ML20065G784

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Resubmitted Montly Operating Repts for Feb 1994 for Point Beach Nuclear Plant,Units 1 & 2
ML20065G784
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 02/28/1994
From: Arnold R
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20065G782 List:
References
NUDOCS 9404130202
Download: ML20065G784 (9)
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Text

19 OPERATING DATA REPORT DOCKET NO. 50-266 DATE:

03/01/94 COMPLETED BY: Richard F. Arnold TELEPHONE:

(414) 755-6193 OPERATING STATUS

1. UNIT NAME:

POINT BEACH NUCLEAR PLANT - UNIT 1

. NOTES

2. REPORTING PERIOD:

February - 1994

3. LICENSED THERMAL POWER (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 DEPENDAB'LE 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 672.0 1,416.0 204,384.0
12. NUMBER OF HOURS REACTOR WAS CRITICAL 672.0 1,416.0 170,134.9
13. REACTOR RESERVE SHUTDOWN HOURS

~0.0 0.0 667.3

14. HOURS GENERATOR ON LINE 667.4 1,411.4 167,051.6
15. UNIT RESERVE SHUTDOWN HOURS

'O_O O.0 846 9

16. GROSS THERMAL. ENERGY GENERATED (MWH) 982,233 2,110,584 235,592,354 i
17. GROSS ELECTRICAL ENERGY GENERATED 332,400 714,830 79,568,960
18. NET ELECTRICAL ENERGY GENERATED (MWH) 318,383 685,229 75,840,819
19. UNIT SERVICE FACTOR 99.3%

99.7%

81.7%

jg.

20. UNIT AVAILABILITY FACTOR 99.3%

99.7%

82.1%

IDNQ -

000.

21. UNIT CAPACITY FACTOR (USING MDC NET) 97.7%

99.8%

76.2%

go

22. UNIT CAPACITY FACTOR -(USING DER NET)

'95.3%

97.4%

74.7%

23. UNIT FORCED OUTAGE RATE 0.0%

0.0%

1.6%

00

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

Ny Refueling Outage,' 04/02/94, 30 Q

.2 5.

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

OQ NA 1 %.

DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977 hg

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& Q.Cf.

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POINT BEACII NUCLEAR PLANT DOCKET NO.

50-266-f(

AVERAGE DAILY UNIT POWER LEVEL UNIT NAME

' Point Beac!L Unit 1'

~

MONTII FEBRUARY - 1994 DATE March 1.1994 COMPLETED BY R. F. Amold TELEPIIONE 414/755-6193 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET -

1 493 11 492 21

'494' 2

494 12 493 22 493-3 492 13 490 23 494 4

494 14 496 24 493 5

490 15 495 25 493 6

128 16 493 26 494 7

329 17 494 27 492 8

486-18 499 28 495 9

481 19-489

+

10 493 20 495 PDF-0028a.

, 03-90)

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s er POINT BEACH NUCLEAR PLANT.

Docket No.

50-266' Unit Name 1 Point Beach; Unit 1 UNIT SHUTDOWNS AND POWER REDUcrIONS Date March 1; 1994

.-j Completed By R. F. Arnold REPORT MONTH FEBRUARY-1994 Telephone No.

414n55-6193 -

Method of Shuttmg 8

2 Down Licensee Event System Component Cause ami Corrective Action No.

Date Type Duration Reason I

2/6/94 S

4.6 H

6 NA CJ VALVEF

'Ihe unit was reduced to 2% power to facilitate identifcation of a primary vstem leak,;

Although the leak rate did not require shutdown per Technical Specifications, the pour reduction was made to adress ALARA concerns about dose rates in the primary loops. Two 2' E obe valves were found approximately 1/4 turn open. The vahes are on a drain line to the l

reactor coolant drain tank off of the excessleidownline on the *A* loop. The valves were shut, which terminated the leak. The unit was then returned to 100% power. Investigation is..

in progress to determine how the valves became partially open.

'F: Forced Reason:

' Method:

' Exhibit G - Lustructions

'2 S: Scheduled A - Equipment Failute (explain) 1 - Manual -

for preparation of

' B - Maintenance or Testing 2 - Manual Scram data entry sheets

. C - Refueling 3 - Automatic Scram LER rde (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 G - Operational Error (explaic)

H - Other (explain) e PBF-0028b (03-90)

n:

Ik' i

[ 'y-JDOCKET NO.

.50-266

' UNIT NAME Point Beach Unit 1 DATE March 1,'1994

' COMPLETED BY-R.

F. Arnold

' TELEPHONE 414/755-6193 Unit 1 operated at an average of 474 MWe_ net for the report.

period and experienced one significant load reduction.

The load reduction facilitated the identification and subsequent isolation.

of a primary system leak.

An Unusual Event was declared as a result of having both emergency. diesel generators declared out of-service.

~A Notice of Enforcement Discretion was granted to suspend a dual u'4t shutdown as required by Technical Specifications while one of the emergency diesel generators was repaired and returned to service.

LER 266/301 94-002-00 is being submitted to describe this event.

1 Safety-related maintenance included:

1.

Completed the annual maintenance overhaul of both G01 and G02 emergency _ diesel generators.

2.

Repaired the pump to motor shaft coupling on the Gol emergency diesel generator DC fuel oil pump.

u

3. A jumper wire for the brush rigging assembly for.the DC excitor for the G01 emergency diesel. generator was replaced.

'The jumper wire lugs were replaced ~during the. annual maintenance overhaul and problems associated with cable re-installation resulted in voltage fluctuations during load testing.

4. Replaced the 4.16 KV safeguards buses A05 and A06 degraded

~

voltage relays with relays that have better. accuracy and.

-improved reset characteristics.- The Agastat. time delayLrelays-for the associated degraded voltage relays were adjusted to.

O minimum time as an interim measure in. order to improve.safet

~

margin while addressing analytical questions associated with' C

the relays.

j u

5.

Installed a 4-rotor limit switch and thermal' overload ~on the, emergency diesel generator day tank inlet second-off motor operated isolation valve-operator.

1 1

1

.page 1

)

J 5.:..

m 6'. R'oplaced 26.480'VAC molded case circuit breakers as part of the breaker upgrade' program.

' 7. Replaced and calibrated the bistable for steam generator 1B j

loop-low-low /high level. controller.

i s

4

.e 1

4'.

page 2

. ~.

OPERATING DATA REPORT DOCKET NO. 50-301 DATE:

03/01/94 COMPLETED BY: Richard F. Arnold TELEPHONE:

(414) 755-6193 OPERATING STATUS

1. UNIT NAME:

POINT BEACH NUCLEAR PLANT - UNIT 2

. NOTES

2. REPORTING PERIOD: February - 1994
3. LICENSED THERMAL POWER (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.sPOWER 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 672.0 1,416.0 189,169.0
12. NUMBER OF HOURS REACTOR WAS CRITICAL 672.0 1,416.0 165,616.6
13. REACTOR RESERVE SHUTDOWN' HOURS 0.0 0.0' 233.9

= 4

14. HOURS GENERATOR ON LINE.

672.0 1,416.0 163,282.7

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 302.2
16. GROSS THERMAL ENERGY GENERATED (MWH) 992,516 2,106,235 234,477,419
17. GROSS ELECTRICAL ENERGY GENERATED 340,260 721,600 79,745,860
18.. NET ELECTRICAL. ENERGY GENERATED. (MWH) 325,847 691,165 76,021,805
19. UNIT SERVICE FACTOR 100.0%

100.0%

86.3%

20. UNIT AVAILABILITY FACTOR' 100'0%-

100.09 86.5%

21. UNIT CAPACITY FACTOR' (USING MDC NET) 100.0%

100.6%

82.3%

~i

22. UNIT CAPACITY FACTOR ' (USING DER NET) 97.6%.

98.2%

80.9%

.23. UNIT FORCED OUTAGE RATE O.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 DATE OF.STARTUP:

NA DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER.22, 1977 A

a e,r-.

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e

-,.. ~.

POINT BEACII NUCLEAR PLANT DOCKET NO.

50-301 AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Bexh. Unit 2 MONTH FEBRUARY - 1994 DATE March 1.1994 COMPLETED BY R. F. Arnold TELEPIIONE 414/755-6193 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY.

MWe NET DAY MWe NET DAY MWe NET 1

492 11 491 21 492 2

493 12 493 22 493 3

494 13 470 23 491 4

493 14 493 24 493 5

492 15 492 25 492 6'

491 16 494 26 489 7

492 17 493 27 327 8

488 18 500 28 488' 9

481 19 487 10 4 92 20 495 e

0 e

PBF-0028a

, (03-90) l.

._.,. :. -. _ J

- POINT BEACH NUCLEAR PLANT -

- Docket No.

_.f9-301 Unit Name Point Beach. Unit 2 UNIT SHITFDOWNS AND POWER REDUCTIONS Date March I.1994 Completed By R. F. Arnold REPORT MONTH FEBRUARY - 1994 Telephone No.

414/755-6193 Method of Shutting Duration Down:

Licensee Event System Component Cause and Corrective Action No.

Dare Type' Olours)

Reason'.

Reactor '

Report No.

Code' Code' To Prevent Recurrence s

1 2!27/94 S

.O B

5 NA CH PUMPB Power was reduced to 52% to facilitate the repair of a main feedwater pump. The outboard motor bearing seal was replaced because of oil leakage. The oil was leaking on the inner seal and blowing oil into the motor windings. The seat was replaced and the unit was returned to.

100% power.

f

'F: Forced Reason:-

' Method:

'-* Exhibit G - Instructions 2

S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of.

l-B L-Maintenance or Testing 2 - Manual Scram data entry sheets l

C - Refueling '

3 - Automatic Scram LER file (NUREG-0161) l D - Regulatory Restriction Continuation of E - Operator Training & -

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

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

H - Other (explain) e -

I +

r

' (03-90. ).

i.

t

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c.

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n

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. -~

e i

.DObKET NO.

50-301 UNIT NAME Point Beach Unit 2 DATE-March 1, 1994 COMPLETED BY R.

F. Arnold TELEPHONE 414/755-6193 Unit'2 operated at an average of 485 MWe net'for the' report period with one significant load reduction.

The' load reduction.

facilitated the repair of a main feedwater pump motor bearing.

seal.

Safety-related maintenance included:

i

1. Replaced the 4.16 KV safeguards buses A05 and A06 degraded voltage relays with relays that have better accuracy and improved reset characteristics.

The Agastat time delay relays for the associated degraded voltage relays were adjusted to-y minimum time as an interim measure'in order to improve safety margin while addressing analytical questions associated with j

the relays.

R 1

2. The inner seal of the outboard motor'bearingfon the "B" main feedwater pump was replaced.

The seal was leaking and was blowing oil into the motor windings.

3.

Replaced'two 480 VAC molded case-circuit breakers as.part of.

the breaker upgrade program.

i

4. Replaced the packing, brass and one new plunger cui P-002A -

charging pump.

i n

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