ML20216J037

Safety Evaluation Supporting Amend 99 to License DPR-36

ML20216J037
Person / Time
Site:	Maine Yankee
Issue date:	06/25/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20216H992	List: ML20216H984 ML20216J016 ML20216J037
References
NUDOCS 8707020080
Download: ML20216J037 (2)

Text

a e UNITED STATES

![pR rig[o, NUCLEAR REGULATORY COMMISSION g

a g ' )2 WA$Ht NGTON, D. C. 20555

\ ..v /

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT NO. 99 TO FACILITY OPERATING LICENSE NO. DPR-36 MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER STATION DOCKET N0. 50-309 INTRODUCTION By letter dated February 24, 1987, Maine Yankee Atomic Power Company proposed chanaes to the Maine Yankee Atomic Power Plant Technical Specifications (TSs)5.9.1.6,"SemiannualRadioactiveEffluentReleaseReports,"and5.9.1.7, "Special Reports." The proposed change to TS 5.9.1.6 would allow additional time for the filing of supplemental dose and meteorological summary reports; the proposed change to TS 5.9.1.7 would ensure that the references to other TS sections are correct. i The licensee stated that the proposed change to TS 5.9.1.6 will provide the added time necessary for preparing the annual summaries of meteorological history, and {

estimated dose commitments resulting from plant operation. These reports would be required to be submitted within 90 days after January 1 of each year. This change will not affect the submittal of plant radioactive effluent data as required by 10 CFR 50.36a, paragraph (a)(2). The additional time for these sub- l mittals is requested to complete the reduction of the hourly meteorological data, I processing of the additional information concerning the atmospheric dispersion of gaseous effluents and resultant doses (which requires completion of all effluent radionuclide analyses including strontium 89 and 90 for the last sampling  ;

period of the reporting year), perform the calculations and prepare and review l the final report. The proposed change to TS 5.9.1.7 will update the references  !

for the Excessive Radioactive Release Report. ,

EVALUATION The staff has reviewed the licensee's submittal and finds that the proposed ,

changes are of an administrative nature and meet the intent of the guidelines of NUREG-0472, " Standard Radiological Effluent Technical Specifications (RETS) for Pressurized Water Reactors," and are, therefore, accepteble.

8707000080 870625  !

PDR ADOCK 00000309 j P PDR l

i

.g' 4

ENVIRONMENTAL CONSIDERATION Th15 amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.

The staff has determined that the amendment involves 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 Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set c forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

CONCLUSJ0g We have concluded, based o.t the considerations discussed above, that (1) there is reasonable assurance t ' hat the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendmer,t will not be inimical to the common defense and security or to the health and safety of the public.

Date: June.25, 1987 Principal Contributor: C. Nichols

]

l l

r

^

i d  !

i l

1 I

. o

'\

I June 25, 1987

]

AMENDMENT NO. 99 TO DPR MAINE YAt'KEE ATOMIC POWER STATION I

(

1 DISTRIBUTION: l Docket File k i NRC PDR Local PDR PRC System PD#I-3 Reading M. Rushbrook (5)

P. Sears (2)

S. Varga S. Boger W. Jones ,

D. Hagan l T. Barnhart (4)

E. Jordan J. Partlow C. Miles, PA R. Diggs, LFMB OGC-Bethesda ACRS (10) j cc: Plant Service List l

_