05000336/LER-2003-006, Regarding Two Manual Reactor Due to Turbine Trips Caused by Turbine Vibrations
| ML040340229 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/23/2004 |
| From: | Price J Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 04-024 LER 03-006-00 | |
| Download: ML040340229 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2) 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
| 3362003006R00 - NRC Website | |
text
--171n-'N
,, 3 Ir
,"teX': A pB
-.2 zf Dominion Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road Waterford, Cr1 06385 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 JM~ 23 MJO Serial No.:
NL&OS/MAE Docket No.:
License No.:
04-024 Rev 0 50-336 NFP-49 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)
MILLSTONE POWER STATION. UNIT NO. 2 LISENSEE EVENT REPORT 2003-006-00 TWO MANUAL REACTOR TRIPS DUE TO TURBINE TRIPS CAUSED BY TURBINE VIBRATIONS This letter forwards Licensee Event Report (LER) 2003-006-00, which documents two events at Millstone Power Station, Unit No. 2, which occurred on November 27 and November 28, 2003.
This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(iv)(A), any event or condition that resulted in manual or automatic actuation of reactor protection system.
There are no regulatory commitments contained within this letter.
If you should have any questions regarding this submittal, please contact Mr. David W.
Dodson at (860) 447-1791, extension 2346.
Very truly yours, aJ Price 4i Vice President - Millstone Attachment (1)
-'i
4:
LI--
Serial No.04-024 Millstone Unit No. 2, Licensee Event Report 2003-006-00 Page 2 of 2 cc:
H. J. Miller U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. R. M. Pulsifer NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station The Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Millstone Power Station, Unit No. 2 LER 2003-006-00 Dominion Nuclear Connecticut, Inc.
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 required 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)
I PAGE (3)
Millstone Power Station - Unit No. 2 05000336 1 OF 3
TITLE (4)
Two Manual Reactor Trips Due to Turbine Trips Caused by Turbine Vibrations EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MO DAY YEAR YEAR SEQUENTIAL REV MO DAY YEAR FACILITY NAME DOCKET NUMBER
- NUMBER NO.
05000
, 11 27 2003 2003 -
006 -
- 00.
01 23 2004 FACILITY NAME DOCKET NUMBER 05 0 0 0 OPERATING 1
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check all that apply) (11)
MODE (9) l20.2201(b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) l 50.73(a)(2)(ix)(A)
POWER 720 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(;ii) 50.73(a)(2)(x)
LEVEL (10) 20.2203(a)(1) 50.36(c)(11(i)(A)
X 50.73(a)(2)(iv)(A) 73.71 (a)(4)
_me.!,_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) 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(iii)
=
50.46(a)(3)(Di)
=
50.73(a)(2)(v)(C)
Specify In Abstract below or 20.2203(a)(2)(iv) 150.73(a)(2)(i)(A) 50.73(a)(2)(v)(D)
_ in (If more space Is required, use additional copies of NRC Form 366A) (17)
The risk associated with a reactor trip is considered similar as for any general plant transient. Therefore, these two events have low safety significance.
- 4.
Corrective Action
The Corrective Action is to conduct a lessons learn from the Millstone Unit No. 2 startup to determine any changes required for future Millstone Unit No. 2 startups and applicability of these changes to Millstone Unit No. 3 startup (which will also have new monoblock LP rotors) following refueling outage 9, by February 15, 2004.
5. Previous Occurrences
No previous similar events were identified.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].