1CAN078509, Monthly Operating Rept for June 1985

Monthly Operating Rept for June 1985

ML20135B267
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/30/1985
From:	Enos J, Morton K ARKANSAS POWER & LIGHT CO.
To:	Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
1CAN078509, 1CAN78509, NUDOCS 8509100496
Download: ML20135B267 (7)

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OPERATING DATA REPORT f

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DOCKET NO.

50-313

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June, 1985 l:

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COMPLETED BY:K.

L. Morton TELEPHONE:

501-964-3115

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OPERATING STATUS g.g.i f.j. 4% J..

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Unit Name:

Arkansas Nuclear One - Unit 1 c

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Reporting Period:

June 1 - 30, 1985

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Licensed Thermal Power (MWt):

2568 4.

Nameplate Rating (Gross MWe):

902.74

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Design Electrical Rating (Net MWe):

850 L

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Maximum Dependable Capacity (Gross MWe):

883 4

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Maximum Dependable Capacity (Net MWe):

836

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If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since

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Last Report, Give Reasons:

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Power Level To Which Restricted.

If Any (Net MWe):

None T.':hi.[-

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Reasons For Restrictions.

If Any:

None

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,}j.y MONTH YR-T0-DATE CUMULATVE 11.

Hours in Reporting Period 720.0 4,343.0 92,322.0 J.

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Number of Hours Reactor was

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Critical 716.3 3,154.3 61,812.2 E O'.,1 al j<.

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Reactor Reserve Shutdown Hours 0.0 0.0 5,044.0 14.

Hours Generator On-Line 700.4 3,U42.0 60,445.5 15.

Unit Reserve Shutdown Hours 0.0 0.0 817.5 16.

Gross Thermal Energy Generated (MWH) 1,675,609.0 7,375,980.0 143,/28,796.0 17.

Gross Electrical Energy Generated (MWH) 562,025.0 2,482,059.0 47,444,330.0 18.

Net Electrical Energy Generated (MWH) 535,770.0 2,350,072.0 45,212,595.0 19.

Unit Service Factor 97.3 70.0 65.5 20.

Unit Availability Factor 97.3 70.0 66.4 21.

Unit Capacity Factor (Using MDC Net) 89.0 64.7 58.6 22.

Unit Capacity Factor (Using DER Net) 87.5 63.7 57.6 23.

Unit Forced Outage Rate

2. 7 18.8 14.8 24.

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

None 25.

If Shut Down At End of Report Period.

Estimated Date of Startup:

26.

Units in Test Status (Prior to Commercial Operation):

Forecast Achieved 2

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8509100496 850630

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f AVERAGE DAILY UNIT POWER LEVEL DOCKET N0:

50-313 UNIT:

One DATE:

June, 1985 COMPLETED BY: K. L. Morton TELEPHONE:

501-964-3115 MONTH June DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.............

111 2.............

342 3............

374 4.............

679 5.............

813 6.............

817 7.............

819 8.............

818 9.............

816 10............

816 11............

818 12............

822 13............

829 14............

829 15............

829 16............

829 17............

829 18............

830 19............

829 20............

830 21............

829 22............

829 23............

828 24............

827 25............

825 26............

826 27............

655 28............

375 29............

823 30............

828 31............

AVGS:

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

Compute to the nearest whole megawatt.

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OPERATING

SUMMARY

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,N j[>:.,'f-p[,r%j' The unit began the month with the reactor critical and the generator off line while repairs were being made to the E2-A feedwater heater expansion joint.

The repairs were finished and the unit escalated in power with the

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main generator being tied on line at 1233 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.691565e-4 months <br /> on the first of June.

The

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unit attained 49% power operation and was held there for maintenance on the

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"B" main feedwater pump.

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At 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> on the 2nd, with the maintenance completed, the unit was bi-escalated in power to 75% where a 5-hour hold was made for xenon burn.

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1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> the unit attained 90% full power operation and remained at that

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't'f,'~-)4). ' 11 power level until 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />, when the unit experienced a runback due to

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problems with the "B" MFW pump which resulted in MFW pump "B" tripping.

The

c. d k plant stabilized at 23% power and was then escalated to 45%.

The unit 3C.,.. '.) k.7 remained there until 1959 hours0.0227 days <br />0.544 hours <br />0.00324 weeks <br />7.453995e-4 months <br /> when the "A" MFW pump tripped causing the reactor and turbine to trip off 1ine.

The reactor reached criticality at

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2342 hours0.0271 days <br />0.651 hours <br />0.00387 weeks <br />8.91131e-4 months <br /> on the same day and the turbine was tied on line at 0302 hours0.0035 days <br />0.0839 hours <br />4.993386e-4 weeks <br />1.14911e-4 months <br /> on

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The unit attained 90% full power at 1342 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.10631e-4 months <br /> and remained there until 1815

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,p hours when a power reduction was begun to 45% to work on the main feedwater 39 1

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pumps.

The maintenance was completed and a power escalation begun at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on the 4th.

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$3 The unit reached 100% operation at 1518 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.77599e-4 months <br /> on the 4th and remained there Q '.

until 1650 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.27825e-4 months <br /> on the 27th.

At this time the unit experienced a runback J. c.P.,1;.T ' ;p due to a trip of the "B" MFW pump. The plant was stabilized and held at 39%

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h',,.7 Y-[ N.M power until 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> on the 28th, at which point the unit was escalated in

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power, attaining 100% operation at 0225 hours0.0026 days <br />0.0625 hours <br />3.720238e-4 weeks <br />8.56125e-5 months <br /> on the 29th.

The unit remained there through the end of the month.

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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR June, 1985 DOCKET NO 50-313 UNIT NAME ANO - Unit 1 DATE July 5, 1985 COMPLETED BY K. L. Morton TELEPHONE 501-964-3115 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to No.

Date Type *

(Hours)

Reason 2 Down Reactor 3 Report #

Codei Code 5 Prevent Recurrence 85-03 19850531 F 12.55 A

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' Reactor trip on high RCS~

85-004 pressure.

Initiating event was an inadvertent j

closure of an intercept l-valve causing a trip of l

the "A" main feedwater l

pump and a failure of the L

E2-A low pressure l

feedwater heater expansion joints.

The heater was repaired and the unit-placed back on line.

85-04 19850602 F 0

A 5

N/A SJ P

Plant runback from 90% to 23% due to "B" main feedwater pump trip.

Escalated to 45% and repaired pump.

85-05 19850602 F 7.05 A

3 ILER-313-SJ P

Unit trip from 45% on loss i

85-005 of "A" main feedwater pump trip.

Brought unit back on line.

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Method:cf Liczns93 Cruss & Corr:ctiva;.

Duration Shutting Event System Component-Action to

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No.

Date TEEe

'(Hours)

Reason 2

.Down Reactor 3 Report.#-

Code 4 Code 5~

Prev'ent Recurrence.

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.85-06 19850603 F 0

A 5

N/A.

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. Power reduction for main ~

l feedwater pump. maintenance; and repair.'

Escalated;to 100% upon completion.

85-07 19850627 F 0

A 5

N/A SJ P-Plant runback from 100% toL 39% full-power'due to^"B" ~

main feedwater pump trip.,

Repaired problem and escalated to 100%.

1 2

3.

4 F:

Forced Reason:

Method:

Exhibit G - Instructions 5:

Scheduled A-Equipment Failure (Explain) 1-Manual for. Preparation of Data B-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling.

3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction.

4-Continuation-1022)

E-Operator' Training &

5-Load Reduction

-License Examination 9-Other 5

F-Administrative Exhibit I - Same Source G-Operational Error-(Explain)

H-Other (Explain) 1 L----------

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1 DATE:

June, 1985 REFUELING INFORMATION 1.

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

Scheduled date for next refueling shutdown.

August, 1986 3.

Scheduled date for restart following refueling.

October, 1986 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. 10 CFR Section 50.59)?

Yes.

Reload Report and associated proposed Technical Specification change request.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information. May 1, 1986 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.

None 7.

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

a) 177 b) 456 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 1

9.

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

DATE:

1998

1 l

ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 l

July 15, 1985 l

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1CAN078509 l

l Mr. Harold S. Bassett, Director l

Division of Data Automation l

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. OPR-51 Monthly Operating Report Gentlemen:

The Arkansas Nuclear One - Unit 1 Monthly Operating Report for June 1985 is attached.

Very t ly yours,

/

J. Ted Enos Manager, Licensing JTE:MCS:ac Attachment cc:

Mr. Robert D. Martin Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Ar1ington, TX 76011 Mr. Richard t'.

DeYoung Of fice of Inspection and Enforcemerit U. S. Nuclear Regul'. tory Commission Washington, DC 20555

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MEMBEA h*00LE E4UTH UTsuT Es system