ML20114B960
| ML20114B960 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/25/1992 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20114B957 | List: |
| References | |
| NUDOCS 9209010016 | |
| Download: ML20114B960 (5) | |
Text
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5.3 REACTOR j
Acolicability i;
Applies to the design features of the reactor core and reactor coolant
- system, i
l Ob.iective I
To define the significant design features of the reactor core and reactor coolant system.
l Specification i
5.3.1 REACTOR CORE i
5.3.1.1 The reactor core is composed of slightly enriched uranium dioxide pellets contained in fuel rods. A fuel assembly i
normally contains 208 fuel rods arranged in a 15 by 15 lattice.
l The details of the fuel assembly design are described in THI-1 l
UFSAR Chapter 3.
5.3.1.2 The reactor core shall approximate a right circular cylinder with an equivalent diameter of 128.9 inches. The active fuel 4
height is defined in TMI-l UFSAR Chapter 3.
l 5.3.1.3 The core average and individual batch enrichments for the l
present cycle are described in THI-l UFSAR Chapter 3.
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The control rod assemblies (CRA) and axial power shaping rod 5.3.1.4 assemblies (APSRA) are distributed in the reactor core as shown l
in TMI-l FSAR Chapter 3.
The CRA and APSRA design data are also described in the UFSAR.
l 5.3.1.5 The TMI-l core may contain burnable poison rod assemblies (BPRA) as described in TMI-l UFSAR Chapter 3.
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5.3.1.6 Reload fuel assemblies and rods shall conform to design and evaluation data described in the UFSAR. 2gnrichment shall not exceed a nominal 5.0 weight percent _of U 5.3.2 REACTOR COOLANT SYSTEM i
5.3.2.1 The reactor coolant system shall be designed and constructed in i
accordance with ccde requirements.
(Refer to UFSAR Chapter 4 for details of design and operation.)
5.3.2.2 The reactor coolant system and any connected auxiliary systems exposed to the reactor coolant conditions of temperature-and pressure, shall be designed for a pressure of 2,500 psig and a temperature of 650'F. The pressurizer and pressurizer surge line shall be designed for a temperature of 670*F.
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5-4 Amendment No. J7%, H 7, JEP, 157 92o9010016 920825 PDR ADOCK 05000289 P
5.4 NEM AND SPENT FVEL STORAGE FACILITIES
{*
Acolicability Applies to storage facilities for new and spent fuel assemblies.
4 Ob.iective To assure that both new and spent fuel assemblies will be stcred 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 spnt fuel pools.
For the new fuel storage vault, the fuel assemblies are stored in racks in parallel rows, having a nominal center to center distance of 21-1/8 inches in both directions. The spacing in the new fuel less than 0.95 based on storage vault is sufficient to maintain K,, d water or less than 4
storage of fuel assemblies in clean unborate 0.98 based on storaga in an optimum hypothetical low density moderator (fog or foam) for fuel agemblies with a nominal enrichment of 5.0 weight percent U When fuel is being stored in the 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 fissile or moderating material to provide sufficient neutron leakage to satisfy the NRC maximum allowable reactivity value under the optimum low moderator density condition.
For Spent Fuel Pool "A", the fuel assemblies are stored in racks in parallel rows, having a nominal center to center distance of 11.1 inches in both directions for the Region I racks and 9.2 inches in both directions for the Region II racks. The spacing in the Spent Fuel Pool "A" storage locations for both Region I and II is adequate to maihtain K,,
less than 0.95.
Region I will store fuel with a maximum 5.0 per, cent initial enrichment.
Region II will store new fuel with low ent! hment. When fuel is being moved in or over the L
Spent Fuel Storage Pool "A" and fuel is being stored in the pool, a boron concentration of at least 600 ppmb must be maintained to meet the NRC maximum allowable reactivity value under the postulated accident condition.
For Spent Fuel Pool "B", the fuel assemblies are stored in racks in parallel rows, having nominal center to center distance of 13-5/8 inches in both directions. This spacing is sufficient to maintain a K,,,ichment of 4.37 weight percent Ulessthan0.95basedonfuelasgmblieswit enr When fuel is being moved in or over the Spent Fuel Storage Pool "B" and fuel is being stored. in the pool, a boron concentration of at least 600 ppmb must De maintained to meet the NRC maximum allowable reactivity value under the postulated accident condition.
b.
Deleted.
c.
New fuel may also be stored in shipping containers.
i 5-6 2nendment No. JM,164
4 5.4.2 SPENT FUEL STORAGE (Reference 1) a.
Irradiated fuel assemblies will be stored, prior to offsite shipment, in the stainless steel lined spent fuel pools, which are located in the fuel handling building.
- b. Whenever there is fuel in thw pool except for initial fuel loading, the spent fuel pool is filled with water borated to the j
concentration used in the reactc.' 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:
a 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 Buildino l
Fuel Assys.
846
- 496 54 Cores 4.78 2.8 0.37 Includes three spaces for accommodating failed fuel NOTE:
- containers. An additional 648 storage locations can be installed to provide a total of 1494 locations or 8.44
- cores, e.
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 Dry New Fuel Storage Area Building Spent and Soent Fuel Pool A Fuel Pool B Horiz.
0.38 g l
Vertical 0.25 g The "B" pool fuel storage racks are designed using the NOTE: **
floor response spectra of the Fuel Handling Building.
- f. Fuel in the storage pool gall have a U ss loading equal to or 2
less than 66.2 grams of U per axial centimeter of fuel I
assembly.
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- g. When spent fuel assemblies are stored in the Spent Fuel Pool "A", Region 11 storage locations, the combination of initial enrichment and cumulative burnup for spent fuel assemblies shall be within the acceptable area of Figure 5-4.
- h. When spent fuel assemblies are stored in the Spent Fuel Pool "B", storage locations, the combination of initial enrichment and cumulative burnup for spent fuel assemblies shall be within the acceptable area of Figure 5-5.
REFERENCES (1) UFSAR, Section 9.7
" Fuel Handling System" 5-7 Amendment No. Ef, J)S, J57, 164
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INITIAL EtRICHMENT, WTs U-235 Figure 5-4 MINIt1JM BURNUP REQUIREMENTS FOR Fl.EL IN REGION II OF THE POOL A STORAGE RACKS -
5-7a Amendment No. 164
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ACCEPTABLE BURNUP
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' MINIMUM BURNUP REQUIREMENTS FOR FUEL IN THE POOL "B" STORAGE RACKS 5-7b
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