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| {{#Wiki_filter:y CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION@BR:9609190064 DOC.DATE: 96/09/13 NOTARIZED: | | {{#Wiki_filter:y CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION VERRILLI,M. | | ACCESSION @BR:9609190064 DOC.DATE: 96/09/13 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power & I ight Co. |
| Carolina Power&I ight Co.DONAHUE,J.W. | | DONAHUE,J.W. Carolina Power & Light Co. |
| Carolina Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000400 | | RECIP. NAME RECIPIENT AFFILIATION |
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| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 96-016-00:on 960814,reactor trip bypass breaker surveillance test, required by TSs not performed. | | LER 96-016-00:on 960814,reactor trip bypass breaker surveillance test, required by TSs not performed. Caused by inadequate procedures not ensuring testing done prior to A placing them in svc.Rev of deficient procedures.W/960912 ltr DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL ) SIZE: |
| Caused by inadequate procedures not ensuring testing done prior to placing them in svc.Rev of deficient procedures.W/960912 ltr DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL)SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.A NOTES:Application for permit renewal filed.05000400 t" 0 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/DSIR/EIB EXTERNAL: L ST LOBBY WARD NOAC MURPHYiG.A NRC PDR COPIES RECIPIENT LTTR ENCI ID CODE/NAME 1 1 LE,N 1 AEGD/SP-D/~B 1 FILE CENTE~R 1 NRR DE/EE~B 1 NRR/DRCH/HHFB 1 NRR/DRCH/HOLB 1 NRR/DRPM/PECB 1 NRR/DSSA/SRXB 1 RGN2 FILE 01 1 1 LITCO BRYCE,J H 1 1 NOAC POOREgW.1 1 NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 R D U N NOTE TO ALL"RIDS" RECIPIENTS: | | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26 Carolina Power 8a Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 SEP 1 8 1996 U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 Serial: HNP-96-158 10CFR50.73 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 96-016-00 Sir or Madam: 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 t" 0 |
| This report describes a failure to perform proper surveillance testing on the reactor trip bypass breakers as required by Technical Specifications. | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCI ID CODE/NAME LTTR ENCL R PD2-1 PD 1 1 LE,N 1 1 INTERNAL: ACRS 1 AEGD/SP-D/~B 2 2 AEOD/SPD/RRAB 1 FILE CENTE~R 1 1 NRR/DE/ECGB 1 NRR DE/EE~B 1 1 NRR/DE/EMEB 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 NRR/DSSA/SRXB 1 1 D RES/DSIR/EIB 1 RGN2 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 2 2 NOAC MURPHYiG.A 1 1 NOAC POOREgW. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 U |
| Sincerely, J.W.Donahue Director of Site Operations Harris Plant MV Enclosure c: Mr.J.B.Brady (HNP Senior Resident-NRC)Mr.S.D.Ebneter (NRC Regional Administrator | | N NOTE TO ALL "RIDS" RECIPIENTS: |
| -Region II)Mr.N.B.Le (NRC Project Manager-NRR)'9609i90064 960rsti3 PDR ADOCK 05000400 S PDR State Road H34 New Hill NC NRC FORM 366 (4.95)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each block)APPROVED BY OMB NO.3150.0104 EXPIRES 04/30/96 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THI MANDATORY WFORMATION COLLEC'I)ON REOUESTI 5M HRS.REPORTED lESSONS LEARNED ARE INCORPORATED (NTO THE UCENSING PROCESS AHD FEO BACK TO UIOUSTRY.FORWARD COMMENTS REGAROU(G BURDEN ESTIMATE'FO THE)NFORMATION ANO RECORDS MANAGEMENT BRANCH IT6 f33L US.NUCLEAR REGUtAIORY COMMISSION, WASHINGTON, DC 20555600), ANO YO THE PAPERWORK REDUCTION PROJECT 0)50.OID(l OfFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACIUTY NAME (I)Harris Nuclear Plant Unit-1 OOCKET NUMBER 12)50-400 PAGE (3)1OF2 TITLE (4)Failure to perform reactor trip bypass breaker surveillance testing required by Technical Specifications. | | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| MONTH OAY 8 14 YEAR EVENT DATE (5)LER NUMBER (6)YEAR SEO E I NUMBER REVISION NUMBER 96-016-0 REPORT DATE (7)MONTH OAY YEAR 9 13 96 FACIUTY NAME FACIUTY NAME OTHER FACILITIES INVOLVED (8)OOCKET NUMBER 05000 DOCKET NUMBER 05000 OPERATING MODE (9)POWER LEVEL (10)1 00%20.2201(b) 20.2203(a)
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26 |
| (1)20.2203(a)(2) li)20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a) | | |
| (2)(iv)50.73(a)(2)(i)50.73(a)(2)(ii) 20.2203(a)(2)(v)20.2203(a)(3)(i) 20.2203(a) | | Carolina Power 8a Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 SEP 1 8 1996 U.S. Nuclear Regulatory Commission Serial: HNP-96-158 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 96-016-00 Sir or Madam: |
| (3)(n)20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.36(c)(1)50.36(c)(2) | | In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report describes a failure to perform proper surveillance testing on the reactor trip bypass breakers as required by Technical Specifications. |
| LICENSEE CONTACT FOR THIS LER (12)TELEPHONE NUMBER Bnoivde Area Code)50.73(a)(2)(viii)50.73(a)(2)(x) 73.71 OTHER Specify in Abstract below or in NAC Form 366A THIS REPORT IS SUBMITTED PUR SUANT TO THE REQUIREMENTS OF 10 CFR B)(Check one or more)(11)Michael Verrilli Sr.Analyst-Licensing (919)362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPROS CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPROS SUPPLEMENTAL REPORT EXPECTED (14)YES (lf yes, complete EXPECTED SUBMISSION DATE).X NO EXPECTED SUBMISSION DATE (15)MONTH OAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single.spaced typewr((ten lines)(16)On August 14, 1996, during a review of the Harris Nuclear Plant (HNP)Final Safety Analysis Report (FSAR), a deficiency was identified with surveillance testing for the reactor trip bypass breakers.Specifically, Technical Specifications require performing a remote manual shunt trip test prior to placing the reactor trip bypass breaker in service.Testing of the remote manual shunt trip at HNP has previously been conducted after the reactor trip bypass breakers were racked into the"connected" position and closed.Therefore, the breakers were actually in service and connected to the rod control system during previous testing of the remote manual shunt trips.This condition was caused by inadequate surveillance test procedures which did not ensure testing of the reactor trip bypass breakers before placing them in service.This condition has existed since May 1986, when the procedures were revised to incorporate testing of the reactor trip bypass breakers.A probable cause for the May 1986 procedure error was a mis-interpretation of the term"in-service" and how it applied to the reactor trip bypass breakers.Investigation also revealed that conflicting information in the FSAR could have been a contributing factor to the procedure error.Immediate corrective actions included revising the deficient surveillance procedures. | | Sincerely, J. W. Donahue Director of Site Operations Harris Plant MV Enclosure c: Mr. J. B. Brady (HNP Senior Resident - NRC) |
| Additional corrective actions will include revising the deficient FSAR sections and reviewing the event with appropriate Operations and Maintenance personnel.
| | Mr. S. D. Ebneter (NRC Regional Administrator - Region II) |
| NRC fORM 366A l496)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION US.NUCLEAR REGULATORT COMMISSION TAG)LITT NAME n)Shearon Harris Nuclear Plant~Unit rY1 OOCXET 50400 LER NUMBER IB)BEOUENTIAL RETIBION NUMBER NUMBER 96-016-00 PAGE I3)2 OF 2 TEXT III mort spssv r's rsrprpsd.vsv sddr)drrrsl sopr'vs ol fYRC form 36QI ill)EVENT DESCRIPTION:
| | Mr. N. B. Le (NRC Project Manager - NRR) |
| On August 14, 1996, with the plant in mode 1, operating at 100%power, a deficiency was identified with the Train A and Train B Solid State Protection System Actuation Logic&Master Relay Tests (MST-I0001 and MST-I0320).
| | '9609i90064 960rsti3 PDR ADOCK 05000400 S PDR State Road H34 New Hill NC |
| This deficiency was identified during a review of the Harris Nuclear Plant (HNP)Final Safety Analysis Report (FSAR)which describes the testing process for the reactor trip bypass breakers (EIIS Code: JG-BKR).Specifically, Technical Specification Table 4.3-1 requires performing a remote manual shunt trip test prior to placing the reactor trip bypass breakers in service.However, testing of the remote manual shunt trip at HNP has previously been conducted after the reactor trip bypass breakers were racked into the"connected" position and closed.Therefore, the breakers were actually in service and connected to the rod control system during previous testing of the remote manual shunt trips, which constitutes a violation of Technical Specifications and is reportable per 10CFR50.73(a)(2)(i)(b).
| | |
| CAUSE: The cause of this event was inadequate surveillance test procedures.
| | NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150.0104 (4.95) EXPIRES 04/30/96 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THI MANDATORY WFORMATION COLLEC'I)ON REOUESTI 5M HRS. REPORTED lESSONS LEARNED ARE LICENSEE EVENT REPORT (LER) INCORPORATED (NTO THE UCENSING PROCESS AHD FEO BACK TO UIOUSTRY. |
| MST-I0001 and MST-I0320 did not ensure that the reactor trip bypass breakers were tested before being placed in service.These breakers have a"test" position which should have been used, rather than racking the breaker into the"connected" position and closing them, which actually connected the reactor trip bypass breakers to the rod control system and placed them in service.This condition has existed since May 1986, when both procedures were revised to incorporate testing of the reactor trip bypass breakers.A probable cause for the May 1986 procedure error was a mis-interpretation of the term"in-service" and how it applied to the reactor trip bypass breakers.Investigation also revealed that conflicting information in FSAR section 7.2.2.2.3.10 could have been a contributing factor to the pr'ocedure error.This section incorrectly states that HNP"does not propose to verify the operability of each bypass breaker prior to placing it in service each time the main reactor trip breakers are to be tested." SAFETY SIGNIFICANCE:
| | FORWARD COMMENTS REGAROU(G BURDEN ESTIMATE 'FO THE )NFORMATION ANO RECORDS MANAGEMENT BRANCH IT6 f33L US. NUCLEAR REGUtAIORY COMMISSION, (See reverse for required number of WASHINGTON, DC 20555600), ANO YO THE PAPERWORK REDUCTION PROJECT 0)50. |
| There were no safety consequences as a result of this event.MST-I0001 and MST-I0320 have provided previous testing of the reactor trip bypass breaker remote manual shunt trips prior to opening the main reactor trip breakers.Based on a review of completed testing, the reactor trip bypass breakers functioned properly during this previous testing.PREVIOUS SIMILAR EVENTS: There have been no previous HNP events related to improperly testing the reactor trip bypass breakers prior to placing them in service.CORRECTIVE ACTIONS COMPLETED:
| | digits/characters for each block) OID(l OfFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503. |
| 1.Procedures MST-10001 and MST-I0320 were revised to ensure that the reactor trip bypass breakers are properly tested before placing them in service.CORRECTIVE ACTIONS PLANNED: 1.'SAR section 7.2.2.2.3.10 will be revised to eliminate the conflicting wording pertaining to the testing of the reactor trip bypass breakers.This will be completed by November 15, 1996.2.This event will be reviewed with Maintenance and Operations personnel involved with developing, revising and reviewing procedures to emphasize the importance of fully understanding Technical Specification testing requirements.
| | FACIUTY NAME (I) OOCKET NUMBER 12) PAGE (3) |
| This will be completed by December 1, 1996.}} | | Harris Nuclear Plant Unit-1 50-400 1OF2 TITLE (4) |
| | Failure to perform reactor trip bypass breaker surveillance testing required by Technical Specifications. |
| | EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| | FACIUTY NAME OOCKET NUMBER SEO E I REVISION MONTH OAY YEAR YEAR MONTH OAY YEAR NUMBER NUMBER 05000 FACIUTY NAME DOCKET NUMBER 8 14 96 016 0 9 13 96 05000 OPERATING THIS REPORT IS SUBMITTED PUR SUANT TO THE REQUIREMENTS OF 10 CFR B) (Check one or more) (11) |
| | MODE (9) 20.2201(b) 20.2203(a)(2) (v) 50.73(a) (2) (i) 50.73(a)(2) (viii) 20.2203(a) (1) 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a)(2)(x) |
| | POWER LEVEL (10) 1 00% 20.2203(a)(2) li) 20.2203(a) (3)(n) 50.73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c) (1) 50.73(a)(2)(v) Specify in Abstract below or in NAC Form 366A 20.2203(a) (2) (iv) 50.36(c)(2) 50.73(a)(2)(vii) |
| | LICENSEE CONTACT FOR THIS LER (12) |
| | TELEPHONE NUMBER Bnoivde Area Code) |
| | Michael Verrilli Sr. Analyst - Licensing (919) 362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| | REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPROS TO NPROS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH OAY YEAR YES SUBMISSION (lf yes, complete EXPECTED SUBMISSION DATE). X NO DATE (15) |
| | ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single. spaced typewr((ten lines) (16) |
| | On August 14, 1996, during a review of the Harris Nuclear Plant (HNP) Final Safety Analysis Report (FSAR), a deficiency was identified with surveillance testing for the reactor trip bypass breakers. Specifically, Technical Specifications require performing a remote manual shunt trip test prior to placing the reactor trip bypass breaker in service. Testing of the remote manual shunt trip at HNP has previously been conducted after the reactor trip bypass breakers were racked into the "connected" position and closed. Therefore, the breakers were actually in service and connected to the rod control system during previous testing of the remote manual shunt trips. |
| | This condition was caused by inadequate surveillance test procedures which did not ensure testing of the reactor trip bypass breakers before placing them in service. This condition has existed since May 1986, when the procedures were revised to incorporate testing of the reactor trip bypass breakers. A probable cause for the May 1986 procedure error was a mis-interpretation of the term "in-service" and how it applied to the reactor trip bypass breakers. |
| | Investigation also revealed that conflicting information in the FSAR could have been a contributing factor to the procedure error. |
| | Immediate corrective actions included revising the deficient surveillance procedures. Additional corrective actions will include revising the deficient FSAR sections and reviewing the event with appropriate Operations and Maintenance personnel. |
| | |
| | NRC fORM 366A US. NUCLEAR REGULATORT COMMISSION l496) |
| | LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION TAG)LITT NAME n) OOCXET LER NUMBER IB) PAGE I3) |
| | BEOUENTIAL RETIBION NUMBER NUMBER Shearon Harris Nuclear Plant ~ Unit rY1 50400 2 OF 2 96 - 016 - 00 TEXT IIImort spssv r's rsrprpsd. vsv sddr)drrrsl sopr'vs ol fYRC form 36QI ill) |
| | EVENT DESCRIPTION: |
| | On August 14, 1996, with the plant in mode 1, operating at 100% power, a deficiency was identified with the Train A and Train B Solid State Protection System Actuation Logic & Master Relay Tests (MST-I0001 and MST-I0320). This deficiency was identified during a review of the Harris Nuclear Plant (HNP) Final Safety Analysis Report (FSAR) which describes the testing process for the reactor trip bypass breakers (EIIS Code: JG-BKR). Specifically, Technical Specification Table 4.3-1 requires performing a remote manual shunt trip test prior to placing the reactor trip bypass breakers in service. However, testing of the remote manual shunt trip at HNP has previously been conducted after the reactor trip bypass breakers were racked into the "connected" position and closed. Therefore, the breakers were actually in service and connected to the rod control system during previous testing of the remote manual shunt trips, which constitutes a violation of Technical Specifications and is reportable per 10CFR50.73(a)(2)(i)(b). |
| | CAUSE: |
| | The cause of this event was inadequate surveillance test procedures. MST-I0001 and MST-I0320 did not ensure that the reactor trip bypass breakers were tested before being placed in service. These breakers have a "test" position which should have been used, rather than racking the breaker into the "connected" position and closing them, which actually connected the reactor trip bypass breakers to the rod control system and placed them in service. This condition has existed since May 1986, when both procedures were revised to incorporate testing of the reactor trip bypass breakers. A probable cause for the May 1986 procedure error was a mis-interpretation of the term "in-service" and how it applied to the reactor trip bypass breakers. Investigation also revealed that conflicting information in FSAR section 7.2.2.2.3.10 could have been a contributing factor to the pr'ocedure error. This section incorrectly states that HNP "does not propose to verify the operability of each bypass breaker prior to placing it in service each time the main reactor trip breakers are to be tested." |
| | SAFETY SIGNIFICANCE: |
| | There were no safety consequences as a result of this event. MST-I0001 and MST-I0320 have provided previous testing of the reactor trip bypass breaker remote manual shunt trips prior to opening the main reactor trip breakers. |
| | Based on a review of completed testing, the reactor trip bypass breakers functioned properly during this previous testing. |
| | PREVIOUS SIMILAR EVENTS: |
| | There have been no previous HNP events related to improperly testing the reactor trip bypass breakers prior to placing them in service. |
| | CORRECTIVE ACTIONS COMPLETED: |
| | : 1. Procedures MST-10001 and MST-I0320 were revised to ensure that the reactor trip bypass breakers are properly tested before placing them in service. |
| | CORRECTIVE ACTIONS PLANNED: |
| | : 1. 'SAR section 7.2.2.2.3.10 will be revised to eliminate the conflicting wording pertaining to the testing of the reactor trip bypass breakers. This will be completed by November 15, 1996. |
| | : 2. This event will be reviewed with Maintenance and Operations personnel involved with developing, revising and reviewing procedures to emphasize the importance of fully understanding Technical Specification testing requirements. This will be completed by December 1, 1996.}} |
|
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18022B0551998-05-20020 May 1998
LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr
ML18016A4061998-04-30030 April 1998
LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive
ML18016A3841998-04-13013 April 1998
LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr
ML18016A3441998-03-12012 March 1998
LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV
ML18016A3291998-02-27027 February 1998
LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr
ML18016A3211998-02-20020 February 1998
LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr
ML18016A3131998-02-0909 February 1998
LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01
ML18016A2641997-12-18018 December 1997
LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr
ML18016A2501997-11-24024 November 1997
LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr
ML18016A2201997-10-22022 October 1997
LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures
ML18016A2081997-10-14014 October 1997
LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr
ML18016A2111997-10-14014 October 1997
LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced
ML18016A1931997-09-29029 September 1997
LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr
ML18016A1891997-09-12012 September 1997
LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr
ML18016A1881997-09-12012 September 1997
LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr
ML18012A8641997-08-18018 August 1997
LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr
ML18012A8581997-08-0808 August 1997
LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc
ML18012A8551997-08-0808 August 1997
LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls
ML18012A8471997-07-31031 July 1997
LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr
ML18012A8371997-07-24024 July 1997
LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold
ML18012A8291997-07-11011 July 1997
LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr
ML18012A8301997-07-0808 July 1997
LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr
ML18012A8241997-07-0202 July 1997
LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr
ML18022B0181997-06-13013 June 1997
LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr
ML18012A8081997-06-0909 June 1997
LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr
ML18012A8021997-06-0606 June 1997
LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr
ML18012A8011997-06-0404 June 1997
LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr
ML18012A7951997-05-29029 May 1997
LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr
ML18012A7891997-05-22022 May 1997
LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr
ML18012A7871997-05-19019 May 1997
LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr
ML18012A7761997-05-0707 May 1997
LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr
ML18012A7751997-05-0505 May 1997
LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr
ML18012A6291997-04-24024 April 1997
LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr
ML18022B0151997-04-17017 April 1997
LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr
ML18012A6041997-04-0303 April 1997
LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr
ML18012A6031997-03-31031 March 1997
LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr
1999-09-10
[Table view]
Category:RO)
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18022B0551998-05-20020 May 1998
LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr
ML18016A4061998-04-30030 April 1998
LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive
ML18016A3841998-04-13013 April 1998
LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr
ML18016A3441998-03-12012 March 1998
LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV
ML18016A3291998-02-27027 February 1998
LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr
ML18016A3211998-02-20020 February 1998
LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr
ML18016A3131998-02-0909 February 1998
LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01
ML18016A2641997-12-18018 December 1997
LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr
ML18016A2501997-11-24024 November 1997
LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr
ML18016A2201997-10-22022 October 1997
LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures
ML18016A2081997-10-14014 October 1997
LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr
ML18016A2111997-10-14014 October 1997
LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced
ML18016A1931997-09-29029 September 1997
LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr
ML18016A1891997-09-12012 September 1997
LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr
ML18016A1881997-09-12012 September 1997
LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr
ML18012A8641997-08-18018 August 1997
LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr
ML18012A8581997-08-0808 August 1997
LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc
ML18012A8551997-08-0808 August 1997
LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls
ML18012A8471997-07-31031 July 1997
LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr
ML18012A8371997-07-24024 July 1997
LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold
ML18012A8291997-07-11011 July 1997
LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr
ML18012A8301997-07-0808 July 1997
LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr
ML18012A8241997-07-0202 July 1997
LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr
ML18022B0181997-06-13013 June 1997
LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr
ML18012A8081997-06-0909 June 1997
LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr
ML18012A8021997-06-0606 June 1997
LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr
ML18012A8011997-06-0404 June 1997
LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr
ML18012A7951997-05-29029 May 1997
LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr
ML18012A7891997-05-22022 May 1997
LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr
ML18012A7871997-05-19019 May 1997
LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr
ML18012A7761997-05-0707 May 1997
LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr
ML18012A7751997-05-0505 May 1997
LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr
ML18012A6291997-04-24024 April 1997
LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr
ML18022B0151997-04-17017 April 1997
LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr
ML18012A6041997-04-0303 April 1997
LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr
ML18012A6031997-03-31031 March 1997
LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr
1999-09-10
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A9151999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18017A8621999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18017A8361999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr
ML18016B0151999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9851999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr
ML18017A8981999-05-12012 May 1999
Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines.
ML18016A9581999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr
ML18016A9011999-04-12012 April 1999
Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8941999-04-0505 April 1999
Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760
ML18016A9101999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr
ML18016A8661999-03-31031 March 1999
Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept.
ML18017A8931999-02-28028 February 1999
Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant.
ML18016A8551999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8531999-02-18018 February 1999
Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'.
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18022B0631999-02-0404 February 1999
Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings
ML20202J1161999-02-0101 February 1999
SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program
ML18016A8041999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7801998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr
ML18016A7671998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr
ML18016A9731998-11-28028 November 1998
Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr
ML18016A8351998-11-28028 November 1998
ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1.
ML18016A7411998-11-25025 November 1998
Rev 1 to Shnpp Cycle 9 Colr.
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A7071998-11-0303 November 1998
Rev 0 to Harris Unit 1 Cycle 9 Colr.
ML18016A7201998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr
ML20154F8701998-10-0606 October 1998
Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves
ML18016A6201998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr
ML18016A5971998-09-21021 September 1998
Rev 1 to Harris Unit 1 Cycle 8 Colr.
ML18016A5881998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr
ML18016A5071998-07-31031 July 1998
Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr
ML18016A9431998-07-0707 July 1998
Rev 1 to QAP Manual.
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A9371998-06-30030 June 1998
Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp.
ML18016A4861998-06-30030 June 1998
Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18016A4521998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr
ML18016A7711998-05-26026 May 1998
Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'.
1999-09-30
[Table view] |
Text
y CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION @BR:9609190064 DOC.DATE: 96/09/13 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power & I ight Co.
DONAHUE,J.W. Carolina Power & Light Co.
RECIP. NAME RECIPIENT AFFILIATION
SUBJECT:
LER 96-016-00:on 960814,reactor trip bypass breaker surveillance test, required by TSs not performed. Caused by inadequate procedures not ensuring testing done prior to A placing them in svc.Rev of deficient procedures.W/960912 ltr DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL ) SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:Application for permit renewal filed. 05000400 t" 0
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCI ID CODE/NAME LTTR ENCL R PD2-1 PD 1 1 LE,N 1 1 INTERNAL: ACRS 1 AEGD/SP-D/~B 2 2 AEOD/SPD/RRAB 1 FILE CENTE~R 1 1 NRR/DE/ECGB 1 NRR DE/EE~B 1 1 NRR/DE/EMEB 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 NRR/DSSA/SRXB 1 1 D RES/DSIR/EIB 1 RGN2 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 2 2 NOAC MURPHYiG.A 1 1 NOAC POOREgW. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 U
N NOTE TO ALL "RIDS" RECIPIENTS:
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FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26
Carolina Power 8a Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 SEP 1 8 1996 U.S. Nuclear Regulatory Commission Serial: HNP-96-158 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 96-016-00 Sir or Madam:
In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report describes a failure to perform proper surveillance testing on the reactor trip bypass breakers as required by Technical Specifications.
Sincerely, J. W. Donahue Director of Site Operations Harris Plant MV Enclosure c: Mr. J. B. Brady (HNP Senior Resident - NRC)
Mr. S. D. Ebneter (NRC Regional Administrator - Region II)
Mr. N. B. Le (NRC Project Manager - NRR)
'9609i90064 960rsti3 PDR ADOCK 05000400 S PDR State Road H34 New Hill NC
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150.0104 (4.95) EXPIRES 04/30/96 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THI MANDATORY WFORMATION COLLEC'I)ON REOUESTI 5M HRS. REPORTED lESSONS LEARNED ARE LICENSEE EVENT REPORT (LER) INCORPORATED (NTO THE UCENSING PROCESS AHD FEO BACK TO UIOUSTRY.
FORWARD COMMENTS REGAROU(G BURDEN ESTIMATE 'FO THE )NFORMATION ANO RECORDS MANAGEMENT BRANCH IT6 f33L US. NUCLEAR REGUtAIORY COMMISSION, (See reverse for required number of WASHINGTON, DC 20555600), ANO YO THE PAPERWORK REDUCTION PROJECT 0)50.
digits/characters for each block) OID(l OfFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.
FACIUTY NAME (I) OOCKET NUMBER 12) PAGE (3)
Harris Nuclear Plant Unit-1 50-400 1OF2 TITLE (4)
Failure to perform reactor trip bypass breaker surveillance testing required by Technical Specifications.
EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
FACIUTY NAME OOCKET NUMBER SEO E I REVISION MONTH OAY YEAR YEAR MONTH OAY YEAR NUMBER NUMBER 05000 FACIUTY NAME DOCKET NUMBER 8 14 96 016 0 9 13 96 05000 OPERATING THIS REPORT IS SUBMITTED PUR SUANT TO THE REQUIREMENTS OF 10 CFR B) (Check one or more) (11)
MODE (9) 20.2201(b) 20.2203(a)(2) (v) 50.73(a) (2) (i) 50.73(a)(2) (viii) 20.2203(a) (1) 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a)(2)(x)
POWER LEVEL (10) 1 00% 20.2203(a)(2) li) 20.2203(a) (3)(n) 50.73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c) (1) 50.73(a)(2)(v) Specify in Abstract below or in NAC Form 366A 20.2203(a) (2) (iv) 50.36(c)(2) 50.73(a)(2)(vii)
LICENSEE CONTACT FOR THIS LER (12)
TELEPHONE NUMBER Bnoivde Area Code)
Michael Verrilli Sr. Analyst - Licensing (919) 362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPROS TO NPROS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH OAY YEAR YES SUBMISSION (lf yes, complete EXPECTED SUBMISSION DATE). X NO DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single. spaced typewr((ten lines) (16)
On August 14, 1996, during a review of the Harris Nuclear Plant (HNP) Final Safety Analysis Report (FSAR), a deficiency was identified with surveillance testing for the reactor trip bypass breakers. Specifically, Technical Specifications require performing a remote manual shunt trip test prior to placing the reactor trip bypass breaker in service. Testing of the remote manual shunt trip at HNP has previously been conducted after the reactor trip bypass breakers were racked into the "connected" position and closed. Therefore, the breakers were actually in service and connected to the rod control system during previous testing of the remote manual shunt trips.
This condition was caused by inadequate surveillance test procedures which did not ensure testing of the reactor trip bypass breakers before placing them in service. This condition has existed since May 1986, when the procedures were revised to incorporate testing of the reactor trip bypass breakers. A probable cause for the May 1986 procedure error was a mis-interpretation of the term "in-service" and how it applied to the reactor trip bypass breakers.
Investigation also revealed that conflicting information in the FSAR could have been a contributing factor to the procedure error.
Immediate corrective actions included revising the deficient surveillance procedures. Additional corrective actions will include revising the deficient FSAR sections and reviewing the event with appropriate Operations and Maintenance personnel.
NRC fORM 366A US. NUCLEAR REGULATORT COMMISSION l496)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION TAG)LITT NAME n) OOCXET LER NUMBER IB) PAGE I3)
BEOUENTIAL RETIBION NUMBER NUMBER Shearon Harris Nuclear Plant ~ Unit rY1 50400 2 OF 2 96 - 016 - 00 TEXT IIImort spssv r's rsrprpsd. vsv sddr)drrrsl sopr'vs ol fYRC form 36QI ill)
EVENT DESCRIPTION:
On August 14, 1996, with the plant in mode 1, operating at 100% power, a deficiency was identified with the Train A and Train B Solid State Protection System Actuation Logic & Master Relay Tests (MST-I0001 and MST-I0320). This deficiency was identified during a review of the Harris Nuclear Plant (HNP) Final Safety Analysis Report (FSAR) which describes the testing process for the reactor trip bypass breakers (EIIS Code: JG-BKR). Specifically, Technical Specification Table 4.3-1 requires performing a remote manual shunt trip test prior to placing the reactor trip bypass breakers in service. However, testing of the remote manual shunt trip at HNP has previously been conducted after the reactor trip bypass breakers were racked into the "connected" position and closed. Therefore, the breakers were actually in service and connected to the rod control system during previous testing of the remote manual shunt trips, which constitutes a violation of Technical Specifications and is reportable per 10CFR50.73(a)(2)(i)(b).
CAUSE:
The cause of this event was inadequate surveillance test procedures. MST-I0001 and MST-I0320 did not ensure that the reactor trip bypass breakers were tested before being placed in service. These breakers have a "test" position which should have been used, rather than racking the breaker into the "connected" position and closing them, which actually connected the reactor trip bypass breakers to the rod control system and placed them in service. This condition has existed since May 1986, when both procedures were revised to incorporate testing of the reactor trip bypass breakers. A probable cause for the May 1986 procedure error was a mis-interpretation of the term "in-service" and how it applied to the reactor trip bypass breakers. Investigation also revealed that conflicting information in FSAR section 7.2.2.2.3.10 could have been a contributing factor to the pr'ocedure error. This section incorrectly states that HNP "does not propose to verify the operability of each bypass breaker prior to placing it in service each time the main reactor trip breakers are to be tested."
SAFETY SIGNIFICANCE:
There were no safety consequences as a result of this event. MST-I0001 and MST-I0320 have provided previous testing of the reactor trip bypass breaker remote manual shunt trips prior to opening the main reactor trip breakers.
Based on a review of completed testing, the reactor trip bypass breakers functioned properly during this previous testing.
PREVIOUS SIMILAR EVENTS:
There have been no previous HNP events related to improperly testing the reactor trip bypass breakers prior to placing them in service.
CORRECTIVE ACTIONS COMPLETED:
- 1. Procedures MST-10001 and MST-I0320 were revised to ensure that the reactor trip bypass breakers are properly tested before placing them in service.
CORRECTIVE ACTIONS PLANNED:
- 1. 'SAR section 7.2.2.2.3.10 will be revised to eliminate the conflicting wording pertaining to the testing of the reactor trip bypass breakers. This will be completed by November 15, 1996.
- 2. This event will be reviewed with Maintenance and Operations personnel involved with developing, revising and reviewing procedures to emphasize the importance of fully understanding Technical Specification testing requirements. This will be completed by December 1, 1996.
