Text

Monthly Operating Rept for Jul 1987
	ML20237J588
Person / Time
Site:	Duane Arnold
Issue date:	07/31/1987
From:	Axline J, Hannen R; IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	DAEC-87-0796, DAEC-87-796, NUDOCS 8708180242
	Download: ML20237J588 (9)
	v • d • e

OPERATING DATA REPORT i

)

DOCEET NO. 050-0331 DATE 08-15-87 J

COMPLETED BY Jef f S. Ax11ne TELEPHONE 319-851-7600 OPERATING STATUS i

Notes

1. Unit Name Duane Arnold Eneroy Center

]

I

2. Reporting Perlod July, 1987

3. Licensed Thermal Power (MWt): 1658 d

i I

4. Namtplate Rating (Gross MWe):

565 (Turbine) j i

5. Design Electrical Rating (Net MWe): 538 i

6. Maximum Dependable Capacity (Gross MWe: 545

7. Maximum Dependable Capacity (Net MWe):

515 i

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

]

1

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

10. Reasons for Restrictions, if Any Thic Month Yr-to-Date Cumulative i

4 i1. Holrs In Reporting Period 744 5087 109535

12. Number of Hours Reactor Was Critical 605.4 2381.7 77052

13. Reactor Reserve Shutdown Hours 0

0 192.8 l

1

14. Hours Generator On-Line 546 2250.6 74991.2 l

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15. Unit Reserve Shutdown Hours 0

0 0

l

16. Gross Thermal Energy Generated (MWH) 682627.2 2878305.6 94960499

17. Gross Electrical Energy Generated (MWH) 221913 978145

-31836230

18. Net Electrical Energy Generated (MWH) 207581.2 914022 29818822.1

19. Unit Service Factor 73.4 44.2 68.5

20. Unit Availability Factor 73.4 44.2 68.5

21. Unit Capacity Factor (Using MDC Net) 54.2 34.9 52.9

22. Unit Capacity Factor (Using DER Net) 51.9 33.4 50.6

23. Unit Forced Outage Rate 0

0 14.5

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

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

/

[ h i k (9/77) 8708180242 870731 i

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i PDR ADOCK 05000331 1

R PDR-g l

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

UNIT Duane Arnold Energy Center I

DATE 08-15-87 '

COMPLETED BY Jef f S. Axllne i

TELEPHONE 319-851-7600 MONTH July, 1987 g

1 l

'1 MY AVERAGE DAILY POWER LEVEL, DAY AVERAGE DAILY POWER LEVEL

.{

l (MWe-Net)

(MWe-Not)-

1 69 17 465 2

115 18 458 3

167 19 443 14 226 20 4 54 d

I 5 35 21 486

)

6 0

-22 505

7 0

23 499 l8 0

24 4 51 l9 0

25 475 10 0

26 4 52 q

'01 0

27 507 02 0

28 4 92 1

33 31 29 487 24 171 30 489 l

95 263 31 490 16 416 INSTRUCTIONS Cn this format, list the average dally unit power level in MWe-Net for each day in the reporting nonth. Compute 9he nearest whole'segawatt.

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L 00CKET NO. 050-0331.

l l

UNIT Duane Arnold Energy Center i

l DATE 08-15-87

)

COMPLETED BY Jeff S.

Axilne TELEPHONE 319-851-7600 i

REFUELING INFORMATION.

)

r I

J 1

Name of facility.

[

1 l

A.

Duane Arnold Energy Center I

i 2

Scheduled date for next refueling shutdown.

i A.

Fall, 1983

)

[

3 Scheduled date for restart following refueling.

i A.

Fall, 1988

{

l 4

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

5.

Scheduled date(s) for submitting proposed licensing action and supporting' q

information.

N/A I

6 Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significa1t changes in fuel design, _new operating procedures.

l None l

7 The number of fuel assemblies (a) In the-core and (b) In the spent fuel l

storage pool.

A.

a) 368 b) 824 6

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 p roj ect ed date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

l l

A.

1998 j

i I

i l

I

DOCXET NO. 050-0331 UNIT Duane Arnold Energy Center DATE 08-15-87 COMPLETED BY Jeff S.

Axline TELEPHONE 319-851-7600 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 7-1-87 At the beginning of the month the Duane Arnold Energy Center (DAEC) was 1

1 operating at 22% of rated thermal power with 69 MWe-net being supplied to l

the grid.

At this time the

'A' outboard Maln Steam isolation Valve (MSIV) would not fully open.

(

I 7-4-87 At 0705 hours0.00816 days 0.196 hours 0.00117 weeks 2.682525e-4 months a 7 day Limiting Condition for Operation (LCO) was entered when the Reactor Core isolation Cooling (RCIC) system was declared inoperable due to a feedwater stop valve in its exhaust line being inoperable.

At 1403 hours0.0162 days 0.39 hours 0.00232 weeks 5.338415e-4 months , the valve was repaired and determined operable.

This made RCIC operable, ending the 7 day LCO.

l 7-5-87 At 1420 hours0.0164 days 0.394 hours 0.00235 weeks 5.4031e-4 months , the plant was shutdown to perform maintenance on the

'A' outboard MSlV.

7-11-87 With the plant in hot standby, a 1/2 Group i isolation occurred during venting of the Main Turbine Electrohydraulic Control (EHC) Piping.

The EHC i

piping was being vented following repairs to pin-hole leaks whlch were discovered during reactor startup eeriler in the day.

During venting.of the EHC piping, three of the tour Turbine Stop Valves lifted off their seat.

This removed the Main Condenser Low Vacuum, Group I isolation bypass signal.

This satisfled the necessary logic to close the inboard Main Steam Line draln valve and inboard Recirculation Sample Flow Control _ valve.

The Intermediate cause of the event was the Turbine Stop valves lifting off their seat due to air which was trapped in the EHC piping and caused a vold to form.

The root cause of this event was lack of procedural guidance alerting operators to the potential of Turbine Stop valve motion during EHC system venting.

I As corrective action, a note wIll be added tc the applicable operating instruction (01) warning personnel that during EHC system venting, potential Stop valve Cycling and subsequent Group i isolations can occur l

due to the loss of tho main condenser low vacuum isolation Dypass signal.

j l

LER 87-022 7-12-87 At 0607 hours0.00703 days 0.169 hours 0.001 weeks 2.309635e-4 months , the reactor mode switch was placed in the run mode.

Maintenance on the

'A' outboard MSlV had been completed satisfactorily.

DOCKET NO. 050-0331 UNIT Duane Arnold Ensrgy Center DATE 08-15-87 COMPLETED BY Jeff S.

Axtine TELEPHONE 319-851-7600 R

I f

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE i

7-13-87 At 1925 hours0.0223 days 0.535 hours 0.00318 weeks 7.324625e-4 months , a 7 day LCO was entered when the diesel fire pump f a i l ed to meet required discharge pressure at required flow.

After adjustments and calibration of pump equipment and instruments did not resolve the problem, It was decided that the pump would have to be rebuilt.

Unexpected problems during reassembly of the pump caused it to be Inoperable at the end of the 7 day LCO making this a reportable event.

At 2216 hours0.0256 days 0.616 hours 0.00366 weeks 8.43188e-4 months on July 20, 1987, the pump was declared operable following satisfactory performance of its operability test.

LER 87-025 I

7-14-87 With the plant operating at 40% of rated thermal power the High Pressure

]

Coolant injection (HPCI) system was declared Inoperable when It failed to l

meet the quarterly operability test.

The HPCI lube oil pressure control valve diaphragm was discovered to be leaking.

It was discovered after q

removal that this diaphragm, which was installed on July 10, 1987, was not the reinforced diaphragm that was supposed to.be used for this application.

On July 16, 1987, the correct diaphragm was installed and at 1949 hours0.0226 days 0.541 hours 0.00322 weeks 7.415945e-4 months the HPCI system was declared operable.

LER 87-023 7-14-87 At 2013 hours0.0233 days 0.559 hours 0.00333 weeks 7.659465e-4 months a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO was entered due to the High Pressure Coolant injection (HPCI) system and Low Pressure Coolant injection (LPCI) system being declared inoperable.

At 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months the 8A' LPCI Inject, outboard Isolation valve was declared operable thus making LPCI operable, ending the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO.

HPCI continued to be Inoperable (see LER 87-023).

7-26-87 At 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months a 7 day LCO was entered when the

'A' Emergency Service Water (ESW) pump was declared inoperable due to high river water temperature. At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months the LCO was exited when the river water temperature fell below the high temperature mark.

7-28-87 At 1109 hours0.0128 days 0.308 hours 0.00183 weeks 4.219745e-4 months a 30 day LCO was entered when the

'A' containment level recorder was taken out of service for planned maintenance.

At 1845 hours0.0214 days 0.513 hours 0.00305 weeks 7.020225e-4 months the recorder was returned to service, ending the 30 day LCO.

7-29-87 At 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months a 30 day LCO was entered when the

'A' and

'B' suppression pool level recorders were taken out of service, one at a time, for corrective maintenance.

After calibration, the recorders were returned to service, ending the 30 day LCO.

i

)

l l

J

8 DOCKET NO. 050-0331 UNIT Duane Arnold Energy Center DATE 08-15-87 COMPLETED BY Jeff S.

Ax!Ine TELEPHONE 319-851-7600 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Five Reactor Water Cleanup Isolations occurred during the final days of July due to spurlous trips of the Steam Leak Detection System.

4.

Investigation into the root causes is continuing.

LER 87-024 At the end of the month, the plant was operating at 94% of rated thermal jpower with 489 MWe-ne t being supp!!ed to the grid.

No LCOs were in affect lat this time.

l De I

4 o

e t

i e

I i

Iowa Electric Light and Power Company J

August 15, 1987

)

DAEC-87-079F I

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 1

Washington, D. C.

20555 i

Subject:

Duane Arnold Energy Center Docket No. 50-331 l

Op. License DPR-49 l

July,1987 Monthly Operating Report

Dear Sirs:

i i

Please find enclosed the Duane Arnold Energy Center Montnly Operating Report for June, 1987. The report has been prepared in accordance with the guidelines j

of Regulatory Guide 1.16 and distribution has been made in accordance with DAEC l

Technical Specifications, Appendix A, Section 6.11.1.c.

l Very truly yours, f

4Y **

AM Rick L. Hannen Plant Superintendent - Nuclear Duane Arnold Energy Center RLH/JA/go*

Enclosures File A-118d cc:

Mr. A. Bert Davis Mr. Phillip Ross Regional Administrator U. S. Nuclear Regulatory Commission Region III Maryland Mational Ban'k Building U. S. Nuclear Regulatory Commission Washington, D. C.

20555 (2) 799 Roosevelt Road Glen Ellyn, IL 60137 (1)

NRC Resident Inspector Mr. Anthony J. Cappucci Mr. Dennis Murdock Project Manager Central Iowa Power Cooperative BWR Project Directorate #2 Box 2517 U. S. Nuclear Regulatory Commission Cedar Rapids, IA 52406 7920 Norfolk Avenue Bethesda, MD 20814 Mr. Russ Gamble Corn Belt Power Cooperative INP0 Records Center 130013th Street North 1100 Circle 75 Parkway Humboldt, IA 50548 Suite 1500 Atlanta, GA 30339 J' \\\\

4WO 3a(0

/

s Duane Arnold Ener[vVenter

3277 UAEC Itoad

Palo, Imva 52324

319R51-7611

_ _ - _

ML20237J588

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