% ..

Point Beach Shift Operational Data surnmary September 1994,

.

Unit 1 Unit 2 .-

Day Gen XO2 XO4 XOB X27 Net MWe Avg MWe Gen XO2 XO4 XO8 X27 Net MWe Avg MWe

1 12380 502 28 1 5 11845 494 12290 504 41 1 5 11740 4892 12320 500 29 1 5 11786 491 12220 504 41 1 5 11670 486

4 3 12300 501 29 1 4 11766 490 12240 505 40 1 4 11691 4874 10770 483 29 1 5 10253 427 12200 503 40 1 5 11652 4865 12340 500 30 1 5 11805 492 12230 505 41 1 5 11679 487 .

6 12340 502 30 1 4 11804 492 12230 506 40 1 4 11680 4877 12310 502 29 1 5 11774 491 12220 506 41 1 5 11668 4868 12330 502 30 1 5 11793 491 12250 507 40 1 5 11698 4879 12280 501 31 1 5 11743 489 12180 507 39 1 5 11629 485

10 12240 500 27 1 4 11709 488 12150 504 35 1 4 11607 48411 12250 499 29 1 4 11718 488 12170 504 38 1 4 11624 48412 12310 501 29 1 5 11774 491 12210 506 40 1 5 11658 48613 12310 502 29 1 5 11774 491 12210 506 41 1 5 11658 48614 12290 501 29 1 5 11755 490 12190 506 41 1 5 11638 48515 12270 501 29 1 5 11735 489 12180 506 39 1 5 11630 48516 12390 502 29 1 5 11854 494 12140 505 39 1 5 11591 48317 12380 506 30 1 4 11839 493 12000 503 39 1 4 11453 47718 12280 494 29 1 5 11752 490 11760 501 40 1 5 11214 46719 12250 501 29 1 4 11715 488 11660 501 40 1 4 11114 46320 12260 501 29 1 5 11724 489 11580 502 39 1 5 11033 46021 12300 501 32 1 7 31760 490 11410 498 38 1 7 10867 45322 12340 502 37 1 3 11798 492 11370 500 33 1 3 10834 45123 12330 500 38 1 4 11787 491 10680 491 35 1 4 10149 423,

24 12350 501 37 1 5 11807 492 230 14 385 1 G -174 -7

25 12510 510 38 1 5 11957 498 0 0 321 1 5 -327 -1426 11960 487 40 1 4 11429 476 0 0 52 1 4 -56 -227 12260 500 79 1 4 11677 487 0 0 4 1 4 -9 028 12270 500 46 1 4 11719 488 0 0 42 1 4 -47 -2,

] 29 12270 499 42 1 5 11724 489 0 0 46 1 5 -51 -2

| 30 12260 500 39 1 4 11717 488 0 0 45 1 4 -50 -2 -r

!|

| MONTHLY TOTALS - UNIT 1 MONTHLY TOTALS - UNIT 2

Gross generation: 367450 MWhr Gross generation: 276000 MWhr

Total station service: 16164 MWhr Total station service: 13541 MWhrNet generation: 351287 MWhr Net generation: 262460 MWhrAverage daily power: 488 MWe Average daily power: 365 MWe

,

9411230220 941104 6. PDR ADOCK 0500

R

.. . ~, ._m .

*,

OPERATING DATA REPORADOCKET NO. 50-266

.

' 'DATE: 10/05/94 .

COMPLETED BY: M. B. Koudelka.

TELEPHONE: 414-755-6480OPERATING STATUS

. . . . . . . . . . . . . . . . . .

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

2. REPORTING PERIOD: September - 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. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE): na10. REASONS FOR RESTRICTIONS, (IF ANY):

na

THIS MONTH YEAR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720.0 6,551.0 209,519.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 5,925.6 174,644.5*

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 667.314. HOURS GENERATOR ON LINE 720.0 5,877.1 171,517.315. UNIT RESERVE SHUTDOWN. HOURS 0.0 0.0 846.9

. 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,089,561 8,742,192 242,223,962

17. GROSS ELECTRICAL ENERGY GENERATED 367,450 2,957,720 81,811,850

18. NET ELECTRICAL ENERGY GENERATED (MWH) 351,286 2,826,716 77,982,30619. UNIT SERVICE FACTOR 100.0% 89.7% 81.9%20. UNIT AVAILABILITY FACTOR 100.0% 89.7% 82.3%

21. UNIT CAPACITY FACTOR (USING MDC NET) 100.6% 89.0% 76.4%

22. UNIT CAPACITY FACTOR (USING DER NET) 98.2% 86.8% 74.9%23. UNIT FORCED QUTAGE RATE 0.0% 0.0% 1.5%

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):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 SEPTEMBER 22, 1977

.-

__ i--.____.--'__________- _ _ _

..

POINT BEACH NUCLEAR PLANT Docket No. 50-266Unit Name Point Beach. Unit 1 * ,

UNIT SIIUTDOWNS AND POWER REDUCTIONS Date October 5.1994Completed By M. B. Koudelka ',

REPORT MONTH SEPTEMBER - 1994 Telephone No. 414r755-6450 '

hfethod ofShuuing

Duratian hn Licensee Event System Component Cause and Corrective ActionNo. Date Type' (llours) Reason: p,3 cmp Report No. Code * Code' To Prevent RecurrenceNA NA NA NA NA NA NA NA NA NA

!

.

'F: Forced 2Reason: ' Method: ' Exhibit G - InstructionsS: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation ofB - Maintenance or Testing 2 - Manual Scram data entry sheets'

C - Refueling 3 - Automatic Scram LER file (NUREG-0161)D - Regulatory Restriction 4 - Continuation ofE - Operator Training & Previous Shutdown

Licensing Exam 5 - Reduced LoadF - Administrative 6 - Other (explain) ' Exhibit 1 - Same SourceG - Operational Error (explain)H - Other (explain)

.

t..

PBF-0028t>

(03 90)i'

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ = . . _

*..,

POINT BEACH NUCLEAR PLANT DOCKET NO. 50-266 -

AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach, Unit 1

MONTH SEPTEMBER - 1994 DATE October 5.1994

COMPLETED BY M. B. Koudelka

TELEPHONE 414-755-6480

AVERAGE AVERAGE AVERAGEDAILY DAILY DAILY

POWER LEVEL POWER LEVEL POWER LEVELDAY MWe NET DAY MWe NET DAY MWe NET

1 494 11 488 21 490

2 491 12 491 22 492,

3 490 13 491 23 491

4 427 14 490 24 492.

5 492 15 489 25 498

6 492 16 494 26 476

7 491 17 493 27 487

,8 491 18 490 28 488

9 489 19 488 29 489

10 488 20 489 30 488

t

|

'

|_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ ~

._ . . . ..

. '|,

-.,.

DOCKET NO. 50-266UNIT NAME Point Beach Unit 1DATE October 5, 1994COMPLETED BY M. B. KoudelkaTELEPHONE 414/755-6480

Unit 1 operated at an average of 488 MWe net for the reportperiod.

Licensee Event Report 50-266/94-008-00, Containment IntegrityRequirements Not Satisfied During Valve Testing, was submitted.

Safety-related maintenance included:

1. CO2 electrical control board pre-wiring for new 2A06 panel.

2. 1C075 turbine IOPS main trip panel relay 01-B replacement.

3. 1CC-V-22 and 1CC-V-23 P11A&B component cooling pump casingvent valve replacements.

4. ICS-466AA and 1CS-476AA HX-1A&B steam generator feedwatercheck valves heat tracing installation.

5. G02 emergency diesel generator relay STLO2 readjustment and.PT fuse replacements.

6. G04 emergency diesel generator starting air motor rebuilts.

7. 1N42 and 1N46 power range channel adjustments.

8. 1P2C charging pump bonnet and diaphragm replacement.

9. 1P11A component cooling pump bolts were tightened.

10. 1SI-151R-08 safety injection / containment spray full flowtest line common header pipe support addition.

- _

.

' .

.

,- -

% % % % %0692 7 066762 2 0. . . . . . . .

7 2 76 6 2 1 14 7 3 2 2 5 4,9,8E 083 5 0 , 8 88. .

V 2 2 3 9 7 03, 5I , , 5 6 3T 4 0 8a 9, 2, 4,. .

k A 97 6l L 1 1 1 1 2 8 _

e U 4 87. .

d M 2Uu 0 :

S Co 8 . .

K 4 N6 O

. - . . SB 5 A

5 E % % % % % 7R 00050.96 6 2 01 . 7 . . 3 06 55 7

0 M - . 3 9 -

3 4 4 E E 1 7 05 03 1 3 7 7 7 5 0 1V T 5 8 8 , , ,- 9 1 . . 999 9

0 / : 4 I A 5 83 0 ,, 3, 3,5 5 Y G D 8 4 0 20 B . . 6 6 6 5 2, 1 2

O. / : , ,,

O 0 D E T T 933 : RRN 1 E N E. . )

T O O R H B -T E H P A C ME L P E E A E: . .

K E P E R Y E TC T M L PO A O E . . T F ED D C T S O S

A % % % % %L 0005 09 09 002 3 0 N D. .

O7 0 5 E:

E 06 04 02 0,4,77 7 5 3 0I P TC H 2 5 5 , 7 7 7 T U A. .

N T 7 5 5 1 62 A T DI N 2 7 6 R RS O 8 2 2 U A R.

M D T ES S T)

.E . 7 S D TT A I N F E

.O H N H A O LG Ta .

U E C,

O : E T RR T A N. . . . . . . )

H E A D0 T W D N

M D I29 03 E,

T 0 T E T DI 5 5 S E P A EN 0 8 M N Y M T

T U 4 E T I S(

R 7 : T T EO - 9 ) I Y

'(

S UP 4 E N S E Q: (

W) AE T 5. 8 H E)

R N MES L H T R _) ) ) ,

A4 8 WG F A H W TT N D. : :A L9 1 3 ) S MN I ) C W M E E O O ST P9 5 2 ES I Y I MD NN M I A(

A 1 1 5 WOTT _, N T E R(_

D R MREA DA I TD CR 6 E D __A - GNR E RS D AE D E P E_TF CR ERT MD T TG E : : T( (_E Y CI U TE A X T AN L r) )_I C eTENY Y T I ( SO SANR GG E R L

T UbWW( TTI R AH R REE NN N O UA N mMM I I C T DW U E G N I I P C,

R e( GCCA S S O N ON E RS S R E LE H t S NAAP EN I RWEHE Y G OU UE E R A _

P C PRS I PP A RO ROON GG T( TV C(

O A eE OTAAC I E TD I N RY C AO F _E S WRACC HT P CTLWYE G ARRR O SB OG R N CC AU OG NR RFOO D R

EEI I I GE HND REE O TTE E D OP (

T LLL HR NRS OTE NTYC CG L N T:

S ND LG ABB R WT I U NLE CTAAAU E CU I OANCAAU S TS E R HEA AI FF TD AT OI MI I D D C OE RR VOS CLFL U E T FA P RRTRN NC TR OU R T LI A I YY OH AT E E ATE E O P OE AE ARC EB TT C DS P H RCP P LR EHS RVMTI CAI I D S N N

T EEE S E O R EER R CRI LCCE W A:

G EG ELD DE VF FRN EEE TVI AACS ON MNDTE G E NO ES HL CRAP P RN D4 DI AI EA MMN LS I RGE TEEE VAAOW T9 ET NTS LNUU A N RO R LS ACC FO U/TA R NPGMMH RO S E TS S S E D H0RR TOE E I I I C ES RB CRTS S TTTTTTES3 OE I PCMSXX WA UMAU I OOTI I I I I UN / PP NE I AEAAFAOEA OU E ONRRE NN NNNH OF0EO URLNDMMI NPRN H NRHUG GNUUUUUS NI 1 R

A. . . . . . . . . . . . . . . . . . . . . . . . .

1 2 3 4 56 7 8 90 1 2 3 4 5 6 7 89 01 2 3 4 5 T1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 A

D

.

-. '

. .

[| |l |!l| (l |

POINT BEACH NUCLEAR PLANT Docket No. 50-301Unit Name Point Beach, Unit 2 -

UNIT SHUTDOWNS AND POWER REDUCTIONS Date October 5.1994Completed By M. B. Koudelka -

REPORT MONTH SEPTEMBER - 1994 Telephone No. 414/755-6480"

-

Method of -

ShumngDuranon Down Licensee Event System Compcment Cause an! Corrective Acton

,2No. Date Type' Olours) Reason Reactor Report No. Code * Code' To Prevent Recurrences

2 9/24/94 S 165,5 C 1 NA NA NA Scheduled refucimg and maintenance outage (U2R20). Major work items include amptectorupgrades, RIIR pump rotor replacement,4-rotor linut switch upgrades, main feedwater checkvalve replacements, reactor heat shield. SI-854A&B internals replacement, Gai-tronics upgrade,G04 emergency diesel generator tie-in work, reactor coolant pump seal water flow transminerreplacement, safeguards sequence omtng relay replacements, control rod dnve mechanism controlcurrent uming modificanon, degraded gnd voltage relay work, steam generator blowdown heatexchanger replacement, and containment service water pipe supports as part of continuedBulletin 79-14 upgrades.

2'F: Forced Reason: 3Method: ' Exhibit G - InstructionsS: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of

B - Maintenance or Testing 2 - Manual Scram data entry sheetsC - Refueling 3 - Automatic Scram LER file (NUREG-0161)D - Regulatory Restriction 4 - Continuation ofE - Operator Training & Previous Shutdowm

Licensing Exam 5 - Reduced leadF - Administrative 6 - Other (explain) ' Exhibit 1 - Same SourceG - Operational Error (explain)H - Other (explain)

PBF4x)28b

(03-@)

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______- - __--__-_--______ -_ _ - _ _ _ . _ _ _ _. - - - _ _ _ _ _ .

*. . .,

.

EPOINT BEACH NUCLEAR PLANT DOCKET NO. 50-301-,

AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach. Unit 2,

'

MONTH SEPTEMBER - 1994 DATE October 5,1994.

i COMPLETED BY M. B. Koude|ka *

|'

TELEPHONE 414-755-6480

AVERAGE AVERAGE AVERAGEDAILY DAILY r ALLY

POWER LEVEL POWER LEVEL POWET LEVELDAY MWe NET DAY MWe NET DAY M M NET

1 489 11 484 21 453

2 486 12 486 22 451

3 487 13 486 23 423

4 486 14 485 24 -76

5 487 15 485 25 -14

6 487 16 483 26 -2

7 486 17 477 27 0.

8 487 18 467 28 -2

9 485 19 463 29 -2

|10 484 20 460 30 -2

-

,

+

. . - . - . . . . - .. ..

. - ,

p % 4

<. . . ..

,

!i

.

DOCKET No. 50-301UNIT NAME Point Beach Unit 2DATE October 5, 1994COMPLETED BY M. B. KoudelkaTELEPHONE 414/755-6480

Unit 2 operated at an average of 365 MWe net for the reportperiod. The unit was shutdown for a refueling and maintenanceoutage on September 24, 1994.

Safety-related maintenance included:

1. 2CS-466AA HX-1A steam generator feedwater check valvepressure seal and hinge pin gasket replacements.

2. 2P158-M safety injection pump motor meggared and main power'

cables connected for new diesel project.

3. 2SI-841A-0, 2SI-878A-0, 2SI-878B-0, 2SI-878C-O and2SI-878D-O P15A&B safety injection pump and accumulatoroperators 4-rotor limit switch installations.

!

4. 2SW-2907 HX-15A-D containment recirculation heat exchangeremergency flow control valve packing adjustment.

.

)

,

|

1

!

l

4

. . .. _ ____-_____O