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LICENSEE EVENT REPORT (LER)
AGILITY NAME (1)
Washin ton Nuclear. Plant - Unit 2 DOCKET NUMB R (f)
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INOPERABILITYOF HIGH PRESSURE CORE SPRAY SYSTEM DUE TO PARTIALFAILUREOF PUMP MOTOR UPPER AIR DEFLECTOR EVENT DATE 5)
MONTH OAY YEAR YEAR LER NUMBER SEQUENTIAL NUMBER 6)
EVISIOH UHBER REPORT DATE 7
MONTH OAY YEAR OTHER FACILITIES INVOLVED 8
FACILITY NAMES CKET NUHB RS(S) 0 5
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MIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5:
(Check one or more of the following) (11 5
OWER LEVEL (io) 0.402(b) 0.405(a)(1)(i) 0.405(a)(1)(ii) 0.405(a)(1)(iii) 0.405(a)(1)(iv) 0.405(a)(1)(v) 0.405(C) 0.36(c)(1) 0.36(c)(2) 0.73(a)(2)(i) 0.73(a)(2)(ii) 50".73(a)(2)(iii) 50.73(a)(2)(iv)
X 50.73(a)(2)(v) 0.73(a)(2)(vii) 0.73(a)(2)(viii)(A) 0.73(a)(2)(viii)(B) 50.73(a)(2)(x) 77.71(b) 3.73(c)
THER (Specify in Abstract elow and in Text, NRC orm 366A)
LICENSEE CONTACT FOR THIS LER (12)
M.P. Reis, Compliance Supervisor TELEPHONE NUMBER REA CODE 5
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COMPLETE OHE LIHE FOR EACH COMPONENT FAILURE DESCRIBED IH THIS REPORT (13)
CAUSE
SYSTEM COMPOHEHT MANUFACTURER EPORTABLE g)<~i!
0 HPRDS Pi!'i'($
CAUSE
SYSTEM COMPONENT MAHUFACTURER EPORTABLE
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C' p?':..y SUPPLEMENTAL REPORT EXPECTED (14)
YES (If yes; carpiete EXPECTED SUBHISSIOH DATE)
HO tenet na>
XPECTED SUBMISSIOH MONTH DAT TEAR ATE (15)
On May 22, 1992, during an inspection of the High Pressure Core Spray (HPCS) pump motor, a small piece of the aluminum upper air deflector was found lodged inside the motor stator.
Several cracks were also discovered in the air deflector.
After further investigation, this problem was determined to be reportable because it could have affected operability of the HPCS System.
The root cause of this event was a plant/equipment related deficiency involving improper work practices used on the HPCS pump throttle bushing during initial plant construction.
This condition resulted in tearing of the upper air deflector due to excessive uplift forces.
The tear propagated along surface indications that were residual from manufacturing during subsequent operating cycles due to a high frequency, low stress fatigue mechanism.
It has been determined that the indications alone could not have initiated air deflector failure.
As corrective action, inspection and testing of the HPCS pump motor was performed, the upper air deflector was replaced, and the lower air-deflector was inspected.
Additionally, air deflectors for the Service Water pumps, which are similarly designed, were inspected.
An evaluation of Emergency Core Cooling System (ECCS) pump/motor maintenance procedures willbe performed in order to determine. if adequate guidance is provided to prevent similar damage in the future.
This event did not adversely affect the health and safety of the public or Plant personnel.
9209020023 920827 PDR ADOCK 05000397 8
PDR
'LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION AClLITY NAME (1)
Washington Nuclear Plant - Unit 2 DOCKET NUMBER (2) 0 5
0 0
0 3
9 7
ev.
No.
2 2 5 1
LER NUMBER (8) ear umber AGE (3) 2 F
5 ITLE (4)
INOPERABILITY OF HIGH PRESSURE CORE SPRAY SYSTEM DUE TO'PARTIAL FAILURE OF PUMP MOTOR UPPER AIR DEFLECTOR Plan ndi i n Plant Mode - 5 (Refueling)
Power Level - 0%
vent De cri i n On May 22, 1992, during an inspection of surge ring support brackets and fasteners on the High Pressure Core Spray (HPCS) System Pump Motor (HPCS-M-P/1), a piece of the aluminum upper air deflector was found lodged inside the motor stator.
On May 28, 1992, after further investigation, this problem was determined to be reportable because it could have affected operability of pump HPCS-P.-1 and the HPCS System.
At the time of the event the Plant was shutdown for the annual maintenance and refueling outage.
The inspection that identified this condition was being performed in response to a recommendation in a General Electric Service Information Letter (SIL 484) pertaining to pump motor surge ring support brackets and fasteners.
Although no problems were noted with these brackets and fasteners, the 5-inch by 4-inch (nominally 3/32-inch thick) piece of the deflector that was discovered could have resulted in localized areas of motor damage or there could have been excessive heating of the motor windings due to a reduction of proper air flow during operation of the pump. Ifthe entire annulus portion of the deflector would have failed during pump operation, it most probably would have resulted in motor failure.
The purpose of the air deflector is to direct cooling air to the motor windings.
The HPCS pump motor is a 3,000 hp, 1800 RPM, 4140 volt, squirrel-cage induction motor-that is mounted vertically above the HPCS pump (General Electric, Model 5K6357XC10A/PZ55).
The degradation or.
failure of this pump/motor combination could have affected the safety function of the HPCS System, which is to maintain vessel inventory and cool the reactor core during accident conditions.
mm i
e rr iveA in As immediate corrective action, an investigation into the cause of this event was initiated. No other immediate actions were required because the Plant was shutdown for the annual maintenance and refueling outage at the time of discovery.
'LICENSEE EVENT REPORT ( ER)
TEXT CONTINUATION AGILITY N E (1)
Mashington Nuclear Plant - Unit 2 DOCKET NUHBER (2) 0 5
0 0
0 3
9 7
LER NUHBER (8) ear umber ev.
No.
2 25 I
AGE (3) 3 F
5 ITLE (4)
INOPERABILITY OF HIGH PRESSURE CORE SPRAY SYSTEM DUE TO'PARTIAL FAILURE OF PUMP MOTOR UPPER AIR DEFLECTOR hrEvl in rr iv i n This event is reportable in accordance with the requirements of 10CFR50.73(a)(2)(v) as an event or condition that alone could have prevented the fulfillmentof the safety function of a system that is needed to mitigate the consequences of an accident.
This event was also verbally reported to the NRC in accordance with the requirements of 10CFR50.72 as a four-hour, nonemergency notification on May 28, 1992.
Physical examinations and analyses of the failed upper air deflector have been performed by the Supply System's Materials Engineering Group.
The scope of these examinations and analyses.
included fractographic and metallurgical examinations, chemical and modal analyses, and finite element analysis of the static loading condition.
Fracture mechanics analysis of the, dynamic loading condition was not deemed necessary due to the conclusive nature of results acquired from other examinations and analyses.
Examination of the upper air deflector identified one instance of tearing and several instances of indentation-type deformation corresponding with air deflector hold-down bracket locations.
The tearing was several inches long, and formed a part of the main fracture.
Other observed features included: 1) fatigue symptoms in the principal cracks that merged with the tear, and 2) surface indications that were residual from the air deflector manufacturing process.
It has been determined that the indentation-type deformations noted at air deflector hold-down bracket locations were the result of normal bracket preload stresses.
The existence of air deflector tearing has been attributed to a previous event involving improper upliftof the HPCS pump/motor assembly.
A review of equipment history records for the HPCS pump/motor indicates that an event involving excessive uplift force on the rotor of the HPCS pump motor occurred when the'HPCS pump throttle bushing was installed during initial plant construction.
Other damage resulting from this uplift event was repaired at the time of occurrence.
Based upon the results of examinations and analyses, it was concluded that failure of the upper air deflector was precipitated by stress risers that were created by tom material in the vicinityof the air deflector hold-down brackets.
Actual failure of the air deflector resulted when fatigue cracks were initiated at these stress risers and propagated along existing surface indications during succeeding plant operating cycles due to a high-frequency, low-load mechanism.
Although manufacturing related surface indications contributed to fatigue crack propagation and subsequent failure of the upper air deflector, it has been determined that these indications alone could not have caused air deflector failure.
'LICENSEE EVENT REPORT (
R)
TEXT CONTINUATION ACILITY KAHE (1)
Washington Nuclear Plant - Unit 2 OOCKET NUHBER (2) 0 5
0 0
0 3
9 7
LER KUHBER (8) ear umber ev.
No.
2 25 1
AGE 3) 4 F
5 ITLE (4)
INOPERABILITY OF HIGH PRESSURE CORE SPRAY SYSTEM DUE TO'PARTIAL FAILURE OF PUMP MOTOR UPPER AIR DEFLECTOR The root cause of this event was a plant/equipment related deficiency involving improper installation work practices used on the HPCS pump throttle bushing during initialplant construction.
The
'excessive uplift forces experienced during installation of this component introduced a tear in the upper air deflector.
Fatigue cracks were later initiated and propagated along stress risers associated with the tear, and ultimately resulted in failure of the upper air deflector.
Failure of the HPCS pump upper air deflector did not result directly from a manufacturing defect, and is not considered to be reportable under 10CFR21.
This event was not contributed to by any
- systems, structures or components that were inoperable at the start of the event.
Fu her C rrective A ion As corrective action, visual inspection of the HPCS motor stator windings, and megger and DC high-potential tests of the HPCS motor stator insulation were performed.
The visual inspection confirmed that HPCS pump/motor stator windings had not been damaged, and megger and DC high-potential tests demonstrated that the HPCS pump/motor stator insulation had not been degraded.
The failed upper air deflector was replaced with a new deflector, and the HPCS pump/motor lower air deflector was visually inspected.
Additionally, air deflectors for the Service Water System Pump Motors were visually inspected.
No evidence of cracking was identified during inspection of the HPCS pump lower,air deflector or Service Water System pump air deflectors.
Based upon these air deflector inspections and discussions with the vendor, it was determined that'nspection of air deflectors for Residual Heat Removal (RHR) and Low Pressure Core Spray (LPCS) motors, which are also of a similar design, was not necessary.
The condition described in this report occurred during initial plant construction, and did not involve inadequate maintenance practices or procedures; however, an evaluation of Emergency Core Cooling System (ECCS) pump/motor maintenance procedures willbe performed in order to verify that adequate guidance exists to prevent similar air deflector damage in the future.
Completion of this evaluation is scheduled for March 31, 1993.
afe i nifi n
HPCS is a part of the ECCS.
Its purpose is to supply water to the reactor vessel over a wide range of accident conditions.
For small-break Loss of Coolant Accidents (LOCAs) that do not result in rapid reactor depressurization, the system is designed to maintain reactor water'level.
For large breaks, the system provides core spray cooling.
The ECCS has built-in redundancy, and is comprised of HPCS, LPCS, ADS, and the RHR - LPCI Mode.
Failure of HPCS is bounded within the ECCS single failure analysis.
LICENSEE EVENT REPORT (
R)
TEXT CONTINUATION ACILITT H E (I)
Washington Nuclear Plant - Unit 2 DOCKET HUHBER (2) 0 5
0 0
0 3
9 7
ear LER HUHBER (8) umber ev.
Ho.
2 25=
I AGE (3) 5 F
5 ITLE (4)
INOPERABILITY OF HIGH PRESSURE CORE SPRAY SYSTEM DUE TO'PARTIAL FAILURE OF PUMP MOTOR UPPER AIR DEFLECTOR The condition described in this report did not result in actual failure of HPCS during an event where it was required to operate.
Consequently, this event did not affect the health and safety of either the public or Plant personnel.
However, even iffailure or unavailability of the ECCS function associated with HPCS had occurred during the period when air deflector damage was unrecognized, either the RCIC or ADS System could have'een used as a backup to the HPCS System.
imilar Ev n There have been LERs written due to the inoperability of the HPCS System; however, none of these reports pertained to failure of pump motor air deflectors.
II Inf rmai n
Text Reference
~EE II I
$gggm Q~m~nn High Pressure Core Spray (HPCS) System Motor HPCS-M-P/I Pump HPCS-P-I Emergency Core Cooling System (ECCS)
Reactor Core Isolation Cooling (RCIC) System Low Pressure Core Spray (LPCS) System Residual Heat Removal (RHR) System Automatic Depressurization System (ADS)
BG BG BG BM BN BM BO BG MO
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| 05000397/LER-1992-001, :on 920102,high Pressure Core Spray Declared Inoperable Due to Battery Inoperability.Caused by Instructional Presentation Deficiencies in TS Requirements. Notes Were Added to Surveillance Procedure |
- on 920102,high Pressure Core Spray Declared Inoperable Due to Battery Inoperability.Caused by Instructional Presentation Deficiencies in TS Requirements. Notes Were Added to Surveillance Procedure
| 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) | | 05000397/LER-1992-002, :on 920113,determined That MSIV Leakage Control Sys Fan Testing Incorrectly Performed.On 920127, Determined That Setpoint for Pressure Switch Did Not Ensure Proper Sys Operation.Ts Waiver Obtained |
- on 920113,determined That MSIV Leakage Control Sys Fan Testing Incorrectly Performed.On 920127, Determined That Setpoint for Pressure Switch Did Not Ensure Proper Sys Operation.Ts Waiver Obtained
| 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)(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) | | 05000397/LER-1992-003, :on 920123,circulating Fan CAC FN-1B Failed to Start During Performance of Surveillance Test.Caused by Tripped Overloads.Thermal Overloads Reset & Surveillance Test Performed |
- on 920123,circulating Fan CAC FN-1B Failed to Start During Performance of Surveillance Test.Caused by Tripped Overloads.Thermal Overloads Reset & Surveillance Test Performed
| 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)(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) | | 05000397/LER-1992-004, :on 920227,noted Scram Discharge Vol Level Switches Not Tested Post Scram as Required.Caused by Testing Not Being Performed.Corrective Actions Were Not Required |
- on 920227,noted Scram Discharge Vol Level Switches Not Tested Post Scram as Required.Caused by Testing Not Being Performed.Corrective Actions Were Not Required
| 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)(B), Prohibited by Technical Specifications 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) | | 05000397/LER-1992-005, :on 920219,thermal Overloads Prevented Motors from Performing Safety Functions.Caused by Misapplication of Design Inputs.Motors Replaced |
- on 920219,thermal Overloads Prevented Motors from Performing Safety Functions.Caused by Misapplication of Design Inputs.Motors Replaced
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-006, :on 920220,reactor Bldg to Suppression Chamber Vacuum Breaker Setpoints Were Incorrectly Set.Caused by Analysis Deficiency.Setpoint Documentation Changed & Procedures Deviated & Setpoints Reset |
- on 920220,reactor Bldg to Suppression Chamber Vacuum Breaker Setpoints Were Incorrectly Set.Caused by Analysis Deficiency.Setpoint Documentation Changed & Procedures Deviated & Setpoints Reset
| 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)(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) | | 05000397/LER-1992-007, :on 920225,both Divs of Primary Containment Atmosphere Control Hydrogen Recombiner Sys Inoperable & Plant Shutdown Initiated.Caused by Less than Adequate Design.Design Changes Implemented |
- on 920225,both Divs of Primary Containment Atmosphere Control Hydrogen Recombiner Sys Inoperable & Plant Shutdown Initiated.Caused by Less than Adequate Design.Design Changes Implemented
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(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) | | 05000397/LER-1992-008, :on 920301,standby Gas Treatment Sys Fan Flow Limiter Setpoint Error Identified.Caused by Analysis Deficiency.Investigation Into Instrument Setpoint Accuracy Ongoing |
- on 920301,standby Gas Treatment Sys Fan Flow Limiter Setpoint Error Identified.Caused by Analysis Deficiency.Investigation Into Instrument Setpoint Accuracy Ongoing
| 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) | | 05000397/LER-1992-008-01, :on 920301,SGTS Fan Flow Limiter Setpoint Error Discovered.Caused by Analysis Deficiencies.Sgts Fan Flow Limiter Setpoint Changed & Rev 2 of Jco Approved W/New Offsite Dose Calculations |
- on 920301,SGTS Fan Flow Limiter Setpoint Error Discovered.Caused by Analysis Deficiencies.Sgts Fan Flow Limiter Setpoint Changed & Rev 2 of Jco Approved W/New Offsite Dose Calculations
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) | | 05000397/LER-1992-009, :on 920302,determined That Containment Instrument Air Pressure Switch Setting Changes Required. Caused by Analysis Deficiency.Pressure Switches Were Reset in Accordance W/New Setpoint Calculations |
- on 920302,determined That Containment Instrument Air Pressure Switch Setting Changes Required. Caused by Analysis Deficiency.Pressure Switches Were Reset in Accordance W/New Setpoint Calculations
| 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) | | 05000397/LER-1992-010, :on 920303,standby Gas Treatment Differential Pressure Controller Setpoint Error Identified.Caused by Analysis Deficiency.Setpoint Methodology Program to Review Selected non-harsh Setpoints Extended |
- on 920303,standby Gas Treatment Differential Pressure Controller Setpoint Error Identified.Caused by Analysis Deficiency.Setpoint Methodology Program to Review Selected non-harsh Setpoints Extended
| 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)(B) | | 05000397/LER-1992-011, :on 920305,discovered That Method of CRD Hydraulic Isolation Did Not Meet TS Requirements.Caused by Less than Adequate Procedures Due to Omission of Relevant Info in Procedure.Exhaust Water Valve Closed |
- on 920305,discovered That Method of CRD Hydraulic Isolation Did Not Meet TS Requirements.Caused by Less than Adequate Procedures Due to Omission of Relevant Info in Procedure.Exhaust Water Valve Closed
| 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)(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) | | 05000397/LER-1992-012, :on 920318,determined That Removal of Access Plugs Over RHR Pump Rooms a & B Exposed Both Rooms to Potential Flooding from Common Source.Caused by Faulty Mgt Methods.Interim Guidance Provided |
- on 920318,determined That Removal of Access Plugs Over RHR Pump Rooms a & B Exposed Both Rooms to Potential Flooding from Common Source.Caused by Faulty Mgt Methods.Interim Guidance Provided
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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) | | 05000397/LER-1992-013, :on 920318,annunciator for RHR B/C VLV Open Permissive Found Lit & RHR Pressure Switch Found Isolated During Startup.Cause Not Determined.Pressure Switch Returned to Svc & Annunicator & Permissive Cleared |
- on 920318,annunciator for RHR B/C VLV Open Permissive Found Lit & RHR Pressure Switch Found Isolated During Startup.Cause Not Determined.Pressure Switch Returned to Svc & Annunicator & Permissive Cleared
| 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)(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) | | 05000397/LER-1992-014, :on 920326,920414 & 920512,engineers Identified TS Violations Associated W/Flow Measurements in Hpcs,Lpcs & RHR Sys,Respectively.Caused by Inadequate Design Analysis. Tests Performed to Verify Flows |
- on 920326,920414 & 920512,engineers Identified TS Violations Associated W/Flow Measurements in Hpcs,Lpcs & RHR Sys,Respectively.Caused by Inadequate Design Analysis. Tests Performed to Verify Flows
| 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)(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) | | 05000397/LER-1992-015, :on 920413,unexplained Pressure Drop in ADS B Section of Containment Instrument Air Sys Header Occurred. Caused by Inadequate Written Procedures.Valve CIA-V-41B Inspected & PPM-8.9.130 Replaced |
- on 920413,unexplained Pressure Drop in ADS B Section of Containment Instrument Air Sys Header Occurred. Caused by Inadequate Written Procedures.Valve CIA-V-41B Inspected & PPM-8.9.130 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-016, :on 920424,determined That RCIC Sys Not Adequately Transferred to Remote Shutdown Panel.Caused by Misapplication of Design Inputs.Power Supply for RCIC Control Sys (48-volt Dc) Will Be Modified |
- on 920424,determined That RCIC Sys Not Adequately Transferred to Remote Shutdown Panel.Caused by Misapplication of Design Inputs.Power Supply for RCIC Control Sys (48-volt Dc) Will Be Modified
| 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) | | 05000397/LER-1992-017, :on 920508,personnel Determined That Heat Removal Capability of Train a RHR Heat Exchanger Less than Design Allowable.Caused by Insufficient Monitoring of Plant Components.Corrective Actions Not Required |
- on 920508,personnel Determined That Heat Removal Capability of Train a RHR Heat Exchanger Less than Design Allowable.Caused by Insufficient Monitoring of Plant Components.Corrective Actions Not Required
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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) | | 05000397/LER-1992-018, :on 920428,determined That Six Locations Not Provided W/Emergency Lighting Capacity & Operator Actions Required for Fire Outside Main CR Not in Procedures.Caused by Inadequate Design.Lighting Provided |
- on 920428,determined That Six Locations Not Provided W/Emergency Lighting Capacity & Operator Actions Required for Fire Outside Main CR Not in Procedures.Caused by Inadequate Design.Lighting Provided
| 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) | | 05000397/LER-1992-019, :on 920430,determined That Automatic Depressurization Sys Potentially Inoperable Due to Inadequate Installation Instructions of Solenoid Pilot Valve Power Cables.Design Change Implemented |
- on 920430,determined That Automatic Depressurization Sys Potentially Inoperable Due to Inadequate Installation Instructions of Solenoid Pilot Valve Power Cables.Design Change Implemented
| 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) | | 05000397/LER-1992-020, :on 920508,discovered Low Elements for Low Pressure Core Spray Min Flow Control Not Properly Installed. Procedures Modified to Include Check of Instrument Startups Prior to Running Pump |
- on 920508,discovered Low Elements for Low Pressure Core Spray Min Flow Control Not Properly Installed. Procedures Modified to Include Check of Instrument Startups Prior to Running Pump
| 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)(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) | | 05000397/LER-1992-021, :on 920513,discovered That Certain QC-2 Instruments Were Not Appropriately Isolated from QC-1.Caused by Less than Adequate Design.No Corrective Action Was Taken |
- on 920513,discovered That Certain QC-2 Instruments Were Not Appropriately Isolated from QC-1.Caused by Less than Adequate Design.No Corrective Action Was Taken
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-022, :on 920514,plant Engineer Determined That Labyrinth Seals Installed in Replacement CAC Blowers Were Not Environmentally Qualified.Caused by Inadequate Work Practices & Procedures.Personnel Counseled |
- on 920514,plant Engineer Determined That Labyrinth Seals Installed in Replacement CAC Blowers Were Not Environmentally Qualified.Caused by Inadequate Work Practices & Procedures.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) | | 05000397/LER-1992-023, :on 930519,review of non-licensed Operator Tour Log Revealed Missed TS Surveillance & Fire Tour Data Due to Less than Adequate Work Practices.Investigation Into Event Expanded.No Violations Noted |
- on 930519,review of non-licensed Operator Tour Log Revealed Missed TS Surveillance & Fire Tour Data Due to Less than Adequate Work Practices.Investigation Into Event Expanded.No Violations Noted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000397/LER-1992-024, :on 920519,discovered Inadvertent Emergency Ventilation Actuation.Caused by Work Practices Being Less than Adequate.Technicians Were Counseled |
- on 920519,discovered Inadvertent Emergency Ventilation Actuation.Caused by Work Practices Being Less than Adequate.Technicians Were Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000397/LER-1992-025-01, :on 920528,HPCS Pump Motor & Small Piece of Aluminum Upper Air Deflector Found Lodged in Motor Stator & Cracks Found in Deflector.Caused by Use of Improper Work Practices.Deflectors Replaced.Not Reportable Per Part 21 |
- on 920528,HPCS Pump Motor & Small Piece of Aluminum Upper Air Deflector Found Lodged in Motor Stator & Cracks Found in Deflector.Caused by Use of Improper Work Practices.Deflectors Replaced.Not Reportable Per Part 21
| 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) | | 05000397/LER-1992-025, :on 920522,during Insp of HPCS Pump Motor,Small Piece of Aluminum Upper Air Deflector Found Lodged Inside Motor Stator.Caused by Personnel Error.Evaluation of ECCS Will Be Performed to Prevent Future Damage |
- on 920522,during Insp of HPCS Pump Motor,Small Piece of Aluminum Upper Air Deflector Found Lodged Inside Motor Stator.Caused by Personnel Error.Evaluation of ECCS Will Be Performed to Prevent Future Damage
| 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) | | 05000397/LER-1992-026, :on 920605,determined That Mo of RHR Train a May Have Prevented Full Closure of Drywell Spray Supply Valve.Caused by Inadequate Testing of Plant Equipment.Mo Repaired & Tested to Perform Design Function |
- on 920605,determined That Mo of RHR Train a May Have Prevented Full Closure of Drywell Spray Supply Valve.Caused by Inadequate Testing of Plant Equipment.Mo Repaired & Tested to Perform Design Function
| 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)(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)(8) | | 05000397/LER-1992-027, :on 920613,lack of Breaker Coordination Due to Instantaneous Trip Circuitry.Amptector Discriminator Circuit for Each of Six Feeder Breakers Disabled |
- on 920613,lack of Breaker Coordination Due to Instantaneous Trip Circuitry.Amptector Discriminator Circuit for Each of Six Feeder Breakers Disabled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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 | | 05000397/LER-1992-028, :on 920617,diesel Room Normal Air Handling Fans Precluded Performance of Required Design Function.Caused by Equipment Design Deficiency.Loop Test Procedure Will Be Revised |
- on 920617,diesel Room Normal Air Handling Fans Precluded Performance of Required Design Function.Caused by Equipment Design Deficiency.Loop Test Procedure Will Be Revised
| 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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-029, :on 920624,RHR Shutdown Cooling Isolation Occurred & Shutdown Cooling Supply Line Inboard Isolation Valve Automatically Closed.Caused by Inadequate Personnel Work Practices.Shutdown Cooling Reestablished |
- on 920624,RHR Shutdown Cooling Isolation Occurred & Shutdown Cooling Supply Line Inboard Isolation Valve Automatically Closed.Caused by Inadequate Personnel Work Practices.Shutdown Cooling Reestablished
| 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) | | 05000397/LER-1992-030, :on 920630,containment Isolation Occurred, Resulting in Shutdown of nonsafety-related HVAC Equipment & Actuation of Containment Isolation Valves.Caused by Poor Work Place Layout.Event Reviewed W/Personnel |
- on 920630,containment Isolation Occurred, Resulting in Shutdown of nonsafety-related HVAC Equipment & Actuation of Containment Isolation Valves.Caused by Poor Work Place Layout.Event Reviewed W/Personnel
| 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) | | 05000397/LER-1992-031, :on 920701,potential for Exceeding Continuous Rating of Divs I & II DG 1 & 2 Identified Due to Inadequate Circuit Electrical Separation.Caused by Design Deficiency. Items Placed on Hourly Fire Tour |
- on 920701,potential for Exceeding Continuous Rating of Divs I & II DG 1 & 2 Identified Due to Inadequate Circuit Electrical Separation.Caused by Design Deficiency. Items Placed on Hourly Fire Tour
| 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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-032, :on 920702,unplanned Actuation of ESF Component Occurred Due to Decrease in Reactor Water Level Resulting from Voided Feedwater Piping.Water Level Restored within Normal Operating Parameters |
- on 920702,unplanned Actuation of ESF Component Occurred Due to Decrease in Reactor Water Level Resulting from Voided Feedwater Piping.Water Level Restored within Normal Operating Parameters
| 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) | | 05000397/LER-1992-033, :on 920706 & 920711,determined That SRV Failed to Reseat at Required Pressure Per Ts.Caused by Two Adjusting Rings within SRV Found Set at Wrong Position. Training Will Be Provided to Shop Personnel |
- on 920706 & 920711,determined That SRV Failed to Reseat at Required Pressure Per Ts.Caused by Two Adjusting Rings within SRV Found Set at Wrong Position. Training Will Be Provided to Shop Personnel
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(i)(A), Completion of TS Shutdown 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) | | 05000397/LER-1992-034, :on 920713,determined That Nonwater Tight Penetration Seals in ECCS Pump Rooms Could Result in Common Mode Failure from Flooding.Inadequate Penetration Seals in ECCS Pump Rooms Except for Door Seals Reworked |
- on 920713,determined That Nonwater Tight Penetration Seals in ECCS Pump Rooms Could Result in Common Mode Failure from Flooding.Inadequate Penetration Seals in ECCS Pump Rooms Except for Door Seals Reworked
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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)(ii)(A), Seriously Degraded 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) | | 05000397/LER-1992-034-01, Forwards LER 92-034-01,describing Identification of Addl Unqualified Penetration Seals in ECCS Pump Room & Providing Status of Penetration Seal Rework | Forwards LER 92-034-01,describing Identification of Addl Unqualified Penetration Seals in ECCS Pump Room & Providing Status of Penetration Seal Rework | | | 05000397/LER-1992-034-02, Forwards LER 92-034-02.Supplemental Rept Describes Completion of Penetration Seal Rework & Changes to Flood Watch Requirements | Forwards LER 92-034-02.Supplemental Rept Describes Completion of Penetration Seal Rework & Changes to Flood Watch Requirements | | | 05000397/LER-1992-035, Responds to NRC 920831 Request for Addl Info Re LER 92-035 on Inadequate Testing of Scram Discharge Vol Vent & Drain Valves.Improvements to Plant Evaluation Requests Underway & Incident Review Board Established in June 1992 | Responds to NRC 920831 Request for Addl Info Re LER 92-035 on Inadequate Testing of Scram Discharge Vol Vent & Drain Valves.Improvements to Plant Evaluation Requests Underway & Incident Review Board Established in June 1992 | | | 05000397/LER-1992-035-01, Forwards LER 92-035-01.Suppls Provides Details & Clarifications Requested in NRC .Futher Review Indicates That Changes to post-mod Testing Plan Were Contributing Cause for Event | Forwards LER 92-035-01.Suppls Provides Details & Clarifications Requested in NRC .Futher Review Indicates That Changes to post-mod Testing Plan Were Contributing Cause for Event | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000397/LER-1992-036, :on 920719,primary Containment Lighting Circuit Not Deenergized as Required by Tech Specs.Caused by Technical Inaccuracy in Procedure for Plant Startup.Plant Startup Procedures & Drywell Entry Revised |
- on 920719,primary Containment Lighting Circuit Not Deenergized as Required by Tech Specs.Caused by Technical Inaccuracy in Procedure for Plant Startup.Plant Startup Procedures & Drywell Entry Revised
| 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)(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) | | 05000397/LER-1992-037, :on 920815,reactor Manually Acrammed Due to Indications of Core Instability.Caused by Unanticipated Interaction of Operating Conditions & Components.Revised Operating Strategies & Related Procedures |
- on 920815,reactor Manually Acrammed Due to Indications of Core Instability.Caused by Unanticipated Interaction of Operating Conditions & Components.Revised Operating Strategies & Related Procedures
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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) | | 05000397/LER-1992-037-02, Forwards LER 92-037-02.Rev Provides Updated Info Re C/As for Manual Reactor Scram Due to Core Instability.Commitment to Obtain Amend to TS to Eliminate Requirements for Calculating T Deleted.Confusion Eliminated Through Trai | Forwards LER 92-037-02.Rev Provides Updated Info Re C/As for Manual Reactor Scram Due to Core Instability.Commitment to Obtain Amend to TS to Eliminate Requirements for Calculating T Deleted.Confusion Eliminated Through Training | | | 05000397/LER-1992-038, :on 921014,technicians Failed to Perform Main Condenser Offgas Sample Analysis Per TS 3.3.7.12,due to Personnel Error & Inadequate Work Mgt Methods.C/A Included Counseling,Equipment Repair & Further Training |
- on 921014,technicians Failed to Perform Main Condenser Offgas Sample Analysis Per TS 3.3.7.12,due to Personnel Error & Inadequate Work Mgt Methods.C/A Included Counseling,Equipment Repair & Further Training
| 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)(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) | | 05000397/LER-1992-039, :on 920921,RWCS Isolated on High Differential Flow While ROs Were Attempting to Place filter-demineralizer RWCU-DM-1B Back Into Service.Caused by Inadequate Mgt Methods.Degraded Equipment Repaired & Procedures Updated |
- on 920921,RWCS Isolated on High Differential Flow While ROs Were Attempting to Place filter-demineralizer RWCU-DM-1B Back Into Service.Caused by Inadequate Mgt Methods.Degraded Equipment Repaired & Procedures Updated
| 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) | | 05000397/LER-1992-040, :on 920930,determined That Start & Load Time for Standby & HPCS DG Not Measured During Monthly Surveillance Testing.Caused by Deficiencies in Mgt Methods. Expedited Effort Initiated to Amend Procedure |
- on 920930,determined That Start & Load Time for Standby & HPCS DG Not Measured During Monthly Surveillance Testing.Caused by Deficiencies in Mgt Methods. Expedited Effort Initiated to Amend Procedure
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-041, :on 921027,offsite Power Source Determined Inoperable During Brief Periods of Prior Operaton Due to Low Voltage Condition on 230 Kv Grid.Caused by Design Deficiency & Inadequate Mgt Methods.Ts Procedure Changed |
- on 921027,offsite Power Source Determined Inoperable During Brief Periods of Prior Operaton Due to Low Voltage Condition on 230 Kv Grid.Caused by Design Deficiency & Inadequate Mgt Methods.Ts Procedure Changed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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 | | 05000397/LER-1992-042, Forwards Public Version of LER 92-042,Rev 0.Root Cause Is Inadequate Policy Re Free Release of Potentially Contaminated Liquids.Conclusions of Ongoing MORT Analysis Will Be in Suppl to LER | Forwards Public Version of LER 92-042,Rev 0.Root Cause Is Inadequate Policy Re Free Release of Potentially Contaminated Liquids.Conclusions of Ongoing MORT Analysis Will Be in Suppl to LER | | | 05000397/LER-1992-043, :on 921202,determined That Discrepancy Existed Between Plant Procedures & Monitoring Range of RPV Instrumentation in MCR & at Remote Shutdown Panel.Caused by Insufficient Communication.Procedures Revised |
- on 921202,determined That Discrepancy Existed Between Plant Procedures & Monitoring Range of RPV Instrumentation in MCR & at Remote Shutdown Panel.Caused by Insufficient Communication.Procedures Revised
| 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) | | 05000397/LER-1992-044, :on 921208,HPCS Sys Pump Suction Valve Switchover Occurred,Due to Spurious Actuation of Either One or Both CST Pipe Break Detectors.Engineering Will Evaluate Replacement of Detectors & Alternate Design |
- on 921208,HPCS Sys Pump Suction Valve Switchover Occurred,Due to Spurious Actuation of Either One or Both CST Pipe Break Detectors.Engineering Will Evaluate Replacement of Detectors & Alternate Design
| 10 CFR 50.73(a)(2)(iv), System Actuation |
|