ML20031E991
| ML20031E991 | |
| Person / Time | |
|---|---|
| Site: | 07002937 |
| Issue date: | 10/02/1981 |
| From: | Kenyon B PENNSYLVANIA POWER & LIGHT CO. |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 19754, PLA-941, NUDOCS 8110190004 | |
| Download: ML20031E991 (3) | |
Text
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RECBVm 3N-55 October 2, 1981 00CKEICL8" 6
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Washington, D.C.
20555 C (7 SUSQUEllANNA STEAM ELECTRIC STATION SNM LICENSE SNM-1878 ER 100450 FILE 841-06 PLA-941 DOCKET #70-29-37 Reference s:
December 23, 1980 letter--Curtis to Director NMSS (PLA-594)
February 27, 1981 letter--Curtis to Director NMSS (PLA-647)
The attached page amends our December 23, 1980 application for SNM license number SNM-1878, as modified by letter dated February 27, 1981. We propose that the maximum U235 enrichment of 3.00 weight percent be increased to a maximum U235 enrichment of 3.10 weight percent. This change accounts for measurement and enrichment variations usually encountered during the manufacturing process. The total quantity of U235 licensed under SNM-1878 remains unchar.ged at 3,043 Kg.
The December 23, 1981 transmittal may be updated by removing page 2 (dcted 02/27/81) and page 3 (undated) and inserting the attached pages 2 and 3 (dated 10/2/81).
This application is exempt from licensing fees per 10CFR170.11(3).
Any questions regarding this application should be directed to Mr. Thomas E. Ganglof f, (215) 770-5/480 of the Nuclear Licensing Group.
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'd Bruce D. Kenyon 9;
OCT 8 M* i Vice President-Nuclear Operations g,
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Attachments
.8110190004 811002 (DRADOCK 07002937
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3.0 CORPORATE INFORMATION The information set forth in the application for Construction Permit and Operating License, Docket No. 50-387 dated July 20, 1978 for the Susquehanna Steam Electric Station Unit 1, is hereby incorporated by reference.
Information concerning control and ownership of the applicant is also set forth in the application for Construction Permit and Operating License.
4.0 RADIOACTIVE MATERIAL Initial Core Fuel Assemblies Maximum square dimension of 5.47 in, fuel Active fuel length 150 in.
Overall fuel bundle / assembly length 1/6.16 in.
Maximum square dimension of fuel channel 5.45 in, t
Overall channel length (maximum) 166.97 in.
Channel wall thickness
.080 in.
Rod array type 8x8u 64 rods 62 fuel rods 2 water rods Fuel rod Pitch 0.640 in.
I Fuel rod clad thickness 0.032 in.
Rod clad material Zircaloy Fuel rod outside diameter
.483 in.
Fuel pellet diameter
.410 in.
Fuel pellet material UO2 3
Nominal fuel stack density 10.32 gm/cm t
Total number of fuel 764 (3 types) assemblies t
Maximum U-235 enrichment (weight %)
3.10 Average U-235 enrichment (weight %)
1.88 Average U-235 enrichment (weight %)
.711 1.76 2.19 per assembly type Number of assemblies92-240 432 per type 10/2/81 i-
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UO2 v2ight p r cerembly (kg) 207.58 207.31 207.00 Gd 02 3 wieght per assembly (kg) 0.0 0.20 0.44 Average UO weight per fuel rod (kg) 3.34----------
j U weight per assembly (kg) 182.96 182.73 182.45 (ib) 403.36 402.85 402.23 The composition and location of each type fuel rod in the assembly naving the highest enrichment can be found in NEDC-21307, February 1977, entitled "BWR5 Standard Plant Fuel Design Summary" (pgs 15,17 &
18; figs 6 & 8).
These figures are included as proprietary figures 4.3-3 and 4.3-5 of the Susquehanna SES FSAR. Other fuel bundle types are described in NEDE 20944P.
The maximum amount of special nuclear material, as kilograms of U-235, which may be possessed at any one time is 3,043 kilograms. This represents the initial core and fifty additional assemblies per enrichment type based on nominal weights and enrichments.
5.0 TRANSPORTATION All initial core fuel bundle are to be delivered to the site in accordance with shipping procedures and arrangements of the General Electric Company. The fuel bundles will be shipped by the fuel manufacturer as authorized under NRC Certificate of compliance number USA /4986/B(F) Revision 8.
Fuel will normally be shipped to the site by truck, with a maximum of 16 containers per truck and two bundles per container.
6.0 STORAGE CONDITIONS The fuel bundle / assemblies will be stored on the refueling floor of the Reactor Building (see SSES Fiaal Safety Analysis Report, Section 9.1) in either the new fuel storage vault dry, in the spent fuel pool, or in their metal shipping containers on the refueling floor. When the fuel bundle / assemblies are stored in the spent fuel pool, the pool may be dry, partially flooded, and/or completely flooded during residence in the storage rack. The refueling floor is surrounded by structural steel and metal siding and, therefore, it is considered unlikely that a fire will occur. However, the use of flammable materials on the refueling floor will be carefully controlled as an added margin of safety. In addition, the movement of the new fuci vault cover will be administrative 1y controlled by approved plant procedures. The refueling floor is shown on SSES Final Safety Analysis Report (FSAR) Figures 1.2-23, 1.2-24, 1.2-25, and 9.1-16B.
Preoperational testing, to the extent necessary to prove that tiu fuel handling equipment is functioning properly and is safe to handle the 3
10/2/81 1W~ux
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