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Category:Meeting Summary
MONTHYEARML23320A2472023-11-17017 November 2023 Constellation - Summary of November 14, 2023, Public Pre-Application Meeting with Constellation Energy Generation, LLC on Adoption of TSTF-591 ML23276A6522023-10-11011 October 2023 Pre-submittal Meeting Summary, September 14, 2023 ML23263B1062023-09-22022 September 2023 R. E. Ginna Nuclear Power Plant - Constellation - Pre-Application Amse 9/18/2023 Meeting Summary ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23181A0612023-06-30030 June 2023 Summary of the June 15, 2023 Public Outreach to Discuss the NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Nuclear Power Station, Units 2 and 3 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 ML22158A3102022-06-0808 June 2022 Summary of May 31, 2022, Public Outreach to Discuss NRC 2021 End of Cycle Performance Assessment of Dresden Power Station, Units 2 and 3, and Quad Cities Power Station, Units 1 and 2 ML22060A0782022-03-0707 March 2022 Summary of Meeting with Constellation Energy Generation, LLC Regarding a Proposed Alternative to Extend the In-service Inspection Intervals 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, ML21195A3942021-07-14014 July 2021 Summary of the June 29, 2021, Public Outreach to Discuss the NRC 2020 End-Of-Cycle Plant Performance Assessment of Dresden Nuclear Power Station, Units 2 & 3, and Quad Cities Nuclear Power Station, Units 1 & 2 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 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 ML21033A6582021-02-0404 February 2021 Summary of October 13, 2020, Presubmittal Meeting Between the U. S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding Post Shutdown Emergency Plan Staffing to Support the Planned Early Closures 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 ML20280A2482020-10-0707 October 2020 Summary of September 22, 2020, Presubmittal Meeting Between the NRC and Exelon Generation Company LLC Regarding Licensing Activities to Support the Planned Early Closures of Byron, Units 1 and 2 and Dresden, Units 2 and 3 ML20234A4422020-08-21021 August 2020 Summary of the July 29, 2020 Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of Dresden Nuclear Power Station, Units 2 and 3 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 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 ML18347B4932019-01-0202 January 2019 Summary of Pre-Application Meeting with Exelon Generation Co., LLC (Exelon) Forthcoming License Amendment Requests to Revise Technical Specification Requirements for Main Steam Isolation Valve Leak Rate Tests 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 ML18297A1722018-10-26026 October 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Planned License Amendment Request to Adopt TSTF-427 ML18220B2772018-08-0808 August 2018 Summary of Open House to Discuss the 2017 End-Of-Cycle Plant Performance Assessment of Dresden Nuclear Power Station Units 2 and 3 ML18120A1772018-05-0101 May 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Draft Guidance for Emergency Response Organization Staffing 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 ML17347B1022017-12-14014 December 2017 Summary of Meeting with Exelon Generation Company, LLC on Its Planned Fleet License Amendment Request to Revise the Minimum Staffing Requirements for Emergency Response ML17317A9002017-11-13013 November 2017 Summary of Teleconference on November 9, 2017, Regarding Verbal Authorization of Relief Request to Use Alternative for Dresden Nuclear Power Station, Units 2 and 3 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) ML17156A5712017-06-0505 June 2017 Summary of May 25, 2017, Open House to Discuss the 2016 End-of-Cycle Plant Performance Assessment of Dresden Nuclear Power Station Units 2 and 3 ML16196A2692016-07-14014 July 2016 Summary of June 30, 2016, Public Meeting with Exelon Generation Company, LLC, to Discuss the 2015 End-of-Cycle Plant Performance Assessment of Dresden Nuclear Power Station, Units 2 and 3 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 ML16035A1762016-02-11011 February 2016 Summary of January 7, 2016, Meeting with Exelon Generation Company, LLC on It'S Planned Fleet License Amendment Request to Revise the Minimum Staffing Requirements for Emergency Response (CAC Nos. MF7162 - MF7183) ML16040A2182016-02-11011 February 2016 January 21, 2016, Summary of Meeting with Exelon Generation Company, LLC Licensing Managers ML15147A6102015-06-15015 June 2015 Summary of the April 7, 2015, Meeting with Exelon Generation Company LLC, on the License Amendment Request to Add Spent Fuel Pool Methodology and Proposed Change to Technical Specification 4.3.1 for Dresden Nuclear Power Station, Units 2 an ML15154A4592015-06-0101 June 2015 Meeting Summary with Public to Discuss the 2014 Annual Assessment Results for Braidwood and Dresden Nuclear Power Stations at the Braidwood City Hall in Braidwood, Illinois ML15051A0442015-03-23023 March 2015 Summary of 1/14/15, Preapplication Meeting with Exelon Generation Company, LLC Regarding Planned Change on Planned Change of Methodology in Updated Final Safety Analysis Report (UFSAR) for Dresden Nuclear Power Station (TAC Nos. MF5469 and ML14344A3252015-01-28028 January 2015 Summary of November 25, 2014, Meeting with Exelon Generation Company, LLC Regarding It'S Application to Add a Methodology to Technical Specification 5.6.5 (TAC Nos. MF3359-MF3362) ML14254A1532014-09-22022 September 2014 8/19/2014, Summary of Closed Meeting with Exelon Generation Company, LLC, Regarding Areva Am Fuel Transition for Dresden and Quad Cities Nuclear Stations ML14226B0122014-09-11011 September 2014 May 19, 2014 Summary of Meeting with Exelon Generation Company, LLC Regarding Areva Xm Fuel Transition for Dresden and Quad Cities Nuclear Stations ML14190B0172014-07-0808 July 2014 June 25, 2014, Summary of Dresden Nuclear Power Station Open House to Discuss the 2013 Annual Assessment Results ML13150A1662013-05-30030 May 2013 Meeting Summary with Public to Discuss the 2012 Dresden Nuclear Power Station Units 2 and 3 End-of-Cycle Performance Assessment ML12179A2952012-06-27027 June 2012 Summary of Open House Meeting to Discuss the 2011 Dresden Nuclear Power Station, Units 2 and 3, End-of-Cycle Performance Assessment ML12110A3112012-05-0303 May 2012 4/10/2012 Summary of Public Meeting with Exelon Generation Company, LLC Regarding Its Future Submittal of Technical Specification Changes of Licensed Operator Eligibility Requirements 2023-09-22
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UNITED STATES A NUCLEAR REGULATORY COMMIS~N WASHINGTON, 0. C. 20555 Mm' z n1976 DOCKET NOS. : 50-237, ~50-254, 50-265, 50-298 LICENSEES: COf.11-'fol,ll.JEALTH EDISON COMPANY, NEBRASKA PUBLIC POWER DISTRICT FACILITIES: DRESDEN UNITS 2 AND 3, QUAD CITIES UNI'l'S 1 AND 2, COOPER l\Tl.JCLEAR STATION SUN?.,lARY OF H.EETING REGAR.Dii\G THE AIR CONTAIN?*1ENT ATHOSPHERE DILUTIO~~
(ACAD) HYDROGEN cor,iTROL SYSTEHS FOR THE ABOVE FACILITIES On April 22, 1976, representatives of the Cor~onwealth Edison Company (CECo), Nebraska Public Power District (NPPD), Sargent and Lundy, Energy Incorporated (EI) and General Electric Company (GE) met with the Regulatory staff to discuss questions relating to the installation of ACAD and Contaim1ent Atmosphere :Monitoring (CAM) systems at Dresden Units 2 and 3, Quad Cities Units 1 and 2, and Cooper Nuclear Station.
Enclosure 1 is a list of meeting attendees. Enclosures 2 and 3 arc questions resulting from preliminary review b~ C. Grimes and J, Knight (DOR-OT) of the CECo ACAfJ submitt;:il. The purpose of the* meeting was to discuss the answers to the questions in enclosures 2 and 3.
Summary P. Bieniarz, o~ Energy Incorpor~ted (EI), consultant to CECo and NPPD for ACAD design analysis, provided answers to questions 9, 11, 12, and 13 of enclosure 2. Methods at calibrating flow measuring devices were discussed. It was agreed that both CECo and NPPD devices would be calibrated to indicate flow rates for gases at standard temperature and pressure (STP). Hr. Bieniarz stated that flow rates in his analysis were for gases at STP.
The NRC staff agreed to clarify its position on implement~ng paragr2ph II.12 of Standard Review Plan 6.2.5 concerning backup purge requirements.
The licensees described their respective CAN systems including bases for selection of* sensing locations .. F. Rudek, GE Space Division, described the new ?latinum-Electrochemical hydrogen detection system that CECo will use. The NRC staff asked CECo to submit additional information on the accuracy, qualif.ication tests, calibration techniques, halide poisoning characteristics, and de::;ign life of the system. CECo agreed to ~rovide this information. NPFJ intends to modify the existing I
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l hydrogen detection syatem at Cooper Station for use aB the CA11 system *
- . The NRC may have to re-evaluate the Cooper hydrogen monitoring system in light of its being used as a safety system.
ACAD system design and operation were discussed. NPPD agreed to submit performance curves for their AC.AD compressors. CECo has not yet
- procured compressors so perfo~nce curves will be provided later.
During discussion of question 8 of enclosure 2, it became apparent that CECo and EI were not in agreer:i.ent on ACAD operating procedures.
The NRC staff asked CECo to clarify its intentions so that an orderly review of its ACAD. submittal might continue. CECo agreed to do this.
In the course of answering questions 13 throu8h 16 of enclosure 3, lI CECo agreed to submit additional data regarding design criteria and single failure analysis of instrullientation and control 9ystems and isolation valve pilot sol~noids, a description of the Instrument Air system, nnd physical sepnration of instrumentation and control cables for the Cl\11 and AC1ill systems.
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Hichael 11*. Fletcher
- Operating Reactors Branch 02 Division of Operating Reactors
Enclosures:
DISTRIBUTION:
- 1. Attendance List *Docket (5)
- 2. Questions NRC PDRs
- 3. Questions Local PDRs 'I NRR Reading ORB-2 Reading MNFletcher
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1 Form AEC-318 (Rey. 9*53) AECM 0.<40
- U. 9. GOVERNMENT PRINTJNQ OFFICEI 1974-6%8*1615
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> ** e ENCLOSURE NO. 1 ATTJJ:IDA.i.~.CE LIST COMHONWF.ALTH EDISON COMPAHY G. Abrell
- R. T. Steen C. A. Lindberg NEBRASKA PUBLIC POWER DISTRICT T. E. Kissam J. M. Pilant R. E. Wilbur 1
GE - SPACE DIVISION F. Rudek SARGENT & LUNDY F. Tsai.
- w. J. Robinson.
ENERGY INCORl'ORATh:D P. B. Bieniarz NRC - STAFF R. P. Snai.der M. H. Fletcher J. Slider
- c. Grimes J. E. Knight
- c. W. Thayer OFFICE~*
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- Oesc~ibe in more detail the dest~n ~n~ principl~*of operation of the hydrogen detectors. Provide a sketch *.
2~ What periodic .calibration is to be pe~forrned to assure a correct read-In~ wh~n needed? .. *
- 3. *Are there any poss i b 1e pa 1 Ja::tium poi son ing mechan i $ms. at th~ detector 1ocations7 . . *-- .. -- *. .
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What are the effects of radiat.ion .(expected during a LOCA) on the out-put of the hydrogen detection system? *
- 6. What is the accuracy of the calibration gas?
- 7. What is the accuracy of the hydrogen detection system with the sensor elevated to the LOCA temperature?
- 8. Describe the installation details of the hydrogen detector that assures that the calibration gas is not diluted during the calibration.
- 9. Describe the qualification tests performed on the hydrogen detectors which qualify them for a LOCA environment.
- 10. Is it *possible for the detectors located in the suppression cha~ber to be irr*nerscd in water at any time during a LOCA and if so what effect does this have on th~ output?
- 11. Provide logic diagrams for the.control systems.
- 12. The drawings appear to be incorrect for the flow control valves for both the air injection and venting systems. Explain the purpcse of the iir supply which is applied directly to the solenoid valve and give the controlled valve position for loss of ~ir ~nd lo~£ of electrical power.
Describe the power train assignment to instrumentation, i:ontrol system, an~ isolation valve pilot solenoids.
Describe the air supply system to the control and. isolation valves.
Describe the criteria employed in the 'design i.e. Codes, Standards, Reg Guides etc. To whJch these systems are designed. *.
- 16. Describe the p~ysical separation fo~ electrical, instrumentation, irid
. control cables for the CAM & ACAD Syster.is *
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" e MEETING
SUMMARY
DISTRIBtrrION:
- Docket NRC PDR Local PDR ORB #2 Reading NRR Reading B. Rusche E. Case
- v. Stello K. R. Goller D. Eisenhut T. J. Carter B* A. Purple G. E. Lear R. w. Reid L. c. Shao R.* L.
- Baer A. Schwencer B. K. Grimes Project Manager - R. Silver, P. o** Connor, M.- Fletcher OELD OI&E (3)
RMD.iggs R. Fraley, ACRS (16)
T. B. Abernathy J. R. Buchanan NRC
Participants:
~ . 1,*(_e#)~~