ML17279A569

LER 87-026-00:on 870824,during NRC Safety Sys Functional Insp,Determined That Table of Diesel Fuel Vs Tank Dipstick Level for Each Diesel Oil Storage Tank in Error.Caused by Inadequate Process Control of Plant setpoints.W/870925 Ltr

ML17279A569
Person / Time
Site:	Columbia
Issue date:	09/25/1987
From:	Powers C, Washington S WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-87-026, LER-87-26, NUDOCS 8709300211
Download: ML17279A569 (8)

Text

REGULA INFORMATION DISTR IBUTI STEM < R IDS)

ACCESSION NBR: 870930021 1 DQC. DATE: 87/09/25 NOTARIZED: NO DOCKET FACIL: 50-3'P7 WPPSS Nuclear Progecti Unit 2i Washington Public Pose 05000397 AUTH. NAME AUTHOR AFFILIATION WASHINGTON'. L. Washing ton Pub lie Power Supp 1 g System POWERS'. M. Washington Public Poeer Supply System RECIP. NAME REC IP IENT 'FFILIATION

SUBJECT:

LER 87;026-00: on 870824'uring NRC safety sos functional inspi determined that table of 'diesel fuel versus tank dipstick level for each diesel oil storage tank in error.

Caused bg inadequate error margin. W/870'F25 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR I ENCL I SIZE:

TITLE: 50. 73 Licensee Event Report (LER) Incident Rpti etc.

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NOTES:

. RECIPIENT COP IES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 PD5 PD 1 1 SAMWORTHi R 1 INTERNAL: ACRS MICHELSON 1 ACRS MOELLER 2 2 AEOD/DOA . 1 1 AEQD/DSP/NAS 1 1 AEQD/DSP/RQAB 2 2 AEOD/DSP/TPAB 1 1 DEDRO 1 1 NRR/DEST/ADS 1 0 NRR/DEST/CEB'RR/DEST/ICSB 1 1 NRR/DEST/ELB 1 1 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 S/SIB 1 1 NRR /P MAS/ ILR8 1 REG FIL 02 1 1

'RES DEP Y G I 1 RES TELFORDi J 1 1 RES/DE/EIB 1 RGN5 F ILE 01 1 1 EXTERNAL: EG8cG GRQH> M 5 5 H ST LOBBY WARD 1 1 LP D'R 1 l NRC PDR 1 1 NSIC HARRISi J 1 1 NSIC NAYS> G 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 43

NRC Form 365 U.S. NUCLEAR REGULATORY COMMISSION (04)3)

AppADYED DMB No. 3(600104 EXPIRES: 8(31(88 LICENSEE EVENT REPORT (LER)

FACILITY NAME (Il DOCKET NUMBER (2) PAGE 3 Washington Nuclear Plant Unit 2 0 5 0 0 0 3 9 7 1 QFO TITLE (4I sese enera or ore 1ese ue 1 e s n Limit Due To Inadequate Setpoint Process Control EVENT DATE IS) LER NUMBER (6) REPOAT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR ~:

)N%

SEGVENTrAL NUMBER MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER($)

0 5 0 0 0 091 58 7 8 7 0 2 6 0 0 0 925 87 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REOUIREMENTS OF 10 CFR (): (Check one or more of the follovffnp( (11 OPERATING MODE (8) 20A02(8) 20A05(c) 50.73(ell2)Ov) 73.7)(8)

POWER 20AOS ( ~ l(1)(i) 60>e(c)0) 60,73(e)(2)(v) 73.71(c)

LEYEL 0 9 8 20.405 ( ~ l(1) (8 I p

ONr'" 20A06( ~ l(1) (ill) 50.38(c) (2) 60.73(e I (2) (I)

(2)(vil) 60.73(e) (2)(vill)(8) 60.73(e) (2)(vBI)(Al OTHER (Specify In Ahstrect below end In Test, IVAC Form BSSA) 20A05( ~ l(1)(lv) 50.73(e) (2) (li) 50,73(e)

ICE Fr"'enr+ @ 20.405(el(1) (vl 60.73(e) (2) (ill) 60.73(el(2)(xl LICENSEE CON'TACT FOR THIS LER 02)

NAME TFLEPHONE NUMBER AREA CODE S.L. Washington, Compliance Engineer 50 93 77 208 0 COMPLETE ONE LINE FOR EACH COMPONENT FAILUAE DESCRIBED IN THIS REPORT (13) rl~ 2 840~

CAUSE SYSTFM COMPONENT MANUFAC.

TUREA REPOATABLE TO NPRDS 'PRg+'AUSE SYSTEM COMPONENT MANUFAC.

TURER EPORTABLE TO NPADS CAsr~

Mk9REIj23 SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE 116)

YES (II yes, complete EXPECTED SUB4IISSIDIV DATE( X NO ABSTRACT (Limit to (400 spices, I e., epproilmrnely flfteen slnpleepece typewritten lines( (Id)

On August 24, 1987 during an HRC Safety System Functional Inspection (SSFI) it was determined that the Table of Diesel Fuel (Gallons) versus Tank dipstick level for each Diesel Oil Storage Tank was in error. There are three Diesel Oil Storage Tanks at WHP-2, one associated with each Diesel/Generator Set. On September 15, 1987 using new tables based on new Generation Engineering calculations, Plant logs from July 1986 to September 1987 were reviewed and it was determined that there were four intervals during this period when the amount of fuel in a storage tank was below the Plant Technical Specification limit. These occurrences were for the Division 1 or 2 Diesel/Generator Systems only. The High Pressure Core Spray Diesel/Generator Storage Tank was never, for the review period, below its Technical Specification limit.

Corrective actions include: A Task Force is reviewing the setpoint process at WHP-2, new calculations for usable tank capacity versus dipstick level were completed, the Operation's equipment operator daily log sheets were revised with the new tank level criteria, the revised tables have been incorporated into the Plant Procedures, and the tank low alarm level setpoints will be changed.

The cause of this event was inadequate process control of Plant setpoints during the Startup of WHP-2. Secondly, the original calculations provided for an error margin but the margin proved insufficient to account for the discrepancies found during the re-calculation.

8709300211 870'))25 PDR ADOCK 05000397 S PDR NAC Form 3dd

NRC form 344A U.S. NUCLEAR REGULATORY COMMISSION (943)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3(50-0)04 EXPIR ES: 8/31/88 FACILITYNAME (11 DOCKET NUMBER (2) LER NUMBER (4) PAGE (3)

SEQUENTIAL PrIj REVISION re NUMEER '.;i NUMEER Washington Nuclear Plant Unit 2 0 5 0 0 0 39 787 0 2 6 00 02 0 4 TEXT /// moro Epocc )I Iocvircr/, PEP ~ //oooo/HRC form 385A3/ ((7)

Abstract (cont'd.)

There are no adverse consequences to Plant Safety associated with this event because Division 1 and 2 Diesel/Generator Systems are redundant, and there was never a case found during this review where both tanks were low at the same time.

Also,'he worst case found resulted in a six (6) day and sixteen (16) hour capacity at maximum load versus the required seven (7) days, and two outside sources of diesel fuel are available within twenty four hours.

Plant Conditions a) Power Level 985 b) Plant I/Iode 1 Power Operation Event Descri tion On August 24, 1987 during an HRC Safety System Functional Inspection it was determined that Plant Procedure Tables of usable fuel oil in the diesel oil storage tank versus the tank dipstick level were in error. Plant Technical Specifications, 3.8.1.1 "A. C. Sources Operating" and 3.8.1.2 "A.C. Sources Shutdown" both require a fuel oil storage system with a minimum of 53,000 gallons for DGl and DG2 (DO-TK-1A 8 18) and 33,000 gallons for DG3 (DO-TK-2).'

review of Plant logs for one year (July 1986 to'resent) determined that there were four intervals (see Table 1) when the actual amount of usable fuel oil in a Division 1 or 2 tank was below the Technical Specification limit. There were no cases. found when the High Pressure Core Spray Diesel Generator fuel oil was below its Technical Specification Limit. The worst case discovered by this review was between October 6 through 17, 1986, when the oil level in the, storage tank for DG1 reached 50,230 gallons. The event duration was from Plant Startup to September 1987.

The results of the errors causes the Diesel Oil Storage Tank Low Level alarm to actuate at 51,108 gallons for the DG1 and DG2 Storage Tanks, 1,892 gallons below the Technical Specification limit, and 31,700 gallons for- the DG3 tank, 1,300 gallons below the Technical Specification limit.

NRC FORM 344A RU.S.GPO,1988 0 824 538/455 1903)

NRC form SSSA U.S. NUCLEAR REGULATORY COMMISSION (94)3)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3)50&104 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (3) LER NUMBER (6) rAGE (3)

YEAR SEOVENTIAL I II V IS IO N NVMOER NVMOEA OF Washington Nuclear Plant . Unit 2 0 5 0 0 0 3 9 7 8 7 0 2 6 0 0 TEXT /// mo/e AOece /4 Ieevnd, oeo /d/Oo'one/ HRC fomI 3/)Sl'I/ ((T)

TABLE 1 List of dates when the amount of diesel oil in a storage tank was below Technical Specification limits. Technical Specification limit 53,000 gallons.

Date Plant 0 eratin Hode Division Gal 1 ons October 6, 1986 50,230 through October 17, 1986 December /I, 1986 52,380 through December 11, 1986 January 28, 1987 51,960 Harch 28, 1987 51,960 through April 1, 1987 The root cause of this event was inadequate process control of setpoint calculations during the startup of MNP-2. This area was evaluated during the NRC SSFI. The specific cause for this event was an inadequate error margin in the original calculation which fai'led to account for the dead storage oil (oil below the transfer pump suction), volume of the structural steel internal to the tank, and the proper head shape. of the tank.

Intermediate Corrective Action Hew calculations for each Diesel Oil Storage Tank were completed and Plant Operations was given new values for the daily dipstick measurements that verify compliance with the Technical Specification limits.

Further Corrective Action and Evaluation The table of usable tank capacity (gallons) versus the dipstick measure was revised and was incorporated into Plant procedures.

The low level alarm setpoint Haster Data Sheet is being revised and the instruments will be recalibrated to a new trip setpoint that will alarm prior to reaching the minimum Technical Specification fuel oil limit.

A Task Force led by a Plant Engineering Hanager is reviewing the setpoint process based on the findings of the NRC SSFI. It is expected that this review will result in further corrective actions which will be tracked by our response to the SSFI Report.

NRC FORM SSSA o U S GPO.1988 0 834 538/455 (983)

NRC Fmm 366A U.S, NUCLEAR REGULATORY COMMISSION 19831 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROV EO OMB NO. 3150&IOA EXPIRES: 8/31188 FACILITYNAME 111 OOCKET NUMBER l31 LER NUMBER 161 PAGE 131 YEAR SEOVENTIAL SIP REVISION NVM86 II NUMBER IIIashin ton Nuclear Plant - Unit 2 o s o o o 39 787 0 2 6 0 0 OF TEXT Cfmom ppACP 1P fpqv&d. NAP RRPfBAAfPIRC fomI 3556 Bl 1131 The MNP-2 Technical Specifications (LCO 3/4.8.1.1 and LCO 3/4.8.1.2) does not have an action statement specifically related to the fuel oil requirements and requires either testing of the remaining diesels (which exacerbates the problem) or application of Technical Specification 3.0.3. The Supply System intends to prepare a license amendment request to add an action statement associated with the fuel oil requirement.

Safet Si nificance The design bases for fuel storage is to provide enough fuel for each Diesel/Generator System to operate continuously for seven (7) days at post LOCA maximum load demands. The Division 1 and 2 Diesel Generators are redundant and one unit is required to safely shutdown the Plant. No cases were found where 'nly both tanks were below the Technical Specification limit at the same time. During this event the worst case provided enough fuel for six (6) days and sixteen (16) hours of operation at maximum demand. Two outside sources of diesel fuel are available to the Plant within twenty four hours. Therefore, due to the redundancy of the Division 1 and Division 2 Diesel Generator Systems and the fact that both divisions maintained a minimum of 955 of the capacity requirement and was additionally backed by offsite fuel sources, there are no adverse safety consequences associated with this event.

Similar Events None EIIS Information Text Reference EIIS Reference System Component Diesel Generator (DG-1, DG-2) EK DG High Pressure Core Spray Diesel Generator (DG-3) EK -DG Diesel Oil Storage Tank DC TK (DO-TK-)A, DO-TK-18, 5. DO-TK-2)

,NRC FORM 366A ~ U SGPO 1986 OBEA 538/455 (9831

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 Docket No. 50-397 September 25, 1987 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO.87-026

Dear Sir:

Transmitted herewith is Licensee Event Report No.87-026 for the WNP-2 Plant.

This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportabi lity, corrective action taken, and action taken to preclude recurrence.

Very truly yours,

.H. Powers (H/D 927M)

WNP-2 Plant Manager CMP:db

Enclosure:

Licensee Event Report No.87-026 cc: Hr. John B. Hartin, NRC Region V Hr. C. 3. Bosted, NRC Site (H/D 901A)

INPO Records Center Atlanta, GA Hs. Dottie Sherman, ANI Hr. D. L. Williams, BPA (H/D 399)

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