ML20010A299
| ML20010A299 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/24/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20010A126 | List: |
| References | |
| NUDOCS 8108110291 | |
| Download: ML20010A299 (2) | |
Text
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4 JUL 211981 ENVIRONMENTAL IMPACT APPRAISAL StePPORTING NtENDMENT NO. 2 TO CPPR-108 AND AllEhDflENT NO. 2 TO CPPR-109 RELATIl4G TO THE ENCLOSURE BUILDlHG MODIFICATIONS AL'!!N W. V0GTLE NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-424 AND 50-425 Description of the Proposed Action By 1ctter dated December 19, 1980, Georgia ower Company filed a request with a
tr.e Nuclear Regulatory Commission (the Coraission) to reflect a modification in plant design. The action proposed by the permittee is the isst.ance of amendrients to Construction Pera.its CPPR-108 and CPPR-109 that would substitute for the enclosure building an equipment building from grade to the 270-foot level as well as a more restrictive primary containment leakage comitment which, together with onsite meteorolegical data, would ensure that offsite post-accident radiological deses are less than doses judged to be acceptable for design now and at the time construction was initally authorized.
The staff's Final Environmental Statement (FES) relating to the Construction of Vogtle Units 1 and 2 was published in March 1974.
Environmental Impact of the Proposed Action The Commission has reviewed tr.e proposed enclosure in.11 ding modifications for Alvin W. Vogtle Nucelar Plant, Units 1 and 2, to determine the possible radio-logical and nonradiological consequences.
Evaluation of the possible i
consequences follows:
Tne applicant has sutaitted by a letter dated December 7,1979, additioaal meteorological data. Employing these late.ct data and a minimum leak rate of 0.2% per day, we have found that, the radiological dose consequences for the modified desigr. are less than the results for the original plant design. Tne calculated dose consequences (Tables 15.1 and 15.2 of the Safety Evaluation Report) are less than the guidelines of 10 CFR Part 100 in both the original and mcdified design cases. Therefore, we conclude that the Final Environmental Statensnt issued March 1974, remains valid with regard to radiological environmental impacts.
In a letter dated December 19, 1980, the appli; ant has submitted further information concerning nonradiological impactt on both plant construccion and operation due to the enclosure building modifications. According to our evaluation, the only impacts cn construction would te a savings in construction man-hours and resource commitments. The physical area affected by the construction activity would be the same for either the orginial or modified plant design. For plant operation, there would be no change from the original design c types or amounts of acnradiological effluents.
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w Therefore, we conclude that the Final Loviron6 ental Statement, issued March 1974, remains valid with regard to nonradiological environmental impacts of plant. construction and operation.
Approval of this action does not preclude future changes as deemed necessary by accident analyses on.the mitigation of more severe accident sequences than postulated design basis accidents which will' be performed during the operating license review for the entire Vogtle. plant.
Conclusion and Basis for Negative Declaration On the basis 'of the foregoing informattor., the NRC concludes that there will be. no environmental impacts resulting from the proposed action in addition.to those impacts already predicted and impacted in the Commission's Final Environ-mental Statement, issued in March 1974. Having reached this conclusion, the staff has further conclud6d that no environmental impact statement for the proposed action need be prepared, and that a negative declaration to.this effect is appropriate.
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