ML20052B858
| ML20052B858 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/12/1982 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 8205040071 | |
| Download: ML20052B858 (3) | |
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APR 1 2 1982 LB#1 Reading TERA DEisenhut NRC/PDR BJYoungblood L/PDR RLTedesco NSIC Docket Mo.:
50-395' RVollmer TIC RHartfield, MPA ACRS (16) opfon ifr. T. C. Nichols, Jr.
H Vice President ?, Grouo Executive RMattson
!!uclear Operations D
OELD South Carolina Electric 4 Gas Company 0IE 4
Post Office Rox 764 49 WKane Colunbia, South Carolina 2921A MService 9,q\\h[;9 c.;
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Dear it. Nichols:
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Sub.f ect: Process Control Program - Virgil C. Sumner Nuclear S aj: ongvg.,#V, j
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dP In our Safety Evaluation Report we provided our evaluation of a ure M
fomaldehyde radwaste solidification system which you originally proposed as the system to be used for solidifying wet solid wastes. Subsequentl y, in letters dated November 4,1981, December 28, 1991 and January 26, 1992 you confimed that this system will not be used and will be replaced by a skid-mounted cement solidification systen which will be provided by Chen-nuclear. Irc.
Me have reviewed the infomation provided to date on the cement solidification system and have detemined that we nord certain additional infomation in order to complete our evaluation. The infomation that we request is identified in the enclosure to this letter. Your responses should be provided to us by May 15, 1982.
Original signed by:
Willia:n Kane B. J. Younqblood, Chief Licensing Rranch No.1 Division of Licensino
Enclosure:
As stated cc: See next paqe i
82050400Tl A
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Nac ronu ais now nacu ono OFFIClAL RECORD COPY usca mi-m+o
Mr. T. C. Nichols, Jr.
Vice President & Group-Executive Nuclear Operations I
South Carolina Electric & Gas Company Post Office Box 764 Columbia, South. Carolina 29218
'. cc: Mr. Henry. Cyrus Senior Vice President South Carolina Public Service Authority 223 North Live Oak Drive Moncks Corner, South Carolina 29461 J. B. Knotts, Jr., Esq.
Debevoise & Liberman 1200 17th Street, N. W.
Washington, D. C.
20036 M'r. Mark B. Whitaker..Jr.
Group Manager - Nuclear Engineering & Licensing South Carolina Electric & Gas Company Post Office 764 Columbia, South Carolina 29218
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Mr. Brett Allen Bursey Route 1, Box 93C Little Mountain, South Carolina 29076 Resident Inspector / Summer NPS c/o U. S. NRC-Route 1, Box 64 Jenkinsville, South Carolina 29065 Mr. James P. O'Reilly U. S. NRC, Region II 101-Marietta Street
' Suite 3100 Atlanta, Georgia 30303 1
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4 ENCLOSURE RE0 VEST FOR ADDITIONAL INFORMATION 321'.17 Describe how you propose to comoly with the interface requirenents spelled out in the Chemnuclear Topical Report for their cement solidification system.
321.18 Provide tables showing how the utility equipment, components, struc-tures and services that interface with the skid-mounted cement solidification system comoly with the applicable criteria of Regulatory Guide 1.143, Rev.1, October 1979, " Design Guidance for Radioactive Waste Management: Systems, Structures and Components Installed in Light-Water-Cooled Nuclear Power Plants" and Branch Technical Position ETSB 11-3, Rev. 2, July 1981, " Design Guidance for Solid Radioactive Waste Management systems Installed in. Light-Water-Cooled Nuclear Power Plants".
321.19 Describe how the plant design, as it relates to the cement solidifica-tion system, reflects consideration of the following design features intended to maintain occupational radiation exposures ALARA:
a.
Minimizing the length of piping runs
- b.. Avoiding -low points and dead legs in piping c.
Using larger diameter piping to minimize plugging 321.20 Clarify whether heat tracing has been incorporated for tanks that contain evaporator concentrates that are likely to solidify at ambient tenperatures.
321.21 Describe the equipment, components or structures and services you provide for containing radioactive spills that may occur in the cement solidification system.
t 321.22 Describe the plant inspection program to assure that cement and/or l
conditioning chemicals are maintained at the proper quality during the time they are stored.
321.23 Describe how the curie content and identification of radionuclides in each container are determined prior to shipment.
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