ML20215E428
| ML20215E428 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/08/1986 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| TAC-61179, TAC-61180, NUDOCS 8610150294 | |
| Download: ML20215E428 (5) | |
Text
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i Docket Nos.: 50-369 and 50-370 0 8 OCT 1986 Mr. H.B. Tucker, Vice President i
Nuclear Production Department I
Duke Power Company 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Tucker:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING RADI0 ACTIVE RELEASES TO THE CATAWBA RIVER The NRC staff is reviewing your March 19, 1986 request for amendments to change the McGuire Technical Specifications to add an alternate path for radioactive liquids released to unrestricted areas. The proposed amendments would authorize the release of radioactive liquids to the Catawba River by way of the Conventional Wastewater Basin.
We find that additional information, requested by the enclosure, is needed to complete this review. Your response to the enclosure is requested within 45 days of this letter. Contact me at (301) 492-8961 if you have any questions.
Sincerely, Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A cc w/ encl:
See next page
Enclosure:
As stated DISTRIBUTION:
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Docket Nos.: 50-369 and 50-370 0 8 OCT 1986 Mr. H.B. Tucker, Vice President Nuclear Production Departrent Duke Power Company 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Tucker:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING RADI0 ACTIVE RELEASES TO THE CATAWBA RIVER The NRC staff is reviewing your March 19, 1986 request for amendments to change the McGuire Technical Specifications to add an alternate path for radioactive liquids released to unrestricted areas. The proposed amendn:ents would authorize the release of radioactive liquids to the Catawba River by way of the Conventional Wastewater Basin.
We find that additional information, requested by the enclosure, is needed to complete this review.
Your response to the enclosure is requested within 45 days of this letter. Contact me at (301) 492-2961 if you have any questions.
Sincerely, R '-
Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A cc w/ encl:
See next page
Enclosure:
As stated
Mr.'H. B. Tucker o
Duke Power Company McGuire Nuclear Station cc:
Mr. A. Carr Dr. John M. Barry.
Duke Power Company Department of Environtrental Health P. O. Box 33189 Mecklenburg County 422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 County Manager of Mecklenburg County 720 East Fourth Street Charlotte, North Carolina 28202 Chairman, North Carolina Utilities Comission Mr. Robert Gill Dobbs Building Duke Power Company 430 North Salisbury Street Nuclear Production Department Raleigh, North Carolina 27602 P. O. Box 33189 Charlotte, North Carolina 28242 Mr. Dayne H. Brown, Chief Radiation Protection Branch J. Michael McGarry, III, Esq.
Division of Facility Services Bishop, Liberman, Cook, Purcell Department of Human Resources
.and Reynolds 701 Barbour Drive 1200 Seventeenth Street, N.W.
Raleigh, horth Carolina 27603-2008 Washington, D. C.
20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Comission Route 4, Box 529 Hunterville, North Carolina 28078 Regional Administrator, Region II U.S. Nuclear Regulatory Comission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 L. L. Williams Area Manager, Mid-South Area ESSD Projects Westinghouse Electric Corporotion MNC West Tower - Bay 239 P. O. Box 355 Pittsburgh, Pennsylvania 15230 4
Enclosure o
REQUEST FOR /DDITIONAL IhFORMATION REGARDING RELEASE OF RADICACTIVE LIQUID EFFLUENTS _FROM THE CONVENTIONAL WASTEWATER BASIN TO THE CATAWBA RIVER 1.
Radioactive liquid effluents from the McGuire Nuclear Station are now sampled, analyzed and released by a monitored pathway.
The radioactive liquids are diluted by the circulating water and released to Lake Norran.
The lake provides aoditional dilution anc delay before the radioactivity reaches the river.
la.
The proposed new release pathway will not have the dilution and delay provided by the lake. Discuss the provisions made for assuring that the radioactivity concentrations are sufficiently low at the proposed point of release and provide a comparative analysis of river concentrations for the proposed and existir.g release points.
Ib.
Discuss the applicability of existing technical specifications 3/4.11.1 to the proposed action, and identify changes, if any, to your request needed to assure that the new release point in con,bination with the existing release point are kept within the guidelines of Appendix I to 10 CFR Part 50 (i.e., pursuant to Appendix I, the releases are to be controlled so the combined doses from both release points (existing end proposed) do not collectively exceed the Accendix Icriteria).
Ic.
The technical specifications should require appropriate sampling and analysis prior to each release to and from the conventional wastewater basin. The analysis shculd be sensitive enough to assure n'easurement of activity in the range of interest in Appendix I evaluations; the LLD for Cs-137 for releases from the Basin, for example, should be no greater than 0.1 pCi/1. Discuss the various sampling and analyses associated with the proposed action and identify the measurement sensitivity for the instruments to be used.
Id.
Address the capability to obtain representative sanples from the Conventionel Wasterwater Collection System.
le.
Discust the capability to prevent unmonitored releases to and from the Conventional Wastewater Basin.
If.
Discuss the capabilities to detemine the quantities to be released so they can be reflected in dose calculations.
E.
Address the accon>uletion of radioactivity in the sludge in the Conventional Wastewater Basin, the frequency and method of sludge removal and disposal, the radiological concentrations and exposures projected for sludge control and procedures used to maintain these exposures ALARA.
3.
As part of your environmental assessment, ioentify and discuss the potential alternatives to the proposed action.
You state that the proposed action is requested, in part, because turbine building sumps become contaminated l
2
- during operation with primary-to-secondary leakage, and that long-term operation with such leakage requires processing)at a rate that would exceed the cacacity of the Liquid Radwaste System (LRS. Accordingly, your discussion of alternatives should include (1) design changes to upgrade the capacity of the LRS, and (2) operational restrictions consistent with existing LRS capacity.
Justify the proposed action in view of available alternatives.
4 Identify any waste stream other than that of the Conventional k'astewater Treatnent System that will also be released at the proposed alternate release point.
Discuss the measures taken to ensure adequate control of releases via any such other waste strearas through this release point.
In-clude sampling, analysis and monitoring provisions for any such waste stream.
T 1
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