ML20099E471
| ML20099E471 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/31/1984 |
| From: | Fay C, Krause C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC |
| References | |
| NUDOCS 8411210323 | |
| Download: ML20099E471 (10) | |
Text
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-%g OPERATING DATA REPORT DOCKET NO. 50-266 DATE November 7, 1984 COMPLETED BY C. U. KRAUSE TELEPHONE 414 277 2001 OPERATING STATUS
- 1. UNIT NAME: POINT BEACH huCLEAR PLANT UNIT 1
. NOTES
- 2. REPORTING PERIOD:
OCTOBER 1984
- 3. LICENSED THERMAL POWER (MWT): 1518.
- 4. NAMEPLATE RATING (GROSS MWE):
523.8
- 5. DESIGN ELECTRICAL RATING (NET MWE): 497.
l
- 6. MAXIMUM DEPEN 9ABLE CAPACITY (GROSS MWE): 509.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 485.
B. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVF REASONS:
NOT APPLICABLE
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE): NOT APPLICABLE
- 10. REASONS FOR RESTRICTIONS, (IF ANY): NOT APPLICABLE THIS MONTH YR TO DATE CUMULATIVE D
KO O
66 R
- 11. HOURS IN REPORTING PERIOD 745 7,320 122,616
- 12. NUMBER.0F HOURS REACTOR WAS CRITICAL 745.0 4,956.1 99,034.6
- 13. REACTOR RESERVE SHUTDOWN HOURS o.0 4.3 629.7
- 14. HOURS GENERATOR ON LINE 745.0 4,916.0 96,523.5
- 15. UNIT RESERVE SHUIDOWN HOURS 0.0 9.0 802.5
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,114,168 7,217,132 130,752,444
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 384,780 2,491,490 43,887,470
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 368,508 2,376,888 41,739,322
- 19. UNIT SERVICE FACTOR 100.0 67.2 78.7
- 20. UNIT AVAILABILITY FACTOR 100.0 67.3 79.4
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 102.0 67.0 69.6
- 22. L' NIT CAPACITY FACTOR (USING DER NET) 99.5 65.2 68.5
- 23. UNIT FORCED OUTAGE RATE 0.0 0.0 2.5
- 24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
- S, ga Annual refueling scheduled to commence April 19, 1985.
Xe-
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUTDOWN DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977
DOCKET NOo 50-266-UNIT NAME Point Beach Unit1"
'A DATE November 7, 1984' COMPLETED BY C. W.
Krause q
TELEPHONE 414/277-2001 AVERAGE DAILY UNIT POWER LEVEL 1
MONTH October, 1984 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1
501 11 500 21 503 2
500 12 500 22 502 3
502 13 500 23 500 4
500 14 502 24 502 5
314 15 500 25 502-6 500 16 498 26 502 7
500 17 502 27 502 8
501 18 495 28 502 9
500 19 500 29 500 10 500 20 502 30 502 31-501 EQR-28a (01-79)
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266~
UNIT NAME Point Beach Unit l i DATE November 7, 19&4 REPORT MONTH October, 1984 COMPLETED BY C.
W.
Krause-TELEPHONE' 414/277-2001 m
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Date g
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- s :I:
e v.c Report No.
ca eU To Prevent Recurrence Q*
e to C O
- E:
U O
4 841005 S
0 H
4 N/A ZZ ZZZZZ2 Power reduction to maintain 345 KV system stable.during Wisconsin Public Service Corporation line outage.
^
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3 F: Forced Reason:
Method:
Exhibit G-Instruc-S: Scheduled A-Equipment Failure (explain) 1-Manual tions for Prepar-B-Maintenance or Test 2-Manual Scram ation 'of Data Entry C-Refueling 3
.7 stomatic 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)
NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE Docket No.:
50-266 Unit Name:
Point Beach Unit 1 Date:
November 7,.1984 Completed By:
C. W. Krause Telephone:
414/277-2001 Unit 1 operated at approximately 500 MWe net throughout the period with one major load reduction.
On October 5, load was re-duced to approximately 310 MWe net for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> to maintain the 345 KV system stable during a Wisconsin Public Service Corporation line outage.
Primary-to-secondary leakage remains less than 10 gallons per day.
The return of the last spent fuel assembly occurred on October 14, 1984.
This ends 14 months of spent fuel shipments from facilities in New York and Illinois to the plant.
On October 18, 1984, the Unit 1 gas stripper released approxi-mately 150 gallons of liquid via the recovery heat exchanger vent which was discovered uncapped.
Air samples taken in the area in-dicated the release was below reportable limits.
On October 19, 1984, the power supplies for the Unit 1 con-tainment air monitors were discovered full of water resultant from heavy rains leaking through the facade roof.
I&C personnel replaced the power supplies and are preparing a modification to prevent recurrence.
This event was not considered reportable.
On October 28, 1984, at 2:45 AM, control room operators received a ground fault alarm on motor control center 1B03 and a subsequent trip of IP11A component cooling water pump.
Redundant pump 1P11B automatically started to restore component cooling water system operation.
Investigations indicate that insulation on the motor windings failed and caused a fire.
The p'. ant entered a 24-hour limiting condition for operation.
Maintenance personnel replaced the failed motor with a motor from Unit 2 which was not needed and pump 1P11A returned to service and terminated the 24-hour limiting condition for operation.
Other safety-related maintenance completed during the period included the continuing work on the station battery and inverter modification, continuing work on the auxiliary safety instrumentation panel,and repair to auxiliary feedwater check valve AF-102.
OPERATING DATA REPORT DOCKET NO. 50-301 l
DATE November 7, 1984 COMPLETED BY C. W. KRAUSE TELEPHONE 414 277 2001 OPERATING STATUS
- 1. UNIT NAME: POINT BEACH NUCIEAR PLANT UNIT 2
. NOTES
- 2. REPORTING PERIOD:
OCTOBER 1984
- 3. LICENSED THERMAL POWER (MUT): 1518.
- 4. NAMEPLATE RATING (GROSS MUE):
523.8
- 5. DESIGN ELECTRICAL RATING (NET MUE): 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, 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 745 7,320 107,401
- 12. NUMBER OF HOURS REACTOR UAS CRITICAL 0.0 6,489.2 94,917.4
- 13. REACTOR RESERVE SHUIDOWN HOURS 0.0 8.8 207.1
- 14. HOURS GENERATOR ON LINE 0.0 6,417.9 93,320.7
- 15. UNIT RESERVE SHUTDCUN HOURS 0.0 15.4 198.1
- 16. GROSS THERMAL ENERGY GENERATED (MdH) 0 9,542,695 130,437,472
- 17. GROSS ELECTRICAL ENERGY GENERATED (MUH) 0 3,229,550 44,189,380
- 18. NET ELECTRICAL ENERGY GENERATED (hWH) 0 3,083,126 42,083,726
- 19. UNIT SERVICE FACTOR 0.0 87.7 86.9
- 20. UNIT AVAILABILITY FACTOR 0.0 87.9 87.1
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 86.8 79.8
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 84.7 78.8
- 23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.3
- 24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
NONE
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOVEMBER 17, 1984 DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977
DOCKET-NO.
50-301 4
UNIT NAME Point' Beach Unit 2~
DATE November 7, 1984
- ~
COMPLETED BY C. W.
Krause TELEPHONE 414/277-2001-AVERAGE DAILY UNIT POWER LEVEL MONTH Octnhor. 14R4 AVERAGE AVERAGE AVERAGE DAILY
. DAI LY, DAILY POWER LEVEL POWER LEVEL POWER LEVEL CAY MWe NET DAY MWe NET DAY MWe NET 1
-5 11
-2 21
-2 2
-2 12
-2 22
-2 3
-2 13
-2 23
-2 4
-2 14
-2 24
-2 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
-2 EQR-28a (01-79)
.)
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301' UNIT NAME Point Beach Unit'2-DATE November 7, 1984 REPORT MONT!!
October, 1984 COMPLETED BY C.
W.
Krause TELEPHONE 414/277-2001 "L
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O mae am ae No.
Date g
cg g
pgg Licensee Event gg gg Cause and Corrective Action e
p=
e v.c Report No.
m Eo To Prevent Recurrence a-m gmg g
a 3
840928 S
745.0 C
1 N/A ZZ ZZZZZ2 Continuing 47-day refueling outage.
1 3
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 Exhibit I-Same AD-28B G-Operational Error (explain)
Source (01-78)
H-Other (explain)
me NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE Docket No.:
50-301 Unit Name:
Point Beach Unit 2 Date:
November 7, 1984 Completed By:
C. W. Krause Telephone:
414/277-2001 Unit 2 was in a refueling shutdown during the entire period.
Containment cleanup was completed on October 2, 1984.
During the "B" reactor coolant pump motor overhaul / inspection, Maintenance personnel discovered a rotor short in the stator windinga and preparations are being made to change out the motor with the onsite spare.
Leak checks and eddy current inspections of the steam genera-tors were completed during the period.
Leak tests revealed one leaking tube in "A"
One leaking tube and one tube with a wet end were discovered in "B"
The eddy current inspection of "A" steam generator revealed 2 undefinable indications (squirrels), 3 tubes with indications <40% and 9 tubes with indications >40%.
All but one indication were located within the tubesheet and all 14 tubes have been plugged.
The eddy current inspection of "B" steam generator revealed one tube with a pluggable indication.
This tubc, along with the 2 tubes discovered during the leak check, were plugged.
While in preparation of unlatching control rods before lifting the reactor vessel head, it was discovered that several control rod drive shaft guide tube flexure heads were damaged.
Entry into the cavity was made to remove the loose and broken flexure heads to eliminate any chance of the loose parts getting into the reactor coolant system.
Thirty-seven damaged flexure heads were removed along with one 1/4" x 1/8" hex head bolt.
A final video camera exam indicated only one additional damaged head.
Subsequently, all flexure heads were removed and the inserts were replaced with flexureless inserts.
The Westinghouse inspection of the optimized fuel assemblies was completed with no indications or problems.
The par exam of the reactor vessel was completed with no indications.
All split pins were UT inspected.
Three cracked split pins were discovered; both split pins on assembly B6 and one split pin on assembly B8.
The cracks occurred in the flange-to-shank region and visual verification with UT results confirmed all nuts were present.
Other safety-related maintenance completed during the period included the replacement of source range detectors 2N31 and 2N32, the removal of the incore flux thimble tubes for flux thimble replacement, inspection and repairs to the main feed regulating
. L.
. valves, main steam isolation valves and the main steam nonreturn valves, repairs to purge exhaust valve operator 2-3212, commence-ment of the installation of primary side loose parts monitoring system, replacement of the "A" residual heat removal pump, con-tinuing work on the auxiliary safety instrumentation panel modification, pressurizer safety valve testing, safety-related hydraulic snubber surveillance, cleaning and eddy current testing of the "C" component cooling water heat exchanger,and the instal-lation of a new fuel gripper assembly.
On October 22, 1984, the Unit 2 plant experienced the loss of normal AC power when a 13.8 KV bus tie was opened prior to the closure of the station transformer 2X03 low side breaker H06.
Power was immediately restored by the 4D emergency Diesel.
This event was reported to the NRC because of the safeguards actuation of the Diesel.
Weld repairs were completed on the moisture separator reheater steam channels and cladding is continuing on the turbino crossunder piping.
Replacement of extraction steam piping is in progress.
Also in progress is a modification to install a turbine bearing j
oil lift system.
Other secondary plant work included the cleaning and inspection l
of the turbine lube oil cooler tube bundic, steam turbine and generator overhaul, flushing and filtering of the turbine lube oil system, machining of the governor valve gasket seats, rebabbiting of 3 turbine low pressure rotor bearings, and the cleaning and eddy current testing of the generator hydrogen coolers, both trains of the 5 feedwater heaters, the condensate cooler,and the 4 condenser waterboxes.
Further tube degradation was noted in the waterboxes.
Examinations revealed the indications to be the result of ID tube inlet and outlet crosion and pitting, OD ammonia grooving near the air ejector penetration, and OD tube steam erosion over the top of the tube bundles.
, e'.
l
. c-Wisconsin Electnc ecwea coursur 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 November 9, 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 October 1984.
Very truly yours, Vice Presi ent-Nuclear Power C. W. Fay Attachments Copies to J. G.
Keppler - NRC, Region III NRC Resident Inspector R. S. Cullen - PSCW
' I i