ML20135A940

Proposed Tech Specs,Allowing Use of Credit for Soluble Boron in Spent Fuel Pool Criticality Analyses

ML20135A940
Person / Time
Site:	Prairie Island
Issue date:	02/21/1997
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20135A931	List: ML20135A929 ML20135A937 ML20135A940 ML20135A945 ML20135A948
References
NUDOCS 9702280025
Download: ML20135A940 (65)

Text

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?

Exhibit B  !

Prairie Island Nuclear Generating Plant k'

February 21, 1997 Revision to License Amendment Request Dated July 28, 1995  !

Proposed Ghanges Marked Up  ;

On Existing Technical Specification Pages Exhibit B consists of existing and new Technical Specification pages with the original proposed changes and all revisions highlighted on those pages. The existing and new pages affected by this License Amendment Request are listed below:

l EXISTING PAGES NEW PAGES l TS-vi Figure TS.3.8-2 TS xi TS.4.20-1 TS-xiii Figure TS.S.6-3 TS.3.8-4 Figure TS.S.6 4 TS.3.8-5 Figure TS.5.6-5 Figure TS.3.8-1 Figure TS.S.6-6 Table TS.4.1-2B (Page 1 of 2) Figure TS.S.6-7 Table TS.4.1-2B (Page 2 of 2) Figure TS.S 6-8 TS.5.6 1 Figure TS.S.6-9 TS.5.6-3 Figure TS.S.6 10 Figure TS.5.6-1 Figure TS.S.6-11 Figure TS.5.6-2 Figure TS.S.6-12 B.3.8-2 B.3.8-5 B.3.8-3 B.4.20-1 B.3.8-4 97022fH)O25 970221 PDR ADOCK 05000282s PENI p i

)

)

TS-vi REV 122 1/2':/96 TABLE OF CONTENTS (Continued)

TS SECTION TITLE PAGE 4.12 Steam Generator Tube Surveillance TS.4.12-1 A. Steam Generator Sample Selection and TS.4.12-1 Inspection B. Steam Generator Tube Sample Selection TS.4.12-1 and Inspection C. Inspection Frequencies TS.4.12-3 D. Acceptance Criteria TS.4.12-4  !

E. Reports TS.4.12-5 l 4.13 Snubbers TS.4.13-1 4.14 Control Room Air Treatment System Tests TS.4.14-1 4.15 Spent Fuel Pool Special Ventilation System TS.4.15-1 4.16 Deleted  !

4.17 Deleted '

4.18 Reactor Coolant Vent System Paths TS.4.18-1 A. Vent Path Operability TS.4.18-1 B. System Flow Testing . TS.4.18-1 4.19 Auxiliary Building Crane Lifting Devices TS.4.19-1 4120]!]S@htlFUelyP601?St6tageIConfiprhti'6n^y"" "" ,;; "*1Tsj4720j1

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TS-xi REV 122 1/2':/95 IABLE OF CONTENTS (continued)

TS BASES SECTION TITLE PAGE i

4.0 BASES FOR SURVEILLANCE REQUIREMENTS  !

4.1 Operational Safety Review B.4.1-1 4.2 Inservice Inspection and Testing of Pumps B.4.2-1 and Valves Requirements 4.3 Primary Coolant System Pressure Isolation B.4.3 1 Valves 4.4 Containment System Tests B.4.4-1 4.5 Engineered Safety Features B.4.5-1 4.6 Periodic Testing of Emergency Power Systems B.4.6-1 4.7 Main Steam Isolation Valves B.4.7-1 4.8 Steam and Power Conversion Systems B.4.8-1 4.9 Reactivity Anomalies B.4.9-1 4.10 Deleted 4.11 Deleted 4 l12 Steam Generator Tube Surveillance B.4.12-1 4.13 Snubbers B.4.13-1 4.14 Control Room Air Treatment System Tests B.4.14-1 4.15 Spent Fuel Pool Special Ventilation System B.4.15-1 l 4.16 Deleted 4.17 Deleted 4.18 Reactor Coolant Vent System Paths B.4.18-1 4.19 Auxiliary Building Crane Lifting Devices B.4.19-1

% 20T;Spsnt]FuelyPoo_1yStoragei.configurati6nT ,, , iB74!2031:

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1 TS-xiii REV 123 5/21/96 APPEMDIX A TECHNICAL SPECIFICATIONS l

LIST OF FIGURES  !

l TS FIGURE TITLE 2.1-1 Reactor Core Safety Limits 3.1-1 Unit 1 and Unit 2 Reactor Coolant System Heatup Limitations 3.1-2 Unit 1 and Unit 2 Reactor Coolant System Cooldown Limitations 3.1-3 DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity >l.0 uCi/ gram DOSE EQUIVALENT I-131 3.8-1 Spent Fuel Pool Unrestricted Region Mirefriawhie-Burnup and).Ds;chflTims RequirementsWiOFATFdel 3 ; 8f2'.[  !:Spe'st]Fus1?Poo11 Unr'estrict#df RegioH"BUrnup[sndlDb'c^ay[TimWRehdirsments KJTD:; Fuel::1 3

3.10-1 Required Shutdown Margin Vs Reactor Boron Concentration 4.4-1 Shield Building Design In-Leakage Rate 5.6-1 Spent Fuel Pool Burned / Fresh Checkerboard Cell Layout '

5.6-2 Spent Fuel Fool Checkerboard Regler Minimu Eurnup RequirementcInterface"Reqdirements 516?3} xa TSpent}Fuelgool!::CheckerboardReg16nfBurnu{sndfDscaf]TimsiReg61Eessnts 6.0FA Fuelb NoiGAD L516947 EspentfFuel::(P6olf Chscherb6srdlRegiod Burhupfind}DsEspjTime?Rsqdirements H STDfFuelt No1; GAD L576s53 ,7SpenthFuelfPool:8Ch6Werboafd[Rsgibh";Burnuf;addTDiesff^Tims? Requirements

~ "

KOFOFuelk4.7 GAD L5?6f6? ^ Spent? Fuul? Poor Chs;bkerboard}Rugi6niLBarnUMind.?Dscay2 Tim 6):Rs4Girsments

< STD Fuel,f4 GAD 1 ~

5.6f7J ) Spentj Fuel; Poolj Checksrbohrd2Regiod7 Burnupland.iDehay;;TimeiRsquirements

-;0FA Fueli18: GAD E5f6sBT 1 Sp'ent.; Fuel . Pool? Chuckerbsard i Regi6niBurnuplandl Ds'esf1Tiine ? Re qsirements C.STDfFuelM 8 GAD l.5 l619 j  ? Spent:FuellFool JCheckerb'ard" 6

~

Rig 16ntBdrnu d'and?DscayfTitse Rsquirements

~

- 0FA-Fuel,fl2. GAD

. 5;l,6s10f , ( Spent:: Fuelgool(Checkerbasrd(Regi6niBurnupiand DecayJ TimeT Requirements OSTD;Fuelii12fGAD f 5;6?ll" ' jSpentiFue19PoolfCheckerboardl Region [BurnUplandiDehay}TimsfReqUlrements a OFA FuelF 16.1or!MoreTGAD)

J5.6-121 [Shent Fuel / Pool-} Check.eiboar'dj.Regionf BdrnUpEand7DecaylTime?Requirenient's v:STD Fuelp 16for:MoreLGAD B.2.1-1 Origin of Safety Limit Curves at 2235 psig with delta-T Trips and Locus of Reactor Conditions at which SG Safety Valves Open

l TS.3.8-4 REV 108 9/3/93 i

3.8.C. Small Spent Fuel Pool Restrictions l

l No more than 45 recently discharged assemblies shall be located in the small

( pool (pool No. 1).

l l D. Spent Fuel Fool Special Ventilation System l 1. Both trains of the Spent Fuel Pool Special Ventilation System shall ,

be OPERABLE at all times (except as specified in 3.8.D.2 and 3.8.D.3 l

! below). l l

2. With one train of the Spent Fuel Pool Special Ventilation System inoperable, fuel handling operations and crane operations with loads over )

I spent fuel (inside the spent fuel pool enclosure) are permissible during l the following 7 days, provided the redundant train is demonstiated 1 OPERABLE prior to proceeding with those operations.

)

3. With both trains of the Spent Fuel Pool Special Ventilation System j inoperable, suspend all fuel handling operations and crane cperations '

with loads over spent fuel (inside the spent fuel pool enclosure). )

4. The provisions of specification 3.0.C are not applicable.

E. Spent Fuel Pool storace

1. Fuel Assembly Storage

a. Tc be etered uithcut rectrictier ir the cpent fuel pec1, the burnup and initial enricher.t of a fuc1 accc bly ch:11 bc .zithir the i unrectricted range of Figure TS.3.8 1.The[coinbinst'isti;fof[iilifi'al {

snrichmentZburnup?ancVdecs ?tiinelbfishch?; spent): fuel):assemblyy;. stored.

i in.; thef spentifuels poolbshalll;be' withinj the{unrestrictied' range [of_ ' l Figures : TS . 3 ; 8 11or;TS 23j 842 M asCapplicablei:F orifuellas s emb11essshal;l l

be' s tored linj accordance lyithj Specificatio;n p5 M A ; M e i i

b Fuc1 accc blic: .ith ec binatier cf burnup cnd initici enrichment l 1: the rectricted range cf Figure TS.3.S 1 chall be etered in cecordance uitb Specific: tier 5.6.^.1.d.

eb. If the requirements of 3.8.E.1.a and 3.8.E.1.b are not met, immediately initiate action to move any noncomplying fuel assembly to an acceptable location.

de. The provisions of Specification 3.0.C are not applicable.

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3.8.E.2. Spent Fuel Pool Boron Concentration a .' The spent fuel pool boron concentration shall be_2 1,800 ppm when fuel assemblies aith cerbinctier of burnup and initial enrichment ir the restricted ren; ef Figur: TE.3.8 1 are stored in the spent fuel pool nd  : pent fuel peel zerific tier her net beer perferred since the lect e c rent f ny fuel 22:crbly ir the spent fuel p::1.

l b.

If the requircr:nte ef specificatier 3.8.E.2.2 cre :pplicchi: :nd the  !

spent fuel pool boron concentration is not within &&e-limit, then s immediately: I l

1. Suspend movement of fuel assemblies in the spent fuel pool, and  !

2. Either iInitiate action to restore spent fuel pool boron concentration to within 4ts-limit er perferr : pent fuel peel erificatien. '

c. The provisions of Specification 3.0.C are not applicable. l r

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l FZGURE TS.3.8-1 REV 108 9/3/93 i

12000 J

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k i i ft 1 i r ,I , ,/

10000 'm e .

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, tNustnicum n .

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I ' I I 1 - ,/

\ f /

8000 1 I if P 1 i /

s < -

.s s , ,

m 7000 1 , s' /

p /

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- . . - 1 y som 'n+  ;

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5000 DELETE .

l lg 2 II II Fe' . i

1. 1/ 6  %

k l

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g 12- Rts t xagiEu ,a II 1

1. / 1 El \

I/ lt 11 s i s  %

1. g I L  ;

I E 1000 r

/ t s .

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k '

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3.5 4.0 4.5 5.0 l

INITIAL NOMINAL U-235 ENRICHMENT (w/o) i l'

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FIGURE TS.3.8-1 Spent Fuel Fool Unrestricted Region Minimum Burnup Requirements

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j FIGURE TS.3.8-1 REV

' 40000 I i l f l  !

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! 1 0 Years 35000 /

/, 5 Years

/ /, 10 Years

/ //j 20 15 Years Years b I / //// '

g 30000 I ///)Y

% I / ////

O / //g WRESTRICTED

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a 25000 / fH/

@ //f//

u /f/#

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3 20006 /4W '

Qw ////

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$ /M i 15000 /w t /A V I a

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& j 10000 F j I A l 2F RESTFJCTED I

5000 f

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1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) i l \

FIGURE TS.3.8-1 Spent Fuel Pool Unrestricted Region Burnup and Decay Time Requirements - 0FA Fuel i

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FIGURE TS.3.8-2 REV 40000 0 Years j ]

1. 1 j i

,/ j 5 Years

! 35000 I / /- 10 Years

/ / [ 15 Years

/ / // 20 Years

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.y 30000 , ,/,/,,,///

y l / ////

g UNRESTNCTED / ////

3 / f///

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@ 25000 a l //f//

Y l / fM m I ///H I / //H a> 20000 -

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10000 ,rg 4

/F F RESTRICTED A V 5000 f l

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l o i 1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) l l

l FIGURE TS.3.8-2 Spent Fuel Pool Unrestricted Region Burnup and Decay Time i Requirements - STD Fuel 1

i

Table TS.4.1-2B (Page 1 of 2)

REV 108 9/3/93 TABLE TS.4.1-2B i

MINIMUM FREQUENCIES FOR SAMPLING TESTS 1

TEST FREQUENCY

1. RCS Gross 5/ week  !

Activity Determination

2. RCS Isotopic Analysis for DOSE 1/14 days (when at power)

EQUIVALENT I-131 Concentration i

3. RCS Radiochemistry E determination 1/6 months (1) (when at power) 1 4 RCS Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, whenever (

Including I-131, I-133, and I-135 the specific activity ex- I ceeds 1.0 uCi/ gram DOSE _

EQUIVALENT I-131 or 100/E uCi/ gram (at or above cold  :

shutdown), and I b) One sample between 2 and 6 )

hours following THERMAL l POWER change exceeding 15 l percent of the RATED THERMAL POWER within a one hour period (above hot shutdown) l S. RCS Radiochemistry (2) Monthly i 1

6. RCS Tritium Activity Weekly l

7. RCS Chemistry (Cl*,F*, 02) 5/ Week l 1

8. R.CS Boron Concentration *(3) 2/ Week (4) I

9. RWST Boron Concentration Weekly

10. Boric Acid Tanks Boron Concentration 2/ Week

11. Caustic Standpipe NaOH Concentration Monthly

12. Accumulator Boron Concentration Monthly

13. Spent Fuel Pit Boron Concentration Menthly/ Weekly'"'"

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_m 4 m J ..mr. & A-+.,_.,.,.J -

4 .A 4 .J 4 ha &- e+- -,-a 4 - M .d k m.+.4_ m -

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Table TS.4.1-2B (Page 2 of 2) i REV 10" 9/3/93 I '

TABLE TS.4.1-2B l s

MINIMUM FREOUENCIES FOR SAMPLING TESTS  !

TEST FREOUENCY I 14. Secondary Coolant Gross Weekly Beta-Gamma activity >

t

15. Secondary Coolant Isotopic 1/6 months (5) -

l Analysis for DOSE EQUIVALENT '

! I-131 concentration ,

16. Secondary Coolant Chemistry pH 5/ week (6) pH Control Additive S/ week (6)

Sodium 5/ week (6) .

l t l

i Notes:

i l 1. Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was last suberitical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />  ;

or longer. '

2. To determine activity of corrosion products having a half-life greater than 30 minutes.

3 During REFUELING, the boron concentration shall be verified by chemical  ;

analysis daily.

4. The maximum interval between analyses shall not exceed 5 days.

5. If activity of the samples is greater than 10% of the limit in Specification 3.4.D, the frequency shall be once per month.

6. The maximum interval between analyses shall not exceed 3 days, The minimum : pent fuel peel berer cercentretier fre specific: ler 3.8.E.1.b cb=11 bc crified by cheri 21 rnelyci 2:chly "'.ile : cpent fuci :ch centairing fuel in lec ted ir the rpent fuci peel.

9. The spent fuel pc:1 herer cencontretier ch:ll be verified 22 hly, by cheri 21 cn 1yric, te hr zithir tF^ 11=it: ef Specificatier 3.8.E.2.2 uher fuci ::c blice uith a ce=binatier cf burnup :nd initial enrich ent ir the rectricted range of Figure TS.3.8-1 cre ntered ir th: cpent fuel perl nd epent fuel peci verificatier has net beer perferred cince the lect = crc =cr* cf any fuci ecre=bly i- the : pent fuel peel.

l 1 - . -

l TS!'4720;1 -

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[: 201 ^ S6ehP Fdel'7P6oF S tbrike~Cohfisn'rati6n AbbliEabilitV 1 This]sdrve 111ance:]}s }applic'ab1E2 shshessf(fuelsis!s t6rsafiHJths':isplsnE{fds1 pools; ,

Obiective l i

ToNerify' that[fue1Tassembliesiin)f ths:;:spentifusl^ pobWare[stdrdafin]?hadsrdhndy wit %tise-: requiremsntsioff Specification '3.2 8 ? Elt'a7 t

56ecifiEsti6n N;spsntisf6e;17oo1TihWE6E6f IVerifissEibn~fshs1Ehsiperf6imisdipithiii!7.Tdayashf ths;; completion of;anyffu6lihandling; campaign.[shich :Linvolves;: thej relocatiotn 6f fuelfassembliestwithin:theispent[fue1[ pool;oritheladditionfofifuel asssmbliss l

hot theispent:; fuels poolf-

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I TS.5.6-1 5.6 FUEL HANDLING l

A. Criticality Consideration

1. The spent fuel storage racks are designed (Reference 1) and shall be maintained with:

l a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight

! percent; b) Kerr%1' 0Mifffullylflo6dsdswithinnboratedjwat;er$whichsindludeMhii .

a '

' llowancesforf uncertaintiesf asldescribed7in(Refere.nce)31 bd. K.tr s 0.95 if fully flooded with = berated water [borsEsditFf750 ppm, which includes an allowance for uncertainties as described in Reference 33; ed. New or spent fuel assemblies with a combination of Bischi~rg6 burnup? and-initial enrichment?ahd:dec;aylt;tiims in the unrestricted range of Figures TS.3.8-l[oqTSj318/2,fas[applicib1eQ maf[bs allowed unrestricted storage in the spent fuel racks; and de. New or spent fuel assemblies with a combination of dischargs burnupy and-initial enrichmentihhdid.schy*tiins' in thE restricted range of Figures TS.3.8-1[6;r[TS(3f8-2 Qasispplicable?@ illlba stored in compliance with Figures TS.5.6-1 andthrbugh TS.S.6-312.

2. The new fuel storage racks are designed (Reference 1) and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;

b. K.tr s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Reference 2; and i

c. K,rt s 0.98 if accidentally filled with a low density moderator which resulted in optimum low density moderation conditions.

3. Fuel will not be inserted into a spent fuel cask in the pool, unless a minimum boron concentration of 1800 ppm is present. The 1800 ppm will ensure that k,gg for the spent fuel cask, including statistical uncertainties, will be less than or equal'to 0.95 for all postulated arrangements of fuel within the cask. The criticality analysis for the TN-40 spent fuel storage cask was based on fresh ft;e1 enriched to .

3.85 weight percent U-235. j l

B. Spent Fuel Storare Structure The spent fuel storage pool is enclosed with a reinforced concrete l building having 12- to 18-inch thick walls and roof (Reference 1).

l The pool and pool enclosure are Class I (seismic) structures that i

afford protection against loss of integrity from postulated tornado missiles. The storage compartments and the fuel transfer canal are i connected by fuel transfer slots that can be closed off with

pneumatically sealed gates. The bottoms of the slots are above the tops of the active fuel in the fuel assemblies which will be stored vertically in specially constructed racks.

TS.S.6-3 REV 108 9/3/93 D. Spent Fuel Storaste Capacity The spent fuel storage facility is a two-compartment pool that, if completely' filled with fuel storage racks, provides up to 1582 storage locations. The southeast corner of the smc11 pool (pool no. 1) also serves as the cask lay down area. During times when the cask is being

, used, four racks are removed from the small pool. With the four storage racks in the southeast corner of pool 1 removed, a total of 1386 storage locations are provided. To allow insertion of a spent fuel cask, total storage is limited to 1386 assemblies, not including those assemblies which can be returned to the reactor.

i l

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1 i l Reference l 1. USAR, Section 10.2 i

2. " Criticality Analysis of the Prairie Island Units 1 & 2 Fresh and Spent Fuel Racks", Westinghouse Commercial Nuclear Fuel Division, February 1993.

3'.' <?' Northern? States [P6sertPrairiFIslandiUnitsf17aridf2 [Spsnti?lFusitRack Criticali ty(Asalysis iUdingtS61uble 4 Bosonscredit"j Wes tinghous e;:iColimis rcial NucleasiFuelfDivisionEFebruaryfl9.971,

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FIGURE TS.5.6 1 i

REV 108 9/3/93 1

' E E .E E.

"55I ,-- liiE3" raas "h ~!!! EEi!!!!E 5i

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E5;ss M p @iisi j ~5EE !s""M E!ES! EEs~E

.. =:= = r-- =

I;;ml Essiill Biiiiti!D  !!!Hililii 1

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!!!Hi!]j $[jHi,3 iM M' r- E"E -Eis l 5$$ . !55 65$ 240!E i PATTERN FOR CHECKERBOARD REG N i

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! RMGMGMMM DELETE 2

=_ //m 'y WHi- i mEE

=-  :-- :

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I l I f BOUND BE'IVEEN CHECKERBOARD AND UNRES CTED REGIONS I

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Fresh el: Enrichments up to 5.0 w/o u 235, no restrl 'ons on burnup M

ns Che erboard Region Must satisfy minimum burnup requirements of Figur 15.5.6-2.

j B ed Fuel:

nrestreited Region l

i ff,/

7

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Burned Fuel: Must satisfy minieun burnup requirements of Figure Ts.3. -1.

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Note: The Checkerboard and unrestricted regions can alternatively e

( separated by a single row of vacant cells on each adjacent f .

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1 FIGURE TS.5.6-1 Spent Fuel Pool Burned / Fresh Checkerboard Cell Layout i

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i FIGURE TS.S.6-2 REV 108 9/3/93 1

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30000 l l

/

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/ 2 l

/.

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25000 \,( / /

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% PTELEl / /  !

\ / / l n \ / / \

(g \ ,

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f. l g

v \ [ [

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B \ / /

51520 l

kV 7 /

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/ / \

1 / / \  ;

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/ [ \

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S./5 3.0 3.5 4.0. 4. 5.0 INITIAL NOMINAL U-235 ENRICHMENT (w/o)

FIGURE TS.5.6-2 Spent Fuel Fool checkerboard Region Minimum Burnup Requirements

bl l

FIGURE TS.S.6-1 REV lI E E E

E E E E E E .

1 Fresh Fuel: Must be less than or equal to nominal 4.95 w/o 23sU No restrictions on burnup Burned Fuel: Must satisfy minimum burnup requirements of Figures TS.5.6-3 through TS.5.6-12 depending on number of GAD rods in fresh fuel i

[ FIGURE TS.5.6-1 Spent Fuel Pool Burned / Fresh Checkerboard Cell Layout

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j FIGURE TS.S.6-2

• REV l l

l l

4 Interface j

! lE MIME l

i i EBRER

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I Fresh Fuel: Must be less than or equal to 2

l nominal 4.95 w/o "U

! No restrictions on burnup

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' Burned Fuel: 3x3 Checkerboard Region j Must satisfy minimum burnup requirements l i of Figures TS.S.6-3 through TS.S.6-12 n

Burned Fuel: All Cell Unrestricted Region  !

l i Must satisfy minimum burnup requirements l l

P of Figures TS.3.8-1 or TS.3.8-2 4

i FIGURE TS.5.6-2 Spent Fuel Pool Checkerboard Interface Requirements

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FIGURE TS.5.6-3 REV 55000 ,

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5 Years

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l j j j 10 Years f

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45000 I 4 I I / / /l /j 20 Years  ;

g ACCEPTABLE

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f f f

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ff l E-*

x 40000

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a 35000  !

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C l W i / / /// I 3 4 /i / ///

sn 30000 f f fif f j i /vsy

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1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)

TS.S.6-3 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, No GAD

FIGURE TS.5.6-6 REV 60000 0 Years

/

5 Years .

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/, / 10 Years 50000 I I[ / is Years TM / / // 20 Years S / / /// ,

N / / ///

$ / / ///

3 40000

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/ ////

@ / ////

B  ! //// ,,

8 / //// h

>' 30000 7XM

' fc> / /M n / //#

• /M/

's /M/\

g 20000 jffj ,

IU//

///[ NOT ACCEPTABLE

//8 I

10000 UK 7

I I

i 1

O [

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) -

f TS.S.6-4 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, No GAD l

l

FIGURE TS.S.6-5 REV 60000 l l

50000 ACCEPTABLE 3

E* /

> 0 Years ,

i x

5 Years i h '/.[

/ 10 Years 15 Years l

l

' 20 Year: '

~ 40000 //// l

@ ////

B /////

8 //'#

>,30000

$ ////

$ /// l 8 /Hfr \

4 fjf l a 20000 f'l4Y l

w ////l

//K

/M

/[ NOT ACCEPTABLE 10000 M

2, AY

/

/

0 /

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)

TS.S.6-5 Spent Fuel Pool Checkerboard Region Lurnup and Decay Time Requirements - 0FA Fuel, 4 GAD

FIGURE TS.S.6-6 REV 60000  ; ,

I il i I '""

50000 II I /

AC U IA M [ j 5 Years

[ [, 10 Years llC

[ / /j ' * * * * "

15 Years 8 / / ///

h40000

/ ////

I / ////

I / //#

$ / ////

y m / ////

3 30000 I I/M/

g I /XH/

g //H/

• I//N/

• A///

20000

!#8 w bW N#

//f

/d NOT ACCEPTABLE

! I I ,

l 10000

/Jr

. V J

I O [

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) ,

i TS.5.6-6 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 4 GAD l i

I i

l FIGURE TS.S.6-7 )

REV l

! i l \

i I 50000  ;

( .

i i

i ,

6 i

+ l t i  :

45000 l , ,

l

! I I J 0 Years

! ACCEPTABLE '

r

' 5 Years 40000 a

, , ,j f 10 Years O ' # ## 15 Years i 1

P 'II ## 20 Years )

E / / ///

Ng: 35000 / //// l l

x / / /// l

~

f //// l g / ////

3 C

30000 / /. f/)II M //Hf ,

0 / /H) i

• / //// l

/ ff/)

~> 25000 f ffy , ,

/////

Qm fiHN l

en

/H//

go ) /Hf

< 20000 ,ffffj ur/ ,

$ /NJ'

//av a

k ) f/1 l 15000 sy,  :

~

//A l bW

1. 1. NOT ACCEPTABLE 10000 v

f[

AV 2

5000 t

[

/

I O /

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) l l TS.S.6-7 Spent Fuel Fool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, 8 GAD

-_ _ - = ._

l i

FIGLTE TS . S . 6 - 8 REV i

50000 i i  ! , e i l i e i i i i i e i e i , 0 Years 1 e i i i  ! / ,

45000 ', , , , , j ', 3 y,,,, l i i i 4 / / 1 i 6 i f f j 10 Years i pgggp74g / / ,/ . 15 Years

/ I/ / 20 Years 40000 / ' / i/ //

n I p ) / ///

E" / / / // '

% / ////

' 'i " ' l D

n 35000 i / / / // ,

E l / / /// \

~ f f///

g / / ///

5 C 30000 ) / ///

k / / ///

0 // ///

• I / \ / /// \

~>' 25000 i ) //H \

D l/ f/// l

{m f////

/l//f/

l m / //H 4 20000 / /Hs  ;

/ //N

& / /M a /HH l

% /H l 15000 yfy,// ,

HM  ;

/Hf 10000 fp f [ NOT ACCEPTABLE ff r

A

=

5000 [

r i

I i 0 /

1.0 2.0 3.0 4.0 5.0  !

Initial U-235 Enrichment (w/o) l l

I 1

TS.5.6-8 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 8 GAD

-- ^ . _ . -

FIGURE TS.S.6-9 REV i

l 45000 , , ,

' i

' I I I l

' i 8 s o Years 40000 I i i ,f I ' / / s Years y

! !' 10 Years ACCEPTABLE

> // 15 Years

/ / /4 20 Years 3s 35000

/ / ///

x / / ///

I I /////

h:n ' I l / 6/ //)

8 I I / //N 5 30000 ' / //H  :

j O,

f//H c / //// i i

' f//H 0 ' / /N/

c 25000 s '

of//g ca

/ ////

y / //H m l //H/

Qc) 20000 ' /N# '

m /////

m /f/f

1. /Hf/

a f N/f

$ 15000 em '/4I' m

Hff

//K 10000 -

7 fI#l r NOT ACCEPTABLE l

F f

J 5000 f f

)

/

/ I 0

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)

TS.5.6-9 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, 12 CAD

l l

l FIGURE TS.5.6-10 REV 45000 , , o y,,,,

' /

I I /r $ Years

! j j

1. ' / /. to years 40000 I I I / //

I I I / / yj 15 Years 20 Years

- i j  ; f f f fj ACCEPTABLE

/ ////

^ / / ///

' I / //// l

'x

@ 35000 ' i / / /// i i t / / /// \ \

% 1 O I i ) ) /// l

' ' // /// [

$ 30000

~ l I / A/// j l I / / ///

a p I i / / ///

i / / ///

f ' / / ///

2 25000 i i / ////

ca \

l l / //// '

y I i ////

m 6/ /N/

g '/M

/

e 20000 /\/H/

m m / ////

1. 1/M a /////

//'#

$ 15000 M/A[ '

w ////

f/E g l NOT ACCEPTABLE 10000 # \

A V E l 1

5000 [ ,

I I I I

/ i 0 / I 1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)

TS.5.6-10 Spent Fuel Pool Checkerboard Region Burnup 4ia Decay Time Requirements - STD Fuel, 12 GAD

FIGURE TS.5.6-11 REV 45000 , ,

i l I

' l 8 8 1 1 40000 I I l I t I i i _

j 0 Years l 1 f 5 Years ACCEPTAKE / /

/ /j 10 Year.

3 35000 8 8 / /// 15 Years E*

g j f fjj 20 Years

/ ///f

$5 / ////

/ //Ar 5 30000 / f/f/

/ ////

On

/ f/f/

y /ff//

u '

/M/

0 25000 ' t /WJ m ~

/V/H H

f/Xf/

///H Qe 20000 M#

m ///#

• //ff 4 fjgr H /)f//

//E

$ 15000 I /Nr w I//F Uf ^ ^

10000 hV l B

N 1

f 5000 j

/

/

I 0 Il 1.0 2.0 3.0 4.0 5.O Initial U-235 Enrichment (w/o)  ;

TS.S.6-11 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, 16 or More GAD l

l 1

I l

l FIGURE TS.5.6-12 REV 45000 , , ,

i 6 1 I t 0 Years l

j 8 r 5 Years 40000 i 7 j

/ / 10 years f f j 1$ *****

ACCEPTABLE / / // 20 Year.

/ / /// 1 3Em 35000 fl / //f

\

/ / / f/

2 // //f l h3 ) //// 1

/ / ///

3 30000 / ) ///

/////

a / / ///

D

/ //// .

l 0 / ////

D 25000 f/ ////

\

(

l/////

>i / ////

a / //#

l j / //#

e 20000 / f//f

.a

• //ff ,

1. //Hf  !

H /H//

IM '

w

$ 15000 /Hf HM ffM g[ NOT ACCEPTABLE 10000 47 <

/f M

F 5000 1 J

/

/

i 0 /

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)

TS.5.6-12 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 16 or More GAD

B.3.8-2 REV 109 9/3/93 3.8 REFUELING AND FUEL IIANDLING Bases continued During movement of irradiated fuel assemblies or control rods, a water level of 23 feet is maintained to provide sufficient shielding.

The water level may be lowered to the top of the RCCA drive shafts for latching and unlatching. The water level may also be lowered below 20 feet for upper internals removal / replacement. The basis for these allowance (s) are (1) the refueling cavity pool has sufficient level to allow time to initiate repairs or emergency procedures to cool the core, (2) during latching / unlatching and upper internals removal / replace-ment the level is closely monitored because the activity uses this level as a reference point, (3) the time spent at this level is minimal.

The Prairie Island spent fuel storage racks have been analyzed [(RsfereHEe[8) Tid sddoidsdE6"sith{thEmsth6d616gy[Ebbt'sihid?lWMReference 54)QThsti/msthadol6gy

'ensurssLthstithe tspentifuelt rack multiplicatidnifsdtafW%rrdisilhsssthusiO;95 asirecommended(bj{ANSl{57 $ 2fl983 [(Referencef 6)fand;NRC]fui.dands[(RefekenceM)

ThelbodesNaiethodsJiandstechniquesicbbtsinedpinithel method 61bgy{urejussdf t satisfygthisicri,terigonfK,try TheResulting) Prairie @slan,djspentifue1[ rack cri.ticalityjanalysia %e-allows for the storage of fuel assemblies with enrichments up tota?uiakised?bf 5.0 weight percent U-235 while maintaining K rr 5 0.95 including unceEEaiiitlss(and7efedit!forisolubleib6fah. IHisdditibHEshbf efitiEalitiyioffthe]E61V(FMerlN 1? O)[isias suri di on : a795d 51b'a s is @ithou t$ th e presenceiofithsjolublsjborosisfthefpoolf{Casdin;is?thkeh{f6sirddidactEvs~

decay 7 timelbfitheTspentj fuel!andif6rithe presencefoff fuelj rodsf contsining

~

Gadolinium barnab.lejpoison!

~

The Prairie Island specific criticality analysis (Reference 8) utilized the following storage configurations-or-regiene to ensure that the spent fuel pool will remain suberitical during the storage of fuel assemblies with all possible combinations of burnup and initial enrichment:

1. The first regic6tofagifdonfihofstibij utilizes a checkerboard loading l pattern to accommodate new or low burnup fuel with a maximum enrichment of  !

5.0 wt% U-235. This configuration stores " burned" and " fresh" fuel .

assemblies in a M 3x3 checkerboard patternTasish6wn71H7Fihbre;TSs5 6tl.

Fuel assemblies stored in " burned" cell locations arelselectedTbassdfonTs combination;6f.Tfue17 assembly?:typsMinitialfsnrichmcht@dischargelburnupland decay! time:((FigurasiTS.5;6f3[through;TSj51.6t12)=uct %;ze cr ' initial ersicMedflhE: ther 2.5 ztt U-235 (nc= incl) er ccticfy =in4=u= burnup requirement. ThisriteiiE9forTthelfdel:EstoredsinTths?"burnsd"'locstions{is

)

alsoldependention[thec numb)r;ofhodsJ containing Cadoliniumjinithe[centerT

" fresh"Lfueliassembly"; sThe use of empty cells is also an acceptable option

^

forl he "burnid" cell locations. %ThisTwil17allowithuestorageNf/newlor^los i v

barnup?fuelfaisemblies ;inithe ostercrows t of Jthefspenti fuelL' storage tracks becausec.the' area ontsideltheiracksicanjbeLconsideredito.ibe(empty; cell') s I

J

l I

B.3.8-2 Continuation Fusliss s smUlissi tha t% fall? intF thsT rss t rib te d ffsngs?;o f! Figur esET513 ? 8 Wor TS 23 (8/ 2) are de qdired -(to [bei s tora 6 ins" fresh't [ cellllocatif onsfas ishowntih" Figure;TS';St6-1;'3The?criteriaiinc16ded$injFi$dressTSi3;841;LandyTS(3l8)2 for~ thei selection ofEfue17a~ s semblies: toibe? stored?irsthst." fresh"icell loc'ationslis.[. based lonEafcombinstion%f}fdelgassemblyf typ%jinitial[

ente dec. ayitime f and.'.' dischargeu1 b' rnup2Fuc1 ^.cce=blice ctered ir the I enrichm7 requir==~nt: Ecr burnup cr burnchle =becrbcrc.

2. The second regicnst@(sgej'c'6hfi5dfstibh does not utilize any special loading pattern. Fuel assemblies with burnupp and-initial enrichmentQdad{;deday time' which fall into the unrestricted range of Figurei TS.3.8-1Mf;TSi3{84 1 2,jds"applinab1pfcanbestoredanywhereintheregionwithnospesial~

placement restrictions. Fuc1 cccc=blicc %ich fell inte the rectricted r-enge of Figur: TS.2. -1 muct be ctered in the checkerbeerd regier ir  !

2002 d r. : .:1$ S;': ifi ::irr 5. f . ^.1. d.

1 4

l 4

_ _ - _ . . _. _ _ . . ._m_ . - _ - _ _ _ _ . _ . - . . _. __

i B.3.8-3 REV 109 0/3/93 i

3.8 REFUELING AND FUEL HANDLING Bases continued '

i The burned / fresh fuel checkerboard region can be positioned anywhere within the spent fuel racks, but the boundary between the checkerboard region and the unrestricted region must be either: ,

i

1 -. separated by a vacant row of cells, or l 2. the interface must be configured such that there is one row carryover of the pattern of burned assemblies from the checkerboard region into the

first row of the unrestricted region (Figure TS.5.6-12).

4 Specifications 3.8.E.1; 5.6. A;1^ld' and 5.6. A!1Te" ensure' that 'fus1' is' stored'id the' spent fuel racks in'accordance with the storage configurations assumed in the Prairie Island spent fuel rack criticality analysis, (Reference ,8);

1

Figur: Ts.3.8-1, "hicF cpecific: the minirur burnup requircrent fer j unrectricted eterege ir the spent fuel peel, it b ::d er enrichment frc: 3.97 4

~

te 5.0 u:!gh* percent " 235. Enri F:ent lever ther 3.87 unight percent are eenservatively beunded by the minirr burnup requircrent fer 3.87 ucight 2 percent U-235 uhich i: 2000 "3D/M*". Thereferc, Figure TS.3.S-1 h: beer dre-te require that fuci zith 2n initial ::.ricF=cre cf Iccc than 3.?? reight i percent U-235 have 2000 =3D/M*U burnup er greater befer: unrectricted eterage

ir the

pent fuci peci .:111 bc 211 cued.

%: ::ter ir the pent fuci peci nere:117 centnin: ::1ubic herer, "hich rasu14e i ir large cuberiticality : rgine under actual eper: ting cenditiene. Meuever_7 the N C guidelirer, b :cd uper the accidert conditier ir "hich 211 ::1ubic peiecr i 22:=cd te have beer lect, specify that the limiting % ef ^ 95 he cvaluated ir th: nbrener cf celubic herer Mence, the decign er bcth regien:

i it bered er the ur: ef unberated unter, uhich encure: that c ch regier in sairteined ir : ruberiticci cenditier during n:rm:1 Operatier eith the regien:

fully 1c:ded.

ThsP ?rsitie ?IslundTs pshtiPdelip661Te ri tiEal'ityishalys is FsddisdeWYa117th'sNfusi typesichrrentlpfsthreMi kchsispeu sfdelipboi nnd/in!sse$ nsth5Meahto k iThs^

'fue.l? tjpesjc 0FA,;1;and.LVan,onsideredlin[thefahalysidsincludA,[th(,Westinghb6~se(Stsu,d tagejPlusfdesigns.pand Jthe 1 Exxon) fu,e.1; sis embly~g.typesyinJstoragelin

--n. -- . ~,-

' he;7 Prairie /Isladdispentifueijobit JThe10FAidesihnatiohjontthe (figdiestin t

Sedti6ns 53f8?and?SW A bouniif alif 6f[the Westinshbuse30FA[andjVantaget i Plds ?fdb1 As semb11 e ufatiPra ni e91 sl. adiC ~EThe.TST. D [dsh isnationionhthef. fi gure s!.; in LSe c tions

= .- .

~ ..

.. . ~ - . .

3, ,18. #and,95 w g. 6- s. A th.o_.undi x -

alliofSth. ..e.f- We s tinghouses

- - - - . STD.-- iand fExton-?

1 fuel? as sembl i. e si- at PrairieiIs. land)

Most accident conditions i,nft.hs,,ispentifdelip6olldewi;11 not result in ah cignificent increase in K,gf of{the{rackskinthe activity cf either of the two regien~st6 rags [cohfigdrationsl. Examples of theose accident conditions;;;which  ;

gilgogesultlintan?increassli@K,cfaretheice ef c cling, the dropping cf l a fuel assembly dr'opjfon the top of 'the racks, and the dropping cf a fuel assembly dr6p!!between rack modules and wall (rack design precludes this condition)kand7hTdropiersp1;acementfsffalfdylisssembly[intiaZthe] cask 11oadins areaTo. f?theismallsp.ool . However, twb? accidents can be postulated whichichat . .

of(thW3ds13;661(Eoolis[ spit [emlandithejsscond@ouldjbefalmis1dsdloffaIfde15

B.3.8-3 Continuation assembl97ist6Pa MellR foU which? thsYre s c rictionEonT10ch tibh burn.uE*nfEeca,7.m ..ine$ orJGailo. ,li. ni.dat:credi,t?a.re.V: hor satis. f. ie, df. N'enr16hs lt - ~

~ ~ -

For '(n16EEnrdMs[ofjthese a psituisted? accident conditions, the double contingency principle of ANSI /ANSn8.lil98Q "'5.1 1975 can be applied. This states that one is not required to assume two unlikely, independent, concurrent events to ensure protection against a criticality accident.T MhdsR f6rTthsse pos t"ols tsd.Ta6c ide nEc ohditibbs UthsTprsiehEWT6fMdd1EloEal?iulbblaf b o roniin dths

^

spent ;fucif ponl$ water [(aboveftheM50 ; ppmtrequissd stosmai6tAinntr j;less7 thai 0.95-6nder-normalfeonditions)lcunbs;.asenmedfaslla?realistih[initialicondition since n6t[ ass;uming;(it;s[presience;lw6ul;dibe(.;aisecondfunlikely evest.g i

E c dcubic centingency principlc 211ce: credit fer eclubic herer under bner:21 er recident cenditiene, cince enly : cingic accident need be cencidered at ene time. Fer c".c=ple, the mect ecvere accident scencrie in th^ accidental miclending cf c fuci ::cebly inte : r ck lec tier fer "hich the restriction:

er lecctier, enriebment, er burnup are et enticfied. E in eculd pctentially i incren c the reactivity ir cpent fuel r:4ks,--Calddliti6nsysr{peff6rmed {

(Refsrenchi8)?t6'determihe? the*asoantibfFsolbbidiboronfregnired L tof offsetschi I highest?reactifity1increaseIcansed;byleitherLofftheselp6stulatedi;aecidentsland

~  ;

to. maintain Khgilessjthaniorfequdl to 0195hlIt{was{foundgMt[a[spentifusl" l Poolboroniconcentrationyogl300?pp{m:v[asyadequatgeftomitigatethesepostu l

criticality related accidents [ahd;toimaintainj K rr(less{thanlogeqdal;std e Oi95.-6!

Specification 3.8.E.2 ensures the spent fuel pool contains adequate dissolved boron anytiac fuci 22:cablic: .zith : ec=binatier of burnup and initial enrichment ir the rectricted range cf Figure TE.2.8-1 cre etered ir the fuel pec1 and : cpent fuel peci verificctier hac net beer perfermed since the lect j meverent cf any fuci 22:c=bly ir the spent fuel peel. E c cgetive reactivity l effect cf tbc sclubic-b2rer . culd ts{ compensate for the increased reactivity l caused by a mispositioned fuel assemblyT6rfaF1Hss[bfsspinElfGslfpbo1Tc6611hg.

Th6;T1800? ppm ^ spentRfuel?:p6oll boronTc'6'heentrationjlimittin j Specificatif onf 3. 8W[2  !

was7 chosen .taEbei consistenMwith[the L bbrant concentrationflimitf required j bj '

Specification j 3';8'.Bild e t: fog::aispentJ fuel (cask l contaihin6(fuelf ' '  ;

B.3.8-4 REV -l'm o. ,' ' ,' o. '.

3.8 REFUELING AND FUEL HANDLING Bases continued The berer cencentretier requircrente f Specific tier 3.8.E.2 cre ne lenger 4=pened "ber ne fuel re rent: cre cecurring and : cpent fuel p 1 >crificatier h:2 heer ecmpleted, beenure Se eterage requirement: ef Specific:tien 3.8.E.1 crd 5.5.^.1.d ere ther adequate te pre >cnt criticality.

Specif!catier 3.8.E.2.2 ic net impered "her enly fuci ::: blic cith ecmbinatier cf burnup and initial enri:Fment ir the unrectricted rang ef Figure TS.3.8 -1 cre etered ir the cpent fuci peel. TFr requirc ente af Specificatier 3.8.F.2.2 are n t required ir that enre beccure eith culy fuc1 acerablic: that h ze burnup and initial enrichment ir the unrectricted range c6 Figure TS.3.8-1 it ic et percibic te cause er in 6 crtent criticality by micpecitiening fuci ::cebly ir the cpent fuci peel.

s, S.,ps. uif_i6at. iud. I.5.7. 67EE. 'E.steiz. .iYsHt,hatEthsVips..m..m m . . .

mm. htTfus1?m.is hki%.. teib'.s11'ss.

... m . m. Rt. -.hsnN, equaltto10]95WheQ1oode..'d j with!?waterj b..oratedstos7507 ppm) M spentgfdeltpool boron? dilution 0 s 6alys islwasi pe r fdimsWwhichis6hfifmsdichhnsuf fidiastlitim&Vfs' avdilab1M., ,toidhfectfAh 6n f6renhE 0;,95 f KerrVdes~ign.

. ~.-

i iss.ba+siss,d

.~

. exceeded.' jThesspenti.

S mitl~ga[tAiaY f+ue1+1 poolt dilutidnf, bo....~ront Sfj 't tneVsp,An.

u s i_s .tifd conhindedNhht?hnfun hilu

. ....x-tion 4 ff thNa --

ti f sil s pe

.- p ob hn.,pfannsdi6riinddips bbfon N::odcentya sl6ht f r- 5M1806s$.pm

~- a~ -

-~~--~---- m r tA n,.o/t--

nti50 s evid$

pps.a

. i71s Nh e?

n.. o.t; a f Cred. .ibl. ,;s-,e,v,e n t.h.mM a y.. m .m r w .3. ~y .

4 e c w ww,~ ., -

.w Whsenit m m he.m.w,. i.m. -; requ rements x o f;yS. pec,if,i,c.m ...ciy.vw.at on. 3 er8. gJg.1;wvararey.not7meth

, . mmed.

.y-sy . ,g.y.iw~

. atesact on

w. i-, . www....i mustibeltakenysfo5mosef anjidbnicompi ingifdh13 assembly $to }aniascept(abidi16lcasi6d ,

t6{ preserve {the$onble@ontingency[prige@lejassuspti6hldffthejriticAliti )

a. ~cc id.e. n.. t. i.. .a.,n,a. .l_ y.s..,.i.s..

~

q b. .a {

When the-r+qec=cnte ef Specific tier 3. 8. E.2. 2 crc applicabic, and the l concentration of boron in the spent fuel pool is less than requiredlby  !

Sp'edifiestibul318]Ej.27s, 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 efficiently achieved by immediately suspending the movement of fuel assemblies. The concentration of boron is restored I

^

simultaneously with suspending movement of fuel assemblies.  ::cptabic 21ternatize ir te ccepletc : 2 pent fuci peci */crificatier Heuczer, prier te  !

recu-ing eczement of fuci 2 ce=blice, the cencentretier cf berer munt be I rectered. " in decc net preclud^ me 2: rent cf a fuci :cc=bly te e enfc pecitica,- The?(suspsns16n(6 fifdelim6YssentliMno tf}ihtunded fro [prscludsisyvemsht i

of 7aTfdsEAssembl,.p.;

n. a . ~ c to.f, a Isaf.e.,{ po.si.tions.

~. .w. --

^

. : pent fuci peel >crificatier ic required fellering *he lect me>crent cf fuci scermblice ir the pent fuel peel, if fuci ::::blic cith ecebinatier cf burnup and initial erricFeent ir the rectricted-range of Figure TS.3.8 1 cre etered ir th: : pent fuel peel. ".1 : "crificatier 2111 cenfirm that any fuel cccerblice uith : ecchinctier of burnup cnd initial erricE ent ir the rectricted range of Figure TS.3.8-' cre etered 1 :ccrdance zith the require =cnt: ef Specific: tier 5.5.^.1.d.

w i 1 4' J J -l l

4 - : Y s-75..y B7.3yg.8.

s  !

g R.a EV-r u i

l 3,] 8] REFUELINC fAND 9FUEI!*HANDQ]!g i i

. i

~ . ~ . . . , - . - .- I

! Rg33Afcontin-.m ue d I l

References

1. USAR, Section 10.2.1.2 i

2. USAR, Section 14.5.1 o.

l 3. USAR, Section 10.3.7 1

4. " Criticality Analysis'of the Prairie Island Units,1 & 2 Fresh and Spent Fuel Racks", Westinghouse Commercial Nuclear-Fuel Division, February.

1993.

1 4.

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B;4?2001-452.05; gjiFnF Fuel"Pobli StoraidTC6nfi d6Fati sn Bases Thi st idrvs illisc e Nre rifissTths tTthi$ fuelT h s ssmbli esiiinT th4?s pentE fuel storagedrackstare:sstored61n?adcordanceiwithjthef regsirementsjof" '

Speci.ficatib.ns(3;8.El1y516(Aklid-andj5;6.A,1.bj.Q ThEJ s dkve111stisilis;Ysi;dirsdito bsic6mp16tidlyithh6Kdsysfa'ftefiths

~

comple tion?ofl any 7 fuels handlingicampaign (whichlinvolves?lthet rslocatidnTof fue1-l assemblies 1within?thef spent 2 3 fuelipsol or:fths:l; addition.[off fuel' asseinbliesL to;theispent) fuel? pool:. LTher extent %f 2axfuelthandlinglcampaigd will;beidefinedbylpisnt?administrativelprocsduresL;;EAamp1bsfof4al; fuel handlingi campaisn;(would] include :: alls of; the ? fdeli;i. handling > performed lddring?d refueling; putsge;- orj associatedjwithithelplaaementj;ofynewt fuel (intoi the spent)fuelgpool'J I t ? isino ti thFrinten ti b f Tthis(shrve 111anc e i; t67 r e quirs? the!66mple tidhi;;o fM spentj.fue14poolyinvsntoryJverification{during intstrupti6nstinLfuel handling,daring'a:Edefined2fuelihand11ng campaignP ;Nofspenttifuelspd61 inventoryLverification)isj required:following fuelt movements;phereino;i:fahl; assemblies are;; relocated;tondifferentispentf fuelirackilocationsjt The" If day "allowanch ffoM comple tiiod;76 f"this 7s nrvs 111anss^ pidvidh s;~'ide q uate time;forfthelcompletioni.ofia spe.nt/fue12pooliinventorfJverification while minimizing o theftime r a h fuelt as s emblyfmay) belaisloaded ;i in!:. the spenti fuel pool, . If ? a: fuel Lassemblylisfmi' loadedi s during' ~af feel;;handlingf campaign $ ths minimumibo ronj eoncentrationl: required ibyf Specifica tion r3. 8. E; 20 wi111: enhure that(the; spent?fuelrackK,fremains!within~limitalun'tilfthefspent' fuel pool-[ inventory; verification;isiperformedt

~)

I I l l l

i I

l Exhibit C l Prairie Island Nuclear Generating Plant I

l February 21, 1997 Revision to License Amendment Request Dated July 28, 1995 l

Revised Technical Specification Pages 1 l

4 I

l Exhibit C consists of revised and new pages for the Prairie Island Nuclear l Generating Plant Technical Specifications with the proposed changes )

incorporated. The revised and new pages are listed below:

l l 1

TS-vi TS-xi TS-xiii ,

TS.3.3 4 Figure TS.3.8-1 j Figure TS.3.8-2 Table TS.4.1-2B (Page 1 of 2) i Table TS.4.1-2B (Page 2 of 2)

TS.4.20-1 1 TS.S.6-1 l l TS.5.6-3 l l Figure TS.S.6-1 l l Figure TS.S.6-2  !

I Figure TS.S.6-3 i Figure TS.5.6-4 Figure TS.S.6-5 Figure TS.5.6-6 l Figure TS.S.6-7 l Figure TS.5.6-8 l Figure TS.5.6-9 Figure TS.S.6-10 Figure TS.S.6-11 Figure TS.S.6-12 B.3.8-2 B.3,8-3 l B.3.8-4 B.3.8-5 l B.4.20-1 l

l l

i l

i i

i

i TS-vi l REV l TABLE OF CONTENTS (Continued) l TS SECTION TITLE PAGE l l

i 4.12 Steam Generator Tube Surveillance TS.4.12-1 '

A. Steam Generator Sample Selection and TS.4.12-1 Inspection l B. Steam Generator Tube Sample Selection TS.4.12-1

! and Inspection l l

C. Inspection Frequencies TS.4.12-3 D. Ac'ceptance Criteria TS.4.12-4 E. Reports TS.4.12-5 4.13 Snubbers TS.4.13-1 4.14 Control Room Air Treatment System Tests TS.4.14-1 4.15 Spent Fuel Pool Special Ventilation System TS.4.15-1 4.16 Deleted 4.17 Deleted 4.18 Reactor Coolant Vent System Paths TS.4.18-1 A. Vent Path Operability TS.4.18-1 B. System Flow Testing TS.4.18-1 4.19 Auxiliary Building Crane Lifting Devices TS.4.19-1 ,

l 4.20 Spent Fuel Pool Storage Configuration TS.4.20-1 l l l

' \

i l

l I

1 ,

l TS-xi REV TABLE OF CONTENTS (continued)

TS BASES SECTION TITLE PAGE i

l 4.0 BASES FOR SURVEILLANCE REQUIREMENTS l 4.1 Operational Safety Review B.4.1-1 l 4.2 Inservice Inspection and Testing of Pumps B.4.2-1 l and Valves Requirements 4.3 Primary Coolant System Pressure Isolation B.4.3-1 Valves l 4.4 Containment System Tests B.4.4-1 l 4.5 Engineered Safety Features B.4.5-1 l 4.6 Periodic Testing of Emergency Power Systems B.4.6-1 l 4.7 Main Steam Isolation Valves B.4.7-1 l 4.8 Steam and Power Conversion Systems B.4.8-1 4.9 Reactivity Anomalies B.4.9-1 4.10 Deleted 4.11 Deleted 4.12 Steam Generator Tube Surveillance B.4.12-1 4.13 Snubbers B.4.13-1 4.14 Control Room Air Treatment System Tests B.4.14-1 l 4,15 Spent Fuel Pool Special Ventilation System B.4.15-1 4.16 Deleted 4.17 Deleted 4.18 Reactor Coolant Vent System Paths B.4.18-1 l 4.19 Auxiliary Building Crane Lifting Devices B.4.19-1 4.20 Spent Fuel Pool Storage Configuration B.4.20-1 l

I l

l i

I 1

l

+

TS-xiii REV l APPENDIX A TECHNICAL SPECIFICATIONS i

LIST OF FIGURES j TS FIGURE TITLE l 2.1-1 Reactor Core Safety Limits 3.1-1 Unit 1 and Unit 2 Reactor Coolant System Heatup Limitaticns )

3.1-2 Unit 1 and Unit 2 Reactor Coolant System Cooldown Limitations 3.1-3 DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit i Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity >1.0 uCi/ gram DOSE EQUIVALENT I-131 3.8-1 Spent Fuel Pool Unrestricted Region Burnup and Decay Time Requirements - 0FA Fuel 3.8-2 Spent Fuel Fool Unrestricted Region Burnup and Decay Time )

Requirements - STD Fuel  ;

3.10-1 Required Shutdown Margin Vs Reactor Boron Concentration 4.4-1 Shield Building Design In-Leakage Rate ,

1 5.6-1 Spent Fuel Pool Burned / Fresh Checkerboard Cell Layout 5.6-2 Spent Fuel Pool Checkerboard Interface Requirements 5.6-3 Spent Fuel Pool Checkerboard Region Burnup and Decay Tinie Requirements - 0FA Fuel, No GAD 5.6-4 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, No GAD 5.6-5 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, 4 CAD 5.6-6 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 4 GAD 5.6-7 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, 8 GAD 5.6-8 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 8 GAD i 5.6-9 Spent Fuel Pool Checkerboard Region Burnup and Decay Time )

Requirements - 0FA Fuel, 12 CAD I 5.6-10 Spent Fuel Pool Checkerboard Region Burnup and Decay Time ,

Requirements - STD Fuel, 12 GAD l 5.6-11 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, 16 or More CAD 5.6-12 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 16 or More CAD B.2.1-1 Origin of Safety Limit Curves at 2235 psig with delta-T Trips  ;

and Locus of Reactor Conditions at which SG Safety Valves Open

. . - .. . - - . - ~ . - - --. . . - -

i TS.3.8-4 REV 3.8.C. Small Spent Fuel Pool Restrictions No more than 45 recently discharged assemblies shall be located in the j small. pool (pool No. 1).  ;

4 D. Soent Fuel Pool Special Ventilation System

6

1. Both trains of the Spent Fuel Pool Special Ventilation System i shall be OPERABLE at all times (except as specified in 3.8.D.2 and l 3.8.D.3 below). I

2. With one train of the Spent Fuel Pool Special Ventilation System inoperable, fuel handling operations and crane operations with loads over spent fuel (inside the spent fuel pool enclosure) are permissible during the following 7 days, provided the redundant train is demonstrated OPERABLE prior to proceeding with those operations.

3. With both trains of the Spent Fuel Pool Special Ventilation System i inoperable, suspend all fuel handling operations and crane  !

operations with loads over spent fuel (inside the spent fuel pool l enclosure).  !

4 The provisions of specification 3.0.C are not applicable.

E. Soent Fuel Pool Storare i

1. Fuel u sembly Storage

a. The combination of initial enrichment, burnup and decay time' of j each spent fuel assembly stored in the spent fuel pool shall be I within the unrestricted range of Figures TS.3.8-1 or TS.3.8-2, as applicable. . or fuel assemblies shall be stored in accordance with Specification 5.6.A.1.e.

b. If the requirements of 3.8.E.1.a are not met, immediately initiate action to move any noncomplying fuel assembly to an acceptable location.

c. The provisions of Specification 3.0.C are not applicable. l

2. Spent Fuel Pool Boron Concentration

a. The spent fuel pool boron concentration shall be 2 1,800 ppm when fuel assemblies are stored in the spent fuel pool.

b. If the spent fuel pool boron concentration is not within limit, 3 then immediately: j l

1. Suspend movement of fuel assemblies in the spent fuel pool,  !

and

2. Initiate action to restore spent fuel pool boron  ;

concentration to within limit. I

c. The provisions of Specification 3.0.C are not applicable.

FIGURE TS.3.8-1 REV 40000 l 4  :

' 0 Years l 35000 / i

/, 5 Years ]

/! /, 10 Years l

^ I I/> $!II'E!

l llll

?

x 30000 /////

' / /M f

UNRESTFUCTED / //#

/ /M

!//# l o,25000 / fM p '

C //f//

Y ////f m fM/

M#

">20000 l

fH//

$ ////

g ur to ////

a 15000 >/// ,

$ /M l w /M l M

10000 j [

2

1. RESTRICTED I

5000 f

[

5

/

0 /

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)

FIGURE TS.3.8-1 Spent Fuel Pool Unrestricted Region Burnup and Decay Time Requirements - OFA Fuel

FIGURE TS.3.8-2 f

i REV j

! l l

l 40000 i I

l 1 0 Years g g j

! l /  !

' ' / / ' *****

i 35000 I / /- 10 Years i I / / /. 15 Years

// //

20 Years )

?

- / A /// i

/ / //# l S

E 30000  ! / / ///

i

~ l / ////

f UNRESTMCTED / ////

/ fAf/

a 25000 I/ ////

l :s

' C //f//

\ Y / VM i m / /Y// i

• >20000 l

t f/ff S ///#

//f//

m J///

15000

1. 1. i

\

a ////

//f/

% //M  !

M 10000 ['

/F E

RESTRICTED f

5000 [

}

[

l 0 / I 1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) l FIGURE TS.3.8-2 Spent Fuel Pool Unrestricted Region Burnup and Decay Time Requirements - STD Fuel l

i i

Table TS.4.1-2B (Page 1 of 2) ;

REV i TABLE TS.4.1-2B  ;

MINIMUM FREOUENCIES FOR SAMPLING TESTS i TEST FREO*JENCY  !

1. RCS Cross 5/ week ,

Activity Determination '

2. RCS Isotopic Analysis for DOSE 1/14 days (when at power)

EQUIVALENT I-131 Concentration  ;

3. RCS Radiochemistry E determination 1/6 months (1) (when at power) l i

4. RCS Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, whenever  !

Including I-131, I-133, and I-135 the specific activity ex- i ceeds 1.0 uCi/ gram DOSE _ j EQUIVALENT I-131 or 100/E  !

uCi/ gram (at or above cold ,

shutdown), and  ;

b) One sample between 2 and 6 i hours following THERMAL -

POWER change exceeding 15  !

percent of the RATED THERMAL  !

POWER within a one hour  !

period (above hot shutdown) j

5. RCS Radiochemistry (2) Monthly

6. RCS Tritium Activity. Weekly

7. RCS Chemistry (Cl*,F*, 02) 5/ Week

8. RCS Boron Concentration *(3) 2/ Week (4)

9. RWST Boron Concentration Weekly ,

i

10. Boric Acid Tanks Boron Concentration 2/ Week

11. Caustic Standpipe NaOH Concentiation Monthly

'12. Accumulator Boron Concentration Monthly

13. Spent Fuel Pit Boron Concentration Weekly l

R

Table TS.4.1-2B (Page 2 of 2) ,

REV j TABLE TS.4.1-2B lHE.IMUM FREOUENCIES FOR SAMPLING TESTS TEST FREOUENCY j l

14. Secondary Coolant Cross Weekly Beta-Gamma activity

]

15. Secondary Coolant Isotopic 1/6 months (5) j Analysis for DOSE EQUIVALENT I I-131 concentration I

16. Secondary Coolant Chemistry PH 5/ week (6) pH Control Additive 5/ week (6)

Sodium 5/ week (6)

Notes:

1

1. Sample to be taken after a minimum of 2 EFPD and 20 days of POWER I OPERATION have elapsed since reactor was last suberitical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 4 or longer.

2. To determine activity of corrosion products having a half-life greater  !

than 30 minutes. I

3. During REFUELING, the boron concentration shall be verified by chemical analysis daily.

4. The maximum interval between analyses shall not exceed 5 days.

5. If activity of the samples is greater than 10% of the limit in Speciff cation 3.4.D, the frequency shall be once per month.

6. The maximum interval between analyses shall not exceed 3 days.

i i

l TS.4.20-1

! REV l

4.20 Spent Fuel Pool Storace Configuration '

Apolicability This surveillance is applicable whenever fuel is stored in the spent fuel pool.

Obiective To verify that fuel assemblies in the spent fuel pool are stored in accordance with the requirements of Specification 3.8.E.1.a.

Specification A spent fuel pool inventory verification shall be performed within 7 days of the ,

completion of any fuel handling campaign which involves the relocation of fuel assemblies within the spent fuel pool or the addition of fuel assemblies to the spent fuel pool.

1 i

l l

l l

l l

l 1

l l

I l

l l

l

TS.5.6-1 REV l

5.6 FUEL HANDLING A. Criticality Consideration l l

1. The spent fuel storage racks are designed (Reference 1) and shall be l maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; l

b. Kerr < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Reference 3; i

c. Ke rr s 0.95 if fully flooded with water borated to 750 ppm, which  !

includes an allowance for uncertainties as described in Reference 3;

d. New or spent fuel assemblies with a combination of discharge burnup, initial enrichment and decay time in the unrestricted range of Figures TS.3.8-1 or TS.3.8-2, as applicable, may be alloned unrestricted storage in the spent fuel racks; and I

e. New or spent fuel assemblies with a combination of discharge burnup, initial enrichment and decay time in the restricted range of Figures TS.3.8-1 or TS.3.8-2, as applicable, will be stored in compliance with Figures TS.S.6-1 through TS.S.6-12.

2. The new fuel storage racks are designed (Reference 1) and shall be maintained with:

1

, a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;

, b. K e rr s 0.95 if fully flooded with unborated water, which includes i an allowance for uncertainties as described in Reference 2; and j c. K o rt s 0.98 if accidentally filled with a low density moderator which resulted in optimum low density moderation conditions.

3. Fuel will not be inserted into a spent fuel cask in the pool, unless a minimum boron concentration of 1800 ppm is present. The 1800 ppm will ensure that k e er for the spent fuel cask, including statistical uncertainties, will be less than or equal to 0.95 for all postulated arrangements of fuel within the cask. The criticality analysis for the TN-40 spent fuel storage cask was based on fresh fuel enriched to 3.85 weight percent U-235.

B. Spent Fuel Storate Structure The spent fuel storage pool is enclosed with a reinforced concrete building having 12- to 18-inch thick walls and roof (Reference 1).

The pool and pool enclosure are Class I (seismic) structures that afford protection against loss of integrity from postulated tornado missiles. The storage compartments and the fuel transfer canal are connected by fuel transfer slots that can be closed off with pneumatically sealed gates. The bottoms of the slots are above the tops of the active fuel in the fuel assemblies which will be stored vertically in specially constructed racks.

l l TS.S.6-3 REV 1

D. Spent Fuel Storar.e Capacity The spent fuel storage facility is a two-compartment pool that, if completely filled with fuel storage racks, provides up to 1582 storage locations. The southeast corner of the small pool (pool no. 1) also serves as the cask lay down area. During times when the cask is being used, four racks are removed from the small pool. With the four l storage racks in the southeast corner of pool 1 removed, a total of 1386 storage locations are provided. To allow insertion of a spent fuel cask, total storage is limited to 1386 assemblies, not including those assemblies which can be returned to the reactor.

1 I

I Reference I l

1. USAR, Section 10.2 i

2. " Criticality Analysis of the Prairic Island Units 1 & 2 Fresh and Spent l Fuel Racks", Westinghouse Commercial Nuclear Fuel Division, February 1993. l

3. " Northern States Power Prairie Island Units 1 and 2 Spent Fuel Rack l Criticality Analysis Using Soluble Boron Credit", Westinghouse Commercial l j Nuclear Fuel Division, February 1997. j i  !

i

a FIGURE TS.S.6-1

' REV  !

k 4

E E E I

]

l E E E 1

E E E .

j Fresh Fuel: Must be less than or equal to nominal 4.95 w/o 23sU 3

- ,(:,,,$,$j55$

+*. No restrictions on burnup ,

Burned Fuel: Must satisfy minimum burnup requirements of Figures TS.5.6-3 through TS.5.6-12 depending i on number of GAD rods in fresh fuel 4

FIGURE TS.S.6-1 Spent Fuel Pool Burned / Fresh Checkerboard Cell Layout a

l FIGURE TS.5.6-2 REV i

l Interface

'~

l ER l lE EE l

4 I EE

! l

}

i

.;.;.;.;.: Fresh Fuel: Must be less than or equal to k,~~' nominal 4.95 w/o "U l

~

No restrictions on burnup i Burned Fuel: 3x3 Checkerboard Region

Must satisfy minimum burnup requirements

! of Figures TS.5.6-3 through TS.5.6-12 i

l \ Burned Fuel: All Cell Unrestricted Region N Must satisfy minimum burnup requirements of Figures TS.3.8-1 or TS.3.8-2 l

1 i

l l

j FIGURE TS.S.6-2 Spent Fuel Pool Checkerboard Interface Requirements 1

i t

l

}

t FIGURE TS.5.6-3

' REV 55000 ' ,,

i i i

i i i ,

i i , 0 Years 50000 jl ', /

l

, j j 5 Years

/ / 10 Years l j pj 45000 , , ,

j f /f '

!! N'S f f f ff" g ACCEPTABLE I I I 6 / / / //

b ' ' ' ' ' "

z 40000 e / / / //

O I f f///

f / / ///

f l / ////

~

g 35000 a / / / //

p t / / ///

C .

• / / ///

4 l e / / ///

0 l * / / ///

ca 30000 , f f fiff 6 > fif /;f

> '/ / ///

e /J /Af i /4 / ///l fe 25000 f f f,7 in / ////

to / ////

4 / ///)

a 20000 ' ' 'f' i fff 0 f ////

f //M \

///// I f /)ff '

15000 fef , ,

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f7 F

5000

) l s

1 0 1 1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)

TS.5.6-3 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, No GAD 1

l

i FIGURE TS.5.6-4 REV I

60000 l } I i 0 Years

\

,/ 5 Years '

50000 I / // '

ACCEPTAKE / l/ // 20 Years 5 l l / / ///

N  ! / ///

$ / / ///

b 40000

~

I A ////

/ ////

5 / ////

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20000 w //#/

/HP M/[ NOT ACCEPTAKE

\

///

10000

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1 0 [

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)

TS.5.6-4 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, No GAD

1

! i i

l I

FIGURE TS.S.6-5 f l

' REV l

l I

60000  ;

i l

l I

50000 ACCEPTABLE

- l o Years p

/ '

5 Years

> 10 Years O

b 40000 I ///2 !! N'S

~ ////

? ////

0 ///Y E AUf

> 30000 E /N/

$ /f/

$ ////

////

20000 w ///

///

/AV

// NOT ACCEPTABLE

' 2 10000 1 >

)F -

/

/

0 /

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) l

! TS.S.6-5 Spent Fuel Pool Checkerboard Region Burnup and Decay Time i Requirements - 0FA Fuel, 4 GAD i

l 1

l l

FIGURE TS.S.6-6 l REV i

1

?

60000 l l .

I ,

I ***"

50000 I /

/ j 5 Years n / /, 10 Years 0 / //j is vaars

& / ////

l 40000 I / ////

/ ////  :

Q.

/ /bV  ;

E / /4'/

M / ////

I / ////

h 30000 I !////

i

$ ///// '

8 //Hf 2 ////  !

rd

/8/8 .l

$ 20000 /Hf NY  ;

Hf

/2I NOT ACCEPTABt.E i 10000 M'

V A

I O [

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)

TS.5.6-6 Spent Fuel Fool Checkerboard Region Burnup and Decay Time  !

Requirements - STD Fuel, 4 GAD f i

l l

FIGURE TS.S.6-7 REV 50000 _ ,

i i

i i ,

I $ 1 1 45000 ,

I ' > 0 Years

/

ACCEPTABLE ' /> s Years 40000 #'#

rj 10 Years 3P l g

j f gj 20 15 Years Years

.E , fffg N ' ' ' / //'

O 35000

• f / /// i

/\ / //f

_f f / ///

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a ' /M' D

C 30000 $ /\ / <//

4 t/ ////

/ //// ,

$ / ////

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B.3.8-2 REV 3.8 REFUELING AND FUEL HANDLING Bases continued During movement of irradiated fuel assemblies or control' rods, a water level of 23 feet is maintained to provide sufficient shielding.

T The water level may be lowered to the top of the RCCA drive shafts for latching and unlatching. The water level may also be lowered below 20 feet for upper internals removal / replacement. The basis for these allowance (s) are (1) the refueling cavity pool has sufficient level to l allow time to initiate repairs or emergency procedures to cool the  :

core, (2) during latching / unlatching and upper internals removal / replace-ment the level is closely monitored because the activity uses this level as a reference point, (3) the time spent at this level is minimal.

The Prairie Island spent fuel storage racks have been analyzed (Reference

8) in accordance with the methodology contained in Reference 5. That methodology ensures that the spent fuel rack multiplication factor, Kerr.  :

is less than 0.95 as recommended by ANSI 57.2-1983 (Reference 6) and NRC '

guidance (Reference 7). The codes, methods and techniques contained in the methodology are used to satisfy this criterion on K.tr. The resulting Prairie Island spent fuel rack criticality analysis allows for the storage of fuel assemblies with enrichments up to a maximum of 5.0 weight percent U-235 while maintaining K.tr s 0.95 including uncertainties and credit for soluble boron. In addition, sub-criticality of the pool (K err

< l.0) is assured on a 95/95 basis, without the presence of the soluble t boron in the pool. Credit is taken for radioactive decay time of the spent fuel and for the presence of fuel rods containing Gadolinium burnable poison.

The Prairie Island specific criticality analysis (Reference 8) utilized ,

the following storage configurations to ensure that the spent fuel pool l will remain suberitical during the storage of fuel assemblies with all l

. possible combinations of burnup and initial enrichment: 1

1. The first storage configuration utilizes a checkerboard loading ,

pattern to accommodate new or low burnup fuel with a maximum I enrichment of 5.0 wt% U-235. This configuration stores " burned" and

" fresh" fuel assemblies in a 3x3 checkerboard pattern as shown in Figure TS.S.6-1. Fuel assemblies stored in " burned" cell locations are selected based on a combination of fuel assembly type, initial enrichment, discharge burnup and decay time (Figures TS.S.6-3 through TS.5.6-12). The criteria for the fuel stored in the " burned" locations is also dependent on the number of rods containing Gadolinium in the center " fresh" fuel assembly. The use of empty cells is also an acceptable option for the " burned" cell locations. l This will allow the storage of new or low burnup fuel assemblies in the outer rows of the spent fuel storage racks because the area outside the racks can be considered to be empty cells.

l B.3.8-3 REV 3.8 REFUELING AND FUEL HANDLING  !

Bases continued Fuel assemblies that fall into the restricted range of Figures TS.3.8-1 or TS.3.8-2 are required to be stored in " fresh" cell locations as shown in Figure TS.5.6-1. The criteria included in Figures TS.3.8-1 and TS.3.8-2 for the selection of fuel assemblies to be stored in the " fresh" cell locations is based on a combination of fuel assembly type, initial enrichment, decay time and discharge burnup.

2. The second storage configuration does not utilize any special loading pattern. Fuel assemblies with burnup, initial enrichment and decay time which fall into the unrestricted range of Figures TS.3.8-1 or Ts.3.8-2, as applicable, can be stored anywhere in the region with no special placement restrictions.

The burned / fresh fuel checkerboard region can be positioned anywhere within the spent fuel racks, but the boundary between the checkerboard region and the unrestricted region must be either:

1. separated by a vacant row of cells, or #

2. the interface must be configured such that there is one row carryover of the pattern of burned assemblies from the checkerboard region into the first row of the unrestricted region (Figure TS,5.6-2).

Specifications 3.8.E.1, 5.6.A.1.d and 5.6.A.1.e ensure that fuel is stored in the spent fuel racks in accordance with the storage configurations assumed in the Prairie Island spent fuel rack criticality analysis (Reference 8).

The Prairie Island spent fuel pool criticality analysis addresses all the fuel types currently stored in the spent fuel pool and in use in the reactor. The fuel types considered in the analysis include the Westinghouse Standard (STD), OFA, and Vantage Plus designs, and the Exxon fuel assembly types in storage in the Prairie Island spent fuel pool.

The OFA designation on the figures in Sections 3.8 and 5.6.A bound all of the Westinghouse OFA and Vantage Plus fuel assemblies at Prairie Island.

The STD designation on the figures in Sections 3.8 and 5.6.A bound all of the Westinghouse STD and Exxon fuel assemblies at Prairie Island.

Most accident conditions in the spent fuel pool will not result in an increase in K.tr of the racks in either of the two storage configurations.

Examples of those accident conditions which will not result in an increase in K e rr are a fuel assembly drop on the top of the racks, a fuel assembly drop between rack modules and wall (rack design precludes this condition), and a drop or placement of a fuel assembly into the cask loading area of the small pool. However, two accidents can be postulated which could increase reactivity. The first postulated accident would be a loss of the fuel pool cooling system and the second would be a misload of a fuel assembly into a cell for which the restrictions on location, enrichment, burnup, decay time or Gadolinium credit are not satisfied.

B.3.8-4 l REV j

\

4 3.8 BEFUELING AND FUEL HANDLING Bases continued For an occurrence of these postulated accident conditions, the double contingency principle of ANSI /ANS-8.1-1983 can be applied. This states '

that one is not required to assume two unlikely, independent, concurrent events to ensure protection against a criticality accident. Thus, for these postulated accident conditions, the presence of additional soluble boron in the spent fuel pool water (above the 750 ppm required to maintain K,gg less than 0.95 under normal conditions) can be assumed as a realistic initial condition since not assuming its presence would be a second unlikely event.

1 Calculations were performed (Reference 8) to determine the amount of j

., soluble boron required to offset the highest reactivity increase caused l

. by either of these postulated accidents and to maintain K,gg less than or l equal to 0.95. It was found that a spent fuel pool boron concentration  !

of 1300 ppm was adequate to mitigate these postulated criticality related l accidents and to maintain K err less than or equal to 0.95. Specification !

3.8.E.2 ensures the spent fuel pool contains adequate dissolved boron to {

compensate for the increased reactivity caused by a mispositioned fuel l assembly or a loss of spent fuel pool cooling. The 1800 ppm spent fuel i pool boron concentration limit in Specification 3.8.E.2 was chosen to be l consistent with the boron concentration limit required by Specification '

3.8.B.1.c for a spent fuel cask containing fuel.

Specification 5.6. A.1.c requires that the spent fuel rack K rt be less o

than or equal to 0.95 when flooded with water borated to 750 ppm. A spent fuel pool boron dilution analysis was performed which confirmed

, that sufficient time is available to detect and mitigate a dilution of the spent fuel pool before the 0.95 K rre design basis is exceeded. The spent fuel pool boron dilution analysis concluded that an unplanned or inadvertent event which could result in the dilution of the spent fuel pool boron concentration from 1800 ppm to 750 ppm is not a credible event. j 1

When the requirements of Specification 3.8.E.1.a are not met, immediate action must be taken to move any non complying fuel assembly to an acceptable location to preserve the double contingency principle assumption of the criticality accident analysis.

1' When the concentration of boron in the spent fuel pool is less than required by Specification 3.8.E.2.a. immediate action must be taken to preclude the occurrence of an accident or to aitigate the consequences of an accident in progress. This is most efficiently achieved by immediately suspending the movement of fuel assemblies. The concentration of boron is restored simultaneously with suspending movement of fuel assemblies. The suspension of fuel movement is not intended to preclude movement of a fuel assembly to a safe position.

B.3.8-5 REV 3.8 REFUELING AND FUEL HANDLING Bases continued References

1. USAR, Section 10.2.1.2

2. USAR, Section 14.5.1

3. USAR, Section 10.3.7

4. " Criticality Analysis cf the Prairie Island Units 1 & 2 Fresh and Spent Fuel Racks", Westinghouse Commercial Nuclear Fuel Division.

February 1993.

5. WCAP-14416-NP-A, " Westinghouse Spent Fuel Rack Criticality Analysis Methodology", Revision 1, November 1996.

6. American Nuclear Society, "American National Standard Design Requirements for Light Water Reactor Fuel Storage Facilities at Nuclear Power Plants", ANSI /ANS-57.2-1983, October 7, 1983.

7. Nuclear Regulatory Commission, Letter to All Power Reactor Licensees from B. K. Grimes, "OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications", April 14, 1978.

8. " Northern States Power Prairie Island Units 1 and 2 Spent Fuel Rack Criticality Analysis Using Soluble Boron Credit", Westinghouse Commercial Nuclear Fuel Division, February 1997.

l i

t i

B.4.20-1 REV 4.20 Soent Fuel Pool Storane Configuration l

Bases This surveillance verifies that the fuel assemblies in the spent fuel storage racks are stored in accordance with the requirements of Specifications 3.8.E.1, 5.6.A.1.d and 5.6.A.l.e.

The surveillance is required to be completed within 7 days after the completion of any fuel handling campaign which involves the relocation of fuel assemblies within the spent fuel pool or the addition of fuel assemblies to the spent fuel pool. The extent of a fuel handling campaign will be defined by plant administrative procedures. Examples of a fuel handling campaign would include all of the fuel handling performed during a refueling outage or associated with the placement of new fuel into the i spent fuel pool. l It is not the intent of this surveillance to require the completion of a l spent fuel pool inventory verification during interruptions in fuel I handling during a defined fuel handling campaign. No spent fuel pool i inventory verification is required following fuel movements where no fuel  :

assemblies are relocated to different spent fuel rack locations. ,

The 7 day allowance for completion of this surveillance provides adequate  !

time for the completion of a spent fuel pool inventory verification while l minimizing the time a fuel assembly may be misloaded in the spent fuel  !

pool. If a fuel assembly is misloaded during a fuel handling campaign, the ,

minimum boron concentration required by Specification 3.8.E.2 will. ensure i that the spent fuel rack K.tr remains within limits until the spent fuel pool inventory verification is performed.  !

l I

1 I

, . - . . - - - . . .. ~ . . . - . . . . - . - _ - , , - _ - . , = . , _ - - . . - _ - . .. ,

! .I 1

Exhibit D

, Prairie Island-Nuclear Generating Plant l February 21, 1997 Revision to l License Amendment Request Dated July 28, 1995

, Prairie Island Spent Fuel Pool Dilution Analysis 1

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