•

•

• ,,---

Document Control Desk LR-N990336

ATTACHMENT 3

SALEM UNIT 1

• MARKED UP TECH SPEC PAGES

The following Technical Specifications for Facility Operating License No. DPR-70 are affected by this change request: ·

Technical Specification

INDEX

2.2.1

3/4.1.1.1

3/4.1.2.6

3/4.1.3.4

3/4.1.3.5

3/4.2.1

3/4.3.1.1

3/4.3.2.1

3/4.3.3.1

3/4.3.3.7

3/4.3.3.8

3/4.3.3.9

3/4.3.4

3/4.4.1.4

3/4.4.5

9909070073 990825 PDR ADOCK 05000272 P PDR

'\ I

Page

I, Ill, V, VI, VIII, IX, XI, XII, XIII, XIV, XV, XVII, and XVIII

2-6 2-7

3/4 1-1

3/4 1-16

3/4 1-22

3/41-23

3/4 2-2 3/42-3

3/4 3~12

3/4 3-22 3/4 3-34

3/4 3-35 3/4 3-36a 3/4 3-37 3/4 3-38a

3/4 3-53 3/4 3-56

3/4 3-63

3/4 3-68

.... ~314-3-71

3/4 4-3b

3/44-8

I

•

Document Control Desk LR-N990336

ATTACHMENT 3

The following Technical Specifications for Facility Operating License No. DPR-70 are affected by this change request: (continued)

Technical Speciffcation

3/4.4.6.1

3/4.4.6.3

3/4.4.8

3/4.4.9.3

3/4.4.10.1

3/4.5.3

3/4.5.5

3/4.6.1.1

3/4.6.1.2

3/4.6.1.6

3/4.6.1.7

3/4.6.2.2

3/4.6.3.1

3/4.7.9

3/4.7.10

3/4.8.2.3

3/4.9.7

3/4.9.8

3/4.9.10

3/4.10.1

3/4.11.2

Page

3/4 4-14.

3/4 4-16a 3/4 4-16b 3/4 4-16c

3/4 4-20

3/4 4-31

3/4 4-32

3/4 5-6

3/4 5-7

3/4 6-1

3/4 6-2

3/46-8

3/4 6-8a

3/4 6-10

3/4 6-13

3/4 7-31

3/4 7-33

3/4 8-8

3/4 9-7

3/4 9-8

3/4 9-10

3/4 10-1

3/4 11-10

•

•

•

Document Control Desk LR-N990336

ATTACHMENT 3

The following Technical Specifications for Facility Operating License No. DPR-70 are affected by this change request: (continued)

Technical S~ec.ification Page

B 3/4.4.8 B 3/4 4-5

B 3/4.4.9 B 3/4 4-6

B 3/4.7.9 B 3/4 7-6

5.4.1 5-4

6.12.2 6-28

•

•

DEFINITIONS

SECTION .. 1.0 DEFINITIONS

DEFINED TERMS ACTION .... AXIAL FLtJX DIFFERENCE CHANNEL CALIBRATION CHANNEL CHECK . . . . CHANNEL FUNCTIONAL TEST CONTAINMENT INTEGRITY CORE ALTERATION . . . . CORE OPERATING LIMITS REPORT QOSB EQUIVALENT I-131 E-AVERAGE DISINTEGRATION ENERGY ENGINEERBI> SAFETY FEATORB RESPONSE TIMB FREQUENCY NOTATION . . . . . . . . FULLY WITHDRAWN . . . . . . . . . GASEOUS RAOWASTE TREATMENT SYSTEM IDENTIFIED LEAKAGB . . . MEMBER(S) OP THB PUBLIC .. OFFSITE OOSB CALCULA~:nt--fBIH\l:AL (OOCM) OPERABLB - OPERABI . OPERATIC~ MOOB • • M 0 'D f£ PHYSICS TESTS PRESSURE BOUNDARY LBJ~~ PROCESS CONTROL PROGRAM PURGE-PURGING . . . . . QUADRANT POWER TILT RATIO RATED THERMAL POWER ..... REACTOR TRIP SYSTEM RESPONSB TIMB REPORTABLB EVENT SHUTDOWN MARGIN SITE BOUNDARY SOLIDIFICATION . SOURCB CHECK . • STAGGBRBI) TEST BASIS THERMAL POWD UNIDENTIFIED LBAUGS UNRESTRICTED ARD • • • VENTILATION BXBAtJST TRD'l'MD'l' SYSTBM VENTING ....••.•......

SALEM - UNIT 1 I

·-

-·

l-l l-l l-l l-l l-l l-l l-2 l-2 l-2 l-2 l-3 l-l l-l 1-3 1-3 1-3 l-4 l-4 1-4 l-4 1-S l·S,, 1-S l-5 l-5 l-5 l-6 l-6 l-6 l-6 1-6 1-6 l-6 1-7 1-7 1-7 1-7 1-7

Amendment No. 201

•

•

~

. ;~:f!ri!:«i ;qHp!';'!ONS Ml QP3'!;;~ ~ StJ,Vt;;,;.n.~Cl a!og;J~S

SiwQI

U!t...,g MNG•UU;I .. wrnyxn comgL sxs-msf uu

3/4.l.l &OIATIOK CONT1lOL

sm.&c:dovft ~r11n • T > zoo•r. Shuc:down Kar1in • T•v1 s zoo•r loroa Bll~•iaa. av1 ~oderac:ar T..,eracur• Co.f f1c1enc !tin~ T....-racura far C:ic:icalicy

3/4. l. 2 IOL\TIOll SYSTDIS

Flow Padw • Shuc:dovft Flaw Pacn. • O,•rac:int Ch&r1iq "- • Shuc:doft Ch&r11q Pump • O,•rac:in1 Ion• A.ci' Trwfer ,...,. · SlNcuua lol'ic Acid TH11af1r .,,...,. · 0,H'Al1q lorac:ad Vac:ar SO\ll'cea • Shue:.,._ lorac:ad Vac:er SO\ll'cea • Operac:ina

3/4. l. l ltDVAIU COlftl.Ot. ASSIDUU

GrCN1J Keipe Poeic:ioa Indicac:inc Sy1c: .. • O,.racinc Poaic:ion Indicac:inc Sy1c:1.. • Shue:.,._ llo4 Dl'o, Tlae Slluc:dowa lod Imerc:ioa Uaic: Conc:rol loci Iuerc:ian c.iaic.

SA1.lll • U1ltT 1 III

• I

~

3/4 O·t

3/'6 l·l

~ 3/'6 l·5 3/'6 l-6

3/li. 1·7 l/4 l·I l/4 l·lO 3/4 l· u ~ 3'/4 1· 13 Q _./ l/4 1·14 3/4 1·16

..

3/4 l·U 3/4 l· l9 3/4 1·20 3/4 1·2l 3/4 l.·22

. 3/4 1.. 23

~I tr DC llo. lOl

I .

•

•

llmll

LIMlTillQ c:olmrr?Olll roa OPIRATIOM AHD SUl.VIILLANCE REQUIUMIHTS ..

SECTIQM fASil

UJ....i

3/4.4.l -~R COOLANT t.OOPS,Altillf&--ftiet;llllf!r--e9ee'l~~'fi'

\:9tazeup mid Po .. r eperattozJ .iJ.o~~A:i....Q~G~A!•~iJ ........ l/4

Hot Shutdown Cold Shutdown

3/4.4.2.l SAFSTY VALVES • SHOTDONll

3/4.4.2.2 SAFETY VALVES • OPERATING .

3/4.4.3 RELIEF VALVES .

3/4.4.4 PRESSUllIZD .

3/4.4.S STEAM GEHBRATORS

. .

3/4.4.6 REACTOR COOLAH'l' SYSTDI LU~rAGS

DELETm

. ...

.

. .

.

.3/4

.3/4

.l/4 4-4

. 3/4 4-4•

. . 3/4 4-5

. . .3/4 4-6

.3/4 4-7

.3/4 4-14

. 3/4 4-15 ,,.

.3/4 4•16&

3/4.4.8 SPECIFIC: ACTIVITY .........••. 3/4 4-20

3/4.4.9 PRESSURS/TEMPBRATURS LIMITS

Reactor Coolant Syatem Preaaurizer . . . . . . . . . overpr•••ur• Protection Syat... •

3/4.4.10 STllOC'l'UDL nrrscDlITY

ASMll coca Cl••• 1. 2, and 3 component•

3/4.4.11 INTEHTIOllALLY ILAlllC

3/4. 4 .12. HJAD vmrrs- . . .

SALEM • UNIT 1 v

.3/4 4-24

.3/4 4·29

.3/4 4·30

.3/4 4.·32

.3/4 4.-34.

.3/4 t-35

Amendment No.1ao

!.'

•

•

SIC'T!OM

l/t 5

l/t.5.1

l/t.5.Z

J/t.5.J

l/t.5.t

J/t.5.5

l/t,f

l/t,l.l

l/t.1.i

l/t.l.J

l/t.l.t

m•alHCX ;cu '99Lr• sxs™ ,,ccn AC~TOU

secs suasYsTDll - r ... 1so•r

ECCS SualYSTIMI • r .. c 1so•r

SW. IM.nc:TtO• ft.QV . . . . .

Rll'Ull.IHG WATD STOU.GI TAllK

comrmgr sxsmg

cancailulanc tnc_,ricy cancaiamanc t.caka9• . cancaimlmlC Air Lock8 Iacernal Pr•••uz~ . . ,· Air r-...racuz• . . . canca1D119AC SCr\&GCUZal IAc.,ricy eancaimlmlC veac11aciall Sytic.. .

ccmca~c lpny symc.. . Spray Mdiei.,. Sy9c• . . . canca11111mlC cooliail Syac•

ll'JGOI• WlysH• llaccnC ilydnfea IKCMUaUleH

SAUM · UlltT l Vt

..

J/t s-1

J/t S·l

,. J/4·1-1 J/t 1·2 • J/t f·S J/t ,_, J/4 1·7 3/4 l·I l/t ••••

l/4 ,.,

3/4 1·10 3/4 l•ll

3/t l•U

3/4 f•U 3/t l•U

urtnac No. t i8

I

•

•

::N"Cr!::NS FOR OPW!:O~ "-"o Si..~Vt::.:..A.'iCE H:L :?.!.~t."'°:5 ----··-- -- -·· -----··-·--··-···-·· ?.l.Ct -) I:.. 8

)/t..8.3

>. . C • SOUlCtS

~.c. O\str\but\on • Operat\nl .. A.C. O\stt\but\on • Shut4oWft t:5·VoLt O.C. u~sttibut\on • Operatinl t~5-VoLt o.c. Oistr\but\on • Shut4own :s-VoLt o.c. Distribution • Oper1tin1 . 28· · .: o.c. Distribution· Shut4oVft Et.£: :c>.L EQUt?M!Nt ?RO't! . :·:t uEV!CU .

•

v!tt

31:. 8·6 )/lo 8-i 1/'6 8·8 11:. 8-to )/'6 8-tt

"" 8·t1

)/I. 8· l"

,.

\

•

:.'iOEl • -

30AQN CQltC!NTUTtON. . . . . . . . . . . . . .

OEC.U Tt~ •• . . .

3/&.9.l

3/£.9.2

3/4.9.l

3/4.9.4

3/· 9.5 . . . . . . . . . . . . .

OA,_I T'UV!l. • ~J!l. 14.ANQt.t~G .ia!A •

~IStOUA&. ~tl1' ~t'IQVAL ..vtQ COOUllT CI~CtJUTtON

All w1c1r ~•v•ls •••••••••••••••• '.. =- ·111c1r \.1ve t • • • • • • • • • • • • • • • c:NT.&t~ICMT il•JRGI ..\ltQ ;iqESSUR!•''AC'Jll' ~El.!EF : SOU it CN SY ST!M • • • • . • • • • • •

JI i. 9. L 0 ..... TU \.£Vil.. • ~E.aCT'Oll V!SSEl.

! / .i. 9 • ll STOUGI ilOQt. ·~ Ttlt 1-~11.. • • •

J/4,9.~2 ~J!l. ~MOt.Utl Aa!A V!NTtUTtCN SYST!M.

. . . . . J/4.10.Z ~au, ~EIGHT, :~st~TtCN ..\HQ 11ow1a

JtS'T1'19UTtON \.t~tTS • • ••• . . . . . . .

I e e •

J,'l ,.;

3/ l ~=-z

J;l • 4 • ... ~ ! ,' l ... -·

• 9ASIS

SIC'T'!ON

3/&.0

l/&.l

l/&.1.1

l/&.1.2

• l/&.1.l

3/& .z. l/&.Zel

l/&.Z.Z .,.. 3/&.Z.l

3/&.2.&

l/&.2.5

•

•

Ul•~ICAltLtTl ••••••• • • e • o • • • ~ • • • • ,

• • • • • • • • • • • • • • • • •

IOIATtQI STSTIJ'S • • • • • • • • • • • • • • • • • • •

lllOYAl'91 CQNTI01. WGe\.US ••••• • e • • • • • • •

MIAT I .... QlWB; 'iCfCS_.--L .uG f/I uJ''\ ~t:llAL.. pe~ ~~ EJ(T'MJUT *IT QtMdl. r~ A..,.. • • • • • • • •

ouAGUIT' UT o• 'UAICTllS • • • • • • • • • • • • • • • • • • • •

HGI -I l/& Q.~

' l/& l·l I l/& L·l .

I 3/& l·' ,.

~ I l/& z.A. .,.-....__.,·/

I/&~\ I l/&;t.J ~ )

: ;/ "--- ,•

•

•

!ASES ====:::c:==-= - --.---=========

J, t l l

3. • l .•

l 't."

)/t.t.2

l/t.4.l

l/t.t.t

J/t.t.5

Lt.t.6

l.t.t.7

.-.ONITOlIMG :~S~UMl:N'l'ATtQN

:""..'11.IINS OVIRSPI~ rROT'IC'T:OK

suaoa cooLJ.ltT sxsm

ilEAC'TOR COOIJ.HT :.ooPS ~ coot.ANT ::R~J'U.TtON

SAlrt'Y 'J.Ul/IS

Ut.IIW V.UV'IS

rRS:SStraUD

STEAM ODIUATOlS

il.EAC'TO& COOt.\HT SYSTD UA..11'...\GS

~ E:t.r:'!?>

3. t t 8 Sr!CIF:C ~CTtVITY

1:t.t.~ rRISStrU/TIMJDATVU t.IMITS

J. t. t. l.O ST1lUC'T'J1tAI,, UITIG&%TY

1 ., t. a at.\NX

xt:

a l/ •

I l/4

I l/4

I l/4

.• l/4 t•l.

.I J/4 t·l.a

.I l/4 t·l.a

.• J/4 t•l

.• l/4 4•2

.I l/4 4•l

.I l/4 4·5

.I l/4 t·I

.• l/4 t·l.1

.• lit •·J.1

.I l/4 4•1.7

Amendment: ~o

,.

• BAS BS SBCT:ION PAGB 3/4 5 BMBKGBNCY CORB COOL:ING SYSTBMS (BCCS)

3/4.S.l ACctJMt7LATORS • . . . . . . . . • • • . • . • . .B 3/4 5-l

BCCS SCBSYSTBMS . . . . . . . . . . . . . .B 3/4 5-l

BBLl:'1'& 0 - 13 3/lf s -2.

3/4.S.S RBlnJBL:INQ WATBR STORA.GB TANK (RWST)

3/4.6 CONTAINMBNT SYSTBMS

3/4.6.l l?R:IMARY CONTAINMBNT . . . . . . . . . -· .B 3/4 6-l 3/4.6.2 DBPRBSStJRIZATION AND COOL:INQ SYSTBMS . . .B 3/4 6-3 3/4.6.3 CONTA:rNMBNT ISOLATION VALVBS . . . . . .B 3/4 6-3 3/4.6.4 COMBOST:IBLB GAS CONTROL . . . . . . .B 3/4 6-4

SALBM - CHIT l XUI Amendment No. 101

•

•

BASES

------------------------------------------------------------------------------.. SECTION ~

3/4.7 PLANT SYSTEMS

3/4.7.1 TURBINE CYCLE ••••..••••.....•. 8 3/4 7-1

3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION B 3/4 7-4

3/4.7.3

3/4.7.4

3/4.7.S

3/4.7.6

3/4.7.7

3/4.7.8

3/4.7.9

COMPONENT COOLING WATER SYSTEM

SERVICE WATER SYSTEM

FLOOD PROTECTION • • •

CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM • • • •

AUXILIARY BUILDING EXHAUST AIR FILTRATION SYSTEM • • ·• . •

SEALED SOURCE CONTAMINATION

SNUBBERS

. B 3/4 7-4

B 3/4 7-4

B 3/4 7-5

• • • • • • 0 • B 3/4 7-5

3/4.7.10 CHILLED WATER SYSTEM - -

3/4.8

3/4.8.1 3/4.8.2 3/4.8.3

AUXILIARY BUILDING SUBSYSTEM . . • . . • . •• 8 3/4 7-8

ELECTRICAL POWER SYSTEMS

A. C. SOURCES ••••••••• ·• • • • • • • • B 3/4 8-1 ONSITE POWER DISTRIBOTION SYSTEMS . • • • • B 3/4 8-1 ELECTRICAL EQUIPMENT .. PROTECTIVE DEVICES • • • • 8 3/ 4 8-2 I

SALEM - UNIT 1 ·XIV Amendment No. 212

•

• BASES ============================================================================== SECTION

3/4.9 REFUELING OPERATIONS

B 3/4 9-1 3/4.9.l BORON CONCENTRATION

B 3/4 9-1 3/4.9.2 INSTRUMENTATION

B 3/4 9-1 3/4.9.3 DECAY TIME

B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS '

B 3/4 9;.Y' 3

B 3/4 9-)' 3

B 3/4 9-,7 2

3/4.9.S

3/4.9.6

3/4.9.7

COMMUNICATIONS

MANIPULATOR CRANE

CRANE TRAVEL - SPENT FUEL STORAGE BU,!LDING

B 3/4 97 3 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION

3/4._9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM ............ . B 3/4 9-;¥' 'f

3/4.9.10 WATER LEVEL - REACTOR VESSEL

and AND lf_ 3/4.9.11 STORAGE POOL

B 3/4 9-J/'

3/4.9.12 FUEL HANDLING AREA VENTILATIO~ SYSTEM B 3/4 9-)/ y

3/4.10 SPECIAL TEST EXCEPTIONS

SHUTDOWN MARGIN . . . . . • . • . . • B 3/4 10-1

3/4.10.1

3/4.10.2

3/4.10.3

3/4.10.4

G~OUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS

PHYSICS TESTS

NO FLOW TESTS

SALEM - UNIT 1 xv

B 3/4 10-1

B 3/4 10-1

B 3/4 10-1 ..

Amendment No.192

•

INDEX

DESIGN FEATURES =================.:============================================================ SECTION PAGE

5.1 SITE

Exc~i:_~~on A-re-a-.-----.---,- -.--·-·--- '. ___ '. __ .. __ ._ ........ 5-1 ,.,--Low Population Zone ........ · .--. --;--. ; . -. -·- 5.:'."L_____ --~-

5 {~~a...,....g..,_~G-.... ....._~L~~·· 5-1 ::::::=. __ .

Configuration . Design Pressure and Temperature

5.3 REACTOR CORE

Fuel Assemblies Control Rod Assemblies

5.4 REACTOR COOLANT SYSTEM

Design Pressure and Temperature Volume

5.5 METEOROLOGICAL TOWER LOCATION

5.6 FUEL STORAGE

Criticality Drainage Capacity ..

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT

SALEM - UNIT 1 XVII

-1 5-4

5-4 5-4

·~~'--... ~ . 5-5

\

Amendment No. 59

•

ADMINISTRATIVE CONJ'ROLS

========~==================================~=================s=====~ SECTION

6.1 ?.ESPONSIBILITY

6.2 ORGANIZATI_N

Onsite and Offsite Organizations Facility Staff . . Shift Technical Advisor

6.3 FACILITY STAFF QUALIFICATIONS.

6-1

6-1 6-~ G. 6-7

6-7

6 . 4 TRAINING . . . . . . . . . . . . . . . . . . . . . . . . 6-7

6.5 REVIEW AND AUDIT (THIS SECTION DELETED) . . . . . . . . . 6-8

6.6 REPORTABLE EVENT ACTION

6.7 SAFETY LIMIT VIOLATION

6.8 PROCEDURES AND PROGRAMS

6.9 REPORTING REQUIREMENTS

6.9.l ROUTINE REPORTS

6.9.2 SPECIAL REPORTS

6.10 RECORD RETENTION

6.11 RADIATION PROTECTION PROGRAM

6.12 HIGH RADIATION AREA ..

6.13 PROCESS CONTROL PROGRAM (PCP)

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)

6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS

6.16 ENVIRONMENTAL QUALIFICATION

6-16

6-16

6-17

6-20

6-24 4,J

6-)< 02 s 6-26

6-)< 2 7

6-~ 2g

6-,.M" ~ C\

6-)¥ z. '\

6-pf 3 0

,,

SALEM - UNIT 1 XVIII Amendment No. 192

• IJ. It ... Generater .. ter

. ._.. __ ...,_ ... ••• .. •• t ..

fS. ....n.lt...--.stn CMIMt .....

II. ....lfH .. lal:f ~-Ir C.lMt ....

ll. hdtl• Tirllt A. 1.- Td• lpt-

llM•n I. h•t.e It .. Walft

ClM•n

lt. --- cilel•t .... lna--R heltl• Td•

~.A UJt llN I T I

• • TAILE 2.2-1 tContinuedt l'F.ACTOR TRIP 519TDI lllSTRUMF.llTATIOll TRIP SETPOINTS

TIU• snro1n

a t.01 of .. rrow ra .... l•Utr .... nt ...--••c~ at•.. ....rator

a 2111 .olt•-••c:lli bu•

a H.S •• - uc:lli bu•

a es ••lt

• ISi off full open

.. t ... 11~•·

..t .... 1«:91•

'

1-6

ALLOWABLE VALUES

a 1.01 of .. rrow r•...- l~atr..-..t •pa•-••ch at ...... nerato1

• a ZISO .olta-uch bu•

a S6.t la - ••c:lli bu•

a es ••'• s ISi off f•ll open

. . .. ,. ·~

"-enct.ent No. Ill

I

• •

• "' ~. r 1•1 ~

'" I .......

HOil I:

• !AUl.~ ?.__:?_- !_ (Cont inut:d)

HlAClUH IHIP SY~ILH IN~IHUHLNIATION lHIP SEIPOINIS

' NOlATION

lncHuted Al .at llAHll TlllHHAL Pm1£R

I - " lodiuted T .al HAllll TtllkHAL POWU ~ ~11. 9°f •vg P " Pressurizer pressure. psiy

p· - 22JS psig (tndic•ted HCS nomin•I oper•ttny pressure)

lta 1S. _ -·- - Tht- function gent:uled by the le•d-l•g ·controller for I dyn•wic coo1vcn~allon )t~ 2S • dVCJ

1

'

1 - Time consldnls ulilizt:d in the le.ad ldg controller for· I 'I - 30 ~a:c~. ~ 2 avg •2 "' 4 secs. ,......~,,.. ,_.....,Y

- L•Pl•ce tr•n>fo111 ope~~~~-~ s

'

•

•

3/4.l REACTIVITY CONTROL SYSTEMS

3/4.l.l BORAIION CONTRQL

SH!,ITDOWN MABGIN • Tavg > 200°F

LIMITING CONDITION FOR OPERATION

3.l.l.l The SHUTOOWN MARGIN shall be z l.3t ~k/k.

APPLICABILITY: MODES l, 2*, 3, and 4.

ACTION:

With the SHUTDOWN MAR.GIN < l.3t Ak/k, immediately initiate and continue boration at a 33 gpm of a solution containing a 6,560 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS

4.l.l.1.l The SHOTDOWN MARGIN shall be determined to be a 1.3t Ak/k:

a. Within one hour after detection of an inoperal:>le control rodole. If th• inoperal:>l• control rod i• immoval:>l• or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at lea•t equal to the withdrawn worth of the immovable or untrippable control rod(s).

b. 12 hours by verifying th• limit• in the COLR per

Specification

c. When in MODS '"··within 4 hour• prior to achieving reactor criticality by verifying that the predicted critical control rod position is within th• limits in the cot.a per specification 3.1.3.S.

* see Special Te•t Exception 1.10.1

~ With lCdf a 1.0

#I With lCdf < 1.0

SALEM - UNIT 1 3/4 l-l Amendment No. 201

•

•namn aarngL sxsIJ!l.1

19pm 9m .sqsmsgs - OP!MUHg

LlKlTUIG c:mDl'!tC:. roa OPDATIOll ............... ................ . ................................................. . l.l.2.6

a.

~ a •ini.9'111, tb• follcwiaq borated veter •ouree(1J •hall be ~ •• required by 1pec:itication1 J.l.l.l &Ad 3.1.l.ls

A tlari.c: acid noraqe •y•t• w.Ltlla ·

l. A concail2ed ?Ol1me of bor:ated water in acccr~t·1~re 3.1.l, ;--~ ---·· . I·.

~ 3.1-2 2. A boron concentration in accord&nce with tic;ur•A••l.t"J &nd1

.. r. A minil!Na aolution eilllperatuce of 6J•r. ·~· b. Th• r•fuelin9 water 1tora9e tanll w.Lth:

l. A contained vclwne ot between 364,500 and 400,000 9allona cf wacer,

2. A boron concentration of between 2,300 and 2,500 ppa, and

J. A minimum tolut~on t .. perature of Js•r.

N'PtICAJit:TI: MOOES l, 2, 3 and •·

ACI!ON:

a. With the boric ac~d etoraqe 1y1t .. inoperable and bein9 ~••d •• one ot th• &beve required b

•

•

·-

ACTIOl!t

With a aui.mum of ou shutdown rod not rutLY WI'ftlDllWll, ac:apt for surveillance tutin1 punat to Specificatioa 4.1.3.1.2, within ou hour either a

a. PULLY wrrBDIAW the rod, or,

b. Declare the rocl to ~ inoperable and applJ Specification 3.l.3.l.

S1JIVIILLA!fCI RJQUillMINTS

4.1.3.4 lacll shutdown rod shall be dataminell to be lUl.LY wrrBDIAWll bf u.a of Cha 1rouf d=·M cauntera, and ftrifi..& bf the wloa rod po•itioa indicators** a

a. WitJWI 15 aimatu prior to vithdrawl of 111iJ roa ta contnl b.a •• 1. c. or D dviq m approacll to ructn criticality, llld

•;, .. · 'iii. -- • f-r-'•

*S• SpM!al Tut bcepti ... 3.10.% ad l.10.l · **For pawn leftla bel0..50I OM boa thamal "80U ti•" i• pemitt..&.

Duriq thi8 90U tui.. ti. abM1'1Ce ftl• ot rocl mti• 18 liaitad to •iz •t.,.. . . . . Nitla left anatu mm or eqaa1 to 1.0 @S_.,.Ulnc:a ~.1.3.4.a 18 anUcable prin to vithdnW'llll c:aauol banJs8 in pnpuatioa fn startup (Koda 2).

SAl.111 - UlllT 1 . 3/4 1-22 A- f nt Mo. 103

6-·

I r

•

•

''b''

.. .-··· ··----..... -·--··-···---- - ··---·---·

LIMITING CONDITION FO~R~O~P°'E~RA;;;T;;-,.,. ....... --~~~~~~--------~--~--------~~.;.--•

3.l.3.5 The control banks shall be limited in physical insertion as specified in the CORE OPERATING LIMITS REPORT (COLR) .

APPLIC.ABILITX: MODES l*, and 2•j

ACTION:

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3~1.2, either:

a. Restore the control banks to within the limits within two hours, or

b. Reduce THERMAL POWER within two hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank position using the insertion limits specified in the COLR, or

c. Be in at least HOT STANDBY within 6 hours.

,.

SURVEILLANCE REQU~REMENTS

4.1.3.S The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours by use of the group demand counters and verified by the analog rod position indicators•• except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod position• at least once per t hours••.

• see Special Teat Bxceptiona 3.10.2 and 3.10.3 ** For power levela below SOt one hour thermal "soak time• is permitted.

curing thi• soak time, the abaolute value of rod motion i• limited to six stepa.

j With Kw. greater than or equal to l.O

SALEM - UNIT l 3/4 1-23 Amendment No. 201

•

•

•

eOWER DISTRIBUTION LIMITS

LIMITING CONDITION FOR Oi?E~TION (Continued)

b.

c.

i?OWER unless COLR and ACT

90% of specified in the

THERMAL !?OWE be increased above 50% of ~TED THERMAL i?OWER unless the indicated A.FD has not been outside of the limits specified in the COLR for more than l hour penalty deviation cumulative during the previous 24 hours.

SURVEILLANCE REQUIREMENTS

4.2.l.l The indicated AXIAL FLUX DIFFERENCE shall be determined to be within its limits during i?OWER Oi?ERATION above 15% of ~TED THEJUfAL i?OWER by:

a. Monitoring the indicated A.FD for each OPERABLE excore channel:

b.

1. At least once per 7 days when the AFD Monitor Ala.rm is OPERABLE, and

2 . At ~east once per hour for the first 24 hours after restoring the AFD Monitor Alarm to Oi?ERABLE status. ,,

Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at least once per hour for the first 24 hours and at least once per 30 minutes thereafter, when the AXIAL FLUX DIFFERENCE Monitor Ala.rm is inoperable. The logged values of the indicated AXIAL FLUX DIFFERENCE shall be assumed to exist during the interval preceding each logging.

4.2.l.2 The indicated AFD shall be considered outside of its limits when at least 2 of 4 or 2 of 3 OPERABLE excor• channels are indicating th• AFt> to be outside of the target band. Penalty deviation outside of the target band I shall be accumulated on a tim9 basis of:

a. one minute penalty deviation for each one minute of POWER OPERATION ou~aidla of the l!!!!!t• ac THERMAL POWER level• equal to or above 50% o!. JWnD THENCAL POWER, and

b. on ... halt minute penalty deviation for eacb one minute of POWER OP~Oll outside of th• limits at THERMAL POWER levels below 50% of AATID THERMAL POWER •

SALEM - UNIT l 3/4 2-2 ~ndlllent No. 201

I I

•

•

'I ..

:! •:. • s.--·,. ~4 --·- ... -· :ays.

! . z., 1

. ... -~ ·-.

-. . -....... ·:·----

=:~!~ :1;s !·:~~r :!:!·-·~·-; ~:.:~·::11! :~ .o.:!!"'!~C! "",.! .. !~: ':: -:a.z.1.. :r- : .. ·~~!!~ _ ... -.). : i ~!.

: i

'I

I ! I

I'

'

I ~ I'

-11&.!?M"-I! • .. ~ !~: : •:,.-s,.,• . - --.. !~ ~~! . . . !!"! ~,.--. .. . - . ...

~ i I

/

3/4 2-3

-

,.

a'"• .. :·! -' -- - -: - -~-- :!: !. ---

• • TABLI i . 3 -1 (CoDtimaed)

pp(."10& TJlIP SYSTDI DISJJt""PVATIOll

gg-rI,.t'· OllJiT

I. U. La•• oC •la.1"° ~ H. ~t._ Guerato~ --~ ...,,_l--1.ow-Lolf

15. DSLSDD

11. Tu.rid.De Trip , ·a. Low Auto•top Oil itre••ur• b. '!Uzbiae Stop VAlYe Clo•ur•

' 11. Safety llljec:ticm J:Dpat fram U•

20. ...ctor Coolant ea. llreaker ~iUcm Trip

a1. 11eaator Trip ar..br

BALa - UIDT 1

Cff&IQIKL

ggq

8 !' 8 ~·· ''tt

......

...... •••• ...... ...... ...... ...... ......

3/i l-12 '

a

a

a

a

. ..... . ..... . ..... . .....

. .....

. .....

• caaMMgJ. llODU DI WBXCll

WllllCl'Iom&L SUllVJlil.I 1 W:S

nu "'19'•• ...... 1 ' Q 1. 2

Q 1

Q 1

S/u0 • 1. 2 S/u0 • 1. 2

•• ., Cli) 1.

a

.Cl) Cll) CU) 1. 2 and. I aad aCHI .Clil 1. 2 and.

~·t~

• ACTION 19 -

ACTION 20 -

ACTION 21 -

ACTION 22 -

ACTION 23 -

• SALEM - UNIT 1

TABLE 3.3-3 (Continued)

Wita 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:

a. The inoperable channel is placed in the tripped condition within 6 hours.

b. The Minimum Channels OPERABLE requirements is met; however, the inoperable channel may be bypassed for up to 4 hours for surveillance testing of other channels per Specification 4.3.2.1.1.

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 6 hours or, be in at least HOT STANDBY within the next 6 hours and in at least HOT SHUTDOWN within the following 6 hours; however, one channel may be bypassed for up to 4 hours for surveillance testing per Specification 4.3.2.1.1 provided the other channel is OPERABLE.

With the number of OPERABLE channels one less than the Mipimum Number of Channels, operation may proceed provided that the I inoperable channel is restored to OPERABLE within 72 hours.

NOT USED

number of OPERABLE channels one less than the Total ~--' of Channels, restore the inoperable channel to

status within 48 hours or be in HOT STANDBY within rs and in at least HOT SHUTDOWN within the following

3/4 3-22 Amendment No. 191 I

•

.. ~a:~ ~:;:.: :~an~el sha:.l :e :es:ed ac :.ease :nee ~er 52 :iays on a ,;7;.,j.,j£iU::J :::3'": aAs:s. 7he ::-v..-."Nil. r"~"NCT::N '":!ST of Heh :.ogi.c ::-.ar.:-.el. s~all ~er:.~y :hat :..:s assoc:..a:ed :1:.esel ;ener~cor a~::m•ci.c :.~ad se-:r~en:e : :.~.er :.s Ci>ER.Aat.i ·.n:n ::-.e :..~cer•1al bec·.-een -!ach. load olo

•

•

•

..

r !!lt!yrm" r! e11 lt•. l. J ~"mlt:ll H!tr'!tnf!l'UQI!

uoLlTtON .Qtmt~ tMTV?iATtON

1.3.l.l nte ,...1&C1011 mn1=r1"t f1ttC".mMQC1011 C11&Mel1 ,,.._..flt 1'181• J.l .. 111111 ~· QnJU&I wfQ Cftl1f" 1t1N1CP1t llQl1ftQ wi1C:S1ft =- ••1'1 • 1 f 81 u. Al!!rlc:.tlrL*!': Al s~ '" raa11 1.1·•·

1:£i91!:

a.

, . WH:a a .... 1H10lt -1UP"1tt ~lllM•1 &1IP'91=-"• sec;af,.i Ut::W!• t~ ~·wall.le ,,_. '"Ta.aft 1.1-4, MJ1i1H ~· MQ011ti = •1~11 CM 1 fm1C •1Cft111 4 ""'" OP •la" ='le ~1 , ........ , ..

II. ~Ullo• 01' .... l"te1at1• '111111to~"' =a,a,...11 fltOOtrUlt, WI Cft9 AC'T'tOI ,,_. 111 1'aD1t l. l•t.

c:. iii• '""1110M of soec1McaC10ft1 1.a.1 &M 1.a.& '" 1•ai &11Hca11e.

:. . •.J".J.t; Q.:11 l"U1U10ll :U1W"111t f1tUP.1•MH~M Cl'tUftel snatt 11 --r ~iPWuc QPL'U&I ~ Cft9 or.tl"!llllCa of :.... C:.watll. QtlCx.1: .. ;..~"1?. 1

........ CM.IS1Anaa.1.- .. owu111..A1JCTt01W..J'1!f .. " ... C1ou .-P1"t tit• ~ca• snca 1· n =- ~11·1-c1u ,,... 1n r1a1e &.l•l. ....... __ _

\ s-av12cE oia: .::,

l/4 l·l5

--~--

2.

INSTRUMENT

PROCESS ~~~;J.f·:· .-:. b. Noble ~:~t.~,~~ '°nitora

;·-~' 1; 'V-1) Hediua~~ ~Uioary

Buil4i!19"·~~l &yat•• (Pl~~··\~,}~!~~

2) High.~• ~f,Aary Building lxhau•t &yet•• lPl•nt vent)

l) Moain,stea•line Discharge (Safety valve• and AtlDOa~heric Ste .. Dullll•)

t) Conden••r KxbAuat &y•t•

• TABLE J.l-6 (Continued) BAJ>IATION MQNITQBING JNSTRlJtlEN'fA'[IOH

MINIMUM CHANNBLS OPERABLE

l

l

l/ HS Line

i·

APPLJCABLE MODES

1,2,lU

l, 2, lU

1,:.1,li.t

ALARM/TRIP SETPOINT

61. ox10 11-&Ci I cm1 U~lana only)

61. Oxl011£Ci/cm1

(Al.arm only)

dO mR/hr . (Alarm only)

61. 27xl04 cpm (Ala11n only)

l .· CC*'fllOL ROON 62. t8xl01 cpm

•· Air lntoake -hdi•tion Level

••

II Control ROOlll air intak~s shared between Unit l and 2.

• • ALL HODES and during movement of irradiated fuel, as11ef!lbl ies amJ

MEASUREMENT RANGE

1-10• cpm

•

C.ot!E AL-f£~AlloNS etn·e alterilt:ion11 ~

/ --__/---..___

• ACTION

;p

21

21

2}

Cl_. ,, ,, f\{4?

•

•

ACTION 19 -

TABLE 3.3-6 (Continued>

TABLE NOTATION

With the~number of channels OPERABLE less than required by the Minimum Channel• OPERABLE requirement, perform area survey• of the monitored area with portable monitoring instrumentation at least once per 24 hour•.

ACTION 20 - With the number of channel• OPERABLE le•• than required by the Minimum Channel• OPERABLE requirement, comply with the ACTION requirement• of Specification 3.4.6.l.

ACTION 22 - With the number of channel• OPERABLE le•• than required by the Minimum Channel• OPERABLB requirement, comply with the ACTION requirement• of Specification 3.9.9.

ACTIOR 23 - With the number of OPERABLE Channels le•• than required by the Minimum Channel• OPERABLB requirement•, initiate the preplanned alternate method of monitoring the appropriate parameter(•), within 72 hour•, and:

1) either restore the inoperable Channel(•) to OPERABLE status within. 7 day• of the event, -or

2) ,.

prepare and aubmit a Special Report to the Connia•ion pursuant to Specification 6.9.2 within 14 day• following the event outlining the action taken, the cauae of the inoperability and the plana and •chedul' for reatoring th• system to OPBRABLB statua.

ACTION 24 - With.the number of channel• OPERABLE one le•• than required by the Minimum Channel•.OPERABLB requirement, restore the inoperable channel(•) to OPBRABLB •tatua within 7 day• or initiate and maintain operation of th• Control Rocm Emergency Air Conditioning Sy•tem (CRBAcs) in the pre••urization or. recirculation mode of operation. CORB ALTERATIONS and movement of irradiated fuel

~~lie• will.be ouop9Dded during operation in the recirculation

2. 5 -w,t: no channel• OPBRABLB in a Control Room air intake, i diately initiate and maintain operation of the CRBACS in the

.rPreaaurization or recirculation mode of operation. CORS / ALTDA'l'IOHS and movement of irradiated fuel u•elablie• will be

.. - ' - _,../ .. suapended during operation in th• :ecirculation .mod•. -

SALEM - UNIT 1 3/4 3-37 Amendment No.190

INSTRUMENT

. '·~~)t~:~. ~. 2 . PROCESS MONI,qfA;.;;

~;~~·::... ·. ·.

b. Noble Gaa .,~;n~·~~' ~nitors ·

1) Hediua ~~ ~'Ji•ry Buildin9 sxai.~ fy•t•• (Plant Vent)

2) High Range Auxiliary Building Exhaust Sy•te• (Plant· Vent)

l) Main ~teamline Discruarge CSafety Valvea _,.d Atmospheric ou.p.;

t) condenser Exh. Sys.

l . CONTROL RooH

a. Air Intake· - Radiation Level

TABLE f.l-l tiouedJ RAJ)IATION MONITORING INSTRU.1£NIATJ0H

SlJBVEILLAUC£ REQUIR£Milff§

CHANNEL CHANNELS

CHECKS SOUR~E

CHECKS CHANNEL. FUNCTIONAL

CALIBRATION TEST

s M R

s H R

s H R Q

s M R

s M R Q

~·

• HODES IN WHICH

SURVEILLANCi REQUIREI;>

• 1. 2, l " •

1, 2, l " 4

1, 2, J " 4

l, 2, l " •

••

** ALL MODES and during movement of irradiated fuel assemblies and I

•

I I

!

"ii •• --.. 0 an

t..UIITtNC CONDITION roa OPEIA?tOM

3.l.l.1 Th• acc:14enc aon1:.ort.n1 Ln1c:~enc&c:J.on c::t\an.nel.a aho"" Ln T&ble l.1•11 1ha11 b• operable.

a. A.I shovn Ln Table l.l·ll.

b. -:'he prov111on. of Spec1ficac1on 3.0.~ are noc a,pl1cable.

~.l.3.7 Each acc1denc aon1cot1n1 ln.1 Oft c &rme all b• daaon•c:acad OP perforaanc• of ch• CHANMIL CM!~hNa,;z. CHA:nl!L CAL.II TtON!}°'erac1ona ac che f:eq~enc1•• 1novt1 1n Table ~.l•ll.

·.

:'ABU; 3.3-ll !continued)

• 7ABLE N07ATION

AC7:0N l #1tn th• nu.mber oC OPERABLE accident monitorinq char.~els less than :~e ~e~r•4 Number of Channels shown in Table 3.3-~l. :estor• the ~~operable chanr.el(s} to CPERA!LE status within 7 days, or be in HOT ~:·:.::::·~ ·..i~:~~n :~e next ~2 hours.

~C7!:N 2 ~i:h :~e ~~~ber of ~PEP.ABLE accident monitorinq chanr.els ~ess :~an :~e ~:~:!'i'~"M ~umber of Channels shown in :'able 3.3-ll, :estore :he ~~operao:e :har.r.el{s) to OPERABLE status within ~a hours or be ~~ ~C7 5HU7~CWN ··n thin the next lZ hours.

ACTION 3 deleted

ACTICN 4 With the number of OPERABLE c~anr.els one le t~e Required Number of Channels shown in T

Steam Gen•rator el.

~ I ACTION the of OPERABLE channels less than the '· IRequir shown in Table 3.3-ll, operation maY'

roceed prov that Steam Tables are available in the Control Ropm nd :he following ·red Channels shown in Tabl• 3.3-ll are PE~LE to provide an a calculating Reactor Coolant

.,?

•

ystem subcooling margin:

Reactor Coolant Outlet ;t1ide Ranqe)

~eactor Coolant Pressure (Wide Range)

SALEM - UNIT l 3/4-3-56

--·

Amendment No .. :~:

:) <

/

•

•

.. TARLE ~.3-12 (Continued) TABLE NOTATION

(l) The CHANNEL FUNCTIONAL TEST shall also derrcnstrate that autornatic isolation. of this pathway and control room alarm annunciation occurs if any of the following conditions exist:

l. Instrulll!nt indicates measured levels at or ·above the alarm/trip setpof nt.

2. Circuit failure. (Lass of Power)

3. Instrument indicates a dOwnscale failure. (Indication on instrulTl!nt drawer in Control Equipl'1!nt Room only)

(2) The CHANNEL FUNCTIONAL TEST shall also ~errcnstrate that .:ontrol room alarm annunciation occurs if any of the following conditions P.:cist:

l. .Instl'"Ul"ent indicates 1'1!asured levels at or above the alarm/trip setpnf nt.

2. Circuit failure. (Lass of Power) ,.

. 3. Instrument indicates a ct>wnscale failure. (Indication on instrument drawer in Control Equiplll!nt Room only)

4. Instrul"ent controls not set in operate mde. (On i nstrull1!nts equipped with operate rrcde switches only)

(3) The initial CHANNEL CALIBRATION was perforl'!ld using appropriate liquid or gaseous calibration sources obtained from reputable suppliers. The activity of the calibration sources were reconfirmed using a nulti-channP.1 analyzer which was calibrated using one or rrcre NBS standards.

(4) CHANNEL CMECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK sh~ll be Plade at least once per 24 nours on days on which continuous, periodic, or batch releases are made.

• During liquid additions ta the tank.

•• ·If ·unlc level ·indication is not provid-.rl, vertif1cat1on wi 11 be done by visual insp-.ct1~n.

SALEJ14 - UNIT l

an in-line channel which requires perind1c Any count rate indication above 10,000 c:p"" cnnstitutes a. ca~11ance purpnses •

3/4 3-63 Amendment No. 64

•' ' I

TA8LB 4.3-13 RAQIOACIIVE GA8EOUS EFPLUEN'f MQNITQRING INSTRlJMIN1ATIQN

auRYEILJ.ANCB R£0UIREM§N"fS

INSTRUMENT

1. WASTE GAS HOLDUP SYSTEM a. Noble Gas Activity Monitor - Providing

p

Alarm and JU,ltcmcttic Termination of Release

I

b. Oxygen MOnitor D

I

.i

2. CONTAINMENT PUR~B AND PRB.SSURB .. VACUUM RELIEF

a. Noble Ga~ Aptivity Monitor - Prov~ding p

Alarm and Aut~ti.c Termina~ion of Release : '

3. PLANT VENT HBADBR SYSTEMI a. Noble Ga~ ~ctivi.ty Monitor

D

b. Iodine sampler w

c. Particulate sampler w

' d. Plow Rate 150nitor D

e. sampler Plow Rate Monitor w

OURCE

p

N.A.

p

.M

N.A.

N.A.

N.A.

N.A.

CHANNEL CALIBRATION

R (3)

Q(4)

R (3)

R(3)

N.A.

N.A.

R

R

CHANNEL FUNCTIONAL

TBST

. Q (1)

M

Q (1)

Q (2)

N.A.

N.A.

N.A.

N.A.

MODES IN WHICH SURVEILLANCE.

REQUIRED.

*

**

***

*

*

*

*

*

I The following process streams are routed to the plant vent where they are effectively monitored by the

instruments de,scribed:

(a) Condenser Air Removal System (b) Auxiliary Building Vent.ilation System (c) Fuel Handling Building ventilation System (d) Radwaste.Area Ventilation System (e) Containment Purges

,. "T r.'M - flNT'T' 1

'

3/4 3-68 Amendment No. 157

'

•

•

•.l.~.l ?ha .-..e re~ir•• ~bin. ov.r•,.•' proceccioe 1yec .. 1hall b~ ~crace4 OfllAl1.I:

&.

b.

Aa- leuc one• per U llOftCh• by perf orunce of a CHAlGlll. CALXl&Atto• oft ch• c~bina over•,.•' proceccioa 1y•c ....

~Q:;;:;... -AC' l .. 8CJ\eft9 pa l.0 MftW by cU1 .. 1ullDUn1 ac l• .. C OM of each of c~• aoove va ve1 anct perfocw1n1 • viaU&l and 1uface lnapecclon of v v , d11ka &Ni 1c1 .. &nil ver1fy1n1 nio 1.111aCc~pc&bl1 flav1 or cor:o11on. If 1.1nACc1pc&Dl• !lave or 1aca111ve cor:o11on are fo\11\d, all oc.her valve• of chac ~ 1ba11 b• 1napecc•c&.

~.l.•.• ~•r1fy ch• c11c fr1q\&an&Y .. 1nca1na c.be prob&Dl11cy of a ai11ll1 1jeccioe 1ac1daftC v1c..t\1D MIC pU.d.el1na• by reTl.ev1n& c.be .. c.nodolo11 pr•••ncad

in WCAl· l.U25:

•• b.

AC leaac one• every cw nf,...Un& wca1••·

A.teer ..01f 1cac1ona co U.• .. 1a C\&l'ttlna •~ curb1D9 over1peect proceccloft valv••·

,,

stJ.DI • IJlllT l. l/f. 1·71

.... . .

I

.·

•

•

~EAC~OR coo !..ANT svsre:-.

~O Ul SHUT OOWM

UritlTING: CONOlTtOft FOA OPERATrO,.

..

_.-·.:... ...... :;--_·.~ ... :-_,

3.4.1.4 iwot· rHfdual l'IHt removal lciops sh11l he OPERABI.£• antf at least on• RHA loop snall be 1n oper~tfon.••

APPUC~S[UTY: . MQ(E 5.U

ACT tON:

a. ~1th le~s than tht abov• required loops ooerabl•, i"'"'d1ately 1n1t11t• corrective action to return the required loops to OP€AABl1 status as soon as possf blw.

o. W1tn no RHA loop tn operation, suspen~ all 09er1t1ons tnvolvinq a rettuct1on in boron concentrat1on of the R11ctor Coolant Syst"" and f""'9d1attly tn1t1at~ corrective actfon to r•turn th• r~quirerl· RHA lnop to operation.

Sl.J'Rvt t L~NC! Q~OUIREM€NTS

4.4.l'.4·At lust one resfdu1l neat remaval loop sn111 l'le verHttd to 1'19-tn operat1on and circulating reactor coolant at leut once per U hours.

r.

I On• RM~ loop "'IY be inop•rablt for up to two nours for survt111ance testtnq, provided th• other RHA loop ts OPERABll and 1n 01)tration. Add1t1on1lly, four filled re1ctor coolant.loops, ~1th at 111st ~wo stea• 91ner1tor1 •itn tne1r sacnnd1ry side water levels greater tnan or equ1l to 51 (n1rr~ ran941). mey b• subst1tuttct for one resf dual l'IHt ,,fl'GVI 1 1 nap.

pu• sn1l l n~t o. starttd wi~tt one or ,,.,re of tl'!e tw••H~tiur•t less thin or equ1l to· 312., unless l) tl'!e

prtssurizar ter v u111e is less thlft 1650 cubte , .. , (1qu;v1lent to q3 2.°I. pprox IRlt•lY 9al"ot 1tval), or Zl the secondary w1tar tllftlPtrature of

· 1~ st118 91t1er1 or is ltss thin SQ., above e1ch of the RCS cold ,eg .. .-:; ~~,·~-"'-'·· --of'!\, .. • ~-.~: :. ~ •,(~j .... ~ I

. -~1~,~i.Sis ·:- · :. ·· 1i(i0rt;1HJ RHR Toop operattility Ny ne 11c1pt1d as fol 1ov~: ~1" (.~~·~~~~~~ .. ·-.$· •.

. >\ '~.~~~~!.7·;r_;;;~ 1 or tftllr9ency power source ""' "'• t noperab l •. ·· ·. · · It~:.; Ofte:: s-.f"tt c1· w1t1r -ht1cier lftl1 be out of sarv1 ce provi dtd t!'I e

equtplll9ftt l httd in Tattl• 3.4-l "h ·oP£RAILI •

.. The residual l'l11t remav1l pu,.t may b4t dll-.ner9ized for up to 2 .. ..,,.J,.~ provided ll no ooerattons are pe,.,..ttt14 that would cause d11ut~~n ), t~- nttctar coolant systlftt baron conclfttrat10fl. &nd Z) core cut'~t tt!'1Ptr1ture 1t lftlin·uined at 1Hst lO., belas&turattatt tefl'Oerii:~'"!.

SAWt • UNIT l 3/4 '·lb AM!HDMDIT ~O.

REACTOR COOLANT SYSTEM

SURVEILLANCE REQUIREMENTS

c. The tubes.select!d as the.secon~ an~ third samples (if reQuired by Tablt 4.4 2) during each inserv1c1 inspection may be subjected t . partial tube inspection provided: 0 c .. 1. Tne tubes selected for these samples include the tubes from

those areas of the tubt sheet array where tubes with· imperfections were previously found.

2. The inspections include those portions of the tubes where imperfections were previously found.

The results of each sample inspection shall be classified into one of the following three categories:

Category Inspection Results

Cml Less than SI of tht total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C·Z Ont or mart tubes, but not more than ii of the total tubes inspected art d1f1ctive, or between si and 10\ of the total tubes inspected art degraded tubes.

C·3 Mort than l~ of th• total tubes 1nspecte9 are degraded tubes. or more than ll of the inspected tubes are defective.

Note: In all inspections, previously degrade~ tubes must exhibit significant (>l~l further wall penetrations to be included in th• abov• perc1ntag1 calculations.

4.4.S.3 Inspection Frequencies - Th• above required ins1rvice inspections of steam generator tubes shall bt performed at the following frequencies:

a. The first inservict inspection shall bt performed after 6 Effective Full Power Months but w;th1n 24 calendar months of initial criticality. Subsequent ins1rvic1 inspections shall bt performed at intervals of not less than 12 nor more than 24 calendar months after th• previous 1nspect1on. If two cons1cut1v• inspections following service und1r AVT conditions, not including the pres1rvic1 inspection, result in all inspection result• falling into the C·l category or if two consecutive inspections d111tOnstrat1 th previously observed degradation has not continued an o additiona~

··has· occurred, -th• Jnsptction interval may bt ext• td to a maximum of once per 40 months. d~~ro.da-.-t-i 0 ""'

b. If the results of the. 1ns1rvic•.insp1ct1on of a staua generator conductect in accordance with- Table 4.4-2 at 40 month intervals fall i~ Category C-3, the inspection frequency shall be increased to at least once per 20 1110nths. The increase in inspection frequency shall apply until the· subsequent inspections satisfy th• criteria of Sp1cif1cat1on 4.4.5.3.a; th• interval may thin bt extended to a maximwa of once per. 40 months.

SALEM.- UNIT 1 3/4 4-8 Amendment No. 118

•

•

~£)C~~- ~:o~~r SYS~!.~

3/£.1.5 ~!'.)~:R ::ot.AHr SY~ !.~~GE

L~K.AGC: :m~::N SYS'i:'4S

---

3.•.S.1 rhe followfnt ~11c~or Coolant Syst .. t11k1ge_ d1~t1on systllllS s111ll oe OPEAAl1.£:

1. 'rh1 contai,,,,.nt atznasonere oart1culatt rac&1oact1v1ty !ftQnftar11"19 syst•,

~- ~h1 cantairmant SUll1J 11v1l :nan1cor1ng syst•, and

c. Eft.l'!el'" c,,• cantafnmant fan ccoltr ccnda1111ta f1ow rate Of" .t"• cantairan9nt u:nason1re gueaus rac&io1ct1vit~ rnDnitor1ng syst•.

~PPL!~BtLIT'f: ~OES 1. Z. 3 ind 4.

~~!OH:

~it" only ~ of t"• at:IOvt required 1111.191 d1t1ct1on systllftl OPEill.ILE. og1ration ~1 cont1nu1 for uo co 30 dlys Or"'OvfdlG grab 1111Dl1s of t.l'!t cont&iMJNnt ai:msoft1re are oDUinld ancs analyzlC u 111st one. 01r Z4 MOur1 •n1n tne required gaseaus and/or oar-t1culata rad1oaci1v1ty mcnitor1ng sysc .. ts 1nop1r1blli ot,,.,..1sa, be fn at l111t MOT STAHOIY •1t,,in :n1 next 5 "ourt anca in COLD SMUTtlCWll w1tn1n '!J'te following 30 "Our1.

SURV!IL~NCE ~!qUtR£Pi!!MTS

4.4.5.1 T'l'lt 1t1k•t• dataet1o" syn- snall be d-nstnta4 OP!RAll.£ t11:

1

a. Cantairmnt aenasor.ere 01~1culu1 and g11eau1 (; f tlt1nG l.lltdl-;:::::::L-----"110n1tar11!f-rs1st1n .. o;rlo""4nce of C~HEL Ot!CX.t~"u. c,\LllRATlQltand C1'1AMNIL FIJMCTtONAL iiST &~ ~ne fT"tQu1nc11s SC1Ktfft*J1t l'&blt 4. l•l .

I

. ' . -.~::. ~ifi"·' ~:- -~~ -

~~ · .e:&etta-frmae suno level an4 conta1,,_.t fan =al tr candaft11ca ·'. ~ ~/

-· REACTOR COOLANT SYSTEM

•

PRIMA.RY COOLANT SYSTEM PRESSURE ISOLATION VALVES LIMITING CONDITION FOR OPERATION .. 3.4.6.3 ~~Coolant System Pressure

~-all be OPERABLE. Isolation Valves specified in Table

APPLICABILITY: MODES 1, 2, 3, and 4.

~~: 3

a. With any Reactor Coolant System P ssurelr elation Valve leakaqe qreater than the specified limit in Table 4.4-~ solate the high pressure portion of the affected system from e low pressure portion within 4 hours by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

SURVEILLANCE REQUIREMENTS

~.4.6.3 Eac9 eactor Coolant System Pressure Isolation Valve specified in Table 4. 4~ hall be demo.nstrated OPERABLE pursuant to Specification 4. o. s, except th in lieu of any leakaqe testing required by Specification 4.0.5, ea tr ve shall be demonstrated OPERABLE by verifying leakage to be within its limit: r

a. At least once per 18 months.

b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours or more and if leakage testing has no~ been performed in the previous 9 months.

c. Prior to returning the valve to service following maintenance repair or replacement work on the valve.

d. For the Residual Heat R•.moval and Safety Injection Systems t and c d leg injection valves and accumulator valves listed in Table 4.4-.A3th testinq will be done within 24 hours following valve actua ion due automatic or manual action or flow through the valve. For a.....__.LTY'..., systems testing will be done once per refueling.

The provision& of specification 4.0.4 are not applicable for entry into MODE 3 or 4.

SALEM - UNIT 1 3/4 4-16• Amendment No. 210

•

•

REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES •

Low Pressure Safety Injection Loop 11, cold leg

Loop 12, cold leg

Loop 13, cold leg

Loop 13, hot leg

Loop 14, cold leg

Loop 14, hot leg

Intermediate Pressure Safety Loop 11, cold leg Loop 11, hot leg

Loop 12, cold leg Loop 12, hot leg

Loop 13, cold leg ~oop 13, hot leg

Loop 14, cold leg Loop 14, hot leg

Safety Injection Accumulators loop ll, cold leg loop 12, cold leg loop 13, cold leg loop 14, cold leg

Valve No.

11SJ56 11SJ43 12SJ56 12SJ43 13SJ56 13SJ43 13SJl56 13RH27 14SJS6 14SJ43 14SJl56 14RH27

Injection 11SJ144 llSJl56 llSJl39 12SJl44 12SJ156 12SJl39 13SJl44 13SJ156 13SJ-l39 14SJ144 14SJ156 14SJ139

to cold leg 11SJ55 l2SJSS 13SJSS l4SJSS

Safety Injection Boron Injection loop ll, cold leg

to cold legs llSJl 7

loop 12, cold leg loop 13, cold leg loop 14, cold leg

RHR Suction loop ll loop 11

SALEM - UNIT l

l2SJ17 ----l3SJ17

14SJ17 lSJlSO

lRHl 1RH2

3/4 4-16b

Maximum (a) (b) Allowable Leakage .

S 5.0 GPM each valve S 5.0 GPM each valve S 5.0 GPH each valve S 5.0 GPM each valve S 5.0 GPH each valve S 5.0 GPM each valve S 5.0 GPM each valve S 5.0 GPM each valve S S.O GPM each valve S 5.0 GPM each valve S 5.0 GPH each valve S 5.0 GPM each valve S S.O GPM each valve

S 5.0 GPM each valve S 5.0 GPH each valve S 5.0 GPM each valve S 5.0 GPH each va1ve S 5.0 GPH each valve S 5.0 GPM each valv~ S S.O GPM each valve

·s 5.0 GPM each valve S 5.0 GPM each valve S 5.0 GPM each valve S S.O GPM each valve S 5.0 GPM each valve S 5.0 GPM each valve

S 5.0 GPM each valve S S.O GPM each valve S S.O GPM aach valve S 5.0 GPM each valve

s s.o GPM each valve s s.o GPM each valve -s s.o GPM each valve s s.o GPM each valve s s.o GPM each valve

s s.o GPM each valve s s.o GPM each valve

Amendment No.210

-

•

•

•

(a) l. Leakage rates less than or equal to l.O gpm are considered acceptabl~. However, for initial tests, or tests following valve repair or replacement, leakage rates less than or equal to 5.0 gpm are considered acceptable.

(b)

2. Leakage rates greater than l.O gpm but less than or equal to 5.0 gpm are considered acceptable if the· latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

3. Leakage rates greater than l.O gpm but less than or equal to 5.0 gpm are considered unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

4. Leakage rates greater than 5.0 gpm are considered unacceptable.

Minimum differential test pressure shall not be less.than 150 psid.

,,

,_.

SALEM - UNIT l 3/4 4-l6c .Amendment No. 21 O

•

•

•

'''SR' cm tr axnp

•••••llB•••••••••••••••••••••••••G•••••••••••O••••••••• ••• • • ••••••••••••

J.4.1 ?~• •pec1f1e IC,1•1.ty ot tfte pr111&1y c:oo11.nc 1ftall be 11.al.t ... tor

•• ~ 1. 0 .. c119na CCII IQUlV~ft I•Ul, a.n• .. AlfLIWtLtD1 MCIOla 1, 2, J, 4 &n4 S

AS:!Qla

•· Witft ch• 1pecific 1c:t1v1cy of cne pru.arp coo1aa• > 1.0 .c~/~raa · OOSI IQOlVALlllT I•lll tor •r• cnu 41 "°"'"• clul'iftt one- conun1.1o1.1e cu. lncerrel or HceecU.n9 en. uau U.aie • ....._ oa f19'1r• J. 4• 1, =• ia &C lea1' llO'f STAllOll wlta T c SOO•r w1&a1a t h.._a •. .... --

D. Vita tfte 1pecU1e an1•1ty of tftie piM.ly coolan > 1001i .ct/9r~ • be i.a a& lean ltOf S'fMOIY witJa T

1"9 c SOO•• w&.&JU.a I l'lftrw.

MOOll 1, 2, J, 4 ~ S

•• Wl.tll Ch• •pecUl.c •ftl.•1.ty of t1l91...ttr:Mllkyl-OOtl IQOt~ l•1J1 or > 100/ ana1y•1• req\11z ... nt1 of l.t .. H'Cl•Uy of the pri.llU'y c:oolu

SQ'llVIII.t.AllCS UQGlWI ........................................

,.

•pee:-.!:.; Li.mi.:1.

•.•.I tl'l• .,..u1e an1•1ty of tne P•ia&IT coo 1 1:le 4ee•n1n•4 : = ~• wL.tl'U.a tfte l.~t• ., pecfonance of ill• 1-.u. .. ...a aaalyai.a pr09ru Qf

J/4 •-ao

•

•

&IA'iXQI CQQ4K'[ SXSI!ll

gypnpSJU PIQDCTIOM SYSTEMS

Suaft~ UQUtlllXD'TS

a.~rforaance of a CHA!fll!L Fi.JMCTIONAL T!ST on che POPS acCUACion' . channel, buc •~~ludin& valve o~aracion, vithin 31 day1 prior co~

enc•rin& •condition in ~ch ~h• POPS ia requi~•d OPERAJLE 1~~-+ 1~1"¥\u. f»"" ~I dojs #ic.rt.o• ,., w.,e.,, ~ PoPS i.1 ~~u•r~ OPERAet:e. ~ Perfor.ance of a CHAMMIL CALillATlOll on Ch• POPS accuacion

channel at le~nc• per ll •ncn.. · ~ "-- / -~ _,.,,/' ----- /

c. Verifying che POPS i1~ la o~c once per 72 hours vhen ch• POPS i1 bein& ~•d for overpre11u.r• proceccion.

d. Tucin1 punU&nC co Speciflcacion 4. 0 .. 5.

4.4.9.l.2 Th• RCS venc(1) shall be verified co be open at lea1c once per 12 hour•* vhen rhe venc1(1) ia being ~•d for overpre11ur• protection.

,,

•!ace,c vheft ch• venc pachway i• provided vieb a valve vhicb i• loc~ed. ,1ealecl. or othervi•• Heu.red in ch• open poaition, then verify these va l.·•es open ac leaac one• per 31 d&ya .

SALIK. • UHl't l J/4 4·ll 150

•

•

.-• ~ . - .

--~t::·:~~I~:-.·~-:~-~

••

•

---~~;!~c ~~~~·" ........... ,.:;......~ . • -:;..":·;:- .!-

p

PPGllffil - u ___ ,___ _,£~-cog CQPU.,,-m;;;;?·--''5':~tJD..· taxi

•

~i '~ ~ .""" 'I

l.5.5 r~. rtfutlf"f •lttr StQflg9: e1na

1. -' eont•f "" volu• of eei,.. .. lM,500 1tt4

l'.t. .. DOPOft:· eOftClfttfltfM of ~tWtttt 2 ,JOO .,.,,

e. 4 11tf 1ttn11e w1t•1t U1•1r1C1i,. of 35-tr·.

tit: .. ,.,.. APttUCM f UTT:- ~EIS l. Z • l &ft4 •. ... . _ ,.

-~J}f.~.: ~~t~~-:: "':- ._.. . ACT ro": '.'';~ . ..;-::;':'_~ -~. .

.~~~?t:-~f~,~--~-~ Wt t,. tft• ,.,,ue11rtt •• i ... ttOf'lt• tlftlt f "°''"''•· ,...,,,. tit• UM to QllllJI~.;. :. natut wtUtffl 1 "•r or b• fft ., lHSt HOT STAIUIY •1tltfll .......... 1 .. caL~:..-... .•·• • •

·. . ...... , Yefii')'fftf tfte.IC t ...... t..,.

~ u .. ernure ts c 31.,. · .. ~·· .

zr-· . , ...

1 .

. . . ~--~ ... . .. .. ::-

···: . ..

'~;-,~ ~"t;:,'/;' ' /;:'. ·, :;:.. ' ef ~ ~!f ~:~~~~~.

i

•

•

•

3/4.6 CONTAINHBNT SYSTBKS

3/4.6.1 PRIMARY CON'l'AINMBN'l'

COHTAINMBHT IHTWQR:ITY •

LIMITING COND:IT:IOH POR OPBRAT:IOH ••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••• 3.6.1.1 PrimAry CON'l'AJ:NKBNT INTJ:GR:ITY shall be maintain•d.

APPLICABILI'l'Yz MODBS 1, 2, l and 4. ~

ACTIOH1

Without primary COH'l'AJ:NllJDIT DITBGRI'l'Y, r••tor• COHTAJ:HllD'f IH'l'SGR:I'l'Y within one hour or be in at l•••t HOT STANDBY within the next 5 hour• and in COLI> SBlJ'n)()Wlf within the following 30 hour•.

StJRWILLANCS RBQOIRlOIBNTS

••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••• 4.5.1.1 Primary COH'l'AJ:NKJDl'l' INTIGRITY •hall be. demon•tratedr

a. At. l•••t. once p•r 31 day• by verifying thats

1. All penetration•* not capable of being clo••d by OPSRABLB containment. automatic i•olation valv•• and required to be clo••d during accident. condition• are clo••d by valve•, flange•, or deactivated automatic valve• ••cured in eir po•ition•, except. for valve• that. are opened under ~ admini•trative control a• permitted by Specificatio 3.5.3.~ and

2. All equipment hatche• are clo••d and ••al•d.

b. By verifying that each containment air lock i• OPSRABLS per Specification 3.5.1.3.

c:. At 1-a•t once per 12 hour• by verifying that th• •urveillance· requirement• of 4.6.2.3.a are met for pesietration• •••oaiated with th• c:ontaima.en~ fan coil unit•.

d. At l•••t once per 18 moDth• by verifying that: the •urveillance r•quir.-.nt• of 4.6.2.3.ci are met for penetraticm9 •••ociated with th• contaimuAt fan coil unita.

*Bxcept vent•, drain8, t••t: cosmeatiOD9, etc:. which are (1) one inch nominal pipe diameter or -1•••• .... (2) ... located in•id• th• contaim1911t, and, (3) locked, sealed, or oth•rwi•• ••cu.red in th• clo••d po•ition. Th••• penetration• •hall be verified c:lo••d at l•••t once per 92 d•Y•·

SA.I.Bii - OHIT 1 3/4 6-1

.... ·. _ ... ~ ... ·.~·. • .. ,.,_ :·-···-___ .... ,,._ ......... -··-··-·····-·····'"

~ CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE

LIMITING CONDITION F~ OPERATION

=============================-~==============================--=========-- ----

3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate (Type A test) in accordance with the Containment Leakage Rate Testing Program.

b. A comb~ned leakage rate in accordance with the Containment Leakage Rate Testing Program for all penetrations and valves subject to Type B and C tests.

APPLICABILITY: MODES l, 2, 3 and 4.~ ACTION:

With either (a) the measured overall integrated containment leakage (Type A test) not in accordance with the Containment Leakage Rate Testing Program, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types s·and C tests not in accordance with the Containment Leakage Rate Testing Program, restore the leakage rate(s) to within the limit(s) prior to increasing the Reactor Coolant System temperature above 200°F.

SURVEILLANCE REQUIRE?-iENTS =============--======----===

4.6.1.2 The containment leakage rates shall be demonstrated as follows:

a. Type A tests shall be in accordance with the Containment Leakage Rate Testing Program.

b. Type B and C tests shall be conducted in accordance with the Containment Leakaga Rate Testing Program.

c. Air locks shall ba tested and demonstrated OPERABLE in accordance with the Containment Leakage Rate Testing Program.

·enera tor eplacemen valves en in Mod will im.mobili The ne-time e~mption

SALEM - UNIT l 3/4 6-2 Amendment No. 207

/

• CONTAINMEH'l' S'HTIXS CONTAINMENT S'l'P.1J~ IH'l'EGRI'rY

LIMITING CONl)ITIOHS l'OR OPERATION

3.6.1.& 'l'he at:ructu:al intec)rity of th• containmmit ahall be{maintained at a level conaiatmit with the acceptance criteria in Specificat~ 4.6.1.6.1..

APPLICABILITY: MODJ:S 1, 2, 3 and 4.

ACTION:

With the at:ructural inteqrity of th• cont&iftllll9nt not contozminq to the above requir-...nta, reatore the atructu:al inteqrity to witlU.n the limit• prior to increaainq the Reactor Coolant Syatem tmm;perature above 20091'.

StJRVl!ILLANCJ: RJ:Q1JI~S

4.6.1.6.1 Contaiftllll9ftt Surtacea The at:ructural inteqrity of the expoaed acceaaible interior and exterior aurfacea of th• containment, includinq the liner plate, ahall be detezmined in accordance with the Containment Leakaqe Rate Teatinq Proqram.

4.6.1.6.2 Report• Any abnozmal deqrad&tion of the containment at:ructure detected durinq the above required inapectiona ahall be evaluated for reportability purauant to 10Cl'll50.72 and iOCJ'RS0.73. 'rh• evaluation •hall be doc:um9nted and ahall include a d8acription of th• condition of the concrete, the inapection procedure, the tolerance• on crac:kinq, and the corrective action taken.

-SALDI - CHI'? 1 3/t 6-1 •-ndeent Bo. f 81, 207

CONTAINMJSHT SYSTJD{S

CONTAUJMmrr VINTU+ATION SYSTIQI

LIMITING CONDITXON FOR OPBRATION

~-···~········································································

3.6.l.7 Th• containment purge •upply and exhau•t closed. (Valv•• immobilized in •hut po•ition with operator• i•olated and tagged out of ••rvice).

APPLIC,ABILITX: MODBS l, 2, 3, and 4.~

ACTION:

i•olation valv••* shall be control air to valve

With on• containment purge •upply and/or exhau•t i•olation valve open, close the open valve(•) within one hour orb• in at leaat HOT STANDBY within the next 6 hour• and in COLD SHUTDOWN within the following 30 hour•.

SURVBILLANCB RBQOIRBHBNTS

············································································~·

4.6.1.7 Th• containm•nt purge •upply and exhauat iaolation valve• •hall be determined clo••d at leaat once per 31 day•.

..

granted th• c:ontai nt purg• •u y 1111d/or iaolation v v•• open in and 4 fo owing the • aa

(1R13). Th,,.-:CY1lll1ll&~~_.t.;S.a..,, or having t valve• open limit•d to'~Olillil&loa!IUL...L.11.2.J:....Jii~~ Bach valv will b•

nitial •ntry nto Med• 2. into Mod• allowing lR

*Th• c:ontainm•nt pr•••ure-vacuua relief i•olation int•rmittent baaia, under admini•trativ• control, requirem•nt of Sp•cific:ation 3.6.1.4.

valv•• may b• open•d on an a• n•c•••ary to ••ti•fy th•

SALBll - ONIT 1 3/4 6-Sa Amendment No. -4-h

I

206 I

•

CONTAINMEN'l' SYSTEMS

SPRAY ADDITIVE SYSTEM

LIMITING CONDITION FOR OPERATION ~••ma-.a•=-=:~•----•Ja..••awa -.---~--•••----•18aa_,,aa..,,-m,......,.,._ .. .,...,....,..,._._ .... ..,._,,.,...,.

3.6.2.2 The spray additive syatem shall be OPERABLE with:

a. A spray additiv. tank containinq a volume of b.tween 2568 and 4000 gallon• of between 30 and 32 percent by weight NaOB solution, and

b. Two spray additive eductors each capable of adding !faOB solution from the chemical additive tank to a containment spray system pump flow.

APPLICABILITY: MOOBS 1, 2,. 3 and 4.

ACTION:

With the spray additive ayatem inoperable, restore the ayatem to OPERABLE statua within 72 hour• or b9 in at leaat BO'r STANDBY within tu neat 6 hours; restore the spray additive ayatem to OPEltABLB atatua within th• next 4a hours or be in COLO SHtJTDOWH within th• followinq 30 houra.

,. SURVEILLANCE REQtJIREMEHTS =--a=, ........ .,... ..................................................................... .., ........................ ~.---=~=====

4.6.2.2 The spray additive natrated. CPZRABLlt:

a. At leaat once pez: ri.fyinq that each valve (manual, power opera tic) in th• flow pat&. that is not locked, sealed, or othnW:i: .. ~ecured in poaition, ia in ita correct poaition.

b. At leaat once per 6 month• by:

1. Verifying the aolution level in th• tank, and

2. Verifyinq th..-·concentrat:ion of the Na08 solution by chemical analysi11.

c. At l•a•t once per 18 month• durinq ahutdown, by verifyinq that each. aut:omati.o valve in th• flow path. actuatea. tO> it• correct poaition on a Containmmit Biqh-Biqh preaaure teat signal.

d. At .. leaat .once .per .S -Y•ara .. by:

1. Verifying a NaOB solution flow rate of 12 ± 3 gpa from the spray additiv9 tank through sample valve 1CS61 with the spray additive tank at: 2.S ± O.S paiq and

I I

SALEM - UNIT 1 3/ol 6-10 Anmndmant No. 122 I

• CONTAINMENT SYSTEMS

SURVEILLANCE REQUIREMENTS (Continued) ==============================================================================

4.6.3.1.2 Each ~containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a. Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.

b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.

c. Not used.

d. Verifying that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates to its isolation position.

e. Verifying that the Containment Pressure-Vacuum Relief Isolation valves are limited to s 60° opening angle.

4.6.3.1.3 At least once per 18 months, verify that on a main steam isolation test signal, each main steam isolation valve actuates to its isolation r position.

4.6.3.1.4 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its l~mit when tested pursuant to Specification 4.0.5.

4.6.3.1.5 Each containment purg isolation valve shall be demonstrated OPERABLE within 24 hours after ea h closing of the valv , except when the valve is being used for multiple cyclings, then at least once per 72 hours, by verifying that when the measur leakage rate is added to e leakage rates determined pursuant to Specif'cation • for all other Type Band C penetrations, the combined le kage rate is leG:t[han ore l to 0.60La.

i+~G.. I.~· 4.6.3.1.6 A pressure drop test o identify excessive de radation of resilient valve seals shall be conducted n the:

a. Containment Purge Sup once per 6 months.

b. Deleted.

SALEM - UNIT 1 3/4 6-13 Amendment No. 189

.. i.

Pt.AHT SYST!HS

SUIVIIU.AMCI R!QUIUMllftS ( Continmcll

J. Snubber rel .... • rate. where required, i• within th• · siaecif i•d rans• in compr•••ion or tenaion. For snubbers specifically required not to di•place under cantinuou. load, tbe ability of th• snubber to witti.tand loacl without

• diaplacm11nt shall be verif i•d. '

t. Snubber Servic• Life Monitorin1

A record of the ••rvica life of uch mubber, th9 d••ipat-4 ••rvic• life c09lllllllc .. and the inata •intuanc• racoru an vhich ti. da9ipated se shall be •intainecl u required by Spacif lcati

Conc:urrct vit!a ti. first iuentc:a 'linal ina· once pe~ 11 80fttba tmnafter, the iutallation ~c• record& for eacb aubber •hall be mi...- to qrif y that th• indicated .. rvic• life baa not b..a esc...s.cl" or vill not be exceeded prio~ to the nui scheduled snubber servfca Jff1 review. If the inclic:at-4 service life vill be uc811ded· prio~· to the nut scheduled snubbe~ .. rvtce life reviw, ti. llNbbal' Mrrice-· life •ball be reevaluat94 o~ ti. mubber shall be Nplac:M.ol'·recoaditionecl •o as to Utand iU 1amc:a life beyotMl tha c1aca· ot: t'ile nut scheduled .. nic• life rwiw. Thi• ~aluati• ... raplac • nt or

·ncoaclitioniq shall be" imlic:ata4 ill.Cb& racftda- ,.

::. - )·~ .

... ~~ ·:~ '! ~ ....

H • .:.- ·r~ : & • q~..:' , .. -~, ;, .: •. · : .:;. • ..:. .~;~_t,.·

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··- ~~·-~-~-. -·-·· ~ ·~: ·• ._,

"'.). :: ·:! r

··. ·-: ....... ~... ... .. ,

. . SALIN • UMl'f 1 . _3/4. T•lf · ...

.. ... - .. ·- .., · : ,. mat No. 93

~

. -- -. '°"' .......

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PLANT S'tSTD4S

3/4.1.10 CHILLED WATER S'tSTD4 • AUXILI..l.P.Y BUILDING SUBSYSTD4

::M!TING CONDITION FOR OPE~TICN • ••••••••--••---•••••••••••••••••••••••••••••••a••••••••••••••••••

3.7.10 7h• chilled water.system loop which services the safety-related load! in the A~x1l1ary Bu1ldin9 shall be OPE~t.E with:

a. 7hree OPE~LE chillers

b. 7wo OPE~LE chilled water pwnps

JUIPL!CABit.ITY: ALL MODES and durin9 movement of irradiated fuel a!seml,)l~es.

ACTION: MODES 1, 2, 3, and 4

a. With on• chiller inoperable:

1. Remove th• appropriate non-essential water system within~

/ c~~si..e: 2. Restore th• chiller to opeulllr su

_/

3. Se in at SHUT~OWN within the followin9

heat loads from the chil!ed

us within l4 days or;

6 hours and in c~t~

b. With :wo chil!ers inoperable:

c:.

l. Remove the appropriate non-essential heat loads from the chil:ed water system within 4 hours and;

2. A.li9n th• control room emer9ency air conditionin; system (CR~Cs1 for sin9le filtration operation usin; th• Salem Unit 2 train within 4 hours and;

3. Restore at least on• chiller or;

4.

tus within 72 hours

6 hours and in COLD

ter pump inoperable, restore th• chilled water atus-within-7-days or be in at least HOT STANDS~ ours and in COLD SHUTDOWN within the following 3J

hours .

3/4 7-33 Amendment No. SALEM - UNIT l

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&~iC7R+C.QL PCWER sxs;;Ms

;,s-·.10LT p.c. CISTRIBtJIION - QPERAT!~G

L:M!T!NG CONDITION FOR OPERATION

3.8.~.3 Th• fO"llowing o.c. bus trains shall be OPERABLE and energized: ..

TRAIN ~A consisting of l2S-volt O.C. bus No. lA, l2S-volt o.c. battery No. lA and battery charger lAl.

TRAIN lB consisting Of l25-volt O.C. bus No. lB, l25-volt o.c. battery No. lB and battery charger lBl.

TRAIN lC consisting . lC, 125-volt O.C. battery No. lC and batte

APPL;CYIL!TY: MOOES l, 2, 3 and

AC';'!ON:

a. With one l2S-volt o.c. bus inoperable or not energized, restore the inoperable bus to OPERABLE and energized •tatu• within 2 hour• or be in at lea•t HOT STANDBY within the next 6 houra and in COLD SHUTDOWN within the following 30 hour•.

b. With one 125-volt o.c. battery charger inoperab:e, re•tore the inoperable charger to OPERABLE 1tatua within 2 hour• or connect the backup charger for no more than 7 day• or be in at leaat HOT STANDBY within the next 6 hour• and in COLD SHUTDOWN within the following 30 hours.

c. With one or more 125-volt o.c. batteri•• with one or more battery cell parameter• not within the Category A or B limit• of Table 4.8.2.3-l:

l. verify within l hour, that the electrolyte level and float voltage for the pilot cell meet• Table 4.8.2.3-1 Category C limit•, and

2. Verify within 24 hour•, that the battery cell parameters of all connected cell• meet Table 4.8.2.3-1 Category C limits, and

3. R••tore battery cell parameter• to Category A and B limit• of Table 4.8.2.3·1 within 31 day•, and

4. If any of the above listed requirement• cannot be met, comply with the requirement• of action f.

d. Wi.th one .or more l25·volt o.c. batterie• with one c:r more battery cell parameter• not within Table 4.8.2.3·1 Category C values, comply with the requirement• of action f.

e. With average electrolyte temperature of repre•entative cell• les• than &s•F, comply with the requirement• of action f .

f. Reatore the battery to OPERABLE statua within 2 hour• or be in at lea•t HOT STANDBY within the next 6 hour• and COLD SHO'n)OWN within the following 30 hour•.

SALEM - UNIT l 3/4 8·8 Amendment No. 177

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~EFUELt~G Q?(AATtONS

CRANE rqAVEt • FUEL HANOlIN6 AAEA

LI"lTtNG CONOITIOll FIJI OPIAATtON

3.9.7 l.Dads 1n 11c1s1 o' 2200 Pounds s"1ll OI ?ron101t1d from tr•vel over fuel assenettes 1n i;.ne storage Pl'>Ol •

A?P\.tCABtLtTY: ll'lt,, '·Jel usel!'I011es 1,, t"'• S~r191 ;J.lOl.

W1tl'I t"'• requ1r1nwnts of tP!e •bOve si:>ecH1cat1on rot Hthf11d, phct t"e cr•n• load 1n 1 Sift i:andttton. The provtstons of SpecHtcuton 3.0.3 are rct 1ppltc1blt.

SURVEILLANCE ~EIJJIREMENTS

4.9.7 The overload cutoff •nt~s crane travel wttl'I loads tn 11c1ss ~f 2200 pounds o~•r futl assema}1es snail·~ dt""nstrattd OP€RABLE witl'ltn 7 days prior to crane 1JH and at lfntA~Ptr.)7 days t,.,erufttr durtng t"'• crane operation. / "'~ \

I vri(.L 1

1~J

SALE~ • UNIT l 3/4 9.7

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LIMITING CONDITION FOR OPERATION

3.9.8.1 At least one residual heat removal loop shall be in operation.

APPLICA!IL!IY: MODE 6.

ACTION:

a. With less than one residual heat removal loop in operation, except as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetrations providing direct accesa from the containment atmosphere to the outside atmosphere within 4 hours.

b. The residual heat removal loop may be removed from operation for up to 1 hour per 8 hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

c. The provisions of Specification 3.0.3 are not applicable.

SUR.VEILU\NCE REQUIR.EMETS ,.

4.9.8.1 At least once' per 12 hours one RHR loop shall be verified in operation and circulating coolant at a flow rate of:

a. greater than or equal to 1000 gpm, and

to maintain the RCS temperature at less than or equal to

SAi.£M • UNIT l 3/4 9-8 Amendment No. 109

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I I I)-: : : 3.g. lJ ~:Just/ 23 '~et ~f wa:er s!'lal l ~e '1Ti1ntaf,,ed over :ht too ; ; of :ie l"U,::r ;irusul"'~ssel fl an gt. 1 I ' I 1 '.l?=t.::.!S!L~~ ':'Dveme"t of ~'Jtl assembHes o,. :ol"ltrol ~ds .-H~i,, j j :rie ru,:or .:ires sure vessel .. nil e in ~DE s. i I ~C~!'J~: .

t !.,..;:!'! :~e r!~uirements of :!'le above s~e~1ffc:at1on not sathffed, 1 ~al1 o;,eratiOl"IS fnvolvfMg ~vement of !l'Jtl usembl f es or c=ntrol !:!'le =iressure vessel. ~!'le ;ircvisions of S;iec:ific:ation 3.~.l art ia~~l ic:able.

1 I. l: l I : ! I! I I

: i I I

I' l I I I I I

! l : I I I

11

11 , , s1·~·,~r 1 ' ~c~ ~£OUIREMEHTS I\ WI"\-··- - -I I

sus.,tnd r"OdS wf:hin not

,.

: ~ l.1.10 711• -..cir Tevtl stit111 bt determined to bt a'! .hut fts minimum 1: l"!~uirtd depth within Z !'!our1 ;:rior :o tht start of and at 1 east once ! : ;:er Z4 hours. th1rt1ft1r during :rovem1nts of ~uel usembl hs or contro 1 . , I ; 1 ~ods. •I I I : I

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'. \ SAl.~!'1 ..; U~tT 1 3/4 9-10 AZ-IENCMEMT ~O. 23

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.. 3 ~J ~ ~e S~WM ~~.~ requ1remenc of Spec1f~cat1on l.l l ~ s·..;.s~er.ded ~or :nea111urement of control rod worth and 1hucdo rg· p ::-.e re.sc-:: ~ ·1 -:. -::·1 equ:. ·1.slenc co ac lea1t th• hi9he1c e1c1uca control ro ..,orth ~9 &va1~.u:i~e !or '::-lp i.n1ertlon from OPIRAILI control rQdl1l .. ~ (. 1

Y, • ) "«ii t.: ;,;a : :. :;x ~c; 2 . . __ ~'---"

&. W1ch any full length control rod noc fully ia•erced accS •ich le11 than ch• &Dove reacc1v1cy equivalent availal:)le !or trip 1n••rcian. 1a11M1diacely :.nic1ace and conc1nu• b0rac1on ac a Jl gpa of a 1011.u:ion containing I ~ 6.560 ppm bOron or lCI equivalent \Jllt1l the SHO'TDOWll ~IR re~1red Cy f Spec1f1cac1on 3.1.l.l 11 r11cored.

b. ~ich all full ~enqch control rod• 1n1erted and the reactor •~critical 'r:ry ~e11 than the above reactivity equivalenc, i.amediately initiate and conunu• borat1on at z ll gpm of a 1olutiOG ccmcainin9 ~ ,,5,0 ppa eic=cm or 1c• equivalent until the SHt1TOOWll !GJGIW re~ir•d by 9pec1ficacicn 3.l.l.l 11 reacored.

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t.lO. l.l '!"he po•1c1on of each full length Uld p&r1: lengch rocS either parually or l'tTU.Y WI'na:IRAMll 1hall oa determined at leuc aace per l hour•.

t.10.1.l Bach full l•n~h rocS not fully in•erced 1hall oa deml:m1craced cap&Dl• of full 1n••rtica when tripped frc:m ac leaat ch• so• •ithdrawn po11c1on w1chin lt hour• prior co reducing ch• SKtrn)Otlll ~1• co le11 ch.an :h• l1m1c• of Sp•cificatian 1.1.1.1 .

S.Al.D · :."NIT l. 3/4 10·1. Amendment No.145

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.. TABLE 4.11-2 (Continued)

TABLE NOTATtON

a. The LLD is defined in Table

b. The principal ga11111a emitters for which the LLO specification applies exclusively are th• following radionuclides: Kr-87. Kr-88, :ta-133, ~-l33m, 14!·135, X.-138 fer gaseous emissions- and Mn-54, Fe-59, Co-58, Co-60 •. Zn-65, flb-9~• Cs-134, Cs-137, C•·l4l and Ce-144 for- particulate emissions. This 1 fst does nat IT9tn that only tnesa nucl 1des are to be detected an4 reported. Other peaks that are measurable and- identifiable, togeth1r with th• above nuclides, shall also. be identified and reported.

c. Sampling and analysis shall also be perforl!lld following shutdown--. startup \ or a THERMAL POWER change that. within one rour, exceeds 15 percent of RATED THERMAL POWER unless:

l. Analysis snows that the DOSE EQSIVM.£Nt I-131 concentration in the . primary coolant nu not increased nare than a factor of tn,..e.

z. Th1 noble gas activity nanitor snows· that effluent activity has not incrtas-6 by rrara.tnan a factor of three. ~

d. Trit1um grab samples shall be taken at least one• per 24 hours wne-n the refueling canal is flooded.

e. Tritium grab samples shall bl taken at least once p1r 7 days from the ventilation exhaust fros the spent fuel pool area whenever spent fuel is in the spent fuel pool. ., ..,.

f. Tht ratio of the samplt flow rate ta the sampltd stream flow ;iltt shall be known for the time period cawrtd by each dos• or dine rat• cal cul at ion made in accard1nca with Specifications 3.ll.2.l. 3.ll.2.2 and J.ll.2.3.

SALEM •- UllT 1. ---· 3/4 11-10- Aii&*)t•&t No. 64

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MAC::OB C99WT SY.Jlla

IASIS

••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••

J/!.!.1 SPJC?PIC &c:tIVIII

Tft• liaitation• on th• 1pecif ic activity of the priaary ccolant eniure

that th• !eeultin; 2 hour do••• at th• tit• boundary vill not exceed an

appropr1ately 1mall fraction of Pa~ 100 llait• follovin; a 1team qeneracor

tub• ~ptur• accident 1r conjunction vif h an a11"8ed 1teady 1t1te

pri.111.Lry-to-eecondary 1teaa 9ener1tor le1k19e rate of 1.0 OPN. Th• value• tor

the liait• on •pecif ic activity repr•••n• interia 11.aitl ba•ed upon a

par ... tri.c ••aluation by th• N1lC of tntical •it• location•. Th••• valun are

coneer"f'ative in that 1pecific 1it• par ... t•r• of the Sal .. 1ite, 1uch a1 •~:•

boundary location and meteoroloqical condi~ion1, were no• con1id•r•d ~:i ::i~•

evaluation. Tft• N1lC i• finaliain9 1it• 1119cific criteria vhicn vill be u1ed

a• the ba•i• tor the r .. valuation of the 1119cif 1c aeti•1ty li.ait• of th11

eite. Thi• reevaluation may re1ult in hi;her liait•.

~ Reducin9 T ..t'·~

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1) Allowaltle coimlt1MUo.w of pru8'&re u4 t._.rat\ln to~ 1pec1t1c c....-rat\lr• cft&n1• rat•• •r• ti.low ~ co cae r1.-c of t~ li.ait lin•• 1"°"'9. L.J.aic l1n•• tor cooldc:Nll rat .. becw..n tho•• pr•••n:1a

obta1n•c& by int1rpolat1oa.

2 > °"'9H Uau u.a .. •ball be calc"latM s-r1o.&1cau1 us.q •thod.I pro•1.d•d ~1-. .

J) '"'9 1econ4.ary 11da of ch• ac ... 1 .. racor mat DOC M pnanril-' above 200 pe11 if ti. c....-rat\lr• of ct. ,, ... 19D9raco1 1• bela. 70 r.

4) The pnHvUer hutl.&p ancl CHldc:Nll rat .. •ball llOC UHM 100°1/hr and 200°1/hr. r..,.ctiwel1. ~ 1pr11 1ball noc b9 ~ if c..b9 t..P.rac~r• difference betVlltlD tbli pr1a8\&rl1er IDA ta. ••r•J flu1• 1• rr-ac•r :hAn 320~. •

.5 > Syn• prue"tce hydrotHU an4 1n·••nice lua IM tr,drotuu •hAll ~ pedor.M at pn•.vu 1n accorc&.aace wt.ca c..b9 ~1r-u of U>ll &oi~er ~cl PTe.e...-. Ve•••l Code. Section XI.

~ tract\ln tout ... •• properti•• of the fP-!'itlc .. ce1iall ta t!le r-.ccor YHMl ar• date~ in accord.Mee vita taa MIC StaM.ad lni• Pan, A.Sn1 !ll.5•12, an• ta accorr&.ftc• wtth acidltlonal r .. ctor Y'e8Ml r~1r..anc1. ~••• propert1 .. are t!lila ... l\l&tacl 1n accord.lac• wttb Ap~la ~ of en. l976 s~r Addutda te S.Uoa Ill d the UHi loUH w PTHIUe v .... 1 Cod• anc& :~.

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PLANT SYSTEMS

BASES ==============================================================================

3/4.7.9 ..

SNUBBERS

All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic· or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on nonsafety related systems and then only if their failure or failure of the system on which they were installed, would have no adverse effect on any safety related system.·

A list of individual snubbers required to be operable per the technical specifications with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section S0.7l(c) of 10 CFR Part SO. The accessibility of each snubber shall be determined and approved by the Station Operations Review Committee. The determination shall be based on the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.) and the recommendations of Regulatory Guide 8.8 and 8.10. The addition or deletion of any snubber shall be made in accordance with Section SO.S9 of 10 CFR Part SO •

. The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failur nd i determined by the number of inoperable snubbers found during an ins performed before that interval has elapsed may be used point to determine the next inspection. The inspection each category of snubbers. The snubbers are cacegorized -.&._...-='...,.. (i.e., accessible or inaccessible during reactor operation). The next visual inspection for each category may be twice, the same, or reduced by as much as two-thirds of the previous inspection interval. This interval depends on the number of unacceptable snubbers found in proportion to the total number of snubbers in each category from the most recent inspection. Intervals may be increased up to 48 months if few unacceptable snubbers are found in these inspections. The visual inspection interval will not exceed 48 months. However, as for all surveillance activities, unless otherwise noted, allowable tolerances of 25t are applicable for snubbers. Table 4.7-3 establishes three limits for determining the next visual inspection interval corresponding to _ _ the -populatio-n of each category of sn-ubbers. - For a category that -differs from the representative·-sizes·· provided;;·---the-vaiueirfor the n-ext inspection interval may be found by interpolation from the limits provided in Columns A, B, and C. Where· the limit for unacceptable snubbers in Columns A, B, or C is determined by interpolation and includes a fractional value, the limit may be reduced to the next lower integer. The first inspection interval determined using Table 4.7-3 shall be based upon the previous inspection interval as established by the requirements in effect before amendment (161). Any inspection whose results require a shorter inspection interval will override the previous schedule.

SALEM - UNIT 1 B 3/4 7-6 Amendment No. 161

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DESIGN FEATURES

DESIGN PRESSURB AND TEMPERATURE

.. . 5.2.2 The reactor containment is designed and shall be maintained for a maximum internal pressure of 47 psig. Containment air temperatures up to 351.3°E' are acceptable providing the containment pressure is in accordance with that described in the UFSAR.

5.3 REACTOR CORE

FUEL ASSEMBLIES

5.3.l The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of zircaloy or ZIRLO clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

CONTROL ROD ASSEMBLIES ,.

5.3.2 The reactor core shall contain 53 full length and n~ part length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.

5.4

DES ERATURB ·

coolant system is designed and shall be maintained:

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SAL.EM - UNIT 1 5-4 Amendment No. 198

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sucb that: a major porticm of the body cuJlct ncaiw in c:na bar a dam in .. mrm locatad within lEgll ~, sudl • .PMR

CXl1tai.rlnllil, ~ m encL exists tar Pltl) - of lcx:ld.n:J, ans no 8nclmure can azam tha inlivimal anu, thm· that

rqm ott, iaDwly pamt.t and a fl•mhinJ light llhal.l i:. activate aa a waminJ • In lim of tha stay ti.- specitic:aticn ot tha RWP, clirect: er - ..... of cl.cald circuit TV WU) a:mt.imam