|
|
Line 17: |
Line 17: |
| =Text= | | =Text= |
| {{#Wiki_filter:PRIORITY (ACCELERATED RIDS PROCESSING) | | {{#Wiki_filter:PRIORITY (ACCELERATED RIDS PROCESSING) |
| REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9509280061 DOC.DATE: 95/09/22 NOTARIZED: | | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION VERRILLI,M. | | ACCESSION NBR:9509280061 DOC.DATE: 95/09/22 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 P AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power & Light Co. |
| Carolina Power&Light Co.DONAHUE,J.W. | | DONAHUE,J.W. Carolina Power & Light Co. |
| Carolina Power&Light Co.RECIP.NAME RECIPIENT AFFILIATXON DOCKET 05000400 P | | RECIP.NAME RECIPIENT AFFILIATXON |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER 95-006-00:on 950824,determined discrepancy re design of RAB EES constituted condition outside design basis.Cause still under investigation. | | LER 95-006-00:on 950824,determined discrepancy re design of RAB EES constituted condition outside design basis. Cause still under investigation. Established administrative leakage limit of 1 gallon per hour.W/950922 ltr. |
| Established administrative leakage limit of 1 gallon per hour.W/950922 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED LTR ENCL SIZE TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:Application for permit renewal filed.05000400 T RECIPIENT ID CODE/NAME PD2-1 PD INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DSSA/SPLB NRR/DSSA/SRXB RGN2 FILE 01 EXTERNAL: L ST LOBBY WARD NOAC MURPHY,G.A 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 1 1 RECIPXENT ID CODE/NAME LE,N AEO~~RAB ENT N~'D E B NRR/DISP/PIPB NRR/DRCH/HICB NRR/DRPM/PECB NRR/DSSA/SPSB/B RES/DSIR/EIB LITCO BRYCE,J H NOAC POORE,W.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 D C'M'N'OTE TO ALL"RIDS" RECZPZENTS: | | DISTRIBUTION CODE: IE22T COPIES RECEIVED LTR ENCL SIZE TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESKS ROOM OWFN 5DS (415 2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUXRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 27 Carolina Power 8 Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 SEP 22 1995 Letter Number: HO-950702 U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 95-006-00 Gentlemen:
| | NOTES:Application for permit renewal filed. 05000400 T |
| In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted.
| | RECIPIENT COPIES RECIPXENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 PD 1 1 LE,N 1 1 INTERNAL: ACRS AEOD/SPD/RRAB 1 1 AEO ~~RAB 2 2 1 1 ENT 1 1 NRR/DE/ECGB 1 1 N~'D E B 1 1 NRR/DE/EMEB 1 1 NRR/DISP/PIPB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 D NRR/DRCH/HOLB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SPSB/B 1 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 2 2 C ' |
| This report concerns an identified condition that was determined to be outside the design basis of the plant, related to the Reactor Auxiliary Building Emergency Exhaust System.Sincerely, J.W.D nahue General Manager Harris Plant MV Enclosure Mr.S.D.Ebneter (NRC-RII)Mr.N.B.Le (NRC-PM/NRR)Mr.S.A.Elrod (NRC-SHNPP)9S0928006i 950922 PDR ADOCK OS000400 S PDR State Road 1134 New Hill NC NRC-FORN 366 (5-92)t U.S.NUCLEAR REGULATORY COHHISSION LICENSEE EVENT REPORT (LER)FACILITY NAHE (1)Shearon Harris Nuclear Plant-Unit
| | NOAC MURPHY,G.A 1 1 NOAC POORE,W. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 M ' |
| //1 (See reverse for required number of digits/characters for each block)APPROVED BY OHB NO.3150-0104 EXPIRES 4/30/98 ESTINTED BURDEN PER RESPONSE TO CQNPLY WITH THIS INFORNTION COLLECTION REQUEST: 50.0 HRS.REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FEO BACK TO INDUSTRY.FORWARD CQNNENTS REGARDING BURDEN ESTINTE TO THE INFORNTION AND RECORDS NNAGEHENT BRANCH U.S.NUCLEAR REGULATORY CDYiNISSION. | | N |
| WASHINGTON.
| | 'O TO ALL "RIDS" RECZPZENTS: |
| DC 20555-0001.
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESKS ROOM OWFN 5DS (415 2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| ANO TO THE PAPERWORK REDUCTION PROJECT (3150-0104).
| | FULL TEXT CONVERSION REQUXRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 27 |
| OFFICE OF NNAGENENT AND BUDGET.WASHIHGTON.
| | |
| OC 20503.DOCKET NUMBER (2)PAGE (3)1 of 3 TITLE (4)Emergency Core Cooling System piping not fully contained within Reactor Auxiliary Building Emergency Exhaust S stem bounda resultin in condition outside desi n basis.EVENT DATE (5)HONTH DAY YEAR YEAR LER HUNBER (6)SEQUENTIAL NUNBER 08 24 95 95--006 REVISION NUYBER 00 NONTH DAY 09 22 95 REPORT DATE (7)FACILITY NANE FACILITY HANE DOCKET NUNBER 05000 DXKET NUHBER 05000 OTHER FACILITIES INVOLVED (8)OPERATING HODE (9)POWER LEVEL (10)76K THIS REPORT IS SUBHITTED PURSUANT 20.402(b)20.405(a)(1)(i) 20.405(a)(1)(ii) e)(ll)TO THE REQUIREHENTS OF 10 CFR 5: (Check one or mor 20.405(c)50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.36(c)(l) 50.36(c)(2) 73.71(b)73.71(c)OTHER 20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)(l)(v) 50.73(a)(2)(i)
| | Carolina Power 8 Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 SEP 22 1995 Letter Number: HO-950702 U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 95-006-00 Gentlemen: |
| X 50.73(a)(2)(ii) 50.73(a)(2)(iii)
| | In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report concerns an identified condition that was determined to be outside the design basis of the plant, related to the Reactor Auxiliary Building Emergency Exhaust System. |
| LICENSEE CONTACT FOR THIS LER (12)50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x)(Specify in Abstract below and in Text, NRC Form 366A)NANE Michael Verrilli Sr.Analyst-Licensing TELEPHONE NUNBER (Include Area Code)(919)362-2303 COHPLETE ONE LINE FOR EACH COHPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COHPONENT NNUFACTURER TO NPRDS",''''',,:i'.ii<j;:"',:;:ll::;:
| | Sincerely, J. W. D nahue General Manager Harris Plant MV Enclosure Mr. S. D. Ebneter (NRC - RII) |
| CAUSE SYSTEH CONPONENT NNUFACTURER REPORTABLE TO NPROS SUPPLEHENTAL REPORT EXPECTED (14)X YES (If yes.complete EXPECTED SUBNISSION DATE).EXPECTED SUBMISSION DATE (15)HONTH DAY YEAR 11 30 95 ABSTRACT (Limit to 1400 spaces.i.e..approximately 15 single-spaced typewritten lines)(16)On August 24, 1995, a discrepancy related to the original design of the Reactor Auxiliary Building (RAB)Emergency Exhaust System was determined to constitute a condition outside the design basis of the plant as described in the Harris Plant Final Safety Analysis Report (FSAR).This discrepancy pertains to a portion of Emergency Core Cooling System (ECCS)piping that is physically located outside of the boundary of the RAB Emergency Exhaust System envelope, which adversely impacts the dose assessments that were performed in the FSAR.In the event leakage consisting of highly radioactive water occurred from this section of piping during a postulated design basis loss of coolant accident (LOCA), the discrepancy would introduce non-conservative factors into the FSAR analysis performed to determine dose rates resulting from ECCS leakage outside Containment.
| | Mr. N. B. Le (NRC - PM/NRR) |
| Specifically, the FSAR dose rate analysis assumed that released effluent would first be processed through the RAB Emergency Exhaust System filtration units, prior to being released to the atmosphere. | | Mr. S. A. Elrod (NRC - SHNPP) 9S0928006i 950922 PDR ADOCK OS000400 S PDR State Road 1134 New Hill NC |
| This was based on the fact that all leakage was assumed to be contained within the RAB Emergency Exhaust System envelope and did not factor in the potential increased dose resulting from"unfiltered" leakage from the RAB which could occur outside the system boundary.The cause of this condition is still under investigation and will be provided in a supplement to this LER.Compensatory measures have been established to allow for continued operation. | | |
| These measures include development of administrative ECCS leakage limits, monitoring and inspection of the subject ECCS piping and administrative controls to maintain the RAB boundary to minimize unfiltered leakage from being released to the atmosphere in the event of the postulated accident scenario.A 1-hour non-emergency report was made to the NRC per 10CFR50.72, via the Emergency Notification System. | | NRC- FORN (5-92) 366 LICENSEE EVENT REPORT t U.S. NUCLEAR REGULATORY COHHISSION (LER) |
| NRC FORM 366A (5-92)LICENSEE EVENT REPORT (LER)t APPROVED BY OMB NO.3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714).U.S.NUCLEAR REGULATORY CONISSION. | | APPROVED BY OHB NO. |
| WASHINGTON. | | EXPIRES 3150-0104 4/30/98 ESTINTED BURDEN PER RESPONSE TO CQNPLY WITH THIS INFORNTION COLLECTION REQUEST: 50.0 HRS. |
| OC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104) | | REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FEO BACK TO INDUSTRY. |
| .OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)Shearon Harris Nuclear Plant-Unit¹I DOCKET NUMBER (2)05000/400 YEAR 95 LER NUMBER (6)SEQUENTIAL NUMBER 006 REVISION NUMBER 00 PAGE (3)2 OF 3 TEXT (If more space'is required.use additional copies of NRC Form 3664)(17)EVENT DESCRIPTION: | | (See reverse for required number of digits/characters for each block) FORWARD CQNNENTS REGARDING BURDEN ESTINTE TO THE INFORNTION AND RECORDS NNAGEHENT BRANCH U.S. NUCLEAR REGULATORY CDYiNISSION. WASHINGTON. |
| In July 1995, during a review of regulatory issues, the validity of the dose assessment analysis for Emergency Core Cooling System (ECCS)leakage outside of containment, contained in section 15.6.5 of the Harris Final Safety Analysis Report (FSAR), was questioned by Harris plant personnel. | | DC 20555-0001. ANO TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF NNAGENENT AND BUDGET. WASHIHGTON. OC 20503. |
| Additional research into this analysis was performed by CP8cL Engineering personnel. | | FACILITY NAHE (1) DOCKET NUMBER (2) PAGE (3) |
| The main concern was that the methodology of the ECCS leakage assumptions in the dose calculation did not match the assumptions in the Standard Review Plan (SRP).After reviewing sufficient information confirming that a potential problem did indeed exist, a Condition Report (CR¹95-1862)was initiated on August 7, 1995, and a formal investigation was initiated to resolve the concern.After re-evaluating the ECCS components located outside the boundary of the RAB Emergency Exhaust System and the corresponding assumed external leakage rates, it became apparent that dose rates exceeded those values originally used to establish the licensing basis of the plant.A 1-hour non-emergency report for a condition outside the design basis of the plant was made to the NRC per 10CFR50.72, via the Emergency Notification System on August 24, 1995.Continued operation was justified with compensatory measures that included establishment of an ECCS leakage limit of 1 gallon per hour to ensure that off site dose remains within 10CFR100 limits.In addition, the affected piping areas are being monitored for leakage and radiation monitor trends are being periodically reviewed by operators as an early means of leakage detection. | | Shearon Harris Nuclear Plant-Unit //1 1 of 3 TITLE (4) Emergency Core Cooling System piping not fully contained within Reactor Auxiliary Building Emergency Exhaust S stem bounda resultin in condition outside desi n basis. |
| Further engineering analysis efforts continue and the results of these will be provided with a supplement to this Licensee Event Report.CAUSE/SAFETY SIGNIFICANCE: | | EVENT DATE (5) LER HUNBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| The cause of this condition and the associated safety significance are still under investigation. | | SEQUENTIAL REVISION FACILITY NANE DOCKET NUNBER HONTH DAY YEAR YEAR NUNBER NUYBER NONTH DAY 05000 08 24 95 95 -- 006 00 09 22 95 FACILITY HANE DXKET NUHBER 05000 OPERATING THIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREHENTS OF 10 CFR 5: (Check one or mor e) (ll) |
| Information will be provided in a supplement to this LER upon completion of a formal root cause investigation and additional engineering analysis to evaluate the resulting dose from ECCS leakage.PREVIOUS SIMILAR LERs: There have been no similar LER's submitted. | | HODE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b) |
| | POWER 20.405(a)(1)(i) 50.36(c)(l) 50.73(a)(2)(v) 73.71(c) 76K LEVEL (10) 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1)(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) (Specify in 20.405(a)(1)(iv) X 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) Abstract below and in Text, 20.405(a)(l)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) NRC Form 366A) |
| | LICENSEE CONTACT FOR THIS LER (12) |
| | NANE TELEPHONE NUNBER (Include Area Code) |
| | Michael Verrilli Sr. Analyst - Licensing (919) 362-2303 COHPLETE ONE LINE FOR EACH COHPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| | CAUSE SYSTEM COHPONENT NNUFACTURER REPORTABLE TO NPRDS |
| | ",''''',,:i'.ii<j;:"',:;:ll::;: CAUSE SYSTEH CONPONENT NNUFACTURER TO NPROS SUPPLEHENTAL REPORT EXPECTED (14) HONTH DAY YEAR EXPECTED YES SUBMISSION X ( If yes. complete EXPECTED SUBNISSION DATE). DATE (15) 11 30 95 ABSTRACT (Limit to 1400 spaces. i.e.. approximately 15 single-spaced typewritten lines) (16) |
| | On August 24, 1995, a discrepancy related to the original design of the Reactor Auxiliary Building (RAB) Emergency Exhaust System was determined to constitute a condition outside the design basis of the plant as described in the Harris Plant Final Safety Analysis Report (FSAR). This discrepancy pertains to a portion of Emergency Core Cooling System (ECCS) piping that is physically located outside of the boundary of the RAB Emergency Exhaust System envelope, which adversely impacts the dose assessments that were performed in the FSAR. In the event leakage consisting of highly radioactive water occurred from this section of piping during a postulated design basis loss of coolant accident (LOCA), the discrepancy would introduce non-conservative factors into the FSAR analysis performed to determine dose rates resulting from ECCS leakage outside Containment. Specifically, the FSAR dose rate analysis assumed that released effluent would first be processed through the RAB Emergency Exhaust System filtration units, prior to being released to the atmosphere. This was based on the fact that all leakage was assumed to be contained within the RAB Emergency Exhaust System envelope and did not factor in the potential increased dose resulting from "unfiltered" leakage from the RAB which could occur outside the system boundary. |
| | The cause of this condition is still under investigation and will be provided in a supplement to this LER. |
| | Compensatory measures have been established to allow for continued operation. These measures include development of administrative ECCS leakage limits, monitoring and inspection of the subject ECCS piping and administrative controls to maintain the RAB boundary to minimize unfiltered leakage from being released to the atmosphere in the event of the postulated accident scenario. A 1-hour non-emergency report was made to the NRC per 10CFR50.72, via the Emergency Notification System. |
| | |
| | NRC FORM (5-92) 366A LICENSEE EVENT REPORT (LER) t APPROVED BY OMB NO. |
| | ESTIMATED BURDEN EXPIRES PER 3150-0104 5/31/95 |
| | |
| | ===RESPONSE=== |
| | THIS INFORMATION COLLECTION REQUEST: |
| | TO COMPLY WITH 50.0 HRS. |
| | FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714). U.S. NUCLEAR REGULATORY CONISSION. |
| | WASHINGTON. OC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104) . OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. |
| | FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | SEQUENTIAL REVISION YEAR NUMBER Shearon Harris Nuclear Plant - Unit ¹I 05000/400 NUMBER 2 OF 3 95 006 00 TEXT (If more space 'is required. use additional copies of NRC Form 3664) (17) |
| | EVENT DESCRIPTION: |
| | In July 1995, during a review of regulatory issues, the validity of the dose assessment analysis for Emergency Core Cooling System (ECCS) leakage outside of containment, contained in section 15.6.5 of the Harris Final Safety Analysis Report (FSAR), was questioned by Harris plant personnel. Additional research into this analysis was performed by CP8cL Engineering personnel. The main concern was that the methodology of the ECCS leakage assumptions in the dose calculation did not match the assumptions in the Standard Review Plan (SRP). After reviewing sufficient information confirming that a potential problem did indeed exist, a Condition Report (CR ¹95-1862) was initiated on August 7, 1995, and a formal investigation was initiated to resolve the concern. After re-evaluating the ECCS components located outside the boundary of the RAB Emergency Exhaust System and the corresponding assumed external leakage rates, it became apparent that dose rates exceeded those values originally used to establish the licensing basis of the plant. |
| | A 1-hour non-emergency report for a condition outside the design basis of the plant was made to the NRC per 10CFR50.72, via the Emergency Notification System on August 24, 1995. |
| | Continued operation was justified with compensatory measures that included establishment of an ECCS leakage limit of 1 gallon per hour to ensure that off site dose remains within 10CFR100 limits. In addition, the affected piping areas are being monitored for leakage and radiation monitor trends are being periodically reviewed by operators as an early means of leakage detection. Further engineering analysis efforts continue and the results of these will be provided with a supplement to this Licensee Event Report. |
| | CAUSE / SAFETY SIGNIFICANCE: |
| | The cause of this condition and the associated safety significance are still under investigation. Information will be provided in a supplement to this LER upon completion of a formal root cause investigation and additional engineering analysis to evaluate the resulting dose from ECCS leakage. |
| | PREVIOUS SIMILAR LERs: |
| | There have been no similar LER's submitted. |
| CORRECTIVE ACTIONS COMPLETED: | | CORRECTIVE ACTIONS COMPLETED: |
| The following compensatory measures have been established and are applicable for operation in Modes 1-4 pending completion of the engineering analysis: 1.An administrative leakage limit of 1 gallon per hour has been established for this portion of the ECCS system.This administrative limit provides assurance that offsite doses would remain within 10CFR100 limits.2.The affected piping areas are being periodically inspected for leakage by Operations personnel. | | The following compensatory measures have been established and are applicable for operation in Modes 1-4 pending completion of the engineering analysis: |
| 3.Radiation monitor trends are being periodically reviewed by Operations personnel as an early means of leakage detection. | | : 1. An administrative leakage limit of 1 gallon per hour has been established for this portion of the ECCS system. This administrative limit provides assurance that offsite doses would remain within 10CFR100 limits. |
| 4.Administrative controls were developed to maintain the RAB boundary to minimize unfiltered leakage. | | : 2. The affected piping areas are being periodically inspected for leakage by Operations personnel. |
| NRC FORM 366A (5-92)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)t APPROVED BY OMB NO.3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714).U.S.NUCLEAR REGULATORY COMMISSION. | | : 3. Radiation monitor trends are being periodically reviewed by Operations personnel as an early means of leakage detection. |
| WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104) | | : 4. Administrative controls were developed to maintain the RAB boundary to minimize unfiltered leakage. |
| .OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.PAGE (3)FACILITY NAME (1)Shearon Harris Nuclear Plant-Unit¹I DXKET NUMBER (2)05000/400 YEAR 95 LER NUMBER (6)SEQUENTIAL NUMBER 006 REVISION N(1vBER 00 3 OF 3 TEXT (If more space is required, use additional copies of/(RC Form 3664)(17)CORRECTIVE ACTIONS PLANNED: 1.A root cause investigation will be completed. | | |
| 2.Additional engineering analysis will be performed to determine the impact this design has on applicable dose rate calculations. | | NRC FORM (5-92) 366A LICENSEE EVENT REPORT U.S. NUCLEAR REGULATORY COMMISSION (LER) t APPROVED BY OMB NO. |
| '.Revisions will be made to the Harris FSAR as appropriate and will be submitted to the NRC.4.A supplement to this LER will be developed and submitted to the NRC.EIIS INFORMATION: | | EXPIRES 3150-0104 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. |
| S stem Name/Code: | | FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714). U.S. NUCLEAR REGULATORY COMMISSION. |
| Chemical and Volume Control System (CVCS)-CB Residual Heat Removal/Low Pressure Safety Injection-BP High Pressure Safety Injection-BQ}} | | WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104) . OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. |
| | FACILITY NAME (1) DXKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | SEQUENTIAL REVISION YEAR Shearon Harris Nuclear Plant - Unit ¹I 05000/400 NUMBER N(1vBER 3 OF 3 95 006 00 TEXT (If more space is required, use additional copies of /(RC Form 3664) (17) |
| | CORRECTIVE ACTIONS PLANNED: |
| | : 1. A root cause investigation will be completed. |
| | : 2. Additional engineering analysis will be performed to determine the impact this design has on applicable dose rate calculations. |
| | '. |
| | Revisions will be made to the Harris FSAR as appropriate and will be submitted to the NRC. |
| | : 4. A supplement to this LER will be developed and submitted to the NRC. |
| | EIIS INFORMATION: |
| | S stem Name/Code: |
| | Chemical and Volume Control System (CVCS) - CB Residual Heat Removal/Low Pressure Safety Injection - BP High Pressure Safety Injection - BQ}} |
|
---|
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
PRIORITY (ACCELERATED RIDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9509280061 DOC.DATE: 95/09/22 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 P AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power & Light Co.
DONAHUE,J.W. Carolina Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATXON
SUBJECT:
LER 95-006-00:on 950824,determined discrepancy re design of RAB EES constituted condition outside design basis. Cause still under investigation. Established administrative leakage limit of 1 gallon per hour.W/950922 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED LTR ENCL SIZE TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:Application for permit renewal filed. 05000400 T
RECIPIENT COPIES RECIPXENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 PD 1 1 LE,N 1 1 INTERNAL: ACRS AEOD/SPD/RRAB 1 1 AEO ~~RAB 2 2 1 1 ENT 1 1 NRR/DE/ECGB 1 1 N~'D E B 1 1 NRR/DE/EMEB 1 1 NRR/DISP/PIPB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 D NRR/DRCH/HOLB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SPSB/B 1 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 2 2 C '
NOAC MURPHY,G.A 1 1 NOAC POORE,W. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 M '
N
'O TO ALL "RIDS" RECZPZENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESKS ROOM OWFN 5DS (415 2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
FULL TEXT CONVERSION REQUXRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 27
Carolina Power 8 Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 SEP 22 1995 Letter Number: HO-950702 U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 95-006-00 Gentlemen:
In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report concerns an identified condition that was determined to be outside the design basis of the plant, related to the Reactor Auxiliary Building Emergency Exhaust System.
Sincerely, J. W. D nahue General Manager Harris Plant MV Enclosure Mr. S. D. Ebneter (NRC - RII)
Mr. N. B. Le (NRC - PM/NRR)
Mr. S. A. Elrod (NRC - SHNPP) 9S0928006i 950922 PDR ADOCK OS000400 S PDR State Road 1134 New Hill NC
NRC- FORN (5-92) 366 LICENSEE EVENT REPORT t U.S. NUCLEAR REGULATORY COHHISSION (LER)
APPROVED BY OHB NO.
EXPIRES 3150-0104 4/30/98 ESTINTED BURDEN PER RESPONSE TO CQNPLY WITH THIS INFORNTION COLLECTION REQUEST: 50.0 HRS.
REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FEO BACK TO INDUSTRY.
(See reverse for required number of digits/characters for each block) FORWARD CQNNENTS REGARDING BURDEN ESTINTE TO THE INFORNTION AND RECORDS NNAGEHENT BRANCH U.S. NUCLEAR REGULATORY CDYiNISSION. WASHINGTON.
DC 20555-0001. ANO TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF NNAGENENT AND BUDGET. WASHIHGTON. OC 20503.
FACILITY NAHE (1) DOCKET NUMBER (2) PAGE (3)
Shearon Harris Nuclear Plant-Unit //1 1 of 3 TITLE (4) Emergency Core Cooling System piping not fully contained within Reactor Auxiliary Building Emergency Exhaust S stem bounda resultin in condition outside desi n basis.
EVENT DATE (5) LER HUNBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
SEQUENTIAL REVISION FACILITY NANE DOCKET NUNBER HONTH DAY YEAR YEAR NUNBER NUYBER NONTH DAY 05000 08 24 95 95 -- 006 00 09 22 95 FACILITY HANE DXKET NUHBER 05000 OPERATING THIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREHENTS OF 10 CFR 5: (Check one or mor e) (ll)
HODE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)
POWER 20.405(a)(1)(i) 50.36(c)(l) 50.73(a)(2)(v) 73.71(c) 76K LEVEL (10) 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1)(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) (Specify in 20.405(a)(1)(iv) X 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) Abstract below and in Text, 20.405(a)(l)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) NRC Form 366A)
LICENSEE CONTACT FOR THIS LER (12)
NANE TELEPHONE NUNBER (Include Area Code)
Michael Verrilli Sr. Analyst - Licensing (919) 362-2303 COHPLETE ONE LINE FOR EACH COHPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYSTEM COHPONENT NNUFACTURER REPORTABLE TO NPRDS
",,,:i'.ii<j;:"',:;:ll::;: CAUSE SYSTEH CONPONENT NNUFACTURER TO NPROS SUPPLEHENTAL REPORT EXPECTED (14) HONTH DAY YEAR EXPECTED YES SUBMISSION X ( If yes. complete EXPECTED SUBNISSION DATE). DATE (15) 11 30 95 ABSTRACT (Limit to 1400 spaces. i.e.. approximately 15 single-spaced typewritten lines) (16)
On August 24, 1995, a discrepancy related to the original design of the Reactor Auxiliary Building (RAB) Emergency Exhaust System was determined to constitute a condition outside the design basis of the plant as described in the Harris Plant Final Safety Analysis Report (FSAR). This discrepancy pertains to a portion of Emergency Core Cooling System (ECCS) piping that is physically located outside of the boundary of the RAB Emergency Exhaust System envelope, which adversely impacts the dose assessments that were performed in the FSAR. In the event leakage consisting of highly radioactive water occurred from this section of piping during a postulated design basis loss of coolant accident (LOCA), the discrepancy would introduce non-conservative factors into the FSAR analysis performed to determine dose rates resulting from ECCS leakage outside Containment. Specifically, the FSAR dose rate analysis assumed that released effluent would first be processed through the RAB Emergency Exhaust System filtration units, prior to being released to the atmosphere. This was based on the fact that all leakage was assumed to be contained within the RAB Emergency Exhaust System envelope and did not factor in the potential increased dose resulting from "unfiltered" leakage from the RAB which could occur outside the system boundary.
The cause of this condition is still under investigation and will be provided in a supplement to this LER.
Compensatory measures have been established to allow for continued operation. These measures include development of administrative ECCS leakage limits, monitoring and inspection of the subject ECCS piping and administrative controls to maintain the RAB boundary to minimize unfiltered leakage from being released to the atmosphere in the event of the postulated accident scenario. A 1-hour non-emergency report was made to the NRC per 10CFR50.72, via the Emergency Notification System.
NRC FORM (5-92) 366A LICENSEE EVENT REPORT (LER) t APPROVED BY OMB NO.
ESTIMATED BURDEN EXPIRES PER 3150-0104 5/31/95
RESPONSE
THIS INFORMATION COLLECTION REQUEST:
TO COMPLY WITH 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714). U.S. NUCLEAR REGULATORY CONISSION.
WASHINGTON. OC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104) . OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
SEQUENTIAL REVISION YEAR NUMBER Shearon Harris Nuclear Plant - Unit ¹I 05000/400 NUMBER 2 OF 3 95 006 00 TEXT (If more space 'is required. use additional copies of NRC Form 3664) (17)
EVENT DESCRIPTION:
In July 1995, during a review of regulatory issues, the validity of the dose assessment analysis for Emergency Core Cooling System (ECCS) leakage outside of containment, contained in section 15.6.5 of the Harris Final Safety Analysis Report (FSAR), was questioned by Harris plant personnel. Additional research into this analysis was performed by CP8cL Engineering personnel. The main concern was that the methodology of the ECCS leakage assumptions in the dose calculation did not match the assumptions in the Standard Review Plan (SRP). After reviewing sufficient information confirming that a potential problem did indeed exist, a Condition Report (CR ¹95-1862) was initiated on August 7, 1995, and a formal investigation was initiated to resolve the concern. After re-evaluating the ECCS components located outside the boundary of the RAB Emergency Exhaust System and the corresponding assumed external leakage rates, it became apparent that dose rates exceeded those values originally used to establish the licensing basis of the plant.
A 1-hour non-emergency report for a condition outside the design basis of the plant was made to the NRC per 10CFR50.72, via the Emergency Notification System on August 24, 1995.
Continued operation was justified with compensatory measures that included establishment of an ECCS leakage limit of 1 gallon per hour to ensure that off site dose remains within 10CFR100 limits. In addition, the affected piping areas are being monitored for leakage and radiation monitor trends are being periodically reviewed by operators as an early means of leakage detection. Further engineering analysis efforts continue and the results of these will be provided with a supplement to this Licensee Event Report.
CAUSE / SAFETY SIGNIFICANCE:
The cause of this condition and the associated safety significance are still under investigation. Information will be provided in a supplement to this LER upon completion of a formal root cause investigation and additional engineering analysis to evaluate the resulting dose from ECCS leakage.
PREVIOUS SIMILAR LERs:
There have been no similar LER's submitted.
CORRECTIVE ACTIONS COMPLETED:
The following compensatory measures have been established and are applicable for operation in Modes 1-4 pending completion of the engineering analysis:
- 1. An administrative leakage limit of 1 gallon per hour has been established for this portion of the ECCS system. This administrative limit provides assurance that offsite doses would remain within 10CFR100 limits.
- 2. The affected piping areas are being periodically inspected for leakage by Operations personnel.
- 3. Radiation monitor trends are being periodically reviewed by Operations personnel as an early means of leakage detection.
- 4. Administrative controls were developed to maintain the RAB boundary to minimize unfiltered leakage.
NRC FORM (5-92) 366A LICENSEE EVENT REPORT U.S. NUCLEAR REGULATORY COMMISSION (LER) t APPROVED BY OMB NO.
EXPIRES 3150-0104 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714). U.S. NUCLEAR REGULATORY COMMISSION.
WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104) . OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1) DXKET NUMBER (2) LER NUMBER (6) PAGE (3)
SEQUENTIAL REVISION YEAR Shearon Harris Nuclear Plant - Unit ¹I 05000/400 NUMBER N(1vBER 3 OF 3 95 006 00 TEXT (If more space is required, use additional copies of /(RC Form 3664) (17)
CORRECTIVE ACTIONS PLANNED:
- 1. A root cause investigation will be completed.
- 2. Additional engineering analysis will be performed to determine the impact this design has on applicable dose rate calculations.
'.
Revisions will be made to the Harris FSAR as appropriate and will be submitted to the NRC.
- 4. A supplement to this LER will be developed and submitted to the NRC.
EIIS INFORMATION:
S stem Name/Code:
Chemical and Volume Control System (CVCS) - CB Residual Heat Removal/Low Pressure Safety Injection - BP High Pressure Safety Injection - BQ