Letter Sequence Request |
|---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement
|
MONTHYEARML0525500522005-09-0101 September 2005 Response to Requested Information Part 2 of NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0603903012006-02-0909 February 2006 GSI Letter RAI Response to GL 2004-02 (TAC Nos. MC4676 and 4677) Project stage: RAI CP-200700085, Supporting Information Regarding the Proprietary Nature of Gothic Code Input Data2007-12-0303 December 2007 Supporting Information Regarding the Proprietary Nature of Gothic Code Input Data Project stage: Request CP-200700090, Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2007-12-0303 December 2007 Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request CP-200800834, Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors2008-06-19019 June 2008 Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors Project stage: Request ML0817601002008-06-27027 June 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Approval of Extension Request Project stage: Other ML0835004652008-11-26026 November 2008 Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Cover Letter Project stage: Request ML0916604102009-05-11011 May 2009 E-mail Draft Request for Additional Information, Licensees Supplemental Responses Dated February 29 and November 26, 2008, to GL 2004-02 Project stage: Draft RAI ML0916604222009-05-11011 May 2009 Request for Additional Information Supplemental Responses to Generic Letter (GL) 2004-02 Dated 02/29/2008 and 11/26/2008 Project stage: RAI ML0915307112009-06-16016 June 2009 Notice of Meeting with Representatives of Luminant Generation Company Llc., to Discuss Draft Request for Information for Generic Letter 2004-02 Response Project stage: Draft RAI ML0918207102009-07-0202 July 2009 Revised Notice of Meeting with Representatives of Luminant Generation Co., LLC, Comanche Peak to Discuss Draft Request for Information for Generic Letter 2004-02 Response Project stage: Draft RAI ML0919604492009-07-0808 July 2009 Alion Meeting Presentations on RAI 9 - Pool Fill Transport, & RAI 6 - Fiber Erosion Testing Project stage: Request ML0919402772009-07-0909 July 2009 Luminant Holistic Overview: Presentation Will Cover Information Related to RAIs 1 - 5, 7, 12 - 14,16 - 19, 21, 25 - 36 and Overall Response to GL 2004-02 Project stage: Request ML0919400832009-07-0909 July 2009 Pci RAI 8, Test Protocol, Erosion Issue, RAI 15, Test Protocol, Latent Fiber Issue, Areva RAI 20, Test Flume, Fiberglass Larges Question Project stage: Request ML0919400852009-07-0909 July 2009 Luminant RAI 24 and 37, Secondary Line Breaks, Debris Load and Testing Project stage: Request ML0919400842009-07-0909 July 2009 Luminant RAI 22 and 23 SBLOCA, Vortex, Air Ingestion, Void Fraction and Flashing Issues Project stage: Request ML0919402762009-07-0909 July 2009 NRC Opening Remarks Discuss the Draft Us Nuclear Regulatory Commission Request for Additional Information for Generic Letter GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressur Project stage: Draft RAI ML0919403532009-07-13013 July 2009 Notice of Forthcoming Conference Call on July 23, 2009, with Luminant Generation Company LLC to Discuss Draft Request for Additional Information Re Generic Letter 2004-02, Dated May 11, 2009 Project stage: Draft RAI ML0916707382009-07-15015 July 2009 Request for Additional Information Supplemental Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0920203432009-07-22022 July 2009 Revised Conference Call with Luminant Generation Company, LLC, to Discuss Draft Request for Additional Information Re Generic Letter 2004-02, Dated May 11, 2009 Project stage: Draft RAI ML0919705782009-07-31031 July 2009 Summary of Category 1 Meeting with Luminant Generation Company LLC, Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Meeting ML0923300622009-09-0101 September 2009 Summary of Meeting with Luminant Generation Company LLC, to Discuss Draft Request for Additional Information Re Generic Letter 2004-02 for Comanche Peak, Units 1 and 2 Project stage: Draft RAI ML0926107912009-09-10010 September 2009 Supplement Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request CP-200901396, Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basic Accidents at Pressurized-water Reactors2009-10-12012 October 2009 Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basic Accidents at Pressurized-water Reactors Project stage: Supplement ML0930800032009-10-13013 October 2009 Supplement to Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML1009505642010-04-19019 April 2010 Generic Letter 2004-02 Supplemental Response Project stage: Other ML13045A4102013-02-15015 February 2013 2/28/13 Notice of Meeting Via Conference Call with Luminant to Discuss Generic Safety Issue 191, Assessment of Debris Accumulation on PWR (Pressurized-Water Reactor) Sump Performance, for Comanche Peak, Units 1 and 2 Project stage: Meeting ML13059A2022013-02-28028 February 2013 Email Licensee Slides for 2/28/13 Meeting Via Conference Call Project stage: Meeting ML13059A1812013-02-28028 February 2013 Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, Project stage: Meeting ML13067A0292013-03-15015 March 2013 2/28/13 - Summary of Meeting Via Conference Call with Luminant to Discuss Generic Safety Issue 191, Assessment of Debris Accumulation on PWR (Pressurized-Water Reactor) Sump Performance, for Comanche Peak, Units 1 and 2 Project stage: Meeting CP-201300670, Closure Options for Generic Safety Issue 191 (GSI-191), Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance2013-05-16016 May 2013 Closure Options for Generic Safety Issue 191 (GSI-191), Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance Project stage: Other ML13267A1972013-09-30030 September 2013 Request for Additional Information, Closure of Option 2a to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage; Related to Generic Safety Issue 191 Project stage: RAI CP-201301214, Response to Request for Additional Information Regarding Closure Options for Generic Safety Issue 1912013-10-31031 October 2013 Response to Request for Additional Information Regarding Closure Options for Generic Safety Issue 191 Project stage: Response to RAI 2009-07-02
[Table View] |
Text
il5,
a NRC - Luminant Power Public Meeting Comanche Peak Nuclear Power Plant Secondary Line Breaks July 9th 2009 Secondary Line Breaks
- Containment Spray provides containment heat removal - maximum 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> mission time for equipment qualification.
Decay heat removal is by the secondary systems (not by ECCS, i.e., 50.46)
RG 1.82 R3
" "Some PWRs may require recirculation from the sump for licensing basis events other than LOCAs. Therefore, plants should review the licensing basis and include potential break locations in the main steam and main feedwater lines as well in determining the most limiting conditions for sump operation."
- GDC-4 is the Comanche Peak licensing basis for secondary line breaks
- CPNPP elected to evaluate sump performance using the same break selection criteria as for LOCA.
Comparison of Fiber Load Fibrous MSLB (lbs)
Prototype (lbs)
LOCA (lbs)
Bounded Latent Fiber 24 30 24 Yes LDFG Fines 42.6 53.8 Yes LDFG Smalls 160 540.75 183 Yes LDFG Large 18.4 LDFG Intact 18.6 Kaowool 353.6 448.8 Prototype Sil-temp 52.4 71.4 Prototype Min-K 12.96 8
1.6 No Covers 27.2 Total 645.6 1099 218.8 Prototype
Comparison of Particulate Load MSLB (lbs)
Prototype (lbs)
LOCA (lbs)
Bounded Dirt/Dust 136 170 136 Yes Min-K Fines 52.16 34.3 lbs 6.72 No Acceptable Epoxy 217.5 3860.9 262.9 Yes Acceptable IOZt 366.9 267.5 376 Yes Unqualified Epoxy 2838 (6 mil) 12920 lbs as 2838 (6 mil)
Yes.
(outside ZOI) particulate fines (walnut shells)
Unqualified IOZ Yes (outside ZOI) 16834 25634 16834 Unqualified Alkyd Yes (outside ZOI) 104 992 104 Total 20, 549 43,879 20,557.6 Yes Prototype (small flume) Testing
- Ultra-Conservative test temperature - < 50 F
" Fiberglass fibers settle in 20 to 60 minutes in 50 F water versus 20 to 30 seconds in 120 F water
[NUREG/CR-2982, "...water temperature has a paramount effect on buoyancy..."]
- Tests conducted at 128 F and 169 F confirmed the effect on settling of fiberglass [Test Report No. ITR-92-03N]
- MSLB Head Loss - Small Flume 0.005 ft. (0.0044 fps)
- LOCA Head Loss - Small Flume 0.4682 ft. (0.0073 fps)
- LOCA Head Loss - Large Flume 0.6 ft. (0.0073 fps)
RAI 13
Conclusion
- Debris Generation and Transport analyses were performed consistent with the SER for NEI 04-07
" Prototype testing showed that LOCA debris loads and conditions bounded the secondary break head loss
" Large flume testing under the March 2008 protocol confirmed the the small flume test protocol was conservative for this case
" CPNPP has provided reasonable asurrance, that the Containment Spray System wil perform its design function for secondary line breaks