ML20080R878
| ML20080R878 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/21/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080R882 | List: |
| References | |
| NUDOCS 9503100123 | |
| Download: ML20080R878 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMISSION PUBLIC SERVICE ELECTRIC AND GAS COMPANY DOCKET NOS. 50-272 AND 50-311 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMEA_GI The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance'of amendments to Facility Operating License Nos. DPR-70 and DPR-75, issued to Public Service Electric and Gas Company, et al. (PSE&G or the licensee) for operation of Salem Nuclear Generating Station (SNGS), Units 1 and 2, located in Salem County, New Jersey.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
By letter dated April 16,1993 (NLR-N83042), PSE&G requested a license amendment to reflect changes to the Updated Final Safety Analysis Report
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(UFSAR) for Salem, Units 1 and 2.
The proposed UFSAR change would add an exception to a general statement in the containment isolation system description.
The general statement is that automatic containment isolation valves that receive signals to close, fail closed on loss of air or power.
The proposed exception would apply to the outboard isolation valves for the control air system. These four valves (11,12, 21, ai,d 22CA330, collectively identified as CA-330) fail closed on loss of air but fail as-is upon loss of the vital 12S VDC power supply to their solenoid control valves.
Need for Proposed Action:
The revision of the licensing basis is needed to exempt the CA-330 valves from the general statement in the UFSAR that automatic containment 9503100123 950221
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.1 isolation valves that receive signals to close,. fail closed on loss of air'or lq power. The staff has examined the design of the isolation system for the l
control air header piping penetration. With the exception of the failure.
position for valve CA-330 on loss of its 125 VDC power supply, the design meets all applicable criteria.. Failure of the 125 VDC power supply results in l
a slight degradation in containment isolation reliability. Unon failure of the 125 VDC power supply, the valve will remain in the "as is" position.
i Since the valve is normally open, this means that the valve will stty open and will not close on an isolation signal or loss of air header pressure.
For all
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other single failures, the valve will automatically close upon either loss of air or an isolation signal.
Environmental Imoacts of the Pronosed Action:
The staff has evaluated the conditions for the "as-is" failure and finds that the reduction in safety margin due to this condition is acceptably small.
First of all, there is a check valve in series with the air-ope' rated valve so that containment integrity is maintained at all times. Secondly, the probability of loss of air pressure is quite low since the normal air supply 1
is backed up with a safety grade supply which is activated automatically upon.
sensing low air pressure. With an operable air supply, the penetration is not a containment leak path since the air pressure is greater than the peak calculated containment pressure.
The change will not increase the probability or consequences of l
accidents, no changes are being made in the types of any effluents that may be released offsite, and there is no significant increase in the allowabid individual or cumulative occupational radiation exposure. Accordingly, the
J, Commission concludes that there are no significant radiological environmental impacts associated with the proposed action.
With regard to potential nonradiological impacts, the proposed action does involve features located entirely within the restricted area as defined in 10 CFR Part 20.'
It does not affect nonradiological plant effluents and has no other environmental impact. Accordingly, the Commission concludes that there are no significant nonradiological environmental impacts associated with the proposed action.
1 Alternatives to the Proposed Action:
Since the Commission has concluded there is no measurable environmental impact associated with the proposed action, any alternatives with equal or greater environmental impact need not be evaluated. As an alternative to the proposed action, the staff considered denial of the proposed action. Denial of the application would result in no change in current environmental impacts.
The environmental impacts of the proposed action and the alternative action are similar.
Alternate Use of Resources:
This action does not involve the use of any resources not previously considered in the Final Environmental Statement for the Salen Nuclear Generating Station, Units 1 and 2, dated April 1973.
Aaencies and Person Contacted:
In accordance with its stated policy, the staff consulted with the New Jersey State official regarding the environmental impact of the proposed action. The State official had no comments.
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H FINDING OF NO SIGNIFICANT IMPACT-Based upon the environmental assessment, the Commission concludes that
- the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the Commission has determined not to prepare
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an environmental impact statement for the proposed action.
1 For further details with respect to the proposed action, see the application for license amendments dated April 16, 1993, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, and the local public document room located at the Salem Free Public Library,112 West Broadway, Salem, NJ j
08079.
Dated at Rockville, Maryland, this 21st day of February 1995.
FOR THE NUCLEAR REGULATORY COMISSION r
J hn F. Stolz, Dire' or roject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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