ML20135F277
| ML20135F277 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| 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.
'F: Forced Reason:
' Method:
' Exhibit G - Instructions 2
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.
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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 cleaned.
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4, 2P-10B residual heat removal pump control switch replaced.
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5.
2P-1IB component cooling water pump changeout.
I 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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