1CAN098305, Monthly Operating Rept for Aug 1983

Monthly Operating Rept for Aug 1983

ML20078K484
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/15/1983
From:	John Marshall, Morton K ARKANSAS POWER & LIGHT CO.
To:	Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
1CAN098305, 1CAN98305, NUDOCS 8310190117
Download: ML20078K484 (7)

Text

.

i OPERATING DATA REPORT DOCKET NO.

50-313 DATE 4/15/R3 COMPLETED BY K.L.Morton TELEPHONE En!_oga 't115 5

OPERATING STATUS

1. Unit Name:

Arkansas Nuclear One - Unit 1 N"'"

2. Reporting Period:

August 1-31, 1983

3. Licensed Thermal Power (MWt):

2568 902.74

4. Nameplate Rating (Gross MWe).

850

5. Design Electrical Rating (Net MWe):

883

6. Maximum Dependable Capacity (Gross MWe):

836

7. Masimum Dependable Capacity (Net MWe):

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

One

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

10. Reasons For Restrictions. If Any:

This Month Yr. to Date Cumulatise 744.0 5,831.0 76,266.0 i1. Hours in Reporting Period 709.0 1.586.5 49.593.8

12. Number of Hours Reactor was Critical 0.0 0.0 5,044.0

13. Reactor Resene Shutdown flours

14. Hours Generator On-Line 685.0 1,376.0 48,433.5 0.0 0.0 817.5

15. Unit Resene Shutdown Hour,

~

1,611,957.0 3.083.978.0 114,853,792.0

16. Gross Thermal Energy Generated (MWil) 525,895.0 1,006,406.0 37,771,450.F

17. Gross Electrical Energy Generated (MWH)

18. Net Electneal Energy Generated (MWHi 500,927.0 956,517.0 35,994,327.0 92.1 23.6 bd.b

19. Unit Senice Factor 92.1 23.6 64.6

20. Unit Asailability Factor

21. Unit Capacity Factor (Using MDC Net) 80.5 19.6_

56.5 79.2 19.3 55.5

22. Unit Capacity Factor (Using DER Net) 7.9 39.7 16.6

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nat 6 Months tT pe, Date.and Duration of Each1:

3

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

26. Units in lest Status (Prior to Commercial Operations:

Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY COMMERCI AL OPER AIlON 8310190117 830915 FDR ADOCK 05000313

goj77, R

PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-313 UNIT I

~

9/15/83 DATE COMPLETED BY K.L.Morton TELEPHONE 501-964-3115 MONTH __ August,1983 DAY AVERAGE DA;;.Y POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) g ywe.3,g,

1 709 17 812 2

~

714 812 is 807 811 3

39 4

809 810 20 5

808 21 810 807 809 6

22 7

RnR 23 810 8

808 24 777 9

806 31 25 805 170 10 26 11 806 27 12 807 492 28 808 733 13

9 I4 24 810

,39 t

is 303 275 3:

802 l

16 INSTRUCTIONS On this format list the average daily unit power lesel in Mwe. Net for each day in the reporting month. Compute to the nearest whole megawa.i.

W177 i

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

AUGUST 1983 UNIT 1 The unit started the month power limited due to a tube ' leak in the "A" condenser.

This condition was a carry over from July. The leaking tube was located and plugged. The unit began escalating power to 100% at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on August 2.

The unit remained at 100% full power until 0034 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> on August 14.

The unit was then backed down to 95% power for turbine throttle valve testing.

During the test, the turbine tripped and subsequently the reactor tripped.

The reactor was brought critical at 0948 hours0.011 days <br />0.263 hours <br />0.00157 weeks <br />3.60714e-4 months <br /> and the generator was placed on line at 2122 hours0.0246 days <br />0.589 hours <br />0.00351 weeks <br />8.07421e-4 months <br />.

The unit escalated in power and attained 100% full power operation at 0826 hours0.00956 days <br />0.229 hours <br />0.00137 weeks <br />3.14293e-4 months <br /> on August 16.

The unit remained at 100% power until 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on August 24 when the unit tripped due to the "B" MSIV drifting closed.

The MSIV closure was caused by loss of air to a ruptured air filter in the MSIV air supply line.

The unit was placed back on line at 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br /> on August 25.

The unit maintained 25% power until 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> on August 26 when a power reduction was begun to replace PSE-6604, the MS Gland Seal steam rupture disc. Once the repair was made, the unit was tied back on line at 0722 hours0.00836 days <br />0.201 hours <br />0.00119 weeks <br />2.74721e-4 months <br /> and escalated in power to 42% where a power hold was established due to a bad condensate polisher.

At 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br /> with four (4) polishers in service, a power escalation was commenced to 67% where polisher WP reached 65 psi. The unit remained there until 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> on August 29; at this time, the power level was raised to 90%. The unit stayed there until 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> and subsequently reached 100% and remained there until 0759 hours0.00878 days <br />0.211 hours <br />0.00125 weeks <br />2.887995e-4 months <br /> on August 31. At this time, the unit tripped due to an unexplained feedwater pump trip. The unit was restored to power with the reactor going critical at 1733 hours0.0201 days <br />0.481 hours <br />0.00287 weeks <br />6.594065e-4 months <br /> and the unit tied on line at 2203 hours0.0255 days <br />0.612 hours <br />0.00364 weeks <br />8.382415e-4 months <br />. The unit finished the month in a power escalation.

e

DOCKET NO. 50-311 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT N AME ANO-Unit 1 DATE S m 9-_

14A1 COMPLETED B.

K.

L. Morton REPORT MONTH AUGUST TELEPHONE (501) 96/4-111s 3

c

'x:

=.

.i ?

g fgX Licensee 3-r, b.,

Cause & Corrective n

No.

Date g

3g

.s

,;5 g 5 Event 77 6-.?

Action to y, E 5

jgg Report :

EV

!O Prevent Recurrence H

6 83-04 830814 F

20.8 A

3 N/A HA TURBIN Turbine tripped during turbine throttle valve testing. Returned to power.

83-05 830824 F

19.8 A

3 N/A PA FILTER Ruptured air filter on air supply line to MSIV caused loss of air and subsequent drifting closed of MSIV, causing the unit to trip. Replaced filter and returned to power.

83-06 830826 F

4.3 A

1 N/A HD XXXXXX Shutdown to replace Main Steam Gland Seal steam rupture disc. Returned to power upon completion of replace-ment.

83-07 830831 F

14.1 A

3 N/A CH PUMPXX The unit tripped due to an unex-plained main Feedwater Pump trip.

Returned unit to power.

3 4

I 2

Method:

Exhibit G - Instructions F: Forced Reason:

1-Manual for Preparation of Data S: Scheduled A Equipment Failure (Explain)

B. Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee 3-Automatic Scram.

Event Report (LER) File (NUREG.

C Refueling 4 Continuation 0161)

D-Regulatory Restriction E-Operator Training & License Examination 5-Load Reduction 5

F-Administ rative 9-Other Exhibit I - Same Source G-Operational Error (Explain) t9/77)

Il-Other (Explain)

UNIT SHUTDO'aNS AND POWER REDUCTIONQ INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearing on the report form.

.,4cport period. In 3ddition,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 than 20% reduction LICENSEE EVENT REPORT #.

Reference the applicable

. in ave' rage daily power level 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 reduction. Enter the first four parts (event year, sequential snould b'e noted, even though the unit may not have been shut down completely. For such reductions in power level, report number occurrence code and report type) of the fne l

the duration should be listed as zero, the method of reduction part designation as described in item 17 of instructions for should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Repori Action to Prevent Recurrence column should explain. The (LER) File (NUREG.0161). This information may not he Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns. of cource. smce should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of the outage or power reduction.

n t a reportable occurrence 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 shutdow i or significant reduction in 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 in another.

reduction originated sh'ould be noted by the two digit code of

~

~

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 umt has achieved its first power generation, no num-for 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 7.Z 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 Entry beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-Oltil1.

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

or significant power reductions are reported.

TYPE. 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 valve operated through error: list valve as initiated by no later than the weekend following discovery component.

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

If a chain 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. includ.

completed in the absence of the condition for which corrective ing the other components which fail. should he described action 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 existing code should be de-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.

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

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

The column should include the specific cause for each shut down or significant power reduction and the immediate and REASON. Categorize by letter designation in accordance contemplated long term corrective action taken, if appmpo-with the table appearing on the report form. If category 11 ate. This column should also be used for a description of the must be used. supply brief comments' major safety-related corrective maintenance performed dunng the outage or power reduction including an identification of METHOD OF SHUTTING DOWN THE REACTOR OR the critical path activity and a report of any single release of REDUCING POWER. Categonee by number designation radioactivity or single radiation exposure specifically associ-3 ote that this differs from the Edisen Electric Institute sted with the outage which accounts for more than 10 percent N

(eel) definitions of "Forceu Partial Outage" and " Sche.

of the allowable annual values.

duled 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 ihn is too small a change to warrant explanation.

narrative.

~

REFUELING INFORMATION l.

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

To be determined 7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

a) 177 b) 316 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 968 increase size by 9.

The projected dr.te of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

DATE:-

~

~

~ - -

~~

c.

O o

ARKANSAS POWER & LIGHT COMPANY POST OFF!CE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501)371-4000 September 15, 1983 1CAN098305 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information Office of Resource Management U. S. Nuclear Regulatory 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 August 1983 for Arkansas Nuclear One - Unit 1.

Very truly yours,

./ O//f onn R. Marshall Manager, Licensing JRM:SAB:rd Attachment cc:

Mr. John T. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 if; Mr. Richard C. DeYoung i

Office of Inspection and Enforcement I

U. S. Nuclear Regulatory Commission Washington, DC 20555 MEMBEA MsOOLE SOUTH UTIUT:ES SYSTEM

)