ML20210G948
| ML20210G948 | |
| Person / Time | |
|---|---|
| Site: | 07002972 |
| Issue date: | 09/03/1986 |
| From: | Johnson I COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 2032K, 27403, NUDOCS 8609260014 | |
| Download: ML20210G948 (7) | |
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Address Reply to: Post Omco Box 767
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September 3, 1986 kA
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RETURN TO 396-SS g-su r
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Attn: Materials Licensing Section RECENED 3
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Subject:
Byron Station SEP 15 W86 F r Special Nuclear Materials License (SNM) g, NUCLEAR REGULATORY /
Number 1916 9
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Dear Sir:
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This is to request amendment of the Byron Station Special Nuclear Materials (SNM) License Number 1916.
Amendment I contains proposed changes that would permit the wet storage of Byron Unit 2 new fuel in the spent fuel storage pool, the storage and installation of the Byron Unit 2 startup sources, and other changes that are considered to be administrative in nature resulting from the first two changes.
Attachment A to this letter contains the proposed changes to SNM-1916 and the basis for each change. Attached are two copies of the requested amendment.
Expedited consideration of this amendment is requested. The revision to license SNM-1916 is needed to permit transfer of the californium neutron sources in advance of the commencement of core loading and finalization of the core loading procedures. It appears that issuance of the amendment by October 10, 1986 will provide adequate lead time, please contact this office at (312) 294-3977 if there are any further questions regarding this submittal.
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- fer 10CPN 170.11(3), we have determined that no fee is required.
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ttachment A: Proposed Amendment to the
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ATTACHMENT A Proposed Amendment to the Byron Station Special Nuclear Materials License No. 1916 Present Wording:
19.
Fuel assemblies shall be stored in such a manner that water would drain freely from the assemblies in the event of flooding and subsequent draining of the fuel storage area.
New fuel assemblies may be stored in the Spent Fuel Storage 20.
Pool subject to the following additional conditions:
The maximum U-235 enrichment shall be 3.22 w/o.
a.
b.
The fuel assemblies shall be stored in a checkerboard pattern.
The Fuel Handling Foreman shall verify correct fuel c.
assembly location after insertion of each fuel assembly into the assigned storage rack in accordance with a prepared written procedure approved by an Operating Engineer and the Technical Staff Supervisor.
d.
An independent loading verification shall be made by a Quality Control Inspector.
The fuel handling foreman and the quality control e.
inspector shall each sign a document assuring proper storage of each fuel assembly.
f.
The fuel assemblies shall be protected to preclude damage and preserve fuel assembly cleanliness while fuel is stored in the Spent Fuel Storage Pool.
Proposed Wording:
Fuel assemblies either stored in the New Fuel Storage Vault 19.
or stored dry in the Spent Fuel Storage Pool shall be stored in a manner that water would drain freely from the assemblies in the event of flooding and subsequent draining of the fuel storage area.
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. 20.
New Fuel Assemblies may be stored in the Spent Fuel Storage i
Pool subject to the following conditions:
The maximum U-235 enrichment shall be 3.20 w/o for a.
i dry storage.
1 b.
New fuel assemblies, when stored in~a dry condition i
shall be stored in a checkerboard pattern.
i When new fuel is stored in a dry condition, the Fuel c.
Handling Foreman shall verify correct fuel assembly l
location after insertion of each fuel assembly into the assigned storage rack in accordance with a j
prepared written procedure approved by an Operating Engineer and the Technical Staff Supervisor.
d.
When new fuel is stored in a dry condition, an independent loading verification shall be made by a i
i Quality Control Inspector.
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e.
When new fuel is stored in a dry condition, the Fuel Handling Foreman and the Quality control Inspector shall each sign a document assuring proper storage of each fuel assembly.
f.
When new fuel is stored in a dry condition, the fuel assemblies shall be protected to preclude damage and preserve fuel assembly cleanliness.
2 g.
New fuel may be present in the spent fuel storage l.
pool while the pool in being flooded, provided that the checkerboard loading pattern is maintained until i
the pool is completely flooded.
h.
New fuel storage and fuel handling operations, while the pool is flooded, will be conducted in accordance with Chapter 9 of the Byron FSAR, as amended.
29.
Two fuel assemblies may be placed in two water filled failed fuel containers for primary neutron source i
installation and shielded storage provided that the water is at a boron concentration of at least 2000 ppm.
Reason for Chances i
i The change being made to Item 19 references the specific l
locations where fuel assemblies may be stored, (i.e. in the New Fuel Storage Vault and the Spent Fuel Storage Pool).
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. Changes to Item 20: a) result from making provisions for the dry storage of new fuel in the Spent Fuel Storage Pool. The proposed amendment includes references to " dry storage" as part of the license condition. The amendment also changes the maximum U-235 enrichment to 3.20 w/o to be consistent with the criticality analysis for dry storage of new fuel in the Spent Fuel Racks as found in Chapter 9 of.the Byron Station Final Safety Analysis Report (FSAR).
Changes made to Items 20 b) through f) inclusive result from including references to " dry storage"-as conditions to the SNM.
Items 20 g) and h) will allow the storage of new fuel in the Spent Fuel Storage Pool while the pool is being flooded.
Item 29 will modify SNM license 1916 to allow the temporary storage and installation of start-up sources. Due to ALARA considerations, it is desirable to install the two californium primary neutron sources into two new fuel assemblies in the spent fuel pit. Two damaged fuel storage containers filled with borated water will be used for radiation shielding.
The containers will be located in the failed fuel container rack shown in FSAR figures 9.1-2 and 9.1-4 (enclosed). This rack is designed to maintain the center-to-center spacing at greater than 20 inches. The installation operation will be performed shortly before the start of core loading and the two new fuel assemblies with installed neutron sources will be temporarily stored in these containers until transferred to the reactor.
Basis for Change:
The changes being made to Items 19 and 20 a) through f) are
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administrative in nature, resulting from either referencing the locations where new fuel may be stored (i.e. New Fuel Storage Area and the Spent Fuel Storage Pool)'or have been made to include the dry storage provision specifically in the license conditions of the SNM.
An additional change made to item 20 a) is to make the U-235 enrichment value consistent with that of Chapter 9 to the Byron FSAR.
The provisions for dry storage of new fuel in the Spent Fuel Storage Pool were approved in the the SNM License No. 1916, dated March 4, 1985. These proposed changes merely reference this provision in each license condition item where it is applicable. -
Items 19 g) and h) will permit the storage of new fuel in the Spent Fuel Pool in the event it is flooded and as it is being flooded with borated water. This provision is sought in the event that the Byron Unit 2 fuel is being loaded at the same time that Byron Unit 1 is being refueled.
- Chapter 9 of the Byron FSAR addresses three different cases; dry storage of new fuel with 3.?.0 enrichment in a checkerboard loading pattern, optimum moderation (i.e. minting) with k,gg less than 0.98 and flooded conditions with kegg less than 0.95.
Criticality analyses have shown kegg to be less than the design basis limit in both cases.
Therefore, the storage of new fuel in the Byron Spent Fuel Storage Pool while it is being flooded (Item 20g)) and the storage of new fuel in a flooded pool (Item 20h)) is bounded by criticality analyses found in Chapter 9 of the Byron FSAR.
Item 29 permits the storage and placement of startup sources in fuel assemblies prior to the commencement of core loading. The two fuel assemblies to receive primary sources will be installed in failed fuel containers located in two nonadjacent failed fuel container rack locations 44 inches apart. The failed fuel container has the cylindrical dimension of a 13 inch schedule 10 pipe and contains a stainless steel angle framework centered in the container to support the fuel assembly. This framework is nominally 9 inches square. Between the two loaded failed fuel containers will be a third borated water filled, failed fuel container to be used as a shielded temporary storage location for the primary source rod. When we unload the new fuel vault into the spent fuel pit, the closest a new fuel assembly would be stored with respect to a source bearing assembly would be 20 3/8" inches.
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spacing. This arrangement has been analyzed by NUS Corporation, the original rack criticality analyst, and found to have no adverse affect on certter-Yo CC OF the original results.
The total amount of water used will not exceed 250 gallons. Even if this borated water were to completely leak into the surrounding Spent Fuel Pit, it would be less than 1/4 inch in depth, still more than 18 inches below the active fuel in storage.
, Normal station radiation procedures will be used to support the movement of primary neutron sources. Health Physics personnel will monitor personnel area dose rates, conduct area surveys and contamination swipe surveys, and appropriately post any radiation areas. Personnel dosimetry will include badges specifically designed for neutron exposure. Expected dose rates for source loading both with and without borated water shielding are as follows for selected areas:
Area Without Water With Water Welding Work Area 158 mrem /hr 0.00326 mrem /hr (9 ft. above source) 426' elevation at North 4.16 mrem /hr 0.079 mrem /hr end of pit South SFP wall at 688 mrem /hr 50.8 mrem /hr source level 426' elevation at South 9.51 mrem /hr 5.9 E-6 mrem /hr end of pit l
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