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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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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