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Category:Letter type:RA
MONTHYEARRA-19-091, Commitment Change Summary Report - 20192019-12-27027 December 2019 Commitment Change Summary Report - 2019 RA-19-080, Response to Request for Additional Information (RAI) Related to Oyster Creek Nuclear Generating Station - Post-Shutdown Decommissioning Activities Report2019-10-18018 October 2019 Response to Request for Additional Information (RAI) Related to Oyster Creek Nuclear Generating Station - Post-Shutdown Decommissioning Activities Report RA-19-076, Request for Continuation of NRC Actions and Approvals Following Transfer of the Licenses from Exelon Generation to Holtec Decommissioning International, LLC2019-09-12012 September 2019 Request for Continuation of NRC Actions and Approvals Following Transfer of the Licenses from Exelon Generation to Holtec Decommissioning International, LLC RA-19-065, Signature Verification and Acceptance of Amendment 19 to Indemnity Agreement No B-37 to Renewed Facility License No. DPR-162019-08-28028 August 2019 Signature Verification and Acceptance of Amendment 19 to Indemnity Agreement No B-37 to Renewed Facility License No. DPR-16 RA-19-052, Security Plan, Training Qualification Plan, Safeguards Contingency Plan, (Revision 18)2019-06-11011 June 2019 Security Plan, Training Qualification Plan, Safeguards Contingency Plan, (Revision 18) RA-19-023, Annual Radioactive Effluent Release Report for 20182019-04-30030 April 2019 Annual Radioactive Effluent Release Report for 2018 RA-19-019, Submittal of Changes to Technical Specifications Bases2019-04-12012 April 2019 Submittal of Changes to Technical Specifications Bases RA-19-012, Supplement for License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements2019-03-0707 March 2019 Supplement for License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements RA-19-007, Response to RAI and Supplemental Information Re Request for Changing Emergency Preparedness License Amendment 294 Effective Date (Change to Adiabatic Heat-Up Calculation)2019-02-13013 February 2019 Response to RAI and Supplemental Information Re Request for Changing Emergency Preparedness License Amendment 294 Effective Date (Change to Adiabatic Heat-Up Calculation) RA-19-003, Amendment No. 17 to Indemnity Agreement No. 8-372019-01-0808 January 2019 Amendment No. 17 to Indemnity Agreement No. 8-37 RA-18-103, Annual Sea Turtle Incidental Take Report - 20182018-12-13013 December 2018 Annual Sea Turtle Incidental Take Report - 2018 RA-18-080, License Amendment Request: License Condition Revision for Removal of Cyber Security Plan Requirements2018-11-12012 November 2018 License Amendment Request: License Condition Revision for Removal of Cyber Security Plan Requirements RA-18-098, License Amendment Request Supplement - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-11-0606 November 2018 License Amendment Request Supplement - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme RA-18-097, Exelon Nuclear Radiological Emergency Plan and Addendum Revisions2018-10-24024 October 2018 Exelon Nuclear Radiological Emergency Plan and Addendum Revisions RA-18-092, License Amendment Request - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-10-22022 October 2018 License Amendment Request - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme RA-18-093, Request to Reinitiate Consultation Regarding the OCNGS Sea Turtle Incidental Take Statement2018-10-16016 October 2018 Request to Reinitiate Consultation Regarding the OCNGS Sea Turtle Incidental Take Statement RA-18-091, Request to Reclassify Oyster Creek Nuclear Generating Station Under 10 CFR 171.15, Annual Fees: Reactor Licenses and Independent Spent Fuel Storage Licenses2018-10-0101 October 2018 Request to Reclassify Oyster Creek Nuclear Generating Station Under 10 CFR 171.15, Annual Fees: Reactor Licenses and Independent Spent Fuel Storage Licenses RA-18-090, Notice Regarding Proposed Amendment No. 1 to Master Terms for Decommissioning Trust Agreements2018-10-0101 October 2018 Notice Regarding Proposed Amendment No. 1 to Master Terms for Decommissioning Trust Agreements RA-18-083, Certification of Permanent Removal of Fuel from the Reactor Vessel for Oyster Creek Nuclear Generating Station2018-09-25025 September 2018 Certification of Permanent Removal of Fuel from the Reactor Vessel for Oyster Creek Nuclear Generating Station RA-18-088, Radiological Emergency Plan Addendum Revision. Includes EP-AA-1010, Addendum 3, Revision 4, Emergency Action Levels for Oyster Creek.2018-09-25025 September 2018 Radiological Emergency Plan Addendum Revision. Includes EP-AA-1010, Addendum 3, Revision 4, Emergency Action Levels for Oyster Creek. RA-18-087, Response to Request for Additional Information (RAI) Related to Post-Shutdown Decommissioning Activities Report2018-09-24024 September 2018 Response to Request for Additional Information (RAI) Related to Post-Shutdown Decommissioning Activities Report RA-18-084, Secondary Containment Capability Test2018-09-14014 September 2018 Secondary Containment Capability Test RA-18-078, Submittal of Sea Turtle Incidental Take Report 2018-0042018-08-15015 August 2018 Submittal of Sea Turtle Incidental Take Report 2018-004 RA-18-077, Sea Turtle Incidental Take Report 2018-0032018-08-14014 August 2018 Sea Turtle Incidental Take Report 2018-003 RA-18-072, Pressure and Temperature Limit Report Revision 12018-06-29029 June 2018 Pressure and Temperature Limit Report Revision 1 RA-18-066, Response to Questions Pertaining to Licensed Operator2018-06-18018 June 2018 Response to Questions Pertaining to Licensed Operator RA-18-070, Submittal of Sea Turtle Incidental Take Report 2018-001 on June 04, 20182018-06-0808 June 2018 Submittal of Sea Turtle Incidental Take Report 2018-001 on June 04, 2018 RA-18-068, Response to Request for Additional Information (RAI) Regarding Request for Approval of Decommissioning Quality Assurance Program, Revision 0 for Oyster Creek Nuclear Generating Station2018-06-0606 June 2018 Response to Request for Additional Information (RAI) Regarding Request for Approval of Decommissioning Quality Assurance Program, Revision 0 for Oyster Creek Nuclear Generating Station RA-18-065, Registration of Use of Cask to Store Spent Fuel2018-05-31031 May 2018 Registration of Use of Cask to Store Spent Fuel RA-18-059, Request for Relief and Rescission of Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2018-05-30030 May 2018 Request for Relief and Rescission of Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events RA-18-055, 10 CFR 50.46 Annual Report2018-05-23023 May 2018 10 CFR 50.46 Annual Report RA-18-053, Update to Spent Fuel Management Plan2018-05-21021 May 2018 Update to Spent Fuel Management Plan RA-18-052, Supplement to Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance and Supplement to Request for Exemption from 10 CFR 140.11(a)(4), Concerning Primary and Secondary ...2018-05-0808 May 2018 Supplement to Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance and Supplement to Request for Exemption from 10 CFR 140.11(a)(4), Concerning Primary and Secondary ... RA-18-049, Registration of Use of Cask to Store Spent Fuel2018-05-0707 May 2018 Registration of Use of Cask to Store Spent Fuel RA-18-046, Oyster Creek, Transmittal of Annual Radiological Environmental Operating Report for 20172018-04-30030 April 2018 Oyster Creek, Transmittal of Annual Radiological Environmental Operating Report for 2017 RA-18-047, Annual Radioactive Effluent Release Report for 20172018-04-30030 April 2018 Annual Radioactive Effluent Release Report for 2017 RA-18-018, Submittal of Changes to Technical Specifications Bases2018-04-13013 April 2018 Submittal of Changes to Technical Specifications Bases RA-18-021, Request for Exemption from Record Retention Requirements2018-04-12012 April 2018 Request for Exemption from Record Retention Requirements RA-18-028, Request for Rescission of Commission Order Modifying License with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)2018-04-12012 April 2018 Request for Rescission of Commission Order Modifying License with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109) RA-18-027, Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2018-04-12012 April 2018 Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RA-18-036, Response to Request for Additional Information (RAI) and Supplement Regarding License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled ...2018-03-29029 March 2018 Response to Request for Additional Information (RAI) and Supplement Regarding License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled ... RA-18-019, Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance2018-03-29029 March 2018 Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance RA-18-020, Request for Exemption from 1 O CFR 140.11 (a)(4), Concerning Primary and Secondary Liability Insurance2018-03-29029 March 2018 Request for Exemption from 1 O CFR 140.11 (a)(4), Concerning Primary and Secondary Liability Insurance RA-18-032, Revision to Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2018-03-27027 March 2018 Revision to Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues RA-18-034, Request for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv)2018-03-22022 March 2018 Request for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) RA-18-015, Withdrawal of Application to Revise Technical Specifications to Implement BWRVIP-18, Revision 2-A and Relief Request for Extension of Torus Examinations2018-02-15015 February 2018 Withdrawal of Application to Revise Technical Specifications to Implement BWRVIP-18, Revision 2-A and Relief Request for Extension of Torus Examinations RA-18-014, Response to Request for Additional Information (RAI) and Supplemental Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-02-13013 February 2018 Response to Request for Additional Information (RAI) and Supplemental Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme RA-18-008, Summary of Changes to Quality Assurance Topical Report, NO-AA-102018-02-0808 February 2018 Summary of Changes to Quality Assurance Topical Report, NO-AA-10 RA-18-010, Supplement to Relief Request for Extension of Torus Examinations2018-01-24024 January 2018 Supplement to Relief Request for Extension of Torus Examinations RA-17-086, Commitment Change Summary Report - 20172017-12-21021 December 2017 Commitment Change Summary Report - 2017 2019-09-12
[Table view] Category:Part 21 Correspondence
MONTHYEARRA-17-059, Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2017-08-29029 August 2017 Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification ML14079A0272014-03-13013 March 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML1024605372010-09-0202 September 2010 Part 21 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML1000700732009-11-19019 November 2009 USNRC 10CFR Part 21 Notification - Flowserve Figure 848 Disk/Disk Nut Separation ML0608600852006-03-21021 March 2006 Rosemount Nuclear Instruments, Inc., Notification Under 10 CFR Part 21 for Model 1153 and Model 1154 Pressure Transmitters ML0501102232005-01-0707 January 2005 Non-Emergency Event Report, Overstress Condition on Single Failure Proof Crane Trolleys ML0428002672004-09-29029 September 2004 Submittal of Part 21 Final Report: Non-conservative SLMCPR ML0335301272003-12-16016 December 2003 Part 21 Report on Potential Concern Regarding Specific Lot of Fluorocarbon Rubber Inserts ML0320604292003-07-21021 July 2003 Notification of Possible Defect Associated with Thermo Westronics Model 2100C Series Recorders ML0215601132002-05-10010 May 2002 Letter from W. G. Hampton Subject: 10CFR21 Notification - Potential Defect Involving Fan Assemblies Use in Forced Air Cooled Uninterruptible Power Supply Systems 2017-08-29
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Exelon Generation 200 Exelon Way Kennett Square. PA 19348 RS-17-122 RA-17-059 www.exeloncorp.com August 29, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRG Docket No. 50-219 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRG Docket Nos. 50-254 and 50-265 Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues
References:
- 1) Letter from Greg Krueger (NEI) to Mr. John Lubinski (U.S. Nuclear Regulatory Commission), Anchor Darling Double Disc Gate Valve Industry Resolution Plan Update (Project 689), dated August 4, 2017 2) Letter from W. J. Trafton (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Amendment to Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues," dated June 20, 2017 (RA-17-059)
- 3) BWROG Topical Report TP-16-1-112, "Recommendations to Resolve Flowserve 1 O CFR Part 21 Notification Affecting Anchor Darling Double Disc Gate Valve Wedge Pin Failures (Revision 4)," dated August 2017 In Reference 1, the Nuclear Energy Institute (NEI) provided the NRG a near-term plan for the U.S. Nuclear Industry to address the known Anchor Darling Double Disk Gate Valve (ADDDGV) issues leading up to the February 2017 LaSalle County Station, Unit 2 valve stem-disc separation on a High Pressure Core Spray Motor Operated Valve (MOV). The NEI letter states that each affected utility will communicate to the NRG by August 31, 2017, a list of "High Significance" valves and an associated repair schedule. "High Significance" as defined by the NEI are safety related MOVs having an active safety function to either Open or Open/Close with an "UNSA T" wedge pin analysis.
Excluding LaSalle County Station, Units 1 and 2, this scope of valves within Exelon Generation Company, LLC (EGG) is limited U.S. Nuclear Regulatory Commission Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues August 29, 2017 Page2 to only the Oyster Creek Generating Station. Further, this letter provides additional information for all susceptible High Risk valves at Quad Cities Nuclear Power Station, Units 1 and 2, in addition to the Oyster Creek Nuclear Generating Station and LaSalle County Station, Units 1 and 2. In Reference 2, EGC provided commitments associated with the resolution of ADDDGV Part 21 issues for the LaSalle County Station, Units 1 and 2. This LaSalle letter committed the station to repair all susceptible safety related MOVs by the next available refueling outage. For the remaining EGG plants, Attachment 1 contains commitments regarding the repair and resolution of the susceptible High Risk MOVs at the Oyster Creek Generating Station and Quad Cities Nuclear Power Station, Units 1 and 2. Excluding LaSalle County Station, Units 1 and 2, as discussed in the preceding paragraph, Oyster Creek Nuclear Generating Station and Quad Cities Nuclear Power Station, Units 1 and 2, are the only EGC plants with susceptible High Risk MOVs. High Risk MOVs are determined using the procedurally established NRC approved Joint Owner's Group Generic Letter (GL) 96-05 Risk Ranking Methodology and includes both High and Medium Risk GL 96-05 MOVs. Additionally, there are no susceptible Low Risk MOVs that meet the NEI definition of "High Significance" within the EGG fleet. EGC is an active participant in the Boiling Water Reactors Owners Group (BWROG) committee that is developing corrective actions and maintenance activities to ensure proper functioning of the Anchor Darling valves. All affected EGC plants will comply with the Reference 3 recommended actions to address applicable GL 96-05 MOVs affected by the ADDDGV Part 21. The requirements for each category of valves is in accordance with the BWROG simplified recommendations and schedule for Part 21 applicable MOVs. These include the following aspects:
- Screening evaluation method for susceptible MOVs
- Stem Rotation Check Methods
- Diagnostic Test I Evaluation Methods
- Repair Schedule A brief explanation of the specific valve repair and test/inspection commitment scope as contained in Attachment 1 are as follows: Category A -The Category A group includes Susceptible High and Medium Risk GL 96-05 MOVs with multiple Open/Close active safety function strokes. This group of valves will be repaired by the next refueling outage. For EGC, the MOVs that meet this criteria include: Plant Oyster Creek Nuclear Generating Station Oyster Creek Nuclear Generating Station Valve ID V-14-0034 V-14-0035 U.S. Nuclear Regulatory Commission Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues August 29, 2017 Page 3 These Oyster Creek Nuclear Generating Station MOVs function as Isolation Condenser Condensate Return valves with active safety functions in both Open and Close directions.
These valves are classified as susceptible MOVs of High Significance and High Risk. Category B -The Category B group includes Susceptible High or Medium Risk GL 96-05 MOVs and only stroke once, open or closed, to perform their safety function.
This group of valves will either be repaired at the next refueling outage OR pass diagnostic tests and stem rotation checks during the next refueling outage with final repair within two refueling outages (as applicable).
For EGG, the MOVs that meet this criteria include: Plant Quad Cities Nuclear Power Station, Unit 1 Quad Cities Nuclear Power Station, Unit 1 Quad Cities Nuclear Power Station, Unit 2 Quad Cities Nuclear Power Station, Unit 2 Valve ID 1-1201-2 1-1201-5 2-1201-2 2-1201-5 These Quad Cities Nuclear Power Station, Units 1 and 2, MOVs function as Reactor Water Cleanup Containment Isolation Inboard and Outboard Valves and have an active safety function to Close Only. Repairs are scheduled for next refueling outage for each unit. Plant Oyster Creek Nuclear Generating Station Oyster Creek Nuclear Generating Station Oyster Creek Nuclear Generating Station Oyster Creek Nuclear Generating Station Valve ID V-14-0030 V-14-0031 V-14-0032 V-14-0033 These Oyster Creek Nuclear Generating Station MOVs function as Isolation Condenser Steam Supply Isolation Valves and have an active safety function to Close Only. Diagnostic testing and stem rotation checks are planned for the next refueling outage (2018). Planned repairs are contingency only given that the Oyster Creek Nuclear Generating Station is scheduled to permanently shut down in 2019. This plan is in full compliance with BWROG recommended actions. Note that the Category B Valves listed above have a Close Only safety function such that they are not considered to be susceptible MOVs of "High Significance." Also in Reference 1, NEI states that susceptibility reviews and repair plans for all safety related valves against the revised BWROG Guidance (Reference
- 3) be communicated to the NRG by December 31, 2017. EGG will communicate this information including repair schedule commitments in a separate letter in accordance with the NEI Plan.
U.S. Nuclear Regulatory Commission Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues August29,2017 Page4 Should you have any questions or require additional information, please contact Tom Loomis at 610-765-5510.
Respectfully, Jam rt:: Director -Licensing
& Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Summary of Commitments cc: Regional Administrator
-NRC Region I Regional Administrator
-NRC Region Ill NRC Senior Resident Inspector
-Oyster Creek Nuclear Generating Station NRC Senior Resident Inspector
-Quad Cities Nuclear Power Station S. T. Gray, State of Maryland Illinois Emergency Management Agency -Division of Nuclear Safety -(w/o attachments) R. R. Janati -Bureau of Radiation Protection, Commonwealth of Pennsylvania
-(w/o attachments Manager, Bureau of Nuclear Engineering, New Jersey Department of Environmental Protection Mayor of Lacey Township, Forked River, NJ ATTACHMENT Summary of Commitments
SUMMARY
OF REGULATORY COMMITMENTS The following table identifies commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRC's information and are not regulatory commitments.)
COMMITTED COMMITMENT TYPE COMMITMENT DATE OR ONE-TIME Programmatic "OUTAGE" ACTION (YES/NO) (Yes/No) Category A MOVs to be repaired at the Oyster Creek Nuclear Generating Station: MOV Number Outage(Year)
Yes V-14-0034 OC1 R27(2018)
V-14-0035 OC1 R27(2018)
Category B MOVs to be repaired at the Quad Cities Nuclear Power Station, Units 1 and 2: MOV Number Outage(Year)
Yes Unit 1 1-1201-2 01 R25(2019)
Unit 1 1-1201-5 01 R25(2019)
Unit 2 2-1201-2 02R24(2018)
Unit 2 2-1201-5 02R24(2018)
Perform diagnostic testing and stem rotation checks with contingent repairs on the following Oyster Creek Nuclear Generating Station MOVs: MOV Number Outage(Year)
Yes V-14-0030 OC1 R27(2018)
V-14-0031 OC1 R27(2018)
V-14-0032 OC1 R27(2018)
V-14-0033 OC1 R27(2018)