ML18152B141

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LER 88-014-00:on 880421,smoke Detectors Found Inoperable & Fire Watch Not Timely Posted.Caused by Administrative Oversight.Smoke Detectors a & B Repaired & Returned to Svc. Fire Watch Assigned to containment.W/880511 Ltr
ML18152B141
Person / Time
Site: Surry Dominion icon.png
Issue date: 05/11/1988
From: Benson D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-018, 88-18, LER-88-014-01, LER-88-14-1, NUDOCS 8805190097
Download: ML18152B141 (4)
v • d • e


Text

POW 28-06-01 NRC Form 386 U.S. NUCLEAR REGULATORY COMMISSION (9-831 APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31/88 LICENSEE EVENT REPORT (LER)

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. I FACILITY NAME (11 DOCKET NUMBER (21 I PAGE (31 TITLE (41 Surry Power Station, Unit 1 O 15 I O IO I O 12 I 8 I O 1 IOF OI 3 Failure To Comply With Technical Specification Due To Administrative Oversiqht EVENT DATE (5) LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED 18)

MONTH DAY YEAR YEAR t:t sEz~~~~~AL tr~~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI o 14 211 8 8 8\ 8 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more of the folloV(ing/ 111)

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20.4061*111 )(iii) 60.73(1) l2llil 60.7311l 12llviiil IA) 366A/

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- 50.7311l12llxl LICENSEE CONTACT FOR THIS LER 112)

NAME TELEPHONE NUMBER AREA CODE D. L. Benson, Station Manager 810 14 3151 71-1311 1814 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113)

MANUFAC- MANUFAC-CAUSE SYSTEM COMPONENT TURER TURER X IIC PILI I Rl21910 N I I I I I I I I I I I I I I I I I I I I 1 SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED I YES /If yes, complete EXPECTED SUBMISS/DN.DATE/

ABSTRACT (Limit to 1400 speces, i.e., opproximotely fifteen singte-spoc6 typewritten lines/ (181 rxi NO SUBMISSION DATE 1151 I I I On April 21, 1988 at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, with Unit 1 in refueling shutdown, during the performance of a periodic test, the three containment smoke detectors {EIIS-IC} located in the air recirculation duct work were determined to be inoperable.

Technical Specification 3.21.B.1 requires that a minimum of one of these detectors be operable or a fire patrol watch inspect the area hourly. A specific fire watch was not posted until 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br /> on April 25, 1988.

  • The 'A' and 'B' smoke detectors failed due to a loose connection at their remote monitoring panel {EIIS-PL}. The cause of the failure of the 'C' smoke detector has not yet been determined.

The failure to post a timely fire watch was due to an administrative oversight. The 1 A' and 'B' smoke detectors were repaired and returned to service at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> on April 26, 1988.

The 'C' smoke detector will be repaired prior to restart from the current refueling outage.

A shift order has been issued for all Licensed Operators to review the requirements of T. s. 3.21.

8805190097 880511 PDR ADOCK 05000280 S DCD NRC Form 386 19-83)

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NRC Farm 3HA (9-831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION e

POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150--0104 EXPIRES: 8/31/88 FACILITY NAME (11 DOCKET NUMBER (21 LER NUMBER (61 PAGE (3)

Surry Power Station, Unit 1 TEXT (/f mot9- Is,.,,,_, - .<<I-NRC Form 31111A'*I !17) 1.0 Description of the Event On April 21, 1988 at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, with Unit 1 in refueling shutdown, during the performance of a periodic test, the three containment smoke detectors

{EIIS-IC} located in the air recirculation duct work were determined to be inoperable. Technical Specification 3.21.B.1 requires that a minimum of one of these detectors be operable or a fire patrol watch inspect the area hourly. A specific fire watch was not posted until 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br /> on April 25, 1988.

2.0 Safety Consequences and Implications The smoke detectors located in the containment air recirculation duct work are designed to detect a fire in containment. Throughout the event, the containment was occupied by numerous personnel including a Senior Reactor Operator functioning as the Containment Coordinator. All Station personnel are trained in proper methods for reporting a fire.

Because the containment was continually occupied by trained personnel during the event, it is reasonable to assume that any fire in containment would have been promptly detected and reported. Therefore, the health and safety of the public were not affected.

3.0 Cause The 'A' and 'B' smoke detectors failed due to a loose connection at their remote monitoring panel

{EIIS-PL}. The cause of the failure of the 'C' smoke detector has not yet been determined. The failure to post a timely fire watch was due to an administrative oversight.

4.0 Immediate Corrective Action(s)

At 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br /> on April 25, 1988, a fire watch was assigned to the Unit 1 containment.

5.0 Additional Corrective Action(s)

The 'A' and 'B' smoke detectors were repaired and returned to service at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> on April 26, 1988.

The 'C' smoke detector will be repaired prior to restart from the current refueling outage.

NRC FORM 366A (9-831

  • U.S.GPO: 1988-0-824*538/455

POW 28-06-01 e e U.S. NUCLEAR REGULATORY COMMISSION NRC Form 3HA 19-831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED 0MB NO. 3150-0104 EXPIRES: B/31 /BB FACILITY NAME 111 DOCKET NUMBER 121 LER lliUMBER 161 PAGE 131 Surry Power Station, Unit 1 0 15 I O I O I o I 2 I 8 IO 8I 8 - OI 1I ll - o I n nh OF n I~

TEXT (If,_. -  ;, ,.,,,..,,, ,,_ _ltiaMI NRC Fonn .il!IIA'1J 1171 6.0 Action(s) Taken to Prevent Recurrence A shift order has been issued for all Licensed Operators to review the requirements of T. s. 3.21.

7.0 Similar Events None_.

8.0 Manufacturer/Model Number Remote Monitoring Panel: Robertshaw Integrated Systems Division/FMS-1000.

NRC FOAM 3S6A 19-831

  • U.S.GPO: 1986*0*624-538/455

e e VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P. 0. Box 311!i Surry, Virginia 23883 May 11, 1988 U.S. Nuclear Regulatory Commission Serial No.: 88-018 Document Control Desk Docket No.: 50-280 016 Phillips Building Licensee No.: DPR-32 Washington, D.C. 20555 Gentlemen:

Pursuant *to Surry Power Station Technical Specifications, Virginia Electric and Power Company_hereby submits the following Licensee Event Report for Surry Unit 1

  • REPORT NUMBER 88-014-00 This report bas been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control.

Very truly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323

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