ML20033G855

Proposed Tech Specs Re Containment Isolation Valves

ML20033G855
Person / Time
Site:	Catawba
Issue date:	03/29/1990
From:	Tucker H DUKE POWER CO.
To:
Shared Package
ML20033G854	List: ML20033G853 ML20033G855
References
NUDOCS 9004120217
Download: ML20033G855 (54)

Text

ATTAcitMINT I Pit 0 POSED CitANGES TO TECHNICAL SPECITICATIONS l

l 1

9004120217 900329 FDR ADOCK 05000413

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P PDC

i OtFINIT! "

IPIA

• jl

.7 CONTA!WWff INTEGR!TY shall exist when:

8 e

1 7

a.

All penetrations required to be closed during accident conditions are l

d I either:

i i

• g 1)

Capable of being closed by an OPERA 8LE containment automatic 4

j (

isolation valve system, or 9[

i P

2)

Closed by manual valves, blind flanges, or deactivated automatic I

4

[j j i valves secured in their closed positions, : c::: a e m....

i p

r

' ::^ t.N;...-.;.;.;,ee

F b.

All equipment hatches are closed and sealed.

l J

qr J,

c.

Each air lock is in compliance with the requirements of $pecification

3. 6.1. 3, j

d.

The containment leakage rates are within the limits of Specification i

h.

3.6.1.2, and i

I The sealing mechanism associated with each penetration (e.g., welds, f

e, bellows, or 0-rings) is OPERA 4LE.

l CCNie0LLED LEAKAGE w

1. 4 CCNTROLLED LEAKAGE shall be that seal water flow supplied to the reactor i

~

cooiant pump iesis.

CORE ALTERATION i

l 1.9 CORE ALTERATION shall be the movement or manioulation of any component l

.ithin the reactor pressure vessel with the vessel menc removed and fuel in l

the vessel.

Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.

DOSE EQUIVALENT I 131 l

1.10 00$t EQUIVALENT I-131 shall be that concentration of I 131 (microcurie / gram)

.nich alone would produce the same thyroid cose as the cuantity and isotopic mixture of I 131, 1 132.

133, 1 134, and 1-135 actually present.

The thyrcia cose conversion f actors used for this calculation shall be those listed in Taele !!! of TID-14444, " Calculation of Distance Factors for Power and Test Reactor Sites."

i I

AVERAGE O!SINTEGRATION ENERGY 1.11 I shall be the average (weighted in proportien to the concentration of each radionuclide in the sample) of the sua of the average beta and gamma energies per disintegration (MeV/c) for the radionuclices in the sample.

CATAWBA UNITS 1 & 2 1-2

l

+

l.

09' O GMk C644m M,5 P4Wie S wW 4%

M M M WMV4$ ett egeh 3/4.4 CONTAlletNT $YlTEMS 3/4,L1__ftDERY CONTAIleatNT c e,4ed * *l CONTAM INT $ttlfY LIMITING CON 0!T!0N FOR OPtRATICN 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY:

M00tl 1, 2, 3, and 4 j

A.13.IN.:

l Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> er be in at least HOT STAN00Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLO i

SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SUovt!LLANCE REQUIREMENTl 4.6.1.1 Primary CONTAINMENT INTEGt!TY shall be demonstrated a.

At least nce per 31 days by verifying that all penetrations not a

capabl f being closed by 0PERA8LE centsinnent 49tematic isolation valve and requ' red to be closed during accident conditions are i

cies.4 y vaives, niind fian,ee, or c.sctivated oute.atic vaives secured in their positions) 1 49894**W89498>4=4=4e=

l l

b.

By verifying that each containment air Inck is in compliance with the requirements of $pecification 3.6.1.3; and Af ter each closing of each penetration su. ject to Type I testing, b c.

except the containment air locks, if ooened following a Type A or test, by leak rate testing the seal with gas at a pressure not less then P,14.68 psig, and verifying that when the measured leakage rate for thloe seals is added to the leakage rates determined pursuant to Specification 4.6.1.2d. for all other Type 4 and C penetra'tions, the combined leakage rate is less then to 0.60 L,.

i "tacept valves, blind flanges, and deactivated automatic valves which are located inside the annulus or the containment and are locked, scaled or otherwise secured in the closed position.

These penetrations shall be verified closed during each COLD $HUTDOWN except that such verification need not be performed more often than once per $2 days, th Valus w h. sh ene y b e g en ed e w a n o* n t s t~mi H e n + bssis t%

eJm'.n t e ram ve. ee nh\\ a e t Idtnt4tta t r) Fs e p, T~A ble s 4. 6. 2. - /

pd lle. le e l - 2..

l CATAWBA

• UNITl 1 & 2 3/4 6 1

i l

j

(

CMT4110Elli.lYSTDtB CONTAll0ELLEMM i

LINITING COM ITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be lieited to:

l a.

An overall integrated leakage rate of:

)

1)

Less than or equal to L,, 0.305 by weight of the containment llI air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,, 14.64 psig, or

{

2)

(Unit 1) Less than or equal to L, 0.1225 by weight of the g

containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of P,

7.34 psig.

g J

A combined leakage rate of less than 0.60 L, for all penetrations j

b.

i and valves subject to Type 8 and C tests, when pressurized to P,,

and A combined bypass leakage rate of less than 0.07 L, for all c.

penetrations. identified 4r9eMy$.9% as segndary containment bypass leakage paths when pressurized to P,-

l APplICA81LITv:

MODES 1, 2, 3, and 4.

l ACTION:

I With:

(a) the measured overall integrated containment leakage rate exceeding 0.75 j

L, or 0.75 L, as applicable, or (b) the measured combined leakage rate for all g

penetrations and valves subject to Types 8 and C tests exceeding 0.60 L,, or

.l (c) the combined bypass leakage rate exceeding 0.07 L,, restore the overall

{

integrated leakage rate to less than 0.75 L,'or less than 0.75 L, as applicable, I

g and the combined leakage rate for all penetrations and valves subject to Type B l

and C tests to less than 0.60 L, and the combined bypass leakage rate to l

1ess than 0.07 L, prior.to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS l

1 I

4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR Part 50 using the methods and. provisions of ANSI N45.4-1972 or the mass plot method:

3 Tie Ame v.edenwme4 nnypein le k=ge e=Ws one dedifid '*

c.6e=Am PSmet 'Takte. 4. 6-t.

CATAWBA - UNITS 1 & 2 3/4 6-2 Amendment No. 41 (Unit 1) i Amendment No.' 34 (Unit 2)

j IABtE 3.6-1 5tCONDARY Colli AIISENI BVPA55 iE AILAGE PAlltS s

PtHLIRAll IEST e

Mtseta SERVICE RELEASE IOCAIIGIl IVPE i

e i

}

M216 Pr eerizer Relief Iank hkeup Auxiliary Smilding Type C

^

en i

co M212 Nitr to Pressuriser Relief lank Aemiliary Sullding Type C

.=

=

M327 Reactor Ces

4. Peep fletor Drain Ianet Auxiliary Building Type C Peep Bisc 2

s M259 Reactor h6eup Wate Flush Header Auxiliary Su ing Type C 1

tre j

M373 Ice Condenser Glycol P Bisclearge Auxiliar i lding Type C Line f

4.

j

.a M372 Ice Condenser Glycol Pumps Sesc iliary Smilding lype C i

)

Line W

l M332 Cont. Hydrogen Purge Inlet Blouer A

j Bisclearge Line spliere type C i

M348 Reactor Coolant Drain lank s

Ammi ry Basilding type C l

Space to hste Gas Syst M221 Ventilation Unit C isate v

i Drain Header Anexiliary Gui

'ag Type C 3

038O M356

[apsipment tamination time Assuiliary Sesilding type C M358 Refueli ter Peep Suction Anexiliary Sesilding Type C M377 Re ing Cavity Iill Iine Assaillary Sesilding Iype C M235 Pressurlier Sample Auxiliary Sesilding type C l

l M3 Reactor Coolant Hot leg Sample Assailiary Basilding i

C k

=

-e-<

3 e

-e,,

-~w w--w,

,w.

-v

i i

i l

IABIE 3.6-1 (Continesed) n h

SICONDARY CONIAIOBENI SVPA55 if AIWlfe PAI005 i

t j

E PillllllAll Esg f

l IIIsetR SERVICE Rett A5f IOCAlleII IVPE

{

c l

4 fa M323 C

Coeliseg to Ceaponent l

M Cool Brain Susp Auxiliary Sesilding typet l

l s

e-M240 feesclear e Water to Reactor l

l Coolant Peep tower Cent.

j m

j Vent. Units Assuiliary Sesildi Type C l

i M230 pluclear Service Water em Reactor j

l Coolant Pump and toue eat.

l Vent. tinits Aasmili Basilding Type C j

\\

M385 Nuclear Service Water to I W r j

Containment Ventilatica Units la ine Sesilding Type C w

1 M308 Iluclear Service Water to tipper i

a Centainment ventilation Units ine Sesilding Type C j

t M213 Incore lastrumentation ge Ir.

Aasmili

- BesiIdiseg Type C Ml40 Incore Instr.smeest-oet Room Purge out Aasmiliary iding lype C f

M456 tapper Compar t Pestge inlet Aesmillary Sesil Type C l

?

l M432 tappe empartment Purge Inlet Aasmillary Basilding Type C M357 ewer Compartment Purge falet Aasmiliary Basilding Type C 1

l M368 Containment Purge [nheesst Assaillary Building lype C i

l 3

Containment Purge txhaust Aasmiliary Sesildiseg fyre C l

l f9434 lanser Enepartment Purge inlet Aeonillary Sesildises lype C l

i

j i

l I

l 1A8tE 3.6-1 (Continued) f n

I SECONDARY CONIAIISENT SYpASS LEAIUEE PATHS h

THEIRATION ST InsSER SERVICE RELEASE LOCATICII IYPE b

M386 Contal Air Release Aesniliary Building lype C i

Y M204 Containment Ai ition Ansailiary Building Type C g

l M316 Int. Fire Protection ader -

Auxiliary Sesilding Type C j

m Hose Racks M337 Demineralized Water Auxiliary Buil Type C i

1 i

M220 Instrument Air Aasmiliary iding Type C i

i M219 Station Air Anaxili Guilding Type C l

M M215 Breathing Air lary Sullding lype C i

e i

O M329 Reactor Coolant Painp Motor Oil Fill ili Building lype C

{

M361 Int. Fire Protection Header -

Auxiliary Gu ing Type C Sprinklers l

M119 Containment Purge Exhaust Auxiliary Building Type C l

33 Accisnislators Type C f

fk M331 Nitrogen Supply to Ce teg Aesniliary Gesilding i

l tf i

gg M322 Safety Injecti Test Line Aasmiliary Sesilding Type C j

l l

((

M454 UHi Test Aeoniliary Basilding C

Isole 1 f

uw M328*

C t Cooling to Reactor Auxiliary Smilding type gg V

el Support and RCP Coolers i

33 M

• Not appl' le for Unit I until af ter the first refueling eestage.

l o,,.. r<,,,,,,,,,, of perietr<st ionis.issu iated witti deletion f uIu, unis w i r icau is = 1 wer

,,e l

app l ic< stile.

t

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Unit one penetrations (all are test type 5 and C) that need not be tested unti rier to estering NOT SHUTDOWN following the Unit One first refueling.

i l

PENET 10N REL_ EJ l

NUM SERVICE LO W ION 1

i M230 Nuclear Service Water from Reactor Auxiliary J

Coolant Pump and Lower Containment Building l

Ventilation Units.

t l

M215 e

thing Air Auxiliary l

Building M219 Station r

Auxiliary Building i

M354 Refueling Wate ump 5 ion Auxiliary j

Building i

M356 Equipment Decont n ion Line Auxiliary t

ll Suilding M345 Recycle Hol Tank from ictor Coolant Auxiliary i

Drain Tan Valve 1WL606 on Building i

M204 Contai nt Air Addition Auxiliary Building M259 R ctor Makeup Water Flush Header Auxiliary Building E101-450 Electrical penetrations for various Auxiliary equipment Building M374 Containment Floor Sump and Incore Jxiliary Instrumentation Sump Pump Discharge B

1 ding v

CATAWBA - UNITS 1 & 2 3/4 6-74 Amendment No. 8 (Unit 1)

Amendment No. 1(Unit 2)

CONTAINMENT $YSTDes l

3/4.6.3 CONTAIM G T ISOLATION VALVES LINITING COMIITEW POR OPERATION I

1 i

l 3.6.3 The containment isolation valves ; =fffM fr. TO'n 3.3-0; =: 3.5 J shall be OPERA 8LE with isolation times k:' :185

.t:r ir. id' : 3,5-2: =: :. 0- 3.

l APPLICABILITY:

MODES 1, 2, 3, and 4.

' repicect isellacd No etn e r 4% 7 i

w es*.

i n

ACTION-

[ t.anW.o me.rtt l

j:3 A With.one or more of ;,Misolation valve (s) specified in.O'=R SygHo n N,. 4!.. : c:... O i

inoperable, maintain at least one isolation valve OPERA 8LE in each affected penetration that is open and:

+

j a.

Restore the inoperable valve (s) to OPERA 8LE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or i

i l

b.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or I

c.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at j

least one closed manual valve or blind flange, or d.

Se in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

l SURVEILLANCE REQUIREMENTS

[EcwJn c or*cimmere.)

4.6.3.1 3he(isolation valvejf r-4 '4 " i e'--

' '-2: =: 2.5-25 shall be demonstrated OPERA 8LE prior to returning the valve to service after mainte-nance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance'of a cycling test and verifi-cation of isolation time.

l g

1 i

i l

l

^k

• ect 'IsoWOon fim e5 c.ce, provjdecj in FSRR.SECkion %.6, 4

CATAWBA - UNITS 1 & 2 3/4 6-20 l

1

i I

CON _TA1!gtNT__f.Y1 TEM $

f SURVE!LL " * ~

1RS Wffi (Continued)

{

4.4.3.2 fac ise a va l ve -- - " " ' * -' ' - - ' ' ^ ~ - " ^ ^ ^' s ha l l t e demonstrated OPERABLE during the CCLD SHUT 00W or REFUELING MODE at least once per la months byt a.

Verifying that en a Phase "A" Isolation test signal, each Phase "A" isolation valve actuates to its isolation position;""-

b.

Verifying that en a Phase "B" Isolation test signal, each Phase "B" isolation valve, actuates to its isolation position;**

c.

Verifying that on a Containment Radioactivity-High test signal, each purge and exhaust valve actuates to its isolation position; and Verifyin

>705 isolation test d.

• signal,gthatenaHighRelativeHumidity(iesu)pplyandexh I

each upper and lower containment pur va ve actuates to its isolation position.

ggg

4. 6. 3. 3 The isolation time of each power operated or automatic & valve e 4ebnes=4 4=ee es*4 4mm shall be detemined to be within its limit when testae i

pursuant to Specification 4.0.5.

i i

l l

1 i

~2This surveillance need not be performed until prior to entering HOT SHUTDCWN following the Unit 1 first refueling.

CATAWBA - UNITS 1 & 2 1/4 6-21

i l

r IABIE 3.6-2a 9;;'

INIII I CSIIIAIISENT 150tAIISIl VAtVES M8m E

VALVE fl810CIIGff M

I$stAllW I N (s) 1.

Phase "A" I tien T

3 g

p y.

88-578#

team Generator IA Blowdown Centainment Outside Ise ion

<33

}

m t

88-2111#

5 Generater 18 Slowdown Centainment entside ation ils t

88-6341#

Steam rater EC Slowdown Centainment Swisi seletion ile 88-188#

Steam ater 18 Slowdown Containment Out Isoletten ile

?

)

88-56A#

Steam Gener IA Blowdown Centalament de Isolation ile i

88-19As Steam Generate Slowdown Cental aside Isolatten ile c.

I l

88-684#

Steam Generator I lewdown Cental t Inside Isoletten ile l

88-8A#

Steam Generator 18 8 C ^.-__ t Inside Isolation The f

i 88-1488#

Steam Generater IA 81 aimment Iselation typass Ele

)

88-1588#

Steam Generator 18 Sir ^_-

- ^ainment Isolation typass ils g

88-1498#

Steam Generator EC St C

inment Isolation typass ile K

j 4

88-1418#

Steam Generator 18 8 Centa Iselation typass 318 y

i i

CA-149#

Steam Generator flain feedwater to ary Feedseter IIezzle Isolation

<5

-t2 l

CA-158#

Steasy Genera 18 flain Feedseter to Auxil Feedwater IIezzle Isolation 25 I

CA-1518 Steam Gene er IC plain Feedsater to Aessiliary ter IInzzle Iselation 25 CA-152#

Steam f rator 18 m in lecilwater to Asemillary I ter IIezzle Isolation 35 m

i CA-185#

AuxiI ~ ry fluirle temper SGIA i

<5 a

CA-186#

Au iary IInzzle leaper SGIS 25 m

CA-181#

iIiary flozzle leaper SGIC 25 U

CA-188#

AuxiIiary 8001zle Temper SGIS 25 CF-60#

Steams Generator 18 feedwater Centainment Isolation 25 Cf-51#

Steam Generator 10 Feedwater Centainment Isolation 25 CF-47#

Steam Generator 18 feedwater Centainment Isolation 25 Cf-33#

Steam Generator IA fecesater Centainment Isolation 25 CF-90#

Steam Generator IA Ieedseter Peerge Valve

<5 CF.

Steam Generator 18 feedwater Peerge Valve

< tHf Steam Generator IC feedwater Peerge Valve

$5 F-8/#

SteamGenerator18feedwaterPeergeVajye

$5 k

w

=

=

r

,a

,,.,._.,.,s

i i

r F

j IABLE 3.6-2a (Continued) i UNIT 1 CGIIIAIISEIII 150LAT1011 VALVES E

i IWWM i

e VALVE IItBSER FUIICTIGII I

ATICII T- (s) c 5

l d

1.

Phase "A" Isolat (Continued) e KC-3058#

C s Letdoun Hx Supply Containment Isolation (Outside

<23 e.

KC-3158f Exc Letdoun Hx Return Header Containment Isolati side) 723 m

KC-320Af IICOT Hu ly Hdr Containment Isolation (Outside 72s KC-3328f IICST Hx Re a Ndr Containment Isolation (Insi 723 i

KC-333Af IICDI Mx Ret Ndr Containment Isolation (

de) 720 i

KC-4298 RB Drain Header side Centainment Isolati ile t;

KC-4304 RB Drain Header ide Containment Ise een

{1e l

l N8-2608 Reactor Makeup Water i to Flush ader

<10 l

N

~

100-538 Nitrogen to Pressurizer Reli ank #1 Containment Isolation entside

<10 l

4 IIC-54A Nitrogen to Pressurizer of fl Centainment Isolation Inside ile i

100-568 mal Pump Disch Cont Is ion 710 NC-1958 IIC Peep Motor Oil C inment Isolati tside ile IIC-196A IIC Pump Ilotor Oil tainment Iselation

'de

{le IIF-228A Unit 1 Air ling thiits Glye ul Supply Contai t isolation Outside

<10 NF-2338 Unit 1 A' ilandling Units Glycol Return Cental selation Inside ile IIF-234A Unit I r Handling Units Glycol Return Containment ation Gutside

{te l

NI-47A lator H Supply Gutside Centainment Isolation

<le kk' 2

NI-95A est Hdr Inside Containment Isolation ils aa NI-968 Test Ndr Outside Containment Isolatten ile 101-1208 Safety Injection Pump to Accumulater Fill time Isolation ile z2

??

NI-1228f Hot Leg injection Check 1811124. INI128 Test Isolation ile co w NI-1548f Hot Leg Recirculation Check IIII125, IIII129 Test Isolation ile I NI-25 UHI Check Valve Test Line Isolatten S

EE W

NI-UNI Check Valve Test Line Isolatten i

,feste 1

-le l

2648 LNel Check Valve lest Line Oestside Contalsment Isolation

3 I

nw Mote 1: Upon capping of penetrations associated witit deletten of leII, tIiese specifications are ne

~

1onger appIicabie.

\\

TABLE 3.6-2a (Continued) 9 y

UNII 1 CONTAIISENT ISOLATION VALVES I

It4N VALVE IRSSEB FUIICTICII ISOLATIINI j

1.

Phase "A" I tien (Continued) l C

iNI-266A IAII Check Valve Test Line Inside Centainment Isolation Note 1 LMI-267A I Check Valve Test Line Inside Centalament Isolatten 7

i e.

l NI-153M He og Injection Check III156, NI159 Test Isolation 7

u ISI-3A Pressur r Liquid Sample Line Inside Centainment Isol

<le

[

lei-6A Pressesriz tean Sample Line Inside Centainment. Ise ten ile 100-78 Pressurizer le IIeasier Outside Centainment. Ise ion ile 100-22A IIC Not Leg A e Line Inside Centainment Ise ion ile 100-25A IIC IIst Leg C Samp ine Inside Containment lation ile 100-268 IIC Hot Leg Sample side Centainment lation Ele w) 100-728 NI Accumulator IA Sampi ine Inside lament Isolation ile let-758 NI Accumulator 18 Sample L Insi^ _~ ^= lament. Isolation ilo i

100-788 NI Accumulator IC Saeyle Li Centainment Isolation ile j

106-818 NI Accumulator 18 Sample Line de Centainment. Isolation Ele i

106-82A NI Accumulator Sample IIdr ide lament. Isolation ile

]

106-187M

% IA 15per SheII Sample talament lation Inside ile i

let-190M SG 1A 81oudoun Line e Containment latten Inside ile I

100-1918f SG 1A sample Ndr C inment Isolatten de Ele l

304-1978#

SG 18 Upper Shel le Containment. Isolat Inside its j

get-2000f SG 18 81 na Sample Centalement Isolati Inside ile ff 100-201M SG 18 Samp3 Centainment Isolatten Gutside 714 i

==

ISt-207M SG IC Shell Sample Centalsment Isolatten Insi ile kk let-210Af SG IC oudoun Line Sample Centalement. Isolatten Inst Ele i

i gg 100-2119e CG-Sample Ndr Centainment Isolatten Gutside 318 l

100-2178f IS IDper Shell Sample Centalement Isolatten Inside

$le j

f,2 100-2200#

SG 18 Blenalown Line Sample Centafament Isolatten Inside

$le o

100-221M SG 18 Sample Ndr Centainment. Isolatten Gutside ile uu ww

! 22 IIW-158 Letdeun Containment Iselatten Gutside

<10 11 IIV-89A IIC Pumps Seal Beturn Centalement Isolatten Incide ile

[

pov-0 IIC Pumps Seal Return Centainment Isoletten Gutside

148f Charging Line Containment Isolation entside

$1 i

vv adote 1: Upon capping of penetrations associated w@ deletten of UNI, these specifications are no a......-

2... I i eab 1 4

i i

samat 3.6-24 (Continued) g I

g t#11I I CGIIIAIISEIII ISOLATISII VALVES I

Ilme i

g VALVE IItNSER f tNICIIGII I

igen J- (s) l 1

• i m

1.

Phase "A" Isolat (Continued) e e-W-11A 4

tetdown Grifice Outlet - Centainment Isolation

<38 j

n W-13A 75 Letdeue Grifice Outlet - Centainment Iseletion 730 W-104 High P urizer letdeun Grifice Outlet - Contal Iselatten ils i

W-872A 5taney Pump to RCS seals ile i

RF-3898 Interior fire tection Centainment Blese Iselatten Valve

<5 (Out:Ide Cental t) j RF-4478 Reactor Building Spr Iers Cental isolation Walve

<5

[

(outside Centainment V8-838 Breathing Air Unit 1 Contai t Isolation

<le l

E VY-188**

Containment H Purge Annulus ide Containment Isolation

<le l

2 l

VY-17Aa*

Containment H P to Annulus out Centainment Isolation ile VY-158**

Containment H ge Steuer Outlet C inment Isolation (outside) jae i

l VI-312A RS Isol on Valve for VI Supply to annutes t.

<le VP-lBa*

r Containment Purge Supply #1 Outside Isolat

~ <5 VP-2A**

r Containment Purge Supply #1 Inside Isolation 25 VP-38**

Upper Containment Purge Supply #2 Outside Isolation 25 i

VP-4A**

tapper Containment Purge Supply #2 Inside Isolation 25

}

VP-68**

tower Containment Purge Sepply #1 Sutside Isolation 25 VP-7A**

tower Containment Purge Sepply 88 Inside Isolation 25 j

VP-Iover Containment Purge Sepply #2 Outside Iselation

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N ^ ? IA8tE 3.6-2a (Centinmed) l9 UNTI I CONTAlleElli ISOLATIGII VALVES i -4 ~ i l suulical ijg VALVE fRSSER FUIICTICII ISSLATIGII TWE (s) [ i IQ (Centinmed) ie 2. Phase "8" Isolati ,~ ! e-Rff-4378 to IIC Pumps and LCVU Sepply Outside C -f-t Isolation <68 im INI-484A Ret rem IIC Pumps and LCVtf Return Inside ainment Isolation 264 i RN-4878 Return IIC Peups and LCVU Return Centainment Isolation 260 Ril-4048 Supply to r Centainment Supply lation units Centainment -ile j l Isolation ( side) RN-429A Return from W ontainment ilation Ifnits Containment Isolation <10 l l l (Inside) RII-4328 Return from Upper Cent ' t Ventilation Units Containment Isolation $le l l, (Outside) VI-778 Instrument Air tainment Outse Isolation <Is f is![ l IU SM-1 # Nain Ste 0 Isolation <5 SM-3 # hin as IC Isolation 25 i j 5pe-5 # Na' team 18 Isolation 25 i Sft-7 # in Steam 1A Isolation 25 i 25 500-9 # flain Steam 10 Isolation Sypass Ctri. 25 l 536-10 # h in Steam IC Isolation Bypass Ctrl. ? 25 $f0-11 # flain Steam 18 Isolation Sypass Ctrl. -5 I SM-12 Main Steam 1A Isolation typass Ctrl. 1 <5 j 5 9# flain Steam 1A PORV 25 l V-13 # Main Steam 18 PORV is SV-7 # flain Steam IC PORV ~5 l SV-1 # Main Steam 10 PORV { WL-867Aa* Containment Vent Unit Drains Inside Centainment Isolation ile ta-M9B** Containment Vent Unit Drains Outside Centalement Isolation l i. u ~ ^^ ---1___,, _ _,

o A TA8tE 3.6-2a (Continued) 4 CONIAIISEIII 150LATION VALVES INutIIM l g VALVE BENBER FUNCil010 AIISI i g (g) i ~* i 3. Manual i ~ NC-141 H Drain Tank Pump Discharge N.A. IIC-142 IIC H Drain Tank Pump Discharge N.A. Ni-3 Boron I tion Tank Line to Cold Le9s N.A. FW-ll Refueling r Peep Section M.A. l FW-13 8efueling Wat Pump Section N.A. CF-91# Feedwater IA N.A. CF-93# Feedwater 18 N.A. j CF-95# Feedwater IC N.A. CF-97# fee &ater 10 N.A. w1 CA-121# Aux. Fee & ater IA N.A. BW-If Aux. Feedwater IA N.A. 1 4 CA-1200 Aux. Feedwater 18 N.A. j 8W-26# Aux. Feedwater 18 N.A. l CA-119# Aux. Feedwater IC N.A. BW-17# Aux. Feedwater N.A. CA-118f Aux. Feedwa 10 N.A. i BW-lof Aux. F ter 10 N.A. lg SM-16# Nain as IA N.A. SM-73#* Mai team lA N.A. SM-105# n Steam 1A N.A. 3 l33g SM-1213 in Steam lA N.A. SM-143s Main Steam 1A N.A. SM-723* Main Steam 18 N.A. g& SM-104# Main Steam 18 N.A. SM-120s Main Steam 18 N.A. 4 i 3 ". SM-1 IIain Steam 18 N.A. Main Steam ]g .A. l i 99 17# Main Steam 18 N-pp SM-18s Main Steam IC N.A. SM-71#a Main Steam IC II. A. w l vv (

r \\ \\_ j mett 3.6-2a (Centinmed) i j 9g uMII I CONIAINNENI ISOLATION WALM S l-I fuut3Ings E VALVE IllsWER FUNCil011 3 ggg y g (,} j Q d 3. Manual (Conti ) i e' SM-103# in Steam IC 3,3, l N SM-Il9# iia Steam IC g,g, j l SM-141# IIain as IC gg,3, j SA-4# Nain Ste IC N.A. j $M-19# m in Steam Is,a. l 1 SM-70f* h in Steam 10 II. A. i SM-102# Nain Steam 10 N,A, j SM-Il8# Main Steam 10 N.A. $M-140# IIain Steam 19 N.A. i )m WE-20* Coat Side Supply Ital II. A. i WE-22" Coat Side Sepply Isol N.A. .4 WE-56* Cent Olds Supply Isol N.A. l e FW-4* Refueling Water N.A. NV-862#* Pressurizer Auxiliary Spr IS Gets Centainment N.A. i 4 WLA-21#* Steam Generater Drain Bischarge side Containment isolation N.A. l WLA-24#* Steam Generator Dr Pump Bischarge Out Centainment Isolation N.A. i f l IAttE IIDIAIIGIIS l f j

• May be opened on an int attent basis under administrative centrol.
  • Valve aise recei a Nigh Radiation (N) and/or a High Relative Ilumidity isolat signal.

j i

1. Not subj e Type C leakage tests.

l j IISI - ines are for valve operation only, and do not include any senser response er circuit lay times. i See Specification 3/4 3.2 for system actuation response times. l i 1 i l l

(- l b IAttE 3.6-20s I 9 if teIII 2 0001IAI40Elli 150LATIGII WALVES I IRSIIMI E VALVE IItBSIES FINICIIOBI 154 iM (s) i U j l. Please "A" Isola ~ \\ s' 08-578# 5 Generator 2A SI W Centainment entside Isola <38 88-218# Ste rater 28 Slomatsun Centainment Outside I tien ils 88-618# Steam rater 2C Sleudoun Centainment Outsi latten ile I 88-10S# Steam Gene er 29 Blaudoun Centainment out Isolatten ile l 88-56Af Steam Generat 2A Sloudoun Containment I de Isolation jle BS-19Af Steam Generator Sleudoun Cental aside Iselation <le l 88-60A# Steam Generator 2C - r_ - Cental Inside Iseletten ile i 88-8Af Steam Generater 28 Si r7- __ _;t Inside Isolation ile lament Isolation typass ile 88-1488# Steam Generator 2A SI, tainment Isolation typass {te l l ) 88-150S# Steam Generator 28 SI l 88-1498# Steam Generater 2C SI C imment Isolation typass $le e. j 88-1479# Steam Generator 28 Conta t Isolatten typass $le o j CA-149# Steam Generat A flein Fee 6ater to lary Feehater IIezzle Isolatten <5 1 CA-150# Steam -Gener er 28 plain Feeduster to Ammi Fee 6ater 80ezzle Isolation 25 l 2 CA-151# Steam ator 2C plain feedwater to Ammili seduster senzzle Isolation 35 CA-152# Steam rator 29 flain Ieedwater to Assaillary ter Nozzle Isolatiese <5 ? CA-185# Aux ary flozzle Iceper SG7A <5 i CA-186# ,liary IInzzle leaper 5G28 25 CA-18?# xiIiary flozzle leaper SG2C 35 CA-188# Auxiliary flozzle Temper SG29 $5 CF-60# Steam Generator 28 Feedenter Centainment Isolation $5 l CF-51# Steam Generator 2C Feeduster Centalement Isolation $5 ) 4 i CF-42# Steam Generater 28 feeduster Centalement Isolation $5 i j CF-3 Steam Generater 2A Fee h ater Centalaneet Isolation $5 1 CF-Steam Generator 2A Feeduster Purge Valve $5 { -89# Steam Generator 23 Feessater Purge Valve <5 i CF-88# Steam Generator 2C Feeduater Purge Valve j CF-87# Steam Generator 29 feedwater Purge Valve 1 3 8 ~ s i

._=- l l i l I TABLE 3.6-2b (Continued) [ i n i h UNIT 2 CGIIIAIISENT ISOLATISI VALVES k IM8M { { g VALVE paseER FUIICTIGII I IIgg g (g} 1 1. Phase "A" Isolgt (Continued) l i e e-KC-30588 Exc Letdown Hx Supply Centainment Isolation (Outside) <23 n KC-31588 Excess tdown Nx Return Meader Centainment Isolation side) 723 l l KC-320Af IIC8T Nx ly 90dr Centainment Isolation (entside) 22e i l KC-33298 IICOT Nx Ret Centainment Isolatien (Inside) 22e KC-333Af IIC8T Nm Retcrn Centainment Isolation (Outsi E2e l KC-4298 88 Drain Header I Centainment Isolation ile l KC-430A R8 Drain Header Outsi Centainment Isolat' ile 1 i A i w NS-2608 Reacter Makeup Water Tank i lush <1e i i 80C-538 Nitrogen to Pressurizer Relief

1. 1 Centainment Isolation Gutside

<le o. J. IIC-54A IIitrogen to Pressurizer Selle Centainment Isolation Inside ile 10C-568 Net Pimp Disch Cent Isolat Ele i 1 110-1958 IIC Pump' Meter Oil Conta t Isolation side ile l i IIC-1964 IIC Pump Motor Oil amont Isolation Ins Ele j I ^ t I pIF-228A Unit 2 Air Handl^ Units Glytol S g ly Cental Isolation Out. side <le IIF-2338 Unit 2 Air ing Units Glycol Retura Centainment lation Inside ile l I HF-234A Unit 2 Air ling limits Glycol Return Centainment I tien outside ile l (( ~ l NI-47A Acc ater N Supply Outside Centainment Isolatten <le l 2

, 2 l

gg III-954 T Ndr Inside Containment Isolatten ils i NI-968 st Ndr Outside Containment Isolatten 210 f

, s l

NI-1208 Safety Injection Pump to Accumulater Fill Line Isolation ile i ff NI-122SS IIst Leg injection Check 211I124, 2 Nil 28 Test Isolation ile W NI-15400 Het Leg Recirculation Check 2 Nil 25, 2NR129 Test Iselation ~ e 5(fMI-2558 tell Check Valve Test Line Isolatten mm NI-IAII Check Valve Test Line Iselatten ils e1 EE r i NI lAtt Check Valve Test Line Outside Containment Isolation ilej j l I Note 1: Upon capping of penetrations associated with deletten of INII. the5e Specifications are no ) longer applicable. 1

m.-____.__. I i i

l

~ I i TABLE 3.6-2b (Continised) Q + i

j i UNIT 2 CONTAIIBENT ISOLATIGII VALVES E

j i VALVE R FUIICTIGIl ISOLA c h 1. Phase " Isolatten (Continued) l f* l ,NI-266A IAII Check Valve Test Line Inside Centaisusent Isolation gege 1 ) e-Q81-267A IAII Check Valve Test Line Inside Centalement Isolaties i i N NI-153M Ilot Leg Injection Clieck Ni1%, NI159 Test Isolation i l i 100-3A surizer Lisguid Sample Line Inside Centainment lation <le let-6A P izer Steam Sample Line Inside Cental selatten ile Ist-78 Press zer Sample Ileader Gastside Centai selation its 100-22A IIC Not L A Sample Line Inside Contal Isolatten its i let-25A IIC IIst Leg Sample Line Inside Cental Iselation ile w 100-268 IIC Not Leg e Ildr Distside Cental Isolation ile l 5 104-728 III Accumislater Sample Line Ins Centalement Isolation ils as 106-758 NI Accesmaalater 2E le Line de Centalement Isolation ile 104-788 NI Accumeslater 2C Li aside Centainment. Iselation ile w 104-818 III Accessislator 29 Sampi Inside Centalemens. Isolation ile Ist-82A III Accesmulator Sample side Centalement Isolation ils let-187M M 2A' % r Shell e Can Isolation Inside ile let-190M % 2A Blowdown Li le Conta Isolation Inside ile 304-1918# SG 2A Sample entaisinesit. Isol Sist. side ils 136-1979f % 28 Upper il Sample Containment lation Inside ils pet-2000s % 28 81 Line Sample Centalement. atten Inside ile (( ISS-201M % 28 le Hdr Centainment Iseletten Guts ils i sa let-207M Upper Shell Sample Centalement. Isolatten ide 210 l ll let-210M 2C Blowdown Line Sample Centalement Isolatten ide ile ss 136-21198 % 2C Sample Ndr Containment Iselatten Gutside ile 134-21798 % 20 upper Shell Sample Centainment Isoletten Inside ile IE 100-220er M 29 Blowdown Line Sample Centalement Isolatten Inside Ele i Eu b let-221M % 20 Sample Ndr Containment Isolatten Gutside ile i XX 1 EE IIV-Letdown Containment Isolation Gutside <le IIC Pumps Seal Return Containment. Isoletten Inside ile ew -918 IIC Pumps Seal Return Containment Isolatten Gutside _e j NV-3148# Charging Line Containment Isolatten testsida $1 f 86ote 1: tipon cappiews of penetrat iovis associated wph deletion of INil, these specifications are no l N Ioeuser ape Iicataley - ] -

I "( IA8tf 3.6-2b (Continesed) 9y (NIII 2 COIIIAIISENI 150tAlleII WALVES iE OREBIEEE E VALVE IRNEKR FUIICTICII MTIM i- (s) 4 { 1. Phase "A" Isola (Continesed) l cx i W-IIA 4 tetdown Orifice Oestlet - Containment Isolati <33 IIV-13A. 75 Letdown Grifice Gestlet - Centainment Isola 733 l Ilv-10A liigh P serizer tetdown Grifice Gestlet - Cent t Isolation 73e IIV-872A Staney Pump to ACS seals ~ile i 4 l j Rf-3898 Interior fire P tien Containment Rack Isolation valve <5 l -l (0estside Contal t) l RF-4478 Reactor Basilding Spri rs C minnent Isolation Valve <5 (0estside Containment) ,s [ V8-838 Breathing Air Unit antai Iselation <3e e ) U VY-188** Containment eerge to Annesless Ins Centainment Iselation <le j VY-17A** Contal Nr Peerge to Annesless eastsi ainment Isolation ile i VY-158** Conta~ t It, Peerge Blower Gestlet, Centa Isolation (Gestside) its j i VI-312A Isolation Valve for VI Supply to annesles <le i VP-18** Upper Containment Pierge Supply #1 Gastside Isolation <5 i VP-2A** Hyper Containment Peerge Sepply #1 Inside Isolation 25 3 t WP-38** IWr Contaisement Peerge Sepply #2 Gastside Isolation 25 VP-4 upper Containment Purge Supply #2 Inside Isolation 25 2 tower Containsect Peerge Sepply #1 Gastside Isolation 25 VP -7A** tower Containnrat Pearge Supply #1 Inside Isolation ~5 i VP-88** Lower Containment Pierge Supply #2 Sietside Isolation 25 i i j VP-9A** Lower Containment Purge Sepply #2 Inside Iselation ~5 i i VP-lea ** Upper Containment Purge Emenanest #1 Inside Isolation <5 I l j ( a 6 i i

4 4 1 ~ 1 1 --^ K 1 r-y ;_^ gggg) 'I I h UIIII 2 C00ItAI8SENT 150tATION VAtVES C,i ORESIMI E VALVE IRSSE fleICTIGII I Allg { M (s) ] 1. Phase "A" I tien (Continued) e' VP-IIS** r Containment Purge Enhaust #1 Outside Isolation <5 VP-12A** Centainment Purge Exhaust #2 Inside Isolatten 25 VP-138** ainment Peerge Enhaust #2 entside Isolatl 25 i VP-15A** teuer C ainment Purge Entionst #1 Inside Isolat 25 VP-168** teuer Cent i Purge Exhaust #1 Outside I tien 25 VP-17A** Incere Instru. een Purge Sew ly Inside I len 25 VP-188** Incere Instru.. Peerge Sewly outside lation 35 VP-19A** lascere lastru. Reen P Emenaesst de Isolation <5 w l } VP-205** Incore Instru. Seen P side Isolation 15 [ VQ-2A** Containment Air Release I lation <5 f Vg-38** Containment Air Release side lation 25 1 Vg-158** Containment Air Addi Outside I tien 25 VQ-16A** Containment Air ion Inside Isolat 35 VS-548 Unit 2 Conta~ t Header Outside Isolation <l5 j K-8078# NCDI P s Discharge Outside Containment Isolati <le K-80$Af IICDI s Discinarge Inside Centainment Isolation ile l E-450A Vent inside Containment Isolatten ils i E-4518 i Vent Oestside Centainment Isolatten ile E-825Af** NB Sump Pump Disc 8 sarge Inside Centainment Isolation ile l M-8278f** RS Sump Pump Bischarge outside Centainment Isolation i,le i ) Vft-Il98 Demin. Idater Containment Outside Isolation $le i 1 l ' 2. Pha 8" Isolation i C-3388# IIC Pump Supply Header Pent. Isolation (Gutside) j KC-424Hf $1C Pumps lieturn Ndr. Pent. Inside Isolation 348 KC-425Ai NC Pumps Return Ndr. Destside Iselation $48 l ) 2

l t oew= - s f 1 TASTE 3.6-2b (Continued) l 4 ) 9 LNITI 2 COIliAIISENT ISOLATIGII VALVES l l g l b = = = = - l E VALVE InseER FisICTICII IIW M is) l ) Z l v' 2. Phase '8" Iselati Continued) ~ e-Alt-4378 Sepp to IIC Pumps and LCVU Sepply Outside Containment selation <68 5 l w RIt-484A Return IIC Pusys and LCVIf Return Inside Ccatai Isoletten I68 l Rf1-4875 Retearn f Pew and LCVtf Return Gutside Isoletten 268 i RIl-4048 Sepply to Containment Sepply Ventilation its Centainment Ile l Isolation ( de) ~ l RIt-429A Return from 4 W r tainment Ventilati it,s Containment Isolation <3e I (Inside) sit-4328 Retesen from I W r Centa Venti ion IInits Centainment Isolation -<10 (Outside) s [ VI-778 Instrument Air Containment s Isoletten <3e Set-1 # flain Steam 29 Iselat' <5 5ft-3 # flein Steam 2C Iso ion 25 l 596-5 # flain Steam 28 lation 25 i Sft-7 # flein Steam Iselation 25 500- 9 # flain St 20 Isolation Bypass Ctrl. 25 i 500-10 # flai eam 2C Isolation typass Ctrl. 25 $ft-il # Steam 28 Iselation Bypass Ctrl. 25 5f8-12 # in Steam 2A Isolation Bypass Ctrl. 15 <5 SV-19 # flein Steam 2A PGAV 25 SV-13 # Itain Steam 25 PORV SV-7 plain Steam 2C PORW 25 25 l 5 plain Steam 2D PORV -867A** Centainment Vent Unit brains Inside Centainment Isolation ile WL-8698** Containment Vent tinit Brains Outside Centalement Isolation 1' L N

i l 1 1. i I i IAttE 3.6-2b (Centinued) J l j "e talil 2 CONIAlfSENT 150tA11M VALWE5 I i VALVE ImaSER FUIICTIGII 1 c i 5 3. Manual i H \\ f NC-141 Peep H Drain Tank Peep Disclearge M.A. I 100-142 Hz Drain lank Peep Discharge N.A. NI-3 njection Tank Line to Cold Legs N.A. FW-11 Refuel Water Peep Section N.A. l l FW-13 Refueling ter Peep Sesction N.A. CF-918 Feessater 2A N.A. i CF-938 Feessater 28 N.A. CF-958 Feedmater 2C N.A. CF-978 Feessater 29 N.A. CF-121f Aux. Feessater 2A N.A. w SW-18 Anex. Feedwater 2A N.A. CA-120f Aux. Feedwater 23 N.A. 8W-26f Anam. Feedseter 23 N.A. l 4 CA-119e Aux. Feedwater 2C N.A. i SW-17f Anax. Feedwater 2C N.A. CA-11af Ansa. Feedwater 29 N.A. 1 BW-les Aux. Feessater 20 N.A. t 500-16f Main Steam 2A N.A. I 1 596-738 Main Steam ^ S.A. N.A. I Q Set-1058 flain Ste A 588-1218 flain 2A N.A. h2 500-1438 fla ~ team 2A N.A. l 596-72#

• n Steam 29 N.A.

( 33 Sft-104f flain Steam 28 N.A. i l fl 596-1200 flein Steam 29 N.A. { SM-1428 Main Steam 28 A. O SA-If Main Steam 28 N. l j 500-17 Main Steam 28 N.A. l gy Main Steam 2C N.A. j l 718" flain Steam 2C N.A. UU J 1 ..., - ~. ~ .w .vv . ----- --i

i 1 1 i IAStE 3.6-2h (centsauemp 9 y INIII 2 CONIAllSE861588 AIISI VALVES emIIIIESI l g VALVE IllegER ItsICTIGII g ggg y g,} ] Q 3. Manual (Continued l ea

• =

SM-103# IIe Steam 2C 3.A. j l m SM-Il9# Itain am 2C g.A. SM-141F Itain Ste 2C N.A. i SA-4# flain Steam N.A. l l SM-19# Nain Steam 29 N.A. j SM-70s= plain Steam 20 N.A. SM-102# flain Steam 29 Is. A. i SM-Il8# Nain Steam 29 N.A. SM-140# 10ain Steam 20 N.A. R WE-20* Cent Side Supply Isel N.A. WE-22* Cent SIdg Segyly Isel N.A. I WE-56* Cent Side Sepply Isol N.A. j O FW-4* Refueling Water II. A. i IfV-862#* Pressurizer Auxill Spray IS Gutside alament N.A. i WLA-21#* Steam Generater ain Peg SiscInorge Sutsi ainment Iselation N.A. i j WLA-24#* Steam Genera Srain Pump Siscinarge Outside inment Iselation N.A. t i IA8tt IIDIATIGIS l l

• May be opened on an i reittent basis under administrative _centrol.

I j

• • Valve also rece' s a High Radiation (H) and/or a migli Selative thenidity isolation signal.

1. Ilot subje o Type C leakage tests.

j NOIE: s are for valve operation only, and de not include any senser response er circuit delay times. See Specification 3/4 3.2 for system actuation r p times. l i

CONTAINMENT SYSTEMS 8ASES 3/a.6.2 DEPRESSURIZATION AND COOLING SYSTEMS The OPERA 8!LITY of the Containment Spray System ensures that containment depressurization and cooling capability will be availaole in the event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the safety analyses. However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere, and therefore the time requirements for restoring i an inoperable Spray System to OPERA 8LE status have been maintained consistent with those assigned other inoperable ESF equipment. 3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERASILITY of the containment isolation valves ensures that the f containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 through 57 of Appendix A to 10 CFR Part 50. Containment isolation within the time limits specified for those isolation valves designed to close auto-matica11y ensures that the release of radioactive material to the environ-ment will be consistant with the,ssumptions used S the analyses for a LO r 3/4.6.4 COM6USTIBLE GAS CONTROL The OPF.RASILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. Either reconejner unit is capaele of controlling the expected hydrogen generation associated with: (1) zirconium-water reactions, (2) radiolytic decomposition of water, and (3) corrosion of metals within containment. These Hydrogen. Control Systems are consistent with the recommendations of Regulatory Guide 1.7,'" Control of Combustible Gas Concentrations Following a LOCA," March 1971. The OPERABILITY of at least 35 to 36 ignitors per train (70 of 72 for botn trains) ensures that the Distributed Ignition System will maintain an effective i coverage throughout the containment provided the two inoperable ignitors are' not c on corresponding redundant circuits which provide coverage for the same region. This system of ignitors will initiate combustion of any significant amount of hydrogen released after a degraded core accident. This system is to ensure burning in a controlled manner as the hydrogen is released instead of allowing it to be ignited at high concentrations by a random innition source. F co.hed isendien vdves see hdel w MAA T=Wes is.6-1. 4d iW. ' wse % wh e6the *t4Ait tset.ATTeN Ttg*#4 tedeMon 4;ene we wwe. gtwem 4 we y , elonese. C ha een maJ4. le auerJeewf wilk +be regwi,esnents e( qes te ne PSAR c i c pg g o g al ssenJary eos4e6ns ent hvemos teshese pa6hs es( ne ve94 pet >4 4 fece gge,,4 o,g$gesag w M I Tehlt 4 -13 CATAWBA - UNITS 1 & 2 8 3/4 6-4

y. ..-g 9 .g a f ATTACilMENT II PROPOSED CilANGES TO FSAR ( i

I 1 fN) N 16.6 Ct3OIITMENTS RELATED TO ENGINEERED SAFETY FEATURES (NON-ESF SYSTEMS) -l 16.6-1 CONTAINMENT LEAKAGE l COMMITMENT Secondary containment bypass leakage paths shall be identified in Table 16.6.1-1. t APPLICABILITY: See Catawba Technical Specification Limiting Condition for Operation 3.6.1.2. REMEDIAL ACTION: See Catawba Technical Specification Limiting Condition for Operation 3.6.1.2. TESTING RE0VIREMENTS: See Catawba Technical Specification Surveillance Requirement 4.6.1.2. BASES: Technical Specification 3.6.1.2c specifies a combined bypass leakage rate of less than 0.07 La for all penetrations identified in Table 16.6.1-1 as secondary containment bypass leakage paths when pressurized to Pa. Identi-fication of secondary containment bypass leakage paths in Table 16.6.1-1, i rather than in Catawba Technical Specifications Section 3/4.6.1, allows future changes to be evaluated in accordance with the process described in 10 CFR 50.59. l i l 16.6-1 i l l

TABLE 16.6.1-1 (Page 1 of 4) SECONDARY CONTAll#9ENT BYPASS LEAKAGE PATHS 1 PENETRATION TEST NUPEER SERVICE RELEASE LOCATION g i M216 Pressurizer Relief Tank Makeup Auxiliary Building Type C M212 Nitrogen to Pressurizer Relief Tank Auxiliary Building Type C M327 Reactor Coolant Pump Motor Drain Tank Auxiliary Building Type C Pump Discharge M259 Reactor Makeup Water Flush Header Auxiliary Building Type C M373 Ice Condenser Glycol Pumps Discharge Auxiliary Buf1 ding Type C Line M372 Ice Condenser Glycol Pumps Suction Auxiliary Building Type C Line M332 Cont. Hydrogen Purge Inlet Blower Discharge Line Atmosphere Type C M348 Reactor Coolant Orain Tank Gas Auxiliary Building . Type C-Space to Waste Gas System M221 Ventilation Unit Condensate Drain Header Auxiliary Building Type C M356 Equipment Decontamination Line Auxiliary Building Type C M358 Refueling Water Pump Suction Auxiliary Building Type C M377 Refueling Cavity Fill Line Auxiliary Butiding Type C M235 Pressurizer Sample Auxiliary Building Type C t

TABLE 16.6.1-1 (Page 2 of 4) SECONDARY CONTAIDMENT BYPASS LEAKAGE PATHS PENETRATION TEST NUpBER SERVICE RELEASE LOCATION M M310 Reactor Coolant Hot Leg Sample Auxiliary Building Type C M323 Component Cooling to Component Cooling Drain Sump Auxiliary Building Type C M240 Nuclear Service Water to Reactor Coolant Pump and Lower Cont. Vent. Units Auxiliary Building Type C l M230 Nuclear Service Water From Reactor Coolant Pump and Lower Cont. Vent. Units Auxiliary Building Type C M385 Nuclear Service Water to Upper Containment Ventilation Units In Turbine Building Type C M308 Nuclear Service Water to Upper Containment Ventilation Units Out Turbine Building Type C M213 Incore Instrumentation Room Purge In Auxiliary Building Type C MI40 Incore Instrumentation Room Purge Out Auxiliary Building Type C -M456 Upper Compartment Purge Inlet Auxiliary Building Type C M432 Upper Compartment Purge "nlet Auxiliary Building Type C M357 Lower Compartment Purge Inlet Auxiliary Building Type C M368 Containment Purge Exhaust Auxiliary Building Type C M433 Containment Purge Exhaust Auxiliary Building Type C i W4 tower Compartment Purge Inlet Auxiliary Building Type C

TABLE 16.6.1-1 (Page 3 of 4) SECONDARY CONTAIIstENT BYPASS LEAEAGE PATMS PENETRATION TEST NUISER SERVICE RELEASE LOCATION TYPE M386 Containment Air Release Amulliary Building Type C M2G4 , Contalement Air Addition halliery Building Type C M316 Int. Fire Protection Header - h illary Building Type C Hose P.acks C337 Demineralized Water Auxiliary Butiding Type C M220 Instrument Air h illary Building Type C M219 Station Air buillary Building Type C M215 Breathing Air halliary Building Type C M329 Reactor Coolant Pump Motor 011 Fill Auxiliary Building Type C l l M361 Int. Fire Protection Header - halliary Building Type C l Sprinklers M119 Containment Purge Exhaust buillary Sullting Type C M331 Nitrogen Supply to Cold leg buillary Building Type C Accumulators M322 Safety injection Test Line b litary Building Type C M454 UNI Test Line h illary Building Type C Note 1 C328* Component Cooling to Reactor Amulliary Building Type C Wes,el Support and RCP Coolers 54. -..:51..t,1v f or lin i t _ I unt il a f ter t re f i rst ref ueling outage. 9... i.e pp e e.-;.. t 3 cne t r a t s sv. - .e +n s ted with deletion of UHI, this specification is no longer applicatale. f.

0 I O TABLE 16,6,1=1 fpane 4 of 4) Note Unit one peitetretions (all are test type B and C that need not be tested until prior to entering HOT $HUTDOWN following the Unit One first refueling. l PENETRATION RELEA$E WMatt $ERVICE LOCATION M230 Nuclear Service Water from Reactor Auxiliary Coolant Pump and Lower Contair. ment But1 ding i Ventilation Units l l i M215 Breathing Air Aust11ery Butiding j M21g $tation Air Auxiliary Building M358 Refueling Water Pump Suction Auxiliary i butiding l M356 Equipment Decontamination Line Availiary Building M345 Recycle Holdup Tank from React:r Auxiliary Coolant Orain Tank (Valve IWLEC6 Building only) M204 Containment Air Addition Auxiliary Building i M259 Reactor Makeup Water Flush Heacer Auxiliary Building E101 450 Electrical penetrations for varicus Auxiliary equipment Building M374 Containment Floor Sump and Incore Auxiliary Instrumentation Sump Pump Otscharge Butiding

I i i l Ull 16.4 - ~ TImitt RELATED TD ENGINEERED $AFETY FEATURES (WON-elf $YSTEMS) 16.6 2 CONTAINMENT !$0LAT!0N VALVES CDm!TMENT 4 Containment isolation valves and the required isolation times shall be identified in Table 16.6.2-1 (Unit 1) and 16.6.2-2 (Unit 2). l APPLICABILITY: See Catawba Technical Specification Limiting Condition for Operation 3.6.3. REMEDIAL ACTION: See Catawba Technical Specification Limiting Condition for Operation 3.6.3. TESTING REQUIREMENTS: See Catawba Technical Specification Surveillance Requirements 4.6.3.1, 4.6.3.2, and 4.6.3.3. l BAl((: Technical $pecification 3.6.3 requires cont 6inment

olation valves to be operable with isolation times less than or equal te ne required isolation times.

Containment isolation valves and required isolation times are identified in Tables 16.6.2-1 (Unit 1) and 16.6.2-2 (Unit 2). Identification of containment isolation valves and isolation times in Tables 16.6.2-1 and i 16.6.2-2, rather than in Catawba Technical Specificatiens Section 3/4.6.3, allows future changes to be evaluated in accordance with the process described in 10 CFR 50.59. 16.6-2

TABLE 16.6.2-1 (Page 1 of 8) UNIT 1 CONTAINMENT ISOLATION VALVES MAIIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) 1. Phase "A" Isolation BB-578# Steam Generator IA Blowdown Containment Outside Isolation <10 E0 BB-21B# Steam Generator IB Blowdown Containment Outside Isolation 120 88-61B# Steam Generator IC Blowdown Containment Outside Isolation 1 BB-10B# Steam Generator ID Blowdown Containment Outside Isolation 210 BB-56A# Steam Generator IA Blowdown Containment Inside Isolation 210 20 BB-19A# Steam Generator 1B Blowdown Containment Inside Isolation 120 BB-60A# Steam Generator IC Blowdown Containment Inside Isolation 120 BB-8A# Steam Generator ID Blowdown Containment Inside Isolation 1 BB-148B# Steam Generator IA Blowdown Containment Isolation Bypass 310 BB-150B# Steam Generator IB Blowdown Containment Isolation Bypass $10 BB-1498# Steam Generator IC Blowdown Containment Isolation Bypass $10 BB-1478# Steam Generator ID Blowdown Containment Isolation Bypass $10 CA-149# Steam Generator IA Main Feedwater to Auxiliary Feedwater Nozzle Isolation $5 CA-150# Steam Generator IB Main Feedwater to Auxiliary Feedwater Nozzle Isolation SS CA-151# Steam Generator IC Main Feedwater to Auxiliary Feedwater Nozzle Isolation $5 CA-152# Steam Generator ID Main Feedwater to Auxiliary Feedwater Nozzle Isolation SS CA-185# Auxiliary Nezzle Temper SGIA $5 CA-186# Auxiliary Nozzle Temper SGIB $5 CA-187# Auxiliary Nozzle Temper SGIC 15 CA-188# Auxiliary Nozzle Temper SG1D $5 CF-60# Steam Generator ID Feedwater Containment Isolation <5 CF-51# Steam Generator IC Feedwater Containment Isolation 75 CF-42# Steam Generator IB Feedwater Containment Isolation 25 CF-33# Steam Generator IA Feedwater Containment Isolation 25 CF-90# Steam Generator IA Feedwater Purge Valve 35 CF-89# Steam Generator IB Feedwater Purge Valve 55 CF-88# Steam Generator IC Feedwater Purge Valve 55 CF-87# Steam Generator ID Feedwater Purge Valve 15

o O TABLE 16.6.2-1 (Pace 2 of 8) UNIT 1 CONTAINMENT ISOLATION VALVES MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) 1. Phase "A" Isolation (Continued) KC-305B# Excess Letdown Hx Supply Containment Isolation (Outside) 520 KC-315B# Excess Letdown Hx Return Header Containment Isolation (Outside) <20 KC-320A# NCDT Hx Supply Har Containment Isolation (Outside) 220 KC-332B# NCDT Hx Return Hdr Containment Isolation (Inside) 220 KC-333A# NCDT Hx Return Hdr Containment Isolation (Outside) 220 KC-429B RB Drain Header Inside Containment Isolation 210 KC-430A RB Drain Header Outside Containment Isolation 310 NB-260B Reactor Makeup Water Tank to Flush Header $10 NC-53B Nitrogen to Pressurizer Relief Tank #1 Containment Isolation Outside $10 NC-54A Nitrogen to Pressurizer Relief Tank #1 Containment Isolation Inside $10 NC-56B RMW Pump Disch Cont Isolation <10 NC-1958 NC Pump Motor Oil Containment Isolation Outside 310 NC-196A NC Pump Motor Oil Containment Isolation Inside $10 NF-228A Unit 1 Air Handling Units Glycol Supply Containment Isolation Outside $10 NF-233B Unit 1 Air Handling Units Glycol Return Containment Isolation Inside $10 NF-234A Unit 1 Air Handling Units Glycol Return Containment Isolation Outside $10 NI-47A Accumulator N, Supply Outside Containment Isolation $10 NI-95A Test Hdr Inside Containment Isolation <10 NI-968 Test Hdr Outside Containment Isolation 210 NI-120B Safety Injection Pump to Accumulator Fill Line Isolation 310 NI-1228# Hot Leg Injection Check INI124,1NI128 Test Isolation 510 NI-154B# Hot leg Recirculation Check INI125, 1NI129 Test Isolation $10 NI-255B UHI Check Valve Test Line Isolation <1 NI-258A UHI Check Valve Test Line Isolation 210 Note 1 NI-264B UHI Check Valve Test Line Outside Containment Isolation 310 Note 1: Upon capping of penetrations associated with deletion of UNI. these specifications are no longer applicable.

O TABLE 16.6.2-1 (Page 3 of 8) UNIT 1 CONTAIN"ENT ISOLATION VALVES MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) 1. Phase "A" Isolation (Continued) I-266A UHI Check Valve Test Line Inside Containment Isolation <1 Note 1 2) 10 Ull-267A UHI Check Valve Test Line Inside Containment Isolation NI-153M Hot Leg Injection Check NI156, NI159 Test Isolation 210 NM-3A Pressurizer Liquid Sample Line Inside Containment Isolation <10 20 1 NM-6A Pressurizer Steam Sample Line Inside Containment Isolation 20 1 NM-78 Pressurizer Sample Header Outside Containment Isolation NM-22A NC Hot leg A Sample Line Inside Containment Isolation 210 NM-25A NC Hot Leg C Sample Line Inside Containment Isolation 310 NM-26B NC Hot Leg Sample Hdr Outside Containment Isolation <10 20 1 NM-72B NI Accumulator IA Sample Line Inside Containment Isolation 20 1 IM-75B NI Accumulator IB Sample Line Inside Containment Isolation 20 1 NM-788 NI Accumulator IC Sample Line Inside Containment Isolation NM-81B NI Accumulator ID Sa.:ple Line Inside Containment Isolation 310 NM-82A NI Accumulator Sample Hdr Outside Containment Isolation <10 NM-187M SG 1A Upper Shell Sample Containment Isolation Inside 210 NM-190M SG 1A Blowdown Line Sample Containment Isolation Inside 210 20 1 NM-191BK SG 1A Sample Hde Containment Isolation Outside 20 1 NM-197B# SG IB Upper Shell Sample Containment Isolation Inside NM-200B# SG IB Blowdown Line Sample Containment Isolation Inside 210 20 1 NM-201M SG 18 Sample Hdr Containment Isolation Outside 20 1 NM-207M SG IC Upper Shell Sample Containment Isolation Inside NM-210M SG IC Biowdown Line Sample Containment Isolation Inside 210 20 1 NM-2118# SG IC Sample Hdr Containment Isolation Outside 20 1 NM-217B# SG ID Upper Shell Sample Containment Isolation Inside NM-220B# SG ID Blowdown Line Sample Containment Isolation Inside 210 NM-221M SG ID Sample Hdr Containment Isolation Outside 310 Note 1: Upon capping of penetrations associated with deletion of UHI, these specifications are no longer applicable.

TABLE 16.6.2-1 (Page 4 of 8) UNIT 1 CONTAINMENT ISOLATION VALVES MAXIMUM VALVE NUMBER FUNCTIO _N IS0tATION TIME (s) 1. Phase "A" Isolation (Continued) NV-ISB Letdown Containment Isolation Outside <10 NV-89A NC Pumps Seal Return Containment Isolation Inside 210 NV-918 NC Pumps Seal Return Containment Isolation Outside 210 NV-314B# Charging Line Containment Isolation Outside 310 NV-11A 45 gpm Letdown Orifice Outlet - Containment Isolation $10 NV-13A 75 gpm Letdown Orifice Outlet - Containment Isolation 110 NV-10A High Pressurizer Letdown Orifice Outlet - Containment Isolation <10 NV-872A Standby Makeup Pump to RCS seals 310 RF-389B Interior Fire Frotection Containment Hose Rack Isolation Valve -<5 (Outside Containment) RF-447B Reactor Building Sprinklers Containment Isolation Valve $5 (Outside Containment) VB-83B -Breathing Air Unit 1 Containment Isolation 110 VY-18B** Containment H, Purge to Annulus Inside Containment Isolation 510 VY-17A** Containment H, Purge to Annulus Outside Containment Isolation $10 VY-ISB** Containment H, Purge Blower Outlet, Containment Isolation (Outside) SIO VI-312A RB Isolation Valve for VI Supply to annulus Vent. 110 VP-1B** Upper Containment Purge Supply #1 Outside Isolation $5 VP-2A** Upper Containment Purge Supply #1 Inside Isolation 15 VP-38** Upper Containment Purge Supply #2 Outside Isolation 15 VP-4A** Upper Containrent Purge Supply #2 Inside Isolation 15 VP-6B** Lower Containment Purge Supply #1 Outside Isolation 15 VP-7A** Lower Containment Purge Supply #1 Inside Isolation 15 VP-88** Lower Containment Purge Supply #2 Outside Isolation 15

O TABLE 16.6.2-1 (Pace 5 of 8) UNIT 1 CONTAINMENT ISOLATION VALVES MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) 1. Phase "A" Isolation (Continued) VP-9A** Lewer Containment Purge Supply #2 Inside Isolation $5 VP-10A** Upper Containment Purge Exhaust #1 Inside Isolation <5 VP-11B** Upper Containment Purge Exhaust #1 Outside Isolation 25 VP-12A** Upper Containment Purge Exhaust #2 Inside Isolation 55 VP-13B** Upper Containment Purge Exhaust #2 Outside Isolation SS VP-15A** Lower Containment Purge Exhaust #1 Inside Isolation $5 VP-168** Lower Containment Purge Exhaust #1 Outside Isolation $5 VP-17A** Incore Instru. Room Purge Supply Inside Isolation <5 VP-18B** Incore Instru. Room Purge Supply Outside Isolation 25 VP-19A** Incore Instru. Room Purge Exhaust Inside Isolation 35 VP-20B** Incore Instru. Room Purge Exhaust Outside Isolation 55 VQ-2A** Containment Air Release Inside Isolation <5 VQ-3B** Containment Air Release Outside Isolation 25 VQ-ISB** Containment Air Addition Outside Isolation 25 VQ-16A** Containment Air Addition Inside Isolation 35 VS-54B Unit 1 Containment Header Outside Isolation $15 WL-807B# NCDT Pumps Discharge Outside Containment Isolation $10 WL-805A# NCDT Pumps Discharge Inside Containment Isolation <10 20 WL-450A NCDT Vent Inside Containment Isolation 120 WL-451B NCOT Vent Outside Containment Isolation 1 WL-825A#** RB Sump Pump Discharge Inside Containment Isolation 310 WL-827B#** RB Sump Pump Discharge Outside Containment Isolation $10 YM-119B Demin. Water Containment Outside Isolation $10

0 TABLE 16.6.2-1 (Page 6 of 8) UNIT 1 CONTAINMENT ISOLATION VALVES MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) 2. Phase "B" Isolation KC-338B# NC Pump Supply Header Pent. Isolation (Outside) 540 KC-424B# NC Pumps Return Hdr. Pent. Inside Isolation 140 KC-425A# NC Pumps Return Hdr. Outside Isolation 140 RN-437B Supply to NC Pumps and LCVU Supply Outside Containment Isolation $60 RN-484A Return from NC Pumps and LCVU Return Inside Containment Isolation 160 RN-487B Return from NC Pumps and LCVU Return Outside Containment Isolation 160 RN-404B Supply to Upper Containment Supply Ventilation Units Containment 510 Isolation (Outside) RN-429A Return from Upper Containment Ventilation Units Containment Isolation $10 (Inside) RN-432B Return from Upper Containment Ventilation Units Containment Isolation 110 (Outside) VI-77B Instrument Air Containment Outside Isolation $10 SM-1 # Main Steam ID Isolation <5 SM-3 # Main Steam IC Isolation 25 SM-5 # Main Steam IB Isolation 25 SM-7 # Main Steam 1A Isolation 25 SM-9 # Main Steam ID Isolation Bypass Ctrl. 25 SM-10 # Main Steam IC Isolation Bypass Ctr1. 25 SM-11 # Main Steam IB Isolation Bypass Ctrl. 75 SM-12 # Main Steam 1A Isolation Bypass Ctrl. 35 SV-19 # Main Steam 1A PORY <5 SV-13 # Main Steam IB PORV 25 SV-7 # Main Steam IC PORV 25 SV-1 # Main Steam ID PORV 35

3 TABLE 16.6.2-1 (Page 7 of 8) UNIT 1 CONTAINMENT ISOLATION VALVES NAXIMUM VALVE NUMBER FUNCTION IS0t.ATION TIME (s) 2. Phase "B" Isolation (Continued) WL-867A** Containment Vent Unit Drains Inside Containment Isolation <10 WL-869B** Containment Vent Unit Drains Outside Containment Isolation 310 3. Manual NC-141 NC Pump H, Drain Tank Pump Discharge N.A. NC-142 NC Pump H, Drain Tank Puang Discharge N.A. NI-3 Boron Injection Tank Line to Cold legs N.A. FW-11 Refueling Water Pump Suction N.A. FW-13 Refueling Water Pump Suction N.A. CF-91# Feedwater IA N.A. CF-93# Feedwater IB N.A. CF-95# Feedwater IC N.A. CF-97# Feedwater ID N.A. CA-121# Aux. Feedwater IA N.A. BW-1# Aux. Feedwater IA N.A. CA-120# Aux. Feedwater IB N.A. BW-26# Aux. Feedwater IB N.A. CA-119# Aux. Feedwater IC N.A. BW-17# Aux. Feedwater IC N.A. CA-118# Aux. Feedwater ID N.A. BW-10# Aux. Feedwater ID N.A. SM-16# Main Steam 1A N.A. SM-73#* Main Steam 1A N.A. SM-105# Main Steam 1A N.A. SM-121# Main Steam 1A N.A. SM-143# Main Steam 1A N.A. SM-72#* Main Steam IB N.A. SM-1048 Main Steam IB N.A.

O TABLE 16.6.2-1 (Page 8 of 8) UNIT 1 CONTAINMENT ISOLATION VALVES MAXINUM VALVE NUMBER FUNCTION ISOLATICH TIME (s) 3. Manual (Continued) SM-120# Main Steam IB N.A. SM-142# Main Steam IB N.A. SA-1# Main Steam IB N.A. SM-17# Main Steam 1B N.A. SM-18# Main Steam IC N.A. SM-71#* Main Steam IC N.A. SM-103# Nin Steam IC N.A. SM-119# Main Steam IC N.A. SM-141# Main Steam IC N.A. SA-4# Main Steam IC N.A. SM-19# Main Steam ID N.A. SM-70#* Main Steam ID N.A. SM-102# Main Steam ID N.A. SM-118# Main Steam ID N.A. SM-140# Main Steam ID N.A. WE-20* Cont Bldg Supply Isol N.A. WE-22* Cont Bldg Supply Isol N.A. WE-56* Cont Bldg Supply Isol N.A. FW-4* Re'Jueling Water N.A. NV-862#* Pritssurizer Auxiliary Spray ND Outside Containment N.A. WLA-21#* St.eam Generator Drain Pump Discharge Outside Containment Isolation N.A. WLA-24#* Ss.eam Generator Drain Pump Discharge Outside Containment Isolation N.A. TABLE NOTATIONS

• May be opened on an intemittent basis under administrative control.
  • Valve also receives a Hign Radiation (H) and/or a High Relative Humidity isolation signal.

1. Not subject to Type C leakage tests.

NOTE: Times are for valve operation only, and do not include any sensor response or circuit delay times. See Specification 3/4 3.2 for system actuation response times.

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o TABLE 16.6.2-2 (page 2 of 8) UNIT 2 CONTAINMENT ISOLATION VALVES MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) 1. Phase "A" Isolation (Continued) KC-305B# Excess Letdown Hx Supply Containment Isolation (Outside) 520 KC-315B# Excess Letdown Hx Return Header Containment Isolation (Outside) <20 KC-320A# NCDT Hx Supply Hdr Containment Isolation (Outside) 320 KC-332B# NCDT Hx Return Hdr Containment Isolation (Inside) <20 KC-333A# NCDT Hx Return Hdr Containment Isolation (Outside) 320 KC-429B RB Drain Header Inside Containment Isolation ~<10 KC-430A RB Drain Header Outside Containment Isolation 510 NB-2608 Reactor Makeup Water Tank to Flush Header $10 NC-53B Nitrogen to Pressurizer Relief Tank #1 Containment Isolation Outside $10 NC-54A Nitrogen to Pressurizer Relief Tank #1 Containment Isolation Inside $10 NC-56B RMW Pump Disch Cont Isolation <10 NC-1958 NC Pump Motor Oil Containment Isolation Outside 310 NC-196A NC Pump Motor Oil Containment Isolation Inside $10 NF-228A Unit 2 Air Handling Units Glycol Supply Containment Isolation Outside $10 NF-233B Unit 2 Air Handling Units Glycol Return Containment Isolation Inside $10 NF-234A Unit 2 Air Handling Units Glycol Return Containment Isolation Outside $10 NI-47A Accumulator N, Supply Outside Containment Isolation $10 NI-95A Test Hdr Inside Containment Isolation <10 NI-968 Test Hdr Outside Containment Isolation 210 NI-120B Safety Injection Pump to Accumulator Fill Line Isolation 310 NI-122B# Hot Leg Injection Check ENI124, 2NI128 Test Isolation $10 NI-154B# Hot leg Recirculation Check 2NI125, 2NI129 Test Isolation $10 NI-255B UHI Check Valve Test Line Isolation <1 NI-258A UHI Check Valve Test Line Isolation 31 Note 1 NI-264B UHI Check Valve Test Line Outside Containment Isolation $1 Note 1: Upon capping of penetrations associated with deletion of UHI, these specifications are no longer applicable.

B TABLE 16.6.2-2 (Page 3 of 8) UNIT 2 CONTAINMENT ISOLATION VALVES MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) 1. Phase "A" Isolation (Continued) hNI-266A UHI Check Valve Test Line Inside Containment Isolation $10 Note 1 U I-267A UHI Check Valve Test Line Inside Containment Isolation <1 NI-153A# Hot Leg Injection Check NI156, NI159 Test Isolation 210 NM-3A Pressurizer Liquid Sample Line Inside Containment Isolation $10 NM-6A Pressurizer Steam Sample Line Inside Containment Isolation 510 NM-7B Pressurizer Sample Header Outside Containment Isolation $10 NM-22A NC Hot Leg A Sample Line Inside Containment Isolation $10 NM-25A NC Hot leg C Sample Line Inside Containment Isolation 510 NM-26B NC Hot Leg Sample Hdr Outside Containment Isolation $10 NM-72B NI Accumulator 2A Sample Line Inside Containment Isolation $10 NM-758 NI Accumulator 28 Sample Line Inside Containment Isolation $10 NM-78B NI Accumulator 2C Sample Line Inside Containment Isolation <10 NM-81B NI Accumulator 2D Sample Line Inside Containment Isolation 310 NM-82A NI Accumulator Sample Hdr Outside Containment Isolation <10 NM-187A# SG ZA Upper Shell Sample Containment Isolation Inside 210 NM-190A# SG 2A Blowdown Line Sample Containment Isolation Inside 310 NM-191B# SG 2A Sample Hdr Containment Isolation Outside $10 NM-197B# SG 2B Upper Shell Sampie Containment Isolation Inside <10 NM-200B# SG 28 Blowdown Line Sample Containment Isolation Inside 310 NM-201A# SG 28 Sample Hdr Containment Isolation Outside <10 NM-207A# SG 2C Upper Shell Sample Containment Isolation Inside 310 NM-210A# SG 2C Blowdown Line Sample Containment Isolation Inside $10 NM-211B# SG 2C Sample Hdr Containment Isolation Outside <10 NM-217B# SG 2D Upper Shell Sample Containment Isolation Inside 310 NM-220B# SG 2D Blowdown Line Sample Containment Isolation Inside 510 NM-221A# SG 20 Sample Hdr Containment Isolation Outside $10 Note 1: Upon capping of penetrations associated with deletion of UHI, these specifications are no longer applicable.

TABLE 16.6.2-2 (Page 4 of 8) UNIT 2 CONTAINMENT ISOLATION VALVES MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) 1. Phase "A" Isolation (Continued) NV-ISB Letdown Containment Isolation Outside <10 NV-89A NC Pumps Seal Return Containment Isolation Inside <10 NV-91B NC Pumps Seal Return Containment Isolation Outside ~510 NV-314B# Charging Line Containment Isolation Outside 510 NV-11A 45 gpm Letdown Orifice Outlet - Containment Isolation $10 NV-13A 75 gpm Letdown Orifice Outlet - Containment Isolation $10 NV-10A High Pressurizer Letdown Orifice Outlet - Containment Isolation $10 NV-872A Standby Makeup Pump to RCS seals 510 RF-389B Interior Fire Protection Containment Hose Rack Isolation Valve -<5 (Outside Containment) RF-4478 Reactor Building Sprinklers Containment Isolation Valve -<5 (Outside Containment) VB-83B Breathing Air Unit 2 Containment Isolation $10 VY-18B** Containment H, Purge to Annulus Inside Containment Isolation $10 VY-17A** Containment H, Purge to Annulus Outside Containment Isolation $10 VY-ISB** Containment H, Purge Blower Outlet, Containment Isolation (Outside) 510l VI-312A RB Isolation Valve for VI Supply to annulus Vent. 510 VP-1B** Upper Containment Purge Supply #1 Outside Isolation 55 VP-2A** Upper Containment Purge Supply #1 Inside Isolation 55 VP-3B** Upper Containment Purge Supply !2 Outside Isolation $5 VP-4A** Upper Containment Purge Supply #2 Inside Isolation SS VP-6B** Lower Containment Purge Supply #1 Outside Isolation 55 VP-7A** Lower Containment Purge Supply #1 Inside Isolation $5 VP-88** Lower Containment Purge Supply #2 Outside Isolation 55

TABLE 16.6.2-2 (Page 5 of 8) UNIT 2 CONTAINMENT ISOLATION VALVES MAXIP:UM VALVE NUMBER FUNCTION ISOLATION TIME (s) 1. Phase "A" Isolation (Continued) VP-9A** Lower Containment Purge Supply #2 Inside Isolation 55 VP-10A** Upper Containment Purge Exhaust #1 Inside Isolation 55 VP-11B** Upper Containment Purge Exhaust #1 Outside Isolation 55 VP-12A** Upper Containment Purge Exhaust #2 Inside Isolation 55 VP-13B** Upper Containment Purge Exhaust #2 Outside Isolation $5 VP-15A** Lower Containment Purge Exhaust #1 Inside Isolation 55 VP-16B"* Lower Containment Purge Exhaust #1 Outside Isolation SS VP-17A** Incore Instru. Room Purge Supply Inside Isolation $5 VP-188** Incore Instru. Room Purge Supply Outside Isolation SS VP-19A** Incore Instru. Room Purge Exhaust Inside Isolation 55 VP-20B** Incore Instru. Room Purge Exhaust Outside Isolation 55 VQ-2A** Containment Air Release Inside Isolation <5 VQ-38** Containment Air Release Outside Isolation 25 VQ-ISB** Containment Air Addition Outside Isolation 25 VQ-16A** Containment Air Addition Inside Isolation' 35 VS-548 Unit 2 Containment Header Outside Isolation $15 WL-807B# NCDT Pumps Discharge Outside Containment Isolation 510 WL-805A# NCDT Pumps Discharge Inside Containment Isolation 510 WL-450A NCDT Vent Inside Containment Isolation <10 WL-451B NCDT Vent Outside Containment Isolation 210 WL-825A#** RB Sump Pump Discharge Inside Containment Isolation 310 WL-827B#** RB Sump Pump Discharge Outside Containment Isolation $10 YM-119B Demin. W'at er Containment Outside Isolation $10

Q TABLE 16.6.2-2 (Page 6 of 8) UNIT 2 CONTAINMENT ISOLATION VALVES MAXIM' M J VALVE NUMBER FUNCTION ISOLATION TIME (3) 2. Phase "B" Isolation KC-3388# NC Pump Supply Header Pent. Isolation (Outside) 140 KC-424B# NC Pumps Return Hdr. Pent. Inside Isolation 140 KC-425A# NC Pumps Return Hdr. Outside Isolation 140 RN-437B Supply to NC Pumps and LCVU Supply Outside Containment Isolation 160 RN-484A Return from NC Pumps and LCVU Return Inside Containment Isolation 160 RN-487B Return from NC Pumps and LCVU Return Outside Containment Isolation 160 RN-404B Supply to Upper Containment Supply Ventilation Units Containment $10 Isolation (Outside) RN-429A Return from Upper Containment Ventilation Units Containment Isolation 110 (Inside) RN-432B Return from Upper Containment Ventilation Units Containment Isolation $10 (Outside) VI-77B Instrument Air Containment Outside Isolation 110 SM-1 # Main Steam 2D Isolation <5 SM-3 # Main Steam 2C Isolation 25 SM-5 # Main Steam 2B Isolation 25 SM-7 # Main Steam 2A Isolation 75 SM-9 # Main Steam ZD Isolation Bypass Ctr1. 35 SM-10 # Main Steam 2C Isolation Bypass Ctr1. SS SM-11 # Main Steam 2B Isolation Bypass Ctr1. 55 l SM-12 # Main Steam 2A Isolation Bypass Ctr1. 15 l SV-19 # Main Steam 2A PORV <5 i SV-13 # Main Steam 2B PORV 25 SV-7 # Main Steam 2C PORV 25 2_5 SV-1 # Main Steam 2D PORV a

TABLE 16.6.2-2 (Page 7 of 8) UNIT 2 CDNTAINMENT ISOLATION VALVES MulMUM VALVE NUMBER FUNCTION ISOLATION TIME (s) 2. Phase "B" Isolation (Continued) WL-867A** Containment Vent Unit Drains Inside Containment Isolation 110 WL-869B** Containment Vent Unit Drains Outside Containment Isolation $10 3. Manual NC-141 NC Pump H, Drcin Tank Pump Discharge N.A. NC-142 NC Pump H, Drain Tank Pump Discharge M.A. NI-3 Boron Injection Tank Line to Cold ' gs N.A. FW-11 Refueling Water Pump Suction M.A. FW-13 Refueling Water Pump Suction N.A. CF-91# Feedwater 2A N.A. CF-93# Feedwater 28 N.A. CF-95# Feedwater 2C N.A. CF-97# Feedwater 2D N.A. CF-121# Aux. Feedwater 2A N.A. BW-1# Aux. Feedwater 2A N.A. CA-120# Aux. Feedwater 28 N.A. BW-26# Aux. Feedwater 28 N.A. CA-119# Aux. Feedwater 2C N.A. BW-17# Aux. Feedwater 2C N.A. CA-118# Aux. Feedwater 2D N.A. BW-10# Aux. Feedwater 2D N.A. SM-16# Main Steam 2A N.A. SM-73# Main Steam 2A N.A. SM-10$# Main Steam 2A N.A. SM-121# Main Steam 2A N.A. SM-143# Main Steam 2A N.A. SM-72#* Main Steam 28 N.A. SM-1048 Main Steam 28 N.A.

e O TABLE 16.6.2-2 (page 8 of 8) UNIT 2 CONTAINMENT ISOLAllON VALVES MAXIMUM VALVE NUMBER FUNCTION ISOLATION TIME (-) 3. Manual (Continued) SM-120# Main Steam 28 N.A. SM-142# Main Steam 28 N.A. SA-I# Main Steam 2B N.A. SM-17# Main Steam 28 N.A. SM-18# Main Steam 2C N.A. SM-71#* Main Steam 2C N.A. SM-103# Main Steam 2C N.A. SM-119# Main Steam 2C N.A. SM-141# Main Steam 2C N.A. SA-4# Main Steam 2C N.A. SM-19# Main Steam ZD N.A. SM-70#* Main Steam ZD N.A. SM-102# Main Steam 20 N.A. SM-118# Main Steam 2D N.A. SM-1408 Main Steam 2D N.A. WE-20* Cont Bldg Supply Isol N.A. WE-22* Cont. Bldg Supply Isol N.A. WE-56* Cont Bldg Supply Isol N.A. FW-4* Refueling Water N.A. NV-862#* Pressurizer Auxiliary Spray ND Outside Containment N.A. WLA-21#* Steam Generator Drain Pump Discharge Outside Containment Isolation N.A. WLA-24#* Steam Generator Drain Pump Discharge Outside Containment Isolation N.A. TABLE NOTATIONS

• May be opened on an intermittent basis under administrative control.
  • Valve also receives a High Radiation (H) and/or a High Relative Humidity isolation signal.

1. Not subject to Type C leakage tests.

NOTE: Times are for valve operation only, and do not include any sensor response or circuit delay times. See Specification 3/4 3.2 for system actuation response times.

, v 5 ic 4 ,s.. .e' 4 1 1 1 4 ).~,~ 1 J. 7 ii r' ATTACSHWT Ill 1 D18CUS$1001. NO SIGNIFICANT RAZARDS ANALYSIS AND RNVIR000GMTAL IMPACT STATBENT '^ l . i. b [. .i ..v., d 4 p j g i W 'I 1 ,I ti / i i i i ~ t 4 6 Y i.I i s 4 L ' 4 6' 4 s I .):.r y - T, 4 I s. $ !( [ 3,i. t i. . ? y r a r .I l i. - 's = j, . t ,t .j 7-e h-- twerg ea-wv.$ q.p ytt 7 N (*yar.-y *pq rgym m 9g ygg. 4 g.am g gaw4,9Q..,9.m9a.p.s+ig' 19 e 'h Wh @, - h4 ' 6 4 --rh(- $-fa..e di 4 g "+Mit r g.-1-g

it o e DISCUSSION. NO SIGNIFICANT RA7.ARDS AMALYSIS AND ENV1kONMENTAL IMPACT S'IATEMENT The proposed amendment relocates Catawba Nuclear Station Technical Specification Table 3.6-1. Secondary Containment Bypass Leakage paths. Table 3.6 2a. Unit 1 Containment Isolation Valves..and Table 3.6-2b. Unit 2 Containment Isolation Valves, to Catawba FSAR Chapter 16. Selected Licensee Commitments (SLC) Manual. The proposed changes to Technical Specifications 1.7. 4.6.1.1. 3.6.1.2. 3.6.3. 4.6.3.1. 4.6.3.2. 4.6.3.3, and Basis Section 3/4.6.4 reflect the relocation of Tables 3.6-1, 3.6-2a. and 3.6-2b to the FSAR and clarify the existing Specifications. The proposed relocation of Technical Specification Tables 3.6-1, 3.6-2a and 3.6-2b is an aduinistrative change because all the information in these tables is contained in proposed FSAR Table 16.6.1-1. Secondary Containment Bypans Leakage paths. Table 16.6.2-1 Unit 1 Containment Isolation Valves, and Table 16.6.2-2 Unit 2 Containment Isolation Valves. A copy of the SLC manual will le maintained at the control room, and the proposed TSAR Tables will be readily available to the operators. The proposed changes would not result in any change to the intent or requirements of any Limiting Condition for Operation or Surveillance Requirament. Technical Specification Tables 3.6 2a and 3.6-2b permit the opening of certain manual valves during operation as long as they are administrative 1y controlled. Operatior, of these valves allows testing maintenance, and other activities. The proposed change and footnote to Surveillance Requirement 4.6.1.1 supports the removal of TS Tables 3.6-2a and 3.6-2b. These proposed changes do not result in any change to existing requirements. proposed changes to Technical Specifications 4.6.1.1, 3.6.1.2. 3.6.3 4.6.3.1. 4.6.3.2, and 4.6.3.3 delete references to Technical Specification Tables 3.6-1, 3.6-2a. and 3.6-2b to reflect the relocation of these Tables into Catawba TSAR Chapter 16. These revisions do not change the intent of the Technical Specifications or make any requirement less restrictive. The additions of the words " containment" and/or " containment isolation" to Technical Specification Surveillance Requirements 4.6.3.1. 4.6.3.2 and 4.6.3.3 are also an administrativo change. These proposed changes clarify the existing Specification and are int. ended to avoid possible confusion as to the valves covered by Technical Specification 3/4.6.3. The intent of the Specification will not be changed as a result of the additional wording.

c 1 ,o j Page 2 o I The proposed changes to Basis Section 3/4.6.3 reflect the relocation of Tables 3.6-1, 3.6 2a, and 3.6-2b to the SbC manual. The changes to the Basis also indicate that future changes to the proposed SbCs would be evaluated in accordance with the process described in 10 CFR 50.59 to determine whether an unreviewed safety question is involved. Changes determined to involve an unreviewed safety consideration will require prior NRC approval. Changes deterained not to involve an unreviewed safety consideration could be pursued without prior NRC approval as revisions to the FSAR. A report of such changes, including a summary of the safety evaluation of each, would be sutaitted annually to the NRC pursuant to 10 CFR 50.59. All changes made to the FSAR would also be submitted to the NRC with the annual FSAR update, or more frequently, as required by 10 CFR 50.71. The NRC has determined as part of its implementing policy for Technical Specifications improvements that the subject penetrations and valves are appropriate for this process. A similar change, for McGuire Nuclear Station, deleting corresponding tables from the TS and adding them to the McGuire FSAR has already been approved. 10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the proposed amendment vould not:

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

2) Create the possibility of a new or different kind of accident from any accident previously evaluatedt or

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

The proposed relocation of Tables 3.6-1, 3.6-2a, and 3.6-2b to the FSAR does not involve an increase in the probability or consequences of any previously evaluated accident. The proposed amendment does not change any Technical Specification requirement. The relocation of these Tables is an administrative change which doss not impact previous assumptions and conclusions of FSAR accident analysis. Relocation of these Tables to the FSAR does not adversely affect containment leakage or integrity. The proposed relocation of Tables 3.6-1, 3.6-2a, and 3.6-2b does not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed amendment is administrative in nature and would not result in changes to the design or operation of Catawba Nuclear Station. The relocation of these Tables does not create any new accident scenarios. The proposed telocation of Tables 3.6-1, 3.6-2a, and 3.6-2b does not involve a significant reduction in a margin of safety. The transfer of the Technical Specification Tables to the FSAR is an administrative matter which does not affect margins of safety. The allowed containnent leak rate is unaffected, and there is no reduction in any margin of safety.

e' (,5 A' Page 3 The proposed amendments to Technical Specifications 4.6.1.1, 3.6.1.2, 3.6.3. 4.6.3.1. 4.6.3.2, and 4.6.3.2 are administrative changes which do not involve any significant hazards consideration. These changes have been itemized and described previously in this analysis. These are purely administrative changes which clarify the Technical Specifications and reflect the relocation of Tables 3.6-1, 3.6-2a. and 3.6 2b t o the TSAR. These changes do not involve an increase in the probability or consequences of an accident previously evaluated or create the possibility of a new or different kind of accident from any accident previously evaluated. These changes do not involve any reduction in a margin of safety. Based on the preceding discussions. Duke Power Company concludes that the proposed amendment does not involve a significant hazards consideration. F.nvironment al Impact The proposed Technical Specification change has been reviewed against the criteria of 10 CPR 51.22 for environmental considerations. As shown above, the proposed change does not involve a significant hazards consideration, nor increases individual or cumulative occupational radiation exposures. Based on this, the proposed amendment meets the criteria given in 10 CFR 51.22(c)(9) for a categorical exclusion from the requirements for an F.nvironmental Impact Statement.}}