ML20155B707
| ML20155B707 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/31/1988 |
| From: | Fay C, Krause C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CON-NRC-88-052, CON-NRC-88-52 VPNPD-88-317, NUDOCS 8806130305 | |
| Download: ML20155B707 (9) | |
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DOCKET NO.
50--266 UNIT NAME Point Beach, Unit'1' DATE June 6,'1988 COMPLETED BY C. W.
Krause TELEPHONE 414/221-2001 AVERAGE DAILY UNIT POWER LEVEL MONTH MAY 1988 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL' DAY MWe NET DAY MWe NET DAY MWe NET 1
-2 11
-3 21 102 2
-2 12
-10 22 250' 3
-1 13
-7 23 461 4
0 14
-8 24 497 5
0 15
-9 25 499-6
-2 16
-9 26 498 7
-2 17
-11 27 500 8
-2 18
-13 28 501 9
-3 19
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-6 20 27
.30 502 31 502 EQR-28a (04-86)
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-266-UNIT NAME Point Beach Unit 1 -:
DATE June 6, 1988 REPORT MONTH MAY 1988 COMPLETED BY C.
W.
Krause.
TELEPHONE 414/221-2001 5o 4
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Forced 2 Reason:
3 Method:
4 Exhibit G-Instructions S:
Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of 4
B - Maintenance or Test 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 Exhibit I-Same Source F - Administrative 6 - Other (explain)
G - Operational Error (explain) j H - Other (explain)
EQR-28B l
(06-86)
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NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE Docket No.
50-266 Unit Name Point Beach Unit 1 Date June 6, 1988 Completed By C.-W.
Krause Telephone 414/221-2001 Unit 1 was in the process of recovering from its annual refueling outage, with the primary coolant system drained to the 3/4 pipe level at the start of the month.
On May 10, following the start of the "B" reactor coolant pump, Operations personnel received an alarm indicating that' pressurizer power operated relief valve, PCV-430, was not fully closed.
The relief valve apparently lifted due to the pressure transient from starting the "B" pump.
The valve reseated and there was no visible indication of discharged primary coolant to the pressurizer relief tank.
A significant operating event report will be written to document
-the event.
On May 15, a steam leak from steam generator feed isolation check valve, CS-476BB, was noted while inspecting containment isolation valves during the primary leak test.
The unit was returned to cold shutdown and repairs to the valve were completed on May 16.
Primary system heatup recommenced and the reactor was critical on May 18.
The unit was placed on line at 1400 on May 20, and was taken off line for 36 minutes on May 21 for an overspeed test of the main turbine.
Following the test, power was ramped to 30% and held for chemistry concerns until 0150 on May 22.
During the ramp up to full power on May 23, rod position indicators for assemblies G-7 and C-7 were declared inoperable due to apparent misalignment with their bank position indications.
As required by Technical Specifications, power was held at less than 75% while hot channel factors were analyzed.
The analysis results indicated that design limits would not be exceeded and the ramp up to full power was recommenced.
The unit achieved full power at 1330 on May 23.
There were no significant load reductions throughout the remainder of the period.
Safety related maintenance performed during the period included renewing the containment liner plate expansion joints, replacement of several reactor protection safeguards relays, and 1-repairs to pressurizer power operated relief valve, PCV-431C, and its hand controller.
Also, work was completed on replacing EQ splices for 21 solenoid-operated containment isolation valves.
On May 16, LER 88-004, "Containment Isolation Valve Leakage In Excess of Technical Specification Limits" was issued.
The circumstances of this event were discussed in the April, 1988, monthly report.
The April monthly report also stated that l
LER 88-005 would be issued for the purge supply and exhaust valves auto-close trip test failure that occurred on April 28.
Further evaluation of the event indicated that it is not reportable as an LER.
Instead, a significant operating event report will be written.
OPERATING DATA REPORT DOCKET NO. 50-301 DATE June 6, 1988 COMPLETED BY C. U. KRAUSE TELEPHONE 414 221 2001 OPERATING STATUS
- 1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 2
. NOTES
- 2. REPORTING PERIOD:
MAY 1988
- 3. LICENSED THERMAL POUER (MUT): 1518.
- 4. NAMEPLATE RATING (GROSS MUE):
523.8
- 5. DESIGN ELECTRICAL RATING (NET MUE): 497.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MUE): 50?.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MUE): 485.
- 8. IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
NOT APPLICABLE
- 9. POWER LEVEL TO UHICH RESTRICTED. IF ANY (NET MUE): NOT APPLICABLE
- 10. REASONS FOR PESTRICTIDHS, (IF ANY): NOT APPLICABLE THIS MONTH YR TO DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744 3.647 138.792
- 12. NUMBER OF HOURS REACTOR UAS CRITICAL 744.0 3.627.6 122.022.0
- 13. REACTOR RESERVE SHUTDOUN HOURS 0.0 1.1 216.1
- 14. HOURS GENERATOR ON LINE 744.0 3,584.2 120.054.3
- 15. UNIT RESERVE SHUTDOUN HOURS 0.0 5.0 297.4
- 16. GROSS THERMAL ENERGY GENERATED (MUH) 1,127.476 5.383.218 169,953,813
- 17. GROSS ELECTRICAL ENERGY GENERATED (MUH) 384.230 1,841,660 57,621,880
- 18. NET ELECTRICAL ENERGY GENERATED (MUH) 367.122 1.760,604 54.896.347
- 19. UNIT SERVICE FACTOR 100.0 98.3 86.5
- 20. UNIT AVAILAPILITY FACTOR 100.0 98.4 86.7
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 101.7 99.5 80.7
- 22. UNIT CAPACITY FACTOR (USING DER NET) 99.3 97.1 79.6
- 23. UNIT FORCED OUTAGE RATE 0.0 0.7 1.2
- 24. SHUTDOUNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):
Seven-week refueling outage to begin on October 8, 1988.
- 25. IF SHUTDOUN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP: NOT SHUTDOWN DATA REPORTED AND FACTORS CALCULATED AS REDUESTED IN NRC LETTER DATED SEPTEMBER 22. 1977
- c.. :1 DOCKET NO.
50-301-o UNIT NAME Point Beach, Unit 2 DATE June 6, 1988 COMPLETED BY C.
W. Krause TELEPHONE 414/221-2001 AVERAGE DAILY UNIT POWER LEVEL MONTH MAY 1988 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL l
DAY MWe NET DAY MWe NET DAY MWe NET
.I' 1
495 11 494 21 495 i
2 494 12 494 22 493 3
494 13 493 23 495 4
492 14 495 24 489 5
493 15 496 25 492 6
493 16 495 26 496 l
7 494 17 494 27 495 8
494 18 493 28 496 9
472 19 495 29 495 I
10 494 20 491 30 495
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NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE
. Docket No.
50-301 Unit Name Point Beach Unit 2 Date June 6, 1988 Completed By C. W.
Krause Telephone 414/221-2001 Unit 2 operated throughout the period at approximately 495 MWe net with no significant reductions in load.
There was no major safety related maintenance performed on the unit during the period and no LERs were issued.
F
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Wisconsin Electnc POWER COMPANY 231 W Mcho:n Po. Box 204 M.hohee.W 53201 M14) 2212345 VPNPD-88-317 NRC-88-052 June 10, 1988 U.
S. NUCLEAR REGULATORY COMMISSION Document Control Desk Washington, D.
C.
20555 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, Point Beach Nuclear Plant, for the calendar month of May 1988.
Very truly yours,
/
J C. W.
Fay Vice President Nuclear Power Attachments Copies to R.
S.
Cullen, PSCW NRC Regional Administrater, 9,egt.on III NRC Resident Inspector l
.~,ou-an c,-u
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