ML18009A761

LER 90-023-00:on 901124,emergency Diesel Generator a Inadvertently Started.Caused by Operator Failure to Correcty Verify Component Under Test.Operator Counseled Re self- verification.W/901219 Ltr

ML18009A761
Person / Time
Site:	Harris
Issue date:	12/19/1990
From:	Barker D, Richey R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-900205-(O), LER-90-023-01, LER-90-23-1, NUDOCS 9012280113
Download: ML18009A761 (5)

Text

ACCELERATED DIS TBUTION DEMONSTIW. ON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9012280113 DOC.DATE: 90/12/19 NOTARIZED: NO DOCKET FACXL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION BARKER,D.W. Carolina Power & Light Co.

RXCHEY,R.B. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 90-023-00:on 901124,emergency diesel generator A inadvertently started. Caused by operator failure to correcty verify component under test. Operator counseled re self- D verification.W/901219 ltr.

DISTRIBUTION CODE: XE22T COPIES RECEIVED:LTR ENCL SIZE:

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

NOTES:Application for permit renewal filed. o5ooo4oo A D

RECIPXENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-1 LA 1 1 PD2-1 PD 1 1 BECKER,D 1 1 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPBll 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 PLB8D1 1 1 NRR/DST/SRXB 8E 1 1 EG FX 02 1 1 RES/DSXR/EIB 1 1 RGN2 ILE 01 1 1 EXTERNAL EG&G BRYCE g J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 D

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR ENCL 3

Carolina Power 8 Light Company P.O. Box 165 ~ New Hill, N. C. 27562 R. B. RICHEY Vice President Harris Nuclear Project Letter Number'. HO-900205 (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 90-023-00 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. B. Richey Vice President Harris Nuclear Project RBR:msb Enclosure cc: Mr. R. A. Becker (NRR)

Mr. S. D. Ebneter (NRC RII)

Mr. J. E. Tedrow (NRC - SHNPP) 9012280113 901219 PDR 4DOCK 05000400 S PDR HEM/LER-90-023/1/OS1

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (64)9) APPROVEDOMB NO.3)504))04 E XP IR E S: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LlCENSEE EVENT REPORT (LER) COMMENTS REGARDING BUAOEN ESTIMATE TO THE RECORDS AND AEPOATS MANAGEMENT BRANCH (F830), V.S. NUCLEAR AEGULATOAYCOMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3(504104), OFFICE OF MANAGEMENTAND BUDGFT, WASHINGTON, DC 20503.

FACILITY NAME III DOCKET NUMBER (2) PA E SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 TITLE ( ~ I 0 5 0 0 04 00ioF03 Inadvertent Start of 'A'mergency Diesel Generator

'VENT DATE (5) LE R NUMBER (4) REPORT DATE (7I OTHER FACILITIES INVOLVED (4)

MONTH DAY YEAR YEAR P/F<~ SSOUENTIAL MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(s)

NUM8ER ('II'UMSSR 0 5 0 0 0 11 24 9 090 0 2 3 00 12 19 90 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT To THE RLOUIREMENTS OF 10 CFR (); ICh<<h onr or morr of the foffrrrinr/ (11)

OPERATING MODE (9) 20.402(4) 20.405lcl 50.73(s) (2)(Ic) 73.71(5)

POWER 20.405(s l(1 I (II SOM(cl(ll 50.7$ (el(2)NI 73.71(cl LEYEL 0 0 0 20 405(sl(1 l(SI 50.34( cl(2) 50.73(s)(2) (oil) OTHER /Specify in Ahtooct i>>fonr rmf in Trit, Hf(C Form Y vrCi 20.406( ~ ) (I l(iii) 50.7$ (s l(2)(il 50.7$ (s) (2) (rill) (AI 3EEAI 20A05(sl(1 l(N) 50.73(s l(2) I 8) 50,7$ (s)(21(rlSI(BI 20.406(s) (1)(r) 50.73(el(2) IIQ) 60.7$ (sN2) (xl LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER David W. Barker AREA CODE Regulatory Compliance Specialist 919 362 25 0 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFAC.

TURER TO NFROS 9 .: c I): m; CAUSE SYSTEM COMPONENT MANUFAC.

TVRER EPORTABLE TO NPAOS r

r,rr i., I SUPPLEMENTAL REPORT EXPECTED ('l4) MONTH OAY YEAR EXPECTED SUBMISSION DATE (15)

YES /if yet, ctmorfrte EXPECTED Suaht/SS/OH OA rEI NO ABBTRAOT ILimlt to /400 u>>cet, I r., epproiimrtely fifteen tinpfeeprce typrnrrfttrn lin<<I (14)

On November 24, 1990, the plant was in Mode 5, 150'F with Reactor Coolant System fill and vent in progress. At 1004 a licensed reactor operator was conducting a slave relay test (OST-1084 ESFAS Train "B" Slave Relay Test) as a retest following work on valve BD-20. Step 5 of the procedure directs the operator to "Open Protection System Safeguards Test Train "B" Cabinet 2 door and, with Shift Foreman's approval, commence slave relay test." The operator mistakenly went to the "A" train Cabinet 2 door and energized slave relay K610 resulting in an inadvertent start of the "A" Emergency Diesel Generator (EDG). The cause of this event was failure on the part of the operator to adequately identify the component under test. The "A" EDG started and ran normally and would have responded to an Engineered Safety Feature (ESF). signal if required. All other components actuated to their ESF required positions correctly There were no safety consequences resulting from this event.

This event is being reported in accordance with 10CFR50.73 (a) (2) (iv) as an actuation of an ESF.

NRC Ferns 368 (689)

NRC FORM 365A UN. NUCLEAR REGULATORY COMMISSION

((+9) PROVED OMB NO. 31500'104 EXPIRES: 4/30/92 LICENSEE EVENT REPORT (LER) ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTI 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP430). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, ANO TO THE PAPERWORK REDUCTION PROJECT (3)S0010i). OFFICE OF MANAGEMENTANO BUDGET, WASHINGTON,OC 20503.

FACILITYNAME (11 DOCKET NUMBER (2)

LER NUMBER (5) PAGE (3)

YEAR SEQUENTIAL IIEVISION SHEARON HARRIS NUCLEAR POWER PLANT NVMSSII HVMSSII UNIT 1 o4 00 023 TEXT ///m//m ~ b m//v/red, usr //I'0BIM/NRC Ann 35((43/(17) o 5 o o 9 0 0 0 2 OF 0 3 EVENT DESCRIPTION:

the plant was in Mode 5, 150'F with Reactor Coolant System fill and"B"vent24,in1990, On November progress. A slave relay test {Section 7.5 of OST-1084, ESFAS Train Slave Relay Test) was being performed as a retest following work on valve BD-20. At 1004 a licensed reactor operator was performing Step 5 of the procedure, which states, "Open Protection System Safeguards Test Train "B" Cabinet 2 door and, with Shift Foreman's approval, commence slave relay test."

The operator mistakenly went to the "A" train Cabinet 2 door. The trains are physically arranged in a line of 10 cabinets with five in each train. The outside of each cabinet is labeled with the train designator located near eye level. Labeling was determined not to be a contributing factor in this event. A communications headset had been left near the "A" train door from a previous test. The operator saw the headset and thought it had been placed there for the test he was conducting. The operator verified the correct cabinet door, but not the correct safety train. The operator energized the slave relay per the test procedure, but since he was on the "A" train, the "A" EDG started.

CAUSE:

The cause of this event was failure on the part of the operator to correctly verify the component under test.

SAFETY SIGNIFICANCE:

There were no significant safety consequences as a result of this event. The "B" EDG was in the maintenance mode to prevent it from starting on the slave relay test. The "A" 'EDG started when the wrong train slave relay was actuated. The "A" EDG started and ran normally and would have responded to an ESF signal if required. All other affected components actuated to their ESF required positions correctly. LER 89-013 discussed an event where incorrect electrical contacts were jumpered during troubleshooting causing actuation of an ESF component.

CORRECTIVE ACTIONS:

1. The individual operator involved was counseled on the importance of self-verification in task performance.

2. A review of the self-verification process with all applicable operations personnel will be performed in the next annual training.

NR C Form 3SBA (BB9)

NRC FOAM 368A ILS. NUCLEAR REGULATORY COMMISSION (669) PROVED OMB NO. 315001(M EXPIRES: o/30/92 LICENSEE EVENT REPORT (LER) ESTIMATED BURDEN PEA RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP630), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (3)500)OOI. OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON, DC 20503.

FACILITYNAME (ll DOCKET NUMBER (21 LER NUMBER (8) PAGE (3)

YEAR SEQUENTIAL IIEVISION HARRIS NUCLEAR POWER PLANT

'HEARON NVMOB/l NVMBSN UNIT 1 o 5 o o o 400 90 0 2 3 0 0 03 op 0 3 TEXT RY m<<o Joooo lo>>qo/oN/ o>> <<R/R/<<>>//VRC F<<nJ 36649/ (17)

EISS CODE INFORMATION:

Emergency Diesel Generator Engineered Safety Features Actuation System JE NR C Form 388A (669)