05000280/LER-2009-002, Emergency Service Water Pumps Potential Flooding Due to Inadequate Procedure
| ML093350531 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/23/2009 |
| From: | Gerald Bichof Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 09-718 LER 09-002-00 | |
| Download: ML093350531 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2802009002R00 - NRC Website | |
text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 1 0CFR50.73 November 23, 2009 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Surry Power Station 5570 Hog Island Road Surry, Virginia 23883 Serial No.:
09-718 SS&L/TJN RO Docket No.: 50-280 50-281 License No.: DPR-32 DPR-37
Dear Sirs:
Pursuant to 10 CFR 50.73, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to Surry Power Station Units 1 and 2.
Report No. 50-280, 50-281/ 2009-002-00 This report has been reviewed by the Facility Safety Review Committee and will be forwarded to the Management Safety Review Committee for its review.
Very truly yours, Gerald T. Bisif, Site Vice President Surry 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 NRC Senior Resident Inspector Surry Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES: 8/31/2010 (9-2007)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE SURRY POWER STATION, UNIT 1 05000280 1 OF4
- 4. TITLE Emergency Service Water Pumps Potential Flooding Due to Inadequate Procedure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SFACILITY NAME DOCUMENT NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR SurrY PowE SttonEnt U5008 NUMBER NO.
Surry Power Station, Unit 2 05000281 09 24 2009 2009 002 00 11 23 2009 FACILITY NAME DOCUMENT NUMBER 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
Dj 20.2201(b)
E]
20.2203(a)(3)(i)
LI 50.73(a)(2)(i)(C)
[j]
50.73(a)(2)(vii)
E] 20.2201(d)
E] 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
LI 50.73(a)(2)(viii)(A)
N LI 20.2203(a)(1)
[:] 20.2203(a)(4)
L]
50.73(a)(2)(ii)(B)
LI 50.73(a)(2)(viii)(B)
[] 20.2203(a)(2)(i)
Ej 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
E] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
[]
20.2203(a)(2)(ii)
[]
50.36(c)(1)(ii)(A)
L]
50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
LI 20.2203(a)(2)(iii)
LI 50.36(c)(2)
E]
50.73(a)(2)(v)(A)
[]
73.71(a)(4)
LI 20.2203(a)(2)(iv)
[j 50.46(a)(3)(ii) j] 50.73(a)(2)(v)(B)
LI 73.71(a)(5)
LI 20.2203(a)(2)(v)
[]
50.73(a)(2)(i)(A)
I 50.73(a)(2)(v)(C)
E] OTHER 100%
LI 20.2203(a)(2)(vi)
[j 50.73(a)(2)(i)(B)
FI 50.73(a)(2)(v)(D)
VOLUNTARY LER
- 12. LICENSEE CONTACT FOR THIS LER NAME TELEPHONE NUMBER (Include Area Code)
B. L. Stanley, Director Safety and LicensinQ (757) 365-2003CAUSE SYSTEM COMPONENT I MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT' MANU-REPORTABLE FACTURER TO EPIX IF FACTURER TO EPIX D "
BI I
HX II Y
I
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION LI YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
I-.
NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On September 24, 2009, with Units 1 and 2 at 100% reactor power, it was discovered that the three emergency service water (ESW) pump oil cooler outlet lines, which penetrate the pump base plates, were not sealed to prevent pump house water intrusion. The ESW pump house is designed to withstand flooding from hurricane driven tidal surges of 22.7 feet. With the pump base plates at approximately 18 feet above sea level, potential pump inoperability would occur if the water level rises above 18 feet. The cause evaluation identified that in the 1990's, the threaded interface seals on the outlet lines were no longer utilized. The evaluation also found the apparent cause to be inadequate procedural guidance for sealing the outlet lines.
Following discovery, seals were installed.
The maintenance procedure has been strengthened to prevent recurrence.
An evaluation determined this issue to be of very low risk significance, therefore, the health and safety of the public was not affected. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B),
any event or condition which was prohibited by Technical Specifications.
NRC FORM 366 (9-2007)
PRINTED ON RECYCLED PAPER (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)
5.0 ADDITIONAL CORRECTIVE ACTIONS
An extent of condition walk down was performed at the ESW pump house and no other water ingress gaps were identified.
6.0 ACTIONS TO PREVENT RECURRENCE The maintenance procedure has been revised to require the penetrations through the pump base plate to be sealed if maintenance is performed.
7.0 SIMILAR EVENTS
None
8.0 ADDITIONAL INFORMATION
NonePRINTED ON RECYCLED PAPER