ML091590022: Difference between revisions
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| issue date = 06/11/2009 | | issue date = 06/11/2009 | ||
| title = Summary of Teleconference Held on 5/27/09, Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification on Certain RAIs (RAI 3.3.2.2.3.3-1, RAI 3.3.2.2.7.3-1, and RAI 3.3.2.2.7.3-2), for Cooper License Renewal | | title = Summary of Teleconference Held on 5/27/09, Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification on Certain RAIs (RAI 3.3.2.2.3.3-1, RAI 3.3.2.2.7.3-1, and RAI 3.3.2.2.7.3-2), for Cooper License Renewal | ||
| author name = Tran T | | author name = Tran T | ||
| author affiliation = NRC/NRR/DLR/RPB1 | | author affiliation = NRC/NRR/DLR/RPB1 | ||
| addressee name = | | addressee name = |
Revision as of 22:52, 11 July 2019
ML091590022 | |
Person / Time | |
---|---|
Site: | Cooper ![]() |
Issue date: | 06/11/2009 |
From: | Tam Tran License Renewal Projects Branch 1 |
To: | Nebraska Public Power District (NPPD) |
tran t, NRR/RPB1, 415-3617 | |
References | |
Download: ML091590022 (4) | |
Text
June 11, 2009
LICENSEE: Nebraska Public Power District FACILITY: Cooper Nuclear Station
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 27, 2009, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND NEBRASKA PUBLIC POWER DISTRICT, RELATED TO A CLARIFICATION ON CERTAIN REQUESTS FOR ADDITIONAL INFORMATION (RAI 3.3.2.2.3.3-1, RAI 3.3.2.2.7.3-1, RAI 3.3.2.2.7.3-2), 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 May 27, 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 telephone 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
ML091590022 OFFICE PM:RPB1:DLR LA:DLR PM:RPB2:DLR BC:RPB1:DLR NAME TTran SFigueroa ESayoc (TTran for) DPelton (DAshley for) DATE 06/11/09 06/10/09 6/10/09 6/11/09 Memorandum to Nebraska Public Power District from Tam Tran dated June 11, 2009
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 27, 2009, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND NEBRASKA PUBLIC POWER DISTRICT, RELATED TO A CLARIFICATION ON CERTAIN REQUESTS FOR ADDITIONAL INFORMATION (RAI 3.3.2.2.3.3-1, RAI 3.3.2.2.7.3-1, RAI 3.3.2.2.7.3-2), FOR COOPER NUCLEAR STATION LICENSE RENEWAL DISTRIBUTION
- HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRer1 Resource RidsNrrDlrRer2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource ------------- T. Tran E. Sayoc F. Lyon 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) S. Burnell (RIV)
Cooper Nuclear Station cc: Mr. Ronald D. Asche President and Chief Executive Officer Nebraska Public Power District 1414 15th Street Columbus, NE 68601 Mr. Gene Mace Nuclear Asset Manager Nebraska Public Power District P.O. Box 98 Brownville, NE 68321 Mr. John C. McClure Vice President and General Counsel Nebraska Public Power District P.O. Box 499 Columbus, NE 68602-0499 Mr. David Van Der Kamp Licensing Manager Nebraska Public Power District P.O. Box 98 Brownville, NE 68321
Mr. Michael J. Linder, Director Nebraska Department of Environmental Quality P.O. Box 98922 Lincoln, NE 68509-8922
Chairman Nemaha County Board of Commissioners Nemaha County Courthouse 1824 N Street Auburn, NE 68305 Ms. Julie Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R&L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. H. Floyd Gilzow Deputy Director for Policy Missouri Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102-0176 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 218 Brownville, NE 68321 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 Director, Missouri State Emergency Management Agency P.O. Box 116 Jefferson City, MO 65102-0116 Chief, Radiation and Asbestos Control Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366
Ms. Melanie Rasmussen Radiation Control Program Director Bureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319 Mr. Keith G. Henke, Planner Division of Community and Public Health Office of Emergency Coordination 930 Wildwood P.O. Box 570 Jefferson City, MO 65102
Cooper Nuclear Station cc: Mr. Art Zaremba, Director of Nuclear Safety Assurance Nebraska Public Power District P.O. Box 98 Brownville, NE 68321 Mr. John F. McCann, Director Licensing, Entergy Nuclear Northeast Entergy Nuclear Operations, Inc. 440 Hamilton Avenue White Plains, NY 10601-1813 Mr. Stewart Minahan Vice President Nuclear and Chief Nuclear Officer Cooper Nuclear Station 72676 - 648A Avenue Brownville, NE 68321
Mr. Mike Boyce Cooper Strategic Initiatives Manager Cooper Nuclear Station 72676 - 648A Avenue Brownville, NE 68321
Mr. Dave Bremer License Renewal Project Manager Cooper Nuclear Station 72676 - 648A Avenue Brownville, NE 68321 Mr. Bill Victor License Renewal Project Licensing Lead Cooper Nuclear Station 72676 - 648A Avenue Brownville, NE 68321 Mr. Jim Loynes License Renewal Project Engineer Cooper Nuclear Station 72676 - 648A Avenue Brownville, NE 68321
ENCLOSURE 1 TELEPHONE CONFERENCE CALL COOPER NUCLEAR STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS May 27, 2009
PARTICIPANTS AFFILIATIONS Tam Tran U.S. Nuclear Regulatory Commission (NRC) Robert Sun NRC Dave Bremer Nebraska Public Power District (NPPD)
Jim Loynes NPPD Scott Freborg NPPD Dave Lach Entergy Alan Cox Entergy Don Fronabarger Entergy Andrew Taylor Entergy
ENCLOSURE 2 TELEPHONE CONFERENCE CALL COOPER NUCLEAR STATION LICENSE RENEWAL APPLICATION BRIEF DESCRIPTION May 27, 2009
The U.S. Nuclear Regulatory Commission (NRC) staff and representatives of Nebraska Public Power District held a telephone conference call on May 27, 2009, to discuss clarifications for certain draft requests for additional information listed below.
Discussion
- RAI 3.3.2.2.3.3-1 (Draft)
Background:
Section 3.3.2.2.3.3 "Cracking due to Stress Corrosion Cracking (SCC)" of the SRP-LR identifies SCC as an aging effect requiring management for stainless steel diesel engine exhaust piping, piping components, and piping elements exposed to diesel exhaust. The GALL report identifies this MEAP combination in item VII.H2-1. AMR item AP-33 in Table II.A of NUREG-1833, "Technical Bases for Revision to the License Renewal Guidance Documents," provides a basis for why it is important to identify SCC as an AERM for the internal surfaces of stainless steel emergency diesel generator exhaust piping that are exposed to diesel exhaust. Specifically, NUREG-1833 states that hot diesel engine exhaust may contain moisture and particulates which lead to SCC in stainless steel diesel exhaust components.
Issue: Contrary to the License Renewal Guidance identified above, the applicant states that stainless steel exhaust components are not subject to significant moisture accumulation that would allow cracking to occur. The staff disagrees with this approach, and takes the position that this must be identified as an AERM similar to the GALL item VII.H2-1.
Request: Please provide an AMP and AMR line item to manage the aging effect recommended by GALL VII.H2-1.
The applicant indicated understanding of this request for information and that similar items have been communicated to other applicant(s) previously, in earlier application(s) for other plant(s).
RAI 3.3.2.2.7.3-1 (Draft)
Background:
Section 3.3.2.2.7.3, "Loss of Material due to General, Pitting, and Crevice Corrosion" of the SRP-LR identifies loss of material as an aging effect requiring management for steel and stainless steel diesel exhaust piping, piping components, and piping elements exposed to diesel exhaust. The applicant has credited the plant specific AMP, B.1.31, Periodic Surveillance and Preventive Maintenance (PSPM) Program with managing this aging effect for emergency diesel generator exhaust piping, piping components, and piping elements.
Issue: The PSPM Program identifies the use of visual inspections performed on a "representative sample" of diesel generator exhaust gas components to manage the loss of material aging effect. The AMP indicates that sample size is determined using guidance from EPRI TR-107514, Age-Related Degradation Inspection Method and Demonstration, for a 90% confidence level that 90% of the population does not experience degradation. However, it is not clear what the population and sample size will be for the diesel generator system exhaust components. Additionally, the AMP indicates that "components with the same material-environment combinations at other facilities may be included in the sample." The inspection of components at other facilities would not necessarily offer an accurate representation of the aging effects at the current facility, and thus brings into question the extent of which this method will be used and the effect of its inclusion on the overall population and sample size.
Request: a) Please provide the total actual population and sample size of diesel generator exhaust gas components to manage the loss of material aging effect at Cooper Nuclear Station. b) Please clarify the use of "inspection of components at other facilities" as part of the representative sample for diesel generator exhaust gas components to manage the loss of material aging effect at Cooper Nuclear Station, and identify the specific impact this will have on the overall population and sample size.
The applicant indicated understanding of this request for information.
RAI 3.3.2.2.7.3-2 (Draft)
Background:
Section 3.3.2.2.7.3, "Loss of Material due to General, Pitting, and Crevice Corrosion" of the SRP-LR identifies loss of material as an aging effect requiring management for steel and stainless steel diesel exhaust piping, piping components, and piping elements exposed to diesel exhaust. The applicant has credited the plant specific AMP, B.1.16, Fire Protection Program with managing this aging effect for the diesel fire pump engine exhaust piping, piping components, and piping elements.
Issue: LRA AMP, B.1.16, Fire Protection Program states as an enhancement that the diesel fire pump engine carbon steel exhaust components are inspected for evidence of corrosion or cracking. However, the LRA is not clear whether the inspection will be an internal inspection or external only. An internal inspection is necessary to inspect for the aging effects caused by exhaust gas.
Request: Please clarify whether the inspection conducted by the Fire Protection Program includes the internal surface of the components.
The applicant indicated understanding of this request for information.