ML18005A562

LER 88-017-00:on 880726,Tech Spec 3.7.7 Violated.Caused by Inoperability of Emergency Svc Water Pump a & Train a Essential Svcs Chilled Water Sys.Bay Inspected Under Water & Traveling Screen Operation W/Bay drained.W/880825 Ltr

ML18005A562
Person / Time
Site:	Harris
Issue date:	08/25/1988
From:	Jerrica Johnson, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-880166-(O), LER-88-017-01, LER-88-17-1, NUDOCS 8808300247
Download: ML18005A562 (5)

Text

ACCESSION NBR:8808300247 DOC.DATE: 88/08/25 NOTARIZED: NO . DOCKET ¹ FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION JOHNSON,J.R. Carolina Power & Light Co.

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

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 88-017-00:on 880726,Tech Spec violation due to failure of emer g ency svc water traveling screens.

W/8 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73 Licensee Event Report (LER), Inci ent Rpt, etc.

NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 BUCKLEY,B 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 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 NR S/SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 IL 02 1 1 RES TELFORD,J 1 1 SIR DEPY 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EG&G WILLIAMSgS 4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRISgJ 1 1 NSIC MAYS,G 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 46 ENCL 45

{ee NRC For I 386 U.S. NUCLEAR REGULATORY COMMISSION I9 413)

APPROVED OMB NO. 31500)04 EXPIRES: 8/31/88 LICENSEE EVENT REPORT (LER)

FACII.ITY NAME (1) DOCKET NUMBER (2) PAGE 3 Shearon Harris Nuclear Power Plant Unit 1 0 5 0 0 0 400 1 OFO 3 Technical Specification Violation due to failure of Emergency Service Water Traveling Screens EVENT DA'TE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

YEAR SEQUENTIAL REVISION MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER(s)

MONTH DAY YEAR NUMBER NUMBER 0 5 0 0 0 0 7 2 6 8 8 8 8 0 1 7 0 0 0 825 8 8 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CFR ('I: (Check one or morr of the foi/osyinp) (11)

OPERATING MODE (9)

I 20A02(h) 20.405(c) 60,73(s) (2) (Iv) 73.71(h)

POWER 20AOS( ~ l(ll(ll 50.38 (c I (I) 60,73(s)(2)(v) ill(B) 73.71(cl LEVEL 20.405( ~ I ( I ) I 4) 50M(c)(2) 60.73(s)(2)(v4) OTHER (Specify In Atra{rect priory snd In Teat, Ni(C Form 20.405( ~ l(1 )(BII 60.73(s) (2) (I) 60.73(s) (2)(vBI)(Al 366AI

.: 'gP'A'. ':, 20.40S(s l(1) (Iv) 60.73(e ) (2) (4) 50.73(s) (2)(el Ct .

co rrrpr{.%OAwiMAM'A'Oro 20.406 (a) ll) ( vl 50.73(s) (2HBII 50.73( ~ ) (2) (x)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER Joseph R. Johnson AREA CODE Senior Specialist Regulatory Compliance 9 193 62- 20 83 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

)oc

'oo MANUFAC. REPORTABLE MANUFAC. EPORTABLE CAUSE SYSTEM COMPONENT TO NPRDS CAUSE SYSTEM COMPONENT TURER TVRER TO NPRDS r{ C n ~ v X S CN R23 3 Y REPORT EXPECTED (14)

II'UPPLEMENTAL MONTH OAY YEAR EXPECTE'D SUBMISSION DATE (16)

YES IIIyn, compfetr EXPECTED SVBgtISSION DA TEI NO ABSTRACT ILimit to 1400 specet, I r., epprosimeteiy fiftrrn sinpirrpece typrvrrittrn linn) (18)

ABSTRACT:

On July 26, 1988, the plant was operating in Mode 1 at 83X power. At 2010, the Auxiliary Reservoir Bay 8 Traveling Screen for the "A" Emergency Service Water (ESW) Pump failed which caused the "A" ESW Pump to be inoperable. This loss of ESW resulted in the "A" train Essential Services Chilled Water System (ESCWS) to be inoperable. Due to the Technical Specification definition of "Operable", the "A" train equipment, including the Reactor Auxiliary Building (RAB) Emergency Exhaust Fan, E-6 A-SA, were considered to be inoperable due to the inoperability of the room cooling units. The E-6 B-SB RAB Emergency Exhaust Fan had been inoperable since July 22, 1988, due to a flow control problem. Since both RAB Emergency Exhaust Fans were inoperable, the plant was no longer in compliance with Technical Specification 3.7.7, and entered Technical specification 3.0.3 at 2010.

The "A" ESW Pump suction was realigned to the Main Reservoir and was declared operable at 2044, and Technical Specification 3.0.3 no longer applied.

Corrective actions included an underwater inspection of the affected bay and inspection of the Traveling Screen operation with the" bay drained. The cause of the Traveling Screen failure was due to loose bolts on the screen guides, which caught and jammed the screen, resulting in a sheared pin on the motor drive sprocket. The shear pin was replaced and the loose bolts were Q tightened.

8808300247 880825 PDR ADOCK 05000400 S PNU NRC Form 388 (9 831

~ .

NRC Form 366A U.S, NUCLEAR REGULATORY COMMISSION (943)

LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVED OMS NO. 3)60&)04 EXPIRES: 8/3)/88 FACILITY NAME () I DOCKET NUMBER Il) LER NUMSER (6) PAGE IS)

SEOVENTIAL REVISION Shearon Harris Nuclear Power Plant NVMSER NVM SR Unit 1 TEXT ///morI N>>co /I Err/rkorS IIIo DESCRIPTION:

~ /VRC Form 3656'll I)TI o s o o o 4 088 017 0 0 0 2 OF 0 3 On July 26, 1988, the plant was operating in Mode 1 at 83X power. The "A" train Emergency Service Water (ESW) pump was aligned to the Auxiliary Reservoir and was running to supply the "A" ESW header (EIIS:BI). At 2010, a shear pin on the Bay 8 Traveling Screen motor drive sprocket sheared, resulting in the failure of the Traveling Screen. As a result of this equipment failure, the "A" ESW Pump was declared inoperable. With an inoperable "A" train ESW pump, the "A" train Essential Services Chilled Water System (ESCWS) was declared inoperable. Consequently, "A" train equipment dependent on the "A" ESCWS for room cooling was al'so declared inoperable.

This caused the Reactor Auxiliary Building (RAB) Emergency Exhaust Fan (E"6 A-SA) (EIIS:VL) to be declared inoperable. The other RAB Emergency Exhaust Fan E-6 B-SB had been inoperable since July 22, 1988, due to a flow control problem. Since both RAB Emergency Exhaust Fans were inoperable, the plant was no longer in compliance with Technical Specification 3.7.7, and.. entered Technical Specification 3.0.3 at 2010.

The "A" ESW Pump suction was manually realigned to the Main Reservoir and was declared operable at 2044, and Technical Specification 3.0.3 no longer applied.

CAUSE Maintenance personnel . developed a comprehensive plan to determine the root cause of the failure, Bay 8 was visually inspected by divers on July 28, 1988; no problems were found. On August 4, 1988, Bay 8 was drained and inspected. The shear pin was replaced in the Traveling Screen motor drive sprocket and maintenance personnel observed the screen in operation. The cause of the failure was attributed to two loose bolts on the screen guides.

The bolts had backed out far enough to catch the edge of the screen as it rolled around, causing the mechanism to jam, resulting in a sheared pin on drive sprocket. The Traveling Screen was manufactured by Rexnord the'otor Company, Model-Envirex. The loose bolts were tightened to prevent recurrence of the problem.

The E-6 B-SB RAB Emergency Exhaust Fan had been declared inoperable on July 22, 1988, when it failed to pass an operational surveillance test, OST-1052 RAB Emergency Exhaust System Operability. . The unit did not provide sufficient flow and the low flow was attributed to the setpoint for the flow controller. The setpoint had been previously set at the lower tolerance end of the required flow range (6800 CFM plus or minus lOX). This was done to prevent the fan from exceeding the high flow limit in case of a malfunction.

The calibration procedure was changed to require setting the setpoint at 6800 CFM, and the controller card was calibrated to this limit. The E-6 B-SB fan was subsequently retested and declared operable at 2310 on July 26, 1988.

NRC FORM 366A RUSOPO:1988-0.826 638/4SS

$ 83)

NRC Form 3SSA U.S. NUCLEAR REOULATORY COMMISSION (843)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3(50M(04 EXPIRES: 8/3l/88 FACILITY NAME (I l DOCKET NUMBER lll LER NUMBER (5) PACE (3)

Shearon Harris Nuclear Fower Fiant YEAR )PS SEOUENTIAL ER

>fr;.'UM R(VISION

& NUM ER Unit 1 0 5 0 0 0 4 0 0 8 8 017 00 03 OF 0 3 TExT ///moro spoco IS /I/I/iorL ooo o//ooo'one/HRc Forrrr 35(/AS/ I(TI ANALYSES OF EVENT:

This event is being reported in accordance with 10CFR50.73(a)(2)(i)(B) as a violation of Technical Specifications.

There were no automatic safety system responses 'resulting from this event.

The plant continued to operate at 83K power throughout the event.

The failure of the Traveling Screen and resultant loss of "A" train ESW had no direct impact on plant safety since the "B" ESW train was available. The traveling screens remove debris at the intake so their failure would cause the corresponding ESW pump to fail only if excessive debris were present. To date, this has not been a problem at SHNPP.

The E-6 B-SB Emergency Exhaust Fan had been declared inoperable due to low flow prior to this event, however, the fan could have still been used in an emergency situation if needed. At the time of the traveling screen failure, the flow controller had already been re-calibrated, but the paperwork had not been completed at that time to allow the fan to be declared operable. The fan was declared operable again" at 2310, only 3 hours 'after the event. Although both RAB Emergency Exhaust Fans were declared inoperable, both were fully functional and able to perform their intended function.

The plant has experienced previous problems with the Bay 8 Traveling Screen on two occasions. The motor drive sprocket shear pin sheared on JunE 29, 1988, and again on July 7, 1988. Neither of these events caused a violation of Technical Specifications and were not reportable events. In each case the shear pin was replaced, and the screen tested satisfactorily. At that time, Maintenance personnel were unable to determine the reason for the problem.

Due to this third failure, a more extensive investigation, as described above, was conducted to determine the root cause of the failures.

CORRECTIVE ACTIONS

1. The Bay 8 Traveling Screen was inspected. The motor drive sprocket shear pin was replaced and the loose bolts on the screen guides were tightened to prevent recurrence of the problem.

2. The flow controller card for the E-6 B-SB RAB Emergency Exhaust Fan was calibrated to 6800 CFM, and the fan was returned to service at 2310 on July 26, 1988.

NRC FORM 3OSA o U.S GPO;(888 0-824 538/855 8383 I

CARE Carolina Power & Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 AUG 25 1988 File Number: SHF/10-13510C Letter Number'. HO-880166 (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 88-017-00 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 RAW:tbb Enclosure cc: Dr. J. Nelson Grace (NRC RII)

Mr. B. Buckley (NRR)

Mr. G. Maxwell (NRC SHNPP)

MEM/LER-88-017/Osl