Letter Sequence Request |
---|
|
|
MONTHYEARRA-17-055, License Amendment Request to Implement BWRVIP-18, Revision 2-A2017-08-30030 August 2017 License Amendment Request to Implement BWRVIP-18, Revision 2-A Project stage: Request RA-17-084, Submittal of Relief Request for Extension of Torus Examinations in Accordance with 10 CFR 50.55a(z)(1)2017-12-19019 December 2017 Submittal of Relief Request for Extension of Torus Examinations in Accordance with 10 CFR 50.55a(z)(1) Project stage: Request ML18003A4122018-01-0303 January 2018 NRR E-mail Capture - for Your Action - RAI - Oyster Creek BWRVIP LAR (CAC No. MG0180; EPID No. L-LLA-2017-0304) Project stage: RAI 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 Project stage: Withdrawal ML18047A4302018-03-16016 March 2018 FRN, Withdrawal of Request to Revise License Condition to Implement BWRVIP-18, Revision 2-A, BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines (CAC MG0180; EPID L-2017-LLA-0304) Project stage: Withdrawal ML18047A4272018-03-16016 March 2018 Letter, Withdrawal of Request to Revise License Condition to Implement BWRVIP-18, Revision 2-A, BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines (CAC MG0180; EPID L-2017-LLA-0304) Project stage: Withdrawal NRC-2018-0058, FRN, Withdrawal of Request to Revise License Condition to Implement BWRVIP-18, Revision 2-A, BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines (CAC MG0180; EPID L-2017-LLA-0304)2018-03-16016 March 2018 FRN, Withdrawal of Request to Revise License Condition to Implement BWRVIP-18, Revision 2-A, BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines (CAC MG0180; EPID L-2017-LLA-0304) Project stage: Withdrawal 2018-01-03
[Table View] |
|
---|
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] |
Text
Exelon Generation ,
10 CFR 50.SSa RA-17-084 December 19, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Submittal of Relief Request for Extension of Torus Examinations in Accordance with 10 CFR 50.55a(z)(1)
Pursuant to 10 CFR 50.55a, "Codes and standards," paragraph (z)(1 ), Exelon Generation Company, LLC (EGC), is requesting relief from the current examination requirements of Containment Shell (Torus) performed in accordance with American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI "Rules for lnservice Inspection of Nuclear Power Plant Components", Subsection IWE on the basis that the proposed alternative would provide an acceptable level of quality and safety.
The relief request as described in the attachment to this letter proposes an alternative to the inspection frequency of torus examinations for the current (second) 10-Year Containment lnservice Inspection (GISI) interval. The alternative requests a 16-month extension of the ASME Section XI examination for the torus visual inspections currently required to be performed in the OC1 R27 Refuel Outage (September 2018).
Exelon requests approval of the proposed relief request by July 31, 2018 in order to utilize the proposed change in the Fall 2018 Refueling Outage which is currently scheduled to start in mid-September 2018.
This letter contains no new regulatory commitments. If you have any questions regarding this letter, please contact David Distel at 610-765-5517.
Respectfully submitted, d~~
James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Attachment:
10 CFR 50.55a Request Number l5R-11, Relief Request for Extension of Torus Examinations in Accordance with 10 CFR 50.55a(z)(1)
U.S. Nuclear Regulatory Commission Relief Request - Alternative to ASME Code December 19, 2017 Page 2 cc: NRC Regional Administrator - 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
Attachment 1 Oyster Creek Nuclear Generating Station 10 CFR 50.55a Request Number ISR-11, Relief Request for Extension of Torus Examinations in Accordance with 10 CFR 50.55a(z)(1)
CISI Program Plan Oyster Creek Nuclear Generating Station, Second Interval 10 CFR 50.55a RELIEF REQUEST: ISR-11 Revision 0 (Page 1 of 4)
Relief Request for Extension of Torus Examinations in Accordance with 10 CFR 50.55a(z)(1)
- 1. ASME CODE COMPONENTS AFFECTED:
Code Class: MC
Reference:
IWA-2432, IWE-2412, Table IWE-2500-1 Examination Category: E-A, Containment Surfaces Item Number: E1.11, E1.12 and E1.20
Description:
Visual Examination of Containment Shell (Torus) and Vent System Component Number: Unit 1, TORUS, VENTSYS-001
- 2. APPLICABLE CODE EDITION AND ADDENDA:
The current (second) 10-Year Containment lnservice Inspection (GISI) interval at Oyster Creek Nuclear Generating Station is based on the 2001 Edition through 2003 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Division I, Subsection IWE.
- 3. APPLICABLE CODE REQUIREMENT:
Oyster Creek second 10-Year GISI interval is established in accordance with Inspection Program Bas outlined in ASME Code Section XI, Paragraphs IWA-2432 and IWE-2412.
Paragraph IWA-2432, "Inspection Program B," requires that each inspection interval consist of a 10-Year duration, except as modified by IWA-2430(d) which permits the inspection interval to be reduced or extended by as much as one year, provided that successive intervals are not altered by more than one year from the original pattern of intervals.
Paragraph IWE-2412, "Inspection Program B" requires the examinations specified in Table IWE-2500-1 to be completed during each successive inspection interval, in accordance with Table IWE-2412-1.
Table IWE-2412-1 divides the 10-Year Inspection Interval to three Inspection Periods.
Per Appendix B of Oyster Creek Second 10-Year Containment (IWE) lnservice Inspection Program (Reference 2), the Torus is considered Examination Category E-A (Item Number E1 .11 & E1 .12) and the Torus Vent System is considered Examination Category E-A (Item Number E1 .20).
In order to comply with Table IWE-2500-1 Oyster Creek Nuclear Generating Station is required to perform a Visual examination of 100% of the Torus surface areas and 100%
of the Torus Vent System during the third Inspection Period.
CISI Program Plan Oyster Creek Nuclear Generating Station, Second Interval 10 CFR 50.SSa RELIEF REQUEST: ISR-11 Revision 0 (Page 2 of 4)
Relief Request for Extension of Torus Examinations in Accordance with 10 CFR 50.55a(z)(1)
- 4. REASON FOR REQUEST:
Oyster Creek is currently in the last (third) period of Second GISI Interval (Reference 2) which will end on September 10, 2019. During the OC1 R27 Refueling Outage (September 2018) Oyster Creek is required to perform visual examination (VT-3) on submerged and vapor areas of the Torus including the Vent System. Oyster Creek performed the required first and second period examinations during refueling outages OC1R23 and OC1R25 in the Fall of 2010 and 2014, respectively.
The First GISI Interval was extended an additional 1-year from September 9, 2008 to September 9, 2009 in accordance with ASME Section XI, IWA-2430. The Second GISI Interval started on September 10, 2009 and ends on September 1O, 2019. The Second GISI Interval cannot be further extended by application of IWA-2430{d) because it causes successive intervals to be altered by more than one year from the original pattern of intervals.
Oyster Creek plans to permanently shutdown on December 31, 2019 (Reference 1).
Exelon Generation Company, LLC (EGC) has evaluated the extensive resources required for planning and execution of torus desludging as well as the worker radiation dose exposures resulting from performance of torus inspections. EGC has established a technical basis for extending torus inspections from 48 months to 64 months (Reference
- 3) and concludes that the proposed alternative as described herein provides an acceptable level of quality and safety.
- 5. PROPOSED ALTERNATIVE AND BASIS FOR USE:
Proposed Alternative EGC proposes an alternative to the inspection frequency of Torus and Vent System visual examinations for the current (second) 10-Year Containment lnservice Inspection (GISI) Interval. The alternative requests a 16-month extension of the ASME Section XI examinations currently required to be performed in the OC1 R27 Refuel Outage (September 2018). This request would extend the torus inspections to January 31, 2020. The proposed alternative would provide an acceptable level of quality and safety.
No alternatives to the examination processes required by ASME Code are proposed.
This deferral will allow planning and execution resources to be applied to other plant activities that will improve nuclear safety and safe plant operations, and will avoid unnecessary radiation dose exposures resulting from performance of these inspections in the OC1 R27 Refuel Outage.
CISI Program Plan Oyster Creek Nuclear Generating Station, Second Interval 10 CFR 50.55a RELIEF REQUEST: ISR-11 Revision 0 (Page 3 of 4)
Relief Request for Extension of Torus Examinations in Accordance with 10 CFR 50.55a(z)(1)
Basis for Use EGC's request is based on a MPR calculation 0083-0338-CALC-001, Torus Pit Geometry and Coating Chips Generation Evaluation for Oyster Creek Nuclear Generating Station," (Reference 3). This calculation provides a technical basis for extending torus inspections from 48 months to 64 months by evaluating Torus structural integrity and Emergency Core Cooling System (ECCS) strainer head loss.
Torus structural integrity is evaluated by estimating the maximum pit depths at 48 months and 64 months after the most recent inspection using data from OC1 R25 and OC1 R23 refueling outages. Estimated maximum pit depths are compared to Torus pitting acceptance criteria (Reference 4). Both vapor and submerged areas of the Torus are considered for evaluation. Results of the MPR calculation estimated the maximum pit depth of 0.080 inch at 48 months and 0.107 inch at 64 months which is significantly less than the Torus pitting acceptance criteria (0.173 inch).
ECCS strainer head loss is evaluated by estimating the total weight of the fractured and cracked torus coating blisters at 48 months and 64 months after the most recent inspection using data from OC1 R25 and OC1 R23 refueling outages. Estimated total weight of the fractured and cracked torus coating blisters are compared to the ECCS strainer acceptance criteria. Results of the MPR calculation estimated the total weight of the fractured and cracked torus coating blisters to be 2.28 lbs. at 48 months and 2.56 lbs. at 64 months which is significantly less than the ECCS strainer acceptance criteria (1 O lbs.).
Based on the results of MPR calculation, it is concluded that the Torus structural integrity and ECCS strainer acceptance criteria are predicted to be met in both the vapor and submerged areas of the Torus if the inspection is extended from 48 months to 64 months. Therefore, extending the torus inspections by 16 months will provide an acceptable level of quality and safety.
- 6. DURATION OF PROPOSED ALTERNATIVE:
The proposed alternative is requested to extend torus visual examinations from the OC1 R27 Refuel Outage (September 2018) to January 31, 2020. In Reference 1, EGC had previously notified the NRC of EGC's plans to permanently shut down Oyster Creek and cease operation no later than December 31, 2019. EGC believes that the deferred inspection will not be required to be performed at the January 31, 2020 milestone because Oyster Creek will cease operations and submit the certifications required by 10 CFR 50.82(a)(1 ). The requested inspection deferral does, however, preserve the requirement to perform the inspection in the event that permanent cessation of operation occurs after December 31, 2019.
CISI Program Plan Oyster Creek Nuclear Generating Station, Second Interval 10 CFR 50.55a RELIEF REQUEST: ISR-11 Revision 0 (Page 4 of 4)
Relief Request for Extension of Torus Examinations in Accordance with 10 CFR 50.55a(z)(1)
- 7. PRECEDENTS:
None.
- 8.
REFERENCES:
- 1. Exelon Generation Company, LLC letter to USNRC, "Permanent Cessation of Operations at Oyster Creek Nuclear Generating Station," dated January 7, 2011
- 2. Oyster Creek Second 10-Year Containment (IWE) lnservice Inspection Program Plan, ER-OC-330-2006, Revision 1, dated July 26, 2011
- 3. MPR Calculation 0083-0338-CALC-001, "Torus Pit Geometry and Coating Chips Generation Evaluation for Oyster Creek Nuclear Generating Station," Revision 3
- 4. MPR-2974 "Oyster Creek Nuclear Generation Station Torus Pitting Inspection Evaluation Criteria," Revision O