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| | issue date = 01/15/1996 | | | issue date = 01/15/1996 |
| | title = 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 | | | title = 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 |
| | author name = MATHEWS C M, SMEDLEY R W | | | author name = Mathews C, Smedley R |
| | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), | | | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:POWERINli | | {{#Wiki_filter:* |
| *. MICHlliAN-S PROliRESS Palisades Nuclear Plant: 27780 Blue Star* Memorial Highway, Covert, Ml 49043 January 15, 1996 U S Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT | | POWERINli *. |
| * LICENSEE EVENT REPORT 95-014 -PRIMARY COOLANT PUMP OIL COLLECTION DEFICIENCIES CREATED BY PIPING MODIFICATION.
| | MICHlliAN-S PROliRESS Palisades Nuclear Plant: 27780 Blue Star* Memorial Highway, Covert, Ml 49043 January 15, 1996 U S Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT LICENSEE EVENT REPORT 95-014 - PRIMARY COOLANT PUMP OIL COLLECTION DEFICIENCIES CREATED BY PIPING MODIFICATION. |
| Licensee Event Report (LER) 95-014 is attached. | | Licensee Event Report (LER) 95-014 is attached. This event is reportable to the NRC in accordance with 10CFR50.73(a)(2)(ii)(B). |
| This event is reportable to the NRC in accordance with 10CFR50.73(a)(2)(ii)(B). | |
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| ==SUMMARY== | | ==SUMMARY== |
| OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments. | | OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments. |
| Richard W Smedley Manager, Licensing CC Administrator, Region Ill, USNRC Project Manager, NRR, USNRC NRC Resident Inspector | | Richard W Smedley Manager, Licensing CC Administrator, Region Ill, USNRC Project Manager, NRR, USNRC NRC Resident Inspector - Palisades Attachment 9601220287 960115 PDR ADOCK 05000255 s PDR 22Ct{~ - |
| -Palisades Attachment 9601220287 PDR ADOCK s | | A CMS' ENERGY COMPANY |
| -960115 05000255 PDR A CMS' ENERGY COMPANY
| | |
| *
| | ATTACHMENT CONSUMERS POWER COMPANY PALISADES PLANT DOCKET 50-255 LICENSEE EVENT REPORT 95-014 PRIMARY COOLANT PUMP OIL COLLECTION DEFICIENCIES CREATED BY PIPING MODIFICATION. |
| * ATTACHMENT CONSUMERS POWER COMPANY PALISADES PLANT DOCKET 50-255 LICENSEE EVENT REPORT 95-014 PRIMARY COOLANT PUMP OIL COLLECTION DEFICIENCIES CREA TED BY PIPING MODIFICATION.
| | 4 Pages |
| 4 Pages NRC Form 366 {9-831 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8131/85 LICENSEE EVENT REPORT (LERI FACILITY NAME {1) DOCKET NUMBER {21 PAGE (3) Palisades Plant 0 5 0 0 0 2 5 5 OF 0 4 TITLEt41 LICENSEE EVENT REPORT 95-014-PRIMARY COOLANT PUMP OIL COLLECTION DEFICIENCIES CREATED BY FC-860 PIPING MODIFICATION EVENT DATE {51 REPORT DATE (61 OTHER FACILITIES INVOLVED {81 REVISION FACILITY NAMES MONTH DAY YEAR YEAR NUMBER MONTH DAY YEAR N/A .0 5 0 0 0 0 199595-014-0001 5 9 6 N/A 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR t: /Check one or more of the following! | | |
| {111 OPERATING MODE {91 N 20.402{b) | | NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION |
| : 50. 73(a){2){ivl 50.73(a){2){v) 73.71{b) 73.71{C) 20.405{&){1
| | {9-831 APPROVED OMB NO. 3150-0104 EXPIRES: 8131/85 LICENSEE EVENT REPORT (LERI FACILITY NAME {1) DOCKET NUMBER {21 PAGE (3) |
| ){i) 20.405{a){1 | | Palisades Plant 0 5 0 0 0 2 5 5 OF 0 4 TITLEt41 LICENSEE EVENT REPORT 95-014- PRIMARY COOLANT PUMP OIL COLLECTION DEFICIENCIES CREATED BY FC-860 PIPING MODIFICATION EVENT DATE {51 REPORT DATE (61 OTHER FACILITIES INVOLVED {81 REVISION FACILITY NAMES MONTH DAY YEAR YEAR NUMBER MONTH DAY YEAR N/A .0 5 0 0 0 0 199595-014-0001 5 9 6 N/A 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR t: /Check one or more of the following! {111 OPERATING MODE {91 N 20.402{b) 20.405{cl 50. 73(a){2){ivl 73.71{b) 20.405{&){1 ){i) 50.36{c){1) 50.73(a){2){v) 73.71{C) 20.405{a){1 ){iii 50.36{c){21 50. 73{a){2){viil OTHER {Specify in Abstract 20.405{&){1 ){iii) 50. 73ta){2Hil 50. 73{a){2){viii){AI below and in Text, 20.405{a){1 ){iv) x 50. 73taH2Hiil 50. 73{a){2){viii){BI NRC Form 366A) 20.405{a){1 IM 50. 73{a){2Hiiil 50.73{a){2){x) |
| ){iii 20.405{cl 50.36{c){1) 50.36{c){21 | | LICENSEE CONTACT FOR THIS LER {121 NAME TELEPHONE NUMBER AREA CODE Clayton M Mathews, Licensing Engineer 6 6 7 6 4 8 9 3 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT {131 MANUFAC- REPORTABLE MANUFAC-CAUSE SYSTEM COMPONENT TURER TO NPRDS CAUSE SYSTEM COMPONENT TURER SUPPLEMENTAL REPORT EXPECTED {14) MONTH DAY YEAR EXPECTED SUBMISSION YES Vt yes. complete EXPECTED SUBMISSION DATE) DATE {151 ABSTRACT {Limit to 1400 spaces, I.e., epproxlmately fifteen slngle-spece typewritten Unesl {161 On January 19, 1995 at 11 :30 am, with the plant operating at full power, it was discovered that the Primary Coolant Pump Oil Collection System was in a degraded condition. A plant modification during the 1990 Refueling Outage changed the Primary Coolant Pump oil piping in the vicinity of the sight glass drain so that piping extended beyond the coverage areas of the existing collection system which had been installed earlier to meet the requirements of 10CFR50, Appendix R. In addition, previously installed spray shields around certain flanged connections and upper oil drain pans were found missing. |
| : 50. 73ta){2Hil
| | Compensatory measures of monitoring oil and air temperature were implemented until the necessary oil collection system modifications were completed during the _1995 Ref~eli_l"!g_ Outage. |
| : 50. 73{a){2){viil
| | The oil collection system is presently in compliance with the design requirements. - -- - |
| : 50. 73{a){2){viii){AI
| | The reportability of the condition was evaluated at the time of discovery. At that time, it was concluded that a report was not necessary because the prevention of oil fires by the oil collection system was not required to preserve safe shutdown capability. Since that time, the NRC staff has provided us with additional verbal guidance on Appendix R reportability. Therefore, we now consider the condition to be reportable. |
| : 50. 73{a){2){viii){BI 50.73{a){2){x)
| | |
| OTHER {Specify in Abstract NAME 20.405{&){1
| | NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (9*83) APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/85 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (3) PAGE (4) |
| ){iii) 20.405{a){1 | | SEQUENTIAL REVISION YEAR NUMBER NUMBER Palisades Plant 0 5 0 0 0 2 5 5 9 5 0 1 4 Q 0 Q 2 OF Q 4 EVENT DESCRIPTION On January 19, 1995 at 11 :30 am, with the plant operating at full power, a fire protection engineer discovered that the Primary Coolant Pump Oil Collection System was in a degraded condition. He was performing a scheduled review of the adequacy of Primary Coolant Pump oil collection system while reviewing a proposed plant modification to add a new type of oil level monitoring. |
| ){iv) 20.405{a){1 IM Clayton M Mathews, Licensing Engineer x 50. 73taH2Hiil | | Further investigation found that a plant modification installed during the 1 990 Refueling Outage had changed some Primary Coolant Pump oil piping. Piping in the vicinity of the sight glass drain extended beyond the coverage areas of the existing collection system. In addition, for unknown reasons, previously installed oil spray shields around certain flanged connections and upper oil drain pans were found to be missing. |
| : 50. 73{a){2Hiiil LICENSEE CONTACT FOR THIS LER {121 AREA CODE 6 6 below and in Text, NRC Form 366A) TELEPHONE NUMBER 7 6 4 8 9 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT {131 CAUSE SYSTEM COMPONENT TURER REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED {14) YES Vt yes. complete EXPECTED SUBMISSION DATE) ABSTRACT {Limit to 1400 spaces, I.e., epproxlmately fifteen slngle-spece typewritten Unesl {161 CAUSE SYSTEM COMPONENT TURER MONTH DAY EXPECTED SUBMISSION DATE {151 3 YEAR On January 19, 1995 at 11 :30 am, with the plant operating at full power, it was discovered that the Primary Coolant Pump Oil Collection System was in a degraded condition.
| | Since the Primary Coolant Pumps are required by 10CFR50, Appendix R, to have a lube oil collection system that will collect all potential oil leakage from pressurized and unpressurized pipe joints and keep it from contacting hot primary coolant system piping or other ignition sources, the system was judged to no longer meet design requirements. |
| A plant modification during the 1990 Refueling Outage changed the Primary Coolant Pump oil piping in the vicinity of the sight glass drain so that piping extended beyond the coverage areas of the existing collection system which had been installed earlier to meet the requirements of 1 OCFR50, Appendix R. In addition, previously installed spray shields around certain flanged connections and upper oil drain pans were found missing. Compensatory measures of monitoring oil and air temperature were implemented until the necessary oil collection system modifications were completed during the _1995 Outage. The oil collection system is presently in compliance with the design requirements. | | Compensatory measures were then initiated until permanent design changes could be made. |
| ----The reportability of the condition was evaluated at the time of discovery. | | They were: |
| At that time, it was concluded that a report was not necessary because the prevention of oil fires by the oil collection system was not required to preserve safe shutdown capability. | | : 1. Increased monitoring of the Primary Coolant Pump upper and lower level lube oil reservoir levels for unexplained significant reductions in oil levels. This monitoring was done once a shift with increased awareness of the operations staff for the potential impact due to improper Primary Coolant Pump oil collection system coverage. |
| Since that time, the NRC staff has provided us with additional verbal guidance on Appendix R reportability. | | : 2. Continued monitoring of the containment air temperature with increased awareness of the operations staff that unexplained increases in temperature could be caused by a Primary Coolant Pump lube oil fire. |
| Therefore, we now consider the condition to be reportable. | | Oil collection system modifications which corrected the deficiencies were completed during the 1995 refueling outage. The oil collection system is presently in compliance with the design requirements. ** ** *--- ---- -**--. -- . *- __ _ |
| NRC Form 366A (9*83) FACILITY NAME (1) Palisades Plant EVENT DESCRIPTION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER (2) LER NUMBER (3) SEQUENTIAL YEAR NUMBER 0 5 0 0 0 2 5 5 9 5 0 1 4 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/85 REVISION NUMBER PAGE (4) Q 0 Q 2 OF Q 4 On January 19, 1995 at 11 :30 am, with the plant operating at full power, a fire protection engineer discovered that the Primary Coolant Pump Oil Collection System was in a degraded condition. | | The reportability of the condition was evaluated at the time of discovery. At that time, it was concluded that a report was not necessary because the prevention of oil fires by the oil collection system was not required to preserve safe shutdown capability. Since that time, the NRC staff has provided us with additional verbal guidance on Appendix R reportability. Therefore, we now consider the condition to be reportable. |
| He was performing a scheduled review of the adequacy of Primary Coolant Pump oil collection system while reviewing a proposed plant modification to add a new type of oil level monitoring. | | |
| Further investigation found that a plant modification installed during the 1 990 Refueling Outage had changed some Primary Coolant Pump oil piping. Piping in the vicinity of the sight glass drain extended beyond the coverage areas of the existing collection system. In addition, for unknown reasons, previously installed oil spray shields around certain flanged connections and upper oil drain pans were found to be missing. Since the Primary Coolant Pumps are required by 1 OCFR50, Appendix R, to have a lube oil collection system that will collect all potential oil leakage from pressurized and unpressurized pipe joints and keep it from contacting hot primary coolant system piping or other ignition sources, the system was judged to no longer meet design requirements. | | NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (9-83) APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/85 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (3) PAGE (4) |
| Compensatory measures were then initiated until permanent design changes could be made. They were: 1 . Increased monitoring of the Primary Coolant Pump upper and lower level lube oil reservoir levels for unexplained significant reductions in oil levels. This monitoring was done once a shift with increased awareness of the operations staff for the potential impact due to improper Primary Coolant Pump oil collection system coverage. | | SEQUENTIAL REVISION YEAR NUMBER NUMBER Palisades Plant 0 5 0 0 0 2 5 5 9 5 0 1 4 0 0 0 3 OF 0 4 CAUSE OF THE EVENT The degraded condition of the Primary Coolant Pump lube oil collection system was caused by: |
| : 2. Continued monitoring of the containment air temperature with increased awareness of the operations staff that unexplained increases in temperature could be caused by a Primary Coolant Pump lube oil fire. Oil collection system modifications which corrected the deficiencies were completed during the 1995 refueling outage. The oil collection system is presently in compliance with the design requirements. | | : 1. Inadequate design basis documentation for this system. |
| ** ** *--------**--. --. *-__ _ The reportability of the condition was evaluated at the time of discovery. | | : 2. Lack of review by experienced Fire Protection personnel for design modifications that were judged by the design engineer as having no impact on Fire Protection Program requirements. |
| At that time, it was concluded that a report was not necessary because the prevention of oil fires by the oil collection system was not required to preserve safe shutdown capability. | | ANALYSIS OF THE EVENT This Primary Coolant Pump lubricating oil system piping was modified in the 1 990 Refueling Outage. This modification (FC-860) replaced the threaded pipe and fittings on the Primary Coolant Pump oil gauge fill, drain, and instrument systems with socket welded components; added or replaced existing gate valves with ball valves and replaced the sight glasses. These changes were made to reduce the potential oil leak locations. Additional isolation valves were also added that extended the piping beyond the original design envelope. |
| Since that time, the NRC staff has provided us with additional verbal guidance on Appendix R reportability. | |
| Therefore, we now consider the condition to be reportable. | |
| NRC Form 366A (9-83) FACILITY NAME (1) Palisades Plant CAUSE OF THE EVENT LICENSEE EVENT REPORT (LERI TEXT CONTINUATION DOCKET NUMBER (2) YEAR 0 5 0 0 0 2 5 5 9 5 LER NUMBER (3) SEQUENTIAL NUMBER 0 1 4 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/85 REVISION NUMBER PAGE (4) 0 0 0 3 OF 0 4 The degraded condition of the Primary Coolant Pump lube oil collection system was caused by: 1. Inadequate design basis documentation for this system. 2. Lack of review by experienced Fire Protection personnel for design modifications that were judged by the design engineer as having no impact on Fire Protection Program requirements. | |
| ANALYSIS OF THE EVENT This Primary Coolant Pump lubricating oil system piping was modified in the 1 990 Refueling Outage. This modification (FC-860) replaced the threaded pipe and fittings on the Primary Coolant Pump oil gauge fill, drain, and instrument systems with socket welded components; added or replaced existing gate valves with ball valves and replaced the sight glasses. These changes were made to reduce the potential oil leak locations. | |
| Additional isolation valves were also added that extended the piping beyond the original design envelope. | |
| When this condition was discovered, compensatory additional monitoring was initiated. | | When this condition was discovered, compensatory additional monitoring was initiated. |
| Necessary oil collection system modifications were completed during the 1 995 Refueling Outage to reconfigure the oil drip trays. The oil collection system is presently in compliance with 1 OCFR50 Appendix R and design requirements. | | Necessary oil collection system modifications were completed during the 1 995 Refueling Outage to reconfigure the oil drip trays. The oil collection system is presently in compliance with 10CFR50 Appendix R and design requirements. |
| SAFETY SIGNIFICANCE Analyses of oil fires in the vicinity of primary coolant pumps,, irrespective of the oil collection systems, have been performed to assure the capability to meet shutdown criteria. | | SAFETY SIGNIFICANCE Analyses of oil fires in the vicinity of primary coolant pumps,, irrespective of the oil collection systems, have been performed to assure the capability to meet shutdown criteria. The only reason that oil collection systems are installed at Palisades is because they are explicitly required by 10CFR50, Appendix R. Other installed equipment provided adequate early warning to minimize the probability of a fire due to leaking oil. |
| The only reason that oil collection systems are installed at Palisades is because they are explicitly required by 1 OCFR50, Appendix R. Other installed equipment provided adequate early warning to minimize the probability of a fire due to leaking oil. | | * During the period between discovery and correction,. compens~tory _measures were established to minimize the probability that a Primary Coolant Pump lubricating oil system. leak would go unnoticed. Those measures included monitoring the oil level every shift and planning to take appropriate actions if a significant leak were identified. Oil level changes as small as 2 percent or 0.4 gallon were detectable. |
| * During the period between discovery and correction,. | |
| _measures were established to minimize the probability that a Primary Coolant Pump lubricating oil system. leak would go unnoticed. | |
| Those measures included monitoring the oil level every shift and planning to take appropriate actions if a significant leak were identified. | |
| Oil level changes as small as 2 percent or 0.4 gallon were detectable. | |
| Permanent corrections were made to the oil collection system by modifications that were completed during the 1995 Refueling Outage. The oil collection system is presently in compliance with the design requirements. | | Permanent corrections were made to the oil collection system by modifications that were completed during the 1995 Refueling Outage. The oil collection system is presently in compliance with the design requirements. |
| t . NRC Form 366A (9-83) U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/85 *'-LICENSEE EVENT REPORT CLER) TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER (21 YEAR Palisades Plant 0 5 0 0 0 2 5 5 9 5 CORRECTIVE ACTIONS The following corrective actions have been completed: | | |
| LER NUMBER (3) SEQUENTIAL NUMBER 0 4 REVISION NUMBER PAGE (4) Q Q Q 4 OF Q 4 1. A walkdown of the Primary Coolant Pump oil collection system was performed.
| | t |
| The as-built configuration of the system was defined. 2. The design basis documentation was updated to define the basis for the Primary Coolant Pump lubricating oil collection system. 3. A review to determine possible effects on the Fire Protection Program is now being performed by experienced Fire Protection personnel for all new plant modification packages. | | . NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (9-83) APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/85 |
| : 4. The Primary Coolant Pump lubricating oil collection system was modified during the 1 995 Refueling Outage to meet design requirements.}} | | *'- LICENSEE EVENT REPORT CLER) TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER (21 LER NUMBER (3) PAGE (4) |
| | SEQUENTIAL REVISION YEAR NUMBER NUMBER Palisades Plant 0 5 0 0 0 2 5 5 9 5 0 4 Q Q Q 4 OF Q 4 CORRECTIVE ACTIONS The following corrective actions have been completed: |
| | : 1. A walkdown of the Primary Coolant Pump oil collection system was performed. The as-built configuration of the system was defined. |
| | : 2. The design basis documentation was updated to define the basis for the Primary Coolant Pump lubricating oil collection system. |
| | : 3. A review to determine possible effects on the Fire Protection Program is now being performed by experienced Fire Protection personnel for all new plant modification packages. |
| | : 4. The Primary Coolant Pump lubricating oil collection system was modified during the 1 995 Refueling Outage to meet design requirements.}} |
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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
POWERINli *.
MICHlliAN-S PROliRESS Palisades Nuclear Plant: 27780 Blue Star* Memorial Highway, Covert, Ml 49043 January 15, 1996 U S Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT LICENSEE EVENT REPORT 95-014 - PRIMARY COOLANT PUMP OIL COLLECTION DEFICIENCIES CREATED BY PIPING MODIFICATION.
Licensee Event Report (LER)95-014 is attached. This event is reportable to the NRC in accordance with 10CFR50.73(a)(2)(ii)(B).
SUMMARY
OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.
Richard W Smedley Manager, Licensing CC Administrator, Region Ill, USNRC Project Manager, NRR, USNRC NRC Resident Inspector - Palisades Attachment 9601220287 960115 PDR ADOCK 05000255 s PDR 22Ct{~ -
A CMS' ENERGY COMPANY
ATTACHMENT CONSUMERS POWER COMPANY PALISADES PLANT DOCKET 50-255 LICENSEE EVENT REPORT 95-014 PRIMARY COOLANT PUMP OIL COLLECTION DEFICIENCIES CREATED BY PIPING MODIFICATION.
4 Pages
NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION
{9-831 APPROVED OMB NO. 3150-0104 EXPIRES: 8131/85 LICENSEE EVENT REPORT (LERI FACILITY NAME {1) DOCKET NUMBER {21 PAGE (3)
Palisades Plant 0 5 0 0 0 2 5 5 OF 0 4 TITLEt41 LICENSEE EVENT REPORT 95-014- PRIMARY COOLANT PUMP OIL COLLECTION DEFICIENCIES CREATED BY FC-860 PIPING MODIFICATION EVENT DATE {51 REPORT DATE (61 OTHER FACILITIES INVOLVED {81 REVISION FACILITY NAMES MONTH DAY YEAR YEAR NUMBER MONTH DAY YEAR N/A .0 5 0 0 0 0 199595-014-0001 5 9 6 N/A 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR t: /Check one or more of the following! {111 OPERATING MODE {91 N 20.402{b) 20.405{cl 50. 73(a){2){ivl 73.71{b) 20.405{&){1 ){i) 50.36{c){1) 50.73(a){2){v) 73.71{C) 20.405{a){1 ){iii 50.36{c){21 50. 73{a){2){viil OTHER {Specify in Abstract 20.405{&){1 ){iii) 50. 73ta){2Hil 50. 73{a){2){viii){AI below and in Text, 20.405{a){1 ){iv) x 50. 73taH2Hiil 50. 73{a){2){viii){BI NRC Form 366A) 20.405{a){1 IM 50. 73{a){2Hiiil 50.73{a){2){x)
LICENSEE CONTACT FOR THIS LER {121 NAME TELEPHONE NUMBER AREA CODE Clayton M Mathews, Licensing Engineer 6 6 7 6 4 8 9 3 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT {131 MANUFAC- REPORTABLE MANUFAC-CAUSE SYSTEM COMPONENT TURER TO NPRDS CAUSE SYSTEM COMPONENT TURER SUPPLEMENTAL REPORT EXPECTED {14) MONTH DAY YEAR EXPECTED SUBMISSION YES Vt yes. complete EXPECTED SUBMISSION DATE) DATE {151 ABSTRACT {Limit to 1400 spaces, I.e., epproxlmately fifteen slngle-spece typewritten Unesl {161 On January 19, 1995 at 11 :30 am, with the plant operating at full power, it was discovered that the Primary Coolant Pump Oil Collection System was in a degraded condition. A plant modification during the 1990 Refueling Outage changed the Primary Coolant Pump oil piping in the vicinity of the sight glass drain so that piping extended beyond the coverage areas of the existing collection system which had been installed earlier to meet the requirements of 10CFR50, Appendix R. In addition, previously installed spray shields around certain flanged connections and upper oil drain pans were found missing.
Compensatory measures of monitoring oil and air temperature were implemented until the necessary oil collection system modifications were completed during the _1995 Ref~eli_l"!g_ Outage.
The oil collection system is presently in compliance with the design requirements. - -- -
The reportability of the condition was evaluated at the time of discovery. At that time, it was concluded that a report was not necessary because the prevention of oil fires by the oil collection system was not required to preserve safe shutdown capability. Since that time, the NRC staff has provided us with additional verbal guidance on Appendix R reportability. Therefore, we now consider the condition to be reportable.
NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (9*83) APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/85 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (3) PAGE (4)
SEQUENTIAL REVISION YEAR NUMBER NUMBER Palisades Plant 0 5 0 0 0 2 5 5 9 5 0 1 4 Q 0 Q 2 OF Q 4 EVENT DESCRIPTION On January 19, 1995 at 11 :30 am, with the plant operating at full power, a fire protection engineer discovered that the Primary Coolant Pump Oil Collection System was in a degraded condition. He was performing a scheduled review of the adequacy of Primary Coolant Pump oil collection system while reviewing a proposed plant modification to add a new type of oil level monitoring.
Further investigation found that a plant modification installed during the 1 990 Refueling Outage had changed some Primary Coolant Pump oil piping. Piping in the vicinity of the sight glass drain extended beyond the coverage areas of the existing collection system. In addition, for unknown reasons, previously installed oil spray shields around certain flanged connections and upper oil drain pans were found to be missing.
Since the Primary Coolant Pumps are required by 10CFR50, Appendix R, to have a lube oil collection system that will collect all potential oil leakage from pressurized and unpressurized pipe joints and keep it from contacting hot primary coolant system piping or other ignition sources, the system was judged to no longer meet design requirements.
Compensatory measures were then initiated until permanent design changes could be made.
They were:
- 1. Increased monitoring of the Primary Coolant Pump upper and lower level lube oil reservoir levels for unexplained significant reductions in oil levels. This monitoring was done once a shift with increased awareness of the operations staff for the potential impact due to improper Primary Coolant Pump oil collection system coverage.
- 2. Continued monitoring of the containment air temperature with increased awareness of the operations staff that unexplained increases in temperature could be caused by a Primary Coolant Pump lube oil fire.
Oil collection system modifications which corrected the deficiencies were completed during the 1995 refueling outage. The oil collection system is presently in compliance with the design requirements. ** ** *--- ---- -**--. -- . *- __ _
The reportability of the condition was evaluated at the time of discovery. At that time, it was concluded that a report was not necessary because the prevention of oil fires by the oil collection system was not required to preserve safe shutdown capability. Since that time, the NRC staff has provided us with additional verbal guidance on Appendix R reportability. Therefore, we now consider the condition to be reportable.
NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (9-83) APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/85 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (3) PAGE (4)
SEQUENTIAL REVISION YEAR NUMBER NUMBER Palisades Plant 0 5 0 0 0 2 5 5 9 5 0 1 4 0 0 0 3 OF 0 4 CAUSE OF THE EVENT The degraded condition of the Primary Coolant Pump lube oil collection system was caused by:
- 1. Inadequate design basis documentation for this system.
- 2. Lack of review by experienced Fire Protection personnel for design modifications that were judged by the design engineer as having no impact on Fire Protection Program requirements.
ANALYSIS OF THE EVENT This Primary Coolant Pump lubricating oil system piping was modified in the 1 990 Refueling Outage. This modification (FC-860) replaced the threaded pipe and fittings on the Primary Coolant Pump oil gauge fill, drain, and instrument systems with socket welded components; added or replaced existing gate valves with ball valves and replaced the sight glasses. These changes were made to reduce the potential oil leak locations. Additional isolation valves were also added that extended the piping beyond the original design envelope.
When this condition was discovered, compensatory additional monitoring was initiated.
Necessary oil collection system modifications were completed during the 1 995 Refueling Outage to reconfigure the oil drip trays. The oil collection system is presently in compliance with 10CFR50 Appendix R and design requirements.
SAFETY SIGNIFICANCE Analyses of oil fires in the vicinity of primary coolant pumps,, irrespective of the oil collection systems, have been performed to assure the capability to meet shutdown criteria. The only reason that oil collection systems are installed at Palisades is because they are explicitly required by 10CFR50, Appendix R. Other installed equipment provided adequate early warning to minimize the probability of a fire due to leaking oil.
- During the period between discovery and correction,. compens~tory _measures were established to minimize the probability that a Primary Coolant Pump lubricating oil system. leak would go unnoticed. Those measures included monitoring the oil level every shift and planning to take appropriate actions if a significant leak were identified. Oil level changes as small as 2 percent or 0.4 gallon were detectable.
Permanent corrections were made to the oil collection system by modifications that were completed during the 1995 Refueling Outage. The oil collection system is presently in compliance with the design requirements.
t
. NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (9-83) APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/85
- '- LICENSEE EVENT REPORT CLER) TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER (21 LER NUMBER (3) PAGE (4)
SEQUENTIAL REVISION YEAR NUMBER NUMBER Palisades Plant 0 5 0 0 0 2 5 5 9 5 0 4 Q Q Q 4 OF Q 4 CORRECTIVE ACTIONS The following corrective actions have been completed:
- 1. A walkdown of the Primary Coolant Pump oil collection system was performed. The as-built configuration of the system was defined.
- 2. The design basis documentation was updated to define the basis for the Primary Coolant Pump lubricating oil collection system.
- 3. A review to determine possible effects on the Fire Protection Program is now being performed by experienced Fire Protection personnel for all new plant modification packages.
- 4. The Primary Coolant Pump lubricating oil collection system was modified during the 1 995 Refueling Outage to meet design requirements.
