ML19320D452

Monthly Operating Rept for June 1980

ML19320D452
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/15/1980
From:	Pendergraft R ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19320D451	List: ML19320D450 ML19320D452
References
NUDOCS 8007210382
Download: ML19320D452 (5)

Text

-

' p AVER ACE D ALLY UNIT POWER LEVEL

'd DOCKET No 50-368 UNIT 2

7/15/80 DATE COMPLETED BY Rex Pendergraft (501)968-2519 TELEPHONE MONDf JUNE. 1980 DAY AVERAGE D ALLY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Neti s y w e.ses, i

879-i7 881 880 is 878 3

877 19 851 4

874

o 811 5

218 812 6

0 808 O

23 806 8

79 526 24 9

847 0

s 10 876 o

3, 11 550 o

37 1:

216 o

13 874 o

14 880 o

3, is 880 NA 3

16 879 1

- INSTRUCTIONS On this fonnat !:st the aserage hii; unit puwer leselin MWe Net for each day in the rer.ortineinonth. Compute to

. the nearest whole rnegawatt.

19/77i 80072103 D

OPERATING DATA REPORT DOCKET NO. 50-368 DATE 7 /15/Hn COMPLETED BY Rex Pendergraft TELEPHONE (5011968-2519 OPERATING STATUS Arkansas Nuclear One - Unit 2-N

1. Unit Name.

Jura 1-30, 1980

2. Reporting Period:

3. Licensed Thermal Power MWtp:

2815 959

4. Nameplate Rating (Gros, Mhen:

922

5. Design Electrical Rating iNet 3 thel.

Not Vet Determined

6. Maximum Dependable Capacity,Grm MWe):Not yet Detem1in$d

7. Maximum Dependable Capacity (Net Mhe;:

8. If Changes Occur in Capacity Ratinp titems Number 3 Through 7) Since Last Report. Gise Reasons:

None

9. Power Lesel To which Restricted. If Any (Net MWel:

None

10. Reasons For Restrictions. If Any:

NA This Month Yr. to-Cate Cumulatise 720.0 2327.0 2327.0 i1. Hours in Reporting Period

12. Number Of Hour > Reactor has C: a.al 485.3 1762.3 1762.3

13. Reactor Reserve Shutdown Hours 0.0 80.9 R0.9

14. Hours Generator On-Line 478.5 1729.1 1729.1

15. Unit Rewrse Shutdown Hour, 0.0 75.0 76.0 1254162.0 4142818.0 4142818.0

16. Gross Thermal Energy Generated IMWH,

17. Gros > Electrical Energy Generated IMhill 406950.0 1356980.0 1356930.0 388381.0

_1291646.0 1291646.0

18. Net Electrical Energy Generated (MhH)

19. Unit Service Factor 66.5 74.3 74.3

20. Unit Availability Factor 66.5 77.5 77.5 59.1 60.9 60.9

21. Unit Capacity Factor IUsing MDC Net) 59.1 60.9 60.9

22. Unit Capacity Factor (Using DER Neti

23. Unit Forced Outage Rate 33.5 25.7 25.7

24. Shutdown, Scheduled Oser Next 6 MonthsiType. Date,and Duration of Eacht:

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

July 2. 1980

26. Units in Test Status iPrior to Commercial Operations:

Forecast Achiesed INITI A L CRITICT LITY INITI \\ L ELECTRICITY

( O\\l\\lERCI AL OPER \\ TION p

gil.**)

g

DOCKLINO.

50 ~168

]i UNIT SilU1 DOWNS AND POWER RLDUCllONS UNIT NA%IE ANO-IIn f e ?

DATE 7/l5/an C041PLI:IED liY llex Pandargraft RtrOR r uGN nI _ June 1 lit.EPilONE. JiO1-968-2519 1 u,3 5

c 3

?

, E "I I 8cC8850c

,j *f j'#b fJisse & foficcihe g

y

~

Dale i

3@

4

.555

. I' vent U 'g

&j Ai,imn in Report EU E'

Presen Recurreni,e E

5 A

~ d ;(:

H o

c 80-11 6-5-80 F

75,7 A

1 None llB PIPEXX Steam leak on main steam line in reactor building. Unit was cooled down'and leak repaired.

80-12 6-11-80 F

13,5 A

3 None IA INSTRLJ Two spurious DNBR/LPD trips occurred simultaneously on the core protection calculators (CPC's) 80-13 6-24-80 F

152.3 A

3 80-042/01T EA ELECON Partial loss of offsite power due to a ground fault on one of the 500KV transmissi m lines.

I 2

1 4

I i..rs ed Reamn :

Method:

l'.stutus G - Insten imos

% A l cduled A-l:quipment l'.ulure (IApl.sm) 1 -M.an ual f..r Preparainen of D.it.:

Il-Maintenance of Test 2 Manu:il Scraan.

I nis) Sheen for Iicemee C. Refueling

.LAutonutk N rain.

I vens Repois (1.1 R)I de INtlRI G.

D-Regulator) Itcstaistion 4 Ollies (lispt. sin)

Ol til I l.-Opes.itos Isanung i i nense I sanun.stion II.Adnumstraine i

i, Opes.iuona! I iro, i t spl..)

I sintin i. Sam. S.iusce ii !)

11 Other ll:splain)

REFUELING INFORMATION 1.

Name of facility.

Arkansas Nuclear One - Unit 2 2.

Scheduled date for next. refueling shutdown.

3/19/81 3.

Scheduled date for restart following refueling.

5/19/81 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license a=endment?

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 Cor:mittee to determine whether any unreviewed safety questions are associated witu the core reload (Ref. 10 CFR Section 50.59)?

Yes.

Description of effects of new core loading.

5.

Scheduled date(s) for submitting proposed licensing c tion and supporting information.

1/19/81 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.

As cart of a research and development effort, two fuel assemblies will be loaded possessing design characteristics related to extended burnup.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 58 (new, normally stored in new ruel pit) 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 486 increase size by 0

9.

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

DATE:

1989

.6

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- JUNE, 1980 UNIT II The unit was operating at 100% full powet at the beginning of this report-ing period. On 6-5-80,La forced outage occurred as a result of a steam leak on the main steam line inside the reactor building. A small main-

-steam pressure tap line had broken due to a crack in the socket veld area of the-isolation valve. All pressure taps similar to the failed tap were cut off and permanently capped to prevent a similar failure.

During the return to power, two reactor trips were experienced due to steam generator level (high and low). A return to power operation was accomplished on 6-8-80.

On 6-11-80, a reactor trip occurred when two simultaneous spurious DNBR/LPD trips were experienced (CPC ASD). The cause of the spurious trips Taas found to be related to the ground shield on the CPC signal cable.

The unit was again returned to power operation on 6-12-80.

A reactor trip occurred on 6-24-80 when a partial' loss of offsite power caused the generator output breakers to open. The loss of offsite power was due -to a ground fault on one of the 500 kv transmission lines. Follow-ing the reactor trip, reactor coolant system leakage rate was noticed to have increased. A reactor building entry was made to investigate the leak-age problem.

Investigation revealed excess reactor coolant pump seal leak-age on the "A" RCP. A decision to cool down and repair the seal was forth-coming. The unit has remained off line for the remainder of this month for RCP seal repair.

i u