ML18153A239

LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued

ML18153A239
Person / Time
Site:	Surry
Issue date:	03/13/1998
From:	Christian D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18153A238	List: ML18153A237 ML18153A239
References
LER-98-005, LER-98-5, NUDOCS 9803240344
Download: ML18153A239 (3)

Text

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NRC FQRM 366 (4-95)

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• APPROVED BY 0MB NO. 3160-0104 EXPIRES 4/30/98 .

ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS.

REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSEE EVENT REPORT (LER) LICENSING PROCESS AND FED BACK TO INDUSTRY.

.. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6F33),

U.S. NUCLEAR REGULATO.RY COMMISSION, WASHINGTON, DC (See reverse for required number pf digits/characters for each block) 20555-0001. AND TO THE PAPER\11/0RK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

NAME(1) DOCKET NUMBER (2) PAGE(3)

SURRY POWER STATION ,Unit1 05000-280 .1 OF3 TITLE (4)

Fire Watch Inspection Frequency Exceeds One Hour EVENT DATE (5) I - LER NUMBER (6) ,I REPORT DATE (7) .11 OTHER FACILITIES INVOLVED (8)

SEQUENTIAL REVISION FACILITY NAME DOCUMENT NUMBER MONTH DAY YEAR YEAR MONTH DAY YEAR

• NUMBER NUMBER Surry Power Station, Unit 2 05000-,281 02 12 98 1998 -- 005 -- 00 03 13 98. FACILITY NAME DOCUMENT NUMBER 05000-II .:.-:;-_-TING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)

- E (9) N 20.2201 (b)

• 20.2203(a)(2)(v) 50. 73(a)(2)(i) 50. 73(a)(2)(viii)

X I POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50. 73(a)(2)(X)

L (10) *100% 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) ... 50. 73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) - 50. 73(a)(2)(v) Specify in Abstract below 20.2203(a)(2)(iv) 50.36(c)C2> 50. 73(a)(2)(vii) or in NRC Form 366A NAME LICENSEE CONTACT FOR THIS LER (12)

I TELEPHONE NUMBER (Include Area Code)

D. A Christian, Station Manager (757) 365-2000 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS NA NA NA NA NA I

I SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR I X I YES (If yes, complete EXPECTED SUBMISSION DATE). I I NO SUBMISSION DATE 04 03 98 I ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)  :

On February 12, 1998, during Fire Protection Audit 98-02 being conducted by the Nuclear Oversight Department, a situation *that* occurred on June 6, 1997 was identified where a Technical Specification fire watch exceeded the required inspection frequency. On i

June 6, 1997, with Units 1 and 2 operating at 100% power, a fire detection alarm panel became inoperable. As required by Technical* Specification 3.21.B.1, a fire watch patrol was established within onehour. TS 3.21.B.1 also requires a fire watch inspection frequency of the affected fire areas "at least once per hour." The required fire area inspections were performed, i however the at-least-once-per-hour frequency was exceeded by one to seven minutes for some fire area patrols. The tardy fire watch patrols were performed by one individual. A fire did not occur, and there were no safety implications or consequences as a result of this event.

A Category 2 Root Cause Evaluation (RCE) is being conducted to determine the cause of this event and recommend corrective actions. This report is being made pursuant to 10CFR50. 73(a)(2)(i)(B) and will be supplemented upon completion of the RCE.

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9803240344 980313 ~;

PDR ADOCK 05000280 S. PDR ,;,.

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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

TEXT.CONTINUATION FACILITY NAME (1) DOCKET LER NUMBER (6) PAGE (3)

Surry Power Station, Unit 1 05000 - 280 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER Surry Power Station, Unit 2 05000 - 281 1998 -- 005 -- 00 2 OF3

. TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

1.0 DESCRIPTION

OF THE EVENT On February 12, 1998, during Fire Protection Audit 98-02 being conducted by the Nuclear Oversight Department, .a situation that occurred on June 6, 1997 was identified where a .

Technical Specification (TS) fire watch exceeded the required inspection frequency.

On June 6, 1997, with Units 1 and 2 operating at 100% power, a fire detection alarm panel was declared inoperable at 0059 hours6.828704e-4 days <br />0.0164 hours <br />9.755291e-5 weeks <br />2.24495e-5 months <br />. As required by TS 3.21.8.1, a fire watch patrol was established within one hour and the TS action statement was exited at 0119 hours0.00138 days <br />0.0331 hours <br />1.967593e-4 weeks <br />4.52795e-5 months <br />.

TS 3.21.B.1 also requires a fire watch inspection frequency of the affected fire areas "at least once per hour." Based on log entries, the required fire area inspections were performed, however the at-least-once-per-hour frequency was exceeded by one to seven minutes for some fire area patrols. The tardy fire watch patrols were performed by one individual.

This report is being made pursuant to 10CFR50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications*. *** *** ** **

2.0 SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS The required fire watches were initiated within the TS-required time period of one hour.

The affected fire areas requiring inspection were inspected, and the required number of inspections were performed. The personnel performing the fire watches were fire watch qualified to detect, report, and extinguish fires. Fire suppression equipment remained operable throughout the time frame.

If a fire had occurred, it would have been detected, reported, and extinguished. However, a fire did not occur. Therefore, this event resulted in no significant safety consequences or implications, and the health and safety of the public were not affected.

3.0 CAUSE A Category 2 Root Cause Evaluation (RCE) is being conducted to determine the cause of this event. Upon completion of the RCE, a supplement to this Licensee Event Report (LER) will be submitted. The LER supplement will include discussion of the cause of this event.

4.0 IMMEDIATE CORRECTIVE ACTION(S)

When Nuclear Oversight discovered that the required fire watch inspection frequency of "at least once per hour" had been exceeded, a station deviation was issued.

NRC FORM 366A (4-95)

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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)

. ,., i

,, LICENSEE EVENT REPORT (LER)

. ' TEXTCONTINUATION FACILITY NAME (1) DOCKET LER NUMBER (6) PAGE (3)

Surry Power Station, Unit 1 05000 - 280 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER i

Surry Power Station, Unit 2 05000 - 281 1998 -- 005 -- 00 3 OF3

. TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

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5.0 ADDITIONAL CORRECTIVE ACTIONS As a result of the issuance of the station deviation, the Category 2 RCE was initiated to

. determine the cause of the event and to recommend corrective actions .

6.0 ACTIONS TO PREVENT RECURRENCE Following completion of the RCE, a supplement to this Licensee Event Report (LER) will be submitted. The LER supplement will include discussion of the corrective actions to prevent recurrence of a similar event.

7.0 SIMILAR EVENTS LER 50-280, 50-281/96-007-00, titled "Fire Watch Patrol Inspection Frequency Exceeds One Hour," and-dated September, 19,.1996. _

• 8.0 MANUFACTURER/MODEL NUMBER Not applicable.

9.0 ADDITIONAL INFORMATION None.

NRC FORM 366A (4-95)