ML20079Q735
| ML20079Q735 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/30/1983 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | ALABAMA POWER CO. |
| Shared Package | |
| ML20079Q741 | List: |
| References | |
| NUDOCS 8402010336 | |
| Download: ML20079Q735 (4) | |
Text
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7590-01 UNITED STATED NUCLEAR REGULATORY COMMISSION In the Matter of
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Docket Nos. 50-348
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and 50-364 ALABAMA POWER COMPANY
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(Joseph M. Farley Nuclear Plant
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Unit Nos. 1 and 2)
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EXEl1PTION I.
The Alabama Power Company -(the licensee) is the holder of Facility Operating License Nos. NPF-2 and NPF-8 which authorized operation of the Joseph M. Farley Nuclear Power Plant Unit Nos. 1 and 2.
These licenses provide, among other things, that they are subject to all rules, regulations and Orders of the Commission now or hereafter in effect.
The facility comprises two pres.surized water reactors at the licensee's site located near the City of Dothan, Alabama.
II.
On November 19, 1980, the Commission published a revised Section 10 CFR 50.48 and a new Appendix R to 10 CFR 50 regarding fire protection features of nuclear power plants (45 FR 76602).
The revised Section 50.48 and Appendix R became effective on February 17, 1981.
Section III of Appendix R contains fifteen subsections, lettered A through 0, each of which specifies requirenents for a particular aspect of the fire protection features at a nuclear power plant.
One of these fifteen subsections, III.G, is the subject of this exemption request.
8402010336 031230 PDR ADDCK 05000348 F
7550-01 Subsection III.G.2 of Appendix R requires that one train of cables and equipment necessary to achieve and maintain safe shutdown shall be maintained free of fire damage by specific use of fire barriers, separation or enclosures.
If these conditions are not met,Section III.G.3 requires an alternative shut-down capability independent of the fire area of concern.
III.
By letter dated June 18. 1982, the licensee requested an exemption from the technical requirements of Section III.G.2 of Appendix R to 10 CFR 50 to the extent that it requires specified fire protection measures for the protection of safe shutdown cables and equipment located inside con-tainment for both units.
In our evaluation of these exemptions, we stated that the licensee had not provided a fire hazards analysis which compared the level of safety provided by existing arrangements to that required by Appendix R to 10 CFR 50 and, therefore, recommended the denial'of these
. exemptions.
By letter dated July 27, 1982, the licensee provided additional information.
The licensee identified three systems that did rot meet the requirements of Section III.G inside containment for which exemptions were reauested.
These three systens are the pressurizer power operated relief valves and block valves, reactor vessel head vent valves and instrumentation for the pressurizer pressure and level indication.
The licensee revised the June 18, 1983 exemption request to cover only cables and components of these three systems inside the containment building for Uni-ts 1 and 2.
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7590-01..
IV.
The protection for redundant trains of safe shutdown equipment inside containment does not meet the technical requirements of Section III.G because twenty-feet of separation does not exist between redundant cables free of intervening combustibles.
Due to the specific ccnfigurations and locations of the cables and-components within the containment and due to the restricted access to these sub-areas during plant operations, an exposure fire involving the accumulation of significant quantities of transient combustible materials is unlikely.
Because the cables in these sub-areas inside containment are qualified to IEEE* Standard 383 and are routed in conduit, it is our opinion that a fire of sufficient magnitude to damage redundant cables or components is unlikely.
Based on our evaluation, the existing protection for the containment area of Units 1 and 2 provides a level of fire protection equivalent to the technical requirements of Section III.G of Appendix R.
Therefore, the exemption shculd be granted.
V.
Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12(a),
an exemption is authorized by law and will not endanger life or property or the common defense,and security and is otherwise in the public interest, are hereby grants an exemption from the requirements of Section III.G.2 of Appendix R to the extent that they apply to the specific systems in the Containment Building as described herein.
e 7590-01 The NRC staff has determined that the granting of this Exemption will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental inpact statement or negative declaration and environmental impact appraisal need not be prepared in connection with this action.
A copy of the Safety Evaluation ' dated December 30, 1983, related to this action is available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W. Washington, D.C. and at the local public document room located at the George S. Houston Memorial Library, 212 W. Burdeshaw Street, Dothan, Alabama.
copy may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.C.
20555, Attention:
Director, Division of Licensing.
This Exemption is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
\\M 4. M DarrellG.gisenhut, Director Division of' Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 30thday of December 1983
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