Similar Documents at Salem |
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARLR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N22-0068, In-Service Inspection Activities - 90-Day Report2022-08-10010 August 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0013, In-Service Inspection Activities - 90-Day Report2022-02-10010 February 2022 In-Service Inspection Activities - 90-Day Report LR-N21-0075, Updated Steam Generator Tube Inspection Report - March 2020 to Reflect TSTF-577 Reporting Requirements2021-11-0202 November 2021 Updated Steam Generator Tube Inspection Report - March 2020 to Reflect TSTF-577 Reporting Requirements LR-N21-0076, Updated Steam Generator Tube Inspection Report - Twenty-second Refueling Outage (2R22) to Reflect TSTF-577 Reporting Requirements2021-11-0101 November 2021 Updated Steam Generator Tube Inspection Report - Twenty-second Refueling Outage (2R22) to Reflect TSTF-577 Reporting Requirements LR-N21-0032, Report of Changes, Tests, and Experiments2021-04-0202 April 2021 Report of Changes, Tests, and Experiments LR-N21-0021, In-Service Inspection Activities - 90-Day Report2021-03-11011 March 2021 In-Service Inspection Activities - 90-Day Report LR-N21-0014, Snubber Program Plan, Fifth Ten-Year Inspection Interval, Effective from January 1, 2021 Through December 31, 20302021-02-16016 February 2021 Snubber Program Plan, Fifth Ten-Year Inspection Interval, Effective from January 1, 2021 Through December 31, 2030 LR-N20-0062, Steam Generator Tube Inspection Report - March 20202020-09-17017 September 2020 Steam Generator Tube Inspection Report - March 2020 LR-N19-0106, Submittal of Program for Salem Units 1 and 2 Fifth Ten-Year Interval Inservice Testing Program2019-11-25025 November 2019 Submittal of Program for Salem Units 1 and 2 Fifth Ten-Year Interval Inservice Testing Program LR-N19-0089, In-Service Inspection Activities - 90-Day Report2019-09-12012 September 2019 In-Service Inspection Activities - 90-Day Report LR-N19-0011, In-Service Inspection Activities - 90-Day Report2019-02-11011 February 2019 In-Service Inspection Activities - 90-Day Report LR-N18-0054, Steam Generator Tube Inspection Report: Twenty-fifth Refueling Outage (1R25)2018-05-0707 May 2018 Steam Generator Tube Inspection Report: Twenty-fifth Refueling Outage (1R25) LR-N17-0174, Steam Generator Tube Inspection Report - Twenty-Second Refueling Outage (2R22)2017-11-21021 November 2017 Steam Generator Tube Inspection Report - Twenty-Second Refueling Outage (2R22) LR-N17-0134, In-Service Inspection Activities, 90-Day Report2017-08-28028 August 2017 In-Service Inspection Activities, 90-Day Report LR-N17-0009, Steam Generator Tube Inspection Report - Twenty-fourth Refueling Outage (1R24)2017-01-20020 January 2017 Steam Generator Tube Inspection Report - Twenty-fourth Refueling Outage (1R24) LR-N16-0187, In-Service Inspection Activities - 90-Day Report, Owner'S Activity Report S1RFO242016-10-11011 October 2016 In-Service Inspection Activities - 90-Day Report, Owner'S Activity Report S1RFO24 LR-N16-0025, In-Service Inspection Activities - 90-Day Report2016-02-26026 February 2016 In-Service Inspection Activities - 90-Day Report LR-N15-0037, In-Service Inspection Activities - 90-Day Report2015-02-23023 February 2015 In-Service Inspection Activities - 90-Day Report LR-N14-0232, Steam Generator Tube - Inspection Report - Twentieth Refueling Outage (2R20)2014-10-30030 October 2014 Steam Generator Tube - Inspection Report - Twentieth Refueling Outage (2R20) ML14070A2542014-03-26026 March 2014 Review of the Fall 2012 Steam Generator Tube Inservice Inspections During Refueling Outage 2R19 LR-N13-0256, Inservice Inspection (Lsi) Program Plan, Fourth Ten-Year Interval2013-11-11011 November 2013 Inservice Inspection (Lsi) Program Plan, Fourth Ten-Year Interval LR-N13-0159, In-Service Inspection Activities - 90-Day Report2013-07-24024 July 2013 In-Service Inspection Activities - 90-Day Report LR-N13-0021, Inservice Inspection Activities - 90-Day Report2013-02-0101 February 2013 Inservice Inspection Activities - 90-Day Report LR-N13-0021, Salem Nuclear Generating Station Unit 2 - Inservice Inspection Activities - 90-Day Report2013-02-0101 February 2013 Salem Nuclear Generating Station Unit 2 - Inservice Inspection Activities - 90-Day Report LR-N11-0382, Inservice Inspection Activities - 90-Day Report2012-01-19019 January 2012 Inservice Inspection Activities - 90-Day Report LR-N11-0213, Inservice Inspection (Lsi) Program Plan, Fourth Ten-Year Interval2011-08-11011 August 2011 Inservice Inspection (Lsi) Program Plan, Fourth Ten-Year Interval LR-N10-0361, Request for Relief from ASME Code Pressure Test for Service Water Supply Buried Piping2010-10-12012 October 2010 Request for Relief from ASME Code Pressure Test for Service Water Supply Buried Piping LR-N10-0256, Submittal of Inservice Inspection Activities - 90-Day Report2010-07-20020 July 2010 Submittal of Inservice Inspection Activities - 90-Day Report LR-N10-0007, Additional Information Related to Relief Requests S1-I3R-93, S2-I3R-94, and SC-I3R-952010-01-13013 January 2010 Additional Information Related to Relief Requests S1-I3R-93, S2-I3R-94, and SC-I3R-95 LR-N10-0002, Inservice Inspection Activities - 90-Day Report2010-01-0808 January 2010 Inservice Inspection Activities - 90-Day Report ML1034404472009-12-23023 December 2009 Document: Inservice Testing Auxiliary Feedwater Valves Mode 3. S2.OP-ST.AF-0007Q Rev. 20 LR-N09-0295, Units 1 and 2, Supplement to License Amendment Request S09-06, Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components2009-12-21021 December 2009 Units 1 and 2, Supplement to License Amendment Request S09-06, Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components LR-N09-0016, Inservice Inspection Activities - 90-Day Report2009-02-0505 February 2009 Inservice Inspection Activities - 90-Day Report LR-N08-0174, Inservice Inspection Activities - 90-Day Report2008-08-0606 August 2008 Inservice Inspection Activities - 90-Day Report ML0807200682008-02-25025 February 2008 Re-Submittal of Inservice Testing Program Relief Requests P01, V03 and V04 LR-N07-0172, Inservice Inspection Activities - 90-Day Report2007-07-20020 July 2007 Inservice Inspection Activities - 90-Day Report LR-N07-0071, Generation - Unit 2, Withdrawal of Inservice Inspection Program Relief Requests S2-I2-RR-B01 and S2-I2-RR-C012007-03-26026 March 2007 Generation - Unit 2, Withdrawal of Inservice Inspection Program Relief Requests S2-I2-RR-B01 and S2-I2-RR-C01 LR-N07-0045, Steam Generator Tube ISI Summary Report2007-03-0101 March 2007 Steam Generator Tube ISI Summary Report LR-N05-0380, Inservice Inspection Activities - 90 Day Report Fourteenth Refueling Outage Salem Generating Station Unit 22005-08-11011 August 2005 Inservice Inspection Activities - 90 Day Report Fourteenth Refueling Outage Salem Generating Station Unit 2 LR-N05-0240, Inservice Inspection Program Relief Request S2-13-RR-F012005-04-24024 April 2005 Inservice Inspection Program Relief Request S2-13-RR-F01 LR-N05-0168, Relief, Inservice Inspection Program Relief Request S2-13RR-F01 Re Requirements for Testing Dynamic Restraints2005-04-0808 April 2005 Relief, Inservice Inspection Program Relief Request S2-13RR-F01 Re Requirements for Testing Dynamic Restraints LR-N04-0328, Inservice Inspection Activities - 90 Day Report Sixteenth Refueling Outage2004-09-0101 September 2004 Inservice Inspection Activities - 90 Day Report Sixteenth Refueling Outage LR-N04-0299, Inservice Inspection Program Relief Requests S1-RR-04-V01 and V022004-07-0909 July 2004 Inservice Inspection Program Relief Requests S1-RR-04-V01 and V02 ML0408000072004-05-0404 May 2004 Review of Inservice Inspection Reports for Steam Generator Tube Inspections Conducted During the 2002 Refueling Outages LR-N04-0130, Update ASME XI Code of Record, Request That Relief Request S1-I3-RR-A13 Be Withdrawn2004-03-24024 March 2004 Update ASME XI Code of Record, Request That Relief Request S1-I3-RR-A13 Be Withdrawn LR-N04-0242, Unit 2 - Inservice Inspection Program, Long Term Plan, Third Interval, Revision 0, Volume a, Drawing ISI301 Through ISI2462003-11-30030 November 2003 Unit 2 - Inservice Inspection Program, Long Term Plan, Third Interval, Revision 0, Volume a, Drawing ISI301 Through ISI246 LR-N04-0424, Unit 2 - Inservice Inspection Program, Long Term Plan, Third Interval, Revision 0, Volume a, Appendix C Through Appendix E2003-11-30030 November 2003 Unit 2 - Inservice Inspection Program, Long Term Plan, Third Interval, Revision 0, Volume a, Appendix C Through Appendix E LR-N02-0453, Supplemental Information Inservice Inspection Program Relief Requests S2-RR-03-V01 and V022003-10-24024 October 2003 Supplemental Information Inservice Inspection Program Relief Requests S2-RR-03-V01 and V02 LR-N03-0451, Inservice Inspection Program Relief Requests S2-RR-03-V01 and V022003-10-23023 October 2003 Inservice Inspection Program Relief Requests S2-RR-03-V01 and V02 2023-07-26
[Table view] Category:Letter type:LR
MONTHYEARLR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0095, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 20222022-12-20020 December 2022 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2022 LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0092, Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG2022-12-0909 December 2022 Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments LR-N22-0084, Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095)2022-11-17017 November 2022 Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095) LR-N22-0090, Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2022-11-10010 November 2022 Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2022-09-27027 September 2022 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate LR-N22-0066, License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)2022-08-31031 August 2022 License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM) LR-N22-0063, Spent Fuel Cask Registration2022-08-10010 August 2022 Spent Fuel Cask Registration LR-N22-0068, In-Service Inspection Activities - 90-Day Report2022-08-10010 August 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature2022-08-0707 August 2022 License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature LR-N22-0062, Spent Fuel Cask Registration2022-07-21021 July 2022 Spent Fuel Cask Registration LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2022-06-29029 June 2022 License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0043, Core Operating Limits Report - Cycle 292022-05-0909 May 2022 Core Operating Limits Report - Cycle 29 LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022 Emergency Plan Document Revisions Implemented March 24, 2022 LR-N21-0052, Request for Relief from ASME Code Defect Removal for Service Water Buried Piping2022-04-0707 April 2022 Request for Relief from ASME Code Defect Removal for Service Water Buried Piping LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022 Guarantees of Payment of Deferred Premiums LR-N22-0022, Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds2022-03-21021 March 2022 Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds LR-N22-0017, Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data2022-02-25025 February 2022 Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022 Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility LR-N22-0013, In-Service Inspection Activities - 90-Day Report2022-02-10010 February 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs LR-N21-0061, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2021-12-0909 December 2021 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N21-0083, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion2021-11-24024 November 2021 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0066, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2021-11-10010 November 2021 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations 2023-09-08
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 FEBA ZOO9 0 PSEG Nuclear LLC LR-N09-0016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-001 Salem Nuclear Generating Station Unit 1 Facility Operating License No. DPR-70 NRC Docket No. 50-272
SUBJECT:
Inservice Inspection Activities Day Report This letter submits the Owner's Activity Report for Inservice Inspection (ISl) activities conducted at the Salem Generating Station Unit No. 1 during the nineteenth refueling outage. This report is submitted in accordance with Code Case N-532-1 "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission Section XI, Division 1," and within the ninety (90) day reporting requirement. to this letter contains the required Salem Unit 1 Owner's Activity Report.
Should you have any questions regarding this submittal, please contact E. H. Villar at (856) 339-5456.
Sincerely, Robert Braun Site Vice President - Salem Enclosures (1) 4q-7 95-2168 REV. 7199
FEB 0 5 2009 Nuclear Regulatory Commission Page 2 LR-N09-0016 C Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Project Manager - Salem U.S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)
Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 Mr. Milton Washington Chief Inspector NJ Department of Labor Division of Public Safety, Occupational Safety and Health Bureau of Boiler and Pressure Vessel Compliance P. O. Box 396 101 South Broad Street Trenton, NJ -08625-0392
Nuclear Regulatory Commission LR-N09-0016 Salem Unit I Owner's Activity Report - S1 RI 9 In Accordance With ASME Section XI Code Case N-532-1
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FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number SIRFO 19 Owner PSEG Nuclear LLC, PO Box 236, Hancocks Bridge, NJ 08038 Plant Salem Generating Station Unit No. 1 Commercial Service Date July 1, 1977 Refueling Outage No. 19 Current Inspection Interval Third (3 rd) {IWE/IWL (Ist)}
Current Inspection Period Third (3 rd) {IWE/IWL ( 3 rd)}
Edition and Addenda of Section XI Applicable to the inspection plan 1998 Edition 2000 Addenda; IWE and IWL - 1998 Edition, 1998 Addenda; Appendix VIII examinations - 1995 Edition 1996 Addenda as amended by Final Rule Date and revision of inspection plan 11/2003, Revision 1 Edition & Addenda of Section XI Applicable to repairs and replacements, if different than the inspection plan ASME Class 1, 2 and 3 - 1998 Edition, 2000 Addenda; Class MC/CC - 1992 Edition, 1992 Addenda (Unless specifically identified in the individual repair plan)
CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report conform to the requirements of Section XI.
Certification of Authorization No. N/A Expiration Date N/A Signed 4 ;jý. , f.f Itrt,.
4 ,t.Arcf, e - Date 67 t/5- /Zeo?
- / -wderor Owner'm'Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New J~rsey and employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut have inspected the items described in this Owner's Activity Report, during the period April 20, 2007 to. November 14, 2008, 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 requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, evaluations and corrective measures described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions "IjL.j-,8SA /,U'."/C?8 Inspector's Signature National Board, State, Province, and Endorsements Date J /1/5s~,
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TABLE 1 - ABSTRACT OF EXAMINATIONS AND TESTS Exam Total Total Total Total Remarks Category Examinations Examinations Examinations Examinations Required for the Credited for the Credited (%) for Credited (%) To 3 rd Interval 3 rd Period the 3rd Period Date for the 3rd Interval B-A 21 0 0 5 3rd Interval, 3 rd Period; See Note 1 B-B 5 0 0 60 3 rd Interval, 3 rd Period; See Note 5 B-D 30 0 0 37 3rd Interval, 3 rd Period; See Note 2 B-G-1 12 4 33 58 3Yd Interval, 3rd Period; See Note 1 B-G-2 84 23 27 90 3 rd Interval, 3 rd Period B-K 13 2 15 92 3 rd Interval, 3rd Period B-L-1 1 0 0 100 3 rd Interval, 3 rd Period; See Note 1 B-L-2 1 0 0 0 3 rd Interval, 3rd Period; See Note 3 B-M-1 1 1 100 100 3rd Interval, Yd 3 Period; See Note 1 B-M-2 8 0 0 50 3 rd Interval, 3rd Period; See Note 3 B-N-i 5 0 0 40 3 d Interval, 3Yd Period B-N-2 1 0 0 0 3rd Interval, 3rd Period; See Note 1 B-N-3 14 0 0 0 3 rd Interval, 3 d Period; See Note 1 B-0 1 0 0 0 3rd Interval, 3rd Period; See Note 1 B-P 12 2 17 83 3 rd Interval, 3rd Period C-A 21 4 19 76 3 rd Interval, 3 rd Period C-B 8 0 0 63 3 rd Interval, 3 rd Period; See Note 6 C-C 32 7 22 90 3 rd Interval, 3 rd Period C-D 2 0 0 50 3 rd Interval, 3rd Period; See Note 7 C-G 3 0 0 67 3rd Interval, 3 rd Period; See Note 8 C-H 155 39 25 55 3rd Interval, 3 rd Period D-A 32 0 0 72 3 rd Interval, 3 d Period D-B 162 34 21 88 3rd Interval, 3 rd Period F-A 358 8 2 73 3 d Interval, 3 rd Period R-A 166 33 20 80 Yd 3 Interval, 3 d Period; See Note 4 IWE/IWL 1st Interval 3 rd Period 3 rd Period 1st Interval E-A 474 158 33 99 1' Interval, 3 rd Period; See Note 9 L-A 558 0 0 67 1" Interval, 3 rd Period; Notes:
- 1) Deferral permissible for: B-A, B-E, B-G-l, B-L-l, B-M-l, B-N-2, B-N-3, B-O
- 2) Reference Table IWB-2500-1, Exam Category B-D, Program (B) Notes 2 and 5.
- 3) To be examined only if disassembled for maintenance, repair or volumetric exam. Reference Table IWB-2500-1, Exam Category B-L-2, B-M-2, Note 2
- 4) Risk Informed was implemented in the second interval, third period, replacing ASME categories B-F, B-J, C-F-i, and C-F-2.
- 5) Reference Table IWB-2500-1, Exam Category B-B, Note 1
- 6) Reference Table IWC-2500-1, Exam Category C-B, Note 4
- 7) Reference Table IWC-2500-1, Exam Category C-D, Note 2
- 8) Reference Table IWC-2500-1, Exam Category C-G, Note 1
- 9) Inaccessible components will be examined when they become accessible.
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TABLE 2 - ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Exam Item Item Description Flaw Flaw or Relevant Condition Category Number Characterization Found During Scheduled (IWA-3300) Section XI Examination or Test (Yes or No)
C-A C1.20 CHEMICAL AND VOLUME CONTROL TANK Two subsurface Yes SHELL TO LOWER HEAD WELD axial linear Sum# 204800 - Head to indications in head Lower Shell Weld.
to lower shell weld Scheduled Section XI Exam, Original Exam during IR13 no flaw growth noted.
Engineering Evaluation (Fracture Mechanics Analysis) - Use As Is.
R-A RI.15-2 14 RPV HOT LEG NOZZLE TO SAFE-END ID connected Yes (29-RC- 1140-1) circumferential Sum# 047301 - RPV 14 Hot indication 2.06" Leg Nozzle to Safe End long (1.9%) and Alloy 600 Weld. Indication 24.3% Through . evaluated using Flaw Wall Depth in RV Evaluation Handbook and Nozzle Safe End found acceptable for service Weld for 36 months.
Weld Mitigated using MSIP.
TABLE 3 - ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Code Repair, Itefim Description Description of Work Flaw or Relevant Date Repair/
Class Replacement, or Condition Found Completed Replacement Corrective During Scheduled Plan Number Measure Section XI Examination or Test (Yes or No) 2 Replacement 3/4" Elbow leak in line to Replaced leaking Yes 11/3/2008 60079160 12CS46 elbow in vent line to valve 12CS46 2 Replacement 3/4" weld leak D/S of Replace tubing by NO 10/2/2008 60078450 1CV299 Welding 3 Replacement 3/8" tubing leak D/S of Replace tubing by NO 5/16/2007 60069462 1SW366 Welding 3 Replacement 2" Valve body leak in Replace NO 12/18/2008 60078980 1 lSW241 S1SW -11 SW241 3 Replacement 3/8" tubing weld leak D/S Replace tubing by NO 9/27/2007 60067703 of 12CC197 Welding 3 Replacement 3/8" tubing leak D/S of Replace tubing by NO 5/29/2007 60069652 11SW97 Welding 3 Replacement 3/8" tubing leak D/S of Replace tubing by NO 7/13/2007 60070719 11 SW55 Welding 3 Replacement 3/8" tubing leak D/S of Replace tubing by NO 8/9/2007 60070974 12SW97 Welding 3 Replacement 3/8" tubing leak D/S of Replace tubing by NO 8/17/2007 60071025 12SW74 Welding 3 Replacement 3/8" tubing leak at Replace tubing by NO 8/24/2007 60071201 1PL4285 between valves Welding 13SW243 and 13SW405 3 Replacement 3/8" tubing leak at Replace tubing by NO 9/21/2007 60071356 1PL4284 Welding 1,1 3 Replacement 3/8" tubing weld leak U/S Replace tubing by NO 10/25/2007 60072363 of 1SW656 Welding
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