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| {{#Wiki_filter:-1 ACCELHRATZD M BUTION MMONSTRA7ION SYSTEM REGULATORY INFORMATXON DXSTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8801220203 DOC.DATE: 88/01/14 NOTARIZED-NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION SCHWABENBAUER Carolina Power&Light;Co.WATSON,R.A. | | {{#Wiki_filter:- 1 ACCELHRATZD M BUTION MMONSTRA7ION SYSTEM REGULATORY INFORMATXON DXSTRIBUTION SYSTEM (RIDS) |
| Carolina Power 6 Light Co.RECIP.NAME RECIPIENT AFFILIATION DQCKET 05000400 9 0500040 NOTES:Application for permit renewal filed. | | ACCESSION NBR:8801220203 DOC.DATE: 88/01/14 NOTARIZED- NO DQCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION SCHWABENBAUER Carolina Power & Light; Co. |
| | WATSON,R.A. Carolina Power 6 Light Co. |
| | RECIP.NAME RECIPIENT AFFILIATION |
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| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 87-067-00:on 871214,containment ventilation isolation:-due to spurious high radiation alarm while sampling.W/8 ltr.DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR L ENCL SIZE: TITLE: 50.73 Licensee Event Report, (LER), Incident Rpt, et:c.RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY,B INTERNAL: ACRS MICHELSON AEOD/DOA AEOD/DSP/ROAB ARM/DCTS/DAB NRR/DEST/ADS NRR/DEST/ELB NRR/DES T/MEB NRR/DEST/PSB NRR/DEST/SGB NRR/DLPQ/QAB NRR/DREP/RAB RZ SIB G F 02 RES/DE/EIB RGN2 FILE 01 EXTERNAL EGGG GROH i M H ST LOBBY WARD NRC PDR NSIC MAYS,G COPIES LTTR ENCL 1 1 1 1 1 1 1 1 2 2 1-1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 5 5 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD ACRS MOELLER AEOD/DS P/NAS AEOD/DSP/TPAB DEDRO NRR/DEST/CEB NRR/DEST/ICSB NRR/DE ST/MTB NRR/DEST/RSB NRR/DLPQ/HFB NRR/DOEA/EAB NRR/DREP/RPB NRR/PMAS/ILRB RES TELFORD,J RES/DRPS DIR FORD BLDG HOY,A LPDR NSIC HARRIS,J COPXES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1'1 1 1 1 i R A S A TOTAL NUMBER 0$COPIES REQUIRED: LTTR 46 ENCL 45 | | LER 87-067-00:on 871214,containment ventilation isolation |
| | :-due to spurious high radiation alarm while sampling. |
| | W/8 ltr. |
| | DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR L ENCL SIZE: |
| | TITLE: 50.73 Licensee Event Report, (LER), Incident Rpt, et:c. 9 NOTES:Application for permit renewal filed. 0500040 RECIPIENT COPIES RECIPIENT COPXES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 A BUCKLEY,B 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DS P/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 - |
| | 1 DEDRO 1 1 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/ICSB 1 1 NRR/DES T/MEB 1 1 NRR/DE ST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 1 NRR/DLPQ/HFB 1 1 NRR/DLPQ/QAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 RZ SIB 1 1 NRR/PMAS/ILRB 1 1 G F 02 1 1 RES TELFORD,J 1 1 RES/DE/EIB 1 1 RES/DRPS DIR 1 1 RGN2 FILE 01 1 1 EXTERNAL EGGG GROH i M 5 5 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR '1 1 i R NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 S |
| | A TOTAL NUMBER 0$ COPIES REQUIRED: LTTR 46 ENCL 45 |
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| NRC Form 388 (949 l LICENSEE EVENT REPORT (LER)US.NUCLEAR AEOULATOAY COMMISSION APPROVEO OMB NO.31500)04 EXPIRES: 8/31/88 FACILITY NAME (I)SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE DOCKET NUMBER (2)PA 5 3 o s o o o 40 0>'OF04 CONTAINMENT VENTILATION ISOLATION DUE TO A SPURIOUS HIGH RADIATION ALAMO WHILE SAMPLING AT MONITOR EVENT DATE (5)LER NUMBER (8)REPORT DATE (7)OTHER FACILITIES INVOLVED ISI MONTH OAY YEAR YEAR'SEaUSNTrAL g4 NUMSSA (I(.SA MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERIS)0 5 0 0 0 1 2148 78 7 0 6 7 00 011 488 0'50oo OPERATINO MODE (9)]POIVER LEVEL 0 Vd''V(~s (20.402(b)20405(e)(I)(0 20.405(el(1)(8) 20.405(e I (1)(5 I)20405(e)(I)Or) 20.405(e)('I)(r)20405(cl SOM(c)III SOM(c)(2)50.73(el(2)(I) 50.73(s)(2)(8)50.73(s)(2) | | NRC Form 388 US. NUCLEAR AEOULATOAYCOMMISSION (949 l APPROVEO OMB NO. 31500)04 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (2) PA 5 3 SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE o s o o o 40 0>'OF04 CONTAINMENT VENTILATION ISOLATION DUE TO A SPURIOUS HIGH RADIATION ALAMO WHILE SAMPLING AT MONITOR EVENT DATE (5) LER NUMBER (8) REPORT DATE (7) OTHER FACILITIES INVOLVED ISI |
| IIII)50.7 3(s I (2)(lel 50.734)(2)(rl 50.73(el(2)(rS) 50.73(e)(2)(rllll(AI 50.73(s I 12 I (rI II)(B)50.73(e)(2)(el THIS REPORT IS SUBMITTED PUASVANT TO THE REQUIREMENTS OF 10 CFR ('ll fChrcfr onr or more of tire follorflnPI (11)73.71(8)73.71(c)OTHER ISpecify In 48rtrect Oelorernd In Text, IIAC Form 3884)NAME LICENSEE CONTACT FOR THIS LER (12)R.SCHWABENBAUER
| | ' SEaUSNTrAL MONTH OAY YEAR YEAR g4 NUMSSA (I(. SA MONTH DAY YEAR FACILITYNAMES DOCKET NUMBERIS) 0 5 0 0 0 1 2148 78 7 0 6 7 00 011 488 THIS REPORT IS SUBMITTED PUASVANT TO THE REQUIREMENTS OF 10 CFR ('ll fChrcfr onr or more 0'50oo OPERATINO of tire follorflnPI (11) |
| -REGULATORY COMPLIANCE TECHICIAN TELEPHONE NUMBER AREA CODE 91 9362-2 669 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT 14ANUFAC.TUR ER EPOATABLE TO NPRDS sc'''CAUSE SYSTEM COMPONENT MANU FAC.TVRER'P EPORTABLE'TO NPRDS 2....A...AM. | | MODE (9) |
| r I K SUPPLEMENTAL REPORT EXPECTED (14)EXPECTED SUBMISSION PATE (I SI MONTH OAY YEAR YES Ilf yrr, complrtr EXPECTED SII84IISSION 04TEI NO ABSTRACT IUmlt to 1400 lpeerr, I r., rpproxlmerrly flfrrrn rlnplerprcr ryperrrlrtrn Iinrrl (18)ABSTRACT: The plant was operating in Mode 1, Power Operation, at 99 percent reactor power on December 14, 1987.At 0340 hours while a chemistry technician was obtaining a grab sample from Containment Leak Detection Radiation Monitor, REM-1LT-3502A-SA, a high radiation alarm was generated.
| | ] 20.402(b) 20405(cl 50.7 3(s I (2)(lel 73.71(8) |
| The high radiation alarm generated a containment ventilation isolat:on signal which resulted in the closure of all containment ventilation valves in accordance with plant design.The cause of the alarm was a spurious electronic signal spike.The alarm was cleared, the monitor was verified to be operating correctly, and the containment ventilation normal valve line-up was restored.The grab sample taken when the monitor alarmed was analy ed and found to be within acceptable limits.Actions to prevent recurrence are.'grab sample lines have been clearly labeled to ensure correct hook-up, sampling frequencies have been reduced, and a Plant Change Request will be installed which provides an improved signal smoothing algorithm. | | POIVER 20405(e) (I) (0 SOM(c)III 50.734) (2)(rl 73.71(c) |
| NRC Form 388 This event is being reported in accordance with 10CPR50.73(a)(2)(iv) as an automatic actuation of an Engineered Safety Feature.8801220203 880114 PDR ADOCK 05000400 8 DCD R
| | LEVEL 0 20.405(el(1)(8) SOM(c)(2) 50.73(el(2)(rS) OTHER ISpecify In 48rtrect Vd '' V( Oelorernd In Text, IIAC Form 20.405(e I (1)(5 I) 50.73(el(2)(I) 50.73(e) (2)(rllll(AI 3884) |
| NRC form 355A (083(LICENSEE EVENT REPORT ILER)TEXT CONTINUATION UA.NUCLEAR REOULATORY COMMISSION APPROVEO OMS NO.3(50M104 EXPIRES: 8/31/88 PACILITY NAME (I I SHEARON HARRIS NUCLEAR POWER, PLANT UNIT ONE COCKET NUMBER (2l LER NUMEER (4l YEAR@g 55OUENTIAL:ag NUM II RCVI5ION NUM55/I PACE (3l TEXT//l moro spece lr roEM(orE rrm RR/Oono///RC | | ~s ( 20405(e)(I)Or) 50.73(s) (2) (8) 50.73(s I 12 I (rI II)(B) 20.405(e) ('I ) (r) 50.73(s)(2) IIII) 50.73(e) (2) (el LICENSEE CONTACT FOR THIS LER (12) |
| %%drm BRAS/(IT(DESCRIPTION:
| | NAME TELEPHONE NUMBER R. SCHWABENBAUER - REGULATORY COMPLIANCE TECHICIAN AREA CODE 91 9362 -2 669 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) sc |
| 0 5 0 0 0 400 067 0 0 2 OF 0 4 The plant was operating in Mode 1, Power Operation, at 99 percent reactor power on December 14, 1987.At 0340 hours a chemistry technician was preparing to pull a grab sample from the Containment Leak Detection Radiation Monitor, (EIIS:IK)REM-1LT-3502A-SA.
| | ' ' ' |
| This monitor provides an indication of reactor coolant (EIIS:AB)leakage and provides an automatic isolation of the normal containment purge system (EIIS:BD)upon receiving a high radiation alarm.The grab samples taken from this monitor are used to evaluate airborne radioactivity and oxygen levels in Containment (EIIS:NH)prior to personnel entry.The chemistry technician connected the sample apparatus to the monitor grab sample lines and proceeded to close the grab sample bypass valve, initiating the grab sample.As the sample started the technician noticed the water flow in the tritium bubbler was reversed so he isolated the grab sample and checked his sample apparatus.
| | 'P 14ANUFAC. EPOATABLE MANUFAC. ' |
| The technician did not make any changes and started the process again which resulted in the same condition to occur.He then checked his hookup again and this time discovered that the sample lines from the monitor to the sample apparatus were reversed.He then corrected this problem and once again began closing the bypass valve to initiate the grab sample.As the grab sample started the technician noticed a surge in the grab sample flow caused by water in the tubing (from the tritium sampler).This surge coincided with a high radiation alarm received in the Main Control Room (MCR)and at the monitor skid.At this time the technician called the MCR to inform them of the event and that his sampling was the probable cause.In accordance with plant design a containment ventilation (EIIS:JM)isolation signal was generated when the monitor went into alarm and all containment ventilation isolation.
| | CAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT EPORTABLE TUR ER TO NPRDS TVRER TO NPRDS r |
| valves closed as required.The monitor alarm was then cleared and operations personnel visually verified the monitor to be operating correctly and returned the containment ventilation system to its normal operating valve lineup.The grab sample was then completed at 0400 hours, analyzed, and found to be within acceptable limits.CAUSE: While there was personnel error in the initial connection of the sampling device it could not be proven that this alone was the cause of the event.Sample valve manipulations apparently caused a flow surge which apparently initiated a high activity signal spike and caused the monitor to alarm.This alarm, in turn, caused the required automatic actuation of the containment ventilation isolation system which responded per plant design.NRC POIIM 555*(083 I oU.S.QPO:1085 0824 d38/45d
| | 2 |
| | ....A...AM. K I SUPPLEMENTAL REPORT EXPECTED (14) MONTH OAY YEAR EXPECTED SUBMISSION PATE (I SI YES Ilfyrr, complrtr EXPECTED SII84IISSION 04TEI NO ABSTRACT IUmlt to 1400 lpeerr, I r., rpproxlmerrly flfrrrn rlnplerprcr ryperrrlrtrn Iinrrl (18) |
| | ABSTRACT: |
| | The plant was operating in Mode 1, Power Operation, at 99 percent reactor power on December 14, 1987. At 0340 hours while a chemistry technician was obtaining a grab sample from Containment Leak Detection Radiation Monitor, REM-1LT-3502A-SA, a high radiation alarm was generated. The high radiation alarm generated a containment ventilation isolat:on signal which resulted in the closure of all containment ventilation valves in accordance with plant design. |
| | The cause of the alarm was a spurious electronic signal spike. |
| | The alarm was cleared, the monitor was verified to be operating correctly, and the containment ventilation normal valve line-up was restored. The grab sample taken when the monitor alarmed was analy ed and found to be within acceptable limits. |
| | Actions to prevent recurrence are. |
| | labeled to ensure correct hook-up, sampling frequencies have been reduced, and |
| | 'grab sample lines have been clearly a Plant Change Request will be installed which provides an improved signal smoothing algorithm. |
| | This event is being reported in accordance with 10CPR50.73(a)(2)(iv) as an automatic actuation of an Engineered Safety Feature. |
| | 8801220203 880114 PDR ADOCK 05000400 8 DCD NRC Form 388 |
|
| |
|
| NRC form 344A (SS3)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION UA.NUCLEAR REOULATORY COMMISSION APPROVEO OMS NO.3(9)WIOO EKPIRESI 4/31/SS SACILITY NAME (1)SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE TEXT/Jf/Sere Santo)I IOUM)OS INO//I/oao/kRC Form 3SSA3)OT)CAUSE: (continued) | | R NRC form 355A UA. NUCLEAR REOULATORY COMMISSION (083( |
| OOCKET NUMSER (2)o s o o o 4 0 YEAR 8 7-0 6 7 LER NUMSER (4)Sf OUCNIIAL NVMOER REVISION NVM ta fAOE (3)OF 0 0 3 0 4 However, a spurious, high activity alarm and consequent ventilation isolation were experienced during a routine sampling evolution at 0408 on December 16, 1987.The coincidence of the alarms with the sampling cannot be explained at this time.ANALYSIS: This event is being reported in accordance with 10CFR50.73(a)(2)(iv) as an automatic actuation of a plant Engineered Safety Feature (ESF).No safety consequences resulted from this event.The grab sample results, taken during the event, indicate there was no increase in containment airborne activity during the time the monitor was in alarm.It is'eportable because the possible automatic actuation of ESF was not anticipated due to personnel error in failing to notify the MCR prior to sampling.This monitor has a history of susceptibility to otherwise innocuous disturbances resulting in spurious alarms.Had the alarm been caused by excessive Reactor Coolant System (RCS)leakage, it would have been contained in the containment building, as required, by the actuation of the containment ventilation isolation system which responded per design.There have not been any similar events reported.CORRECTIVE ACTIONS/ACTIONS TO PREVENT RECURRENCE:
| | LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVEO OMS NO. 3(50M104 EXPIRES: 8/31/88 PACILITY NAME (I I COCKET NUMBER (2l PACE (3l LER NUMEER (4l SHEARON HARRIS NUCLEAR POWER, PLANT YEAR 55OUENTIAL:ag RCVI5ION |
| 1.A Plant Change R(dquest (PCR)will be installed which provides an improved signal smoothing algorithm to reduce the monitors susceptibility to spurious alarms.2.Sampling frequencies on monitor REM"1LT-3502A-SA have been reduced to once a week or as required.3.Radiation monitor grab sample lines have been clearly labeled to ensure correct hookup.4.Alternative methods are being investigated for grab sampling locations/methods. | | @g NUM II NUM55/I UNIT ONE TEXT //lmoro spece lr roEM(orE rrm RR/Oono///RC %%drm BRAS/ (IT( |
| NRC SORM 3OOA (943)a U.S OPO:104dd)d)24 438/ddd e | | 0 5 0 0 0 400 067 0 0 2 OF 0 4 DESCRIPTION: |
| NRC form 888A (!HLI)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION US.NUCLEAR RECULATORY COMMISSION APPROVED OMS NO.3(EOMI(>>EXPIRES: 8/2(/88 PACILITY NAME (Il SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE TEXT//f more g>>ce/r//r/rerE r>>o//rior>>////IC Arm Sr)I/AEI (IT)DOCKET NUMBER (2)YEAR o s o o o 400 87 LER NUMBER (8)SEQUENTIAL NUMIIER 067 REVI5ION NUM eR PACE (8)oF 04 000 4 CORRECTIVE'CTIONS/ACTIONS TO PREVENT RECURRENCE (continued) 5.The leak detection monitor will be declared inoperable and appropriate Technical Specification actions taken when sampling is done rom its flow path.NIIC PO/IM 840*(843)<<U.S.OPO:18804424.538/455 CSEE>>Carolina Power&Light Company HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 JAN 14 1988 File Number.'HF/10-13510C Letter Number'.HO-880003 (0)U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 87-067-00 Gentl.emen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. | | The plant was operating in Mode 1, Power Operation, at 99 percent reactor power on December 14, 1987. At 0340 hours a chemistry technician was preparing to pull a grab sample from the Containment Leak Detection Radiation Monitor, (EIIS:IK) REM-1LT-3502A-SA. This monitor provides an indication of reactor coolant (EIIS:AB) leakage and provides an automatic isolation of the normal containment purge system (EIIS:BD) upon receiving a high radiation alarm. The grab samples taken from this monitor are used to evaluate airborne radioactivity and oxygen levels in Containment (EIIS:NH) prior to personnel entry. |
| This report fulfills the requirement for a written report within thirty (30)days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983.Very truly yours,/Zoic'J~~R.A.Watson Vice President Harris Nuclear Project RAW:acm Enclosure cc'.Dr.J.Nelson Grace (NRC-RII)Mr.B.Buckley (NRR)Mr.G.Maxwell (NRC-SHNPP)MEM/LER-87"067/1/OS1}} | | The chemistry technician connected the sample apparatus to the monitor grab sample lines and proceeded to close the grab sample bypass valve, initiating the grab sample. As the sample started the technician noticed the water flow in the tritium bubbler was reversed so he isolated the grab sample and checked his sample apparatus. The technician did not make any changes and started the process again which resulted in the same condition to occur. He then checked his hookup again and this time discovered that the sample lines from the monitor to the sample apparatus were reversed. He then corrected this problem and once again began closing the bypass valve to initiate the grab sample. As the grab sample started the technician noticed a surge in the grab sample flow caused by water in the tubing (from the tritium sampler). |
| | This surge coincided with a high radiation alarm received in the Main Control Room (MCR) and at the monitor skid. At this time the technician called the MCR to inform them of the event and that his sampling was the probable cause. In accordance with plant design a containment ventilation (EIIS:JM) isolation signal was generated when the monitor went into alarm and all containment ventilation isolation. valves closed as required. |
| | The monitor alarm was then cleared and operations personnel visually verified the monitor to be operating correctly and returned the containment ventilation system to its normal operating valve lineup. |
| | The grab sample was then completed at 0400 hours, analyzed, and found to be within acceptable limits. |
| | CAUSE: |
| | While there was personnel error in the initial connection of the sampling device it could not be proven that this alone was the cause of the event. |
| | Sample valve manipulations apparently caused a flow surge which apparently initiated a high activity signal spike and caused the monitor to alarm. This alarm, in turn, caused the required automatic actuation of the containment ventilation isolation system which responded per plant design. |
| | NRC POIIM 555* |
| | (083 I oU.S.QPO:1085 0824 d38/45d |
| | |
| | NRC form 344A UA. NUCLEAR REOULATORY COMMISSION (SS3) |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMS NO. 3(9)WIOO EKPIRESI 4/31/SS SACILITY NAME (1) OOCKET NUMSER (2) LER NUMSER (4) fAOE (3) |
| | YEAR Sf OUCNIIAL REVISION SHEARON HARRIS NUCLEAR POWER PLANT NVMOER NVM ta UNIT ONE o s o o o 4 0 8 70 6 7 0 0 3 OF 0 4 TEXT /Jf /Sere Santo )I IOUM)OS INO //I/oao/kRC Form 3SSA3) OT) |
| | CAUSE: (continued) |
| | However, a spurious, high activity alarm and consequent ventilation isolation were experienced during a routine sampling evolution at 0408 on December 16, 1987. The coincidence of the alarms with the sampling cannot be explained at this time. |
| | ANALYSIS: |
| | This event is being reported in accordance with 10CFR50.73(a)(2)(iv) as an automatic actuation of a plant Engineered Safety Feature (ESF). |
| | No safety consequences resulted from this event. The grab sample results, taken during the event, indicate there was no increase in containment airborne activity during the time the monitor was in alarm. |
| | It is 'eportable because the possible automatic actuation of ESF was not anticipated due to personnel error in failing to notify the MCR prior to sampling. |
| | This monitor has a history of susceptibility to otherwise innocuous disturbances resulting in spurious alarms. |
| | Had the alarm been caused by excessive Reactor Coolant System (RCS) leakage, it would have been contained in the containment building, as required, by the actuation of the containment ventilation isolation system which responded per design. |
| | There have not been any similar events reported. |
| | CORRECTIVE ACTIONS/ACTIONS TO PREVENT RECURRENCE: |
| | : 1. A Plant Change R(dquest (PCR) will be installed which provides an improved signal smoothing algorithm to reduce the monitors susceptibility to spurious alarms. |
| | : 2. Sampling frequencies on monitor REM"1LT-3502A-SA have been reduced to once a week or as required. |
| | : 3. Radiation monitor grab sample lines have been clearly labeled to ensure correct hookup. |
| | : 4. Alternative methods are being investigated for grab sampling locations/methods. |
| | NRC SORM 3OOA a U.S OPO:104dd)d)24 438/ddd (943) |
| | |
| | e NRC form 888A US. NUCLEAR RECULATORY COMMISSION |
| | (!HLI) |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3(EOMI(>> |
| | EXPIRES: 8/2(/88 PACILITY NAME (Il DOCKET NUMBER (2) LER NUMBER (8) PACE (8) |
| | YEAR SEQUENTIAL REVI5ION SHEARON HARRIS NUCLEAR POWER PLANT NUMIIER NUM eR UNIT ONE o s o o o 400 87 067 000 4 oF 04 TEXT //f more g>>ce /r //r/rerE r>>o //rior>>////IC Arm Sr)I/AEI (IT) |
| | CORRECTIVE'CTIONS/ACTIONS TO PREVENT RECURRENCE (continued) |
| | : 5. The leak detection monitor will be declared inoperable and appropriate Technical Specification actions taken when sampling is done rom its flow path. |
| | NIIC PO/IM 840* <<U.S.OPO:18804424.538/455 (843) |
| | |
| | CSEE>> |
| | Carolina Power & Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 JAN 14 1988 File Number.'HF/10-13510C Letter Number'. HO-880003 (0) |
| | U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 87-067-00 Gentl.emen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983. |
| | Very truly yours, |
| | /Zoic'J~~ |
| | R. A. Watson Vice President Harris Nuclear Project RAW:acm Enclosure cc'. Dr. J. Nelson Grace (NRC - RII) |
| | Mr. B. Buckley (NRR) |
| | Mr. G. Maxwell (NRC SHNPP) |
| | MEM/LER-87"067/1/OS1}} |
LER 87-067-00:on 871214,containment Ventilation Isolation Occurred Due to High Radiation Alarm While Grab Sampling at Monitor REM-1LT-3502A-SA.Caused by Personnel Error & Eletronic Signal Spike.Sample Line labeled.W/880114 Ltr| ML18005A249 |
| Person / Time |
|---|
| Site: |
Harris  |
|---|
| Issue date: |
01/14/1988 |
|---|
| From: |
Schwabenbauer, Watson R
CAROLINA POWER & LIGHT CO. |
|---|
| To: |
|
|---|
| References |
|---|
| HO-880003-(O), LER-87-067, LER-87-67, NUDOCS 8801220203 |
| Download: ML18005A249 (10) |
|
|
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18022B0551998-05-20020 May 1998
LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr
ML18016A4061998-04-30030 April 1998
LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive
ML18016A3841998-04-13013 April 1998
LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr
ML18016A3441998-03-12012 March 1998
LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV
ML18016A3291998-02-27027 February 1998
LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr
ML18016A3211998-02-20020 February 1998
LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr
ML18016A3131998-02-0909 February 1998
LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01
ML18016A2641997-12-18018 December 1997
LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr
ML18016A2501997-11-24024 November 1997
LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr
ML18016A2201997-10-22022 October 1997
LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures
ML18016A2081997-10-14014 October 1997
LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr
ML18016A2111997-10-14014 October 1997
LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced
ML18016A1931997-09-29029 September 1997
LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr
ML18016A1891997-09-12012 September 1997
LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr
ML18016A1881997-09-12012 September 1997
LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr
ML18012A8641997-08-18018 August 1997
LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr
ML18012A8581997-08-0808 August 1997
LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc
ML18012A8551997-08-0808 August 1997
LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls
ML18012A8471997-07-31031 July 1997
LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr
ML18012A8371997-07-24024 July 1997
LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold
ML18012A8291997-07-11011 July 1997
LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr
ML18012A8301997-07-0808 July 1997
LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr
ML18012A8241997-07-0202 July 1997
LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr
ML18022B0181997-06-13013 June 1997
LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr
ML18012A8081997-06-0909 June 1997
LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr
ML18012A8021997-06-0606 June 1997
LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr
ML18012A8011997-06-0404 June 1997
LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr
ML18012A7951997-05-29029 May 1997
LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr
ML18012A7891997-05-22022 May 1997
LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr
ML18012A7871997-05-19019 May 1997
LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr
ML18012A7761997-05-0707 May 1997
LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr
ML18012A7751997-05-0505 May 1997
LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr
ML18012A6291997-04-24024 April 1997
LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr
ML18022B0151997-04-17017 April 1997
LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr
ML18012A6041997-04-0303 April 1997
LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr
ML18012A6031997-03-31031 March 1997
LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr
1999-09-10
[Table view]
Category:RO)
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18022B0551998-05-20020 May 1998
LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr
ML18016A4061998-04-30030 April 1998
LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive
ML18016A3841998-04-13013 April 1998
LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr
ML18016A3441998-03-12012 March 1998
LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV
ML18016A3291998-02-27027 February 1998
LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr
ML18016A3211998-02-20020 February 1998
LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr
ML18016A3131998-02-0909 February 1998
LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01
ML18016A2641997-12-18018 December 1997
LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr
ML18016A2501997-11-24024 November 1997
LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr
ML18016A2201997-10-22022 October 1997
LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures
ML18016A2081997-10-14014 October 1997
LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr
ML18016A2111997-10-14014 October 1997
LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced
ML18016A1931997-09-29029 September 1997
LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr
ML18016A1891997-09-12012 September 1997
LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr
ML18016A1881997-09-12012 September 1997
LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr
ML18012A8641997-08-18018 August 1997
LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr
ML18012A8581997-08-0808 August 1997
LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc
ML18012A8551997-08-0808 August 1997
LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls
ML18012A8471997-07-31031 July 1997
LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr
ML18012A8371997-07-24024 July 1997
LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold
ML18012A8291997-07-11011 July 1997
LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr
ML18012A8301997-07-0808 July 1997
LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr
ML18012A8241997-07-0202 July 1997
LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr
ML18022B0181997-06-13013 June 1997
LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr
ML18012A8081997-06-0909 June 1997
LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr
ML18012A8021997-06-0606 June 1997
LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr
ML18012A8011997-06-0404 June 1997
LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr
ML18012A7951997-05-29029 May 1997
LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr
ML18012A7891997-05-22022 May 1997
LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr
ML18012A7871997-05-19019 May 1997
LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr
ML18012A7761997-05-0707 May 1997
LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr
ML18012A7751997-05-0505 May 1997
LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr
ML18012A6291997-04-24024 April 1997
LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr
ML18022B0151997-04-17017 April 1997
LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr
ML18012A6041997-04-0303 April 1997
LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr
ML18012A6031997-03-31031 March 1997
LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr
1999-09-10
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A9151999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18017A8621999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18017A8361999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr
ML18016B0151999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9851999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr
ML18017A8981999-05-12012 May 1999
Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines.
ML18016A9581999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr
ML18016A9011999-04-12012 April 1999
Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8941999-04-0505 April 1999
Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760
ML18016A9101999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr
ML18016A8661999-03-31031 March 1999
Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept.
ML18017A8931999-02-28028 February 1999
Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant.
ML18016A8551999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8531999-02-18018 February 1999
Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'.
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18022B0631999-02-0404 February 1999
Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings
ML20202J1161999-02-0101 February 1999
SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program
ML18016A8041999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7801998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr
ML18016A7671998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr
ML18016A9731998-11-28028 November 1998
Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr
ML18016A8351998-11-28028 November 1998
ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1.
ML18016A7411998-11-25025 November 1998
Rev 1 to Shnpp Cycle 9 Colr.
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A7071998-11-0303 November 1998
Rev 0 to Harris Unit 1 Cycle 9 Colr.
ML18016A7201998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr
ML20154F8701998-10-0606 October 1998
Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves
ML18016A6201998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr
ML18016A5971998-09-21021 September 1998
Rev 1 to Harris Unit 1 Cycle 8 Colr.
ML18016A5881998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr
ML18016A5071998-07-31031 July 1998
Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr
ML18016A9431998-07-0707 July 1998
Rev 1 to QAP Manual.
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A9371998-06-30030 June 1998
Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp.
ML18016A4861998-06-30030 June 1998
Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18016A4521998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr
ML18016A7711998-05-26026 May 1998
Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'.
1999-09-30
[Table view] |
Text
- 1 ACCELHRATZD M BUTION MMONSTRA7ION SYSTEM REGULATORY INFORMATXON DXSTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8801220203 DOC.DATE: 88/01/14 NOTARIZED- NO DQCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION SCHWABENBAUER Carolina Power & Light; Co.
WATSON,R.A. Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 87-067-00:on 871214,containment ventilation isolation
- -due to spurious high radiation alarm while sampling.
W/8 ltr.
DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR L ENCL SIZE:
TITLE: 50.73 Licensee Event Report, (LER), Incident Rpt, et:c. 9 NOTES:Application for permit renewal filed. 0500040 RECIPIENT COPIES RECIPIENT COPXES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 A BUCKLEY,B 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DS P/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 -
1 DEDRO 1 1 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/ICSB 1 1 NRR/DES T/MEB 1 1 NRR/DE ST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 1 NRR/DLPQ/HFB 1 1 NRR/DLPQ/QAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 RZ SIB 1 1 NRR/PMAS/ILRB 1 1 G F 02 1 1 RES TELFORD,J 1 1 RES/DE/EIB 1 1 RES/DRPS DIR 1 1 RGN2 FILE 01 1 1 EXTERNAL EGGG GROH i M 5 5 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR '1 1 i R NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 S
A TOTAL NUMBER 0$ COPIES REQUIRED: LTTR 46 ENCL 45
NRC Form 388 US. NUCLEAR AEOULATOAYCOMMISSION (949 l APPROVEO OMB NO. 31500)04 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (2) PA 5 3 SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE o s o o o 40 0>'OF04 CONTAINMENT VENTILATION ISOLATION DUE TO A SPURIOUS HIGH RADIATION ALAMO WHILE SAMPLING AT MONITOR EVENT DATE (5) LER NUMBER (8) REPORT DATE (7) OTHER FACILITIES INVOLVED ISI
' SEaUSNTrAL MONTH OAY YEAR YEAR g4 NUMSSA (I(. SA MONTH DAY YEAR FACILITYNAMES DOCKET NUMBERIS) 0 5 0 0 0 1 2148 78 7 0 6 7 00 011 488 THIS REPORT IS SUBMITTED PUASVANT TO THE REQUIREMENTS OF 10 CFR ('ll fChrcfr onr or more 0'50oo OPERATINO of tire follorflnPI (11)
MODE (9)
] 20.402(b) 20405(cl 50.7 3(s I (2)(lel 73.71(8)
POIVER 20405(e) (I) (0 SOM(c)III 50.734) (2)(rl 73.71(c)
LEVEL 0 20.405(el(1)(8) SOM(c)(2) 50.73(el(2)(rS) OTHER ISpecify In 48rtrect Vd V( Oelorernd In Text, IIAC Form 20.405(e I (1)(5 I) 50.73(el(2)(I) 50.73(e) (2)(rllll(AI 3884)
~s ( 20405(e)(I)Or) 50.73(s) (2) (8) 50.73(s I 12 I (rI II)(B) 20.405(e) ('I ) (r) 50.73(s)(2) IIII) 50.73(e) (2) (el LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER R. SCHWABENBAUER - REGULATORY COMPLIANCE TECHICIAN AREA CODE 91 9362 -2 669 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) sc
' ' '
'P 14ANUFAC. EPOATABLE MANUFAC. '
CAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT EPORTABLE TUR ER TO NPRDS TVRER TO NPRDS r
2
....A...AM. K I SUPPLEMENTAL REPORT EXPECTED (14) MONTH OAY YEAR EXPECTED SUBMISSION PATE (I SI YES Ilfyrr, complrtr EXPECTED SII84IISSION 04TEI NO ABSTRACT IUmlt to 1400 lpeerr, I r., rpproxlmerrly flfrrrn rlnplerprcr ryperrrlrtrn Iinrrl (18)
ABSTRACT:
The plant was operating in Mode 1, Power Operation, at 99 percent reactor power on December 14, 1987. At 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br /> while a chemistry technician was obtaining a grab sample from Containment Leak Detection Radiation Monitor, REM-1LT-3502A-SA, a high radiation alarm was generated. The high radiation alarm generated a containment ventilation isolat:on signal which resulted in the closure of all containment ventilation valves in accordance with plant design.
The cause of the alarm was a spurious electronic signal spike.
The alarm was cleared, the monitor was verified to be operating correctly, and the containment ventilation normal valve line-up was restored. The grab sample taken when the monitor alarmed was analy ed and found to be within acceptable limits.
Actions to prevent recurrence are.
labeled to ensure correct hook-up, sampling frequencies have been reduced, and
'grab sample lines have been clearly a Plant Change Request will be installed which provides an improved signal smoothing algorithm.
This event is being reported in accordance with 10CPR50.73(a)(2)(iv) as an automatic actuation of an Engineered Safety Feature.
8801220203 880114 PDR ADOCK 05000400 8 DCD NRC Form 388
R NRC form 355A UA. NUCLEAR REOULATORY COMMISSION (083(
LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVEO OMS NO. 3(50M104 EXPIRES: 8/31/88 PACILITY NAME (I I COCKET NUMBER (2l PACE (3l LER NUMEER (4l SHEARON HARRIS NUCLEAR POWER, PLANT YEAR 55OUENTIAL:ag RCVI5ION
@g NUM II NUM55/I UNIT ONE TEXT //lmoro spece lr roEM(orE rrm RR/Oono///RC %%drm BRAS/ (IT(
0 5 0 0 0 400 067 0 0 2 OF 0 4 DESCRIPTION:
The plant was operating in Mode 1, Power Operation, at 99 percent reactor power on December 14, 1987. At 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br /> a chemistry technician was preparing to pull a grab sample from the Containment Leak Detection Radiation Monitor, (EIIS:IK) REM-1LT-3502A-SA. This monitor provides an indication of reactor coolant (EIIS:AB) leakage and provides an automatic isolation of the normal containment purge system (EIIS:BD) upon receiving a high radiation alarm. The grab samples taken from this monitor are used to evaluate airborne radioactivity and oxygen levels in Containment (EIIS:NH) prior to personnel entry.
The chemistry technician connected the sample apparatus to the monitor grab sample lines and proceeded to close the grab sample bypass valve, initiating the grab sample. As the sample started the technician noticed the water flow in the tritium bubbler was reversed so he isolated the grab sample and checked his sample apparatus. The technician did not make any changes and started the process again which resulted in the same condition to occur. He then checked his hookup again and this time discovered that the sample lines from the monitor to the sample apparatus were reversed. He then corrected this problem and once again began closing the bypass valve to initiate the grab sample. As the grab sample started the technician noticed a surge in the grab sample flow caused by water in the tubing (from the tritium sampler).
This surge coincided with a high radiation alarm received in the Main Control Room (MCR) and at the monitor skid. At this time the technician called the MCR to inform them of the event and that his sampling was the probable cause. In accordance with plant design a containment ventilation (EIIS:JM) isolation signal was generated when the monitor went into alarm and all containment ventilation isolation. valves closed as required.
The monitor alarm was then cleared and operations personnel visually verified the monitor to be operating correctly and returned the containment ventilation system to its normal operating valve lineup.
The grab sample was then completed at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, analyzed, and found to be within acceptable limits.
CAUSE:
While there was personnel error in the initial connection of the sampling device it could not be proven that this alone was the cause of the event.
Sample valve manipulations apparently caused a flow surge which apparently initiated a high activity signal spike and caused the monitor to alarm. This alarm, in turn, caused the required automatic actuation of the containment ventilation isolation system which responded per plant design.
NRC POIIM 555*
(083 I oU.S.QPO:1085 0824 d38/45d
NRC form 344A UA. NUCLEAR REOULATORY COMMISSION (SS3)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMS NO. 3(9)WIOO EKPIRESI 4/31/SS SACILITY NAME (1) OOCKET NUMSER (2) LER NUMSER (4) fAOE (3)
YEAR Sf OUCNIIAL REVISION SHEARON HARRIS NUCLEAR POWER PLANT NVMOER NVM ta UNIT ONE o s o o o 4 0 8 70 6 7 0 0 3 OF 0 4 TEXT /Jf /Sere Santo )I IOUM)OS INO //I/oao/kRC Form 3SSA3) OT)
CAUSE: (continued)
However, a spurious, high activity alarm and consequent ventilation isolation were experienced during a routine sampling evolution at 0408 on December 16, 1987. The coincidence of the alarms with the sampling cannot be explained at this time.
ANALYSIS:
This event is being reported in accordance with 10CFR50.73(a)(2)(iv) as an automatic actuation of a plant Engineered Safety Feature (ESF).
No safety consequences resulted from this event. The grab sample results, taken during the event, indicate there was no increase in containment airborne activity during the time the monitor was in alarm.
It is 'eportable because the possible automatic actuation of ESF was not anticipated due to personnel error in failing to notify the MCR prior to sampling.
This monitor has a history of susceptibility to otherwise innocuous disturbances resulting in spurious alarms.
Had the alarm been caused by excessive Reactor Coolant System (RCS) leakage, it would have been contained in the containment building, as required, by the actuation of the containment ventilation isolation system which responded per design.
There have not been any similar events reported.
CORRECTIVE ACTIONS/ACTIONS TO PREVENT RECURRENCE:
- 1. A Plant Change R(dquest (PCR) will be installed which provides an improved signal smoothing algorithm to reduce the monitors susceptibility to spurious alarms.
- 2. Sampling frequencies on monitor REM"1LT-3502A-SA have been reduced to once a week or as required.
- 3. Radiation monitor grab sample lines have been clearly labeled to ensure correct hookup.
- 4. Alternative methods are being investigated for grab sampling locations/methods.
NRC SORM 3OOA a U.S OPO:104dd)d)24 438/ddd (943)
e NRC form 888A US. NUCLEAR RECULATORY COMMISSION
(!HLI)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3(EOMI(>>
EXPIRES: 8/2(/88 PACILITY NAME (Il DOCKET NUMBER (2) LER NUMBER (8) PACE (8)
YEAR SEQUENTIAL REVI5ION SHEARON HARRIS NUCLEAR POWER PLANT NUMIIER NUM eR UNIT ONE o s o o o 400 87 067 000 4 oF 04 TEXT //f more g>>ce /r //r/rerE r>>o //rior>>////IC Arm Sr)I/AEI (IT)
CORRECTIVE'CTIONS/ACTIONS TO PREVENT RECURRENCE (continued)
- 5. The leak detection monitor will be declared inoperable and appropriate Technical Specification actions taken when sampling is done rom its flow path.
NIIC PO/IM 840* <<U.S.OPO:18804424.538/455 (843)
CSEE>>
Carolina Power & Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 JAN 14 1988 File Number.'HF/10-13510C Letter Number'. HO-880003 (0)
U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 87-067-00 Gentl.emen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983.
Very truly yours,
/Zoic'J~~
R. A. Watson Vice President Harris Nuclear Project RAW:acm Enclosure cc'. Dr. J. Nelson Grace (NRC - RII)
Mr. B. Buckley (NRR)
Mr. G. Maxwell (NRC SHNPP)
MEM/LER-87"067/1/OS1