ML19263C226

Monthly Operating Rept for Jan 1979

ML19263C226
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	02/06/1979
From:	Papworth L DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML19263C225	List: ML19263C224 ML19263C226
References
NUDOCS 7902130065
Download: ML19263C226 (15)

Text

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THIS DOCUMENT CONTAINS P00R QUALITY PAGES OPERATING DATA REPORT DOCKET NO. 50-409 DATE 02-06-79 COMPLETED BY rth TELEPil0NE O 31 OPERATING STATUS

1. Unit Name: La Crosse Boiling Water Reactor Not'5

2. Reporting Period: 0000 79-01-01 to 2400 79-31-01

3. Licensed Thermal Power (MWt): 165 65.3

4. Nameplate Rating (Gross MWe):

50

5. Design Electrical Rating (Net MWe):

6. Maximum Deper.dable Capacity (Gross MWe):

50

7. Maximum Dependable Capacity (Net MWe):

LR

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

9. Power Lesel To Which Restricted,if Any(Net MWe): 48 Net MWe

10. Reasons For Restrictions. If Any:

Self-trrposed restriction due to nuclear Instrurr.entation noise et higher power levels (volds in stearn separators).

This Month Yr..to-Date Cumulatise

11. Ilours in Reporting Period 744 744 81,099

12. Number Of Ilours Reactor Was Critical 505.8 505.8 51.685.0

13. Reactor Reserve Shutdown llours 0

0 478

14. Ilours Generator On-Line 438.5 438.5 47.156.6

15. Unit Reserve Shutdown flours 0

0 79

16. Gross Thermal Energy Generated (MNs, 14.711 34.731 6.57i.973

18. Net Electrical Energy Generated (MWH; 8.700 9.772 1.992.081

17. Gross Electrical Energy Generated (MWil) 9.772 8.700 1,840,503

19. Unit Service Factor 58.9 58.9 58.1

20. Unit Availability Factor 58.9 58.9 58.2

21. Unit Capacity Factor (Using MDC Net >

24.4 24.4 47.3

22. Unit Capacity Fac;or (Using DER Net) 23.4 23.4 45.4

23. Unit Forced Outage Rate 41.1 41.1 6.0

24. Shutdowns Scheduled Oser Next 6 Mot ths tType. Date, and Duration of Each t:

D e f..e l l rm thutrfnwn. March 24. 1979. 8-Week Duration.

NA

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

26. Units in Test Status t Prior to Commercial Op ration):

Forecast Achiesed INITI \\ L CR!TICALITY INiil \\l. f LECTRICITY CO\\t\\lLR( l \\L OPE-R UION 7902130065

1 of 2 UNIT SilU1 DOWNS AND POWER REDUCTIONS DOCKET NO. 50-409 UNIT NAME LAN DATE 07-06-70 COMP D BY REPORT MONT11_Ja nua ry 1979

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4 25E Evens v7 E?

Action to jE d

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SC yL Prevent Recurrente 6

78-17 Continued F

NA A

4 NA CB PUMPXX CONTINUED REDUCED POWER LEVEL OPERATION from WITH IB FORCED CIRCULATION PUMP PRO-December VfDING CORE FLOW.

IA FORCED CIRCUL-1978 ATION PUMP SECURED DUE TO INDICATIONS 1F EXCESSIVE FACE SEAL WEAR.

REPAIRS TO BE EFFECTED IN FUTURE.

79-01 79-01-13 F

268.9 A

3 NA RB CONROD FAILURE OF A CONTROL ROD SCRAM SOLEN-OID ON CONTROL R0D DRIVE NO. 13 RE-SULTED IN THE IB STATIC INVERTER SHIFTING TO THE INTENDED ALTERNATE POWER SOURCE. A FAILURE OF A CIRCUlT BOARD WITHIN THE STATIC INVERTER IN-DUCED A REACTOR SCRAM AS IT ATTEMPTED TO SHIFT BACK TO THE PRIMARY POWER SOURCE.

THE CONTROL ROD DRIVE SCRAM S0LEh0lD AND THE STATIC INVERTER BOARD WERE REPLACED.

2 3

4 i !oued Reasem :

M ethod :

F sinhit G - Inst ruttiins s %hsJ deJ A Equipmeni Failure iLsplain)

!-Manual for Preparainm of Data B. Maintenance or Test 2-Manual Scratn.

Entr> Sheets for Licensee C Refuct;ng 3-Automatic Scram.

Event Report (i.L R) File (NUREG-D-Regularo.) Restriction 4-Other ( E splain )

0161i E-Operator Training & liense Examination F-Admamstrative 5

Goperational Error (E splain)

I shibis 1 - Same Source i> ?I

!! Ot her I E splam )

2 of 2 UNIT SliU,lDOWNS AND POWER REDUCTIONS DeCKET NO.

50-409 UNIT NAAIE LACBWR DATE 06-79 REPORT MONTil January 1979 COMPl.ETED SY _L.G.Papworth TELEPHONE 605-689-2331

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Date

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3-4 jg5 Event u7 91 Atw,n to Cause & Correctne

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j is j Report at iE C j'

Prevent Recurrense 5

79-02 79-01-24 F

36.6 A

3 NA RB CONROD FAILURE OF A CONTROL ROD SCRAM SOLEN-OID ON CONTROL ROD DRIVE (CRD) NO.

13 RESULTED IN A PARTIAL SCRAM OF 13 PRESELECTED CONTROL RODS AS IN!TI-ATED BY A CRD LOW ACCUMULATOR Olt LEVEL SIGNAL.

THE REMAINING CONTROL RODS WERE MANUALLY SCRAMMED. THE SCRAM SOLEN 01D WAS REPLACED.

I 2

.I I I orted Renon 4

Method -

S S heduled A Iquipment 1.

,, ( 1. s plain t t 41anual I shihat G - Instrustiim for Preparation of Data B Mairitenance or Test

.' Manual S tarn.

Entry Sheets for lxensee C. Refuel.ng A Automatic Stani.

Event Report Il I R) file i\\1 di G D-ReFulatory Restrittion 4-Ot her l l. splain )

0161) l Opcialor Training A lx. w: I s.mnation 1%drvunntratne G4)perational I.tror Ii spianit r6 77) li-Other f t:splam) l'sinbit 1 - Saine Sour c

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-409 UNIT LACBWR DATE 02-06-79 L.G.Papworth COMPLETED BY 608-M9-2331 TELEFllONE January 1979 McNm DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 0 I

22 37 22 2

gg 0

3 22 g,

0 22 4

20 0

22 0

5 21 0

6 22 22 0

7 22 23 22 24 1

g 0

22 25 9

22 5

10 26 11 22 27 13 19 12 22 28 7

21 13 29 21 14 0

30 0

15 3

21 0

16 INSTRUCTIONS On this format, hst the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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JANUJa,Y 1979 I'4STRUENT A':D ELECTRICAL PAINTENANCE LER OR NATURE OF OUTAGE

ALEUNC~ICU E0ui:"ENT

A'NTENANCE NUMBER CAUSE I

RESULT C% RECTI'.'E ACTIC's

= ECURITY SYSTEM CORFICTIVE MR2362 NA ILM CURRENT NO ALARM ZONE 5 ADJUSTED LINE CURRENT icURITY SYSTE'i CORRECTIVE MR2381 NA BROKEN WIRE NO ALARM FISET REPLACED LEAD-IN WIRE CONE 3 I

.:CU R I TY SYSTEM CORFICTIVE MR2367 NA DEFECTIVE CONTACTS IN ALARM ZONE 5 REPLACED ACCESS SWITCH odCURITY SYSTEM CORRECTIVE MR2429 '

OUTAGE LOOSE ALARM CARD NO ALAPM RESET TIGHTENED ALARM CARD 79-01 ZONE 4 JIRE DETECTION CORRECTIVE MR2363, NA CONTAMINATION LOW DETECTION CLEANED FIRE DETECTOR II$AD MR2374, MR2375 CURRENT

!LL FILM DEMINERALIZER CORRECTIVE MR2309 NA CAPACITOR LEAKAGE NO MANUAL CONTROL REPLACED CAPACITOR IN CIRCU

JEL CIL LEVEL GAUGE CORRECTIVE MR2377 NA WARE MANUAL PUMP INOP.

REPLACED LEATHER PIS'[ON SEA

RG -I NTE R. POWER SYSTEM CORRECTIVE MR2388 OUTAGE DEFECTIVE CIRCUIT NO TRANSFER REPLACED DEFECTIVE SYNC.

79-01 BOARD FUNCTION B

'RD

• TROL ROD DRIVE PREVENTIVE MR2400 OUTAGE P.M. DUE COMP LETED P. M.

REPLACED CRD CONTROL SWITCH 79-01 CONTROL ROD DRIVE CORRECTIVE MR2391 OUTAGE DEFECTIVE SOLENOID SCRAM VALVE OPEN REPLACED SOLENOID COIL 79-01 s :UND. FICIRCUIATION SYSTEM PREVENTIVE MR2084 OUTAGE P.M. DUE COMPLFTED P.M.

REPLACED TRANSMITI'ER WI'111 79-01 SPARE l

HIGH PRESSURE SERVICE CORRECTIVE MR2409 OUTAGE FROZEN SENSE LINE RECORDER INOPERABIE REROUTED NEW LINE WATER 79-01 EORCED CIRCULATION 1A PREVENTIVE MR-2399 OUTAGE REQUEST COMPLETED P.M.

CALIBRATED INSTRUMEN'IS SYSTEM 79-01 l CONDENSATE SYSTEM CORRECTIVE MR2401 OUTAGE BRNEN AF

NO POSITION REPLACED ARM l

79-01 INDICATION

JANUARY 1979 INSTRw'ENT AND ELECTRICAL MAINTENANCE LER OR

'1ALFUNCTION fATURE OF OUTAGE ECUI;"ENT

A I NT ENANCE NUMBER C40tE RESULT CORRECTIVE ACTION E LECTRIC AT DIS TRIBUTION CORRECTIVE MR2402, OUTAGE CRACKED EPOXY SEAL AIR LEAK 1sGE RESEALED PENETRATIONS 2403, 2404, 2405 79-01 IIR 79-02

, CONTROL ROD DRIVE CORRECTIVE MR2433 OUTAGE DEFECTIVE SWITCH PRESSURE DRIFT REPLACED PRESSURE SWITCH 79-01

• NUCLEAR INSTRUMENTATION CORRECTIVE MR2437 NA DEFECTIVE CAPACI70F INOPE RABIE REPLACED CAPACITOR CONTROL ROD DRIVE CORRECTIVE MR2443 OUTAGE DEFECTIVE SOLENOID SCRAM VALVE OPEN REPLACED SOLENOID COIL 79-02 i

ENVIRONMENTAL MONITORING CORRECTIVE MR2337 NA DEFECTIVE D/P NO TEMPERATURE REPLACED REPAIRED AMPLIFIER AMPLIFIER READOUT CONDENS ATE SYSTEM CORRECTIVE MR2451 NA INCORRECT CONTROL LEVEL CONTRCL HIGH ADJUSTED CONTROL SETPOINT SETPOINT i

l i

i l

4 i

MECHANICAL ?'A!::TENANCE JANUARY 1979 LER OR MALFUNCTION NATURE OF OUTAGE EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION L awe r Control Rod Corrective Outage Normal wear.

Oil leak.

Repacked accumulator

!cive in Position 18, MR 2306 &

79-01 piston rod.

Frame 16 MR 2418 Seal Injection Valves Preventive Outage NA NA Disassembled and 52-25-007, 52-25-005, MR 2397 79-01 flushed valves to check e.

52-25-015 for foreign materials in Seal Injection Syste.

E.

3 Feedwater Heater Corrective Outage Temperature Leak at flange Replaced flange gasket.

Tube Side Relief Valve MR 2338 79-01 and pressure joint.

cyr. les.

Reheater Level Chamber Corrective Outage Damaged Mica Poor read-Replaced glass, gaskets Sight Glass MR 2325 79-01 ability and mica.

CRD Nitrogen Charging Corrective Outage Wear Val"es Inoper-Replaced valves.

System Valves 32 MR 2152 &

79-01 able 003, 004, 005 & 006 MR 2159 Discharge Check Valve Corrective Outage Corrosion of Back-leakage Replaced check valve.

for "A"

HVA Pump MR 2314 79-01 Valve Seat through valvo.

Eme rgency Airlock Preventive Outage Normal Use Door seal Replaced inner door MR 2336 79-01 cracked and seal.

frayed.

Lower Control Rod Corrective Outage Open circuit Control rod Installed spare lower Drive in Position #13, MR 2391 79-01 in scram solen-scrammed with-CRD (Frame # 9).

Re-Frame #26 oid.

out scram placed scram solenoids signal.

on Frame #26.

"B" CRD Hydraulic Corrective Outage Indefinite Pump could not Replaced pump.

Charging Pump MR 2416 79-01 maintain pres-sure.

leak ! ebuilt seal.

"A" Forced Circulation Corrective Outage Shaft Seal **

Excessive R

P ump (FCP)

MR 2396 79-01 failed.

off flow.

JANUARY 1979 MECHANICAL MAINTENANCE LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION

[aste Water Piping Corrective Outage Indefinite.

Leak on inlet Patched leak witn MR 2357 79-01 piping to flow epoxy compound.

totalizer.

Lower CRD Position #4, Corrective Outage Normal wear.

Oil leak.

Repacked accumulator Frame #13 MR 2421 79-01 piston v'i.

Lower CRD Position #12, Corrective Outage Hydraulic Scram Excessive oil Replace [ with spare Frame #4 MR 2418 79-01 Motor shaft leakage.

drive unit (Frame #26) seal failed.

Replaced seal.

CRD Hydraulic Charging Corrective Outage O-Ring failed.

Excessive oil Replaced 0-Ring.

Pump Pelief Valve MR 2425 79-01 leakage.

Oil Tanks for HPSW Preventive NA NA NA Pumped oil from bo. 3m Diesel Pumps and "B"

of tanks to remove Emergency Diesel Gener-m31sture and sediment.

ator.

e e

h.

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE JANUARY 1979 At the onset of the January reporting period, power generation was continuing at a reduced output of 22 MWe-net (49% reactor rated thermal power).

Operation at this reduced level was due to the necessary securing of Forced Circulation Pump 1A in December 1978 due to indications of excessive upper face seal wear.

Forced Circulation Pump 1B was providing total core flow.

Reactor operation continued at the abcVe stated power level until 0835 hours0.00966 days <br />0.232 hours <br />0.00138 weeks <br />3.177175e-4 months <br /> on January 13, 1979, when a reactor scram occurred.

A short circuit to ground in one of the two scram solenoids on Control Rod Drive (CRD) No. 13 caused the control rod to scram and the 1B static inverter to shift to the alternate power source.

A failure of a synchronization circuit board with-in the static inverter indirectly caused a low voltage on the non-interruptible bus as the static inverter attempted to automatic-ally shift back to the initial power sour e.

The resultant low voltage induced the full scram signal.

A new synchronization board was installed in the static inverter and a new scram solenoid installed on the control rod drive mechanism.

The upper face seal on Forced Circulation Pump 1A was replaced during this shutdown and periodic Type B and C leakage rate testing was also conducted.

The reactor was taken critical at 1456 hours0.0169 days <br />0.404 hours <br />0.00241 weeks <br />5.54008e-4 months <br /> on January 22, 1979 and the turbine generator was synchronized to the DPC grid at 1327 hours0.0154 days <br />0.369 hours <br />0.00219 weeks <br />5.049235e-4 months <br /> on January 24, 1979.

A reactor partial scram occurred that same day at 2042 hours0.0236 days <br />0.567 hours <br />0.00338 weeks <br />7.76981e-4 months <br /> from a power level of 10 MWe-ret (31%

reactor rated thermal power).

A short circuit to ground in a scram solenoid had again occurred as in the above case, but in a different control rod drive mechanism.

The partial scram was initiated by a low CRD accumulator oil level condition as a result of the cubject control rod scramming.

The remaining control rods were maneally scrammed.

The defective control rod scram solenoid was replaced.

Tne reactor was taken critical at 1236 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.70298e-4 months <br /> on January 25, 1979 and the gene;rc" closed in with the DPC grid at 0923 hours0.0107 days <br />0.256 hours <br />0.00153 weeks <br />3.512015e-4 months <br /> on January 26, 1979.

Powc escalation continued until 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br /> that same day when, at a power level of 9 MWe-net (31% reactor rated thermal power), the lA F orced Circulation Pump was again secured due to indications of Excessive face seal wear.

Power escalation continued in a one loop operational mode and a 21 MWe-net (49% reactor rated thermal power) output was achieved on January 28, 1979.

Operation continued at this level for the remainder of the month.

The reoccurring Forced Circulation Pump seal problem is being analyzed with emphasis on material suitability.

Repairs to the pump will be effected during a forthcoming refueling outage.

1 of 2

The maximum power level at which the reactor was operated during January 1979 waa 49% of rated thermal power and the maximum net electrical generated power was 22 MWe-net.

The off-gas activity levels, as measured at the 150 ft 3 holdup tank effluent monitor (prior to entry into the augmented off-gas holdup system) did not exceed 501 curies / day during Janut:ry 1979 and the alpha activity in the primary coolant did not exc?ed 9.7 x 10-7 pCi/gm during the reporting period.

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

2 of 2

REFUELING INFORMATION REQUEST 1.

Name of Facility La Crosse Boiling Water Reactor (LACBWR) 2.

Scheduled date for next refueling shutdoun.

The tentatively scheduled date for the next refueling shut-down (EOC-V) is March 24, 1979.

3.

Scheduled date for restart follouing refuc ting.

The tentatively scheduled date for subsequent reactor startup is May 24, 1979.

4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If answer ia yea, uhat, in general, uilt these be?

If anover is no, has the reload fuel design and core configur-ation been revicued by your Plant Safety Revieu Committee to de termine uhe ther any unrevieved safe ty questions are assoc-iated uith the core reload (Ecf. 10 CFR Section 50.69)?

If no auch revicu has taken place, uhen is it scheduled?

It is presently believed that subsequent operation after re-fueling will require a license amendment and technical specifi-cation changes.

It is anticipated that the core loading for the coming fuel cycle VI will include several Allis-Chalmers Core I (Type I) fuel assemblies which are a type used previously but are not presently incorporated into technical specifications addressing APLHGR, MCPR, LHGR, etc.

5.

Scheduled date (s) for submitting proposed licensing action and supporting information.

February 23, 1979.

6.

Important licensing considerations accociated uith refueling, e.g.,

new or different fuel design or supplier, unrevieved design or performance analycie methods, significant changes in fuel design, neu operating procedures.

See 4. above.

1 of 2

REFUELING INFORf1ATIOIT REQUEE - (Cont'd)

)

7.

The number of fuel acaemblics (1) in the core and (b) in the opent fuct storage pool.

Core loading:

72 fuel assemblies.

Spent fuel storage pool loading:

13 '

rradiated fuel assemblies.

One dummy fuel assembly is stored in t__

spent fuel pool.

8.

The preacnt licensed opent fuel pool storage capacity and the cine of any increase in licensed storage capacity that has teen requested or is planned, in number of fuel assemblice.

Presently licensed storage capacity:

134 fuel assemblies.

Planned storage capacity:

440 fuel assemblies.

9.

The projected date of the last refueling that can be dic-charged to the opent fuel pool assuming the precent licenced capacity.

Refueling discharge capacity unavailable since EOC-IV, May 1977.

l.

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