ML19329F211
| ML19329F211 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 02/13/1976 |
| From: | Bauman R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.024, RTR-REGGD-1.024 2160, NUDOCS 8006230735 | |
| Download: ML19329F211 (3) | |
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General Offices: 'J12 West MicNgan Avenue, Jackson, Micnigan 49201 e Area Code 517788-05S0 February 13, 1976 N
.N Director of Nuclear Reactor Regulation Attention: Mr Roger Boyd, Director
-s Division of Project Management U. S. Nuclear Regulatory Co= mission Washington, DC 20555 MIDLAND PROJECT 7
DOCKET NUMBERS: 50-329, 50-330 REGULATORY GUIDE IMPLE)ENTATION FILE: 0505 SERIAL: 2160 The enclosed information is provided to formally submit the Midland project response to Regulatory Guide 1.24.
This Regulatory Guide 1.24 position is essentially the same as the position previously submitted for Regulatory Guide 1.25 and was discussed with your staff during the December 19, 1975 Miscellaneous Regulatory Guide meeting.
In addition, the applicant wishes to inform you that Regulatory Guides 1.h0 and 1.81 should be added to the applicants response to NRC Electrical Engineering Question 221.1.
Question 221.1 asked for a list of Electrical Regulatory Guides discussed with your staff to which the project complies without exception.
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ASSUMPTIONS USED FOR EVALUATING THE POTENTIAL RADIOLOGICAL CONSEQUENCES OF A PRESSURIZED WATER REACTOR RADIOACTIVE GAS STORAGE TANK FAILURE (March 23, 1972)
RESPONSE TO REGULATORY POSITION The assumptions of the Regulatory Position of Regulatory Guide 1.25 are used in the analysis of the potential radio-logical consequences of a fuel handling accident with the following exceptions or clarifications.
(1)
Reference:
Paragraph C.2 of the Regulatory Guide.
The atmospheric dispersion factors used in the final analysis will be based on onsite meteorological data.
The atmospheric dispersion factors used in the Pre-liminary Analysis are based on the meteorological data collected at Dcw Chemical Plant and Tricity (Saginaw)
Airport.
(2)
Reference:
Paragraph C.3.a of the Regulatory Guide.
Whole-body gamma doses and beta skin doses are presented separately, as the dose from beta radiation to whole-body is negligible.
The total dose to the skin is the sum of the beta skin dose and whole-body gamma dose.
In the calculation of skin dose due to beta radiation, credit will be taken for the inert thigkness of the skin, which is approximately 7 mgms/Cm Due to the limited extent of the effluent plume, the gamma. dose conversion factors will be realistically
' determined using the finite cloud model as proposed in Meteorology and Atomic Energy (A).
(3)
Reference:
Paragraph C.3.b of the Regulatory Guide.
Dose conversion factors are taken from the most recent data available.
J Li (A)
- Slade, D.H., Meteorology and Atomic Energy, 1968.
U.
S. Atomic Energy Commission, Office of Information Services TID-24190 (1968).
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NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL
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DATE OF DOCUMENT
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