05000280/LER-2003-001, Re Electrical Conduit Bushing Failure Results in Reactor Trip

Re Electrical Conduit Bushing Failure Results in Reactor Trip

ML030920215
Person / Time
Site:	Surry
Issue date:	03/26/2003
From:	Blount R Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
03-197, SPS:BAG/TJN R2 LER 03-001-00
Download: ML030920215 (6)

LER-2003-001, Re Electrical Conduit Bushing Failure Results in Reactor Trip

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
2802003001R00 - NRC Website

text

1 OCFR50.73 Virginia Electric and Power Company Surry Power Station 5570 Hog Island Road Surry, Virginia 23883 March 26, 2003 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.:

03-197 SPS: BAG/TJN R2 Docket No.: 50-280 50-281 License No.: DPR-32 DPR-37

Dear Sirs:

Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to Surry Power Station Units 1 and 2.

Report No. 50-281/2003-001-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be forwarded to the Management Safety Review Committee for its review.

Very truly yours, Richard H. Blount, Site Vice President Surry Power Station Enclosure Commitment contained in this letter:

A Root Cause Evaluation (RCE) was initiated to determine the cause of this event.

The approved recommendations from the RCE necessary to prevent recurrence will be implemented through the corrective action program.

I cc:

United States Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23 T85 Atlanta, Georgia 30303-8931 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

I

.4 t

APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 NRC FORM 366 U.S. NUCLEAR REGULATORY (7 2001)

COMESLIORN the NRC may not conduct or sponsor, and a person Is not required to respond to, the information collection FACILITY NAME (1)

DOCKET NUMBER (2)

PAGE (3)

SURRY POWER STATION, Unit 2 05000 - 281 1OF4 l

TITLE (4)

Electrical Conduit Bushing Failure Results in a Reactor Trip EVENT DATE (5) l LER NUMBER (6) ll REPORTDATE 7 OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR l

SEQUENTIAL REVISION MONTH DAY FACILll Y NAME DOCUMENT NUMBER NUMBER NUMBER YE_____

SURRY POWER STATION, Unit 1 05000-280 01 25 2003 2003

-- 001 --

00 03 26 2003 FACILITY NAME DOCUMENT NUMBER 2003

.1105000-OPERATING 1 THIS REPORTIS SUBMITTED PURSUANTTOTHE REQUIREMENTS OF 10 CFR§: (Check all thatapply) (11)

MODE (9)

N J

20.2201 (b) 20.2203(a)(3)(iu) 50 73(a)(2)(i)(B) 50 73(a)(2)(ix)(A)

POWER l

20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(m) 50.73(a)(2)(x)

LEVEL (10 100 =

20.2203(a)(1) 50.360(1)(i)(A)

X 50 73(a)(2)(rv)(A) 73 71(a)(4) 20 2203(a)(2)(i) 50.36©(1)(ii) (A) 50.73(a)(2)(v)(A) 73 71 (a)(5) 20.2203(a)(2)(ii) 50.360(2) 50.73(a)(2)(v)(B)

OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)

Specify in Abstract below or 20 2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) in (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17) 6.0 ACTIONS TO PREVENT RECURRENCE A Root Cause Evaluation (RCE) was initiated to determine the cause of the reactor trip due to generator differential. Conclusions from the RCE will be evaluated and the approved recommendations from the RCE necessary to prevent recurrence will be implemented through the corrective action program.

7.0 SIMILAR EVENTS

None.

8.0 MANUFACTURER/MODEL NUMBER The insulated bushing was a Seimens Westinghouse Manufacturing part number 57D2226G01.

9.0 ADDITIONAL INFORMATION

None.