ML19206B132
| ML19206B132 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/27/1976 |
| From: | Gammill W Office of Nuclear Reactor Regulation |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19206B131 | List: |
| References | |
| NUDOCS 7905070415 | |
| Download: ML19206B132 (3) | |
Text
.
DISTRIBUTION:
DOCKET FILES N
NRR RDG
\\
EMB RDG DSE RDG
\\
\\
\\
\\
hE10iL*liDCI TO2:
D. B. Vassallo, Assistant Director for Light Water Reactors, DPM FROM:
U. P. Ca::::ill, Assistant Director for Site Tecnnology, DSI
SUBJECT:
5.TIOR0 LOGICAL SUPPLD'Z';T TO THE SEP. FOR '"*.iREE MILE ISLCD, UNIT NO. 2 TLWT NA22: Three Mile Island, Unit ;o. 2 LICC;SI';G STAGE: OL DOCST ';U'ElER:
50-320 2ES?0;;SIELE B?a'ICH: LUR#2 REQUESTED CC"PLETIC'; DATE: December 15, 1976 REVIEW SATUS:
Complete Enclosed is supplecental input to the Safe 7 Evaluation Peport for Ihree Mile Island, Unit 2, addressin:; the cercorological evaluation for conformance with the requirements of Appendix I to 10 CFR Part 33.
Sectica 2.3.5, "Iong-Term (Ecutine) Diffusion Estimates" has been amended to include a nore complete description of the model ano assunptions used, including a list of the relative concentration and deposition values used in the dose estinate su=marv which apnears in Section 11.0, ""adioactive 'iaste Management".
We rccor=end a revision in the SIR Supplenent 7ebnittal frc
- 2. Vol b r to D. Vassallo, " Supplement to the SER for Ihree Mile Island Nuclear Station, Unit No. 2, Rc;;arding Cc=pliance with Appendix I" dated October 27, 1976. With this revisal of Section 11.3 the last sentence of the second paragraph would be, "At=cspheric transport and diffusion estimates applicable to the dose calculaticus are described in Section 2.3.5, %ng-Tern (Routine) Diffusion Esti=stes'".
/
This input waA prepared by L. Andrews and 2. H. Markee, Jr., htcoroloS7 Section HMB.
William F.
Iancill, Assiatant Director for Site Technology Division of lite Safety and Environ =ent.cl Analysis
,,'I DSE:HMB DSE:
as stated-
--DSE:HMB---
--DSE:ST o,,,c.
___LAndrewsi =._EHMarnee __.LHulman WGa-41_
k w an = = *e. _ gee w g y c
12/16]76 12]A o]_7k _ 12 /_. ]2 6_..
12[.. [7 6
- oan, Forza ABC-):3 (Rae. M5) AzcM 0240 W un se eovan=mant emense arricas tw4.sas.ies 790so7oy/f
i SUPPLE". NT TO TV.E SAFI Y EVALUATION RE?CRT FOR T'-i?.EE MILE ISLAND NUCLEAR STATION, U'iIT S0. 2 METRCPOLITA'i EDISCN CCMPANY DOCU T Si;M3ER 50-320 2.3.5 Lone-Ters (Ecutine) Dif fusion Es timates We have made reasonable esti=ates of average at=cspherie dispersica conditicus for the Three Mile Island site using our at=ospheric dispersion =cdel for long-term releases (Sagendorf and Goll, draft, 1976). This codel is based upon the " Straight-Line Trajectory Mcdel" described in Regulatory Guide 1.111," Methods of Esti=ating A:=cspheric Transport and Dispersion of Casecus Effluents frec Light-Water-Cooled Reactors." The model assu=es a mixture of elevated and ground-level releases, based on the criteria established in Regulatory Guide 1.111.
Non-continuous and inter =ittant gasecus releases were evaluated separately frc= centinuous releases.
The calculations also include an estimate of maximu= increase in cal-culated relative concent sti:n and deposition due to open terrain recirculatica of airficw not considered in the straight-line trajectory =edel.
Table 2.3.5-1 lists relative concentration and depositica values used in the dose estimations which are su==arized I
in Section 11.0, " Radioactive Waste Management."
,3 '; }
n t._
t 6-
TABLE 2.3.5-1 T!!REE HILE ISLAND, UNIT 2, RELATIVE CONCENTitATION [X Q) AND DEPOSITIO!! (D/Q) USED IN DOSE ESTIlfATE SU} DIAR.
Direction Distanca (mi)
X/Q D/Q X/Q D/Q Source Receptor (From Source)
Continuous Relenco Periodic Relcace (240.2 hre
'cach) llll Reactor Vent Realdencey/
E 0.43 2.3E-06 3.8E-09 5.2E-06 1.2E-07 Carden W
,0.37 1.9E-06 2.7E-08 4.7E-06 9.4E-08 WNW 0.37 1.4E-06 2.2E-08 6.7E-06 1.4E-07 N
1.00 3.0E-07 4.1E-09 9.3E-07 1.8E-08 Cows NNE
,2.34 4.9E-07 1.8E-09 2.5E-06 8.9E-09 Turbine Vent Residencey/
E 0.43 3.6E-05 1.1E-07 Carden W
0.37 4.7E-05 1.3E-07 1RlW 0.37 4.5E-05 1.1E-07 h
H 1.00 6.4E-06 1.3E-08 Cows NNE 2.34 1.2E-06 1.8E-09 r-J e
hen
References:
1.
Sagendorf, J. F., and J. T. Goll,1976: ICQD0Q, Program for the Evaluation of Routine Effluent Releases at Nuclear Power Stations, (DRAIT).
U. S. Nuclear Regulatory Co==1ssion, Office of Nuclear Reactor Regulation, Washington, D. C.
2.
U. S. Nuclear Regulatory Co==1ssion,1976: Regulatory Guide 1.111, Methods of Isti=ating At=ospheric Transport and Dispersion of Gaseous Effluents in Routine Releases From Light ater-cooled Reactors.
w USNRC, Office of Standards Development, Washington, D. C.
t n
,'i '; _'
g I