ML112340443

Monthly Operating Rept for Jan 1992 for Duane Arnold Energy Center

ML112340443
Person / Time
Site:	Duane Arnold
Issue date:	01/31/1992
From:	Denise Wilson, Tran H IES Utilities, (Formerly Iowa Electric Light & Power Co)
To:	NRC/IRM
Shared Package
ML112340444	List: ML112340443
References
DAEC-92-0059, DAEC-92-59, NUDOCS 9202190330
Download: ML112340443 (8)

Text

ACCELERATED DI jJBUTION DEMONSTI 6 TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9202190330 DOC.DATE:.4.

"-NOTARIZED:

NO FACIL:50-331 Duane Arnold Energy Center, Iowa Electric Light & Pow AUTH.NAME AUTHOR AFFILIATION TRAN,H.

Iowa Electric Light & Power Co.

WILSON,D.

Iowa Electric Light & Power Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Monthly o

' Rg rept for Jan 1992 for Duane Arnold Energy Center.

2021 tr.

lc r}

DOCKET #

05000331 R

DISTRIBUTION CODE: IE24D TITLE: Monthly Operating COPIES RECEIVED:LTR _I ENCL Report (per Tech Specs)

NOTES:

INTERNAL:

EXTERNAL:

RECIPIENT ID CODE/NAME PD3-3 LA SHIRAKI,C.

ACRS AEOD/DSP/TPAB NRR/DOEA/OEAB RGN3 EG&G BRYCE,J.H NSIC COPIES LTTR ENCL 3

3 1

1 10 1

1 1

1 1

10 1

1 1

1 1

RECIPIENT ID CODE/NAME PD3-3 PD AEOD/DOA NRR/ DLPQ/LPE B10 NRC PDR COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR SIZE:

I D

S

/

A D

D S

24 ENCL 24

Iowa Electric Light and Power Company February 15, 1992 DAEC-92-0059 Mr. A. Bert Davis Regional Administrator Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Subject:

Duane Arnold Energy Center Docket No:

50-331 Op. License DPR-49 January 1992 Monthly Operating Report

Dear Mr. Davis:

Please find enclosed the Duane Arnold Energy Center Monthly Operating Report for January 1992.

The report has been prepared in accordance with the guidelines of NUREG-0020 and distribution has been made in accordance with AEC Technical Specifications, Section 6.11.1.c.

V ytr yours David L. Wilson Plant Superintendent - Nuclear DLW/HT/eah Enclosures File A-118d cc:

Dir. of Nuclear Reactor Regulation Document Control Desk U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D. C. 20555 (Orig.)

Mr. Clyde Shiraki Project Manager 1 Whiteflint North Mail Stop 13E21 11555 Rockville Pike Rockville, MD 20852 INPO Records Center 1100 Circle 75 Parkway Suite 1500 Atlanta, GA 30339-3064 Mr. Steve Brown Iowa State Utilities Board Lucas State Office Building Des Moines, IA 50319.

Mr. Fred Yost Director Research Services Utility bata Institute 1700 K St. NW, Suite 400 Washington, DC 20006 9202190330 920131 PDR ADOCK 05000331 R

PDR Mr. William Loveless U.S. NRC 1 Whiteflint North Mail Stop 11C14 11555 Rockville Pike Rockville, MD 20852 (2)

NRC Resident Inspector Mr. Dennis Murdock Central Iowa Power Cooperative Box 2517 Cedar Rapids, IA 52406 Mr. Dale Aherns Corn Belt Power Cooperative 1300 13th Street North Humboldt, IA 50548 Dr. William R. Jacobs, Jr.

GDS Associates, Inc.

Suite 720 1850 Parkway Place Marietta, GA 30068-8237 Duane Arnold Energy Center

• 3277 DAEC Road

• Palo, Iowa 52324

• 319/851-7611

--r 14 "6j

OPERATING DATA REPORT DOCKET NO.

050-0331 DATE 02-15-92 COMPLETED BY Hai Tran TELEPHONE (319) 851-7491 OPERATING STATUS

1. Unit Name:

Duane Arnold Energy Center

2. Reporting Period:

January 1992

3. Licensed Thermal Power (MWt):

1658

4. Nameplate Rating (Gross MWe):

565 (Turbine)

5. Design Electrical Rating (Net 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 the Last Report, Give Reasons:

N/A Notes through 7) Since

9. Power Level to Which Restricted, If Any (Net MWe):

Approximately 82% at the end n4 +h mon+h

10. Reasons for Restrictions, If Any:

Plant is in coast-down condition This Month Yr-to-Date Cumulative

11. Hours in Reporting Period

12. Number of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor

20. Unit Availability Factor

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 744.0 744.0

.0 744.0

.0 1064340.0 357200.0 333481.8 100.0 100.0 87.0 83.3 0.0 744.0 744.0

.0 744.0

.0 1064340.0 357200.0 333481.8 100.0 100.0 87.0 83.3 0.0

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

Refuel Outage 11, February 27, 1992. 59 days

25. If Shutdown at End of Report Period, Est. Date of Startup:

N/A (9/77) 149016.0 109532.3 192.8 106652.1

.0 144117936.4 48323526.0 45297993.9 71.6 71.6 58.7 56.5 13.0

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 DATE 02-15-92 COMPLETED BY Hai Tran TELEPHONE (319) 851-7491 MONTH January 1992 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 479 2

479 3

473 4

474 5

462 6

469 7

464 8

462 9

464 10 461 11 458 12 456 13 456 14 452 15 452 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 447 444 448 439 442 435 435 448 419 431 429 434 420 424 421 421

REFUELING INFORMATION DOCKET NO. 50-0331 DATE 02-15-92 COMPLETED BY Hai Tran TELEPHONE (319) 851-7491

1.

Name of facility.

a.

Duane Arnold Energy Center

2.

Scheduled date for next refueling shutdown.

a.

February 27, 1992

3.

Scheduled date for restart following refueling.

a.

April 26, 1992

4.

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

Yes, RTS-218 and RTS-242 have been submitted.

5.

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

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.

N/A

7.

The number of fuel assemblies (a) in the core, (b) in the spent fuel storage pool, and (c) new fuel vault -

new fuel assemblies.

a.

368

b.

1048

c.

104

8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity ?hat has been requested or is planned, in number of fuel assemblies.

a.

2050 -

Licensed Capacity or

b.

1898 under the presently installed storage rack capacity.

9.

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

a.

2000 -

Licensed Capacity or

b.

1997 under the presently installed storage rack capacity.

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH:

January 1992 Docket No.:

Unit:

Date:

Completed By:

Telephone:

050-0331 Duane Arnold Energy Center 02-15-92 Hai Tran (319) 851-7491 I

I INo. I Date II I None I I

I I

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IReason(2)

I1______________ I______________

I I

I II I

II I

I II I

II I

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I Method OT Shutting (3)

Down Reactor Licensee Event Report #

2 -

Reason:

A-Equipment Failure (Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain)

Comp.

Code (5) 3 -

Method 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continued 5-Reduced Load 9-Other (Explain) 4-Exhibit G Instructions for Preparation of Data Entry Sheets for Licensee Event Report 0LER) File (NUREG-5 -

Exhibit 1 Same Source (9/77)

Cause

-1 I System l

Code 1(4)

Cause

MAJOR/SAFETY RELATED MAINTENANCE Docket No.:

Unit:

Date:

Completed By:

Telephone:

050-0331 Duane Arnold Energy Center 02-15-92 Hai Tran (319) 851-7491 DATE 01-15-92 01-23-92 01-29-92 l SYSTEM Nuclear Steam System (NSSS)

Supply Shutoff Residual Heat Removal (RHR) System Nuclear Steam System (NSSS)

Supply Shutoff I

I COMPONENT Triple Low Reactor Water Indicating Switches Various Valve Motor Leads and Hand Switches High Reactor Water Level Indicating Switches DESCRIPTION Due to the discovery of an error in the low reactor water level trip setpoints, reactor water level indicating switches recalibrated.

triple the were Various valve motor leads and hand switches were inspected and repaired as necessary.

Due to the discovery of an error in the high reactor water level setpoints, the reactor water level indicating switches recalibrated.

hig 0

were

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE DOCKET NO.

050-0331 DATE 02-15-92 COMPLETED BY Hai Tran TELEPHONE (319) 851-7491 01-01-92 The plant was operating in coastdown condition with 91.6% of rated thermal power delivering 479.4 MWe to the grid.

There were three 10 CFR 50.73 reportable events in two reports during the month.

The first report includes two unplanned LCO events (Limiting Conditions for Operation) for instrumentation for the Emergency Core Cooling Systems (ECCS).

There was no unplanned significant reduction in power level event during the month.

01-15-92 While confirming calculations and assumptions used in establishing the triple low reactor water level trip setpoints, engineers discovered an error in GE SIL-299 (General Electric Service Information Letter) in describing the proper instrument offset to compensate for the effects of high drywell temperature on wide range YARWAY indications.

The plant entered a twenty-four hour LCO.

The instruments were recalibrated to the proper setpoints, and the LCO was cancelled.

LER 92-001 01-26-92 The plant was operating at 83.0% power.

During surveillance testing on the Standby Gas Treatment system, a fire door in the turbine building sump room was blocked open without the Technical Specification required compensatory action of a fire watch in place. The interim corrective action was to establish a fire watch upon the discovery.

The cause of the event was inadequate procedural instructions.

Throughout the period of the event, the fire detection equipment in the area was operable.

The event had no effect on plant safety, availability, or personnel safety.

LER 92-002 01-29-92 While performing additional reviews of level instrument setpoints, the engineering department discovered a discrepancy in the high reactor water level setpoints that provide the trip signals for high level trips for the High Pressure Coolant Injection and Reactor Core Isolation Cooling systems.

The cause of this problem was the result of rerouting the reference legs to outside containment in 1988.

At elevated drywell temperature, the associated-instruments would not provide the high level trips because of the density differences between the variable leg piping, which is still inside the containment, and the reference leg.

The plant entered a twenty-four hour LCO following determination of this problem. The LCO was exited following recalibration of the affected instruments.

LER 92-001 01-31-92 At the end of the month the plant was operating at 81.3% of rated thermal power delivering 420.5 MWe to the grid.

I