ML20042C429

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Oct 1981
ML20042C429
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 11/09/1981
From: Goodman L
DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML20042C423 List:
References
NUDOCS 8203310400
Download: ML20042C429 (9)
v • d • e


Text

page 2 of 2 o

REFUELING INFORMATION REQUEST - (Cont'd) 8.

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

440 Fuel Assemblies 9.

The Projected Date of the Last Refueling that can be Discharged to the Spent Fuel Pool Assuming the Present Licensed Capacity.

1990 i

l l

i.

8203310400 811109 PDR ADOCK 05000409 R

PDR

Page 1 of 2 REFUELING INFORMATION REQUEST 1.

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

Scheduled Date for Next Refueling Shutdown The tentatively scheduled date for the next refueling shutdown (EOC-VII) is February 1, 1982.

0 3.

Scheduled Date for Restart Following Refueling

^

The tentatively scheduled date for subsequent reactor startup is April 1, 1982.

e 4.

Will Refueling or Resumption of Operation Thereafter Require a Technical Specification Change or Other License Amendment?

If answer is yes, what, in general, with these be?

If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

If no such review has taken place, 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's 50.59 review of the reload fuel design and core configuration will be conducted prior to the commencement of refueling.

5.

Scheduled Date(s) for Submitting Proposed Licensing Action and Supporting-Information.

N/A 6.'

Important Licensing Considerations Associated with Refueling, e.g., New or Different Fuel Design or Supplies, Unreviewed Design or Performance Analysis Methods, Significant Changes in Fuel Design, New Operating Procedure None 7.

The Number lof Fuel Assemblies '(a) ~in the Core and (b) in:the Spent Fuel-Pool Core Loading:- '72 Fuel Assemblies Spent-Fuel Storage' Pool. Loading:

165' Irradiated-Fuel Assemblies.

o

i,

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE OCTOBER 1981 At the onset of the October reporting period, power generation continued at 85% Reactor Rated Thermal Power (38 MWe-Net).

This power level has been scheduled to extend the time period between refueling outages.

At 0324 on October 18, 1981, a reduction in power commenced in order to remove the 1B Forced Circulation Pump (FCP) from service, due to coupling oil leakage.

At 1341 on October 18, the o

reactor autamtically shut down due to low recirculation flow due to the 1A PCP flow being reduced while the 1B FCP was being returned to service.

At 2102 on October 18, the reactor was taken critical and the turbine-generator was synchronized to the DPC grid at 0535 on October 19.

Power escalation continued until October 21, when 85% Reactor Rated Thermal Power (38 MWe-Net) was achieved.

Power generation continued at this level throughout the remainder of the reporting period.

Significant maintenance items performed during the October 1981 reporting period are indicated on the attached Instrument and Electrical Maintenance and Mechanical Maintenance listings.

r_

MECHANICAL MAINTENANCE 1 Of 1 LER OR fiATURE OF OUTAGE MALFUfiCTI0fi EQUIPMEfiT MAlfiTEfiAfiCE fiUMBER CAUSE RESULT CORRECTIVE ACT10ft 1B Seal Injection CORRECTIVE NA Normal Wear Excessive Seal Replac'ed parts, Pump Plungers MR-0904 Water Leakage Including throat bushing, packing adaptors, plungers and repacked all three plungers.

lA Low Pressure CORRECTIVE NA Unknown; Appeared to be Disassmbled and in-Service Water (LPSW)

MR-0910 Possibly Shell no discharge

spected, but found Pump Fragments and pressure.

nothing wrong.

Debris Block-Tested OK.

ing Inlet 1B Traveling Screen CORRECTIVE NA Broken Chain Would not Replaced with a whole MR-0923 drive.

new chain.

Racctor Building East CORRECTIVE NA Expansion Loss of Freon Replaced expansion Air Conditioner MR-0926 Valve Leak valve.

lA Control Rod Drive CORRECTIVE NA Fretting of Excessive leak Replaced O-Rings and (CRD) Hydraulic Charg-MR-0939 O-Ring of Pydraul tightened follower ing System Discharge up tight.

Valve Post Accident Sampling NEW INSTALL-NA NA Moved H2 Detectors FC-71-80-1 System ATION from Electrical MR-0920 Penetration Room into Maintenance Shop 1B Forced Circulation CORRECTIVE OUTAGE Loose Plexi-Leaked oil.

Tightened plexiglass Pump Coupling Oil MR-0947 8 1 - 15 glass Inspec-cover on coupling System tion Cover housing.

~

INSTRUMENT Afl0 ELECTRICAL MAINTENANCE 2 of 2 LER OR flATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Control Room Two-Way Corrective NA Damaged by Push-to-Talk Replaced Microphone Radio Microphone MR-0933 Operations Inoperative Fire Barriers Corrective' NA Sag in Flam-Barrier not Added Flammastic MR-0953 mastic Filled Over. Existing Flam-MR-0955 mastic Cond:nser Vacuum Corrective NA Unknown Blown Fuse Replaced Fuse Pump Control Circuit MR-0958 Checking Circuit Firo' Control System New Installation NA FACILITY Completed New Completed FC 06-81-13 Main and Reserve Power MR-0970 CHANGE 06-81-13 Installation Transformer Nuclear Instrument Preventive NA Test Due Completed-Tests Completed Test N-5 Channels N-5 Through Through N-9 N-9 4

Safety. System Preventive NA Test Due Completed Tests Completed Safety CH 1, 2 &;H O #3 2

System Tests 1, 2,

& 3 a

e W

INSTRUMEtiT AND ELECTRICAL MAINTENANCE 1 of 2 LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Sccurity System Corrective NA Unknown False Alarm Balanced Alarm Unit AP=19-3 MR-0922 S curity System Corrective NA Normal Usage Lock Loose Tightened Lock Mechanism Crib, House Door.

MR-0938 Security System Corrective NA Unknown False Alarm Balanced and Cleaned

,E-Field MR-0934 Pot R 1 V tage lator curhy System Co m ive NA Unknown false Alarm Board Security System Corrective NA Normal Usage Lock Loose Replaced Screws in Lock Airlock Gate MR-0964 Radiation'Off-Gas-Corrective NA Flow Rate Exceeds Meter Off-Scale Installed Auxiliary Flow Readout MR-0914 Meter Capability Readout Meter with Higher Scale Fuel Storage Well Corrective NA Misaligned Alarm Contin-Realigned Photo Lamp Pump Area Radiation MR-0911 Photocell uous Entry Alarm Radiation Area Monitor Corrective NA Power Resistor Inoperative Replaced Power Power Supply MR-0946-Burnout Monitor Resistor Radiation Unit Corrective NA Factory Mod-Completed Mod-Completed Modification SPING 4 MR-0965 ification ification Installation Installation Underwater' Lamps

~ Corrective NA Normal Usage Lamp Burnout Replaced Lamp Bulbs MR-0908 Heating Boiler Corrective NA Normal Usage Defective Replaced Pressuretrol MR-0915 Pressuretrol Shutdown Condenser Cond.

Corrective NA Coil Burnout Closed Shutdown Replaced Solenoid Drain Line Solenoid MR-0927 Condenser Conden-Valve Coil sate Drain Valve

4 AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.

50-409 UNIT - LACBWR DATE 11-09-81

~'

C0\\fPLETED BY L.S. GOODMAN TELEPilONE 608-689-2331 OCTOBER 1981

\\f0N111 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

IMWe Net) 1 37 37 38 2

38 is 15 3

38, gg 14 4

38 20 29 3

38 21 37 6

38 38 22 7

38 38 23 g

38 38 24 9

38 23 39 (CST 25 IIRS. )

10 38 26 38 11 38 27 38 12 38 2g 38 13 38 29 38 14 38 30 38 15 38 31 38 38 16 INS 1RUC110NS

' On this format, hst the average d 'ly unit power levelin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

N/77) 4

z 1

UNITSHUIDOWNS AND POWER REDUCTIONS DOCKET NO..50-409 UNIT NAME W RWR DATE 11-04-81 REPORT MONTit OCTOBER'1981 COMPLETED 8Y T-c rnnnuw TELEPHONE 609-689-2331

[

~5-

=

es

. 5us 5

.I e E

g.E X Licensee c-r Cause & Corrective No.

Date

[

3g R

.g g &

Event 5 y,,

h%

?

Action to

$E E

j di g Report =

iN G

}C Prevent Recurrence j-5 d

e f

?.

81-15 10-18-81 F

O A

4 NA CB PUMPXX POWER'WASbREDUCED'zFROM 85% TO l

  1. ,41% IN CORDER i.TO' REMOVE.1B 2FORCEDCCIRCULATION; PUMP-FROM t:

} SERVICE. DUET'IO' A' COUPLING OIL LEAK.

JTIE*PIMIGLMINSPETICN CNER

',CrLTIE,000PLING.IDUSING MAS TIGTf-

'f

?HED WHICH.&Oww; TIE LEAKAGE.

81-16 10-18-81 F

15.9 G

3, NA CB INSTRU 1THE' REACTOR AUTOMATICALLY;cSHUT iDOWN'DUE'TO 7OW' RECIRCULATION"

.FICW DUE 'ID'.TIIc. lA KP FION BEING

~

iREDUCED EHILE. TIE 1B JOPCED CIRCUL-lATIONTPUMP. WAS BEING REIUIMD 'IO TSERVICEP10 ADDITIONAL TRAINING 10N' THISLINFREQUENT' EVOLUTION s

.m uWILL_BE_PROVIDED. _ _

j i

2 1

4 F Forced Reason:

Method:

Exhibit G Instructions 5 Scheduled A. Equipment Failure (Explain)

Ent:3 Sheets for Licensee 1 Manual for Preparation of Data B. Maintenance or Test C Refueling

.t. Automatic S. ram.

Event Report (1.ERI File iNURLG-D. Regulator) Restriction 4 Other(I:xplain) 0161)

Eoperator Training & thense Examination F Administrative 5

G-Operational Error iExplain)

Esinhit I Same S. urce W/77)

II-Other (Explain)

}

O

OPERATING DATA REPORT DOCKET NO. _50-409 DATE 11-06-Y1 COMPLETED BY

_L.S. GOODMAN

~

TELEPilONE.EnR-6R 4-2331 OPERATING STATUS N"5

1. Unit Name: La Crosse Boilinct Water l<eactor 0001, 10-01-81 'IO 2400, 10-31-81
2. Reporting Period:
3. Licensed Thermal Power ($1Wt):

165 65.3

4. Nameplate Rating (Gross $1We):

50

5. Design Electrical Rating (Net 5tWe):
6. Masimum Dependable Capacity (Gross MWe): --5 0
7. Masimum Dependable Capacity (Net MWe):

_d R

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

a

9. Power Lesel To which Restricted.If Any (Net MWe):
10. Reasons For Restrictions. If Any:

This Month Yr..to.Date Cumulatise II. Ilours in Reporting Period 745 7296 105,195

12. Number Of flours Reactor Was Critical 737.7 5822.4 69,919.4
13. Reactor Resene Shutdown flours 0

0 478

14. Ilour, Generator On-Line 729.1 5465.3 64,496.6
15. Unit Resene Shutdown Ilours 0

0 79

16. Gross Thermal Energy Generated (MWil) 101,161 7 743.219.7 8,827,557.2
17. Grow Elcetrical Energy Generated (MWH) 28.672,___,_,

211,003 2,641,638

18. Net Electrical Energy Generated (MWH) 26,821 195.715 2.442.995
19. Unit Senice Factor 97 9 74.9 61.3 97.9 74.9 61.4
20. Unit Asailability Factor
21. Unit Capacity Factor IUsing MDC Net) 75.0 55.9 48.4
22. Unit Capacity Factor (Using DER Net) 72.0 53.7 46.5
23. Unit Forced Outage Rate 2.1 8.6 7.2
24. Shutdowns Scheduled Oser Nest 6 Months (Type.Date.and Duration of Eacht:

MPP11RLTNG. FERRUARY 1, D WEEKS

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

NA

26. Units In Test Status tPrior to Commercial Operation):

Forecast Achiesed INITI A L CRITICA LITY INITIAL ELECTRICITY CO\\tMERCI A L OPER ATION r, -

Retrieved from "https://kanterella.com/w/index.php?title=ML20042C429&oldid=4542925"