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Category:Inservice/Preservice Inspection and Test Report
[Table view] Category:Letter
MONTHYEARML23342A1162024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 IR 05000219/20230022023-11-0909 November 2023 EA-23-076 Oyster Creek Nuclear Generating Station - Notice of Violation and Proposed Imposition of Civil Penalty - $43,750 - NRC Inspection Report No. 05000219/2023002 ML23286A1552023-10-13013 October 2023 Defueled Safety Analysis Report (DSAR) ML23249A1212023-09-0606 September 2023 NRC Inspection Report 05000219/2023002, Apparent Violation (EA-23-076) ML23242A1162023-08-30030 August 2023 Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Report January 1, 2021 Through December 31, 2022 ML23214A2472023-08-22022 August 2023 NRC Inspection Report 05000219/2023002 IR 05000219/20230012023-05-31031 May 2023 NRC Inspection Report No. 05000219/2023001 IR 07200015/20234012023-05-16016 May 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2023401 ML23114A0912023-04-24024 April 2023 Annual Radioactive Effluent Release Report for 2022 ML23114A0872023-04-24024 April 2023 Annual Radioactive Environmental Operating Report for 2022 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000219/20220022023-02-0909 February 2023 NRC Inspection Report No. 05000219/2022002 ML23031A3012023-02-0808 February 2023 Discontinuation of Radiological Effluent Monitoring Location in the Sewerage System ML23033A5052023-02-0202 February 2023 First Use Notification of NRC Approved Cask RT-100 ML23025A0112023-01-24024 January 2023 LLRW Late Shipment Investigation Report Per 10 CFR 20, Appendix G ML22347A2732022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 ML22297A1432022-12-15015 December 2022 Part 20 App G Exemption Letter L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 IR 07200015/20224012022-12-0606 December 2022 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2022401 (Letter & Enclosure 1) ML22280A0762022-11-0202 November 2022 Us NRC Analysis of Holtec Decommissioning Internationals Funding Status Report for Oyster Creek, Indian Point and Pilgrim Nuclear Power Station ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22286A1402022-10-13013 October 2022 NRC Confirmatory Order EA-21-041 IR 05000219/20220012022-08-11011 August 2022 NRC Inspection Report 05000219/2022001 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22214A1732022-08-0202 August 2022 Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML22207B8382022-07-26026 July 2022 NRC Confirmatory Order EA-21-041 ML22130A6882022-05-10010 May 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 ML22118A6122022-04-28028 April 2022 Annual Radioactive Environmental Operating Report for 2021 ML22118A5822022-04-28028 April 2022 Annual Radioactive Effluent Release Report for 2021 ML22091A1062022-04-0101 April 2022 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) L-22-022, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec. ML22069A3762022-03-10010 March 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML22032A0582022-03-0808 March 2022 EA-21-139; EA-150: Oyster Creek Nuclear Generating Station - NRC Investigation Report Nos.. 1-2021-002 & 1-2021-014 ML22060A2202022-03-0202 March 2022 NRC Office of Investigations Case No. 1-2021-009 ML22049B2452022-02-19019 February 2022 Late Low Level Radwaste Shipment Report Pursuant to 10 CFR 20 Appendix G IR 05000219/20214022022-01-26026 January 2022 EA-21-041: Confirmatory Order Related to Oyster Greek Nuclear Generating Station - NRC Investigation Report I-2020-007; NRC Inspection Report Nos. 05000219/2021402 & 07200015/2021401 ML22025A3422022-01-25025 January 2022 and Big Rock Point - Changes to Site Organization ML22025A2182022-01-25025 January 2022 Late LLRW Shipments Investigation Report Pursuant to 10 CFR 20, Appendix G ML22021B5512022-01-21021 January 2022 Compensatory Measures Not Implemented Per Site'S Physical Security Plan Due to Multiplexer (Mux) Power Supply Failure L-21-134, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations2021-12-17017 December 2021 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations ML21349A5192021-12-15015 December 2021 Commitment Change Summary Report ML21285A1912021-11-30030 November 2021 Nrc'S Analysis of Holtec Decommissioning International'S Decommissioning Funding Status Report for Oyster Creek Nuclear Generating Station and Pilgrim Nuclear Power Station, Docket Nos 50-219 and 50-293 IR 05000219/20210032021-11-16016 November 2021 NRC Inspection Report No. 05000219/2021003 L-21-118, Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades2021-11-0909 November 2021 Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades IR 05000219/20214042021-08-26026 August 2021 NRC Independent Spent Fuel Storage Security Inspection Report No. 07200015/2021402 and Security Decommissioning Inspection Report 05000219/2021404 - (Public) 2024-01-09
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Exelon Generation@ RA-17-014 February 10, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
- Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 Docket No. 50-219 Oyster Creek Route 9 South P.O. Box388 Forked River, NJ 08731 ASME Code,Section XI 1 OCFR50.55a
Subject:
Oyster Creek Nuclear Generating Station (OCNGS) 1 R26 Refueling Outage lnservice Inspection (ISi) Form OAR-1 Owner's Activity Report The purpose of this letter is to provide the Oyster Creek Nuclear Generating Station Owner's Activity Report (OAR-1) for lnservice Inspections as required by the American Society of Mechanical Engineers (ASME) Code,Section XI, 2007 Edition with 2008 Addenda ASME Code Case N-532-4 Repair/Replacement Activity Documentation Requirements and lnservice Summary Report Preparation and Submission -Section XI, Division 1. Attachment 1 is the Form OAR-1 Owner's Activity Report covering ISi activities associated with the 1 R26 Refueling Outage which started on September 19, 2016, and was the first outage of the second period of the current ISi inspection interval. OCNGS was unable to complete the Form OAR-1 within 90 calendar days of the completion of the refueling outage as required by Code Case N-532-5. This non-compliance was entered into the site corrective action program under Issue Report Number 3961771 and communicated to the NRC per letter RA-16-112 dated January 11, 2017 (Accession Number ML 17018A073). If you should have any questions, please contact the Oyster Creek ISi point of contacts, Valmicky Samlal at 609-971-4112 or Tedd Nickerson at 609-971-2197. Sincerely, Vice President Oyster Creek Nuclear Generating Station U.S. Nuclear Regulatory Commission February 10, 2017 Page 2 of 2
Enclosures:
Attachment 1 -Form OAR-1 Owner's Activity Report-1 R26 Outage cc: USNRC, Regional Administrator, Region I USNRC, Senior Project Manager, NRR USNRC, Senior Resident Inspector Gary Gustafson, Hartford Steam Boiler l&I Co.
FORM OAR*l OWNER'S ACTIVITY REPORT Plant: Oyster Creek Nuclear Generating Station, US Route 9 South, Forked River. NJ 08731 Unit No: _1'"'--____ Commercial service date: December 23, 1969 Refueling Outage No: _.2=6,__ ___ _ {if appncableJ Current Inspection -""IS"-l ==Sth_,_/""'C"'"IS:.:..l ll11, 2!14,. 3m, other} Current inspection period: _1 ... s ... 1 .... Edition and Addenda of Section XI appl!cable to the Inspection plans: 2007 Edition with 2008 Addenda for ISi and 2001 Edition with 2003 Addenda for CISI Date and revision of inspection plans: 09/02/2015, Revision 2 for ISi and 07 {26/2011. Revision 1 for ClSI Edition and Addenda of Section XI applicable to repa;r/replacement activities, if different than the inspection plans NA Code Cases used for inspection and evaluation: N-432-1, N-513-3. N-516-3, N-526, N-532-5. N-537. N-561-2, N-583. N-586*1, N-597-2, N-600, N-606-1, N-609, N-613-1, N-629, N-638-4, N-639, N-641, N-647, N-648-1, N-649. N-651, N-658, N-661-2, N-663, N-665, N-666, N-683, N-696, N-700, N-705, N-712,
- N-730. N-733, N-735, N-747, N-762, N-765, N-769, N-773, N-786. and N-789 CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (bl the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c} the repair/replacement activities and evaluations supporting the completion of ""'o""'c .... 1 .. R""'2""6 ________ conform to the requlrements of Section XI. (refueling outage number) Signed Gene Navratil. 151 Program Owner Ownor or Owner's Des!gnee, Title Date a/t/17 CERTIFICATE OF INSERVICE INSPECTION !, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requlrements of Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, el!pressed or implied, concerning the repalr/replacemen.t a(..iivities and evaluation descrribed in this report. Furthermore, nelther the inspector nor his employer shall be liable in any manner for any personnel injury or property damage or a loss of any kind arising ftom or Ga!Y 13855 ANIC N.1948 (Notional B"trd M"mbe< a>nd Endcrs*men!) Date __ -zht 7 Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category Item Description Evaluation Description and Item Number F-A, F1.20C Containment Spray piping support Support evaluated with one anchor bolt not 241-0080 credited for structural support per Engineering Change 617885. B-P, BlS.10 Mechanical joint leakage identified Mechanical joint leakage evaluated as acceptable during Class 1 leakage test per IR 3968718.
Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number 3 P-3-3A Replace ESW pump. 02/07/2017 R2131578 1 P-37-4 Replace recirculation 02/02/2017 C2036150 pump seal. 3 Y-11-2 Replace expansion 01/29/2017 CZ036974 joint. 1 V-1-164 Replace main steam 01/10/2017 R2181961 relief valve due to failed lift test. Valve lifted at -3.3% of set pressure (-4 psig out of tolerance) and would have fulfilled its function to relieve reactor pressure If reauired. 1 Control Rod Drive Replace control rod 02/06/2017 C2036154 14-47 drive due to flange joint leak.