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| {{#Wiki_filter:February 9, 2006Mr. Michael R. Kansler President Entergy Nuclear Operations, Inc. | | {{#Wiki_filter:February 9, 2006 Mr. Michael R. Kansler President Entergy Nuclear Operations, Inc. |
| 440 Hamilton Avenue White Plains, NY 10601 | | 440 Hamilton Avenue White Plains, NY 10601 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FORADDITIONAL INFORMATION REGARDING RELIEF REQUEST RR-39, IMPLEMENTATION OF BWRVIP GUIDELINES (TAC NO. MC8587) | | JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST RR-39, IMPLEMENTATION OF BWRVIP GUIDELINES (TAC NO. MC8587) |
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| ==Dear Mr. Kansler:== | | ==Dear Mr. Kansler:== |
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| On October 7, 2005, Entergy Nuclear Operations, Inc. (Entergy), submitted a relief request forthe James A. FitzPatrick Nuclear Power Plant which would implement various Boiling Water Reactor Vessel Internals Program (BWRVIP) guidelines in lieu of the American Society for Mechanical Engineers Boiler and Pressure Vessel Code inspection requirements on reactor vessel internals and components.The Nuclear Regulatory Commission staff is reviewing the submittal and has determined thatadditional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). On February 6, 2006, the Entergy staff indicated that a response to the RAI would be provided within 60 days. Please contact me at (301) 415-2901 if you have any questions on this issue.Sincerely,/RA/John P. Boska, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-333 | | On October 7, 2005, Entergy Nuclear Operations, Inc. (Entergy), submitted a relief request for the James A. FitzPatrick Nuclear Power Plant which would implement various Boiling Water Reactor Vessel Internals Program (BWRVIP) guidelines in lieu of the American Society for Mechanical Engineers Boiler and Pressure Vessel Code inspection requirements on reactor vessel internals and components. |
| | The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). On February 6, 2006, the Entergy staff indicated that a response to the RAI would be provided within 60 days. |
| | Please contact me at (301) 415-2901 if you have any questions on this issue. |
| | Sincerely, |
| | /RA/ |
| | John P. Boska, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333 |
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| ==Enclosure:== | | ==Enclosure:== |
| RAIcc w/encl: See next page
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| ML060390736 *see memo dated February 1, 2006OFFICELPL1-1/PMLPL1-1/LACVIB/BCLPL1-1/BCNAMEJBoskaSLittleMMitchell*RLauferDATE2/09/062/09/062/01/062/09/06 FitzPatrick Nuclear Power Plant cc:
| | RAI cc w/encl: See next page |
| Mr. Gary J. TaylorChief Executive Officer Entergy Operations, Inc.
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| 1340 Echelon Parkway Jackson, MS 39213Mr. John T. HerronSr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.
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| 440 Hamilton Avenue White Plains, NY 10601Mr. Theodore A. SullivanSite Vice President Entergy Nuclear Operations, Inc.
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| James A. FitzPatrick Nuclear Power Plant
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| P.O. Box 110 Lycoming, NY 13093Mr. Kevin J. MulliganGeneral Manager, Plant Operations Entergy Nuclear Operations, Inc. | | ML060390736 *see memo dated February 1, 2006 OFFICE LPL1-1/PM LPL1-1/LA CVIB/BC LPL1-1/BC NAME JBoska SLittle MMitchell* RLaufer DATE 2/09/06 2/09/06 2/01/06 2/09/06 FitzPatrick Nuclear Power Plant cc: |
| James A. FitzPatrick Nuclear Power Plant | | Mr. Gary J. Taylor Resident Inspector's Office Chief Executive Officer James A. FitzPatrick Nuclear Power Plant Entergy Operations, Inc. U. S. Nuclear Regulatory Commission 1340 Echelon Parkway P.O. Box 136 Jackson, MS 39213 Lycoming, NY 13093 Mr. John T. Herron Ms. Charlene D. Faison Sr. VP and Chief Operating Officer Manager, Licensing Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc. |
| | 440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Mr. Theodore A. Sullivan Mr. Michael J. Colomb Site Vice President Director of Oversight Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc. |
| | James A. FitzPatrick Nuclear Power Plant 440 Hamilton Avenue P.O. Box 110 White Plains, NY 10601 Lycoming, NY 13093 Mr. David Wallace Mr. Kevin J. Mulligan Director, Nuclear Safety Assurance General Manager, Plant Operations Entergy Nuclear Operations, Inc. |
| | Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant James A. FitzPatrick Nuclear Power Plant P.O. Box 110 P.O. Box 110 Lycoming, NY 13093 Lycoming, NY 13093 Mr. James Costedio Mr. Oscar Limpias Manager, Regulatory Compliance Vice President Engineering Entergy Nuclear Operations, Inc. |
| | Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant 440 Hamilton Avenue P.O. Box 110 White Plains, NY 10601 Lycoming, NY 13093 Mr. Christopher Schwarz Mr. Travis C. McCullough Vice President, Operations Support Assistant General Counsel Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc. |
| | 440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Mr. John F. McCann Mr. Charles Donaldson, Esquire Director, Licensing Assistant Attorney General Entergy Nuclear Operations, Inc. New York Department of Law 440 Hamilton Avenue 120 Broadway White Plains, NY 10601 New York, NY 10271 |
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| P.O. Box 110 Lycoming, NY 13093Mr. Oscar LimpiasVice President Engineering Entergy Nuclear Operations, Inc.
| | FitzPatrick Nuclear Power Plant cc: |
| 440 Hamilton Avenue White Plains, NY 10601Mr. Christopher SchwarzVice President, Operations Support Entergy Nuclear Operations, Inc.
| | Regional Administrator, Region I Ms. Stacey Lousteau U.S. Nuclear Regulatory Commission Treasury Department 475 Allendale Road Entergy Services, Inc. |
| 440 Hamilton Avenue White Plains, NY 10601Mr. John F. McCannDirector, Licensing Entergy Nuclear Operations, Inc.
| | King of Prussia, PA 19406 639 Loyola Avenue Mail Stop L-ENT-15E Oswego County Administrator New Orleans, LA 70113 Mr. Steven Lyman 46 East Bridge Street Oswego, NY 13126 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Dept. of Public Service 3 Empire State Plaza Albany, NY 12223-1350 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Mr. James H. Sniezek BWR SRC Consultant 5486 Nithsdale Drive Salisbury, MD 21801-2490 Mr. Michael D. Lyster BWR SRC Consultant 5931 Barclay Lane Naples, FL 34110-7306 |
| 440 Hamilton Avenue White Plains, NY 10601Resident Inspector's OfficeJames A. FitzPatrick Nuclear Power Plant U. S. Nuclear Regulatory Commission
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| P.O. Box 136 Lycoming, NY 13093Ms. Charlene D. FaisonManager, Licensing Entergy Nuclear Operations, Inc.
| | REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST RR-39 ENTERGY NUCLEAR OPERATIONS, INC. |
| 440 Hamilton Avenue White Plains, NY 10601Mr. Michael J. ColombDirector of Oversight Entergy Nuclear Operations, Inc.
| | JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 By letter dated October 7, 2005, Agencywide Documents Access and Management System accession number ML052900075, Entergy Nuclear Operations Inc. (Entergy or the licensee) submitted relief request RR-39 for the James A. FitzPatrick Nuclear Power Plant (JAFNPP). |
| 440 Hamilton Avenue White Plains, NY 10601Mr. David WallaceDirector, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
| | The licensee proposes to use Boiling Water Reactor Vessel Internal Program (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessl Code (ASME Code) for inservice inspection of Reactor Pressure Vessel (RPV) internal components. |
| James A. FitzPatrick Nuclear Power Plant
| | The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed relief request and would like additional information to clarify the submittal: |
| | : 1. According to Sections 3.3 and 3.4 of the BWRVIP-76, BWR Vessel and Internals Project, BWR Core Shroud and Flaw Evaluation Guidelines report, core shroud welds shall be inspected every 6 years when the enhanced visual test (EVT-1) method is used for one-sided weld inspections, and shall be inspected every 10 years when the subject welds are examined with the ultrasonic test (UT) method. The inspection frequency for the core shroud welds as indicated in Section 6.4 of the submittal is not consistent with the aforementioned requirement. Therefore, the NRC staff requests that the licensee revise the inspection frequency requirement for the subject welds in Section 6.4 of the submittal. |
| | : 2. In Attachment 2 of the submittal, the licensee provides a comparison of ASME Category B--1 and B--2 examination requirements with the BWRVIP guidelines. The NRC staff requests that the licensee include the following welds in this attachment. |
| | (A) ASME Item B13.30, Table IWB-2500-1, Shroud support welds H9 and H12. |
| | (B) ASME Item B13.40, Table IWB-2500-1, Shroud horizontal welds H1 and H2. |
| | (C) ASME Item B13.40, Table IWB-2500-1, Shroud H8 Attachment welds. |
| | : 3. According to Figure 3-3 of the BWRVIP-76 report, vertical and top guide ring segment welds shall be inspected every 6 years when the EVT-1 is used for one-sided weld inspections and shall be inspected every 10 years when the subject welds are examined with the UT method. In Attachment 2 of the submittal, the inspection frequency Enclosure |
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| P.O. Box 110 Lycoming, NY 13093Mr. James CostedioManager, Regulatory Compliance Entergy Nuclear Operations, Inc.
| | requirement for the vertical and top guide ring segment welds (Item B13.40 in Table IWB-2500-1 of the ASME Code, Section XI) is not consistent with the aforementioned requirement specified in the BWRVIP-76 report. Therefore, the NRC staff requests that the licensee revise the inspection frequency requirement for the subject welds in Attachment 2 of the submittal. |
| James A. FitzPatrick Nuclear Power Plant
| | : 4. In Attachment 2 of the submittal, the licensee indicates that the BWRVIP-38, BWR Vessel Internal Project, BWR Shroud Support Inspection and Flaw Evaluation Guidelines, report will be used for inspecting core shroud attachment welds. The staffs final safety evaluation (SE) of the BWRVIP-38 report indicates that when inspection tooling and methodologies are developed that allow the welds in the lower plenum to be accessible, the guidelines will state that the licensee will inspect these welds with the appropriate non-destructive examination methods in order to establish a baseline for these welds. One of the core shroud attachment welds that has limited accessibility in the lower plenum is the H12 weld. Therefore, the NRC staff requests that the licensee revise Attachment 2 to include a commitment that the shroud support weld-H12 be inspected when the inspection tooling and methodologies permit such an inspection. |
| | | : 5. In Attachment 4 of the submittal, the licensee does not address the inspection requirements for the following welds, and the NRC staff requests that the licensee include them in this attachment. |
| P.O. Box 110 Lycoming, NY 13093Mr. Travis C. McCulloughAssistant General Counsel Entergy Nuclear Operations, Inc.
| | Jet pumps riser welds-RS-4 and RS-5. |
| 440 Hamilton Avenue White Plains, NY 10601Mr. Charles Donaldson, EsquireAssistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 FitzPatrick Nuclear Power Plant cc:
| | : 6. In a letter dated October 1, 2003, the licensee submitted a similar relief request for the Vermont Yankee Nuclear Power Station (VYNPS). The NRC staff approved the VYNPS relief request by an SE dated September 19, 2005. In Table 1 of the VYNPS relief request, the licensee provided details of its inspection requirements for the reactor vessel internals (RVI) components and the corresponding inspection bases that were delineated in the respective BWRVIP reports. The NRC staff requests that the licensee provide similar inspection requirements and the inspection frequency for the JAFNPPs RVI components. This information will enable the NRC staff to perform an effective review of the BWRVIP inspection criteria that will be used by the licensee for the JAFNPPs RVI components.}} |
| Regional Administrator, Region IU.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406Oswego County Administrator Mr. Steven Lyman 46 East Bridge Street Oswego, NY 13126Mr. Peter R. Smith, PresidentNew York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399Mr. Paul EddyNew York State Dept. of Public Service 3 Empire State Plaza Albany, NY 12223-1350SupervisorTown of Scriba Route 8, Box 382 Oswego, NY 13126Mr. James H. SniezekBWR SRC Consultant 5486 Nithsdale Drive Salisbury, MD 21801-2490Mr. Michael D. LysterBWR SRC Consultant 5931 Barclay Lane Naples, FL 34110-7306Ms. Stacey LousteauTreasury Department Entergy Services, Inc.
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| 639 Loyola Avenue Mail Stop L-ENT-15E New Orleans, LA 70113 EnclosureREQUEST FOR ADDITIONAL INFORMATIONREGARDING RELIEF REQUEST RR-39ENTERGY NUCLEAR OPERATIONS, INC.JAMES A. FITZPATRICK NUCLEAR POWER PLANTDOCKET NO. 50-333By letter dated October 7, 2005, Agencywide Documents Access and Management Systemaccession number ML052900075, Entergy Nuclear Operations Inc. (Entergy or the licensee) submitted relief request RR-39 for the James A. FitzPatrick Nuclear Power Plant (JAFNPP).
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| The licensee proposes to use Boiling Water Reactor Vessel Internal Program (BWRVIP)guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessl Code (ASME Code) for inservice inspection of Reactor Pressure Vessel (RPV) internal components.The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licenseeprovided that supports the proposed relief request and would like additional information to clarify the submittal:1.According to Sections 3.3 and 3.4 of the BWRVIP-76, "BWR Vessel and InternalsProject, BWR Core Shroud and Flaw Evaluation Guidelines" report, core shroud welds shall be inspected every 6 years when the enhanced visual test (EVT-1) method is used for one-sided weld inspections, and shall be inspected every 10 years when the subject welds are examined with the ultrasonic test (UT) method. The inspection frequency for the core shroud welds as indicated in Section 6.4 of the submittal is not consistent withthe aforementioned requirement. Therefore, the NRC staff requests that the licenseerevise the inspection frequency requirement for the subject welds in Section 6.4 of the submittal.2.In Attachment 2 of the submittal, the licensee provides a comparison of ASME CategoryB--1 and B--2 examination requirements with the BWRVIP guidelines. The NRC staffrequests that the licensee include the following welds in this attachment.(A) ASME Item B13.30, Table IWB-2500-1, Shroud support welds H9 and H12.
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| (B) ASME Item B13.40, Table IWB-2500-1, Shroud horizontal welds H1 and H2.
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| (C) ASME Item B13.40, Table IWB-2500-1, Shroud H8 Attachment welds.3.According to Figure 3-3 of the BWRVIP-76 report, vertical and top guide ring segmentwelds shall be inspected every 6 years when the EVT-1 is used for one-sided weld inspections and shall be inspected every 10 years when the subject welds are examined with the UT method. In Attachment 2 of the submittal, the inspection frequency requirement for the vertical and top guide ring segment welds (Item B13.40 in TableIWB-2500-1 of the ASME Code, Section XI) is not consistent with the aforementionedrequirement specified in the BWRVIP-76 report. Therefore, the NRC staff requests thatthe licensee revise the inspection frequency requirement for the subject welds in of the submittal.4.In Attachment 2 of the submittal, the licensee indicates that the BWRVIP-38, "BWRVessel Internal Project, BWR Shroud Support Inspection and Flaw Evaluation Guidelines," report will be used for inspecting core shroud attachment welds. The staff'sfinal safety evaluation (SE) of the BWRVIP-38 report indicates that when inspection tooling and methodologies are developed that allow the welds in the lower plenum to beaccessible, the guidelines will state that the licensee will inspect these welds with the appropriate non-destructive examination methods in order to establish a baseline for these welds. One of the core shroud attachment welds that has limited accessibility inthe lower plenum is the H12 weld. Therefore, the NRC staff requests that the licenseerevise Attachment 2 to include a commitment that the shroud support weld-H12 be inspected when the inspection tooling and methodologies permit such an inspection. 5.In Attachment 4 of the submittal, the licensee does not address the inspectionrequirements for the following welds, and the NRC staff requests that the licenseeinclude them in this attachment. Jet pumps riser welds-RS-4 and RS-5.6.In a letter dated October 1, 2003, the licensee submitted a similar relief request for theVermont Yankee Nuclear Power Station (VYNPS). The NRC staff approved the VYNPSrelief request by an SE dated September 19, 2005. In Table 1 of the VYNPS relief request, the licensee provided details of its inspection requirements for the reactor vessel internals (RVI) components and the corresponding inspection bases that were delineated in the respective BWRVIP reports. The NRC staff requests that the licenseeprovide similar inspection requirements and the inspection frequency for the JAFNPP's RVI components. This information will enable the NRC staff to perform an effectivereview of the BWRVIP inspection criteria that will be used by the licensee for the JAFNPP's RVI components.}}
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Letter Sequence RAI |
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MONTHYEARJAFP-05-0151, Request for Approval of Relief Request No. RR-39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection2005-10-0707 October 2005
Request for Approval of Relief Request No. RR-39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection
Project stage: Request
ML0603907362006-02-0909 February 2006
Request for Additional Information Regarding Relief Request RR-39, Implementation of BWRVIP Guidelines
Project stage: RAI
JAFP-06-0059, Response to Request for Additional Information, Regarding Request for Approval of Relief Request No. 39, Section XI Code2006-04-0303 April 2006
Response to Request for Additional Information, Regarding Request for Approval of Relief Request No. 39, Section XI Code
Project stage: Response to RAI
JAFP-06-0085, Revision to Response for Additional Information Regarding Request for Approval of Relief Request No. 39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspect2006-05-31031 May 2006
Revision to Response for Additional Information Regarding Request for Approval of Relief Request No. 39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection
Project stage: Request
ML0622002262006-08-30030 August 2006
Relief Request No. RR-39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection
Project stage: Other
2006-04-03
[Table View] |
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Category:Letter
MONTHYEARIR 05000333/20230042024-02-0707 February 2024
Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001
ML24037A0102024-02-0606 February 2024
Requalification Program Inspection
ML24018A0012024-01-18018 January 2024
Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information
ML24004A2302024-01-0808 January 2024
Project Manager Reassignment
ML23356A0832024-01-0404 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23278A1292023-12-14014 December 2023
Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines
JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023
License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications
IR 05000333/20234012023-12-0808 December 2023
Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only)
RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023
Request for Exemption from 10 CFR 2.109(b)
JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023
Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements
JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023
and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023
Emergency Plan Document Revision
JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023
Registration of Spent Fuel Cask Use
IR 05000333/20230032023-11-13013 November 2023
Integrated Inspection Report 05000333/2023003
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
IR 05000333/20230102023-10-26026 October 2023
Biennial Problem Identification and Resolution Inspection Report 05000333/2023010
JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023
Registration of Spent Fuel Cask Use
IR 05000333/20233012023-10-19019 October 2023
Initial Operator Licensing Examination Report 05000333/2023301
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023
Physical Security Plan, Revision 24
JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023
Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis
IR 05000333/20230052023-08-31031 August 2023
Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005)
JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023
Correction to the 2022 Annual Radioactive Effluent Release Report
ML23228A1342023-08-16016 August 2023
Licensed Operator Positive Fitness-For-Duty Test
IR 05000333/20230022023-08-0707 August 2023
Integrated Inspection Report 05000333/2023002
RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023
Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor
JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023
License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis
JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023
10 CFR 50.46 Annual Report
JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023
License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance
ML23208A1622023-07-27027 July 2023
Operator Licensing Examination Approval
IR 05000333/20234022023-07-26026 July 2023
Security Baseline Inspection Report 05000333/2023402
IR 05000333/20230112023-07-25025 July 2023
Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011
IR 05000333/20235012023-07-20020 July 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501
JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023
License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation
IR 05000333/20234202023-06-26026 June 2023
Security Baseline Inspection Report 05000333 2023420
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
ML23164A0322023-06-13013 June 2023
Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000333/2023010
ML23152A0042023-06-0101 June 2023
Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000333/2023401
RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023
Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023
2022 Annual Radiological Environmental Operating Report
IR 05000333/20230012023-05-0303 May 2023
Integrated Inspection Report 05000333/2023001
ML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
ML23114A2522023-04-28028 April 2023
Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023
2022 Annual Radioactive Effluent Release Report
IR 05000333/20230122023-04-13013 April 2023
Quadrennial Fire Protection Inspection Report 05000333/2023012
ML23095A3722023-04-0505 April 2023
2023 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
IR 05000333/20220042023-03-20020 March 2023
Integrated Inspection Report 05000333/2022004
JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023
2022 REIRS Transmittal of NRC Form 5
ML23061A1632023-03-0303 March 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3
2024-02-07
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24024A1372024-01-24024 January 2024
NRR E-mail Capture - Final Snsb RAI Regarding FitzPatrick Amendment to Modify Safety Relief Valves Setpoint Lower Tolerance
ML24018A0012024-01-18018 January 2024
Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information
ML23264A7992023-09-21021 September 2023
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1
ML23164A0322023-06-13013 June 2023
Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000333/2023010
ML22321A0102022-11-17017 November 2022
Notification of Conduct of a Fire Protection Team Inspection
ML22124A2672022-05-0404 May 2022
Request for Additional Information for James A. FitzPatrick Nuclear Power Plant TSTF-505
ML22041B5362022-02-10010 February 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541
ML22020A0642022-01-13013 January 2022
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles
ML21256A1902021-09-10010 September 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21187A0522021-07-0606 July 2021
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2024-01-24
[Table view] |
Text
February 9, 2006 Mr. Michael R. Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST RR-39, IMPLEMENTATION OF BWRVIP GUIDELINES (TAC NO. MC8587)
Dear Mr. Kansler:
On October 7, 2005, Entergy Nuclear Operations, Inc. (Entergy), submitted a relief request for the James A. FitzPatrick Nuclear Power Plant which would implement various Boiling Water Reactor Vessel Internals Program (BWRVIP) guidelines in lieu of the American Society for Mechanical Engineers Boiler and Pressure Vessel Code inspection requirements on reactor vessel internals and components.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). On February 6, 2006, the Entergy staff indicated that a response to the RAI would be provided within 60 days.
Please contact me at (301) 415-2901 if you have any questions on this issue.
Sincerely,
/RA/
John P. Boska, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
RAI cc w/encl: See next page
ML060390736 *see memo dated February 1, 2006 OFFICE LPL1-1/PM LPL1-1/LA CVIB/BC LPL1-1/BC NAME JBoska SLittle MMitchell* RLaufer DATE 2/09/06 2/09/06 2/01/06 2/09/06 FitzPatrick Nuclear Power Plant cc:
Mr. Gary J. Taylor Resident Inspector's Office Chief Executive Officer James A. FitzPatrick Nuclear Power Plant Entergy Operations, Inc. U. S. Nuclear Regulatory Commission 1340 Echelon Parkway P.O. Box 136 Jackson, MS 39213 Lycoming, NY 13093 Mr. John T. Herron Ms. Charlene D. Faison Sr. VP and Chief Operating Officer Manager, Licensing Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Mr. Theodore A. Sullivan Mr. Michael J. Colomb Site Vice President Director of Oversight Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant 440 Hamilton Avenue P.O. Box 110 White Plains, NY 10601 Lycoming, NY 13093 Mr. David Wallace Mr. Kevin J. Mulligan Director, Nuclear Safety Assurance General Manager, Plant Operations Entergy Nuclear Operations, Inc.
Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant James A. FitzPatrick Nuclear Power Plant P.O. Box 110 P.O. Box 110 Lycoming, NY 13093 Lycoming, NY 13093 Mr. James Costedio Mr. Oscar Limpias Manager, Regulatory Compliance Vice President Engineering Entergy Nuclear Operations, Inc.
Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant 440 Hamilton Avenue P.O. Box 110 White Plains, NY 10601 Lycoming, NY 13093 Mr. Christopher Schwarz Mr. Travis C. McCullough Vice President, Operations Support Assistant General Counsel Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Mr. John F. McCann Mr. Charles Donaldson, Esquire Director, Licensing Assistant Attorney General Entergy Nuclear Operations, Inc. New York Department of Law 440 Hamilton Avenue 120 Broadway White Plains, NY 10601 New York, NY 10271
FitzPatrick Nuclear Power Plant cc:
Regional Administrator, Region I Ms. Stacey Lousteau U.S. Nuclear Regulatory Commission Treasury Department 475 Allendale Road Entergy Services, Inc.
King of Prussia, PA 19406 639 Loyola Avenue Mail Stop L-ENT-15E Oswego County Administrator New Orleans, LA 70113 Mr. Steven Lyman 46 East Bridge Street Oswego, NY 13126 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Dept. of Public Service 3 Empire State Plaza Albany, NY 12223-1350 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Mr. James H. Sniezek BWR SRC Consultant 5486 Nithsdale Drive Salisbury, MD 21801-2490 Mr. Michael D. Lyster BWR SRC Consultant 5931 Barclay Lane Naples, FL 34110-7306
REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST RR-39 ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 By letter dated October 7, 2005, Agencywide Documents Access and Management System accession number ML052900075, Entergy Nuclear Operations Inc. (Entergy or the licensee) submitted relief request RR-39 for the James A. FitzPatrick Nuclear Power Plant (JAFNPP).
The licensee proposes to use Boiling Water Reactor Vessel Internal Program (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessl Code (ASME Code) for inservice inspection of Reactor Pressure Vessel (RPV) internal components.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed relief request and would like additional information to clarify the submittal:
- 1. According to Sections 3.3 and 3.4 of the BWRVIP-76, BWR Vessel and Internals Project, BWR Core Shroud and Flaw Evaluation Guidelines report, core shroud welds shall be inspected every 6 years when the enhanced visual test (EVT-1) method is used for one-sided weld inspections, and shall be inspected every 10 years when the subject welds are examined with the ultrasonic test (UT) method. The inspection frequency for the core shroud welds as indicated in Section 6.4 of the submittal is not consistent with the aforementioned requirement. Therefore, the NRC staff requests that the licensee revise the inspection frequency requirement for the subject welds in Section 6.4 of the submittal.
- 2. In Attachment 2 of the submittal, the licensee provides a comparison of ASME Category B--1 and B--2 examination requirements with the BWRVIP guidelines. The NRC staff requests that the licensee include the following welds in this attachment.
(A) ASME Item B13.30, Table IWB-2500-1, Shroud support welds H9 and H12.
(B) ASME Item B13.40, Table IWB-2500-1, Shroud horizontal welds H1 and H2.
(C) ASME Item B13.40, Table IWB-2500-1, Shroud H8 Attachment welds.
- 3. According to Figure 3-3 of the BWRVIP-76 report, vertical and top guide ring segment welds shall be inspected every 6 years when the EVT-1 is used for one-sided weld inspections and shall be inspected every 10 years when the subject welds are examined with the UT method. In Attachment 2 of the submittal, the inspection frequency Enclosure
requirement for the vertical and top guide ring segment welds (Item B13.40 in Table IWB-2500-1 of the ASME Code,Section XI) is not consistent with the aforementioned requirement specified in the BWRVIP-76 report. Therefore, the NRC staff requests that the licensee revise the inspection frequency requirement for the subject welds in Attachment 2 of the submittal.
- 4. In Attachment 2 of the submittal, the licensee indicates that the BWRVIP-38, BWR Vessel Internal Project, BWR Shroud Support Inspection and Flaw Evaluation Guidelines, report will be used for inspecting core shroud attachment welds. The staffs final safety evaluation (SE) of the BWRVIP-38 report indicates that when inspection tooling and methodologies are developed that allow the welds in the lower plenum to be accessible, the guidelines will state that the licensee will inspect these welds with the appropriate non-destructive examination methods in order to establish a baseline for these welds. One of the core shroud attachment welds that has limited accessibility in the lower plenum is the H12 weld. Therefore, the NRC staff requests that the licensee revise Attachment 2 to include a commitment that the shroud support weld-H12 be inspected when the inspection tooling and methodologies permit such an inspection.
- 5. In Attachment 4 of the submittal, the licensee does not address the inspection requirements for the following welds, and the NRC staff requests that the licensee include them in this attachment.
Jet pumps riser welds-RS-4 and RS-5.
- 6. In a letter dated October 1, 2003, the licensee submitted a similar relief request for the Vermont Yankee Nuclear Power Station (VYNPS). The NRC staff approved the VYNPS relief request by an SE dated September 19, 2005. In Table 1 of the VYNPS relief request, the licensee provided details of its inspection requirements for the reactor vessel internals (RVI) components and the corresponding inspection bases that were delineated in the respective BWRVIP reports. The NRC staff requests that the licensee provide similar inspection requirements and the inspection frequency for the JAFNPPs RVI components. This information will enable the NRC staff to perform an effective review of the BWRVIP inspection criteria that will be used by the licensee for the JAFNPPs RVI components.
