ML19261D459

Monthly Operating Rept for May 1979

ML19261D459
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/14/1979
From:	Shively C ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19261D455	List: ML19261D454 ML19261D459
References
NUDOCS 7906190273
Download: ML19261D459 (5)

Text

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AVER AGE D AILY UNIT P0hER LEVEL DOCKET NO. 50-368 Lwir ANO-2 D**D 'D eo e.s J .

ff1 h.l u o DATE June 14,1979 COMPLETED By C.N. Shivelv TELEPHONE (5011 968-2519

\10Nni May DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (Mhe NetI (MWe Net)

' 0 17 2 0 18 0 3 0 19 0 4 0 20 0 5

0 21 0 6

22 0 7 0 23 0 s 0 24 0 9 0 25 0 10 0 26 0 27 0 12 0 28 0 13 0 -

29 0 14 0 30 0 15 0 31 0 16 0 2307 222 INSTRUCTIONS

1. 'N#' '"t each Jay m the ' 0, ttm.; ns.inth. Compute to 9e r.earest Ihol e l p 7 9 0 619 0>73

OPERATLNG DATA REPORT DOCKET NO 50-368 DATE June 14, 1979 CONIPLETED BY C.N. Shively TELEPHONE (501: 968-2519 OPERATING STATUS '

1. Unit Name: Arkansas Nuclear One - Unit 2 Notes

2. Repoeing Penod: Mav 1-31. 1979

3. Licensed Thermal Power (51%t): 2315

4. Nameplate Rating (Gross \lhe): 959

5. Design Electrical Rating (Net SIWE): 912

6. Starimum Dependable Capacity (Gross 5twe): NA 7 Niaximum Dependable Capacity (Net 31We): NA

5. If Changes Occur in Capacity Ratings (Items Number 3 Through 7; tince Last Report.Gise Reasons:

None

9. Power Level To which Restricted.lf Any(Net 5tWer Ncne 10 Reasons For Restrictions. lf Any: NA This Month Yr..to-Da te Cumularise

11. Hours in Reporting Period 744.0 3623.0 4367.0

12. Number Of Houn Reactor was Critical 0.0 680.9 1115.8 1.1 Reactor Resene Shutdown Hours 388.3 1705.3 1847.5 14.' Hours Generator On Line 0.0 603.1 655.9

15. Unit Reserve Shutdown Hours 0.0 1.1 1.1

16. Gross Thermal Energy Generated (51WH) 0.0 321836. 36A414.

1" Gross Electrical Energy Generated (5tWM) 0 9_,__,. 70137 7;7n4.

16. Net El ctrical Energy Generated (51WH) 0.0 9 2 t s 7. 5Atal.

19. Unit Senice Factor *

20. Unit bailability Factor

21. Unit Capacity Factor (Using MDC Net) NA Until_Commercini noeratie

. Unit Capacity Factor (Using DER Net)

23. Unit forced Outage Rate -

24. Shutdowns Scheduled Oser Ne.st 6 Months (Type. Date.and Duration of Each1:

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

o. Units in Test Status (Prior to Commercial OperationL Forecast Achieved .

INITIA L CRITICA LITY -

12/Oc;778 INITIAL ELECTRICITY -

12/26/78 CO\t\tERCIAL OPER ATION -

2307 223 (4/77 )

L DOCKET NO. 50-368 IlNil SilUIDOWNS AND l'OWER REDUC 110NS ,

UNIT NAME ANO-2 DATE . lone 14. 1979 di POR I MONIll Kb y COMPLEIED BY _C.N. Shively TELEPilONE f5011 96R 9s;to 1

"i-

_ r. 5 -s

1;*1.

7 E4 1 kensee

-, 2e = g% g Cause & Coircosive No. Date c.

3g j jgy tvens  ;;; 7 g At i,,,,, g o

$E E j5g Reposi

• EU j' Pseveni Recursence 6

79-8 790122 F 300.1 A NA 79-032 El; ENGINE Emergency Diesel Generator motor fa i lu re.

790513 F 49.2 11 NA NA IIB VALVEX Main steam safety valve blowdown testing.

790515 F 270.2 A NA 79-033 CB PIPEXX RCP "C" Seal pressure sensing line leak.

790526 F 39.0 11 NA NA ilB VAINEX Main steam safety valve blowdown testing.

790528 F 85.5 A NA NA OB Pl#lPXX RCP "C" seal failure.

tN N C=_3 U -

CD N I IL 1.uicd 2

Reau >n :

.1 MethW:

4 Exhibis G InsisusIsons (w)

N S S t.i d oleil A 1.guipment l'.nlure(I xplain) 1 Manual foi Picpasation of Dana _

N 11 Maintenance oi 'Icst 2 Manual Scram. I nes> Shcess lus 1.kenwe 4, 4 C Refuchng .4 Automatic Stsam. Event Repos e 11 I RI l'alc int'RI G- b.] dJ l} Regelitory itesteission 4 Othc (I splaml 0161) '

l Opciator Isaimng1 E nenw I xannnation 1 Ailnusmes.asive 5 k __

G Opciational I snos llN '4so) ITinini 1 - Same Sunce pl/71) 11 Ot her ilNplain t '

b

REFUELING INFORMATION '

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

2. Scheduled date for next refueling stutdown. 09-01-80

3. Scheduled date for restart following refueling.

4 12-01-80 4.

Will refueling or resu=ption of operation thereafter require a technical specification change or other license acendment?

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 CTR Section 50.59)?

vas naccrintion of effects of new core loading.

5.

Scheduled date(s) for submitting proposed licensing action and supporting infor=ation. 08-01-80 6.

Important licensing considerations asscciated with refueling, e.g.,

new or different fuel design o.r supplier, unreviewed design or parfor=ance analysis methods, significant changes in fuel design, new operating procedures.

NONE 7.

The nu=her of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 0 8.

The present licensed spent fuel pool storage capacity and the si:e of any increase in licensed storage capacity that has been requested or is planned, in nu=ber of fuel asse=blies.

present_ 4 9 A increase size by n 9.

The projected date of the last refueling that can be discharged to the cpent fuel pool cssu=1ng the present licenced capacity.

DATE: 1988 2307 225 umm Q

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- MAY, 1979 UNIT II ,

The Emergency Diesel Generator #2 repair continued from the previous conth until May 4, when acceptance testing was initiated. The test-ing of the diesal was successfully completed on May 11, and the emer-gency diesel generator unit was declared operable.

A Crosby pressure relief valve was obtained and mounted on the Main Steam Header in place of one of the existing usin steam relief valves.

The unit was heated up to Mode 3 condition on May 13. Relief setpoint and blowdown testing was conducted and based on the results, it was decided to replace all of the original main steam code relief valves with Crosby valves.

On May 14, during relief valve testing, a non-isolatable leak was discovered on the "A" reactor coolant pump upper seal cavity pressure sensing line. Following the completion of the seal sensing line repair and Crosby main steam relief valve installation, the unit was heated up to Mode 3 conditions on May 26.

Testing of the new main steam relief valve setpoint and blowdown was begun; however, leakage from the "A" Reactor Coolant Pump seal forced the unit to a Mode 3 condition. Repairs continued throughout the remainder of the month.

2307 226

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