05000280/LER-2009-001, Inoperable Emergency Service Water Pump Caused by Inadequate Design Change
| ML092170162 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/29/2009 |
| From: | Gerald Bichof Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 09-432 LER 09-001-00 | |
| Download: ML092170162 (6) | |
| 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) 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 |
| 2802009001R00 - NRC Website | |
text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 1 0CFR50.73 July 29, 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.:
09-432 SS&L/TJN RO Docket No.: 50-280 50-281 License No.: DPR-32 DPR-37
Dear Sirs:
Pursuant to 10CFR50.73, 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/ 2009-001-00 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. Bisch Site Vice President Surry Power Station Enclosure Commitments contained in this letter:
A new modification will be developed and the design change process will be strengthened to prevent recurrence.
Serial No.: 09-432 Docket Nos: 50-280/ 50-281 Page 2 of 2 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 OF 4
- 4. TITLE Inoperable Emergency Service Water Pump Caused by Inadequate Design Change
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCUMENTNUMBER I
NUMBER NO.
Surry Power Station, Unit 2 05000281 05 30 2009 2009 001 --
00 07 29 2009 FACILITY NAME DOCUMENT NUMBER I1I I 1 1
05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) li 20.2201(b)
Li 20.2203(a)(3)(i)
[I]
50.73(a)(2)(i)(C)
Li 50.73(a)(2)(vii)
Li 20,2201(d)
Li 20.2203(a)(3)(ii)
LI 50.73(a)(2)(ii')(A)
[]
50.73(a)(2)(viii)(A)
N
[] 20.2203(a)(1)
[]
20.2203(a)(4)
[]
50.73(a)(2)(ii)(B)
[]
50.73(a)(2)(viii)(B)
--'1 20.2203(a)(2)(i)
[
50.36(c)(1)(i)(A)
Li 50.73(a)(2)(iii)
[] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
"]
20.2203(a)(2)(ii)
[] 50.36(c)(1)(ii)(A)
Li 50.73(a)(2)(iv)(A)
Li 50.73(a)(2)(x)
Li 20.2203(a)(2)(iii)
[]
50.36(c)(2)
Li 50.73(a)(2)(v)(A)
[]
73.71(a)(4)
Li 20.2203(a)(2)(iv)
[] 50.46(a)(3)(ii)
[]
50.73(a)(2)(v)(B)
[]
73.71(a)(5)
[1 20.2203(a)(2)(v)
Li 50.73(a)(2)(i)(A)
L] 50.73(a)(2)(v)(C)
Li OTHER 100%
L] 20.2203(a)(2)(vi)
FX I 50.73(a)(2)(i)(g)
[]
50.73(a)(2)(v)(D)
VOLUNTARY LER
- 12. LICENSEE CONTACT FOR THIS LER NAME TELEPHONE NUMBER (Include Area Code)
Brandford L. Stanley, Director Safety and Licensing (757) 365-2003CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM MPONENT MANU-REPORTABLE IFACTURER TO EPIX FACTUREIR TO EPIX B
BI ENG D699 Y
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
W NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On May 30, 2009, with Units 1 and 2 at 100% reactor power, diesel engine driven Emergency Service Water Pump "A" (ESWP A) failed to start due to water intrusion into exhaust piping. The exhaust piping was recently modified to add missile protection and the applied sealant failed.
Following engine repairs and change of the sealant material type, the pump was declared operable on June 3, 2009. During operator rounds on June 6, 2009, water was discovered leaking around the exhaust pipe for ESWP A and the pump was again declared inoperable. The pump was returned to pre-modification configuration and declared operable on June 9, 2009. The direct cause of both events was water intrusion into the ESWP diesel exhaust. The root cause was the failure of the design change to account for a full range of design inputs. A new modification will be developed and the design change process will be strengthened to prevent recurrence. The ESWP A failures did not affect the health and safety of the public. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B), any operation or condition that was prohibited by the plant's Technical Specification, and 10 CFR 50.73(a)(2)(v)(D), any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.
NRC FORM 366 (9-20307)
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
A new design change will be developed to provide missile protection for the ESWPs exhaust lines.
6.0 ACTIONS TO PREVENT RECURRENCE The design process procedures will be revised related to design considerations of material suitability, environmental conditions, and potential failure modes. Related training will include particular attention on consideration of adverse weather conditions and the potential for introduction of new failure modes or increased potential for a particular failure mechanism.
7.0 SIMILAR EVENTS
The root cause of the water intrusion into the ESWP A is considered a repeat of design issues identified on an inadequate engineering evaluation for a September 2008 event. The August 30, 2008 implementation of a design to provide missile protection for the ESWP B exhaust line resulted in the pump being declared inoperable on September 2, 2008.
Exhaust particulate buildup on a foreign material exclusion screen was considered to have caused back pressure in the exhaust piping. The exhaust piping screen was removed and ESWP B returned to service on September 2, 2008. The cause was a human performance error related to the change process selected to implement the modification of the diesel engine exhaust. Further modifications of the ESWPs were made using the design change process. The root cause evaluation corrective actions for the ESWP A event will further correct the ESWP B event cause.
8.0 ADDITIONAL INFORMATION
Manufacturer-Detroit Diesel Model Number-7084-7002PRINTED ON RECYCLED PAPER