Text

Monthly Operating Rept for Sept 1983
	ML20081M316
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/30/1983
From:	John Marshall, Morton K; ARKANSAS POWER & LIGHT CO.
To:	Bassett H; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	1CAN108303, NUDOCS 8311170209
	Download: ML20081M316 (7)
	v • d • e

.

OPERATING DATA REPORT DOCKET NO. 50-313 DATE 10/15/83 COMPLETED BY K.L.Morton TELEPflONE 501-964-3115 OPERATING STATUS

1. Unit Name:

Arkansas Nuclear One - Unit 1 N"

2. Reporting Period:

September 1-30, 1983

3. Licensed Thermal Power IMWt p:

2568

4. Nameplate Rating (Gross MWe):

902.74 850

5. Design Electrical Rating (Net MWe):

883

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report. Gise Reasons:

None

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

10. Reasons For Restrictions.If Any:

This Month Yr to-Date Cumulatise 720.0 6,551.0 76,986.0

11. Hours In Reporting Period

12. Number Of flours Reactor Was critical 632.7 2,219.2 50,226.5 0.0 0.0 5,044.0

13. Reactor Resene Shutdown flours 14 liours Generator On-Line 607.7 1,983.7 49,041.2

15. Unit Resene Shutdown flour, 0.0 0.0 817.5 1,403,472.0 4,487,450.0 116,257,264.0

16. Gross Thermal Energy Generated (MWil) 461,995.0 1,468,401.0 38,233,44b.0

17. Gross Electrical Energy Generated (MWil)

18. Net Electrical Energy Generated (Mwill 439,960.0 1,396,477.0 36,434,287.0 84.4 30.3 63.7

19. Unit Senice Factor

20. Unit Asailability Factor 84.4 30.3 64.8 5

21. Unit Calmitv 1 actor (Using MDC Net) 73.1 25.5 56.6 71.9 25.1 55.7

22. Unit Capacity Factor iUsing DER Net) 15.6 34.0 16.5

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Ne.st 6 Months (Type. Date.and Duration of Each 3:

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

26. Units In Test Status iPrior to Commercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITIA L ELECTRICITY COM41ERCIAL OPER ATION 8311170209 830930 PDR ADOCK 05000313 R

PDR go/77 J

/

AVERAGE DAILY (JNIf POWER LEVEL DOCKET NO.

50-313 I

LWIT DATE 10/15/83 K.L.Morton COMPLETED BY (501)064-3115 TELEPilONE MONTH September,1983 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-NetI (MWe Net) i 138 37 778 2

138 594 18 578 595 3

39 730 4

20 652 5

808 21 806 6

810 812 22 497 810 7

23 8

0 811 24 9

0 812 25 0

766 30 26 11 77 763 27 12 678 815 28 797 815 i3 810 34 30 818 15 812 3,

16 810 INSTRUCTIONS On this format. list the average daily umt power lesel in Mwe. Net for each daF in il'# '#P"ning month. Compute :o the nearest whole megawatt.

W177 )

DOCKET NO. 50-313 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME ANO-Unit 1 DATE Oct. 5.1983 COMPLETED BY K. L. Morton REPORT MONTH September TELEPHONE (501) 964-3115

~:.=

a 50 "k

-. EU Licensee E-r E 9.,

Cause & Corrective No.

Date E

5E k

)5$

Event 53 S.?

Action to C

j@

3dc Repori e N0 5'

Prevent Recurrence g

o e

C 83-09 830901 F

8.9 A

3 N/A CH PUMPXX The unit tripped due to an unex-plained Main Feedwater Pump trip.

The unit was returned to power.

83-10 830902 F

12.3 A

5 313-83-019 ch HTEXCH Shutdown to repair leak in feedwater heater E-2A shell expansion joint.

Leak was repaired and the unit re-turned to power.

83-11 830907 F

91.1 A

5 N/A CB PIPEXX Shutdown to repair leaking weld on RCP-32C. seal vent line. Repaired weld and returned to power.

83-12 830917 F

0.0 H

9 N/A WC DEMINX Power reduction due to high sodium content of the feedwater. Regen-erated polishers, cleaned the feed-water and returned to 100% F.P.

I operation.

I 2

3 4

F: Forced Reason:

Method:

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

Entiy Sheets for Licensee C. Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D Regulatory Restriction 4 Continuation 0161)

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

F-Administrative 9-0ther G. Operational Error (Explain)

Exhibit 1 - Same Source N/77)

Il-Other (Explain)

L__

UNIT SHUTDONNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearing on the report form.

report period. In addition,it should be the source of explan.

If category 4 must be used, supply brief comments.

ation of significant dips in average power levels. Each signi-ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT 4 Reference the applicable in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reportable occurrence pertaining to the outage or power should b'e noted, even though the unit may'not have been reduction. Enter the first four parts (event year, sequenual shut down completely. For such reductions in power lev-1, TCPort number, occurrence code and report type) of the fne l

the duration should be listed as rero,the method of reduction part designation as desenbed in item 17 of Instructions for should be listed as 4 (Other), and the Cause and Corrective Prep:tration of Data Entry Sheets for Licensee Event Report Ac' ion to Prevent Recurrence column should explain. The (LER) File (NUREG 0161). This information may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, smee sould be used to provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of the outage or power reduction.

not a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence.

NUMBER. This column should indicate the' sequential num-the positive indication of this lack of correlation should be ber assigned to each shutdown or significant reductionin power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system in which the outage or power reduction begins in one report period and ends in another.

an entry should be made for both report periods to be sure reduction originated should be noted by the two digit code of all shutdowns or significant power reductions are reported.

Exhibit G - Instructions for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num-f r Licensee Event Report (LER) File (NUREG4)l61).

ber should be assigned to each entry.

Systems that do not fit any existing code should be designa-ted XX. The code ZZ should be used for those events where DATE. This column should indicate the date of the start a system is not applicable.

of each shutdown or significant power reduction. Report as year, month, and day. August 14,1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814. When a shutdown or significant power reduction, from Exhibit 1 - Instructions for Preparation of Data Entr>

beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NURLG.0lbl L be made for both report periods to be sure all shutdowns using the following critieria:

or significant power reductions are reported.

TYPE. Use "F" or "S" to indicate either " Forced" or " Sche.

duled " respectively, for each shutdown or significant power B.

If net a component failure, use the related component.

reduction. Forced shutdowns include those required to be e.g., wrong valve operated through error: list vahe as initiated by no later than the weekend following discovery component.

of an off normal condition. It is recognized that some judg.

ment is required in cWegorizing shutdowns in this way. In C.

If a chain of failures occurs, the first component to mal-general, a forced shutdown is one that would not have been function should be listed. The sequence of events. inciud-completed in the absence of the condition for which corrective ing the other components which fail. should be described action was taken-under the Cause and Corrective Action to Prevent Recur.

rence column.

DURATION. Self explanatory. When a shutdown extends beyond the end of a report period, count only the time to the Components that do not fit any existmg code should be de.

signated XXXXXX. The code ZZZZZZ should be used for end of the report period and pick up the ensuing down time events where a component. designation is not applicable.

m the following report periods. Report duration of outages rounded Io the nearest tenth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

The sum of the total outage hours plus the hours the genera.

RENCE. Use the column in a narrative fashion to amplifs m tor was on line should equal the gross hours m the reportmg explain the circumstances of the shutdown or power reduction period.

The column should include the specifie cause for each shut down or significant power reduction and the immediate and REASON. Categorite by letter designation in accordance contemplated long term corrective action taken. if approrn-with the table appearing on the report form, if category 11 ate. This colunm should also be used for a description of the must be used, supply brief comments.

major safety related corrective maintenance perfonned dunng METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification of REDUCING POWER. Categortie by number designation the critical path activ ty and a report of any single release of radioactivity or single radiation exposure specifically associ INote that this differs from the Edison Electric Institute ated with the outage whish accounts for more than 10 percent (eel) definitions of " Forced Partial. Outage" and " Sche, of the allowable annual values.

daled Partial Outage." For these :erms. eel uses a change of For long textual reports continue narrative on separate paper 30 MW as the break point. For larger power reactors.30 MW and reference the shutdown or power reduction for this is too small a change to warrant explanation.

narrative.

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

SEPTEMBER, 1983 UNIT 1 The Unit started the month in a pcwer escalation from an unexplained feedwater pump trip which occurred last month. At 0234 hours0.00271 days 0.065 hours 3.869048e-4 weeks 8.9037e-5 months on September 1 the Unit tripped from 55% power due to a trip of the "B" Main Feedwater Pump.

A recovery was initiated, and the Unit was tied back on line at 1126 hours0.013 days 0.313 hours 0.00186 weeks 4.28443e-4 months the same day.

The Unit then began a power escalation and attained 75%

power at 0930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months on September 2.

Subsequently, the Unit began a controlled shutdown due to an expansion joint failure on the shell of Feedwater Heater E-2A.

The turbine generator was tripped at 1046 hours0.0121 days 0.291 hours 0.00173 weeks 3.98003e-4 months and reactor power was maintained at 10% until the heater was repaired; the Unit was tied back on line at 2305 hours0.0267 days 0.64 hours 0.00381 weeks 8.770525e-4 months . The Unit began escalating in power and attained 90% power on September 3.

The Unit remained there until 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months on September 4 due to Xenon restrictions. The Unit attained 100% full power operation at 1030 hours0.0119 days 0.286 hours 0.0017 weeks 3.91915e-4 months on the same date and remained there unit 1106 hours0.0128 days 0.307 hours 0.00183 weeks 4.20833e-4 months on September 7.

The Unit then began decreasing power due to a Reactor Coolant Seal leak on a reactor coolant pump seal vent line.

The Unit was taken off line at 1715 hours0.0198 days 0.476 hours 0.00284 weeks 6.525575e-4 months and placed in cold shutdown for the vent line repair.

The Unit was returned to operation again at 1223 hours0.0142 days 0.34 hours 0.00202 weeks 4.653515e-4 months on September 11 and attained 75% power at 0035 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months on September 12.

After a 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months hold, the Unit reached 90% power at 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months and held for Xenon until 0405 hours0.00469 days 0.113 hours 6.696429e-4 weeks 1.541025e-4 months on September 13 where upon it attained 100% full power operation. The Unit remained at 100%. full power until 1717 hours0.0199 days 0.477 hours 0.00284 weeks 6.533185e-4 months on September 17 when a reduction was begun to reduce power to 75% due to high feedwater sodium content.

The Unit attained 75% power at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months and remained there until 1303 hours0.0151 days 0.362 hours 0.00215 weeks 4.957915e-4 months on September 20. At this time, the Unit began increasing power and reached 90% power at 1435 hours0.0166 days 0.399 hours 0.00237 weeks 5.460175e-4 months and held for Xenon until 2345 hours0.0271 days 0.651 hours 0.00388 weeks 8.922725e-4 months , then the Unit commenced power escalation and attained 100% full power at 0125 hours0.00145 days 0.0347 hours 2.066799e-4 weeks 4.75625e-5 months on September 21. The Unit remained at 100% full power until 1420 hours0.0164 days 0.394 hours 0.00235 weeks 5.4031e-4 months on September 26 when a reduction was begun to reduce power to 85% due to a power tilt imbalance.

The Unit remained there until 1315 hours0.0152 days 0.365 hours 0.00217 weeks 5.003575e-4 months on September 27 at which time the Unit attained 100% full power operation.

The Unit finished the month at 100%

full power operation.

l

~

i

1

~

REFUELING INFORMATION I

1.

Name of facility.

Arkansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown.

September 15, 1984 3.

Scheduled date for restart following refueling.

September 15, 1984 i

4.

Will refueling or resumption of operation thereafter require a i

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 nd 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 9

F 5.

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

September 1,1984 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.

To be determined s

7.

The number of fuel assemblies (a) in the core and (b) in the spent i

fuel storage pool.

a) 177 b) 316 8.

The present licensed spent fuel pool storage capacity and the size of any increase in. licensed storage capacity that has been requested I

or is planned, in number of fuel assemblies.

.present 46n increase size by 9.

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

DATE: ~ -1998

-~

I r

i L

C ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501) 371-4000 October 15, 1983 1CAN108303 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:

Attached is the NRC Monthly Operating Report for September 1983 for Arkansas Nuclear One - Unit 1.

Very truly yours, John R. Marshall Manager, Licensing JRM:SAB:rd Attachment cc:

Mr. John T. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 d

'y i

s i

MEMeen Mioots sours uritiries svsTeM

1CAN108303, Monthly Operating Rept for Sept 1983

Text

SUMMARY

SUBJECT:

Navigation menu

1CAN108303, Monthly Operating Rept for Sept 1983

Text

SUMMARY

SUBJECT:

Navigation menu

Search