05000423/LER-2005-002, Regarding Inadvertent Reactor Trip and Safety Injection

Regarding Inadvertent Reactor Trip and Safety Injection

ML051790197
Person / Time
Site:	Millstone
Issue date:	06/16/2005
From:	Scace S Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
05-353 LER 05-002-00
Download: ML051790197 (7)

LER-2005-002, Regarding Inadvertent Reactor Trip and Safety Injection

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)(iii) 10 CFR 50.73(a)(2)(x)
4232005002R00 - NRC Website

text

Dominion Nuclear Connecticut, Inc.

D Millstone Power Station WUWUUom i io Rope Ferry Road Waterford, C.T 06385 JN 1 6 2 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.

NSS&L/DF Docket No.

License No.05-353 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION, UNIT 3 LICENSEE EVENT REPORT 2005-002-00 INADVERTENT REACTOR TRIP AND SAFETY INJECTION This letter forwards Licensee Event Report (LER) 2005-002-00 documenting an event at Millstone Power Station, Unit 3 that occurred on April 17, 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 the reactor protection system, multiple main steam isolation valves, emergency core cooling systems, and auxiliary feedwater system.

If you have any questions or require additional information, Mr. David W. Dodson at (860) 447-1791, extension 2346.

please contact Very truly yours, C e-dEScace:e Director - Nuclear Station Safety and Licensing Attachments:

(1)

Commitments made in this letter: None.

cc:

Mr. S. J. Collins, Administrator U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Is?

Serial No.05-353 LER 2005-002-00 Page 2of2 Mr. G. F. Wunder 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.05-353 LER 2005-002-00 ATTACHMENT LICENSEE EVENT REPORT 2005-002-00 INADVERTENT REACTOR TRIP AND SAFETY INJECTION MILLSTONE POWER STATION UNIT 3 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 reauired number of diaitslcharacters 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 OF4 TITLE (4)

Inadvertent Reactor Trip and Safety Injection EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8)

FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR SENUENTIAL REV MO DAY YEAR 05000 NUMBER NO.

FACILITY NAME DOCKET NUMBER 04 17 2005 2005 -002- 00 06 16 2005 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REUIREMENTS OF 10 CF (Check all that apply) 011)

MODE (9) 20.2201(b) 20.2203(aX3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)

POWER 100 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)

LEVEL (10) l 20.2203(a)(1) 50.36(c)(1 Xi)(A)

X 50.73(aX2)(ivXA) l 73.71 (a)(4)

_ 20.2203(a)(2yi)

_ 50.36(c)(1)(ii)(A)_ 50.73(a)()(A)

(A) 7 73.71(aX5) 20.2203(a)(2)(ii) 50.36(cX2) 50.73(a)(2Xv)(B)

X OTHER 20.2203(a)(2)(iii)

_ 50.46(a)(3X15) 50.73(a)(2XvXC)

Specify in Abstract below or 20.2203(a)(2)(iv) 5 3(a)(2XiXA) 50.73(a)(2XvXD) in (If more space is required, use additional copies of (if more space is required, use additional copies of NRC Form 366A) (17)

6.

Special Reporting Pursuant to Technical Specification 3.5.2, ACTION b, the following additional information is being reported:

Millstone Power Station Unit 3 has accumulated six SI actuations to date while in Modes 1, 2, or 3. The prior five actuations occurred in 1986 as documented in LERS 86-001-00, 003-00, 019-00, 021-00, and 027-00. The total accumulated usage factor for the SI nozzles resulting from the six SI actuations is less than 0.70.

This Licensee Event Report satisfies the Technical Specification requirement for a 90-day Special Report on the safety injection actuation.

7.

Previous Occurrences

No previous similar events were identified related to tin whiskers.

Energy Industry Identification System (EIIS) codes are identified in the text as [XX].

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