ML18098A070

Letter Responding to the Ncr Letter of March 15, 1976 Requesting Plans for Meeting the Requirements of Paragraph 50.34a of 10 CFR Part 50 and Enclosing a Schedule for Meeting the Requirements

ML18098A070
Person / Time
Site:	Saint Lucie
Issue date:	04/16/1976
From:	Robert E. Uhrig Florida Power & Light Co
To:	Deyoung R Office of Nuclear Reactor Regulation
References
Download: ML18098A070 (8)

Text

-NRCFORM 195 (2 76)U.S.NUCLFAR REGULATORY ISSION DOCKET NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL FILE NUMBER Mr UeYoung FROM: Florida Pwr&Lignt Co M7.am'., Fla 8.E Uhrzg DATE OF DOCUMENT 4-1I7-7u DATE RECEIVED g 23 7t SLFTTER%ORIGINAL OCOPY DESCRIPTION C3NOTORIZED R UNC LASS IF I E D PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED 1 one szgned Ltr w/attcnrnents.....re our 3-15-76 1Lr.....furnzsnxng info concernmng Appendxx I into~~~'LANT NAME: St Lucre gi SAFETY ASSIGNED AD: BRANCH CHXEF: FOR AC'I ION/INFORMATION ASSIGNED AD: BRANCH CHIEF~ENVIRO-28-7D eni PROJECT MANAGER: LXC~SSTo PROJECT MANAGER: LIC~ASST'NRC PDR I&E GOSSICK&STAFF SE DEl EN INEER KNXGHT SHNEXL PAMLICKX INTERNAL D IST Rl BUTION BENAROYA IPPOLITO OPERATING REACTORS STELLO OPERATXNG TECH ERNST ALLARD SPANGLER SITE TECH GAMMXLL STEPP HULI IAN PROJECT MANAGEMENT BOYD P.COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LPD TIC NS ASLB REACTOR SAFETY.ROSS NOVAK ROSZTOCZY CHECK'T&I SALTZMAN RUTBERG EXTERNAL DISTRIBUTION NATL LAB REG, V"XE LA PDR CONSULTANTS.

EISENHUT SHAO BAER SCHWENCER GRXMES SITE SAFETY&ENV ANALYSIS DENTON&MULLER BROOKHAVEN NATL LAB ULRIKSON(ORNL)

SITE ANALYSIS VOLTPIER BUNCH J~COLLINS KREGER RaI-Ke~Con CONTROL NUMBER Rosa

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'A-'~(P L1I~gaC 5 l4uCS 0~5008 C0+"~'Lo%o~('v O.BOX 013100, MIAMI, FlORIDA 33101 FLORIDA POWER 8I LIGHT COMPANY April 16, 1976 L-76-163 Director of Nuclear Reactor Regulation.Attention:

Mr.R.C.DeYoung, Assistant Director for Light Water Reactors Division of Project Management U.S.Nuclear Regulatory Commission Washington, D.C.20555

Dear Mr.DeYoung:

CO,-gp~I i+Re: St.Lucie Unit 1 Docket No.50-335 A endix I Information Your letter of March 15, 1976 requested that we forward to you our plans for meeting the requirements of paragraph 50.34a of 10 CFR Part 50.Florida Power and Light Company'intends to use the following inputs to meet paragraph 50.34a requirements for St.Lucie Unit, 1.a.Site-specific information related to agriculture and marine productivity, resident and transient populations, and recreation activities (including shoreline usage for boating, swimming, etc.).b.Site-specific information for meteorology is to be developed by using Dames and Moore computer codes LSD-1 through LSD-7.These data relate to the'dispersion and disposition of effluents to terrestrial areas, water bodies, and the atmosphere.

c.Source term calculations which have been developed using the design and operational characteristics of St.Lucie Unit l.d.The GALE code for use in completing calculations of source term releases in St.Lucie Unit 1 liquid and gaseous effluents.

e.As applicable, supplemental calculational models will be used to convert gaseous and liquid source term releases into individual and population doses.(Nuclear Safety Associates, 5101 River Road, Bethesda, Md.codes GASI and GASP for gases and LINDY and LIP for liquids.)HELPING BUILD FLORIDA

, V I Director of Nuclear Reactor Regulation Attention:

Mr.R.C.DeYoung, Assistant Director Page Two April 13, 1976 The guidelines of Regulatory Guides 1.AA, 1.BB, 1.DD, 1.EE, and 1.FF will be used as the basis for our inputs.Cost-benefit data (per Regulatory Guide 1.FF)will be developed as we document our compliance with Appendix I requirements.

Our compliance documents will cite the basis for our calculations and conclusions.

An outline of our accomplishments to date and our future plans for meeting paragraph 50.34a is attached.Ver uly yours, Robert E.Uhrig Vice President REU/MAS/cpc Attachment cc: Jack R.Newman, Esquire t y al'l ST.LUCIE UNIT 1 SCHEDULE FOR MEETING THE REQUIREMENTS OF 10 CFR 50.34a l.Accomplishments to Date: a.Data gathering is complete for 1)development of source terms 2)radiological assessment of liquid and gaseous effluents 3)individual and population dose calculations based on a)food pathways b)demography c)atmospheric dispersion 4)cost-benefit analysis b.Calculations 1)source term and radiological assessment calculations are, complete I 2)dose calculations are 90%complete 2.Future Plans: a.Technical Specification changes will be prepared pending receipt of additional guidance now being developed by the NRC b.May 1, 1976-Complete dose calculations and cost-benefit analysis c.May 14, 1976-Complete draft compliance report and submit for FPL management review d.June 4, 1976-Submit final compliance report to the NRC ll r