ML19209C221

Monthly Operating Rept for Sept 1979

ML19209C221
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	10/04/1979
From:	Goodman L DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML19209C219	List: ML19209C218 ML19209C221
References
NUDOCS 7910120218
Download: ML19209C221 (7)

Text

9 OPERATING DATA REPORT DOCKET NO. 50-409 DATE 10-04-79 COMPLETED BY I 9 r:nnnMAN TELEPHONE AnA-684-2331 OPERATING STATUS

1. Unit 5ame: La Crosse Boilino Waar Reactor Notes

.:. Reporting Period: 0000 79-01-09 to 2400 74-30-04

3. Licensed Thermal Power (MWt1:

165

4. Nameplate Rating (Gross MWe):

65.3 I

5. Design Electrical Rating (Net MWe):

50

6. Masimum Dependable Capacity (Gross MWe):

40

7. Maximum Dependable Capacity (Net MWe):

48

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

9. Power Level To which Restricted. !f Any (Net MWel:

48 MVe-Net

10. Reasons For Restrictions. lf Any:

SELF-lMPOSEli RESTRICTION DUE TO NUCLEAR INSTRUM2NTA-TION NOISE AT HIGHER POWER LEVELS.

This Month Yr..to.Date Cumulatise

!!. Hours in Reporting Period 720 6641 86.o06

12. Number Of Hours Reactor Was Critica!

R76-3 LAn6 1 CC 7Ay e

13. Reactor Reserve Shutdown Hours 0

0 478

14. Hours Generator On-Line 521.4 4319.2 51.037.7

15. Unit Reserve Shutdown Hours 0

0 79

16. Gross Thermal Energy Generated (MWH y 62.968 481.392 7.018.635

17. Gross Electrial Energy Generated (MWH) 18,398 126,508 1,962.916 137.552 2.119,861

18. Net Electrical Energy Generated (MWH) 17,044

19. Unit Service Factor 72.4 65.9 58,7

20. Unit Availability Factor 72.4 65.9 58.7

21. Unit Capacity Factor (Usmg MDC Net) 49.3 40.2 47.0

22. Unit Capacity Factor (Using DER Net) 45.8 38.6 45.I

23. Unit Forced Outage Rare 27.6 13.1 6.2

24. Shutdowns Scheduled O=er Nett 6 Months (Tvne. Date,and Duration of Fach p:

REFUELING SHUTDOWNt MA'CH 1 1980. 6-8 WEEKS DURATION.

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

7 10

26. Units in Test Status ePrior Io Commercial Operation s:

Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY CO%l%IERCI A L OPER A flON p.-,

l'I u 121 alf 7910120

50-409 L

llNil SilUIDOWNS AND POWER Ri DUCilONs IMKKET NO.

l LACBWR q

UNIT NAhtE 1

DATE 10-04-79 COMPLETED BY L.S. GOODMAN Rf PORI MONTil SEPTEMBER 1979 TELEPilONE 608-689-7111 5?

'b d Eh 1.icenset E g, k

Cause & Coereciise No.

Daie i

3g i

is&

Eveni 37 s.T Aoion in 35=

Repois a m' O E'

Picsens Recurrente g

v 6

79-12 79-09-04 F

136.5 A

1 NA CB VALVEX The reactor was shut down to permit repair of a packing on the 1A Forced Circulation Pump Discharge Bypass Valve. The valve was repacked.

Maintenance was also performed on the turbine governor control system.

79-13 79-09-28 F

62.2 A

3 NA RB CRDRVE liechanical seal leakage in Upper Control Rod Drive Mechanism #10 led to seal leakof f water accumulating on a scram solenoid causing it to short, resulting in a scram.

I 2

3 4

I Forced Reason.

kleshott:

I minbit G - Instinctions S Ssheduled A 1quipment I ailure(Explain)

!-Manual for Pieparaison ot Data

~

ll Maintenance or Test 2-Manual Scrain l'.nto Shee S los 1.icensee C Refueling

3. Autonutic Sivain.

Event Repois eI i Rn File tNtiRI G-D Regulas.ny Resisitison 4-Other I1.x plain 1 01oi1 1 Opciaio Training A l esense I ununation s

I:- Ad rninistialis e 5

y G Operaisonal 1.oror 11 spl.on) l'shibit 1 Saine Source 19/77) ll Other il splain)

N

r LNH SHUTDOWNS AND POhER REDUCTIONS INSTRUCTIONS This report should desenbe all plant shutdowns durmg the m accordanse with the table appearing on the report form.

report period. In addemn. it should be the source of explan-If category 4 must be used. supply bnef comments.

anon of significant dir m average power levels. Each sigm-ficant reduction m power level (greater than 20% reduction LICENSEE EVENT REPORT :r.

Reference the appbcable m average daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportable occurrence pertaming to the outage or power reduction. Enter the first four parts (event year, sequential should be noted, even though the umt may not have been shut down completely. For such reductions in power level, report number. occurrence code and report type) of the five l

the durat.on should be bsted as zero,the method of reduction part designation as described in item 17 of instructions for should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This information may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, smce should be used to provide any needed explanation to fully further investigation may be required to ascertain whether ur describe the etreumstances of the outage or power reduction.

n t a reportable occurrence was tr.volved.) If the outage or power reduction will not result in a repostable occurrence.

NUSt BER. Tlus column should mdisate the sequential num-the positne indication of this lack of correlation should be ber assigned to each shutdown orsigmticant reduction m power noted as not applicab'e (N/A).

for that calendar year. When a shutdown or significant power SYSTESI CODE. The system m which the outage or power redu, tion begms m one report penod and ends m another, reduction onginated sh' uld be noted by the two digit code of o

an entry should be made for both report renods to be sure all shutdowns or sigmficant power reductions are reported.

ba G - Inuruenons for Pieparation of Data Entry Sheets Until a unit has achieved its first power generation. no num-f r Licensee Event Report (LER) File (NUREG-0161 L her shouki'.e assigned to each entry.

Syuems that do not fit any existmg code should be designa-ted XX. The code ZZ should be used for those events where DATE. This column shuuid mdioate 'he date of the start a s> stem is not appheable.

of each shutdown or signitieant power reduction. Report as year. month. and day. August 14.1977 would be reported CON!PONENT CODE. Select the most appropnate component as 70514. When a shutdown or sigmticant power reduetton from Ethibit I instructions for Preparation of Data Entry becms in one report period and ends m another, an entry should Sheets for Lisensee Event Report (LER) File (NUREG Olol L be made for both report penods to be sure all shutdowns ustnc the followmc entrena:

or sigmticant power reductions are reported.

~

TYPE. L se "F" or "S" to mdicate either " Forced" or " Sche-duied.' respectivet), for each shutdown or sigmticant power B.

If not a component failure, use the related component reduenon. Forced shutdowns melude those required to be e.g.. wrong valve operated through error: list vahe as mitiated ey no later than the weekend followmg discover) oomponent.

of an ott-normal condition. It is recogmzed that some Judg.

ment is required m categonnng shutdowns m tius way. In C.

If a cham of failures occurs, the first component to mab general. a torced shutdown is one that would not have been funetton should be listed. The sequence of events. melud.

sumpieted m the absence of the condition for which corrective mg the other components whim 1.d. should be desenbed action was taken.

under the Cause and Correctra 4. ton to Present Recur-rence column.

DURATION. Self.e splanatory. When a shutdown extends beyon the end or a report penod. count only the time to the Components that do not fit any existmg code should ne de.

signated XXXXXX. The code ZZZZZZ should be used for end of the report penod and pieg up the ensuing down time eIents where a component designation is not appheable m the followmg report renods. Report duration of outages rounded to the nearest tenth er an hour to fasditate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

The sum of the total o.itage hours plus the hours the genera-RENCE. Use the column m a narrative fastaon to amphis o:

tor was on hne should equal the gress hours m the reportmg penod.

explam the circumstances of the shutdown or power reduction.

The column should melude the specific cause for each shut.

down or significant pnwer reduction and the immediate and REASON. C.ategorve by settei Jeugnatmn m awordance ontemplated long term corrective action taken. If appropn-woh'the table appeanne on the report form. It category H are. This column should also be used for a description of the must be used. supply bnet somments' maior satety-related corrective mamtenance performed durmg

\\tETHOD OF SHi" IING DOWN THE RCACTOR OR

1. ""I '# or power reduction meluding an identification at the enuca.

REDUCING POWER rateern,e b3 number deugnatwn i path activuy and a report of any single release of radioastnity or smcle radiation exposure spesthealh assoct l%te t hat tim Jitten f rom the F Jison Fle,ine Institute ated wnh the outace which acsounts for more than 10 perant tt t h delimtions os "For ed Partial Outace end " Sche.

of the aUowaole annual salues:

s amcJ Pa:tial Outaec I. r ' hew

.o I i ! u>c3.,,hange or For long testual reports contmue narratne on separate paper

. 0 \\ln a, the breA pmt l o-.ane. mw t 1 reactors JO Nin and iets iena rl e shutdow n m power reJ a non m ou 3o smail a. hance a

i n.a rai ne A

AVERAGE DAILV UNIT POWER LEVEL DOCKET NO.

50-409 LACBWR UNIT 10-04-79 D.*TE L.S. GOODMAN C04fPLETED BY 608-689-2331 TELEPHONE

\\lONTH SEPTEMBER 1970 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 4%IWe Neti (5fWa-Net) 39 17 32 1

2 39 18 34 3

3E 19 36 4

0 20 38 5

0

,3 39 6

0 39 40 o

33 8

n 24 40 9

1 25 43 10 13 26 43 11 17 27 43 1:

21

s 18 13 2

29 0

26 14 30 0

28 15 3,

16 30 INSTRUCT 10NS On this forrnat. list the average daily unit power levelin NfWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

u773

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE SEPTEMBER 1979 At the onset of the September reporting period, power generation was at a reduced level of 85% Reactor Rated Thermal Power (39 MWe-Net).

The power level has been reduced to stretch optimum pro-duction until March 1980 to extend core life.

The reactor was shut down on September 4, 1979, to investigate and verify nature of a water leak in Forced Circulation pump cubicle lA.

It was determined that the water leak was originating through a packing on the 2-inch bypass valve around Forced Circul-ation Pump Discharge Valve lA.

Following repacking of the valve and minor preventive maintenance on the turbine governor control system, the reactor was taken critical at 1530 on September 7th.

The turbine generator was synchronized to the DPC grid at 1905 on September 9th.

Power escalation continued until September 25th.

A maximum power level of 97% Reactor Rated Thermal Power (47 MWe-Net) was reached and held for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> for the annual MAPP* Rating Test.

Power was then decreased to 93% Reactor Rated Thermal Power (43 MWe).

Operation continued at this power level.

At 0946 on September 28th, a reactor scram occurred due to an electrical short of the scram solenoid on CRD #10.

This was caused by water accumulating on the solenoid as a result of excessive leak-age from the mechanical seal in the upper control rod drive mechanism.

The plant remained in a shutdown condition for the duration of the reporting period in order to perform the necessary corrective mainten-ance.

The mechanical seal was replaced.

Significant maintenance items performed during the September 1979 reporting period are indicated on the attached Instrument and Electrical Maintenance and Mechanical Maintenance listings.

• Mid-Continent Area Power Pool Iia 4 125

II"A 126 1 of 2 If$TRllMI f;T Af;li il ICIPICAI PAINT E fJ ATRL SEPTEMBER 1979 LFR OP MAIFUfCTION flAluRL Of OUTAr.E FOUIIMEfiT MAIlliEfiAf1Cf f tif'DI R CAUSl f!LSULT CORRECTIVE ACIION Ilydraalic Valve Accum-Corrective NA Normal Usage Alarm incorrect Adjusted Alarm Switch ulator MR-2698 Turbine Expansion Recorder Corrective NA Selector Switch Worn Contacts Readjusted Contacts MR-2773 Usage IB Bypass Steam Valve Corrective Outage Normal Usage Auto Start incor-Adjusted Start MR-2728 79-12 rect Pressure Switch Turbine Oil Pump Corrective Outage Unknown Burned Out Cell Replaced Coil and Breaker MR-2776 79-12 Adjusted Unit Fire Sprinkler System Corrective Outage Installation Seal Leaking Replaced Seal MR-2715 79-12 Damage Control Rod Drive #20 Corrective Outage Pressure Readout Calibration Due Adjusted Pressure MR-2689 79-12 Installed Readout Initial Pressure Preventive Outage Calibration Calibrated Unit Calibrated Unit Regulator MR-2779 79-12 Requested Automatic Gain Control Preventive Cutage Calibration Adjusted #7 Calibrated Ch. 7 Auto-MR-2770 79-12 Requested Multiplier matic Gain Control (AGC)

Water Level System Preventive Outage Calibration Calibrated Unit Calibrated Ch. 1,2&3 MR-2787 79-12 Requested

, Control Rod Drive #3 Corrective Outage Shorted Connector inoperative Lamp Replaced 23 Pin MR-2785 79-12 Connector Radiation Monitoring Preventive NA Calibration Due Calibrated Units Calibrated Fixed and Portable Survey Meters Radiation Monitoring Corrective NA Alarm inoperative Burned Out Buzzer Replaced Buzzer for Unit #5 Fire Detector Corrective NA Defective Circuit Detector Alarming Replaced Unit with Spare MR-2798 Security System Corrective NA Switch inoperative Zone 9 in Alarm Replaced Alarm Card MR 2804 NA Normal Usage Detector inoper-Cleaned Control Switches F

IV

_h9 qu pme ative

2 of 2 INSTRUMENT AND ELECTRICAL MAINTENANCE SEPTEMBER 1979 LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Security System Preventive NA P.M. Work Due Clean Camera Cleaned and Adjusted MR-2809 CCTV Camera Turbine Supervisory Correcti,ve NA Normal Usage Incorrect Printout Replaced Rotary Recorder MR-2805:

Switch Security-System Corrective NA Open Wire No A'larm Light Replaced Wire on Lamp MR-2814:

Socket Control Rod Drive #10 Corrective Outage Shorted Solenoid Hydraulic Failure Replaced Solenoid with MR-2816 79-13 Spare 6

M

.-.4 M

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MECifA!JICAL MAI!JTE!JA!JCE SEPTEMBER 1979 LER OR fMTURE Of OUTAGE MALFUT[CTI0fl EQUIPMENT MAINTEllAf;CE NUMBER CAUSE RESULT CORRECTIVE ACTI0fi IA Seal Injection Pump Corrective NA Ruptured Bladder Accumulator would Replaced bladder.

Discharge Accumulator MR-2775 not maintain pressure.

Turbine Govenor Preventive Outage NA NA Removed Servo Valve and MR-2780 79-12 check for wear and cleanliness.

Turbine Primer Pump Corrective Outage Thrust Bearing Homentary Turbine Replaced thrust bearing.

MR-2778 79-12 Seizing Control Oil Pres-sure Drop.

18 Seal injection Preventive Outage NA NA Inspected pump suction Pump MR-2764 79-12 valves and replaced all valve discs.

Lcwer CRD Frame #2 Preventive Outage NA NA Performed Preventive MR-2783 79-12 Maintenance checks and stored for spare.

Main Steam Bypass Corrective Outage Normal Wear Vorn seat and Rebuilt steam trap with Steam Trap MR-2671 79-12 orifice.

new partc.

Reheater Level Chamber Corrective Outage Broken Sight Water leakage Machined level chamber MR-2788 79-12 Glass causing isolation surfaces and replaced of sight glass, sight glass.

Main Air Lock Inner Corrective NA Unknown Sheared Drive Key Replaced shaft key.

Door MR-2808 on worm gear shaft.

Containment Building Corrective NA Normal Wear Failure to main-Replaced worn vanes Air Monitor MR-2802 tain performance and bearings.

requirements.

Control Rod Drive #10 Corrective Outage called Seal in Leakage, causing Lowered surrounding MR-2821 79-13 Jpper CRD #10 solenoid on scram lower CRDM's.

Replaced MR-2822 block to short.

seal on upper CRDh #10.

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