ML19350E692

Monthly Operating Rept for May 1981

ML19350E692
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/15/1981
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19350E691	List: ML19350E690 ML19350E692 ML19350E695
References
NUDOCS 8106230446
Download: ML19350E692 (6)

Text

_

. AVERAGE DAILY UNIT POWER level. 4 50-313 9

DOCKEiNO.

LNIT

~

t or rE 6-15-81 COMPLETED BY L.S. 8ramlett TELEPHONE (5013968-2519 MCNm May, 1981 DAY AVERAGE DAILY POh'ER LEVEL DAY AVERAGE DALLY POWER LEVEL (MWe-Net) (Mwe-Net) 1 825 37 824 2 826 ig 824 3 827 ', 824 4 825 ,o 822 5 825 821 21 6 826 ,2 820 827 23 821 8 827 ,4 822 9 828 821 25 30 829 ,6 822 33 829 822 3

i2 826 824

,3 13 465 ,, 825 j4 533 825 39 15 819 , 824 al 16 822

, INSTRUCTIONS On this format list the are: .: :ily unit power leselin MWe Net for each day in the reporting snonth. Compute to  !

the nearest whole rnegautt.

(9.I77)

THIS DOCUMENT CONTAINS P00R QUAUTY PAGES

f r ,

t x

OPERATING DATA REPORT -

DOCKET NO. 50-313 DATE 6-15-81 COMPLETED BY L.S.Bramlett TELEPHONE IRn1 j aM-2519 O' PERATING STATUS Notes

1. Unit Name: Arkansas Huclear One - Unit 1

2. Reporting Period:

May 31, 1981 2568

3. Licensed Thermal Power (MWt s:

4. Nan.eplate Rating (Gross MWel:

902.74 850

5. Design Electrical Rating (Net alwe):

883

6. Maximum Dependable Capacity (Gross alWe):

86

' 7. Maximum Dependable Capacity (Net SIWE):

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

Nnna - -

None

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

10. Reasons For Restrictions.lf Any: WA ,,

This Month Yr to-Datn Cumulative

11. Hours in Reporting Period 744.0 3623.0 56538.0 734.7 1862.4 37652.7

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shu:down Hours 0.0 149.0 5044.0 l'4. Hours Generstor On-Line 730.5 1786.0 36831.0

15. Unit Reserve Shutdown Hours 0.0 0.0 817.5

- 16. Gross Thermal Energy Generated IMWH1 1855601 4334598 88508564-

17. Gross Electrical Energy Generated (MWH) 624288 1451530 29150091

18. Net Electrical Energy Generated IMWHI 597488 1386160 27801799

19. Unit Service Factor 98.2 49.3 65.1

20. Unit Availability 1 actor 98.2 49.3 66.6

21. Unit Capacity Factor (U>ing MDCNet) 96.1 45.8 58.8

22. Unit Capacity Factor (Using DER Neti 94.5 45.0 57.9 23.- Unit Forced Outage Rate 1.8 2.0 16.7

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

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved 4

INITIA L CRITICA LITY I

i INITIA L ELECTRICITY COMM ERCIAL OPERATION l i

(0/771

,, . _ _. _. . . _ - . - ,_-. _ . ~ . _ _ . - _ . - - . . . . . . _ _ _ _ _ _ , ~ - , . _ . _ - .

REFUELING INFORMATION E,' OI

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

2. Scheduled date for next refueling shutdown. 1/1/83

3. Scheduled date for restart following refueling. 3/15/83

4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license acend:ent?

If answer is yes, what, in general, will th-se be?

If answer is no, has the reload ' fuel desi 8n and core configuration been reviewed by ycur Plant Safety Review Coc=ittee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Yes.

Reload reoort and associated m Josed Technical Soecification chances. Also, the safety analysis 'of eicht demonstrationrhigh burn-uo assenblies will be orovided.

5. ~ Scheduled date(s) for submitting proposed licensing action and -

supporting infon=ation. 10/1/82 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 reload 72 fresh fuel assemblies and operate for approximately 16 months._E,ight of which will be hiah burn-uo test assemblies.

7.

The number of fuel asse=blies (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 nu=ber of fuel assemblie.s.

present 589 increase size by 0 9.

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

DATE: 1986

DOCKET NO. 50-313 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME ANO-Unit I DATE 6-1-R1 COMPLETED BY L.S.Bramlett REPORT MON ril May 1981 ,

(5011968-2519 TELEPflONE

.$ g  ; Y Licensee [v, t C.ause & Currective No. Date g 5g 4 ,s& Eveni g g'8 Action to H yE 5 jgg Repori # mV g' Prevent Recurrence d

.)

81-05 810513 F 13.5 A 3 N/A lift Instru A false condenser hotwell level signal caused the condensate pumps to trip, this caused the MFW pumps to trip on low suction pressure and in turn tripped the reactor on MFW-pump anticipatory trip circuitry.

The false signal will be investi-gated during a future outage to confinn preliminary results of a possible ground fault.

I 2 3 4 F; Foiced Reason: Method: Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data D Maintenance or 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 & Ucense Examination 5-Load Reduction F Administrative 5 9-Other Exhibii ! Same Source C-Operational Error (Explain) 01/77) Il-Othe r (Explain)

UNIT SHUTDO*aNS AND POWER REDUCTIONS I

INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearinF on the report rom:.

t* port period. In addition,it should be the source of explan. If category 4 must be used, supply brief ecmments.

ation of significant dips in average power levels. Each signi.

ficant reduction in po"er level (greater than 20% reduction . LICENSEE EVENT REPORT s. Reference the applicable in average daily pow t 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 tie noted, enn though the unit may not have been .redoction. Enter the first four parts (event year, sequental shut dowm cornpletelyl . For such reductions in power level, report number, occurrence code and report type) of the rise the duration should be listed as zero,the method of reduction part designation as described in item 17 of Instructions sur 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 shotC 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 course. since should be used to provide any needed explanation to fully further investigation may be required to ascertain 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 currelation should be ber assigned to each shutdown orsigni'icant reductionin power noted as not applicable (N/A).

for that calendar par When a shutdow.t 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 :eport periods a 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 Gst power generation, no num- f r Licensee Event Report (LER) File (b UREG.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 ! - Instractions for Preparation of Data Entn beginsin one report period and ends in another, an en.ry should Sheets for Licensee Event Report (LER) File (SUREC.01oi1.

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

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 offoormal cor3ition. 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 la the absence of the condition for which corrective ing the other components which fail. should be described

~

action wu 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.

end of the report period and pick up the ensuing down time s gnated XXXXXX. The code ZZZ2.ZZ should be used for in the following report periods. Report duration of outages events where a component. designation is not applicable.

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

The sum of the total outage hours plus the hous the genera. CAUSE & CORRECTIVE ACTION TO PREVENT Pr. CUR.

tor was on line should equal the gross hours in the reporting RENCE. Use the co'umn in a narratise fashion to amplin m period. explain the circumstances of the shutdown or power reduction

. - - - ~ . . .

The column should include the specific cause for each shut REASON. Categcrize by letter designation in accordance *" ' '** E" ** # " "nd the'immediate and with the table appening on the report form. If category H c ntemplated long term corrective aetm.n taken. if appropn.

must be used. supply brief comments. ate. This column should also be used wr a description of the major safety.related corrective maintenance performed during MCTHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification os REDUCING POWER. the critical path activity and a report of any single release or, Categorize by number designation . radioactivity or single radiation exposure specifica!!y INote that this ditfers from the Edison Electric Institute sted with the outage which accounts for more than 10 percent (eel) definitions of " Forced Partial Oute" and " Sche. of the allowable annual values.

duled Partial Outage " For these terms. EEI 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 thts is tuo small a change to warrant explanation. narrative.

d NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- MAY 1981 UNIT I The unit operated at 100% full power and continued there until 5/13/81.

On this date the reactor tripped on the anticipatory trip circuitry for loss of feedwater pumps. The feedwater pumps tripped on low suction pressure when the condensate pumps tripped on a false condenser hotwell low level signal. The unit returned to 100% power operation on 5/15/81 and continued operation there through the remainder of the month.

A correction was made of 1.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> additional to the unit forced outage hours for the yearly totals and cumulative totals due to an error in the March 1981 report.

~

.g__ .

e f

i I

--- - ~ = - ' ' '