ML092650057: Difference between revisions
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| issue date = 09/28/2009 | | issue date = 09/28/2009 | ||
| title = Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application | | title = Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application | ||
| author name = Tran T | | author name = Tran T | ||
| author affiliation = NRC/NRR/DLR/RPB1 | | author affiliation = NRC/NRR/DLR/RPB1 | ||
| addressee name = Minahan S | | addressee name = Minahan S | ||
| addressee affiliation = Nebraska Public Power District (NPPD) | | addressee affiliation = Nebraska Public Power District (NPPD) | ||
| docket = 05000298 | | docket = 05000298 | ||
| Line 134: | Line 134: | ||
the licensee stated that enhancements will be made to the cont ainment ISI Progr am to inspect surfaces for signs of distress, there needs to be adequate assurance that there is proper maintenance of the protective coatings in containment, such that they will not degrade and become a debris source that may challenge the emergency core cooling system's performance. | the licensee stated that enhancements will be made to the cont ainment ISI Progr am to inspect surfaces for signs of distress, there needs to be adequate assurance that there is proper maintenance of the protective coatings in containment, such that they will not degrade and become a debris source that may challenge the emergency core cooling system's performance. | ||
Request 1. On page B-10 of the LRA (Agencywide Documents Access Management System Accession No. ML083030227), line item XI.S8 states that the NUREG-1801 program is not credited for aging management. The containment ISI Program manages the effect of aging on the drywell shell. Please discuss how the containment ISI Program meets the recommendations of NUREG-1801 X1.S8 in managing the effects of aging at CNS. | Request 1. On page B-10 of the LRA (Agencywide Documents Access Management System Accession No. ML083030227), line item XI.S8 states that the NUREG-1801 program is not credited for aging management. The containment ISI Program manages the effect of aging on the drywell shell. Please discuss how the containment ISI Program meets the recommendations of NUREG-1801 X1.S8 in managing the effects of aging at CNS. | ||
: 2. Please describe, in detail, the CNS service level 1 coatings program. | : 2. Please describe, in detail, the CNS service level 1 coatings program. | ||
: a. Please describe how the program will ensur e that there will be proper maintenance of the protective coatings insi de the containment, such that they will not become a debris source that could impact the operability of post-accident safety systems that rely on water recycled through the containment sump or drain system in the extended period of operation. b. Please describe the frequency and scope of the inspections, acceptance criteria, and the qualification of personnel who perform containment coatings inspections.}} | : a. Please describe how the program will ensur e that there will be proper maintenance of the protective coatings insi de the containment, such that they will not become a debris source that could impact the operability of post-accident safety systems that rely on water recycled through the containment sump or drain system in the extended period of operation. b. Please describe the frequency and scope of the inspections, acceptance criteria, and the qualification of personnel who perform containment coatings inspections.}} | ||
Revision as of 17:59, 11 July 2019
| ML092650057 | |
| Person / Time | |
|---|---|
| Site: | Cooper |
| Issue date: | 09/28/2009 |
| From: | Tam Tran License Renewal Projects Branch 1 |
| To: | Minahan S Nebraska Public Power District (NPPD) |
| tran t, NRR/DLR/RPB1, 415-3617 | |
| References | |
| TAC MD9737, TAC MD9763 | |
| Download: ML092650057 (4) | |
Text
September 28, 2009
Mr. Stewart B. Minahan Vice President - Nuclear and Chief Nuclear Officer Cooper Nuclear Station 72676 - 648A Avenue Brownville, NE 68321
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE COOPER NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO.
MD9763 AND MD9737)
Dear Mr. Minahan:
The purpose of this letter is to transmit the request for additional information B.1.10-5. The staff has identified, in the enclosure, areas where this additional information is needed to complete the review of the Cooper Nuclear Station license renewal application. We request that you provide your response to these questions within 30 days of the date of this letter in order to maintain the license review schedule.
This item in the enclosure was discussed with Mr. David Bremer. If you have any questions, please contact Ms. Bennett M. Brady at 301-415-2981 or by e-mail at Bennett.Brady@nrc.gov , or Mr. Tam Tran at 301-415-3617 or by e-mail at Tam.Tran@nrc.gov. Sincerely, /RA/
Tam Tran, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation
Docket No. 50-298
Enclosure:
As stated
cc w/encl: See next page
ML092650057 OFFICE LA:DLR PM:DLR:RPB1 PM:DLR:RPB1 BC:DLR:RPB1 PM:DLR:RPB1
NAME IKing BBrady TTran DPelton TTran (Signature) DATE 09/23/09 09/28/09 09/28/09 09/28/09 09/28/09 Letter to Stewart B. Minahan from Tam Tran dated September 28, 2009
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE COOPER NUCLEAR STATION LICENSE RENEWAL APPLICATION (TAC NO.
MD9763 AND MD9737)
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 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 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. Julia Sc hmitt, 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
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 Drive 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. 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
Mr. Garry Young License Renewal Manager Entergy Nuclear 1448 S.R. 333, N-GSB-45 Russellville, AR 72802
Mr. Alan Cox License Renewal Technical Manager Entergy Nuclear 1448 S.R. 333, N-GSB-45 Russellville, AR 72802
Mr. Dave Lach LRP Entergy Project Manager Entergy Nuclear 1448 S.R. 333, N-GSB-45 Russellville, AR 72802 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION COOPER NUCLEAR STATION LICENSE RENEWAL APPLICATION
Request for Additional Information B.1.10-5 Containment Inservice Inspection Program
=
Background===
The Generic Aging Lessons Learned Report states that proper maintenance of protective
coatings inside cont ainment is essential to ensure operability of post-accident safety systems that rely on water recycled through the containment sump or drain system. Degradation of coatings can lead to clogging of strainers, which reduces flow through the sump or drain system.
Issue:
The Cooper Nuclear Station (CNS) license renewal application (LRA) does not credit the protective coating monitoring and maintenance program for aging management; the containment Inservice Inspection (ISI) Program manages the effects of aging on the drywell shell. Although
the licensee stated that enhancements will be made to the cont ainment ISI Progr am to inspect surfaces for signs of distress, there needs to be adequate assurance that there is proper maintenance of the protective coatings in containment, such that they will not degrade and become a debris source that may challenge the emergency core cooling system's performance.
Request 1. On page B-10 of the LRA (Agencywide Documents Access Management System Accession No. ML083030227), line item XI.S8 states that the NUREG-1801 program is not credited for aging management. The containment ISI Program manages the effect of aging on the drywell shell. Please discuss how the containment ISI Program meets the recommendations of NUREG-1801 X1.S8 in managing the effects of aging at CNS.
- a. Please describe how the program will ensur e that there will be proper maintenance of the protective coatings insi de the containment, such that they will not become a debris source that could impact the operability of post-accident safety systems that rely on water recycled through the containment sump or drain system in the extended period of operation. b. Please describe the frequency and scope of the inspections, acceptance criteria, and the qualification of personnel who perform containment coatings inspections.