Text

Monthly Operating Rept for Mar 1986
	ML20155F130
Person / Time
Site:	Duane Arnold
Issue date:	03/31/1986
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-86-0257, DAEC-86-257, NUDOCS 8604210340
	Download: ML20155F130 (9)
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OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 04-15-86 COMPLETED BY Bradford N. Thomes TELEPHONE 319-851-7309 OPERATING STATUS Notes

1. Uni t Name Duane Arnold Energy Center

2. Reporting Period March, 1986

3. Licensed Thermal Power (MWt):

1658

4. Nemoplate Rating (Gross MWe):

565 (Turbinel

5. Design Electrical Rating (Not MWe):

5 38

6. Meximum Dependable Capact ty (Gross MWe):

545

7. Maximum Dependable Capacity (Not MWe):

515 8.- If Changes occur in Capacity Ratings (i tems 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 Month Yr-to-De to Cumu la ti ve

11. Hours in Reporting Period 744.0 2160.0 97848.0

12. Number of Hours Reactor Was Critical 350.8 1766.8 69088.7

13. Reactor Reserve Shutdown Hours 0

0 150.3' 14.' Hours Generator On-Line 344.1 1760.1 67319.6

15. Unit Reserve Shutdown Hours 0

0 0

167 Gross Thermal Energy Generated (MWH) 457795 2141016 84747250

17. Gross Electrical Energy Generated (MWH) 156539 732495 28388556

18. Not Electrical Energy Generated (MWH) 14 7219 687491 26584128

19. Unit Service Factor 46.3 81.5 68.8

20. Unit Availability Factor 46.3 81.5 68.8

21. Unit Capacity Factor (Using MDC Net!

38.4 61.8 52.8

22. Unlt Capacl ty Factor (UsIng DER Not) 36.8 59.2 50.5

23. Unit Forced Outage Rate 0

0 15.6

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

25. If Shut Down At End Of Report Period, Estimated Date of Startup: April 6, 1986 0 860331 (9m)

R K 0%331 5e&

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 UNIT Duane Arnold Energy Center DATE 04-15-86 COMPLETED BY Bradford N. Thomes TELEPHONE 319-851-7309

.' MONTH March. 1966 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-No t)

(MWe-Not) 1 406 17 0

2 4 12 18 0

3 445 19 0

4 443 20 0

~ 5 443 21 0

6 445 22 0

7 448 23 0

8 442 24 0

9 4 29 25 0

10 44 7 26 0

11 448 27 0

12 445 28 0

13 447 29 0

14 399 30 0

15 33 31 0

16 0

INSTRUCT IONS On this format, list the average dally unit power level in MWe-Net for each day in the reporting conth. Compute the nearest whole megawatt.

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a D;ckrt Na, 050-0331 Unit N x o D e^

Arc,1d E~'rgy C e ^ te v-Date 04-15-86 MAJOR / SAFETY RELATED MAINTENANCE Comp l e ted by Bradford N.

Thomas Telephone 319-858-7309

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DATE SYSTEM COMPONENT DESCRIPTION 03/11/86 Reactor Core isolation Cooling RCIC Sy s tem S ta ti c i n ve r ter Replaced f aul ty RCIC tu r b i n e / p ump I n i tia tion (RCIC)

(BN-INVT-K603) and control i ns tr umen ta ti on s ta t i c inverter (LER 86-05) 03/15/86 Safety Related Motor Operators Limitorque Motor Operators inspection and replacement of Limitorque Motor Operator Internal wiring to ensure compliance w i th Environmental Qualification (EQ) S ta n da rd s 03/17/86 Sa f e ty Re la ted Sys tem Mechanical Mechanical Snubbers Mechanical Snubber visual Inspection Snubbers S tand by Diesel Generator Standby Diesel Genera tor S ta n d by Diesel Generator Annual Inspection (EK-DG-1G-31)

Tranverse incore Probe (T IP)

TIP

'C' Ball Valve 9emoved Inoperable Ball Valve (LER 86-03) 03/22/86 Standby Diesel Generator Standby Diesel Generator Standby Diesel Generator Annual Inspection (EK-DG-1G-21)

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' s Dacket No. 050-0331 Uni t Name Duane Arnold Energy Cen ter Da te 04-15-86 Comp l e te d by Bradford N. Thomas Telephone 319-851-7309 REFUELING INFORMATION 1

Name.of facility.

A.

Duane Arnold Energy Cen ter 2

Scheduled d a te for next ref ueling shu tdown.

A.

February, 1987 3.

Scheduled da te for res ta r t following refueling.

A.

April, 1987 4

Will refueling or resump tion of operation thereaf ter require a technical speci f ica tion change or other license nmendment?

A.

None currently I den ti f l ed 5.

Scheduled da te ( s ) for submi tting proposed licensing action and supporting information.

A.

None currently i den tl f lod 6

I mpor ta n t licensing considera tions as soc i a ted w i th refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance ana lys is methods, significant changes in fuel design, new opera ti ng procedures.

None 7

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

A.

a) 368 b) 696 8

The present licensed spent fuel pool s tora ge capac i ty and the size of any increase in licensed storage capacity tha t has been reques ted or is planned, in number of fuel assemblies.

l A.

2050 9

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

A.

1998 l

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?b-Docket No. 050-0331 Uni t N3eo Dunne Arnold Energy Cen ter Date 04-15-86 Completed by Bradford N. Thomas Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE

-03/01/86 At the beginning of the mo n th the Duane Arnold Energy Center was in normal power opera tion wi th 406 MWe (not) being provided to the Grid.

03/04/86 At 0450 hours0.00521 days 0.125 hours 7.440476e-4 weeks 1.71225e-4 months a 7 day LCO was entered when the Diesel Fire Pump was removed from service to' replace a leaking gasket in th e flow con trol valve.

The LCO was termi n a ted a t 2045 hours0.0237 days 0.568 hours 0.00338 weeks 7.781225e-4 months when the Diesel Fire Pump was restored to service.

03/10/86 At 1908 hours0.0221 days 0.53 hours 0.00315 weeks 7.25994e-4 months a Class

'C' fire was discovered in wiring providing power to temporary electric heaters in the partially completed new Radwaste Building.

The Fire Brigade promp tl y responded and extinguished the fire with ope ra tions securing the power supplies. A reflash watch was es tablished at 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months w i th the Fire. Brigade being secu ed at th a t time.

03/11/86 At 1823 hours0.0211 days 0.506 hours 0.00301 weeks 6.936515e-4 months a 7 day LCO was antered when ths Elec tric Fire Pump was removed from service to perform the Electric and Jockey Fire Pump inspection. The LCO was termi n a ted at 1805 who the Elec tric F ire Pump was returned to serv i ce.

At 204 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months a 7 day LCO was entered when the RCIC turbine / pump initiation and control power sta tic inverter was found not to be providing ou tput power,- rendering the RCIC sys tem inoperable. The suspect Inverter was replaced and tes ted sa ti s f ac torily. The sys tem was returned to service and th e 7 day LCO was term i na ted on 03/12/86 a t 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

(LER 86-05) 03/13/86 At 1655 hours0.0192 days 0.46 hours 0.00274 weeks 6.297275e-4 months the RWCU sys tem i s o l a ted on a high dif f eren tial flow condition while placing the

'B' filter domineralizer into service following a resin precoat process. As part of a con ti nu l ng i nves ti ga ti on ef f ort another a ttemp t was made to p lace

'B' filter domineralizer system into sa vice.

RWCU again isolated at 1802 hours0.0209 days 0.501 hours 0.00298 weeks 6.85661e-4 months .

It was concluded there was a bonaffde sys tem leakage.

During a scheduled plant shu tdow n in mid-March a gasket in the f i l ter deelnerallzer tank was replaced which secured the leak.

(LER 86-06) 03/14/86 At 1220 hours0.0141 days 0.339 hours 0.00202 weeks 4.6421e-4 months the HPCI s y s tem, during a newly developed Tes t Procedure (Cold / Quick HPCl Start), did not reach full flow condiflons until slightly after 29 seconds. The Tes t Procedure accep tance criteria and UFSAR call for reaching full flow wi th i n 25 seconds. Consequently HPCI was declared inoperable and a 7 day LCO commenced.

"Duane Arnold Energy Cen ter Power Uprete including trans ien t and accident analysis ba s i s, " (which has been approved by the NRC as the uprate licensing basis) s ta tes tha t the " maximum

4' Dac ko t No. 050-0331 Uni t Nsmo Dunno Arnold Energy Cen tnr Da te 04-15-86 Comp l e ted by Bradt grd N. Thomas Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERAT ING EXPERIENCE f

03/14/86 allowed delay time from I n i ti a ti ng signal to rated flow available and (Co n t. )

Injection valve open" is 30 seconds.

Add i tiona l ly, GE HPC1/RCIC Sys tems Engineers, s ta ted tha t the 29 second s tart time was not Indica tive of system degrada tion and tha t the slower time was probably a result of s ta r t i n g from cold conditions. To confirm this analysis, a second HPCI s tar t was performed before the sys tem cou ld cool down and the time to full flow was consistent w i th previous tes ts.

'Given this analysis it was concluded tha t HPCl was capable of fulfilling i ts safety function. The LCO was cancelled on 03/16/86 a t 0129 hours0.00149 days 0.0358 hours 2.132936e-4 weeks 4.90845e-5 months when the plant entered the cold shu tdown condition in prepara ti on for a ma i n tena nce ou tage.

At 1840 hours0.0213 days 0.511 hours 0.00304 weeks 7.0012e-4 months operators began reducing reactor power in anticipation of a scheduled maintenance ou ta ge.

03/I5/86 At 0807 hours0.00934 days 0.224 hours 0.00133 weeks 3.070635e-4 months the Mai n Genera tor was removed from the Grid.-

At 1318 hours0.0153 days 0.366 hours 0.00218 weeks 5.01499e-4 months during reactor shutdown for a scheduled main tenance ou tage a "RHR SYSTEM i & il DISCHARGE HEADER Hl/LO" annuncia tor was receiveJ. A RHR flow control valve was closed to i sol a te back leakage from a RHR outboard I so l a ti on/LPC I Inject valve.

Based on design Information available in th e Con tro l Room i t was de termined tha t w i ti MD-2003 and MO-2004 closed and a LOCA or LOOP-LOCA signal being received th e Diesel Gene ra tors feeding bus IA3 or IA4 would be subject to over load i ng.

Therefore, the LPCI sys tem was appropr ia te l y declared inoperable and a 7 day LCO commenced.

An Analysis just completed Indicated tha t replacement of particular RHR/LPCl Motor Operators (MO) performed during the cycle 8 ref ueling ou tage have less combined loading on the bus.

Therefore the proposed lineup of having both valves closed is accep table for power opera tion.

The LCO was cancelled on 03/16/86 a t 0129 hours0.00149 days 0.0358 hours 2.132936e-4 weeks 4.90845e-5 months when the plant entered the cold shutdown cond i tion in prepara ti on for a ma i n tenance ou tage.

At 14 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months the reactor was sub-critical.

At 1723 hours0.0199 days 0.479 hours 0.00285 weeks 6.556015e-4 months the RCIC sys tem I sol a ted wi th the reactor in shutdown modo a t 0% reactor power and above 150 psig.

At the time of th e isol a tion, a daily test procedure which monitors temperatures and tempera ture dif f erentials in the RCIC Steam Leak De tec ti on System was in progress.

A spurious signal crea ted when placing a tempera tu re dif f erential sw i tch in the READ posi tion was considered the cause of the Isola tion signal. The RCIC isolation was promptly reset.

(LER 86-07) 03/16/86 A t 0129 hours0.00149 days 0.0358 hours 2.132936e-4 weeks 4.90845e-5 months the Reac tor Head Ven ts were opened which placed the plant in a Cold Shu tdown condition.

03/17/86 A t 0714 hours0.00826 days 0.198 hours 0.00118 weeks 2.71677e-4 months the Saf ety Rela ted Mechanica l Snubber Visual Inspections commenced.

At 0728 hours0.00843 days 0.202 hours 0.0012 weeks 2.77004e-4 months th e

'A' S tandby Diesel Generator Annual I n sp ec ti on commenced.

r 2

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Docko t No.. 050-0331 Uni t Ncco Dunna Arneio Ennrgy Cont r Dato 04-15-86 Completed by Bradford N. Thomas Telephone 319-851-7309 7

NARR AT I VE

SUMMARY

OF OPER AT I NG EXPERI ENCE 03/18/86 At 0721 hours0.00834 days 0.2 hours 0.00119 weeks 2.743405e-4 months a faulty

'C' tip ball valve was removed which had been removed from service (left in the open 'pos i tion) since 01/04/86 On 01/04/86 an additional ball valve was placed in series wi th the f au l ty one.

(LER 86-03) 03/22/86 At 0804 hours0.00931 days 0.223 hours 0.00133 weeks 3.05922e-4 months the

'B' S ta nd by Diesel Generator Annual inspec tion commenced.

03/25/86 The

'B' Channel of the RPS sys tem was in the tripped condition as expected l

.due to a 24 VDC battery discharge tes t in progress. At 1305 hours0.0151 days 0.363 hours 0.00216 weeks 4.965525e-4 months a spurious signal was received on RPS Channel

'A' which in turn resulted in a full RPS trip.

The RPS trip was reset lemedia tely wi thou t recurrence.

Since all rods were fully in, no rod movement took place.

The causa of th e l

'A' side trip is believed to h a v e been a spurlous electrical spike genera ted

[

by ou tage ac tivi ti es.

l (LER 86-08)-

-03/27/86 At 1909 hours0.0221 days 0.53 hours 0.00316 weeks 7.263745e-4 months during Steam Line High Rad i a tion instrument Calibra tion, a gamma source was placed too close to two (2) instrument channels at th e same time which resu l ted in a full RPS trip.

The likelihood of this trip is I

specified in the Ca li bra tion Tes t Procedure. Opera tors were aware of the j

high proba bil i ty of generating a trip in more than one in s trumen t channel.

Because of this high proba bi l i ty of a RPS trip, th is even t is considered proplanned.

03/29/86 At 0959 hours0.0111 days 0.266 hours 0.00159 weeks 3.648995e-4 months wi th the reactor in shutdown, an unplanned 1/2 Group til f

iso la ti on, and an au to s tar t of the

'A' Standby Gas Trea tment Sys tem were I n i ti a ted by a downscale trip of the

'A' Reactor Building Exhaust l

Ven tila tion Radia tion Moni tor.

The'downscale trip was a result of I

Inadvertently doenergizing a circuit in order to perf orm, unrel a ted maintenance.

(LER 86-09) l 03/31/86 At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months the Saf ety/Ref lef Valve which had inadverten tly opened on 02/07/86 successfully passed its operability tes t following power cable replacement.

At the end of the mon th the DAEC was in the final s tages of a Mai n tenance/ Surveillance Tes t Outage.

Planned Reactor S tar tup was scheduled I

for 04/06/86 f

l 1

l L

h

/

Iowa Electric Light and Power Company April 15, 1986 DAEC 0257 Cirector, 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 March, 1986 Monthly Operating Report

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for March, 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, Daniel L. Mineck Plant Superintendent - h" clear Duane Arnold Energy Cente-DLM/BNT/pl*

Enclosures File A-118d, TE-5 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, O. 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)

Marion, IA 52302 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 Suite 1500 p /,

Atlanta, GA 30339

[

l I IJuane Arnolel Energy Center

3277 I).1EC linatl

l'alo, Iowa.5232.s

319 MI-761I

-

ML20155F130

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