ML20215F572

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Nov 1986
ML20215F572
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 11/30/1986
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-86-0986, DAEC-86-986, NUDOCS 8612230456
Download: ML20215F572 (8)


Text

-

OPERATING DATA REPORT DOCKET NO. 050-0331 l

' DATE 12-15-86 i

COMPLETED BY Bradford N. Thomes TELEPHONE 319-851-7309 OPERATING $TATUS l

Notes

1. Unit Name Duane Arnold Eneroy Center
2. Reporting Period November, 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 MWer 54 5
7. Maximum Dependable Capacity (Not MWe):

515

8. If Changes Occur in capacity Ratings (ltems 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-Date Cumu lat ive

11. Hours in Reporting Period 720 8016 103704
12. Number of Hours Reactor Was Celtical 720 6902.8 74224.7
13. Reactor Reserve Shutdown Hours 0

42.5 192.8

14. Hours Generator On-Line 720 6753 72312.5
15. Unit Reserve Shut &wn Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1132810 8882764.4 91488999.4
17. Gross Electrical Energy Generated (MWH) 393835 29 % 953 30653014
18. Not Electrical Energy Generated (MWH) 371913 2815349.8 28711986.8
19. Unit Service Factor 100 84.2 69.7
20. Unit Availability Factor 100 84.2 69.7
21. Unit Capacity Factor (Using MOC Net) 100 68.2 53.8
22. Unit Cipacity Factor (Using DER Net) 96.0 65.3 51.5
23. Unti Forced Outage Rate 0

4.2 15.0

24. Shuthwns Scheduled 0ver Next 6 Months (Type, Date, and 0uration of Each):

Ref uel Outaae scheduled for Mid-March. 1987 8612230456 861130 PDR ADOCK 05000331 R

PDR

25. If Shut Down At End of Report Period, Estimated 0 ate of Startup N/A f Y' (9/ 77)

\\

1.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 UNIT Duane Arnoi d Energy Center DATE 12-15-86 COMPLETED BY Bradford N. Thomes TELEPHONE 319-851-7309 MONTH November, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 535 17 516 2

517 18 515 3

539 19 516 4

536 20 509 l

5 539 21 509 6

531 22 506 7

526 23 500 8

526 24 509 9

525 25 502 j

10 529 26 503 11 527 27 501 12 524 28 500 13 524 29 497 14 519 30 487 15 519 31 16 514 INSTRUCTIONS On this format, liet the average delly unit power level in MWe-Net for each day In the reporting mon +h.

Compute the nearest whole megawatt.

(9/77) l l

G E

r R

U e

t N

a a(

m e

C a s e st nl y

n a ei e

a s

oD cF c

r a

i i

r m

t f L

)

u n

o co R

o E

h u

rE S

T r n oL d

9 t of

(

e l

. 0 si m

a M

3 nt st a

e 7

e I

at r S

1 r 6 d

s

- r e o 3

A 8

r 1

u G a e p 1

3 o

5 a

ph e 0

3 5

f 8

C t eS R t

\\

i r i

O d

1 a

9 b P yt

)

b 0

e 2 r

1 i

r n 1 i

5 1

B 3

h rt e6 h

0 h

x on v1 x

.eey e E f E E 0 E

amt b n Caa o

4 5

N D d h t

ep ot t e el k

l e

m) ca l

cIf pT a n O

m

.Ioo ri o

mc a C

ee oaeoo aS l

r p

c c x S i E t

(

l l

a

a a m r

,* oo d u u o e ae7 > m on nt h h e a ut t M M A O e - - - -

1 2 3 4 M

SI 3

C 6

. t s nt 8

I T

9 n er 1

C

. v o U

cE p n

o D

e i

E r

t R

C e

i t

b a

m 2

n E

e i

v C

m O

o a

N x

P L

=

,$O m

E D

  • =f3 N

H

)

e

)

n s

n A

T

  • o]gy i

n i

N S

O a

e a

Z M

c l

l U

p ni p

O T

x oL x

D R

E i

E T

O NeS eeE

(

t t &

(

s c

U P

H E

e e i g r

S R

rT r n o

u t i r) i l

r s n er n o

ei vE i l

i a

a R ai a

Esoz~

F e r t l

l U

c yT a a p eo!eLaO t n g r r n x n a n o rt oE e ni t osi

(

i t m el at

pt el an a r ni n u u ri r e ouif g e m eh s q a e e pd p t aE M R R O A O O

$ x +-

e - - - - - - - -

R A B C D E F G H 2

e d

t e

a l

D d u ed c e rh oc F S

)

7 o

7 N

F S

/

9 l

(

Oscket No. 050-03);

Unit Derso Armeld Earray Crater Date 12-15-86 MAJOR / SAFETY RELATED MAINTENANCE Completed By Bradf ord N.

Thomas Telephone 1319-851-7309 DATE SYSTEM COMPONENT DESCRIPTION 11-04-86 Reactor Core isolation Cooling RCIC Pump Outlet Flow Meter Replaced the def ect i ve pump outlet f' low meter' (RCIC)

FIC2509 with a like-for-like.

(LER 86-023)

Control Buil ding Standby Filter

'A' SBFU Calibrated the

'A' train flow - in dicat ing' Unit (SBFU) controller (FIC7320A)

Res i dua l Heat Removal (RHR)

'A' RHR Minimum Flow Valve

' Replaced burned out valve control transformer.- '

(MO-2009) 11-12 Main Steam Line isolation Valve

-'A',

'B',

'C',

'D'

- MSIV-LCS Flow Removed from service for yearly calibration.

11-13-86 Leakage Control System (MSIV-LCS)

Transmitter 11-17-86 Fire Protection System Diesel Fire Pump Engine Removed from service and sent offsite for major overhaul.

11-18-86 RHR

'A' RHR Minimum Flow Valve Replaced a defective valve closing starter, r

(MO-2009) 11-19-86 Standby Gas Treatment

'A' SBGT Temperature Transmitter Planned ma i ntenance for. ca l i brat ion of the (SBGT)

'A' Temperature Transmitter.

11-21-86 High Pressure Coolant injection HPCI High Steam Flow Differential Dried out moisture in pressure switch and (HPCI)

Pressure Indicating Switch recalibrated'after mo i s t u r e caused a mo me n t a r y contact short which. Isolated the HPCI system.-

(LER 86-024) 11-25-86 SBGT

'B' SBGT Flow In dicat ing Replaced a defective flow In di ca t i ng Controller controller.

11-26-86 Fire Protection Diesel Fire Pump Repacked pump.

-I L

pz o-4.'

00CKET NO. 050-0331 UNIT Du*26 Arneld En ray C+nter D AT E 12-15-86 COMPLETED BY Bra df or d N._ Thomas TELEPHONE 319-851-730~9 REFUELING INFORMATION 1.-

Name of facility.

A.

Duane Arnol d Energy Center 2

Scheduled date for next refueling s h u t dow n.

A.

March, 1987.

3.

Sche duled 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 submittal B.

Additional MAPLHGR curves for new fuel bundles being I nt ro duce d for Cycle 9 5

Scheduled date(s) for submitting proposed licensing action and supporting information.

A.

Submitted B.

Submitted 6

Important licensing consi derations associated with refueling, e.g.,

new or dif f erent fuel des ign or supplier, unreviewed de s i gn or performance ana lys is metho ds, significant changes in fuel design, new operating procedures.

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 i

w.

f e

DOCKET NO. 050-0331 UNIT Du ne Arn11d Eneroy C nter DATE 12-15-86 COMPLETED BY Bra df or d N. Thomas TELEPHONE 319-851-7309 NARRATIVE

SUMMARY

OF OPER ATING EXPERI ENCE 11-01-86 At the beginning of the month the Duane Arnol d Energy Center (DAEC) was operating at 100% of rated power with 535 MWe (Net) being provi de d to the j

grid.

11-04-86 At 0333 hours0.00385 days <br />0.0925 hours <br />5.505952e-4 weeks <br />1.267065e-4 months <br /> a 7 day Limiting Con dition for Operation (LCO) was entere d when the Reactor Core Isolation Cooling (RCIC) system was de c l a r e d Inoperable. The control room RCIC pump outlet flow meter was not respon ding to actual KCIC pump flow variations during the quarterly RCIC Surveillance test.

The flow meter was replaced and the RCIC system was returned to service after successful completion of the quarterly test.

The 7

LCO was then terminated at 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> on 11-05-86 (LER 86-023) i At 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br /> the

'A' train of the Control Buil ding Standby Filter Units (SFU) was dec l a r e d inoperable.

This placed the plant in a7 day LCO.

The flow in dicating controller was recalibrated and the LCO was terminated at 1249 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.752445e-4 months <br /> on 11-06-86 with the system being returned to its normal stan dby status.

l 11-12-86 The

'A',

'B',

'C',

and

'O' trains of the Main Steam Line isolation -

through Leakage Control System (MSlV-LCS) were remove d f rom service at different 11-13-86 times for the yearly calibration of the flow transmitters. This placed the I

plant in and out of four 30 day LCOs.

The final LCO was terminated at 1352 hours0.0156 days <br />0.376 hours <br />0.00224 weeks <br />5.14436e-4 months <br /> on 11-13-86 with the

'D' train placed back in service, 11-14-86 At 1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br /> the final shipment of the new fuel was placed on the refuel floor.

11-17-86 At 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br /> a7 day LCO was entered when the diesel fire pump was remove d from service in order to perform major overhaul work on the di es e l engine.

The engine was sent offsite for a complete engine overhaul. The system was returne d to service following successful post-maintenance testing at 1331 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.064455e-4 months <br /> on 11-24-86 The LCO was terminated at this time.

11-18-86 At 0236 hours0.00273 days <br />0.0656 hours <br />3.902116e-4 weeks <br />8.9798e-5 months <br /> the

'A' Res i dua l Heat Removal Service Water (RHRSW) pump was dec l a r e d Inoperable when a vlbration pad f ell off the pump du r i n g surveillance testing.

This placed the plant in a 30 day LCO.

The LCO was cancelod at 0155 hours0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br /> on 11-19-86 after replacement of the vlbrotlon pad and completion of the surveillance test.

From 1800 to 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> the 1906 NRC observe d Emergency Preparedness Drill was con ducted at DAEC.

11-19-86 At 0748 hours0.00866 days <br />0.208 hours <br />0.00124 weeks <br />2.84614e-4 months <br /> a7 day LCO was entered when the

'A' train of the S tan dby Ga s l

Treatment System was removed from Service for planne d main tenance.

A Temperature Transmitter was callbrated and the system returned to service i

at 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> on 11-20-86 The LCO was exitod at this time.

l l

O DOCKET CO. 050-0331 UNIT Dua*n Arnal d En ray C+3t"r D AT E 12-15-86 COMPLETED BY Bra df or d N.

Thomas TELEPHONE 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 11-20-86 At 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br /> the 'A8 train of the RHR system was dec l a r e d inoperable when a snubber on the system was f oun d to be low on fluid.

A 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO was entered to replace or restore the snubber to its operable status, and perform an engineering evaluation.

The fluid level was restored an d the snubber was declered operable on 11-21 at 1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br />.

11-21-86 At 0822 hours0.00951 days <br />0.228 hours <br />0.00136 weeks <br />3.12771e-4 months <br /> the HPCI System Isolated when a spurious isolation signal was received f rom a Dif f eren+1al Pressure Switch which senses high steam flow.

Investigation revealed moisture in the switch compartment, which likely resulted in a momentary short of contacts at the contact block.

The switch compartment was deled and recalibrated successf ully.

Following completion of the HPCI operability test, the HPCl was declared operable at Ol19 hours on 11-22-86 The LC0 was exited this time.

(LER 86-024) 11-25-86 At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> a 7 day LCO was entered when the 808 SOGT System was remove d from service for planned maintenance.

During this maintenance the flow in dlcating controller was f ound not to be callbrating properly and was rep lace d.

The LCO was exited at 1728 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.57504e-4 months <br /> with the system belno returned to service.

11-26-86 At 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> the Diesel Fire Pump was removed from service for pump repacking. The plant entered a 7 day LCO at this time.

The pump was repacked and returned to service at 1437 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.467785e-4 months <br /> on 11-29-86 The LCO was terminated at this time.

11-30-86 The OAEC was operating with all ro ds full out at the end of the month.

Coa s t dow n towar d the cycle 8/9 Ref uel Outage had started in ml d November.

The plant was operating at 91% of rated thermal power with 487 MWe (Net) being provi de d to the grld.

Iowa Electric Light and Power Company December 15, 1986 DAEC-86-0986 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 l

Op. License DPR-49 November, 1986 Monthly Operating Report

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly L

Operating Report for November, 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, Vl*

Daniel L. Mineck i

Plant Superintendent - Nuclear Duane Arnold Energy Center 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 I

Region !!!

Washington, D. C.

20555 l

799 Roosevelt Road Glen Ellyn, IL 60137 (1)

NRC Resident inspector i

Director, Office of Management and Mr. Dennis Murdock l

Program Analysis Central lowa Power Cooperative V. S. Nuclear Regulatory Commission Box 2517 Washington, D. C. 20555 (1)

Cedar Rapids, IA 52406 l

V. S. Nuclear Regulatory Commission Mr. Russ Gamble

(

ATTN: Mr. R. Gilbert Corn Belt Power Craperative i

Phillips Building 1300 13th Street North l

Washington, D. C. 20555 Humboldt, IA 50548 i

INPO Records Center 1100 Circle 75 Parkway i

Suite 1500 i i Atlanta, GA 30339 lhiane ArnoM Iunrry renter ' 3277 IMIT Itoast

  • I%Ia, hmn 32324
  • Stu Ml ?tilI

.