1CAN028403, Monthly Operating Rept for Jan 1984

Monthly Operating Rept for Jan 1984

ML20080T861
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/31/1984
From:	John Marshall, Morton K ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
1CAN028403, 1CAN28403, NUDOCS 8403020075
Download: ML20080T861 (7)

Text

.

OPERATING DATA REPORT DOCKET NO.

50-313 DATE Jan.

1984 COMPLETED BY.K. L. Morton TLLEP110NE 501-964-3115 OPERATING STATUS

1. Unit Name:

Arkansas Nuclear One - Unit 1 N"'"

2. Reporting Period:

January 1-31, 1984

3. Licensed Thermal Power IMWil:

2568 02.74

4. Nameplate RatinglGross MWe):

5. Design Electrical RatingINet MWe).

850 883

6. Maximum Dependable Capacity (Gross MWe): 836 -

7. Maximum Dependable Capacity (Net MWel:

8. If Channes' Occur in Capachy RatinFs litems Number 3 Through 7)Since Last Report.Gise Reasons:

None.

9. Power Leiel To Which Restricted,if Any (Net MWe):

10. Reasons For Restrictions. lf Any:

T his Month Yrao-Date Cumulatise 744.0 744.0 79,939.0 j

ll, llours in Reporting Period 744.0 744.0 w,la,d

12. Number Of flours Reactor has Critical

13. Reactor Reserve Shutdown llours 0.0 0.0 5,044.0 i

14. Hours Generator On Line 744.0 744.0 51,994.2 IS. Unit Reserve Shutdown liour, 0.0 0.0 817.5

16. Gross Thermal Energy Generated (Mwil, 1.901.268.0 1.901.268.0

.123,821,565.0

17. Gross Electrical Energy Generated IMWill 640.055.0 640.055.0 40,778d20.0

18. Net Electrical Energy Generated IMWHI 614.465.0 614,465.0 38,872,853 0

19. Unit Service facto, 100.0 100.0 6b.0

20. Ur.it Availability Factor 100.0 100.0 66.1 98.8 98.8 bd.2

21. Unit Capacity I actor IUsing MDC Neti

22. Unit Capacity Factor (Using DER Net, 97.2 97.2 57.2

23. Unit Forced Outage Rate 0.0' O.0 lb.8'

24. Shutdowns Scheduled Over Next e Months (Type.Date,and Duration of Eacht:

None.

25. If Shut pow;i At End Of Report Period.Evimated Date of Startup:

26. Units In Tot Status tPriar to Commercial OperationI:

Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICil'Y COMMERCIA L OPER A TION 8403020075 840131 PDR ADOCK 05000313 R

PDR p,p y,

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-313 UNIT ONE DATE

_Jan., 1984 COMPLETED BY K. L. Morton TELEPHONE 501-964-3115 MONm January. 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL iMWe Net)

(MWe-Net)

I 827 37 829 2

828 828 18 3

828 830 828 828 4

20 5

828 829 21 827 6

22 828 7

829 828 23 8

828 24 828 9-828 25 828 no 828 826 26 i

828 27 825 12 829 823 28 13_

828 820 29 34 826 818 39 15 R76 789 3:

16 828 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

01/77 )

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

JANUARY 1984 UNIT 1 The Unit started the month at 100% full power.

At 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br /> on January 5, power was reduced to 95% due to the secondary level in the "A" OTSG reaching l

'the high level limit. The controlling operating range level transmitter was l

switched from LT-2 to LT-3 and the power was escalated back to 100%.

At 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> on January 20, the secondary level in the "A" OTSG once again reached the high level limit on the contro' ling operating range level transmitter.

Reactor power was reduced to 95.5% in order to reduce the IcVel to an acceptable limit.

The Unit remained at 97.5% power until 2235 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.504175e-4 months <br /> on January 30 when the power was reduced to 95% due to suspected tube degradation in the "A" OTSG.

At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on January 31, the Unit was lowered to 94% power and remained there through the.end of the month.

( ",

a e

4

na

.s i %

DOCKF7NO.

50-313 UNIT SHUTDOWNS AND POWER REDUCTIONS U.VIT NAME ANO - Ur i t 1 DATE Feb.

1584 COMPLETED BY Ken Morton REPORT MONTH Januarv.1984-TELEPHONE _ 501- % 4-3115 a

'! E 3

y Y5 Licensee

,En, Cause & Corrective l

No.

Date g

3g j

,g g &

Event

??

n.'8 Action to

$E 5

35g Report *

'E U Present Recurrence H

O e-C N/A N/A

.!/A N/A N/A N/A N/A N/A N/A N/A

(

1 I

l L

l 1

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.

Entr> Sheets for Licensee l

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 Exhibit I - Same Source G Operational Error (Explain)

. 08/77)

Il Other (Explain)

.+

UNIT SHUTDO' NS AND POWER REDUCTIONS

~~

INST RUCTIONS This report should dekube all p ant shutdowns durmg h m at ordan e wit h nie t ar.e appea mg on Ihr repon h.m report period in addition, it should be the source of explan-11 category 4 mua be use i. supply boet <omments ation of sigmficant dips m averhe I wer levels Lach sigm-ficent reductmn to power level (greater than 203 reduction Li(ENSEE EVENT REPORI Referen<e the appihable a

tri aver gt daily power level tm the precedmg 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) rePor table ou unente pen ainmg te the outage or po w e i shotud be noted, even tN.s the Lmt may not have beert red uc non Enter the hrsi tour parts (esent s ear. sequennal shut down completely I Foi such reductions m power level, re po r t numb i occurrente tode and report ty pel of the tiu the emnon should he hsted as /eto. the method of reduction pa rt designanon as des <nbeit m item 17 of inst rut nons n should he hsted as 4 (Other). and the ( ause and Corrective Preparanon of Data i nto Sheets f or luensee i sent Repon i

Action to Bevent Recur. nce column should explam The (I LR I f ile IN t;RI f.-0161 )

T hn mrormanon may noi N Cause and Corrective Actwo to Prevent Recurrence column inunediatch cudent toi all sm.h shutdowns of wune saae should ne usc' to provide any needed explanation to f ully tunher invesnanon inn he requned to astenam w hether o desenht the urtumstances nt the outage or power reduction

""' d "F "dMC

" '" ente w as muh ed i 11 the outage or power reduc t o m wil! mit resuh in a reponable ouurrente NUM14ER Dus wNmn stmld indhate the sequennal num.

the posit ne indhat mn this M a sor relanor, should be ber av.igned to each shutdown or sigmficant reduction in powe, noted as not applaable IN Ai for tha: calendar year When a shutdown or sigmthara power Si. STEM ( ODE redut t.on begins m oru report penod and ends in another.

The ss uem m whnh the outage or power an entry should he made for both report permds to be sure red'iction ongmated should he noted by the two digtt code of all shutdowns e sigmficant power reductions are reported Insuus nom for Preparation of Data i ntry Sheen uM G Until a unit has achieved its f 9st power generation, no num-

'"' k""S# I ' #"' RCP" il l R ) F I" ( Nl RI L U l bl I ber should be assigned to each entr>

Sy stems that d not fit any custing wde shoulJ be designa-ted XX f he aide // should he used f or those esents w here DATE. This column should mdicate tb Jate of the start a system n, not appucable N cach shutdown or wi6 cam p.mer reduction Report as year. month, and day Augov l( 1m would be reported

( OMPONENl ( ODL Selea the most appropnaie w:,ponem as 770814. When a shu jown or.gmtkant power reduction f rom I xhibit I instr Ations for Preparation of Dat a l ot n begms m one report penod and ends m another, an entry should Sheets f or l hensee i sent Repon iLi R) Fde BURI Goloi i be made for both report penods to he sure all shutdowns usmg the f ollowing < nneria or sigmficant power redu;tions are reported TYPE LLe "F' or "S" to mdicate either "Ferced" m " Sche-duled/ respectivel). f or each shutdown or significant power 14 11 not a wmponen, tailure. use the related wmponent red uc tion. Forced shutdowns inclub those required to be

!.[h e c. w rong uhe operated through error hst uhe as initiated by no later than the weekend following discovery wmponen t of an oll-normal conditmn it is recognued that some tudg-

. g. %,.'

o -

ment is required in categorumg shutdowns m this way in C 11 a cham of f ailures occurs. the inst wmponent to mal.

M'.,

general, a forced shutdown is one that would not have been f uncnon should be hsted The sequente of esents melud.

M[ M completed m the absence of the condition for w hith corrective ing the other components which f ail. should he dennbed action was taken unJer the Cause and ( orrettne Achon to Present Retur ren e wlumn

M DURATION Self-e xplanat ory When a shutdown extends beyond the end of a report penod. count only the time to the

( omponents that do not ht ans custmg wde should be de-

-1 end of the report penod and phk up the ensumg down time signated XXXXXX The wde ////Z/ should be used toi he events where a componen t designation is not applhable m the following repon renods. Report duranon of outages rounded to the nearest tenth of an hour to f acihtate summatmn

1. .) s The sum of the total outage hours plus the hours the genera-CM & CORRLCTIVE ACTION TO PRE \\ LNT RLC UR M

RENCE l se lhe column in a narratne tashmn lo amphis b

tor was on line should equal the gross hours in the repommg h

P"""#

explam the circumstantes of the shutdown or power redut non 9+

The column shauld mdude the spetith ause foi caJ sinn REASON. Categoive bs letter designation in ascordance down or sigmticam power redusnan and the nun.ediate au contemplate 1 lone terni s orrectne a< tion iaken it appropii with the table appearmg on the report form. It category H m This column should also be used for a Jeswruon of ihi must be used.,uppl> briel comments maior safety-related wrrectne mamtenance penormed dunng METHOD OF SilUTTING DOWN THE REACTOR OR

1. "' E# "' P" # '

" # " '"'i"d *8 "" 'd'"" """ "'

REDUCING POWER Categonee by number designation

1. M

""d"'"P""# " ""d# *"##

radmatovits or smgle raAauon exposure speuthalls assoti INote that this difices nom the Edison I lectnt Institute Jted with the oulJge w hhh Ju ount3 tof more t h.m 10 pehem (Ell) defimtions of "F orted Partial Outage" and " Sche.

ot the allowable annul ulues daled Paittal Outage For these terms. FLI uses a thange of For long textual reports coatmue narratne on separate paper 30 MW as the break pomt I or larger power reactors. 30 MW and referente the sh u +w n oi pow ei vedus 1 o o

e. n s b t t H ' smJII J t hJnSe 14 6 wJrlJMt explanation HJrralne

A anuarY 1984 1

REFUELING INF0dMATION 1.

Name of facility.

Arkansas Nuclear One - Unit 1 1

2.

Scheduled date for next refueling ahutdown.

November 1,1984 3.

Scheduled date for restart following refueling. January 10, 1985 4.

Will refueling or resumption of operation thereafter require a technical specification change or other licensa amendment?

If answer is yes, what, in general, will these be?

If answer is no, has the reload fuel design and core configuration bnen 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 Technical Specification change.

5.

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

SeDtember 1, 1984 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, 2

new operating procedures.

Yes, the reload analysis will be done using newly developed thermal 7

hydraulic codes. Babcock & Wilcox will be submitting Topical Reports on the new codes for NRC review prior to September 1,1984.

?.

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

a),

177 b) 316 8.

The present licensed spent fuel pool storage capacity and the size e

of any increase in licensed storege capacity that has been requested or is planned, in number of fuel assemblic2.

present 968 licensed but increase size by under construction 9.

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

DATE: ~1998 -

- - ~ - -

m.

, ~ ~

o J

.., s.W

-ANNUAL REPORT OF SAFETY VALVE AND RELIEF _ VALVE FAILURES AND CHALLENGES gr-1 This:' annual ~ report -is s'ubmitted-in the January report in response to

' requirements implemented as a result of NUREG-0737, Item II.K.3.3.

8' For ANO-1,.no challenges.to the-primary system. code safeties nor Electronic q

, Relief Valve.(ERV) have occurred in the year 1983 due to. system conditions.

For ANO-2, no challenges.to the primary system code safeties have occurred g3 in the; year 1983 due to system conditions ANO-2 does not have an ERV.

c, 3-J.,

s P

w

. [

. e g.

l.

1. [

w m

t t

P N

b q

.Y q

• t

-k

?

~

s.

p

.z:

't k..,

4 1-

+

e

l m

1 ARKANSAS POWER & LIGHT COMPANY POST OFRCE BOX 551 UTTLE ROCK. ARKANSAS 72' 03 (501) 371-4000 February 15, 1984 1CAN028403 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information Office of Resource Management U. S. Nuclear Regulatory Commission Washington, D. C.

20555

SUBJECT:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report (File:

0520.1)

Gentlemen:

Attached is the NRC Monthly Operating Report for January 1984 for Arkansas Nuclear One - Unit 1.

Very truly yours,

. M.'~d John R. Marshall Manager, Licensing JRM:SAB:s1 Attachment cc:

Mr. John T. Collins Regional Administrator U. S. Nuclear Regulatory Commission rlegion IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Mr. Richard C. DeYoung Office of Inspection and Enforcement A

U. S. Nuclear Regulatory Commission

't Washington, DC 20555 I] I i

MEMBER MIDOLE SOUTH UTIUTIES SYSTEM