Similar Documents at Ginna |
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Category:Letter
MONTHYEARML24339B7292024-12-18018 December 2024 Amd - Constellation - Adoption of TSTF-591 ML24353A0522024-12-18018 December 2024 R.E Ginna Nuclear Power Plant - Annual Commitment Change Notification RS-24-077, Application to Revise Technical Specifications for Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2024-12-0909 December 2024 Application to Revise Technical Specifications for Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process IR 05000244/20244012024-11-20020 November 2024 R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2024401 ML24319A0102024-11-15015 November 2024 24-04 Ginna OI Unsub to Licensee 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 RS-24-010, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102024-01-31031 January 2024 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 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 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-2018-002, Loss of Offsite Power to Vital Bus Due to Human Error Causes Automatic Actuation of Emergency Diesel Generator a2018-12-20020 December 2018 Loss of Offsite Power to Vital Bus Due to Human Error Causes Automatic Actuation of Emergency Diesel Generator a 05000244/LER-2018-001, R.E. Gina Nuclear Power Plant Regarding Leakage in Reactor Coolant System Pressure Boundary Through an Existing Weld in Original Installation Equipment Due to Orifice Wear/Erosion Resulting in Progressively Increasing System2018-03-23023 March 2018 R.E. Gina Nuclear Power Plant Regarding Leakage in Reactor Coolant System Pressure Boundary Through an Existing Weld in Original Installation Equipment Due to Orifice Wear/Erosion Resulting in Progressively Increasing System . 05000244/LER-1917-001, R. E. Ginna Re During Surveillance Testing, Lift Pressure Setpoints on Three Main Steam Safety Valves Found Outside Technical Specifications Limits Due to Stiction2017-06-16016 June 2017 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-2016-001, 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 182016-04-0707 April 2016 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 05000244/LER-2015-001, Regarding Human Performance Error During Data Collection Activity Results in a Condition Prohibited by Technical Specification 3.1.7, Rod Position Indication2015-08-26026 August 2015 Regarding Human Performance Error During Data Collection Activity Results in a Condition Prohibited by Technical Specification 3.1.7, Rod Position Indication 05000244/LER-2014-003, Regarding a Emergency Diesel Generator Output Breaker Fails to Close During Routine Surveillance Testing, Resulting in a Condition Prohibited by Technical Specifications and a Potential Inability to2014-11-0606 November 2014 Regarding a Emergency Diesel Generator Output Breaker Fails to Close During Routine Surveillance Testing, Resulting in a Condition Prohibited by Technical Specifications and a Potential Inability to 05000244/LER-2014-002, Regarding Unanalyzed Condition Due to Postulated Hot Short Fire Event Involving DC Control Circuits Affecting Multiple Fire Areas2014-05-0808 May 2014 Regarding Unanalyzed Condition Due to Postulated Hot Short Fire Event Involving DC Control Circuits Affecting Multiple Fire Areas 05000244/LER-2014-001, Re Total Particulate Concentration in B Emergency Diesel Generator Fuel Oil Storage Tank Exceeded Acceptance Criteria - Cause Attributed to Contamination from Using a Temporary Fuel Oil Storage Tank2014-03-19019 March 2014 Re Total Particulate Concentration in B Emergency Diesel Generator Fuel Oil Storage Tank Exceeded Acceptance Criteria - Cause Attributed to Contamination from Using a Temporary Fuel Oil Storage Tank 05000244/LER-2013-003, Regarding Unanalyzed Condition for Potential Floodwater Intrusion Into Vital Battery Rooms2013-11-18018 November 2013 Regarding Unanalyzed Condition for Potential Floodwater Intrusion Into Vital Battery Rooms 05000244/LER-2013-002, Reactor Trip Due to Generator Trip During Main Generator Reactive Power Testing2013-09-17017 September 2013 Reactor Trip Due to Generator Trip During Main Generator Reactive Power Testing 05000244/LER-2013-001, For R.E. Ginna Nuclear Power Plant, Regarding Unanalyzed Condition Due to Missing Barrier2013-05-31031 May 2013 For R.E. Ginna Nuclear Power Plant, Regarding Unanalyzed Condition Due to Missing Barrier 05000244/LER-2012-001, Regarding Automatic State of B Emergency Disesel Generator Caused by Loss of Offsite Circuit 767 Due to Wildlife2012-07-26026 July 2012 Regarding Automatic State of B Emergency Disesel Generator Caused by Loss of Offsite Circuit 767 Due to Wildlife 05000244/LER-2011-003, Regarding Reactor Trip Due to Failure of Tubine Lube Oil Piping2011-12-0202 December 2011 Regarding Reactor Trip Due to Failure of Tubine Lube Oil Piping 05000244/LER-2011-002, Regarding Train B Actuation Logic Circuit to Operate the B MSIV Was Not Operable2011-10-17017 October 2011 Regarding Train B Actuation Logic Circuit to Operate the B MSIV Was Not Operable 05000244/LER-2011-001, Re Unanalyzed Condition Due to Postulated Fire Causing a Station Blackout2011-10-0404 October 2011 Re Unanalyzed Condition Due to Postulated Fire Causing a Station Blackout 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 05000244/LER-2078-007, For R. E. Ginna, Bus 16 Circuit Breaker for B Emergency Generator1978-09-14014 September 1978 For R. E. Ginna, Bus 16 Circuit Breaker for B Emergency Generator 05000244/LER-2078-006, R. E. Ginna, Main Steam Line Snubbers, Positions MS146 Top and Bottom1978-08-0303 August 1978 R. E. Ginna, Main Steam Line Snubbers, Positions MS146 Top and Bottom ML18142A8761978-08-0303 August 1978 LER 1978-006-00 for R. E. Ginna, Main Steam Line Snubbers, Positions MS146 Top and Bottom 05000244/LER-2078-007-01, Bus 14 Breaker for C Safety Injection Pump1978-06-0606 June 1978 Bus 14 Breaker for C Safety Injection Pump ML18142A8771978-06-0606 June 1978 LER 1978-007-01 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump 05000244/LER-2078-005, For R. E. Ginna, Unplanned Reactivity Insertion of More than 0.5% K/K While Subcritical1978-05-0202 May 1978 For R. E. Ginna, Unplanned Reactivity Insertion of More than 0.5% K/K While Subcritical 05000244/LER-2078-004, For R. E. Ginna, Motor Control Center 1C Circuit Breaker to Motor Control Center 1H Trip1978-03-31031 March 1978 For R. E. Ginna, Motor Control Center 1C Circuit Breaker to Motor Control Center 1H Trip 05000244/LER-2078-002, R. E. Ginna, Power Range Low Range Trip Set Point Test1978-02-10010 February 1978 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 05000244/LER-2078-003, B Steam Generator Tube Leak1978-02-0808 February 1978 B Steam Generator Tube Leak 05000244/LER-2077-008, B Steam Generator Tube Leak1977-07-18018 July 1977 B Steam Generator Tube Leak ML18142B2221977-07-18018 July 1977 LER 1977-008-00 for R.E. Ginna, B Steam Generator Tube Leak 05000244/LER-2077-006, C Charging Pump Varidrive on 6/19/19771977-07-0707 July 1977 C Charging Pump Varidrive on 6/19/1977 ML18142B2281977-06-0808 June 1977 Accumulation of Borated Water Near a Valve in Safety Injection System Piping 05000244/LER-2076-030-03, Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak1977-05-27027 May 1977 Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak 05000244/LER-2077-003, Abnormal Degradation of Steam Generator Tubes1977-05-16016 May 1977 Abnormal Degradation of Steam Generator Tubes 05000244/LER-2077-007, Bus 14 Breaker for C Safety Injection Pump1977-03-31031 March 1977 Bus 14 Breaker for C Safety Injection Pump 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 05000244/LER-2077-001, R. E. Ginna, Bus 14 Circuit Breaker for C Safety Injection Pump1977-01-27027 January 1977 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 05000244/LER-2076-030, A Mixed Bed Demineralizer Inlet Piping Leak1977-01-12012 January 1977 A Mixed Bed Demineralizer Inlet Piping Leak 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 05000244/LER-2076-029, R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition1977-01-11011 January 1977 R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition 05000244/LER-2076-028, R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work1977-01-11011 January 1977 R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work ML18142B2441977-01-0404 January 1977 LER 1976-027-00 for R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line 2024-03-07
[Table view] |
LER-2075-010, For R. E. Ginna, Unresponsive Emergency Generator Governor Control Switch |
Event date: |
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Report date: |
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2442075010R00 - NRC Website |
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text
TRIBUTION FOR PART 50 DOCK~MATERIAL (TEMPORARY FORM)
CONTROL NQ:
13583 FILE. XNCIDENZ REPORT FIT FROM.
Rochester Gas Imi Elec.
Co Rochester;.N;Y'..
e Jr DATE OF DOC 12-2-75 12-4-75 XXX DATE REC'D LTR TWX RPT OTHER TO:
James P.O'Reill ORIG Noae'C OTHFR 3
SENT AEC PDR SENT LOCAL PDR CLASS UNCLASS IlXX PROP INFO INPUT NO CYS REC'D
.3 DOCKET NO:
50-244 DESC R IPTION:
Letter trans the follwoing....
4 PLANT NAME:
RE Ginna 8
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ENCLOSURES:
Unusual. Event Report h'. 75-10; on.1.1-6-75, Concerning a, Unresponsiye Emirgency Generator Govenor.........'. W/Attabbaierlt;.',/
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ROCHESTER GAS AND ELEC FRIC CORPORATION LEON D. WHITE. JII.
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Subject:
Unusual Event 75-10, Unresponsive Emergency Generator Governor R. E. Ginna Nuclear Power Plant, Unit No. '1 Docket No. 50-244
Dear Mr. O'Reilly:
In accordance with Technical Specifications, Article 6.6.2b, the attached report of Unusual Event 75-10 is hereby submitted.
Two additional, copies of this letter and the attachment are enclosed.
Very truly yours, L. D. White, Jr.
Attachment cc:
Mr. Donald F. Knuth (30)
Mr. William G. McDonald (3)
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CONTROL. BLOCK:
1 LICENSEE EVENT REPORT (PLEASE. PAINT ALLREQUIRED INFORMATIDf)I)
LICENSEE NAME EVENT TYPE LICENSE TYPE 4
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1 1
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)4 YREG 1
30 31 32 25 26 14 15 7
09 LICENSE NUMBER 00 0000'0 00 CATEGORY [OD1] CON'T~
7 8
57 58 REPORT REPORT TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE L
~I 0
5 0 0 2
4 4
1 1
0 6
7 5
2 0
2 7
5 59 60 61 68 69 74 75 80
EVENT DESCRIPTION
Jog urin erformance of PT-12. 1 Emer enc Generator 1A immediatel followin close and 7
0 9 00 [pg trip of a service water pump breaker, the generator wattmeter indicated no response to 7
0 9 80 [pg~] switch to check currents the meter indication changed to about full load, and subsequent 7
8 9 80 Qpg anipulation of the governor control verified proper response. (Unusual Event 50-244/75-10),
80 7
0 9 SYSTEM
CAUSE
CODE CODE COMPONENT CODE [oa~) ~EE
~F G
3 N
3 R
1) 7 8 9 10 11 12 17
~ CAUSE DESCRIPTION PRME COMPONENT SUPPUER COMPONENT MANUFACTURER A
1 5
2 43 47 40
~08 NA 7
8 9 00 Jog Recommended actions to determine the cause and remedial action taken are given on the 7
89 00 peration of the governor control switch.
During operation of the phase current selector 7
0 9
~10 attached sheet.
OTHER STATUS AMOUNT OF ACTIVITY 7
09 FACIUTY STATUS
% POWER
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8 9
10 12 13 FORM OF 7
0 9
10 11 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
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PERSONNEL INJURIES NUMBER
DESCRIPTION
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NA 7
09 11 12 OFFSITE CONSEQUENCES METHOD OF OISCOVEAY b
44 45 46 44 45 DISCOVERY DESCRIPTION NA LOCATION OF AELEASS NA 00 00 00 00 80 80
~15 7
09 LOSS OR DAMAGE TO FACILITY TYPE
DESCRIPTION
Q~g z
7 09 10 PUBLICITY [is~]
7 89 ADDITIONAL FACTORS
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NA NA NA NA 00 00 80 80 7
09 NAME:
Bruce A. Snow 80'HDNE.716/546-2700, ext.
291-7'FO Sl 04)~
Licensee Event Report Unusual Event 50-244/75-04 PORC Recommendations 1.
Check wiring of emergency generator metering.
2.
Perform test procedure PT-12.1 Emergency Diesel Generator 1A to the extent necessary.to observe proper indicated response to generator governor control once each calendar week with appropriate personnel to observe the generator start and operation, to include station mechanics and electricians.
This is to begin on the following day, 1 1/7/75, and continue until'the next scheduled monthly surveillance.
Remedial Action Taken 1.
The appropriate personnel have checked and tightened all connections of the emergency generator metering wiring.
2.
Satisfactory response has been demonstrated on each of the five tests conducted following the incident.
'his action is being documented in Corrective Action Report CAR-1047;
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05000244/LER-2075-001, For R. E. Ginna, Drop of Two Control Rods | For R. E. Ginna, Drop of Two Control Rods | | 05000244/LER-2075-002, For R. E. Ginna, Failure of the 1C Safety Injection Pump to Start Manually from Bus 16 Ginna Station | For R. E. Ginna, Failure of the 1C Safety Injection Pump to Start Manually from Bus 16 Ginna Station | | 05000244/LER-2075-003, R. E. Ginna, Failure of 1C Safety Injection Pump to Start Manually from Buss 16 | R. E. Ginna, Failure of 1C Safety Injection Pump to Start Manually from Buss 16 | | 05000244/LER-2075-004, For R. E. Ginna, Failure of the Main Steam Line Isolation (Msli) Valves Solenoid Valves to Operate Properly at Ginna Station | For R. E. Ginna, Failure of the Main Steam Line Isolation (Msli) Valves Solenoid Valves to Operate Properly at Ginna Station | | 05000244/LER-2075-005, For R. E. Ginna, Failure of the IC Safety Injection Pump to Start Manually from Bus 16 at Ginna Station | For R. E. Ginna, Failure of the IC Safety Injection Pump to Start Manually from Bus 16 at Ginna Station | | 05000244/LER-2075-006, Transfer of a Steam Generator Level Control Input Signal from Level Transmitter LT-461 to Level Transmitter LT-462 on 9/2/75 | Transfer of a Steam Generator Level Control Input Signal from Level Transmitter LT-461 to Level Transmitter LT-462 on 9/2/75 | | 05000244/LER-2075-007, For R. E. Ginna, Abnormal Degradation of Steam Generator Tubes | For R. E. Ginna, Abnormal Degradation of Steam Generator Tubes | | 05000244/LER-2075-008, For R. E. Ginna, Control Rod G-5 Lift Coil Open Circuit | For R. E. Ginna, Control Rod G-5 Lift Coil Open Circuit | | 05000244/LER-2075-009, For R. E. Ginna, Reactor Coolant Iodine-131 Equivalent Activity | For R. E. Ginna, Reactor Coolant Iodine-131 Equivalent Activity | | 05000244/LER-2075-010, For R. E. Ginna, Unresponsive Emergency Generator Governor Control Switch | For R. E. Ginna, Unresponsive Emergency Generator Governor Control Switch | | 05000244/LER-2075-011, For R. E. Ginna, (30-Day Report), Charging Pump Disclosure Drain Line Pinhole Leak | For R. E. Ginna, (30-Day Report), Charging Pump Disclosure Drain Line Pinhole Leak | | 05000244/LER-2075-012, For R. E. Ginna, (30-Day Report), Charging Pump Discharge Drain Line Pinhole Leak | For R. E. Ginna, (30-Day Report), Charging Pump Discharge Drain Line Pinhole Leak | | 05000244/LER-2075-013, For R. E. Ginna, 30 Day, B Steam Generator Tube Degradation | For R. E. Ginna, 30 Day, B Steam Generator Tube Degradation | |
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