ML20138M754

Monthly Operating Rept for Nov 1985

ML20138M754
Person / Time
Site:	Duane Arnold
Issue date:	11/30/1985
From:	Mineck D, Putnam K IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
DAEC-85-981, NUDOCS 8512230145
Download: ML20138M754 (9)

Text

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f OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 12-15-85 4

C(NPLETED BY Kenneth S. Putnam TELEPHONE 319-851-7456 OPERATING STATUS Notes

1. Un it Name Duane Arnold Energy Center 2.. Reporting Period November.'1985

3. Licensed Thermal Power (MWt):

1658

4. Nameplate Rating (&oss MWe):

565 (Turbine)

5. Design Electrical Rating (Not MWe):

538

6. Maximum Dependable Capacity (Gross MWe):

545

7. Maximum Dependable Capacity (Not MWe):

515

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since the Last Report, Give Reasons:

9. Power Level to Which Restricted, if Any (Not MWe):

10. Reasons For Restrictions, if Any:

This Month Yr-to-Date Cumulative l

11. Hours in Reporting Period 720.0 8016.0 94944.0

-12. Number of Hours Reactor Was Critical 720.0 3989.2 66577.9

13. Reactor Reserve Shutdown Hours 0

0 150.3

14. Hours Generator On-Line 720.0 3%7.8 64815.5

15. thit Reserve Shutdown Hours 0

0 0

16.' Gross Thermal Energy Generated (MWH) 807202 5205526 81665461

17. Gross Electrical Energy Generated (MWH) 275451 1745991 27333345

18. Not Electrical Energy Generated (MWH) 257 % 2 1636889 25593041

19. Unit Service Factor 100.0 49.5 68.3

20. Unit Availability Factor 100.0 49.5 68.3

21. thIt Capacity Factor (Using MDC Net) 69.6 39.7 52.3

22. Unit Capacity Factor (Using DER Net) 66.6 38.0 50.1

23. thit Forced Outage Rate 0

0 16.1

24. Shutd>wns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Surveillance and maintenance outage, March, 1986, one week dsration i

i

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

N/A (9/77) 8512230145 851130 gM PDR ADOCK 050 31 R

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 (NIT Duane Arnoi d Eneroy Center DATE 12-15-8'!

COMPLETED BY Kenneth S. Putnam TELEPHONE 319-851-7456 MONiet November, 1985

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

(MWe-Net) 1 348 17 354 2-352 18 339 3

345 19 256 4

313 20 269 5

405 21 267 6

491 22 313 7

495 23 344 8

500 24 345 9-374 25 344 10 360 26 348 11' 351 27 345 12 351-28 3 54 13 352 29 347 14 358 30 3 50 15 402 31 16 368 lNSTRUCTIONS On this format, list

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Docket No. 050-0331 Unit Name Duane Arno l d Eneroy Center Date 12-15-85 Comp lete d by Kenneth S.

Putnam Telephone 319-851-7456 REFUELING INFORMATION 1.-

Name of facility.

A.

Duane Arnol d Energy Center 2

Sch e du l e d date for next refueling s h ut down.

A.

1987

. 3.-

Sche du l e d date for restart following refueling.

A.

1987 4

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

A.

None currently i de n t i f i e d

- 5 Sche du l e d - date(s ) for submitting proposed licensing action and supporting Information.

- A.

None currently i den t i f l e d 6.

Important licensing con s i derat io ns associated with refueling, e.g.,

new or di f f erent fuel de s i g n or supplier, unreviewed design or performance ana l y s is met ho ds, significant changes in fuel design, new operating procedures.

None 7

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

I, n the spent fuel

- s to r a g e pool.

A.

a) 368 b) 696 8

The present licensed spent fuel pool storage capacity and the size of any increase in li cense d storage capacity that has been requeste d or is planned, in number of fuel assemblies.

A.

2050 9

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

A.

1998 i

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Docket No. 050-0331 Uni t Name Juane Arnold Energy Center Date 12-15-85 Comp l e ted by Kenneth S.

Pu tna m Telephone 319-851-7456 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 11/01/85 At the beginning of the mon th th e plant was in normal power operation at approximately 65% of rated power.

Power levels were res tr i c ted to hold the fuel burn w i th i n u ti l i ty goals.

The plant was in day 8 of a 90 day LCO on the Post-Accident Samp ling Sys tem (PASS) and day 10 of a 30 day LCO on th e Main Steam Isolation Valve Leakage Control S y s tem.

11/04/85 At 0020 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> the High Pressure Coolant injec tion Sys tem (HPCI) was vo l u n ta r i l y removed from service to permit planned maintenance on a s tea m supply i sol a ti on valve (MO-2237).

Power levels had been reduced to approxima tely 4 0% to permit worker entry i n to the area.

(LER 85-043)

At 0711 hours0.00823 days <br />0.198 hours <br />0.00118 weeks <br />2.705355e-4 months <br /> i t was noted that core thermal l i mi ts were being approached due to Xenon burning out.

Between th i s time and 1057 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.021885e-4 months <br /> some problems were experienced in ma i n ta i n i n g core thermal l i m i ts w i th in Technica l Specification values.

Technical Specification action s ta temen ts requiring restoring the reactor to wi thin a cce p ta bl e l i mi ts were entered and followed.

At 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> a final con trol rod manipula+1on was comp l e ted.

At 1052 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />4.00286e-4 months <br /> testing showed all core thermal pa ra me ters to be well w i th i n a ccep ta b l e l imi ts.

At 1157 hcurs the Emergency Noti f ica tion Sys tem (ENS) I nd i ca ti ng light was noted to be off.

The NRC was notified of th e problem via normal phone lines and the ENS sys tem returned to service by 1336 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.08348e-4 months <br />.

At 1636 hours0.0189 days <br />0.454 hours <br />0.00271 weeks <br />6.22498e-4 months <br /> the

'B' pa th of the S ta nd by Liqui d Con trol Sys tem was declared inoperable, due to a broken I ns trumen t tap on th e discharge a cc umu l a tor,

commencing a 7 day LCO.

At 1822 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.93271e-4 months <br /> maintenance and tes ting of the HPCI sys tem was completed, ending the 7 day LCO.

11/05/85 At 1011 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.846855e-4 months <br /> the Reactor Core Isola tion Cool ing Sys tem (RCIC) was v o l u n ta r i l y removed from service for maintenance on a s tea m drain trap bypass valve (CV-2409) and to perform a minor design change to pos i tion i nd i ca ti on circuitry.

(LER 85-044)

At 134 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> the

'A' Main Steam i sol a ti on Valve - Leakage Control S y s tems was tes ted sa ti s f actori ly, ending a 30 day LCO.

11/06/85 At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> the offgas extended range ef f luent moni tor was removed from service f or ma i n tenance.

A 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO was entered to es ta b l i sh a l terna te sampling means.

At 1418 hours0.0164 days <br />0.394 hours <br />0.00234 weeks <br />5.39549e-4 months <br /> the main tenance activi ties were comp l e ted,

th e monitor re tu r ne d to service, and the LCO exi ted.

Docket Ns. 050-0331 Unit Name Duane Arnold Energy Center Date 12-15-85 Completed by Kenneth S.

Putnam Telephone 319-851-7456 N ARRATIVE SUMM ARY OF OPERATING EXPERI ENCE ( Co n t i n u e d) 11/07/85 At 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> post-maintenance testing of the RCIC system foun d the RCIC tur bi ne

+o trip on overspeed.

(LER 85-044)

At 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br /> repair an d testing of the

'B' Stan dby Liqui d control discharge accumulator were comp l e te d, en di ng the 7 day LCO.

11/08/85 At 1722 hours0.0199 days <br />0.478 hours <br />0.00285 weeks <br />6.55221e-4 months <br /> the RCIC system successfully completed testing, en ding the 7 day LCO.

11/12/85 At 0510 hours0.0059 days <br />0.142 hours <br />8.43254e-4 weeks <br />1.94055e-4 months <br /> the

'B' Core Spray Subsystem was de c l a re d inoperable when the minimum flow valve di d not close on flow exces ding 600 gpm as anticipated.

A 7 day LCO was entere d.

At 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br />, du r i n g performance of preventive maintenance, the circuit breaker tripped on the power supply to the Resi dua l Heat Removal Service Water System (RHRSW).

A heat exchanger outlet valve (MO-2046) tripped due to a component failurs within the breaker.

A7 day LCO was en tere d.

At 1616 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.14888e-4 months <br /> repair and testing of the

'B' Core Spray Subsystem was completed an d the 7 day LCO was ended.

At 1634 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.21737e-4 months <br /> the

'A' RHRSW system was returned to service en ding the 7 day LCO.

At 1638 hours0.019 days <br />0.455 hours <br />0.00271 weeks <br />6.23259e-4 months <br /> a roving fire watch was established on Reactor Bu i l ding penetrations which ha d been i denti t le d as de f i c i en t during routine inspection. Personnel were not available to establish continuous fire watches within less than one hour per Technical Specifications. By 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> continuous fire watches were es ta b l i she d.

Subsequent investigation (on 11/13/85) revealed that all the penetration seals were functional as fire barriers an d that the def iciencies noted were largely cosmetic in nature, hence, no fire watches were necessary.

11/13/85 At 0723 hours0.00837 days <br />0.201 hours <br />0.0012 weeks <br />2.751015e-4 months <br /> the electric fire pump was removed from service for planned maintenance.

A 7 day LCO was entered requiring completion of repairs or submittal of a special report to the Commission. Work was completed at 1937 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.370285e-4 months <br /> on 11/23/85 (SPECIAL REPORT 85-046 pen ding)

At 1835 hours0.0212 days <br />0.51 hours <br />0.00303 weeks <br />6.982175e-4 months <br /> maintenance and testing of the Post-Acci dont Sampling System was completed an d the 90 day LCO exited.

Oscket No. 050-0331 Un i t Name Duane Arnold Energy Center Date 12-15-85 Completed by Kenneth S.

Putnam Telephone 319-851-7456 N ARR ATI V E S UMM ARY OF OPERATING EXPERIENCE (Co n t in u e d) 11/16/85 At 0805 hours0.00932 days <br />0.224 hours <br />0.00133 weeks <br />3.063025e-4 months <br /> a momentary secon dary containment violation occurred when the airlock doo r s to the main supply fan room were simultaneously open.

(LER 85-045 pen ding) 11/22/85 At 1405 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br /> a momentary secon dar y containment violation occurred when rallroad doo r s and the offgas retention bu l l ding doo r s were simultaneously open.

(LER 85-45 pen ding) 11/30/85 At the en d of the month the plant was in normal operation at 378 MWe (gross).

This exten ded our current days of continue d operation to 130 days.

1 w

lowa Electric Light and Ibwer Company December 15, 1985 DAEC-85-981 Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attn: Document Control Desk

Subject:

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

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for November,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, Sec. n 6.11.1.c and Regulatory Guide 10.1.

Very truly yours, QJ4Q 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 Comission Maryland National Bank Building 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 i

Washington, D. C. 20555 (1)

Marion, IA 52302 U. S. Nuclear Regulatory Comission Mr. Russ Gamble ATTN: Mr. M. Thadani Corn Belt Power Cooperative Phillips Building 1300 13th Street North Washington, D. C. 20555 Humboldt, IA 50548 INP0 Records Center 1100 Circle 75 Parkway Suite 1500 Atlanta, GA 30339 fg Q n.,,. n : ma.. un awa, na.c n..,,,u,. u,,- wa. aumm.a,1