ML20094S324
| ML20094S324 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/31/1984 |
| From: | Fay C, Krause C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| NUDOCS 8408210232 | |
| Download: ML20094S324 (10) | |
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.1 UNIT NAME Point Beach Unit 1 DATE August 8, 1984 COMPLETED BY C.
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Krause-TELEPHONE 414/277-2001 AVERAGE DAILY UNIT POWER LEVEL MONTH July, 1984
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AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. '50-266 UNIT NAME Point Beach Uniti.1 DATE August 8, 1984 REPORT MONTH July, 1984 COMPLETED BY C.
W.
Krause TELEPHONE 414/277-2001.
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1 N/A XX ELECOB Unit shutdown to perform in con-tainment maintenance on the reactor.
coolant loose parts monitoring sys-tem.
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F: Forced Reason:
Method:
Exhibit G-Instruc-S: Scheduled A-Equipment Failure (explain) l-Manual tions for Prepar-B-Maintenance or Test 2-Manual Scram ation of Data Entry
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C-Refueling 3-Automatic Scram Sheets for LER File D-Regulatory Restriction 4-Other (explain)
E-Operator Training & License Exam F-Administrative 5 Exhibit I-Same AD-28B G-Operational Error (explain)
Source (01-78)
H-Other (explain) j
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. During the period, Chemistry had determined that there is a potential detectable (<0.1 gallons per day) primary-to-secondary leak rate in the Unit 1 steam generators by one method of analysis (rad gas ratio).
Chemistry is monitoring air ejector rad gas and primary-to-secondary leakage is holding at a detectable rate.
On July 18, 1984, a small fire occurred in the Health Physics laundry area.
The fire was the result of an obstructed solenoid drain valve on a washer.
The fire brigade mustered and disconnected the power supply and the fire extinguished.
The solenoid valve was replaced and the washer was declared operational.
g On July 31, 1984, a manual turbine runback to 94% was initiated after a feedwater heater bypass valve control circuit breaker trip.
The breaker was tripped by contract personnel during a control room modification to install the auxiliary safety instru-montation panel.
The breaker was closed and the unit was returned to full power.
On July 2, the periodic containment tendon surveillance program began.
One wire is being removed from each of 3 tendons to be destructively tested.
Other safety-related maintenance included work on the blowdown evaporator reboiler, completion of modifications to the auxiliary feedwater motor-operated valves, and a security system computer software upgrade to include fire doors.
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DOCKET NO.
50-301 UNIT NAME Point Beach Unit 2 DATE August 8, 1984' COMPLETED BY ' C. W.
Krause TELEPHONE 414/277-2001 AVERAGE DAILY UNIT POWER LEVEL MONTH July,-1984 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1
462 11 494 21 494 2
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NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE Docket No.
50-266 Unit Name Point Beach Unit 1 Date August 8, 1984 Completed By C. W. Krause Telephone 414/277-2001 Unit 1 operated at approximately 498 MWe net throughout the period with one significant load reduction.
On July 21, 1984, at 0223 hours0.00258 days <br />0.0619 hours <br />3.687169e-4 weeks <br />8.48515e-5 months <br />, the unit was taken off line to clean 19 blocked incore thimbles in the containment.
When the system was returned to service, 12 of the 19 thimbles operated without blockage.
During the 21 1/2-hour outage, the cabling for the reactor coolant system loose parts monitoring system between 6 sensors and the preamps was replaced.
The system is now operating satisfactorily.
Also completed during the outage was the rep]acement of a coupling upstream of the "A" reactor coolant pump seal water bypass orifice and the replacement of a solenoid operator to letdown orifice valve 1-200A.
Af ter maintenance was completed, the reactor was taken critical at 1923 hours0.0223 days <br />0.534 hours <br />0.00318 weeks <br />7.317015e-4 months <br /> and Unit 1 returned on line at 2354 hours0.0272 days <br />0.654 hours <br />0.00389 weeks <br />8.95697e-4 months <br />.
The reactor protection system actuated twice while the reactor was suberitical during the outage.
First, at 0417 hours0.00483 days <br />0.116 hours <br />6.894841e-4 weeks <br />1.586685e-4 months <br /> on July 21, 1984, the reactor tripped on source range Channel 32 high flux when the source range detectors were energized.
I&C is investi-gating the possible failure of the source range detector.
- Second, at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />, the reactor tripped again due to switching the turbine first stage pressure channel to " test" for maintenance work.
Putting the channel to " test" unblocked nwer trip setpoints and the reactor tripped on low pressurizer pressure.
Both of these subcritical reactor protection actuations are considered reportable under Licensee Event Report rules.
At 0247 hours0.00286 days <br />0.0686 hours <br />4.083995e-4 weeks <br />9.39835e-5 months <br /> on July 11, 1984, there was a Tref step change of 7'F on Unit 1 which resulted in an automatic control rod in-sortion.
The control rods were shifted to manual and Unit 1 was maintained at full power.
The step change was caused by failure of the Tref controller high limiter.
The Tref controller high limiter was repaired and returned to service.
This event was not considered reportable.
During monthly surveillance testing, I&C found that a fuse for the bistable for Unit 1 power-operated relief valve 430 had failed.
The relief valve would not have opened on a high pressure signal due to this failure.
The redundant valve, PORV-431C was operational throughout the period.
This event was not considered reportable.
I
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NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE Docket No.
50-301 Unit Name Point Beach Unit 2 Date August 8, 1984 Completed By C. W. Krause Telephone 414/277-2001 Unit 2 operated at approximately 493 MWe net throughout the entire period with no significant load reductions.
Primary-to-secondary leakage remains at less than 10 gallons per day.
During the period, Operations has been closely monitoring containment sump levels along with containment air monitors in an investigation regarding a potential reactor vessel head area leak.
Safety-related maintenance performed during the period included work on charging pump 2P2B varidrive system.
A number of containment tendons were inspected in situ during the periodic surveillance program.
Also during the period, construction began on the modifi-cation to install an auxiliary safety instrumentation panel in the control room.
y
>Hscomun Electnc ma cwnur 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE WI 53201 August 10, 1984 Director of Regulatory Operations U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Gentlemen:
MONTHLY OPERATING REPORTS POINT BEACH NUCLEAR PLANT Attached are monthly operating reports for Units 1 and 2, Point Beach Nuclear Plant, for the calendar month of July 1984.
Very truly yours,
[M C
Vice Presid nt-Nuclear Power C. W.
Fay Attachments Copics to J. G. Keppler - NRC, Region III NRC Resident Inspector C. F. Riederer - PSCW In A4 I}l