Text

Monthly Operating Rept for Jan 1985
	ML20107E724
Person / Time
Site:	Duane Arnold
Issue date:	01/31/1985
From:	Mineck D, Putnam K; IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	; NRC OFFICE OF ADMINISTRATION (ADM)
References
	DAEC-85-0143, DAEC-85-143, NUDOCS 8502250747
	Download: ML20107E724 (10)
	v • d • e

.

(PERAT I PG D ATA REPORT e

D OCK ET NO. 050-0331 D AT E 02-15-85 COMP LETED BY Kenneth S. Putnam TELEPHONE 319-851-7456 OPERAT IPG STATUS Pbtes

1. U n i t Name D uane Arnold Energy Center

2. Report ing Perlod January, 1985 3 Li censed Thermal Power (MWt):

1658

4. Namep late Rating (Gross MWe) :

565

5. D esign E lectrical Rating (Net MWe):

538

6. Maximum O ependable Capaci ty (Gross MWe) :

545

7. Mnximum D ependable Capacity (Net MWe):

515 8 It Changes Occur i n Capaci ty Ratings (Ite, Number 3 Through 7) Si nce the Last Report, Gi ve Reasons :

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

Average maximum attelnable power was approximately 83% of full power.

10. Reasons For Restrictions, i f Any -

Coastdown due to fuel d ep l et ion.

Maximtsn attainable power was approximately 86.4% power on January 1, 1985 and 79.0% on January 31, 1985.

This Month Y r-to-O ate Cumulative I

11. Hours in Reporting Period 744.0 744.0 87672.0

12. Number of Hours Reactor Was Cri tical 744.0 744.0 63332.7

13. Reactor Reserve Shutdown Hours 0.0 0.0 150.3 14 Hours Generator On-Line 744.0 744.0 61591.7

15. U n it Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 974568 974568 77434503

17. Gross E lectrical Energy Generated (MWH) 325586 325586 25912940

18. Net Electrical Energy Generated (MWH) 304146 304146 24260297

19. U nit Service Factor 100.0 100.0 70.3

20. Unit Availability Factor 100.0 100.0 70.3

21. U nit Capacity Factor (Using M)C Net) 79.4 79.4 53.7

22. Unt t Capact ty Factor (Us ing DER Net) 76.0 76.0 51.4

23. U nit Forced Outage Rate 0.0 0.0 16.8 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refuel outage ben tnning 2/1/85 of a duration of approximately 16 weeks.

8502250747 850131 PDR ADOCK 05000331 R

PDR g

25 If Shut Down At End Of Repcrt Period, Estimated C ate of Startup:

}

(9/77)

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 5

UNIT Duar.e Arnold Eneroy Center DATE 02-15-85 COMPLETED BY Kerneth S. Putnam TELEPHONE y 7-851-7456 MONTH January, 1985

-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 433 17 412 2

437 18 400 3

427 19 399 4

424 20 407 5

426 21 399 6

419 22 400 7

418 23.

400 8

429 24 395 9

420 25 400 10 423 26 323 11 367 27 395 12 410 28 399 13 416

- 29 393 14' 417 30 393 15 416

-31 391 16 409

~

INSTRUCTIONS On this format, list the averego dally unit power level in MWe-Net for eech, day in the reporting month. Compute to ;

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Docket No. 055-0331 U nit D uane Arnold Enerny Ctr D at e 02-15-85 Cn=; : et ed by Kenneth S. Putnam Tolophone 319-851-7456 NARRATIVE SU MM ARY OF OP ER AT I NG EXP ER I EN CE J

01/01/85 Normal plant operation at 4C5 MWe (gross).

t 01/02/85 At 0359 hours0.00416 days 0.0997 hours 5.935847e-4 weeks 1.365995e-4 months , the "A"

Standby Fil ter U nit auto-Initiated as a result of low ventilation inlet air temperature.

(LER 84-043) 01/17/85 At 0820 hours0.00949 days 0.228 hours 0.00136 weeks 3.1201e-4 months , workers in the Essential Switchgear Room inadvertently tripped open a breaker which rendered an emergency diesel generator inoperable. Operators were I mmsd l ately Informed of the event by both control room annunciation and the notification by the workers and restored the sy stem to normal status within minutes.

01/18/85 At 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months , survelllance testing found that the solenold valve controlling reagent gas flow to the "A" H022 analyzer was leaking by and could not be isolated by the normal method during testing.

The "A"

analyzer was conservatively vaclared Inoperable. The "B"

analyzer was already considered Inoperable due to a failed valve rendering it incapable of obtalning a sample from the torus area.

A 24-hour LCO was entered, a plant shutdown commenced,'and an Unusual Event was declared. Special testing of the "A"

H022 analyzer confirmed that it was, In fact, operational at.1125' hours on 01/19/85, end ing the Unusual Event and the 24-hour LCO.-

At 1014 hours0.0117 days 0.282 hours 0.00168 weeks 3.85827e-4 months , workers inadvertenly damaged a cooling Jacket line for the "B" D i esel Generator. The diesel generator was declared Inoperable and a-7-day LCO communced. Repairs were completed and the diesel generator _was declared ooproble at 2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months , end i ng the 7-day LCO.

At 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months , the Post-Accident Samp l ing Stat ion-' w as decl ared Inoperable when It was -found to. have air Inleakage on the drywell air sampilng line.

A 7-day LCO was declared to cont.fra that a sample could be ob,tained in a timely manner (within 24. hours of a decIslon to' sample).

~

01/19/85 At 1150 hours0.0133 days 0.319 hours 0.0019 weeks 4.37575e-4 months ,-the "B"

Standby Filter Unit. heaters were found inoperable due to a temperature switch be i ng ou t of ca l i brat ion.-

The "B"

Standby Filter Un it -was deci rred Inoperable end.a ' 7-d ay-LCO commenced..The sy stem was returned to. service at 2125 hours0.0246 days 0.59 hours 0.00351 weeks 8.085625e-4 months ending the LCO.

01/22/85 At:1310 hours, the Post-Accident Sampling Station was returned t 'o -

service ending. iae 7-d ay LCO.-

01/23/85 At 1G17 hours,-the Reactor' Water Cleanup System' Isolated on a

+

spurious. signal from i t s ;- s tea m leak detection logic. The; event

raposted itself at 1958 hours0.0227 days 0.544 hours 0.00324 weeks 7.45019e-4 months and.again at 0853 hours0.00987 days 0.237 hours 0.00141 weeks 3.245665e-4 months onL01/25/85

'In each case.the Reactor ? Water Cleanup Room-was Inspected and no leakege was'found.

-( LER 85-01 ~

p end ing)

L-d

~

i D ocket No. 055-0331 Unit Duane Arnold Energy Ctr D a te 02-15-85 Completed by Kenneth S.

Putnam Telephone 319-851-7456 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Cont) 01/24/85 At 1520 hours0.0176 days 0.422 hours 0.00251 weeks 5.7836e-4 months , the Control Room received an alarm Indicating that the "B"

Essential Service Wster (ESW) pump was de-energized.

The auxillary operator was immediately dispatched to the essential Switchgear Room to investicate.

Workers running cablos In the area had inadvertently tripped a breaker supplying power to the "B"

ESW pump.

The system was restored to service by 1533 hours0.0177 days 0.426 hours 0.00253 weeks 5.833065e-4 months .

At 1540 hours0.0178 days 0.428 hours 0.00255 weeks 5.8597e-4 months , the Auxillary Operator discovered tnat another breaker in the same area controlling the auxillary system power of the "B" D i es e l Generator was also tripped. The breaker was re;2rned to its normal position and all work activities in the area were halted while the event was further Investigated and workers were instructed about the caution that must be exercised when working around safety-related equipment.

The "B"

Emergency O l esel Generator's tube oII temperature was found to be out of the normal band.

The "B" D i ese l Generator was conservatively declared Inoperable and a 7-day LC0 commenced.

Investigation Indicated that the tube oil cooling pump powered from the auxillary power breaker was de-energized for less than 30 minutes.

01/25/85 At 1250 hours0.0145 days 0.347 hours 0.00207 weeks 4.75625e-4 months , surveillance testing found that'an excess flow check valve on a line from the "B" Recirculation Pump cavity seal would not shut.

A 24-hour LC0 was temporarily entered until a manual isolation valve on the line was closed.

While performino tests which required lowering the reactor building alr temperature, the temperature of the Standby Liquid Control pump suction piping Indicated.one degree Fahrenholt below the guidallnes of Technical Speelfications (SBLC tank. liquid;

. temperatures remained well above this value).

A 24-hour'LCO was therefore entered at 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months and an Unusual Event was consequently' declared. Portable space heaters were installed near the piping and the temperature was restored to acceptable levels at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months 'ending the 24-hour LCO and the (Inusual Event.'

At 1638 hours0.019 days 0.455 hours 0.00271 weeks 6.23259e-4 months , a momentary secondary containment Violation occurred when doors between the reactor building and turbine building were Inadvertently opened simultaneously due to a failed Interlock.

.(LER 85-03.

pending) 01/28/85 At 0250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months , _ surveillance testing discovered a problem with the- _

HPCI system.

The turbine stop valve'would not open due to e pilot s:

valve being stuck' closed. -The HPCI system was declared.-Inoperable and a 7-day _LCO commenced.

(LER 85-02 pending)

Docket "o.

055-0331 Unit C sano Arnold Energy Ctr Date 02-15-85 Completed by Kenneth S. Putnam Telephone 319-851-7456 NAR9ATIVE SU MM ARY OF OP ER AT l hG EXPERIENCE (Cont) 01/29/85 At'1145 hours0.0133 days 0.318 hours 0.00189 weeks 4.356725e-4 months , operability testing of the HPCI sy stem was completed, ending the 7-day LCO.

01/30/85 At 0825 hours0.00955 days 0.229 hours 0.00136 weeks 3.139125e-4 months a failed Interlock solenold permitted both the.

reactor building rallrced airlock door and the off-gas retention-building door to be simultaneously open thus momentarily violating secondary containment Integrity.

( LER 8 5-03 pending) 01/31/85 At the end of the month the plant was in normal operation at 425

- MWe (gross).

l L

s

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Docket No. 050-0331 Un it Duane Arnold Energy Ctr Date 02-15-85 Completed by Kenneth Putnam Telephone 319-851-7456 RFFUELING INFORMATION 1

Name of facility.

A.

Duane Arnold Energy Center 2

Scheduled date for next refueling s h u td ow n.

A.

February, 1985 3.

Scheduled date for restart'following refueling.

A.

May, 1985 4

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes.

A.

Reload license submittal.

B.

Additional MAPLHGR curves for now. fuel bundles being introduced for Cycle 8 C.

Revised Spent Fuel Storage Technical Specifications.

D.

Supplemental Reload License submittal,for Cycle 8 Lead Test Fuel Assemblies including MAPLHGR curves.

5 Scheduled date(s) for submitting proposed licensing action and-supporting Information.

A.

Submitted C.

Submitted B.

Submitted D.

Submitted-6 Important licensing considerations associated with refueling,-e.g., now; or dif f erent fuel designlor supplier, unreviewed-deslanaor performance-ana lys is -methods,. signi f icant changes in fuel-deslan,:new operating Ai procedures.

5 GE Lead test assemblies wt ich ' Incorporate advanced fuel. designs'will be loaded-for Cycle 8 7

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

i A '. -. a l l 36 8 b) 576.

N

. h. '

Docket No. 055-0331 Unit Duane Arnold Energy Ctr Da te 02-15-85 Completed by Kenneth S.

Putnam Telephone 319-851-7456 REFUELING INFORMATION (Continued) 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.

A..

2050 9

The' projected date of the last refuellnq that can be discharged to the spent fuel pool assuming the preJent licensed capacity.

A.

1998

/

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$ i N

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g ;.

Iowa Electric Light and Ibwer Company February 15, 1985 DAEC-85-0143 Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Ccmmission Washington, D. C.

20555 Attn: Document Control Desk

Subject:

Duane Arnold Energy Center Docket No. 50-331 Op. License DPR-49 January, 1985 Monthly Operating Report

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for January,1985. The report has been prepared in accordance with the guidelines of Regulatory Guide 1.16 and distribution has been made in accordance with DAEC Technical Specifications, Appendix A, Section 6.11.1.c and Regulatory Guide 10.1.-

Very truly yours, J1Aa Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/KSP/kp*

Enclosures File A-118d, TE-5 cc: Director, Office of Inspection Mr. Phillip Ross and Enforcement U. S. Nuclear: Regulatory Commission U. S. Nuclear-Regulatory Commission.

Maryland l National-Bank Bldg.'

Region III Washington, D.

C'.

20555 799 Roosevelt Road' Glen Ellyn, IL 60137 (1)

NRC Resident Inspector.

Director, Office of Management and Mr. Dennis Murdock Program Analysis Central Iowa Power Cooperative-U. S. Nuclear Regulatory Comission -

Box 2517

Washington, D. -C. -20555 _(1)

Marion,:IA 52302 U. S. Nuclear. Regulatory _Comission.

Mr. George Toyne,. Gen.iMgr.

ATTN:~Mr. M. Thadani Corn Belt Power Cooperative Phillips Bldg.

Box 508 Washington, D. C. 20555 Humboldt, IA 505481 L

INP0 Records Center pg v

.1100 Circle 75 Parkway l-Suite 1500 s

Atlanta, GA: 30339 Duane Arnold Energy Center

P.O. Box.351

Cedar napkin, Iowa 52406 e 318!8817611

'

ML20107E724

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