ML20101Q861

Monthly Operating Rept for June 1992 for Fort Calhoun Station

ML20101Q861
Person / Time
Site:	Fort Calhoun
Issue date:	06/30/1992
From:	Cavanaugh G, Gates W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-92-219R, NUDOCS 9207150135
Download: ML20101Q861 (8)

Text

_ _ _ _ _

., , . , ..- .. - -.. .c zm.==_ . . -r.msw w _ .n . - -

-. _ - -w ,E

- Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska FB102-2247 402/636-2000 Jul5 14, 1992 LIC-92-219R Commission U.

ATTN:S. Nuclear, Document Regulatorbesk Control Hail Station P;-137 Washington, DC 20555

Reference:

Docket No. 60-?85 Gentlemen:

SUBJECT:

June 1992 Monthly Operating Report (MOR)

Enclosed . is the June 1992 MOR ior Fort Calhoun Station (FCS) Unit No. I as required by FCS Technical Specification Section 5.9.1.

If you shor'd have any questions, please contact me.

S8ncerely, {

' AO N.N41 ~

W. G. Gates Division Manager Nuclear Optcations WGG/gec Entlasures c: 1.eBoeuf, Lamb, Leiby & MacRae '

J. L. Milhoan, NRC Regional Administrator, Region IV R. P. Mullikin, NRC Senier Resident inspector h 4 S 0. Bloom, NRC Acting Project Manager R. T. Pearce, Combunion Engineering R. J. Simon, Westinghouse Office of Mana9ement & Program Analysis (?)

IdPO Records Center American Nuclear Insurs s

\

9207150133 920630 PDR- ADOCKO$00-]5 p p ...

a. a . snggy, ), (

yt

n;i ; > g - -

- = - - - - .-

y[ ' -

)y' 1- k3- ~

1_ .

'4 sc t'.

hk CPERATING DATA REPORT-y,y

• DOCKET NO. 50-285 -

UNIT FOR; -CALHOUN STATION i# DATE 3 yid Os B92 COMPLETED BY G. h. CAVANAUGH

> OPERATING STATUS TELEPHONE TTU2)~6T622474

, .--~. _ _ _-

1. Unit Name FORT-CALHOUN STATION i L2. 2 Repor ting Pe r i~6d : (UNE 19T2~ NOTES

, ?3.: Licensed Thernel: Power (MWt): 1500 4./ Nameplate Rating (Gross =MWe): 502

5'. Design Elec. Rating (Net MWe)', 47Tf 3 6., Max.'Dep. Capacity (Gross MWe): 502

7.. Max. Dep. Capecity (Net MWe): 47_8_

1 8.1-IfLchanges occur in Capacity Ratings (3 through 7) utnce last. teport, Egive reasons:

9. Pov br. Level to which restric ted, if any (Net MWe): NA ,_ _ _ ,

50. Reasons for restrictionsi if an',':

NA _ . - _ . _._ _.

THIS MONTH YR-TO-DATE CUMULATIVEs

.  ;:ll.; Hours-in; Reporting Period........... 720.0 4367.0 164497'.0 (12.HNumberiofLHours Reuctor was1 Critical- ~ ~ ~MT[} 2168.2 'lT6f8T.l]

1109.3

-11L/ReactornReserve. Shutdown Hours...... .0 .0-

- il4..yHoursLGenerator On-line............. ~~~~ ~

~689.7 2104.9 125Te~2.0?'

.0 415.JUnit' Reserve Shutdown Hours......... .0 .0 c16. Gross' Thermal-Energy Generated (MWH) 199520.3 2750171.9 164373897.6 '

' 17kGros's!Elec. Energy Generated (MWE).. 334823.0 919TM.T ~$TeV52~'.5.2

18.! Net Elec. Energy Generated (MWH).... -318YS C6 ~ 871756.9 51605500.T ,

J19.fUnit= Service Factore................ ?S.8~ -48.2 16.3

=20'./UnitHAva11 ability Factor............- 95.8 48.2- 71I'J

'70.2 O 21 1 Unit Capacity F&ctors(using MDC Net) 9Fil 41.8

_F22.LUr.it Capacity Factor.(using DER Net) 92.ti 41.8' -

. 66.4 7 . 23 . r Un i t Fo r ced Oilt ag e Ra t e . . . . . . . . . . . . . 4.7 2. T T(

J24'.dShutdowns scheduled over next 6 months (type,-date, and duration of each):

1.F. ORT.fALHOUJLSTATIOILIS _CURRJ:NTLY IN SHUTOOWN_DUF_TO A fv2BLEM WITH A .

SAFETY RELIEF. VALVE. .

L25.[lf' shut'down at end.of report period, estimated date of startup: _01/29/92

[26t l Units 11n tes* stat.us-(prior to comm. oper.): Fo: cast Achieved INITIAL'. CRITICALITY

. INITIAL. ELECTRICITY N/A _ ].

COMMERCIAL OPERATICU . - . -

' 4 .TU _

,g ..

y r

=)

01^- #

s (' -

,'f 4

i c -,. : ,

J R

o AVERAGE DAILY UNIT-POWER LEVEL

! -. s a

'b ,

ET NO. .

E , _

0s~fis2

~

-DATE JfJfiY

'T COMPLETED BY G.-R.-CAVANAUGH TELEPHONE T402) TifiC7474 f

MONTH. JUNE 1992 ggy fyl

• DA?.' AVE'R AGE-DAILY POWER LEVEL DAl AVERAGE DAILY POWER LEVEL 1 (MWe-Net) (MWe-Net)

.. : 1 ! :3- .

17 477 3

'2-

-53 18 477 ,

3 '05 3 19 478 s '4. 4 69 20 479 479

-5 -. 462 . 21 t0 {6j ._,,,,__. -483? 22 479 a: .

7... -

482 -

23- 478 _ _ _ _

t

'8- .

482. 24 478 i:" , ;9 482 25 475

, , f109 482 . 26 475

,. ,C ' .

ll i. ~ 4 61 --.. ,- .

27 . 4 7 5.- .

y ",

.a o

j2l 480' . 28 478 13' -478: 29. 4_78- ---

al i .14 , __

_478 .

30 477 477- 31 f , =15; ,

. < 11 6.- _

477-TN'STRUCTIONE ,

i ,

[Onithis form, list' the. a" era.ge daily unit power level in-MWe-Net for each

$ daysin the' reporting l.onth. . Compute to the nearesh whole megawatt.

'n v

l 6 M _.

g (.

3-l 1$ .k'*

, .4 4

M/,.ijl .,

.a ,

y.

ww-

~;=.p c  ;;+

9 , y x~um:n-pn:.. e-n cy,ym.vn..s:

., , un

.- - -u- -n.4

- ^ m;:

ys ,. .a,.,-

g--; .:

= =.- /~8m: p.m.

n -

.g:

m: w sk-e w,:-

o,, ~=-

e ;: - n

,,e - ,;.- : _ . ~- yp;u. p... ,;py?

- 1- , ;g :;.

< + s -- -

.= . - , .;

-2859 ^ V.. L D.m > -

00CKEF NO.) -

M % i~ m .m

X!Di!T[$HUTDOWNS (JEi POWERJ. EDUCTIONS: , gg; '

?y?h 4

-n y, m

L;=

- > g -

3~~

g g g,w $y . g, g 4 "- x ry:

7DATEKJuly-8.-1992 T y ,

~ , 9 . ,

~ ~

$;f  ;~ " - .

- ~- -

,.  : COMPLETED BY'.G.:R. Cavanauch M MTy ' ^ '

.*  : TELEPHONE '(402) . 636-2474 :

+

'c

,V- ,.,s- < r a ')" l

• -%, . REPORT, MONTH June'19925 -

Q s

,m , , .

i,s . --.1.- ,. - , .

-g

~

Nd. -

2 Daie i iTne' . Duration : - R2ame' a ' Mc H of: ' .iceru.ee i . 'sysem L ccerconeer - cause & Corrective -

a

+  :- (Hai.rs), . . :Shurrungi ' Evers , CueF - Cadet E Action to "

. . Domo Reactnr' =: Report k . Prevers Recurrenec ' i.-~

i _ c- - -

, l;

.9244- ~900531'

'F' 30.3

- A-  ?!T 92419- ,.RB .~0NROD

. ~)ri May 31. 39"2. Cocpol Element Asaceably (CEA) No. 35 dropped in:o

(.

1;- .

. f.c :a.: tor ccee. Rescoor power was reduced tr. 7L*% witida one hour perJ

-4 --

Tecimicel Speciscations. Attempts no recover tue CEA wh% . 70% i i

1-power were masts:,ceaafat: The generstor 3 as teken dline endy in 6e L

. I nrr#mg on June 1.1F..~ , ,

~ ...

w.

5 N

'i. l. .

I L..,.., a.

g i.

z s

- se i

(

.I

~

1  :

. +

4

..T '

-f 1'  !

g 4 L 4

t .

2. 1~ .t F: Forced .

Reanora: M:thod: ExhiM 0 "a h -

S: Schedoled - A-Equipmera Failure (Exp!aia) ~1-Manual for Spars.tionof Dets - i

. B-Mainten mee or Test - 2-Manual Scram., Entry Sheets fo.1* ensee t i- C-Refueling . .. 3-Autamatic 5 cram." Event Report (LEE) Fn (NUREG-0161) .

D-Regulatory Restrictica ... 4-0.her (Exp!ain) - ..

E operdor TreWg A Ucecae Examinadon F-Administrative G-Operational Ener d.xplairs) Exhibit I - Same Scarce H-Other (ExplainF

-3 2

g W e w ' , - ' r " r r r' -

t V4 J  % e .c - +m=n "

-ei. .

1 as

~ ,

+ . ,

6- ,

. . Refueling Information g-$ Fort Calhoun - Unit No.1 4m

' f Report fov Je r.inth ending June 1992' L;.1 Scheduled date fer next refueling shutdown. Seutember 1993 _

2. Scheduled date for restart fallowing refueling. No' ember L993

• 3EWill refueling or remmption of operat eens-thercafter reqaire a t')chnical specification chango or other license amendment? Yes

..< .a. Ifanswer is-yes, what, in general, will tusse be?

Incorporate specific requirements resulting y from reload safety analysis.

~

b. If answer is no, has tne reload fuel design and cure;canfiguraticn been reviewed by your: Plant Safety Review Com7d uae in determine whether any enrevieweo safety yqucstions. are assotiated with the core reload. N/A _

c. If=no-such review has taken place, when is it Y scheduled? N/A <

?4'. Scheduleo date(s)-for submitting pruposed

-licensing action and' support information. June 1991 IS- . Ir.portant licer.fing considera$ ions associated with refueling, e.g., new or different fuel design-tor supplier, unreviewed desicn or performance

---analysis methods, significant changes in fuel 4 design,:new cperating proce:!ures. - t!ew fuel scpplier New LOCA analysis 6.'The number cf fuel assemblies: a)-in the' core 133,Ag er,bl gs b) in the spent ,529Tspmb1'es fuel pool ~

c) spent fuel pool vL storage capacity 17 9 f.sse 611es d) planned spent Planred to De fuel pool increased with higher m storage capacity der.sity spent it.ai racks.

.7.1The projected date of. the last refueling that can bo J - distnarged to the spent. fuel pool assuming the fu , '

7present licensed capacityv 1995*

n

! * -- Caphbility of lW ucre offload of 133 assemblies lost. Reracking to be parformed between the'1993 and 1995 defueling Outages.

~

O Prepared by _ OLL ~ Date u

l ,

i l

,s

' %g:x _ -

7 OMAHA PUBLIC POWER O! STRICT

- Fort Calhoun Station Unit No. 1

. JUNE 1992 Monthly Operating Report I. OPERATIONS

SUMMARY

FortCalhounStation(FCS)wasshutdownJune1stano2ndduetoaGropped Contiol Element Assembly (CLA #35 in Shutdown Group A) caused by a shorted trip coil that-occurred on May 31, 1992. The reactor was placed in hot shutdown on June 1, 1992 and the trip coil was replaced. The reactor was taken critical at 0211 on June 2, 1992 ano the plant resumed 100% power operation on June 4, 1992.

l Both channels of the Qualified Safety Parameter Display System (QSPDS) were declared inoperable on June 4,1992 due to potential calibration inaccuracies which could have been incurred due to an improperly calibrated piece af test equipment (hand held pyrometer). Both channels were recalibrated using a properly calibrated pyrometer, and declared operable the same day.

Dua to severe weather on June 15, 1992, Fort Calhoun Stetton initiated a Missouri . River debris watch and received permission from the State of Nebraska to install deflector logs upstream of the sr.reen house.

Excessin debris (mostly hav) caused the Heal Power Station (a fossil plant upstream from FCS) to trip on low condenser vacuum due to plugging i of traveling screens. The debris dissipated befcre reaching FCS.

On June 10, 1992 bothcontrolelementdrivemechanism(CEDM)coolingfans (VA-2A and 20) tripped due to a false alarm in Containment Fire Detection Zone No. 19. A containment ertry was made to ensure no steam leak was .

occurring near the reactor vessel head (fire was ruled out since other containment-fire zones didn't alarm). An emergency temporary modification was initiated to in%all a. Jumper into the Zone No.19 circuitry to allow running VA-2A and 28, 9

On June 25, 1992, the linea heat rate (LHR) as displayed on the emergency response facility (ERF) cvaputer reached the administrative limit of 13.75 kW/ft (core epurating limit is 13.8 kW/ft). Power was reduced over a three dcy period from 100% to 98.5% to maintain the LHR at less than 13.75 kW/ft. On June 27, 1992, after completion of a reanalysis of the available margin in LHR based upon actual end of Cycle 13 burnus values {

(instead of assumed burnup values), the Plant Review Committee (PRC) approved raising the LHR core operating limit to'14.2 kW/f t. The increase in.the LHR limit allowed FCS to return the reactor to 100% power.

On June 26, 1992 Turbine Stop Valve No. 2 (SV-2) failed to close during the performance of weekly turbine testing per 01-5T-10. Since SV-2 failed to close, trip unit No.10 on reactor protection system (RPS) channel "B" was placed in " Bypass *. This resulted in FCS entering a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> lhiting condition for operation (LCO) per Technical Specification 2.15.1.

Troubleshooting revealed that the failure of SV-2 to close was due to a

Monthly Operating Report June 1992 Page 2 i

malfunctioning test relay. Upon confirming that the normal valve close circuit was operable, the LC0 was exited. A temporary modification completed in early July 1992 lnstalled a switch in place of the test relay. The switch is to be replaced with a new test relay in late July 1992.

On June 30, 1992 the Pyrotronics (TM) XL-3 Fire Detection Panel located in the Control Room caused numerous f alse clarms de : to a failed circuit card. The failure tri9 ped ventilation unics in the Control Room and containment, and started bott, fire pumps. Technical Specification 2.19 -

required continuous fire watches in Room No.19 and the other rooms witti a alarms / malfunctions on tra XL-3 Fire Detection Panel. The circuit er d was re) laced, the XL-3 panel was verified operable and the Techni;al Specification LCO exiteo later that same day.

The following NRC Inspections took place during June 1G92:

IER Not Title 91.-14 Monthly Resident Inspection ,

The following LERs were submitted curing June 1992: ,

LER No. Description LER-92-014 Reacter Trh following Maintenance on Moisture Separator Level Instrument LER-92-018 Corrosion of Boric Acid system Bcits -

LER-92-019 Control Element Assembly Drop and Sub equent Plant Shutdown Due to Clutch Coil Failure A. SAFETY VALVES OR PORV CHALLENGCS OR FAILURES THAT OCCURRED None D

'B. RESULTS OF LEAV RATE TESTS Reactorcoolantsystem(RCS)leakageduringthemonthofJune1992 was generally low. Early in June 1992_, there were two (2) negative Total and Unknown leak rate test results thas occurred during periods of water addition for reactivity control. Also, early in the month, higher than normal leak rates were attributed to charging >

pump CH-1C packing leakage. This pump was isolated and later repacked beginning on June 13.

1

_ _ _ _ . _ . . . . . _ . . . . . . . . . . . . . . . . -q.q ,,y. ,, ,

, 3, y , ,

,y

. , -. _ _ __ .~ . . _ . . _ . - - _ _ _

+

'M6nthly Operating Report 1

June 1992 l Page 3  !

Once the plant achieved equilibrium conditions at full licensed  !

power, the Total leak rate was approximately 0.1 gpm. On June 30, i the Total leak rate increased to 0.376 gpm due to "B" charginC pump discharge valve (CH-192) packing leakage. I C. CHANGES, TESTS AND- EXPERIMENTS REQUIRING NUCLE /.R REGULATORY COMMISSION-AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment NR,, Deseri_ tion 146 This amendment revises the Technical Specifications to increase the maximum allowable setpoint drift for the main steam safety valve (MSSV) setpoirt from 11% to +3%/-2% and to specify lift sei. tings for all MSSVs and for the two pressurizer safety valves.

D .- - SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE M0!iTH OF JUNE 199?

Some of the significant corrective maintenance work performed during the month of June follows:

Lift was adjusted on raw water pump AC-10A.

I Spent fuel pool circulatin0 pump AC-5C was rebuilt. -

New internal discherge pump check valves and top caps were installed per ECH 90-258 into charging pump CH-10. ,

. Adjusted relief cetpoint on charging pump CH-1C suction relief valve CH-178. .

Corrected leak on fuel oil transfer pump suction strainer F0-SA-1.

Replaced instrunent air regulator on high pressure safety

-injection (HPSI) pump SI-2A discharge valve HCV-2928.

Replaced the breaker in MCC-4A2 C04, feeder for boric acid.

pump CH-4B, to correct tripping probien. -

Replaced 52/AS auxiliary switch .(General Electric Type SBM)-

.c for breaker IA4-5, feeder for feed pump FW-4C.

t a!

t

. ._.,