Text

Monthly Operating Rept for Feb 1982
	ML20041G375
Person / Time
Site:	Duane Arnold
Issue date:	03/12/1982
From:	Brown S; IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	;
Shared Package
ML20041G373	List: ML20041G372; ML20041G375;
References
	NUDOCS 8203220156
	Download: ML20041G375 (8)
	v • d • e

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e OPERATING DATA REPOP.T DOCKET NO. 050-0331 DATE March if 1982 t

COMPLETED 11Y.S_idney_15611-L. Brown TELEPl!ONE 319-851 OPERATING STATUS I. Unit Name:

Duane Arnold Eneroy Center Notes

2. Re;iorting Period:

February, 1982

3. Licensed Thermal Power (MWt):

1658

4. Nameplate Rating (Gross MWe): 565 (Turbine Rating)-

5. Design Electrical Rating (Net MWe): " 538 545

6. Maximum Dependable Capacity (Gror.s MWe):

7. Maximum Dependable Capacity (Nct MWe):

515

8. If Changes Occur in Capacity Rating (Items Number 3 Through 7) Since Last Report. Give Reasons:

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

10. Reasons For Restrictions.If Any:

' This Month

- Yr.-to-Date Cumulative "i

672 1,416

-62,040

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 672 l',416

'44,894.7

13. Reactor Reserve Shutdown llours 0

0 0-672 1;416 43,805.4

~14. Ilours Generator On-Line

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Ge' emted (MWH) 1,031,146 2,002,899 55,056,297

17. Gross Electrics! Energy Generated (MWH) 744 f14 674;476 18.454.515

18. Net Electrical Energy Generated.(MWH) 329,880..

641,183 17,272,769

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19. Unit Service Factor 100%

100%"

70.6%

20. Unit Availability Factor 100%

100%

70.6%

21. Unit Capacity Factor (Using MDC Net) 95.3%~

87.9%

54.1%

91.2%

84.21, 51.77

22. Unit Capacity Factor (Using DER Net) l

23. Unit Forced Outage Rate :

0 0

16.7%

24. Shutdowns Selieduled Over Next 6 Months (Type. Date.and Duration of Eachl:

Maintenance; April 1, 1982; two weeks i

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

Turbine Rating:

565.7 MWe i

Generator Rating:

663.5 (MVA) x.90 (Power Factor) = 597 MWe 1

8203220156 820312 PDR ADDCK 05000331 R

PDR

. (q77)

e AVERAGE DAILY UNIT POWER LEVEL 050-0331

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DOCKET NO.

uuane arnoio UNIT Enerav Center DATE Narch 12. 1182 COMPLETED BY Sidney L. Brown TELEPilONE 314-A51-5611 MONT!!

Februa rv. 1982 DAY AVERAGE DAILY POWEl[ LEVEL DAY

' AVERAGE DAILY POWER LEVEL (MWe-Net)

(y we.Ne,,

I 506 17 509

~'

502 505 2

., 3 3

507 39 510 509 479 4

20 506 494 5

21 6

4' 77 22 503 7

481 500 23

'~

494 506 8

x 9

508 25 311 507-414 10 26

'1I 499

499 27 504 506 12 --

28

'509 33 14 505 30 494 15 33 16

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ll INSTRUCTIONS On this forrnat. list the average daily unit power lesciin MWe Net for each day in the reporting month. Compute to

t the ricatest whole owgawatt.

(9/771

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050-0331 UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNITNAME uuane arnoic Ener9f Centej DATE Marcn le, 1i.82 COMPLETED DY S i CDeY l. D rc',,7 REPORT MONT!! Februa ry. go7 TELEPi!ONE 310-851-5611

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.E Licensee

,E,%

h1, Cause & Corre,,iive No.

Date i

5g n

jjs Event g

Q Action to H

$E 5

I@g Report :

mO Prevent Recurrence o

o c

3 820225 F

0 A

4 LER 82-015 CF VALV0P Worn stem nut.cn the "B" RHR SW A

M0V 1947 prevented valve operation.

This resulted in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LC0 and

[

a forced, power reduction because the "B" containment spray system was compromised and the "A" RHR system had previously been declared inoperable. The forced power reduction ended 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months into the l

24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LC0 after the "A" RHR 4

system was made operable. The stem l

nut on MOV-1947 was replaced and j

satisfactorily tested.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructiens S: Scheduted A Equipment F:ilure(Exp! sin) 1-Manu:1 for Prep: ration of Dats B-Maintenance oi Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Autematic Scram.

Event Report (LER) File (NUREG-l D Regu! story Restriction 4-Other (Explsin) 0161)

E Orcu:or Training & Ueense Exam! nation F

F Administrative 5

G-Op:m:ienal Errer (Explain)

Exhibit I 5:me Sourec (9/77)

Il-Othtr (Espisin)

I O

A

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ucci:et to.

050-0331 Unit. Duane Xi~nolTEnergy~(i a e hW 82 REFUELING INfultitATION Completed by 3, t Brown

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' Telephone 319-tisl !ggi 1.

Name of facility.

A.

Duane Arnold Energy Center 2.

Scheduled date for next refueling shutdown.

A.

September 4,1982 3.

Scheduled date for restart following refueling.

A.

Unknown 4.

Will refueling or renumption of operation thercafter require a technical cpecification change or other license amend, ment?

A.

Yes.

New'MAPLilGR tables will have to be included in Technical Specifications.

5.

Scheduled date(c) for submitting proposed licensing action and nupporting information.

? A.

Unknown at this time.

6.

Important licencing considerations accociated with refueling, e.g.,

new or different fuel desig:. or supplier, unrevicued design or per-formance analynin methods, significant changes in' fuel design, new operating procedures.

A.

New fuel assemblies to be placed in itic reactor will be more highly enriched than those currently in use.

7.

The numbar of fuel assemblien (a) in the core and (b) in the npent fuel storage pool.

A.

a) 368 b) 448' O.

lhe present licensed opent fuel pool storage capacity and the cize of any increase in licensed storage capacity that has been requented or in planned, in number of fuel accemblien.

A.

2050 9.

The projected date of the last refueling that can be diocharged to the opent fuel pool assuming the present licensed capacity.

A.

1998 e

I t I

i A

Docket No. 055-0331 Unit Duane Arnold Energy Ctr Date March 12, 1982 Completed by Sidney L. Brown Telephone 319-851-561(

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 2-1 At the beginning of this reporting period, the plant was operating at 511 MWe.

2-4 During a normal operation surveillance test, RCIC injection valve, MOV 2512, was opened and would not close. The valve was repaired by replacing the motor operator circuit breaker close contactor coil.

R0 Report 82-007 2-5 During normal operation while moving new fuel through the opened outer reactor building railroad airlock door, the inner railroad airlock personnel door was inadvertently opened, violating secondary containment integrity. A defective solenoid was replaced, the interlock design will be reviewed, and personnel will be instructed about secondary containment requirements.

R0 Report 82-009 2-6 During normal operations, the 'B' oxygen analyzer for the containment atmosphere dilution system was reading upscale. The analyzer was repaired by retightening a connection.

R0 Report 82-010 2-8 During normal operation, a self-cleaning strainer 1S-85B on the suction line to the

'B' screen wash pump for the river water supply system became plugged.

The plugged strainer was cleared and a failed strainer shear pin replaced.

R0 Report 82-011 During normal operation while performing surveillance. testing, the main steam isolation valve leakage control system bypass valve, MOV-8403C, opened but failed to close. The fault was caused by a failed motor starter contactor coil auxiliary switch which was replaced.

R0 Report 82-012 2-14 New fuel arrived on site.

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4 Docket No. 055-0331 Unit Duane Arnold _tnergy Ctr Date March 12, 1982 Completed by Sidney L. Brown Telephone 319-851-5611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 2-15 During normal operation, control building isolation damper, IV-AD-31A, was stuck open. The damper was shut, but it was determined that it would not automatically close if isolation was required.

R0 Report Pending 2-19 During normal operation, the f ailures of one snubber, GBB-4-SS-211 and one hanger on the 'A' RilR discharge line were identified.

R0 Report Pending 2-20 During normal operation, snubber GBB-3-SS-235 on the 'B' RHR system was removed from service for testing af ter it was identified that the pipe clamp was rotated and the snubber extension was bent. The snubber was replaced and the pipe clamp properly positioned.

R0 Report 82-013 2-21 During normal operations, the torus level transmitter, LT-4363, started behaving erratically.

R0 Report Pending 2-24 During a normal operation surveillance test RHR service water valve M0V-1947 f ailed to close. The valve stem nut and gaskets were replaced which corrected the problem.

R0 Report 82-015 2-25 During a normal operation surveillance test, the main steam high temperature switch would not trip.

R0 Report Pending 2-28 The plant was operating at 528 MWe at 2253 hours0.0261 days 0.626 hours 0.00373 weeks 8.572665e-4 months .

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Docket Pio.

050-0331 Unit Duane Arnoia tnercy center

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Date Marcn 12c 1952 MAJOR SAFETY RELATED MAINTENANCE Conpleted by Stoney L. Brown Telephone 319-851-5611 I

SYSTEM COMPONENT DESCRIPTION DATE 2-4-82 RCIC MOV-2512 Replaced motor operator circuit breaker close contactor coil 2-5-82 Containment Atmosphere Control SV 8105A, SV 8105B and SV 8102B I Disassembled, inspected and reassembled 1

1 2-5-82 Primary Containment LR 4385 (B Torus level indicator)

Calibrated and re-installed l 2-8-82 MSIV-LCS MOV-8403C I Replaced auxiliary switch I

I l2-11-82 River Water Supply IS-85B (Strainer for screen wash Replaced shear pin and cleaned strainer pump)

I l Replaced snubber 2-20-82 RHR Snubber GBB-3-SS-235 2-23-82 Control Bldg. H&V RE 6101A ( Air intake monitor) l Lubricated l

l 2-23-82 Containment Atmosphere Control RE 8102B (Gaseous Monitor)

Replaced tube I

!i 2-23-82 Containment Atmosphere Control RE 8103A (Iodine Monitor)

Replaced detector i

2-26-82 RHR I GBB-5-H-18 Hanger Clamp Repositioned clamp 2-26-82 RHR GBB-5-SR-130 Clamp y Repositioned clamp Retorqued bolts i 2-26-82 RHR GBB-4-H-20D Pipe Support 2-26-82 RHR GBB 4-SS-216 Snubber Support Retorqued bolts 2-26-82 RHR GBB-5-SS-215 Pipe Hanger Retorqued bolts and repositioned clamp l 2-26-82 RHR GBB-4-SS-211 Snubber Support Replaced snubber support i

2-26-82 RHR GBB-3-SS-237 & 238 Pipe Clamp Clamp inspected and realigned t

2-26-82 RHR GBB-4-SS-213 Pipe Clamp Repositioned I

DockGt No.

050-0331 Unit Duane Arnold Energy Center Date Marcn 12, 1982 MAJOR SAFETY RELATED MAINTENANCE Completed by sidney L. Brofn Telephone 319-651-5611 DATE SYSTEM l

COMPONENT DESCRIPTION GBB-4-H7 Pipe Hanger Repositioned support 2-26-82 RHR 2-26-82 RHR GBB-4-H7, GBB-4-H200, GBB-4-H4, Adjusted hangers GBB-4-H10, GBB-4-Hil, GBB-4-H12, GBB-4-H13, GLE-7-H14, GBB-5-H18 and DBB-1-H20A Pipe Hangers 2-26-82 RHR Cooling Water MOV-1947 Replaced stem nut and gaskets

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ML20041G375

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