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MONTHYEARML15321A3702015-12-0101 December 2015 GSI-191 Program Strainer Head Loss Testing and Option 2b Closure Approach Project stage: Request ML15327A2242015-12-0101 December 2015 Strainer Head Loss Test 6 Rejection Project stage: Request ML15337A0362015-12-16016 December 2015 Summary of December 1, 2015, Meeting with Exelon Generation Company, LLC, Regarding Risk-Informed Approach Resolution of Generic Letter, 2004-02 Project stage: Meeting ML16242A1782016-09-0101 September 2016 Presentation Slides from Public Meeting Regarding Calvert Cliffs GSI-191 Resolution Update Project stage: Request ML16273A3772016-09-29029 September 2016 Memo to File: E-mail from R.Guzman to T.Tate Regarding Meeting Summary of Calvert Cliffs Nuclear Power Plant Units 1 and 2 - GSI-191 Resolution and GL 2004-02 Closure Project stage: Meeting 2015-12-16
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Category:Meeting Summary
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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. 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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 ML16117A1972016-04-21021 April 2016 4/21/2016 - Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Annual Assessment Meeting, and Sign-in Sheet and Summary Data Sheet ML16075A4562016-04-12012 April 2016 February 24, 2016, Summary of Meeting with Exelon Generation Company, LLC, to Discuss the Flaw Indication in the Calvert Cliffs Unit 1 Pressurizer Safety Valve Dissimilar Metal Weld ML16085A3292016-04-0606 April 2016 Summary of March 22, 2016, Meeting with Exelon Generation Company, LLC, on Proposed License Amendment Request to Adopt ANSI 3.1-2014 Operating Training Standards 2024-01-09
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December 16, 2015 LICENSEE: Exelon Generation, LLC
FACILITY: Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NOS. 1 AND 2 - SUMMARY OF DECEMBER 1, 2015, MEETING WITH EXELON GENERATION COMPANY, LLC, REGARDING RISK-INFORMED APPROACH RESOLUTION OF GENERIC LETTER 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" (CAC NOS. MC4672 AND MC4673)
On December 1, 2015, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Exelon Generation, LLC, (or the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the strainer chemical effects head loss testing and the option 2b simplified risk-informed closure plan for the resolution of Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors" for the Calvert Cliffs Nuclear Power Plant (Calvert Cliffs). The meeting notice and agenda, dated November 17, 2015, is available in the Agencywide Documents Access and Management System (ADAMS) Accession No. ML15328A047. A list of attendees is provided as Enclosure 1.
The licensee presented information regarding the strainer chemical effects head loss testing and the option 2b simplified risk-informed closure plan to resolve GL 2004-02. The licensee's slides can be viewed at ADAMS Accession Nos. ML15321A370 and ML15327A224.
The licensee presented information on the results of its strainer head loss testing. The licensee discussed the test parameters including the flow rate assumed when chemical precipitates may be present at the strainer. The NRC staff did not have an immediate concern, but did have questions related to the timing of precipitation to determine if the flow rate at the time of chemical addition was appropriate.
The licensee stated that it is pursuing modifications to the recirculation actuation signal logic to ensure that if a low pressure safety injection (LPSI) pump fails to trip, there will be adequate time to stop flow from the LPSI pump before the time when precipitates may form and reach the sump strainer.
At the previous public meeting, held August 20, 2015, the NRC staff queried the licensee on its basis for rejecting test 6. At The December 1, 2015, public meeting the licensee discussed its documented basis for rejecting test 6. The NRC staff questioned the location of the strainers and whether there was the possibility of having water cascading near the strainer that would produce agitation similar to the stirring conditions seen in test 6. The licensee clarified that their strainers are located in the basement next to a cavity and would not have the agitation conditions equivalent to the stirring in test 6. The staff noted that assurance was needed that the test protocol was followed as there were errors made during test 6. The licensee then further described precautions and oversight during the tests that helped to ensure the tests were performed correctly.
The licensee noted that it would like to use test 5 to establish the head loss in its closure plan.
The licensee had determined that test 5 had the highest head loss below the threshold that was set.
The licensee proceeded to discuss its simplified risk-informed approach for resolution. The licensee described how the threshold break size was defined, as well as how the changes in core damage frequency and large early release frequency were calculated, and how the deterministic analysis fits into the risk-informed approach.
While describing the applicable head loss test for the risk-informed approach, the NRC staff asked the licensee if it had head loss test plots for all of the tests that were conducted. The staff noted that having these plots for all of the tests would be useful in their review.
The NRC staff queried the licensee on how the smaller breaks and non-piping breaks were considered in its analyses. The staff informed the licensee that a justification for how these breaks were modeled would be needed in the licensee's eventual submittal. One of the most significant issues discussed was the need for the licensee to justify its methodology for sizing breaks and determining ZOIs for longitudinal welds in the reactor coolant system piping. The NRC staff also questioned the licensee on the amount of dissimilar metal welds (or welds with known degradation mechanisms) that were included in the total population of welds that would pose a potential problem if failed.
At the end of the presentation the licensee spoke about a potential approach to responding to GL 2004-02 without requesting a license amendment. The NRC staff acknowledged that the licensee is looking into this option. The staff had several questions as to how the licensee would accomplish this. It was determined that this may be a topic of discussion at the next public meeting and in the meantime the staff can discuss this internally and the licensee can prepare a presentation to the staff. The licensee agreed to further investigate the following items raised by the NRC staff during the meeting:
1. Provide the head loss plots for all of the strainer head loss test runs. 2. Determine the maximum concentration of aluminum in a post-LOCA pool as predicted by WCAP-16530 for Calvert Cliffs. 3. Provide justification for the assumption that chemicals precipitates will not form until after the containment sprays are terminated (i.e., lower emergency core cooling system flow rate). 4. Determine the number of dissimilar metal welds (or welds with degradation mechanisms other than design and construction) included in the sub-set of welds that could pose a problem if the weld failed.
5. Provide the basis for how non-piping loss of coolant accident contributors were considered in the licensee's analyses. 6. Justify the exclusion of small pieces of debris from strainer head loss tests, and that tests that included only fines are adequate for determining debris limits. 7. Provide a representative set (e.g., the top 100) of sequences in the probabilistic risk analysis that would lead to core damage due to debris generation and transport. 8. Confirm the materials used in the reactor coolant system piping. The NRC staff will follow-up with internal piping experts to discuss the treatment of potential breaks in longitudinal welds in piping.
Members of the public were in attendance. No feedback from the public was received. No members of the public made any comments during the meeting.
Please direct any inquiries to me at 301-415-2549, or Alexander.Chereskin@nrc.gov.
/RA/ Alexander N. Chereskin, Project Manager Plant Licensing Branch I-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
5. Provide the basis for how non-piping loss of coolant accident contributors were considered in the licensee's analyses. 6. Justify the exclusion of small pieces of debris from strainer head loss tests, and that tests that included only fines are adequate for determining debris limits. 7. Provide a representative set (e.g., the top 100) of sequences in the probabilistic risk analysis that would lead to core damage due to debris generation and transport. 8. Confirm the materials used in the reactor coolant system piping. The NRC staff will follow-up with internal piping experts to discuss the treatment of potential breaks in longitudinal welds in piping.
Members of the public were in attendance. No feedback from the public was received. No members of the public made any comments during the meeting.
Please direct any inquiries to me at 301-415-2549, or Alexander.Chereskin@nrc.gov. /RA/ Alexander N. Chereskin, Project Manager Plant Licensing Branch I-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 LPLI-1 R/F RidsAcrsAcnw_MailCTR RidsNrrDorlLplI-1 RidsNrrPMCalvertCliffs RidsNrrLAKGoldstein RidsRgn1MailCenter TWertz, NRR RidsNrrDeEsgb RidsNrrDssSsib M. Yoder, NRR S. Smith, NRR P. Klein, NRR M. Diaz-Colon, NRR L. Robinson, NRR A. Guzzetta, NRR A. Obodoako, NRR J. Stang, NRR A. Russell, NRR M.Waters, OEDO ADAMS Accession Nos.: PKG: Meeting Notice: ML15328A047 Meeting Summary: ML15337A036 Handouts: ML15321A370 and ML15327A224 OFFICE NRR/DORL/LPLI-1/PM NRR/DORL/LPLI-1/LANRR/DSS/SSIB NRR/DRA/APLA NAME AChereskin KGoldstein VCusumano SRosenberg DATE 12/09/2015 12/ 04 /2015 12/15/2015 12/10/2015 OFFICE NRR/DE/ESGB NRR/DORL/LPLI-1/BCNRR/DORL/LPLI-1/PM NAME GKulesa TTate AChereskin DATE 12/11/2015 12/16/2015 12/16/2015 OFFICIAL RECORD COPY LIST OF ATTENDEES DECEMBER 1, 2015, MEETING WITH EXELON GENERATION, LLC TO DISCUSS CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1, AND 2 RISK-INFORMED APPROACH FOR GL 2004-02 RESOLUTION U.S. Nuclear Regulatory Commission A. Chereskin S. Smith M. Yoder P. Klein M. Diaz-Colon A. Russell C.J. Fong T. Tate S. Laur*
A. Obodoako*
Exelon Generation, LLC, and Contractors C. Sellers M. Gahan K. Greene A. Drake P. Rominc G. Hughes E. Federline A. Elliot J. Landale J. Quinn*
S. Kinsey* Members of the Public Ron Holloway*
T. Sande*
- via teleconference Enclosure