ML20028F885
| ML20028F885 | |
| Person / Time | |
|---|---|
| Site: | 07002968 |
| Issue date: | 09/30/1982 |
| From: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Jennifer Davis NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 8302040597 | |
| Download: ML20028F885 (6) | |
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7o-2947 T P E C L E V E i A N D E L E C T R I C
! L L U M ! !! AT I N G C O M P A L! Y P O DOX 5000 - CLEVELAND, Ohio 44101 - TELEPHONE (216) 622-9800, - ILLUMINATING BLOG. - 55 PUBLIC SOUARE Semng The Best Location in the Nation
[p}/hpp/jdg D dwyn R. Davidson VicE PRtSIDEN systru EuciNe tarwo 48D constauction September 30,1982
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John G. Davis, Director M
Office of Nuclear Material Safety and Safeguards R[C{fy{g M U. S. Nuclear Regulatory Commission Washington, D. C.
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Perry Nuclear Power Plan h n T o n. 124,{ F
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Docket Nos. 50-440; 50-4419 SNM License Application
\\f" Amendment i
Dear Mr. Davis:
In accordance with 10 CFR 70.34, Amendment of Licenses, the Cleveland Electiac illuminating Company (CEI) requests that the Application for Storage Only of Unirradiated Reactor Fuel and Associated Radioactive Material dated August 30, 1982, be amended to have in ef fcct the Physical Security Plan instead of the Interim Security Plan. It is CEl's intention to have the Physical Security Plan in effect prior to arrival of unirradiated reactor fuel and associated radioactive material on site.
The Perry Nuclear Power Plant Security Plan, dated March 1,1982, was approved in a.etter dated June 2,1982, from A. Schwencer, Licensing Branch No. 2.
Since the Physical Security Plan will be in ef f ect prior to the arrival of unirradiated reactor fuel and associated radioactive material on site, an Interim Security Plan will not be submitted.
Enclosed are eight (8) copies of the amended pages of CEl's Application for storage only of Unirradiated Reactor Fuel and Associated Radioactive Material. Please insert the Amendment i material dated September 30, 1982, into the Special Nuclear Material License Application as per the attached Amendment 1 Instruction Sheet.
If you have any questions, please contact me.
,s Very truly yours, A,
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1 AMiPOMENT I INSTRUCTION SHEET REMOVE INSERT Page 11 Page 11, Amendment !
Page 24 Page 24, Amendment I-Page 26 Page 26, Amendment 1 Page 32 Page 32, Amendment 1 i
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l-SNM Lic n o I
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1.2.1 Storage Locations Fuel bundles or assemblies will be stored in the spent fuel I
storage racks in the Reactor Building, floor elevation 689'-6",
or the spent fuel storage racks or new fuel vaults in the Fuel Handling Building, floor elevation 620-6".
Descriptions and drawings of these areas are provided in the FSAR as refer-enced in Section 1.2.4.
The relative locations of these areas are as shown in Figures 4 and 5.
Truckloads of fuel, consisting of 15 containers of two (2) bundles each, will be temporarily stored in the Fuel Handling Building during receipt, inspection and channeling of the bundles. The bundles will be stored in the metal shipping containero during this activity.
If delays due to malfunc-tions of eqttipment or test or construction activities should occur, a maximum of 30 containers, or 60 bundles, could be storal in this area.
If equipment um1 functions preclude the unloading of fuel, one trailer could be parked in the Fuel Handling Building. The 15 containers on the trailer would be included in the 30 container maximum note above.
Criticality control is discussed in Sections 2.2.2 and 2.2.3.
Both the Fbel Handling Building and the Containment Building are within the Protected Arce and access is controlled in ac-cordance with the Physical Security Plan.
1.2.2 Adjacent Area Activities Consistent with the administrative controls and restrictions provided in the paragraphs below, no operations other than fuel
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and component inspection. handling, and storage will be per-l formed in the " fuel storage and handling" area.
Crane opera-tions will be restricted such that no more than one channeled fuel assembly or equivalent weight per crane will be allowed over storage areas containing fuel.
Loaded fuel shipping containers or properly designed overload test weights may be handled in these areas provided they are at no time suspended over the fuct assemblics in storage.
Any non-fuel related activi-ties which must be conducted in the fuct handling area will be reviewed and approved by the General Supervising Engineer.
Technient Section, or his designee.
Any non-fuel activities in the "fuct storage and handling aren", on elevation 620'-6" of the Fuel Handling Building will be restricted as follows during fuct handling:
i 1
a)
No painting, grinding, sandblosting, or similar activites are allowed.
b)
No overhead work is allowed, c).
No crane operations other than those required for fuct handling and inspection are allowed.
September 30, 1982 Amendment 1
SNM Liccn;3 P g2 24 1.3 Physical Protection The quantity of U-235 in the fuel (contained in uranium enriched above natural uranium but less than 10% in the U-235 isotope) exceeds 10,000 grams and the fuel therefore is specified to be "special nuclear material of low strategic significance", in 10CFR72.2 (y) 3.
The physical protec-tion requirements given in 10CFR73.67 (f) are addressed in the Physical Security Plan for protection of the unirradiated fuel bundles.
As noted in 1.1.3 of this application the average initial core enrichment is 1.876%
The highest enrichment contained in any bundle is 3.00% U-235.
1.4 Transfer of Special Nuclear Materials 1.4.1 Fuel Shipments General Electric Company will be responsible for the shipment of fuel to the plant site from their Wilmington, N.C. facility.
The fuel will be shipped in approved shipping containers.
If for any reason fuel would have to be shipped back to the Wilmington facility from the plant, CEI will be responsible for the shipment.
1.4.2 Packaging of Fuel for Transportation General Electric Company will be responsible for the packaging of fuel for s'tipment from the Wilmington facility to Perry.
CEI will be responsible for the packaging of any fuel which is required to be returned to the GE Wilmington facility.-
1.5 Financial Protection and Indemnity Proof of financial protection will be provided to meet NRC requirements and will be forwarded at a later date.
2.0 HEALTH AND SAFETY 2.1 Radiation Control 2.1.1 Training and Experience The technical qualifications for personnel with Radiation Protection responsibilities are described in Table 13.1-3 of the FSAR.
2.1.2 Contamination Monitoring Administrative controls will be covered under the sections of the Perry Nuclear Power Plant Operations Manual which govern the plant Health Physics Program. These procedures include receipt surveys on new fuel, fuel inspectioa surveys, storage September 30, 1982 Amendment 1
SNM LicinC2 e
P g2 26 2.2.2 Storage of Loaded Shipping Containers The fuel bundles may be stored in their steel shipping con-tainers.
If they are stored in this way, the shipping con-tainers will be stored in no more active array than they were during shipping. The containers may be stacked no more than 3 containers high. The shipping containers will be located in limited access areas according to the Physical Security Plan.
l 2.2.3 Nuclear Safety of Storage Location 2.2.3.1 Criticality Control New Ebel Vaults The calculations of k are based upon the geo-metric arrangements oINhe fuel array and sub-criticality does not depend upon the presence of neutron absorbing materials. The arrangement of fuel assemblies in the fuel storage racks results in k below0.95inadryconditionorcompletelyfloodIbf with water which has a density of I g per cc.
To meet the requirements of General Design Criterion 62, geometrically-safe configurations of fuel stored in the new fuel array are employed to assure that k will not exceed 0.95 if fuel is stored in the dry,gg condition or if the abnormal condition of flooding (water with a density of 1 g/cc) occurs.
In the dry condition, k is maintained equal to or less than 0.95 due to8bermoderation.
In the flooded condition, the geometry of the fuel storage array assures the k
will remain equal to or less than 0.95 due t8$vermoderation. The floor of each vault is sloped to a drain at the low point to drain any water that may be int rod uced. The design of the fuel, racks, and vault ensures that water will not be retained in or around a channeled or unchanneled fuel bundle should the vault be flooded and drained.
The new fuel storage racks are designed to store the fuel assemblies in an array which is suf ficient to maintain a k of 0.95 or less in the normal dry condition or bnormal completely water flooded condi-tion. The racks are not designed to maintain a k of 0.98 or less under optimum moderation (foam, sEN1 droplets, spray or fogging). The condition of optimum moderation is precluded since the new fuel storage vault is provided with solid watertight cover.
c.dministrative controls will be used to preclude entry of sourceo of optimum moderation into the new i
September 30, 1982 Amendment I
l SNM Licina Pcg2 32 not be possible under these accident conditions. The conse-quence of the accident would be limited to the minimal ef fect of possible rupture of fuel rods and subsequent release of unirradiated uranium dioxide fuel.
3.0 OTHER MATERIAL REQUIRING NRC LICENSE Authorization is requested to receive, possess, inspect and use antimony -
beryllium (SbBe) neutron sources, in-vessel neutron detectors containing U-235 enriched greater than 20% and an irradiated neutron detector storage cask containing depleted uranium.
These are in addition to the fuel bundles previously described in this application.
3.1 In-Vessel Neutron Detectors 3.1.1 Description The neutron detectors consist of three types:
Source Range Monitors (SRM), Intermediate Range Monitors (IRM) and Local Power Range Monitors. All of these detectors are scaled sources. The Transvering In-Core Probes (TIP) are the gamma sensitive type and do not contain any special nuclear material.
The quantities of U-235 are shown in the following table:
Activity Qty.
Description Grams U-235 (microcuries)
(See Note Per Per Below)
Detector Total Detector Total 8
SRM Detectors
.00272
.02176 5.82 X 10~
4.66 X 10
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~3 16 IRM Detectors
.00075
.01200 1.60 X 10 2.56 X 10
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196 LPRM Detectors
.00022
.04312 4.71 X 10 9.23 X 10
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The total quantity of U-235 enriched greater than 20% is 0.07688 grams. This quantity of enriched U-235 does not exceed the " Formula quantity" defined in 10CFR73.2 bb.
Therefore, the physical protection requirements of 10CFR73 do not apply.
3.1.2 Storage and Handling Neutron detectors may be temporarily stored adjacent to the fuel pools in the Nel Handling Building under the auspices of the Physical Security Plan. The neutron detectors will be l
installed in their normal use configuration in the reactor vessel when not stored in the Nel Handling Building. Storage in this configuration will be in the detector dry tubes in the reactor vessel for the SRM, IRM and LPRM detectors. The spare neutron detectors will be stored adjacent to the fuel pools in the Fuel Handling Building under the auspices of the Physical l
Security Plan.
September 30, 1982 Amendment 1 i
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