Letter Sequence Other |
---|
|
|
MONTHYEARML0807200682008-02-25025 February 2008 Re-Submittal of Inservice Testing Program Relief Requests P01, V03 and V04 Project stage: Other ML0825502182008-10-10010 October 2008 Safety Evaluation of Relief Requests for the Third 10-Year Interval of the Inservice Testing Program for Salem Nuclear Generating Station, Unit Nos. 1 and 2 Project stage: Approval 2008-10-10
[Table View] |
Similar Documents at Salem |
---|
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
MONTHYEARIR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection LR-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 ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement 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 ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) 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 ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) ML23233A0762023-08-21021 August 2023 Requalification Program Inspection ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 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 IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 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 ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 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-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) 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 ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership 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 ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, 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 ML23044A1052023-03-13013 March 2023 Issuance of Amendment Nos. 345 and 326 Relocate Technical Specifications Requirements for Reactor Head Vents to Technical Requirements Manual ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report IR 05000272/20230112023-03-0707 March 2023 Comprehensive Engineering Team Inspection Report 05000272/2023011 and 05000311/2023011 IR 05000272/20220062023-03-0101 March 2023 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2022006 and 05000311/2022006) 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 ML23034A1532023-02-0909 February 2023 Operator Licensing Examination Approval ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping 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 2024-02-05
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236,, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear L.L. C.FB2 5 2008 1 OCFR50.55a(g)(5)(iii)
LR-N08-0032 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SALEM GENERATING STATION -UNIT 1 and UNIT 2 FACILITY OPERATING LICENSE NOS. DPR 70 and DPR-75 NRC DOCKET NOS. 50-272 and 50-311
Subject:
RE-SUBMITTAL OF INSERVICE TESTING PROGRAM RELIEF REQUESTS P01, V03 AND V04
References:
(1) Letter from PSEG to NRC: "Salem Generating Station Inservice Testing Program, for the Third IST Interval, Salem Nuclear Generating Station, Units 1 and 2, Facility Operating Licenses DPR-70 and DPR-75, Docket Nos. 50-272 and 50-311," dated August 30, 1999 (2) Letter from NRC to PSEG: "Salem Nuclear Generating Station, Unit Nos. 1 and 2, Re: Inservice Testing Program -Third Interval Submittal," dated September 26, 2001 (3) Letter from PSEG to NRC: "Response to Request for Additional Information Regarding Relief Requests SI-RR-04-VO1 and V02 Salem Nuclear Generating Station, Units 1, Facility Operating Licenses DPR-70, Docket Nos. 50-272," dated January 6, 2005.In Reference 1, PSEG Nuclear LLC (PSEG) first submitted Relief Requests P01, V03 and V04 as part of the original Salem Inservice Testing Program (IST) Third Interval submittal to the NRC: P01 was to allow the ability to analyze pump conditions rather than just repair or replace. This ability was originally in the old 1983 edition of the ASME Code, but was inadvertently removed in the 1988 edition.A407 Document Control Desk FEB LR-N08-0032 V-03 was to allow for major component testing, versus individual testing for certain skid-mounted, non-code components.
Solenoid operated globe valves in the air supply lines to the diesel generator starting air motors are skid-mounted and were not provided with position indication to facilitate individual valve exercise and stroke time testing. As alternate testing, the stroke time and exercise testing of these valves is considered satisfactory by satisfactory testing of the major component they support (per NUREG 1482).V-04 is related to the remote position indication for certain containment sump valves. It is impractical to open these containment compartments to verify remote position indication by direct observation every two years. As alternate testing they will be verified once every other refueling concurrent with Environmental Qualification inspections.
The NRC had previously granted the equivalent V04 relief request for the Salem IST Second Interval period.In Reference 2, the NRC stated its understanding that the Salem IST Program Third Interval, and associated relief requests, would be resubmitted by PSEG. The NRC further stated that they would close out the original request (Reference
- 1) and would review the resubmitted Salem IST Program, with its associated relief requests, upon receipt.In Reference 3, the Salem IST Program, Third Interval, was subsequently resubmitted, including Relief Requests P-01, V-03 and V-04, as part of the RAI response submittal.
However, since the relief requests were included as part of the larger program document, they were apparently not reviewed; in subsequent discussions the NRC indicated that relief requests should be made as separate submittals.
Consequently, pursuant to 1OCFR50.55a(g)(5)(iii), this letter re-submits the relief requests associated with the Salem IST Program Third Interval, for NRC approval (Attachment 1 to this letter).If you have any questions or require additional information, please do not hesitate to contact Mr. Jeff Kennan at (856) 339-5429.Sincerely, Robert C. Braun Site Vice President Salem Generating Station Attachments:
1 (IST Relief Requests P01, V03 and V04)
-Document Control Desk 2008 LR-N08-0032 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 Unit 1 and Unit 2 U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector
-Salem Unit 1 and Unit 2 (X24)Mr. P. Mulligan Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625 Attachment I Relief Requests P01, V03 and V04 LR-N08-0032 SALEM GENERATING STATION IST PUMP RELIEF REQUEST P01 COMPONENTS:
ASME Class 2 and 3 Pumps CLASS: ASME Section XI Class 2 and 3 ASME TEST REQUIREMENTS:
OMa -1988, Part 6, Paragraph 6.1 states, in part -If deviations fall within the required action range of Table 3, the pump shall be declared inoperable until the cause of the deviation has been determined and the condition corrected.
BASIS FOR RELIEF: The 1983 ASME Section XI Code, subsection IWP-3230(c) stated that,"Corrective actions shall be either replacement or repair per IWP-31 11, or shall be an analysis to demonstrate that the condition does not impair pump operability and that the pump will fulfill its function.
A new set of reference values shall be established after such analysis." The OMc -1994 Addenda (ISTB 6.2.2) and the OM 1995 Edition (ISTB 6.2.2) both state that,"If the measured test parameter values fall within the required action range of Table 5.2.1-1, Table 5.2.2-1, or Table 5.2.3-1, as applicable, the pump shall be declared inoperable until either the cause of the deviation has been determined and the condition is corrected, or an analysis of the pump is performed and new reference values are established in accordance with ISTB 4.6." The Code applicable for the second interval IST Program and the latest issued Code both provide for analysis of pump test data in lieu of repair or replacement of the pump if the test parameters fall within the required action range. The OMa Code-1988 Edition did not include such provisions.
Communications with members of the OM Committee indicate that this was an oversight and that it was never intended to delete the ability to analyze the test data and determine if the pump is still capable of performing its intended safety function.ALTERNATIVE TESTING: Should pump test parameters fall within the required action range of Table 3 (OMa Code 1988 Edition), then the OM Code 1995 Edition, subsection ISTB 1 Attachment 1 LR-N08-0032 Relief Requests P01, V03 and V04 6.2.2 will be utilized.
Since subsection ISTB 4.6 in the 1995 Code Edition references ISTB 6.2.2, subsection ISTB 4.6 from the OM Code 1995 Edition will also be applied.2 Attachment I Relief Requests P01, V03 and V04 LR-N08-0032 SALEM GENERATING STATION (NON-CODE)
VALVE RELIEF REQUEST V03 SYSTEM: Diesel Starting Air -Salem 1 and 2 COMPONENTS:
11DAI3A, 13B, & 13C 21DA13A, 13B, & 13C 12DA13A, 13B, & 13C 22DA13A, 13B, & 13C 11DA14A, 14B, & 14C 21DA14A, 14B, & 14C 12DA14A, 14B, & 14C 22DA14A, 14B, & 14C FUNCTION: These solenoid operated globe valves are located in the air supply lines to-the diesel generator starting air motors from the starting air receivers and are skid-mounted.
These valves perform an active safety function in the open position.
The valves must be capable of opening when the associated engine receives a start signal to provide a flow path for starting air to the engine.CATEGORY:
B CLASS: NONE TEST REQUIREMENTS:
(1) The stroke time for all power operated valves shall be measured in accordance with the requirements of Part 10-4.2.1.4.
(2) Stroke times for power-operated valves shall be evaluated and corrective action taken in accordance with Part 10-4.2.1.9.
BASIS FOR RELIEF: These valves are maintained in the closed position and are not provided with position indication to facilitate individual valve exercise and stroke time testing. There are four (4) solenoid valves per generator, which are exercised together during monthly diesel generator start testing. On a quarterly basis the diesel generator is started from one starting air bank to demonstrate design capability of the diesel to start using a pair of starter motors. Stroke time and exercise testing of these solenoid valves is considered satisfactory if the diesel achieves Technical Specification voltage and frequency in < 13 seconds during monthly diesel testing when the diesel is started on a single air bank. Individual valve stroke timing is not possible during the diesel start process since this skid-mounted system was not designed to include features for inservice testing.NUREG 1482, Revision 0, Section 3.4 identifies that for skid-mounted 3
Attachment 1 Relief Requests P01, V03 and V04 LR-N08-0032 components testing of the major component is an acceptable means for verifying component subassembly operational readiness.
ALTERNATE TESTING: Quarterly open stroke time and exercise testing shall be considered satisfactory if the diesel achieves Technical Specification voltage and frequency in __ 13 seconds when started from one air bank during monthly diesel testing per Technical Specification 4.8.1.1.2.
4 Attachment I Relief Requests P01, V03 and V04 LR-N08-0032 SALEM GENERATING STATION IST VALVE RELIEF REQUEST V04 SYSTEM: ECCS -Salem 1 and 2 COMPONENTS:
11SJ44, 12SJ44 21SJ44, 22SJ44 FUNCTION: These motor operated valves are located in the supply lines from the containment sump to the respective RHR pump suction. The valves perform an active safety function in the open position.
The valves must be capable of opening to align the containment sump to the ECCS subsystems during the recirculation phase of emergency core cooling.The valves perform a passive safety function in the closed position to properly align ECCS subsystems to the RWST during the injection phase of emergency core cooling, and to prevent the RWST inventory from back flowing to the containment sump.CATEGORY:
B CLASS: 2 TEST REQUIREMENTS:
Position Indication
-Valves with remote position indicators shall be observed at least once every 2 years, in accordance with the requirements of Part 10-4.1.BASIS FOR RELIEF: These valves are located in separate compartments in the containment.
The compartments are accessible from outside the containment through four-foot diameter manways which must be unbolted and manually removed for entry. These manways are sealed by gaskets on the flange surface to which they are bolted. The proper sealing of this surface is necessary to ensure containment integrity.
If the valves are verified for proper remote position indication (RPI) every two years, hatch removal would be required for RPI verification only. In order to minimize the potential for damage to flange surfaces and gaskets, the valves should be verified for RPI accuracy when other scheduled maintenance/inspection activities are performed.
It is impractical to open these compartments to verify remote position indication by direct observation every two years.5 Attachment 1 Relief Requests P01, V03 and V04 LR-N08-0032 ALTERNATE TESTING: Remote position indication will be verified once every other refueling concurrent with Environmental Qualification inspections, or at any other time the manways are removed (ref. Maintenance Procedure SC.MD-EU.ZZ-0006(Q)), but in no case more often than once every two years.This alternate testing was previously approved in NRC Safety Evaluations dated October 9, 1992 (TAC Nos. M74790 and M74791) and April 15, 1994 (TAO Nos. M88144 and M88145).There has been no change in the field to invalidate the above basis for relief from the Second to the Third IST interval.6