ML18153A252

LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame

ML18153A252
Person / Time
Site:	Surry
Issue date:	04/22/1998
From:	Christian D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18153A250	List: ML18153A249 ML18153A252
References
LER-98-005, LER-98-5, NUDOCS 9804270426
Download: ML18153A252 (4)

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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB NO. 3150-0104 (4-95) EXPIRES 4/30/98 ESilMATED BURDEN PER RESPONSE TO COMPLY WITH THIS YANDA TORY INFORMATION COLLECTION REQUEST 50 0 HRS REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSEE EVENT REPORT (LER) L:CENSING PROCESS AND FED BACK TO INDUSTRY FORWARD SOMMENTS REGARDING BURDEN ESTIMATE TO THE NFORMATIQN AND RECORDS MANAGEMENT BRANCH (T-6r3J\

J S NUCLEAR REGULA TORY COMMISSION WASHINGTON DC (See reverse for required number of digits/characters for each block) 20555-0001 ANO TO THE PAPERWORK REDUCTION PROJECT 3'50,0l04J QFC::ICE OF YANAGEMENT AND BUDGET WASHING TON DC 20503 FACILITY NAME (1 I DOCKET NUMBER 121 PAGE (3)

SURRY POWER STATION, Unit 1 05000 - 280 1 OF 4 II TITLE (41 Fire Watch Inspection Frequency Exceeds One Hour EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) 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 FACILITY NAME DOCUMENT NUMBER 02 12 98 1998 -- 005 -- 01 04 22 98 05000-OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)

MODE(9) N 20.2201(b) 20.2203(a)(2)(v) X 50. 73(a)(2)(i) 50. 73(a)(2)(viii)

POWER 20.2203(a){1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50.73(a)(2)(x)

LEVEL (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 ,n Abstract below 20.2203(a)(2)(iv) 50.36(c){2) 50. 73(a)(2)(vii) or in NRC Form 366A LICENSEE CONTACT FOR THIS LER 121 NAME D. A. Christian, Site Vice President l ~ ; ~ ; ; N ; ; ; : ; ~ ~ ; e ~ea Code)

COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS NA NA NA NA NA SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR I YES .

(If yes, complete EXPECTED SUBMISSION DATE).

IX I NO SUBMISSION DATE 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 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 one hour. 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, 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) was conducted to determine the cause of this event and recommend corrective actions. The cause was lack of attention to detail by the individual involved. This report is being made pursuant to 10CFR50.73(a)(2)(i)(B).

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

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FAC~LITY NAME (1) DOCKET LER NUMBER (6) PAGE (3)

YEAR SEQUENTIAL REVISION Surry Power Station, Unit 1 05000 - 280 NUMBER NUMBER Surry Power Station, Unit 2 05000 - 281 1998 --005-- 01 2 OF4 TEXT (If more space is required, use additional copies of NRG 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.B.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) was conducted to determine the cause of this event. The cause was lack of attention to detail by the individual involved, in that some of the inspections of the affected fire areas were not performed within the required frequency of "at least once per hour." Because the event occurred several months prior to being identified, it was not possible to identify what specifically caused the individual's inattention to detail.

The following contributing cause was also identified:

NRG FORM 366A (4-95)

e 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)

I YEAR SEQUENTIAL REVISION Surry Power Station, Unit 1 05000 - 280 NUMBER NUMBER Surry Power Station, Unit 2 05000 - 281 1998 -- 005 -- 01 3 OF 4 TEXT (If more space is required. use additional copies of NRC Form 366A) (17) 3.0 CAUSE (continued)

As a result of an event that occurred in the latter half of 1996, fire watch training had been revised to emphasize the need to perform the patrols during the required frequency of "at least once per hour," as well as to notify the foreman and the Operations Shift Supervisor if the required frequency was not satisfied. Although the individual involved had received the revised fire watch training, the individual did not realize there was a need to notify anyone when the required fire watch frequency was not satisfied in the June 1997 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.

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. The RCE has been completed and the corrective actions discussed in Section 6.0 have been approved for implementation.

The individual involved was coached on the requirement to perform fire watch patrols within the required time frame, as well as to notify the foreman and the Operations Shift Supervisor if the required fire watch frequency is exceeded.

6.0 ACTIONS TO PREVENT RECURRENCE The fire watch training job performance measurement (JPM) will be revised to require completion of a Fire Watch Tour Sheet. This JPM will emphasize the frequency

.requirements associated with continuous and hourly fire watches. The need to notify the foreman and the Operations Shift Supervisor if the required fire watch frequency is exceeded will also be emphasized.

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.

NRC FORM 366A (4-95)

II

• e 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)

YEAR SEQUENTIAL REVISION Surry Power Station, Unit 1 05000 - 280 NUMBER NUMBER Surry Power Station, Unit 2 05000 - 281 1998 -- 005 -- 01 4 OF 4 TEXT (If more space is required. use additional copies of NRC Form 366A) (17) 8.0 MANUFACTURER/MODEL NUMBER Not applicable.

9.0 ADDITIONAL INFORMATION None.

NRC FORM 366A (4-95)