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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20042F9581990-05-0707 May 1990 LER 90-001-01:on 900124,shift Surveillance Log Did Not Meet Requirements of Tech Specs.Caused by Deficient Procedure. Surveillance Log Revised to Include Daily Instrument Check. W/900507 Ltr ML19332E7591989-11-27027 November 1989 LER 89-008-00:on 891027,primary Containment Isolation Sys Group II & III Isolations Occurred When Spurious Reactor Low Level Signal Sensed by Instruments.Possibly Caused by Air Bubble in Sensing Lines.Line backfilled.W/891127 Ltr ML20003C3331981-02-23023 February 1981 LER 81-014/03L-0:on 810131,Leeds & Northrup Model W multi-point Temp Recorder TR-2-10-131 Found Not Recording Suppression Chamber Water Temp Per Tech Spec.Caused by Bound Drive Motor.Instrument Repaired & Returned to Svc on 810202 ML19331C7811980-06-19019 June 1980 LER 80-012/03L-0:on 800520,during Full Power Operation, Routine Testing Revealed Pressure Switch 5121B Setpoint at 700 Psi Above Tech Spec.Caused by Personnel Error.Setpoint Adjusted.Technician Instructed ML19210D6251979-11-16016 November 1979 LER 79-049/01T-0:on 791101,four Seismic Supports Found W/Safety Factors of Less than Two.Caused by Engineering Design Deficiency.Redesign Performed.Corrective Action Implemented within Seven Days ML19247A0721979-07-20020 July 1979 LER 79-031/03L-0 on 790622:during Electrical Storm,Lost Main Stack Sampling Sys & Automatic Initiation Capability. Caused by Blown Fuses from lightning-induced Electrical Transient.Fuses Replaced ML19282C1531979-03-14014 March 1979 LER 79-007/03L-0 on 790212:during Surveillance,Setpoint of a Logic Automatic Depressurization Sys Time Delay Relay Was Greater than Tech Spec Limit.Caused by Setpoint Drift on GE Model CR-2820 Time Delay.Relay Readjusted & Tested 1990-05-07
[Table view] Category:RO)
MONTHYEARML20042F9581990-05-0707 May 1990 LER 90-001-01:on 900124,shift Surveillance Log Did Not Meet Requirements of Tech Specs.Caused by Deficient Procedure. Surveillance Log Revised to Include Daily Instrument Check. W/900507 Ltr ML19332E7591989-11-27027 November 1989 LER 89-008-00:on 891027,primary Containment Isolation Sys Group II & III Isolations Occurred When Spurious Reactor Low Level Signal Sensed by Instruments.Possibly Caused by Air Bubble in Sensing Lines.Line backfilled.W/891127 Ltr ML20003C3331981-02-23023 February 1981 LER 81-014/03L-0:on 810131,Leeds & Northrup Model W multi-point Temp Recorder TR-2-10-131 Found Not Recording Suppression Chamber Water Temp Per Tech Spec.Caused by Bound Drive Motor.Instrument Repaired & Returned to Svc on 810202 ML19331C7811980-06-19019 June 1980 LER 80-012/03L-0:on 800520,during Full Power Operation, Routine Testing Revealed Pressure Switch 5121B Setpoint at 700 Psi Above Tech Spec.Caused by Personnel Error.Setpoint Adjusted.Technician Instructed ML19210D6251979-11-16016 November 1979 LER 79-049/01T-0:on 791101,four Seismic Supports Found W/Safety Factors of Less than Two.Caused by Engineering Design Deficiency.Redesign Performed.Corrective Action Implemented within Seven Days ML19247A0721979-07-20020 July 1979 LER 79-031/03L-0 on 790622:during Electrical Storm,Lost Main Stack Sampling Sys & Automatic Initiation Capability. Caused by Blown Fuses from lightning-induced Electrical Transient.Fuses Replaced ML19282C1531979-03-14014 March 1979 LER 79-007/03L-0 on 790212:during Surveillance,Setpoint of a Logic Automatic Depressurization Sys Time Delay Relay Was Greater than Tech Spec Limit.Caused by Setpoint Drift on GE Model CR-2820 Time Delay.Relay Readjusted & Tested 1990-05-07
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000278/LER-1999-005-03, :on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With1999-10-20020 October 1999
- on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With
ML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 05000278/LER-1999-004-03, :on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held1999-10-0101 October 1999
- on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held
ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML15112A7681999-09-20020 September 1999 SER Accepting Revision 25 of Pump & Valve Inservice Testing Program,Third 10-year Interval for Plant,Units 1,2 & 3 ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 05000278/LER-1999-003-03, :on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With1999-09-13013 September 1999
- on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With
ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with 05000277/LER-1999-005-01, :on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.With1999-07-16016 July 1999
- on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.With
ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with 05000278/LER-1999-002-02, :on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.With1999-05-0606 May 1999
- on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.With
ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 05000278/LER-1999-001-03, :on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments1999-04-0808 April 1999
- on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments
ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With 05000278/LER-1998-009-01, :on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with1999-01-20020 January 1999
- on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with
ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection 05000277/LER-1998-008-01, :on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With1998-12-30030 December 1998
- on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With
05000277/LER-1998-007-02, :on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With1998-12-0404 December 1998
- on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With
ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 05000278/LER-1998-005-03, :on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.With1998-11-20020 November 1998
- on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.With
ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 05000277/LER-1998-006-02, :on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With1998-10-0909 October 1998
- on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With
ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with 05000277/LER-1998-005-02, :on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made1998-09-18018 September 1998
- on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made
05000278/LER-1998-004-03, :on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc1998-09-18018 September 1998
- on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc
ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 1999-09-30
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Text
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CCN-90-14114 ;
PHILADELPHIA ELECTRIC COMPANY PEACil IKYl'IDM ATOMIC POWER STATION R. D. I, hot 20H I Delta, Pennsylvania 17314 rum mornm.v.es roe a os ascett wr pl7) 4Kr?014 i
June 5, 1990 Docket No. 50-278 Document Control Desk :
U. S. Nuclear Regulatory Commission Washington, DC 20555 '
SUBJECT:
Licensee Event Report Peach Bottom Atomic Power Station - Unit 3 This LER concerns a Primary Containment isolation System actuation which occurred due to a false isolation signal generated during surveillance testing.
Reference:
Docket No. 50-278 Report Number: 3-90-005 Revision Number: 00 ;
Event Date: 05/07/90 Report Date: 06/05/90- '
facility: Peach Bottom Atomic Power Station RD 1 Box 208, Delta, PA 17314 This (ER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(iv). -
Sincerely, l l Plant Manager cc: J. J. Lyash, USNRC Senior Resident inspector T. T. Martin, USNRC, Region I
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On 5/7/90, 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />, a Group 2A Primary Containment Isolation System (PCIS) isolation occurred during the performance of a surveillance test. The isolation resulted in the closing of the Reactor Water Cleanup (RWCU) System suction and discharge valves. The valve closures resulted in the tripping of the RWCU pumps.
The PCIS isolation occurred when a test lead from a voltmeter being used as part of the test dislodged, became grounded, and blew the circuit fuse for t.a RWCU suction line break and RWCU tieat Exchanger tilgh Temperature isolation logic circuit. On 5/8/90, 0208 hours0.00241 days <br />0.0578 hours <br />3.439153e-4 weeks <br />7.9144e-5 months <br />, the fuse was replaced and RWCU was placed back in service. The cause of this event was inadequate worker practice involving repositioning test leads at the voltmeter while installed in equipment circuitry as well as the use of short test leads and cotton gloves when performing the surveillance test. The technician involved was counseled. Other technicians will be similarly advised on repositioning voltmeter test leads when installed in equipment circuitry as well as the use of longer length test leads when necessary and to discontinue the use of cotton gloves during surveillances when not required. There were 2 previous similar LERs identified.
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Exemis swa FACILifv InAmt On Dockt1 teueA96R Las gga ,dutseth ist PA08 (Si Pnch Bottom Atoraic Power Station ***a " P'OP. ' tTJ.O Unit 3 0 l6 l 0 l 0 l 0 l 2 l7 l8 9l0 - oj o l5 - ojo ol2 oF ol 3 rarw . ee w =c m.ama nn ROQuirement for the Report This report is required per 10 CFR 50.73(a)(2)(iv) because an event occurred which resulted in an automatic actuation of an Engineered Safety feature (ESf).
Unit Status at Time of the Event
-Unit 3 was in tne Run mode of operation at 84% rated power.
-3B and 3C Reactor Water Cleanup (RWCU) (Ells:CE) pumps (Ells:P) in service.
-Both RWCU filter Demineralizers (Ells:f0M) in service.
-Surveillance test $13F-12-124-A1CQ " Calibration of RWCU High flow Instrument DPIS 12-124A" in progress.
Description of the Event On 5/7/90, 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />, a Group 2A Primary Containment isolation System (PCIS)
(Ells:JM) isolation occurred during the performance of surveillance test $13F-12-124-A1CQ " Calibration of RWCU High flow Instrument OPIS-3-12-124A". The Group 2A PCIS isolation resulted in the closing of the motor operated RWCU System suction and discharge valves (Ells:ISV) (M0-3-12-15, MO-3-12-18, and M0-3-12-68). The closure of these valves resulted in the tripping of the 3B and 3C RWCU pumps.
The PCIS isolation occurred when a test lead from a voltmeter being used as part of the survelliance test dislodged from the voltmeter socket and became grounded. The other end of the grounded lead had been installed in the positive side of the circuit for Differential Pressure Indicating Switch DPIS-3-12-124A (Ells:PIS). DPIS-3 124A is'used to provide a trip signal to isolate the RWCU System upon a RWCU suction line break event. Wito the test lead became grounded, the circuit fuse (Ells:fU) blew. The circuit contains the RWCU suction line break and RWCU Heat Exchanger (HX)
Discharge High Temperature isolation signal logic. Blowing the fuse resulted in these isolation signals which causes a Group 2A PCIS isolation (i.e., RWCU System suction and discharge valves close).
On 5/8/90, 0208 hours0.00241 days <br />0.0578 hours <br />3.439153e-4 weeks <br />7.9144e-5 months <br />, the fuse was replaced and the RWCU isolation reset. The RWCU System was then placed back into service.
Cause of the Event The isolation occurred when a test lead from the voltmeter being used as part of the surveillance dislodged and became grounded. The root cause of the test lead becoming grounded was inadequate worker practices. While repositioning a voltmeter lead, the technician performing the surveillance (Utility, non-licensed) inadvertently moved the voltmeter such that the test lead became dislodged and grounded on nearby piping (Ells: PSF). This was attributed to the short length of voltmeter leads being used and the use of cotton gloves by the technician and the fact that the other end of the ,
test lead was still installed in the circuitry. Cotton gloves were not required to be used but were being used by the technician because the instrumentation being j worked on was associated with the contaminated RWCU System. The use of cotton gloves '
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olo ol3 0F ol3 twu me: m e anco mnenn contributed to the mishandling of the voltmeter l'f the technician when repositioning the test leads in the voltmeter.
Analysis of the Event No safety consequences occurred as a result of this event.
When the spurious RWCU System suction line break and RWCU Hx Discharge High Temperature isolation signals were generated, the Group 2A PCIS isolation function performed properly. The purpose of the suction line break isolation is to limit the loss of Reactor Coolant System water if the RWCU System suction line would break.
The purpose of the RWCU Hx Discharge High Temperature isolation is to protect the ion exchange resins in the RWCU filter demineralizers due to high temperature.
During this event, the RWCU System was out of service for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The purpose of the RWCU System is to circulate Reactor water through demineralizers to maintain a high degree of water purity. No significant changes to Reactor water purity occurred. Similarly, had this event occurred at 100% power, it would not be expected that significant changes to Reactor water purity would have occurred.
Corrective Actions lhe blown fuse was repleted on 5/8/90, 0?08 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and the RWCU System placed into service, lhe technician involved was counseled on repositioning voltmeter test leads when installed in equipment circuitry as well as on the use of longer length test leads when required and not using cotton gloves if not required by Health Physics.
Technicians who perform similar surveillances will be informed of this event and advised about repositioning test leads while installed in equipment circuitry as well as the use of longer length voltmeter leads when necessary and also to discontinue the use of cotton gloves if not required when performing surveillances.
Previous Similar Events There were 2 previous LERs identified involving RWCU isolations during surveillance i testing. LER 2-86-11 involved an isolation as a result of testing a wrong component during surveillance. LER 3-87 05 involved an isolation as a result of incorrectly l l
installing a jumper during a surveillance. Both of these events involved personnel j crror in not following procedures. Personnel counseling for these events did not prevent the occurrence of this LER because the counseling involved adherence to j procedures and not worker practices. -
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NM 90RW 366A 'G8. CPD: 1998- 9 0 069 ti O M P
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