ML19274C890
| ML19274C890 | |
| Person / Time | |
|---|---|
| Issue date: | 07/26/1978 |
| From: | Anderson F NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | Stanford R NRC OFFICE OF STANDARDS DEVELOPMENT |
| References | |
| FRN-43FR46309, RULE-PR-72 NUDOCS 7901050237 | |
| Download: ML19274C890 (7) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISslON g:
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MEMORANDUM FOR:
R. E. L. Stanford, Fuel Process Systems Standards Branch, Division of Engineering Standards, SD FROM:
F. D. Anderson, Site Designation Standards Branch, Division of Siting, Health and Safeguards Standards, SD
SUBJECT:
CORRECTIONS AND ADDITIONS FOR DRAFT 10 CFR PART 72,
" LICENSING REQUIREMENTS FOR THE STORAGE OF SPENT FUEL IN AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION" At the recent Commission meeting which discussed the subject proposed regulation, Chairman Hendrie requested that the novel approaches used in the regulation be addressed in the Statement of Consideration with the viable alternatives. The attached enclosure provides such a discussion for the siting criteria approach in which either the proposed approach or a minimum distance with subsequent accident evaluation could be used.
Also included in the attached enclosure are corrections that must be made in Subpart E, " Siting Criteria", which I prepared.
These corrections are clarification of definitions (Subpart A) for terms which are used in Subpart E and some correction: in the criteria.
All of these corrections are necessary for clarification and consistency.
Corrections for other subparts are given which you may use or not as you determine.
Unless the corrections and additional discussion regarding the siting criteria approach are incorporated into the proposed regulation for public release, I do not believe that I will have satisfied my implied commitment to Chairman Hendrie.
L.i G. k.. L u.. -
Fredric D. Anderson Site Designation Standards Branch Office of Standards Development
Enclosure:
As stated geoioso>37
Enclosure A a would be applied to any potential accident at ISFSI which is considered credible, can be mechanistically described and can be realistically evaluated.
Comments regarding the site criteria stated in Subpart E of the proposed Part 72 should address the possible alternative approach as well as the stated approach for ISFSI accident evaluations.
With spent fuel comitted to storage for an indefinite period of time, and i ts ul timate...... "
2.
Rewrite the following definitions in Section 72.3, page 11 - 13, as given:
"(g) " Controlled area" is that area immediately surrounding the ISFSI complex, the use of which is controlled by the licensee ?or the duration of the license and W.Mn which the ISFSI operatiens are performed.
(h) " Design basis" contains the parameter values associated with that level of severity of an external or internal event or combina-tion of such events selected for design of all or any part of an ISFSI. The use of the design basis ensures that the structures, systems and components important to safety (in relation to that event or combination of events) will maintain their integrity and will not suffer loss of function during or after the event or before completing its design function.
These parameter values may be restraints derived from generally accepted " state-of-the-art" practices for achieving functional goals, or requirements derived from analysis (based on calcula-tions and/or experiments) of the effects of a postulated event under which a structure, system, or component must meet its functional goals.
(1)
" Design basis for external events" includes (i) estimates of severe natural events to be used for deriving design basis and such estimates will be based on consideration of historical data of the associated parameters, ohysical data or analysis of upper limits of the physical processes involved; and (ii) estimates of severe external man-induced events to be used for deriving design basis and such estimates will be based on analysis of human activity in the region taking into account the site characteristics and the risks associated with the event.
(2)
" Design basis for internal events" includes (i) estimates of severe internal events to be used for deriving design basis and such estimates will be based on consideration of avail-able data on failure rates of process, control and engineered safety equipment and systems, and (ii) estimates c/
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Enclosure A 5.
In Section 72.62 (b) change " evaluated" to " analyzed".
6.
In Section 72.64 (b) change "Each" to "The proposed".
7.
In Section 72.65 of Subpart E, make the following changes:
"(a) The proposed site..... and distribution of people in the region. '
Such a study shall include evaluation of present and future uses
- 4.:. / w of land and water within the region and shall take into account any special......
(b) A control v d.....for the proposed site.
(c) The licensee..... from the controlled area.
(d) The neighboring area..... evaluated with respect to both the potential for adverse consequences to people or to the environment from a release of radioactive material and the capability of
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implementing protective measures as may be necessary to mitigate the immediate effects of such a release.
(e) The distribution of people in the region..... from normal and
.e potential accidental releases of radioactive material or other
..e toxic materials and the potential impact frem construction, operat. ion and decom.nissioning of the ISFSI,during its lifetime."
(f) No changes "
8.
Replace Section 72.66 with the following:
"72.66 Criteria for Definina Acceotable Seismic Desian (a) Sites with a horizontal ground motion potential of greater than 0.25 g with a 500 year recurrence interval (equivalent to a 90'.' probability of not being exceeded in 50 years) shall be deemed unsuitable for an ISFSI.
(b)
Sites which meet the critericn of "a" above and which are founded on bedrock are suitable for an ISFSI. Unless some unusual geo-logical characteristic is identified, no detailed site specific earthquake analysis is required.
For soil sites, where vibratory ground motion could potentially cause failure, it must be shown by a site specific investigation and analysis that soil failure will not occur due to the expected vibratory ground motion at the siteduring the projected operating lifetime of the installation]
Enclosure A are within the limits of 40 CFR Part 190.
The total quantities of radioactive material released in effluents shall be kept as low as is reasonably achievable."
6.
In Paragraph (18) (iii) to read:
"with appropriate confinement, ventilation and filtration systems","
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