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Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2
	ML18107A517
Person / Time
Site:	Salem
Issue date:	08/25/1999
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18107A516	List: ML18107A514; ML18107A517;
References
	NUDOCS 9909070073
	Download: ML18107A517 (122)
	v • d • e

I 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 Page I, Ill, V, VI, VIII, IX, XI, XII, XIII, INDEX XIV, XV, XVII, and XVIII 2-6 2.2.1 2-7 3/4 1-1 3/4.1.1.1 3/4 1-16 3/4.1.2.6 3/4 1-22 3/4.1.3.4 3/41-23 3/4.1.3.5 3/4 2-2 3/4.2.1 3/42-3 3/4 3~12 3/4.3.1.1 3/4 3-22 3/4.3.2.1 3/4 3-34 3/4 3-35 3/4.3.3.1 3/4 3-36a 3/4 3-37 3/4 3-38a 3/4 3-53 3/4.3.3.7 3/4 3-56 3/4 3-63 3/4.3.3.8 3/4 3-68 3/4.3.3.9

....~314-3-71 3/4.3.4 3/4 4-3b 3/4.4.1.4 3/44-8 3/4.4.5 9909070073 990825 PDR ADOCK 05000272 P PDR

'\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 Page 3/4.4.6.1 3/4 4-14.

3/4.4.6.3 3/4 4-16a 3/4 4-16b 3/4 4-16c 3/4.4.8 3/4 4-20 3/4.4.9.3 3/4 4-31 3/4.4.10.1 3/4 4-32 3/4.5.3 3/4 5-6 3/4.5.5 3/4 5-7 3/4.6.1.1 3/4 6-1 3/4.6.1.2 3/4 6-2 3/4.6.1.6 3/46-8 3/4.6.1.7 3/4 6-8a 3/4.6.2.2 3/4 6-10 3/4.6.3.1 3/4 6-13 3/4 7-31 3/4.7.9 3/4 7-33 3/4.7.10 3/4 8-8 3/4.8.2.3 3/4 9-7 3/4.9.7 3/4.9.8 3/4 9-8 3/4 9-10 3/4.9.10 3/4 10-1 3/4.10.1 3/4 11-10 3/4.11.2

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 l-l ACTION . . . . l-l AXIAL FLtJX DIFFERENCE l-l CHANNEL CALIBRATION *- l-l CHANNEL CHECK . . . . l-l CHANNEL FUNCTIONAL TEST l-l CONTAINMENT INTEGRITY l-2 CORE ALTERATION . . . . l-2 CORE OPERATING LIMITS REPORT l-2 QOSB EQUIVALENT I-131 l-2 E-AVERAGE DISINTEGRATION ENERGY l-3 ENGINEERBI> SAFETY FEATORB RESPONSE TIMB l-l FREQUENCY NOTATION . . . . . . . . l-l FULLY WITHDRAWN . . . . . . . . . 1-3 GASEOUS RAOWASTE TREATMENT SYSTEM 1-3 IDENTIFIED LEAKAGB . . . 1-3 MEMBER(S) OP THB PUBLIC .. l-4 OFFSITE OOSB CALCULA~:nt--fBIH\l:AL (OOCM) l-4 OPERABLB - OPERABI . 1-4 OPERATIC~ MOOB *

M 0 'D f£ l-4 PHYSICS TESTS 1-S PRESSURE BOUNDARY LBJ~~ l*S,,

PROCESS CONTROL PROGRAM 1-S PURGE-PURGING . . . . . l-5 QUADRANT POWER TILT RATIO l-5 RATED THERMAL POWER . . . . . l-5 REACTOR TRIP SYSTEM RESPONSB TIMB l-6 REPORTABLB EVENT l-6 SHUTDOWN MARGIN l-6 SITE BOUNDARY l-6 SOLIDIFICATION . 1-6 SOURCB CHECK .

1-6 STAGGBRBI) TEST BASIS l-6 THERMAL POWD 1-7 UNIDENTIFIED LBAUGS 1-7 UNRESTRICTED ARD * *

1-7 VENTILATION BXBAtJST TRD'l'MD'l' SYSTBM -* 1-7 VENTING . . . . * * . * . . . . . . 1-7

SALEM - UNIT 1 I Amendment No. 201

~

. ;~:f!ri!:< zoo*r. 3/'6 l*l Shuc:down Kar1in

T*v1 s zoo*r loroa Bll~*iaa. av1
~oderac:ar T..,eracur* Co.f f1c1enc
~
3/'6 l*5
!tin~ T....-racura far C:ic:icalicy 3/'6 l-6 3/4. l. 2 IOL\TIOll SYSTDIS Flow Padw
Shuc:dovft 3/li. 1*7 Flaw Pacn.
O,*rac:int l/4 l*I Ch&r1iq " -
Shuc:doft l/4 l*lO Ch&r11q Pump
O,*rac:in1 3/4 l* u Ion* A.ci' Trwfer ,...,.
SlNcuua ~
lol'ic Acid TH11af1r .,,...,.
0,H'Al1q 3'/4 1* 13 Q _./
lorac:ad Vac:ar SO\ll'cea
Shue:.,._ l/4 1*14 lorac:ad Vac:er SO\ll'cea
Operac:ina 3/4 1*16 3/4. l. l ltDVAIU COlftl.Ot. ASSIDUU GrCN1J Keipe 3/4 l*U Poeic:ioa Indicac:inc Sy1c:..
O,.racinc 3/4 l* l9 Poaic:ion Indicac:inc Sy1c:1..
Shue:.,._ 3/4 1*20 llo4 Dl'o, Tlae 3/4 1*2l Slluc:dowa lod Imerc:ioa Uaic: 3/4 l.*22 Conc:rol loci Iuerc:ian c.iaic. . 3/4 1.. 23
SA1.lll
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SECTIQM llmll LIMlTillQ c:olmrr?Olll roa OPIRATIOM AHD SUl.VIILLANCE REQUIUMIHTS 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 .3/4 Cold Shutdown .3/4 3/4.4.2.l SAFSTY VALVES
SHOTDONll .. ... . . .l/4 4-4 3/4.4.2.2 SAFETY VALVES
OPERATING . . . . 3/4 4-4*
3/4.4.3 RELIEF VALVES . . . . 3/4 4-5 3/4.4.4 PRESSUllIZD . .3/4 4-6 3/4.4.S STEAM GEHBRATORS . . .3/4 4-7 3/4.4.6 REACTOR COOLAH'l' SYSTDI LU~rAGS
.3/4 4-14
. 3/4 4-15 ,,.
.3/4 4*16&
DELETm 3/4.4.8 SPECIFIC: ACTIVITY . . . . . . . . . * * . 3/4 4-20 3/4.4.9 PRESSURS/TEMPBRATURS LIMITS Reactor Coolant Syatem .3/4 4-24 Preaaurizer . . . . . . . . . .3/4 4*29 overpr***ur* Protection Syat... * .3/4 4*30 3/4.4.10 STllOC'l'UDL nrrscDlITY ASMll coca Cl*** 1. 2, and 3 component* .3/4 4.*32 3/4.4.11 INTEHTIOllALLY ILAlllC .3/4 4.-34.
.3/4 t-35 3/4. 4 .12.
..HJAD vmrrs- .
SALEM
UNIT 1 v Amendment No.1ao
SIC'T!OM l/t 5 m*alHCX ;cu '99Lr* sxs' ,,ccn l/t.5.1 AC~TOU J/t s-1 l/t.5.Z secs suasYsTDll - r... 1so*r J/t S*l J/t.5.J ECCS SualYSTIMI
r.. c 1so*r l/t.5.t SW. IM.nc:TtO* ft.QV . . . . . I J/t.5.5 Rll'Ull.IHG WATD STOU.GI TAllK l/t,f comrmgr sxsmg l/t,l.l cancailulanc tnc_,ricy J/4*1-1 cancaiamanc t.caka9* . J/t 1*2
cancaimlmlC Air Lock8 J/t f*S J/t ,_,
Iacernal Pr***uz~ . . ,*
Air r-...racuz* . . . J/4 1*7 canca1D119AC SCr\&GCUZal IAc.,ricy 3/4 l*I eancaimlmlC veac11aciall Sytic.. . l/t ****
l/t.1.i l/4 , . ,
ccmca~c lpny symc.. .
3/4 1*10 Spray Mdiei.,. Sy9c* . . .
canca11111mlC cooliail Syac*
.. 3/4 l*ll 3/t l*U l/t.l.J l/t.l.t 3/4 f*U ll'JGOI* WlysH* 3/t l*U llaccnC ilydnfea IKCMUaUleH
SAUM
UlltT l Vt urtnac No. t i8

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>. . C
SOUlCtS 31:. 8*6
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~.c. O\str\but\on
Operat\nl . . 1/'6 8*8 A.C. O\stt\but\on
Shut4oWft t:5*VoLt O.C. u~sttibut\on
Operatinl 11:. 8-to t~5-VoLt o.c. Oistr\but\on
Shut4own )/'6 8-tt
s-VoLt o.c. Distribution
Oper1tin1 . "" 8*t1 28* * .: o.c. Distribution* Shut4oVft
)/I. 8* l" Et.£: :c>.L EQUt?M!Nt ?RO't! . :*:t uEV!CU .
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~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
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!ASES a l/
I l/4 J, t l l .-.ONITOlIMG :~S~UMl:N'l'ATtQN I l/4
3.
l .* :""..'11.IINS OVIRSPI~ rROT'IC'T:OK I l/4 l 't." suaoa cooLJ.ltT sxsm ilEAC'TOR COOIJ.HT :.ooPS ~ coot.ANT
R~J'U.TtON .* l/4 t*l.
)/t.t.2 SAlrt'Y 'J.Ul/IS .I J/4 t*l.a l/t.4.l Ut.IIW V.UV'IS .I l/4 t*l.a l/t.t.t rRS:SStraUD .* J/4 t*l J/t.t.5 STEAM ODIUATOlS .* l/4 4*2 Lt.t.6 il.EAC'TO& COOt.\HT SYSTD UA..11'...\GS .I l/4 4*l l.t.t.7 ~ E:t.r:'!?>
3. t t 8 Sr!CIF:C ~CTtVITY .I l/4 4*5 1:t.t.~ rRISStrU/TIMJDATVU t.IMITS .I l/4 t*I J. t. t. l.O ST1lUC'T'J1tAI,, UITIG&%TY .* l/4 t*l.1 1 ., t. a at.\NX .* lit **J.1
.I l/4 4*1.7
xt: Amendment: ~o
BAS BS SBCT:ION 3/4 5 BMBKGBNCY CORB COOL:ING SYSTBMS (BCCS)
PAGB 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 COMPONENT COOLING WATER SYSTEM . B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM B 3/4 7-4 3/4.7.S FLOOD PROTECTION * *
B 3/4 7-5 3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM * * * * * * * * *
0
B 3/4 7-5 3/4.7.7 AUXILIARY BUILDING EXHAUST AIR FILTRATION SYSTEM * * ** .
3/4.7.8 SEALED SOURCE CONTAMINATION 3/4.7.9 SNUBBERS 3/4.7.10 CHILLED WATER SYSTEM - -
AUXILIARY BUILDING SUBSYSTEM . . * . . * . ** 8 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES * * * * * * * * * ** * * * * * *
B 3/4 8-1 3/4.8.2 ONSITE POWER DISTRIBOTION SYSTEMS . * * *
B 3/4 8-1 ELECTRICAL EQUIPMENT .. PROTECTIVE DEVICES * * *
8 3/ 4 8-2 3/4.8.3 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 COMMUNICATIONS B 3/4 9;.Y' 3 3/4.9.S B 3/4 9-)' 3 3/4.9.6 MANIPULATOR CRANE B 3/4 9-,7 2
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BU,!LDING RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION B 3/4 9 7 3 3/4.9.8 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF 3/4._9.9 ISOLATION SYSTEM . . . . . . . . . . . . . B 3/4 9-;¥' 'f 3/4.9.10 WATER LEVEL - REACTOR VESSEL and AND B 3/4 9-J/' lf_
3/4.9.11 STORAGE POOL 3/4.9.12 FUEL HANDLING AREA VENTILATIO~ SYSTEM B 3/4 9-)/ y 3/4.10 SPECIAL TEST EXCEPTIONS
. * . * . .
B 3/4 10-1 3/4.10.1 SHUTDOWN MARGIN . . . .
3/4.10.2 G~OUP HEIGHT, INSERTION AND POWER B 3/4 10-1 DISTRIBUTION LIMITS B 3/4 10-1 3/4.10.3 PHYSICS TESTS B 3/4 10-1 3/4.10.4 NO FLOW TESTS ..
SALEM - UNIT 1 xv Amendment No.192
INDEX DESIGN FEATURES
===========.:======================================================
PAGE SECTION 5.1 SITE Exc~i:_~~on A-re-a-.-----.---,- -.--*-*--- '. ___'. __ . .__ ._ . . . . . . . . 5-1
,.,--Low Population Zone . . . . . . . . * .--. --;--. ; . -. -*- 5.:'."L_____ --~-
5 {~~a...,....g..,_~G-.... ....._~L~~** 5-1
=.__ .
Configuration . -1 5-4 Design Pressure and Temperature 5.3 REACTOR CORE 5-4 Fuel Assemblies 5-4 Control Rod Assemblies 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature *~~'--...
Volume ~
. 5-5 5.5 METEOROLOGICAL TOWER LOCATION 5.6 FUEL STORAGE
\
Criticality Drainage Capacity . .
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT
SALEM - UNIT 1 XVII Amendment No. 59
ADMINISTRATIVE CONJ'ROLS
========~==================================~=================s=====~
SECTION 6.1 ?.ESPONSIBILITY 6-1 6.2 ORGANIZATI_N Onsite and Offsite Organizations 6-1 Facility Staff . . 6-~ G.
Shift Technical Advisor 6-7 6.3 FACILITY STAFF QUALIFICATIONS. 6-7 6.4 TRAINING . . . . . . . . . . . . . . . . . . . . . . . . 6-7 6.5 REVIEW AND AUDIT (THIS SECTION DELETED) . . . . . . . . . 6-8 6.6 REPORTABLE EVENT ACTION 6-16 6.7 SAFETY LIMIT VIOLATION 6-16 ,,
6.8 PROCEDURES AND PROGRAMS 6-17 6.9 REPORTING REQUIREMENTS 6.9.l ROUTINE REPORTS 6-20 6.9.2 SPECIAL REPORTS 6-24 4,J 6.10 RECORD RETENTION 6-)< 02 s 6.11 RADIATION PROTECTION PROGRAM 6-26 6.12 HIGH RADIATION AREA . . 6-)< 2 7 6.13 PROCESS CONTROL PROGRAM (PCP) 6-~ 2g 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-,.M" ~ C\
6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6-)¥ z. '\
6.16 ENVIRONMENTAL QUALIFICATION 6-pf 3 0
SALEM - UNIT 1 XVIII Amendment No. 192
TAILE 2.2-1 tContinuedt l'F.ACTOR TRIP 519TDI lllSTRUMF.llTATIOll TRIP SETPOINTS
... TIU* snro1n ALLOWABLE VALUES IJ. . ._..__Generater It. . . ...,_ ..ter a t.01 of .. rrow ra.... l*Utr....nt
...--**c~ at*.. ....rator a 1.01 of .. rrow r*...-
pa*-**ch at......nerato1 l~atr..-..t
. .**t . . I fS. ....n.lt...--.stn a 2111 .olt*-**c:lli bu* a ZISO .olta-uch bu*
CMIMt . . . . .
II. ....lfH..lal:f ~-Ir a H.S ** - uc:lli bu* a S6.t la - **c:lli bu*
C.lMt . . . .
ll. hdtl* Tirllt A. 1.- Td* l p t - a es **lt a es **'*
llM*n s ISi off f*ll open I. h*t.e It. . Walft
ISi off full open ClM*n
. .t . . .11~**
lt. - - - cilel*t .... ..t .... 1<<:91*
lna--R heltl* Td*
.. . *~
~.A UJt llN I T I 1-6 "-enct.ent No. Ill
!AUl.~ ?.__:?_- !_ (Cont inut:d)
~.
r 1*1 HlAClUH IHIP SY~ILH IN~IHUHLNIATION lHIP SEIPOINIS
~
NOlATION '
HOil I:
lncHuted Al .at llAHll TlllHHAL Pm1£R I- " lodiuted T .al HAllll TtllkHAL POWU ~ ~11. 9°f
vg P " Pressurizer pressure. psiy
'"I
....... 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~ S 2
dVCJ 1 1 - Time consldnls ulilizt:d in the le.ad ldg controller for* I 'I - 30 ~a:c~.
~
2
2 "' 4 secs. ,......~,,.. ,_.....,Y avg s - L*Pl*ce tr*n>fo111 ope~~~~-~
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 rodo<s)and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod(*) is inoperal:>le. 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 roa LlKlTUIG c:mDl'!tC:.
OPDATIOll l.l.2.6 ~ 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. 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<lration water ay*t-*, r**tore th*
1tocaqe *y*t . . to OPl~ta atatu* within 72 hour* er be in at l***t HOT STAllDIY within the neat 6 hour* and borated ~o a SK'CJ'n)OW!f ~G:N equivalent to at l***t l\ delta~,~ at 2oo*r1 r**tor* th* boric ac~~
1toraqe *y*t . . to OP!RAlt.I atatu* w~thin the nea~ 7 ~*Y* o: ce ~n COt.D SKUTOOW'M within th* neat JO hcur1.
b. Wi~n th~ refu*lin9 ~*t*r 1tora9* tank inopera.bl*. r**t=r* th*
ta.nl& tc OP!RA.lt.I *tatu* within on= hour or b* in at l*a*t HOT STMDIY within the nu:t 6 hour* and in COLD SHUTt>OWN with.1.n th*
followin9 JO hour*.
s~vt:r:.I.Al'fc:z. R!:QUIUMEMTS 4.l.2.6 Each borated water 1ource *hall ce detn0netrated OPEJ\ASt.Z:
S.1.1.EK - UlfIT l J/4 l-16, Amendment. ~::.
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 f-r-'*
'iii. - - *
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 f t l
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 I
pnpuatioa fn startup (Koda 2).
. 3/4 1-22 A- f nt Mo. 103 SAl.111 - UlllT 1 r 6-*
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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
SURVEILLANCE 4.1.3.S REQU~REMENTS The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 b.
i?OWER unless Oi?E~TION (Continued) 90% of specified in the COLR and ACT I
c. 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
I 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:
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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after restoring the AFD Monitor Alarm to Oi?ERABLE status. ,,
b. Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 .
-..... -~
ays.
! *:.
s.--*,.
~4
! . z., 1
~:.:~*::11! =:~!~ :1;s !*:~~r :!:!*-*~*-;
"",.! .. !~: ':: -:a.z.1.. :r- : ..
.).-
~ .o.:!!"'!~C!
~~!!~
-11&.!?M"-I! * .. ~ !~: : *:,.-s,.,* !~ ~~! a'"*
i ~!.
~,.-
~-- !.
~i I
/
i
'I I
!I I'
II '~
3/4 2-3
TABLI i . 3 -1 (CoDtimaed) pp(."10& TJlIP SYSTDI DISJJt""PVATIOll caaMMgJ. llODU DI WBXCll Cff&IQIKL WllllCl'Iom&L SUllVJlil.I 1 W:S gg-rI,.t'* OllJiT ggq nu
...... "'19'**
I. U. La** oC *la.1"° ~ 8 a 1 H. ~t._ Guerato~ --~ ...,,_l--1.ow-Lolf 8 ~**
tt a Q '
1. 2
15. DSLSDD
...... a Q 1
...... a 1 Q
11. Tu.rid.De Trip ,
a. Low Auto*top Oil itre**ur*
b. '!Uzbiae Stop VAlYe Clo*ur*
...... S/u0
S/u 0 *
1. 2
1. 2
11. '
Safety llljec:ticm J:Dpat ea.
fram U*
...... ...... * *. , Cli) 1.
20. ...ctor Coolant llreaker a
~iUcm Trip a1. ar..br ...... I
.Cl) Cll) CU) 11eaator Trip 1. 2 and.
aad aCHI
...... .Clil
1. 2 and.
~*t~
BALa - UIDT 1 3/i l-12 '
ACTION 19 -
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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
b. The Minimum Channels OPERABLE requirements is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.2.1.1.
ACTION 20 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.1 provided the other channel is OPERABLE.
ACTION 21 - 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 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .
ACTION 22 - NOT USED ACTION 23 - number of OPERABLE channels one less than the Total
~--' of Channels, restore the inoperable channel to status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within rs and in at least HOT SHUTDOWN within the following
SALEM - UNIT 1 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<:Jt
~:.:~:.n l second of :.-3 :ies:.;n :.n:erval.
~ 21 ::ach ::-:i:.:l :r !.ogi.c :hannel shal:. '::e :es:ed at eas: e*1ery 62 :iays :n a
;cagsu*d ";;2ili 9 '5'TAGGc~Et>- Te:~T cA'SIS.
. .. :-~.e--------=----
3l ::.:.;..-.~£:. :~~c-=:o"~na:-~de. . ~/
I exerci.n:-.g :=-.e cransm:i.c:er by apply:.ng e:.:her a vac~um or ~ressure :o :h* appropr:.ace si.d* of cne
-ansm:.::er.
( " )
NOT *.:s&:o NOT '.;SEO l Sl ,,
!:lpucs from ~ndervolcage .. 'Ji.cal Bus. sh*ll b* tested monthly. !nput*:
~rom Sol:.d State Protecti.on System sh*ll b* tested every 6l days on a ST~GGEREO '":EST BASIS.
-:~,*
w*.
S.U.iM
UNIT l 3/4 3-H Amendm*n~ No .18 7
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
1f 81 u.
Al!!rlc:.tlrL*!': Al s~ '" raa11 1.1***
1:£i91!: , .
a.
II.
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 1fm1C *1Cft111 4 ""'" OP *la" ='le ~1
~Ullo* 01' ....
WI Cft9 l"te1at1* '111111to~"' =a,a,...11 fltOOtrUlt, 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 n =- ~11*1-c1u ,,... 1n r1a1e &.l*l.
1*
\ s-av12cE oia: .::,
l/4 l*l5
--~--
TABLE J.l-6 (Continued)
BAJ>IATION MQNITQBING JNSTRlJtlEN'fA'[IOH MINIMUM ALARM/TRIP MEASUREMENT CHANNBLS APPLJCABLE RANGE ACTION MODES SETPOINT OPERABLE INSTRUMENT
2. PROCESS ~~~;J.f*:* .-:.
b. Noble ~:~t.~,~~ '°nitora 1 * ;p
-~' 1; 'V- l
61. ox10 11-&Ci I cm
1) Hediua~~ ~Uioary U~lana only)
Buil4i!19"*~~l &yat**
(Pl~~**\~,}~!~~ 1,2,lU 61. Oxl0 11£Ci/cm 1 21
2) High.~* ~f,Aary l (Al.arm only) /"
Building lxhau*t &yet**
lPl*nt vent) 21 l, 2, lU dO mR/hr .
l) Moain,stea*line l/ (Alarm only)
Discharge (Safety HS Line valve* and AtlDOa~heric "
Ste. . Dullll*) 2}
61. 27xl0 4 cpm 1-10* cpm i* 1,:.1,li.t t) Conden**r KxbAuat (Ala11n only)
&y*t*
l .* CC*'fllOL ROON
62. t8xl0 1 cpm
Air lntoake -
hdi*tion Level l_. ,, ,,
C f\{4? <:.C.
I
.~
.1 .
II Control ROOlll air intak~s shared between Unit l and 2. C.ot!E AL-f£~AlloNS etn*e alterilt:ion11 ~

ALL HODES and during movement of irradiated fuel, as11ef!lbl ies amJ
/ -- __/---..___
r 1. II 11 Ame udme 11 t No . l YO 3/4 l*J6a
. I r1 1.i.i I ~'~(j~ U.1.t
TABLE 3.3-6 (Continued>
TABLE NOTATION ACTION 19 - 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:
i no channel* OPBRABLB in a Control Room air intake, 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
TABLE f.l-l tiouedJ RAJ)IATION MONITORING INSTRU.1£NIATJ0H SlJBVEILLAUC£ REQUIR£Milff§ CHANNEL HODES IN WHICH CHANNELS SOUR~E CHANNEL. FUNCTIONAL SURVEILLANCi INSTRUMENT CHECKS CHECKS CALIBRATION TEST REQUIREI;>
. '*~~)t~:~. ~.
2. PROCESS MONI,qfA;.;;
~;~~*::... *. *.
b. Noble Gaa .,~;n~*~~' ~nitors * *
1) Hediua ~~ ~'Ji*ry s M R 1. 2, l "
Buildin9 sxai.~ fy*t**
(Plant Vent)
2) High Range Auxiliary s H R 1, 2, l " 4 Building Exhaust Sy*te*
(Plant* Vent) l) Main ~teamline s H R Q 1, 2, J " 4 Discruarge CSafety Valvea _,.d Atmospheric ou.p.;
t) condenser Exh. Sys. s M R l, 2, l "
l . CONTROL RooH
a. Air Intake* - Radiation Level s M R Q **
I I
~* <'M.E """ -r£RATIC>N-S
ALL MODES and during movement of irradiated fuel assemblies and durip~ ee~* *lte~*tiona. &
./\I.EM UN IT 1 l/4 J-l8a Ame11dme11t No. 190
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.
. <;.~:-~**~:~t.~,~
-. .::~~*~~~?*: ,. *~ **~: . -..
.~~:t*~~}
3/4 ,.,,
SALDI
MT 1
)
'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 IRequir the roceed prov nd :he following of OPERABLE channels less than the PE~LE to provide an a ystem subcooling margin:
shown in Table 3.3-ll, operation maY' that Steam Tables are available in the Control Ropm
red Channels shown in Tabl* 3.3-ll are calculating Reactor Coolant 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.
an in-line channel which requires perind1c Any count rate indication above 10,000 c:p"" cnnstitutes a.
ca~11ance purpnses
SALEJ14 - UNIT l 3/4 3-63 Amendment No. 64
I TA8LB 4.3-13 RAQIOACIIVE GA8EOUS EFPLUEN'f MQNITQRING INSTRlJMIN1ATIQN auRYEILJ.ANCB R£0UIREM§N"fS CHANNEL MODES IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE.
OURCE CALIBRATION TBST REQUIRED.
INSTRUMENT
1. WASTE GAS HOLDUP SYSTEM p p R (3) . Q (1) *
a. Noble Gas Activity Monitor - Providing Alarm and JU,ltcmcttic Termination of Release I D N.A. Q(4) M **
b. Oxygen MOnitor I
.i .. VACUUM RELIEF
2. CONTAINMENT PUR~B AND PRB.SSURB p p R (3) Q (1) ***
a. Noble Ga~ Aptivity Monitor - Prov~ding 3.
Alarm and Aut~ti.c PLANT VENT HBADBR SYSTEMI
a. Noble Ga~ ~ctivi.ty Monitor Termina~ion of Release D .M R(3) Q (2)
w N.A. N.A. N.A. *
b. Iodine sampler w N.A. N.A. N.A. *
c. Particulate sampler D N.A. R N.A. *
d. '
Plow Rate 150nitor N.A. R N.A.
w
e. sampler Plow Rate Monitor 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 Amendment No. 157 3/4 3-68
,. "T r.'M - flNT'T' 1
.l.~.l ?ha .-..e re~ir** ~bin. ov.r*,.*' proceccioe 1yec..
1hall b~ ~crace4 OfllAl1.I:
I 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 b.
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 jeccioe 1ac1daftC v1c..t\1D MIC pU.d.el1na* by reTl.ev1n& c.be .. c.nodolo11 pr***ncad 1
in WCAl* l.U25:
AC leaac one* every cw nf,...Un& wca1***
b. A.teer ..01f 1cac1ona co U.* ..1a C\&l'ttlna *~ curb1D9 over1peect proceccloft valv***
stJ.DI
IJlllT l.
l/f. 1*71
_.-*.:... ...... :;--_*.~ ...:-_,
~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 OPAABl1 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~OUIREMNTS 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.
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 r.
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 1nap.
pu*
tw**H~tiur*t sn1l l n~t o. starttd wi~tt one or ,,.,re of tl'!e 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
. -~1~,~i.Sis *:- * :. ** 1i(i0rt;1HJ RHR
.... ~ I 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:~'"!.
3/4 '*lb AM!HDMDIT ~O.
SAWt
UNIT l
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 0 .
partial tube inspection provided: 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 i i 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 l l 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
--- 1
~£)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:
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 .
. ' . -.~::. ~ifi"*' ~:- -~~ -
~~ * .e:&etta-frmae suno level an4 conta1,,_.t fan =al tr candaft11ca
'. ~ ~/<-t'fov . race-.(ff t211nt used) "'n1tor1nt syst-*01rf'orm1nce of
'.!"~* CH.AHN&_ CAkIBAATtOM It 1111i anca DIP 18 rrmn~s.
I lS~Ln< ~~IT I
1 3/4 1\-14
-
REACTOR COOLANT SYSTEM PRIMA.RY COOLANT SYSTEM PRESSURE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.4.6.3 ~~Coolant System Pressure Isolation Valves specified in Table
~-all be OPERABLE.
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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .
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:
a.
b.
At least once per 18 months.
Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or more and if leakage testing has no~ been performed in the previous 9 months.
r
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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 Maximum (a) (b)
Valve No. Allowable Leakage .
Low Pressure Safety Injection S 5.0 GPM each valve Loop 11, cold leg 11SJ56 S 5.0 GPM each valve 11SJ43 S 5.0 GPH each valve Loop 12, cold leg 12SJ56 S 5.0 GPM each valve 12SJ43 S 5.0 GPH each valve Loop 13, cold leg 13SJ56 S 5.0 GPM each valve 13SJ43 S 5.0 GPM each valve Loop 13, hot leg 13SJl56 S 5.0 GPM each valve 13RH27 S S.O GPM each valve Loop 14, cold leg 14SJS6 S 5.0 GPM each valve 14SJ43 S 5.0 GPH each valve Loop 14, hot leg 14SJl56 S 5.0 GPM each valve 14RH27 S S.O GPM each valve Intermediate Pressure Safety Injection S 5.0 GPM each valve Loop 11, cold leg 11SJ144 S 5.0 GPH each valve Loop 11, hot leg llSJl56 S 5.0 GPM each valve llSJl39 S 5.0 GPH each va1ve Loop 12, cold leg 12SJl44 S 5.0 GPH each valve Loop 12, hot leg 12SJ156 S 5.0 GPM each valv~
12SJl39 S S.O GPM each valve Loop 13, cold leg 13SJl44 *s 5.0 GPM each valve
~oop 13, hot leg 13SJ156 S 5.0 GPM each valve 13SJ-l39 S 5.0 GPM each valve Loop 14, cold leg 14SJ144 S S.O GPM each valve Loop 14, hot leg 14SJ156 S 5.0 GPM each valve 14SJ139 S 5.0 GPM each valve Safety Injection Accumulators to cold leg loop ll, cold leg 11SJ55 S 5.0 GPM each valve loop 12, cold leg l2SJSS S S.O GPM each valve loop 13, cold leg 13SJSS S S.O GPM aach valve loop 14, cold leg l4SJSS S 5.0 GPM each valve Safety Injection Boron Injection to cold legs loop ll, cold leg llSJl 7 s s.o GPM each valve loop 12, cold leg l2SJ17 s s.o GPM each valve loop 13, cold leg ----l3SJ17 -s s.o GPM each valve loop 14, cold leg 14SJ17 s s.o GPM each valve lSJlSO s s.o GPM each valve RHR Suction loop l l lRHl s s.o GPM each valve
loop 11 SALEM - UNIT l 1RH2 3/4 4-16b 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.
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.
(b) Minimum differential test pressure shall not be less.than 150 psid.
SALEM - UNIT l 3/4 4-l6c
.Amendment No. 21 O
SR' cm t r 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 *.
Vita tfte 1pecU1e an1*1ty of tftie piM.ly coolan > 1001i .ct/9r~
D.
be i.a a& lean ltOf S'fMOIY witJa T "9 c SOO** w&.&JU.a I l'lftrw.
1 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 . . *pee:-.!:.;
H'Cl*Uy of the pri.llU'y c:oolu Li.mi.:1.
SQ'llVIII.t.AllCS UQGlWI
.*.I wL.tl'U.a tl'l*
tfte
.,..u1e l.~t*
an1*1ty of tne P*ia&IT coo
. , pecfonance of ill* 1-.u.. .
1 1:le 4ee*n1n*4 : = ~*
...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 l l *ncn.. *
~ "-- / -~ _,.,,/' /
c. Verifying che POPS i1~ la o~c once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 .
150 J/4 4*ll SALIK.
UHl't l
.-* ~ . - .
--~t::*:~~I~:-.*~-:~-~<-*:*X"i::~~~:t
~!AC~ 'iY°- . js;trat
~~*: .~ !~*~:,~~-~~-.. ~ -~-:.;~i *,~::~**~~~~:~~.
J ~ 4. 10 .. '!TRk..-URAt" !PtfEGRITY
~SME ::CE :~ASS 1, Z and 3 COMPONENTS 3.4.10.l il'I* structural int19r1ty of ASH! Code Class 1. anct J co~~ z ponenu sn1ll be ~int1in1ct irt ac:c:c,.d1nc1 witl't Soeci11cat1an 4.4. lfl. t. )
APPt.ICABtL!TY: ALL ~DES . '--\._;'
AC'!'IOPt:
a. With tl'te structural intt<<;rity of ar.., *~Ml Code Class l .
ionent ( s) not c:anformi ng to tn* above ,..qui ~t*.
tl'I* stM1ctur1l integrity oi' the affectM camponut(s) - ** .
..,,ift1;n iU limit or- iscihtt tti1 .lff'ec:ttcl c:a.onet(s) r:l
to int"rtuing tne ~11ctor Coohnt S1st* tmceratu.-. mo,_. ,,
50°F above :!11 mi nim\lr. :1mp1r1tiire ,.equt ,.ect by NOT. cont.~:~-t .,*:*- $;
~. wi tn :ne structural integrity of any ~SME Code Cl us Z com*
ponent(s} not conforming to the abov* requtrltlllftts. r-esto~e !~e structuT"ll integrity of tne 1ff1c:ttd c:ampontnt(s) to within iu 1;m;t or isolate ttt* aff1ct1ct comoonent(s} prior to incr11sin9 tne Reactor Coo\1nt SysU. t1111Perat&n** lbove zoo*F.
c. With the strvctural integrity of any ASME Code Class 3 component(I) not confonninf to the 1bove* ,.._t.....,ts. restor~
tn* stnc'Cural hlt"trH:y of the *ectecl c:OllOOft**t.(sl to witttin..1ts. litltt or isolue th* affectH c_.,Pt(s~ fretft s1n1ca.; .
4c.4-. ltt. ...- .* ** * *siP\iciu;.l-int19r1tJ ..of ASMI Cede *etas* T* i* lftG l*
comoonents sria\ l ~ demftttratff:
-<".-:-:..r:.::~.; ..\*-~--~:- :.:. :-:-r.~
a.. Pt~ tha. .reqvtr-. .
.tt;, af* So*if1catt***~.. ~~~~~'~ .....
~ . . . . .; . . .. .* . ~* .-.~:-~*:: ~,:~:~* ::~*.;:: :: .;: . :
!t~. Ptl"' the, ;.Q\ltrtNDtl' of., th* IU,....:.t~~'CiOJt'-
12ro1,l"ta sg.ac.ifid flf 5P~.tf1Qt.1*.*~*.. l~l**~ff~k;~,:; *
.,::;~.::,*~~;t~i_..*.. ' ;,
l SALDt
UMlT 1 11*- a-3~*(* ... ~.. :.,..
..). :,,~::~
-:!-"......- .... z~
'"

/:'."~f:~;,~;: .. '. ..
- *: - : :. *~~~~::~k:-;~~'~;: .
*:_.-: :,f-* *.4Jit-::;:.-._*~* :;:*
- --~~;!~c ~~~~*" .
~
........... ,.:;......~
PPGllffil cog CQPU.,,-m;;;;?*--
- u ___, _ _ _ _,£~-
5':~tJD..* taxi <no*r
~r..~- *:* *.:::/\:*:**\*iu*$.~-=..~ --~-"' ~;:::*~~v._,,
t.~~-roa, . ....:*._ . *-*- .. . . OPDATtOtt
... '-~i*:~;~;-~~*:r,,:-.;~~<~~ .
l; 5. l ~-*tnl9'~;: on* ECCS 1\lbsy1t1a co.,r1H4 of the. followtna 1haU b*
0 P!IAJf.I': ~* :< , 'e*~'- .
a. On* OP!IAlt.1, cencrtfugal charalna Pumf: and. aaaociaced ftcw pach
capable of taklna 1ucc1on lroa the- refueltns vacar 1cor*1* tank and craiwferrtna 1uccion co ch* reeldl&al heac r ....al pu., d11charg*
ptp1na aaia;
l. DiHhar11na 1nco **c~ leaccol' Coolanc Syac. . (&CS) cold i. 1 .
b. One OPllAILS rH1dual heac. re...,al. ,.._ d'uaeclau4 reddual heat U*Yal heaC exch&n&er &1\4 fl . . pa~ C. . .1. of CUlftl IUCCion fro*
ch* refueUna vacar- scoraa* c.u- on-* **f*C7' laJMCloa lip&l. and cranaferrtn1 1w:cton co cho concalmenc: *-... durlna ~;:*~ / . _
recirc"lacioft pba** of operacton ancl:; ... ,_,..,~~\;:'.* . ___
- . - ~~~~ ~-. ~-:..~~ . _,..; .
l. Dbchar1tn1 1nca **ch ICS cold: let. Ulllif** upea ~_'\.;_
. ,.:.. ~'.~ '.'i;f.:::***-
,. -~. -;,1 *.. ~ -~*:.. ..
1ni.c1acloa.
,,"- ~{f?J .
AJtlUWILITX: KODC -*
ACIIQI:
2. Dbchar11n1 1ncca eve RCS hoc lep. ~J- * *:t,~~:'.'1\ .
tf' ,,,,.__ ,, ..
--':-~~:
a. Widt ne< ECCS 1\lb.,1C* OfllAIU-* becau.e-of t"- tnoperabU1cy of elcher cU c*nCrtfupl chacain&- ~or cbe- fl..- CMclli fr* the refuaUna vacea acorap. -canllt.__ r**CH* ac* leue Oft8 ICCS* 1ub1yscea co OPllAaL&~C&Cl&e vtcbla l ~ *~ "- la COl.D- SMU!'DOUlf' within ch* next
..-.,ec* Onl.Alta . ._..,of a., t_,.cabilicy of
~~,_reac-.,aa
-~- a.~us l.e. . . oae ICca ....,.,_ca dllel- Ma&: r_.al: . _ .. ..+mpa os. realcllaal heat c-oo1ane s,aa.T-~}~ c11aa- 35e*r OIDAILI stat:ua by wi*
.~
i*:~
..~-.
,....,.1-~::._,. .**. - *.
, .: di&., iCCa: f.* act:\lac** Allllt laJ....- vaces iaco th* leaccor a.., a s.-w letorc IM11 k P n f " * - ' aubmitced co loa* ,_.,*
c* S,.Ot.llcacl* *~ *.1, vt.tbia 90 day*
""": '""'*-.:*"7-'-".- l.M ot~um. . ol dlla unactea _. cM cacal
.~ ~:::~~:1i*..
7
&tna-p *hall be O~:--..ft~ . .C. . . . .~;--!'!lfi**-* of che ilCS colct tep l* 1~ ~~.~-!;:~~~~~!t-1f!~C:~lllfe$,~th* head ls
"" cM SALDI
Ulll'r 1
ruacoa ~*~:f~;,;;_ <:,:'#:'(~'~~!: c:;;* ~ "
.. , *:J~::i/:~'.:"-ii' . l/li.* ,.~_..~::*::,:~~~:".~~~r_;,:. M11*r1Mac ?let. ~~a
/~>-:~-~*-. *- ;_-;, . . . . -# *, -"~;'1~'.;~,~~;~~~~~:~~:i¢f*.
,:,_,~r:i:;~~,:.~
'~ ~
~i l.5.5 1.
l'.t.
r~.
rtfutlf"f *lttr eont*f "" volu* of eei,.... lM,500 1tt4
.. DOPOft:* eOftClfttfltfM of ~tWtttt StQflg9: e1na 2 ,JOO .,.,,
tit:
e. 4 11tf 1ttn11e w1t*1t U1*1r1C1i,. of 35-tr*.
APttUCM f UTT:- ~EIS l. Z* l &ft4 *. ... . _,.
ACT ro":
-~J}f.~.: ~~t~~-::
'.;~ ..;-::;':'_~ -~.
.~~~?t:-~f~,~--~-~
Wt t,. tft* ,.,,ue11rtt **i ... ttOf'lt* tlftlt f natut wtUtffl 1 "*r "°"** ,...,,,.
or b* fft ., lHSt HOT STAIUIY *1tltfll .......... 1.. caL~:<:.. :-
tit* UM to QllllJI~.;. :.
SHUTaMt wttltf" tit* foll~tftf 30 Ptaurt. -~.*~~1;,*}~~:.-* *- ..
~ \ '* ~~t:#* -~!< .
$ i.aw rLl.&NCI ~EQU tAEMIJITS
.5.5 n.. AVST' si.an - ~ltrttld OPIUIW:
1. At l 111** once ,_.: 1 d** apg:
1. "'"i"*****l*t.el flt ~-*tllltt. lfllll:
...... L~*rattoe of' tft**C.,.._
. * . ...._~- .O..::.>..-... .***
. . . . . ., Yefii')'fftf tfte.IC t ......t..,.
~ u ..ernure ts c 31.,. *
~**
zr-*
1.
. ~--~ ...
'~;-,~ ~"t;:,'/;' '/;:'.*, :; . ' ~ ~!f~:~~~~~. ef
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 i*olation valv*** shall be closed. (Valv** immobilized in *hut po*ition with control air to valve operator* i*olated and tagged out of **rvice).
APPLIC,ABILITX: MODBS l, 2, 3, and ACTION:
4.~
I 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 valv** may b* open*d on an int*rmittent baaia, under admini*trativ* control, a* n*c***ary to **ti*fy th*
requirem*nt of Sp*cific:ation 3.6.1.4.
SALBll - ONIT 1 3/4 6-Sa Amendment No. h 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 t u neat 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; 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 a.
The spray additive At leaat once pez:
(manual, power opera natrated. CPZRABLlt:
ri.fyinq that each valve 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: I
1. Verifying a NaOB solution flow rate of 12 +/- 3 gpa from the I spray additiv9 tank through sample valve 1CS61 with the spray additive tank at: 2.S +/- O.S paiq and 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after ea h closing of the valv , except when the valve is being used for multiple cyclings, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , 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
1 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 qrify 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,.*
} -
- ~~*-~-~-. -*-** ~ *~: ** ._,
"'.). :: *:! r
..i. **. *-: ....... ~... ...
SALIN
UMl'f 1 . _3/4. T*lf * ... * : ,. mat No. 93
.. ... - .. *- .., ~
. -- -. '°"' .......
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 ALL MODES and durin9 movement of irradiated fuel a!seml,)l~es.
JUIPL!CABit.ITY:
ACTION: MODES 1, 2, 3, and 4
a. With on* chiller inoperable:
1. Remove th* appropriate non-essential heat loads from the chil!ed water system within~
/ c~~si..e:
2. Restore th* chiller to opeulllr su us within l4 days or;
b.
_/
3. Se in at SHUT~OWN within the followin9 With :wo chil!ers inoperable:
6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in c~t~
l. Remove the appropriate non-essential heat loads from the chil:ed water system within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and; tus within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 
3. Restore at least on* chiller or; 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD 4.
ter pump inoperable, restore th* chilled water c:. atus-within-7-days or be in at least HOT STANDS~
ours and in COLD SHUTDOWN within the following 3J hours .
SALEM - UNIT l 3/4 7-33 Amendment No.
&~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 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .
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 .
SALEM -
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*.
UNIT l 3/4 8*8 Amendment No. 177
~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 OPRABLE witl'ltn 7 days prior to crane JH and at lfntA~Ptr.)7 days t,.,erufttr durtng 1
t"'* crane operation. / "'~ \
I 1~J vri(.L 1 SALE~
UNIT l 3/4 9.7
'""c,,,
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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
b. The residual heat removal loop may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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
, I I,
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 1
!.,..;:!'! :~e r!~uirements of :!'le above s~e~1ffc:at1on not sathffed, sus.,tnd
~al1 o;,eratiOl"IS fnvolvfMg ~vement of !l'Jtl usembl f es or c=ntrol r"OdS wf:hin
!:!'le =iressure vessel. ~!'le ;ircvisions of S;iec:ific:ation 3.~.l art not ia~~l ic:able.
1 I.
l:
l: I!
I!
I
i I
I' lI I
I I I I I
!l
I I I 11 11
,I\, s1*~*,~rWI"\-**-' ~c~- ~£OUIREMEHTS 1
I I
~ 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
!, :I ;:er Z4 hours. th1rt1ft1r during :rovem1nts of ~uel usembl hs or contro 1
~ods.
I 1
I I
I
'I
, I
'. \ SAl.~!'1 ..; U~tT 1 3/4 9-10 AZ-IENCMEMT ~O. 23
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.
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
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 1fst 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 f.
the spent fuel pool.
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 Aii&*)t*&t No. 64
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 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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'*~<500*r pr~vent* the r*l*a** of acti*ity 1hculd
1team av.,, ~.Jf" "\
~enerator tube ~ur*~*inc* tl'I~ 1aturation pr***ur* of the pri.aary coolant ~*
t ; ,.
val****
belQW th* lUt pc'e11ur* of th* .atmc1ph*ric neu relief Th*
1urv*ill1nc* requ~d* adequate 111uranc* that exce11iv* *p*e~!~:
a~ivi.ty level* 1n th* prialry coolant vill tie ~*t*eted. in 1uffi.cient :~~* :o take correctiT* action. Inforsation ol:ltained on iodine 1pil&in9 wUl c* ~Hd to ****** tl'I* ~ ...t*r* 111ociat.ed vittl 1pil&in9 phenmena. A reduct ~:in ~:i frequency of 11otopia analy*** followin9 paver chan9** may tie permi**~bl* ~!
ju*tif iecl try the da*a obtainecl
SAl.U - UNIT 1
wq
~ )
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 l n i
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& :~.
<:alc"lAC1* *tboa 4ucr1bed l.n WC.U*7924*A, "lul* fH But"' ancl Cool:iown t.tat.t c~ .. Af1t.l 1975".
Heat~ _. cooldoMI Ua1t C\lfVH are calc"laucl \Lliftl c!le *H 1J.a1un1 value of t1'9 *1l*ductll1tJ r*f*rence c...-rat\lr*. IT'ii!!..~ at th9 end of :~
affecctve t~11 ,..... year* of 1ervtc* life. ~ 15 l1Pf 1ervtce 11!*
periM* u CMHA 1uca. tMC CM li.aittn1 ITMM I t tM 1/*T locatin 1D Ch*
core retiOft u IT..tH tl\aa cl'I* lT of cu*u.auq *1rH*Uace4
iHUrial** **The*Hlection cit**1ucl'l *a~iUn1 . RT~mf Hl"rH *chat *11 c~nentl 1JI CM Reactor Coolant Syat.. v111 ~-operat~ cone*r¥&t1vely in accordance wlth appltca~l* Cod* r*q"tr .....c1.
SA.l.Dt * ::MIT l ! J/4 4*6 Amendment No. i::
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
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:
SAL.EM - UNIT 1 5-4 Amendment No. 198
sucb that: a major porticm of the body cuJlct ncaiw in c:na bar a dam in
.. mrm CXl1tai.rlnllil, ~ m encL 8nclmure can locatad within lEgll ~, sudl * .PMR exists tar Pltl) - of lcx:ld.n:J, azam tha inlivimal anu, thm* that ans no 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 W U ) a:mt.imam
&Ul~~lniiill.-mmy be lllld9 by ~1*1 qia1 ifi8cl in i:adiatim pmtcticn
-PE"Cmkm* to pmvida paaitiw tDCpOm cxa1b:ol c:wr. tm activiU. within t:lw
/
a1'8.
6.13 HD '!H cnmg, PIQiWI CPC:fl 6.13.1 in.- PCP shall m cq:op:uwd bf tm a,.1*im prUr to~-
6.13 .2 Limml I init:latai dJangm to the PCP:*
1. Shall m mtlld.ttm to tm 0mn1-icn in t:m s.i.anmal. .
Radinw:tiw Ettlumt: RltlMm Rap:a:t far: t:ba pmrial in 1libidl tha c:hmlJa(*) . . lllld9. 'lhia *lJ:ni:ttal mball ccntain:
a. SUtticimtly d9tail.ed* infcmmticn to tra11¥ *w nit t:m
b ..'.
raticmal.e. tar ti. cb1nJ9 wit:tazt i:..fit of additicml ar
~-ital :infazmticn; A dmt:mminatiCln that the c:hmlJa d:ld t-* retJCW tba OVEllll ccaifaDllnam of ti. .,, jd1 ti<WAa'l'J: 1'UA~ SJ'S'l'J:K 1-3 mEN'l'IJ'IJ:J) %ZAIOiQll 1-l MEHBIR(S) OF THI POBI.IC 1-l OFFSI'l'Z OOSZ ~ 1-,
1-4 OPERABLE - OPERAS OPERA.TIONAL N:mK 1-,
1-,
PHYSICS TZSTS PRESSORE llOtJNrlAU 1-5 PROCESS CON'l'AOL PROc:1WC (PO) 1-5
~C2-PCRCIHQ 1-5
-**------.. -- -------**-* ~**-:-*1-s Qt1ACR..\N'l' POWl:R 'l'II.1" RM'IO RAnn THERIGL PONZJt 1-5 REACTOR m?P SJ'S'l'ZN RZSIOHSI 'l'lMI 1-5 REPOR'l:.UI.I EVZlft' 1-6 SHC'l'J:)OWN HM.c:DI 1-6 SIT.I: llOONnAR% 1-6 SOLIJ)Ii'?CA1'%c::if .1-i SOtmel CHICK 1-6 S~Bl'l'USD 1-6 THERMAL JIOll&Jt 1-6 1-7 wmEN'l'IFDD I.ZADGa CNRZS'l'RIC'l'J:D ..\DA - ...... **- ~--- .:- ;-- .
. 1-7 1-'7 WN'l'ILM'ION-*&XHADS'l'- ~ -srsm.
WR'l'DIG *- .------
-* . . . -..-........---...--~-~--- 1-1 1-7
Aaendunt Ho. 197
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
==================================================================
SECTION
. . .. PAGE 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES Operating ......................... *.* .................. 3 / c : J 4 -
Shutdown .............................................. 3/4. -7d..I 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating ......................... 3/4 8-8 A.C. Distribution - Shutdown .......................... 3/4 8-9 125-Volt D.C. Distribution - Operating ................. 3/4 8-10 125-Volt D.C. Distribution - Shutdown ................. 3/4 8-12 28-Volt D.C. Distribution - Operating ................. 3/4 8-13 28-Volt D.C. Distribution - Shu~down .................. 3/4 8-15 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices ......................... ~ .......... 3/4 8-16 SALEM - UNIT 2 VIII Amendment No. 28
mg
,~ .... . . . ...
µmmw; CQBPtnon~ma grgu1a.yp*joayi1t1,na BFTUMM~
lgrtQI 3Jt,9 BQP!LJF QPQATlOQ 3/4.t.1 -. IOROll COllCDDAnOll ********************************* , ** 3/4 9* 1 3/4.9.2 llfs-r&1llllltTATlCJll -. * * *** * * * * *** * * * * * * * * ~ * * * * * * * ** * ******* 3/4 g. 2 l/4.9~*3 DICAY Tl!ll ...** * ***.**.* ................ * ~ *******..*..... l/4 9. 3 l/4.9.4 COll'l'AIHMDI! IUltDlRG famAUOIS *******************. , 3/4 9.4 l/4.9.5 3/4.9.6 l/4.9.7 CIAHI ?IAVIL
FUil. HANJ)tIIC Al!A ******************* ,*. 3/4 9* 7 l/4.t.I llSIDtW. Hr.AT llMO'IAL ARD COOLAlft' Clacut.ATIOlf All V8t*r ?Av.la **********.****..*******.***** : ....... 3/4 9*1 Low Vacer t.av.1 -~******************!******************3/4 9.9 3/4.9.9 111.llP lSOL\tlOll SYSTlll ******************************* 3/4 9*10
3/4. 9 .10 3/4. 9 .11 3/4. 9.12 VATD LIVIL
UACTOa VISHL * * : ~ *~~-*** ** ................ 3/4 9*It .
STOIA.GI 100L VAT!& LIVIL .............................. 3/4 9*12 FUEL IL\IDLlllG ADA Vllft'ILA.nOll SYS'l'DC ................. 3/4 9* 13 l/4, 10 SPGW tr.rr ncsm;og ..
3/4.10.1 s~ llAIGlll ************************.*******..*.**. 3/4 10-1 3/4 .10. 2 GIOU1 HIIGIT, IlliatIOlf ARD POVa Dls-rlllftlQil ~TS *.**..*.*..*.************.**....... l/4 10
2 3/4.10.3 l'llYSICI TISTI **********..****.*.**************........ 3/4 10*4 3/4 .10 .4 !fO rim TUTS .******.._._ *...**..... _***....*...* o ********* 3/4- 10* 5 SALEK
UHl'l' 2 Amendment No. 78
==::::::::=::::::============-=--=--**-"----
BASl:S SIC'l'IOlf
.mu
!AB 3 /4 . 0 Af PLICAl?L?'l'f ****** ************************************ a 3/4 0-1 3/4 . 1 RllS'fmn C9N'17l9L ITS'l'ZIG 3/4.1.1
~Cir~*************************************** 3/4 1-1 3/4.1.2 BORA1'ICll STl'fl:NI *************************************** 3/4 1-3 3/4.1.3
!CWABL1 CON':ROL ASSZMat.%11 **************************** B l/4 1-4 3/4.2 PONJI DIS'l'ltilp'l'IQM LDCrl'S 3/4.2.1 AXIAi. FLCX DI~CI -------
8 3/4 2-1 3/4.2.2 HEAT FI.OX !IOI elWll& FMIGR and A!Jll ~\JCLe'A~ E:t-liHALPY Hor c:HANNE- ANO "RAOIAl. Pt"AK'trJt; FAffCR-S 3/4.2.3 ~
3/4 2-4 3/4.2.4
.I QOAJ:IRAN'l' POWER TILT RA1'IO ***************************.* 8 3/4 2-5 3/~
3/4.2.S O!m I'~ DRS * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *B SALDI - OHlT 2 %Z Aaea+ent No. 197 I
BASIS 3 . 4. 3 ;NSIRtlMpf!ATIOll P~~~c:TIV'E Iff!fttJMlll!'M?O~.... ." ..................... ~
ENGINl:EUI) SARTY F!ATOUS !!SPI INSTRUMINTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B l/4 3-1
)/t.l.l MOlfITORIIRI IHSTRUMmoTATICll ............................ 8 l l
e : J 3/4. t RACIOB COOI.Nf'I SYSTEM.
J/4.t.l REACTOR COOLANT t.OOH Alm C:OOLAHT CIRC'Ut.ATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 It 4 - l J/t.4.2 and SAFETY VAl.WS . . . . . . . . . . . . * * ......**.****....*.***..**.. B J/4 t*l J/t.t.3 J/t.4.4 PRESStnlIZD . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B JI 4 t
2 J/4.4.5 RELIEF VALVIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B J/4 4*2 l/t.t.6 STEAM GENSl.ATORS ........*....*..*.****..*............. B l/t 4*3
)/4.t.7 REACTOR COOLANT SYSTEM LEAJCAGI ........................ B J/4 4*4 3/4.t.11 CEI.ETEO J/t.4.9 SilEC:IFIC: ACTIVITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B J/4 4*6 3/4.4.lO PRESStnlS/T!MJllL\T'OU LIMITS .........*................. B -7
)/4.4.ll ........... a J/4 4~ 18
, - ~ - ;.. . B 3/4 4 - I ~
SALEM
t.'NIT 2 XII Amendmenc No. 161
IND BX BAS BS
~*n******************s**********=*=**======*=****=~===*********==***=*a*
SBCTION PAGB 3/4.5 BMBRGBNCY CORB COOLING SYSTBMS (BCCS) 3/4.5.1 ACctJH1J'LATORS ****************************************** B 3 / 4 5 -1 3/4.5.2 and BCCS SOBSYSTBMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 5-1 3/4.S.3 3/4.S. r"' J e:cno~ F't.t:.W - * * * * * * .. B .3/'t S- Z.
3/4.S.S RBl'tJBLING WATBR STORA.GB TANJt (RWST) ************** **** B 3/4 S:J'_3 3/4.6 CONTAINMBNT SYSTBHS 3/4.6.1 PRIMAJlY . COHTAINJIBH'l' * * * * * * * * * * * * * * * * * * * * * * ************* B 3 / 4 5 -1 3/4.6.2 DBPRBSS~IZATIOH ANI> COOLING SYSTBHS *******************B 3/4 6-3 3/4.6.3 CONTAINMBNT ISOLATION VALVBS **************************B 3/4 6-4 3/4.6.4 COMBUSTXBLB GAS CONTROL *******************************B 3/4 6-4
SAL.BM - UNIT 2 XIII Amendment No. 78
INDEX
BASES SECTION 3/4.7
.. PAGE PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE .......................................*. 8 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION *..*.*........*....*.....*..*........*..*... 8 3/4 7-4 3/4.7.3 COMPONENT COOLING WATER SYSTEM ........*..*....*.*..... 8 3/4 7-4 3/ 4. 7. 4 SERVICE WATER SYSTEM .................................. B 3/ 4 7-4 3/4.7.5 FLOOD PROTECTION ...................................*.. 8 3/4 7-5 3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM ...*.............................*. 8 3/4 7-5 3/4.7.7 AUXILIARY BUILDING EXHAUST AIR FILTRATION SYSTEM .............................*....... 8 3/4.7.8 SEALED SOURCE CONTAMINATION ........................... 8 3/4.7.9 SNUB8ERS .............................................. 8 3/4 7-6 3/4.7.10 CHILLED WATER SYSTEM -
AUXILIARY BUILDING SYSTEM ....*.......*....**.......... 8 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 3I 4 . 8
1 A. C. SOURCES *...***.*...... *........................... 8 3 I 4 8-1 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS ..**.*...***.*...*... 8 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES .*.**.......... 8 3/4 8-2
SALEM - UNIT 2 XIV Amendment No. 192
INDEX DESIGN FEATURES
==================================================================
SECTION
. PAGE 5.1 SITE Exclusion Area ..*.*...*................*.*..*...* **...*..... 5-1 Low Population Zone .........*..***.......**..*...**....*..* 5-1 UvREsnucTE1) A~ttiO!> r()fl. R1u)1f)AC.T'I~ GA$4f'()L>5 Al\lP Lit;<J*O ers:-w~t<JrS.... S-I 5.2 CONTA Configuration .*..*.....**........*......*.....***..**...**. 5-l Design Pressure and Temperature ........*....*****...*.***.. 5-4 5.3 REACTOR CORE Fuel Assemblies ........* ..**..... * ........*.....*..*.**..... 5-4 Control Rod Assemblies *...*....**..*..**.**.***.*.*******.* 5-'1 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature .............*..*..**. L* **.** 5-4 ,.
Volume ........... * .. *................................... ~ ...... 5-4
5. 5 METEOROLOGICAL TOWER LOCATION .............................. 5-s*
5.6 FUEL STORAGE Criticality .............................*.......* *. . . . * . ... 5-5 Drainage . . . . . . . . . . . . . . . . . . . . . . . . . . . * . . . * . . . . * * * . * . . . . * **.. 5-5 b Capacity . . . . . . . . . * . . * . . . * * * * * . . . . * . . . . . . * . . . . . . . . . . * . . *... 5-5 b 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT .............**.......... 5-5 6
\-._ -"--.
-~*
~.
.~*
..~ ...~*---- _:. __._;_-:...._ --*
SALEM - UNIT 2 XVII Amendment No. 28
ADMINISTRATIVE CONTROLS
======~==============*=====================================
SECTION
6 .1 RESPONSIBILITY .............................................. 6-1 6.2 ORGANIZATION Onsite and Offsite Organizations ........................... 6-1 Facility Staff ............................................. 6-1 Shift *Technical Advisor .................................... 6-7 6.3 FACILITY STAFF QUALIFICATIONS .............................. 6-7 6.4 TRAINING ................................................... 6-7 6.5 REVIEW AND AUDIT (THIS SECTION DELETED) .................... 6-8
.................................... 6-16 r 6.6 REPORTABLE EVENT ACTION ..
6.7 SAFETY LIMIT VIOLATION .................................... 6-16 6.8 PROCEDURES AND PROGRAMS .................................... 6-_;.<" 17 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS ................* ....................... . 6-JH' z D 6.9.2 SPECIAL REPORTS .,., ..................................... . 6-)d 2 Lf 0...
6 . 10 RECORD RETENTION .......................................... . 6-~ '2. 5 6.11 RADIATION PROTECTION PROGP.AM .............................. 6-~ 2. ~
6 .12 HIGH RADIATION AREA *****.**..*...****...**....*..*..*.**.*.. 6-~ ~ ry 6.13 PROCESS CONTROL PROGRAM (PCP) ......... ; .................... 6-~ 28 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS .
AND SOLID WASTE TREATMENT SYSTEMS ......................... 6-.J?T 2. ~
SALEM - UNIT 2 XVIII Amendment No.175
SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2. l The reactor trip system instrumentation setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.
APPLICABILITY: As shown for each channel in Table 3.3-1.
ACTION:
With a reactor trip system instrumentation setpoint less conservative than the v in the Allowable Values column of Table 2.2-1, declare the channel lnoperable apply the applicable ACTION statement requirement of Specifica-tion 3.3.1.lu il the channel is restored to OPERABLE status with its tr:-ip I setpoint ad' ted consistent with the Trip Setpoint value.
SALEM - UNIT 2 2-4
TABLE 2.2-1 (Continue
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP S&TPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
13. $te. . Generatoi Water ~ 9.0% of narrow range instrument 2 8.0i oL narrow range instruaent Level-- Low-Low span-each steaa generator span-each ateaa generator
14. Deleted ' I
15. Undervoltag~-Raactor ~ 2900 volts-each bus ~ 2850 volte-each bua Coolant PuaP*
16. UnderLrequency-Reactor ~ 56.5 Hz - each bus ~ 56., Hz - each bua Coolant Puai>*
17. Turbine Trip A. Low Trip Sy*t- 2 45 paig ~ 45 paig l>reaaure; B. Turbine Stop Valve s 15i off full open s 15i off full open Safety Injection Input Not Applicable Not Applicable froa 118i>8CL ES~
19. Reactor Coolant Puap Not Applicable Not Applicable.
Breaker l>oaition Trip SALEM - UNIT 2 2-6 Amendment No. 154
3/4 t.IMITING CONCITIONS FOR OPERA';':ON oNQ St1£!.VJ;!t:..;.ric;; ~;;ou:~::~::~r:-s 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION J.0.1 ~pli&nce with the limitin9 Ccnditicn* fer Operation contained in i::r.a
ucc*ed~nq *p*citicaticn* i* required during th* OPERATIONAL MODES er ocher condition* *p*cified therein; except that upon failure to m*~t che Limiting Condition* for Operation, the a**ociated ACTION requirement~ *hall be mec.
3.0.2 Noncompliance with a *pecification *hall exiat when th* requirement* of
_the Limitin9 condition for Operation and a**ociated ACTION requirement* are not met within th* *pecified time interval** If th* Limitinq Condition for Operation i* r**tored prior to expiration of the 1pecified time interval*,
ccmpletion of the ACTION requirement* i* not required.
3.0.3 Whan a Limitinq Condition for Operation i* not met except a* provided in th* a**ociated ACTIOK requirement*, within one hour action *hall be initiated to place th* unit in a MODS in which the *pecif ication do** net apply by placinq it, a* applicable, in:
1. At l***t HOT STANtllY within the next 6 hour*,
2. At l***t HOT SHUTCOWlf within the followinq 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and
3. At l*a*t cot.n SHUTDOWH w.ithin th* eub1equent 24 hour*.
Where corrective mea*ure* are completed that permit operation under th* ACTION requirement*, the ACTIOK may be taken i~ accordance with the *pecifi*d tim*
limit* ** mea*ured frcm th* time of failure to meet the timitinq Condition for operation. Exception* to th*** requirement* are 1tated in the individual
pecif ication*.
3.0.4 Entry ineo an OP!llATIOllllL HCO& or oti..r *J?90if iod condition~
(a) 1hall not be made when the condition* of th* timitinq condition for 0519ration are not met and th* a*1ociated ACTIOK requir** a 1hutdcwn if they aze.~ met within a *pecified time interval.
(~) may be made in accordance with ACTION requirmB8nt* when conformance to*~ pe.:mit* continued operation-of the facility *for.an unlimited pu-i.ocl of time.
Thi* provi*ion *hall not __ prevent .P****.9* thro~qb or to OPERATIONAL MODES u required to comply with ACTION requirement*. Exception* to th*** requirements are *tated in th* individual *pecificaticn* *
SALEM - UNIT 2 3/4 0-1 Amendment No. 110
3/4.1. RQFTMn c:gmoL sxsmq 3/4.1.1 BORATION CON'1'!0J, SH0'1'DOWN H11RGDI - 'l'&!f > 2oo*:r
.LOOTING CONDITION FOR OPERATION 3.1.1.1 '?he SHO".rI)ONN MMGDI *ball !)e ;:-tar thaA or eqaa1 to 1.3t delta Jt/t. (
AJIPLICAln:.Itx: !ClD&S l., 2 *, 3 , and 4.
ACTI9H:
With th* SHDfl>OWH MUGDI l*** than 1.3* delta k/k, ;-*diatal.y initiate and f continue boratiOA at 233 vpa of a *olution cont*1ningo 2 6,5&0 ppa boron or eqW.valent until the ~red SHO'mOWN !QRCDI i* r**tored.
4.1.l.l.l 'l'h* SHU'l'ZXJWN ~IN *hall be determined to a ;:eater than or oqu&J.
to l.3t delta k/k:
a.
Within l hoUZ' ~t*r detect.ion ct an inoperable ccnt:o~ rod(*) and at laaat once pe: 12 hour* the:e~te: while the rod(*) i* incper&Cle . .
If th* inoperable control rod i* immovable C!r unt:ipp&Dl*, th* above required SHUTDOWN MJ.RGIN *hal.l ~ inc:euecl by an amount at least equal to th* withdrawn worth cf th* .illaov&Dl* or unt:ippable control rod(s).
/
b. When in ~I l or ~I 2 with Katt q:eater than or equal to l. 0, "t
.least once per 12 hou:* by verityinq that control bazDt witima*al""-::s vi thin the liai ta in the CO~ per Specification 3 .1~3. 5. ~a.l'l'K<s~
c. When in ~DI 2 vi th ~t leH than l. 0, vi thin 4 hour* prior to achievinq reactor criticality by verify2.nq that th* predicted cr1t1cal*cont:ol .rod po*ition ia vithi.Zl the l.iaiu in the COLR per Spec1f1cat:.ion 3.1.3.5.
s.. Special Teat EJi:cept:.ion 3.10.1
SALEM - 'ONI'l' 2 Aaeacteut Ho. 197
RF.ACTIYITY CONTROL SYSTEMS LIMITING-~RDITION FOR OPERATION 3.1.3.4 .All shutdown rocb shall be .FULLY VITHDRAWN .
APPLICABILITY: MODES"i*, and 2*#@.
ACTION:
Yith a maxilllUll of one shutdown rod not FULLY VITHDRAWN, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour either:
a. FULLY VITHDRAV the rod, or,
b. Declare the rod to be inoperable and apply Specification 3.1.3.1.
SURVEILIANCE REQUIREMENTS 4.1.3.4 Each shutdown rod shall be determined to be FULLY YITHDRAWN by use of the group demand counters, and verified by the analog rod position indicators**:
a. Within 15 minutes prior to withdrawal of any rods in control banks A, B, C, and D during an approach to reactor criticality, and
b. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.
See Special Test Exceptions 3.10.2 and 3.10.3.
For power levels below 50t one hour thermal "soak time" is permitted.
During this soak time, the absolute value of rod motion is limited to six steps.
@ Surveillance 4 .1. 3. 4. a ls applicable prior to withdrawing any contro 1 banks in preparation for startup (Mode 2).
With Keff greater than or equal to 1.0.
Note: This page effective prior to startup from fifth refueling outage scheduled to begin March 1990. Letter dated Jan. 11, 1990 .
SALEM
UNIT 2 3/4 1-19 Amendment No. 66
LIMITING COIU>I'l'IOH l'OR OPERATION C!ON~OL... "ROD "J:NbE'~TIOr-.l L.\f'V\lTS
<:, ~Q.V\<a e " b
3.1.3.!i Th* control .bank* *hall be liaitad :in phy*ical :in8ertion u in the CORE OPUATINQ %.IKITS BllaJt'l' (COI.a)
aped.f'ied I Al'PLIWILI'l'I: ltODEI 1 *, aDd 2*1 ACTION:
With the cont:ol ~* i.nmerted beyond the above iDaertion l.imu, 9Zcept ~or aurveillanc:e te*t:i.J:MJ ~nant to Spec:i~icaticm C.1.3.1.2, either:
a. Restore the control ~. to withi.n the J.j,&it. vith:i.n two houra, or
b. Reduce '1'HE>>.GU. POWIK wit!Un two ho~* to l*** than or equal to that fraction o~ RA'?ID THEJQQL POWER which i* allowed by the bank position u*inq th* ina*rtion limit. aped.fied in th* COI.R., er
. c. Be in at least HO'l' S'l:ANDBY *ith:in 6 hou:a.
SORVE II.I.ANO: REQUIJWCHTS 4.1.3.5 Th* position of each control bank shall be dete:ained to be *ithi.n the ins*rtion lim..its at leaat one* per 12 hour* by use of th* group demand count*r* and verified by th* analog rod poaition indicators 0 exc*pt during tim* int*:val.s when th* Rod In.ertion Limit. Mcnitor ia inoperaDl*, then verify th* individual rod position.I at ..leaat ..once per~ hcura**.
See Sped.al T*At &xceptiona 3.10.2 aad 3.10.3
For power levela l:lelow !Ot one hoUZ' the:m&l "soak ti.lie" ia pe:aitted.
During this aoak b.ae, th* al)aolute value of rod action i* l~ted to au
tel>**
I With !Ceff ;r-ter ~ or equal. to 1.0 SAI.EM - tJNl'l' 2 3/C 1-20 Amendment No. 197
POWER pIS'l'RI19TION I.IMt'l'S LIMITING CONDI'l'IOM l'Oll Ol'EAATION (Cc:>nt.inued) ti.
90t of' RA.TC> ~
t:&rqet band . .
c.
~ baa beeZl **t:L*~i.ed. I TH!~ POWZ* *hall no~ in~~ !ot of' RA.Tm THUHAI.
lml.*** ~ ~cated Alt) baa not !:lea outaim o~ ~
I POWEa tuqet ~ aa 8P9ci~ied in -the CO?.lt f'or aore th&D 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months penalty drn.ation cmaul.ative durinq th* previoua 2* hoara. Po~ increaaea
~ sot of' RATEI> 'l'HUM1J.. POWER do not .reqgire ~ nthin the t:a.rqet ~provided the ac:=aulat:Lve p.Dalty dni.aticm j,a AOt viola~.
SORVEILU.NCE REQOIUMl:N'l'S 4.2.l.l 'l'he indicated AXUl. FLUX DIFFEIU!NC! shall be deteZ1U.ned to be with.in its limita ~nq POWER OPEl\M'ION al)ove lSt o~ RAUt> TKIRMAL POWER. by:
a. Mc:>ni.torinq th* .indicated fc:>r each OP!RABI.1 ucore channel:
A!'!)
l. At least one* per 7 days when the Am Mc:>nitor Al&%S ia OPERABLE , and.
2. At least once per hour for th* fi.rat 2* hou.ra aft.:
restoring the An:> Mc:>ni tor Ala.z:m to OPERABLE statue.
-b. Mc:>nitcri.nq and. lo9¢n9 -th* 1.nd.icated. AXIAI. *FI.lJX 't>I!TERENC:Z !'or each OPERABI.Z exco.re channel ~ least once per hour ~or the first 24 hc:>u.rs and. at least one* per 30 &inutea thereafter, when th* AXZAI.
FLUX DI!TERJ:Na M.onitc:>r Al.us is inc:>peral:lle. Th* lc:>c;qed. value* of the indicated AXIAL FLUX DIFFERENCE shall be &HWled tc ex:i.st du.ring th* .:i.nt*rva.1 prec=em.nq each lc:>ql)inq.
4.2.l.2 'l'h* .indicated Am shall be ccnaidered outaide o~ ita tarqet band. vhen at leaat 2 er aore ORRABI.& ucore channels &:* ~cat:Lnq th* Al1:> tc be outa.:i.de th* tarqet band. Pen.alty ~at:Lon cutaide o~ the target band. ah&l.1 be accuaula eecl en a t.:Lae baaia o~:
a. Ofte_.m.:iute-penalty-cariatiozi ..f'or--ch-*one-ai.nute*of'-PORZJt OPERA'l'IOK outa.:i.ct. o~ the t&r9*t band at ~ i-onJl i.vei. equal to or above 50t o~ RABI) '1'HE~ IOWla, and ** ' *' -
ti. One-hai~ ainute penalty ~ation ~or -ch one m.Aute of' 1'0WER OPERATION outside o~ th* target band at 'l'HE~ PONllt le'"1a below SOt of RAftt> THE~ POWEJt *
31* 2-2 AIDendmen t No. 197 SAI.EK - tJNI'l' 2
TABLE 3.3-l IContinutdl
ACTION_ 10 -
With the number of OPERASI.!: Channel* one le** than the Minimum Channel* OPERABLE requirement, r**tore the inoperable channel to OPERABLE *tatu* within 6 hour* or be in at lea*t HOT STANDBY in the next 6 hour*1 however, one channel may be bypa**ed for up to 4 hou~* for *urveillance t**tin9 par Specification 4.3.l.l.l provided th* other channel i* OPERABLE.
ACTION 11 - With le** than the Minimum Number of Channel* OPERABLE, operation may continue provided the inoperable channel i*
placed in the tripped condition within 6 hour*.
ACTION 12 - With th* number of channel* OP!RABLB one l*** than required by the Minimum Channel* OPERABLE requirement, r**tore the-inoperable channel to OPERABLE *tatu* within 48 hour* or be in HOT STANDBY within th* next 6 hour* and/or open th*
reactor trip breaker**
ACTION 13 - With th* number of OP!RABLZ channel* one l*** than the Minimum Channel* OPERABLZ requirement, r**tore the inoper&Dla chan~*l to OP!RABLZ *tatu* within 48 hour* or open th* reactor tr~p breaker* within the next hour.
ACTION 14 - With one of the diver** trip feature* (Undervoltage or *hunt trip attachment) inoperaala, r**tore it to OP!RABLZ**tatu*
within 48 hour* or declare the breaker inoper&Dl* and be in at l*a*t HOT STAHI>IY within 6 hour*. The breaker *hall not be bypa***d while one of th* diver** trip feature* i* inoper&Dl*
except for the time required for performin9 maintenance to r**tore the breaker to OP!RABLZ *tatu**
RIACTQB TBIP SXSTIM ImBLOCJtl DESIGNATION CQNQITION AHQ SITPQIN'l' ryNCTIOI With 2 of 2 Int*rmediate Rani!i P-6 prevent* or def eat*
Neutron Plux Channel* < 6x10 the manual block of amp** *ource ran9e reactor trip.
Wi~k 2 of 4 Power Range Neutron P-7 prevent* or d s:'i...Vll Ch l* It 11' of RA'l'ID th* automatic blo TBJl'ulAL POW&Jl or 1 of 2 Turbin* reac:tor trip on1
~ . . . .-1** chamber pr***ure channel* a a pr***ur* equivalent flow in more the one primary coolant loop, to 11' of RAriD THZJUW. POVD. reac:tor coolant pump
._ undervolta9* and under-frequency, pr***uria*r low pr***ure, pr***uriaer hi9b level, and the openin9 of more than one reac:tor coolant pump breaker.
SALO - UNIT 2 3/4 3-7 Am9ndll9nt No.121
*TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL, cttA t-lN cl- FOHCTIONAL SURVEILLANCE FOHCTIOHAL DNIT CHECK CALIBRATION TEST REQUIRED
1. Manual Reactor Trip Switch N.A. R1111 1, 2, and *
2. Power Range, Neutron Flux s ol2J I Mill and Q"'
Q 1, 2, and 3* I
3. Power Range, Neutron l'lux, N.A. R'" 1, 2 Bigh Po*itive Rate
... Power Range, Neutron Flux, Bigh Negative Ralte N.A. R 1, 2
5. Intermediate RAnge, Neutron Flux s Rce11 s/u 1u 1, 2 and *
6. Source Range, Neutron Flux s 111 R Q and s/u'i' 2, 3, 4, 5 and *
7. Overtemperature AT s R Q 1, 2
8. Overpower AT s R Q 1, 2
9. Pre**urizer Preaaure--Low s R Q 1, 2
10. Pre**urizer Prea*ure--Bigh s R Q 1, 2
11. Pre**urizer water Level--Bigh s R Q 1, 2
12. Lo** of Flow - Single Loop s R Q 1 SALEM - UNIT 2 3/4 3-11 Amendment No. 187
TABLE 4.3-1 (Continued)
CHANNEL MODES IN WHICH CBANHEL FUNCTIONAL SURVEIL~CE FUNCTIONAL UNIT CHECK TEST REQUIRED
13. Lo** of rlov Two Loop* s R N.'6. *1 ci I'
14. Steam Generator Water Lev*l--Low-Low s
,~
Ii '6'
.. R Q 1, 2
15. DELETED
16. Undervoltage - Reactor Cool&n~ Pualp* N.A. R 1 1 7. Underf'requency - Reactor Cooiant Pump* N.A. R 1
18. Turbin* Trip
a. Low Autostop Oil Pressure N.A. N.A. s/uu1
b. Turbin* stop Valve Closure N.A. N.A. S/UUI I a "2....
19. Safety Injection Input from ESF N.A. N.A. M'" 151
20. Reactor Coolant Pump Breaker N.A. N.A. R Po*ition Trip 21.
i Reactor Trip Breaker N.A. N.A. MC51 1111 cu1 and acui 1, 2 and
I
22. Automatic Trip Logic N.A. Mesi N.A. 1, 2 and *
".l."
~
SALEM - UNIT 2 3/4 3-12 Amendment No. 157
INSTRUMENTATION
3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.l The Enqineerad Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5. .
APPLICABILITY: As shown in Table 3.3-3.
ACTION:
a. With an ESFAS instrumentation channel trip satpoint less conservative than the value shown in the Allowable Values column of Tabla 3.3-4, declare the channel inoperable and apply the applicable ACTION
requirement of Tabla 3.3-3 until the channel is restored to OPERABLE status with the trip satpoint adjusted consistent with the Trip Setpoint value.
b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4.3.2.l.l Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CH.AmtEL CA+-IBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at frequencies shown in Table 4.3-2.
4.3.2.1.2 The loqic for the interlocks shall be demonstrated OPERABLE durinq the automatic actuation loqic test. The total interlock function shall be demonstrated OPERABLE at least once per 18 months durinq CHANNEL CALIBRATION tastinq of each channel affected by interlock operation.
4 . 3 . 2 .1 . 3 The ENGINEERED SAFETY FEATURES RESPONSE TIMI of each ESFAS function shall be demonstrated to bQ within the limit at least once per 18 months. Each test shall include at least one logic train such that both loqic trains are tested at least once per 36 months and one channel per function such that all channels are tasted at least once per N times 18 months where N is the total numbe~ of redundant channels in a specific ESFAS function as shown in the "Total No. of Channels" Column of Tabla 3.3-3. Tho provisions of Specification 4.0.4 are not applicable to MSIV closure time tasting. The_ provisions of $pecificati.on. 4. 0. 4 . are not applicable to the turbine driven auxiliary feedwater pump provided the surveillance is performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after th* secondaJ:Y steam generator pressure is greater than 680 psiq.G)--e.--"
n to this s inq Unit 2 surveill SALEM - UNIT 2 3/4 3-14 Amendment No.198
TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNI.T CHECK CALIBRATION TEST REQUIRED AUXILIARY FEEDWATER 8.
a. Automatic Actuation Logic N.A. N.A. M(2) 1,2,3
b. NOT USED
c. Steam Generator Water s R Q 1,2,3 Level...;.'-Low-Low
d. Undervbltage - RCP s R Q 1,2
e. S.I. See 1 above (All S.I. surveillance requirements)
f. Trip of Main N.A. N.A. S/U(4) 1,2 Feedwater Pumps
g. Station Blackout See 6 and 7 above (SEC and U/V Vital Bus)
9. SEMIAUTOMATIC TRANSFER TO RECIRCULATION
a. RWST Low Level s ** R Q 1,2,3
b. Automatic Initiation Logic N.A. N.A. 1,2,3,4 SALEM - UNIT 2 3/4 3-36 Amendment No. 156
INSTRUMENTATION
3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITI~N FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.
APPLICABILITY: As shown in Table 3.3-6.
ACTION:
a. With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.
b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable~
SURVEILLANCE REQUIREMENTS *
4.3.3.1 Each radiation monitoring instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECg,,CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.
S OURte'. C..li t:: C.K )
SALEM - UNIT 2 3/4 3-38
TABLE 9. !Coi.tinuedl RADIATION MONITORING INSTRQMENTATION MINIMUM CHANNELS APPLICABLE ALARM/TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE
ACTION
2. PROCESS MONITORS
b. Noble Gas Effluent Monitors i
1) Medium Range Auxiliary 1* 1,2,3&4 s3. ox10*2µci/cm 1 26 Bu~lding Bxha~at System (Alarm only)
(Plant Vent) i
2) High Range Auxiliary 1 1,2,3&4 sl. Ox10 2µCi/cm 1 10*1-105 µCi/cm1 26 Building Bxhaust System (Alarm only)
(Plant Vent)
3) Main Steamline 1/ 1,2,3&4 10 mR/hr 1-10* mR/hr 26 Discharge (Safety MS Line (Alarm only) vaives and Atmospheric steam Dumps)
4) Condenser Exhaust 1 1,2,3&4 s7. 12x10* cpm 1-10' cpm 26
system (Alarm only) i 3* CONTROL ROOM
a. Air Intake - 2/Intake## ** s2. 48x10 1 cpm 10 1-101 cpm Radiation Level I# Control Room air intakes shared between Unit 1 and 2.
ALL MODES and during movement of irradiated fuel assemblies and du SALEM - UNIT 2 3/4 3-39a
1*
((. (.(. "
Amendment No.173 I
TABLE (Continued) 3.3-6 TABLE NOTATION ACTION 23 - Witft the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
ACTION 24 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.l.
ACTION 25 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.
ACTION 26 - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:
l) either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or *
2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlini,ng the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
ACTION 27 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel(s) to OPERABLE status within 7 days or initiate and maintain operation of the Control Room Emergency Air Conditioning System (CREACS) in the pressurization or recirculation mode of operation. CORE AL'.I'ERATIONS and movement of irradiated fuel assemblies will be suspended during operation in the recirculation channels OPERABLE in a Control Room air intake, ediately initiate and maintain operation of the CREACS in the essurization or recirculation mode of operation.. CORE
.. ALTERATIONS -*and--movement*-of--irradi-ated**fuel* assemblies will be suspended during operation in the recirculation mode .
SALEM - UNIT 2 3/4 3-4.0 Amendment No.173
INSIRtJMENIAIION ACCIDENT MONITORING INSIR1JMENIATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The accident monicoring inscrumenc~cion channel* shown in !*ble 3.3-ll shall be operable.
APPLICABILirt: MODES l, 2, and 3.
ACTION:
a. As shown in Table 3.3-ll.
b. The provisions of Specificacion 3.0.4 are not applicable.
4.3.3.7 demonstrat CHANNEL C 4.3-ll.
SALEK
UNIT 2 3/4_3*50 Amendment No. 95
TABLE 3. 3-11 ACCIDENT MONITORING INSTRUMENTATION REQUIRED MINIMUM NO. OF NO. OF INSTRUMENT CHANNELS CHANNELS ACTION I
1. Reacto~ Cool~n~; ,~f ~*~, 1l'~~era tu re - 2 l 1,, 2 TllOT Olide Ran~fl ;J;*il* :,f : * *, *
..... ~, .. , *!* . r
2. Reacto~ Cool.in~/~9.4~f JpPerature - 2 l . 1, 2 I~ '~Hie_ ~~'~" ,.j:~t**:*-~ . ' *.
f. a~~f G~~ ~~~h~i~:;~~~;~-t~lf \d~*. ~if'>9.~ l 2 l .1, 2
4. Press~rizer Wat~r Level 2 l 1, 2
5. s~eam Line Pressure 2/Stearn Generator l/Stearn Generator 1, 2
~- ~~ea'!' <!ei;ttli=~~~r Wat~r L~vql 'Narrow 2/Stearn Generator I/Stearn Generator 1, 2
' Range) ~-
1. Steam Generator Water Level (Wide 4~earn Generator) 3 (!/Stearn Generator) l, 2
~~,~~>.:
~*,, R~~~,};~Bi ija~*H*. ~~Q~age T~ok W~~er 2 l l, 2 Levol *
. * *I ' ..
deleted 10.
h ~~~l..~1'rl.~e~~~e~ pow ~t~ 4 (l/~te~rn Generator) 3 (l/~tearn Generator) 4, 6
11. ~e~c~~f Co~lapt :JY.~f~Jll Subco9l.iQ9 2 1 1, 2 I .t
~rgin Hon1tor 12~ PORV Position Indicator 2/valve** l 1, 2
\
SALEM - UNIT 2 3/4 3-51 Amendment No. 125
TABLE 3.3-11 (continued)
TABLE NOTATION ACTION 1 With the number of OPERABLE accident monitoring channels less than tfte Required Number of Channels shown in Table 3.3-11, restore the inoperable channel(s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
ACTION 2 With the number of OPERABLE accident monitoring channels less than the Minimum Number of Channels shown in Table 3.3-11, restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT SHUTDOWN ,within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
ACTION 3 deleted ACTION 4 e less than the Required Table 3.3-11, a ions may roceed provided that an OPERABLE Steam Generator Wide Range Level channel is available as an alternate means of indication for the Stearn Generator with no OPERABLE Auxiliary Feedwater Flow Rate Channel.
number of OPERABLE channels less than the Required Channels shown in Table 3.3-11, operation may proceed provided t Stearn Tables are available in the Control Room and t~e following Requir Channels shown in Table 3.3-11 are OPERABLE to provide an alternate ns of calculating Reactor Coolant System subcooling margin:
a. Reactor Coolant (Wide Range)
b. Reactor Coolant Pressure (Wide Range)
SALEM - UNIT 2 3/4 3-Slb Amendment No. 125
TABLE 4.3-11 SURVEILLANCE REQYIREMENTS FOR ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHANNEL IN§TRUMENI CHECKS CALIBBATION ,,
1. Reactor Coolant OUtl~t Temperature - M R THOT (Wide Range)
2. Reactor Coolant Inlet Temperature - M R ...-BA""" N. A.
TcoLD (Wide Range)
3. Reactor Coolant Pressure (Wide Range) M R ~ N.A.
4. Pressurizer Water Level M R J1K ~.A.
s. steam Line Pressure M ~ tl.A.
6. Steam Generator Nater Level M pl(" tJ. A*
(Narrow Range)
7. Steam Generator Water Level M ~tJ.A*
(Wide Range) :
8. Refuelin~ Water Storage TanJc Water Level M ;uf N*A*
9. deleted
10. Auxiliary Feedwater Flow Rate
11. Reactor Cool~nt System Subcooling M ,, 11
.,._rgin Monitor ~ 1.(.
Auxiliary Feedw~ter System is used on each startup and flow rate indicacion is verified at that time.
The instriunents usdd to develop RCS subcooling margin are calibrated on an 18 month cycle; the monitor will be CfllllP*~ed quarterly with calculated subcooling margin for known input values.
.... 411.
SALEM - UNIT 2 3/4 3-52 Amendment No. 125
TABLE 4.3-11 (Continued)
SURVEILLANCE REQUIREMENTS FOR ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECKS TEST
12. PORV Position Indicator M R
13. PORV Block Valve Position Indicator M Q*
14. Pressurizer Safety yalve Position M Indicat9~
15. Containment Press~e - Narrow Range M )J1IC
16. Conta~nment '
Pressure - Wide Range M R t ,, )IK
17. containment Water Level - Wide Range M R ~"bb JiK' f\l. A I
18. core Bxit Thermocouples M R ~ tJ, A.
19. Reactor Vessel Level Instrumentation M R ,)111( rJ. A.
System (RVLIS)
Unless the bl~ck valve is closed in order to meet the requirements of Action b, or c in specification 3.4.5.
I SALEM - UNIT 2 3/4 3-52a Amendment No. 136
TABLE 4.3-12 (Continued)
TABLE NOTATION (1)
The CHAMEL FUNCTIONAL TEST shall also denanstrate that auto*ttc fsahtfon of this pathway and cantral rao* 11ar111 annunchtfon occurs 1f i"1 of the fo 1lowf ng condtttons ext st: * *
1. Instru*nt tndtc1t11 masured lev*ls at or 1blne the 1l1r*/trf p S*tpo1nt.
2. Ctrcutt failure.
3.
(Loss of Po*r) (Auto*ttc Isolation only)
Instru*nt t_ndtcates a cmwnscale failure. I-(2) The CHANN!L FUNCTIONAL TEST shall also demnstrata that CDntrol rao* *hr*
1nnunct1tton occurs tf any of the fallowtng condttfons extst:
1. Instru*m: fndtc1tes **sured lev*ls at or setpotnt.
bo* the alarm/trip
2. Circuit failur*. (Loss of lta*r) (Indtcatton only)
3. Instrul9nt f ndtc1t1s 1 dawnscale failure
t
(3)
4. InstruNnt controls not set fn operate nade
The 1nft1al CHANNEL CALIBRATION was perfor1111d using apprapr11t* 1fqutd or gas10us c1ltbr1tton sources obtained fro~ reputable supplf*rs. The actf vtty of th* calfbratfon sources. -.r* recanffr ..d ustng 1 111ltf-ch1nft9l analyzer wtltd'I was calfbt"atld usfng one or 11are NBS standards *
. (4) CHANNEL CHECK shall cansht of *rttytng fndtcatfon of flow during i-rtods of rtltase. CHMNEL CHECK shall be Ndl at least onca per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on wntcn canttnuous, pertodtc, or bitch releases .,.. * * *
Durt ng 1tqutcl ldd1t1ons to the tank.
If tank le*l 1nd1catfon ts fDt provtdld, ftrttftcatfon wt11 be daft9 by visual fnspectton.
The Rl8 chlnrie ts an o-ff*lt* dlanft91 which requires perfadtc decontalllinat1on ArtJ munt rate tndf cat fan 1bav.t 10,000 cp* mnstftutes a SouR C E...C:HANNeCHECIC ~ CDllPl fanca purposes.
SALEM
UNIT 2 3/4 3-58 Amencinent No. 36
TABLB t 3 - 13 I
BJWIQACTIVB QASBOUS BFFLQBN'f MQNITQRINQ INSTRlJHlijUTATIOH SURViILLAUCB RBOQIRiMitfTS CHANNEL HODBS IN WHICH RCB CHANNEL FUNCTIONAL SORVBILLANCI INSTRUMENT CALIBRATION TBST RaQUIR&D 1 I Nf'STB GAS HOLDUP SYSTIH *
Noble Gaa Activit;y Honitor Providing p R (3) Q(l)
AlapD and AutCllatic Termination of Release
b. Oxygen Monitor D N.A. Q (t) M **
2. corrrAIHMBHT PORGB AND PRBSSURB - VACUUM RELIEF
a. Noble Gaa Activity Hon.tor - Providing P p R (3) Q(l) ***
Alal;'lll and Automatic Termination of Release
3. PLANT VKHT HBADBR SYSTEM#
a. Noble Gas Activity Monitor D M R (3) Q(l) *
b. Iodine Saq>hr w N.A. N.A. N.A. *
c. Parti~late Sampler w N.A. N.A. H.A. *
d. Flow Rate llon~tor D H.A. R H.A. *
e. Sampler Flow Rate Monitor w N.A. R N.A.
I The following ~recess streams are routed to the plant vent where .they are effectively monitored by the in*trwnenta dea~r~bed:
(a) Condenser Air Removal System (b) ~iliary Building Ventilation System (c) Puel ~andling Building Ventilation System
'I (d) Radwa*te Area Ventilation Syatem (e) Containment Purges Amendment No. 138 SALEM
UNIT 2 3/4 3-63
Slll.VIIUARCI UQUllEMDrs ( Coacinuad) 4.3.4.3 the above required turbine overapeed proeeocten ayat..
hall be d **crated Ol'ELULE:
A& leut .Rll~~r 18 montha by performance of-* ~ CHADll; CALI OR on turbine ovarapeed protection ayat....
0 ..sce
b. At l t~per month* by diauaembllna at leut one of each of fhe valvea and performina a vi.ual and *urface inapec valve aeat*, diaka and at... and verifyina no unacceptable flava or corroaioa. If unacceptable !lava or exce*aive corroaion are found, all other valvea of that type aball be lmpected.
4.3.4.4 Verify th* te*t frequency ..intaiiw the probability of a *i**ile ejection incident within Nae guideline* by revt.evtns tb9 ..thodology pr***nted in WCAP*11525:
a. At leut once every two refuelina outaaea.
b.
After mod1f1catiom to* th* *in turbine or turbina overapeed
'rotection valve*.
SA,! D
URIT 2 3/4 3.,, MIMmDC .... 97 L
REACTOR COOLANT SYSTEM HOT SHUTDOWN LIMITING CONDitION FOR OPERATION.
3.4.1.3 a. At least two of the coolant loops listed below shall be OPERABLE:
1. Reactor Coolant Loop 21 and its associated steam generator and reactor coolant pump,*
2. Reactor Coolant Loop 22 and its associated steam generator and reactor coolant pump,*
3. Reactor Coolant Loop 23 and its associated steam generator and reactor coolant pump,*
4. Reactor Coolant Loop 24 and its associated steam generator and reactor coolant pump,lll
5. Residual Heat Removal Loop 21,
6. Residual Heat Removal Loop 22.
b. At least one of the above coolant loops shall be in operation.**
APPLICABILITY: MODE 4.
ACTION:
a. With less than the above required loops OPERABLE, ;11111ediately initiate corrective action to return the required loops to OPERABLE status as soon as possible; be in COLD SHUTDOWN w;thin 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .
b. With no coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and i11111ediately initiate corrective action to return the required coolant loop to operation.
A reactor cooia shall not be started with one or more of the RCS cold leg tures s than or equal to 312°F unless 1) the pressurizer water vol is less than 1650 cubic feet (equivalent to approximately 921 of 1ev or 2) the s condary water temperature of each,, steu generator is less ..t an .SQO.F~bov*- ac:h-of-the RCS-*co1d*-1eg temperatures.
UllPS may be de-energized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided 1) no operati s are P*nli d that would cause dilution of the reactor coolant syste11 ron concentrat n, and 2) core outlet temperature is maintained at le st 10°F~ below S uration temperature. \...,_
\
SALEM - UNIT 2 3/4 4-3
REACTOR COOLANT SYSTEM tlt*/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION*
3.4.7. 1 Th* following Reactor Coolant System leakage detection syst... shall be OPERABLE: _
a. The contain11ent atllosphere particulate radioactivity 110nitoring sys ta,
~ The containMnt pocket Sl.llP level monitoring system, and
c. Either the contai,...nt fan cooler condensate f1ow rate or the contain-
..nt atllosphere gaseous radf oactfvity 110nitorf ng syst.11.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
. With only two of the above required leakage detection syst.ms OPERABLE, opera*
' tion *Y continue for up to 30 days provided grab suples of the contaf,..nt ..
tllosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the quired gaseous and/or particulate radioactivity 11anitoring system f 1 operable; otherwise, be in at least HOT STANDBY within the nut 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .
SURVEILLANCE.RE UIREMEHTS 4.4.7. 1 The leakage detection systtms shall d OPERABLE by:
a.
b. Contaf rmen pocket SUllP level and contairment an cooler condensate f1ow rate (ff befng used) *nftoring 1y1i..t*pe o
of CHANNEL CALIBRATION at leut once per 11 llOnths *
SALEM
UNIT 2 3/4 4-11 I
QACTOB CQOL.NfT SX!ITg 3/f,f,9 SPJCIP?C AC'f:ryITX
I.IJll'1'?118 CIOllDlTlCJB roa

*****-*--*~**

3.4.9 a.
OPDATIOll .
Tbe 8P9Gifia ac:Ci*ity of th* primary coolant *hall be limited toa S 1.0 #'Ci/gr.. DOSS BQUIVAL&llT -?~131, and
b. -
S 100/S l&Ci/graa.
APPLICMILift1 HODSa 1, 2, 3, 4 and 5.
ACTIQ11 HODSa 1, 2 and 3*
a. With the *pecific aceivity of the primary coolant > 1.0 pCi/qraa DOS* SQUIVU.m I-131 for more than 48 hour* ~in9 one continuou*
time interval or excHcU.n9 the limit line *hown on Pigure 3.f-1, be in at l*a*t BOT STAllDBY with T avv < soo** within ' hour*.
b.
With th* *pecific aceivity of the primazy coolant > 100/* pCi/gr1a, be in at l*amt BOT STAHDBY with Tavv < soo*r within & hour**
MODSS 1, 2, 3, 4 and I
a. With the *pec:ific aceivity of th* p coolant > 1. Ci/grm DOSS BQUIVALD'f I-131 or > 100/S p /gr,,., perform th*
ling and analy*i* requirement* of itea 4a Table~until th* cific aceivity of the primary coolant i it* limit*.
I 4.4.9 'l'he *pecific aceivity of th* pr~l.r"J~oolant *hall be det mined to be within the lillit* by perfomanc* of t *ampli119'and ana *i*
prograa of Table 4.4-4.
with T avv -
> soo*r.
SALD - UlflT 2 3/4 4-23 ~ndment No. 112
REACTOR COOLMT SYSTEM*
3.4.11 STRUCTURAL INTEGRITY ASME CODE CLASS 1 2 Ind 3 COMPONENT$
I UMmNG CONDITION FOi OPERATION*
3.4.11.l *The structural 1nt.gr1ty of ASMI Code Cl nents shall be *intainad in accardanc* with Spec1f1ca APPLICABILITY: ALL tlJDES.:
ACTION:
L * "'1th the structural f ntev1 ty of any ASMI *Code Cl u* l cC..,Onent(I) not cantonrtng to the above requi~ta., restore the* structural fnt.gr1ty. of the affected C011POMnt(1) to wttlifl\ 1ta 11stt or isolate tM afflC'ted c011pOnut(1) prior to f ncr1a11ng the R*actor Caolant Systa. tlilperature .,... than SG°F above th8 *1 n1. . taperature requ1Nd by flJT cana1derat1ons. * ..
b. With the 1tructu~l 1nt8gr1ty of any ASME Code Clu1 2 CGllPOnent(s)
..... not canforaing to the above requ1......U, re1tow:e tM structural i*nt.grity of tn. affected cmponilat(s) to ~thin fta lfstt or 1solat8 the afflC'tid caaponent(s) prior to 1ncnu1ng the Ructor ~lant Syst.. t.perature above 200°F.
c. W1tb the structunl 1ntegrtty of any ASME Code C1u1 3 component(*)
not canfol'll'fng to the above requi'NMftta, NltoN it. struetural
1ntegMty of tfte afflC'ted cmponent(s) to within 1ta 11*1t or isolate tJle afflC'tad cmponut(1) froa s*nic..
d. Th* pl'O'l'f 110... of Specification 3.0.4 are not appltcabl*~
SURVEILLANCE REQUIREMENTS
4. 4.11.1 In acld1tf.0n. to. the requi remnts .. of .Speci f1 cati.on ,4. f. 5, each R11cto ...
Coolant Pmp flywt.el shall be inspected per the rec:omendat.1on1 of Regulatory Position C.4.b of Raaulatory Guide 1.14, R*visfon 1, August 1975.
4.4.11.2 A~nt.d In1ervfC8 Inspect.ton Progr.. for Staall Generator Channel H1ad1 - Thi
Zl stui Ginerator Criirinei h11d shill be u1tr11on1cally 1n1pecud in 1 selected area.during **ch of the f1"t th"9 refueling outag11 using the s. . ultruon1c f nspectfon procadura and equipment used to g1nerat1 the baseline data. These in11n1c* ultrasonic inspect.ions shall verity that the cracks observed in the stainless st.Hl cladding prio* to aperatfon have not propagated fnto th* base *terfal.
SALEM
UNIT 2 3/4 4*33
!QBGERCX CORI COOLitfG SYSD'JIS ECCS SUISXSTEMS - Tays <3So*r LIMITING CONDITION FOR OPERATION 3.5.3 ,.. a minimum, one ECCS subsystem compri*ed of the following *hall be OPERABLE:
a. One OPERABLE centrifugal char_ging puap# am u*ociated flov path capable of taking suction fro* the refueling water *torage tank and transferring suction to the residual heat re110Val puap di*charge piping and;
1. Diacharging into each Reactor Coolant Syatea (RCS) cold leg.
b. One OPERABLE re*idual heat re110Val pump and u*ociated reaiclual heat removal heat exchanger and flov path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction t~ the containment sump during the
recirculation phaae of operation and;
1. Discharging into each RC! cold leg, and; upon ll&llU&l initiation,
2. Discharging into two RCS hot leg*.
AlPLICABILITX: MODE 4.
ACIIQB:
a. With no ECCS subsystea OPERABLE became of the lnoperability of either the centrifugal charging pump or the flov path froa th*
refueling water storage tank, re*tore at leut one ECCS subsystem to am:iAitris~tu within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWR within the next 20 houra.
sub*yst- OPERABLE became of the inoperability of dual heat re110val heat exchanger or r**idual heat
, restore at l=ast one ECCS *ub*y*t- to OPERABLE atatus or - the lleactor Coolant Sy*tea T l*** than 35o*p by use a tarnata beat removal -thoda. avg
c. In m.*ewnc the ECCS la actuated and inject& vatar into th* Reactor Coolant:, Syatea, a Special Report aball be prepared and submitted to tbe eo..taaion pursuant to Specification 6.9.2;withln 90 day*
-*cSeacribing*the eircuutanc** of* the actuation and the total acc\mll.ated actuation cycle* to date. '1'he current value ef the usage factor for each affected safety injection nozzle *ball be provided in thia Special Report vbenev.r ita valu. aceeda 0.70.
A uximua of one aaf*ty injection pump or one centrifugal charging pump shall be OPllAILI in MODI 4 when th* temperature of om or 111Dre of the RCS cold lega i* le** than or equal to 312*r, Mode 5, or Koda 6 when the head is on the reactor ... ssel.
SALEK
lJRI'I' 2 3/4 5.7 DandMnt No .'t.o
EMERGENCY CORE COO LIN6 SYSTEMS REFtE LING WATER STORAGI TANK LIMITING CONDITION FOR OPERATION 3.5.5 The refueling water storage tank (RWST) shall OPERABLE wft".
a. A contained volume of b*tween 364,500 and 4 ,ooot';~tld wat r.
b. A boron concentration of between 2,300 and "
c. A m1n1~* water t1111P*r1turt of 35.,.
APPLICABILITY: MOIES 1, 2, 3 and 4.
ACTION:
With the refueling w1t1r storage tank fncperabl*, restore the tank to* OPERABLE status wfthf n 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be fn at least HOT STANIBY w1th1n I hours incl fn COLD SHllTCDWN withf n th* follc.ing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months *
SlR'IE I LLANCE REQUIREMENTS 4.5.5 Th* RWST Shill be daanstratld OPERA81!:
a. At least one* per 7 days by:
1. Vtri fy1 ng th* Wit tr 1*ve1 1n the tank , and
2. Verifying* th* boron concentrat1on of the water.
b. At least once per 24 hou" by verifying th* RWST t111Per1ture when the ouU1d9 a1r t111P*r1ture 1s < 35.,:.
SALEM
UNIT 2 3/4 5-9 Amendment No. 55
3/4.6 CONTAINMENT SYSTEMS
3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTBGRITY LIMITING CONDITION FOR OPBRATION 3.6.l.l Primary CONTAINMBNT INTBGRITY shall be maintained.
APPLICABILITY: MODBS 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTBGRITY, restore CONTAINMENT INTBGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .
SORVBILLANCE REQUIREMBNTS 4.6.1.1 Primary CONTAINMENT INTBGRITY shall be demonstrated:
a. At least once per 31 day* by verifying that all penetra capable of being clo**d by OPERABLB containment autsllfiiii"E1~~
valv** and required to be closed during accident re closed by valves, blind flange*, or deactivated utomatic v v secured in their positions, except for valv** t at ~-r/"'c ned y under Administrative contro*l aa permitted by Spec o 3.6.3,...Y, and all equipment hatch** ar* closed and seale9.
b. By verifying that each containment air lock i* OPBRABLB per Specification 3.6.l.3.
c. After each clo*ing of a penetration subject to Type B t**ting, except containment air lock*, if opened following a Type A or B te*t, by leak rate t**ting in accordance with th* Containment Leakage Rate Testing Program.
d. At least once per 12 hour* by verifying that th* *urveillance requirements of 4. 6. 2. 3 .*a are met for p*n*t:ration* a11soci~ted with the containment fan coil unit*.
e. At l***t once per 18 month* by verifying that the surveillance requirement* of 4.6.2.3.d are met for penetration* a**ociated with the containment fan coil unit*.
Bxcopt vents,* drain*;;**te*t connection** etc. *which are "(l) on* inch nominal pipe diameter or le*** (2) located in*id* the containment, and (3) locked, sealed, or otherwi** **cured in the clo**d position. Th***
penetration* shall b* verified clo**d at lea*t one* per 92 day* *
SALJDI - UNIT 2 3/4 6-1 Amendment No. 193
CONTAINMEN'l' SYSTEMS CONTAINMENT STROCTCRAL INTEGRITY LIMI'l'INCI CONDI'l'IOHI,. !'OR OPDA'rIOH 3.6.1.6 'l'he atructural inteqrity of the containnmnt *hall level conaiatent with the acceptance criteria in Specifica APPLICABILITY: MOOJ:S 1, 2, 3 and C.
AC'l'IOH:
With the *tructural inteqrity of the cont:&immnt not conf'ozain9 to the above requi%'91Dent8, re*tore the atructural inteqrity to within the limit* within 2C hour* or be in at lea*t BO'l' S'l'ANDBY within the nest 6 hour* and in COLD SBt1'1'DOWH-within th* followin9 30 hou:*.
SCRVZILLAHC:Z RE_SIOIJUl:MZH'rS C.6.1.6.1 contai=-nt Su:facea '1'he *tructural intec)zity of the ezpoaed acce**ible interior and ezterior *urface* of the containnmnt, includinq th*
liner plate, 9hall.. be ct.tezmined in accordance with the contaimlll9At Leakaqe ..
R&te 'l'eating Proqram C.6.1.6.2 Report* Any abnozmal de4)rad&tion of the containmmnt atructure detected durinq the above required inapectiona *hall be evaluated for reportability purauant to 10Cl'RS0.72 and 10Cl'R50.73. '1'he evaluation *hall be documented and *hall incluct. a d9*cription of the condition of the concrete, the inapection procedure, the tolerance* on crackin9, and the corrective action taken .
SALDI - tlHI'l' 2- 3/4 6-8 Amenc:lment No. 112, 1SS, 188
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
4.6.3.2 Each containment isolation valve shall be demonstrated OPERABLE during the COLD SHOTDOWH or REFUELING*MODE at least once per 18 months by:
a. Verif~ing that on a Phase A containment isolation teat signal, each Phase A i~olation 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.
4.6.3.3 At least once per 18 months, verify that on a main steam isolation test signal, each main steam isolation valve actuates to its isolation position.
4.6.3.4 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested -
pursuant to Specification 4.0.5.
4.6.3.5 Each containment purge isolation valve shall be demonstrated OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after each closing of the var~e, except when the valve is being used for multiple cyclings, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.SalaaSS!""'for all other Type B and c penetrations, the combined leakage rate i less than r equal to o .*6oLa.
4.6.3.6 A pressure drop test to identify excessive degradation of resilient valve seal* shall be conducted on the:
a. Containment Purge Supply and Exhaust Isolation Valves at least once per 6 months.
b. Deleted *
SALEM - UNIT 2 *3/4 6-15 Amendment No. 4 93, 1 72
PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION
~
3.7.l.S Each main steam line isolation valve shall be OPERABLE.
APPLICABILITY: MODES l, 2 and 3 ..
ACTION:
MODES l - With one main steam.line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; Otherwise, be in MODE 2 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
MODES 2 - With one or more main steam line isolation valve(s) inoperable, and 3 subsequent operation in MODES 2 or 3 may proceed provided;
a. The isolation valve(s) is (are) maintained closed, and
b. The isolation valve(s) is (are) verified closed once per 7 days.
Otherwise, be in MODE 3, HOT STANDBY, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and MODE 4, HOT SHUTDOWN, within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
SURVEILLANCE REQUIREMENTS 4.7.l.S OPERABLE pursuant to The provisions o .4* are not
SALEM - UNIT 2 3/4 7-10 Amendment No. 170
PUN'! SYS'!'!MS SURVEILLANCE REQUIREMENTS (Continued)
3. Snubber rel~se rata, where required, is within the specified range in compression or tension. For snubbers specifically required not to displaca under continuous load, the ability of th* snubber to withstand load without displacement shall be verified *
f. Snubber Service Lifa Monitorins A record of the service life of each snubber, the dat...__.....,...,.__
which the designated service life ccnmences and t ;nstallat'on maintenance records on which the designated sa *ca life is shall be maintained as required by Spacificat on 6.10.2~
m..
Concurrent with the first insarvica visual ins action and at least once par 18 months thereafter, th* insta ~n~~----
maintananca records for each snubber shall be reviewed to verify that th* indicated service life h&9 not bean azcaedad or will not be exceeded prior to th* next scheduled snubber service life review. rrl th* indicated service life will be azc..dad prior to the next scheduled snubber service life review. the snubber service life shall be rGavaluatad or the snubber shall be replaced or reconditioned so as to aztend its service life beyond the date of th* nest scheduled service life review. This reevaluation, replacement or raconditionin1 shall be indicated in th* records *
SALEM - UNIT 2 . 3/4 7-26 Amandmant No.68
!?LANT SYSTEMS
3/4.7.10 CHILLED ~ATER SYSTEM - AUXILIARY BUILDING SUBSYSTEM
~IM:TING CONDITIO~ FOR OPERATION
=========:!'!::==========================================
3.7.10 The ~hilled water system loop which services the safety-related loads in the Auxiliary Building shall be OPERABLE with:
a. Three OPERABLE chillers
b. Two OPERABLE chilled water pumps APPLICABILITY: ALL MODES and during movement of irradiated fuel assemblies.
ACTION: MODES 1, 2, 3, and 4
a. With one chiller inoperable:
1. Remove the appropriate loads from the chilled water system
2. Restore the chiller 14 days or;
3. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .
b. With two chillers inoperable:
1. Remove the appropriate non-essential heat loads from the chilled water system within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and;
2. Align the control room emergency air conditioning system (CREACs) for single filtration operation using the Salem Unit 1 train within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and;
3. Restore at least one chiller s within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or;
4.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .
c. With pump inoperable, restore the chilled water us within 7 days. or. be .. in .at . least HOT STANDBY rs and in COLD SHUTDOWN within the following 30 SALEM - UNIT 2 3/4 7-28 Amendment No. 182
PLANT SYSTSMS LIMITING CONDITIO~ FOR OPERATION
=====================================================
ACTION: .
MODES 5 and 6 or during movement of irradiated fuel assemblies.*
a. With orte chiller inoperable:
1. loads from the
2. Restore the chiller t us within 14 days or;
3. Suspend CORE ALTERATIONS and movement of irradiated fuel assemblies.
b. With two chillers inoperable:
1. Remove the appropriate non-essential heat loads from the chilled water system within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and;
2. Align the control room emergency air conditioning system (CREACs) for single filtration operation usi~g the Salem Unit 1 train within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and;
3. Restore at least one chiller s within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or;
4. Suspend CORE ALTERATIONS and movement of irradiated fuel assemblies.
c. With pump t and SURVEILLANCE REQUIREMENTS
========~=================================================
4.7.10 The chilled water loop which services the safety-related loads in the Auxiliary Building shall be demonstrated OPERABLE:
a. At least once per 31 days by verifying that each manual valve in the chilled water system flow path servicing safety related components chat is not locked, sealed, or otherwise secured in position, is in its correct position.
b. At least .. once __per.18.months,. by--veri.fying-that-*eachaufomatic valve actuates to its correct position on a Safeguards Initiation signal.
c. At least once per 92 days by verifying that each chillers starts and runs.
During Modes 5 and 6 and during movement of irradiated fuel assemblies, chilled wacer components are not considered to be inoperable solely on che basis c~at che backup emergency power source, diesel generator, is inoperable.
SALEM - UNIT 2 3/4 7-29 Amendment No. 182 J
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
3. The connection resistance is:
.. slSO micro ohms for inter-cell connections, s350 micro ohms for inter-rack connections, s350 micro ohms for inter-tier connections, s70 micro ohms for field cable terminal connsctions,and s2500 micro ohms for the total battel:Y' connection resistance which includes all inter-call connections (includinq bus bars), all inter-rack connections (includinq cable resistance) all inter-tier connections (includinq cable resistance) and all field terminal connections at the battel:Y'.
a. At least once par 18 months by varifyinq that the battery charqer will supply at least 170 amperes at 125 volts for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
f. At least once per 18 months, durinq shutdown, by verifying that the battel:Y' capacity is adequate to supply and maintain in OPERABLE status all of the actual or simulated emergency loads for the desiqn duty cycle when the battel:Y' is subjected to a battery service test.~
q. At least once par 60 months, durinq shutdown, by verifying
that the battel:Y' capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. Satisfactory completion of this performance discharqa test shall also satisfy the requirements of Specification 4.8.2.3.2.f if the performance discharge test is conducted durinq a shutdown where that test and the batt*l:Y service test would both be required.
h. At least once par 12 months, durinq shutdown, if the battery shows signa of daqradation OR has reached 85% of the service life with a capacity lass than 100% of manufacturers rating, by verifying that the batt*l:Y' capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge teat. Deqradation is indicated when the battery capacity drops more than 10% of rated capacity from its
,capacity on the previoua performance test, or is below 90%
of the manufactur~r's ratinq.
i. At least once per 24 months, during shutdown, .if the battery has reached 85% of the service life with capacity qraatar than or equal. to 100% of manufacturers ratinq, by verifyinq that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharq* test.
tion to thia surveillance Unit 2 prior SALEM - UNI'!' 2 3/4 S=lla Amendment No.198
ELECTRICAL POWER SYS'I'EMS SURVEILLANCE REQUIREMENTS (Continued)
2. Th* pilot cell specific gravity, corrected to 77°F, and full el*~trolyt* l*vel, is greater than or equal to l.200.
3. The pilot call voltage is greater than or equal to 2. 08 volts.
4. Tha overall battery voltage i* qr*at*r than or equal to 27 volts.
b. At lea*t once per 92 day* by verityinq that:
l. Th* voltaq* ot each connected cell i* gr*at*r than or equal to 2.13 volt* under float charq* and haa not decr*a*ed more than 0.27
!roa th* value ob**rved durinq the original acceptance
2. Th* specific gravity, corrected to 77°F and full elect decreased ta*t.
3. Th* electrolyte level of each conn*ctacl cell i* between tha minimum and maxilllwa level indication JD&Zk*.
c. At lea*t one* per 18 month* by verityinq that:
l.
2.
Th* cell*, cell plate* and batt*ry racka show no visual indication of physical damage or abnormal. dat*rioration.
Th* cell-to-c*ll and t*rmin.al conn*ction* al:e clean, tight, and coated with anti-corroaion material.~
3. Th* battery charger will supply at l***t 150 ampere* at 28 volt.s tor at lea*t 4 hour*.
d. At least one* per 18 aontha, durinq ahutdown, by verityinq that th*
battery capacity i* ac:t.qu&t* to supply and 111&.intain in OPERABLE status all of th* actual or aimulated emergency loada tor th* de*iqn duty cycl* when the ba.tteey is subjected to a batt*ry service te*t.~
e. At laaat one* per 60 montha, during shutdown, by verityinq that th*
battery capacity ia at l*a*t 80, ot th* manutactw:*r'* rat.inc; when subjected to a perfo%1D&nc* di*~g* teat. Satiatactory coapl*tion ot thia performance discharge t**t shall also sati*!y th* requirements of Specification 4.8.2.5.2.d if th* perto%1D&nce di*chArq* teat i* conducted durinq a shutdown where that teat and the batt*ry service t*at would both be reqW.red.
c*
operation continue compl*ted at
turning to SALEM - UNI'? 2 .3/4 8-1' Aaendlllent No. 198
REFUELING OPERATIONS CRANE TRAVEL - FUEL HANDLING AREA
LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2200 pounds shall be prohibited from travel over fuel assembJ 1es in the storage pool.
APPLICABILITY: Wf th fuel assemblies in the storage pool.
ACTION:
With the requirements of the at>ove spec1f1cat1on not satisfied, place the crane load in a safe condition. The provisions of Specification 3 .O .3 are not applicable.
SURVEILLANCE REQJIREMENTS 4 .9 .7 The overlo'1d cutoff which of 2200 pounds over fuel assemblies 7 days prior to crane use and at le I. crane operation.
SALEM - UN IT 2 3/4 9-7 ~tNo. 51
REfUELING OPERATIONS
ALL WATER LEVEL~
LIMITING CONDITION FOR OPERATION 3.9.8.l ~t least one residual heat removal loop shall be in operation.
APPLICABILITY: 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 i.n boron concentration of the Reactor Coolant System. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphP.re within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
b. The residual heat removal loop may be removed from operation for up to l hour per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the performance of CORE AL1'ERATIONS in the vicinity of the reactor pressure vessel hot legs.
c. The previsions of Specification 3.0.3 are not applicable .
SURVEILIANCE REQUIREMENTS .
4.9.8.l At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months one RHR loop shall be verified in operation and circulating coolant at a flow rate of:
maintain the RCS temperature at less than or equal to
I SALEM
UNIT 2 3/4 9*8 Amendment. No. 87
a. The LLD is defined in TABLE 4.11-2 (Continued)
TABLE NOTATION
b. The principal gairma emitters for which the LLD specification applies exclusf.vely are the following rad1onuclides: Kr-87, Kr*88, Ye*l33,
te-133~, :ta-135, 1.e-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list es r1>t ITl!an that only these nuclides are to be detected and reported. Other peaks that are ITl!asurable and identifiable, together with the above nuclides, shall also be identified and reported.
c. Sampling and analysis ~hall also be perfor1111d following shutdown, startup or a THERMAL POWER change that, within one hour, exceeds lS percent of RATED THERMAL POWER unless:
l. Analysis shows that the DOSE E~IVALENT I-131 concentration in th*
primary coolant has not increased nare than a factor of three.
2. The noble gas activity na"itor shows that et.fluent acth1ty has not increased by nare than a factor of three.
Tritium grab samples shall be taken at least one* per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.
e. Tritium grab samples shall ~ taken at least once per 7 days from the ventilation exhaust from th9 spent fuel pool area whenever spent fuel is in the spent fuel pool.
f~ The ratio of the sample flow rate to the safl1)1ed stream flow rate shall be known for the tim period cover*d by each s1 or ci>se rate cal cul at ion made in accordance with Spec1f1cati~n1 l.ll.2el, loll.2.2 and 3.11.2.3.
SALEM - UN IT 2 3/4 11-10 Anmdlmt: No * ..-3&
~
UMi'1'QI ameM" 1111111
auu
g l/f,f,I sqexpe pmn wmans.i*aacciacic._...,c:c;ar..iL&. naaa * *.., _ _ _ _ _
Th* limitation* on the *pecif ic aativity of the primary coolant *n*ure that th* re*ultin9 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months do*** at the *ito boundary will not exceed an appropriately ...11 traction of Pare 100 limite followirMJ a *t*. . generator tube rupture aceid*~ in c:onjunatiaa witb an aa*umecl *t*ady atat*
priaary*to-aeeondarf *t*. . 99fterator leaka99 rat* of 1.0 GPK. Th* value* for the limit* on apec:if ic aeti*ity repnHR iutuill liait* baHCI upon a par~ia eTaluation by the DC of typical *it* locatiou. Th*H value* are con*ervatiV9 in that *pec:ifia *it* par...ter9 of the 1~1. . *ite, *ucb ** *it*
boundary location and meteorol09ical condition*, were not con*idered in thi*
evaluation. Th* lQlC i* finaliai.J19 *it* *pacific criteria.which will be u*9d aa the ba*i* tor the r..,,aluation of th* *pec:ific aati*ity liait* of thi*
ite. Thi* reeTaluation may re.ult in higher limit*.
Reducin9 T to l*** t saa*r Dr*v nt* the r*l*a** of acti*ity *hould a av9 occ~~
t*aa generator tube ru ur*~*inc* th *aturation pr***ur* of the primary coolant i* below the r***ur* t th* atmo*pheric**t*. . relief valv***
Th* *urveillance requir...nt* prOTid* adequate a*aurance that exc***iv*
pacific aativity level* in the primary coolant will be detected in *ufficient time to take correetiTe aetion. Information obtained on iodine apikin9 will be u*ed to a***** th* par~*r* a**ociatecl witb *pikin9 phenomena. A reduction in frequency of iaotopic analy*.. fol1owi.J19 powez" change* may be perm!se~l* if ju*tif iecl by th* data obtained *
SALDI
Ull1T 2
l/4 4-* Amendment No. 112
REACTQR COOLANT SYSTEM BASES Finally, the new 10CFRSO rule which addre;ses the metal temperature of the closure head flange regions is considered. This 10CFRSO rule states that the metal temperature of the closure flange regions must exceed the material RTNDT by at least l20°P ~or normal operatior- when the pressure exceeds ~o percent of the preservice hydrostatic test pressure (621 psig for Salem) . Table B3/4.4-l indicates that the limiting RTNDT of 28°F occurs in the closure head flange of Salem Unit l, and the minimum allowable temperature of this region is l48°P at pressures greater than 621 psi9. These limits do not affect Figures 3.4-2 and 3.4-3.
Although the .pressurizer operates in temperature ranges above those for which there is.reason for concern of non-ductile failure, operating limits are provided to* assure compatibility of operation with the fatigue ana:ysis performed in accordance with the ASME*code requirements."
POPSs or an RCS vent opening of greater than 3.14 hat the RCS will be protected from pressure transients which: could exc1).!d the imits of Appendix G to 10 CFR Part so- when one or more of the RCS col ~a e less than or equal to 312 ° F. Either POPS has adequate re 1ev1ng capa ility to protect the RCS from overpressurization when ansient is limit to either (l) the start of an idle RCP with the secondary water tempe ature of the steam generator less than or equai to S0°F above the RCS cold g temperatures, or (2) the start of an Intermediate Head Safety Injection ump pump and its injection into a water solid RCS, or the start of a Hi ead Safety Injection pump in conjunction with a running Positive
placement pump and its injection into a water solid RCS.
SALEM - UNIT 2 B 3/4 4-12 Dece~r 22, 1994
3/4.10 SP!C!AL T!ST !XC!Pl'IONS BASES 3/4.10.1 SHUTDOWN-MARGIN
This special ta*t excaption provides that a minimum amount of control rod worth is ialadiataly available for reactivity control when tests are performed for control rod worth meaauremant. This special test exception is required to permit th* P*~iodic verification of the actual versus predicted core reactivity condition occurring as a result of fuel burnup or fuel cycling operations.
3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS This special test exception permits individual control rods to be positioned outside of their normal group heights and insertion limits during the performance of such PHYSICS T!STS as those required to 1) ma&aure control rod worth, and 2) determine the reactor.stability index and damping factor under xenon oscillation conditions.
3/4.10.3 PHYSICS TESTS This special test excaption permits PHYSICS T!STS to be performed at less than or equal to 5% of RATED THERMAL POWER with the Reactor Coolant System T slightly lower than normally allowed so that the fundamantal nuclear
cftlfacteristics of the reactor core and related in*trumentation can be verified. In ordar for various characteristics to be accurataly measured, it is, at times, necessary to operate outsida th* normal re*trictions of ~hese Technical Specifications. For instance, to maasura the modarator temperature coefficient at BOL, it is necessary to position t!}! various control rods at heights which may not be allowed by Specification * *
which may, in turn, cause the RCS T to fall slightly below the minili\ii temperature o Specification J~Y~l.4.
3 .I. 3.S 3/4.10.4 NO FLOW TESTS This special te*t exception permits reactor ~iticality under no flow conditions and is required to perform certain startup and PHYSICS TESTS while at low THERMAL POWll level**
SALIM
UNIT 2 B 3/4 10*1 Amendment No. 66
DES?CilH FEA~S r>zstc:N mssmq; MP TliMDlW'tJP 5.2.2 'l'h*
reactor containment ia deai;ned and *hall be aain1:&.:i.ned tor a maziaua internal prea.ure* ot 47 paigo. Cont-;n*ut aJz t-.perat=ea up to 351.J*r are acceptable provid:i.zs9 t:he cont*in**nt preaau:e i* in acco:dance with that de*c:dl:>ed iA the OFSAll.
!.3 gAC'1'0R cog m;, .YSIMILill
!.3.1 Th* nacto~ core 9hal.1 c:ontaill 193 fuel ...~... &ach uaably ahal.1 c:onai*t o~ a . .t:ia d s:izaaloy o~ ZIIW> cl.ad hel. rod.a with an initial cempoait:ion ot na=ual or aliqhtl.y enriched uranima dioxide u tuel material.
Liaited *W::latituti.ona ot zircom.aa alloy or *ta.i.Al*** *teal tiller rod.a tor fuel rcda, in accordance with NRC-apprOY9d applic:ationa ot fuel ~
contigu:ationa, aay be uaed. i'lael aaaem>li** *hall be liaited to tho** ~~=i de*iCJ"A* that have t>>een analyzed with appli~l* Mite *~t l!l.pp:~"9d code~ liinQ met.hods and ahovn ~ teata or analyaes to cc:ply witb. &l.l :l!uel safety da*i;n ba**** A liaited nwnbel: ot l=liei1 t.-.tet as*cmli** that have not completed r9i)re*~tab.ve t~=~ may be placed in nonliaitinq core r991ona *
CONT!OL ROD ASSJ:MBLIJS 5.3.2 'l'h* reactor core shall contain 53 full lenqth and no part lan;th cont:ol rod ass.mbli*** 'l'h* full length control rod ***embliea *hall contain a
.nominal 142 inch** ot absod>er liaterial. Th* noainal value* ot ab*or~r material shall be 80 percat dlver, 15 percent indima and S percent cadmiW1L.
All cont:ol *rods *hall be clad with *tai.nl*** __
~ tubU19._
col.ant; q*t'!lll.i* deai;ned and*hall be aai.At&i.ned:
a. In acco.rdulca *i th t:he coda reqW.:uent specified in Section 4. 1 o~ the !'SM, with allowance tor noaaal dec;radaticm ~*wmt to th*
appl.icabl* Sa.rveillance ~ra.nta,
b. For a pr**ll~ d 2415 pal.go, cad c:. . For a tesp9ratuze d 4550..,, except t= the pma11d.s9r wb.icla i* sao*r.
VOLQHI 5.*.2 'l'h* total water and ate- volmae ot the reactor coolant aystea i* .
12,441 ~ 426 ~ic E. .t at a noainal T.,. ot S73.o*r .
SAID
llHl:T 2 !-* Aaenclaent Ho.197

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