ML20065T128

Monthly Operating Rept for Aug 1982

ML20065T128
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/23/1982
From:	Gertsch A ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20065T123	List: 1CAN098209, Forwards Monthly Operating Rept for Aug 1982 ML20065T128
References
NUDOCS 8211020227
Download: ML20065T128 (6)

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OPERATING DATA REPORT DOCKET NO. 50-313 DATE 9/23/82 COMPLETED BY A. J. Gertsch TELEPilONE 501-964-3155 OPERA T ING STA1 US N"

I. Unit Name: n.' kansas Nuclear One - Unit 1

2. Reporting Period:

August 1-31, 1982

3. Licensed T hennal Power (MW I: 2568

4. Nameplate Rating (Gross MWel: 902.74

5. Design Electrical Rating (Net MWe): 850

6. Maximum Dependable Capacity (Gross MWe): 883 836 ,

7. Maximum Dependable Capacity (Net MWe):

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

9. Power Lesel To Which Restricted.lf Any (Net MWe): None

10. Reasons For Restrictions. lf Any: N/A This Month Yr. to.Date Cumulatise

11. Ilours in Reporting Period 744.0 5831.0 67506.0

12. Number Of liours Reactor Was Critical 426.3 4100.7 46348.2

13. Reactor Resene Shutdown llours 0.0 0.0 5044.0

14. Ilours Generator On-Line 406.8 4040.3 45424.1

15. Unit Resene Shutdown ilours 0.0 0.0 817.5

16. Gross Thermal Energy Generated iMWill 901905.0 8768639.0 108298845.0

17. Grow Electrical Energy Generated (MWill 285450.0 2894650.0 35731406.0 269973.0 _2]J5482.0 34061883.0 Ih. Net Electrical Energy Generated (MWill 54.7 69.3 67.3

19. Unit Senice Factor

20. Unit Asailability Factor 54.7 69.3 68.5 43.4 56.3 60.4

21. Unit Capacity Factor (Using MDC Nett

22. Unit Capacity Factor (Using DER Net) 42.7 55.4 59.4 45.3 15.3 16.0

23. Unit Forced Outage Rate 24 Shot <founs Schedo!n! Over Next 6 Momb iT)pt Date.nnd Duration of Eacht

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

26. Units In lest Status (Prior to Commercial Operation): Forecast Achiesed .

INill A L CRIIICA LITY INill A1. ELECT RICIIY COM'.1ERCI AL OPLR A llON 8211020227 820923 PDR ADOCK 05000313 R PDR to!77 :

AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-313 I

UNIT DATE 9/22/32 COMPLETED By A. J. Gertsch TELEPHONE 501-964-3155 MONm August 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL -

(MWe Net) (Mwe-Net )

i 809 17 0 2 807 47 18 3 Af)7 19 591 4 804 20 750 187 5 21 790 6 0 '

637 22

- 0 7 23 89' 0

8 24 272 9 0 337~

25 jo 0 26 681 0

11 27 802 0

12 28 804 0

13 29 697 0

34 672 30 is 0 5 31 0

16 INSTRUCTIONS On this format.hst the aserage dail) unit power leselin MWe Net for each da) in the reportm; month.Compuie to the nearest whole megawatt.

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- AUGUST, 1982 UNIT ONE Unit One began the month of August at 99.82% full power. At 0602 hours0.00697 days <br />0.167 hours <br />9.953704e-4 weeks <br />2.29061e-4 months <br /> on August 5, the reactor / turbine tripped on a RPS anticipatory trip based upon a false indication of loss of both main feedwater pumps. The trip occurred as reactor power was being reduced for recovery of a dropped control rod. The RPS sensed failure of both main feedwater pumps as the "B" pump was tripped off line. Checks of the main feedwater pump anticipatory trip system have not identified the cause of the trip. On August 18, as the unit was returning to power, the reactor  !

was manually tripped from 13% full power following auto actuation of i SLBIC. Failure of the #3 governor valve limiter circuit prevented the valve from fully closing causing header pressure to decrease uncontrollably. Repairs to the governor valve were effected and Unit 1 returned to 100% full power August 21.- On August 22, Unit 1 tripped on high reactor power following a malfunction of the main turbine overspeed protection circuit. Header pressure oscillations induced by the erroneous speed condition caused the ICS to overcorrect reactor power.

The Unit tripped on the high power setpoint of "B" and "D" RPS channels. On August 23, Unit 1 returned to power operations and achieved 100% full power August 27. August 29, reactor power was reduced to approximately 91% full power following failure of the expansion joint in the extraction line to the E-4A feedwater heater.

Unit 1 ended August at 92.34% full power.

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DOCKET NO.

50-313 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT N AME ANO-UNIT 1 DATE Sept. 8 1982 COMPLETED BY A.J. Gertsch REPORT MONTH AUGUST TELEPHONE 501-964-3155 n.

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, .5 g 3 jYE Licensee ,E-r, [q, Cause & Corrective No. Dite 3g 2gE Event g ['E Action to H

i yE $

3 j5g Report r mV g' Prevent Recurrence d

82-04 820805 1 320.1 A 3 NA IA INSTRU Malfunction of the nnin feedwater anticipatory trip system during a power runback for dropped rod recovery caused the unit to trip on false indication of loss of both main feedwater punps.

82-05 820822 1 17.1 A 3 NA HA 'IURBIN ICS overcorrection to header pressure oscillaticms caused by a malfunction of the main turbine overspeed protecticn circuit initiated a RPS trip for high reactor power.

3 4 I 2 F: Forced Reason: Method: Exhibit G-Instructions A-Equipment Failure (Explain) 1-Manual for Preparation of Data S: Scheduled 2-Manual Scram. Entry Sheets for Licensee B-Maintenance of Test C Refueling 3 Automatic Scram. Event Report (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 I - Same Source (9/77) li 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 *. 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. Enter the first four parts (event year, sequential shut down completely l. For such reductions in power level, fePort 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 Repori 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 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 as 770814. When a shutdown or significant power reduction from Exhibit 1 - Instractions for Preparation of Data Entry begins in one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-OlolI.

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 reqmred 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 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-signated XXXXXX. The code ZZZZZZ should be used fm 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.

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

The sum of the total outage hours plus the hours the genera. CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-RENCE. Use the column in a narrative fashion to amplifs m tor was on line should equal the gross hours m the reportmg period. explain the circumstances of the shutdown or power retiuetion l The colutun should include the specilie cause for each shui I

down or significant power reduction and the ~immediate and REASON. Categorize by letter designation in accordance with the table appearing on the report form. It 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 msjor safety-related conective mamtenance perfomied dunng METHOD OF SHUTTING DOWN THE REACIOR OR the outage or power reduction including an identification of REDUCING POWER. Categorite by number designation the critical path act.vity and a report of any single release of radioactivity or single radiation exposure specifically associ-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 Outage" and " Sche, of the allowable annual values.

duled Putial 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 w arrant explanation. narrative.

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u ust 1982 REFUELING INFORMATION 1.- Name of facility. Arkansas Nuclear One - Unit 1

2. Scheduled date for next refueling shutdown. November 26. 1982

3. Scheduled date for restart following refueling. February 15. 1983

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 Specification chanaes.

5. Scheduled date(s) for submitting proposed licensing action and supporting information. November 1, 1982

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.

tiill reload 72 fresh fuel assemblies, four of which will be hiah burn-uo test assemblies. and onorate for annrnximatelv 16 months.

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

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

to the spent fuel pool assuming the present licensed capacity.

DATE: 1986 l

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