ML20217A419

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Proposed Tech Specs Modifying TS 5-4 Re Spent Fuel Pools
ML20217A419
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 11/14/1990
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20217A406 List:
References
NUDOCS 9011210054
Download: ML20217A419 (5)
v • d • e


Text

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ATTACHMENT Technical Specification Change 1

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                                                                      'l TSCR201 9011'210054 901114 PDR   ADOCK 05000289 P               PDC                                     .

 ,.         .                                          LIST OF FIGURES Figure                            ,T_i_th 3.5-2K thru    DELETED
                         . 3.5-2L                                                            i i

3.5-2M LOCA. Limited Maximum Allowable Linear Heat Rate i 3.5-1 Incore Instrumentation -Specification Axial Imbalance i Indication, TMI-1 3.5 Incore Instrumentation Specification Radial Flux Tilt  ; Indicatinn, TMI 3.5-3~ Incore Instrumentation Specification 3.11 Transfer Path to and from Cask loading Pit  ! 4,17-1 Snubber Functional- Test - Sample' Plan 2 0 5-1

Extended Plot Plan TMI
                     ,     5-2      Site: Topography 5 Mile Radius
                                                                                            -{
                         '5-3      - Locations of- Gaseous ' Effluent Release Points and-Liquid Effluent Outfalls:

5-4 Relationship Between Initial Enrichment and Acceptable  ! Fuel Burnup (Spent Fuel Pool A - Region II) l 

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1 h s !,g viii Amendment Nos. 72, 77, 126, 139, 142, 149, 150, 156 l -; 

                                                                                                        . - ~                        - . .       _ -
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LSI NEW AND SPENT FL'LL STORAGE FACRITIES 

             -    Applicability                                                                                                                       !

Applies to storage facilities-for new and spent fuel assemblies. Objective To assure that both new and spent fuel assemblies will be stored in such a manner that an inadvertent criticality could not occur. Specification 5.4.1 NEW FUEL STORAGE

a. New fuel will normally be stored in the new fuel storage vault or spent fuel pools. The fuel assemblies are stored '

in racks in parallel rows, having a nominal center to i center distance of 21-1/8 inches in.both directions-for the new fuel storage vault. The fuel assemblies are  ; stored in racks in parallel rows, having a nominal center  : l to center distance of.11.1 inches in both directions for. p the Region I. racks and 9.20 inches in both directions for the Region -II racks for the Spent Fuel Pool "A"~ The fuel assemblies are stored in racks in parallel rows, having a 

                             -nominal center to center distance of 13-5/8 inches =in both                                                    -

. ' directions for the Spent Fuel Fool "B". This spacing is 

                              . sufficient to maintain a K effective of less than'.95-based on fuel assemblies with an enrichment of.4.3 weight                                                              :

percent'U"

  • for the new fuel storage vault'and Spent Fuel Pool "B". The. spacing is sufficient to maintain a K effective of less.than .95 based on fuel assemblies with-l- .an enrichment of 4.6. weight percent US*" for Region I of L the Spent Fuel Poo1L"A". When fuel is'being stored in the 1 new fuel storage vault, . twelve (12) storage locations-(aligned'in two rows of,six locations each; transverse row '

numbers four and eight) must be.left vacant of fissileLor' 

                             . moderating material ~ to ' provide sufficient neutron leakage to satisfy:the NRC maximum' allowable reactivity value-p                               under the optimum lowLmode;ator density condition. When                                                                >

fuel is' being movedvin~ or over the Spent Fuel Storage Poo1 ~ 

                               "A" and-fuel is being stored in the pool,.a boron                                                               -

concentration'of at least' 600lppmb must be maintained.to s y . ensure . meeting the:NRC. maximum allowable reactivity .value ' . E under the postulated accident condition of.a misplaced  ; l" fuel assembly. y

h. Deleted.-

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c. New fuel'may also be stored in shipping containers.

5-6 + l Amendment No. 138 o

l k a e 5.4.2 SPENT. FUEL STORAGE

a. Irradiated fuel assemblies will be stored, prior to offsite shipment, in the stainless steel lined spent fuei pools, which are located in the fuel handling building,
b. Whenevea there is fuel in the pool except for initial fuel loading, the spent fuel pool is filled with water borated to the concentration used in the reactor cavity and fuel transfer canal,
c. Deleted.
d. The fuel assembly storage racks provided and the number of fuel elements each will store are listed by location below:

Spent Fuel Pool A Spent Fuel Pool B- Dry New Fuel North End of Fuel South End of Fuel Storage Area Handling Building Handling Building Fuel Handling Building

Fuel A'ssys 846 ** 496 *** 66**** t Cores 4.78- 2.8 0.37
                        ' NOTES: . c** Includes three spaces for accommodating failed fuel containers. An additional 648 storage locations can be installed to provide a . total of 1494 locations, or 8.44 Cores.
                                   ***~ Spent Fuel l Pool B contains spent fuel storage racks with a
                                         -center-to-center spacing of 13 5/8' inches to increase the-storage capacity of the pool.
                                 **** Includes twelve spaces which.are required to be vacant of 1

fissile or moderating material.so'that there is sufficient neutron leakage.-

e. L All of the fuel assembly storage racks provided are designed to Seismic-Class 1 criteria to the accelerations indicated below:  !

Fuel Handling Building Fuel . Handling N Dry New Fuel Storage Area Building Spent , 

                                         - And Spent Fuel -pool A                  Fuel pool B                                          :
                       .Horiz.                     0.38 g                                  .
                       ; Vertical-                 0.25;g.                                   *
  • The "B" pool fuel storage racks-ars designed using the floor response spectra of the Fuel Handling Building. j
f. Fuel in the storage pool shall have a U-235 loading equal to'
                                            - or less than 57.8 grams of U-235 per axial centimeter. of fuel                            i assembly.                                                                                  '

g.: 'When ss.m t fuel assemblies are stored in Region II storage racks of the Spent Fuel Pool "A", the combination of initial enrichment and cumulative burnup for spent fuel assemblies shall be within the' acceptable area of Figure 5-4. REFERENCES 

                        ~(1) FSAR, Section 9.7            " Fuel Handling System" i

5-7 l Amendment No; 34, 138. 157 . -

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