ML20052G043

Monthly Operating Repts for Apr 1982

ML20052G043
Person / Time
Site:	Point Beach
Issue date:	05/06/1982
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20052G038	List: ML20052G037 ML20052G043
References
NUDOCS 8205140260
Download: ML20052G043 (10)

Text

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,yn CPERATING DATA REPORT c a, DOCKET r40. 50-266 bO Q

0 DATE May 6, 1982

$8 00 CU$iLETED ti C. W. F AY TE3 TELEPHONE 414 277 2811 E$O OPERAIING STATUS

1. UNIT NAME: POINT PEACH NUCLEAR PLAhT UNIT 1 . NOTES .

2. REFORTING FERIOD: APRIL 1982 . .

'. LlLtshED THERnAL F0uiR (hWT): 1518. . .

4. NAhEPLATE RATING (GROSS hue): 523.8 . .

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

6. nAXInun DEPENDABLE CAPACITY (5ROSS MWE): 519. . .

7. nAXInun DEPENDABLE CAPACITY (hET nWE): 495. .. .. .. . .. ...............

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

NOT APFLICABLE

9. F0WER LEVEL TO WHICH RESTRICTED, IF ANY (NET MUE): 445.0

10. REASONS FOR RESTRICTIONS, (IF ANY): Maximum dependable capacity reduced because of self-imposed hot leg iemperature limitation in an attempt to limit steam generator tube corrosion.

THIS n0 NTH YR 10 DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 719 2,879 100,655

12. NunBER OF HOURS REACTOR UAS CRITICAL 446.1 2,455.1 82,808.3

13. REACTOR RESERVE SHUTDOWN HOURS 0.9 11.4 418.7

14. HOURS GENERATOR ON LINE 438.4 2,424.5 80,396.7

15. UNIT RESERVE SHUTDOWN HOURS 5.8 27.4  ??i.?

16. 6ROSS THERnAL ENERGY GENERATED (NUH) 510,547 3,103,250 110,456,090

17. GROSS ELECTRICAL ENERGY GENERATED (nWH) 169,870 1.039.180 37,060,460

18. NET ELECTRICAL ENERG't GENERATED (MUH) 159,961 987.831 35,269,042

19. UNIT SERVICE FACTOR 61.0 84.2 79,9

20. UNIT AVAILABILITY FACTOR 61.8 85.2 80.7

21. UNIf CAPACITY FAC)CR (USING MDC NET) 44.9 69.3 .71.8

22. UNIT CAPACITY FACTOR (USING DER NET) 44.8 69.0 70.5

23. UNIT FORCED OUTAGE RATE 0.0 0.5 3.0

24. SHUTDOWNS SCHEDULED OVER NEXT 4 NONTHS (TYPE, DATE, AND DURATION OF EACH):

NONE

25. IF SHOIDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUIDOUN DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977'

DOCKET NOo 50-266 UNIT NAME Point Beach Unit 1 DATE May 6, 1982 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL _

MONTH April, 1982 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY 4

POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 -2 11 -11 21 369 2 -2 12 62 22 371 3 -2 13 364 23 369 4

4 -2 14 369 24 370 5 -2 15 371 25 374 6 -2 16 372 26 363 7 -2 17 371 27 369 8 -2 18 373 28 369 9 -3 19 369 29 369 10 -6 20 372 30 370 31 ---

AD-28A (1-77)

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

UNIT NAME Point Beach Unit 1 REPORT MONTH April, 1982 COMPLETED W F TELEPHONE 414/277-2811

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'o a e 70o so ao No. Date g mg g jjy Licensee Event vg 'g g'g Cause and Corrective Action e :s ::: o a .c Report No. m Eo To Prevent Recurrence Q* 0; oma o s: > u O

3 820326 S 280.6 B 1 82-007/0lT-0 CB F The unit was taken off line on 03/26/82 for a scheduled steam generator inspection. The unit was returned to service on 04/12/82 following the successful completion of steam generator inspections and repairs.

1 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) (NUREG-0161)

E- Operator Training & License Exam F- Administrative 5 AD-28B Exhibit I- Same 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 May 6, 1982 Completed By C. W. Fay Telephone- 414-277-2811

! Unit 1 was returned to service at 1638 hours0.019 days <br />0.455 hours <br />0.00271 weeks <br />6.23259e-4 months <br /> on

! April 12 following the completion of thc steam-generator inspections and repairs.

Visual tubesheet inspections during the 800 psid secondary-to-primary hydrostatic condition revealed two leaking tubes and six leaking explosive plugs. The explosive plugs verified to be leaking in excess of twc drops per minute were repaired via the use of welded plugs. The tubes verified to be leaking were also plugged.

Eddy current inspections revealed that 19 tubes in the "A" steam generator and nine tubes in the "B" steam generator contained indications exceeding the 40% plugging 'imit. These tubes were mechanically plugged. In addition, all of the tubes containing undefinable eddy current indications in the tubesheet region were plugged to further ensure the reliability of the unit.

Licensee Event Report No. 82-007/0lT-0 dated April 16 provides a description of the above event which 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".

To minimize the rate of corrosion, the Unit 1 primary i

system was returned to power at a reduced hot leg temperature of 557*F. In addition, a crevice flush was performed'before f the unit was returned to service to remove impurities from the tubesheet crevice.

Some of the milestones encountered in preparing Unit 1 for its return to power operation are indicated below. Mechanical l

I and welded plug installation was complated on April 9. The l 800 psid secondary-to-primary hydrostatic leakage test and visual channelhead closecut inspection were performed on the same day. Primary system heatup commenced on April 11 following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of crevice flushing. A bubble was drawn

in the pressurizer at 0213 hours0.00247 days <br />0.0592 hours <br />3.521825e-4 weeks <br />8.10465e-5 months <br /> on April 12. Criticality l

was achieved at 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br /> on April 12. The unit was phased on line at 1638 hours0.019 days <br />0.455 hours <br />0.00271 weeks <br />6.23259e-4 months <br /> on the same day.

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Unit 1 operated at an average of 370 MWe net from April 13 to the end of the reporting period with no load reductions. Primary-to-secondary leakage remains less than ten gallons per day. In fact, the air ejector radiation monitor is the lowest it has been in years being comparable or lower than Unit 2's normal level.

On April 8, it was discovered that the 4160 V and voltage relays, applicable to both units, which disconnect the safeguards buses and start the diesel generators were not in strict compliance with the Technical Specification setpoint requirements. The i.nvestigation found the Technical Specifications in error referencing a 0.3 second at zero V setpoint. This value is not attainable with the relays operating as designed.

Interim relief was acquired from NRR of the NRC on April 9. A new Technical Specification is being written for submittal along with a 30-day Licensee Event Report documenting the event.

On April 14, it was discovered that the setpoint for the P-6 bistable, applicable to both units, has not been in accordance with the Technical Specification safety limit. This was discovered during a procedural review process. This bistable energizes the source range instrumentation following a shutdown as the neutron flux decays. A 30-day Licensee Event Report will be written on the finding and appropriate setpoint and procedural changes will be made.

On April 15 during the performance of a routine surveillance test, it was found that the Unit 1 AT setpoint No. 2 overpower, white channel, exceeded Technical Specification limitations. The setpoint change was caused by instrument drift and was corrected immediately. A 30-day Licensee Event Report will be prepared describing the event.

At 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on April 22, an auxiliary operator inadvertently performed a valve alignment assignment intended for venting and draining of the Unit 2 primary system on the Unit 1 primary system. Due to normal operating system valve alignments, no significant consequences resulted from the personnel I error. Performance of the valve alignment on the operating system I resulted in venting the pressurizer relief tank to the containment a tmosphere , causing an increase in the activity of the containment atmosphere. No radioactivity was released to the environment.

Safety-related maintenance included installation of seismic restraints, TMI electrical equipment backfitting, replacement of the pulsation dampners on the IP2C charging pump, repairs to the lower personnel airlock latching mechanism, and repair work on rod position instrument plugs.

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OPERATING DATA REPORT DOCKET NO. 50-301 DATE May 6, 1982 COnPLETED BY C. W. FAY TELEPHONE 414 277 2811 UPERATING STATUS

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

2. REPORTING PERIOD: APRIL 1982 . .

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

4. NAMEPLATE RATING (GROSS MWE): 523.8 . .

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

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

7. MAXIMUM DEPENDABLE CAPACITY (NET dWE): 495. .............. ..........

8. IF CHANUES 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. H02RS IN REPORTING PERIOD 719- 2,8?? 85,440

12. NUMBER OF HOURS REACTOR.WAS CRITICAL 365.7 2,525.7 76,914.1

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 c.0 193.0

14. HOURS GENERATOR ON LINE 362.6 2,522.6 75,581.2

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 178.0

16. GROSS InERNAL ENEF61 bENERATED (MWH) 528,202 3,731,768 103,988,612

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 168,270 1,253,540 35,276,550

18. NET ELECTRICAL ENERGY GENERATED (MWH) '59,327 1,192.320 33,581,786

19. UNIT SERVICE FACTOR 50.4 87.6 88.5

20. UNIT AVAILABILITY FACTOR 50.4 87.6 88.7

21. UNIT CAPACITY FACTOR (USING MDC NET) 44.8' 84.1 80.0

22. UNIT CAPACITY FACTOR (USING DER NET) 44.6 83.7 79.1

23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.6

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

NONE

25. IF CHuluuWN AT END OF REPCRT PERIOD, ESTIMATED.DATE OF STARTUP: MAY 29,1982 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 May 6, 1982 4 ,

COMPLETED BY C. W. Fay

TELEPHONE 414/277-2811

! AVERAGE DAILY UNIT POWER LEVEL

MONTH April, 1982 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY ,

POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 459 11 440 21 -2 f

2 457 12 437 22 -2 l 3 456 13 436 23 -2 4 453 14 434 24 -2 5 452 15 426 25 -2 6 449 16 -1 26 i 7 448 17 -10 27 -2 i

8 447 18 -7 28 -2 I

9 443 19 -2 29 -2

10 442 2d -2 30 -2 i 31 ---

I AD-28A

(1-77)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 April, 1982 DATE May 6, 1982 REPORT MONTH COMPLETED BY C. W. Fay TELEPHONE 4[4/277-2811

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No. Date g gg g jjg Licensee Event g D'g o'g Cause and Corrective Action E-* :3 :::

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1 820416 S 356.4 C 1 N/A N/A N/A Unit 2 was shut down for its eighth I

refueling outage. Major work items scheduled to be performed this out-age include containment integrated leakage rate testing, eddy current inspection of the steam generator ,

tubes, variousSection XI material testing, "A" reactor coolant pump motor replacement, replacement of various safety grade pressure trans-mitters, and TMI work packages. The unit is scheduled to return to ser-

, vice on 05/29/82.

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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 i F- Administrative 5 AD-28B Exhibit I- Same G- Operational Error (explain) Source (01-78) H- Other (explain)

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-301 Unit Name Point Beach Unit 2 Date- May 6, 1982 Completed By C. W. Fay Telephone 414/277-2811 Unit 2 operated-in stretch operation at an average of 445 MWe net with no load reductions and one scheduled outage..

The unit was taken off line at 0234 hours0.00271 days <br />0.065 hours <br />3.869048e-4 weeks <br />8.9037e-5 months <br /> on 04/16/82 for its eighth scheduled refueling. Reactor shutdown was completed the same day at 0540 hours0.00625 days <br />0.15 hours <br />8.928571e-4 weeks <br />2.0547e-4 months <br />.

Following cooldown, a successful 10-year hydro was performed on the residual-heat removal, main steam and feedwater systems, including the steam generators. In addition, the following Section XI' inspections were performed: UT of the reactor vessel head shell-to-flange weld; UT of the inside radius of the "B" steam generator inlet and outlet nozzle-to-shell welds; UT of the inside radius of the pressurizer spray nozzle weld; UT and VT of one longitudinal, and one circumfarential pressur-izer shell weld; VT of the cladding surroundintl the cold leg manways on both steam generators; VT of the cladding surrounding the pressurizer manway. No reportable indications were discovered.

A containment integrated leakage rate test was performed between 04/18/82 and 04/21/82. The test and verification phases were completed at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> on 04/21/82. The test phase lasted 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> due to a commitment to the NRC; actual acceptance was accomplished at 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Eddy current inspection of the steam generator tubes was started on 04/24/82. The initial inspection program in the "A" steam generator included 575 tubes through the U-bend.

The inspection program was expanded twice in accordance with i Technical Specification 15,4.2.A and finally included all, except peripheral, tubes to the first support. The inspection program in the "B" steam generator included 250 tubes through the U-bend and 31 tubes full length. Again the program was expanded in accordance with Technical Specification 15.4.2.A and finally included essentially all tubes between columns 23 and 61. The inspections revealed that 7 tubes in the "A" steam generator and 6 tubes in the "B" steam generator contained indications in excess of the 40% plugging limit of Technical Specification 15.4.2.A.S. The tubes containing indications greater than the plugging limit were mechanically plugged.

As a preventive measure, 3 additional tubes were plugged in the "A" steam generator. One of these tubes contained a 27%

indication and the other two contained undefinable indications

- all within the tubesheet region.

A 24-hour written notification of the degraded steam generator tubes was made on 04/29/82. A 14-day Licensee Event Report is being prepared.

Steam generator secondary side sludge lancing is scheduled to be performed following the installation of primary steam generator manways. 6-On 04/26/82, it was discovered that the 480 V load shedding relay settings for the Unit 2 B04 bus were not within the Technical Specification time limit at 90% voltage. The time delay for the three relays were 4.20, 4.20 and 4.15 seconds versus the Technical Specification limit of 3.5 seconds il5%. The 0 voltage setting was in specification, however, and the 50% voltage time delay was within the bounds of the characteristic curve.

The relay time delays have been adjusted to be within specifi-cation. A 30-day Licensee Event Report will be submitted on this event.

On 04/27/82, during an inspection of the "A" reactor coolant pump motor, hair-line cracks were discovered in the motor's rotating element. These cracks are located at the interface between the shorting rings and shorting bars. Presently, pre-parations are underway for motor replacement.

Safety-related maintenance performed during the period consisted of routine refueling main'.enance, steam generator tube plugging, "A" reactor coolant pump seal overhaul and motor inspection, repair and calibration of the main steam safety valves, seismic restraint installation, TMI electrical equipment backfitting, overhaul of the auxiliary feed pump turbine, re-placement of various pressure transmitters, and the performance of preventive maintenance to various valves.