ML20009C878

Monthly Operating Rept for June 1981

ML20009C878
Person / Time
Site:	Duane Arnold
Issue date:	07/14/1981
From:	Van Sickel J IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20009C877	List: ML20009C876 ML20009C878
References
NUDOCS 8107220091
Download: ML20009C878 (7)

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OPERATING DATA REPORT DOCKET NO. 050 0111 DATE Ja;1 COMPLETED fly J 9Van y Sickel 14 981-TELEPl!ONE 314-R51-5611 ~

OPERATING STATUS -

Duane Arnold Enern,y. Center Notes

1. Unit Name:

2. Repbrting Period: June, 1981,

3. Licens-d Thermal Power (MWt): 1658

• 4. Nameplate Rating (G..sss MWe): 565 (T ebine Rating)

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

6. Maximum Dependable Capacity (Gross MWe): 545

7. Maximum Dependable Capacity (Net MWe): 615

8. If Changes Occur in Capacity Ratingi(Items Number 3 Through '/) Since Last Report.Give Reasons:

9. Po xer Level To Which Restricted,If Any (Net .\"Ve):

10. Reasons 7r or Restrictions,1f Any:

' This Month . Yr to.Date Cumulative II. Hours in Reporting Pedod 720 4343 56.207

12. Number Of Hours Reactor Was Critical 571.5 2515.6 39,682.3

13. Reactor Resene Shutdown Hours --

0 0 0

'14. Ilours Generator On-Line 522.5 2380.9 38,657.9 .

15. Et Reserve Shutdown Hours 0 0 0 l 16. Gross wrmal En:rgy Generated (MWH) 503.820 4.239.446 49.238.084 -

l 17. Gross Electrical Energy Generated (MWH) 167,510 _ _ ,

1,098,699 16.501,386 l

18. Net Electrical Energy Generated.(MWH) 155,257 1,043,154 15,445,192

19. Unit Semce Factor 72.6% 54.8% _

6*.8%

f 20. Unit Availability Factor 72.6% 54.8% 68.8%

l 21.-Unit Capacity Factor (Using MDC Net) '

._ _41.9%

• i,6. 6 %. 53. 4,%

40.1%

l 22. Unit Capacity Factor (U4ng DER Net) 44.6% 51.1%

l 23. Unit Forced Outage Rate 18.7% 7.0% -1 13 . 4 %

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

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

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• Turbine Rating: 565.7 MWe *

Generator Rating,

;663.5 (MVA) x .90 (Power Factor) = 597 MWe , , .

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4 AERACE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 UNIT Duane Arnold Ene .

DATE Inly 14 1981 COMPLETED BY J. Van Sickel

. TELEl'ilONE _319-311.-5611 MONTI{ June .,19 R1 DAY AVERAGE DAILY POWER LEVEL DAY ^ AVER AGE DAILY POWER LEVEL (MWe Net) (MWe Net)

> 1 0 .

17 0 2 64 18 175 3

8 259

.__ . 39 4 0 20 253 __

s . 0 21 339 6 91 22 3RR

, ,7 182 23 380

( 8 299 24 319 l 9 81 '25 323 l 10 271' 26 334

~ 11 337 27 297-

12 402 - - -

28 319

$ 13 '420 ._ p 381

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g 242 272 34 30 s

15 5 33 j 16 'O i .

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h INSBUCTIONS j- On this format, list the averag; daily unit power levelin MWe-Net for each day in the reporting month. Compute to 1 the nearest whole megawatt.

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1 UNITSIlUTDOWNS AND POWER REDUCTIONS DOCKET NO. 0-0-0111 -

UNITr .uiE nuanci a,-nnla crergy Ctr .i

, DATE 1"1v 14 14R1 COMPLETED BY - LVpri $1ckel

• REPORT MONT11 .1n n o . 14R1 TELEPl!ONE 319-V 1-%11 . ,

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-, .! ? 3i; }.c.55 js Licensee E%  % ,Cause & Co:rective ba. Date y 3 ES, Event l'8 pu Action to .

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fEi 2 j di g Report # mO. g Prevent Recurrence 6 -

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7. '810531 F. 27.2 A 1,3 Continuation of previous shutdown to j

. replace a relief valve pilot assembly  ;

1 81-021 'l

8. 810603 F 75.4 A 1,3 SA VALV0P Power was reduced arid the unit taken -

off line due to problems with a dry-

, well to torus vacuum breaker. Reactor ~

scrarmied in the IRM range. g

9. 810608 S 0 H 4 Power was reduced to perform. control rod witiidrawals .

10. 810609 F 17.4 A 3 Reactor s' crammed from a trip of the. -

"B" RPS M-G set

11. 810614 S 0 F 4 Power'was reduced to perform special f test procedure #91, R/V te.,ts -

I 2 3 4 F: Forced Reason: Method: Exhibn G. Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Dats .

B Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee r C Refueling 3 Automatic Scram. Event Report (LER) File (NUREG. I D Regularory Restriction 4-O!her (Explain) 0161)

E-Operator Training & Liecase Exam! stion l F-Administrative 5 G-Operational Error (Explain) Exhibit I Same Source (9/77) 11 Other (Explain) +

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UNITS!!UTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-0331 ,

UNIT NAME Duane Arnnld Fndtgy Ctr

• DATE 1"l v 14- 14A1 REPORT MON 111 June. 1981 COMPLETED BY J Van sirkel 't ,

TELEPl!ONE 319-RR1-5611 ', -

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". .2 _:: 3- .o ,5 M Licensee gto 3 c "o ,Cause & Corrective No. Da:e g is g g ,gg5 Event u? E.'o

• aciior to c$ 5 5 Report # N0 jig Q -

f' Prevent Recurrence 12.

e I 810615 S 77.5 F 1,3 Unit was 'taken off line for a drywell  !

inspection followinig SpTP #91. Reactor scrammed in the IRM range i

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13. 810630 S 0 F 4.

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Power was reduced du.e to lack of system demand i

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I 2 3 4 F: Forced Reason:

• Method: -

Exhibit G-instructions '

S: Scheduled A Equirment Failure (Explain) 1-Manual for Preparation of Data B-Main:enance of Test 2 Manual Scram. .

C. Refueling Entry Sheets for Licensee 3 Aufomatic Scram. -  !

D Regulatory Restriction Event Repor (LER) File (NUREG- I 4-Other (Explain) 0161)

E-Operator Training & License Examination l F Administrative i.

5 8 G Operational Error (Explain) ,

(9/77) 11-0 her(Explain) Exhib;t i San e Source  !

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U6cKet no. 0S0-0331

. Unit Duane Arnold Energy fci REFUfLING INf0Rf1ATION Late July __14. E81 Completed by _). Van Sickel Telephone 319-851-5611

1. Name of facility. <

A. Jane Arnold Energy Center

2. Scheduled date for next refueliig shutdown.

Ac Fall, 1982 . .

3. Scheduled date for rt tart following refueling.

-A. Unknown .

. 4. Will refueling or resumption of operation thercafter require a technical specification change or other license amendment?

A. Yes. Nen MAPLHGR tables will have to be included in Technical Specifications.

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

l A. Unknown ct this time.

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

new or different fuel design or supplier, unreviewed design or per-formance analysis methods, significant changes in' fuel design, new operating procedures.

A. ew ft.1 assemblies to be placed in the reactor wil.1 Se more highly enriched.than those^ currently in use. , .

7. The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool.

A. a) 368 b) 44'8' O. The present licensed spent fuel pool stornga capacity and the size of any increase in licensed storage capacity that has been requested

. or is planned, in number of fuel assemblics. .

A. 2050 .

9. The projected date of the last refueling that coa be discharged to the spent fuel pool assuming the present licensed capacity.

A. 1998 '

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Docket No. 050-0331 I Unit Duane Xil.old Energy Crnig Date July 14, 1981 7

. Completed by J. Van Sickel 1 Telephone 319-851-5611

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l NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 6-1 At the beginning of the report period the plant was in cold shutdown to allow replacement of the pilot assembly on relief valve PSV-4406.

Work was cc.npleted and a reactor startup was begun. The reactor was critical at 1454 hours0.0168 days <br />0.404 hours <br />0.0024 weeks <br />5.53247e-4 months <br />.

6-2 The main generator es placed on the line at C312 hours.

During reactor startup suppression cha aber to drywell vacuum breaker, CV-4327H, did not close after torus inerting.

R0 Report 81-021 6-3 Due to the problem with CV-4327H a plant shutdown was begun. The generator was removed from the line at 0332 hours0.00384 days <br />0.0922 hours <br />5.489418e-4 weeks <br />1.26326e-4 months <br />. A reactor scram occurred at 0503 hours0.00582 days <br />0.14 hours <br />8.316799e-4 weeks <br />1.913915e-4 months <br /> while ranging IRM switches.

The reactor was in cold shutdown at 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br />. Repairs were completed and reactor startup was begun at 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br />.

6-4 The reactor was critical at 0205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br />. During a drywell inspection the pilot assembly on relief valve PSV 4406 was -found leaking steam.

A reactor shutdown was begun. All control rods were inserted by 1325 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.041625e-4 months <br />. The reactor was in cold shutdown at 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br />.

6-5 Reactor startup was begun. The reactor was critical at 2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br />.

6-6 The main generator was placed on the line at 0655 hours0.00758 days <br />0.182 hours <br />0.00108 weeks <br />2.492275e-4 months <br />.

6-7 During surveillance testing the RCIC turbine repeatedly tripped due to .

overspeed on fast starts.

R0 Report 81 022 A control rod sequence exchange was completed between 1645 and 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br />.

6-9 Power was reduced in order to perform control rod withdrawals. Rod withdrawals were completed at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> and a power increase begun.

6-9 A reactor scram occurred at 0757 hours0.00876 days <br />0.21 hours <br />0.00125 weeks <br />2.880385e-4 months <br /> due to the trip of the "B" RPS M-G set. A drywell entry was made in an effort to find the source of a nitrogen leak in the drywell. The leak was found on the actuator for the "A" feedwater checkvalve. The leak was repaired and preparations for plant startup were begun. The reactor was critical at 2123 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.078015e-4 months <br />.

6-10 The main generator was placed on the line at 0123 hours0.00142 days <br />0.0342 hours <br />2.03373e-4 weeks <br />4.68015e-5 months <br /> and a power increase was begun.

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Dock:t No. C M-0331 Unit Duana Irnold Energy Center

. Date July 14, 1981 Completed by J. Van Sickel Telephone 319-851-5611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 6-11 During surveillance testing RCIC rteam line high flow PDIS 2442 tripped at 100 inches of water. The required setpuint is 110 5 inches.

R0 Report 81-023 6-13 The plant was operating at 448 MWe at 2235 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.504175e-4 months <br />.

6-14 Power was reduced in praparation for performance of Special Tes:

Procedure (SpTP) #91.

SpTP #91 was begun at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />. The test involved cycling a main steam relief valve several times and maasuring the resulting suppression chamber loadinn.

6-15 SpTP #91 was completed at 0007 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. A plant shutdown for inspection of the drywell was in progress. The generator was removed from the line at 0307 hours0.00355 days <br />0.0853 hours <br />5.076058e-4 weeks <br />1.168135e-4 months <br />. A reactor scram occurred at 0342 hours0.00396 days <br />0.095 hours <br />5.654762e-4 weeks <br />1.30131e-4 months <br />. The reactor was ir. cold shutdan at 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br />.

While the plant was shutdown it was determined that the "B" c'ontainment radiation monitor was running with no sample point selected. In addi-tion the "A" containment particulate radiation element, RE-8101A, was inoperable.

R0 Report 81-026 6-16 During surveillance testing, drywell equipment drain line (containment isolation) valve CV-3729 did not give a fully closed indication.

R0 Report 81-024 During surveiliance testing the "B" RHR service water pump, IP-22B, did not develop the required discharge pressure u rated flow.

R0 Deport 81-025 Plant stortup was delayed when an inspection revealed a leak in the body of RrIC test valve MOV 2515.

6-17 An engineering evaluation of MOV-2515 determined the valve was acceptable for plant operation as long as the valve was maintained in the closed position. Plans for replacing the valve were initiated.

Reactor tartup was begun at 2302 hours0.0266 days <br />0.639 hours <br />0.00381 weeks <br />8.75911e-4 months <br />.

6-18 The reactor was critical at 0002 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The main generator was placed on the line at 0858 hours0.00993 days <br />0.238 hours <br />0.00142 weeks <br />3.26469e-4 months <br /> and a power increase begun. Power was held at approximately 50% to allow for work on a flange leak on the "B" reactor feed pump.

Docket No. 050-0331 Unit Duane Arnold Energy Center Date Lu]y 14, 1981

. Cnmpleted by J. Van Sickel Telephone 319-?,51-5611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 6-20 During normal operation off gas system radiation monitor RM 4101A failed upscale.

R0 Report Pending lepairs to the "B" reactor feed pump were completed and a power increase was begun.

6-23 The plant was operating at 426 MWe. Power changes were being made in respon:e to system power demands.

6-30 The plant was operating at 338 MWe at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> and following load as directed by the system cont ol center.

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Docko' No, 050-0331 '

,) 1 UnitDaann Arnold Erorev Centet  !

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Date July 14, 1981 ';

P t y a" MAJOR SAFETY RELATED MAINTENANCE ep o 9 g g_ 56 -

l DATE SYSTEM COMPONENT DESC^UPTION ,

6-1-81 RHR PS-1925B Replacer actuating lever 6-7-81 CRD Hydraulic Co'ntrol Rod 26-15, 38-27, 26-31, 34-23 Replacep drive 6-8 CRD Hydraulic Control Rod 14-15, 22-39, 10-27, 10-35, Replaced drive 02-23 -

6-8-31 Containment AN-8181B - Installed new chemicals

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Atmoso. here Contral 6-11-81 Main Steam- PSh-4406 Replaced. pilot. assembly ")

Isolations and ADS i - .

6-15,-81 Control Building RE-6101A Installed new' detector Area Rad Monitor - . ,

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Installed new chemicals 6-T5 Containment AN-8181A Atsuspheric ' Control ..

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Replaced solenoid valve

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'6-17-81 Primary Containment SV-3729 ,.'

6-18-81 , Neutron' Monitoring 'IRM "C" Replaced detecto.r

. 6-18-81 Main Steam PSV 4405 Replaced pilot assembly Isolation & ADS , ,

Installed new chemicals 6-22-81 Containment AN-8181B.  ?

Atmospheric Con't rol 6-22-81 Drywell- Radiation RE-8101B Replaced detector. -

Monitors .

6-22-81 CRD-Electrical Relay C11-K1 Replaced' relay i

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6-26-81 Containment AN-8181A. Installed new chemicals ,,

t Atmospheric Control ,,,

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