ML20199J665
| ML20199J665 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/20/1997 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20199J664 | List: |
| References | |
| NUDOCS 9711280195 | |
| Download: ML20199J665 (52) | |
Text
{{#Wiki_filter:_-_-- ENCLOSURE 3 l V0GTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECilNICAL SPECIFICATIONS ADDlIlONAL FUEL ST0JMOILRACKS FOR UNIT _1.fUEldTORAGE POO1 I INSTRUCTIONS FOR INCORPORATION The proposed change to the Vogtle Electric Generating Plant Technical Specifications would be incorportted as follows. Remove page Insert Page viii viii ix ix 3.7-40 3.7-40 3,7-41 3.7-41 3.7-42 3.7-42 4 0-2 4.0 2 4.0 3 4.0-3 4.0 3a 4.0 3a 4.0-3b 4.0 3b 4,0-4 4.0-4 4.0 7 4.0 7 4.0 9 4.0-9 4.0-10 4.0 10 Changes to tne Technical Specification bases would be incorporated as follows: Remove Page Insert Page Il 3.7-92 B 3.7-92 13 3.7-93 B 3.7-93 133.794 Il 3.7-94 B 3.7-94a B 3.7-94b 133.795 B 3.7-95 B 3 7 97 B 3.7-97 Il 3.7-97a Il 3.7 07b B 3.7-98 B 3.7-99
- These instructions are consistent with the technical crecifications following their revision according to the changes contained in LCV-0849-E.
9711200195 971120 PDR ADOCK 05000424 E31 P PDR
. . - - ~ ., -. - --, - - -. ~
i k t TA8LE OF CONTENTS (continued) : i LIST OF TABLES j 1,1-1 MODES . . . . . . . . . . . . . . . . . . . . . . . 1.1-7 ; 3.3.1-1 Reactor Trip System Instrumentation . . . . . . . . . 3.3-14_ l 3.3.2-1 Engineered Safety Feature Actuation System
. instrumentation . . . . . . . . . . . . . . . . . 3.3-30 3.3.3-1 Post Accident Monitoring Instrumentation . . . .-. . . 3.3-42 3.3.4-1 Remote Shutdown System Instrumentation and Controls . 3.3-45 3.3.6-1 Containment Ventilation Isolation Instrumentation . . 3.3-53 '3.3.7-1 CREFS Actuation Instrumentation . . . . . . . . . < . . 3.3-59 3.7.1-1 Maximum Allowable Power Range Neutron Flux High Trip Setpoint with Inoperable Main Steam Safety Valves . 3.7-3 '
3.7.1-2 Main Steam Safety Valve Lift Settings . . . . . . . . 3.7-4 ; 3.6.4-1 Discharge Test Surveillance Requirements . . . . . . . 3.8-29 3.8.6-1 Battery Cell Parameters Requirements . . . . . . . . . 3.8-35 5.5.9-1 Minimum Number of Steam Ganerators to Be l Inspected During !nservice Inspection . . . . . . 5.0-18 : 5.5.9-2 Steam Generator Tube Inspection . . . . . . . . . . . 5.0-19 I i LIST'0F FIGURES l 2.1.1-1 Reactor Core Safety Limits . . . . . . . . . . . . . . 2.0-2 , 3.4.16-1 Reactor Coolant Dose Equivalent I-131 Reactor Coolant j Specific Activity Limit Versus _ Percent of Rated l Thermal Power with the Reactor Coolant Specific Activity > 1 pCi/ gram Dose Equivalent I-131 . . . 3.4-44 I 3.7.18-1 Vogtle Unit 1 Burnup Credit Requirements for All Cell Storage . . . . . . . . . . . . . . . . . 3.7-42 3.7.18-2 Vogtle Unit 2.Burnup Credit Requirements for All Cell. Storage . . . . . . . . . . . . . . . . . . 3.7-43: 4.3.1-I "
- ;tle L5it I n 7 c = 33; n g ,,,g g 7,,
-S-r:t :f i Ste .;e . . h.b.7.e ,,,d . ... . . . . . . 4.0-4 4.3.1-2 Vogtle Unit 2 Burnup Credit Requirements for
' 3-out-of-4 Storage . . . . . . . . . . . . . . . . 4.0-5 Vogtle Units l iand 2 viii Amendment No. (Unit 1)
Amendment No. (Unit 2)
TA8LE.0F CONTENTS (continued) 4.3.1-3 Vogtle Unit 2 Burnup Credit Requirements for 3x3 Storage . . . . . . . . . . . . . . . . . . . . . 4.0-6 4.3.1-4 Vogtle Units 1 and 2 Empty Cell Checkerboard Storage Configurations . . . . . . . . . . . . . . 4.0-7 4.3.1-5 Vogtle Unit 2 3x3 Checkerboard Storage Configuration . 4.0-8 4.3.1-6 Vogtle Units 1 and 2 Interface Requirements (All Cell to Checkerboard Storage) . . . . . . . . 4.0-9 4.3.1-7 Vogtle Unit /-1-end 2 Interface Requirements (Checkerboard Storage Interface) . . . . . . . . . 4.0-10 4.3.1-8' 'Yogtle Unit 2 Interface Requirements _ (3x3 Checkerboard to Al'. Cell Storage) . . . . . . 4.0-11 4.3.1-9 Vogtle Unit 2 Interface Requirements (3x3 to Empty Cell Checkerboard Storage) . . . . . 4.0-12 Vogtle Units 1 and 2 ix Amendment flo. (Unit 1) Amendment No. (Unit 2)
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Fuel Assembly Storage in the fuel Storage Pool 3./ 18 t 3.7 PLANT SYSTEMS ; 3.7.18 Fuel Assembly Storage in the Fuel Storage Pool' ' LCO 3.7.18 The combination of initial enrichmentj burnup and ! configuration of fuel assemblies stored in the fuel storage pool shall be within the Acceptable Burnup Domain of Figures ; 3.7.18-1 (Unit 1), 3.7.18-2 (Unit 2), or in accordance with i Specification 4.3.1.1.(mit I),e 4,3,4 2. (WNE), APPLICABILITY: Whenever any fuel assembly is stored in the fuel storage pool. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 --------NOTE---------
- LCO not met. LCO 3.0.3 is not applicable.
Initiate action to Immediately move the ncncomplying fuel assembly to an acceptable storage location. b Vogtle Units 1 and 2 3.7-40 Amendment No. (Unit 1) Amendment No. (Unit 2)_ !
l l Fuel Assembly Storage in the fuel Storage Pool 3.7.18 SURVEILLANCF RE0VIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify by a combination of visual Prior to inspection and administrative means that storing the the initial enrichment, burnup, and storage fuel assembly location of the fuel assembly is in in the fuel accordr.nce with Figures 3.7.18-1 (Unit 1), storage pool 3.7.18-2 (Unit 2), or location. Specification 4.3.1.1 (A,f Q o e A,3 lo T (Un ol2), Vogtle Units 1 and 2 3.7-41 Amendment No. (Unit 1) Amendment No. (Unit 2)
1-. hh ' f Fuel Assembly Storage in the Fuel Storage Pool p p_ j . 3.7,18 l 1 i1 l l l t I t il l 1 I f I l ii l iil I i i t ! I i i i i e I i i t i I l t 1 i i i i i l i i l i i i i lI i 1 i i i i i l I i i i i i f i i i i i i i i i i i l i i l-t 1 i i I i i / l' ll I ' 35000 f f( l /
/
30000 --
.j l
- f I 3 / I
;:! 25000 , / ,
/
a /
/
20000 ACCEPTABLE '
/
J
/
/
/
- 15000 /
8 '
- u. /
/
/ ,
10000
/ l UNACCEPTABLE F-l
/
/
' I 5000 ; j I
/
I
/
0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5:0 w- Qnitjal --U 235 Enrichment (nominal w/o) ,/ Figure 3,7.18-1 Vogtle Unit 1 Burnup Credit Requirements for All Cell Storage Vogtle Units 1 and 2 3,7-42 Amendment No. (Unit 1) Amendment No. (Unit 2)
I Fuel Asseinbly darage s'n Ile fuel Shraye pgl : J 7, /r ! 15000 f i' 1 i ..
.O ACCEPTABLE
$ 10000
/
h / a / g
/
/
k
~
/
$ 5000
~ /
/
/
/
,/ UNACCcPTABLE --
)
/
0 3.0 3.5- 4.0 4.5 5.0 Initial U 235 Enrichment (nominal w/o) 3,1, I f~ l Figur/Vogtle Unit i Burnup Credit Requirements for All Cell Storage a a d 2.
- g Vogtle UnigIh e! pe,!eremen S ;7,: p. ; ggg -
- 3. 7 -N2 -
4 Design Features 4.0 l 4.0 DESIGN FEATURES (continued) , 4.3 fuel Storage ; 4.3.1 Criticality DLnifIh 4.3.1.1. The spent fuel storage racks are designed and shall be l maintained with: -
- a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; l nsa or f,drI8bNy 5/'"! f"# , . b. K 1.0 when fully flooded with unborated water a 55 era f jif3 *8
/ A , g;mbiu/18# wblc<hincludesanallowanceforuncertaintiesas
,, described in Section 4.3 of the FSAR.
o{ htwf ord IP'}lal nomv, al
. k s0 tnrg6meaY#a # o8##/j* g / 604,,: ppm.95 when fully HUnit-4)-or 500flooded with p; m-{ Wit 'it, water which borated to
. u -
includes an allowance for uncertainties as benup_t/ oms #H # I p'P# #. described in Section 4.3 of the FSAR;
),7, / 9 -l o r A d P d *
- h: :r p rtiell p w o h i-e - sneti:: effer:a:.;;ti:1::::dlie .ad initi:1 asia.t t( ff f f d ', g , / o n e d ir ear.4 c k- nt an t5: "acceat*h1- burr. p denia" :f-4Ws-Br7r16-t-(Unid :r 3.7.!" 2 (Wit 2) ::y-IMS S"#f.e90a//0 f. # 3 / -be-41-lowed-tenrestricted-stecoge 4n 1.he Oatt -! en-G4 gg op 33y h e 0//d"'#g - Un i t-2-fuel-s t o r ag,e- pool y-re spect 4 ve ly,-
6 P Co weepit p<rcent if LTT" , (A n resIri, d ) 4'l#F8ff ld e. New'or ar ially spent fuel assemblies with a mariw4M aembinet ..=bernua - ::inal-
-l/it M O l f vt / Sbrdff enrichment in +ha "dre;d initial da rin" t:ble-burne; :f-F-tiirre 4rarl-1-may be stored in the Unit I fuel pool storage pooi in a 3-out-of-4 checkerboard storage configuration as shown in Figure 4.3.1-4.
"rr er p:rti:lly :;:ni f ;l :::e-Li!e: eith : -
-me&ur t-44441-:n-i:M::t ar 5.0 ;:i-ht ;: :ent.
-U-ft5 msi bw -itored ia th: 5 +t-: ft:I :ter:;: p::1-
! -2 ::t- F 4 d:9erhamed 5targ- ra s p ;tj:n
-es skewa in et;gre i,-3,3 3,_
Interfaces between storage configurations in the Unit I fuel storage pool shall be in compliance withfigure/4.3.1-6e-d'.3.!* "A" assemblies are new or partially spent fuel assemblies with a (continued) Vogtle Units 1 and 2 4.0-2 Amendment No. (Unit 1) Amendment No. (Unit 2)
Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) combination of burnup and initial nominal or wlu,ed Asve o enrichment in the " acceptable burnup~ domain" of a s sembl i e s .ar4-mew-ep. Figure 3.7.18-1,<4 "B" M14 yerm m rc[errect **Miy :;t-'. _su.f"-!,:::: _._a .il,i;; with : :::i'n:ti: n ., au.
- w--_i
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a4 7 " MO**if fw s wisi
,1 ,.1,= ..._
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. :::1 110: are assemblies with initial enrichments
/trt Ndn // yud / up to a maximum of 5.0 weight percent U-235.
-fo /, # f / a /- M ~ / _ ":^._er ;;r',441.ly inont fuel usembMes-w44h -
/ -MinaMon-c' b'"a"n anoin4Mel nomini- -
-swidentia the "eccantable '"r-"; 'i""!!a,, :,;
sei
.+4,w,_4a,}.-2-may e r-~~ ^^^ ia
- 3-aut ee-ster.=d af ' th!!h !n the Tb ;I" Unit)St0T2;2 afiIpdd' en-as-shown_in Lisue-444-47 I u_. -. ... 4.n. ..... ru.i .....ui4.,- m4 6 =.
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.--y-
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r---
-in-a-2.eet-of-4-deckarbaa r'd sterage co=fi;"rettee
-e: the"- in figure ' 3-!-4, .
u .. . . . - _.1. i s o .., ru.i , , , - t i a .--," 'm e . i. . r= ' =' ---- !
.combinat.io' n.'.of'- ."rn;; :nd initiel : !=a1" _' = l
-snrichment in tha "sc :;t:ble b;rn:; d:::in" ;f--
-figwee-4drl-3 :y b; :t:r:d in th; Unft- 2 ';;1-
-sterage-;::!-es " law --! ' :-t" fu=1 mer: ' tes ia -
-the-3x3-eheekeri::rd- : tert;e c^-f!;2r:ti:n :: :hn:-
-in44;;re 4.3r14, "r er ;:rt':lly :;:nt ';;i-
-assembMes "ith fe444el n;;;;in;! ri:.'.:;nt: 1;;;
-than-ee-eque,. iw_
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... . .m . v . . r .- _ . . . .. ...
%"4=; e maximum-r:':r; ace f;;; :;;;;il, ,%.1:: - 1
-than--or ::;;;1-to-h410 et '""T -ey be :t:r:d in ths Un44-3-feel-storag= ree1 as "'t;h :nrid ::t" f"e!-
,asse-51ies in the art chackarboard-sta-:;: l'
- aff;;r;;i;n :: :h:x; in Tivo i 4.3-147-
- - . m-
- a. . . . . r. . ,. ._ _, s . . . . . . . . . . . _
wvsul lyWI E "k I VII a ist s t ru Unit 2 ';;1-s4,:r:;:-;--!,,,5,:11 , ,0 , b,-, i= cer:11 re:-
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,,w.w. ,.3 u, w,, , . . . , , m.w.. ., . . . . ;
ess--Alias = e ne" er partia!!y spe.t-
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---4.3.1-;.
-- fueF-:::r-51 !es wi t h ? ce-'4*at4en-ef burn;; : d (continued) i Vogtle Units 1-and 2' 4.0-3 Amendment No. (Unit 1) j Amendment No. (Unit 2) i
.,e. , -y ., .- ,-,we, , - ..--r,. ---
-y,..i +.i -,.-,y, -
-q-
t Desi n features i 4.0 4.0' DESIGN FEATURES 4.3 fuel Storage (continued) - Jnitici nominal enrian nt in the "eccei,tebl.
-burnup 6 :in" of Ti;;;re 3.7.104. "lF esse...L11 ;-
-ara new or-par 444My--spent-fuel-essembl4es-w4tba-sombination-of-burnep-and-initial nominal- -
-enrichment-in-the ^ acceptable-burnup er in8-of--
Figure-4:3TF2. "C* astembl44s-ara _assembl4es-witL--
-4nttiel-enrichmente-up-tc : =e imum-of 5,0-we41M---
percent-U-235. "t:^--essemblies era new cr-- p;rt < :lly-
-epent-fwe1-essembl4et-w+th-e-eembletiemef ber e; and 4 alt 4al-nomine?- eniiG ..Hn th. ".cce-t:ble-
--burnup-dor a4a" :f F f teve-4-3*S--- 844" :::: 51ies -
-are_new or-partisHy Tpent-Tuel arsemblies-with-intt441-nominal-enefehment-s-less-then er :geel-to-
-3,20-weight-percent-U 235 or-having-a-aaximum-
-reference-fuel-assemblyJ, less than er-equabte
-h 410-a t-68'F-
/ 0, y
- f. A nominal-10.6-inch center to center pitch in the l Unit I high density fuel storage rackgt-and-
-g,-A-nominal-10,68-inch-center te center pitch in the- l '
north-south-directten end ;- n::inal-Mr4-inch
.- cantar to center-- sitch in-the-eeet-west-dicestion--
1M - I" the Unit-3 At 9 : hr.:!ty fuel stereye racu. - q ,3 l . 2. h'
- t 2) >
4.3.1./ The new fuel storage racks are designed and shall be 3 maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of 5.05 weight percent;
- b. k , s 0.95 if fully flooded with unborated water, wh,ichincludesanallowanceforuncertaintiesas ,
described in Section 4.3 of the FSAR;
- c. k ,, s 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 4.3 of the FSAR; and
- d. A nominal 21-inch center to center. distance between fuel assemblies placed in the storage racks.
I L l- Vogtle Units 1 and 2 4.0-3a Ame unent No. (Unit 1) Amendment No. (Unit 2) i I
To st e f : 1 g,s I.2 (UHET O Q tof 3 { 4.3.1.7 The spent fuel storage racks are designed and shall be maintained with: .
- a. Fuel assemblies having a maximum U-235 enrichment
- 2. [Uas,b 2) of 5.0 weight percent; l
- b. K wh,{c< h includes1.0 when an fullyallowarice flooded forwith uncertainties unboratedaswater described in Section 4.3 of the iSAR.
- c. k'g",, :s 0.95 when fully flooded with water borated to
. ;;r (":it :) :r 500 ppm ("-it 33. which includes an allowance for uncertainties as .
described in Soction 4.3 of the FSAR;
- d. New or partially spent fuel assemblie' With a combination of burnup and initial .ioninal enrichment in the " acceptable burnup domain" of Figurer 3.7.; -; (".,it !) :r 3.7.18-2 (";it 3) may be allowed unrestricted storage in the '.'ait ;r Unit 2 fuel storage pool, r::;;;tivelyr u m'__ - - .. ..
cwwy w w w w .,,, s i t. n , ,, , O
--- - . -' fWU bOWII[ @ f.Il b wird i T,i $ ! Il "III . VI uus siup
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= = =A d = 11 u --A "88** -#'
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r--'-# -r-' by ,. - -
-L' ^35 may uw aivi.d l., iii. buii i f;;I :t ri;! "cel
-in . - ..t -;f ' :h::Eerbaard ste-2;r ce"'!;'2 retia =
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EW UI yuq b 4 5 5 5J a y.ss b m e-Fars ---wPw yv.- c#g*ew.gr -w t+-.gg w 4'am- --e,. .,s. gr-mi. *t -w- -w- se----y- w>ev-w=t=-emW--,-gi--'t-r-weer.-w-*7eP. ?-e--+w =>Mewe --
i_ F , fo68%, ca 1 el a r h i ut e :: :f _. ..., ...; . .. . . . . ; .. . ... :
--e-t i n n; " ....,n !: tr =; t ..c ;f f!h : 55 5 ib5 2 1t;;ti; -
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- _. . ..E: .... . .. '.. .... .: ..;...... ..t2 : e 2: :-
2 9e : :- L....,. ; _ ;.. ;f r:.... :.;.: :.
.....sii=> wun mn .; .... ;M r.;;
- ' r : f 5. " ; ;,0.; ,,.. w,. . J-;;;.
- v. + a New or partially spent fuel assemblies with a '
i combination of burnup and initial nominal enrichment in the " accept:ble burnup domain" of r Figure 4.3.1-2 may be stored in the Unit 2 fuel starage pool in a 3-out-of-4 checkerboard storage coa. figuration as shown in Figure 4.3.1-4. , 3 Aew or partially spent- fuel assemblies with a maximum initial enrichment of 5.0 weight percent U-235 may be stored in the Unit 2 fuel storage pool , in a 2-out-of-4 checkerboard storage configuration as shown in Figure 4.3.1-4. New or partially spent fuel assemblies with a combination of burnup and initial nominal ; enrichment in the " acceptable burnup domain" of_ t Figure 4.3.1-3 may be stored in the Unit 2 fuel sto. age pool as " low enrichment" fuel assemblies in the 3x3 checkerboard storage configuration as shown in Figure 4.3.1-5. New or partially spent fuel assemblies with initial nominal enrichments less than or equal to 3.20 weight percent U-235 or having a maximum reference fuel assembly K. less than or equal to 1.410 at 68'F may be stored in the Unit 2 fuel storage pool as "high enrichment" fuel assemblies in the 3x3 checkerboard storage configuration as shown in Figure 4.3.1-5. Interfaces between storage configurations in the < Unit 2 fuel storage pool shall be in compliance with Figures 4.3.1-6. 4.3.1-7, 4.3.1-8, and 4.3.1-9. "A" assemblies are new or partially spent . fuel assemblies with a combination of burnup and. , I
+
--r~.a..,~.p.r.,...,.y,
-, ,+ ,,,,,wr,cy-.y.~ y.., ,%.w,, , -r.n.,,, ..4,,<.,e. -
....,..~,.--.m.me-.,%,,e, - . - . . . . . . - . . . . ~ . . _ -----.,w-w,- .- ..,
V i yn ' cgrfinued I ( 100 initial nominal enrichment in the " acceptable burnup domain" of Figure 3.7.18-2. "B" assemblies are new or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain
- of Figure 4.3.1-2. "C' assemblies are assemblies with initial enrichments up to a maximum of 5.0 weight percent U-235. "L' asse.nblies are new or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 4.3.1-3. "H" assemblies i are new or partially spent fuel assemblies with initial nominal enrichments less than or equal to 3.20 weight percent U-235 or having a maximum reference fuel assembly K. less than or equal to 3 1.410 at 68'F.
f d :rin:1 l0.0 in:n :: t r +a :::t:r pfte in th; l
/. 'J-'t I- high d::;it; '.;; ster.;; . eek;; ;d
'tl A nominal 10.58-inch center to center pitch in the north-south direction and a nominal 10.4-inch l
center to center pitch in the east-west direction I in the Unit 2 high density-fuel storage racks. _ { l
Design features i 4.0 4.0 DESIGN FEATURES 4.3' Fuel Storage (continued) 4.3.2 Drainaoe l The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 194 foot-1 1/2 inch. 4.3.3 Canacity f q 7,5 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than fuel ' assemblies in the Unit I storage pool and no more than 2098 fuel assemblies in the Unit 2 storage pool. i f Vogtle Units 1 and 1! 4.0-3b Amendment No. (Unit 1) Amendment No. (Unit 2)
9 fb. ,
/ ~~N %,_...__'~~~
/ - - . ~ . , Design features I 4.0 N~ % ~~~~ %
l l-l l ll1l l! ll l1l l ll ll llll llll , Ill }lll lIll llll' llll lll l l l f Ill llll llll llll lll llll " II; lill lll ll Il iIil lill ilil lil ll Illi Illi 250oo j u l l l 20000 / 3- /
@ /
a , g 15000 ACCEPTABLE /
/
} !
' 10000 !
.)
/
e / -
/ l UNACCEPTABLE f
/ I 5000
/
)
f 0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 ,
. __ initial U.235 Enrichment (nominal w/o) !
Figure 4.3.1-1 Vogtle Unit 1 Burnup Credit Requirements for ' 3-out-of-4 Storage -
~
.; z - . -- . -
Vogtle Units 1-and 2 4.0-4 Amendment No. (Unit 1) Amendment No. (Unit 2)
Design Features 4.0 Z ZZ Z ZZZZ Z Z Z Z Z ZZZ ZZXZ l 3 out of 4 Checkerboard Storage ((4nels l a n d 2-Z _ Z Z Z Z Z . E Z 2 out of-4 Checkerboard Storage (u nil 2) Empty Storage Cell Fuel Assembly in Storage Cell Figure 4.3.1-4 Vogtle Units 1 and 2 Empty Cell Checkerboard Storage Configurations Vogtle Units 1 and 2 4.0-7 Amendment No. (Unit 1)
-Amenament No. (Unit 2)
l
\
l Design Features 4.0 i l A A A A A A
%tes
! A A A A A A .s . Ali ceu Enrichment Interface B " 3 0"' Of 4 h A Enrichment Empty = Empty Cell Empt) B Empty I A A A B B B A A A Empty B Empty i A A A l Boundary Between All Cell Storage and 3 out of-4 Storage [/24dr /a.4 A A A A A A Notes A A A A A A A s AU Cell
, Enrichment interface N A A A A A A B " 3' "' f 4 Enrichment C = 2.Out.Of-4
- - - - ~
Empty B Empty I A A . A Enrichment Empty = Empty Cell C Empiy B A A A Empty C Empty A A A i Boundary Between All Cell Storage and 2 out-of-4 Storage (%,12) Note:
- 1. A row of empty cells can he used at the interface to separate the configurations.
- 2. It is acceptable to replace an asyembly with an empty cell.
i Figure 4.3.1-6 Vogtle Units 1 and 2 Interface Requirements (All Cell to Checkerboard Storage) Vogtle Units 1 and 2 4.0-9 Amendment No. (Unit 1) Amendment No. (Unit 2)
Design Features 4.0 _m B Empi) B Empi) B Empi) Note: 11 B 11 B B B a 3.out. ora Endchment Interface e = 2.out ora N B mory B Empiy B tmpiy
"- ~ -
Enrichment Empty = Empty Cell Empiy C Empey l B B B C reper C Empty B tmpty Empty C Empiy ; B B B I Boundary Between 2 out of-4 Storage and 3-out of-4 Storage Empiy B Empiy B B B Note B B B B tmpir B a = 3.out.or : Enrichment Interface c m 2.out.ou
\ Empiy B tmper B B B
" ~ -
~ Enrichment Empty = Empty Cell C Empiy C' empiy B cmpir Empiy C impiy B B B C Empiy C Empiy B Empty i
e Boundary Between 2 out-of-4 Storage and 3-out of-4 Storage Note:
- 1. A row of empty cells can be used at the interface to separate the configurations.
- 2. It is acceptable to replace an assembly with an empty cell.
Figure 4.3.1-7 Vogtle Unit /4-4r.d 2 Interface Requirements (Checkerboard Storage Interface) Vogtle Units 1 and 2 4.0-10 Amendment No. (Unit 1) Amendment No. (Unit 2)
Fuel Storage Pool Boron Concentration B 3.7.17 B 3.7 PLANT SYSTEMS B 3.7.17 Fuel Storage Pool Boron Concentration BASES
- lll 16 BACKGROUND Fuel assemblies are stored in high density racks. The -
Unit I spent fuel storage racks contain storage locations for498-fuel assemblies, and the Unit 2 spent fuel storage racks contain storage locations for 2098 fuel assemblies. rke und I re.cVs ute Westinghouse 17x17 fuel assemblies with initial enrichments goralasa negron of up to and including 5.0 weight percent U-235 can be stored in any location in the Unit 1 or Unit 2 fuel storage absorber in a NuX pool provided the fuel burnup-enrichment combinations are within the limits that are specified in Figures 3.7.18-1 irap dr.r/jn , Tge (Unit 1) or 3.7.18-2 (Unit 2) of the Technical U"s't 2. re.c kt con aln Specifications. Fuel assemblies that do not meet the burnup-enrichment cambination of Figures 3.7.18-1 or borMItX bowever no 3.7.18-2 may be stored in the storage pools of Units 1 or 2 in accordance with checkert; pard storage configurations credsYs./ s fakte for described in Figures 4.3.1-7through 4.3.1-9. The gorag(X. acceptable fuel assembly storage configurations are based on the Westinghouse Spent Fuel Rack Criticality Methodology, described in WCAP-14416-NP-A, Rev. 1, (Reference 4). This methodology includes computer code benchmarking, spent fuel rack criticality calculations methodology, reactivity equivM encing methodology, accident methodology, and soluble boron credit methodology. The Westinghouse Spent Fuel Rack Criticality Methodology ensures that the multiplication factor, K ,,, of the fuel and spent fuel storage racks is less than or equal to 0.95 as recommended by ANSI 57.2-1983 (Reference 3) and NRC guidance (References 1, 2 and 6). The codes, methods, and techniques contained in the methodology are used to satisfy this criterion on K.,,. The methodology of the NITAWL-II, XSDRNPM-5, and KENO-Va codes is used to establish the bias and bias uncertainty, PHOENIX-P, a nuclear design code used primarily for core reactor physics calculations is used to simulate spent fuel storage rack geometries. (continued) Vogtle Units 1 and 2 B 3.7-92 Revision No. j l
Fuel Storage Pool Boron Concentration B 3.7.17 BASES BACKGROUND Reference 4 describes how credit for fuel storage pool (continued) soluble boron is used under normal storage configuration conditions. The storage configuration is defined using K.,, calculations to ensure that the K will be less than 1.0 withnosolubleboronundernormal,,storageconditions including tolerances and uncertainties. Soluble boron credit is than used to maintain K.,,J ess than or equal to - 600 0.95. The Unit 1 'acol requires 4Wppm and the Unit 2 pool requires 500 ppe in .1aintain K.,, less than or equal to 0.95 for all allowed nm nations of storage configurations, enrichments, and wenups. The analyses assumed 19.9% of the boron atoms have atomic weight 10 (8-10). The effects of B-10 depletion on the boron concentration for maintaining K.,, :s; 0.95 are negligible. The treatment of reactivity equivalenet.1g uncertainties, as well as the calculation of postulated accidents crediting soluble boron is described in WCAP-14416-NP-A, Rev. 1. This methodology was used to evaluate the storage of fuel with initial enrichmer.ts up to and including 5.0 weight . percent U-235 in the Vogtle fuel storage pools. The resulting enrichment, and burnup limits for the Unit I and Unit 2 pools, respectively, are shown in Figures 3.7.18-1 and 3.7.18-2. Checkerboard storage configurations are defined to allow storage of fuel that is not within the acceptable burnup domain of Figures 3.7.18-1 and 3.7.18-2. These storage requirements are shown in Figures 4.3.1,Y2 through 4.3.1-9. A boron concentration of 2000 ppm assures that no credible dilution event will result in a K.,, of
> 0.95.
APPLICABLE Most fuel storage cool accident conditions will not result SAFETY ANALYSES in an increase in K Examples of such accidents are the drop of a fuel assem.,,.bly on top of a rack, and the drop of a fuel assembly between rack modules, or between rack modules and the pool wall. I From a criticality standpoint, a dropped assembly accident occurs when a fuel assembly in its most reactive condition is dropped onto the storage racks. The rack structure from a criticality standpoint is not excessively deformed. Previous accident analysis with unborated water showed that the dropped assembly which comes to rest horizontally on top of the rack has sufficient water separating it from the (continued) Vogtle Units 1 and 2 S 3.7-93 Revision No.
.. Fuel Storage Pool 1 Boron Concentration-The holowMeresse So'r is bounde-in Ygc},y,Yy tlaeje 4e decrease in fra.j,erature B 3.7.17 by the mhelscemeni af a. fueI satsem Jly l>ekten the ruc k BASES . 4 nd peel we.II.r r.,r He u .'I / rac ks. --
3 p
-APPLICABLE active fuel height of stored assemblies to preclude SAFETY ANAL.YSES. neutronic interaction.. For the berated water condition, the (continued) interaction is even less since the water contains boron, an additional thermal. neutron absorber.
t-However, three accidents can be postulated for each storage configuration which could-increase reactivity beyond the c analyzed condition. The first postulated accident would be ' a' change in pool temperature to outside the range of temperatures assumed in the criticality analyses (50*F to-185'F). The second accident would be dropping a fuel assembly into an already loaded cell. The third would be
.the misloading of a fuel assembly into a cell for which the !
restrictions on location, enrichment, or burnup are not satisfied. - for ne w/t 2 'ra.c.ks I'r flar br Im)" An increase in the temperat re the water passing through rack, suc A u /Ae the-stored fuel assemblies auses a 4ecrease in water f M l re ' density which = ld__r :11; esuftsih an addition of - negative reactlvityf Howev r sihee'Boraflex is not considered to be-present nd the fuel storage pool water has a high concentration of boron, a density decrease causes a positive reactivity addition. The reactivity effects of a temperature range from 32'F to 240*F were evaluat'ed. The l increase in reactivity due to the increase bounded by the misload accident, forue md, z reincier temperature
,a is)
A Fe rl4 a.c.cdent wasFor the accident of dropping a fuel assembly into an already eu latcJ f,c the loaded cell, the-upward axial leakage of that call will be q*.f , 4,j 4. I, will . be insignificant. reduced,1.ns however, is becausethe overall the totaleffect axial on the rack reactivity ra c ks c ada',#88 f leakage in both the upward and downward directions-for the O ral. Tkt fourH entire fuel array-is worth about 0.003 Ak. -Thus, minimizing a,ce.sdent Wo* O ' the upward-only leakage of just a single cell will not cause any significant increase in reactivity. Furthermore, the-4/ ace,nenf of et neutronic coupling between the dropped assembly and the-fuel etsemd, y bb'en alreadynozzle assembly loaded assembly structure which will beseparate would low duethe toactive several inches of Se rack adpot fuel r ions. Therefore, this accident would be bounded by g the mi]s oad accident.
- la'ndfinI - acdent The fuel assembly misloading. accident involves placement of-a fuel; assembly in a location for which it-does_not meet the f,,. Me &III racQS equirements for-enrichment or burnup, including the placement of an assembly in a location that is required-to be left empty. -The result of the misloading is to add positive reactivity, increasing K.,, toward 0.95 The (continued)
Vogtle Units 1 and 2 - B 3.7-94 Revis1on No. i
Fuel Storage Pool Boron Concentration B 3.7.17 BASES (continued) t'C 0 - APPLICABLE- maximumrequiredadditional-borontokompensateforthis SAFETY ANALYSES event is 1250 ppm for Unit 2, and 4Me ppm for Unit I which (continued) is well below the limit of 2000 ppm. The concentration of dissolved boron in the fuel storage pool satisfies Criterion 2 of-the NRC Policy Statment. 1 LCO The fuel storage pool boron concentration is required to be
-1 2000 ppa. The specified concentration of dissnived boron in the fuel storage pool preserves the assumptions used in the analyses of the potential criticality accident scenarios as described in reference 5. The amount of soluble boron required to offset each of the above postulated accidents was evaluated for all of the proposed storage configurations. That evaluation established the amount of soluble boron necessary to ensure that K.,, will be maintained less than or equal to 0.95 should pool temperature exceed the assumed range or a fuel assembly misload occur. The amount of soluble boron necessary to g mitiaate these events was determined to be 1250 ppm for Unit 2 and'4He ppm for Unit 1. The specified minimum boron concentration of 2000 ppa assures that the concentration will remain above these values. In addition, the boron concentration is consistent with the baron dilution evaluationthatdemonstratedthatanycredibledilution/00 event could be terminated prior to reaching the boron concentration for a K,,, of > 0.95. These values are-459 ppm for Unit I and 500 ppm for Unit 2.
APPLICABILITY This LCO applies whenever fuel assemblies are stored in the spent fuel storage pool. ACTIONS A.1. A.2.1. and A,2.2 The Required Actions are modified by a Note indicating that LC0 3.0.3 does not apply. When the concentration of boron in the fuel storage pool is less than required, immediate action must be taken to preclude the occurrence of an accident or to mitigate the-consequences of an accident in progress. This is most (continued) Vogtle Units 1 and 2 B 3.7-95 Revision No.
Fuel Assembly Storage in the Fuel Storage Pool B 3.7.18 8 3.7 PLANT SYSTEMS B 3.7.18 Fuel' Assembly Storage in the Fuel Storage _ Pool BASES 14 76 BACKGROUND T$eUnitIspenthuelstoragerackscontainstorage i locations for-MPfuel assemblies, and the Unit 2 spent fuel storage racks contain storage locations for 2098 fuel assemblies. I Westinghouse 17X17 fuel assemblies with an enrichment of up to and including 5.0 weight percent U-235 can be stored in the acceptable storage configurations that are specified in Figures 3.7.18-1 (Unit 1), 3.7.18-2 (Unit 2), and 4.3.1 r(2. through 4.3.1-9. The acceptable fuel assembly storage locations are based on the Westinghouse Spent Fuel Rack Criticality Methodology, described in WCAP-14416-NP-A, Rev. 1 (reference 1). Additional background discussion can be found in 8 3.7.17. l Westinghouse 17x1 fuel assemblies with nominal enrichments no w/o'"U may be stored in all storage calfreater than locations of the Unit 1 pool. Fuel assemblies with initial nominal enrichment greater than , 8 w/o "U must gp minimum burnup requirement as show in Figure
% n3 a k of sw I.41/ at cold Westinghouse 17x17 fuel assemblies with nominal enrichments i no greater than . w/o'"U say be stored in a 3-out-of-4 reae.fre core checkerboard arrangement with empty cells in the Unit I condit0nr may pool,, 5::1 ::: s tie: with 4-iti:1 ne m :! e-H :F r-t 4[r o f e cfore J y==ter the 2. 05 a/:'"U ;;;t--c:ti:fy : mini :: bur;;p ,,
_ req &:::nt es sh:wn in .Tur; 4.3.bl. There a.re no minimuo4 Ih all cs}f2 *f y,m ypp;cepen fr (,, fys condi ura.h'of n. the 4,'f I few / Westinghouse 17x17 fuel assemblies with nominal enrichments dorage m c h* no greater that 5.0 w/o*"U may be stored in a 2-out-of-4 checkerboard arrangement with empty cells in the Unit ! :r Unit 2 pool. There are no minimum burnup requirements for this configuration. Westinghouse 17x17 fuel assemblies with nominal enrichments no greater than 1.77 w/o8 "U may be -stored in all storage cell locations of the Unit 2 pool. Fuel assemblies with initial nominal enrichment greater than 1.77 w/o'"U must satisfy a minimum burnup requirement as shown in Figure 3.7.18-2. (continued) Vogtle Units 1 and 2 - B 3.7-97 Revision No.
.. 2
- Fuel Assembly Storage _in-the fuel Storage Pool.
B 3.7.18 l BASES ;
= BACKGROUND: ' Westinghouse 17x17' fuel assemblies'with nominal enrichments ->
-(continued) no greater than 2.40 w/o"'U may- be stored -in a 3-out-of-4 d checkerboard arrangement'with empty; cells-in the Unit 2 pool. Fuel assemblies with initial nominal-enrichment
-greater than 2.40 w/o"'U must satisfy a minimum burnup -
requirement as shown in Figure 4.3.1-2. Westinghouse 17x17.fuelLassemblies may be stored in the Unit 2 pool in a 3x3 array. The center:assembl an initial enrichment _ no greater than 3.20 w/o"y "U. must have Alternatively, the center of the 3x3' array may be loaded with any assembly which meets-a-maximum infinite multiplication factor (K.) value of 1.410 at 68'F. One method of achieving this value of. K. is _by_ the use of IF8As. The:surr.,unding fuel assemi.Hes must have an initial nominal l' enrichment no greater than 1.48_w/o"'O or satisfy a minimum-burnup requirement for. higher initial enrichments as shown in Figure 4.3.1-3. . APPLICABLE -. Most fuel storage pool accident conditions will not result SAFETY ANALYSIS in an increase in K drop of a fuel assem.,,._ bly onExamples top of a rack of such andaccidents the drop are of athe fuel assembly between rack modules or between rack modules and the pool wall. However, accidents can be postulated-for each storage _ configuration which could increase reactivity beyond the analyzed condition. A discussion of these accidents is contained in 8 3.7.17. The' configuration of fuel assemblies in the fuel storage pool satisfies Criterion 2 of the NRC Policy Statement. LCO Ther restrictions on the placement of fuel assemblies within the fuel storage pool ensure the K ,, of the fuel storage pool will always remain ( 0.95, assuming the pool to be:
- _ flooded with borated water.
The combination of initial enrichment and burnup are specified in Figures 3.7.18-1 and.3.7.18-2 for all cell storage in the Unit I and Unit 2 pools, respectively. Other
- acceptable enrichment _burnup and checkerboard combinations
- ~ aredescribedinFigures4.3.1-fthrough4.3.1-9.
2 (continued) g Vogtie. Units'l'and 2 8 3.7-98 Revision No. s n.,y - e- -nw,w,,mn.We ..,nw , , ,w,--w,-,,- - , , ,w,,---..m.wn-- 1-wn- m++ , -, , , ,v-
l l Fuel Assemoly Storage in the fuel Storage Pool , 8 3.7.18 i BASES (continued) APPLICABILITY ~ This LCO applies whenever any fuel assembly is stored in the fuel storage pool. ACTIONS L.1 Required Action A.1 is modified by a Note indicating that LCO 3.0.3 does not apply. When the configuration of fuel assemblies stored in the fuel storage pool is not in accordance with the acceptable , combination of initial enrichment, burnup, and storage configurations, the immediate action is to initiate action to make the necessary fuel assembly movement (s) to bring the configuration into compliance with Figures 3.7.18-1 (Unit 1), 3.7.18-2 (Unit 2), or Specification 4.3.1.1. (unM) 4,3, s.L( N f 21 If unable to move irradiated fuel assemblies while in MODE 5 or 6 LCO 3.0.3 would not be applicable. If unable to move irradiated fuel assemblies while in MODE 1, 2, 3, or 4, the action is independent of reactor operation. Therefore inability to move fuel assemblies is not sufficient reason to require a reactor shutdown. SURVEILLANCE SR 3.7.18.1 REQUIR Z NTS This SR verifies by administrative means that the initial enrichment and burnup of the fuel assembly is within the acceptable burnup domain of Figures 3.7.18-1 (Unit 1) or 3.7.18-2 (Unit 2). For fuel assemblies in the unacceptable range of Figures 3.7.18-1 and 3.7.18-2, performance of this SR will also ensure compliance with Specification 4.3.1.1.(unitI) Fuel assembly movement will be in accordance with preapproved plans that are consistent with the specified fuel enrichment, burnup, and storage configurations. These plans are administratively verified prior to fuel movement. Each assembly is verified by-visual inspection to be in accordance with the preapproved plan prior to storage in the fuel storage pool. Storage commences following unlatching of the fuel assembly in the fuel storage pool. (continued) Vogtle Units I and 2 8 3.7-99 Revision No.
s A REVISED PAGES (typed) i
t, , i l TA8LE OF CONTENTS -(continued) 1 ' LIST OF TABLES. 1 .l.1-1 MODES . . . . ... . ._._ . .=. . . . . ._. . . . . 1.1-7 .3.3.1 Reactor Trip System Instrumentation- .. . . . . . . . . 3.3-14 ~ 3.3.2-1 Engineered Safety Feature Actuation System Instrumentation . .- . . . . . . . . . . . . . . . 3.3-30 3.3.3-1 Post Accident Monitoring Instrumentation . . ._._. . . . 3.3-42 3.3.4-l_ _ Remote Shutdown System Instrumentation and Controls . 3.3-45 3.3.6-1 Containment Ventilation Isolation Instrumentation . . 3.3-53 3.3.7-1^ CREFS Actuation Instrumentation . . . . , . . . . . . 3.3-59 3.7.1-1 Maximum Allowable Power Range Neutron Flux Hi ) Trip Setpoint with Inoperable Main Steam Safe , ves . 3.7-3 3.7.1-2 Main Steam Safety Valve 1.ift Settings . . . . . . . . 3.7-4 3.8.4-1 Discharge Test Surveillance Requirements . . . . . . . 3.8-29 3.8.6-1 Battery Cell Parameters Requirements . . . . . . . . . 3.8-35 5.5.9-1 Minimum Number-of Steam Generators to Be Inspected During Inservice Inspection . . . . . . 5.0-18 5.5.9-2 Steam Generator Tube Inspection . . . . . . . . . . . 5.0-19 LIST-0F FIGURES 2.1.1-1 Reactor Core Safety Limits . . . . . . . . . . . . . . 2.0-2 5.4.16-1 Reactor Coolant Dose Equivalent I-131 Reactor Coolant Specific Activity Limit Versus Percent of Rated Thermal Power with the Reactor Coolant Specific Activity > 1 Li/ gram Dose Equivalent I-131 . . . 3.4-44 3.7.18-11 Vogtle Unit 1 Burnup Credit Requirements for All Cell Storage . . . . . . . . . . . . . . . . . 3.7-42 3.7.18-2 Vogtle Unit 2 Burnup Credit Requirements for All Cell Storage . . . . . . . . . . . . . . . . . .-3.7-43 14.3.1 . Deleted . . . . . . . . . . . . . . . . . . . . . . . , 4.0-4 l 4.3.1 Vogtle Unit 2 Burnup Credit Requirements for 3-out-of-4 Storage . . . . . . . . . . . . . . . . 4.0-5 'Vogtle Units 1 and 2 viii Amendment No. (Unit 1) Amendment No. (Unit 2)
. TABLE OF CONTENTS (continued)-
4.3.1-3 Vogtle Unit 2:Burnup Credit Requirements for 3x3 Storage . . . . . ... . . . . . . . ... . . . . . 4.0-6 4.3.1-4 Vogtle Units 1 and 2 Empty Cell Checkarboard Storage Configurations . . . . . . . . . . . . . . 4.0-7 4.3.1-5 Vogtle Unit 2 3x3 Checkerboard Storage Configuration . 4.0-8 4.3.1-6. Vogtle Units'I and 2 Interface Requirements (All Cell to Checkerboard Storage) . . . . . . . . .- 4.0-9 4.3.1-7 -Vogtle Unit 2 Interface Requirements l (Checkerboard Storage Interface) . . . . . . . . . 4.0 L4.3.1-8 Vogtle Unit 2 Interface Requirements (3x3 Checkerboard to All Cell Storage) . . . . . . 4.0-11
.4.3.1-9 Vogtle Unit 2: Interface Requirements (3x3 to Empty' Cell Checkerboard Storage) . . . . .-. 4.0-12 Vogtle Units 1 and 2 ix Amendment.No. (Unit 1)
Amendment No. (Unit 2)
1 Fuel Assembly Storage in the' Fuel Storage Pool 3.7.18 3.7 PLANT SYSTEMS 3.7.18 Fuel Assembly. Storage in the Fuel Storage Pool LCO 3.7.18 The combination of initial enrichment burnup and configuration of fuel assemblies stored in the fuel storage-pool shall be within the Acceptable Burnup Domain of Figures 3.7.18-1 (Unit 1), 3.7.18-2 (Unit 2), or in accordance with Specification 4.3.1.1 (Unit 1) or 4.3.1.2 (Unit 2). l 4 APPLICABILITY: Whenever any fuel assembly is stored in-the fuel storage pool. [CTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 --------NOTE---------
. LCO not met. LC0 3.0.3 is not applicable.
Initiate action to Immediately move the noncomplying fuel assembly to an acceptable store ge location. Vogtle Units 1 and 2 3.7-40 Amendment No. (Unit 1) Amendment No. (Unit 2) ___--_ _ _-- j
Fuel- Assembly Storage in the Fuel Storage Pool-
-3.7.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY' SR-.3.7.18.1- Verify by a combination of visual Prior to inspection and administrative means that storing the the initial enrichment, burnup, and storage fuel assembly location of the fuel assembly is in in the fuel accordance with Figures 3.7.18-1 (Unit 1), storage pool 3.7.18-2 (Unit 2), or Specification 4.3.1.1 location.
(Unit 1) or 4.3.1.2 (Unit 2). 4 Vogtle Units 1 and 2 3.7-41 Amendment No. (Unit 1) Amendment No. (Unit 2)
.. .. . _ . . . . . . _ _ _ . _ . . . __ ~ . - . . . . . .
Fuel- Assembly Storage 'n the Fuel. Storage Pool i 3.7.18 15000 E o ACCEPTABLE f10000 O' , e
/
/
5' k: /
/
m ,/ t m 5000 -
'/
k / J 2
/
l
! UNACCEPTABLE --
I 0 -l 3.0 .3.5 4.0 4.5 5.0 Initial U-235 Enrichment (nominal w/o) 1 k Figure 3.7.18-1 Vogtle Unit 1 Burnup Credit Requirements for All Cell Storage Vogtle Units 1 and 2 3.7-42 -Amendment No. (Unit 1) Amendment No. (Unit 2)
1 De' sign Features' 4.0 l; T _HISPAGE-APPLICADLE(TOUNIT1ONLY. 4.0 DESIGN. FEATURES (continued) 4.3- Fuel' Storage 4.3.1 Criticality (Unit 1)- 4.3.1.1- The spent fuel. storage racks are designed and shall be l m:intained with: ,
- a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;
- b. K ,, < 1.0 when fully' flooded with unborated water which includes an allowance for uncertaintiss as described in Section 4.3 of the FSAR.
- c. K.,, s 0.95 ~when fully flooded with water borated to 600 ppm, which includes an allowance for uncertainties as described in Section 4.3 of the FSAR;
- d. .New or partially spent fuel-assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 3.7.18-1 or having a maximum reference fuel assembly Km less than or equal to 1.431 at 68'F may be allowed unrestricted storage in the Unit 1 fuel storage pool,
- e. New or partially spent fuel assemblies with a maximum initial enrichment of 5.0 weight percent U-235 may be stored in the Unit 1 fuel storage pool
'in a 3-out-of-4 checkerboard storage configuration as shown in Figure 4.3.1-4.
I Interfaces between storage configurations in-the Unit I fuel storage pool shall be in compliance with Figure 4.3.1-6. "A" assemblies are new or l partially spent fuel assemblies with a combination of burnup and initial nominal- enrichment in the
" acceptable burnup domain" of Figure 3.7.18-1, or which have a maximum reference fuel assembly Kn less than or equal to 1.431 at 68 F. "B" assemblies.are assemblies with initial enrichments up to a maximum of 5.0 weight percent U-235. ,
(con +.inued) Vogtle Units 1 and 2 4.0-2 Amendment No. (Unit 1) Amendment No. (Unit 2)
' Des'ign Features' 4.0 4.0 DESIGN-FEATURES 4.3- Fuel Storage- (continued)-
- f. A nominal 10.25 inch center to center pitch in the l-
-Unit;l high density fuel storage racks.
(Unit 2) 4.3.1.2 The spent fuel storage . racks are designed and shall be : l maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of 5.0. weight percent;
- b. K.,, < l.0 when fully flooded with unborated water which includes an allowance for uncertainties as described in Section 4.3 of the FSAR.
- c. K.,, s 0.95 when fully flooded with water borated to 500 ppm, which includes an allowance for uncertainties as described in Section 4.3 of the FSAR;
- d. New or partially spent fuel assemblies with a combination of burnup-and initial . nominal enrichment in the " acceptable burnup domain" of Figure 3.7.18-2 may be allowed unrestricted storage l in the Unit 2 fuel storage pool.
I
- e. New or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 4.3.1-2 may be stored in the Unit 2 fuel storage pool in a 3-out-of-4 checkerboard storage configuration as shown in Figure 4.3.1-4.
New or partially spent fuel assemblies with a maximum initial enrichment of 5.0 weight percent U-235 may be stored in the Unit 2 fuel storage pool in a 2-out-of-4 checkerboard storage configuration as shown in Figure 4.3.1-4. New or partially spent fuel assemblies with a combination of burnup and initial nominal
. enrichment in the " acceptable burnup domain" of Figure 4.3.1-3 may be stored in the Unit 2 fuel (continued)
- Vogtle Units 1 and 2' 4.0 1 Amendment No. (Unit 1)
Amendment No. (Unit 2)
--= - . . .. - - - - - -
Design Features ; 4.0 4~.0 -DESIGN FEATUPES - 4.3 Fuel Storage- (continued)- ' storage pool as " low enrichment" fuel assemblies -in the 3x3 checkerboard storage configuration as shown in Figure 4.3.1-5. New or partially spent fuel assemblies with initial nominal enrichments less than or equal to 3.20 weight percent U-235 or having a maximum reference fuel assembly K. less r than or equal- to 1.410 at 68 F may be stored in the Unit 2 fuel storage poolLas "high enrichment" fuel-assemblies-in the 3x3 checkerboard' storage configuration as shown in: Figure 4.3.1-5. Interfaces between storage configurations in the Unit 2 fuel storage pool shall be in compliance with Figures 4.3.1-6, 4.3.1-7, 4.3.1-8, and 4.3.1-9. ."A" assemblies are new or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 3.7.18-2. "B" assemblies are new or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 4.3.1-2. "C" assemblies are assemblies with initial enrichments'up to a maximu... J 5.0 weight percent U-235. "L" assemblies are new or partially spent fuel assemblies with a combination of burnup and initial nominal enrichment in the " acceptable burnup domain" of Figure 4.3.1-3. "H" assemblies
-are new or partially spent fuel assemblies with initial nominal enrichments less than or equal to 3.20 weight percent U-235 or having a maximum reference fuel assembly K.-less than or equal to 1 410 at 68 F.
- f. A nominal :0.58-inch crater to center pitch in the l north-south direction and a nominal 10.4-inch center to center piten in the east-west direction in the Unit 2 high density fuel storage racks, t
+ (continued)
.Vogtle Units l'and 2 4.0-3a Amendment No. (Unit 1)
Amendment No. (Unit 2) s,- ~ . - ,
5 l
. Design Features 4.0 4.0 DESIGN FEATURES ;
14.3.FuilStorage-(continued) 4.3.1.3 .The new fuel storage racks are designed and- shall- be
. j maintained with:
- a. : Fuel _ assemblies having-a maximum U-235 enrichment of 5.05 weight percent;.
b~. k , s 0.95 if fully flooded with unborated water, wh,ichincludesanallowanceforuncertaintiesas described in Section 4.3'of the FSAR; , c, k,,, s 0.98 if moderated by aqueous foam, which includes an allowance for-uncertainties as described in Section 4.3 of the FSAR; and
- d. A nominal 21-inch-center to' center distance between fuel assemblies placed .in the storage racks.
4.3.2 Drainaae - The spent fuel storage pool is designed and shall be maintained to prevent: inadvertent draining of the pool below elevation 194 foot-1 1/2 inch. 4.3.3 Caoacity , The spent fuel-storage pool is designed and shall be maintained with a stbrage capacity limited to no more than 1476 fuel l assemblies in the. Unit I storage pool and no more than 2098 fuel assemblies in the Unit 2 storage pool. LVogtle Units 1 and 2 -4.0-3b Amendment'No. (Unit 1) Amendment No. (Unit 2)
Design Features-4.0 (This figure _ has been deleted.) Figure 4.3.1-1 Vogtle Unit 1 Burnup Credit Requirements for 3-out-of-4 Storage Vogtle Units 1 and 2 4.0-4 Amendment No. (Unit 1)- Amendment No. (Unit 2)
. - . - - . - . - . . _ . _ _ - . - . - - . _ _ - _ - - - _ =
Design Features
;.0 d
_2 . Z Z Z72 Z Z Z Z Z E Z Z 3 out-of 4 Checkerboard Storage (Units I and 2) Z Z T ,Z E E E Z 2-out-of-4 Checkerboard Storage (Unit 2) i Empty Storage Cell Fuel Assembly in Storage Cell l Figure 4.3.1-4 Vogtle Units 1 and 2 Empty Cell Checkerboard a' Storage Configurations Vogtle Units I and 2 4.0-7 Amendment No. (Unit 1) Amendment No. (Unit 2)
l l Design Features 4.0 i l A A A. A A A Note: A A A 'A A A A = An Ceu Interface Enrichment A A A A A a = 3.out or.4
\ "- -
Enrichment Empty = Empty Ceu Empty B Empty l A A A B B B' A A A Empty B Empey A A A i
~
e Boundary Between All Cell Storage and 3-out-of-4 Storage (Units 1 and 2) A A A A A A i Note:
- A A A A A A Am AH CeH I Enrichament Interface am 3.o tm N A A A A A A Enrichment C = 2.Out.Of-4 Empty B Empty ; A A A Enrichawat Empty = Empty CeH C Empty B A A A Empiy C Empty A A A i
s - Boundary Between All Cell Storage and 2-out-of-4 Storage (Unit 2) Note:
- 1. A row of empty cells can be used at the interface to separate the configurations.
- 2. It is acceptable to replace an assembly with an empty cell.
Figure 4.3.1-6 Vogtle Units 1 and 2 Interface Requirements (All Cell to Checkerboard Storage) Vogtle Units 1 and 2 4.0-9 Amendment No. (Unit 1) Amenament No. (Unit 2)
Design Features 4.0 B tmpi> B tmpiy B tmpty Note: B B B B B B a = 3 out.or-4 Enrichment B tmpiy .B tmpiy B tmpiy c = 2.out.ow
, Enrichment Empty = Empty Cell Empty C Empty B B B u
C Emper C tm,iy B tmper empty C Empty B B B l a Boundary Between 2-out-of-4 Storage and 3 out of-4 Storage Empty B tmpiy B B B Note: B B B B tapty B a - 3. oui.or.4 Enrichneent Empiy B tmpey B B B c = 2.ous.or.4 Enrichment Empty = Empty Cell C Empir CI Empty B tmpiy Empty C Empiy B B B C Emper C Empir B tmpty i a Boundary Between 2-out-of-4 Storage and 3-out of-4 Storage Note:
- 1. A row of empty cells can be used at the interface to separate the configurations.
- 2. It is acceptable to replace an assembly with an empty cell.
~ Figure 4.3.1-7 Vogtle Unit 2 Interface Requirements (Checkerboard Storege Interface) Vogtle Units 1 and 2 4.0-10 Amendment No. (Unit 1) Amendment No. (Unit 2)
Fuel Storage Pool Boron Concentration-B 3.7.17 B 3.7 ' PLANT SYSTEMS B 3.7.17 Fuel Storage Pool Boron Concentration-BASES BACKGROUND Fuel assemblies are stored in high density racks. The
- Unit'l spent fuel storage racks contain storage locations for 1476- fuel assemblies, and the Unit 2 spent fuel storage l racks contain storage locations for 2098 fuel assemblies.
The-Unit I racks use-boral as a neutron absorber in a flux trap design. The Unit 2 racks contain Boraflex, however, no credit is taken for Boraflex. Westinghouse 17x17 fuel assemblies with initial enrichments of up to and including 5.0 weight percent U-235 can be stored in any location in the Unit 1 or Unit 2 fuel storage pool provided the fuel burnup-enrichment-combinations are within the limits that , are specified-in Figures 3.7.18-1 (Unit-1) or 3.7.18-2 (Unit 2) of the Technical Specifications'. Fuel assemblies that do not meet the burnup-enrichment combination of Figures 3.7.18-1 or 3.7.18-2 may be stored in the storage pools of Units I or 2.in accordance with checkerboard storage configurations described in Figures 4.3.1-2 through l 4.3.1-9. The acceptable fuel assembly storage configurations are based on the Westinghouse Spent Fuel Rack Criticality Methodology, described in WCAP-14416-NP-A, Rev. 1, (Reference 4). This methodology includes computer code benchmarking, spent fuel rack criticality calculations . methodology, reactivity equivalencing methodology.. accident methodology, and soluble boron credit methodology. The Westinghouse Spent Fuel Rack Criticality Methodology ensures that the multi)11 cation factor, K,,,, of the fuel and spent fuel storage raccs is less than or equal to 0.95 as recommended by ANSI 57.2-1983 (Reference 3) and NRC guidance (References 1, 2 and 6). 'The codes, methods, and techniques contained in the methodology are used to satisfy this criterion on K.,,. The metnodology of the NITAWL-II, XSDRNPM-S, and KENO-Va codes is used.to establish the bias and bias uncertainty, PH0ENIX-P, a nuclear design code used primarily for core reactor physics calculations is used to simulate spent fuel storage rack geometries. (continued) Vogtle Units.1 and 2 B 3.7-92 Revision No.
1 Fuel Storage Pool Boron Concentration - B 3.7.17 i BASES -_ BACKGROUNO- Reference 4 describes how credit for fuel storage pool
-(continued) soluble boron-is used under normal storage configuration conditions. ~The storage configuration is defined using K.,,
calculations to ensure that the K will be less than 1.0 with no soluble boron under normal,,storagt conditions including tolerances and uncertainties.- Soluble boron credit is then used to maintain K.,, less than or equal _ to 0.95. The Unit 1 pool requires 600 ppm and the Unit 2 pool l requires 500 ppm to maintain K ,, less than or equal to 0.95 for all allowed combinations of storage configurations, enrichments, and burnups. The analyses assumed 19.9% of the boron atoms have atomic weight 10 (B-10). The effects of B-10 depletion on the boron concentration for maintaining ,- K.,, s 0.95 are negligible. The treatment of reactivity equivalencing uncertainties, as well as the calculation of postulated accidents crediting soluble boron is described .n WCAP-14416-NP-A, Rev. 1. This methodology was used to evaluate the storage of fuel with initial enrichments up to and including 5.0 weight percent U-235 in the Vogtle fuel storage pools. The resulting enrichment, and burnup limits for the Unit 1 and Unit 2 pools, respectively, are shown in Figur i 3.7.18-1 and 3.7.18-2. Checkerboard storage configurath...s are defined to allow storage of fuel that is not within the acceptable burnup domain of Figures 3.7.18-1 and 3.7.18-2. These storage requirements are shown in Figures 4.3.1-2 l through 4.3.1-9. A borop concentration of 2000 ppm assures that no credible dilution event will result in a K.,, of
> 0.95.
APPLICABLE Most fuel storage pool accident conditions will not result SAFETY ANALYSES in an increase in K.,,, Examples of such accidents are the drop of a fuel assembly on top of a rack, and the drop of a fuel assembly between rack modules, or between rack modules and the pool wall. From a criticality standpoint, a dropped assembly accident occurs when a fuel assembly in its most reactive condition is dropped onto the storage racks. The rack structure from a criticality standpoint is not excessively deformed. Previous accident analysis with unborated water showed that the dropped assembly which comes-to rest horizontally on top
- of the rack has sufficient water separating it from the (continued)
Vogtle Units 1 and 2 B 3.7-93 Revision No.
Fuel Storage-Pool Boron Concentration B 3.7.17 BASES APPLICABLE active fuel height of stored assemblies to preclude SAFETY ANALYSES neutronic interaction. For the borated water condition, the-(continued) interaction is even less since the water contains boron, an additional thermal neutron absorber. However, three accidents can be_ postulated for each storage configuration which could increase reactivity beyond the analyzed condition. The first postulated accident would be a change in pool temperature to outside the range of temperatures assumed in the criticality. analyses (50'F to 185'F). The second accident would be dropping a fuel-assembly into an already loaded cell. The third would be the misloading of a fuel assembly into a cell for which the restrictions on location, enrichment, or.burnup are not satisfied. An increase in the tempereture of the water passing through the stored fuel assemblies causes a decrease in water density which results in an addition of negative reactivity for flux trap design racks such as the Unit I racks. However, since Boraflex is not considered to be present for the Unit 2 racks and the fuel storage pool water has a high concentration of boron, a density decrease causes a positive reactivity addition. The reactivity effects of a temperature range from 32 F to 240*F were evaluated. The increase in reactivity due to the increase in temperature is bounded by the misload accident, for the Unit 2 racks. The increase in reactivity due to the decrease in temperature below 50'F is bounded by the misplacement of a fuel assembly between the rack and pool walls for the Unit I racks. For the accident of dropping a fuel assembly into an already loaded cell, the upward axial leakage of that cell will be , reduced, however, the overall effect on the rack reactivity will be insignificant. This is because the total axial leakage in both the upward and downward directions for the entire fuel array is worth about 0.003 Ak. Thus, minimizing the upward-only leakage of just a single cell will not cause any significant increase in reactivity. Furthermore, the . neutronic coupling between the dropped assembly and the already loaded assembly will be low due to several inches of assembly nozzle structure which would separate the active fuel regions. Therefore, this accident would be bounded by the misload accident. (continued) Vogtle Units 1 and 2 8 3.7-94 Revision No. l
fuel Storage Pool Boron Concentration B 3.7.17
- BASES' APPLICABLE- - The fuel assembly misloading ~ accident involves placement of
- SAFETY ANALYSES a fuel assembly in a location for which it does not meet the (continued) requirements for enrichment: or bt rnup, including the -
placement of an-assembly in a location .that is required to be left empty. 'ne result of the misloading is to add positive reac'.tvity, increasing K.,, toward 0.95. A fourth accident was evaluated for the Unit I fuel storage racks-containing boral. The fourth. accident was the misplacement of a fuel assembly between the rack and pool wall. This was the limiting accident for the Unit I racks. The t
- (continued)
Vogtle Units 1 and 2 8 3.7-94a Revision No.
1 Y h- 6 t Fuel Storage PooliBoron Concentration
~
;B 3.7;172 g(
+-
_U . 4
^
- APPLICABLEJ. - '~ ' '
SAFETY ANALYSES
- (continued)f s
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4
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f(This page intentionally left blank.) F a 4
- (continued)-
;LVogtle, Units--1(and 2 B 3.7-94b Revision-No.
k- e g k
.v.. <.U E e , I .-- .m 4 ive, .,,m. ,yw-, w r< - - , , - < e - w - , . ,.,.yt - + , . . - - - - -g- .,
Fuel Storage-Pool Boron Concentration B 3.7.17 BASES - (continued)
- APPLICABLE . maximum required additional boron to compensate for this SAFETY ANALYSES event is 1250 pam for Unit 2, and 800 ppm for Unit 1-which ~l (continued) is well below tie -limit of 2000 ppm.
The concentration of. dissolved boron in the fuel-storage pool satisfies Criterion 2 of the NRC Policy Statment. J. LCO The fuel storage _ pool boron concentration is required to be 1 2000 ppm. The specified concentration of dissolved boron in the fuel storage pool preserves the assumptions used in the analyses of the. potential criticality accident scenarios as described in reference 5.- The amount of soluble boron required to offset each of the above postulated accidents was evaluated for all of the proposed storage configurations. That evaluation establi:hed the amount of soluble boron necessary to ensure that K will be maintained less- than or equal to 0.95 sh$uld pool temperature exceed the assumed range or a fuel assembly misload occur. The amount of soluble boron necessary to mitigate these events was determined to be 1250 ppm for Unit 2 and COO ppm for Unit 1. The specified minimum boron l concentration of 2006 ,;m assures that the concentration will remain-above these v. lues. In addition, the boron concentration is consist? . with the boron dilution
. evaluation that demonstrated that any credible dilution event could be terminated prior to reaching the boron concentration for a K.,, of > 0.95. These values are 600 ppm l for Unit I and 500 ppm for Unit 2. j APPLICABILITY This LCO applies whenever fuel assemblies are stored in the spent fuel storage pool.
ACTIONS A.1. A.2.1~. and A.2.2 The Required Actions are modified by a Note indicating that LC0 3.0.3 does not-apply. When the concentration of boron in the fuel storage pool is less than required, immediate a:. tion must be taken to preclude the-occurrence of an accident or to mitigate the consequences of an accident in progress. This is most (continued) Vogtle Units 1 and 2 B 3.'7-95 Revision No.
; Fuel . Assembly Storage in the Fuel Storage Pool B 3.7.18
- B 3.7': PLANT SYSTEMS-(B 3.7.18 Fuel Assembly Storage in the fuel Storage Pool -
BASES BACKGROUND The Unit I spent fuel storage racks contain storage locations' for 1476 fuel assemblies, and the Unit 2 spent l fuel storage racks contain storage locations for 2098 fuel assemblies. Wettinghouse 17X17 fuel assemblies with an enrichment of 99 to and including 5.C weight percent U-235 can be stored in the acceptable storage configurations that are specified in Figures 3.7.18-1 (Unit 1), 3.7.18-2 (Unit '2)', and 4.3.1-2 l through 4.3.1-9. The acceptable fuel assembly storage locations are based on the Westinghouse Spent Fuel Rack Criticality Methodology, described in WCAP-14416-NP-A, Rev. 1 (reference 1). Additional background discussion can be found in B 3.7.17. Westinghouse 17x17 fuel assemblies with nominal enrichments no greater than 3.50 w/ou may be stored in all storage l cell locations of the Unit 1 pool. Fuel assemblie: with initial nominal enrichment greater than 3.50 w/o'"U must ~ l satisfy a_ minimum burnup requirement as shown in Figure 3.7.18-1. Fuel assemblies having a 14e of 1.431 at cold reactor core conditions may also be stored in all cells of the Unit 1 fuel storage racks. Westinghouse 17x17 fuel assemblies with nominal enrichments no greater-than 5.0 w/ou may be stored in a 3-out-of-4 l checkerboard arrangement with empty cells in the Unit 1 pool. There are no minimum burnup requirements for this configuration. Westinghouse 17x17 fuel assemblies with nominal enrichments no greater that 5.0 w/oU may be stored in a 2-out-of-4 checkerboard arrangement with empty cells in the Unit 2 pool. There are no minimum burnup requirements for this configuration. (cmatinued)- Vogtle Units 1 and.2 B 3.7-97 Revision No. f --
.+y-
fuel Assembly Storage in the fuel Storage Pool B 3.7.18 BASES
)
BACKGROUND Westinghouse 17x17 fuel assemblies with nominal enrichments (continued) no greater than 1,7/ w/o'"U may be stored in all storage cell locations of the Unit 2 pool, fuel assemblies with initial nominal enrichment greater than 1.77 w/o'"U must satisfy a minimum burnup requirement as shown in figure 3.7.18-2. 3
\
6 (continued) Vogtle Units 1 and 2 B 3.7-97a Revision No. I-.. .. .
fuel Assernbly Storage in the fuel Storage Pool B 3.7.18 BASES BACKGROUND (continued) k (This page t.1tentionally left blank.) , (continued) Vogtle-Units 1 and_2 B 3.7-97b Revision No.
I' Fuel Assembly Storage in the fuel Storage Pool , B 3.7.18 t BASES ; BACKGROUND Westinghouse-17x17 fuel assemblies with nominal enrichments (continued) no greater than 2.40 w/o"'u may be stored in a 3-out-of-4 checkerboard arrangement with empty cells in the Unit 2 . pool. Fuel assemblies with initial nominal enrichment r greater than 2.40 w/o"'O must satisfy a minimum burnup requirement as shown in figure 4.3.1-2. . Westinghouse 17x17 fuel assemblies may be stored in the l Unit 2 pool in a 3x3 array. The center assembl must have aninitialenrichmentnogreaterthan3.20w/o'y'U. Alternatively, the center of the.3x3 array may be loaded . with any assenbly which meets a maximum infinite
- multiplication factor (K.) value of 1.410 at 68'F. One method of achieving this value of K. is by the use of IFBAs.
The surrounding fuel assemblies must have an initial nominal enr!chment no greater than 1.48 w/o"'u or satisfy a minimum burnup requirement for higher initial enrichments as shown in Figure 4.3.1-3. , APPLICABLE Most fuel storage pool accident conditions will not result SAFETY ANALYSIS in n increase in K.,,. Examples of such accidents are the drop of a fuel assembly on top of a rack and the drop of a fuel assembly between rack modules or between rack modules and the pool wall. However, accidents can be postulated for each storage configuration which could increase reactivity beyond the analyzed condition. A discussion of these accidents is contained in B 3.7.17. The. configuration of fuel assemblies in the fuel storage pool satisfies Criterion 2 of the NRC Policy Statement. . LCO The restrictions en the placement of fuel assemblies within the fuel storage rsol ensure the K,,, of the fuel storage pool will always remain < 0.95, assuming the pool to be flooded with borated water. The combination of initial enrichment and burnup are specified in Figures 3.7.18-1 and 3.7.18-2 for all cell storage in the Unit I and Unit 2 pools, respectively. Other acceptable enrichment burnup and checkerboard combinations are described in Figures 4.3.1-2 through 4.3.1-9. l (continued) Vogtle Units 1 and 2 B_3.7-98 Revision No.
Fuel Assembly Storege in the fuel Storage Pool B 3.7.18 BASES (continued) APPLICABILITY This LCO applies whenever any fuel assembly is stored in the fuel storage pool. ACTIONS AJ Required Action A.1 is modified by a Note indicating that LC0 3.0.3 does not apply. When the configuration of fuel assemblies stored in the fuel storage pool is not in accordance with the acceptable combination of_ initial enrichment, burnup, and storage configurations, the immediate action is to initiate action to ma(e the necessary fuel assembly movement (s) to bring the configuration into compliance with figures S 7.18-1 (Unit 1), 3.7.18-2 (Unit 2), or Specification 4.3.1.1 (Unit 1) or 4.3.1.2 (Unit 2). If unable to move irradiated fuel assemblies while in MODE 5 or 6. LCO 3.0.3 would not be applicable. If unable to move irradiated fuel assemblies while in MODE 1, 2, 3, or 4, the action is indtperient of retetor operation. Therefore inability to muet fuel r 3emblies is not sufficient reason to require a reactor shutuown. SURVEILLANCE SR 3.7.18.1 REQUIREMENTS This SR verifies by administrative means that the initial enrichment and burnup of the fuel assembly is within the acceptable burnup domain of Figures 3.7.18-1 (Unit 1) or 3.7.18-2 (Unit ?). For fuel assemblies in the unacceptable range of Figures 3.7.18-1 and 3.7.18-2, performance of this SR will also ensure compliance with Specification 4.3.1.1 (Unit 1) or 4.3.1.2 (Unit 2). l Fuel assembly movement will be in accordance with preapproved plans that are consistent with the specified fuel enrichment, burnup, and storage configurations. These plans are administrative 1y verified prior to fuel. movement. Each assembly is verified by visual inspection to be in
-accordance with the preapproved plan prior to storage in the fuel storage pool. Storage commences following unlatching of the fuel assembly in the fuel storage pool.
(continued) Vogtle Units 1 and 2 B 3.7-99 Revision No.
ENCLOSURE 4 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECilNICAL SPECIFICATIONS ADDITIONAllVEL STORAGERACKS FOR UNIT I FUEL STORAGE POOL, ENVIRONMENTAL ASSESSMENT Information Supporting an Environmental Assessment An environmental assessmee i not required for the proposed change t>ecause the requested changes to the license conform to the criteria for " actions eligible for ' categorical exclusion," as specified in 10 CFR 51.22(c)(9). The changes will have no impact on the environment. The proposed changes do not involve a significant hazards consideration as discussed in the preceding section. The proposed changes do not involve a significant change in the types or a significant increase in the amounts of any efliuents that may be released offsite. The Unit I fuel storage pool and the Unit 2 fuel storage pool were initially designed and constructed to the same requirements. The Unit 2 pool was filled with fuel storage racks with 2098 storage locations while the Unit 1 pool was lefl empty except for 2 racks with 288 storage locations. This change reflects the addition of more storage capacity to the Unit 1 pool. The increased number of storage locations in the Unit 1 fuel storage pool remains less than the number of storage locations previously approud by the NRC fbr the identical Unit 2 pool. 41
i ENCLOSURE 5 VOGTLE ELECTRIC GENERATING PLANT i' REQUEST TO REVISE TECHNICAL SPECIFICATIONS ADDITIONAL FUEL STORAGli RACKS FOR UNIT 1 FUEL STORAGE POOL i CRITICALITY ANALYSES 5 P I i k i F I 4 9 b r f f 5
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