05000338/LER-2005-001, Regarding Condition Prohibited by Technical Specification - Low Temperature Overpressure Protection
| ML053410379 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/29/2005 |
| From: | Jennifer Davis Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 05-749 LER 05-001-00 | |
| Download: ML053410379 (4) | |
| 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) 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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)(A) |
| 3382005001R00 - NRC Website | |
text
1 OCFR50.73 Virginia Electric and Power Company North Anna Power Station P. 0. Box 402 Mineral, Virginia 23117 November 29, 2005 U. S. Nuclear Regulatory Commission Serial No.:
05-749 Attention: Document Control Desk NAPS:
MPW Washington, D. C. 20555-0001 Docket No.: 50-338, 339 License No.: NPF-4, 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 Units 1 and 2.
Report No. 50-338, 339/2005-001-00 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.
Sincerely, 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. J. T. Reece NRC Senior Resident Inspector 3.-
North Anna Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2007 (6-2004)
Estimated burden per response to comply with this mandatory collection request: 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 and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, LICENSEEEVENT REPORT (LER) t Washington, DC 20555-0001, or by internet e-mail to infocoects(nrc.gov, and to LICE SEE VEN REP RT (ER)the Desk Officer, Off ice of Information and Regulatory Affairs, NEOB-1 0202 (3150-(See reverse for required number of digits/characters for each block)
- 06) Ofice of Management and Budget, Washington, DC 20503. If a means used toips nformation collection does not display a currently valid 0MB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE NORTH ANNA POWER STATION, UNIT 1 05000 338 1 OF 3
- 4. TITLE Condition Prohibited by Technical Specification - Low Temperature Overpressure Protection
- 5. EVENT DATE
- 6. LER NUMBER I
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MI
_DYYAREA SEQENIAL REISN MONTH DAY FACI~LIY NAME DOCUMENT NUMBER MONTH DAY YEARUE O
YEAR North Anna Power Station, Unit 2 05000339 10 03 2005 2005
-- 001 --
00 l
1 29 2005 FACILIlY NAME DOCUMENTNUMBER I £ 0 1 1 J______________________ 05000
- 9.
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
OPERATING MODE 1
20.2201 (b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
- 10. POWER 20.2201(d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL 100%
20.2203(a)(1)
=
50.36(c)(1)(i)(A)
=
50.73(a)(2)(iv (A)
=
73.71 (a)(4) l 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71(a)(5) l l
20.2203(a)(2)(ii)
=
50.36(c)(2)
=
50.73(a)(2)(v)(B)
OTHER l
l _
20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) 20.2203(a)(2)(iv)
X 50.73(a)(2)(j)(A__50.73(a)(2)(v)(D) 20.2203(a)(2)(y)
__50.73(a)(2)(i)(B) 50.73(a)(2)(vii)
Specify in Abstract below or 20.2203(a)(2)(vi) 50.73(a)(2)(i)(C) 50.73(a)(2)(viii)(A) in (if more space is required, use additional copies of NRC Form 366A) (17)
3.0 CAUSE
During the process of converting the original TS to the ITS, the requirement to implement two independent means to prevent an inadvertent injection into the RCS was not identified and therefore changes to the affected procedures that implement the Technical Specification requirements of LCO 3.4.12 were not completed.
4.0 IMMEDIATE CORRECTIVE ACTION(S)
With Unit 2 in Mode 5 for a refueling outage, Operations personnel entered the action for TS 3.4.12. The Unit 2 discharge motor operated valves (EIIS Systems-BP and BO, Component-ISV) for the LHSI and charging pumps were verified closed.
5.0 ADDITIONAL CORRECTIVE ACTIONS
Operating and Emergency procedures for both units were revised to require a second independent action to prevent injection into the RCS. Maintenance Operating Procedures will be revised prior to their next required use.
6.0 ACTIONS TO PREVENT RECURRENCE The station has been using the ITS for over three years and this is the first incident where a condition identified in the TS Bases was not adequately addressed by the implementing procedures resulting in a condition prohibited by TS. The event is considered an isolated case. Revisions to the procedures controlling the LHSI and charging pumps operations will ensure the actions required by TS 3.4.12 are satisfied.
7.0 SIMILAR EVENTS
None
8.0 ADDITIONAL INFORMATION
None