NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With

Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With

ML20206N306
Person / Time
Site:	Point Beach
Issue date:	04/30/1999
From:	Kaminskas V, Koudelka M WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NPL-99-0273, NPL-99-273, NUDOCS 9905170197
Download: ML20206N306 (9)

Text

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POWER COMPANY Point Beoch Nuclear Plant (920) 755-2321 6610 Nuclear Rd., Two Rivers. WI 54241 NPL 99-0273 May 6,1999 Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Mail Station PI-137 Washington, DC 20555 Ladies / Gentlemen:

DOCKETS 50-266 AND 50-301 MONTHLY OPERATING REPORTS POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2  ;

Attached are monthly operating reports for Units 1 and 2 of the Point Beach Nuclear Plant for the {

calendar month of April,1999.

Sincerely,

. [@2" b Vito A. Kaminskas Manager, )

Regulatory Services & Licensing MBK/tja Attachments //

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cc: J. D. Loock, PSCW NRC Regional Administrator, Region III NRC Resident Inspector 9905170197 990430 . . ,

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DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE 05/05/99 COMPLETED BY M. B. Koudelka TELEPHONE 920/755-6480 The daily power average for Unit I during April,1999, was 401.3 MWe.

The following Licensee Event Report (LER) was submitted to the NRC during April,1999:

' LER 266/1999-001-01, Safety Injection Recirculation Line to Refueling Water Storage Tank Frozen.

Safety-related maintenance included:

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1. '

l A52-86 alternate power to I A-06 from G-04 emergency diesel generator reduced voltage test performed.

2. IC-1 equipment access air lock O-ring lubricated.

3. IC-2 personnel access air lock 0-ring lubricated and linkage repaired.

4. RO-04008 P-38A auxiliary feedwater pump mini-recirculation orifice elbow, pipe, flow tap tube and valve replaced.

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m DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 DATE 05/05/99 COMPLETED BY M. B. Koudelka TELEPliONE 920/755-6480 The daily power average for Unit 2 during April,1999, was 513.6 MWe.

The following Licensee Event Report (LER) was submitted to the NRC during April,1999:

LER 301/99-002-00, Red Channel of Steam Generator Pressure Indication Passes Through Fire 7ene.

Safety-related maintenance included:

1. 2CV-00204A IIX-3A&B non-regen heat exchanger inlet valve stem replaced.

2. 2DY-03 white 125 VDC/120 VAC inverter capacitors replaced and voltage adjusted.

3. 2MS-00268 liX-1B steam generator blowdown line drain valve replaced.

4. 2MS-02015 tiX-1B steam generator header atmospheric steam dump control valve trim assembly replaced.

5. 2RC-00523A R-1 reactor vessel level indicator overpressure protection relief valve installed.

6. 2RC-00529 T-2 pressure relief tank reactor makeup water inlet check valve canopy seal ring installed.

7. 2RC-00537 RC-5003&K reactor vessel LT-447/447A thermal relief valve installed.

8. 2RC-00545D IIX-1 A steam generator cold leg channelhead vent overpressure protection relief valve installed.

9. 2RC-00546D llX-1B steam generator hot leg channelhead vent overpressure protection relief valve installed.

10. 2RC-00547D liX-I A steam generator hot leg channelhead vent overpressure protection relief valve installed.

I1. 2RC-00548D liX-1B steam generator cold leg channelhead vent overpressure protection relief valve installed.

12. 2Ril-00720 residual heat removal return to reactor coolant system valve seal weld perfoimed.

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