ML101340462

03/04/10 Summary of Telephone Conference Call Held on Between NRC and PSEG Nuclear,Llc Concerning Draft Rei'S Pertaining to the Hope Creek Generating Station, License Renewal Application

ML101340462
Person / Time
Site:	Hope Creek
Issue date:	05/28/2010
From:	Bennett Brady License Renewal Projects Branch 1
To:	Office of Nuclear Reactor Regulation
Bennett Brady, DLR/NRR
References
Download: ML101340462 (9)

Text

May 28, 2010 LICENSEE: PSEG Nuclear, LLC FACILITY: Hope Creek Generating Station, Units 1 and 2

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MARCH 4, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PSEG NUCLEAR, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE HOPE CREEK GENERATING STATION, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PSEG Nuclear, LLC (the applicant), and Exelon held a telephone conference call on March 4, 2010, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Hope Creek Generating Station, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs D-RAIs. provides a listing of the participants and Enclosure 2 contains a listing of the D-RAIs discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

/RA/

Bennett M. Brady, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-354

Enclosures:

1. List of Participants

2. List of Draft Requests for Additional Information cc w/encls: See next page

ML101340462 OFFICE LA:DLR PM:RPB1:DLR BC:RPB1:DLR SFigueroa NAME BBrady BPham 5/ 17 /10 5/28/10 5/28/10 DATE

TELEPHONE CONFERENCE CALL HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS MARCH 4, 2010 PARTICIPANTS AFFILIATIONS Donnie Ashley U.S. Nuclear Regulatory Commission (NRC)

Raman Pichumani NRC Juan Uribe NRC George Seibold PSEG Nuclear, LLC (PSEG)

Jim Stavely PSEG Don Warfel Exelon John Hufnagel Exelon Enclosure 1

DRAFT REQUESTS FOR ADDITIONAL INFORMATION HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION MARCH 4, 2010 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PSEG Nuclear, LLC held a telephone conference call on March 4, 2010, to discuss and clarify the following draft requests for additional information (D-RAIs) concerning the Hope Creek Generating Station (HCGS), license renewal application (LRA).

D-RAI 2.4-1 Which components, if any, in the HCGS LRA Table 2.4.3 (Auxiliary Building Service / Radwaste Area) include the main steam tunnel structural elements? If these are omitted, please justify their omission.

Discussion: The applicant understands the question and stated that the elements have not been omitted and will provide the response.

D-RAI 2.4-2 HCGS LRA Section 2.4.4 (Component Supports Commodity Group) states that snubbers are also included in the boundary of this commodity group; however they are considered active components and are not subject to an aging management review (AMR), except for the end connections, which perform a passive function for structural support. This statement implies that the end connections are subject to an AMR. Identify in which category are these end connections included in the HCGS LRA Table 2.4.4.

Discussion: The applicant stated that the snubbers are included in the bolted connections section. The reviewer understands the response and agrees to withdraw the question and renumber the remaining questions.

D-RAI 2.4-3 Reinforced concrete isolation walls are included in the LRA Table 2.4.2 (Auxiliary Building Control/Diesel Generator Area); however, the isolation function is not listed as an intended function in any concrete component listed in the aforementioned table. Please clarify if this intended function is listed as a different function (shielding, structural support, etc) or justify its exclusion.

Discussion: The applicant understands the question. The question will be renumbered RAI 2.4-2.

Enclosure 2

D-RAI 2.4-4 Horizontal seismic restraints are shown in Figures 3.8.1 and 3.8.13 of the HCGS UFSAR for the Torus of the Primary Containment. These are not included in Table 2.4.7 of the HCGS LRA Section 2.4.7 (Primary Containment). Justify their exclusion.

Discussion: The applicant understands the question. The question will be renumbered RAI 2.4-3.

D-RAI 2.4-5 Please indicate where the structural elements that transfer the reactor pressure vessel (RPV) loads to the RPV ring girder and subsequently to the RPV pedestal (shown in Figure 3.8.1 in HCGS UFSAR) are evaluated in the HCGS LRA. If they have not been evaluated, please justify their exclusion.

Discussion: The applicant understands the question. The question will be renumbered RAI 2.4-4.

D-RAI 2.4-6 HCGS LRA Table 2.4.7 (Primary Containment) lists the torus ring girder as one of the components subject an AMR. But this table does not include the RPV ring girder, as shown in UFSAR Figure. 3.8.1. Please justify the omission of the latter.

Discussion: The applicant understands the question. The question will be renumbered RAI 2.4-5.

D-RAI 2.4-7 Based on a review of the HCGS LRA Sections 2.4.7 (Primary Containment) and 2.4.8 (Reactor Building) and of Tables 2.4-7 and 2.4.8, it is not clear if the following components have been included in the scope of license renewal and subject to an AMR:

a) Refueling seal assembly b) Weld pads on the drywell shell for attachment of pipe supports c) Water seal plates at the base of the drywell head, as shown in UFSAR Figure 3.8.1 d) Spent fuel pool liner plate leak chase system If these components are covered somewhere else in the LRA, please indicate the location. If they are excluded from the scope of license renewal, please provide the basis for their exclusion.

Discussion: The applicant understands the question. The question will be renumbered RAI 2.4-6.

D-RAI 2.4-8 UFSAR Figure 3.8-29 (Biological Shield Plan and Elevation) shows details of shear ties. Please identify the component in LRA Table 2.4.7, which includes these structural elements If these components are covered somewhere else in the LRA, please indicate the location. If they are excluded from the scope of license renewal, please provide the basis for their exclusion.

Discussion: The applicant understands the question. The question will be renumbered RAI 2.4-7.

Memorandum to PSEG Nuclear, LLC from B. Brady, dated May 28, 2010

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MARCH 4, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PSEG NUCLEAR, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE HOPE CREEK GENERATING STATION, LICENSE RENEWAL APPLICATION DISTRIBUTION:

HARD COPY:

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Hope Creek Generating Station cc:

Mr. Robert Braun Mr. Michael Gaffney Senior Vice President Nuclear Manager - Hope Creek Regulatory PSEG Nuclear LLC Assurance One Alloway Creek Neck Road PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Brian Booth Director Nuclear Oversight Mr. Ali Fakhar PSEG Nuclear Manager, License Renewal P.O. Box 236 PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. John Perry Station Vice President - Hope Creek Township Clerk PSEG Nuclear Lower Alloways Creek Township P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Larry Wagner Mr. Paul Bauldauf, P.E., Asst. Director Plant Manager - Hope Creek Radiation Protection Programs PSEG Nuclear LLC NJ Department of Environmental One Alloway Creek Neck Road Protection and Energy, CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. Michael Gallagher Mr. Brian Beam Vice President - License Renewal Projects Board of Public Utilities Exelon Nuclear LLC 2 Gateway Center, Tenth Floor 200 Exelon Way Newark, NJ 07102 Kennett Square, PA 19348 Regional Administrator, Region I Mr. Jeffrie J. Keenan, Esquire U.S. Nuclear Regulatory Commission Manager - Licensing 475 Allendale Road PSEG Nuclear LLC King of Prussia, PA 19406 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Paul Davison Vice President, Operations Support Mr. Gregory Sosson PSEG Nuclear LLC Director Corporate Engineering One Alloway Creek Neck Road PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038

Hope Creek Generating Station cc:

Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Senior Resident Inspector Hope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038