ML19207B096

Monthly Operating Rept for Jul 1979

ML19207B096
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/14/1979
From:	Shively C ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19207B095	List: ML19207B094 ML19207B096
References
NUDOCS 7908230371
Download: ML19207B096 (5)

Text

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. AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-313 UNIT _AN0-1 DATE R 74-CON 1PLET ED By C.N. Shively T ELEPliONE (5011968-2519 MONni July DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) 014e Neti i 743 7 0 2 806 is 0 3 810 19 _.Q..___ .

4 811 20 0 5 810 0 21 6 812 n 22 7 814 23 0 a 772 24 0 9 50 25 0 10 40 _

26 0 11 n 27 0 12 0 2s 0 13 0 _

29 n 14 n 30 n is o si 0 16 n INSTRUCTIONS On this tormat, hst the aserage dail.s umt pim er lesel in MWe-Net for each day in the reporting inonth. Compute to the nearest whole nepwatt.

, -k n u (9/77) n Dj 19082309q

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OPER ATLNG DATA REPORT DOCKET NO 50-313 DATE 8-14-79 C051PLETED BY C.N Shtvelv TELEPHONE 50l/966-2M9 OPERATING STATUS

1. Unit Name: Arkansas Nuc19ar One-lJnit 1 Notes

2. Reporting Period: July 1-31, 1979

3. Licensed Thermal Power (51% t): 2568

4. Nameplate Rating (Gross SIWE): 902.74

5. Design Electrical Rating (Net 51We): 850

6. 51aximum Dependable Capacity (Gross Siwe): 883

7. 51aximum Dependable Capacity (Net 51We): 836

8. If Change < Occur in Capaci y Ratings (Items Number 3 Through 7)Since Last Report. Gise Reasons:

None .

9. Power Lesel To Which Restricted. If Any (Net .\1We): Nono

10. Reasons For Restrictions. If Any: NA This Slonth Yr..to.Date Cumulatise

11. Hours In Reporting Period 774.0 _. 5.087.0 40.458.0

12. Number Of Hours Reactor h is Critical 223.0 1,779.2 27.489.3 13 Reactor Resene Shutdown Ho urs 521.0 1,679.6 3,669.5

14. Hours Generator On.Line 208.7 1,645.4 26,859.1

15. Unit Resene Shutdown Hours U.0 D9I.D 796.7

16. Gross Thermal Energy Generated 151WH) 491.118.0 3.807_.883.0 64.704.592.0 l' Gross Electrical Energy Generated q %!WH) 162.93L.0___...l.279.148.0 21 .519.829.0

16. Net Electrical Energy Generated (51WH) 155.233.0 1,218.796.0 20,529,342.0

19. Unit Senice Factor 28.1 32.3 66.4.

20. Unit Availability Factor 28.1 44.0 68.4

21. Unit Capacity Factor (Using .\tDC Net) 25.0 28./ 60.7

22. Unit Capacity Factor (Using DER Net) 24.5 28.2 59.7

23. Unit Forced Outage Rate 71.9 55.7 16.0

24. Shutdowns Scheduled Oser Next 6 51onths (Type. Date,and Duration of Each):

25. If Shut Down At End Of Report Period. Estimated Date of Startup: August 13, 1979

26. Units in Test Status (Prior io Commer ial Operation). Forecast Achieved INITIA L CRITICALITY t INITIAL ELECTRICITY CO51\f ERCl A L OPER ATION 1

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(9/77)

. REFUELING INFORMATION

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

2. Scheduled date for next refueling shutdown. 10/01/1980

3. Scheduled date for restart following refueling. 12/01/1980

4. Will refueling or resumption of operation thereaf ter 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 fection 50.59)?

Yes, Reload Report and associated proposed Technical Specification Changes.

5. Scheduled date(s) for submitting proposed licensing action and supporting information. 08/01/1980

~

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 rpinad 72 frpsh fuel assemblies and ooerate for aooroximately 16 months.

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 176

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 590 increase size by 0

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

DATE: March. 1988 kt d ,

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UNIT SilUTDOWNS AND POWER REDUC 110NS DOCKET NO. 313 UNIT N AME ANO-Unit 1 DATE __CLl,4479 REPORT MONTil July COMPLETED BY C.N. Shivelv 11?LEPil0NE (5011968-2519

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3 :n 5 5

=n rs j Date 3. k5 5 ?jd I 'FC"5C I'C "'

5't $% Cause & Corrective No.

p 53 0 5,7 93 Action to

• 5 3 *j Report n to u Prevent Recurrence CO $E }O -

c5 79-02 Turbin Turbine governor valve position 790708 F 14.1 A 3 NA IfA indication arm failed.

Main Turbine bearing high vibration.

79-03 790709 F 521.3 A 1 HA HA Turbin

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, i 2 3 4 F: F..rted Reason : Method: Exhibit G - Instructions

] S: Scheduled A-Equipment Failure (I!xplain) 1-Manual for Preparation of, Data lt-Maintenance or Test .' Manual Scram.

linity Shters for Licensee C-Refueling 3- Automatic S( ram. Event Report (1 ER)Iile INURI G D. Regulatory Resinction 4 -Ot her (I!*,pl.un ) 0161)

I -Operator Trainmg & lxense 1 xanonation I Administrative 5 G-Operation . I iros (I xplain) Exhibit I Same Sonice 19/77) 11 Othu (E xplain)

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- JULY, 1979 UNIT 1 The unit increased to 100% reactor power from the 75% test plateau on 7/ 2. Full power core physics testing was completed on 7/4. On 7/8, unit load was being reduced, in order to remove Main Feedwater Pump PlB, when the turbine controls began operating erratically and eventually caused the reactor to trip on high RCS pressure. The uni' was placed back'on line the next day; however, a high turbine beari 3 vibration limited load to approximately 24% reactor power. The unit was sub-sequently taken back off line on 7/10 for further investigation. The unit remained off line for the remainder of the month.

On 7/13, Bechtel, the A-E for ANO, made notification that the main steam snubbers, which were designed for a seismic event, were not ade-quately designed for a turbine trip transient, (Reference LER 50-313/79-

-- 010/03L). Modifications were in progress throughout the remainder of the month.

On 7/15, seismically-supported pipe supports, in response to NRC IE Bulletin #79-14, inspections began. Inspection of pipe hanger and support anchor bolts, in response to NRC IE Bulletin #79-02 also began.

Inspections and modifications were in progress throughout the remainder of the month.

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