ML20117H698

Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A

ML20117H698
Person / Time
Site:	Fort Calhoun
Issue date:	05/20/1996
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20117H692	List: LIC-96-0070, Forwards Application for Amend to License DPR-40,revising TS to Clarify Surveillance Test Requirements in TS 3.1,Tables 3-1,3-2,3-3 & 3-3A,per GL 96-01 & NUREG-1432 ML20117H695 ML20117H698
References
NUDOCS 9605290062
Download: ML20117H698 (33)

Text

-

f i - -

o I

t w

I 1

TECHNICAL SPECIFICATIONS '

1 i

l TABLE OF CONTENTS PAGE .

l DEFINITIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........................... 1 l l

l l

1.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SE'ITINGS . . . . . . . . . . . . . . . . 1-1 I  :

(

! 1.1 Safety Limits - Reactor Core ................ . . . . . . . . . . . . . . . . . . . 1-1  ;

l 1.2 Safety Limit, Reactor Coolant System Pressure . ........................ 1-4 l.3 Limiting Safety System Settings, Reactor Protective System . . . . . . . . . . . . . . . . . 1-6 i

[

2.0 LIMITING CONDITIONS FOR OPERATION . ......................... . . 2-0 2.0.1 General Requirements ... .. ........................... 2-0 2.1 Reactor Coolant System ........ .. . .... . . . .. . . . . . . . . . .. . . . . . 2-1 2.1.1 Operable Components ................................... 2-1 2.1.2 Heatup and Cooldown Rate . . . .. ......................... 2-3 2.1.3 Reactor Coolant Radioactivity ... .. ...... .. .. .. ...... ..... .. 2-8 1

2.1.4 Reactor Coolant System Leakage Limits . . . . . . . . . . . . . . . . . . . . .. 2-11 l

[ 2.1.5 Maximum Reactor Coolant Oxygen and Halogens Concentrations . . .. . . . . 2-13 l

2.1.6 Precurizer and Main Steam Safety Valves . . . . . . . . . . . . . . . . . . . . . . 2-15 2.1.7 Pressurizer Operability . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 2-16a l 2.1.8 Reactor Coolant System Vents . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-16b 2.2 Cheraical and Volume Control System .............................. 2-17 2.3 Emergenc- / Core Cooling System . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . .. 2-20 2.4 Containment Cooling . . . ........... ....................... . 2-24 2.5 Steam and Feedwater System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-28 2.6 Containment System . . . . . ............. . . . . . . . . . . . . . . . . . . . . 2-30 2.7 Electrical Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-32 2.8 Refueling Operations ...... .................................. 2-37 2.9 Radioactive Waste Disposal System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-40 2.10 Reactor Core . . . . . . . . . . . . . . . . . . . . . ........................ 2-48 ,

i 2.10.1 Minimum Conditions for Criticality . . . . . . . . . . . . . . . . . . . . . . . . . 2-48 l

^

pity-C6HRt(SystemWs-Phytics Par Limits . . . . ..... ...... ...................... 20 2.10.3 D_EL_ETED

-m h Cer: !:==:::::!c 2 51 2.10.4 Power Distribution Limits . . . . . . . . . . . . . . . . . . . . . . 2-56 2.11 Deleted DELETED,

&w ..-

l 1 Amendment No. 4-! ,15.27,32,38,52,5 d .

I

_C7.- ,47. ,_DA,O

. _ f. ,Of ,1. A f_,1._ C1,147. 140 1

I J

l 960529006i 960520 PDR ADOCK 05000205 s enn

b 9

' 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System (Continued) 2.1.7 Pressurizer Operability Aeolicability Applies to the status of the pressurizer and pressurizer heaters.

Obiective To specify minimum requirements pertaining to the pressurizer water volume and availability of heaters for accident conditions. l Soecifications j (1) The pressurizer shall be operable with at least 150 KW of pressurizer heaters, I and pressurizer inventory shall be maintained in a range of level 40.5% to 69.2 %.

]

a. With the pressurizer inoperable due to an inoperable emergency power .

supply to the pressurizer heaters either restore the inoperable l emergency power supply within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. With the pressurizer otherwise inoperable, be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

This is applicable for Modes 1 and 2.

b. With the pressurizer level outside the above range, either restore the wit

• level within the specified l' u SHUTDOW i m the follow 1 g 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This is applicable for  !

e and , ::.;;p: during :ncnily ::::ing of i; pr;.::uri :: !;c 1 l centro! circuit.

i Basis vf )

The requirement that 150 KW of pressurizer heaters and their associated controls be l capable of being supplied electrical power from an emergency bus provides assurance l

that these heaters can be energized during a loss of offsite power condition to )

maintain natural circulation at HOT SHUTDOWN. Either diesel generator is equipped with 225 KW of heater capacity. Either diesel will fulfill the minimum requirements of this specification. The level should be maintained above the lower limit to prevent heater cutoff and the upper limit should not be exceeded to prevent going solid or reducing the effectiveness of the pressurizer sprays by immersion during an RCS swell transient.

2-16a Amendment No. 5456

O l

l 4

i-3.0 SURVEILLANCE REOUIREMENTS 3.1 Instrumentation and Control L

Aeolicability Applies to the reactor protective system and other critical instrumentation and l controls.

i i

l Obiective l t  :

1 I

To specify the minimum frequency and type of surveillance to be applied ,to critical  !

l plant instrumentation and controls. j Specifications

. Calibration, testing and checking of instrument channels, reactor protective system and engineered safeguards system logic channels and miscellaneous instrument systems and controls shall be performed as specified in Tables 3-1 to 3-3a.

Basis l Failures such as blown instrument fuses, defective indicators, and faulted amplifiers which result ir " upscale" or "downscale" indication can be easily recognized by simple observation of the functioning of an instrument or system. Furthermore, such i failures are, in many cases, revealed by alarm or annunciator action and a check  !

supplements this type of built-in surveillanc  !

g If the channels ~are n~ o rmallp'off Liale during' times wisn SuWeillanc^c'is'~r@dited,' tiid  ;

(' CHANNEL CHECK will only verify that they are off scale in the same direction.f Off scale low current loop channels are verified to be reading at the bottom of the r_ange and not failed _d,ownscale,

~ ,

stric't xperie e in operation of conventional power plants and on reported nuclear plant experience, a checl:ing frequency of once-per-shift is deemed adequate for reactor and steam system instrumentation. Calibrations are performed to ensure the presentation and acquisition of accurate information The power range safety channels are calibrat d (lientibiila66egjhysip). ily against a calorimetric balance standard to a count for errors induced by changi rod patterns and core physics parameters.

r Other channels, subject only to the " drift" errors, can be expected to remain within acceptable tolerances if recalibration is performed on a refueling frequenc

! 3-1 Amendment No. 9,122,125,157

im s i%

4 3.0 SURVEILLANCE REOUIREMENTS 3.1 Instmmentation and Control (Continued)

Substantial calibration shifts within a channel (essentially a channel failure) will be revealed during routine checking and testing procedures.

The minimum calibration frequencies of once-per- ay (hsitibalaiQikijsihiiss} nip) for the power range safety channels, and once eac fueling shutdown for the process system channels, are considered adequate.

The minimum testing frequency for those instrument channels connected to the Reactor Protective System and Engineered Safety Features is based on ABB/CE probabilistic risk analyses and the accumulation of specific operating history. The quarterly frequency for the channel functional tests for these systems is based on the analyses presented in the NRC approved topical report CEN-327-A, "RPS/ESFAS Extended Test Interval Evaluation," as supplemented, and OPPD's Engineering Anal sis EA-FC-93-064, "RPS/ESF Functional Test Drift Analysis."

ThR16V[E6ipenniMEsitp6inibifeiF[6pedidifreliif5faly6"(PORVE.CHANNEC PUNCTIONAllTESTl Verifies!6perabilitifofithstandstidd*sirssidylssingftlEinstalisi hyitches rgregiist;jRYj!actuatioh couldMisuriz{ti(naskN6istjyjM6dlif

)J I

3-2 Arr.endment No. M3

• . s TABLE 3-1 MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTEh!

Channel Description Surveillance Function Freauency Surveillance Method

1. Power Range Safety a. Ch ck! S a. Ccmper!=n cf fcur pener ch==! readin;;

Channels fer 509 net:r- = =d her ! pc" -

.1. )_Ne..utn..w.t .F.. l. u.it 1)l.l ". C. H. . A. N..N. ..E...C CHECK 2))Thermalpwerf 2)( [ CHANNEL CHECK

b. Adjustment DM b. Channel adjustment to agree with heat balance calculation.

c. C:!!b=:: =d Te t QM c. pHANNEL FUNCTIONAL TEST h::=c! :=: mgnc!

c ::rify

• rip , :!amr, =d Te: per := ve =d

icn=r circuits.

2. Wide-Range Logarithmic a. Check S a. QHANNEL CHEC.K Cc pan =n of ' cur cide ng:

Neutron Monitors  ::: dinO :.

i

b. Test *4 P b. CHANNEC4FUNCTIONAIrTEST In::=c! :=:

sign:E e ';::iff SUR 4.di :n ,'=d :dp, pen:: !:ce!

pe  :=:ve, r:===: 2 curacy.

3. Reactor Coolant Flow a. Check S a. CHANNEllCHECK Cc= pari = cf reur =p =:e deta! '!c ' :ndice!c=.

b. Tes..t. C:!!b=:: QmR b. NE n CHAN.g . L FUNCTION. . g.g AL T..gE. ,ST"no.g g ', differ =, :id devices-

c. Calibrate' RQ'2' c. CHANNELCALIBRATIONj Bis::b!: trip :=:::"*

3-3 Amendment No. 60,463 J

• e o

TABLE 3-1 (Continued)

MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTEM Channel Description Surveillance Function Frequency Surveillance Method

4. Thermal Margin / Low a. Check: S a. Q.ask+

Pressure 1) Pressure; CHANNEL" CHECK Setpoint Ud5;E-!sEF6f'feuf =p:=:: ::! u!:::d trip T =p =1. :um . p==un =: p9' :ndica::c=.

I

2) Pressure 2) CHANNEL CHEC

• Input D6si;ln!sb~s ~cf ~ 'bi:: p==urizer p==um 4 :nd!:::!~ : (same as 5(a) below),

t. c.,.i. :.n.. ...

._. n. t. c.m.t. . .. .

!) T = pen:u=  !) Knur ==::=. sub :::::ed fer P.TD

'npu: ecinciden- :+' ' nc z, p==ue : pu:.

l

2) P==um 2) Sc ., p==u= pp!!cd : ==c: cc aciden:

' pu: _ _ _ _

i:bygg,.7 =;- =::= ::!!'=:i-be.

~

Test Q"W be.

CHAN, -

o u x .. ...

-. - N.E.U.~,,

.. .. F_UN.~.CTION. AL.T. E. ST.

. . - ~

c3 (Calibratei .  ::R; '

fc2 ft)? il.1)] iCHANNEMCALIBRATION s m, a [@Pytj Temperature.{

Q)] IPressure7 72); [ CHANNEL CALIBRATION I

& I.n. pu..t.s..

5. Iligh-Pressunzer a. Check S a. CHANNELCHECK Pressure C5 .psH65F6f fdiffhp =:: p==u= indie :i =.

b. Test C 'ib=: QmR

b. C.HANN. EL F.UNC. TI.ON.All. TEST. Knc m p==um

c. C libra x_a .m. .te.T - est R. .,Q* c. .CH.. A....N.

4.

NE.._if, CA1I.B. RA_T.~IO.. N. ! Bic :b!: trip :=:er"*

3-4 Amendment No M3 w -- --

• , 4 TAELE 3-1 (Continued)

MINIMUM EEOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYST131 Channel Description , Surveillance Function Freauency Surveillance Method

6. Check CHANNEIRCHECK Cemp =en "r eur !:ce!

Steam Generator level a. S a.

indids: ins %j ifste-

b. Test C: lib = e QmR b. CHANNEL 31 FUNCTIONAL 2 ! TEST . Known difffEs.s!Ff'2h3Es'hpp!MisEdssi. -

c. Calibrate Test R Q'2+ c. CHANNEL CALIBRATIONj Bi::25!: ::ip e::er'4

7. Steam Generator a. Check S a. CHANNEIJCHECK Ccmpa::n er reur p: essure Pressure i ndissfidnipeisn5 :c a

b. Test C:!!b=:e QmR b. CHANNEL FUNCTIONAllTEST Enern p==um iipp!!sfFFEsfE.~

c. Calibrate Test RQ"* c. CHAN!fEL CALIBRATION Bi ::b!: tip ::::er"'

8. Containment Pressure a. Test C:!!b=: 3 QWR

a. .C.gH.j-AN. N. .E. .L. FU..N.sC.~ TION. AL TESTap==um s - - K:'

er..-...~...

b. palitirate Test R..Q"* b. .CHANNE.IE CA.LI.B. R,. ATIO. NS S!me!::: p==um

..u..........g~ g. s --

9. l.oss of lead a. Test P a. CHANNEL FUNCTIONALTEST =un!!y tip 2/'

id61siE5In~hteE sispih!ns.

10. Manual Trips a. Test P a. C g.HA..NN.7g. v . FUN-- C.s.T,I.O..NAL .T. EST!!y EL3 ww - --

=u  ::::

I1. Steam Generator a. Check S a. CHANNELCHECK Cerp icn er feur diff:=nti !

Differential Pressure EFfinid~ 'f.d!E:Iss: 6:r=n 'h: *: e ::::r  ;

n

=

en.

b. Test C:!!b=:e Q")R b. 5 CHANNEllMFUNCTIONALT TEST Known i'ifffEsifff;'2EE!! E":pp!!6d ie inde;;;

'r-

c. Calibrate

. . - c Test RQ*

c. CHANNE.T - ..

T.C...A.. L. IBR. A, -TION Bi ::b!: : ip 3-5 Amendment N 7hM3

• t 1

TABLE 3-1 (Continued)

MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTEM Channel Description Surveillance Function Freauency Surveillance Method M

12. Reactor Protection a. Test Q*0 a. CHANNEU FUNCTIONAL TEST ie.e=2! :=: i System Logic Units 3!E6?is ^3Ed3E~Esi:~F.3:2.biF ' 8:2 :!u::b pc== [

eentfaeters-

13. Axial Power Distribution a. Checki- S a.

r-1 )'TAxial Shape 4 1 )1GaCHANN.ELCH. ECIC Ccmpri== cf fc=

. . . ,( -

g. .g.

2.f..iUpperlTrip Setpo._ intl l 2 )% _

CHANNE.L C. ,. HECK Ccmpri==

cf fc=

3.). Lower Trip;Se..poin. t?-

31)e; iCHANNEL m -

CHECK Ccmpri=

c' fer

b. C:!!b=:e Tesu.

~

i

a. R Q9

b. .C H A N N. E.I) UN IONAL::T.EST En .

c==nt: ,

c. Test C. alibra.ncli.. s Q* R9 ~ c.  !

CHA.;N.. NElf.,,CAL,IBR.,,ATIO. N Trip :=,: Lac ~n ::!:!. . . . .

_.._r_ ..__.._rr..- .-

..r_. _._._.._r_

saiculaneer Notes: (!) n.: bic::b!: : rip :=:= inj:::: : cigan' h:c :50 bic::b!: =d p= cid= p=:i:ic: :::dcu: cf :..: :np =: pcir-(1)(3) e quarterly tests will be done on only one of four channels at a time to prevent reactor trip. '

(2 alibrate using built-in simulated signals.

(3)(4h 'ot required unless the reactor is in the power operating condition and is therefore not required during plant startup and shutdown periods. I P

i 3-6 Amendment N #r422,41  ;

i i

i I

h

. f

<. t TABLE 3-2 MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method

1. Pressurizer Pressure Low a. Check S a. C... H. si..A..N.NE.

--w If, E C.s.s H. g ...C. .K. . Cc=p::i== cf fcur =p:=::

i' 4 .

:== = :=:;0=.

b. Cdib=:e Te.~sti,.,. . . - .

Q"Y.- 9R s-

b. MNCTIONAL., TEST. Encen p==um

!cgie cer: Erd.

d

c. Test Calibrate? RQ*P+

c. C AN.E gg uf.g. i.c gggj.jgf .5..;p 7 ; egg 3 a-+ime-

2. Pressurizer IAw a. Calibrate R a. CHA N : CALIBRATION Pan cf !(h):bec:.

~

Pressure Blocking Circuit W

3. Safety Injection Actua- a. Test Q a. CHANNEll FUNCTIONAL TEST (Simulation of tion Logicl2 ~ PPLS6r~CPHS"2/4'~ logic)~udin[bui! :- :: Ming nye:r Sc:P "c=dby pcrer" =d "nc c=dby

, p^r::" cimuit: '"! S ::ced 'c ^. =d B ch=n:!:

Tec . :" >c-ifj f=:!cning cf:":ictien ci cuit cf !! i equip =n: nc=:!!y cp:=::d by =fe:y fen: = 1

ica :ign6.

b. Test RM b. CHAN NCTIONAL TEST D6-EpMi:'Eu:enliid'i$f  :!: d^ = n = : cperanon

(!::  !(5) c: O)) =d :nduding n!! nc=d ep =:icn 1

~

3-7 Amendment No. 54,441

- - - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . _______ -- -___ - ________ - _ - _ - - - - _ - _ _ _ _ _ _ _ _ - _ - - - - - _ - - _ _ _ _. __-________-__-___________-__--_____________-_______---____--_____D

• t TABLE 3-2 (Continued)

MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF ENGINFERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method

4. Containment Pressure a. Tssi Cdib=:

" QR

~

a. CHAN NACTE.E c:: p====

High Signal 325!$11EEEEEETC"!S'32EiI:n !cgic =f'i d.

b. CaibhEE Test sw.w .w > s. sRQ b. + Hw . AN..

C..w.- u: .w AU m o. x TIBRA..gcw NFB..g.f*TC.g.v.w.

a.:+j -

N =, =O. m.;.P= itch

5. Contamment Spra a. Test Q a. CHANNEUFUNCTIONAUTEST [ Simulation of Xctuation Logic PPLSind CPH5^2/4 logic)'~~ E!Eg' . , bui!

.  :- :=,:!ng o ._. n.. . . ......a.s ,.., . :..__.

_..__._:_..:._..:ii.i._._._a.,.__. .. ... .. .-.,.o..___i_..- ... .

, ~ _ . .,m. . . .. . . . . . .

2. . . . . :r,..

. . .c.. . _.:+ _r .: :.: .:_. : ..:. _c n.

equip = =* nc-- . =f-*y f=::=

__. . ..:__ .. _> . . _ 'd!y 07 =: ' by

b. Test RO b. CHANNECFIJNCTIONAIITEST Cc=p':::

EMEEE$F^iEi~121!ss'"E=Eif^6p5=:5~- (?::- 1(b)

=d 1('-)) =d  :: !: ding :" nc=:' cu:c=:ic cpe=:icn-

6. Containment Radiation a. Check D a. CHANNEL CHECK High Signalm 3-8 Amendment No. M3,41,173

. t

. TABLE 3-2 (Continued)

MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROIE Channel Description Surveillance Function Frequency Surveillance Method

6. (continued) b. Test Q b. CHANNEL FUNCTIONAL TEST

c. Calibrate R c. Secondary and Electronic Calibration performed at refueling frequency. Primary calibration performed with exposure to radioactive sources only when required by the secondary and electronic calibration.

7. Manual Safety Injection a. Test R a. CHANNEIIFUNCITONAUTEST "-- -' : :" "^-

'~ ~ ' " " ~ ~ ~ ~ * " ~ ~~

! ::iction Actuatlod

8. anual ont me t

a. Test C. hecEEN ~~wea R a. "ru ' : ::!:!ce Obserdisolatidnjaldsl6siir6]

isolation ! . . .:::::en A, ctu.ation ,"

CHANNElj

. . ~ " " ~

R b. 05 =: !=!::52n va're  !=u=. '~~~'^"~~

F_U. N. CT.,IO.._NA,..C.. TEST

9. Manual I ::ia:icn~ Containment Za. Test R a. CHANNEUFUNCTIONAUTEST Cent !rm::: Sprjf'Actuationi 9 M-liF'A5153h"35EF5:!53fpEEpiEnd val /= tr:M : pra:e!y.

10. Automatic lead a. Test Q a. CHANNElfFUNCTIONAUTEST Sequencers M3fF 3psedEE 2'! E UEEE61'd d:g nfey fe:::= =::::!c : : ef !::-- 3(2) above-

11. Diesel Testing See Technical Specification 3.7 3-9 Amendrpent No. 54,! ! ! ,! 52,41 1-7-1 7

• . o e

TABLE 3-2 (Continued)

MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF ENGINEERED SAFFTY FEATURES. INSTRUMENTATION AND CONTROIS I

L Channel Description Surveillance Function Frecuency Suneillance Method

12. Diesel Fuel Trans- a. Test M a. Pump run to refill day tank.

fer Pump [

13. SIRW Tank Low a. Check S a. CHANNEL CHECK Ve:ify !=c! :ndie :icn Mrcern .

Ixvel Signal :nd:pfndde:f^:E29.ib. ,

b. Test Q b. CHANNEIJFONCTIONAL TEST A :::: prezure E!i-is!di!E.j;~' hs"Y:s.F 'ei:s!

• hpp!!ed te erh :=k bub 5!::, ent : : ::::. ,

i

c. Calibrate R c. CHANNELi CAllBRATION Knc=- != ! .:g na!

hpp!ief!6^ Ef6EEE STII!:;ie vermed.

14. Safety Injection a. Check S* a. Verify that level and pressure Tank Level and Pres- are within limits.

sure !n :=en" 3-10 Amendment N 444d63,4M

. t i I

i TABLE 3-2 (Continued)

MINIMUM FREOUENCIES FOR CHECKS. CAllBRATIONS AND TESTING OF ENGINEERED SAFF1IT FEATURES. INSTRUMENTATION AND CONTROL 3 Channel Description Surveillance Function Frecuency Suneillance Method

14. (continued) b. Calibrate R b. CHANNEllCALIBRATION Kncrc ;: zur: =d

!!!ffiiisiisJiiddiis"s;ip!!df:c prezu:: =d !:ve!

sensors.

15. Boric Acid Tank Level a. Check W a. Verify that level is within limits. ,

16. Boric Acid Tank a. Check W a. Verify that temperature is within limits.

Temperature

17. Steam Generator low a. Check S a. CHANNEL CHECK Cc=p :: four :ndependen-Pressure Signal (SGLS) pfdsEn's!Ediditihn:7 r

b. Test Q'b b. CHANNEL FUNCTIONAL TEST Simu!a:ed sign !.

t

c. Calibrate R c. CHANNEL) CALIBRATION Ee m pre: ure app!!ed 16'ffed5 Ed' EHf-fii[h6!nd, r 'egic cre--tien, b!=k pe---iz:: , :::c ::::: =d "c've !c:ure:.

3-11 Amendment No ,461,472

'. s' TABLE 3-2 (Continued)

MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Freauency Surveillance Method

18. SIRW Tank Temperature a. Check D"* a. Verify that temperature is within limits.

b. Test R b. Measure temperature of SIRW tank with standard laboratory instru-m nts.

19. Manual Recirculation a. Test R a. CHANNEL FUNCTIONAL TEST "--" ' : : " ^-

' ' ~~ " ' ' ~ ~ ' '

Xctuation Sui:che

20. Recirculation Actuation a. Test Q a. CHANNEU FUNCTIONAL TEST P -: ef ::= 3(c)

Imgic hsiEini"fE^ie:GsEs;;!n'eph h=d':e i ::!::: STLS.

b. Test RA b. C. . H. ..A.N..: N,.E

..~ .

...~.L i.l FUNC.,T.IO.

y, N Al?.. T. EST. Comp! ::

....._...~.my.........

21. 4.16 KV Emergency Bus a. Check S a. Verify voltage readings are above Imw Voltage (Loss of alarm initiation on degraded voltage Voltage and Degraded lev 1 - upervisory lights *o

• Voltage) Actuation Imgic

b. Test Q b. CH ANNE 12 FUNCTIONAL 5 TEST :(Undervoltage ieliy[5)essEsElli2!Sisd"6:-S bi esif e: : : nc.

c. Calibrate R c. CHANNELCALIBRATION Ence- r!::ge app!::d fe"ibEse E3 ~ !EuWE er trip ::::::i^ 'egic

. ._: "-d . j 221 [ Manual Edwpacy,lO,ff. -si.t_e.~. " M.

CT

-...e_st?s WL m_,. R__L af

- 1.~

C.. H. A. .N_N_EU. . F.. ..U, N_ C. T.._ ION..A. L.. .T... ES.T..

Power Low Trip Actuation m

3-12 Amendment No 4!,!53,163,172 a

TABLE 3-2 (Continued)

MINIMUM FREOUENCIES FOR CHECKS. CAllBRATIONS AND TESTING OF ENGINLEKED sat EI Y FEATURES. IN:sIKUMENTATION AND CON I KOLS Channel Description Surveillance Function Frequency Surveillance Method 33-2'l Auxiliary Feedwater c._ ct. . _i_, c c.._,_..y___.

_i____._.,_.._,__.:_

. m_... c_._..__.__

u . ...

. . w . s.

..-7....... ..........go.

M..r ._ , I _.._I. I_...

. . . . D- .._ ..\-

t u f.;,t_

-~ . - O*/

t. c. a.. :t. .. _. _ o, t. 1...._.

b. . O ck S 2. Cc=p : :n ' p=d=: p=== ==rngs.

S:=_=..C=:=.

o..----.. 1- . - :c-m .

t. c.a .:t. .. _ .. _ o. . t. .v....._:____:_,._.__.

C:!!5=:: " 2. Mne.m :!g=' :pp!!=' te :=:e .

c.  :.

n: r.=-

St r .. C . : =.a. =n. :=._,

u. :.._i- . . . . . . . . .

4.-.....:_ c: ..-...j

v. ._ . n c. . . . : _ .a .t._. . t.- _ c : :. : .. :, . : _. . . : . .. . .

x -. . . . . . , . - .. . . - . . . . . ..

t. .r _.

. . . o.

. t. c.,j. ..._ __ r._._ . : _ .a ._ , _ r i rur :., : . : , :,., .: _.. . . . .. . .

' ^ "

Fa? ^LCheck?? " .. FS ? laR 0)) .: Steam Generatore 4 T :( ICHANNEl; CHECK

~ "

' ' P1)

- ~ ' " " ~ " " ~~ '

iWater Level law" '

m ,

....--n

. ii. (W. _id..e.._: R..a.m.ge)~ ~

' ' ' ~

3:2);1lNCHANNEL

~ ~ " * * * " ~ " - ' ' ~ ' ~CHECK

. x _

.a.mmwa

, mf2}?'

_:M ?Siesm ~ 1 Pre..--

GensfatsE "1.

- - ssu.re.. - ~= law ^ ^ ~

'" ' ' ~ ^'~~

v v^" 4 V <;'M!y -W/t:5 -

R$

.- 'yg.....'M$ .

+

JN.lQRN

{b7 UTest:1._ _ tb2

.ctuation thi.c.ay w:. ,. .ax a. ' ~;

x. .m~:

. ya. ,. > .ma EI)2i -

~.. --(A- .-

7 s.i)} duCH. A. NNE!!.F.UN. CTION. . ALTEST

~ - -

~ TcN"

!!W  ? Calibrate $ " S .1RT . ...

 ; il)";m.1 Steam Genera $.?? '

1; '

' ~** s1)'d ' s'CHANNEITCALIBRATION

' ~ ' ' ' ' ' ~ ' '

iWater I. eve!<Imw"^~^

2 . _ . ,en em - f m(W_id. e_R. an.g_e) ^ ' .

I

""7 m C Mem. _ ' " om _.., . am .._CHA_NNE. li~CA. ~i_lBR. ATION - - -

~ mau.xs , --

m m_.____ .-

1 . <

y> m

'E3)? .x Steam Generasor3 ^ sw~ +J .1.. .

u 3)2.~(yCHAN,N. E..L.CALIBR. ATI.O. N.

am - xmmebemn mwndHigh~^ ' ~ ~ ^ ' ^

2..47 ? Manual- Auxiliary~ *^Feedwateri ~ ^ ^# ~

"Ta0' ".Ji~TestF"' " g""MRT ^ ' ~ . " ' * *N2*"%.0aQ" " " " " "" 7^ .lCHANNEUFUNCTIONAL

" " ^ ^ " ~ " ~ ' " ^ ~ ^ ^ " TEST

' ' ' ' ' ' '~ '

" "

• Actuation -^

NOTES: (1) Not required unless pressurizer pressure is above 1700 psia.

(2) CRHS monitors are the containment ats-@rc gaseous radiation monitor and the Auxiliary Building Exhaust Stack gaseous radiation monitor.

(3) Not required unless steam generator pressure is above 600 psia.

(4) QP - Quarterly during designated modes and prior to taking Jie reactor critical if not completed within the previous 92 days (not applicable to a fast trip recovery).

6 Not equired w en outb id(7Q)iTests b'ackup channels such as derived circuits andyquipment that cannot be tested when thel pig _i[at power

-12a mendment No 41,51,65,122,!53,!!,172 I

]

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

e. .'

l TABLE 3-3 (Continued)

MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTLNG OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS l Surveillance Channel Description Function Frequency Surveillance Method

4. DELETED

)

5. Primary to Secondary a. Check D a. CIIANNEL CHECK Leak-Rate Detection Radiation Monitors b. Test Q b. CIIANNEL FUNCTIONAL TEST (RM-054A/B, RM-057)

c. Calibrate R c. Secondary ard Electronic calibration performed at refueling freqtrncy. Primary Calibration performed with exposure to radioactive sources only when re ired by the seconda and ele roni calibration.

c'

~

6. Pressurizer Level a. Check S a. Ve,rifpithat level.is within~ limits. Ccmperise rz. .,..^.ur..n. .in. .'r ir..=.-

.v

b. C:!!bm:0 C.. heck '

9-*~ R M..i.::

xw x-

b. C.

. AN E.C. HE. CK E c"- differen:!:! pre:==

g.g.l.f +-

c. Ten .C. a. l.ib. rates.

• M R!!) c. CHA.N.NEI;C.AL,,IB. RATION Sign ! : !:.- me:::

~  ; , ,

7. CEA Drive System a. Test R a. Verify proper operation of all CEDM system Interlocks interlocks, using simulated signals where necessary.

b. Test P b. If haven't been checked for three months and plant is shutdown.

3-14 Amendment No 4-52,4-74

l

<. t I

\

• i l

! TABLE 3-3 (Continued)

MINihlUM FREOUENCIES FOR CIIECKS, CALIBRATIONS AND TESTING l OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS i

Surveillance Channel Description Function Frequency Surveillance Method

( 8. Dropped CEA Indication a. Test R a. Insert a negative rate of change power signal to all four Power Range Safety Channels to test alarm.

b. Test R b. Insert CEA's below lower electrical limit t t st dro CEA alarm.

9. Calori netric Instmmen- a. Calibrate R a. CHANNEI)CAllBRATION App!y !:ne t-tation d/p :c feed::::: Sc= censcrs.

10. Control Room Ventilation a. Test R a. Check damper operation for DBA mode. <

b. Test R b. Chec control room for positive pressure.

I1. Containment llumidity a. Test R a. CHANNEllFUNCTIONALTEST P! ace =ne :n :

Detector Me %!;;h' HEE!dhp":iE6:phefs. )

12. Interlocks-Isolation Valves a. Test R a. CHANNELFUNCTIONAL TEST Knc=, prezure on Shutdown Cooling Line of265p:!GIh!Ei6F5**ipiEsse : : :!!ers.

13. Control Room Thermome- a. Test R a. Compare reading with calibrated ter thermometer. If not within i 2*F, replace.

3-15 Amendment No. 46,32,!23,!57

'. t TABLE 3-3 (Continued)

MINIMUM FREOUENCIES FOR CHECKS. cal.IBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description Function Frequency Surveillance Method

14. Nuclear Detector Well a. Check S a. CHANNEL CHECK Cc=pri=n c':ndgenden-Cooling Annulus Exit iss.pdisEii;hSd!hds.

Air Temperature

^ 'ne r-Detectors b. Calibrate R b. CH. ANNEIJCALIBRA.

.~ T..IO,. N C:!!b=::

15. Reactor Coolant System a. Check M a. Calculation of reactor coolant flow Flow rate.

16. Pressurizer Pressure a. Check S a. CHANNEI/ CHECK Cc=pri=r cf ndependen-a = a :.:x. :: ' '

r---------o---

17. Resctor Coolant Inlet a. Check S a. CHANNELCHECK Cc=pri=n of :ndependen:

Temperature iss.ps:Epiiifd!hj5.

18. lew-Temperature Set- a. Test PM a. CHANNEE FUNCTIONAL TEST (excluding point Power-Operated sctuation[Vesiff"spk:bi'!:y 5f Ecid :!ch"clicui: y Relief Valves fcf l5i::=p= :u= =:pcir pc.=: cre=::d =!ief v:!=: by u !!!=:!cn of :nc!:!!d :ee: eni:cher.

b. Calibrate R b. j C.HANN.=EL.CALIBRAT. IO. N C 'ib=:: ::mp=2:u=

m. 2 =. . w...=. 1, ; - - -

-y~ . . .

3-16 Amendment N . 8,32,39,96

=. s' TAILE 3-3 (Continued) .

MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description Function Freauency Surveillance Method

19. Auxiliary Feedwater Flow d2 Check M C H_AN..

w . - .N. EIICHEC, .-

K O=:t ch::E.

b], Calibrate R C.HA.NNEC.-_CALIB.R.

, - a- ~ ~ A.T_ ION Kncr p==ur:

W

20. - Subcooled Marei n Monitor a3, Check M CH NE m2.C_H.E.CK O=:: che:E.

m.s.ANm_I -_

bl

~+

Calibrate R CHANNEC' CALIBRATION Kncem p=:: =

iggggp[:5.:.=gggggg;;;3=g;gy;7q79 mputs-

21. PORV Operation and Acoustic s,i T. .e_s.t

. Ghesar M .C..H. A_NN.EL.. . --FU.N..C.,TIO. N.AL. tT,E,mST Ch=:: ch :k.

m Position Indication b] Calibrate R CHANNEI CALIBRATION App!y ::cuni input.

V=ify R Op:=:icn en :=:rg:ncy pc== supply.

22. PORV Block Valve Operation a" Check Q Cycle valve. Valve is exempt from and Position Indication testing when it has been closed to comply with LCO Action Statement 2.1.6(5)a.

10 a

Calibrate R Check valve stroke against limit switch position.

V=ify R ^penbi!hy c :==gency pc== :upp!y.

23. Safety Valve Acoustic s_i. Te_st GherA M CH.

s- A... N..NEO...,F. .U. N.. _C.T...I.O. ~NA. -

L.. TEST Cima:: ch=k Position Indication b; Calibration R pHANNEL; CALIBRATION .'.pp!y accu:>i :npu:.

24. PORV/ Safety Valve Tail af Check M CHANNEL;C((E@ Cime:: che:L Pipe Temperature b; Calibrate R CHANN_ERCALIBRATION App!y Lnce :nput.

3-16a Amendment No 39,51,110,1M

/. .-

t TAILE 3-3 (Continued) ,

MINIMUM FREOUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description Function Freauency Surveillance Method

25. Containment Purge Isolation a. Check M a3 Verify valve position using control Valves (PCV-742A, B, C, & D) room indication.

26. Containment Hydrogen a. Check M a. CHANNEC CHECK Cempri=n of ::2 ding: frc=

Monitors (VA-81 A&B)  ??deiidsihE.ds?

b. Test Q b. Calibrate span /zero using sample gas and check flow rates.

c. Calibrate R c. CHANNEC CALIBRATION C !!b=:: =ing E?.6"isisEds^spp!!:d f63sE==.

27. Containment Water Ixvel a. Check M a. CHANNEUCHECK Ccmp== :ndependen kc:!

Narrow Rang- (LT-599 & iisdi-ijE ~~^'^^

LT-600)

b. Calibrate R b. CHANNEC CALIBRATION Encrn sign !:

hpj!!sfiE': .3n.'

~ "

Wide Range (LT-387 & a. Check M a. CIIANNEIJCHECK Obsers: c :! readin; =d

~

LT-388)  !!b.s!ilifd!! Bh!iis: ding.

b. Calibrate R b. CHANNEllCALIBRATION K cam cigna!: '~ '

hyp!!sile"HEBEs?

28. Containment Wide Range a. Check M a. CHANNEI; CHECK Ccmp=: :ndependen-Pressure Indication hissiiiF3531-!si ~

b. Calibrate R b. C...H... A.. N.. N.. E. I!CALIBR_A.. T.. IO._N. App!y Ene -

29. Toxic Gas Detectors:

YIT-6288A&B (Cl2) a. Check S a. Comparison of readings from redundant YIT-6286A&B (liCl, II SO 3 4) channels.

b. Calibrate M b. Calibrate span /zero using calibration card.

c. Calibrate R c. Calibrate span /zero adjustment with calibration card, and verify using gas standards.

3-16b Amendment No 64,68,82,87.447

• e i e

TA%LE 3-3 (Continued) .

MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Descrirdion Function Frequency Surveillance Method YIS-6287A&B (N2 11,NII 4 3

) a. Check S a. Comparison of readings from redundant channels.

b. Calibrate Q b.

30. Core Exit Thermo- a. Check M a. CHANNEli CHECK Cc=pri= cf meding: f=:r couple ' ' 2 ' 2C#* ^

b. Calibrate R b. CHANNELCALIBRATION C:!!5=:icn er ^,lD ius elfi~fiEEN-?5ir'is'. fig :: =::.

31. Ileated Junction nermocouple (YE-116A and YE-116B) a. Check M a. CHANNEI1 CHECK Cc=pri== = ding: f==

=s:= a = v.a::= x-

b. Calibrate R b. CHANNELCALIBRATION C:!!b=:! er ^./D Ess sesE 4EniEn ::a';6 ting:ceume PM - Prior to scheduled cold leg cooldown below 300*F; monthly whenever temperature remains below 300*F and reactor vessel head is installed.

3-16c Amendment No. 87,407,440,4M I 4

'. l TAILE 3-3A s

MINIMUM FREOUENCY FOR CHECKS. CALI" RATIONS AND FUNCTIONAL TESTING

• OF ALTERNATE SHUTDOWN PANELS (Al-185 AND AI-212)

AND EMERGENCY AUXILIARY FEEDWATER PANEL (AI-179) INSTRUMENTATION AND CONTROL CIRCUITS Surveillance Channel Description Function Frequency Surveillance Method

1. WIDE RANGE a. CHECK M a. CHANNEL CHECK CO PARE "!!DE R

• NGE LOGARITIIMIC POWER AND LTARITM!C MV!ER *.ND SOURCE R? NGE SOURCE RANGE MONITORS !ND! CAT!ONS ufgru cgy7 pet 393g9 (Al-212) IND! CAT!OF l b. CALIBRATE R b. CHANNELCALIBRATION CAL!BRATE US!NG

!NTERWCTEST C!"CU!TS.

2. REACTOR COOLANT COLD a. CllECK M a. CHANNEL' CHECK COMPARE REACTOR LEG TEMPERATURE CTLAur COLD' LEO TEMPER ATURE (Al-185) "!!T" CO".0L BOARD !ND! CAT!ON

b. CALIBRATE R b. CHANNELCALIBRATION AD?UST TO MNO"'N

~

CURRENT SOURCE.

3. REACTOR COOLANT HOT a. CHECK M a. CHANNEL CHECK CO"^.RE REASOR LEG TEMPERATURE COOLp ut ug7 [gg 7gs,pgq37ggg yf373 (Al-185) CONTROL BOARD IND!C?T!ON

b. CALIBRATE R b. .CHANNEUCALIBRATION AD?UST TO KNOWF.

CU"" EFT SOURCE.' ' ~ '

4. PRESSURIZER LEVEL a. CHECK M a. CHANNELCHECK COMPARF PRESSUR!ZER (Al-185) LEyrturrni~ CON 7not3c339!N95c37!ay

b. CALIBRATE R b. CHANNEC CALIBRATION MMO?'u'pyyggppy nigpqgggggg . ppt!gg .

TO SENSOR

5. VOLUME CONTROL a. CHECK M a. CHANNEllCHECK CO"* RE VOLUME TANK LEVEL

~

CeyToer;7 A ug Lgygt w 7pcogrget (Al-185) BOARD !NDICATION

b. CALIBRATE R b. CHANNEL CALIBRATION MMOW D!rtERENT! *.L"PRESSUP E * "PL!ED TO SENSOR.

6. ASP CONTROL a. TEST R a. CHANNEC FUNCTIONAL TEST VERIFY CIRCUITS PROPER ^PU"'*.ND '# ^ LVE OPER AT!ON AND (Al-185) IMD! CAT!OF T"ROUON '.NUAL S"!!TCM GPERAT!ON 3-16d Amendment No 424

TAELE 3-3A (Continued) .

MINIMUM FREOUENCY FOR CIIECES CALIBRATIONS AND FUNCTIONAL TESTING OF ALTERNATE SIIUTDOWN PANELS (Al-185 AND Al-212)

AND EMERGENCY AUXILIARY FEEDWATER PANEL (Al-179) INSTRUMENTATION AND CONTROL CIRCUITS Surveillance Channel Description Function Frequency Surveillance Method

• ' k,i LE EL, W DE RANGE "~~ -'

EL]ECK C-OMW.RE !NDEPENDEuT

( Al-179)

b. CALIBRATE R b. CHANNEIICALIBRATION MMO'."" ~D!FFEFEW ^.L ^ PPLIED

. TO SENSORS.

8. STEAM GENERATOR a. CllECK M a. CHANNEL CHECK CO'.'P ".RE !NDEPENDENT LEVEL, NARROW RANGE !ND! CATIONS.'

(Al-179)

b. CALIBRATE R b. CHANNEL CALIBRATION KNOm"~ ~D!rFERE"TIAL a.PPL!ED TO SENSORS.

9. STEAM GENERATOR a. CilECK M a. CHANNEL CHECK COMPARE !NDEPENDENT PRESSURE INo!c,4 75cgg.' ~ -

(Al-179)

b. CALIBRATE R b. CHANNELCALIBRATION NNOWF "RESSURE

~

APPLIED TO SENSORS.'

10. PRESSURIZER a. CilECK M a. CHANNEL CHECK COMPARE !MDEPENDENT PRESSURE ~!N93C,iT39ug ~

(Al-179)

b. CALIBRATE R b. CHANNECCALIBRATION KNO"'" PRESSURIs APPLIED'TO SENSOR '

11. EAFW CONTROL a. TEST R a. CHANNEC FUNCTIONAL TEST VER!FY CIRCUlTS PROPER'"^.LVE OPEP 'T!OF ^.ND (Al-179) !NDICATIO" T"ROUO" *!ANUAL SWITC!!

OPER^?!O" 3-16e Amendment No.

a. /

TABLE 3-5 (Continued) s USAR Section .

Test h saxy Reference 10c. { continued) 4. Automatic and/or manual initi- R ation of the system shall be demonstrated.

11. Containment Cool- 1. Demonstrate damper action. I year, 2 years, 5 years, and every 5 9.10 ing and Iodine years thereafter.

Removal Fusible Linked Dampers 2. Test a spare fusible link.

12. Diesel Generator Calibrate R 8.4.3 Under-Voltage Relays

13. hiotor Operated Verify the contactor pickup value at R Safety injection <85% of 460 V.

Imop Valve hiotor Starters (IICV-311,

"'.4, 317, 320, 327,

.9, 331, 333, 312, 315, 318, 321)

14. Pressurizer IIcaters Verify control circuits operation R for post-accident heater use.

15. Spent Fuel Pool Test neutron poison 1, 2, 4, 7, and 10 years after Racks dimensional change $rt= dx;g,j installation, and every 5 years weight, neutron attet 4Rm^d'ss C-- thereafter.

and specific graGty cne n.

16. Reactor Coolant 1. Verify all naam:al isolation During er.ch refueling outage just Gas Vent System a

• es in each vent path are prior to plant start-up.

tu the open position.

2. Cycle cach automatic valve in R the vent path through at least one complete cycle of full travel from the control room.

Verification of valve cycling may be determined by observa-tion of position indicating lights.

3. Verify flow through the reactor R o' coolant vent system vent paths.

3-20d Amendment No '!,5!,T,75,7-',80,155,159

1

.- j U.S. Nuclear Regulatory Comission ,

LIC-96-0070 l i

ATTACHMENT B !

i l

1 1

, ION, JUSTIFICATION AND NO SIGNIFICANT HAZARDS CONSIDERATIONS

55 ION AND JUSTIFICATION

.na Public Power District (0 PPD) proposes to revise Tables 3-1, 3-2, 3-3, and 3A of Fort Calhoun Station (FCS) Unit No.1, Technical Specification (TS) 3.1,

.able 3-5 of TS 3.2, and the Table of Contents as follows:

, T1. Delete Table of Contents reference to In-Core Instrumentation and revise TS 2.11 to " DELETED" for consistency. Amendment 167 deleted TS 2.10.3, "In-Core Instrumentation." Amendment 169 inadvertently reinserted "In-Coce Instrumentation" back into the Table of Contents.

2. Delete TS 2.1.7(1)b reference to monthly testing of the pressurizer level -

control circuit. This change is in addition to the change to TS 2.1.7(1)b submitted in OPPD's Application for Amendment dated September 6,1995, -

which sought to remove only the word "monthi= ' The applicable Surveillance Test (TS 3.1, Table 3-3, Item 6) wili no longer apply to ,

pressurizer level instrumentation but will instead apply to the parameter pressurizer level (See Item 13 below). Furthermore, the monthly test to which TS 2.1.7(1)b currently refers is being changed to a CHANNEL CHECK as discussed in Item 13 below.

3. Add clarifying statements to the Basis of Specification 3.1. The additional statements 1) clarify expectations regarding a channel check of channels that are normally off scale during times when the surveillance is required, 2) note that the low temperature setpoint power o valve (PORV) channel functional test (Table 3-3, Item 18.a)perated relief excludes PORV actuation, and 3) clarify that the pwer range safety channels daily calibration consists of heat balance adjustment only. These statements are based on similar information found in NUREG-1432, Combustion Engineering (CE) Standard Technical Specifications (STS).

4. Replace unnecessary text in the Surveillance Method column of Tables 3-1, 3-2, 3-3, and 3-3A with the defined terms, CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, or CHANNEL CALIBRATION. This change will simplify the tables by matching the Surveillance Function (e.g., " Check") with the appropriate definition (e.g., CHANNEL CHECK). Because of this change, a few items in the tables will require text to be moved t either the Channel Description or the Surveillance Function columns to adequately describe the surveillance. In addition, several items in the tables were reordered to a Check-Test-Calibrate sequence for consistency (e.g., Table 3-1, Items 3 & 4, etc.).

5. Change Table 3-1, Item 1.c, (quarterly surveillance of power range safety i.

channels) from " Calibrate and Test" to " Test." Item 1.b requires the -

power rance safety channels to be adjusted (calibrated) daily against a calorimetric balance standard to account for errors induced by changing rod patterns and core physics parameters. As stated in the Basis of Specification 3.1, "The minimum calibration frequencies of once-per-day for the power range safety channels, . . . are considered adequate."

Item 1.c is meant to verify trip unit operability; thus, it is best '

described as a " Test."

i '

1 .

W .. . - _ - _ _ _ _ _ - - - - _ - -

'W DISCUSSION, JUSTIFICATION AND NO SIGNIFICANT HAZARDS CONSIDERATIONS DISCUSSION AND JUSTIFICATION:

Omaha Public Power District (0 PPD) proposes to revise Tables 3-1, 3-2, 3-3, and 3-3A of Fort Calhoun Station (FCS) Unit No.1, Technical Specification (TS) 3.1, Table 3-5 of TS 3.2, and the Table of Contents as follows:

1. Delete Table of Contents reference to In-Core Instrumentation and revise TS 2.11 to " DELETED" for consistency. Amendment 167 deleted TS 2.10.3, "In-Core Instrumentation." Amendment 169 inadvertently reinserted "In-Core Instrumentation" back into the Table of Contents.

2. Delete TS 2.1.7(1)b reference to monthly testing of the pressurizer level control circuit. This change is in addition to the change to TS 2.1.7(1)b submitted in OPPD's Application for Amendment dated September 6,1995, which sought to remove only the word " monthly." The applicable Surveillance Test (TS 3.1, Table 3-3, Item 6) will no longer app.ly to pressurizer level instrumentation but will instead apply to the parameter pressurizer level (See Item 13 below). Furthermore, the monthly test to which TS 2.1.7(1)b currently refers is being changed to a CHANNEL CHECK as discussed in Item 13 below.

3. Add cl ari fying statements to the Basis of Specification 3.1. The additional statements I) clarify expectations regarding a channel check of l channels that are normally off scale during times when the surveillance is required,2)notethatthelowtemperaturesetpointpowero valve (PORV) channel functional test (Table 3-3, Item 18.a)perated relief excludes PORV actuation, and 3) clarify that the power range safety channels daily calibration consists af heat balance adjustment only. These statements are based on similar informatien found in NUREG-1432, Combustion Engineering (CE) Standard Technical Specifications (STS).

4. Replace unnecessary text in the Surveillance Method column of Tables 3-1, 3-2, 3-3, and 3-3A with the defined terms, CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, or CHANNEL CALIBRATION. This change will simplify the tables by matching the Surveillance Function (e.g., " Check") with the appropriate definition (e.g., CHANNEL CHECK). Because of this change, a few items in the tables will require text to be moved to either the Channel Description or the Surveillance Function columns to adequately describe the surveillance. In addition, several items in the tables were reordered to a Check-Test-Calibrate sequence for consistency (e.g., Table  ;

3-1, Items 3 & 4, etc.).

5. Change Table 3-1, Item 1.c, (quarterly surveillance of power range safety channels) from " Calibrate and Test" to " Test." Item 1.b requires the power range safety channels to be adjusted (ca'ibrated) daily against a calorimetric balance standard to account for errors induced by changing rod patterns and core physics parameters. As stated in the Basis of  ;

Specification 3.1, "The minimum calibration frequencies of once-per-day l for the power range safety channels, . . . are considered adequate."

Item 1.c is meant to verify trip unit operability; thus, it is best described as a " Test."

1

\

p .

\ e, ,

\:

DISCUSSION AND JUSTIFICATION (Continued):

6. Remove Footnote No.1 in Table 3-1, and reorder the remaining footnotes.

i Footnote No.1 describes the operation of the bistable trip tester and 15

not needed to clarify any of the surveillance tests that reference it.

7. As stated above, Table 3-1, Item 4 (Thermal Margin / Low Pressure (TM/LP))

is being reordered into a Check-Test-Calibrate sequence. Using the i

defined term CHANNEL CALIBRATION in Item 4.c will allow OPPD to relax the l

current TM/LP calibration with negligible impact on safety. Calibration l of the temperature input will still require a knawn resistance to be substituted for the resistance temperature detector (RTD) but will no longer require that this be done coincident witn a known pressure input.

Similarly, calibration of the pressure input will still require the a) plication of a known pressure to the sensor but will not require that t ais be done coincident with the temperature calibration. The channel functional test that is part of a channel calibration will verify the proper trip function for the process input parameters.

8. Revise the Channel Description for Table 3-2, Items 3, 5, 21, and 23.d to I refer to Engineered Safety Feature (ESF) " Actuation Logic." For consistency, the term " Initiation" is being replaced with " Actuation ~ in the Channel Description for Table 3-2, Items 7, 8, and 9 (testing ESF l manual actuation).

9. Delete " Instruments" from the Channel Description of Table 3-2, Item 14 I l (safety injection tank (SIT) level and pressure instruments). This will l make the Channel Description consistent with the Surveillance Method, l 1.e., " Verify that SIT level and pressure are within limits."

l

10. Insert a new Item 22 into Table 3-2 for testing manual actuation of the Off-site Power Low Signal (0PLS) channel and move the current Item 22 to Item 23. Testing manual actuation of the OPLS channel is currently accomplished during the refueling calibration of Item 21. Therefore, the intent of this change is to more clearly state the requirement for testing manual actuation of OPLS and not to change the test currently done.

11. Table 3-2, Item 23 (formerly Item 22) concerning the Auxiliary Feedwater Channel is being revised to a Check-Test-Calibrate Surveillance Frequency sequence for coraistency with the other items in Table 3-2. Item 24 is

! being added to Table 3-2 for testing manual actuation of the Auxiliary l Feedwater Channel. Testing manual actuation of the Auxiliary Feedwater Channel is currently accomplished under the existing Specification (Item 22.d.b). Therefore, the intent of this change is to more clearly state

the requirement for testing manual actuation of the Auxiliary Feedwater l Channel and not to change the test currently done.

12. Add Footnote No. 7 to Table 3-2 to clarify that the refueling frequency ESF channel functional test pertains to the backup channels such as

, derived circuits and equipment that cannot be tested when the plant is at

power.

i i

2

)

i

)

"e .

l DISCUSSION AND .10STITICATION (Continued):

13. Revise the Channel Description of Table 3-3, Item 6, to " Pressurizer Level" and change the shiftly surveillance (Item 6.a) to " Verify that level is within limits." This change makes Item 6.a similar to CE STS Surveillance Requirement (SR) 3.4.9.1 (pressurizer water level). For consistency, Item 6 is being reordered into a Check-Test-Calibrate Surveillance Function sequence. Thus, the refueling calibration (currently Item 6.b) will switch places with Item 6.c. The monthly " Test" (currently Item 6.c) will be changed to " Check" and become Item 6.b.

l Following the change, Item 6.b will be similar to CE STS SR 3.3.11.1 (post l accident monitoring instrumentation) and the monthly CHANNEL CHECK will supplement the shiftly level verification.

14. Upgrade Table 3-3, Items 21 (PORV Operation and Acoustic Position Indication) and 23 (Safety Valve Acoustic Position Indication) from a

" Check" to a ' Test." A channel functional test is the most appropriate means of verifying PORV operation & acoustic position indication and I safety valve acoustic position indication. An oscillator and installed I

impactors are used to generate noise signals; thus, this surveillance is more accurately described as a channel functional test rather than a channel check.

15. Delete the requirement of Table 3-3, Items 21 (PORV Operation & Acoustic Position Indication), and 22 (PORV Block Valve Operation & Position Indication) to verify valve operability while powered from the emergency power supply. The PORVs and PORV Block Valves are powered from permanent Class 1E power supplies. Therefore, the requirement to verify operability of these valves while they are powered from the emergency power supply should be deleted as it provides no additional benefit. This revision is in accordance with the exception for plants with a permanent Class 1E power supply to these valves (CE STS, SR 3.4.11.4).

16. Delete the requirement of 75 2.2, Table 3-5, Item 15, to test spent fuel pool surveillance coupons f r a change in hardness. This requirement related to monitoring of Boratlex* neutron absorber was inadvertently left in OPPD's Application for Amendment dated December 7,1992, which proposed an increase in the FCS spent fuel pool storage capacity. The new high density storage racks contain Boral* as the neutron absorber. Boral* is a cermet composite material composed of type 1100 aluminum and boron compounds, which doec not embrittle significantly when exposed to radiation. Thus, the requirement to test the Boral* surveillance coupons I for hardness is unnecessary.

l i

i f

3 i

e I

BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATIONS:

The proposed Technical Specification (TS) changes do not involve significant hazards considerations because operation of Fort Calhoun Station (FCS) Unit No.

1 in accordance with these changes would not:

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated.

The changes to the Table of Contents are administrative in nature to reflect the removal of incore instrumentation (Specification 2.10.3) from the TS by Amendment 167 and for consistency. Amendment 169 inadvertently reinserted incore instrumentation back into the Table of Contents.

The change to Specification 2.1.7(1)b is necessary because the requirement to test the signal to alarm-meter relay located in Specification 3.1, Table 3-3, Item 6 is being deleted. The test, which verifies the high and low pressurizer level alarm settings and the pressurizer heater cutout function is unnecessary. 0;erating experience has shown that a shiftly pressurizer level verificaticn as proposed for Specification 3.1, Table 3-3, Item 6.a is sufficient to detect any level deviatior, and verify that operation is within safety analyses assumptions. The level alarms serve as early warning devices but do not provide an accident mitigation function. Replacing the monthly test with a channel check is in accordance with NUREG-1432, Combustion Engineering (CE), Standard Te hnical Specifications (STS), Surveillance Requirement (SR) 3.3.11.1 (post accident monitoring instrumentation). The monthly channel check supplements the shiftly level verification.

The Basis of Specification 3.1 is revised to clarify expectations regarding a channel check of channels that are normally off scale when the surveillance is required. In this situation, the channel check only verifies that they are off scale in the same direction. Off scale low current loop channels are verified to be reading at the bottom of the range and not failed downscale. These statements are taken from the Bases of CE STS SR 3.3.4.1 Engineered Safety Features Actuation System (ESFAS)

Instrumentation (Anal d .  ;

i In addition, the Basis of Specification 3.1 is revised to clarify that l power operated relief valve (PORV) actuation is not required during the j channel functional test of the PORV low temaerature setpoint (Table 3-3, i Item 18.a). PORV actuation is not required aecause it could depressurize the reactor coolant system. This clarification is modeled after a similar i statement from the Bases of SR 3.4.12.6 (Low Temperature Overpressure Protection (LTOP) System) of the CE STS. l Changing Specification 3.1, Tables 3-1, 3-2, 3-3, and 3-3A by using defined terms to enable the Surveillance Method to match the Surveillance Function is an administrative change esigned to simplify the tables.

iemoval of the extraneous text does not alter the surveillance because the defined terms are equivalent in meaning to the deleted text.

4 m

-~ l e l

)

BASIS FOR N0 SIGNIFICANT HAZARDS CONSIDERATIONS (Continued): l The reordering of several items in the tables into a Check-Test-Calibrate  !

sequence adds consistency to the tables. Text revisions in the Channel  ;

Description or Surveillance Function columns of Tables 3-1 and 3-2 add  !

clarity and/or consistency. Footnote No. 1 in Table 3-1 concerning the '

bistable trip tester was deleted because it is unnecessary.

The Surveillance Function of Table 3-1, Item 1.c (Power Range Safety Channels) is being changed to " Test" from " Calibrate and Test." It is not necessary for Item 1.c to require both because Item 1.b already requires the power range safety channel adjustment (calibration) to be performed l daily. As stated in the Basis of Specification 3.1, "The minimum 1 calibration frequencies of once-per-day for the power range safety I channels, . . . are considered adequate." To further clarify the issue,  :

the Basis of Specification 3.1 is being revised to note that the daily I calibration is a heat balance adjustment only.

Changing Table 3-1, Item 4 (Thermal Margin / Low Pressure (TM/LP)) to use the defined term CHANNEL CALIBRATION will allow OPPD to relax the current TM/LP calibration requirements with a negligible impact on safety. i Calibration of the temperature input and pressure input will still require l calibration to known standards (i.e., resistance and pressure), but will allow the calibrations to be done separately instead of coincidently. The channel functional test that follows the channel calibration verifies proper function of the TM/LP circuitry.

Removing the word " Instruments" from the Channel Description of Table 3-2, Item 14 makes the Channel Description consistent with the Surveillance Method. Table 3-2, Item 14 is not intended to verify safety injection I tank (SIT) instrumentation operability but rather that the parameters level and pressure are within limits. Generic Letter (GL) 93-05, Item 7.4, states that the operability of SIT instrumentation is not directly related to the capability of a SIT to perform its safety function. GL 93-05 concludes that the surveillance should only confirm that the parameters defining SIT operability are within their specified limits.

Items 22 & 24 are being added to Table 3-2 to clearly state the requirement for testing manual actuation of the Engineered Safety Features (ESF) channels for Off-sita Power Low Signal (0PLS) and Auxiliary Feedwater. Although testin t manual actuation of these channels is done 1 via the existing Specificatius, the requirement to do so is not clearly l stated. Reordering lable 3-2, Item 23 into a Check-Test-Calibrate l Surveillance Frequency aequence adds clarity and consistency. '

The addition of Footnote No. 7 to Table 3-2 clarifies that the refueling

, frequency ESF channel functional test pertains to the backup channels such as derived circuits and equipment that cannot be tested when the 31 ant is at power. Operating certain relays during power operation could cause plant transients or equipment damage.

s 5

BASIS FOR N0 SIGNIFICANT HAZARDS CONSIDERATIONS (Continued):

The revisions to Table 3-3, Item 6, clarify that pressurizer 1c,el is the parameter to be verified and not the pressurizer level instruments. The revision to Item 6.a is consistent with CE STS SR 3.4.9.1 (pressurizer water level). Reordering Item 6 into a Check-Test-Calibrate Surveillance Function sequence makes Item 6 consistent with the ordering of the other items in Table 3-3. The requirement to test the signal to alarm meter relay currently located in Specification 3.1, Table 3-3, Item 6.c is unnecessary. Operating experience has shown that a shiftly pressurizer level verification as proposed for Specification 3.1, Table 3-3, Item 6.a is sufficient to detect any level deviation and verify that operation is within safety analyses assumptions. Thus, the monthly " Test" requirement will be replaced with a " Check" to supplement the less formal but more frequent shiftly level verification of Item 6.a.

Table 3-3, Items 21 (PORV Operation & Acoustic Position Indication Channel) and 23 (Safety Valve Acoustic Position Indication Channel) should be revised to a channel functional test from a channel / circuit check. An oscillator and installed impactors are used to generate noise signals and therefore, this surveillance is more accurately described as a channel functional test rather than a channel check.

Table 3-3, Items 21 and 22 (PORV Block Valve Operation & Position Indication) should have the requirement to verify operation on the emergency power supply deleted. Permanent Class 1E power supplies the PORV and PORV Block Valve. Therefore, verification of PORV or PORV Block Valve operability while powered from the emergency power supply system provides no additional benefit. (Operability of the emergency supply system is tested in accordance with Specification 3.7.) power The l proposed revision is in accordance with the exception for plants with a permanent Class 1E power supply to these valves as stated in CE STS, SR 3.4.11.4.

Deletion of the requirement of TS 3.2, Table 3-5, Item 15, to test spent fuel pool surveillance coupons for a change in hardness corrects an oversight in the Application for Amendment dated December 7, 1992.

, As stated in the Safety Evaluation Report enclosed with Amendment 155, l "Each coupon, upon its removal from the mounting jacket, will be analyzed

! according to the following tests:

• visual observation and photography

• neutron attenuation

!

• dimensional measurements (length, width, and thickness)

• weight and specific gravity."

The tests listed above are sufficient to detect degradation of the Boral*

material and do not require that the surveillance coupons be tested for hardness.

6 4

1

~

~ e

'7 BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATIONS (Continued):

Based on the above discussion, the proposed changes clarify and standardize existing surveillance requirements, remove redundant requirements, correct minor oversights from previous amendment requests or are in accordance with CE STS. Thus, none of the requested changes involve a significant increase in the probability or consequences of an accident previously evaluated.

(2) Create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed revisions will not result in any physical alterations to the plant configuration, changes to setpoint values, or changes to the application of setpoints or limits. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

(3) Involve a significant reduction in a margin of safety.

The proposed changes clarify existing surveillance requirements, remove redundant requirements, correct minor oversights from previous amendment l requests or are in accordance with CE STS. Thus, none of the requested changes involves a significant reduction in a margin of safety.

Based on the above considerations, it is OPPD's position that this proposed amendment does not involve significant hazards considerations as defined by 10 l CFR 50.92. The proposed changes will not result in a condition that significantly alters the impact of the Station on the environment. Thus, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9), and pursuant to 10 CFR 51.22(b) no environmental assessment need be prepared.

7