ML19242D573

Monthly Operating Rept for Jul 1979

ML19242D573
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	08/06/1979
From:	Papworth L DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML19242D566	List: ML19242D565 ML19242D573
References
NUDOCS 7908150428
Download: ML19242D573 (10)

Text

.

OPERATING DATA REPORT DOCKET NO.

50-409 DATE O 79 COMPLETED BY f.n Peworth TELEPHONE 608-680-2331 OPERATING STATUS N '"

L' nit Name: la Crns** RnI1Tng Varar Dearter

2. Reportuig Period: 0030 70-01-07 to 2400 74-31-07

3. Licensed Thermal Power IMh t):

165

4. Nameplate Rating (Gross Mhel:

65.3 l

50

5. Design Electrical Rating (Net MWeI:

6. Maximum Dependable Capacity (Gross MWe): 50 NO

7. Maximum Dependable Capacity (Net MWe):

S. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report. Give Reasora:

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

48 MWe-Net

10. Reasons For: Restrictions. If Any:

Self-f moosed Restriction due to Nuclear Instrumen-tatfor. Noise at Higher Power I.evels.

This Month Yr..to.Date Cumulatise

11. Hours In Reporting Period 744 5087 85,442

12. Number Of Hours Reactor was Critical 710.0 3.286 54.465.2

13. Reactor Reserve Shutdown Hours 0

0 478

14. Hours Generator On.Line 678.3 3,054.3 49,772.4

15. Unit Reserve Shutdown Hours 0

0 79

16. Gross Thermal Energy Generated t MWH) 01.210 114.649 6.841.001 17 Gross Electrical Energy Generated (MWH1 25.824 _ _

88.496 2.070.805

18. Net Electrical Energy Generated (MWH) 24.055 80.690 1.412.443

19. Unit Sersice Factor 31.2 60.0 58.3

20. Unit Asailability Factor 91.2 60.0 58.4

21. Unit Capacity Factor iUsing MDC Net) 67.4 33.1 46.6

22. Unit Capacity Factor (Using DER Net) 64.7 31.7 44.8

23. Unit Forced Outage Rate 8.8 13.0 6.0

24. Shutdowns Scheduled Oser Next 6 Months iType. Da'e.and Duration of Eachi-None Scheduled

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

NA

26. Units in Test Status q Prior eo Commercial Operation):

Forecast hhiesed tr3IbbD INITI AL CRITICALITY INITI AL ELECTR! CITY COM\\tERfl AL OPER \\ TION r,-,

7 DU815 0 fM,

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-409 gggy LACBWR DATE 08-06-79 L.G.Papworth COMPLETED BY 08-689-2331 TELEPHONE MONnt JULY 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

( M We-Net I

( MWe-Net )

42 36 i

37 42 2

is 37 26 3

19 37 4

6

o 37 5

0 37 12 6

- 38 23 38 7

3 s

12 38

4 25 38 9

30 10 35 26 38 11 37

7 38 37 12 33 33 13 37 29 38 i4 37 3a 37 37 15 3:

29 16 37 INSTRUCTIONS On this format. inst the average daily unit power levelin MWe-Net for each day in the reporting month.Comrute to the nearest whole megawatt.

b31040 m,

5 of 2 Page IXX KET NO.

50-409 UNil SilulDOWNS AND POWLR REDUCTIOFS LACBWR UNIT N AME DA1E 08-06-79 COMPLETED 8y L.G.Papworth RLPOR I MON iil JULY 1979 308-689-2331 lELEPflONE n.

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79-08 79-07-03 F

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3 NA CD XXXXXX A REACTOR SCRAM OCCURRED DUE TO PER-SONNEL ACTION WHILE PERFORMlHG MAIN-TENANCE ON A CONTROL ROD POSITION SECONDARY INDICATION CIRCUlT. WHEN A CIRCUlT FUSE WAS REMOVED FROM THE CIR-CULT, WHICH ALSO SUPPLIES POWER TO A STEAM PRESSURE TO TURRINE INDICATION TRANSMITTER, THE MSly CLOSED WHICH PROMPTED AN AUTOMATIC REACTOR SCRAM.

79-09 79-07-04 F

33.92 A

1 79-13 HE VALV0P A PLANT SHUTDOWN WAS CONDUCTED TO REPAlR THE MAIN STEAM BYPASS VALVE OPERATING CYLINDER WHICH HAD DEVELOP-ED A HYDRAULIC OlL LEAK. REPAIRS WERE PERFORMED WHICH INCLUDED REPLACE-MENT OF VALVE OPERATING CYLINDER SEALS.

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UNIT SHUTD0%NS AND POWER REDUCTIONS INSTRUCTIONS This report should desenbe all plant shutdowns dunng the m accordance with the table appearing on the report iorm.

report penod. In addition. it should be the source of explan-If category 4 must be used supply brief comments.

ation of sigmficant dips in aserage power levels. Each signi-LICENSEE EVENT REPORT er.

Reference the appheable ticant redueuon m power level (greater thaa 204 reduction m aserage dady power level for the precedmg 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 red uction. Enter the first four parts (esent year, sequential should be noted. even thouch the unit may not have been shut down completeiy. For'such reductions in power level, report number, occurrence code and report type) of the tive 1

the duration should be bsted as zero, the method of reduct:on Part designation as desen;ed in item 17 of instructions for should be hsted as 4 (OL :rh and the Cause and Corrective Preparanon of Data Entry Sheets for Licensee Event Report Aeuon ta Present Recurrence column should explam. The (LER) File (NUREG-0161). This mformanon may not be Cause and Correctne Action to Present Recurrence column immediately evident for all such shutdowns, of course. since should t'e used to provide any needed explanatten to fuuy further msesrigation m:y be required to ascertam whether or dessnbe the circumstances of the outage or power redaction.

not a reportable occurrense was mvolved.) If the outage er power reduction wiu not result m a reportable occurren c NUMBER. Ttus column.houlJ mdicate the sequentul num, the positne mdication of this lack of correlation sheu!d ae noted as not applicable tN At ber a> signed to each shutdown or sigmtisant r Juctic m power for that calendar y ear When a shutdown or signi6eant ps wer SYSTEM CODE. The system m which the outage or power reduction becms in one report penod anJ ends in anotur.

an entrs shoulJ be made for both report penods to be see reduction originated should be noted by the two digit code of Exhibit G - Instructions for Preparanon of Data Entr> dheets au shutdowns or sigm6 cant power reductions are reported Untd a umt has a.kved its first power generation. no num-for Licensee Event Report (LER) File (NUREG-Olol t ber should be assigned to e eh entry.

Systems that do not fit any existmg code should be designa.

ted XX. The code ZZ should be used for those esents where DATE. This column shou!d mdi, ate the date of the start a system is not appheable.

of each shutdown or >igmtkant pewer redueuun. Report as y ear. month, and de. August 14. IC would be reported COMPONENT CODE. Select the most appropnate,omponent as "05.4. When a shutdown or sigm6eant power reducuan from Exhibit i Instructic ts for Preparation of Data Ente beginsin one report penod and ends m another. in entr> should Sheets for Lisensee Esent Report (LER) File (NCREG Olol) be made for both report penods to be sure all shutdowns usmz the foHowmg entiena:

or sigmticant power reductions are reported.

TYPE. L se "F" or "S" to mdicate either " Forced" or "Sehe.

d uied.' respectne!). for each shutdown or s:gn 6eant power B.

If not a componera failuie. use the reiated component red uc tion.

Forced shutdowns melude those required to be e2, wrong valse operated through error; list salve as

mtiated by no later than the weekend fouowmg discover) component.

of an ott. normal sondition. It is recogmzed that some judg.

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

11 a cham of fa !ures occurs the Grst component to mal-general. a torced shutdown is one that would not hase been function should be listed. The sequence of events. me'ud.

sompleted m the absence of the condition for wruch correctne ing the other components wluch fail, should be desenbed acuen w as tar en.

under the Cause and Correcuve Acuon to Prevent Recur-rence column.

DURATION. Seif-caplanat ory. When a shutdown extends Components that do not fit any ejustmg code should be de-beyond the end of a report penoa.sount only the time to the signated XXXXXX. The code ZZZZZZ should be used for end of the report penod and pick up the ensumg down time events where a coinptment dengnation is not appbcable.

m the foUowing report renods Report durabon of outues rounded to the nearest tenth at an hour to f acihtate summation CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-The sum of the total outage hours plus the hours the genera-RENCE. Use the colun.n m a narranve fastuon to arnphfy or tor was on ene should equal the eras, hours m the reportma explam the circumstances of the shutdown or power reduction.

P' ""1 The column should mclude the specific cause for casn shut.

down or sigm6eant power reducuon and the immediate and REASON

(.aieson/e m.ettei Jewnat an m auordarce entemplated long term corrective action taken, it appropn-on the rctmrt form. If sategor) 11 with the UNe arreann.:

ate This column shoulJ also be used for a description of the must be used. 3uprly boet somment' mJMr sJtet)*related correClive maintenance performed dunng me or power reduenon mcluding an ident 6 canon of

\\f E THOD Of-SHUTfl% DOWN TiiE REACTOR OR

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REDUCING POWER

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• n o m outage whi n aesounts tur more than !0,,eue "

ill11 de nm tio n > of "I orsed 15r t ui t luus and "Sshe.

or the aho*anle annual sa!ues rueJ IS.nai i s na 1., %

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Page 2 of 2 UNil SIIUll} OWNS AND POWI R RI DUCIIONS g

DATE _08-06-79 COMPLETED BY l G.Papworth t

RLPORI' MON 1ll JULY 1979 60 M 9-2331 IELEPil0NE a..

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c5 79-10 79-07-07 F

12.18 A

3 NA CJ INSTRU A FAILURE OF A SEAL INJECTION DIFFER-ENTIAL PRESSURE TRANSMITTER CAUSED BOTH FORCED CIRCULATION PUMPS (FCP)

TO TRIP, WHICH PROMPTED THE SAFETY SYSTEM TO SCRAM THE REACTOR BECAUSE A POWER-TO-FLOW MISMATCH THEN EXISTED.

THE TRANSMITTER 'JAS REPLACED.

79-11 79-07-31 F

NA B

4 NA HC XXXXXX A POWER REDUCTION FROM 85% TO 46% WAS CONDUCTED FOR THE PURPOSE OF REMOVING ONE OF THE TWO TURBINE CONDENSER WATER B0XES FROM SERVICE TO REMOVE RIVER SILT. THIS WAS DONE IN AN EFFORT TO REDUCE A CONDENSER BACK PRESSURE CONDITION.

I 2

3 4

i lin ecJ Reason:

M et hod.

IN!nhis G lossentinos 5 h hed uled A l~quipment l'ailure (1.xpidu)

I Manual for Pseparatton of D ta 11 Maintenance or Test 2-Manual Ser ain.

1.nu) Sheets f or 1.itenve C Retueling L Automatic Stram.

I vent Reposi (l.1 Ri l ile (NU RI G-D IOgulatoi> Resuistion 4 Other 11 spf.nni O l t> I l 1 -Operator 1rammg i l uense 1 xanunanon

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UNIT SHUTDOWNS AND PO%ER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns dunng the m accordance with the table appeanng on the report form.

report period. In addition, it should be the source of explan.

If category 4 must be used. supply brief comments.

ation of sigm6eant dips :n average power levels. Each signi-LICENSEE EVENT REPORT 3 Reference the appbeable ticant reduction m power ievel (greater than 204 reduction in average dady power level for the precedmg 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportable occurrence pertatmng to the outage or power red uc tion. Enter the first four pa.ts (event year, sequential should be noted. even though the unit may not have been shut down completely l For such reductions m power level, rep r number, occurrence code anc report ty pe) of the !ne the duration should be bsted as zero, the method of reduction part designation as dewnbed m Iten 17 of instructions for should be hsted as 4 (Other), and the Cause and Corrective Preparation of Data Fntry Sheets fot Licensee Event Report Action to Prevent Recurrence column should explam. The (LER) Fde (NUREG-0161). Th2s mformation may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns. of course. since should be used to provide any needed esplanation to fully further mvestigation may be required to ascertam whether or describe the circumstanees of the outage or power redaction.

n t a rep rtable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence NUMBER. This column should.ndicate the sequential num_

the positne indication of this lack of correlation should he ber assigned to each shutdown or sign 10 cant reduction m power noted as not applicable (N A).

for ihat calendai y ear When a s.iutJown or sigmficant power SYSTEM CODE. The system in which the outae or pewer reduction beg:ns m one report pened and ends in another.

reduction oriemated sh' uld be noted by the two digit code of o

an entry should be made for, oth report penods te be sure

~

c Exhibit G - Instructions for Preparation of Data Entry Sheets all shutdowns or sigm6 cant power reductions are reported.

Untd a umt has ach'ieved its first powet generation, no num-f r Licensee Event Report (LER) File (NLREG41el L ber should be assigned to each entry.

Systems that do not 61 any existmg code should be desyna.

ted XX. The code ZZ should be used for those events where DATE. This column should mdisate the date of the start a system is no. ippheable.

of each shutJown or sigmticant power reduction. Report as year. month, and day August 14. IC7 would be reported COMPONENT CODE. Select the most appropnate somponen as 770814. When a shutdown or sigmticant power reduct:on nom Exhibit i 1rotructions for Preparanon of Data Entry begms m one report penod and ends m another, an entry should Sheets for Licensee Eve.t Report (LER) Fde (NUREG.01e1 L be made for both :eport penods to be sure all shutdowns usmg the following eritiena:

or sigmficant power reductions are reported.

TYPE. L se "F" or "S" to mditate either " Forced" or "Sehe.

duled.' respect:vely, for each shutdown or sigmticant power B.

If not a somponent f. dure, use the related component red uc tion.

Forced shutdowns :nclude those required to be e.g.. wrong valve operated through error: hst vabe as mituted by no later than the weekend followmg diseosery component.

of an ott. normal condition it is recogmzed that some judg-meni is required m categonzmg shutdowns m th25 way. In C.

If a cham of failures occurs. the first component to mal.

general. a forced shutdown :s one that would not hase been function should be hsted. The sequence of events. melud-

.ompleted m the absence of the condition for wruch corrective ing the other components which fad, should he described acuon was taken.

under the Cause and Corrective Action to Prevent Recur.

rence column.

DURATION. Self. explanatory When a shutdown extends Components that do not fit any ex:stmg ende should he de.

beyond the end of a report penod, wount only the time to the signated XXXXXX. The code ZZZZZZ should be used for end ut the report penod and pick up the ensumg down time events where a component designation is not apphcable.

m the f ollowing report penuds. Report durauen of outages rounded to the nearest tenth ot an huur to facditate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-The sum of the total outage hcurs plus the hours the genera.

RENCE. Use the column m a narratne fastuor to amphfv er tur was on hne should equal the grass hours m the reportmg exp am the circumstances of the shutdown or power reduction.

penod.

The column should include the specific cause for each shut-down or significant power reduction and the immediate and REASON

(.ategorve n>

4ettei Jeuenanon in ascordance sontempiated long terrn correctne action taken. if approrn.

.u t h t he t anic appearme on the report form. If category 11 are. This coiumn should also be used for a desenption of the must he useJ..upply boet som m en t s j

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE JULY 1979 At.he onset of the July reporting period, power generation was continuing at an output of 42 MWe-Net (93% Reactor Rated Thermal Power).

A reactor scram occurred at 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br /> on July 3, 1979 due to closure of the Main Steam Isolation valve (MSIV).

The closure was indirectly initiated by personnel action when a fuse was removed frcm an instrumentation circuit to allow replace-ment of a control rod secondary position indication light.

Steam pressure to turbine indication is also in this same circuit and when the fuse was removed, power was lost to that indication which caused the MSIV to close and a reactor scram to then result.

A reactor startup was conducted the same day with the reactor taken critical at 2205 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.390025e-4 months <br />.

The turbine generator was synchron-ized to the DPC grid at 1057 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.021885e-4 months <br /> on July 4th.

At 2025 hours0.0234 days <br />0.563 hours <br />0.00335 weeks <br />7.705125e-4 months <br /> the same day, a reactor shutdown was initiated for the purpose of repair of the Main Steam By' ass Valve operating cylinder which had developed a hydraulic oi..

leak.

Following plant shutdown, repairs were conducted which included replacement of the valve operating cylinder seals.

Following Main Steam Bypass Valve cylinder repairs, a reactor startup was conducted with the reactor taken critical at 1955 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.438775e-4 months <br /> on July 5.

The turbine generator was connected to the DPC grid at 0645 hours0.00747 days <br />0.179 hours <br />0.00107 weeks <br />2.454225e-4 months <br /> on July 7.

At 1837 hours0.0213 days <br />0.51 hours <br />0.00304 weeks <br />6.989785e-4 months <br /> on July 7, a reactor scram occurred at a power level of 75% rated thermal power.

A condition of low seal in-jection differential pressure, which was a result of a faulty differential pressure transmitter, tripped both forced circulation pumps which prompted the safety system to scram the reactor due to a power-to-flow mismatch.

The differential pressure transmitter was promptly replaced and a reactor startup initiated with the reactor taken critical at 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> the same day.

The turbire generator was connected to the DPC grid at 0648 hours0.0075 days <br />0.18 hours <br />0.00107 weeks <br />2.46564e-4 months <br /> on July 8.

Power escalation continued until July 11 when turbine condenser back pressure (reduction in condenser vacuum) reached an adminis-trative limit.

The back pressure was thought to be caused by accumulation of river silt in the condenser.

Power generation continued in the range of 83% - 86% rated thermal power until July 31 when a power reduction to 46% was performed so that one of the two turbine condenser water boxes could be removed from service for silt removal.

1 of 2 JOICN

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE - JULY 1979 (Cont'd)

Reactor power was being maintained at 46% at end of month.

Electrical generation was 16 MWe-Net.

The maximum power level at which the reactor was operated during July 1979 was 42 MWe-Net (93% Rated Thermal Power).

The off-gas activity levels, as measured at the 150 ft3 holdup tank effluent monitor (prior to entry into the augmented off-gas holdup system) did not exceed 563 curies per day (this at 93%

power) during July 1979 and the alpha activity in the primary coolant did not exceed 6. 5 x 10-7 pCi/gm during the reporting period.

Significant maintenance items performed during the July 1.979 reporting period are indicated on attached Instrument and Electrical Maintenance and Mechanical Maintenance listings.

b910 '10 2 of 2

J'JLY 1979 MI:clI AN I C A1. M A I NTI'N ANCI'.

LER OR flATURL OF DUlAGE

_____ _ ___ MALFUNCTION C

E0ulHifNT MAINTINANCI f,;Ml.

fAUSE RESULT CORRECTIVE ACTION

_ _ _ _' I R__.___ _ __________ _

i CRD Hydraulic Charging Corrective flA Improper Seal Hydraulic Oil Leak Rebuilt Accumulator and Accumulator MR 2714 Around Base of from Base of Reinstalled Accumulator Accumulator High Volume Accumulator Corrective Outage Normal Wear leakage Through Rebuilt Spare Pilot Valve (HVA) Valve MR 2701 79-09 Valve and installed in System 1A and 18 Forced Circul-Preventive Outage NA NA Replaced Cup Seals.

ation Pump Discharge MR 2724 79-09 old Seals satisfactory.

Rotoport Valves Main Steam Bypass Valve Corrective LER Hydraulic Valve Excessive Leakage Replaced Seals in Actuator MR 2722 79-13 Actuator Seals Through Seals Hydraulic Cylinder of Failed Valve Actuator Heating Boiler Preventive NA NA NA Open Boller for Cleaning and Inspection High Pressure Service Corrective NA Excessive End Play Mechanical Scal had insatiled New Mechanical Water (HPSW) Electric MR 2711 in Pump Shaft Excessive Leakage Seal and Contacted Pump Pump Through it Manufacturer for Pump Repair Heating Steam to Contain-Corrective NA Normal Wear Leakage by Valve Installed New Valve ment Manual isolation Valve C'

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JUL" 1979 INSTRUMENT AND flFCTRICAL MAINTENANCE LER OR NATURE OF OUTAGE MALFUNCTION EQUll'HENT MAINTENANCE NilMBER CAllSE RESULT CORRr:TIVE ACTION Diesel Fire Pump 1A Corrective NA Diode Shorted Start Solenoid Replaced Defective Diode MR 2716 Shorted Control Rod Drive Corrective

! Outage Usage Light inoperative Replaced Lamp MR 2717 79-08 Turbine Control Corrective Outage Contaminated Drain Valve Slow Cleaned Solenoid Valve HR 2710 79-10 Valve Well Water Corrective NA Adj ustment Low Low Water Pressure Adjusted Pressure MR 2725 Switch Seal injection Corrective Outage System Pulsations Capsule Weld Broke Replaced with Spare Unit MR 2731 79-10 Water Storage Tank Corrective Outage Unknown Feed Back Arm Off Replaced Feed Back Arm MR 2721 79-09 Was te Wa te r Moni tor Corrective NA C on

• an. i na t ed No Alarm Cleaned Alarm Contacts MR 2737 Contacts Environmental Temperature Corrective NA Defective incorrect Readout Replaced Unit After MR 2600 Transistor Repair Area Radiation Monitor Corrective NA Usage Inoperative Replaced Defective MR 2743 Power Supply Capacitor Conductivity Recorder Corrective NA Usage Worn Gear Replaced Drive Gear MR 2741 Make-Up Demineralizer Corrective NA Contaminated inoperable Cycle Cleaned Program MR 2723 Contacts Contacts Heating Boller Facility Change NA Insurance Company Back-Up Low Level Completed Facility 79-02 Request Switch Installed Change Security System New install-NA New Installation Additional Micro-Installed Additional ation Wave Units in-Wire C"

NA stalled

!O CD 5

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