ML19338F470

Monthly Operating Rept for Sept 1980

ML19338F470
Person / Time
Site:	Fort Calhoun
Issue date:	10/10/1980
From:	Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19338F468	List: ML19338F467 ML19338F470
References
NUDOCS 8010200402
Download: ML19338F470 (9)

Text

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..AVERAGt. DAILY UNIT POWER LEVEL

' DOCKET NO. 50-285 UNIT Fort Calhoun No. 1 DATE Octobe.- 10, 1980 COMPLETED BY T. L.~Patterson TELEPHONE (402)536-4413 MONTH-September, 1980 DAY

' AVERAGE DAILY POWER LEVEL DAY

~ AVERAGE DAILY POWER LEVEL (MWe-Net) -

(MWe-Net)

I 436.4' 462.6 37 2

442.4-464.4 18 3-458.2 ~

295.4 39 457.2 373.8 20 457.9 375.3 5

2, l

6

.457.1-22 371.6 7 s-456.l'~

23 302.2 8-455.1 24 301.3 9

455.6 25 302.2 l

30 458.6'-

26 302.6 l

-1I 460.2' 27 301.6 12 459.7 300.9

-28 i

'13 459.4 300.5 l

29 l

14 460.1 299.2 39 15'.

461.7 3,

.16 463'5-

~ INSTRUCTIONS.

-t:, *his format. list the average daily ~ unit power levelin MWe-Net for each day in the reporting month. Compute to

the nearest whole megawatt.

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e OPERATING DATA REPORT' u

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- DOCKET NO. 50-285-a

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DATE 1 October-10, 1980?

+5 COMPLETED BY Tc L. Patterson :

^

su TELEPHONE: (402)536-4413

' IOPERATING STATUS I

O Unit Name:

Fort Calhoun No.11 Not*5 d/ Reporting Periodi 'SeDtember,i1980

,3.: Licensed Thermal Powei(MWt):-

1500-

[

T. Naineplate. Rating (Gross MWe){.

502-4 bl:x

! 5.i Design Electrical Rating (Net MWe):. 4574

26. Maximum De'pendable Capacity (Gross MWe):l 401 L

17. Maximum Dependable Capacity (Net MWe)i 457

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

NRC"acoroved st' retch poweri o -1500:MWt effective Auoust 15. 1980 t

L-

19. Power Level To Which Restricted,If Any(net MWe)i N/A

10. Reasons For Restrictions,1f'Any:

N/A-M, j-

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This Month ;

Yr.-to.Date Cumulative,.

y i1. Hours In Reporting Period :-

i20.0

6,575.0~

61,512.0 l:

- 12c' Number'Of flouriReaktor Was Critical.

718.6 3,167.7--

47.569.3-

!4

/13[ Reactor Reserve Shutdown Hours 3

-0.0

- 0.0 -

'1,309.51

[>

il4.l Hours Generator On.Line' -

716.4*

3,103.7--

46,554'.8

-w 715; Unit Reserve Shutdown Hours 0.0

'0.0 0.0~

~

ll6.1 Gross ThermSI Energy Generated (MWii) --

935.546.7

4.102.293.0-57.337.322.3'

17.- Cross Electrical Energy Generated (MWH)1 3051248.D_ _.

l'.333'.180.0

18.993.409.6_,

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is.. Net Ele'etrichl Energy Genera'ted (MWH) 289.263.3-1.263.462;3 17.950.982.1 19.

Unit Service' Factor:

'99.5^

47.2 75.7-

, gf S20J Unit'Avsilability Factor r 99.5-

-47.2 7 S. 7--

21 p. Unit Capacity Facht (Using MDC Net)j 87.9

- 42.0 '

64.3 7.

87.9 42.0-63.9-3 22.(Unit Capacity Factor;(Using DER Net) -

7 1

[f l23. Unit Forced Outage Ratet 0.5-0.4 4 ~. 2 -

c24[ SSundiiwin SchEdukd Over Nex't 6 Months (Type, Date,and Duration of Each):

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25. If Shut Down At End Of Report Period. Estimated Date of Startupi Jp-12QUnits in tnt'Sthius (Prior to Commercial Op' eiation)

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Y DOCKET NO., 50-285 UNITSIIUTDOWNS AND POWER REDUCTIONS UNITNAME Fort Calhoun Nc.il'

'DATE October 10. 1980.

u-

.. COMPLETED By lT.

L'. Patterson REPORTMONTil September.1980 TELEPilONE - (402)S36-4413 t:

3E-3.

.Y ~

Licensee

-,E t, Cause & Corrective.

No.

,Date g-q g;

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3,3 g3 Action to

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. Report a m O_

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~ Prevent Recurrence '

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o 80-03

-800919 F

3.6 A

3 RB CKTBRK Control rod clutch power supply-breaker tripp_ed when switching power sources _ to-investigate

.,s '-

voltage spiking on' inverter C.

M 1

I-3 4

'F: Forced.

Reason:

Method:

Exhibit G-Instructions S: Scheduled A. Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C. Refueling.

3-Automatic Scram.

Event Report (LER) File tNUREG-'

D. Regulatory Restriction --

4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administ rative -

'5 (9/77)

II-Ot her (E xplain)

Exhibit I - Same Source G-Operational Eiror (Explain)

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= Refueling-Infon:ntion;, _

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3 Fort Calhoun ;-. Unit f No. l~

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. EcportiforM.the montli ending September'30, 1980 (1. 1ScheduledSte for,next' refueling shutdown.:

e Septembe 15, 1981 2d Scheduled date-for restartCfollowing refueling; November 15,.1981

. Will refueling:or. resumption of operation thereafter -

M3.

srequire-altechnicallspecification'changeor:other

. No-

~

11icense amendment?

,.; a. -If answer is yes, what, in general', will these bs? :

~

b; ~If answer is no,lias the reload fuel design chd core configuration been reviewed by

- your, Plant ~ Safety-Review Conmittice to deter-

. mine whether any unreviewed. safety: questions No.

are associated with the core reload. -

c. lIf no such' review hasitaken place, when is

~it scheduled?,.

-September 1, 1981 4.

Scheduled.date(s) for submitting proposed licensing iaction andLsupport infouration.

t--

-5. DImportant licensing considerations associated with

~

refueling, eig., ncw orfdifferent fuel:: design or isupplier, unraicw d desian or performance analysis irethods, 'significant changes 'in fuel; design,: new operating procedures.'

133 asserrblies

~ 6. JThe nurberto'f fticl[ assemblies: 'a) in the core b)Lin; the-spent _ fuel pool:

19/

c): spent fuel:-pool-e storage capacity 483 xd) plarmed spent ' fuel pool:

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1 storage capacity 483

7 4Tholprojected dateJof the 'last refueling thatL can be.

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+ : discharged.to the spentiifuel' pool" assu:ning the present -

' liceivicd: capacity. "

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) OMAHA'PUBLIC' POWER DISTRICT..

Fort Calhoun' Station Unit No.ol

.y M

- [

. September;1980

^.f

MonthlK 0perations_ Report s

MI; : OPERATIONS

SUMMARY

i 1The' Fort Calhoun Station was, operated.at stretch power during the month aof. September. Using alspecial test. procedure plant power and reactor.

-inletztemperature were' increased and performance. data obtained. To l accommodate : system load' power vas tinitially. reduced to 80% and: subse.

'quently to 655. : One' reactor trip occurred in September as a result of loss of power to.the control rod clutches. ~All' systems-responded-I

. normally.and the generator. was synchronized Lto the grid the same day.

l-Six' shift training continued and preparations vere completed for full-

-time' training of the hot license' candidates prior to the' late' fall exam.

' Normal operational testing requirements was completed as scheduled.

A.

PERFORMANCE CFR ACTERISTICS

'LER NumberL Deficiency i

LER-80-017 During nomal power operation, it was discovered

..by Operations personnel that the setpoint_. selector i

switches ' for RMO-61, ' stack particulate radiation-monitor,- were -set in the higher of the two 'setpoint

~

pos1tions. - This position ~is normally used when.

.te=perature inversions; exist. -At thi time.-of find--

.ing the switches'in the wrong position, an inversion did:not exist.

Tech.' Spec. 5.9 2(3) applies.

-LER-80-018 During normal ' operation a sample of the gas space-:-

. on the ;VCT vas being: drawn through the gas analyzer.

A malfunction-of the sampling' apparatus-caused the inadvertant release of a small cyality 'of radio-active material,to"be. auxiliary building environment..

= Subsequently the material _was passed to the atmos :

phereLthrough the auxili m/ building ventilation:

system. The release.vas; monitored o.

short duration' f

and vasewithin'the, Tech. Spec.flimits..' Notification

' of the NRC and'offsite support agencies was made

?per I.E.'Information Notice 80-16, Tech. Spec.

5 9 2.b(h)'and FCS Energency_ Plan.

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. LER 020 1.During-normal? power operation,.it was. discovered <by;

operatorfobservation that'the Axial Power Distribution-

~

f(APD) 'setpoints on~'D channel vere out - ~ f tolerance -

o

, f in the non-conservative direction. The other three channels-were operable at'the' time and vould have

!provideda necessary triplof the reactor'if necessary.

s sTechnidal Specification ~1.3(8), Table 1.1, Item 8, F

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andl Figure 1;2 applies.

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Monthly:OherationsReport; August 198,0.

Page Two-A'. -

PERFORMANCE CHARACTERISTICS'(Continued):

! LER Number

_ ' Deficiency -

LER-80-021:

Transformer (Th).of-DG-l' failed. This transformer feeds.the. control circuitry for the 15 kw diesel oilfimmersion heater as vell as supplying power to

' alarm relays for the following-items: low lube-

-oil pressure,Llow;1ube oil level, high and/or lov

, lube oil temperature,-water. temperature, water level and water' pressure. During the time of the transformer failure, DG-2:as well as the 161 ky-

/

and 345 kb cystems vere available and operable.,cIn

-addition, DG-1 was considered inoperable'only during

~ths. time that the transformer and associated-equip-e ment were being changed out, i.e. only while DG-1 was'in " Local' Maintenance".

LER-80-022

.During performance of ST-ESF-2, F.2-(B Safety

, Injection Actuation Signal ~ Surveillance Test) th'e -

86B/ VIAS

• lockout failed to trip due to a burnt coil. During the time of the incident, the

.86A/ VIAS *, the 86Al/ VIAS

• and'the 86B1/ VIAS

• vere operable and available.to initiate safeguards-equipment should the need arise.

" Ventilation Isolation Actuation Signal

.B.

CHANGES IN-OPERATING METHODS None

~

'C.

-RESULTS.OF SURVEILLANCE TESTS AND-INSPECTIONS-Surveillance tests as required by the' Technical Specifications -Section 3.0'and Appendix Bs. vere. performed in accordance with

~

the. annual surveillance test' schedule. The following is a

' summary:of the surveillance ; tests which results in Operations

~

-Incidents and.are not reported elsewhere in the report:

Operations 1 y

• = Incident

..-Deficiency OI-1013< ~(ST-RPS-ll)

AD-1 Mdtrix' logic relay drop out lite 4

remainsd / lit ' when hold. voltage was ' applied.

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?Mont'hly Operations Repol:t September 1980' 1

Page Three L.

CHANGES,. TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION D

APPROVAL' LProcedure Description

-SP-RPS-5.

- Excore Detector Symetric Offset Recalibration

~

- prior.to 1500 MWht/Results documented in procedure.

' DOR-79-180 Replacement of. Unqualified Transmitter in Loops 90r, 904,1109,1110/ Completed as designed.

DCR-79-148 Elimination of__ Turbine Trips Caused -by Battery Transients / Completed as designed.

E.

RESULTS OF-LEAK RATE TESTS ~

No Leak Rate Tests were done during September.

F.

CHANGES IN PLANT GPERA.ING STAFF None G. -

TRAINING-Training for the month of' September included emergency procedures and sampling, new systems, Emergency Duty Officer.and fire brigade training for Operators. Safety' meetings and one hour a week train--

ing on supervisor selected topics for maintenance personnel.

" H.~

CHANGES, TESTS.AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59

.None-q!!lp Approved By

( L AQs-Fort Calhoun Station 1,

' MW f

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w-z LMhnthly: Operations Report LSeptember 1980i

.Pase'Four-II. MAIIITE3ANCE.(Significant Safety Related) s M. O.

Date Description Corrective Action-s

.6882

9'-2-80 Auxiliary Feedwater Setpoint.

Changed setpoints per CP-FWRS-A and CP-FWES-B.

13992

.'2-1-80 Aux. Bldg. HEPA Filters Changed filters 6828-8-20-80'-

SI-6D Magnatrol Lov Level Filled SI Tank Reference Legs

' Annunciator-on Level Instrument.

619h

.6-13-80

' Steam GeneratorsPressure Sigma.

Repaired meter failed.

6869-24-80 RMO-57 Pump von't run Rebuilt Pump

'h000= 1-80

Aux. Bldg. HEPA filters Changed filters

6158 6-20-80 DG-1 Exhaust System Leak Repaired Pipe

-6827 8-19-80

, Raw Water HCV-2879B will not open-Lubricate operator 70h0 9-80 "D"< Channel TU-3 Lov Flow pre-trip-Recalibrated trip unit

.setpoints.out of-specification.

f

.7018 9-6 RPS "D" Channel APD-Setpoints'out Rotated.svitches~and cleaned

- of Specification contacts.

16959 9 h 'RPS "AC" Matrix Relay Replaced AC-1 Relay and performed ST-RPS-11.

7017 9-5-80.

. RPS "D" Channel Trip Unit #3 front Replaced trip unit performed patch card connector Pin'#1-CP-RPS-3

~

672h' 9-8-80 WD-32 Analyzer leaks Inspected per procedure and

- repaired tubing leak.

l7065 9-11-80:

Lockout Relay 508 Replaced burned out relay

-.7057 9-10-80

' DG-1 Imersion Heater Transformer Replaced transformer

-7003 9-5-80 iRM_055 overboard Discharge in Cleaned RM-055

- alarm' l7032 9-8-80)

~ CPHS,86Al supervisory light Cleaned switches burned out 17.033-9-12-80 RCV-059 did close when RM-059'

Repacked valve

_ packing too

-vas tripped:-

-tight.

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Monthly; Operations Report.

~Sep.tember 1980

Page Five '

- I; MAI:i'"ENA3CI'(Significant Safety Related) -

M. O. #

t Date-Description-Corrective Action l

7016 9-10-80.

CH-1B - New valves, ' valve seatis, '

. Completed per MP-CH-1-1 and pistons.-

T1611

9-22A80 ~

HCV-8814A: failed open-Replaced solenoid valve 1

'T142

'9-19-60' RRS "C" Channel TU-T calibrate Ccmpleted

-TA32' 9-18-80 LFP-1B Diesel Fire Pump runa hot Removed strainer-and. cleaned T

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