ML19308A899
| ML19308A899 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/27/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19308A883 | List: |
| References | |
| NUDOCS 7912120681 | |
| Download: ML19308A899 (3) | |
Text
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V.
UNITED STATES NUCLEAR REGULATORY COMMISSION
[
I W ASHINGTON, D. C. 20555 4
t 8'
SAFETY EVALUATION BY THE OFFICE OF NUCLE DPR-38, SUPPORTING AENDMENT NO. 36 TO FACILITY OPER 36TO FACILITY OPERATING LICENSE NO. DPR-47 AMENDMENT NO.
AMENDMENT NO. 33 TO FACILITY OPERATING LI DUXE POWER COMPANY OCONEE NUCLEAR STATION, UNITS NOS.1, 2 AND 3 50-269, 50-270 AND 50-287_
DOCKETS NOS.
Introduction d
Duke Power Company (licensee) requeste 27, 1976, i
changes to the Technical Specifications for the Oco By letter dated May and gaseous effluents.
Discussion The changes to the Technical Specifications are:
The addition of the condensate monitoring tank and the laund led shower tank to Table 4.1-3 as part of the list of tanks to be sampj 1.
for radioactivity prior to release.now be performed instead of ll tanks.
Changes in gamma isotopic analysis sensitivities for the waste g 13 tanks, unit vent and reactor building purge in Table 4.
2.
i Changes in water samples used for offsite radiological monitor n 4.11-2, and the addition of a requirement to measure I-131 in Table 3.
Revision of analytical sensitivies in Table 4.11.3.
4.
Evaluation _
The condensate monitoring tank and the lau i
1.
For the low activity waste tank and to release of each batch. condensate test tank the requirement fo activity, Ba-La-140 and I-131 were deleted.
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I analyses, the licensee will now perform a gama isotopic analysis including dissolved noble gases on the contents of all tanks prior to the release of effluents. We find that these changes will provide more encompassing information than the gross activity measurements and will include the isotopes now being analyzed.
We therefore conclude that these changes are acceptable.
2.
Gama isotopic analysis sensitivities for the waste gas decay tank, unit vent and reactor building purge in Table 4.1-3 were revised to include separate sensitivities for gases and for particulates and iodines.
Separating the sensitivities is an improvement over having a sensitivity for all of the activity combined, since the sensitivity is now more representative of the type of activity (i.e. gaseous or particulate) being measured. We find these changes to be desirable and conclude that they are acceptable.
3.
In the samples required for the offsite radiological monitoring program (Table 4.11-2), water supply samples were divided into two categories: water supply (raw) and water (other than raw water supply). A requirement to measure I-131 in the monthly raw water supply was added to the analyses now performed to check on the intake of this isotope by livestock consuming water from Hartwell Reservoir. Tne requirement for I-131 analyses on the monthly and quarterly milk samples was deleted since it is per-formed on the weekly samples. We find these changes to be acceptable.
4.
The required analytical sensitivities in Table 4.11-3 were revised to be consistent with current guidance to demonstrate that the effluent releases are within the Appendix I design objective annual exposure limits and to reflect the current Oconee radiological sampling program.
Sensitivities were added for 9 isotopes that were not previously listed in the Table. The sensitivity for I-1g1 analyses on water samples was changed from 0.5 to 1.5 p C1/m since this value is considered to better represent the current state of technology. We conclude that these changes are acceptable.
In summary, we conclude that the requested changes will provide more definitive information from the radiological program.
We have determined that this amendment does not authorize a change in 4
effluent tses or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuar,t to 10 CFR 551.5(d)(4), that an environmental statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
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,. Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendrents do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the prsposed manner, and (3) such activities will be conducted in caupliance with the Commission's regulations and the issuance of these amendnents will not be inimical to the common defense and security or to the health and safety of the public.
Date: January 27, 1977 i
h
UNITED STATES NUCLEAR REGULATORY COPHISSION DOCKETS NOS. 50-269, 50-270 AND 50-287 DUKE POWER COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendments Nos. 36, 36 and 33 to Facility Operating Licenses Nos. DPR-38, DPR-47 and DPR-55, respectively, issued to Duke Power Company (the licensee),
which revised Technical Specifications for operation of the Oconee Nuclear
' Station Units Nos.1, 2 and 3 (the facility) located in Oconee County, Sauth Carolina. The amendments are effective as of their date of issuance.
These changes are related to the measurement and control of radioactive liquid and gaseous effluents from the Oconee Nuclear Station and will provide more definitive information from the radiological monitoring program.
The application for these amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.
The Commission has made appropriate findings as required by the Act and the Conunission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.
Prior public notice of these amendments was not required since these amendments do not involve a significant hazards consideration.
G79HW0 573
2-l The Comission ha's determined that the issuance of these amendments will not result in any significant envirt.imental impact and that pursuant to 10 CFR 551.5(d)(4) an er vironmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of these amendments.
For further details with respect to this action, see (1) the i
application for amendment dated May 27,1976,(2) Amendments Nos. 36, 36 and 33 to Licenses Nos. DPR-38, DPR-47 and DPR-55,respectively, and (3) the Comission's related Safety Evaluation. All of these items are available for public inspection at the commission's Public Document Room, 1717 H Street, N. W., Washington, D. C. and at the Oconee County Library, 201 South Spring Street, Walhalla, South Carolina 29691. A copy of items (2) and (3) may be obtained upon request addressed to the U. S.
Nuclear Regulatory Comission Washington, D. C.
20555 Attention:
Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this 27th day of January 1977.
FOR THE NUCLEAR REGULATORY COMMISSION i1449/$%-
e A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors e
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