ML100710645
| ML100710645 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/20/2010 |
| From: | Tam Tran License Renewal Projects Branch 1 |
| To: | Nebraska Public Power District (NPPD) |
| Tran, T NRR/ADRO/DLR/RPB1, 415-3617 | |
| References | |
| Download: ML100710645 (12) | |
Text
April 20, 2010 LICENSEE:
Nebraska Public Power District FACILITY:
Cooper Nuclear Station Power Plant
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 20, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND NEBRASKA PUBLIC POWER DISTRICT, RELATED TO A CLARIFICATION FOR CERTAIN RESPONSES TO 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 January 20, 2010, to discuss clarifications for certain responses to 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 License Renewal 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
ML100710645 OFFICE LA:DLR PM:RPB1:DLR PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME SFigueroa TTran BBrady (TTran for)
BPham (BBrady for)
TTran DATE 3/18/10 4/13/10 4/13/10 4/20/10 4/20/10
LIST OF PARTICIPANTS FROM THE TELEPHONE CONFERENCE CALL FOR COOPER NUCLEAR STATION LICENSE RENEWAL APPLICATION January 20, 2010 PARTICIPANTS AFFILIATIONS T. Tran U.S. Nuclear Regulatory Commission (NRC)
B. Brady NRC F. Farzam NRC A. Sheikh NRC J. Gavula NRC S. Gardocki NRC B. Lehman NRC D. Bremer Nebraska Public Power District (NPPD)
W. Victor NPPD J. Sweley NPPD D. Lach Entergy A. Cox Entergy T. Ivy, Entergy J. Robinson Entergy R. Ahrabli Entergy
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 NPPD, held a telephone conference call on January 20, 2010, to discuss clarifications for certain responses to requests for additional information listed below.
Clarification for RAI 2.3.4.2.CM-3 response The Staff and the applicant discussed RAI 2.3.4.2 CM-3, regarding the Condensate Storage Tanks (CST) in scope for license renewal in the applicants letter of response (NLS2009095).
The Staff reiterated that in modes 4 and 5, the CNS Technical Specification requires the operability of two low pressure ECCS (a safety-related system) during shutdown operations.
The Condensate Storage Tank is allowed by the Technical Specifications to be a water source for this safety-related system in modes 4 and 5, and in situations when the suppression pool is unavailable. The Technical Specification Bases explains the safety basis for this TS is to prevent fuel uncovery during a drain down event. Additionally, the CNS USAR credits CST inventory as an alternate mean for filling the Spent Fuel Pool. Therefore, the CST has an (a)(2) function and should be included within the scope of license renewal.
The applicant provided a detailed discussion of this issue to the staff during the conference call of 1/18/2010. The Staff indicated that this item would remain as an Open Item.
Clarification for RAI B.1.10-5 and RAI 2.4-2(c) responses In RAI 2.4-2(c), the staff requested clarification on the exclusion of the Drywell coating from the scope of license renewal. In response to RAI 2.4-2(c), the applicant stated that the protective coating is excluded from the scope of license renewal since (1) it is not safety related; and (2) the failure of the protective coating will not prevent satisfactory accomplishment of a safety function.
In RAI B.1.10-5, the staff requested the applicant to provide more information on the CNS service level 1 coating program. In response to RAI B.1.10-5, the applicant stated that the CNS service level 1 coating program (1) provides specific instructions for maintenance of safety related coatings applied to concrete and steel surfaces within the drywell and torus; and (2) ensures that service level 1 coating is applied and maintained such that the coating will not become detached creating potential debris.
The response to RAI 2.4-2(c) is not consistent with the response to RAI B.1.10-5 relative to safety function classification. The staff requested the applicant to clarify this inconsistency.
The applicant provided the following clarifications:
The applicant provided a discussion of this issue to the staff during the conference call of 1/14/2010. This item was revisited at length during the 1/20/2010 call. It was agreed that protective coating is maintained as part of the monitoring program of the in-scope structures and components. It was further agreed that a supplemental response to RAI 2.4-2 (c ) will be submitted to clarify that the protective coating will be considered in the scope of license renewal.
The staff also accepted that since there is no line item in the GALL AMR tables for coatings, it was not necessary to revise the CNS LRA AMR tables. However, the staff and the applicant agreed that it is appropriate to include discussion of the GL 98-04 coatings program in Appendix B of the LRA. The applicant agreed to discuss this program within the B.1.36 Structures Monitoring Program description. The staff agreed that this is acceptable.
Subsequent to the conference call, the following change to LRA Section B.1.36 was proposed to the staff:
B.1.36 STRUCTURES MONITORING Program Description The Structures Monitoring Program is an existing program that performs inspections in accordance with 10 CFR 50.65 (Maintenance Rule) as addressed in Regulatory Guide 1.160 and NUMARC 93-01. Periodic inspections are used to monitor the condition of structures and structural commodities to ensure there is no loss of intended function.
Since protective coatings are not relied upon to manage the effects of aging for structures included in the Structures Monitoring Program, the program does not directly address protective coating monitoring and maintenance. However, observation of the condition of the paint or coating is an effective method for identifying the absence of degradation of the underlying material. Therefore, monitoring of the condition of coatings on SSCs within the scope of the Structures Monitoring Program is implicitly included within that program. To address the potential impact of coating failure on ECCS sumps, the CNS coatings program was established as described in response to GL 98-04 (Ref.
CNS letter NLS980166 to NRC, dated Nov. 4, 1998). This CNS coatings program effectively manages the condition of Service Level 1 protective coatings in the containment to ensure coating degradation does not negatively impact the ability of the ECCS sumps to perform their intended functions.
The staff review of the proposed resolution: the above statement is not acceptable to the staff because it only addresses coatings in the containment. Structures Monitoring Program scope defined in Section B.1.36 of the LRA includes 33 structures/components. Majority of these structures/components are located outside containment. The 10 elements of Structures Monitoring Program in Section B.1.36 does not address coating inspection or frequency.
Clarification for RAI B.1.18-5 response In its response dated November 4, 2009, the applicant stated: use of CHECWORKS satisfies the criterion for predictive modeling in the FAC Program, but the CHECWORKS software is not used to verify compliance with regulatory commitments. The applicant also stated: it should be noted that the use of CHECWORKS is not characterized as a regulatory commitment for future action proposed in the LRA, since the established FAC Program already includes the use of CHECWORKS as the analytical tool for predictive modeling. The staff requested the applicant to clarify whether or not it commits to use CHECWORKS during the period of extended operation, in following GALL Section XI.M17 (which credits use of a predictive code, such as CHECWORKS). The staff has a concern that the outputs of predictive software shall be validated so that wall thinning predictions can be relied upon for an effective aging management program.
The applicant provided the following clarifications:
The applicant provided a discussion of this issue to the staff during the 1/14/2010 conference call. This item was revisited during the 1/20/2010. Among other things, the applicant acknowledged that the use of predictive software (such as CHECWORKS) in conformance with GALL was an implicit commitment. The Staff took issue with the characterization of this commitment as implicit. During the conference call, the applicant clarified that it had made in the LRA an ongoing commitment for a flow accelerated corrosion (FAC) program that follows the guidelines of NSAC-202L. Accordingly, the applicant stated that it amends its previously position to be:
Regarding the credit taken in the LRA for conforming to the GALL and to EPRI NSAC-202L (which references use of CHECWORKS or similar predictive software), NPPD acknowledges that the USAR supplement Section A.1.1.18 includes the commitment to follow this during the PEO."
The staff indicated that this issue would be resolved.
Torus coating In its response dated July 29, 2009, the applicant stated that there are no current plans to recoat the interior of the entire torus. The applicant further stated that the torus will continue to be inspected as required by ASME Section XI, Subsection IWE during the period of extended operation, and indications will be evaluated to determine the appropriate corrective actions, including recoating if necessary.
The staff reviewed the CNS response to RAI B.1.10-2 and requested the applicant to provide additional information in RAI B.1.10-6. The staff concern was that the large number of repairs, excessive zinc depletion, and pitting at thousands of locations to the torus during the last 35 years indicate that the integrity of the torus coating cannot be relied upon during the period of extended operation and have significantly exceeded its useful life. Normal life of the torus coating is 15-20 years. In addition, CNS internal documents concerning self assessment of the torus coating have previously recommended recoating of the torus. Therefore, the staff requested the applicant to provide detailed justification for not making a commitment to recoat the torus prior to the start of period of extended operation.
In its response to RAI B.1.10-6, dated December 21, 2009, the applicant stated a total of approximately 2200 coating repairs have been made to the torus shell since 2001. Out of these 2200 locations, 18 locations had pits where the nominal thickness has been reduced by greater than 10 percent of the nominal shell thickness. The applicant also stated that engineering evaluation was performed that determined that loss of material at the 18 pits was acceptable.
Therefore, applicant has not performed any supplementary volumetric (UT) examination at these 18 pits that are located under water. However, the applicant performs augmented visual testing (VT) of the wetted surfaces of the torus once during each inspection period (3 times in 10 years) as required by the ASME Code. The applicant further stated that it has no plans to perform UT examination of the wetted surface of the torus shell because divers visually inspect the shell surface from the inside every other outage. In conclusion, the applicant stated that the CNS ASME Section XI, IWE program provide will effective aging management of the torus during the period of extended operation; however, recoating remains an option, if warranted in the future.
The staff reviewed the applicants response to the RAI B.1.10.6, and found it unacceptable because it does not provide commitment to recoat the torus shell internal surface before the period of extended operation. The applicant did not address the issue of how torus coating can last 60 years when the normal life of this coating is only 15-20 years. In addition, the applicant did not provide the coating repairs performed to the torus before 2001 during the first 25 years of the plant operation. According to NUREG 1522, Assessment of Inservice Conditions of Safety-Related Nuclear Plant Structures, the applicant identified numerous pits in 4 of the 16 bays of the torus and coating was repaired at 150 locations in these 4 bays, during 1993.
Based on current degree of coating failure, it does not appear that the existing coating is suitable for service beyond the current licensing period of 40 years. Depletion of zinc coating has reduced the ability to provide corrosion protection to the exposed steel substrate and localized coating failures have exposed areas of bare steel. If the zinc remained available in sufficient quantities, localized bare metal surrounded by intact coating should not be exhibiting active corrosion as it has been.
The applicant has not been managing the coating failures by making coating repairs to areas that have had localized coating failures, whether above or below the waterline. This has apparently resulted in localized galvanic corrosion with high corrosion rates (pitting), instead of very low and predictable general corrosion rates. It has also contributed to the amount of sludge and corrosion products collecting in the suppression pool. Instead, the applicant has been allowing corrosion and applying an epoxy coating intended to arrest the pitting. The applicant was attempting to manage the pitting corrosion in the context structural integrity without correcting the causes. The available data indicate that the condition worsened over time, so this method of aging management is not being successful. Pitting corrosion rates are typically much higher and less predictable than general corrosion rates, and a through-wall pit would impact containment integrity without necessarily impacting structural integrity.
The staff has concluded that while the applicant met their obligations under the ASME Code; however, the ASME Code does not address consideration of plant life extension or determination of when a coating should be replaced. The normal life of the zinc coating which was applied to the torus is 15-20 years and is not suitable for service beyond the current licensing period of 40 years. In addition, thousands of coating repairs have been performed and extensive localized coating failures have been observed in the torus shell. Therefore this issue is unresolved and will be tracked as a new open item.
No further discussion took place other than the staff indicated that this is a new open item.
Memorandum to: Nebraska Public Power District from J. Daily dated April 20, 2010
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 20, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND NEBRASKA PUBLIC POWER DISTRICT, RELATED TO A CLARIFICATION FOR CERTAIN RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION, FOR COOPER NUCLEAR STATION LICENSE RENEWAL DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC [or NON-PUBLIC, if appropriate]
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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 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 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. 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 Mr. Jerry Perry 500 S. Main Street Rock Port, MO 64482 Ms. Yolanda Peck 1008 Central Ave.
Auburn, NE 68305 Ms. Kendall Neiman 830 Central Ave.
Auburn, NE 68305 Ms. Annie Thomas 1522 I Street Auburn, NE 68305 Mr. John Chaney 1101 17th Street Auburn, NE 68305 Mr. Darrell Kruse 2415 McConnell Ave.
Auburn, NE 68305 Ms. Daryl J. Obermeyer 64381 727A Road Brownville, NE 68321 Ms. Sherry Black, Director Auburn Memorial Library 1810 Courthouse Ave.
Auburn, NE 68305 Board of Brownville, NE Attn: Chairman Marty Hayes P.O. Box 67 223 Main Street Brownville, NE 68321 Mr. Bob Engles Mayor of Auburn, NE 1101 J Street Auburn, NE 68305
Cooper Nuclear Station cc:
Ms. Jo Stevens Mayor of Rock Port, MO 500 S. Main Street Rock Port, MO 64482 Mr. John Cochnar U.S. Fish and Wildlife Service Ecological Services Nebraska Field Office 203 West Second Street Grand Island, NE 68801 Mr. John Askew Regional Administrator U.S. EPA Region 7 901 N. 5th Street Kansas City, KS 66101 Ms. Joann Scheafer, Director Nebraska Department of Health & Human Services 301 Centennial Mall South Lincoln, NE 68509 Mr. Doyle Childers, Director Missouri Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Mr. Mark Miles State Historic Preservation Officer Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Mr. Michael J. Smith State Historic Preservation Officer Nebraska State Historical Society P.O. Box 82554 Lincoln, NE 68501 Mr. Robert Puschendorf Nebraska State Historical Society 1500 R Street, P.O. Box 82554, Lincoln, NE 68501-2554 Mr. Jim Loynes License Renewal Project Engineer Cooper Nuclear Station 72676 - 648A Avenue Brownville, NE 68321 Ms. Carla Mason ADC Digital Communications 820 Central Ave.
Auburn, NE 68305 Mr. Matthew Leaf KTNC/KLZA Radio1602 Stone St.
Falls City, NE 68355 Mr. Stewart B. Minahan Vice President Nuclear and Chief Nuclear Officer Cooper Nuclear Station 72676 - 648A Avenue Brownville, NE 68321