ML20066L306
| ML20066L306 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/18/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066L315 | List: |
| References | |
| NUDOCS 8211300437 | |
| Download: ML20066L306 (7) | |
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UNITED STATES E'
NUCLEAR REGULATORY COMMISSION
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. DPR-32 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated October 6,1982, 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 in 10 CFR Chapter I; B.
The facility will operate in co'nformity with the application, the provisions of the 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 conducted in compliance with the Commission'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 of the Comission's regulations and all applicable requirements have been satisfied.
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[ C211300437 821118 '
PDR ADOCK 05000280 P
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Accordingly, the license is amended by chtriges to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. OPR-32 is herehy amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 81, 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.
F )R THE NUCL REGULATORY COMMISSION te
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Operating Reactors Il nch #1 Division of Licensin,
Attachment:
Changes to the Technical Specifications Date of Issuance: November 18, 1982 i
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[o n:. ?g UNITED STATES y
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated October 6,1982, 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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 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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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license snendment, and paragraph 3.8 of Facility Operating License No. OPR-37 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix l
A, as revised through Amendment No. 82, are hera5y incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendnent is effective as of the date of its issuance.
F0il THE NUCLEAR REGULATORY COMMISSION fh I
L-VKrs.a C f
even perating Reactors B anch #1 Division of Licensi g
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 18, 1982 l
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 81 TO FACILITY OPERATING LICENSE NO. OPR-32 AMENDMENT NO. 82 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages 3.11-3 3.11-3 3.11-5 3.11-5 S
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TS 3.11-3
%4 Above are met.
10.
The requirements of Specification 3.0.1 are not applicable.
B.
Caseous Wastes la.
The controlled release rates of gaseous wastes, excluding halogen i
and airborne particulates originating from station operation shall be limited as follows:
5
,3 1 2.0 x 10 g (Qi MPC)g see where Q, is the controlled release rate (curies per second) of any radiois6 tope i and (MPC) g, in units of microcuries per cubic centi-meter is defined in column 1. Table II of Appendix B to 10 CFR 20.
b.
With the release rate of gaseous vastes exceeding the above limit, without delay restore the release rate to within the limit.
c.
The provisions of specification 6.6.2.a are not applicable.
2.
The release rates of activity shall not exceed 16 percent of those specified in paragraph B.la above when averaged over any calendar l
quarter or 10 percent of those specified in paragraph B.la above when averaged over any 12 consecutive months.
3a.
The release rate limit of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days released from the site to the environs as part of the gaseous vastes shall be l
i such that 5
3 x 10 q y
I where Q = the measured release rate of the radioiodines and radioactive materials in particulate form with half-lives greater than eight days (Ci/sec).
b.
The average release rate per site of all radiciodines and radioactive materials in particulate form with half-lives greater i
j than eight days during any calendar quarter shall be such that I
5 13 [3 x 10 q) ig Amendment Nos. Si & 82
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TS 3.11-5 fuel in the containment.
- 11. The requirements of Specification 3.0.1 are not applicable.
Basis The releases of radioactive materials will be kept es low as practicable as required by 10 CFR 50 and will not exceed the concentration limits specified l
in 10 CFR 20. At the same time, the licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases in excess of four percent of the concentration limits specified in 10 CFR 20.
However, all releases must be kept within the concentration limits specified in 10 CFR 20.
It is ex-pected that using this operational flexibility under unusual operating conditions,,
the licensee shall exert every effort to keep levels of radioactive materials released from the plant as low as practicable and that annual releases will not exceed a small fraction of the annual average concentration limits #specifi.d in 10 CFR 20.
The limiting conditions for operatien contained in specification A-3 above.
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I which relates to the total number of curies which may be released in liquid I
1 l
effluents in any year, is based on the expected performance of the Surry Power Station assuming both units are operating with 0.25 percent leaking fuel and each unit is experiencing a 20 gallon per day primary to secondary system leak rate.
l The formulas and limits prescribed in specifications 3.11.B.1 and B.2 take atmospheric dilution into account and assures that at the point of, maximum ground concentration at the site beundary, the requirements of 10 CFR 20 vill not be exceeded. The limit is based on the highest annual average value of X/Q which will occur at the Amendment Nos. 81 & 82
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