ML20040D130
| ML20040D130 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 01/13/1982 |
| From: | Check P Office of Nuclear Reactor Regulation |
| To: | Longenecker J ENERGY, DEPT. OF |
| References | |
| NUDOCS 8201300278 | |
| Download: ML20040D130 (7) | |
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January 13, 1982 CRBR reading file
/DocketFile NRC PDR 1 PDR Docket No. 50-537 R. Stark C. Thomas P. Check J. Neheraias Mr. John R. Longenacker W. F ster i
Licensing and Environmental Coordination P. Shuttleworth Clinch River Breeder Reactor Plant U. S. Department of Energy, NE-561 Washington, D. C. 20545
Dear Mr. Longenecker:
I
SUBJECT:
CLINCH RIVER BREEDER REACTOR PLANT, REQUEST FOR ADDITIONAL INFORMATION As a result of our review of your application for a construction pennit for tne Clinch River Breeder Reactor Plant, we find that we need additional infor-mation in the area of Radiation Protection. Please provide your final responses within sixty days of the receipt of this request.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not reouired under P. L.96-511.
If you desire any discussion or clarification of the information requested, please contact R. M. Stark Project Manager (301) 492-8948.
Sincerely, l
l Original Signed by l
Pat:I S. Chn k iviat 0CD i
Paul 5. Check Director CR3R Program Of fice Office of Nuclear Reactor Regulation
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OFFICIAL RECORD COPY usom. =-m2
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Dr. Cadet H. Hand, Jr., Director Barbara A. Finamore Bodega Marine Laboratory S. Jacob Scherr University of California Ellyn R. Weiss P. O. Box 247 Dr. Thomas B. Cochran Bodega Bay, California 94923 Natural Resources Defense Council, Inc.
1725 I Street, N.W.
Daniel Swanson Suite 600 Office of the Executive Washington, D.C.
20006 Legal Director U. S. Nuclear Regulatory Commission Washington, D.C.
20555 William B. Hubbard, Esq.
Assistant Attorney General State of Tennessee Office of the Attorney General 422 Supreme Court Building i
Nashville, TN 37219 Luther M. Reed, Esq.
Attorney for the City of Oak Ridge 253 Main Street, East Oak Ridge, TN 37830 h,
George L. Edgar, Esq.
Morgan, Lewis & Bockius 1800 M Street, N.W.
Washington, D.C.
20036 Herbert S. Sanger, Jr., Esq.
General Counsel Tennessee Valley Authori~ty Knoxville, TN 37902 Chase Stephens, Chief Docketing and Service Section Office of the Secretary U. S. Nuclear Regulatory Commission Wasnington, D.C.
20555 Raymond L. Copeland Project Management Corp.
P. O. Box U Oak Ridge, Tennessee 37830 L. Ribb LNR Associates Nuclear Power Safety Consultants 8605 Grimsby Court Potomac, MD 20854 h-
o Clinch River / Request for'Infonnation Radiation Protection Provide commitments to conform to the provisions of the following CS 471.1 Regulatory Guides, as they apply to CRBRP, or describe alternative measures to be taken to provide a comparable degree of worker protection.
1.97,
" Instrumentation for Light-Water-Cooled Nuclece Power Plants to Assess Plant and Environs Conditions During and following an Accident" 8.12,
" Criticality Accident Alarm Systems" 8.13,
" Instruction Concerning Prenatal Radiation Exposure" 8.14,
" Personnel Neutron Dosimete s" 8.15,
" Acceptable Programs for Respiratory Protection" 8.26,
" Applications of Bioassay for Fission and Activation Products" 8.27,
" Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear Power Plants" 8.29,
" Instructions Cor.cerning Risks from Occupational Radiation Exposure"
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. CS 471.2 As specified in Regulatory Guide 8.19, you should use personnel (12.1.5) exposure data for specific kinds of wort and job functions available from similar operating plants. Describe information you have obtained concerning operating LMFBR's, regarding source terms and occupational radiation exposures.
CS 471.3 As specified in Regulatory Guide 1.70, Section 12.3.4, you (12.2. 4.2.1 )
should describe criteria and methods for obtaining represen-tative inplant airborne radioactivity concentrations, including airborne radiciodines and other radioactive materials. Describe how radiolodines will be determined during use of gaseous and particulate radioactivity monitors CS 471.4 As specified in Es9ula tviy CJ;de !.!0, ', action 1E.3.1.2, you (12) should describe any special protective features that use,. shielding, geometric arrangement, or remote handling to assure that ORE are ALARA. Describe the spent-fuel transfer process, with clear drawings of fuel at each step of that process, showing relevant shielding present, access control features, and maximum dose rates in occupiable space near by. Describe pnecautions taken to pre /ent inadvertent access to all unshielded potentialy veij :.;y;. ouistion,
areas in the vicinity of the spent fuel transfer pathway.
All accessible portions of the spent fuel transfer pathway must be shielded during fuel transfer. Use of removable shielding for this a
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. purpose is acceptable. This shielding shall be such that the resul-tant contact radiation levels shall be no greater than 100 rads per hour. All accessible portions of the spent fuel transfer pathway where potenially lethal radiation fields are possible during fuel transfer, shall be clearly marked with a sign indicating that fact.
If removal shielding is used for the fuel transfer pathway, it must also be explicitly marked as above.
If other than permanent shielding is used, local audible and visible alarming radiation monitors must be installed to alert personnel if temoorary fuel transfer pathway shielding is removed during fuel transfer opera-t tions.
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CS 471.5 As specified in Regulatory Guide 8.8, you should attain the (12.3) objectives in Section C to provide assurance that exposures l
of station personnel to radiation will be ALARA through'out the plant, from planning and design through decommissioning.
I Describe the features that you have incorporated into your design to maintain occupational radiation exposures as low as is reasonably achievabic during the eventual decommissioning of the plant.
l CS 471.6 As specified in NUREG-0718, " Proposed Lic$nsing Requirements l
for Pending Applications for Construction t ermits and Manufac-turing License" (II.B.2), as it relates to CRBRP, you should i
perform radiation and shielding design reviews of spaces around 6
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, systems that may contain highly radioactive fluids; implement plant design modifications necessary to permit adequate access to vital areas and protect safety equipment; and to the extent possible, provide preliminary design infonnation at a level consistent with that nonna11y required at the construction pennit stage of review.
Where new designs are involved, provide a general discussion of their approach to meeting the requirenients by specifying the design concept selected and the supporting design bases and criteria; demonstrate that the design concept is technically feasible and within the state of the art, and that there exists reasonable assurance that the requirements will be implemented properly prior to the issuance of operating licenses.
CS 471.7 As specified in NUREG-0718, " Proposed Licensing Requiremehts for (12.1.11.5)
Pending Applications for Construction Permits and Manufacturing License", (III.D.~3.1), as it relates to CRBPP, you should address Action Plan requirements regarding radiation protection plans which will keep exposures to workers as low as is reasonably achievable during both normal operation and accident conditions, and which would allow plant workers to take effective action to control the course and consequences of an accident.
A general explanation of how the requirements will be met is required prior to issuance of the contruction pennit. Sufficient detail
should be presented to provide reasonable assurance that the requirements will be implemented properly. Staff guidance is provided in NUREG-0761, " Radiation Protection for Nuclear Power Reactor Licensees".
CS 471,8 As specified in NUREG-0718, " Proposed Licensing Requirements for Pending Applications for Construction Pemits and Manufac-turing License", (III.D.3.3), as it relates to CRBRP, you should review your designs to assure that provisions for moni-toring inplant radiation and airborne radioactivity are apprc-priate for a broad range of routine and emergency conditions.
To the extent possible, provide preliminary design information at a level consistent with that nomally required at the con-struction permit stage of review. Where new designs are in-l volved, provide a general discussion of your approach to,Heting the requirements by specifying the design concept selected and the supporting design bases and criteria. Demonstrate that the design concept is technically feasible and within the state of the art, and that there exists reasonable assurance that the requirements will be imlemented"penng.rly prior to the issuance of operating licenses.
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