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Category:Meeting Briefing Package/Handouts
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23272A0622023-09-29029 September 2023 Ultimate Heat Sink Temperature Tech Spec Limit Change ML23229A0132023-08-17017 August 2023 Relief Request for Alternative Requirements for Byron Unit 1 Reactor Pressure Vessel Inservice Inspection Intervals NRC Meeting Handout ML23229A4832023-08-17017 August 2023 RR 20-Year ISI Pre-Submittal NRC Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation 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 ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting ML21320A0672021-11-17017 November 2021 NRC Pre-Submittal Meeting - Braidwood, Unit 2, LAR for Removal of Unit 2 License Condition for Closure Stud Hole Location No. 35 (EPID L-2021-LRM-0089) (Slides) ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21166A3722021-06-15015 June 2021 End-of-Cycle Meeting Presentation ML21130A6252021-05-12012 May 2021 NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides) ML21078A0952021-03-0808 March 2021 Session W20 - James Petty - Slide Deck 3 ML20258A0302020-09-22022 September 2020 Decommissioning Licensing Action Submittal Plan for Byron and Dresden Stations Early Shutdowns ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20209A5322020-07-24024 July 2020 2019 Braidwood and Byron End-of-Cycle Presentation ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20091L0432020-04-0101 April 2020 Public Meeting Handout for Braidwood, Unit 2, April 1, 2020 ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML18018B4432018-01-25025 January 2018 Summary of December 17, 2017, Closed Meeting with Exelon Generation Company, LLC, Regarding Tvel Lead Test Assemblies to Be Placed in the Braidwood Reactor (EPID 000976/05000456/L-2017-LRM and 000976/05000457/L-2017-LRM-0047 ML17296A2032017-10-0303 October 2017 Accident Tolerant Fuel Lead Test Assembly Deployment ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML16334A4642016-12-0505 December 2016 Westinghouse Pre-Application Meeting: License Amendment Request to Modify Byron Station Facility Operating License in Support of the Molybdenum-99 Isotope Production Project - December 5, 2016 ML16327A3702016-11-25025 November 2016 Enclosure 3: Exelon Byron Station Design (Meeting Handout) ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML16062A4222016-03-0202 March 2016 Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal ML15342A1012015-12-0909 December 2015 TORMIS Computer Code Methodology Public Meeting Slides ML15232A6832015-08-27027 August 2015 Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request ML15209A9722015-07-30030 July 2015 Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations 2024-01-08
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23272A0622023-09-29029 September 2023 Ultimate Heat Sink Temperature Tech Spec Limit Change ML23229A0132023-08-17017 August 2023 Relief Request for Alternative Requirements for Byron Unit 1 Reactor Pressure Vessel Inservice Inspection Intervals NRC Meeting Handout ML23229A1722023-08-17017 August 2023 RR Pen-75 Pre-Submittal NRC Meeting Handout ML23229A4832023-08-17017 August 2023 RR 20-Year ISI Pre-Submittal NRC Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides 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 ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting ML22098A0512022-04-11011 April 2022 2 Cycle 25 High Burnup Lead Test Assembly NRC Pre-Submittal Meeting on April 22, 2022 (EPID L-2022-LRM-0022) (Slides) ML21320A0672021-11-17017 November 2021 NRC Pre-Submittal Meeting - Braidwood, Unit 2, LAR for Removal of Unit 2 License Condition for Closure Stud Hole Location No. 35 (EPID L-2021-LRM-0089) (Slides) ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21166A3722021-06-15015 June 2021 End-of-Cycle Meeting Presentation ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21130A6252021-05-12012 May 2021 NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides) ML21078A0952021-03-0808 March 2021 Session W20 - James Petty - Slide Deck 3 ML20258A0302020-09-22022 September 2020 Decommissioning Licensing Action Submittal Plan for Byron and Dresden Stations Early Shutdowns ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20209A5322020-07-24024 July 2020 2019 Braidwood and Byron End-of-Cycle Presentation ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20091L0432020-04-0101 April 2020 Public Meeting Handout for Braidwood, Unit 2, April 1, 2020 ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 ML18086A8432018-03-27027 March 2018 NUREG-1021, Revision 11 Implementation ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17291B0282017-10-17017 October 2017 Submittal of Slide Package Westinghouse Encore Lead Test Rod Program Byron Unit 2 (Proprietary/Non-Proprietary) ML17296A2032017-10-0303 October 2017 Accident Tolerant Fuel Lead Test Assembly Deployment ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations ML16334A4452016-12-0505 December 2016 Pre-submittal Meeting Byron UT RR Presentation ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16062A4222016-03-0202 March 2016 Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal ML15342A1012015-12-0909 December 2015 TORMIS Computer Code Methodology Public Meeting Slides ML15232A6832015-08-27027 August 2015 Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request ML15209A9722015-07-30030 July 2015 Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood ML15204A5052015-07-23023 July 2015 EPRI Tech Basis for Brd-Byr Head RR ML15204A4932015-07-23023 July 2015 Bb Station Requests for Relief for Alternate Examination Frequency ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations 2024-01-08
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Byron and Braidwood Recent Potential Over Power Issues November 19, 2003 CONTACTS:
NRR/DE: Angelos Marinos (301.415.2911)
NRR/DLPM: George Dick (301.415.3019)
NRR/DIPM: Jack Foster (301.415.3647)
Back und Initial testing of the CROSSFLOW Ultrasonic Flow Measurement (UFM) System at Byron and Braidwood was completed in late 1998 and early 1999. The instruments were implemented for use at Braidwood in June 1999 and at Byron in May 2000.
1 The CROSSFLOW instrumentation at Byron and Braidwood, like many other plants, is used for venturi measurement correction. Note: Byron and Braidwood use this system for venturi calibration and verification, not for measurement uncertainty recapture.
Briefing 2003-08 2
Backqround i During the last week of August, Exelon, in response to a difference in thermal power between Byron Unit 1 and Braidwood Unit 1, added additional instrumentation to Byron Unit 1 and began continuous monitoring of feed flow instruments to verify accuracy of UFM system.
On 8/29/03 Byron reported to the NRC (EN 40117) that results of the continuous monitoring and additional instrumentation indicated that there were signal abnormalities or contaminations associated with the UFM System.
Briefing 2003-08 3
Background
-i?There were inconsistencies in the UFM signals on all four loops for Byron Unit 1 and one loop for Byron Unit 2 and therefore they subsequently reduced power. Sum of the loops was not equal to the total at the manifold.
1ýFrom analysis, it was determined that Byron Units 1 and 2 had potentially exceed their licensed thermal power limit by approximately 1.5% and 0.33%, respectively.
.1 As a result of the recent over power issues at Byron, Braidwood investigated both Units 1 and 2.
Briefing 2003-08
Background
'],rOn 8/31/03, the investigation revealed that Braidwood Unit 2 (EN 40123) had potentially exceed their licensed thermal power limit by approximately 0.39%.
1 The power level for all affected units was reduced to less than 100% consistent with the feedwater flow as measured directly by the associated venturi.
Briefing 2003-08 5
Cross-Correlation Process
-iFCross-Correlation measures the velocity of eddies within the fluid using a non-intrusive transducer mounted externally on existing piping.
For this process, an ultrasonic beam is modulated by the eddies that are present in the flowing liquid.
As the modulated signal is processed, a random signal, which is the signature of the flowing eddies, is obtained.
The modulated signals from the upstream and downstream transducers are displaced in time by the time that it takes for the eddies to pass between the two transducer sets.
Briefing 200.3-08 6
AB B ffA(t+ A t) fB(t) dt C
0 0
0 0
At C
0,
A B w
Time
Possible Root Cause
ý14 From the Byron draft root cause report of 9/26/03, the root cause for both Byron and Braidwood UFM events was noise contamination of the ultrasonic signal.
A The cause of this contamination was determined to be acoustic resonant response of the feedwater piping system.
I Feedwater flow pressure pulses occurred at frequencies which caused the UFMs to indicate lower than actual feedwater flowrates resulting in a non-conservative calorimetric result.
Briefing 2003-08 9
4)
Other Similar Event River Bend reported (EN 39835) on 5/10/03 that they may have exceeded rated thermal power (RTP) during previous operating cycles. This observation was based on data analysis following testing of their installed feedwater ultrasonic flow meter (CALDON TRANSIT-TIME).
Licensee determined that the thermal power was exceeded by up to 0.7% in previous cycles. The licensee determined that the primary root cause (LER 50-458/03-005-00) was due to incorrect pipe wall smoothness following initial installation which caused changes in velocity profiles.
Corrective Action - Replaced older version of UFMs with newer and more accurate version - Developed computer points for best statistical estimate of core thermal power.
Briefing 2003-08 10
Risk/Safety Impact I Safety Impact - negligible in that the margin to operating limits was sufficient to accommodate the potential over power.
- Not Safety Related System - Excore and RPS provide safety related function in over power conditions.
- Not Risk Significant - within deterministic and parameter limits (operating limits - design limits) and no "Initiating Event.
Briefing 2003-08
Communications
ýj, Two 50.72 Event Notification Reports (40117 - 8/29/03 and 40123 - 8/31/03) - Two 50.73 LERs. Byron (LER 03-003-00 MI-032810527) and Braidwood (LER 03-002-00 ML032810226).
.3 Westinghouse Technical Bulletin "CROSSFLOW Ultrasonic Flow Measurement System Signal Issues" TB-03-6 (9/05/03).
-1, Byron Root Cause Report 9/26/03. (Draft - not on docket)
'I CENPD-397-P-A Rev 1 - "Improved Flow Measurement Accuracy Using Crossflow Ultrasonic Flow Measurement Technology" May 2000.
1 NRR to provide applicable Information Notice to Industry.
Briefing 2003-08 12
6 Potential Generic Implications 3 80 plants using this configuration from Westinghouse/AMAG (40 plants in the US and 40 plants internationally).
I Westing house/AMAG has stated that they believe this situation is not completely unique to Byron and Braidwood and is applicable to other plants utilizing this ultrasonic system.
I Ongoing review of archived installation data has not identified similar signal contamination at other installations.
Briefing 2003-08 13
NRC Regulatorv Aspects
ý-ýi Part 21 - Westinghouse/AMAG have evaluated this issue and determined it applicable to other plants - LERs from both Byron/Braidwood - NSAL to be released in November (J. Foster - R. Doney).
Emergent International Issues - Unsolicited correspondence providing public information to international stakeholders (M. Cullingford).
Westing house/Westi ng house Owners Group (B. Benney
& D. Holland). Ongoing discussions with NRC staff.
Research - Providing technical consulting on Flowmeter issues including CROSSFLOW to NRR staff. Possible future anticipatory research in this area (S. Arndt).
Briefing 20013-08 14
Conclusions
-1Broad effects associated with potential over power issues, but because of the narrow band relating to corre ction factors associated with thermal power, it is considered less significant on the safety/risk scale.
I Important issue relative to economics and compliance for the vendor/licensee.
i The NRC staff will continue to monitor both US and worldwide experience with over power issues and evaluate the need for additional generic regulatory action based on future operational events.
Briefing 2003-08 15