ML19295A222
| ML19295A222 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/07/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19295A221 | List: |
| References | |
| NUDOCS 8009290620 | |
| Download: ML19295A222 (31) | |
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SAFETY EVALUATION AND ENVIRONMENTAL IMPACT APPRAISAL BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
TO FACILITY LICENSING N0. DPR-2, AMENOMENT NO.
TO FACILITY LICENSING NO. DPR-19, AND AMEN 0 MENT N0.
TO FACILITY LICENSING NO. ORP-25 COMMONWEALTH EDIS0N COMPANY DRESDEN NUCLEAR POWER STATION, UNIT NOS. 1, 2, AND 3
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DOCKET NOS. 50-010/237/249
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INTRODUCTION On May 5,1975, the Nuclear Regulatory Commission announced its decision in the rulemaking proceeding concerning the numerical guides for design objec-tives and limiting conditions for operation to meet the criterion "as low as
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is reasonably achievable" for radioactive materials in light-water-cooled nuclear power reactor effluents. This decision is set forth in Appendix I to 10 CFR Part 50.UI On September 4,1975, the Commission adopted an anendment to Appendix I(
to provide persons who have filed applications for construction permits for light-water-cooled nuclear power reactors which I
were docketed on or after January 21, 1971, and prior to June 4,1976, the
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option of dispensing with the cost-benefit analysis required by Section 11.0 of Appendix I, if the proposed or installed radwaste systems satisfy the guides on design objectives for light-water-cooled nuclear power reactors proposed by the Regulatory Staff in the rulemaking proceeding on Appendix I (Docket RM-50-20), dated February 20, 1974.(3)
Following ELD review of the Generic Cost / Benefit Analysis, a paragraph
-ill be added which will provide jus'.ification for using the September 4, 1975, amendment to Appendix I for application for construction prmits
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filed prior to January 2,1971.
Section V.B of Appendix I to 10 CFR Part 50 requires the holder of a license authorizing operation of a reactor for which application was filed prior to i
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, January 2,1971, to file with the Commission by June 4, 1976; (1) infor-mation necessary to evaluate the means employed for keeping levels of radioactivity in effluents to unr+stricted areas "as low as is reasonably achievable," and (2) plans for prmp sed Technical Specifications developed for the purpose of keeping releases of radioactive materials to unrestricted areas during normal operation, including anticipated operational occurrences "as low as is reasonably achievable."
In conformance with the requirements of Section V.B of Appendix I, the Commmonwealth Edison Company (CEC) filed with the Commission on June 4, 12,1976,(6,7) the necessary information to permit 1976,(4,5) and November an evaluation of the Dresden Nuclear Power Station, Unit tios.1, 2, and 3, with respect to the requirements of Sections II. A, II.B, and II.C of Appendix 1.
In these submittals, CEC provided the necessary information to show conformance with the Commission's September 4,1975 amendment to Appendix I rather than perform a detailed cost-benefit analysis required by Section II.D of Appendix 1.
l-By letter dated
, CEC submitted proposed changes to Appendix A Technical Specifications for Dresden Nuclear Power Station, Unit Nos.1, 2, and 3.
The proposed changes implement the requirements of Appendix I to 10 CFR Part 50 and provide reasonab e assurance that releases of radioactive materials in liquid and gas. aus effuents are "as low as is reasonably achievable" in accordance with 10 CFR Parts 50.34a and 50.36a.
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, DISCUSSION The purpose of this report is to present the results of the NRC staff's detailed evaluation of the radioactive waste treatment systems installed at Dresden Nuclear Power Station, Unit Nos.1, 2, and 3; (1) to reduce and maintain releases of radioactive materials in liquid and gaseous effluents to "as low as is reasonably achievable" levels in accordance with the requirements of 10 CFR Parts 50.34a and 50.36a, (2) to meet the individual dose design objectives set forth in Sections II. A, II.B, and II.C of Appendix I to 10 CFR Part 50, and (3) to determine if the installed C
radwaste systems satisfy the design objectives proposed in RM-50-2 rather than an individualized cost-benefit analysis as required by Section II.D of Appendix 1.
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I.
Safety Evaluation The NRC staff has performed an independent evaluation of the licensee's proposed method to meet the requirements of Appendix I to 10 CFR Part 50.
f The staff'c evaluation consisted of the following:
(1) a review of the i
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information provided by the licensee in his June 4,1976, and November 12, 1976, submittals; (2) a review of the radioactive waste (radwaste) treat-ment and effluent control systems described in the licensee's Final Safety Analysis Report (FSAR);(0 (3) the calculation of expected releases of radioactive materials in liquid and gaseous effluent (source terms) for the Dresden facility; (4) the calculation of relative concentration (X/Q)
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. hi and deposition (D/Q) values for the Dresden site; (5) the calculation of individual doses in unrestricted areas; and (6) the comparison of the calcu-lated releases and doses with the pro. posed design objectives of RM-50-2 and
!fU the requirements of Sections II. A, II.B, and II.D of Appendix I.
f The radwaste treatment and effluent control systems installed at Dresden, Unit Nos. 2 and 3, have been previously described in Section 3.0 of the staff's Safety Evaluation Reports (SER) dated October 17, 1969, and November 18, 1970, respectively,(9,10) and in Section 3.5 of the Final Environ-mental Statement (FES) dated November 1973.IIII For Unit No.1, these systems are discussed in the licensees Preliminary Hazard Summary Report dated September 1957. Unit Nos. 2 and 3 share a common liquid and gaseous radwaste system and Unit No.1 is provided with separate liquid and gaseous radwaste systems.
Since the FES and SER were issued, the licensee has modified these systems to include addition of charcoal delay systems to Unit Nos.1, i
2, and 3, and the addition of a purge tank and two demineralizers in Unit Nos. 2 and 3, liquid radwaste system. The modifications noted above were considered in the staff's evaluation.
Based on more recent operating data at other operating nuclear power reactors, which are applicable to Dresden Station, Unit Nos.1, 2, and 3, and on changes in the staff's calculation models, new liquid and gaseous source terms have been generated to determine conformance with the requirements of Appendix I.
The new source terms, shown in Tables 1 through 4, were calculated using the nF g
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, (12) model and parameters described in NUREG-0016.
In making these deter-minations, the staff considered waste flow rates, concentrations of radio-active materials in the primary system, and equipment decontamination
!:1 factors consistent with those expected over the 30 year operating life of
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the plant for normal operation including anticipated operational occurrences.
The principal parameters and plant conditions used in calculating the new liquid and gaseous source terms are given in Tables 5 and 6.
The staff also reviewed the operating experience accumulated at Dresden, Unit Nos.1, 2, and 3, in order to correlate the calculated releases given in Tables 1 through 4 with observed releases of radioactive materials in liquid and gaseous effluents. Data on liquid and gaseous effluents are contained in the licensee's Semi-Annual Operating Reports covering the period of 1974 through 1976. A summary of these releases is given in Tables 7 and 8.
Dresden, Unit No.1, reached initial criticality in October 1959 and comer'-
cial operation in July 1960; Unit No. 2 in January 1970 and 1972, respectively; and Unit No. 3 in January 1971 and in November 1971, respectively. The staff considered effluent release data from January 1974 through December 1976 for comparing actual releases from Dresden, Unit Nos.1, 2, and 3, with calcu-l ated, releases. The staff considers these effluent release data to be more representative of the long term operation of the plant since the licensee modified the radwaste systems during 1975.
The actual liquid effluent releases of 0.35 Ci/yr for Unit No.1, and 0.61 Ci/yr/ reactor for Unit Hos. 2 and 3, shown in Tables 7 and 8, are in good
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. agreement with the staff's calculated values of 0.27 Ci/yr for Unit No.1, and 0.78 Ci/yr/ reactor for Unit Nos. 2 and 3.
The actual releases of iodine-131 of 0.37 Ci/yr for Unit No.1 and 0.49 Ci/yr/ reactor for Unit Nos. 2 and 3, are also in good agreement with the staff's calculated values of 0.67 Ci/yr for Unit No.1, and 0.62 Ci/yr/ reactor for Unit Nos. 2 and 3.
5 For noble gases, the actual releases of 4.6 x 10 Ci/yr for Unit No.1 and 4
1.6 x 10 Ci/yr/ reactor for Unit Nos. 2 and 3 were higher than the staff's 4
4 calculated values of 1.2 x 10 Ci/yr for Unit No.1 and 1.1 x 10 Ci/yr/ reactor for Unit Nos. 2 and 3 due to the higher actual air inleakage to the main condenser s than assumed in the calculation of the noble gas releases.
L-Based on the above evaluation of operating data, the staff believes that the calculational model reasonably characterizes the actual releases of radio-active materials in liquid and gaseous effluents from Dresden, Unit Hos.1, f
2, and 3.
The calculated releases given in Tables 1 through 4 were used in" g
t the staff's dose assessment discussed below.
The staff has made reasonable estimates of average atmospheric dispersion conditions for the Dresden site using an atmospheric dispersion model appropriate.'or long term releases.
The model used by the staff is based upon the " Straight-Line Trajectory Model" described in Regulatory Guide 1.ll1.II4I I:
Releases from the Unit 1 stack and Units 2 and 3 stack were considered as g=
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elevated; releases from the Unit 1 radwaste building were considered as ground level; and releases from the Units 2 and 3 reactor building were considered as partially elevated, in conformance with the criteria recomm-ended in Regulatory Guide 1.111.
An estimate of increase in calculated relative concentration (X/Q) and relative deposition (D/0) due to spatial
.i1 temporal variations in airflow, not considered in the straight-line model, was included using Figure 2 of Regulatory Guide 1.111.
The calculations also included considerations of intermittent releases during more adverse atmospheric dispersion conditions than indicated by an annual average calculation as a function of total duration of release (Sagendorf and Goll, draft 1976). Radioactive decay of effluents and
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depletion of the effluent plume were also considered as described in Regu-I latory Guide 1.111. One year (3/74-2/75) of onsite meteorological data was used in the analysis.
Elevated releases were evaluated using joint frequency distributions of wind speed and direction measured at the 91m level by atmospheric stability (defined by the vertical temperature gradient between the 10m and 91m l ev el )., Ground level releases were evaluated using joint frequency distributions of wind speed and direction measured at the 10m level by atmospheric stability (defined by the vertical temperature gradient-between the 10m and 46m levels).
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_g, The staff's dose assessment considered the following three effluent cate-gories:
(1) pathways associated with radioactive materials released in liquid effluents to the Illinois River, (2) pathways associated with noble gases released to the atmosphere; and (3) pathways associated with radio-iodines, particulates, carbon-14, and tritium released to the atmosphere.
The mathematical models used by the staff to perform the dose calculations to the maximum exposed individual are described in Regulatory Guide 1.109.(
The dose evaluation of pathways associated with the release of radioactive materials in liquid effluents was based on the maximum exposed individual.
For the total body dose, the staff considered the maximum exposed individual to be an adult consuming 730 liters /yr from the water intake at Marseills, Ill.,
and use of the shorelire for recreational purposes (10 hr/yr).
The dose evaluation of noble gases released to the atmosphere included a p
calculation of beta and gamma air doses, at the site boundary and total body and skin doses at the residence having the highest dose. The maximum air doses at the site boundary were found at 0.49 miles N relative to the Dresden I
Unit 1 plant stack. The location of maximum total body and skin doses were j
determined to be at the same location.
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The dose evaluation of pathways associated with radioiodine, particulates, f
carbon-14, and tritium released to the atmosphere, was also based on the l_
maximum exposed individual.
For this evaluation, the staff considered the maximum exposed individual to be a child residing at 1 mile north of the Dresden Station with the pathways of inhalation and ground plan radiation.
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_g-Using the dose assessment parameters noted above and the calculated rpleases of radioactive materials in liquid effluents given in Tables 1 and 2, the staff calculated the annual dose or dose commitment to the total body or to any organ of an individual, in an unrestricted area, as shown in Table 11, to be less than 3 mrem / reactor and 10 mrem / reactor, respectively, in conformance with Section II. A of Appendix 1.
Using the dose assessment parameters noted above, the calculated releases of radioactive materials in gaseous effluents given in Tables 3 and 4, and the appropriate relative concentration (X/Q) value given in Tables 9 and 10, the staff calculated the annual gamma and beta air doses at or beyond the site boundary to be less than 10 mrad / reactor and 20 mrad / reactor, respectively,.
in conformance with Section II.B of Appendix I.
Using the dose assessment parameters noted above, the calculated releases of radiciodine, carbon-14, tritium, and particulates given in Tables 3 and 4, and the appi'opriete relative concentration (X/Q) and deposition (D/Q) values given in Tables 9 and 10, the staff calculated the annual dose or dose commitment to any organ of the maximum exposed individual to be less than 15 mrea/ reactor in conformance with Section II.C of Appendix I.
i The summary of calculated doses given in Table 11 are different from and replace those given in Tables 5.1 through 5.5 of the FES.
Rather than perfo ming an individualized cost-benefit analysis required by Section II.D of Appendix I, the licensee elected to show conformance with the numerical design objectives specified in the September 4,1975 amendment S
to Appendix I (RM-50-2). As shown in Tab'les 1 and 2, the calculated release of radioactive naterial in liquid effluents is less than 5 Ci/yr/ reactor, excluding tritium and dissolved noble gases. As given in Tables 3 and 4, the calculated quantity of iodine-131 released in gaseous effluents is less than 1 Ci/yr/ reactor.
The calculated doses are less than the dose design objec-tives set forth in RM-50-2, and, therefore, satisfies the requirements of Sec-tien II.D of Appendix I.
CONCLUSION Based on the foregoing evaluation, the staff concludes that the radwaste treatment systems installed at Dresden, Unit Nos.1, 2, and 3, are capable of reducing releases of radioactive materials in liquid and gaseous effluents to "as lcw as is reasonably achievable" levels in accordance with the require-I ments of 10 CFR Part 50.34a, and therefore, are acceptable.
L The staff has performed an independent evaluation of the radwaste systems installed '.' Dresden Unit Nos.1, 2, and 3.
This evaluation has shown that the installed systems are capable of maintaining releases of radioactive materials in liquid and gaseous effluents during normal operation including anticipated cperational occurrences such that the individual doses will not exceed' numerical dose design objectives of Section II. A,11.8, and II.C of Appendix I to 10 CFR Part 50.
In addition, the staff's evaluation has shown that the radwaste systems satisfy the design objectives set forth in RM-50-2 and, therefore, satisfies the requirements of Section 11.0 of Appendix I to 10 CFR Part 50.
[',.'.c The staff concludes, based on the consid'erations discussed above, that:
(1) because the revised Technical Specifications do not involve a signi-ficant increase in the probability of consequences of accidents previously considered, and does not involve a significant hazard consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defence and security or to the health and safety of the public.
II. Environmental Imoact Appraisal The licensee is presently licensed to possess and operate the Dresden Nuclear Power Station, Unit Nos.1, 2, and 3, located in the State of Illinois, in Grurdy County, at power levels up to 700 megawatts thermal (MWt) for Unit No. I and up to 2527 megawatts thermal (MWt) for Unit Nos. 2 and 3.
The proposed changes to the liquid and gaseous release limits will l
not result in an increase or decrease in the power level of the units.
Since neither power level nor fuel burnup is affected by the action, it does not affect the benefits of electric power production considered for th,e captioned facility in The Commission's Final Environmental State-ment (FES) for Dresden Nuclear Power Station, Unit Nos. 2, and 3, Docket Nos. 50-237/249.
The revised liquid and gaseous effluent limits will not significantly change the total quantities or types of radioactivity discharged to the environment from Dresden Station, Unit Nos.1, 2, and 3.
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The revised Technical Soecifications implement the rea'iirements of Appendix I t=
to 10 CFR Part 50 and provide reasonable assurance that releases of radioactive materials in liquid and gaseous effluents will be "as low as is reasonably achievable."
If the plant exceeds one-half the design objectives in a quarter, the licensee must:
(1) identify the cases, (2) initiate a program to reduce the releases; and (3) report these actions to the NRC.
The revised Technical Specifications specify that the annual average release be maintained at less than twice the design objective quantities set forth in Sections II. A, II.8, and II.C of Appendix I.
Conclusion and Basis for Negative Declaration r1 On the basis of the foregcing evaluation, it is concluded that there would be no significant environmental impact attributable to the proposed action.
Having I
made this conclusion, the Commission has further concluded that no environmental r-impact statement for the proposed action need be prepared and that a negative l
declaration to this effect is appropriate.
Dated:
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--8 rr REFERENCES _
l.
Title 10', CFR Part 50, Appendix I.
Federal Register, Y. 40, p.19442, itay 5,1975.
O 2.
Title 10, CFR Part 50, Amendment to Paragraph II.D of Appendix I, Federal Register, V. 40, p. 40816, September 4,1975, and revised as of January 1,1976.
3.
U. S. Atomic Energy Commission Concluding Statement of Position of the Regulatory Staff (and its Attachment) - Public Rulemaking Hearing on: Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criteria "As Low As Is Reasonably Achievable" for Radioactive I aterial in Light-Water-Cooled fluclear Power Reactors, Docket No. RM-50-2, Washington, D.C., February 20, 1974.
I 4.
"Information Relevant to Keeping-Levels of Radioactivity in Effluents To Unrestricted Areas As low As Is Reasonably Achievable," Dresden Station, Unit No.1, June 4,1976, Commonwealth Edison Company.
5.
"Information Relevant to Keeping Levels of Radioactivity in Effluents To Unrestricted Areas As Low As Is Feasonably Achievable," Dresden Station, Unit Hos. 2 and 3, June 4.1976, Commonwealth Edison Company.
j-6.
" Amendment 1 to Dresden Station, Unit No.1, Appendix I Report,"
November 12, 1976, Commonwealth Edison Company.
7.
"A.mendment 1 to Dresden Station, Unit Nos. 2 and 3, Appendix I Report,"
l November 12, 1976, Commonwealth Edison Company.
8.
Dresden Nuclear Power Station, Unit Hos. 2 and 3, " Final Safety Analysis Report," November 1968, Commonwealth Edison Company.
9.
Staff of the U. S. Atomic Energy Commission, " Safety Evaluation in the Ma tter of Dresden Nuclear Power Station, Unit No.
2," Docket No.
50-237, Washington, D. C., October 1969.
- 10. Staff of the U. S. Atomic Energy Commission, " Safety Evaluation in the Matter of Dresden 11uclear Power Station, Unit No.
3," Docket No.
50-249, Washington, D. C., November 1970
- 11. 'Staf f of the U. S. Nuclear Regulatory Commission, " Final Environmental Statement Related to the Operation of Dresden Nuclear Power Station,"
Co=onwealth Edison Company, Docket Nos. 50-237/249, Washington, D. C.,
November 1972.
- 12. NUREG-0016, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWR-GALE Code),"
April 1976.
b
. 13. Sagendorf,'J. F. and Goll, J. T.,1976:
X0000Q, Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, (DRAFT).
U. S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washiiigton, D.C.
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14.
Staff of the U. S. Nuclear Regulatory Commission, Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," March 1976.
15.
Staf f of the U. S. Nuclear Regulatory Commission, Regulatory Guide 1.109, " Calculation of Annual Average Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Implementing Appendix I," March 1976.
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UNITED STATES NUCLEAR RFGULATORY" COMMISSION DOCKET NOS. 50-010/237/249 COMMONWEALTH EDISON COMPANY NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY CPERATING LICENSES AND NEGATIVE DECLARATION The U.S. Nuclear Regulatory Commission (the Commission) has issued Amendment No.
to Facility Operating License No. DPR-2, Amendment No.
to Facility Operating License No. DPR-19, and Amendment No, to Facility Operating License No. DPR-25, issued to Commonwealth Edison Company, #or revised Technical Specifications for operation of the Dresden Nuclear Powar Station, Unit Hos.1, 2, and 3, located in Goose Lake Township, Groundy County, Illinois. The amendments are effective as of the date of issuance.
This amendment to the Technical Specifications will (1) implement the requirements of Appendix I to 10 CFR Part 50, (2) establish new limiting conditions for operation (LCO) for the quarterly and annual average release rates, and (3) revise environmental monitoring programs to assure conformance with Commission regulation..
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.
The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment. Prior
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public notice of this amendment was not required since the amendment does not involve a significant hazard consideration.
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The Commission has prepared an environmental impact appraisal for the revised Technical Specifications and has concluded that an environ-mental impact statement for the particular action is not warranted because there will be no significant effect on the quality of the human environment beyond that which has already been predicted and described in the Commission's Final Environmental Statement for the facility dated November,1973.
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For further details with respect to this action, see (1) the application far amendments dated
, (2) Amendment Nos.
to License Hos.
DPR-21, DPR-19, and DPR-25, and (3) the Commission's related Safety Evalua-t' tion and Environmental Impact Appraisal. All of these items are available I
for public inspection at the Commission's Public Document Room,1717 H Street, j
H. W., Washington, D. C., and at the Morris Public Library, Morris, Illinois s+,ea 60451. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.
- 20555, Attention: Director, Division of Operating Reactors.
Dated at Bethesda, Maryland this day of FOR THE NUCLEAR REGULATORY COMMISSION Don K. Davis, Acting Chief Operating Reactors Branch #2 Division of Operating Reactors l -
TABLE 1 CALCULATED RELEASES OF R.C._JACTIVE MATERIALS IN LIQUID EFFLUENTS FROM DRESDEN STATION, UNIT NO.1 Nuclido Ci/yr Nuclide Ci/yr Corrosion 6 Activation Products Fission Products C
Na-24 8.3(-3)a, b Zr-95 2 (-5)
P-32
_6.8(-4)
Nb-95 3(-5)
Cr-51 1.8 (-2)
Nb-98 2 (-5) eb-54
- 1. 2 (-3)
Mo-99 5.1 (-3)
Mn-56 3(-3)
Tc-99m 9.4 (-3)
- 3. 7 (-3)
Ru-103 2.1(-4)
Fe-59 1.1 (-4)
Rh-103m 7 (-5)
Co-58 4.7(-3)
Ru-105
- 3. 2 (-4)
Co-60 1(-2)
Rh-105m 3.3 (-4) 2(-5)
Rh-105 2.7 (-4)
Ni-65 Cu-64 2.3(-2)
Ru-106 2.4 (-3) 2n-65 7.3(-4)
Rh-106 1(-5) 2n-69m '
1.7(-3)
Ag-110m 4.4 (-4) 2n-69 1.8(-3)
Te-129m 1.4 (-4)
Zr-95 1.4 (-3)
Te-129 9 (-5).
l-Nb-95 2(-3)
Te-131m 1.7 (-4) h W-187 4.3(-4)
Te-131 3 (-5)
Np-239 1.7(-2)
- 2. 8 (-2) e-3(-5)
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Fission Products I-133 2.6(-3) l Br-83 2.8(-4) 1-133 4.7(-2)
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Sr-89 3.6(-4)
I-134 4.7(-4)
Sr-90 2(-5)
Cs-134 1.4 (-2)
Sr-91 2.1(-3)
I-135
- 1. 2 (-2)
Y-91m 1.4 (-3)
Cs-136 6.7(-4)
Y-91 2(-4)
Cs-137 2.7(-2)
Sr-92 6.7(-4)
Ba-137m 2.4 (-3)
Y-92 1.8(-3)
Cs-138 7 (-5)
Y-93
- 2. 3 (-3)
Ba-139 1.5 (-4)
Ba-140 1.4 (-3) 9 e
..._____________.i TABLE 1 (continued CALCULATED RELEASES OF P.ADI0 ACTIVE MATERIALS IN LIQUID EFFLUENTS FROM DRESDEN STATION, UNIT NO.1 (CONTINUED)
Nuclide Ci/yr Fission Products (continued)
La-140 5.1(-4)
La-141 6(-5)
Ce-141 1.1(-4)
La-142 1.1 (-4)
Ce-143 5 (-5)
Pr-143 1.4 (-4)
Ce-144 5.2(-3) f Pr-144 1(-5)
All Others 4 (-5)
Total (except H-3) 2.7(-1) t
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-3 a - Exponential notation; 8.3(-3) = 8.3 x 10 l-b - Nuclides whose release rates are less than 10~ Ci/yr.
are not listed' individually, but are included in the i
f category "All Others".
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CALCULATED RELEASES OF RADIOACTIVE MATERIALS IN LIQUID EFFLUENTS FROM DRESDEN STATION, UNIT NOS 2 AND 3 Nuclide Ci/yr/ reactor Nuclide Ci/vr/ reactor Corrosion'6 Activation Products Fission Products Na-24 3.6(-2)a, b T,c-9 9:a 3.6 (-2)
.P-32 2.2(-3)
Ru-103 2.3 (-4)
Cr-51 5.6(-2)
Rh 103m
- 2. 3 (-4)
Mn-54 6.9(-4)
Ru-105 1.2 (-3)
Mn-56 7.1(-3)
R~h-105m 1.2 (-3)
Fe-55 1.2(-2)
Rh-105 1.5(-3)
Fe-59
- 3. 4 (-4)
Ru-106 3 (-5)
L; Co-53 2.3(-3)
Rh-106 3 (-5)
Co-60 4.6 (-3)
Ag-110m 1(-5)
Ni-63 1(-5)
Te-129m
- 4. 5 (-4)
Ni-65 4 (-5)
Te-129 2.9(-4)
Cu-64 1(-1)
Te-131m 6.6 (-4)
Zn-65 2.3 (-3)
Te-131 1.2(-4) 2n-69m 7.3(-3)
I-131 1(-1)
Zn-69
- 7. 8 (-3)
Te-132 9 (-5)
W-187 1.7(-3)
I-132 5.1(-3)
Np-239 6(-2)
I-133 2(-1)
Fission Products I-134 1(-4)
Br-83 5.8(-4)
Cs-134 3.5 (-3)
Sr-89 1.1(-3)
I-135 5(-2)
Sr-90 7(-5)
Cs-136
- 2. 2 (-3)
Y-90 1(-5)
Cs-137 8.1(-3)
Sr-91,
9.5(-3)
Ba-137m 7.6(-3)
Y-91m 6.1(-3)
Ba-139 1.3(-4)
Y-91
- 6. 6 (-4)
Ba-140 4.4 (-3)
Sr-92 1.6 (-3)
La-140 1.4 (-3)
Y-92 7.5(-3)
La-141 2.7 (-4)
Y-93 1(-2)
Ce-141
- 3. 6 (-3)
Zr-95 8 (-5)
La-142 1.2 (-4)
Nb-95 S(-5)
Ce-143 2.1(-4) ht-97 2(-5)
Pr-143
- 4. 5(-4)
- 1. 8 (-2)
Ce-144 3(-5)
ITABLE 2 (Continued)
Nuclide Ci/yr Fission Products Pr-144 3(-5)
All Others 1(-5) tal
- 7. 8 (-1)
(except H-3)
H-3 32 a = Exponential notation, 3.6 (-2) = 3.6 x 10'
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b = Nuclides whose release rates are less than 10 Ci/yr are not listed individually, but are included in the category "All Others".
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lABLE 3 CALCULATED RELEASES OF RADIOACTIVE MATERIAL IN GASEOUS EFFLUENTS FROM DRESDEN STATION, UNIT NO. 1
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Ci/yr
~
Mechanical Radio-Reactor Auxiliary Turbine Air Radwaste Gland Vacuum Nuclide Building rnildinn Buildint Eiector Building Seal Pumo Total Kr-83n a
a a
a a
55 a
55 Kr-85m 3
3 68 2
a 96 a
170
?
Kr-85 a
a a
31 a
a a
31 Kr-87 3
3 130 a
a 330 a
470 Kr-88 3
3 230 a
a 330 a
570 i
Kr-89 a
a a
a a
1400 a
1400 Xe-131m a
a a
1 a
a a
1 Xe-133m a
a a
a a
5 a
5 i
Xe-133 66 66 250 23 10 130 2300 2800 Xe-135m 46 46 650 a
a 39 a
780 I
Xe-135 34 3 81 630 a
45 37 0 350 1500 Xe-137 a
a a
a a
1700 a
1700 Xe-138 7
7 1400 a
a 1300 a
2700
~
Total Noble Gases 12,000 I-131 1.7(-1)D 1.7(-1) 1.4(-1) a 5(-2) 6.1(-2) 3(-2) 6.7(-1)
I-133 6.8(-1) 6.8(-1) 7.6(-1) a 1.8(-1) 2.1(-1) a 2.5 Cr-51 3( 10 3( 11) 1.3(-2) c 9(-3) e c
2.3(-2)
Mn-54 3(-3) 3(-3) 6( 11) c 3(-2) e c
3 7(-2)
Fe-59 4(-4) 11 ( 11 )
5( 11) c 1.5(-2) e e
1.6(-2)
~
co-58 6(-4) 6( fi) 6(-4) c 4.5(-3) e c
6.3(-3)
Co-60 1(-2) 1(-2) 2(-3) c 9(-2) e c
1.1(-1)
Zn-65 2(-3) 2(-3) 2C-4) c 1.5(-3) e c
5.7(-3)
Sr-89 9(-5) 9(-5) 6(-3) e 4.5(-4) e c
6.6(-3)
Sr-90 5(-6) 5(-6) 2(-5) c 3(-4) e c
3.3(-4) t Zr-95 11 ( 11 )
2i ( 11 )
2(-5) c 5(-5) e c
9.5( !!)
sb-124 2( 11) 2(-4) 1( 11) c 5(-5) e c
7.5(-4)
Cs-134 4(-3) 21(-3) 3(-4) c 4.5(-3) e c
1.3(-2) i Cs-136 3( 11) 3( 11) 5(-5) e 4.5( 21) e c
1.1(-3)
Cs-137 5.5(-3) 5.5(-3) 6(-4) c 9(-3) e c
2.1(-2)
Ba-140 4(-4) 4(-4) 1.1(-2) c 1 ( 11 )
e c
1.2(-2)
Ce-141 1(-4) 1(-4) 6(-4 c
2.6(-3) e c
3.11(-3)
Ar 211 25 25 25 C-14 9.5 H-3 8
8 16 Hj
.g
._...; =.....
Footnotds for Table 3:
a = less than 1.0 C1/yr/ reactor for noble gases and carbon-14, less than 10-4 Ci/yr/ reactor for iodine.
b = exponential notation; 1.7(-1) = 1.7 x 10-I c = less than 1% of total for this nuclide e
t e
er e
(;
TABLE 4 CALCULATED RELEASES OF RADIOACTIVE, MATERIAL IN GASE0US EFFLUENTS FROM DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3 Ci/yr/ reactor Mechanical Radio-Reactor Auxiliary Turbine Air Radwaste Gland Vacuum Nuclide Building Building Building Ejector Building Seal Pump Total Kr-83n a
a a
a a
23 a
23 Kr-85a 3
3 68 89 a
41 a
200 Kr-85 a
a a
190 a
a a
190 Kr-87 3
3 130 a
a 140 a
280 Kr-88 3
3 230 8
a 140 a
380 Kr-89 a
a a
a a
580 a
580 Xe-131m a
a a
30 a
a a
30 Xc-133m a
a a
a a
2 a
2 Xe-133 66 66 250 2300 10 55 2300 3000 Xe-135m 46 46 650 a
a 16 a
760 Xc-135 34 34 630 a
45 150 350 1200 Xe-137 a
a a
a a
710 a
710 Xe-133 7
7 1400 a
a 550 a
2000 Total Noble Gases 11000 I-131
- 1. 7 (-1)b 1,7(_1)
- 1. 9 (-1) a 5(-2)
- 1. 3 (-2) 3(-2) 6.2(-1) j
I-133
- 6. 8 (- 1) 6.8(-1) 7.6 (-1) a
- 1. 8 (-1) 4.7(-2) a 2.3 Cr-51 3(-4) 3 (-4) 1.3 (-2) c 9 (-5) e c
1.3(-2)
Mn-54 3(-3) 3 (-3) 6(-4) c 3 (-4) e c
9'. 6 (-4)
Fe-59 4 (-4) 4(-4) 5(-4) c 1.5(-4) e c
6.6(-4)
Co-58 6(-4) 6(-4) 6(-4) c
- 4. 5 (-5) c
'c 6.6(-4)
Co-60 1(-2) 1(-2) 2 (-3) c 9 (-4) e c
3.1 (-3)
Zn-65 2 (-3) 2 (-3) 2 (-4) c 1.5(-5) e c
2.5 (-4)
Sr-S9 9 (-5) 9(-5) 6 (-3) c
- 4. 5 (-6) e c
6(-3)
Sr-90 5 (-6) 5 (-6) 2 (-5) c 3(-6) c c
2.3(-5)
Zr-95 4 (-4) 4 (-4) 1(-4) c 5 (-7) e c
1.1(-4)
Sb-124 2(-4) 2 (-4) 3 (-4) c 5(-7) e c
3 (-4) -
Cs-134 4 (-3) 4 (-3) 3 (-4) c 4.5 (-5) e c
4.3(-4)
Cs-136 3(-4) 3 (-4) 5(-5) c 4.5(-6) c c
6.2 (-5)
Cs-137 5.5 (-3)
- 5. 5 (-3) 6(-4) c 9 (-5) c c
8.1(-4)
Ba-140 4 (-4) 4 (-4) 1.1(-2) c c
c c
1.1(-2)
Ce-141 1(-4) 1(-4) 6(-4) c
- 2. 5 (-6) e c
6.3 (-4)
Ar-41
32 a - less than 1.0 Ci/yr/ reactor for noble gases and carbon-14, 1ess than 10-4 Ci/yr/ reactor for iodine.
-1 b - exponential notation; 1.7(-1) = 1.7 x 10 c - less than 1% of total for this nuclide d - radionuclides not listed are released in quantities less than those specified in notes a and c from all sources E
([.
-z TABLE 5 PRINCIPAL PARAMETERS AND CONDITIONS USED IN CALCULATING RELEASES OF RADIOACTIVE MATERIAL IN LIQUID AND GASEOUS EFFLUENTS FROM DRESDEN NUCLEAR POWER STATION, UNIT NO. 1 Reactor Power Level (MWt) 700 Plant Capacity Factor 0.80 Offgas Release Rate Noble Gases, Ci/sec After 30-min. Decay 60,000 Iodine-131, Ci/yr, Downstream of Main Condenser Air Ejectors 5
Primary Coolant System 3
Mass of Coolant in Reactor Vessel (1bs) 4.2 x 10 4 Mass of Steam in Reactor Vessel (1bs) 1.7 x 10 4
Cleanup Demineralizer Flow (1bs/hr) 4 x 106 Steam Flow Rate (Ibs/hr) 1.6 x 10 6 Condensate Demineralizer Flow (Ibs/hr) 1.6 x 10 Number of Main Condenser Shells 1
Air Inleakage to Main Condenser, cfm/shell 10 t
Gaseous Waste Holdup Times Krypton (days) 2.3 1
Xenon (days) 4.8 i
Gland Seal Vent (hrs) 0.033 Decontamination Factors (DF)
I Cs, Rb Other Nuclides 2
2 Equipment Drain System 10 10 10 S
Floor Drain System 10 105 10 ep
...<g.-.
.4..
. -. ~.....
~..
=
(-
TABLE 6 j PRINCIPAL PARAMETERS AND CONDITIONS USED IN CALCULATING RELEASES OF RADIOACTIVE MAE RIAL IN LIQUID AND GASECUS EFFLUENTS FROM DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3l Reactor Power Level (Ef t) 2527l Plant Capacity Factor 0.80 f
Offgas Release Rate Noble Gases, Ci/see After 30-min. Decay 60,000 Iodine-131, Ci/yr, Downstream of Main Condenser Air Ejectors 5
Primary Coolant System 1
Mass of Coolant in Reactor Vessel (Ibs)
.1.7x10fy.
Mass of Steam in Reactor Vessel (1bs)
I!6jx 10 3 5
Cleanup Demineralizer Flow (1bs*/hr) 3".2 x 10 6 Steam Flow Rate (Ibs/hr) 9.8lx 10 '
6 Cor.densate Demineralizer Flow (1bs/hr) 9.8l x 10 j.-
Number of Main Condenser Shells 1
i i
Air Inleakage to Main Condenser, efm/shell 10 Gaseous Waste Holdup Times ~
j, Krypton (days) 1.6 Xenon (days) 27 Gland Seal Vent (hrs) 0.03 Decontamination Factors (DF)
I
Cs, Rb
'Other Nuclides 2
2 Equipment Drain System 10 10
-10 5
Floor DrainsSystem 10 105 10 9
4
-_e
= =.
. =,...
TABLE 7 DRESDEN NUCLEAR POWER STATION, UNIT NO. 1 DOCKET NO.50-010 a
a a
Liquid Effluent Release Data 1974 1975 1976 (Ci/yr)
Radioactive Waste Total Fission and Activation Products 2.9 8.4(-1) 3.5(-1)b F
Total Tritium 19 2.7(-1) 2.4(-2)
Gaseous Effluent Release Data (Ci/yr)
Radioactive Waste Total Noble Gases 9.8 3.2(+5) 4.6(+5)
Total Iodine-131 4.l(-1) 6(-1) 3.7(-1)
Total Tritium (c) 34 61 a - From data in the Semi-Annual Operating Reports, Docket No.50-010, 1974,1975, and 1976, Commonwealth Edison Company.
b - Exponential notation; 3.5(-1) = 3.5 x 10-I c - Not available
!~
i
. i.
TABLE 8 DRE'SOEN NUCLEAR POWER STATION, UNIT NOS. 1, 2, AND 3 DOCKET N0. 50-237/249 a
a 0
Liauid Effluent Releasa Data 1974 1975 1976 (C1/yr/ reactor)
Radioactive Waste Total Fission and Activation Products 15 4.l(-1) 6.l(-1)b Total Tritium 11 27 9.9 Gaseous Effluent Release Data (Ci/yr/ reactor)
Radioactive Waste Total Hoble Gases 3.2(+5) 3.7(+5) 1.6(+4)
Total Iodine-131 2
4.l(-1) 4.9(-1)
Total Tritium 57 110 69 a - From data in the Semi-Annual Operating Reports, Docket No. 50-237/249 1974,1975, and 1976, Commonwealth Edison Company, b - Exponential notation; 6.l(-1) = 6.1 x 10-I
1 I
TABLE 9 I
DRESDEN NUCLEAR POWER STATION, UNIT 1 j
RELATIVE C0t! CENTRATION (X/Q) AND DEPOSITION VALUES (D/Q) j USED FOR DOSE CALCULATIONS i
l Receptor Release X/Q D/0 Tyge Direction Direction / miles Type (sec/ meters )
(meters-2) 3 Site Boundary N
0.49 Plant Stack
-8
-9 (Continuous) 5.9 x 10 4.3 x 10 i
Radwaste Bldg.
'l (Continuous) 1.4 x 10-4 1.4 x 10-7 1
i Residence H
1.0 Plant Stack 5.5 x 10 l
-9 (Continuous) 3.2 x 10 i
Radwaste Bldg.
-5
-0
'i i
(Continuous) 2.8 x 10 2.7 x 10 Residence /
NE 1.5 Plant Stack
_7
_9 1
Garden (Continuous) 1.3 x 10 1.6 x 10 l
Radwaste Bldg.
-6
-9 (Continuous) 2.4 x 10 5.1 x 10 e
i e
I TABLE 10 h
i DRESDEllfl0 CLEAR POWER STAT 101, UNIT N05. 2 AND 3 i
RELATIVE C0ilCEllTRATI0il (X/Q) AtID DEPOSITION VALUES (D/Q) i USED FOR DOSE CALCULAT10iiS l
I f
Receptor Release X/Q D/Q M
Direction Direction / miles Type (sec/reters )
(meters-2) l 3
Site Boundary 0.48 P1 ant Stack
-8
-9 j
(Continuous) 2.1 x 10 4.3 x 10 i
Radwaste Bldg.
-7
-8 i
(Continuous) 7.4 x 10 2.0 x 10 Residence il 1.0 Plant Stack i
-0 (Continuous) 8.6 x 10 3.4 x 10-i Radwaste Bldg.
l (Continuous) 1.5 x l'0 8.2 x 10'9
-6 8
O l
Residence /
NE 1.5 Plant Stack l
Garden (Continuous) 4.8 x l'0 1.0 x 10-9
-0 i
Radwaste Bldg.
2.2 x 10 I
-9 (Continuous) 4.4 x 10 I
I I
i t
i
-t j
l TABLE 11 i
COMPARISON OF DRESDEN UNIT N05.1, 2&3 WITil I
APPENDIX 1 TO 10 CFR PART 50, SECTIONS II.A, II.B. NID II.C (MAY 5,1975)a NID l
SECTION II.D, ANNEX (SEPTEMBER 4,1975)b l
t COLUMN 1 COLUWI 2 COLUWI 3 COLUWI 4 9
Calculated Calculated '
b Appendix l Annex Doses Doses a
c ifnit No.1 Units Nos. 2&3 1
Criterion Design Objectives Design Objectives Liquid Effluents Dose to total body from all pathways 3 mrem /yr/ unit 5 mrem /yr/ site 0.01 mrem /yr/ unit 0.02 mrem /yr/ unit
}
i Dose to any organ from all pathways 10 mrem /yr/ unit 5 mrem /yr/ site 0.1 mrem /yr/ unit 0.74 mrem /yr/ unit d
Noble Gas Effluents i
i Gama dose in air 10 mr d/yr/ unit 10 mrad /yr/ site 0.56 mrad /yr/ unit 0.46 mrad /yr/ unit Beta dose in air 20 mrad /yr/ unit 20 mrad /yr/ site 0.66 mrad /yr/ unit 0.20 mrad /yr/ unit Dose to total body of an individual 5 mrem /yr/ unit 5 mrem /yr/ site 0.37 mrem /yr/ unit 0.31 mrem /yr/ unit l
Dose to skin of an individual 15 mrem /yr/ unit 15 mrem /yr/ site 0.90 mrem /yr/ unit 0.30 mrem /yr/ unit l
Radiofodines and Other Radionuclides Released e
to the Atmosphere i
Dose to any organ from all pathways 15 mrem /yr/ unit 15 mrem /yr/ site 3.3 mrem /yr/ unit 0.31 mrem /yr/ unit aFederal Register, V.40, p. 19442, flay 5, 1975.
}
l bFederal' Register, V.40, p. 40816, September 4,1975.
Design objectives given on a site basis. Therefore, these design objectives apply to 3 units at the site.
l C
Limited to noble gases only.
i
," Carbon-14 and Tritium have been added to this category.
I i
i