|
|
| (5 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML121380483 | | | number = ML121380483 |
| | issue date = 05/22/2012 | | | issue date = 05/22/2012 |
| | title = Grand Gulf, Unit 1, Memo to File, Verbal Authorization of Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval ( | | | title = Memo to File, Verbal Authorization of Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval |
| | author name = Wang A B | | | author name = Wang A |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = | | | addressee name = |
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:May 22, 2012 | | {{#Wiki_filter:May 22, 2012 MEMORANDUM TO: Docket File FROM: Alan B. Wang, Project Manager /RA/ |
| | | Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
| MEMORANDUM TO: Docket File FROM: Alan B. Wang, Project Manager /RA/ Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| GRAND GULF NUCLEAR STATION, UNIT 1 - VERBAL AUTHORIZATION OF RELIEF REQUEST ISI-17, PROPOSED ALTERNATIVE REGARDING STRUCTURAL WELD OVERLAY (SWOL) ON THE N06-KB RESIDUAL HEAT REMOVAL SYSTEM/ LOW-PRESSURE COOLANT INJECTION "C" NOZZLE TO SAFE-END DISSIMILAR METAL WELD (TAC NO. ME8525) | | GRAND GULF NUCLEAR STATION, UNIT 1 - VERBAL AUTHORIZATION OF RELIEF REQUEST ISI-17, PROPOSED ALTERNATIVE REGARDING STRUCTURAL WELD OVERLAY (SWOL) ON THE N06-KB RESIDUAL HEAT REMOVAL SYSTEM/ |
| | LOW-PRESSURE COOLANT INJECTION C NOZZLE TO SAFE-END DISSIMILAR METAL WELD (TAC NO. ME8525) |
| By letter dated May 2, 2012, as supplemented by letter dated May 9, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML12124A245 and ML12131A408, respectively), Entergy Operations Inc. (Entergy, the licensee), submitted relief request (RR) ISI-17 for the Grand Gulf Nuclear Station, Unit 1 (GGNS) for U.S. Nuclear Regulatory Commission (NRC) review and approval. | | By letter dated May 2, 2012, as supplemented by letter dated May 9, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML12124A245 and ML12131A408, respectively), Entergy Operations Inc. (Entergy, the licensee), submitted relief request (RR) ISI-17 for the Grand Gulf Nuclear Station, Unit 1 (GGNS) for U.S. Nuclear Regulatory Commission (NRC) review and approval. |
| The licensee submitted the RR under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(a)(3)(i). In this submittal, the licensee proposed an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, paragraphs IWA-4411 (a) and (b), IWA-4420 and IWA-4600(b), and associated linked and branching requirements. As part of its compliance with these requirements, the licensee proposed to implement the ASME Code, Section XI, Code Cases N-504-4, "Alternate Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping," and N-638-4, "Similar and Dissimilar Metal Welding using Ambient Temperature Machine GTAW [Gas Tungsten Arc Weld] Temper Bead Technique," as conditionally approved by the NRC. Under this RR, the licensee would perform a structural weld overlay (SWOL) using these ASME Code Cases on the N06-KB residual heat removal system (RHR)/low-pressure coolant injection (LPCI) "C" nozzle to safe-end dissimilar metal weld. The SWOL would be installed on the subject weld without removing the defect in the weld and the application of the SWOL is to arrest the growth of the existing defect while establishing a new structural pressure boundary. The licensee has made a regulatory commitment to provide a flaw evaluation as part of the technical basis to justify this repair and stated in its letter dated May 2, 2012, in part, that "preservice and inservice inspection of the weld overlay will be performed to ensure structural integrity is maintained." | | The licensee submitted the RR under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(a)(3)(i). In this submittal, the licensee proposed an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, paragraphs IWA-4411 (a) and (b), IWA-4420 and IWA-4600(b), and associated linked and branching requirements. As part of its compliance with these requirements, the licensee proposed to implement the ASME Code, Section XI, Code Cases N-504-4, Alternate Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping, and N-638-4, Similar and Dissimilar Metal Welding using Ambient Temperature Machine GTAW [Gas Tungsten Arc Weld] Temper Bead Technique, as conditionally approved by the NRC. Under this RR, the licensee would perform a structural weld overlay (SWOL) using these ASME Code Cases on the N06-KB residual heat removal system (RHR)/low-pressure coolant injection (LPCI) C nozzle to safe-end dissimilar metal weld. The SWOL would be installed on the subject weld without removing the defect in the weld and the application of the SWOL is to arrest the growth of the existing defect while establishing a new structural pressure boundary. The licensee has made a regulatory commitment to provide a flaw evaluation as part of the technical basis to justify this repair and stated in its letter dated May 2, 2012, in part, that preservice and inservice inspection of the weld overlay will be performed to ensure structural integrity is maintained. |
| | The licensee provided information to demonstrate that the proposed alternative would maintain an acceptable level of quality and safety under all licensing basis conditions of operation. The NRC staff has completed its review of the information provided in the licensees submittal for proposed alternative ISI-17 regarding the repair of RHR/LPCI C nozzle to safe-end dissimilar metal weld N06B-KB and concludes that the information provided by the licensee is consistent |
|
| |
|
| The licensee provided information to demonstrate that the proposed alternative would maintain an acceptable level of quality and safety under all licensing basis conditions of operation. The NRC staff has completed its review of the information provided in the licensee's submittal for proposed alternative ISI-17 regarding the repair of RHR/LPCI "C" nozzle to safe-end dissimilar metal weld N06B-KB and concludes that the information provided by the licensee is consistent with the provisions of 10 CFR 50.55a(a)(3)(i) and supports the granting of the proposed alternative to the ASME Code requirements.
| | with the provisions of 10 CFR 50.55a(a)(3)(i) and supports the granting of the proposed alternative to the ASME Code requirements. |
| Conclusion | | Conclusion Pursuant to 10 CFR 50.55a(a)(3)(i), as of May 10, 2012, the NRC authorizes the licensee to implement the proposed alternative in accordance with the information provided in the licensees letter dated May 2, 2012, and supplemented by letter dated May 9, 2012. The authorization is immediately effective for the N06-KB RHR/LPCI C nozzle to safe-end dissimilar metal weld and will remain in effect for during the third inservice inspection interval of the GGNS. |
| | |
| Pursuant to 10 CFR 50.55a(a)(3)(i), as of May 10, 2012, the NRC authorizes the licensee to implement the proposed alternative in accordance with the information provided in the licensee's letter dated May 2, 2012, and supplemented by letter dated May 9, 2012. The authorization is immediately effective for the N06-KB RHR/LPCI "C" nozzle to safe-end dissimilar metal weld and will remain in effect for during the third inservice inspection interval of the GGNS. | |
| All other ASME Code requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. | | All other ASME Code requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. |
| The participants in the telephone call were: | | The participants in the telephone call were: |
| | | NRC Michael Markley, Branch Chief, NRR/DORL/LPL4 Stacy Rosenberg, Branch Chief, NRR/DE/EVIB Ganesh Cheruvenki, NRR/DE/EVIB John Tsao, NRR/DE/EPNB Bob Hagar, RIV/DRP/RPB-C/ |
| NRC Michael Markley, Branch Chief, NRR/DORL/LPL4 Stacy Rosenberg, Branch Chief, NRR/DE/EVIB Ganesh Cheruvenki, NRR/DE/EVIB John Tsao, NRR/DE/EPNB Bob Hagar, RIV/DRP/RPB-C/ Wayne Sifre, RIV/DRS/EB-1/ Alan Wang, NRR/DORL/LPL4 | | Wayne Sifre, RIV/DRS/EB-1/ |
| | | Alan Wang, NRR/DORL/LPL4 Entergy Operations, Inc. |
| Entergy Operations, Inc. | |
| Steve Scott, Entergy Central Engineering Joe Weicks, Entergy Central Engineering Michael Briley, Entergy Central Engineering Ron Williams, Entergy Engineering Programs Jamie Gobell, Arkansas Nuclear One Project Management Dennis Wiles, GGNS Engineering Director William Simms, Entergy Services, Inc. Design Engineering Jeff Seiter, GGNS Licensing From Structural Integrity: | | Steve Scott, Entergy Central Engineering Joe Weicks, Entergy Central Engineering Michael Briley, Entergy Central Engineering Ron Williams, Entergy Engineering Programs Jamie Gobell, Arkansas Nuclear One Project Management Dennis Wiles, GGNS Engineering Director William Simms, Entergy Services, Inc. Design Engineering Jeff Seiter, GGNS Licensing From Structural Integrity: |
| Moses Taylor Jr., P.E Anthony J. Giannizzi | | Moses Taylor Jr., P.E Anthony J. Giannizzi Docket No. 50-416 |
| | |
| Docket No. 50-416 | |
|
| |
|
| ML121380483 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DE/EVIB/BC NRR/LPL4/BC NRR/LPL4/PM NAME AWang JBurkhardt SRosenberg MMarkley AWang (LWilkins for) -DATE 5/21/12 5/18/12 5/21/12 5/22/12 5/22/12}} | | ML121380483 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DE/EVIB/BC NRR/LPL4/BC NRR/LPL4/PM NAME AWang JBurkhardt SRosenberg MMarkley AWang (LWilkins for) |
| | -DATE 5/21/12 5/18/12 5/21/12 5/22/12 5/22/12}} |
Letter Sequence Other |
|---|
|
|
MONTHYEARML1212906172012-05-0808 May 2012
E-mail, Request for Additional Information, Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval
Project stage: RAI
GNRO-2012/00045, Response to Request for Additional Information Regarding Request ISI-172012-05-0909 May 2012
Response to Request for Additional Information Regarding Request ISI-17
Project stage: Response to RAI
ML1213804832012-05-22022 May 2012
Memo to File, Verbal Authorization of Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval
Project stage: Other
ML12214A3182012-08-17017 August 2012
Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval
Project stage: Other
2012-05-08
[Table View] |
|
|---|
Category:Memoranda
MONTHYEARML23047A3822023-03-21021 March 2023
Summary of December 15, 2022 Periodic Advanced Reactor Stakeholder Public Meeting
ML22147A0932022-06-0606 June 2022
2021 Annual Assessment Public Meeting Summary
ML22034A3932022-02-16016 February 2022
Calendar Year 2021 Security Baseline Completion Memo
ML21295A0882021-10-21021 October 2021
Fiscal Year 2021 Research and Test Reactors Inspection Program Completion Status
ML21181A3352021-07-0101 July 2021
June 23, 2021, Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project
ML21158A2232021-06-0808 June 2021
Meeting Summary for Ticap Workshop 3
ML21132A2952021-05-14014 May 2021
Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project
ML20150A4212020-11-23023 November 2020
Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Entergy Nuclear Company, LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Grand Gulf ISFSI
ML20218A7512020-08-0707 August 2020
Summary of June 25, 2020 Teleconference with Grand Gulf Nuclear Station
ML19182A3562019-07-23023 July 2019
Quarterly Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 - April 1 to June 30, 2019
ML19204A1492019-07-16016 July 2019
FEMA Region IV Memo 07-16-19: Hurricane Barry Preliminary Capabilities Assessment
ML19204A1482019-07-15015 July 2019
FEMA Region VI Memo 07-15-19: Hurricane Barry Preliminary Capabilities Assessment
ML19018A2692019-03-12012 March 2019
Safety Evaluation Input for Grand Gulf Nuclear Station Unit 1, License Amendment Request to Implement Technical Specification Task Force-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control
ML18173A0082018-06-20020 June 2018
Cancelling Numerous Inspection Report Numbers
ML16287A5902016-11-17017 November 2016
Renewal of Full-Power Operating Licenses for Grand Gulf Nuclear Station Unit 1 (TAC No. ME7493)
ML16294A2072016-10-27027 October 2016
Communications Plan Regarding the Renewal of the Grand Gulf Nuclear Station Unit 1, Operating License
ML16210A5262016-07-28028 July 2016
License Renewal Application
ML16067A2402016-03-31031 March 2016
Advisory Committee on Reactor Safeguards Review of the Grand Gulf Nuclear Station, Unit 1, License Renewal Application - Transmittal of Final Safety Evaluation Report
ML16088A2042016-03-28028 March 2016
Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template)
ML16088A2052016-03-28028 March 2016
Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations
ML15324A0862015-11-24024 November 2015
Summary of Conference Call Confirming Staff Understanding of Basis for Closing Open Item in Grand Gulf Reevaluated Flood Hazard Staff Assessment of Response to 10 CFR 50.54(f) Information Request- Flood Causing Mechanism Reevaluation
ML15195A3552015-08-31031 August 2015
Issuance of Amendment Request for Changing Five Technical Specifications Allowable Values
ML14163A7302014-06-12012 June 2014
Supplemental Inspection Charter to Evaluate Licensee Actions Related to Pi for Unplanned Scrams Per 7000 Critical Hours, Which Crossed Green-White Threshold During First Quarter 2013
ML14043A1102014-02-28028 February 2014
01/29/2014 Summary of Public Meetings to Discuss Draft Supplement 50 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Grand Gulf, Unit 1, (TAC Nos ME7385 and ME7386)
ML13207A0462013-07-26026 July 2013
EA-13-058 Teleconference Notice
ML13182A4262013-07-0202 July 2013
Notice of Forthcoming Meeting with Entergy Operations, Inc., for a Predecisional Enforcement Conference Related to the Grand Gulf Nuclear Station (EA-13-058)
ML12334A5862013-01-0303 January 2013
Summary of Telephone Conference Call Held on October 9, 2012, Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station
ML12264A6492012-11-15015 November 2012
Summary of Telephone Conference Call Held on August 29, 2012, Between the NRC and Entergy, Concerning RAI Pertaining to the Grand Gulf Nuclear Station, LRA
ML12264A3922012-11-0909 November 2012
Summary of Telephone Conference Call Held on 9/04/12 Between the Us NRC and Entergy Operations, Inc. Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, License Renewal Application
ML12202A2142012-08-15015 August 2012
5/30/12 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA
ML1213804832012-05-22022 May 2012
Memo to File, Verbal Authorization of Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval
ML1201303402012-01-18018 January 2012
1/30/2012-Notice of Forthcoming Meeting with Entergy Operations, Inc., to Discuss Schedule for Completion of Steam Dryer Review Related to Grand Gulf Nuclear Station, Unit 1, Extended Power Uprate
ML11362A4332012-01-0606 January 2012
Forthcoming Meeting to Discuss the License Renewal Process and Environmental Scoping for Grand Gulf Nuclear Station, Unit 1, License Renewal Application
ML11333A2452011-11-29029 November 2011
Acceptance of License Renewal Application, Grand Gulf Nuclear Station, Unit 1
ML1115704052011-06-0606 June 2011
Notice of Meeting with Entergy Operations, Inc., to Discuss Implementation of Quality Oversight and Verification Programs at Entergy Sites Including Actions Being Taken to Enhance Effectiveness
ML1107504052011-03-21021 March 2011
Notice of Meeting with Entergy Operations, Inc., to Discuss Fleetwide Submittal for Proposed Technical Specification and Quality Assurance Program Manual Changes Related to Unit Staff Qualification Requirements
ML1029401582010-11-0505 November 2010
Acceptance of License Amendment Request for an Extended Power Uprate (Epu), Grand Gulf Nuclear Station, Unit 1
ML0914701272009-06-0303 June 2009
Memo to Michael T. Lesar from John Goshen Federal Register Notice Publishing an Environmental Assessment and Finding of No Significant Impact for a Request for an Exemption from 10 CFR 72.212(a)(2) and 10 CFR 72.212(b)(7)
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0614505922006-05-26026 May 2006
Wits 200600198 - Actions to Be Taken in Response to Hurricane Lessons Learned Task Report
ML0607302642006-03-0707 March 2006
Closure Memorandum: Issue for Resolution 2005-083: Evaluation: Part 21 - Engine Systems - Governor Drive Coupling Element
ML0516003452005-06-14014 June 2005
Draft Information Memo - May 6 - May 27, 2005
ML0506104872005-03-23023 March 2005
Draft Information Memo - May 1, 2005 Thru May 27, 2005
ML0429402412004-10-25025 October 2004
Draft Information for June 1, 2004 to June 30, 2004
ML0423804012004-08-27027 August 2004
Draft Information Memo for April 1, 2004 to April 30, 2004 - Marilyn R. Wohl
ML0422602762004-08-12012 August 2004
Meeting Summary of the August 8, 2004 Public Workshop - Region IV Operator Licensing Feedback
ML0408607972004-03-25025 March 2004
Memo to John Harris Re Correction of License Authority Files for Grand Gulf, Unit 1
ML0402202322004-02-23023 February 2004
Draft Information Report for October 3, 2003, to November 24, 2003
ML0330102972003-11-0707 November 2003
Draft Information for August 4, 2003, to October 2, 2003
ML0322601032003-08-18018 August 2003
Draft Information Inputs for June 3, 2003 to July 31, 2003
2023-03-21
[Table view]
Category:Code Relief or Alternative
MONTHYEARML23270B9932023-09-29029 September 2023
Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary
ML21294A0672021-10-28028 October 2021
Inservice Testing Program Relief Request VRR-GGNS-2021-1, Alternative Request for Pressure Isolation Valve Testing Frequency
ML21299A0032021-10-28028 October 2021
and Waterford Steam Electric Station, Unit 3 - Approval of Request for Alternative EN-20-RR-003 from Certain Requirements of the ASME Code
ML21258A4082021-09-21021 September 2021
Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of Boiling Water Reactor Vessel and Internals Project Guidelines
CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020
Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)
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
CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019
Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1
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
CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017
Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1
ML17285A7942017-10-30030 October 2017
Grand Gulf Nuclear Station, Unit 1 - Relief Request GG-ISI-021 Proposing An Alternative For Fourth Ten Year Inservice Inspection Program (CAC NO. MF9752; EPID L-2017-LLR-0031)
ML17235A5332017-08-31031 August 2017
Relief Request GG-ISI-022 to Allow Use of Later Editions and Addenda of American Society of Mechanical Engineers Code for Inservice Inspection
ML16160A0922016-06-16016 June 2016
Relief Request GG-IST-2015-1 Related to the Inservice Testing Program
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
CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015
Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division
ML14184A7822014-08-0101 August 2014
Relief Request GG-ISI-017, Alternative to Reactor Vessel Internal Structure Examination, Use of BWRVIP Guidelines, B13.10, Categories B-N-1 and B-N-2, Third 10-Year Inservice Inspection Interval
ML14148A2622014-06-30030 June 2014
Relief Request GG-ISI-017, Alternative to Reactor Vessel Internal Structure Examination, Use of BWRVIP Guidelines, Third 10 -Year Inservice Inspection Interval
ML12326A3312012-11-30030 November 2012
Relief Requests GG-ISI-014, GG-ISI-015, and GG-ISI-016, Pressure Retaining Welds in Control Rod Housings, Pumps and Valves, and Supports, 2nd 10-Year Inservice Inspection Interval
ML12214A3182012-08-17017 August 2012
Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval
ML1213804832012-05-22022 May 2012
Memo to File, Verbal Authorization of Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval
GNRO-2012/00040, Relief Request ISI-17 Repair Plan for Lsi Weld N06B-KB2012-05-0202 May 2012
Relief Request ISI-17 Repair Plan for Lsi Weld N06B-KB
ML1127103282011-11-0404 November 2011
Request for Alternative GG-ISI-013 from Examination Requirements for Reactor Pressure Vessel Weld Inspections for Third 10-Year Inservice Inspection Interval
GNRO-2011/00009, Request for Alternative GG-ISI-013 Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections2011-04-0606 April 2011
Request for Alternative GG-ISI-013 Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections
ML1005401832010-03-15015 March 2010
Relief Request to Use a Portion of a Later Edition of the ASME OM Code for Main Steam Safety Relief Valve Inservice Testing
2CAN011005, Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-7162010-01-28028 January 2010
Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
ML0906304692009-03-30030 March 2009
Request for Alternative CEP-CISI-001, Use Alternative Requirements in ASME Code Case N-739-1
ML0903708982009-03-0606 March 2009
Unit 3 - Request for Alternative CEP-ISI-012, Use Alternative Requirements in ASME Code Case N-753
CNRO-2009-00001, Relief Requests for Third 120 Month Inservice Inspection Interval2009-01-23023 January 2009
Relief Requests for Third 120 Month Inservice Inspection Interval
ML0816200052008-07-11011 July 2008
Relief Request VRR-GGNS-2007-01 and -02, Alternative Inservice Test Requirement, Extension to ASME OM Code 5-Year IST Interval for Main Steam Safety Relief Valve
ML0724300052007-09-21021 September 2007
Request for Alternative GG-ISI-002 - to Implement Risk-Informed Inservice Inspection Program Based on the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-716
ML0703004142007-02-13013 February 2007
Relief, Request for Alternative GG-ISI-003 to Extend the Current Inservice Inspection Interval
ML0701200812007-02-0202 February 2007
River Bend Station, & Waterford Steam Electric Station, Unit 3 - Request for Alternative CEP-PT-001, Visual Exam of Vent & Drain Leakage Tests (TAC MD1399, MD1400, MD1401, MD1402, & MD1403)
ML0522402612005-08-31031 August 2005
Request 1st-2005-1, Use of Subsequent American Society of Mechanical Engineers Operation and Maintenance Code Edition and Addenda for Condition Monitoring Check Valves
ML0435702742004-12-21021 December 2004
ANO Units 1 and 2; Grand Gulf; River Bend and Waterford Unit 3
ML0420304392004-07-21021 July 2004
Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code, Section XI, Inservice Testing Program
ML0323901902003-08-26026 August 2003
Ltr. to M.A. Krupa ANO-1, Grand Gulf River Bend Station & Waterford Steam Electric Station, Unit 3, Request to Use American Society of Mechanical Engineers Boiler & Pressure Vessel (Code) Case N-663
CNRO-2002-00059, Request for Use of Non-ASME Code Repair to Standby Service Water Piping in Accordance with NRC Generic Letter 90-052002-12-18018 December 2002
Request for Use of Non-ASME Code Repair to Standby Service Water Piping in Accordance with NRC Generic Letter 90-05
2023-09-29
[Table view] |
Text
May 22, 2012 MEMORANDUM TO: Docket File FROM: Alan B. Wang, Project Manager /RA/
Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
GRAND GULF NUCLEAR STATION, UNIT 1 - VERBAL AUTHORIZATION OF RELIEF REQUEST ISI-17, PROPOSED ALTERNATIVE REGARDING STRUCTURAL WELD OVERLAY (SWOL) ON THE N06-KB RESIDUAL HEAT REMOVAL SYSTEM/
LOW-PRESSURE COOLANT INJECTION C NOZZLE TO SAFE-END DISSIMILAR METAL WELD (TAC NO. ME8525)
By letter dated May 2, 2012, as supplemented by letter dated May 9, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML12124A245 and ML12131A408, respectively), Entergy Operations Inc. (Entergy, the licensee), submitted relief request (RR) ISI-17 for the Grand Gulf Nuclear Station, Unit 1 (GGNS) for U.S. Nuclear Regulatory Commission (NRC) review and approval.
The licensee submitted the RR under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(a)(3)(i). In this submittal, the licensee proposed an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, paragraphs IWA-4411 (a) and (b), IWA-4420 and IWA-4600(b), and associated linked and branching requirements. As part of its compliance with these requirements, the licensee proposed to implement the ASME Code,Section XI, Code Cases N-504-4, Alternate Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping, and N-638-4, Similar and Dissimilar Metal Welding using Ambient Temperature Machine GTAW [Gas Tungsten Arc Weld] Temper Bead Technique, as conditionally approved by the NRC. Under this RR, the licensee would perform a structural weld overlay (SWOL) using these ASME Code Cases on the N06-KB residual heat removal system (RHR)/low-pressure coolant injection (LPCI) C nozzle to safe-end dissimilar metal weld. The SWOL would be installed on the subject weld without removing the defect in the weld and the application of the SWOL is to arrest the growth of the existing defect while establishing a new structural pressure boundary. The licensee has made a regulatory commitment to provide a flaw evaluation as part of the technical basis to justify this repair and stated in its letter dated May 2, 2012, in part, that preservice and inservice inspection of the weld overlay will be performed to ensure structural integrity is maintained.
The licensee provided information to demonstrate that the proposed alternative would maintain an acceptable level of quality and safety under all licensing basis conditions of operation. The NRC staff has completed its review of the information provided in the licensees submittal for proposed alternative ISI-17 regarding the repair of RHR/LPCI C nozzle to safe-end dissimilar metal weld N06B-KB and concludes that the information provided by the licensee is consistent
with the provisions of 10 CFR 50.55a(a)(3)(i) and supports the granting of the proposed alternative to the ASME Code requirements.
Conclusion Pursuant to 10 CFR 50.55a(a)(3)(i), as of May 10, 2012, the NRC authorizes the licensee to implement the proposed alternative in accordance with the information provided in the licensees letter dated May 2, 2012, and supplemented by letter dated May 9, 2012. The authorization is immediately effective for the N06-KB RHR/LPCI C nozzle to safe-end dissimilar metal weld and will remain in effect for during the third inservice inspection interval of the GGNS.
All other ASME Code requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
The participants in the telephone call were:
NRC Michael Markley, Branch Chief, NRR/DORL/LPL4 Stacy Rosenberg, Branch Chief, NRR/DE/EVIB Ganesh Cheruvenki, NRR/DE/EVIB John Tsao, NRR/DE/EPNB Bob Hagar, RIV/DRP/RPB-C/
Wayne Sifre, RIV/DRS/EB-1/
Alan Wang, NRR/DORL/LPL4 Entergy Operations, Inc.
Steve Scott, Entergy Central Engineering Joe Weicks, Entergy Central Engineering Michael Briley, Entergy Central Engineering Ron Williams, Entergy Engineering Programs Jamie Gobell, Arkansas Nuclear One Project Management Dennis Wiles, GGNS Engineering Director William Simms, Entergy Services, Inc. Design Engineering Jeff Seiter, GGNS Licensing From Structural Integrity:
Moses Taylor Jr., P.E Anthony J. Giannizzi Docket No. 50-416
ML121380483 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DE/EVIB/BC NRR/LPL4/BC NRR/LPL4/PM NAME AWang JBurkhardt SRosenberg MMarkley AWang (LWilkins for)
-DATE 5/21/12 5/18/12 5/21/12 5/22/12 5/22/12
