ML20032D656

Monthly Operating Repts for Oct 1981

ML20032D656
Person / Time
Site:	Point Beach
Issue date:	11/09/1981
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20032D651	List: ML20032D650 ML20032D656
References
NUDOCS 8111170360
Download: ML20032D656 (10)

Text

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OPERA flNG DATA REPORT DOCKET NO. 50-266

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DATE Novenber 9, 1981

$IC COMPLETED BY C. W. FAY 88 E t>

TELEPHONE 414 277 2811 c[

OPERATING STATUS gm o-

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 1

. NOTES

,oEEI.

2. REPORTING PERIOD:

OCTOBER 1981 sj$**

3. LICENSED THERMAL POWER (HWT):

1518.

4. NAMEPLATE RATING (GROSS MWE):

523.8

5. DESIGN ELECTRICAL RATING (NET nUE): 497.

6. MAXIMUM DEPENDABLE CAPACITY (GROSS nWE): 519.

7. MAXIMUM DEPENDABLE CAPACITY (NET MuE):

495.

B. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

NOT APP : CABLE

9. POUER LEVEL TO UHICH RESTRICTED, IF ANY (NET MWE):

445.0

10. REASONS FOR RESTRICTIONS, (IF ANY): Maximum dependable capacity reduced becauce 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 96,312

12. NUMBER OF HOURS REACTOR UAS CRITICAL 200.0 6,368.5 79,803.3

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 1.3 607.0

14. HOURS GENERATOR ON LINE 193.4 6,338.8 77,475.7

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 764.3

16. GROSS THERMAL ENERGY GENERATED (MuH) 257,443 7,912,401 106,750,845

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 84,440 2,563,760 35,823,480

18. NET ELECTRICAL ENERGY GENERATED (MUH) 78.809 2,429,079 34,096.365

19. UNIT SERVICE FACTOR 26.0 86.9 80.4

20. UNIT AVAILABILITY FACTOR 26.0 86.*

81.2

21. UNIT CAPACITY FACTOR (USING MDC NET) 21.4 67.3 72.6

22. UNIT CAPACITY FACTOR (USING DER NET) 21.3 67.0 71.2

23. UNIT FORCED OUTAGE. RATE 0.0 0.2 3.1 l

24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

l

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: DECEMBER 6,1981 t

DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

i OPERATING DATA REPORT DOCKET NO. 50-301 DATE November 9, 1981 COMPLETED BY C. W. FAY TELEPHONE 414 277 2811 OPERATING STATUS j

l l

1. UNIT NAME: -POINT BEACH NUCLEAR PLANT UNIT 2

. NOTES l

2. REPORTING PERIOC:

OCTOBER 1981

3. LICENSED THERMAL POWER (MWT): 1518.

4. NAMEPLATE RATING-(GROSS nWE):

523.8 l

5. DESIGN ELECTRICAL RATING (NET MWE): 497.

t

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 MWE): NOT APPLICABLE

10. REASONS FOR RESTRICTIONS, (IF ANY): NOT APPLICABLE THIS MONTH YR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 745 7,296 81,097

12. NUMBER OF HOURS REACTOR WAS CRITICAL 736.3 6,383.5 72,933.5

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 6.7 193.0

14. HOURS GENERATOR ON LINE 731.8 6,315.2 71,613.7

15. UNIT RESERVE SHUTDOWN HOURS 0.0 54.1 176.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,088,553 9,312,654 98,102,400

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17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 375,340 3,162,920 33,286,770 l

18. NET ELECTRICAL ENERGY GENERATED (MWH) 358,455 3,016,086 31,679,507

19. UNIT SERVICE FACTOR 98.2 86.6 88.3

20. UNIT AVAILABILITY FACTOR 98.2 87.3 88.5

21. UNIT CAPACITY FACTOR (USING MDC NET) 97.2 83.5 79.6 i

l

22. UNIT CAPACITY FACTOR (USINP DER NET) 96.8 83.2 78.6 l

23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.7

24. 3HUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

l Refueling outage April 16, 1982, expected to last approximately six weeks.

l

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25. IF SHUTDOWN Al END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUTDOWN

' DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED' SEPTEMBER 22, 1977 l

4

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266 i

UNIT NAME Point Beach Unit 1 DATE November 9, 1981 REPORT MONTH October, 1981 COMPLETED BY C.

W.

Fay j

TELEPHONE 414/277-2811 i

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C M Cn o D

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4 o ee on m

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No.

Date g

yg jyy Licensee Event y

g'g Cause and Corrective Action to e

c=

e a sc Report No.

m Eo To Prevent Recurrence O*

M 0 ta c o

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o O

5 811009 S

551.6 C

1 N/A N/A N/A The unit was shut down for its annual refueling outage.

Major q

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work items to be performed during l

the outage include eddy current inspection and test sleeving of l

the steam generators, radiographic inspection of the "B" reactor i

coolant pump, containment fire detectors, transmitter changeout, l

and TMI conduit work, and turbine l

work.

The unit is scheduled to return to service on December 6, 1981.

i I

1 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-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 1

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 DATE November 9, 1981 REPORT MONTH October, 1981 COMPLETED '6Y C.

W.

Fay TELEPHONE 414/277-2811

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c M CD o D

as "c

St Pe En

- e au o

mac p ro ce No.

Date g

cg g

jjg Licensee Event gg y

Cause and Corrective Action

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e p=

e or Report No.

m Eu To Prevent Recurrence Qw M

c) to a o

2:

U 8

5 811003 S

13.2 B

1 N/A ZZ ZZZZZ2 The unit was taken off line for repair of excessive steam leakage from the after high pressure tur-bine access balancing port.

4 1

3 Ft 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)

(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)

DOCKET NO.

50-266 UNIT NAME Point Beach Unit 1

~

DATE November 9, 1981 COMPLETED BY C.

W.

Fay TELEPHONE 414/277-2811 4

AVERAGE DAILY UNIT POWER LEVEL MONTH October, 1981 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET _

1 419 11

-7 21

-1 2

421 12

-2 22

-1 3

419 13

-2 23

-2 4

421 14

-2 24

-2 5

418 15

-2 25

-2 6

41G_

16

-2 26

-2 7

11 5 17

-2 27

-l 8

408 18

-2 28

-1 9

-6 19

-2 29

-1 10

-9 20

-2 30

-1 31

-1 AD-28A (1-77)

DOCKET NO.

50-301 UNIT NAME Point Beach Unit 2 DATE Novert.ber 9, 1981 COMPLETED BY C.

W.

Fay i

TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH October, 1981 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1

494 11 496 21 493 2

494 12 494 22 494 i

3 132 13 494 23 494 4

465 14 494 24 495 5

472 15 494 25 493 6

497 16 493 26 495 7

494 17 496 27 497 8

495 18 500 28 490 4

9 496 19 486 29 494 10 497 20 494 30 495 31 496 AD-28A (1-77)

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No.

50-266 Unit Name Point Beach Unit 1 Date November 9, 1981 Completed By C. W. Fay Telephone 414/277-2811 Unit 1 operated at 417 MUe net with no load reductions until 2243 hours0.026 days <br />0.623 hours <br />0.00371 weeks <br />8.534615e-4 months <br /> on October 8, 1981, when load reduction in preparation for the refueling outage commenced.

At 0125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br /> on October 9, 1981, Unit 1 was taken off line for Refueling 9.

Reactor shutdown was completed the same day at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />.

Following cooldown, a successful 10-year hydrostatic test was performed on the main steam and feedwater systems, including the steam generators.

A containment integrated leak rate test (ILRT) was performed between October 12, 1981 and October 14, 1981.

Prior to containment leak rate testing, the depressurization system was installed.

This required a leak test of the service air containment isolation check valve.

The valve failed its initial test, as noted below (Licensee Event Report No. 81-014/0lT-0).

After containment pressuri-zation was initiated, a visual inspection of containment at 5 psig was performed and no detectable leaks were noted.

The results of testing done at the test pressure of 45 psia also proved to be satisfactory, including the verification phase.

Steam generator work performed during October included sludge lancing, which was completed on October 20, 1981.

Twenty-three gallons of sludge were removed from the "A" steam generator and 19 gallons were removed from the "B"

steam generator.

On October 24, 1981, a leak test of the "B"

steam generator was performed; one dripping (2-3 per minute) explosive plug, 2 wet end explosive plugs, and 4 explosive plugs coated with boric acid were observed.

Decontamination of the "A" steam generator channelhead was started on Octo-ber 24, 1981 and completed on October 26, 1981.

Eddy current examination of the steam generator tubes was condu ted from October 26, 1981 to October 30, 1981.

Ten tubes in the "A"

steam generator and 7 tubes in the "B" steam generator were verified to have degradations greater than the 40%

plugging limit.

These tubes are scheduled to be plugged or sleeved later in the outage.

In addition, eddy current results showed 5 tubes with 20% to 40% indications (2 in the cold leg),

3 tubes with less than 20% indications and 15 tubes with un-definable indications in the "A" steam generator; and 3 tubes with 20% to 40% indications and one tube with an undefinable indication in the "B" steam generator.

A licensee event report will be filed regarding the degraded steam generator tubes in accordance with the Technical Specifications.

E i

I.,

Two other licensea reportable events concerning Unit 1

)

occurred during October.

On October 10, 1981, while per-forming a refueling leakage test of Unit 1 containment isolation valves, the service air containment isolation check valve was found to have leakage such that the limit in Technical Specification 15.4.4.III.B was exceeded.

The check valve was cleaned, reassembled, and successfully re-tested.- This. event is covered in Licensee Event Report No. 81-014/0lT-0.

Also, on October 10, 1981, during performance of TS-30, High ar.d Low Head Safety Injection Check Valve Leak Test, leakage of approximately 6 gpm past check valve 1-853C was i

noted.

This is greater than the acceptance criteria for a satinfactory leak test of this valve.

This event is covered 1

in L12ensee Event Report No. 81-015/01T-0.

There were also two reportable events common to both units occurring during the period.

On-October 16, 1981, the I

plant smoke detector system was inoperable for approximately 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

An error in wiring during backfitting of the fire system caused fuses to blow and the system to deenergize.

The event has been determined to be reportable and a licensee event report will be filed.

On October 16, 1981, Westinghouse. notified Point Beach Nuclear Plant of a potential safety hazard concerning the performance of the Westinghouse manufactured NBFD relay.

This event is reportable in accordance with Technical Speci-fication 15.6.9.2.A.9.

A 24-hour written notification has j

been filed and a 14-day follcwup report will be filed.

Safety-related maintenance performed during the period consisted of routine refueling maintenance plus work on tube sleeving in the "A" steam generator.

A complete core un-loading was performed'in preparation for an examination of the "B" reactor coolant pump and maintenance of portions of the residual heat removal system.

1

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1 i

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Y-NARRATIVE

SUMMARY

OF' OPERATING EXPERIENCE Docket No.

50-301 Unit Name Point Beach Unit 2 Date November 9, 1981 Completed By C. U. Fay Telephone 414/277-2811 Unit 2 operated at an average level of 495 MWe net through-out the period except for one brief maintenance outage and three load-reductions at the request of the Power Supply Super-visor.

A scheduled outage for repair of excessive steam leakage from the after high pressure turbine access balancing port was conducted from 0303 hours0.00351 days <br />0.0842 hours <br />5.009921e-4 weeks <br />1.152915e-4 months <br /> to 0412 hours0.00477 days <br />0.114 hours <br />6.812169e-4 weeks <br />1.56766e-4 months <br /> on October:3,-1981.

The steam leakage was successfully repaired.

The three load reductions took place on October 1, 1981 to 470 MUe for one hour, on October 4, 1981 to 390 MWe for 8.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, and on October 5, 1981 to 400 MWe for 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

One reportable event occurred during the period.

At 2227 hours0.0258 days <br />0.619 hours <br />0.00368 weeks <br />8.473735e-4 months <br /> on October 22, 1981, during routine operations, the NRC Resident Inspector noted that the status light for valve 2SI-866A, (high head "A" safety injection pump discharge valve) indicated the valve to be-in the shut position.

This motor-operated gate valve serves as an isolation valve for the "A"

train.

This event is reportable in accordance with Technical Specification 15.6.9.2.A.6.

A 24-hour written notification has been filed and a 14-day followup report will be filed.

{

Safety-related maintenance performed during the period con-sisted of replacing a switch in the "B" safeguards train.

i i

4

e SUPPLEMENT TO MONTHLY REPORT FOR October 1981 REFUELING INFORMATION REQUEST In accordance with our letter dated February 21, 1978, which provided certain refueling inforr.ation, we are providing the following update to that refueling information:

(NC = No Change) a) Next Scheduled Refueling' Shutdown:

Unit 1:

10/1/82 Unit 2:

4/16/82 b) Scheduled Date for Restart:

Unit 1: _12/17/82 Unit 2:

6/11/82 c) License Amendment Required / Staff 10 CFR 50.59 Review Completed:

Unit 1:

None Anticipated Unit 2:

None Anticipated d) Scheduled Date for Submitting Supporting Information:

Unit 1:

August 1982 Unit 2:

January 1982 e) Important Licensing Considerations:

Unit 1:

None Unit 2:

None f) Number of Fuel Assenblies in Storage Pool:

344 g) Other: