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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 |
| | |
| | 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
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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
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Independent Spent Fuel Storage Installation Security Inspection Plan
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Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Report January 1, 2021 Through December 31, 2022
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IR 05000219/20230012023-05-31031 May 2023
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NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2023401
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Annual Radioactive Effluent Release Report for 2022
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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
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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
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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
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NRC Confirmatory Order EA-21-041
ML22130A6882022-05-10010 May 2022
Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G
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Occupational Radiation Exposure Data Report - 2021
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Annual Radioactive Environmental Operating Report for 2021
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Annual Radioactive Effluent Release Report for 2021
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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
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NRC Office of Investigations Case No. 1-2021-009
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Late Low Level Radwaste Shipment Report Pursuant to 10 CFR 20 Appendix G
IR 05000219/20214022022-01-26026 January 2022
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IR 05000219/20210032021-11-16016 November 2021
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2024-01-09
[Table view] |
Text
,
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.