ML20086J060

Monthly Operating Repts for Nov 1991 for Point Beach Units 1 & 2

ML20086J060
Person / Time
Site:	Point Beach
Issue date:	11/30/1991
From:	Peterson D WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20086J054	List: ML20086J052 ML20086J060 ML20086J064
References
NUDOCS 9112100272
Download: ML20086J060 (8)

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OPERATING' DATA' REPORT'

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DOCKET NO. 50-266 DATE December 4, 1991 COMPLETED BY D. C.

Peterson I 73 M TELEPHONE-M14)755-2321 t3 -

J3-OPERATING STA*1U5 t)

I. UNIT'NAME:

POINT BEACH NUCLEAR PLANT UNIT 1'

. !OTES OtJ 2. REPORTING PERIOD:

h0VEMBER'1991-k.d 3. LICENSED THERMAL POWER '(MWT):

1518.'S 4.

NAMEPLATE RATING (GROSS MWE}:

523.8'.

g C1 - 5. DESIGN ELECTRICAL RATING (NET MWE):

497.

6. MAXIMUM DEPENDABLE CAPACITY-(GROSS MWE):

509.

j h % 7. MAXIMUM DEPENDABLE CAPACITY.(NETIMWE):

485.

UP 8.

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

NOT APPLICABLE

9. POWER LEVEL TO WHICH RESTRICTED, IF.ANY.(NET MWE): NOT APPLICABLE 10 REASONS FOR RESTRICTIO!*% (IF ANY): NOT APPLICABLE THIS MONTH YR TO DATE CUMULATIVE

11. HOURS IN-REPORTING PERIOD 720 8,016.

184,680

12. NUMBER OF HOURS REACTOR WAS CRITICAL 657.3 6,878.9 152,646.5

13. REACTOR RESERVd SHUTDOWN HOURS 0.0 0.0 652.7

14. HOURS GENERATOR ON LINE 643.5 6,781.1 149,684.7

15. UNIT RESERVE SHUTDOWN HOURS 0.0 9.0 846.9

16. GROSS THERMAL ENERGY GENERATED (MWH) 957,418 10,151,555 209,558,250 4

17. GROSS ELECTRICAL ENERGY' GENERATED (MWH)-

324,220 3,432,490 70,734,870 i

18. NET ELECTRICAL ENERGY GENERATED (MWH) 309,104 3,275,576 67,396,616

19. UNIT SERVICE FACTOR 89.4 8s.6 81.1

20. UNIT AVAILARILITY FACTOR 89.4 84.7 81.5 l

21. UNIT CAPACITY FACTOR (USING MDC NET) 88.5

-84.3 74.9

22. UNIT CAPACITY FACTOR (USING DER NET).

86.4 82.2 73.4

23. UNIT FORCED OUTAGE RATE 10.6 1.5 1.7

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

1 U1R19; Unit 1, Refueling and Maintenance Outage, 04/10/92 - 05/22/92

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 e

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POINT BEACH NUCLEAR PIANT DOCKET NO.

50-2M AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach. Unit 1 MONTil NOVEMBER - 1991 DATE Decemter 4.1991 ' '

COMPLETED BY D. C. Peterson TELEPlIONE 414/755-2321 AVERAGE

-AVERAGE AVERAGE DAILY DAILY DAILY '

POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MW-NET DAY MWe NET 1

494 11 490 21 492 2'

495 12 40 22 493 3

494 13 492 23 494 4

495 14 493 24 493 5

495 15 495 25 492 6

495 16 494 26 493 7

493 17 495 27 126 8

489 18 441 28

-12 9

493 19 494 29

-13 10 417 20 493 30 33 PBF-0028a (OLW)

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POINT IIEACl{ NUCLEAR PLAMP Docket No.

^M-2M Unit Name.

Point BeachdJnit 1

. UNIT SilUTDOWNS AND POWER REDUCTIONS Date

_ December 4.1991

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Comp!cted By D. C. Peterson REPORT MONTil NOVEMBER -- 1991 Telephone No.

414H55232L Ext. 361 l

Methat of Shutting.;

No.

Date Type' Duration Reason Ikwn '

liensee Ihnt System Component Cease and Conective Actson 8

911127 F

76 3

.F I

Wi!

lit Each Plant shutthmn to correct high conductivity is the steam generator caused by a condenser leakage. Condenser tubes ident.fied and repaired.

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'F: Forced Reason:

' Method:

' Exhibit G - Instructions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of II - Maintenance or Testing 2 - Manual Scram data entry sheets C.- Refueling 3 - Automatic Sciam 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

.i G - Operational Error (caplain)

II - Other (explain)

. rlmacsu

03-90) a,

1

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DOCKET NO.

50-266-UNIT NAME-Point Beach Unit 2 DATE December 4, 1991 COMPLETED BY D. C. Peterson TELEPHONE 414/755-2321, Ext. 361 Unit 1 operated at approximately 429.4 MWe not throughout this report period with one significant load reduction with unit shutdown.

During this period, Unit i experienced one reportable event in accordance with 10 CFR 50.73; LER 91-014, Turbine Runback Due to Nuclear Power Range Instrument Chr.nnel Spike.

Safety-related maintenance included the following:

replaced inverter DYOB, replaced fan on inverter DYOD, replaced valve, port connection plug and nut on *ast connection valve downstream of purge exhaust accumulator check valve, installed drip pan on actuator side of both main steam isolation valves, and rer_oved and replaced seal leakage splash guard to enable measuring clearance between bearing housing and seal for information regarding new seal on residual hert removal pump.

Attached page is a corrected copy of last month's NRC monthly report.

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OPERATING DATA REPORT-DOCKET NO. 50-301 t..

DATE Dece.tber 4, 1991'-

COMPLETED BY D.

C.

Peterson TELEPHONE (414)755-2321

' OPERATING STATUS I

1. UNIT NAME:

POINT BEACH NUCLEAR PLANT UNIT 2

. NOTES.

2. REPORTING PERIOD: ' NOVEMBER 1991

3. LICENSED THERMAL POWER (MWT):

1518.5 4.

NAMEPLATE RATING,(GROSS MWE):'

523.8

'5. DESIGN ELECTRICAL RATING (NET MWE):

497.

6. MAXIMUM DEPENDABLE. CAPACITY (GROSS MWE):

509.

I

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 TO WHICH RESTRICTED, IF ANY (NET MWE): NOT APPLICABLE 10 REASONS FOR RESTRICTIONS, (It ANY): NOT APPLI' CABLE I

L THIS MONTH YR TO DATE CUMULATIVE i

11. HOURS IN REPORTING PERIOD 720 8,016 169,465 j

12. NUMBER OF HOURS REACTOR WAS CRITICAL 431.2 6,912.2-147,996.8

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 216.7

14. HOURS GENERATOR ON LINE 362.7 6,843.7 145,763.1

15. UNIT RESERVE SHUTDOWN HOURS O.0 0.0 302.2

16. GROSS THERMAL ENERGY GENERATED (MWH) 475,898 10,237,777 208,402,186 I

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 161,700 3,409,590 70,796,850

18. NET ELECTRICAL ENERGY GENERATED (MWH) 150,913 3,340,928 67,472,994

19. UNIT SERVICE FACTOR 50.4 a5.4 86.0

20. UNIT AVAILABILITY FACTOR 59.4 85.4 86.2

21. UNIT CAPACITY FACTOR (USING MDC NET)'

43.2 85.9 81.4

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22. UNIT CAPACITY FACTOR (USING DER NET) 42.2 83.9 80.1

23. UNIT FORCED OUTAGE RATE 7.5 0.4 1.1

' 2 4. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE,.DATE, AND DURATION OF EACM):

'NONE

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHL"rDOWN DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN N14C LETTER DATED SEPTEMBER 22, 1977

PObfr BEAC11 NUCLEAR PLANT DOCKET NO-51L'M11 AVERAGE DAILY UNIT POWER LEVEL UNIT NAME -

Point Beach. Unit 2 l

MONTH NOVEMBER - 1991 DATE December 4.1091.

COMPLETED BY D. C. Peterson TFI FPilONE 414n55-2321 AVFDAGE AVERAGE AVERAGE I.2.u.t DAILY DAILY PObER L'IVEL POWER LEVEL POWER LEVEL p.AY MWe NET DAY MWe NET DAY MWe NET 1

-2

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11

-12 21 500 2

-2 12

-14 22 Sil 3

-2 13

-14 23 Mt 4

-2 14 20 24 502 5

-2 15 86 25

' 5(0 6

-7 16

-13 26 501 7

-17 17 99 27 395 8

9 18 343 28 481

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9

-O 19 m

29 477 10

-9 20 492 30 499 rur-com (0190) m

j POllW BEACH NUCLEAR PIANT Docket No.53-301

~1 Unit Name Point Beach. Unit 2 11 NIT SIIUTDOWNS AND POWER REDUCTIONS Date Decernber 4.1991 Completed By D. C. Peterson REPORT MONTH NOVEMBER-1991 Telephone No.

414/755-2221. Ext. 361 Method of Shutting h

Date Tyy'

. Duration Reason Down Ixensee Event System Component Cause and Corrective Action 2

(Ifours)

Reactd Recort &

Crwie" Code #

To Prevent Rscmn uce 1

910928 S

324.2 C

Scheduled refueling and maintenance outage, U2R17, Major work items inc!wde inspection and eddy current testing of sacam generators, inst 4tation of full fkiw test lines for residual beat removat, safety injection and containment spray pumps and increase of the steamstriven auxiliary feedwater pump mini - recreulation kne.

2 911114 S

3.8 B

1 Generator taken off hne for tuibine <wrspeed test, ecactor remained critient 3

911115 P

293 A

1 CD VALVE Steam Icaks ce mus*are seperator reheater steam supply teakoff to condenser and stearn header non-return check 4

911127 F

F 1

Power reduced to correct high conductivity in sacam generator, caused by cr%nser tube -

leak.

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'F: Forced

" 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 - Automatie Scram LER rde (NUREG-0161)

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

Predous Shutoown Licensing Exam 5 - Reduced Imd F-Administrative 6 - Other (explain)

' Exhibit 1 - Same Source G - Operational Error (explain)

II - Other (explain)

PtlF-e32Sb (0340)

DOCKET NO.

50-301 UNIT NAME Point Beach Unit 2 DATE December 4, 1991 COMPLETED BY D.

C.

Peterson TELEPHONE 414/755-2321, Ext. 361 Unit 2 started up after a refueling and maintenance outage, U2R17, to operate at approximately 210 MW9 averaged throughout this report period.

Two shutdowns occurred during this time period, a scheduled turbine overspeed test, and the other due to steam leaks.

One significant power reduction occurred as the result of a condenser tube leak.

During this period, Unit 2 experienced one reportable event in accordance with 10 CTR 50.73; LER 91-005 Both Safety Injection Pump Breakers Racked in with Reactor Coolant System Temperature less than 275 degrees Fahrenheit.

Safety-related maintenance included the following:

corrected wire label errors in blue channel of nuclear instrumentation system,-installed new valve and reset set point to 145 psi for excess letdown shell side outlet relief to prevent excessive leakage, inspected and rebuilt valve and operator and repacked both sides of operating shaft of main steam isolation valves, replaced pre-amp and set new discriminator voltage on source range detector, replaced defective switch on Loop B Train B containment pressure to safety injection test switch, replaced tier 2 on Train B containment pressure to steam line isolation test switch, replaced packing, gaskets and trim assembly on pressurizer power relief valve, replaced failed reset switch and speed detector board for turbine independent overspeed protection Channel A, completed modifications to feedwater piping supports, and replaced pressurizer liquid sample valve body.

Attached page is a corrected copy of last month's NRC monthly report.

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