ML20097A894

Environ Assessment & Finding of No Significant Impact Re Util 911220 Request for Exemption from 10CFR50,App J,Section III.D.2(a) & III.D.3 Re 2-yr Test Interval for Type B & Type C Component Testing

ML20097A894
Person / Time
Site:	Browns Ferry
Issue date:	05/28/1992
From:	Hebdon F Office of Nuclear Reactor Regulation
To:
Shared Package
ML20097A895	List: ML20097A894
References
NUDOCS 9206030247
Download: ML20097A894 (5)

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.c 7590-01 1

UNITED STATES NUCLEAR REGULATORY COMMISSION TENNESSEE VALLEY AUTHOR [Il BROWNS FERRY NUCLEAR PLANT, UNIT 2 QQCKET NO. 50-260 Edli;0NMENTAL ASSESSMENT AND FINDING OF NO SIQUlFICANT IMPACT The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an exemption from the requirements of Sections III.D.2(a) and III.D.3 of Appendix J to 10 CFR Part 50 to the Tennessee Valley Authority (the licensee) for the Browns Ferry Nuclear Plant, Unit 2.

The unit is located at the licensee's site in Limestone County, Alabama.

The exemption was regeested by the-licensee in its letter dated December 20, 1991.

ENVIRONMENTAL ASSESSMENT ldantification of Proposeg Actioni The_ proposed exemption would allow the licensee deviction from tha provisions of Sections Ill.D.2(a) and III.D.3 of Appendix J to 10 CFR Part 50 that require Type B and Type C component leak rate testing during refueling outages on an interval not to exceed two years.

In its letter of

. December 20, 1991,- the licensee requested an extension of the allowable test

interval for 87 components to permit realignment of the test program with the Browns Ferry Nuclear, Plant, Unit 2 refueling cutage schedule. The letter stated this outage will begin no later than-January 29, 1993. The required extension is no more than 177 days for any single component.

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Ihe..Need for the Proposed Actj.nn:

The proposed exemption is required to permit the licensee to avoid ar otherwise unnecessary a.1d lengthy plant outage, The required testing is ordinarily performed during refueling outages.

Environmental _jmpacts of the Proogsed Actign:

The proposed exemption will not_ increase potential radiological environmental ef fects due to containment leakage beyond those already permitted by the regulations. Testing of Type B and Type C components under Appendix J tc 10 CFR Part 50 is intenced to demonstrate that contain-ment leakage from these components is within defined acceptable limits.

Thnse limits provide information used to calculate the maximum radiological consequences of a design-basis accident. Appendix J limits the combined leak rate for all penetrations and valves subject to Type B and C tests to less thtn 0.6 times the maximum allowable containment leakage r;te with the containment pressurized to its design limit (commonly termed "0.6 La").

The licensee states in its Decenber 20,'1991 letter that the most recent testing of the Type B and C components yielded leakane of 1 css than 17% of the Appendix J limit. When the projected component degradation is added, leakage at the end of the proposed extcnded interval is expected _ to te well within acceptable limits.

Therefore, the Commission concludes there would be no adverse radiological environmental impact: as a consequence of the proposed exemption oeyond that already permitted by the regulaticns.

With regard to potential non-radiological environmental impact, the i

proposed exemption involves systems located within the restricted areas as defined-in 10 CFR Part 20. The exemption does not affect non-radiological l-l plant effluents and has no other environmental impact.

Therefore, the l

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- Commission concludes that there is no significant non-radiological environ-

- mental impact associated with the p.oposed exemption.

- Since it does not invol' e adverse radiological or other er.vironmental impacts, the Commission concludes the preposed exemption does not significantly change the conclusions of the~ licensee's " Final Environmental Statement, Browns Ferry Nuclear Plant Units 1, 2, and 3", dated September 1,.1972.

Alterm tive to the Proposqd Ac.1]_qn:

Because the staff has conchided that there is no significant environ-rnental impact associated with the proposed exemption, any alternative to the exemption will-have either no significantly different environmental impact, or greater environmental impact.

The principal alternative would be to deny the requested exemption.

l This denial would require an additional plant outage to perform testing.

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l Such an outage would result in additional occupational radiation dose to l

l piant' workers without a compensatory increase in public health and safety.

Therefore, this alternative is not decirable.

Alternative _jhe of Resourc31:

This action does not insolve the use of resources not previously considered in connection with the " Final Environmental Statement, Browns l

Ferry Nuclear Plant Units 1, 2, and 3",

dated September 1,1972.

b.gencies._ag Persgns Contacted:

The NRC staff has reviewed the licensee's request dated December 20, 1991, that supports the proposed exemption. The NRC staff did not consult other agencias or persons.

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4 LINDING OF N0__SIGNIF RANT 1& ACT The Commission has determined not to prepare an environtr. ental impact statement for the proposed exemption.

Based upon the foregoing environ-mental assessment, we conclude that the proposed action will not have a significant effect on the quality of the human environment.

For details with resper.t to this action, see the licensee's request for the exemption dated December 20, 1991, which is available for public inspection at the Commission's Public Document Rcom, Gelman Building, 2120 L Street,-N.W., Washingtcn DC, and at the Athens Public Library, South Street, Athens, Aiabama 35611.

Dated at Rockville, Maryland this 28th day of May J992.

FOR THL NUCLLAR REGULATORY COMMISSION

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n Frederick J. Hebdo#n, Director

-Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Reg'ilation

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i DJ1TRIBUTION 4DocketeFile.

NRC & Local PDRs S.-'Varga 14-E-1 G. Lainas 14-H-3 F. Hebdon-H. Sanders

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J. Williams T. Ross OGC E. Jordan

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OPA

.B. Wilson RII BFN Rdg. File c

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