ML20024F121

Proposed Tech Specs Re Reactor Trip Sys Instrumentation

ML20024F121
Person / Time
Site:	Byron
Issue date:	09/06/1983
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20024F115	List: ML20024F114 ML20024F121
References
NUDOCS 8309080245
Download: ML20024F121 (62)

Text

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i i 4 w j i 2 ] 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION .m- .. 4 LIMITING CONDITION FOR' OPERATION ^- 1 l -._, - ~, 3.3.1 As a minimuur, the Reactor Trip Systest instrumentation channels and Ji' [ fnterlocks of. Table 3.3-L shall. be OPERA 8LE with RESPONSE TIMES as. shown in .,ig Ai 1 .TabTe 3.3-Z.. .,.., ~. ~. . -~..-- -- -,c . s.:. ..a -x.s.; m

.? ' P 4:D3 APPLICA8ILITY:- As shower ier TabTe'3.3.1.

 ? w ACTION: T2' i.. ~ ' ~ ~~ ~ ~' As_shown _in._Tabl.e.3.3-1., SURVEILLANCE REOUIREMENTS 4.3.1.1 Each Reactor Trip Systest instrumentation channel and intericek and - ~~ the-automatic trip logic shall be demonstrated OPERA 8LE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1. 4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to< be within its ifait at least once.per 18 months. Each test shalf include at least one train such that both trains are tested at least once per 36' months and one channel per-function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific Reactor trip function as shown in t.he " Total No. of Channels" column of Table 3.3-L n p ( F NO 6 9 e BYRON - UNII' 1 3/4 3-1 B m

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I TABLE 3.3-1 (Continued) Eg REACTOR TRIP SYSTEM INSTRUNENTATION z MINIRIM. g TOTAL NO. CHANNELS CHANNELS APPLICABLE q FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 17. Safety injection input from ESF 2 1 2 1, 2 9 18. Reactor Coolant Pump //,y. f yg kgg7 kgg Breaker Position Trip 2. .ater: a-2 1 ch:r i 1/tr :hcr 1 l'J b. Above P-7 ?-! 5:!: ?-0 1/ breaker 2 1/ breaker 1 11# I per operating loop 19. Reactor Trip System Interlocks i w i ] E a. Intermediate Range l Neutron Flux, P-6 2 1 2 2,, d b. Low Power Reactor Trips Block, P-7 j i P-10 Input 4 2 3 1 8 l or P-13 Input 2 1 2 1 8 c. Power Range Neutron f Flux, P-8 4 2 3 1 8 r N A un

i. i TABLE 3.3-1 (Continued) c.<o g .REAC10R TRIP SYSTEM INSTRUMENTATION z MINIMUM g TOTAL NO. CilANNELS CHANNELS APPLICA8LE q FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERA 8LE N00ES AC110N ~ d. Power Range Neutron Flux, P-10 4 2 3 1, 2 8 2 e. Turbine Impulse Chamber Pressure, P-13 2 1 2 1 8 i f ) 20. P. ::ter ! rip Srech::: 2 1 2 1, 2 9-I 2 1 2 38, , 5* 10 irip:d'r.:.er'::tL:g!: 2 1 2 1, 2 9 ..ut^

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21. ^ 2 1 2 3*, 4*, 5* 10 CT M b rni 'fn'Frlock' j.gic o, 4 l -i I l

TABLE 3.3-1 (Continued) TABLE NOTATIONS 4 = L With the Reactor Trip System breakers in the closed position, the Control Rod Drive System capable of rod withdrawal. ?:ft51:ni;;ndin;""O;;;rre;'eftrceele. pope.etien.E) DEI 8 ,)( L The provisions of Specification 3.0.4 are not applicable.

1. 1. elow the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

B

1. 1. 1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

ACTION STATEMENTS ~ ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERA 8LE requirement, restore the inoperable channel to OPERABLE status within 48 hours or be in HOT STANDBY within the next 6 hours. ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: The inoperable channel is placed in the tripped condition a. within 1 hour; b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours for surveillance testing of other channels per Specification 4.3.1.1; and Either, THERMAL POWER is restricted to less than or equal c. to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours per Specification 4.2.4.2. BYRON - UNIT 1 3/4 3-7

4 TA8LE 3.3-1 (Continued) ACTION STATEMENTS (Continued) I, ACTION 3 - With the number of channels OPERA 8LE one less 'than the Minimum Channels OPERA 8LE requirement and with the THERMAL PCWER level: I a. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; and b. Above the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint but below 10% of RATED THERMAL POWER, i restore the inoperable channel to OPERA 8LE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER. ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes. ACTION 5 - With the number of OPERA 8LE channels one less than the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour and at least once per 12 hours - thereafter. s I ACTION 6 - With the number of OPERA.8LE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: a. The inoperable channel is placed in the tripped condition within 1 hour; and b. The Minimum Channels' OPERA 8LE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours for surveillance testing of other channels per Specification 4.3.1.1. ACTION 7 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour. l-ACTION 8 - With less than the Minimus Number of Channels OPERA 8LE, within 1 hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state c for the existing plant condition, or apply Specification 3.0.3. 8YRON - UNIT 1 3/4 3-8 --,-%-= =w. -r e-------------r-,- .,-w .-,----v-, - - - - -,-,,--nv ---w.s,--- ,,--e, ,r----s,---,y--- ---,-e

TABLE 3.3-1 (Continued) ACTION STATEMENTS (Continued) ACTION 9 - With the number of OPERA 8LE channels one less than the Minimum Channels OPERA 8LE requirement, be in at least HOT STAN08Y j within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1, j provided the other channel is OPERA 8LE. ACTION 10 - With the number of OPERA 8LE chanc.els one less than the Minimum Channels OPERA 8LE requirement, restore the inoperable channel to OPERA 8LE status within 48 hours or open the Reactor trip breakers within the next hour. ACTION 11 - With the number of OPERA 8LE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within I hour. t h l SYRON - UNIT 1 3/4 3-9

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==* u p N fM 4 40 f"* E @l P* Id. 9 BYRON - UNIT I. 3/4 3-10 O e. e

a '.h. 6 e ...i..ry g, - ,,...'J..s, ,{ ...s...,. y8a. 7.,,..,. ....n .,s.., . *....>.. ;.. t.4.- i..M . c '., -.. v 'e r '".* r .or ,2 .w.. g.. -.r. s.. *...*. 3 n... x. . z ~ )**....m. ya

n. s 2.

, ',g- ;, ..4,,,

. ;....~;,.,

n. ~%.. +', 1. , A... y.g. s,. . - * +..., 4s. v j. r., a = .g. .., i r sev p s..y . *.,s' W. ".-. ' ~. T ~ .- O .a.,,...'t-r,,..., a. < - n..,,,.4. .c. ...,y..... j .t.., -,. ? 4. > f. y. f,.. ' a-Y ^, '.i% rd.."* W T 4.T '.W ' O -- % ' ** ., 7 . m. '"*T.*** t. 'i L e .s j ,.y

.,,.. m

c

.,. G.d. -, y. '..a.We.,:: y.. +. w., ....M. ' ; i.. : a,&...,.., ..a; ...m. ......n +. ...y.. r t r

y. '.....',;.

. s z. ...:. c u m%.+.a k... w-,.......... -- - un ss- ..y ~. :.

• a

..W',v:.W%-jh'a,b.e* *,id 4. y..? ;t;r %' v.v '..~ ' V. .%. 6 '.,1,.,

,. A '. ~ ';c v

..f.,. f +. IsTigry't

P'.'.,$*.1

• 8

$p.~ag'.g**f,g%.t.Q. r.p] J,7;, C. J. * . ;...%*q _ %. gly;p*** p.

• e

r--J

... ' 5. 3.0.3.., b. f.< .u.c. ,r,f t ? ;.: y: c.. :. :.

t.

y..v.- ..% q,. g. x.... y c..c -. t- .*, s -..,, e ...p. .. s,. 4... .g ..,,.,.. e;.., .a...z. a ~,. + --.~e.,... e s.4,

n. s.);... **.

.o p. w..m>. .s, x y....ispt d.,, y. h on~med., e n,...s. 3 n.. .s. e 3 ..r. .,., w, ,,5 . e ..rr 94 . _ s;, esc s .en,

. ~.,L

.~ . g /.-,,w.g 6 4 9. ts W s #4 4 sa.c.W4 .r.e. m., p p. .f w j......e w e se..,,,,,.,, ~*. .- v > se. see ve... ,.6. v.. .r w'.. .ws,. e i., :..es.. e . a ,.-.s.. *

• e

, -p a h a {##.,,*.g .. 9 ,.*.,w 5.e., s y, 4./..., e ; ' 4.. '..c.. s ..a

e..

• . = +

.s+

...> i. to.,, e,,

,l v* ..,.,$.y,.,,,a,,. : y..g g.e. e e. ; =., ey Ann, .,2.*.., y g. gy,. gy g _... _... ~......,.. c4,. M g.Q ; .g p sgg y*b.g 4 p

• N.,. yv n,,.,. 4 m.. N e.,.9.. A.

.*.r,w x.gew a a 3, c... ~ n... . s.. .. n...,. ,~,.3_ ,.,..,...m ~..,. O Lg. O. 3,.

p... ~.c r..m,. v. eg.....~.......,... s....,

.. > = w,am. g.g..,; u, ...a ~ ,... - r. .. +.,

s.,......~ g

.. y.gn., ..g u.a. w.,..... n m,. . v:.v. w.cw .g ,.. e,.. ,. - ~ .,... a,.a..,

a.._

...c. .., _ ~... 4" ~7 tab 'A MM N

• = >.

. v..r.:. 2.:n. . <A w ..v3.. .v. E E. 3 E E E --E E a vivi V-- ._g,......,..m g/l W ^ m .g h. ..r..t.,... .y._. ~ iE. . ~. - s.. n. v..

• J 4

C >= 0 3 4 O ..s m - + .v.s .a. r,, o,,4 m.,, . l - - A. pr.< *.wo..rnsa 2..oe.-.t -s.

.u M* 4

. p b.,er,. gy g ..- ee..,. v. y u 4. -..s..... <.w.. A -e.- I a >= m. E M = w g l -a i.w p 4/5 spaw 8 s >=

1. =

M s W . b C S l e e ..,O g . a e. y p. 3 A ^ g e g .. p O O e G., ma iA h in f/L O. '4 Q ~ ' sC e..es e* Le af. >= W 6 C. 8. y- .ns w S SL - p C* S E S O V eg -p g g-b 5 .ag a== O i . g m & f%s. >- - 0 3 6 e 6 X e a e e3 is 0. e b 6 W qw w sk .L 4 ee .ed S C ed p-3D C.D - b-S> .O-be n=nr C 6 6> 0. 6 eA h= b

==

• • ee.

O O V l> E 9 C ' *==*.S e ** 4 e

==* e .at "J e < 3 W G

• • "" Q.

A 9 C w

• =s+

4 M CQ C Wt 6 S O b e e me 0 ea 6 C 'A S O. O. 48 O M >t-W 44 (J 4 e e u

=

es e = = =. O e C Q. 3e u Q. Q. b' -C Q

==

1. ==

b e b @t

=

>=' O '-a g 4 6 6=== ==9 O 6 b >= C U w >= U s-. enn 13 .ee 3 e .6

==

=

am y ge e 5 = -* ca o b e o2 b b d e >= l>, O O O ,,C e EA >= t- .a ed

• e ed a

5, 6 6 e g u o u y e e m e g e e 3 3 O s== a 4A EA 3 3 >- 4A W X E E 4 >= w e-o. eo e-> ,=* m a.* n=* er N N BYROM - UNIT 1. 3/4 3-11 s ame - ~ - - -,,,. - - - - -. - - - - - - -. - - - - - -... - - - -. -. -, -. - - - - - -

i REVIEW COVER SHEET S!N. 3.) PAGE NO. 3 k 3 % TOl6 SPECIFICATION NO. i SPECIFICATION TITLE AcTBR MP MM GMFA)TdhpN i l CONTAINED NUMERICAL PARAMETERS REFERENCE SOURCE OF ORIGIN i Me 4.3-l i e MODIFICATIONS APPLIED he., JUSTIFICATION L h l l t LEAD REVIEWER SUPPORT REVIEWER OSR DATE i i l

t ,t . 9 P...a.t.: 3 ' '..j, ; f,, +*

2. c j

2 -f. 1 h. .3 y 5 TABLE 4.3'1 J -4 i o 1 r t.

• • 1 i

e REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS *::(' 'r t , ' ' b. [- 3'.J: i.. p.., c 1 TRIP'. -K' ANALOG ACTUATING N :.?;i. h.Q<k.M00ES FO N l CHANNEL DEVICE, '. 1.ir';. WHICH. CHANNEL CHANNEL.' 'i OPERATIQHAL, OPERATipHALM.' ACTUATION 4 SURVCiLLANCE. l FUNCTIONAL UNIT. . CHECK CALIBRATIONi TEST TEST- . p LOGIC TEST' IS REQUIRED e.m>. l g, s } [j... ., N 'A.. 1, 2. 38 4",5"= 1. ManuallleactorTrip .?, N.'A., N.A.

[!

M A. .52

a

,t ..i94/g.a ,o ~ Neutron Flux 1 il. 'e *' ; }$ N R,. /'. !,.- ~. c 2. PowerRange,HighSetpolet'l1l.l.S M(3,4)<[' '.,. y N. iN. Aj d !Q:'. N A $! 1, i D(2,4) -M

i %i... l.,.f.t r.y...L. ;, 5 dP, 1.;

ar ,e 4 s i s , l. ; '- ,s.! Q(4. 6) ! 4' S 4 P.0l.'. .i ,i.$,pj. f* d 4 A 1 J 1g'gg ' 7 i iv R(4,5)i } J !N. { . Low Setpoint $. y: ~ 'R(4) H ~ n.,,, M, n, '. ., i. 7 - p2,~

n.. (

w r m .i

1. a., o.p.., ; ;a..

. H !! '..k,N,4,ti4 g., j, d 4 M. A..c 2.. M'.1.. Power Range Neutron Flux, N. A.. R(4) d %,r J.y+t. l ' w i H.igh Positive Rate l', .1., 3 $ et g,. 5. t..s.:.. i. Power Range. Neutron Flux, 1 N. A, t.. s,. .c s.,.,.,.. .,.,x-... p(4) i M '. EN. A; j', c { :.9,.; N.$, O 'li it. o...;.l. <. High Negatlye Rate . [ '. j p P.,., ; :.0 4 ,.( .y p .,... I i -. - .s ... ggg. S R(4,5),. S/U(1),M .j.Af,.'.?!.' N. A.'s. 1 . 2. 'l" ' : S. Intermediate Range, Neutron Flux ) l t- ) 6. . Source Range, Neutron Flux 5 R(4,5) 5/p(1),M(9)' h,N. Al 50 ^ I, N.A./

• 3", 3. 4; 5n...' J

~ 1., e ' l,s.E N.A', C,' N,A.1 >' 1, 2 7. Overtemperature AT 5 R M ,.Y.s y

• . i.

f, '.; 8. Overpower AT S R H . N. A,U '.i../.. N. A. :. 1, 2 ;.- . : vtv 9. Pressuriger Pressure--Low

S R

H ,:H.A, i,L, J;.5 N.A.,~ 3 ! '... " - .. >.,...' s.. 10. Pressurizer Pressure--High ~.S R H - ( N. A. % X. 'i... N, A,1.' 1, 2 E 1. .t ,t ? s 1.- n. h N.' A,'., -g.,. N.A.

11. Pressurizer Water Level--High 5

R M 4.k.. p A.O.1): R,i L.:., 12. Low Reactor Coolant flow ,S. L N. A.' 1 M i 4, fc: i .&. 1 5;' .~ ? i\\ N. hY

• A.'.t\\.

4, k ', i - * [f i.o m (p.J.?jd;.:{ $ &.#GQl wing o. h #.' i. l

..,3

• (h

l-s

,i [ TABLE 4.3-1 (Continued) S 3 a en

p, REACTOR TRIP SYSTEN INSTRUMENTATION SURVEILLANCE REQUIREENTS - ' s q.,

o y.:.s x TRIP

c ""'; r 1; s 1.jp.?,ri N00ES FDR ANALOG ACTUATIN(i

+ c. CHANNEL DEVICE .. a w r. ~ r' *, WHICH H CHANNEL CHANNEL OPERAT10NAL. OPERATIONAL.< ' ACTUATION SURVE!LLANCE-H FUNCTIONAL UNIT CHECK CAllBRATION TEST TEST t7 LOGIC TEST IS REQUIRED -. g,' N.A.- 1, 2 13. Steam Generatoi. Water Levei-- S R N '. I ~N.A.T!j'M L

• L8W s - 1

,.X,. ,qi { ..,,.Sc. ~ - a- ' n.J: J '1 M 3 ',0. ;. ;C:..N. A.'. - 1 .s

14. Undervoltage - Reactor Coolant N.A.

R I f. N.A. Pumps 4 . 6; N'p. 2 V M. f '.* 1.' C - 9'L - -!, f f.i c hd14[4j!!%hI ^[ l ' \\ fh*.N.A. ~ 5-i

15. Underfrequency - Reactor

~ N.A. R j Coolarit Pumps )- .,/.g. ep* .'(.y.z.;,...k.b:(fi;,+:w;;,;..-l(' [$ 1, 3 ),

16. Turbine Trip j.f

,j, Q R S/U(li 10)i N; A. Y' 1' a. Low Fluid Oil Pres'suret M. A.' R - N.A. .J 4 .!'T.5.g S/p(1,' 10)i..N.A. a 1 T , b. Turbine'Stop Valve. --t' N.Al. >- R ' N.A. U Closure + ! .',. W. c. '. s' 't r. t - r. v,, e j 17. Safety, Inject. ion input from ' N.A. N. A. ,1 4 N.A. ". 6,$ R, - c . N. A.' i s 1, 2 ^ ESF ~ W a. .1

.y a. -

,+ 6k' 8( f '& '. h.4 i 18. Reactor Coolant Pump Breaker 7-N.A; N.A. N. A. - C9;yR:[4. '.J N, A,.. 1 Position Trip . t 'f,0 -Q ] L ' 3 ' '. c. 2 i ? ,... t. p. ^ 1,

19. Reactor Trip System Interlocks'

~ ;.[, V.. ' ] ',.. ' '. C..~ .', : ~ a. Intermediate Range . c, i.e.1 P ~ ~- " y N A.E.' '?f H.A, - 2" i Neutron Flux, P-6 , M.A. R(4) N l b. Low Power Reactor 'n,T l Trips Block, P-7 .N.A. R(4), N (8) , M. A. ' : :. ~ N. A. 1 . si e. 1 1 j e . 4 ;' c. Power Range Neutron s ,1 Fluz, P-8 N.A. R(4) N (8)

7.. ' N. A.',1 e N. A.'

1.'.' ~ > 's. ._h.. j <i..' l} ' ,E, f.. < j .s. ' * [, ~_ \\t e { i'*$ lN ' (. 5.' I' s s, 4 ~ $h [](i' -( f [!)[ a 'f (Ni-'.,k ;,". Y'~ I 3 v., s.. l .w e ~ ' I ? $ .*s b.k. i$ h ki* ' ?* ? { 5 y$1.: i '#' s 'Y"

• l d.'--.

4

r--, a l y y .s + . g3 gy s .a .,o_ . -. ~: , y'-

s w

ci a . 1., c ey g-4 u. t. .,... d~. s w i a m J

== w w C3 J.," s.. s ~' ~ w Je @ .. en. _ rn 3 .:r - e = mzww '8w u > m c%e N N '. - ~. -, - '-/ - -+ s

• • CE

..*e, e.., f E.* ,e, e *,..** - Q@ a. M-

==e M N e-4 s .w Y . og,..*, ' d E. = p + ,,9 .t., A n,q.Ap. ,,, p.. = 4.,,,., vfy3'4;g'W,*;.}'./ ~' s .f. ,./f

• D p f*..~.

w.3,..

) . f, + *'w,d. '. ]. '

• D""

x' ..o.,e. m.. -. e.,,c, A. s...s g q!., t.% '.W. s. +1 =

• 's

- ' %."r m.*. vft:. m.e > ,.. J; : < s k.... ** n.

1. ~-

5 z. ,'s 6% f ^ L*! * '~' 'e'; -0.'y M ',*s- .\\. S?.- - k [,,:*4' e, W L ,."A..f** ' **. e' .f*

e _1,,hy

'z

z.... x... x

~

• - - ~

.. *- - >= t.3 - x a, '.. - n.'.,*~~..~~- = d 6" - e . 's. 2 ~ ~ ., *s & F

• T,'"
• t

1. e.**' 9p 9=esEA' '#' 4 b P.'

• p.

y. .... ~, - <. ~ - - ..y w.u O + - e.,,. W..... 9, s. ~..w 4. s..:n

s. ;'..,d, - *., ~.Q.' *~ Q,s. -. r v.4. - Q > -

Y. .-1 .9 b 7 w g,--<- ..~,.c....'

• e e

.- 4 a ;.. .e, o r#%ep +....." >, /). - <.. .t g., ~, r .. *....s.~c. gu. ..4.. ... t e, .o....z--o.. . ~:-..., ..-,,.v

• e.p* 9.'P..e.. d a

. '.. s

s. ! c *E.

t.' n.

• ~ W.?

,st.4

• g**~* M.' w.'N f M -. i

i t.4 - . = s, r*- 4 s t, ,-.*.~ s r.e (/>., _. f.3 ..%e -. -. * ' F*ier - a-..#...e:a,. 44,4.eey,s 4..d. <-.i.,.., m a;,,,v r w #c.,vs u.

c. -.n.

nr-E. ,E,, 4,. aC,,. %e <v. .1 o. + -. - >,.. ; w.), f f*, ./ oll. ly _, *., [g$ s

• )5 {.

1 - e &. % $, ~' E....,, 7 .[f"<$ ' .? ? - w . ee ' W U >= ' - Y, + 4.9- ..A.:, OL'd ,o . - y-w. I J- -. s,. A*,. 4. y.. > 7,. 4.P;. ~. ..4<- g,.. qu< i -(: 4

=== 6.2

• g >=

a. :l

.v .E j ->wM

• 4-
• ...gw,'*

e . p.e .. <r .,s

• s*

e -s g g g j%, 8 D ,,3 y .O W 4 Q Q p.. w s ry 4 v.- 5~.,i

.s ;.

r-C E g, b&d s 4 s t m w ggg aC, 4, - = = c w >= e.g e - a Z E >= E E E E <wm <Zcw 3 m Z C 2 ~ w M C U C >= 9 e C 2 .../... =, U. C v...., s s...u...~..,,_.v.. ...cq,, w. O >= ,r. =... +... ..s g

• ==d

>= t 4 c.e >= t Z >= m 4 ( W e.s& 4 T M. E w tz %e T 3 E G2 E E E E OC Z a= W >= 4J J M Z( G3 2 UU (

== > = E w .s >= w W. 4

• C.

aC..

• C.

M. 3m v M w E E E' E 3 a. uu .2 d,. vI

== E >= b K e C W -A u4 O M u w> W e m s 5 eM .as 15 = s.= M 85 C 3C 3 s e 80 Q..U 3 Q.Q= b w 3 ga ct w s-. = = 89 e O.

5. O WJ KC eb O

C3 1= >.e m b s. w w >= u.ad E Aw

• • • V 3

3 6e b +4 Q c 3 L. O f5 - J

a. 2 >= C.

+4 S6 U Q S

1. 5 ed ed e

3C "U e E aC * >= 6 C4 N BYRON - UNIT 1 3/4 3-14 o O D eo e m ,.,4.- r--

.l ,. l 7 u . - : - e.: ',-~ TABLE 4.3-1 (Continued) ~ < ~. ~ g ~ ' I.' TAELE NOTATIONS With the Reactor Trip System breakers clos'ed and the Control Roa ~ . J;,.. .Orive. System capable of rod withdrawal. 9- .., ~. -.~ eOCs ~ ., ~ - - .. =... ..u .v. '.Below P-6 (I'ntermediate Range Neutron F1'ux' Interlock)'Setpoint.'$$$ $ E l e i . 7N. .v., _5 r; ~"- -N# - Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint. p, ..i ' t * ' fJ I '." -,^. ~. (1)- 'If.not performed in previous 7 days.. ~ J m .. "...N.:e. :.c L. ; .u .J' . N,, :. ...(2L.... Comparison of' calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with o

i. -

.S% j calorimetric power if sbsolute difference is greater than 25. '?.2,$ T' The provisions of Specification 4.0.4 are rot applicable for entry ..~. + into MODE 2 or 1.

27. - -

-= ' Single point &aparison of incore to excore axial flux difference n (3) above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 3%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1. (4)*- Neutron detectors may be exc1'uded from CHANNEL CALIBRATION. ~ (5) Detector plateau curves shall be obtained, evaluated and compared ~ -. - -. - to manufacturer's, data. For the Intermediate Range and Power Range Neutron Flux channels the provisions of-Specification 4.0.4 are not _.__. applicable for entry ~ into MODE 2 or 1. ~ (6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. r) The provisions of-Specification 4.0.4.are not applicable for entry f 4. into MODE 2 or 1. e (, 7) Each train shall be, tested at least every 2 ys on a STAGGERED TEST 8 ASIS. l With power greater than or equal to the interlock Setpoint the required (8) operational test'shall consist of ver.ifying that the interlock is in i the required state by observing the permissive annunciator window. i Monthly surveillance in MODES 3*, 4* and 5* shall also include (9) i l verification that permissives P-6 and P-10 are in their required state for _ existing plant conditions by observation of the permissive annunciator window. Monthly surveillance shall include verification. of the Baron Dilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period. I (10) - Setpoint verification is not applicable. i l (11) - At least once per 18 months and following maintenance or adjustment I of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the Undervoltage and Shunt trips. 8YRON - UNIT 1 3/4 3-15 ( l 1

REVIEW COVER SHEET SPECIFICATION NO. 3 .34 PAGE NO. N 3-)h TO M SPEClF1 CATION TITLE E%F-As, IksT12uhE}JTATTON CONTAINED NUMERICAL PARAMETERS REFERENCE SOURCE OF ORIGIN Tdk 3.3-3 M MODIFICATIONS APPLIED b h dbput. 9-l\\ e:n MJ 'fe,lm dih" Gib /40 *(P-W V v s / JUSTIFICATION m, /t ee 1 LEAD REVIEWER SUPPORT REVIEWER OSR DATE i I

4 '

• INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION ~ '" e _3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation '...,. channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip ' .;+- -Setpoints set consistent with the values shown in the Trip Setpoint column of ' T, '. Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5. ,,y ,,,,,; g, APPLICABILITY: As shown in Table 3.3-3. ~.c:r ~. ,s 9-ACTION: , o - ~ y,,. 3.... -l, r ,. w.# -.;.. c,.

4.,..,.a...With an ESFAS$. Instrumentation or Interlock Trip Setpoint. trip less.

J. 6.~. i conservative than the value shown in the Trip Setpoint column of A g..S. ..; Table 3.3-4 adjust the Setpoint consistent with the Trip Setpoint value. 1W 2 - ~ - f p -b. . ith an ESFAS Instrumentation or Interlock Trip Setpoint less conserva-W ' ^ ' ' tive than the value shown in the Allowable Values column of Table 3.3-4, place the channel in the tripped condition within I hour, and within l < the following 12 hours either: i 1. Determine that Equation 2.2-1 was satisfied for the affected channel and adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-4, or ^ 2.' ' Declare the channel inoperable and apply the applicable ACTION l - statement requirements of Table 3.3.3 until the channel is - restored to OPERABLE status with its Setpoint adjusted consistent > " + - , : with the Trip Setpoint value. Equation 2.2-1 I + R + 5 i TA Where: Z = the value from Column Z of Table 3.3-4 for the affected 'l

channel, i

R ' = the "as measured" value (in percent span) of rack error l l ., $,c

for the affected channel, S'~ =. either the "as measured" value (in percent span) of the sensor error, or the value for column S (Sensor Error) of Table 3.3-4 for the affected channel, and TA = the value from column TA (Total Allowance) of Table 3.3-4 for the affected channel.

- ~ SURVEILLANCE REQt'IREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERA 8LE by the performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2. 4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tes,ted at least once~ per N times 18 months where N is' the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3. BYRON - UNIT 1 3/4 3-16 e.

i l TA8tE 3.3-3. R ~ ~ (t m - ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION ,1...:.,. ' y .?. i a c T NININUM .1 ' . ;?. s h OF CHANNELS 10.TalP OPERABLE MODES 7, ACTION TOTAL NO. CHANNELS CHANNELS ' . APPL.ICA8LE M N FUNCTIONAL UNIT e i 1. Safety Injection (Reactor .T,, '?> Trip, feedwater Isolation, ,,,'.,.y. Control Roce Isolation, Start ... : '1,. 1 A Diesel Generators, Containment ' M. 'i. I 4 1- 'iP. Cooling Fans and Essential '.. $.. s1 )' i Service Water) - '.g . ~7ly2,3,4'r'.f18' , a. Manual Initiation 2 1 2 -. +. g.e. i b. Automatic-Actuation '2 1 2 - :,.yJ.J-2,3,4 14 s ~ l g . Logic and Actuation

• i.^ ;;-

Relays .+V: s a ' ' s w e '- c. Containment 3 2 2 AT 1,! 2, a 15* -a s Pressure-High-1 29 s. .,s. y , 198 i d. ' Pressurizer 4 2 3 1,': 2, 3 Pressure - Low 'W Yu e. ~ Steam Line Pressure-3/sta. gen. 2/sta. gen. 3/sta. gen. ~ f.1, 2, 3 15* any steam l ; i Low (above P-11) lip } t y n t i u .t ., e ~,_'.'y-'

• 7 l

,7 ' ) :4 7 {. s - , :w.+ ', ; i... > i . s ; y f.. -.e,. u

si f. ( > 3'.

. [- ..'N. A l v f ' ',.f.' '. ' a . I; '.g@3 ) i! j ' 7[' ' j e .n 'i 1 m & l.i; G O Q :s . i A Q.'1 :s ; _' f ~ f '..' 3"

e' r# e .( \\ /- M r. / .;s. >. n s.

e..

..,....,t.. .a 2,,, ' ( \\. l:

'j

O.1

'T I /.'. TABLE 3.3-3 (Continued) 9 1 t

. 3-r.

i e K ~ $,' ',i '. gg ENGlHEERED SAFETY: FEATURES ACTUATION SYSTEM INSTRUNENTATION.' ~

- 'h z

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4 'n ! E.w.., M..;.r.. J ' D.*,.,:j TA8LE 3.3-3 (Continued) 4< + %.C. +w - +,. .. + v,,.. g : TABLE NOTATIONS. s-c. . -. c..,., #. .. ".i o. y-t : ...^ ~ M .., a.. ;.. o,.;. e,.y s. c. ~. 4.., n ,1. 1 ....w ~ '9%y. Trip function may be blocxed frr this, MODE below the P-11 (Pressurizer ', 0, *.y

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..~ .,...:>..;... p -n ,.. y,ip function autosetically blocked above P-11 and may be blocked below ' ' '? Tr r-r .o...#.e P*1t wherr Safety Infectiorr' ort low steam pressure is not blocked; ~ . ~.7 .. l':,,1..:;., N,yy py@; . _. i. ',;,. ,.y.,,,. m... e .z..n x -v e., ee. t )( ".7,MThe.provisicas. of 5;ecification13.0.4 are not. appi fcable ! ~ , : ::U....~ Y,,.,. - ~ y., ~;,:.. 1:v.:. w ~ .s u s.u..<.. - e ACTI0t* STATEMENTS ... ~ ACTION 14 - Wittr the number of' 0PERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANCBY ... within 6$ hours and.in COLD SHUT 00WN within the following 30 hours; however, one channel may.be bypassed for up to 2 hour for m . surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE. ,...n ..r-+~. ' ~~~~~ ACTIOW 15'- With the number of OPERABLE channels one less than the Total I Number of Channels, operation may proceed until performance of the next required operationat test provided the inoperable channel is placed in the tripped condition within 1 hour. ACTION 1E - With the number' of OPERABLE char nels c'ne less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One acditional ~ channel may be bypassed for up to 2. hours for surveillance testing per Specification.4.3.2.1. ACTION 17 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply 1 and exhaust valves are maintained closed. g e 8F k .s 1 l l BYRON - UNIT I. 3/4 3-25 1

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.f. 2 O.;~'...w. ACTI0ft 18:- With the number of OPERABLE channels one Tess than the ' Minimum 3.l.E Z. A.'? i.c; Channels OPERABLE' requirement, restore the inoperable channel o U.d 7- %.9..MW W O ts OPERA 8LE status. within 48 hours or be in at. least HOT STANDBY .id ' ', ' 'f.27.. i,2.within. the next G hours and i~n COLD SHUT 00WM within the following - 'i . ? '..'. ;. $ 3.~~.3p.j:kyl.;.llq3G:- hourspL. m>..;.a y.. V. '-,.,..s b i: l' Q w-m. ~-~c . ~ - ,.......1., s, - -. ii ~,;.. s ,a e s ~n -. ., ~. ~.. ,r irc. a y. ~

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.,'-.: 9. 'ab.'.aiWWy.'With the number of OPERABLE channels one less than Number of. Channels,. STARTUP and/or POWER OPERATION may proceed: ' ~1 ~ .", ' "' '* T;,'"..- ..,~, : .w -,..v ~* pro,vided,' the. f. o. iT.owi.ng conditions are satisff ed: - . -~ x , r ; e.. ai v. T' W "" 7' ' " ' W-~'E ~. ....f W.cE.5 -hu$.WNi ' hen inoperable channel is placed.in the tripped condition "M , 9.&c. ".w,7$, aq T wp .N 3. 9,. g ~., + Wy;w.6...<-M...:w.: wi.thi.n 1. hour,, and - ef w... -. <...q,. c... tr p The Minimum Channels OPERABLE requirement is met; however, M -..,e,..i the inoperable channel may be bypassed for up to 2 hours c..

- A for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 20 - With less than the Minimum Number of Channels OPERABLE, within [ 1 hour determine by observation of the associated permissive

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~ c - 3.0.3. . - he - ~ c l ACTION 21 - With the number of OPERAB'LE Channels one less than the Minimum - Channels OPERABLE requirement, be in at least HOT STAN08Y within 6 hours and in at least HOT SHUTDOWN.within the following T.T S' hours; however, one channel may be bypassed for up ta 2 hours ... f. <. for surveillance testing per Specification 4.3.2.1 provided the w "/-other channel is OPERABLE. l ACTION 22 - W.ith the number of OPERABLE channels one less than the Total

d. Number of Channels, restore the inoperable channel to OPERABLE M status within 48 hours or be in at least HOT STANOBY within.

+. ', ' G. hours and in at least HOT SHUTDOWM within the following 6 hours.-

ACTION 27 - With the number of'0PERABLE channels on'e less than the Total Nuncer of Channels, restore the inoperable channel to OPERABLE status within 48 hours or declare the associated valve inoperable l ~ and take. the ACTION required by Specification 3.7.1.5. i ~t. I BYRON - UNIT L 3/4 3-26

REVIEW COVER SHEET SPECIFICATION NO. . 9. 2 PAGE NO. 3, k 3~ 1 7 'Py M SPECIFICATION TITLE dh4S MOTdDM CONTAINED NUMERICAL PARAMETERS REFERENCE SOURCE OF ORIGIN d9 3 3"A M - I U / sw 3-3/, 34 MODIFICATIONS APPLIED @ CMhd8 3.6051mYA b5 OMA M L 3'17 d ) V 1 O i V (Sh CYnoe \\]70 >ocrs Th WRO & M 3' 2*7 1 b~ (b Cv2 hI o I (%60 4, m o y a , a u-l JUSTIFICATION l l i LEAD REVIEWER SUPPORT REVIEWER OSR DATE i i

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sm mmp,,e,y pt... m....-. .c . e r-+ w e-+ w ,.n, w,.m. e.Feedwater-Isolation. * **m:v. *: -*:, s : e 7 w --* w....,,,u g ..,hW, /&.?,c:.;y, Costatnment Isolat on-hase "A*O 5%pSUdc 12.(2)/27IU . W TWM,e",.; , ~..... .u..., i P u ', &s ' 2 in, ' mu . r;w:n y.m ~., gg3 y. .t. ~ . /10(.g3 'v.~..e,v~. .,n M ; ?-%3%. v ex ..,.P.;.a s..... < 25. ...,.A..' Co.ntai.nm, e.nt Ven.t. Isol. ation,.. s ~ o.,M s . e. -- Auxilf ar.y~F.eedwater. v., Mm.. '.4-P. < 60 -. ~......,.,.. , %.w.... ~. u - -4 47 g /32g. .4 5.. r."- fa. Essential-Service' Wet 4r-

u.. ' ' w IU/40(2) i 55 g..

Coittainment. Cooling Fans j, h., Control.Roosr IsoTation ..m.,'...,..: -.w +' ' N. A.. L Start. Diesel Generator % v'~ s 1 11 .... s" ; r.a. ~, ' ' 4. Steam Line Pressure-tow w.,s n g etated.sida d..taar,6i.e.W ..p

• 4J.

..= % e % + - 4.,s.

,4 Safety Infection.(ECCS). v...-.,,;...r~y..

.d 22(4}/12.(5) -

. - -, ' v+. u - l a. _2 1) Reactor Trip

1. ~~

I3) 27 Feedwater Isolation i7 17(2)/27(U c l ' 3)'. Containment Isolation-Phase "A" < 25I1)/10(2) t

4). Containment Vent Isolation l

5). - Auxiliary Feedwater .;j,+t-. >7.< 60 .y 6). Essential Service Water ...,~.,. u _. 47 1)/32.2)- v. 7) Containes.st Cool'ing Fans.' '[ < 55(1)/40(2) 8)' Control Room Isola.Non. ~- N. A.. ~ .< 11 / 9). Start Ofesel Generator a _5 _ 1. b. Steas Line Isolation N ~ . 01.;' ., ~ l SYRON - UNIT 1 3/4 3-36 U

i ...s.. .s . w. n.. ,..,. 7. m. ,.. f..,,,.9.. (.y .a p, 3,.-.. 1,:. e,.. t... n J., c..,,..,w. v,...:...>.,..m.... ..n - :. e. a., ..>.,.:..e. s...... .4 ,e. -... e, ~ c.,. ,. '..M ;., &,.

e.,.G';M.9Q &....I,#. J' W' ~ M'. n ;%*M',./.:q;,)

t..s.. .s 'i . n j:5p; p '.%,:n.4'.W i>:Y.. .s... ...~:.

<u

. a.c....~,. :

n.,..... c.,s p;. -..,.

.,~.n.. .:m. ~ :: s. a. ;.,,....;~,..,p... . x.. ?,. ~v, n i .v -... m..... t i. m,,. v.,.,;'..... ^ - T TA8LE 7.3-5 (Continued) . ; ~.a m-

• '.w.+ e d,:

u, ...,a . 4 :' ',' 1 .t.:.,..,., . vr ..C. s;:g 4 o,.w yo ,...s,,.;.4w. : o :#. 3,... ;...... . -//$.MU,3....;. O y/ 6.g.. ENGINEERED SAFETY FEATURES RESPONSE TIMES ..y - p ,., f',Jw

u..

-. e, e,.- o..a. '. y%, .,..n l-~5 s. ;. ~., c..,. , v....,. e.,.m. w,.,, s...... - :,... l..ai.C-.Q.:.. y6 RESPONSE TIME IN SECON05..; s. ..e,.i ~ n ,.,,.n;;,ff INITIATING. SIGNAL AND FUNCTION, P Z ;. .<,w s..: m M ; c,'.:. %q.r P m..;... ent Pressure--Hf ch-3..s.as y,.;;n,*. y :p%yllnf.y... .) a.,..s. . :,-.;;. a no.....,,qw.y;gg .,..., e.3.g.xContaine. x .a. .,'.:yl m.: e ' 7.y i .\\ n ,. %. 5 3 y +

• * ' * -- 4 in r..e.*,.:t. c. ~.,ontainment. Spray *. n'-:.'9. *An@m, 4 % w # t

'7.,^~'.*..M..t.W'". ..sc.:.w. e n r<ss,. .i,, ..,2... e - ar C m,. a...... c.4.-.--.. .N. +-..,%...W.. s' N.. e' 57 m w.. : ' J/. X $ 'C d. N~ :/7/ 2J.~.-.my,c.. m a ... w.... s...,:a. c,.. a..a ..~.,,:..... /.. a, v a.

c.,..

., g.7,774 . 2.!Ji,. gvu.. %./ '" CLatainment Is.o.l.a.t on,,h.as..e,:v.S*-u.q. nn. r~ o :. .6 - y -~ y n.v o..:n%,

13 i

P ,,.;....a.: ;. ;. + ., ~.. r; , m,,... w. s -e ,hw...% ar i.i.- ;r.<.~., ..v., w ..-m.'..., w. ,4f. ...~ %,...tg n w ~:....,.. u...,.-i. .., y m..g,g: .n ; ;.. a. ~..>,.. 9. w a,;q-p f.'.R,qrgA, -{ % p.;y;p, . s;cFr.dSh Steas Generator Water Level-Hfon-Hich ... n. .y ;r t..&w

,.,.iu m.

n-.n...; m. .. s u.,.. - m r ?..,4.:?U " P - f.o.&. 2., h? ", * *...~~ " :c.'Z' 5 * '.-:q..;

s::.. Turbine TH p.-

.,~........- -# 1 7(3) .a.,.,,, s ....,,. b. 4 Fee &sater Isolation: < m .,s. .w i '~# 7'. Steam Generator Water level - Low-low .. A, I . Motor-driven Auxiliary l a. < 60 . Feedwater Pump l, ~. b. Ofesel-driven Aux 1Tia.r.y. a.. l .c

.r,.

.... 60, v.- Fee.,,dwater Pumps,... 3. 3.., , m. .,.. n e,-, .,m; 8. Containment Pressure--High-2 i . _.17 Staan Line Isolation' ... a 1 _.. ^ L RWST Level-Low-Low Coincident with Safety Injection s Automatic Openin9 of Contafnment 2g2)/26M ~ T Sump Suction Isolation Valves

10. Undervoltaae RCP Bus,

~ ' ~ ~ a. Motor-Oriven Auxfif ary Feedwater Pump l b. Of esel-0 riven Auxiliary Feedwater Pump i 11 [' .u 11'. Ofvf sion [ESF Bus Undervoltage ~ Motor-Oriven Auxiliary Feedwater Pump < 60 ~ et.# ~ v --. ._. y.: ,. m r ,.,4, :.2 &.. n. . s. 2 . y... l

• L s
• ,.e.

E,,gA%3 SYRON - UNIT 1. 3/4 3-37 ? . _. -.._ n.,

.s-s w r., 'I. ... _ y.. s.. y - .e ' ue r r ,e 6..n.. g.. y. ..r.. s.'..., 8 h. '*.a."...'. - #.. J'. c. a e. t. s . fr. ' V, ' '. ' ' s. ;L s *. e-.#.

• s

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• a

+ b. l s,. s

e.. n. --..

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.;'..h, ' ' ;

.y' ..x s s..,g , v... a.. e ,...n .n ? ..~ .....v.'.;..+...,.vTA8tE'1.5-5 (Continued) 4 ' ;. m %v.4;...w - *'.w! *. *. ' > -..,. :. ~ ~ a.. .e.

• ;. c.n, e. o-s,.p e. ' w. 1. -...w.. v.

.. h. en. M - a' .s

2.. ?; g 4 3. *

• e

.r. 9 =. ' 1[. N m i & ,sh '.,:;;.

• m. : % '. - eJ_ c.lu.a. =. '

r'.'n , d ; dy'..Q.. } '4 ENGINEERED SAFETY FEATURES RESPONSE TI .;..,~ . 1 >. y 5.. d.-Nif [.M J.4G v L. ' .v ~... ..,an,.y, w . c... m.p. n. v..... ~. ....,.,.+....

e..

,:.,.9. <. ..J'IRTIATING SIGNAL AND FUNCTT0ft. - p.... m... . :,,,n ~.. ~ N-hi.~1 M. a. RESPONSE TIME IN SECONOSr-r ~.. a ..r ..a: & a rv w v.a.m ...,., : i.J.u d.4 , CT';i2d Losi of PoweEi *I.kk.N.4.m).h. 7.'.%.n,y)["h. ~. +,$.n%.! n..$ .'l f 9 .,.. -.+. . m., u ., a n u w ....- n.,.. ".c. v. -..r ~,.... ~..<....,n:,, u u ..,, m.... .v. n a..,-c s. a: a.,.'.. ' ESF. Bus Undervoltage. ' i.n:o*e. 's.M..*u.p'Ao.n'N M.c 15'*.7 '. - L ' ". '.. ":.W.*J.t"'f ~ W'

r. t s,r.< e.. s&

....t. r .,. >.... ?It. ~. i.. e. ... a .,.. n s.~ .; a......m .~.w ,..... b.. Gri.d.. Degraded' Voltagen..,~,.....,a ,v... ~.. c., c.-.. 1G.... t .s ..,.... ~.....s.. .~ ....<. a. n. ..s.... > n,...o.w e.m..m:w.w. w . m ,. r:

o,.y

.ev. m. ..,.y c,.o. .. s v s.>, m .e. u. m.-.w.,... m....,m.,,.,.e.. ~.,,. .1, . " i..+7 ^..' m-w. .~,,.o.,,..n., ..,u.,.,. m.7.,.. ' '.M. <.>,.'r.. '"$'..,M.,.. : !.T-..cJ., /. - L T. . - a n.. .e.,. w. I13;;- Necative 5toas Lfne Pressure.. c..r c .w ~v .c...,,.-.. ate-H gtp - at.. .,. ec.a, 4.,

w.,v...x.

.. v. - ,.m. 4M. v.f. 9 a..,e. g - ~. y.

3.' -

o r ~ .n . _ x.. w. . ~.,.:. .+..,. a...., ; -,., :.. w a........, m..., : ..a. ..a

Staas. Line Isolatto.m.,

.e 7- .. ~.. ~ . s. . ~,. ,. m..., v.,,. . (. ~.. ..y.,n .. y. m n. r... .. g. m......>.~......v

14. Containment Isolation-Phase. " A' '

< 5-. t Containment Vent Isolation a [ .~ r l

15. Auxiliary Feedwater Pump suction

. +. -. -. e '<-*... u -.. - ~.. - - -

---

-~~"-

Pressure-Low ..n.. .;4 e., e......-,.....- ....v.. .~ Auto, Suction Switchover to ESW - ft. A - l A, ,-s s o.., s p.. e ,-'a) a *:5 + ....sr .s. su., ...ci+.v' s I, g +e. t

u. v s.

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r l A. .s . * * *.a '*' f .v e 4 ) r i e a e, w. , j v= h.*r. -,- . f. 7..t-- ~ ;.% s e S. . t s s. ~ [., 1

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s. '

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• M'N1,..

1 c.'N.W.;m-g,.. .a. ,. p.,- -m :.i.r TABLE 3.3-9 (Continuedl - ' E;* . f c.. r m ;>,. O - m .. ;,g% n,w'h ; y, ~ ;um. k a:-< ;'. -, s .p g .e b , p-y, L.- y;yQ w.-V.4W.r.'%t'M TABLE NOTATIONS H 'S,'<- ,,.AA V wyi.tg . ',( <N,<.. m

s. :.-w. '. d

- - - i = s.1., c L c. - + -*. .*.-l

r. m.

o. % *,. g%g $. .x s..w - sG y..len ' 3 p',.* to P m,r.1;. y 7 . r ef r i,, f D c.,- s~

, y :, :y y..g. u ":,

..t... '.O v u~..' r ~ . ^O .. :.., e. m-m(U..Diesei gene.rator st,arting. and sequen. ce., loading delays included.. .s... w n.s ' p<.,s..=' 9 A ; ....z..c.s ....., a.. ..p. . ~. ..,J-<= 5. '. 7-1.:. w" 'n. =. r V~ w :

• w'-

.ox ..a > >..O,,:y.'.%("2h. Diesel generator starting' and sequence loading delay not included. .- P..m .0 w '. . I,. y'.: 7.f,:.i,.h.a.y.. ,.e,. ~y.,. 7,e' W,.Q.s..f s,i.te po, wer..availa. b,le.,<,., 3 f .,.g.......f ;l3, c...m..,3 .e,c,..,..,.4.- . ~. ~.. e,,. ,.,e.. 1 .: y u. ,..../,.., t pg e t. 9...+,. -, e e.-. fy

• s...ua,.,v o

. c,. r '.... 2..,. -. - e.,. <.. .... ~ e e . ap *.. 2 f. .n ...m a ,.%. u - ^ i ..e. u.W % (3V,..AW.me. rated...vaiv.es...,,.A *x-N -r. A.."...oc. .. ~. M A.,.%...

• a op

...n.....,...i . +- -J.. A... ' ; .... ~..,,.,..v. v..... .. :.. w <. s.v v.... ~ , c 2. $ -f.

• ~ +... -.,:.,~.r,.f. s. w \\.

.../...,, / e. a - g

c. 7.1. 3 y,w..,(.4%.;0f esel, generator. s'tartJng, and, sequenca 1 goading, delay included. RHR.

.y,-*t-g d s.-

4. d s *

"..A .,,,,,, Q w. '.- ~.. - - - .-s %.m.*

W w.s pumps not include &

A..q. A. %. n,z,...~.~.w... s,s-.., .m.3 w m...,....- ~ s.. -"w.

• wn f.'

. @,.. ;m.s...w ?s We.. .y ~s 3~'-.. ~ i'.9 ww .;f f.w,.,y(5)A;OfeseT' generator starting and' sequence loading delays not included ,L.h ',~SN3. t; - Offsite power available.~ RHR pumps-not included. ..r.. O.m ~ .w,%) .s.. ... f. 2. ., w.,. ..c.. (Si..... Se. qu..en. ce, de. lay.....s not. included. s. s., s. <.t ~. '

• m,e. s

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• e

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• M.i.;$ 3.
• 4
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f' REVIEW COVER SHEET SPECIFICATION NO. 3 ll.3. Q. PAGE NO. 4 3-#oTo45 SPECIFICATION TITLE [$f$$ D NUMdMN CONTAINED NUMERICAL PARAMETERS REFERENCE SOURCE OF ORIGIN %h 4.3-9 MODIFICATIONS APPLIED h JQ@ 3 ' 4/ q] M Scut 3 -+3, M3 ' L&;J ht - <>J c L nd A r, LLJ,J i JUSTIFICATION M A14eA 3-4.7 M a v v r ~- gf g LEAD REVIEWER SUPPORT REVIEWER OSR DATE _ _

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REVIEW COVER SHEET SPECIFICATION NO. 3. 3.3.6 PAGE NO. 3 3-8dS%@ SPECIFICATION TITLE M&f"E~ SDN Q STQlittEDTA m u CONTAINED NUMERICAL PARAMETERS REFERENCE SOURCE OF ORIGIN ~Tode s.s-9 h 43-6 M MODIFICATIONS APPLIED

Mone, JUSTIFICATION LEAD REVIEVER SUPPORT REVIEWER OSR DATE

. ~..

m l INSTRUMENTATION REMOTE SHUT 00WN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room. APPLICA8ILITY: MODES 1, 2, and 3. ACTION: With the number of OPERA 8LE remote shutdown monitoring channels less a. than required by Table 3.3-9, restore the in1perable channel (s) to OPERA 8LE status within 7 days, or be in HOT SHUTOOWN within the next 12 hours, b. The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.5 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECK and CHANNEL CALI8 RATION operations at the frequencies shown in Table 4.3-6. BYROM - UNIT 1 3/4 3-58 1

TABLE 3.3-9 0 REMOTE SHUT 00WN MONITORING INSTRtMENTATION gz MINIMUM READOUT TOTAL NO. CHANNELS g LOCATION OF CHMaeELS OPERA 8tE q INSTRUMENT 1. Intermodlate Range Nuclear Lowel IPLO6J 2 1 2. Sourca Range Nuclear Count Rate IPLO6J 2 1 3. Reactor Coelant Temperature - IPLO5J 2 1 Wide Range 4. Pressurizer Pressure IPLO6J 2 1 5. Pressurizer Level IPLO6J 2 1 6. Steam Generator Pressure IPLO4J/IPLD5J 2/ste gen 1/sta gen l't04J 2/sta gen 1/sta gen y 7. Steam Generator Level 8. aHR Flow Rate LOCAL 2 1 LOCAL 2 'l 9. RHR Temperature ~ 10. Auxiliary feedpater flow Rate IPLO4J/IPLO5J 2 1

TABLE 4.3-6 g RDIDTE SHUTDOWN MONITORING INSTRUMENTATION 2 SURVEILLANCE REQUIREsENTS e E CHANNEL CHANNEL y INSTsR8 TENT CHECK CALIBRATION ~ 1. Intermediate Range lluclear Level N N.A. 2. Source Range Nuclear Count Rate M N.A. 3. Reacter Coelaat Temperatase.- Wide Range M R 4. Pressurizar Pressure M R 5. Pressurizer Level M R } 6. Steam Generater Pressure M R M 7. Steam Generator Level M R Yg 8. 8948 Flow Rate M R 9. RNR Temperature M R 10. Auxiliary Feeduater Flow Bata M R ) l l A

REVIEW COVER SHEET SPECIFICATION NO. 6 . 6.3. b PAGE NO. M 3-6/TO M SPECIFICATION TITLE cf6 NodfTZ)MCr "M(A Mod CONTAINED NUMERICAL PARAMETERS REFERENCE SOURCE OF ORIGIN ~L 3.3-10 To ola 43-7 N MODIFICATIONS APPLIED ODM JUSTIF; CATION LEAD REVIEVER SUPPORT REVIEWER OSR DATE

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION _ LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERA 8LE. APPLICA8ILITY: MODES 1, 2, and 3. ACTION: With the number of OPERA 8LE accident monitoring instrumentation a. channels less than the Required Number of Channels shown in Table 3.3-10, restore the inoperable channel (s) to OPERA 8LE status within 7 days,'or be in at least HOT SHUT 00WN within the next 12 hours. With the number of OPERA 8LE accident monitoring instrumentation b. channels less than the MINIMUM CHANNELS OPERABLE requirements of Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 48 hours or be in at least HOT SHUT 00WN within the next 12 hours. The provisions of Specification 3.0.4 are not applicable. c. SURVEILLANCE REQUIREMENTS Each accident monitoring instrumentation channel shall ba demonstrated 4.3.3.6 OPERA 8LE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7. 1 .A y f? BYRON - UNIT 1 3/4 3-61

O IABLE 3.3-10 E ACCIDENT NONITORING INSTRUMENTATION 8 TOTAL MINIMUM 7 NO. OF CHANNELS c CHANNELS OPERABLE z INSTRUMENT 2 1 [ 1. Containment Pressure 2 1 2. Reactor Coolant Outlet Temperature - TH0T (Wide Range) 2 1 3. Reactor Coolant inlet Temperature - TCOLD (Wde Range) 2 1 4. Reactor Coolant Pressure - Wide Range 2 1 5. Pressurizer Water Level 2/ steam generator 1/ steam generator 6. Steam Line Pressure 7. Steam Generator Water Level - Narrow Range 1/ steam generator 1/ steam generator ' 1/ steam generator 1/ steam generator 8. Steam Generator Water Level - Wide Range 2 1 5 9. Refueling Water Storage Tank Water Level 2/ steam generator 1/ steam generator { 10. Auxiliary Feedwater Flow Rate ~ l 1 11. Reactor Coolant System Subcooling Margin Monitor 1/ Valve 1/ Valve 12. PORV Position Indicator (0 pen / Closed) 1/ Valve 1/ Valve 13. PORV Block Valve Position Indicator (0 pen / Closed) 1/ Valve 1/ Valve 14. Safety Valve Position Indicator (0 pen / Closed) 2 1 15. Containment Floor Drain Sump Water Level 2 1 16. Containment Water Level 4/ core quadrant 2/ core quadrant 17. In Core Thermocouple 4 i l

TABLE 3.3-10 (Continued) E ACCIDENT MONITORING INSTRuNENTATION g TOTAL MININUM gi NO. OF CHANNELS q CHANNELS OPERABLE INSTRUMENT g 2 1 18. Containment High Range Area Radiation 2 1 19. Containment itydrogen Concentration 4 2 20. Neutron Flux (Power Range) 21. Auxiliary Building Vent Stack - Wide Range Noble Gas 1/ stack 1/ stack 1/sta line 1/sta line 22. Main Steam Line Radiation C

TABLE 4.3-7 5 h ACCIDENT MDNITORING INSTRUNENTATION SURVEILLANCE REQUIREMENTS CMANNEL CMANNEL CHECK CALIBRATION INSTRUMENT M R ~ 1. Containment Pressure IWId* "*"9') 2. Reactor Coolant Outlet Temperature - THOT M R i. 3. Reactor Coolant Inlet Temperature - TCOLD (Wide hnge) M R f 4. Reactor Coolant Pressure - Wide Range M R 5. Pressurizer Water Level M R 6. Steam Line Pressure M R 7. Steam Generator h ter Level - Narrow Range M R m 8. Steam Generator h ter Level - Wide Range f M R 9. Refueling Water Storage Tank h ter Level "a M R 10. Auxiliary Feeesater Flow Rate M R 11. Reactor Coolant System Subcooling Margin Monitor M R 12. PORV Position Indicator (0 pen / Closed), M R 13. PORV 81ock Valve Position Indicator (0 pen / Closed) M R 14. Safety Valve Position Indicator (Open/ Closed) M R 15. Containment Flow Drain Sump Water Level (Narrow Range) M R

16. Containment h ter Level (Wide Range)

M R 17. In Core Thermocouples j l t

IABLE 4.3-7 (Continued) g ACCIENT MONITORING INSTRUMENTAT10N SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION i q j 18. Containment High Range Area Radiation y g ~ i 19. Containment Hydrogen Concentration M g 20. Neutron Flux (Power Range) g g 21. Auxiliary Building Vent Stack - Wide Range Noble Gas M g 22. Main Steam Line Radiation H R R* Y O i i i i .}}