ML112340110

Forwards Monthly Operating Rept for Oct 1979

ML112340110
Person / Time
Site:	Duane Arnold
Issue date:	11/15/1979
From:	Hammond E IES Utilities, (Formerly Iowa Electric Light & Power Co)
To:	NRC/IE
Shared Package
ML112340111	List: ML112340110 ML19210D003
References
NUDOCS 7911200405, RAA-DAEC-316
Download: ML112340110 (8)

Text

REGULAORY*FURMATION DISTRIBUTION 8 (IS)

A'CCESSION NbR:7911200405 DOC.DATE: 79/11/15 NOTARIZED: NO 0OCKET #

FACIL:50-331 Duane Arnold Energy Center, Iowa Electric Light & Pow 05000331 AUTHNAME AUTHOR AFFILIATION HAMMUNDE.L, Iowa Electric Light & Power Co.

HECIPNAME RECIPIENT AFFILIATION Office of Inspection & Enforcement, Office of the Director

SUBJECT:

Forwards monthly operating rept for Oct 1979, DISTRIBUTION CODE: A0088 COPIES RECEIVED:LTR -J ENCL L SIZE:

TITLE: Annual, Semi-Annual & Monthly Operating Reports (OE Stag NOTES: ---------------------

RECIPIENT ID CODE/NAME ACTION:

05 bC &/3

3 INTERNAL: 01 FILE 11 I 10 DIR O0R 19 REAC SAFT BR 21 EE8 23 EFFL TR SYS EXTERNAL:

03 24 26 LPDR NATL LAB P'-

ACRS COPIES LIrTR ENCL 6i 6

1 2

1 1

1 1

1 1

15 1

2 1

1 1

I 1

1 15 RECIPIENT ID CODE/NAME 02 14 18 20 22 NRC PDR MPA ENGR BR PLANT SYS BR CORE PERF BR 04 NSIC 25 BROOKHAVEN COPIES LYTR ENCL 1

2 1

1 1

1 1

1 1

1 1

I

c1Jfln, TOTAL NUMBER OF COPIES REQUIRED: LTTR 38 ENCL A

Iowa Electric Light and Power Company November 15, 1979 RAA-DAEC-316 Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Monthly Operating Report File: A-118d

Dear Sirs:

Please find enclosed 10 copies of the Duane Arnold Energy Center Monthly Operating Report for October, 1979.

The report has been prepared in accordance with the requirements of Regulatory Guide 1.16 and distribution has been made in accordance with Regulatory Guide 10.1.

Very truly yours, Ellery L. Hammond Chief Engineer Duane-Arnold-Energy Center ELH/JVS/n Encl.

cc:

D. Arnold S. Tuthill R. Peterson J. Rehnstrom L. Root W. Bryant D. Mineck D. Wilson B. York R. Hannen Dennis Murdock Directorate of Inspection and Enforcement U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 (1)

Director, Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (2)

'7q fI Too Aoof

• Cedar Rapids, Iowa 52406

• 319/851-5611

OPERATING DATA REPORT DOCKET NO.

050-0331 DATE November 15, 1979 COMPLETEDBY J, L2L S

Y1 TELEPHONE 319-851-56 OPERATING STATUS

1. UnitName:

Duane Arnold. Energy Center Notes

2. Reporting Period:

0ctnher, 1)7c

3. Licensed Thermal Power (MWt):

1 ISi

4. Nameplate Rating (Gross MWe):

LLr; (TiiyhjnP Ra ing)

5. Design Electrical Rating (Net MWe):

538

6. Maximum Dependable Capacity (Gross MWe):

5V

7. Maximum Dependable Capacity (Net MWe):

515

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

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

10. Reasons For Restrictions, If Any:

This Month

. Yr.-to-Date Cumulative Hours In Reporting Period Number Of Hours Reactor Was Critical Reactor Reserve Shutdown Hours Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWH)

Gross Electrical Energy Generated (MWH)

Net Electrical Energy Generated (MWH)

Unit Service Factor Unit Availability Factor Unit Capacity Factor (Using MDC Net)

Unit Capacity Factor (Using DER Net)

Unit Forced Outage Rate 745 719.2 0

714.4.

0 626,808 206,765 190,967 95.9%

95.9%

49.8%

47.6%

4.1%

7,296 5,547.5 0

5,446.7 0

7.119-096 2 406.628 2,258,512 74-7 74.7%

60.1%

57 5%

25.3%

41,616 29,160.3 0

28,433.7 0

35.180736 11,744,057 10,974,812 68.3%

68.3%

51.2%

49,.0%

21.6%

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

~Refueling, February 9.1980. 12 weeks

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

Turbine Rating:

565.7 MWe Generator Rating:. --663.5- (MVA) x.90 (Power Factor) = 597 MWef (9/77)

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

21.,

22.

23.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

050-331 UNIT Duane Arnold Energy Center DATE November 15.

1979 COMPLETEDBY J. Van Sickel TELEPHONE 319-851-5611 MONTH October. 1979 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 192 2

3 4

5 6

7 8

9 10 11 12 13 14 is 16 210 220 199 220 167 158 186 198 196 193 207 210 170 283 270 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 305 18 314 19 20 21 22 23 24 2s 26 27 28 29 30 31 309 203 183 278 220 0

190 407 389 491 477 471 434 INSTRUCTIONS a

On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORTMONTH October, 1979 DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE 050-0331 Duane Arnold Energy Cente November 15, 1979

.1 Ian ickol 319-851-5611 Licensee E,

c 0 Eens Cause & Corrective a

Event o

Action to Report#

Prevent Recurrence

14.

791006 S

0 F

4 N/A -

ZZ ZZZZZZ Power reduced due to lack of demand and to conserve fuel for winter peak loads

15.

791020 S

0 F

4 N/A ZZ ZZZZZZ Power reduced due to lack of demand and to conserve fuel for winter peak loads.

16.

791023 F

0 A

4 N/A ZZ ZZZZZZ Power reduced in preparation for plant shutdown.

17.

791024 F

28.8 A

1 N/A CH PIPEXX Plant shutdown to repair "B" feed pump seal water line.

18.

791031 F

1.8 A

3 N/A HA INSTRU Turbine trip and reactor scram during turbine stop valve testing due to EHC low pressure indication.

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)

HI-Other (Explain) 3 4

Method:

I -Manual 2-Manual Scram.

3-Automatic Scram.

4-Other (Explain) 5 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

Exhibit I - Same Source (9/77)

.0 S

F: Forced S: Scheduled

Uocket No.

Ub U-U.3I Unit Duane Arnold Energy De U E L N G I N F O R M A T I O N C

1 S

U L LC~

iFORMTIONCompleted by J. Van Sickel Telephone 319-851-5611

1. Nameff,

>F"'K FaIlit

y.

A. Duane Arnold Energy Center

2.

Scheduled date for next refueling shutdown.

A. February 9, 1980

3.

Schedtled daLe for restart following refueling.

A. May 3, 1980

4.

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

A. Yes.

MCPR and MAPLHGR operating limits as.derived from transient and accident analyses.

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

A. Unknown.

6. Important licensing considerations associated with refueling, e-.go, new or different fuel design or supplier, unreviewed design or per formance analysis methods, significant changes in fuel design, new operating procedures.

A.

The reload will consist of up to 92 8 x 8 2 water rod bundles.

7.

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

A.

a) 368 b) 276

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 planned, in number of fuel assemblies.

A. 2050

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

A.

1998

Docket No.-N5TU-155F Unit uane Arnold Energy Center Dat-i 9-L CompT= ed by 3. Van Sickel Telephone 319-851-5611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 10-1 At the beginning of the report period the plant was operating at 209 MWe. Plant load was administratively limited in order to conserve fuel for winter peak loads.

The plant was following load to the extent possible while staying within administrative limits.

10-3 During surveillance testing "B" rod block monitor (RBM) was found to be inoperable and generating a continuous rod withdrawal block. "A" RBM was tested and found to be operable.

RO 79-028 10-15 The "A" feed pump was started. Plant load was increased due to increasing system demand.

10-20 Plant load was reduced due to lack of demand and to conserve fuel for winter peak loads.

10-23 The "B" feedwater pump seal water return line was found leaking. The leak was in an unisolable location so preparations for a plant shutdown were begun.

10-24 The main generator was tripped at 0117 hours0.00135 days <br />0.0325 hours <br />1.934524e-4 weeks <br />4.45185e-5 months <br />. The reactor was subcritical at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br />. The RCIC turbine was operated from 0348 hours0.00403 days <br />0.0967 hours <br />5.753968e-4 weeks <br />1.32414e-4 months <br /> to 0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> for vessel pressure control.

10-25 Repairs were completed and plant startup begun. The reactor was critical.

at 0219 hours0.00253 days <br />0.0608 hours <br />3.621032e-4 weeks <br />8.33295e-5 months <br />. The main generator was placed on the line at 0607 hours0.00703 days <br />0.169 hours <br />0.001 weeks <br />2.309635e-4 months <br /> and a power increase was begun. The plant was at 388 MWe at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />.

A fuel preconditioning ramp was begun at 2345.hours.

10-26 At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> "B" rod block monitor was found inoperable. An RO investigation is in progress.

During the performance of a special test of standby diesel generator 1G-21, the fuel oil level in the diesel fuel storage tank dropped below the 35,000 gallon technical specification limit. An RO investigation is in progress.

10-28 The plant was operating at 508 MWe.

10-29 The RCIC system was declared inoperable due to a packing leak on CV-2409.

A seven day LCO was started.

10-30 CV-2409 was repaired and the RCIC system tested with satisfactory results.

The seven day LCO was cancelled.

10-31 At 2214 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.42427e-4 months <br /> a turbine trip and reactor scram occurred during turbine stop valve testing. The turbine supervisory instrument system first hit was EHC low pressure. An investigation was begun.

MAJOR SAFETY RELATED MAINTENANCE Docket No.

050-0331 1

Unit Duane Arnold Energy Center Date Novemhr 15 17q' Completed by J. Van Sick4l Telephone 319-851-5611__

I I

I DATE 10-3-79 10-4-79 10-6-79 10-9-79\\

10-9-79 10-19-79 10-23-79 10-23-79 10-25-79 10-26-79 10-29-79 10-30-79 SYSTEM DATE Containment Atmospheric Control Neutron Monitoring Containment Atmospheric Control Containment Atmospheric Control RHR ESW River water supply RHR ESW Neutron Monitoring Fuel pool cooling and cleanup ESW COMPONENT LR 4385.

Rod block Monitoring "B" AN-8181B AN-8181B MOV-2009 1S-89A, 1S-89B 1P-117B 1S-90A, 1S-90B IS-89A, 1S-89B Rod Block Monitor 'B" Wall penetration on HCD-23 1S-89B UESCR IPTION Replaced pen and tape assembly Reconnected pin connector Changed chemicals and calibrated Checked span and recalibrated Rebuilt valve operator Cleaned strainers Adjusted impeller Cleaned strainers Cleaned strainers Installed new amplifier card Installed grout Cleaned strainer I

I