ML20116K500

Monthly Operating Repts for Oct 1992 for Pbnp,Units 1 & 2.W/

ML20116K500
Person / Time
Site:	Point Beach
Issue date:	10/31/1992
From:	Link B, Peterson D WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-92-127 VPNPD-92-345, NUDOCS 9211170230
Download: ML20116K500 (10)

Text

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. Wisconsin i Electnc POWER COMPANY 231 W Mchort PO k>n 2046. Milchee WI $3 %1 (414)221-2345 VPNPD-92-345 NRC-92-127 November 10, 1992 Document Control Desk U.S.

NUCLEAR REGULATORY COMMISSIGN 3

Mail Station P1-137 Washington, DC 20555 Gentlemen:

DOCliETS 50-266 AND 50-301 MORTHLY OPEJtATING B RO3T_SS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Attached are monthly operating reports for Units 1 and 2, Point Beach Nuclear Plant, for the calendar month of October 1992.

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sincerely,

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Bob Link Vice President Nuclear Power Attachments cc:

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Smith, PSCW NRC Regional Administrator, Region III NRC Resident Inspector 170018 f

9211170230 921031 ADOCK0500g6 DR A subsdm d1%vawi Exm-Gqvntk>n

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T, OPERATING DATA REPORT 1,

DOCKET No. 50-266

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DATE: Noveeber 3, 1992 COMPLETED BY: Don C. Peterson TELEPHONE:

414-755-2321 Ext. 361

' OPERATING STATUS 1.' UNIT.NAME: POINT BEACH NUCLEAR PLANT ~ UNIT 1 NOTES

2. REPORTING: PERIOD: October - 1992 I

3..' LICENSED THERMAL POWER-(MWT):

1518.5

4. NAMEPLATE RATING (GROSS MWE):- 523.is

5. DESIGN ELECTRICAL RATINGL(NET MWE)= '497.O 6.LMAXIMUM DEPENDAELE' 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, G2VE REASONS:

na

9. POWER. LEVEL TO WHICHlRESTRICTED, IF ANY'(NET MWE): na 10.- REASONS FOR RESTRICTIONS, (IF ANY):

na THIS MONTH YEAR TO DATE t.;UMULATIVE 11.' HOURS IN REPORTING PERIOD 745.0 7,320.0 192,744.0

12. NUMBER OF' HOURS REACTOR WAS CRITICAL 731.6

-6,028.8 159,419.3

13. REACTOR RESERVE SHUTDOWN HOURS' 12.2 14.6 667.3 14.: HOURS GENERATOR ON LINE 719.4 5,946.7 156,375.4

15. UNIT. RESERVE SHUTDOWN HOURS

'O.0 0.0 846.9

16. GROSS THERMAL ENERGY GENERATEDJ(MWH).

1,083,794 8,871,709 219,521,712

17. GROSS ELECTRICAL. ENERGY GENERATED 367,510 3,020,390 74,124,120

18. NET ELECTRICAL ENERGY..GENERATEDi(MWH)

~350,898 2,882,675 70,632,448 19.' UNIT SERVICE FACTOR 96.6%

81.2%

81.1%

20.' UNIT AVAILABILITY FACTOR

~96.6%

81.2%

81. 6%..

-21. UNIT CAPACITY, FACTOR'(USING MDC. NET)'

97.1%

81.2%

,75.2%-

22. UNIT CAPACITY FACTOR:(USING' DER NET)'

94.8%

79.2%

73.7%

23. UNIT FORCED OUTAGE RATE' O.0%'

O. 4ts 1.7%

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

' Refueling / Maintenance shutdown la scheduled from: April2, 1993 to May 19, 1993..'A refueling duration of 47.~ days.,

25..IF SHUTDOWN.LT END OF REPORT PERIOD,' ESTIMATED.DATE OF.STARTUP:

na DATA REPORTED AND FACTORS CALCULATED.AS REQUESTED IN MRC LETTER DATED SEPTEMBER 22,.1977 tmv 101902 x

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a D( M M_T No

% Zu, POINT ItEArli NIT 1. EAR PIANT ATTR AG1: Dtil.Y IWIT POMR IIVE:L UNIT NAME Pat Ec.uktJHi 1 l

Movill or TofWR Pr0 DATE N<nt e hcr (. Tre COMPLETED BY D C Peterum TELErliONE 412/ N -21:1 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY PtWe NET DAY MY'; NET DAY MWeNET 1

493 11 451 21 491 2

492 12 471 22 ri:

.3 493 13 t>2 23 3 23 l

4 492 i4 491 24 E2 l

5 59 15 491 25 r23 6

339 16 493 26 to 7

491 17 493 27 402 2S t>3 8

492 18 S 33 9

492 19 54 29 491 10 493 20 472 30

• >2 31

1. 22 P!;F-00ZRa (01'M)

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POINI BliAtil NUC11IAR P1 ANT Dmket N.

%2fA Urdt Name Pomt Bcxh, Umt l' IINIT S11tTTDOWNS AND POWER REDUCTIO!ES Date Wmembcr5.192

.i Completed By D. C. Pcteru m j

REPORT MONT11 O(TOBIIR - IW2 Telephone No.

414/755-1121. Ext. %I kicameor Shwitmg No. -

' Daec Type' Duratam Reawm?

.Down i ut asce fitne

%ssem t mpreene Caec and Cormtwe Actme

'4 921005 F

25 6 A

3 9241541 CC Vahrs White testmg the t.'ess 1 x mam steam isolatsoa vatve. the B* tram e.r v*nant sent ce the tabe rperatce cycned. mteg air. reso!Ymt m the ekswre of the *A* mam steam iw&wm valve. Th,s lead to a turteme trip and reaoor trip.

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' ' F: Forced Reason:

' Method-

' ' Exhibit G - Instructions 2

1

.Si Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maink

--e or Testing 2 - Manual Scram data entry sheets i

C. Refuelk 3 - Automatic Scram LER file (NUREG41161)

D - Regulatory Restriction

4. Continuation of '

E Operator Training &.

' Previous Shutdown Licensing Exam 5 - Reduced Load z G - Operational Error (explain).

6 - Other (explain)

' Exhibit I - Same Source -

F-Administrative H

H "J-1:er (explain) :

< PUF-Q28b i J (03-90).

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i DOCKET NO.

50-266 UNIT NAME Point Beach Unit 1 DATE November 5, 1992' COMPLETEU BY D.

C.

Peterson TELEPHONE 414/755 2321, Ext. 361 Unit 1 operated at approximately 471 MWe average daily power level throughout this report period with one significant power l

reduction.

An inadvertent turbine trip to reactor trip occurred i

during main steam isolation _ valve testing on October 5.

j Safety related maintenance included the following:

-t 1.

Inrpected and replaced torque switches of safety elated motor-operated service water header r

j isolatian valves.

2.

Replaced main steam isolation valve air vent solenoid.'

The valve was found tripped after the reactor tripped.

3.

Installed static transfer ability on yellow channel 125 volt DC/120 volt AC inverter, r

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w OPERATING DATA REPORT DOCKE" No. 50-301 DATE: November 3, 1992 COMPLETED BY: Don C.

Peterson TELEPHONE: 414-755-2321 Ext. 361 OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT - UNIT 2. NOTES

2. REPORTING PERIOD: October - 1992

3. LICENSED THERMAL POWER (MWT):

1518.5

4. NAMEPLATE RATING (GROSS W*E):

523.8

5. DESIGN ELECTRICAL RATING (NET MWE):

497.0

6. MAXIMUM DEPENDABLE CAPACITY (CROSS MWE):

509.0.

7. MAXIMUM DEPEJDABLE 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 WHICl2 RESTRICTED, IF ANY (NET MWE): na

10. REASONS FOR RESTRICTIONS, (IF ANY):

na THIS MONTH TEAR TO DATE CUMULATIVE

11. HOURS IN. REPORTING PERIOD 745.0 7,320.0 177,529.0

.12. NUMBER OF; HOURS REACTOR WAS CRITICAL O.0 6,461.1 155,190.9

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 13.2 229.9

14. HOURS GE-.dTOR ON LINE O.0 6,447.9 152,937.4

15. UNIT RESC

.C SHUTDOWN HOURS 0.0 0.0 302.2

16. GROSS THERMAL ENERGY GENERATED (MWH).

O 9,684,192 219,151,349

17. GROSS EL2CTRICAL ENERGY GENERATED 0

3,327,750 74,487,130 18., NET ELECTRICAL ENERGY CENERATED (MWH)

O 3,179,792 70,999,570

19. UNIT SERVICE FACTOR O. 01b 88.14 86.1%

20. UNIT AVAILABILITY FACTOR O.0%

88.1%

86.31L

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

89.6%

81. 81k

22. UNIT CAPACITY FACTOR (USING DER NET)'

O. 01L

87. 41k

80. 51k

23. UNIT FORCED OUTAGE RATE O.0%

0.0%

1.01k

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

none

25. IF SHUTDOWI AT END OF REPORT PERIOD, ESTIFATED DATE OF STARTUP:

November 12, 1992 DATA REPORTED AND FACTORS CALCTTLATED AS REQUESTED IN NRC Lhntu " 1TED SEPTEMBER 22, 1977 Note Line 18.

Zero electrical output was recorded for the " Month", but the " Year To Date" and the Turnulative" decreased by an. amount equal to station service. (-1565 ntrs.)

NOV 101997

n POINT BEACli NUCLEAR PIANT DOCKET NO.

50-31!

AVERAGE DAILY tiNIT PO%TR IDTL UNIT NAME Poi,t Re x h. U 2.__

MONTH OCTOBER - l'N2 DATE Neve+r 5. I'n2 -

COMPLETED BY D. C Petersen TELETIIONE 414/75 5 2321 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY FOWER LEVEL FOWER LEVEL FOWER LEVEL DAY AnVe NET DAY KnVe NET DAY MWe NET 1

-3 11

-2 21

-2 2'

-2 12

-2 22

-2

-2 13

-2 23

-2 3

4

-2 14

-2 24

-2 5

-2 15

-2 25

-2 6

-2 16

-2 26

-2 7

-2 17

-2 27

-2 8

-2 18

-2 28

-2 9

-2 19

-2 29

-2 1

l 10

-2 20

-2 30 l l

31

-2 l

PBF-(X12Ea (G90) i-

se Unit Itme Point Be ch. Unit 2 UNIT SHUTDOW'VS AND POWTR REDUCTIONS D:te '

Nmember 5.1992

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Completed By D. C Peterson 3.

REPORT MO'TH OCTOBER - 1992 Telephone No.

414'755-2321. Ext. 361

}

Method of shortieg Duration beensee Event System Cc ponent Cawse and Cerve Action a

No.

Date Type' (Howrs)

Reason' peg Report Na Code

• Code' To Prevent Reevrrence

.3' 9?J925 5

745 C

1 Sched*o refwebeg and maintecatice outagt U2R11L Major =crk stens inciede inspectice a r2 eddy current test:rg of steam gua..;m., replacement of sa'ety ingecron MOV 878A, B.

d C rneters =tth 15 Ft-ib meto s; DC2 bettery panel replacemert; preve,e safeguares 48CV buses 2E3 and 2-B04 with strrppeg separation for non-safety related breakers; rnechamcal i

and elecrical modication to the main steam isolation vatwes; and chminaten of NtS tod drop te:Sme runback signal 4

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'F: Forced

' Reason-

' Method- ~

• Exhibit G - Instructions -

)

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

B -' Maintenance or lesting '

2 - Manual Scram data entry sheets

.[

C - Refuelir.g l

. 3 - Automatic Scram

'LER rue (NVREG-0161)

D - Regvlatory Restriction 4 - Continuation of E - Operator Traming &.

-. Previous Shutdown Liceming Exam -

5 - Reduced Load F - M=inieratise :

6 - Other (explain)

' Exhibit I - Same Source

. G - Operational Error (explain)

H - Other (explain)~

est.co m (03 90) '

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DOCKET 110.

50-301 UNIT llAME Point Beach Unit 2 DATE November 5,1992 COMPLETED BY D.

C.

Potorson TELEPHONE 414/735-2321, Ext. 361 7

Unit 2 was in a refueling outage during the month of October, with zero electrical output.

During this period, two reportable events were issued for Unit 2.

LER 92-003-00, one train of containment spray inoperable due to foreign

material, was reported on a

voluntary basis.

LER 92-004-00, manual reactor trip during hot control rod drop testing, was reported in accordance with 10 CFR 50.73 (a) (2) (iv).

While operating in a shutdown cooling modo during refuuling with the residual heat removal system in operation, shutdown cooling was lost for 1 minuto due to an ESF actuation.

Safety-related maintenance included the following:

1.

Miscellaneous lug replacement and tightening in the reactor protection relay racks discovered by the as-built drawing investigations.

2.

Repaired packing leak on residual heat removal to letdown isolation.

3.

Repaired leaking channel head drain plug on the

'B' eteam generator.

4.

Replaced four leaky explosive plugs in the

'A' steam generator with mechanical plugs.

5.

As part of the refurbishment modification of the main steam isolation valves the shafts were replaced.

6.

Installed 4-rotor limit switches in safety, related motor operated valves to improve accuracy of valve position indication.

7.

Replaced and calibrated NI source range channel detector.

8.

Installed a modified rotating assembly (impeller, seals, bearings) in the

'A' residual heat reinoval pump and replaced an unused seal drain line with a pipe plug.

9.

Replaced gaskets, o-rings and switches on pressurizer solenoid-operated vont valves.

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i

10. - Rowaldad a crack in the packing lantern leakoff line on 1

j residual heat removal minimum recirculation control valve.

11.

Checked and adjusted the emergency diesel generator-j safeguards load sequenced time delay relays.

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12.

Plugged thirty-six tubes in the

'A' steam generator and forty-nine tuben in the

'B' steam generator.

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