ML17229A569

Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity

ML17229A569
Person / Time
Site:	Saint Lucie
Issue date:	12/31/1997
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229A570	List: ML17229A569 ML17229A571 ML17309A916 ML17309A917
References
NUDOCS 9801070050
Download: ML17229A569 (18)

Text

St.Lucie Unit 2 Docket No.50-389 Proposed License Amendment SERB S~~~ST.LUCIE UNIT 2 MARKED-UP TECHNICAL ESPECIFICATION PAGES Page XXII (INDEX-LIST OF FIGURES)Page 5-4 INSERT-A Page 5-4A Proposed Figure 5.6-1a Proposed Figure 5.6-1b Proposed Figure 5.6-1c Proposed Figure 5.6-1d Proposed Figure 5,6-1e~80gg70050 97<>3<89 POR ADQCK 05000 II I I l LIST OF FIGURES (Continued)

RXXXQ'S INDEX L-97-325, Attachment 3 FIGURE 3.4-3 3.4-4 REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITATIONS FOR 15 EFPY, COOLDOWN AND INSERVICE TEST...............

REACTOR COOLANT SYSTEM PRESSURE-TEHPERATURE LIMITATIONS FOR 15 EFPY, MAXIMUM ALLOWABLE COOLDOWN RATES..........

PAGE 3/4 4-31b 3/4 4-32 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST.............

3/4 7-25 B 3/4.4-1 NIL-DUCTILITY TRANSITION TEHPERATURE INCREASE AS A FUNCTION OF FAST (E)1 HeV)NEUTRON FLUENCE (550 F IRRADIATION)

FOR REACTOR VESSEL BELTLINE MATERIALS....

B 3/4 4-10 5.1-1 ITE AREA HAPo~~~o~~~~~o~~~~~~~~~~~~~o~~~~~o~~~~~oooo'f86HHE~FS-.BURNU~U9tEHBfPr~k PAIRABE-eF-RIR-A osooo-o'o 5-2 6.2-1 6.2-2 ELETED~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~o~~~~~o~~~~~D ELETED o o~~~~~~~~o~~~~~~~~~~~~~~o~o~~~~~o~~~~~o~~~~o~D 6-3 6-4 5.6-1a I 5.6-1b I 5.6-1c REQUIRED FUEL ASSEMBLY BURNUP vs INITIAL ENRICHMENT and DECAY TIME, REGION ZI, 1.3 w/o REQUIRED FUEL ASSEMBLY BURNUP vs INITIAL ENRICHMENT and DECAY TIME, REGION ZZ, 1.5 w/o REQUIRED FUEL ASSEMBLY BURNUP vs INITIAL ENRICHMENT and DECAY TIME, REGION I, 1.4 w/o 5.6-1e REQUIRED FUEL ASSEMBLY BURNUP vs ZNZTIAL ENRICHMENT and DECAY TIME, REGION I, 1.82 w/o REQUIRED FUEL ASSEMBLY BURNUP vs INZTIAL ENRICHMENT'EGION Ig 2 82 w/o ST.LUCIE-UNIT 2 XXII Amendment No.~

~~~P C t W~P f~P y'Ig Iy~~'4 I/P~i)/'py y~8 a~4 JA DESIGN FEATURES I L-97-325, Attachment 3, VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,931+275 cubic feet at a nominal Tof 572'F.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

.6.1 The spent fuel storage racks are designed and shall be mai ined with:~pe&~e~~s<<~i'J f f equi val ent to 1 ess than or equal to 0 when f 1 ooded wi unborated'ater, which includes a co ervative al lowance of 0.4 hk ff for Total Uncertainty.

eff 2.A nominal 8.inch center-to-c er distance between fuel assemblies pla in the sto ge racks.3.A boron concentra i eater than or equal to 1720 ppm.Region I can be used store fu which has a U-235 enrichment less than or equa o 4.5 weight pe ent'.Region II can be used to store fuel ch has achieved suffi ent burnup such that storage in gion I is not required.The nitial enrichment vs.burnup r uirements of Figure 5.6-1 shall be et prior to storage of f assemblies in Region II.b.he new fuel storage racks are designed for dry stora of unirradiated fuel assemblies having a U-235 enrichment 1 than or equal to 4.5 weight percent, while maintaining a k<<o ess than or equal to 0.98 under the most reactive conditi5h.

DRAINAGE 5.6.2 The spent fuel storage pool is'designed and shall be maintained to prevent inadvertent draining of the pool below elevation 56 feet.CAPACITY 5.6.3 The spent fuel storage pool is de ned and shall be maintained with a storage capacity limited to no more than fuel assemblies.

5.7 COMPONENT

CYCLIC OR TRANSIENT LIMITS f,560 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.ST.LUCIE-UNIT 2 5-4 Amendment No.

j+pal~V lp j f ly e Cl'(~)~.I'.ig~p~y>~k St.Lucie Unit 2 Docket No.50-389 Proposed License Amendment~~~y'A I hI H.'-97-325, Attachment 3 INSERT-A to L-97-325, Attachment 3 5.6.1 a.The spent fuel pool and spent fuel storage racks shall be maintained with: A k,<<equivalent to less than 1.0 when flooded with unborated water, including a conservative allowance for biases and uncertainties.

2.A k,<<equivalent to less than or equal to 0.95 when flooded with water containing 520 ppm boron, including a conservative allowance for biases and uncertainties.

3.A boron concentration greater than or equal to 1720 ppm.A nominal 8.96 inch center-to-center distance between fuel assemblies placed in the storage racks.5.6.1 b.Fuel placed in Region I of the spent fuel storage racks shall be stored in a configuration that will assure compliance with 5.6.1 a.1 and 5.6.1 a.2, above, with the following considerations:

Fresh fuel shall have a nominal average U-235 enrichment of less than or equal to 4.5 weight percent.2.The reactivity effect of CEAs placed in fuel assemblies may be considered.

3.The reactivity equivalencing effects of burnable absorbers may be considered.

The reactivity effects of fuel assembly burnup and decay time may be considered as specified in Figures 5.6-1c through 5.6-le~5.6.1 c.Fuel placed in Region ZI of the spent fuel storage racks shall be placed in a configuration that will assure compliance with 5.6.1 a.l and 5.6.1 a.2, above, with the following considerations:

Fuel placed in Region EI shall meet the burnup and decay time requirements specified in Figure 5.6-1a oz 5.6-1b.2~The reactivity effect of CEAs placed in fuel assemblies may be considered.

3.The reactivity equivalencing effects of burnable absorbers may be considered.

5.6.1 d.The new fuel storage racks are designed for dry storage of unirradiated fuel assemblies having a U-235 enrichment less than or equal to 4'weight percent, while maintaining a k,<<of less than or equal to 0.98'nder the most restrictive condition.

~~..~e~'I t'~

L-97-325, Attachment 3 t 30,000 B RNUP REQUIRED FOR ST GE IN REGION II BURN=(11r200)X (ENRICHMENT I/O-13,900 l0,000 0 lB 0 2S 3.0 384.0 4S'.0 INITIAL U-235 ENRICHMENT, M/0 pppg,cE.wivh PRoposzD F'LGoREs~.(-ia.4rQ6'4-'t~

shan~o~+4e@ex+8 pge.~.~llje EN~CURNU~EQM-REMENTS-FG~ONrG~F FUEL-ASSEMB&~I&-RES+6~ST.LUCIE-UNIT 2 AMENDMENT NO.M Re-wwl,gi a~esP>

I t~I f/t e (9k H I H fa4V~Jjg~~t~P j3 Q 4u o~o~o sq 3 Pel.~~~a P Fpgy4'~'0 P g(>'g+++4P f~+~'~4,aw4 l~a~~4 e~4~4~/i P~'V ey~~/gf,j Is&!S~~~'P A A'4 PO~~r~~sg 0'4A//gnaw~=~JW,a~$J 0 Figure 6.6-1a Required Fuel Assembly Burnup vs initial Enrichment and Decay Time Region ll,1.3 w/o 0 years-40000-CL~c 300M E I~20000~Cl E 10000~Acceptable Bumup 5 years 10 years 15 years 20 years 0 2.0 2.5 3.0 3.5 4.0 4.5 5.0 initial U-235 Enrichment (w/0) f*~'

Figure 5.6-1b Required Fuel A'ssembly Burnup vs initial Enrichment and Decay Time Region ll, 1.5 w/o 0 years D 30000.I CL C I ro 8)20000 4 6 I 10000 LL Acceptable Bu mup 5 years 10 years 15 years 20 years 1.5 2.0 2.5 3.0 3.5 InlUal U-235 Enrichment (w/o)-4.0 4.5 5.0 t t, V'~,

Figure 5.6-1c.Required Fuel Assembly Burnup vs initial Enrichment and Decay Time Region l, 1.4 w/o 40000 I 30000 F I~20000 10000 0 1.5 2.0 Acceptable Bumup 2.5 3.0 3.5 Initial U-235 Enrichment (w/o)4.0 0 years years 10 years 15 years 20 years 4.5 CO hJ 50 r+P+

Figure 5.6-1 d.Required Fuel Assembly Burnup vs initial Enrichment and Decay Time Region l,1.82 wlo 0 years 25000 A K CL~20OOO IQ~>>15OOO n 10000 Acceptable Bumup 5 years 10 years 20 yeats I CO 4l Ql 2.0 2.5 3.0 3.5 IniUal U-235 Enrichment (wlo)4.0 4.5 50 r+GD Figure 5.6-1 e 15000 Required Fuel Assembly Burnup vs Initial Enrichment Region l, 2.82wlo 0 years 10000 O E 5000 Accap tabb Butnup>-464.82'3+46045'P2 6066 6'E-7T63.1 1.5 2.0 2.5 3.0 3.5-lnltlal U-235 Enrichment (wlo)4.0 4.5 5.0 St.Lucie Unit 2 Docket No, 50-389 Proposed License Amendment SH'torag~apacit~otubleJ3 St.Lucie Unit 2 Criticality Safety Analysis for the Spent Fuel Storage Rack Using Soluble Boron Credit, CENPD-387:

Combustion Engineering, Inc., October 1997.