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Category:Letter
MONTHYEARIR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 IR 05000382/20230032024-01-23023 January 2024 Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23340A2292023-12-28028 December 2023 Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR 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 ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23312A1832023-11-14014 November 2023 Integrated Inspection Report 05000382/2023003 and Notice of Violation 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 IR 05000382/20234012023-10-0404 October 2023 Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only) IR 05000382/20230052023-08-21021 August 2023 Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005) IR 05000382/20233012023-08-15015 August 2023 NRC Initial Operator Licensing Examination Approval 05000382/2023301 IR 05000382/20230022023-08-0808 August 2023 Integrated Inspection Report 05000382/2023002 IR 05000382/20234022023-08-0707 August 2023 NRC Security Inspection Report 05000382/2023402 (Full Report) IR 05000382/20230402023-07-12012 July 2023 Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter ML23191A4562023-07-10010 July 2023 Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information ML23158A1042023-06-0808 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000382/2023401 ML23145A2272023-06-0202 June 2023 95001 Supplemental Inspection Report 05000382/2023040, and Exercise of Enforcement Discretion ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment IR 05000382/20230012023-04-24024 April 2023 Integrated Inspection Report 05000382/2023001, Independent Spent Fuel Storage Installation Report 07200075/2023001, and Exercise of Enforcement Discretion ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23108A2542023-04-18018 April 2023 WCGS Information Request, Security IR 2023401 IR 05000382/20234032023-04-17017 April 2023 Security Baseline Inspection Report 05000382/2023403 ML23093A2122023-04-0303 April 2023 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2022 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc ML23059A2592023-03-0707 March 2023 Correction to Issuance to Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23065A2002023-03-0303 March 2023 EN 56252 Update - Flow Serve - Final Notification of Potential Part 21 on Peerless 56 Frame DC Motors ML23060A1092023-03-0101 March 2023 Proof of Financial Protection (10 CFR 140.15) IR 05000382/20220062023-03-0101 March 2023 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3, (Report 05000382/2022006) ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b IR 05000382/20230902023-02-0101 February 2023 Final Significance Determination of a White Finding, NOV, and Follow-Up Assessment Letter; NRC Inspection Report 05000382/2023090 ML23032A5062023-02-0101 February 2023 Technical Specification Index and Bases Update to the NRC for the Period November 11, 2021 Through July 25, 2022 ML23030A6642023-01-27027 January 2023 Flowserve, Part 21 Second Interim Notification Report Re Peerless 56 Frame DC Motors IR 05000382/20220042023-01-26026 January 2023 Integrated Inspection Report 05000382/2022004 and Independent Fuel Storage Installation Inspection Report 07200075/2022001 ML23024A0822023-01-20020 January 2023 Stephens Insurance, Entergy - 2023 Nuclear Energy Liability Evidence of Financial Protection ML23018A2202023-01-18018 January 2023 Quality Assurance Program Manual Reduction in Commitment IR 05000382/20220912023-01-12012 January 2023 Emergency Preparedness Inspection Report 05000382/2022091 and Preliminary White Finding and Apparent Violation IR 05000382/20220032023-01-0505 January 2023 Revised Integrated Inspection Report 05000382/2022003 ML22342B1402022-12-0202 December 2022 56252-EN 56252 - Flowserve - Limitorque - Interim Report Potential Part 21 on Peerless 56 Frame DC Motors ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22332A5292022-11-29029 November 2022 Notification of NRC Initial Operator Licensing Examination 05000382/2023301 IR 05000382/20220132022-11-28028 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000382/2022013 IR 05000382/20220022022-11-0101 November 2022 Revised Integrated Inspection Report 05000382/2022002 2024-01-31
[Table view] Category:Safety Evaluation
MONTHYEARML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22194A9012022-07-20020 July 2022 Issuance of Amendment No. 268 Adoption of Technical Specification Task Forcetraveler TSTF-569, Revise Response Time Testing Definition, Revision 2 ML22153A4452022-07-0808 July 2022 Issuance of Amendment No. 267 for Reactor Coolant System Pressure/Temperature Limits and Low Temperature Overpressure Setpoints Applicable for 55 Effective Full Power Years ML22145A0152022-05-27027 May 2022 Issuance of Amendment No. 266 to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22075A1022022-04-29029 April 2022 Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual 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 ML22061A2172022-03-15015 March 2022 Revision of the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule 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 ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21166A1832021-09-15015 September 2021 Issuance of Amendment No. 261 Regarding Removal and Relocation of Boration System Technical Specifications ML21131A2432021-08-24024 August 2021 Issuance of Amendment No. 260 Digital Upgrade to the Core Protection and Control Element Assembly Calculator System ML21082A3022021-05-19019 May 2021 Issuance of Amendment No. 259 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML20280A3292020-10-20020 October 2020 Issuance of Amendment No. 258 Regarding Technical Specification 3/4.8.1 Surveillance Requirements ML20205L5742020-08-25025 August 2020 Issuance of Amendment No. 257 Control Room Air Condition System Technical Specifications ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20022A2582020-01-28028 January 2020 Re-Issuance of Approval of Relief Request WF3-RR-19 2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control ML20002A0202020-01-13013 January 2020 Approval of Relief Request WF3-RR-19-2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control System ML19275D4382019-10-24024 October 2019 Redacted - Issuance of Amendment No. 256 for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components ML19282D8922019-10-15015 October 2019 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule 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 ML19247B1972019-09-0909 September 2019 Approval of Relief Request W3-ISI-032,Relief from the Requirements of ASME Code Section XI Regarding Volumetric Examination ML19232A0252019-08-27027 August 2019 Authorization of Proposed Alternative to ASME Code Section XI, IWA-4000, Repair/Replacement Activities ML19164A0012019-06-28028 June 2019 Issuance of Amendment No. 254 Regarding Revision of Technical Specification 3/4.7.4, Ultimate Heat Sink, ML19157A3162019-06-12012 June 2019 Authorization of Proposed Alternative to ASME Code Case N-770-2 ML19022A3372019-02-13013 February 2019 Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload ML18282A0302018-10-18018 October 2018 Proposed Alternative to ASME Code, Section XI, Regarding Charging Pipe Visual Inspection ML18180A2982018-07-23023 July 2018 Issuance of Amendment No. 252 Adoption of the Raptor-M3G Code for Neutron Fluence Calculations ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 ML18026B0532018-04-26026 April 2018 Issuance of Amendment No. 251 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control,(Cac No. MF9537; EPID L-2017-LLA-0205) ML17341A1202017-12-11011 December 2017 Relief Request PRR-WF3-2017-3, Request for Alternative to ASME OM Code Requirements for Comprehensive Testing of High Pressure Safety Injection Pump AB (CAC No. MF9875; EPID L-2017-LLR-0049) ML17328A8822017-11-29029 November 2017 Requests for Relief GRR-1, PRR-1 and PRR-2, Alternatives to ASME OM Code Requirements for Inservice Testing for the Fourth 10-Year Program Interval (CAC Nos. MF9869, 9870, and 9871; EPID L-2017-LRM-0045-47) ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML17069A1872017-03-22022 March 2017 Request for Alternative to 10 CFR 50.55a(c) ASME Code Section III Code Case 1361-1, Relief Request W3-ISI-024 ML17045A1482017-03-0303 March 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16235A2282016-12-0909 December 2016 Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML16278A0172016-10-19019 October 2016 Entergy Fleet Relief Request RR-EN-ISI-15-1, Alternative to Maintain Inservice Inspection Related to Activities to the 2001 Edition/2003 Addendum of ASME Section XI Code ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16159A4192016-07-26026 July 2016 Issuance of Amendment No. 249 Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control ML16182A2702016-07-0606 July 2016 Relief Request PRR-WF3-2016-1, Alternative to the Inservice Testing Program ML16126A0332016-06-27027 June 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule ML15289A1432015-11-13013 November 2015 Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times ML15267A7972015-10-0606 October 2015 Safety Evaluation Regarding the Aging Management Program for Reactor Vessel Internals ML15139A4832015-08-31031 August 2015 Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power 2023-05-01
[Table view] |
Text
May 20, 2008 Vice President, Operations Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - CORRECTION TO REQUEST FOR ALTERNATIVE W3-R&R-006 - PROPOSED ALTERNATIVE TO ASME CODE REQUIREMENTS FOR WELD OVERLAY (TAC NO.
MD5388)
Dear Sir or Madam:
Entergy Operations, Inc. (the licensee) submitted by letter dated April 26, 2007, as revised by supplemental letter dated February 21, 2008, an alternative to the requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWA-4000 for mitigating primary water stress-corrosion cracking on nine specific dissimilar metal welds using preemptive full structural weld overlays at Waterford Steam Electric Station, Unit 3 (Waterford 3). The licensee proposed the alternative for the current second 10-year inservice inspection (ISI) interval which ends on May 30, 2008. Pursuant to paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations (10 CFR), by letter dated April 21, 2008, the U.S. Nuclear Regulatory Commission (NRC) staff authorized the use of the proposed alternative for the second 10-year ISI interval at Waterford 3.
The NRC staff inadvertently issued pages 3, 9, and 11 of the Safety Evaluation with administrative errors. The corrected pages, with the changes denoted by the vertical bar on the right, are enclosed. Please note that Page 12 is being sent because of the overflow from Page 11.
The affected pages of the safety evaluation are enclosed.
Sincerely,
/RA/
N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Safety Evaluation, pages 3,9,11, and 12 cc w/encl: See next page
ML081400568 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NAME NKalyanam GLappert THiltz DATE 5/20/08 5/20/08 5/20/08 Waterford Steam Electric Station, Unit 3 (2/25/08) cc:
Senior Vice President Mr. Timothy Pflieger Entergy Nuclear Operations Environmental Scientist - Supervisor P.O. Box 31995 REP&R-CAP-SPOC Jackson, MS 39286-1995 Louisiana Department of Environmental Quality Vice President, Oversight P.O. Box 4312 Entergy Nuclear Operations Baton Rouge, LA 70821-4312 P.O. Box 31995 Jackson, MS 39286-1995 Parish President Council St. Charles Parish Senior Manager, Nuclear Safety P.O. Box 302
& Licensing Hahnville, LA 70057 Entergy Nuclear Operations P.O. Box 31995 Chairman Jackson, MS 39286-1995 Louisiana Public Services Commission P.O. Box 91154 Senior Vice President Baton Rouge, LA 70825-1697
& Chief Operating Officer Entergy Operations, Inc. Mr. Richard Penrod, Senior Environmental P.O. Box 31995 Scientist/State Liaison Officer Jackson, MS 39286-1995 Office of Environmental Services Northwestern State University Associate General Counsel Russell Hall, Room 201 Entergy Nuclear Operations Natchitoches, LA 71497 P.O. Box 31995 Jackson, MS 39286-1995 Resident Inspector Waterford NPS Manager, Licensing P.O. Box 822 Entergy Operations, Inc. Killona, LA 70057-0751 Waterford Steam Electric Station, Unit 3 17265 River Road Regional Administrator, Region IV Killona, LA 70057-3093 U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011
3.0 LICENSEE=S PROPOSED ALTERNATIVE
3.1 ASME Code Components Affected
The licensee proposes to install a preemptive full structural weld overlay on the DMWs listed in Table 1. The weld overlay will also be installed on six similar metal welds, also identified in Table 1.
TABLE 1 DISSIMILAR METAL WELD DETAILS Material Identification Nozzle Type Nozzle ISI Weld and Pipe Size carbon steel ISI weld Safe end (SE) (SST) Pipe/Fitting Pressurizer to Surge SA 508, Cl. 2 DMW 82/182 SA- 351, SST Weld SA-351, CF8M Line w/ SST Clad ID 16-017 CF8M (Cast ID 16-016 (1)
(Pipe) 12 in. NPS SST)
Pressurizer to Relief SA 508, Cl. 2 DMW 82/182 SA- 351, SST Weld SA-403, WP304 Valve (RC-317A) w/ SST Clad ID 26-006 CF8M (Cast ID 26-007 (Elbow) 6@ NPS SST)
Pressurizer to Relief SA 508, Cl. 2 DMW 82/182 SA- 351, SST Weld SA-403, WP304 Valve (RC-317B) w/ SST Clad ID 26-001 CF8M (Cast ID 26-002 (Elbow) 6@ NPS SST)
Pressurizer spare nozzle SA 508, Cl. 2 DMW 82/182 SA-351, CF8M SST Weld SA-403, (Capped) w/ SST Clad ID 26-010 (Cast SST) ID 26-011 WP304/316 4@ NPS (End Cap)
Pressurizer to spray line SA 508, Cl. 2 DMW 82/182 SA-182, SST Weld SA-376, TP304 4@ NPS w/ SST Clad ID 25-029 Type 316 ID 25-028 (1)
(Pipe)
Hot Leg 1 to SDC SA 105, Cl. 2 DMW 82/182 SA- 351, SST Weld SA-358, Type 304 (1) 14= NPS w/ SST Clad ID 15-008 CF8M ID 21-001 (Pipe)
(Cast SST)
Hot Leg 2 to SDC SA 105, Cl. 2 DMW 82/182 SA- 351, SST Weld SA-358, Type 304 (1) 14= NPS w/ SST Clad ID 06-006 CF8M ID 22-001 (Pipe)
(Cast SST)
Hot Leg 1 to Surge line SA 105, Cl. 2 DMW 82/182 SA- 351, SST Weld SA-351, CF8M (1) 12= NPS w/ SST Clad ID 15-009 CF8M ID 16-001 (Pipe)
(Cast SST)
Hot Leg to Drain SA 105, Cl. 2 DMW 82/182 SA-182, SST Weld SA-376, TP304 (1) 2@ NPS w/ SST Clad ID 15-006 Type 316 ID 32-001 (Pipe)
NPS = nominal pipe size; SDC = shutdown cooling; SST = stainless steel, Code Class 1 (1)
To facilitate preservice/ISI of these austenitic stainless steel welds, the preemptive structural weld overlay for each DMW will be extended across the stainless steel weld.
3.2 Code Requirements Subarticle IWA-4170(b) of the ASME Code,Section XI, requires that repairs and the installation of replacement items be performed in accordance with the Owner=s Design Specification and the original Construction Code of the component or system. Alternatively, Subarticle IWA-4170(b) of the ASME Code,Section XI, allows for use of later Editions and
4.3.2 Preservice Examination Section 3.0(b), APreservice Inspection,@ of Attachment 2, Reference 2, requires an UT of the installed weld overlay and the upper (outer) 25 percent of the original pipe-wall thickness.
The required examination volume is defined in Figure 2 of Attachment 2, Reference 2. The staff finds that the preservice examination requirements are acceptable because they are consistent with Code Case N-504-3; the ANO Request for Alternative ANO1-R&R-010; the Farley and Vogtle Relief Request ISI-GEN-ALT-06-03; and the ASME Code,Section XI, Appendix Q.
4.3.3 Inservice Examination Section 3.0(c) of Attachment 2 of Reference 2 requires inservice examination be conducted ultrasonically with the examination volume defined in Figure 2 of Attachment 2 of Reference 2. The requirements in Section 3.0(c) of Attachment 2 are consistent with the ANO Request for Alternative ANO1-R&R-010; the Farley and Vogtle Relief Request ISI-GEN-ALT-06-03; and the ASME Code,Section XI, Appendix Q with the following exception.
In Section V.A.3.c, Reference 2, the licensee discussed the inspection issues regarding cast stainless steel (CASS) which was used to fabricate the safe ends at the 7 nozzles specified in the DMW Details Table on Page 21 of 51 (of Reference 2). The licensee stated and the staff agrees that the UT has not been qualified in accordance with Appendix VIII, Supplement 11 of the ASME Code,Section XI, in the examination of CASS. The licensee stated further that a flaw with a depth of 75 percent of pipe thickness and circumference of 360 degrees will be assumed in the crack-growth calculation for the cast stainless steel safe ends. In light of the limited UT capability to examine CASS, the staff determined that the postulated 75 percent depth flaw in the crack-growth calculation was not sufficiently conservative to demonstrate the structural integrity of the CASS component.
The licensee stated that, to address this issue, it will perform UT examination during the first or second refueling outage following weld overlay application per Section 3.0(c)(1) in addition to performing UT examinations every 10 years, pending qualified PDI techniques for CASS.
The licensee further stated that until PDI procedures are qualified for CASS materials, it will perform Abest effort@ ISI of the CASS component per the ASME Code,Section XI, Appendix III. The use of Appendix III for examination of CASS is consistent with subarticle VIII-3110(c) of Appendix VIII to the ASME Code,Section XI. Once qualified, the licensee will implement these PDI procedures at the next scheduled ISI as required by Section 3.0(c) of , Reference 2.
The staff finds that the licensees strategy for additional examination of the CASS component is acceptable.
4.4 Proposed Ambient Temperature Temper Bead Welding The requirements for the proposed ambient temperature temper bead welding are discussed in Attachment 3 to Reference 2, and are based on Code Case N-638-1. The requirements in to W3-R&R-006 are consistent with Code Case N-638-1; the ANO Request for
accordance with the UT criteria of Appendix VIII, Supplement 11. Prior to the Supplement 11 program, EPRI was maintaining a performance demonstration program (the precursor to the PDI program) for weld overlay qualification under the Tri-party Agreement with the NRC, BWR Owner=s Group, and EPRI, as discussed in the NRC letter dated July 3, 1984. Later, the NRC staff recognized the EPRI PDI program for weld overlay qualifications as an acceptable alternative to the Tri-party Agreement in its letter dated January 15, 2002, to the PDI Chairman (ADAMS Accession No. ML020160532).
The PDI program is routinely assessed by the staff for consistency with the current ASME Code and proposed changes. The PDI program does not fully comport with the existing requirements of Supplement 11. The PDI representatives presented the differences between Supplement 11 and the PDI program at public meetings in which the NRC participated (Memorandum from Donald G. Naujock to Terence Chan, ASummary of Public Meeting Held January 31 - February 2, 2002, with PDI Representatives,@ March 22, 2002 (ADAMS Accession No. ML010940402), and Memorandum from Donald G. Naujock to Terence Chan, ASummary of Public Meeting Held June 12 through June 14, 2001, with PDI Representatives,@
November 29, 2001 (ADAMS Accession No. ML013330156)). Based on the discussions at these public meetings, the staff determined that the industry=s PDI program provides an acceptable level of quality and safety.
The licensee proposed to use the PDI program as indicated in Attachment 6 to Enclosure 3 of Reference 2, to satisfy the Appendix VIII, Supplement 11, qualification requirements. The PDI initiatives will be used for qualification of UT to detect and size flaws in the preemptive full structural weld overlays of this request. The NRC staff evaluated the differences between the PDI program and Supplement 11 as shown in Attachment 6 to W3-R&R-006. The NRC staff concludes that the justifications for the differences are acceptable and the PDI program provides an acceptable level of quality and safety. Therefore, the proposed Waterford 3 PDI program is acceptable for use in lieu of Supplement 11 of Appendix VIII to the ASME Code,Section XI.
4.6 Commitments As part of Request for Alternative W3-R&R-006, the licensee made the following commitments as shown in Enclosure 4 of Reference 2:
(1) The licensee will submit the following information to the NRC within 14 days from completing the final UTs of the completed weld overlays:
- Weld overlay examination results including a listing of indications detected,
- Disposition of all indications using the standards of ASME Code,Section XI, IWB-3514-2 and/or IWB-3514-3 criteria and, if possible, the type and nature of the indications, and
- A discussion of any repairs to the weld overlay material and/or base metal and the reason for the repairs.
(2) Prior to entry into Mode 4 start-up from RF15, the licensee will submit to the NRC a stress analysis summary demonstrating that the hot-leg piping and
pressurizer nozzles will perform their intended design functions after the weld overlay installation. The stress analysis report will include results showing that the requirements of NB-3200 and NB-3600 of the ASME Code,Section III, are satisfied. The stress analysis will also include results showing that the requirements of IWB-3000 of the ASME Code,Section XI, are satisfied. The results will show that the postulated crack including its growth in the nozzles will not adversely affect the integrity of the overlaid welds.
(3) Unless PDI procedures are qualified in time to support the preservice examinations required by Attachment 2, the licensee will perform a Abest effort@
preservice examination of the cast stainless steel region, following installation of the weld overlays during refueling outage RF15.
(4) Until PDI procedures are qualified to examine the upper 25 percent of the cast stainless steel, Entergy will perform Abest effort@ ISI of the region shown in Figure 2 of Attachment 2. Once qualified, the licensee will implement these PDI procedures at the next scheduled ISI as required by paragraph 3.0(c) of Attachment 2. Note: ISI of weld overlays for stainless steel welds is performed at the frequencies required by the Waterford 3 ISI Program as stipulated in Section V.A.3.
(5) ISI of the DMW weld overlays with cast stainless steel safe ends will be performed at a higher frequency than those without cast stainless steel safe ends. First, the initial UT inspection of the DMW weld overlays will be performed during the first or second refueling outage after installation. Then, instead of being inspected on a 25 percent sample basis, these weld overlays will be UT examined once every 10 years from the date of installation until such time when a technique is qualified to examine cast stainless steel in accordance with the PDI Program. Once the subject DMW overlays are UT examined by a qualified PDI technique (for cast stainless steel) and no planar flaws are detected, then the DMW overlays will be placed into a population in which 25 percent of that population is examined once every 10 years. Until such time, the UT inspections of the subject DMW overlays (with cast stainless steel safe ends) will not be credited to satisfy the 25 percent sample inspection requirement. Note: ISI of weld overlays for stainless steel welds is performed at the frequencies required by the Waterford 3 ISI Program as stipulated in Section V.A.3.j.
The NRC staff finds that the above commitments are acceptable because the weld overlay examination results and stress analysis will provide verification of the condition of the weld overlays after installation.
5.0 CONCLUSION
The NRC staff has reviewed the licensee=s submittal and determined that Request for Alternative W3-R&R-006 (Reference 2), will provide an acceptable level of quality and safety.
Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the staff authorizes the use of Request for Alternative W3-R&R-006 for the installation of full structural weld overlays on the dissimilar metal welds of the Pressurizer Nozzle to Surge Line, Pressurizer Nozzle to Relief Valve (two