Similar Documents at Surry |
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Category:Letter
MONTHYEARML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection 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 ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 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 IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - 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 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 ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign 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 IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change 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 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 IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 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 Event Report (LER)
MONTHYEAR05000281/LER-2020-001, Cancellation of LER 2020-001-00 for Surry Power Station Unit 2 Re Loss of Containment Cooling Affecting Containment Partial Pressure Indication2020-11-0606 November 2020 Cancellation of LER 2020-001-00 for Surry Power Station Unit 2 Re Loss of Containment Cooling Affecting Containment Partial Pressure Indication 05000280/LER-2019-0022020-02-0404 February 2020 LER 2019-002-00 for Surry Power Station Unit 1, Items Non-Conforming to Design for Tornado Missile Protection 05000280/LER-2017-0012017-10-0606 October 2017 1 OF 3, LER 17-001-00 for Surry, Unit 1, Regarding Shutdown due to an Unisolable Leak in Reactor Coolant Pressure Boundary 05000281/LER-2016-0012016-12-0202 December 2016 Unit 2 Reactor Trip due to Generator Differential Lockout, LER 16-001-00 for Surry Power Station, Unit 2, Regarding Reactor Trip Due to Generator Differential Lockout 05000280/LER-2016-0012016-07-11011 July 2016 1 OF 4, LER 16-001-00 for Surry Power Station, Unit 1 and 2, Regarding Emergency Service Water Pump Inoperable Due to Corrosion of Valve Support ML1015505662009-03-0404 March 2009 Event Notification for Surry on Relief Valve Failure Results in Tritium and Cesium Spill ML0702501902007-01-17017 January 2007 Special Report on Qpt Not Less than Two Percent for Twenty Four Hours ML19105B1281979-08-21021 August 1979 LER 1979-011-03X for Surry Units 1 & 2 Loss of Power with Both Units at Cold Shutdown, Observed Radiation Monitors Without Power ML19093B4141978-09-26026 September 1978 Reporting Condenser Cooling Water Outlet Temperature to James River Decreased by 3.5oF as Measured at Station Discharge Structure ML19105A3001978-09-0808 September 1978 LER 78-013-03X-1, LER 78-029-03L-0, & LER 78-031-03L-0 for Surry 2 Re Critical Below Minimum Insertion Limit on D Control Bank ML19105A3011978-09-0101 September 1978 LER 1978-028-03L-0 for Surry 2 Re Containment Pressure Exceeded Allowable Limit ML19095A4971978-08-25025 August 1978 Submit Licensee Event Report No. LER 78-024/03L-0 Re No Alarm During a Planned Release of Liquid Radioactive Waste ML19095A4981978-08-22022 August 1978 Submit Licensee Event Report Nos. LER 1978-019/03L-0, LER 1978-021/03L-0, LER 1978-022/03L-0, LER 1978-023/03L-0, LER 1978-025/03L-0, LER 1978-026/03L-0 for Surry Unit No. 1 ML19105A0771978-08-16016 August 1978 Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria ML19105A0781978-08-16016 August 1978 Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria ML19105A0791978-08-11011 August 1978 LER 78-026/03L-0. Follow-up Inspection for Valve Cleanliness, Discovered That Containment Spray Isolation Valves (MOV-CS-201C and D) Contained No More That Five Milliliters. Technical Specification TS 6.6.2.b.(3) ML19095A4991978-08-0404 August 1978 Sutmit Licensee Event Report No. LER 78-018/03L-0 Re Two Main Steam Safety Valves Were Not within Plus or Minus 3% of Setpoint as Required ML19105A0801978-07-28028 July 1978 LER 1978-022-03L-0 Re Axial Power Distribution Monitoring Was Exceeded,& Three LERs 1978-021-03L-0, LER 1978-023-03L-0, & LER 1978-024-03L-0 Re Inlet Circulating Water Temperature Exceeded ML19095A5001978-07-28028 July 1978 Submit Licensee Event Report Nos. LER 78-017/03L-0 Re Not Documenting Four Electric Maintenance Procedures & Two Periodic Tests, & 78-020/03L-0 Re Suspended Air Bubbles in Reservoir Fluid ML19095A2281978-07-27027 July 1978 Reporting & Providing Additional Information on Incidence of Missing Two Steam Generator Tube Plugs Found During Inspection ML19095A2291978-07-26026 July 1978 Reporting of Cooling Water Discharge Temperature Change Rate on 7/9/1978 & Found No Evidence of Any Detrimental Effects in River or Its Inhabitants ML19095A5011978-07-21021 July 1978 Submit Licensee Event Report No. LER 78-016/03L-0 Re Valve MOV-RH-100 Was Not Opening ML19105A0821978-07-17017 July 1978 LER 1978-025-03L for Surry Unit 2 Excessive Gap Around Battery Room Ventilation Duct ML19105A0811978-07-17017 July 1978 LER 1978-025-03L for Surry Unit 2 Excessive Gap Around Battery Room Ventilation Duct ML19095A5021978-07-0707 July 1978 Submit Licensee Event Report Nos. LER 78-013/03L-0 Re Six Snubbers Not Meeting Test Criteria, & 78-014/03L-0 Re Mount Plate Was Warped, & 3 of 8 Bolts Were Insufficiently Embedded ML19095A5031978-06-27027 June 1978 Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces ML19095A5041978-06-27027 June 1978 Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces ML19105A0831978-06-23023 June 1978 LER 1978-017-03L, LER 1978-018-03L, LER 1978-019-03L, & LER 1978-020-03L for Surry Unit 2 Related to Snubbers ML19095A2481978-06-19019 June 1978 06/19/1978 Letter Reporting Increase of Condenser Cooling Water Discharge ML19095A5051978-06-0707 June 1978 Submit Licensee Event Report No. LER-78-012/03L-0 Re Inside Recirculation Spray Pump 1-RS-P-1A, Failure to Rotate by Hand ML19105A0851978-05-23023 May 1978 LER 1978-015-03L for Surry Unit 2 Finding of Air Leak on Header of Control Room Emergency Air Supply Bank ML19095A5061978-05-23023 May 1978 Submit Licensee Event Report Nos. LER-78-008/03L-0, LER-78-009/03L-0, LER-78-010/03L-0, LER-78-011/03L-0 for Surry Unit No. 1 ML19105A0861978-05-12012 May 1978 LER 1978-013-03L for Surry Unit 2 Reactor Brought Critical Below Minimum Insertion Limit on D Control Bank ML19105A0871978-05-0505 May 1978 LER 1978-014-03L for Surry Unit 2 Charging Pump Service Water Pump a Tripped on High Current ML19095A5071978-05-0505 May 1978 Submit Licensee Event Report No. LER-78-007/03L-0 Re Leak on Body to Bonnet Joint Diaphragm Valve 1-CH-98 ML19105A0881978-04-19019 April 1978 LER 1978-006-01T for Surry Unit 2 Review of Fire Protection Yard Piping Revealed That Two Pipe Extensions May Not Have Been Seismically Qualified ML19095A5081978-04-19019 April 1978 Submit Licensee Event Report No. LER-78-006/01T-0 Re Seismically Disqualified Two Pipe Extensions on Fire Protection Yard Piping ML19095A5091978-04-0707 April 1978 Forwarding Licensee Event Report No. LER-78-005/01T-0 Re Westinghouse'S Error in LOCA-ECCS Evaluation Model, Which Will Result in Higher Calculated Peak Clad Temperature ML19105A0901978-04-0606 April 1978 LER 1978-012-01T for Surry Unit 2 Failure to Meet Containment Integrity ML19105A0921978-04-0404 April 1978 LER 1978-011-03L for Surry Unit 1 Loss of Service Water Flow Through Charging Pump Intermediate Seal Cooler ML19095A5101978-04-0404 April 1978 Submit Licensee Event Report No. LER-78-004/03L-0 Re Loss of Service Water Flow Through Charging Pump Intermediate Seal Cooler ML19105A0931978-03-30030 March 1978 LER 1978-008-03L Re Snubber Body in Contact with Structure; LER 1978-009-03L Re Trip of Boric Acid Transfer Pump; & LER 1978-010-03L Re Failure of Pressurizer Channel ML19095A5111978-03-28028 March 1978 Submit Licensee Event Report No. LER-78-003/03L-0 Re Failed Heat Tracing, Panel 8 Circuit 24 ML19095A5121978-03-21021 March 1978 Submit Licensee Event Report No. LER-78-002/01T-0 Re Additional Radial Peaking Factor Surveillance ML19105A0941978-02-27027 February 1978 LER 1978-006-03L Re Failure of Sola Transformer, & LER 1978-007-03L Re Trip of Boric Acid Transfer Pump on Thermal Overload ML19095A5131978-02-24024 February 1978 Submit Licensee Event Report No. LER-78-001/03L-0 Re Hydraulic Shock Suppressor Found Inverted with Empty Reservoir ML19105A0951978-02-16016 February 1978 LER 1978-003-03L Re Erroneous Readings of Loop a Hot Leg Temperature Protection Channel; LER 1978-004-03L Re Unqualified Welding of Two Diaphragm Welds on Heat Exchanger; & LER 1978-005-03L Re Low Current Condition from Heat Tracing ML19105A0971978-02-0202 February 1978 LER 1978-001-03L for Surry Unit 2 Inoperability of Condenser Circulating Water Outlet Valve ML19095A5141978-01-0909 January 1978 Submit Licensee Event Report Nos. LER-77-021/03L-0 & LER-77-022/03L-0 ML19105A0991978-01-0909 January 1978 LER 1977-021-03L Re Routine Sampling of Bast a Revealed Tank Was at Concentration of 11.5%, & LER 1977-022-03L Re Failure of Comparator to Trip During Routine Test of a Steam Generator Level Protection Channel II 2020-02-04
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NRC FORM 366 i U.S. NUCLEAR REGULATORY COMMISSION
(, " 11'.J11 LICENSEE EVENT REPORT CONTROL BLOCK: I IG) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 .
~ I VI A I s IP
- 7 8 9 LICENSEE COOE I s I 1 101 14 ~5
° I 0, - 1 °I O I OIO I O ,~ I O [ 0101 LICENSE NUMBER ~5 26 4 j l 11 I 111 LICENSE TYPE 101 I 10 30 57 CAT 58 CON'T ITDJ :~~~~~ 1.1...J©I o1 s I o1 o Io 12 I 8 I o1010 12 r 2 rs I 7 I 81@1 o I 3J 21 71718 10 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES {10) * . .
inuring normal operation at full'power, a low temperature indication was
[]JI] jobserved on Panel 8, Circuit 24 of the heat tracing system. This circuit
((II] !serves the boric acid filter and piping. This condition was contrary to
~ 1T. S. 3.2.C.5 and is reportable in accordance with T.S. 6.6.2.b(2). The
((:II) !health and safety of the public were not affected because the redundant
~ !he~t tracing circuit was operable.
[§]TI 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUB CODE SUBCODE ITIII 7 8 9 I Pie I@ 1.EJ@ LAJ@
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@ REPORT NUMBER IZ I 8 I I -I Io I o I 3 l I/I I oI -31 ~ 1=J LQ1
- 21 22 23 24 26 27 28 29 30 31 32
( ACTION
_ TAKEN FUTURE ACTION EFFECT ON PLANT SHUTDOWN METHOD HOURS
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CAUSE DESCRIPTION AND CORREC"flVE ACTIONS @ _
[IJ)) !The problem was identified as a short in the wiring to the strip heater o~
CIII] (the boric acid flow transmitter (FT-1113). The wiring was replaced and
[I]}] Jthe circuit returned to service.
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_ __J 80 FACILITY r::;;:;.,. METHOD OF ~
STATUS % POWER OTHER STATUS ~ DISCOVERY DISCOVERY DESCRIPTION ITEl W@ Li I o I ol@I._---=NA:a.:;......._ ___. ~s A 1@_1:--P_a_n_e_l_A_l_a_rm ___________ --1 7 12 44 46 80 S AlTIVITY cJ~TENT lJ RELEASED OF RELEASE AMOUNT OF ACTIVITY@
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/
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E:0 I O10 NUMBER IO l@.______N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
DESCRIPTION~
_J 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY '4J' TYzE DESCRIPTION v:.:;/ NA
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Docket No. 50-280 Report No. 78-003/031-0
- , Surry Power Station, Unit 1 Failed H~at Tracing, Panel 8 Circuit 24
- 1. Description During normal operation, a low temperature indication was observed on Panel 8, Circuit 24 of the heat tracing system. The breaker was found trip-ped. This circuit serves the boric acid filter and associated piping. The event is contrary to.Technical Specification 3.2.C.5 and is reportable in accordance with Technical Specification 6.6.2.b(2).
- 2. Probable Consequences The health and safety of the public were not affected by this event b.ecause the redundant channel of heat :tracing for the components involved was operable. No obstruction to boric acid flow was observed.
- 3. Cause of Event The problem was identified as a short circuit in the w1r1ng to the strip heater on the boric acid flow transmitter (FT-1113).
- 4. Immediate Corrective Action The deteriorat.ed wiring was replaced. The circuit tested satisfactori-ly and was returned to service.
- 5. Scheduled Corrective Action No further corrective action is scheduled or planned.
6 *. Action Taken to Prevent Recurrence No specific action is anticipated. Periodic testing provides a means of diagnosing problems in all heat tracing circuit. Faults are repaired as they are identified.
- 7. Generic Implications There are n~ generic implications of this event in that no manufactured unit or component exhibits a regular failure. Failures are associated with boric acid incursion.