ML19343A110

Monthly Operating Rept for Aug 1980

ML19343A110
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	09/08/1980
From:	Goodman L DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML19343A109	List: ML19343A108 ML19343A110
References
NUDOCS 8009160253
Download: ML19343A110 (10)

Text

.--

G m)

OPERATING DATA REPORT 50-409 DOCKET NO.

DATE 09-08-60 COMPLETED BY L.S. GOODMAN TELEPHONE 6nR-689-2331 OPERATING STATI!S N"

1. Unit Name: La Crosse Boiling Water Reactnr

2. Reporting Period: 1000, 80-01-08 to 2400. 80-31-08 165

3. Licensed Thermal Power IMWt):

65.3

4. Nameplate Rating (Gross MWe):

50

5. Design Electrical Rating iNet MWe):

t>. Maximum Dependable Capacity (Gross MWe):

50 48 i

7. Masimum Dependable Capacity (N+t MWet:

S. -!f Changes Occur in Capacity Ratings tirems Number 3 Through 7) Since Last Report. Gise Reasons:

9. Power Lesel to 7.lich Restricted.lf Any (Net M%el:

10. Reasons For Restr.ctions. If Any:

This Month Yr..to Date Cumularise

11. Hours In Reporting Period 744 1855 94.970

12. Number Of Hours Reactor Was Critical 337.0

.. np 9

[g_ c;ng _ a

13. Reactor Resene Shutdown Hours 0

0 4,JJ.

14. Hours Generator On.Line 264.8 4501.8 57 506.6 0

0 7J

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 32.466.7 597.266.4 1 1R7.046.9

~

17 Gross Electrical Energy Generated (MhH) 8.695 _ _ _ _ _.

172.871 2.372.003 lb. Net Electrical Energy Generated IMwH) 7,d96 160,797 2.193.532 35.6 76.9 61 6

19. Unit Senice Factor

20. U tit Asailability Factor 35.6 76.9 E0. 6

21. Unit Capacity Factor (Using MDC Net) 21.0 57.2 4_11 20.2 54.9 46.'

22. Unit Capacity Factor iUsing DER Net,

23. Unit Forced Outage Rate 64.4 14.2 7,1

24. Shutdowns Scheduled Oser Nest (> Months aType. Date and Duration of Each p-ESTIMATED REFUELING OUTAGE. NOVEMBER 22J930 (6 Weakd

25. If Shut Down At End Of Report Period. Estimated Date of Startup: _dANUARY.3, 1981 2tt Cmts in Test Status a Prior to Commercial Operation Forecast

\\chies ed INITI \\ L CRITICA LI TY INITI \\L ELECTRICITY COMMERCI\\l OPER \\ TION i - -,

soo91co 2 53 y.

.. ~

,,y

---m

-,. -g-

-w

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-409

!.ACBWR UNIT 09-08-80 DATE L.S.G000 MAN COMPLETED BY 608-689-2331 TELEPHO.NE ucNTil _ AUGUST 1900 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL tMWe-Net)

(MWe-Net) 0 I7 1S 0

't 37 12 19 4

37 20 17 21 19 ri 37 22 12 7

37 23 0

s 13 24 0

9 0

0 25 0

to 26 0

27 0

28 0

13 0

0 29 la 0

0 30 15 0

31 0

0 r e, INSTR UCTIONS On :his tormat.hst the nerage daily umt power lesel in MWe Net for each day in the reporting m.. nth. Compute to tr:e nearest whde nwgawait.

19/77)

1 of 2

^

>I 80 COMPI. LIED sty L.S. GOODMAN Rt Pon: mon sil August 1980 Ettrilost 608-689-2331 1

3 h

I it canct CJtese A ('utles like D>ie 5

3; a

na i,<..

o a

44,,,,n...

$5 5

j ;f3 Rep.n o -

S0

}'

l'sesent Recurecaus c

b 80-07 08-08-80 F

253.7 A

3 NA CJ INSTRU FORCED CIRCULATION PUMPS TRIPPED DUE TO LOSS OF SEAL INJECTION FLOW. LOSS OF SEAL INJECTION FLOW WAS CAUSED BY LOW LEVEL IN RESERVOIR DUE TO LEVEL CONTROLLER MALFUNCTION. SEAL INJECT RESERVOIR LEVEL CONTROLLERS AND INDI-CATORS WERE RECALIBRATED AND THE SYSTEM TESTED WITH SATISFACTORY RE-SULTS. DURING THE SliUTDOWN A FLANGE LEAK ON CONTROL' R00 DRIVE MECHANISM

1. 28, Tile 1A FCP SEAL, AND THE GLAND i

STEAM GENERATOR WERE ALSO REPAIRED.

80-08 08-22-80

'F 225.5 A

3 NA CH INSTRU THE SHUTDOWN RESULTED WHEN REACTOR FEED PUMP 1A TRIPPED DUE TO ELECTRIC-AL S110RT ON A PRINTED CIRCUIT CONTROL 4

CARD CAUSED BY WATER ENTERING CCNTROL ENCL 0SURE. DECONTAMINATION OF OVE_R _

(Con'd on 2 of 2).......

1 ienAeJ Ri asini.

McIloid.

I'sliiini (;. leise rinsisiisis S< hcJuicJ A 1.tmpment I a fuse (1 y:li.n) 1 M.inual 1.n Picp.uainen. I Data H Maintensine oi Iesi

'. M.anual S sam.

I nin Slictis 10 1 icemce 0-Rc fueling 4-Aulinn.itic S s.em.

I seni l<ep.nt il l R l l ite (W Rl (,

l} NfgtulJttu) NhlflLitent 4 IllitCs ll hplJHit Olhil 1 Opeldlin IIJillling', d I hef tst* I %JtLH44Jtit*86 I

l' At.lIllillhl s Jll% t' G Opes.sii.inal I inn 11 splam t i statut 1 S.n ne S..u n e t*8/ 77 6 ll Othes il splamt

2 of 2 h

h i

o tlNil SiltilDOWNS ANI) POWI R HI DUrllONS ACB J o6 Ud-e Dut _Q9-08-8fL 00MPl.t IED BY L.S. GOODMAN MIIUR I MONiil AUGUST 1980 101.1 PiloNE 608-689-2331__

~s-

}

h I konset

['t

-(,

fausc d ('ntictitte Daie l-3g 4

2s&

lacni g

p'?

A6 son to 3:

e 3i & =!

ltep...i e av heveni Returien.c 3

u 6.

HEAD FLOOR CAUSED WATER TO DRIP THROUGH SMALL UNSEALED CONDUIT CHASE.

THE CONDUIT CllASE WAS SEALED. WHILE THE PLANT WAS SHUT DOWN, MAINTENANCE WAS ALSO PERFORMED ON THE SEAL IN-JECTION SYSTEM AND THE MECHANICAL SEALS IN CONTROL R0D DRIVE MECHAN-ISMS NOS. 5 AND 21.

l 2

1 4

I l'oted Reason.

Mello.J '

I statut G - Instenstains s S beduled

\\ l.guipment I aihue (I splam) 1 Manual f.n Peepai.sti..n..I l)ata B Maintenance or Tes:

?-Manual S iam.

I ntes Shecis to: 1.icemce C Refucimg L Automata Stam.

I sent 1(ep..si il I 10 f.!c (Nt Hi 4 D Regulains> ltesisittn.n 4 Othen11silam)

O t til i I Opcsaios Daming & I ascuse I sanunation i AdiminbldJlltE*

5 G Opcsati..nal i e n : 11 splain t I sintot I Same S..uise es/77 11 Gibee 11 splam)

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AUGUST 1980 At the onset of the Aucust 1980 reporting period, power generation was continuing at 85% Reactor Rated Thermal Dower (37 MWe-Net).

level has been scheduled to extend This operating until refueling becemes necessary. care if fe to stretch optimum production On August 8,1980, at 0843, the reactor automatically shut down on low seal inject flow. power-to-flow when the Forced Circulation Pumps (FCP) tripped due to but was manually shut dcwn at 1518 to repair a flange leak on Rod Drive Mechanism No. 28.

During the shutdcwn, corrective maintenance was also performed on the 1A FCP teal and the gland steam generator.

At 0940 on August 17, the reactor was returned to critical.

August 18, the LACBWR turbine-generator wcs cent.ected to the DPC grid and At 2225 on slow escalation cemenced.

On August 22 at 1430, the reactor autenatically shut down when the IA Reactor Feed Pumo (RFP) tripoed due to water dripoing onto and shorting out a porti the D.FP centrols.

washed and water had dripoed through a conduit chase, which sealed.

prior to the shutdown.The olant had achieved 55". Reactor Rated Themal Power (2 At 1712 on August 24, the reactor was returned to critical August 25 at.12% Peactor Rated Thermal Power, a scram occu,rred when the but at 1449 on Forced Circulation Pumps tripped due to low seal injection leakoff flow, M en The low leakoff flow cordition occurred because the Sea bypass valves did not compensate fast enough to maintain sufficient flow to the FCP's.

The bypass valve contrcilers were checked thoroughly and tested with satisfactory results.

At 1750 on August 25, the reactor was returned to critical, but at 2056 it was manually shut down due to a mechanical seal leak on Upper Control Pod Drive *21.

of the August 1980 reporting period for seal recair work.The plant are indicated on the attached Instrument and Electrical Ma Mecnanical Paintenance listings.

L.

.. ~.. -....

4

[

. D.lllf E H 3 8 I M E N I N 'I' j i l P fi;>

'it. II:Pt n!

opI Ar.1 MI I I!NC I I #**

t'/ l!.ll MilRI

. f *l l u

( 7.M 9 RI SUI I CCRRE CT IM i.i~ '

f'",fi"I'.T.

., SHUTDOWN CONDENSER FACILITY CHANGE LER REMOVED VALVE AND UNTESTED FITTING WELDED TEST CHA"BER ON j

NO. 22-80-1 80-05 lWITH. CAP.

PUMP; REPLACED 1/2" LINE

]

(MR 3295)

-l LOWER CRD IN POSITION #5 PREVENTIVE OUTAGE NA NA PERFORMED PREVENTIVE i (FRAME #20).

(MR 3313)

.80-07 MAINTENANCE TESTED AND STORED FOR SPARE UPPER CRD IN POSITION #28 CORRECTIVE OUTAGE FLANGE LEAK EXCESSIVE LEAKAGE PERFORMED CORRECTIVE-(HR 3306) 80-07 AND PREVENTIVE MAINTEN-ANCE AND REINSTALLED 1A-FORCED CIRCULATION CORRECTIVE OUTAGE UPPER MECHANICAL EXCESSIVE LEAKAGE REPLACLD UPPER SEALS, PUMP (MR 3306) 80-07 SEALS WORN FACE SEAL RING, SEAL SEAT RING, MECHANICAL a

SEAL AND 0-RINGS OOFF-GASAIREJECTOR FACILITY CHANGE OUTAGE NA NA INSTALLED 2 " GATE d

NO.

55-80-2 80-07 VALVE IN LOOP SEAL (MR 3320)

}ilB SEAL INJECT SUCTION CORRECTIVE OUTAGE VALVE STEM ON LOSE AIR FROM INSTALLED NEW BLADDER

{; BLADDER (MR 3316) 80-07 BtADDER LEAK BLADDER GLATID STEAM GENERATOR CORRECTIVE OUTAGE-GASKET-STEAM STEAM LEAK AT INSTALLED NEW GASKETS (MR 3192) 80-07 CUT FLANGE ON EACH SIDE OF HEAD ljWELLNO.4 l CORRECTIVE

.NA PR0 KEN DISCl!ARGE LOSS OF WELL INSTALLED NEW 3" x 18' (MR 3241)

PIPE WATEf:

PIECE OF PIPE

iUPPER CRD IN POSITION #21 CORRECTIVE OUTAGE MECHANICAL SEAL EXCESSIVE SEAL PERFORMED CORRECTIVE AND-(MR 3348) 80-08 FACE CUT LEAKAGE PREVENTIVE MAINTENANCE jj AND REINSTALLED

){UPPERCRDINPOSITION#5 CORRECTIVE OUTAGE MECHANICAL SEAL EXCESSIVE SEAL PERFORMED CORRECTIVE AND '

(MR 3348) 80-08 FACE CUT LEAKAGE FREVENTIVE MAINTENANCE AND REINSTALLED e

, it

l of 2 INSTRUMENT AND ELECTRICAL MAINTENANCE LER OP

'UfTURE OF DU1AGI MAI i t!flCT 10N EQUIFMENT MAINTillAHLi f.h!11'.l p CAUSI RLSULT CORRECTIVL ACT!d SECURITY SYSTEM LORRECTIVE NA BURN-0VT NO AUDIBLE INDICA-REPLACED EXPLOSIVE MR3272 MR3289 l

TION DETECTOR SPEAKER f

SECURITY SYSTEM CORRECTIVE NA MISALIGNMENT POOR OUALITY ADJUSTED CCTV CAMERAS MR3294 PICTURE

1. 6 AND #8 I

SEAL INJECTION SYSTEM CORRECTIVE OUTAGE TEST REQUEST COMPLETED TESTS COMPLETED OPERATIONAL MR3299 80-D8 TEST TURBINE OIL Pt;MP BREAKER CORRECTIVE OUTAGE BURN-00T BREAKER IN0 PERATIVE REPLACED SPRING RELEASE

{

MR3301 80-07 COIL I

WASTE WATtT ) UMP GAUGE CORRECTIVE OUTAGE PLUGGED INLET GAUGE IN0 PERATIVE REPLACED GAUGE MR3211 80-07 FIRE DETECTION SYSTEM PREVENTIVE OUTAGE TEST DUE COMPLETED TEST COMPLETED FIRE DETECTOR 80-07 TEST SAFETY SYSTEM PREVENTIVE OUTAGE lEST DUE COMPLETED TESTS CMPLETED SAFETY SYSTEP 80-07 TECH. SPEC. TESTS FOR CH 1, 2 AND WATER LEVEL 43 SEAL INJECTION RESERVOIR CORRECTIVE OUTAGE TEST REOUESTED COMPLETED TESTS TESTED ALL CONTROL MR3225 80-07 FUNCTIONS CONUUCTIVITY RECORDER CORRECTIVE OUTAGE NORMAL USAGE INCORRECT PRINTOUT CLEANED SWITCH AND MR3328 80-07 SLIDE WIRE SECURIiY SYSTEM GATE CORRECTIVE NA BROKEN SWITCil UNEXPECTED GATE REPLACED CONTROL SWITCH MR3323 CLOSURE MR3329 SECURITY SYSTEM CAMERA CORRECTIVE NA MISALIGNMENT P00R PICTURE REALIGNED CAMERS 1 & 7 1 AND 7 MR3339 FORCED CIRCULATION PUMP CORRECTIVE OUTAGE BROKEN CONNECTOR INCORRECT READOUT REPLACED DETECTOR VIBRATION DEVICE MR3332 80-07 HYDR 0 GEN ANALYZER CORRECTIVE NA CONTAMINATION IMPROPER READING CLEANED AND CALIBRATED MR3334 SYSTEM MAIN EXCITER AUTO VOLTAGE CORRECTIVE OUTAGF BURN 0UT NO AUTO EXCITATION REPLACED B00ST AMPLIFIER CONTROL MR3333 80-07 CONTROL

I 2 of 2 INSTRUMENT AND ELECTRIrAL MAINTENANCE

= _ - -. -

NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTIO:i DIESEL FIRE PUMP CORRECTIVE LER LOW CELL ON BAT-REPLACEMENT DUE REPLACED START MR3330 80-08 TERY ^

BATTERIES l

NUCLEAR INSTRUMENTATION PREVENTIVE NA TEST DUE COMPLETED TESTS COMPLETED N-5 THROUGH N-9 PLUS HOT SHORT CONTROL ROD DRIVE 28 CORRECTIVE OUTAGE UNKNOWN N0 GAS PRESSURE REPLACED PRESSURE MR3341 80-08 READING TRANSMITTER SECURITY SYSTEM ZONE 10 CORRECTIVE NA MISALIGNMENT NO ALARM ADJUSTED MAGNETIC MR3326 SWITCH SECURTTY SYSTEM STACK CORRECTIVE NA UNKNOWN NO ENTRY ADJUSTED CARD READER SHACK CARD READER MR3338 FEED PUMP CONTROL CORRECTIVE OUTAGE CONTAMINATION &

AMPLIFIER BURN-REPAIRED CONTROL MR3342 80-08 ELECTRICAL SHORT OUT AMPLIFIERS CONTROL R00 DRIVE #28 CORRECTIVE OUTA55~~ WATER IN TRANS-DEFECTIVE TRANS-REPLACED TRANSMITTER MR3313 80-07 MITTER MITTER CONTROL R3D DRIVE CORRECTIVE OUTAGE DEFECTIVE SWITCH HARD OPERATION REPLACED SWITCH WITH

~~

SELECTOR LWITCH MR3335 80-08 NEW UNIT NUCLEAR li4STRUMENT CORRECTIVE OUTAGE INOPERATIVE INCORRECT READING REPLACED TUBES AND CH. N-1 MR3347 80-08 ON METER INSTALLED SPARE FORCED CIRCULATION PUMP CORRECTIVE OUTAGE INOPERATIVE NO READING ON REPAIRED OPEN WIRES ON TEMPERATURE READOUT IB MR3343 80-08 METER THERMOCOUPLE TURBINE ROTOR JACKING CORRECTIVE OUTAGE WEAR SWITCH IN0PERA-REPLACED PRESSURE SWITCH GEAR INTERLOCK MR3336 80-08 TIVE UNDERWATER LAMPS CORRECTIVE OUTAGE UceGE BURNED OUT LAMPS REPLACED LAMPS MR3355 80-08

Pg. 1 of 2

' REFUELING INFORMATION REOUEST 1.

Name of Facility:

La Crosse Boiling Water Reactor (LACBWR) 2.

Scheduled Date for Next Refuelina Shutdown:

The tentatively scheduled date for the next refueling shutdown (EOC-VI) is November 22, 1980.

3.

Scheduled Date for Restart Followino Refuelina:

The tentatively scheduled date for subsequeid reactor startup is January 3, 1981.

4.

Will Refuelina or Resumotion of Operation Thereafter Recuire a Technical Specification Change or Other License Amendment?

If answer is yes, what in oeneral, will these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety cuestions are associated with the core reload (Ref.

10 CFR Section 50.59)?

If no such review has taken olace, when is it scheduled?

No Technical Specification. Change or license amendment will be needed for refueling or subsequent resumption of operation. The Safety Review Committee review of the reload fuel design and core configuration will be conducted prior to reload.

5.

Scheduled Date(s) for Submitting Procosed Licensino Action and Supoorting Information.

NA 6.

Important Licensing Considerations Associated with Refueling, e.g.

New or Different Fuel Design or Supolies, Unreviewed Desion or Performance Analysis Methods, Sianificant Chances in Fuel Desian, New Ooerating Precedures.

None 7.

The Number of Fuel Assemblies (a) in the Core and (b) in the Soent Fuel Dool.

Core Loading:

72 Fuel Assemolies Spent Fuel Storage Pool Loading:

133 Irradiated Fuel Assemblies

4

• Pg. 2 of 2 REFUELING INFORMATION RE00EST - (Cont'd) 8.

The Present Licensed Scent Fuel Pool Storage Capacity and the Size of any Increase in Licensed Storage Capacity that has been Requested or so Planned, in Number of Fuel Assemblies.

LACBWR is presently in the process of increasing the spent fuel pool storage capacity from 134 to 440 fuel assemblies.

9.

The Projected Cate of the last Refueline that can be Discharged to the Spent Fuel Pool Assuming the Present Licensed Capacity.

1990

._