05000339/LER-2001-004, Technical Specification Missed Surveillance Due to Test Procedure Error
| ML020450188 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/01/2002 |
| From: | Heacock D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 02-002, NAPS MPW LER 01-004-00 | |
| Download: ML020450188 (7) | |
| 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)(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 |
| 3392001004R00 - NRC Website | |
text
1 OCFR50.73 Virginia Electric and Power Company North Anna Power Station P. O. Box 402 Mineral, Virginia 23117 February 1, 2002 U. S. Nuclear Regulatory Commission Serial No.:
02-002 Attention: Document Control Desk NAPS:
MPW 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. 50-339/2001-004-00 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 1/
2'
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 l1)
DOCKET NUMBER (2)
PAGE (3)
NORTH ANNA POWER STATION, UNIT 2 05000 - 339 1 OF6 TITLE (4)
TECHNICAL SPECIFICATION MISSED SURVEILLANCE DUE TO TEST PROCEDURE ERROR 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_05000-12 10 2001 2001
-- 004 --
00 02 01 2002 FACILITY NAME DOCUMENTNUMBER M ( J 505000-OPERATING 1 ] THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) (11) lMODE (9) l5 20.2201 (b) 20.2203(a)(3)(ii) l50.73(a)(2)(ii)(B) l 50.73(a)(2)(ix)(A)
POWER l
20.2201(d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (10 0%
20.2203(a)(1) 50.36(c)(1)(i)(A) 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)(iii) l_l_50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Specify in Abstract below or 20.2203(a)(2)(iv) 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 (If more space is required, use additional copies of (if more space is required, use additional copies of NRC Form 366A) (17)
LER 50-338/89-004-00 documents the failure of ten containment isolation valves to achieve acceptable Type C leakage limits. The LHSI hot leg injection isolation MOVs were not among the ten failures.
8.0 MANUFACTURERIMODEL NUMBER Mark No.
02-SI-MOV-2890B Manufacturer Anchor Darling Industries Component 10" Darling OS&Y Motor Operated Gate Valve SO-E5071
9.0 ADDITIONAL INFORMATION
North Anna Unit 1 was operating in Mode 1 at 100 percent power and was not affected by this condition since the Unit 1 controlling test procedure required the equalizing valves to be open during Type C testing of each LHSI hot leg injection isolation MOV.