ML20071G279

/03L-0 on 781214:during 1978 Refueling Outage, Certain Surveillance Tests Req by Tech Specs Could Not Be Performed Because of Shutdown Condition.Facil Lic Change 77-11 Submitted to NRC on 781109 to Delete Requirements

ML20071G279
Person / Time
Site:	Fort Calhoun
Issue date:	12/19/1978
From:	Kusek L OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20071G278	List: ML20071G273 ML20071G279
References
LER-78-044-03L, LER-78-44-3L, NUDOCS 7812270333
Download: ML20071G279 (7)

Text

.

tm .

LICENSEE EVENT REPORT CON 7act BLOCx: 1 1 I I I I l tri. EASE PRINT GQ TYPE ALL REQUIRED INFOKMATItN) i e@

I ]

'oitl4 l*I s I" IF lC ucassas cess IS 11 i*

l@l *$

o I O I O I O WGEN44N4MHm lo Io lo lo In  :$ lo :SIn l@lhI1l11111l@l WOEN$t Tvel 4J 57 sa7$d@

CON'T cf5!

4

• '*0,"[

, e l L @l 015cocxt?NyMsga 6G el t o 1010121815 @l 1121 il L I 718 64 69 EvtNT QATg 74 75 @li l 2 l .10 I T IB age:mTATE 8:

EVENT OES*RIPTION AND PROBASLE CONSECUENCES h I 1 o i:3 IDuring the 1978 Refueling Outage certain surveillance tests reentrad tv See-ten 3.0 s-d as I

3 ,3 ,  ; Appendix B of the Fort Ca N un Station Technical Specifications vere not perfer=ed.

,o ,,,gscheduled because of the refueling shutdevn condition (Operating Mode 5) of the tlant.

l

, , ,, , , Facility License Change No. 77-11 vas sub=itted to the Nuclear Regulater/ Cen:=ission on l046} lSepte= Der 9, 1977, an again On November 9, 1978. The approval of this Facility License l y,;.,9 0bange vould delete the requirements to perform these surveillance tests when the plant l ,

t

- . is in the refueling shutdovn condition. 30 I

I L9 VALyg

? , 9 COMP.

$YSTEM CAU$t *AU$1 SuSCODE SUSCODE COct COQt SUSCODE COMPCNENT CCQt jiTTG 1 x 1 x l@ {x,,J@ l zi@ 1212 l c 1: Ic12 l@ L.ij is is i

@ W: @ 2

. . i2 ii  :

OccymmfNCE mtPcm? 9 tV'520N

' $EQUE NT! AL Nc.

a tPCmT NC. CCCE *V et EVENTytam,

@ ;Lf9.80 <;ja7 17 18 I l-1 Ioi4ihI L<,J l of 3I II I l-l Lo,,J 22 :2  :. a 2, a a ;o si  ::

_2i NPRO PmlME COM*. COV*0NENT Shut 3CwN ATTACHMENT syPPUEm MANyPAC vatm ACTION .Pytymt testC* $USMITTED PCmM >us.

dCum3 **

L.21]@ 12iololo'2 TAKEN ACTION CNPLANT METHCO l01010101.o l.JJ @ L.2.J.J@

fxl@ixl@ l Zl@

22 2 2.

la21 @ 2_, i o CAUSE DESCRIPTION AND CORRECTIVE ACTICNS h a~*d ba I l ialIThe subject surveillance tests either could not be terfe n ed, er these yhdah

-w, -.^ e'-~ t

,, ,.,lperfor=ed veuld not yield useful or meaningful data when the tia-- is t r

g  ; ;shutdevn condition. Facili y License Change No. 77-11 was sub=itted :: the Nuclear t I

,, ,,, l Regulate:/ Cen=ission en Septe=ber 9,1977, and again en Neve=Cer 9.1972 i

?

t i1 !'l l 33 7 8 9 "E"00 0' --

-+

s actuTV 30 CIS00vtav CfSOOVtmY OE30m'PTf 0N s A?us  % PCwt9 CT).Em STATUS I P a'*ia -

f l1 85l lEl y 4 9 lofofchl to  :: 11

?*A de l lA

.S l h Tec'ar.iaal d6 99acifica-10".

20 ACT1ViTV CONTENT - LOCATION CP m! LEASE - ,

EEL 3 Asts op ati3 A38 AMOUNT CP AO*lvtTV I

! SA l I S l l C ( *(h l Cl :4l NA ~

M 85 3J 3 3 i: 11

• tP10NNE. EMPO$b8 83 ,

n,veta vet Ots mtP*1CN d i p i -i I c ! o I o !@l : !@l NA 1:

• 3 3 t1  ; 2 usas:sstu. s is '

w.ie t s :Es:miPm0N NA l1 i na 101010l@l i- ,:

1 t

.:3s vot

s :n aunct OES:miet:ON

-: =A::u-v g' . ' '

i-l3i } 21/El

• Na-i;

.mI;"%L..:~@

2 781227crs3 sa: 's: = - ,

, r ,, i i .

ii::iiiii ,:

niy mim gg o u  :

> i a  :

- 30 7-CN E:

N/.ycassorsApeq

. ~--- -. - - - - - . - _ - - - ..

t N

LIE TS-OLL C aha Public Power District Fort Calhoun Station Unit No. 1 Dcchet No. 050cc285 4

Attachment No. 1 Safety Analysis A review of the subject surveillance tests (see Attachment No. 2) indicates that failure to perfom these tests during the refueling shutdown condition would j

not result in degraded system performance or any unsafe condition. Some of these s cieillance tests cannot be performed because test initirl conditions cannet be satisfied due to the refueling shutdown status of the plant. If these initial conditions vero relaxed or deleted, damage to equipment may result. Other sur-veillance tests if performed during the refueling shutdown conditien vonld yield i ( results/ test data which would not be useful or meaningful.

Selected surveillance tests were perfor=ed in order to determine the enerability of safety syste=s prior to the plant's return to operation after the 1978 Refueling oute.ge. In addition it is and has been co=nen practice to test equip =ent and systems after maintenance er =odifications have been gL r

s e

, -- m -- -- , , , , , ~+ ,n.,- - . , - - - - , - - - - - --,

1E?. 78-chi C=aha Public Pover District j

Fer Calhoun Sta, ion Unit 30. 1 D cket Ho. 05000265

• Attachment No. 2 Cause Descrittien and Corrective Action The following surveillance tests were not perfor=ed during the 1978 Refueling Outage because of the refueling shutdevn status of the plant.

Surveillance Test Surveillance Test Section Nu=ber Title Regulating CIA Groups / Transient 7.2 ST-CEA-1 Insertion L1=it Check

{

Regulating CIA Groups / Transient F.3 ST-CIA-1 Insertion Limit Check Con rel Element Asse=bly Check F.h ST-CEA-1

?DIL, Drl and SEQ Mcnitoring Syste= Test F.5 ST-CEA-1 Secondary CEA Position Indicating F.6 ST-CIA-1 Syste= FDIL, Drl, OCS and Overlap Monitoring Systa= Test RCS Ccid Leg Te=peratr e Check F.1 ST-017-1 F.1 ST-CIIM-1 S/G Water Iodine-131 Concentration 7.1 ST-CEi-1 Secondary Plan: 31cvdown and Leakage Releases Isotcpic A::ivity Analysis Secondary Plant 31cvdown and Leakage F.2 ST-CE4-1 Proper:icnal C =posite for Tritiu=

Analysis and Gross Alpha Analysis RM-057 Condenser Air Ejec cr Releases F.2 ST-C E4-1 Gross Ga==a and Individual Ga--a I=itters Activity Analysis F.1 ST-DG-1 Diesel Fuel Invente:/

3iver Te=peratr e Monit: ring-Data F.1 ST-ITI-1 Collection Eiver Te=peratre Mcnitoring-Data F.2 SI-ET7-1 Collection F.;

37_rr;-2 Surfaca N-c ' # -- a Measre=ents and I:cther: 710ts

-N*" r~ -- , y

- . _ - _ . _ _ - _ . ~_

• ~.i' "6-Chh C-aka Public ?cver District Fort Calhoun Station Unit No. 1 Dcchet Sc. 050002S5 Attachment 30. 2 (Continued)

Surveillance Test Surveillance Test Nu=ber Title Section ST-ETI-2 Surface The.-=1 Flu =e Isother= Reports F.2 ST-EN-2 Triple-depth Ther-=1 Plu=e Measurements F.3 and Isothe._. Plots ST-Erl-2 Triple-depth Ther=al Flu =e Isother: F.h Reports

( ST-Erl-2 Ther=al Plu=e Measurements F.5 (Infrared Sca=ing)

ST-ETI-2 The._.21 Plu=e Isothermal Plots F.6 (Infrared Sca=ing)

ST-E N h Traveling Screen I=pingement F.1 (Not Required Vnen Circulators Are Down)

ST-Eri L Processing of I=pinge=ent Data (Data F.2 Not Required 7nen Circulators Are Down)

ST-ISF-1 Pressuricer Pressure Channel Check F.1 ST-ESF-1 Fressuricer Pressure Channel Check F.2 ST-ISF-2 Channel "A" Safety Injectic: Actuation F.1 Signal Test ST-ESF-2 Channel "3" Safety Injection Actuation F.2

' Signal Test i

Contain=ent Pressure Cha=e1 Check F.1 ST-ESF-3 ST-ISF h Channel "A" Centain=ent Spra/ F.1 l

l Actuation Signal Tes Cha=el "S" Centain=en: Spray F.2 ST-ISF L Actuation Si nal Tes i

Aute=stic Lcad Sequenc*r Che0k E1 '

.e ._ r..ez _ ,:

Diesel Genera:cr Chech F.2 ST-ISF-6 S*3W Tank level Cha=e1 Check F.1 ST-ESF ~

i 5 3W T .nh Level Cha=e1 ~ heck I2

.e . _ --:-. _ i l

i I

i l

l 1

LIR 'TS-Ohh C=aha Public Power District i

Fcrt Calhoun Station Unit Uc. 1 i Locket No. 05000285 Attach =ent No. 2 (Continued)

Surveillance Test Surveillance Test Nu=ber Title Secticn ST-ESF-8 Safety Injection Tank Level and F.1 Pressure Instru=ents Check ST-ESF-9 Ecric Acid Tank Level Check F.1 ST-ESF-11 Stea: Generator Pressure Channel Check F.1

( ST-ESF-12 SIRW Tank Te=perature Check F.1 ST-ESF-12 SIRW Tank Te=perature Check F.2 ST-ESF-13 Channel "A" Recirculation Actuation F.1 Signal Test ST-ESF-13 Channel "B" Recirculation Actuation F.2 Signal Test ST-FW-1 Pu=p and Re=otely Operated Valve Check F.1 ST-ICI-l Calculation of Tctal Integrated F.1 Radial Feaking Factor and Total Planar Radial Feaking Factor ST-ICI-2 Incore Detector Alar = Li=its Verification F.1

, k ST-ISI-CVCS-3 CVCS Fu=p Test F.1 ST-?L-1 Fressurizer Level Channel Check F.1 ST-?L-1 Pressurizer Level Channel Check F.2 ST-RA-1 Reactivity Salance F.1 ST-RA-1 Nor=ali:stien of Cc=puted Ecren F.2 Concentratien vs. Surnup Cu-te ST-RCF-1 Reacter Ccclant Syste Flev Rate F.1 Deter =ination Rese:cr Occian: SFste: I/.tr.h Este 7.1 S~-R1T-3 Calculation ST-?25-1 ?cver Range Safety Channels Check F.1

?cver Range Safety Channel Ai,'us:=ent F.2 ST-?SS-1

l' 4

T. 7bOhh O=sha Public Power District Fort Calhoun Statien Unit No. 1 Decket No. 05000285 Attachment No. 2 (Continued)

Surveillance Test Surveillance Test Section Number Title Power Range Safety Channels Test F.3 ST-RPS-1 Wide Range Logarithmic Channel Functional F.2 ST-?SS-2 Check F.1 ST-??S-3 Reactor Coolant Flow Check Reactor Coolant Lov Flov Trip Check F.2 ST-?SS-3 Ther al Margin /Lov Pressure Channels F.1 ST-??S h .

Check Thermal Margin /Lov Pressure Channels F.2 ST-RPS h Check High Pressurizer Pressure Channels Check F.1 ST-RPS-5 High Pressurizer Pressure Channels Check F.2 ST-R?S-5 F.2 ST-RPS-o Steam Generator Level Channels Test F.1 ST-?SS-7 Stea= Generator Pressure Check F.2

- ST-??S-7 Stea= Generator Pressure Channels Test High Centainment Pressure Channels Check F.1 ST-??S-6 F.1 ST-RPS-9 Turbine Loss of Lead Channel Check Manual Trip Check F.1 ST-?SS-10 i

' RFS Lcgic Units Test F.1 ST-??S-11 F.1 ST-?SS-12 Axial ?cver Distribution Channels Check F.2 4

ST-??S-12 Anial Fever Distributien Channels Test C=' 4 %e- 4 ~ cecondar/ CIA Positiening F.1 ST-SCIA?!S-1 F.2 ST-SCIA?IS-1 Calibration of Secendar/ CIA Inter 1ceks and Alar:s Ingineered Safeguards V.echanical Checks F.1 ST-5:/CS-1

- e 4

i La 78-ohh C=aha Public Power District Fort Calheun Station Unit No.1 Docket No. 05000255 Attachment No. 2 (Continued)

Surveillance Test Surte111ance Test Section nu=ber Title F.2 ST-SI/CS-1 SI Tank Check Valve Check F.1 ST-T3-1 Turbine Runback Circuit Check It was deterraned that the above surveillance tests either could not be i perfo: ed er those which could be performed would not yield useful or meaningful data when the plant was in the refueling shutdown ecndition.

Facility License Change No. 77-11 was sub=itted to the Nuclear Regulator /

Cc==ission on September 9,1977, and again on November 9,1978, in order to ful-fill the requirements specified by the C=aha Public Power District as corrective action to a previously identified ite= of nonce:pliance. The approval of this Facility License Change would delete the requirements to perfor= the subject surveillance tests when the plant is in the refu211ng shutdown condition (Operating Mode 5).

/

j ./

1jfllft}b

, .- -_. . _ , . - . . _ _ . _