ML20002E260
| ML20002E260 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1980 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| Shared Package | |
| ML20002E259 | List: |
| References | |
| RTR-REGGD-3.054, TASK-FP-034-4, TASK-FP-34-4, TASK-OS REGGD-03.XXX, REGGD-3.XXX, NUDOCS 8101260841 | |
| Download: ML20002E260 (6) | |
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O DRAFT VALUE/ IMPACT STATEMENT 1.
THE PROPOSED ACTION 1.1 Description Spent fuel may be stored in either a wet or dry mode. Water basins have largely been used since the mid-1940s for the handling, transfer, and storage of spent fuel at reactor sites. There is a strong indication that spent fuel can be stored under water for several decades without serious degradation.
Dry storage has not been used for spent fuel from commercial light water reac-tors, but has been used for a number of years for other types of spent fuel.
One of the principal design parameters for a spent fuel storage intallation that is applicable to all modes of storage is the heat generation by the fuel.
This proposed action will present values of heat generation rates that are acceptable to the NRC staff for use as design input for an Independent Spent Fuel Storage Installation (ISFSI).
l.2 Need A number of methods have been developed for calculating the long-term heat generation rates of power reactor spent fuel as a function of burnup and decay times. No standard method for calculating this long-term heat generation has been published by NRC, nor has the practice of applicants or the staff in this respect been uniform.
A definite need for criteria covering this parameter exists.
1.3 Value/ Impact 1.3.1 NRC The value of the proposed action to the NRC staff will be the consistent use of standardized methodology to determine heat generation values.
Since the accepted values of heat generation and the methodology proposed to determine such values will be the same as the values and methodology often used now by f
the staff, there should be little impact.
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1.3.2 Other Government Aaencies This proposed action would provide a standardized set of values for use by the Department of Energy in the design and construction of ISFSI facilities.
1.3.3 Industry The value/ impact on applicants will be the same as that on the NRC staff.
The time required to determine heat generation values by the proposed methodo-logy is believed to compare favorably with the time required for use of the previously existing approaches.
Further, adoption of the proposed methodology would provide both a standardized set of values and a standardized methodology for detertaining such values.
1.3.4 Public No impact on the public can be foreseen.
1.4 Decision Standar'd methodology should be used for calculating the long-term heat generation rates as a function of burnup and decay times.
2.
TECHNICAL APPROACH 2.1 Technical Alternatives The proposed action requires the specification of one parameter, and the methodology employs the use of the ORIGEN-S code that is a part of the SCALE code system developed for the NRC through the Office of Nuclear Material Safety and Safeguards. No technical alternatives are needed.
2.2 Decision on Technical Approach The proposed action requires the use of the basic ORIGEN-S code within the SCALE system to provide the time-dependent libraries and updated cross sec-tions for the actinide elements and fission products.
Results obtained from this code can yield burnup rates as a function of decay time.
An acceptable i
range of values derived in this manner can be established by the NRC staff.
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3.
PROCEDURAL APPROACH e
3.1 Procedural Alternatives Potential SD procedures that may be used to promulgate the proposed action and technical approach include the following:
Regulation Regulatory Guide Branch Position
. 3EG-Series Report 7
3.2 Value/ Impact of Procedural AlterrTatives The matter is not of sufficient importance to justify issuance of a regu-A NUREG-series lation. No branch position has been prepared or is anticipated.
report is now being developed for publication in September 1981.
3.3 Decision on Procedural Approach A regulatory guide should be prepared.
4.
STATUTORY CCh5IDERATI0fi 4.1 NRC Aucnority The authority for this guide is derived from the safety requirements of the Atomic Energy Act of 1954, as amended, and the Energy Reorganization Act of 1974, as implemented by the Commission's regulations.
In particular, Sec-tion 72.15, " Contents of Application: Technical Information," of 10 CFR Part 72, " Licensing Requirements for the Storage of Spent Fuel in an Independ-ent Spent Fuel Storage Installation," requires that a safety analysis report that covers the design and operation of the proposed mode of storage be prepared.
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4.2 Need for NEPA Ass ssment The proposed action is not a major action as defined by para-graph 51.5(a)(10) of 10 CFR Part 51 and does not require an environmental impact statement.
5.
RELATIONSHIP TO OTHER EXISTING OR PROPOSED REGULATIONS OR POLICIES Information about an ISFSI to be included in the safety analysis report as part of a license application is described in the following two guides:
1.
Revision 1 to Regulatory Guide 3.44, " Standard Format and Content for the Safety Analysis Report To Be Included in a License Application for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation (Water-Basin Type)," dated November 1980, deals with wet-mode storage.
2.
Draft Guide FP 029-4, " Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Dry Storage)," under development, deals with dry-mode storage.
These guides identify the need to calculate the heat generated by spent fuel but also indicate that it will not be necessary to include standard methodology in the application information.
6.
SUMMARY
AND CONCLUSIONS A regulatory guide on the method for calculating the long-term heat genera-tion rates of spent fuel as a function of burnup and decay times should be prepared.
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