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Monthly Operating Rept for Jan 1986
	ML20153C710
Person / Time
Site:	Duane Arnold
Issue date:	01/31/1986
From:	Mineck D, Bernard Thomas; IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	DAEC-86-0120, DAEC-86-120, NUDOCS 8602210540
	Download: ML20153C710 (8)
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(PERQTI PG [MTA REPORT 1

DOCKET PO. 050-0331 DATE 02-I 5-86 COMPLETED BY Bradford % Thomas TEL EPHOPE 319-8 51-7309 1

OPERtTI PG STATUS i

Petes

1. Unit Peme Duane Arnold Energy Center c

2. Reporting Period January. 1986

3. Licensed Thermal Power (MWt):

I6 58

4. heeplate Rating -(&oss Pete):

565 (Turbine) r

5. Design Electrical Rating ( ht MWe):

538

6. Maximum Dependable Capacity (Gross MWe):

54 5

7. Maximum Dependable Capacity ( ht MWe):

51 5 5

8. If Changes Occur in Capacity Ratings (Items kmber 3 Through 7) Since the Last Report, Give Reasonst i

9. Power Level to which Restricted, if Any ( ht MWe):

10. Reasons For Restrictions, if Any:

1 i

This Month Yr-to-Dat e Cumulative I

744.0 744.0 96432.0 f

11. murs in Reporting Period 744. 0 744. 0 68065.9

12. haber of ' Hours Reactor Was Critical 0

0 1 50.3

13. Resctor Reserve Shutdown Hours 74 4. 0 744. 0 66303.5

14. Nurs Generator On-Line 0

0 0

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15. Unit Reserve Shutdown Hours 82190 8T190 834 58424 f

I6. Gross Thermal Energy Generated (MWH) 29 1212 291/1?

2794 7273 l

17. Gross Electrical Energy Generated (MWH) 272830 272830 26169467

18. Mt Electrical Energy Generated (MWH) 100.0 100.0 68.8

19. Unit Service Factor 100.0 100.0 68.8 l

20. Unit Availability Factor 7f 2 71.2 T.7

21. Unit Capacity Factor (Using MOC Net) 68.2 68.2 50.4

22. Unit Capacity Factor (Using DER ht) 0 0

15.8

23. Unit Forced Outage Rate

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

Inspections An approximately one and one-half week outage to perfor m annual surveillance tests and 1

i scheduled for mid-March 1986 WA

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

1 (9/77) 8602210540 860131 PDR ADOCK 05000331 PDR,

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r-AVERAGE DAILY UNIT POWER LEVEL DOCKET PC. 050-0331

' UNIT Duane Arnold Energy Center DATE 02-15-86 COMPLETED BY Bradford N, Thoms TELEPHD E 319-851-7309 MONTH January, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAE DALLY POWER LEVEL (MWe-Net)

(MWe-Net )

1 415 17 339 2

430 18 2 57 3

442 19 323 4

420 20 34 0 5

4 17 21 34 1 6

420 22 32 7

366 23 34 3 8

342 24 34 6 9

3 50 25 34 7 10 34 7 26 368 11 34 8 27 426 12 34 6 28 417 13 34 5 29 39 3 14 34 7 30 377 15 34 5 31 376 16 346 I NSTRUCTIONS On this format, list the overage daily unit power level in MWe-ht for each day In the reporting ponth. Compute 9he nearest whole megawatt.

(9/77)

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.,.n Docket No. 050-0331 Unit Nome Duane Arnold Energy Center Dato 02-15-86 MAJOR / SAFETY R EL AT E D M A I NTE NA NCE Completed by Bradford N.

Thomas Telephone 319-851-7309 DATE SYSTEM COMPO NE NT DESCRIPTION 01/01/86 Diesel Fire Pump Pump Turbocharger Replaced turbocharger 01/04/86 Transverse incore Probe (TIP)

TIP

'C' Ball Valve Installed additional ball valve I/ 04 / 8 6 (LER 86-03) 01/14/86 Co n t a i n m e n t Atmosphere Monitoring

'B' H202 Analyzer Sample Pump Replaced pump motor (LER 86-02)

System (CAMS) f 01/14/86 Core Spray

'B' Water Supply isolation Repacked valve valve (BM-I S V-214 6 )

/

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I i

1 t

Docket No. 050-0331 Unit.Peme Duane Arnold Energy Center Date 02-IS-86 Completed by Bradford N.

Thomas Telephone 319-851-7309 1

R E F U E L I NG I NFORM AT I O N 1

Na me of facility.

A.

Duane Arnold Energy Center 2

Scheduled date for next refueling shutdown.

A.

February, 1987 3.

Scheduled date for restart following refueling.

A.

April, 1987 3

j 4

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

I i

-A.

No n e currently identitled 5

Scheduled date(s) for submitting proposed licensing action and a

supporting information, i

A.

No n e currently identified 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, i

j No n e l

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

A.

al 368 b) 696 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 j

planned, in number of fuel assemblies.

i A.

2050 4

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

4 A.

1998 1

i

<j 1

a 4

.y-..-,m.,

m, m-..

,-.,_. __,,,., m m

-m-.-.,

Docket No. 05C-0331 Unit Na m e Duane Arnold Energy Center Date 02-15-86 Completed by Bradford N.

Thomas Telephone 319-851-7309 NARR A TI VE

SUMMARY

OF OPER ATI NG EXPER I E hCE 01/01/85 The plant was in normal power operation with 415 MWe (not) going out to the grid with power limited to stay within utility fuel burn goals.

The plant was in day 2 of a 7 day LCO for repairs to the diesel fire pump.

01/03/86 At 174 0 hours0 days 0 hours 0 weeks 0 months the diesel fire pump was declared operable and the LCO was terminated after repairs to the turbocharger unit were completed.

01/04/86 A new

'C' TlP ball valve was installed further away from containment than the existing valve when the existing valve nas determined to be sticking partially open.

(LER 86-03) 01/09/86 At 0539 hours0.00624 days 0.15 hours 8.912037e-4 weeks 2.050895e-4 months a 30 day LCO was entered when the

'A' Main Steam isolation Valve - Leakage Control System (MSIV-LCS) was determined to be Inoperable when the

'A' bleed flow control valve gave an intermediate position signal while in the closed position.

A faulty torque switch was replaced and the system was returned to service after successful post-maintenance testing.

The LCO was terminated on 1/18/86 at 1722 hours0.0199 days 0.478 hours 0.00285 weeks 6.55221e-4 months .

02) train was declared inoperable 01/14/86 At 1306 hours0.0151 days 0.363 hours 0.00216 weeks 4.96933e-4 months the

'B' hydrogen oxygen (H2 when removed from service for replacement of the sample pump and motor.

A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO and Unusual Event were entered due to the

'A' train already being inoperable.

The LCO and unusual Event were terminated when the

'B' train was returned to service at 19 0 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months s.

(LER 86-02) 01/15/86 At 1004 hours0.0116 days 0.279 hours 0.00166 weeks 3.82022e-4 months a 30 day LCO was entered when a reactor coolant conductivity monitor was removed from service to replace a conductivity indicating transmitter gauge.

Repairs were made and the system aas returned to service at 1440 hours0.0167 days 0.4 hours 0.00238 weeks 5.4792e-4 months thus ending the LCO.

At 1556 hours0.018 days 0.432 hours 0.00257 weeks 5.92058e-4 months the CO2 system was declared inoperable due to a leak at the manual / automatic actuating valve.

A 14 day LCO was commenced and a firewatch was established.

Repairs were made and the LCO was terminated on 01/16/86 at 2027 hours0.0235 days 0.563 hours 0.00335 weeks 7.712735e-4 months when the system was returned to service.

AT 1631 hours0.0189 days 0.453 hours 0.0027 weeks 6.205955e-4 months the

'B' core spray was declared inoperable and a 7 day LCO was entered when the s8' pump suction valve failed to close consistently during surveillance tests.

A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO and unusual Event were entered on 01/16/86 at 1546 hours0.0179 days 0.429 hours 0.00256 weeks 5.88253e-4 months when apparent high vibration readings on the

'A' core spray pump led to its being declared inoperable.

The

'B' suction valve was repacked and was returned to service at 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months thus ending the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO and Unusual Event (see 1/21/86).

The

'A' pump was still considered inoperable due to unexplained vibration and the 7 day LCO continued.

The

'A' core spray system was kept in its operable lineup until the pump seal was disassembled the following day.

01/18/86 At 012 0 hours0 days 0 hours 0 weeks 0 months power was reduced to approximately 405 to allow a control rod sequence exchange.

At 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months on 01/19/86 a reactor power increase was commenced.

Docket No. 050-0331 Unit Na m e Duane Arnold Energy Center Date 02-15-86 Completed by Bradford N.

Thomas Telephone 319-851-7309 NARR A T I VE

SUMMARY

OF OPER A TI NG EXPER I E hCE (Continued) 01/21/86 At 2244 hours0.026 days 0.623 hours 0.00371 weeks 8.53842e-4 months , with the help from pump mantfacturer and vibration specialist personnel, it was determined the

'A' core spray pump was opera bl e, thus ending the 7 day LCO.

The apparent high vibration readings were determined not to be tne result of excessive pump vlbration and pump seal and suction pipe disassembly revealed no operability concerns.

Therefore, the

'A' core spray system was operable as well on 1/15/86 mhen the

'B' system was inoperable.

At 0801 hours0.00927 days 0.223 hours 0.00132 weeks 3.047805e-4 months a 7 day LCO was entered when the

'B' Standby Gas Treatment (S8GT) system was removed from service to perform an annual deluge test.

The LCO was terminated when the system was returned to service at 1319 hours0.0153 days 0.366 hours 0.00218 weeks 5.018795e-4 months .

At 1912 hours0.0221 days 0.531 hours 0.00316 weeks 7.27516e-4 months a 7 day LCO was entered when the diesel fire pump was secured due to an oil leak.

Repairs were made and the pump was returned to service on 01/24/86 at 1627 hours0.0188 days 0.452 hours 0.00269 weeks 6.190735e-4 months thus ending the LCO.

01/22/86 At 0603 hours0.00698 days 0.168 hours 9.970238e-4 weeks 2.294415e-4 months the

'A' Standby Filter Unit (SFU) auto-Initleted as a result of low Inlet air temperature.

An inoperable Inlet air preheat coll had been covered with plastic to prevent cold air flow into the plenum.

Control personnel were not notified that the system was ready to be placed in service and didn't recover the coil with plastic.

Cold air passing by the out of service coil caused SFU Initiation.

The SFU was returned to standby and the preheat coil returned to service the same day.

(LER 86-01)

At 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months the

'A

' SBGT was removed from service to perform an annual deluge test.

A 7 day LCO was entered.

The system was returned to service at 1006 hours0.0116 days 0.279 hours 0.00166 weeks 3.82783e-4 months thus ending the LCO.

01/31/86 At the end of the month, the plant was operating at 376 MWe (not).

As of January 31st, the plant had operated conti.nuously for 19 2 d a y s.

l

Iowa Electric Light and Ibwer Company February 15, 1986 DAEC-86-0120 Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attn: Document Control Desk

Subject:

Duane Arnold Energy Center Docket No. 50-331 Op. License DPR-49 January,1986 Monthly Operating Report

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for January, 1986.

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 and Regulatory Guide 10.1.

Very truly yours, Daniel L. Mineck P1 ant Superintendent - Nuclear Duane Arnold Energy Center DLM/BNT/kp*

Enclosures File A-118d, TE-5 cc: Director, Office of Inspection Mr. Phillip Ross and Enforcement U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Connission Maryland National Bank Building Region III Washington, D. C.

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

NRC Resident inspector Director, Office of Management and Mr. Dennis Murdock Program Analysis Central towa Power Cooperative U. S. Nuclear Regulatory Connission Box 2517 Washington, D. C. 20555 (1)

Marion, IA 52302 U. S. Nuclear Regulatory Connission Mr. Russ Gamble ATTN: Mr. M. Thadani Corn Belt Power Cooperative Phillips Building 1300 13th Street North Washington, D. C. 20555 Humboldt, IA 50548 INP0 Records Center 1100 Circle 75 Parkway Suite 1500 Atlanta, GA 30339 YA t corer.or tslikr et > tw.us t '<a.o rutmis. tan...utem :s tw.sv u ti

'I s

ML20153C710

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