ML18106B053

Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel

ML18106B053
Person / Time
Site:	Salem
Issue date:	02/02/1999
From:	Public Service Enterprise Group
To:
Shared Package
ML18106B052	List: ML18106B050 ML18106B053 ML18106B054
References
NUDOCS 9902090146
Download: ML18106B053 (4)

Text

DESIGN FEATURES

a. In accordance with the code requirements specified in Section 4.1 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 2485 psig, and

c. For a temperature of 650°F, except for the pressurizer which is 680°F.

VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12,446 +/- 426 cubic feet at a nominal Tavg of 573°F.

I 5.5 METEOROLOGICAL TOWER LOCATION 5.5.l The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY 5.6.l.l The ne~ fuel storage racks are designed and shall be maintained with:

a. A maximum Ketf equivalent of 0.95 with the storage racks flooded with unborated water.

b. A nominal 21.0 inch center-to-center distance between fuel assemblies.

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5.6.l.2 The spent fuel storage racks are designed and shall be maintained with:

a. A maximum K.ff equivalent of 0.95 with the storage racks filled with unborated water.

b. A nominal 10.5 inch center-to-center distance between fuel aaaemblies stored in Region 1 (flux trap type) racks.

c. A nominal 9.05 inch center-to-center distance between fuel assemblies stored in Region 2 (non-flux trap) racks.

d. Fuel assemblies stored in Region l racks shall meet one of the following storage constraints.

l. Unirradiated fuel assemblies with a maximum enrichment of 4~25 w/o U-235 have unrestricted storage.

SALEM - UNIT l 5-5 Amendment No. 201 9902090146 990202 r:--~ I PDR ADOCK 050002721 p PDRLl

DESIGN FEATURES

2. Unirradiated fuel assemblies with enrichment* greater than 4.25 w/o U-235 and l~ss than or equal to 5.0 w/o U-235, th£t do not contain Integral Fuel Burnable Ab*orber (IFBA) pin.s, m&y only be stored in the perit:"; ... ral cells facing th* concrete wall.

3. Unirradiated fuel assembli** with enrichment* (E) greater than 4.25 w/o U-235 and l*** than or equal to 5.0 w/o U-235, that eenta!n IRI. n.U wid\ a nominal 2.35 111 1*10/Uzwar inch leading, and a m*mber of IF!A. rod.a.equal to or greater than th*

RYaber determined by th* equatien below, ha¥9 Ynraatristad ster*1**

N

• 42.67 (!-alt,2S)

4. Irradiated fuel aaaemblie* with enrichments (!) greater than 4.25 w/o U-235 and lea* than or equal to 5.0 v/o, that havft attained the minimum burnup (BU) ** determined by th* ~qu.ation balow, have unrestricted storage.

BU (MWD/\tg U) - -26.212 + 6.t677E

a. Fuel assemblies 1tored in Region 2 rack9 shall 1Het one of tht3 following storage conatrainta.

l. Unirradiatad fuel as*ellbli** with a maxi.um anricl"ulaGnt of 5.0 w/o U-235 ma.y be stored in a checkerboard pattern vith intat'Ilediat* cells cont&ining only water or non*fi3ailJ ~aa=i~g IUtsria.l.

2. Unirradbted fuel asaemblie* with a maxi.mull ilnric~nt (3) .)f S. 0 v/o U-235 may be stored. in the central cell. of my J:t3 array of celh provided the surrounding eight cdls ara 3~ty or conta.in fu.l uHllbli** that have attained the rilini;:rum burnup (BU) u determined by th* equation below.

2 BU (MYiD/k3 U) * -15.48 + 17.80!

• 0.7038!

In this configuration, none of the nine calla in "tJ.nY 3~J ~rray shall be colllliOn to cells in any other ai.Jlilar 3x3 ~rray. .~long th* rsck periphery, the concrete wall 11 equiv:lhine to J *Jutsr cell3 in a 3x3 array.

3. Ine.diatad fuel aaHmbli** llith a ll.!IXimua 81U'ic~nt ( ~) *J E 5. u Y/o U-235 th£t have attained th* mini.mull burtl\.ll) (BU) -1.;ll detsrained by the equation below, have unreatrict:ad .1tora~a.

2 3 BU (i'ND/kg U) - -32.06 + 25.21!

• 3.723! + 0.3535!

4. Irradiated fual asserablia* vi th a maximum enrichmont <~ l ) :: ) . 0 w/o U-235 that have attained the 11ini.Jlua burnup (BU) .J.3 detGrmined by the eqU&tion belov, may be storl!ld in a ?"' r ~?hHal cell facing the concrete wall.

BU (l'NO/ltg U) * -2~.:~

• 15.L~i

• 0.6021 2

SALEM

• UNIT 1 5-6 Amendment No. 151

DESIGN FEATURES

=======================:==========================================

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY 5.6.1.l The new fuel storage racks are designed and shall be maintained with:

a. A maximum K.~~ equivalent of equal to 0.95 with the storage racks flooded with unborated water.

b. A nominal 21.0 inch center-to-center distance between fuel assemblies.

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5.6.1.2 The spent fuel storage racks are designed and shall be maintained with:

a. A maximum Keff equivalent of 0.95 with the storage racks filled with unborated water.

b. A nominal 10.5 inch center-to-center distance between fuel assemblies stored in Region 1 (flux trap type) racks.

c. A nominal 9.05 inch center-to-center di~tance be:wcen fuel assemblies stored in Region 2 (non-flux trap) racks.

d. Fuel assemblies stored in Region 1 racks shall meet one of the following storage constraints.

1. Unirradiated fuel assemblies with a maximum enrichment of 4.25 w/o U-235 have unrestricted storage.

2. Unirradiated fuel assemblies with enrichments greater than 4.25 ~/o U-235 and less than or equal to 5.0 w/o U-235, that do not contain Integral Fuel Burnable Absorber (IFBA) pins, may only be stored in the peripheral cells facing the concrete wall.

3. Unirradiated fuel assemblies with enrichments (E) greater than 4.25 w/o U-235 and less than or equal to 5.0 w/o U-235, t,hat: coi::ita in LE.M_r_ods wi tb a ~.om-:'h-r-ra+/--2'.73-5-mg-lt.=J.-G-,Ll.i.ne.ai::...

.i-nch load:i:!ig, and a nmn:b-er-c;f"-lttl1~:-rud:s-e~

~e-r--1-e-t=e-rm:i.-ne~e-equ.a..t,_ion-he..1ew,-ha..v:e tlT'l restricted --s~*~-e-.

SALEM - UNIT 2 5-5 Amendment No. 131

Document Control Desk e

LRN990056 LCR 898-017 TECHNICAL SPECIFICATION CHANGE REQUEST PERMISSIBLE ENRICHMENT VALUES FOR NEW FUEL STORAGE SALEM GENERATING STATION FACILITY OPERATING LICENSES DPR-70 AND DRP-75 DOCKET NOS. 50-272 AND 50-311 CRITICALITY ANALYSIS OF SALEM UNITS 1 AND 2 FRESH FUEL RACKS