05000339/LER-2004-001, Regarding Inoperable Emergency Diesel Generators Due to Shims for Exhaust Support Missing or Not Secured
| ML041890408 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/29/2004 |
| From: | Jennifer Davis Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 04-368 LER 04-001-00 | |
| Download: ML041890408 (6) | |
| 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 |
| 3392004001R00 - NRC Website | |
text
1 OCFR50.73 Virginia Electric and Power Company North Anna Power Station P. 0. Box 402 Mineral, Virginia 23117 June 29, 2004 U. S. Nuclear Regulatory Commission Serial No.:
04-368 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. 50-339/2004-001-00 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, J. M. Davis, 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 23T85 Atlanta, Georgia 30303-8931 Mr. M. T. Widmann NRC Senior Resident Inspector North Anna Power Station
APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 NRC FORM 366 U.S. NUCLEAR REGULATORY Estimated burden per response to comply with this mandatory Information collection (7-2001)
COrequest:
50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are Incorporated Into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records Management Branch CT-B E6), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to bjsl @nrc.gotv, and to the Desk Officer, Office of Information and Regulatory Affairs. NEOB-10202 (3150-LICENSEE EVENT REPORT (LER) 0104), Office of Management and Budget, Washington, DC 20503. It a means used (See reverse for required number of digits/characters for each block) to impose Information colltection ddoteos no~t disoprl ay a curentoy vaid 0MB contiretol respond to, the Information collection.
FACILfTY NAME (1)
DOCKET NUMBER (23PAG (3)
NORTH ANNA POWER STATION,UNIT 2 l105000 -339 lI 1 0F 5 TITLE (4) lnooerable Emeraencv Diesel Generators Due to Shims for Exhaust Support Missino or Not Secured EVENT DATE (5I LER NUMBER (6 REPORT DATE (7)
OTHER FACILITIES INVOLVEDI(8)
MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR FACILrIY NAME DOCUMENTNUMBER NUMBER NUMBER 05000 05 09 2004 2004
- - 001 -
06 29 2004 FACILITY NAME 05000-I_
___DOMETNBR OPERATING THIS REPORT IS SUBMITTED PURSUANTTOTHE REQUIREMENTS OF 10 CFR §: (Checkall that apply) (11)
MODE (9) 6 l 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 l 0 l 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) l 50.36(c)(1)(ii)(A)
X 50.73(a)(2)(v)(A) 73.71(a)(5) 20.2203(a)(2)(ii) l_7_50.36(c)(2)
X 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(iii) l 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
SpecityIn Abstract below or 20.2203(a)(2)(iv)
X 50.73(a)(2)(i)(A)
X 50.73(a)(2)(v)(D)
In (If more space is required, use additionalcopies 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 50-339/88-004-00 dated June 17,1988 documents an event when the Unit 2 "J" EDG was out of service during preplanned maintenance and the Unit 2 NH" EDG became inoperable during testing.
LER 50-338/97-008-00 dated November 4,1997 documents an event when the Unit 1 "J" EDG was inoperable to perform surveillance testing and the Unit 1 "H" EDG was inoperable due to an engine cooling fan failure.
LER 50-338, 339/2000-002-00 dated April 27, 2000 documents an event when the Unit 1 "J" EDG was removed from service for maintenance during a refueling outage and the Unit 1 "H" EDG was subsequently determined to be inoperable due to hydraulic lock.
8.0 ADDITIONAL INFORMATION
The issue with the EDG exhaust piping is limited to the support that is anchored to the south wall of the EDG exhaust bunker. The purpose of this support is to provide for seismic restraint of the old EDG exhaust pipe. The configuration of the support structure is the same for each EDG. Inspection and repair of the subject EDG exhaust supports to the original design configuration addressed the seismic implications of the issue. The problem is not believed to extend to any other supports in the EDG exhaust bunker since the other supports are not subject to the same loading conditions as the subject supports.
On April 27, 2004, inspection of the Unit 1 "J" EDG identified one shim on the engine exhaust stack seismic support on the south wall had fallen out of place. This condition was subsequently analyzed and the support was found to retain its operability. The shim was replaced and the anchor bolts were re-torqued to a minimum of 125 ft-lbs.
On May 10, 2004, inspection of the Unit 1 "H" EDG identified two shims on the engine exhaust stack seismic support on the west wall had fallen out of place and the associated anchor bolt nuts were missing. This condition was subsequently analyzed and the support was found to retain its operability. The shims were replaced and the anchor bolts were re-torqued to a minimum of 125 ft-lbs.