05000336/LER-2004-002, Regarding Automatic Reactor Trip on Low Steam Generator Level Resulted from a Feedwater Pump Trip During Test

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Regarding Automatic Reactor Trip on Low Steam Generator Level Resulted from a Feedwater Pump Trip During Test
ML041460459
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/11/2004
From: Price J
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
04-282 LER 04-002-00
Download: ML041460459 (6)
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LER-2004-002, Regarding Automatic Reactor Trip on Low Steam Generator Level Resulted from a Feedwater Pump Trip During Test
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation
3362004002R00 - NRC Website
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text

4wDominion-Dominion Nuclear Connecticut, Inc.

Millstone Power Station Rope Ferry Road Waterford, CT 06385 "MAY U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.

MPS Lic/RWM Docket No.

License No.04-282 RO 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION, UNIT 2 LICENSEE EVENT REPORT 2004-002-00 AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR LEVEL RESULTED FROM A FEEDWATER PUMP TRIP DURING TEST This letter forwards Licensee Event Report (LER) 2004-002-00, documenting an event that occurred at Millstone Power Station, Unit 2, on March 15, 2004. This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(iv)(A), as an event or condition that resulted in an actuation of a reactor protection system.

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

Very truly yours, J.

grce Si e ice President - Millstone

'-"11

Serial No.04-282 LER 2004-002-00 Page 2of2 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.04-282 LER 2004-002-00 Millstone Power Station, Unit No. 2 LER 2004-002-00 Dominion Nuclear Connecticut, Inc.

NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 (7 1 C O A

, the NRC may not conduct or sponsor, (See reverse for reaulred number of diqitslcharacters 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 2 05000336 1 OF3 TITLE (4)

Automatic Reactor Trip on Low Steam Generator Level Resulted From a Feedwater Pump Trip During Test EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8) 7 FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR SEQUENTIAL lREV MO DAY YEAR 05000 NUMBER NO.DYjYA 50 j

FACILITY NAME DOCKET NUMBER 03 15 2004 2004-002-00 05 11 2004 05000 OPERATING 1

THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CF R: (Check all that apply) (11)

MODE (9) 20.2201(b) 20.2203(aX3Xii) 50.73(a)(2Xii)(B) 50.73(aX2)(ixXA)

POWER 100 20.2201(d)

_ 20.2203(a)(4)

_ 50.73(a)(2Xiii) 50.73(a)(2Xx)

LEVEL (10) 20.2203(a)(1) 50.36(c)(1 XiXA) x 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(a)(2yi) 50.36(c)(1)(ii)(A) 50.73(aX2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii)

_ 50.36(c)(2) 50.73(aX2)(v)(B)

_ OTHER 20.2203(a)(2)(iii) 50.46(a)(3Xii) 50.73(aX2)(v)(C)

Specify In Abstract below or l

_ 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)

3. Assessment of Safety Consequences

The purpose of the SGFW system is to provide water to the SGs for the transfer of thermal energy from the primary side of the SGs to the secondary side. The SGFW system is not safety related. The risk associated with this reactor trip is generally considered the same as from any normal plant trip since the Main and Auxiliary pumps remained available for decay heat removal. During and after the plant trip, there were no challenges to design basis event mitigation functions and no loss of any credited safety function from structures, systems and components. Consequently, this event is considered to be of loW safety significance.

4.

Corrective Action

Corrective actions are being addressed in accordance with the Millstone Corrective Action Program. Prior to use of the 'B' SGFW pump in support of unit restart, action was taken to repeat the testing to evaluate the reliability of installed components. To prevent recurrence, the performance of applicable sections of the emergency governor and trip lockout exerciser test procedure at power levels that could challenge a reactor trip from a SGFW pump trip has been suspended until such time as an appropriate final resolution to this condition is specified.

5.

Previous Occurrences

No previous similar events/conditions were identified.

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

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