Similar Documents at Ginna |
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Category:Letter
MONTHYEARIR 05000244/20244012024-11-20020 November 2024 R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2024401 IR 05000244/20240032024-11-0808 November 2024 Integrated Inspection Report 05000244/2024003 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000244/20243012024-10-22022 October 2024 Initial Operator Licensing Examination Report 05000244/2024301 ML24286A0022024-10-11011 October 2024 Core Operating Limits Report Cycle 45, Revision 0 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing RS-24-092, Revised Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-09-25025 September 2024 Revised Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000244/20245012024-09-24024 September 2024 LLC - Emergency Preparedness Biennial Exercise Inspection Report 05000244/2024501 IR 05000244/20240052024-08-29029 August 2024 Updated Inspection Plan for R.E. Ginna Nuclear Power Plant (Report 05000244/2024005) ML24234A0922024-08-21021 August 2024 Requalification Program Inspection IR 05000244/20240102024-08-19019 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000244/2024010 ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000244/20240022024-08-0505 August 2024 LLC - Integrated Inspection Report 05000244/2024002 and Independent Spent Fuel Storage Installation Report 07200067/2024001 ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24170A3852024-07-16016 July 2024 R. E. Ginna Nuclear Power Plant - Alternative Associated with Inservice Testing of B Auxiliary Feedwater Pump - PR-03 ML24197A0302024-07-15015 July 2024 LLC - Operator Licensing Examination Approval RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions IR 05000244/20244022024-06-20020 June 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000244/2024402 RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24143A0752024-05-22022 May 2024 Re. Ginna Nuclear Power Plant and Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License ISFSI Casks ML24136A1692024-05-14014 May 2024 And Independent Spent Fuel Storage Installation (ISFSI) - 2023 Annual Radioactive Effluent Release Report and 2023 Annual Radiological Environmental Operating Report ML24134A0042024-05-13013 May 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000244/2024010 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000244/20240012024-04-24024 April 2024 LLC - Integrated Inspection Report 05000244/2024001 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000244/20240112024-04-10010 April 2024 LLC - Fire Protection Team Inspection Report 05000244/2024011 ML24101A0432024-04-10010 April 2024 2024 10 CFR 50.46 Annual Report RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24110A0122024-03-28028 March 2024 2023 Report of Individual Monitoring for R.E. Ginna Nuclear Power Plant LLC, License DPR-18 ML24088A2042024-03-28028 March 2024 R. E. Ginna Nuclear Power Plant - Response to NRC Request for Additional Information Regarding Relief Request Associated with Inservice Testing of ‘B’ Auxiliary Feedwater Pump 05000244/LER-2023-003-01, Re. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam2024-03-0707 March 2024 Re. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam IR 05000244/20230062024-02-28028 February 2024 Annual Assessment Letter for R.E. Ginna Nuclear Power Plant, LLC, (Report 05000244/2023006) IR 05000244/20230042024-02-0505 February 2024 LLC - Integrated Inspection Report 05000244/2023004 ML24026A0112024-01-26026 January 2024 R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of ‘B’ Auxiliary Feedwater Pump IR 05000244/20230102023-12-19019 December 2023 LLC - Age-Related Degradation Inspection Report 05000244/2023010 ML23348A0992023-12-15015 December 2023 R. E. Ginna Nuclear Power Plant – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23347A0092023-12-13013 December 2023 Annual Commitment Change Notification ML23346A0142023-12-12012 December 2023 LLC - Senior Reactor and Reactor Operator Initial License Examinations 05000244/LER-2023-003, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator Level2023-12-11011 December 2023 Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator Level ML23341A1252023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23321A1392023-11-17017 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums 05000244/LER-2023-002, Overtemperature Delta Temperature Reactor Protection System and Auxiliary Feedwater System Actuations on Due to 100% Load Rejection Caused by Turbine Overspeed Circuit Card Failure2023-11-0808 November 2023 Overtemperature Delta Temperature Reactor Protection System and Auxiliary Feedwater System Actuations on Due to 100% Load Rejection Caused by Turbine Overspeed Circuit Card Failure. IR 05000244/20230032023-10-25025 October 2023 LLC - Integrated Inspection Report 05000244/2023003 ML23292A0282023-10-19019 October 2023 LLC - Notification of Conduct of a Fire Protection Team Inspection RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles 2024-09-25
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000244/LER-2023-003-01, Re. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam2024-03-0707 March 2024 Re. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam 05000244/LER-2023-003, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator Level2023-12-11011 December 2023 Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator Level 05000244/LER-2023-002, Overtemperature Delta Temperature Reactor Protection System and Auxiliary Feedwater System Actuations on Due to 100% Load Rejection Caused by Turbine Overspeed Circuit Card Failure2023-11-0808 November 2023 Overtemperature Delta Temperature Reactor Protection System and Auxiliary Feedwater System Actuations on Due to 100% Load Rejection Caused by Turbine Overspeed Circuit Card Failure. 05000244/LER-2023-001, Vital Bus 17 Failed to Load Onto Emergency Diesel Generator B During Load / Safeguard Sequence Testing; Corroded Breaker Shunt Trip Attachment Plunger Found Which Indicated an Earlier Violation of Technical Specification 3.8.12023-06-0707 June 2023 Vital Bus 17 Failed to Load Onto Emergency Diesel Generator B During Load / Safeguard Sequence Testing; Corroded Breaker Shunt Trip Attachment Plunger Found Which Indicated an Earlier Violation of Technical Specification 3.8.1 05000244/LER-2021-002, Valid Auxiliary Feedwater System Actuation on Lowered Steam Generator Level Due to Failure to Control Main Feed Water Flow and Delay in Closing Main Steam Isolation Valves2021-12-0202 December 2021 Valid Auxiliary Feedwater System Actuation on Lowered Steam Generator Level Due to Failure to Control Main Feed Water Flow and Delay in Closing Main Steam Isolation Valves 05000244/LER-2021-001, Service Water Pump a Declared Inoperable Due to Winding Failure Following Replacement Resulting in Violation of Technical Specifications LCO 3.7.8.A (One Service Water Pump Inoperable Greater2021-11-19019 November 2021 Service Water Pump a Declared Inoperable Due to Winding Failure Following Replacement Resulting in Violation of Technical Specifications LCO 3.7.8.A (One Service Water Pump Inoperable Greater . 05000244/LER-2017-0012017-06-16016 June 2017 During Surveillance Testing, Lift Pressure Setpoints on Three Main Steam Safety Valves Found Outside Technical Specifications Limits Due to Stiction., LER 17-001-00 for R. E. Ginna re During Surveillance Testing, Lift Pressure Setpoints on Three Main Steam Safety Valves Found Outside Technical Specifications Limits Due to Stiction 05000244/LER-2016-0012016-04-0707 April 2016 Loss of Station Auxiliary Transformer 12A resulting in automatic start of Emergency Diesel Generator A due to undervoltage signals to safeguards buses 14 and 18., LER 16-001-00 for R. E. Ginna Nuclear Power Plant Regarding Loss of Station Auxiliary Transformer 12A Resulting in Automatic Start of Emergency Diesel Generator A due to Undervoltage Signals to Safeguards Buses 14 and 18 ML0509600362004-12-17017 December 2004 Final Precursor Analysis - Ginna Grid Loop ML0429403762004-10-12012 October 2004 LER 04-S01-00 for R. E. Ginna Regarding Safeguards Event ML0202800752002-01-22022 January 2002 LER 01-S01-00 for R E Ginna Nuclear Plant Re Safeguards Event ML18142A8511978-09-14014 September 1978 LER 1978-007-00 for R. E. Ginna, Bus 16 Circuit Breaker for B Emergency Generator ML18142A8761978-08-0303 August 1978 LER 1978-006-00 for R. E. Ginna, Main Steam Line Snubbers, Positions MS146 Top and Bottom ML18142A8771978-06-0606 June 1978 LER 1978-007-01 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump ML18142B2141978-05-0202 May 1978 LER 1978-005-00 for R. E. Ginna, Unplanned Reactivity Insertion of More than 0.5% K/K While Subcritical ML18142B2131978-03-31031 March 1978 LER 1978-004-00 for R. E. Ginna, Motor Control Center 1C Circuit Breaker to Motor Control Center 1H Trip ML18142B2171978-02-10010 February 1978 LER 1978-002-00 for R. E. Ginna, Power Range Low Range Trip Set Point Test ML18142B2191978-02-0808 February 1978 LER 1978-003-00 for R.E. Ginna, B Steam Generator Tube Leak ML18142B2221977-07-18018 July 1977 LER 1977-008-00 for R.E. Ginna, B Steam Generator Tube Leak ML18192A0761977-07-0707 July 1977 LER 1977-006-00 for R.E. Ginna, C Charging Pump Varidrive on 6/19/1977 ML18142B2281977-06-0808 June 1977 LER 1977-024-00 for R.E. Ginna, Accumulation of Borated Water Near a Valve in Safety Injection System Piping ML18142B2291977-05-27027 May 1977 LER 1976-027-03 for R.E. Ginna, Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak ML18142B2351977-05-16016 May 1977 LER 1977-003-00 for R.E. Ginna, Abnormal Degradation of Steam Generator Tubes ML18142B2211977-03-31031 March 1977 LER 1977-007-00 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump ML18142B2381977-01-27027 January 1977 LER 1977-01-00 for R. E. Ginna, Bus 14 Circuit Breaker for C Safety Injection Pump ML18142B2401977-01-12012 January 1977 LER 1976-030-00 for R.E. Ginna, a Mixed Bed Demineralizer Inlet Piping Leak ML18142B2421977-01-11011 January 1977 LER 1976-028-00 for R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work ML18142B2431977-01-11011 January 1977 LER 1976-029-00 for R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition ML18142B2441977-01-0404 January 1977 LER 1976-027-00 for R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line ML18142B2461976-12-0808 December 1976 LER 1976-026-00 for R. E. Ginna, Unit 1, Controller Output for Cv Spray Naoh Valve 836A Was Less than 10 Ma ML18142B2471976-11-0909 November 1976 LER 1976-025-00 for R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent ML18142B2491976-10-22022 October 1976 LER 1976-024-00 for R. E. Ginna, Unit 1, Accumulation of Borated Water Near Valve in Safety Injection System Piping Between Boric Acid Tanks and Safety Injection Pumps ML18142B2521976-09-14014 September 1976 LER 1976-023-00 for R. E. Ginna, Unit 1, Incorrect Piping Installation for Modification SM 75-9.21 ML18142B2571976-08-19019 August 1976 LER 1976-021-00 for R. E. Ginna, Unit 1, D Bank Group 2 Rcc'S G-3 and G-11 Partially Dropped Into Core ML18142B2531976-08-19019 August 1976 LER 1976-022-00 for R. E. Ginna, Unit 1, Error in Westinghouse Safety Analysis Methods ML18142B2761976-07-19019 July 1976 LER 1976-20-00 for R.E. Ginna, a Accumulator Level Below Technical Specification Limit ML18142B2721976-07-16016 July 1976 LER 1976-19-00 for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor. for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor ML18142B2741976-07-16016 July 1976 LER 1976-20-00 for R. E. Ginna, on Completion of Monthly Surveillance Test of 1A Emergency Generator (Eg), Operator Opened Bus 14 Breaker from Eg and Received Diesel Generator Supply Breaker Overcurrent Trip Alarm ML18142B2751976-07-16016 July 1976 LER 1976-20-00 for R.E. Ginna, Unit 1, on Completion of Monthly Surveillance Test of 1A Emergency Generator (Eg), Operator Opened Bus 14 Breaker from Eg and Received Diesel Generator Supply Breaker Overcurrent Trip Alarm ML18142B2781976-06-21021 June 1976 R. E. Ginna - Supplemental Report on LER 1976-10-00, R. E. Ginna Plant, Containment Purge Supply Valve Having Excessive Leakage During Testing ML18142B2801976-06-0404 June 1976 LER 1976-016-00 for R.E. Ginna, Rod Position Deviation Channel Was Found to Be Inoperable ML18142B2821976-05-24024 May 1976 LER 1976-015-00 for R.E. Ginna, Air Ejector and Blowdown Radiation Monitors Alarmed ML18142B2841976-05-11011 May 1976 LER 1976-013-00 for R.E. Ginna, Drop of Two Control Rods ML18142B2851976-05-10010 May 1976 LER 1976-014-00 for R.E. Ginna, N44 Power Range Detector High Voltage Power Supply Failure ML18142A9761976-04-23023 April 1976 LER 1976-012-00 for R.E. Ginna, Containment Personnel Airlock Handwheel Shaft Seal Excessive Leakage During Testing ML18142A9791976-03-22022 March 1976 LER 1976-010-00 for R. E. Ginna, Containment Purge Supply Value Excessive Leakage During Testing ML18142A9781976-03-19019 March 1976 LER 1976-011-00 for R.E. Ginna, Zero Flow Indicated for Cleanup Filtering Path in Charcoal Filter in Control Room Ventilation System ML18142A9801976-03-12012 March 1976 LER 1978-009-00 for R. E. Ginna, Bus 18 Breaker from a Emergency Generator Overcurrent Relay ML18142A9811976-03-11011 March 1976 LER 1976-008-00 for R. E. Ginna, Abnormal Degradation of Steam Generator Tubes ML18142A9831976-02-28028 February 1976 LER 1976-007-00 for R. E. Ginna, Concerning Relay for Train a Containment Isolation and Containment Ventilation Isolation Failure to Latch 2024-03-07
[Table view] |
Text
CONTROL NO: FILE.INCIDENT REPORT FILE NRI DISTRIBUTION FOR PART 50 DO T MATERIAL (TEMPORARY FORiVI)Pp FROM.Rochester Gas and Electr Corp Rochester, N..Y.L.D White Jr DATE OF DOC 8-22-75 DATE R EC'D LTR TWX 8-26-75 RPT OTHER TO: Mr James P.O'Reilly ORIG not sigHed CC OTHER SENT AEC PDR SENT LOCAL PDR CLASS UNC LASS PROPINFO INPUT NO CYS REC'D DOCKET NO: 50<<244 DESCRIPTION:
Ltr trans the following:
ENCLOSURES:
Abnormal Occurrence'f75-13 on 8-15-75'.concer'ning the transfer of r'efueling water to containment basement~',~~~PLANT NAME BUTLER (L)W/Copies CL~RK (I.)W/Copies PARR (L)W/Copies KNIEL (L)Ml/Copies~REGAN (E)W/Copies LEAR (L)W/Copies SPELS Ml/Copies ZIEMANN (L)Ml/Copies DICKFR (E)W/Copies KNIGHTON (E)Ml/Copies YOUNGBLOOD (E}W/Copies SCHWENCER (L)W/Copies STOLZ (L)Ml/Copies VASSALLO (L)W Copies RPLE (I)opies W/Copies INTERNAL DISTRIBUTION FOR ACTION/INFORMATION
>V~8"-"26"-75 JGB TECH R EVI EW~NRC PDR~SCHROEDER OGC, ROOMi P-50GA~ACCARY GOS" ICK/STAF F KNIGHT~CASE PAW!ICKI GIAMBUSSO SHAO BOYD"~~STE LLO MOOR E,(L)~"-~HOUSTON DEYOUNG (L)"'"'OVAK SKOVHOI T (L)~ROSS GOLLER (L)(Ltr)~IPPOLITO P.COLLINS/TEDESCO DENISE J.COLLINS REG OPR LAI NAS WFlIi E 5 REGION (2)BENAROYA~.~'IPC/P (3)~VO L LME R STEELE DENTON"-'GR IMES GAMMI LL KASTNFR BALLARD SPANGLER E NVI RO MULLER DICKER KNIG HTON YOUNGBLOOD REGAN P ROJ EC1 LD R HAR LESS, LIC ASST R.DIGGS ILI H.GEARIN (L)E.GOULBOURNE (L)P.KREUTZER (E)J.LEE (L)M.RUSHBROOK (L)S.RFED (E)M.SERVICE (L)HSHEPPARD (L)M: SLATER (E)H.SMITH (I.}S.TEETS (L)G.WILLIAMS (E)V, Wll SON (L)R.INGRAM (L)M, DUNCAN A/T I ND BRAITMAN SALTZMAN MELTZ~PLANS IViCDONALD CHAPMAN.DUBF (Ltr)E.COUPE PETERSON HARTFIELD (2)n KLECKER EISENHUr'WIGG)NTOiU
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ROCHESTER GAS AND EL,ECTRIC CORPORATIOH l V~.~l><tory
~I Cell~C o 85'AST AVENUE, ROCHESTER, M.Y.14649 TCIC Slalom I.roN D.ivlf ITE>JB, VICE PACSIDCtiT Il.hfi'iqOHE inc~ceae vie 5.46-2700 August 22, 1975 Mr.James P.O'Reilly, Director U.S.Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406'i)c Wry)(
Subject:
Abnormal Occurrence 75-13, Transfer of refueling water to containment basement R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244
Dear Mr.O'Reilly:
In accordance with Technical Specifications, Article 6.6.2a, the attached report of Abnormal Occurrence 75-13 is hereby submitted.
Two additional copies of this letter and the attachment are enclosed.Very truly yours,~idler d~, P~-L.D.White, Jr.Attachment cc: Mr.Donald P.Knuth (40)Mr.William G;McDonald'(1)~pe(g II@5L~UGLY hg75
- ,g;UCENSEE EVENT REPCI(ITe CONTROL 8LOCK
- LICENSEE NAME Qg N Y R E C'09 LICENSE NUMBER 1 0 0-0 0 0 0 0 14 15 (PLEASE PRIF4T ALL REQUIRED INFORMATIDN)
LICENSE EVENT TYPE TYPF 0 0 4 1 1 1 1~0'1 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE~o<coNT~DI T L 0 7 8 57 58 59 60 61 DOCKET NUMBER EVENT DATE REPORT DATE 5 0-0 2 4 4 0 8 1 5 7 5, 0 8 2 2 7 5 68 69 74 75 60 EVENT DESCRIPTION
~02 Durin erformance of eriodic test PT-2.3 Safe uard Valve eration a flow ath 7 8 9 80[oD3]from refueling water storage tank RWST to containment sum B was inadvertentl esta 7 89 80 t00j4 lished and containment'integrity requirement was violated.Upon receipt of alarms and 7 8 9 80[oa~l evaluating indications, operator immediately secured flow path.A similar ocCIIrrence, 7 0 9 80 Jog which did not involve containment inte rit, was re orted as AO 75-10.Abnormal Occurrence 50-244 75-13)80 COMPONENT MANUFACTURER
'L00LATIDN H 9 9 9 44 47 48 7 0 S PRME SYSTEM CAUSE COMPONENT CODE CODE COMPONENT CODE SUPPUER Q<zj~SP~A V A L V E X E 7 8 9 10 11 12 17 43 CAUSE DESCRIPTION
[oaf Q erator closed MOV-851B erroneousl reo ened it before the next ste to stroke 7 8 9 80~09 MOV-850B, and initialed the procedure step"Close MOV-851B".He noted it was time 80 DISCOVERY DESCRIPTION Operator observations after alarms 7 89 FACILITY, STATUS'OWER Qg E~io o 7 8 9 10 12 13 FORM OF ACTNITY COATENT RELEASEO OF RELEASE Q~g H z NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q~jo~00 0 E NA 7 8 9 11 1'2 13, PERSONNEL INJURIES NUMBER DESCRIPTION
[g~00 0 NA 7 09 11 12 METHOD OF DISCOVERY OTHER STATUS NA a 44 45 46 AMOUNT OF ACTIVITY LOCATION OF RELEASE NA 44 45 00 80 80 OFFSITE CONSEQUENCES Qs]7 8 9 80~10 for his hourly readings and turned to the Head Control (cont'd.on attached sheet)7 8 9 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION
[ice]H 7 89 10 PUBLiCITY 80 80 7 0 9 ADDITIONAL FACTORS Q~g Following evaluation of conditions it was learned that containment integrity requiremen 7 8 9 Qqg]was violated for approximately 3 minutes, and approximately(cont'd.on attached sheet)7 09 NAIViE: 00 Bruce A.Snow PHDNEI 7 16 546 2700, ext~29 1-2 14 QI'i1 011 A*'l 4$, J')'
~~~P-Licensee Event R~~or 50-&$4/75-13 2.Cause Descri tio'n cont'd.Operator to ask him to take them.Returning to the procedure he saw that the next step a'fter the last step he had initialed was to open MOV-850B.Upon the opening of MOV-850B with MOV-851B open, flow was established from the RWST to Sump B.The PORC recommended the following immediate remedial action: 1.Make an inspection of containment to evaluate the extent of any possible damage.2.Pump out Sump B and inspect it for any debris, and inspect the Reactor Coolant Drain Tank located there for any possible damage.3.Have health physics personnel evaluate the extent of airborne contamination.
4..Reprimand the Control Room operator.Further actions to prevent recurrence recommended by PORC are to change PT-2.3 to incorporate requ'irements that 1.No other activities relative to maintenance or testing may b'e performed'which may distract Control Room personnel involved in the performance of this test.In the event any emergency and/or unusual conditions develop, the test is to be terminated until such conditions cease to exist.I 2.The Control Room personnel involved in the test will not have simultaneous Control Room responsibilities relative to normal duties and routine operations.
3.More definite precautions are to be added to PT-2.3 at the steps concerned involving valves which created the inadvertent flow path.I Additional Factors cont'd.k 12,000 gal.of refueling water was transferred to containment.
The Technical Specification for RWST inventory was not violated.There were indications that approximately 1 inch of water had been on the floor.No damage to any safe-guards equipment was noted.Processing the developed waste water is being carried out according to normal procedures.
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3.-'8:=..il)I.(.D+a4OV<50B",+beirut" to 18 JSR.'gaff j P cloec BBV-8588 (Recite to 1.8 RBR pcapp8.I P Open R)V-S5LS (Gecirc to lB RHR pas(p)'," 8 I~.Before.actually opc atiag the switch to close RDV-85iBB he placebo his ie-itiaXa Q the apace provided oa'tbo proccdura a1'ongside this operatioa.-He thea.aoticed that it Mne.tire&r hie'to get'the 14&)Kf geaeratfoa reffdiqys p cad he meeatarily turaod aul ashad the Read Coatrol Oporator to get the rend-%age.~.btu"Be.'taraed arouffd to coatkaae,the procechxr'e and ha sap that tha otep"after the 1ast stop that..hi iaitis?ed van to Q~?SV&50B"Ho had~~'~~h 7 I~~I I c~l occurrence:
875 R3.1 le!1 never:cXoscd:
89V-05XB'e Wcn.ho opcxatcxF the switch to open;80V-0508-ar
~path'van open from the, Refueling; Hater Storage TanTic to contaiment Smrp.9-Shortly, after this.operation the.htgb XeveX alazsc in Sump 9 sounded in.the.controL eocene follcrzcd chart Ey aftazwaxIda.
by a.high XevaX aXszm.in.Su=p CL Sy the time.the operator rcaXf=cd-.
what.hnd happened and.coulct get.l3Ã-85XE closc4 approximatoEy IZ 000 SaXXons of.ReMeing Pater Storage TaaEc water had run'nto Sump 9 avarHcrus6-onto thc containacnt.
basement floor, and drained through.tha floor drains-.ta Sump fL%he appzoxianta tiara.that contcxxcment integrity.
van.vfioXatecE ona 3 csinutes Tha PORC.saat.
at: ISO, revkccced tha occurrence and made the foXZasring.
rccaumdntions." (a)IhEce an Knspwtioa.of contatumnnt;.(b)ReprimancE the contxoX racaa operator (c)Eave the Kcalth Phys%ca perammcE-:take a particuXatn aampXe in the baaeuent of containmant (d)Pump the water fanic Sump PI and ihspect the Sump.8 area for any debris aud also: inspect CElL Reactor Coolant 9?Sin Tank vhich't@Xocatcd in.S~S~iLn.inspection vas made of: containment at.I530'Xhc: on1y evidence of the water vas several usmXX puddles oK water here and them.on.the floor, Sump B fuXL of.'water and'n indfcation.
ia aevaraX-pIacea.that approxfanteZy X~of water had been.on tha basement.floor She plant.continued operation.
at XODX power.aX'I during tha occurrence and no operating problems hnvo been.encounteract since the occurrence I cc Cn L",9~J~F 8 A~~I~Swsrhtoutq RG&E'orp Mhitc Jr~RG&E Corp Swaeh'~RG&R Corp Sacs RG&K Cozy CharXeadf Plat t, Superintendent.
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