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{{#Wiki_filter:-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.
{{#Wiki_filter:-NRCFORM 195                                                 U.S. NUCLFAR REGULATORY       ISSION DOCKET NUMBER (2 76)
EISENHUT SHAO BAER SCHWENCER GRXMES SITE SAFETY&ENV ANALYSIS DENTON&MULLER BROOKHAVEN NATL LAB ULRIKSON(ORNL)
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
SITE ANALYSIS VOLTPIER BUNCH J~COLLINS KREGER RaI-Ke~Con CONTROL NUMBER Rosa  
: 8. E Uhrzg                                           g 23 7t SLFTTER               C3NOTORIZED                  PROP                  INPUT FORM            NUMBER OF COPIES RECEIVED 1
~%~~~r*t~~~~1~
    %ORIGINAL         R UNC LASS IF I E D OCOPY                                                                                              one szgned DESCRIPTION                                                          ENCLOSURE Ltr w/attcnrnents.....re             our 3-15-76   1Lr.....
'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:
furnzsnxng info   concernmng Appendxx           I into
Mr.R.C.DeYoung, Assistant Director for Light Water Reactors Division of Project Management U.S.Nuclear Regulatory Commission Washington, D.C.20555
                                                                                  ~   ~
                                ~
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)
NS ASLB LA PDR CONSULTANTS.                                              Rosa


==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.
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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.
* t
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  
            ~ ~ ~  ~  1 ~
, 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.
                        'A-'~                                    O. BOX 013100, MIAMI, FlORIDA 33101 (P
Our compliance documents will cite the basis for our calculations and conclusions.
L1I~gaC FLORIDA POWER 8I LIGHT COMPANY l4uCS 0~5008 5    C0 +" ~'Lo%
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}}
o~
('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
 
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
 
r ll}}

Latest revision as of 09:58, 21 October 2019

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)
v • d • e


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

8. E Uhrzg g 23 7t SLFTTER C3NOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED 1

%ORIGINAL R UNC LASS IF I E D OCOPY one szgned DESCRIPTION ENCLOSURE Ltr w/attcnrnents.....re our 3-15-76 1Lr.....

furnzsnxng info concernmng Appendxx I into

~ ~

~

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)

NS ASLB LA PDR CONSULTANTS. Rosa

~ % ~ ~ ~

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  • t

~ ~ ~ ~ 1 ~

'A-'~ O. BOX 013100, MIAMI, FlORIDA 33101 (P

L1I~gaC FLORIDA POWER 8I LIGHT COMPANY l4uCS 0~5008 5 C0 +" ~'Lo%

o~

('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

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

r ll

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