05000339/LER-2001-005, Re Automatic Reactor Trip Due to Turbine Control System Power Supply Failure

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Re Automatic Reactor Trip Due to Turbine Control System Power Supply Failure
ML020650357
Person / Time
Site: North Anna 
Issue date: 02/15/2002
From: Heacock D
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
02-035 LER-01-005-00
Download: ML020650357 (6)


LER-2001-005, Re Automatic Reactor Trip Due to Turbine Control System Power Supply Failure
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition

10 CFR 50.73(a)(2)(ix)(A)

10 CFR 50.73(a)(2)(iii)

10 CFR 50.73(a)(2)(x)

10 CFR 50.73(a)(2)(iv)(A), System Actuation

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
3392001005R00 - NRC Website

text

1 OCFR50.73 Virginia Electric and Power Company North Anna Power Station P. 0. Box 402 Mineral, Virginia 23117 February 15, 2002 U. S. Nuclear Regulatory Commission Serial No.:

02-035 Attention: Document Control Desk NAPS:

JHL Washington, D. C. 20555-0001 Docket No.: 50-339 License No.: NPF-7

Dear Sirs:

Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to North Anna Power Station Unit 2.

Report No. 50-339/2001-005-00 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, D. A. Heacock, Site Vice President North Anna Power Station Enclosure Commitments contained in this letter: None 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. M. J. Morgan NRC Senior Resident Inspector North Anna Power Station VQLi D

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

NORTH ANNA POWER STATION, UNIT 2 r05000 - 339

[ 1OF5 TITLE (4)

Automatic Reactor Trip Due To Turbine Control System Power Supply Failure EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR I

FACILITY NAME 05000-l NUMBER NUMBER l___

l 12 22 2001 2001

-- 005 --

00 02 15 2002 FACILITYNAME DOCUMENTNUMBER 05000-OPERATING 1 1 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) (11)

MODE (9) l 1 J

20.2201(b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)

POWER 20.2201(d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)

LEVEL (10) 100%

20.2203(a)(1) 50.36(c)(1)(i)(A)

X 50.73(a)(2)(iv)(A) l 73.71(a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A) l_l 5073(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)

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

Specify in Abstract below or 20.2203(a)(2)(iv) l 50.73(a)(2)(i)(A) l 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 (If more space is required, use additional copies of NRC Form 366A) (17)

7.0 SIMILAR EVENTS

LER 50-338/86-002-00 documents a reactor trip, from 100%, power generated by a low-low level in "B" steam generator caused by closure of the turbine governor valves. The closure of the turbine governor valves was attributed to problems associated with the control system.

LER 50-338/89-014-00 documents a reactor trip from, 90% power, due to loss of electro hydraulic control (EHC) system pressure. The turbine trip solenoid operated valve 20-ET o-ring failed.

LER 50-338/89-017-00 documents a reactor trip, from 7% power, generated by a low-low level in "B" steam generator caused by electro hydraulic control (EHC) system pressure transients. The EHC system pressure transient was caused by leaking turbine overspeed protection circuitry (OPC) valves.

8.0 MANUFACTURERIMODEL NUMBER The 15 amp auctioneering diode that failed was manufactured by Powerex Inc. (PRX),

Part No. 368C.

The test switch that failed was a heavy duty double-pole, single throw switch manufactured by Eaton Commercial Controls Division, Catalog No. 7310K38.

9.0 ADDITIONAL INFORMATION

North Anna Unit 1 was in Mode 1 at 100% power and was not affected by this event.