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Category:Annual Operating Report
MONTHYEARML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 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 ML22179A3102022-06-22022 June 2022 Connecticut, Inc - 2021 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirement of 10 CFR 50.46 ML22108A0362022-03-21021 March 2022 Summary of Facility Changes, Tests and Experiments ML20181A5392020-06-29029 June 2020 Submittal of 2019 Annual Report of Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML19179A1472019-06-21021 June 2019 2018 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML18184A3462018-06-28028 June 2018 2017 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML17184A1462017-06-27027 June 2017 Transmittal of 2016 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML16179A2052016-06-21021 June 2016 2015 Annual Report of Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML15105A2412015-04-10010 April 2015 Independent Spent Fuel Storage Installation (Isfsi), Annual Radiological Environmental Operating Report ML14188C0562014-06-27027 June 2014 Annual Report of Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML14118A0422014-04-22022 April 2014 Independent Spent Fuel Storage Installation (Isfsi), Submittal of 2013 Annual Radioactive Effluent Release Report ML14118A0372014-04-22022 April 2014 Independent Spent Fuel Storage Installation (Isfsi), Submittal of 2013 Annual Radiological Environmental Operating Report ML14118A0392014-04-21021 April 2014 Annual Environmental Operating Report for 2013 ML13183A0682013-06-26026 June 2013 2012 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML13141A4142013-04-22022 April 2013 Independent Spent Fuel Storage Installation - 2012 Annual Radioactive Effluent Release Report ML13114A0562013-04-16016 April 2013 Independent Spent Fuel Storage Installation (Isfsi), Submittal of 2012 Annual Radiological Environmental Operating Report ML1219103392012-06-28028 June 2012 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML12135A0422012-04-26026 April 2012 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report ML12125A1252012-04-23023 April 2012 Independent Spent Fuel Storage Installation (ISFSI) - 2011 Annual Radiological Environmental Operating Report ML1118004992011-06-27027 June 2011 2010 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46, Kewaunee, Millstone, North Anna, Surry ML11130A0212011-04-29029 April 2011 Submittal of Annual Environmental Operating Report ML11123A2152011-04-26026 April 2011 Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report for 2010 ML11123A2142011-04-26026 April 2011 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report ML1018104352010-06-29029 June 2010 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML1009700602010-03-30030 March 2010 Summary of Facility Changes, Tests and Experiments for 2009 ML0918202722009-06-30030 June 2009 Submittal of 2008 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML0912703092009-04-27027 April 2009 Independent Spent Fuel Storage Installation (Isfsi), Annual Radiological Environmental Operating Report, January 1, 2008 to December 31, 2008 ML0909203162009-03-27027 March 2009 Submittal of Summary Description of Facility Changes, Tests and Experiments Identified in Regulatory Evaluations Implemented 2008 ML0817904372008-06-26026 June 2008 Annual Report of Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML0812806332008-04-28028 April 2008 Annual Radioactive Effluent Release Report, (01/01/07 - 12/31/07) ML0809205222008-03-24024 March 2008 Summary of Facility Changes, Tests and Experiments During 2007 Pursuant to 10 CFR 50.59(d)(2) ML0710301592007-04-0202 April 2007 Annual Environment Operating Report for 2006 ML0708606842007-03-19019 March 2007 Summary of Facility Changes, Tests and Experiments ML0605906112006-02-28028 February 2006 Annual Steam Generator Tube Inspection Report -2005 ML0518603972005-06-30030 June 2005 Annual Report of Emergency Core Cooling System Model Changes ML0510900222005-04-0707 April 2005 Annual Environmental Operating Report ML0509605022005-03-29029 March 2005 Summary of Facility Changes, Tests, and Experiments for 2004 ML0210706712002-04-0808 April 2002 Annual Environmental Operating Report ML0112403702001-04-27027 April 2001 Independent Spent Fuel Storage Installation Annual Radiological Environmental Operating Report 2024-06-25
[Table view] Category:Letter
MONTHYEARIR 05000338/20240032024-10-28028 October 2024 – Integrated Inspection Report 05000338-2024003 and 05000339-2024003 ML24283A0392024-10-0909 October 2024 Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 5.5.13.D ML24281A1372024-10-0707 October 2024 ISFSI - Submittal of Cask Registration for Spent Fuel Storage 05000338/LER-2024-001-01, Automatic Reactor Trip Due to Prni High Negative Rate2024-09-24024 September 2024 Automatic Reactor Trip Due to Prni High Negative Rate IR 05000338/20244202024-09-23023 September 2024 Security Baseline Inspection Report 05000338/2024420 and 05000339/2024420, Cover Letter ML24243A0872024-09-20020 September 2024 Response to EPA Comments Regarding the Final Site Specific Supplement to the Generic Eist for License Renewal North Anna Power Station, Units 1 and 2 IR 05000338/20244022024-09-17017 September 2024 Security Baseline Inspection Report 05000338/2024402 and 05000339/2024402 ML24215A2622024-08-28028 August 2024 Transmittal Letter for Subsequent Renewed License IR 05000338/20240052024-08-27027 August 2024 Updated Inspection Plan for North Anna Power Station, Units 1 and 2 (Report 05000338/2024005 and 05000339/2024005) ML24234A0742024-08-15015 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-23-63, NEI 03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24206A0062024-08-0808 August 2024 Notice of Availability of the Final Environmental Impact Statement for the North Anna Nuclear Power Station Unit Numbers 1 and 2 Subsequent License Renewal (Docket Numbers: 50-338 and 50-339) ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24241A0692024-08-0606 August 2024 ISFSI, Submittal of Cask Registration for Spent Fuel Storage IR 05000338/20240022024-08-0202 August 2024 Integrated Inspection Report 05000338/2024002 and 05000339/2024002 ML24206A0432024-07-26026 July 2024 Feis - Letter to the Applicant 05000338/LER-2024-001, Automatic Reactor Trip Due to Prni High Negative Rate2024-07-25025 July 2024 Automatic Reactor Trip Due to Prni High Negative Rate ML24206A0902024-07-24024 July 2024 Owners Activity Report ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 05000339/LER-2024-001, Loss of Generator Field for 2J EDG During 2-PT-82.282024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 IR 05000338/20240102024-05-24024 May 2024 NRC Fire Protection Team Inspection (FPTI) Report 05000338/2024010 and 05000339/2024010 IR 05000338/20240012024-05-10010 May 2024 Integrated Inspection Report 05000338/2024001 and 05000339/2024001 IR 05000338/20244032024-04-30030 April 2024 – Security Baseline Inspection Report 05000338-2024403 and 05000339-2024403 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24110A1502024-04-18018 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report ML24110A1392024-04-18018 April 2024 Annual Environmental Operating Report ML24087A0572024-04-16016 April 2024 Correction to Issuance of Amendment Nos. 296 and 279 ML24088A2692024-03-27027 March 2024 Core Operating Limits Report Cycle 31 Pattern Sos Revision 0 ML24086A4292024-03-25025 March 2024 Response to Request for Additional Information Associated with Alternative Request N1-I5-NDE-007 Request to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24082A2742024-03-22022 March 2024 Request for Approval of Alternative Request N1-I5-NDE-007 to Deter Additional Required Reactor Coolant Pump Casing Inspection 2024-09-24
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VIRGINIA ELECTRIC AND POWER COMPANY RICHM0OND, VIRGINIA 23261 March 24, 2008 United States Nuclear Regulatory Commission Serial No. 08-0125 Attention: Document Control Desk NAPS/JHL Washington, D. C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS 1 AND 2
SUMMARY
OF FACILITY CHANGES, TESTS AND EXPERIMENTS Pursuant to 10 CFR 50.59(d)(2), enclosed is a summary description of Facility Changes, Tests and Experiments identified in Regulatory Evaluations implemented at the North Anna Power Station during 2007.
If you have any questions, please contact Page Kemp at (540) 894-2295.
Very truly yours, D. G. Stoddard Site Vice President Attachment cc: U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 NRC Senior Resident Inspector North Anna Power Station JtL(7 KtMA
ATTACHMENT 10 CFR 50.59
SUMMARY
DESCRIPTION OF FACILITY CHANGES. TESTS AND EXPERIMENTS North Anna Power Station Units 1 and 2 Virginia Electric and Power Company (Dominion)
ý- ' ý NORTH ANNA UNITS 1 & 2 10 CFR 50.59
SUMMARY
DESCRIPTION OF FACILITY CHANGES, TESTS AND EXPERIMENTS REGULATORY EVALUATION: 07-SE-OT-01 Document Evaluated: Engineering Transmittal-NAF-07-0047, Rev. 0, Changes to the North Anna Containment Analyses and LOCA Alternate Source Term Analyses for Reduced RS Pump Flow Rates Brief
Description:
The plant safety analysis was revised to reduce the minimum assumed flow rates for the inside and outside recirculation spray (RS) pumps.
Reason for Change: Implement changes to the North Anna Units 1 and 2 UFSAR Chapter 6 containment analysis and LOCA Alternate Source Term analysis in UFSAR Chapter 15 to incorporate a reduction in the minimum recirculation spray (RS) pump flow rates, Summary: The IRS pump flow rate is changed from 3100 gpm to 3050 gpm. The ORS pump flow rate is changed from 3450 gpm to 3350 gpm. This change was made to provide margin for the RS pump test program. For NRC GSI-1 91, the design basis debris head loss that is applied to the RS strainers increases the suction head loss and reduces the minimum delivered flow.
The GOTHIC containment analyses in calculations SM-1 511-1, SM-1 512-00B, and SM-1513-1 demonstrate that the containment design criteria continue to be met for revised flow rates of 3050 gpm for the IRS pumps (50 gpm reduction) and 3350 gpm for the ORS pumps (100 gpm reduction). The LOCA containment depressurization analyses continue to be bounded by the limits from the LOCA dose consequences analysis basis from Technical Specification Change Request N-051. Containment pressure is less than or equal to 42.7 psig (Pa) in the first hour after a LOCA, is less than 2.0 psig during the period 1-6 hours after the LOCA, is sub-atmospheric within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and remains sub-atmospheric thereafter. Further, the containment pressure and temperature profiles remain within the equipment qualification limits. The reduced flow rates were also analyzed for the effect on NPSH available for the RS and low head safety injection (LHSI) pumps. There was a 0.1 ft reduction in RS pump NPSH margin and a 0.3 ft reduction in the LHSI pump NPSH margin during recirculation. The LHSI and RS pumps continue to have sufficient NPSH margin to meet the new design basis head loss requirements.