ML12271A471

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Summary of Telephone Conference Call Held on 09/07/12 Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc., Concerning Requests for Additional Information Pertaining to the Grand Gulf Nuclear Station, LRA
ML12271A471
Person / Time
Site: Grand Gulf 
(NPF-29)
Issue date: 01/03/2013
From: Ferrer N
Office of Nuclear Reactor Regulation
To:
Entergy Operations
Ferrer N, 415-1045
References
TAC ME7493
Download: ML12271A471 (5)


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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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January 3, 2013

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Entergy Operations, Inc.

FACILITY:

Grand Gulf Nuclear Station

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON SEPTEMBER 7, 2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY OPERATIONS, INC., CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION (TAC. NO. ME7493)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Operations, Inc., (Entergy) held a telephone conference call on September 7,2012, to discuss and clarify the staff's requests for additional information (RAls) concerning the Grand Gulf Nuclear Station, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's RAls. provides a listing of the participants and Enclosure 2 contains a listing of the RAls discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

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Nathaniel Ferrer, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos.50-275 and 50-323

Enclosures:

1. List of Participants
2. List of Requests for Additional Information cc w/encls: Listserv

TELEPHONE CONFERENCE CALL GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS September 7,2012 PARTICIPANTS AFFILIATIONS Nate Ferrer Ted Ivy U.S. Nuclear Regulatory Commission Entergy Operations, Inc.

ENCLOSURE 1

REQUESTS FOR ADDITIONAL INFORMATION (SET 35)

GRAND GULF NUCLEAR STATION LICENSE RENEWAL APPLICATION September 7, 2012 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Operations, Inc., held a telephone conference call on September 7,2012, to discuss and clarify the following requests for additional information (RAls) concerning the license renewal application (LRA)..

Draft RAI 3.5.2.1-2 Background. The Generic Aging Lessons Learned (GALL) Report recommends that Groups 7, 8 steel tank liners exposed to a fluid environment should be managed for loss of material due to pitting or crevice corrosion and cracking due to stress corrosion cracking (SCC) (e.g., GALL Report items III.A7.T-23 and III.A8-23). Standard Review Plan for License Renewal (SRP-LR)

Table 3.5-1, item 52, recommends a plant-specific aging management program (AMP) to manage for this aging effect.

Issue. LRA Tables 3.5.2-1,3.5.2-2 and 3.5.2-3 state that the containment building reactor pressure vessel (RPV) pedestal stainless steel sump liners and penetrations; water control structures basin debris stainless steel screen and grating, stainless steel cooling tower fill, and fan stack stainless steel grating; and turbine building, process facilities, and yard structures stainless steel sump liners exposed to a fluid environment will be managed for loss of material due to pitting or crevice corrosion by the applicant's Structures Monitoring Program. The staff noted that use of the Structures Monitoring Program is acceptable for managing the aging effect of loss of material due to pitting or crevice corrosion for these components because loss of material will be managed through visual inspections conducted by qualified personnel at intervals not to exceed five years in accordance with recommendations in NEI 96-03, ANSI/ASCE 11-99, and ACI 349.3R-02. However, it is not clear to the staff how cracking due to stress corrosion cracking will be managed to meet the recommendations of GALL Report items IILA7.T-23 and III.A8-23.

Request. Explain how cracking due to stress corrosion cracking of these components will be managed to meet the recommendations of GALL Report items IILA7.T-23 and IILA8-23.

Discussion: The applicant stated that the referenced items point to LRA Table 3.5.1, item 52, which in turn refers to LRA Section 3.5.2.2.2.4, which explains that the temperature of the affected components is below the temperature threshold for SCC. The staff confirmed that this information is available in the LRA and will not issue this question as a formal RAI.

ENCLOSURE 2

ML12271A471

  • concurred via email PM:RPB1 :DLR LA:RPB1 :DLR BC:RPB1 :DLR PM:RPB1 :DLR NFerrer YEdmonds DMorey NFerrer 12/4/12 10/18/12 12/26/12 113/13

Memo to Entergy Nuclear, Inc, from Nathaniel Ferrer dated January 3, 2013

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON SEPTEMBER 7, 2012 BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY OPERATIONS, INC., CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE GRAND GULF NUCLEAR STATION, LICENSE RENEWAL APPLICATION (TAC. NO. ME7493)

DISTRIBUTION:

E-MAIL:

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