ML20059J646

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Monthly Operating Repts for Oct 1993 for Point Beach Nuclear Plant,Units 1 & 2
ML20059J646
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 10/31/1993
From: Arnold R, Link B
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-93-121 VPNPD-93-193, NUDOCS 9311120306
Download: ML20059J646 (10)
v • d • e


Text

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-;y, Wisconsin; Electnc POWER COMPAin 231 W fAchgan PO Box 2046. MJwookee.WI 53201-2046 (414)221-2345 '

VPNPD-93-193 NRC-93-121

. November.4,-1993 i

Document' Control Desk U.S.

NUCLEAR 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.nonth of October 1993..

Sincerely,

/ $

sMtW Bob Vice President Nuclear Power MFB/jg

cc:

L. L.. Smith, PSCW NRC Regional' Administrator, Region'III NRC Resident Inspector

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OPERATING DATA REPORT DOCKET NO. 50-266

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DATE: 11/01/93

' I COMPLETED BY:

Richard F. Arnold TF',EPHONE :

(414).755-6193 OPERATING STATUS I

1. UNIT NAME:

POINT BEACH NUCLEAR PLANT - UNIT 1

. NOTES I'

2. REPORTING PERIOD: October - 1993
3. LICENSED THERMAL POWER (MWT) :

1518.5-4.

NAMEPLATE RATING (GROSS MWE):

523.8 l

5. DESIGN ELECTRICAL RATING (NET MWE):

497.0

6. MAXIMUM DEPEMDABLE~ CAPACITY (GROSS MWE) 509.0 i-7.

MAXIMUM DEPENDADLE 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 7,296.0 201,504.0

12. NUMBER OF. HOURS REACTOR WAS CRITICAL 745.0 6,371.6

~ 167,254.9

13. FE. ACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 667.'3
14. HOURS GENERATOR ON LINE 745.0 6,336.8 164,176.2
15. UNIT RESERVE. SHUTDOWN. HOURS 0.0 0.0 846.9,
16. GROSS THERMAL ENERGY GENERATED (MWH)-

1,130,948 9,528,325 231,265,298'

'17.

GROSS ELECTRICAL ENERGY GENERATED 383,240 3,224,970

.78,101,370.-

.18.. NET ELECTRICAL ENERGY. GENERATED-(MWH) 366,566 3,083,024 74,435,187

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19. ' UNIT SERVICE FACTOR -

100.0%

8E.9%

81'. 5 %

20. UNIT AVAILABILITY FACTOR 100.0%

86.9%

81.9%

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

'87.1% -

75.8%

22.-UNIT CAPACITY FACTOR (USING DER NET)_

.99.0%

85.0%

74.3%

2 23.. UNIT FORCED OUTAGE RATE-

0. 0 %.

. 0. 0%.

1.6%

'24.

SHUTDOWNS 1 SCHEDULED OVER NEXT 6 MONTHS..(TYPE, DATE, AND DURATION OF EACH) :

Refueling Outage, 04/02/94, 42 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 6

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POINT BEACII NUCLEAR PLANT DOCKET NO.

' 50-266' AVERAGE DAILY UNIT POWER LEVEL.

-UNIT NAME Point Beach. Unit 1

^

i-MONTH OCTOBER - 1993 DATE November 1.1993 i

COMPLETED BY R. F. Arnold TELEPIIONE 414/755-6193 i.

. AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY-POWER LEVEL POWER LEVEL POWER LEVEL

' DAY MWe NET DAY MWe NET DAY MWe NET E

1 4M 11 492 21 494 2

'490 12 492 22 492

- 3 493 13 492 23 493 4

493 14 494 24 493 5

493 15 492 25 491 6'

492 16-493 26 492 7

492 17 488

27 493 1

8 493 18 493 28 492 e

9 493'

-19 494 29 -

493 7

10 494 20 492

'30 494 31 475 I

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POINT BEAGI NUCLEAR PLANT -

Dochet No.-

50-266 Unit Name Point Beach. Unit 1 UNIT SIIUTDOWNS AND POWER REDUCTIONS :

Date November IJ 1993

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Completed By -

R. F. Arnold REPORT MONTII OCTOBER - 1993 Telephone No.

414/755-6193 Method of Shutting No.'

Date Type' Duration Reason' ~

Down Licensee Event System Component Cause and Corrective Action NA NA NA NA

'iA NA NA NA NA NA l

'F: Forced ;

2 Reason:

SMethod:

' Exhibit G - Instructions 5: 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)

' Exhibit l'- Same Source G i_ Operational Error (explain) 11 - Other (explain)

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DOCKET NO.

50-266 1

UNIT NAME Point Beach Unit 1-DATE

. November 1, 1993 l

COMPLETED BY R.

F. Arnold l

i TELEPHONE 414/755-6193 i

Unit 1 operated at approximately 492 MWe net-for the report

.l period with no significant load reductions.

Licensee Event Report 266/301 93-008-00, SW-LW-61 Determined To Be Inoperable During Surveillance Testing,.was-submitted.

e Safety-related maintenance included:

i 1.

Power range channel, N42, was adjusted while' performing an j

' instrumentation calibration procedure for the power range q

comparator channel (N-00046).

2. A capacitor in.the channel 4 (yellow) Tave Mamp to control-system I/I converter was replaced.

The installed spare was replaced with the repaired converter.

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-OPERATING DATA REPORT DOCKET NO. 50-301.

4 DATE:

11/01/93 COMPLETED BY:

Richard F. Arnold TELEPHONE:

(414) 755-6193 OPERATING STATUS

1. UNIT NAME:

POINT BEACH NUCLEAR PLANT - UNIT 2 NOTES

2. REPORTING PERIOD: October - 1993

-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):

NA

10. REASONS FOR RESTRICTIONS, (IF ANY) :

NA THI'3 MONTH YEAR TO DA'IE CUMULATIVE f

11. HOURS IN REPORTING PERIOD 745.0 7,296.0 186,289.0
12. NUMBER 0F HOURS REACTOR WAS CRITICAL 59.6 6,460.7 162,736.6
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 4.0 233.9
14. HOURS GENERATOR'ON LINE 28.8 6,420.2 160,402.7 15 ' UNIT RESERVE-SHUTDOWN HOURS 0.0 0.0 302.2 13,664 9,567,750 230',214,011
16. GROSS THERMAL ENERGY GENERATED. (MWH)
17. GROSS ELECTRICAL ENERGY GENERATED 3,110 3,281,040 78,281,160
18. NET ELECTRICAL ENERGY GENERATED (MWH) 0 3,134,297 74,620,704
19. UNIT. SERVICE FACTOR.

3.?$

88.0%-

8 6.1*: -

20. UNIT AVAILABILITY FACTOR 3.9%

88.0%

86.3%

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

88.6%

'82.0%'

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

86.4%

80.6%

23. UNIT FORCED OUTAGE RATE 0.0%

'O.3%

1.0%

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

NONE

25. IF SHUTDOWN AT'END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPe NA-

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DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER-DATED SEPTEMBER-22, 1977 4.

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POINT BEACll NUCLEAR PLANT.

DOCKET NO.

50-301 AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach. Unit 2-'

' MONTH OCTOBER - 1993 DATE November 1.1993 4

COMPLETED BY R. F. Arnold TELEPIIONE 414/755-6193-AVERAGE

. AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL.

7-DAY MWe NET DAY MWe NET DAY M We NET -

1

-2 11

-2 21

-2 2

-2 12

-2 22

-2 3

-2 13

-2 23

'4 a

.4

-2 14

-2 24

-2 5

-2 15

-2 25

-10 6

-2 16

-2 26

-11 7

-2 17 27

-13

. l 8

-2 18

-2 28

-12 9.

-2 19

-2 29.

13 10

-1 20

-2 30-

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POINT BEACli NUCLEAR PLANT DiDocket No.

50-301 Unit Name.

Point Beach. Unit 2 UNIT 511UTDOWNS AND POWER REDUCTIONS Date -

November 1.1993 '

Completed By.

R. F. Arnold REPORT MONTII OCTOBER - 1993 Telephone No.

414n55-6193 i-Method of 8

Shutting Duration Down Licensee Event System Component Cause and Corrective Action No.

Date Type' Olours)

Reason

  • Reactor Report No.

Code

  • Code' To Prevent Recurrence 3

9/25/93 5

716.2 C

1 NA NA NA Scheduled refuelmg and maintenance outage (U2R19). Major work items include inspection am! -'

eddy current testing of the steam generators, inspection of the high pressure turbine, replace breakers in safeguards motor control centers 2B-32 aral 2B42, perform as-bui't electrical walkdowns of electrical distribution buses. 2A and 2B reactor coolant pump seat inspection armi component replacement, and replace twenty one 480 V safety-related molded case circuit breakers.

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'F: Forced 2 Reason:-

.' Method:

' Exhibit G '- Instructions S: Scheduled

. A - Equipment Failure (explain) ' 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 & :

_5 - Reduced lead Previous Shutdown -

Licensing Exam 3

F - Administrative 6 - Other (explain)

Exhibit I - Same Source 4-

. G -. Operational Error (explain)

H - Other (explain).

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l DOCKET NO.

50-301

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UNIT NAME Point Beach Unit 2 DATE November 1, 1993 j

COMPLETED BY R. F. Arnold

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TELEPHONE 414/755-6193 l

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Unit 2 generator was placed back on line on October 30, 1993 after completion of U2R19 refueling and maintenance outage, i

Safety-related maintenance included:

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1. Replaced 21 480 V-safety-related molded case circuit f

breakers as part of the molded case circuit breaker' upgrade.

2.

Four rotor limit switches were installed on the motor i

operators for eight safety-related valves (CC-00719,

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'CC-00754A, CC-00759B, SI-00860C, SI-00870B, SI-00896B,-

{

SW-02908, AF-04006).

l 3.

Installed new torque switch for the motor operator on the

-l residual heat removal heat exchanger shell side inlet valve (CC-00738B).

4.

Performed amptector retrofit on the 480 V supply breaker (B52 - 03 8C) to 2B-31 primary auxiliary building motor control center.

5.

Installed hasps and locks on the switch covers and labeled' d

the switches on the "A" and "B"

train safeguards relay racks.

6.

Pre-tested, rebuilt and post-tested' snubbers HS-2501R-15, HS-2501R-49 and HS-36.

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7.

Replaced upper operating arm,. shortened set screw on~~the.

l limit switch actuator and relocated equipment label'on, main

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-steam header isolation valves MS-02017 and MS-02018.

8.

Replaced the outboard motor bearing on. safety injection pump

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9. As-built visual inspection of wiring =for instrumentation ~was.

performed on residual. heat removal heat exchangers HX-011A and HX-011B, refueling' water storage tank immersion heaters, i

safety injection accumulators T-034A and T-034B, spray add

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tank T-038, residual heat removal pumps P-010A and P-010B,.

l containment spray. pumps P-014A and P-014B, and safety l

. injection pumps P-015A and P-015B.

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10. NRC Bulletin 79-14 line walkdowns were completed for= service water piping inside containment.

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