ML20108D716

Monthly Operating Repts for Nov 1984

ML20108D716
Person / Time
Site:	Point Beach
Issue date:	11/30/1984
From:	Fay C, Krause C WISCONSIN ELECTRIC POWER CO.
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8412130368
Download: ML20108D716 (10)

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l DOCERT NO.

50-266 UNIT MADE Point Beach Unit 1 December 7, 1984 l

DATE i

COMPLETED BY C. W. Krause t

TELEPHONE 414/277-2001 AVERAGE DAILY UNIT POWER LEVEL MONTH November, 1984 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POtER LEVEL POWER LEVEL POWER LEVEL DAY 3ede MET DAY 3ede NET DAY 3efe MET 1

SG2 11 503 21 501 2

500 12 503 22 503 3

393 13 501 23 489 4

500 14 505 24 503 5

501 15 500 25 502 6

502 16 502 26 503 7

504 17 501 27 503

-8 503 13 502 23 503 9

504 19 502 29 502 10 505 20 501 30 502 31 EQR-2Ba C1-79)

- m 9

UNIT SHUTDONNS AND PONER REDUCTIONS

-DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 D

REPORT MONTH November, 1984 D

r TELEPHONE 414/277-2001 l

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on ce oca Ew c

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man om ce No.

Date g

ag-jgg Licensee Event y

Q Cause and Corrective Action a

p

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u.c Report No.

ca Eo To Prevent Recurrence o-m; e to c o

E 3

o 8

5 841102 S

14.5 B

4 N/A ZZ EZZZZ" Power reduction to check and plug leaking condenser tubes.

1 2

3,,,,,,

3 N For M 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 Restrictica 4-Other (explain)

(NUREG-0161)

E-Operator Training & License Exam F-Administrative 5 Exhibit I-Same AD-283 G-Operationa1 Error (expli.in)

. Source (01-78)

H-Other (explain)

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No.:

50-266 Unit Name:

Point Beach Unit 1 Dator December 7, 1984 Completed By:

C. W. Krause Telephone:

414/277-2001 Unit 1 operated at approximately 501 MWo not throughout the period with one major load reduction.

On November 2 & 3, 1984, load was reduced to approximately 263 MWo not for 14.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for the performance of the turbino stop valve test and condonsor tubo leak checks.

The condensor tubo leak checks revealed ono leaking tubo.

The plugging of this leaking tubo proved offective as the steam generator blowdown cation conduc-tivity improved from 0.6 umhos/cm to 0.25 pmhos/cm.

This improvement is significant and well below the Steam Generator Owner's Group guidelines.

The unit surpassed 44 billion KWH's of generation on November 10, 1984, and the primary-to-secondary steam generator leakage romained at lots than 10 gallons por day.

On November 8, 1984, in preparation for maintenanco on the 2A03 normal foodor breaker, the bus tio breaker from 1A03 to 2A03 was closed.

At that timo, the breaker immediately tripped open duo to the closing logic.

Simultaneoualy, 2A03 normal foodor breakor was opened inadvertently causing a loss of power to 2A03.

This action caused an undorvoltage sensed on 2A05, thereby giving a start signal to 3D.

3D started and closed in on 2A05.

Normal power was restored to 2A03, 2A05, 2A01 & 2B01, and 3D was secured.

A Licensoo Event Roport has boon submitted on this avont.

On November 20, 1984, at approximately 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, a fire was reported in the vicinity of the Unit 1 hydrogen dryor.

The fire was small and wan extinguished promptly with a hand-hold fire extinguishor.

The firo was caused by grinding sparks igniting a small amount of hydrogen leaking frcm the dryor.

A mooting was hold betwoon the fire protection personnel and tho individuals authorized to executo ignition control permits to rectify this situation.

Safety-related maintenanco performed includes the continuing work on the installation of tho auxiliary safoty instrumentation panol, repairing a soul leak on the IP2B charging pump and repairing a cryogonic compressor.

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OPERATING DATA REPORT

~

4 DOCKET NO. 50-301 ~

DATE December 7, 1984 l

COMPLETED BY C. W. KRAUSE:

TELEPHONE

'414 277.2001 OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 2

. NOTES

2. REPORTING PERIOD: NOVEMBER 1984

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

i 4.-NAMEPLATE RATING (GROSS MWE):

523.8

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

6. HAXIMUM' DEPENDABLE CAPACITY (GROSS MWE): 509.

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 485.

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

-NOT APPLICABLE

9. POWER LEVEL T0 WHICH RESTRICTED, IF ANY (NET MWE): NOT APPLICABLE

10. REASONS FOR RESTRICTIONS, (IF ANY): NOT APPLICABLE i

THIS MONTH YR TO DATE CUMULATIVE'

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11. HOURS IN REPORTING PERIOD.

720 8,040 108,121 i

12. NUNRR OF HOURS REACTOR'WAS CRITICAL 311.0 6,800.2 95,228.4 1

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 8.8 207.1 l

.14. HOURS GEhERATOR ON LINE 249.7 6,667.6 93,570.4

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15. UNIT RESERVE SHUTDOWN HOURS 0.0 15.4 198.1 16.' GROSS THERMAL ENERGY GENERATED' OiWH).

252,959 9,795,654 130,690,431 17.-GROSS ELECTRICAL ENERGY' GENERATED-(MWH) 86,310 3,315,860 44,275,690

18. NET ELECTRICAL ENERGY GENERATED (MWH) 79,051 3,162,177 42,162,777

19. UNIT SERVICE FACTOR c

34.7 82.9 86.5

20. UNIT AVAILABILITY FACTOR 34.7 83.1 '

86.7 j

21. UNIT CAPACITY FACTOR (USING nDC NET).

22.6 81.1 79.4

22. UNIT CAPACITY FACTOR (USING DER NET) 22.1 79.1 78.5 t

23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.3 l

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

NONE

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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-l l

i

DOCKET NO.'I

'50-301 UNIT NAME Point Beach Unit 2:

'DATE December 7, 1984 COMPLETED BY C.

W.

Krause TELEPHONE 414/277-2001 AVERAGE DAILY UNIT POWER LEVEL

, MONTH November, 1984 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER. LEVEL DAY MWe NET DAY MWe NET-DAY MWe NET 1

-2 11

-2 21 148 2

-2 12

-2 22 370 337 3

-2 13

-7 23 4

-2 14

-8 24 273 5

-2 15

-8 25 272 6

-2 16

-7 26 263 7

-2

.17

-12 27 275 8

-2

'18

-14 28 438 493 9

-2 19

-15 29 496 10

-2 20 24 30 31 EQR-28a (01-79)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301 UNIT NAME Point Beach Unit'2 REPORT MONTH' November, 1984 DATE December 7.

1984 COMPLETED BY C.

W.

Krause TELEPHONE-414/277-2001 t

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Dum o co am No.

Date g

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g'g Cause and Corrective Action e

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v4 Report No.

m so To Prevent Recurrence Qv M

W U) C o

C N

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3 840928 S

L215.3 C

1 N/A ZZ 5ZZZZZ Continuation of 53-day refueling outage.

4 841120 S

9.6 B

1 N/A ZZ

$ZZZZZ Unit removed from service to complete off-line turbine testing.

t F: Forced Reason:

3 Method:

Exhibit G-Instruc-i S: Scheduled A-Equipment Failure (explain) l-Manual tions for Prepar-i B-Maintenance or Test 2-Manual Scram ation of Data Entry C-Refueling 3-Automatic Scram Sheets for LER Filei 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)

.w

. NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE-Docket-No.:

50-301 Unit Name:~

Point Beach Unit 2 Date:

December:7, 1984 Completed By:

C. W. Krause Telephone:

414/277-2001 Unit 2 Refueling 10 ended when the generator was phased to the:line at 1205 hours0.0139 days <br />0.335 hours <br />0.00199 weeks <br />4.585025e-4 months <br /> on November 20, 1984.

Events leading up to the unit's phase-to-line include changing out and balancing the "B" reactor coolant pump motor, final wiring of the turbine oil-lift pump and modifying the reactor trip breakers.

On November 7, 1984, installation of the new incore thimbles began.

Thirty-five of the 36 thimbles were replaced.

The thirty-sixth thimble was not able to be replaced and the decision was made to

. operate with 35.-

All 35 of the incore detector thimbles are func-tional.

On' November 13, 1984, the primary system was filled and vented and containment integrity was established.

Heatup commenced on November 14, 1984, for the steam generator crevice flush.

After.the crevice. flush was completed, preparations to go critical were made.

On November 16, 1984, a AT Technical Specification setpoint change was approved that allowed. Unit 2 to go critical.

On November 17, 1984, hot rod drop testing was performed and at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on November 18,.1984, Unit 2 went critical.

"Beginning of life" physics testing was completed

-later in the day.

On November 19, 1984, a Chemistry " hold" was in effect on the unit due to the secondary water having

-sodium concentrations higher than the Steam Generator Owner's Group guidelines.

With Chemistry giving the "go. ahead", the unit was on line at 1205 hours0.0139 days <br />0.335 hours <br />0.00199 weeks <br />4.585025e-4 months <br /> on November 20, 1984, and-at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, the overspeed trip tests were completed.

Shortly

.after midnight on November 21, 1984, the unit was put back on line.

On November 23, 1984, in conjunction with a "high level turbine building sump". alarm, the "B" main feed pump was found to have gross seal leakage.

At 0921 hours0.0107 days <br />0.256 hours <br />0.00152 weeks <br />3.504405e-4 months <br />, a load rampdown of 5% per minute commenced.

At 0931 hours0.0108 days <br />0.259 hours <br />0.00154 weeks <br />3.542455e-4 months <br />, with the unit at approximately 256 MWe net, the "B" pump was secured.

Disassembly of the pump revealed the top halves of both the north and south journal bearings had babbitt broken out.

Further disassembly:showed the oil deflectors and the stuffing box bushings destroyed.. Removal of the pump cover revealed 3 large

pieces of the impeller and a chip from the volute vane were missing.

Two pieces of the impeller were found in the SA feed-

-water heater and the remaining pieces along with the chip from the volute vane were found in the pump's mini-recirc valve.

Two other pieces of what appeared to be welding slag were also

. pulled out of the mini-recirc valve.

~

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,- 's. '

.. A spare rotating assembly wasLinstalled and the. pump'was

-reassembled.

At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on November 27, 1984,"the "B" pump

.was put back in service.

Unit 2 remained at approximately 256 MWe net during the main feed pump repair and after the. pump was restarted and observed for abnormalities, power level was ramped up, and by November 29, 1984, the unit was at full power.

Other safety-related maintenance performed during the period includes recalibrating the reactor coolant temperature detector system RTD's, continuing the installation of the auxiliary safety instrumentation panel and replacing the spherical bearings on.the 800 K Anker-Holth snubbers.

During preparation for the Unit 2 startup, one of the RTD bypass manifold isolation valves, 564A, was found to have a broken stem.

Because these isolation valves have had a history of failure, the internals and the bonnet were removed and the body was capped.

r Primary-to-secondary steam generator leakage is less than

10. gallons per day.

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~=

WhiiC00 Sin Electnc me couna 231 W. MICHIGAN. P.0, BOX 2046. MILWAUKEE WI 53201 December 10, 1984 Director of Regulatory Operations U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.

20555 Gentlemen:

MONTHLY OPERATING REPORTS POINT EEACH NUCLEAR PLANT Attached are monthly operating reports for Units 1 and 2, Point Beach Nuclear Plant, for the ca!.endar month of November 1984.

Very truly yours,

?

b Vice Pre ident-Nuclear Power C. W. Fay Attachments Copies to J. G. Feppler - NRC, Region III NRC Resident Inspector R.

S., Cullen - PSCW

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