ML18098A070

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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 NextEra Energy icon.png
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 U.S. NUCLFAR REGULATORY ISSION DOCKET NUMBER (2 76)

FILE NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL FROM: DATE OF DOCUMENT Mr UeYoung Florida Pwr & Lignt Co 4-1I7-7u M7.am'., Fla DATE RECEIVED

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NAME: St Lucre gi 'LANT SAFETY FOR AC'I ION/INFORMATION ENVIRO 7D eni ASSIGNED AD: ASSIGNED AD :

BRANCH CHXEF: BRANCH CHIEF ~

PROJECT MANAGER: PROJECT MANAGER:

LXC ~ SSTo LIC ~ ASST' INTERNAL D IST Rl BUTION NRC PDR ERNST I&E DEl BENAROYA ALLARD SPANGLER GOSSICK & STAFF EN INEER IPPOLITO SITE TECH KNXGHT OPERATING REACTORS GAMMXLL SE SHNEXL STELLO STEPP PAMLICKX HULIIAN OPERATXNG TECH PROJECT MANAGEMENT REACTOR SAFETY. EISENHUT SITE ANALYSIS BOYD ROSS SHAO VOLTPIER P. COLLINS NOVAK BAER BUNCH HOUSTON ROSZTOCZY SCHWENCER J ~ COLLINS PETERSON CHECK GRXMES KREGER MELTZ 'T RaI-Ke ~

HELTEMES & I SITE SAFETY & ENV Con SKOVHOLT SALTZMAN ANALYSIS RUTBERG DENTON & MULLER EXTERNAL DISTRIBUTION CONTROL NUMBER LPD NATL LAB BROOKHAVEN NATL LAB TIC REG, V"XE ULRIKSON(ORNL)

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('v April 16, 1976 L-76-163 CO,-

Director of Nuclear Reactor Regulation

.Attention: Mr. R. C. DeYoung, Assistant Director for Light Water Reactors Division of Project Management gp~

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 I i+

Dear Mr. DeYoung:

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

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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

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