ML20045A976

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for May 1993 for Point Beach Nuclear Plant,Units 1 & 2
ML20045A976
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 05/31/1993
From: Arnold R, Link B
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-93-070, CON-NRC-93-70 VPNPD-93-111, NUDOCS 9306150422
Download: ML20045A976 (9)


Text

.

W1sconsin Electnc POWER COMPANY ni a uen.;nn Pc e00046 tumuuee w Sr>oi M54) 2212345 VPNPD 111 NRC-93-0'/0 June 8, 1993 Document Control Desk U.S.

NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, D.C.

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 May 1993.

Sincerely,

-m

.I Bob Link Vice President Nuclear Power MFB/jg cc:

L.

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

1 i

t i

9306150422 930531 El f

PDR ADOCK 05000266 f4 R

PDR jf?

Asubwfho dilimsinE'kwGWkahiw N

-OPERATING DATA REPORT DOCKET NO. 50-266 DATE: 06/02/93 COMPLETED BY: Richard F. Arnold TELEPHONE:

(414}755-6193 i.

OPERATING STATUS

1. UNIT NAME:

POINT BEACH NUCLEAR PLANT - UNIT 1 NOTES

2. REPORTING PERIOD: May - 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 THIS MONTH YEAR TO DATE CUMULATIVE

11. HOURS-IN REPORTING PERIOD 744.0 3,623.0 197,831.0 12.. NUMBER OF HOURS REACTOR WAS CRITICAL 652.6 2,698.6 163,581.9
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 667.3
14. HOURS GENERATOR ON LINE 618.9 2,663.8 160,503.2
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 846.9
16. GROSS THERMAL ENERGY GENERATED (MWH) 870,753 3,964,306 225,701,279
17. GROSS ELECTRICAL ENERGY GENERATED 294,140

_1,340,680 76,217,080

18. NET ELECTRICAL ENERGY GENERATED (MWH) 279,367 1,280,573 72,632,736
19. UNIT' SERVICE FACTOR 83.2%

'73.5%

81.1%

20. UNIT AVAILABILITY FACTOR 83.2%

73.5%

81.6%

21. UNIT CAPACITY FACTOR _(USING MDC NET) 77.4%

72.9%

75.3%

22. UNIT CAPACITY FACTOR (USING DER NET) 75.6%

71.1%

73.9%

23. UNIT FORCED OUTAGE' RATE

'O.0%

0.0%

1.6%

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-

'e=

a w w w-w

--=.eny~ames tvw=

r

-sw

-e--+e-

+-.s-e--

e-A4ewu www as

-..s*m.m

.e d-

-m

-ev N

-- m

-+

u rwwh md We m m--,-am u

ie am '

e

.-W

, '- j POINT BEACli NUCLEAR PLAhT DOCKET NO.

50-266 i

J AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach. Unit 1

.I MONT11 M AY - 1993 DATE June 2.1993 COMPLETED BY-R. F. Arnold TELEP110NE 414/755 4193 l

AVERAGE AVERAGE-AVERAGE DAILY DAILY DAILY =

POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET M

_ MWe NET 1

-4 11 496 21 494 2

-12 12 495 22 495 3-

-12 13 495 23 496 4

-12 14 494 24 494 l

5

-13 15 489 25 496' 6

27 16 494 26 494 7

116 17 495 27 495 8

260 18 494 28 -

496 9

407 19 494 29 494 10 492 20 496 30 498 31 496

- PBF@28a (03-90) y-

,rw

.y

w<e4s ur -v

v-

--'Ww

+ b w

w ev*

s~

+

w,4,-

r eww

+~*

v-v

  • -*'w t vr*

-w^-

  • r"w-mes' u w v*
  • <*eer

=7-e a -- - - - -


s-

M POINT BEACil NUCLEAR PLANT Docket No.

50-266

~

Unit Name Point Beach. Unit 1.

UNIT SIItrFDOWNS AND POWER REDUCTIONS Date June 2.1993 Completed By R. F. Amold REPORT MONTil M AY - 1993 Telephone No. __414/755-6193 Method of Shatting No.

Date Type' Duration

. Reason

  • Down Licensee Event System Congonent cause and Corrective Action 1

3/27/93 125.1 C

I NA NA NA Scheduled refueling outage (UIR20). Major work items include inspection and eddy cuners testing of the steam generaton, nwchanicaland electrical upgrades of the main steam isolation salves, installation of rod drup testing equipment, amptector upgrades for 480 V bus feeder and MG set breeLers, P-30A/C/D/E circulation water pump inspections and as4 milt electrical walkdowns of reactor protection end safeguards system.

'F: Forced 2Reason:

$ Method:

' Exhibit G - Instmetions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 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 G - Operational Error (explain)

II - Other (explain)

PBF-0028b -

(03-90)

~-..

.-s

k DOCKET NO.

50-266 UNIT NAME Point Beach Unit 1 DATE June 2, 1993 COMPLETED BY R.

F.

Arnold TELEPHONE 414/755-6193 Unit 1 operated at approximately 375 MWe net for the report period.

Unit 1 generator was placed back on line on May 6, 1993 after compfetion of U1R20 refueling and maintenance outage.

Licensee Event Report 50-266/93-004-00, Containment Hatch Temporary Third Door Tied Open During Refueling Operation, was submitted.

Licensee Event Report 50-266/93-005-00, Inadvertent Engineered Safety Feature Actuation, was submitted.

1 Licensee Event Report 50-266 and 50-301/93-006-00, Containment Isolation Valve not Leak Tested in Accordance with Technical Specification Requirements, was submitted.

SuppJement 1 to Licensee Event Report 50-266 and 50-301/92-009, Component Cooling Water System Surge Tank Vent Valves Outside Design Basis, was submitted.

Safety-related maintenance included:

1.

The motor and motor bearings for safety injection pump P-015A were replaced.

2.

Shims and disc hangers were installed on the discharge check valves for service water pumps P-032A, P-032C, P-032D and P-032E.

3.

The manually veerated breaker for steam generator lA sample isolation valve control and position switch power was replaced.

4.

The "R" contact terminations for the boric acid tank selector switch (43/T-006) were check tightened.

5.

Maintained and inspected G02 emergency diesel generator output breaker.

OPERATING DATA REPORT DOCKET NO. 50-301 DATE: 06/02/93 COMPLETED BY:

Richard F. Arnold i

TELEPHONE:

(414)755-6193 OPERATING STATUS

1. UNIT NAME:

POINT BEACH NUCLEAR PLANT - UNIT 2

-NOTES

2. REPORTING PERIOD: May - 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 THIS MONTH YEAR TO DATE CUMULATIVE

11. HOURS IN REPORTING' PERIOD 744.0 3,623.0 182,616.0
12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 3,610.7 159,886.6
13. REACTOR RESERVE SHUTDOWN HOURS O.0 4.0 233.9
14. HOURS GENERATOR ON LINE-744.0 3,602.3 157,584.8
15. UNIT RESERVE'SHUTDCWN HOURS _

0.0 0.0

.302.2

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,121,723 5,381,310 226,027,571
17. GROSS ELECTRICAL ENERGY GENERATED 384,780 1,846,590 76,846,710
18. NET ELECTRICAL ENERGY Gl:NERATED (MWH) 367,914 1,767,941 73,254,348'
19. UNIT SERVICE FACTOR 100.0%

99.4%

86.'3%

-20. UNIT AVAILABILITY FACTOR 100.0%

99.4%

86.5%

21. UNIT CAPACITY FACTOR (USING MDC NET) 102.0%

100.6%

82.1%

22. UNIT CAPACITY FACTOR (USING DER NET) 99.5%

98.2%

80.7%

23. UNIT FORCED OUTAGE RATE 0.0%

0.6%

1.0%

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

Refueling Outage, 09/25/93,'50 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

POINT BEACH NUCLEAR PLANT DOCKET NO.

50-301

~.

AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach. Unit 2 MONTH M AY - 1993 DATE June 2 1993 COMPLETED BY R. F. Amold TELEPHONE 414/755-6193 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY' MWe NET DAY MWe NET DAY MWe NET -

1 496 11 496 21 494 2

496 12 496 22 495 3

495 13 495 23 469 4

496 14 495 24 494 5

495 15 497 25 495 6

496 16 495 26 495 7

497 17 495 27 495 8

496 18 495 28 495 9

495 19 497 29 494 10 4%

20 497 30 499 31 491 PBF-0028a (03-90) 1

POINT BEACH NUCLEAR PLANT Docket No.

50-301-Unit Ncme Point Beach. Unit 2 UNIT SIIUTDOWNS AND POWER REDUCTIONS Date June 2.1993 Cornpleted By R. F. Arnold

+

REPORT MONTH M AY - 1993 Telephone No.

414G55-6193 Method of Shutting Duration go n Licensee Event Systern Cornponers Cause and Corrective Action No.

Date Type' (llours)

Reason p,ygn,s Report No.

Code' Code' To Prevent Recurrence s

NA NA NA NA NA NA NA NA NA f

l

'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 Automatic Scram LER file (NUREG4161)

D - Regulatory Restriction 4 - Continuation of

- E - Operator Training &

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

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

PBF-0028b -

(03 00).

~

DOCKET NO.

50-301 UNIT NAME Point Beach Unit 2 DATE June 2, 1993 COMPLETED BY R.

F. Arnold TELEPHONE 414/755-6193 Unit 2. operated at approximately 495'MWe net throughout the report period with no significant load reductions.

Licensee Event Report 301/93-003-00 and 301/93-001-00, Monthly Reactor Protection and Safeguards and Nuclear Instrumentation systems Testing not Performed Within Required Periodicity, was submitted.

This LER was submitted as a result of the Notice of Enforcement Discretion received during the previous reporting period.

safety-related maintenance included:

1.

Adjusted cam lock, tightened set screws and replaced vent valve on the 26 ft. level containment equipment access airlock.

2.

Replaced the seal on the inner door (containment side) of the 66 ft. level containment personnel access airlock.

t 3.

Replaced the coil for the safety injection test line return position switch relay.

i 4.

The coarse level was adjusted for the 4 nuclear instrument power range channels.

i f

i w-

-