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' 37 462.6 2 442.4- 18 464.4 3- 458.2 ~ 295.4 .

39

. 457.2 20 373.8 5

457.9 375.3 2,

6 .457.1- 22 371.6 l

7 s- 456.l'~ 23 302.2 455.1 8- 24 301.3 9 455.6 25 302.2 I l 30 458.6'- 26 302.6 l

-1I 460.2' 27 301.6 12 459.7 -28 _.

300.9 i '13 459.4 29 300.5 l l 14 460.1 39 299.2 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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• > u OPERATING DATA REPORT'

- - n '. , 7 a - DOCKET NO. 50-285-

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DATE 1 October- 10, 1980?

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COMPLETED BY Tc L. Patterson : '

. TELEPHONE: (402)536-4413

' IOPERATING STATUS I Not*5

• Fort Calhoun No.11 * '

O Unit Name:

d/ Reporting Periodi 'SeDtember,i1980 .

, . ,3.: Licensed Thermal Powei(MWt):- 1500-

[ T4. Naineplate. Rating (Gross MWe){. 502-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 powerit o -1500:MWt effective Auoust 15. 1980 L-N/A

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

10. Reasons For Restrictions,1f'Any: N/A-M, ,

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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~

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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_,

e ;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--

' '. 7 21 . p. Unit Capacity Facht (Using MDC Net)j 87.9 - 42.0 ' :64.3 7

3 22.(Unit Capacity Factor;(Using DER Net) - 87.9 1 42.0- 63.9-

[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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DOCKET NO., 50-285 UNITSIIUTDOWNS AND POWER REDUCTIONS UNITNAME Fort Calhoun Nc.il' u- 'DATE October 10. 1980.

.. 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; -@ ,g g 5 Event - 3,3 g3 Action to

• -. $5 $ ~gg; . Report a m O_ o U '

~ Prevent Recurrence '

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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.

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'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 G-Operational Eiror (Explain) ,

Exhibit I - Same Source (9/77) II-Ot her (E xplain)

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= Refueling- Infon:ntion; , _

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 M3. . Will refueling:or. resumption of operation thereafter -

srequire-altechnicallspecification'changeor:other

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. No-11icense amendment?

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

these bs? :

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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

-September 1, 1981

~it scheduled?,.

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- "

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storage capacity 483

.. g xd) plarmed spent ' fuel pool:

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1 storage capacity 483

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

' liceivicd: capacity. " 19"5

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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 i ..by Operations personnel that the setpoint_. selector 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.f short duration' 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-

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

, f in the non-conservative direction. The other three

- channels-were operable at'the' time and vould have s !provideda necessary triplof the reactor'if necessary.

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

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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 1

September 1980' -

Page Three L.D CHANGES,. TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION 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!

Approved By ,

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AQs-Fort Calhoun Station 1 ,

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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

'T142 1

'9-19-60' RRS "C" Channel TU-T calibrate Ccmpleted Removed strainer-and. cleaned

-TA32' 9-18-80 LFP-1B Diesel Fire Pump runa hot T

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