ML20011D590

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Nov 1989 for Duane Arnold Energy Ctr
ML20011D590
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 11/30/1989
From: Hannen R, Tran H
IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
DAEC-89-0888, DAEC-89-888, NUDOCS 8912280042
Download: ML20011D590 (7)


Text

1 c

p.

Iowa Electric Light and Power Company December 15, 1989 DAEC-89-0888 Mr. A. Bert Davis Regional Administrator Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Subject:

Duane Arnold Energy Center Docket No:

50-331 Op. License DPR-49 November.1989 Monthly Operating Report-

Dear Sirs:

Please find enclosed the Duane Arnold _ Energy Center Monthly Operating Report for November, 1989. 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, Section 6.11.1.c.

Very trul yours,

,h

_,=, -> t 2 -W 8' 7 Rick L. Hannen Plant Superintendent - Nuclear RLH/gt+

Enclosures File A-118d cc: U P/S PNRC m Mr. William t.oveless w

ATTN: Document Control Desk U.S. NRC Washington, D. C.

20555 Maryland National Bank Building Mail Stop 7602 Mr. J. R. Hall Washington, D.C.

20555 (2)

Project Manager 1 Whiteflint North

.NRC Resident Inspector-1 1

Mail Stop 13E21 11555 Rockville Pike Mr. Dennis Murdock Rockville, MD 20852 Central Iowa Power Cooperative Box 2517 l,

INPO Records Center Cedar Rapids, IA 52406 1100 Circle 75 Parkway Suite 1500 Mr. Russ Gamble-

)

Atlanta, GA 30339 Corn Belt Power Cooperative 1300 13th Street North Mr. Steve Brown Humboldt, IA 50548 lowa State Utilities Board Lucas State Office Building i

Des Moines, IA 50319 a

ceneral office

  • r.o. Box ss1 cedar aspids. rows s2tos. stsisse 44ss 8912280042 891130 DR ADOCK 0500 1

.. = -

e 3

OPERATINS DAfd REPett I

DOCKET NO.

616 6111 patt : Fin-av COMPLETED BY iC ".ran l

TELEPHONE XIT am1-yevi OPERATING STATUS Notes 1

1. Unit Name

- 6 maid L=a. cantar j

2. Repertins Porled u= - " - - i ta t
3. Lleensed Therest Power (leftle 16&a
4. Nameplete Reting (Scoes lafels 165 (Turt.inal
5. Design Electrieel Reting (Not thsel RBa
6. Monieue Dependable Cepecify (Seets P4fe):

A&E

7. Meuleue Dependable Cepenity (Not MWols saa
4. If Changee Deeur in Capesity totanos (Itena Number 3 through 7) $inee the Lost Report, Save Reesens: N/A i

1

9. Power Level to Which Restricted, If Any (Not MWel: N/A
10. Reseems for Restrictione, If Any: N/A l

i This Month Vr to Dete Cumulative

11. Hours in Rooerting Period

___ 729.9 asia.t 116888.0

)

12. Number of Hours Reacter Wes Critteel 121.3 6176.9 9119E. 4
18. Reacter Reserve Shutdown Hours a

9 192.a

14. Heure Genereter on Line rae.s sant.1 ea463.7
15. Unit Reserve Shutdown Neurs 9

e__

t

16. Dress Thereal Energy Generated (MitH)

.487229.6

.8a21846.2 liaa61s14.a r

17. Gross Electrieel Energy Generated (MWM) 137572.0 2946821.0 19926249.8
18. Not Electrieel Energy Generated (MWM) 124681.3 2781954.6 17571228.6
19. Unit Servloe Facter 39.5 72.6 69.6 to. Unit Availah111ty Foster 39.5 72.6 69.7
21. Unit cepeelty Fester (Using pec Net) 12.2 as.a ss.4
22. Unit Copa:1ty Facter (using DER Not) 12.2 63.a-53.4
23. Unit Forced Outage Rete 12.4 la.9 14.s
24. Shutdowns Seheduled Over Next 6 Nonths (Type, Dete, and Durellen of each: Mana
25. If Shutdown et End of Report Perled, Est. Date of Stortwo t-(9/77) i 1

I e

e a-

-.--e.-n--..

v,-

1 AVERADE DAILY UNIT POWER LEVEL DOCKET NO.

618 e111 DAff 12-m-av l

i COMPLFitD sv uni 'ran

(

ftLEPMOIE tus ' ami 7evi j

MONTH Nsr. - ^

1989 DAY AVERAtt DAILY POWER LEVEL DAY AVERAM DAILY POWER LEYtL j

(Mue-Met)

(Mue Neti

'i 1

114 16 8

2 EIS 17 8

3 au 13 e

4 str 19 e

189 20 e

i 6

111 21 e

7 112 22 e

4 499 23 4

9 il 24 199 le e

2$

M9 1

11 e

26 199 12 e

27 e

13 e

28 8

14 e

29 e

18 a

30 the 31 h/A r

1 k

(

l l

~.

Docket No.:

958-8331 Unit: Duane Arnold Enorey Center UNIT SHUTDOWNS AND POWER REDUCTIONS Dete 12-15-89 Car,Ieted By: Nei Tran REPORT MONTH: November 1989 Telephone:

(319) 851-7491 I

l l

l l

l Method of I Licensee i System l Comp.I 1

i l

l Duration i I Shuttins (3) i Event l Code I Code i I No. I Date l Type (131 (Hours) l Reason (2)l Down Reactor i Report 8 l (4)

I (5) l Cause 1

I I

l l

i I

l.__

l I

I I

I I

I I

I l

I i

1 1 11-8-89 i S/F 338.02 l B

i 1

1 N/A I N/A I N/A IThe reactor was shutdown for i 1

i i

l i

I I

I feeintenance on a NPCI check i

i l

l l

l l

l l

l Ivalve.

The valve was 1

1 l

l 1

i l

i l

I lexperiencine excessive i

I l

l l

l I

I I

l1eakmee theeuch the bonnet l

l l

l l

I I

I feesket. The valve was l

l 1

1 I

I I

I Irepaired and returned te 1

l l

l l

I I

leervice prior to startup.

I i

l i

l i

l i

I IThe eutage was extended due i

l 1

l l

l l

1 1

Ito a failure of T seet en og l

l l

l l

l l

l l Primary Centainment Isolation l

l 1

l l

1 1

I I

Iwelve.

The extention is l

l 1

l 1

I I

I

{ considered a forced outase.

i l

l I

l l

I I

I I

I2 l 11-26-89 1 F

l 81.39 A

i 1

l N/A I N/A l N/A IThe reactor was shutdown i

I l

l l

1 I

I I

Idurine startup due to a

(

l l

l l

l l

l i

1 Ipressure relief valve en the l I

l I

l l

I I

I I

lana mein steam line momentar-l l

I I

i 1

1 I

I I

lily openine twice.

The volvel i

I I

I I

I I

i 1

twas repaired and returned to i l

l l

l l

l l

l l

Iservice.

I I

i i

1 I

I I

l l

I I

i 1

1 I

i 1

I I

I I

I I

I I

I I

I l

8 I

I I

I I

I I

I I

I I

I I

I l

l l'

I I

I I

I I

I I

I i

l i

I I

I I

I I

I I

I I

I I

I I

I I

I I

I i

i i

I i

i I

I i

l l

l l

1 1

1 I

l I

i 1 - F: Forced 2 - Reesen:

3 - Method

+ - Exhibit G-5:

Scheduled A-Eguipment Failure (Explain) 1-Menval Instructions for B-Meintenance or Test C-Refueline 2-Manual Scram Preparation of Bate 3-Automatic Scram Entry Sheets for D-Regulatory Restriction 4-Continued Licensee Event Report E-Operator Training S License Examination 5-Reduced Lead (LER) File (NUREG-F-Administrative 9-Other (Explain) 8161)

G-Operational Error (Explain)

H-Other (Explain) 5 - Exhibit I-Same Source (9/77)

Docket No.:

CSS-0331 Unit: Duane ArneId Enerey conter MAJOR / SAFETY RELATED MAINTENANCE Date:

12-15-89 Completed By: Mai Tran Telephone:

(319) 851-7491 I

t DATE I

SYSTEM l

COMPONENT I

DESCRIPTION l

l I

I 4

I 11-03-89 l Steam Leak Detection System.

l l A concern was raised w2th the posssble i

l l

l I interaction between SL9S and the Fire l Suppression Subsystem deluge function for l

I l

l I HPCI and RCIC eesuipeent rsome.

It appeared l that an initiation of the deluge system I

l i would prevent the SL9S automatic isoletion i

l i from occurring due to the deluge system I

l I having a lower temperatuee setpoint. The i

l I

l I delvoe system was isolated and modifications,

l were initmated.

I l

I 11-98-89 i High Pressure Coolant l Check Valve i MPCI check valve was experiencine excessive l Injection System I

l leak age. The condition did not affect NPCI i

l I

I l operability.

i 11-18-89 l Turbine Main Steam Line i Valve i Four turbine control valves were repaired l

l I

I 1 for excessive leakage.

I 11-21-89 i Standby Ges Treatment System i Isolation Valve i A drywell exhaust isolation valve failed I

l i LLRT. The "T" seel in the valve was fewnd l

I l broken.

The valve was repaired and returned.

l l

1 to service.

I I

i 11-26-89 l "B" Main Steam Line l Valve l

I I lhe pressure relief valve on "B" Mein Steam I

l I Lane momentarily lifted twice.

The plant i

l was shutdown to repair the valve.

I I

f I

I I

I I

I I

I I

I I

i i

I I

1 l

l l

1 I

l 1

I I

i i

i I

j i

l I

I I

(

l i

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I l

i I

I I

I I

I i

1 I

I I

I I

l l

4 REFUEL 2006 IteFonpIATION i

DOCKET 800.

RAa eni i

DATE '2 in"ren ev COnyttTED BY liti TtLtPsesset nv azi-74vi i

)

1.

Mees of feellity, s.

Duane Arnold Ensegy Center 2.

Seheduled este for neat refueling shuteoun.

1 e.

June,1990 3.

Scheduled date for restert following refueling.

4 I

)

e.

August, 1990 4

Will refueling or resumption of operation thereaf ter require a

]

technical specification ehengo or other 11oenee seenementf slo 5.

Schoeuled esteIei for subeitting proposed 11 censing oction end supporting inforestten 6.

Important atoonsing eensteoretions esseeletoe with refueling, e.g., new i

or elfforent fuel eesten er supplier, uneeviemos design or perfereenee enelysis methoes, signifloent ehenges in fuel cosign, new operating procedures.

l We will be getting et le fuel.

7.

i The number of fuel assemblies to) in the core and (b) in the opent fuel etorage pool.

e.

364 b.

944 L

4.

The preeeni 11coneed opent fwel peel eiorese cepec1ty and ihe etae ef r

increase in 11oeneed storego especity that has been roguestee or is eny planned, in number of fuel assemblies.

a.

tele - Licensed Cepec4ty or a

b.

leto under the proeent1y ineielled eiorage eook espec1ty.

l l

9.

The projected dote of the last refueling that een be discharged to the seent iuol pool easueing the prosent 11conmed cepeeity.

a.

2000 Llooneed Cepeelty or b.

1997 under the presently installed storage reek cepecity.

1 4

a t

.. ~ _

_ _ _ _.~

4 I

t IIARRATIVE SupptARY OF OPERATIIIS EXPERIEtICE i

l j

DOCKET Dep. gas sM1 DATE iz IJ6-er i

C0pePLETED BY nel ren TELEP90000E tz1v ami 7egi l

11 01 89 At the beginnine of the month the plant was operating et 100% of rated thereal j

power with 534 #Roo not being eglivered to oustomers connected to the prie. There were three reportable events curing the month.

l 11 0$*89 with the plant speesting et 100% power, the long toes operability of the reeutred Stees Leak betection System (SLD&l eroe tempeesture auteestie f eeletten for the Nigh Pressure Coelant Injection and Reester Core Isoletten Cooling erees were 4

euestioned.

The eeneern reisted to the possible interaction with the Fire Sworession deluge function for the roepective feuipment Rooms. It espoored that the SLDS automatic isolation would not oooser. Subseeuent eyelvetion concluded that en inattetten of the celues in either room could prevent the teoletion from i

ocourring et certain steso Isakage rates. The root cause appears to be e look of s.comunloetten between engineering dieciallnes during plant eenstruction. Planned corrective action will modify both room's celuge.

(LER 89 014) 4 1

11*04 49 At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> the plant someewed to shutdown the reactor for various maintenance l

teoksllen volve were repaired during this eutage.feue turbine control velves, and a drywell exhaust A MpCI cheek volve, isole l

11 15-89 with the plant in sold shutdown, e Primary Containment lastetton Systes group V i

isoletten coeurred. Group V is the Reactee efeter Cloenup (RefCU) system isoletten.

r The isoletten oceurree due to a high dif ferential flew eendition of greater then 3

i et esig for esce than le seconds.

It is suspected that the seuse for the extenced i

dif ferential flew eenditten was e combinetten of the reactor being at steo rie presouro combined with an air bubble within the "A" filtee desinere11 ace.

i The system was unteeleted approulmetely three minutes later, and pleoed book in servloe with both filter deelneralisers in servloe. lee further problems were enseunters.

(LER 89 015) i l

11 15 49 Annual audits of the vender screening progrees determined employees of three 4

veneers had been granted unescorted access with incomplete screenings. Aeoess was granted following notifteetion free the vendors that the screening has been coupleted.

I (LER 49 801) 11 23 49 At 0551 hours0.00638 days <br />0.153 hours <br />9.11045e-4 weeks <br />2.096555e-4 months <br /> the plant commenced rosetor startup. At about 2121 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.070405e-4 months <br />, the sein I

generator was, connected to the grid enri distributing a load of SS Phoe-net.

11 26 89 At 0909 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.458745e-4 months <br /> with the reacter operettag et 72%, the plant commenced reactor

?

shutdown eue to the pressure relief velve on "B" esin steen line somentarily lifting twice.

11 28 89 At 0054 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />, the plant entered a 7 eer LCO ese to the Fire Proteetion Pump (Wiesel deivoni f aillne during a survo111ence ieet.

The LCO was eenoelled on 12 4 89 et 2256 hours0.0261 days <br />0.627 hours <br />0.00373 weeks <br />8.58408e-4 months <br /> witfi the ouseessful repete of the fire pump.

11 29 89 At telt hours, the plant oeamenced pulling control rods for reacter startup. The reester beoemo critteel at 0523 hours0.00605 days <br />0.145 hours <br />8.647487e-4 weeks <br />1.990015e-4 months <br />.

On 11 50 89 et 0844 hours0.00977 days <br />0.234 hours <br />0.0014 weeks <br />3.21142e-4 months <br />, the-esin genereter wee eennected to the grid.

7 11 30 89 At tae and of the month the plant was operating et 55% of rated theresi power delivering 240 ftse not to customers connected to the grid.

l i

L

.. ~.,, -

, < _ - ~,.. _ - - - - _ - - - - - -. _ -

~ - - -

-a