ML19282B209
| ML19282B209 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1979 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Permutter C AFFILIATION NOT ASSIGNED |
| References | |
| FOIA-79-15 NUDOCS 7903090371 | |
| Download: ML19282B209 (3) | |
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FEB 2 81979 y
Ms. Carol S. Perlmutter 520 Walnut Street IN RESPONSE REFER Audubon, NJ 08106 TO F01A-79-15
Dear Ms. Perlmutter:
This is in response to your letter dated January 16, 1979 in which you requested, pursuant to the Freedom of Information Act, a copy of all reports, memoranda, or other materials regarding the formula used by the Commission, for determining low population zones, including any evaluations, revisions, or suggestions for revisions, and other documents relating to the subject.
Your letter was received by the Office of Administration on January 22, 1979.
In response to your request, the documents listed on the appendix are enclosed.
In a telephone conversation with Mr. Stephen Isaacs of the NRC, you were informed that information responsive to your request is contained in several basic raports. These reports and other historical reports regarding the subject matter of your request are enclosed.
The computer printout referenced in Mr. Isaac's conversation contains information similar to that contained in the enclosed report numbered TID 14844 and therefore is not enclosed.
If we can be of further assistance in this matter, please advise us.
Sincerely, J. M. Felton, Director Division of Rules & Records Office of Administratica
Enclosures:
As stated 7903090y7l
a, Appendix F0lA-79-15 1.
Undated, paper, Accident analysis and Site Evaluation.
2.
NRC Rules and Regulations, Title 10, Chapter 1.
a.
Part 100 - Reactor Site Criteria b.
Part 50 - Domestic Licensing and Utilization Facilities 3.
NRC Regulatory Guides:
a.
1.3 - Assumptions used for evaluation the potential radiological consequences of a loss of coolant accident for boiling water reactors.
b.
1.4 - Assumptions used for evaluation the potential radiological consequences of a loss of coolant accident for pressurized water reactors.
c.
1.109 - Calculation of annual doses to man from routine releases of reactor effluents for the purpose of evaluating compliance with 10 CFR Part 50, Appendix I.
d.
1.70.14 - Information for safety analysis reports emergency planning.
e.
13.3 - Emergency planning.
f.
1.101 - Emergency planning for nuclear power plants.
4.
Standard Review Plan 15.6.5.
5.
Technical Information Document (TID) - 14844 Calculation of Distance Factors for Power and Test Reactor Sites.
6.
NUREG-75/lli - Guide and Checklist for Development and Evaluation of State and Local Government Radiological Emergency Response Plans in Support of Fixed Nuclear Facilities.
7.
NUREG-0396 - Planning Basis for the Development of State and Local Government Radiological Emergency Response Plans in Support of Light Water Nuclear Power Plants.
8.
10/19/78 - Rough draft of a summary of changes that have taken place over the years in Part 100 calculations.
9.
7/18/78 - Request for initiative of change actions to Regulatory Guides 1.3 and 14.
10.
Undated - Primary document unknown - Enclosure C, proposed regulatory guidance on accident evaluations for siting and licensing purposes.
' F01A-79-15 11.
NUREG-0347 - Safety Evaluation Report related 'to construction of Yellow Creek Nuclear Plant Units 1 and 2.
12.
NUREG-0348 - Demographic Statistics Pertaining to Nuclear Power Reactor Sites.
13.
NUREG-0308 - Safety Evaluation Report related to the operation of Arkansas Nuclear One Unit 2.
14.
September '6,1977 - Memo for V. Stello from H. Denton, Input for Commission Paper on accident evaluation practices.
15.
April 6, 1978 - Letter to R. Fraley, ACRS from L. P. Crocker,
- 16. NUREG-0478 - Metropolitan Siting - A Historical Perspective.
.