ML19319D076
| ML19319D076 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/17/1978 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19319D073 | List: |
| References | |
| NUDOCS 8003050858 | |
| Download: ML19319D076 (5) | |
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Technical Specification Change Recuest No. 23 (Apoendix A)
Replace pages 5-4, 5-5 and 5-6 with the attached revised pages 5-4, 5-5 and 5-6.
Proposed Change l.
Change the maximum enrichment in weight percent of U-235 in Section 5.3.1 from "3.50" to "3.30."
2.
Expand Section 5.6.1 to indicate that the high density spent fuel racks will have a 10.5 inch center-to-center spacing instead of the present spacing of 21-1/8 inch center-to-center distance.
3.
Change the number of spent fuel storage locations from "240" to "1153" and the number of failed fuel containers from "15" to "6."
Reason for Proposed Change As a result of the great deal of uncertainty concerning the future of reprocessing nuclear fuel in the United States, Florida Power Corporation has decided to pursue the licensing and subsequent installation of high density fuel storage racks at Crystal River Unit 3.
We feel that this course of action is required in order to protect our ability to continue to operate CR#3 until resolution of the spent fuel problem is achieved on a national level.
To achieve this goal, Florida Power Corporation has hired Nuclear Energy Services, Inc. (NES) to design and fabricate the high density, fuel storage racks'for CR#3.
On January 9, 1978, FPC filed with the NRC conceptual design information concerning this proposed design modification.
On March 3, 1978, FPC sub-mitted for the Comission's review the following detailed design information:
1.
Poison Material Description - Soecification 80A1488.
2.
NES Report
" Structural Analysis Ocsign Report for the Crystal River Unit 3 High Density Fuel Storage Racks," NES 81 A0522.
3.
NES Report
" Thermal-Hydraulic Design Analysis Report for the Crystal River Unit 3 High Density Fuel Storage Racks," NES BlA0523.
4.
NES Engineering Drawings:
80E1489, 80E1490, 8001491, 8001492, 80D1493, 80D1494, 80D1495, 8001496, 3001497, 80D1498, 80D1499 and 80D1500.
5.
NES Specification No. 80A1487
" Specification for the Fabrication and Inspection of the Crystal River Unit 3 High Density Fuel Storage Racks".
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The results of the detailed Nuclear Analysis of the high density rack modifications as well as FPC's Environmental and Cost / Benefit Assessment of the new design will be submitted to the NRC on March 17, 1978.
Along with the detailed design information identified above, the NRC requested that FPC submit at this time any changes to the CR#3 Technical Specifications that are necessary as a result of our intentions to c:pand the spent fuel storage capacity at CR#3.
In response to this request, FPC is submitting to the Commission the attached changes to Section 5.0 3
of the CR#3 Technical Specifications.
Safety Analysis Justifying Proposed Change The safety analysis justifying the changes proposed to the CR#3 Technical Specifcations is contained within the analyses submitted in the above-mentioned FPC letters dated January 9,1978, March 3,1978, and March 17, 1978.
t DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 55 psig and a temperature of 281*F.
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5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The rector core shall contain 177 fuel assemblies with each fuel assembly containing 208 fuel rods clad with Zircaloy -4.
Each fuel 4
rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 2229 grams uranium.
The initial core loading shall have a maximum enrichment of 2.83 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 3.30 weight percent U-235.
4 The first cycle fuel loading shall contain 68 burnable poiEon rod assemblies with each assembly containing up to 16 burnable poison rods of sintered Al 0 -B C clad with Zircaloy-4.
23 4 CONTROL RODS 5.3.2 The reactor core shall contain 61 safety and regulating and 8 axial power shaping (APSR) control rods.
The safety and regulating control rods 4
shall contain a nominal 134 inches of absorber material..
The APSR's shall contain a nominal 36 inches of absorber material'at their lower ends.
The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium.
All control rods shall be clad with stainless steel tubing.
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CRYSTAL RIVER - UNIT 3 5-4 t;
DESIGN FEATURES 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
a.
In accordance with the code requirements specified in Section 4.1.2 of the FSAR, with allowance for normal degradation pursuant to applicable Surveillance Requirements.
b.
For a pressure of 2500 psig, and c.
For a temperature of 650*F, except for the pressurizer and pressurizer surge line which is 670*F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12,180 1 200 cubic feet at a nominal T of 525'F.
avg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 The new fuel storage racks are designed and shall be maintained with a nominal 21-1/8 inch center-to-center distance between fuel assemblies placed in the storage racks.
The high density spent fuel storage racks are designed and shall be maintained with a nominal 10.5 inch center-to-center distance between fuel assemblies placed in the storage racks.
Both of these rack desi gns ensure a keff equivalent to < 0.95 with the storage pool filled with unborated water.
The kef 1 6.95 includes a conservative allowance of >1% ak/k for uncertainties.f of DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 138 feet 4 inches.
CRYSTAL RIVER - UNIT 3 55
m
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DESIGN FEATURES CAPACITY ~
5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1153 fuel assemblies and 6 failed fuel containers.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified-in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limit of. Table 5.7-1.
CRYSTAL RIVER - Unit 3 5-6 t