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MONTHYEARLR-N13-0205, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident-Base Case Velocity...2013-09-10010 September 2013 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident-Base Case Velocity... Project stage: Response to RAI 0CAN091301, Response to NRC Request for Information (RFI) Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi..2013-09-12012 September 2013 Response to NRC Request for Information (RFI) Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi.. Project stage: Response to RAI LR-N14-0051, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. Project stage: Response to RAI 0CAN031404, ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima2014-03-28028 March 2014 ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima Da Project stage: Response to RAI ML14092A4172014-03-31031 March 2014 Response to March 12, 2012 Information Request Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1 Project stage: Request RS-14-065, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of The..2014-03-31031 March 2014 Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of The.. Project stage: Response to RAI LIC-14-0047, Omaha Public Power District - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi2014-03-31031 March 2014 Omaha Public Power District - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Project stage: Request ML14204A6202014-07-21021 July 2014 Response to Request for Additional Information Regarding Seismic Hazard and Screening Report for Seismic Recommendation 2.1 Project stage: Response to RAI ML14204A6192014-07-21021 July 2014 Response to March 12, 2012 Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 Project stage: Request NL-14-099, Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights.2014-08-18018 August 2014 Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights. Project stage: Request 0CAN081401, Response to Request for Additional Information (RAI) Associated with Near-Term Task Force (NTTF) Recommendation 2.1, Seismic Hazard and Screening Report2014-08-21021 August 2014 Response to Request for Additional Information (RAI) Associated with Near-Term Task Force (NTTF) Recommendation 2.1, Seismic Hazard and Screening Report Project stage: Response to RAI RS-14-206, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-08-28028 August 2014 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other PLA-7224, Response to March 12, 2012 Information Request - Supplemental Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 - PLA-72242014-08-28028 August 2014 Response to March 12, 2012 Information Request - Supplemental Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 - PLA-7224 Project stage: Request RS-14-230, Supplemental Information Related to the Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2, 1 of the Near-Term Task Force Review Of...2014-08-29029 August 2014 Supplemental Information Related to the Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2, 1 of the Near-Term Task Force Review Of... Project stage: Supplement LIC-14-0124, Supplemental Information Related to Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The...2014-10-22022 October 2014 Supplemental Information Related to Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The... Project stage: Supplement LR-N14-0227, Seismic Hazard and Screening Report - Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-10-30030 October 2014 Seismic Hazard and Screening Report - Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Supplement 0CAN111401, Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-11-0404 November 2014 Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Other NL-14-139, Additional Information Regarding the Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-11-0505 November 2014 Additional Information Regarding the Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Request ML14310A0222014-11-13013 November 2014 Report Regarding Individual Plant Examination of External Events Supporting Information for Seismic Screening Project stage: Other ML14246A4282014-11-21021 November 2014 Screening and Prioritization Results Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident Based on Individual Plant Examination of External Events Project stage: Approval ML14310A0332014-12-15015 December 2014 NRC Response to Licensees Notification of Revised Regulatory Commitments Associated with Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Revie Project stage: RAI ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review Project stage: Other ML17123A3782016-04-27027 April 2016 Reevaluated Seismic Hazard Mitigating Strategies Assessment Report Project stage: Other ML16365A0322016-12-21021 December 2016 Response to March 12, 2012 Information Request, Spent Fuel Pool Seismic Evaluation for Recommendation 2.1 Project stage: Other 2014-03-28
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Category:Audit Report
MONTHYEARML22101A1522022-04-14014 April 2022 Regulatory Audit Report Regarding Request to Review Appendix E to Fleet Topical Report DOM-NAF-2 ML19259A0362019-10-0707 October 2019 Summary Report for the Audit of the Response to 10 CFR 50.54(F) Information Request -Flood-Causing Mechanism Reevaluation ML15057A1902015-03-16016 March 2015 Audit of the Licensee'S Management of Regulatory Commitments, Regulatory Commitments Changes, and Appropriateness of Application of the Regulatory Commitments ML14275A0172014-11-17017 November 2014 Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14310A0222014-11-13013 November 2014 Report Regarding Individual Plant Examination of External Events Supporting Information for Seismic Screening ML14002A1032014-02-19019 February 2014 Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13338A4332014-01-31031 January 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML1132606112011-12-28028 December 2011 Audit of the Licensee'S Management of Regulatory Commitments ML0722905502007-08-30030 August 2007 GSI-191, Generic Letter 2004-02 Corrective Actions Audit Report ML0720400692007-07-13013 July 2007 Request for Proprietary Review of Draft Corrective Actions Audit Report for Generic Safety Issue - 191 Related to Generic Letter 2004-02 ML0430903702005-05-0505 May 2005 Audit of Dominion Nuclear Connecticut, Inc'S Management of Regulatory Commitments ML0503300592005-02-0202 February 2005 Audit and Review Report for Plant Aging Management Reviews and Programs 2022-04-14
[Table view] 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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 13,2014 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
lnnsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060
SUBJECT:
MILLSTONE POWER STATION, UNIT 2- REPORT OF REGULATORY AUDIT REGARDING INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS SUPPORTING INFORMATION FOR SEISMIC SCREENING (TAC NO. MF3968)
Dear Mr. Heacock:
By letter dated March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued an information request, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident" (hereafter referred to as the 50.54(f) letter) (Agencywide Documents Access Management System (ADAMS) Package Accession No. ML12056A046), to all power reactor licensees and holders of construction permits. The 50.54(f) letter, in part, requested that licensees reevaluate the seismic hazards at their sites against present-day NRC requirements. For central and eastern United States sites, the 50.54(f) letter required licensees to submit a seismic hazard evaluation to the NRC by March 31, 2014.
By letter dated March 31, 2014 (ADAMS Accession No. ML14092A417), Dominion Nuclear Connecticut, Inc. (Dominion, the licensee) submitted its Seismic Hazard and Screening Report for Millstone Power Station, Units 2 and 3 (Millstone) to the NRC. Dominion concluded in the report that the Individual Plant Examination of External Events (IPEEE) is adequate for seismic screening purposes and that both Millstone, Units 2 and 3 screen out of conducting additional seismic risk evaluations.
The NRC endorsed industry guidance "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," provides the criteria used to determine if the licensee's IPEEE submittal is adequate to use for seismic screening purposes. If one or more of the criteria are not deemed adequate, the staff may still decide that the overall IPEEE analysis is adequate to support its use for seismic screening.
The NRC staff reviewed Dominion's submittal and determined that additional information was needed to determine the IPEEE adequacy for seismic screening of Millstone, Unit 2.
By letter dated July16, 2014 (ADAMS Accession No. ML14195A034), the NRC issued a request for additional information (RAI) to the licensee. Dominion submitted its RAI response by letter dated July 21, 2014 (ADAMS Accession No. ML14204A620). The letter identified that an audit may be needed to support this activity. Accordingly the NRC conducted an audit on
D. Heacock October 23, 2014, at the Nuclear Energy Institute facilities in Rockville, MD. The plan for this audit dated October 22, 2014, can be found in ADAMS under Accession No. ML14295A085.
The scope of this audit was limited to the information provided and referenced in Dominion's Seismic Hazard and Screening Report and response to the RAI. The purpose of this audit was to enable the NRC staff to come to a better understanding of the differences between original and reconstituted IPEEE supporting calculations performed on the Chill Water Surge Tank and Battery Rack DB1 and DB2. The information gained from this audit will inform the NRC's seismic screening determination for Millstone, Unit 2.
If you have any questions, please contact Michael Balazik at 301-415-2856 or by e-mail at Michaei.Balazik@ nrc.gov Sincerely, lazik, Project n ger Japan Lessons Learned Division Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
Audit Report cc w/encl: Distribution via Listserv
AUDIT REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS SUPPORTING INFORMATION FOR SEISMIC SCREENING DOMINION NUCLEAR CONNECTICUT, INC MILLSTONE POWER STATION, UNIT 2 DOCKET NO. 50-336 BACKGROUND On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued an information request, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident" (hereafter referred to as the 50.54(f) letter)
(Agencywide Documents Access Management System (ADAMS) Package Accession No. ML12056A046), to all power reactor licensees and holders of construction permits. The 50.54(f) letter, in part, requested that licensees reevaluate the seismic hazards at their sites against present-day NRC requirements. For central and eastern United States sites, the 50.54(f) letter required licensees to submit a seismic hazard evaluation to the NRC.
By letter dated March 31, 2014 (ADAMS Accession No. ML14092A417), Dominion Nuclear Connecticut, Inc. (Dominion, the licensee) submitted its Seismic Hazard and Screening Report for Millstone Power Station, Units 2 and 3 (Millstone) to the NRC. Dominion concluded in the report that the Individual Plant Examination of External Events (IPEEE) is adequate for seismic screening purposes and that both Millstone, Units 2 and 3 screen out of conducting additional seismic risk evaluations.
The NRC endorsed industry guidance "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," provides the criteria used to determine if the licensee's IPEEE submittal is adequate to use for seismic screening purposes. If one or more of the criteria are not deemed adequate, the staff may still decide that the overaiiiPEEE analysis is adequate to support its use for seismic screening.
The NRC staff reviewed Dominion's submittal and determined that additional information was needed to determine the IPEEE adequacy for seismic screening of Millstone, Unit 2. By letter dated July16, 2014 (ADAMS Accession No. ML14195A034), the NRC issued a request for additional information (RAI) to the licensee. Dominion submitted its RAI response by letter dated July 21, 2014 (ADAMS Accession No. ML14204A620).
Enclosure
The scope of this audit was limited to the information provided and referenced in Dominion's Seismic Hazard and Screening Report and response to the RAI. The purpose of the audit was to enable the NRC staff to come to a better understanding of the differences between original and reconstituted IPEEE supporting calculations performed on the Chilled Water Surge Tank and Battery Rack DB1 and DB2. The information gained from this audit will inform the NRC's seismic screening determination for Millstone Unit 2.
AUDIT ACTIVITIES The NRC audit team consisted of:
- Michael Balazik, Japan Lessons-Learned Division, Office of Nuclear Reactor Regulation
- Frankie Vega, Japan Lessons-Learned Division, Office of Nuclear Reactor Regulation
- Nilesh Chokshi, Division of Site Safety & Environmental Analysis, Office of New Reactors
- Kamal Manoly, Division of Engineering, Office of Nuclear Reactor Regulation
- Thomas Weaver, Division of Engineering, Office of Nuclear Regulatory Research
- Diane Jackson, Division of Site Safety & Environmental Analysis, Office of New Reactors
- Ricardo Rodriguez, Division of Site Safety & Environmental Analysis, Office of New Reactors The licensee supporting staff consisted of:
- Marc Hotchkiss, Dominion Nuclear
- Eric May, Dominion Nuclear
- Divakar Bhargava, Dominion Nuclear
- Joe Vasquez, Dominion Nuclear
The audit team reviewed the following types of information:
- Dominion 14-350_MPS2 RAI Response : "Response to Request for Additional Information Regarding Seismic Hazard and Screening Report for Seismic Recommendation 2.1, dated July 21, 2014
- ETE-CEM-2014-0001 Attachment 7, Resolution of Open Items from IPEEE Adequacy Review, Rev. 1
- 96- ENG -1380M2: "Qualification of Battery Racks DB1 and DB2 Anchorage Outlier Resolution for SQUG/A46, Rev. 2
- 97C2799-C-015 Rev.1: "Miscellaneous Seismic Capacity Calculations- excerpts for T98, dated December 31, 1997
- Drawing 25203-33027-00002: "Seis. Rstnts. For Bats. DB1 & DB2 (North) East & West Bat. RMS. EL. 14'-6", Rev. 1
- Drawing 25203-39020 Sh 7 and 11: " Rack Assembly Two-Step, 24 Cells LCU" Rev. 2
- C-73-267, Chilled Water Surge Tank Item T98, Rev. 5
- M-5957, Seismic Calculations Millstone, Unit 2 Nuclear, dated February 15, 1972
- MMOD M2-96568: "Modification of Station Batteries 201 A And 201 B Rack Anchorage-excerpt, Rev. 0
- S&A 93C2799- C- 007: "Seismic Capacity of DB1 Battery Rack", dated October 30, 1995
- DM2-S-0698-96, Battery Racks DB1 & DB2 Anchorage Modification to Resolve USIA-46 Outlier, dated July 23, 1996
AUDIT
SUMMARY
The audit team performed an independent review of the calculation packages referenced above.
The team's observations were discussed with the licensee to further understand the licensee's actions in demonstrating the adequacy of their IPEEE program to meet the SPID screening criteria. The information gained from this audit will assist the NRC in determining the seismic screening for Millstone, Unit 2.
Discussions with the licensee led to an increased level of clarity regarding the licensee's IPEEE program. Specifically, the staff reviewed Millstone's updated High Confidence Low Probability of Failure (HCLPF) capacity calculations for two components: the chilled water surge tank and the battery racks DB1 and DB2. As part of the NRC's IPEEE screening review, the staff asked the licensee for additional clarification regarding the HCLPF for these two components. As part of the response to the staff's RAI, the licensee reconstituted these calculations since they were unable to locate them as part of the originaiiPEEE documentation. During the audit these calculations, along with supporting documentation, were reviewed by the staff in order to confirm the licensee's conclusion which assigned HCLPF values of .25g or higher for the two components. Based on a detailed staff review and after discussions with the licensee, the staff was able to confirm that the stated conclusions were acceptable. The staff was also able to understand the differences between the original and reconstituted IPEEE calculations performed for these two components. In addition to the calculation review, the staff confirmed that certain modifications were made, as credited in the seismic hazard and screening report.
By discussing these specific topics in depth with the licensee and reviewing the documentation, the team was able to meet the objectives of the audit and has a better understanding of the licensee's IPEEE program with regards to meeting the SPID screening criteria and has sufficient information to address the issues identified in the audit plan.
CONCLUSION The staff was able to obtain the needed information in order to make a conclusion on whether the IPEEE is adequate to support its use for seismic screening for Millstone, Unit 2. No further information will be requested.
D. Heacock October 23, 2014, at the Nuclear Energy Institute facilities in Rockville, MD. The plan for this audit dated October 22, 2014, can be found in ADAMS under Accession No. ML14295A085.
The scope of this audit was limited to the information provided and referenced in Dominion's Seismic Hazard and Screening Report and response to the RAI. The purpose of this audit was to enable the NRC staff to come to a better understanding of the differences between original and reconstituted IPEEE supporting calculations performed on the Chill Water Surge Tank and Battery Rack DB1 and DB2. The information gained from this audit will inform the NRC's seismic screening determination for Millstone Unit 2.
If you have any questions, please contact Nicholas Michael Balazik at 301-415-2856 or bye-mail at Michaei.Balazik@nrc.gov Sincerely, IRA/
Michael F. Balazik, Project Manager Japan Lessons Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-245
Enclosure:
Audit Report cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC MBalazik, NRR JHMB R/F NDiFrancesco, NRR RidsNrrDorllpl1-1 Resource FVega, NRR RidsNrrPMMillstone Resource DJackson, NRO RidsNrrLASLent Resource SWhaley, NRR ADAMS Accession Number* ML14310A022 OFFICE NRR/JLD/JHMB/PM NRR/JLD/JHMB/PE NRR/JLD/JHMB/BC NAME MBalazik FVega SWhaley DATE 11/10/14 11/10/14 11/12/14 OFFICE NRO/DSENRGS1 NRR/JLD/JHMB/LA NRR/JLD/JHMB/PM NAME DJackson SLent MBalazik DATE 11/10/14 11/10/14 11/13/14 OFFICIAL RECORD COPY