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en COOPER NUCLE AR ST ATION Nebraska Public Power District
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NLS950057
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February 6, 1995
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U.S. Nuclear Regulatory Cominission Document Control Desk i
Washington, D.C.
20555
Dear Sir:
Cooper Nuclear Station Licensee t, vent Report 95-001 is forwarded as an attachment to this letter.
I Sincerely, v
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)
J. T.
ierron P1 nt Manager 1
/nr Attachment cc:
L. J. Callan G. R. Horn
[
J. H. Mueller R. G. Jones l
R. A. Sessoms K. C. Walden INPO Records Center NRC Resident Inspector j
R. J. Singer CNS Training CNS Quality Assurance R. L. Koch
,1.
j a.. J 9502140370 950206 gp; PDR ADOCK 05000298 S
PDR f
v
NRC FCSM 366 U.S. NUCLEAR RE'tdaA R*Y C01stI5SION APPROWED BY (35 No. 3150-0104 (5-92)
EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH I"
, LICENSEE EVENT REPORT (LER)
$ARD l"c"MMENfS REGARDING BUR EN SI TE O THE INFORMATION AND RECORDS MANAGEMENT BRANCH j
(MNBB 7714), U.S. NUCLEAR REGULATORY COMMIS$10N, (See reverse for required nunber of digits / characters for each block)
WASHINGTON, DC 20555 0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104),
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAfEE (1)
DOCKET NL55ER (2)
PAGE (3)
COOPER NUCLEAR STATION 05000298 1 OF 3 j
TITLE (4) Surveillance Testing of Detection System Supervisory Circuits IVrNT DAir (5)
I trR MtseBra (6)
REPORT DATE (7)
OTHER FACILITIES IINOLVED (8)
S ISION MONTH DAY YEAR years MONTH DAY YEAR NUMBER NUMBER 95 FACILITY NAME DOCKET NUMBER 01 07 95 95
-- 001 --
00 02 06 OPERATING THIS RIPORT IS SUBMITTED PtRSUANT TO THE REQUIRFIENTS OF 10 CFR i: (Check one or more) (11) g MODE' (9) 20.402(b) 20.405(c) 50.73(e)(2)(iv) 73.71(b)
POWER 000 LEVEL (10) 20.405(a)(1)(ti) 50.36(c)(2)
- 50. 73(a)(2)(vi l )
OTHER 20.405(a)(1)(tii) x 50.73(a)(2)(1) 50.73(a)(2)(viii)(A)
(Specify in 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B)
[C 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)l LICENSEE CONTACT FOR THIS LER (17) l NAME TELEPHONE NUMBER (include Area Code)
Art Alford, Senior Staf f Nuclear Licensing & Safety Eng.
(402) 825-3811 CGEPLETF ONE LINE FOR IACH CGOPOIIFNT FAltlRE DFSCRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUFACTURER
CAUSE
SYSTEM COMPONENT MANUFACTURER g
D IC DET K120 Y
SUPPLIIENTAL REPORT EXPICTFD (14)
EXPECTED MONTH DAY YEAR YES SUBMISSION X
NO (If yes, conplete EXPECTED SUBMISSION DATE).
DATE (15) 1 ARSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
During installation of design change (DC; 94-0302, three Diesel Generator (DG) carbon dioxide (CO2) photoelectric detector supervi e r, circuitn falled to annunciate when doenergized.
The failure to annunciate was due to sticking contacts which were cleaned and retested satisfactorily. An investigation into the incident determined that the supervisory circuits were not being tested every six months as required by Technical Specification 4.14. B.
The CO2 photoelectric detectors are part of a non-proprietary in-house system design which contains loss of power relays.
These relays were not included in the surveillance procedures when the system was originally installed in 1979.
On Febcuary 1,1995, during the ongoing review of other potentially missed surveillances on supervisory circuits, it was discovered that the supervisory circuits associated with the fire detectors serving the Service Water Pump (SWP) room Halon systems were also not being tested every six months per the Technical Specifications.
This review is continuing.
Per NUREG-1022, the cause of this event is attributed to Defective Procedure, NUREG-1022 code D, specifically an inadequate Design Change Process.
This also satisfies the Special Report requirement of Technical Specification 3.14.B.2.
kRC
I 1
,M C FORM 366A U.S. NUCLEAR REGULATORY COMEISSION APPROVED BY OMB No. 3150-0104 i
(5 92)
EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER)
THE INFORMATION AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (MNBB U14), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104),
OFFICE OF MANAGEMENT AND BUDCET. WASHINGTON, DC ?0503.
fACitITY NAMF (1)
DoCET NtstBER (?)
LER M!BIBER (6h PAGE (3)
SEQUENTIAL REVISION YEAR COOPER NUCLEAR STATION 05000298 2 OF 3 95
-- 001 --
00 TEXT (If more space is reautred. use additional copies of NRC Form 366A) (IT)
Plant Status The plant was in cold shutdown at the time of the event.
Event Description
During a clearance order being hung for a design change, three DG CO2 photoelectric detector loss of power supervisory circuits failed to annunciate when deenergized. The detectors' internal trouble relay was determined as the cause.
When the detectors' trouble relay is deenergized, its contacts are designed to open and annunciate in the control room. However, when the DG CO2 detectors' trouble relay was deenergized, the contacts remained closed. The detectors' contacts were cleaned and retested satisfactorily.
The DG CO2 detection system and supervisory circuit is of an in house non-proprietary design that does not have an Underwriter's Laboratories (UL) listing. The supervisory circuit for each detector consists of a loss of power relay integral to the detector itself which annunciates within the plant status computer (RONAN) system.
Supervisory meter relays provide annunciation of overall CO2 system power failure.
These meter relays are tested every 18 months. This system was installed in 1979.
On February 1, 1995, during the ongoing review of other potentially missed surveillances on supervisory circuits, it was discovered that the supervisory circuits associated with the fire detectors serving the Service Water Pump (SWP) room Halon systems were also not being tested every six months per the Technical Specifications.
This review is continuing.
Of ten available supervisory circuits, seven are tested by CNS procedures; however, the supervisory circuit associated with the Halon system detectors themselves is one of the three not tested.
The other two are ground fault and pull station supervisory circuits that are not required to be tested by Technical Specifications.
For the SWP Halon system, the test procedure was originally developed and is routinely performed by an outside vendor that has little familiarity with CNS Technical Specification requirements.
Recognition of the Technical Specification requirement for testing the detector supervisory circuits therefore went unnoticed by the test performers. This system was installed in 1985.
Cause
The root cause is an inadequate design change process.
The design change process in use at the time did not provide c*necklists or other steps in the procedure to assure that appropriate Technical Specification surveillance requirements are incorporated into plant procedures.
Checklists have been provided since 1988.
l t
,NAC FONM 366A U.S. NUCLEAR RElaAATORY C(BOIISSION APPROWED BY (35 N0. 3150-0106 (5 92)
EXPIRES 5/31/95 1
l ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH I
THIS INFORMATION COLLECTION REQUESir 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO
. LICENSEE EVENT REPORT (LER)
THE INFORMATION AND RECORDS MANAGEMENT BRANCH
{
" EXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104),
OFFICE OF j
MANAGEMENT AND BUDGET. WASHINGTON, DC 20503.
FACILITY IWWE (1)
DOCKET IRAGER (2)
LER IRAGER (6?
PAGE (3)
SEQUENTIAL REVISION YEAR COOPER NUCLEAR STATION 05000298 3 OF 3 95
-- 001 --
00 TEXT (If more 9;oace is recuired. use additional copies of NRC Form 366A) (17) l Safety Si r.ni ficance Although not all of the detector supervisory circuits were tested as required by the Technical Specifications, the alarm functions and system supervisory circuits have been tested and verified operable as required by Surveillance Procedures.
By not testing the individual detector supervisory circuits, had a detector lost power or continuity, it may not have been immediately identified. However, the ability to initiate CO2 or Halon, as applicable, was not compromised.
Based on the above, the safety significance of this event is minimal.
Corrective Action
A fire watch was posted in the DG fire areas and was maintained until the detection system was declared operable.
A temporary procedure change notice to the surveillance procedure was written, the DG CO2 i
detector supervisory circuits were tested and declared operable, and then the fire watch was released.
An hourly firewatch patrol was established for the SWP roo:n.
The SWP room Halon detector supervisory circuit will be verified operable by March 1, 1995.
A surveillance testing validation program, the purpose of which is to review the surveillance testing methods and scope against the Technical Specifications requirements, including fire detection supervisory circuits, is in progress. The Fire Protection i
surveillance validation will be completed by June 1, 1995.
The design change process has been significantly improved since these systems were originally installed, no additional action is planned.
Similar Events
None.
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LIST OF NRC COMMITMENTS l ATTACHMENT 3 l
3 Correspondence'No: NLS950057 The following table identifies those actions committed to by the District in this document.
l Any other actions discussed in the submittal represent intended or planned actions by the District.
They are described to the NRC for the NRC's information and are not regulatory I
commitments
Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITTED DATE
COMMITMENT
OR OUTAGE The SWP room Halon detector supervisory circuit will be 3/1/95 verified operable.
A surveillance testing validation program, the purpose of which is to review the surveillance testing methods and scope to the Technical Specification requirements, 6/1/95 including fire detection supervisory circuits, is in progress.
PROCEDURE NUMBER 0.42 REVISION NUMBER 0 PAGE 10 0F 16
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| 05000298/LER-1995-001, :on 950107,tested Surveillance of Detection Sys Supervisory Circuits.Caused by Defective Procedure.Fire Watch Posted in DG Fire Areas & Maintained Until Detection Sys Was Declared Operable |
- on 950107,tested Surveillance of Detection Sys Supervisory Circuits.Caused by Defective Procedure.Fire Watch Posted in DG Fire Areas & Maintained Until Detection Sys Was Declared Operable
| 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) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(e)(2)(iv) | | 05000298/LER-1995-002, :on 950110,14 PCIVs Documented as Not Having Been Modified to Prevent Potential auto-opening Upon Manual Reset.Caused by Personnel Error.Control Circuitry of 14 PCIVs Modified to Prevent auto-opening |
- on 950110,14 PCIVs Documented as Not Having Been Modified to Prevent Potential auto-opening Upon Manual Reset.Caused by Personnel Error.Control Circuitry of 14 PCIVs Modified to Prevent auto-opening
| 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) | | 05000298/LER-1995-003, :on 950128,annual Cycling Surveillance of Fire Protection Valves Was Missed.Caused by Defective Procedure. Temporary Procedure Change Was Initiated to Sp 6.4.5.2.9 |
- on 950128,annual Cycling Surveillance of Fire Protection Valves Was Missed.Caused by Defective Procedure. Temporary Procedure Change Was Initiated to Sp 6.4.5.2.9
| 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)(B) | | 05000298/LER-1995-004, :on 950201,primary Containment Group Isolations Occurred.Caused by Surveillance Procedure Deficiencies.Sp 6.3.10.2 Was Terminated & Correct Valve Lineup Was Determined |
- on 950201,primary Containment Group Isolations Occurred.Caused by Surveillance Procedure Deficiencies.Sp 6.3.10.2 Was Terminated & Correct Valve Lineup Was Determined
| 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)(viii)(B) | | 05000298/LER-1995-005, :on 950210,safety Relief Valves Failed to Operate from Control Room.Caused by Rust/Corrosion in Solenoid Valve Assembly Resulting in Binding of Plunger to Bonnet Tube.Failed Solenoid Valves Replaced |
- on 950210,safety Relief Valves Failed to Operate from Control Room.Caused by Rust/Corrosion in Solenoid Valve Assembly Resulting in Binding of Plunger to Bonnet Tube.Failed Solenoid Valves 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) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000298/LER-1995-006, :on 950209,SRMs Documented as Not Having Been Calibrated in Accordance W/Stated Requirements of Tss.Caused by Personnel Error.Srm Quarterly Calibration Surveillance Procedure Revised & SRM Recalibrated |
- on 950209,SRMs Documented as Not Having Been Calibrated in Accordance W/Stated Requirements of Tss.Caused by Personnel Error.Srm Quarterly Calibration Surveillance Procedure Revised & SRM Recalibrated
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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) 10 CFR 50.73(a)(2)(1) | | 05000298/LER-1995-007, :on 950224,iodine Channel of CR Air Sampling Monitor RMV-RM-1 Failed to Meet Calibr Tolerance Required by Sp 6.4.6.3.1 Due to Inadequate Procedure.Sps 6.4.6.3.1 & 6.2.3.3.1 Will Be Revised by 950430 |
- on 950224,iodine Channel of CR Air Sampling Monitor RMV-RM-1 Failed to Meet Calibr Tolerance Required by Sp 6.4.6.3.1 Due to Inadequate Procedure.Sps 6.4.6.3.1 & 6.2.3.3.1 Will Be Revised by 950430
| 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) | | 05000298/LER-1995-008, :on 950314,particulate Filter in Erp Normal Range Kaman Was Discovered Missing Due to Defective Procedure.Examined Remaining Monitors & Backup Samplers to Verify Proper Installation of Filters |
- on 950314,particulate Filter in Erp Normal Range Kaman Was Discovered Missing Due to Defective Procedure.Examined Remaining Monitors & Backup Samplers to Verify Proper Installation of Filters
| 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)(B) | | 05000298/LER-1995-009, :on 950401,fire Suppression Water Sys Did Not Meet Minimum Requirements for Operability Due to Pinhole Leak Developing in Section of Piping.Pinhole Leak Was Temporarily Repaired |
- on 950401,fire Suppression Water Sys Did Not Meet Minimum Requirements for Operability Due to Pinhole Leak Developing in Section of Piping.Pinhole Leak Was Temporarily Repaired
| 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) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000298/LER-1995-010, :on 950413,unanalyzed Condition Discovered During Closeout of RHR Min Flow Valve Design Change (DC) 94-332.Caused by Improper Review of Previous DC 76-2.Util Implemented DC 94-332 |
- on 950413,unanalyzed Condition Discovered During Closeout of RHR Min Flow Valve Design Change (DC) 94-332.Caused by Improper Review of Previous DC 76-2.Util Implemented DC 94-332
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000298/LER-1995-011, :on 950509,three Fire Detectors in DG Rooms Did Not Give Trouble Alarm When Removed from Bases.Caused by Neglected Removal of Mfg Jumpers.Jumpers Removed & Zone Retested Satisfactorily |
- on 950509,three Fire Detectors in DG Rooms Did Not Give Trouble Alarm When Removed from Bases.Caused by Neglected Removal of Mfg Jumpers.Jumpers Removed & Zone Retested Satisfactorily
| 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) | | 05000298/LER-1995-012, :on 951014,RPS Trip Signal & Primary Containment Group Isolations Occurred During Shutdown for Refueling Outage.Evaluated & Revised Procedures.W/Forwarding Ltr |
- on 951014,RPS Trip Signal & Primary Containment Group Isolations Occurred During Shutdown for Refueling Outage.Evaluated & Revised Procedures.W/Forwarding Ltr
| 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) | | 05000298/LER-1995-013, :on 950523,determined That Plant Procedural Requirements Inconsistent W/Assumptions & Commitments Made to NRC on 910930.Caused by Programmatic Deficiency.Rev to Procedure 5.2.5.1 Made |
- on 950523,determined That Plant Procedural Requirements Inconsistent W/Assumptions & Commitments Made to NRC on 910930.Caused by Programmatic Deficiency.Rev to Procedure 5.2.5.1 Made
| 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) 10 CFR 50.73(a)(2)(viii)(B) | | 05000298/LER-1995-015, :on 951026,F Bus Was Transferred to Emergency Transformer Due to Error Committed by Engineer in Providing Test Instructions in Mwr 95-2599.Counseled Engineer That Prepared Mwr 95-2599 |
- on 951026,F Bus Was Transferred to Emergency Transformer Due to Error Committed by Engineer in Providing Test Instructions in Mwr 95-2599.Counseled Engineer That Prepared Mwr 95-2599
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(viii) | | 05000298/LER-1995-016, :on 951027,during Core off-load,MCR Supply Fans Shut Down.Single Train CREFS Inoperable.Caused by Personnel Error.Cr Ventilation Restored 9 Minutes Later.Licensed Operator Responsible Counseled |
- on 951027,during Core off-load,MCR Supply Fans Shut Down.Single Train CREFS Inoperable.Caused by Personnel Error.Cr Ventilation Restored 9 Minutes Later.Licensed Operator Responsible Counseled
| | | 05000298/LER-1995-017, :on 951023,safety/relief & Safety Valves Found Outside TS Limiting Safety Sys Setting.Caused by Corrosion Bonding of Pilot Disc to Pilot Seat.Safety Relief Valve Surveillance Procedure Revised |
- on 951023,safety/relief & Safety Valves Found Outside TS Limiting Safety Sys Setting.Caused by Corrosion Bonding of Pilot Disc to Pilot Seat.Safety Relief Valve Surveillance Procedure Revised
| 10 CFR 50.73(a)(2) | | 05000298/LER-1995-018, :on 951121,recognized Design Bases of Steam Tunnel Blowout Panels Not Well Documented.Cause Cannot Be Established.Bulk of Fiberglass Removed from Blowout Panels |
- on 951121,recognized Design Bases of Steam Tunnel Blowout Panels Not Well Documented.Cause Cannot Be Established.Bulk of Fiberglass Removed from Blowout Panels
| 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1) | | 05000298/LER-1995-019, :on 951124,CR Emergency Filter Sys (CREFS) Was Inoperable Due to EDG Being Unavailable.Restored CREFS to Operability |
- on 951124,CR Emergency Filter Sys (CREFS) Was Inoperable Due to EDG Being Unavailable.Restored CREFS to Operability
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000298/LER-1995-020, :on 951125,found That Drawing Change Process Deficiency Resulted in Noncompliance w/1CFR50 App R.Design Change Process Being Revised & Training Will Be Presented to Appropriate Design Personnel on Process Revs |
- on 951125,found That Drawing Change Process Deficiency Resulted in Noncompliance w/1CFR50 App R.Design Change Process Being Revised & Training Will Be Presented to Appropriate Design Personnel on Process Revs
| 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) | | 05000298/LER-1995-021, :on 951209,RHR Pump a Tripped During SDC Mode, Due to Spurious Actuation of Either SDC Suction High Pressure Switch or Momentary Loss of 16A-K28 or 16A-K50 Logic Relay.Sdc Returned to Svc |
- on 951209,RHR Pump a Tripped During SDC Mode, Due to Spurious Actuation of Either SDC Suction High Pressure Switch or Momentary Loss of 16A-K28 or 16A-K50 Logic Relay.Sdc Returned to Svc
| 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 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1) | | 05000298/LER-1995-022, :on 951213,reactor Trip Signal,Esf Occurred. Caused by Personnel Error.Training to Maint Planners Provided to Enhance Ability to Identify & Develop Post Maint Testing Requirements |
- on 951213,reactor Trip Signal,Esf Occurred. Caused by Personnel Error.Training to Maint Planners Provided to Enhance Ability to Identify & Develop Post Maint Testing Requirements
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) | | 05000298/LER-1995-023, :on 951030,loss of Configuration Control by Valve Vendor Occurred.Caused by MOV Program Ownership & Weaknesses in Programmatic Controls.Vendors for MOVs Included in GL 89-10 Program Audited |
- on 951030,loss of Configuration Control by Valve Vendor Occurred.Caused by MOV Program Ownership & Weaknesses in Programmatic Controls.Vendors for MOVs Included in GL 89-10 Program Audited
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