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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 (GGNS) 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 ore-mail nathaniel.ferrer@nrc.gov. __-,____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 (GGNS) 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 ore-mail nathaniel.ferrer@nrc.gov. __-,____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 RAI NUREG-0831, "Safety Evaluation Related to the Operation of Grand Gulf Nuclear Station, Units 1 and 2," Section 9.5.1.1, "Water Supply System," dated September 1981, discussed the radwaste building water supply system. The staff notes that license renewal application (LRA) boundary drawing LRA-M-0035G, shows the radwaste building fire water system as not within the scope of license renewal. Verify whether the radwaste building fire water system is in the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an aging management review (AMR) in accordance with 10 CFR 54.21 (a)(1). If the system is excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion. RAI 2.3.3.12-2 The following LRA boundary drawing shows the following fire protection systems/components as not within the scope of license renewal: LRA Drawing Systems/Components Location Fire water suppression systems associated with LRA-M-0035L Emergency Safety Features Transformers, ESF11 H3 and ESF21 The staff requests that the applicant verify whether the fire protection systems/components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an AMR in accordance with 10 CFR 54.21 (a)(1). If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion. RAI 2.3.3.12-3 LRA Tables 2.3.3-12 and 3.3.2-12 do not include the following fire protection components: fire hose connections, and hose racks pipe supports, hangers, and couplings yard fire hydrants water sprinklers and hose standpipe floor drains for fire water fire water systems associated with standby gas treatment system charcoal filters and containment exhaust system charcoal filters fire water supply filter housings dikes and curbs for oil spill confinement ENCLOSURE   
 
-2 Verify whether the fire protection components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a} and whether they are subject to an AMR in accordance with 10 CFR 54.21 (a}(1). If they are excluded 'from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion. RAI 2.3.3.13-1 The following LRA boundary drawings show the following fire protection systems/components as not within the scope of license renewal: LRA Drawing Systems/Components Location LRA-M-0035E Pressure relief valves, piping, and components associated with carbon dioxide (C02) fire suppression system G3 LRA-M-0035F Halon 1301 fire suppression system in Division III Switchgear Room Emergency Remote Shutdown Panel Room OC405 C4 E4 G4 Division I Switchgear Room Control Cabinet Room A6 F6 Room OC 406 Room OC 705 88 Fa Verify whether the fire protection systems/components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a} and whether they are subject to an AMR in accordance with 10 CFR 54.21(a}(1}. If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion. RAI2.5-1 There has been operating experience regarding the failure of cable tie-wraps caused by the age related brittleness of the plastic material. These cable tie-wraps would be considered long-lived passive components depending on whether they have a credited design function. In LRA Section 2.5, the electrical commodity groups subject to aging management review are described. Explain how Grand Gulf manages the aging of cable tie-wraps if they are credited in the plant design basis. In addition, justify why the cable tie-wraps are not included within the scope of license renewal.
Requests for Additional Information cc w/encl: Listserv GRAND GULF NUCLEAR LICENSE RENEWAL REQUESTS FOR ADDITIONAL INFORMATION SET RAI NUREG-0831, "Safety Evaluation Related to the Operation of Grand Gulf Nuclear Station, Units 1 and 2," Section 9.5.1.1, "Water Supply System," dated September 1981, discussed the radwaste building water supply system. The staff notes that license renewal application (LRA) boundary drawing LRA-M-0035G, shows the radwaste building fire water system as not within the scope of license renewal. Verify whether the radwaste building fire water system is in the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an aging management review (AMR) in accordance with 10 CFR 54.21 (a)(1). If the system is excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION DISTRIBUTION: HARDCOPY: DLRRF E-MAIL: PUBLIC [or NON-PUBLIC, if applicable] RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource NFerrer DDrucker DWrona DMorey AWang RSmith, RIV BRice, RIV DMclntyre, OPA 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)  
RAI 2.3.3.12-2 The following LRA boundary drawing shows the following fire protection systems/components as not within the scope of license renewal: LRA Drawing Systems/Components Location Fire water suppression systems associated with LRA-M-0035L Emergency Safety Features Transformers, ESF11 H3 and ESF21 The staff requests that the applicant verify whether the fire protection systems/components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an AMR in accordance with 10 CFR 54.21 (a)(1). If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.
RAI 2.3.3.12-3 LRA Tables 2.3.3-12 and 3.3.2-12 do not include the following fire protection components: fire hose connections, and hose racks pipe supports, hangers, and couplings yard fire hydrants water sprinklers and hose standpipe floor drains for fire water fire water systems associated with standby gas treatment system charcoal filters and containment exhaust system charcoal filters fire water supply filter housings dikes and curbs for oil spill confinement ENCLOSURE   
-2 Verify whether the fire protection components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a} and whether they are subject to an AMR in accordance with 10 CFR 54.21 (a}(1). If they are excluded 'from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.
RAI 2.3.3.13-1 The following LRA boundary drawings show the following fire protection systems/components as not within the scope of license renewal: LRA Drawing Systems/Components Location LRA-M-0035E Pressure relief valves, piping, and components associated with carbon dioxide (C0 2) fire suppression system G3 LRA-M-0035F Halon 1301 fire suppression system in Division III Switchgear Room Emergency Remote Shutdown Panel Room OC405 C4 E4 G4 Division I Switchgear Room Control Cabinet Room A6 F6 Room OC 406 Room OC 705 88 Fa Verify whether the fire protection systems/components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a} and whether they are subject to an AMR in accordance with 10 CFR 54.21(a}(1}.
If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.
RAI2.5-1 There has been operating experience regarding the failure of cable tie-wraps caused by the age related brittleness of the plastic material.
These cable tie-wraps would be considered long-lived passive components depending on whether they have a credited design function.
In LRA Section 2.5, the electrical commodity groups subject to aging management review are described.
Explain how Grand Gulf manages the aging of cable tie-wraps if they are credited in the plant design basis. In addition, justify why the cable tie-wraps are not included within the scope of license renewal.
 
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARDCOPY:
DLRRF E-MAIL: PUBLIC [or NON-PUBLIC, if applicable]
RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource NFerrer DDrucker DWrona DMorey AWang RSmith, RIV BRice, RIV DMclntyre, OPA 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:==
==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 (GGNS) 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 ore-mail nathaniel.ferrer@nrc.gov. Sincerely, IRAJ 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 (GGNS) 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 ore-mail nathaniel.ferrer@nrc.gov.
Sincerely, IRAJ 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 following pages ADAMS Accession No 'ML 12139a055.. ,OFFICE ILA:RPB1 :DLR PM:RPB1:DLR BC:RPB1 :DLR PM: RPB1:DLR NAME YEdmonds NFerrer DMorey NFerrer DATE 05/23/12 05/29/12 05/30/12 05/30/12 OFFICIAL RECORD COpy
 
}}
Requests for Additional Information cc w/encl: Listserv DISTRIBUTION:
See following pages A D AMS Accession No 'ML 1213 9a055.. ,OFFICE ILA:RPB1 :DLR PM:RPB1:DLR BC:RPB1 :DLR PM: RPB1:DLR NAME YEdmonds NFerrer DMorey NFerrer DATE 05/23/12 05/29/12 05/30/12 05/30/12 OFFICIAL RECORD COpy}}

Revision as of 16:58, 28 July 2018

Grand Gulf LRA RAI Set 19
ML12139A055
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 05/29/2012
From: Ferrer N B
License Renewal Projects Branch 1
To: Mike Perito
Entergy Operations
Ferrer N B
References
TAC ME7493
Download: ML12139A055 (5)
v • d • e


Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 May 29,2012 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 (GGNS) 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 ore-mail nathaniel.ferrer@nrc.gov. __-,____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 RAI NUREG-0831, "Safety Evaluation Related to the Operation of Grand Gulf Nuclear Station, Units 1 and 2," Section 9.5.1.1, "Water Supply System," dated September 1981, discussed the radwaste building water supply system. The staff notes that license renewal application (LRA) boundary drawing LRA-M-0035G, shows the radwaste building fire water system as not within the scope of license renewal. Verify whether the radwaste building fire water system is in the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an aging management review (AMR) in accordance with 10 CFR 54.21 (a)(1). If the system is excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAI 2.3.3.12-2 The following LRA boundary drawing shows the following fire protection systems/components as not within the scope of license renewal: LRA Drawing Systems/Components Location Fire water suppression systems associated with LRA-M-0035L Emergency Safety Features Transformers, ESF11 H3 and ESF21 The staff requests that the applicant verify whether the fire protection systems/components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an AMR in accordance with 10 CFR 54.21 (a)(1). If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAI 2.3.3.12-3 LRA Tables 2.3.3-12 and 3.3.2-12 do not include the following fire protection components: fire hose connections, and hose racks pipe supports, hangers, and couplings yard fire hydrants water sprinklers and hose standpipe floor drains for fire water fire water systems associated with standby gas treatment system charcoal filters and containment exhaust system charcoal filters fire water supply filter housings dikes and curbs for oil spill confinement ENCLOSURE

-2 Verify whether the fire protection components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a} and whether they are subject to an AMR in accordance with 10 CFR 54.21 (a}(1). If they are excluded 'from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAI 2.3.3.13-1 The following LRA boundary drawings show the following fire protection systems/components as not within the scope of license renewal: LRA Drawing Systems/Components Location LRA-M-0035E Pressure relief valves, piping, and components associated with carbon dioxide (C0 2) fire suppression system G3 LRA-M-0035F Halon 1301 fire suppression system in Division III Switchgear Room Emergency Remote Shutdown Panel Room OC405 C4 E4 G4 Division I Switchgear Room Control Cabinet Room A6 F6 Room OC 406 Room OC 705 88 Fa Verify whether the fire protection systems/components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a} and whether they are subject to an AMR in accordance with 10 CFR 54.21(a}(1}.

If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAI2.5-1 There has been operating experience regarding the failure of cable tie-wraps caused by the age related brittleness of the plastic material.

These cable tie-wraps would be considered long-lived passive components depending on whether they have a credited design function.

In LRA Section 2.5, the electrical commodity groups subject to aging management review are described.

Explain how Grand Gulf manages the aging of cable tie-wraps if they are credited in the plant design basis. In addition, justify why the cable tie-wraps are not included within the scope of license renewal.

REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION DISTRIBUTION:

HARDCOPY:

DLRRF E-MAIL: PUBLIC [or NON-PUBLIC, if applicable]

RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource NFerrer DDrucker DWrona DMorey AWang RSmith, RIV BRice, RIV DMclntyre, OPA 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 (GGNS) 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 ore-mail nathaniel.ferrer@nrc.gov.

Sincerely, IRAJ 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 following pages A D AMS Accession No 'ML 1213 9a055.. ,OFFICE ILA:RPB1 :DLR PM:RPB1:DLR BC:RPB1 :DLR PM: RPB1:DLR NAME YEdmonds NFerrer DMorey NFerrer DATE 05/23/12 05/29/12 05/30/12 05/30/12 OFFICIAL RECORD COpy

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