1CAN068311, Monthly Operating Rept for May 1983

Monthly Operating Rept for May 1983

ML20077A312
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/15/1983
From:	John Marshall, Morton K ARKANSAS POWER & LIGHT CO.
To:	Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
1CAN068311, 1CAN68311, NUDOCS 8307220278
Download: ML20077A312 (11)

Text

x OPERATING DATA REPORT DOCKET NO. 50-313 DATE 6/15/83 COMPLETED BY K.L.Morton TELEPHONE 501-964-3115 OPERATING STATUS Notes Arkansas Nuclear One-Unit-1

1. Unit Name:

May 1-31,1983

2. Reporting Period:

2568-

3. Licensed Thermal Power (MWt):

902.74

4. Nameplate Rating (Gross MWe):

850

5. Design Electrical Rating (Net MWe):

883

6. Maximum Dependable Capacity (Gross MWe):

836

7. Maximum Dependable Capacity (Net MWe):

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

9. Power Level To which Restricted,if Any (Net MWe):

None

10. Reasons For Restrictions. lf Any:

This Month Yr..to-Date Cumulative 744.0 3623.0 74058.0 i1. Hours in Reporting Period 78.'1 228.7 48236.0

12. Number Of Hours Reactor Was Critical

13. Reactor Resene Shutdown Hours 0.0 0.0 5044.0

14. Hours Generator On-Line 61.1 65.3 47122.8 0.0 0.0 817.5

15. Unit Resene Shutdown Hours l

16. Gmss Thermal Energy Generated (MWH) 52579.0' 73319.0 111843133.0' l

17. Gross Electrical Energy Generated (MWH) 15718.0 16076.0 36781120.0 13605.O.

13775.0 35051585.0

18. Net Electrical Energy Generated (MWH)

-8.2 1.8 63.6

19. Unit Senice Factor 8.2_

1.8 64.7

20. Unit Availability Factor 2.2 0.5 56.6

21. Unit Capacity Factor (Using MDC Net) 2.2 0.4 55.7 22.' Unit Capacity Factor (Using DER Net) 14.5 13.7 15.6

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Months tType. Date.and Duration of Each):

None j

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

~ 26. Units in Test Status iPrior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY l

INITIAL ELECTRICITY y

+

N COMMERCIAL OPER ATION 8307220278 830615 hDRADOCK 05000313

("/771 PDR

. _ _._= - -=

. _ - _ - - = _ -

AVERAGE DAILY UNIT POWER LEVEL 50-313 DOCKET NO.

1 UNIT DATE 6/15/83 K.L.Morton COMPLETED BY 501-964-3115 TELEPHONE MONTH May. 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(ywe Net) 0 I

O g7 0

0 2

18 0

0 3

i, 4

0 0

20 0

0 s

21 0

0 6

22 0

0 7

23 0

0 8

24 0

0 9

25 0

0 10 26 0

0 11 27 0

0 12 28 0

13 29 0

240 14 3g 0

299 15 3,

0 16 i

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

(9/77)

W

, smi

., w p w wn g a :a n-4

50-313 DOCKET NO.

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME ANO-Unit 1 DATE - June 9.

1983 COMPLETED BY KEN MORTON REPORT MONTH MAY TELEPHONE (501) 964-3115

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3 Yk Licensee

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1, Cause & Corrective No.

Date g

3g s

2y5 Event g?

g3 Action to g'

Prevent Recurrence H

$5 5

j di g Report :

mV 6

82-07 821108 S

672.5 C

4 N/A N/A N/A 1-R5 Refueling Outage.

83-01 830529 F

10.4 G

3 N/A HA TURBIN Operator failure to reset reactor anticipatory turbine trip during power escalation.

1 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheets for beensee C Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation 0161)

E-Operator Training & Ucense Examination 5-Load Reduction 5

l F Administrative 9-Other G-Operational Error (Explain)

Exhibit 1 - Same Source j

(9/77) 110ther (Explain)

REFUELING INFORMATION 1..

'Name of facility.

Arkansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown. September 15, 1984 3.

Scheduled date for restart following refueling. December 15. 1984 4.

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

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

If answer is no, has the reload fuel design and core configuration 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)?

Yes.

Reload report and associated proposed Technical specification change.

l 5.

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

September 1. 1984 6.

Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or l

performance analysis methods, significant changes in fuel design, new operating procedures.

To be determined.

l l

t 7.

The number of fuel assemblies (a) in the core and (b) in the spent i

fuel storage pool. a) 177 b) 316 L

8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

present 589 increase size by 379 9.-

The projected date of the last refueling that can be discharged l

to the spent fuel pool assuming the present licensed capacity.

~ '~

DATE:

1989

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- MAY, 1983 UNIT 1 The unit started the month in an extension of the IRS refueling outage to repair the Number 5 Main Turbine Generator Bearing and complete an 1

inspection of the upper core barrel support bolts.

From May 19 to May 28, l

the unit experienced a fai?ure of the "D" Reactor Coolant Pump seal, a i

hydrogen leak on the Main Generator and a failure of the "B" Reactor Coolant Pump seal.

On May 28 at 1443 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.490615e-4 months <br />, the reactor was brought critical; the turbine was i

placed back on line at 2321 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.831405e-4 months <br /> the same day.

On May 29 at 1154 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.39097e-4 months <br />, the turbine was taken off line to perform a turbine overspeed trip test.

It was reconnnected to the grid at 1305 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.965525e-4 months <br /> and power escalation was begun.

At 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> the reactor tripped due to failure to reset the reactor anticipatory turbine trip setpoint on the RPS.

The recovery was normal and the reactor was brought critical again on May 29 at 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br />.

The turbine was tied to the grid on May 30 at 0021 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />.

The unit continued on line through the remainder of the month with power physics testing holding at 40% and 75% full power.

NOTE:

A correction was made to the April, 1983, Monthly Operating Report.

The time the reactor was critical was actually 150.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> instead of 56.4.

This correction resulted in a change in the following areas:

Time Reactor Critical Time Reactor Not Critical In Scheduled Shutdown In Forced Shutdown Reactor Service Factor The values computed in the May MOR reflect the correction.

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OPERATING DATA REPORT DOCKET NO. 50-313 DATE

/15/83

.L.Morton CORRECTION COMPLETED BY -_501-m-3115 TELEPHONE

~ OPERATING STATUS Notn Arkansas Nuclear One-Uni,t-1

1. Unit Name:

April 1-30.1983

2. Reporting Period:

2568

3. Licensed Thermal Power (MWt):

902.7_4

4. Nameplate Rating (Gross MWe):

850

5. Design Electrical Rating (Net MWe):

883

6. Masimum Dependable Capacity (Gross MWe):

0 t

7. Masimum Dependable Capacity (Net MWe):

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

1 None

9. Power Lesel To Which Restricted,if A'ny (Net MWe):

10. Reasons l'or Restrictions. If Any:

s Yr.-to-Date Cumulatise This Month w

719.O 2870_0 73314.0 I1. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 150.6

'150.6 48157.9 2

13. Reactor Resene Shutdown Hours 0.1

'0 0 5044.0

4. 2_

4.2 47061.7

14. Hours Generator On-Line 0.0 0.0 817.5

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated IMWH) 20740.0 20740.0 111790554.0 358.0 358.0 36765402.0

17. Gross Electrical Energy Generated (MWH)

- 170.0 170.0 35037980.0

18. Net Electrical Energy Generated (MWHI 0.6

' O.1 64.2

19. Unit Service Factor

- 20. Unit Availability Factor 0. 6_ -

= 0, F ;

65.3 0.0 57.2 0. 0_

e

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0_

56.2

22. Unit Capacity Factor (Using DER Net)-

s 15.6 0.0

-0.O

^

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 Months IType. Date.and Duration of Each):

. ~

I-

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

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

Forecad -

Achiesed INITI A L CRITICA LITY

~

INITIAL ELECTRICITY COMMERCIAL OPER ATION i-(4/77)

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AVERAGE DAILY UNIT POWER LEVEL j

e DOCKET NO.

50-313 UNIT 1

.c i

6/15/83 037g COMPLETED BY K.L.Morton CORRECTION TELEPilONE

'3 ;

MONTH April 1983'

~

y DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe. Net) g ywe. Net) 0 1

0 17 2 -

0 0

,3 0

0 3

4 0~

20' 0

~

0 5-0 21 0

0 6

22 0

0 I,,

7 23 0

0 s

74 0

0 9

25 0

0 10 26 il 5

0 27 12 1

0 28 0

0 13 29 14 0

0 30 0

15 3,

16 0

e_

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

a (9/77)

.w.4 x.

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2

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CORRECTION c

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UNIT SHUTDOWNS AND POWER REDUCTIONS

' ANO-IT 1

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NAME DATE, TUNE 9. 1983 APRIL COMPLETED BY 1&M MORTON REPORT MONTil TELEPHONE (sn1T o AA_ti i s

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.5 ?

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Licensee gn, Cause & Corrective No.

Date L

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Ihent 3?

g3 Action to

$~

's 5 :!

Repor! =

m' O e'

Prevent Recurrence H

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6 82-07 821108 S

714.8 C

4 N/A N/A N/A 1-R5 Refueling Outage _

j

, ~. -

s b.

b 1

2 3

4 F: Fmeed Reason:

Method:

Exhibit G-instructions

~

S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.

Entr> Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report ILER) File (NUREG-D Regulatory Restriction 4-Continuation 0161) i E-Operator Training & License Examination

.5-Load Reduction 2

? -Other 5

F-Administ rative 9

Exhibit I - Same Source i

G-Operational Error (Explain) j (9/77) ll-Other (E xplain)

Q

.3 s

g s ;.

t

UNIT SHUTDO*,NS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appeanng on the report form.

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

ation of significant dips in average power levels. Each signi-ficant reduction in power level (greater thart 20"o reductior LICENSEE EVENT REPORT :t.

Reference the, applicable

~

in average daily power lev:1 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 pertaining to the outage or power should b'e noted, even though the unit may not ha-e been reduction. Enter the first four parts (event year. seOential l

- shut down completely. For such reductions in power level, report number. occurrence code and report type) of the fne the duration should be listed as zero, the method of reduction part designation as desenbed in item 17 of Instructions for should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for twensee 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, since should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of tf e outage or power reduction.

n t a reportable occistrence was involved.) If the outage or power reduction will not result in a reportable occurrence.

NUMBER. This column should indicate the sequential num-the positive indication of this lack of correlation should be ber assigned to each shutdown or significant reductionin power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system in which the outage or power reduction begins in one report period and ends m another.

reduction originated sh' uld be noted by the tw'o digit code of o

an entry should be made for both report periods to be sure all shutdowns or significant 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.0161).

ber should be assigned to each entry.

Systems that do not fit any existing 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 applicable.

of each shutdown or significant power reduction. Report as year. month, and day. August 14,1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814. When a shutdown or significant power reduction from Exhibit I - Instractions for Preparation of Data Entr> n beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-Olbi).

be made for both report periods to be sure all shutdowns using the following critieria:

or significant power reductions are reported.

WPE. Use "F" or "S" to indicate either " Forced" or " Sche-duled," respectively, for each shutdown or significant power B.

If not a component failure. use the related component reduction. Forced shutdowns include those required to be e.g., wrong va!ve operated through error; list valve as initiated by no later than the weekend following discovery component.

cf a off-normal condition. It is recognized that some judg.

ment a required in categorizing shutdowns in this way. In C.

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

general, a forced shutdown is one that would not have been function should be listed. The sequence of events.melud-completed in the absence of the condition for which corrective ing the other components which fail, should be described action was taken.

under the Cause and Corrective Action to Prevent Recur.

s rence column.

DURATION. Selfexplanatory. When a shutdown extends Components that d' not fit any existing code should be de.

o beyond the end of a report period. count only the time to the signated XXXXXX. The code ZZZZZZ should be used for end of the report period and pick up the ensuing down time events where a component designation is not applicable.

in the following report periods. Report duration of outages rounded to the nearest tenth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-The sum of the total outage hours plus the hours the genera-RENCE. Use the column m a narratise fashion to amphis or tor was on line should equal the gross hours in the reportmg explain the circumstances of the shutdown or power reduetion period.

The column should include the specilie cause for each shui-down or significant power reduction and theimmediate and REASON. Categorize by letter designation in accordance with the table appearing on the report form. If category H contemplated long term corrective action taken. if appropn-must be used, supply bnef comments.

ate. This colunm should also be used for a desenprion of the major safety related corrective maintenance perfomied dunng METHOD OF SHUTTING DOWN THE REACIOR OR the outage or power reduction iaeluding an identification ot REDUCING POWER.

Categonie by number designation the critical path activity and a report of any smgle release of radioactivity or single radiation exposure 'pecifically associ-s INote that this differs from the Edison Electric Institute sted with the outage which accounts for more than 10 percent (EEI) definitions of " Forced Partial 0 ttage" ard " Sche.

of the allowable annual values.

dated Partial Outage." For these terms. eel uses a change of For long textual reports continue narrative on separate paper 30 MW as the break point. For larger power reactors.30 MW and reference the shutdown or power reduction for thb is too small a change to warrant explanation.

narrative.

ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501)371-4000 June 15, 1983 1CAN068311 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information Office of Resource Management U. S. iiuclede Reguldt.ory Commission Washington, D. C.

20555

SUBJECT:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report (File:

0520.1)

Gentlemen:

Attached is the NRC Monthly Operating Report for May 1983 for Arkansas Nuclear One - Unit 1.

Very truly yours, ohn R. Marshall Manager, Licensing JRM:SAB:rd Attachment cc:

Mr. John T. Collins Regional Administrator i

U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 s9b MEMBEF1 MIDDLE SOUTH UTILITIES SYSTEM