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MONTHYEARML0515100172005-05-31031 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 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 Calvert Cliffs, Units 1 & 2 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 Calvert Cliffs 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 ML0827404972008-09-30030 September 2008 Calvert Cliffs Nuclear Plant, Attachment 2, ECCS and CS System Figures Project stage: Other 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 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-(TAC Nos. MC4672 and MC4673) 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 Catawba Units 1 & 2, 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: Request 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 (TAC Nos. MC4672 and MC4673) Project stage: Response to RAI 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 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 ML13050A5112013-02-19019 February 2013 MC4672-3 Corrected Notice -Public Meeting on March 20, 2013 Re-GL2004-02 Project stage: Request ML13045A1822013-02-19019 February 2013 March 20, 2013, Notice of Forthcoming Teleconference with Calvert Cliffs and Nrc/Nrr Staff to Have Additional Discussions of Licensees'S Proposed Path for Resolution of Generic Letter 2004-02 Project stage: Meeting 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 Licensee'S 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 ML14206B0012014-02-14014 February 2014 Long-Term Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. CCNP-CHLE-011, Revision 2 Project stage: Request ML14142A3232014-05-22022 May 2014 NRR E-mail Capture - Calvert Cliffs May 21, 2014 Public Meeting Presentation Project stage: Request ML14206A9932014-07-25025 July 2014 Conrete Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. CCNPP-CHLE-010, Revision 1 Project stage: Request ML14206B1442014-11-0606 November 2014 May 21, 2014 Summary of Meeting with Exelon Generation Company, LLC, to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02 Project stage: Meeting ML14206A2062014-11-0707 November 2014 July 2, 2014 Summary of Meeting with Exelon Generation Company, LLC to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02 Project stage: Meeting ML15154B5572015-06-17017 June 2015 May 19, 2015 Summary of Meeting with Exelon Generation Company, LLC, on Calvert Cliffs Nuclear Power Plant, Units 1 and 2 - Chemical Effects Testing for Resolution of Generic Letter 2004-02 (TAC Nos. MC4672 & MC4673) Project stage: Meeting ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach Project stage: Request 2013-11-01
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Category:Meeting Summary
MONTHYEARML24155A1992024-06-0303 June 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Meeting Summary ML24128A2512024-05-14014 May 2024 Summary of April 11, 2024, Public Meeting with Constellation Energy Generation, LLC Regarding Proposed Alternative to Implement American Society of Mechanical Engineers Operation and Maintenance Code Case OMN-32 ML24113A2872024-04-25025 April 2024 Summary of Public Meeting with Constellation Energy Generation, LLC Regarding Hooded Masks ML23352A0592024-01-0909 January 2024 Summary of December 11, 2023, Meeting with Constellation on Alternative Request Involving Carbon Fiber Reinforced Polymer Composite ML23320A2472023-11-17017 November 2023 Constellation - Summary of November 14, 2023, Public Pre-Application Meeting with Constellation Energy Generation, LLC on Adoption of TSTF-591 ML23263B1062023-09-22022 September 2023 R. E. Ginna Nuclear Power Plant - Constellation - Pre-Application Amse 9/18/2023 Meeting Summary ML23179A0012023-06-28028 June 2023 6/7/2023 - Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - Meeting Summary ML23055A0352023-03-24024 March 2023 Summary of February 23, 2023, with Constellation Energy Generation, LLC on Proposed Changes to Emergency Plans to Revise Emergency Action Levels ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML22264A1992022-11-14014 November 2022 Summary of August 22, 2022, Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Performance Monitoring of Steam Generator Welds (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and ML22187A1462022-07-0606 July 2022 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Meeting Summary ML22159A2272022-06-0808 June 2022 Summary of May 10, 2022, Pre-Application Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, Llc, Regarding a Proposed License Amendament Request (Lar) for Calvert Cliffs Nuclear Power Plant ML22144A0202022-05-26026 May 2022 Summary of Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Proposed Alternative for Examinations of Certain Pressurizer Welds at Calvert Cliffs ML22066A0012022-03-22022 March 2022 Summary, January 10, 2022, Closed Meeting with Exelon Generation Company, Llc, Proposed Relief Request for Alternative Repair of Buried Saltwater Piping with Carbon Fiber Reinforced Polymer Composite System ML21333A1532021-11-30030 November 2021 Summary of November 16, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Extend the Inservice Inspection Interval ML21237A0412021-08-30030 August 2021 Summary of the July 27, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use Case OMN-28, ML21228A0742021-08-27027 August 2021 Summary of July 13, 2021, Meeting with Exelon Generation Company, LLC Concerning License Amendment Request for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Concerning Spent Fuel Pool Cooling Design Basis Change (L-2021-LLA-0112) ML21176A0822021-07-0606 July 2021 June 15, 2021, Summary of Meeting with Exelon Generation Company, LLC Vessel Nozzle Repair Related to a Planned Request for an Alternative Related to Reactor Pressure ML21161A1082021-06-25025 June 2021 Summary of Pre-Application Meeting with Exelon Generation Company, LLC on Planned Submittal of License Amendment Request for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Concerning Spent Fuel Pool Cooling Design Basis Change ML21139A1852021-06-22022 June 2021 Summary of Meeting with Exelon Generation Company, LLC Regarding Its Requested Alternative to Eliminate Certain Documentation Requirements for the Replacement of Pressure Retaining Bolting ML21011A2822021-01-21021 January 2021 Summary of January 6, 2021, Presubmittal Meeting Between the NRC and Exelon Generation Company, LLC Regarding Licensing Activities to Support the Planned Early Closures of Byron, Unit Nos. 1 and 2 and Dresden, Units 2 and 3 ML20351A2832020-12-18018 December 2020 Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Exemption to Reduce the Frequency of Updates to Its Inservice Testing and Inspection Programs ML20342A3522020-12-10010 December 2020 Summary of November 13, 2020, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alterantive to Certain Documentation Requirements for the Replacement of Pressure Retaining Bolting (EPID-L-2020-LRM-0102) ML20323A0332020-12-0101 December 2020 Summary of November 4, 2020, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Reduce the Frequency of Updates to Its Inservice Testing and Inspection Programs ML20272A0132020-10-0707 October 2020 Summary of September 3, 2020, Meeting with Exelon Generation Company, LLC Concerning Supplemental Position Indication Testing Interval Alternative Request ML20197A2722020-07-15015 July 2020 2020 Beaver Valley, Calvert Cliffs, Limerick Peach Bottom, Susquehanna Annual Assessment Webinar Summary ML20181A0002020-06-29029 June 2020 Summary of 6/24/20 Meeting with Exelon Generation Company, LLC Regarding Planned Request for Alternative to Supplemental Valve Position Indication Testing Requirements for Braidwood, Calvert Cliffs, Clinton, Limerick, Nine Mile, Peach Botto ML19326A3152019-12-0303 December 2019 Summary of November 18, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Supplemental Valve Position Indication Testing Requirements ML19326C3582019-12-0303 December 2019 Summary of November 20, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Revise the Quality Assurance Program ML19162A0272019-06-21021 June 2019 Summary of June 4, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Extend the Test Interval for Safety Relief Valves ML19136A2752019-05-15015 May 2019 Aam 2019 Meeting Summary ML19135A1052019-05-15015 May 2019 Aam Summary Data Sheet of 2018 Plant Performance ML20108F0902019-04-20020 April 2019 April 15, 2020, Meeting Summary with Exelon Generation Company, LLC Regarding Planned Request to Defer Submittal of Owner'S Activity Report (Braidwood 2,Byron 2,Calvert Cliffs 1, LaSalle 1, Limerick 1, Nine Mile Point 2, Quad 2, R. E. Ginna ML19036A8832019-02-0707 February 2019 Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use ASME Code Case N-879 ML18354B1712019-01-0202 January 2019 Summary of December 19, 2018, Meeting with Exelon Generation Company, LLC Regarding the Use of Boiling Water Reactor Vessel and Internals Project Guidelines ML18325A1712018-11-28028 November 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Planned Fleet License Amendment Request to Revise Technical Specifications for High Radiation Areas ML18292A8202018-10-24024 October 2018 October 4, 2018, Summary of Pre-Application Meeting with Exelon Generation Co., LLC on Planned Submittal of Licensing Action for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Risk-Informed Categorization and Treatment ML18197A2292018-07-20020 July 2018 Summary of Meeting with Exelon Generation Company, Llc, on Planned Submittal of Risk Informed License Amendment and Exemption Requests Concerning Resolution of Generic Issue 191 (CAC Nos. MF8521 and MF8522; EPID L-2016-LRM-0001) ML18197A4362018-07-18018 July 2018 May 21, 2018, Summary of Meeting with Exelon Generation Company, LLC, on Planned Submittal of Risk-Informed License Amendment and Exemption Requests Concerning Resolution of Generic Issue 191 ML18191A9962018-07-13013 July 2018 Plants, - Summary of June 14, 2018, Meeting with Exelon Generation Company, LLC, on Planned Submittal of License Amendments Concerning Alternating Current Sources and Control Room Emergency Ventilation System ... ML18120A1772018-05-0101 May 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Draft Guidance for Emergency Response Organization Staffing ML18096B0782018-04-12012 April 2018 Summary of Meeting with Exelon Generation Company, LLC, on Planned Submittal of License Amendments Concerning Emergency Operation Facility and Technical Support Center (EPID L-20118-LRM-0016) ML18096B1982018-04-0606 April 2018 Summary of Public Annual Assessment Meeting Calvert Cliffs Nuclear Power Plant Dated April 6, 2018 ML18065A8362018-03-0707 March 2018 Summary of February 27, 2018, Meeting with Exelon Generation Company, LLC Planned Fleet License Amendment Request to Relocate Staff Qualification Requirements from TSs to the Quality Assurance Topical Report ML18058A5232018-03-0101 March 2018 Summary of February 26, 2018, Meeting with Exelon Generation Company, LLC Regarding Proposed Alternative to the Main Steam Isolation Valve Testing Requirements ML17249A3202017-09-18018 September 2017 Summary of Meeting with Exelon Generation Company, LLC, on Planned Submittal of Risk-Informed License Amendment and Exemption Requests Concerning Resolution of Generic Issue 191 ML17184A0092017-07-10010 July 2017 Summary of June 29, 2017, Meeting with Exelon Generation Company, LLC, on Proposed Changes to Emergency Plans to Revise Emergency Action Levels (CAC Nos. MF9779-MF9801) ML17143A3572017-05-23023 May 2017 Summary of Public Meeting Calvert Cliffs Nuclear Plant ML16228A0622016-08-15015 August 2016 Summary of July 26, 2016, Public Meeting on Status of Associated Effects Submittals Related to the Reevaluated Flood Hazards at Exelon Generation Company, LLC Sites as Part of the Response to Near-Term Task Force Recommendation 2.1, Floodin ML16118A1322016-04-26026 April 2016 4/21/2016 - Summary of Annual Assessment Meeting for Calvert Cliffs Nuclear Power Plant 2024-06-03
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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 11,2013 LICENSEE: Calvert Cliffs Nuclear Power Plant, LLC FACILITY: Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2
SUBJECT:
SUMMARY
OF JUNE 12,2013, MEETING WITH CONSTELLATION ENERGY GROUP, INC., TO CONTINUE DISCUSSIONS ON THE PROPOSED RISK-INFORMED APPROACH TO THE RESOLUTION OF GENERIC LEITER 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" WITH A FOCUS ON REFINED CHEMICAL EFFECTS TESTING (TAC NO. MC4672 AND MC4673)
On June 12, 2013, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Constellation Energy Group, Inc., the licensee at NRC Headquarters, Three White Flint North, 11601 Landsdown Street, Rockville, Maryland.
The purpose of the meeting was to discuss the licensee's proposed risk-informed approach to the resolution of Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors (PWRs)" with a focus on refined chemical effects testing for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (Calvert Cliffs). The meeting notice and agenda, dated May 29,2013, is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML13148A396. A list of attendees is provided as Enclosure 1. but may not be all inclusive.
The licensee (1) presented an overview of Calvert Cliffs' GL 2004-02 resolution plan; (2) discussed Calvert Cliffs' test plans and protocol, (CCNPP-CHLE-005, "Chemical Effects Autoclave Experiment Test Plan," Revision 2 [ADAMS Accession No. ML13149A399]; CCNPP CHLE-006. "Metals Bench-Top Autoclave Experiment Test Plan," Revision 0 [ADAMS Accession No. ML13149A405]; and CCNPP-CHLE-002, "Chemical Effects Head Loss Experimental Test Protocol," Revision 0 [ADAMS Accession No. ML13149A394]); (3) discussed the outstanding phenomena identification and ranking table (PIRT) items; and (4) discussed an open item from the March 20. 2013, public meeting and future meeting dates. (See Enclosure 2).
Discussion of CCNPP-CHLE-005. "Chemical Effects Autoclave Experiment Test Plan"
- 1. The NRC staff questioned an apparent discrepancy between test duration of 21 hours and 24 hours in the documentation. The licensee clarified that the testing will confirm the exact time needed at 195 degrees Fahrenheit (OF) to match an equivalent material dissolution at the elevated temperatures. Tests will be run for 24 hours with periodic water sampling to determine when the lower temperature corrosion is equal to the higher temperature corrosion.
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- 2. The NRC staff questioned whether the CCNPP-CHLE-005 test had already been completed.
This question stemmed from language in the CCNPP-CHLE-002 document that indicated the results of autoclave testing was already complete. The licensee clarified that the testing had not been performed, and in fact a facility for the testing had not yet been selected.
- 3. The NRC staff noted that the material quantities listed in the experimental parameters appeared to be very small. The NRC staff comment is based on a concern that such small samples of material may not be representative of the bulk material properties. The licensee indicated that they plan to use autoclaves with a 5-8 gallon capacity, much larger than the 1 liter capacity originally envisioned. The licensee's plan to use larger capacity autoclaves was informed by scoping tests with small sample sizes that experienced repeatability issues.
The larger autoclave size is also expected to reduce the effects of measurement precision on the tests.
- 4. Other discussion items of note regarding CCNPP-CHLE-005 included sample size measurement accuracy, concrete surrogate chemical similarity with the plant, buffer addition timing, and chemistry analysis.
Discussion of CCNPP-CHLE-006, "Metals Bench-Top Autoclave Experiment Test Plan"
- 1. CCNPP-CHLE-006 testing may be conducted in a facility different from the CCNPP-CHLE 005 tests due to time constraints. However, these tests will also be done in relatively large autoclaves with volumes between 5 and 8 gallons.
- 2. The NRC staff questioned the method of buffer addition for the test and the impact that it may have on material dissolution. The licensee will consider the best methodology to create a realistic pH profile in the tests.
- 3. The NRC staff noted that many of the comments for CCNPP-CHLE-005 also apply to CCNPP-CHLE-006 due to the similarity of the test plans. Comments regarding flow over coupons, pH profile, chemical sampling, reactive material sample size, water used to soak fiber, etc. should be considered for both test plans.
- 4. The licensee stated that the tests are run for 48 hours because they expect the majority of the dissolution to occur during the early, high temperature period. Temperature is decreased to 170 of in 48 hours. The NRC staff noted that there may be some delay in timing of dissolution due to synergistic effects between materials in the tests. Based on the results of the CCNPP*CHLE-006 tests, materials may be omitted from the long term test if; (1) they cannot be detected in solution (no dissolution), and (2) the material is not identified as having a synergistic effect with other materials. The licensee also noted that the test matrix may evolve as they learn more about the interactions between materials or the effects of other test parameters. The licensee will also consider taking samples at times during the tests instead of only at the end. This may help determine saturation limits for various materials and may provide useful trending information.
-3 Discussion of CCNP-CHLE-002, "Chemical Effects Head Loss Experiment Test Protocol"
- 1. The NRC staff asked if a facility had been selected for this testing. The licensee stated that they have multiple competitive bids, but that they have not made a final selection at the time of this meeting.
- 2. The licensee stated that the fluid volume of the loop will be about 750 gallons. The NRC staff noted that the flow rate through the debris bed is stated to be 1 gallon per minute (gpm). The NRC staff also noted that the flow through the loop parallel to the debris bed is about 6 gpm resulting in a total flow rate of 7 gpm. The turnover time of the loop is, therefore, greater than 100 minutes. Given the volume of the loop relative to the flow through the debris bed, the NRC staff stated that it was important to characterize the test loop response, as well as the debris bed response to precipitate during shakedown testing.
For example, the time between addition of precipitate in shakedown tests and a head loss response, along with reaction kinetics, should be considered when determining hold times for temperature plateaus.
- 3. Except for debris bed fiber that is not representing plant debris, the NRC staff stated that if fiber is rinsed, boiled, or soaked prior to placing in the test loop that the licensee should consider whether it is necessary to include the water in the test because it could influence chemical reactions. The licensee stated that they would evaluate the need to include this water in the testing.
- 4. The NRC staff requested that the licensee validate that the flow over the coupons and baskets is representative of the plant. Dense packing of baskets and coupons to the point that flow is precluded should be avoided. The licensee stated that they had considered this and that the packing of coupons and materials in baskets would be such that flow around materials would be representative of the plant. Materials will not be tightly packed into baskets
- 5. Regarding coatings material in the test tank, areas are scaled based on the surface area of failed zone of influence coatings. For unqualified coatings, they are to be painted on coupons and allowed to fail as they would in the plant. The NRC staff questioned whether fresh coatings would fail similarly to aged and irradiated coatings in the plant. The licensee will consider attempting to remove the need to include coatings from the chemical effects test. Some industry information indicates that they may not be a large contributor to chemical species in the pool. The licensee may perform additional autoclave testing to validate that their plant specific coatings will not contribute to chemical effects. The NRC staff indicated that autoclave testing may be useful to address questions about unqualified coating chemical leaching and to potentially reduce the burden of having to include coatings in each CCNPP-CHLE-002 test tank.
- 6. The NRC staff questioned the ratio of submerged versus sprayed unqualified coatings in the test tank. The test plan indicated that most of the coatings would be in the spray zone. The NRC staff noted that the unqualified coatings should be considered as failed and submerged per the NRC staffs review guidance on coatings. This concern will either be addressed by the licensee in the revised test plan, or may be superseded depending on the outcome of the potential autoclave work discussed in item number 5 above.
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- 7. For baseline tests to determine the sensitivity of the debris bed to WCAP type precipitates, precipitate concentration should be based on the screen area, not the volume of the loop.
The licensee stated that they will consider the appropriate tests required to validate that the new facility test beds are capable of detecting small amounts of WCAP precipitate. The licensee stated that they understood that the amount of precipitate added to the test should be based on the area of the debris bed.
- 8. Regarding the duration that the spray will run in the test, the licensee stated that for the initial test the sprays will be maintained for the entire test. If various break scenarios are performed during subsequent testing, the spray duration will be as predicted for the scenario.
- 9. The NRC staff disagreed with the statement in the test plan which states that a 10 percent or less change in head loss as negligible. From an NRC staff perspective, a 10 percent or less change in the measured head loss due to chemical effects still needs to be accounted for in the overall evaluation. The NRC staff stated that previous technical reviews by the NRC staff considered the conservative assumptions in the evaluation, as well as remaining uncertainties. The licensee stated that they are currently re-evaluating how results from the testing will be used in the final analysis.
- 10. Other Notes: The licensee stated that they will ensure that the loop is designed to preclude hideout of any materials. Also, the scaling description in the procedure will be rewritten to be more specific for each class of material. The licensee will work on scaling of the buffer baskets in the test facility and validate that the concrete and other fibrous material surrogates are appropriately representative for the chemical tests.
Discussion of Outstanding Phenomena Identification and Ranking Table (PIRTlltems
- 1. Concerning radiological effects, the licensee stated that they would include strong acids to address the effects of pool pH caused by radiolysis. The licensee noted that fibrous insulation materials are similar to low density fiberglass used in high activity filters and adverse effects had not been noted on the filters. Since discussion of PIRT items was not on the meeting agenda, the NRC staff was not prepared to discuss them in detail.
- 2. For coatings, the licensee noted that alkyd coatings have been observed to release trace amounts of chemicals that would not significantly impact pool chemistry and that epoxy coatings were judged not to contribute to the post loss-of-coolant-accident chemical environment and were excluded from integrated chemical effects test (ICET). The NRC staff noted that the epoxy considered during ICET was qualified coating and may be significantly different from non-qualified coatings. Also, the alkyd coating study was not formally reviewed by the NRC staff. The licensee may perform autoclave testing on plant-specific coatings to determine whether they should be included in the long term chemical effects testing.
- 3. With respect to the PIRT item on agglomeration, the licensee stated that they would do nothing to inhibit it.
- 5 The NRC staff and the licensee agreed to include PIRT items on the next meeting agenda so that both parties could be better prepared to discuss the issues.
Members of the public were in attendance. Public Meeting Feedback forms were not received.
Please direct any inquiries to me at 301-415-1016,0 Nadiyah.Morgan@nrc.gov.
hiya!s. Morgan, Project Manager lant Licensing Branch 1-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosures:
- 1. List of Attendees
- 2. License Handout - Calvert Cliffs Chemical Effects in Risk-Informed GSI-191 Resolution cc w/encls: Distribution via Listserv
LIST OF ATTENDEES JUNE 12,2013, MEETING WITH CONSTELLATION ENERGY GROUP, INC.
RISK-INFORMED APPROACH TO THE RESOLUTION OF GL 2004-02 CALVERT CLIFFS NUCLAR POWER PLANT. UNIT NOS. 1 AND 2
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Andre Drake l Ron Holloway i Robert Peterson Ernie Kee South Texas Project Nuclear Operating Company r-"-"" ~ ------.,-..."~~-,"'~-~,-~.--~--------." ..., r*-~* .... *'~-Y_r~_.~"".~-. ~.hh~_~" .._____
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i Steve Blossom i South Texas Project Nuclear Operating Company Enclosure 1
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Calvert Cliffs Chemical Effects in Risk Informed GSI-191 Resolution Fourth Discussion With NRC Staff June 12, 2013 Enclosure 2
Agenda
- Introductions
- Objectives for Meeting
- Overview of Calvert Cliffs GSI-191 Resolution Plan
- Detailed review of CCNPP Test Plans and Protocol
- Discussion of Chemical Effects PIRT Items
- Open Items from March 20, 2013 Meeting
- Schedule for future periodic meetings CENGw a joint venture 01 _ _ _ _ _--,
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CCN PP Attendees
- Tom Konerth - Supervisor Mechanical Design
- Andre Drake - Lead Design Engineer GSI-191
- Ken Greene - Licensing Engineer
- John Swailes - Project Manager GSI-191
- Craig Sellers - Project Manager RI GSI-191
- Andrew Henni - Lead Design Engineer RI GSI-191
- Robert Peterson - Independent Oversight RI GSI-191
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Objectives of Meeting
- Review & Work Towards Agreement on Autoclave Test Plans - CCNPP-CHLE-OOS & CCNPP-CHLE-006
- Review & Work Towards Agreement on Integrated Test Protocol- CCNPP-CHLE-002
- Obtain Feedback and Resolve Concerns on Conceptual Design of Integrated Test Facility
- Address Unresolved Issues
- Present Propose Schedule for Future Meetings
- Capture Staff Issues and Concerns CENG"
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Overview of CCNPP GSI-191 Resolution Plans
- SECY-12-0093 Option 2
- Option 2a - Refined Chemical Effects Testing
- CCNPP Single GSI-191 Issue is Chemical Effects
- Conventional Debris Bed Head Loss Negligible j "v' ~_f
- Insignificant Chemical Effects Possible Deterministic Resolution
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- Option 2b - Risk-Informed Approach
- Alternative Solution if 2a Unsuccessful
- Defense in Depth if 2a Successful
- Consistent with STP Approach
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Autoclave Test Plan - CCNPP-CHLE-OOS
- High Temperature Portion of LOCA Profile
- Compare Corrosion/Dissolution
- 10 Hours at Temp Profile >195°F
- 24 Hours at Constant 195°F
- Determine Appropriate Time Duration to Account for High Temperature Portion of LOCA
- Section-by Section Review CENG~
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Autoclave Test Plan - CCNPP-CHLE-006
- Metals Corrosion Experiment
- Investigate..-Sing!e and Synergistic Corrosion Effects of Differing ~ Combinations --------
- Determine Which Metals are Most Appropriate for Integrated Chemical Effects Head Loss Tests
- Section-by Section Review CENG~,
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Integrated Chemical Effects Screening Test CCN PP-CH LE-002
- Time Duration at 195°F - CCNPP-CHLE-OOS
- Metal Contribution - CCNPP-CHLE-006
- Debris Bed Sensitivity and Repeatability Demonstrated During Shake Down Testing
- Turbidity Criteria Developed During Shake Down Testing
- Section-by-Section Review CENG,~
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Revised Test Facility Conceptual Design r-"7,---""- iSTOP, lH!NK. ACI A"O ~EVIEW F4 HEAtTIeN CH~~S£H PR:!A~~15~l~~~ER
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HEAT ExCHANGER L80P 1 I r="" - 1I I I I 11£'" ~~~<[}"fJli~\'tLE' P"I:
- Does Staff have Concerns with CCNPP Plans to Begin Detailed Design and Fabrication of Facility?
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Chemical Effects PIRT Items
- Radiological Considerations
- Effects on Pool pH Addressed by Addition of Strong Acids
- Materials Similar to LDFG Used as High Activity Filters
- Radionuclides in Debris Bed Flushed by Strainer Flow
- Alkyd Coatings Release Organics and Trace Quantities of Metals with Negligible Impact on Pool Chemistry
- Epoxy Coatings Are Judged to Not Contribute to the Post LOCA Chemical Environment and were Excluded from ICET
- Nothing Will be Done to Prevent or Inhibit Agglomeration CENG.
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Open Items - March 20, 2013 Meeting
- 1" & %" DP Instrument Piping/Tubing
- %" Pressure & Level Instrument Piping/Tubing
- %" Reactor Head Vent Piping CENG..
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Schedule for Future Periodic Meeting
- Debris Bypass/Penetration Test Plan
- Interim Chemical Effects Bench-Top Test Results
- September 2013 Oi<<. _ - r-, \
- Chemical Effects Bench-Top Test Results
- Final Chemical Effects Screening Test Protocol CENG."
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ML13179A313 Handouts: ML OFFICE DORULPLI-1/PM DORULPLI-1/LA DElESGB/BC DSS/SSIB/BC DORULPLI-1/BC NAME NMorgan KGoldstein GKulesa SBailey RBeali (A)
(DPickett for)
DATE 7/3/13 7/1/13 7/8/13 7/9/13 7/11/13}}