ML20213H077

Monthly Operating Rept for Oct 1986

ML20213H077
Person / Time
Site:	Duane Arnold
Issue date:	10/31/1986
From:	Mineak D, Bernard Thomas IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
DAEC-86-0836, DAEC-86-836, NUDOCS 8611190074
Download: ML20213H077 (10)

Text

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OPE ltATING DATA REPORT DOCKET NO. 050-0331 DATE 11-15-86 COWLETED BY Bradford N. Thomas TELEPHONE 319-851-7309 OPERATING STATUS Notes

1. Unit name Duane Arnold Energy Center

2. Reporting Period October, 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 (Not MWe):

10. Reasons For Restrictions, if Any:

This % nth Yr-to-Date Cumulative

11. Hours in Reporting Period 745 72 %

102984

12. Number of Hours Reactor Was Critical 4%.8 6182.8 73504.7

13. Reactor Reserve Shutdown Hours 0

42.5 142.8

14. Iturs Generator On-Line 447.6 6033 71592.5

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 621660 7749954.8 90356189.4

17. Gross Electrical Energy Generated (MWH) 209568 2603118 30259179

18. Net Electrical Energy Generated (MWH) 197398 2443437.3 28340074.3

19. Unit Service Factor 60.1 82.7 69.5

20. Unit Availability Factor 60.1 82.7 69.5

21. Unit Capacity Factor (Using MDC Net) 51.4 65.0 53.4

22. Unit Capacity Factor (Using DER Net) 49.2 62.2 51.2

23. Unit Forced Outage Rate 28.3 4.7 15.1

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

Refuel Outage currently scheduled for Hid-March, 1987 i

l

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

N/A 5h(9/77) 8611190074 861031 7

PDR ADOCK 05000331 R

PDR

AVERAGE DAILY UNIT POWER LEVE.

DOCKET NO. 050-0331 UNIT Duane Arnoid Energy Center DATE 11-15-86 COMPLETED BY Pradford N. Thones TELEPHONE 319-851-7309 MONTH October, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 0

3 0

19 57 4

0 20 236 5

0 21 404 6

0 22 452 7

0 23 526 8

0 24 535 9

37 25 539 10 100 26 546 11 359 27 536 12 477 28 525 13 467 29 531 14 533 30 531 15 361 31 533 16 13 INSTRUCTIONS On this format, list the average dslly unit power level in MWe-Net for each dsy in the reporting month. ComVJte tho nearest whole megawatt.

(9/77) i l

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UNIT SHUTDO"NS AND PO ER REDUCTIONS Occkot No. 050-0331 Unit Naco Durstn Arnold Energy Cot tor s

Da to 11/15/86 REPORT MONT H Octo ber, 1986 Comp l e ted by Bradford N.

Thomas Telephone 319-851-7309 m

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Continued plant shutdown to allow maintenance personnel access to primary containment (drywell) for repair of the Recirculation Pump Lube Oil System.

14 10/06/86 F

89 A

1 B0 PSF Plant startup was terminated due to steam leaks detected during the 400#

Reactor Vessel Drywell Inspection on the RFR Head Spray Line.

15 10/15/86 F

84.8 A

1 86-20 VI, KP-I S V-During a functional test of the (bntreil KP 33-111 Building Standby Filter Units the charcoal bed deluge system was inadvertently activated which rendere<l both trains of the standby filter uni s inoperab le. This required the plant no l

be placed in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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Method:

Exhibit G-I ns tructions S: Scheduled A-Equipment Failure (Explain)

I-Manual for Preparation of Da ta B-Maintenance or Tes t 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Au toma ti c Scram Event Report (LER) File ( NilR E G-D-Regu la tory Res tr i c ti on 4-Other ' Explain) 0161)

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D2ckct N2 050-0331 Unit Nwia Dun' Arnnld E' rgy C e :t ~ r,

Dzto 10-15-86 MAJOR / SAFETY RELATED MAINTENANCE Completed by Bra df or d N.

Thomas Telephone 319-851-7309 DATE SYSTEM COMPONENT DESCRIPTION 10-06-86 Rss i dua l Heat Removal (RHR) Head Hea d Spray Flange Connections Repaired steam leaks on head spray flange Spray connections di s covere d during the 400#

Reactor Vessel Drywell inspection.

10-14-86 Off-Gas Recombiner Drain Line Control valve Rewired Contro l Valve logic after enginearing ha d de t er m i n e d the valve was wire d for fsil open logic Instead of fall closed as de s i g n - d.

10-15-86 Control Bu i l di ng S tan dby Filter SFU Charcoal B e ds Rep lace d charcoa l be ds du e to an Ina dver tent deluge activation during preventative maintenance (LER 86-20).

10-18-86

'F' Average Power Range Monitor

'F' APRM Power Supply Replaced a faulty

'F' APRM Power Supply.

(APRM) 10-22-86 Drywell (D/W) Ra di at ion

'B' D/W Re di at ion Detector Dried out detector an d replaced protective Monitoring plastic w i n cb w.

High Pressure Coolant injection HPCI to Torus Suction isolation Repaired faulty DC shunt win dings in mo to r Valve operator (LER 86-22).

10-28-86 Sta n dby L iqu i d Control (SBLC)

'B' SBLC Pump Repacked pump.

Docket No. 050-033I Unit Name Dueno Arno l d Eneroy Center i

'"1 Dato 11-15-86 Comp lete d by Bra dfor d N.

Thomas Telephone 319-851-7309 REFUELING INFORMATION

)

1 Name of facility.

A.

Duane Arnoi d Energy Center 2

Sche du l e d date for next ref ueling shut down.

A.

March, 1987 3.

Sche du le d date for restart following refueling.

A.

May, 1987 4

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

Yes A.

Reload license submittel B.

Additional MAPLHGR curves for new fuel bun dies being I n tro du ce d for Cycle 9 5

Sche du l e d date(s) for submitting proposed licensing action and supporting Information.

A.

Submitted B.

Submitted 6

Important IIcensing const derations associated with refueling, e.g.,

new or di f f erent fuel de s i g n or supplier, unreviewed de s i g n or performance ana lys is metho ds, significant changes In fuel design, new operating p ro ce du re s.

None 7

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

A.

a) 368 b) 696 8

The present IIcensed spent fuel pool storage capacity and the size of any increase in license d 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 li censed capacity.

A.

1998

Docket Ns. 050-0331 Unit Nsco Dunno Arnold Encrav Cantor Dato 11-15-86 Co mp l e te d by Bradford N.

T ho ma s Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 10-1-86 At the beginning of the month the Duane Arnold Energy Center (DAEC) was in a continued ma intenance outage which had begun 9-22-86 10-5-86 At 1410 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.36505e-4 months <br /> Reactor Startup commenced fo llowing comp letion of the scheduled maintenance outage.

At 2354 hours0.0272 days <br />0.654 hours <br />0.00389 weeks <br />8.95697e-4 months <br /> personnel entered primary containment (Drywell) for the 400# Reactor Vessel pr es su r i zat io n wa l kdo wn.

10-6-86 At 0122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> Reactor shutdown was commenced due to steam leaks detected during the Drywell Inspection on the head spray co n n e c t io n flanges located on the vessel head.

10-8-86 At 2123 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.078015e-4 months <br /> Reactor startup commenced after successful i so l e t io n of the steam leaks on the head spray line.

At 2249 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.557445e-4 months <br /> the Reactor reached criticality and the head vents were c lo sed at 2326 hours0.0269 days <br />0.646 hours <br />0.00385 weeks <br />8.85043e-4 months <br />.

10-9-86 At 1819 hours0.0211 days <br />0.505 hours <br />0.00301 weeks <br />6.921295e-4 months <br /> the generator was syncrInized to the grid.

10-11-86 At 0951 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.618555e-4 months <br /> a 30 day LCO was entered when a reactor coo lant co n d u ct i v i ty mo n i to r wa s remo ved from service for preventive maintenance. A clogged filter was replaced and the unit was returned to service. The LCO was terminated at 1401 hours0.0162 days <br />0.389 hours <br />0.00232 weeks <br />5.330805e-4 months <br />.

10-14-86 At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> a 7 day LCO was entered when the

'B' Diesel Ge n e r a to r f uel oil transfer pump was declared i no pera b l e after falling ASME pump discharge requirements. The decrease in measured flow was determined to be related to test methods and Instrumentation limitations. A design change package is scheduled to Install a new f lo wmeter in the system and will allevlate test method errors. Plant Performance evaluated test results and determined that the minimum f lo w requirements were above the UFSAR l i m i ta t io n s. The LCO was terminated at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />.

10-15-86 At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO was entered and plant s h u tdo wn commenced when both Standby Filter Units (SFU) were declared inoperable.

Technicians performing preventive maintenance Inadvertently activated The charcoal bed deluge system.

This was caused by a procedural deficiency which did not alert technicians to reset the system after co mp let ion o f the preventive maintenance being performed. The main generator was removed from service at 010 5 ho u r s o n 10-16-86 and the plant was in co l d sh u t do wn at 1047 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.983835e-4 months <br />.

The charcoal was changed out and the system was returned to service after successful post maintenance testing.

Reactor startup then co mm e n c e d at 0625 hours0.00723 days <br />0.174 hours <br />0.00103 weeks <br />2.378125e-4 months <br /> on 10-18 The Maln Generator was syncronized to the grid at 1336 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.08348e-4 months <br /> on 10-19-86 (LER 86-20).

e Docket No. 050-0331 Unit Nams Duene Arnol d Energy Center Date 11-15-86 Comp lete d by Bra dfor d N.

Thomas Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPER I ENC E 10-19-86 At 1523 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.795015e-4 months <br /> operations tripped the main turbine with reactor power at 16% due to high con den ser vacuum.

The steam Jet air ejector drain traps were Isolated which in turn lowered con denser vacuum.

The main turbine generator was then returned to service at 1758 hours0.0203 days <br />0.488 hours <br />0.00291 weeks <br />6.68919e-4 months <br />.

10-20-86 At 1121 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.265405e-4 months <br /> the Reactor Water Cleanup (RWCU) system isolated due to a high temperature signal from the non-regenerative heat exchanger outlet temp.

Investigation revealed that a worker had i na dverten t l y mispositione d a temperature Indicating controller setpoint dial du r i n g de co n t a m i r. a t i o n. The RWCU system was returned to service at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on 10-20-86 (LER 86-21).

At 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> a 30 day LCO was entered when a reactor coolant co n du ct i v i ty monitor was removed from service to replace a clogged filter.

The LCO was terminated at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on 10-21 with the monitor being returne d to service.

10-21-86 At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> a7 day LCO was entered when a Drywell Ra di at ion Monitor was determine d to be rea ding dow n s ca l e.

The de t e c to r was found wet an the protective window was cracked.

The detector was dr ie d ou t, and a new pl ast ic win dow was I n st a l l e d.

The LCO was terminate d at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> on 10-22-86 with the monitor being returned to service.

10-22-86 At 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> a 7 day LCO was entered w5en High Pressure Coolant injection (HPCI) system was dec l ar e d Inoperable after unsuccessful completion of the annual HPCI Actuation Logic Functional test.

The Torus supply stop valve di d not fully open du r i n g stroking.

Investigation revealed burned series f iel d win dings.

The motor was sent offsite for repair and HPCI was then returned to service after successful post-maintenance testing at 1318 hours0.0153 days <br />0.366 hours <br />0.00218 weeks <br />5.01499e-4 months <br /> on 10-25-86 (LER 86-22).

At 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> a 7 day LCO was entered when the

'B' SFU was dec l are d inoperable as the heaters continually tripped of f on high temperature.

An electronic controller was reset and the heaters returned to service.

The LCO was terminated at 2153 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.192165e-4 months <br /> on 10-24-86 10-25-86 At 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> the

'A' Loop River Water Supply pumps f ailed to meet ASME discharge requirements.

A 7 day LCO was ent er e d.

Plant Performance engineers evaluated the ASME reference data an d recommen ded new reference points be used.

This was deci de d af ter or igina l test results were determined to be well above the pump manufactures curve end both pumps were deliver ing above the Tech Spec requirements. The

'A' RSW pumps were declared operable at 2053 hours0.0238 days <br />0.57 hours <br />0.00339 weeks <br />7.811665e-4 months <br /> thus cancelling the LCO.

i

__-,.a.-

- v.-

e-Dacket No. 050-0331 Unit Naso Dunno Arnold Energy Center Date 11-15-86 Completed by Bradford N.

Thomas Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 10-27-86 At 0716 hours0.00829 days <br />0.199 hours <br />0.00118 weeks <br />2.72438e-4 months <br /> a 30. day LCO was entered when the off-gas rad i atio n detector (Kaman No. 10) was found to have a lo w so u r ce response.

The sensor was recalibrated and the LCO was terminated 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> o n 10-29-86 with the mo n i to r being returned to service.

10-29-86 At 0524 hours0.00606 days <br />0.146 hours <br />8.664021e-4 weeks <br />1.99382e-4 months <br /> a 7 day LCO was entered when the

'B' Standby Liquid Co n t ro l (SBLC) pump was remo ved f rom service due to a packing leak.

The pump was repacked and returned to service at 1858 hours0.0215 days <br />0.516 hours <br />0.00307 weeks <br />7.06969e-4 months <br /> on 10-31-86.

The LCO was then terminated.

At the end of the month the DAEC was operating at 100% of rated power with 563 MWe Net being provided to the grid.

In add i t io n, fifty-six (56) fuel bundles for the cycle 8/9 reload out of one hundred and twenty-eight (128) were delivered t hro ug ho u t the mo n t h of October and were being stored on the refuel f loo r.

k l

L

T F

Iowa Electric Light and Power Company November 15, 1986 DAEC-86-0836 Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Comission Washington, D. C.

20555 Attn: Document Control Desk

Subject:

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

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for October, 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 ours, II/t+h:.,

Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/BNT/bj*

Enclosures File A-118d cc: Director, Office of Inspection 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. R. Gilbert Corn Belt Power Cooperative Phillips Building 1300 13th Street North Washington, D. C. 20555 Humboldt, IA 50548 INP0 Records Center l

1100 Circle 75 Parkway

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Suite 1500 I

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Atlanta, GA 30339 Duane Arnoki Energy Center

• 3277 DAEC Ik>ad

• Palo, Iowa 52324 *319A317G1I