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| {{#Wiki_filter:---) NllC ,_.., -IS-all U.I. NUCl.IAll lllQULA TDllY CO-.ION .-OVID DMI NO. Jll0-41CW LICENSEE EVENT REPORT (LER) IXl'lllll. | | {{#Wiki_filter:~~--- |
| If.II 111 'ACILITY -111 I DOCltlT ,._.,. Cll I .. --* PALISADES NUCLEAR PLANT O 15 I 0 I 0 I 0 I 2 I 5 I 5 1 J OF n I TITLI 161 Failure To Establish Fire Watch Associated With Inoperable Sprinklers IVINT DATI Ill 111 llll'OllT DATI 171 DTMlll "ACILITIU IMYOLVID *1 MONTH QAY Yl!All YEAll }\ | | ) |
| rr: :i= MONTH DAY YEAR 'AC:ILITY | | NllC ,_.., - U.I. NUCl.IAll lllQULA TDllY CO-.ION IS-all .-OVID DMI NO. Jll0-41CW IXl'lllll. If.II 111 LICENSEE EVENT REPORT (LER) |
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| DOCKIT NUMellllll NIA 0 I 5 0 I 4 8 7 81 7 -01115 -0 I 0 0 I 6 0 I 3 81 7 NI A 0 115 I 0 I 0 I 0 I I I OPlllATING TMll lllPOllT II 1U911TTID l'UlllUANT TO THI lllQUllllMINTI 0, to C,11 §:IC/tell | | 'ACILITY - |
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| ,,,, llODI Ill N -t-----r---'--+-1 20.Gfil *.'7119112111wl l'OWall l ..* 111111 "" -71.71111 n.11*1 **11111 *.nlalCllC*I LIVcto 1 1L o, 9 19 - | | Failure To Establish Fire Watch Associated With Inoperable Sprinklers IVINT DATI Ill l.lllN~ll 111 llll'OllT DATI 171 DTMlll "ACILITIU IMYOLVID *1 MONTH QAY Yl!All YEAll } \ ll~~=~AI. rr: :i= MONTH DAY YEAR 'AC:ILITY ......... DOCKIT NUMellllll NIA 0I 5 0 I4 8 7 81 7 - 01115 - 0 I0 0 I 6 0 I3 81 7 NI A 0 115 I 0 I 0 I 0 I I I |
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| '*"" LICINlll CONTACT "Oii THll Liii 1121 lllAMI TILll'HONI NUMlllll AlllA CODI' C S Kozup, Technical Engineer, Palisades cor.LITI ONI LINI POii IACH cor.oNINT
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| 'AILUlll 018ClllllD IN TMll llll'OllT 1111 CAUH IYITIM COMl'ONINT MANU,AC:. | | l'OWall 111111 "" **11111 1 |
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| TUlllll A I I I I I I I I I I I I I I I I I I I I I I I I I I I I IU .. UMINTAL 1111 1 011T IX'8CTID 11" IXPICTID MONTH DAY VJAll allMllllDN DATI 1111 I I I Abstract On March 22, 1987 at approximately 1445, while performing a quarterly test to verify fire suppression system flow operability, Operations personnel identified that water flow switch fire detector WFS-262 [KP;FIS] was inoperable. | | ~---"'-...._ 9.......................... |
| Technical Specification 3.22.1, Action 1, states that when the number of instruments (detectors) operable is less than required, "within one hour, establish a fire watch patrol to inspect the zone with the inoperable instrument at least once per hour". Contrary to this requirement, no fire watch patrol was established until April 20, 1987. The Plant was in hot shutdown condition (primary coolant system: 2032 psia, 532 degrees) at the time of the event. The inoperable detector was identified and logged on test data sheets by Auxiliary Operators, who then initiated a work request for detector repair. Results of the test were reviewed by the Shift Supervisor, however, no hourly fire watch patrol was established. | | 19 - OTHlll 16-,,._ In~ |
| The failure to implement the required Technical Specification Action Statement resulted from the quarterly test used to verify fire suppression system operability not identifying equipment directly associated with Technical Specification. | | 111111111 111.a111121 *.nt.11211wll |
| 8706100284 870603 PDR ADOCK 05000255 S PDR NllCF--18-131 LER 87-015 | | - . - In T1*r. NllC '°"" |
| . *"' NRC Form -A U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMS NO. 3150--0104 EXPIRES: 8/31 /85 | | -- |
| * 19-831 . LICENSEE EVENT REPORT (LERI TEXT CONT_INUATION FACILITY NAME 111 DOCKET NUMHR 12) LEl'I NUMaER Ill PAGE 131 PALISADES NUCLEAR PLANT 0 I 5 I 0 I 0 I 0 I 21 5 I 5 81 7 -011 I 5 -0 I 0 o* 1 2 OF 0 I 3 TEXT l/r --is '9qUirwl, -...,,,.. NRC Fonn BA'*I 1171 Description On March 22, 1987 at approximately 1445, while performing a quarterly test to verify fire suppression system flow operability, Operations personnel identified that water flow switch fire detector WFS-2G2 [KP;FIS] was inoperable.
| | l:llli= =~:; |
| Technical Specification | | **71111CllCwllllCAI |
| : 3. 22 .1, Action 1, states that when .the number of.instruments (detectors) operable is less than required, "within one hour, establish a fire watch patrol to .inspect the zone with the inoperable instrument at least once per hour". Contrary to this requirement, no fire watch patrol was established until April 20, 1987. The Plant was in hot shutdown condition (primary coolant system: 2032 psia, 532 degrees) at the time of the event. The detector is a Notifier, model NVR-2BZ and is normally maintained under a* static water pressure of approximately 100 psig. The Fire Protection System (FPS) associated with this detector is actuated by the melting of a fusible link within the sprinkler heads. Wl;len the fusible link releases, it causes the spray head pressure to drop and a pilot valve to -open. Water is then permitted to pass through the water flow switch fire detectors which sense the flow and annunciate in the Control Room. The inoperable detector was identified and logged by Auxiliary Operators (AO) on the test data sheets. A work request, as required by the test, was also initiated by the AOs and indicated on the data sheet. Results of the test were then reviewed by the Shift Supervisor, however, an hourly fire watch patrol was not established until April 20, when Operations personnel, releasing the detector for repair, -identified that the fire watch patrol was not being performed.
| | ~ I0.7~1121111 I0.7SC.ICllCMI *.711alCllCwlllC81 |
| Cause Of The Event The failure of the on-duty Shift Supervisor to implement the required Technical Specification Action statement for the inoperable water flow switch fire detector resulted from a lack of awareness to Action Statements directly associated with this detector. | | '*"" |
| The quarterly test (CL 2i.13) used to verify the fire suppression system operability does .not identify equipment directly associated with Technical Specifications*, does not prescribe actions beyond initiating a work order to repair the inoperable instrument, and does not reference Technical Specifications within the test. Corrective Actions The quarterly test' (CL* 21.13) described in this event is being revised to include references to appropriate Technical Specifications and to call out equipment which, if inoperable, would invoke Action Statements described in Technical Specifications. | | ID.7:111112111111 111.nt.JIJllal LICINlll CONTACT "Oii THll Liii 1121 lllAMI TILll'HONI NUMlllll AlllA CODI' C S Kozup, Technical Engineer, Palisades cor.LITI ONI LINI POii IACH cor.oNINT 'AILUlll 018ClllllD IN TMll llll'OllT 1111 COMl'ONINT MANU,AC:. SYITIM COWONINT MANU,AC:. |
| NFOC FORM 31in1i1.I.\. | | CAUH IYITIM TUlll!ll TUlllll A I I I I I I I I I I I I I I I I I I I I I I I I I I I I IU. .UMINTAL 11111011T IX'8CTID 11" MONTH DAY VJAll IXPICTID allMllllDN DATI 1111 I I I Abstract On March 22, 1987 at approximately 1445, while performing a quarterly test to verify fire suppression system flow operability, Operations personnel identified that water flow switch fire detector WFS-262 [KP;FIS] was inoperable. Technical Specification 3.22.1, Action 1, states that when the number of instruments (detectors) operable is less than required, "within one hour, establish a fire watch patrol to inspect the zone with the inoperable instrument at least once per hour". Contrary to this requirement, no fire watch patrol was established until April 20, 1987. The Plant was in hot shutdown condition (primary coolant system: 2032 psia, 532 degrees) at the time of the event. |
| 0 I -u .l.J 19-831 | | The inoperable detector was identified and logged on test data sheets by Auxiliary Operators, who then initiated a work request for detector repair. |
| , "'RC Form 3MA 19-831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150--0104 EXPIRES: 8/31 /85 FACILITY NAME 111 LEll NUMeEll Ill PALISADES NUCLEAR PLANT 0 I 5 I 0 I 0 I 0 12 I 51 5 81 7 -0111 5 -0 I 0 0 I 3 OF 0 I 3 TDCT llf--ii,..,,._, --NRC Fonn .-..*111171 All Operations Department Fire Protection System checklists (tests) will be reviewed to ensure appropriate references are made to Technical Specifications and actions described therein. Analysis Of The Event Operability of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early states. Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program. The inoperability of the water flow switch fire detector will cause the loss of an annunciated alarm in the c'ontrol Room, but wi.11 not render the fire suppression system inoperable. | | Results of the test were reviewed by the Shift Supervisor, however, no hourly fire watch patrol was established. The failure to implement the required Technical Specification Action Statement resulted from the quarterly test used to verify fire suppression system operability not identifying equipment directly associated with Technical Specification. |
| If activated, the sprinkler would perform its designed function. | | 8706100284 870603 PDR ADOCK 05000255 S PDR NllCF-- |
| In addition, sprinkler system activation would cause a fire suppression system pump to actuate and an alarm to annunciate in the Control Room. Due to the failure to implement the required hourly fire watch patrol, the capability for prompt detection of local fires was reduced, however, in addition to the above, Operations personnel perform shiftly walkdowns of the affected area (1-2 Diesel Generator Room). Also, the water flow switch fire detector in the 1-1 Diesel Generator Room, which is directly adjacent to the 1-2 Diesel Room was operable during the period detailed above. This event is being reported per 10CFR50.73 (a)(2)(i) as a condition prohibited by the Plant's Technical Specifications. | | 18-131 LER 87-015 |
| Additional Information For information regarding the cause of the water flow switch fire detector's inoperability and corrective actions taken, reference LER 87-010. For information describing previous occurrences of failure to perform a one hour fire watch patrol reference: | | |
| LERs; 83-061, 83-068 and 83-076 NRC FORM :drls\il.t\. | | . *"' |
| v 1 -v 19-831 _I General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 June 3, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -LICENSEE EVENT REPORT 87-015 -FAILURE TO ESTABLISH FIRE WATCH ASSOCIATED WITH INOPERABLE SPRINKLERS Licensee Event Report (LER) 87-015, (Failure to Establish Fire Watch Associated With Inoperable Sprinklers) is attached. | | NRC Form - A U.S. NUCLEAR REGULATORY COMMISSION |
| This event is reportable to the NRC per 10CFR50.73(a)(2)(i). | | * 19-831 . |
| Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector | | LICENSEE EVENT REPORT (LERI TEXT CONT_INUATION APPROVED OMS NO. 3150--0104 EXPIRES: 8/31 /85 FACILITY NAME 111 DOCKET NUMHR 12) |
| -Palisades Attachment}} | | LEl'I NUMaER Ill PAGE 131 PALISADES NUCLEAR PLANT 0 I 5 I 0 I 0 I 0 I 21 5 I 5 81 7 - 011 I 5- 0 I 0 o* 1 2 OF 0 I3 TEXT l/r - - is '9qUirwl, - ...,,,.. NRC Fonn BA'*I 1171 Description On March 22, 1987 at approximately 1445, while performing a quarterly test to verify fire suppression system flow operability, Operations personnel identified that water flow switch fire detector WFS-2G2 [KP;FIS] was inoperable. Technical Specification 3. 22 .1, Action 1, states that when .the number of.instruments (detectors) operable is less than required, "within one hour, establish a fire watch patrol to .inspect the zone with the inoperable instrument at least once per hour". Contrary to this requirement, no fire watch patrol was established until April 20, 1987. The Plant was in hot shutdown condition (primary coolant system: 2032 psia, 532 degrees) at the time of the event. |
| | The detector is a Notifier, model NVR-2BZ and is normally maintained under a* |
| | static water pressure of approximately 100 psig. The Fire Protection System (FPS) associated with this detector is actuated by the melting of a fusible link within the sprinkler heads. Wl;len the fusible link releases, it causes the spray head pressure to drop and a pilot valve to -open. Water is then permitted to pass through the water flow switch fire detectors which sense the flow and annunciate in the Control Room. |
| | The inoperable detector was identified and logged by Auxiliary Operators (AO) on the test data sheets. A work request, as required by the test, was also initiated by the AOs and indicated on the data sheet. |
| | Results of the test were then reviewed by the Shift Supervisor, however, an hourly fire watch patrol was not established until April 20, when Operations personnel, releasing the detector for repair, -identified that the fire watch patrol was not being performed. |
| | Cause Of The Event The failure of the on-duty Shift Supervisor to implement the required Technical Specification Action statement for the inoperable water flow switch fire detector resulted from a lack of awareness to Action Statements directly associated with this detector. The quarterly test (CL 2i.13) used to verify the fire suppression system operability does .not identify equipment directly associated with Technical Specifications*, does not prescribe actions beyond initiating a work order to repair the inoperable instrument, and does not reference Technical Specifications within the test. |
| | Corrective Actions The quarterly test' (CL* 21.13) described in this event is being revised to include references to appropriate Technical Specifications and to call out equipment which, if inoperable, would invoke Action Statements described in Technical Specifications. |
| | NFOC FORM 31in1i1.I.\. 0 I -u .l.J 19-831 |
| | |
| | , "'RC Form 3MA U.S. NUCLEAR REGULATORY COMMISSION 19-831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED OMB NO. 3150--0104 EXPIRES: 8/31 /85 FACILITY NAME 111 LEll NUMeEll Ill PALISADES NUCLEAR PLANT 0 I 5 I 0 I 0 I 0 12 I 51 5 81 7 - 0111 5 - 0 I0 0I3 OF 0 I3 TDCT l l f - - ii,..,,._, - - N R C Fonn .-..*111171 All Operations Department Fire Protection System checklists (tests) will be reviewed to ensure appropriate references are made to Technical Specifications and actions described therein. |
| | Analysis Of The Event Operability of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early states. Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program. |
| | The inoperability of the water flow switch fire detector will cause the loss of an annunciated alarm in the c'ontrol Room, but wi.11 not render the fire suppression system inoperable. If activated, the sprinkler would perform its designed function. In addition, sprinkler system activation would cause a fire suppression system pump to actuate and an alarm to annunciate in the Control Room. |
| | Due to the failure to implement the required hourly fire watch patrol, the capability for prompt detection of local fires was reduced, however, in addition to the above, Operations personnel perform shiftly walkdowns of the affected area (1-2 Diesel Generator Room). Also, the water flow switch fire detector in the 1-1 Diesel Generator Room, which is directly adjacent to the 1-2 Diesel ~enerator Room was operable during the period detailed above. |
| | This event is being reported per 10CFR50.73 (a)(2)(i) as a condition prohibited by the Plant's Technical Specifications. |
| | Additional Information For information regarding the cause of the water flow switch fire detector's inoperability and corrective actions taken, reference LER 87-010. |
| | For information describing previous occurrences of failure to perform a one hour fire watch patrol reference: LERs; 83-061, 83-068 and 83-076 NRC FORM :drls\il.t\. v 1 - v ~_,. |
| | 19-831 |
| | _I |
| | |
| | General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 June 3, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - |
| | LICENSEE EVENT REPORT 87-015 - FAILURE TO ESTABLISH FIRE WATCH ASSOCIATED WITH INOPERABLE SPRINKLERS Licensee Event Report (LER) 87-015, (Failure to Establish Fire Watch Associated With Inoperable Sprinklers) is attached. This event is reportable to the NRC per 10CFR50.73(a)(2)(i). |
| | Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment}} |
|
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18066A6271999-09-0202 September 1999
LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr
ML18066A6221999-08-20020 August 1999
LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr
ML18066A3781999-01-20020 January 1999
LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr
ML18068A4851998-10-29029 October 1998
LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
ML18066A2831998-08-18018 August 1998
LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
ML18066A2261998-06-30030 June 1998
LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
ML18066A1781998-06-0909 June 1998
LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures
ML18065B2451998-05-13013 May 1998
LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge
ML18065B1151997-12-0909 December 1997
LER 97-013-00:on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability
ML18067A7751997-11-11011 November 1997
LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved
ML18067A7581997-10-30030 October 1997
LER 97-010-00:on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation
ML18067A7461997-10-23023 October 1997
LER 97-009-00:on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure.
ML18067A7191997-10-10010 October 1997
LER 97-008-00:on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed
ML18067A6951997-09-24024 September 1997
LER 97-007-00:on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts
ML18067A5651997-06-0303 June 1997
LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested
ML18067A5461997-05-12012 May 1997
LER 97-006-00:on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities
ML18067A4431997-03-24024 March 1997
LER 97-004-00:on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS
ML18067A4391997-03-21021 March 1997
LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired
ML18067A4401997-03-21021 March 1997
LER 97-003-00:on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be verified.W/970321 Ltr
ML18066A8931997-02-21021 February 1997
LER 97-002-00:on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared operable.W/970221 Ltr
ML18066A8751997-02-0505 February 1997
LER 97-001-00:on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator repaired.W/970205 Ltr
ML18066A8041996-12-23023 December 1996
LER 96-014-00:on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment
ML18066A7831996-12-16016 December 1996
LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced
ML18065A9951996-10-0404 October 1996
LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg
ML18065A9171996-09-0909 September 1996
LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr
ML18065A8961996-08-29029 August 1996
LER 96-011-00:on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments
ML18065A8811996-08-20020 August 1996
LER 96-005-01:on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced
ML18065A8741996-08-16016 August 1996
LER 96-010-00:on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected
ML18065A8651996-08-12012 August 1996
LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr
ML18065A8601996-08-0202 August 1996
LER 96-006-01 on 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit
ML18065A8321996-08-0101 August 1996
LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board
ML18065A7691996-06-12012 June 1996
LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr
ML18065A6901996-05-0101 May 1996
LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr
ML18065A6681996-04-22022 April 1996
LER 96-007-00:on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting modified.W/960422 Ltr
ML18065A5721996-03-11011 March 1996
LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded
ML18065A5261996-03-0101 March 1996
LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr
ML18065A5111996-02-19019 February 1996
LER 94-012-02:on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD.W/960219 Ltr
ML18065A5061996-02-19019 February 1996
LER 96-004-00:on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts
ML18065A5021996-02-15015 February 1996
LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr
ML18065A4581996-01-31031 January 1996
LER 96-001-00:on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS.W/960131 Ltr
ML18065A4421996-01-19019 January 1996
LER 95-016-00:on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save Pcs Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision.W/960119 Ltr
ML18065A4041996-01-15015 January 1996
LER 95-014-00:on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis documentation.W/960115 Ltr
ML18065A3291995-12-0404 December 1995
LER 95-013-00:on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as required.W/951204 Ltr
ML18065A2361995-11-0202 November 1995
LER 95-012-00:on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt connections.W/951102 Ltr
ML18065A2051995-10-20020 October 1995
LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised
ML18065A0841995-09-18018 September 1995
LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr
ML18065A0681995-09-14014 September 1995
LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line
ML18065A0651995-09-0808 September 1995
LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment
ML18064A8781995-08-28028 August 1995
LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage
ML18064A8831995-08-21021 August 1995
LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr
1999-09-02
[Table view]
Category:RO)
MONTHYEARML18066A6271999-09-0202 September 1999
LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr
ML18066A6221999-08-20020 August 1999
LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr
ML18066A3781999-01-20020 January 1999
LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr
ML18068A4851998-10-29029 October 1998
LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
ML18066A2831998-08-18018 August 1998
LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
ML18066A2261998-06-30030 June 1998
LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
ML18066A1781998-06-0909 June 1998
LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures
ML18065B2451998-05-13013 May 1998
LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge
ML18065B1151997-12-0909 December 1997
LER 97-013-00:on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability
ML18067A7751997-11-11011 November 1997
LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved
ML18067A7581997-10-30030 October 1997
LER 97-010-00:on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation
ML18067A7461997-10-23023 October 1997
LER 97-009-00:on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure.
ML18067A7191997-10-10010 October 1997
LER 97-008-00:on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed
ML18067A6951997-09-24024 September 1997
LER 97-007-00:on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts
ML18067A5651997-06-0303 June 1997
LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested
ML18067A5461997-05-12012 May 1997
LER 97-006-00:on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities
ML18067A4431997-03-24024 March 1997
LER 97-004-00:on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS
ML18067A4391997-03-21021 March 1997
LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired
ML18067A4401997-03-21021 March 1997
LER 97-003-00:on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be verified.W/970321 Ltr
ML18066A8931997-02-21021 February 1997
LER 97-002-00:on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared operable.W/970221 Ltr
ML18066A8751997-02-0505 February 1997
LER 97-001-00:on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator repaired.W/970205 Ltr
ML18066A8041996-12-23023 December 1996
LER 96-014-00:on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment
ML18066A7831996-12-16016 December 1996
LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced
ML18065A9951996-10-0404 October 1996
LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg
ML18065A9171996-09-0909 September 1996
LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr
ML18065A8961996-08-29029 August 1996
LER 96-011-00:on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments
ML18065A8811996-08-20020 August 1996
LER 96-005-01:on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced
ML18065A8741996-08-16016 August 1996
LER 96-010-00:on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected
ML18065A8651996-08-12012 August 1996
LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr
ML18065A8601996-08-0202 August 1996
LER 96-006-01 on 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit
ML18065A8321996-08-0101 August 1996
LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board
ML18065A7691996-06-12012 June 1996
LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr
ML18065A6901996-05-0101 May 1996
LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr
ML18065A6681996-04-22022 April 1996
LER 96-007-00:on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting modified.W/960422 Ltr
ML18065A5721996-03-11011 March 1996
LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded
ML18065A5261996-03-0101 March 1996
LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr
ML18065A5111996-02-19019 February 1996
LER 94-012-02:on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD.W/960219 Ltr
ML18065A5061996-02-19019 February 1996
LER 96-004-00:on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts
ML18065A5021996-02-15015 February 1996
LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr
ML18065A4581996-01-31031 January 1996
LER 96-001-00:on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS.W/960131 Ltr
ML18065A4421996-01-19019 January 1996
LER 95-016-00:on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save Pcs Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision.W/960119 Ltr
ML18065A4041996-01-15015 January 1996
LER 95-014-00:on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis documentation.W/960115 Ltr
ML18065A3291995-12-0404 December 1995
LER 95-013-00:on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as required.W/951204 Ltr
ML18065A2361995-11-0202 November 1995
LER 95-012-00:on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt connections.W/951102 Ltr
ML18065A2051995-10-20020 October 1995
LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised
ML18065A0841995-09-18018 September 1995
LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr
ML18065A0681995-09-14014 September 1995
LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line
ML18065A0651995-09-0808 September 1995
LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment
ML18064A8781995-08-28028 August 1995
LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage
ML18064A8831995-08-21021 August 1995
LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr
1999-09-02
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999
Rev 5 to Palisades Nuclear Plant Colr.
ML18066A6761999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant
ML18066A6271999-09-0202 September 1999
LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr
ML18066A6351999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant
ML18066A6771999-08-31031 August 1999
Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant
ML18066A6221999-08-20020 August 1999
LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr
ML18066A6061999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr
ML18066A5201999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr
ML18066A4841999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr
ML18066A6371999-04-30030 April 1999
Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant
ML18068A5941999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr
ML18066A4161999-04-0101 April 1999
Rev 4 to COLR, for Palisades Nuclear Plant
ML18066A4501999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr
ML18066A4671999-03-31031 March 1999
Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant.
ML18068A5351999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr
ML18066A3931999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr
ML18066A3781999-01-20020 January 1999
LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr
ML20206F6131998-12-31031 December 1998
1998 Consumers Energy Co Annual Rept. with
ML18066A3651998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr
ML18066A3421998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr
ML18066A3301998-11-11011 November 1998
Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used
ML18068A4921998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr
ML18068A4851998-10-29029 October 1998
LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
ML18066A3181998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant
ML18066A2901998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr
ML18066A3191998-08-31031 August 1998
Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant
ML18066A2831998-08-18018 August 1998
LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML20237E0301998-07-31031 July 1998
ISI Rept 3-3
ML18066A2701998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr
ML18066A2311998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Palisades Nuclear Plant
ML18066A2261998-06-30030 June 1998
LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
ML18066A3061998-06-18018 June 1998
SG Tube Inservice Insp.
ML20249C4951998-06-17017 June 1998
Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review
ML18066A1781998-06-0909 June 1998
LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures
ML18066A1711998-06-0101 June 1998
Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46
ML18066A1741998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr
ML18066A2321998-05-31031 May 1998
Revised MOR for May 1998 for Palisades Nuclear Plant
ML18068A4701998-05-31031 May 1998
Annual Rept of Changes in ECCS Models Per 10CFR50.46.
ML18065B2451998-05-13013 May 1998
LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge
ML18066A2331998-04-30030 April 1998
Revised MOR for Apr 1998 for Palisades Nuclear Plant
ML18068A3461998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr
ML18066A3411998-04-22022 April 1998
Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events.
ML18065B2071998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr
ML20217C2741998-03-31031 March 1998
Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts
ML18066A2341998-03-31031 March 1998
Revised MOR for Mar 1998 for Palisades Nuclear Plant
ML18068A3041998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr
ML18066A2351998-02-28028 February 1998
Revised MOR for Feb 1998 for Palisades Nuclear Plant
ML18065B1641998-02-0505 February 1998
Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance.
ML18067A8211998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr
1999-09-30
[Table view] |
Text
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TITLI 161 111 PALISADES NUCLEAR PLANT I O 15 I 0 I 0 I 0 I 2 I 5 I 5 1 JOF nI ~
Failure To Establish Fire Watch Associated With Inoperable Sprinklers IVINT DATI Ill l.lllN~ll 111 llll'OllT DATI 171 DTMlll "ACILITIU IMYOLVID *1 MONTH QAY Yl!All YEAll } \ ll~~=~AI. rr: :i= MONTH DAY YEAR 'AC:ILITY ......... DOCKIT NUMellllll NIA 0I 5 0 I4 8 7 81 7 - 01115 - 0 I0 0 I 6 0 I3 81 7 NI A 0 115 I 0 I 0 I 0 I I I
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ID.7:111112111111 111.nt.JIJllal LICINlll CONTACT "Oii THll Liii 1121 lllAMI TILll'HONI NUMlllll AlllA CODI' C S Kozup, Technical Engineer, Palisades cor.LITI ONI LINI POii IACH cor.oNINT 'AILUlll 018ClllllD IN TMll llll'OllT 1111 COMl'ONINT MANU,AC:. SYITIM COWONINT MANU,AC:.
CAUH IYITIM TUlll!ll TUlllll A I I I I I I I I I I I I I I I I I I I I I I I I I I I I IU. .UMINTAL 11111011T IX'8CTID 11" MONTH DAY VJAll IXPICTID allMllllDN DATI 1111 I I I Abstract On March 22, 1987 at approximately 1445, while performing a quarterly test to verify fire suppression system flow operability, Operations personnel identified that water flow switch fire detector WFS-262 [KP;FIS] was inoperable. Technical Specification 3.22.1, Action 1, states that when the number of instruments (detectors) operable is less than required, "within one hour, establish a fire watch patrol to inspect the zone with the inoperable instrument at least once per hour". Contrary to this requirement, no fire watch patrol was established until April 20, 1987. The Plant was in hot shutdown condition (primary coolant system: 2032 psia, 532 degrees) at the time of the event.
The inoperable detector was identified and logged on test data sheets by Auxiliary Operators, who then initiated a work request for detector repair.
Results of the test were reviewed by the Shift Supervisor, however, no hourly fire watch patrol was established. The failure to implement the required Technical Specification Action Statement resulted from the quarterly test used to verify fire suppression system operability not identifying equipment directly associated with Technical Specification.
8706100284 870603 PDR ADOCK 05000255 S PDR NllCF--
18-131 LER 87-015
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NRC Form - A U.S. NUCLEAR REGULATORY COMMISSION
LICENSEE EVENT REPORT (LERI TEXT CONT_INUATION APPROVED OMS NO. 3150--0104 EXPIRES: 8/31 /85 FACILITY NAME 111 DOCKET NUMHR 12)
LEl'I NUMaER Ill PAGE 131 PALISADES NUCLEAR PLANT 0 I 5 I 0 I 0 I 0 I 21 5 I 5 81 7 - 011 I 5- 0 I 0 o* 1 2 OF 0 I3 TEXT l/r - - is '9qUirwl, - ...,,,.. NRC Fonn BA'*I 1171 Description On March 22, 1987 at approximately 1445, while performing a quarterly test to verify fire suppression system flow operability, Operations personnel identified that water flow switch fire detector WFS-2G2 [KP;FIS] was inoperable. Technical Specification 3. 22 .1, Action 1, states that when .the number of.instruments (detectors) operable is less than required, "within one hour, establish a fire watch patrol to .inspect the zone with the inoperable instrument at least once per hour". Contrary to this requirement, no fire watch patrol was established until April 20, 1987. The Plant was in hot shutdown condition (primary coolant system: 2032 psia, 532 degrees) at the time of the event.
The detector is a Notifier, model NVR-2BZ and is normally maintained under a*
static water pressure of approximately 100 psig. The Fire Protection System (FPS) associated with this detector is actuated by the melting of a fusible link within the sprinkler heads. Wl;len the fusible link releases, it causes the spray head pressure to drop and a pilot valve to -open. Water is then permitted to pass through the water flow switch fire detectors which sense the flow and annunciate in the Control Room.
The inoperable detector was identified and logged by Auxiliary Operators (AO) on the test data sheets. A work request, as required by the test, was also initiated by the AOs and indicated on the data sheet.
Results of the test were then reviewed by the Shift Supervisor, however, an hourly fire watch patrol was not established until April 20, when Operations personnel, releasing the detector for repair, -identified that the fire watch patrol was not being performed.
Cause Of The Event The failure of the on-duty Shift Supervisor to implement the required Technical Specification Action statement for the inoperable water flow switch fire detector resulted from a lack of awareness to Action Statements directly associated with this detector. The quarterly test (CL 2i.13) used to verify the fire suppression system operability does .not identify equipment directly associated with Technical Specifications*, does not prescribe actions beyond initiating a work order to repair the inoperable instrument, and does not reference Technical Specifications within the test.
Corrective Actions The quarterly test' (CL* 21.13) described in this event is being revised to include references to appropriate Technical Specifications and to call out equipment which, if inoperable, would invoke Action Statements described in Technical Specifications.
NFOC FORM 31in1i1.I.\. 0 I -u .l.J 19-831
, "'RC Form 3MA U.S. NUCLEAR REGULATORY COMMISSION 19-831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED OMB NO. 3150--0104 EXPIRES: 8/31 /85 FACILITY NAME 111 LEll NUMeEll Ill PALISADES NUCLEAR PLANT 0 I 5 I 0 I 0 I 0 12 I 51 5 81 7 - 0111 5 - 0 I0 0I3 OF 0 I3 TDCT l l f - - ii,..,,._, - - N R C Fonn .-..*111171 All Operations Department Fire Protection System checklists (tests) will be reviewed to ensure appropriate references are made to Technical Specifications and actions described therein.
Analysis Of The Event Operability of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early states. Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.
The inoperability of the water flow switch fire detector will cause the loss of an annunciated alarm in the c'ontrol Room, but wi.11 not render the fire suppression system inoperable. If activated, the sprinkler would perform its designed function. In addition, sprinkler system activation would cause a fire suppression system pump to actuate and an alarm to annunciate in the Control Room.
Due to the failure to implement the required hourly fire watch patrol, the capability for prompt detection of local fires was reduced, however, in addition to the above, Operations personnel perform shiftly walkdowns of the affected area (1-2 Diesel Generator Room). Also, the water flow switch fire detector in the 1-1 Diesel Generator Room, which is directly adjacent to the 1-2 Diesel ~enerator Room was operable during the period detailed above.
This event is being reported per 10CFR50.73 (a)(2)(i) as a condition prohibited by the Plant's Technical Specifications.
Additional Information For information regarding the cause of the water flow switch fire detector's inoperability and corrective actions taken, reference LER 87-010.
For information describing previous occurrences of failure to perform a one hour fire watch patrol reference: LERs;83-061, 83-068 and 83-076 NRC FORM :drls\il.t\. v 1 - v ~_,.19-831
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General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 June 3, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
LICENSEE EVENT REPORT 87-015 - FAILURE TO ESTABLISH FIRE WATCH ASSOCIATED WITH INOPERABLE SPRINKLERS Licensee Event Report (LER)87-015, (Failure to Establish Fire Watch Associated With Inoperable Sprinklers) is attached. This event is reportable to the NRC per 10CFR50.73(a)(2)(i).
Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment
