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==Dear Mr. Perito:==
==Dear Mr. Perito:==
By letter dated October 28, 2011, Entergy Operations, Inc., submitted an application pursuant to Title 10 of the Code ofFederal Regulations Part 54, to renew the operating license for Grand Gulf Nuclear Station, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information were discussed with Jeff Seiter, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1045 or bye-mail at nathanieIJerrer@nrc.gov. Sincerely. Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-416  
By letter dated October 28, 2011, Entergy Operations, Inc., submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Grand Gulf Nuclear Station, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information were discussed with Jeff Seiter, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1045 or bye-mail at nathanieIJerrer@nrc.gov.
Sincerely.
Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-416  


==Enclosure:==
==Enclosure:==
Requests for Additional Information cc w/encl: Listserv GRAND GULF NUCLEAR LICENSE RENEWAL REQUESTS FOR ADDITIONAL INFORMATION SET RAI4.2.4-1 The U.S. Nuclear Regulatory Commission (NRC or the staff) has identified an issue about Entergy Operations, Inc. (the applicant),s disposition of this time-limited aging analysis (TLAA) for the circumferential weld inspection relief. The Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) Section 4.2.3.1.4 states that if the applicant indicates that relief from circumferential weld examination will be made under 10 CFR 50.55a(a)(3), the applicant will manage this TLAA in accordance with 10 CFR 54.21 (c)(1 )(iii). In contrast, the applicant dispositioned this TLAA in accordance with 10 CFR 54.21 (c)(1)(ii), inconsistent with the SRP-LR. Explain why the TLAA for the circumferential weld inspection relief is dispositioned in accordance with 10 CFR 54.21 (c)(1)(ii). Alternatively, revise the TLAA disposition to be in accordance with 10 CFR 54.21 (c)(1)(iii). RAI B.1.11-2a The "detection of aging effects" program element of the Generic Aging Lessons Learned (GALL) Report aging management program (AMP) XLM9 states that portions of the susceptible components determined to be limiting will be inspected as part of the 10 year In-service Inspection (lSI) program during the period of extended operation. Furthermore, the sample size should be 100 percent of the accessible component population, excluding components that may be in compression during normal operations. However, during its audit, the staff found that the description of the enhancement to the applicant's Boiling Water Reactor (BWR) Vessels Internals AMP could be taken to be a sampling-based, condition monitoring program where 100 percent of the accessible and susceptible components would not be inspected. By letter dated June 27,2012, the staff issued request for additional information (RAI) B.1.11-2 requesting that the applicant provide more details so that the nature of the enhancement can be verified by a future license renewal audit In the applicant's July 25, 2012, response to RAI B.1.11-2, the applicant states: The enhancement stated in LRA Section B.1.11, BWR Vessel Internals, for the management of loss of fracture toughness due to neutron irradiation and thermal aging embrittlement is consistent with the guidance provided in NUREG-1801, Rev. 2, Section XLM9, BWR Vessel Internals. This guidance establishes the overall parameters of this aspect of the BWR Vessel Internals Program. Details of this aspect of the program remain to be determined, including: the specific scope of components susceptible to neutron irradiation and thermal aging embrittlement, the inspection techniques to be used, sequence of inspections to be conducted, and the methods for evaluating inspection results and extrapolating those results to inaccessible components. ENCLOSURE   
 
-These details will be developed as part of the implementation of the program enhancement described in LRA B.1.11. No revisions to UFSAR Supplement A.1.11 are warranted. Based on its review of the applicant's response, the staff needed additional information to find the applicant's program acceptable. The staff requests the applicant to address the following items: Provide a plant-specific description of the components made from the cast austenitic stainless steel (CASS), X-750 alloy, precipitation-hardened (PH) martensitic stainless steel, and martensitic stainless steel that are exposed to the reactor coolant and neutron flux environment. Describe if the sample size for the initial inspection of susceptible components will be 100 percent of the accessible components. If only portions of susceptible components will be inspected, provide justification. Revise part (b) of the enhancement, as necessary, making it consistent with the response. Clarify if the augmented inspections will be a one-time inspection or periodic. RAI 8.1.38-3a Background. In the GGNS response to RAI B.1.38-3 dated July 26,2012, the applicant stated that one dosimetry capsule was pulled at the end of the first operating cycle and the results from that capsule have been used in the fluence evaluations performed through operating cycle 13. Since GGNS has been approved to use the Instrument Surveillance Procedure (ISP) to meet the Appendix H requirements (November 4, 2003), no future withdrawals are planned. With input from the BWR Vessel and Internals Program (BWRVIP), the first cycle flux wire dosimetry results have been shown to be unreliable for reasonable end-of-license fluence projections. BWRVIP-86, Revision 1, Section 5, includes provisions for ongoing vessel dosimetry for plants that do not have dosimetry capsules tested. The dosimetry activities for the GGNS Reactor Vessel Surveillance Program are adequate, and therefore consistent with the GALL Report. Issue. The staff is concerned that the July 26, 2012, response is not complete. Request. Explain why the 1 st cycle flux wire dosimetry results are considered to be unreliable for reasonable end-of-license fluence projections.
Requests for Additional Information cc w/encl: Listserv GRAND GULF NUCLEAR LICENSE RENEWAL REQUESTS FOR ADDITIONAL INFORMATION SET RAI4.2.4-1 The U.S. Nuclear Regulatory Commission (NRC or the staff) has identified an issue about Entergy Operations, Inc. (the applicant),s disposition of this time-limited aging analysis (TLAA) for the circumferential weld inspection relief. The Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) Section 4.2.3.1.4 states that if the applicant indicates that relief from circumferential weld examination will be made under 10 CFR 50.55a(a)(3), the applicant will manage this TLAA in accordance with 10 CFR 54.21 (c)(1 )(iii). In contrast, the applicant dispositioned this TLAA in accordance with 10 CFR 54.21 (c)(1)(ii), inconsistent with the SRP-LR. Explain why the TLAA for the circumferential weld inspection relief is dispositioned in accordance with 10 CFR 54.21 (c)(1)(ii).
Alternatively, revise the TLAA disposition to be in accordance with 10 CFR 54.21 (c)(1)(iii).
RAI B.1.11-2a The "detection of aging effects" program element of the Generic Aging Lessons Learned (GALL) Report aging management program (AMP) XLM9 states that portions of the susceptible components determined to be limiting will be inspected as part of the 10 year In-service Inspection (lSI) program during the period of extended operation.
Furthermore, the sample size should be 100 percent of the accessible component population, excluding components that may be in compression during normal operations.
However, during its audit, the staff found that the description of the enhancement to the applicant's Boiling Water Reactor (BWR) Vessels Internals AMP could be taken to be a sampling-based, condition monitoring program where 100 percent of the accessible and susceptible components would not be inspected.
By letter dated June 27,2012, the staff issued request for additional information (RAI) B.1.11-2 requesting that the applicant provide more details so that the nature of the enhancement can be verified by a future license renewal audit In the applicant's July 25, 2012, response to RAI B.1.11-2, the applicant states: The enhancement stated in LRA Section B.1.11, BWR Vessel Internals, for the management of loss of fracture toughness due to neutron irradiation and thermal aging embrittlement is consistent with the guidance provided in NUREG-1801, Rev. 2, Section XLM9, BWR Vessel Internals.
This guidance establishes the overall parameters of this aspect of the BWR Vessel Internals Program. Details of this aspect of the program remain to be determined, including: the specific scope of components susceptible to neutron irradiation and thermal aging embrittlement, the inspection techniques to be used, sequence of inspections to be conducted, and the methods for evaluating inspection results and extrapolating those results to inaccessible components.
ENCLOSURE   
-These details will be developed as part of the implementation of the program enhancement described in LRA B.1.11. No revisions to UFSAR Supplement A.1.11 are warranted.
Based on its review of the applicant's response, the staff needed additional information to find the applicant's program acceptable.
The staff requests the applicant to address the following items: Provide a plant-specific description of the components made from the cast austenitic stainless steel (CASS), X-750 alloy, precipitation-hardened (PH) martensitic stainless steel, and martensitic stainless steel that are exposed to the reactor coolant and neutron flux environment. Describe if the sample size for the initial inspection of susceptible components will be 100 percent of the accessible components.
If only portions of susceptible components will be inspected, provide justification.
Revise part (b) of the enhancement, as necessary, making it consistent with the response. Clarify if the augmented inspections will be a one-time inspection or periodic.
RAI 8.1.38-3a Background.
In the GGNS response to RAI B.1.38-3 dated July 26,2012, the applicant stated that one dosimetry capsule was pulled at the end of the first operating cycle and the results from that capsule have been used in the fluence evaluations performed through operating cycle 13. Since GGNS has been approved to use the Instrument Surveillance Procedure (ISP) to meet the Appendix H requirements (November 4, 2003), no future withdrawals are planned. With input from the BWR Vessel and Internals Program (BWRVIP), the first cycle flux wire dosimetry results have been shown to be unreliable for reasonable end-of-license fluence projections.
BWRVIP-86, Revision 1, Section 5, includes provisions for ongoing vessel dosimetry for plants that do not have dosimetry capsules tested. The dosimetry activities for the GGNS Reactor Vessel Surveillance Program are adequate, and therefore consistent with the GALL Report. Issue. The staff is concerned that the July 26, 2012, response is not complete.
Request. Explain why the 1 st cycle flux wire dosimetry results are considered to be unreliable for reasonable end-of-license fluence projections.
October 17,2012 Mr. Michael Perito Vice President, Site Entergy Operations, Inc. P.O. Box Port Gibson, MS REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO. ME7493)  
October 17,2012 Mr. Michael Perito Vice President, Site Entergy Operations, Inc. P.O. Box Port Gibson, MS REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO. ME7493)  


==Dear Mr. Perito:==
==Dear Mr. Perito:==
By letter dated October 28, 2011, Entergy Operations, Inc., submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Grand Gulf Nuclear Station, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information were discussed with Jeff Seiter, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1045 or bye-mail at nathaniel.ferrer@nrc.gov. Sincerely, IRA! Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-416  
By letter dated October 28, 2011, Entergy Operations, Inc., submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Grand Gulf Nuclear Station, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information were discussed with Jeff Seiter, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1045 or bye-mail at nathaniel.ferrer@nrc.gov.
Sincerely, IRA! Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-416  


==Enclosure:==
==Enclosure:==
Requests for Additional Information cc w/encl: Listserv DISTRIBUTION: See next page ADAMS Accession No'.. ML *via email OFFICE PM:RPB1 :DLR LA:RPB2:DLR* BC:RPB1 :DLR PM: RPB1:DLR NAME NFerrer IKing DMorey NFerrer DATE 10/10/12 10104112 10110/12 10/17/12 OFFICIAL RECORD COpy Letter to M. Perito from N. Ferrer dated October 17,2012 REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION DISTRIBUTION: E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource NFerrer DDrucker DWrona DMorey AWang RSmith, RIV BRice, RIV GPick, RIV DMclntyre, OPA
 
}}
Requests for Additional Information cc w/encl: Listserv DISTRIBUTION:
See next page ADAMS Accession No'.. ML  
*via email OFFICE PM:RPB1 :DLR LA:RPB2:DLR*
BC:RPB1 :DLR PM: RPB1:DLR NAME NFerrer IKing DMorey NFerrer DATE 10/10/12 10104112 10110/12 10/17/12 OFFICIAL RECORD COpy Letter to M. Perito from N. Ferrer dated October 17,2012 REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION DISTRIBUTION:
E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource NFerrer DDrucker DWrona DMorey AWang RSmith, RIV BRice, RIV GPick, RIV DMclntyre, OPA}}

Revision as of 11:27, 24 July 2018

Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application (TAC No. ME7493)
ML12278A036
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 10/17/2012
From: Ferrer N B
License Renewal Projects Branch 1
To: Mike Perito
Entergy Operations
Ferrer N, 415-1045
References
TAC ME7493
Download: ML12278A036 (5)
v • d • e


Text

UNITED NUCLEAR REGULATORY WASHINGTON, O.C. 20555-0001 October 17, 2012 Mr. Michael Perito Vice President, Site Entergy Operations, Inc. P.O. Box 756 Port Gibson, MS 39150 REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO. ME7493)

Dear Mr. Perito:

By letter dated October 28, 2011, Entergy Operations, Inc., submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Grand Gulf Nuclear Station, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information were discussed with Jeff Seiter, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1045 or bye-mail at nathanieIJerrer@nrc.gov.

Sincerely.

Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-416

Enclosure:

Requests for Additional Information cc w/encl: Listserv GRAND GULF NUCLEAR LICENSE RENEWAL REQUESTS FOR ADDITIONAL INFORMATION SET RAI4.2.4-1 The U.S. Nuclear Regulatory Commission (NRC or the staff) has identified an issue about Entergy Operations, Inc. (the applicant),s disposition of this time-limited aging analysis (TLAA) for the circumferential weld inspection relief. The Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) Section 4.2.3.1.4 states that if the applicant indicates that relief from circumferential weld examination will be made under 10 CFR 50.55a(a)(3), the applicant will manage this TLAA in accordance with 10 CFR 54.21 (c)(1 )(iii). In contrast, the applicant dispositioned this TLAA in accordance with 10 CFR 54.21 (c)(1)(ii), inconsistent with the SRP-LR. Explain why the TLAA for the circumferential weld inspection relief is dispositioned in accordance with 10 CFR 54.21 (c)(1)(ii).

Alternatively, revise the TLAA disposition to be in accordance with 10 CFR 54.21 (c)(1)(iii).

RAI B.1.11-2a The "detection of aging effects" program element of the Generic Aging Lessons Learned (GALL) Report aging management program (AMP) XLM9 states that portions of the susceptible components determined to be limiting will be inspected as part of the 10 year In-service Inspection (lSI) program during the period of extended operation.

Furthermore, the sample size should be 100 percent of the accessible component population, excluding components that may be in compression during normal operations.

However, during its audit, the staff found that the description of the enhancement to the applicant's Boiling Water Reactor (BWR) Vessels Internals AMP could be taken to be a sampling-based, condition monitoring program where 100 percent of the accessible and susceptible components would not be inspected.

By letter dated June 27,2012, the staff issued request for additional information (RAI) B.1.11-2 requesting that the applicant provide more details so that the nature of the enhancement can be verified by a future license renewal audit In the applicant's July 25, 2012, response to RAI B.1.11-2, the applicant states: The enhancement stated in LRA Section B.1.11, BWR Vessel Internals, for the management of loss of fracture toughness due to neutron irradiation and thermal aging embrittlement is consistent with the guidance provided in NUREG-1801, Rev. 2, Section XLM9, BWR Vessel Internals.

This guidance establishes the overall parameters of this aspect of the BWR Vessel Internals Program. Details of this aspect of the program remain to be determined, including: the specific scope of components susceptible to neutron irradiation and thermal aging embrittlement, the inspection techniques to be used, sequence of inspections to be conducted, and the methods for evaluating inspection results and extrapolating those results to inaccessible components.

ENCLOSURE

-These details will be developed as part of the implementation of the program enhancement described in LRA B.1.11. No revisions to UFSAR Supplement A.1.11 are warranted.

Based on its review of the applicant's response, the staff needed additional information to find the applicant's program acceptable.

The staff requests the applicant to address the following items: Provide a plant-specific description of the components made from the cast austenitic stainless steel (CASS), X-750 alloy, precipitation-hardened (PH) martensitic stainless steel, and martensitic stainless steel that are exposed to the reactor coolant and neutron flux environment. Describe if the sample size for the initial inspection of susceptible components will be 100 percent of the accessible components.

If only portions of susceptible components will be inspected, provide justification.

Revise part (b) of the enhancement, as necessary, making it consistent with the response. Clarify if the augmented inspections will be a one-time inspection or periodic.

RAI 8.1.38-3a Background.

In the GGNS response to RAI B.1.38-3 dated July 26,2012, the applicant stated that one dosimetry capsule was pulled at the end of the first operating cycle and the results from that capsule have been used in the fluence evaluations performed through operating cycle 13. Since GGNS has been approved to use the Instrument Surveillance Procedure (ISP) to meet the Appendix H requirements (November 4, 2003), no future withdrawals are planned. With input from the BWR Vessel and Internals Program (BWRVIP), the first cycle flux wire dosimetry results have been shown to be unreliable for reasonable end-of-license fluence projections.

BWRVIP-86, Revision 1, Section 5, includes provisions for ongoing vessel dosimetry for plants that do not have dosimetry capsules tested. The dosimetry activities for the GGNS Reactor Vessel Surveillance Program are adequate, and therefore consistent with the GALL Report. Issue. The staff is concerned that the July 26, 2012, response is not complete.

Request. Explain why the 1 st cycle flux wire dosimetry results are considered to be unreliable for reasonable end-of-license fluence projections.

October 17,2012 Mr. Michael Perito Vice President, Site Entergy Operations, Inc. P.O. Box Port Gibson, MS REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO. ME7493)

Dear Mr. Perito:

By letter dated October 28, 2011, Entergy Operations, Inc., submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Grand Gulf Nuclear Station, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information were discussed with Jeff Seiter, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1045 or bye-mail at nathaniel.ferrer@nrc.gov.

Sincerely, IRA! Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-416

Enclosure:

Requests for Additional Information cc w/encl: Listserv DISTRIBUTION:

See next page ADAMS Accession No'.. ML

  • via email OFFICE PM:RPB1 :DLR LA:RPB2:DLR*

BC:RPB1 :DLR PM: RPB1:DLR NAME NFerrer IKing DMorey NFerrer DATE 10/10/12 10104112 10110/12 10/17/12 OFFICIAL RECORD COpy Letter to M. Perito from N. Ferrer dated October 17,2012 REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION DISTRIBUTION:

E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource NFerrer DDrucker DWrona DMorey AWang RSmith, RIV BRice, RIV GPick, RIV DMclntyre, OPA

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