Letter Sequence Meeting |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement
Administration
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
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MONTHYEARML0506900352005-03-0303 March 2005
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
ML0515100172005-05-31031 May 2005
Draft RAI on Response to Generic Letter 2004-02
Project stage: Draft RAI
ML0515303042005-06-0303 June 2005
6/3/05, Calvert Cliffs - RAI Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
Project stage: RAI
ML0520200572005-07-15015 July 2005
Response to NRC Request for Additional Information Re NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Response to RAI
ML0603803582006-02-0909 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
ML0609500512006-04-12012 April 2006
Approval of Extension Request for Completion of Corrective Actions in Response to Generic Letter 2004-02
Project stage: Other
ML0618702222006-06-30030 June 2006
Update of Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Basis Accidents at Pressurized Water Reactors
Project stage: Other
ML0626405472006-09-20020 September 2006
Update of Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Other
ML0633407022006-12-18018 December 2006
Unit No.1 - Approval of Extension Request for Completion of Corrective Action in Response to Generic Letter 2004-02
Project stage: Other
ML0712703722007-05-0202 May 2007
Revision to Generic Letter 2004-02 Response
Project stage: Other
ML0734504992007-12-10010 December 2007
Attachment (1) Request for Extension of the Completion Date for Corrective Actions Related to Generic Letter 2004-02
Project stage: Request
ML0734504982007-12-10010 December 2007
Request for Extension for Completion of Activities Related to Generic Letter 2004-02
Project stage: Request
ML0811307392008-04-22022 April 2008
Revision to Generic Letter 2004-02 Response
Project stage: Other
ML0817101052008-06-18018 June 2008
Attachment 1, Request for Extension of the Completion Date for Corrective Actions Related to Generic Letter 2004-02
Project stage: Request
ML0827404892008-09-30030 September 2008
Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Supplement
ML0827404972008-09-30030 September 2008
Attachment 2, ECCS and CS System Figures
Project stage: Other
ML0833003202008-12-0404 December 2008
Request for Additional Information Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors-Calvert Cliffs Unit 1 & 2
Project stage: RAI
ML0906807672009-03-0404 March 2009
Request for Additional Information: Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Supplement
ML1009500782010-04-12012 April 2010
Request for Additional Information Generic Letter 2004-02 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2-
Project stage: RAI
ML1011903842010-05-0606 May 2010
Notice of Forthcoming Conference Call with Calvert Cliffs to Discuss Supplemental Responses to Generic Ltr. 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Request
ML1014708982010-06-0707 June 2010
Summary of Meeting with Calvert Cliffs Nuclear Power Plant, LLC, to Discuss Supplement to Responses to Generic Letter 2004-02
Project stage: Meeting
ML1028701002010-09-30030 September 2010
Draft Responses to NRC Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents on Pressurized-Water..
Project stage: Draft Response to RAI
ML1029306502010-10-20020 October 2010
Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC Regarding McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2,
Project stage: Other
ML1030810242010-11-10010 November 2010
Summary of November 1, 2010, Meeting with Duke to Discuss Responses to Generic Letter (GL) 2004-02 (Tac Nos. MC4673, MC4674, MC4692, and MC4693)
Project stage: Meeting
ML1031903612010-11-10010 November 2010
Response to Request for Additional Information Regarding Generic Letter 2004-02
Project stage: Response to RAI
ML12356A0852012-12-27027 December 2012
January 8, 2013 - Notice of Teleconference with Calvert Cliffs Nuclear Power Plant, LLC
Project stage: Meeting
ML13038A5432013-01-24024 January 2013
Chemical Effects Head Loss Experiment (Chle) Test Protocol for Calvert Cliffs Nuclear Power Plant (CCNPP-CHLE-002, Revision 0d)
Project stage: Request
ML13038A6042013-01-24024 January 2013
PIRT Item Summary
Project stage: Request
ML13038A4872013-01-24024 January 2013
CCNPP-CHLE-001, Revision 0c, Chemical Effects Head Loss Experiment (Chle) Test Plan for Calvert Cliffs Nuclear Power Plant
Project stage: Request
ML13038A5782013-01-24024 January 2013
Chemical Effects Pirt Considerations for Calvert Cliffs Nuclear Power Plant (CCNPP-CHLE-003, Revision 0b)
Project stage: Request
ML13086A5512013-01-24024 January 2013
MC4672 & MC4673 - CCNPP-CHLE-003, Rev 0c Chemical Effects PIRT Considerations Excerpts with Respect to GL2004-02, GSI-191
Project stage: Other
ML13030A3482013-02-0707 February 2013
Summary of Teleconference with Calvert Cliffs Nuclear Power Plant, Units 1 and 2 to Discuss Proposed Risk-Informed Approach to the Resolution of Generic LTR 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Des
Project stage: Meeting
ML13045A1822013-02-19019 February 2013
March 20, 2013, Notice of Forthcoming Teleconference with Calvert Cliffs and Nrc/Nrr Staff to Have Additional Discussions of Licenseess Proposed Path for Resolution of Generic Letter 2004-02
Project stage: Meeting
ML13050A5112013-02-19019 February 2013
MC4672-3 Corrected Notice -Public Meeting on March 20, 2013 Re-GL2004-02
Project stage: Request
ML13086A5502013-03-0101 March 2013
MC4672 & MC4673, CCNPP-CHLE-002, Rev 0e Chemical Effects Experimental Protocol with Respect to GL2004-02, GSI-191
Project stage: Request
ML13088A2202013-03-18018 March 2013
MC4672 & MC4673 - CCNPP-CHLE-005, Rev 1 Chemical Effects Autoclave Experimental Plan with Respect to GL2004-02, GSI-1 91
Project stage: Request
ML13086A5492013-03-20020 March 2013
MC4672 & MC4673 - Licensee Presentation-Category 1, Public Meeting on March 20, 2013 with Respect to GL2004-02, GSI-191
Project stage: Meeting
ML13091A0552013-04-10010 April 2013
Summary of Meeting on March 20, 2013, with Calvert Cliffs Nuclear Power Plant, LLC, to Discuss the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation D
Project stage: Meeting
ML13149A3942013-05-20020 May 2013
Chemical Effects Head Loss Experiment (Chle) Test Protocol for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-002, Revision 0 May 20, 2013
Project stage: Request
ML13149A3992013-05-20020 May 2013
Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005, Revision 2, May 20, 2013
Project stage: Request
ML13149A4052013-05-23023 May 2013
Metals BENCH-TOP Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-006, Revision 0, May 23, 2013
Project stage: Request
ML13148A3962013-05-29029 May 2013
Forthcoming Meeting with Calvert Cliffs Nuclear Power Plant, LLC to Discuss Licensees Proposed Plan for Resolution of GL 2004-02
Project stage: Meeting
ML13179A3132013-07-11011 July 2013
June 12, 2013 Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculati
Project stage: Meeting
ML13224A0942013-08-0606 August 2013
Chemical Effects PIRT Considerations for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-003, Revision 0c
Project stage: Request
ML13224A1032013-08-0808 August 2013
CCNPP-CHLE-007, Revision 0c, Coatings Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant
Project stage: Request
ML13226A0902013-08-14014 August 2013
Notice of Forthcoming Meeting with Constellation Energy Nuclear Group, LLC
Project stage: Meeting
ML13304B4032013-11-0101 November 2013
Notice of Forthcoming Meeting with Constellation Energy Nuclear Group, LLC,
Project stage: Meeting
ML13319A9392013-11-13013 November 2013
Ri GSI-191 November 2013 Meeting with NRC Rev 0
Project stage: Request
ML13310B9292013-12-0606 December 2013
Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During .
Project stage: Meeting
ML14014A0392014-01-29029 January 2014
Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During
Project stage: Meeting
2010-06-07
[Table View] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 7, 2010 LICENSEE:
Calvert Cliffs Nuclear Power Plant, LLC FACILITY:
Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2
SUBJECT:
SUMMARY
OF MAY 24,2010, MEETING WITH CALVERT CLIFFS NUCLEAR POWER PLANT, LLC TO DISCUSS SUPPLEMENTAL RESPONSES TO GENERIC LETTER 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED WATER REACTORS" (TAC NOS. MC4672 AND MC4673)
On May 24,2010, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Calvert Cliffs Nuclear Power Plant, LLC (the licensee) and their contractors. The meeting was held via a toll-free audio telephone conference call that was available to interested members of the public. [See the Meeting Notice dated May 6, 2010 (Agencywide Document Access Management System (ADAMS) Accession No. ML101190384).] The purpose of the meeting was to discuss remaining issues identified during NRC staff review of the Calvert Cliffs Nuclear Power Plant Generic Letter (GL) 2004-02 Supplemental Responses. A list of attendees is provided in the enclosure.
The NRC staff issued a Request for Additional Information (RAI) regarding GL 2004-02 to the licensee on April 12, 2010 (ADAMS Accession No. ML100950078). The letter requested the licensee to be prepared to discuss their proposed responses with the staff prior to formal submittal. The licensee provided draft responses and the staff discussed each proposed response in detail with the licensee and their contractor. The following summarizes the discussion of each proposed response:
RAI1 - 9 The NRC staff concludes that the draft responses to questions 1 through 9 are acceptable as is and do not require further modifications.
RAI10 The NRC staff questioned the debris size distribution for Nukon and Thermal Wrap insulation systems. The licensee stated that its response will remain consistent with the safety evaluation for NEI-04-07, "Pressurized Water Reactor Sump Performance Evaluation Methodology," and will consider the impact on its test protocol.
RAI11 The licensee previously used a zone of influence (ZOI) of 9.8 pipe diameters (D) for Marinite board. As discussed in the draft response, the licensee will use a ZOI of 17.0D for Marinite board in future testing and analyses. The licensee's response should identify the "before" and "after" Marinite debris quantities when changing from 9.8D to 17.0D. With this change, the response will be acceptable.
RAI12 The NRC staff concludes that the draft response to question 12 is acceptable as is and does not require further modification.
- 2 RAI13 This was a multi-part question focusing on the single failure of a low-pressure safety injection (LPSI) pump to trip at the time of switchover from the injection phase to the recirculation phase of the postulated accident.
RA113.a The licensee's response should state that if procedure changes to manually trip the LPSI pump are not made, debris addition will be made at the higher flowrate.
RA113.b The NRC staff concludes that the draft response to question 13.b is acceptable as is and does not require further modification.
RA113.c The licensee will provide containment basement drawings showing the sump and physical obstructions to flow. The licensee will re-evaluate their draft response to provide better support for coating transport assumptions.
RA113.d The NRC staff concludes that the draft response to question 13.d is acceptable as is and does not require further modification.
RA113.e The licensee's draft response stated that they evaluated the net positive suction head margin, assuming a LPSI pump failed to stop operating, in a conservative manner. The licensee's response should provide further discussion explaining the conservatisms. Specifically, the response should (1) discuss why the friction losses in Table 13-1 are considered conservative and (2) state that the pump flow rates in Table 13-1 are provided at run-out conditions. With these changes, the response will be acceptable.
RAI14 The licensee's response stated that coating chips were not observed to transport towards the sump. The licensee should provide containment drawings indicating the flow paths to the sump and consider providing the computational fluid dynamics results and describe the coating types. Since the NRC staff expects non-zero coatings transport, holistic arguments about why the coatings would not have a major impact on the head loss would be helpful.
RA115-20 The NRC staff concludes that the draft responses to questions 15 through 20 are acceptable as is and do not require further modifications.
RAI21 With regard to the sump level calculations, the NRC staff asked what assumptions were made with respect to water droplets in transition from containment sprays, water holdups on vertical and horizontal surfaces, and water shrinkage due to cooling. The licensee's response should describe the modifications that will increase the containment sump level. The licensee should also state that a small break at the top of the pressurizer is not a limiting break or would not result in a significant head loss.
RAI22 The NRC staff concludes that the draft response to question 22 is acceptable as is and does not require further modification.
- 3 The licensee agreed to provide revised responses to RAI questions 13.c and 14 by June 4, 2010. The NRC staff agreed to review these revised responses and provide feedback to the licensee by June 11, 2010. Finally, the licensee agreed that, by the end of June 2010, they will provide their schedule for submitting final responses to all RAls.
Members of the public were not in attendance. Therefore, Public Meeting Feedback forms were not received.
Please contact me at 301-415-1364 regarding any questions.
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv
LIST OF ATIENDEES MAY 24120101 MEETING WITH CALVERT CLIFFS NUCLEAR POWER PLANT, LLC SUPPLEMENTAL RESPONFS TO GENERIC LE;TTER 2004-02 C?!IVf}rt Cliffs Nuclear Power Plant LLC ALlQN Pat Furio Crag Sellers Mike Gahan Larry Smith Andre Drake Doug Lauver John Swailes MPR Associates Washington ConSUlting Steve Kinsey Steve Unikewicz Maryland Degartment of Natural Resources Susan Gray t'Juclear Regulatory Commission Mike Scott John Lehning Steve Smith Matt Yoder Doug Pickett
- 3 The licensee agreed to provide revised responses to RAI questions 13.c and 14 by June 4, 2010. The NRC staff agreed to review these revised responses and provide feedback to the licensee by June 11, 2010. Finally, the licensee agreed that, by the end of June 2010, they will provide their schedule for submitting final responses to all RAls.
Members of the public were not in attendance. Therefore, Public Meeting Feedback forms were not received.
Please contact me at 301-415-1364 regarding any questions.
Ira!
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL1-1 r/f RidsACRSAnew_MaiICTR RidsNrrDorlLpl1-1 MKotzalas, EDO RidsNrrLASLittle RidsOgcMailcenter RidsRgn'l MailCenter RidsNrrPMCalvertCliffs RidsNrrDssSsib SSmith, SSIB JLehning, SSIB MYoder, CSGB ADAMS Accession No. ML101470898 OFFICE LPL1-1/PM LPL1-1/LA SSIB/BC LPL1-1/BC NAME DPickett SLittie MScott NSalgado DATE 06/01 /10 06/01 /10 06/04/10 06/07/10
