<?xml version='1.0' encoding='utf-8'?>

<rss version="2.0">
  <channel>
    <title>The Federal Register</title>
    <link>http://thefederalregister.com/b.p/agency/Nuclear_Regulatory_Commission/2003-12-15/</link>
    <description>Daily Publications of Meetings and Rules Changes for the Federal Government</description>
    <pubDate>Sun, Nov 23 2008 11:00:00 GMT</pubDate>
    <lastBuildDate>Sun, Nov 23 2008 11:00:00 GMT</lastBuildDate>
    <webMaster>info@thefederalregister.com</webMaster>
    <item>
  <title><![CDATA[
Florida Power and Light Company; St. Lucie Plant, Unit No. 1,  Environmental Assessment and Finding of No Significant]]></title>
  <link>http://thefederalregister.com/d.p/2003-12-15-03-30860</link>
  <description><![CDATA[
</p><p>    The U.S. Nuclear Regulatory Commission (NRC) is considering 
issuance of an exemption from Title 10 of the Code of Federal 
Regulations (10 CFR) Part 50, Appendix R, Section III.G.2.d for 
Facility Operating License No. DPR67, issued to Florida Power and 
Light Company (the licensee), for operation of the St. Lucie Plant, 
Unit No. 1, located in St. Lucie County, Florida. Therefore, as 
required by 10 CFR 51.21, the NRC is issuing this environmental  assessment and finding of no significant impact.<br/> Environmental Assessment</p>
<h3>Identification of the Proposed Action</h3>
<p>    Pursuant to 10 CFR Part 50, Appendix R, Section III.G.2.d, cables 
and equipment and associated nonsafety circuits of redundant trains 
located inside noninerted containments are required to be separated by 
a horizontal distance of more than 20 feet with no intervening 
combustibles or fire hazards. The proposed action would allow a minimum 
horizontal separation of 7 feet between redundant cable trays with no 
intervening combustibles in the <script type="text/javascript">
<!--
google_ad_client = "pub-2051746026283201";
google_ad_width = 728;
google_ad_height = 15;
google_ad_format = "728x15_0ads_al";
//2007-08-22: federalregister-rss
google_ad_channel = "2005962856";
google_color_border = "CC0000";
google_color_bg = "FFFFFF";
google_color_link = "CC0000";
google_color_text = "000000";
google_color_url = "008000";
//-->
</script>
<script type="text/javascript"
  src="http://pagead2.googlesyndication.com/pagead/show_ads.js">
</script>
]]></description>
  <guid>http://thefederalregister.com/d.p/2003-12-15-03-30860</guid>
  <pubDate>Mon, Dec 15 2003 11:00:00 GMT</pubDate>
</item>
<item>
  <title><![CDATA[
Notice of Availability of Environmental Assessment and Finding of  No Significant Impact for License Amendment for the]]></title>
  <link>http://thefederalregister.com/d.p/2003-12-15-03-30858</link>
  <description><![CDATA[<script type="text/javascript">
<!--
google_ad_client = "pub-2051746026283201";
google_ad_width = 728;
google_ad_height = 15;
google_ad_format = "728x15_0ads_al";
//2007-08-22: federalregister-rss
google_ad_channel = "2005962856";
google_color_border = "CC0000";
google_color_bg = "FFFFFF";
google_color_link = "CC0000";
google_color_text = "000000";
google_color_url = "008000";
//-->
</script>
<script type="text/javascript"
  src="http://pagead2.googlesyndication.com/pagead/show_ads.js">
</script>
]]></description>
  <guid>http://thefederalregister.com/d.p/2003-12-15-03-30858</guid>
  <pubDate>Mon, Dec 15 2003 11:00:00 GMT</pubDate>
</item>
<item>
  <title><![CDATA[
Draft Criteria for Determining Feasibility of Manual Actions To  Achieve Post-Fire Safe Shutdown]]></title>
  <link>http://thefederalregister.com/d.p/2003-12-15-03-30859</link>
  <description><![CDATA[ The U.S. Nuclear Regulatory Commission (NRC) is considering a 
revision to the fire protection regulations in 10 CFR Part 50, Appendix 
R, Paragraph III.G.2 to allow the use of manual actions by nuclear 
power plant operators to achieve hot shutdown conditions in the event 
of fires in certain areas provided the actions are evaluated against 
specific criteria and determined to be acceptable. For complying with 
the requirements of Appendix R, Paragraph III.G.2, licensees who rely 
on operator manual actions which have not been reviewed and approved by 
the NRC are generally considered to be in noncompliance. However, the 
NRC believes that manual actions relied upon by licensees are safe and 
effective if they meet appropriate acceptance criteria. Accordingly, 
until the fire protection regulations are revised, the NRC is planning 
to issue an interim enforcement policy to exercise enforcement 
discretion for noncompliant licensees if their manual actions meet the 
NRC's interim acceptance criteria. The NRC<script type="text/javascript">
<!--
google_ad_client = "pub-2051746026283201";
google_ad_width = 728;
google_ad_height = 15;
google_ad_format = "728x15_0ads_al";
//2007-08-22: federalregister-rss
google_ad_channel = "2005962856";
google_color_border = "CC0000";
google_color_bg = "FFFFFF";
google_color_link = "CC0000";
google_color_text = "000000";
google_color_url = "008000";
//-->
</script>
<script type="text/javascript"
  src="http://pagead2.googlesyndication.com/pagead/show_ads.js">
</script>
]]></description>
  <guid>http://thefederalregister.com/d.p/2003-12-15-03-30859</guid>
  <pubDate>Mon, Dec 15 2003 11:00:00 GMT</pubDate>
</item>
<item>
  <title><![CDATA[
Entergy Operations, Inc., System Energy Resources, Inc., South  Mississippi Electric Power Association, and Entergy]]></title>
  <link>http://thefederalregister.com/d.p/2003-12-15-03-30961</link>
  <description><![CDATA[
</p><p>    The U.S. Nuclear Regulatory Commission (the Commission) is 
considering issuance of an amendment to Facility Operating License No. 
NPF29 issued to Entergy Operations, Inc., System Energy Resources, 
Inc., South Mississippi Electric Power Association, and Entergy 
Mississippi, Inc. (Entergy) for operation of the Grand Gulf Nuclear 
Station, Unit 1 (GGNS), located in Claiborne County, Mississippi.
</p><p>    By letter dated December 5, 2003, Entergy submitted a revised 
application for amendment to GGNS Technical Specification (TS) 3.3.6.1, 
``Primary Containment and Drywell Isolation Instrumentation,'' to add a 
provision to the applicability function that will eliminate the 
requirement that the Residual Heat Removal (RHR) System Isolation, 
Reactor Vessel Water LevelLow, Level 3, be operable under certain 
conditions during refueling outages. Specifically, the proposed change 
requested in the original application dated May 12, 2003, would remove 
the requirement for this isolation function, specified in Tabl<script type="text/javascript">
<!--
google_ad_client = "pub-2051746026283201";
google_ad_width = 728;
google_ad_height = 15;
google_ad_format = "728x15_0ads_al";
//2007-08-22: federalregister-rss
google_ad_channel = "2005962856";
google_color_border = "CC0000";
google_color_bg = "FFFFFF";
google_color_link = "CC0000";
google_color_text = "000000";
google_color_url = "008000";
//-->
</script>
<script type="text/javascript"
  src="http://pagead2.googlesyndication.com/pagead/show_ads.js">
</script>
]]></description>
  <guid>http://thefederalregister.com/d.p/2003-12-15-03-30961</guid>
  <pubDate>Mon, Dec 15 2003 11:00:00 GMT</pubDate>
</item>
</channel>
</rss>

