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MONTHYEARML17055A7092017-02-24024 February 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Acceptance of Three Inservice Testing Program Alternative Requests Project stage: Acceptance Review ML17123A2622017-05-16016 May 2017 Inservice Testing Alternative for Pumps Per Code Case OMN-21 (RR-PR-02) Project stage: Other 2017-02-24
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Category:Letter
MONTHYEARNL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in 05000348/LER-2024-002-01, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) 05000348/LER-2024-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 05000364/LER-2024-002, for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. ML24061A1692024-03-22022 March 2024 PM Reassignment Letter Farley March 2024 2024-09-05
[Table view] Category:Safety Evaluation
MONTHYEARML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 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 ML23136B1542023-07-0303 July 2023 Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis ML23164A2072023-06-14014 June 2023 Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Draft Safety Evaluation ML23054A4552023-03-16016 March 2023 Issuance of Amendment Nos. 245 and 242, Regarding LAR to Revise Technical Specification 3.4.10, Pressurizer Safety Valves, to Decrease Low Side Setpoint Tolerance LCO Value ML22308A0592022-11-0808 November 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a Licensee-Controlled Document ML22286A0742022-11-0808 November 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a Licensee-Controlled Document ML22069A0042022-04-27027 April 2022 Issuance of Amendments Revision to TSs to Adopt TSTF-269-A, Rev. 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves ML22032A2432022-03-0707 March 2022 Issuance of Amendment Nos. 241 and 238 to Eliminate the Encapsulation Vessels Around the First Containment Spray and Residual Heat Removal / Low Head Safety Injection Recirculation Suction Isolation Valves ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21344A0032022-01-26026 January 2022 Issuance of Amendments Regarding Revision to Use Beacon Power Distribution Monitoring System ML21316A0552022-01-0505 January 2022 1 & 2, and Vogtle Electric Generating Plant, 1 & 2 - Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0163 ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls ML21217A0912021-09-21021 September 2021 SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21167A3152021-07-30030 July 2021 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position ML21137A2472021-06-30030 June 2021 Issuance of Amendment Nos. 233 and 230, Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21161A2012021-06-22022 June 2021 Associated Independent Spent Fuel Storage Facilities - Reduction in Commitment to the Quality ML20303A1192020-12-11011 December 2020 Issuance of Amendment Nos. 232 and 229 Regarding Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML20224A2852020-10-13013 October 2020 Issuance of Amendment Nos. 231 and 228 to Revise Technical Specifications 3.3.1 and 3.3.7 ML20121A2832020-10-0909 October 2020 Issuance of Amendments 230 and 227 Measurement Uncertainty Recapture Power Uprate ML20196L9292020-10-0606 October 2020 Issuance of Amendment Nos. 229 and 226 Regarding Spent Fuel Pool Criticality Safety Analysis ML20132A2072020-05-0808 May 2020 9 to the Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of the Plant and Chapter 2 (Part 1 of 3); Redacted Version ML20034E8942020-02-11011 February 2020 Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19261A0142019-09-23023 September 2019 Correction to Safety Evaluation for Amendment Nos. 225 and 222 Regarding Implementation of NEI 06-09, Revision 0-A ML19175A2432019-08-23023 August 2019 Issuance of Amendments 225 and 222 Implementation of NEI 06-09, Risk-Informed Technical Specifications Initiative 4B, Risk-Managed Technical Specification (Rmts) Guidelines, Revision 0-A ML19213A1942019-08-0808 August 2019 Relief from Impractical American Society of Mechanical Engineers Code Requirements (FNP-ISI-RR-02) ML19192A1712019-08-0202 August 2019 Relief from Inservice Impractical ASME Code Requirements (FNP-ISI-RR-03) ML19156A2622019-07-30030 July 2019 Issuance of Amendments 224 and 221 Performance-Based Fire Protection Alternative for Thermal Insulation Material ML19071A1382019-07-16016 July 2019 Issuance of Amendments 223 and 220 Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations TSTF-51 and TSTF-471 ML19129A2322019-07-0101 July 2019 Inservice Inspection Alternative, FNP-ISI-ALT-05-04, Regarding Examination Frequency for Tendon Anchorhead Replacement ML19064A7742019-04-26026 April 2019 Issuance of Amendments Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum on Shift Staff Tables ML18334A2282018-12-10010 December 2018 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-03 ML18320A0572018-11-30030 November 2018 Plant, Units 1 and 2 - Proposed Inservice Inspection Alternative GEN-ISI-ALT-2017-03, Code Case N-513-4 for Moderate Pressure ML18271A2072018-11-0707 November 2018 Issuance of Amendments 221 and 218 Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow ML18183A0732018-07-26026 July 2018 Unites 1, 2, 3, and 4; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2(CAC Nos. MG0188, MG0189, MG0191, MG0192, MG0193, MG0194, and MG0195; EPID L-2017-LLA-0293) ML18151A1742018-06-27027 June 2018 Issuance of Amendment Nos. 219 and 216, Adopt Technical Specification Task Force Traveler TSTF-412, Revision 3, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable ML17291A7812018-03-0101 March 2018 Issuance of Amendments to Correct Non-Conservative Technical Specification 3.7.1 (CAC Nos. MF9465 and MF9466; EPID L-2017-LLA-0181) ML17261A0872018-02-28028 February 2018 Issuance of Amendments to Revise Actions of TS 5.5.17, Containment Leakage Rate Testing Program (CAC Nos. MF8844 and MF8845; EPID No. L-2016-LLA-0015) ML18022A1072018-01-25025 January 2018 Inservice Inspection Alternative GEN-ISI-ALT-2017-02, Version 1.0, Regarding the Use of ASME Code Case N-789-1 (CAC Nos. MF9942, MF9943, MF9944, and MF9945; EPID L-2017-LLR-0059) ML17354A9162017-12-28028 December 2017 Inservice Inspection Alternative FNP-ISI-ALT-05-01, Version 1, to Use ASME Code N-854 (CAC Nos. MG0107 and MF0108; EPID L-2017-LLR-0086) ML17271A2652017-12-20020 December 2017 Issuance of Amendments Adopting Alternative Source Term, TSTF-448, and TSTF-312 (CAC Nos. MF8861, MF8862, MF8916, MF8917, MF8918, MF8919; Epids Nos. L-2016-LLA-0017,L-2016-LLA-0018, L-2016-LLA-0019) ML17298A4162017-11-0101 November 2017 Relief Request FNP-ISI-ALT-22, Inservice Inspection Alternative for Code Case N-786-1 ML17269A1662017-11-0101 November 2017 Issuance of Amendments Related to NFPA 805 Supplement (CAC Nos. MG0094 and MG0095; EPID L-2017-LLA-0261) ML17214A5462017-10-0202 October 2017 Issuance of Amendments Regarding the Adoption of TSTF-547, Revision 1, Clarification of Rod Position Requirements ML17205A0202017-09-15015 September 2017 Issuance of Amendments to Revise TS 3.8.9, Distribution Systems - Operating ML17180A4392017-07-18018 July 2017 Inservice Testing Alternative for Pumps Per Code Case OMN-20 (RR-VR-01) 2024-08-29
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 16, 2017 Mr. James J. Hutto Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
P.O. Box 1295 I Bin 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - INSERVICE TESTING ALTERNATIVE FOR PUMPS PER CODE CASE OMN-21 (RR-PR-02)
(CAC NOS. MF9261, MF9262)
Dear Mr. Hutto:
By letter dated February 6, 2017, Southern Nuclear Operating Company Inc. (SNC or the licensee) submitted three relief requests for the Joseph M. Farley Nuclear Plant (FNP), Unit 1 and Unit 2. The three relief requests are:
RR-VR-01, Version 1: Establish 1st interval grace periods per Code Case OMN-20.
RR-PR-02, Version 1: Establish test flow reference ranges per Code Case OMN-21.
RR-PR-03, Version 1: Service Water Pumps and Transfer Pumps Pressure Accuracy.
This letter applies to the relief request RR-PR-02. Relief request RR-PR-03 was approved in U.S. Nuclear Regulation Commission (NRC) letter dated April 12, 2017. Relief request RR-VR-01 continues to be under NRC review.
The licensee is requesting to use the requirements in American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code)
Case OMN-21 as an alternative to the inservice testing (IST) requirements of the 2004 Edition through 2006 Addenda of the ASME OM Code for the FNP IST program during the fifth 10-year interval, which will start on December 1, 2017, and end November 30, 2027.
The licensee submitted the request pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.55a(z)(1 ), on the basis that the alternative provides an acceptable level of quality and safety.
The NRC staff has reviewed the proposed alternative (RR-PR-02, Version 1) and concludes, as set forth in the enclosed safety evaluation, that the alternative provides an acceptable level of quality and safety. The NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ).
All other ASME OM Code requirements for which relief was not specifically requested and approved remain applicable.
If you have any questions, please contact the Project Manager, Shawn Williams, at 301-415-1009 or by e-mail at Shawn.Williams@nrc.gov.
Sincerely, Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364
Enclosure:
Safety Evaluation cc w/enclosure: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION OFFICE OF NUCLEAR REACTOR REGULATION ALTERNATIVE REQUEST RR-PR-02. VERSION 1.0 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
INSERVICE TESTING PROGRAM FIFTH 10-YEAR INTERVAL JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 DOCKET NUMBERS 50-348 AND 50-364
1.0 INTRODUCTION
By letter dated February 6, 2017, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17037D324), Southern Nuclear Operating Company Inc. (SNC or the licensee) submitted three relief requests for the Joseph M. Farley Nuclear Plant (FNP),
Unit 1 and Unit 2. The three relief requests are:
RR-VR-01, Version 1: Establish 1st interval grace periods per Code Case OMN-20.
RR-PR-02, Version 1: Establish test flow reference ranges per Code Case OMN-21.
RR-PR-03, Version 1: Service Water Pumps and Transfer Pumps Pressure Accuracy.
This safety evaluation addresses only RR-PR-02. Relief request RR-PR-03 was approved in U.S. Nuclear Regulation Commission's (NRC) letter dated April 12, 2017 (ADAMS Accession No. ML17093A692). Relief request RR-VR-01 continues to be under NRC review.
In Relief request RR-PR-02, the licensee is requesting to use the requirements in American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) Case OMN-21 as an alternative to the inservice testing (IST) requirements of the 2004 Edition through 2006 Addenda of the ASME OM Code.
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.55a(z)(1 ),
the licensee requested to use the proposed relief request on the basis that the alternative provides an acceptable level of quality and safety.
Enclosure
2.0 REGULATORY EVALUATION
Paragraph 10 CFR 50.55a(f), "lnservice Testing Requirements," requires, in part, that IST of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraphs 10 CFR 50.55a(z)(1) or 10 CFR 50.55a(z)(2).
In proposing alternatives, a licensee must demonstrate that the proposed alternatives provide an acceptable level of quality and safety (10 CFR 50.55a(z)(1)) or compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety (10 CFR 50.55a(z)(2)). In accordance with 10 CFR 50.55a(z)(1 ), SNC stated that alternative RR PR-02 would provide an acceptable level of quality and safety.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the Commission to authorize the alternative requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 Components Affected Relief was requested for the following pumps:
ASME OM Pump Groups ASME Description Pump Type Code (Unit 1) Code Class Category 01 E11 P001A Residual Heat Removal Centrifugal 2 Group A 01 E11P001 B (RHR) 01E13P001A Containment Spray (CS) Centrifugal 2 Group B 01E13P001 B 01E21P002A Charging/High Head Centrifugal 2 Group A Q1E21P002B Safety Injection (HHSI) 01E21P002C Q1E21P005A Boric Acid Transfer Centrifugal 3 Group A 01E21P005B (BAT)
Q1N23P001A Motor Driven Auxiliary Centrifugal 3 Group A 01N23P001B Feedwater (AFW) 01N23P002 Turbine Driven AFW Centrifugal 3 Group B
ASME OM Pump Groups ASME Description Pump Type Code (Unit 1) Code Class Category Q1P16P001A Service Water Vertical Line 3 Group A Q1P16P001B Shaft Q1P16P001C Centrifugal Q1P16P001D Q1P16P001E Q1P17P001A Component Cooling Centrifugal 3 Group A Q1P17P001B Water Q1P17P001C ASME OM Pump Groups ASME Description Pump Type Code (Unit 2) Code Class Category Q2E11P001A Residual Heat Removal Centrifugal 2 Group A Q2E11P001B (RHR)
Q2E13P001A Containment Spray (CS) Centrifugal 2 Group B Q2E13P001B Q2E21P002A Charging/High Head Centrifugal 2 Group A Q2E21P002B Safety Injection (HHSI)
Q2E21P002C Q2E21P005A Boric Acid Transfer Centrifugal 3 Group A Q2E21P005B (BAT)
Q2N23P001A Motor Driven AFW Centrifugal 3 Group A Q2N23P001B Q2N23P002 Turbine Driven AFW Centrifugal 3 Group B Q2P16P001A Service Water Vertical Line 3 Group A Q2P16P001 B Shaft Q2P16P001C Centrifugal Q2P16P001D Q2P16P001E Q2P17P001A Component Cooling Centrifugal 3 Group A Q2P17P001B Water Q2P17P001C
3.2 Applicable ASME OM Code ASME OM Code-2004 Edition with Addenda through OMb-2006.
The licensee requested relief from the following OM Code requirements:
ISTB-5121, Group A Test Procedure, paragraph ISTB-5121 (b) states, in part, that "The resistance of the system shall be varied until the flow rate equals the reference point. ...
Alternatively, the flow rate shall be varied until the differential pressure equals the reference point..."
ISTB-5122, Group B Test Procedure, paragraph ISTB-5122(c) states, in part, that "System resistance may be varied as necessary to achieve the reference point."
ISTB-5123, Comprehensive Test Procedure, paragraph ISTB-5123(b) states, in part, that "The resistance of the system shall be varied until the flow rate equals the reference point.
Alternatively, the flow rate shall be varied until the differential pressure equals the reference point."
ISTB-5221, Group A Test Procedure, paragraph ISTB-5221 (b) states, in part, that "The resistance of the system shall be varied until the flow rate equals the reference point.
Alternatively, the flow rate shall be varied until the differential pressure equals the reference point."
ISTB-5222, Group B Test Procedure, paragraph ISTB-5222(c) states, "System resistance may be varied as necessary to achieve the reference point."
ISTB-5223, Comprehensive Test Procedure, paragraph ISTB-5123(b) states, in part, that "The resistance of the system shall be varied until the flow rate equals the reference point.
Alternatively, the flow rate shall be varied until the differential pressure equals the reference point.
3.3 Duration of the Proposed Alternative Fifth 10-year IST program interval beginning December 1, 2017, and ending November 30, 2027.
3.4 Reason for Request The licensee states, in part, that:
For pump testing, there is difficulty adjusting system throttle valves with sufficient precision to achieve exact flow reference values during subsequent IST tests.
Section ISTB of the ASME OM Code does not allow for variance from a fixed reference value for pump testing. However, NUREG-1482, Revision 2, Section 5.3, acknowledges that certain pump system designs do not allow for the licensee to set the flow at an exact value because of limitations in the instruments and controls for maintaining steady flow.
ASME OM Code Case OMN-21, "Alternative Requirements for Adjusting Hydraulic Parameters to Specified Reference Points," provides guidance for adjusting reference flow, differential pressure (~P) to within a specified tolerance during pump inservice testing. The Code Case states that:
It is the opinion of the Committee that when it is impractical to operate a pump at a specified reference point and adjust the resistance of the system to a specified reference point for either flow rate, differential pressure or discharge pressure, the pump may be operated as close as practical to the specified reference point with the following requirements. The Owner shall adjust the system resistance to as close as practical to the specified reference point where the variance from the reference point does not exceed + 2% or - 1% of the reference point when the reference point is flow rate, or + 1% or -2% of the reference point when the reference point is differential pressure or discharge pressure.
3.5 Proposed Alternative The application states, in part, that:
FNP seeks to perform future inservice pump testing in a manner consistent with the requirements as stated in ASME OM Code Case OMN-21. Specifically, testing of all pumps identified [above] will be performed such that the flow rate is adjusted as close as practical to the reference value and within proceduralized limits of +2% / -1 % of the reference flow rate when the reference point is flow rate and the differential pressure will be adjusted as close as practical to the reference value and within the proceduralized limits of +1 % I -2% of the reference differential pressure when the reference point is differential pressure.
FNP plant operators will continue to strive to achieve the exact test reference values (flow or differential pressure) during testing. Typical test guidance will be to adjust flow or differential pressure to the specific reference value with additional guidance that if the reference value cannot be achieved with reasonable effort, the test will be considered valid if the steady state flow rate is within the proceduralized limits of +2% / -1 % of the reference value or the steady state differential pressure is within the proceduralized limits of +1 % I -2% of the reference value.
3.6 Basis for 10 CFR 50.55a(z)(1)
The licensee stated that as an alternative to the specific ASME IST Requirements, IST for the pumps identified in Table RR-PR-02 will be performed consistent with ASME OM Code Case OMN-21, which ensures adequate indication of pump performance and thus provides an acceptable level of quality and safety per the requirements in 10 CFR 50.55a(z)(1 ).
3.7 NRC Staff Evaluation Pursuant to 10 CFR 50.55a, "Codes and standards," paragraph (z)(1 ), the licensee proposed an alternative to the pump testing reference value requirements of the ASME OM Code on the basis that the proposed alternative would provide an acceptable level of quality and safety. The licensee requested that the alternative be applicable to inservice testing of all IST Program pumps for FNP, Units 1 and 2, as listed above for the duration of the fifth IST interval beginning December 1, 2017, ending November 30, 2027.
An inquiry was submitted to the ASME OM Code to determine what alternatives may be used when it is impractical to operate a pump at a specified reference point for either flow rate, differential pressure, or discharge pressure. ASME Code Case OMN-21 was developed to provide guidance on alternatives. The guidance in Code Case OMN-21 states that when it is impractical to operate a pump at a specified reference point for either flow rate, differential pressure or discharge pressure, the pump may be operated as close as practical to the specified reference point with the following requirements. Code Case OMN-21 specifies that the variance from the reference point shall not exceed +2 percent or -1 percent of the reference point when the reference point is flow rate, or +1 percent or -2 percent of the reference point when the reference point is differential pressure or discharge pressure.
Code Case OMN-21 was approved by the ASME Operation and Maintenance Standards Committee on April 20, 2012, with the NRC representative voting in the affirmative. The licensee proposes to adopt Code Case OMN-21. The applicability of Code Case OM-21 is the ASME OM Code 1995 Edition through the 2011 Addenda. The NRC staff notes that the language from Code Case OMN-21 has subsequently been included in the ASME OM Code, 2012 Edition.
The NRC staff notes that in certain situations, it is not possible to operate a pump at a precise reference point. The NRC staff has reviewed the alternatives proposed in ASME OM Code Case OMN-21 and found that the proposed alternatives are reasonable and appropriate when a pump cannot be operated at a specified reference point. Operation within the tolerance bands specified in ASME OM Code Case OMN-21 provides reasonable assurance that licensees will be able to utilize the data collected to detect degradation of the pumps.
Based on the above, the NRC staff concludes that the license's proposed implementation of the alternatives contained in ASME OM Code Case OMN-21 provides reasonable assurance of safety for the components listed in Section 3.1 of this safety evaluation. Therefore, the NRC staff concludes that the licensee's proposed alternative provides an acceptable level of quality and safety.
4.0 CONCLUSION
As set forth above, the NRC staff finds that the proposed alternative provides an acceptable level of quality and safety for the pumps listed table RR-PR-02. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for alternative request RR-PR-02. Therefore, the NRC staff authorizes alternative request RR-PR-02, Version 1, for FNP Units 1 and 2 for the fifth 10-year IST program interval which is scheduled to begin on December 1, 2017, ending November 30, 2027.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject requests remain applicable.
Principal Contributor: John Billerbeck, NRR Date: May 16, 2017
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - INSERVICE TESTING ALTERNATIVE FOR PUMPS PER CODE CASE OMN-21 (RR-PR-02)
(CAC NOS. MF9261, MF9262) DATED MAY 16, 2017 DISTRIBUTION:
PUBLIC LPL2-1 R/F RidsACRS_MailCTR Resource RidsNrrDorlLpl2-1 Resource RidsNrrKGoldstein Resource RidsRgn2MailCenter Resource RidsNrrPMFarley Resource JBillerbeck, NRR ADAMS Access1on No.: ML17123A262 *B 1 e-ma1*1 OFFICE NRR/DORL/LPL2-1 /PM NRR/DORL/LPL2-1/LA NRR/DE/EPNB/BC* NRR/DORL/LPL2-1/BC NAME SWilliams KGoldstein DAiiey MMarkley DATE 05/10/17 05/08/17 03/31/17 05/16/17 OFFICIAL RECORD COPY