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1 LICENSEE EVENT REPORT (LER)
Facility Name (1)
Docket Nuder (2)
Pace (3)
Zion. Unit 2 01 51 01 01 01 31 01 4 1lof!0!3 Failure of 0 diesel generator while 2A diesel generator was inoperable Event Date (5)
LER Neber (6)
Report Date (7)
Other Facilities Involved (8)
//j Revision Month Day Year Facility Names Docket Nueer(s) fj/j/ Sequential
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Month Day Year Year
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Nueer f
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Nueer
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01 51 01 01 01 I I 012 119 816 816 010 15
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Oli 0 15 116 816 0151010101 l l THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10CFR OPERATING (Check one or more of the followine) (11) 1 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)
Polder 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)
(10) 0l9 l8 20.405(a)(1)(ii)
_X_ 50.36(c)(2) 50.73(a)(2)(vii)
Other (Specify l
LEVEL 1
i 20.405(a)(1)(iii) 50.73(a)(2)(viii)(A) in Abstract below
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20.405(a)(1)(iv) 50.73(a)(2)(i) 50.73(a)(2)(viii)(8) and in Text)
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20.405(a)(1)(v) 50.73(a)(2)(ti)
/ / /
50.73(a)(2)(iii) 50.73(a)(2)(x) j j jj LICENSEE CONTACT FOR THIS LER (12) vn-gs4 AREA CODE n
Steven W. Sassaman. Technical Staff Engineer. Extension 320 3l1l2 714161-l210181 COMPLETE ONE LINE FOR EACH COMPONEN FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUFAC-REPORTABLE
CAUSE
SYSTEM COMPONENT MANUFAC-REPORTA8LE TURER TO NPRDS TURER TO NPRDS X
ElK l Rll lY Cl6 l 314 Y
l l l l l l l A
ElK l 115 lV C16 l 314 N
l l l l l l l SUPPLEMENTAL REPORT EXPECTED (14)
Expected Month l Day 1 Year Submission j
lyes (If ves couplete EXPECTED SUBMISSION DATE)
X l NO l
l l
l APSTRACT (Limit to 1400 spaces, i.e, approximately fifteen single-space typewritten lines) (16) l On 2/19/96, 2A diesel generator was started for a perfonnance test (PT-11 Diesel Generator Loading Tast). Two minutes after starting, at 2030, 2A diesel tripped off due to a partially closed fuel oil day i
tink supply valve. O diesel was started for a PT-il test in response to 2A diesel inoperability. At 2117 0 diesel came up to rated speed, then tripped. A generating station emergency plan event was declared until 2A l
diesel had successfully coupleted PT-11 at 0030, 2/20/96. On 0 diesel, investigation found that a relay in I
the starting circuit failed to remain sealed in with one of its own contacts after the initial starting signal was given. The contact was off center and intennittently failed. Before the relay problem was found, a subsequent failure occurred at 2135 on 2/20/96 during a PT-11 test.
Safeguards starting was available through relays that would have bypassed the faulty relay. The relay was replaced and 0 diesel was successfully tested and back in service by 1040, 2/23/96.
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8605220261 860516 PDR ADOCK 05000304 ffcN S
PDR u
i ib 02.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
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l FACILITY NAME (1)
DOCKET NUMER (2)
_ LER NUMER (6)
Pace (3)
/j/j Revision fjj/
Sequential
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Year f
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Nueer
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Nueer Zion. Unit 2 0 l 5 1 0 1 0 1 0 l 310 14 8l6 010l5 0l1 012 0F 013 TEXT Energy Industry Identification System (EIIS) codes are identified in the text as [xx]
A.
PLANT CONDITIONS PRIOR TO EVENT:
i Unit 1:- MODE 1 - Power Operation RX Power - 98%
Unit 2: MODE 1 - Power Operation RX Power - 98%
B.
DESCRIPTION OF EVENT
On 2/19/96, 2A diesel generator was started for a perfonnance test (PT-11 Diesel Generator Loading Test).
7 The engine started at 2030, reached rated speed, but began to decelerate. The operator attempted to raise the engine speed, but the engine continued to decelerate until it tripped at 2032._ The first-out annunicator trip flag was "Overspeed". Due to the 2A diesel inoperability, O diesel was started for a i
PT-il test. At 2117, O diesel came up to rated speed, then tripped. The first-out annunciator trip flags were " Lube Oil Pressure, Vibration, and Overspeed". A generating station emergency plan (GSEP) unusual event was declared and the NRC was notified at 2143. The GSEP event remained in effect until 2A diesel had successfully coupleted PT-11 at 0030, 2/20/96.
I i
At 0117 on 2/20/86, a PT-11 test was successfully perfonned on 0 diesel generator. At this point however, j
the cause of the original 0 diesel generator failure was unknown. Therefore, at 1045, O diesel generator was taken out of service for troubleshooting. After approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of investigation, the engineer felt that he had located the problem. Following several successful maintenance starts, PT-ll test was attempted at 2135 on 2/20/85. During this test, O diesel generator again came up to rated speed and tripped off. At this point, another investigation of the entire starting system was perfonned. The source of the trouble was found on 2/22/86, and 0 diesel generator was given a successful PT-ll on 2/23/86 i
and placed back in service.
l l
The engine is a Cooper Bessemer KSV-16-T diesel that runs an emergency 4 megawatt generator.
C.
CAUSE OF EVENT
4 After an inspection of 2A diesel generator's fuel system was made, a partially closed fuel oil day tank l
supply valve was found. The valve is a plug type which is turned 90 degrees to go from full closed to full open. It was probably closed accidentally by stationmen cleaning the engine following a February 18th, 1986 PT-11. The fuel oil supply valves on the other diesel generators were inspected and verified open.
A faulty relay, in the Cooper Bessemer En-tronic Control system, caused the O diesel engine to trip soon after starting. The relay failed intemittently, thus trouble shooting involved intensive investigation j
of the entire starting system. The second failure to start, which occurred on February 20th at 2135 during a subsequent PT-ll test, led to discovery of the relay problem. A movable contact was found off center thus not always providing the continuity needed to keep the relay energized after the initial start signal was given. Without this self sealing action, the engine would trip itself and indicate a nonnal engine shutdown on the annunciator.
t The "Overspeed" annunciation for 2A diesel and the " Lube Oil Pressure, Vibration, and Overspeed" annunciations for 0 diesel were erroneous indications. The small pneumatic pistons for the annunciator l
flags may be scratched, thus preventing them from being locked out when the true flag is up. During maintenance runs while troubleshooting the engines, Technical Staff engineers saw the "Nonnal Panel Shutdown" flag come up first followed by other flags which did not lock out, i
i 02740 4
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION e
FACILITY NAME (1)
DOCKET NUPBER (2)
LER NbpBER (6)
Page (3)
///j Revision Year
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Sequential j///
Ntaber f
fff
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Number Zion. Unit 2 0 l 5101010131014 8l6 0l0l5 0 l1 0l3 0F 013 TEXT Energy Industry identification System (Ell 5) codes are identified in the text as [xx]
0.
SAFETY ANALYSIS
After each failure of 0 diesel generator, all engineered safety feature (ESF) buses were verified to have nonnal power. Diesels lA and 18 for Unit I and diesel 28 for Unit 2 were verified operable by PT-il testing. Diesel 2A was verified operable by PT-il testing at 0030 on 2/20/86 thus ending the GSEP condition.
lhe troubleshooting group discovered that at the time of its PT-ll failures, O diesel would still have started for a loss of power or safeguards actuation condition, because an independent set of relays would have bypassed the faulty relay. Therefore, O diesel was only inoperable for manual starts. Since the bypass relays would have started 0 diesel on a safeguards actuation, and since 2A diesel was back in service while O diesel was out of service for troubleshooting, there were always at least 2 diesel generators available to provide emergency power if needed.
E.
CORRECTIVE ACTIONS
Due to the location of the engine fuel oil isolation valves and the possibility of a recurrence, the valve handles have been removed on all engines. A caution card has been attached to each engine fuel oil isolation valve with instructions to leave the valve in the open position and to remove the valve handle.
lhe faulty relay in the O diesel generator control cabinet was replaced with a new one. Additional starts were perforred using a brush recorder to monitor key portions of the starting circuits. No other problems were indicated. The diesel was given a successful PT-il test on February 23rd and placed back in service.
Work Requests have been written to rebuild all diesel generator first-out annunciator panels. No further corrective actions are required.
F.
PREVIOUS OCCURRENCES
1 lhere have been no previous occurrences of fuel oil supply valves being accidentally closed.
1 A search of the NPRDS computer files did not indicate previous relay trouble of this kind in the Cooper Bessemer En-tronic control system.
G.
COMPONENT FAILURE DATA
I MANUFACTURER NOMENCLATURE MODEL NUPBER MG PART NUPEER Kunnan Instrument 3 Pole, Double threw Kurman Instrument Cooper Bessemer Corp. (made for 11 pin plug relay, Corp. No.: 2603C Co. No.: 2-04E-158-001 Cooper Bessemer) 1 3/8" X 1 3/8" X 2 1/4",
clear plastic cover 02140
r O Zi;n Gen:riting Stition Commonw::lth Edi:on 101 Shiloh Blvd.
Zion, Illinois 60099 Telephone 312/746-2084 May 16, 1986 t
U.
S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
References:
10CFR50
Dear Sir:
The enclosed Supplemental Licensee Event Report from Zion Generating Station is being transmitted to you to add additional information to the event description.
This report is number 86-005-01, Docket No. 50-304/DPR-48.
Very trul
- yours,
/
lG.
f<
J.' P iml Station Manager Zion Generating Station GJP/gn
Enclosure:
Licensee Event Report No. 86-005-01 Attachment cc:
J. G. Keppler, NRC Region III Administrator M.
Holzmer, NRC Resident Inspector INPO Record Center CECO Distribution List
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| 05000295/LER-1986-001-05, :on 860112,discovered That Violations of Tech Spec 3.7.2 Occurred When Cooling to Auxiliary Feedwater Pump 1B Isolated from 851221 to 860112.Caused by Personnel Error.Valve Opened.Procedure Revised |
- on 860112,discovered That Violations of Tech Spec 3.7.2 Occurred When Cooling to Auxiliary Feedwater Pump 1B Isolated from 851221 to 860112.Caused by Personnel Error.Valve Opened.Procedure Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-001-01, :on 860103,fluctuation of Output of Inverter Power Supply Bus 213 Caused Charging Flow Control Valve & RHR Pump Suction Isolation Valve to Fail.Cause Unknown |
- on 860103,fluctuation of Output of Inverter Power Supply Bus 213 Caused Charging Flow Control Valve & RHR Pump Suction Isolation Valve to Fail.Cause Unknown
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) | | 05000295/LER-1986-002-08, :on 860218,fire Pump Out of Svc for More than 7 Days.Caused by Performance of Routine Maint Repairs. Redundancy Provided Via Svc Water Booster pumps.Motor-driven Fire Pump Tested Once Per Wk |
- on 860218,fire Pump Out of Svc for More than 7 Days.Caused by Performance of Routine Maint Repairs. Redundancy Provided Via Svc Water Booster pumps.Motor-driven Fire Pump Tested Once Per Wk
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-002-03, :on 860116,ESF Actuation of Auxiliary Feedwater Pumps Occurred.Caused by Inadequate Procedure.Procedure Change 0-86-77 Initiated to Eliminate Inadvertent Starting of Auxiliary Feedwater Pumps |
- on 860116,ESF Actuation of Auxiliary Feedwater Pumps Occurred.Caused by Inadequate Procedure.Procedure Change 0-86-77 Initiated to Eliminate Inadvertent Starting of Auxiliary Feedwater Pumps
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-003-03, :on 860203,14-day Approval of Temporary Change to Procedure E 015-1 Missed.Caused by Weakness in Administrative Procedure Review.Method of Tracking Approval Requirement Will Be Developed |
- on 860203,14-day Approval of Temporary Change to Procedure E 015-1 Missed.Caused by Weakness in Administrative Procedure Review.Method of Tracking Approval Requirement Will Be Developed
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) | | 05000295/LER-1986-003-04, :on 860214,block Valve 1MOV-RC800A Not Stroked Quarterly Since June 1985.Caused by Error in Tech Specs & Inservice Insp Testing Valve Program.Program Being Upgraded |
- on 860214,block Valve 1MOV-RC800A Not Stroked Quarterly Since June 1985.Caused by Error in Tech Specs & Inservice Insp Testing Valve Program.Program Being Upgraded
| 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1986-004-01, :on 860120,inadvertent Closing of Valve 2MOV-VC8100 Occurred Due to Failure of Test Switch.Switch Replaced |
- on 860120,inadvertent Closing of Valve 2MOV-VC8100 Occurred Due to Failure of Test Switch.Switch Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1986-005, :on 860219,diesel Generators 2A & O Tripped During Performance of PT-11 Loading Tests.Caused by Inadvertent Partial Fuel Supply Valve Closure & Faulty Kurman Instrument Relay.Relay Replaced |
- on 860219,diesel Generators 2A & O Tripped During Performance of PT-11 Loading Tests.Caused by Inadvertent Partial Fuel Supply Valve Closure & Faulty Kurman Instrument Relay.Relay Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(8) | | 05000304/LER-1986-005-04, :on 860219,diesel 2A Tripped Off Due to Partially Closed Fuel Oil Day Tank Supply Valve.When Diesel 0 Subsequently Started,Diesel Tripped.Related Failure Occurred on 860220.Caused by Faulty Relay |
- on 860219,diesel 2A Tripped Off Due to Partially Closed Fuel Oil Day Tank Supply Valve.When Diesel 0 Subsequently Started,Diesel Tripped.Related Failure Occurred on 860220.Caused by Faulty Relay
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1986-005-08, :on 860410,discovered That Outlet Dampers for Cribhouse Svc Water Area Ventilation Fans Obs & Ocs Failed Open & Inoperable.Caused by Fans Taken Out of Svc for Damper Repairs.Fans Placed Back in Svc |
- on 860410,discovered That Outlet Dampers for Cribhouse Svc Water Area Ventilation Fans Obs & Ocs Failed Open & Inoperable.Caused by Fans Taken Out of Svc for Damper Repairs.Fans Placed Back in Svc
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) | | 05000000/LER-1986-005-03, Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points | Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points | | | 05000304/LER-1986-006-01, :on 860122,during Logic Testing,Train B Breaker Rather than Train a Opened.Caused by Miswiring of Reactor Trip Switchgear During Mod.Investigation of Shut Trip Mod Activities in Progress.Testing Completed |
- on 860122,during Logic Testing,Train B Breaker Rather than Train a Opened.Caused by Miswiring of Reactor Trip Switchgear During Mod.Investigation of Shut Trip Mod Activities in Progress.Testing Completed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | | 05000295/LER-1986-006-04, :on 860224,during Functional Test of Halon Fire Protection Sys,Fire Damper Between North & South Cable Penetration Vaults Inoperable Due to Obstruction by Cable. Caused by Personnel Error.Personnel Counseled |
- on 860224,during Functional Test of Halon Fire Protection Sys,Fire Damper Between North & South Cable Penetration Vaults Inoperable Due to Obstruction by Cable. Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-006, :on 860122,during Logic Testing,Train B Trip Breaker Opened Instead of Train A.Caused by Miswiring of Reactor Trip Switchgear During Mod.Investigation of Shunt Trip Mod Activities in Progress |
- on 860122,during Logic Testing,Train B Trip Breaker Opened Instead of Train A.Caused by Miswiring of Reactor Trip Switchgear During Mod.Investigation of Shunt Trip Mod Activities in Progress
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1986-007, :on 860123,before Trip Breakers Opened Manually,Reactor Trip Occurred After Switching Instrument Power Supply.Caused by Failure to Communicate Station Policy.Supervisor Will Receive Addl Training |
- on 860123,before Trip Breakers Opened Manually,Reactor Trip Occurred After Switching Instrument Power Supply.Caused by Failure to Communicate Station Policy.Supervisor Will Receive Addl Training
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1986-007-04, :on 860307,while in Normal Operation at 99% Power,Containment Isolation EIIS Sys Bd Valve LAOV-IA01A Closed,Isolating Instrument Air EIIS Sys Ld to Containment. Caused by Misadjusted Relay |
- on 860307,while in Normal Operation at 99% Power,Containment Isolation EIIS Sys Bd Valve LAOV-IA01A Closed,Isolating Instrument Air EIIS Sys Ld to Containment. Caused by Misadjusted Relay
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1986-008-01, :on 860221,negative Flux Rate Trip Discovered Calibr to Nonconservative Value.Caused by Discrepant Westinghouse Owners Group Procedure Restrictions.Tech Spec Approved by NRC |
- on 860221,negative Flux Rate Trip Discovered Calibr to Nonconservative Value.Caused by Discrepant Westinghouse Owners Group Procedure Restrictions.Tech Spec Approved by NRC
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(vi) 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-008-03, :on 860302,reactor Coolant Sample for Iodine Analysis Performed 50 Minutes Early.Caused by Misunderstanding of Tech Spec.Radiation Protection Personnel Will Be Notified of Requirements |
- on 860302,reactor Coolant Sample for Iodine Analysis Performed 50 Minutes Early.Caused by Misunderstanding of Tech Spec.Radiation Protection Personnel Will Be Notified of Requirements
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1986-008, :on 860221,negative Flux Rate Trip Discovered to Be Calibr to Nonconservative Value.Caused by Input Changes to Accident Analysis for Dropped Rods.Safety Analysis Procedures Reviewed |
- on 860221,negative Flux Rate Trip Discovered to Be Calibr to Nonconservative Value.Caused by Input Changes to Accident Analysis for Dropped Rods.Safety Analysis Procedures Reviewed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(vi) 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-009-01, :on 860302,main Feed Breaker to 480-volt Ac Motor Control Ctr 2371 Tripped Open,Isolating Instrument Air to Containment Which Caused Pressurizer Spray Valves & RCS Letdown Valves to Close |
- on 860302,main Feed Breaker to 480-volt Ac Motor Control Ctr 2371 Tripped Open,Isolating Instrument Air to Containment Which Caused Pressurizer Spray Valves & RCS Letdown Valves to Close
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-009-03, :on 860302,breaker Trip Occurred on ESF 480-volt Ac Motor Control Ctr 2371,resulting in Loss of Power.Cause Unknown.Breaker Replaced W/Spare |
- on 860302,breaker Trip Occurred on ESF 480-volt Ac Motor Control Ctr 2371,resulting in Loss of Power.Cause Unknown.Breaker Replaced W/Spare
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1986-009-04, :on 860303,vent Fan Outlet Damper for 1B Diesel Generator Room Failed to Close Upon Receiving Actuation Signal from Fire Detection Sys.Caused by Coupling Pin Failure.Coupling Pin Fixed |
- on 860303,vent Fan Outlet Damper for 1B Diesel Generator Room Failed to Close Upon Receiving Actuation Signal from Fire Detection Sys.Caused by Coupling Pin Failure.Coupling Pin Fixed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1986-010-01, :on 860303,discovered That Aircraft Fire Outlet Damper on OAS Ventilation Fan for Crib House Svc Water Pump Area Removed for Maint.Temporary Fire Seal Installed.Job Sheets Added to Damper Work Requests |
- on 860303,discovered That Aircraft Fire Outlet Damper on OAS Ventilation Fan for Crib House Svc Water Pump Area Removed for Maint.Temporary Fire Seal Installed.Job Sheets Added to Damper Work Requests
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-010-04, :on 860219,during Performance of Diesel Generator Loading Test,Generator Tripped.Caused by Partially Closed Fuel Oil Day Tank Suppl Valve.On 860220,second Generator Tripped Due to Failed Relay.Relay Replaced |
- on 860219,during Performance of Diesel Generator Loading Test,Generator Tripped.Caused by Partially Closed Fuel Oil Day Tank Suppl Valve.On 860220,second Generator Tripped Due to Failed Relay.Relay Replaced
| 10 CFR 50.73(a)(2)(x) | | 05000304/LER-1986-010, :on 860219,diesel Generator 0 Failed While Diesel Generator 2A Inoperable.Caused by Partially Closed Fuel Oil Day Tank Supply Valve & Faulty Relay.Valve Handles Removed on Engines & Relays Replaced |
- on 860219,diesel Generator 0 Failed While Diesel Generator 2A Inoperable.Caused by Partially Closed Fuel Oil Day Tank Supply Valve & Faulty Relay.Valve Handles Removed on Engines & Relays Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1986-010-02, :on 860303,observed That Outlet Damper for OAS Ventilation Fan for Crib House Svc Water Pump Area Removed. Caused by Fan Maint.Temporary Fire Seal Installed Over Open Penetration for Duration of Maint on Fan |
- on 860303,observed That Outlet Damper for OAS Ventilation Fan for Crib House Svc Water Pump Area Removed. Caused by Fan Maint.Temporary Fire Seal Installed Over Open Penetration for Duration of Maint on Fan
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1986-011-04, :on 860324,during Periodic Test of Nuclear Instrumentation Sys Reactor Protection Logic,Reactor Tripped.Caused by Procedural Deficiencies Resulting in Induced Noise.Revs to Procedures Planned |
- on 860324,during Periodic Test of Nuclear Instrumentation Sys Reactor Protection Logic,Reactor Tripped.Caused by Procedural Deficiencies Resulting in Induced Noise.Revs to Procedures Planned
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | | 05000295/LER-1986-011-01, :on 860228,diesel Generator O Failed to Start from Train B During Performance of Quarterly Test of ESF Safeguard Actuation.Caused by Faulty Emergency Starting Relay Sockets.Sockets Resoldered |
- on 860228,diesel Generator O Failed to Start from Train B During Performance of Quarterly Test of ESF Safeguard Actuation.Caused by Faulty Emergency Starting Relay Sockets.Sockets Resoldered
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-012-04, :on 860408,during Periodic Test of Auxiliary Feed Pump Oil Pumps,Auxiliary Feed Pump 2B,rather than Auxiliary Feed Pump Oil Pump 2B,started.Caused by Operator Error & Inconsistent Switch Locations |
- on 860408,during Periodic Test of Auxiliary Feed Pump Oil Pumps,Auxiliary Feed Pump 2B,rather than Auxiliary Feed Pump Oil Pump 2B,started.Caused by Operator Error & Inconsistent Switch Locations
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii)(A) | | 05000295/LER-1986-012-01, :on 860311,reactor Tripped from 100% Power. Caused by Open Reactor Trip Breaker During Performance of Test While Interlock Cell Switch Closed & Training Inadequate.Reactor Trip Breaker Removed |
- on 860311,reactor Tripped from 100% Power. Caused by Open Reactor Trip Breaker During Performance of Test While Interlock Cell Switch Closed & Training Inadequate.Reactor Trip Breaker Removed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-013-04, :on 860501,discovered That Pressurizer Surge nozzle-to-vessel Weld Not Inspected During First Insp Interval.Caused by Personnel Failure to Comply W/Asme Section Xi.Outage Insp Procedures Reviewed |
- on 860501,discovered That Pressurizer Surge nozzle-to-vessel Weld Not Inspected During First Insp Interval.Caused by Personnel Failure to Comply W/Asme Section Xi.Outage Insp Procedures Reviewed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1986-013-01, :on 860324,lower Limit of Detection for Gross Beta/Gamma Analysis Sump Discharge Failed to Meet Tech Spec Requirements.Caused by Inadequate Procedures.Procedures Revised |
- on 860324,lower Limit of Detection for Gross Beta/Gamma Analysis Sump Discharge Failed to Meet Tech Spec Requirements.Caused by Inadequate Procedures.Procedures Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1986-014-02, :on 860408,OB Auxiliary Bldg Supply Fan Outlet Damper Found Failed Open W/Fan Off.Caused by Turning Off 120-volt Ac Switch for Damper Control Loop.Notice Will Be Posted on Switches Requiring Closed Dampers |
- on 860408,OB Auxiliary Bldg Supply Fan Outlet Damper Found Failed Open W/Fan Off.Caused by Turning Off 120-volt Ac Switch for Damper Control Loop.Notice Will Be Posted on Switches Requiring Closed Dampers
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) | | 05000304/LER-1986-014-04, :on 860519,reactor Tripped from 99.5% Power on lo-lo Steam Generator 2A Level.Caused by Technician Inadvertently Turning Off Feedwater Pump Controls.Large Caution Labels Installed on Feed Pump Controls |
- on 860519,reactor Tripped from 99.5% Power on lo-lo Steam Generator 2A Level.Caused by Technician Inadvertently Turning Off Feedwater Pump Controls.Large Caution Labels Installed on Feed Pump Controls
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1986-015-01, :on 860415,four Bolt Holes W/O Fire Stop Matl Filling Found in Rod Control Room Wall.Caused by Failure to Follow Procedures & Failure to Notify Fire Station Mgt.Holes Filled.Periodic Surveillance Now Required |
- on 860415,four Bolt Holes W/O Fire Stop Matl Filling Found in Rod Control Room Wall.Caused by Failure to Follow Procedures & Failure to Notify Fire Station Mgt.Holes Filled.Periodic Surveillance Now Required
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1986-015-04, :on 860729,inadvertent ESF Equipment Actuated During Safeguards Testing.Probably Caused by Sticky Contact on Reset Pushbutton.Reset Pushbutton Replaced |
- on 860729,inadvertent ESF Equipment Actuated During Safeguards Testing.Probably Caused by Sticky Contact on Reset Pushbutton.Reset Pushbutton Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1986-016-01, :on 860419,auxiliary Bldg Ventilation Standby Instrument Air Compressors Isolated.Cause Undetermined. Requirement for Shift Mgt Verification of Compressor Unisolation Steps in PT-210A Added |
- on 860419,auxiliary Bldg Ventilation Standby Instrument Air Compressors Isolated.Cause Undetermined. Requirement for Shift Mgt Verification of Compressor Unisolation Steps in PT-210A Added
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-016-04, :on 860627,reactor Tripped from Approx 70% Power.Caused by Lightning Strike Which Hit One or More Containment Lightning Rods.Two New Mods Initiated to Enhance Existing Lightning Protection Sys |
- on 860627,reactor Tripped from Approx 70% Power.Caused by Lightning Strike Which Hit One or More Containment Lightning Rods.Two New Mods Initiated to Enhance Existing Lightning Protection Sys
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1986-017-01, :on 860424,discovered That Control Room make-up Ventilation Train HEPA Filters Not Leak Tested Immediately After Replacement.Caused by Inadequate Work Request.Filters Passed Leak Test on 860424 |
- on 860424,discovered That Control Room make-up Ventilation Train HEPA Filters Not Leak Tested Immediately After Replacement.Caused by Inadequate Work Request.Filters Passed Leak Test on 860424
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-017-05, :on 860924 & 26,pressurizer Level Channel 2L-461 Abnormally High.Caused by Leaking Valves on Valve Manifold Due to Apparent Improper Torquing by Valve Mfg. Manifold Valves Retorqued.Part 21 Related |
- on 860924 & 26,pressurizer Level Channel 2L-461 Abnormally High.Caused by Leaking Valves on Valve Manifold Due to Apparent Improper Torquing by Valve Mfg. Manifold Valves Retorqued.Part 21 Related
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-018-05, :on 860921,essential Svc Bus 247 Experienced Degraded Bus Voltage Condition.Caused by Operator Error.Sys Design in Review Process to Determine Necessary Actions. Procedure Changes Will Be Made |
- on 860921,essential Svc Bus 247 Experienced Degraded Bus Voltage Condition.Caused by Operator Error.Sys Design in Review Process to Determine Necessary Actions. Procedure Changes Will Be Made
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(8) | | 05000295/LER-1986-018-01, :on 860504,reactor Tripped Due to electro-hydraulic Control (EHC) Hydraulic Fluid Pressure Problems.Caused by Drift of Autostart Pressure to Backup EHC Pump.Pressure Switches Replaced & Recalibr |
- on 860504,reactor Tripped Due to electro-hydraulic Control (EHC) Hydraulic Fluid Pressure Problems.Caused by Drift of Autostart Pressure to Backup EHC Pump.Pressure Switches Replaced & Recalibr
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1986-019, :on 860514,QA Dept Discovered That Fuel Handling Instruction FHI-21,Rev 4,not Reviewed by Technical Staff Supervisor.Caused by Personnel Error.Ler Will Be Distributed to Personnel Involved in Review |
- on 860514,QA Dept Discovered That Fuel Handling Instruction FHI-21,Rev 4,not Reviewed by Technical Staff Supervisor.Caused by Personnel Error.Ler Will Be Distributed to Personnel Involved in Review
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1986-019-01, :on 860514,QA Dept Discovered Rev 4 to Fuel Handling Instruction FHI-21,in Use Since 850314,not Reviewed by Technical Staff Supervisor.Procedure Reviewed & LER Circulated to personnel.W/860613 1tr |
- on 860514,QA Dept Discovered Rev 4 to Fuel Handling Instruction FHI-21,in Use Since 850314,not Reviewed by Technical Staff Supervisor.Procedure Reviewed & LER Circulated to personnel.W/860613 1tr
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-019-05, :on 860920,reactor & Generator Tripped.Caused by Personnel Error During Replacement of High Pressure Turbine Impulse Pressure Transmitter.Disciplinary Action Taken & Procedure Modified |
- on 860920,reactor & Generator Tripped.Caused by Personnel Error During Replacement of High Pressure Turbine Impulse Pressure Transmitter.Disciplinary Action Taken & Procedure Modified
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1986-020-04, :on 861004,1x2 Ft Hole Discovered in Wall Between Charging Pump Rooms 2A & 2B W/O Posting of Fire Watch as Required by Tech Specs.Caused by Failure of Supervisor to Follow Station Procedures |
- on 861004,1x2 Ft Hole Discovered in Wall Between Charging Pump Rooms 2A & 2B W/O Posting of Fire Watch as Required by Tech Specs.Caused by Failure of Supervisor to Follow Station Procedures
| 10 CFR 50.73(a)(2)(i) | | 05000000/LER-1986-020-07, :on 860505,both Automatic & Manual Safeguards Actuation Capability Defeated.Caused by Equipment Operator Removing Wrong Fuses.Discipliary Action Taken Against Individual & Procedure to Be Improved |
- on 860505,both Automatic & Manual Safeguards Actuation Capability Defeated.Caused by Equipment Operator Removing Wrong Fuses.Discipliary Action Taken Against Individual & Procedure to Be Improved
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1986-020-06, :on 861130,two Containment Isolation Valves Discovered Open During Audit of Chain Locked Valves,Per IE Info Notice 86-055.Caused by Inadequate Administrative Procedures.Procedures Revised |
- on 861130,two Containment Isolation Valves Discovered Open During Audit of Chain Locked Valves,Per IE Info Notice 86-055.Caused by Inadequate Administrative Procedures.Procedures Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1986-021-05, :on 861014,discovered Svc Water Vent Fan Outlet Damper Failed Open W/Fan Off.Caused by Loose Cover Plate on Miller Control Valve on Damper Actuator.Cover Plate Tightened & Damper Closed |
- on 861014,discovered Svc Water Vent Fan Outlet Damper Failed Open W/Fan Off.Caused by Loose Cover Plate on Miller Control Valve on Damper Actuator.Cover Plate Tightened & Damper Closed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1986-022-01, :on 860512,auto-start of Auxiliary Feedwater Pumps Occurred During Draining of Steam Generator During Water Chemistry Mods.Caused by Lack of Procedure for Draining.Procedures Revised |
- on 860512,auto-start of Auxiliary Feedwater Pumps Occurred During Draining of Steam Generator During Water Chemistry Mods.Caused by Lack of Procedure for Draining.Procedures Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) |
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