0CAN089704, Monthly Operating Repts for Jul 1997 for Arkansas Nuclear One

Monthly Operating Repts for Jul 1997 for Arkansas Nuclear One

ML20210L966
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/31/1997
From:	Mims D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0CAN089704, CAN89704, NUDOCS 9708210386
Download: ML20210L966 (14)

Text

_ _ - _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - - _ - - _

O Ent:rgy oper:tions,Inc.

/

h[

1448 SA 333 RusseMio. AR 72801 Tel501858 5000 August 13,1997 OCAN089704 U. S. Nuclear Regulatory Commission Document Control Desk -

Mail Station OPI-17 Washington, DC 20555

Subject:

Arkansas Nuclear One - Units 1 and 2

- Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6

~

Month'y Operating Report Gentlemen:

Arkansas Nuclear One (ANO), Units 1 and 2 Technical Specifications 6.12.2.3 and 6.9.1.6, respectively, require the submittal of a Monthly Operating Report. The purpose of this letter is to complete the reporting requirement for July 1997, Very truly yours, r/

Dwi ht C, fims Dir cto(, uclear Safety

(

DCM/c attachment y&

(kh001 9708210386 970731 PDR ADOCK 05000313 R

peg l

~ U. S. NRC August 13,1997

- OCAN089704 Page 2 -

'cc:

Mr. Ellis W. Akrschoff Regional Adadaistrator U. S. Nuclear Regulatory Commission Region IV =

611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 l

U. 5. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike l

Rockville, MD 20852 1

3

Arkansas Nuclear One Unit 1 l

Monthly Operating Report 1

i

OPERATING DATA REPORT DOCKET NO:

50 313 DATE:

August 13,1997 COMPLETED BY: M. S. Whitt TELEPHONE:

(501) 858-5560 OPERATING STATUS 1.

Unit Name:

Arkansas Nuclear One - Unit 1 2.

Reporting Period:

July 1-31 3.

Licensed Thermal Power (MWt):

2,568 4.

Nameplate Rating (Gross MWe):

903 5.

Design Electrical Rating (Net MWe): 850 6.

Maximum Dependabic Capacity (Gross MWe): 883 7.

Maximum Dependable Capacity (Net MWe): 836 8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9.

Power Level To Which Restricted. If Any (Net MWe):

10.

Reasons For Restrictions, if Any:

l l

MONTH YR-TO-DATE CUMULATIVE 11.

Hours in Reponing Period 744.0 5,087.0 198,258.0 f

12.

Number of Hours Reactor Was Critical 744.0 5,087.0 149,582.6 13.

Reactor Reserve Shutdown Hours 0.0 0.0 5,044.0 14.

Hours Generator On-Line 707.7 5,050.7 147,146.0 15.

Unit Reserve Shutdown Hours 0.0 0.0 817.5 16.

Gross Thermal Energy Generated (MMTI) 1,757,313 12,485,973 344,013.763 17.

Gross Electrical Energy Generated (MWH) 592,118 4,322,900 115,472,276 18.

Net Electrical Energy Generated (MWH) 564,539 4,138,471

_109,9'!3,703 19.

Unit Service Factor 95.1 99.3 74.2 20.

Unit Availability Factor 95.1 99.3 74.6 2L Unit Capacity I' actor (Using MDC Net) 90.8 97.3, 66.3 22.

Unit Capacity Factor (Using DER Net) 89.3 95.7 65.2 23.

Unit Forced Outage Rate 4.9 0.7 9.6 24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

i 25.

If Shut Down At End of Report Period. Estimated Date of Stanup:

26.

Unit: in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 08/06n4 INITIAL ELECfRICITY 08/17n4 COMMERCIAL OPERATION 12/19/74 1

w

.--__a

?

. AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO: 313 UNIT:

One DATE:

- August 13,1997

' COMPLETED BY: M. S. Whitt -

.)

TELEPHONE:

(50l) 858-5560

- MONTH July 1997 -

r.

DAY'-

~ AVERAGE DAILY POWER LEVEL 1

(MWe-Net) 1...................

430 2.......................

827 l

l3...

835 i

4.............

836 5..........................

839 6......................

839

.7i

-840 8.

840 9.....................

840 10........

841 11.....................

840 12................

841 13..................,,.

839 14.

838 15.....................

836 16....................

837 17.....................

836 18..

835 19...

783

.20..,.....................

287 21.......

-36

'22.................

403 23 =

785 L 24.

832 25......,..

830

-- 26..

-830

27................

828

-28...........,......

826 29 827-30.......

828 3 1.........

830 AVGS:

759 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each

! day in reporting month. Complete to the sicarest whole megawatt.

~

UNIT SHUTDOWNS AND POWER REDUCTIONS

~

REPORT FOR JULY 1997 DOCKET NO.

50-313 UNIT NAME ANO Unit i DATE August 13,1997 COMPLETED BY M. S. Whitt TELEPHONE 501-858-5560 METHOD OF LICENSEE

^ DURATION SIIUTTING DOWN EVENT

. SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO ZLQ PATJ TYPE' (IIOURS)

REASON:

REACTOI(s REPORT #

CODE' CODES PREVENT RECURRENCE 9748 970701 -

F 27.5 A

5 N/A SJ CLU Power held at 55% due to a short la power supply to clutch le motor operater -

for main feedwater block valves.

97-05 970724 F

14.7 A

5 N/A SD HX

- Power reduced te 40% to silow repair work an E-5A feedwater heater tube leak.

9746 970720 F

36.3 A

5 N/A SD HX

. Unit talen offline to complete repair work on E-5A feedwater bester.

1 2

3 4

F: Forced Reason:

Method:

Exhibit G -Instructices S: Scheduled A - Equipment Failure (Esplain) 1 - Manual for Preparation of Pata B-Maintenance of Test 2 - Msnaal Scram.

Entry Sheets for Ucessee C-Refueling 3 - Autos =atic Scrust Event Report (LER) File (NLTEG-0161)

D-Regulatory Restriction 4 - Centhention E - Operator Training & Ucense Examlastion 5-Imd Reduction F-Administration 9 - Other 5

G - Operational Ermr -

Exhibit I-Same Source H - Other (Enplain)

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

JULY 1997 UNIT ONE The month began with the unit operating at 55% power due to problems with the main feedwater block valves. The valves were successfully repaired and the unit was returned to 100% power at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> on the second.

A power reduction to 85% was commenced at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on the eighteenth to allow cleaning of the service water (SW) bays. At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on the nineteenth, power was further reduced tn 40% due to a tube leak in feedwater heater E-5 A. The unit was taken off-line on the twentieth to allow repairs to the heater and placed back on-line at 0603 hours0.00698 days <br />0.168 hours <br />9.970238e-4 weeks <br />2.294415e-4 months <br /> on the twenty-second. SW bay cleaning was completed and the unit was returned to 100% power on the tv.enty-fourth. At 2117 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.055185e-4 months <br /> on the thirty-first, power was reduced to 95% for cycling of the condenser cooling water inlet valves. After cycling of the valves, a power incie.ne was commenced at 2150 hours0.0249 days <br />0.597 hours <br />0.00355 weeks <br />8.18075e-4 months <br />. Full power was attained at 2221 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.450905e-4 months <br /> and the unit operated the remainder of the month at 100%.

There were no challenges to the primary system code safeties nor automatic actuation of the electromatic relief valve during this reporting period.

Reporting Period: July 1997 REFUELING INFORMATION

1. - Name of facility: Arkansas Nuclear One - Unit i 2.

Scheduled date for next refueling shutdown:. March 20.- 1998

3.. Scheduled date for restart following refueling: May 9.1998 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 there be? If answer is no, has the reload fuel design and core con 6guration been reviewed by your Plant Safety Resiew Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref,10CFR l

Section 50.59)?-

L No. No 5.

Scheduled date(s) ibr submitting proposed licensing action and supporting information:

N!.6 6.

- Impodant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significans chap iin fuel design, new

- operating procedures.

None olanned

7. ' The number of fuel assemblics (a) in the core, (b)in the spent fuel storage poo' nd (c) dry cask storage:

a) J12 b)258 c) 48 5

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 918 increase size by 0

9. - The projected date of the last refueling that can be discharged to the spent fuel pool assumis6 the presentlicensed capacity:

Full core off-load capability no lonner available until a sufficient amount of spent fuel can be o!acM in on-site dry storane.

Arkansas Nuclear One Unit 2 Monthly Operating Report 1

OPERATING DATA REPORT DOCKET NO:

50-368 DATE:

August 13,1997 COMPLETED BY: M. S. Whitt TELEPIlONE:

(501)858 5560 OPERATING STATUS 1.

Unit Name:

Arkansas Nuclear One - Unit 2 2.

Reporting Period:

July 1-31 3.

Licensed Thennal Power (MWt):

2,815 4,

Nameplate Rating (Gross MWe):

9,42 57 5.

Design Electrical Rating (Net MWe): 896_

6.

Maximum Dependable Capacity (Gross MWe): 897 7,

Maximum Dependable Capacity (Net MWe): 858 8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9.

Power Level To Which Restricted if Any (Net MWe):

10.

Reasons For Restrictions. If Any:

MONTH YR-TO-DATE CUMULATIVE 11.

Hours in Reportir' Period 744.0 5,087.0 152,087.0 12, Number of Hours Reactor Was Critical 744.0 4,370.6 119,905 0 13.

Reactor Reserve Shutdown Hours 0.0 0.0 0.0 14.

Hours Generator On-Line 744=0 4,341.3 117,669.3 15.

Unit Reserve Shutdown Hours 0.0 0.0 0.0 16.

Gross Thermal Energy Genera'd (MWH) 2,093,041 11,713,567 314,048,984 17.

Gross Electrical Energy Generated (MWII) 675,945 3,904,576 103,655,821 18.

Net Electrical Energy Generated (MWH) 645,084 3,721,017 98,665,581__

19.

Unit Service Factor 100.0 85.3 77.4 20.

Unit Availability Factor 100.0 85.3 77.4 21.

Unit Capacity Factor (Using MDC Net) 101.I 85.3 75.6 22.

Unit Capacity Factor (Using DER Net) 95.I 80.2 71.I 23.

Unit Forced Outage Rate 0.0 0.0 9.8 24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25.

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

26.

Units in Test Status (Prior to Commercial Operatien):

Forecast Achieved INITIAL CRITICALITY 12/05n8 INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80 r

i

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-368 UNIT:

Two DATE:

August 13,1997 COMP!ITED BY: M. S. Whitt TELEPHONE:

(501)858 556C MONTH luly 1997 D AY--

- AVERAGE DAILY POWER LEVEL -

(MWe-Net) 867 2..................

864 I'

3......................,

865 I

4.........

872 5.......

878 6,......,,.........,,.

877 7,......................

873 8....

870 9....................

868 10......

870 1 1....,

867 12.

865 13...................,

865 14.......................

865 15..................,,

867 16.,,,...,..

867 l

17;.......................

866 18..,,,.......

865 19.

866 20.....................

866

21...............

865 22.................

866 2 3............

865 24....................

863 25...............

861 26....

862 27.....-...............

862 28.'...

863-

- 2 9........

868 3 0.............

871-31......

870 AVGS:..

867 l

INSTRUCT!QN On this format, list the average daily unit power level in MWe-Net for each day in reporting month.

. Complete to the nearest whole megawatt.

UNIT SHUTDOWNS AND POWER REDULTIONS

~

. REPORT FORJULY 1997 DOCKET NO.

50-368 UNITNAME ANO Unit 2 DATE-August 13,1997 I

- COMPLETED BY M. S. Whitt TELEPHONE 501-855-5560 ME THOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO E

DATE TYPE 8 GIOURS)

REASON 2 REACTOR 8 REPORT #

CODE' CODES PREVENT RECURRENCE none 1

2.

3 4

F: Forced Reason:

Methed:

Exhibit G-Instructions 5: Scheduled A - Equipsient Failure (Esplein) 1 - Meneel for Prepareties of Data B - Meistemence of Test 2 - Manuel ScremL Entry Sheets for Ucensee C-Refueling 3 - Autenistic Screen.

Event Report (IER) File (NUREG-4161)

D-Regulatory Restriction 4 - Continuaties E - Operater Troising & Ucesse Exeuniention 5-I4ad Reducties F-Admeinistration 9 - Other 5

G - Operational Error Exhibit I-Semie Searce H-Other (Explels)

.NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

JULY 1997 1

UNIT TWO 1

The month cegan with the unit operating at 100% power.

At 2131 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.108455e-4 months <br /> on the thirtieth, power was reduced to 98% for steam generator moisture

. carryover testing. Following completion of the tests, the unit was returned to 100% power on the thiny-first. The unit operated at 100% power for the remainder of the month.

i There were no challenges to the primary system code safeties nor automatic actuation of the low temperature overpre sure protection valves during the reporting period.

i I

a

Reporting Period: July 1997 REFUELING INFORMATION i.

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

Scheduled date for next refueling shutdown: lanuary 8.1999 3.

Scheduled date for restart following refueling: February 22.1999 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 there 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.10CFR Section 50.59)?

No.No 5.

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

1 N/A 6.

Important li:tnsing considerations associated with refueling, e.g., new or different fuel design or suppher, unreviewed design or performance analysis methods, significant changes in fuel design, new opert. ting procedures.

Nonc olanned 7.

The number of fuel assemblies (a) in the core (b) in the spent fuel storage pool and (c) dry cask storage:

a) 121 b)219 c) 48 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 988 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:

Fuii core off-load capability no longer available until a sufficient amount of spent fuel can be placed in on-site dry storage.

I

.