ML19308D718
| ML19308D718 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/28/1976 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Deyoung R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003120871 | |
| Download: ML19308D718 (5) | |
Text
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OCCKET NUMDER Ua NUCLE AR REGULATORY PMMISSION (2 7 )
50- 302.
I NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL FROM:
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Mr Deyoung Florida Power & Light Co 5 28 St Petersburg, Fla ATE RECEIVED g.1 76 J i Rodgers OLETTER CNOTORIZED "J
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Ltr trats the following:
" Appendix I Analysis for Crystal River Nuclear Unit"........dtd May 1975 & prepared by NUS...
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PLANI NAME: Crystal River FOR ACTION /INFOR.1ATION 6-2-76
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In Re:
Florida Power Corporation Crystal River Unit #3 Docket No. 50-302
Dear Str. DeYoung:
Attached are forty (40) copies of the NUS Corporation report entitled, " Appendix I Analysis for Crystal River Nuclear Unit",
dated Stay, 1976.
This report demonstrates that the potential radiation deses from Crystal River Unit #3 meet the design objectives set forth in Section II of Appendix I to 10CFR50.
The Final Safety Analysis Report (FSAR) for CR #3 will be re-vised via of Amendment No. 49 to include a reference to the NUS Appendix I Report.
These proposed FSAR revisions are attached for your review.
In addition, Florida Power Corporation is currently reviewing the NRC's " Draft Stodel Technical Specifications" related to Appendix I implementation, to determine the modifications necessary to include plant specific information.
We will be ready at your earliest possible convenience after June 4, 1976, to discuss our Appendix I evaluation and the pro-posed Technical Specifications for the purpose of keeping releases of radioactive materials in effluents as low as reasonab1f achiev-able.
Very truly,,yours,
[ \\/ c-S ' l. a 54%L J.,T. R'odgers/
Asst. Vice President JTR/iw General Office 3201 Tn.rtysourtn street soutn. P.O. Box 14042. St. Petersburg, Fonda 33733 813 - 866-5151
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(Proposed;FSAR Revision To Be Included in Am. h9)
AEPENDIX 11 B
' Appendix I Analysis for Crystal River Unit 3.(1)
Thh Crystal River. facility has been evaluated with respect to its ability Go m t the requirements set'forth in Section II of Appendix I to 10CFR50.
sp;cifically,Section II of Appendix I(2) sets forth the following design ebjcetives:
A.
The calculated annual total quantity of all radioactive material above background to be released from each light-water-cooled nuclear power reactor to unrestricted areas will not result in.an estLnated annual dose or dose commitnent from liquid effluents for any individual in an unrestricted area from all pathways of exposure in excess of 3 millirens to the total body or 10 millirens to any organ.
B.l.' The calculated annual total quantity of all radioactive matcrial above background _to be released-frca each light-water-cooled nuclear power reactor to the atmosphere will not result in an estimated annual air dose; from gaseous effluents at any location near ground level which could be occupied by individuals in unrestricted areas
-in excess of.10 millirads for gnm-a radiation or 20 millirads for beta radiation.
- 2..Notwithstanding the guidance of paragraph B.1:
(a) The Commission may specify, as guidance on design
' objectives, a lower quantity of radioactive material above background to be released to the atmosphere if it appears that the use of the
-dnaign objectives in paragraph B.1 is likely to result in an estimated
-annual external dose from gaseous effluents to any individual in an
' unrrstricted area in excess of 5 millirems to the total-body; and
_(b) Design objectives based upon a higher quantity _of radio-active material above background to be released to the atmosphere than-
-th9-quantity specified in paragraph B.1 vill be deemed to meet the rcquirementsLfor keeping levels of radioactive material in gaseous
~ ffluents as low as is reasonably achievable if the applicant provides c
.rtesonable assurance that the proposed higher quantity will not result in an estinated annual external dose from gaseous effluents to any individual in unrestricted areas in excess of 5 millirems to the total
- bodyfor 15 millirems to the skin.
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(_ Propos:;d _ FSAR Revi
>n To Be
' Included in Am. h9)
- ' Appendix 11 B -~ Appendix I LAnalysis for-Crystal River Unit 3 Radioactive source terms were calculated in a manner consistent with Draft Regulatory' Guide 1.B3.(.3) Specific data used are given in Appendix A.
Also shown in Appendix A are flow diagrams of the primary vaste processing and the miscellanecus vaste processing systems. Meteorology information
.used_in the calculation of doses was consistent with Regulatory Guide 1.111. b)
For liquid effluent discharge, no dilution of the liquid effluents beyond the condenser cooling water discharge canal was assumed. For calculating doses to the maximum individual, this procedure is considered realistic, inasmuch as seafood is taken directly from the discharge canal and the shallow area it traverses. For population doses, this procedure is conserva-tive - doses resulting frca liquid effluent release are overestimated.
Dose calculations were done in a manner consistent with Regulat'ry Guide 1.109(5) (formerly Draft Regulatory Guide 1.AA).
The NRC LADTAP and GASPAR ccmputer codes were used.
No effluent release data are available since the unit is not yet operational.
These results indicate that the maximum radiation dose as calculated for off-site individuals from all normal sources is well within the requirements of Appendix I to 10CFR50.(2) Similarly, the integrated dose from all normal sources as a result of normal operation of the nuclear plant will
- have a negligible effect on population radiation burden.
(Proposed FSAR R;vit. n To Be
- g,v.',+ Included in Am, 49)
,Appendix.11 B'- App:ndix'I-Analysis.for' Crystal River. Unit 3 References
'(1)
" Appendix I Analysis Crystal River. Nuclear Unit," NUS Corporation,
'NUS-1721, May, 1976.
(2)~,
Title 10 Code of Federal Regulations Part 50, Appendix I, U.S. Nuclear Regulatory Commission (April 1976).
(3)-
" Calculation of Releases of Radioactive Mater 1L.
in Liquid and Gaseous
~ Effluents from Pressuri::ed Water Reactors (PWR's)," Draft Regulatory Guide 1.BB, U.S. Nuclear Regulatory Commission (Sept. 9, 1975).
-(h)
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases frem Light-Water-Cooled Reactors,"
. Regulatory Guide 1.111, U.S. Nuclear Regulatory Commission (March 1976).
(5)
Calculstion of Annual Doses to Man from Routine Releases of Reactor
. Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Regulatory Guide '. 109, U.S. Nuclear Regulatory Commission (March 1976).
s 11B-4
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