Similar Documents at Surry |
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Category:Letter
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Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2302024-05-13013 May 2024 Core 1 Cycle 33 Pattern Mdr Revision 0 ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign ML24130A2032024-05-0909 May 2024 Proposed License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections Supplemental Information ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 IR 05000280/20240112024-04-24024 April 2024 Notification of Surry Power Station Comprehensive Engineering Team Inspection - U.S. NRC Inspection Report 05000280/2024011 and 05000281/2024011 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 ML24108A1812024-04-15015 April 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable Supplemental Information ML24095A2172024-04-12012 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report ML24088A2482024-03-26026 March 2024 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests- Response to Request for Additional Information ML24087A2082024-03-22022 March 2024 Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements ML24078A2642024-03-21021 March 2024 – Regulatory Audit in Support of License Amendment Request to Proposed Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML24087A1522024-03-18018 March 2024 Annual Changes, Tests, and Experiments Report Regulatory Commitment Evaluation Report ML24023A5762024-03-0808 March 2024 Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center IR 05000280/20230062024-02-28028 February 2024 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2023006 and 05000281/2023006 ML24032A4712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000280/20230042024-02-0909 February 2024 Integrated Inspection Report 05000280/2023004 and 05000281/2023004 IR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 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 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 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 ML23334A2342023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 2024-08-12
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARML18338A1062018-11-22022 November 2018 30-Day Special Report for an RCS Pressure Transient ML0835305382008-12-17017 December 2008 Submittal of Results of Be-LBLOCA Reanalysis with Astrum and 30-Day 10 CFR 50.46 Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML0708200742007-03-22022 March 2007 Day Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML19093B3511976-07-13013 July 1976 in Accordance with Technical Specification 4.14.C.1 for Surry Power Station, Report Describes Occurrence During Difference Between River Water Ambient Temperature Measured at Station High Level Intake & Cooling Water ML19093B3521976-04-0606 April 1976 in Accordance with Technical Specification 4.14.C.1 for Surry Power Station, Report Describes Occurrence During Difference Between River Water Ambient Temperature Measured at Station High Level Intake & Cooling Water 2018-11-22
[Table view] Category:Written Event Report (30 or 60 day)
MONTHYEARML19093B3511976-07-13013 July 1976 in Accordance with Technical Specification 4.14.C.1 for Surry Power Station, Report Describes Occurrence During Difference Between River Water Ambient Temperature Measured at Station High Level Intake & Cooling Water ML19093B3521976-04-0606 April 1976 in Accordance with Technical Specification 4.14.C.1 for Surry Power Station, Report Describes Occurrence During Difference Between River Water Ambient Temperature Measured at Station High Level Intake & Cooling Water 1976-07-13
[Table view] |
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__.--... VIRGINIA ELECTRIC AND PoWER COMPANY RIOHMOND, VIRGINIA. 23261
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J Mr. Benard c. Rusche Serial No. 966 Director of Nuclear Reactor Regulation PO&M./ALH: j lf
- u. s. Nuclear Regulatory Connnission Washington D.c. 20555 Docket Nos. 50-280 50-281 Attn: Mr. Robert w. Reid, Chief License Nos. DPR-32 Operating Reactors Branch 4 :: \ ;'~ .' :'.-.,. :; f: )! /]\ :: :'~' ! , ',.f , ,. , pI?~-3 7
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Dear Mr. Rusche:
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In accordance with Technical Specification 4.14.C.1 for Surry Power Station, this report describes an occurrence during which the difference be-tween the river water ambient temperature measured at the station high level intake and cooling water at the discharge control structure exceeded 15 degrees F.
At the time of the occurrence both Units 1 and 2 were operating at 100 percent power. On March 26, 1976, at approximately 1915 the temperature difference (~T) across the station exceeded 15 degrees F. The condenser outlet circulating water valves, which had been throttled to maintain the inlet canal level at 23.5 feet, were opened fully to increase water flow through the con-denser. This action reduced the temperature difference to within 15 degrees at 1935. At no time did the station~ T exceed 15 .5 degrees F.
The temperature increase was caused by a rapid drop in the river water ambient temperature. This rapid cooling was the result of river tidal action and the natural cooling of river water that occurs during the afternoon and evening hours.
Radical temperature fluctuations in river water ambient temperature such as encountered in this instance, make it extremely difficult to predict when action is necessary to avoid the 15 degrees F increase across the station.
There was no evidence of any adverse environmental from this occurrence.
Very truly yours,
- c. M. Stallings Vice President-Power Supply and Production Operations cc: Mr. M. V. Sinkule