05000339/LER-2003-001, For North Anna Power Station, Unit 2 Regarding Automatic Reactor Trip Due to Steam Flow - Feed Flow Mismatch
| ML031140350 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/17/2003 |
| From: | Heacock D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 03-256 LER 03-001-00 | |
| Download: ML031140350 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 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)(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 |
| 3392003001R00 - NRC Website | |
text
1 OCFR50.73 Virginia Electric and Power Company North Anna Power Station P. 0. Box 402 Mineral, Virginia 23117 April 17, 2003 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.:
NAPS:
Docket No.:
License No.:
03-256 MPW 50-339 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. 50-339/2003-001-00 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, A. Heacock, ite 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
l APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 NRC FORM 366 U S NUCLEAR REGULATORY Esm (7-201 COMMISSON 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) j PAGE (3)
NORTH ANNA POWER STATION, UNIT 2 05000 - 339 1 OF4 TITLE (4)
Automatic Reactor Trip Due to Steam Flow - Feed Flow Mismatch EVENT DATE 5 LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR FACILITY NAME DOCUMENTNUMBER l
NUMBER NUMBER l 05000-03 31 2003 2003
- - 001-00 04 17 2003 FACILITY NAME DOCUMENT NUMBER lI 05000-OPERATING THIS REPORT IS SUBMITTEDPURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) (11)
MODE (9) 1 I 20 2201(b) 20.2203(a)(3)(n) 50.73(a)(2)(n)(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) l_l_50 36(c)(1)(i)(A)
X 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(a)(2)(i) 50 36(c)(1)(ii)(A) 50.73(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)(ii) l 50.46(a)(3)(n) 50.73(a)(2)(v)(C)
Specfy 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)
A root cause evaluation is being performed regarding the automatic reactor trip. Corrective actions will be performed as necessary following completion of the evaluation.
7.0 SIMILAR EVENTS
LER N2-91-009-00 dated 10/10/91, documents an automatic reactor trip from "B" steam generator low level coincident with a steam flow greater than feed flow mismatch caused by closure of the "B" main feed regulating valve.
8.0 ADDITIONAL INFORMATION
At the time of this event Unit 1 was defueled as part of a scheduled refueling outage.
Component failure information
Description
Driver Card Mark No. 02-FW-FCY-2498 Manufacturer:
Westinghouse Model No.:
2837A16G03 Our Instrument and Calibration group is refurbishing these driver cards on site.