ML20135F277

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Revised Monthly Operating Rept for Jan 1997 for Point Beach Nuclear Plant,Unit 2
ML20135F277
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 01/31/1997
From: Koudelka M
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20135F271 List:
References
NUDOCS 9703110305
Download: ML20135F277 (2)


Text

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POINT BEACH NUCLEAR PLANT Docket No. 50-301 Unit Nome Point Beach. Unit 2 UNIT SIIUTDOWNS AND POWER REDUCTIONS Date 3/6/97 - . .

Completed By M. B. Koudelka REPORT MONTH JANUARY - 1997 Telephone No. 414rl55-6480 Mettw! of Ucensee Event Duration Reactor Report No. System Component Cause and Corrective Action P5o. Date Type' (Hours) Reason' Shut Down' Code' Code' To Prevent Recurrence 4 961005 S 672.0 C 1 NA NA NA Scheduled refueling and snaintenance outage (U2R22). Major work items include: Replacing both Unit 2 steam generators; main control board wire separation resolution; replace 8 main steam condenser valves; HP turbine crossurufer piping; repair service water west header; replace boric acid and reactor makeup water totalizers; replace safety injection accuumlator level transmitters; modify XO2, X03, and XO4 transformer metering and relay circuits; and exciter modification.

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'F: Forced Reason: ' Method: ' Exhibit G - Instructions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG-0161)

D - Regulatory Restriction 4 - Continuation of E - Operator Training & Previous Shutdown Licensing Exam 5 - Reduced Load 5

F - Administrative 6 - Other (explain) Exhibit I - Same Source G - Operational Error (explain)

H - Other (explain) 9703110305 970306 PDR ADOCK 05000266 R PDR PBF-0028b (03-90)

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,. DOCKET NO. 50-301

. UNIT NAME Point Beach Unit 2 DATE 03/06/97 COMPLETED BY M. B. Koudelka TELEPHONE 414/755-6480 t

2 Unit 2 was in a refueling outage d-.. ring the entire February,1997 report period; The following Licensee Event Report was submitted to the NRC in February,1997:

Licensee Event Report 50-301/97-001-00, Containment Liner Clearance not in Accordance with Plant i Design Basis

, Safety-related maintenance included:

1. 2B429A-B958B P-10B residual heat removal pump normal / alternate transfer switch inspection.

1 j 2. 2CV-1299 HX-4 inlet from reactor coolant loop "A" cold leg support and restraint installed.

3. 2CV-1400 CV-371 A letdown line containment isolation downstream test connection fitting a cleaned.

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! 4, 2P-10B residual heat removal pump control switch replaced.

2 l 5. 2P-1IB component cooling water pump changeout.

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6. 2P-15A safety injection pump overhaul.
7. 2RH-700-0 reactor coolant system to P-10A&B residual heat removal pump suction header operator sealtite replaced, i

j 8. 2SI-870A P-14A containment spray pump suction from T-13 refueling water storage tank light socket replaced.

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