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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
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LICISEE EVEiVT REPORT (PLEASE PRINT ALLREQIjIRED INFORIVlATIOM<
CONTROL BLOCK:
a-s 1
LICENSEE NAME Y
R E
G 1
EVENT TYPE LICENSE
~
TYPE I
I 1
I
~01 UCENSE NUMBER 0
0 0 0
0 0
0 0 0
'4 25 26 30 31 32 14 15 REPORT REPORT II CATEGORY TYPE SOURCE
'OCKET NUMBER IoD1]coN'i~
0 L
0 5
0 0 2
4 4
I 7
8 57 58 59 60 61
~
68 69 EVENT DESCRIPTION Qpg During normal operations an auxiliary operator found EVENT DATE REPORT DATE 0
0 8
7 6
0 6
0 8
7 7'4 75 BC an accumulation of borated water 80 7
89 IH I Safety Injection Pumps.
Further investigation revealed a leak in a section of 8" 7
8 9 80 Jog Schedule 10 stainless steel pipe between valves 826A and 826B.
The unit was taken 7
8 9 80
[@pe to cold shutdown as recommended by PORC.
Leaks were (cont' on attached sheet) 7 8 9 PAME 80 SYSTEM CAUSE COMPONENT CODE CODE COMPONENT CODE SUPPER VCLATQN
~or ~SF F
P I
P E II jI N
K 0
5 5
N 7
8 9 10 11 12 17 43 48 CAUSE DESCRIPTION 0 8 As a result of metallurgical analysis and metallographic examinations, chloride stress I
COMPONENT MANUFACTURER 44 47 EH 09 corrosion cracking is believed to be the cause of the leaks.
As the investigation con-Kl tinued, further information was submitted in a supplemental (cont'd. on attached sheet) 7 8 9 80
[pp~]
near a valve in the Safety Injection System piping between the Boric Acid Tanks and
)
7 89 FACIUTY STATUS
% POWER E
~IO O
NA
, 7 8
9 10 12 13 FORM OF r
ACTIVITY.
COhITENT AELEASEO OF RELEASE AMOUNT OF ACTIVITY Q~g s
z NA 7
8 9.
10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
~ts ~00 0
S NA 7
8 9 11 12 13 PERSOiVNEL INJURIES NUMBER DESCRIPTION
~i~ ~00 o
NA 7
89 11 12 OFFSITE CONSEQUENCES
~15 NA OTHER STATUS METHOD OF DISCOVERY b
44 45 46 44 45 Press release on October 8, 1976 ADDITIONAL FACTORS
~18 7
89 Ii+s 7
8 9 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Q~g L
See Event Description
'7 8 9 10 PUBLICITY 7
89 DISCOVERY OESCAIPTION B
o erator LOCATiON OF RELEASE NA 80 80 60 80 80
.Licensee Event Repo.i
.. Reportable Occurrence 50-2
/76-24 Event Descri tion (cont'd.)
found in two sections of pipe, and liquid penetrant and ultrasonic examina-tion of 75 welds and the piping associated with those welds in the boric acid tank outlet piping revealed five other sections of pipe ol'ittings with indications.
All seven of these components of the piping system containing leaks or indications were replaced.
(Reportable Occurrence 76-24).
Cause Descri tion (cont'd.)
report, dated February 10, 1977, which supported this conclusion, and pro-vided the corrective action performed and being considered.
The supplemental
,report also described our December 21, 1976 response to IE Circular 76-06 which stated that during the 1977 refueling and maintenance ou)age additional testing and examination would be performed on piping and selected welds in the containment spqay and safety injection systems.
During the 1977 refueling and maintenance outage the boric acid storage tank outlet piping was modified to eliminate all inaccessible portions.
The exam-inations and testing consisted of the following:
1.
Nine welds in the Boric Acid Piping were ultrasonically examined.
As this included the remaining two welds which were previously inaccessible, all the welds of the heat traced boric acid supply piping to the safety injection pumps have been ultrasonically examined.
2.
Five welds in the Containment Spray Pump Discharge piping inside con-tainment were ultrasonically examined.
3.
The Boric Acid Piping to the Safety Injection Pumps and the containment spray pump suction piping was hydrostatically tested to 280 psig (mini-mum).
4.
The containment spray pumps discharge piping was.hydrostatically tested to 380 psig (minimum).
5; The Safety Injection Pumps Discharge Piping was hydrostatically tested to 1880 psig (minimum).
6..
The Spray Additive Tank was pressure tested, using a nitrogen medium, to 375 psig (minimum):
Allwelds and piping inspected and tested as. listed above were found to be acceptable.
The welds and piping in the Safety Injection and Containment Spray Systems willcontinue to be examined in accordance with the require-ments of the Ginna Station Inservice Inspection Program to assure the continued integrity of these systems.
I