ML18153C301

LER 90-007-00:on 900628,determined That Fire Protection Surveillance Procedure Verifying Operability of Fire Dampers Not Completed within Required Grace Period,Per Tech Specs. Caused by Administrative oversight.W/900727 Ltr

ML18153C301
Person / Time
Site:	Surry
Issue date:	07/27/1990
From:	Kansler M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-469, LER-90-007-01, LER-90-7-1, NUDOCS 9008010118
Download: ML18153C301 (5)

Text

..

-\

Virginia Electric* and Power Company Surry Power Station P. 0. Box 315

. Surry, Virginia 23883 July 27, 1990 U. S. Nuclear Regulatory Commission Serial No.: 90-469 Document Control Desk Docket No.: 50-280 Washington, D. C. 20555 License No.: DPR-32 Gentlemen:

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

REPORT NUMBER 90-007-00 This report has been reviewed by the Station Nuclear Safety and Operating

• committee and will be reviewed by Corporate Nuclear Safety.

Enclosure cc: Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323

NRC F°'"' Jae f9.SJ, POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMI ND. J1&1M11CM LICENSEE EVENT REPORT (LERI EXPIRE&: 1/31/*

FACILITY NAME 111 DOCKET NUMHR 121 PAGE 131 TITLE ,,

Surry Power Station, Unit 1 !o 1s Io 10 Io 1218 IO 1 ioF O 14 Fire Protection Dampers Surveillance Procedure Not Performed Within Technical Specification Required Interval Due to Administrative Oversight EVENT DATE 151 LER NUMBER 16i REPORT DATE 171 OTHER FACILITIES INVOLVED Ill MONTH DAY YEAR FACILITY NAMES DOCKET NUMIIERISI THIS REPORT IS SUBMITTED PURSUAa.lT TO THE REQUIREMENTS _OF 10 CFR -* ,c,,,_.. 011, e* """0't o* r11a *0,10-,,,ngl f111 OPERAT1,;c; N

MOOE Iii, 20.402101 20.'ll!ilcl 50.731111211 .. 1 ......._ 73.711bl I o, - 20.40511111 Iii!

IO.Jllcl111 I0.7Jlall21M ,___ 7J.711cl POWER LEVEL 1101 . 9 18 20.40511ll1Hiil IIO.Jllcll21 II0.7Jlall211ril ,.._ OTHER (Sp<<ify in Abnnct l>>low end in Te*t. NRC Form 20.40511ll11Cilll II0.7:t111121111 I0.7Jlall21i.tllllAI 3(S6A)

Lx.

20.-lall1111YI 20.-lall11M II0.731all211UI I0.7Jlall2111111 LICENSEE CONTACT FOR THIS LER 1121

- I0.7Jlall211wtiillll I0.7Jlall211xl NAME TELEPHONE NUMBER AREA CODE M. R. Kansler, Station 1-!anager 81 0 14 3 I 5 17 I - I 31 118 14 COMPLETE ONE LINE FOR EACH ~NENT FAILURE DESCRIIED IN THIS REPOIIT 1131

. -:-:*.*=*,.,://::,:;:=:::::;:::::::::::::::::

CAUSE SYSTEM COMPONENT MANUFAC-CAUSE SYSTEM . COMPOl'IENT MANUFAC* Fl EPORT All LE :..':\::/:*,::\:':\:;:::***::u::rt TURER TURER TO NPRCS :*:-:-:"//:\':_::,:.

I I I I I I I I I I I I I I I I I I I I I I l I I l I I

.,,,.LEMENTAL RDOIIT IXJIICTID IHI MONTH DAY YEAR rx, IXl'ECTED IUIMISIION

! Yl!I (H l"W, ~ EXf'ECTED SU.IA/$$/ON DATE/ NO DATE 11111 I I I On June 28, 1990 at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />, with Unit 1 at 98% reactor power and Unit 2 at 100% reactor power, it was determined that a fire protect10n surveillance procedure that verifies operability of Unit 1 and Unit 2 fire dampers had not been completed within the required grace. period allowed by Technical Specifications (TS). The dampers are considered fire barrier penetration seals as identified in TS.- The dampers were immediately declared inoperable and fire watches were posted within one hour as required by TS. The surveillance procedure was completed* satisfactorily at 1320

• hours on June 28, 1990, and the fire watches

• were secured. The cause of this event was administrative oversight by the fire protection group.

Administrative changes have been initiated . to. enhance the methods used to inform

• and remind personnel responsible for PTs of the scheduled due dates.

NIIC,__ . .

19-13 t

U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS*

LICENSEE EVENT REPORT (LER) INFORMATION CO_LLECTION REQUEST: 50.0 HRS. _FQRWARO COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISS-ION, WASHINGTON, DC 20555, AND TO 1"HE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

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

YEAR  :::::::::;: SEQUENTIAL ::::::::::: REVISION

NUMBER  :::::::::: NUMBER Surry Power Station, Unit 1 o 1s Io Io Io 12 Is 10 9j o - o 10 I 7 - 01 o 012 OF o I4 TEXT /ff mom space is rr,quintd, use additional NRC Form 366A's/ (171

1.0 DESCRIPTION

OF THE EVENT On June 28, 1990 at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />, with Unit 1 at 98% reactor power and Unit 2 -at 100% reactor power, it was determined that a fire protection (EIIS-KQ) surveillance procedure had not been completed within its required grace period. -The procedure -verifies operability of fire dampers m the Unit 1 and Unit 2 emergency switchgear rooms, Unit 1, and Unit -2 cable spreading rooms and the Unit 2 "B" battery -room. The dampers

_(EIIS-BDMP) are considered fire barrier penetration seals a:s identified m Technical Specification 3.21.A.9. The dampers were immediately declared inoperable and fire watches were posted within one hour as required by Technical Specifications.

Technical Specification Section 4.18.G requires that fire barrier penetrations be verified functional once per 18 months with a +

25% grace period. The allowable time frame for performance of the surveillance test was July 2, 1989 through March 31, 1990 with a scheduled date of November 15, 1989. The test was completed satisfactorily at 1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br /> on June 28, 1990 and the fire watches were secured.

2.0 SAFETY CONSEQUENCES AND IMPLICATIONS The fire protection dampers are designed to provide three-hour fire protection ratings for the affected penetrations to prevent fires from spreading between adjacent ar~as. The surveillance test was completed satisfactorily and verified that the dampers had remained operable throughout the period, therefore, no unreviewed safety question existed and the health and safety of the public were not affected.

NRC Form 366A (6-89)

,: NRC FORM 366A U.S. NUCLEAR-REGULATORY COMMISSION

'- (6-89) APPROVED 0MB ND. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LERI INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCff (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1"HE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

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

Surry Power Station, Unit 1 o 1s101010121s10 9jO - 01017 - 010 o 13 oF o 14 TEXT /ff more spaco is required, use additional NRC Form 366A'*I (17) 3.0 CAUSE The cause of this event was administrative oversight by the fire protection group. The .scheduling group distributes to each*

department a scheduling package containing a Periodic Test (PT) summary sheet listing required surveillance tests and scheduling data sheets which are to be attached to. each procedure upon completion of the surveillance test. The summary sheets and scheduling data sheets are left with the department which is to perform the surveillance tests. A missed surveillance 1s more likely. to occur on procedures with longer intervals due to the length of time between receiving the scheduling package (July 1989 in this case) and the actual due date of the procedure (November 1989 schedule date and

. an overdue date of March 31, 1990).

4. 0 IMMEDIATE CORRECTIVE ACTION<S}

The dampers were declared inoperable and fire watches were established within the required Technical Specification time limits.

5. 0 ADDITIONAL CORRECTIVE ACTION<S)

The surveillance procedure was performed satisfactorily, and the fire watches were secured.

6. 0 ACTIONS TO PREVENT RECURRENCE

1) Fire protection personnel involved m the missed surveillance were reinstructed regarding the necessity to strictly adhere to PT schedules.

NRC Form 366A (6-89)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-89) APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION 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 (11 DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

Surry Power Station, Unit 1 TEXT (If more space is required, UIS(J *ddition*I NRC Form 366A's) (17)

2) Additional administrative procedures have been put in place which will highlight PTs which have become overdue. Further, any PT with an interval of quarterly or greater will -be identified as soon as their scheduled date has passed.

7 *0 SIMILAR EVENTS None.

8. 0 -MANUFACTURER/MODEL NUMBER Not applicable.

NRC Form 366A (6-89)