ML20116J886

Monthly Operating Rept for Oct 1992 for Fort Calhoun Station

ML20116J886
Person / Time
Site:	Fort Calhoun
Issue date:	10/31/1992
From:	Cavanaugh G OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20116J877	List: ML20116J874 ML20116J886 ML20116J896
References
NUDOCS 9211160419
Download: ML20116J886 (6)

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ENCLOSURE 1 OMAHA PUBLIC POWER DISTRICT fort Calhoun station Unit No. 1 October 1992 Monthly Operating Report 1.

OPERATIONS SUMMAP.Y During Jctober. Fcrt Calhoun Station (FCS) operated continuously at a-nominal 100% power level. On Octcber '5,1992 the Army Corps of Engineers began river flow reductions for the winter season.

By the end of the month, the Missouri River level was approximately 986' 6".

To allow for intake grid cleaning, FCS removed the circulating water pumps from service one at a time.

Several times during the month, the main turbine control-valves exhibited slight drift (both cpen and closedb The drift was generally limited to about 1% valve position. This corresponds to about a 0.2"F change in cold leg temperature, and two (2) to three (3) MWt (a 0.00133 to 0.002 percent reactor power)ious voltages to find variation of Troubleshooting by the Instrument and Control Technicians recorded var a cause for the drift.

At the end of October, the results had been inconclesh a with no identified cause.

Troubleshooting continued at the end of the month.

On tctober 25, 1992, the "A" channel of nuclear instrumentation was declared inoperable due to fluctuations in measurements.

Per the Technical apecifications, FCS entered Limiting Condition of Operation (LCO) 2.15 (1 were placed )in bypass w'. thin one hour.and appropriate trip units of the Reactor Protective Syste Instrumentation and Control Techricians conducted troubleshooting and adjusted voltage-to the channel, with limited success.

Cablin outside containment-for the "A" safety channel was switched with the A" control channel. -This-resulted in ibs-problem being exhibited on the "A" control channel drawer in the control room.

A containment entry was made to trace the problam on the containment side.

Technicians repaired a -bad connection found.ir, containment but this did not correct the fluctuation problem.

Subsequently-a temporary " modification was installed to exchange the "A" safety channel with the A control channel, and also to exchange the "D" safety channel with the "B" control channel to maintain a symmetric excore monitoring ccnfiguration.

FCS personnel comoleted the cr sige first with the "A" channel, followed by the "D" channei.

Both safety channels were declared operable October 31, 1992, and the LCC was exited.

While the final analyses are being completed concerning the Shape-Annealing Factor and the effects of R d Shadowing, Operations placed restrictions on rod motior.

The following NRC inspections were completed during October 1992:

IER No.

Title 92-20 Emergency Exercise Inspection 92-22 Monthly Resident Inspection 25-Check Valve Program Inspection 92-27 Maintenance Program Inspection 92-28 Securit

.jstems Inspection 9P11160419 921113 PDR ADOCK 05000285 d

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October 1992 Monthly Operating Report Page 2 The following LERs were submitted during October 1992:

LER No.

LER Date Des-riotion 92-019, 10/22/92 CEA Drop Due to Cluts., Coil Failure Rev. 1 92-010 10/30/92 Auxiliary Steam in Room 57 Outside Rev. 2 Design Basis (HELB)

A.

SAFETY VALVES OR PORY CHALLEMGES OR FAILURES WHICH OCCURRED None.

B.

RESULTS OF LEAK RATE TESTS The plant operated throughout the month at a nominal 100 percent power. With no reactivity changes, the leak rate as measured by a -

daily surveillance test was consistent.

The totcl RCS leak rate has averaged sliohtly ever 0.1 gpm. This is a reduction from 0.2 gpm at the end e' Septamber.

75% of the total leakage was "known leakage",

indicated s an increase in Ree: tor roolant Drain Tank level.

The remair. der;was

" unknown leakage". The "enknown leakage" was minimal throughout the -

month. Trending of the con +.ainment cump level this month indicates that there was nt jligible unknown leakage in the containment.

The RCS leakage rate is steaJy with no adverse' trends noted.

C.

CHANGES, TESTS AND EXPEHTHENTS REQUIRING NUCLEAR REGULATORY COMMISSION ~ AUTHORIZATION PURSUxNT TO 10CFR50.59 None.

D.

SIGNIFICANT SAFETY RELATED MAINTEhANCE FOR THE MONTH OF OCTOBER 1992 Significant safety relater, work performed during October 1992 included:

Replaced valve and stainless steel tubing on discharge sample valve AC-1121 for the fuel transfer canal drain pump (AC-13A).

Replaced suction / discharge valves and seats. packing, guide bushings and front and top cap gaskets on charging pump CH-lC.

Performed troubleshooting on the inlet valve YCV-1045 for the-steam driven Auxil_iary Feedwater Pump (FW-10) to investigate._

seat leakage. Adjusted-the packing ed rebuilt the actuator, solving the leakage problem.

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OPERATING DATAEREPORT DOCRET NO.

50-285

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UNIT FORT CALHdUN STATIQTI DATE NOVEMBER 09 1992 COMPLETED BY

~G.

R.

CAVANAUGd OPERATING STATUS TELEPHONE (402) 6J6-2474

~~

l. Unit Name:

FORT CALHOUN 'TATION

2. Reporting Period:

OCTOBER 1992 NOTES 3.' Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe':

5 0'T

'5._-Design Elec. Rating (Net MWe):

478 1 6. Max. Dep. Capacity (Gross MWe):

502

7. Max. Dep. Capacity (Net MWe):

478~

8. If changes occur in Capacity Ratings (3 through 7) since last report -

give reasons:

NA

9. Power Level to which restricted, i f any (Net MWe): NA

10. Reasons for restrictions, if-any:

NA-THIS MONTH YR-TC-DATE CUMULATIVE t

l11._ Hours in Reporting Period...........

12. Number.of Hours Reactor was Critical

~~745.0 7320.0-167450.~0 745.0 4 317.~6-129146.3

13. Reactor F,eserve-Shutdown Hours......

.0

.0 1369.5

14. Hours Generator On-line.............

.745.6 4222.1

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127599.2 15.--Unit Reserve Shutdown-Hours.........

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.0-

.0,

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-16. Gross Thermal Energy Generated-(MWH) 111315 F6

'57$H63.T 167177291.6-

17. Gross Elec. Energy (n nerated (MWH)..

376408.0 1971' 5'67.~0 -

550976~9 U

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-18.. Net Elec. Energy Generated (MWH)....

359495.9 1825897.0 152559648 4

- 19. Unit Service Factor.................

100.~6

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-76.2

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'20.Junit Availability Factor............

- 100.0

57. 7

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21. Unit. Capacity _ Factor (using MDC Net) 101.0-5272 68.2--

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2?.fUnit' Capacity Faccor (using DER Net)

- 101.0-5 2 '. T ~

66.4~

. 24. Unit Forced Outagt Rate.............

- ~ '

.0-17.3 4.4

24. Shutdowns l scheduled over next 6 months (type, date, and durction offeach):

- NONE.

. 2 5 '. If shut down at_end of-report period, estimated date of startup:

26.(Units in test status (prior to comm. oper.):.

Fer? cast LAchieved:

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' INITIAL CRITICALITY-l INITIAL. ELECTRICITY.

N/A"-

J' COMMERCIAL OPERATION L

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-t AVERAGE : DAILY. UNIT l'OWER LEVEL

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DOCKET NO.

50-285 UNIT

'YORT CALHOUN=. STATION--

DATE NOVEMBER 09-1992 COMPLETED BY G. R. CAVANAUGH TELEPHONE

( 40'2TT36-24 m MONTH OCTOSER 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL' (MWe-Net)

(MWe-Net) 1 481 17 485 2

480 18 486 3

479 19 485 4

479 20 486 5

479 21 485' 6

479 22 484 7

480 23 481 8

482 24 481

'9 4,84 25 479-404 26 480-

- 11 484 27

_483 12.

483 28' 483^

13 ~

483 29_

484 14-483 30

-493 15 484 > 484 16 485 ZNSTRUCTIONS On'this form, list the average daily unit-power ievel in MWe-Net':for=each day in the reporting month.. Compute to-the nearest wnole magawatt.-

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Refut. ling Infotuation fort Calhoun - l' nit No. 1 4

Report for the month ending October 1992

1. Scheduled dated for next1 refueling snutdown.

September 1993 2 Scheduled dr.te for restart following refueling.

Eqysmber 1993 3, Will refueling or resumption of operations thereafter require a technical specification change or other license amendment?

Yes

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

Incorporate specific requirements resulting from

-reload safety

analysis,

b. If answer is no, has the reload fuel-design and core configuration been reviewed by your Plant Safety Revie Committee to determine whether any unreviewed safety questions are associated with the core reload.

3/A

c. If no such review has taken place, when is it scheduled?

N/A

4. Scheduled date(s) for submitting proposed licersing action and support information.

hat.J 993

5. Important licensing considerations associated with refueling, e.g., new or different fuel design or suppliar, unreviewed design or performance analysis methods, significant chan design, new operating procedures, ges in fuel None Planned

-6. The number of fuel assemblies:

a) in t!.e core

.l33 Asseral' es b) fuel pool in the spent

_529 Assemal'es c) spent fuel pool' storage capacity 729-Assemblies d) plant.ed spent P1anned to be-fuel. pool increased with high storage capacity density spent fuel racks.

7. The projected date of the last refueling that car be discharged to tt.e spent fuel pool assuming the

'present licensed capacity.

1995*

o-. Capability of full core offload of 133 assemblies lost. Reracking to be perfo med between-the 1993 and 1995 Refueling Outages. -

-Prepared by_ L ~ :N M Date 11-G h i

UhIT SHtf7 DOWNS AND POWER REDUCTIONS DOCKET NO. 50-285 UNIT NAME Fr:rt Calhoun St.

DATE November 9. 199L COMPLETED BY G. R. Cavanauch TELEPHONE (402) 636-2474 REPORT h0 NTH October 1992 No.

Date -

Type' Duraton Reamm' Method of Lice:tsee Syseem Cornconers Cause & Correctwe (Haurs)

Shucing Event Code

• Code' Actxe an Prevent Recurreree Dewn Reactor' meport #

None During O feber 1992, the ptarm <perated at a arrenal 100% pcmer.

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2 Exhibn G - Insmictkms Met!xxt:

F: Forced Renam:

for Preparation of Data S: Scheduled A-Equipme:1 Failure (Explain)

I-Manual 2-Manual Scram.

Emry Sheets for Ucemee B-Maissenance or Ted Evera Report (1.IR) Fde (NUREG4161) 3-Automats Scrant C-RefueEng D-steguistory Renn 40.her (Explain)

- E{yeratoe Training & License Examination F-Adnmaistr:6ve Exhibit 1 - Same Scarce G<sperational Emr (Explain) lleher (Explain)

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