ML18085A103

Proposed Tech Specs 3/4.4 & 3/4.9 Re RCS & Refueling Operations,Respectively,Providing Redundancy in Decay Heat Removal Capability in All Modes of Operation

ML18085A103
Person / Time
Site:	Salem
Issue date:	10/15/1980
From:	Public Service Enterprise Group
To:
Shared Package
ML18085A102	List: ML18085A101 ML18085A103 ML19340B132
References
NUDOCS 8010210477
Download: ML18085A103 (17)

Text

. ' -1 PROPOSED CHANGE REACTOR COOLANT SYSTEM REFUELING OPERATIONS TECHNICAL SPECIFICATIONS SALEM UNIT NO. 1 Descripton of Change This change would establish required reactor coolant loop and/or residual heat removal loop configurations to provide adequate core cooling for each mode of operation.

Reason for Change To provide for redundancy in decay heat removal.capability in all modes of operation.

Safety Evaluation This change will require that four reactor coolant loops be operable* in modes 1 and 2, two reactor coolant loops be operable in mode 3, two.coolant loops be operable from reactor coolant loops and/or residual heat removal loops in mode 4, two residual heat removal loops operable in mode 5, and at least one residual heat removal loop operable in mode 6.

All of the above described Technical Specification changes repre-sent changes in administrative control which require that redun-dant sources of reactor decay heat capability be operable as described.

This is a more conservative approach to reactor protection which does not require any plant modifications, and will enhance safety.

3/4.4 REACTOR COOLANT SYSTEM I 3/ 4.4.1 REACTOR COOLANT LOOPS NORMAL OPERATION LIMITING CONDITION FOR O~ERATION 3.4.1. 1 All reactor coolant loops shall be in operation.

MODES 1 a."'o 'Z.

• APPLICABILITY: A1 11stec:i bcle::, bat excladi119 '18BE 5.*

ACTION:

Wi~ l~sa +i.,._, ... ti.., c:i.bovc 1"e'l.c.&ir<"d \'"Co..,to1r ~oolo."'l loops ,., ope1ro.~ta'1 1 be P:IH1ue P 71 Uflli!ls ::itl: cithe1 of the fcllc11i11g ACTHHIS .

. ,., "'t leo..sl

• t-COT STA.NOBY wi+l.t;"' 1 kou.r.

a. IJitl: e11e t eaete: nolant lee~ ana uuaiat@a pas;i;; m~t L

=i~e1 D:thn, STU!IllP ud,'cr c:c:ntil"l1:11d P0'/56! OPER;ATIOPi 1n3 ~: oeud pre:ided IllERMOL £!Gl'5R h rutric:ted t:i leu tnon J5% of R:Hrn ;11GRr1:aL P6\JER ind the hll O' :ir:t9 ESF i n!t1 umentlti on channels asseciated with the lee~ net in =~erD:tic:n, more ~l1:1d

• in tbeir tri~~ed cenditien within 1 h:iur:

I LW loe, channel tJB!d in the esi11cide11cc cir cai t

=ircuit *dth Stea= Flew f!i~e fo:* S::fe*r IP'lje:ti:=:

0. Stea::: Flu.1 Mi~li i1a11:1el ased Fu: Safet3 L:jectiu::,

,, EH ffc1 e11tial P: us1:111 Set' eu StuSJ Uecs 'lii:ie .e'9n1erJ Ui~d fe1* 51hty h*jeeztien (ti ip all biltat:lu hi oh indi nte 1 e. ai::Uve loop stea= proes iure * 'i ta respect ta thi! i =!l@ h;p ltHi= pr Uil:ll"lil)

I. IJith ue 1 ueto: :sohnt lo=i= and uu:h:tad lilt;1i*'f1 Jiet i" epa:=athn, itilbn~uel!t STAHUP and PQ' '56! QPl:!i?HION 1aa. e g;*:

of R.S.TED TllERW:L P@~iER 111ay proceed p: u, ided.

] TtU fc l h in:; 13 ti OnS nil 1 ! bUi U1:1:q::;let!il! ,; j th th!! I !!86t0 I iR at least 1-IBT ST:";ll§BY.

1) R:edete tile e.er te111pe1ateare _T b1 ;p setµoi1tt to ti::

.m:1u1 1~1:ified in Si;ieeifieabio:: 21.21.1 Fe: 3 loo,.

011r1 ti ;n

-+ I.-ise ..i prapo~~J Q.clci;i,*a\.1 tu ro.~e 3/4 4 - 1

• See Special Test Exception 3.10.4 .

SALEM - UNIT 1 3/4 4-1

PROPOSED ADDITION TO PAGE 3/4 4-1 SURVEILLANCE REQUIREMENT 4.4~1.1 The above required reactor coolant loops shall be verified to be in

_operation and circula~~ng reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

REACTOR COOLANT SYS°TEM

~CHON (Co11tinl;led)

'"T\.h'S po-"jt" \-c p lc...c.cd b) o.. 'tto..c..~ed I°°' '3 ie ti) Place the follmliug reactgr trip s5sbe111 and ESf' iRstr~mentation channels, associate~ with the loop AOt in eperatieA, in their tripp@= con=itiens:

1) z) Or,e1 tempe1 at1;11 e sT cha::nel.

3) au!@ circttit with Steam Flo,, High fQI Sihtj InjectiorL

4) Steam line P1essu1e lQw :hannel use~ ia tbe

'COir:leidenee eireuit with Stea:m Flew !ligh fe= *.1 5ihtj Injectioi=i.

5) Steam Fhw lligh :flannel usea fe1 Safet). Inje:ti:n

£} Oifferentia1 P1essere 8et1iee11 Stea::: ti11es Miglt el!lu1nel uud for Safet;) Injection (t1 i~ all bistabhs ;;hi ch indicate 1a;; acti; e 1oop steam

~ressure.*ith respect t~ the idle loop steam pl !!SUI !) ,

c} Cl1a1*1ge tile fl 8 inter lock s1tpoint f1 01;-i the .alble spe:ifi@= in Table 3,3 1 to 76% of MTE§ Tl!Eflf1Al

~-

2. THERMAL P@>JER iJ 1cs-::1 icted to 71% of RATED TMEiU1AL f30tJ!IL SALEM - UN IT 1 3/4 4-2

. *. *-:R.EACTOR COOLANT SYSTEMe HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.l.2 a. At least two of the reactor coolant loops listed below shall be

• OPERABLE:

l.

- -- 1t Reactor Coolant Loop fc.A'{ and its associated steam generator and reactor coolant pump,

'2.

2. Reactor Cool ant .Loop -'8t and *its associated steam generator and reactor coo~ant pump, .

. .. f3

3. Reactor Coolant Loop .Let and its associated steam generator and reactor coo1aT1t pump, *

• t4 .

4. Reactor Coolant Loop ..(.et and its associated steam generator and reactor coolant pump.

b. At least one of the above coolant loops shall be in operation.*

APPLICABILITY: MODE 3

• . *ACTION:

a. With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within.the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. . *

b. With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant

• ~- System and.immediately initiate corrective action to return the**

required coolant loop to operation.

~

SURVEILLANCE REQUIREMENTS 4.4.1. 2.1 At 1east the above required reactor cool ant pumps, if not in

<>perati on'* shall be detennined to be OPERABLE once per 7 days by verifying correct breaker a1ignments and i~dicated power availability.

4.4.J.2.2 At l~ast one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.2..3 Tl-ic ""~cpur-ecl sfc~Q.""" 'ei..el'"c..lo"'C5) sl.,c..11 6c defeY-.....,ii..ed ope"tPc.fol~ b.,\t'l"ityil'I~

~ec.0"'4.._~., s1&e wo.. f~~ le.v~/ tu be> ~1-~ ..fe"r -t~a..., ,,,.. ect,. . . A-1 to .i; 'Y. of no..rro..J ro."'"le. o.i leo..,t O!'!Ce per 1 '2 ...,.,.,.,,.s. * * * .

• All reactor coolant pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided (1) no operations are permitted that "oc1d cause dilution of the reactor coolant systc~ boron concentration, and (2) core outlet temperature is maintained at least 10°F below saturation temperature. .

~ :STS SALEM - UNlT 1 3/4 4-'2

-**-i;:

REACTOR COOLANT SYSTEM AS~HHI ~i:em ei11aed~

/

Tl\ is p-,~ t""Cpl&.uc\ b' ~ -tt o..c.~ eel rc-.ie 8elc;; r TC.

I

~:::t.i1!;:*1:::: !!:"1::!,~::::e:w:;: '!~:s 1

1:t0:::::; ;;:

I; 0

~:::t:me;,  ;;: '3 :::

eoel ut er t!Ui dt1al hut rim="tl 1

• : *  :::1.:::::e~; :: ::d::s:;; ;:::t t!:::~ee Pliil~~,

• 11 a.e.a e.

1pp1i~r=!*isiou

• !!!* n~1 e.

ef Sp1cific1thn1 and 3.Q.1 Ii! n;t

--- - -*-* -~

LLL; thi:r,

'Ji ~I 1 e11e 1 eae~a' at least 11nce J::I! I Jl days dI!

i=ee~a11t te mi n that:

!i;Qp SRd U SCIC::i zited pump "Ct in CJ:!li'Bs 1

I =:!!le: 1t;:ii:i:H esbh  ! 1!1!1:~ei~* :!:~*~ ~ !~!:~!I! r!~~ I1' ~H* ESE l!~~ue~~~c

!;i ! **~

'11st: sR1e11tat~cm ;1!111118~; s~e;i~~e= ~ 11 :!:le Ae:;::sm stDt111uU al:=

ha"e: been ~hcea ht iheir tri p;:e 3 zeeetitiees. eed

e. u: t~IF~ Iii i iute*~et=I~ !iill! t;;G*~ ;1:t RiS CH ! eset £:2* 3 3* ee;= e~H:n*a

tie::, ~h setpoi11t IS ;tj~; e~ lit!.:i:H TMl5~1 ~1 ,I:: PH;~;era:.

1

• P.11 :eado: eee1a~t fl~i!l!l~8 ud residual hea ... reme,,al p1::1mps ma:* ee ae eei::il!!g~ !eel  :!e~ llfil :Ee ~ ee111!!, pee!I!~ eleel ae ei:iel!a:!i~ iill!IS ;iiooe F1erl!la Uee! 11e ae!:

-eotH :I uuu ~ilutien ef tbe rueter eeel ut system bel<"ea C:Ol'lC:iflt"'at; 0"

; l!!Hl:t;i* ush11t Fll:il;!FI SAen FIOt ee ste: t_e! iii 1:11 e11e 91 111e1 e ei ~Si lii(ii*

==~ d 319 hi=1:111*ah!!!U 1eiS thal!!l 3H!°F ul!llus n tee f:ll!HSUl!!!UI! :.is1:5e1*

uel uiae h his tl=lil'I l!iQGl eui~e t:eet ~e~~~!11aJ eat te Jfillil re id ma :es~;* 92°*

ei h"e; ~ el! 2~ tee see:eeela!!!~* **a:l:e!!! :!:e!!li;:el!ahl!e e" ea :;l!:l stuia ~@e@satr;te ai l:@ss Utill"I 50°F abe"e eace of tee ers eeld leg tereftetat!ll"'S I

I iALEM - UNIT 1 3/4 4-3 Amendment Ne. 24

. . : ,J{EACTOR COOLANT SYSTEM.

SHUTDOWN

• .e LIMITING CONDITION FOR OPERATION 3.4.1.3 a. At least two of the coolant loop~ listed below shall be OPERABLE:

it . .

1. *Reactor Coolant Loop (.-(} and ;ts associated steam generator and reactor coolant pump,*

f2

2. Reactor Coolant Loop (.B') and its associated steam generator and reactor coolant pump,* *.

t3

3. Reactor Coolant" Loop {2') and its associated steam generator and reactor coolant pump,*

- ~ 14

4. Reactor Coolant Loop tB') and its associated steam generator and reactor coolant pump,*

11 .,.)2-

5. Residual Heat Removal Loop (~.

12 ~

.6. Residual Heat Removal Loop ts') *

b.

• At least one of the above coolant loops shall be in operation.**""'

. APPLICABILITY: . MODEl't+ and. 5 ACTION:. *

a. With less than the above required. loops OPERABLEs immediately initiate corrective ~ction to return the required loops to

• OPERABLE status as soon as possible; be in COLD SHUTDOHN

.*.* within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.:

b. With no coolant loop in operation, suspend all operations

• invo1~ihg a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.

• * (,3.2 % df fre*n ... r,*;er- ,

• . (eiAtl i""'-*"c.1<tlo .. ) :S t'2. .

• A reactor coolant pump shall not bejstar~;~~ith one or more of the RCS cold .

leg temperatures less than or equal to { °F unless 1) the pressurizer water volume is less than1w'o cubic feet.or 2) the secondary water te~perature of each steam generator--:r51ess than ;o Of above each of the RCS cold leg temperatures.

• • lh11 All1~11 e1 !l=Fl!l!CFIE3 pe::e: Sl!l~JH mas kl! ~ASpel asle ;n MQElE 5, Jo-- re\f '"'°'\

• • "'All reactor coolant pumps and di;eay heat removal pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided 1) no operations are pennitted that would cause dilution of the*reactor coolant system boron concentration, and 2) core outlet temperature is maintained at least lQOf below saturation te~perature.

t! ST5=

SAi.EM *UNIT 1 3/4 4-'3

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.Ll.8.1 Tiie reqeired residaal l1eat; remota1 1cop(s) shall be determh1ed OPE~.8L£ p1r Sp1eifie1ti=n 1.e.s. .

1 .

4.4.1.3.2' The required reactor coo1ant pump(s). if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability. ~

2 ~

4.4~~1.3..6 The required steam generator(s) sha11 be detennined OPERABLE by verifying secondary side level to be greater than or equal t~ ~ ~~t least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3

. of' l'\O:.Y"~QVJ '"°'"'~~

4.4.1.3.K At least *one coolant loop snall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

• 5AL E. M

• UN\i' 1

REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.l.4 Two residual heat removal loops* shall be OPERABLE* and at least one RHR loop shall be in operation.**

APPLICABILITY: MOOE 5.

ACTION:

a. With less than the above required loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.

b. With no RHR loop in operation, suspend all operations involving a

. reduction in boron concentration of the Reactor Coolant System and inimediately initiate corrective action to return the required RHR loop to operation.

SURVEILLANCE REQUIREMENTS 4.*4.1.4 At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

1. Four filled and intact reactor coolant loops may be substituted for one residual heat removal loop. A reactor coolant pump shall not be started

• .with one or more of the RCS cold leg temperatures less that or equal to 1 ?O 31'2. ...~F unless 1) the pressurizer water "9lume is less than ~ubic feet

'3.1.%afU4!Jl=f::ida :anga, i:;ld; pressurizer level indication, or 2) the.secondary

'° water temperature of each steam generator is less than S0°F above each of the RCS cold leg temperatures.

• The nonnal or emergency power source may be inoperable.

• '1r'The residual heat removal pumps may be de-energized for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided 1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) core outlet temperature is 11aintained at least l0°F below saturation temperature.

s 31' SALEM - UNIT ~ 3/4 4-.H'

REFUELING OPERATIONS COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8 At 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 ~eactor decay heat load or a reduction in boron concentration of the Reactor Coolant Sysiem. Close al~ containment p*netrations provtding direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b. The residual heat removal loop may be removed from operation \

)

for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

c. The provisions of Specification !.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8 A residual heat removal loop shall be determined to be in operation and circulating reactor ~oolant at a flow rate of > 3000 gpm at least once per X hours.

• 1'2.

SALEM-UNIT l 3/4 9-8

• • . Enclosure REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent Residual Heat Removal (RHR) loops shall be OPERABLE.*

APPLICABILITY: MODE 6 when the water level above the top of the T'tactor pressure vessel flange is less than 23 feet.

ACTION:

a ... With less than the required RHR loops OPERABLE, immediately initiate correct;ve action to return the requ;red RHR loops to OPERABLE status as soon as possible.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLAN~E REQUIREMENTS 4.9.8.2 The required Residual Heat Removal loops shall be determined 'OPERABLE per Specification 4.0.5.

• the nonnal or emergency power source may be inoperable for each RHR loop.

SALE'""* UN IT 8 a.

~-STS 3/4 9-J

REFUELING OPERATIONS BASES 3/4. 9.6 MANIPULATOR CRANE OPERABILITY The OPERABILITY requirements for the manipulator cranes ensure that: 1) manipulator cranes will be used for movement of control rods and fuel assemblies; Z) each crane has sufficient load capacity to lift a control rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the.activity release will be limited to that

-contained in.a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.

3/4.9.8 *coOLANT CIRCULATION The requirements that at least one residual heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140°F as required during the REFUELING MODE and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution focident and prevent boron stratification.

-+ r... Sert P"° fos<!.".( o.~c{:f.*o..,. to P-,~ IS 3/4 9-'2.

3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge penetrations will be automatically isolated upon detection of high radiation levels within the contairunent. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

SALEM - UN IT 1 B 3/4 9-2

PROPOSED ADDITION TO PAGE B 3/4. 9-2 The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange ensures that 1 single failure of the operating RHR loop will not result in a corn~1ete loss of residual heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop. adequate time h provi'ded to initiate emergency procedures to cool the core.

3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS The plant is designed to operate with a11 reactor coolant loops in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients. WHh GR! l!e!St~I! =~e~ Ult helil i:iet :ii:! liljil@t!!ithll!I,

~HeRn.~.1= J:!@Ue~ is rest1 ~ stee te 'Ii; ~6 pe1ee11t e~ Ri~=FEEl :fMei:(HAe ~Oliie~ Em ti~

=the O>i e 1 te111pe ra tu re &T tr ip is 1 eset. Ei titer aetion ensures that the DNSR

~1~~ ~ -be m&~l'lta~Re~ 1bei,*e ~. 3@. ~G!iS sf f:~ Sil ~A t1~e ~ ee Fl s ~,1; ~ ~ S!Hl!H! a fl l!Uetl:l1* ti!~ i= u~ )J=@l!iit~R\jl abQ*~e '~"' ~ n~ i=el!~el!lt ef QA*f~9 *115RMAI. ~e11ee ~

11M~e a foss el= :!Efo~~ ~11 ~me ~eel'! ,~n~ Ga:ese a 1uGti:i1 t1 ~P ~~ i:ii:ia1*ath9 abe 1e P 8 (39 percent of RATED TMERMAL POHER). }" MO'DES 1 o.."'J '2 wit-t., c~e 1-eo.dor Cool°"""'t loop ~o+ ;.., Opitro..t,*o~ ti.,1s ~f>ei:.(t'rc. ... lo"1 i-cci_ ... ivc-5 tt... ...t H'l.r p~ ...t-lac i .. c:.t lit.,.st HOT SiA.NOGY 1.o11tt.;.... 1 ~01.H"*

A s~Rg~e l!east0r =~e~aRt ~Qe~ pre1~~1s 1~~i4ci1~t ~eat t!em~va~

upa1:nu,. ihl! l!@mG!;'~ 1!!1!1j Ul!8 d@H;1 ~U49 II~~~ I!! h

"'~*

sn1~1ee ¥; ho,;e.1!1 1 ,

!~l!!lgh f'.i:tHt:1n =sM ~ dl!i!ati 9RS l!l!=!liiti l!I! !ilh~i 1!!19 I QIH~ hCIFI iRtJ GF1erath1~ iR t~e sbt:1teh1~~ e=eH~; IEC'l tile :if ee~~euet ea13 a:i rs u51,'er eerr1eti * *e acti e1u Gallll Cl t bl! me:ae t:itAiR the 111 O\l&bh =bit i:if ser,ica time.

-+ I11serf P"°fo-sec\ o-46.i t; 0"' to po..~e- ~ 5/4 4-1 The operation of one Reactor Coolant Pump or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with boron reduc-tions wi 11, therefore, be within the capability of operator recognition an d control.

The restrictions on starting a Reactor Coolant Pump below p... 7 with on e or more RCS cold 1egs 1ess than or equal to 312°F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the 1imits of *Appendix G to 10 CFR Part so. Th e RCS wi11 be protected against overpressure transients and wi11 not exceed the limits of Appendix G by either ( 1 ) restricting the water volume in the pressurizer and thereby providing a volume for the primary cool ant to expand into, or (2) by restricting starting from the RCPs to when the secondary water temperature of each steam generator is 1ess than 50°F abov e each of the RCS cold leg temperatures.

SALEM - UNIT 1 B 3/4 4-1 Amendment No. 24

PROPOSED ADDITION TO PAGE B 3/4 4-1 In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure consirlerations require that two loops be OPERABLE.

In MODES 4 and 5, a single reactor coolant loop or RHR loop provides sufficient. heat reiroval capability for removing decay heat; but single failure considerations require that at least two loops be OPERABLE. ThllS, if the reactor coolant loops are not OPERABLE, this specification requi~ two RHR loops to be OPERABLE.

REFUELING OPERATIONS BASES 3/4.9.6 MANIPULATOR CRANE OPERABILITY The OPERABILITY requirements for the manipulator cranes ensure that: 1) manipulator cranes will be used for movement of control rods and fuel assemblies, 2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction. on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.

3/4. 9.8 COOLANT CIRCULATION

• The requirements that at least one residual heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140°F as required during the REFUELING*MODE and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

-+ f~S~'t"'t fU"Cl~OS~d O..°'d\.\io'°" to po..9e ~ :5/4 9-Z 3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge penetrations will be automatically isolated upon detection of high radiation levels within the contairunent. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

SALEM - UN IT l B 3/4 9-2

. 1 J* .* i""*

PROPOSED ADDITION TO PAGE B 3/~ 9-2 The requirement to have two R~R loops OPERABLE when there is less than 23 feet of water above the core ensures that a sipgle failure of the operating RHR loop will not result in a complete loss of residual heat removal capability..

With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the c*ore.