ML20027E829

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Monthly Operating Repts for Oct 1982
ML20027E829
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 11/08/1982
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20027E828 List:
References
NUDOCS 8211160225
Download: ML20027E829 (10)


Text

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t arnoo OPERATING DATA REPORT . 1 llBf DOCKET NO. 50-266

$ DATE November 8, 1982 00 Agl COMPLETED BY C. W. FAY o

@lEj TELEPHONE 414 277 2811 OPERATING STATUS

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@$" 1. UNIT NAME: POINT BEACH UCLEAR PLANT UNIT 1 . NOTES .

2. REPORTING PERIOD: OCTOBER 1982 . .
3. LICENSED THERMAL POWER (MUT): 1518. . .

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4. NAMEPLATE RATING (GROSS MUE): 523.8 . .
5. DESIGN ELECTRICAL RATING (NET MUE): 497. . .
6. HAXIMUM 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 UHICH RESTRICTED, IF ANY (NET MUE): 390.0
10. REASONS FOR RESTRICTIONS, (IF ANY): Power level restricted because of self-imposed hot leg temperature limitation in an attempt to limit steam generator. tube corrosion.

THIS MONTH YR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 745 7,296 105,072
12. NUMBER OF HOURS REACTOR WAS CRITICAL 515.3 6,642.4 86,995.6
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 11.4 618.7
14. HOURS GENERATOR ON LINE 505.6 6,602.1 84,574.3
15. UNIT RESERVE SHUTDOWN HOURS 0.0 27.4 791.7
16. GROSS THERMAL ENERGY GENERATED (MWH) 595,125 7,996,075 115,348,915
17. GROSS ELECTRICAL ENERGY GENERATED (HWH) 196,200 2,656,150 33,677,430
18. NET ELECTRICAL ENERGY GENERATED (MWH) 184,437 2,515,783 36,796,994
19. UNIT SERVICE FACTOR 67.9 90.5 80.5
20. UNIT AVAILABILITY FACTOR 67.9 90.9 81.2
21. UNIT CAPACITY FACTOR (USINS HDC NET) 50.1 69.7 71.7
22. UNIT CAPACITY FACTOR (USING DER NET) 49.9 69.4 70.5
23. UNIT FORCED OUTAGE RATE 0.0 0.2 2.8
24. SHUTOOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

NONE

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: DECEMBER 10,1982 DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

e OPERATING DATA AEPORT -

DCCKET NO. 50-301 DATE November 8, 1982 COMPLETED BY C. W. FAY TELEPHONE 414 277 2811 OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 2 . h0TES .
2. REPORTING PERIOD: OCTOBER 1982 . .
3. LICENSED THERMAL POWER (MUT): 1518. . .
4. NAMEPLATE RATING (GROSS MWE): 523.8 . .
5. DESIGN ELECTRICAL RATING (NET MUE): 497. . .
6. MAXIhUM DEPENDABLE CAPACITY (GROSS MUE): bl9. . .
7. MAXINUM DEPENDABLE CAPACITY (NET MUE): 495. ........................
8. IF CHANGES OCCUR 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 RESTRICTIONS, (IF ANY): NOT APPLICARLE THIS MONTH YR TO DATE CUMULATIVE
11. HOURS IN REPORTING PERIOD 745 7,296 89,857
12. NUMBER OF HOURS REACTOR WAS CRITICAL 741.4 6,203.7 80,594.1
13. REACTOR RESERVE SHUTDOWN HOURS 1.3 3.8 196.8
14. HOURS GENERATOR ON LINE 737.4 6,132.6 79,191.2
15. UNIT RESERVE SHUTDOW." kOURS 't.6 3.2 181.2
16. GROSS THERMAL ENERGY GENERATED (MWH) 1,094,393 9,060,327 109,317,171
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 368,190 3,039,930 37,062,940
18. NET ELECTRICAL ENERGY GENERATED (MWH) 351,325 2,898,854 35,282,320
19. UNIT SERVICE FACTOR 99.0 84.1 88.1
20. UNIT AVAILABILITY FACTOR 99.2 84.1 88.3
21. UNIT CAPACITY FACTOR (USING MDC NET) 95.3 80.3 79.9
22. UNIT CAPACITY FACTOR (USI1G DER NET) 94.9 79.9' 79.0
23. UNIT FORCED OUTAGE RATE 0.0 0.1 1.5
24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

Eleven-week refueling outage scheduled to begin Fbrch 25, 1983.

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTINATED DATE OF STARTUP: NOT SHUTDOWN 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 November 8, 1982 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 I AVERAGE DAILY UNIT POWER LEVEL MONTH October, 1982 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL l DAY MWe NET DAY MWe NET DAY MWe NET 1 364 11 363 21 373 2 369 12 371 22 -10 3 346 13 371 23 -8 4 368 14 370 24 -2 5 368 15 369 25 -2 6 369 16 370 26 -2 7 370 17 370 27 -2 8 370 18 368 28 -2 9 371 19 371 29 -2 10 358 2 371 30 -2 31 -2 AD-28A (1-77)

DOCKET NO. 50-301 -

UNIT NAME Point Beach Unit 2 ,

DATE November 8, 1982 i

COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH October, 1982 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL j DAY MWe NET DAY MWe NET DAY MWe NET 1 277 11 486 21 486 2 461 12 473 22 487 3 427 13 486 23 487 4 442 14 487 24 487 5 485 15 483 25 487

6 486 16 470 26 487 i

7 488 17 475 27 488 8 483 18 466 28 486 l

9 486 19 477 29 488 j 10 473 2d 452 30 487 31 487 AD-28A (1-77)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266 UNIT NAME Point Beach Unit"1

. October, 1982 DATE November 8, 1982 REPORT MONTH COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 m

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e 32 vu "co 3R c v as re v 'o in ce No. Date g gg g jjg Licensee Event y g'g Cause and Corrective Action e om m

e vx Report No. m eo To Prevent Recurrence Q- gmg g 8

5 821022 S 238.4 C 1 N/A ZZ ZZZZZ2 Began seven-week refueling outage.

1 4 F: Forced Reason: Method: Exhibit G-Instruc-S: Scheduled A- Equipment Failure (explain) 1- Manual tions for Prepar-B- Maintetance or Test 2- Manual Scram ation of Data Entry C- RefuelLng 3- Automatic Scram Sheets for LER File D- Regulatory Restriction 4- Other (explain) (NUREG-0161)

E- Operator Training & License Exam F- Administrative 5 Exhibit I- Same AD-28B G- Operational Error (explain) Source (01-78) H- Other (explain)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301 UNIT NAME Point Beach Unit'2 '

REPORT MONTH October, 1982 COMPLETED W av TELEPHONE 414/277-2811

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D 'O En Co i No. Date g gg g jjg Licensee Event y g'g Cause and Corrective Action To Prevent Recurrence 3 e om o oa Report No. m so o

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I 5 820925 S 7.6 B 1 N/A CB PUMPX) No. 2 seal on "B" reactor coolant

. pump exhibited signs of increased i degradation and was replaced.

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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 l

C- Refueling 3- Automatic Scram Sheets for LER File D- Regulatory Restriction 4- Other (explain) (NUREG-0161)

, E- Operator Training & License Exam F- Administrative 5 Exhibit I- Same AD-28B G- Operational Error (explain) Source (01-78) H- Other (explain)

O NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unit Name Point Beach Unit 1 Date November 8, 1982 Completed By C. W. Fay Telephone 414/277-2811 Unit 1 operated at 368 MWe net from October 1, 1982 until October 22, 1982, when after 194 days of continuous operation it was shut down for its tenth refueling outage. During the reporting period while the unit was operating, the primary-to-secondary leakage was less than 10 gallons per day.

At 0447 hours0.00517 days <br />0.124 hours <br />7.390873e-4 weeks <br />1.700835e-4 months <br /> on October 2, 1982, valve 1CV-3200C failed to close during a surveillance test which is performed quarterly.

This valve is one of two valves in series in the suction of the containment radioactive gas and particulate sampling system. Valve CV-3200C is located inside containment and receives a containment isolation signal along with series valve CV-3200B, which is located outside containment.

The problem was identified as a stuck solenoid, which prevented the air pressure from bleeding off the valve operator and subsequently prevented the valve from closing. The problem was corrected and the valve was cycled several times without further problems and the system returned to normal. The valve failure constitutes a violation of Technical Specification 15.3.6 and a 14-day Licensee Event Report is currently being drafted to be filed with the NRC.

The Resident Inspector has been notified of this event.

On October 15, 1982, at 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />, while calibrating 1R15 (Unit 1 air ejector radiation monitor) in the Unit 1 turbine hall, a leak occurred in the connection fittings. This resulted in the release of about 1.2 cubic feet of radioactive gas to the Unit 1 turbine hall. A total of about 0.16 Curies were released to the turbine hall. A red phone notification of the event was made.

The release rate was calculated to be 0.5% of the annual average allowable. This event was not considered reportable.

Also on October 15, 1982, a turbine runback reduced load to 320 MWe net for one hour. The runback resulted when due to a mis-understanding, the wrong instrument bus was shifted. In order to investigate an arcing problem with motor-generator set 1GYO4, the yellow bus was supposed to be shifted to its alternate power supply. Instead the white bus was shifted, and before it was noted and corrected, 1GYO4 was tripped causing a runback. The white bus was returned to its normal power supply, the yellow bus shifted to its alternate and the unit returned to full power. An additional result of the lost bus was the loss of 1PT-950, Unit 1 containment pressure. The loss of this channel for approximately one minute reduced the degree of redundancy required by Technical Specifi-cation 15.3.5-3 to zero. Both sets of containment spray logic were operable at all times; one with 3 out of 3, one with 2 out of 3 channels available.

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This event of lost redundancy is reportable in accordance with Technical Specification 15.6 9.2.A.2. The Resident Inspector has been notified of the event and Licensee Event Report 82-018/01T-0 will be sent to the NRC describing the event.

During the shutdown, the secondary sides of Unit 1 "A" & "B" steam generators were leak tested. Two explosive plugged tubes in the "A" steam generator had leakage rates of 1 and 2 drops per minute while one explosive plugged tube in the "B" steam genera-tor leaked approximately one drop per minute and two others were visibly wet.

Eddy current inspection results of the primary side of the steam generators revealed 7 tubes with pluggable indications: Four tubes in "A" steam generator and 3 tubes in "B" steam generator.

Mechanical plugging and a closeout inspection was completed on the steam generators and a 24-hour written notification of the degraded tubes was made to the NRC under Licensee Event Report No. 82-017/01T-0.

During performance of inservice inspection related activities on Unit 1 valve 559B, "B" loop RTD bypass manifold isolation was found to have a body-to-bonnet leak. Four of 12 body-to-bonnet studs were corroded; one losing approximately 50% diameter. It is believed that this leak was the small, difficult to find leak that has plagued Unit 1 containment for some time. This event constitutes a reportable event as an abnormal degradation of the reactor coolant system boundary.

Other work completed in conjunction with the outage was the overhaul of the "A" reactor coolant pump motor, safety valve in-spections, moisture separator reheater inspections, turbine generator overhaul, "B" reactor coolant pump motor and seal inspection and the changeout of the air-operated isolation valves of the steam generator blowdown line.

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J NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-301 Unit Name Point Beach Unit 2 Date November 8, 1982 Completed By C. W. Fay Telephone 414/277-2811 Heatup of the primary coolant was accomplished on Unit 2 following reactor coolant pump seal replacement and at 0335 hours0.00388 days <br />0.0931 hours <br />5.539021e-4 weeks <br />1.274675e-4 months <br /> on Octo-ber 1, 1982, the reactor was taken critical. The turbine was phased on line at 0737 hours0.00853 days <br />0.205 hours <br />0.00122 weeks <br />2.804285e-4 months <br /> and achieved full power 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> later. There were no other significant load reductions during the report period.

During restoration of the Unit 2 low steam header safety in-jection actuation bistables, a significant voltage perturbation occurred while attempting to replace a blown fuse on 2PC-483AX in the red instrument rack. The voltage perturbation was the result of a relay failure. The relay was replaced and tested satisfactorily on October 1, 1982. This event was not considered reportable.

On October 5, 1982, while returning to service the Unit 2 letdown gas stripper,an undetermined number of diaphragm valves began leaking primary coolant into the auxiliary building. The inlet valve to the letdown gas stripper (2GS-3) was closed when the stripper was placed in service which caused the line to pressurize to the relief valve-setpoint. The NRC was notified of the event via the red-phone. The maximum discharge rate amounted to .632%

of the Technical Specification 15-minute release rate. A significant operating event report is currently being prepared to cover this event.

On October 6, 1982, Unit 2 main steam line pressure transmitter, 2PT-478, setpoint was discovered low during routine surveillance testing. This transmitter actuates a safety injection signal upon I a low steam line pressure. The transmitter was recalibrated and is operating satisfactorily. This event is reportable in accordance with Technical Specification 15.3.5-1 and a 30-day Licensee Event Report will be filed with the NRC.

4 SUPPLEMENT TO MONTHLY REPORT FOR October 1982 REFUELING INFORMATION REQUEST In accordance with our letter dated February 21, 1978, which provided certain refueling infonnation, we are providing the following update to that refueling information: (NC = No Change) l a) Next Scheduled Refueling Shutdown: Unit 1: 09/30/83 Unit 2: 03/25/83 b) Scheduled Date for Restart: Unit 1: 03/30/84 Unit 2: 06/10/83 c) License Amendment Required / Staff Yes, steam generator 10 CFR 50.59 Review Completed: Unit 1: replacement Yes, steam generator Unit 2: sleeving l

i d) Scheduled Date for Submitting Supporting Information: Unit 1: submitted Unit 2: submitted Steam generator e) Important Licensing Considerations: Unit 1: replacement steam generator Unit 2: sleeving f) Number of Fuel Assemblies in Storage Pool: 396*

g) Other:

  • Includes 20 spent fuel assemblies from the Unit 1 fall 1982 refueling.

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