ML18012A466

LER 96-025-00:on 961218,determined Missed Surveillance Test on PORV Block Valve 1RC-115.Caused by Personnel Error.Tested 1RC-115 & Counseled Personnel involve.W/970117 Ltr

ML18012A466
Person / Time
Site:	Harris
Issue date:	01/17/1997
From:	Donahue J, Verrilli M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HNP-97-005, HNP-97-5, LER-96-025, LER-96-25, NUDOCS 9701230114
Download: ML18012A466 (4)

Text

CATEGORY 1 REGULA RY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9701230114 DOC.DATE: 97/01/17 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power a Light Co.

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

RgCIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 96-025-00:on 961218,determined missed surveillance test on PORV Block Valve 1RC-115.Caused by personnel error. Tested 1RC-115 a counseled personnel involve.W/970117 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

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

NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES "ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 PD 1 1 LEgN 1 1 INTERNAL: ACRS 1 1 %65~) B 2 2 AEOD/SPD/RRAB 2 2 ILE CENTE 1 1 NRR/DE/ECGB 1 1 NRR/DW/EECB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 ~ 1 RES/DET/EIB 1 1 RGN2 FILE 01 1 1 D EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 1 1 NOAC MURPHYiG.A 1 1 NOAC POORE,W. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 U

N NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26

Carolina Power R Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 JAM I 7 1997 U.S. Nuclear Regulatory Commission Serial: HNP-97-005 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 96-025-00 Sir or Madam:

In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report describes a procedural deficiency caused by personnel error which resulted in a missed surveillance test.

Sincerely, J. W. Donahue Director of Site Operations Harris Plant MV Enclosure c: Mr. J. B. Brady (HNP Senior NRC Resident)

Mr. L. A. Reyes (NRC Regional Administrator, Region II)

Mr. N. B. Le (NRC - NRR Project Manager) 970i230ii4 970ii7 PDR ADOCK 05000400 S PDR State Road H3A New Hill NC

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3160%104 f(a5) EXPIRES 04/30/96 ESTIMATED BURDEN PFR RESPONSE TO C0MPlT WITH TIN MANDATORY NIFORMATION COllECTIOH RED('EST: 5LO HRS. REPORTED lESSONS lEARNED ARE LICENSEE EVENT REPORT (LER) D(CORPORATED O(TO THE UCENQHG PROCESS AND fEO BACK TO DIOUSTRT.

FORWARD COMMENTS REGARODIG BURDEN ESTIMATE TO THE U(FORMATIN ANO RECORDS MANAGEMENT BRANCH IT@ f33L US. NUC(EAR REGUlATORI COMMISQOM, (See reverse for required number of WASHOIGTON, OC 20%50001, ANO TD THE PAPERWORK REOUCTNN PRMECT (3150 digitslcharacters for each block) 010(I, OFFICE Of MANAGEMENT AND BUDGET, WAQBNGTOIL OC 205DL FACIUTY NAME (ll DOCKET NUMBB( (2l PAGE (3)

Harris Nuclear Plant Unit-1 50-400 1 OF2 TIT(E (4)

Procedure deficiency caused by personnel error resulting in failure to perform Technical Specification surveillance testing on PORV Block Valve 1RC-115 EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED(6)

FACIUTY NAME DOCKET NUMBER SEOUENTIAL REYISION MONTH OAT YEAR MONTH BAY YEAR NUMBER NUMBER FACIUTY NAME DOCKET NUMBEII 12 18 96 96 025 0 17 97 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR B: (Check one or more) (11)

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

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

LEVEL (10) 100% 20.2203(a)(2)(i) 20.2203(a) (3)(ii) 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)(l) 50.73(a) (2)(v) SpecHY in Abstract below or in NRC Form 3BBA 20.2203(a)(2)(iv) 50.36(c) (2) 50.73(a) (2) (vii)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (Irrrdude Area Code)

Michael Verrilli Sr. Analyst - Licensing (919) 362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

REPORTAB(E REPORTAB(E CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPROS TO NPROS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH OAY YEAR YES SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE). X NO DATE(16)

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

On December 18, 1996, with the plant operating in Mode 1 at 100% power, investigation determined that the Remote Shutdown Operability Operations Surveillance Test (OST-1813) did not test Power Operated Relief Valve, Block Valve 1RC-115 and that this condition resulted in a missed surveillance test during the last refueling outage (RFO-6).

Technical Specification 4.0.3 was invoked at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on December 18, 1996 and testing to verify the operability of 1RC-115 was completed at approximately 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />.

This event was caused by personnel error during the revision process when OST-1813 was last revised in September 1995. The step which had previously tested the function of 1RC-115 was inadvertently deleted during this revision.

Subsequent procedure reviews failed to identify this deficiency.

Immediate corrective actions included testing 1RC-115 on December 18, 1996 per temporary operations surveillance test (OST-9024T). Additional actions included counseling the personnel involved in developing and reviewing the procedure revision. Planned actions will include performmg an assessment of a sample of RFO 7 procedure revisions and revising OST-1813 to include testing of 1RC-115 prior to its next scheduled performance in RFO 7.

NRC fORM 366A US. NUCLEAR REGULATORT COMMISSION IL-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION fACIUTT NAME Il) OOCKET LER NUMBER IB) pAGE rn SEOUENTIAL REVISNN TEAR NUMBER NUMBER Shearon Harris Nuclear Plant - Unit ¹1 50400 2 OF 2 96 - 025 - 00 TEXT rtr tmvo svotois rmrvvmE vso od&mvol votvos ol HRC Fmtv 36&9 LIT)

EVENT DESCRIPTION:

On December 18, 1996, with the plant operating in Mode 1 at 100% power, investigation determined that technical specification 4.3.3.5.2 had been violated. Specifically, the Remote Shutdown Operability - Refueling Interval, Operations Surveillance Test procedure (OST-1813) was found to not include testing of Power Operated Relief Valve (PORV), Block Valve 1RC-115 (EIIS Code:AB-V). The procedure steps for testing 1RC-115 had been inadvertently deleted during development of Revision ¹5 in September 1995. OST-1813 was performed after this revision during the last refueling outage (RFO 6) and since this valve is required by the Safe Shutdown Analysis for remote shutdown in the case of fire as listed in Harris Plant Calculation E-5523, the failure to test 1RC-115 during RFO 6 violates Technical Specification 4.3.3.5.2 surveillance requirement and is reportable per 10CFR50.73.a.2.i.B. OST-1813 did include testing of 1RC-115 prior to Revision 5.

Technical Specification 4.0.3 was invoked at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on December 18, 1996 for the missed surveillance test. A special/temporary test (OST-9024T) was developed to verify the remote shutdown function of 1RC-115. This test was satisfactorily completed at approximately 1630 on December 18, 1996.

CAUSE:

The cause of this event was personnel error during the development and review process for revision ¹5 to OST-1813.

The step that had previously tested the remote operation of 1RC-115 was inadvertently deleted during revision ¹5 typing and this error was not detected by subsequent technical and safety reviews.

SAFETY SIGNIFICANCE:

There were no adverse safety consequences associated with this event. OST-1813 performed during RFO 6 on September 7, 1995 verified the remote function operability of Pressurizer PORV 1RC-116. The PORVs and PORV Block Valves are designed in series with different safe shutdown division power supplies. This ensures that a spurious actuation caused by fire induced damage would not occur on both valves simultaneously resulting in a loss of Reactor Coolant System pressure control. Also, though testing was not performed on 1RC-115 during RFO 6, the successful test performed on December 18, 1996 provides confidence that 1RC-115 would have functioned properly from the Auxiliary Control Panel if needed.

This is being reported per 10CFR50.73.a.2.i.B as a violation of Technical Specifications.

PREVIOUS SIMILAR EVENTS:

LER ¹95-001 involved an administrative error made during a procedure revision and was submitted on February 16, 1995. Other Harris Plant LERs related to deficient surveillance procedures have also been submitted, but were not directly caused by an administrative error made during the typing process. A comprehensive review of the implementation of Technical Specification surveillance requirements was initiated in the 4th quarter of 1995 and will be completed concurrent with the Harris Plant's conversion to the Improved Standard Technical Specifications.

CORRECTIVE ACTIONS COMPLETED:

1. Testing of the remote shutdown function of 1RC-115 was completed per OST-9024T on December 18, 1996.

2. Appropriate personnel involved in the OST-1813 procedure revision (rev. 5) process in September 1995 were counseled on this event.

CORRECTIVE ACTIONS PLANNED:

1. Procedure OST-1813 will be revised to include testing of 1RC-115 prior to its next performance in RFO 7, which is currently scheduled to begin in April 1997.

2. An assessment will be performed on a sample of procedure revisions completed to support the up-coming refueling outage (RFO 7). This assessment will be completed prior to the beginning of the outage which is currently scheduled to begin in April 1997.