ML20077A553

Monthly Operating Repts for Oct 1994 for Point Beach Nuclear Plant Units 1 & 2

ML20077A553
Person / Time
Site:	Point Beach
Issue date:	10/31/1994
From:	Koudelka M, Maxfield G WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PBL-94-0344, PBL-94-344, NUDOCS 9411230320
Download: ML20077A553 (13)

Text

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Point Beach Nuc! eor Plant 6610 Nuclear Rd.Two Rr/ers.WI 54241 (414) 755-2321 PBL 94-0344 November 4, 1994 Document Control Desk U.

S. INCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:

DOCKETS 50-266 AND 50-301 MONTHLY OPERATING REPORTS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Attached are monthly operating reports for Units 1 and 2 of the Point Beach Nuclear Plant for the calendar month of October, 1994.

I Sincerel,

G. J. Max eld PBNP anager d'a I

Attachments i

cc:

L. L.

Smith, PSCW NRC Regional Administrator, Region III NRC Resident Inspector I

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Point Beach Shif t Operational Data Summary October 1994 Unit 1 Unit 2 Day Gen XO2 XO4 XO8 X27 Net MWe Avg MWe Gen XO2 XO4 XO8 X27 Net MWe Avg MWe 1

12210 495 41 1

4 11670 486 0

0 41 1

4 46

-2 2

12270 497 41 1

4 11728 489 O

O 36 1

4

-40

-2 3

12260 497 42 2

5 11715 488 0

1 33 2

5

-40

-2 4

12270 499 42 4

5 11721 488 0

0 34 4

5 42

-2 5

12270 498 40 3

5 11725 489 O

O 29 3

5

-37

-2 6

12270 498 37 4

4 11728 489 0

0 30 4

4

-38

-2 7

12290 499 33 4

4 11751 490 0

0 32 4

4 40

-2 8

12370 498 36 4

4

-11829 493 O

O 32 4

4

-40

-2 9

12450 499 38 4

4 11906 496 O

O 35 4

4

~43

-2 10 12400 499 30 4

4 11864 494 O

O 28 4

4

-36

-1 11 12410 499 30 3

4 11874 495 0

0 33 3

4 40

-2 12 12380 502 34 2

5 11838 493 O

O 39 2

5

-46

-2 13 12360 499 31 1

4 11826 493 O

O 38 1

4

-43

-2 14 12390 500 31 1

5 11854 494 O

O 40 1

5

~4 5

-2 15 12340 498 31 1

4 11807 492 O

O 40 1

4

-44

-2 16 12350 497 29 1

4 11819 492 O

O 40 1

4 45

-2 17 12350 499 30 1

4 11817 492 O

O 40 1

4 45

-2 18 12340 500 29 1

5 11806 492 O

O 41 1

5

-47

-2 19 12380 501 34 0

4 11841 493 O

O 42 0

4

-46

-2 20 12340 501 36 1

5 11798 492 O

O 43 1

5 49

-2 21 12490 503 35 1

5 11947 498 0

0 45 1

5

-51

-2 22 12260 502 35 1

4 11719 488 O

O 47 1

4

-52

-2 23 12370 502 34 1

4 11830 493 O

O 45 1

4

-50

-2 24 12370 503 37 1

5 11825 493 0

0 46 1

5

-52

-2 25 12410 505 40 1

4 11860 494-0 0

41 1

4

-46

-2 26 12400 504 38 1

6 11852 494 O

O 47 1

6

-54

-2 27 12380 504 36 1

5 11834 493 0

0 50 1

5

-56

-2 28 12390 504 34 1

5 11846 494 O

O 242 1

5

-248

-10 29 12400 504 36 1

5 11855 494 O

O 280 1

5

-285

-12 30 12930 522 36 1

5 12367 515 O

O 335 1

5

-341

-14 ll 31 12380 506 30 1

5 11839 493 0

0 337 1

5

-343

-14 MONTHLY TOTALS - UNIT 1 MONTHLY TOTALS - UNIT 2 Gross generation:

383480 MWhr Gross generation:

O MWhr Total station service:

16799 MWhr Total station service:

2421 MWhr Net generation:

366682 MWhr Net generation:

-2421 MWhr Average daily power:

493 MWe Average daily power:

-3 MWe

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OPERATING DATA REPORT DOCKET NC. 50-266 DATE:

11/04/94 COMPLETED BY:

M.

B.

Koudelka

.t TELEPHONE:

414 755-6480-OPERATING STATUS l

1.

UNIT NAME:

POINT BEACH NUCLEAR PLANT - UNIT 1

. NOTES

2. REPORTING PERIOD: October - 1994

[

3 LICENSED THERMAL WWER (MWT):

1518.5 4.

NAMEPLATE RATING (GROSS MWE):

523.8 5 DESIGN ELECTRICAL RATING (NET MWE) :

497.0 6.

MAXIMUM. DEPENDABLE CAPACITY (GROSS MWE) 509.0.

7.

MAXIMUM DEPENDABLE CAPACITY (NET MWE) :

485.0 8.

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

NA 9.

POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE): NA

10. REASONS FOR RESTRICTIONS, (IF ANY):

NA THIS MONTH YEAR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 745.0 7,296.0 210,264.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 745.0 6,670.6 175,389.5

13. REACTOR RESERVE SHUTDOWN HOURS O.0 0.0 667.3

14. HOURS GENERATOR ON LINE 745.0 6,622.1 172,262.3

15. UNIT RESERVE SHUrDOWN HOURS 0.0 0.0 846.9

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,131,283 9,873,475 243,355,245

17. GROSS ELECTRICAL ENERGY GENERATED 383,480 3,341,200 82,195,330

18. NET ELECTRICAL ENERGY GENERATED (MWH) 366,681 3,193,397

-78,348,987

19. UNIT SERVICE FACTOR 100.0%

90.8%

81.9%

20. UNIT AVAILABILITY FACTOR 100.0%

90.8%'

82.3%

21. UNIT CAPACITY FACTOR (USING MDC NET) 101.5%

'90.2%

76.5%

22. UNIT CAPACITY FACTOR (USING DER NET) 99.0%

88.1%

75.0%~

23. UNIT FORCED OUTAGE RATE 0.0%

0.0%

1.5%

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

I Refueling Outage, 03/11/95, 39 days

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

NA DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN'NRC LETTER DATED SEPTEMDER 22, 1977

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POINT BEACH NUCLEAR PLANT DOCKET NO.

50-266 AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach, Unit 1 P/"TH OCTOBER -

1994 DATE November 4,1994 COMPLETED BY M. B. Koudelka TELEPHONE (414)755-6480 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1

486 11 495 21 498 2

489 12 493 22 488 3

488 13 493 23 493 4

488 14 494 24 493 5

489 15 492 25 494 6

489 16 492 2G 494 7

490 17 492 27 493 8

493 18 492 28 494 9

496 19 493 29 494 10 494 20 402 30 515 31 493 l

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POINT BEACH NUCLEAR PLANT Decket No.

50-266 Unit Name Point Beach.- Unit 1 UNIT SHUTDOWNS AND POWER REDUCTIONS Date November 4.1994 Completed By M. B. Koudelka REPORT MONTH OCTOBER - 1994 Telephone No.

414/755-6480 Method of Shurrmg Duranon Down Licensee Event System Component Cause and Corrective Action No.

D. ate Type" (flours)

Reason' Reactor' R port No.

Code' Code' To Prevent Recurrence NA NA NA NA NA NA NA NA NA NA

'F: Forced 2 Reason:

' Method:

' Exhibit G - Instructions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG-0161)

D - Regulatory Restriction 4 - Continuation of E - Operator Training &

Previous Shutdown Licensing Exam 5 - Reduced Load F - Administrative 6 - Other (explain) 8 Exhibit I - Sarre Source G - Operational Error (explain)

H - Other (explain) i I rntwo2sb l

(03-90)

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DOCKET NO.

50-266 UNIT.NAME-Point Beach Unit 1 DATE November 4, 1994 COMPLETED BY M.

B. Koudelka TELEPHONE 414/755-6480 Unit 1 operated at an' average of 493 MWe net for the report

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period.

Licensee Event Reports 50-266/94-009-00, Inadvertent Emergency Diesel Start and Loss of Station Battery Charger; and, 50-266/94-010, Inadvertent Emergency Diesel Generators Start, Loss of Two Station Battery Chargers, and Unit 2 Loss of Decay Heat Removal, were submitted.

Safety-related maintenance included:

1.

CO2 electrical control board motor control center switches installed.

2.

1P29T turbine-driven auxiliary feedwater pump turbine bearing oils sampled.

3.

1B52-16C breaker cycled.

4.

Rewired 1B52-22A breaker and cubicle.

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OPERATING DATA REPORT DOCKET NO. 50-301 DATE:

11/04/94 COMPLETED BY:

M.

B.

Koudelka 4

TELEPHONE:

(414) 755-6480 OPEPATING STATUS 1

1.

UNIT N7NE:

POINT BEACH NUCLEAR PLANT - UNIT 2 NOTES

2. REPORTING PERIOD: October - 1994 3.

LICENSED THERMAL POWER (MWT) -

1518.5 1

4, NAMEPLATE RATING (GROSS MWE)-

523.8

5. DESIGN ELECTRICAL RATING (NET MWE):

497.0

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

509.0.

7.' MAXIMUM DEPENDABLE CAPACITY (NET MWE) :

485.0 8.

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

NA 9.

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

NA

10. REASONS FOR RESTRICTIONS, (IF ANY)

NA THIS MONTH YEAR.TO DATE CUMIFATIVE

11. HOURS IN REPORTING PERIOD 745.0 7,296.0 195,049.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 6,387.0 170,587.6

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 233.9 l

14. HOURS GENERATOR ON LINE 0.0 6,385.5 168,252.2

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 302.2_

I

16. GROSS THERMAL ENERGY GENERATED (MWH) 0 9,588,393 241,959,577

17. GROSS ELECTRICAL' ENERGY GENERATED 0

3,243,160 82,267,420

18. NET ELECTRICAL ENERGY GENERATED (MWH) 0 3,097,915 78,428,555

19. UNIT SERVICE FACTOR 0.0%

87.5%

86.3%

20. UNIT AVAILABILITY' FACTOR 0.0%

87.5%

86.4%

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0%

87.5%

82.3%

I

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0%

85.4%

80.9%

23. UNIT FORCED OUTAGE RATE 0.0%

0.0%

1.0%

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

NONE

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATS OF STARTUP:

11/01/94 DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

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POINT BEACH NUCLEAR PLANT DOCKET NO.

50-301' AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach, Unit 2 MONTH OCTOBER -

1994 DATE November 4,1994 COMPLETED BY M. B. Koudelka TELEPHONE (414)755-6480 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

-2 2

-2 12

-2 22

-2 3

-2 13

-2 23

-2 4

-2 14

-2 24

-2 5

-2 15

-2 25

-2 6

-2 16

-2 26

-2 7

-2 17

-2 27

-2 8

-2 18

-2 28

-10 9

-2 19

-2 29

-12 10

-1 20

-2 30

-14 31

-14

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POINT BEACll NUCLEAR PLANT _

' Docket No.

50-301 Unit Name Point Beach. Unit 2 UNIT SIIUTDOWNS AND POWER REDUCTIONS Date November 4.1994 Completed By Af. B. Koudelka s.

REPORT h10NTII OCTOBER - 1994 Telephone No.

414/755-6480 Method of Shumng Duration pown Ucensee Event System Component Cause and Corrective Action No.

Date Type' Olaurs)

Reason pene,np Report No.

Code

• Code' T 'revent Recurrence 2

0/24/94 S

745 C

1 NA NA NA Scheduled refuelmg and maintenance et age (U2R20). Major work items include amptector upgrades, RHR pump retor replacement,4-rotor limit switch upgrades, main feedwater check valve replacements, reactor heat shield SI-854A&B internals replacement, Gaisonics upgrade, G04 emergency d esel generator tie-in work, reactor coolant pump seal water flow transmit:er replacement, safeguards sequence timing relay replacements, control rod drive mechanism control current timing modification, degraded grid voltage relay work, steam generator blowdown heat exchanger replacement, and containment service water pipe supports as part of continued Bulletin 79-14 upgrades.'

L

'F: Forced 2Reason:

3hiethod:

' Exhibit G - Instructions i

S: Scheduled A - Equipment Failure (explain) 1 - h1anual for preparation of B - hiaintenance or Testing 2 - h1anual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG-0161)

D - Regulatory Restriction 4 - Continuation of E - Operator Training &

Previous Shutdown Licensing Exam 5 - Reduced Load F - Administrative 6 - Other (explain)

Exhibit I - Same Source 5

G - Operational Error (explain)

II - Other (explain)

PDFW28b (03-90)

/

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. DOCKET NO.

50-301 UNIT NAME Point Beach Unit'2 DATE November 4, 1994 COMPLETED BY M.

B. Koudelka TELEPHONE 414/755-6480 Unit 2 was shutdown for a refueling and maintenance outage since September 24, 1994.

The unit is estimated for startup on November 1, 1994.

Licensee Event Reports 50-301/94-002-01, Quarterly Technical Specifications Test of PORV Block Valve Not Performed; 50-301/94-003-00, Steam Generator Tube Degradation; and 50-301/94-004-00, Late Reactor Coolant System Chloride Sample, were submitted.

Safety-related maintenance included:

1.

2A05 bus loss of voltage relay replacements.

2.

2B52-40B&C breaker direct tripping actuator inspections.

.3.

2CO3 steam and turbine auxiliary control board Train A power available light socket replaced.

4.

As-built wire tracing performed on panels 2C75, 2C208B, 2C208C, and 2N04.

5.

Four-rotor limit switches installed on 2CV-112C-0, 2CC-754B-0, SI-896A-0, 2SI-841B-O and 2SI-860D-0.

6.

2CV-133 residual heat removal to letdown isolation valve I

regulator repaired.

7.

2CV-371-S letdown line containment isolation solenoid valve rebuilt.

8.

2FE-175 and 2FE-176 reactor coolant pump A and B #1 seal water return low range flow elements repaired.

9, 2FI-626 residual heat removal pump flow indicator repaired.

10.

Various wiring changes made and testing performed on panels and buses in support of G04 emergency diesel generator tie-in work.

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.11.

2HS-22 Loop AEcubicle snubber stud'and nut replacement.

12.

2HX-15A8 containment accident recirculation heat exchanger welded in pipe plug.

13.

2LT-460B HX'1A steam generator. wide range level transmitter calibrated.

14.

Replaced breakers on 2 MOB-322., 2 MOB-331, 2 MOB-333, 2 MOB-334, and 2 MOB-335 and seventeen MOBS cycled.

15.

2MS-2019-M steam generator header-auxiliary feedwater pump steam supply motor-operated valve motor torque switch replacement.

16.

2MS-5916 auxiliary feedwater pump turbine casing pressure sentinel lockwire reinstalled.

17.

2N42 nuclear instrumentation power range channel module replaced and calibrated.

18.

2P1B-M reactor coolant pump motor repaired crack in weld.

19.

2P10B residual heat removal pump rotating assembly replaced.

20.

2PC-429C-XAT Train A pressurizer pressure to safety injection test switch replacement.

21.

2PI-4198A air lock outer door vacuum pump suction pressure indicator repaired.

22, 2PT-420B and 2PT-430 reactor coolant and pressurizer 3

pressure transmitters cleaned and fittings tightened.

23.

2R1 reactor vessel head shielding installed.

24.

2RC-508-0 reactor makeup water supply valve stroked.,

25.

2RC-538 pressurizer relief tank gas analyzer system isolation valve diaphragm replaced.

26.

2RC-581 pressurizer and reactor vessel line low point drain valve repaired.

27.

2RH-624 and 2RH-625 residual heat remcval heat exchanger outlets control position indicators installed.

28.

2RH-709B residual heat removal pump discharge valve repairs.

Q i

29.,2RH-861B residual heat removal pump suction header relief to pressurizer relief tank valve tested and setpoint adjustment.

30.

2SC-966C reactor coolant hot leg sample valve stroke tested.

31.

2SI-825A refueling water storage tank outlet to safety injection pump gasket replacement.

32, 2SI-850A&B residual heat removal pump Sump B suction valve limit switch setting adjusted.

33.

2SI-851A residual heat removal pump suction from containment sump B valve disc and seat inspection.

34, 2SI-854A refueling water storage tank to residual heat removal pump suction header check valve replacement.

35.

2SI-854B refueling water storage tank to residual heat removal suction header check valve rubber seat and disc

repair, i

36, 2SI-856B refueling water storage tank outlet to residual heat removal pump suction header valve inspection.

37.

2SI-866B core deluge injection line isolation status light indication moved.

38.

2SI-896B safety injection pump suction valve disc repositioned.

39.

2SI-897A&B safety injection test line return valve status light indication adjusted.

40 2SI-957 safety injection accumulator nitrogen header vent control valve U-bolt replaced.

41.

2SW-15A-D containment recirculation heat exchanger inlet check valves inspected.

42, 2SW-2959, 2SW-2963, 2SW-2967, and 2SW-2971 containment recirculation heat exchanger outlet relief valve replaced.

43.

2SW-4301 cavity cooling coil outlet relief valve replaced.

44, 2SW-4389 auxiliary feedwater pump discharge relief valve replaced.

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45..'2TC-405L, 2TC-406L, 2TC-407L and 2TC-408L delta flux controllers calibrated.

46.

Recalibrated 2TE-401B, SN-1046, 2TE-403A, SN-1054,-2TE-408A and SN-1059.

47.

2VNPSE-3213-0 purge exhaust fan suction control-operator instrumentfair regulator replaced.

48.

2VNPSE-3245 purge supply fan discharga control solenoid valve replaced.

49.

2W1A1 containment accident recirculation-fan field balancing.

50.

WL-1728 sump A drain valve replaced.

51, 2Z42 incore thimble seal table inspection.

refueling cavity Loop A cold leg sandbox cover gasket 52.

2Z434 inspection.

53.

Replaced 97 panelboard breakers.

54.

Nine time delay relays were replaced.

Diagnostic tests performed on seven main steam and safety 55.

injection valves.

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