Similar Documents at Ginna |
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Category:Licensee Event Report (LER)
MONTHYEAR05000244/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
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
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
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
ML18142B2531976-08-19019 August 1976
LER 1976-022-00 for R. E. Ginna, Unit 1, Error in Westinghouse Safety Analysis Methods
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
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
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
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
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
ML18143A4971976-02-19019 February 1976
LER 1976-006-00 for R.E. Ginna, Malfunction of Undervoltage Relay During Surveillance Test on 2/6/1976
ML18142B8941976-02-0606 February 1976
LER 1975-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage
ML18142B8931976-02-0606 February 1976
LER 1976-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage
ML18142B8951976-01-26026 January 1976
LER 1975-013-00 for R. E. Ginna, 30 Day, B Steam Generator Tube Degradation
ML18142B8961976-01-0808 January 1976
LER 1975-012-00 for R. E. Ginna, (30-Day Report), Charging Pump Discharge Drain Line Pinhole Leak
ML18142B8971976-01-0808 January 1976
LER 1975-012-00 for R. E. Ginna, (30-Day Report), Charging Pump Discharge Drain Line Pinhole Leak
2017-06-16
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LICISEE EVEiVT REPORT CONTROL BLOCK: (PLEASE PRINT ALL REQIjIRED INFORIVlATIOM<
a-s 1 LICENSEE LICENSE ~ EV ENT NAME UCENSE NUMBER TYPE TYPE
[oaf N Y R E G 1 0 0 0 0 0 0 0 0 0 '4 I I 1 I ~0132
~
7 89 14 15 25 26 30 31 II CATEGORY REPORT REPORT SOURCE 'OCKET NUMBER EVENT DATE REPORT DATE IoD1]coN'i TYPE 0 L 0 5 0 0 2 4 4 I 0 0 8 7 6 0 6 0 8 7 7'4 7 8 57 58 59 60 61 ~ 68 69 75 BC EVENT DESCRIPTION Qpg During normal operations an auxiliary operator found an accumulation of borated water 7 8 9 80
[pp~] near a valve in the Safety Injection System piping between the Boric Acid Tanks and )
7 89 80 IH8 9 I Safety Injection Pumps. Further investigation revealed a leak in a section of 8" 7 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 COMPONENT CODE CODE COMPONENT CODE SUPPER MANUFACTURER VCLATQN
~or ~SF F P I P E II jI N K 0 5 5 N 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION EH0 8 As a result of metallurgical analysis and metallographic examinations, chloride stress I Kl09 corrosion cracking is believed to be the cause of the leaks. As the investigation con-tinued, further information was submitted in a supplemental (cont'd. on attached sheet) 7 89 80 FACIUTY METHOD OF STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY OESCAIPTION E ~IO O NA b 45 46 B o erator
, 7 8 9 10 12 13 44 FORM OF r ACTIVITY . COhITENT AELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATiON OF RELEASE Q~g s z NA NA 7 8 9. 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
~ts ~00 0 S NA 80 7 8 9 11 12 13 PERSOiVNEL INJURIES NUMBER DESCRIPTION
~i~ ~00 o NA 60 7 89 11 12 OFFSITE CONSEQUENCES
~15 NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Q~g L See Event Description
'7 8 9 10 80 '
PUBLICITY Press release on October 8, 1976 7 89 ADDITIONAL FACTORS
~18 7 89 Ii+s
.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):
All welds 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 will continue to be examined in accordance with the require-ments of the Ginna Station Inservice Inspection Program to assure the continued integrity of these systems.
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