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| =Text= | | =Text= |
| {{#Wiki_filter:REGULATO'NFORMATION DISTRIBUTION STEM<BIDS)ACCESSION NBR: 8709280186 DOC.DATE: 87/09/21 NOTARIZED: | | {{#Wiki_filter:REGULATO 'NFORMATION DISTRIBUTION STEM <BIDS) |
| NO ,.FACI~: 50-400 Shearon Harris Nuclear Power Planti Unit ii Carolina AUTH.NAME AUTHOR AFFILIATION SCHWABENBAUER Carolina Poeer 5 Light Co.WATSON'.A.Carolina Poeer ic Light Co.REC IP.NAME REClPIENT AFFILIATION DOCKET 05000400
| | ACCESSION NBR: 8709280186 DOC. DATE: 87/09/21 NOTARIZED: NO DOCKET |
| | ,.FACI~: 50-400 Shearon Harris Nuclear Power Planti Unit ii Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION SCHWABENBAUER Carolina Poeer 5 Light Co. |
| | WATSON'. A. Carolina Poeer ic Light Co. |
| | REC IP. NAME REClPIENT AFFILIATION |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER 87-043-00: | | LER 87-043-00: on 870820> discovered that six manual isolation valves not j,nc luded in Oper ations Surveillance Test OST-1029. Caused bg personnel error. Test r evised to include valves in monthly verification of position. W/870'F21 ltr. |
| on 870820>discovered that six manual isolation valves not j,nc luded in Oper ations Surveillance Test OST-1029.Caused bg personnel error.Test r evised to include valves in monthly verification of position.W/870'F21 ltr.DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR~ENCL~SIZE: TITLE: 50.73 Licensee Event Report (LER)i Incident Rpt etc.NOTES: Application for permit reneeal Wi led.05000400 REC IP IENT ID CODE/NAME PD2-1 LA BUCKLEYiB INTERNAL: ACRS M ICHELSON AEOD/DQA AEOD/DSP/RQAB DEDRO NRR/DEST/CEB NRR/DEST/ICSB NRR/DEST/MTB NRR/DEBT/RSB NRR/DLPG/HFB NRR/DQEA/E*B NRR/DREP/RPB NRR/PMAS/ILRB RES DEPY GI RES/DE/EIB EXTERNAL: EG5G GROHi M LPDR NSIC HARRIS'COP IES LTTR ENCL 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 5 5 1 1 REC IP IENT ID CODE/NAME PD2-1 PD ACRS MOELLER AEOD/DSP/NAS AEOD/DSP/TPAB NRR/DEST/ADS NRR/DEBT/ELB NRR/DEST/MEB NRR/DEST/PSB NRR/DEST/SGB NRR/DLPG/GAB NRR/DREP/RAB NRR//SIB EG FIL 0&R ELFORDi J RGN2 FILE 01 H ST LOBBY WARD NRC PDR NSIC MAYST G COPIES LTTR ENCL 1 1 2 2 1'1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COP I ES REQUIRED: LTTR 44 ENCL 43 | | DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ~ ENCL ~ |
| ~w NRC Fore 308 (943)LICENSEE EVENT REPORT (LER)UA.NUCLEAR REGULATORY COMMISSION APPAOVED OMB NO.31504104 EXPIRES: 8/31/88 FACILITY NAME 0)SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKKT NUMBER (2)PAQK 31 0 5 0 0 0 4 0 O 1.OFQ 4 SIX OUTSIDE CONTAINMENT.
| | SIZE: |
| ISOLATION VALVES WERE OMITTED FROM MONTHLY POSITION C ECK DUE TO PERSONNEL ERROR IN PROCEDURE DEVELOPMENT.
| | TITLE: 50. 73 Licensee Event Report (LER)i Incident Rpt etc. |
| KVKNT DATE (5)MONTH DAY YEAR LEA NUMBFR (6)YEAR ggj SEQUENTIAL
| | NOTES: Application for permit reneeal Wi led. 05000400 REC IP IENT COP IES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 BUCKLEYiB 1 INTERNAL: ACRS M ICHELSON 1 ACRS MOELLER 2 2 AEOD/DQA 1 AEOD/DSP/NAS AEOD/DSP/RQAB 2 2 AEOD/DSP/TPAB 1' DEDRO 1 1 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEBT/ELB 1 NRR/DEST/ ICSB 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB NRR/DEST/PSB 1 NRR/DEBT/RSB 1 1 NRR/DEST/SGB 1 NRR/DLPG/HFB 1 NRR/DLPG/GAB 1 1 NRR/DQEA/E*B 1 NRR/DREP/RAB 1 NRR/DREP/RPB 2 2 NRR/ /SIB 1 1 NRR/PMAS/ ILRB 1 1 EG FIL 0& 1 1 RES DEPY GI 1 1 R ELFORDi J 1 RES/DE/EIB 1 RGN2 FILE 01 1 1 EXTERNAL: EG5G GROHi M 5 5 H ST LOBBY WARD LPDR 1 NRC PDR NSIC HARRIS' 1 NSIC MAYST G TOTAL NUMBER OF COP I ES REQUIRED: LTTR 44 ENCL 43 |
| 'VMSKR gYg'.REVISION 46 NVMSKR MONTH OAY YEAR REPORT DATE (7)DOCKtT NUMBEA(S)0 5 0 0 0 FACILITY NAMES OTHER FACILITIES INVOI.VED (S)~0 5 0 0 0 OPEAATINO MODE (9)POWER LEVEL (10)20A02(b)20A05(~)(1)(il 20A05(e)(I)(ii)
| |
| .20A05(~)(1)(iii)20A05(c)(I)(Ir)20A05(e)5048(cl(1) 50.38(c)l2)50.73(e)(2)li)50.73(e)121(ill 50,73(e)(2) lirl 50.73(el(2) lrl 50.73(e)(2)(rii)50.73(e)(2)(xiii)(A)50,73(e)(2)(rid)(B)
| |
| THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CF R g: (Check one or more of the follorflnFI (11)73.71(bl 73.71(cl OTHKR (Specify In Ahttrect heforr end ln Text, IIRC Form 3ESAJ NAME 20AOS(c)(I)(r)
| |
| D HW N 50.73(el(2)
| |
| Ail)LICENSEE CONTACT FOR THIS LEA (12)REGULATORY COMPLIANCE 50.73(e)(2)(xl AREa COOP.TELEPHONE NUMBER 62-2 COMPLETE ONE LINE FOR tACH COMPONENT FAILUAE DESCRIBEO IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC TURKR rrscco EPORTABLE'~ig+)'O NPROS 16'r CAUSE SYSTEM COMPONENT MANUFAC.TURER EPORTABLE A TO NPRDS r>.r.~SUPPLEMENTAL REPORT KXPECTED (IC)YEs Ilf yet, complete ExpEcTED sUshtlssloff DA TEI AdsTRAcT ILlmlt to Ie00 tpecet, I e., epproxlmeteiy fllteen tlnoleepece typewrinen llneel 118)ABSTRACT EXPECTED SUBMISSION DATE (15)MONTH DAY YEAR The plant was operating at 100 percent reactor power in Mode 1, Power Operation, on August 20, 1987.During a review of containment isolation valves, it was discovered at 1400 hours that six manual isolation valves were not included in Operations Surveillance Test (OST)-1029, Containment Penetration Outside Isolation Valve Verification, as required.OST-1029',satisfies.
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| Technical Specifications item 4.6.l.l.a for a 31-day verification that the valves are closed and locked.Upon'iscovery, a check of the six isolation valves was made and it was found that'll six valves were closed and locked as required.There is no indication that any of the valves have been opened since they were placed in their proper closed position prior to initial criticality of the plant.The cause of the event was personnel error in omitting the six isolation valves from OST-1029 for verification of their locked closed position as required.The immediate corrective action upon discovery was to verify that the six valves were in the closed and locked position as required, which they were.Action to prevent recurrence is that OST-1029 has been revised to include these six valves in the monthly verification of position.NRC Form Sdd This event is being violation of Technical 870'7)280l86 PDR ADOCK reported in accordance with lOCFR50.73(a)(2)(i)(B) as a Specifications Action item 4.6.1.1.a.
| |
| 870%1 0S000O00 rl PDR'r/
| |
| RC For)SISSSA (94)3)4 LICENSEE EV REPORT (LER)TEXT CONTINUATI U.S.NUCLEAR RECULATORY COMMISSION APPROVEO OMS NO.3(50M(04 EXPIRES: 8/31/88 FACILITY NAME (1)SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 TEXT/1/'mora 4/>>cv/4 vr/Vtrad, v44 add/dor>>/NRC Form 35543/(13)DOCKET NUMBER (3)LER NUMBER (8)SaavaNTIAL NUMaaR YEAR@g"o s o o o 4 00 87 0'ASVISION NVMSSR PACE (3)0 0 020F0 The plant was operating in Mode 1, Power Operation, at 100 percent reactor power on August 20, 1987.'lant personnel were implementing a program to identify and tag containment isolation valves[see LER-87-014-00 corrective action no.(1)j.This program involved a review of procedures, drawings, and a plant walkdown.During the review, it was discovered that the following six manual isolation valves were not included in Operations Surveillance Test (OST)"1029, Containment Penetration Outside Isolation Valve Verification, as required.1FP-355: Fire Protection water supply to containment.(EIIS:KP)1DW-63: Demineralized water supply to containment.(EIIS:KC)1SI-302 and 1SI-304: Drain valves off of the safety injection recirculation sump valve chambers.(EIIS:BP)1CT-103 and 1CT-106: Drain valves off of the containment spray recirculation sump valve chambers.(EIIS:BE)OST-1029 satisfies Technical Specifications item 4.6.1.1.a for a 31-day verification that the valves are closed and locked.Upon discovery that the six valves were missing from OST-1029's monthly position check, operations personnel immediately verified that the valves were in the closed and locked position as required.There is no indication that any of the valves have been opened since they were placed in their proper closed position prior to initial criticality of the plant.Plant conditions during and following this event was 100 percent reactor power in Mode 1, Power Operation.
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| OST-1029 has been revised to include the six valves which were omitted from the procedure.
| |
| NRC FORM 348A*U.S.OPO: I 988.0.834 538/455 J NRC FosiyrXSA (94)3)a s LICENSEE EYIO REPORT ILER)TEXT CONTINUATI U.S.NUCLEAR REQULATORY COMMISSION APPROVEO OMS NO.3150&)04 EXPIRES: 8/31/88 FACIUTY NAME (1)SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1.TEXT///mead 4Pddd 1I/sdv)dd, I/w a/s//I/dsas////I C hmi 3584'4/(IT)COCKET NUMBER (3)YEAR oo s7 LER NUMBER (6)I': "g>>SEOVENTIAL NVMSER 043 REVISION NUMSER-0 0 PACE (3)0 30F 0 4 Cause: The reason for the errors in the procedure was investigated.
| |
| The results of that investigation are as follows'.-
| |
| 1)1FP-355" In the original design, this valve had an air operator and was closed by a phase A isolation signal.The actuator was deleted by a subsequent change that was not reflected in the flow drawings until the spring of 19S7.Thus, the valve was not included in the early drafts of the procedure.
| |
| 2)1DW-63" In the initial draft of the procedure, this valve was included but with the incorrect"noun name".It was listed as"Primary Water Supply" vice the real title of"Demineralized Water Makeup".Since Primary Water Supply is not a containment isolation valve, 1DW-63 was deleted from the procedure.
| |
| 3)1SI-302, 1SI-304, 1CT-103, 1CT"106-The initial draft of the procedure did not include these valve chamber drain valves.The investigation concluded that these valves were omitted because they do not connect directly to containment.
| |
| In each case listed, the system valve lineup checklist which is separate from OST-1029 put the valves in the required locked closed position.The root cause of the event is personnel error in omitting the valves in the monthly surveillance test to check their position.~anal sis: Operation of plant components and systems and the health of the general public were unaffected by this event as the valves were in their proper position when checked'.In the case of 1FP-355 and 1DW-63 additional check valves are in series to provide redundant containment isolation capability.
| |
| Had the valves'been open during accident'conditions, the potential for additional containment releases to the Reactor Auxiliary Building is minimized.
| |
| In the case of the valve chamber drain valves, a chamber does not communicate directly with the containment.
| |
| The valve chamber serves to collect and isolate potential leakage from the containment sump isolation valves and from the pipe penetration to the containment sump.If these valves were left open the leakage would be released into the Reactor Auxiliary Building drains or leak-off holdup tanks.Releases into the Reactor Auxiliary Building would either be monitored by area radiation monitors andlor the Plant Vent Stack radiation monitors.This event is reportable in accordance with 10CFR50.73(a)(2)(i)(B) as a violation of Technical Specifications Action Item 4.6.1.1.a.
| |
| There have not been any similar events reported of this nature.NRC FORM SOdA*U.S.QPO:1988 0 834 538/455 RC For)drSSBA (34)3)'ICENSEE'EVIO REPORT (LER)TEXT CONTINUATI U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO.3150-0104 EXPIRES: 8/31/88 FACIUTY NAME (1)SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NUMSER l21 YEAR LER NUMBER (6)SEOUENTIAL NUMSER'.Ir r REVISION NUMSER PAOE (3)TEXT/((more 4/reoe/4/lr/rer/Iree////oee/HRC Ferrrr 3//543/(17)0 5 0 0 0 4 0 0 8 7 043 0 0 0 4 OF 0 4 Corrective Action: The valves were checked and verified to be in their proper position upon discovery that they were omitted from OST-1029.Action to Prevent Recurrence:
| |
| l.OST-1029 has been revised to include the six valves in the monthly surveillance test to check their position, and has been performed.
| |
| 2.A review of drawings for all systems with fluid*penetrations into the containment building was done to verify that OST-1029 is complete and has no additional errors.'NRC FORM SSSA*U.S.GPO:1988 0-824 538/45S
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|
| |
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| Carolina Power 5 Light Company gsgPC-0>(ggse~>~HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 SEP2 Ilg87 File Number,'HF/10-13510C Letter Number: HO-870498 (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 87-043-00 Gentlemen:
| | ~ w NRC Fore 308 UA. NUCLEAR REGULATORY COMMISSION (943) |
| In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. | | APPAOVED OMB NO. 31504104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITYNAME 0) DOCKKT NUMBER (2) PAQK 31 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 0 5 0 0 0 4 0 O 1.OFQ 4 SIX OUTSIDE CONTAINMENT. ISOLATION VALVES WERE OMITTED FROM MONTHLY POSITION C ECK DUE TO PERSONNEL ERROR IN PROCEDURE DEVELOPMENT. |
| 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, 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-87-043/1/OS1}} | | KVKNT DATE (5) LEA NUMBFR (6) REPORT DATE (7) OTHER FACILITIES INVOI.VED (S) ~ |
| | MONTH DAY YEAR YEAR ggj SEQUENTIAL |
| | 'VMSKR 46 gYg'. REVISION NVMSKR MONTH OAY YEAR FACILITYNAMES DOCKtT NUMBEA(S) 0 5 0 0 0 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CF R g: (Check one or more of the follorflnFI (11) |
| | OPEAATINO MODE (9) 20A02(b) 20A05(e) 50,73(e)(2) lirl 73.71(bl POWER 20A05( ~ ) (1)(il 5048(cl(1) 50.73(el(2) lrl 73.71(cl LEVEL (10) 20A05(e)(I)(ii) 50.38(c) l2) 50.73(e) (2) (rii) OTHKR (Specify In Ahttrect heforr end ln Text, IIRC Form |
| | . 20A05( ~ )(1)(iii) 50.73(e) (2) li) 50.73(e) (2) (xiii)(A) 3ESAJ 20A05(c ) (I ) (Ir) 50.73(e) 121(ill 50,73(e)(2)(rid)(B) 20AOS(c)(I)(r) 50.73(el(2) Ail) 50.73(e) (2)(xl LICENSEE CONTACT FOR THIS LEA (12) |
| | NAME TELEPHONE NUMBER AREa COOP. |
| | D HW N REGULATORY COMPLIANCE COMPLETE ONE LINE FOR tACH COMPONENT FAILUAE DESCRIBEO IN THIS REPORT (13) 62 -2 rrscco CAUSE SYSTEM COMPONENT MANUFAC EPORTABLE '~ig+) ' 'O CAUSE SYSTEM COMPONENT MANUFAC. EPORTABLE A TURKR NPROS 16 r TURER TO NPRDS r>. r. |
| | ~ SUPPLEMENTAL REPORT KXPECTED (IC) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15) |
| | YEs Ilfyet, complete ExpEcTED sUshtlssloff DA TEI AdsTRAcT ILlmlt to Ie00 tpecet, I e., epproxlmeteiy fllteen tlnoleepece typewrinen llneel 118) |
| | ABSTRACT The plant was operating at 100 percent reactor power in Mode 1, Power Operation, on August 20, 1987. During a review of containment isolation valves, at 1400 hours that six manual isolation valves were not included in Operations it was discovered Surveillance Test (OST)-1029, Containment Penetration Outside Isolation Valve Verification, as required. OST-1029 ',satisfies. Technical Specifications item 4.6.l.l.a for a 31-day verification that the valves are closed and locked. |
| | 'll Upon'iscovery, six a check of the six isolation valves was made and valves were closed and locked as required. There is no indication that any of the valves have been opened since they were placed in their proper closed it was found that position prior to initial criticality of the plant. |
| | The cause of the event was personnel error in omitting the six isolation valves from OST-1029 for verification of their locked closed position as required. |
| | The immediate corrective action upon discovery was to verify that the six valves were in the closed and locked position as required, which they were. |
| | Action to prevent recurrence is that OST-1029 has been revised to include these six valves in the monthly verification of position. |
| | This event is being reported in accordance with lOCFR50.73(a)(2)(i)(B) as a violation of Technical Specifications Action item 4.6.1.1.a. |
| | NRC Form Sdd 870'7)280 l 86 870%1 PDR ADOCK 0S000O00 rl |
| | 'r/ |
| | |
| | RC For)SISSSA U.S. NUCLEAR RECULATORY COMMISSION (94)3) 4 LICENSEE EV REPORT (LER) TEXT CONTINUATI APPROVEO OMS NO. 3(50M(04 EXPIRES: 8/31/88 FACILITYNAME (1) DOCKET NUMBER (3) PACE (3) |
| | LER NUMBER (8) |
| | YEAR SaavaNTIAL ASVISION |
| | @g NUMaaR NVMSSR SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 "o s o o o 4 00 87 0 |
| | ' |
| | 0 0 020F0 TEXT /1/'mora 4/>>cv /4 vr/Vtrad, v44 add/dor>>/NRC Form 35543/ (13) |
| | The plant was operating in Mode 1, Power Operation, at 100 percent reactor power on August 20, 1987. 'lant personnel were implementing a program to identify and tag containment isolation valves [see LER-87-014-00 corrective action no. (1)j. This program involved a review of procedures, drawings, and a plant walkdown. During the review, it was discovered that the following six manual isolation valves were not included in Operations Surveillance Test (OST)"1029, Containment Penetration Outside Isolation Valve Verification, as required. |
| | 1FP-355: Fire Protection water supply to containment. (EIIS:KP) 1DW-63: Demineralized water supply to containment. (EIIS:KC) 1SI-302 and 1SI-304: Drain valves off of the safety injection recirculation sump valve chambers. (EIIS:BP) 1CT-103 and 1CT-106: Drain valves off of the containment spray recirculation sump valve chambers. (EIIS:BE) |
| | OST-1029 satisfies Technical Specifications item 4.6.1.1.a for a 31-day verification that the valves are closed and locked. |
| | Upon discovery that the six valves were missing from OST-1029's monthly position check, operations personnel immediately verified that the valves were in the closed and locked position as required. There is no indication that any of the valves have been opened since they were placed in their proper closed position prior to initial criticality of the plant. |
| | Plant conditions during and following this event was 100 percent reactor power in Mode 1, Power Operation. |
| | OST-1029 has been revised to include the six valves which were omitted from the procedure. |
| | NRC FORM 348A *U.S.OPO: I 988.0.834 538/455 |
| | |
| | NRC FosiyrXSA s U.S. NUCLEAR REQULATORY COMMISSION (94)3) a LICENSEE EYIO REPORT ILER) TEXT CONTINUATI APPROVEO OMS NO. 3150&)04 EXPIRES: 8/31/88 FACIUTY NAME (1) COCKET NUMBER (3) LER NUMBER (6) PACE (3) |
| | YEAR I': SEOVENTIAL "g>> |
| | NVMSER REVISION NUMSER SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1. |
| | oo s7 043 0 0 0 30F 0 4 TEXT ///mead 4Pddd 1I /sdv)dd, I/w a/s//I/dsas////I C hmi 3584'4/ (IT) |
| | Cause: |
| | The reason for the errors in the procedure was investigated. The results of that investigation are as follows'.- |
| | : 1) 1FP-355 " In the original design, this valve had an air operator and was closed by a phase A isolation signal. The actuator was deleted by a subsequent change that was not reflected in the flow drawings until the spring of 19S7. Thus, the valve was not included in the early drafts of the procedure. |
| | : 2) 1DW-63 " In the initial draft of the procedure, this valve was included but with the incorrect "noun name". It was listed as "Primary Water Supply" vice the real title of "Demineralized Water Makeup". Since Primary Water Supply is not a containment isolation valve, 1DW-63 was deleted from the procedure. |
| | : 3) 1SI-302, 1SI-304, 1CT-103, 1CT"106 The initial draft of the procedure did not include these valve chamber drain valves. The investigation concluded that these valves were omitted because they do not connect directly to containment. |
| | In each case listed, the system valve lineup checklist which is separate from OST-1029 put the valves in the required locked closed position. |
| | The root cause of the event is personnel error in omitting the valves in the monthly surveillance test to check their position. |
| | ~anal sis: |
| | Operation of plant components and systems and the health of the general public were unaffected by this event as the valves were in their proper position when checked'. |
| | In the case of 1FP-355 and 1DW-63 additional check valves are in series to provide redundant containment isolation capability. Had the valves 'been open during accident 'conditions, the potential for additional containment releases to the Reactor Auxiliary Building is minimized. |
| | In the case of the valve chamber drain valves, a chamber does not communicate directly with the containment. The valve chamber serves to collect and isolate potential leakage from the containment sump isolation valves and from the pipe penetration to the containment sump. If these valves were left open the leakage would be released into the Reactor Auxiliary Building drains or leak-off holdup tanks. |
| | Releases into the Reactor Auxiliary Building would either be monitored by area radiation monitors andlor the Plant Vent Stack radiation monitors. |
| | This event is reportable in accordance with 10CFR50.73(a)(2)(i)(B) as a violation of Technical Specifications Action Item 4.6.1.1.a. |
| | There have not been any similar events reported of this nature. |
| | NRC FORM SOdA *U.S.QPO:1988 0 834 538/455 |
| | |
| | RC For)drSSBA U.S. NUCLEAR REGULATORY COMMISSION (34)3) |
| | 'ICENSEE'EVIO REPORT (LER) TEXT CONTINUATI APPROVEO OMS NO. 3150-0104 EXPIRES: 8/31/88 FACIUTY NAME (1) DOCKET NUMSER l21 LER NUMBER (6) PAOE (3) |
| | YEAR SEOUENTIAL REVISION SHEARON HARRIS NUCLEAR POWER PLANT NUMSER '.Ir r NUMSER UNIT 1 TEXT /((more 4/reoe /4 /lr/rer/ Iree ////oee/HRC Ferrrr 3//543/ (17) 0 5 0 0 0 4 0 0 8 7 043 0 0 0 4 OF 0 4 Corrective Action: |
| | The valves were checked and verified to be in their proper position upon discovery that they were omitted from OST-1029. |
| | Action to Prevent Recurrence: |
| | : l. OST-1029 has been revised to include the six valves in the monthly surveillance test to check their position, and has been performed. |
| | : 2. A review of drawings for all systems with fluid* penetrations into the containment building was done to verify that OST-1029 is complete and has no additional errors. |
| | 'NRC FORM SSSA *U.S.GPO:1988 0-824 538/45S |
| | |
| | gsgPC-0> |
| | Carolina Power 5 Light Company (ggse~> ~ |
| | HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 SEP2 I lg87 File Number,'HF/10-13510C Letter Number: HO-870498 (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 87-043-00 Gentlemen: |
| | In 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, 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-87-043/1/OS1}} |
|
|---|
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
REGULATO 'NFORMATION DISTRIBUTION STEM <BIDS)
ACCESSION NBR: 8709280186 DOC. DATE: 87/09/21 NOTARIZED: NO DOCKET
,.FACI~: 50-400 Shearon Harris Nuclear Power Planti Unit ii Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION SCHWABENBAUER Carolina Poeer 5 Light Co.
WATSON'. A. Carolina Poeer ic Light Co.
REC IP. NAME REClPIENT AFFILIATION
SUBJECT:
LER 87-043-00: on 870820> discovered that six manual isolation valves not j,nc luded in Oper ations Surveillance Test OST-1029. Caused bg personnel error. Test r evised to include valves in monthly verification of position. W/870'F21 ltr.
DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ~ ENCL ~
SIZE:
TITLE: 50. 73 Licensee Event Report (LER)i Incident Rpt etc.
NOTES: Application for permit reneeal Wi led. 05000400 REC IP IENT COP IES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 BUCKLEYiB 1 INTERNAL: ACRS M ICHELSON 1 ACRS MOELLER 2 2 AEOD/DQA 1 AEOD/DSP/NAS AEOD/DSP/RQAB 2 2 AEOD/DSP/TPAB 1' DEDRO 1 1 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEBT/ELB 1 NRR/DEST/ ICSB 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB NRR/DEST/PSB 1 NRR/DEBT/RSB 1 1 NRR/DEST/SGB 1 NRR/DLPG/HFB 1 NRR/DLPG/GAB 1 1 NRR/DQEA/E*B 1 NRR/DREP/RAB 1 NRR/DREP/RPB 2 2 NRR/ /SIB 1 1 NRR/PMAS/ ILRB 1 1 EG FIL 0& 1 1 RES DEPY GI 1 1 R ELFORDi J 1 RES/DE/EIB 1 RGN2 FILE 01 1 1 EXTERNAL: EG5G GROHi M 5 5 H ST LOBBY WARD LPDR 1 NRC PDR NSIC HARRIS' 1 NSIC MAYST G TOTAL NUMBER OF COP I ES REQUIRED: LTTR 44 ENCL 43
~ w NRC Fore 308 UA. NUCLEAR REGULATORY COMMISSION (943)
APPAOVED OMB NO. 31504104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITYNAME 0) DOCKKT NUMBER (2) PAQK 31 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 0 5 0 0 0 4 0 O 1.OFQ 4 SIX OUTSIDE CONTAINMENT. ISOLATION VALVES WERE OMITTED FROM MONTHLY POSITION C ECK DUE TO PERSONNEL ERROR IN PROCEDURE DEVELOPMENT.
KVKNT DATE (5) LEA NUMBFR (6) REPORT DATE (7) OTHER FACILITIES INVOI.VED (S) ~
MONTH DAY YEAR YEAR ggj SEQUENTIAL
'VMSKR 46 gYg'. REVISION NVMSKR MONTH OAY YEAR FACILITYNAMES DOCKtT NUMBEA(S) 0 5 0 0 0 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CF R g: (Check one or more of the follorflnFI (11)
OPEAATINO MODE (9) 20A02(b) 20A05(e) 50,73(e)(2) lirl 73.71(bl POWER 20A05( ~ ) (1)(il 5048(cl(1) 50.73(el(2) lrl 73.71(cl LEVEL (10) 20A05(e)(I)(ii) 50.38(c) l2) 50.73(e) (2) (rii) OTHKR (Specify In Ahttrect heforr end ln Text, IIRC Form
. 20A05( ~ )(1)(iii) 50.73(e) (2) li) 50.73(e) (2) (xiii)(A) 3ESAJ 20A05(c ) (I ) (Ir) 50.73(e) 121(ill 50,73(e)(2)(rid)(B) 20AOS(c)(I)(r) 50.73(el(2) Ail) 50.73(e) (2)(xl LICENSEE CONTACT FOR THIS LEA (12)
NAME TELEPHONE NUMBER AREa COOP.
D HW N REGULATORY COMPLIANCE COMPLETE ONE LINE FOR tACH COMPONENT FAILUAE DESCRIBEO IN THIS REPORT (13) 62 -2 rrscco CAUSE SYSTEM COMPONENT MANUFAC EPORTABLE '~ig+) ' 'O CAUSE SYSTEM COMPONENT MANUFAC. EPORTABLE A TURKR NPROS 16 r TURER TO NPRDS r>. r.
~ SUPPLEMENTAL REPORT KXPECTED (IC) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15)
YEs Ilfyet, complete ExpEcTED sUshtlssloff DA TEI AdsTRAcT ILlmlt to Ie00 tpecet, I e., epproxlmeteiy fllteen tlnoleepece typewrinen llneel 118)
ABSTRACT The plant was operating at 100 percent reactor power in Mode 1, Power Operation, on August 20, 1987. During a review of containment isolation valves, at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> that six manual isolation valves were not included in Operations it was discovered Surveillance Test (OST)-1029, Containment Penetration Outside Isolation Valve Verification, as required. OST-1029 ',satisfies. Technical Specifications item 4.6.l.l.a for a 31-day verification that the valves are closed and locked.
'll Upon'iscovery, six a check of the six isolation valves was made and valves were closed and locked as required. There is no indication that any of the valves have been opened since they were placed in their proper closed it was found that position prior to initial criticality of the plant.
The cause of the event was personnel error in omitting the six isolation valves from OST-1029 for verification of their locked closed position as required.
The immediate corrective action upon discovery was to verify that the six valves were in the closed and locked position as required, which they were.
Action to prevent recurrence is that OST-1029 has been revised to include these six valves in the monthly verification of position.
This event is being reported in accordance with lOCFR50.73(a)(2)(i)(B) as a violation of Technical Specifications Action item 4.6.1.1.a.
NRC Form Sdd 870'7)280 l 86 870%1 PDR ADOCK 0S000O00 rl
'r/
RC For)SISSSA U.S. NUCLEAR RECULATORY COMMISSION (94)3) 4 LICENSEE EV REPORT (LER) TEXT CONTINUATI APPROVEO OMS NO. 3(50M(04 EXPIRES: 8/31/88 FACILITYNAME (1) DOCKET NUMBER (3) PACE (3)
LER NUMBER (8)
YEAR SaavaNTIAL ASVISION
@g NUMaaR NVMSSR SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 "o s o o o 4 00 87 0
'
0 0 020F0 TEXT /1/'mora 4/>>cv /4 vr/Vtrad, v44 add/dor>>/NRC Form 35543/ (13)
The plant was operating in Mode 1, Power Operation, at 100 percent reactor power on August 20, 1987. 'lant personnel were implementing a program to identify and tag containment isolation valves [see LER-87-014-00 corrective action no. (1)j. This program involved a review of procedures, drawings, and a plant walkdown. During the review, it was discovered that the following six manual isolation valves were not included in Operations Surveillance Test (OST)"1029, Containment Penetration Outside Isolation Valve Verification, as required.
1FP-355: Fire Protection water supply to containment. (EIIS:KP) 1DW-63: Demineralized water supply to containment. (EIIS:KC) 1SI-302 and 1SI-304: Drain valves off of the safety injection recirculation sump valve chambers. (EIIS:BP) 1CT-103 and 1CT-106: Drain valves off of the containment spray recirculation sump valve chambers. (EIIS:BE)
OST-1029 satisfies Technical Specifications item 4.6.1.1.a for a 31-day verification that the valves are closed and locked.
Upon discovery that the six valves were missing from OST-1029's monthly position check, operations personnel immediately verified that the valves were in the closed and locked position as required. There is no indication that any of the valves have been opened since they were placed in their proper closed position prior to initial criticality of the plant.
Plant conditions during and following this event was 100 percent reactor power in Mode 1, Power Operation.
OST-1029 has been revised to include the six valves which were omitted from the procedure.
NRC FORM 348A *U.S.OPO: I 988.0.834 538/455
NRC FosiyrXSA s U.S. NUCLEAR REQULATORY COMMISSION (94)3) a LICENSEE EYIO REPORT ILER) TEXT CONTINUATI APPROVEO OMS NO. 3150&)04 EXPIRES: 8/31/88 FACIUTY NAME (1) COCKET NUMBER (3) LER NUMBER (6) PACE (3)
YEAR I': SEOVENTIAL "g>>
NVMSER REVISION NUMSER SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1.
oo s7 043 0 0 0 30F 0 4 TEXT ///mead 4Pddd 1I /sdv)dd, I/w a/s//I/dsas////I C hmi 3584'4/ (IT)
Cause:
The reason for the errors in the procedure was investigated. The results of that investigation are as follows'.-
- 1) 1FP-355 " In the original design, this valve had an air operator and was closed by a phase A isolation signal. The actuator was deleted by a subsequent change that was not reflected in the flow drawings until the spring of 19S7. Thus, the valve was not included in the early drafts of the procedure.
- 2) 1DW-63 " In the initial draft of the procedure, this valve was included but with the incorrect "noun name". It was listed as "Primary Water Supply" vice the real title of "Demineralized Water Makeup". Since Primary Water Supply is not a containment isolation valve, 1DW-63 was deleted from the procedure.
- 3) 1SI-302, 1SI-304, 1CT-103, 1CT"106 The initial draft of the procedure did not include these valve chamber drain valves. The investigation concluded that these valves were omitted because they do not connect directly to containment.
In each case listed, the system valve lineup checklist which is separate from OST-1029 put the valves in the required locked closed position.
The root cause of the event is personnel error in omitting the valves in the monthly surveillance test to check their position.
~anal sis:
Operation of plant components and systems and the health of the general public were unaffected by this event as the valves were in their proper position when checked'.
In the case of 1FP-355 and 1DW-63 additional check valves are in series to provide redundant containment isolation capability. Had the valves 'been open during accident 'conditions, the potential for additional containment releases to the Reactor Auxiliary Building is minimized.
In the case of the valve chamber drain valves, a chamber does not communicate directly with the containment. The valve chamber serves to collect and isolate potential leakage from the containment sump isolation valves and from the pipe penetration to the containment sump. If these valves were left open the leakage would be released into the Reactor Auxiliary Building drains or leak-off holdup tanks.
Releases into the Reactor Auxiliary Building would either be monitored by area radiation monitors andlor the Plant Vent Stack radiation monitors.
This event is reportable in accordance with 10CFR50.73(a)(2)(i)(B) as a violation of Technical Specifications Action Item 4.6.1.1.a.
There have not been any similar events reported of this nature.
NRC FORM SOdA *U.S.QPO:1988 0 834 538/455
RC For)drSSBA U.S. NUCLEAR REGULATORY COMMISSION (34)3)
'ICENSEE'EVIO REPORT (LER) TEXT CONTINUATI APPROVEO OMS NO. 3150-0104 EXPIRES: 8/31/88 FACIUTY NAME (1) DOCKET NUMSER l21 LER NUMBER (6) PAOE (3)
YEAR SEOUENTIAL REVISION SHEARON HARRIS NUCLEAR POWER PLANT NUMSER '.Ir r NUMSER UNIT 1 TEXT /((more 4/reoe /4 /lr/rer/ Iree ////oee/HRC Ferrrr 3//543/ (17) 0 5 0 0 0 4 0 0 8 7 043 0 0 0 4 OF 0 4 Corrective Action:
The valves were checked and verified to be in their proper position upon discovery that they were omitted from OST-1029.
Action to Prevent Recurrence:
- l. OST-1029 has been revised to include the six valves in the monthly surveillance test to check their position, and has been performed.
- 2. A review of drawings for all systems with fluid* penetrations into the containment building was done to verify that OST-1029 is complete and has no additional errors.
'NRC FORM SSSA *U.S.GPO:1988 0-824 538/45S
gsgPC-0>
Carolina Power 5 Light Company (ggse~> ~
HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 SEP2 I lg87 File Number,'HF/10-13510C Letter Number: HO-870498 (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 87-043-00 Gentlemen:
In 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, 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-87-043/1/OS1
