ML17174A113
| ML17174A113 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, Zion  |
| Issue date: | 10/29/1979 |
| From: | Peoples D COMMONWEALTH EDISON CO. |
| To: | Gammill W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7911060452 | |
| Download: ML17174A113 (16) | |
Text
Commonwe9 Edison e
One First National Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 October 29~ 1979 Mr. W. P. Gammill, Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors u.s. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Dresden Station Units 1, 2 and 3 Quad-Cities Station Units 1 and 2 Zion Station Units 1 and 2 Requirements of 40 CPR 190 NRC Docket Nos. 50-10/237/249,
- so*-254/265 *and s o*-2*9s/3*0*4*
Reference (a):
September 17, 1979 letter from
- w. P. Gammill to All Power Reactor Licensees concerning the requirements of 40 CFR 190
Dear Mr. Gammill:
Commonwealth Edison Company is cognizant of the pro-visions of 40 CFR 190 that establish annual dose commitments to any member of the public in the general environment from all uranium fuel cycle sources, except those specifically excluded by the regulation.
At present, a commitment to meet these regulations is not contained in the Technical Specifications of Commonwealth Edison's Dresden, Quad-Cities or Zion Stations.
However, proposed Technical Specifications containing Commonwealth Edison's commitment to 40 CFR 190 for these stations have been submitted to the NRC Staff for their consideration and approval.
In response to your request of Reference (a),
Commonwealth Edison will meet the requirements of 40 CFR 190.
Until the Technical Specifications are issued by the NRC Staff, Commonwealth Edison's proposed method for demonstrating con-formance with the provisions of. 40 CFR 190 is set forth in the attachment to this letter.
This attachment contains Chapter 2.3, "Environmental Standards for the Uranium Fuel Cycle," from the Commonwealth Edison Offsite Dose Calculation Manual *.
Please address any questions that you might have regarding this matter to this office.
WFN:mae attachment Very truly yours,
.:, - i_ "):* J_.:_.,
D. L. Peoples Director of Nuclear Licensing
'l 911 0 6 0 i,S-;2...
ATTACHMENT
-- CHAPTER 2
- 3 ENVIRONMENTAL STANDARDS FOR THE URANIUM FUEL CYCLE FROM COMMONWEALTH EDISON OFFS'YTE DOSE CALCULATION MANUAL NRC DOCKET NOS. 50-10/237/249, 50-254/265 AND 50-295/304
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.e 2.3.1 Sources of Radiation and Radioactivity 2.3.l.l Uranium Fuel Cycle - Definition REVISICN l SEPTEMBER 1979 The uranium fuel cycle is defined in 40 CFR 190 (Reference 6.12) to include:
- a.
operations of milling of uranium ore,
- b.
ch~mical conversion of uranium,
- c.
isotopic enrichment of uranium,
- d. fabrication of uranium fuel,
- e.
generation of electricity.by a nuclear power plant using uranium fuel, and f..
~eprocessing of spent uranium fuel.*
Specifically excluded are:
- a. mining operations, b *. operations at waste disposal sites,
- c.
trans.p<;:>rtation of radioactive material, and
- d.
the use o( recovered nonuranium special nucleat or by~product materials from the cycle.
- 2.*3*.1 *. 2 Radiological Imoact of titanium Fuel Cycle Operations Environmental Radiation Protection Standards, 40 CFR 190,*require that the radiaticn dose resulting from all ope.rations of the*
2.3-1
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.tu::v.iSION.!.
- SEPTEMBER 1979 uranium fuel cycle (except the *specific exclusions noted) be considered in determining compliance.
Therefore each of the operations will be discussed and the radiological impact in the Commonwealth Edison Company (CECo) service area will be considered.*
2.3.1.2~1 Milling Reference 6.13 (Page 4), Reference 6.14 (Section 2.4), and Reference 6.15 (Page IV F-29) indicate that the maximum indi-vidtial doses due to milling will be less than 10 CFR 20* limits.
Therefore, the dose contribution to any person living in this service area due to milling operations, all more than 100 kilometers distant, is expected to be negligible compared to.40 CFR 1.90 limits.
2.3.1.2.2 Conversion
. Reference 6.14 (Section 3.4) and Reference 6.15 {Page IV F-40 and '!'able IV F-10) indicate that the maximum individual doses d~e:to UF6 conver~i~n will be less than l~ CFR 20 limits.
Therefore, the _dose contribution to ~ny perion living in this service _area due to UF6 conversion operations, all more than 100 kilometer~. distant, is expected to be negligible compared to 40 CFR 190 limits.
2~3.1.2.3 Enrichment Reference 6.14 (Section. 4.4) and Reference 6.15 (Page IV F-51)
- indicate that the maximum individual doses due to uranium enrichment will.be.less than 10 CFR 20 limits. Therefore, the dose contribution to any person living in this service
- area due to uranium enrichment operations, all more than 100 kilo;neters distant, is expected to be negligible compared to 40 CFR 190 iimits.
2.3-2
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e DR¥T REVISION l SEPTE4-1BER 1979 2.3.1.2.4 Fabrication Reference 6.14 (Section 5.4) and Reference 6.15 (Page IV F-63) indi6ate that the maximum individual doses due to fuel element fabrication will be less than 10 CFR 20 limits.
Therefore, the dose contribution to any person living in this service
.area.due to fuel fabrication operations, all mere than 100 kilometers distant, is expected to be negligible comparad to 40 CFR 190 limits.
2.3.1.2.S Generation of Electricity The.generation of electricity using a nuclear power plant results in radioactivity released in gaseous and liquid effluents.
The-radiological impact of these requires assessment (using the methodology of Sections 2.1 and 2.2 of this report) and comparison with 40 CFR 190 limits *
- Also, boiling water reactors (BWR' s) *contain radioactive ni tro-gen.;,..16 (N-16) in their steaml.ines and turthri~s:.. i.n sufficient*
~nough qua~tities to result in measurabl~ offsite doses.
The magnitude of.this so-called skyshine dose mus~ also be considered in determining 40 CFR 190 compliance.
Offsite doses due to.,other contained sources in the nuclear p~~er plant are negligible compared to those due to effluents and N-16 skyshine.
Measurements of the radiation environment due to N-16 have be.en made at.the Dresden St~tion (Reference 6.19).
An empirical fit to the measured dat~ is given in Equation 2.38:
O(R,P) -
SF OF (2.28 x 10-S) P exp (-0.007 R)
(2.38) 2.3-3
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D {R, P)
SF OF
- p
- 0. 007.
R
- l.
REVISION 1 SEPTEMBER 1979 Dose Due to*N-16
- Shielding Factor
{mrern)
The shielding factor for protection against gamma radiation.
SF = 0.7 for a home.
"("'?
Occupancy Factor The at-home occupancy factor:
.For fisherman 0.95 For all others 1.0 Constant
{mremjMWe-hr)
A constant to fit the equation to measured.
data.
Electric Power Generated (MWe-hr)
The total electric energy generated in the time period of interest.
Constant A constant to fit the equation to measured data.
Distance (m)
Distance from *the turbine to the ~ose point of. interest.
2.3-4
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- REVISION l SEPT&\\1BER 1979 This equation will be used at all CECo BWR's up to a distance of 1100 meters.
B~yond that distan~e the fit !and data) are considered unreliable and, further, the dose at this range is at most O.1 mrem/yr for CECo Stations.*
In certain situations more than *one nuclear power plant site may ccntribrite to a radiological dose to be considered in making 40 CFR 190 dose assessment.
At present (July 1979), the nuclear power stations in CECo's service* area are sufficiently distant from one another that the radiological dose, if not negligible
.compared to 40 CFR 190 limits., is due to only one site.
- Hence, adding dose components from several stations is not required.
However, within CECo's *service area the following future additive cf:>mbination is considered.
At some point within the triangle formed by the La* Salle, Dresden, and Braidwood Stations, an additive dose ~rom airborne releases may be postulated.
- However, the distances are such (La Salle to Dresden, 39 kilometers; Dresden to Braidwood, 18 kilometers; Braidwood to La Salle, 37 kilometers) that at any intermediate point postulated, the station-combined
. dose is less than that maximum calculated for an individual station.
Therefore, the combined effect of airborne releases will not be considered further.
Such is not the case for future releases of radioactivity into the ~qtiatic environment where, if more than 6ne facility uses the same receiving body of water, the station-combined dose must be considered.
Dresden and (the future) La Salle County Stations discharge their liquid waste.into the Illinois River and (the future) Braidwood Station discharges into the Kankakee Rive~
which flows into the rllinois at Dresden.
Quad Cities and (the future) Carroll County Stations use the Mississippi River and.
(the future) Byron Station uses the.Rock River which flows into the Mississippi at Moline, Illinois, downstream of Qu~d Cities.
~
For these two situ~tions the com~ined impact from upstream liquid waste discharges must be considered at each downst!"eam* location.
2.3-5 I
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l REVISION 1 SEP'l:'E:1BER 19 7 9 The dose contribution of *nuclear p6wer plants in other service areas ~eed not be.cionsider~d in CECo's 40 CF~ 190 assessment.
The Duane Arnold Station is about 135 kilometers from Quad Cities; the Clinton Station is about 125 kilometers from Braidwood and La Salle; and the Bailly Station is about 100 kilometers from Dresden.
2.3.1.2.6 Reprocessing Reference 6.15 (Table IV E-12) indicates that maximum.individual doses due to fuel reprocessing will be less than 10 CFR 20 limits.
Therefore, th~ dose contribution to any person living in this service area due to fuel reprocessing operations, ~11 more than 100.kilometers distant, is expected to be negligible compared to AO. CFR 190 limits.
2.3.1.~.7 Waste Disposal Sites
.The radiation dose associated with *the burial of.low level radio-
~ctive radwaste ne~d not be considered in d~termining complianca with 40 CFR 190 as this source is specifically excluded by the law.
Inasmuch as the licensed burial facility at Sheffield, Illinois, is near CECo's service area, at least a comment regardir.g it as ~ potential source is warranted.
The radiological impact of burial sites is discussed briefly in Chapter IV, Section H, Part 3.1.2.1 of Reference 6.15 (Page IV a~2a ff).
No significant movement of radioactivity into the general environment is expected, though some tritium has been found in groundwater near the Sheffield facility.
However, no significant dose contribution to a person living in the vicinity of CECo 's nuclear power plants is expected. * (The Quad Cities Station is about 60 kilometer~ fr6m Sheffield; Syron and La Salle are each about 90 kilometers from Sheffield.)
. 2. 3-6
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l 2.3.1.2.8 Transportatiori REVISION 1 SEPTEMBER 1979 The radiation dose associated with the transport of low level radioactive waste and spent fuel is also excluded from consid-eration by the requirements of 40 CFR 190.
This subject has been reviewed in References 6.16 and 6.17, and summarized again iri Reference 6.15 (Chapter IV, Section G).
The expected dose asso-ciatec with transportation is 3.4 x 10-3 mrem/person/reactor/yr.
2.~.1.2.9 Storage of Soent Fuel in Offsite Facilities
. The radiation doses associated with releases of radioactivity by independent spent fuel storage facilities (ISFS~) should also be considered in determining compliance with 40 CFR 190.
One ISFSF is being operated within CE;Co's service area; that is General Electric Company's Morris Operations Plant at Morris, Illinois, adjacent to CECo's Dresden Station.
Minute quantities of Kr-85 and other radioactive particulates are released in air-borne effluents.
A dose assessment was performed using typical release data provided by the General Electric Company and the ODCM environmental dose assessment models for Dresden.
(The effluent is released through a. 300-foot vent stack; hence the similarity between. the two facilities.
However, no adjustments were made for differences in site boundary ranges or ranges to dairies.
These differences are not expected to affect the con-clusion from the dose assessment.)
The estimated annual airborne releases from the GE Morris Oper-ation plant ar.e 6 x 104 µCi of tritium, < 55 x 106 µCi of Kr-85, 3 µCi of Co-60, and 1 µCi of Cs-137.
The maximum whole body dose from these radionuclides is 4 x 10-4 mrem/yr.
So long as this plant remains a spent f~el storage facility and does ~ot reprocess the fuel the dose contribution t6 any person living* in its vicinity will be negligible and not considered further in the Dresden 40 CFR 190 analysis.
. 2. 3-7
DR:Ar REVISION 1 SEPTE:*1DER J. 9 7 9
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2.3.1.2.10 Long-Term Storage of* High Level Radioactive Wastes
- l.
The dose associated with the long-term storage of high level radioactive wastes is excluded from consideration as far as 40
-CFR 190 is concerned.
The radiological impact is discussed in Reference 6.15 (Chapter IV, Section H, Part 3.2) and should be
.negligible in the CECo service area.
2.3.1.3 Summary The magnitude of radiological dose due to various operations of the uranium fuel cycle and its impact in the Commonwealth Eqison Company service area has been r'eviewed with respect to
- the_requirements of 40 CFR 190.
The only dose components requiring consideration are those due to:
a*.
radioactivity in nuclear power plant liquid and gaseous effluents, and
- b.
the direct radiation due N-16 in BWR steam piping, turbines, and associated equipment.
2.3.2 Numerical Models 2.3.2.l A'irborne Releases and Direct Radiation 2.3.2.1.1 Whole Body Dose The maximum whole body (WB) dose from airborne* releases and direct radiation will be determined by adding, for each sector, the* dose 6ontributions, if applicable, from all (1) noble gases~
(2) airborne radioiodines, "particulates", and other non-noble gas. radionuclides; * (~direct radiatior.. from BWR turbine N-16 skyshine as computed at the nearest actual res-idence in. each sector (Ta bl~ 7. 24) ; \\ and at Dresden only, the contributions from (4) riobl~ ;ase.s/ and (5} airborne "par.ticulates" from the Morr.is Operations p\\-..an..t/if spent fuel is reprocessed.
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SEPTEMBER 1379 At Zion, sectors wAe site boundary is over Wke Michigan will not be considered.in the 40 CFR 19a analysis.
At Dresden and* Quad Cities Equations 2.39 and 2.40, respectively, will be used to compute the direct radiation dose in sectors whose r~stricted area b6undary is over water.
This dose, which accounts for possible fishing activities in the vicinity, will then be added to the nearest residence dose computed with Equation 2.38 using an at-home occupancy factor of 0.95 rather than the usual l.a.
An occupancy factor of a.as is used for fishermen (O.a25 at each of two locations at Quad Cities) and a boat shielding factor of I.a.
At Dresden:
D(R,P) = (1.0) (O.aS) 2.28 x la-S Ri
= 488 m R2, R3 = 6la m 3
L i=l P.
- l.
Electric power generated by each unit in the year At Quad Cities:*
P. exp c-a.007 x R.)
1 1
(MWe-hr)
D(R,P) = (I.a) (a.025) 2.28 x 10-5 P [exp (-0.007 R1 )~ +
exp (-0.007 R2>]
Rl = 100 m R2 = 4aa m p
Electric power generated by the station
. 2. 3-9 (MWe-hr)
(2.39)
(2. 40)
REVISION 1 SEPT!:.'1BER 1979 Table 2.3-1 shows the methodology for determining the maximum whole body dose from airborne releases and direct radiation.
2.3.2.1.2
- Thyroid Dose The maximum thyroid dose from airborne releases and direct radia~iOn Will be determined. by adding,* fOr each SeCtOr I the dose contributions from the various sources in a manner similar to that for the maximum whole bqdy dose, as de~cribed above.*
and in Table 2.3-1.
2.3.2~1.3 Any Other Organ Dose In this class the dose. from airborne rel.eases and dir.ect radiation to the GI-LLI, bone, _liver,*.kidney, lung, and skin will be determined separately in each sector, and the maximum value chosen to repiesent nany other organn (AOO) for purposes of determining_ compliance.
The maximum AOO dose will be determined in a manner similar to that for the maximum whole body dose, as des~ribed in Subsection 2.3.2.1.1 and in Table 2.3-1.
2.3.2.2 Radioactivity in Liquid Releases The maximum whole body, thyroid, and AOO doses from radioactivity in individual station liquid.releases will be determined using,*
for.the fish pathway, the near-field estimate of dilution at the station; an~ using, for ~he drinking watei pathway, the average flow of the re¢eiVing body of water at the nearest downstream community water system, if the water system is near the station.
Otherwise, the drinking water pathway will
- not be considered.
For situations involving combined-station releases, for the fish pathway, for releases from all upstream CECo facilities, the tissue doses *will be determined. using the average flow of the receiving body of water at.the station.
Tab1e*2.3-l ~hews the. methodology for determining these doses.
2.3-10
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2.3.3 Symbols Used.in Section 2.3 SYMBOL D{R,P)
P, P.
1 SF OF Dose due to N-16 skyshine Electric power generated by station* or unit i Distance Shielding Factor Occupancy Factor 2.3-11 Rl:."V:L.S ION 1 SEPTEM3ER 1979
- UNIT,
{mrem)
{MWe-hr)
(meters)
T r
. I t
I i
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. i 2.3.4 Constants Used in Section 2.3-NUMERICAL VALUE 2.28 x* 10-5 0.007.
0.7 1.0 o.os.
0.95 1.0 NAME Fitted Constant Fitted Constant Shielding Factor
.a~ home Shielding Factor on a Boat Occupancy Factor While Fishing Occupancy Factor at Home for Fishermen Occupancy Factor at Home for Everyone but Fishermen 2.3-12
. REVISION 1 SEPTEMBER 1979 UNIT (mremjMWe-hr)
(m-1)
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TABLE 2.3-1 NUMERICAL MODELS FOR COMPUTING RADIATION* DOSE FROM URANIUM FUEL CYCLE OPERATIONS8 FUEL CYCLE OPERATION.
CLASSIFICATION OF RADIATION WHOLE BODY.
ANY OTHER ORGAN THYROID GI-LLI BONE LIVER KIDNEY LUNG SKIN FOOT*
NOTES
- l. Nohle Gases
- 2.
Afr borne Iodine and Particulates
- 3.
Liquid Waste
- 4.
Direct Radiation F.quation 2.5 Equation 2.5 Equation Equation 2.11 2.11 Equation Equatio~
2.22 2.22 Equation 2.38 Equation 2.38
Equation 2.5 ------
Equ~tion 2.11----
Equation 2.22 ----
Equation 2. 38 ----
Equation 2.7 Equation 2.11 WB Corr.ponent Equation 2.22 WB Compone.nt E;quation 2.38 FUEL '.STORAGE FACILI'fY
- a.
S.
Noble Gases
- 6.
Airborne Particulates N/A N/A N/A N/A Not Applicable Not Applicable N/A N/A The maximum sector doses for the whole body, thyroid, and any other'organ, sununed over all classifications of radiation, will be added to similar tissue dose~ received from radioactivity in liq~id releases, or combined-station releases, if applicable.
The maximum dose of each tissue class will be compared to the limits established in 40 CFR l~O.lO(a).
b c
d 0
e
r TABLE 2.3-1 (Cont'd) b~
'fhe dose to all organs except the thyroid will be determined first with Equation 2*.11 then adjusted through multiplication by a factor 0.5/fg ~ 1 where f~ is given in Table 7.1-2.
c *. Only the fish pathway portion of Equation 2.22 will be used unless the commuriit~ water system is near the station.
For combined aquatic pathway doses from more than one station the dose from each upstream CECo station will be determined with.Equation 2.22, using Mw/Fw instea~ of Mf/Ff at the individual station~
- d.
Except for special considerations bf fishermen at Dresden ~nd Quad Cities direct radiation from BWR turbine N-16 will be computed at the nearest actual resident in each sector and.not at the site boundary.
A shielding and occupancy factor of
- 0. 7 w i 11 be used..
- e.
So long as this plant remains a spent fuel storage facility and does not reprocess the fuel, its contribution to the total dose will not be considered further.
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