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| issue date = 02/16/1996
| issue date = 02/16/1996
| title = LER 96-002-00:on 960117,failure to Perform Required Surveillance Testing During Planned Maint Outage in Oct 1994 Identified.Caused by Personnel Error.Personnel Involved counseled.W/960216 Ltr
| title = LER 96-002-00:on 960117,failure to Perform Required Surveillance Testing During Planned Maint Outage in Oct 1994 Identified.Caused by Personnel Error.Personnel Involved counseled.W/960216 Ltr
| author name = DONAHUE J W, VERRILLI M
| author name = Donahue J, Verrilli M
| author affiliation = CAROLINA POWER & LIGHT CO.
| author affiliation = CAROLINA POWER & LIGHT CO.
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:~CATEGORY ly REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9602230145 DOC.DATE: 96/02/16 NOTARIZED:
{{#Wiki_filter:~           CATEGORY               ly 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:9602230145         DOC.DATE:   96/02/16   NOTARIZED: NO           DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina                 05000400 AUTH. NAME         AUTHOR AFFILIATION VERRILLI,M.         Carolina Power 6 Light Co.
Carolina Power 6 Light 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


==SUBJECT:==
==SUBJECT:==
LER 96-002-00:on 960117,failure to perform required surveillance testing during planned maint outage in Oct 1994 identified.
LER   96-002-00:on 960117,failure to perform required surveillance testing during planned maint outage in Oct             1994 identified. Caused by personnel error. Personnel involved counseled.W/960216     ltr.
Caused by personnel error.Personnel involved counseled.W/960216 ltr.DZSTRZBUTZON CODE: ZE22T COPZES RECEZVED:LTR t ENCL I SZZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:Application for permit renewal filed.05000400 G 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 MURPHYEG.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 RECIPIENT ID CODE/NAME LE,N AB LE CENT NRR LB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2 FILE 01 LITCO BRYCEEJ 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 0 E N NOTE TO ALL"RZDS" RECIPIENTS:
DZSTRZBUTZON CODE: ZE22T COPZES RECEZVED:LTR t ENCL I                 SZZE:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK/ROOM OWFN 5D-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  
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:Application for permit renewal         filed.                             05000400 G RECIPIENT           COPIES              RECIPIENT        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 1
1        LE CENT AB        2 1
2 1
NRR/DE/ECGB             1      1      NRR        LB          1    1 NRR/DE/EMEB             1      1      NRR/DRCH/HHFB          1    1 NRR/DRCH/HICB            1      1      NRR/DRCH/HOLB          1     1 NRR/DRCH/HQMB            1      1      NRR/DRPM/PECB          1    1 NRR/DSSA/SPLB            1      1      NRR/DSSA/SRXB         1    1            D RES/DSIR/EIB            1      1      RGN2     FILE   01     1    1 0
EXTERNAL: L ST LOBBY WARD          1      1      LITCO BRYCEEJ     H   2    2 NOAC MURPHYEG.A          1      1      NOAC POORE,W.         1     1 NRC PDR                  1     1     NUDOCS FULL TXT        1     1 E
N NOTE TO ALL "RZDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK/
ROOM OWFN 5D-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    4 Light Company Harris Nuclear Plant PO 8ox 165 New Hill NC 27562 FEB 16 1996 U.S. Nuclear Regulatory Commission                                            Serial: HNP-96-022 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 96-002-00 Gentlemen:
In accordance with Title      10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report concerns a personnel error during a procedure revision performed in June 1993 that resulted in the failure to perform surveillance testing for the Charging/Safety Injection Pump Alternate Min-Flow Motor Operated Valves.
Sincerely, J. W. Donahue Genera! Manager Harris Plant MV Enclosure cs      Mr. S. D. Ebneter (NRC - RII)
Mr. N. B. Le (NRC - PM/NRR)
Mr. D. J. Roberts (NRC - HNP) 230023 rit602230145 9602l6 PDR      ADOCK 05000400 8                          PDR State Road H34 New Hill NC
 
  / 8 U
 
NRC FORM 366                              U.S. NUCLEAR REGULATORY COMMISSION                              APPROVED BY OMB No. 3150-0104 (465)                                                                                                              EXPIRES 04/30/96 ESTIMATED BURDEN PER RESPONSE        TO COMPlY WITH TH)S MANDATORY (NFORMATION COllECTION REDDEST: 500 HRS. REPORTED lESSONS lEARNED ARE LICENSEE EVENT REPORT                        (LER)                      (NCORPORATEO INTO THE UCB(SING PROCESS ANO FED BACK TO )NDUSTRY.
FORWARD COMMBITS REGARDING BURDEN ESTIMATE TO THE UIFORMATION ANO RECORDS MANAGEMENT BRANCH ITS F33L US. NUCLEAR REGUlATORY COMM)SSIN.
(See reverse for required number of                              WASHINGTON. OC 20555000(, ANO TO THE PAPERWORK REDUCTION PROJECt (3(50.
digits/characters for each'lock)                                0(04L OFF(CE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.
FAciuTY NAME n)                                                                            DOCKET NU'IBER (2)                                    PAGE (3)
Harris Nuclear Plant Unit-1                                                                    50-400                              1  OF 3 TITLE (4)
Failure to perform slave relay surveillance testing for the CSIP Alternate Mini-Flow Motor Operated Valves.
EVENT DATE (5)                  LER NUMBER (6)                REPORT DATE (7)                        OTHER FACILITIES INVOLVED (6)
FAG IUTY NAME                                DOCKETNUMBER SEOUENTIAL    REVISION MONTH      OAY    YEAR      YEAR                              MONTH    OAY    YEAR NUMBER      NUMBER                                                                                    05000      ~
FACILITYNAME                                DOCKET NUMBER 11        07      94        96    002          00                  16    96 05000 OPERATING                  THIS REPORT IS SUBMITTED PUR SUANT- TO THE REQUIREMENTS OF 10 CFR B: (Check one o r moro) (11)
MODE (9)                      20.2201(b)                    20.2203(a)(2)(v)                    50.73(a)(2)(i)                          50.73(a)(2)(viii)
POWER 20.2203(a) (1)                  20.2203(a)(3)(i)                    50.73(a)(2)(ii)                        50.73(a) (2) (x)
O'Y LEVEL (10)                    20.2203(a) (2)(i)              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) l2)(v)                  Specify in Abstract be low or rn NRC Form 366A 20.2203(a) (2) (iv)            50.36(c) (2)                        50.73(a)(2)(vii)
LICENSEE CONTACT FOR THIS LER (12)
NAME                                                                                            TELEP)(ONE NUMBER (lrrolude Area Code)
Michael Verrilli Sr. Analyst - Licensing                                                                t919) 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)                                                                      MONTH        OAY        YEAR EXPECTED YES                                                    ll                                          SUBMISSION (if yes, complete EXPECTED SUBMISSION DATE).                          X No                          DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On January 17, 1996, during a Technical Specification testing program review, a failure to perform required surveillance testing during a planned maintenance outage in October, 1994 was identified. Specifically, on October 30, 1994, the plant was shut down and taken to Mode-5 (Cold Shutdown). This outage exceeded 72 hours and per Technical Specification requirements Engineered Safety" Feature slave relay testing was required.
To satisfy this requirement OST-1083 and OST-1084 were satisfactorily completed, however the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves, 1CS-746 and 1CS-752 were not tested due to an error that occurred during a procedure revision in June 1993.
1 In September 1992, a plant modification was completed on the Charging/Safety Injection Pump (CSIP) Alternate Mini-Flow System that necessitated revisions to Operations Surveillance Test procedures OST-1083 and OST-1084. These revisions were completed in June 1993 and removed the slave relay testing for CSIP Alternate Mini-FlowIsolation Valves (1CS-746 and 1CS-752) from OST-1083 and OST-1084 and transferred the testing requirement to procedure OST-1809. The cause of the Technical Specification violation was personnel error during the June 1993 procedure revision process for OST-1083 and OST-1084. OST-1809 was successfully performed during Refueling Outage 6 on September 8, 1995. This test verified the operability of these circuits, thus no immediate corrective action was required upon identification of the deficiency. Additional corrective actions included personnel counseling, appropriate procedure revisions and the continuation of an in-progress Technical Specification testing program review.
 
V 7
 
NRC FORM 36BA                                                                                                            US. NUCLEAR REGULATORT COMMISSION (4BSI LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (I I                                  OOCKET        LER NUMBER (BI                PAGE I(3)
SEOUENTUIL      REVISION YEAR NUMBER        NUMBER Shearon Harris Nuclear Plant - Unit //1                              50400                                    2      OF    3 06  -    002      -    00 TEXT  llfmoro sposo a rorrudod, vso oddrrdrool sopas ot pVRC Form 3BQ/ (I 7)
EVENT DESCRIPTION:
On January 17, 1996, a failure to perform Technical Specification surveillance testing during an October 1994 planned maintenance outage was identified. The identification of this condition was a result of an on-going comprehensive Technical Specification testing program review that began in September 1995 following submital of LER 95-07.
JJ Specifically, on October 30, 1994, the plant was shut down and taken to Mode-5 (Cold Shutdown) for a planned maintenance outage. This outage exceeded 72 hours and therefore, per Technical Specification 4.3.2.1 requirements, Engineered Safety Feature (ESF) slave relay testing was required for the 13 ESF relays delineated in Table 4.3-2 that had not been tested in the last 92 days due to being at full power operations. To satisfy this requirement OST-1083 and OST-1084 were completed on November 3, 1994.
However, the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves (1CS-746 and 1CS-752, EIIS Code BQ-ISV) were not tested due to an error that occurred during procedure revisions performed in June 1993 on Engineered Safety Feature (ESF) 18-Month Slave Relay Operations Surveillance Test procedures OST-1083 and OST-1084. This error inv'olved inappropriately removing the slave relay testing for the 1CS-746 and 1CS-752 circuits from OST-1083 and OST-1084 and transfering the testing requirement to procedure OST-1809 (Refueling Water Storage Tank switchover to the Containment sumps), which is also an 18-month ESF response time test. OST-1809 was not performed following the October maintenance outage, thus resulting in the testing ommision and Technical Specification violation.
During the investigation of this event, personnel performing the Technical Specification testing program review verified that OST-1809 had been successfully performed during Refueling Outage 6 on September 8, 1995, which verified the operability of the affected circuits.
The June 1993 revisions to OST-1083 and OST-1084 were performed to incorporate a plant modification (PCR-6547) on the Charging/Safety Injection Pump (CSIP) Alternate Mini-Flow lines. This modification removed the previously installed relief valves and provided an "open" signal to 1CS-746 and 1CS-752 upon receipt of a Safety Injection signal.
This condition was determined to be a violation of the Technical Specification surveillance test periodicity requirement and is being reported per 10CFR50.73(a)(2)(i)(b).
CAUSE:
The cause of the Technical Specification violation was personnel error during the June 1993 procedure revision process for OST-1083 and OST-1084. The testing requirements for the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves (1CS-746 and 1CS-752) were inappropriately transferred to OST-1809, which was not identified or scheduled as a Mode-5 "event related" surveillance test.
A (4- 5)


Carolina Power 4 Light Company Harris Nuclear Plant PO 8ox 165 New Hill NC 27562 FEB 16 1996 U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 Serial: HNP-96-022 10CFR50.73 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO 50 400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 96-002-00 Gentlemen:
In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted.
This report concerns a personnel error during a procedure revision performed in June 1993 that resulted in the failure to perform surveillance testing for the Charging/Safety Injection Pump Alternate Min-Flow Motor Operated Valves.Sincerely, J.W.Donahue Genera!Manager Harris Plant MV Enclosure cs Mr.S.D.Ebneter (NRC-RII)Mr.N.B.Le (NRC-PM/NRR)Mr.D.J.Roberts (NRC-HNP)230023 rit602230145 9602l6 PDR ADOCK 05000400 8 PDR State Road H34 New Hill NC
/8 U NRC FORM 366 (465)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each'lock)
APPROVED BY OMB No.3150-0104 EXPIRES 04/30/96 ESTIMATED BURDEN PER RESPONSE TO COMPlY WITH TH)S MANDATORY (NFORMATION COllECTION REDDEST: 500 HRS.REPORTED lESSONS lEARNED ARE (NCORPORATEO INTO THE UCB(SING PROCESS ANO FED BACK TO)NDUSTRY.FORWARD COMMBITS REGARDING BURDEN ESTIMATE TO THE UIFORMATION ANO RECORDS MANAGEMENT BRANCH ITS F33L US.NUCLEAR REGUlATORY COMM)SSIN.
WASHINGTON.
OC 20555000(, ANO TO THE PAPERWORK REDUCTION PROJECt (3(50.0(04L OFF(CE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FAciuTY NAME n)Harris Nuclear Plant Unit-1 DOCKET NU'IBER (2)50-400 PAGE (3)1 OF 3 TITLE (4)Failure to perform slave relay surveillance testing for the CSIP Alternate Mini-Flow Motor Operated Valves.EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (6)MONTH OAY YEAR YEAR SEOUENTIAL NUMBER REVISION NUMBER MONTH OAY YEAR FAG IUTY NAME DOCKETNUMBER 05000~11 07 94 96-002-00 16 96 FACILITY NAME DOCKET NUMBER 05000 OPERATING MODE (9)POWER LEVEL (10)O'Y 20.2201(b) 20.2203(a)
(1)20.2203(a)
(2)(i)20.2203(a)(2)(ii) 20.2203(a)(2)(iii)20.2203(a)
(2)(iv)20.2203(a)(2)(v) 20.2203(a)(3)(i) 20.2203(a)(3)(n)20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(iv) 50.73(a)l2)(v)50.73(a)(2)(vii) 50.73(a)(2)(viii) 50.73(a)(2)(x)73.71 OTHER low Specify in Abstract be or rn NRC Form 366A THIS REPORT IS SUBMITTED PUR SUANT-TO THE REQUIREMENTS OF 10 CFR B: (Check one o r moro)(11)NAME LICENSEE CONTACT FOR THIS LER (12)TELEP)(ONE NUMBER (lrrolude Area Code)Michael Verrilli Sr.Analyst-Licensing t919)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 ll (if 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 typewritten lines)(16)On January 17, 1996, during a Technical Specification testing program review, a failure to perform required surveillance testing during a planned maintenance outage in October, 1994 was identified.
Specifically, on October 30, 1994, the plant was shut down and taken to Mode-5 (Cold Shutdown).
This outage exceeded 72 hours and per Technical Specification requirements Engineered Safety" Feature slave relay testing was required.To satisfy this requirement OST-1083 and OST-1084 were satisfactorily completed, however the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves, 1CS-746 and 1CS-752 were not tested due to an error that occurred during a procedure revision in June 1993.1 In September 1992, a plant modification was completed on the Charging/Safety Injection Pump (CSIP)Alternate Mini-Flow System that necessitated revisions to Operations Surveillance Test procedures OST-1083 and OST-1084.These revisions were completed in June 1993 and removed the slave relay testing for CSIP Alternate Mini-FlowIsolation Valves (1CS-746 and 1CS-752)from OST-1083 and OST-1084 and transferred the testing requirement to procedure OST-1809.The cause of the Technical Specification violation was personnel error during the June 1993 procedure revision process for OST-1083 and OST-1084.OST-1809 was successfully performed during Refueling Outage 6 on September 8, 1995.This test verified the operability of these circuits, thus no immediate corrective action was required upon identification of the deficiency.
Additional corrective actions included personnel counseling, appropriate procedure revisions and the continuation of an in-progress Technical Specification testing program review.
V 7 NRC FORM 36BA (4BSI LICENSEE EVENT REPORT (LER)TEXT CONTINUATION US.NUCLEAR REGULATORT COMMISSION FACILITY NAME (I I Shearon Harris Nuclear Plant-Unit//1 TEXT llf moro sposo a rorrudod, vso oddrrdrool sopas ot pVRC Form 3BQ/(I 7)OOCKET 50400 LER NUMBER (BI YEAR SEOUENTUIL REVISION NUMBER NUMBER 06-002-00 PAGE I(3)2 OF 3 EVENT DESCRIPTION:
On January 17, 1996, a failure to perform Technical Specification surveillance testing during an October 1994 planned maintenance outage was identified.
The identification of this condition was a result of an on-going comprehensive Technical Specification testing program review that began in September 1995 following submital of LER 95-07.JJ Specifically, on October 30, 1994, the plant was shut down and taken to Mode-5 (Cold Shutdown)for a planned maintenance outage.This outage exceeded 72 hours and therefore, per Technical Specification 4.3.2.1 requirements, Engineered Safety Feature (ESF)slave relay testing was required for the 13 ESF relays delineated in Table 4.3-2 that had not been tested in the last 92 days due to being at full power operations.
To satisfy this requirement OST-1083 and OST-1084 were completed on November 3, 1994.However, the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves (1CS-746 and 1CS-752, EIIS Code BQ-ISV)were not tested due to an error that occurred during procedure revisions performed in June 1993 on Engineered Safety Feature (ESF)18-Month Slave Relay Operations Surveillance Test procedures OST-1083 and OST-1084.This error inv'olved inappropriately removing the slave relay testing for the 1CS-746 and 1CS-752 circuits from OST-1083 and OST-1084 and transfering the testing requirement to procedure OST-1809 (Refueling Water Storage Tank switchover to the Containment sumps), which is also an 18-month ESF response time test.OST-1809 was not performed following the October maintenance outage, thus resulting in the testing ommision and Technical Specification violation.
During the investigation of this event, personnel performing the Technical Specification testing program review verified that OST-1809 had been successfully performed during Refueling Outage 6 on September 8, 1995, which verified the operability of the affected circuits.The June 1993 revisions to OST-1083 and OST-1084 were performed to incorporate a plant modification (PCR-6547) on the Charging/Safety Injection Pump (CSIP)Alternate Mini-Flow lines.This modification removed the previously installed relief valves and provided an"open" signal to 1CS-746 and 1CS-752 upon receipt of a Safety Injection signal.This condition was determined to be a violation of the Technical Specification surveillance test periodicity requirement and is being reported per 10CFR50.73(a)(2)(i)(b).
CAUSE: The cause of the Technical Specification violation was personnel error during the June 1993 procedure revision process for OST-1083 and OST-1084.The testing requirements for the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves (1CS-746 and 1CS-752)were inappropriately transferred to OST-1809, which was not identified or scheduled as a Mode-5"event related" surveillance test.A (4-5)
((
((
NRC EORM 355A)5-95)LlCENSEE EVENT REPORT (LER)TEXT CONTINUATION US.NUCLEAR REGULATORT COMMISSION EACILITT NAME III Shearon Harris IVuclear Plant~Unit)I'I TERT rH nor opooo R nqanC oso odNo)ool oopio of HRC fee 3555)(I 1)OOCKET 50400 LER NUMBER IB)SEOUENTIAL RE@SION NUMBER NUMBER 86-002-00 PAGE)3)3 OF 3 SAFETY SIGNIFICANCE:
NRC EORM 355A                                                                                                     US. NUCLEAR REGULATORT COMMISSION
There were no adverse safety consequences as a result of this event.The CSIP Alternate Mini-Flow Isolation Valve circuits were tested satisfactorily on September 8, 1995 to verify operability.
)5-95)
This testing provides confidence that had an accident occurred requiring CSIP mini-flow protection,due to the re-pressurization of the Reactor Coolant System during a safety injection, the isolation valves would have opened to prevent pump damage.PREVIOUS SIMILAR EVENTS: Previous events have been submitted as LERs related to surveillance testing deficiencies caused by procedural inadequacies.
LlCENSEE EVENT REPORT (LER)
LER 95-07, which was submitted on September 28, 1995, contained a corrective action to perform a comprehensive Technical Specification testing program review and it was during this review process that the CSIP Alternate Mini-Flow Isolation Valve condition was identified.
TEXT CONTINUATION EACILITT NAME III                                   OOCKET      LER NUMBER IB)                PAGE )3)
This review is being performed by a multi-discipline team and is still in progress.CORRECTIVE ACTIONS COMPLETED:
SEOUENTIAL    RE@SION NUMBER        NUMBER Shearon Harris IVuclear Plant     ~
1.Slave relay testing was satisfactorily completed on September 8, 1995 that verified the operability of the CSIP Alternate Mini-Flow Isolation Valve circuits.2.Personnel involved in the June 1993 procedure revision process for OST-1083 and OST-1084 were counseled.
Unit )I'I                     50400                                  3      OF    3 86 -    002      -    00 TERT rH nor opooo R nqanC oso odNo)ool oopio of HRC fee 3555) (I 1)
3.Surveillance procedures OST-1083 and OST-1084 were revised on February 16, 1996 to include the requirements for CSIP Alternate Mini-Flow Isolation Valve slave relay testing.CORRECTIVE ACTIONS PLANNED: 1.The comprehensive Technical Specification testing program review that identified this condition is currently in progress and will be completed as described in LER 95-07.EIIS CODES: High Head Safety Injection-BQ}}
SAFETY SIGNIFICANCE:
There were no adverse safety consequences as a result of this event. The CSIP Alternate Mini-Flow Isolation Valve circuits were tested satisfactorily on September 8, 1995 to verify operability. This testing provides confidence that had an accident occurred requiring CSIP mini-flow protection,due to the re-pressurization of the Reactor Coolant System during a safety injection, the isolation valves would have opened to prevent pump damage.
PREVIOUS SIMILAR EVENTS:
Previous events have been submitted as LERs related to surveillance testing deficiencies caused by procedural inadequacies. LER 95-07, which was submitted on September 28, 1995, contained a corrective action to perform a comprehensive Technical Specification testing program review and it was during this review process that the CSIP Alternate Mini-Flow Isolation Valve condition was identified. This review is being performed by a multi-discipline team and is still in progress.
CORRECTIVE ACTIONS COMPLETED:
: 1. Slave relay testing was satisfactorily completed on September 8, 1995 that                         verified the operability of the CSIP Alternate Mini-Flow Isolation Valve circuits.
: 2. Personnel involved in the June 1993 procedure revision process for OST-1083 and OST-1084 were counseled.
: 3. Surveillance procedures OST-1083 and OST-1084 were revised on February 16, 1996 to include the requirements for CSIP Alternate Mini-Flow Isolation Valve slave relay testing.
CORRECTIVE ACTIONS PLANNED:
: 1. The comprehensive Technical Specification testing program review that identified this condition is currently in progress and will be completed as described in LER 95-07.
EIIS CODES:
High Head Safety Injection - BQ}}

Latest revision as of 06:03, 22 October 2019

LER 96-002-00:on 960117,failure to Perform Required Surveillance Testing During Planned Maint Outage in Oct 1994 Identified.Caused by Personnel Error.Personnel Involved counseled.W/960216 Ltr
ML18012A140
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 02/16/1996
From: Donahue J, Verrilli M
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HNP-96-022, HNP-96-22, LER-96-002-01, LER-96-2-1, NUDOCS 9602230145
Download: ML18012A140 (9)
v • d • e


Text

~ CATEGORY ly REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9602230145 DOC.DATE: 96/02/16 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power 6 Light Co.

DONAHUE,J.W. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 96-002-00:on 960117,failure to perform required surveillance testing during planned maint outage in Oct 1994 identified. Caused by personnel error. Personnel involved counseled.W/960216 ltr.

DZSTRZBUTZON CODE: ZE22T COPZES RECEZVED:LTR t ENCL I SZZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:Application for permit renewal filed. 05000400 G RECIPIENT COPIES RECIPIENT 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 1

1 LE CENT AB 2 1

2 1

NRR/DE/ECGB 1 1 NRR LB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 D RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 0

EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCEEJ H 2 2 NOAC MURPHYEG.A 1 1 NOAC POORE,W. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 E

N NOTE TO ALL "RZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK/

ROOM OWFN 5D-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 4 Light Company Harris Nuclear Plant PO 8ox 165 New Hill NC 27562 FEB 16 1996 U.S. Nuclear Regulatory Commission Serial: HNP-96-022 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 96-002-00 Gentlemen:

In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report concerns a personnel error during a procedure revision performed in June 1993 that resulted in the failure to perform surveillance testing for the Charging/Safety Injection Pump Alternate Min-Flow Motor Operated Valves.

Sincerely, J. W. Donahue Genera! Manager Harris Plant MV Enclosure cs Mr. S. D. Ebneter (NRC - RII)

Mr. N. B. Le (NRC - PM/NRR)

Mr. D. J. Roberts (NRC - HNP) 230023 rit602230145 9602l6 PDR ADOCK 05000400 8 PDR State Road H34 New Hill NC

/ 8 U

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB No. 3150-0104 (465) EXPIRES 04/30/96 ESTIMATED BURDEN PER RESPONSE TO COMPlY WITH TH)S MANDATORY (NFORMATION COllECTION REDDEST: 500 HRS. REPORTED lESSONS lEARNED ARE LICENSEE EVENT REPORT (LER) (NCORPORATEO INTO THE UCB(SING PROCESS ANO FED BACK TO )NDUSTRY.

FORWARD COMMBITS REGARDING BURDEN ESTIMATE TO THE UIFORMATION ANO RECORDS MANAGEMENT BRANCH ITS F33L US. NUCLEAR REGUlATORY COMM)SSIN.

(See reverse for required number of WASHINGTON. OC 20555000(, ANO TO THE PAPERWORK REDUCTION PROJECt (3(50.

digits/characters for each'lock) 0(04L OFF(CE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.

FAciuTY NAME n) DOCKET NU'IBER (2) PAGE (3)

Harris Nuclear Plant Unit-1 50-400 1 OF 3 TITLE (4)

Failure to perform slave relay surveillance testing for the CSIP Alternate Mini-Flow Motor Operated Valves.

EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (6)

FAG IUTY NAME DOCKETNUMBER SEOUENTIAL REVISION MONTH OAY YEAR YEAR MONTH OAY YEAR NUMBER NUMBER 05000 ~

FACILITYNAME DOCKET NUMBER 11 07 94 96 002 00 16 96 05000 OPERATING THIS REPORT IS SUBMITTED PUR SUANT- TO THE REQUIREMENTS OF 10 CFR B: (Check one o r moro) (11)

MODE (9) 20.2201(b) 20.2203(a)(2)(v) 50.73(a)(2)(i) 50.73(a)(2)(viii)

POWER 20.2203(a) (1) 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a) (2) (x)

O'Y LEVEL (10) 20.2203(a) (2)(i) 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) l2)(v) Specify in Abstract be low or rn NRC Form 366A 20.2203(a) (2) (iv) 50.36(c) (2) 50.73(a)(2)(vii)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEP)(ONE NUMBER (lrrolude Area Code)

Michael Verrilli Sr. Analyst - Licensing t919) 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) MONTH OAY YEAR EXPECTED YES ll SUBMISSION (if yes, complete EXPECTED SUBMISSION DATE). X No DATE (15)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

On January 17, 1996, during a Technical Specification testing program review, a failure to perform required surveillance testing during a planned maintenance outage in October, 1994 was identified. Specifically, on October 30, 1994, the plant was shut down and taken to Mode-5 (Cold Shutdown). This outage exceeded 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and per Technical Specification requirements Engineered Safety" Feature slave relay testing was required.

To satisfy this requirement OST-1083 and OST-1084 were satisfactorily completed, however the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves, 1CS-746 and 1CS-752 were not tested due to an error that occurred during a procedure revision in June 1993.

1 In September 1992, a plant modification was completed on the Charging/Safety Injection Pump (CSIP) Alternate Mini-Flow System that necessitated revisions to Operations Surveillance Test procedures OST-1083 and OST-1084. These revisions were completed in June 1993 and removed the slave relay testing for CSIP Alternate Mini-FlowIsolation Valves (1CS-746 and 1CS-752) from OST-1083 and OST-1084 and transferred the testing requirement to procedure OST-1809. The cause of the Technical Specification violation was personnel error during the June 1993 procedure revision process for OST-1083 and OST-1084. OST-1809 was successfully performed during Refueling Outage 6 on September 8, 1995. This test verified the operability of these circuits, thus no immediate corrective action was required upon identification of the deficiency. Additional corrective actions included personnel counseling, appropriate procedure revisions and the continuation of an in-progress Technical Specification testing program review.

V 7

NRC FORM 36BA US. NUCLEAR REGULATORT COMMISSION (4BSI LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (I I OOCKET LER NUMBER (BI PAGE I(3)

SEOUENTUIL REVISION YEAR NUMBER NUMBER Shearon Harris Nuclear Plant - Unit //1 50400 2 OF 3 06 - 002 - 00 TEXT llfmoro sposo a rorrudod, vso oddrrdrool sopas ot pVRC Form 3BQ/ (I 7)

EVENT DESCRIPTION:

On January 17, 1996, a failure to perform Technical Specification surveillance testing during an October 1994 planned maintenance outage was identified. The identification of this condition was a result of an on-going comprehensive Technical Specification testing program review that began in September 1995 following submital of LER 95-07.

JJ Specifically, on October 30, 1994, the plant was shut down and taken to Mode-5 (Cold Shutdown) for a planned maintenance outage. This outage exceeded 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and therefore, per Technical Specification 4.3.2.1 requirements, Engineered Safety Feature (ESF) slave relay testing was required for the 13 ESF relays delineated in Table 4.3-2 that had not been tested in the last 92 days due to being at full power operations. To satisfy this requirement OST-1083 and OST-1084 were completed on November 3, 1994.

However, the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves (1CS-746 and 1CS-752, EIIS Code BQ-ISV) were not tested due to an error that occurred during procedure revisions performed in June 1993 on Engineered Safety Feature (ESF) 18-Month Slave Relay Operations Surveillance Test procedures OST-1083 and OST-1084. This error inv'olved inappropriately removing the slave relay testing for the 1CS-746 and 1CS-752 circuits from OST-1083 and OST-1084 and transfering the testing requirement to procedure OST-1809 (Refueling Water Storage Tank switchover to the Containment sumps), which is also an 18-month ESF response time test. OST-1809 was not performed following the October maintenance outage, thus resulting in the testing ommision and Technical Specification violation.

During the investigation of this event, personnel performing the Technical Specification testing program review verified that OST-1809 had been successfully performed during Refueling Outage 6 on September 8, 1995, which verified the operability of the affected circuits.

The June 1993 revisions to OST-1083 and OST-1084 were performed to incorporate a plant modification (PCR-6547) on the Charging/Safety Injection Pump (CSIP) Alternate Mini-Flow lines. This modification removed the previously installed relief valves and provided an "open" signal to 1CS-746 and 1CS-752 upon receipt of a Safety Injection signal.

This condition was determined to be a violation of the Technical Specification surveillance test periodicity requirement and is being reported per 10CFR50.73(a)(2)(i)(b).

CAUSE:

The cause of the Technical Specification violation was personnel error during the June 1993 procedure revision process for OST-1083 and OST-1084. The testing requirements for the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves (1CS-746 and 1CS-752) were inappropriately transferred to OST-1809, which was not identified or scheduled as a Mode-5 "event related" surveillance test.

A (4- 5)

((

NRC EORM 355A US. NUCLEAR REGULATORT COMMISSION

)5-95)

LlCENSEE EVENT REPORT (LER)

TEXT CONTINUATION EACILITT NAME III OOCKET LER NUMBER IB) PAGE )3)

SEOUENTIAL RE@SION NUMBER NUMBER Shearon Harris IVuclear Plant ~

Unit )I'I 50400 3 OF 3 86 - 002 - 00 TERT rH nor opooo R nqanC oso odNo)ool oopio of HRC fee 3555) (I 1)

SAFETY SIGNIFICANCE:

There were no adverse safety consequences as a result of this event. The CSIP Alternate Mini-Flow Isolation Valve circuits were tested satisfactorily on September 8, 1995 to verify operability. This testing provides confidence that had an accident occurred requiring CSIP mini-flow protection,due to the re-pressurization of the Reactor Coolant System during a safety injection, the isolation valves would have opened to prevent pump damage.

PREVIOUS SIMILAR EVENTS:

Previous events have been submitted as LERs related to surveillance testing deficiencies caused by procedural inadequacies. LER 95-07, which was submitted on September 28, 1995, contained a corrective action to perform a comprehensive Technical Specification testing program review and it was during this review process that the CSIP Alternate Mini-Flow Isolation Valve condition was identified. This review is being performed by a multi-discipline team and is still in progress.

CORRECTIVE ACTIONS COMPLETED:

1. Slave relay testing was satisfactorily completed on September 8, 1995 that verified the operability of the CSIP Alternate Mini-Flow Isolation Valve circuits.
2. Personnel involved in the June 1993 procedure revision process for OST-1083 and OST-1084 were counseled.
3. Surveillance procedures OST-1083 and OST-1084 were revised on February 16, 1996 to include the requirements for CSIP Alternate Mini-Flow Isolation Valve slave relay testing.

CORRECTIVE ACTIONS PLANNED:

1. The comprehensive Technical Specification testing program review that identified this condition is currently in progress and will be completed as described in LER 95-07.

EIIS CODES:

High Head Safety Injection - BQ

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