ML18009A853

LER 91-003-00:on 910121,missed Surveillance Test During Emergency Diesel Generator Fuel Oil Sampling.Caused by Personnel Error.Training Conducted for Chemistry Personnel & Procedure RST-209 revised.W/910319 Ltr

ML18009A853
Person / Time
Site:	Harris
Issue date:	03/19/1991
From:	Richey R, Verrilli M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-910028-(O), LER-91-003-01, LER-91-3-1, NUDOCS 9103270214
Download: ML18009A853 (6)

Text

ACCELERATED /STRIBUTION DEMONRATION SYSTEM 1

REGULATORY INFORMATXON DXSTRIBUTION SYSTEM (RIDS)

'CCESSION NBR:9103270214 DOC.DATE: 91/03/19 NOTARIZED: NO DOCKET I FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power & Light: Co.

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

RECIP.NAME RECIPXENT AFFILIATXON

SUBJECT:

LER 91-003-00:on 910121,missed surveillance test during emergency diesel generator fuel oil samplinq.Caused by personnel error. Training conducted for chemz.stry personnel &

Procedure RST-209 revised.W/910319 ltr.

IncidentQRpt, etc.

DISTRIBUTION CODE: IE22T COPIES RECEIUED:LTR I ENCL SIZE:

TXTLE: 50.73/50.9 Licensee Event Report (LER),

NOTES:Application for permit renewal filed. o5ooo4oo RECIPXENT COPXES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 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' 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 NRRJ+SZ/Q B.8D1 1 1 NRR/DST/SRXB 8E 1 '

1 RQG 1 1 RES/DSIR/EIB 1 RGN2 FILE 01 1 1 EXTERNAL: EG&G BRYCE,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 NOTE TO ALL "RIDS" RECIPIENTS PLEASE HELP US TO REDUCE %ASTE! 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 33 ENCL 33

Carolina Power & Light Company P. O. Box 165 ~ New Hill, N. C. 27562 R. 8. RlCHEY Vice President Harris Nuclea'r Project MAR 1 9 )99)

Letter Number.'HO-910028 (0)

U.S. Nuclear Regulator'y Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR'OWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 91-003-00 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, A( J~

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)

MEM/LER-91-003/1/OSl 5r10327021'4 910319 f/

Poli ADOCK 05000400 I/r

NRC FOAM 366 UN. NUCLEAR REGULATORY COMMISSI (689) APPAOVED OMB NO. 31504104

,EXPIRES; 4/30(92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION-AEGUESTI 600 HRS. FORWARD LICENSEE EVENT REPORT'(LER) COMMENTS REGARDING BURDENESTIMATE TOTHE RECORDS ANO REPORTS MANAGEMENT BRANCH IP4)30), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31600104). OFFICE OF MANAGFMENT ANO BUDGET. WASHINGTON, OC 20503.

FACII,ITY NAME nl DOCKET NUMBER (2) PA 5 3 Shearon Harris Nuclear Plant Unit Ill 0 5 0 0 0 P Q P 1 OFQ 3'ITLE (4)

Hissed Surveillance Test during Emergency Diesel Generator Fuel pil Sampling EVENT DATE (Sl LEA NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (6)

MONTH DAY YEAR YEAR SEOVSNTtAL RSVtSION OAY YEAR FACILITYNAMES DOCKET NUMBER(S)

NUMSESI tPX NVMSEII MONTH 0 5 0 0 0 0 121 919 1, 003 0 0 0 3 9 1 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT T0 THE RLOUIAEMENTS OF 10 CFR (I: (Check one or more ol the lollowlnp) (11)

MODE (9) 20,402(b) 20.405 (cl 50.73(e) (2)(NI 73.71(II)

POWER 20.405(e) (I) lll 50.36(cl(1) 50.73(el(2) (vl 73.7( lcl LFVEL 1 p p 20.405( ~ ) (1) (9) 50.36(c) l2) 60.73(e) (2)(vSI OTHER ISpeclly in 4hstrect oelow end In Text, IIRC Form 20.405(el(1(B6 I 50.73(e I l2) (Il 50.73(el(2)lrBI)(A) SSS4) 20.405(e) (I )(lr) 50,73(e) (2)(III i 50.73(e) (2) (rltl)IS) 20.405(el(1)(vl 50.73(e)(2) (ill) 50.73(el (2)(x)

LICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NUMBER Michael Verrilli Specialist Regulatory Compliance AREA CODE 91 936 2- 230 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) co.

CAUSE SYSTEM COMPONENT MANUFAC TVRER EPORTABLE TO NPADS

> . P% CAUSE'YSTEM COMPONENT MANUFAC TVRER EPORTAB LE TO NPADS P";

Nk.

" Ps(sxt7l texts o

o SUPPLEMENTAL REPORT'XPECTED IN) MONTH 88k% DAY YEAR EXPECTED SUBMISSION DATE (15)

YES IIIyes, complete EXPECTED SVShtISSIDN D4 TEI NO ABSTRACT ILlmlt to 1400 sprees, I.e., epproximetefy li Iteen slnprecpece typewritten lintel (16)

On January 21, 1991, a fuel oil shipment for the Emergency Diesel Generators arrived on-site. Technical Specifications contain specific sampling and analysis requirements for this oil, prior to off-load. During the sample process the required test to determine kinematic viscosity was inadvertently waive'd. The cause of this omission was an error during communications between laboratory personnel and technicians in the field. This condition was discovered during a routine documentation'eview by the Chemistry Foreman on 2/21/91. Upon discovery, the remaining sample was immediately tested for viscosity and was found to meet the applicable Technical Specification requirements'his event is being reviewed by the Chemistry Unit and the applicable procedures will be revised to provide more specific guidance regarding fuel oil sample and analysis requirements.

This event is being reported in accordance with lpCFR50.73 (a) (2) (i) (B) as a Technical Specification violation.

NRC Form 366 (669)

NRC FORM 366A US. NUCLEAR REGULATORY COMMISSION (64)9) r * .r r APPROVED OMB NO,31504104

'EXPIRES: 4/30/92 "LICENSEE EVENT'REPORT ILER) ',

• ESTIMATED~BURDEN'PER~RESPONSE TO'COMPLY"WTH 'THIS>>"

INFORMATION COLLECTION REQUEST: 500 HAS. FORWARD COMMENTS REGARDING BUADEN ESTIMATE TO THE RECORDS TEXT-CONTINUATION AND REPORTS MANAGEMENT BRANCH (PJ)30), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31500104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2)

LER NUMBER (5) PAGE (3)

Shearon Harris Nuclear Plant YEAR 5,. SEQUENTIAL ??O? REVISION NUMBER 8~rI NUM ER Unit'I)l 400 91 0 0 3 0. 0 P 20F P TEXT illmo>> <<>>oo JI >>EVP<<L 9>> odFB'oool NRC %%dmI 3BSEB) (17)

EVENT DESCRIPTION:

At approximately 0800 on January 21, 1991, while operating in Mode-1 at 100X power, a 'fuel oil shipment for the Emergency Diesel Generators arrived on-site.

Technical Specification (TS) 4.8.1.1.2.c.l sets forth sample and analysis requirements that must be satx.sfied prior to the fuel being off-loaded into the fuel oil storage tanks. Part (b) of this section specifically requires a kinematic viscosity test be performed, if the oil's gravity value (determined, at HNP lab) is not compared to the gravity value provided on the suppliers certificate. At 1020, Chemistry personnel obtained the required sample and transported it to the lab for analysis. , While performing the analysis and interpreting the data provided by the supplier, a communication error occurred between lab personnel and the technicians at the truck. Information was communicated to the technicians that was understood to be a comparison between HNP lab results for gravity and supplier provided gravity data. At this point the technicians 'considered the comparison to be complete, waived the'inematic viscosity test and approved the fuel oil off-load to the fuel oil storage tanks. During a subsequent documentation review on 2/21/91, the responsible Chemistry Foreman identified that this comparison had not actually been made and the viscosity test should have been conducted prior to off-load. At this point, it was determined that a TS surveillance requirement had not been satisfied. The foreman "'immediately initiated a test for kinematic viscosity on the remaining fuel oil sample, notified control room personnel of this condition and submitted an Adverse Condition Report for ev'aluation.

This event is being reported in accordance with 10CFR50.73 (a) (2) (i) (B) as a TS violation due to not performing a required surveillance test CAUSE:

The cause of this event was personnel error. This primarily involved communication between personnel in the field and those in the on-site laboratory. The result was the inadequate transfer of chemistry data during the analysis of the fuel oil samples. An additional contributing factor was a lack of familiarity on the part of the involved Chemistry personnel, with the vendor supplied documentation and the governing procedures for fuel oil analysis. This is an infrequent evolution that is performed approximately once every two .years.

There have been no similar events reported.

N AC FoIIB 366A (689)

NAC FORM366A C U.S. NUCLEAR AEGULATOAYCOMMISSIO (6$ 0) APPROVED OMB NO. 3)500104 EXPIRESI S)30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REOUESTI 500 HRS. FORWARD

'TEXT"CONTINUATION 'COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS

'OCKET ANO REPORTS MANAGEMENT BRANCH (F430). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. DC 20555, AND TO 1NE'PAPERWORK REDUCTION PROJECT (31504)OE). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, OC 20503.

FACILITYNAME u) NUMBER (2) PAGE (3)

LER NUMBER (6)

Shearon Harris Nuclear Plant YEAR iMII SEOUENTIAI NUMSEA IP)C REVISION 5 NUM EA Unit f/1 o s o o o4 00 ~

9 0 0 3 0 0 0 30F 0 3 TEXT N mom EFEES Is ISEUPAP, IIsp afIS5onal NRC %%dmI 36643) ()7)

SAFETY SIGNIFICANCE:

V I

There were no safety consequences as a result of this event. As determined by the viscosity analysis performed on 2/21/91, the fuel oil met TS requirements and had no adverse effects on the capability of the Emergency Diesel Generators to perform their design function.

CORRECTIVE ACTIONS:

1 ~ Satisfactory analysis for kinematic viscosity was conducted on the remaining fuel oil sample on 2/21/91.

2 ~ Training will be conducted for Chemistry =-

personnel to enhance their awareness of fuel oil. sampling and analysis requirements. This training will include a review of this event, applicable procedures, and . vendor supplied documentation for fuel oil shipments.

3. Procedure RST-209 is being revised to require a documented comparison of the suppliers gravity value to the gravity value determined by the HNP laboratory.

EIIS CODE INFORMATION:

Fuel Oil Storage and Transfer System DE NRC FianII 366A (666)