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| {{#Wiki_filter:CATEGORY 1 REGULATO Y INFORMATION DISTRIBUTION STEM (RIDS)"~ACCESGION MBR:9708060308 DOC.DATE: 97/07/31 NOTARIZED: | | {{#Wiki_filter:CATEGORY 1 REGULATO Y INFORMATION DISTRIBUTION STEM (RIDS) |
| NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME-=-., AUTHOR AFFILIATION ELLINGTON,M. | | "~ |
| .Carolina'ower
| | ACCESGION MBR:9708060308 DOC.DATE: 97/07/31 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME -= ., AUTHOR AFFILIATION ELLINGTON,M. . |
| &Light Co.DONAHUE,J.W. | | Carolina'ower & Light Co. |
| , Carolina Power&Light Co.RECIP.NAME RECIPIENT'AFFILIATION DOCKET 05000400 05000400 g 0- | | DONAHUE,J.W. , Carolina Power & Light Co. |
| | RECIP.NAME RECIPIENT 'AFFILIATION |
|
| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 97-018-00:on 970701,determined that plant procedures had not received proper reviews&approvals. | | 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.Involved site mgt counseled.W/970731 ltr. |
| Caused by failure to comply-w/plant administrative procedure AP-006.Involved site mgt counseled.W/970731 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL: SIZE:.TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.V NOTES:Application for permit renewal filed.RECIPIENT ID CODE/NAME PD2,.-1 PD INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR COPIES LTTR ENCL 1-1 1 1 1 1 1 1 1 1=1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME ROONEYEV RAB ILE CENTE NR E EELB, NRR/DRCH/HHFB | | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL : SIZE: |
| :.NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2 FILE 01 LITCO BRYCEgJ H NOAC QUEENEREDS 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 R 0 NOTE TO ALL"RZDS" RECZPZENTSZ PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK/ROOM OWPN SD-5(EXT.415-2083)TO ELZMZNATE YOUR NAME PROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEEDl FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25 Carolina Power&Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 JUL 31 1997 U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 Serial: HNP-97-.143 10CFR50.73 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1-DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 97-018-00 Sir or Madam:~g'In accordance with Title",10.to the.Code of Federal Regulations,lthe enclosed Licensee Event Report is submitted.-'This
| | .TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| 'report de'scribes operation with procedures that were not properly reviewed and approved.Sincerely, J.W.Donahue Director of Site Operations Harris Plant MSE/mse~6M'nclosure~~GG ,c: ':.'r,'-J.'!B.:"-Brady (HNP Senior.NRC:Resident)'.';;: | | V NOTES:Application for permit renewal filed. 05000400 g 0 |
| ".:.--..''::: | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME PD2,.-1 PD LTTR ENCL 1- 1 ID CODE/NAME ROONEYEV 1, LTTR ENCL 1 |
| .-:;...:;,,: | | R INTERNAL: ACRS 1 1 RAB 2 2 AEOD/SPD/RRAB 1 1 ILE CENTE 1 1 NRR/DE/ECGB 1 1 NR E EELB, 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB =1 1 :.NRR/DRCH/HOLB 1 .1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DET/EIB 1 1 RGN2 FILE 01 1 1 0 |
| .;.:.i."..:.:..'.:Mr L'.A.Reyes'(NRC Regional Administrator;.Region:11);:: | | EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCEgJ H 1 1 NOAC POORE,W. 1 1 NOAC QUEENEREDS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RZDS" RECZPZENTSZ PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK/ |
| Mr.V.L.Rooney (NRC-NRR Project Manager)IIIIUlllllllllllHIIIIIIIIUILIUIIU 5413 Shearon Harris Road New Hill NC j~ | | ROOM OWPN SD-5(EXT. 415-2083) TO ELZMZNATE YOUR NAME PROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEEDl FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25 |
| NRC FORM 366, H-35)r e U.S.'NUCLEAR REGULATORY COMMISSION LXCENSEE EVENT REPORT (LER){SBB reverse for required number of digits/characters for each block)APPROVED BY OMB NO.31 500104 EXPIRES 0430lss ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATOR INFORMATION COLLECTION REOUEsnf 50.0 HRS.REPORTED LESSONS LEARNE ARE INCORPORATED INTO THE UCENSING PROCESS AND FED BACK TO INDUSTRY FORWARD COhNFMS REGARDUIG BURDEN ESTIMATE TO THE INFORMATION AN RECORDS MANAGEMENT BRANCH IT41 F33), U.S.NUCLEAR REGULATOR COMMISSION, WASIENGTON DC 205550001 ANDTO THE PAPERWORK REDUCllo PROJECT (31500104), OFFlCE OF MANAGIJJtENT AND BUDGET, WASHINGTON, 209XL FACIUTY NAME (I)Shaaron Harris Nuc(ear Plant, Unit-1 TITLE I4)Operation with procedures not properly reviewed and approved DOCKET NUMBER{2)50-400 PAGE (3)1 OF3 MBNTN DAY YEAR 07 01 97 OPERATING MODE{9)POWER LEVEL (10)SEDUENTIAL REVISION NUMBER NUMBER 97-018-00 20.2201(b) 20.2203(a) | | |
| (2)(i)20.2203(a) l2)(iii)20.2203(a) | | Carolina Power & Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 JUL 31 1997 U.S. Nuclear Regulatory Commission Serial: HNP-97-.143 ATTN: NRC Document Control Desk 10CFR50.73 Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1-DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 97-018-00 Sir or Madam: |
| (2)(iv)DAY'YEAR 07 31 97 20.2203(a) | | ~ g In accordance with Title",10.to the. Code of Federal Regulations,lthe enclosed Licensee Event Report is submitted.-'This 'report de'scribes operation with procedures that were not properly reviewed and approved. |
| (3)(ii)60.36{c)l1)60.36(c)l2)20.2203(a) | | Sincerely, J. W. Donahue Director of Site Operations Harris Plant MSE/mse |
| (2)(v)FACILITY NAME FACILITY NAME 60.73(a)l2)(i)60.73(a)(2)
| | ~6M 'nclosure |
| {iii)60.73(a)(2)(v)60.73(a)(2)(vii)DOCKET NUMBER DOCKET NUMBER 05000 60.73(a)(2)(viii)73.71 OTHER Specify In Abstract below or in NRC Form 366A NAME Mark Ellington Senior Analyst-Licensing TELEPHONE NUMBER (Inoerde Ares Code)(919)362-2057 CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPROS CAUSE SYSTEM MANUFACTURER REPORTABLE TO NPRDS YES{If yes, complete EXPECTED SUBMISSION DATE).X NO EXPECTED SUBMISSION DATE{16)MONTH DA YEAR ABSTRACT{Limit to 1400 spaces, i.e., approximately 16 single-spaced typewritten lines){16)On July 1, 1997, with the plant at approximately 100%power in Mode 1, an investigation determined that some Harris Nuclear Plant (HNP)procedures had not received proper reviews and approvals.
| | ~ ~ GG |
| Specifically, approximately 150 temporary procedure changes affecting over 100 procedures were not reviewed and approved within 14 days in accordance with Technical Specification (TS)6.8.3 and 6.5.1.Additionally, many of these procedures were used to operate the plant without the required TS review and approval.The cause of this TS violation is failure to comply with plant administrative procedure AP-006.Contributing factors were: (1)A misunderstanding of the basis of the requirements in the AP-006 by site personnel. | | ,c: ':.'r,'- J.'! B.:"- Brady (HNP Senior. NRC:Resident)'.';;: ".:. --..''::: .-:;...:;,,: .;.:.i." ..:.:. |
| (2)Inadequate management involvement once the problem was brought to management's attention as evidenced by not stopping the Handwritten Revision non-intent process once a problem was identified. | | .'.:Mr L'. A. Reyes'(NRC Regional Administrator;.Region:11);:: |
| The following corrective actions have been performed: | | Mr. V. L. Rooney (NRC - NRR Project Manager) |
| (1)HNP procedures identified as deficient have been properly reviewed and approved in accordance with TS, (2)Involved Site Management has been counseled that procedure non-compliance must be prevented and promptly corrected upon discovery, (3)Communications to appropriate site personnel have been made on how AP.-006 implements TS requirements, (4)AP-006 has been revised to clarify implementation of TS requirements and (5)The Supervisor-Operations Support, involved in this event, has been disciplined by Plant Management A comprehensive review of the procedure change and review process will be completed by 9/1/97. | | IIIIUlllllllllllHIIIIIIIIUILIUIIU 5413 Shearon Harris Road New Hill NC |
| RC FORM 3EEA 495)LICENSEE EVENT BEPOBT (LEB)TEXT CONTINUATION ILS.NUCLEAR REGULATORT COMMISBIO FACILITY NAME (I)Shearon Harris Nuclear Plant-Unit 1 EXT Pinero oOoalt ooqoind, mooiRRoooorooyiieolHRC Faao3GRRl I)7)DOCKET 50400 LER NUMBER IB)BEOUENTUL REVISION NUMBER NUMBER 97-018-00 PAGEIB)2 OF 3 VENT DESCRIPTION: | | |
| n July 1, 1997 with the plant at approximately 100%power in mode 1, an investigation determined some HNP procedures ad not received the required TS reviews and approvals. | | j~ |
| Specifically, approximately 150 temporary procedure changes fecting over 100 procedures were not reviewed and approved within 14 days in accordance with TS 6.8.3.Additionally, any of these procedures were used to operate the plant without the required TS review and approval.e plant definition for a temporary procedure change is a change that will eventually be removed from the procedure. | | NRC FORM 366, e |
| ANSI 18.7 definition is somewhat different in that temporary procedure changes could be incorporated, as appropriate, into the ext revision to the procedure. | | U.S.'NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 31 500104 EXPIRES 0430lss H-35) r ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATOR INFORMATIONCOLLECTION REOUEsnf 50.0 HRS. REPORTED LESSONS LEARNE ARE INCORPORATED INTO THE UCENSING PROCESS AND FED BACK TO INDUSTRY LXCENSEE EVENT REPORT (LER) FORWARD COhNFMS REGARDUIG BURDEN ESTIMATE TO THE INFORMATIONAN RECORDS MANAGEMENT BRANCH IT41 F33), U.S. NUCLEAR REGULATOR COMMISSION, WASIENGTON DC 205550001 ANDTO THE PAPERWORK REDUCllo |
| J~S 1994 AP-006,"Procedure review and approval," was revised to include permanent, Handwritten Revision non-intent rocedure changes that could take advantage of the 14-day limit for review and approval described in TS for temporary hanges to procedures. | | {SBB reverse for required number of PROJECT (31500104), OFFlCE OF MANAGIJJtENTAND BUDGET, WASHINGTON, 209XL digits/characters for each block) |
| AP-006 was revised to require the reviews and approvals described in TS for temporary changes to rocedures, however the procedure did not reference TS.Consequently', involved site personnel did not understand that andwritten Revision non-intent procedure changes were in fact temporaiy procedure changes as referenced in TS and ANSI 18.7.uring Refueling Outage 7 (RFO7), Handwritten Revision non-intent procedure changes were processed without review and pproval within 14 days as required by AP-006, especially in the Operations organization. | | FACIUTYNAME (I) DOCKET NUMBER {2) PAGE (3) |
| The Operations Procedure oordinator informed his supervisor (Supervisor | | Shaaron Harris Nuc(ear Plant, Unit-1 50-400 1 OF3 TITLE I4) |
| -Operations Support or S-OS)that the 14-day limit for review and approval f Handwritten Revision non-intent procedure changes would not be met due to the large volume (39)to be processed. | | Operation with procedures not properly reviewed and approved FACILITYNAME DOCKET NUMBER SEDUENTIAL REVISION 'YEAR MBNTN DAY YEAR DAY NUMBER NUMBER FACILITYNAME DOCKET NUMBER 07 01 97 97 018 00 07 31 97 05000 OPERATING MODE {9) 20.2201(b) 20.2203(a) (2) (v) 60.73(a) l2)(i) 60.73(a)(2) (viii) |
| The ourse of action determined by the S-OS was to direct the procedure coordinator to focus on temporary changes to procedures ince they were required by TS and document the Handwritten Revision non-intent procedure changes that went overdue by a ondition report.The situation grew worse due to mis-communication between the S-OS and site management. | | POWER LEVEL (10) 20.2203(a) (2)(i) 20.2203(a) (3) (ii) 60.73(a)(2) {iii) 73.71 OTHER 20.2203(a) l2) (iii) 60.36{c) l1) 60.73(a) (2) (v) Specify In Abstract below or in NRC Form 366A 20.2203(a) (2) (iv) 60.36(c) l2) 60.73(a) (2) (vii) |
| The S-OS nformed site management of the problem and his course of action.At this time, he requested relief from the 144ay AP406 uirement to perform required reviews and approvals of Handwritten Revision non-intent procedure changes.The relief was ot granted, but no other course of action was directed or suggested. | | NAME TELEPHONE NUMBER (Inoerde Ares Code) |
| Without further guidance, the S-OS concluded his course f action was acceptable to plant management. | | Mark Ellington Senior Analyst- Licensing (919) 362-2057 REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM MANUFACTURER TO NPROS TO NPRDS MONTH DA YEAR EXPECTED YES SUBMISSION |
| s a result over 125 Handwritten Revision non-intent procedure changes affecting approximately 90 Operation's procedures ere not properly reviewed and approved as required by TS 6.8.3.Additionally, many of these procedures were used by perations without being properly reviewed and approved.fter combining procedure change deficiencies from other plant organizations with the Operations organization, the total umber of procedure changes that did not receive proper review and approval was approximately 150, affecting pproximately 100 procedures. | | {Ifyes, complete EXPECTED SUBMISSION DATE). X NO DATE {16) |
| Some of these violations occurred in 1996, but were not recognized as TS violations at that me.AUSE: ailure to comply with plant administrative procedure, AP406, caused these events.Contributing factors were: (1)A sunderstanding of the basis of the requirements in the AP-006 by site personnel and (2)Inadequate management volvement once the problem was brought to management's attention as evidenced by not stopping the Handwritten evision non-intent process once a problem was identified.
| | ABSTRACT {Limitto 1400 spaces, i.e., approximately 16 single-spaced typewritten lines) {16) |
| | On July 1, 1997, with the plant at approximately 100% power in Mode 1, an investigation determined that some Harris Nuclear Plant (HNP) procedures had not received proper reviews and approvals. Specifically, approximately 150 temporary procedure changes affecting over 100 procedures were not reviewed and approved within 14 days in accordance with Technical Specification (TS) 6.8.3 and 6.5.1. Additionally, many of these procedures were used to operate the plant without the required TS review and approval. |
| | The cause of this TS violation is failure to comply with plant administrative procedure AP-006. Contributing factors were: |
| | (1) A misunderstanding of the basis of the requirements in the AP-006 by site personnel. (2) Inadequate management involvement once the problem was brought to management's attention as evidenced by not stopping the Handwritten Revision non-intent process once a problem was identified. |
| | The following corrective actions have been performed: (1) HNP procedures identified as deficient have been properly reviewed and approved in accordance with TS, (2) Involved Site Management has been counseled that procedure non-compliance must be prevented and promptly corrected upon discovery, (3) Communications to appropriate site personnel have been made on how AP.-006 implements TS requirements, (4) AP-006 has been revised to clarify implementation of TS requirements and (5) The Supervisor-Operations Support, involved in this event, has been disciplined by Plant Management A comprehensive review of the procedure change and review process willbe completed by 9/1/97. |
| | |
| | RC FORM 3EEA ILS. NUCLEAR REGULATORT COMMISBIO 495) |
| | LICENSEE EVENT BEPOBT (LEB) |
| | TEXT CONTINUATION FACILITYNAME (I) DOCKET LER NUMBER IB) PAGEIB) |
| | BEOUENTUL REVISION NUMBER NUMBER Shearon Harris Nuclear Plant - Unit 50400 2 OF 3 1 |
| | 97 - 018 - 00 EXT Pinero oOoalt ooqoind, mooiRRoooorooyiieolHRC Faao3GRRl I) 7) |
| | VENT DESCRIPTION: |
| | n July 1, 1997 with the plant at approximately 100% power in mode 1, an investigation determined some HNP procedures ad not received the required TS reviews and approvals. Specifically, approximately 150 temporary procedure changes fecting over 100 procedures were not reviewed and approved within 14 days in accordance with TS 6.8.3 . Additionally, any of these procedures were used to operate the plant without the required TS review and approval. |
| | e plant definition for a temporary procedure change is a change that will eventually be removed from the procedure. ANSI 18.7 definition is somewhat different in that temporary procedure changes could be incorporated, as appropriate, into the ext revision to the procedure. |
| | J ~ S 1994 AP-006, "Procedure review and approval," was revised to include permanent, Handwritten Revision non-intent rocedure changes that could take advantage of the 14-day limit for review and approval described in TS for temporary hanges to procedures. AP-006 was revised to require the reviews and approvals described in TS for temporary changes to rocedures, however the procedure did not reference TS. Consequently', involved site personnel did not understand that andwritten Revision non-intent procedure changes were in fact temporaiy procedure changes as referenced in TS and ANSI 18.7. |
| | uring Refueling Outage 7 (RFO7), Handwritten Revision non-intent procedure changes were processed without review and pproval within 14 days as required by AP-006, especially in the Operations organization. The Operations Procedure oordinator informed his supervisor (Supervisor - Operations Support or S-OS) that the 14-day limit for review and approval f Handwritten Revision non-intent procedure changes would not be met due to the large volume (39) to be processed. The ourse of action determined by the S-OS was to direct the procedure coordinator to focus on temporary changes to procedures ince they were required by TS and document the Handwritten Revision non-intent procedure changes that went overdue by a ondition report. The situation grew worse due to mis-communication between the S-OS and site management. The S-OS nformed site management of the problem and his course of action. At this time, he requested relief from the 144ay AP406 uirement to perform required reviews and approvals of Handwritten Revision non-intent procedure changes. The relief was ot granted, but no other course of action was directed or suggested. Without further guidance, the S-OS concluded his course f action was acceptable to plant management. |
| | s a result over 125 Handwritten Revision non-intent procedure changes affecting approximately 90 Operation's procedures ere not properly reviewed and approved as required by TS 6.8.3. Additionally, many of these procedures were used by perations without being properly reviewed and approved. |
| | fter combining procedure change deficiencies from other plant organizations with the Operations organization, the total umber of procedure changes that did not receive proper review and approval was approximately 150, affecting pproximately 100 procedures. Some of these violations occurred in 1996, but were not recognized as TS violations at that me. |
| | AUSE: |
| | ailure to comply with plant administrative procedure, AP406, caused these events. Contributing factors were: (1) A sunderstanding of the basis of the requirements in the AP-006 by site personnel and (2) Inadequate management volvement once the problem was brought to management's attention as evidenced by not stopping the Handwritten evision non-intent process once a problem was identified. |
| AFETY SIGNIFICANCE: | | AFETY SIGNIFICANCE: |
| ere were no safety consequences associated with this event.Subsequent review and approval of procedures specified in this ER did not reveal operation of the plant outside its licensing or design basis.Additionally, the procedure changes did not equire alteration as a result of the subsequent 10 CFR 50.59 reviews. | | ere were no safety consequences associated with this event. Subsequent review and approval of procedures specified in this ER did not reveal operation of the plant outside its licensing or design basis. Additionally, the procedure changes did not equire alteration as a result of the subsequent 10 CFR 50.59 reviews. |
| | |
| | ra'r . |
| | l NRC FORM ILS. NUCLEAR REGULATORY COMMSSIO 344A'4-951 LICENSEE EVENT REPORT (LEB) |
| | TEXT CONTINUATION |
| | <<FACILITYNAME III DOCKET LER NUMBER I4) <<PAGEOI SEOUENTUIL REVSION NUMRER NUMRER 50400 3 OF |
| | ''3 Shearon Harris Nuclear Plant ~ Unit 81 97 - 018 - 00 TEXT Ilhooco cPocoiscrqo4NL ocoadfitkorl cero'mollllIC farm 36Ql (17j PREVIOUS SIMIL'AREVENTS: |
| | r No prev'ious HNP. events have been reported related to missing the'144ay TS requirement for temporary changes to |
| | =procedures. |
| | r II CORRECTIVE ACTIONS COMPLETED: |
| | ~ ~ |
| | l 1'.. r . HNP procedures identified as deficient have been properly reviewed and approved in accordance with TS. |
| | : 2. Involved Site Management has been counseled that procedure noncompliance must be prevented and promptly corrected upon discovery. |
| | : 3. Communications to appropriate site personnel have been made on how AP-006 implements TS requirements. |
| | ~ ~ |
| | : 4. = - 'P-006 has been'revised to clarify implementation'of TS requirements.. |
| | : 5. The Supervisor-Operations Support, involved in this event, was disciplined by Plant Management. |
| | 1 CORRECTIVE ACTIONS PLANNED: |
| | r |
| | : 1. A comprehensive review of the procedure change and review process willbe completed by 9/1/97. |
|
| |
|
| ra'r.lNRC FORM 344A'4-951
| | 0 C~ |
| <<LICENSEE EVENT REPORT (LEB)TEXT CONTINUATION ILS.NUCLEAR REGULATORY COMMSSIO<<FACILITY NAME III DOCKET LER NUMBER I4)<<PAGEOI Shearon Harris Nuclear Plant~Unit 81 TEXT Ilhooco cPocoiscrqo4NL ocoadfitkorl cero'mollllIC farm 36Ql (17j 50400 SEOUENTUIL REVSION NUMRER NUMRER 3 OF''3 97-018-00 3.PREVIOUS SIMIL'AR EVENTS: r No prev'ious HNP.events have been reported related to missing the'144ay TS requirement for temporary changes to=procedures.
| | 1 |
| r II CORRECTIVE ACTIONS COMPLETED:
| | :l.}} |
| ~~l 1'..r.HNP procedures identified as deficient have been properly reviewed and approved in accordance with TS.2.Involved Site Management has been counseled that procedure noncompliance must be prevented and promptly corrected upon discovery.
| |
| 'Communications to appropriate site personnel have been made on how AP-006 implements TS requirements.
| |
| ~~4.=-'P-006 has been'revised to clarify implementation'of TS requirements..
| |
| 5.The Supervisor-Operations Support, involved in this event, was disciplined by Plant Management.
| |
| 1 CORRECTIVE ACTIONS PLANNED: r 1.A comprehensive review of the procedure change and review process will be completed by 9/1/97.
| |
| 0 C~1:l.}}
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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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CATEGORY 1 REGULATO Y INFORMATION DISTRIBUTION STEM (RIDS)
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ACCESGION MBR:9708060308 DOC.DATE: 97/07/31 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME -= ., AUTHOR AFFILIATION ELLINGTON,M. .
Carolina'ower & Light Co.
DONAHUE,J.W. , Carolina Power & Light Co.
RECIP.NAME RECIPIENT 'AFFILIATION
SUBJECT:
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.Involved site mgt counseled.W/970731 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL : SIZE:
.TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
V NOTES:Application for permit renewal filed. 05000400 g 0
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME PD2,.-1 PD LTTR ENCL 1- 1 ID CODE/NAME ROONEYEV 1, LTTR ENCL 1
R INTERNAL: ACRS 1 1 RAB 2 2 AEOD/SPD/RRAB 1 1 ILE CENTE 1 1 NRR/DE/ECGB 1 1 NR E EELB, 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB =1 1 :.NRR/DRCH/HOLB 1 .1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DET/EIB 1 1 RGN2 FILE 01 1 1 0
EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCEgJ H 1 1 NOAC POORE,W. 1 1 NOAC QUEENEREDS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RZDS" RECZPZENTSZ PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK/
ROOM OWPN SD-5(EXT. 415-2083) TO ELZMZNATE YOUR NAME PROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEEDl FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25
Carolina Power & Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 JUL 31 1997 U.S. Nuclear Regulatory Commission Serial: HNP-97-.143 ATTN: NRC Document Control Desk 10CFR50.73 Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1-DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 97-018-00 Sir or Madam:
~ g In accordance with Title",10.to the. Code of Federal Regulations,lthe enclosed Licensee Event Report is submitted.-'This 'report de'scribes operation with procedures that were not properly reviewed and approved.
Sincerely, J. W. Donahue Director of Site Operations Harris Plant MSE/mse
~6M 'nclosure
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,c: ':.'r,'- J.'! B.:"- Brady (HNP Senior. NRC:Resident)'.';;: ".:. --..::: .-:;...:;,,: .;.:.i." ..:.:.
.'.:Mr L'. A. Reyes'(NRC Regional Administrator;.Region:11);::
Mr. V. L. Rooney (NRC - NRR Project Manager)
IIIIUlllllllllllHIIIIIIIIUILIUIIU 5413 Shearon Harris Road New Hill NC
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NRC FORM 366, e
U.S.'NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 31 500104 EXPIRES 0430lss H-35) r ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATOR INFORMATIONCOLLECTION REOUEsnf 50.0 HRS. REPORTED LESSONS LEARNE ARE INCORPORATED INTO THE UCENSING PROCESS AND FED BACK TO INDUSTRY LXCENSEE EVENT REPORT (LER) FORWARD COhNFMS REGARDUIG BURDEN ESTIMATE TO THE INFORMATIONAN RECORDS MANAGEMENT BRANCH IT41 F33), U.S. NUCLEAR REGULATOR COMMISSION, WASIENGTON DC 205550001 ANDTO THE PAPERWORK REDUCllo
{SBB reverse for required number of PROJECT (31500104), OFFlCE OF MANAGIJJtENTAND BUDGET, WASHINGTON, 209XL digits/characters for each block)
FACIUTYNAME (I) DOCKET NUMBER {2) PAGE (3)
Shaaron Harris Nuc(ear Plant, Unit-1 50-400 1 OF3 TITLE I4)
Operation with procedures not properly reviewed and approved FACILITYNAME DOCKET NUMBER SEDUENTIAL REVISION 'YEAR MBNTN DAY YEAR DAY NUMBER NUMBER FACILITYNAME DOCKET NUMBER 07 01 97 97 018 00 07 31 97 05000 OPERATING MODE {9) 20.2201(b) 20.2203(a) (2) (v) 60.73(a) l2)(i) 60.73(a)(2) (viii)
POWER LEVEL (10) 20.2203(a) (2)(i) 20.2203(a) (3) (ii) 60.73(a)(2) {iii) 73.71 OTHER 20.2203(a) l2) (iii) 60.36{c) l1) 60.73(a) (2) (v) Specify In Abstract below or in NRC Form 366A 20.2203(a) (2) (iv) 60.36(c) l2) 60.73(a) (2) (vii)
NAME TELEPHONE NUMBER (Inoerde Ares Code)
Mark Ellington Senior Analyst- Licensing (919) 362-2057 REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM MANUFACTURER TO NPROS TO NPRDS MONTH DA YEAR EXPECTED YES SUBMISSION
{Ifyes, complete EXPECTED SUBMISSION DATE). X NO DATE {16)
ABSTRACT {Limitto 1400 spaces, i.e., approximately 16 single-spaced typewritten lines) {16)
On July 1, 1997, with the plant at approximately 100% power in Mode 1, an investigation determined that some Harris Nuclear Plant (HNP) procedures had not received proper reviews and approvals. Specifically, approximately 150 temporary procedure changes affecting over 100 procedures were not reviewed and approved within 14 days in accordance with Technical Specification (TS) 6.8.3 and 6.5.1. Additionally, many of these procedures were used to operate the plant without the required TS review and approval.
The cause of this TS violation is failure to comply with plant administrative procedure AP-006. Contributing factors were:
(1) A misunderstanding of the basis of the requirements in the AP-006 by site personnel. (2) Inadequate management involvement once the problem was brought to management's attention as evidenced by not stopping the Handwritten Revision non-intent process once a problem was identified.
The following corrective actions have been performed: (1) HNP procedures identified as deficient have been properly reviewed and approved in accordance with TS, (2) Involved Site Management has been counseled that procedure non-compliance must be prevented and promptly corrected upon discovery, (3) Communications to appropriate site personnel have been made on how AP.-006 implements TS requirements, (4) AP-006 has been revised to clarify implementation of TS requirements and (5) The Supervisor-Operations Support, involved in this event, has been disciplined by Plant Management A comprehensive review of the procedure change and review process willbe completed by 9/1/97.
RC FORM 3EEA ILS. NUCLEAR REGULATORT COMMISBIO 495)
LICENSEE EVENT BEPOBT (LEB)
TEXT CONTINUATION FACILITYNAME (I) DOCKET LER NUMBER IB) PAGEIB)
BEOUENTUL REVISION NUMBER NUMBER Shearon Harris Nuclear Plant - Unit 50400 2 OF 3 1
97 - 018 - 00 EXT Pinero oOoalt ooqoind, mooiRRoooorooyiieolHRC Faao3GRRl I) 7)
VENT DESCRIPTION:
n July 1, 1997 with the plant at approximately 100% power in mode 1, an investigation determined some HNP procedures ad not received the required TS reviews and approvals. Specifically, approximately 150 temporary procedure changes fecting over 100 procedures were not reviewed and approved within 14 days in accordance with TS 6.8.3 . Additionally, any of these procedures were used to operate the plant without the required TS review and approval.
e plant definition for a temporary procedure change is a change that will eventually be removed from the procedure. ANSI 18.7 definition is somewhat different in that temporary procedure changes could be incorporated, as appropriate, into the ext revision to the procedure.
J ~ S 1994 AP-006, "Procedure review and approval," was revised to include permanent, Handwritten Revision non-intent rocedure changes that could take advantage of the 14-day limit for review and approval described in TS for temporary hanges to procedures. AP-006 was revised to require the reviews and approvals described in TS for temporary changes to rocedures, however the procedure did not reference TS. Consequently', involved site personnel did not understand that andwritten Revision non-intent procedure changes were in fact temporaiy procedure changes as referenced in TS and ANSI 18.7.
uring Refueling Outage 7 (RFO7), Handwritten Revision non-intent procedure changes were processed without review and pproval within 14 days as required by AP-006, especially in the Operations organization. The Operations Procedure oordinator informed his supervisor (Supervisor - Operations Support or S-OS) that the 14-day limit for review and approval f Handwritten Revision non-intent procedure changes would not be met due to the large volume (39) to be processed. The ourse of action determined by the S-OS was to direct the procedure coordinator to focus on temporary changes to procedures ince they were required by TS and document the Handwritten Revision non-intent procedure changes that went overdue by a ondition report. The situation grew worse due to mis-communication between the S-OS and site management. The S-OS nformed site management of the problem and his course of action. At this time, he requested relief from the 144ay AP406 uirement to perform required reviews and approvals of Handwritten Revision non-intent procedure changes. The relief was ot granted, but no other course of action was directed or suggested. Without further guidance, the S-OS concluded his course f action was acceptable to plant management.
s a result over 125 Handwritten Revision non-intent procedure changes affecting approximately 90 Operation's procedures ere not properly reviewed and approved as required by TS 6.8.3. Additionally, many of these procedures were used by perations without being properly reviewed and approved.
fter combining procedure change deficiencies from other plant organizations with the Operations organization, the total umber of procedure changes that did not receive proper review and approval was approximately 150, affecting pproximately 100 procedures. Some of these violations occurred in 1996, but were not recognized as TS violations at that me.
AUSE:
ailure to comply with plant administrative procedure, AP406, caused these events. Contributing factors were: (1) A sunderstanding of the basis of the requirements in the AP-006 by site personnel and (2) Inadequate management volvement once the problem was brought to management's attention as evidenced by not stopping the Handwritten evision non-intent process once a problem was identified.
AFETY SIGNIFICANCE:
ere were no safety consequences associated with this event. Subsequent review and approval of procedures specified in this ER did not reveal operation of the plant outside its licensing or design basis. Additionally, the procedure changes did not equire alteration as a result of the subsequent 10 CFR 50.59 reviews.
ra'r .
l NRC FORM ILS. NUCLEAR REGULATORY COMMSSIO 344A'4-951 LICENSEE EVENT REPORT (LEB)
TEXT CONTINUATION
<<FACILITYNAME III DOCKET LER NUMBER I4) <<PAGEOI SEOUENTUIL REVSION NUMRER NUMRER 50400 3 OF
3 Shearon Harris Nuclear Plant ~ Unit 81 97 - 018 - 00 TEXT Ilhooco cPocoiscrqo4NL ocoadfitkorl cero'mollllIC farm 36Ql (17j PREVIOUS SIMIL'AREVENTS:
r No prev'ious HNP. events have been reported related to missing the'144ay TS requirement for temporary changes to
=procedures.
r II CORRECTIVE ACTIONS COMPLETED:
~ ~
l 1'.. r . HNP procedures identified as deficient have been properly reviewed and approved in accordance with TS.
- 2. Involved Site Management has been counseled that procedure noncompliance must be prevented and promptly corrected upon discovery.
- 3. Communications to appropriate site personnel have been made on how AP-006 implements TS requirements.
~ ~
- 4. = - 'P-006 has been'revised to clarify implementation'of TS requirements..
- 5. The Supervisor-Operations Support, involved in this event, was disciplined by Plant Management.
1 CORRECTIVE ACTIONS PLANNED:
r
- 1. A comprehensive review of the procedure change and review process willbe completed by 9/1/97.
0 C~
1
- l.