ML20010E411
| ML20010E411 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png (DPR-61-A-040, DPR-61-A-40) |
| Issue date: | 08/26/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20010E408 | List: |
| References | |
| NUDOCS 8109040092 | |
| Download: ML20010E411 (5) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION n
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CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. DPR-61 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Connecticut Yankee Atomic Power Company (the licensee) dated July 16, 1980, as amended October 16, 1980, 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 Commission; 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 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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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8109040092 810826 PDR ADOCK 05000213 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 40, 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.
FOR THE NUCLEAR REGULATORY COMMISSION y
ennis
. Crutch ie hie Operating Reactors Bra ch #5 Division of Licensing -
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 26, 1981 l
r ATTACHMENT TO LICENSE AMENDMENT NO. 40 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following pages of Appendix B (Environmental) Technical Specifications with the enclosed pages. The revised pages reflect the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 2.4-5 2.4-5 2.4-9 2.4-9 i
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Specificat' on 2.4.1.6 requires that the licensee maintain and operate i
the equipment installed in the liquid waste syst' ens to reduce the release of radioactive materials in liquid effluenta to e' low as practicable consistent with the requirements of 10 C?R Parc 50.36a.
Normal use and maintenance of installed equipment in the liquid waste system provides reasonable ~ assurance that the quantity released will not exceed the design objective. In order to keep releases of radio-active materials as low as practicable, the specification requires operation of equipment whenever it appears that the projected cumulative discharge rate will exceed one-fourth of this design objective annual quantity during any enlendar quart er.
Specification 2.4.1.7 limits the amount of radioactive material'that could be inadvertently released to the environment to an amount that will not exceed the Technical Specification limit.
In addition to limiting conditions for operation listed under Specifications 2.4.1.2 and 2.4.1.3, the reporting requirements of Specification 2.4.1.8 delineate that the licensee shall identify the cause whenever the cumulative release of radioactive materials in liquid waste e'ffluents exceeds one-half the design objective annual quantity during any calendar quarter and describe the pro-posed program of action co reduce such releases to design objective levels on timely basis. This report must be filed within 30 days following the calendar quarter in which the release occurred.
The sampling and monitoring requirements given under Specification 2.4.2 provide assurance that radioactive materials'ht liquid wastes are properly controlled and monitored in conformance with the requirements of Design Criteria 60 and 64. These requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive liquid wastes released to the environment. Reports on the quantities of' radio-active materials released in liquid waste effluents are furnished to the Commission according to Section 5.6.1 of these Technical Specifications in conformance with Regulatory Guide 1.21.
On the basis of such reports and any additional information the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.
The points of release to the environment to be monitored in Section 2.4.2 include all the monitored release points as provided for in Table 2.4-3.
2.4.3 Specifications for Gaseous Waste Effluents t
2.4.3.1 (1) The release rate limit of noble gases from the site shall be:
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2.4-5 Amendment No. 40 m.
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These specifications provide reasonable assu'rance that the re-sulting annual air dose from the site due to gamma radiation will not exceed 10 mrad, and uan annual air dose from the site due to beta radiation will not axceed 20 mrad from noble gases, and that the annual dose to any organ of an individual from iodines and particulates will not exceed 15 mrem per site. At the same time these specifications permit the ficxibility of operation, compatible with considerations of health and safety, to assure that the public is provided with a dependable source of power under unusual operating conditions which may tempora-rily result in releases higher than the design objective levels but still within the concentration limits specified ir 10 CFR Part 20.
It is expected that using this operational ficxibi-
. lity under unusual operating conditions, and by exerting every
' effort to keep levels of radioactive material in gaseous vaste effluents as low as practicable, the annual releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20. These efforts should include consideration of meteorological conditions during releases.
There is a reduction factor of 1220 by which the maximum per-missible concentration of radioactive iodine in air should be reduced to allow for the grass-goat-milk pathway.
(The factor is 243 for the grass-cow-milk pathway). This factor has been derived for radioactive iodine, taking into account the milk pathway. It has been applied to radionuclides of iodine and to all radionuclides in particulate form with a half-life greater than eight days. The factor is not appropriate for iodine where milk is not a pathway of exposure or for the other radionuclides.
i The design objectives have been developed based on operating experience taking into account a combination of system' vari-ables including defective fuel, primary system leakage, pri-mary to secondary system leakage, steam generator blowdown and the performance of the various vaste treatment systems.
For Specification 2.4.3.1(1) dose calculations have been made for the critical sector. These calculations consider site meteorology, ' buoyancy characteristics, and radionuclide content of the effluent of each unit. Meteorological calculations for offsite locations were performed, and the most critical one was selected to set the release rate. The controlling dis'tance is 510 meters to the NNW and the calculated X/Q is 1.4 x 10-5 sec/m3, The gamma dose contribution was determined using Equation 7.63 in Section 7-5.2.5 of Meteorology'and Atomic Energy - 1968.
The releases from vents are considered to be ground level re-leases which could result in a beta dose from cloud submersion.
2.4-9 Amendment No. 40
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