ML20054M140

Monthly Operating Rept for May 1982

ML20054M140
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/15/1982
From:	Gertsch A ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20054M139	List: 1CAN068209, Forwards Monthly Operating Rept for May 1982 ML20054M140
References
NUDOCS 8207090293
Download: ML20054M140 (5)

Text

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OPERATING DATA REPORT DOCKET NO.

50-313 DATE 5/15/82 COMPLETED BY A.J.Gertsch TELEPHONE (5011964-3155 OPERATING STA I US N"

Arkansas Nuclear One - Unit 1

1. Unit Name:

2. Reporting Period:

May 1 - 31. 1982

3. Licensed Jhermal Power (MWt):

2568 902.74

4. Nameplate Rating (Gross MWe):

850

5. Design Electrical Rating tNet MWe):

883

6. Masimum Dependable Capacity (Gross MWe):

OOO

7. Masimum Dependable Capacity (Net MWe);

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

None

9. Power Lesel To which Restricted. lf Any (Net MWe):

10. Reassms For Restrictions. If Any:

N/A This Month Yr..to Date Cumulatise 744.0 3,623.0 65,298.0 II. Ilours in Reporting Period 388.9 2,435 1

-44,683.3

12. Number Of liours Reactor Was Critical 0.0 0.0 5,044.0

13. Reactor Resene Shutdown 11oun 359.7 2,399.0 43,782.8

14. Ilours Generator On-Line 0.0 0.0 817.5

15. Unit Resene Shutdown lloun

16. Gross Thermal Energy Generated (MWil) 486,646.

4,816,699.

104,346,905.

17. Gross Electrical Energ, Generated (MWil) 145,644.

1,605,220.

34,441,976.

5

18. Net Electrical Energy Generated (Mwill 133,056.

1,518,386.

32,834,787.

48.3 66.2 67.1

19. Unit Senice Factor 48.3 66.2 68.3

20. Unit Avaitahility Factor

21. Unit Capacity Factor (Using MDC Net) 21.4 50.1 60.1 21.0 49.3 59.2

(

22. Unit Capacity Factor (Using DER Net,

23. Unit Forced Outage Rate 0.0 0.0 15.5

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

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

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

Forecast Achiesed INITI A L CRITICA LITY INI fl A L ELECTRICI TY COM\\1ERCl \\ L OPER \\ TION t

8207090293 820618 PDR ADOCK 05000 R

AVERAGE DAILY UNIT POWER LEVEL 50-313 DOCKET NO.

UNIT I

DATE 5/15/82 COMPLETED BY A. J. Gertsch TELEPHONE (501) 964-3155 MONm May 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(ywe.3, y 1

0 305 i7 0

316 2

ig 3

0 39 315 4

0 297 20 5

0 297 7,

0 346 6

,2 7

0 718 33 8

0 792 24 9

0 197 23 10 108 0

,6 ii 372 0

2, 12 296 0

,g 13 297 0

39 14 298 0

30 is 297 0

3i 16 296 l

INSTRUCTIONS On this format list the aterage daily unit power lesel in MWe Net for each day in the reporting anonth. Compute to I

the nearest whole megawatt.

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l (9/77 )

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a WP-0331 NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- MAY,1982 UNIT I The spring outage for replacement of the "A" OTSG feedwater nozzles was extended into the first 10 days of May when a radiography inspec-tion of the HPI nozzles revealed potential problems in all but the "C"

nozzle.

"A" and "B" nozzles were replaced and the "D" nozzle was re-sized, a leaking seal on the "A" Decay Heat Pump required replacement of the pump seals and bearings, and Generator Hydrogen Seal Oil leaks required replacement of the-hydrog'en seal rings.

Unit One began heat up May 3, and the reactor was brought critical at 0720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> May 9.

The generator was subsequently brought on line at 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br /> May 10.

High level indications and the possibility of tube leaks in the E-IA, E-3A, and E-4A 'feedwater heaters delayed power escalation as the cause of the high levels was investigated. Failure of the E-SA, E-6A, and E-8A feedwater bypass valve in the bypass posi-tion had caused the high levels in E-3A and E-4A.

Following repair of the bypass valve and tube leaks in the E-1A feedwater heater, Unit One resumed power escalation on May 22.

The Unit achieved 97.17 percent full power May 24.

Power was limited due to high "A" OTSG 1evel and low feedwater pump suction pressure. At'0540 hours0.00625 days <br />0.15 hours <br />8.928571e-4 weeks <br />2.0547e-4 months <br /> May 25, high radiation alarms on the condenser off gas and the "A" OTSG N-16 monitors alerted operators of a possible steam generator tube leak. At 1213 hours0.014 days <br />0.337 hours <br />0.00201 weeks <br />4.615465e-4 months <br /> May 25, Unit One was brought to cold shutdown for repair of a tube leak in the "A" OTSG.

Reactor Coolant System leak rate was determined to be less than 1 gpm.

Unit One remained in a cold shutdown through the end.of May for repair of the "A" OTSG tube leak.

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DOCKET NO.

50-313 UNII SilUTDOWNS AND POWER REDUCTIONS UNIT N AME ANO-Unit 1 DATE _ June 2, 1982 COMPLETED BY A.J. Gertsch REPORT MONTil my TELEPHONE 501-964-31ss

=

.5 ?

3 j El Lisensee

,E -t, jt Cause & Correctsve No.

Date a

E2 4

2E$

Fvent 7?

c?

Action to C

j@

d Report a rN 0 fC Prevent Recurrence I

d.

82-02 820326 S

223.3 B

4 N/A CC HTEXCH Continuation of the outage to replace the feedwater nozzles in the "A" OTSG.

82-03 820525 F

161.0 A

1 012 CC HTEXCH A tube leak developed in the "A"

OTSG, Unit was brought to cold shutdown.

One tube was leaking.

Eddy current testing revealed 9 additional tubes which required plugging. Eddy current was used to verify the integrity of other tubes.

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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 Licensee C-Refueling 3 Automatic Scram.

Event Re, ort (LER) File (NUREG.

D Regulatory Restriction 4-Continuation 0161)

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

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

Exhibit 1 - Same Source N/77)

Il-Other (Explain)

UNIT SHUTDONNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearing 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 significant dips in average power levels. Each signi-ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT ar.

Reference the applicable in average 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 />)

'eportable occurrence pertaining to the outage or power should b'e noted, even though the unit may not have been reduction. Enter the first four parts (event year, sequential 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 desenbed 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 Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This mformation may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns. of course. smee I

should be used to provide any needed explanation to fully further investigation may be requised to ascertam whether or desenbe the circumstances of the outage or power reduction.

not 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 shutdown 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 m another, an entry should be made for both report periods to be sure reduction originated should be noted by the two digit code of 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 i

as 770814. When a shutdown or significant power reduction from Exhibit 1 - 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-Olot p.

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 mdicate either " Forced" or " Sche-duled." respectively, for each shutdown or significant power B.

If not a comporient 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 normal condition. It is recognized that some judg-ment is required in categorizing 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.ne other components which fail, should be described action was taken.

under the Cause and Corrective Action to Prevent Recur.

rence column.

DURATION. 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 existing code should be de-s gnated XXXXXX. The code ZZZZZZ should be used foi end of the report period and pick up the ensuing down time events where a component. designation is not applicable.

in the followmg report penods. Report duration of outages rounded to the nearest tenth of an hour to faci!! tate summation.

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

tor was on line should equal the gross hours m the reporting RENCE. Use the column in a narrative fashion to amphis on explain the circumstances of the shutdown or power reductmn pe nod.

The column should include the specific cause for each shm down or significant power reduction and the nnmediate and REASON. Categonie by letter designation m accordance contemplated long term corrective action taken. if appropo-with the table appearing on the report form. If category 11 must be used, supply brief comments.

ate. This column should also be used for a description of the major safety.related corrective maintenance performed dunng METilOD OF SilUTTING DOWN Tile REACTOR OR the outage or power reduction mcluding an identification of REDUCING POWER.

Categortie by number designation the critical path activity and a report of any single release of radioactivity or single radiation esposure specifically associ.

INote that this ditten from the Edison Electric Institute ated with the outage which accounts for more than 10 persent (EEI) defimtions of " Forced Partial Outage" and " 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 pomt. For larger power reactors. 30 MW and reference the shutdown or power reduc tmo for ihn b too small a thange to wariant esplanation.

narratise.

.s s

REFUELING INFORMATION 1.

Name of facility.

Arkansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown. 12/1/82 3.

Scheduled date for restart following refueling. 2/15/83 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 reDort and associated proposed Specification changes.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information. 9/1/82 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.

Will rninad 72 fresh fuel assemblies and operate for approximately 16 months.

Four of which will be high burn-up test assemblies.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 244 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 assemblics.

0 present 589 increase size by 9.

The projected date of the lat. refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

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DATE:

1986 i

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