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Category:Meeting Briefing Package/Handouts
MONTHYEARML19269B6892019-10-0303 October 2019 NEIMA Section 108 Public Meeting Slides - Oyster Creek - October 3, 2019 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 ML18225A1752018-08-15015 August 2018 Decommissioning License Transfer Application NRC Pre-Submittal Meeting ML18201A2372018-07-17017 July 2018 Slides 7/17/2018 PSDAR Meeting ML18201A2842018-07-17017 July 2018 PSDAR Public Meeting the NRC Review Process ML18201A3072018-07-17017 July 2018 Post Shutdown Decommissioning Activities Report (PSDAR) Public Meeting Presentation 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 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 ML17062A5522017-03-0909 March 2017 E EMRV Failure Slides for Regulatory Conference Meeting Notice for 03/09/17 ML16314E4812016-11-14014 November 2016 Part 37 Applicability to Reactor Vessels and Associated Structures, Systems, and Components While in Safstor Awaiting Active Decommissioning Activities - November 14, 2016 ML16092A1402016-04-0606 April 2016 4/6/16, Meeting Slide for Pre-Submittal Meeting with NRC Regarding Oyster Creek Decommissioning Post-Shutdown Emergency Plan License Amendment Request 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 ML15265A3592015-09-21021 September 2015 NRC Oyster Creek Decommissioning Pre-Submittal Meeting Slides 09-21-15 ML15118A8042015-05-0505 May 2015 Webinar 2015 Slides Presentation ML15265A3742015-02-21021 February 2015 NRC Pre-Submittal Meeting 09-21-15 - Decommissioning Submittal List ML12173A1322012-06-21021 June 2012 Summary of Public Meeting with Exelon Generation Company, LLC Regarding Items of Public Interest Related to Oyster Creek Nuclear Generating Station ML12110A3402012-04-19019 April 2012 Annual Assessment Meeting - 2011 ROP-NRC Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML1012300492010-05-0303 May 2010 Slides for the Oyster Creek Annual Assessment Public Meeting ML0934102382009-12-0404 December 2009 Meeting Presentation, ACRS Meeting with the U.S. Nuclear Regulator Commission ML0928701922009-10-0909 October 2009 FEMA Public Meeting at Oyster Creek Slides, October 2009 ML0919803632009-08-20020 August 2009 Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes ML0919801452009-06-17017 June 2009 NRC Discussions with Nj DEP Engineers ML0919605452009-06-17017 June 2009 10/01/2008 Senior Management Briefing Oyster Creek License Renewal Regulatory Footprint, to Describe Current Regulatory Footprint, Additional Options & Actions, and Gov'T & Public Outreach Needs ML0919605462009-06-17017 June 2009 10/01/2008 Senior Management Briefing Oyster Creek License Renewal Regulatory Footprint, Working Discussion of Issues and Options in Response to RA Questions ML0919605472009-06-17017 June 2009 10/01/2008 Senior Management Briefing Oyster Creek License Renewal Regulatory Footprint, Working Discussion of Issues and Options in Response to RA Questions ML0919605572009-06-17017 June 2009 10/01/2008 Senior Management Briefing Oyster Creek License Renewal Regulatory Footprint, to Describe Current Regulatory Footprint, Additional Options & Actions, and Gov'T & Public Outreach Needs ML0919605582009-06-17017 June 2009 10/01/2008 Senior Management Briefing Oyster Creek License Renewal Regulatory Footprint, to Describe Current Regulatory Footprint, Additional Options & Actions, and Gov'T & Public Outreach Needs ML0919605592009-06-17017 June 2009 09/23/2008 DRS Management Briefing Oyster Creek License Renewal Regulatory Footprint, Working Discussion of Issues and Options in Response to RA Questions on a Lr Regulatory Foodprint ML0919605602009-06-17017 June 2009 09/23/2008 DRS Management Briefing Oyster Creek License Renewal Regulatory Footprint, Working Discussion of Issues and Options, in Response to RA Questions ML0919805202009-06-17017 June 2009 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues ML0916802102009-05-28028 May 2009 Oc Aam Public Feedback Form, 05/28/2009, 2008 Annual Assessment Meeting ML0913205742009-05-12012 May 2009 Meeting Slides, Oyster Creek Annual Assessment Meeting 2008 Reactor Oversight Process ML0912702392009-05-0404 May 2009 Calvert County Sheriff- Special Operations Team ML0912406092009-04-23023 April 2009 Meeting, Slides, New Jersey State Police Response to Hostile Action at Nuclear Power Plants, National Radiological Emergency Preparedness Conference ML0919801442008-12-22022 December 2008 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues with Handwritten Notes ML0919801392008-12-22022 December 2008 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues ML0919801402008-12-22022 December 2008 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues ML0919801422008-12-22022 December 2008 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues ML0919801432008-12-22022 December 2008 Brief for Ora Oyster Creek Commitment Inspection Results and Related Issues ML0812007842008-06-0202 June 2008 Meeting Slides, Nrc/Exelon Licensing Counterparts Meeting. ML0810606002008-04-15015 April 2008 Meeting Slides, NRC Annual Performance Assessment of Oyster Creek 2007 Reactor Oversight Program. ML0715204362007-05-23023 May 2007 Feedback Forms, List of Attendees, & Final Slides from the Oyster Creek 2007 Annual Assessment Meeting (Aam) ML0634206092006-11-0404 November 2006 Powerpoint: Oyster Creek 1R21 Outage Startup PORC Update on Drywell Shell Inspections November 4, 2006 (PA) ML0622301292006-07-12012 July 2006 Powerpoint Presentation Associated with Oyster Creek Draft EIS Public Meetings ML0610003702006-04-10010 April 2006 NRC Slides for Annual Assessment Public Meeting with Amergen Reference CY2005 Oyster Creek Station Performance ML0509800822005-04-0808 April 2005 05/12/2005 - Oyster Creek Annual Assessment Meeting Slides for Meeting with Amergen ML0430302762004-09-27027 September 2004 Attendance List for Oyster Creek EDG Cooling Fan Regulatory Conference 2019-10-03
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Oyster Creek Presentation to NRC Staff July 28, 2000 Control Room Habitability Radiological Consequence Analysis for Control Room Operatorsat Oyster Creek Nuclear GeneratingStation using the Alternate Source Term as an NEI PilotPlant submitted March 31, 199 7 Attachment 2
Agenda Topic Presenter I. Background Radvansky II. Oyster Creek Control Room Radvansky HVAC System Configuration III. Discussion of Analysis Metcalf IV. Summary Busch V. NRC Feedback
Background
Oyster Creek Profile 640 MWe BWR II, Mark I Containment, Commercial Operation-December, 1969 Licensing Issue-Resolution of NUREG 0737 III.D.3.4 Thyroid Dose to CR Operator Key Chronological Events
- 1982-1990 Upgrades to System; Formulation and Acceptance of Current Licensing Basis (CLB)-Whole Body and Skin Dose
- 1996, Mar. NRC Request for Resolution of Thyroid Dose
- 1996, Nov. Accepted as an NEI Pilot Plant for Use of Alternate Source Term in a Licensing Submittal
- 1997, Mar. Submittal Issued to NRC
- 2000, Apr. GPUN Letter Requesting Reactivation of Review; Remobilization of Project I
Oyster Creek Control Room HVAC System Configuration SYSTEM LEGEND KITCHEN & RESTROOM EXHAUST
- EXHAUST SýSUPPLY 7/ /1 41- 41-t1 SYSTEM 'A' 1*1+ 1+
CONTROL LOWER CABLE ROOM SPREADING RM CONTROL ROOM ENVELOPE HVAC SYSTEM DIAGRAMMATIC
Discussion of Analysis
"*Current Submittal Analytical Approach
"*Analytical Model for Oyster Creek AST Application
"*Changes from Current Licensing Basis
"*Dose Results by Type
"*Dose Results by Pathway
"*Atmospheric Dispersion--LER 2000-006 P"7
_/_-
I Current Submittal Analytical Approach
- Some Aspects of CLB Retained
- MSIV Leak Rate = f(PDw)
- Occupancy Factors Based on Shifts
- Same X/Qs
- Same Shine Dose
- Steam Line Hold-Up Beyond Outboard MSIVs Not Credited (NRC Request--March 1996 Letter)
- Non-MSIV Bypass Added (NRC Request--March 1996 Letter)
-7 Current Submittal Analytical Approach (Cont)
"* Pilot Plant Status Justification (October 1996)
"* Unique/Interesting Features of Oyster Creek Application
- Credit for Drywell Sprays
- Integrated Containment T/H Analysis
- Significant Potential for No pH Control
- No Control Room Charcoal or Particulate Filters
- Additional Non-MSIV Bypass Pathways
- MSIV Leak Rate = f(PDW)
- No Credit for Deposition Beyond Outboard MSIVs Analytical Model for Oyster Creek AST Application
[M.1* Steamline w/I Open MSIV Drrywell Xspray Steamline w/ Closed MSIVs Xsed Core Other RB Bypass (see Next Overhead) i
-I Torus SGTS Eu..l Reactor Bldg Indicates Filter ESF Leakage (Real or Uliiwa Effective)
LME -
Analytical Model for OC AST Application (Cont)
Other RB Bypass
- Based on "Primary Containment Leakage Rate Testing Program", October 11, 1996
- Lines Which
"*Originate in Primary.Containment
"*Terminate Outside Secondary Containment
"*Not Water-Filled
- Includes: 8" N2 Pathway, 2" N2 Pathway, TIP Purge, Instrument Air, Isolation Condenser Vents, Drywell Spray Test Lines
- Treated in a Manner Similar to Main Steam Lines I
Changes from Current Licensing Basis Aspect Current Licensing Basis Current Submittal Source Term TID-14844 NUREG-1465 Containment Continuous for Pressure Cycled for Activity Removal Sprays* Reduction and Pressure Reduction MSIV Leak = Yes, with UFSAR DW Yes, with Revised (MAAP4) f(PDw) Pressure Pressure Deposition in Hold-Up Only Up to Outboard MSIV Steam Lines*
Pool No Yes (Based on MAAP4 T/H)
Scrubbing*
Occupancy Four Shifts after 24 Hours Five Shifts after 24 Hours Factors Pool pH Not Applicable Revaporization Included
Containment Sprays
"* MAAP4 Analysis Determines Frequency
"* Consistent with EOPs, Now with SAGs
"* Only Design Flow Credited
"* Drywell Sprays
- STARNAUA Analysis for Removal Rates
"*Realistic Impaction
"*Ignores Hygroscopicity and New Droplet Size Data
- Fall Height Rigorously Considers Obstructions
- Drywell Assumed to Be Well-Mixed
"* Torus Sprays
- SRP 6.5.2 Removal Rates (for Pool Bypass)
Deposition in Steam Lines (and Other RB Bypass Pathways)
"* Steam Lines
- Steam Line with One Open MSIV
- Impaction at Inboard MSIV (DF - 2)
- Steam Line with Closed MSIVs
"*Sedimentation (Well-Mixed) Between MSIVs
"*Calculated with STARNAUA
" Impaction at Inboard MSIV Combined with Sedimentation Removal Rates (i.e., "Lambdas")
"* Other Bypass Pathways
- Sedimentation (Plug-Flow) in Piping within Secondary Containment (Large L/D)
I Pool Scrubbing 0 Treatment Consistent with SRP 6.5.5
- Drywell-to-Torus Flow Commences with Core Debris Relocation (Predicted by MAAP4)
- Approx 50% of Drywell Volume Transferred over 10 Minutes Leading to 40% Purge 0 Pool DF - 2.3 (Approx 50% Pool Bypass) 0 DF Effectively Much Smaller 0 10 Minutes of Return Flow Based on Drywell Spray Operation after Partial Drywell Purge 0 Drywell and Torus Considered Well-Mixed after End of Release Period Dose Results by Type
- Organic Iodine Inhalation Dose 1.33 Rem
- Elemental Iodine Inhalation Dose (w/o Revolatilization) 0.14 Rem
- Dose from Inhalation of Particulates 2.17 Rem
- Revolatilized Iodine Inhalation Dose 0.12 Rem
- External Dose (Activity Inside Control Room) 0.37 Rem
- External Dose (Activity Outside Control Room (i.e., Plume) 0.04 Rem
- External Shine (Containment/Core Spray) 0.60 Rem Total = 4.77 Rem Dose Results by Pathway
- Steam Line with Stuck-Open Outboard MSIV 2.3 5 Rem
- Steam Line with Closed MSIVs 0.56 Rem
- Containment Leakage- 0.21 Rem
- ESF Leakage- 0.35 Rem
- Other (Non-MSIV) Secondary Containment Bypass 0.70 Rem
- Containment and Core Spray Piping Shine 0.60 Rem Total = 4.77 Rem Atmospheric Dispersion - LER 2000-006
"* CLB and 1997 Submittal
- Murphy-Campe
- 1982-83 Meteorological Data
- "A" Control Room Air Intake (Only Intake in 1985)
"* Application of ARCON96
- Ground-Level Release X/Qs Only Recalculated
- Both "A" and "B" Air Intakes Considered
- NRC Draft Guidance Employed
-1995-99 Meteorological Data
- OC Meteorological Program Meets RG 1.23
- Includes Statistical Analysis for Trends