Letter Sequence Meeting |
---|
|
|
MONTHYEARHNP-10-125, Request for Exemption in Accordance with 10 CFR 50.12 Regarding Use of M5 Alloy in Fuel Rod Cladding2011-01-19019 January 2011 Request for Exemption in Accordance with 10 CFR 50.12 Regarding Use of M5 Alloy in Fuel Rod Cladding Project stage: Request HNP-11-067, License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis2011-08-22022 August 2011 License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis Project stage: Request ML11238A0782011-08-31031 August 2011 ANP-3011(NP), Rev. 1, Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis. Project stage: Request ML11272A0642011-09-29029 September 2011 NRR E-mail Capture - Acceptance Review for ME6999- Shearon Harris Unit 1, Realistic LBLOCA Methodology (TS 6.9.1.6.2) Project stage: Acceptance Review ML11336A1592011-12-0202 December 2011 Notice of Closed Meeting with Carolina Power & Light Company Regarding Shearon Harris Nuclear Plant, Unit 1 (TAC ME6999), the Purpose of the Meeting Is to Discuss the August 22, 2011, Large Break Loss of Coolant Accident Submittal Project stage: Meeting ML11354A2912011-12-13013 December 2011 Meeting Slides - Meeting with Carolina Power and Light Discussion of ANP-3011 Project stage: Request ML11339A0502011-12-28028 December 2011 Acceptance of Requested Licensing Action Regarding Realistic Large Break Loss-of-Coolant Accident (TAC No. ME6999)(HNP-11-067) Project stage: Acceptance Review HNP-12-028, Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-0282012-01-11011 January 2012 Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-028 Project stage: Meeting ML12076A1422012-01-11011 January 2012 Meeting Topics - Suggested Discussion Items Regarding Large Break Loss-of-Coolant Accident Submittal - Shearon Harris Nuclear Power Plant, Unit 1 Project stage: Meeting ML12076A1652012-01-11011 January 2012 Meeting Slides - Harris Realistic LBLOCA Question Response Meeting Project stage: Meeting ML11354A3782012-02-0808 February 2012 Meeting Handout - Meeting with Carolina Power and Light Suggested Discussion Items Regarding Realistic Large Break Loss-of-Coolant Accident Project stage: Meeting ML11354A2892012-02-0808 February 2012 Summary of Meeting with Carolina Power and Light to Discuss Realistic Large Break Loss-of-Coolant-Accident Project stage: Meeting HNP-12-023, License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis Response to Request for Additional Information2012-02-23023 February 2012 License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis Response to Request for Additional Information Project stage: Response to RAI ML12073A2922012-02-24024 February 2012 License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Project stage: Request ML12067A1802012-02-29029 February 2012 ANP-3011Q1(NP), Revision 000, Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis. Enclosure 4 Response to Request for Additional Information (Non-Proprietary) Project stage: Response to RAI ML12067A2322012-03-16016 March 2012 Request of Withholding Information from Public Disclosure Project stage: Other ML12067A2312012-03-20020 March 2012 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance HNP-12-050, License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Revised Technical Specification Page2012-04-0202 April 2012 License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Revised Technical Specification Page Project stage: Request ML12076A1412012-04-0505 April 2012 Summary of Meeting Summary with Carolina Power & Light to Discuss Realistic Large Break Loss-of-Coolant Project stage: Meeting ML12076A1032012-05-30030 May 2012 Issuance of Amendment Regarding the Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break Loss-of-Coolant Accident Analysis Project stage: Approval 2012-02-23
[Table View] |
|
---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML24100A8062024-04-0909 April 2024 Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024 ML23341A1522023-12-0707 December 2023 December 11, 2023 Public Meeting - RIPE Exemption Request - Licensee Slides ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22153A3842022-06-0606 June 2022 Duke Energy Presentation Material for June 6, 2022 Public Meeting on GSI-191 Closeout ML22091A1332022-04-0101 April 2022 Bru Har Combined 2021 Assessment Meeting Slides ML20100G6342020-04-0909 April 2020 Revised- Bru 2019 Annual Assessment Meeting Slides ML19318F2912019-11-18018 November 2019 Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request ML19214A0562019-08-0707 August 2019 Presentation: Duke Energy Presubmittal Meeting - August 7, 2019 ML19077A3672019-03-14014 March 2019 March 14, 2019 Pre-submittal Meeting TS DNBR Safety Limit Change LAR Meeting Slides ML18351A1342018-12-20020 December 2018 December 20, 2018 Pre-submittal Meeting Slides for Escw Risk-Informed LAR ML18333A1822018-11-0808 November 2018 Pre-Submittal Meeting - November 8, 2018 - License Amendment Request for Shearon Harris Nuclear Power Plant Emergency Plan Revision ML17331A6272017-11-29029 November 2017 Duke Energy Pre-Submittal Meeting Presentation, Brunswick, Harris, and Robinson License Amendment Requests Regarding 10 CFR 50.69 ML17250B2382017-08-30030 August 2017 TMRE Presubmittal NRC ML17044A0892017-03-0202 March 2017 EDG SR Presubmittal Meeting March 2, 2017 ML16267A0292016-09-29029 September 2016 SFP Pre-Submittal Meeting Slides - BWR Storage Rack Inserts, Updated NCS Analysis at Harris Nuclear Plant ML16112A2932016-05-0202 May 2016 05/02/2016 Presentation for Closed Pre-Submittal Meeting with Duke Energy Progress, Inc., to Discuss Fuel Reload Design Methodology Reports and Proposed LAR Re. H. B. Robinson And Shearon Harris Plants (CAC Nos. MF7443 And MF7444) RA-15-0041, Attachment 1, Affidavit and Attachment 3, Pre-Submittal Meeting Presentation Materials on DPC-NF-2010-A and DPC-NE-2011-P Methodologies (Redacted)2015-09-18018 September 2015 Attachment 1, Affidavit and Attachment 3, Pre-Submittal Meeting Presentation Materials on DPC-NF-2010-A and DPC-NE-2011-P Methodologies (Redacted) ML14129A3352014-05-0909 May 2014 Summary of Category 1 Public Meeting - Annual Assessment of Shearon Harris Nuclear Plant ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13212A3372013-07-31031 July 2013 NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting NEI 01-01, NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting2013-07-31031 July 2013 NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting NEI 01-01, 7/31/2013 NRC Public Meeting Presentation on NEI 01-012013-07-30030 July 2013 7/31/2013 NRC Public Meeting Presentation on NEI 01-01 ML13218B3372013-07-30030 July 2013 Handout for 7/30/13 Conference Call Re. Harris Emergency Response Facility Activation Timeliness and Criteria ML13211A3782013-07-30030 July 2013 7/31/2013 NRC Public Meeting Presentation on NEI 01-01 ML13204A2562013-07-0909 July 2013 Handout - LOOP Voltage Setpoint Change Presubmittal Conference Call - July 9, 2013 ML13170A3352013-06-13013 June 2013 Presentation - NRC Special Inspection Meeting - Harris Reactor Pressure Vessel ML12277A0272012-10-0202 October 2012 Slides - Summary of Meeting with Duke Energy Carolinas to Discuss Noncenservative Technical Specifications License Amendment Requests ML12242A4322012-08-28028 August 2012 Summary of Category 1 Public Meeting - Regulatory Conference and Predecisional Enforcement Conference ML12206A3252012-08-0707 August 2012 G20120513/EDATS: OEDO-2012-0436 - Briefing Book for Meeting with Duke Energy on August 7, 2012 ML12188A0712012-07-11011 July 2012 G20120473/ EDATS: OEDO-2012-0404 - Briefing Book - Briefing Package for Meeting with Duke Energy on July 11, 2012 ML12107A0012012-04-16016 April 2012 Meeting Summary - Category 1 Public Meeting - Annual Assessment of Shearon Harris Nuclear Plant ML11354A3782012-02-0808 February 2012 Meeting Handout - Meeting with Carolina Power and Light Suggested Discussion Items Regarding Realistic Large Break Loss-of-Coolant Accident HNP-12-028, Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-0282012-01-11011 January 2012 Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-028 ML12076A1652012-01-11011 January 2012 Meeting Slides - Harris Realistic LBLOCA Question Response Meeting ML1118011132011-06-29029 June 2011 NRC Staff Response to NFPA 805 Transition FAQ 10-0059, Revision 1 ML1113704082011-05-0909 May 2011 Meeting Slides Regarding Human Performance Improvement ML1107301382011-04-21021 April 2011 February 22, 2011, Summary of Pre-application Meeting with Carolina Power & Light and Representatives Regarding Upcoming BWR Boraflew License Amendment Request W/ Public Meeting Slides ML1111000242011-04-20020 April 2011 Meeting Summary - Shearon Harris - List of Attendees ML1014102712010-05-18018 May 2010 Shearon Harris Nuclear Plant Annual Assessment Meeting Slides ML0922900342009-08-17017 August 2009 08/19/09-Meeting Slides for 11th International Seminar on Fire Safety in Nuclear Power Plants and Installations, Risk-Informed, Performance-Based Fire Protection: a U.S. Regulatory Perspective ML0916605042009-06-24024 June 2009 04/21-22/2009 Summary of Category 2 Meeting with Progress Energy Carolinas, Inc., and Duke Energy Carolinas, LLC, to Discuss Topics Involving the License Amendment Requests to Transition Shearon, Unit 1 and Oconee to NFPA 805 ML0904906122009-02-18018 February 2009 NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, February, 2009 ML0829601532008-11-17017 November 2008 Summary of Meeting with Progress Energy Carolinas, Inc., to Discuss Shearon Harris Unit 1 National Fire Protection Association Standard 805 License Amendment Request ML0830800052008-10-31031 October 2008 Meeting Slides, Progress Energy Public Meeting, NRC Region II Visit ML0820703912008-07-17017 July 2008 Meeting Handouts from 7/17/08 Public Meeting on the Harris and Oconee LARs to Transition to NFPA-805 M080717, M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection2008-07-17017 July 2008 M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection ML0818407352008-06-20020 June 2008 NFPA-805 Workshop Handouts - Harris Fire PRA Lessons Learned ML0818407312008-06-20020 June 2008 NFPA-805 Workshop Handouts - Harris NFPA-805 Results and Lessons Learned ML0812003342008-04-17017 April 2008 NFPA 805 Transition Pilot Plant FAQ Log - April 2008 2024-04-09
[Table view] |
Text
SUGGESTED DISCUSSION ITEMS [AS MODIFIED DURING THE MEETING]
LARGE BREAK LOSS-OF-COOLANT-ACCIDENT SUBMITTAL SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 PROGRESS ENERGY DOCKET NO. 50-400
- 1. The submitted ECCS evaluation is not clear as it does not appear to consider the droplet shattering model separate from the fuel relocation study. See, for instance, Figure 6-17.
- a. Please characterize the impact of enabling the droplet shattering model without modeling the fuel relocation.
- b. Similarly, please show the sensitivity of the fuel relocation model study to fuel relocation packing factor. Consideration should be made to include a range of packing factors that is more inclusive of the available data, i.e., 30-80 percent. It would be beneficial if this sensitivity is shown using the Shearon Harris Nuclear Plant (SHP) limiting-peak clad temperature (PCT) case, and using an evaluation model variant that does not include the droplet shattering enhancement.
- 2. Address whether droplet shattering is calculated on all flow blockage (non-vertical) surfaces in the S-RELAP5 calculation. If not, provide the flow blockage surfaces which are assumed to cause droplet shattering.
- 3. Page 122 of ANP-3011(P), Harris Nuclear Plant Unit 1Realistic Large Break LOCA Analysis states, In the present model, the rupture blockage ratio [which is correlated to the number of droplets to yield a maximum atomization factor], , is taken from the swelling and rupture correlation.
- a. Address whether droplet shattering is calculated only against the hot pin rupture, or the additional flow blockage areas (i.e., balloon/burst regions, spacer grids, etc.) assumed to be present upstream of the hot pin rupture location, and address implementation of these models in S-RELPA5.
- b. If the additional flow blockage areas are not based on pre-transient core geometry, discuss how the locations and sizes of flow blockages are distributed.
- 4. On page 123 of ANP-3011(P), it is stated, It can be seen that the code predicted the peak cladding temperature variation well.
The data is so tightly clustered that the degree of agreement is difficult to ascertain.
Please tabulate the data to provide a more quantitative indication. Address how well the S-RELAP5 modification predicted the data.
- 5. Comparative data demonstrate the global effects of the droplet shattering phenomena; however, the correlation as implemented discriminates between large and small droplets and the behavioral differences between the two. Validate droplet size distribution as implemented in model. Explain how the Sugimoto/Murao correlation applies to the scenario in which it is applied.
- 6. Explain how droplet shattering model incorporates the following droplet-dependent heat transfer effects:
- a. Inter-phase heat transfer;
- b. Fluid-structural interactions including cladding, balloon, and spacer heat transfer to coolant; and
- c. Validate heat transfer modeling for these separate effects.