Text

Monthly Operating Rept for May 1981
	ML20004F668
Person / Time
Site:	Duane Arnold
Issue date:	06/15/1981
From:	Van Sickel J; IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	;
Shared Package
ML20004F667	List: ML20004F666; ML20004F668;
References
	NUDOCS 8106220010
	Download: ML20004F668 (8)
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OPERATING DATA REPORT DOCKET NO. 050-0331 DATE.inno 15. 1981 COMPLETED DY 1 Van 94ckel

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TELEPilONE 310 R';1 'ifill

OPFl!ATING STATUS I'

Notes

l. Unit Name:

Duane Arnold Enerov Center

2. Itegiorting Period:.N3Ys 1901 h.

3. Licensed Thermal Power (MWt):

1658 T65 (Turbine Rat.ing)

4. Nameplate Itating (Gross MWe):

538

5. Design Flectrical nating (Net MWe):

545

6. Maximum Dependable Capacity (Gross MWe):

515

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur la Capacity Ratings'(Items Number 3 Through 7) Since Last Iteport.Give Reasons:

9. Power Level To Which itestricted.lf Any (Net MWe):

10. Itcasons For Restrictions.lf A..y.

~ This Month Yr to.Date Cumulative 744 3.622 _

55d87

11. 'llours in Ret 3rting' Period

12. Number Of Ilours Reactor Was Critical 69.1 1,942.1

,_ 39,110.8 _

0-0 0

13. Reactor Reserve Shutdown llours

.9 1,858.4 38,135'4 l

'14. Ilours Generator On Line 0

0 0

15. Unit itescrw Shutaown llours

_._LZM.,026 40.734.264

16. Cross Thermal Energy Generated (MWII) 2.198 24 931,189 16,333,876

17. Gross Electrical Energy Generated (MWil) 13 877,897.

15,289,934

18. Net Electrical Energy Generated.(MWil) 0 51.3%

68.7%

0 lo. Unit Service Factor 51.3%

68.7%

20. Unit Availability Factor 0

4_7.1%_

53.5%

21. Unit Capacity Factor (Using MDC Net) 0 45.0%

51.2%,

22. Unit Capacity Factor (Using DElt Net)

23. Unit Forced Outage Rate 95.9%,

3.1%

18.4%

24. Shutdowr scheduled Over Next 6 Months (Type.Date.and Duration of Eacht:

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

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Turb 5 Rating:

565.7 MWe Generator Rating:, 663.5 (MVA) x.90 (Power Factor) - 597 MWe

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AVERAGE DAILY UNIT POWER LEVEL

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.o 050-0331 DOCKET NO.

0 ane Arnold Ener u

UNIT Cente

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DATE June 15. 1981

.i J. Van Sickel COMPLETED BY 319-851-5611 TELEPilONE tMay, 1981

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DAY AVERAGE DAILY POWER' LEVEI.

DAY

' AVERAGE DAl',Y POWER LEVEL (MWe Net)

(MWe Natl

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-0 37 0

0 gg 2

3 39

. 0 0

0 0

4 20 0

O 21 5

O' 0

6 22 0

0 23

.7 0

0-24 8

'25 0

C 0

10 0

26 0

0 0

27 l

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0 28 0'

'12 0

0 13 29 0

0' 3o i

14 0'

0 31 15 0

16 INSTRUCTIONS On this format. list the average dsity unit power levelin MWe Net for each day in the reporting month. Compute to

'I the scarest whole megswatt.

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UNITSIIUTDOWN3 AND POWER REDUCTIONS DOCKET NO. 050-0331 A"nold Fnergy Ctr..*,'

UNIT NAME D'M ""

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DATE 1"r a 16 1441..

REPORT MONT11 Ma'/. 1981 TELEPIIONE 319-851-5611 3

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33' h-

,g.E Licensee

$3,

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,Cause & Corrective No.

Date y

3g j5 Event

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Action to g

$E j di g Report.r mO u

H Prevent Recurrence b.

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6.

[810521.:

S 722 C

1 Unit remained shutdown for a mainte-

.!i nance and refueling' outage. Startup was delayed by LLRT problems with MSIVs.

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I 17, 810531 F

21.1 A

1, 3 Unit was removed from the line due.

"C to indications of a main ste'am relief Q

valve pilot assembly passing steam.

Q During the shutdown the reactor M

. scrammed in the IRM range?

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F: Forced Reasen:

Method:

Exhibit G. Instructions S: Scheduled A-Equipment Falture(Explain) 1 Manual for Preparation of Dats

- r B Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG.

I' D Regulatory Restrictico 4 Other(Explain) 0161) l, E-Operator T aining & License Examination F Administrative 5

G Operational Error (Explain)

Exhibit I.Same Source

.j (9/77) li-Other (E.xplain) a s

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U50-0331

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.c Unit Duane' 6rnolTEnergy_tl.

Dat(' Y' ted by _ J. Van SicPel ne_.15d931 REFUELING INf0Rl1ATION Compl Telephone 319-851-5611 1.

Name of facility.

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Duane Arnold Energy Center.

2.

Scheduled date for next refueling shutdouq.

A' Fall, 1982

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Scheduled date fo.r restart following refueling.

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Unknown 4.

Will refueling or resumption of operation thercarter require a

~ technical specification change or other license anendment?

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Unknown i

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5.

Scheduled date(s) for submitti'ng proposed licensing action and nupporting information.

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N/A 6.

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

new or different fuel design or supplier, unrevicwed design or per-formance analysis inethods, significant changes in' fuel design, new y

operating procedures.

A.

. Unknown 7

The n' umber of fuel assemblics (a) in the core and (b) in the spent fuel storage pool.

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A'.. a ) 368.

b) 448 D.

The present licensed spent fuel pool storage capaci;./ and the size of any increase in licensed storage capacity that has been requested or is plcnned, in number of fuel acccmblies.

A? 205 9.

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

A.

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I Dock:t No. 050-0331 Unit Duane hrn ild En rgy C Date June 15, 1981 Completed by J. Van Sickel Telephone 319-851-561?.

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 5-1 At the beginning of the report period the plant was shutdown for refueling and maintenance with fuel loading in progress.

5-2 Core loading was completed at 1428 hours0.0165 days 0.397 hours 0.00236 weeks 5.43354e-4 months .

5-3 During a cora verification check, one fuel assembly was found misoriented.

The fuel assembly was reoriented to the proper position.

The moisture separator was installed in the reactor vessel ac 2215 hours0.0256 days 0.615 hours 0.00366 weeks 8.428075e-4 months .

5-6 The steam dryer was installed in the reactor vessel at 1412 hours0.0163 days 0.392 hours 0.00233 weeks 5.37266e-4 months .

The reactor vessel head was placed on the vessel at 1532 hours0.0177 days 0.426 hours 0.00253 weeks 5.82926e-4 months .

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5-8 The reactor vessel head studs were tensioned tt Od20 hours.

5-12 The drywell head was installed and the retaining studs torqued by 0559 hours0.00647 days 0.155 hours 9.242725e-4 weeks 2.126995e-4 months .

5-14 All reactcr cavity shield plugs were installed by 0415 hours0.0048 days 0.115 hours 6.861772e-4 weeks 1.579075e-4 months .

5-15 Controi Rod Drive (CRD) friction testing was begun.

5-18 CRD friction testing was completed at 0252 hours0.00292 days 0.07 hours 4.166667e-4 weeks 9.5886e-5 months .

5-19 Shutdown margin testing was begun at 0517 hours0.00598 days 0.144 hours 8.54828e-4 weeks 1.967185e-4 months . Shutdown margin testing was completed at 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months .

Work was begun to replace CRD 14-39 due to problems which were experienced J

during friction testing of the drive indicating overtravel.

5-20 CRD 14-39 was changed out and the replacement CRD exercised with satisfactory results.

Plant startup was delayed while naintenance was being performed on three MSIVs which had not yet passed LLRT.

5-25 All MSIVs had passed LLRT by 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i 5-26 Preparations for plant startup were begun.The reactor was critical at 2234 hours0.0259 days 0.621 hours 0.00369 weeks 8.50037e-4 months .

5-26 While shutdown for refueling it was determined that the Technical Spacification requirements for determining river water supply system pump TDH were not being met.

In addition, testing determined the pumps could deliver the required flow, but 3 of 4 pumps could not develop the required head.

R0 Report 81-019 e

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Dock:.t No. 050-0331 Unit Duane ArnoFd En rgi f

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Dat; Jun 15, 1981 Completed by J. Van Sickel Telephone 319-851-5611 l

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE

.5-27

.Dur'ng reactor startup, primary centainment was breached when both the inner and outer airlock doors were open simultaneously while an H/P Technician exited the drywell.

R0 Report 81-020 The reactor was shutdown due to an indication that the pilot assembly for main steam relief valve PSV-4400 was passing steam. The reactor was in cold shutdown at 2328 hours0.0269 days 0.647 hours 0.00385 weeks 8.85804e-4 months .

5-28 The pilot assembly on PSV-4400 was replaced and plant startup begun. The reactor was critical at 2115 hours0.0245 days 0.588 hours 0.0035 weeks 8.047575e-4 months .

5-29 A reactor scram occurred at 1612 hours0.0187 days 0.448 hours 0.00267 weeks 6.13366e-4 months while testing PSV 4402. When the valve closed a pressure spike caused an APRM trip.

5-30 The reactor was critical at 0308 hours0.00356 days 0.0856 hours 5.092593e-4 weeks 1.17194e-4 months .

5-31 The main generator was placed on the line at 0159 hours0.00184 days 0.0442 hours 2.628968e-4 weeks 6.04995e-5 months for testing. The generator was removed from the line at 0252 hours0.00292 days 0.07 hours 4.166667e-4 weeks 9.5886e-5 months . The reactor scrammed at 0608 hours0.00704 days 0.169 hours 0.00101 weeks 2.31344e-4 months from IRMs. The reactor was in cold shutdown at 1025 hours0.0119 days 0.285 hours 0.00169 weeks 3.900125e-4 months .

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I Unit c.,o, A*neld Eva*cv centti I

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Date Juna 15, 1981-1 /

o p eted by J. W n Sic W

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MAJOR SAFETY PELATED MAINTENANCE-

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'i DATE SYSTEM COM?0NENT DESCRIPTIOt 1

5-8-81 Containment Atmospheric V-43-109.

Replaced valve

-f Control s

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$- 12-81,

CRD.' Hydraulic HCU 06-11.,'02-23, 06-19 sod.10-39' Replace'd cartridge v '.ve

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Replaced. overload relay, overload relay '

5-13281 4SO Volt MCCs 1B4494 heatersandcontactsinbothStarters.'~.h

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SV-2081

' Replaced solenoid.yalve.

. i 5-17-81 ESW 5-18-81 Off-Gas. Rad Monitoring RM-4iO4, ',

Replaced detec, tor' Repla.ced coil in reverse contactor c.1 19-81

,480 Volt MCCs; 1B34-42 f

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Replac,ed high'. voltage; power supply..'-

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.5-21..8'1, Neutron Moni.toring I RM.. " B." '

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MOV".2316".

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Replaced handwheel stia'ft 5-22 81..

HPCI j

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. Nitrogen Syste,m CV;4.428; EV.4429 / j Installed riew.N R.egt.tlator

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5-23.-S1 '

RHR MOV-190i)

Replace'd, reverse starter.

j t 5-23-81 RHR -

CVi2002A.-

Replaced magneti'c switth

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'5-23-81 RHR M0V-2003A _

a Installed new d.is.k.:

Replaced cartridge' valve

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'5-25-81 CRD Hyd'raulic.

HCli O6-31 '

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.I 5-25-61 ERD.Hydratdid ~

30-11, 18-15; 18,39,.'10-31, 10-11, 14-15,

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'liC0 06-31',.38-19,.14-11, 34-39, 30-15, Replaced accumulator seals and "0." rings.

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34-23,' 22143, 22-03,126-23, and 38-31 5-25-81 CRD Hydraulic CRD S/N 4022, 3996, 4531 and.3979 Rebuilt CRD I

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5-26-81.

' Main Steam Isolations.and CV-4412 Replaced. limit switch.

ADS

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Docket No.

050-033)

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'.(N Unit Du*'m A eid Energp CeE t t

Date June 15. 1981

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Completed by J. Van Sickel MAJOR SAFETY RELATED MAINTEt!ANC.t Telephone 319 9 1 5s11 -

DATE SYSTEM CCM?ONENT DESCRIPTION 5-27-81 Main Steam Isolation and PSV 4400, 4401, 4402, 4405, 4406 and 4407 Removed, tested and reinstalled pilot ADS ~

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Main Steam Isolation and Safety Valve PSV-4403 Valve was removed, tested, overha'uled, 5-27-81

?.DS reset and reinstalled.

3,29-81 Main Steam Isolations and' PSV-4400' Pilo't assembly was replaced.

I' ADS

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ML20004F668

Text

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