ML20004F879
| ML20004F879 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/12/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004F877 | List: |
| References | |
| NUDOCS 8106260096 | |
| Download: ML20004F879 (5) | |
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ga croy, UNITED STATES g 'f 3 #., y j NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555
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%~f MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMEN 0 MENT TO FACILITY OPERATING LICENSE Ament-a it 'No. 57 License No. OPR-36 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Maine Yankee Atomic Power Company (the licensee) dated May 22, 1981 complies with the stanaards and requirements of the Atcmic Energy Act of 19E4, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate ir; conformity with the application, the provisions of the Act, and the rules and regulatians 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 Comission's regulations; O.
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 Commission's regulations and all applicable requirements have been satisfied.
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8106260096
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.B(6)(b) of Facility Operating License No. DPR-36 is hereby amended to read as follows:
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(b) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 57, are hereby incorporated in the license.
The licensee snali operate the facility in accordance with the Technical Specifications.
3.
This license amendment was effective on May 22, 1981.
FUR THE NUCLEAR REGULATORY CCMMISSION YL4GdCEC[
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing Attachments:
Changes to the Technical Specifications Date of Issuance: June 12, 1981 a
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ATTACHMENT TO LICENSE AMENDMENT NO. 57 TO FACILITY OPERATING LICENSE NO. OPR-36 00CKET NO. 50-309 Revise Appendix A as folicws:
Remove Pages Insert Pages 3.17-3 3.17-3 3.17-6 3.17-6, I
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N During normal conditions of plant operation, radio-3.
a.
active gaseous waste from the hydrogenated waste gas system shall be provided a minimum average holdup of 60 days except for low radioactivity gaseous waste resulting from purge and fill operations associated with refueling and reactor startup.
b.
Holdup time less than that specified in B.3.a above shall be covered in the special effluent report to be included in tne semi-annual report required by Section 5.7.3. (1)(a) of these specifications.
c.
The maximum activity to be contained in one gas decay tank shall not exceed 88,400 curies of Xe-133 equivalent.
4.
During the first indication of primary-to-secondary leakage, concurrent with sufficient fuel defects, a determination of the iodine partition factor for the blowdown tank shall be made.
5.
During power operation, the condenser air ejector discharge shall be continuously monitored for gross radiogas activity.
Whenever this monitor is inoperable, grab samples shall be taken from the air ejector discharge and analyzed for gross radiogas activity daily.
6.
Gaies discharged through the stack shall be continuously monitored for gross noble gas and particulate activity. When-ever either of these monitors is inoperable, appropriate grab samples shall be taken and analyzed daily.
7.
Purging of the reactor building ; hall be. governed by the following conditions:
a.
Reactor building purge shall be filtered through the high efficiency particulate air filters and charcoal absorbers whenever the concentration of iodine and particulate isotopes exceeds the occupational MFC inside the reactor building.
b.
Reactor building purge shall be filtered through the high efficiency particulate air filters and charcoal absorbers whenever irradiated fuel is being handled or any object is being handled over irradiated fuel in the reactor building.
Exceorion: The requitements of Par. 7b above shall not apply from May 22, 1981 until either completion of the LPSI cneck valve installation ordered April 20, 1981 or completion of operations involving irradiated fuel handling or handling of any object over irradiated fuel during the cycle 5/6 refueling, whichever is earlier. When refueling operations are conducted under this exception, the containment purge valves shall be trippable manually and automatically.
Amend =ent No. 19, 57 3.17-3
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1Due quantity-and isotopic proportions of radioactive gases released into the reactor coolant system is dependent upon
- several factors including fuel leakage, burnuo and power level.
Changes in power level will affect gaseous generation races temporarily. Gases are released from the reactor coolantito the gaseous waste system during desassifier treatacar of the lecdown.and leakage water. and also during venting of the system.
This venting may occasionally _ be performed to degas the system and so control plant chemistry and/or' reduce coolant radio-active gas concentrations to an acceptable value-for the 4
protection of plant personnel.
Gaseous waste holdup and decay occurs while it is retained in the reactor coolant system and in the surge drum of the gaseous creatment system. The gaseous waste holdup drums are of sufficient capacity to provide an additional average recen-tion period of 60 days during normal operating conditions.
The low as practicable gaseous release objectives expressed in this Specification are based on the guidelines contrined in the proposed Appendix I of 10 CFR 50.
Since these g2ide-lines have not been adopted as yet, ;he release objectives of this Specification will be reviewed at the time Appendix I becomes a regulation to assure that this Specification is based upon the guidelines contained therein.
t" Basis: The exception to Par.'3.17.B.7.b allows installation of additional LPSI check va'lves reducing the probability of event V LOCA to -
proceed without extending unnecessarily the cycle 5/6 refueling outage.
Due to the extended time period between reactor shutdown and the j_
present there has been considerable decay of the ra 'ioactive fission j
products in the fuel. An analysis of a refueling acci/ int inside j
containment shows the doses would be appropriately within the guidelines of 10 CFR 100 (specifically in this case on the order of 100 rem thyroid) taking no credit for either filtration or -
containment isolation.
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T Amendment No. 57 3.17-6 1
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