ML20069A073

Monthly Operating Rept for Jan 1983

ML20069A073
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/15/1983
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20069A045	List: 2CAN028312, Forwards Monthly Operating Rept for Jan 1983 ML20069A073
References
NUDOCS 8303150527
Download: ML20069A073 (7)

Text

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OPERATING DATA REPORT DOCKET NO. 50-368 DATE 2/15/R3 ~

COMPLETED BY L.5.Bramlett TELEPHONE E01 46d 1145 i

OPERATING STAlUS Notes

1. Unit Na'me: Arkansas Nuclear One - Unit 2

2. Reporting Period: __ January 1-31. 1983

3. Licensed Thermal Power (MWt): 2815

4. Nameplate Rating (Gross MWe): 942.57

5. Design Electrical Rating (Net MWe): 912 097

6. Maximum Dependable Capacity (Gross MWe):

7. Masimum Dependable Capacity (Net MWe): 858

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

9. Power Lesel To Which Restricted. If Any (Net MWe): NONE

10. Reas<ms For Restrictions. If Any:

i This Month Yr..to-Date Cumulatise 744.0 744.0 25,008.0

11. Hours In Reporting Period

12. Number Of flours Reactor Was Critical 198.5 198.5 16.354.7 l

13. Reactor Resene Shutdown Hours 45.6 45.6 1.384.1

14. Ho irs Generator On-Line 141.6 141.6. 15.710.3 I 15. Unit Resene Shutdown Hours 0.0 0.0 75.0

16. Gross Thermal Energy Generated (MWH) 387.118.0 387.118.0 38.638.179.0 124.146.0 124.146.0 12.499.450.0

)l 17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWHi 11R.323. 11R.123. 11.836.067.

19. Unit Senice Factor 19.0 19.0 62.8

, 20. Unit Availability Factor 19.0 19.0 63.1

21. Unit Capacity Factor (Using MDC Net) 18.5 18.5 55.2

22. Unit Capacity Factor (Using DER Net) 17.4 17.4 51.9

23. Unit Forced Outage Rate 81.0 81.0 23.0

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

NONF

25. If Shut Down At End Of Report Period. Estimated Date of Startup: February 2. 1983

26. Units In Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICA LITY i INI TI A L ELECT RICI TY CO\lMERCIAL OPER AllON 8303150527 830215 PDR ADOCK 05000368 cof77, R PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-368 UNIT 2 DATE 2/15/83 COMPLETED BY I S _ Rramlett TELEPHONE 501-964-3145 MONTH 11a nita rv . 19R1 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 862 37 0 2 860 18 0 3 856 39 0 4 845 20 0 5

859 21 0

6 649 22 0 7 0 23 0

0 0 8 24 9 0 25 0 10 0 26 0 1I 0 0 27 0

12 28 0 13 0 29 0 14 0 39 0

0 0 is 3, 16 0 INSTRUCTIONS On this format, list the average daily unit power level in MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.

4 (9/771

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- JANUARY 1983 UNIT 2 The unit began the month at 100% full power (FP). On January 3, power was reduced to 96% FP for moderator temperature coefficient (MTC) testing. The unit was returned to 100% FP on January 4 after completion of the MTC test.

On January 6, steam generator chemistry went out of specification; this incident was caused by high sodium levels. Power was reduced and the unit was taken off line to complete condenser tube plugging. On January 9, while in Mode 5, a small leak was detected in the "A" Loop Shutdown Cooling Heat Exchanger. The unit remained shutdown through the end of the month in order to find and isolate the heat exchanger tube leaks.

50-368 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET UNIT NAMENO. ANO-Uni t 2 DATE Foh 14R1 COMPLETED BY L.S. Bramlett REPORT MONTH January TELEPHONE 501-964-3145 n.

, .5 ? 3 Y Licensee ,E g c?

Cause & Corrective Action to No. D.ite c- E i; EE Event s7 S $:g $ jij $ Report : rN 0 j0 Prevent Recurrence c

83-01 830106 F 56.9 F 1 NONE ZZ ZZZZZZ The unit was shutdown because of high sodium levels in the steam generators, procedurally out of specification chemistry. Corrective action taken was to plug the con-denser tubes which were leaking.

830109 F 545.5 B N/A 83-003 SF HTEXCH The unit was again shutdown because of "A" loop shutdown cooler tube leaks. Corrective action was to plug leaking tubes.

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

E-Operator Training & License Examination 5-Load Reduction F-Administrative 5 9-Other Exhibit I - Same Source l G Operational Error (Explain)

W/77) Il-Other (Explaini

UNIT SHUTDO5NS 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 *. 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 />) reportable occurrence pertaining to the outage or power should b'e noted, even though the unit may not have been reduction. Entre the first four parts (event year. sequential shut down completelyl . 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 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 Repon 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, 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 shutdown orsignificant 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 in 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 calumn should indicate the date of the : tart 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-0161 L 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 8.. 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-l 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 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 for end of the report period and pick up the ensuing down time

in the following report periods. Report duration of outages events where a component. designation is not applicable.

l rounded to the nearest tenth of an hour to facilitate summation.

The sum of the total oulage hours plus the hours the genera. CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-l tor was on line should equal the gross hours m the reportmg RENCE. Use the column in a narrative fashion to amplifs m '

l pe nod. explain the circumstances of the shutdown or power reduction The column should include the specitle cause for each shm.

REASON. Categorize by letter designation in accordance down or signilicant power reduction and the'immediate and l

with the table appearing on the report form, if category 11 contemplated long term corrective action taken. if appropo-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 METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction inchtding an identification of REDUCING POWER. Categorize by number designation the critical path activity and a report of any single release of radioactivity or single radiation exposure specifically associ-INote that this differs from the Edison Electric Institute ated with the outage which accounts for more than 10 percent (EEI) definitions 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 point. For larger power reactors. 30 MW and reference the shutdown or power reduction for this is too small a change to warrant explanation. narrative.

REFUELING INFORMATION

1. Name of facility. Arkansas Nuclear One - Unit 2

2. Scheduled date for next refueling shutdown. November 1,1983

3. Scheduled date for restart following refueling. February 1. 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)?

To be determined

5. Scheduled date(s) for submitting proposed licensig action and I supporting information. November 1, if applicable

, 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.

N/A

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 112

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 485 increase size by 503

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

- - ' ~

DATE: ~1991~

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CHALLENGES TO THE SAFETY VALVES FAILURE FOR ANO-2 This annual report is being submitted in accordance with the requirement of NUREG-0737, Item II.K.3.3.

ANO-2 has experienced no challenges due to system conditions to the Primary System Code Safeties (PSCS) during the year 1982. The Unit does not have an Electromatic Relief Valve (ERV).

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