ML20058K286
| ML20058K286 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/08/1993 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20058K284 | List: |
| References | |
| NUDOCS 9312150090 | |
| Download: ML20058K286 (21) | |
Text
-__ _ _____ ____ _ -
ATTACHMENT 1 UNIT 1 TECHNICAL SPECIFICATION REVISED PAGES Table of Contents Page XV 5-1 5-2 5-3
'5-4 5-5 5-6 ;
1 5-7 !
l 1
9312150090 931200 5 PDR ADDCK 05000317 [I P PDR t,i
TABLE OF CONTENTS DESIGN FEATURES SECTION PAGE !
i 5.1 SITE L OC A TICA) - - - - ~ ~ +
- . G-l
-5.1.1 Ma p-De fi n i ng-t he-SITE-BOUNDARY-and-Effluen t itel eas e-Poi nts . . . . . . . . . . .,, . . . . . . 5-1
-5v1.2 Low-Population-Zone . . . . . . . . . . . . . . . . . P i
42 CONTAINMENT
-Gr2r1 Con fi gu ra ti on,,,, . . . . . . . . . . . . . . . . 5 -- I
-5:222 Design-Pressure-And-Temperature . . . . . . . . . . . 5-4 5./1 REACTOR CORE , . , . - - ,o u o E-l !
-Gr3rl-and-5r3-2-Fuel-AssembMes . . . . . . . . . . . . .. . . 5 t Gr3v3 Control-Element-Assembl4e: ............. 5-4 l
--5 A REACTOR-C00LANT4YSTEM-4.4.1 Design-Pressure-And-Temperature . . . . . . . . . . . E4
-5.4.2 Volume- , , , ................... 5 !
-55 METEOROLOGICAL-TOWER 40 CATION . . . . . . . . . . . . 5 I i
l 5.f 3 FUEL STORAGE 1
- 5. 3. I c rikot% !
-516,1 -Cr4t4214ty-- Spent Fuel .............. 5 75' l !
-516r2- Criticality New Fuel ............... . 5-S'/
4.5.3 Drainage . . .................... 5 5.6.4- Capacity . . .................... 5-# 2 l
- 5. S. )
-577 COMP 0NENT-CYCLIC-OR-TRANSIENT-kIMITS . . . ..... 5-5 4 CALVERT CLIFFS - UNIT 1 XV Amendment No. 4P-
e[che tn hal gn) Seflrce toNh IAwb //]
5.0
\ DESIGN FEATURES l .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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l l CALVERT CLIFFS - UNIT 1 5-3 Amendment No. -M9-l
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 e i_nitial core i loading shall have a max eightenrichment of 3000 grams of 2.99uranium 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 l i
- u. _ _ _ .. - . . _ -
._ l I
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
5.5.1 The me\teurological tower shall be located as shown o Figure 5.1-1. : 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 storage pool filled with unborat water. ure a of k ,hof < 0.95 0.T5 withthe includes the conservative allowances for uncert intieg/Thedescri ,,d in Section 9.7.2 of ! - 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 l 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 +
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j-CALVERT CLIFFS - UNIT 1 5-6 Amendment No. 449-
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_ _ . ..-= . . .. . t 9 TABLE 5.7-1 !" C; g COMPONENT CYCLIC OR TRANSIENT LIMITS o s - g On COMPONENT CYCLIC OR TRANSIENT LIMIT DESIGN CYCLE OR TRANSIENT U 7A Reactor Coolant System heatup and cooldown cycles 70*F to 532 F to 70 F 400rhctortripcycles st 100% to 0% RATED THERMAL f POWER $ 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 (U02 ) as fuel material. Limited- ! 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 . 2 may be placed in nonlimiting regions. 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 ! 4 with: i 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: l
- a. Fuel e.ssemblies having a maximum U-235 enrichment of 5.0 weight l percent; ;
- b. k,,,
an a llowance for uncertainties as described in Section 9.7.1 ofs 0.95 if fully floo i the UFSAR; i CALVERT CLIFFS - UNIT 1 5-1 Amen'dment XXX
k
' 5.0 DESIGN FEATURES
- c. k s0 '!
aIYowanc.95 if moderated by e for uncertainties asaqueous describedfoam, which . includes in:Section-9.7.1 of the an ! 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. !
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l 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 ;
5 - ii.2.2 Design Fiessuie and-Teuveretwie . . . . . . . . . . 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
-54.7 Volume . . . . . . . . . . . . . . . . . . . . . . 5' .l 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 l
"b elehe in S 2 l O n b S e f'l2' " U 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. l
- g. Net free volume 2 x 10' cubic feet.
1 i l CALVERT CLIFFS - UNIT 2 5-1 Amendment No. 3 9-
5.0 DESIGN FEATURES f. y t A h c '\ : j , .. . . .. . .M, - i f -/- ,
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5 W .;47fp. y.:. - . 1 FIGURE 5.1-2 LOW POPULATION ZONE CALVERT CLIFFS - UNIT 2 5-3 Amendment No. -449-- i 1 i
5.0 DESIGN FEATURES j l OESIGN PRESSURE AND TEuPERATURE l i t 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.
\
5.3 REACTOR CORE
~
FUEL ASSEMB [ES 5.3.1 The rea\ tor core shall contain 217 fuel assemblieseach wi. fuel
/caloy-4. Each assembly fuel contairitng rod shall a maximum hab a nominal of 176 active fuel fuelofrods length clad with Z} inches and 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. l 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 l l 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 l assemblies placed i the storage racks to ensure a , f 5 0 95 with the i
,, o 5 0.95 includes the storage poo! filled The conservative allowance,th forunborated water.
uncertainties descri in Section 9.7.2 of the 1
- FSAR. The maximum fuel nrichment to be stored th* fuel pool will be
- 4.52 weight percent. $. ,
i s i CRITICALITY - NEW FUEL I j 5.6.2 The new fuel storage rack are f6 signed and shall be maintained with a nominal 18 inch center-to-cente ds tance between new fuel assemblies - , 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 3 l 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 P COMPONENT CYCLIC OR TRANSIENT LIMITS h 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 ll a
.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 (UO2 ) as fuel material. Limited l 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,,,
an a llowance for uncertainties as described in Section 9.7.2 of-s 0.95 if fully f: 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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