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U S. NUCLEt.N MCULATOAV COMMISE ON NRC Perm 384 I.PPROvf D OMG NO 3150 4104 AJi
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LICENSEE EVENT REPORT (LER)
FAGE 43e DOCKET NUMSER (2) 0 l5 l 010 l 013 l 619,1 lOFl015 FACILITY NAI AE til McGuire Nuclear Station, Unit 1 Control Area Ventilation / Chilled Water System Inoperable Due to Thermostat Set Lov and Refrigerant Leak OTHER F ACILITIES INVOLVED 18) ty4NT DATE Ill LER NUMWER (S)
REPORT DATE (7)
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DOCKET NUM9ER 51 MONTH DAY YEAR VEAR n' '
MONTH OAV YEAR McGuire Unit 2 o l5l0 l0lo g 3,7l0 0l 1 0l7 8
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TELEPHONE NUMSER NAME ARE A CODE Phillip B. Nardoci - Licensing 7;Og4 3l7l3 l i 7 4 p l2 i
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YES IH yee complete RKPECTED SUDMISSION DATil ASSTR ACT flert to f 400 speces. te, approspewy freesa nye spece typewretree haest (161 On January 7, 1987, at 0328, the Train B Chiller for the (Shared) Control Area Ventilation / Chilled Water (VC/YC) system tripped on refrigerant low temperature because the chiller thermostat setting was positioned too cold. Train A had been declared inoperable at 0200 due to a loss of refrigerant from a leaking threaded fitting on the chiller's oil cooler. With both trains of VC/YC inoperable, Units 1 and 2 entered Technical Specification (T.S.) 3.0.3, requiring one train of VC/YC to be made operable within one hour.
Units 1 and 2 were in Mode 1, Power Operation, at 100% power at the time of the incident. At 0428, power reduction of both units was begun at the rate of IMW per minute.
The Train B Chiller refrigerant low temperature cutout switch was manually reset and the thermostat was adjusted for warmer exiting chilled water. At 0640, VC/YC Train B was declared operable and the units secured from T.S. 3.0.3.
Refrigerant was added to the Train A Chiller and VC/YC Train A declared operable at 1315.
It could not be determined when the Train B Chiller thermostat had been adjusted to the lower setting. The (alowly) leaking fitting will be repaired once qualified materials are obtained.
The loss of both trains of VC/YC did not last long enough to cause any Control Room Area High Temperature Alares. The health and safety of the public were not affected.
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.U S NUCLEAR FEGULAT0lY COMMIS$10N LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Ae*RovEo oMa No siso-oio4 E xPIRES 8/3i'85 F ACILiiY NAME (11 DOCK E T NUMSE R (2)
LER NUM8ER (6)
PAGE(31 n.R
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- - W,0 0l0 Ol2 Of i0 15 McGuire Nuclear Station - Unit 1 o l5 l0 l0 j o l 316 l9 8l7 d 0] 1 tex 1 IM more spese os requent use e#tene!NRC form 366Nsl(1h On January 7,1987, at 0328, the Train B Chiller [EIIS:CHU] for the (Shared)
Control Area Ventilation / Chilled Water (VC/YC) system [EIIS:VI] tripped on refrigerant low temperature because the chiller thermostat [EIIS:TH] setting was positioned too cold. Train A had been declared inoperable at 0200 due to a loss of refrigerant from a leaking threaded fitting [EIIS: PSF] on the chiller's oil cooler [EIIS:CLR]. With both trains of VC/YC inoperable. Units 1 and 2 entered Technical Specification (T.S.) 3.0.3, requiring one train of VC/YC to be made operable within one hour. Units 1 and 2 were in Mode 1, Power Operation, at 100%
power at the time of the incident. At 0428, power reduction of both units was begun at the rate of IMW per minute. By 0455, the Control Room Hi Temperature procedure was fully implemented. The Control Room reached a maximum temperature of approximately 83 degrees-F.
The Train B Chiller refrigerant low temperature cutout switch [EIIS:TS] was manually reset and the thermostat was adjusted for warmer exiting chilled water.
At 0640, VC/YC Train B was declared operable and the units secured from T.S.
3.0.3.
After the control area temperature had been reduced, refrigerant was added to the Train A Chiller, and VC/YC Train A declared operable at 1315.
EVALUATION:
Background
The VC/YC systema are shared by both units and maintain the environment in the Control Room, Cable Room, Battery Room, Switchgear Rooms, and Electrical Penetration Rooms. These environments must be maintained within acceptable temperature limits for proper equipment operation and operator occupancy during normal and post accident conditions.
l T.S. 3.7.6 states when one train of the VC/YC system is inoperable in Modes 1, 2, 3, or 4, the inoperable train must be restored to operable status within seven days or be in at least Hot Standby within the next six hours and in Cold Shutdown within the following thirty hours. When both trains of the VC/YC system are inoperable T.S. 3.0.3 requires that within one hour, action must be initiated l
to place the units in a mode in which the technical specification does not apply.
l The chillers in the VC/YC system have several machine protection circuits. The refrigerant low temperature cutout, with a manual reset, protects the chiller tubes from freezing by tripping the compressor [EIIS: CMP] if the refrigerant temperature drops too low. The exiting chilled water low temperature cutout stops the compressor if the exiting chilled water drops below its setpoint.
Description of Incident l
l On January 7, 1987, at approximately 0200, VC/YC Train B was shutdown to allow l
maintenance work on the non-safety related outside air fan (EIIS: FAN] and for rotation of VC/YC Trains A and B.
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.U S. NUCLEl.R RECULATOIY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AreaovEo ov8 No. 3 iso-oio4 EXPIRES 8/3i>85 F ACILITY NAME ili DOCM ET NUMBER (21 LER NUM8ER (66 PAGE13) vgAm gy.
McGuire Nucicar Station - Unit 1 ol5jojojol3l6f 8 l7 0l 0l 1 q0 0 l3 OF 0 l5 rEn a m c.. w a..ar,w,.nwrc ram mmn At 0200, VC/YC Train A had failed two start attempts requiring Train B to be restarted. VC/YC Train A was declared inoperable under T.S. 3.7.6 and investigation begun to determine why the Train A Chiller would not start.
At 0328, VC/YC Train B tripped due to the refrigerant low temperature cutout protection circuit actuation. Although no alarms were received in the control room or at the local panel indicating the chiller had tripped, personnel troubleshooting the Train A Chiller informed Control Room personnel that Train B had tripped (a work request was initiated to repair the problems associated with the VC chillers not giving alarms to the HVAC annunciators [EIIS: ANN] when the chillers trip). With both trains of VC/YC inoperable, Units 1 and 2 entered T.S.
3.0.3, requiring action to begin shutting down the units if one train was not made operable within one hour. A work request was written to investigate and repair the VC/YC Train B Chiller.
At 0428, after being unable to return the VC/YC system to operable status, Units 1 and 2 commenced shutdown at the rate of IMW per minute. At approximately 0445, the Control Room Hi Temperature Procedure had been fully implemented to alleviate temperature increases. At 0455, the control room had reached a maximum temperature of 83 degrees-F, (approximately 15 degrees-F above normal), during this event. This elevated temperature caused the 7300 Process Control system [EIIS:JE] to have erratic readings on Channel IV Main Steam pressure for D Steam Generator (S/G) [EIIS:SG]. Station personnel were concerned that if the heat induced erratic steam pressure readings from the 7300 Process Control esbinets caused two channels on one S/G to drop, a safety injection would occur.
At 0505, the Train B refrigerant low temperature cutout switch was manually reset and the chiller was able to be started. However, the Train B VC/YC Chiller tripped two more times due to refrigerant low temperature chiller protection.
It was determined that the thermostat controlling the exiting chiller water temperature was set too cold for proper operation. This resulted in the chiller shutting down to prevent the refrigerant tubes from getting too cold and freezing.
The chiller was again reset and the exiting chiller water thermostat adjusted to a warmer position to obtain the proper temperature. At 0620, VC/YC Train B was running consistently and at 0640, Train B was declared operable and the units secured from T.S. 3.0.3 and the power reduction.
Investigation of the VC/YC Train A inoperability determined that the chiller was low on refrigerant. The loss of refrigerant was due to a leak (discovered in September, 1986) from a threaded fitting to the chiller's oil coolcr.
Refrigerant was added and the refrigerant low tcmperature cutout switch reset. The chiller was successfully run and VC/YC Train A declared operable at 1315.
NRC FORM M6A 19 83)
e Encform364A U S. NUCLE 12 KEGULATOAY COMMIS&loN LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AePaoveo ous No siso-oio4 EXPIRES S!3166 FACILif Y NAME til DOCKET NUMBER (2)
LER NUMBER (4)
PAGE(3)
VEAR
' "hf k gin McGuire Nuclear Station - Unit 1 o [s g o j o g o l 3l6 l 9 8l7 0l 0l 1 0l0 0 l4 0l5 or 1 Ext W more space se reeswed, use edirtanet MC form 366Kal 0h Conclusion The inoperability of both trains of the VC/YC system was not due to a common mode failure. Train A inoperability resulted from a low refrigerant charge in the chiller.
(Low refrigerant charge causes supercooling of the refrigerant due to an increase of the refrigerant expansion volume.) Refrigerant had been slowly leaking out of a threaded fitting on a pipe to the chiller's oil cooler for several months. The fitting could not be repaired without cutting the connected copper piping. Due to delays in obtaining qualified materials to repair the leak, personnel had been informally checking the refrigerant charge on a weekly basis using the Control Room Chiller Preventative Maintenance procedure.
Since the refrigerant charge can be checked only while the chiller package is running, the status of the charge was unknown.
It is suspected that enough charge leak-off occurred while the chiller package was not running to prevent the start attempts on January 7, 1987.
The inoperability of Train B was the result of the exiting chilled water thermostat being set too cold for the chiller to achieve. When the exiting chilled water thermostat is set below the cooling capability of the chiller, the chiller attempts to cool the water to the demanded temperature. On January 7, 1987, the refrigerant temperature dropped to the setpoint of the refrigerant low temperature cutout and the chiller tripped.
The thermostat required an edjustment (warmer) to allow the chiller to continue to operate.
The VC/YC chiller thermostat control knobs do not change position due to vibration. Personnel involved say no one made any adjustments to the Train B chiller prior to repair personnel. The preventative maintenance procedure used to work on the VC/YC Chillers does not have any documentation for 'AS FOUND' and 'AS LEFT' readings for the chiller controls. Therefore, it could not be determined when the thermostat had been adjusted to the colder setting.
A review of past McGuire Reports revealed there have been three incidents which had the VC/YC Chillers trip on low refrigerant temperature. The incident described in LER 369/81-44 required readjustment of the exiting chilled water thermostat because the thermostat was set too cold for the low chiller load. The incident described in LER 369/83-48 also required the thermostat for the exiting chilled water to be adjusted due to previous work in which the chiller condenser tubes [EIIS:TBG) were cleaned. The incident described in LER 369/83-56 was partly due to a leaking flange which resulted in a loss of refrigerant (Situation for Train A in this report).
ADDITIONAL CORRECTIVE ACTIONS
Tags saying "NO ONE IS TO ADJUST ANY OF THESE CONTROLS WITHOUT FIRST CONTACTING HVAC MAINTENANCE" have been hung in front of the VC/YC Chiller control switches inside each of the control cabinets. The Control Room Chiller Preventative
~aceoaM u.*
NRC Form 3644 U S NUCLfMi i.EGULATO%Y COMMidiON LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AremovEo oMe so aiso-oio4 EnPIRES 8/3:15 F ACILl17 NAME HI DOCKE F NUMBE R 128 (gR NUM8ER (GI PAGE III
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- E*a McGuire Nuclear Station - Unit 1 5 l0 l0 j o l 3l6 l 9 q7 OgOg1
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IEXT (# more spece as requesd, ese eenoner WC perm JS6Nsf (i?]
Maintenance procedure will be modified to include on the data sheet to document "AS FOUND" and "AS LEFT" chiller control settings.
The VC/YC Train A leaking oil cooler fitting will be repaired. Station personnel will monitor VC/YC Train A refrigerant charge and oil level on a daily basis until the leak from the threaded fitting on the chiller's oil coller is repaired.
SAFETY ANALYSIS
During this incident, there was a period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 37 minutes when the VC/YC cystem was not providing any cooling. During this time period, the Control Room temperature did not exceed approximately 83 degrees-F due to the utilization of the Control Room Hi Temperature procedure. There were several spurious alarms that apparently resulted from the elevated Control Room temperature. The Channel IV Steam Pressure on D S/G had alarms due to erratic readings of low pressure.
If there had been two out of fot'r channels on one out of four S/Cs indicating low pressure, a Safety Injection / Reactor trip would have occurred. The loss of both trains of the VC/YC system did not last long enough to cause any Control Room area high temperature alarms (Control Room Alert at 85 degrees-F and Alarm at 90 degrees-F).
If the VC/YC system had been inoperable long enough for a more significant temperature increase to take place, there could have been electronic aquipment failures in the 7300 Process Control cabinets [EIIS: CAB] resulting in a Reactor trip concurrent with unreliable readings on unit status.
With the cooling portion of the VC/YC system inoperable, in the event of an accident resulting in the possibility of chlorine or radioactive airborne contamination, the VC/YC system air handling filtration units would have been operated which would have maintained the habitability of the Control Room.
There were no personnel injuries, personnel overexposures, or releases of radioactive material as a result of this incident.
The health and safety of the public were not affected by this incident.
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CHAHLOTTE, N.C. Sil242 HAL H. TUCKEH Tzternown ww a p.amment (704) 073-48lH mm..
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February 6, 1987 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Subject: McGuire Nuclear Station, Units 1 and 2 Docket No. 50-369 and 50-370 LER 369/87-01 Gentlemen:
Pursuant to 10CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event Report 369/87-01 concerning the (shared) control area ventilation / chilled water system being inoperable due to a chiller thermostat set too low and a refrigerant leak which is submitted in accordance with $50.73(a)(2)(1)(B). Initial notification of this event was made (pursuant to $50.72 Section (b)(1)(A) with the NRC Operations Center via the ENS on January 7, 1987. This event was considered to be of no significant with respect to the health and safety of the public.
Very truly yours.
- A. M fn/
/
Hal B. Tucker PBN/45/jgm 3
Attachment xc Dr. J. Nelson Grace American Nuclear Insurers Regior.a1 Administrator, Region II c/o Dottie Sherman, ANI Library U.S. Nuclear Regulatory Commission The Exchange, Suite 245 101 Marietta St., NW, Suite 2900 270 Farmington Avenue Atlanta, GA 30323 Farmington, CT 06032 INFO Records Center Mr. Darl Hood Suite 1500 U.S. Nuclear Regulatory Commission 1100 circle 75 Parkway Office of Nuclear Reactor Regulation Atlanta, CA 30339 Washington, D.C.
20555 M&M Nuclear Consultants Mr. W.T. Orders V
1221 Avenue of the Americas NRC Resident Inspector f
New York, NY 10020 McGuire Nuclear Station
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| 05000369/LER-1987-001, :on 870107,Train B Chiller for (Shared) Control Area Ventilation/Chilled Water Sys Tripped on Refrigerant Low Temp.Caused by Chiller Thermostat Setting Positioned Too Cold.Train B Switch Manually Reset |
- on 870107,Train B Chiller for (Shared) Control Area Ventilation/Chilled Water Sys Tripped on Refrigerant Low Temp.Caused by Chiller Thermostat Setting Positioned Too Cold.Train B Switch Manually Reset
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-002-01, :on 861230,Trains 1A & B of Containment Spray Sys Declared Inoperable.Caused by Senior Reactor Operator Misunderstanding Impact of Containment Spray Sys in Test Mode.Appropriate Training Will Be Reiterated |
- on 861230,Trains 1A & B of Containment Spray Sys Declared Inoperable.Caused by Senior Reactor Operator Misunderstanding Impact of Containment Spray Sys in Test Mode.Appropriate Training Will Be Reiterated
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-003-03, :on 870130,containment Air Return Fans Declared Inoperable.Caused by Inadequate Administrative Controls Resulting in Removal of Water Curbs W/O Reinstallation.Curbs Replaced.Procedures Will Be Revised |
- on 870130,containment Air Return Fans Declared Inoperable.Caused by Inadequate Administrative Controls Resulting in Removal of Water Curbs W/O Reinstallation.Curbs Replaced.Procedures Will Be Revised
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-004-03, :on 870218,reactor Tripped Due to Low RCS Flow. Caused by Failed Surge Capacitor Resulting in Reactor Coolant Pump Motor 1C Tripping on Ground Fault.Surge Capacitor Replaced |
- on 870218,reactor Tripped Due to Low RCS Flow. Caused by Failed Surge Capacitor Resulting in Reactor Coolant Pump Motor 1C Tripping on Ground Fault.Surge Capacitor Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000369/LER-1987-005-02, :on 870224,battery Charger Room Fire Walls Declared Inoperable Due to Walls Not Meeting NRC Commitment Re Boundary Specs.Caused by Improper Const of Walls.Const & QA Requirements Established |
- on 870224,battery Charger Room Fire Walls Declared Inoperable Due to Walls Not Meeting NRC Commitment Re Boundary Specs.Caused by Improper Const of Walls.Const & QA Requirements Established
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | | 05000369/LER-1987-006-02, :on 870310,control Area Ventilation & Chilled Water Sys Train B Chiller Tripped While Train a Inoperable. Caused by Failure to Verify Valve 2RN-43A Open.Train B Chiller Restarted & Declared Operable |
- on 870310,control Area Ventilation & Chilled Water Sys Train B Chiller Tripped While Train a Inoperable. Caused by Failure to Verify Valve 2RN-43A Open.Train B Chiller Restarted & Declared Operable
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-006-01, :on 870310,control Area Ventilation & Chilled Water Sys Train B Declared Inoperable Due to Chiller Trip. Caused by Personnel Error.Work Request Initiated to Investigate & Repair Position Indication |
- on 870310,control Area Ventilation & Chilled Water Sys Train B Declared Inoperable Due to Chiller Trip. Caused by Personnel Error.Work Request Initiated to Investigate & Repair Position Indication
| | | 05000369/LER-1987-007-02, :on 870317,incorrect Actuation Tubing Connections on Halon Fire Suppression Sys Discovered.Caused by Failure of Procedure to Ensure That Tubing Was Properly Reconnected.Tubing Connections Corrected |
- on 870317,incorrect Actuation Tubing Connections on Halon Fire Suppression Sys Discovered.Caused by Failure of Procedure to Ensure That Tubing Was Properly Reconnected.Tubing Connections Corrected
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-008-02, :on 870409,monthly Channel Checks on Reactor Vessel Level Instrumentation Sys Not Performed.Caused by Defective Procedure.Operations Revised Monthly Surveillance Items Procedures |
- on 870409,monthly Channel Checks on Reactor Vessel Level Instrumentation Sys Not Performed.Caused by Defective Procedure.Operations Revised Monthly Surveillance Items Procedures
| | | 05000369/LER-1987-009-02, :on 870415,reactor Tripped Due to Turbine Tripped Signal Generated While Station Personnel Testing Turbine auto-stop Oil Pressure Switch.Caused by Design Deficiency.Preventive Maint Code Changed |
- on 870415,reactor Tripped Due to Turbine Tripped Signal Generated While Station Personnel Testing Turbine auto-stop Oil Pressure Switch.Caused by Design Deficiency.Preventive Maint Code Changed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000369/LER-1987-010-02, :on 870509,pressure Switch on Auxiliary Feedwater motor-driven Pump 1A Suction Discovered Out of Calibr.Caused by Personnel Error.Personnel Will Be Retrained on Recognizing & Compensating for Water Legs |
- on 870509,pressure Switch on Auxiliary Feedwater motor-driven Pump 1A Suction Discovered Out of Calibr.Caused by Personnel Error.Personnel Will Be Retrained on Recognizing & Compensating for Water Legs
| | | 05000369/LER-1987-011-02, :on 870610,leak Rate Testing of Containment Electrical Penetrations Not Performed.Caused by Inadequate Administrative Controls Surveillance Testing.Leak Rate Test Procedures Corrected |
- on 870610,leak Rate Testing of Containment Electrical Penetrations Not Performed.Caused by Inadequate Administrative Controls Surveillance Testing.Leak Rate Test Procedures Corrected
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000369/LER-1987-012-02, :on 870709,diesel Generator Load Sequencer 1A Actuated in LOCA Mode During Routine Periodic Test of Slave Relays in Solid State Protection Sys.Caused by Defective Procedures.Slave Relay Test Procedures Revised |
- on 870709,diesel Generator Load Sequencer 1A Actuated in LOCA Mode During Routine Periodic Test of Slave Relays in Solid State Protection Sys.Caused by Defective Procedures.Slave Relay Test Procedures Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000369/LER-1987-013-02, :on 870729,unit Entered Tech Spec 3.0.3 When Reactor Coolant Loop a Flow Transmitter Signals Blocked to Facilitate Transmitter Replacement.Transmitter Replaced & & Signal Block Removed |
- on 870729,unit Entered Tech Spec 3.0.3 When Reactor Coolant Loop a Flow Transmitter Signals Blocked to Facilitate Transmitter Replacement.Transmitter Replaced & & Signal Block Removed
| | | 05000369/LER-1987-014-01, :on 870730,control Power Circuit Breaker for Diesel Generator 1A Found Inoperable.Caused by Personnel Error.Policies Revised on Use of Safety Tagging Programs |
- on 870730,control Power Circuit Breaker for Diesel Generator 1A Found Inoperable.Caused by Personnel Error.Policies Revised on Use of Safety Tagging Programs
| 10 CFR 50.73(a)(2) | | 05000369/LER-1987-014, :on 870730,control Power Circuit Breaker for Diesel Generator 1A Discovered Open,Rendering Generator Inoperable.Diesel Generator Inoperable for Approx 3 Days. Caused by Personnel Error |
- on 870730,control Power Circuit Breaker for Diesel Generator 1A Discovered Open,Rendering Generator Inoperable.Diesel Generator Inoperable for Approx 3 Days. Caused by Personnel Error
| 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-015-02, :on 870727,fire/flood Barrier Between Diesel Generator & Diesel Lube Oil Holding Tanks Room Breached. Caused by Personnel Error.Personnel Counseled |
- on 870727,fire/flood Barrier Between Diesel Generator & Diesel Lube Oil Holding Tanks Room Breached. Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-016, Informs That Unit 1 Did Not Exceed Indicated Rated Thermal Power & That LER 87-016 Will Not Be Submitted or Used in Future | Informs That Unit 1 Did Not Exceed Indicated Rated Thermal Power & That LER 87-016 Will Not Be Submitted or Used in Future | | | 05000369/LER-1987-018-02, :on 870824,determined Flow Instrument Calibrs for Nuclear Svc Water Pumps 2A & 2B Incorrect.Caused by Inadequate Mgt Review of Procedures That Require Changes. Discharge Flow Loop Calibr Changed |
- on 870824,determined Flow Instrument Calibrs for Nuclear Svc Water Pumps 2A & 2B Incorrect.Caused by Inadequate Mgt Review of Procedures That Require Changes. Discharge Flow Loop Calibr Changed
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-019, :on 870904,auxiliary Feedwater Autostart Occurred.Caused by Defective Procedure Due to Insufficient Instructions to Prevent Loss of Both Main Feedwater Pumps During Shutdown.Pump Control Valves Reset |
- on 870904,auxiliary Feedwater Autostart Occurred.Caused by Defective Procedure Due to Insufficient Instructions to Prevent Loss of Both Main Feedwater Pumps During Shutdown.Pump Control Valves Reset
| | | 05000369/LER-1987-019-02, :on 870904,auxiliary Feedwater Autostart Occurred.Caused by Lack of Sufficient Procedural Instruction to Prevent Loss of Both Main Pumps During Shutdown. Procedures Will Be Revised & Pumps Repaired |
- on 870904,auxiliary Feedwater Autostart Occurred.Caused by Lack of Sufficient Procedural Instruction to Prevent Loss of Both Main Pumps During Shutdown. Procedures Will Be Revised & Pumps Repaired
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000369/LER-1987-020-02, :on 870905,RHR Pump B Declared Inoperable Due to Isolation of Flow Instrument.Caused by Personnel Failing to Assure Instrument Properly Returned to Svc After 870828 Repair of Leak.Instrument Unisolated |
- on 870905,RHR Pump B Declared Inoperable Due to Isolation of Flow Instrument.Caused by Personnel Failing to Assure Instrument Properly Returned to Svc After 870828 Repair of Leak.Instrument Unisolated
| 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(s)(2)(1) | | 05000369/LER-1987-020-01, Forwards Revised LER 87-020-01 Re 8-day Inoperability of RHR Pump 1B Due to Addl Analysis of Event & to Correct Wording in Abstract,Provide Expanded Safety Analysis & Discuss Addl Corrective Action | Forwards Revised LER 87-020-01 Re 8-day Inoperability of RHR Pump 1B Due to Addl Analysis of Event & to Correct Wording in Abstract,Provide Expanded Safety Analysis & Discuss Addl Corrective Action | 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-020, :on 870905,RHR Pump 1B Declared Inoperable Due to Isolated Pump Recirculation Valve Controlling Flow Instruments.Work Requests for Flow Instruments Revised W/ Precautions & Event Will Be Covered During Training |
- on 870905,RHR Pump 1B Declared Inoperable Due to Isolated Pump Recirculation Valve Controlling Flow Instruments.Work Requests for Flow Instruments Revised W/ Precautions & Event Will Be Covered During Training
| | | 05000369/LER-1987-021-01, :on 870916,facility Blackout Occurred Due to Relays Energizing During Testing.Caused by Personnel Error. Busline 1B Stabilized.Evaluation of Compressor Alignments VI & Design Review of Power Supply Initiated |
- on 870916,facility Blackout Occurred Due to Relays Energizing During Testing.Caused by Personnel Error. Busline 1B Stabilized.Evaluation of Compressor Alignments VI & Design Review of Power Supply Initiated
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000369/LER-1987-022, :on 870921,breached Fire Blanket Discovered. Breach Occurred on 870912 When Personnel Cut Blanket to Perform Preventive Maint.Caused by Personnel Failure. Placards Attached Noting Blankets Are Barriers |
- on 870921,breached Fire Blanket Discovered. Breach Occurred on 870912 When Personnel Cut Blanket to Perform Preventive Maint.Caused by Personnel Failure. Placards Attached Noting Blankets Are Barriers
| | | 05000369/LER-1987-022-02, :on 870921,during Annual Fire Protection Audit, Breached Fire Blanket Discovered.Caused by Personnel Not Recognizing Blanket as Fire Barrier.Breach in Barrier Repaired & Fire Blanket Restored |
- on 870921,during Annual Fire Protection Audit, Breached Fire Blanket Discovered.Caused by Personnel Not Recognizing Blanket as Fire Barrier.Breach in Barrier Repaired & Fire Blanket Restored
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-023-02, :on 871001,control Room Ventilation/Chilled Water Trains a & B Chillers Declared Inoperable.Train a Trip Caused by Blown Fuse.Train B Trip Caused by Failure of Actuator Microswitch.Fuse Replaced |
- on 871001,control Room Ventilation/Chilled Water Trains a & B Chillers Declared Inoperable.Train a Trip Caused by Blown Fuse.Train B Trip Caused by Failure of Actuator Microswitch.Fuse Replaced
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-024-02, :on 871002,gap Around Top Sealing Surface of Reactor Bldg Equipment Hatch Discovered.Caused by Inadequate Procedural Instructions & Insufficient Administrative Controls.Procedures to Be Revised |
- on 871002,gap Around Top Sealing Surface of Reactor Bldg Equipment Hatch Discovered.Caused by Inadequate Procedural Instructions & Insufficient Administrative Controls.Procedures to Be Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000369/LER-1987-025-02, :on 871025,pressurizer (Pzr) Dissolved Oxygen (Do) Not Verified to Be within Tech Spec Limits.Caused by Insufficient Communications to Ensure Pzr Do Verified to Be within Tech Spec Limits.Personnel Trained |
- on 871025,pressurizer (Pzr) Dissolved Oxygen (Do) Not Verified to Be within Tech Spec Limits.Caused by Insufficient Communications to Ensure Pzr Do Verified to Be within Tech Spec Limits.Personnel Trained
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-026-02, :on 871105,control Area Ventilation & Chilled Water Sys Train a Declared Inoperable.Caused by Degradation of Control Room Door Seals & Mgt Deficiency.Seals Repaired & Preventive Maint Program to Be Established |
- on 871105,control Area Ventilation & Chilled Water Sys Train a Declared Inoperable.Caused by Degradation of Control Room Door Seals & Mgt Deficiency.Seals Repaired & Preventive Maint Program to Be Established
| 10 CFR 50.73(a)(2) | | 05000369/LER-1987-027, :on 871029,valve IRN-235B Found Leaking.Work Requests Initiated to Repair Seat Leak & Rebuild & Bench Test Operator.On 871119,discovered That Retest of Valve Not Performed.Caused by Personnel Error |
- on 871029,valve IRN-235B Found Leaking.Work Requests Initiated to Repair Seat Leak & Rebuild & Bench Test Operator.On 871119,discovered That Retest of Valve Not Performed.Caused by Personnel Error
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-028, :on 871120,decreased Flow Through Steam Generator (SG) Feedwater Control Valve Bypass Led to Manual Activation of Auxiliary Feedwater Sys to Avoid Trip on Low SG 1D Level.Cause Unknown.Valve Checked |
- on 871120,decreased Flow Through Steam Generator (SG) Feedwater Control Valve Bypass Led to Manual Activation of Auxiliary Feedwater Sys to Avoid Trip on Low SG 1D Level.Cause Unknown.Valve Checked
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000369/LER-1987-029-02, :on 871119,RCS Leakage Calculation Result Greater than 1 Gpm Noted,Due to Packing Leak on Charging Pumpdischarge Control Valve.Caused by Improper Packing Procedure.Improvement Program Underway |
- on 871119,RCS Leakage Calculation Result Greater than 1 Gpm Noted,Due to Packing Leak on Charging Pumpdischarge Control Valve.Caused by Improper Packing Procedure.Improvement Program Underway
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-030-02, :on 870908,supply Valve to Diesel Generator 1B (DG) from Fuel Oil Storage Tank 1B Mistakenly Closed Due to Mislabelled Reach Rods,Leaving DG Inoperable.Caused by Error in Procedure Valve Checklist.List Corrected |
- on 870908,supply Valve to Diesel Generator 1B (DG) from Fuel Oil Storage Tank 1B Mistakenly Closed Due to Mislabelled Reach Rods,Leaving DG Inoperable.Caused by Error in Procedure Valve Checklist.List Corrected
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000369/LER-1987-031-01, :on 871125,Tech Spec 3.0.3 Entered When Both Component Cooling HXs Declared Inoperable.Caused by Equipment Failure.Valve IRN-89 Administratively Blocked Open |
- on 871125,Tech Spec 3.0.3 Entered When Both Component Cooling HXs Declared Inoperable.Caused by Equipment Failure.Valve IRN-89 Administratively Blocked Open
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-032-01, :on 871108,damaged Fire Barrier Discovered on Auxiliary Feedwater Sys Valve Actuator.Cause Unknown.Fire Barrier Repaired on 871113.Addl Corrections from Previous LERs Underway |
- on 871108,damaged Fire Barrier Discovered on Auxiliary Feedwater Sys Valve Actuator.Cause Unknown.Fire Barrier Repaired on 871113.Addl Corrections from Previous LERs Underway
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-033, Informs That LER 87-33 Due on 880108 Delayed Due to Unresolved Concerns & Will Be Submitted on 880129 | Informs That LER 87-33 Due on 880108 Delayed Due to Unresolved Concerns & Will Be Submitted on 880129 | | | 05000369/LER-1987-034-02, On 871109,Fire Doors 819A & 621A Blocked Open & Hourly Fire Watch Not Performed.Caused by Personnel Error. Fire Doors Closed & Mechanical Maint (Mnt) Will Establish Logbook for Tech Spec Items Under Mnt Control | On 871109,Fire Doors 819A & 621A Blocked Open & Hourly Fire Watch Not Performed.Caused by Personnel Error. Fire Doors Closed & Mechanical Maint (Mnt) Will Establish Logbook for Tech Spec Items Under Mnt Control | | | 05000369/LER-1987-034-01, :on 871109,discovered Two Fire Doors Blocked Open & Fire Watch Missed.Caused by Personnel Error.Fire Door Closed & Mechanical Maint (Mnt) Will Establish Log Book for Tech Spec Items Under Mnt Responsibility |
- on 871109,discovered Two Fire Doors Blocked Open & Fire Watch Missed.Caused by Personnel Error.Fire Door Closed & Mechanical Maint (Mnt) Will Establish Log Book for Tech Spec Items Under Mnt Responsibility
| 10 CFR 50.73(a)(2)(i) | | 05000369/LER-1987-035-01, :on 870611,computer Logs Indicated That Unit May Have Operated Above Rated Thermal Power as Defined in Tech Spec.Caused by Number of Decimal Places Used to Adjust Plant Output Were Rounded Off |
- on 870611,computer Logs Indicated That Unit May Have Operated Above Rated Thermal Power as Defined in Tech Spec.Caused by Number of Decimal Places Used to Adjust Plant Output Were Rounded Off
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1987-036-01, :on 871228 & 29,reactor Trips Occurred.Caused by Error in Schematic Diagram & Personnel Error.Diagrams Marked as Incorrect & Changes to Correct Unit 1 & 2 Diagrams Implemented |
- on 871228 & 29,reactor Trips Occurred.Caused by Error in Schematic Diagram & Personnel Error.Diagrams Marked as Incorrect & Changes to Correct Unit 1 & 2 Diagrams Implemented
| 10 CFR 50.73(a)(2)(iv), System Actuation |
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