05000423/LER-2005-003, For Millstone Power Station, Unit 3 Manual Reactor Trip Due to Loss of Two Circulating Water Pumps in Same Condenser Section
| ML053260415 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/10/2005 |
| From: | Price A Dominion, Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 05-773 LER 05-003-00 | |
| Download: ML053260415 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv)(B), System Actuation 10 CFR 50.73(a)(2) 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)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
| 4232005003R00 - NRC Website | |
text
'
Dominion-Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road Waterford, ClT 06385 NOV I 0 2005 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 LICENSEE EVENT REPORT 2005-003-00 MANUAL REACTOR TRIP DUE TO LOSS OF TWO IN SAME CONDENSER SECTION Serial No.05-773 MPS Lic/WEB RO Docket No.
50-423 License No.
NPF-49 CIRCULATING WATER PUMPS This letter forwards Licensee Event Report (LER) 2005-003-00, documenting an event that occurred at Millstone Power Station Unit 3 on September 29, 2005. This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(iv)(A) as an event that resulted in manual or automatic actuation of systems listed in 50.73(a)(2)(iv)(B).
If you have any questions or require additional information, please contact Mr. David W.
Dodson at (860) 447-1791, extension 2346.
Very truly yours, A. \\A.
- - 0'2o4
°;t J. Al Site President - Millstone I
'-' L
Serial No.05-773 LER 2005-003 Manual Reactor Trip 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. G. F. Wunder Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08-B-1A Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004
, the NRC may not conduct or sponsor.
(See reverse for reouired number of diaitstcharacters for each block) and a person is not required to respond to, the information collection.
FACIUTY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Millstone Power Station - Unit 3 05000423 1 OF3 TITLE (4)
Manual Reactor Trip Due to Loss of Two Circulating Water Pumps in Same Condenser Section EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR ISEQUENTIALI REV MO DAY YEAR 05000 NUMBER O.
DY YA 50 FACILITY NAME DOCKET NUMBER 9
29 2005 2005-003-00 11 10 2005 05000 OPERATING 1
THIS REPORT IS SUBMrrTED PURSUANT TO THE REOUIREMENTS OF 10t CFr: (Check all that apply) (11)
MODE (9) 20.2201(b)
I 20.2203(a)(3)(ii) 50.73(a)(2)(li)(B) 50.73(a)(2)(ix)(A)
POWER 100 20.2201 (d) 120.2203(a)(4)
__50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL(10) 1 20.2203(a)(1) 50.36(c)(1)(')(A)
X 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)(li) 50.36(c)(2) 50.73(a)(2) (V)(B)
OTHER 20.2203(a)(2)(m) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Specify In Abstract below or 20.2203(a)(2)(iv) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D)
In (If more space Is required, use additional copies of NRCFornm 366A) (17)
- 3.
Assessment of Safety Consequences
The reactor trip resulted in a loss of normal heat removal (condenser not available). The condenser was not available due to the loss of two circulating water pumps and loss of the C-9 interlock, prohibiting the use of the condenser steam dump valves. When the 'A' CW pump was restored to service at 1343, the condenser became available and the C-9 interlock was actuated.
The auxiliary feedwater system started automatically on the trip as expected and restored the steam generator levels to their normal operating band. Heat removal capability was maintained.
The operator actions and plant mitigating equipment responded as expected with no failures. There were no challenges to any fission product barrier. Therefore, there were no safety consequences to the reactor trip on September 29, 2005.
- 4.
Corrective Action
Actions to Prevent Recurrence:
Actions were initiated in the station corrective action program to review possible design changes to the MP3 intake structure that would reduce the susceptibility to environmentally induced trips.
- 5.
Previous Occurrences
None Energy Industry Identification System (EIIS) codes are identified in the text as [XX].