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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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NRC Discussions with NJ DEP Engineers Backqround On Tuesday 11/18, John Richmond had a conversation with two NJ DEP engineers (Rich Pinney and Ron Zak). These engineers accompanied John Richmond on the license renewal commitments inspection and expressed concerns that the PN the NRC issued on Monday 11/17 omitted some relevant information. Additionally, the NJ DEP engineers felt that the MOU was effectively a 'gag order' preventing them from informing the public. John Richmond explained to the NJ DEP engineers that the purpose of the PN was an outreach to provide preliminary inspection information to the public prior to Oyster Creek restarting from the refueling outage. It was also explained to the NJ DEP engineers that the NRC had not come to a conclusion on the issues they expressed, although we did conclude there are no immediate safety concerns to prevent restart. The conclusions will be included in our inspection report, scheduled for issuance in mid January.
issuance(b)(5)
NJ DEP Eng~ineer Concerns The NJ DEP engineers' concerns are listed below, along with the NRC's perspective on each issue:
- 1. Strippable coating de-lamination
- The strippable coating used to line the containment liner was identified to be de-laminated in areas of the drywell.
- 2. Disconnected tubing from sand bed drain line poly bottles
- During the outage, the tubing from the sand bed to the poly bottles were found to be disconnected for two of the five poly bottles. The poly bottles are used to quantify leakage from the sand bed region. There was no evidence of water leakage and therefore no consequence of these lines being disconnected.
- 3. 1/2 inch deep standing water in the sand bed bays
- The licensee identified water in two of eleven sand bed bays. This was initially characterized by the licensee as moisture, then as a puddle, then as less than 1/2 inch deep. The NRC does not believe there was
- 4. No confidence [sic] in AmerGen's monitoring of sand bed drains, while the plant is on-line (e.g., water could enter a sand bed bay and go undetected)
- The potential for water to leak into the sand bed bays exist during refueling outages when the reactor is fJooded up. While the pJant is onJine, there is no postulated source of water to leak into the sand bed bays. The NJ DEP engineers were unable to postulate a source of water to leak into the sand bed bays during normal operation, but stated that you could not be certain leakage did not exist.
- 5. Brightly rust colored water found in bay 17, on Friday 11/14 [in other bays, the water was not described as brightly rust colored]
- 6. No proof that there is not large [entire surface] areas of rust under the epoxy coating (e.g., the issue may have been mischaracterized as only a small area of one identified blister, versus significant corrosion that has not been evaluated)
Infomasmin nthis record was dltd acOrdance with the Ermedom of Inrform f.t Exemptions___
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- The epoxy coating was applied to arrest corrosion. There have been small areas where the epoxy coating has blistered; however there is no evidence that the epoxy coating is not effective where it is in good condition.
- 7. Corrosion rate of steel shell, in a broken blister, would be the same as uncoated steel, and will be significantly higher that the predicted corrosion rate of the same steel inside an unbroken blister, because in the past, the sand bed region experienced the loss of at least 1/2 inch of steel due to corrosion
- Corrosion rates of steel are well known. The site did experience a high corrosion rate of /2 inch over approximately 10 year period before the sand was removed from the sand bed bays. Wet sand directly against the steel accelerated the corrosion rate. The current configuration with the sand removed is not conducive to this higher corrosion rate. The NRC agrees with the licensee's assessment that a broken blister would corrode significantly between inspections.
Next Steps On Tuesday 11/18, NRC staff members held a meeting to discuss next steps. The agreed upon next steps were:
- Call State of NJ DEP management to determine ifthe concern the engineers raised to our inspector was shared NJ DEP management.
o IN PROGRESS: Patrick Mulligan, Chief NJ DEP BNE. (supervisor of inspectors J. Richmond spoke to) Pat had not heard the concerns from the inspector and doesn't expect these issues will be elevated. Pat will talk to the engineers to better understand their issues. Pat will call back Marjey later today or tomorrow.
Marjey will followup with Doug and John tomorrow.
" Notify Karl Farrar of the emaiL, (b)(5) o COMPLETE
- Marjey, Doug, and John discuss response from NJ DEP management to determine if additional actions are necessary and report back to Marsha.
o INCOMPLETE