05000280/LER-2004-001, Emergency Service Water Pump Found Inoperable After Entry Into a Mode
| ML050450382 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/02/2005 |
| From: | Jernigan D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 05-029 LER 04-001-00 | |
| Download: ML050450382 (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 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) |
| 2802004001R00 - NRC Website | |
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Voluntary Virginia Electric And Power Company Surry Power Station 5570 Hog Island Road Surry, Virginia 23883 February 2, 2005 U. S. Nuclear Regulatory Commission Serial No.:
05-029 Attention: Document Control Desk SPS: BAG/TJN RO Washington, D. C. 20555-0001 Docket No.:
50-280 License No.: DPR-32
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 Unit 1.
Report No. 50-280/2004-001-00 This report has been reviewed by the Station Nuclear fety and Operating Committee and will be forwarded to the Management Safety R eeCommittee for its review.
iery uly yours, gan Site Vice President Surry Power Station Enclosure Commitments contained in this letter:
- 1. The design change for ESW pumps lA and 16 will be revised to require the unused circuit components to be removed with implementation of the new pre-lubrication system. A detailed circuitry evaluation will be performed following implementation.
- 2. Engineering Training will emphasize the appropriate identification of work prerequisites, required sequences, and assumptions in design change packages.
- 3. Programmatic tools used by Maintenance to implement design changes will be reviewed and strengthened to ensure design change package are effectively implemented.
Serial No.:
05-029 Docket No.: 50-280 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. N. P. Garrett NRC Senior Resident Inspector Surry 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 mandatorycollection 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 FOWLPrivacy Serice Branch (T-S F52), U.S. Nuclear Regulatory Commission, LICENSEE EVENT REPORT (LER)
Washington, DC 20555-0001, or by internet e-mail to infocollects.nrccgov.
and to the Desk Officer. Office of Information and Regulatory Affairs, NEOB-10202 (See reverse for required number of digits/characters for each block)
(3150-0066), Office of Management and Budget Washington DC 20503 U a means used to impose information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person Is not required to respond to. the Information collection.
- 3. PAGE SURRY POWER STATION, UNIT 1 05000 280 1 OF 5
- 4. TITLE Emergency Service Water Pump Found Inoperable After Entry into a Mode
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR ENTIA REVISION MONTH DAY YEAR FACILITY NAME DOCU5MENTNUMBER M rH AYNUMBER NO.f_
05000 12 04 2004 2004
-- 001 --
0 02 02 2005 FACILrIYNAME DOCUMENTNUMBER I I 1 1_
0 5 0 0 0
- 9.
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THEREQUIREMENTS OF 10 CFR §: (Check all that apply)
OPERATING MODE N
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 40%
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) 60.36(c)(2) 50.73(a)(2)(v)(B)
X OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Voluntary Report 20.2203(a)(2)(iv)
_ 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) 20.2203(a)(2)(v) 50.73(a)(2)(i)(B) 50.73(a)(2)(vii)
Specify In Abstract beWow or 20.2203(a)(2)(vi) 50.73(a)(2)(i)(C) 50.73(a)(2)(viii)(A)
In (Ifmore space is required, useadditional copies of (if more space is required, use additional copies of (if more space is required, use additionalcopies of NRC Form 366A) (17)
Engineering Training will emphasize the appropriate identification of work prerequisites, required sequences, and assumptions in design change packages.
Programmatic tools used by Maintenance to implement design changes will be reviewed and strengthened to ensure design change packages are effectively implemented.
7.0 SIMILAR EVENTS
None 8.0 MANUFACTURER/MODEL NUMBER Detroit Diesel Part # 0461128P starter motor
9.0 ADDITIONAL INFORMATION
None