2982023-04-0606 April 2023 Units 1 and 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion ML22312A4432022-11-0707 November 2022 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI ML21259A0852021-09-15015 September 2021 North Ann, and Surry, Units 1 and 2, Millstone, Units 2 and 3, Request for Approval of Appendix E of Fleet Report DOM-NAF-2-A Qualification of the Framatome BWU-I CHF Correlation in the Vipre-D Computer Code Response to Request for Addition ML21209A7622021-07-26026 July 2021 Response to Request for Additional Information for Alternative Request V-01 - Proposed Request for Alternative Frequency to Supplemental Valve Positionn Verification Testing Requirements ML21153A4132021-06-0202 June 2021 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML21147A4772021-05-27027 May 2021 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Final Supplemental Response ML21140A2992021-05-20020 May 2021 Response to Request for Additional Information for Proposed License Amendment Request to Add an Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident ML21133A2852021-05-13013 May 2021 Stations, Units 1 & 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix E Fleet Report DOM-NAF-2-A Qualification of the Framatome Bwui CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21105A4332021-04-15015 April 2021 Final Supplemental Response to NRC Genetic Letter 2004-02 on Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accident at Pressurized-Water Reactors ML21105A4822021-04-15015 April 2021 Response to Request for Additional Information for Proposed License Amendment Request to Revise the Millstone, Unit 2 Technical Specification for Steam Generator Inspection Frequency ML21081A1362021-03-19019 March 2021 Response to Request for Additional Information for Alternative Request RR-05-06 - Inspection Interval Extension for Steam Generator Pressure-Retaining Welds and Full-Penetration Welded Nozzles ML20274A3462020-09-30030 September 2020 Response to Request for Additional Information for License Amendment Request to Revise Battery Survillance Requirements ML20261H5982020-09-17017 September 2020 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20252A1912020-09-0404 September 2020 Response to Request for Additional Information Regarding License Amendment Request for a One-Time Deferral of the Millstone Unit 3 Steam Generator Inspections ML20209A5362020-07-27027 July 2020 Response to Request for Additional Information Regarding Relief Request IR-3-33 for Limited Coverage Examinations Performed in the Second Period of the Third 10-Year Inspection Interval ML20079K4242020-03-19019 March 2020 Response to Request for Additional Information for License and Request to Revise TS 3.8.1.1, A.C Sources - Operating, to Support Maintenance and Replacement of the Millstone Unit 3 'A' Reserve Station Service Transformer and 345 Kv South Bu ML20076C8332020-03-16016 March 2020 Response to Request for Additional Information (E-mail Dated 3/16/2020) Alternative Request IR-4-03 for Use of Alternative Non-Code Methodology ML20048A0192020-02-11011 February 2020 Response to Request for Additional Information for License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of a Reserve Station Service Transformer and 345 Kv South Bus. ML20042D9962020-02-10010 February 2020 Response to March 12, Request for Information Enclosure 2, Recommendation 2.1, Flooding Focused Evaluation/Integrated Assessment Submittal ML19284A3972019-10-0303 October 2019 Response to NRC Request for Additional Information on License Amendment Request to Adopt 10 CFR 50.69 ML19249B7672019-08-29029 August 2019 Enclosure 1 - Millstone, Units 2 and 3 and ISFSI; North Anna, Units 1 and 2 and ISFSI; and Surry, Units 1 and 2 and ISFSI - Response to EAL Scheme Change RAIs ML19092A3322019-03-27027 March 2019 Response to Request for Additional Information for Proposed Technical Specification Changes for Spent Fuel Pool Storage and New Fuel Storage ML19011A1112018-12-18018 December 2018 Supplement to the Flooding Hazard Reevaluation Report in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding ML18340A0282018-11-29029 November 2018 Response to Request for Additional Information for Proposed Technical Specifications Changes for Spent Fuel Pool Storage and New Fuel Storage ML18302A1202018-10-22022 October 2018 Response to Request for Additional Information for License Amendment Request to Revise the Technical Specification for Control Building Ventilation Inlet Instrumentation ML18235A3212018-08-17017 August 2018 Response to Request for Additional Information for Proposed Alternative Request P-06 for 'C' Charging Pump ML18225A0662018-08-0606 August 2018 Response to Request for Additional Information for Alternative Requests Associated with the In-Service Testing Program for Pumps, Valves, and Snubbers Fifth and Fourth 10-Year Interval Updates ML18205A1762018-07-19019 July 2018 Response to Request for Additional Information for Alternative Requests Associated with the In-Service Testing Program for Pumps, Valves, and Snubbers Fifth and Fourth 10-Year Interval Updates for Units 2 and 3 ML18170A0932018-06-14014 June 2018 Response to Request for Additional Information Regarding License Amendment Request to Revise Integrated Leak Rate Test (Type a) and Type C Test Intervals ML18151A4672018-05-24024 May 2018 Response to Request for Additional Information Regarding License Amendment Request to Revise Integrated Leak Rate Test (Typed a) and Type C Test Intervals ML17338A0572017-11-22022 November 2017 Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML17300A2202017-10-24024 October 2017 Response to Information Need Request Regarding Mitigating Strategies Assessment (MSA) Report for Flooding ML17053A1062017-02-16016 February 2017 Response to Request for Additional Information Regarding Proposed Alternative Requests RR-04-24 and IR-3-30 for Elimination of the Reactor Pressure Vessel Threads in Flange Examination ML17038A0052017-01-31031 January 2017 Response to RAI Regarding End of Cycle 23 and End of Cycle 17 Steam Generator Tube Inspection Reports, CAC MF8507 & MF8506 ML16365A0362016-12-22022 December 2016 Response to March 12, 2012 Information Request High Frequency Sensitive Equipment Functional Confirmation for Recommendation 2.1 ML16365A0322016-12-21021 December 2016 Response to March 12, 2012 Information Request, Spent Fuel Pool Seismic Evaluation for Recommendation 2.1 ML16321A4542016-11-10010 November 2016 Connecticut and Virginia Electric & Power Company Response to Request for Additional Information Revision 22 of Quality Assurance Program Description Topical Report ML16312A0642016-11-0101 November 2016 Units 1 & 2, Surry, Units 1 & 2, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML16294A2702016-10-18018 October 2016 Response to Request for Additional Information for License Amendment Request Regarding Realistic Large Break Loss of Coolant Accident Analysis - RAI Questions 1 Through 3 ML16291A5082016-10-12012 October 2016 Response to Follow Up Request to Revise ECCS TS 3/4.5.2 and FSAR Chapter 14 to Remove Charging ML16202A0402016-07-14014 July 2016 Response to Request for Additional Information Regarding Spent Fuel Pool Heat Load Analysis License Amendment Request ML16188A1962016-06-30030 June 2016 NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations ML16182A0372016-06-27027 June 2016 Response to Request for Additional Information for License Amendment Request to Revise ECCS TS 3/4.5.2 and FSAR Chapter 14 to Remove Charging ML16159A2382016-06-0101 June 2016 Isfsis, Response to NRC Request for Information Security Plan, Training and Qualification Plan, Safeguards Contingency Plan and ISFSIs Security Program, Rev. 21 ML16148A7012016-05-20020 May 2016 Response to Request for Additional Information Regarding ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval 2023-08-30
[Table view] |
Text
Dominion Energy Nuclear Connecticut, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 ~ Dominion Dominion Energy.com
. November 29, 2018 P' Energy U.S. Nuclear Regulatory Commission Serial No.18-403 Attention: Document Control Desk NRA/SS RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR PROPOSED TECHNICAL SPECIFICATIONS CHANGES FOR SPENT FUEL POOL STORAGE AND NEW FUEL STORAGE By letter dated May 3, 2018, Dominion Energy Nuclear Connecticut, Inc. (DENC) requested Nuclear Regulatory Commission (NRC) approval of the proposed Technical Specifications (TS) changes for Millstone Power Station Unit 3 for spent fuel pool storage and new fuel storage. In an email dated October 18, 2018, the NRC transmitted a request for additional information (RAI) related to the TS change request.
The attachment to this letter provides DENC's response to the NRC's RAI.
If you have any questions regarding this submittal, please contact Shayan Sinha at (804) 273-4687.
Sincerely,
- ,/
/ .' 7
'J:t k~
Gerald T. Bischof Senior Vice President - clear Operations & Fleet Performance COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Gerald T. Bischof, who is Senior Vice President - Nuclear Operations & Fleet Performance of Dominion Energy Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.
- Acknowledged before me this ~ y otA/oVcmhc .. ,2018.
My Commission Expires: S -- 3, - a.:a . Uc.1w.: Xi2/IA/;t....
Notary Public VICKI L. HULL NOTARY PUBLIC REG. # 140542 COMMONWEALTH OF VIRGINIA MY COMMISSlON EXPIRES 5131/2022 I
Serial No.18-403 Docket No. 50-423 Page 2 of 2
Attachment:
Response to Request for Additional Information for Proposed Technical Specification Changes for Spent Fuel Pool Storage and New Fuel Storage Commitments made in this letter: DENG will revise the Updated FSAR to follow the Baral coupon testing schedule requirements in NEI 16-03 following end of Cycle (EOG) 21.
cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 Richard V. Guzman Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C 2 11555 Rockville Pike Rockville, MD 20852-2738 NRG Senior Resident Inspector Millstone Power Station
Serial No.18-403 Docket No. 50-423 ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGE FOR SPENT FUEL STORAGE AND NEW FUEL STORAGE MILLSTONE POWER STATION 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
Serial No.18-403 Docket No. 50-423 Attachment, Page 1 of 4 By letter dated May 3, 2018, Dominion Energy Nuclear Connecticut, Inc. (DENC) requested Nuclear Regulatory Commission (NRC) approval of the proposed TS changes for Millstone Power Station Unit 3 for spent fuel storage and new fuel storage.
In an email dated October 18, 2018, the NRC transmitted a request for additional information (RAI) related to the request. This attachment provides DENC's response to the RAI.
RAI-MCCB-1 Part 50.68(b)(4) of Title 10 of the Code of Federal Regulations (10 CFR) states, in part, that ".. .the k-effective (kerr) of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0. 95 ... " In order to demonstrate that kerr doesn't exceed 0. 95, the licensee submitted its SFP criticality analysis, for MPS3, as part of its LAR dated May 3, 2018. This analysis, in part, takes credit for the neutron absorbing properties of the Bora/ material installed in the SFP racks.
In its LAR, the licensee referenced 'its response to request for additional information (RAJ) Jetter dated November 22, 2017, related to Generic Letter 2016, "Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools", (ADAMS Accession No. ML17338A057), to provide information regarding the Bora/ monitoring program at MPS3. In the RAJ response, the licensee noted that it had discovered weight 'Joss with an unknown cause in its Bora/ coupons since their installation in 2000. In addition, the licensee stated thatit did not discover any degradation that would impact SFP criticalitf In order to have reasonable assurance that the weight loss has not impacted the SFP criticality, the NRG staff has the following questions:
a) Has the weight loss caused any dimensional changes (e.g. length, width, or thickness) in the Bora/ coupons?
b) Has there been any decrease in Boron 10 (B-10) areal density (AD) in the coupons?
c) Provide any corrective actions taken to mitigate the degradation of the Bora/
material, and describe how these actions are meant to mitigate, or account for any impacts to the SFP criticality analysis* due to the *weight loss of the Bora/
coupons.
Serial No.18-403.
,\
Docket No. 50-423 Attachment, Page 2 of 4 DENC Response a) There have been no significant changes to the length or width of the coupons. The thickness has decreased to varying degrees. Table 1 below shows the average dimensional changes of the coupon measurements to date relative to the as-built measurements for each coupon.
Table 1: Percent Change to the Dimensions of the BORAL Coupons Year of Measurement Weight Length*1 Width*1 Thickness.:
2003 -1.4% -0.1% -0.1% -0.7%
2004 -1.9% -0.1% -0.2% 0.3%
2005 -2.7% -0.2% -0.2% -0.2%
2008 -4.4% -0.1% -0.1% -3.3%
2013 -6.1% -0.2% -0.2% -3.0%
2017 -5.8% --0.2% -0.2% -1.3%
1 Average of three measurement locations along the coupon.
2 Average of five measurement locations on the coupon.
b) The coupons have shown no indication that the B-10 areal density (AD) has decreased. Table 2 shows the measured B-10 AD.
Table 2: Percent Change to the 8-10 AD of the BORAL Coupons Year of Measurement B-10 AD 2003 1.6%
2004 0.9%
2005 -4.1 %*
2008 -2.8%*
2013 -5.6%*
2013 1.6%*
Reevaluation 2017 1.1%
- As previously discussed in DENC's response to the RAls for Generic Letter 2016-01 (ADAMS Accession No. ML17338A057), the 2013 coupon's areal density was reevaluated based on the vendor's newer and more accurate chemical analysis of the BORAL standards. This reevaluation changed the B-10 AD from 0.0302 g/cm 2 to 0.0325 g/cm 2 compared to* an as-built value of 0.0320 g/cm 2 . The 2005 and 2008 measurements used the same chemical analysis of the standards as the 2013 measurement and thus, had the same issue. With the more accurate calibrations, these coupon measurements do not indicate that B-10 AD is being lost.
Serial No.18-403 Docket No. 50-423 Attachment, Page 3 of 4 c) DENC does not currently consider that the weight loss in the BORAL coupons is of immediate concern based on three factors:
(1) The weight loss is occurring slowly in comparison to the measurement interval.
(2) It is unclear whether the weight loss phenomenon is also occurring to the BORAL in the SFP racks.
(3) The effect of losing the aluminum clad is small and already quantified in the submitted criticality analysis.
These factors are further explained as follows:
- 1. The 2017 coupon measurement leveled off the weight loss trend. However, conservatively ignoring the 2017 measurement, the trend shows a weight loss of about 0.5% per year. The aluminum clad surrounding the B4C cermet accounts for about 22% of the BORAL mass. If the pre-2017 trend continued, it would take 32 more years until the B4C cermet is exposed to the SFP water environment.
The coupon measurement interval is much shorter than 32 years (See DENC's response to RAI-MCCB-2 below). Therefore, the weight loss phenomenon is occurring slowly enough that DENC will be able to detect the weight loss trend if it recommences and enact mitigating corrective actions before the B4 C cermet is exposed to the SFP environment.
- 2. Prior to the 2017 measurement, the BORAL coupons were not encased in stainless steel wrappers whereas the BORAL panels in the SFP racks are encased. A Condition Report was written regarding the coupon weight loss trend. One of the Corrective Actions to address the cause of the weight loss is to investigate whether storing BORAL coupons fully exposed to the SFP environment on the coupon* tree is contributing to the weight loss, possibly by allowing physical interaction with the tree structure or storage cell. To determine whether the absence of wrappers contributes to the coupon weight loss trend, the remaining coupons were encased in stainless steel sheaths in April 2018.
Future measurements will determine if the stainless steel wrapper has an effect on the BORAL weight loss.
- 3. The possible weight loss and thinning of the BORAL in the SFP racks is evaluated in the criticality analysis. Table 9.6, 9.14, and 9.20 of Attachment 5 to the LAR (ML18128A049) shows the uncertainty cases for BORAL thickness. The uncertainty cases remove al_l of the clad from one side of the BORAL plate for all panels in the pool. Proportionally this is roughly double the amount of weight loss observed to date in the coupons. The SFP k-eff sensitivity to the BORAL thickness is small. For Region 1, the sensitivity is 0.0010 delta k (dk, including statistical uncertainties) compared to the minimum margin to the limit of 0.0079 dk. For Region 2, the sensitivity is 0.0003 dk compared to the minimum margin to the limit of 0.0052 dk. Note that the minimum margin to the limit of the whole LAR is in Region 3 with 0.0049 delta k.
Serial No.18-403 Docket No. 50-423 Attachment, Page 4 of 4 Based on the information presented above, there are no planned corrective actions at this time. It should be noted that if future information challenges the assertions outlined above, then the situation will be reevaluated to determine if corrective actions are needed to mitigate the Baral weight loss.
RAI-MCCB-2 10 CFR 50.68(b)(4) states, in part, that " ... the kerr of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95 ... ". The MPS3 TS 5. 6. 1. 1, "Fuel Storage - Criticality," ensures the sub-criticality requirements of 10 CFR 50.68(b)(4) are met. The kerr found in the SFP criticality analysis is used to demonstrate compliance with TS 5. 6. 1. 1. Certain assumptions in the SFP criticality analysis rely on the condition of the Bora/ neutron-absorbing material. In order to verify the assumed values for certain properties of Bora/ (Boron-10 areal density, length, width, etc.), the licensee has previously implemented a Bora/ coupon monitoring program.
Because the Bora/ coupon monitoring program provides assurance, in part, that TS
- 5. 6. 1. 1 will continue to be met, the NRC staff requires assurance that the coupon monitoring program will not be subject to changes which reduce the effectiveness of the program. Describe how the Bora/ coupon monitoring program will be controlled (e.g.
UFSAR/TS update) to provide assurance that changes reducing the effectiveness of the program will not be made.
- DENC Response The MPS3 Updated FSAR, Section 9.1.2.3 provides the required BORAL coupon testing schedule which at present extends through the end of Cycle (EOC) 21 (spring 2022). Dominion Energy Nuclear Connecticut has committed to revising the Updated FSAR to follow the Baral coupon testing schedule requirements in NEI 16-03, "Guidance for Monitoring of Fixed Neutron* Absorbers in Spent Fuel Pools" following EOC 21. In accordance with NEI 16-03, until the weight loss trend has been arrested, Millstone Unit 3 will test the BORAL coupons approximately every 5 years in accordance with the Millstone procedure for Baral Test Coupons. Revisions to the Updated FSAR are subject to the requirements of 10 CFR Part 50.59.