ML20053B564
| ML20053B564 | |
| Person / Time | |
|---|---|
| Site: | 07002884 |
| Issue date: | 05/17/1982 |
| From: | Crow W, Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20053B556 | List: |
| References | |
| NUDOCS 8205280579 | |
| Download: ML20053B564 (5) | |
Text
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MAY 171982 SAFETY EVALUATION REPORT LONG ISLAND LIGHTING COMPANY APPLICATION DATED SEPTEMBER 25, 1978, AND THE SUPPLEMENTS THERET0 DATED MAY 9, 1979, AND APRIL 30, 1982, FOR A STORAGE LICENSE FOR FUEL FOR THE SHOREHAM NUCLEAR POWER STATION-UNIT I DOCKET NO. 70-2884 By application dated September 25, 1978, and supplements dated May 9, 1979, and April 30, 1982, Long Island Lighting Company (LIL) requested a license to receive, possess, inspect, and store 14,039 kg of uranium source material (0.711 wt% U-235) and 1864 kg of U-235 in uranium enriched up to 2.186% in that isotope in the form of finished fuel assemblies.
The fuel assemblies, which contain uranium at three nominal enrichments (0.711, 1.758, and 2.186%
U-235), will eventually be used in the Shoreham Nuclear Power Station Unit I.
Because of measurement and enrichment variations usually encountered, we propose to license a maximum enrichment of 2.25% U-235 and that the maximum possession limits be 14,908 kg of uranium source material and 1,964 kg of U-235 contained in uranium enriched in that isotope.
The finished fuel assemblies will be supplied by the General Electric Company.
The weight of the uranium contained in an individual fuel assembly is approxi-mately 183 kilograms.
The weight of U-235 in the most highly enriched assembly is 1.39 kilograms.
The fuel assemblies will be stored in their shipping containers, in the new fuel storage vault in the dry state, and in the spent fuel storage pool in the dry or wet state.
The new fuel storage vault has the capacity to accommodate 30% of a full core load.
The spent fuel storage racks have a capacity for 2184 fuel assemblies (390% of a full core load).
In both areas, spaces between fuel storage positions are designed so that it is not possible to insert a fuel assembly in any position within the rack array not intended for fuel.
The fuel assembly racks in the new fuel storage vault are designed so the center-to-center spacing between assemblies within a row is 6.625 inches and 11.5 inches between assemblies in adjacent rows.
The k of an array of fuel assemblies,inthenewfuelvault,havingamaximumU-23bIenrichment of 2.25%,
is less than 0.95 independent of the degree of water moderation.
Calculations made by the staff for the storage of new fuel in the spent fuel racks indicate a k,of greater than unity for water moderator densities in the 10% to 25% range for 3.1% enriched fuel.
All the calculations for fuel at a 2.25% enrichment indicated a k less than unity, with little safety margin.
In the submittal dated May 9, T979, LIL proposed storing fuel assemblies only in alternate rows in the spent fuel pool.
In support of this proposal, calculations were made for both 2.35% and 3.1% enriched fuel assembly arrays.
The calculations show a maximum k of 0.76 for the 2.35% fuel and a maximum k*
of 0.83 for the 3.1% enriched fueT.
In view of the NRC calculations, LIL's calculations, and the increased spacing between fuel assemblies provided for in the LIL May 9, 1979, submittal, it is our view that an adequate margin of 8205280579 820519 PDR ADOCK 07002884 C
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MAY 1 -71982 safety exists to permit safe storage of the fuel.
Accordingly, it is-recommended that Condition No. 11. be added restricting the storage of fuel 4
arsemblies in the spent fuel racks to alternate rows.
f The licensee did not specify criteria for the interim storage of fuel assemblies in their shipping containers.
Therefore, it is recommended that Condition No. 12. be added restricting the size of an array of shipping containers (inner metal and/or inner metal and outer wooden containers) to no more than four containers high.
This condition shall read as follows:
Fuel i
assemblies stored in their shipping containers (inner metal and/or inner metal and outer wooden) shall be limited to arrays up to four (4) high.
The safety of this size array has already been established (see License No. SNM-1097, Amendment No. 5, dated June 6, 1978, Docket 70-1113).
Since more than three fuel assemblies are required to achieve criticality, LIL submitted the supplement dated April 30, 1982, requesting authorization for a maximum of three fuel assemblies out of approved shipping containers or storage locations.
It is recommended Conditior. No.13. be added granting the requested authorization.
j A,* 1ation that would increase the reactivity of the storage arrays would occur it
.ne fuel assemblies were internally water moderated but the spaces between as emb1res were occupied only with air.
This might occur if a storage area were flooded, the area then drained, but with the water retained in the plastic bags which may be used to protect fuel assemblies from dust, etc.
In that case the fuel assemblies would be moderated with water, but with no water shielding between the assemblies.
To prevent such a situation, the Staff has added Condition No. 14., which requires that the fuel assemblies be stored in such a l
manner that would allow water to drain freely from within the assemblies in the event of flooding and subsequent draining of a storage area.
It is the j
Staff's opinion that with this added condition, the applicant has established reasonable and satisfactory precautions to avoid accidental criticality.
The applicant's Physical Security Plan has been reviewed by the Physical Security Licensing Branch, Division of Safeguards, NMSS, and it was approved by letter to LIL dated September 25, 1981.
The applicant has also described the basic aspects of its radiation safety control program, including a description of the training and experience of personnel responsible for administering the program.
The Staff has concluded that the applicant's radiation safety program and personnel are adequate to allow them to reasonably carry out the activities for which a license is requested.
The applicant has requested, pursuant to 10 CFR 70.24(d), an exemption from the provisions of 10 CFR 70.24.
Based on the applicant's demonstration of subcriticality under normal and accident conditions, good cause exists for exemption from the requirements of 10 CFR 70.24.
Because of the inherent features associated with the storage and inspection of unirradiated fuel ew, a~---
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3 MAY 171982 containing uranium enriched to less than 5% in the U-235 isotope when no fuel processing activities are to be performed, the staff hereby determines that granting such an exemption will not endanger life or property or the common defense and security, and is in the public interest.
This exemption is authorized pursuant to 10 CFR 70.14.
Condition No. 15. has been added granting the requested exemption.
An Atomic Safety and Licensing Board issued an order dated October 5, 1979, approving a stipulation entered into on September 18, 1979, by the North Shore Committee Against Thermal and Nuclear Pollution, the Staff and LIL.
The stipulation provided that:
l (1) prior to the issuance of a Part 70 license, the Staff will review and approve written procedures covering the storage, handling, inspection, preparation, radiation monitoring, and physical protection associated with the unirradiated new fuel assemblies at the Shoreham Nuclear Power l
Station.
(2) Prior to the time at which each fuel handling activity will initially be conducted (a) the training relevant to that activity will be completed and documented for all LIL personnel involved in the activity, and (b) the NRC will review and approve the adequacy of such training.
(3) Prior to the issuance of a Part 70 license, LIL will comply with the physical security requirements of 10 CFR 73.47(f).
The following action was taken on the above:
(1)
In reference to (1) above, the required procedures were submitted by letter dated February 9,1982, and revisions thereto submitted by ' letters dated April 30, 1982, and May 13, 1982. The procedures were reviewed and approved by the staff of the Nuclear Regulatory Commission Region I and the Office of Nuclear Material Safety and Safeguards.
(2) With respect to (2) above, Condition No. 16. has been added requiring the training, related documentation and its review and approval by the NRC before the related actisity <ill be carried out.
(3) With respect to (3) above, the referenced Part 73 section has been superseded by 10 CFR 73.0/(f).
The LIL physical security plan has already been approved by the NRC per the latter section of the regulations (see related reference identified above).
In order to provide a reasonable time frame for the review and approval of the LIL training relevant to the fuel handling activities, Condition No. 17 has been added to require the licensee to notify Region I at least one week prior to needing approval.
4 MAY 171982 CONCLUSION Based on the above statements, the Staff believes that the proposed activities can be performed without undue risk to the health and safety of the public.
It has been determined by the Staff that the applicant fulfills the requirements of 10 CFR 70.23(a).
Further, the issuance of this license is not a major Federal action significantly affecting the quality of the human environment and thus, pursuant to 10 CFR 51.5(d)(4), no environmental impact statement, negative declaration, or environmental appraisal need be prepared.
The Staff recommends approval of the application and its supplement with the addition of the following conditions:
11.
Storage of fuel assemblies in the spent fuel racks shall be restricted to alternate rows.
i 12.
Fuel assemblies stored in their shipping containers (inner metal and/or inner metal and outer wooden) shall be limited to arrays up to four (4) high.
13.
As a condition of this license no more than three (3) fuel assemblies may be out of approved shipping containers or storage racks at any one time.
14.
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 storage area.
15.
The licensee is hereby exempted from the provisions of 10 CFR 70.24 insofar as this section applies to materials held under this license.
16.
Prior to the time at which each fuel handling activity will be initially con-ducted (a) the training relevant to that activity will be completed and docu-mented for all Long Island Lighting Company personnel involved in the activ-ity and (b) the NRC Region I Office will review and approve the adequacy of such training.
17.
The licensee shall provide the NRC Region I Office a minimum of one (1) week's notice that the training requirements specified in Condition No. 16 are ready for review so that Region I personnel will have adequate time to l
review and approve the training.
Original Signed by f
N. Kot lach Norman Ketzlach Uranium Process Licensing Section I
Uranium Fuel Licensing Branch Orir.inal aigned b' t.
Division of Fuel Cycle and y
W. T. Crow Material Safety l
Approved by:
W. T. Crow, Section Leader i
- See Previous Concurrence Sheet.
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4 14.
Fuel assemblies shall be stored in such a manner that water wod1d drain
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freely from the assemblies in the event of flooding and subsequent draining of the storage area.
15.
The licensee is hereby exempted from the provisions of 10 CFR 70.24 insofar as this section applies to materials held u er this license.
16.
Prior to the time at which each fuel andling activity will be initially conducted (a) the training releva to that activity will be completed and documented for all Long Isla d Lighting Company personnel involved in the activity and (b) the NRCj 11 review and approve the adeqt.acy of such training.
1 Norman Ketzlach i
.-ranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety l
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l Approved y:
W. T. Crow, Section Leader Uranium Process Licensing Section
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