|
---|
Category:Letter
MONTHYEARIR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 ML24032A1112024-02-0101 February 2024 Owner'S Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML24032A4662024-01-16016 January 2024 Response to Comments on Draft Vpdes Permit No. VA0052451 ML24017A0802024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000338/2024301 and 05000339/2024301 ML23332A7272024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8352024-01-0909 January 2024 Letter to Acee Watt, Thpo, United Keetoowah Band of Cherokee Indians in Oklahoma Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal ML24003A8362024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8372024-01-0909 January 2024 Letter to Elizabeth Toombs, Thpo, Cherokee Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8382024-01-0909 January 2024 Letter to G. Anne Richardson, Chief, Rappahannock Tribe, Inc., Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8392024-01-0909 January 2024 Letter to Gerald Stewart, Chief, Chickahominy Indian Tribe, Eastern Division Re Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal ML24003A8402024-01-0909 January 2024 Letter to Katelyn Lucas, Thpo, Delaware Nation, Oklahoma, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8412024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8422024-01-0909 January 2024 Letter to Paul Barton, Thpo, Eastern Shawnee Tribe of Oklahoma, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8432024-01-0909 January 2024 Letter to Robert Gray, Chief, Pamunkey Indian Tribe, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8442024-01-0909 January 2024 Letter to Russell Townsend, Thpo, Eastern Band of Cherokee Indians ML24003A8452024-01-0909 January 2024 Letter to Stephen Adkins, Chief, Chickahominy Indian Tribe, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8462024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8472024-01-0909 January 2024 Letter to Tom Jonathan, Chief, Tuscarora Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8482024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8492024-01-0909 January 2024 Letter to W. Frank Adams, Chief, Upper Mattaponi Tribe Re Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal ML24003A8502024-01-0909 January 2024 Letter to Wenonah Haire, Thpo, Catawba Indian Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML23332A0872024-01-0404 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML23332A1852024-01-0404 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML23360A6352024-01-0404 January 2024 Letter to Dominion Availability for North Anna Units 1 and 2 Draft Site Specific Environmental Impact Statement ML24003A9022024-01-0303 January 2024 Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 ML23332A1472023-12-21021 December 2023 Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the North Anna Power Station, Units 1 and 2, Subsequent License Renewal Application 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) ML23352A3692023-12-18018 December 2023 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change ML23346A1022023-12-11011 December 2023 2024 North Anna Power Station Brq Inspection Notification Letter ML23346A0972023-12-11011 December 2023 License Amendment Request to Revise the Emergency Plan Relocation of the Technical Support Center - Response to NRC Request for Additional Information ML24012A0892023-12-0707 December 2023 GL Registration from Dominion Virginia Power ML24012A0942023-12-0707 December 2023 GL Report from Dominion Virginia Power Regarding Transfer of Devices ML23334A2432023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23334A2342023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23362A0602023-11-29029 November 2023 ISFSI, Submittal of Cask Registration for Spent Fuel Storage IR 05000339/20234022023-11-27027 November 2023 Security Baseline Inspection Report 05000338 and 05000339/2023402 IR 05000338/20230032023-11-13013 November 2023 Integrated Inspection Report 05000338/2023003 and 05000339/2023003 ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change IR 05000280/20230032023-10-25025 October 2023 Integrated Inspection Report 05000280/2023003 and 05000281/2023003 ML23286A0372023-10-13013 October 2023 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J 2024-02-06
[Table view] Category:Report
MONTHYEARML24032A1112024-02-0101 February 2024 Owner'S Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval ML24032A4662024-01-16016 January 2024 Response to Comments on Draft Vpdes Permit No. VA0052451 ML23214A1942023-09-0505 September 2023 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information - Report ML23167B0072023-05-31031 May 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Supplemental Information - LOCA Dose Calculation Summary ML23103A2282023-04-12012 April 2023 Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML23054A1922023-02-22022 February 2023 ASME OM Code Inservice Testing Program Alternative Request V-01, Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing Supplemental Information ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22255A0102022-06-28028 June 2022 Owner'S Activity Report ML22263A3642022-05-23023 May 2022 Alert and Notification System Evaluation Report - ANS Evaluation Redacted Pages 1 - 95 ML22263A2852022-05-23023 May 2022 Alert and Notification System Evaluation Report_Ans Evaluation_Redacted Page 1-65 ML22263A3692022-05-0101 May 2022 Alert and Notification System Evaluation Report - ANS Evaluation Redacted Pages 96-190 ML22119A1722022-04-13013 April 2022 Post-Accident Monitoring (PAM) Report ML21333A2842021-11-29029 November 2021 Requal Notification Letter ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML20091L9852021-05-0404 May 2021 Record of Decision ML20091L9832021-05-0404 May 2021 SLR License ML21036A0772021-02-23023 February 2021 Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2019 Refueling Outage ML21042B3212021-02-11011 February 2021 Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML20296A6802020-10-22022 October 2020 ASME Section XI Inservice Inspection Program Request for NRC Approval of Proposed Alternative S1-I5-ISL-05 and S2-15-ISL-06 ML20254A3472020-09-0808 September 2020 Supplement to Operator License Examination Comments ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20246G7062020-08-24024 August 2020 Enclosure 4: Attachment 1 - PWROG-18005-NP, Revision 2, Determination of Unirradiated Rt and Upper-Shelf Values of the North Anna Units 1 and 2 Reactor Vessel Materials ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML20149K6712020-05-31031 May 2020 PWROG-19047-NP, Revision 0, North Anna, Units 1 and 2, Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin Analysis ML20076A5762020-05-28028 May 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML20140A2392020-05-18018 May 2020 ASME Section XI Inservicee Inspection Program Proposed Inservice Inspection Alternative N1-15-NDE-002 ML20246G7012020-03-31031 March 2020 Enclosure 4: Attachment 3 - WCAP-18364-NP, Rev. 1, North Anna Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity for Subsequent License Renewal (SLR) ML20090B3972020-03-26026 March 2020 Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency ML20246G7072020-01-31031 January 2020 Enclosure 4: Attachment 4 - WCAP-11164-NP, Rev. 2, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for North Anna Units 1 and 2 Nuclear Power Plants for the Subsequent License Renewal ML19347A4212019-11-26026 November 2019 Owner'S Activity Report ML19249B7682019-08-29029 August 2019 Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) ML19249B7722019-08-29029 August 2019 Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) ML19249B7742019-08-29029 August 2019 Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) ML19249B7782019-08-29029 August 2019 Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 ML19235A0802019-08-19019 August 2019 Thermo-Lag Website ML19235A0792019-08-19019 August 2019 Pyrocrete Website ML19235A0782019-08-19019 August 2019 Mineral Wool Website ML19235A0772019-08-19019 August 2019 Micarta Website ML19235A0762019-08-19019 August 2019 Marinite Website ML19235A0682019-08-19019 August 2019 3M Interam Website ML19235A0692019-08-19019 August 2019 Bio K-10 Website ML19235A0702019-08-19019 August 2019 Cera Blanket Website ML19235A0712019-08-19019 August 2019 Cerafiber Website ML19235A0722019-08-19019 August 2019 Duxseal Website ML19235A0732019-08-19019 August 2019 Gypsum Website ML19235A0742019-08-19019 August 2019 Kbs Sealbags Website ML19235A0752019-08-19019 August 2019 Marinite Slide Plates Products - Piping Tech ML19204A3582019-06-30030 June 2019 WCAP-18258-NP, Revision 1, Flaw Tolerance Evaluation for Susceptible Reactor Coolant Loop Cast Austenitic Stainless Steel Elbow Components for Surry Units 1 and 2. ML19163A1542019-06-0606 June 2019 SLRA - Attachment 4D Letter - Draft to Dominion ML19140A2762019-05-20020 May 2019 Essential Fish Habitat Mapper Results for Surry Power Station 2024-02-01
[Table view] Category:Miscellaneous
MONTHYEARML24032A1112024-02-0101 February 2024 Owner'S Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval ML23054A1922023-02-22022 February 2023 ASME OM Code Inservice Testing Program Alternative Request V-01, Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing Supplemental Information ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22255A0102022-06-28028 June 2022 Owner'S Activity Report ML21333A2842021-11-29029 November 2021 Requal Notification Letter ML20091L9832021-05-0404 May 2021 SLR License ML20091L9852021-05-0404 May 2021 Record of Decision ML21036A0772021-02-23023 February 2021 Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2019 Refueling Outage ML20254A3472020-09-0808 September 2020 Supplement to Operator License Examination Comments ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20076A5762020-05-28028 May 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML19347A4212019-11-26026 November 2019 Owner'S Activity Report ML19163A1542019-06-0606 June 2019 SLRA - Attachment 4D Letter - Draft to Dominion ML19140A2762019-05-20020 May 2019 Essential Fish Habitat Mapper Results for Surry Power Station ML18108A1232018-04-11011 April 2018 Proposed Alternative Requests S1-15-ISl-04 and S2-15-ISl-04 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography in Accordance with 10 CFR 50.55a(z)(1) ML17325A7792017-11-22022 November 2017 Review of Steam Generator Tube Report for the Fall 2016 Inspections During Refueling Outage 27 (CAC No. MF9683; EPID L-2017-LRO-0009) ML17186A0842017-06-29029 June 2017 Flooding Focused Evaluation Summary ML16187A3232016-06-24024 June 2016 Submittal of Owner'S Activity Report (Form OAR-1), for Refueling Outage N2R24 ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report ML15335A0932015-12-15015 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 Recommendation2.1 of the Near-Term Task Force Review ML15238A8442015-09-25025 September 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15232A8112015-08-24024 August 2015 Evaluation of Information Related to Commitments 6 and 8 from Confirmatory Action Letter No. NRR-2011-002 ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al ML15238B5922015-08-17017 August 2015 Review of Commitment Action Completion Confirmation Action Letter Regarding Earthquake in 2011 ML15175A1902015-06-17017 June 2015 Owner'S Activity Report ML15057A2492015-04-20020 April 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 Relating to Recommendation 2.1 ML15097A0782015-04-0707 April 2015 Soarca Surry 2005 Site File ML15072A2992015-03-16016 March 2015 Review of the Fall 2013 Steam Generator Tube Inservice Inspection Report Regarding Surry Power Station, Unit 1 Refueling Outage 25 ML15078A2872015-03-12012 March 2015 Engineering Evaluation 14-E15, Dominion Flooding Hazard Reevaluation Report, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Revision 1, Pp. 1 Through 2-114 ML15078A2892015-03-12012 March 2015 Engineering Evaluation 14-E15, Dominion Flooding Hazard Reevaluation Report, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Revision 1, Pp. 2-219 Through the End ML15078A2882015-03-12012 March 2015 Engineering Evaluation 14-E15, Dominion Flooding Hazard Reevaluation Report, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Revision 1, Pp. 2-115 Through 2-218 ML15058A0342015-02-23023 February 2015 Summary of Facility Changes, Tests and Experiments ML14251A0352014-08-28028 August 2014 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) ML14086A1942014-04-0909 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14092A4142014-03-31031 March 2014 Response to March 12, 2012 Information Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1 ML14084A2122014-03-27027 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14084A3272014-03-27027 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14024A6022014-01-10010 January 2014 Post Accident Monitoring (PAM) Report ML14015A3142014-01-0808 January 2014 Submittal of Owner'S Activity Report Refueling Outage N1R23 (Form OAR-1) ML13172A0092013-07-0101 July 2013 Nd 2, Closure Evaluation for Report Pursuant to 10 CFR 50.46(a)(3) Concerning Significant Emergency Core Cooling System Evaluation Model Error Related to Nuclear Fuel Thermal Conductivity Degradation ML12293A4512012-10-22022 October 2012 ACRS Assessment of the Quality of Selected NRC Research Projects- Fy 2012 ML12257A0862012-09-20020 September 2012 Review of the 2011 Refueling Outage System Generator Tube Inservice Inspection Report ML12166A1342012-06-27027 June 2012 Closeout of Bulletin 2011-01, Mitigating Strategies. ML12166A5192012-06-14014 June 2012 Transmittal of Final Accident Sequence Precursor (ASP) Analysis ML12160A2682012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident ML12073A3852012-03-0808 March 2012 Resources Services, Inc., Notification Letter That Surry Power Station Not Received a Copy of the Waste Shipment Record (Wsr) Signed by the Owner or Operator of the Designated Waste Disposal Site ML12046A8492012-02-27027 February 2012 Review of the Steam Generator Tube Inservice Inspection Report for the Refueling Outage in 2010 ML12060A3492012-02-16016 February 2012 Owner'S Activity Report for Refueling Outage N2R21 ML12039A1602012-01-25025 January 2012 Steam Generator Tube Inspection Report ML12039A1612012-01-25025 January 2012 Steam Generator Tube Inspection Report 2024-02-01
[Table view] |
Text
S..
VIRGINIA ELECTRIC AND POWER COMPANY RicHMoND, VIRGINIA 23261 December 2, 2002 U.S. Nuclear Regulatory Commission Serial No.: 02-662 Attention: Document Control Desk NL&OS/ETS RO Washington, D.C. 20555 Docket Nos.: 50-338/339 50-280/281 License Nos.: NPF-4/7 DPR-32/37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION DOMINION'S RELOAD NUCLEAR DESIGN METHODOLOGY TOPICAL REPORT Dominion's Reload Nuclear Design Methodology Topical Report has been revised to support the transition to Framatome ANP Advanced Mark-BW fuel at North Anna. In a letter dated October 8, 2001 (Serial No.01-623) Virginia Electric And Power Company (Dominion) submitted Revision 2 of VEP-FRD-42, "Reload Nuclear Design Methodology Topical Report," for NRC review and approval. During review of the topical report, the NRC staff identified additional information that is needed to complete their review. The additional information was requested in a letter from the NRC dated October 25, 2002. Attachment 1 to this letter provides the additional information including Dominion's process for the maintenance and modification of "NRC Approved" methodologies.
If you have any further questions or require additional information, please contact us.
Very truly yours, Eugene S. Grecheck Vice President - Nuclear Support Services Attachment Commitments made in this letter: None 7Acx;i
2" cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303-8931 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station Mr. M. J. Morgan NRC Senior Resident Inspector North Anna Power Station Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center, Suite 300 4201 Dominion Blvd.
Glen Allen, Virginia 23060
I-.
Attachment REQUEST FOR ADDITIONAL INFORMATION DOMINION'S RELOAD NUCLEAR DESIGN METHODOLOGY TOPICAL REPORT VEP-FRD-42, Revision 2 North Anna Power Station Units I and 2 Surry Power Station Units I and 2 Virginia Electric and Power Company (Dominion)
=
Background===
In a letter dated October 8, 2001 (Serial No.01-628) Virginia Electric and Power Company (Dominion) submitted Revision 2 of VEP-FRD-42, "Reload Nuclear Design Methodology Topical Report," for NRC review and approval. During review of the topical report, the NRC staff identified additional information that is needed to complete their review. The additional information was requested in a letter from the NRC dated October 25, 2002. The requested information is delineated below.
NRC Request for Additional Information:
"VEPCO is requested to confirm that the submittals listed below are the latest revisions for these codes that have not received NRC staff approval.
- 1. PDQ - The staff will review Topical Report VEP-NAF-1, July, 1990, submitted in a letter from VEPCO to NRC dated October 1, 1990.
- 2. NOMAD - The staff will review Topical Report VEP-NFE-1A, Supplement 1, September 1996, submitted in a letter from VEPCO to NRC dated November 11, 1996.
- 3. TIP/CECOR - The staff will review Topical Report VEP-NAF-2, November 1991, submitted in a letter from VEPCO to NRC dated December 20, 1991.
- 4. RETRAN - The staff will review the information submitted in a letter from VEPCO to NRC dated August 10, 1993. The information provided in this submittal was only applicable for North Anna, Units 1 and 2."
Dominion Response:
PDQ and NOMAD Codes & Models For PDQ, the report submitted by letter Serial No.90-562, dated October 1, 1990 is the latest revision that has not received NRC staff approval. Likewise, the NOMAD report submitted by letter Serial No.96-319, dated November 13, 1996 (versus November 11, 1996 stated above) is the latest revision that has not received NRC staff approval. For both PDQ and NOMAD, the referenced reports are accurate representations of current codes and models with regard to methodology. That is, the theory, sources of input data, solution schemes, geometric mesh structure, energy group structure, and use of the models in the core modeling process have not changed. There have been subsequent code changes to correct minor errors and to accommodate new code edits and additional computing platforms. There have been changes in input to accommodate the evolution of core design features including increased fuel enrichments, changes in BP design, and use of vessel fluence suppression neutron absorber rods. Throughout this period, accuracy of the PDQ model (and by extension the NOMAD model, since PDQ is the source of data and normalization for NOMAD) has been verified each cycle during startup physics testing and during routine core follow. For each cycle, a Startup Physics Test Report and a Core Performance Report is issued to document the Page 1 of 6
behavior of the core relative to the model predictions.
TIPICECOR Code & Model The topical VEP-NAF-2, submitted by letter Serial No.91-746, dated December 20, 1991, is the latest revision of TIP/CECOR that has not received NRC staff approval.
However, Dominion does not consider review of TIP/CECOR necessary for review of VEP-FRD-42 Rev. 2 (the Reload Topical) for several reasons. First, the focus of the Reload Topical is on core design and safety analysis methodology, not core surveillance. TIP/CECOR is not directly discussed in VEP-FRD-42 Rev. 2 because it is not part of the reload methodology. TIP/CECOR uses data provided by the PDQ model (Reload Topical Section 2.1.1, paragraph 2) to perform core power distribution surveillance. Second, TIP/CECOR is not new methodology for measurement of core power distributions. USNRC review and approval for use of CECOR in the synthesis of core power distributions using fixed in-core detector data is documented in a 1980 Combustion Engineering Topical Report (Reference 5 of VEP-NAF-2). TIP/CECOR, the Dominion version of the model, uses the same solution schemes and techniques but employs data at 61 axial points rather than just a few. Finally, although the current interpretation of "essentially the same" had not yet been applied to 1 OCFR50.59 evaluations in 1992, the TIP/CECOR Topical Report and the 10CFR50.59 evaluation performed prior to use of the code clearly demonstrate that TIP/CECOR results are essentially the same as those of the previous measurement code (INCORE). The reason for replacing INCORE with CECOR was not to gain analytical margin, but to be able to accept input representing physically different regions of newer, axially non homogenous cores.
RETRAN Code & Model Consistent with approaches employed by NSSS vendors, Dominion's RETRAN model is qualified on the basis of the plant class for which it will be used. There is not a separate Surry-specific RETRAN model document that parallels the content of the report submitted in Reference 1. However, as discussed further below, the material in Reference 1 is equally applicable to the Surry and North Anna models. The Surry 3-loop model, which was completed after the submittal of Reference 1, uses the same noding, modeling philosophy and code options as the North Anna model. The following description provides some background discussion relating to the RETRAN models in use for North Anna and Surry.
Dominion's reload methodology incorporates the RETRAN-02 code, which was generically approved by the NRC via Reference 2. Dominion is currently using RETRAN-02, Mod 5.2. The NRC issued a generic approval, transmitted in Reference 3, for RETRAN-02 Mod 5.0. Discussions between the utilities and the NRC led to the conclusion that Mods 5.1 and 5.2, which were essentially maintenance upgrades, did not require additional NRC review for utility implementation (References 4 and 5).
Dominion's RETRAN models and capability were approved in Reference 6. As noted in the SER, the Virginia Electric and Power Company (Dominion) Topical Report was Page 2 of 6
supplemented in three subsequent submittals (References 7, 8, 9) prepared in response to NRC Requests for Additional Information.
The RETRAN Topical SER (Reference 6) recognized that model maintenance activities would be performed under the utility 10 CFR 50 Appendix B QA program:
"The staff requires that all future modifications of VEPCO RETRAN model and the error reporting and change control models should be placed under full quality assurance procedures."
Dominion has followed the requirements specified in the SER for VEP-FRD-41 in updating our RETRAN models. Updated models and the qualification results were documented per our 10 CFR 50 Appendix B QA program and provided to the USNRC for information in Reference 1. The qualification, documentation and implementation of these new models was done in a manner that meets the programmatic elements of Generic Letter 83-11, Supplement 1.
Reference 1 presented the 3-loop RETRAN model and qualification results using the North Anna version of the model. The Surry 3-loop model is the same with regard to noding, options and system and component modeling techniques. The Surry and North Anna models differ in order to appropriately reflect plant specific design features such as RCS geometry, system and pump characteristics and setpoint values. Dominion concludes that the model description in Reference 1 accurately describes the key features of the models in use for both Surry and North Anna power stations.
Dominion continues to perform model maintenance activities in accordance with the provisions of the SER and 10 CFR 50 Appendix B. Dominion has made model changes in the past to refine treatment of certain features, to address industry issues or to reflect changes to the plants. These changes were evaluated under the provisions of 10CFR50.59, which will continue to be employed to assess future changes. The following list summarizes several enhancements which are illustrative of the changes that have been made to the models:
"* The current models use the 1979 ANS Decay Heat model option.
"* More detailed main steam safety valve (MSSV) modeling was added to ensure that the concerns raised in NRC Information Notice 97-09, "Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping" are adequately addressed.
"* Hydraulic characteristics in the core regions have been adjusted to reflect current fuel assembly designs.
"* More detailed, mechanistic models for the pressurizer and steam generator level instrumentation were added.
"* A detailed rod control system model was added.
Page 3 of 6
Dominion's Process for the Maintenance and Modification of "NRC Approved" Methodologies Section 2.3 of VEP-FRD-42, Rev. 2, entitled "Analytical Model and Method Approval Processes," indicates several acceptable means by which either analytical models or methods can achieve approved status for use in Dominion's reload methodology. The following discussion describes Dominion's approach in performing maintenance and modifications of NRC Approved methodologies. This approach is applied to all models and methodologies that are employed in Dominion's reload design methodology, and which may be cited either by reference within VEP-FRD-42 or in the COLR.
The determination of the requirement to submit methodology changes to NRC for approval prior to application is based on published NRC guidance, i.e.:
- 10 CFR 50.59, and in particular 10 CFR 50.59c(2)(viii): "(2) A licensee shall obtain a license amendment pursuant to Sec. 50.90 prior to implementing a proposed change, test, or experiment if the change, test, or experiment would (viii) Result in a departurefrom a method of evaluation describedin the FSAR (as updated) used in establishingthe design bases or in the safety analyses."
0 NEI 96-07, Revision 1, "Guidelines for 10 CFR 50.59 Evaluations"
- Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments" (endorses NEI 96-07 Rev. 1) 0 Generic Letter 83-11, Supplement 1, "Licensee Qualifications for Performing Safety Analyses" Relevant sections of these documents upon which we base our determination process are as follows:
- 1. Generic Letter 88-16 establishes the concept of reload cycle dependent operating limits in the Technical Specifications.
"Generally, the methodology for determining cycle-specific parameter limits is documented in an NRC-approved Topical Report or in a plant-specific submittal.
As a consequence, the NRC review of proposed changes to TS for these limits is primarily limited to confirmation that the updated limits are calculated using an NRC-approved methodology and consistent with all applicable limits of the safety analysis. These changes also allow the NRC staff to trend the values of these limits relative to past experience. This alternative allows continued trending of these limits without the necessity of priorNRC review and approval."
- 2. NEI 96-07, Rev. 1, as endorsed by Reg. Guide 1.187, provides guidance for evaluating changes to methods under the provisions of 10CFR50.59. For example, Paragraph 4.3.8.1, states:
Page 4 of 6
4.3.8.1, Guidance for Changing One or More Elements of a Method of Evaluation "The definition of "departure ..." provides licensees with the flexibility to make changes under 10 CFR 50.59 to methods of evaluation whose results are "conservative"or that are not important with respect to the demonstrations of performance that the analyses provide. Changes to elements of analysis methods that yield conservative results, or results that are essentially the same, would not be departuresfrom approved methods."
- 3. USNRC Generic Letter 83-11 Supplement 1 provides a method for utility qualification of analysis methodologies, including those used to establish core operating limits, without formal NRC review and approval:
"The U.S. Nuclear Regulatory Commission (NRC) is issuing this supplement to Generic Letter (GL) 83-11 to notify licensees and applicants of modifications to the Office of Nuclear Reactor Regulation (NRR) practice regarding licensee qualificationfor performing theirown safety analyses. This includes the analytical areas of reload physics design, core thermal-hydraulicanalysis, fuel mechanical analysis, transient analysis (non-LOCA), dose analysis, setpoint analysis, containment response analysis, criticality analysis, statisticalanalysis, and Core Operating Limit Report (COLR) parameter generation. It is expected that recipients will review the information for applicability to their facilities. However, suggestions contained in this supplement to the generic letter are not NRC requirements; therefore, no specific action or written response is required."
"To help shorten the lengthy review and approvalprocess, the NRC has adopted a generic set of guidelines which, if met, would eliminate the need to submit detailed topical reports for NRC review before a licensee could use approved codes and methods. These guidelines are presented in the Attachment to this Generic Letter. Using this approach, which is consistent with the regulatorybasis provided by Criteria II and Ill of Appendix B to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50), the licensee would institute a program (such as training,procedures,and benchmarking) that follows the guidelines, and would notify NRC by letter that it has done this and that the documentation is availablefor NRC audit."
Reflecting this NRC and industry guidance, Dominion's process for maintaining and modifying approved methodologies encompasses these elements:
" Dominion can change, under the provisions of 10 CFR 50.59(c)(2)(viii), NRC approved codes and methodologies used to establish core operating limits, via the processes outlined in NEI 96-07, Rev. 1, without additional NRC review and approval of these changes.
"* Dominion can implement or substitute, under 10 CFR 50.59(c)(2)(viii), NRC approved codes and methodologies for use in establishing core operating limits via Page 5 of 6
the processes outlined in Generic Letter 83-11 Supplement 1, without additional NRC review and approval of these methods.
Dominion concludes that, in updating the list of approved methodologies for establishing core operating limits in the Technical Specifications, utility affirmation that the changes to the methodologies have been done as described by either of the above is adequate to retain the "approved" status for these methods.
References:
- 1. Letter from M. L. Bowling (Virginia Electric and Power Company) to USNRC, "Virginia Electric and Power Company, North Anna Power Station Units 1&2, Supplemental Information on the RETRAN NSSS Model," Serial No.93-505, August 10, 1993.
- 2. Letter from C. 0. Thomas (NRC) to T. W. Schnatz (UGRA), Acceptance for Referencing of Licensing Topical Reports EPRI CCM-5, "RETRAN-A Program for One Dimensional Transient Thermal Hydraulic Analysis of Complex Fluid Flow Systems," and EPRI NP-1850-CCM, "RETRAN-02-A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems," September 4, 1984.
- 3. Letter from A. C. Thadani (NRC) to W. J. Boatwright (RETRAN02 Maintenance Group), Acceptance for Use of RETRAN02 MOD005.0, November 1, 1991.
- 4. Letter from M. J. Virgilio (NRC) to C. R. Lehmann (RETRAN Maintenance Group),
Acceptance for Referencing of the RETRAN-02 MOD005.1 Code, April 12, 1994.
- 5. Letter from G. L. Swindlehurst (RETRAN Maintenance Group) to T. E. Collins (NRC/RSB), RETRAN-02 MOD005.2 Code Version, Notification of Code Release, November 24, 1997.
- 6. Letter from C. 0. Thomas (NRC) to W. L. Stewart (Virginia Power), Acceptance for Referencing of Licensing Topical Report VEP-FRD-41, 'Virginia Power Reactor System Transient Analyses Using the RETRAN Computer Code," April 11, 1985.
- 7. Letter from W. L. Stewart (Vepco) to H. R. Denton (USNRC), "Vepco Reactor System Transient Analyses, Supplemental Information," Serial No. 060, February 27,1984.
- 8. Letter from W. L. Stewart (Vepco) to H. R. Denton (USNRC), "Vepco Reactor System Transient Analyses," Serial No. 376, July 12, 1984.
- 9. Letter from W. L. Stewart (Vepco) to H. R. Denton (USNRC), "Vepco Reactor System Transient Analyses," Serial No. 376A, August 24, 1984.
Page 6 of 6