ML20114D095

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Page 8 to Safety Evaluation Covering Environ Considerations, Inadvertently Omitted from Amends 88 & 60 to Licenses DPR-51 & NPF-6,respectively,due to Reproduction Error
ML20114D095
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 01/16/1985
From:
NRC
To:
Shared Package
ML20114D097 List:
References
NUDOCS 8501300694
Download: ML20114D095 (3)


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_8 The proposed changes will not remove or relax any existing requirement needed to ' provide reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner. The staff, therefore, finds the proposed changes acceptable.

4.0 ENVIRONMENTAL CONSIDERATION

These amendments involve a change in the requirements with respect to the use of facility components located within the restricted area as defined in 10 CFR Part 20 or a change in inspection or surveillance requirements.

The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public coment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assess-ment need be prepared ir connection with the issuance of these amendments.

'5.0 GENERAL CONCLUSION We have concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the propcsed manner, and (2) such activities will be conducted in compliance with the Comission's regula-tions and the issuance of the amendments will not be inimical to the comor, defense and security or to the health and safety of the public.

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Enclosure:

'INEL~ Technical Evaluation 8501300694 850116 DR ADOCK 05000 Date:. December 14, 1984 p

Principal Contributors:

F. Meinke, C. Miller

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INDEX ADMINISTRATIVE CONTROLS SECTION-PAGE 6.6 REPORTABLE OCCURRENCE ACTI0N...............................

6-12 6.7 SAFETY LIMIT VIOLATION.....................................

6-13 6.8 PROCEDURES.................................................

6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTIhE REPORTS AND REPORTABLE OCCURRENCES............

6-14 6.9.2 SPECIAL REP 0RTS.......................................

6-19 6.9.3 SEMIANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT.......

6-19 6.9.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT....

6-21 6.10 RECORD RETENTION..........................................

6-22 6.11 RADIATION PROTECTION PR0 GRAM..............................

6-23 6.12 ENVIRONMENTAL QUALIFICATION...............................

6-23 6.13 HIGH RADIATION AREA.......................................

6-24 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM)....................

6-25 t

I XVII Amendment No. 2J,60 ARKANSAS - UNIT 2

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e TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

.D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

P Completed prior to each release l

N.A.

Not applicable.

A ARKANSAS - UNIT 2 1-9 Amendment No. 60 l

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