05000423/LER-2004-002, Regarding Inoperable Motor Driven Auxiliary Feedwater Pump Resulting from a Degraded Service Water System Brazed Joint
| ML042160296 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/26/2004 |
| From: | Sarver S Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 04-443 LER 04-002-00 | |
| Download: ML042160296 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) 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 |
| 4232004002R00 - NRC Website | |
text
. OF";NVIF4-4 1.V P
'I 0 0
-.1 W Dominion-Dominion Nuclear Connecicut, Inc.
Millstone Power Station Rope Ferry Road Waterford, CT* 06385 IL 2 6 2a U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
MPS Lic/RWM Docket No.
License No.04-443 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION, UNIT 3 LICENSEE EVENT REPORT 2004-002-00 INOPERABLE MOTOR DRIVEN AUXILIARY FEEDWATER PUMP RESULTING FROM A DEGRADED SERVICE WATER SYSTEM BRAZED JOINT This letter forwards Licensee Event Report (LER) 2004-002-00, documenting an historical condition at Millstone Power Station, Unit 3, that was determined reportable on May 26, 2004. This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by technical specifications.
These preliminary conclusions are based on conservative engineering analysis, which is under review. Final conclusions including safety significance will be addressed in a supplement to this report.
If you have any questions or require additional information, please contact Mr. David W. Dodson at (860) 447-1791, extension 2346.
Very truly yours, te n P. Sarver, Director Nuclear Station Operations and Maintenance
Z&
Serial No.04-443 LER 2004-002-00 Page 2 of 2 Attachments:
(1)
Commitments made in this letter: None.
cc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. V. Nerses Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station
Serial No.04-443 LER 2004-002-00 Attachment I Millstone Power Station, Unit No. 3 LER 2004-002-00 Dominion Nuclear Connecticut, Inc.
NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO.3150-0104 EXPIRES 7-3112004
, the NRC may not conduct or sponsor.
(See reverse for reouired number of diaits/characters for each block) and a person Is not required to respond to. the Information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Millstone Power Station - Unit 3 05000423 1 OF3 TITLE (4)
Inoperable Motor Driven Auxiliary Feedwater Pump Resulting From a Degraded Service Water System Brazed Joint EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8) l FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR SEQUENTIAL IR'EV MO DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 05 26 2004 2004 - 002 - 00 07 26 2004 05000 OPERATING 1
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR (Check all that apply) (11)
MODE (9)
_ 20.2201(b)
_ 20.2203(aX3)(ii) 50.73(a)(2Xii)(B) 50.73(a)(2)(ixXA)
POWER
_ 20.2201(d) 20.2203(a)(4) 50.73(a)(2Xiii) 50.73(aX2)(x)
LEVEL(10) 100 20.2203(a)(1)
_ 50.36(cX1 XiXA) 50.73(a)(2)(iv)(A) 73.71(a)(4) 20.2203(a)(2y=) 50.36(c)(1)(ii)(A)
= 50.73(a)(2)(v)(A)
J73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(iii) 50.46(a)(3yii) 50.73(aX2)(v)(C)
Specify in Abstract below or 20.2203(aX2)(iv) 50.73(a)(2XiXA) 50.73(aX2)(v)(D) in (If more space Is required, use additional copies of NRC Form 366A) (17)
- 4.
Corrective Action
The corrective action to prevent recurrence of this specific condition has been completed during the refueling outage. The 'A' and 'B' ESF supply header tees were cut out and replaced with new 3 inch butt-welded piping and branch weldolets.
A multi-year program is continuing to replace major portions of the brazed joint service water system piping to preclude similar brazed joint failures. The corrective actions associated with this condition are being addressed in accordance with the Millstone Corrective Action Program.
- 5.
Previous Occurrences
No previous similar events/conditions were identified.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].