ML051610279
| ML051610279 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/08/2005 |
| From: | Kalyanam N NRC/NRR/DLPM/LPD4 |
| To: | Venable J Entergy Operations |
| Kalyanam N,NRR/DLPM,415-1480 | |
| References | |
| LER 03-002-00 | |
| Download: ML051610279 (4) | |
Text
June 8, 2005 Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 (WATERFORD 3) - FINAL ACCIDENT SEQUENCE PRECURSOR ANALYSIS OF SEPTEMBER 2003 OPERATIONAL EVENT
Dear Mr. Venable:
Enclosed for your information is the Final Accident Sequence Precursor (ASP) Analysis of an operational event which occurred at Waterford 3 in September 2003. The condition was reported by Licensee Event Report No. 2003-002-00, dated November 26, 2003, and documented in U.S. Nuclear Regulatory Commission (NRC) Inspection Report No. 05000382/2003007, dated February 2, 2004. This is being issued as a final analysis since it is a non-controversial, lower risk precursor for which the ASP results are consistent with the results from the Significance Determination Processs final evaluation of the same condition.
The review and comment resolution process for this event are eliminated and it is expected that this will reduce the burden for the NRC staff and the licensee.
Sincerely,
/RA/
N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
As stated cc w/encl: See next page
June 8, 2005 Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 (WATERFORD 3) - FINAL ACCIDENT SEQUENCE PRECURSOR ANALYSIS OF SEPTEMBER 2003 OPERATIONAL EVENT
Dear Mr. Venable:
Enclosed for your information is the Final Accident Sequence Precursor (ASP) Analysis of an operational event which occurred at Waterford 3 in September 2003. The condition was reported by Licensee Event Report No. 2003-002-00, dated November 26, 2003, and documented in U.S. Nuclear Regulatory Commission (NRC) Inspection Report No. 05000382/2003007, dated February 2, 2004. This is being issued as a final analysis since it is a non-controversial, lower risk precursor for which the ASP results are consistent with the results from the Significance Determination Processs final evaluation of the same condition.
The review and comment resolution process for this event are eliminated and it is expected that this will reduce the burden for the NRC staff and the licensee.
Sincerely,
/RA/
N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION PUBLIC PDIV-1 Reading RidsOgcRp RidsAcrsAcnwMailCenter RidsNrrDlpmLpdiv1 (DTerao)
DSkay RidsNrrPMNKalyanam RidsNrrLADBaxley GDeMoss (RES)
RidsRgn4MailCenter(AHowell)
Accession No.:ml051610279 OFFICE PDIV-1/PM PDIV-1/LA PDIV-1/SC NAME NKalyanam DBaxley DTerao DATE 6/8/05 6/8/05 6/8/05 OFFICIAL RECORD COPY
SUMMARY
OF FINAL ACCIDENT SEQUENCE PRECURSOR (ASP) ANALYSIS FAILURE OF EMERGENCY DIESEL GENERATOR (EDG) A FUEL OIL LINE AT WATERFORD STEAM ELECTRIC STATION, UNIT 3 This event is documented in Licensee Event Report 2003-002-00, with an event date of September 29, 2003.
Condition summary:
On September 29, 2003, at about 10:20 a.m. with the plant in Mode 1 (approximately 90 percent power and coasting down for refueling), EDG 'A' was started to perform the monthly surveillance run in accordance with station operating procedures. At approximately 1:09 p.m.,
with EDG 'A' running loaded, the left/right bank cross connect fuel oil tubing failed rendering the engine inoperable. Although, EDG 'A' testing surveillances were successfully completed prior to September 29, 2003, there is firm evidence that after the last successful surveillance on September 2, 2003, EDG 'A' may not have been able to complete a mission run time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Results:
The ASP analysis calculated a delta core damage probability (CDP) of 2x10-6. Since the ASP program acceptance threshold is 1x10-6, this condition is a precursor.
Significance Determination Process (SDP)/ASP comparison:
The result of the SDP analysis was a white finding. The SDP Phase 3 assessment estimated an increase in core damage frequency of 5.2x10-6. Thus, the results from the SDP and ASP evaluations are consistent.
ENCLOSURE
May 2005 Waterford Steam Electric Station, Unit 3 cc:
Mr. Michael E. Henry, State Liaison Officer Department of Environmental Quality Permits Division P.O. Box 4313 Baton Rouge, Louisiana 70821-4313 Vice President Operations Support Entergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995 Director Nuclear Safety Assurance Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Wise, Carter, Child & Caraway P. O. Box 651 Jackson, MS 39205 General Manager Plant Operations Waterford 3 SES Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Licensing Manager Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Winston & Strawn 1700 L Street, N.W.
Washington, DC 20006-3817 Resident Inspector/Waterford NPS P. O. Box 822 Killona, LA 70066-0751 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Parish President Council St. Charles Parish P. O. Box 302 Hahnville, LA 70057 Executive Vice President
& Chief Operating Officer Entergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995 Chairman Louisiana Public Services Commission P. O. Box 91154 Baton Rouge, LA 70825-1697