Text

Monthly Operating Rept for May 1986
	ML20199D031
Person / Time
Site:	Duane Arnold
Issue date:	05/31/1986
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-86-0407, DAEC-86-407, NUDOCS 8606180481
	Download: ML20199D031 (10)
	v • d • e

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7

. 1 OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 06-15-86 COMPLETED BY Bradford N. Thomas TELEPHONE 319-851-7309 OPERATING STATUS Notes

1. thlt Name Duane Arnold Energy Center

2. Reporting Period May, 1986

3. Licensed Thermal Power (MWt):

1658

4. Nameplate Rating (Gross MWe):

565 (Turbine)

5. Design Electrical Rating (Not MWe):

538

6. Maximum Dependable Capacity (Gross MWe):

545

7. Maximum Dependable Capacity (Not MWe):

515

8. If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since the 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 Cumu lative

.11. Hours in Reporting Period 744 3623.0 99311

_ 2. Number of Hours Reactor Was Critical 744 3097.8 70419.7 l

13.' Reactor Reserve Shutdown Hours 0

0 150.3

.14. Hours Generator On-Line

-744 3082 68641.5

15..thit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 807451 3754447 86360682

17. Gross Electrical Energy Generated (MWH) 268494 1272705 28928766

18. Not Electrical Energy Generated (MWH) 251270 1194625 27091262

19. Unit Service Factor 100 85.1 69.1 20.-Unit Availability Factor 100 85.1 69.1 I

21. Imit Capacity Factor (Using MDC Net) 65.6 64.0 53.0

22. Unit Capacity Factor (Using DER Net) 62.8 61.3 50.7

- 23. Ihlt Forced Outage Rate 0

0 15.3

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

A planned maintenance outage between June 8, 1986 and June 14, 1986 for electrical tle in of the newly Installed auxiliary transformer, and minor plant system maintenance.

[

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

]h 8606180481 860531

{DR ADOCK 05000331 (9/77)

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AVERAGE DAILY (NIT POWER LEUEL 1

DOCKET NO. 050-0331 (NIT Duane Arnol d Eneray Center DATE 06-15-86 COMPLETED BY Bradford N. Thomas TELEFHONE 319-851-7309 MONTH May, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1

-530-17 287 2

539 18 291 3

538 19 291 4

532 20 297 5

'436 21 278 6-266 22 285 7

286 23 286 8

288 24 279 9

288 25 281 10 288 26 383 11 287 27 4 94 12 286 28 222 13 291 29 206 14 286 30 390 15 287 31 4 86 16 280 INSTRUCTIONS On this format,' llst the average elly unit power level in MWe-Net for each my in the reporting enth. Compute

.no nearest whole megawatt.

(9/77)

+

UNIT SH UT DO*:NS AND POWER REDUCTIONS Decket No. 050-0331 Unit Ncco Dween Aranid Esargy Coster Da to 06/15/86 REPORT MONTH May, 1986 Comp l e ted by Bradford N. Thomas Telephone 319-851-7309 m

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Date

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4 05/06/86 S

486 F

1 ZZ ZZZZZZ Reactor power voluntarily redsced to approx. 505 to minimize potential plant transient while HPCI and RCIC condensate storage tank (CST) to CST full flow test return lines were unavailable (LER 86-014) 5 05/28/86 F

45.7 A

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'B' Recirculation Motor Generator (MG) Set tripped die to pitted / dirty exciter windings I

I 2

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F: Forced Reason:

Me thod:

Exhibi t G-Ins tructions S: Scheduled A-Equipment Failure (Explain) 1-Manual f or Prepara tion of Da ta 8-Maintenance or Tes t 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Au toma ti c Scram Event Report (LER) File (NUREG-D-Regu la tory Res tr i c ti on 4-Other (Explain) 0161)

E-Opera tor Trai ning & License Examination F-Admi n i s tra ti ve 5

G-Opera tiona l Error (Explain)

Exhibit 1-Same Source (9/77)

H-O th e r (Explain)

Do c kot N3 050-0331 Ualt N;co f! unco Arcai d Ex rgy ' Conter !

Dato 06-15-86 MAJ03/ SAFETY RELATED MAINTENANCE Cocp lotod by Bre df or d N-Theenn Telephone 319-851-7309 DATE SYSTEM COMPONENT DESCRIPTION 05/0l/86 HIqh Pressure Coolant injection HPCI. test discharge piping Finished Installation _of a blind flange (HPCI)

(which began on 04/30/86) on_.the HPCl test

' discharge piping in preparation for planned maintenance on the HPCI test return discharge valve (LER 86-014) 05/04/86 Containment Atmosphere Dilution

'A' Drywell (D/W) H2 Analyzer Replaced H2. catalyst and02 reagent gas (CAD) regulator on

'A' D/W Analyzer 05/05/86 HPCI HPCI Test Discharge Valve Ref urbished the HPCI test discharge valve l

(BJ-ISV-2315) l (LER 86-014) 05/09/86 River Water Supply (RWS)

'C ' RWS Pump (1P-117C)

Remove d

'C ',RWS pump from service to make impeller a dj u s t men t in or der to meet ASME delta P requirements

)

1 05/11/86 Stan dby Gas Treatment (SBGT)

'B' SBGT Train Pressure Recalibrated the

'B' train SBGT pressure System Differential Gage PD1 58038 differential gage j

I 05/15/86 Main Steam Line isolation valve -

'C' MSI V-LCS Blee d Va l ve Replaced faulty relay which ren dere d these Leakage Control System

-(MO 8401/2-C) valves inoperable 05/I7/86 Res i dua l Heat Removal Service

'A' RHRSW Pump (1P-22A) Discharge Refurbished the

'A' RHRSW pump discharge Water (RHRSW)

Auto Vent Valve Auto Vent Valve ( 8.V -4 9 2 6 A )

l05/19/86 MSIV-LCS

'D' MSIV-LCS Flow In dicator Recalibrated F1-8408D l

(F1-8408D) 05/21/86 Recirculation Motor Generator

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Osckot No. 050-0331 Unit Naso Dutno Arnel d Energy Centsr Dato 06-15-86 Completed by Bra df or d N.

Thomas Telephone 319-851-7309 REFUELING INFORMATION 1.

~ Name of facility.

A.

Quane Arnol d Energy Center 12 Sche duled date for next refueling s h u t do w n.

A.

February,_1987 3.

Sche du le d date for restart following refueling.

A.

April, 1987 4

Will refueling or resumption of operation thereafter require a technical specification change or other license amen dmen t ?

A.

None currently identitled 5

Sche du l e d da t e ( s ) for submitting proposed licensing

..t lon a n d supporting Information.

A.

None currently Identified 6.-

Important licensing consi derations associated with refueling, e.g.,_new or dif f erent fuel design or supplier, unreviewed design or performance ana lysis metho ds, significant changes in fuel design, new operating p ro ce du r es.

None 7

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

A.

a) 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 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

Dockot No. 050-0331 Un it N:m3 Duenn Arnnl d Energy Cnnter Dato 06-15-86 Completed by Bra df or d N. Thomas Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERI ENCE 05/01/86 At the beginning of the Month the DAEC was in normal power operation with 530 MWe (not) being provided to the grid.

05/02/86 At 1318 hours0.0153 days 0.366 hours 0.00218 weeks 5.01499e-4 months the con densate lifluent con ductivity monitor (ClT 1704) was returned to service thus terminating the 30 day Limiting Con dition for Operation (LCO) which b e g a r; on 04/11/86.

05/02/86 At 1836 hours0.0213 days 0.51 hours 0.00304 weeks 6.98598e-4 months the High Pressure Coolant injection (HPCI) system was returne d to service after instarlation of a. blin d flange which began on 04/30/86 to support a planned meintenance evolution.

(LER 86-014)

At 1921 hours0.0222 days 0.534 hours 0.00318 weeks 7.309405e-4 months the operations department authorized GE personnel to begin Hg injection into the reactor f ee dwater system for prellminary Hy drogen Water Chemistry (HWC) testing at DAEC.

05/03/86 At 1635 hours0.0189 days 0.454 hours 0.0027 weeks 6.221175e-4 months workers were performing a fire protection surveillance test (fire protection system ring nea der flush) when they di scover e d two manual in dl cat ing valves closed on the main hea der.

With these valves closed in conjunction with the system flushing going on, a portion of the ring head supplying the deluge, sprinkler, hose, and fire main water systems was unintentionally isolated for approximately five hours.

(LER 86-015) 05/04/86 The preliminary HWC testing was successfully completed at 2142 hours0.0248 days 0.595 hours 0.00354 weeks 8.15031e-4 months .

05/05/86 At 2315 hours0.0268 days 0.643 hours 0.00383 weeks 8.808575e-4 months reactor power was volontarily being reduced to approximately 50% to minimize po t e n t-l a l plant transient while HPCI and RCIC con densate storage tank (CST) to CST full flow test return lines were unavailable.

05/06/86 At 0203 hours0.00235 days 0.0564 hours 3.356481e-4 weeks 7.72415e-5 months with the reactor at 50% of rated thermal power the

'A' Reactor Feed Pump an d 888 Con dens a te Pump were removed from service.

At 0610 hours0.00706 days 0.169 hours 0.00101 weeks 2.32105e-4 months the con densate influent con ducti vi ty mon itor (CIT 1704) was removed from service when no flow was de t e c t e d.

The 30 day LCO which was terminated on 05/02/86 was reentered at this time.

05/07/86 At 1322 hours0.0153 days 0.367 hours 0.00219 weeks 5.03021e-4 months the Reactor Water Cleanup.(RWCU) system isolated du e to a lea d being lifted during the calibration of a temperature in dicat ing controller.

The root cause was a mis lea ding electrical schematic which lea d to a inaccurate engineering evaluation of the lifted les d clearance. Callbration was completed an d the RWCU system was returned to service at 1359 hours0.0157 days 0.378 hours 0.00225 weeks 5.170995e-4 months .

(LER 86-016)

At 1755 hours0.0203 days 0.488 hours 0.0029 weeks 6.677775e-4 months the 30 da y LCO on the con den sate influent con duct i v i ty monitor (CIT 1704) was terminated when con duct i v i ty between the hotwell and domineralizers was being prowlded by other means per Tech. Spec.

requirements.

Dackot No. 050-0331 Unit Nsco Dueno Arnold Energy Conter Dato 06-15-86 Comp lete d by Bra df or d N.

Thomas Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 05/11/86 At 1225 hours0.0142 days 0.34 hours 0.00203 weeks 4.661125e-4 months a 7 day LCO was entered when the 'B '- Sta n dby Ga s Treatment system was dec l a re d inoperable after falling a surveillance test.

A pressure differential in dicator was recallbrated and the 7 day LCO was cancelled with the system returned to service at 2010 hours0.0233 days 0.558 hours 0.00332 weeks 7.64805e-4 months .

05/15/86 At 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months a 30 day LCO was entered when the

'C' Maln. Steam Line Iso lat ion-Valve - Leakage Control System (MSlV-LCS) f ailed a surveillance test.

A faulty

'C' MSI V-LCS B loe d va lve re lay was replaced.

The LCO was terminated at 1534 hours0.0178 days 0.426 hours 0.00254 weeks 5.83687e-4 months after successful post-maintenance testing and the return of the system to it's normal lineup.

05/16/86 At 0949 hours0.011 days 0.264 hours 0.00157 weeks 3.610945e-4 months the con densa te influent co n du ct i v i ty monitor (CIT 1704) was returne d to service after filter replacement an d pressure an d flow a djus tment.

(See 05/06/86 an d 05/07/86 entries) 05/17/86 At 0040 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months a 30 day LCO was entered when the 'C ' Res i dua l Heat Removal Service Water (RHRSW) pump was de c l a re d inoperable du e to a f ailed pump discharge auto-vent valve.

The vent-valve was ref urbishe d an d the LCO was terminated on 05/22/86 at 1632 hours0.0189 days 0.453 hours 0.0027 weeks 6.20976e-4 months with the pump being returned to service.

05/19/86 At 0723 hours0.00837 days 0.201 hours 0.0012 weeks 2.751015e-4 months the

'D' MSIV-LCS flow in dicator was not iced to be rea di n g upscale.

A 30 day LCO was entered an d 80' MSIV-LCS was dec l a r e d Inoperable.

Flow in dicator FI 8408D was recali brated an d returned to service-thus cancelling the LCO on 05/31/86 at 0838 hours0.0097 days 0.233 hours 0.00139 weeks 3.18859e-4 months .

05/21/86 At 2216 hours0.0256 days 0.616 hours 0.00366 weeks 8.43188e-4 months the

'A' Recirculation MG-Set was removed f rom service to replace the generator brushes. Change out was comp lete d at 2358 hours0.0273 days 0.655 hours 0.0039 weeks 8.97219e-4 months and the MG-Set was returned to service.

05/22/86 The HPCI system was removed from service at 1543 hours0.0179 days 0.429 hours 0.00255 weeks 5.871115e-4 months for removal of the blank flange Installe d on 05/02/86.

This placed the plant in a7 day LCO.

After successful demonstration o f HPCI operability the LCO was terminated on 05/24/86 at 1815 hours0.021 days 0.504 hours 0.003 weeks 6.906075e-4 months when the HPCI system was returne d to servi ce.

(LER 84-014) 05/26/86 At 0542 hours0.00627 days 0.151 hours 8.96164e-4 weeks 2.06231e-4 months the

'A' f ee dwa ter an d con densate pumps were returned to service after being remove 6 from service on 05/06/86 At. 1053 hours0.0122 days 0.293 hours 0.00174 weeks 4.006665e-4 months a 7 day LCO was entered when the HPCI system was voluntarily remove d f rom service.

The inboar d Steam Supply isolation valve (M02238) was closed to a l low operations personnel to backseat the Outboar d Steam Supply isolation Valve (M02239) du e to a packing leak.

The HPCI system was returned to its normal stan dby mo de at 1254 hours0.0145 days 0.348 hours 0.00207 weeks 4.77147e-4 months thus cancelling the LCO.

(LER 86-014)

I Dockot No. 050-0331 Unit Nano Duenn Arnold Energy Center Dato 06-15-86 Completed by Bra dfor d N.

Thomas Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 05/26/86 At 1756 hours0.0203 days 0.488 hours 0.0029 weeks 6.68158e-4 months a 7 day LCO was entered when the RCIC System was remove d (cont.)

from service to remove a blind flange which was Installed on 04/28/86.

After completion of operability testing the RCIC system was returned to service on 05/27/86 at 1840 hours0.0213 days 0.511 hours 0.00304 weeks 7.0012e-4 months en ding the LCO.

(LER 86-014) 05/27/86 At 1055 hours0.0122 days 0.293 hours 0.00174 weeks 4.014275e-4 months the

'A' Stan dby Filter Unit (SBFU) f ailed a surveillance test when the unit would not Auto-Start on a simulated dema n d signal.

This placed the plant in a 7 day LCO.

Investigation revealed a faulty coil in a logic relay.

The relay was replace d an d post-maintenance testing was comp lete d on 05/29/86 at which time the LCO was terminated with the system being returned to service at 0935 hours0.0108 days 0.26 hours 0.00155 weeks 3.557675e-4 months .

05/28/86 At 0039 the

'B' Recirculation MG-Set tripped with the reactor at 975 of rate d power.

Investigation revealed the generator exciter slip rings to be p i t te d/ di rty. The rings were ref urbishe d an d the MG-Set was returne d to service at 2354 hours0.0272 days 0.654 hours 0.00389 weeks 8.95697e-4 months on 05/29/86.

At I348 hours a 7 day LCO was entered when the HPCI system was removed from service to repack the Outboar d Steam Supply isolation Yalve (M02239).

The valve was repacked and successfully passed stroke time requirements in accor da nce with post-malntenance testing.

The HPCI system was return to service at 1406 hours0.0163 days 0.391 hours 0.00232 weeks 5.34983e-4 months on 05/29/86 thus cancelling the LCO.

(LER 86-014) 05/29/86 A 30 day LCO was entered at 1336 hours0.0155 days 0.371 hours 0.00221 weeks 5.08348e-4 months when the 'Ce RHRSW pump was remove d f rom service for planne d maintenance.

Leaks on the Emergency Service Water (ESW) piping outlet from the

'C' RHRSW motor cooler were then secured.

The pump was returned to service at 1815 hours0.021 days 0.504 hours 0.003 weeks 6.906075e-4 months thus cancelling the LCO.

05/31/86 At the en d of the month the plant was in normal power operation with 486 MWe-Net being provi de d to the grid.

Iowa Electric Light and Power Company June 15, 1986 DAEC-86-0407 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 May,1986 Monthly Operating Report

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Doerating Report for May,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, MlaQ Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/BNT/pl*

Enclosures File A-118d, TE-5 cc: ' Director, Office of Insoection Mr. Phillip Ross and Enforcement U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission 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 Iowa Power Cooperative U. S. Nuclear Regulatory Commission Box 2517 Washington, D. C. 20555 (1)

Cedar Rapids, IA 52406 U. S. Nuclear Regulatory Commission 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 h )i Suite 1500 Atlanta, GA 30339 l

1 nuanc arnata eneuxv center 3277 suec naad rato. rama s232.s ainss.rai 1

ML20199D031

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