ML21152A113

Palisade Nuclear Plant - Proposed Technical Specifications Bases Changes

ML21152A113
Person / Time
Site:	Palisades
Issue date:	06/01/2021
From:	Entergy Nuclear Operations
To:	Office of Nuclear Reactor Regulation
Shared Package
ML21152A108	List: ML21152A110 ML21152A111 ML21152A112 ML21152A113 PNP 2021-005, License Amendment Request to Revise Renewed Facility Operating License and Technical Specifications for Permanently Defueled Condition
References
PNP 2021-005
Download: ML21152A113 (32)

Text

Enclosure Attachment 3 to PNP 2021-005 Proposed Technical Specifications Bases Changes (for information only) 31 pages follow

PALISADES PLANT FACILITY OPERATING LICENSE DPR-20 APPENDIX A PERMANENTLY

-DEFUELED vTECHNICAL SPECIFICATIONS BASES Amendment No. 2-74 Revised 01,QQ.(2020 IXXIXX/20XX ~

LCO Applicability B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES rD LCO J

LCO 3.0.1 through LCO 3.0.Q establish the general requirements applicable to all Specifications and apply at all times unless otherwise stated.

LCO 3.0.1 LCO 3.0.1 establishes the Applicability statement within each individual Specification as the requirement for when the LCO is required to be met (i.e., when the is in the MODES or other specified conditions of the Applicability state nt of each Specification).

facility LCO 3.0.2 LCO 3.0.2 establishes that upon discovery of a failure to meet an LCO, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered , unless othen.*.iise specified.

The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of an LCO are not met. This Specification establishes that:

a. Completion of the Required Actions within the specified Completion Times constitutes compliance with a Specification; and

b. Completion of the Required Actions is not required when an LCO is met within the specified Completion Time, unless otherwise specified.

There are t\t.!Q basic types of Requil=ed ,A.Gtions. The first type of Required Action specifies a time limit in which the LCO must be met. This time limit is the Completion Time to restore an inoperable system or component to OPERA,BLE status or to restore variables to within specified limits.

If this type of Required .A.Gtion is not completed \.<ithin the specified Completion Time, a shutdown may be required to place the plant in a MODE or condition in 'Nhich the Specification is not applicable. ('/\Jhether stated as a Required Action or not, correction of the entered Condition is an action that may always be sonsidered upon entering ACTIONS.)

Palisades Nuclear Plant B 3.0-1 Amendment No. 270 Revised 12/09/2019

LCO Applicability B 3.0 BASES LCO 3.0.2 The seGsnd type sf Required .A.Gtisn speGifies the remedial measures that (continued) permit Gsntinued operation sf the plant that is not further restriGted by the Completion Time. In this Gase, GsmplianGe with the Required AGtisns provides an BGGeptable lei.tel sf safety for Gsntinued operation.

Completing the Required Actions is not required when an LCO is met or is no longer applicable, unless otherwise stated in the individual Specifications.

The nature sf some Required h:tisns sf some Conditions neGessitates that, snGe the Condition is entered, the Required h:tisns must be Gsmpleted ei.ten though the asssGiated Conditions ns longer exist. The individual bCO's ACTIONS speGify the Required Actions where this is the GaSe... An example sf this is in bCO 3.4.3, "PCS Pressure and Temperature (PIT) limits."

The Completion Times sf the Required AGtisns are also appliGable ,,men a system sr GGmpsnent is removed from seiviGe intentionally. The reasons for intentionally relying sn the ACTIONS inGlude, but are not limited ts, perfsrmanGe sf Su,veillanGes, pre*.ienti'Je maintenanGe, Gsrrecii'Je maintenanGe, sr in'Jestigatisn sf operational problems.

Entering ACTIONS for these reasons must be done in a manner that does not Gsmprsmise safety. Intentional entry into ACTIONS should not be made for operational GGni.tenienGe. Additionally, if intentional entry into ACTIONS w<>uld result in redundant equipment being inoperable, alternati*.ies should be used instead. Osing ss limits the time both subsystems/trains Qf a safety funGtisn are inoperable and limits the time Gsnditisns exist *HhiGh may result in bCO 3.0.3 being entered. Individual SpeGifiGatisns may spec:ify a time limit for performing an SR when equipment is remGved from seiviGe sr bypassed for testing. In this Gase, the Completion Times sf the Required h:tisns are appliGable ¥!hen this time limit expires, if the equipment remains remG'Jed from seiviGe sr bypassed.

VVhen a Ghange in MODE sr other speGified Gsnditisn is required ts Gsmply with Required .A.Gtisns, the plant may enter a MODE sr other speGified 6QRditisn in whiGh aRGther Spec:ifiGatisn beGsmes appliGable.

In this Gase, the Completion Times sf the asssGiated Required h:tisns i.oould apply from the point in time that the Re'# SpeGifiGatisn beGsmes appliGable and the .A.CTIONS Csnditisn(s) are entered.

Palisades Nuclear Plant B 3.0-2 Revised 12/09/2019

bCO Applisability BASES RIIIIAted wllaR bCO 3.0.3 bCO ~.0.3 establisl=les .

bCO is* ngt met and**

& tl=le ast1gns tl=lat must be .Impl

• _,, assooialad Raou* nd aR and ng gtl=I er Cgnditign ., .. ,redap Ast,..,i-...:.t"'*

..P -gn a Cgmpletign 11es; gr Tl:le oonditign gf tl=I assg~i~ed ACTIO~:lant ~s ngt spesifisall

• CoRdilioRS slalad * . This RllliaRS Illa! ~ add,assad bl' Illa 00""8poRds I<> 111~* Illa ACTIONS ..., b** oombiRalioR ol

~*ssIbla oolRbiRalioaohlal ooR<lltioR o1 CO 3.0.3 is ,,_"" gj ii: -;-i* Illa! .....iii, CoR<llti*** .,. 8 P aal SeR1111tiR1111&

-

• C<>RdilioR

• tad, IR suoh ..... 1h uoh lllal ORl<>RRg '

bCO 3. g v 3 ba ORl<>,ad i..;;./9

.,..spoRdi I<> suoh ' -* .;bi;;

.. ,ACTIONS spaoilic:ally Thie: Spac:ilic:al" 1alaly. IOR& aRd al&8 thal MODE gr gtb,erign delineates tl=le t*,me hm1 spes*f' . .t f WIIIIIR tho lilRl 1 -~Had ACTIONS. 1'" lor sale oparallo:

OORditio-wll**. ~

• plaoiRg th oporaliOR .,.,-* plORI iR a sale lllal P * - t ,. Rot IRtaRdad"' ba.. dalme<l bl' tho bC~ot ba maiRtaiROd

~-**RI& routine "gl t Ir - ' :U""'Y ,._"al used as 711

~ a

'" '8duRd&RI .;~ """'"" iR lieu o1 ; . ol ,aduR<l&Rt oy<loR>*** * ""'""..

oparalieRal and its 6

UpoR 0RtaRRg bCO 8-&IR& or O0IRP0R0RI& or. alta**-* thal *** or ba1Rg IROparabio. ..-0uld Rot ,aoult sl=lutdQ\4JR befgr . . ~.0.3, 1 l:lgur is I<> parfllil Illa .., ,mbali"!I a oh&R

• al-with Illa lead :P*-r I<> ooordiR!,; plailt oparalioR. ; :.""- orda,~

I<> P"'P8"' I alaotrioal ,; ,opalGhar I<> aosu,a a '8duolioo iR aio .,s ,ooiudao tiRIIII oparalio* ':,.":;.:': tiRIIII liR>it& sp..::~::militj, a*d ..,.;::: gaoaralioR

~

O

_,..,, that . a shUldo-*'R I<> -e aotar """"' l!O gf tl=le

• <t

• wall *<Ill. " pFOG88d IR DES ol 18

~h~~..::*.:;ri-un;a;;-;;;*1h':"p:~~iad ,...;.:.:::~~:'d .;;.~y

.........to upset tl=lat

'!;""Rt,. OPERABLE 888UJRIR9 thal ORiy tl=le Primary Cg I . Tl=l1s reduses tl=I 1::* -m1n1mum aRd GOUid shall paoilioalioR - ~- **s*

• ORI Syota armal stra&

oalaly * ' - - --IR &Rd tho potaR ' _..,***

oomplale tho : - *** The uoa S

SaclioR 1 C ,... 11 ol bCO 3 g anl:'"" uodar oooditi9o!'~ ',"'

• plaat

-8,PFOtaliOR o1 *po *r o Hl,1Gh this

. ' O"'l'iotiOR TiRIIII&.. .3 "" OOR&il!l&Rt willl 11101 e d1ssussign ua<I bRllll8 I<>gf 3

Palisade s ~uslear ri, Plant 4

._.mendment 270 Revised 121091201 Q

bCO Applisability S-3,.0 bCO 3.0.3 (sontinued) onger applisabl AC e.

.. n exists f .., .

or:id1*t1*,..

~

performed . or wh1Gh the Reqwred ,A.stions n

ACTIONS e . h""8 ROW booR

""' XIS o not ha1* .

, Spent Fuel Pool ,!,~n

• • c:it8r of the plant.

A Palisad es Nuslear Plant B 3.0 4 nmendment 2 Revised 1!09/2019270

bCO Applicability bCO 3.0.3 (continued) bCO 3.0.4 I- MOD::~.:.:

entered loll * . O not - wt, or00ope<:~iod

• d' -

Applioabllily°::sp::r into Ille *-. 1 ..t-::ooi:; : ::.*

~~~*d oondition lor :::~"*d operation wilh:~:: ~ oondilion in Ille

. NS lhal permit * . period ol time* COii or olhor period ol time in a Mm:'nl1n"od operation ol Ille . Complianoe with

plalolo le\<el ol-....: ~r olllor *P**~iod oond:.SRI lor an ""Ii-

• slabls ol Ille pla I or """~"""d operaf n p-d** ""

""*h ... n lleloreo " IOA. Thi& i **-

1\p r ~~*** onlry inte a Mooii ~, ~* tho MOOE o11" .. illlolll regllFO

'. Ip "'8b1hly may be .....;* or other spooiliod SRgo. Thorelore iR IA O Ille Applioabilily .

• and Ille Req"ired v. oond1l1on "GI'ions in aft lho '

~ follQ!Ned

-&r entry or oxan,plo, bCO 3 enter~d states that a:*_4.a may be used when t .

lr1p oondilion within1~:pe;t'I* lnslRdmenl oh':,: ~qy1red Aolion 18 be

--ru....

er &peoilio<j in oondili *. o""lelion Time Tr no. n,ysl be plaoed iR willl bCO 3 ~~ IA ~- AppliGabilily ..:::*:::-*

1 11 inle a MOOE or pped oondilion ,.; - ~r. -

rr-:ilily is on;;,,.,;

pe oondilion SRd Ill

• ,~

  ::*:"*nlly Ille oi>SRnol * -

111 :~Co""lotion Time,

• inolr"menl ohannol

-

• in plaoed in tho eg1no wllon Ille Palisade suclear N Plant B 3.0 5 A

._,mendment 270 Re>t1sed 12/09!2019

bCO Applicability B---3,.0 a.A.SES ified condition in the

, into a MODE or other spec f a risk assessment 66 Applioabilily 8'id"' i*g

.1with

• • pe~-*

=;:Bla..,

I.CO 3.0.4.b allOW& *nllly 1

• ot - altar P*rlo..,..GO ~d*ralio* o1 th*

SAd OO"'PO***r* .-:*::.

ol th* ....plal>ilily ol **.:~*h-*t o1 ri*k f8Slllts, deter~,~ I~ the Applicability, and est is MOOE or oth*r specified cond1t1~n in if appropriate.

nt actions, manageme . *u or blended Th* ri*k ..........t - , u** ~....1 will h* oo*du8lad Yantitative, qYalltath e, ~~*s

• the plant d the risk asses . . t implement approaoll**~urea, SAd srilaf1a ,. pl~..~..,; ol IAOi*ta*aAGO

~~~fi~aj{4), whic:ll as*:~*:~ "'  !' ~ "' . =:::t T:a a&&06*=~~ ':.i..isal ri*k

'*;;:..,.1 ao!Mli**

pYrposes jg of h*bCO . . . ' must take of rdless iA11l aooou*~

\*.thether t ealleq i* i*oludad Specification eq Yipment regaG (a)( ) risk assessme nt scope.

. th *ormal 10 C~R 50.65 4 d 1* ~ * . th* prgG<!Qure* SR

. be con dycted ~ YSIRg2 A.ssessIng . an d

. ts will Th* n*k .......,.; by Rogula11lry Guld* 1:18 Nuolaar - r Plaots. It 11 guidSA** **d*rs* org Mai*ta*anse AGIPAIIO* . S*olio* 11 of 11 Managi*g R;k:: 1ai **do"'88 tho gu1dan"i" Regula11lry UI "l~dY&lry GYideliAO '?'

~=S th* -**&Sol Mo*10 dOG*-*ts add....

N NU MARC g3 01 olaar - r l!ISAts. Th*** *I quanUlali"8 SAd Mai*la*SAGO al ~r oo*duot ol th* ri*_k ..

s***ral gu1d'":i:*** f<>r -li*hi*g A&k

• • • • ""'..;*I -***

""::'s1":.

and aotio** jg plan and qualltall"8 _S"' ..,Al aotio**- Th*oe 1

- l e AOk ""':-,:** i* ......, that ...1...1s 1161io** jg reduGO th*

8 *~1*

,. rail riok, i * -

ri*k -*o:*

OORdYol other ao ';' hill aod maA"9*""'*1 _p*r*o** ' *~*d* ol ri*k duralio*

01 1 00 l>j>*=ilio*

• .i aoti*** jg mi*1mla8 o1 baskup **00*** P 1:,::, G01Apa**a1<>ry OE Gllaos* ts i*..-- {**i:-:=RAi*ati<l*

..........8), an . atio* *hould that th* P"'":'.-:i: ~ . p<<>bal,ilily o1 al** be S'-" ol th* bCO ""'"Id be

.....p1a1,1e. Ca**id*r *h thal th* l'fl<lYlrema*ts r

• lhal would completing restorat1~n _sY f ACTIONS Completion ,me

. th expIratIon o *

• met prior t~_ e A licability.

require *"'*'*s th

• -PP and

, be Ysed '..tith .

single, Yltiple systems or m"ides *u t gYidance relatI.eo bC~p=:~:~ ::V..1at11e. NUMARC'Oi:i: p:;..ltipl* ._.., and co CORSI"deration of simYltaneoYs YRS\.

"°""'"***ts. 8 8 hall be consIdere 1 d -. d8larmi*i*s th*

• h

• k ssessrnent Th* re*ulla ol th* ri*~ th* MOOE or oth*r *P**11*~ I ~***- Th* bCO r d condition in t e

'plal>ilily ol **tari*s **po*di*g ri*k 1A8A"9*""'* :

.A.pplicability, and any ':rrdo not h~ to be docYmente .

3.0.4 .b risk assessrnen Palisades NYclear Plant Revised 12!09/201 Q

bCO Applicability B--3.()

BASES bCO 3.0.4 The Technisal Specifications allo*., .

u~~lable in MODE 1 for the d v.;ontinued operation \+.<ith equipment (contim1ed) this Is allowable a*nd *ns . ur ion of the Completion Time c.-:~--

, .., ----e 8I in general th

• k * * -

MODE bounds the risk of transitioning:~ ris impast in that partisular MODES or other specified concf . . in o and through the applisable use of the bCO 3 O 4 b all(}1t1ons in the .A.pplicability of the bCO the ase th risk

• is assessed

• *

• andwance man should edn ger a11Y asceptable, as bee

• long a small subset of systems and cas as stated aboi.te. Ho111ever, there is be ~~ important to risk and us:m:,~:en~~ that have been determined to 8

prohIbIted. The bCOs go¥ernin th , O 3.0.4 .b alloiNance is Not~s prohibiting the use of bC~ 3 ~s: s~s~m ~nd components contain applicable. * * .b b~ stating that bCO 3.0.4.b is not Applicability i..1ith the bCO not met b or other spes1f1ed sondition in the bCO_ 3.0_.4 .c allows entry into a MODE ..

which states bCO 3.0.4 .c is . ased on a Note in the Specification entry into MODES or other sap!:~able. T~~se ~pecific allo\*.,ances permit the as~osiated ACTIONS to :e :~~~=nd1t1ons in ~~e .A.pplicability when operation for an unlimited period of ti do not ~ro.ide for continued been performed. This allo1*,anse me and a risk assessment has not spesific Required .A.ction ota S e:~ ~pply to all _the ACTIONS or to a performed to justify the use of ~CO isat1on. The risk assessments and components. For this reason b3.0.4.b usua_lly only sonsider systems Specifications whish describe v-al~esc~d3.0.~ .c is typically applied to soola_ n~ system spesifis asti1,iity) and , p~ame~rs (e.g., primary SpesIf1cations based on NRC Pjant spesIfIc ~ . beappro¥al.

applied to other The provisions of this Specificat* .

endorsing the failure to exercis~~:eshould not ~e interpreted as components to OPERA.BbE status b g:od prast1_ce of restoring systems or or other specified sondition in the 4pel~:~ntering an associated MODE

• PIC-IIty.

The provisions of bCO 3 _0.4 sh .,

other specified conditions in al~ no~ pr~~nt shanges in MODES or

'.tJith ACTIONS. In addition : : nppl_1s_ab1lity that are required to somply changes in MODES or oth~r s :~~~1s1ons ~~ LC~ 3.0.4 shall not prevent result from any plant shutdoiH: I th~ cond1t1ons in the Applicability that

..a f " ..a .. * -n --IS context a I t

~inet:i as a change in M O D E ~ ~* pan shutdoiNn is Applicability associated ~-<ith tr:r ~~h~r spec1f1ed condition in the MODE 2 to MODE 3, MODE ;:1s~~;11ng from MODE 1 to MODE 2,

o. DE 4, and MODE 4 to MODE 5.

Upon entry into a MODE or other ..

• .t.iith the bCO not met bCO 3 O 1 spes1f1ed cond_ition in the Applicability applisable Conditions' and R~ . . andA 3._0.2 require entry into the resolved, until the bCO is quired ._.ct1ons until the Condition is Applicability of the Teshnic~~ or ~f~t1I ~he plant is not within the pecI IcatIon.

Palisades Nuslear Plant B 3.0 7 Revised 12/09/201 g

LCO Applicability 8-3-:0 LCO 3.0.4 Sw:veillances do not t:i ,

eqblipment SR 3 g o( r ** ,,.arial>las

• S\-EI to""tsida be performed Iha 8 on - _tt:i-e_ asooooalad

. ioopaFal>le i:*~1:d (continbled)

SR 3*0*!*1 Tl>arelore, "lili>iog LCO 3 g l1milo), as parmitlals ""'** ii l>as b g aq"ipmaol lo sen*ioa re inoperabl t fr een remo1 d f .

Spaoif a1* -:~ 8 -0.oomply will> ACTIONS~'""'"' selVioa or will! IhaIC appl" ai,(

I0n 18 to -~re pro11Id a, °"""plioo lo bCO . Tt:ie  ;-pooa 3 g sole pblr ol ll>is raq"ired lasli~g ~ :'""'"'d rnonstrate:

AslioA{s)) lo allo¥< th.;~:-*lo Aol G<>mply

• rmance of a- Tt:ie OPERA.BILITY of tt:ie eqblipment being retblrned t O .

b..- Tt:i o sel"\<1ce* or ePERA,BILITY of ott:ier eqblipment.  ;

Tt:ie administrati\!e controls 1 li..;-;,..;

sen<iGe in c fr

.;:y 1: -;;ii -;;~"'fi~:*

ensblre tt:ie time tt:i

~1> th~ raq"iremaols 11 i~ reluroad lo OPliRAlllblTY. 1 r11:**"'t lo""""""

0 Iha reqwired lasliA 18 ,... 1oo lo Illa other Jl""'9AIP'9 or SpaoillGalloo does ool proide Ii g :" 9 de...oslralo "sad iA lie" o1' *lh ..-,,,., "'81AlaAaAOO. bco 3 g :;"'I> paFlorm aAV Acli<>os aod lhal or praolioabla altaroawos ll>al . . * ""kl Roi be

~;::::~~* Iha A

.n

i::~i~*"::":.~i: MO:~~.:: ~;.~~:

0~*

. LCO 3.0.5 is not intended to brnonstrate eqblipment is e bleed repeatedly

• _a....pla ol da.... AslraliA . _ -

..ctIons not met is . 9 eqwpment 1s OPERABLE .

Raq"ired Aolio S!l'llaro iPCsi :!~sol-:"

• llowpalh will! ....,;..,.:  :~*d ~

opao,og * '""""al ,,_ lhal ,:; I Wllll ll>o Raq"ired oomply with PCS Pl\/ leak ~ . e31a9e ~n order to perform lasliog lo dernonstrate ""'tt:iat 88lalioA Vlll>,e {Pl'I) I 4( . - Coolaol age 18 nO'N '.*.1Itt:iin limit.

Palisades Nblclear Plant B 3.0 6 Amendment 270 Re¥ised 12/09/2019

bCO Applicability S--3-.0 BASES bCO 3.0.5 ~xam_ples of demonstrating equi ment in ll:1h1ch it is necessary to take : . OPERABILITY include instances (continued) a tnp~ed condition that was dirS:~:o:~rable c~annel or trip system out of Required Action Note for this purpo yAa Required Action, if there is no OPERABILITY of equipment remo>' se. nR exam~le ~f verifying

~h~nel out of the tripped conditio~-etd from _sen<1ce is taking a tripped ind1Gate the appropriate response d ~ permit the logic to function and on the inoperable channel. Example~nn: :erforman~e of required testing of other equipment are takin . o emonstrating the OPER4BlblTY the tripped condition ; g an inoperable channel or trip systa~- out of to prevent the trip function from .

of required testing on another hoccurn~g during the performance G annel in the other trip system or lg pe,mlt tile klgio lg luootieo ""~ IRdio '

~unog tile pe.-oe of ,equil'Eld le '(" tile app,op- F&speose 8

e same trip system. ing on another channel in The administr~i>~ controls in LCO 3.0 , .

co~ponents in Chapter 3 of the T h :5 apply '~- all cases to systems or tes~ing could not be conducted ...h~G rncal S~ec1f1cations, as long as the v.CTIONS, as *1.1ell as eq .

~~:::!1 Actions. This includes the rear w I e complying vlith the Required

~ternate equipment or trains

~r rep_ositioning of redundant or Y manipulated to comply '"<ith ino perable to comply \*Jithu1prnent ACTIONS.ren:IOed

-rom f w service or declared LCO 3.0.6 LCO 3.0.6 establishes an exception to LC that have a support system LCO s e . . '? 3.0.2 for supported systems (TS). This exception is pro"ided bp c1f1ed in the Technical Specifications the Co nd'f 11ons and Required ecause LCO 3 0 2 4~- " would require that v

supported system LCO be 't £ ions of the associated inoperable supp_ort system. This ~e=t~o:~:j::!:~y dd~e to the inoperability of the

~quired to ensure the plant is mainta* ': . ecause the actions that are in t~~ support sy~em LCO's Require~e4 r'" a safe condition are specified

~ include entering the supported sy 't £ '?ns. Th_~se Required Actions v.Gt1ons or may specify other Required s:~ s Cond1t1ons and Required nG ions.

Palisades Nuclear Plant B 3.0 Q Amendment 270 Re'lised 12!091-201 g

bCO ,A,pplicability S3/4.O BASES bCO 3.0.6 (contim1ed) ~

.~en a support

\Afh , . .

~n the TS, the su Bt:tem 18 ~noperable and there is Bl deloFFlliAed kl :: i::i *~m{s) ""' <&quired

,ooperabilily. Mou* " po<ablo as a "'""It kl: bCO spodiod l&r ii

~

of tho

• doola<ed ,ooperabl*

lll'W..' Cood;.;~"""'* 18 Aol A&O&S&ary "' **

supper! sy&leRl'a Rs SAd R&quired A<li***  :""!"'rt systam u*I*.:* '""' th& supporteO i.-si&IBAoy of .. &quired AotiOA&. Th& pol&Fllial d1'"f"d "' do .. Ill' th&

&liAiAaled b , ~

illd &llpported s ** qu,~-AII; relaled "' th& &Al .... """'" aAd kl.. L.CO 8 Coo<liliOA& 111 FJI mt<> ...1t,pl& 81lppOR plSAI is ..,;JJ";;"* 1*9 all th& aotioAS thal

• d R&qu1red 88 AotiOA& a,o AoliOAS. . . IA a sale OORdilioA iA th:::""" pport system's

"'l' "'***""' Required tho Ho~1e~er, there are instance 8 .., 8 mat either direct a .. here a support , t ,

&Airy iAI<> Coodilio*:":::* sy&l<>RI "' b& d..ia::7.: Required -

• Thi& - o"""' im *. &quired AGtiOA& l&rth& porabl& or direst

""""' olhor R&qui.:' ~"\"ll' or - * &OFAO spoo~i.;~"';o~ systam.

supperted sy,:.;,

CoAdRioos llld R

~=:

• &OFAO d&I * ,., .,: IOA. R&gar<ll&&s of u-t,

• ~P,""rl.sylil<>Rl's ~:,:~ ~ 1 90 ae<I ,ooporabl& or d'

.* _a,_ kl peFl&FFII0

-1mFAOdial& ,

' .o 0* d1reota a Co*<IRioA& 111d R&quired - *

• l&r * """ orl , _ &Airy iAI<>

bCO 3.0.2. &quired Aotioos shall b& : * ..::d systam, IA accordance tho applioal>I&

with Specificationloss 5_f 5 _13 ' "Safety, Functions Det ensures

- - Upo* : - . , ~ luoolioA i& d&leoled ~":':a11:

Pregra,,_ {SmP),,.

delomi** ~ '!i .;:/'t 3.0.6, 111 .....iuatio::h.lir~ata aollons ""'

roRl&dial th 1086 aotions ' OF-n al unot,on .,.;o1a. "dd'f1 IOAaliy olh

~

• mad& I' .kl

• &upper! &y&Iem .mop -~S4'FJI aotiOA& - b _, or1m,lalioos abT ' e 1denff d '

supported 8Jl'Wm coM*~~11ty 111<1 ......pending .~ "*'~ as a rasult of implom&nts tho r&quir 'IQns 111d R&quira<I Aotions ;:pl100 kl onl<>ring ements of bCO 3 _0 _6 _

• e SFDP Cross systems train th checks ato t .identify

. a loss of safet, .

. . ' ereby OASUriAg

-l f-tt:us et/Bluation deter .

appropriate Cond"f of safely lunotio;':':. 111<1 mines that a loss of saf ,

are R&quira<I required to A<lions ~

be entered. 1:*~ - * .

in t.t.ih1chtho the loss Palisades Nuclear Plant B 3.0 10 Revised 12.10912019

bCO Applicability S--3-,0 BASES LCO 3.0.7 ~pecial tests and operations ar

.!:!:." :::Spe::*::£ preclude these tests and operat* *

=n:iu::*~;:-..,':.:~:,:r*

,o~s. Beca1Jse TS normally allG'N specified requirements to i:ns,hSpecial Test Exceptions (STEs) controlled conditions STE _e c anged or suspended under spee~"f,cations.

. 8 are included i

• otherv4s Unless . _n app r,cable sections of the remain ~nchanged and in eff~ctS:~ec1:_1ed, all oth~r T_S requirements

~propnate requirements of th MO pp ,cable. This *.t.<111 ensure that all directly associated \t.iith or req!~d to~ or other specified condition-AOt perform the special test or operat*ion~.,* *.-111e remain cha~ge~

in or suspended to effect.

The .4.~plicability of an STE LCO

• 4. 8 pee,"al test may be performed .

app~opriate STE LCO or the othe~nder_ either the pro*.<isions of the desired to perform the spe *a1 t applicable TS requirements. U-it-is the requirements of the ST~ b;~ under the proi.<isions of the STE LCO SRs specified in the STE LCO. shall be followed. This includes the ,

Some of the STE bCO require that oper~ion be met (i.e., meetin th one or more of the bCO for normal spec1f1ed normal LCO) The ~p I~ !~~ LCO requires meeting the specified normal bCO .h .., .~* p ica ihty, ACTIONS, and SRs of th 8 t th ' o-..lil .-er are not re

• d meee ST~- LCO when it is in' effect*qu1re to be met in order to meet a spec1f1ed normal LCO the . ~his means that, upon failure to apply, in lieu of the .4.CTIONS ' f thassociated ACTIONS of the STE bCO abo>.~-do exist. There are ins:anc e n~~rnal LCO. Exceptions to the spec1f1ed normal LCO must b ts s..hen the Applicability of the

• re 0&rtaio of ii& S"Miillao:S':",;,":::: il&,fO.CTIONS °'"&I be lak&o, ese requirements must be m t pe ormed, or where all of STE LCO. e concurrently >.*.iith the requirements of the Unless the SRs of the specified n by the special test, those SRs th;rrnal bCO are suspended or changed normal LCO must be met prior to are ne~essary to meet the specified conduct of the special test perfo~m1ng the special test. Durin

""I""' speoili&.Ci~": Su~onao..,. o&&;;,::::~- **u::: ;!.~.;:-*s ~=:a":111.:"

bCO 3.0.S bCO 3.0.S establ' remainlSl:ies

,.. (""R~Ruad) .. Gond't' -HOR& URdor Whish '

Ula~ ""*sidored to

""RSidOROd ;:**(s). This bCO s - " : ' - of pl9¥idiRg luR<liOR sapablo of po::, IROparaiblo **loly du~= Ulo suppolled sy&IB';:";"""'"

app,opriakl b taotiRg, or ..;~-:-: .:.Ii-mmg "'"" "'896ial IORglilad of-:::~ *** or """" 8"Ub

!~R<liOR(&). -~~~ S Roi i:ol

;:::~:}~:-~~:='~-=~=:.~=-=::.~.~=~=::~ir a,,,.,.,,akld meet tl:ie I

& or ""'"' &RUbb

't Spos1l1oali<>R& (TS) Th Ats, wllish .... -

....... IA 10 C~R ,. +H8&RUblae

""'9Q lor R1 *

- - - oulaido of J ...... u...

or administrative GOntr0 I. 50.36(GH2Hii), and , ras requirements SUGl:i aire do no; I' ' - approp .at

' Ille alkawad ti _ " "

associated su me expires SAGI tl:ie snub mu&l lae dosl ~po,t luR<liOR(S), tho"' laer{&) ""' URablo 1" oRl&rad iR ..:~ Roi R19I a,d U,o Co~d"!"d

"'"" wiU, bCO 3 o 1 o ***s &uppolled a,d RequiROd * - O(s) sy&I&:."~ Uloir IC>* * * * -*- ..&lloRS mo=--*:e21)~t~1me~~tl:i~at~tl:i16-f~~-sioiru>

~nfirm tl:iatsnubbo,s at Ieast tra* (.of bCO e pro¥1sions one 7'd--.a.,~

? .01-1.S&.ar

""& ap :~t1Elr1eelmg....j

• .;:,,:* ..,..;'~,: subsy&IBR1) o'="fe11;;~, c:i siit-t.is:isur*oequired to load&. LC&uppo,t luRGlioRS ,., : oapablo of parlormiR supported _by Ulo

.....- 0 3.0.11 doos Roi. P. stulaled dosigR loads g lhOIF ROqU1'8d

""R#ig~= *A10lomeAlalio:P~ !:s""" soismio **ublae:'~' "'"" _soismlc

~~

IR&peGI" &hall bo Mlablo re&IRoilOR, a,d u, ( .*._. **,* .,,. ,,.

P,og::.~- SEP SNB PLP 001 8

':"""'rablo basis*,:-::- ploAt spooilio LCO 30

~.:::..!* . u&ad as a ~,::.:;* orBll8R1iRaliOR apphsation ofaRd bCO ~mg -

3.0.11 lo silo

. : *8 .a applies ..,l:i

-d*RS Ulolr ..... t~* ****, ""'"' SRUblaer&

Palisade SUGlear N Plant Rei.*ised 12!09!2019

bGO Applicability S---3.,{)

BASES bGO 3.0.B bGO 3.0.B.b applies \*.1hen one or more snubbers are not capable of (continued) providing their associated support function(s) to more thar-i one train or subsystem of a multiple train or subsystem support&d system. !.CO 3.0.B.b allo11.1S 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore the snubber(s) before declaring the support&d system inoperable. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Gompl&tion TiFR8 is reasonable based on the low probability of a seismic e1.ient concurrent with an ei.ient that would require operation of the support&d system occurring i.tlhile the snubber(s) are not capable of performing their associated support funstion .

When applying bGO 3.0.B.b at least one Afl!V train (including a minimum set of supporting equipFR8nt required for its successful operation) not associat&d with the inoperable snubber(s) , or soFR8 alternative means of core cooling (e.g. , F&B, fire water system or "aggressive secondary cooldown" using the steam generators) must be a\;'alable.

Implementation of this restriction and the associat&d plant configuration shall be a\;tailable on a reco>.qjrable basis for NRG staff inspection.

bGO 3.0.B requires that risk be assessed and managed. Industry ar-id NRG guidance on the impleFR8ntation of 10 GFR 50.65(a)(4) (the Maintenance Rule) does not address seismic risk. However, use of bGO 3.0.B should be considered with respect to other plant maintenance astivities, and integrat&d into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train or subsystem is properly controlled, and eFR8rgent issues are properly addressed. The risk assessFR8nt need not be quantified, but may be a qualitati¥e a*seness of the 1.iulnerability of systems and components 11.then one or more snubbers are not able to perform their associated support funstion.

bGO 3.0.9 bGO 3.0.9 establishes conditions under which systems described in the Technical Specifications are considered to remain OPERABLE when required barriers are not capable of providing their relat&d support function(s) .

Barriers are doors, walls, floor plugs, curbs, hatches, installed structures or components, or other de1.iices, not explicitly described in Technical Specifications, that support the performance of the safety function of systems described in the Technical Specifications. This bGO states that the support&d system is not considered to be inoperable solely due to required barriers not capable of performing their relat&d support function(s) under the described conditions. bGO 3.0.9 allows 30 days before declaring the supported system(s) inoperable and the bGO(s) associat&d with the support&d system(s) not FR8t. A rna>e:imum tiFR8 is placed on each use of this allowance to ensure that as required barriers are found or are otherwise made una¥ailable, they are restored. Howe\qjr, the allowable duration may be less than the specified maximum time based on the risk assessment.

Palisades Nuclear Plant B 3.0 13 Revised 12!09/-2019

LCO Applicability 9--3,.0 BASES LCO 3.0.Q If the allmwd time expires and the barriers are 1a1~able to per:form their (contim1ed) related support function(s), the supported sys~m s LC~(s) must ~e-declared not met and the Conditions and ~qwred AGt1ons enters in accordance with LCO 3.0.2.

Th is proi.<ision does not apply to barri~rs which -~up~ort \l&nt~~ .

systems or to fire barriers. The Technical Specif 1cat1on~ for -~~t1lat10~

systems pro>.<ide specific Conditions for inoperable barriers: Fire barriers are addressed by other regulatory req1a1irements and associated plant .

rograr:ns This pro>.<ision does not apply to barriers ¥.1hich are not req1a11~ed io support system OPER.A.BILITY (see NRC Reg_ulatory Issue Summary 2001 OQ, "Control of H~ard Barriers," dated Apnl 2, 2001).

The prooisions of LCO 3.0.Q are justifie~ because of the 101N ri~k .

associated with req1a1ired barriers not being capable of pe~orm1~g th:1~

related s1a1pport f~nction . This pro1.<ision is based on cons1derat1on o t e following initiating e1*1ent categories:

• Loss of coolant accidents;

• High energy line breaks;

• Feed\t.iater line breaks;

• Internal flooding;

• External flooding;

• T1a1rbine missile ejection; and

• Tornado or high 11.1ind.

The risk impact of the barriers which cannot pe~orm their related support function(s) must be addressed pursuant to the nsk assessment and management pro1.1ision of the Maintenance R1a1le, 10 CFR 50.~5 (a)(4),

and the associated implementation g1a1idance, Reg1a1 lator=y .~u1de 1.192, r "A.ssessing and Managing Risk Before Maintenance AGt1~1t1es at. Nucle~

UI Plants II Reg1a1latory G1a1ide 1.192 endorses the g1a11dance in Section

-O ..~r . "" "t . th 11 of NUM.4,RC 93 01 , "lnd1a1stry G1a1ideline for MORI-On~.g~ .

Effecti>.<eness of Maintenance at Nuclear Po11.ier Pla~ts. ~h1s _g1a11dance prouides for the consideration of dynamic plant conf1gurat1on 1ss~es, *th em~rgent conditions, and other aspects pertinent to plan~ operation 1.t.11 the barriers 1a1nable to per:form their related support f1a1nct1on(s). These ,

considerations may res1a1lt in risk management ~d other compensato~

actions being required d1a1ring the period that barriers are unable to per:form their related s1a1pport f1a1nction(s).

Palisades N1a1clear Plant B 3.0 14 Re>.<ised 12!0Qt201 Q

bCO AppliGability B---3.0 BASES bCO 3.0.9 bCO 3.0.9 may be applied t syste_m supported by barrier: ~:e or more trai~s or subsystems of a (Gontinued) funG~1on(s), pro*.<ided that risk is at Gannot pro¥1de their related support L:i-:s:::y'::1 AlORll!led

~=*

=r-::QR gf Iha effects QR {iRcludiRS

.

• _applied GonGurrently to ease and from external

~p=

I . ~~~:system sul'pg=~=-":,

gr subsystems I 8

0 " ' subsyslam g1 a

' ::," : : ' .r,ers 3""cll9A{s) fgr diff*-1 ~ ; ; . ~ ;""~ P""'id& their 1&laled .-;.~;;;;

suppGrliRg

.oig - be applied lgr up lg 30 ; :R~at,r,g .,,,.RIB. fgr example, LCO mu t1ple tran supported s 'Stem . ~s or more than one train of a tf pr~teGts against internal oodin~f th: affeGted barrier for one train

R. P - oSaiRsl lgmedg ...,:;' ltl~ ~ - d barrier lgr !tie gltler ner rnay be the . 188

• n

• 18 example th af 8

• luRclleRs 1 r eaoh a"':' plly""'81 ba<rier but """'" d;u;.,..~ 0ecled proteGtlOn 8

If ~uring the time that bCO 3 0 9 i .

~:~:ubeystem b068..... i~g~.::::s t*d. !tie 1&qui..d OPERABLE

-. bE status within 24 h ' I must be restored to subsystem(&) supported by ba:~rs. Othent.<i&e, the train(&) or

"..::!iRIRcli9R{8) RIU81 be de~::.t:op- : pe,tGrm their not met This 24 h er 1

e and the ass *at 1& laled

""!10RI 08Rd~i~RS u..,~ ..:u~~ i:::ed.r,e,,idee ti.., 1g .,;;:::t!d lCOs 0

.0.3 ~-d a rapid plant shutdo'"' ..e~3/41s~ likely lead to entry into b

~~t pFGl>ablllly gl aA iRilialiRg ..;.:i~:.;.~*h ,. RGI juslilied gP.<eR !tie ::,

Gapable of performing their relat~ 16 i.*.iould require the barrier(&)

hour period, the plant risk assoGi!:u~~ort funGti_o~(s). Curing this 24 assessed and managed in aGGo~ *.-1t~ the existing Gonditions is r anGe 'IAth 10 CFR 50.65(a)(4).

Palisades NuGlear Plant Revised 12!0912019

LCO Applicability B 3.0 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES SRs SR 3.0.1 through SR 3.0.4 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated. SR 3.0.2 and SR 3.0.3 apply in Chapter 5 only when invoked by a Chapter 5 specification.

SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance The LCO is assumed to within the specified Frequency, in accordance with SR 3.0.2, constitutes a be met when the SRs failure to meet an LCO. Surveillances may be performed by means of have been met. any series of sequential, overlapping, or total steps provided the entire Nothing in this Surveillance is performed within the specified Frequency. Additionally, the definitions related to instrument testing (e.g., CH,A.NNEL Specification, however, C,A.LIBRATION) specify that these tests are performed by means of any is to be construed as series of sequential, oi.terlapping, or total steps.

implying that the LCO is met when the Surveillance(s) are associated SRs ha¥e been met. Nothing in this Specification, ho11.tever, is known to be not met to be constrned as implying that systems or components are OPERABLE between Surveillance ~

performances.

The systems or components are kno11m to be inoperable, although still meeting the SRs; or b..- The requirements of the Surveillance(s) are known to be not met betv.teen required Surveillance perforrnances.~facility I Surveillances do not have to be performed when the plant is in a MO-De or other specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified . The SRs associated with a Special Test Exception (STE) are only applicable when the STE is used as an allo11.iable exception to the requirements of a Specification.

Unplanned e>Jents may satisfy the requirements (including applicable aGGeptance criteria) for a gii.f8n SR. In this case, the unplanned ei.f8nt may be credited as fulfilling the performance of the SR. This alloi.*Jance includes those SRs whose performance is normally precluded in a given MODE or other specified condition.

Palisades Nuclear Plant B 3.0-16 Revised 12/09/2019

to restore variables that are variables within outside their their specified BASES limits.

SR 3.0.1 Surveillances, * , do (continued) not have to be performed o inoperable equipment bee use the ACTIONS define the remedial measures that apply. eillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to OPERA.BLE status.

Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 3.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary plant parameters not hB\!ing been established . In these situations, the equipment may be considered OPERABLE pro>.<<ided testing has been satisfactorily completed to the e~ent possible and the equipment is not otherwise belie>.<<ed to be incapable of performing its function. This i.\<ill allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.

An example of this process is:

a- High Pressure Safety Injection (HPSI) maintenance during shutdo1J111 that requires system functional tests at a specified pressure. Pro>.<ided other appropriate testing is satisfactorily completed, startup can proceed v.<ith HPSI considered OPERA,BLE.

This allows operation to reach the specified pressure to complete the necessary post maintenance testing.

SR 3.0.2 SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required .4.ction with a Completion Time that requires the periodic performance of the Required ,A.ction on a II once per . . .II *in ter.*al . facility SR 3.0.2 permits 5% extension of the interval specified in the Frequency. T

• extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities).

When a Section 5.5, "Programs and Manuals," specification states that the provisions of SR 3.0.2 are applicable, a 25% extension of the testing interval, whether stated in the specification or incorporated by reference, is permitted.

Palisades Nuclear Plant B 3.0-17 Revised 12/09/2019

LCO Applicability B 3.0 BASES SR 3.0.2 The 25% extension does not significantly degrade the reliability that (continued) results from performing the Surveillance at its specified Frequency. This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs.

Tl=le eXGeptigns ro SR 3.0.2 are tl=lgse S1,11veillam:es fgr ¥A1icl=I tl=le 25%

extensign gf tl=le interval specified in tl=le Frequency does not apply. Tl=lese e;,roeptigns are stated in tl=le individual Specifications. Examples gf wl=lere SR 3.0.2 dges ngt apply are tl=le Cgntainment beak Rate Testing Pmgram required by 10 CFR 50, Appendix J, and tl=le American Society gf Mecl=lanical Engineers (ASME) Cgde inseNice testing required by 10 CFR 50.55a. Tl=lese prggrams establisl=I testing requirements and frequencies in accordance witl=I tl=le requirements of regulations. Tl=le TS canngt, in and gf tl=lemsel>.tes, extend a test inte1Val specified in tl=le regulatigns directly gr by reference.

As stated in SR 3.0.2, tl=le 25% extensign allcvNed by SR 3.0.2 may be applied ro Required .A£tigns wl=lgse Cgmpletign T ime is stated as "gnce per . . .* l=lcv.ve'.<<er, tl=le 25% extensign does not apply tg tl=le initial performance gf a Required Actign 'Nitl=I a periodic Cgmpletion Time tl=lat requires performance on a "gnce per . .. " basis. Tl=le 25% extensiOA applies tg eacl=I performance of tl=le Req1:1ired Actign after tl=le initial perfgrmance. Tl=le initial performance gf tl=le Required Action, wl=letl=ler it is a particular Su1Veillance gr sgme gtl=ler remedial actign, is cgnsidered a single action witl=I a single Cgmpletign Time. One reasgn fgr ngt allgwing tl=le 25% extensign ro tl=lis Cgmpletign Time is tl=lat sucl=I an actign usually verifies tl=lat no lgss of function l=las occurred by cl=lecking tl=le status gf redundant gr di1.ierse cgmpgnents gr accgmplisl=les tl=le functign gf tl=le ingperable equipment in an alternati1.ie manner.

The provisions of SR 3.0.2 are not intended to be used repeatedly to extend Surveillance intervals (otl=ler tl=lan tl=lgse cgnsistent *1.titl=I refueling inteF\<als) or periodic Completion Time intervals beyond those specified.

SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring affected equipment ingperable gr an affected variable outside the specified limits when a Surveillance has not been performed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.

Palisades Nuclear Plant B 3.0-18 Amendment 270 Revised 12/09/2019

LCO Applicability B 3.0 BASES SR 3.0.3 When a Section 5.5, "Programs and Manuals," specification states that (continued) the provisions of SR 3.0.3 are applicable, it permits the flexibility to defer declaring the testing requirement not met in accordance with SR 3.0.3 when the testing has not been completed within the testing interval (including the allowance of SR 3.0.2 if invoked by the Section 5.5 specification). facility This delay period provides an adequate time to perform Surveillan es that have been missed. This delay period permits the performance Surveillance before complying with Required Actions or other r measures that might preclude performance of the Surveillanc .

The basis for this delay period includes consideration of plaAt conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements. When a Surveillance with facility Frequency based not on time intervals, but upon specified ooit nditionS; operating sitblations, or reqblirements of regbllations (e.g., prior to entering MOOE 1 after eaGh fblel loading, or in aGGordanse i.*.,iith 10 Ci;:R 50,

.A.ppendbc J, as modified by approved exemptions, etc.) is discovered to not have been performed when specified, SR 3.0.3 allows forthe full delay period of up to the specified Frequency to perform the Surveillance.

However, since there is not a time interval specified, the missed Surveillance should be performed at the first reasonable opportunity.

SR 3.0.3 proi.(ides a time limit for, and allowanses for the performanse of, Sbliveillanses that besome applisable as a oonseqblence-of MOOE shanges imposed by Reqblired .A.Gtions.

Palisades Nuclear Plant B 3.0-19 Amendment 270 Revised 12/09/2019

LCO Applicability B 3.0 BASES SR 3.0.3 SR 3.0.3 is only applicable if there is a reasonable expectation the (continued) associated eqYipmeRt is OPERA.BI..E gr that variables are within limits, and it is expected that the Surveillance will be met when performed. Many factors should be considered, such as the period of time since the Surveillance was last performed, or whether the Surveillance, or a portion thereof, has ever been performed, and any other indications, tests, or activities that might support the expectation that the Surveillance will be met when performed. AR example of the Yse gf SR 3.0.3 >NoYld be a relay soRtast that 11.ias Rot tested as reqYired iR aGGgrdanse '.*.<ith a partisYlar SR, bYt pre¥iOYS SYGGessfyl perfgrmanses gf the SR iRGIYded the relay sgRtast; the adjaseRt, physisally GQRRested relay GQRtasts were tested dYriRg the SR perfgrrnar1se; the SYbjeGt relay GQRtaGt has beeR tested by angther SR; gr historisal gperatioR gf the sYbjeGt relay GORtast has beeR SYGGessfyl. It is RQt SYffisieRt tg iRfer the behavigr of the assgsiated eqYipmeRt frgm the perfgrmaRGe gf similar eqYipmeRt. The riggr of determiRiRg whether there is a reasoRable expeGtatigR a SYn'-&illance-wiU be met wheR perfgrmed shgyld iRsrease based QR the leRgth of time siRGe the last perfgrmaRGe gf the SYrveillanse. If the SYrveillaRGe has beeR perfgrmed reseRtly, a re¥iew gf the SYrveillanse history and eqYipmeRt performaRGe may be SYffisieRt tg SYppgrt a r&SSQRable expestatigR that the SYrveillanse will be met wheR perfgrmed . For SYrveillanses that have RQt beeR perfgrmed fgr a lgRg perigd gr that have Re\!Elr beeR perfgrmed, a riggrgys evalYatigR based QR gbjeGti\!9 evideRGe shgyld pm>.<ide a high degree of GORfideRGe that the eqYipmeRt is OPERA.BI..E. The e¥alyatigR shgyld be dQGYm&Rted iR syffisieRt detail to allgw a kmwAedgeable iRdi1.tidYal to YRderstaRd the basis fgr the determiRatioR.

Failure to comply with specified Frequencies for SRs is expected to be an infrequent occurrence. Use of the delay period established by SR 3.0.3 is a flexibility which is not intended to be used repeatedly to extend Surveillance intervals.

Palisades Nuclear Plant B 3.0-20 Amendment 270 Revised 12/09/2019

LCO Applicability facility B 3.0 facility BASES SR 3.0.3 While up to 24 ho rs or the limit of e specified Frequency is provided to (continued} perform the miss d Surveillance, it s expected that the missed Surveillance will e performed at t e first reasonable opportunity. The determination of he first reason opportunity should include facility consideration o he impact on plant risk (from delaying the Surveillance

~1Ate11 as any plant configuration changes required or shutting the plant dGWA to pe e Surveillance} and impact on any analysis assumptions, in additio Y-Ait conditions, planning, availability of personnel, and the time required to perform the Surveillance. This risk impact should be managed through the program in place tQ implement 10 CFR 50.65(a}(4) and its implementation guidance, NRC Regulatory Guide 1.162, "Assessing and Managing Risk Before Maintenance

.A.c:ti¥ities at Nuclear Po*.t.ter Plants." This Regulatory Guide addresses consideration of temporary and aggregate risk impacts, determination gf risk management action thresholds, and risk management action up tQ and including plant shutdG!Nn. The missed Surveillance should be treated as an emergent condition as discussed in the Regulatory Guide. The risk e¥aluation may use quantitati'I~, qualitati*,e, or blended methods. The degree gf depth and rigor of the e¥aluation should be commensurate \*Jith the importance gf the component. Missed Surveillances for important components should be analyzed quantitati¥ely. If the results gf the risk ewluation determine the risk increase is significant, this e¥aluation should be used to determine the safest course gf action . All missed Surveillances will be placed in the licensee's Corrective Action Program.

If a Surveillance is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon expiration of the delay period. If a Surveillance is failed within the de lay period, then the equipment is inoperable, or the variable is outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon the failure of the Surveillance.

Completion of the Surveillance within the delay period allowed by this Specification, or within the Completion Time of the ACTIONS, restores compliance with SR 3.0.1.

Palisades Nuclear Plant B 3.0-21 Revised 12/09/2019

variables ensure safe handling and LCO Applicability B 3.0 BASES

- - - - - - - - - - - - - - - - -fuel ._________

storage of spent SR 3.0.4 SR 3.0.4 establishes the requirement that all applicab before entry into a MODE or other specified Condition This Specification ensures that si.q;tei:JHmG--GCm\lX>i=ieR~>¥1:=""~Y-I~

reqYiremeRts ar-id variable limits are met before entry into M(;}IJl~...o,:

GtheF-specified conditions in the Applicability for which thes compoReRts eRsYre safe operatioR of the plaRt.

The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restorin systems or compoReRts to OPER~BLE statYs before entering an associ ed MODE or other specified condition in the Applicability.

variables that are outside their specified limits

• ircumstances, failing to meet an SR will not result in SR . . rl"ll"lunn - - - - - . . - - - - specified condition change. When a si.q;tln!Rr,.;§Yle&,tStEmt;---Gt¥181iGR,--G1em~~\t.~~~}f a variable is variable is iRoperable or outsI

• specified limits, the associated SR(s) outside its are not required to be performed, per . .1, which states that s eillances do not have to be perfarmed n iRoperable eqYipmeRt.

specified limit Wh eqYipmeRt is iRoperable, SR 3.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed.

Therefore, failing to perform the Surveillance(s) within the specified Frequency does not result in an SR 3.0.4 restriction to changing MODES or other specified conditions of the Applicability. However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes.

SR 3.0.4 does not restrict changing MODES or other specified conditions of the Applicability when a Surveillance has not been performed within the specified Frequency, providing the requirement to declare the LCO not met has been delayed in accordance with SR 3.0.3.

The pro¥iSiORS of SR 3.0.4 shall Rot pre¥eRt chaRges iR MODES or other specified coRditioRs iR the Applicability that are reqYired to comply with ACTIONS. IR additioR, the pro¥iSiORS of SR 3.0.4 shall Rot pre\feRt chaRges iR MODES or other specified CORditiORS iR the ,A,pplicability that resYlt from ar-iy plaRt shYtdOWR. IR this GORtext, a plant shYtdmtJ.R is defiRed as a chaRge iR MODE or specified CORditiOR iR the ,A,pplicability associated v.iith traRsitioRiRg from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

Palisades Nuclear Plant B 3.0-22 Revised 12/09/2019

LCO Applicability B 3.0 BASES SR 3.0.4 The precise requirements for performance of SRs are specified such that (continued) exceptions to SR 3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the MOOE or other specified condition in the Applicability of the associated LCO prior to the performance or completion of a Surveillance. A Surveillance that could not be performed until after entering the LCO's Applicability, would have its Frequency specified such that it is not "due" until the specific conditions needed are met.

Alternately, the Surveillance may be stated in the form of a Note as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of SRs' annotation is found in Section 1.4, Frequency.

Palisades Nuclear Plant B 3.0-23 Revised 12/09/2019

SFP Wat.er Level IFACltTY I B 3.7.14 B 3.7 PL.A.NT SYSTEMS B 3.7.14 Spent Fuel Pool (SFP) Wat.er Level BASES BACKGROUND The minimum wat.er level in the SFP meets the assumptions of iodine decontaminat.ion factors following a fuel handling or cask drop accident.

The specified wat.er level shields and minimizes the general area dose when the storage racks are filled to their maximum capacity. The wat.er also provides shielding during the movement of spent fuel.

A general description of the SFP design is given in the FSAR, Section 9.11 (Ref. 1), and the Spent Fuel Pool Cooling and Cleanup System is given in the FSAR, Section 9.4 (Ref. 2). The assumptions of fuel handling and fuel cask drop accidents are given in the FSAR, Section 14.19 and 14.11 (Refs. 3 and 4), respectively.

APPLICABLE The minimum wat.er level in the SFP meets the assumptions of fuel SAFETY ANALYSES handling or fuel cask drop accident analyses described in References 3 and 4 and are consistent with the assumptions of Regulat.ory Guide 1.183 (Ref. 5). The resultant doses are within applicable 10 CFR 50.67 (Ref. 6) limits.

Reference 5 considers 23 ft of wat.er between the top of the damaged fuel assembly and the fuel pool surface for a fuel handling or fuel cask drop accident. This LCO preserves this assumption for the bulk of the fuel in the storage racks. In the case of a single assembly, dropped and lying horizontally on top of the spent fuel racks, or for a fuel handling accident inside containment, there may be < 23 ft of water above the top of the assembly and the surface, by the width of the assembly. Reference 5 specifies methods to address this condition. For additional conservat.ism, the analysis assumes that. all fuel rods fail, although analysis shows that.

only the first few rods fail from a hypothetical maximum drop.

The SFP wat.er level sat.isfies Criteria 2 and 3 of 10 CFR 50.36(c)(2).

Palisades Nuclear Plant B3.7.14-1 Revised 01/29/2020

SFP Wat.er Level B 3.7.14 BASES LCO The specified wat.er level preserves the assumptions of the fuel handling or fuel cask drop accident analyses. As such, it is the minimum required for movement off uel assemblies or movement of a fuel cask in or over the SFP.

The LCO is modified by a Note which allows SFP level to be below the 647 ftelevat.ion to support movement of a fuel cask in or over the SFP.

This is necessary due to the wat.er displaced by the fuel cask as it is lowered or dropped into the SFP. If the SFP level is normal prior to the fuel cask entering the SFP, the SFP could overflow.

APPLICABILITY This LCO applies during movement of irradiat.ed fuel assemblies in the SFP or movement of a fuel cask in or over the SFP since the potential for a release of fission products exists.

ACTIONS The -4.ctions are modified by a Note indiGating that bCO 3.0.3 does not apply.

If mo*.iing irradiated fuel assemblies or fuel Gask in or oi.-er the SFP while in MODE 5 or 6, bCO 3.0.3 'l!OUld not speGify any aGtion. If moi.<ing irradiated fuel assemblies or fuel Gask in or o-.ier the SFP while in MODES 1, 2, 3, and 4, the mo¥ement gf fuel or moi.-ement of a fuel Gask is independent of reaGtor operations. Therefore, in either Gase, inability to suspend mo¥ement gf irradiated fuel assemblies or fuel Gask in or o*.ier the SFP is not suffiGient reason to require a reaGtor shutdown.

A.1 and A.2 When the initial conditions for an accident cannot be met, steps should be taken to preclude the accident from occurring. When the SFP wat.er level is lower than the required level, the movement of irradiat.ed fuel assemblies in the SFP or movement of a fuel cask in or over the SFP are immediat.ely suspended. This effectively precludes a spent fuel handling or fuel cask drop accident from occurring. This does not preclude moving a fuel assembly or fuel cask to a safe position.

Palisades Nuclear Plant B 3.7.14-2 Revised 01/29/2020

SFP Wat.er Level B 3.7.14 BASES SURVEILLANCE SR 3.7.14.1 REQUIREMENTS This SR verifies sufficient SFP wat.er is available in the event of a fuel handling or fuel cask drop accident. The wat.er level in the SFP must be checked periodically. The SYPleillance Freq1,1ency is controlled 1,1nder the Surveillance Frequency Control Program.

REFERENCES 1. FSAR, Section 9.11 The 7 day Frequency is appropriate because the volume

2. FSAR, Section 9.4 in th~ pool is normally stable.

Water level changes are

3. FSAR, Section 14.19 controlled by plant procedures

4. FSAR, Section 14.11 and are acceptable, based on operating experience.

5. Regulat.ory Guide 1.183

6. 10 CFR 50.67 Palisades Nuclear Plant B 3.7.14-3 Amendment No. 271 Revised 01/29/2020

/FACILITY SFP Boron Concentration B 3.7.15 B 3.7 PLANT SYSTEMS B 3.7.15 Spent Fuel Pool (SFP) Boron Concentration BASES BACKGROUND As described in LCO 3.7.16, "Spent Fuel Pool Storage," fuel assemblies are stored in the fuel storage racks in accordance with criteria based on initial enrichment, discharge bumup, and decay time.

The criteria were based on the assumption that 850 ppm of soluble boron was present in the spent fuel pool. The pool is required to be maintained at a boron concentration of~ 1720 ppm. Criterion 2 of 10 CFR 50.36 (c) (2) requires that criticality control be achieved without credit for soluble boron. However, in 1998 the NRC documented requirements that could be established to maintain criticality below0.95. This is documented in "Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light-Water Reactor Power Plants", Laurence I. Kopp, U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Reactor Systems Branch, February 1998. The precedent of taking credit for soluble boron in spent fuel pool water to provide criticality control has also been established. Soluble boron credit was used in the Westinghouse Spent Fuel Rack Criticality Analysis Methodology described in WCAP-14416-NP-A and that methodology was approved for use by an NRC Safety Evaluation dated October25, 1996. The criteria discussed above was developed using a method that closely followed the Westinghouse methodology. Additionally the requirements specified by the NRC guidance are in place at Palisades.

APPLICABLE A fuel assembly could be inadvertently loaded into a fuel storage rack SAFElY ANALYSES location not allowed by LCO 3.7.16 (e.g., an insufficiently depleted or insufficiently decayed fuel assembly). Another type of postulated accident is associated with a fuel assembly that is dropped onto the fully loaded fuel pool storage rack. Either incident could have a positive reactivity effect, decreasing the margin to criticality. However, the negative reactivity effect of the soluble boron compensates for the increased reactivity caused by either one of the two postulated accident scenarios.

The concentration of dissolved boron in the SFP satisfies Criterion 2 of 10 CFR 50.36(c)(2).

LCO The specified concentration of dissolved boron in the SFP preserves the assumptions used in the analyses of the potential accident scenarios described above. This concentration of dissolved boron is the minimum required concentration for fuel assembly storage and movement within the SFP.

APPLICABILllY This LCO applies whenever fuel assemblies are stored in the spent fuel pool.

Palisades Nuclear Plant B 3.7.15-1 Revised 01/29/2020

SFP Boron Concentration B 3.7.15 BASES ACTIONS The ACTIONS are rmdified by a Note indicating that bCO 3.0.3 does not

~

If mo¥ing irradiated fuel assemblies \t.1hile in MOOE 5 or 6, bCO 3.0.3

'f.'Ould not specify any action. If rm¥ing irradiated fuel assemblies 'Nhile in MOOE 1, 2, 3, or 4, the fuel roovement is independent of reacror operation . Therefore, inability ro suspend movement of fuel assemblies is not sufficient reason ro require a reacror shutdown.

A.1. and A.2 When the concentration of boron in the spent fuel pool is less than required, immediate action must be taken to preclude an accident from happening or to mitigate the consequences of an accident in progress.

This is most efficiently achieved by immediately suspending the movement of fuel assemblies. This does not preclude the movement of fuel assemblies to a safe position. In addition, action must be immediately initiated to restore boron concentration to within limit.

SURVEILLANCE SR 3.7.15.1 REQUIREMENTS This SR verifies that the concentration of boron in the spent fuel pool is within the required limit. As long as this SR is met, the analyzed incidents are fully addressed.,f\The Surveillance Frequency is controlled under the C', *-

• C-- - ~ -* r---*--* - - -* .

REFERENCES None The 7 day Frequency is appropriate because no major replenishment of pool water is expected to take place over a short period of time.

Palisades Nuclear Plant B 3.7.15-2 Amendment No. 271 Revised 01/29/2020

rFACILITY Spent Fuel Pool Storage B 3.7.16 B 3.7 PLANT SYSTEMS B 3. 7.16 Spent Fuel Pool Storage BASES BACKGROUND The fuel storage facility is designed to store either nei.v (nonirradiated) n1Jclear f1Jel assemblies, or used (irradiated) fuel assemblies in a vertical configuration underwater. The storage pool is sized to store 892 fuel assemblies, which includes storage for failed fuel canisters.

The fuel storage racks are grouped into two regions, Region I and Region II per Figure B 3.7.16-1. The racks are designed as a Seismic Category I structure able to withstand seismic events.

Region I contains Metamic equipped racks in the spent fuel pool having a 10.25 inch center-to-center spacing and a single Carborundum equipped rack in the north tilt pit having an 11.25 inch by 10.69 inch center-to-center spacing. The Region I Carborundum equipped rack has restrictive loading patterns to address degradation of neutron absorbing material in the rack. The loading patterns accommodate some face-adjacent fuel assemblies with consideration of burn up credit in Sub-Regions 1D and 1E. The Region 1 Metamic equipped racks are only restricted by maximum planar U 235 enrichment. The Region I Carborundum equipped rack also has provisions for storing non-fissile bearing components.

Region II contains racks in both the spent fuel pool and the north tilt pit having a 9.17 inch center-to-center spacing. Because of the smaller spacing and an analyzed solid poison concentration of zero (Boraflex),

Region II also has limitations for fuel storage. Further information on limitations can be found in Section 4.0, "Design Features." These limitations (e.g., enrichment, burnup, loading patterns) are sufficient to maintain a keff of s 0.95 when flooded with borated water and keff < 1.0 when flooded with unborated water.

APPLICABLE The fuel storage facility was originally designed for noncriticality by use SAFETY ANALYSES of adequate spacing, and "flux trap" construction, whereby the fuel assemblies are inserted into neutron absorbing stainless steel cans.

The current criticality calculations also take credit for soluble boron to prevent criticality.

The spent fuel pool storage meets the requirements specified in "Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light-Water Reactor Power Plants", Laurence I. Kopp, U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Reactor Systems Branch, February 1998. This document Palisades Nuclear Plant B 3.7.16-1 Amendment No. ~ . ~ . ~ . 250

Spent Fuel Pool Storage B 3.7.16 BASES ACTIONS The ACTIONS ar:e modified by a Note indicating that LCO 3.0.3 does not

~

If moving irradiated fuel assemblies \*..<<hile in MODE 5 or 6, LCO 3.0.3 would not specify any action. If mcv.'ing irradiated fuel assemblies *.¥hile in MODE 1, 2, 3, or 4, the fuel mO\'ement is independent of r:eactor operation. Therefor:e, in either case, inability to move fuel assemblies is not sufficient r:eason to requir:e a reactor shutdown.

When the configuration off uel assemblies or non-fissile bearing components stored in the spent fuel pool is not in accordance with the storage requirements, immediate action must be taken to make the necessary movement(s) to bring the configuration into compliance with the requirements.

SURVEILLANCE SR3.7.16.1 REQUIREMENTS This SR verifies by administrative means that the combination of fuel assembly maximum nominal planar average enrichment and proposed fuel assembly placement is in accordancewith Specification4.3.1.1 prior to placing the assembly in a Region I Carborundum equipped storage location. This SR also verifies by administrative means that non-fissile bearing component storage will be in accordance with Specification 4.3.1.1 m prior to placing the component in a Region I Carborundum storage location.

This SR also verifies by administrative means that the nominal planar average enrichment is in accordance with Specification 4.3.1.2 prior to placing the assembly in a Region I Metamic equipped storage location.

This SR also verifies by administrative means that the combination of maximum nominal planar average U-235 enrichment, bumup and decay time of the fuel assembly is in accordance with Tables 3.7.16-1 through

3. 7.16-5, as appropriate, in the accompanying LCO prior to placing the fuel assembly in a storage location in the Region I Carborundum equipped rack or the Region II racks.

REFERENCES None Palisades Nuclear Plant B 3.7.16-4 Amendment No. ~ . 238, ~ . 250