ML20113A364
| ML20113A364 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/31/1984 |
| From: | Fay C, Krouse C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC |
| References | |
| NUDOCS 8501210079 | |
| Download: ML20113A364 (10) | |
Text
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".. O OPERATING DATA REPORT
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DOCKET NO. 50-266' 1
l DATE January 7,.1985 COMPLETED BY C. W. KRAUSE TELEPHONE 414 277 2001 t
OPERATING-STATUS
- 1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 1
. NOTES
- 2. REPORTING PERIOD: DECEMBER 1984
- 3. LICENSED THERMAL PCWER.(MUT): 1518.
-4.
NAMEPLATE RATING (GROSS MWE):
523.8
- 5. DESIGN ELECTRICAL RATING (NET MWE): 497.
- 6. MAXIMUH DEPENDABLE CAPACITY (GROSS MWE): 509.
-J
- 7. HAXIMUM DEPENDABLE CAPACITY (NET MUE): 485.
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
NOT-APPLICABLE 1
9.' POWER LEVEL TO UHICH RESTRICTED, IF ANY (HET.MWE): NOT APPLICABLE
- 10. REASONS FOR_ RESTRICTIONS, (IF ANY): NOT APPLICABLE q
THIS MONTH YR TO DATE CUMUL4TIVE
- 11. HOURS IN REPORTING PERIOD 744
-8,784 124,080
.12. NUMBER 0F HOURS REACTOR WAS CRITICAL 744.0 6,420.1.
100,498.6
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 4.3 629.7
- 14. HOURS GENERATOR ON LINE' 744.0 6,380.0 97,987.5
- 16. GROSS THERMAL: ENERGY GENERATED.(MWH)
- 9.0 802.5 0.0
- 15.' UNIT RESERVE SHUTDOWN HOURS 1,114,177 9,413,665 132,948,977-
- 17. GROSS' ELECTRICAL ENERGY GENERATED (MWH) 383,560 3,249,260 44,645,240
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 368,208 3,103,714 42,466,148
- 19. UNIT' SERVICE FACTOR 100.0 72.6 79.0
- 20. UNIT AVAILABILITY. FACTOR:
100.0 72.7 79.6
- 21. UNIT CAPACITY, FACTOR (USING MDC. NET) 102.0 72.9 70.0,
.22.. UNIT CAPACITY FACTOR (USING DER' NET) 99.6, 71.1 68.9.
- 23. UNIT FORCED OUTAGE RATE' O.0 0.0 2.5
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS-(TYPE,.DATE, AND DURATION OF.EACH):
Annual refueling outage scheduled. to comunence April 5,1985.
25.'IF SHUTDOWN AT END OF REPORT. PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUTDOWN 85012 0079 841231 I
K05000g DR A DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977
DOCKET NO.
50-266 UNIT NAME Point Beach Unit 1-DATE January 7, 1985 COMPLETED BY C. W. Krause TELEPHONE 414/277-2001 l
AVERAGE DAILY UNIT POWER LEVEL MONTH December, 1984 AVERAGE-AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1
500-11 503 21 501 2
467 12 499 22 497 3
501 13 499 23 498 4
499 14 502-24 497-t 5
505 15 501 25 487 6
503 16 502 26 464 504 17 502 27 484 l
7 I-503 18 503 28 488 i
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504 19 501 29 444 l
9 10 20 501 30 484 501 31 498 EQR-28a (01-79)
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-NARRATIVE
SUMMARY
-OF OPERATING EXPERIENCE Docket No.:
50-266
' Unit Name:
Point Beach Unit 1 Date:
January 7, 1985 Completed By:
C. W. Krause
. Telephone:
414/277-2001 Unit 1-operated at approximately 500 MWe net throughout the period with-no significant load reductions.
The primary-to-secondary leakage' remains less-than 10 gallons per day.
On December 7, 1984, a Unit 1 containment spray header hydraulic snubber (1HS-16) was. discovered leaking fluid during a Unit 1 containment inspection.
At 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> that day, a 72-hour Limiting Condition for Operation (LCO) was initiated.
The snubber'was removed, tested and found to be, in fact, operable.
Maintenance replaced seals on the snubber reservoir while the unit was at power.
The snubber was returned to service at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on December 10, 1984; thus ending the 72-hour LCO.
On December 17, 1984, a 9 gpm' calculated leak in the LUnit 1 charging line was indicated by a sudden ?_.el drop in the' volume. control tank.
Operators discovered the suction drain valve for the Unit 1 "A" charging pump slightly open due-to stem _ nut mispositioning.
The valve was tightened shut and the leak ceased.
Maintenance work completed during the period included repairs to boric acid heat tracing circuit and repairs to individual rod position indicator.F8.
Modification work completed during the~ period included the startup of the indicators on the Unit 1 auxiliary safety instrumentation panel; Also during the period, initial licensin'g' exams.were administered to 4 Reactor Operator candidates and'2. Senior-Reactor Operator certificate candidates.. Thej2 certificate
. candidates received passing grades, while the exam results
.for the Reactor Operator candidates are still under evalu-ation.
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~0PERATING BATA REPORT
.c DOCKET NO.'50-301
~
l DATE January 7, 1985 J
COMPLETED BY' C. W. KRAUSE
-j TELEPHONE 414 277 2001 OPERATING STATUS;
.1. UNIT NAME: ' POINT BEACH NUCLEAR PLANT UNIT 2'
. NOTES
- 2. REPORTING PERIOD: DECEMBER 1984
. 3. LICENSED : THERMAL POWER (MUT): :1518.
- 4. NAMEPLATE RATING (GROSS MWE):
523.8
- 5. DESIGN ELECTRICAL RATING:(NET MWE): 497.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MUE): 509.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET.MUE): 485.
- 8. IF. CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) _SINCE LAST REPORT, DIVE PEASONS:
NOT APPLICABLE
'9.. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE): NOT APPLICABLE-10.-REASONS FOR RESTRICTIONS, (IF ANY): NOT APPLICABLE q
Tl:IS MONTH YR T0 DATE CUMULATIVE l
- 11. HOURS IN REPORTING PERIOD 744 8,784 108,865
]
12.1 NUMBER OF. HOURS REACTOR WAS CRITICAL 744.0 7,544.2 95,972.4 i
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 8.8 207.1
- 14. HOURS GENERATOR ON LINE.
739.0 7,406.6 94,309.4 315. UNIT RESERVE SHUTDOWN HOURS 0.0 15.4 198.1
- 16. GROSS-THERMAL ENERGY GENERATED (MWH) 1,062,541 10,858,195 131,752,972
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 364,450 3,680,310 44,640,140
- 18. NET ELECTRICAL' ENERGY GENERATED (MWH)'
348,628 3,510,805 42,511,405
- 19. UNIT SERVICE FACTOR 99.3 84.3 86.6
- 20. LINIT.' AVAILABILITY FACTOR' 99.3 84.5 86.8 L
- 21. UNIT CAPACITY FAL7Gl..(USING MDC NET)'
96.6 82.4 79.5 94.3 80.4 78.6
- 22. UNITECAPACITY' FACTOR (USING DER NET)
-23. UNIT FORCED DUTAGE RATE 0.7 0.1 1.3 1
24.. SHUTDOWNS SCHEDULED 0VER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
NONE
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUTDOWN r-DATA REPORTED'AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER' DATED SEPTEMBER 22, 1977
DOCKET NO.
50-301 UNIT NAME Point Beach Unit'2 DATE-January 7, 1985 COMPLETED BY C.
W.
Krause TELEPHONE 414/277-2001 AVERAGE DAILY UNIT POWER LEVEL MONTH December, 1984 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DA'l MWe NET DAY MWe NET DAY MWe NET l'
498 11 426 21 487 2
498 12 332 22 481 3
498 13 494 23 484 4
496 14 495 24 423
'5 500 15 496 25 362 6
499 16 452 26 419 7
500
_17 483 27 452
-8 501 18 493 28 414 9
493 19 493 29 439 10 499 20 493 30 438 31 487 2
EQR-28a
-(01-79).
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-301 UNIT NAME Point Beach Unit 2-DATE January 7, 1985 REPORT MONTH December, 1984 COMPLETED BY C.-W.
Krause TELEPHONE 414/277-2001 m
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oO 5
841211 F
5.0 B
1 N/A ZZ SUPORT Perform preventive maintenance on reactor coolant system "A" hot leg hydraulic support 2HS-22.
I 3
4 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 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 (e < plain)
Source (01-78)
H-Other (explain)
~
_ NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE-Docket.No.:
50-301 Unit Name:
Point Beach Unit 2~
Date:
January 7, 1985 Completed By:
C. W. Krause Telephone:
414/277-2001 Unit 2 operated at approximately 497 MWe net throughout the period with one significant load reduction.
On December 11, 1984, fluid from "A" hot leg hydraulic snubber (2HS-22) was discovered on El. 10' during the Unit 2 containment inspection.
Since this snubber is not accessible while the unit is at power, a short shutdown was planned and a 72-Hour Limiting Condition for Operation (LCO) was initiated.
The generator was taken off line at 2223 hours0.0257 days <br />0.618 hours <br />0.00368 weeks <br />8.458515e-4 months <br /> and an identical snubber (2HS-21), which is accessible, was exchanged with 2HS-22.
Unit 2 generator was placed on line at 1525 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.802625e-4 months <br /> on December 12, 1984, and the unit returned to full power.
Test results on snubber 2HS-22 indicated that at the time of removal operability requirements had been met.
The primary-to-secondary leakage remains less than 10 gallons per day.
Chi December 3, 1984, a confirming sample drawn from "C" boric acid storage tank indicated that boric acid solution was below Technical Specification limits (by approximately 0.1%).. Unit 2 safety injection and chemical and volume control systems were shifted to take suction from the "B"
storage tank.
Further investigations revealed'a now reactor makeup water isolation valve had leaked by about 200 gallons over 2 weeks and caused the dilution in the "C" tank.
The event was not considered reportable, however, the NRC Senior Resident Inspector was notified.
On December 8, 1984, at 2005 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br />, the plant experienced an unscheduled release of 80 gallons of slightly radioactive effluent via the Unit 2 facade sump. The source of the release was determined to be blowdown evaporator distillate.
The bag filter for the evaporator building was plugged causing distillate to divert to a facade sump drain.
Chemistry samples of the sump effluent indicated that the release vas 0.1% of the maximum permissible concentration allowed by' Technical Specifications.
This event was not considered reportable.
^
Maintenance work completed included the: reinstallation of 2PllA component cooling pump, the replacement of the Unit "C" charging pump motor, exchanging of the "B"' hot leg:resis-
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tance temperature detector with the installed spare, replacement of current / pressure (I/P) transducer cn main 1 feed regulating valve bypass valve 2-480, and maintenanceito main, feed regulating valve operator 2-466.
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- 231 W. MICHIGAN, P.O. 00X 2046, MILWAUKEE WI 53201 January 10, 1985 Director of Regulatory Operations U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Gentlemen:
$10NTHLY 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 December 1984.
Very truly yours, J'
Vice Pre ident-Nuclear Power C. W. Fay Attachments Copies to J. G. Keppler - NRC,' Region III NRC Resident Inspector R. S. Cullen - PSCW 4
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