Letter Sequence Other |
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Results
Other: ML073511698, ML081790538, ML091800430, ML093000354, ML101800052, ML110350515, NRC 2009-0113, Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706), NRC 2011-0010, Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
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MONTHYEARML0515203322005-06-0303 June 2005 6/3/05, Point Beach - RAI Potential Impact of Debris Blockage on Emergency Sump Recirculation Pressurized-Water Reactors Project stage: RAI ML0603704912006-02-0909 February 2006 RAI - Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0732303452007-11-16016 November 2007 Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0735116982007-12-20020 December 2007 GSI-191/GL 2004-02 Extension Request Approval (Tac No. MC4705/4706) Project stage: Other NRC 2008-0027, Response to Request for Additional Information License Amendment Request 260 One-Time Extension of Completion Time for Technical Specification 3.7.5. Auxiliary Feedwater System2008-05-15015 May 2008 Response to Request for Additional Information License Amendment Request 260 One-Time Extension of Completion Time for Technical Specification 3.7.5. Auxiliary Feedwater System Project stage: Response to RAI ML0816203372008-06-0909 June 2008 Supplemental Response to Generic Letter 2004-02, Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0817905382008-07-0101 July 2008 Generic Safety Issue 191/Generic Letter 2004-02, Additional Extension Request Approval Project stage: Other ML0822503302008-10-0606 October 2008 Teleconference Summary Regarding Point Beach Nuclear Plant Supplement to the Auxiliary Feedeater Amendment Project stage: Request ML0833001732009-01-0707 January 2009 GSI-191/GL 2004-02 Request for Additional Information Project stage: RAI NRC 2009-0033, Response to Request for Additional Information GSI-191/GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-04-0707 April 2009 Response to Request for Additional Information GSI-191/GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0909805232009-04-0707 April 2009 Response to Request for Additional Information GSI-191/GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0916603262009-06-12012 June 2009 Request for Extension of Unit 1 and 2 Completion Dates for Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC MC4705/4706) Project stage: Request NRC 2009-0053, Request for Extension of Unit 1 and 2 Completion Dates for Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC MC4705/4706)2009-06-12012 June 2009 Request for Extension of Unit 1 and 2 Completion Dates for Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC MC4705/4706) Project stage: Request NRC 2009-0059, Response to Request for Additional Information GSI-I91/GL 2004-02 Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-06-29029 June 2009 Response to Request for Additional Information GSI-I91/GL 2004-02 Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0918004302009-06-30030 June 2009 GSI-191/GL 2004-02 Additional Extension Request Approval Project stage: Other ML0921506362009-07-31031 July 2009 Response to Request for Additional Information GSI-191/GL 2004-02 (TACs MC4705/4706) Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI NRC 2009-0077, Response to Request for Additional Information GSI-191/GL 2004-02 (TACs MC4705/4706) Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-07-31031 July 2009 Response to Request for Additional Information GSI-191/GL 2004-02 (TACs MC4705/4706) Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0930003542009-10-27027 October 2009 Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706) Project stage: Other NRC 2009-0113, Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706)2009-10-27027 October 2009 Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706) Project stage: Other ML1005704542010-03-0303 March 2010 Notice of Meeting with FPL Energy Point Beach, LLC Regarding Discussion of Licensee Responses to Generic Letter 2004-02 for Point Beach Nuclear Plant, Units 1 and 2 Project stage: Meeting ML1005703212010-03-0303 March 2010 Request for Additional Information Generic Letter 2004-02 Round 2 Project stage: RAI NRC 2010-0046, Supplemental Response for Extension Request for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation Durian Design Basis Accidents at Pressurized-Water Reactors2010-06-11011 June 2010 Supplemental Response for Extension Request for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation Durian Design Basis Accidents at Pressurized-Water Reactors Project stage: Supplement ML1018000522010-06-30030 June 2010 Generic Letter Project stage: Other ML1016002922010-07-0808 July 2010 Summary of Meeting with NextEra Point Beach, Llc. Response to GL 2004-02 Project stage: Meeting NRC 2011-0010, Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2011-02-0404 February 2011 Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML1103505152011-02-0404 February 2011 Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other L-2012-098, Units, 1 and 2, Turkey Point, Units 3 and 4, Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Protocol2012-03-0303 March 2012 Units, 1 and 2, Turkey Point, Units 3 and 4, Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Protocol Project stage: Request ML12213A0612012-08-0101 August 2012 8/16/12 Forthcoming Conference Call with NextEra Energy and Florida Power & Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Protocol Project stage: Draft Approval ML12222A0392012-08-0909 August 2012 8/16/2012 Cancellation Notice of Forthcoming Conference Call with NextEra Energy and Florida Power and Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Proto Project stage: Draft Approval ML12121A3842012-08-31031 August 2012 Acknowledgment Letter Regarding Draft Propose Guideline for Strainer Fiber Bypass Test Protocol Associated with Generic Letter 2004 Project stage: Draft Other 2009-06-12
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October 27,2009 NRC 2009-01 13 GL 2004-02 U. S. Nuclear Regulatory Commission AlTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Generic Letter 2004-02 Potential Impact for Debris Blockage in Emeraencv Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC470514706)
References (1)
NextEra Energy Point Beach, LLC, Letter to NRC, dated June 12,2009, Request for Extension of Unit 1 and 2 Completion Dates for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4719 and MC4720)
(ML091660326)
(2)
NRC Letter to NextEra Energy Point Beach Nuclear Plant Units 1 and 2, dated June 30, 2009, GSI-19IIGL 2004-02, Additional Extension Request Approval (TAC Nos. MC4705 and MC4706) (ML091800430)
The purpose of this letter is to inform the NRC staff that there has been a change to the plan associated with the Unit 2 Phase 1 fiber reduction activities that are being implemented during the current Unit 2 refueling outage. The scope of the Phase 1 activities was previously described in Section 3.1 of the enclosure for Reference (1). The change to the plan was discussed with the NRC Point Beach Project Manager on October 23, 2009. This change is driven primarily by the determination of the actual dose rates in the work areas, the work complexity, and NextEra's focus on performing this work through a more dose effective execution plan.
The plan change does not alter the Regulatory Commitments specified in Reference (I) as confirmed by the Commission's evaluation contained in Reference (2) which stated:
"NextEra will complete modifications to resolve GSI-191 at Point Beach Nuclear Plant (PBNP) by June 30,2010, for Unit 1, and by June 30,201 I, for PBNP Unit 2."
NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
Document Control Desk Page 2 Specifically, NextEra Energy Point Beach, LLC (NextEra) intends to defer fibrous insulation replacement activities associated with the reactor coolant pump (RCP) bowls and the steam generator upper shells (i.e., if the 5D Zone of lnfluence (ZOI) issues are not resolved) until the spring 201 1 refueling outage for Unit 2.
The RCP bowl and steam generator upper shell (i.e., if the 5D Zone of lnfluence (ZOI) issues are not resolved) fiber reduction activities are being deferred to the Spring 201 1 outage because the craft hours used for dose estimates have proven to be significantly underestimated due to job complexity. There was no opportunity for previous outage planning as this work scope evolved through industry learnings. Additionally, there was a lack of available dose rate information for ALARA planning for areas inside the steam generator cubicles and around the RCP bowls where work is not normally performed.
Based upon data obtained during the current Unit 2 refueling outage, NextEra estimates that approximately 50 Rem personnel exposure will be received rather than the 9.5 Rem previously planned for. NextEra estimates that completing the revised Phase 1 scope of work (i.e.,
replacement of approximately 505 ft3 of insulation versus the plan to replace 685 ft3 of insulation as discussed below) during the current Unit 2 refueling outage will result in significantly less personnel exposure.
The revised Phase 1 scope of work to be completed during the current Unit 2 refueling outage includes replacement of the insulation on the steam generator channel heads and the reactor coolant system loops as necessary to ensure no NUKONO insulation on these components remains within the ZOI. This will result in replacement of approximately 505 ft3 of insulation rather than the approximately 685 ft3 of insulation previously stated in Reference (1). The modifications to install three additional strainer modules on each train of strainers and structurally reinforce the strainer assemblies to accommodate an increased differential pressure will also be completed during the current Unit 2 refueling outage.
Detailed walkdowns described in Reference (I) are being performed during the current Unit 2 refueling outage in preparation for insulation replacement during the spring 201 1 Unit 2 refueling outage. These walkdowns will include obtaining necessary dose rate data to ensure insulation replacement during the Unit 2 Spring 201 1 refueling outage is maintained ALARA with substantially reduced doses for the project expected.
Installing shielding packages, aggressive cleanup of the reactor coolant system and improved work planning will be incorporated into the insulation removal and installation activities during the spring 201 1 Unit 2 refueling outage. Based upon data gathered during the current Unit 2 refueling outage, NextEra estimates that these activities will result in a reduction in dose of approximately 50%. The lessons learned from the current Unit 2 refueling outage will be applied to similar work activities during the Unit 1 Spring 2010 refueling outage.
The fiber reduction activities and strainer module modifications being implemented during the current Unit 2 refueling outage continue to ensure a high level of emergency core cooling system (ECCS) pump performance.
Document Control Desk Page 3 If you have questions or require additional information, please contact Mr. James Costedio at 9201755-7427.
A copy of this submittal has been provided to the designated Wisconsin Official.
Very truly yours, NextEra Energy Point Beach, LLC cc:
Resident Inspector, Point Beach Nuclear Plant, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Administrator, Region Ill, USNRC PSCW