ML18012A290

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LER 96-002-08:on 960529,failed to Perform Tech Spec Surveillance Testing.Caused by Personnel Error.Counseled Personnel,Revised Procedure & Continued in-progress Tech Spec Testing Program review.W/960628 Ltr
ML18012A290
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 06/28/1996
From: Donahue J, Verrilli M
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HNP-96-110, LER-96-002, LER-96-2, NUDOCS 9607090002
Download: ML18012A290 (15)
v • d • e


Text

CATEGORY $

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9607090002 DOC.DATE: 96/06/28 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 6 Light Co.

RECIP.NAME RECIPIENT AFFII IATION

SUBJECT:

LER 96-002-08:on 960529,failed to perform Tech Spec surveillance testing. Caused by personnel error. Counseled personnel, revised procedure & continued in-progress Tech Spec testing program review.W/960628 ltr.

DZSTRZBOTZON CODE: ZE22T COPZES RECEZVED:LTR L ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

I SIZE:

E 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 LE,N 1 1 INTERNAL: ACRS" 1 1 A~EOD SPD RAB 2 2 AEOD/SPD/RRAB 1 1 ZLE CENTER 1 1 NRR/DE/ECGB 1 1 NRR DE EEGB 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 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 2 2 NOAC MURPHY,G.A 1 1 NOAC POORETW. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 E

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE'ONTACT 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 TE: L CONVERSION REQUIRED TOTAL NUM':R OF COPIES REQUIRED: LTTR 26 ENCL 26

Carolina Power 8 Light Company Harris Nudear Plant PCt 8ox 165 New Hill NC 27562 JUN 28 1996 U.S. Nuclear Regulatory Commission Serial: HNP-96-110 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 96-002-08 Sir or Madam:

In accordance with Title 10 to the Code of Federal Regulations, the enclosed revision to Licensee Event Report 96-002 is submitted. This revision reports an additional Technical Specification Testing deficiency identified during the on-going Technical Specification testing program review.

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

Mr. S. D. Ebneter (NRC - RII)

Mr. N. B. Le (NRC - PM/NRR) 9607090002 960628 PDR ADOCK 05000400 S PDR State Road 1134 New Hill NC

U. S. Nuclear Regulatory Commission Document Control Desk / HNP-96-110 Page 2 of 2 cc: Ms. P. B. Brannan Mr. W. R. Campbell (BNP)

Mr. J. M. Collins Mr. J. P. Cowan Mr. G. W. Davis Ms. S. F. Flynn Mr. G. D. Hicks (BNP)

Mr. M. D. Hill Mr. W. J. Hindman Ms. C. W. Hobbs (HEEC)

Mr. R. M. Krich (RNP)

Ms. W. C. Langston Mr. C. W. Martin (BNP)

Mr. R. D. Martin Mr. P. M. Odom (RNP)

Mr. W. R. Robinson Mr. G. A. Rolfson Mr. R. F. Saunders Mr. C. T. Sawyer Mr. R. S. Stancil Mr. G. M. Stokes Mr. C. N. Sweely Mr. J. P. Thompson (BNP)

Mr. T. D. Walt Mr. R. L. Warden (RNP)

HNP Real Time Training INPO NLS File: HI/A-2D Nuclear Records

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3160-0104 H65) EXPIRES 04/30/99 EST(MATEO BURDEN PER RESPONSE TO COMPLY W(TH THI MANDATORY (NFORMATNH COMECTNN REQUEST: 509 HRS. REPORTED tESSONS (EARNED ARE LICENSEE EVENT REPORT (LER) (HCORPORATED IHTO THE UCENSUIG PROCESS AND FEO BACK TO (HOUSTRY.

fORWARD COMMENTS REGARDUIG BURDEN ESTIMATE TO THE U(FORMATNH AHO RECORDS MANAGEMENT BRANCH IT6 F33L US. NUCLEAR REGUIATORY COMMISS(0)L (See reverse for required number of WASHIHGTO)L DC 20555000), ANO TO THE PAPERWORK REDUCTR)N PROJECT (3(50 digits/characters for each block) 0(0(L Off)CE OF MANAGEMENT ANO BUDGET. WASH)HGTO)L OC 205(XL FACIUTY NAME (1) POCKET NUMSER (3) PAGE (3)

Harris Nuclear Plant Unit-1 50-400 1 OF 10 TITLE (4)

Failure to properly perform Technical Specification surveillance testing.

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

FACIUTY NAME OOCKET NUMSER SEOUENTIAL RENSION MONTH BAY YEAR MONTH OAY YEAR NUMBER NUMBER 05000 FACIUTY NAME DOCKET NUMBER 29 96 96 002 08 6 28 96 05000 OPERATING THIS REPORT IS SUBMITTED PUR SUANT TO THE REQUIREMENTS OF 10 CFR B: (Chock one o r moro) (11)

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

POWER 20.2203(s) (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(s)(2) (iii) 73.71 20.2203(a) (2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) OTHER 20.2203(a)(2) (iii) 50.36(c) (1) 50.73(a)(2)(v) Specify in Abstract below or in NRC Form 366A 20.2203(a) (2)(iv) 50.36(c) (2) 50.73(a) (2)(vii)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (Inrdvde Ares Code)

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

REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPROS TO NPROS SUPPLEMENTAL REPORT EXPECTED (14) MONTH OAY YEAR EXPECTED YES SUBMISSION (If yos, complete EXPECTED SUBMISSION DATE). NO DATE (16) 6 15 96 ABSTRACT (Limit to 1400 spaces, l.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, h'owever the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves, ICS-746 and ICS-752 were not tested due to an error that occurred during a procedure revision in June 1993.

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-Flow Isolation Valves (ICS-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.

One additional Technical Specification testing deficiency (item 25) was identified during the on-going comprehensive Technical Specification testing program review and is being reported by this supplemental report.

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NRC FORM 356A US. NUCLEAR REGULATORY COMMISSION l4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME III DOCKET LER NUMBDI (5) PAGE I3)

$ EOUENTIAL REYISION YEAR NUMBER NUMBER Shearen Harris Nuclear Plant ~

Unit Ill 50400 7 OF 10 96 - 002 - 08 TEXT 8'nore spsse r's reqvierr ese ek&kml eopres ol JVRC Fan 3GQ/ i)T)

CAUSE:

The cause of the original 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 (ICS-746 and ICS-752) were inappropriately transferred to OST-1809, which was not identified or scheduled as a Mode-5 "event related" surveillance test.

Cause For Additional Items Identified:

Item 1:

The failure to adequately test the K635 and K640 slave relays for the AFW Flow Control Valves was caused by inadequate technical reviews associated with plant modification PCR-6502. This resulted in deficient surveillance test procedures developed to verify the operability of the automatic open signal for the fiow control valves on a quarterly basis.

Items 2 3 4 5:

Each of these items were caused by inadequate surveillance test procedures that resulted from incorrectly interpreting how to implement Technical Specification testing requirements. The test procedures for the Safety Injection and Containment Spray manual actuation switches, as well as the FHB Emergency Ventilation system, were based upon this incorrect interpretation and have been deficient since initial development. The radiation monitor MST revisions completed in 1993, were intentionally performed to eliminate what was considered to be redundant and unnecessary testing steps. This decision was also based on the incorrect testing requirement interpretation, as was the revision to OST-1086 that resulted in the acceptance criteria section not listing 1CS-196, and subsequently resulting in the failure to test the valve.

Items 6 throu h 25:

Each of the additional items contained in the revisions to this LER were identified as a result of the on-going Technical Specification testing program review and were caused by inadequate surveillance test procedures. In the case of item )I)11, the two post-accident dampers failed to fully open during testing due to improper actuator sizing and inadequate lubrication and preventive maintenance methods.

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.

There were no adverse safety consequences as a result of the additional items contained in this LER revision. In each case where applicable, subsequent testing was performed that verified the operability of the effected component or circuit. In the case of item Ill, where two of the Containment Fan Cooler Post-Accident Dampers failed to completely open during testing, consequences were minimal. These dampers are required to be open in a post-accident condition within containment to allow a high velocity fan discharge flow to selected areas of containment to accelerate temperature mixing and heat removal. Assuming the failure of these two dampers to open during an accident scenario, combined with the postulated worst case single failure of one safety related electrical supply bus, engineering review has determined that adequate air flow would still exist to ensure containment cooling. This conclusion is based on the availability of one train of Containment Spray and the fact that one fan would remain operable in each Containment Fan Cooler unit. The discharge air flow from each fan would not exit through the post-accident dampers, but would still provide air mixing in containment via the seismic class 1 concrete air shafts.

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.

The additional item reported in this supplement was identified as a result of the on-going Technical Specification testing program review.

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