ML060250166

Submittal of Engineering Analysis Supporting Compensatory Measures Implemented as a Result of GSI-191

ML060250166
Person / Time
Site:	Fort Calhoun
Issue date:	01/20/2006
From:	Faulhaber H Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-04-002, GSI-191, IN-05-026, LIC-06-0004
Download: ML060250166 (2)

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m Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 January 20, 2006 LIC-06-0004 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Ii iII I

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SUBJECT:

1.

Docket No. 50-285

2.

Letter from Harry J Faulhaber to Document Control Desk (NRC) dated November 18, 2005, Request for an Extension to the Completion Date for Corrective Actions Taken in Response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" and Information Regarding Actions taken as a Result of Information Notice 2005-26 (LIC-05-0131)

3.

NRC Information Notice 2005-26, "Results of Chemical Effects Head Loss Tests in a Simulated PWR Sump Pool Environment," dated September 16, 2005

4.

Letter from Harry J Faulhaber to Document Control Desk (NRC) dated August 31, 2005, Follow-up Response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" (LIC-05-0101)

Submittal of Engineering Analysis Implemented as a Result of GSI-191 Supporting Compensatory Measures In Reference 2, the Omaha Public Power District (OPPD) provided information related to Information Notice 2005-26 (Reference 3) and requested an extension to the compliance date for Generic Letter 2004-02 contained in Reference 4. During a telephone call with the NRC staff on January 13, 2006, the NRC requested that OPPD provide documentation of the bases for the interim compensatory measures and strategy described in Reference 2; these measures and strategy include mitigation of a complete loss of sump recirculation capability (i.e., 100% sump strainer blockage) through continued injection of water into the core.

Attached is the requested engineering analysis (EA-FC-04-010, Revision 0) that supports the compensatory measures implemented in response to potential blockage of the sump strainers.

As discussed during the January 13 call, this engineering analysis was developed to support OPPD's response to Bulletin 2003-01. The analysis supports the actions OPPD implemented in 2004, including procedural guidance for refilling of the Safety Injection Refueling Water Tank and continued water injection into the core. In addition, the analysis evaluates some potential enhancements that were not selected for implementation. Reference 2 provided a discussion of additional enhancements to these 2004 compensatory measures that OPPD will implement. EA-FC-04-010 is being revised in support of these enhancements. OPPD will submit this revised engineering analysis not later than February 17, 2006.

Employment with Equal Opportunity 4171

U. S. Nuclear Regulatory Commission LIC-06-0004 Page 2 If you have additional questions, or require further information, please contact Thomas C. Matthews at (402) 533-6938.

Sincerely, Harry J. ;aul Division ager Nuclear Engineering HJF/TRB/trb -

Engineering Analysis (EA-FC-04-010) Recommendations for Implementing of Compensatory Actions in Response to NRC Bulletin 2003-01