ML20062A295

Monthly Oper Rept for Sept,1978

ML20062A295
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	10/05/1978
From:	DAIRYLAND POWER COOPERATIVE
To:	Papworth L
Shared Package
ML20062A297	List: ML20062A295
References
NUDOCS 7810120039
Download: ML20062A295 (10)

Text

5..

OPERATING DATA REPORT DOCKET NO.

50-409 DATE 10-5-78_

COMPLETED BY L.G.Papworth TELEPHONE 608-689-2331 OPERATING STATUS I. Unit Name: La Crosse Boiling Water Reactor Notes

2. Reporting Period: 0000 78-01-09 to 2400 78-30-09

3. Licensed Thermal Power (MWt):

165 65.3

4. Nameplate Rating (Gross MWe):

50

5. Design Electrical Rating (Net MWe):

50

6. Masimum Dependable Capacity (Gross MWe):

48

7. Masimum Dependable Capacity (Net MWe):

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

NA i

1 48 Net MWe 9 Power Lesel To %hich Restricted.lf Any (Net MWe):

10. Reasons For Restrictions.lf Any: Self-Imposed Restriction due to Nuclear Instrumentation Noise at Higher Power Levels (Voids in Steam Separators).

This Month Yr to.Date Cumulatise

11. Hours In Reporting Period 720 6,551 78,146

12. Number Of Hours Reactor Was Critical 720 4.449.2 49,627.7

13. Reactor Resene Shutdown Hours 0

0 478

14. Hours Generator On.Line 720 4.001.9 45,292.2

15. Unit Resene Shutdown Hours 0

0 79

16. Gross Thermal Energy Generated (MWH) 94.918 518.346 6.401.646 17 Gross Electrical Energy Generated (MhH) 27.638 150.097 1,943,241 1

lb. Net Electrical Energy Generated (MhH) 25,937 138,605 1,796,185

19. Unit Senice Factor 100 61.1 58.0

20. Unit Asailability Factor 100 61.1 58.1 75.0 44.1 47.9

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net) 72.0 42.3 46.0

23. Unit Forced Outage Rate 0.0 16.6 5.2

24. Shutdowns Scheduled Oser Nest 6 Months iType. Date,and Duration of Eacht MAINTENANCE, INCLUDING 1A CIRCULATION PDIP MAINTENANCE, REACTOR OPERATOR EXAMINATIONS, CONTAINMENT BLDG.

INTEGRATED LEAK RATE TEST AND ISI.

SHUTDOWN 14 OCTOBER 1978 FOR 4-WEEK DURATION.

F

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

NA

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITi \\ L CRITICA LITY INITI \\L ELECTRICITY COsl\\lERCI AL OPER ATION 7f191 cpg 3f 927-W 1 R 7Er19VS~

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9 INSTRUCTIONS FOR COMPLETING OPERATING DATA REPORT This report should be furmshed each month by licensees. The name and telephone number of the preparer should be provided in

...c des:gnated spaces. The instrucnens below are provided to assist licensees in reportmg the data cons.stently. The number of the mstruction corresponds to the item number of the report format.

1. UNIT NAME. Selfexplanator).

or of commercial operation, whichever comes last, to the end of the period or decommissionmg. whichever comes

2. REPORTING PERIOD. Designate the month for which first. Adjustments in clock hours should be made in the data are presented.

wiuch a change from standard to daylight savings time (or vice versal occurs.

3. LICENSED THERMAL POhER (MW )is the maumum t

thermal power, expressed in megawatts. eur.ently auth.

12. NUMBER OF HOURS REACTOR WAS CRITICAL.

onzed by the Nuclear Regulatory Comm:ssion.

Show the total number of hours the reactor was entical

4. NAMEPLATE RATING (GROSS MW, L The nameplate power designation of the turbine-generator in megavolt

13. REACTOR RESERVE SHUTDOWN HOURS. The total amperes (MVA) times the nameplate power factor of the number of hours dunng the gross hours of reporting turbine generator.

period that the reactor was removed from service for administrative or other reasons but was available for

5. DESIGN ELECTRICAL RATING (NET MW,) is the operation.

nominal net electncal outpyt of the umt specified by the utihty and used for the purpose of plant design.

14. HOURS GENERATOR ON-LINE.

Also called Service Hours. The total number of hours expressed to the near-

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MW,)

est tenth of an hour during the Fross hours of the re-is the gross electrical output as measured at the output porting penod that the unit operated with breakers terminals of the turbine. generator during the most re-closed to the station bus. These hours, plus those lis+ed strictive seasonal conditions-in Unit Shutdowns for the generator outage hours,should

7. MAXIMUM DEPENDABLE CAPACITY (NET MW,).

Maximum dependable capacity (gross) less the normal

15. UNIT RESERVE SHUTDOWN HOURS. The totai n'um-station service loads.

ber of hours expressed to the nearest tenth of an hour S. Self explanatory.

during the gross hours of the reporting period that the unit was removed from service for economic or similar

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY reas ns but was available for operation.

(NET MW,).

Note that this item is apphcable only if

16. GROSS THERMAL ENERGY GENERATED (MWH).

restrictions on the power level are in effect. Short-term (less than one month) limitations on power level need The thermal output of the nuclear steam supply system not be presented in this item.

during the gross hours of the reporting period, expressed n megawatt hours (no decimals).

Since this mformation is used to develop figures on capa-city lost due to restrictions and because most users of the

17. GROSS ELECTRICAL ENERGY GENERATED (MWH).

Operating Plant Status Report" are primarily interested The electrical output of the unit measured at the output in energy actually fed to the distnbution system, it is terminals of the turbine-Fenerator during the gross hours requested that this figure be expressed in MWe-Net in of the reportmg penod, expressed in megawatt hours-(no spite of the fact that the figure must be derised from decimals).

MWt or percent power.

18. NET ELECTRICAL ENERGY GENERATED (MWH).

10 REASONS FOR RESTRICTIONS, IF ANY. If item 9 The gross electrical output of the unit measured at the 1

is used, item 10 should explain why.- Brief narrative is output terminals of the turbine. generator minus the nor-l acceptable. Cite references as appropriate. Indicate mal station service loads dunng the gross hours of the whether restrictions are self. imposed or are regulatory reponing period. expressed in megawatt hours. Negative i

requirements. Be as specifie as possible within space hmi-quantities should not be used, if there is no net positive tations. Plants in startup and power ascension test phase value for the period, enter zero (no decimals).

should be identified here.

l t

11. HOURS IN REPORTING PERIOD. For umts in power 19 For units still in the startup and power ascension test ascension at the end of the penod, the gross hours from

23. phase. items 19-23 shouid not be computed. Instead, enter the beginning of the period or the first electrical produe, N/A in the current month column. These five factors tion, whichever comes last to the end of the perioo.

should be computed starting at the time the unit is de-clared to be in commercial operation. The cumulative For units in commercial operation at the end of the -

_ figures m the_ second and third columns should be based penod, the gross hours from the beginning of the penod on commercial operation as a starting date.

(9/773

saSTRUMENT AND ELECTRICAL MAINTEl...4CE SEPTEMBER, 1978 LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION-NA Improper Setting Alarm In, System Adjust Alarm Point Seal Injection Corrective MR 2164 &

Normal MR 2197~

Radiation Monitoring Corrective NA Defective Resistor Low Voltage at Replaced Resistor MR 2165 Detector Temperature Recorder Corrective NA Alarm Point Drift Alarm Point Low Adjust Alarm Point MR 2160 Environmental Monitor Coryective NA Defective Gauge No Vacuum Reading Replaced Vacuum Cauge MR 2158 lleating and Ventflation Corrective NA Relay Coil Burned Heating Boiler Replaced Relay Coil MR 2163 Inoperative Radiation Monitoring Corrective NA Defective Photo Alarm In Replaced Lamp MR 2167 Lamp Security Corrective NA Improper Alignment Alarm In Aligned Bias Magnet MR 2170 f

Reheat Steam Corrective NA Defective Bellows Reading Low Replace Transmitter l

MR 2166 &

MR 2084 1

Security Corrective NA Contaminated Switch No Reset Action Cleaned Switch Contacts MR 2182

INSTRUMENT AND ELECTRICAL MAINTEt<ANCE SEPTEMBER 1978 (Cont'd)',

g LER OR

~

~

NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION-Reactor Level Corrective NA Lamp Burned Out Dim Indication on Replaced Lamp on Sight MR 2194 Sight Class Glass Low Pressure Service Corrective NA Contaminated No Pressure Indi-Replaced Snubber Water MR 2195 Gauge Snubber cation Ileating and Ventilation Corrective NA IIcating Boller No Low Flame Replaced Program Control MR 2183 Control Improper Unit 4

Temperature Recorder Corrective NA Dirty Selector Erratic Printing Cleaned Selector Switch MR'2185 Switch

MECIIANICAL MAINTENANCE SEPTEMBER, 1978 LER OR MALFUtlCTION NATURE OF OUTAGE Ef)UIPf1ENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION IB Seal Injection Pump Corrective NA Normal Wear Excessive Packing Repacked Pump Plungers MR 2162 Leakage Primary Purification Corrective NA Pressure and Leakage Past Rebuilt and Tested. Relief.

Relief Valves, S/N MR 2142 Temperature Valve Seats Valves Previously Removed TB 70671 6 70672 Cycling From Service Because of Seat Leakage IB LPSW Pump Corrective NA Normal Wear Mechanical Seal Installed ISew Mechanical MR 2186 Leakage Seal J

IA Stack Fan Corrective NA Normal Wear Excessive Belt Replaced Drive Belts MR 2168 Noise and Slippage Back-Up Air Compressor Preventative NA None None Changed Oil Maintenance MR 2172 l

AVERAGE D AILY UNIT POWER LEVEL DOCKET NO.

50-409 LACBWR gg.IT 10-05-78 DATE L.G. M WORM COMPLETED BY 608-689-2331 TELEPHONE SEPTEMBER 1978 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE D AILY POWER LEVEL (Mhe Net) g ywe. Net) 1 36 37

,7 2

36 18 36 3

36 19 36 4

20 36 5

36 21 36 6

36 36 22 7

36 23 36 8

36 36 24 9

35 25 36 10 35 26 36 11 35 2;

36 12 36 36 2g 13 36 29 36 I4 36 36 30 36 15 3,

16 37 INSTRUCTIONS On this format. list the aserage d;i!) unit power leselin MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.

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D 50-409 UNil SilUIDOWNS AND POWER REDUC 110NS DOCKET NO.

UNII N AME LACBWR 10-03-/8 DATE COMPLETED Hy L.G. P APWORT11 RI PORI MONTil EPTEMBER 1973 TELFPHONE 608-689-2331 n.

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4 1.icemcc E-t, gg Cause & Correctne N...

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Attion to S

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d 5Mc Repore at tE 0

!0 Present Recurrence v

O 78-08 Continued F

NA A

4 NA CB PIIMPXX INCREASING VIBRATION READINGS ON from Tile LOWER RADIAL BEARING AND THRUST August BEARING OF Tile FLUID COUPLING ON 1978 FORCED CIRCULATION PUMP 1A REQUIRED CONTINUED REDUCED POWER OPERATION.

Tile BEARINGS WILL BE INSPECTED DURING Tile FORTilCOMING OCTOBER MAINTENANCE OUTAGE.

I 3

4 I I orteil Renon:

Methoil:

Exlubit G-Instructions S. Stheduled A-l quipment Fadure(Explain) l Manual for Preparation of Data 11 Maintenance ni Test 2 Manual Scram.

Entr) Sheets for Licensee C Refuelmg 3 Automatic Scram.

Event ReporI (Li'R) Fde (NURI G-D Regulasury Restriction 44)ther I Explain) 0161) 1.-Operator Training & l.icense Examination F-Administ rative S

G-Operational Liror (1:xplain)

Eshibit I - Same Source el/7 7) 11 Other I L xplain)

UNIT SHUTDOWNS AND POhER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns durmg the in accordance with the taHe appearmg on the report form.

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

ation of sam 6eant dips m average power levels. Each signi-ficant reddction m power level (greater than 207 reduction LICENSEE EVENT REPORT :. Reference the appheable in aserage datly 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 pertammg to the outage or power shouid be noted, esen though the unit may not have been reduction. Ent r the first four parts (event year. sequential shut down completel> 3. For such reductions m power level, report number, occurrence code and report typel of the Ove the duranon should be bsted as zero, the method of reduction Part designauon as desenbed m item 17 of Instructions for shou!d be hsted as 4 (Otherh and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report Action to Present Recurrence column should explam. The (LER) File (NUREG0161) This information may not be Ciuse and Correctise Action to Prevent Recurrence column immediately eudent for all such shutdowns. of $ourse, smce should be used to proside any needed explanation to fully further investigation may be required to ascertam whether or describe the circu~. stances of the outage or power reduction.

not a reportable occurrence was involved.; if the outage or power reduction will not result m a reportable occurrence.

NU41BER. This column should indicate the sequennal num, the positive indicanon of this lack of correlation should be ber assigned to ca.h shutdown or sigmficant reduction m power noted as not apphcable INIAh

[

for that calendar year. When a shutdown or signi6 cant power reduction begms in one report penod and ends in another.

SYSTEM CODE. The system m which the outage or power an entry should be made for both report penods to be sure reduction originated should be noted by the two digit code of al! shutdowns or sigmficant power reductions are reported.

Exhibit G Instructions for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num-f r Licensee Event Report (LER) File (NUREG-Olel t ber should be assigned to each entr).

Systems 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 should indicate the date of the start a system is not apphcable.

of each shutdown or sigmficant power reduction. Report as y ear. month, and day. August 14.1977 would be reported as 770814. When a shutdown or significant power reduction COMPONENT CODE. Select the most appropnate component beginsin one report penod and ends in another. an entry should from Exhibit I - Instructions for Preparation of Data Entry be made for both report periods to be sure all shutdowns Sheets for Licensee Esent Report (LER) File (NUREG.0161 h or s;graficant power reducuons are reported.

usmg the followmg ennena:

TYPE, Use "F" or "S" to mdicate either " Forced" or " Sche.

If a component failed.use the component directly mvolved.

A.

duled.* respecuvely, for each shutdown or significant power B.

l reduction. Forced shutdowns include those required to be If not a component failure, use the related component:

tmt ated by no later than the weekend followmg discovery e.g.. wrong valve operated through error; hst valve as component.

of an off normal condition. It is recognized that some judg-ment is required in categorinng shutdowns in this way. In C.

general. a forced shutdown is one that would not have been If a chain of failures occurs, the first component to mal.

completed m the absence of the cond: tion for wiuch corrective function should be hsted. The sequence of events includ.

ing the other components which fail. should be desenbed action w as taken.

under the Cause and Corrective Action to Prevent Recur-rence column.

DUR ATION. Self explanatory. When a shutdown extends beyond the end of a report period. count only the time to the Components that do not fit any existmg code should be de-end of the report renod and pick up the ensumg down time signated XXXXXX. The code ZZZZZZ should be used for m the following report renods. Report durauon of outages events where a component designation is not appheable.

rounded to the nearest tenth of an hour to facihtate summation.

The sum of the total outage hours plus the hours the genera-CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-j tor was on ime should equal the gross hours in the reportmg RENCE. Use the column m a narrative fashion to amphfy or penod.

explain the careumstarees of the shutdown or power reduction.

ihe column should melude the specific cause for each shut.

REASON.. Categorize b) letter designation in accordance down or significant power reduction and the immediate and i

with the table.spreartng on the report form. If category 11 contemplated long term corrective action taken. if appropri-must be used supply bnef comments ate. This column shot.ld also be used for a desenpuon of the maior safety related corrective maintenance performed durmg METHOD OF SilUTTING DOWN THE REACTOR OR the outage or power reduction meludmg an identification of I

REDUCING POWER. Categonie by number deugnation the cntical path setmt) and a report of an) smple rele se of radioactivity or smgle radiation exposure specithally associ.

INote that this differs from the Edison Electne Institute ated with the outage which accounts for more than 10 percent (EEI) defirutions of " Forced Panial Outage" and " Sche.

of the allowable annual values duled Partial Outage / For these terms. EEI uses a change of For long textual reports continue narrative on separate pape 30 MW as the break pomt. For larger power reactors.30 MW and reference the shutdown or power reduenon for tha 13 luo smJll J ehJnge to aJrrJnt e\\plJnatioll.

nJrrative.

t l

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~- - --,-

e NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE SEPTEMBER 1978 At the onset of the September reporting period, power generation was in progress at a reduced output of 36 MWe-net (81% reactor rated power).

Operation at this reduced level was due to continued indications of increased vibration on the lower radial bearing and thrust bearing of the fluid coupling on Forced Circulation Pump 1A (see June, July and August 1978 narratives).

Reactor power continued at 81% of rated power until September 9, 1978, when a speed reduction of 15 RPM on Forced Circulation Pump 1A and 10 RPM on Forced Circulation Pump 1B was performed.

The associated reduction in core coolant flow reduced reactor power to 80%.

The pump speed reduction was necessitated by continued indications of increased vibration in Forced Circulation Pump 1A fluid coupling bearings.

Reactor power was reduced September 18, 1978 from 80% reactor rated power to 79%, when again, a pump speed reduction was made on both forced circulation pumps due to indications of increased vibration in the Forced Circulation Pump 1A fluid coupling bearings.

Power generation continued at 79% reactor rated power until September 25, 1978, when reactor power was reduced a third time when the pump speeds of both forced circulation pumps were re-duced by 15 RPM due to increased 1A pump vibration indications.

Reactor power generation continued at 78% reactor rated power (36 MWe-Net) for the remainder of the month.

As stated in the June, July and August narrative summaries, eventual corrective action of the indicated vibration problem on Forced Circulation Pump 1A will include inspection of the pump coupling bearing (s).

This will be performed in the forthcoming maintenance outage scheduled to commence October 14, 1978.

The maximum power level at which the reactor was operated during September 1978 was 37 MWe (81%).

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 658 curies per day (this at 81%

power) during September 1978 and the alpha activity in the primary coolant did not exceed 4.5 x 10-7 pCi/gm during the reporting period.

19. UNIT SERVICE FACTOR. Compute by dividing hours the generator was on line (item 14) by the gross hoursin the reporting period (item II). Express as percent to the nearest tenth of a percent. Do not include reserve shut.

down hours in the calcula: ion.

20. UNIT AVAILABILITY FACTOR. Compute by dividing the unit available hours (item 14 plus item 15) by the gross hours in the reporting period (item 11). Express as percent to the nearest tenth of a percent.

21. UNIT CAPACITY FACTOR (USLNG MDC NET). Com-pure by disidmg net electrical energy generated (item 18) by the product of madmum depetidable capacity (item

7) times the gross hours in the reporting penod (item 1I).

Express as percent to the nearest tenth of a percent.

22. UNIT CAPACITY FACTOR (USING DER NETh Com-pute as in item 21. substituting design electrical rating (item 5) for maumum dependable capacity.

23. UNIT FORCED OUTAGE RATE. Compute by dividing the total forced outage hours (from the table m Unit Shutdowns and Power Reductions) by the sum of hours generator on hne fitem 14) plus total forced outage hours (from the table in Unit Shutdowns and Power Reductions).

Express as percent to the nearest tenth of a percent.

24. SHUTDOhNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACHl. Include type (refuehng. mamtenance, otherb proposed date of start of shutdown. and proposed length of shutdown.

It is recognized that shutdowns may be scheduled between reports and that this item may not be allinclusive. Be as accurate as possible as of the date the report is prepared.

This item is to be prepared each month and updated if appropriate until the actual shutdown occurs.

25. Selfcplanatory.

26. Self-explanatory. Note, however, that this informa: ion is requested for all units in startup and power ascension test status and is not required for uruts already in com-

}

mercial operation.

TEST STATUS is denned as that penod fellowmg ini-tial cntieahty dunng which the unit is tested at succes-sisely higher outputs eulmmatmg with operation at full I

power for a sustamed penod and completion of war-ranty tuns. Fol!owmg this phase. the unit is cenerall) considered by the utthty to be availab'e for commercul operation.

1' Date of Cost \\lERCl4L OPERATION is defined as the date that the unit was declared t'y the utthty owner to be available for the regular proJuetion of electneity, usua:ly related to the satisfactor) completion of quah-tlation tests as spect6ed m the purchase contract and to the ascounting pohetes and practices of the utility.

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