Similar Documents at Salem |
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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] Category:Safety Evaluation
MONTHYEARML23192A8212023-08-14014 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 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 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 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership 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 ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping ML22130A7912022-05-24024 May 2022 Issuance of Relief Request No. S1-I4R-210 Fourth Inservice Inspection Interval Limited Examinations ML22061A0302022-04-0404 April 2022 Issuance of Amendment Nos. 343 and 324 Revise Technical Specifications Surveillance Requirements for Auxiliary Feedwater ML22012A4352022-02-14014 February 2022 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Nos. 230, 342, and 323 Delete Definition in 10 CFR 20 and Figures of Site and Surrounding Areas ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21295A2292021-11-15015 November 2021 Issuance of Amendment Nos. 340 and 321 Revise Technical Specifications to Adopt TSTF 569, Revision of Response Time Testing Definitions ML21230A0182021-10-0808 October 2021 Issuance of Amendment No. 339 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report ML21202A0782021-09-0303 September 2021 Issuance of Amendment Nos. 338 and 320 Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21195A0622021-08-0303 August 2021 Issuance of Amendment No. 319 One-Time Request to Revise Technical Specification Action for Rod Position Indicators ML21110A0522021-07-19019 July 2021 Issuance of Amendment Nos. 337 and 318, Revise Technical Specifications to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML21145A1892021-06-10010 June 2021 Authorization and Safety Evaluation for Alternative Request No. SC-I4R-200 ML20338A0382021-02-23023 February 2021 Issuance of Amendment Nos. 336 and 317 Leak-Before-Break for Accumulator, Residual Heat Removal, Safety Injection, and Pressurizer Surge Lines ML20224A2982020-08-20020 August 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20191A2032020-08-0606 August 2020 Issuance of Amendment Nos. 335 & 316-Revise Minimum Required Channels, Mode Applicability, & Actions for Source Range/Intermediate Range Neutron Flux Reactor Trip System Instrumentation ML20104A1862020-04-20020 April 2020 Issuance of Alternative Request SC-I4R-192 for Examination of ASME Code, Section XI, Steam Generator and Pressurizer Nozzle Inside Radius Sections ML20099E2332020-04-20020 April 2020 Issuance of Alternative Request S1-I4R-191 for the Fourth 10-Year Inservice Inspection Interval ML20091K7302020-04-13013 April 2020 Issuance of Relief Request SC-I4R-190 for the Fourth 10-Year Inservice Inspection Interval ML20034E6172020-02-27027 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 222, 333, and 314 Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer ML19352F2312020-02-18018 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2; Issuance of Amendment Nos. 221, 332, and 313 Revise Emergency Plan Staffing Requirements ML19330F1562020-01-14014 January 2020 Issuance of Amendment Nos. 331 and 312 Revise Technical Specifications to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19275D6942019-11-18018 November 2019 Issuance of Amendment Nos. 330 and 311 Revise Technical Specifications to Adopt TSFT-547, Clarification of Rod Position Requirements ML19105B1712019-05-31031 May 2019 Issuance of Amendment Nos. 329 and 310 Revise Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation, Main Steam Isolation Valves, and Add New TS ML19077A3362019-04-11011 April 2019 Issuance of Amendment Nos. 328 and 309 Revise Technical Specifications to Extend Refueling Water Storage Tank Allowed Outage Time ML19044A6272019-03-0606 March 2019 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 214, 327, and 308 Revise Technical Specifications to Adopt TSTF-529 ML19050A3702019-03-0606 March 2019 Alternative to Reactor Vessel Nozzle Welds Examinations Inspection Interval (EPID-L-2018-LLR-0110) ML19009A4772019-01-25025 January 2019 Issuance of Amendment Nos. 326 and 307 Revise Technical Specifications to Increase Vital Instrument Bus Inverter Allowed Outage Time ML18318A2662018-12-19019 December 2018 Issuance of Amendment Nos. 325 and 306 Revise TS Reactor Trip System Instrumentation and Engineered Safety Features Actuation System Instrumentation Test Times and Completion Times ML18142B1262018-05-29029 May 2018 Use of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Inservice Inspection Activities ML18040A7782018-04-18018 April 2018 Issuance of Amendment Nos. 323 and 304 Relocation of Reactor Coolant System Pressure Isolation Valve Tables ML18085B1982018-04-18018 April 2018 Issuance of Amendment Nos. 324 and 305 Revise Technical Specification Actions for Rod Position Indicators ML17355A5702018-02-16016 February 2018 Issuance of Amendment Nos. 322, 303, & 210, to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 (CAC Nos. MF9268/MF9269/MF9270; EPID L-2017-LLA-0173) ML17349A1082018-01-18018 January 2018 Issuance of Amendments Containment Fan Coil Unit Allowed Outage Time Extension (CAC Nos. MF9364 and MF9365; EPID L-2017-LLA-0212) ML17227A0162017-11-14014 November 2017 Issuance of Amendments Accident Monitoring Instrumentation ML17304A9432017-11-0101 November 2017 Use of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Inservice Inspection Activities ML17219A1862017-08-17017 August 2017 Safety Evaluation of Relief Request SC-I4R-171 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17172A5872017-07-17017 July 2017 Safety Evaluation of Relief Request S1-I4R-160 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17165A2142017-06-28028 June 2017 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule App. to Section 5.5 Testing ML17132A0052017-05-19019 May 2017 Alternative Request to Adopt American Society of Mechanical Engineers Code Case OMN-20 (CAC Nos. MF8313 and MF8314) ML17093A8702017-05-16016 May 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Revised PSEG Nulcear LLC Cyber Security Plan Milestone 8 Implementation Schedule ML17012A2922017-02-0606 February 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Issuance of Amendments ML16351A1822017-01-19019 January 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16229A5192016-09-29029 September 2016 Issuance of Amendments Correct Non-Conservative Technical Specifications and Other Discrepancies ML16137A5792016-06-29029 June 2016 Issuance of Amendments Extension of Implementation Period for Salem, Unit No. 1, License Amendment No. 311, and Salem, Unit No. 2 License Amendment No. 292 2023-08-14
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 11,2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038
SUBJECT:
SAFETY EVALUATION OF RELIEF REQUEST REGARDING INSERVICE PUMP TESTING - SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 (TAC NOS. ME7938 AND ME7939)
Dear Mr. Joyce:
By letter dated February 7, 2012 (Agencywide Documents and Access Management System Accession No. ML 112039A070), PSEG Nuclear LLC (PSEG) submitted relief request P-03 for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2. The proposed relief would allow PSEG to use alternative pump testing requirements in lieu of the Comprehensive Pump Test required by American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The licensee proposes to use ASME Code Case OMN-18 with additional limitations on the upper end differential pressure test value and the pressure instrumentation accuracy.
The NRC staff has completed its review of this relief request. The details of the NRC staff's review are included in the enclosed safety evaluation (SE). The NRC staff concludes that the licensee's proposed alternative provides an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a}(3)(i), the NRC staff authorizes the licensee-proposed alternative to use Code Case OMN-18 of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code), with modifications, for certain pumps in the inservice testing (1ST) program at Salem. The alternative is authorized for the remainder of the Salem Unit Nos. 1 and 2 fourth 10-year 1ST program interval.
Use of ASME Code Case OMN-18 is authorized until such time as ASME Code Case OMN-18 is published in a future version of Regulatory Guide (RG) 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code," and incorporated by reference in 10 CFR 50.55a(b). At that time, if the licensee intends to continue implementing this ASME Code Case, it must follow all provisions of ASME Code Case OMN-18 with conditions as specified in RG 1.192 and limitations as specified in 10 CFR 50.55a(b}(4), (b}(5) , and (b}(6), if any, in addition to the modifications described in the attached SE.
All other requirements of the ASME Code,Section XI for which relief has not been specifically requested remain applicable, including a third party review by the Authorized Nuclear Inservice Inspector.
T. Joyce - 2 If you have any questions concerning this matter, please contact the Salem Project Manager, Mr. John Hughey, at (301) 415-3204.
Sincerely, Meena Khanna, Chief Plant Licensing Branch /-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
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- 1< SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RELIEF REQUEST ALTERNATIVE P-03 PSEG NUCLEAR LLC SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
By letter dated February 7,2012 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML 112039A070), PSEG Nuclear LLC (PSEG), the licensee, submitted alternative request P-03 to the Nuclear Regulatory Commission (NRC). The licensee proposed an alternative testing method and acceptance criteria described in the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) Code Case OMN-18, for the pumps listed in Table 3.1 of this safety evaluation (SE).
The proposed alternative would be used in lieu of the current pump testing methods and acceptance criteria described in the AS ME OM Code for the Salem Generating Station (Salem)
Unit Nos. 1 and 2. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(a)(3)(i), the licensee requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety. Relief Request P-03 is applicable to the fourth 10-year inservice testing (1ST) program intervals for Salem Unit Nos. 1 &
2.
2.0 REGULATORY EVALUATION
Section 50.55a of Title 10 of the Code of Federal Regulations (10 CFR), requires that 1ST of certain ASME Code Class 1, 2, and 3 components, including pumps, be performed at 120-month (10-year) 1ST program intervals in accordance with the specified ASME Boiler and Pressure Vessel Code (Code) and applicable addenda incorporated by reference in the regulations, except where alternatives have been authorized or relief has been requested by the licensee and granted by the Nuclear Regulatory Commission (NRC or the Commission) pursuant to paragraphs (a)(3)(i), (a)(3)(ii), or (f)(6)(i) of 10 CFR 50.55a. In accordance with 10 CFR 50.55a(f)(4)(ii), licensees are required to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in the regulations 12 months prior to the start of each 120-month 1ST program interval. In accordance with 10 CFR 50.55a(f)(4)(iv), 1ST of certain components, including pumps, may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to NRC approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met.
Enclosure
-2 In proposing alternatives or requesting relief, the licensee must demonstrate that: (1) the proposed alternatives provide an acceptable level of quality and safety; (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety; or (3) conformance is impractical for the facility. Section 50.55a authorizes the Commission to approve alternatives and to grant relief from ASME Code requirements upon making necessary findings. NRC guidance contained in Generic Letter (GL) 89-04, "Guidance on Developing Acceptable Inservice Testing Programs," provides alternatives to ASME Code requirements which are acceptable. Further guidance is given in GL 89-04, Supplement 1, and NUREG-1482, "Guidance for Inservice Testing at Nuclear Power Plants."
Relief Request P-03 was submitted for the fourth 10-year 1ST interval at Salem Units 1 and 2.
The fourth 10-year 1ST interval began on August 31, 2009,1 and the applicable ASME OM Code edition and addenda for Salem Units 1 and 2 is the 2001 Edition through the 2003 Addenda.
The NRC's findings with respect to authorizing the alternative, P-03, are given below:
3.0 TECHNICAL EVALUATION
3.1 Licensee's Alternative Request P-03 IST8-3300, "Reference Values," specifies that, reference values be established within +/-20 percent of pump design flow rate for the comprehensive test, and that reference values be established within +/-20 percent of pump design flow for the Group A and Group 8 tests, if practicable.
Table IST8-3400-1, "Inservice Test Frequency," specifies that a Group A Test be performed quarterly for Group A pumps and a Comprehensive Test be performed biennially for Group A and Group 8 pumps.
Table IST8-3500-1, "Required Instrument Accuracy," specifies the instrument accuracies for Group A and Comprehensive Tests.
Table 18T8-5100-1, "Centrifugal Pump Test Acceptance Criteria," provides, in part, the acceptance criteria for Group A and Comprehensive Tests for centrifugal pumps.
IST8-5123, "Comprehensive Test Procedure," provides the specific requirements for the comprehensive test for centrifugal pumps (except vertical line shaft centrifugal pumps).
ASME OM Code Case OMN-18, "Alternate Testing Requirements for Pumps Tested Quarterly Within +/-20% of Design FlOW," provides an alternative set of requirements regarding testing and acceptance criteria for centrifugal pumps.
The applicable ASME OM Code edition and addenda for Salem Unit Nos. 1 and 2 is the 2001 Edition through the 2003 Addenda.
1 Per licensee letter dated December 31,2008; ADAMS Accession No. ML090130525.
-3 Alternative testing was requested for the following centrifugal pumps:
Table 3.1 Pump Description I Class Category Unit S 1CVC-1 CVE4 11 Boric Acid Transfer Pumj:! I 3 Group A 1 S 1CVC-1 CVE5 12 Boric Acid Transfer Pump 3 Group A 1 S2CVC-2CVE4 . 21 Boric Acid Transfer Pum~ 3 Group A 2 S2CVC-2CVE5 22 Boric Acid Transfer Pump 3 Group A 2 S1CC-1CCE2 11 COI1!~onent Cooling PumQ_ 3 Grou~A 1 S1CC-1CCE4 12 Component Cooling Pump 3 Group A 1 S1CC-1CCE3 13 Component Cooling Pump 3 Group A 1
. S2CC-2CCE2 21 Component Cooling Pump 3 I GroupA 2 S2CC-2CCE4 22 Component Coolinfl Pump 3 Group A 2 S2CC-2CCE3 23 Component Cooling Pump 3 Group A 2 S1CH-1CHE5 11 Chilled Water Pump. 3 Group A 1 i S1CH-1CHE6 12 Chilled Water Pum2 3 Group A 1 S2CH-2CHE6 . 21 Chilled Water Pump 3 Group A 2 S2CH-2CHE7 22 Chilled Water Pump 3 i Group A 2 S1SF-1SFE5 11 Spent Fuel Cooling Pump 3 Group A 1 S1SF-1SFE6 12 Spent Fuel Cooling Pump 3 Group A 1 S2SF-2SFE5 21 Spent Fuel Cooling Pump 3 Group A 2 S2SF-2SFE6 22 Spent Fuel Cooling Pum~ 3 Group A 2 Reason for Request: (as stated by licensee)
Pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (a)(3), relief is requested from the requirements of ASME OM Code ISTB-5123, Table ISTB-3400-1 and Table ISTB-5100-1.
The basis for the relief request is that the proposed alternative would provide an acceptable level of quality and safety.
The ASME OM Code Committee has approved Code Case OMN-18, "Alternative Testing Requirements for Pumps Tested Quarterly within +/- 20% of Design Flow," which allows owners to perform a Group A test in lieu of the Comprehensive Pump Test (CPT) if the Group A test is conducted at +/- 20% of the design flow rate and uses pressure instruments that meet the CPT accuracy requirements (+/-1/2%). This Code Case was not reviewed for approval in Regulatory Guide 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code",
June 2003.
The basis for this change is that a quarterly Group A pump test, performed at the CPT flow rate provides more consistent data for trending than a Group A test in conjunction with a biennial CPT. The increased requirements imposed by the proposed alternative on the parameters to be monitored during every quarterly pump test and the more accurate instruments that must consistently be used during quarterly testing of pumps classified as Group A, allow PSEG to perform better trending of pump performance data due to the more consistent requirements for each of the quarterly tests.
Due to the increased requirements on the parameters imposed by the proposed alternative during all quarterly tests there is no added value in performing the biennial Comprehensive Test.
Proposed Alternative and Basis for Use: (as stated by licensee)
PSEG proposes that in lieu of the CPT requirements of Table ISTB-3400-1, Group A tests will be performed quarterly within +/- 20 percent of the pump design flow rate, with pressure measuring instrumentation meeting the (+1-1/2%) instrument accuracy requirements of Table ISTB-3500-1 specified for the biennial Comprehensive Test. In addition, PSEG has elected to restrict the upper limit for differential pressure to 6%, which is more conservative than the 10%
upper limit established in Table ISTB-5100-1 for Group A tests as this limit provides needed margin while maintaining an acceptable level of quality and safety, and is consistent with the limit authorized by NRC in similar relief requests. This proposed change to the acceptance range is more restrictive than specified in the current Code Case (OMN-18).
Vibration testing will continue to be performed under the proposed modified Group A test and the acceptance criteria for vibration will be the same as required for Group A tests as shown in Table ISTB-5100-1.
Using the provisions of this relief request as an alternative to those specified in ISTB-5123 will provide adequate indication of pump performance, permit consistent detection of component degradation, and continue to provide an acceptable level of quality and safety.
Therefore, pursuant to 10 CFR 50.55a(a){3){i), PSEG requests relief from the specific ISTB requirements identified in this request.
3.2 NRC Staff Evaluation The licensee is proposing to perform a quarterly 1ST for all pumps listed in Table 3.1 in accordance with a modified Group A test procedure, in lieu of quarterly Group A tests and a CPT every two years.
The ASME OM Code requires that for Group A pumps, a Group A test be performed every quarter, and a CPT be performed biennially. The Group A test is performed within +/-20% of the pump design flow rate and the pressure instrument accuracy is +/-2%, and the upper limit for the "Acceptable Range" and "Required Action Range" for flow rate and differential pressure is 110%
of the reference values. The CPT is performed within +/-20% of the pump design flow rate, the pressure instrument accuracy is +/-1/2%, and the upper limit of the "Acceptable Range" and "Required Action Range" for flow rate and differential pressure is 103% of the reference values.
Vibration monitoring is performed during both the Group A tests and the CPTs.
The licensee proposes that for the pumps listed in Table 3.1, a modified Group A quarterly test will be performed using ASME OM Code Case OMN-18, with modified "Acceptable" and "Required Action" ranges, and the biennial comprehensive test will not be performed. The modified Group A quarterly test would be performed within +/-20% of the pump design flow rate,
- 5 using more accurate pressure instrumentation that is required for a comprehensive test (+/-1/2%
instead of +/-2%). The licensee will use a more limiting upper bound differential pressure (LlP) value of 106% for the "Acceptable Range" in lieu of 110% that is normally required by the ASME OM Code for Group A tests. However, the upper bound 106% is greater than the upper bound value of 103% for the biennial CPT. Using more accurate pressure gauges and a more limiting "Acceptable Range" during the modified quarterly Group A test compensates for the elimination of the CPT with its more limiting "Acceptable Range" upper bound value of 103%.
OMN-18 was published in the 2009 Edition of the ASME OM Code. This edition of the ASME OM Code has not been incorporated by reference into 10 CFR 50.55a, and OMN-18 has not been incorporated into Regulatory Guide (RG) 1.192. However, the NRC staff has reviewed OMN-18, and currently has no concerns with its usage, providing that the upper end values of the Group A test "Acceptable Ranges" for flow (Q) and differential pressure (LlP) are 106%Qr and 106%LlP r ,respectively, and the high values of the "Required Action Ranges" for flow and differential pressure are greater than 106%Q r and 106%LlP r ,respectively. The NRC staff considers the proposed alternative acceptable because all of the tests will be performed with pressure gauges with +/-1/2% accuracy. The elimination of the CPT, with its more limiting "Acceptable Range" upper bound of 103%LlP r, is compensated for by using more accurate pressure gauges on every quarterly test. Regular testing with more accurate instrumentation and tighter acceptance criteria will provide for better trending of pump performance. Therefore, the NRC finds that the proposed alternative provides an acceptable level of quality and safety for testing and acceptance criteria for the pumps listed in Table 3.1
4.0 CONCLUSION
As set forth above, the NRC staff finds that the proposed alternative described in alternative request P-03 provides an acceptable level of quality and safety for the pumps listed in Table 3.1. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(i), and is in compliance with the ASME OM Code requirements. All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject request remain applicable.
Use of ASME Code Case OMN-18 is authorized until such time as ASME Code Case OMN-18 is published in a future version of Regulatory Guide (RG) 1.192 and incorporated by reference in 10 CFR 50.55a(b). At that time, if the licensee intends to continue implementing this ASME Code Case, it must follow all provisions of ASME Code Case OMN-18 with conditions as specified in RG 1.192 and limitations as specified in 10 CFR 50.55a(b)(4), (b)(5), and (b)(6), if any, in addition to the modifications described in the attached SE.
Therefore, the NRC staff authorizes the alternative described in request P-03 for the remainder of Salem Generating Station Unit Nos. 1 and 2 fourth 10-year 1ST program interval, which began on August 31,2009.
Principle Contributor: Michael Farnan, NRR Date: July 11, 2012
T. Joyce -2 If you have any questions concerning this matter, please contact the Salem Project Manager, Mr. John Hughey, at (301) 415-3204.
Sincerely,
/ra/
Meena Khanna, Chief Plant Licensing Branch 1-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC SKennedy, EDO Region I LPL 1-2 R/F RidsAcrsAcnw_MaiICTR Resource RidsNrrDorlLpl1-2 Resource RidsRgn 1MailCenter Resource RidsNrrLAABaxter Resource RidsNrrDeEptb Resource RidsNrrPMSalem Resource MFarnan, NRRIDE/EPTB RidsOgcRP Resource ADAMS Accession No.: ML12185A162 *SE dated 4/11/2012 OFFICE LPL 1-2/PM LPL1-2/LA EPTB/BC* LPL 1-2/BC ABaxter NAIVIE JHughey MKhanaa
/1 DATE 7/06/2012 (KGoldstein fort AMcMurtray 7/05/2012 4/11/2012 7/11/2012 I
OFFICIAL RECORD COpy