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| {{#Wiki_filter:NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3160-0104 (4195) . -EXPIRES 4130/98 ESTIMATED IUIOEN PER RESPONSE TO COMPLY WllH THIS llAHDATORY INFORMATION OOUECTlON REQUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED LICENSEE EVENT REPORT (LER) INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY. | | {{#Wiki_filter:NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3160-0104 (4195) . - EXPIRES 4130/98 ESTIMATED IUIOEN PER RESPONSE TO COMPLY WllH THIS llAHDATORY INFORMATION OOUECTlON REQUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED LICENSEE EVENT REPORT (LER) INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS llAN.\GEMEHT BRANCH (T-8 F33), U.S. NJClEAR REOULATORY COMMISSION, WASHINGTON, DC 21)5511. |
| FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS llAN.\GEMEHT BRANCH (T-8 F33), U.S. NJClEAR REOULATORY COMMISSION, WASHINGTON, DC 21)5511. (See reverse for required number of digits/characters for each block) OOOt, NIO TO THE PAPERV<<>RK REDUC'TION PROJECT (3t!IO-Ot0<, OFFICE OF llAN.\GEMEHT NIO BUDGET, WASHIHGTON, DC 20503 FACILITY NAME (1) DOCKET NUMBER (2) Page (3) PALISADES NUCLEAR PLANT 05000255 1of3 TITLE (4) LICENSEE EVENT REPORT 96-010-TRIP OF HIGH PRESSURE SAFETY INJECTION PUMP WHILE FILLING SAFETY INJECTION TANK EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) MONTH DAY YEAR YEAR I SEQUENTIAL REVISION MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NUMBER 05000 07 17 96 96 010 00 08 16 96 FACILITY NAME DOCKET NUMBER --05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check one or more) (11) MODE (9) N 20.2201(b) 20.2203(a)(2)(v) x 50.73(a)(2)(1) | | OOOt, NIO TO THE PAPERV<<>RK REDUC'TION PROJECT (3t!IO-Ot0<, OFFICE OF (See reverse for required number of digits/characters for each block) llAN.\GEMEHT NIO BUDGET, WASHIHGTON, DC 20503 FACILITY NAME (1) DOCKET NUMBER (2) Page (3) |
| : 50. 73(a)(2)(iii)
| | PALISADES NUCLEAR PLANT 05000255 1of3 TITLE (4) LICENSEE EVENT REPORT 96-010-TRIP OF HIGH PRESSURE SAFETY INJECTION PUMP WHILE FILLING SAFETY INJECTION TANK EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| POWER 20.2203(a)(1) 20.2203(a)(3)(1) 50.73(a)(2)(ii) 50.73(a)(2)(x) | | MONTH DAY YEAR YEAR I SEQUENTIAL NUMBER REVISION NUMBER MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 05000 FACILITY NAME DOCKET NUMBER 07 17 96 96 - 010 - 00 08 16 96 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check one or more) (11) |
| EL (10) 99.6 20.2203(a)(2)(1) 20.2203(a)(3)(ii) | | MODE (9) N 20.2201(b) 20.2203(a)(2)(v) x 50.73(a)(2)(1) 50. 73(a)(2)(iii) |
| : 50. 73(a)(2)(iii) 73.71 1 1:1:: Ifill 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv)
| | POWER 20.2203(a)(1) 20.2203(a)(3)(1) 50.73(a)(2)(ii) 50.73(a)(2)(x) |
| OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v)
| | EL (10) 99.6 20.2203(a)(2)(1) 20.2203(a)(3)(ii) 50. 73(a)(2)(iii) 73.71 |
| Specify in Abstract below or 20.2203(a)(2)(iv) 50.36(c)(2)
| | ~1:::;1;W 11:1:: Ifill 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2) |
| : 50. 73( al (2)(vii) in NRC Fonn 366A LICENSEE CONTACT FOR THIS LE'R (12) NAME TELEPHONE NUMBER (Include Area Code) Clayton M. Mathews (616) 764-2035 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS x ED RLY GOBO Yes SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR I YES x I NO EXPECTED If yes COMPLETE EXPECTED COMPLETION DATE SUBMISSION DATE (15) ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) On July 17, 1996, at 2114 hours, with the reactor at 99.6% power, the Safety Injection Tanks (SIT) were being sampled to verify boron concentration. | | LICENSEE CONTACT FOR THIS LE'R (12) 50.73(a)(2)(iv) 50.73(a)(2)(v) |
| While filling SIT T-82C with High Pressure Safety Injection (HPSI) Pump P-66A, P-66Atripped. | | : 50. 73( al (2)(vii) |
| Since T-82C was inoperable due to low pressure during the sampling evolution, Technical Specification (TS) 3.0.3 was immediately entered. Two minutes later, TS 3.0.3 was exited when nitrogen overpressure was restored. | | OTHER Specify in Abstract below or in NRC Fonn 366A NAME TELEPHONE NUMBER (Include Area Code) |
| The 24-hour Limiting Condition of Operation (LCO) of TS 3.3.2.c was then entered for P-66A. The trip of P-66A was found to be due to its Y-phase time-overcurrent relay actuation. | | Clayton M. Mathews (616) 764-2035 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| Troubleshooting revealed that P-66A tripped due to its relay not properly resetting after each successive start. The start of P-66A for the fill of T-82C was sufficient to reach the overcurrent trip setpoint. | | CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS x ED RLY GOBO Yes SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR I YES If yes COMPLETE EXPECTED COMPLETION DATE x I NO EXPECTED SUBMISSION DATE (15) |
| Following checking and cleaning the P-66A motor, and checking the calibration of and exercising the relay, P-66A was test started three times. Proper relay reset was verified each time. P-66A was then declared operable, but degraded. | | ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) |
| On July 18, 1996, the LCO was exited. The relay was replaced on July 19, 1996, correcting the degraded condition of the breaker. 9608230145 ADOCK PDR NRC FORM 366a 4/95 FACILITY NAME l1l PALISADES NUCLEAR PLANT U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET12l LER NUMBER 6) 05000255 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 96 010 00 PAGE13l 20F3 TEXT (If niore space is required, use additional copies of NRC Form 366A) (17) EVENT DESCRIPTION On July 17, 1996, at 2114 hours, with the reactor at 99.6% power, Safety Injection Tanks (SIT) T -82 A, B, C and D were being sampled to verify boron coricentration, in accordance with Technical Specification Table 4.2.1, Item 5. While filling SIT T-82C with High Pressure Safety Injection (HPSI) Pump P-66A in accordance with System Operating Procedure SOP 3, P-66A tripped approximately two seconds after having been started. Since T-82C was coincidentally inoperable due to low pressure as a result of the sampling evolution, Technical Specification (TS) 3.0.3 was immediately entered. TS 3.0.3 was exited approximately two minutes later when operators restored nitrogen overpressure to T-82C. The Limiting Condition of Operation (LCO) of Technical Specification 3.3.2.c was then entered for P-66A. Observation of the pump breaker 152-207 relays indicated that the trip of P-66A was due to Y-phase time-overcurrent relay actuation (ED;RL Y). Troubleshooting revealed that P-66A tripped due to relay 150/151 Y-207 not properly resetting after each successive start of P-66A for SIT fill; i.e., the induction disc portion of the relay was not returning to its initial position. | | On July 17, 1996, at 2114 hours, with the reactor at 99.6% power, the Safety Injection Tanks (SIT) were being sampled to verify boron concentration. While filling SIT T-82C with High Pressure Safety Injection (HPSI) Pump P-66A, P-66Atripped. Since T-82C was inoperable due to low pressure during the sampling evolution, Technical Specification (TS) 3.0.3 was immediately entered. Two minutes later, TS 3.0.3 was exited when nitrogen overpressure was restored. The 24-hour Limiting Condition of Operation (LCO) of TS 3.3.2.c was then entered for P-66A. The trip of P-66A was found to be due to its Y-phase time-overcurrent relay actuation. |
| The third start of P-66A, for the fill of T-82C, was apparently sufficient for the induction disc to travel to its overcurrent trip setpoint.
| | Troubleshooting revealed that P-66A tripped due to its relay not properly resetting after each successive start. The start of P-66A for the fill of T-82C was sufficient to reach the overcurrent trip setpoint. Following checking and cleaning the P-66A motor, and checking the calibration of and exercising the relay, P-66A was test started three times. Proper relay reset was verified each time. |
| Thus, Y-phase time-overcurrent, in conjunction with the Y-phase high drop-out relay (which was picked up as a result of the P-66A start), then tripped breaker 152-207. A replacement GE overcurrent relay was not immediately available.
| | P-66A was then declared operable, but degraded. On July 18, 1996, the LCO was exited. The relay was replaced on July 19, 1996, correcting the degraded condition of the breaker. |
| Following checking and cleaning the P-66A motor, and checking the calibration of and exercising relay 150/151Y-207, P-66A was successfully test started three times. Proper relay reset was verified each time. P-66A was then declared operable, but degraded due to the suspect condition of relay 150/151 Y-207). On July 18, 1996, at 1102 hours, the LCO of TS 3.3.2.c was exited. Relay 150/151 Y-207 was replaced on July 19, 1996, correcting the degraded condition of breaker 152-207. ROOT CAUSE The apparent cause of the event was a faulty 150/151Y-207 time-overcurrent relay. Some type of minor mechanical interference (dust, grease, etc.) preventerl its induction reset mechanism from returning to its initial position, resulting, ultimately, in the re1ay reaching its overcurrent trip point during the series of P-66A starts to refill the SITs. No definitive evidence of this was found during troubleshooting, with the exception that the faulty relay immediately reset when the breaker cubicle door was opened for troubleshooting.
| | 9608230145 6ggg5~55 |
| The one-time failure of relay 150/151 Y-207 is considered random.
| | ~DR ADOCK PDR |
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| |
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| NRC FORM 366a U.S. NUCLEAR REGULATORY COMMISSION 4195 -FACILITY NAME 11\ PALISADES NUCLEAR PLANT LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET121 05000255 LER NUMBER 6\ YEAR I SEQUENTIAL NUMBER 96 010 -TEXT (If more space is required, use additional copies of NRC Form 366A) (17) SAFETY IMPLICATIONS REVISION NUMBER 00 PAGE 131 30F3 When P-66A tripped, it rendered one HPSI train inoperable and interrupted the refill of T-82C. Aithough T-82C was inoperable due to its pressure being outside of Technical Specifications limits during sampling, it is likely that its safety function could still have been performed. | | NRC FORM 366a U.S. NUCLEAR REGULATORY COMMISSION 4/95 LICENSEE EVENT REPORT (LER) |
| Even if it could not have performed its safety function, however, the Loss of Coolant Accident (LOCA) analysis assumes that only 3 of 4 SITs are available to inject their contents into the Primary Coolant System(PCS). | | TEXT CONTINUATION FACILITY NAME l1l DOCKET12l 05000255 YEAR ILER NUMBER 6) |
| Since T-82 A, 8, and D were operable, the loss of T-82C would not have had any significant effect. Since P-66A is the only pump allowed for filling SITs with PCS pressure greater than 1500 psia per SOP 3, no procedural method to restore the T-82C level was available. | | SEQUENTIAL NUMBER I REVISION NUMBER PAGE13l 20F3 PALISADES NUCLEAR PLANT 96 010 00 TEXT (If niore space is required, use additional copies of NRC Form 366A) (17) |
| In this case, although T-82C level was low, it was still within the required Technical Specifications limits. Operability of T-82C was quickly restored by raising nitrogen pressure. | | EVENT DESCRIPTION On July 17, 1996, at 2114 hours, with the reactor at 99.6% power, Safety Injection Tanks (SIT) |
| If level had been outside the Technical Specification limits, however, the unavailability of P-66A would have delayed restoration significantly. | | T -82 A, B, C and D were being sampled to verify boron coricentration, in accordance with Technical Specification Table 4.2.1, Item 5. While filling SIT T-82C with High Pressure Safety Injection (HPSI) Pump P-66A in accordance with System Operating Procedure SOP 3, P-66A tripped approximately two seconds after having been started. Since T-82C was coincidentally inoperable due to low pressure as a result of the sampling evolution, Technical Specification (TS) 3.0.3 was immediately entered. TS 3.0.3 was exited approximately two minutes later when operators restored nitrogen overpressure to T-82C. The Limiting Condition of Operation (LCO) of Technical Specification 3.3.2.c was then entered for P-66A. Observation of the pump breaker 152-207 relays indicated that the trip of P-66A was due to Y-phase time-overcurrent relay actuation (ED;RLY). |
| The use of P-668 to fill SITs via the Train 1 HPSI header under the same PCS conditions as permitted for P-66A appears to be a technically adequate alternative which should be incorporated into SOP 3. CORRECTIVE ACTION CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED All similar relays in a time-overcurrent application were inspected for potentially degraded conditions. | | Troubleshooting revealed that P-66A tripped due to relay 150/151 Y-207 not properly resetting after each successive start of P-66A for SIT fill; i.e., the induction disc portion of the relay was not returning to its initial position. The third start of P-66A, for the fill of T-82C, was apparently sufficient for the induction disc to travel to its overcurrent trip setpoint. Thus, Y-phase time-overcurrent, in conjunction with the Y-phase high drop-out relay (which was picked up as a result of the P-66A start), then tripped breaker 152-207. A replacement GE overcurrent relay was not immediately available. Following checking and cleaning the P-66A motor, and checking the calibration of and exercising relay 150/151Y-207, P-66A was successfully test started three times. |
| No other potential-problem relays were found. CORRECTIVE ACTION TO PREVENT RECURRENCE | | Proper relay reset was verified each time. P-66A was then declared operable, but degraded due to the suspect condition of relay 150/151 Y-207). On July 18, 1996, at 1102 hours, the LCO of TS 3.3.2.c was exited. Relay 150/151 Y-207 was replaced on July 19, 1996, correcting the degraded condition of breaker 152-207. |
| .1. Review the stock balance of spare motor protection relays for all safety-related motors. Procure necessary spare relays as considered appropriate by System Engineering. | | ROOT CAUSE The apparent cause of the event was a faulty 150/151Y-207 time-overcurrent relay. Some type of minor mechanical interference (dust, grease, etc.) preventerl its induction reset mechanism from returning to its initial position, resulting, ultimately, in the re1ay reaching its overcurrent trip point during the series of P-66A starts to refill the SITs. No definitive evidence of this was found during troubleshooting, with the exception that the faulty relay immediately reset when the breaker cubicle door was opened for troubleshooting. The one-time failure of relay 150/151 Y-207 is considered random. |
| : 2. Revise Standard Operating Procedure (SOP) 3 to permit the use of High Pressure Safety Injection (HPSI) Pump P-668 to fill Safety Injection Tanks at full Primary Coolant System pressure, if justified by engineering analysis.}} | | |
| | -================~! |
| | NRC FORM 366a U.S. NUCLEAR REGULATORY COMMISSION 4195 - |
| | LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION I |
| | FACILITY NAME 11\ DOCKET121 LER NUMBER 6\ PAGE 131 YEAR SEQUENTIAL REVISION NUMBER NUMBER PALISADES NUCLEAR PLANT 05000255 30F3 96 010 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| | SAFETY IMPLICATIONS When P-66A tripped, it rendered one HPSI train inoperable and interrupted the refill of T-82C. |
| | Aithough T-82C was inoperable due to its pressure being outside of Technical Specifications limits during sampling, it is likely that its safety function could still have been performed. Even if it could not have performed its safety function, however, the Loss of Coolant Accident (LOCA) analysis assumes that only 3 of 4 SITs are available to inject their contents into the Primary Coolant System(PCS). Since T-82 A, 8, and D were operable, the loss of T-82C would not have had any significant effect. |
| | Since P-66A is the only pump allowed for filling SITs with PCS pressure greater than 1500 psia per SOP 3, no procedural method to restore the T-82C level was available. In this case, although T-82C level was low, it was still within the required Technical Specifications limits. Operability of T-82C was quickly restored by raising nitrogen pressure. If level had been outside the Technical Specification limits, however, the unavailability of P-66A would have delayed restoration significantly. |
| | The use of P-668 to fill SITs via the Train 1 HPSI header under the same PCS conditions as permitted for P-66A appears to be a technically adequate alternative which should be incorporated into SOP 3. |
| | CORRECTIVE ACTION CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED All similar relays in a time-overcurrent application were inspected for potentially degraded conditions. No other potential-problem relays were found. |
| | CORRECTIVE ACTION TO PREVENT RECURRENCE |
| | .1. Review the stock balance of spare motor protection relays for all safety-related motors. |
| | Procure necessary spare relays as considered appropriate by System Engineering. |
| | : 2. Revise Standard Operating Procedure (SOP) 3 to permit the use of High Pressure Safety Injection (HPSI) Pump P-668 to fill Safety Injection Tanks at full Primary Coolant System pressure, if justified by engineering analysis.}} |
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| ML18065A874 |
| Person / Time |
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| Site: |
Palisades  |
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| Issue date: |
08/16/1996 |
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| From: |
Mathews C
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
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| To: |
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| Shared Package |
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| ML18065A873 |
List: |
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| References |
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| LER-96-010, LER-96-10, NUDOCS 9608230145 |
| Download: ML18065A874 (3) |
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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
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3160-0104 (4195) . - EXPIRES 4130/98 ESTIMATED IUIOEN PER RESPONSE TO COMPLY WllH THIS llAHDATORY INFORMATION OOUECTlON REQUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED LICENSEE EVENT REPORT (LER) INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS llAN.\GEMEHT BRANCH (T-8 F33), U.S. NJClEAR REOULATORY COMMISSION, WASHINGTON, DC 21)5511.
OOOt, NIO TO THE PAPERV<<>RK REDUC'TION PROJECT (3t!IO-Ot0<, OFFICE OF (See reverse for required number of digits/characters for each block) llAN.\GEMEHT NIO BUDGET, WASHIHGTON, DC 20503 FACILITY NAME (1) DOCKET NUMBER (2) Page (3)
PALISADES NUCLEAR PLANT 05000255 1of3 TITLE (4) LICENSEE EVENT REPORT 96-010-TRIP OF HIGH PRESSURE SAFETY INJECTION PUMP WHILE FILLING SAFETY INJECTION TANK EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR I SEQUENTIAL NUMBER REVISION NUMBER MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 05000 FACILITY NAME DOCKET NUMBER 07 17 96 96 - 010 - 00 08 16 96 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check one or more) (11)
MODE (9) N 20.2201(b) 20.2203(a)(2)(v) x 50.73(a)(2)(1) 50. 73(a)(2)(iii)
POWER 20.2203(a)(1) 20.2203(a)(3)(1) 50.73(a)(2)(ii) 50.73(a)(2)(x)
EL (10) 99.6 20.2203(a)(2)(1) 20.2203(a)(3)(ii) 50. 73(a)(2)(iii) 73.71
~1:::;1;W 11:1:: Ifill 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)
LICENSEE CONTACT FOR THIS LE'R (12) 50.73(a)(2)(iv) 50.73(a)(2)(v)
- 50. 73( al (2)(vii)
OTHER Specify in Abstract below or in NRC Fonn 366A NAME TELEPHONE NUMBER (Include Area Code)
Clayton M. Mathews (616) 764-2035 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS x ED RLY GOBO Yes SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR I YES If yes COMPLETE EXPECTED COMPLETION DATE x I NO EXPECTED SUBMISSION DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On July 17, 1996, at 2114 hours0.0245 days <br />0.587 hours <br />0.0035 weeks <br />8.04377e-4 months <br />, with the reactor at 99.6% power, the Safety Injection Tanks (SIT) were being sampled to verify boron concentration. While filling SIT T-82C with High Pressure Safety Injection (HPSI) Pump P-66A, P-66Atripped. Since T-82C was inoperable due to low pressure during the sampling evolution, Technical Specification (TS) 3.0.3 was immediately entered. Two minutes later, TS 3.0.3 was exited when nitrogen overpressure was restored. The 24-hour Limiting Condition of Operation (LCO) of TS 3.3.2.c was then entered for P-66A. The trip of P-66A was found to be due to its Y-phase time-overcurrent relay actuation.
Troubleshooting revealed that P-66A tripped due to its relay not properly resetting after each successive start. The start of P-66A for the fill of T-82C was sufficient to reach the overcurrent trip setpoint. Following checking and cleaning the P-66A motor, and checking the calibration of and exercising the relay, P-66A was test started three times. Proper relay reset was verified each time.
P-66A was then declared operable, but degraded. On July 18, 1996, the LCO was exited. The relay was replaced on July 19, 1996, correcting the degraded condition of the breaker.
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NRC FORM 366a U.S. NUCLEAR REGULATORY COMMISSION 4/95 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME l1l DOCKET12l 05000255 YEAR ILER NUMBER 6)
SEQUENTIAL NUMBER I REVISION NUMBER PAGE13l 20F3 PALISADES NUCLEAR PLANT 96 010 00 TEXT (If niore space is required, use additional copies of NRC Form 366A) (17)
EVENT DESCRIPTION On July 17, 1996, at 2114 hours0.0245 days <br />0.587 hours <br />0.0035 weeks <br />8.04377e-4 months <br />, with the reactor at 99.6% power, Safety Injection Tanks (SIT)
T -82 A, B, C and D were being sampled to verify boron coricentration, in accordance with Technical Specification Table 4.2.1, Item 5. While filling SIT T-82C with High Pressure Safety Injection (HPSI) Pump P-66A in accordance with System Operating Procedure SOP 3, P-66A tripped approximately two seconds after having been started. Since T-82C was coincidentally inoperable due to low pressure as a result of the sampling evolution, Technical Specification (TS) 3.0.3 was immediately entered. TS 3.0.3 was exited approximately two minutes later when operators restored nitrogen overpressure to T-82C. The Limiting Condition of Operation (LCO) of Technical Specification 3.3.2.c was then entered for P-66A. Observation of the pump breaker 152-207 relays indicated that the trip of P-66A was due to Y-phase time-overcurrent relay actuation (ED;RLY).
Troubleshooting revealed that P-66A tripped due to relay 150/151 Y-207 not properly resetting after each successive start of P-66A for SIT fill; i.e., the induction disc portion of the relay was not returning to its initial position. The third start of P-66A, for the fill of T-82C, was apparently sufficient for the induction disc to travel to its overcurrent trip setpoint. Thus, Y-phase time-overcurrent, in conjunction with the Y-phase high drop-out relay (which was picked up as a result of the P-66A start), then tripped breaker 152-207. A replacement GE overcurrent relay was not immediately available. Following checking and cleaning the P-66A motor, and checking the calibration of and exercising relay 150/151Y-207, P-66A was successfully test started three times.
Proper relay reset was verified each time. P-66A was then declared operable, but degraded due to the suspect condition of relay 150/151 Y-207). On July 18, 1996, at 1102 hours0.0128 days <br />0.306 hours <br />0.00182 weeks <br />4.19311e-4 months <br />, the LCO of TS 3.3.2.c was exited. Relay 150/151 Y-207 was replaced on July 19, 1996, correcting the degraded condition of breaker 152-207.
ROOT CAUSE The apparent cause of the event was a faulty 150/151Y-207 time-overcurrent relay. Some type of minor mechanical interference (dust, grease, etc.) preventerl its induction reset mechanism from returning to its initial position, resulting, ultimately, in the re1ay reaching its overcurrent trip point during the series of P-66A starts to refill the SITs. No definitive evidence of this was found during troubleshooting, with the exception that the faulty relay immediately reset when the breaker cubicle door was opened for troubleshooting. The one-time failure of relay 150/151 Y-207 is considered random.
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NRC FORM 366a U.S. NUCLEAR REGULATORY COMMISSION 4195 -
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION I
FACILITY NAME 11\ DOCKET121 LER NUMBER 6\ PAGE 131 YEAR SEQUENTIAL REVISION NUMBER NUMBER PALISADES NUCLEAR PLANT 05000255 30F3 96 010 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
SAFETY IMPLICATIONS When P-66A tripped, it rendered one HPSI train inoperable and interrupted the refill of T-82C.
Aithough T-82C was inoperable due to its pressure being outside of Technical Specifications limits during sampling, it is likely that its safety function could still have been performed. Even if it could not have performed its safety function, however, the Loss of Coolant Accident (LOCA) analysis assumes that only 3 of 4 SITs are available to inject their contents into the Primary Coolant System(PCS). Since T-82 A, 8, and D were operable, the loss of T-82C would not have had any significant effect.
Since P-66A is the only pump allowed for filling SITs with PCS pressure greater than 1500 psia per SOP 3, no procedural method to restore the T-82C level was available. In this case, although T-82C level was low, it was still within the required Technical Specifications limits. Operability of T-82C was quickly restored by raising nitrogen pressure. If level had been outside the Technical Specification limits, however, the unavailability of P-66A would have delayed restoration significantly.
The use of P-668 to fill SITs via the Train 1 HPSI header under the same PCS conditions as permitted for P-66A appears to be a technically adequate alternative which should be incorporated into SOP 3.
CORRECTIVE ACTION CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED All similar relays in a time-overcurrent application were inspected for potentially degraded conditions. No other potential-problem relays were found.
CORRECTIVE ACTION TO PREVENT RECURRENCE
.1. Review the stock balance of spare motor protection relays for all safety-related motors.
Procure necessary spare relays as considered appropriate by System Engineering.
- 2. Revise Standard Operating Procedure (SOP) 3 to permit the use of High Pressure Safety Injection (HPSI) Pump P-668 to fill Safety Injection Tanks at full Primary Coolant System pressure, if justified by engineering analysis.