ML092030305

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Summary of Telephone Conference Call Held on 7/9/2009, Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Requests for Additional Information, for Cooper Nuclear Station License Renewal
ML092030305
Person / Time
Site: Cooper Entergy icon.png
Issue date: 07/29/2009
From: Tam Tran
License Renewal Projects Branch 1
To:
Nebraska Public Power District (NPPD)
tran t, NRR/DLR/RPB1, 415-3617
References
Download: ML092030305 (8)


Text

July 29, 2009 LICENSEE: Nebraska Public Power District FACILITY: Cooper Nuclear Station Power Plant

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON JULY 9, 2009, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND NEBRASKA PUBLIC POWER DISTRICT, RELATED TO A CLARIFICATION FOR CERTAIN REQUESTS FOR ADDITIONAL INFORMATION, FOR COOPER NUCLEAR STATION LICENSE RENEWAL The U.S. Nuclear Regulatory Commission staff and representatives of Nebraska Public Power District held a telephone conference call on July 9, 2009, to discuss clarifications for certain draft requests for additional information for Cooper Nuclear Station license renewal. provides a listing of the participants, and Enclosure 2 contains a brief description of the conference call.

The applicant had an opportunity to comment on this summary.

/RA/

Tam Tran, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-298

Enclosures:

As stated cc w/encls: See next page

ML092030305 OFFICE LA:DLR PM:RPB1:DLR PM:RPB2:DLR BC:RPB1:DLR PM:RPB1:DLR NAME S. Figueroa T. Tran E. Sayoc D. Pelton T. Tran (Signature)

DATE 07/27/09 07/29/09 07/29/09 07/29/09 07/29/09

Memorandum to Nebraska Public Power District from Tam Tran dated July 29, 2009

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON JULY 9, 2009, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND NEBRASKA PUBLIC POWER DISTRICT, RELATED TO A CLARIFICATION FOR CERTAIN REQUESTS FOR ADDITIONAL INFORMATION, FOR COOPER NUCLEAR STATION LICENSE RENEWAL DISTRIBUTION:

HARD COPY:

DLR RF E-MAIL:

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T. Tran E. Sayoc B. Brady F. Lyon I.Couret D. Roth (OGC)

A. Jones (OGC)

N. Taylor (RIV)

E. Collins (RIV)

C. Casto (RIV)

B. Maier (RIV)

V. Dricks (RIV)

D. Chamberlain (RIV)

A. Vegel (RIV)

W. Walker (RIV)

G. Miller (RIV)

G. Pick (RIV)

Cooper Nuclear Station cc:

Mr. Ronald D. Asche Deputy Director for Policy President and Chief Executive Officer Missouri Department of Natural Resources Nebraska Public Power District P.O. Box 176 1414 15th Street Jefferson City, MO 65102-0176 Columbus, NE 68601 Senior Resident Inspector Mr. Gene Mace U.S. Nuclear Regulatory Commission Nuclear Asset Manager P.O. Box 218 Nebraska Public Power District Brownville, NE 68321 P.O. Box 98 Brownville, NE 68321 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Mr. John C. McClure 612 E. Lamar Blvd., Suite 400 Vice President and General Counsel Arlington, TX 76011-4125 Nebraska Public Power District P.O. Box 499 Director, Missouri State Emergency Columbus, NE 68602-0499 Management Agency P.O. Box 116 Mr. David Van Der Kamp Jefferson City, MO 65102-0116 Licensing Manager Nebraska Public Power District Chief, Radiation and Asbestos P.O. Box 98 Control Section Brownville, NE 68321 Kansas Department of Health and Environment Mr. Michael J. Linder, Director Bureau of Air and Radiation Nebraska Department of Environmental 1000 SW Jackson, Suite 310 Quality Topeka, KS 66612-1366 P.O. Box 98922 Lincoln, NE 68509-8922 Ms. Melanie Rasmussen Radiation Control Program Director Chairman Bureau of Radiological Health Nemaha County Board of Commissioners Iowa Department of Public Health Nemaha County Courthouse Lucas State Office Building, 5th Floor 1824 N Street 321 East 12th Street Auburn, NE 68305 Des Moines, IA 50319 Ms. Julia Schmitt, Manager Mr. Keith G. Henke, Planner Radiation Control Program Division of Community and Public Health Nebraska Health & Human Services R&L Office of Emergency Coordination Public Health Assurance 930 Wildwood Drive 301 Centennial Mall, South P.O. Box 570 P.O. Box 95007 Jefferson City, MO 65102 Lincoln, NE 68509-5007

Cooper Nuclear Station cc:

Mr. Art Zaremba, Director of Nuclear Mr. Jim Loynes Safety Assurance License Renewal Project Engineer Nebraska Public Power District Cooper Nuclear Station P.O. Box 98 72676 - 648A Avenue Brownville, NE 68321 Brownville, NE 68321 Mr. John F. McCann, Director Mr. Garry Young Licensing, Entergy Nuclear Northeast License Renewal Manager Entergy Nuclear Operations, Inc. Entergy Nuclear 440 Hamilton Avenue 1448 S.R. 333, N-GSB-45 White Plains, NY 10601-1813 Russellville, AK 72802 Mr. Mike Boyce Mr. Alan Cox Cooper Strategic Initiatives Manager License Renewal Technical Manager Cooper Nuclear Station Entergy Nuclear 72676 - 648A Avenue 1448 S.R. 333, N-GSB-45 Brownville, NE 68321 Russellville, AK 72802 Mr. Dave Bremer Mr. Dave Lach License Renewal Project Manager LRP Entergy Project Manager Cooper Nuclear Station Entergy Nuclear 72676 - 648A Avenue 1448 S.R. 333, N-GSB-45 Brownville, NE 68321 Russellville, AK 72802 Mr. Bill Victor Mr. Stewart B. Minahan License Renewal Project Licensing Lead Vice President Cooper Nuclear Station Nuclear and Chief Nuclear Officer 72676 - 648A Avenue Cooper Nuclear Station Brownville, NE 68321 72676 - 648A Avenue Brownville, NE 68321

LIST OF PARTICIPANTS TELEPHONE CONFERENCE CALL FOR COOPER NUCLEAR STATION LICENSE RENEWAL APPLICATION July 9, 2009 PARTICIPANTS AFFILIATIONS Tam Tran U.S. Nuclear Regulatory Commission (NRC)

S. Min NRC D. Diercks Argonne National Laboratory Dave Bremer Nebraska Public Power District (NPPD)

Jim Loynes NPPD Ken Thomas NPPD Dave Lach Entergy Nuclear Operations, Inc. (Entergy)

Ted Ivy Entergy Andy Taylor Entergy Alan Cox Entergy Jacque Lingenfelter Entergy ENCLOSURE 1

COOPER NUCLEAR STATION POWER PLANT LICENSE RENEWAL APPLICATION (Brief description of the conference call)

The U.S. Nuclear Regulatory Commission (NRC) staff and representatives of Nebraska Public Power District, held a telephone conference call on July 9, 2009, to discuss clarifications for certain draft requests for additional information (RAI) listed below.

A. Clarification on draft RAI RAI B.1.40-4 (Draft)

Background

License Renewal Application (LRA) Section B.1.40 states the chemistry activities for this program are based on Electric Power Research Institute (EPRI) TR-1007820, Closed Cycle Cooling Water Chemistry, Revision 1, dated April 2004, which supersedes EPRI TR-107396, Closed Cycle Cooling Water Chemistry Guideline, Revision 0, issued November 1997.

Generic Aging Lessons Learned (GALL) Aging Management Program (AMP) XI.M21, Closed-Cycle Cooling Water System, states that it relies on maintenance of system corrosion inhibitor concentrations within the specified limits of EPRI TR-107396 to minimize corrosion and stress-corrosion cracking.

Issue The GALL Report does not recommend the use of late revisions of EPRI TR-107396. The applicants program is implemented using the later revision, EPRI TR-1007820, rather than the edition referenced in the GALL Report, EPRI TR-107396. The staff noted the use of EPRI TR-1007820 may potentially impact the program elements, Preventative Actions and Acceptance Criteria of the applicants program, since the corresponding program elements in the GALL Report reference the limits on corrosion inhibitor concentrations specified in EPRI TR-107396.

Request Justify this deviation from the GALL Report and discuss its impact on the program elements, Preventative Actions and Acceptance Criteria, with reference to limits on specific corrosion inhibitor levels, monitoring frequencies, and operating parameters.

The applicant indicated understanding of this RAI.

B. Clarification on response to RAI RAI 3.3.1-1 Regarding RAI 3.3.1-1, which was issued to the applicant on May 1, 2009 (ML091240344) and responded by the applicant on June 15, 2009 (ML091690050), the staff asked for further clarification on the implementation of the criteria for discontinuation of the reactor water cleanup system outboard piping inspections. The staff requested the following clarifications and associated available documentation:

(1) For the inboard piping and piping welds, please clarify on the inter-granular stress corrosion cracking (IGSCC) resistant materials used.

ENCLOSURE 2

(2) Has IGSCC been detected after the foregoing inboard piping replacement?

(3) For the outboard piping (reference: letter from G.A. Trevors to the NRC, Generic Letter 88-01, Cooper Nuclear Station, October 9, 1990), what examination method was used to detect the flaw? What is the technical basis that justifies that the flaw is not IGSCC?

The applicant provided the following clarifications:

(1) The piping material was SS 316NG, which is an IGSCC-resistant material. The weld material was SS 308L with a minimum of 5 FN and max of 10FN to control delta ferrite, and the heat input was controlled. In addition, the welds received induction heating stress improvement to reduce the residual stress. The combination of the weld material and IHSI meets the requirements of NUREG 0313 Rev 1 and GL 88-01 to be qualified for providing resistance to IGSCC in new or replacement boiling water reactor piping welds.

(2) No, IGSCC was not detected from the inboard piping after the replacement. The determinations were provided by qualified examiner(s).

(3) The applicant agreed to take action to recover detailed examination information to confirm the nature of the flaw-defection from 1990 inspection to support closing of the third question. This will be provided in a subsequent response to RAI letter as supplemental information to RAI 3.3.1-1.