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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
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Text
Exelon Generation,.
RA-18-032 NEI 99-04 SECY-00-0045 March 27, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Revision to Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues
References:
- 1. Exelon Generation Company, LLC Letter to USNRC, Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues, dated August 29, 2017 (RA-17-059)
- 2. Exelon Generation Company, LLC Letter to USN RC, Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues, dated December 19, 2017 (RS-17-172)
- 3. Exelon Generation Company, LLC Letter to USN RC, Certification of Permanent Cessation of Power Operations for Oyster Creek Nuclear Generating Station, dated February 14, 2018 (RA-18-027)
In Reference 1, Exelon Generation Company, LLC (EGC) provided a status of the resolution of Anchor Darling Double Disc Gate Valve (ADDDGV) issues specifically related to safety-related Motor Operated Valve (MOV) applications at Oyster Creek Nuclear Generating Station (Oyster Creek), in addition to providing commitment to valve repairs at Oyster Creek. In Reference 2, EGC provided repair schedule commitments for the subject MOVs. In Reference 3, EGC notified the NRC of EGC's revised plans to permanently shut down Oyster Creek and cease operation no later than October 31, 2018.
The purpose of this letter is to notify the NRC of changes to the Oyster Creek ADDDGV MOV commitments for repair (MOVs V-14-0034 and V-14-0035), and diagnostic testing and stem checks with contingent repairs (MOVs V-14-0030, V-14-0031, V-14-0032, V-14-0033) planned for the OC1 R27 Refuel Outage (Fall 2018). These MOVs function as Isolation Condenser Condensate Return valves and Steam Supply Isolation valves. As stated in Reference 3,
U.S. Nuclear Regulatory Commission March 27, 2018 Page 2 Oyster Creek will permanently cease operation by October 31, 2018. As a result of the permanent shut down and reactor vessel defueling, the safety-related function of these MOVs will no longer be required. The Isolation Condenser System was designed to control reactor temperature and pressure when the reactor is isolated from its normal heat removal system.
The function of the Isolation Condensers will not be applicable as they are only required during normal power operations whenever the reactor coolant temperature is greater than 212°F. With no fuel in the reactor, scenarios requiring actuation or isolation of the Isolation Condenser System will no longer be possible. Therefore, the commitments for MOV repair, and diagnostic testing and stem checks with contingent repairs described in References 1 and 2 are no longer applicable and will not be performed.
The revised commitments to not perform repair and testing of the subject MOVs supersede the existing referenced commitments.
These commitment changes have no impact on nuclear safety or safe plant operations. These commitments have not yet been implemented at Oyster Creek and therefore, a notification to the NRC of the commitment changes is warranted in accordance with the EGC Commitment Management Program.
These commitment changes are being submitted for information only. There are no other new or revised regulatory commitments contained in this letter.
If you have any questions regarding this submittal, please contact David J. Distel at (610) 765-5517.
Respectfully submitted, James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC cc: Regional Administrator - NRC Region I NRC Senior Resident Inspector - Oyster Creek Nuclear Generating Station NRC Project Manager, NRR - Oyster Creek Nuclear Generating Station Manager, Bureau of Nuclear Engineering - New Jersey Department of Environmental Protection Mayor of Lacey Township, Forked River, NJ
Text
Exelon Generation,.
RA-18-032 NEI 99-04 SECY-00-0045 March 27, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Revision to Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues
References:
- 1. Exelon Generation Company, LLC Letter to USNRC, Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues, dated August 29, 2017 (RA-17-059)
- 2. Exelon Generation Company, LLC Letter to USN RC, Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues, dated December 19, 2017 (RS-17-172)
- 3. Exelon Generation Company, LLC Letter to USN RC, Certification of Permanent Cessation of Power Operations for Oyster Creek Nuclear Generating Station, dated February 14, 2018 (RA-18-027)
In Reference 1, Exelon Generation Company, LLC (EGC) provided a status of the resolution of Anchor Darling Double Disc Gate Valve (ADDDGV) issues specifically related to safety-related Motor Operated Valve (MOV) applications at Oyster Creek Nuclear Generating Station (Oyster Creek), in addition to providing commitment to valve repairs at Oyster Creek. In Reference 2, EGC provided repair schedule commitments for the subject MOVs. In Reference 3, EGC notified the NRC of EGC's revised plans to permanently shut down Oyster Creek and cease operation no later than October 31, 2018.
The purpose of this letter is to notify the NRC of changes to the Oyster Creek ADDDGV MOV commitments for repair (MOVs V-14-0034 and V-14-0035), and diagnostic testing and stem checks with contingent repairs (MOVs V-14-0030, V-14-0031, V-14-0032, V-14-0033) planned for the OC1 R27 Refuel Outage (Fall 2018). These MOVs function as Isolation Condenser Condensate Return valves and Steam Supply Isolation valves. As stated in Reference 3,
U.S. Nuclear Regulatory Commission March 27, 2018 Page 2 Oyster Creek will permanently cease operation by October 31, 2018. As a result of the permanent shut down and reactor vessel defueling, the safety-related function of these MOVs will no longer be required. The Isolation Condenser System was designed to control reactor temperature and pressure when the reactor is isolated from its normal heat removal system.
The function of the Isolation Condensers will not be applicable as they are only required during normal power operations whenever the reactor coolant temperature is greater than 212°F. With no fuel in the reactor, scenarios requiring actuation or isolation of the Isolation Condenser System will no longer be possible. Therefore, the commitments for MOV repair, and diagnostic testing and stem checks with contingent repairs described in References 1 and 2 are no longer applicable and will not be performed.
The revised commitments to not perform repair and testing of the subject MOVs supersede the existing referenced commitments.
These commitment changes have no impact on nuclear safety or safe plant operations. These commitments have not yet been implemented at Oyster Creek and therefore, a notification to the NRC of the commitment changes is warranted in accordance with the EGC Commitment Management Program.
These commitment changes are being submitted for information only. There are no other new or revised regulatory commitments contained in this letter.
If you have any questions regarding this submittal, please contact David J. Distel at (610) 765-5517.
Respectfully submitted, James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC cc: Regional Administrator - NRC Region I NRC Senior Resident Inspector - Oyster Creek Nuclear Generating Station NRC Project Manager, NRR - Oyster Creek Nuclear Generating Station Manager, Bureau of Nuclear Engineering - New Jersey Department of Environmental Protection Mayor of Lacey Township, Forked River, NJ