ML20058K286

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Proposed Tech Specs Re Design Features
ML20058K286
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 12/08/1993
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20058K284 List:
References
NUDOCS 9312150090
Download: ML20058K286 (21)
v • d • e


Text

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ATTACHMENT 1 UNIT 1 TECHNICAL SPECIFICATION REVISED PAGES Table of Contents Page XV 5-1 5-2 5-3

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TABLE OF CONTENTS DESIGN FEATURES SECTION PAGE i

5.1 SITE L OC A TICA) -

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.1_5 MA DEFINING THE SITE BOUNDARY AND EFFLUENT RELEASE POINTS 5.1.1 A map of the Calvert Cliffs Nuclear Power Plant site iden fying'the major p ant structures as well as defining the radioactive eff ent release points a the SITE B0UNDARY is shown in Figure 5.1-1. LOW POPULATI ZONE 5.1.2 The low p ulation zone shall be as shown in F ure 5.1-2. l 5.2 CONTAINMENT l CONFIGURATION 5.2.1 The reactor contai nt building is steel lined, reinforced concrete building of cylindr cal shape, w h a dome roof and having the i following design features: l r a. Nominal inside diamete 0 feet, = b. Nominal inside height = 2/3 feet. c. Minimum thickness of concret walls = 3 3/4 feet. d. Minimum thickness of concrete f = 3 1/4 feet. e. Minimum thick ss of concrete floo ad.= 10 feet. f. Nominal th kness of steel liner = 1/ inches. g. Net fre volume = 2 x 10' cubic feet. 1 l CALVERT CLIFFS - UNIT 1 5-1 Amendment No. 4fe

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i 5.0 DESIGN FEATURES BESIGN PRESSURE AND TEMPERATURE ) 5.2. The reactor containment building is designed and shall'be maintain for a. aximum internal pressure of 50 psig and a temperature of 276'F., l J 5.3 REACT CORE i P \\ l FUEL ASSEMBLIE j 1 5.3.1 The reacto core shall contain 217 fuel assembif es w each fuel i assembly containing - maximum of 176 fuel rods clad with ' caloy-4. Each fuel rod shall have a ominal active fuel length of 136. inches and i contain a maximum total eight of 3000 grams uranium /. -e i_nitial core i loading shall have a max enrichment of 2.99 weig percent U-235. .j Reload fuel shall be simila in physical design to ie initial core loading and shall have.a maximum enr hment of 4.35 weigh percent U-235. A { 5.3.2 Except for special test a authorized b the NRC, all fuel assemblies under control element a emblies all be sleeved with a sleeve design previously approved by the N CONTROL ELEMENT ASSEMBLIES 5.3.3 The reactor core shall con in 77 ful length and no part length control element assemblies. j 5.4 REACTOR COOLANT SYST l /. l DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor olant System is designed and shall be intained: a. In act ance with the code requirements specified i Section 4.2 of t FSAR with allowance for nonnal-degradation purs nt of the app cable Surveillance Requirements, b. or a pressure of 2500 psia, and For a temperature of 650'F, except for the pressurizer which is 700*F. i CALVERT CLIFFS - UNIT 1 5-4 Amendment No. -1M i u.

._ l s 5.0 DESIGN FEATURES UME' 5.4 The total water and steam volume of the Reactor Coolant System 10,61 0 cubic feet at a nominal T.,, of 532*F. + 5.5 !4_ETE0A0 LOGICAL TOWER LOCATION i The me\\teurological tower shall be located as shown o Figure 5.1-1. 5.5.1 5.5 FUEL STORAGE CRITICALITY - SPENT FUE 5.6.1 The spent fuel stora racks are designe and'shall be maint&ined l with a minimum 10 3/32' x 10 /32" center-to-nter distance between fuel assemblies placed in the'stora racks to e ure a k,hof < 0.95 with the of 0.T5 includes the conservative allowances for uncert intieg/Thedescri,,d in Section 9.7.2 of storage pool filled with unborat water. FSAR. The maximum fuel enriciment stored in the fuel pool will be 4.52 weight percent. CRITICALITY - NEW FUEL 5.6.2 The new fuel storage acks are designe nd shall be maintained with a nominal 18 inch center- -center distance bet n new fuel assemblies-such that k,,, will not e eed 0.95 when fuel havi a maximum enrichment of i 5.0 weight percent U-2 is in place and various densities of unborated water are assumed in uding aqueous foam moderation aNd full flood i conditions. The k, of < 0.95 includes the conservati allowance for-l uncertainties de ribed in Section 9.7.2 of the FSAR. 4 DRAINAGE i 5.6.3 e spent fuel storage pool is designed and shall be maint ined to preve inadvertent draining of the pool below elevation' 63 feet. l I I l CALVERT CLIFFS - UNIT 1 5-5 Amendment No.474-- i

1 l i i l 1 a i 5.0 DESIGN FEATURES CXPACITY 3 5.6. The fuel storage pool is designed and shall be maintained with a i combin storage capacity, for both Units 1 and 2 limited to no more t n 1 j 1830 fue assemblies. P 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The compohqnts identified in Table.5.7-1 are designed and shall be maintained within e cyclic or transient limits of Table 5(7-1. i a l! 6 1 4 t + + l i

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..-= t 9 TABLE 5.7-1 C;g o COMPONENT CYCLIC OR TRANSIENT LIMITS s g O COMPONENT CYCLIC OR TRANSIENT LIMIT DESIGN CYCLE OR TRANSIENT U n 7A Reactor Coolant System heatup and cooldown cycles 70*F to 532 F to 70 F 400rhctortripcycles 100% to 0% RATED THERMAL POWER ts f 10 Primary H tatic Tests 3125 psiafand 60 F > NDIT 320PrimaryLeakTeh sia and 60*F > NOTT Steam Generator 10 Secondary Hydrostatic t ts 1250 psia Secondary Side and u temperature > 100 F 320 Secondary Leak Tests 1000 psia Secondary Side With. Primary - Secondary Ap of 0 psi and shell. side t rature between 100*F and F E a a e

=- i 5.0 DESIGN FEATURES I [ INSERT A] 5.1 SITE LOCATION [ f The site for the Calvert Cliffs Nuclear Power Plant is located on the western i shore of the Chesapeake Bay in Calvert County, Maryland about 10-1/2 miles southeast of Prince Frederick, Maryland. The site is approximately 45 miles j southwest of Washington, D.C. and 60 miles south of Baltimore, Maryland. l 5.2 REACTOR CORE ) i The reactor shall contain 217 fuel assemblies. Each assembly shall consist of. a matrix of zirconium alloy fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0 ) as fuel material. Limited-2 substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be i used. Fuel assemblies shall be limited to those fuel designs that have been i analyzed with applicable NRC staff 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 nonlimiting regions. 2 5.3 FUEL STORAGE 5.3.1 CRITICALITY j i 5.3.1.1 The spent fuel storage racks are designed and shall be maintained with: i 4 R a. Fuel assemblies having a maximum U-235 enrichment of 4.52 weight [ percent; b. k,,, s 0.95 if fully flooded with unborated water, which includes l an allowance for uncertainties as described in Section 9.7.2 of J the UFSAR; i c. A nominal 10-3/32-inch center-to-center distance between fuel i assemblies. l 5.3.1.2 The new fuel storage racks are designed and shall be maintained with: a. Fuel e.ssemblies having a maximum U-235 enrichment of 5.0 weight l percent; b. k,,, llowance for uncertainties as described in Section 9.7.1 ofs 0.95 if fully floo an a i the UFSAR; i CALVERT CLIFFS - UNIT 1 5-1 Amen'dment XXX

k ' 5.0 DESIGN FEATURES k s0 aIYowanc.95 if moderated by aqueous foam, which. includes an c. e for uncertainties as described in:Section-9.7.1 of the UFSAR; and d. A nominal :18-inch center-to-center distance between fuel assemblies placed in.the storage racks. .) 5.3.2 CAPACITY i The spent fuel storage pool is designed and shall be maintained with' a combined storage capacity, for both Units 1 and 2, limited to no more than - 1830 fuel assemblies. b l ) .j i I .) .I t l l CALVERT CLIFFS - UNIT 1 5-2 Amendment XXX 4 i

4 j l l f i a A1TACHMENT 2 i i i i l 4 i i UNIT 2 i l TECHNICAL SPECIFICATION REVISED PAGES E Table of Contents Page XT i 5-1 5-2 5, 5-4 5-5 i l 5-6 l 5-7 i i f 1

i TABLE 0F CONTENTS l DESIGN FEATURES i i SECTION PAGE j i 5.1 SITE LOCA M N 5-t 4rivl Map-Defi ning-the-SITE-BOUNDARY-and-Effluent Relea : Point: 5-1 i -5rh2 Low-Population-Z:n: 5.! -5.2 CONTAI1 MENT l 5.2.1 Configurati on................. 5-1 ii.2.2 Design Fiessuie and-Teuveretwie.......... 5 - S-I 5.J 1 REACTOR CORE -573rl-and-5r3.2-Fuel-Assembl-les.......-....... 5-4 Mr3r3 Control-Element A::=bl4e: 5-4 -L4 REACTOR-C00UWT-SYST~ -fr471 Design-Pressure-and T=perature.......... 5' l .l -54.7 Volume...................... 5' 44 METEGROL9GICAL-TGWER-LOCATION........... 5-5 5.f3 FUEL STORAGE q,3, i G n'f h e( @ - 1 64r1 Gett4caMty-- Spent Fuel 5-J t 4,6v2 Critical 4ty-- New Fuel 5-F / -5.6.3 Drainage -r. 5=5 LE'A Capacity 5-f2 E.3 2 -517 COMPONENT-CYCLIC-GR-TRANSIENT-LIMITS 5-5 i i i CALVERT CLIFFS - UNIT 2 XV Amendment No. @ l l i I

elehe in S 2 l O n b S e f'l2' " U "b 5.0 DESIGN FEATURES l \\ 5.1 SITE PRP DEFINING THE SITE B0UNDARY AND EFFLUENT RELEASE POINTS i 5.1. A map of the Calvert Cliffs Nuclear Power Plant site identify g the major lant structures as well as defining the radioactive effluent release points d the SITE B0UNDARY is shown in Figure 5.1-1. i l LOW POPULAT N ZONE 5.1.2 The low pulation zone shall be as shown in Figure .1-2. l 5.2 CONTAINMENT i CONFIGURATION 4 5.2.1 The reactor contai nt building is a ste lined, reinforced concrete building of cylin ical shape, with a roof and having the i following design features: a. Nominal inside diamet = 130 fee. i b. Nominal inside height = 1 2/ feet. l c. Minimum thickness of concre walls = 3 3/4 feet. j d. Minimum thickness of con ete f = 3 1/4 feet. l e. Minimum thickness of nerete floo pad = 10 feet. l l f. Nominal thickness o steel liner = 1/ inches. g. Net free volume 2 x 10' cubic feet. i l CALVERT CLIFFS - UNIT 2 5-1 Amendment No. 3 9-

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1 FIGURE 5.1-2 LOW POPULATION ZONE CALVERT CLIFFS - UNIT 2 5-3 Amendment No. -449-- i i

5.0 DESIGN FEATURES j OESIGN PRESSURE AND TEuPERATURE i 5.2 2 The reactor containment building is designed and shall be maintaine[ for a\\paximum internal pressure of 50 psig and a temperature of 276*F. t \\ 5.3 REACTOR CORE ~ FUEL ASSEMB [ES The rea\\ tor core shall contain 217 fuel assemblies wi. 5.3.1 each fuel assembly contairitng a maximum of 176 fuel rods clad with Z} inches and /caloy-4. Each fuel rod shall hab a nominal active fuel length of 136.7 contain a maximum total weight of 3000 grams uranium. e initial core loading shall have a\\ maximum enrichment of 2.99 weigh percent U-235. Reload fuel shall be milar in physical design to t e initial core loading and shall have a maxim enrichment of 4.35 weight ercent-U-235. 5.3.2 Except for special test as authorized by he NRC, all fuel assemblies under control etement assemblies s 11 be sleeved with a sleeve design previously approved b the NRC. CONTROL ELEMENT ASSEMBLIES 5.3.3 The reactor core shall conta 77 full length and no part length control element assemblies. 5.4 REACTOR COOLANT SYSTDi DESIGN PRESSURE AND TEMPE URE / 5.4.1 The Reactor Cool t System is designed nd shall be maintained: i a. In accord ce with the code requirements specified in Section 4.2 of the FJA'R with allowance for nonnal dhgradation pursuant of the applicable Surveillance Requirements, b. For pressure of 2500 psia, and c. r a temperature of 650*F, except for the pre surizer, which is 700 F. VOL ' E 5 .2 The total water and steam volume of the Reactor Coolant S tem is 10,614 + 460 cubic feet at a nominal T., of 532*F. CALVERT CLIFFS - UNIT 2 5-4 Amendment No. -149--

a i i 5.0 DESIGN FEATURES i 5.5 METECR0 LOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Ffgure 5. -1. 5.6 FfL STORAGE ~ CRITICALU? SPENT FUEL 1 N 5.5.1 The spent \\ be maintained withaminimum10(uelstorageracksaredesignedandshal /32' x 10 3/32' center-to-center dis nce between fuel assemblies placed i the storage racks to ensure a f 5 0 95 with the i storage poo! filled The ,, o 5 0.95 includes the conservative allowance,th unborated water. for uncertainties descri in Section 9.7.2 of the FSAR. The maximum fuel nrichment to be stored th* fuel pool will be 4.52 weight percent. i i s CRITICALITY - NEW FUEL 5.6.2 The new fuel storage rack are f6 signed and shall be maintained with j a nominal 18 inch center-to-cente d tance between new fuel assemblies s such that k,,, will not exceed 0.95 en fuel having a maximum enrichment of 5.0 weight percent U-235 is in pl ce nd various densities of unborated water are assumed including aqu us fo moderation and full flood conditions. The k,, of 5 0.9 includes he conservative allowance for uncertaintiesdescrfbedin etion 9.7.2' f the FSAR. ORAINAGE l 3 5.6.3 The spent f storage pool is designed a shall be maintained to prevent inadvert draining of the pool below ele ation 63 feet. CAPACITY 5.6.4 T fuel storage pool is designed and shall be mai ained with a combin storage capacity, for both Units 1 and 2, limited o no more than 1830 uel assemblies. .7 COMPONENT CYCLIC OR TRANSIENT LIMITS ~ 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. \\ 1 CALVERT CLIFFS - UNIT 2 5-5 Amendment No. -163-

9 ? Q TABLE 5.7-1 o COMPONENT CYCLIC OR TRANSIENT LIMITS h P M 3 COMPONENT hCLICORTRANSIENTLIMIT DESIGN CYCLE OR TRANSIENT Reactor Coolant System 500 up and cooldown cycles 70 F to 532*F to 7 400 reactb rip cycles 100% to 0% TEITNERMALPOWER 10 Primary Hyd tic Tests 31 sIaand60*F>NDIT 320PrimaryLeakTeh 500 psia and 60*F > NDIT y Steam Generator 10 Secondary Hydrostatic ts 1250 psia Secondary Side and m temperature > 100 F 320 Secondary Lea ests 1000 psia Secondary Side With Primary - Secondary Ap of 820 psi and shell side emperature between 100 F an 200*F $a lla .E

I ~ 5.0 DESIGN FEATURES I 1 j [ INSERT A) l 5.1 SITE LOCATION i 3 The site for the Calvert Cliffs Nuclear Power Plant is located on the western l ? shore of the Chesapeake Bay in Calvert County, Maryland about 10-1/2 miles southeast of Prince Frederick, Maryland. The site is approximately 45 miles t southwest of Washington, D.C. and 60 miles south of Baltimore, Maryland. a r 5.2 REACTOR COR1 i The reactor shall contain 217 fuel assemblies. Each assembly shall consist of-4 a matrix of zirconium alloy fuel rods with an initial composition of natural or slightly anriched uranium dioxide (UO ) as fuel material. Limited l 2 substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been 3 analyzed with applicable NRC staff approved codes and methods and shown by j 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 nonlimiting regions. l t 5.3 FUEL STORAGE t 5.3.1 CRITICALITY 4 5.3.1.1 The spent fuel storage racks are designed and shall be maintained with: _j i a. Fuel assemblies having a maximum U-235 enrichment of 4.52 weight i percent; b. k,,, llowance for uncertainties as described in Section 9.7.2 of-s 0.95 if fully f an a the UFSAR; c. A nominal 10-3/32-inch center-to-center distance between fuel assemblies. 5.3.1.2 The new fuel storage racks are designed and shall be maintained with: a. Fuel assemblies having a maximum U-235' enrichment of 5.0 weight. percent; b. k,,, s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.7.1 of the UFSAR; j i CALVERT CLIFFS - UNIT 2 5-1 Amendment XXX

q 5.0. DESIGN FEATURES l t c. k,, s.0.95 if moderated by aqueous foam, which includes an. allowance for uncertainties as described. in Section 9.7.1 of the. i UFSAR; and d. A nominal 18-inch center-to-center distance between' fuel' assemblies placed in the storage racks. 5.3.2 CAPACITY _ The spent fuel storage pool. is designed and shall be maintained with.a-l combined storage capacity, for both Units 1 and 2, limited to no more than j 1830 fuel assemblies. s i k -r i i i h i L i i -t .i CALVERT CLIFFS - UNIT 2 5-2 Amendment XXX l i ..}}

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