1CAN028505, Monthly Operating Rept for Jan 1985

Monthly Operating Rept for Jan 1985

ML20111D108
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/31/1985
From:	Enos J, Morton K ARKANSAS POWER & LIGHT CO.
To:	Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
1CAN028505, 1CAN28505, NUDOCS 8503180075
Download: ML20111D108 (7)

Text

),

e OPERATING DATA REPORT DOCKET N0:

50-313 DATE:

January 1985 COMPLETED BY:K. L. Morton TELEPHOME:

501-964-3115 OPERATING STATUS 1.

Unit Name:

Arkansas Nuclear One - Unit 1 2.

Reporting Period:

January

'.-31, 1985 3.

Licensed Thermal Power (MWt):

2568 4.

Nameplate Rating (Gross MWe):

902.74 5.

Design Electrical Rating (Net MWe):

850 6.

Maximum Dependable 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):

None 10.

Reasons For Restrictions.

If Any:

None MONTH YR-TO-DATE CUMULATVE 11.

Hours in Reporting Period....

744.0 744.0 88,723.0 12.

Number of Hours Reactor was Critical.....................

163.0 163.0 58,820.9 13.

Reactor Reserve Shutdown Hours........................

0.0 0.0 5,044.0 14.

Hours Generator On-Line......

88.5 88.5 57,492,0 15.

Unit Reserve Shutdown Hours..

0.0 0.0 817.5

16. Gross Thermal Energy Generated (MWH)........................

69,077.0 69,077.0 136,421,893.0 17.

Gross Electrical Energy Generated (MWH)..............

18,999.0 18,999.0 44,981,270.0 18.

Net Electrical Energy Generated (MWH)..............

4,293.0 4,293.0 42,886,816.0 19.

Unit Service Factor..........

11.9 11.9 64.8 20.

Unit Availability Factor.....

11.9 11.9 65.7 21.

Unit Capacity Factor (Using MDC. Net)..............

0.7 0.7 57.8 22.

Unit Capacity irtor (Using DER Net).............

0.7 0.7 56.8 23.

Unit Forced Outage Rate.....

39.5 39.5 14.6 24.

Shutdowns Scheduled Over Ne.xt 6 Months (Type, Date, and Duration of Each):

25.

I-: Shut Down At End of Report Period.

Estimated Date of Startup:

February 23, 1985 26.

Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION i[l 8503180075 850131 PDR ADOCK 05000313 R

PDR

,=

AVERAGE DAILY UNIT POWER LEVEL DOCVET NO:

50-313 UNIT:

One DATE:

Januarv 1985 COMPLETED BY:... L. Morton TELEPHONE:

501-964-3115 MONTH January 1985 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.............

- 6.2 2.............

-10.7 3.............

- 9.1 4.............

-20.0 5.............

-24.5 6.............

-29.2 7.............

-32.4 i

8.............

-33.0 9.............

-26.6 l

10............

- 6.4 l

11............

- 5.3 i

12............

- 5.2 l

13............

- 5.0 14............

- 7.9 15............

- 8.7 16............

-25.1 17............

-32.8 18............

-19.8 19............

- 8.3 20............

- 8.1 21............

- 7.8 22............

-25.3 23............

-32.9 24............

-33.0 25............

-25.1 26............

172.7 27...........

192.3 28...........

189.0 29............

95.8 30............

-14.5 31-............

- 8.0 AVGS:

5.8 INSTRUCTION I

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.

o NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

JANUARY 1984 UNIT ONE The unit started the month in continuation of the IR6 refueling outage.

At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on January 4th, the unit started heating up the Reactor Coolant systems (RCS) and reached hot shutdown on January 6th.

At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on January 9th, the unit began a plant cooldown to replace the "A" and "C" RCP seals.

Following the repairs to the seals, the unit began RCS heatup at 0211 hours0.00244 days <br />0.0586 hours <br />3.488757e-4 weeks <br />8.02855e-5 months <br /> on January 16th and attained hot shutdown on the same day.

At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on January 17th, the reactor was brought critical and Zero Power Physics Testing was begun.

At 0757 hours0.00876 days <br />0.21 hours <br />0.00125 weeks <br />2.880385e-4 months <br /> on January 18th, the unit was again cooled down to replace the "C" RCP seal.

Following the repair of the seal, the unit again began heating up at 0402 hours0.00465 days <br />0.112 hours <br />6.646825e-4 weeks <br />1.52961e-4 months <br /> on January 22nd and reached hot shutdown at 1635 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.221175e-4 months <br /> the same day.

The reactor was brought critical at 0717 hours0.0083 days <br />0.199 hours <br />0.00119 weeks <br />2.728185e-4 months <br /> on January 23rd, and Low Power Physics Testing was resumed.

Upon completion of the testing, the reactor ~was increased in power and the turbine generator was tied on line at 2147 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.169335e-4 months <br /> on January 25th.

This signalled the end of refueling outage 1R6.

The unit was taken to 30% power and remained there due to feedwater chemistry being out of spec because of an unidentified source of air in leakage.

At 1417 hours0.0164 days <br />0.394 hours <br />0.00234 weeks <br />5.391685e-4 months <br /> on January 29th, the unit tripped on high RCS pressure due to feedwater fluctuations in the secondary system.

The unit remained at hot shutdown until 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> on January 30th when a cooldown was begun for replacement of the "C" RCP seal and a burned out control rod drive stator coil on Group 4, Rod 8.

The unit finished the month in cold shutdown mode.

1

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR JANUARY 1985 DOCKET N0 50-313 UNIT NAME ANO - Unit 1 DATE February 5, 1985 COMPLETED BY K. L. Morton TELEPHONE (501) 964-3115 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to l

Ne.

Date Tyge (Hours)

Reason 2 Down Reactor 3 Report #

Code 4 Code 5 Prevent Recurrence 85-05 841012 S

597.8 C

4 N/A N/A N/A 1R6 refueling outage.

85-01 850129 F

57.7 G

3 85-002 JB LI The Unit tripped on high RCS pressure due to steam generator level problems.

f

~.

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 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 s

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

H-Other (Explain) 9 O

9 9

DATE:

January, 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. Itay 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 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 ANNUAL REPORT OF SAFETY VALVE AND RELIEF VALVE FAILURES AND CHALLENGES The annual report of Safety Valve and Relief Valve-Failures and challenges for Arkansas Nuclear One is being submitted as an attachment to the' January.

Monthly Operating Report in response to requirements implemented as a result of NUREG-0737, Item II.K.3.3 and to fulfill Technical Specification reporting requirements (TS 6.12.2.4 for Unit 1 and TS 6.9.1.5.c for Unit 2).

For ANO-1, no challenges to the primary system code safeties nor electromatic relief. valve (ERV) have occurred in the year 1984 due to system-conditions.

However, the ERV was manually opened during a transient which occurred ~on 04/21/84, in an effort to avert a reactor trip on high Reactor Coolant System (RCS) pressure. The ERV reopened correctly and reclosed successfully upon demand.

For ANO-2, no challenges to the primary system code safeties have occurred in the year 1984 due to system conditions.

AN0-2 does not have an ERV.

e

9 ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501)371-4000 February 15, 1985 1CAN028505 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:

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

To be consistent with the guidelines provided in NUREG-0020, effective January 1985, Arkansas Nuclear One will be recording negative generation when computing net electrical energy generation (MWH) totals.

In the past, zero was recorded as net generation when a unit was shut down.

Very truly yours, f

Id/1 J

D

a. Ted Enos M nager, Licensing JTE:SAB:ds Attachment cc:

Mr. Robert D. Martin Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Mr. Richard C. DeYoung i

Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 MEMBEA MOOLE SOUTH UTiUTIES SYSTEM