ML20214C805

Monthly Operating Rept for Apr 1987

ML20214C805
Person / Time
Site:	Duane Arnold
Issue date:	04/30/1987
From:	Axline J, Mineck D IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
DAEC-87-0527, DAEC-87-527, NUDOCS 8705210102
Download: ML20214C805 (7)

Text

.

OPERATING DATA REPORT 1

DOCKET NO. 050-0331 DATE 05-15-87 COMPLETED BY Jeff S. AxlIne TELEPHONE 319-851-7600 OPERATING STATUS Notes

1. Unit Name Duane Arnold Energy Center

2. PoportIng Period AprIi. 1987

~3. Licensed Thermal Power (MWt): 1658

4. Nameplate Rating (Gross MWe):

565 (Turbine) '

5. Design Electrical Rating (Not MWe): 538

6. Maximum Dependable Capacity (Gross MWe: 545

7. Maximum Dependable Capacity (Net MWe):

515

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

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

10. Reasons For Restrictions, if Any:

This Month Yr-to-Date-Cumulative

11. Hours in Reporting Period 719 2879' 107327

12. Number of Hours Reactor Was Celtical 0

1693.5 76363.8

13. Reactor Reserve Shutdown Hours 0

0 192.8

14. Hours Generator On-Line O'

1691.3 74431.9

15. Unit Reserve Shutdown Hours 0

'O O

16. Gross Thermal Energy Generated (MWH) 0

~ 2191651.2 94273844.6

17. Gross Electrical Energy Generated (MWH) 0 755235 31613320.0

18. Net Electrical Energy Generated (MWH) 0 705812.9 29610613.0

19. Unit Service Factor 0

58.7 69.4

20. Unit Avallability Factor 0

58.7 69.4

21. Unit Capacity Factor -(Using K)C Net) 0 47.6 53.6

22. Unit Capacity Factor (Using DER Net) 0 45.6' 51.3

23. Unti Forced Outage Rate 0

0 14.6

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

N Refuel Outage which began March 12. 1987 4

l 4

25. If Shut Down At End of Report Period, Estimated Date Of Startup End of May-i ggs2;gg2 g7,gggy on2) 3),

R

e' t {

' AVERAGE DAILY UNIT POWER LEVEL' L

DOCKET NO. 050-0331 UNIT Duane Arnold Energy Center DATE 05-15-87 00WLETED BY Jeff S. Axtine TELEPHONE 319-851-7600 MONTH ~ AprII, 1987

' DAY.

AVERAGE DA Y POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1

0 17 0

2 0

18 0

'3 0

19 0

4 0

20 -

0-5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

l.

9 0

25 0

10 0

-26 0

11 '

O

.27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0-31 0

16 0

INSTRUCTIONS

-On this format, list the average daily unit power level in MWe-Net for each day in the reporting month Corepute tha nserest whole megawatt.

(9/77) 1.

4 i

1 4

1 i

1 y

g

+ ---

--e 4

s.-

ywar-e,,,g.,,

a,r

+

.~

l UNIT SHUTDOWNS AND POWER REDUCTIONS Dockot No. 050-0331 Unit Naco Dunto Arnold Energy Cen te r.-

Da to 05/15/87 REPORT MONT H April, 1987 Comp l e ted by Jeff S. Axline Teiephone 319-451-7600 m

L a0 a

+

g Licensee 5m o-e oc No.

Date 2E

• 7*

Event 5*

Cause

,e

• j, Report i N$

a0 O~

u o

l Raivel Outaga i

1 3-12-87 S

719 C

2 l

1 2

3 4

F: Forced Reason:

Me th o d :

Exhibi t G-Ins tructions S: Scheduled A-Equipment Failure (Explain) 1-Manual f or Preparation of Da ta B-Maintenance or Tes t 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File (NUREG-D-Regu la tory Restriction 4-Other (Explain) 0161)

E-Opera tor Trai ning & License Examination l

F-Admi n i s tra ti ve 5

l G-Opera tiona l Error (Explain)

Exhiblt 1-Same Source

~

(9/77)

H-O th er (Explain)

Deckot No. 050-0331 Unit Dusen Arnold Energy C <w t :' r -

Date 05-15-87 MAJOR / SAFETY RELATED MAINTENANCE Completed By Jeff S.

Axline Telephone 319-851-7600 l DATE SYSTEM COMPONENT DESCRIPTION i4-2-87 Core Spray isolation Valve Motor (M02100-M)

Repair bare spot on motor wiring.

l

! 4-6-87 Stanoby Gas Treatment Drywell Exhaust isolation Valve Installed 2 gaskets and 2 0-rings.

Cleaned l

(CV4302)

Inside of valve.

j 4-16-87 Stack Gas Radiation Monitoring Kaman #10 Sample Flow Control Replaced flow control valve and flow control Valve and Flow Control Circuit circuit board.

Board i 4-28-87 Stack Gas Radiation Monitoring Offgas Sample Rack Vacuum Pump Replaced carbon vanes.

(IP247A) 1 4-30-87 Chemistry and Radiation Lab Rad CRT Display Replaced electrical components on the CRT Monitoring scan board and reset trip point.

ll 4-1-87 Residual Heat Removal Pipe Welds inservice Inspection.

l thru 4-30-87 Reactor Vessel Recirculation Pipe Welds and Nozzles Inservice inspection.

GC

gsing) l Standby Diesel Generator

'B' Diesel Complete teardown of the diesel to replace cylinders.

Main Steam Line Main Steam Lines Reinsulation of main steam lines is continuing.

Primary Containment Heating and Drywell Coolers Cleaned old coolers and installed 2 Ventilation additional coolers.

Reactor Vessel Recirculation

'B' Recire Pump Replacement of pump seals has been completed.

Reactor vessel Recirculation Jet Pump Sensing Lines installed additional support clamps and replaced hold-down beams.

l Condensate Condensate Pump Balancing of pump Impeller.

Main Steam Main Steam Isolation Valves (MSIV)

Inspection and preparation for weld buildup-of valve discs, i

r-DOCKET NO. 050-0331 UNIT Dunan Arnold Ennroy Crnter

-DATE 05-15-87 COMPLETED BY Jeff S.

Axllne TELEPHONE 319-851-7600 REFUELING INFORMATION 1.

Name of facility.

A.

Quane Arnold Energy Center 2

Scheduled date for next refueling shutdown.

A.

September 14, 1988 3.

Scheduled date for restart following refueIIng.

A.

End of May 4

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

Yes A.

Reload license submittal 8

Additional MAPLHGR curves for new fuel bundles being Introduced for Cycle 9 5

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

A.

Submitted 8

Submitted 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.

a) 0 b) 1892 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 refueling that can be discharged to the spent fuel pool assuming the present Ilconsed capacity.

A.

1998 L

DOCKET NO. 050-0331 UNIT Duano Arnold Ennroy Center DATE 05-15-87 i

COMPLETED BY Jeff S.

Axilne TELEPHONE 319-851-7600 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE l'

4-1-87 At the beginning of the month the Ouane Arnold Energy Center (DAEC) was in cold shutdown continuing the cycle 8/9 refuel outage.

t i

4-2-87 At 1259 hours0.0146 days <br />0.35 hours <br />0.00208 weeks <br />4.790495e-4 months <br /> a fire was reported in the Low Level Radweste Building j

(LLRW).

The fire, which had started in a laundry dryer, was put out a t.

1302. hours.

s 4-2-87 At 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> defueling of the reactor vessel was completed.

4-9-87 At 0846 hours0.00979 days <br />0.235 hours <br />0.0014 weeks <br />3.21903e-4 months <br />, with all fuel removed from the vessel, a Primary Containment lsolation System Group 111 Isolation occurred.

The'cause of the Isolation q

was quickly determined to be an inadvertent de-energization of an essential 4160 VAC bus.

At 0912 hours0.0106 days <br />0.253 hours <br />0.00151 weeks <br />3.47016e-4 months <br /> the bus was re-energized.

it was later determined that Inadequate pre-work review of the effect of removing power supply fuses to this circuit was the cause of the unplanned de-energitation.

(LER 87-010) 4 4-11-87 At 2116 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.05138e-4 months <br /> an unplanned half Group 111 Isolation occurred when a worker j

Inadvertently knocked a jumper off.

The jumper was reconnected and the Isolation was reset at 2222 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.45471e-4 months <br />.

At 0822 hours0.00951 days <br />0.228 hours <br />0.00136 weeks <br />3.12771e-4 months <br /> on April 14, 1987 the 1

same situation occurred.

When the jumper was replaced, a different type of jumper was used to reduce the possibility of this happening again. At 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br /> the Isolation was reset.

(LER 87-011) 4-15-87 At 2228 hours0.0258 days <br />0.619 hours <br />0.00368 weeks <br />8.47754e-4 months <br /> the In-vessel platform was Installed in preparation for work on the jet pump sensing lines.

4-25-87 At 1833 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.974565e-4 months <br /> a fire was reported in the pumphouse.

At 1841 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.005005e-4 months <br /> the fire was put out by the fire brigade.

4-30-87 The new VAX 8600 process computer arrived onsite this month.

It will be Installed and run in parallel with the present computer for one refuel cycle.

The month ended with the cycle 8/9 refuel outage approximately 655 completed.

Up to this paint the outage has gone smoothly and the duration has had to be extended only 2 weeks.

This will put the end of the outage l

in the last week In May.

3 I

4 l

l 1

4

Iowa Electric Light and Power Company May 15, 1987 DAEC 0527 i

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C.

20555

Subject:

Duane Arnold Energy Center Docket No. 50-331 Op. License DPR-49 February,1987 Monthly Operating Report

Dear Sirs:

Please find enclosed the Duane Arnold Energy Center Monthly Operating Report for April, 1987. 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.

Very truly yours,

)fil e t

Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/JA/go*

Enclosures File A-118d cc: Mr. A. Bert Davis Mr. Phillip Ross Regional Administrator U. S. Nuclear Regulatory Commission Region III Maryland National Bank Building U. S. Nuclear Regulatory Commission Washington, D. C.

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

NRC Resident Inspector Mr. Robert A. Gilbert Mr. Dennis Murdock Project Manager Central Iowa Power Cooperative BWR Project Directorate #2 Box 2517 U. S. Nuclear Regulatory Comnission 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 Sulto 1500 Atlan ta, GA 30339 J~f*$

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