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DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,614 + 460 cubic feet at a nominal T avg f 532*F.
DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,614 + 460 cubic feet at a nominal T f 532*F.
t I                         5.5 METEOROLOGICAL TOWER LOCATION i
avg t
5.5.1   The meteorological tower shall be located as shown on Figure 5.1-1.
I 5.5 METEOROLOGICAL TOWER LOCATION i
l                        *                            .
l 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
  ;
5.6 FUEL STORAGE m
  !                          5.6 FUEL STORAGE                                                                           ,
8f
                                                                          -          m                                           .
/4 7
  '                                                                          8f       /4 7
CRITICALITY - SPENT FUEL 10 X l0m 5.6.1 The spent fuel storage' racks are designed and shall be maintainedU with a minimum-1215-x-13-inch-center-to-center distance between fuel lj e
CRITICALITY - SPENT FUEL           10             X l0m 5.6.1 The spent fuel storage' racks are designed and shall be maintainedU with a minimum-1215-x-13-inch-center-to-center distance between fuel                               lj l
l assemblies placed in the storage racks to ensure a k,,< 0.95 with the sto The k
e assemblies placed in the storage racks to ensure a k,,<                       The0.95 with the sto
< 0.95 includes the conservative allowances for uncertainties described in Section 9.7.2 of the FSAR.
                              < 0.95 includes the conservative allowances for uncertainties described in Section 9.7.2 of the FSAR. In addition, fuel in the storage pool shall have a U-235 loading of <-44:Ongrams of U-235 per axial centimeter of
In addition, fuel in the storage pool shall have a U-235 loading of <-44:Ongrams of U-235 per axial centimeter of I' l -
                                                      ~
~
                                                          -                                                  -                      I' l -
Q.
Q.                             fuel assembif.          .
fuel assembif.
CRITICALITY - NEW FUEL 5.6.2 The new fuel storage racks are designed and shall be maintained with a nominal 18 inch center-to-center distance between new fuel assemblies such that K           will not exceed 0.98 when fuel having a maximum .
CRITICALITY - NEW FUEL 5.6.2 The new fuel storage racks are designed and shall be maintained with a nominal 18 inch center-to-center distance between new fuel assemblies such that K will not exceed 0.98 when fuel having a maximum.
enrichment of 4.0 weig8bpercent U-235 is in place and aqueous foam moderation is assumed. The K                     of < 0.98 includes the conservative allowanceforuncertaintiesd8[[ribedinSection9.7.2oftheFSAR.
enrichment of 4.0 weig8bpercent U-235 is in place and aqueous foam The K of < 0.98 includes the conservative moderation is assumed.
allowanceforuncertaintiesd8((ribedinSection9.7.2oftheFSAR.
DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained l
DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained l
to prevent inadvertent draining of the pool below elevation 63 feet.
to prevent inadvertent draining of the pool below elevation 63 feet.
CAPACITY 5.6.4 The fuel storage pool is designed and shall be maintained with a combined storage capacity, for both Units 1 and 2, limited to r.o more                               ,
CAPACITY 5.6.4 The fuel storage pool is designed and shall be maintained with a combined storage capacity, for both Units 1 and 2, limited to r.o more
than G55-fuel assemblies.                        -
(
(
l750 g                              5.7   COMPONENT CYCLIC OR TRANSIENT LIMITS                     8001170 47d
than G55-fuel assemblies.
              .                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.
l750 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 8001170 47d g
5-5                        Amencment No- p, l                             CALVERT CLIFFS UNIT.2                                     ;
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.
Amencment No-p, l
CALVERT CLIFFS UNIT.2 5-5


bWW                     hG       ][ L f}
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      ,            DESIGtt FEATURES
][ L f}
      ;            VOLUME I
DESIGtt FEATURES VOLUME I
:            5.4.2 The total water and steam volume of the reactor coolant systcm is 10,614 + 460 cubic feet at a nominal Tavg f 532 F.
5.4.2 The total water and steam volume of the reactor coolant systcm is 10,614 + 460 cubic feet at a nominal T f 532 F.
    ,'            5.5 METEOROLOGICAL TOWER LOCATI0fl                                   -
avg 5.5 METEOROLOGICAL TOWER LOCATI0fl 5.5.1 The meteorological tower shall be located as showa on Figure 5.1-1.
    !              5.5.1     The meteorological tower shall be located as showa on Figure 5.1-1.
I 5.6 FUEL STORAGE CRITICALITY - SPENT FUEL s.;
I 5.6   FUEL STORAGE CRITICALITY - SPENT FUEL                   s.;           /   "
/
5.6.1     The spent fuel storageLracks are designed and shall be maintained 'I with a minimum 4-h5-x43-inch. center-to-center distance between fuel                           1{
5.6.1 The spent fuel storageLracks are designed and shall be maintained
assemblies
'I with a minimum 4-h5-x43-inch. center-to-center distance between fuel 1{
                    < 0.95.with placed       in thepool the storage     storage filledracks with to         ensure a w3 unborated      k,t6r., equivalent The k ,toof 7 0.95 includes the conservative allowances for uncertainties de&[iibed In Section 9.7.2 of the FSAR. In addition, fuel in the storage pool                           ,
assemblies placed in the storage racks to ensure a k,t6r., equivalent to
          .        shall have a U-235 loading of < 079 rams of U-235 per axial centimeter O- '               of fuel assembly.
< 0.95.with the storage pool filled with unborated w3 The k
Ab5 CRITICALITY - f1EW FUEL 5.6.2 The new fuel storage ra:ks are designed and shall be maintained with a ncminal 18 inch center-to-center distance between new fuel assemalies such that k       will not exceed 0.98 when fuel having a maximum enrichment                   '
, of 7 0.95 includes the conservative allowances for uncertainties de&[iibed In Section 9.7.2 of the FSAR.
of 4.0 weig8(Ipercent U-235 is in place and aqueous foam moderation is assumed. The k           of < 0.98 includes the conservative allowance for uncertainties dN[ribed in Section 9.7.2 of the FSAR.
In addition, fuel in the storage pool shall have a U-235 loading of < 0 9 rams of U-235 per axial centimeter O- '
DRAINAGE 5.6.3     The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 63 feet.
7 of fuel assembly.
CAPACITY 5.6.4 The 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     E& fuel assemblies.
Ab5 CRITICALITY - f1EW FUEL 5.6.2 The new fuel storage ra:ks are designed and shall be maintained with a ncminal 18 inch center-to-center distance between new fuel assemalies such that k will not exceed 0.98 when fuel having a maximum enrichment of 4.0 weig8(Ipercent U-235 is in place and aqueous foam moderation is assumed.
                          \'16 0                                                                           ~
The k of < 0.98 includes the conservative allowance for uncertainties dN[ribed in Section 9.7.2 of the FSAR.
t 5.7   COMP 0tlENT CYCLIC OR TRANSIEllT LIliITS 1763 024 5.7.1     Th'e components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 63 feet.
                                      ~
CAPACITY 5.6.4 The 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 E& fuel assemblies.
                                                                                                                        /
\\'16 0
:                  CALV$RT CLIFFS - UNIT 1                       5- 5                             Ameadment No./7}}
~
t 1763 024 5.7 COMP 0tlENT CYCLIC OR TRANSIEllT LIliITS 5.7.1 Th'e components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
~
/
CALV$RT CLIFFS - UNIT 1 5-5 Ameadment No./7}}

Latest revision as of 19:57, 4 January 2025

Revised Page 5.5 to Tech Specs Re Design Features of Spent Fuel Pool
ML19211D300
Person / Time
Site: Calvert Cliffs  
Issue date: 01/15/1980
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19211D294 List:
References
NUDOCS 8001170472
Download: ML19211D300 (4)


Text

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. (/ t? ctM l

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DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,614 + 460 cubic feet at a nominal T f 532*F.

avg t

I 5.5 METEOROLOGICAL TOWER LOCATION i

l 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE m

8f

/4 7

CRITICALITY - SPENT FUEL 10 X l0m 5.6.1 The spent fuel storage' racks are designed and shall be maintainedU with a minimum-1215-x-13-inch-center-to-center distance between fuel lj e

l assemblies placed in the storage racks to ensure a k,,< 0.95 with the sto The k

< 0.95 includes the conservative allowances for uncertainties described in Section 9.7.2 of the FSAR.

In addition, fuel in the storage pool shall have a U-235 loading of <-44:Ongrams of U-235 per axial centimeter of I' l -

~

Q.

fuel assembif.

CRITICALITY - NEW FUEL 5.6.2 The new fuel storage racks are designed and shall be maintained with a nominal 18 inch center-to-center distance between new fuel assemblies such that K will not exceed 0.98 when fuel having a maximum.

enrichment of 4.0 weig8bpercent U-235 is in place and aqueous foam The K of < 0.98 includes the conservative moderation is assumed.

allowanceforuncertaintiesd8((ribedinSection9.7.2oftheFSAR.

DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained l

to prevent inadvertent draining of the pool below elevation 63 feet.

CAPACITY 5.6.4 The fuel storage pool is designed and shall be maintained with a combined storage capacity, for both Units 1 and 2, limited to r.o more

(

than G55-fuel assemblies.

l750 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 8001170 47d g

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.

Amencment No-p, l

CALVERT CLIFFS UNIT.2 5-5

bWW hG

][ L f}

DESIGtt FEATURES VOLUME I

5.4.2 The total water and steam volume of the reactor coolant systcm is 10,614 + 460 cubic feet at a nominal T f 532 F.

avg 5.5 METEOROLOGICAL TOWER LOCATI0fl 5.5.1 The meteorological tower shall be located as showa on Figure 5.1-1.

I 5.6 FUEL STORAGE CRITICALITY - SPENT FUEL s.;

/

5.6.1 The spent fuel storageLracks are designed and shall be maintained

'I with a minimum 4-h5-x43-inch. center-to-center distance between fuel 1{

assemblies placed in the storage racks to ensure a k,t6r., equivalent to

< 0.95.with the storage pool filled with unborated w3 The k

, of 7 0.95 includes the conservative allowances for uncertainties de&[iibed In Section 9.7.2 of the FSAR.

In addition, fuel in the storage pool shall have a U-235 loading of < 0 9 rams of U-235 per axial centimeter O- '

7 of fuel assembly.

Ab5 CRITICALITY - f1EW FUEL 5.6.2 The new fuel storage ra:ks are designed and shall be maintained with a ncminal 18 inch center-to-center distance between new fuel assemalies such that k will not exceed 0.98 when fuel having a maximum enrichment of 4.0 weig8(Ipercent U-235 is in place and aqueous foam moderation is assumed.

The k of < 0.98 includes the conservative allowance for uncertainties dN[ribed in Section 9.7.2 of the FSAR.

DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 63 feet.

CAPACITY 5.6.4 The 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 E& fuel assemblies.

\\'16 0

~

t 1763 024 5.7 COMP 0tlENT CYCLIC OR TRANSIEllT LIliITS 5.7.1 Th'e components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

~

/

CALV$RT CLIFFS - UNIT 1 5-5 Ameadment No./7