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| {{#Wiki_filter:ACCELERATED DILUTION DEMONS'TION SYSTEM REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RXDS)ACCESSION NBR: 9106190146 DOC.DATE: 91/06/14 NOTARIZED: | | {{#Wiki_filter:ACCELERATED DILUTION DEMONS'TION SYSTEM REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RXDS) |
| NO FACXL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION BARKER,D.W. | | ACCESSION NBR: 9106190146 DOC. DATE: 91/06/14 NOTARIZED: NO DOCKET g FACXL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION BARKER,D.W. Carolina Power & Light Co. |
| Carolina Power&Light Co.RICHEY,R.B. | | RICHEY,R.B. Carolina Power 6 Light Co. |
| Carolina Power 6 Light Co.RECIP.NAME RECIPIENT AFFILIATXON DOCKET g 05000400 | | RECIP.NAME RECIPIENT AFFILIATXON |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 91-013-00:on 910515,reactor trip occurred during performance of calibrs.Caused by personnel error.Need for effective communications stressed to applicable operations personnel.W/910614 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR (ENCL (SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:Application for permit renewal filed.05000400~RECIPIENT ID CODE/NAME PD2-1 LA MOZAFARI,B. | | LER 91-013-00:on 910515,reactor trip occurred during performance of calibrs.Caused by personnel error. Need for effective communications stressed to applicable operations personnel.W/910614 ltr. |
| INTERNAL: ACNW AEOD/DOA AEOD/ROAB/DSP NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB EXTERNAL: EGGG BRYCE,J.H NRC PDR NSIC POORE,W.COPXES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 1 1 1 1 2 2 1 1 1 1 1 1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD ACRS AEOD/DSP/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8D PLBBD1 REG FIL 02 FILE 01 L ST LOBBY WARD NSIC MURPHYiG A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS: | | DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR ( ENCL ( SIZE: |
| PLEASE HELP US TO REDUCE WARM CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPXES REQUIRED: LTTR 33 ENCL 33 V+4 I FORM 22 Carolina Power&Light Company HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 JUN 1 4 1991 Letter Number: HO-910081 (0)U.S.Nuclear Regulatory Commission A'ZTN: 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 91-013-00 Gentlemen: | | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted.
| | NOTES:Application for permit renewal filed. 05000400 ~ |
| 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 Or!ginal Sig'ned By R.8.R/CHEY R.B.Richey Vice President Harris Nuclear Project RBR:dmw Enclosure cc: Mr.S.D.Ebneter (NRC-RII)Ms.B.L.Mozafari (NRC-RII)Mr.J.E.Tedrow (NRC-SHNPP)MEM/LER91-013/1/OS1 9106190146 910614 PDR ADOCK 05000400 DAO
| | RECIPIENT COPXES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 MOZAFARI,B. 1 1 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 PLBBD1 1 1 NRR/DST/SRXB 8E 1 1 REG FIL 02 1 1 RES/DSIR/EIB 1 1 FILE 01 1 1 EXTERNAL: EGGG BRYCE,J. H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHYiG A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WARM CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPXES REQUIRED: LTTR 33 ENCL 33 |
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| NAC FORM 366 (64)9)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILERI APPROVED OMB NO.31504104 EXPIRES: 4I30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION AEOUESTt 50A)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P6301.U.S.NUCLEAR REGULATORY COMMISSION.
| | V+ |
| WASHINGTON.
| | 4 I |
| OC 20555.AND TO THE PAPERWORK AEDUCTION PROJECT (3(500104).
| | FORM 22 Carolina Power & Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 JUN 1 4 1991 Letter Number: HO-910081 (0) |
| OFFICE OF MANAGEMENT AND BUDGET.WASHINGTON, OC 20503.FACILITY NAME (I)DOCKET NUMBER (2)PA E 3 TITLE Iel s Nuclear Power Plant o 5 o o o 400~or0 3 EVENT DATE (5I LFR NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (6)MONTH OAY YEAR YEAR SEQUENTIAL
| | U.S. Nuclear Regulatory Commission A'ZTN: 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 91-013-00 Gentlemen: |
| ~NUMBER 4LVISK MONTH NUMSEII OAY YEAR FACILITY NAMES DOCKET NUMBER(S)0 5 0 0 0 0 5 1 5 919 1 013 0 006 14 91 0 5 0 0 0 OPERATING MODE (9I POWER LEVEL (10)20A02(b)20A06(e)0 I(l))0'(9)20.406(e)(1)(SII 20A05 I~)(I)(lv)20A06(el(1)(v)20.405(e)5036(cl (I)50.&(e)(2) 50.73(e)(2)(I)5073(eol)(N) 60.73(e)(2)(ill)LICENSEE CONTACT FOA THIS LFR (12)50.73(e)(1)
| | 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. |
| Av)60,73(e)(2)(v)EC.71(e)(1HvL'I 50.73(e)(1)(vill)(Al 50.73(~I(2)(vill)
| | Very truly yours Or! ginal Sig'ned By R. 8. R/CHEY R. B. Richey Vice President Harris Nuclear Project RBR:dmw Enclosure cc: Mr. S. D. Ebneter (NRC - RII) |
| (6)50.73(~)(21(el THIS REPORT IS SUBMITTED PURSUANT TO THE RLGVIREMENTS OF 10 CFR (Ir ICnect one or morr of trrr followinpl (11)73.7)(Ir)73.71(c)OTILE R fen-Jolty ln AtA.er telow rnrf ln Teer, ffRC Form 388AI NAME David W.Barker-Sr.Regulatory Compliance Specialist AREA CODE TELEPHONE NUMBER 2-2 0 COMPLETE ONE LINE FOA EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TVAEA EPORTABLE:
| | Ms. B. L. Mozafari (NRC - RII) |
| TO NPRDS yj CAUSE SYSTEM COMPONENT MANUFAC-TURER EPORTABL TO NPADS o'URN 4%R A SUPPLEMENTAL REPOAT EXPECTED (14)YES Ill yrr, complete EXPECTED$(f84tlSSIOff OATEl NO ABSTRACT fLlmlr to le00 rpecrt, f.r., rpproefmetrfy fiftern rlnplr.rpecr typewritten llnnl (ISI ABSTRACT: EXPECTED SUBMISSION DATE (15)4'MONTH DAY YEAR I In preparation for cooldown to repair a steam leak, Control Rod Shutdown Bank"C" was withdrawn fully and all other control rods were wiehdrawn six steps.Nuclear Instrument N-43 was-in the tripped c'o".edition fo'nstallation of monitoring instrumentation during post-refueling start-up testing.When surveillance test inseruments were disconnected following Reactor Coolant System resistance temperature detector testing, a spurious Overeemperature re)Temperature signal was generated causing a reactor trip.The potential for a reactor trip signal during restoration from the surveillance test had been previously discussed by Operations and Maintenance personnel, but the information was not communicated eo the shift operators. | | Mr. J. E. Tedrow (NRC - SHNPP) |
| The procedure governing ehe RTD surveillance test provided precautions during data acquisition, but failed eo identify the risk of generating a trip signal during restoration. | | MEM/LER91-013/1/OS1 9106190146 910614 PDR ADOCK 05000400 DAO |
| This event will be discussed with.maintenance and operations personnel and the surveillance tese procedure will be revised to include appropriate precautions during restoraeion. | | |
| NAC Form 365(669) | | NAC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (64)9) APPROVED OMB NO. 31504104 EXPIRES: 4I30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION AEOUESTt 50A) HRS. FORWARD LICENSEE EVENT REPORT ILERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P6301. U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. OC 20555. AND TO THE PAPERWORK AEDUCTION PROJECT (3(500104). OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON, OC 20503. |
| '\I eVRC FOAM 366 A (64)9)U.S.NUCI.EAA REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPAOVEO OMB NO.31500104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUESTI 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P430), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON. | | FACILITYNAME (I) DOCKET NUMBER (2) PA E 3 TITLE Iel s Nuclear Power Plant o 5 o o o 400 ~ or0 3 EVENT DATE (5I LFR NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (6) |
| OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3)SOD)04). | | MONTH OAY YEAR YEAR SEQUENTIAL NUMBER |
| OFFIC'E OF MANAGEMENT AND BUDGET;WASHINGTON, DC 20503.FACILITY NAME (1)Shearon Harris Nuclear Power Plant DOCKET NUMBER (2)VEAA LER NUMBER (6)SEOVENl'IAL NUMBER;.1~1I REVISION NUMBER PAGE (3)TEXT///mdIP 4P444/4 swtv/Nd, Il)4 4ddidone/P/RC FPmI 3664'll (IT)EVENT DESCRIPTION: | | ~ 4LVISK NUMSEII MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(S) 0 5 0 0 0 0 5 1 5 919 1 013 0 006 14 91 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE RLGVIREMENTS OF 10 CFR (Ir ICnect one or morr of trrr followinpl (11) |
| 0 5 0 0 0 4 0 0 9 0 1 3 0 0 02 O" 0 3 I On 5/15/91 the plant was in Mode 3 following a refueling outage, Nuclear Instrument N-43 had been placed in its tripped condition for installation of monitoring instrumentation (reactivity computer)during post-refueling startup testing.In order to repair a steam leak on Pressurizer Power Operated Relief Valve block valve 1RC-117, preparations were heing made for plant cooldown pe" procedure GP-007;The Reactor Trip Breakers were closed, Control Rod.Shutdown Bank"C" was fully withdrawn and all other rods were withdrawn 6 steps.Surveillance testing was also in progress for Reactor Coolant System (RCS)resistance temperature detector (RTD)cross-calibration in accordance with procedure MST-I0650.
| | MODE (9I 20A02(b) 20.405(e) 50.73(e)(1) Av) 73.7) (Ir) |
| MST-I0650 requires acquisition of data at several different RCS temperature plateaus with the precaution that a reactor trip signal may be generated when RTD leads are lifted for data acquisition. | | POWER 20A06(e)0 I(l) 5036(cl (I) 60,73(e) (2)(v) 73.71(c) |
| MST-I0650 requires opening the reactor trip breakers at each data acquisition plateau, but not during restoration. | | LEVEL (10) )0'(9) 50.&(e)(2) EC.71(e)(1HvL'I OTILE R fen-Jolty ln AtA.er telow rnrf ln Teer, ffRC Form 20.406(e)(1) (SII 50.73(e)(2) (I) 50.73(e)(1)(vill) (Al 388AI 20A05 I~ ) (I ) (lv) 5073(eol)(N) 50.73( ~ I(2)(vill)(6) 20A06(el(1) (v) 60.73(e) (2) (ill) 50.73( ~ ) (21(el LICENSEE CONTACT FOA THIS LFR (12) |
| Although the restoration section of MST-I0650 does not require that the reactor trip breakers be opened, it does require that restoration be performed one RTD at a time.At the 5/15/91 morning outage meeting, maintenance personnel requested that the reactor trip breakers be.left open during the restoration section of MST-I0650. | | NAME TELEPHONE NUMBER AREA CODE David W. Barker Sr. Regulatory Compliance Specialist 2 2 0 COMPLETE ONE LINE FOA EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| This was to facilitate the timely performance by allowing restoration actions on more than one RTD at a time.The Shift Supervisor agreed to leave the Reactor Trip Breakers open, but failed to communicate this to the on-shift operators. | | SYSTEM COMPONENT MANUFAC. EPORTABLE: MANUFAC- EPORTABL CAUSE TVAEA TO NPRDS CAUSE SYSTEM COMPONENT yj TURER TO NPADS o 'URN 4' |
| Data acquisition had been successfully completed and the test instrumentation was being removed (on more than one RTD)when a spurious Overtemperature temperature trip signal was generated resulting in a reactor trip.There has been one similar event involving a reactor trip during performance of instrument calibrations as reported in LER 89-005-00. | | 4% R A SUPPLEMENTAL REPOAT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15) |
| CAUSE: The cause of'his event was personnel error.This Reactor Protection System actuation was caused.by the simultaneous performance of plant cooldown, which required the Reactor Trip Breakers to be closed, and restoration from MST-I0650 concurrent with one channel of N-43 in the trip condition. | | YES Ill yrr, complete EXPECTED $ (f84tlSSIOff OATEl NO ABSTRACT fLlmlr to le00 rpecrt, f.r., rpproefmetrfy fiftern rlnplr.rpecr typewritten llnnl (ISI ABSTRACT: |
| Maintenance personnel performing the surveillance testing failed to follow the procedural requirement for restoring one RTD at a time.The potential for a reactor trip signal during restoration was communicated to'the Shift Supervisor, but this information was not discussed with the on-shift operators. | | I In preparation for cooldown to repair a steam leak, Control Rod Shutdown Bank "C" was withdrawn fully and all other control rods were wiehdrawn six steps. Nuclear Instrument N-43 was -in the tripped c'o".edition fo 'nstallation of monitoring instrumentation during post-refueling start-up testing. When surveillance test inseruments were disconnected following Reactor Coolant System resistance temperature detector testing, a spurious Overeemperature re)Temperature signal was generated causing a reactor trip. The potential for a reactor trip signal during restoration from the surveillance test had been previously discussed by Operations and Maintenance personnel, but the information was not communicated eo the shift operators. The procedure governing ehe RTD surveillance test provided precautions during data acquisition, but failed eo identify the risk of generating a trip signal during restoration. This event will be discussed with. maintenance and operations personnel and the surveillance tese procedure will be revised to include appropriate precautions during restoraeion. |
| ICRC FOAM 366A (689)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVED 6MB NO.31500104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REGUESTI 500 HRS.FORWARD COMMENTS AEGARDING BURDEN ESTIMATE TO THE RECORDS AND AEPOATS MANAGEMENT BRANCH (F430), U.S.NUCLEAR REGULATOR Y COMMISSION, WASHINGTON. | | NAC Form 365(669) |
| DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31600104). | | |
| OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAME 0)DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)Shearon Harris Nuclear Power Plant TEXT/ll more 4/Mce/4 rer/Ir/red. | | '\I eVRC FOAM 366 A U.S. NUCI.EAA REGULATORY COMMISSION APPAOVEO OMB NO. 31500104 (64) 9) |
| ore eddro'orN/I/IC Form 3664'4/(17)0 5 0 0 0 4 0 0 YEAR QVc'1 SEQUENTIAL A'6: NUMBER 0 1 3 REVISION NUMBER 00 03 OF 0 3 SAFETY SIGNIFICANCE: | | EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUESTI 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P430), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3)SOD)04). OFFIC'E OF MANAGEMENTAND BUDGET;WASHINGTON, DC 20503. |
| There were no significant safety consequences as a result of this event..A11 safety systems responded as required.This event is reportable as an actuation of the reactor protection and engineered safeguards systems per 10CFR50.73(a)(2)(iv). | | FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| CORRECTIVE ACTIONS: MST-I0650 will be revised prior to next use to clarify restoration requirements. | | VEAA SEOVENl'IAL ;.1~1I REVISION NUMBER NUMBER Shearon Harris Nuclear Power Plant 0 5 0 0 0 4 0 0 9 0 1 3 0 0 02 O" 0 3 TEXT /// mdIP 4P444 /4 swtv/Nd, Il)4 4ddidone/P/RC FPmI 3664'll (IT) |
| 2.The requirement that surveillance testing be performed only in strict accordance with approved written procedures will be re-emphasized to applicable maintenance personnel. | | EVENT DESCRIPTION: |
| 3.The need for effective communications will be stressed to applicable operations personnel. | | I On 5/15/91 the plant was in Mode 3 following a refueling outage, Nuclear Instrument N-43 had been placed in its tripped condition for installation of monitoring instrumentation (reactivity computer) during post-refueling startup testing. |
| 4.An evaluation will be performed on possible alternatives to the reactivity computer which do not require N-43 to be placed in the tripped condition during post-refueling start-.up. | | In order to repair a steam leak on Pressurizer Power Operated Relief Valve block valve 1RC-117, preparations were heing made for plant cooldown pe" procedure GP-007; The Reactor Trip Breakers were closed, Control Rod. Shutdown Bank "C" was fully withdrawn and all other rods were withdrawn 6 steps. Surveillance testing was also in progress for Reactor Coolant System (RCS) resistance temperature detector (RTD) cross-calibration in accordance with procedure MST-I0650. MST-I0650 requires acquisition of data at several different RCS temperature plateaus with the precaution that a reactor trip signal may be generated when RTD leads are lifted for data acquisition. MST-I0650 requires opening the reactor trip breakers at each data acquisition plateau, but not during restoration. Although the restoration section of MST-I0650 does not require that the reactor trip breakers be opened, it does require that restoration be performed one RTD at a time. At the 5/15/91 morning outage meeting, maintenance personnel requested that the reactor trip breakers be |
| EIIS CODE INFORMATION: | | .left open during the restoration section of MST-I0650. This was to facilitate the timely performance by allowing restoration actions on more than one RTD at a time. |
| | The Shift Supervisor agreed to leave the Reactor Trip Breakers open, but failed to communicate this to the on-shift operators. Data acquisition had been successfully completed and the test instrumentation was being removed (on more than one RTD) when a spurious Overtemperature temperature trip signal was generated resulting in a reactor trip. |
| | There has been one similar event involving a reactor trip during performance of instrument calibrations as reported in LER 89-005-00. |
| | CAUSE: |
| | The cause of'his event was personnel error. This Reactor Protection System actuation was caused .by the simultaneous performance of plant cooldown, which required the Reactor Trip Breakers to be closed, and restoration from MST-I0650 concurrent with one channel of N-43 in the trip condition. Maintenance personnel performing the surveillance testing failed to follow the procedural requirement for restoring one RTD at a time. The potential for a reactor trip signal during restoration was communicated to 'the Shift Supervisor, but this information was not discussed with the on-shift operators. |
| | |
| | ICRC FOAM 366A U.S. NUCLEAR REGULATORY COMMISSION (689) APPROVED 6MB NO. 31500104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILERI INFORMATION COLLECTION REGUESTI 500 HRS. FORWARD COMMENTS AEGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND AEPOATS MANAGEMENT BRANCH (F430), U.S. NUCLEAR REGULATOR Y COMMISSION, WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31600104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, OC 20503. |
| | FACILITY NAME 0) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | YEAR QVc' SEQUENTIAL A'6: REVISION NUMBER NUMBER Shearon Harris Nuclear Power Plant TEXT /llmore 4/Mce /4 rer/Ir/red. ore eddro'orN/I/IC Form 3664'4/ (17) 0 5 0 0 0 4 0 0 1 0 1 3 00 03 OF 0 3 SAFETY SIGNIFICANCE: |
| | There were no significant safety consequences as a result of this event..A11 safety systems responded as required. |
| | This event is reportable as an actuation of the reactor protection and engineered safeguards systems per 10CFR50.73(a)(2)(iv). |
| | CORRECTIVE ACTIONS: |
| | MST-I0650 will be revised prior to next use to clarify restoration requirements. |
| | : 2. The requirement that surveillance testing be performed only in strict accordance with approved written procedures will be re-emphasized to applicable maintenance personnel. |
| | : 3. The need for effective communications will be stressed to applicable operations personnel. |
| | : 4. An evaluation will be performed on possible alternatives to the reactivity computer which do not require N-43 to be placed in the tripped condition during post-refueling start-.up. |
| | EIIS CODE INFORMATION: |
| N/A}} | | N/A}} |
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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
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Text
ACCELERATED DILUTION DEMONS'TION SYSTEM REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RXDS)
ACCESSION NBR: 9106190146 DOC. DATE: 91/06/14 NOTARIZED: NO DOCKET g FACXL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION BARKER,D.W. Carolina Power & Light Co.
RICHEY,R.B. Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATXON
SUBJECT:
LER 91-013-00:on 910515,reactor trip occurred during performance of calibrs.Caused by personnel error. Need for effective communications stressed to applicable operations personnel.W/910614 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR ( ENCL ( SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:Application for permit renewal filed. 05000400 ~
RECIPIENT COPXES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 MOZAFARI,B. 1 1 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 PLBBD1 1 1 NRR/DST/SRXB 8E 1 1 REG FIL 02 1 1 RES/DSIR/EIB 1 1 FILE 01 1 1 EXTERNAL: EGGG BRYCE,J. H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHYiG A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WARM CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPXES REQUIRED: LTTR 33 ENCL 33
V+
4 I
FORM 22 Carolina Power & Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 JUN 1 4 1991 Letter Number: HO-910081 (0)
U.S. Nuclear Regulatory Commission A'ZTN: 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 91-013-00 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 Or! ginal Sig'ned By R. 8. R/CHEY R. B. Richey Vice President Harris Nuclear Project RBR:dmw Enclosure cc: Mr. S. D. Ebneter (NRC - RII)
Ms. B. L. Mozafari (NRC - RII)
Mr. J. E. Tedrow (NRC - SHNPP)
MEM/LER91-013/1/OS1 9106190146 910614 PDR ADOCK 05000400 DAO
NAC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (64)9) APPROVED OMB NO. 31504104 EXPIRES: 4I30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION AEOUESTt 50A) HRS. FORWARD LICENSEE EVENT REPORT ILERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P6301. U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. OC 20555. AND TO THE PAPERWORK AEDUCTION PROJECT (3(500104). OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON, OC 20503.
FACILITYNAME (I) DOCKET NUMBER (2) PA E 3 TITLE Iel s Nuclear Power Plant o 5 o o o 400 ~ or0 3 EVENT DATE (5I LFR NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (6)
MONTH OAY YEAR YEAR SEQUENTIAL NUMBER
~ 4LVISK NUMSEII MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(S) 0 5 0 0 0 0 5 1 5 919 1 013 0 006 14 91 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE RLGVIREMENTS OF 10 CFR (Ir ICnect one or morr of trrr followinpl (11)
MODE (9I 20A02(b) 20.405(e) 50.73(e)(1) Av) 73.7) (Ir)
POWER 20A06(e)0 I(l) 5036(cl (I) 60,73(e) (2)(v) 73.71(c)
LEVEL (10) )0'(9) 50.&(e)(2) EC.71(e)(1HvL'I OTILE R fen-Jolty ln AtA.er telow rnrf ln Teer, ffRC Form 20.406(e)(1) (SII 50.73(e)(2) (I) 50.73(e)(1)(vill) (Al 388AI 20A05 I~ ) (I ) (lv) 5073(eol)(N) 50.73( ~ I(2)(vill)(6) 20A06(el(1) (v) 60.73(e) (2) (ill) 50.73( ~ ) (21(el LICENSEE CONTACT FOA THIS LFR (12)
NAME TELEPHONE NUMBER AREA CODE David W. Barker Sr. Regulatory Compliance Specialist 2 2 0 COMPLETE ONE LINE FOA EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
SYSTEM COMPONENT MANUFAC. EPORTABLE: MANUFAC- EPORTABL CAUSE TVAEA TO NPRDS CAUSE SYSTEM COMPONENT yj TURER TO NPADS o 'URN 4'
4% R A SUPPLEMENTAL REPOAT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15)
YES Ill yrr, complete EXPECTED $ (f84tlSSIOff OATEl NO ABSTRACT fLlmlr to le00 rpecrt, f.r., rpproefmetrfy fiftern rlnplr.rpecr typewritten llnnl (ISI ABSTRACT:
I In preparation for cooldown to repair a steam leak, Control Rod Shutdown Bank "C" was withdrawn fully and all other control rods were wiehdrawn six steps. Nuclear Instrument N-43 was -in the tripped c'o".edition fo 'nstallation of monitoring instrumentation during post-refueling start-up testing. When surveillance test inseruments were disconnected following Reactor Coolant System resistance temperature detector testing, a spurious Overeemperature re)Temperature signal was generated causing a reactor trip. The potential for a reactor trip signal during restoration from the surveillance test had been previously discussed by Operations and Maintenance personnel, but the information was not communicated eo the shift operators. The procedure governing ehe RTD surveillance test provided precautions during data acquisition, but failed eo identify the risk of generating a trip signal during restoration. This event will be discussed with. maintenance and operations personnel and the surveillance tese procedure will be revised to include appropriate precautions during restoraeion.
NAC Form 365(669)
'\I eVRC FOAM 366 A U.S. NUCI.EAA REGULATORY COMMISSION APPAOVEO OMB NO. 31500104 (64) 9)
EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUESTI 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P430), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3)SOD)04). OFFIC'E OF MANAGEMENTAND BUDGET;WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
VEAA SEOVENl'IAL ;.1~1I REVISION NUMBER NUMBER Shearon Harris Nuclear Power Plant 0 5 0 0 0 4 0 0 9 0 1 3 0 0 02 O" 0 3 TEXT /// mdIP 4P444 /4 swtv/Nd, Il)4 4ddidone/P/RC FPmI 3664'll (IT)
EVENT DESCRIPTION:
I On 5/15/91 the plant was in Mode 3 following a refueling outage, Nuclear Instrument N-43 had been placed in its tripped condition for installation of monitoring instrumentation (reactivity computer) during post-refueling startup testing.
In order to repair a steam leak on Pressurizer Power Operated Relief Valve block valve 1RC-117, preparations were heing made for plant cooldown pe" procedure GP-007; The Reactor Trip Breakers were closed, Control Rod. Shutdown Bank "C" was fully withdrawn and all other rods were withdrawn 6 steps. Surveillance testing was also in progress for Reactor Coolant System (RCS) resistance temperature detector (RTD) cross-calibration in accordance with procedure MST-I0650. MST-I0650 requires acquisition of data at several different RCS temperature plateaus with the precaution that a reactor trip signal may be generated when RTD leads are lifted for data acquisition. MST-I0650 requires opening the reactor trip breakers at each data acquisition plateau, but not during restoration. Although the restoration section of MST-I0650 does not require that the reactor trip breakers be opened, it does require that restoration be performed one RTD at a time. At the 5/15/91 morning outage meeting, maintenance personnel requested that the reactor trip breakers be
.left open during the restoration section of MST-I0650. This was to facilitate the timely performance by allowing restoration actions on more than one RTD at a time.
The Shift Supervisor agreed to leave the Reactor Trip Breakers open, but failed to communicate this to the on-shift operators. Data acquisition had been successfully completed and the test instrumentation was being removed (on more than one RTD) when a spurious Overtemperature temperature trip signal was generated resulting in a reactor trip.
There has been one similar event involving a reactor trip during performance of instrument calibrations as reported in LER 89-005-00.
CAUSE:
The cause of'his event was personnel error. This Reactor Protection System actuation was caused .by the simultaneous performance of plant cooldown, which required the Reactor Trip Breakers to be closed, and restoration from MST-I0650 concurrent with one channel of N-43 in the trip condition. Maintenance personnel performing the surveillance testing failed to follow the procedural requirement for restoring one RTD at a time. The potential for a reactor trip signal during restoration was communicated to 'the Shift Supervisor, but this information was not discussed with the on-shift operators.
ICRC FOAM 366A U.S. NUCLEAR REGULATORY COMMISSION (689) APPROVED 6MB NO. 31500104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILERI INFORMATION COLLECTION REGUESTI 500 HRS. FORWARD COMMENTS AEGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND AEPOATS MANAGEMENT BRANCH (F430), U.S. NUCLEAR REGULATOR Y COMMISSION, WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31600104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, OC 20503.
FACILITY NAME 0) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
YEAR QVc' SEQUENTIAL A'6: REVISION NUMBER NUMBER Shearon Harris Nuclear Power Plant TEXT /llmore 4/Mce /4 rer/Ir/red. ore eddro'orN/I/IC Form 3664'4/ (17) 0 5 0 0 0 4 0 0 1 0 1 3 00 03 OF 0 3 SAFETY SIGNIFICANCE:
There were no significant safety consequences as a result of this event..A11 safety systems responded as required.
This event is reportable as an actuation of the reactor protection and engineered safeguards systems per 10CFR50.73(a)(2)(iv).
CORRECTIVE ACTIONS:
MST-I0650 will be revised prior to next use to clarify restoration requirements.
- 2. The requirement that surveillance testing be performed only in strict accordance with approved written procedures will be re-emphasized to applicable maintenance personnel.
- 3. The need for effective communications will be stressed to applicable operations personnel.
- 4. An evaluation will be performed on possible alternatives to the reactivity computer which do not require N-43 to be placed in the tripped condition during post-refueling start-.up.
EIIS CODE INFORMATION:
N/A