ML20050B416

Monthly Operating Rept for Jan 1982

ML20050B416
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/08/1982
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20050B411	List: 2CAN028203, Forwards Monthly Operating Rept for Jan 1982 ML20050B416
References
NUDOCS 8204050306
Download: ML20050B416 (6)

Text

_-

OPERATING DATA REPORT DOCKET NO.

50-DATE 02 08 8 COMPLETED fly L. S. Bramlett T ELEPilONE 501-964-3145 OPER A IING ST A I US N"'"

Arkansas fluclear One - Unit 2

1. Unit Name:

l

2. Reporting Period:._daDuary 1-31. 19R2

3. Licenwd Ibermal Power IMWil:

2815 942.57

4. Nameplate Rating (Grms MWel:

912 S. Design Electrical Mating (Net MWe).

897

6. Maximum Dependable Capacity (Grow MWe):

858 7, Masimum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (items Number 31hrough 7) Since Last Report.Gise Reasom:

flone

9. Power Lesel To Which Restricted if Anv (Net MWe):

None

10. Reasons l'or Restrictions if Any:.N/A 1his Month Yr to-Date Cumulatise l

744.0 744.0 16248.0 l1. Ilours in Reporting P:riod 362.7 362.7 11257.3

12. Number Of flour, Reactor Was Critical 0.0 0.0 1013.7 i

13. Reactor Resene Shutdown llour, 357.4 357.4 10899.2

14. Iloun Generator Oa Line

15. Unit Rewne Shutdown flours 0,0 0.o 75.0 853995.

853995.

26639864.

16. Grms Thermal Energy Generated Olwill 272919.

272919.

8644837.

17. Grow Electrical Energy Generated (MWil, 259186.

89186.

8230184.

18. Net Electrical Energy Generated (M%III 48.0 48.0 67.1

19. Unit Senice Facto, 48.0 48.0 67.5

20. Unit Asailability Factor 40.6 40.6 59.0

21. Unit Capacity Factor (Using MDC Net t 3T2 38.2 55.5

22. Unit Capacity Factor (Using DER Net) 52.0 52.0 21.3

23. Unit Forced Outag-Rate

24. Shutdowm Scheduled Oser Nest 6 Months tType. Date.ar d !M -' ion of Each t:

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

26. Units in lest Statm (Prior to Commercial Operation):

Forecast Achiesed INiil A L CRillCAllIY INiil Al. ELECT RICIIY CO\\l%11 RCI A L OPER A llON i

8204050306 820212 PDR ADOCK 05000368 to/771 R

PDR

AVERAGE DAILY UNIT POWER LEVEL.

DOCKET NO.

50-368 UNIT 2

DATE 02/08/82 L. S. Bramlett COMPLETED BY TELEPHONE 501-964-3145 MONTH January 1982 DAY AVERAGE D ILY P

'ER LEVEL DAY AVER AGE DAILY POWER LEVEL IMWe Net) 1 854 o

,7 2

854 o

', 9 0

3 852 4

853 0

20 5

852 0

21 6

851 0

22 7

4RR 23 156 8

0 431 24 9

0 304 25 to 0

196 26 Ii 0

698 27 12-0 28 821 13 0

873 29 14 0

30 872 is 0

876 3

0 16 INSTRUCTIONS On this format,hst the average daih unit pemer levelin MWe. Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/771

DOCKET NO. 5.0-368 UNII SilCID0%NS AND POWER REDUCTIONS UNIT NAME ANO-II DATE 2/2/82 CCMPLETED BY L. S. Bramlett REPORT MONill Januar' TELEPilONE (501) 964-3145 J

l k$

Licensee j-t.

h*'t l

3?

Cause & Correctne

=

No.

Date Ti E 4

2E3 Esent 77 67 Action to j

jj}

Report :

N0

,$ 0 Present Recurrence

)

82-01 820107 F

370.2 A

1 50-368/82-001 ID Instru Rcs RTD's failing response time testing. See LER 50-368/82-001.

82-02 820124 F

6.5 A

2 N/A CH Valvex Plant trip when both MFW pumps tripped.

i 82-03 820125 F

9.9 A

2 N/A CH Valvex Plant trip when both MFW pumps tripped.

Control valve actuator repaired.

l 4

a 3

3 I

1 1

I i

1 i

1 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintqnance of Test 2-Manual Scram.

Entr> Sheets for Licensee i

C Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG.

D-Regulator) Restriction 4 Continuation 0161)

E-Operator Training & License Examination 5-Load Reduction 5

4 F Administrative 9-Other G-Operational Error (Explain)

Eshibit 1 - Same Source l

Pl/77) li Other (Explain)

^

REFUELING INFORMATION 1.

Name of facility.

Arkansas Nuclear One - Unit 2 2.

Scheduled date for next refueling shutdown. 9/1/82 3.

Scheduled date for restart following refueling. 11/1/82 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.

Description of effects of new core loading.

5.

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

6/1/82 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.

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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) 60 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 485 increase size by 0

9.

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

DATE:

1989 se

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- JANUARY 1982 UNIT 2 The Unit began the month at 100% full power and operated there until January 7,1982. On this date, the unit entered T.S. action statement 3.03 due to notification of the RCS RTD's failing the response time testing. The unit was brought to Mode 5 and remained shutdown until the reactor was taken critical on January 22, 1982.

The unit tripped when both MFW pumps tripped on January 24, 1982.

This occurred again on January 25, 1982. The unit was returned to power operation and reached 100% full power on January 28, 1982.

Normal operation continued through the remainder of the month.

F ANNUAL REPORT OF SAFETY VALVE AND RELIEF VALVE FAILURES AND CHALLENGES This annual report is submitted in the January report in response to requirements implemented as a result of NUP.EG-0737, Item II.K.3.3.

For ANO-1, no challenges to the primary system code safeties nor Electromatic Relief Valve (ERV) have occurred in the year 1981 due to system conditions.

For ANO-2, no challenges to the primary system code safeties have occurred in the year 1981 due to system conditions. AN0-2 does not have an ERV.

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