ML19332E540
| ML19332E540 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, 05000000 |
| Issue date: | 11/28/1989 |
| From: | Jocelyn Craig Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19332E541 | List: |
| References | |
| NUDOCS 8912070349 | |
| Download: ML19332E540 (9) | |
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p ase UNITED STATES
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D. C. 20555 t-L
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 l
DRESDEN NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.109 License No. DPR-19 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Commonwealth Edison Company s
(the licensee) dated June 12 1989 complies with the standards andrequirementsoftheAtomIcEnergyActof1954,asamended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will o>erate in conformity with the application, the provisions of tie Act and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be I.
conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 1
of the Comission's regulations and all applicable requirements have been satisfied.
8912070349 891128
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. B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.122, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY C0lHISS10N t-D John W. Craig, Project Di or Project Directorate III-2 i
Division of Reactor Projects - III, i
IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: November 28, 1989 1
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ATTACHMENT TO LICENSE AMENDMENT H0.122 J
FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removing the page i
identified below and inserting the attached page. The revised page is i
identified by the captioned amendment number and contains marginal lines indicating the area of change.
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REMOVE INSERT i
3.8/4.8-22 3.8/4.8-22 l
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A
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QUAD-CITIES DPR-29 t
L BASES 3.8/4.8 Limiting Conditions for Operation and Surveillance Requirement Bases 3.8/4.8.A.1 GASEOUS EFFLUENTS - DOSE This specification is provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from the units on the site will be within the
' annual dose limits of 10 CFR Part 20 for unrestricted areas.
The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B Table II. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part s
20.106(b)).
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to 500 mrem / year to the total body or to not less than or equal to 3000 mrem / year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year.
For purposes of calculating doses resulting from airborne releases the main chimney is considered to be an elevated release point, and the reactor vent stack is considered to be a mixed mode release point.
3.8/4.8.A.2 DOSE, NOBLE GASES l
This specification is provided to implement the requirements of Sections II.B.
III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I.
The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.
The dose calculations established in the ODCM l
for calculating the doses due to the actual release rates of radioactive noble I
gases in gaseous effluents will be consistent with the methodology provided in l
Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods l
for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors", Revision 1, July 1977.
The i
ODCM equations provide for determining the air doses at the unrestricted boundary based upon the historical average atmospheric conditions.
NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.
3.8/4.8-22 Amendment No.122
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION g
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WA$HINGTON, D. C. 20555 COMMONWEALTH EDISON COMPANY l
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10WA-ILLIN015 GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION. L' NIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 118 License No. DPR-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
i A.
The application for amendment by Commonwealth Edison Company (thelicensee)datedJune 12, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E,
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-30 is here>y amended to read as follows:
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B.
Technical Specifications The Technical Specifications contained in Appendices A and 3, as revised through Amendment No.118, are hereby incorporated in the license. -The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION F
John W. Craig, Project Direc r Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 28, 1989 l
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ATTACHMENT TO LICENSE AMENDitENT N0.118 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 Revise the Appendix A Technical Specifications by removing the page identified below and inserting _the attached page. The revised page is identified by the captioned amendment number and contains margir.a1 lines indicating the area of change.
REMOVE INSERT l
3.8/4.8-15 3.8/4.8-15 i
i
QUAD-CITIES DPR-30 BASES 3.8/4.d.A.1 CASE 0VS EFFLUENTS - DOSE 1
This specification is provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from the units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas.
The annual dose l
limits are the doses associated with the concentrations of 10 CFR Part 20 Appendix B. Table II. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an Individual in an unrestricted area to annual average concentrations exceeding the i
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limits specified in Appendix B. Table II of 10 CFR Part 20 (10 CFR Part t
20.106(b)).
The specified release rate limits restrict, at all times, the j'
corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to 500 mrem / year to the total body or to not less than or equal to 3000 mrem / year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year.
For purposes of calculating doses resulting from airborne
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releases the main chimney is considered to be an elevated release point, and the reactor vent stack is considered to be a mixed mode release point.
3.8/4.8 A.2 DOSE. NOBLE GASES This specification is provided to implement the requirements of Sections II.B.
III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I.
The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix ! that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble
- gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods I
for Estimating Atmospheric Transport and Dispersion of Gaseouc Effluents in Routine Releases from Light-Water Cooled Reactors", Revision 1, July 1977.
The ODCM equations provide for determining the air doses at the unrestricted boundary based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.
13698 3.8/4.8-15 Amendment No.118 1
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NUCLEAR REGULATORY COMMISSION o
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION. UNIT 1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.122 License No. DPR-29 o
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
lie application for amendment by Commonwealth Edison Company (thelicensee)datedJune 12, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth 1:
in 10 CFR Chapter I; B.
The facility will o>erate in conformity with the application, the provisions of tie Act, and the rules and regulations of the Comission;
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C.
Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 1
E.
The issuance of :tzis amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-29 is hereby amended to read as follows:
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