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| {{#Wiki_filter:, AmerGen.AmerGen Energy Company www.exeloncorp.com An Exelon Company Oyster Creek US Route 9 South, P.O. Box 388 Forked River, NJ 08731-0388 November 6, 2006 Technical Specification 4.5.G 2130-06-20417 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 -0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219 | | {{#Wiki_filter:, |
| | AmerGen Energy Company www.exeloncorp.com AmerGen. An Exelon Company Oyster Creek US Route 9 South, P.O. Box 388 Forked River, NJ 08731-0388 November 6, 2006 Technical Specification 4.5.G 2130-06-20417 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219 |
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| ==Subject:== | | ==Subject:== |
| Secondary Containment Capability Test The Oyster Creek Generating Station Technical Specification 4.5.G.4 requires that the results of the secondary containment capability tests shall be in the subject of a summary technical report. Attachment I to this letter provides the 1 R21 Outage test results, as required.If any further information or assistance is needed, please contact Kathy Barnes at 609-971-4970.Sincerely, othy S. Rausch Vice President, Oyster Creek Generating Station Attachment cc: S. J. Collins, Administrator, USNRC Region I G. E. Miller, USNRC Senior Project Manager, Oyster Creek M. Ferdas, USNRC Senior Resident Inspector, Oyster Creek File No. 06005 C)ooI Attachment I Summary Technical report Secondary Containment Capability Test Oyster Creek Generating Station Operating Cycle 20; Prior to Refueling Outage 1 R21 Date Performed: | | Secondary Containment Capability Test The Oyster Creek Generating Station Technical Specification 4.5.G.4 requires that the results of the secondary containment capability tests shall be in the subject of a summary technical report. Attachment I to this letter provides the 1R21 Outage test results, as required. |
| October 8, 2006 1. Wind Speed Test Prerequisite | | If any further information or assistance is needed, please contact Kathy Barnes at 609-971-4970. |
| "... calm wind ..." Observed 2.7 mph in 259.6 direction 2.6 mph in 260.4 direction 2. Standby Gas Treatment System Flow Rate Test Requirement Recorded< 4000 cfm 2485 cfm (recorded) 2429.98 cfm (corrected) 2495 cfm (at end of test)3. Reactor Building Differential Pressure Test Requirements Both Railroad Airlock Doors Closed> -0.25 inches W. G. vacuum Outer Railroad Airlock Door Open> -0.25 inches W. G. vacuum Inner Railroad Airlock Door Open> -0.25 inches W. G. vacuum Test Results 0.362 inches W. G.0.357 inches W. G.0.289 inches W. G.}} | | Sincerely, othy S. Rausch Vice President, Oyster Creek Generating Station Attachment cc: S. J. Collins, Administrator, USNRC Region I G. E. Miller, USNRC Senior Project Manager, Oyster Creek M. Ferdas, USNRC Senior Resident Inspector, Oyster Creek File No. 06005 C)ooI |
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| | Attachment I Summary Technical report Secondary Containment Capability Test Oyster Creek Generating Station Operating Cycle 20; Prior to Refueling Outage 1R21 Date Performed: October 8, 2006 |
| | : 1. Wind Speed Test Prerequisite Observed |
| | "... calm wind ... " 2.7 mph in 259.6 direction 2.6 mph in 260.4 direction |
| | : 2. Standby Gas Treatment System Flow Rate Test Requirement Recorded |
| | < 4000 cfm 2485 cfm (recorded) 2429.98 cfm (corrected) 2495 cfm (at end of test) |
| | : 3. Reactor Building Differential Pressure Test Requirements Test Results Both Railroad Airlock Doors Closed |
| | > - 0.25 inches W. G. vacuum 0.362 inches W. G. |
| | Outer Railroad Airlock Door Open |
| | > - 0.25 inches W. G. vacuum 0.357 inches W. G. |
| | Inner Railroad Airlock Door Open |
| | > - 0.25 inches W. G. vacuum 0.289 inches W. G.}} |
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Category:Fuel Cycle Reload Report
MONTHYEARRA-18-072, Pressure and Temperature Limit Report Revision 12018-06-29029 June 2018 Pressure and Temperature Limit Report Revision 1 ML13262A2792013-07-24024 July 2013 Operating Limits Report Cycle 24 ML12363A0652012-11-0808 November 2012 Core Operating Limits Report for Oyster Creek 1 Cycle 24 RA-11-026, Revision of the Core Operating Limits Report for Reload 22, Cycle 23, Revision 62011-05-12012 May 2011 Revision of the Core Operating Limits Report for Reload 22, Cycle 23, Revision 6 ML1033501282010-11-16016 November 2010 Core Operating Limits Report for Reload 22, Cycle 23, Revision 5 RA-08-106, Issuance of the Oyster Creek Core Operating Limits Report for Cycle 22, Revision 42008-11-0606 November 2008 Issuance of the Oyster Creek Core Operating Limits Report for Cycle 22, Revision 4 RA-08-064, Issuance of Core Operating Limits Report for Cycle 21, Revision 32008-06-30030 June 2008 Issuance of Core Operating Limits Report for Cycle 21, Revision 3 ML0631902192006-11-0606 November 2006 Oyster Creek Generating Station, Secondary Containment Capability Test from 1R21 Outage Test ML0629603682006-10-23023 October 2006 Issuance of the Oyster Creek Operating Limits Report for Cycle 21 (Document No. COLR Oyster Creek 1 Rev 2) ML0615304722006-06-0202 June 2006 Issuance of the Oyster Creek Core Operating Limits Report for Cycle 20, Revision 1 ML0432206362004-11-17017 November 2004 Core Operating Limits Report for Oyster Creek Cycle 20, Revision 0 ML0416301492004-06-0707 June 2004 Core Operating Limits Report, Revision 17 ML0413303962004-05-0404 May 2004 Core Operating Limits Report, Revision 16 ML0317605332003-06-18018 June 2003 Core Operating Limits Report, Revision 15 ML0229100542002-10-0808 October 2002 Core Operating Limits Report - Rev 14 ML0232602272002-08-22022 August 2002 Core Operating Limits Report, Revision 13 2018-06-29
[Table view] Category:Letter
MONTHYEARML24274A0822024-09-25025 September 2024 Independent Spent Fuel Storage Installation Security Plan, Training Qualification Plan, Safeguards Contingency Plan, Revisions 1 and 2 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000219/20240022024-09-0505 September 2024 – NRC Inspection Report 05000219/2024002 and 07200015/2024001 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24214A0372024-08-0101 August 2024 License Amendment Request to Revise Renewed Facility Operating License to Add License Condition 2.C.(18) to Include License Termination Plan Requirements ML24179A1842024-07-23023 July 2024 June 20, 2024, Clarification Call on Preapplication Readiness Assessment of the Holtec Decommissioning International License Termination Plan ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000219/20240012024-05-14014 May 2024 Decommissioning Intl, LLC Oyster Creek Nuclear Generating Station - NRC Inspection Report No. 05000219/2024001 ML24120A0412024-04-29029 April 2024 Annual Radioactive Environmental Operating Report for 2023 L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 ML24120A0402024-04-29029 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24094A2142024-04-19019 April 2024 Preapplication Readiness Assessment of the Holtec Decommissioning International License Termination Plan ML24089A2492024-03-29029 March 2024 Reply to Notice of Violation EA-2024-024 L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) ML24085A7902024-03-28028 March 2024 – Preapplication Readiness Assessment of the License Termination Plan ML24081A2882024-03-21021 March 2024 Request Preliminary Review and Feedback on Chapter 6 of the Draft License Termination Plan ML24046A1242024-02-29029 February 2024 – NRC Inspection Report 05000219/2023003 ML24033A3272024-02-0202 February 2024 Request Preliminary Review and Feedback on Chapter 5 of the Draft License Termination Plan ML23342A1162024-01-0909 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 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 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-23-003, 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 2024-09-05
[Table view] |
Text
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AmerGen Energy Company www.exeloncorp.com AmerGen. An Exelon Company Oyster Creek US Route 9 South, P.O. Box 388 Forked River, NJ 08731-0388 November 6, 2006 Technical Specification 4.5.G 2130-06-20417 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Secondary Containment Capability Test The Oyster Creek Generating Station Technical Specification 4.5.G.4 requires that the results of the secondary containment capability tests shall be in the subject of a summary technical report. Attachment I to this letter provides the 1R21 Outage test results, as required.
If any further information or assistance is needed, please contact Kathy Barnes at 609-971-4970.
Sincerely, othy S. Rausch Vice President, Oyster Creek Generating Station Attachment cc: S. J. Collins, Administrator, USNRC Region I G. E. Miller, USNRC Senior Project Manager, Oyster Creek M. Ferdas, USNRC Senior Resident Inspector, Oyster Creek File No. 06005 C)ooI
Attachment I Summary Technical report Secondary Containment Capability Test Oyster Creek Generating Station Operating Cycle 20; Prior to Refueling Outage 1R21 Date Performed: October 8, 2006
- 1. Wind Speed Test Prerequisite Observed
"... calm wind ... " 2.7 mph in 259.6 direction 2.6 mph in 260.4 direction
- 2. Standby Gas Treatment System Flow Rate Test Requirement Recorded
< 4000 cfm 2485 cfm (recorded) 2429.98 cfm (corrected) 2495 cfm (at end of test)
- 3. Reactor Building Differential Pressure Test Requirements Test Results Both Railroad Airlock Doors Closed
> - 0.25 inches W. G. vacuum 0.362 inches W. G.
Outer Railroad Airlock Door Open
> - 0.25 inches W. G. vacuum 0.357 inches W. G.
Inner Railroad Airlock Door Open
> - 0.25 inches W. G. vacuum 0.289 inches W. G.