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| | issue date = 02/18/2010 | | | issue date = 02/18/2010 |
| | title = Request for Additional Information Regarding GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors | | | title = Request for Additional Information Regarding GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors |
| | author name = Paige J C | | | author name = Paige J |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Nazar M | | | addressee name = Nazar M |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 February 18, 2010 Mr. Mano Nazar Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 TURKEY POINT NUCLEAR GENERATING UNIT NO.4 -REQUEST FOR ADDITIONAL INFORMATION REGARDING GL 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" (TAC NO. MC4726) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2010 Mr. Mano Nazar Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 |
| | |
| | ==SUBJECT:== |
| | TURKEY POINT NUCLEAR GENERATING UNIT NO.4 - REQUEST FOR ADDITIONAL INFORMATION REGARDING GL 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" (TAC NO. MC4726) |
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| ==Dear Mr. Nazar:== | | ==Dear Mr. Nazar:== |
| By letter dated March 19,2009, Florida Power & Light Company (FPL, the licensee), provided responses to the Nuclear Regulatory Commission's (NRC) request for additional information (RAI) regarding Generic Letter (GL) 2004-02, "Potential Impact of debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors." On August 6, 2009, FPL and the NRC held a public teleconference to discuss the March 19 th licensee responses. | | |
| As a result of the August 6 th teleconference, the NRC drafted additional clarifying RAls for Turkey Point Unit 4 Questions 11 and 21. On February 3, 2010, FPL and the NRC held a public teleconference to discuss open items regarding GL 2004-02 and the licensee's responses to Questions 11 and 21. As a result of the meeting, the NRC staff finds that the additional information contained in the enclosed RAI is needed before we can complete the review. If you have any questions, please contact me at (301) 415-5888. | | By letter dated March 19,2009, Florida Power & Light Company (FPL, the licensee), provided responses to the Nuclear Regulatory Commission's (NRC) request for additional information (RAI) regarding Generic Letter (GL) 2004-02, "Potential Impact of debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors." On August 6, 2009, FPL and the NRC held a public teleconference to discuss the March 19th licensee responses. As a result of the August 6 th teleconference, the NRC drafted additional clarifying RAls for Turkey Point Unit 4 Questions 11 and 21. |
| Y . | | On February 3, 2010, FPL and the NRC held a public teleconference to discuss open items regarding GL 2004-02 and the licensee's responses to Questions 11 and 21. As a result of the meeting, the NRC staff finds that the additional information contained in the enclosed RAI is needed before we can complete the review. |
| j , c; Jason C. Paige, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-251 | | If you have any questions, please contact me at (301) 415-5888. |
| | j Y |
| | Sincerel1: . |
| | j , |
| | c; - |
| | Jason C. Paige, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-251 |
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| ==Enclosure:== | | ==Enclosure:== |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION GENERIC LETrER 2004-02 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNIT NO.4 DOCKET NUMBER 50-251 Regarding the licensee's response, as discussed during the February 3,2010, public teleconference, to request for additional information (RAI) 11s, the Nuclear Regulatory Commission staff has identified certain inadequacies regarding the structural analysis performed to demonstrate the structural adequacy of the debris interceptors: |
| | : 1. The licensee indicated that "The method of qualification of the structural adequacy of Debris Interceptors (Dis) for the deadweight, seismic, and hydrodynamic load case is outlined. .. ." Are the deadweight, seismic, and hydrodynamic loads combined to formulate the bounding load combination for the Dis? If this is not the bounding load combination, the licensee should indicate what the bounding load combination is for this structure. |
| | : 2. The licensee described the hydrodynamic load as the "maximum differential pressure" across the Dis. It does not appear that the hydrodynamic loading effects of sloshing during a seismic event were incorporated into the licensee's structural analyses of the 01 structures. The licensee should provide the basis for neglecting the effects of loading from sloshing during a seismic event. Additionally, justification should be provided for why this load would not be included in a bounding load combination. |
| | : 3. The licensee incorporated the use of the momentum function, as it applies to open channel flow, to derive the hydraulic loading on the Dis. Based on the licensee's description of the flow through the Dis in their August 11, 2008, supplemental response, it is difficult to decipher whether a water height gradient exists across the 01 boundary. |
| | Based on the licensee's use of the momentum function from Henderson's Open Channel Flow, the hydraUlic load would be a zero value with no height differential. The licensee should provide a range of parameters that would be used to compute this hydraulic load (q, Y1, Y2), using the function outlined. |
| | : 4. The licensee should provide a justification for not considering live loads induced by post-LOCA debris, which may impact the Dis. |
| | : 5. RAI 11 s requested the licensee to provide the results of their structural analysis. No results were provided. The licensee should provide a tabulated data set showing, at a minimum, the maximum and allowable stresses for all of the Dis components structurally analyzed, including structural members, panels, brackets, bolts, anchors, and all other components. Applicable design margins or interaction ratios based on the aforementioned code allowable values should also be included to provide staff with reasonable assurance of the structural integrity of the Dis. |
| | Enclosure |
| | |
| | February 18, 2010 Mr. Mano Nazar Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 |
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| Request for Additional Information cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION GENERIC LETrER 2004-02 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNIT NO.4 DOCKET NUMBER 50-251 Regarding the licensee's response, as discussed during the February 3,2010, public teleconference, to request for additional information (RAI) 11s, the Nuclear Regulatory Commission staff has identified certain inadequacies regarding the structural analysis performed to demonstrate the structural adequacy of the debris interceptors: The licensee indicated that "The method of qualification of the structural adequacy of Debris Interceptors (Dis) for the deadweight, seismic, and hydrodynamic load case is outlined.
| | ==SUBJECT:== |
| .. ." Are the deadweight, seismic, and hydrodynamic loads combined to formulate the bounding load combination for the Dis? If this is not the bounding load combination, the licensee should indicate what the bounding load combination is for this structure. The licensee described the hydrodynamic load as the "maximum differential pressure" across the Dis. It does not appear that the hydrodynamic loading effects of sloshing during a seismic event were incorporated into the licensee's structural analyses of the 01 structures.
| | TURKEY POINT NUCLEAR GENERATING UNIT NO.4 - REQUEST FOR ADDITIONAL INFORMATION REGARDING GL 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" (TAC NO. MC4726) |
| The licensee should provide the basis for neglecting the effects of loading from sloshing during a seismic event. Additionally, justification should be provided for why this load would not be included in a bounding load combination. The licensee incorporated the use of the momentum function, as it applies to open channel flow, to derive the hydraulic loading on the Dis. Based on the licensee's description of the flow through the Dis in their August 11, 2008, supplemental response, it is difficult to decipher whether a water height gradient exists across the 01 boundary.
| |
| Based on the licensee's use of the momentum function from Henderson's Open Channel Flow, the hydraUlic load would be a zero value with no height differential.
| |
| The licensee should provide a range of parameters that would be used to compute this hydraulic load (q, Y1, Y2), using the function outlined. The licensee should provide a justification for not considering live loads induced by post-LOCA debris, which may impact the Dis. RAI 11 s requested the licensee to provide the results of their structural analysis.
| |
| No results were provided.
| |
| The licensee should provide a tabulated data set showing, at a minimum, the maximum and allowable stresses for all of the Dis components structurally analyzed, including structural members, panels, brackets, bolts, anchors, and all other components.
| |
| Applicable design margins or interaction ratios based on the aforementioned code allowable values should also be included to provide staff with reasonable assurance of the structural integrity of the Dis. Enclosure February 18, 2010 Mr. Mano Nazar Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 TURKEY POINT NUCLEAR GENERATING UNIT NO.4 -REQUEST FOR ADDITIONAL INFORMATION REGARDING GL 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" (TAC NO. MC4726)
| |
|
| |
|
| ==Dear Mr. Nazar:== | | ==Dear Mr. Nazar:== |
| By letter dated March 19,2009, Florida Power & Light Company (FPL, the licensee), provided responses to the Nuclear Regulatory Commission's (NRC) request for additional information (RAI) regarding Generic Letter (GL) 2004-02, "Potential Impact of debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors." On August 6, 2009, FPL and the NRC held a public teleconference to discuss the March 19 th licensee responses. | | |
| As a result of the August 6 th teleconference, the NRC drafted additional clarifying RAls for Turkey Point Unit 4 Questions 11 and 21. On February 3, 2010, FPL and the NRC held a public teleconference to discuss open items regarding GL 2004-02 and the licensee's responses to Questions 11 and 21. As a result of the meeting, the NRC staff finds that the additional information contained in the enclosed RAI is needed before we can complete the review. If you have any questions, please contact me at (301) 415-5888. | | By letter dated March 19,2009, Florida Power & Light Company (FPL, the licensee), provided responses to the Nuclear Regulatory Commission's (NRC) request for additional information (RAI) regarding Generic Letter (GL) 2004-02, "Potential Impact of debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors." On August 6, 2009, FPL and the NRC held a public teleconference to discuss the March 19th licensee responses. As a result of the August 6th teleconference, the NRC drafted additional clarifying RAls for Turkey Point Unit 4 Questions 11 and 21. |
| Sincerely, IRA! Jason C. Paige, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-251 | | On February 3, 2010, FPL and the NRC held a public teleconference to discuss open items regarding GL 2004-02 and the licensee's responses to Questions 11 and 21. As a result of the meeting, the NRC staff finds that the additional information contained in the enclosed RAI is needed before we can complete the review. |
| | If you have any questions, please contact me at (301) 415-5888. |
| | Sincerely, IRA! |
| | Jason C. Paige, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-251 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| | | Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: |
| Request for A dditional Information cc w/encl: Distribution via Listserv DISTRIBUTION: | | PUBLIC RidsOgcRp RidsNrrDorlDpr LPL2-2 RlF RidsAcrsAcnw_ MailCTR RidsNrrDeEmcb RidsNrrPMTurkey Point RidsRgn2MailCenter BJessup, NRR RidsNrrLABClayton (Hard Copy) RidsNrrDorlLpl2-2 JUribe, NRR ADAMS Accession Number" ML100351213 OFFICE LPL2-2/PM LPL2-2/LA EMCB/BC LPL2-2/BC (A) |
| PUBLIC LPL2-2 RlF RidsNrrPMTurkey Point RidsNrrLABClayton (Hard Cop y) RidsOgcRp RidsAcrsAcnw | | NAME JPaiqe BClayton MKhanna BMozafari DATE 02/04/10 02/04/10 02/16/10 02/18/10 OFFICIAL RECORD COPY}} |
| _MailCTR RidsRgn2MailCenter RidsNrrDorlLpl2-2 RidsNrrDorlDpr RidsNrrDeEmcb BJessup, NRR JUribe, NRR ADAMS Accession Number" ML 100351213 OFFICE LPL2-2/PM LPL2-2/LA EMCB/BC LPL2-2/BC (A) NAME JPaiqe BClayton MKhanna BMozafari DATE 02/04/10 02/04/10 02/16/10 02/18/10 OFFICIAL RECORD COPY}}
| |
Letter Sequence RAI |
|---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement
Results
Other: ML060890398, ML060950574, ML073511698, ML081200606, ML081790538, ML090980515, ML092080216, ML092440479, ML100190011, 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
|
MONTHYEARML0515202022005-06-0202 June 2005
6/2/05, Turkey Point, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
Project stage: RAI
ML0515201832005-06-0202 June 2005
Request for Additional Information, Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
Project stage: RAI
ML0515202272005-06-0303 June 2005
6/3/05, Seabrook, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
Project stage: RAI
ML0603703962006-02-0808 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
ML0603704382006-02-0808 February 2006
Request for Additional Information 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
ML0603801332006-02-0909 February 2006
Request for Additional Information 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
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
ML0608903982006-04-11011 April 2006
Requested Extension of Completion Schedule for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Other
ML0609505742006-04-13013 April 2006
Approval of GSI-191/GL 2004-02 Extension Request
Project stage: Other
NRC 2007-0085, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2007-11-16016 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
L-2007-155, Request for Extension of Completion Date of the Generic Letter 2004-02 Actions2007-12-0707 December 2007
Request for Extension of Completion Date of the Generic Letter 2004-02 Actions
Project stage: Request
ML0735116982007-12-20020 December 2007
GSI-191/GL 2004-02 Extension Request Approval (Tac No. MC4705/4706)
Project stage: Other
L-2008-030, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-02-27027 February 2008
Supplemental 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
L-2008-033, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-02-28028 February 2008
Supplemental 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
L-2008-073, NRC Generic Letter 2004-02 Request for an Extension to the Completion Date for Ex-Vessel Downstream Effects Evaluations2008-04-14014 April 2008
NRC Generic Letter 2004-02 Request for an Extension to the Completion Date for Ex-Vessel Downstream Effects Evaluations
Project stage: Request
ML0812006062008-04-29029 April 2008
Approval of Extension Request for GL 2004-02
Project stage: Other
NRC 2008-0038, Supplemental Response to Generic Letter 2004-02, Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-06-0909 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
L-2008-137, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-30030 June 2008
Supplemental 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
L-2008-138, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-30030 June 2008
Supplemental 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
ML0817905382008-07-0101 July 2008
Generic Safety Issue 191/Generic Letter 2004-02, Additional Extension Request Approval
Project stage: Other
ML0826106902008-09-17017 September 2008
Request for Additional Information Related to GL 2004-02
Project stage: RAI
ML0826107052008-09-17017 September 2008
Request for Additional Information (RAI) Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors
Project stage: RAI
ML0834400782008-12-19019 December 2008
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information
Project stage: RAI
ML0833806712008-12-22022 December 2008
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information (TAC Mc 4725)
Project stage: RAI
ML0833001732009-01-0707 January 2009
GSI-191/GL 2004-02 Request for Additional Information
Project stage: RAI
ML0836589782009-01-16016 January 2009
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information
Project stage: RAI
ML0835800232009-01-22022 January 2009
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information
Project stage: RAI
L-2009-063, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2009-03-19019 March 2009
Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Response to RAI
L-2009-062, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2009-03-19019 March 2009
Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
Project stage: Response to 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
ML0909805152009-04-0808 April 2009
SONGS - GSI-191 Chemical Effects
Project stage: Other
L-2009-084, Response to Nrc'S Request for Additional Information2009-04-22022 April 2009
Response to Nrc'S Request for Additional Information
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
ML0920802162009-07-27027 July 2009
Notice of Forthcoming Conference Call with Florida Power and Light Concerning Turkey Point Generic Letter 2004-02 Response
Project stage: Other
L-2009-180, Responses to Nrc'S Request for Additional Information on Generic Letter 2004-02 Supplemental Responses, Dated 02/27/2008 and 06/30/20082009-07-30030 July 2009
Responses to Nrc'S Request for Additional Information on Generic Letter 2004-02 Supplemental Responses, Dated 02/27/2008 and 06/30/2008
Project stage: Supplement
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
ML0924404792009-09-11011 September 2009
Summary of Conference Call with Florida Power & Light, to Discuss Generic Letter 2004-02, Potential Impact of Debris Blackage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactor, Responses
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
ML1001900112010-01-19019 January 2010
Notice of Conference Call with Florida Power & Light Concerning Turkey Point Generic Letter 2004-02 Response
Project stage: Other
ML1003512132010-02-18018 February 2010
Request for Additional Information Regarding GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML1009700022010-04-0909 April 2010
Request for Additional Information, Regarding GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
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
ML1019405202010-07-14014 July 2010
Notice of Conference Call with Florida Power and Light Company to Discuss Draft Responses to NRC Requests for Additional Information for Generic Letter 2004-02
Project stage: Draft RAI
ML1007407182010-07-28028 July 2010
February 3, 2010, Turkey Point, Unit 3 & 4, Summary of Meeting with Florida Power & Light, on Generic Letter 2004-02
Project stage: Meeting
L-2010-205, Responses to Nrc'S Request for Additional Information Dated Feb. 18, 2010 Re Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2010-09-17017 September 2010
Responses to Nrc'S Request for Additional Information Dated Feb. 18, 2010 Re Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Request
ML1009903062010-09-22022 September 2010
Request for Additional Information Regarding GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML1025902742010-12-17017 December 2010
Summary of Teleconference Meeting with Florida Power & Light Company, on Generic Letter 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
ML1103502052011-02-0404 February 2011
Forthcoming Public Teleconference with NextEra Energy Seabrook, LLC, to Discuss Planned Testing for Seabrook Specific Erosion
Project stage: Request
2009-01-07
[Table View] |
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Category:Letter
MONTHYEARL-2024-184, Radiological Emergency Plan Revision 772024-11-0505 November 2024
Radiological Emergency Plan Revision 77
L-2024-173, Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-31031 October 2024
Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles
L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024
Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums
L-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024
Cycle 34 Core Operating Report
ML24291A2882024-10-24024 October 2024
Westinghouse Topical Report - Request for Withholding Information from Public Disclosure
L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024
Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis
ML24276A2302024-10-16016 October 2024
Westinghouse Topical Report – Request for Withholding Information from Public Disclosure
L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes
ML24289A2372024-10-15015 October 2024
Transmittal of Revision 1 Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles
L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024
Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)
L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024
Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles
IR 05000250/20243012024-10-0303 October 2024
NRC Operator License Examination Report 05000250/2024301 and 05000251/2024301
L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024
Submission of Periodic Reports
L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
ML24269A1292024-09-24024 September 2024
Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis
ML24260A2262024-09-18018 September 2024
NRC Examination Results Summary - Examination Reports: 05000250/2024301 and 05000251/2024301
ML24262A2272024-09-18018 September 2024
Transmittal of Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles
ML24158A0052024-09-17017 September 2024
Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses
L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
ML24207A0342024-09-13013 September 2024
– Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter
ML24256A1132024-09-13013 September 2024
Regulatory Audit Summary Related to the Review of Regarding the Updated Spent Fuel Pool Criticality Safety Analysis License Amendment Request
IR 05000250/20240052024-08-23023 August 2024
Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005
ML24234A0062024-08-22022 August 2024
Project Manager Assignment
L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024
Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02
L-2024-122, Core Operating Limits Report2024-08-12012 August 2024
Core Operating Limits Report
ML24163A0012024-08-0505 August 2024
LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review
L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024
Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections
L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024
Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
ML24184B2822024-07-16016 July 2024
– Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML24193A2432024-07-12012 July 2024
– Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan
05000250/LER-2024-002-01, Condition Prohibited by Technical Specifications2024-07-10010 July 2024
Condition Prohibited by Technical Specifications
L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024
Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal
ML24173A1902024-06-28028 June 2024
Withdrawal of an Amendment Request
ML24159A2652024-06-26026 June 2024
Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project
L-2024-102, Official Service List Update2024-06-19019 June 2024
Official Service List Update
L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024
Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project
ML24149A2862024-06-12012 June 2024
NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter
IR 05000250/20244012024-06-0505 June 2024
– Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401
L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024
Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05
L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024
2023 Annual Radiological Environmental Operating Report
IR 05000250/20240012024-05-10010 May 2024
Integrated Inspection Report 05000250/2024001 and 05000251/2024001
ML24135A0942024-05-0909 May 2024
Periodic Update to the Updated Final Safety Analysis Report
ML24127A1862024-05-0909 May 2024
Request for Withholding Information from Public Disclosure
L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024
10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report
ML24127A0632024-05-0606 May 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024
Cycle 34 Core Operating Limits Report
L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024
Cycle 33 Core Operating Limits Report
L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024
Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision
L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024
Radiological Emergency Plan Revision 76
L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024
Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02
2024-09-25
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24282A6722024-10-0808 October 2024
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - Transition to 24-Month Fuel Cycles (L-2023-LLA-0161)
ML24261B8062024-09-17017 September 2024
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - Transition to 24-Month Fuel Cycles (L-2023-LLA-0161)
ML24250A0242024-09-0606 September 2024
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - Transition to 24-Month Fuel Cycles (L-2023-LLA-0161)
ML24250A0852024-09-0606 September 2024
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - Transition to 24-Month Fuel Cycles (L-2023-LLA-0161)
ML24234A0842024-08-21021 August 2024
Notification of Inspection and Request for Information
ML24234A0142024-08-20020 August 2024
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - Spent Fuel Storage License Amendment Request (LAR) (L-2023-LLA-0142)
ML24193A2432024-07-12012 July 2024
– Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan
IR 05000250/20240102024-01-0505 January 2024
Focused Engineering Inspection 05000250/2024010 and 05000251/2024010
ML23226A0752023-08-14014 August 2023
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - RCP LAR (L-2022-LLA-0128)
ML23173A1522023-06-22022 June 2023
Request for Additional Information NextEra Fleet Emergency Plan Amendment Request
ML23129A8322023-05-0505 May 2023
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - RCP LAR (L-2022-LLA-0128)
ML23038A1892023-02-0303 February 2023
RP RFI April 2023
ML22311A5582022-11-22022 November 2022
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep
ML22311A4752022-11-0707 November 2022
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - ITS
IR 05000250/20234012022-10-19019 October 2022
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000250/2023401 and 05000251/2023401
ML22255A0502022-09-15015 September 2022
Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request to Replace Instrumentation with Digital Systems
ML22229A5332022-08-18018 August 2022
Notification of Target Set Inspection and Request for Information (NRC Inspection Report No. 05000250 2022402 and 05000251 2022402)
ML22181A0562022-06-30030 June 2022
NRR E-mail Capture - Request for Additional Information - Turkey Point U3 Sgtir (L-2022-LRO-0070)
ML22081A0292022-03-21021 March 2022
NRR E-mail Capture - Turkey Point Nuclear Generating Unit No. 3 - Request for Additional Information - Icw Alternative
ML22068A2352022-03-17017 March 2022
Licensed Operator Positive Fitness-For-Duty Test
ML22074A0932022-03-14014 March 2022
RP RFI March 2022
ML21342A2932021-12-21021 December 2021
Supplemental Information Needed for Acceptance of Requested License Amendment Request Concerning Technical Specification Conversion to NUREG-1431, Revision 5
ML21298A0572021-10-25025 October 2021
NRR E-mail Capture - Final: Tpn Request for Additional Information - Round 2 Concerning Relief Request 10 - Extension EPID: L-2021-LLR-0077
ML21291A1272021-10-14014 October 2021
NRR E-mail Capture - Request for Additional Information - Fifth Ten-Year Inservice Inspection Interval Relief Request No.10 - Extension (L-2021-LLR-0077)
ML21270A1652021-09-27027 September 2021
NRR E-mail Capture - Turkey Point Request for Additional Information Concerning Full Spectrum LOCA Methodology - EPID L-2021-LLA-0070
ML21252A2142021-09-0101 September 2021
NRR E-mail Capture - Final: Turkey Point Units 3 and 4 - Request for Additional Information Concerning Relief Requests 8 and 9
ML21238A3282021-08-26026 August 2021
RP RFI October 2020
ML20315A0182020-11-10010 November 2020
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
ML20149K6262020-05-27027 May 2020
NRR E-mail Capture - Turkey Point Unit 4 - Request for Additional Information Concerning 2019 Steam Generator Tube Inspections
ML20122A1172020-05-0101 May 2020
NRR E-mail Capture - Final: Turkey Point Units 3 and 4 Request for Additional Information Concerning Emergency Action Level Scheme Change (EPID L-2019-LLA-0271) (FPL: L-2019-203)
ML20104B2232020-04-0909 April 2020
NRR E-mail Capture - Action: Turkey Point Unit 3 - Request for Additional Information Concerning Deferral of Steam Generator Inservice Inspections
ML20084G5622020-03-20020 March 2020
NRR E-mail Capture - Turkey Point Containment Radiation Monitors Request for Additional Information
ML20028C7372019-12-0202 December 2019
Notification of Inspection and Request for Information
ML19184A1002019-07-0303 July 2019
NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4, Request for Additional Information Regarding License Amendment Request 266
ML19101A3312019-04-11011 April 2019
Requests for Additional Information for the Safety Review of the Turkey Point Subsequent License Renewal Application - Set 11 (EPID No. L-2018-RNW-0002) - Enclosure
ML19087A2112019-03-28028 March 2019
Requests for Additional Information for the Safety Review of the Turkey Point Subsequent License Renewal Application - Set 10 (EPID No. L-2018-RNW-0002) - Enclosure
ML19073A0042019-03-14014 March 2019
Safety RAIs - Set 10 - Draft
ML19053A6122019-02-22022 February 2019
Response Date Extension for RAIs Set 8, Revision 1, for the Safety Review of the Turkey Point Subsequent License Renewal Application
ML19037A3982019-02-0606 February 2019
Requests for Additional Information for the Safety Review of the Turkey Point Subsequent License Renewal Application - Set 9 (EPID No. L-2018-RNW-0002) - Enclosure
ML19032A3972019-02-0101 February 2019
SLRA Request for Additional Information RAIs 3.5.2.2.2.6 Revision 1 Set 8 Final
ML19016A2332019-01-16016 January 2019
NRR E-mail Capture - Request for Additional Information - Turkey Point LAR 265 PRA - NFPA RCP Seals - EPID L-2018-LLA-0280
ML18341A0052019-01-15015 January 2019
Requests for Additional Information for the Safety Review of the Turkey Point Subsequent License Renewal Application - Set 8 (EPID No. L-2018-RNW-0002) - Enclosure
ML18341A0042019-01-15015 January 2019
Requests for Additional Information for the Safety Review of the Turkey Point Subsequent License Renewal Application - Set 8 (EPID No. L-2018-RNW-0002) - E-Mail
ML18348A5852018-12-13013 December 2018
Emergency Preparedness Inspection and Request for Information
ML18318A4332018-11-19019 November 2018
Supplemental Information Needed for Acceptance of License Amendment Request to Revise NFPA 805 License Condition for Reactor Coolant Pump Seals
ML18292A7462018-10-31031 October 2018
Requests for Additional Information for the Safety Review of the Turkey Point Subsequent License Renewal Application; Set 7 (EPID No. L-2018-RNW-0002) - Enclosure
ML18269A2282018-10-0404 October 2018
Request for Additional Information for the Safety Review of the Turkey Point Subsequent License Renewal Application - Set 6 (EPID No. L-2018-RNW-0002) - Enclosure
ML18269A2102018-10-0101 October 2018
Requests for Additional Information for the Safety Review of the Turkey Point Subsequent License Renewal Application - Set 4 (EPID L-2018-RNW-0002) - Enclosure
ML18243A0072018-09-17017 September 2018
Requests for Additional Information for the Safety Review of the Turkey Point Subsequent License Renewal Application - Set 3 (EPID No. L-2018-RNW-0002) - Email
ML18259A0002018-09-17017 September 2018
Requests for Additional Information for the Safety Review of the Turkey Point Subsequent License Renewal Application; Set 3 (EPID No. L-2018-RNW-0002) - Enclosure 2
2024-09-06
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2010 Mr. Mano Nazar Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NO.4 - REQUEST FOR ADDITIONAL INFORMATION REGARDING GL 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" (TAC NO. MC4726)
Dear Mr. Nazar:
By letter dated March 19,2009, Florida Power & Light Company (FPL, the licensee), provided responses to the Nuclear Regulatory Commission's (NRC) request for additional information (RAI) regarding Generic Letter (GL) 2004-02, "Potential Impact of debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors." On August 6, 2009, FPL and the NRC held a public teleconference to discuss the March 19th licensee responses. As a result of the August 6 th teleconference, the NRC drafted additional clarifying RAls for Turkey Point Unit 4 Questions 11 and 21.
On February 3, 2010, FPL and the NRC held a public teleconference to discuss open items regarding GL 2004-02 and the licensee's responses to Questions 11 and 21. As a result of the meeting, the NRC staff finds that the additional information contained in the enclosed RAI is needed before we can complete the review.
If you have any questions, please contact me at (301) 415-5888.
j Y
Sincerel1: .
j ,
c; -
Jason C. Paige, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-251
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION GENERIC LETrER 2004-02 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNIT NO.4 DOCKET NUMBER 50-251 Regarding the licensee's response, as discussed during the February 3,2010, public teleconference, to request for additional information (RAI) 11s, the Nuclear Regulatory Commission staff has identified certain inadequacies regarding the structural analysis performed to demonstrate the structural adequacy of the debris interceptors:
- 1. The licensee indicated that "The method of qualification of the structural adequacy of Debris Interceptors (Dis) for the deadweight, seismic, and hydrodynamic load case is outlined. .. ." Are the deadweight, seismic, and hydrodynamic loads combined to formulate the bounding load combination for the Dis? If this is not the bounding load combination, the licensee should indicate what the bounding load combination is for this structure.
- 2. The licensee described the hydrodynamic load as the "maximum differential pressure" across the Dis. It does not appear that the hydrodynamic loading effects of sloshing during a seismic event were incorporated into the licensee's structural analyses of the 01 structures. The licensee should provide the basis for neglecting the effects of loading from sloshing during a seismic event. Additionally, justification should be provided for why this load would not be included in a bounding load combination.
- 3. The licensee incorporated the use of the momentum function, as it applies to open channel flow, to derive the hydraulic loading on the Dis. Based on the licensee's description of the flow through the Dis in their August 11, 2008, supplemental response, it is difficult to decipher whether a water height gradient exists across the 01 boundary.
Based on the licensee's use of the momentum function from Henderson's Open Channel Flow, the hydraUlic load would be a zero value with no height differential. The licensee should provide a range of parameters that would be used to compute this hydraulic load (q, Y1, Y2), using the function outlined.
- 4. The licensee should provide a justification for not considering live loads induced by post-LOCA debris, which may impact the Dis.
- 5. RAI 11 s requested the licensee to provide the results of their structural analysis. No results were provided. The licensee should provide a tabulated data set showing, at a minimum, the maximum and allowable stresses for all of the Dis components structurally analyzed, including structural members, panels, brackets, bolts, anchors, and all other components. Applicable design margins or interaction ratios based on the aforementioned code allowable values should also be included to provide staff with reasonable assurance of the structural integrity of the Dis.
Enclosure
February 18, 2010 Mr. Mano Nazar Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NO.4 - REQUEST FOR ADDITIONAL INFORMATION REGARDING GL 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" (TAC NO. MC4726)
Dear Mr. Nazar:
By letter dated March 19,2009, Florida Power & Light Company (FPL, the licensee), provided responses to the Nuclear Regulatory Commission's (NRC) request for additional information (RAI) regarding Generic Letter (GL) 2004-02, "Potential Impact of debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors." On August 6, 2009, FPL and the NRC held a public teleconference to discuss the March 19th licensee responses. As a result of the August 6th teleconference, the NRC drafted additional clarifying RAls for Turkey Point Unit 4 Questions 11 and 21.
On February 3, 2010, FPL and the NRC held a public teleconference to discuss open items regarding GL 2004-02 and the licensee's responses to Questions 11 and 21. As a result of the meeting, the NRC staff finds that the additional information contained in the enclosed RAI is needed before we can complete the review.
If you have any questions, please contact me at (301) 415-5888.
Sincerely, IRA!
Jason C. Paige, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-251
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsOgcRp RidsNrrDorlDpr LPL2-2 RlF RidsAcrsAcnw_ MailCTR RidsNrrDeEmcb RidsNrrPMTurkey Point RidsRgn2MailCenter BJessup, NRR RidsNrrLABClayton (Hard Copy) RidsNrrDorlLpl2-2 JUribe, NRR ADAMS Accession Number" ML100351213 OFFICE LPL2-2/PM LPL2-2/LA EMCB/BC LPL2-2/BC (A)
NAME JPaiqe BClayton MKhanna BMozafari DATE 02/04/10 02/04/10 02/16/10 02/18/10 OFFICIAL RECORD COPY
