ML18004B851

LER 87-030-00:on 870512,Maint Surveillance Tests I0140, I0141 & I0142 for P-12 Interlock Missed Thus Violating Tech Specs Requirements.Caused by Personnel Error.Procedures revised.W/870611 Ltr

ML18004B851
Person / Time
Site:	Harris
Issue date:	06/11/1987
From:	Schwabenbauer, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-870450-(O), LER-87-030, LER-87-30, NUDOCS 8706160546
Download: ML18004B851 (7)

Text

RF Y INFORMATION DISTRI"I SYSTEM (RIDS)ACCESSION NBR: 8706160546 DOC DATE: 87/06/1 1.NOTARIZED:

NO FACIL: 50-400 Shearon Harris Nuclear Poeer Plant>Unit 1>Carolina AUTH.'AME AUTHOR AFFILIATION SCHWABENBAUER Caro l ina P over 8<L i g h t Co.WATSON>R.A.~Car o l ina P oeer 8c Li g h t Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000400

SUBJECT:

LER 87-030-00:

on$70512>Maint Surveillance Tests I0140>I0141 9~l0142 for P-12 interlock missed thus violating Tech Specs requirements.

Caused bg personnel error.Procedures revised.W/870611 ltr.DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ENCL SIZE: TITLE: 50.73 Licensee Event Report (I ER)>Incident Rpt>etc.NOTES: Application f or permit renewal f iled.05000400 RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY>B COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD COPIES LTTR ENCL 1 INTERNAL: ACRS M I CHELSON AEOD/DOA AEOD/DSP/TPAB NRR/DEST/ADE NRR/DEST/CEB NRR/DEST/ICSB NRR/DEST/MTB NRR/DEBT/RSB NRR/DLPG/HFB NRR/DOEA/EAB

~NRR/DREP/RPB NRR/PMAS/PTSB RES DEPY GI EXTERNAL: EG5G GROH>M LPDR NSIC HARRIS>J 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 5 5 1 ACRS MOELLER AEOD/DSP/ROAB DEDRO NRR/DEST/ADS NRR/DEST/ELB NRR/DEST/MEB NRR/DEST/PSB NRR/DEST/SGB NRR/DLPG/GAB NRR/DREP/RAB-PWA RB REG FILE 02 2 FILE 01 H ST LOBBY WARD NRC PDR NSIC MAYS>G'1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 42 ENCL 40 NRC Form 386 (9.83)LICENSEE EVENT REPORT (LER)U.S, NUCLEAR REOULATORY COMMISSION APPROVED OM 5 NO.3(504(04 EXPIRES: Sl31l88 FACILITY NAME nl SHEARON HARRIS PLANT UNIT 1 TITLE (4)MISSED MONTHLY SURVEILLANCE TESTS FOR P-12 INTERL C DOCKET NUMBER (2)PAOE 3 0 5 0 0 0 4 P O 1 OF 3 EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)IAONTH OAY YEAR YEAR SkM'EQUENTIAL

rr'srS N V MS 6 R REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(SI 0 5 0 0 0 8 7 8 7 0 3 0 0 5 0 0 0 OPERATINO MODE (9)POWER LEYEL O O k..'ss~v rr3+,,~g 20A02(b)20.406(~l(1)(i)20A05(~)(I)(iil 20A06(el(1 l(iii)20A05 (4)(1)(iv)20,406(e)11)(vl 20.40S(el 50.38(cl(1) 50.35(cl(2) 50.7 3(e I (2)Ill 50.73(~l(2)(ii)50.73(el(2)(i(i l LICENSEE CONTACT FOR THIS LER (12(50.73(el(2((iv) 60,73(~)(2)(vl 50.73(e)(2((vB) 50,73(e)(2)(vill)(Al 60.73(el(2)(vliil(BI 60.73(~)(2)(x)THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CF R ((: fCheck one or more of the follorylnp)

(11)73.71(ir)73.71(c)OTHER fSpecify in Ahstrect trefow end ln Text, NRC Form JSSAJ NAME R.SCHWABENBAUER

-REGULATORY COMPLIANCE AREA CODE TELFPHONE NUMBER COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TURER vsyr AM v'PORTABLE TO NPRDS'.'x:.o,.n.:.'..

po6 wcSYSTEM COMPONENT MANUFAC-TURER EPORTABLE TO NPRDS SNK4'Sr!m.'CICO.x xN:cl.i~x.P(SUPPLEMENTAL REPORT EXPECTED (14(I YES flf yes, complere EXPECTED SifSMISSIOhf DATE/NO ABSTRACT (Llmlt to 1400 speces, f e., epproxlmetely fifteen slnpleepece typewrlnen llnesl (ISI EXPECTED SUBMISSION DATE I'(6)MONTH OAY YEAR The plant was operating in Mode 1 at 100 percent Reactor power.At 1255 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.775275e-4 months <br /> on May 12, 1987, it was discovered that Maintenance Surveillance Tests (MST)I0140, I0141, and I0142, the Operational Test procedures for the three Reactor Coolant System (RCS)delta T/Tavg protection loops, do not test the P-12 interlock.

The plant had mistakenly taken credit for these procedures meeting the monthly Analog Operational Test requirements of Technical Specifications 4.3.2.1, Table 4.3-2, Item 10b.Upon discovery, it was immediately verified that the surveillance requirements for these channels were current using the calibration procedures for the three delta T/Tavg protection loops.However, it was also determined that the monthly surveillance testing requirements had been missed in the past.8706160546 870611 PDR ADOCK 05000400 PDR gGW>(/(NRC Form 358 (94)3)

NRC Form BEBA (BA)3)LICE EE NT REPORT (LER)TEXT CON IU N U.S.NUCLEAR REGULATORY COMMISSION APPROVE'O OMB NO.3150M)04 EXPIRES: 8/31/88 FACILITY NAME (1)SHEARON HARRIS PLANT UNIT 1 TEXT//F'moro E/toco/t nrtu/ror/uw a/f//Ooto/

///IC Form 3EBAB/(13)DOCKET NUMBER (2)o 6 o o o 400 LER NUMBER (6)YEAR 9".R BEQUEIITIAL

.~REvtstoN NUMBER>Sot NUMBER 87-03 0-0 0 PAGE (3)0 20F DESCRIPTION On May 12, 1987, while the plant was operating at 100 percent power in Mode 1, it was discovered that Maintenance Surveillance Tests (MST)I0140, I0141, and I0142,, the Analog Operational Test procedures for the three Reactor Coolant System (RCS)delta T/Tavg protection loops, do not test the P-12 interlock.

The P-12 interlock provides protection against an uncontrolled cooldown from the steam dump system.On decreasing reactor coolant loop temperature, P-12 automatically removes the arming signal from the plant steam dump system.The discovery was made by an Instrument and Control (I&C)technician as he was preparing to run MST-I0142.

He discovered the discrepancy while reviewing Technical Specifications and the procedure.

It was then determined that the only test of the P-12 interlock took place during the running of the loop calibration procedures (MST-I0037, MST-I0038, and MST-I0039).

A review of previous calibrations was performed to determine if the plant was in current compliance with Technical Specifications and if any Surveillance Testing had, indeed, been missed.It was immediately verified that the Surveillance requirements on these channels were current due to all three being recalibrated within the previous 6 days.A review of previous calibration dates and plant modes was conducted to determine if the Technical Specification requirements had been violated.Technical Specifications require the P-12 interlock be tested every 31 days plus 25 percent (7 days).The plant entered Mode 3 for the first time at approximately 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on December 24, 1986.The temperature loops were calibrated on several occasions as part of the Power Ascension Test Program.The review for Loop T-412 shows the monthly Operational Test was missed once by ll days between the February 20, 1987 and April 10, 1987.The review for Loop T-422 shows the allowance for the monthly Operational Test was missed once by 13 days between January 15, 1987 and March 7, 1987.The review for Loop T-432 shows the allowance for the monthly Operational Test was never missed on this channel and has been in compliance with Technical Specification requirements.

CAUSE The cause of the event was personnel error through inadequate review of changes to the purpose section of the procedures.

In July, 1986, Maintenance personnel identified 56 surveillance procedures in which the purpose section of the procedure did not match the requirements for the procedure as specified in the Technical Specification cross-reference index.As a result, changes to these procedures then were made.At that time, an error was made on MST-I0140, MST-I0141, and MST-I0142.

These procedures did not check the P-12 interlock, as required by the cross-reference.

While the purpose statement of the procedures were revised, the procedure steps were not.This resulted in the procedures normally relied on to test the P-12 interlock not performing this function.NRC'FORM 3BBA ((F83)*U.S.GPO;1985 0.52E 538/455

~~~0 NRC Form 356A (983)LICE EE ENT REPORT HLER)TEXT CON IVU N U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3150-0104 EXPIRES: 8/31/88 FACILITY NAME (I)DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)SHEARON HARRIS PLANT UNIT 1 TEXT//P more 4/>>ce/4 BEE/rerL l>>e////WORE/I HRC Form 35549/(0)YEAR o s o o o 40 087 SEQUENTIAL NUMBER 0 3 0 REVISION NUMBER 0 003 QF0 3 ANALYSIS There was no impact on safety, as P-12 interlock does not perform a safety function per accident analysis, and when checked was found to be in tolerance.

This event is being reported in'accordance with lOCFRS0.73(a)(2)(i)(B), as Technical Specification 4.3.2.1, Table 4.3-2, Item 10b was violated.CORRECTIVE ACTION 1.The P-12 interlock surveillance requirement has been incorporated into applicable procedures.

2.MST-I0140, MST-I0141, and MST-I0142 have been revised to correct their purpose section.3.'review was conducted of the other 53 MST's changed at the time, and no other discrepancies were found.4.A training session was held with the Maintenance procedure writers as a result of this event.NRC FORM BBBA (94)3)*U,S.GPO:(9884).524 538/455

~0 l

~~~II, 0~Carolina Power&Light Company HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 Jun>>>987 File Number: SHF/10-13510C Letter Number: HO-870450 (0)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 87-030-00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted.

This report fulfills the requirement for a written report within thirty (30)days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983.Very truly yours, RAW:lmj Enclosure R.A.Watson Vice President Harris Nuclear Project cc: Dr.J.Nelson Grace (NRC-RII)Mr.B.Buckley (NRR)Mr.G.Maxwell (NRC-SHNPP)MEM/LER/PAGE 1/Osl