ML20204G798

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Notice of Availability of Draft Generic Technical Position on Items & Activities in High Level Waste Geologic Repository Program Subj to 10CFR60 QA Requirements
ML20204G798
Person / Time
Issue date: 07/25/1986
From: Linehan J
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20204G785 List:
References
REF-WM-1 NUDOCS 8608070392
Download: ML20204G798 (4)


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7590-01 NUCLEAR REGULATORY COMMISSION ,

AVAILABILITY OF DRAFT GENERIC TECHNICAL POSITION ON ITEMS AND ACTIVITIES IN THE HIGH-LEVEL WASTE GE0 LOGIC REPOSITORY PROGRAM SUBJECT TO 10 CFR PART 60 QUALITY ASSURANCE REQUIREMENTS AGENCY: Nuclear Regulatory Commission ACTION: Notice of Availability

SUMMARY

The Nuclear Regulatory Commission (NRC) is announcing the l

availability of the " Draft Generic Technical Position on Items and Activities in the High-level Waste' Geologic Pacosito Piogram Subject to l'0 CFR Part 60 Q.uality Assurance Requirements."

I l DATE: The comment period expires (insert the date 60 days after publication).

ADDRESSES: Send comments to John J. Linehan, Acting Chief, Repository Projects Branch, Division of Waste Management, U.S. Nuclear Regulatory Commission, Mail Stop 623-SS, Washington, D.C. 20555. Copies of this document may be obtained free of charge upon written request to Linda Luther, Docket Control Center, Division of Waste Management, U.S. Nuclear Regulatory Commission, Mail Stop 623-SS, Washington, D.C. 20555, Telephone 1/800/368-5642, Ext. 74426.

8600070392 860725 PDR WASTE WM-1 PDR ,_

7590-01 FOR FURTHER INFORMATION CONTACT: Susan G. Bilhorn, Repository Projects Branch, Division of Waste Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Telephone 301/427-4682.

SUPPLEMENTARY INFORMATION: The Nuclear Waste Policy Act of 1982 (Public Law - 97-425) and the Commission regulation 10 CFR Part 60 provide for interaction between the Department of Energy (D0E) and NRC prior to submittal of a license application for a geologic repository. These interactions are to fully inform DOE about .the information that must be provided in a license application to allow a licerising decision to be'ma'de by NRC.

The principal mechanism for providing guidance to the DOE is the NRC staff's Site Characterization Analysis (SCA) required by the Nuclear Waste Policy Act and 10 CFR Part 60. Other means of providing guidance to supplement the SCAs are staff technical positions on both generic and site-specific issues.

Generic Technical Positions (GTPs) establish the staff's position on broad technical issues that are applicable to any site and Site Technical Positions (STPs) establish the staff's position on a site-specific technical issue. A number of technical ;ositions will be developed by the staff on bolh generic and site-specific issues. This announcement notices availability and solicits, comments on the "Draf t Generic Technical Position on Items and Activities in l

the.High-level Waste Geo.ogic Repository P'rogram-Subject to 10 CFR Part 6'O

3 7590-01 Quality Assurance Requirements." The purpose of this generic technical position is to provide guidance on approaches for identifying items and activities that are important to safety and waste isolation and to address measures to assure the quality of all items and activities that will be used to demonstrate compliance with the licensing requirements of 10 CFR Part 60.

In this GTP the staff explains its view of a 0.5 rem design basis accident dose limit for the geologic repository. While a dose limit for design basis accidents is not explicitly. addressed in 10 CFR Part 60, the threshold value f*r

o. determining which items are important to safety is a 0.5 rem d'se o to an' individual in the unrestricted area (10 CFR 60.2). The 0.5 rem threshold value was incorporated into 10 CFR Part 60 after consideration of comments received on the proposed rule (see NUREG-0804, " Staff Analysis of Public Comments on Proposed Rule 10 CFR Part 60, ' Disposal of High-Level Radioactive Waste in Geologic Repositories'"). At the time the final rule was promulgated, the staff expressed its view that few, if any, accidents could, if unmitigated, exceed the 0.5 rem dose to an individual in the unrestricted area.

The staff is now interested in receiving comments regarding potential off-site e y G

4 1 7590-01 doses resulting from accident scenarios, and the impact of a 0.5 rem dose limit for design basis accidents on the design and cost of a HLW geologic repository.

Dated at Silver Spring, Maryland this Jffl day of J / % .

~J For the Nuclear Regulatory Commission d ,

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John J. Linehan, Acting Chief

Repository Projects Branch Division of Waste Management

,0ffice of Nuclear Material Safety l ,

and Sa.feguards .

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