ML19305A770
| ML19305A770 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1980 |
| From: | Weinstein M NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| Shared Package | |
| ML19305A769 | List: |
| References | |
| TASK-OH-506-1, TASK-OS REGGD-03.XXX, REGGD-3.XXX, NUDOCS 8002270512 | |
| Download: ML19305A770 (5) | |
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- DRAFT VALUE/ IMPACT: STATEMENT-
- 1.
~THE PROPOSED ACTION
' 1.1 ~ Description-
'Each, application _'for a spe'cific license for special nuclear material is required by the Commission'_s regulations to'contain proposed procedures to avoid
. accidental conditions of criticality.
This draft regulatory guide provides guidance for the prevention of. criticality' accidents'in the storage and process-ing of aqueous solutions of enriched uranyl nitrcte in pipe intersections.
~ 1. 2 Need for the Proposed' Action
.No guidance'on nuclear' criticality safety for pipe intersections has been published by the NRC. However, the NRC staff has been involved in the develop-ment, review, and approval of ANSI /ANS-8.9-1978, " Nuclear Criticality Safety Guide for Pipe. Intersections Containing Aqueous Solutions of Enriched Uranyl Nitrate " which was' approved by the -American' National S'tandards Institute on February 15, 1978.' Guidance on nuclear criticality. safety for pipe intersec-g tions should be provided, and consistent with past NRC practice, this guidance will be provided in the' form of a regulatory guide endorsing the approved national standard.
1.3. Value/ Impact of the Proposed Action
/1.3.1 NRC
- The standard presents an empirical model for calculating safe nuclear criticality parameters for systems of intersecting pipes containing enriched uranylenitrate. solution,' guidance on model parameters and limitations, and a general-procedure to ascertain the safety of_ specific pipe intersections.
The proposed action establishes.an NRC position on'anLexisting' national standard an'd therefore. reduces' uncertainty as to what the staff considers acceptable.in er \\P
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the area of nuclear criticality for pipe' intersections.
This will result in more' efficient. regulatory. actions'and decisions and will have minimal impact.
- 1;3.2.0ther Government Agencies
-Not applicable, unless the government' agency is an applicant.
1.3.3 Industry
.The proposed action provides a convenient reference for the licensee or
- license applicant in designing nuclear criticality safety programs to meet regulatory requirements and standards of good nuclear criticality safety prac-tice. -Most of the impact on industry has already occurred during development, review, and approval of the national' standard.
Additional impact associated with the NRC endorsement of the standard should be minimal.
1.3.4 Workers The proposed action should result in a more effective nuclear criticality
. safety program and therefore be of benefit to workers.
1.3.5 Public A beneficial effect on the public can be' expected since the proposed action
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-encourages attainment of a sound nuclear criticality safety program.
- 1.4: Decision on-the Proposed Action
-As.previously' stated, guidance should be furnished on nuclear criticality Iafetyforpipeintersectionscontainingaqueous~solutionofenricheduranyl nitrate.
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' TECHNICAL APPROACH 2.li Technical: Alternatives The proposed action is intended to provide! guidance for nuclear criticality g
safety for pipe intersections containing aqueous solutions of enriched uranyl nitrate.- ' Alte'rnative approaches: relating to this technical consideration' ara
'descr.ibed1in the following section.
- 2.2
- Ditcussion and Comparison of Technical Alternatives 4
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'An acceptable ~ approach en nuclear criticality safety for pipe intersections containing aqueous solutions of enriched uranyl nitrate can be developed based on c'lculational methods that have been teste'd,'by comparison'with experiment, a
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-to establish the reliability-of results' As an alternative, reference can be made to ANSI /ANS-8.9-1978.
An empirical model is employed in ANSI /ANS-8.9-1978 that applies to systems. consisting of a main pipe (the central column) from which' smaller pipes (arms) branch and uses as a criticality parameter the area of intersection of-the arms with the column.
Maximum safe values for both the central column diameter and the area of intersection of the arms with the column
~are provided for conditions of partial and full reflection.
As previously stated, ANSI /ANS-8.9-1978 is an industry-accepted standard and is approved by
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the NRC-staff.
2.~ 3 Decision on Technical-Approach s
The guidance! contained in ANSI /ANS-8.9-1978 will be used where applicable.
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' PROCEDURAL APPNOACH'
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J ;15: Procedural Alternatives 3
PotentialLSD procedures that may be.used to promulgate the proposed action
. an'd f technicals approachlinclude the ~ following:
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Regulation.
Regulatory Guide ANSI Standard, endorsed by.a Regulatory Guide N'JREG Report Branch Position 3.2 Value/ Impact of Precedural Alternatives A NUREG is not a-viable alternative'because the guidance will contain positions. The matter is not of sufficient importance to justify issuance of a regulation. No Branch Position has been prepared or is anticipated.
Prepara-tion of a Regulatory Guide endorsing the ANSI standard is the only viable course of action.-
3.3 Decision on Procecural Approach A Regulatory Guide should be prepared endorsing ANSI /ANS-8.9-1978, accom-panied by possible supplemental provisions.
4.
STATUTORY CONSIDERATIONS 4.1 NRC Authority Section.70.22, " Contents of applications," of 10 CFR Part 70, requires that applications for a license (to receive title to, own, acquire, deliver, receive, possess, use, or transfer special nuclear material) contain, among other information,' proposed procedures to avoid accidental conditions of criticality.
.4.2f Need for NEPA Assessment The proposed action.is not a major action, as defined by paragraph
,51.5(a)(10) of-10 CFR Part 51, and does not req'uire an' environmental impact statement.
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RELATIONSHIP TO OTHER EXISTING OR~ PROPOSED REGULATIONS OR POLICIES The proposed guide is not considered as a substitute for detailed nuclear criticality safety analyses for specific pipe intersections but rather as an integral part of the analysis in order to attain a sound nuclear criticality
, safety program. -No backfitting is expected from its issuance.
6.
SUMMARY
AND CONCLUSIONS A regulatory guide should be prepared endorsing ANSI /ANS-8.9-1978, accom-panied by.possible supplemental provisions.
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REFERENCES None.
UNITED STATES F
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NUCLEAR REGULATCRY COMMISSION WASHINGTON O. C 20555 Pos7 AGE ANO rats paso U S. NUCLE AR mgGuLATony OPPICI AL SUSlNESS Commission PEN ALTY POR PRIV ATE USE,5300 L
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Confirmation of Conversion Factors Relating Exposure and Dose-Equivalent Index Presented in ANSI N13.11 R. C. Yoder C. D. Hooker W. T. Bartlett J. A. Holland J. W. Courtney B. T. Hogan November 1979 Prepared for i
the U.S. N.rclear Regulatory Commission Pacific Northmst Laboratory Operated for the U.S. Department of Energy by Battelle Memorial Institute i
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