ML20066G496

Monthly Operating Rept for Jan 1991 for Fort Calhoun Station Unit 1

ML20066G496
Person / Time
Site:	Fort Calhoun
Issue date:	01/31/1991
From:	Edwards M, Gates W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-91-067R, LIC-91-67R, NUDOCS 9102190153
Download: ML20066G496 (7)

Text

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Omaha Public Power District 444 South 16th Street Mall Omaha Nebraska 68102-2247 402/636-2000 February 14, 1991 LIC-91 067R V. S. Nuclear _ Regulatory Commission Attn: Document Control Desk Mail Station PI-137 Washington, DC 20555

Reference:

Docket No. 50-285

' Gentlemen:

l

SUBJECT:

January Monthly Operating Report (MOR)

L Please find enclosed the January 1991 Monthly Operating Report for the Fort j..

Calhoun Station Unit No.1 as. required by Technical Specification Section l

5.9.1.

l L

If you should have any questions, please contact me.

Sincerely,

p. 7I 2A

\\

W, G. Gates Division Manager Nuclear Operations

'WGG/sel Enclosures o

c:

LeBoeuf, Lamb,.Leiby & MacRae R. D. ' Martin, NRC Regional Administrator, Region IV P. P. Mullikin, NRC Senior Resident Inspector D.

K'. Sentell, Combustion Engineering R. J.-Simon, Westinghouse Office of Management &' Program Analysis (2)

INP0 Records Center l-American Nuclear Insurers 9102190153 910131 PDR ADOCK 05000285

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45 5124 angtoymen tth E u. Oxerunity 7

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AVERAGE DAILY VNIT POWER LEVEL i

DOCKET NO.

50-285

'JNIT Fort Calhoun Station DATE February 6, 1991 COMPLETED BY M. L. EDWARDS TELEPHONE T402)636-2451 MONTH January 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 488 2-0 18 489 3-0 19 489 4

0 20 488 J

5 0

21 488 6

0 22-488 7

0 23 488 8

0~

24 488

=9 101 25 488 10 116 26 489 11 403 27 488 12 462 28 488

13 463-29 488 14 476 30 488 15 488 31 488 16-488-

' INSTRUCTIONS L

On this form,: list the average daily unit rower level in MWe-Net for each day in the reporting month.

Compute to the r.earest whole megawatt.

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l..

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OPERATING DATA REPORT DOCKET N0.

50-285 UNIT Fort Calhoun Station DATE February 6. 1991 COMPLETED BY M. L. EDWARDS TELEPHONE (402)336-2451 OPERATING STATUS 1.

Unit Name:

Fort Calhoun Station Notes 2.

Reporting Period:

January 1991 y

3.

Licensed Thermal Power (MWt):

1500

[

4.

Nameplate Rating (Gross MWe):

502

>A 5.

Design Electrical Rating (Net MWe): 478

{

6.

Maximum Dependable Capacity (Gross MWe):

502 7.

Maximum Dependable Capacity (Net MWe): - 478

8. 'If changes occur in Capacity Ratings (1 tem Numbers 3 through 7) Sin ~ce Last Report, Give Reasons:

N/A-9.

PowerLeveltoWhichRestricted,IfAny(NetMWe): N/A

10. Reasons for Restrictions, If Any: N/A This Month Yr-to-Date Cumulative

11.. Hours in Reporting Period 744.0 744.0 152.114.0

12. Number of Hours Reactor was Critical 564.0 564.0 117,352.7 13.. Reactor Reserve Shutt'.own Hours 0.0 0.0 1,309.5 14.

Hturs Generator On-Line 553.2 553.2 115,983.1

15. Unit Reserve Shutdown Hours 788,2*f!E~

788,242.8 152,071,732.1 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Ene if Generated (MWH)

-259,966.0 259,966.0 50 47,010,092.2

-18 ; Net Electrical. Energy Generated.(MWH) 247,636._9_

247,636.9

,732,413.2

'19.

Unit Service Factor 74.4 74.4 76.2

-20.

!! nit _ Availability Factor 74.4 74.4 76.2

.21.

UnitCapacityFactor(UsingMDCNet) 69.6 69.6 68.0

22. Unit Capacity Factor (Using DER Net)

___ 69.6-69.6 66.5

23. Unit Forced Outage Rate

.5.6 25.6 3.6 24.

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

None-25,-

If Shut Down at End of Report Period, Estimated Date of Startup: N/A

26. Units In Test Status (Prior to Commercial Operation): Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A

~

COMMERCIAL OPERATION

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. Refueling Information-Fort Calhoun - Unit No.1 Report for the month ending January 1991 l'. - Scheduled date for' next refueling shutdown.

Seotember 1991

2.

Scheduled date for restart following-refueling.

November 1991

,3. -Will refueling or resumption of operation thereaf ter. require -a technical specification

. change or other license amendment?

.Y_es

_a..

If answer is yes, what, in' general, will these be?

1 Incorporate-specific requirements resulting

- from reload safety analysis.

~ b.

'-If answer is no, has the reload fuel design and core r.onfiguration' been reviewed 'by-your Plant Safety Review-Committee to determine whether

- ar.y unreviewed' safety questions'are associated with the core reload. '

N/A q

}fR c.

1f no such review has =taken place, when is-1

-~

it: scheduled?

N/A

4.-

Scheduled date(s)- for submitting. proposed licensing = action arid support information.

June 1991

. 5.

Important-licensing consideration's associated Lwith refueling,~ e.g.,; new or different fuel Ldesignior supplier, unreviewed design ort 4

per'formance-analysis methods, significant-

' changes in fuel design, new operating procedures..

' New fuel supplier A

f New LOCA Analysis y

16. - The. number of fuel assemblies: a) in the core 133' Assemblies i

b) -in:the. spent fuel pool

. 477 Assemblies c)_ spent fuel-poolz storage

'-729...As sembl ies.

l capacity-d) planned spent fuel pool

'with higher density. spent Planned:to be::increasedt

, torage capacityv s

fuel; racks.

7.

The1 projected date of the last-refueling that can be-

discharged to. the spent fuelipool assuming the present

-licensed : capacity. ~

1994*

o

! Capability of full; core offload of 133 assemb7 'es lost.

Prepared by' Y Date 2-s-9 r i

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DOCKET NO. 50-285-UNIT NAME Fort Calhoun Station.

DATE February 7, 1991 UNIT..SitUIDOWNS AND POWER REDUCTIONS-COMPLETED BY.. M.I _ Edwards TELEP110ME (4021 636-2451 REPORT HONill January 1991 E

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g7 gg

' Ucensee gI fg

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• Cause a Corrective No.

Date

~jg 5-Eg Event ge g g Action to R

') E gh fleport #

SEg g

Prevent Rectarence 5

90-08 901215 F-190.8 H

1 LER 90-028 XX PSX, AA On December 15, 1990, a through-wall feak on an installed spare Control Element Drive Mechanism (CEDM) pressure housing was identified and a.

s cooldown to cold shutdown was initiated.

The 'affected CEDM housing and a I

second installed spare housing were removed and replaced with blank flanges.

FCS was returned to service on January 8,

1991.

• See LER 90-028 for further muse and corrective ' actions.

1" ^

2 a

F-Forced Heatorr Method Exf*lt G - Instrvetion, S-Scheduled A-E<ripment failure (Explain) 1-Manual for Preparatien of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Ucensee C-Ilefuefno 3-Automatic Scram Event Report (1.ER) ne (NUREO-olet)

D-Regulatory Hestrictfen 4-Other (Explain)

.E-Operator Tralrdno a Ucense Examination 6

F-Administative Exteit 1 - Same Source G-Operational Erre St-other (Expfair.)

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U 10MAHA PVBLIC POWER DISTRICT Fort Calhoun Station Unit No.-l r

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January 1991 Monthly 0parating: Report l'.. OPERATIONS

SUMMARY

In-January, Fort Calhoun Station wasistarting 'up from cold shutdown

~i following repair of a Reactor Coolant System -(RCS) leak on the control element 1 drive mechanism (CEDM) housing.

During tne RCS hot hydrostatic test,.a pressurizer to code safety valve loop' seal _ inlet flange was found to be leaking.

The RCS was cooled down and depressurized for repairs to the flange.. The hydrostatic test performed during the following heat-up still showed some leakage on the flange but at an acceptable rate. Weekly L

monitoring of the leak was ' scheduled and continues to be performed.-

The reactor was taken critical and the generator 'placed on-line January 8, 1991.: A nominal-100% power was attained January 14,-1991. The scheduled monitoring ofmthe' flange leak on January 17 showed the leak had increased, j

Furmanite was used to seal the leakage area and this decreased the leak rateLto approximately one drip per minute.

JThe1following NRC inspections took place in January:

[

IR_90-45 MonthlfEinspection_(fromDecember5,1990toJanuary 14,1991)~

J b

IR 91-02' Service' Water Systems. Team Inspection O

IR 91 : Monthly Inspection (Continued from January 15,1991) u

_.The following iERs were submitted:

LER 90 -Inadequate = Hourly Fire Patrols-

,1

'LER-90-28:

Leakage' Through Control-' Element Drive Mechanism Housing;(Voluntary Report)

A.

. SAFETY VALVES 0R PORY CHALLENGES OR FAILVRES WHICH OCCURRED.

NONE B.; cRESULTS OF LEAK RATE TESTS i

h n

LThe'results of the; Reactor Coolant System; teak Rate Tests for January; =

1 1991 indicate' that the removal of CEDM pressure, housings #9 and L#13:

with the4subsequentLinstallation of blind flanges on these...

penetrations has corrected the high:RCS leakages e'xperiencedilast!

fall. Total RCSfleakage' averaged 0;08 gpm divided equally between "known" and " unknown" leakage'.

.The Leak Rate-Tests for the' month began'on January 8, 1991.

Because:

.of the " feed and. bleed" operations and RCS4 specific' volume changes

- e associated with, plantc start-up and power ascension, the -RCS leak rates

'during this period.were:relatively less accurate; Afteria few days, equilibrium conditions ucre achieved and the negative leak ratesf.no 4

longer appeared.

The minimum calculated leak rate for the month

' appeared;o_n January 12,1991. ;This_ leak rate was -0.253 gpm total and 2

' 0;310:gpm unknown - The maximum leak rate was calculated during a plant transient and is not representative of the actual leak rate.

The maximum leak rate of 0.337 gpm total and 0.271 gpmL" unknown"Lwas calculated on January 25, 1991.

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CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTH0KniATION-PURSUANT TO 10CFR50.59-Amendment No.

Description None D.

SIGNIFICANT' SAFETY RELATED MAINTENANCE FOR THE MONTH OF JANUARY, 1991

-During the forced outage ending January 8, 1991, many maintenance items were completed / corrected including the following:

Replace the solenoid valve and rebuilt the air cylinders on the steam generator RC-2A main steam isolation valve (HCV-1041A).

The raw water (RW) pump strainer (AC-12B) was replaced with a rebuilt strainer.

Rebuilt the valve actuat'

.i the Component Cooling Water (CCW). inlet valve-(HCV-491A) for hea

. changer AC-lC.

Rebuilt the operator on the CCW inlet valve (HCV-489A) for heat

' exchanger AC-1A.

Rebuilt positioner air relays for the containment cooling coil outlet isolation valve:(HCV-400C).

Nachined a pressurizer to code safety valve loop seal inlet flange (RC-142) and replaced gasket.

A' slight leak remained and Furmanite was used to seal it.

CCW/RW heat exchanger (AC-lD) was taken out of service to replace the lifting lugs on the end bell flanges. -The raw water relief valve-(RW-223) was rebuilt.

e 3

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