ML18005A698

LER 88-030-00:on 881008,steam Generator Pressure in turbine- Driven Auxiliary Feedwater Pump Steam Supply Heater Noted. Caused by Inadequate Shift Turnover During Valve Repair During Outage.Valve Seated properly.W/881107 Ltr

ML18005A698
Person / Time
Site:	Harris
Issue date:	11/07/1988
From:	Howe A, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-880227-(O), LER-88-030, LER-88-30, NUDOCS 8811100277
Download: ML18005A698 (8)

Text

4 M IBUTION DEMONSTRA ON SYSTEM I j.

. AC.CELEBRATED REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8811100277 DOC.DATE: 88/11/07 NOTARIZED- NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION HOWE,A.J. Carolina Power & Light Co.

WATSON,R.A. Carolina Power & Light, Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 88-030-00:on 881008,tech spec required cooldown due to inoperable containment isolation valves.

W/8 ltr.

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

NOTES:Application for permit renewal filed. 05000400 ~

RECIPIENT COPIES RECIPIENT COPIES ID ID LTTR ENCL CODE/NAME PD2-1 LA BUCKLEY,B LTTR ENCL 1

1 1

1 CODE/NAME PD2-1 PD 1, 1 A ~

INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 9

ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 '

DEDRO 1 1 NRR/DEST/ADS 7E 1 0 8 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 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 NRR/DRIS/SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 BII ~CE.-:- 1 1 RES/DSIR/EIB 1 1 RES/DSR/PRAB 1 1 RGN2 F1LE 01 1 1 EXTERNAL EG&G WILLIAMSI S 4 4 FORD BLDG HOY,A 1 1 R H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS I J 1 1 I

NSIC MAYS,G 1 1 D

J' NOTE IO ALL RIDS" RECZPIIWZS:

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NRC Form 355 UAI. NUCLEAR REOULATOAY COMMISSION (94)3)

APPROVED OMR NO. 31500104 EXPIRES: 5/31/SS LICENSEE EVENT REPORT {LER)

FACILITYNAME (1) DOCKET NUMBER 12) PA E 3 SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE 0 5 0 0 04 00 1 OFO TECHNICAL SPECIFICATION REQUIRED COOLDOWN DUE TO INOPERABLE CONTAINMENT EVENT DATE (5) LER NUMBER (5) REPORT DATE l7l OTHER FACILITIES INVOLVED (Ql MONTH OAY YEAR YEAR SQOVQNTIAL MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER(5)

'UMSQA 0 5 0 0 0 1 0 08 88 88 0 3 0 0 0 0 6 0 0 0 OPERATINO THIS REPORT IS SUSMITTEO PURSUANT TO THE REOVIREMENTS OF 10 CFA (): (Check one or more of the follovflnfl(11)

MODE (5) 20.402 (b) 50.73(e) (2)(lvl 73.71DI) 20AOS(c)

POWER 20AOS(e) (1)(0 SOM(c)(l) 50.73(e) (2)(rl 73.71(cl LEYEL O O O 20AOS(e) (I l(Q) SOM(c)(2) 50.73(e) (2)(rQ) OTHER (Specify ln Ahrtrect helorr end In Text, NRC Form 20AOS(e)(I)(QI) 50.73(el(2)(I) 50.73(e)(2)(vQI)(Al 366AI 20AOS(e) II)(Iv) 50.73(el(2) (5) 50,73(e) (2) (rQI) (B) 20AOS(e) l1) (rl 50.73(e) (2) (QI) 50.73 4) (2) (x)

LICENSEE CONTACT FOR THIS LER l12)

NAME TELEPHONE NUMBER AREA CODE Andrew J. Howe Senior Specialist

9. 19 362 -27 19 COMPLETE ONE LINE FOll EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) xc MANUFAC REPORTABLE MANUFAC- EPORTABLE CAUSE SYSTEM COMPONENT TO NPAOS CAUSE SYSTEM COMPONENT TVRER TURER TO NPROS 9

'c A S B .I S V A 391 Y ,o ...y,,;AM vA rn SVEPLEMENTAL REPORT EXPECTED (1C) MONTH DAY YEAR EXPECTED SUBMISSION DATE 05)

YES Ilfyer, complete EXPECTED SVSQIISSIDhr DATE/ NO AsSTRAOT Ivmlt to Ic00 rpecet, I.e., eppnrxlmetely fifteen tlnoleepece typtwrltNn llnNI (15)

The plant was in Mode 4 at 345'F Reactor Coolant System (RCS) temperature, heating up following a refueling outage. On October 7, 1988, at 0530, operators observed steam generator pressure in the Turbine Driven Auxiliary Feedwater Pump steam supply header, downstream of the closed containment isolation valves. Attempts to depressurize the header during the morning were unsuccessful, and both isolation valves were declared inoperable due to suspected excessive seat leakage.

The plant was cooled down to 205'F RCS temperature to permit the isolation valves to be removed and inspected. Maintenance personnel determined that the disc of one of the two valves had not been properly fitted to the seat during recent repairs, completed during the outage, prior to returning the valve to service. This was corrected, and both valves were reassembled and returned to service on October 9. These inspections and repairs required more time than was allowed by Technical Specifications, so the plant was taken into Mode 5 at 2318 on October 8 as required by the action statement.

The cause of the event was inadequate shift turnover between mechanics repairing the valve during the outage. The turnover process during outages will be enhanced to prevent recurrence.

8811100277 881107 PDR AGQCK 05000400 F)9(

NRC Form 355 (94)3)

NRC Form 35SA U.S. NUCLEAR RECULATORY COMMISSION (94(3(

LICENSEE EVENT REPORT (LER} TEXT CONTINUATION APPROVEO OM8 NO. 3150-0104 EXPIRES: 8/31/88 FACILITYNAME (11 COCKET NUMSER (31 LER NUMSER (81 PACE (31 YEAR p:m'tvrtloN i.'it ttOVSNTIAL >r~

NVMttlr NVMttA SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE 0 s 0 0 o 40 088 030 0 0 02oF 5 TEXT //I rrroro tpoco/4 rroo/r/Ooro/HRC Forrrr 3/I/(AY/ (1TI INITIAL CONDITIONS:

The plant was being heated up following a refueling outage, with the unit in Mode 4 (subcritical, 200'F < Tavg < 350'F) at 345'F and 340 PSIG in th' primary, and steam generator pressures at approximately 100 PSIG ~

EVENT DESCRIPTION:

(Refer to Attachment 1)

At approximately 0530 on October 7, 1988, steam generator pressure was observed at the steam supply header of the turbine driven auxiliary feedwater pump (TDAFWP) (EIIS:BA:TRB) downstream of the closed containment isolation

,valves, 1MS-70 and 1MS-72 (EIIS:SB:ISV) (Manufacturer, Anchor Darling, Model Number 94-13956). The operator attempted to vent the line by opening drain valves on the turbine inlet header, but the pressure did not decrease. The TDAFWP trip and throttle valve was then opened to relieve the steam pressure by operating the pump; the turbine speed increased and was not reduced after several minutes. The trip and throttle valve was reclosed to secure the TDAFWP.

These evolutions were repeated during the morning by day shift operators.

Temperature measurements downstream of the isolation valves along with audible indications of steam flow confirmed the isolation valves were experiencing seat leakage. The valves were manually torqued shut in an attempt to properly seat the valves, but this was unsuccessful. At 1420, both isolation valves were declared inoperable due to excessive seat leakage; S'pecification 3.6.3, Containment Isolation Valves, Action d, was applied to require the plant be in cold shutdown (subcritical, Tavg </=200'F) within 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br />.

At 2030, the operators commenced a cooldown of the plant to support repairs on these valves. The reactor coolant system was at '205'F by 0300 on October 8, and the valves were removed and examined by maintenance mechanics. It was evident that the disc for valve 1MS-72 was not properly fitted to the seat; valve 1MS"70 displayed no evidence of seat leakage. During the refueling outage, both of these valves had been repaired for minor seat leakage, and apparently adequate information was not turned 'ver during a shift change regarding the status of fitting the disc to the seat for valve 1MS-72.

At 2318 on October 8, the unit entered Mode 5 in compliance with'he action statement of Specification 3.6.3. Repairs to valve 1MS-72 and reinstallation and testing of both isolation valves were accomplished at 1845 on October 9, and the plant re-entered Mode 4 at 2006.

NIIC FOIIM 34OA *U.S.OPO:198~-834 538/455 (9413)

NRC Forrc 304A U.S. NUCLEAR AEOULATORY COMMISSION

$ 431 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPAOVED OMS NO. 3150-0104 EXPIRES: 8/31/88 FACILITYNAME 111 DOCKET NUMSER 121 LER NUMSEA (51 PACE (3)

SCQVENTIAL RLYICIQN SHEARON HARRIS NUCLEAR POWER PLANT YEAR NVMecR NUMSER UNIT ONE 0 5 0 0 0 4 0 0 8 8 00 03 oF 0 5 TEXT /// more cocce /4 rPI/IIeE vss rckNonel H/IC Fomr 3034'4/ I ITI CAUSE:

The isolation valve was rendered inoperable due to inadequate turnover between shifts during valve 'repairs conducted during the refueling outage. The valve disc for 1MS-72 had not been fitted to the seat, but the oncoming mechanics believed this had been completed. A face-to-face turnover between oncoming and offgoing mechanics did not occur for this work.

ANALYSIS:

Valves 1MS-70 and 1MS-72 are remote manual containment isolation valves per Specification 3.6.3; these valves do not receive any automat'ic isolation signal. Since these valves are not subject to type C leakage testing requirements, inoperability due to excessive leakage is determined by judgment. These valves are required to be operable as the steam supply valves to the TDAFWP per Specification 3.7.1.2.

These valves are normally closed and open automatically to start the TDAFWP on either'. (1) low-low steam generator level in 2/3 steam generators at 38.5X narrow range level or (2) loss of the associated safety train emergency bus.

The isolation function of these valves is assumed to be accomplished by the operator for a steam generator tube rupture event and for a piping break of the steam or feedwater piping of the associated steam generator.

The isolation function of the inoperable valve 1MS-72 could have been accomplished, for the existing plant conditions, using the TDAFWP trip and throttle valve and the TDAFWP steam header drain isolation valves. This would have made the TDAFWP unavailable; however, it is not required operable by Technical Specifications in Mode 4 since reactor heat removal is accomplished by the Residual Heat Removal System (EIIS:BP). When the valves were removed from the line and disassembled, the isolation capability was lost; however, the plant was at 205'F at that time, and so neither a steam generator tube rupture nor a secondary piping failure would have consequences requiring the isolation function of the . valves. The probability of steam generator tube ruptures or secondary piping failures is less likely at the reduced pressures existing, at the time of discovery of the inoperable valve.

It is not considered credible to assume this problem could have gone undetected as the plant continued heat up to normal operating conditions, nor could the inoperable valves have been removed 'for inspection and repairs with any steam pressure existing in the steam generators. Therefore, no credible alternative conditions are required to be evaluated in this report.

There have been no previous similar events'his event is being reported. under 10CFR50.73(a)(2)(i)(A) as a completion of a plant shutdown required by Technical Specifications.

NRC FORM 344A *U.S.GPO.'1988.D824 535/455 (9831

NUCLEAR REGULATORY COMMISSION NRC Form SBBA (943)

LICENSEE EVENT REPORT ILER) TEXT CONTINUATION'.S. APPROVEO OMB NO. 3150&(04 EXPIRES: 8/31/88 FACILITYNAME ul OOCKET NUMBER Il) LER NUMBER (81 PAGE (3) 4fvrSION YEAR .jw SEOVSNTIAL NVM %4 NVM844 SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE o so o o 400 88 3 0 0 04oF 05 TEXT/I/moro 4Pocolo/IV/ref, Pm///Ooro////ICFo/III35549/((TI CORRECTIVE ACT10NS:

1. Valve 1MS-72 was fitted properly to its seat, and both valves 1MS-70 and 1MS-72 were installed and returned to operable status on October 9, 1988.

2. To prevent recurrence, during future outages, adequate written turnover will be provided when the schedule does not permit face-to-face turnovers by shift mechanics for maintenance work in, progress.

NRC SORM 346A *U.S.GPO:1988.0 824 538/455 (94(3I

ATTACHMENT 1 TURBINE- DRI YEN AU><ILIARYFEEDWATER PUMP STEAI"1 SUPPLY II"IS-70-SA FROM STEAMLINE B I

I

.IMS-72-SB FROI"I STEAMLItlE C OUTSIDE CONTAINMENT

~~ II'lSIDE

'ONTAI NI1ENT PI TI DRAIN TO MAIN CONDENSER TRIP 8.

THROTTLE GQYERNOR YALYE STEAM EXHAUST VALYE TO ATMOSPHERE T G TURBINE PUMP TURBINEDRIVEN AUXILIARYFEEDVNTER PUMP DRAIN TO MAIN CONDENSER

Caroiina Power 8 Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 NOV 0 7 1S88 File Number'SHF/10-13510C Letter Number'. H0-880227 (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 88-030-00 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 AJH:tbb Enclosure cc: Mr. W. H. Bradford (NRC SHNPP)

Mr. B. Buckley (NRR)

Mr. M. L. Ernst (NRC - RII)

MEM/HO-8802270/1/Osl