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Category:Letter
MONTHYEARML24295A1202024-10-21021 October 2024 Relief Request ANO2-RR-24-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 71 ML24185A2602024-10-0404 October 2024 Issuance of Amendment No. 335 to Revise Typographical Errors in Technical Specifications IR 05000368/20253012024-09-0909 September 2024 Notification of NRC Initial Operator Licensing Examination 05000368/2025301 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000313/20240112024-09-0505 September 2024 Comprehensive Engineering Team Inspection Report 05000313/2024011 and 05000368/2024011 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000313/20240052024-08-21021 August 2024 Updated Inspection Plan for Arkansas Nuclear One – Units 1 and 2 (Report 05000313/2024005, 05000368/2024005) ML24198A0722024-08-21021 August 2024 Correction to Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 IR 05000313/20240022024-08-0606 August 2024 Integrated Inspection Report 05000313/2024002 and 05000368/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification 05000313/LER-2024-001, Source Range Nuclear Instrument Failure Resulting in Condition Prohibited by Technical Specifications2024-07-0101 July 2024 Source Range Nuclear Instrument Failure Resulting in Condition Prohibited by Technical Specifications ML24101A1792024-06-25025 June 2024 Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24143A0632024-05-22022 May 2024 Notification of Inspection (NRC Inspection Report 05000368/2024003) and Request for Information IR 05000313/20240012024-05-0808 May 2024 Integrated Inspection Report 05000313/2024001 and 05000368/2024001 ML24128A2472024-05-0808 May 2024 Project Manager Assignment ML24017A2982024-04-18018 April 2024 Summary of Regulatory Audit Regarding the License Amendment Request to Revise Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML24107A0282024-04-17017 April 2024 Notification of Comprehensive Engineering Team Inspection (05000313/2024011 and 05000368/2024011) and Request for Information ML24086A5412024-04-10010 April 2024 Authorization of Request for Alternative ANO1-ISI-037 Regarding Extension of Reactor Vessel Inservice Inspection Interval IR 05000313/20244022024-04-0808 April 2024 Security Baseline Inspection Report 05000313/2024402 and 05000368/2024402 (Full Report) IR 05000313/20244042024-04-0808 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000313/2024404 and 05000368/2024404) ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24031A6442024-03-14014 March 2024 Issuance of Amendment No. 282 to Modify Technical Specification 3.3.1, Reactor Pressure System (RPS) Instrumentation, Turbine Trip Function on Low Control Oil Pressure ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24102A1342024-03-12012 March 2024 AN1-2024-03 Post Exam Submittal IR 05000313/20230062024-02-28028 February 2024 Annual Assessment Letter for Arkansas Nuclear One- Units 1 and 2 Report 05000313/2023006 and 05000368/2023006 IR 05000313/20230042024-02-0808 February 2024 Integrated Inspection Report 05000313/2023004 and 05000368/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023002 ML24012A0502024-02-0202 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0054 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24017A1582024-01-17017 January 2024 Submittal of Emergency Plan Revision 50 IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment IR 05000313/20234052023-12-12012 December 2023 – Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405 ML23341A0832023-12-11011 December 2023 – Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter ML23305A0922023-12-0707 December 2023 – Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23325A1412023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000313/20230032023-11-21021 November 2023 Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001 ML23324A0172023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report ML23313A0962023-11-13013 November 2023 Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001 ML23243B0452023-11-13013 November 2023 Request for Withholding Information from Public Disclosure ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV 2024-09-09
[Table view] Category:Safety Evaluation
MONTHYEARML24185A2602024-10-0404 October 2024 Issuance of Amendment No. 335 to Revise Typographical Errors in Technical Specifications ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 ML24101A1792024-06-25025 June 2024 Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24086A5412024-04-10010 April 2024 Authorization of Request for Alternative ANO1-ISI-037 Regarding Extension of Reactor Vessel Inservice Inspection Interval ML24031A6442024-03-14014 March 2024 Issuance of Amendment No. 282 to Modify Technical Specification 3.3.1, Reactor Pressure System (RPS) Instrumentation, Turbine Trip Function on Low Control Oil Pressure ML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23142A1062023-05-24024 May 2023 Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22342B1602023-01-10010 January 2023 Requests for Relief ANO2-ISI-023, -024, -025, -026, -027, and -028 to Permit Reduction of Inspection Area Due to Interference (EPIDs L-2022-LLR-0022,-0023, -0024, -0025, -0026, and -0027) ML22263A1912022-12-0909 December 2022 Issuance of Amendment No. 278 Revision to Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations (EPID L-2021-LLA-0181) - Non-Proprietary ML22236A5452022-08-26026 August 2022 Correction to Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22138A4312022-06-23023 June 2022 Issuance of Amendment No. 277 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22039A2822022-03-15015 March 2022 Issuance of Amendment Nos. 274 and 328 One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21225A0552021-12-17017 December 2021 Issuance of Amendment No. 327 Addition of Technical Specification Limiting Condition for Operation 3.0.6 and Adoption of Safety Function Determination Program ML21341B2262021-12-13013 December 2021 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21208A4492021-09-20020 September 2021 Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels ML21132A2792021-05-19019 May 2021 Request for Approval of Change to the Entergy Quality Assurance Program Manual ML21088A4332021-04-14014 April 2021 Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML21027A4282021-03-23023 March 2021 Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent ML21040A5132021-03-10010 March 2021 Issuance of Amendment No. 271 Revision to Loss of Voltage Relay Allowable Values ML20351A1532021-02-0808 February 2021 Issuance of Amendment No. 323 Technical Specification Deletions, Additions, and Relocations ML20288A8242020-11-16016 November 2020 Regulatory Audit Summary Concerning License Amendment Request to Replace the Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent NUREG-1432, Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-14322020-10-30030 October 2020 Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432 ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20160A1472020-06-30030 June 2020 Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML20135H1412020-06-30030 June 2020 Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis ML20121A1932020-05-0606 May 2020 Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves ML20107J3172020-04-23023 April 2020 Relief Request ANO1-ISI-033 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML20087L8032020-04-0808 April 2020 Issuance of Amendment No. 320 to Revise Control Element Assembly Drop Times ML20083J9682020-03-26026 March 2020 Approval of Request for Alternative ANO 2-PT-002 End-of-Internal System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping ML19231A2972020-01-29029 January 2020 Issuance of Amendment No. 318 Addition of Technical Specification Actions to Address Inoperability of the Containment Building Sump ML19220A9382019-09-27027 September 2019 Issuance of Amendment No. 266 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19184A5542019-07-15015 July 2019 Request for Relief ANO1-ISI-032 from the ASME Code Section XI Visual Examination Requirements for the Fourth 10-Year Inservice Inspection Interval ML19156A4002019-06-11011 June 2019 Request for Alternative ANO2-ISI-021 to Permit Continued Application of the 2007 Edition Through the 2008 Addenda of ASME Code ML19098A9552019-05-22022 May 2019 Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3 ML19063B9482019-04-23023 April 2019 Issuance of Amendment No. 315 Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3 ML18337A2472019-01-17017 January 2019 Issuance of Amendment Nos. 263 and 314 Revision to Emergency Action Level Scheme ML18346A3142019-01-0707 January 2019 Relief Nos. ANO1-ISI-027, -028, -029, -030, and -031 from ASME Code, Section XI, Examination Requirements for Fourth 10-Year Inservice Inspection Interval (EPID L-2018-LLR-0063, -0064, -0065, -0066, -0067) ML18317A3822018-12-19019 December 2018 Issuance of Amendment No. 313, Revise Technical Specification 3.3.3.6, Post-Accident Instrumentation ML18298A0122018-11-27027 November 2018 Issuance of Amendment No. 311 Updating the Reactor Coolant System Pressure Temperature Limits ML18260A3392018-10-24024 October 2018 Issuance of Amendment No. 261 Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves 2024-08-13
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 16, 2016 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 2 - RELIEF REQUEST NOS. AN02-ISl-018 AND AN02-ISl-019, RELIEF FROM AMERICAN SOCIETY OF MECHANICAL ENGINEERS SECTION XI VOLUMETRIC EXAMINATION REQUIREMENTS (CAC NOS. MF7271 AND MF7272)
Dear Sir or Madam:
By letter dated January 14, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16015A276), as supplemented by letter dated May 24, 2016 (ADAMS Accession No. ML16147A091), Entergy Operations, Inc. (Entergy, the licensee),
submitted to the Nuclear Regulatory Commission (NRC) requests for relief from certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code), for Section XI volumetric examination requirements at Arkansas Nuclear One (ANO),
Unit 2.
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(6)(i), the licensee requested relief and to use alternative requirements (if necessary), for inservice inspection (ISi) items on the basis that the code requirement is impractical. Specifically, in Relief Request Nos. AN02-ISl-018 and AN02-ISl-019, Entergy requests relief from certain ASME Code Section XI volumetric examination requirements for several pressurizer nozzle welds and shutdown cooling heat exchanger welds. The NRC notes that in the supplement dated May 24, 2016, Entergy stated that it has decided to pursue a complete replacement of the shutdown cooling heat exchangers, the subject components of Relief Request No. AN02-ISl-019, and is therefore withdrawing Relief Request No. AN02-ISl-019 from further review by the NRC. By way of this letter, the NRC acknowledges the withdrawal of Relief Request No. AN02-ISl-019.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that Entergy has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(6)(i). Therefore, the staff grants Relief Request No. AN02-ISl-018 for the ANO, Unit 2, fourth 10-year ISi interval.
If you have any questions, please contact Stephen Koenick at (301) 415-6631 or by e-mail at Stephen.Koenick@nrc.gov.
Sincerely,
/f/-
-~haun M. Anderson, Acting Chief Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NOS. AN02-ISl-018 AND AN02-ISl-019 REGARDING THE PRESSURIZER AND SHUTDOWN COOLING HEAT EXCHANGERS FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL ENTERGY OPERATIONS, INC ARKANSAS NUCLEAR ONE. UNIT 2 DOCKET NO. 50-368
1.0 INTRODUCTION
By letter dated January 14, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16015A276), as supplemented by letter dated May 24, 2016 (ADAMS Accession No. ML16147A091), Entergy Operations, Inc. (Entergy, the licensee),
requested relief from certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code), for Section XI volumetric examination requirements at Arkansas Nuclear One (ANO), Unit 2.
Pursuant to Title 10 of the Code of Federal Regulations (1 O CFR) 50.55a(g)(6)(i), the licensee requested relief and to use alternative requirements (if necessary), for inservice inspection (ISi) items on the basis that the code requirement is impractical. Specifically, in Relief Request Nos. AN02-ISl-018 and AN02-ISl-019, Entergy requests relief from certain ASME Code Section XI volumetric examination requirements for several pressurizer nozzle welds and shutdown cooling heat exchanger welds, respectively.
The NRC notes that in the supplement dated May 24, 2016, Entergy stated that it has decided to pursue a complete replacement of the shutdown cooling heat exchangers, the subject components of Relief Request No. AN02-ISl-019, and is therefore withdrawing Relief Request No. AN02-ISl-019 from further review by the NRC. Thus, the NRC determined that evaluation of Relief Request No. AN02-ISl-019 is not required, and will not be discussed further in the safety evaluation.
2.0 REGULATORY EVALUATION
The ISi of ASME Code Class 1, 2, and 3 components is performed in accordance with Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," of the ASME Code and applicable edition and addenda, as required by 10 CFR 50.55a(g). When conformance to these requirements are determined to be impractical, relief may be granted by Enclosure
not endanger life or property or the common defense and security, and are otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(a)(1 )(ii), 12 months prior to the start of the 120-month interval, subject to the limitations and modifications in 10 CFR 50.55a(b)(2). The Code of record for ANO, Unit 2, for the fourth 10-year ISi interval is the 2003 Addenda to the 2001 Edition of the ASME Code,Section XI.
Section 50.55a(g)(5)(iii) of 10 CFR states, in part:
Determinations of impracticality in accordance with this section must be based on the demonstrated limitations experienced when attempting to comply with the
[ASME] Code requirements during the inservice inspection interval for which the request is being submitted. Requests for relief made in accordance with this section must be submitted to the NRC no later than 12 months after the expiration of the initial or subsequent 120-month inspection interval for which relief is sought.
The licensee submitted Relief Request No. AN02-ISl-018 for ANO, Unit 2 on January 14, 2016, for the fourth 10-year ISi interval, first period, which began on March 26, 2010, and ended on March 25, 2013.
The specific examination requirement for the subject welds is volumetric examination of nozzle-to-vessel welds as defined by Figures IWB-2500-7(a) through IWB-2500-7(d), "Nozzle in Shell or Head" of the ASME Code,Section XI, as specified in Table IWB-2500-1, "Examination Categories" of the ASME Code,Section XI, Examination Category 8-D, Item No. 83.110. When 100 percent of the required volume cannot be examined due to interferences, obstructions, or geometrical configuration, ASME Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds," allows reduction of the examination volume to 90 percent of the required volume. ASME Code Case N-460 has been approved for use by the NRC in Regulatory Guide 1.147, Revision 17, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1" (ADAMS Accession No. ML13339A689).
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 grant relief requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 The Licensee's Relief Requests The proposed relief request relates to ASME Code,Section XI, volumetric evaluation requirements for ANO Unit 2. The relief request is for the pressurizer, specifically the Pressurizer Spray Nozzle-to-Head Weld (05-010) and Pressurizer Safety Valve Nozzle-to-Head Welds (05-011,05-012, and 05-013) for the fourth 10-year ISi interval, first period that started on March 26 201 O and ended on March 25, 2013 for ANO Unit 2.
For the subject welds, the licensee achieved less than 90 percent coverage of the required examination volume, due to the nozzle-to-head configuration of the components. This restriction makes the ASME Code required examination coverage impractical. Plant modifications or replacement of components to allow for complete coverage would be needed to meet the ASME Code requirements. The licensee is not proposing alternative testing, rather, they have examined these welds to the extent practical and will continue to perform pressure testing on the subject components as required by the ASME Code.
3.2 NRC Staff Evaluation The information provided by the licensee in support of Relief Request No. AN02-ISl-018 has been evaluated and the bases for disposition are documented below. By electronic correspondence dated April 26, 2016 (ADAMS Accession No. ML16118A043), the NRC staff issued a request for additional information (RAI) to support the evaluation of Relief Request No. AN02-ISl-018.
The examination coverages achieved for the Pressurizer Nozzle Welds05-010, 05-011,05-012, and 05-013 are less than 90 percent of the required volume and are limited due to the nozzle-to-head configuration of the components. As such, obtaining the ASME Code required examination volume would require significant modification of the pressurizer vessel and nozzles, which imposes a burden upon the licensee.
The licensee stated that the examinations of the Pressurizer Nozzle Welds05-010, 05-011,05-012, and 05-013 were performed with manual ultrasonic testing (UT) examination. In its response to the NRC staff's RAI 2 by letter dated May 24, 2016, the licensee stated that the UT examinations in Relief Request No. AN02-ISl-018 comply with Article 4 to Section V of the ASME Code as specified in Appendix I to Section XI of the ASME Code. The licensee also listed the applicable supplements from Appendix I to Section XI of the ASME Code. The NRC staff accepts the licensee's response and thus, RAI 2 is resolved with respect to Relief Request No. AN02-ISl-018.
Pressurizer Nozzle Welds05-010, 05-011,05-012, and 05-013 were examined to the maximum extent possible from both sides of the weld, using 0-degree, 45-degree, and 60-degree shear and longitudinal wave search units, scanning both parallel and perpendicular to the weld. In RAI 1a, RAI 1b, and RAI 1c the NRC staff requested the licensee to clarify the coverage diagrams provided in the submittal. In its response to RAI 1a by letter dated May 24, 2016, the licensee provided separate axial (perpendicular) and circumferential (parallel) scan diagrams.
These separate diagrams and the supporting information in the licensee's responses to RAI 1b and RAI 1c regarding the diagrams, enabled the NRC staff to confirm the examination coverages achieved. Therefore, RAI 1a, RAI 1b, and RAI 1care resolved. The examination volumes included the weld and base materials near the inside surface of the weld joint, which are regions of high stress, and where one would expect degradation to be manifested should it occur.
For Pressurizer Nozzle Weld 05-010, the UT examinations revealed no recordable indications.
For Pressurizer Nozzle Welds05-011, 05-012, and 05-013, the UT examinations revealed intermittent geometric indications at the interface of the nozzle bore. As stated in Supplement 11 of Appendix I to Section XI of the ASME Code, geometric indications need not be characterized as originating from flaws. In its response to RAI 3 by letter dated May 24, 2016, the licensee stated that the ANO, Unit 2 pressurizer was replaced in 2006 and that there has been no degradation identified in the pressurizer welds thus far. Thus, RAI 3 with respect to Relief Request No. AN02-ISl-018 weld, is resolved. Based on the examination coverage obtained for the subject welds, if significant service-induced degradation were occurring, the NRC staff concluded that there is reasonable assurance that evidence of degradation would be detected by the examination coverage achieved.
Based on the above discussion, the NRC staff determined that obtaining the ASME Code required examination volume is impractical because of the nozzle-to-head configuration of the subject welds. Significant modification of the pressurizer vessel and nozzles would be needed for ASME Code compliance, which imposes a burden upon the licensee. The staff also determined that the volumetric UT examination performed to the maximum extent possible provides reasonable assurance of the structural integrity of the subject pressurizer nozzle welds in Relief Request No. AN02-ISl-018. The licensee will continue to perform the required pressure testing, which includes visual examination for evidence of leakage.
4.0 CONCLUSION
As set forth above, the NRC staff has determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest given due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Furthermore, the staff concludes that the licensee's examinations were performed to the maximum extent possible and provide reasonable assurance of the structural integrity of the subject ANO, Unit 2 pressurizer nozzle welds. Accordingly, the staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(6)(i).
Therefore, the staff grants Relief Request No. AN02-ISl-018 for the ANO, Unit 2, fourth 10-year ISi interval.
All other requirements of Section XI of the ASME Code for which relief was not specifically requested and approved in the subject relief requests remain applicable, including third party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: David Dijamco, NRR/DE/EVIB Date: August 16, 2016
ML16222A137 *concurrence via email OFFICE NRR/DORULPL4-2/PM NRR/DORULPL4-2/LA NRR/DE/EVIB/BC* NRR/DORULPL4-2/BC(A)
NAME SKoenick PBlechman JMcHale SAnderson DATE 8/12/16 8/11/16 7/22/16 8/16/16