ML18153B903

LER 89-035-00:on 890813,one of Auxiliary Ventilation Sys Filtered Exhaust Fans Automatically Restarted After Being Stopped.Caused by Improper Landing of Previously Lifted Lead on Pressure Switch.Personnel reinstructed.W/890908 Ltr

ML18153B903
Person / Time
Site:	Surry
Issue date:	09/08/1989
From:	Kansler M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-037, LER-89-035, NUDOCS 8910020285
Download: ML18153B903 (4)

Text

..I' e VIRGINIA ELECTRIC ANO POWER COMPANY Surrv P-r Station P. 0. Box 31!i Surrv, Virginie 23883 September 8, 1989 U.S. Nuclear Regulatory Cononission Serial Ho.: 89-037 Document Control Desk Docket Nos.: 50-280 Washingt.on, D. C. 20555 50-281 License Nos: DPR-32 DPR-37 Gentlemen:

Pursuant to Surry Power Station 'l'echnical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Units 1 and 2.

REPORT NUMBER 89:....035-oo This report has been reviewed by the Station Nuclear Safety and Operating Cononittee and will be reviewed by Safety Evaluation and Control.

Very truly yours, Enclosure cc: Regional Administrator Suite.2900 101 Marietta Street, NW Atlanta, Georgia 30323

POW 28-06-01 e ~

NRC FORM 366 (6-89) . U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-01;4 EXPIRES: 4/30/92

- STIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION; WASHINGTON, DC 20555, ANO TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) I PAG ("

Surry Power Station, Units 1 and 2 I o.1s101010121 81 0 1 loF O 13 TITLE (4)

Unplanned ESF Actuation, Automatic Start of an Auxiliary Ventilation System Fan Due to an Incorrectly Landed Lead EVENT DATE (5) . LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR ,/J se~i~~~~AL t< ~~t~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERIS) o1 8 1 I 3 8 9 8 I9 - o I 3 I s - oI o o19 o_ 18 8 I9 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R~QUIREMENT& OF 10 CFR §: (Chttek on* or more of rhs following/ (11) .

IN MODE (8) IX 73.71(b)

I *10 20.4021b1 20.4061c) 60.73(1)(2)1iv)

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60.38(c)(1) 60.7311ll2lM 73.711c)

POWER 20.406(1)(1 )Ii) 1-- .___

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.............................+.....-1.......+---l 20.405(1)(1)(11) 1--

50.38lcll2) 50,73(1)12)1i) 60.73C1)(2)(vii) 50.73(1H2llviil)IA) 1--

OTHER (Specify in Abstract b*low ind in Text, NRC.Form 366A/

IIJlllifiilllltil!!fii= :::::::::: --- 50.73(1)(2)(ii) 50.73(1)(2)(iii)

LICENSEE CONTACT FOR THIS LER (12) l50.73(1)(2)(vili)(B) 60.73(1)12)(x)

NAME TELEPHONE NUMBER M. R. Kansler, Station Manager AREA CODE COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUFAC-CAUSE SYSTEM COMPONE.NT MANUFAC*

TURER 6 R~ 0~~:g~E 1

i!i i!i!ili!ili!Jfj!Jii!J!iil!i!iii!i!i!:1i!i!i!i!i!:

CAUSE SYSTEM COMPONENT TURER I I I I I *1 I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED i14) MONTH DAY YEAR EXPECTED

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SUBMISSION I ~ES /If y**. complot* EXPECTED SUBMISSION DATE/ NO DATE 115)

I I I ABSTRACT (Limit to 1400 spaces, i.tJ., 1pproxim1ttJly fifteen single-space typewritten lintn} (16)

On August 13, 1989 at 1532 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.82926e-4 months <br />, with Unit 1 at 100% power and Unit 2 in cold shutdown, one of the auxiliary ventilation system filtered exhaust fans automatically restarted after it had been stopped. The fan is designed to automatically start on a safety injection (SI) signal.

No actual SI signal was present at the time. A four hour non-emergency report was made to the Nuclear Regulatory Commission per 10CFR50.72 of an unplanned engineered safety features component actuation. The cause of the event was the improper landing of a previously lifted lead on a pressure switch. The individuals involved in the event were reinstructed. A root cause evaluation was performed and appropriate actions will be implemented.

NRC Form 366 (6-89)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-891 * ' APPROVED 0MB NO. 3160-0104

• EXPIRES: 4/30/92

.MATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EvfT REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-5301, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555;AND TO_

THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (61 PAGE (3)

Surry Power Station, Units 1 and 2 0 'l.5 I O *, 0 I O I 2 18 I O 8 I 9 - o, 315 - 0 I O O I 2 OF O 13

• TEXT (If more -ce ia ,-qui/Yd, u:. *ddltiona/ NRC Form 31511,1 ;al (17) 1.0 Description of the Event On August 13, 1989 at 1532 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.82926e-4 months <br />, with Unit 1 at 100%

power and Unit 2 at cold shutdown, one of the auxiliary ventilation system filtered exhaust fans (l-VS-F-58B) (EIIS-FAN) automatically restarted after it had bee*n secured. The fan was being operated to

.support an engineering evaluation of the ventilation

.system pressure switches. In accordance with the procedure, the operator placed the fan control switch to the off position and the switch spring returned to the auto position as designed. The fan immediately restarted when the switch returned to* the auto position. Since the fan is designed to automatically start on a safety* -injection (SI) (EIIS-JE) signal, this event is being reported as an unplanned engineered safety features (ESF) actuation. No actual SI signal was present at the time. A four hour non-emergency report was made to the Nuclear Regulatory Commission per 10CFRS0.72.

2.0 Safety Consequences and Implications The filte.red exhaust fans are designed to start and take suction from various potentially contaminated plant locations and discharge through iodine and particulate removal filters upon the initiation of a SI signal. The capability of the fan to perform this function was not affected by the event. Therefore, the health and safety of the public were not affected.

3.0 Cause The cause of the event was the improper landing of a previously lifted lead on a pressure switch associated with the auxiliary ventilation system. A technician incorrectly landed the lead on a terminal adjacent to the intended terminal during activities-supporting an engineering evaluation in progress at the time. The error was not identified during subsequent verifications of the step. With the incorrect lead configuration, an automatic start signal for the fan was *constantly present. Consequently, when the fan was stopped and placed in the automatic mode, it automatically restarted.

NRC Form 366A (6-891

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION ~

(6-89) * .. * . _ APPROVED 0MB NO. 3150-0104

• EXPIRES: 4/30/92 STIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT * (LER) INFORMATION COLLECTION REQUEST: 60.0 HRS. FORWARD TEXT CONTINUATION COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

Surry Power Station, Units 1 and 2 0 I5 I O I O I O I 2 j 8 . I O 8 I 9 - 01 31 5 '- 0 I O OI 3 OF O 13 TEXT (If more apace i8 ,wqul/Wd, u,e llddltional NRC Fom, 366A '*J (171 4.0 Immediate Corrective Action(s)

The pressure switch terminals were examined, the error discovered, and the lead was landed on the correct terminal.

5.0 Additional Corrective Action(s)

A root cause investigation was initiated.

6.0 Action(s) Taken to Prevent Recurrence The individuals involved in the event were reinstructed on the importance of self-checking and proper verification.

In addition, a root cause evaluation has* been performed. The recommendations of the root cause evaluation will be reviewed by the Station Nuclear Safety and Operating Committee and appropriate actions will be implemented.

7.0 Similar Events None.

8.0 Manufacturer/Model Number(s)

N/A NRC Form 366A (6-89)