ML18004B969

LER 87-056-00:on 870924,reactor Tripped Due to Deenergization of P-13 Permissive Bistable.Caused by Personnel Error Due to Insufficient Instructions.Procedure for Mod Implementation revised.W/871026 Ltr

ML18004B969
Person / Time
Site:	Harris
Issue date:	10/26/1987
From:	Schwabenbauer, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-870522-(O), LER-87-056, LER-87-56, NUDOCS 8710290162
Download: ML18004B969 (5)

Text

REGULA Y INFORMATION DIBTRIBUTI YSTEM <RIDB) 1 ACCESSION NBR: 8710290162 DOC. DATE: 87/10/26 NOTARIZED: NO DOCKET ¹ FACIL: 50-400 Shearon Harris Nuclear Power Planti Unit ii Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION SCHWABENBAUER Carolina Power h Light Co.

WATSON'. A. Carolina Power 8. Light Co.

RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

LER 87-056-00: on 870924'eactor tripped,due to de-energization of P-13 permissvie bistable h insufficient mod installation instructions. Caused bg personnel error.

Procedure for mod implementation revised. W/871026 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR t ENCL TITLE: 50. 73 Licensee Event Report (LER)i Incident Rpti etc.

+ SIZE:

NOTES: Application for permit renewal filed. 05000400 RECIPIENT COPIES REC IP IENT COF IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 BUCKLEY'S B 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB i. 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEBT/ADS 1 0 NRR/DEBT/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEBT/ICSB 1 1 NRR/DEST/MEB 1 1 NRR/DEBT/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RBH 1 1 NRR/DEBT/SGB 1 1 NRR/DLPG/HFH 1 NRR/DLPG/G*H 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/R*B 1 1 NRR/DREP/RPB 2 2 NRR R I~BIB 1 1 NRR/PMAS/ILRB 1 1 EC M 02 1 1 RES DEPY GI 1 1 RES TELFORDi J 1 RES/DE/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EGSG GROHi M 5 5 H ST LOBBY WARD LPDR 1 1 NRC PDR NBIC H*RRISi J 1 1 NSIC MAYSi G

-TOT*L NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44 J

NAC Form 385 UA. NUCLEAR REOULATOAY COMMISSION (04)3)

APPROVED OMB NO. 3)500104 EXPIRES: SI31I88 LICENSEE EVENT REPORT tLER)

FACI(.ITY NAME (I) DOCKET NUMBER (2) PA E 3 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 04 00 1 OF03 REACTOR TRIP CAUSED BY THE DE-ENERGIZATION OF P-13 PERMISSIVE BISTABLE DUE TO INSUFFICIENT MODIFICATION INSTALLATION INSTRUCTIONS EVENT DATE (5) LEA NUMBER (SI REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

+xo: sSOUSNTIAL FACILITYNAMES DOCKET NUMBER(SI MONTH DAY YEAR YEAR HFil NUMBER O'r R MONTH OAY YEAR 0 5 0 0 0 0 2 4 87 87 056 0 0102 6 8 7 0'5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR (): ICheck one or more of the follovflnpI (II)

OPERATINO MODE (8) 20A02(8) 20.40S(cl 50.73(e) (2) (lv) 73.71(8)

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NAME TELEPHONE NUMBER AAEA CODE R. SCHWABENBAUER REGULATORY COMPLIANCE TECHNICIAN 91 9362 -2 669 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS AEPOAT (13) v "'or'.'o?v'AUSE r

'e MANUFAC. MANUFAC. EPORTABLE CAUSE SYSTEM COMPONENT SYSTEM COMPONENT TUREA TUAER TO NPADS ox I Xg'

>@SNg; SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE OSI YES Ilfyet, complete EXPECTED $ (fphtlSSION OATEI NO ABSTRACT ILlmir to 1400 rpecer, le., epproximetely flfreen rlnpreopece typewrftten lintel (18)

The plant was in Mode 4, Hot Shutdown, at 0 percent reactor power on September 24, 1987.

Work was in progress to implement a Plant Change Request which modified the Channel IV input to Auxiliary Feedwater isolation logic from process instrumentation. Installation instructions included an option to de-energize Card Frame 8 of Process Instrumentation and Control (PIC) cabinet 4, but did not identify the circuits which may be affected. LnsA of Card Frame 8 places all loops in PIC cabinet 4 in test.

Operations and Instrument and Control personnel reviewed applicable drawings and checked for instruments which would be disabled and also verified other protection channels were not in test or trip condition to prevent an occurrence of 2 out of 3 or 2 out of 4 logic.

O 0 (Y. When the fuses in Card Frame 8 were removed, bistable PS-447E de-energized

<wQ raoa. turbine impulse pressure had exceeded 10 percent power level and removed the P-13 input to indicating

~~/ P-7. Since the turbine stop valves were already closed, logic was completed to remove P-7 NG which resulted in a reactor trip at 0114 hours0.00132 days <br />0.0317 hours <br />1.884921e-4 weeks <br />4.3377e-5 months <br />.

CI) ~

The cause of the event was personnel error based on insufficient modification installation 0 <C instructions on what would result from de-energizing Card Frame 8.

Ql The corrective action/action to prevent recurrence is that the plant procedure for

)m~ modification implementation has been revised to provide more extensive guidance in the reparation of installation instructions.

This event is being reported in accordance with 10CFR50.73(a)(2)(IV).

NRC Form 388 ro.ov

NRC Form 388A U.S. NUCLEAR REGULATORY COMMISSION (9413)

LICENSEE EV NT REPORT (LER) TEXT CONTINUAT N APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/88 FACILITYNAME (I) DOCKET NUMBER (2) LER NUMBER LB) PAGE (3)

SHEARON HARRIS NUCLEAR POWER PLANT YEAR  :/PE: SEQUENTIAL ~+2m REVE)ION

na NUMBER i%A NUMBER UNIT 1 o s o o o 40'0 7 056 0 0 0 20F 0 3 TEXT /P/rrrre Bporo /4))r/rorL Irso a/I/one/HRC Forrrr 3BS4'4/ (17)

DESCRIPTION:

The plant was in Mode 4, Hot Shutdown, at 0 percent reactor power on September 24, 1987.

Shutdown banks C and D were withdrawn and all control and other shutdown banks at 6 steps in accordance with General Procedure (GP)-002, Normal Plant Heatup From Cold Solid to Hot Subcritical Mode 5 to Mode 3.

Work was in progress to implement Plant Change Request (PCR)-2292 which modified the Channel IV input to Auxiliary Feedwater (AFW) (EIIS:BA) isolation logic from process instrumentation. Installation instructions included an option to de-energize Card Frame 8 of Process Instrumentation and Control (PIC) (EIIS:JG) cabinet 4, but did not identify the circuits which may be affected. Loss of Card Frame 8 places all loops in PIC cabinet 4 in test.

Operations and Instrument and Control (16C) personnel reviewed the applicable drawings and checked for instruments which would be disabled and also verified that other protection channels were not in test or trip condition to prevent an occurrence of a 2 out of 3 or 2 out of 4 logic.

When the fuses in Card Frame 8 were removed, bistable PS-447E de-energized indicating

.turbine impulse pressure had exceeded 10 percent power level. This enabled "at power" reactor trips inputs which are normally blocked when both turbine or reactor power is less than 10 percent. As a result, the reactor trip on turbine trip was reinstated. The turbine stop valves were already closed so logic was completed for a reactor trip at 0114 hours0.00132 days <br />0.0317 hours <br />1.884921e-4 weeks <br />4.3377e-5 months <br />.

CAUSE:

The intermediate cause of the event was de-energizing Card Frame 8 which resulted in a reactor trip.

The root cause of the event was personnel error due to insufficient PCR installation instructions which did not indicate what would happen when Card Frame 8 was de-energized, including no list of affected bistables which would be de-energized/tripped. Also, instruction's were written for Mode 5, Cold Shutdown, installation though not specified on the PCR.

NRC FOAM BBBA *U.S.GPO:1988.0 824 538/455 (94LT)

NRC Fossm358A

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION

'.S. NUCLEAR REOULATORY COMMISSION APPROVEO OMB NO. 3150-0104 EXPIRES: 8/31/88 FACILITY NAME (1) OOCKET NUMBER (2) LER NUMBER (6) PACE (3)

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SHEARON HARRIS NUCLEAR POWER PLANT YEAR SEQUENTIAL REVSSION NUMBER NUMBER UNIT 1 400 87 00 03 OF 0 TEXT Ãsmssr<<vasss)I ~, Isse /I/FssF/NRC Fessss 358AB/(IT) o 5 o o o 0 5 6 3 ANALYSIS;.

This event is being reported in accordance with 10CFR50.73(a)(2)(IV).

There were no safety consequences resulting from this event as the plant was already shut down and all plant systems functioned as required. The trip would have occurred as described if the plant was in Modes 5, 4, and 3. In Mode 2, the trip would have occurred if the -turbine was not being rolled with steam. This trip would not have occurred if the reactor or turbine power was greater than 10 percent. Because the trip scenario is 'only possible at no-load or low-load, the consequence would be either negligible and bounded by reactor trips from higher power levels.

There have not been any similar events reported.

CORRECTIVE ACTION/ACTION TO PREVENT RECURRENCE:

Plant procedure MOD-204, Modification Implementation, has been changed to provide a more extensive guidance-in the preparation of installation instructions.

NRC FORM 3MA *U 8 OPO 1985 0.526 538/455 (983)

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I CPRL Carolina Power & Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 n

CD OCT 26 1987 File Number'SHF/10-13510C l C3 Letter Number'. HO-870522 (0)

G 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 87-056-00 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, R. A. Watson Vice President Harris Nuclear Project RAW:skm Enclosure cc. 'Dr. J. Nelson Grace (NRC RII)

Mr. BE Buckley (NRR)

Mr. G. Maxwell (NRC SHNPP)

MEM/LER-87-056/1/OS1