ML19338D496

Monthly Operating Rept for Aug 1980

ML19338D496
Person / Time
Site:	Fort Calhoun
Issue date:	09/08/1980
From:	Hickle B OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19338D495	List: ML19338D494 ML19338D496
References
NUDOCS 8009230351
Download: ML19338D496 (9)

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, . 7 AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO. 50-285

. 3.iT Fort Calhoun #1 DATE September-8,~1980 CONSPI.ETED BY ~B.

J. Hickle TELEPIIONE _(402)536-4413 MONE August, 1980 ,

' DAY AVERAGE DAILY POWER LEVEL DAY. AVER AGE DAILY POWER LEVEL t- . (MWe-Net) (MWe-Net) 434 37 435 2 433 is 435 3 433 39 432 4 434 20 432 3 434 21 431 6 434 22 431 7A. 433 23 434

s. 431- 24 435 9 431 25 435 to '432 26 433

.ti 433 27 _

434 L12. 433~ 28 .

437 13 '433 29 436-14- 434- 30 435 i'

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. INS 1 RUCTIONS O, this format, list the aserage daily unit power level in MWe Net for each day in the reporting nonth. Compute io

. the nearest whole megawatt.

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OPERATING DATA REPORT

DOCKET NO; 50-285- ~

' DATE Septemoer 8,' 1980 '

COMPLETED BY- B. J. Hickle .

TELEPilONE (402)53T-4413

> OPERITING STATU}

FortiCalhoun #1 Notes I. Unit Name:

- 2. Reporting Period:. -August, 1980-2 3. Licensed Thermal Power (MWt):

1420

- 4. Namepu.. ; .ing (Gross MWe):- 502-

5. Design Electrical Rating (Net MWe):. 457

6. Maximum Dependable Capacity (Gross MWe)': 401

'457 7/ Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A

~

9. Power LevelTo Which Restricted,1f An Net' MWe): N/A

10. Reasons For Restrictions.lf Any:

2.

This Month Yr. to-Date Cumulative -

11. Ilours in Reporting Period .744.0 5,855.0 60,792.0

12. Number Of flours Reactor Was Crit' cal 744'.0 2,449.1-- 46,850.7

13. Reactor Reserve Shutdown flours 0.0 0.0 -

1,30925

14. Ilours Generator On-Line 744.0 2.387.3- 45;838.4

15. Unit Resene Shutdown Hours .- 0.0 0.0- 0.0-

16. Gross Thermal Energy Generated (MWH) 1,049,152.6 3,166,746.3: 56,401,725.6- .

17. Gross Electrical Energy Generated (MWH) 339.426.0 1.027,932.0 _18,688,161.6 18.- Net Electrical Energy Generated (MWH) 322,571.2 974,199.0 17,661,718.8 .

19. . Unit Senice Factor 100.0- 40.8 75.4-20." Unit A'vailability Factor ; 100.0 40.8-  : 75.4 .

. 21. Unit Capacity Factor (Using MDC Net) . - 94.9__ 36.4 64.0- g 22.' Unit Capacity Factor (Using DER N'et) . 94.9- 36.4 63.6 23.' Unit Forced Outage Rate 0.0 0.4 -

4.3

24. Shutdowns Schedu?ed Over Next 6 Months (Type. Date,and Duration of Eacht

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? 25. If Shut'Down At End Of Report Period. Estimated Da' te of Startup:

k 26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY . ->

INITIAL ELECTRICITY

- ~, COMMERCI L OPERATION -

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- Fort ^Calhoun?--Unit No. 1 .

Reportifor1thenonth' ending August 31,l1980 .- .

1.J Scheduled <date for nes:t' refueling. shutdown.  :' September-15,-1981

2. i Scheduled date for restart follwing refueling. November 15, 1981

3. , 'Will; refuelingfor resumption of operation thereafter

- require altechnical specification change or other No

-licenseJanendment?

, ' a.: ; If' answer is yes, what, ~in general,;will

.these be?'

b. 'If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Comnittee to deter-mine whether any unreviewed safety. questions NO are associated withLthe core reload.

- c. If no such review has.taken place, when is September 1,'1981 it scheduled?

4. Scheduled-date(s)" for submitting proposed licensing :

action ~and support information.

~5. Important licensing considerations associated with refueling, e.g. , inew or different fuel design or supplier, unroviewed design or performance analysis nethods, significant changes in fuel design, new

- operating procedures. .

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133 assemblics

6. We ntmber of fuel assenblies: a) in the core

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b) in the spent-fuel pool 197 c): spent' fuel pool' "

. rstorage capacity 483 d)-planned spent fuel' pool * "

' storage capacity 483 7.' l'Ihe projected ~datefof: the. last refueling that can be discharged'to ;thejspentifuel pool'asstnting the present 1985 Llicensed capacityn EMM . September 5,E1980

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OMAHA- PUBLIC POWER DISTRICT .

Fort:Calhoun. Station Unit'No.'1

' August 1980 _.

J Monthly Operations Report I. OPERATIONS'SUMARY Fort Calhoun Station' received a license amendment during the month-Lof August which: allowed an. increase 1:s power level'to 1500 MWth. The operations department participated in the review of the operational-readiness of Fort-Calhoun~ Station to increase power-level. Plant

. specific: training was given the Fort Calhoun staff on the expected

. s,r.. tem parameter: and procedure changes which vere required to implement

'tbe-increased power level.

Normal surveillance tests and operational tests were completed with no abnormal results reported.

The unit operated at a nominal 1h20 MWth during the month of August.

Normal six shift training continued during August.

A. . PERFORMANCE CHARACTERISTICS LER Number Deficiency LER 80-012: During performance of ST-RPS-3, F.2, it was discovered that Trip Unit #3 (Reactor Coolant Flow) trip setpoints had drifted,out of specifi-cation in the nonconservative direction. Main-tenance: order #6405 was written to investigate the drift. The R.P.S. was immediately placed in a two-out-of-three logic to trip mode.

Technical Specification 1 3(2) applies.

LER-80-013 During normal power' operation it-vas noted that ,

-Channel AJDC. sequencer SI-1 had a de-energized "on-auto" light associated with AC-3A, or the i safeguards equipment supplied 1from Bus 133B.

.The'AC sequencer.for. channel A relatra safeguards

. equipment remained-operable throughout the event as were the. channel B AC and'DC sequencers. .The safeguards loads from all h80 volt equipment, except 1B3B associated equirment (which is AC-3A

.only) remained operable from the DC channel A sequencer SI-1.

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LMonthly< Operations (Report-IAugust.1980' i

iPage Two I ' A .'

PERFORMANCE CHARACTERISTICS (Continued)

-LER Number ~ . _ Deficiency .

'LER 80-01h  : Transformer -(Th) of DG-r failed. This transformer fed power ;to .the diesel's oil' immersion heater as v ell as.; alarm circuitry; corresponding to _the following items: lLov. lube oil; pressure, lov lube oil level,2and.High orJLov lube oil' temperature.

During the time of the transformer. (Th) failure,-

DG-2 as(vell , the 161KV 'and: 3h5KV systems were available:and. operable and would have been more than capable of mitigating the _ circumstances of '

an accident should the need arise. :In addition, DG-1 wasEconsidered~ inoperable only during'the-time-that the transformer was being changed out,

. i.e. only while DG-1 was in " local maintenance."

LER 80-015 During routine' inspection, it was noted that trip unit setpoints on "C" channel, trip unit.hl(Steam

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Generator Level) had become positive rather than negative. Maintenance' order 6430 was written to investigate and repair the problem. The RPS was immediately placed in a'two-out-of-three logic to trip mode. ' Technical Specification 1.3(5)' applies.

B. CHANGES IN OPERATING METh0DS-None C.- RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None

'D.  : CHANGES', TESTS AND _ EXPERIMENTS CARRIED OUT WITHOUT COLMISSION

. APPROVAL i

Procedure Description SP-RPS-5 Excore Detector Symmetric Offset recalibration/

no adjustment required.

'SP- FAUD-l ' Fuel Assembly Uplift Condition Detection /all results normal.

SPAPRC-3' Reactivity Computer and Beactor Physics Content adjustment /results are normal.

• EEAR(FC-79-166- LCV-2 Replacement / completed per procedure.

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~ Monthly Operations Report August 1980.

Page Three D. LCHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL'(Continued)

Procedure Description-DCR 743-33 -Replacement of. Component Cooling Heat Exchanger Rav Water Inlet Valve / completed per design.

EEAR FC-79-7 Seismic Supports for Reactor Missle' Shields /

-completed as designed.

DCR 76-30 Containment Decon and Cleanup / completed as designed.

EEAR FC-79-108 Diaphram Modification (WD-9h5 and WD-9h6)/

completed as-designed.

E. RESULTS OF LEAK RATE TESTS

'There were no leak rate tests performed during August except ST-CONT-2 by operators on PAL door.

F. CHANGES IN PLANT OPERATING STAFF Miss Elizabeth Goebel started with H.P. group 8-18-80, f-G. TRAINING Training for August included the following:

- EDO Training for plant supervisors.

- System Training for operations.on HVAC, Halon and Fire Detection.  ;

- Fire brigade training for plant personnel.

- Radioactive material handling for CARP personnel. '

- Stretch power for all staff and operations personnel. I

.- Driver training ~for plant personnel.

'- Emergency sampling.

- OIE notices and bulletin review.

- Cycle 6 Tech. Spec.'for operations.

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Safety. meeting for operations,' maintenance and

.teehnicali groups.

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?Monthli. Operations.Repdrt Augast 19801 PagelFour

.H. - CHANGES, TESTS AND EXPERIMENTS REQUIRING. NUCLEAR REGULATORY-.

COMMISSION AUTHORIZATION PURSUANT TO 10CFR50 59..

Chan6ei; To Facility OperatingL License DPR-40s

.. Amendment No. 50,~ dated August 15,'1980.. . This amendment.

changed License Co'ndition 3.A'.' and.the Technical Speci-fications to authorize operation-at 1500.MWt.

Amendment No.,51,: dated August 28,.1980. This amendment-deleted certain' environmental monitoring and reporting

requirements and increased the maximum and. differential condenser cooling vater discharge temperature limits.

Approved By h. tb-

' Manager-Foft Calhoun Station-h

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Monthly. Operations , Report .-

~ August,1980.

~ Page' = Five

'II. MAINTENANCE (Significant Safety Related)

M- 0. # Oate Description- Corrective Acticn

.6h72 T-16-80: .HCV-1108A vill not shut. Replaced solenoid valve 6h90 7-18-80: CH-13 leak. Replaced valve CH-258.

'6568 ~ 7-21-80 RMO-55 leak.. Tightened intake and- discharge

• flanges.

6832 8-20-80 D-2 Fuel'oi1Ltransfer pumps vill Changed out 0-ring in foot valve.

-not pick up suction.

I665h 8-7-80 RM-055 flange leak. Install new gasket.

6579 8 h-80 CH-1B has internal leak. Replaced gaskets and 3 discharge-valves.

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