ML20072A192

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Proposed Tech Specs 5.3 Re Reactor Core Design Features
ML20072A192
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 08/04/1994
From:
SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20072A182 List:
References
NUDOCS 9408120170
Download: ML20072A192 (9)
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l Attachment 1 Revised Technical Specification Pages Unit 1 Revision Paga 5-6 Replace Page 5-7 Replace Unit 2 Revision Page 5-6 Replace Page 5-7 Replace (Change Markups Follow Technical Specification Pages) i i

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9408120170 940804 PDR ADOCK 05000348 P PDR

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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 157 fuel assemblies. Each assembly shall consist of a matrix of zirconium alloy, zircaloy-4, or ZIRLO fuel rods with an i initial composition of natural or slightly enriched uranium dioxide (UO ) 2 as fuel material.

Limited substitutione of zirconium alloy, zircaloy-4, ZIRLO , or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed t

representative testing may be placed in non-limiting core regions.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 control rod assemblies. The control a material shall be silver, indium and cadmium as approved by the NRC.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 5.2 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 9723 i 100 cubic feet at a nominal Tavg of 525*F.

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

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l FARLEY-UNIT 1 5-6 AMENDMENT NO. i l

1 DESIGN EEATURES I

5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Keff less than or equal to 0.95 when flooded with unborated water,  !

which includes conservative allowances for uncertainties and biases. l

b. A nominal 10.75 inch center-to-center distance between fuel l l assemblies placed in the storage racks,
c. A maximum nominal enrichment of:
1. 4.25 weight percent U-235 for Westinghouse LOPAR fuel assemblies.
2. 5.0 weight percent U-235 for Westinghouse OEA or VANTAGE-5 fuel assemblies. Westinghouse OEA and VANTAGE-5 fuel with maximum nominal enrichments greater than 3.9 weight percent U-235 shall contain sufficient integral burnable absorbers  ;

such that a maximum reference fuel assembly w K less than or  !

tqual to 1.455 at 68*F is maintained.

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

a. Keff less than or equal to 0.98, assuming aqueous foam moderation.

t

b. A nominal 21 inch center-to-center distance between new fuel assemblies placed in the storage racks,
c. A maximum nominal enrichment of:
1. 4.25 weight percent U-235 for Westinghouse LOPAR fuel ,

assemblies.

2. 5.0 weight percent U-235 for Westinghouse OEA or VANTAGE-5 fuel assemblies. Westinghouse OEA and VANTAGE-5 fuel with maximum nominal enrichments greater than 3.9 weight percent U-235 shall contain sufficient integral burnable absorbers such that a maximum reference fuel assembly Kw less than or equal to 1.455 at 68*F is maintained.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 149.

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 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.

EARLEY - UNIT 1 5-7 AMENDMENT NO.

DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 157 fuel assemblies. Each assembly shall consist of a matrix of zirconium alloy, zircaloy-4, or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO 2) as fuel material.

Limited substitutions of zirconium alloy, zircaloy-4, ZIRLO , or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC-approved codes and methods, and shown by tcsts or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 control rod assemblies. The control material shall be silver, indium and cadmium as approved by the NRC.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

a. In accordance with the code requiren4ents specified in Section 5.2 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 f or the pressurizer which is 680'F.

VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 9723 1 100 cubic feet at a nominal Tavg of 525 F.

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

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FARLEY-UNIT 2 5-6 AMENDMENT NO.

. . i 4

t DESIGN FEATURES

5. 6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a. Keff less than or equal to 0.95 when flooded with unborated water, which includes conservative allowances for uncertainties and biases.
b. A nominal 10.75 inch center-to-center distance between fuel assentlies placed in the storage racks. i
c. A maximum nominal enrichment of:
1. 4.25 weight percent U-235 for Westinghouse LOPAR fuel assenblies.
2. 5.0 weight percent U-235 for Westinghouse OFA or VANTAGE-5 fuel assemblies. Westinghouse OEA and VANTAGE-5 fuel with maximum nominal enrichments greater than 3.9 weight percent l U-235 shall contain sufficient integral burnable absorbers j such that a maximum reference fuel assembly eK less than or i equal to 1.455 at 68 F is maintained.

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

a. Keff less than or equal to 0.98, assuming aqueous foan moderation.

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b. A nominal 21 inch center-to-center distance between new fuel I assemblies placed in the storage racks. l
c. A maximum nominal enrichment of:
1. 4.25 weight percent U-235 for Westinghouse LOPAR fuel assemblies. j
2. 5.0 weight percent U-235 for Westinghouse OEA or VANTAGE-5 l fuel assemblies. Westinghouse OEA and VANTAGE-5 fuel with  !

maximum nominal enrichments greater than 3.9 weight percent U-235 shall contain sufficient integral burnable absorbers such that a maximum reference fuel assembly eK less than or equal to 1.455 at 68 F is maintained.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 149.

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies.

5.7 COMPONENT CYCLIC OR TPANSIENT LIMIT 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.

EARLEY - UNIT 2 5-7 AMENDMENT NO.

. \

Changes marked with strike-through or bold, italics.

DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor eore shall contain 157 fuel assemblies-with each f uel a ssembly-co ntwi fti4 tg---244-f uebrede-eled-wi t4:4ri+2aley-4 . Each assembly shall consist of a matrix of zirconium alloy, zircaloy-4, or Z1RLO" fuel rods with an initial composition of natural or slightly enriched uranium dioxide WOg) as fuel material. Fw ch-fuebred-shal4-have m nominal-aet4+c fuel lengt41-ef--l i t ineheer Ee--4 nit 4el-eere-loading-ehal4-ha ve a manifmtm-nomittel-enrichmcat of 3.15 .cight per-eent43-2%,-Reload-fuel-sha-ll be citni4er-in-phyaical-design to the ini-t4el-eere-leading-and-ehal4-4tav ; a rac*itnum-nontittal-enr4ehment%f 1.25 .cight pc: cent U-2%-f o r-WeeM +tg house-LG FAR-f uel-and-a-ma xi mum-nemicabentiehmc n t c f 5. 0 .:c4 9 ht peteent43-2-%-fo r-West-i ng house-OFA--a ftd-VANTAGE-6-feel . West 4*ghouse OF?. cnd VANTAGF1-b-fuel-witat-maximunt-+teminal-enrichmente-geester-than 3. 9 .:eight-pereeftt-U-2M-sha14-eent-a4+t-suf fseient-itet+gral-burnable-obsorbers cuch t-hat-the requi remente-of-speei-ficat4 enc 5. 6.1.1. c citd-Grfn4 . 2. c cec =c t . West 4nghouse LG PA R-f uel--doe s-not- requ irM +t teg rel-bu r nable-e bsorbe r er Limited substitutions of zirconium alloy, zircaloy-4, 21RLO", or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 4 8 ful4-length-end no part--lengtit control rod assemb1ies. -The--fu14-length-eont-rel-ted-eesemblies-eha11 eonteit. a nominal 142-4 nehes-e f-e bse r ber-meter 4*l v The nomina 4-+alues-ef-abeerher control materia 1 shall be GO-pereenb silver, 1-5-pereent- indium and 5- percc:tt- cadmium as approved by the NRC. Albeen t+el--t ede-s ha14-be-eled-wit 4t-e te inless-steel-tubingr 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 5.2 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 :emperature 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 9723 1 100 cubic feet at a nominal Tavg of 525 F.

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

FARLEY-UNIT 1 5-6 AMENDMENT NO.

O Changes marked with strike-through or bold, Italics.

DESIGN FEATURES 5.6 FUEL STORAGE l I

CRITICALITY  ;

5.6.1.1 The spent fuel storage racks are designed and shall be maintained l with: ,

a. e-Ke gg less than or equal to 0.95 when flooded with unborated water, I which includes conservative allowances for uncertainties and biases, i Thi+-io-e*eu red-by-ma-in t+ini+nn b.ar A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks.

c . k*r A maximum nominal enrichment of:  ;

2. 4.25 weight percent U-235 for Westinghouse LOPAR fuel a s s emblies .
2. 5. 0 veight percent U-235 for Westinghouse OFA or VANTAGE-5 fuel assemblies. Wes tinghouse OFA and VANTAGE-5 fuel with ==v4~~

nominal enrichments greater than 3.9 veight percent U-235 shall contain sufficient integral burnable absorbers such that a er

.. maximum reference fuel assembly K m less than or equal to

1. 4 55 at 68'E for-West 4*ghouse-OFA and V?J!TI.CE - 5 f uci ::cmbliaer is maintained.

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

4. -Keff less than or equal to 0.98, assuming aqueous foam moderation.

This i s a ssured-by-+na-int-aining+ ,

b.+r A nominal 21 inch center-to-center distance between new fuel assemblies placed in the storage racks.

c . htr A maximum nominal enrichment of r

1. 4.25 weight percent U-235 for Westinghouse LOPAR fuel assemblies.
2. 5.0 veight percent U-235 for Westinghouse OTA or VANTAGE-5 fuel c assemblies. Wes tinghouse OFA and VANTAGE-5 fuel with =>v4~~

nominal enrkchments greater than 3..* veight percent U-235 shall contain sufficient integral burnable absorbers such that a er ~

A maximum reference fuel assembly Km less than or equal to

1. 4 55 at 68 F for-Weet-inghcuse OFA and VANTACE- 5 fuel-***C bliCO -

is maintained.

t DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 149, CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be naintained with a storage capacity limited to no more than 1407 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 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.

i.

FARLEY - UNIT 1 5-7 AMENDMENT NO.

.- Changes marked with strike-through or bold, italics.

DESIGN FEATURES 5.3 REACTOR CORE l

FUEL ASSEMBLIES I 5.3.1 The reactor eere shall contain 157 fuel assemblies with ccch fuci :::cmbly [

eenteining-M4-4uel---+ede-elad-wi+h Z i r ca ley-4r . Each assembly shall consist of a matrix of zirconium alloy, zircaloy-4, or ZIRLO fuel rods with an initial congposition of natural or slightly enriched uranium dioxide (T102 ) as fuel material. Eaeh fuc1 red cha44-4teve-e-nomin 1 cchive fuel icngth of 144 inch: .

The-inkt ia l cc c c leading-shal4-havc a maximum- nc=inal cnriehment-ef- 3.15 . cight percent--U-GM . ncicad fuci chall bc cimilar in-physicci design tc the initial i eerc 1eadin9-and-sha44 -he ve-e-eaMeum-neminal-enriehmcnt cf '. 2 5 cight pc:ccnt U-GM-for-West 4*gh c u c c LO P.'.P feel-end a .cximum-nominal-ent-iehment of 5.0 .cight pereent U- 2 3 5 for--Weet4ngbeuse--GFA-end VIWT7.CE 5 f uel . Mc tinghouac OF" and VANTAGE-6-fuel-with-manmum-nominal-enr4ehmento greet-er--thar. 3.9 cight pc:c:nt U-2-36-eha44--eentei-n-euff i ci e n t integral-burnable-absorbcro cuch that-t-he requi-remente-o f-epeci f ica tion: 5.E.1.1.c and 5.6.1.2.c e-rc =ct. Westinghouse LOPAR-fuc1 Sees--not-requi+c a n beg re4-burnable-ebeerberer Limited substitutions of zirconium alloy, zircaloy-4, ZIRLO , or stainless steel filler rods for fuel rods, it, accordance with NRC-approved app 1Lcations of fuel i rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases. A l limited number of lead test assemblies that have not completed representative l testing may be placed in non-limiting core regions.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 full Icagt-h and no part length control rod assemblies. --The-fu14--4ength-cent-rcl cd as c=bl4e: chall contair : nominel ,

442--inehee--of--absorber-eateedel r The nominal valuco of--absc:bcr control material shall be 40-percent silver, 45 percent indium and 6-percent cadmium as approved by ,

the NRC. M4-eent+el-rede-shell be clad . tith st+inico: steel-tubingr 1 5.4 REACTOR COOLANT SYSTEM l

1 DESIGN PRESSURE AND TEMPERATURE J 5.4.1 The reactor coolant system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 5.2 )

of the FSAR, with allowance for normal degradation pursuant to j 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 9723 i 100 cubic feet at a nominal T avg of 525*F.

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

'FARLEY-UNIT 2 5-6 AMENDMENT NO. {

1-

i

  • .O I

.- Changes marked with strike-through or bold, italics. 1 DESIGli FEATURES 1 l

l 5.6 FUEL STORAGE i CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. a Keff less than or equal to 0.95 when flooded with unborated water, which includes conservative allowances for uncertainties and biases.

Thie-is-oesored by maintaini-ng+

P b.ar A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks.

c.br A maximum nominal enrichment of:

1. 4.25 weight percent U-235 for Westinghouse LOPAR fuel assemblies.
2. 5. 0 veight percent U-235 for Westinghouse OFA or VANTAGE-5 fuel assemblies. Westinghouse OFA and VANTAGE-5 fuel with mav4"m nominal enrichments greater than 3. 9 veight percent U-235 shall contain sufficient integral burnable absorbers such that a er

?; maximum reference fuel assembly K m less than or equal to 1.455 at 68 F for-West 4*ghouse-GFA-and-VANT/ ICE - 5 f uc1 acccmblies r is maintained.

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

a. -a-Kefg less than or equal to 0.98, assuming aqueous foam moderation.

This is assured-by-ma4nteiningt b.er A nominal 21 inch center-to-center distance between new fuel asserrblies placed in the storage racks.

c.br A maximum nominal enrichment of:

1. 4.25 weight percent U-235 for Westinghouse LOPAR fuel assemblies. ,
2. 5. 0 veight percent U-235 for Westinghouse OFA or VANTAGE-5 fuel \

assemblies. Westinghouse OFA and VANTAGE-5 fuel with "nv4==

nominal enrichments greater than 3. 9 veight percent U-235 sha11 contain sufficient integral burnable absorbers such that a er A maximum reference fuel assembly K z less than or equal to i 1.455 at 68'F (+r-Weobi+tghouse--OFA--and-VANT7;CE - 5 fucl assemblieer is maintained.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 149.

CAPACITY I

5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be I maintained within the cyclic or transient limits of Table 5.7-1.

FARLEY - UNIT 2 5-7 AMENDMENT NO. )

1 l

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