ML060390736: Difference between revisions
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| number = ML060390736 | | number = ML060390736 | ||
| issue date = 02/09/2006 | | issue date = 02/09/2006 | ||
| title = | | title = Request for Additional Information Regarding Relief Request RR-39, Implementation of BWRVIP Guidelines | ||
| author name = Boska J | | author name = Boska J | ||
| author affiliation = NRC/NRR/ADRO/DORL | | author affiliation = NRC/NRR/ADRO/DORL | ||
| addressee name = Kansler M | | addressee name = Kansler M | ||
| addressee affiliation = Entergy Nuclear Operations, Inc | | addressee affiliation = Entergy Nuclear Operations, Inc | ||
| docket = 05000333 | | docket = 05000333 | ||
| license number = DPR-059 | | license number = DPR-059 | ||
| contact person = Boska J | | contact person = Boska J, NRR, 301-415-2901 | ||
| case reference number = TAC MC8587 | | case reference number = TAC MC8587 | ||
| document type = Letter, Request for Additional Information (RAI) | | document type = Letter, Request for Additional Information (RAI) | ||
| Line 57: | Line 57: | ||
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. | 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. | ||
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). | 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). | ||
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. | 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. | ||
(B) ASME Item B13.40, Table IWB-2500-1, Shroud horizontal welds H1 and H2. | (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 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.}} | (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.}} | ||
Revision as of 00:43, 14 July 2019
| ML060390736 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/09/2006 |
| From: | Boska J Plant Licensing Branch III-2 |
| To: | Kansler M Entergy Nuclear Operations |
| Boska J, NRR, 301-415-2901 | |
| References | |
| TAC MC8587 | |
| Download: ML060390736 (6) | |
Text
February 9, 2006Mr. Michael R. Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FORADDITIONAL 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 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
Enclosure:
RAIcc w/encl: See next page
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:
Mr. Gary J. TaylorChief Executive Officer Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213Mr. John T. HerronSr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. Theodore A. SullivanSite Vice President Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant
P.O. Box 110 Lycoming, NY 13093Mr. Kevin J. MulliganGeneral Manager, Plant Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant
P.O. Box 110 Lycoming, NY 13093Mr. Oscar LimpiasVice President Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. Christopher SchwarzVice President, Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. John F. McCannDirector, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Resident Inspector's OfficeJames A. FitzPatrick Nuclear Power Plant U. S. Nuclear Regulatory Commission
P.O. Box 136 Lycoming, NY 13093Ms. Charlene D. FaisonManager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. Michael J. ColombDirector of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. David WallaceDirector, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant
P.O. Box 110 Lycoming, NY 13093Mr. James CostedioManager, Regulatory Compliance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant
P.O. Box 110 Lycoming, NY 13093Mr. Travis C. McCulloughAssistant General Counsel Entergy Nuclear Operations, Inc.
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:
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.
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).
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.
(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 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.