ML20074A874
| ML20074A874 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/09/1983 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20074A873 | List: |
| References | |
| NUDOCS 8305160171 | |
| Download: ML20074A874 (9) | |
Text
. _. _ _ - - - _ _ _ _ _ - _ _ _ ______ __ _ __.-.-_ - _ - - ___ -- __- _
- UTCD E8 B5 OPERATING DATA REPORT lp:3 DOCKET NO. 50-266 O
88 7 DATE May 9, 1983 ina3 COMPLETED BY C. W. FAY EN TELEPHONE 414 277 2811 OPERATING STATUS
- 1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 1
. NOTES
- 2. REPORTING PERIOD:
APRIL 1983
- 3. LICENSED THERMAL POWER (MWT): 1518.
- 4. NAMEPLATE RATING (GROSS MUE):
'523.8
- 5. DESIGN ELECTRICAL RATING (NET MWE): 497.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 519.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 495.
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
NOT APPLICABLE
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MUE):
390.0
- 10. REASONS FOR RESTRICTIONS, (IF ANY): Power level restricted becauce of self-imposed hot leg limitation in an attempt to limit steam generator tube corrosion.
THIS MONTH YR TO DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 719 2,879 109,415
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 719.0 2,830.6 90,402.9
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 1.4 625.4
- 14. HOURS GENERATOR ON LINE 719.0 2,823.9 87,932.2
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 793.5
- 16. GROSS THERMAL ENERGY GENERATED (MUH) 840,721 3,288,526 119,237,515
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 281,740 1,094,480 39,972,270
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 267,116 1,039,072 38,020,790
- 19. UNIT SERVICE FACTOR 100.0 98.1 80.4
- 20. UNIT AVAILABILITY FACTOR 100.0 98.1 81.1
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 75.1 72.9 71.1
- 22. 'JNIT CAPACITY FACTOR (USING DER NET) 74.8 72.6 69.9
- 23. UNIT FORCED OUTAGE RATE 0.0 0.2 2.7
- 24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Twenty-six week refueling and steam generator replacement outage scheduled to commence September 30, 1983.
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STAR 10P: NOT SHUTDOWN DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LEITER DATED SEPTEMBER 22, 1977
DOCKET NOo 50-266 UNIT NAME Point Beach Unit 1 DATE May 9, 1983 COMPLETED BY C.
W.
Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL 1
MONTH Aoril, 1983 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1
372 11 371 21 371 2
374 12 373 22 371 3
371 13 371 23 372 4
373 14 372 24 373 4
5 372 15 372 25 372 6
373 16 371 26 372 j
7 373 17 372 27 371 8
373 18 371 28 372 9
372 19 372 29 371 10 359 20 371 30 372 31 AD-28A (1-77)
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NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE Docket No.
50-266 Unit Name Point Beach Unit 1 Date May 9, 1983 Completed By C. W.
Fay Phone 414/277-2811 Unit 1 operated at approximately 371 MWe net throughout the period with no major load reductions.
The primary-to-secondary leakage remains stable at less than ten gallons per day.
On April 5, 1983 at 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br /> the fire detection system for the north half of the cable spreading room was found inoperable.
At 1219 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.638295e-4 months <br /> the system was restored and put back in operation.
At approximately 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br /> on April 6, 1983 contractor personnel inadvertently tripped three circuit breakers inside of control panel C01 while setting up to pull wires to complete NRC-mandated fire protection backfits.
Unit 1 received a common critical control power failure alarm as control room personnel heard molded circuit breakers trip.
Breakers involved were Nos. 151, 152, and 153 which power valve 1CV-3200B, 1B04-86 lockout relay, and 4D emergency diesel fuel tank level control.
The breakers were immediately reset and the control board returned to normal.
This event was regarded as reportable under Technical Specification 15.6.9.2.A.6.
e-
OPERATING DATA REPORT DOCKET NO. 50-301 j
DATE May 9, 1983 COMPLETED BY C. W. FAY TELEPHONE 414 277 2811 OPERATING STATUS
- 1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 2
. NOTES
- 2. REPORTING PERIOD:
APRIL 1983
- 3. LICENSED THERMAL POWER (MWT): 1518.
- 4. NAMEPLATE RATING (GROSS MWE):
523.8
- 5. DESIGN ELECTRICAL RATING (NET MUE): 497.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 519.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MUE): 495.
- 8. IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
NOT APPLICABLE
- 9. POWER LEVEL TO UNICH RESTRICTED, IF ANY (NET MUE): NOT APPLICABLE
- 10. REASONS FOR RESTRICTIONS, (IF ANY): NOT APPLICABLE THIS MONTH YR TO DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 719 2,879 94,200
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 2,003.6 84,061.7
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 196.8
- 14. HOURS GENERATOR ON LINE 0.0 1.992.9 82,648.1
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 181.2
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0 3,007,255 114,522,849
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0 1,009,260 38,810,660
- 18. NET ELECTRICAL ENERGY GENERATED (MUH) 0 963,699 36,952,666
- 19. UNIT SERVICE FACTOR 0.3 69.2 87.7
- 20. UNIT AVAILABILITY FACTOR 0.0 69.2 87.9
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 67.6 79.8
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 67.4 78.9
- 23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.5
- 24. SHUTDOWNS SCHEDULED DVER NEXT 4 MONTHS (TYPE, DATE, AND DURATION OF EACH):
1 NONE
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: JUNE 30, 1983 DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977
DOCKET NO.
50-301 NIT NAME Point Beach Unit 2 l
DATE May 9, 1983 COMPLETED BY C.
W.
Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH April, 1983 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1
-2 11
-2 21
-2 2
-2 12
-2 22
-2 I
3
-2 13
-2 23
-2 i
4
-2 14 1*
24
-2 I
5
-2 15
-2 25
-2 6
-2 16
-2 26
-2 7
-2 17
-2 27
-2 8
-2 18
-2 28
-2 9
-2 19
-2 29
-2 10
-2 20
-2 30
-2 31
- Erroneous results due to unexplained meter change caused by relay testing.
AD-28A (1-77)
UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 DATE May 9, 1983 REPORT MONTH April, 1983 COMPLETED BY C. W.
Fay TELEPilONE 414/277-2811 en 4
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om e
ya Report No.
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830325 S
719 C
1 N/A ZZ 3ZZZZZ Completed Week 6 of the continuina 14-week refueling and steam genera-tor sleeving outage.
I F: Forced Reason:
3 4
Method:
Exhibit G-Instruc-S: Scheduled A-Equipment Failure (explain) l-Manual tions for Prepar-l B-Maintenance or Test 2-Manual Scram ation of Data Entry l
C-Refueling 3-Automatic Scram Sheets for LER File D-Regulatory Restriction 4-Other (explain)
E-Operator Training & License Exam F-Administrative 5
! AD-28B Exhibit I-Same G-Operational Error (explain)
Source (01-78) l II-Other (explain)
NARRATIVE
SUMMARY
OF OPERATING EXPERh ICE Docket No.
50-301 Unit Name Point Beach Unit 2 Date May 9, 1983 Completed By C. W. Fay Phone 414/277-2811 Unit 2 was shut down during the entire report period as it completed the sixth week of the scheduled 14-week refueling and steam generator sleeving outage.
Outage-related work included the removal of "A",
"B",
and "C" moisture separator reheater tube bundles for changeout, the removel of 4A and 4B feedwater heaters for changeout, the rebuilding of "A" reactor coolant pump, the commencement of safeguards relay changeouts, reconditioning of the "C" component cooling water heat exchanger, and the changeout and overhaul of both low-pressure turbine rotors.
Research and repairs are under way regarding the steam erosion experienced in turbine casings and steam piping.
Inspection and minor repairs were initiated on residual heat removal valves 2MOV-700 and 2MOV-701 and to reactor temperature detection manifold isolation valves 2RC-559A and 2RC-559B.
While performing refueling leakage tests of containment isolation valves on April 9, 1983, the "A" reactor coolant pump component cooling water supply containment isolation valve (755A) was found to have leakage such that the limit in Technical Specification 15.4.4.III.B may have been exceeded.
During the initial phase of the type "C" test, pressurization of the test volume to the required test pressure could not be achieved.
Upon failing to obtain test pressure, it was noted that the subject valve was leaking as evidenced by the flow of air through a test connection used to provide a leakage flow path.
At this time, prior to obtaining a leakage rate reading, the testing personnel tapped on the subject valve in an attempt to seat it.
The attempt was successful as no signs of air flow through the leakage path was then evident.
This action by testing personnel prevented the meaningful quantification of the as-found leakage.
This event is reportable in accordance with Technical Specification 15.6.9.2.A.3,
" Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment."
Three relays which provide undervoltage protection to safeguards switchgear 2A05 and 2A06 were discovered out of Technical Specification tolerances during testing.
A 30-day Licensee Event Report will be filed with the NRC. _
r
. On April 28, 1983 it was evaluated that valve 559A, "A"
loop RTD bypass manifold valve isolation valve, body-to-bonnet studs were found degraded due to corrosion and constituted an abnormal degradation of the RCS boundary.
During performance of refueling outage activities, a higher than normal contamination of an area in close proximity to the valve was noted.
An investigation by Maintenance personnel as to the possible cause of the contamination found the valve with signs of body-to-bonnet leakage.
Four of twelve studs were found corroded and are undergoing further evaluation.
All studs will be replaced and the similar valve in the other loop has been inspected with no degradation found.
This has been reported in accordance with' Technical Specification 15.6.9.A.3.
During the period, Health Physics took added precautions as an iodine airborne problem became evident after the reactor vessel head was removed and the core was unloaded.
During the period, eddy current testing and a secondary-to-primary leak check was completed in the steam generators.
The leak check revealed three explosive plugs which appeared wet and three tubes which were dripping or wet in the "A" steam generator and one explosive plug and three tubes which appeared wet in the "B"
Eddy current testing data revealed 16 tubes with indications of >40% repair limit in the "A"
steam generator and two tubes with indications >40% in the "B"
Degraded tubes will be repaired either by sleeving or mechanical plugging and degraded plugs will be weld repaired.
The NRC was notified of the tube degradation with Licensee Event Report No. 83-002/0lT-0.
Additionally, the sleeving program scheduled during this outage, designed to prevent further steam generator tube degradation, is well under way with approximately 54% of the work-completed in the "B" steam generator.