ML17284A537

LER 88-029-00:on 880824,RCS Unidentified Leakage Noted to Be in Excess of 5 Gpm Tech Spec Limit & RCIC Steam Supply Inboard Isolation Valve Had Large Packing Leak.Caused by Maint Program deficiency.W/880922 Ltr

ML17284A537
Person / Time
Site:	Columbia
Issue date:	09/22/1988
From:	Davison W, Powers C WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-029, LER-88-29, NUDOCS 8810040071
Download: ML17284A537 (6)

Text

t gO AC CELERATED DISI'RIBUTION DEMONS ATION SYSTEM Cl(

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8810040071 DOC.DATE: 88/09/22 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS'uclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION DAVISON,W.S. Washington Public Power Supply System POWERS,C.M.'ashington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 88-029-00:on 880824,plant shutdown required by Tech Specs due to high RCS unidentified leakage caused by MPD.

W/8 - ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ( ENCL 3 SIZE: D TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:

RECIPIENT COPIES RECIPIENT COPIES 1' ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1- 1 SAMWORTH, R 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB'H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 RRQZRM/S-I'I4Q+ 1 1 NUDOCS-ABSTRACT '1 1 0 1 RES TELFORD,J 1 1 RES/DSIR DEFY 1 1 RES/DSIR/EIB 1 1 RGN5 FILE 01 1 1 EXTERNAL: EG&G WILLIAMS,S 4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 1'

'D S

TOTAL NUMBER OF COPIES REQUIRED: LTTR 46 ENCL 45

NRC Form 368 V.S. NUCLEAR REGULATORY COMMISSION (94)3)

APPAOVED OMB NO. 3160-0104 EXPIRES: 8/31/88 LICENSEE EVENT REPORT (LER)

FACIL,ITY NAME (II DOCKET NUMBER (2) PAGE 3I Washin ton Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 I OF Q 4

"'"lant Shutdown Required by Technical Specifications Due to High Reactor Coolant System Unidentified Leakage Caused by t1aintenance Program Deficienc EVENT DATE (5) LEA NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8I YEAR SEGVENTIAL DAY YEAR FACILITYNAMES DOCKET NUMBER(5)

MONTH DAY YEAR NVMOESI NISMSEA MONTH 0 5 0 0 0 08 48 8 0 2 9 00 92 8 8 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR (I: (Check ont or mort of rht followinPl lll)

MODE (9) ,20.402((sl 20.405(cl 60.73(sH2)(iel 73.71(8) 1 POWER 20.406( ~ ) (1)(il $ 0.38 (cl (I I 60,73( ~ )(2)(e) 73.71(c)

LEVEL 1 O P 20 405(e l(1) (ii) 50.38(c) (2) 50.73(s)(2) (sir) OTHER fSptcify in yioslrtcr ptiow tnd in Terr, NRC Form 20.405( ~ l(1) (rSI 60.73(s) (2) (I) 50 73(el(2l(eiii)(AI 366AI 20.405 ( ~ ) I 1)(Ir) 60.73(s I l2) (ii) 50.73(s I (2) I Hriil (8)

'A+. 0o' 20,405( ~ I II ) lel 50.73( ~ ) (2) (iiil 50.73(sl(2)ls)

LICENSEE CONTACT FOR THIS LER I12I NAME TELEPHONE NUMBER AREA CODE W.S. Davison Com liance En ineer 0 9 coMPLETE GNE LINE FoR EAcH coMPDNENT FAILURE DEscRIBED IN THIS REPGRT (13) Ext, 2726 MANUFAC. REPORTABLE MANUFAC. REPORTABLE CAUSE SYSTEM COMPONENT TVRER TO NPAOS CAUSE SYSTEM COMPONENT TVRER TO NPRDS ~ji>@+@%

'(.":"48+>'c>>)

(Sr".,'UPPLEMENTAL REPORT EXPECTED (14) "

MONTH DAY YEAR EXPECTED SUBMISSION DATE (15)

YES fir yts, compitrt EXPECTED S(fBMISSfOhf DATE) X NO ABSTRACT fiimir ro f400 sptcn, l t., tpprosimtrtiy fifrttn sinprt specs ryptwrintn linnl (16)

On August 24, 1988, at 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br />, plant operators observed, Reactor Coolant System Unidentified leakage to be in excess of the 5 gallons per minute Technical Specification limit. An Unusual Event was declared, the plant was shutdown and cooled down to Cold Standby. The Reactor Core Isolation Cooling Steam Supply Inboard Isolation valve (RCIC-V-63) was found to have a large packing leak. At 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br /> on August 25, 1988,,

after achieving Cold Shutdown conditions, the Unusual Event was terminated. The root cause was evaluated as a maintenance deficiency in that no preventative maintenance program exists for. valve packing. Had a preventative maintenance program existed, an opportunity to remove the valve lantern ring and properly sequence the packing would have been provided during routine maintenance activities. Corrective actions .consist of revising the plant maintenance procedure, identification of all in containment valves which may require repacking to 'prevent similar occurrences and implementation of a preventative maintenance program to repack those valves. This event posed no threat to the safety of Plant personnel or the public.

38i004007i 880922 PDR ADOCK 0 000 97 p

8 PDC NRC Form 388

NRQ Pono 3SSA U.S. NUCLEAR REOULATORY COMMISSION (943 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3150M/04 EXPIRES; 8/31/88 OOCKET NUMSER (21 LER NUMBER (Sl ~ AOE IS)

VEAR QIE SEOUENTIAL NN NUM ER (Nj REVISION NUMSE/I Washington nuclear Plant - Unit 2 o s o o o 397 8 0 2 9 0 0 0 2 oF0 4 TEXT /8'xvO AOACO /I IOOvnd, ooo NRR/ono/JVRC  %%dnn 3/NA3/1121 Plant Conditions a) Power Level - 100%

b) Plant Mode - 1 (Power Operation)

Event Descri tion On August 24, 1988, at 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br />, plant operators observed Reactor Coolant System

. unidentified leakage to be in excess of the 5 gallons per minute maximum listed in Plant Technical Specifications. As required by plant procedures, an Unusual Event was declared and telephone notifications were made at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />. A normal plant shutdown was commenced at 1137 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.326285e-4 months <br /> with reactor hot shutdown (Mode 3) being achieved at 1411 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.368855e-4 months <br />.

Containment Drywell entry was made at 2144 hours0.0248 days <br />0.596 hours <br />0.00354 weeks <br />8.15792e-4 months <br /> to inspect for the sources of unidentified leakage. At 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br />, RCIC-V-63, (Reactor Core Insolation Cooling Steam Supply Inboard Isolation Valve) was reported as having a large packing. leak.

Further detailed inspection ide'ntified RCIC-V-63 as being the major source of leakage into the Drywell.

At 2310 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.78955e-4 months <br />, the decision was made to proceed to Operational Mode 4 Cold Shutdown to make repairs to the valve. Required plant surveillances were initiated and plant cooldown was commenced. Th'e cooldown proceeded normally with Reactor Heat Removal Shutdown Cooling (RHR SDC) being initiated at 0423 hours0.0049 days <br />0.118 hours <br />6.994048e-4 weeks <br />1.609515e-4 months <br /> on August 25, 1988.

At 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br />, the Unusual Event was terminated and appropriate noti'fications were made.

Further Evaluation

1. This LER is written pursuant to the requirements of 10CFR50.73 (a)(2)(i)(A) to document the completion of a "nuclear plant shutdown required by the Plant's Technical Specifications;"

l

2. The excessive uni denti fi ed 1 eakage was veri fied by the use of both .the installed instrumentation and manual volumetric measurement techniques.

Throughout the duration of the shutdown, the leakage was monitored at an increased frequency to provide trend information.

3. RCIC-V-63 is the primary containment inboard isolation valve for the steam supply line to the RCIC turbine and is not isolable from the reactor pressure vessel. It is a 10 inch motor operated gate valve manufactIIred by Velan Valve Company.

4. Examination of RCIC-Y-63 revealed that portions of the installed valve packing had been extruded through the area between the valve stem and packing gland bushing.

NRC SOIIM ESSA o U.S OPO:1988~24 538/Edd L9831

NRC Forro U.S, NUCLEAR REOULATORY COMMISSION 355A'0431 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3150&104 EXPIRES: 5/31/55 FACILITY NAME (11 DOCKET NUMSER (31 LER NUMSER (SI PACE 13i SEQVENTrAL REVISK)N NVM E4 NVMSE4 Washington Nuclear Plant - Unit 2 o s o o o 39 788 029 0 0 03 OF 0 4 TEXT /// more <<wee /r eeo/'rerE 4>> /A/o/A'4/ //AC Form 3//5AS/ (17)

5. The root cause of this failure was determined to be a maintenance progr'am deficiency, in that, no preventative maintenance program exists for "high risk" valve packing. A potential thus exists for this type. of failure in other "high risk" valves (i.e., those inside primary containment). As part of the event analysis, a random sampling of the records for this high risk family of valves was conducted. This sampling identified no valves which had lantern rings installed. For valves with no lantern ring, PPM 10.2.7 is adequate to ensure proper sequencing of valve packing.

6. A contributing cause of this event has been determined to be procedural inadequacy in that the plant procedure PPM 10.2.7 "Valve Troubleshooting, Handling and Repair" did not contain specific instruction addressing only the addition of packing instead of repacking a valve completely. Corrective maintenance was last performed on the packing of this valve in November of 1986. At that time, packing was successfully added to the valve to stop leakage.

If the valve had been completely repacked, the specific steps of PPM 10.2.7 covering repacking would have directed the removal of lantern rings to increase packing reliability and installation of packing in the sequence recommended by the manufacturer. Instead, since addition of packing is not specifically covered, the procedure was not used and valve maintenance may have been performed in a manner which resulted in an increased probability of packing leakage. Also, for valves with lantern rings, PPM 10.2.7 does not require braided packing above and below the lantern ring as recommended by the manufacturer. '

Corrective Action PPM 10.2.7 will be revised to include specific instr uction on sequencing of packing during both packing addition and complete repacking evolutions based upon recommendations from manufacturer technical manuals.

2. The "high risk" family of valves will be identified and; a review of valve packing records will be performed to determine if lantern rings are installed.

3. An evaluation will be performed to determine the need for a preventative maintenance program to repack "high risk" valves and to remove lantern rings if appropriate.

Sa fety Si ni fi cance All appropriate plant operating procedures, emergency procedures and Technical Specifications relating to unidentified leakage were correctly followed during this event. The operations and management staff functioned to guide the plant in a conservatively safe manner to a shutdown condition well within the time frames listed in the plants Technical Specifications. This event posed no threat to the safety of Plant personnel or the public.

NRC FORM ESSA 4 U.S.GPO:1055&524 535/455 (0431

NRC Form 3SSA U.S. NUCLEAR REOULATORY COMMISSION

)04)3)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3)50M)04 EXP)RES) 8/31/88 FACILITY NAME 11> DOCKET NUMBER l2) LER NUMBER IS) PACE )3)

YEAR SEQUENTIAL II4 V IS IQ N NUM S rl NUMSER Washington Nuclear Plant - Unit 2 0 5 Q 0 0 9 7 8 0 9 0 0 0 4 OF 0 4 TEXT ///more Aoece ir rer)Mired, eee ~ //oroe///RC Fcnrr %MY> l)T)

Similar Events None EIIS Information Text Reference EIIS Reference System, Component Reactor Coolant System NH Containment Drywell NH RCIC-V-63 BN RHR SDC BO Reactor Pressure Vessel NH NRC FOIIM 344A *U.S.GPO;108HH24838/4SS

)043>

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George t1'ashington N'ay ~ Richland, H'ashington 99352

-Docket No. 50-397 September 22, 1988 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C . 20555

Subject:

NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO. 88-029-00

Dear Sir:

Transmitted herewith is Licensee Event Report No. 88-029-00 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, C. . Powers (I'D 927M)

WNP-2 Plant Manager CMP:sm

Enclosure:

Licensee Event Report No. 88-029-00 cc: Mr. John B. Martin, NRC - Region V Mr. C.J . Bosted, NRC Site (M/D 901A)

INPO Records Center - Atlanta, GA Ms. Dottie'herman, ANI Mr. D.L. Williams, BPA (0/D 399)