05000280/LER-1998-005, :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:
|
| References | |
| LER-98-005, LER-98-5, NUDOCS 9804270426 | |
| Download: ML18153A252 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2801998005R00 - NRC Website | |
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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 LICENSEE EVENT REPORT (LER)
REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE L:CENSING PROCESS AND FED BACK TO INDUSTRY FORWARD SOMMENTS REGARDING BURDEN ESTIMATE TO THE NFORMATIQN AND RECORDS MANAGEMENT BRANCH (T-6r3J\\
(See reverse for required number of digits/characters for each block)
- J S NUCLEAR REGULA TORY COMMISSION WASHINGTON DC 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)
MONTH DAY YEAR YEAR SEQUENTIAL REVISION FACILITY NAME DOCUMENT NUMBER.
MONTH DAY YEAR Surry Power Station, Unit 2 05000-281 NUMBER NUMBER 02 12 98 1998
-- 005 --
01 04 22 98 FACILITY NAME DOCUMENT NUMBER 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 l ~;~;;N;;;:;~~;e ~ea Code)
D. A. Christian, Site Vice President 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 IX I NO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE).
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 1 OCFR50.73(a)(2)(i)(B).
,. (4-95)
FAC~LITY NAME (1)
Surry Power Station, Unit 1 Surry Power Station, Unit 2 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET 05000 - 280 05000 - 281 TEXT (If more space is required, use additional copies of NRG Form 366A) (17) 1.0 DESCRIPTION OF THE EVENT e
U.S. NUCLEAR REGULATORY COMMISSION LER NUMBER (6)
PAGE (3)
YEAR SEQUENTIAL REVISION NUMBER NUMBER 1998
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01 2 OF4
- 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:
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FACILITY NAME (1)
Surry Power Station, Unit 1 Surry Power Station, Unit 2 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET I
05000 - 280 05000 - 281 TEXT (If more space is required. use additional copies of NRC Form 366A) (17) e U.S. NUCLEAR REGULATORY COMMISSION LER NUMBER (6)
PAGE (3)
YEAR SEQUENTIAL REVISION NUMBER NUMBER 1998
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01 3
OF 4 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.
II
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FACILITY NAME (1)
Surry Power Station, Unit 1 Surry Power Station, Unit 2 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET 05000 - 280 05000 - 281 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. e U.S. NUCLEAR REGULATORY COMMISSION LER NUMBER (6)
PAGE (3)
YEAR SEQUENTIAL REVISION NUMBER NUMBER 1998
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01 4
OF 4