ML19210D003

Monthly Operating Rept for Oct 1979

ML19210D003
Person / Time
Site:	Duane Arnold
Issue date:	11/15/1979
From:	Van Sickel J IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML112340111	List: ML19210D003
References
NUDOCS 7911200406
Download: ML19210D003 (6)

Text

- .

OPERATING DATA REPORT DOCKET NO. 050-0331 DATE November 15, 1979 COMPLETED BY .1 Van Ric 1 TELEPHONE 319-053-3b OPERATING STATUS Notes

1. Unit Name: Duane Arnold Enerov Center

2. Reporting Period: 0<+nhar 1070

3. Licensed Thermal Power (MWt): 1AER

• 4. Nameplate Rating (Gross MWe): 6AG (T"vhina on tinn)

5. Design Electrical Rating (Net MWe): 91A

6. Maximum Dependable Capacity (Gross MWe): W

7. Maximum Dependable Capacity (Net MWe): 515

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since List 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

11. Hours in Reporting Period 745 7.296 41.616

12. Number Of Hours Reactor Was Critical 719.2 5.547.5 29,160.3

13. Reactor Reserve Shutdown Hours 0 0 0

'14. Hours Generator On.Line 714.4 5.446.7 28,433.7

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 626.808 7.114.096 35.180.736

17. Gross Electrical Energy Genented (MWH) 206.765 _ _ .

9.406.628 11.744.057

18. Net Electrical Energy Generated (MWH) 190.967 2.258.512 10,974,812

19. Unit Service Factor 95.9% 74.75 68.3%

20. Unit Availability Factor 95.9% 74.7% 68.3%

21. Unit Capacity Factor (Using MDC Net) - 49.8% 60.1% 51 .2%

22. Unit Capacity Factor (Using DER Net) 47.6% 97 5% 49.0%

23. Unit Forced Outage Rate 4.1% ,

25.3% 21.6%

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

Refuelino. Februarv 9.?980, 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 MWe-7011200YO

i ,

AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO. 050-331 UNIT Duane Arnold Energ3 Center DATE November 15. 1979

_ COMPLETED BY J. Van Sickel TELEPHONE 319-851-5611 MONTH Octnbar.1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Neti I 192 17 _,_

305 2 210 is 314 3 220 g, 309 4 199 203 20 5 220 21 183 6 167 278 22 7 15'B 220 23 8 186 0 24 9 198 25 190 to W 26 407 11 193 27 389 12 207 491 23 13 210 3, 477 14 170 471 3o is 283 434 3,

16 270 INSTRUCTIONS ,

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) 1363 324

t r

DOCKET NO. 050-0331 UNITSIIUTDOWNS AND POWER REDUCTIONS UNIT NAnfE Duane Arnold Energy Cente' DATE Nnvomher 15. 1979 COMPLETED BY Van Rickn1 REPORT hf 0NTII October, 1979 -_1 TELEPilONE 319-851-5611 ,

~

. q _

%- G C No. Date

{

.! E gg

};;

}{3oc

} Licensee Event E%

g7 {*1 a.

L Cause & Corrective Action to mu 5 [u b

oE jgy Report # Prevent Recurrence d

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 i during turbine stop valve testing i due to EHC low pressure indication.

LN .

& I 2 3 4 u: F: Forced Reason: hiethod: Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain) l-blanual for Preparation of Data u B klaintenance of Test 2-klanual Scram. Entry Sheets for Licensee N 0-Refueling 3 Automatic Scram. Event Repor ti.ER) File (NUREG-  ;

ty, D Regulatory Resiriction 4 Other (Explain) 0161)

E-Operator Training & Ucense Examination F Administrative 5 G-Operational Er rur (I'.xplain) Exhibit 1 - Same Source (9/77) 11 Other (Explain) i 1

UCCKU L nU. U3U-OJJ8

',' s- Unit Duane Arnold Energy Cen Date .Jtoyember- 15. 1979 REFUELING INFORMATION Completed by J. Van Sickel Telephone 319!E51-5611 f,

1. Name iir facility.

A. Duane Arnold Energy Center

2. Selirilo t. i slate for next refueling shutdown.

A. February 9, 1980

3. Schettoteil it.ite for restart following refueling.

A. May 3, 1980

4. Will e fueling 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.g.,

new or different fuel design or supplier, unreviewed design or per-formance analysin 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 pre.sent 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 O

1363 326 ee - _- eo. ...ee4 e 6- -^P"9

Docket No. U)U-U ni . - - -

U-' Unit Donne Arnald Enerov Croter Date Nnunman , 19. 197o

... t . ._

Completed by J. Vnn W fm1

. ,, Telephone 319-091-5611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 10-1 At the beginning of the report period the plant was ope ating 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.

R0 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 1 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 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br />.

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 R0 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 R0 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 LC0 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.

t363 327

. O

~~~50c'k'etNo. 050-0331

, Unit Duane Arnold Enerov renIer Date Novenhor 15.14fd MAJOR SAFETY RELATED MAINTENANCE heephon 319-851 561 '

COMPONENT DESCRIPTION DATE SYSTD4 10-3-79 Containment Atmospheric LR 4385 Replaced pen and tape assembly Control 10-4-79 Neutron Monitoring. Rod block Monitoring ",B" Reconnected pin connector 10-6-79 Containment Atmospheric AN-8181B Changed chemicals and calibrated

. Control 10-9-79\____ _ Containment Atmospheric AN-8181B Checked span and recalibrated Control k Rebuilt valve operator 10-9-79 RHR MOV-2009 10-19-79 ESW IS-89A, 1S-898 Cleaned strainers 10-23-79 River water supply IP-117B Adjusted impeller 10-23-79 RHR IS-90A, 1S-90B Cleaned strainers 10-25-79 ESW lS-89A, 1S-89B Cleaned strainers 10-26-79 Neutron Monitoring Rod Block Monitor "B" Installed new amplifier card 10-29-79 Fuel pool cooling and Wall penetration on HCD-23 Installed grout cleanup 10-30-79 ESW IS-89B Cleaned strainer M

GM

• Le CM N

9