ML20050B692

Monthly Operating Repts for Mar 1980

ML20050B692
Person / Time
Site:	Point Beach
Issue date:	04/07/1980
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20050B691	List: ML20050B690 ML20050B692
References
NUDOCS 8204070224
Download: ML20050B692 (10)

Text

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OPERATING DATA REPORT mim DOCKET No. 50-266 *

88 -

j j DATE April 7, 1980 on i

@@ COMPLETED BY C. W. FAY M

o TELEPHONE 414 277 2811 88ERATIN6 STATU5 8% .

mmo . UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 1 . NOTE 5 .

E U . REPORTING PERIOD: MARCH 1980 .

4

. LICENSED THERMAL POWER (MWT): 1518. .

. NAMEPLATE RATING (GROSS MWE); .523.8 .

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

! . MAXIMUM DEPENDABLE CAPACITY (6ROSS MWE): 519. .

i

. MAXIMUM DEPENDABLE CAPACITY,(NET.MWE); 495.

e. IF CHANGE 5 OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORTe GIVE REASONS:

NOT APPLICABLE

9. POWER LEVEL TO WHICH RESTRICTEDe IF ANY (NET MWE): 390.0

10. REASONS FOR RESTRICTIONSe (IF ANY): SElpupgtitKmNipp005 Power restriction is the result of a self-imposed

) reduction in core average tenperature in an attempt to inhibit corrosion of steam generator tubes within the tubesheet crevice. THIS MONTH YR TO DATE CUMULATIVE

11. HOUR 5 IN REPORTING PERIOD 744 2e184 82e416

12. NUMGER OF HOURS REACTOR WAS. CRITICAL 115.0 le544.7 68,061.2

13. REACTOR RESERVE SHUTDOWN HOUR 5 7.3 17.6 599.8

14. HOUR 5 GENERATOR ON LINE . 0.0 1e415.7 65e809.7 l 15. UNIT RESERVE SHUTDOWN HOURS 122.3 146.6 749 0

16. GROSS THERMAL ENERGY GENERATED (MWH) 0 le696e614 92e449e409

' 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0 554e070 31e187,820

18. NET ELECTRICAL ENERGY GENERATED (MWH) 0 522r615 29,712e793

19. UNIT SERVICE FACTOR 0.0 64.8 79.9 1 20. UNIT AVAILADILITY FACTOR 16.4 71.5 80.8

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 48.3 74.1

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 48 1 72.5

23. UNIT FORCED OUTAGE RATE 0.0 0.0 3.5

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

Unit scheduled to shutdown on July 03, 1980, for ten days to perform steam generator leak testing and eddy current inspection.

25. IF 5HUTDOWN AT END OF REPORT PERIODe ESTIMATED DATE OF STARTUP: APRIL 6 e 1980 i

DATA REPORTED AND FACTORS CALCULATED AS REGUESTED IN URC LETTER DATED SEPTEMGLk 22e 1977 j

OPERATING DATA REPORT DOCKET NO. 50-301

• DATE April 7, 1980 #

1 COMPLETED BY C. W. FAY TELEPHONE 414 277 2811 OPERATING STATUS

1. UNIT NAME: POINT BEACH NOCLEAR PLANT UNIT 2 .t)0TES

2. REPORTING PERIOD: MARCH 1980 . .

3. LICENSED THERMAL POWER (MWT): 1518. . .

4. NAMEPLATE RATING (CROSS MWE); 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 CHANGE 5 OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORTe GIVE REASONS:

NOT APFLICABLE

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)'

NOT APPLICABLE

10. REASON 5 FOR RESTRICTIONSr (IF ANY): NOT APPLICADLE THIS MONTH YR TO DATE COMULATIVE

11. HOUR 5 IN REPORTING PERIOD 744 2,184 67,201

12. NUMDER OF HOURS REACTOR WAS CRITICAL 447.0 1,841.4 60,738.3

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 166.1

14. HOURS GENERATOR ON LINE 438.0 1,832.4 59,559.4

15. UNIT RESERVE SHUTDOWN HOURS 1.1 1.1 107.5

16. GROSS THERMAL ENERGY GENERATED (MhH) 613,022 2e698e713 80,351e249

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 201e970 894,470 27e255e810

, 18. NET ELECTRICAL ENER6Y GENERATED (MhH) 191,808 853,180 25,928,307

19. UNIT SERVICE FACTOR 58.9 83.9 88.6 EO. UNIT AVAILADILITY FACTOR 59.0 84.0 88.8

21. UNIT CAPACITY FACTOR (USING MDC NET) 52.1 78.9 78.7

22. UNIT CAPACITY FACTOR (USIN6 DER NET) 51.9 78.6 77.6

23. UNIT FORCED OUTAGE RATE 41.1 16.1 2.0

24. SHUTD0hN5 SCHEDULED OVER NEXT 6 MONTHS (TYPEe DATER AND DURATION OF EACH):

Refueling shutdown scheduled for April 11, 1980, to last approximately five weeks.

25. IF SHUTDOWN AT END OF REPORT PEPIODe ESTIMATED DATE OF STARTUP: NOT SHUTDOhN DATA REPORTED AND FACTOPS CALCULATED AS REQUESTED IN tlRC LETTEF DATED Sl:PTENDEh 22, 1977

DOCKET NO. 50-266 '.

UNIT NAME Point Beach Unit 1

• DATE April 7, 1980 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH Ma rc.h , 1980 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL DAY POWER LEVEI.

MWe NET DAY MWe NET DAY MWe NET 1 -10 11 -3 21 -2 2 -10 12 -3 22 -2 3 -10 13

, -2 23 -2 4 -12 14 -2 24 -2 5 -11 15 -= 2 25 -2 6 -6 16 -2 26 -2 7 - 3 17 -3 27 -2 8 - 3 18 -3 _

28 -1 9 - 3 19 -2 29 -2 10 - 3 2d -2 30 -1 31 -1 AD-28A (1-77)

DOCKET NO. 50-301 -

I UNIT NAME Point Beach Unit 2 '

DATE April 7, 1980

' COMPLETED BY C. W. Fay i

TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH March, 1980 AVERAGE AVERAGE AVERAGE

, DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL j DAY MWe NET DAY DAY MWe NET MWe NET _

1 -2 11 -

2 21 463 2 -2 12 _

n 22 461 3 -2 13 in 23 465 I

4 -3 14 in, 24 462 5 -1 15 416 25 464 6 -1 16 423 26 463

! 7 -2 17 421 27 464 1

8 -2 18 42, 28 461 9 -2 19 42s 29 458 10 -2 2d 439 30 457 31 453 AD-28A (1-77)

'i UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO; 50-266 UNIT NAME Point Beach Unit 1

{ REPORT MONTH March, 1979 DATE April 7, 1980 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811

~

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C M&o e o- N oa# EW c

.-e mm c mu em en e au o mae am ae No. Date g gg g jjy Licensee Event gg o[o Cause and Corrective Action i

e am e ux Report No. m su To Prevent Recurrence Q~  % emc o x 5 U l

l 800228 S 744 D 1 80-002/0lT CB l lTEXCH As required by the Confirmatory Order of 11-30-79, the unit was taken off line en 2-28-80 for the 60 effective full power day steam gen-erator testing. However, work did not start on Unit 1 until 3-10-80 i because of a forced Unit 2 outage.

j An 800 psi secondary-to primary leak

! test of both generators was per-I formed on 3-11-80 and an eddy cur-

) rent inspection was conducted. Also, i

three tubes were pulled during the I

outage. All tubes with indications and the pulled tube holes were

{ plugged. Also, all tubes and plugs

! identified as leakers during hydro-i static leak testing were repaired.

1 F: Forced Reason: 3

' Method: Exhibit GA 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 D- Regulatory Restriction 3- Automatic Scram Sheets for LER FilG 4- Other (explain) (NUREG-0161)

E- Operator Training & License Exam F- Administrative 5 AD-28B G- Operational Error (explain)

Exhibit I- Same

, (01-78) H- Other (explain)

Source

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301

' UNIT NAME Point Beach Unit 2 REPORT MONTH March, 1979 DATE April 7, 1980 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 y .

m u

c w &o o

~

a e

.<E au c

o

• bu mae

?e am on ce No. Date g cg y jgg Licensee Event gg Cause and Corrective Action e m= o oa Report No. m

{]

Eo a- m omc To Prevent Recurrence o

E 3 0 0

1 800228 F 306 A 1 80-002/ClT CB HTEXCH An orderly shutdown of the unit was completed at 0224 hours0.00259 days <br />0.0622 hours <br />3.703704e-4 weeks <br />8.5232e-5 months <br /> on 2-28-80 following confirmation of primary-to-secondary leakage of 1,420 gal-lons per day in the "A" steam gen-erator. A static head leak check identified the defective tube and a subsequent eddy current inspection i

placed the defect at 10" above the tube end. An eddy current inspec-tion of both steam generators was performed and tubes with defects above the plugging limit were plugged. Several tubes with de fects just below the plugging limit were also plugged. An 800 psi hydrostatic leak test of the "A" steam generator was performed before returning to line.

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

E- Operator Training & License Exam F- Administrative 5 AD-28B G- Operational Error (explain)

Exhibit I- Same (01-78) H- Other (explain)

Source

l l

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unit Name Point Beach Unit 1 Date April 7, 1980 Completed By C. W. Fay Telephone 414/277-2811 The unit was shut down the entire period for the 60 effective full power day steam generator leak testing and eddy current inspection required by the Confirmatory Order of November 30, 1979 and for tube pulling.

Cooldown of Unit 1 commenced at 5:50 p.m. on March 5 and the unit was in cold shutdown at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> on March 6 after approximately six days of standby operation supplying only station steam load requirements. The required steam generator 2000 psi differential leak test and an 800 psi hydrostatic leak check of both steam generators were completed on March 11. No leaks were detected in the "A" steam < generator. One leaking tube (R23C44), one tube that appeared wet (R8C37), and one wet end plug (R23C50) were identified in the "B" steam generator. Licensee Event Report No. 80-002/01T has been filed on this event.

Eddy current inspection of the Unit 1 "A" and "B" steam generators was completed on March 14. A total of about 1,000 tubes were inspected in each steam generator. These included over 100 random tubes in each generator which were inspected for the full length.

Explosive tube plugging of the defective tubes found by eddy current in both steam generators was colapleted on March 17 with the exception of the hot leg end of three tubes.

These three tubes were pulled for laboratory examination and then weld plugged. The three tubes which were pulled are:

R19C37 with a 58% defect located one-half inch above the tubesheet.

R30C41 with a 47% deep crevice defect.

R26C53 with a 86% deep crevice indication that is similar to other undefinable indications.

Four tubes located near tube R30C41 were explosively plugged as a precautionary measure because these tubes may have been damaged during pulling of tube R30C41.

Two explosive plugs were repaired on March 25. These two plugs included the one identified as having a wet end during the March 11 hydrostatic leak test (R23C50) and one (R29C41) which started to leak after removal of an adjacent tube.

Manual weld plugging of the removed tube holes was completed on March 28. An 800 psi secondary-to-primary hydro-static. leak test of the Unit 1 "B" steam generator was completed at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> the following morning. Two leaking tubes (R25C48 and R23C55) , one leaking explosive plug in the hot leg (R25C53),

and one leaking explosive plug in the cold leg (R22C48) were identified. The leaking tubes were explosively plugged and the plugs weld repaired on March 30 and 31. All of these tubes and plugs, except for the one in the cold leg, are adjacent to where a tube was pulled, an explosive plug installed, or a weld repair made during this outage.

A second 800 psi secondary-to-primary hydrostatic leak test was performed on March 31. This leak test identified a leaking tube (R26C52) and a leaking manual weld (R26C53) . The leaking tube is adjacent to a weld repair which was made after the first leak test. The leaking manual weld is also adjacent to this weld repair. Due to its close proximity,, some of the weld metal was machined away when preparing the adjacent plugged tube for weld repair. This manual weld is one of the three made this outage to plug the tubesheet hole where a tube was removed.

The tube was explosively plugged on March 31 and the manual weld repair was completed on April 3.

A final 800 psi secondary-to-primary hydrostatic leak test of the Unit 1 "B" steam generator was performed at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> April 3. One tube (R29C53) was observed to be dripping at a very slow rate and two explosive plugs (R23C53 and R20C46) and one manual weld plug (R19C37) were observed to be wet, but no water was dripping. The leaking t.ibe was mechanically plugged on April 3. The wet plugs were not repaired since a wet end does not pose a significant primary-to-secondary leakage potential.

The containment spray system logic was modified during the period to remove the safety injection signal requirement for automatic spray initiation. A verification test subsequent

, to this modification revealed that a relay in the system would not properly latch. This relay is unrelated to the modification, and Licensee Event Report 80-003/0lT has'been filed on this event.

The relay has been adjasted and proper operation verified. The unit was in cold shutdown at the time.

The "B" reactor coolant pump seals were inspected and the No. 1 seal was replaced during the period. Also, a steam generator safety valve was overhauled during the period.

The last of the old spent fuel storage racks was shipped offsite during this period.

Work continues on IE Bulletin Nos. 79-02, anchor bolt inspection, and 79-14, seismic analysis for as-built safety-related piping systems.

No other major safety-related maintenance was performed during the period.

F d

4 i

i i

I

.. .. l 1

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE  !

l Docket No. 50-301 Unit Name Point Beach Unit 2 Date April 7, 1980 Completed By C. W. Fay Telephcne 414/277-2811 Ur.it 2 was base loaded for 52% of the period with no load reduction after returning to line at 1802 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.85661e-4 months <br /> on March 13 following a steam generator outage. The unit is operating at a reduced pcwer level because of extended fuel burnup.

Eddy current examination of the Unit 2 steam generators and data evaluation were completed on March 9. A 100% inspection of the "A" steam generator hot leg was performed and 149 cold leg tubes were inspected from the hot leg side. A total of 25 tubes requiring plugging were identified. These tubes were explosively plugged except for the hot leg end of the leaking tube which was mechanically plugged to allow for future tube ,

removal for laboratory examination. In addition, ten tubes with 39% indications were plugged as a conservative measure. Eddy current examination in the "B" steam generator consisted of 717 tubes in the hot leg and 685 tubes in the cold leg. Only one tube requiring plugging was found. This tube had a 41% indication located one and one-half inches above the tubesheet in the cold leg. Licensee Event Report 80-002/0lT-0 was issued on March 11 and provides details of this event.

Unit 2 steam generator tube plugging was completed on March 11. The final hydrostatic test of the "A" steam generator and the closeout inspection of the "A" and "B" steam generators were completed at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on March 11; no leaks were observed.

A failed source range detector was replaced during the period.

The "A" containment recirculating fan motor leads were retaped during the period to conform to specification require-ments. All other fan motor leads have already been retaped.

Permanent installation of the pressurizer safety relief valve acoustic monitoring system was completed during the period.

Work continues on IE Bulletin Nos. 79-02, anchor bolt inspection, and 79-14, seismic analysis for as-built safety-related piping systems.

No other major safety-related maintenance was performed during the period.