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| | number = ML070590230 | | | number = ML070590230 |
| | issue date = 03/05/2007 | | | issue date = 03/05/2007 |
| | title = Cooper Nuclear Station - Request for Additional Information - License Amendment Request Onsite Spent Fuel Storage Expansion | | | title = Request for Additional Information - License Amendment Request Onsite Spent Fuel Storage Expansion |
| | author name = Lyon C F | | | author name = Lyon C |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIV | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIV |
| | addressee name = Minahan S B | | | addressee name = Minahan S |
| | addressee affiliation = Nebraska Public Power District (NPPD) | | | addressee affiliation = Nebraska Public Power District (NPPD) |
| | docket = 05000298 | | | docket = 05000298 |
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| =Text= | | =Text= |
| {{#Wiki_filter:March 5, 2007Mr. Stewart B. MinahanVice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321 | | {{#Wiki_filter:March 5, 2007 Mr. Stewart B. Minahan Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATIONRE: LICENSE AMENDMENT REQUEST - ONSITE SPENT FUEL STORAGE EXPANSION (TAC NO. MD3349) | | COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST - ONSITE SPENT FUEL STORAGE EXPANSION (TAC NO. MD3349) |
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| ==Dear Mr. Minahan:== | | ==Dear Mr. Minahan:== |
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| By application dated October 17, 2006, Nebraska Public Power District (NPPD, the licensee)requested the U.S. Nuclear Regulatory Commission (NRC) staff approval of an amendment to the Cooper Nuclear Station technical specifications to increase the capacity of the spent fuel storage pool.The NRC staff has reviewed the information provided in your submittal and determined thatadditional information is required in order to complete its review. Questions in the enclosed request for additional information (RAI) were discussed in telephone calls with Mr. R. Rogers, et al., of your staff on December 7, 2006, and February 15 and 21, 2007. During a discussion with Mr. Rogers on February 27, 2007, it was agreed that NPPD would provide a response by April 10, 2007, to this RAI.The NRC staff considers that timely responses to RAIs help ensure sufficient time is availablefor staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296.Sincerely,/RA/Carl F. Lyon, Project ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-298 | | By application dated October 17, 2006, Nebraska Public Power District (NPPD, the licensee) requested the U.S. Nuclear Regulatory Commission (NRC) staff approval of an amendment to the Cooper Nuclear Station technical specifications to increase the capacity of the spent fuel storage pool. |
| | The NRC staff has reviewed the information provided in your submittal and determined that additional information is required in order to complete its review. Questions in the enclosed request for additional information (RAI) were discussed in telephone calls with Mr. R. Rogers, et al., of your staff on December 7, 2006, and February 15 and 21, 2007. During a discussion with Mr. Rogers on February 27, 2007, it was agreed that NPPD would provide a response by April 10, 2007, to this RAI. |
| | The NRC staff considers that timely responses to RAIs help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296. |
| | Sincerely, |
| | /RA/ |
| | Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Information cc w/encl: See next page | | Request for Additional Information cc w/encl: See next page |
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| ML070590230OFFICENRR/LPL4/PMNRR/LPL4/LANRR/LPL4/BCNAMEFLyonLFeizollahiDTerao DATE3/5/073/5/073/5/07 February 2007Cooper Nuclear Station cc:Mr. Ronald D. Asche President and Chief Executive Officer Nebraska Public Power District
| | ML070590230 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NAME FLyon LFeizollahi DTerao DATE 3/5/07 3/5/07 3/5/07 Cooper Nuclear Station cc: |
| | Mr. Ronald D. Asche Mr. H. Floyd Gilzow President and Chief Executive Officer Deputy Director for Policy Nebraska Public Power District Missouri Department of Natural Resources 1414 15th Street P.O. Box 176 Columbus, NE 68601 Jefferson City, MO 65102-0176 Mr. Gene Mace Senior Resident Inspector Nuclear Asset Manager U.S. Nuclear Regulatory Commission Nebraska Public Power District P.O. Box 218 P.O. Box 98 Brownville, NE 68321 Brownville, NE 68321 Regional Administrator, Region IV Mr. John C. McClure U.S. Nuclear Regulatory Commission Vice President and General Counsel 611 Ryan Plaza Drive, Suite 400 Nebraska Public Power District Arlington, TX 76011 P.O. Box 499 Columbus, NE 68602-0499 Director, Missouri State Emergency Management Agency Mr. Paul V. Fleming P.O. Box 116 Licensing Manager Jefferson City, MO 65102-0116 Nebraska Public Power District P.O. Box 98 Chief, Radiation and Asbestos Brownville, NE 68321 Control Section Kansas Department of Health Mr. Michael J. Linder, Director and Environment Nebraska Department of Environmental Bureau of Air and Radiation Quality 1000 SW Jackson P.O. Box 98922 Suite 310 Lincoln, NE 68509-8922 Topeka, KS 66612-1366 Chairman Mr. Donald A. Flater Nemaha County Board of Commissioners Radiation Control Program Director Nemaha County Courthouse Bureau of Radiological Health 1824 N Street Iowa Department of Public Health Auburn, NE 68305 Lucas State Office Building, 5th Floor 321 East 12th Street Ms. Julia Schmitt, Manager Des Moines, IA 50319 Radiation Control Program Nebraska Health & Human Services R & L Mr. Daniel K. McGhee Public Health Assurance Bureau of Radiological Health 301 Centennial Mall, South Iowa Department of Public Health P.O. Box 95007 Lucas State Office Building, 5th Floor Lincoln, NE 68509-5007 321 East 12th Street Des Moines, IA 50319 February 2007 |
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| 1414 15 th StreetColumbus, NE 68601Mr. Gene MaceNuclear Asset Manager Nebraska Public Power District P.O. Box 98 Brownville, NE 68321Mr. John C. McClureVice President and General Counsel Nebraska Public Power District P.O. Box 499 Columbus, NE 68602-0499Mr. Paul V. FlemingLicensing Manager Nebraska Public Power District P.O. Box 98 Brownville, NE 68321Mr. Michael J. Linder, Director Nebraska Department of Environmental Quality P.O. Box 98922 Lincoln, NE 68509-8922Chairman Nemaha County Board of Commissioners Nemaha County Courthouse 1824 N Street Auburn, NE 68305Ms. 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 68509-5007Mr. H. Floyd GilzowDeputy Director for Policy Missouri Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102-0176Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 218 Brownville, NE 68321Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011Director, Missouri State Emergency Management Agency P.O. Box 116 Jefferson City, MO 65102-0116Chief, Radiation and Asbestos Control Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson Suite 310 Topeka, KS 66612-1366Mr. Donald A. FlaterRadiation 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 50319Mr. Daniel K. McGheeBureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319 Cooper Nuclear Station-2-February 2007 cc:Mr. Keith G. Henke, Planner Division of Community and Public Health Office of Emergency Coordination 930 Wildwood P.O. Box 570 Jefferson City, MO 65102Mr. Kevin V. Chambliss, Director of Nuclear Safety Assurance Nebraska Public Power District P.O. Box 98 Brownville, NE 68321Mr. John F. McCann, DirectorLicensing, Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
| | Cooper Nuclear Station cc: |
| 440 Hamilton Avenue White Plains, NY 10601-1813 REQUEST FOR ADDITIONAL INFORMATIONRELATED TO ONSITE SPENT FUEL STORAGE EXPANSIONCOOPER NUCLEAR STATIONDOCKET NO. 50-298I.The following questions are provided from the Health Physics Branch (IHPB):1.In Section 9.4 of the Holtec Report, you state that the calculated dose rateadjacent to the new fuel racks (if they are completely filled with freshly discharged fuel) would be unacceptably high. 1-a.Provide the current radiation dose rates for those accessible areasadjacent to the area (including any accessible areas below the spent fuel pool (SFP)) where the new fuel racks will be installed. 1-b.For these same areas, provide the calculated dose rates from theproposed new racks (1) if the new racks are completely filled with freshly discharged fuel and (2) if the outer rows of the new racks are loaded with fuel, which has decayed for at least 5 years. 1-c.Provide the number of outer rows, which will be filled with aged fuel toensure that the dose rates in potentially-occupied areas adjacent to the SFP do not exceed the current radiation dose rates for these areas. 2.Provide the expected maximum dose rate above the SFP.
| | Mr. Keith G. Henke, Planner Mr. John F. McCann, Director Division of Community and Public Health Licensing, Entergy Nuclear Northeast Office of Emergency Coordination Entergy Nuclear Operations, Inc. |
| 3.Describe any radiation surveys that will be performed (from the pool rim or bydivers in the pool) to map dose rates in the SFP prior to dive operations. 4.Provide a description of any sources of high radiation that may be in the SFPduring diving operations for minor modification of the beam segments. Discuss what precautions (such as use of TV monitoring, additional lighting, tethers, use of physical barriers between the divers and high-radiation sources, fuel shuffling, etc.) will be used to ensure that the divers will maintain a safe distance from any high-radiation sources in the SFP. Discuss how you plan to alert divers (e.g., by use of continuous voice communication with the divers) in the event that they inadvertently enter an area of high radiation or if they exceed their predetermined dose limit while performing work in the SFP. Discuss the use of multiple dosimeters on divers who will be working in the SFP. Discuss how divers will be monitored for contamination when they exit the SFP. 5.In Section 9.4 of the Holtec Report, you state there are continuous airbornemonitors for airborne activities available in the immediate vicinities of the pool. Describe how these monitors are utilized in the SFP area during the Refueling Floor Operations, including diving operations and SFP rack installations. 6.Discuss the removal, decontamination, and disposal of the storage racks for thecontrol rod blades and the drum platform from the shipping cask storage area. 7.Discuss how the storage of the additional spent fuel assemblies in the SFP willaffect the releases of radioactive gases from the SFP. Specifically address the potential increased releases of Kr-85, I-131, and tritium from the SFP. 8.Discuss how the storage of additional spent fuel assemblies in the SFP will affectthe release of radioactive liquids from the plant as a result of any expected increase in the change-out frequency of the demineralizer resins for the SFP.II.The following questions are provided from the Engineering Mechanics Branch (EEMA):1.As noted in Section 1.3 of the Holtec Report, "[t]he existing swing bolts are usedto fasten the platform to the pool floor rendering them into a fixed appurtenance to the pool slab." Please provide a summary of the stress analysis of the swing bolts and swingbolt anchorages to the pool slab for the loads transmitted by the Rack A fuel rack and platform. Please provide a drawing showing the anchorage pattern. 2.Section 2.1 of the Holtec Report notes that: "[a]lthough both rack modules arefreestanding, and thus may slide during a seismic event, any significant membrane strains in the pool liner are prevented by the presence of the platforms. As a result, the maximum strain sustained by the liner during a seismic event is assumed to be less than the ultimate strain for the liner material (austenitic stainless steel, ultimate strain 0.38)." Please provide a summary of the stress analysis of the 2 inch thick by 2 -1/2 inchwide "cask restraint ring" shown in Section 3711 of Burns & Roe Drawing 4288 for the loads induced by Rack B. 3.Section 2.2 of the Holtec Report notes that: "[b]ecause the platforms are not anintegral part of the rack, their stress analysis and structural qualification are not addressed in this licensing report." Please provide a summary of the stress analyses for the Rack A and Bplatforms. Please provide the drawings for the platforms.4.Section 8.4 of the Holtec Report documents that a modal analysis wasperformed on the SFP floor, and: "it was determined that the first mode frequency in the vertical direction is 35.4 Hz, which is larger than 33 Hz and, thus, in the rigid range. Therefore, seismic amplification due to slab flexibility is not an issue. These results justify development of equivalent static loads using the zero period accelerations as multipliers." Table 8.3.1 of the Holtec Report indicates that an uncracked section moduluswas used for this computation. Please discuss the appropriateness of using an uncracked section modulus to calculate the fundamental frequency of the SFPfloor. How does the calculation for the fundamental frequency of the SFP floorconsider the static mass of the SFP water? This load does not appear to be listed in Table 8.5.1 of the Holtec Report. Section 2.3.3.2.4 of the Cooper Nuclear Station Updated Safety Analysis Report notes that the SFP contains about 2.1 million pounds (2,100 kips) of water. 5.Please discuss any nonconformances that are related to material degradationissues (concrete, rebar) in the SFP.6.Table 6.7.1 of the Holtec Report specifies 4 percent damping for Operating BasisEarthquake (OBE) and 5 percent damping for Safe Shutdown Earthquake (SSE) as input data for the rack seismic analysis. Table 1 of NRC Regulatory Guide 1.61 specifies 2 percent damping for OBE and 4 percent damping for SSE for welded steel structures. Please discuss the appropriateness of the damping values used in the analysis. III.The following questions are provided from the Steam Generator Tube Integrity andChemical Engineering Branch (CSGB):The proposed change revises TS 4.3, "Fuel Storage," to reflect the addition of fuelstorage capacity in the SFP by adding up to two additional storage racks. The increased fuel capacity involves use of the Metamic neutron absorbing material.The staff has conditioned prior acceptance of the Metamic material for use in SFPsupon a coupon sampling program (e.g., Clinton, Arkansas Nuclear One) to ensure performance consistent with that described in the engineering reports. An acceptable coupon sampling program has the following attributes:The size and types of coupons are similar in fabrication and layout to theproposed application, including welds or mechanical fasteners and proximity to stainless steel.The technique for measuring the initial B 4C content of the coupons isdescribed.Scratches and other surface anomalies on the coupons simulateas-installed conditions of Metamic panels.Justification of the frequency of coupon sampling is provided.Tests to be performed on coupons are specified; e.g., weightmeasurement, measurement of dimensions (length, width and thickness),
| | 930 Wildwood P.O. Box 570 440 Hamilton Avenue Jefferson City, MO 65102 White Plains, NY 10601-1813 Mr. Kevin V. Chambliss, Director of Nuclear Safety Assurance Nebraska Public Power District P.O. Box 98 Brownville, NE 68321 February 2007 |
| and B 4C content and acceptance criteria. 1. Provide a detailed description of your coupon sampling program.2. Please describe the scope of the receipt inspections performed on the Metamic panels to establish a baseline. In addition, discuss who will perform thesereceipt inspections and where they will be performed.3.Please discuss the surface preparation or anodizing process that will be used onthe Metamic panels? In addition, what cleaning process will be used to ensuresufficient removal of surface contaminants? Please note, the surface preparation for the coupons is to be similar to what is used on the Metamic panels.4. Please discuss how the Metamic panels are to be attached to the new spentfuel racks (welding, mechanical fasteners, etc.). If the Metamic panels are tobe welded, what welding process will be used and what weld filler material will be
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| used?5. Given that Metamic is a new material for SFP applications, we request that yousubmit the results of each surveillance to the staff. The reporting requirements should be addressed in your surveillance program. The reporting requirements should include the baseline inspection results and the results of all subsequent inspections (i.e., visual, length, width, thickness, weight, and neutron absorption).}} | | REQUEST FOR ADDITIONAL INFORMATION RELATED TO ONSITE SPENT FUEL STORAGE EXPANSION COOPER NUCLEAR STATION DOCKET NO. 50-298 I. The following questions are provided from the Health Physics Branch (IHPB): |
| | : 1. In Section 9.4 of the Holtec Report, you state that the calculated dose rate adjacent to the new fuel racks (if they are completely filled with freshly discharged fuel) would be unacceptably high. |
| | 1-a. Provide the current radiation dose rates for those accessible areas adjacent to the area (including any accessible areas below the spent fuel pool (SFP)) where the new fuel racks will be installed. |
| | 1-b. For these same areas, provide the calculated dose rates from the proposed new racks (1) if the new racks are completely filled with freshly discharged fuel and (2) if the outer rows of the new racks are loaded with fuel, which has decayed for at least 5 years. |
| | 1-c. Provide the number of outer rows, which will be filled with aged fuel to ensure that the dose rates in potentially-occupied areas adjacent to the SFP do not exceed the current radiation dose rates for these areas. |
| | : 2. Provide the expected maximum dose rate above the SFP. |
| | : 3. Describe any radiation surveys that will be performed (from the pool rim or by divers in the pool) to map dose rates in the SFP prior to dive operations. |
| | : 4. Provide a description of any sources of high radiation that may be in the SFP during diving operations for minor modification of the beam segments. Discuss what precautions (such as use of TV monitoring, additional lighting, tethers, use of physical barriers between the divers and high-radiation sources, fuel shuffling, etc.) will be used to ensure that the divers will maintain a safe distance from any high-radiation sources in the SFP. Discuss how you plan to alert divers (e.g., by use of continuous voice communication with the divers) in the event that they inadvertently enter an area of high radiation or if they exceed their predetermined dose limit while performing work in the SFP. Discuss the use of multiple dosimeters on divers who will be working in the SFP. Discuss how divers will be monitored for contamination when they exit the SFP. |
| | : 5. In Section 9.4 of the Holtec Report, you state there are continuous airborne monitors for airborne activities available in the immediate vicinities of the pool. |
| | Describe how these monitors are utilized in the SFP area during the Refueling Floor Operations, including diving operations and SFP rack installations. |
| | : 6. Discuss the removal, decontamination, and disposal of the storage racks for the control rod blades and the drum platform from the shipping cask storage area. |
| | : 7. Discuss how the storage of the additional spent fuel assemblies in the SFP will affect the releases of radioactive gases from the SFP. Specifically address the potential increased releases of Kr-85, I-131, and tritium from the SFP. |
| | : 8. Discuss how the storage of additional spent fuel assemblies in the SFP will affect the release of radioactive liquids from the plant as a result of any expected increase in the change-out frequency of the demineralizer resins for the SFP. |
| | II. The following questions are provided from the Engineering Mechanics Branch (EEMA): |
| | : 1. As noted in Section 1.3 of the Holtec Report, [t]he existing swing bolts are used to fasten the platform to the pool floor rendering them into a fixed appurtenance to the pool slab. |
| | Please provide a summary of the stress analysis of the swing bolts and swing bolt anchorages to the pool slab for the loads transmitted by the Rack A fuel rack and platform. Please provide a drawing showing the anchorage pattern. |
| | : 2. Section 2.1 of the Holtec Report notes that: [a]lthough both rack modules are freestanding, and thus may slide during a seismic event, any significant membrane strains in the pool liner are prevented by the presence of the platforms. As a result, the maximum strain sustained by the liner during a seismic event is assumed to be less than the ultimate strain for the liner material (austenitic stainless steel, ultimate strain $0.38). |
| | Please provide a summary of the stress analysis of the 2 inch thick by 2 -1/2 inch wide cask restraint ring shown in Section 3711 of Burns & Roe Drawing 4288 for the loads induced by Rack B. |
| | : 3. Section 2.2 of the Holtec Report notes that: [b]ecause the platforms are not an integral part of the rack, their stress analysis and structural qualification are not addressed in this licensing report. |
| | Please provide a summary of the stress analyses for the Rack A and B platforms. Please provide the drawings for the platforms. |
| | : 4. Section 8.4 of the Holtec Report documents that a modal analysis was performed on the SFP floor, and: it was determined that the first mode frequency in the vertical direction is 35.4 Hz, which is larger than 33 Hz and, thus, in the rigid range. Therefore, seismic amplification due to slab flexibility is not an issue. These results justify development of equivalent static loads using the zero period accelerations as multipliers. |
| | Table 8.3.1 of the Holtec Report indicates that an uncracked section modulus was used for this computation. Please discuss the appropriateness of using an |
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| | uncracked section modulus to calculate the fundamental frequency of the SFP floor. |
| | How does the calculation for the fundamental frequency of the SFP floor consider the static mass of the SFP water? This load does not appear to be listed in Table 8.5.1 of the Holtec Report. Section 2.3.3.2.4 of the Cooper Nuclear Station Updated Safety Analysis Report notes that the SFP contains about 2.1 million pounds (2,100 kips) of water. |
| | : 5. Please discuss any nonconformances that are related to material degradation issues (concrete, rebar) in the SFP. |
| | : 6. Table 6.7.1 of the Holtec Report specifies 4 percent damping for Operating Basis Earthquake (OBE) and 5 percent damping for Safe Shutdown Earthquake (SSE) as input data for the rack seismic analysis. Table 1 of NRC Regulatory Guide 1.61 specifies 2 percent damping for OBE and 4 percent damping for SSE for welded steel structures. Please discuss the appropriateness of the damping values used in the analysis. |
| | III. The following questions are provided from the Steam Generator Tube Integrity and Chemical Engineering Branch (CSGB): |
| | The proposed change revises TS 4.3, Fuel Storage, to reflect the addition of fuel storage capacity in the SFP by adding up to two additional storage racks. The increased fuel capacity involves use of the Metamic neutron absorbing material. |
| | The staff has conditioned prior acceptance of the Metamic material for use in SFPs upon a coupon sampling program (e.g., Clinton, Arkansas Nuclear One) to ensure performance consistent with that described in the engineering reports. |
| | An acceptable coupon sampling program has the following attributes: |
| | C The size and types of coupons are similar in fabrication and layout to the proposed application, including welds or mechanical fasteners and proximity to stainless steel. |
| | C The technique for measuring the initial B4C content of the coupons is described. |
| | C Scratches and other surface anomalies on the coupons simulate as-installed conditions of Metamic panels. |
| | C Justification of the frequency of coupon sampling is provided. |
| | C Tests to be performed on coupons are specified; e.g., weight measurement, measurement of dimensions (length, width and thickness), |
| | and B4C content and acceptance criteria. |
| | : 1. Provide a detailed description of your coupon sampling program. |
| | : 2. Please describe the scope of the receipt inspections performed on the Metamic panels to establish a baseline. In addition, discuss who will perform these receipt inspections and where they will be performed. |
| | : 3. Please discuss the surface preparation or anodizing process that will be used on the Metamic panels? In addition, what cleaning process will be used to ensure sufficient removal of surface contaminants? Please note, the surface preparation for the coupons is to be similar to what is used on the Metamic panels. |
| | : 4. Please discuss how the Metamic panels are to be attached to the new spent fuel racks (welding, mechanical fasteners, etc.). If the Metamic panels are to be welded, what welding process will be used and what weld filler material will be used? |
| | : 5. Given that Metamic is a new material for SFP applications, we request that you submit the results of each surveillance to the staff. The reporting requirements should be addressed in your surveillance program. The reporting requirements should include the baseline inspection results and the results of all subsequent inspections (i.e., visual, length, width, thickness, weight, and neutron absorption).}} |
Letter Sequence RAI |
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MONTHYEARML0700303222007-01-0909 January 2007
Request for Additional Information License Amendment Request for Spent Fuel Pool Storage Capacity
Project stage: RAI
ML0635407392007-01-12012 January 2007
Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing in Conjunction with the Expansion of Spent Fuel Pool Storage Capacity
Project stage: Other
ML0635407342007-01-12012 January 2007
Letter to License Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing in Conjunction with the Expansion of Spent Fuel Pool Storage Capacity
Project stage: Other
ML0704502422007-02-27027 February 2007
Withholding from Public Disclosure, Table 4-1 of Hi (Holtec International)-2043224, MD3349
Project stage: Other
ML0704502372007-02-27027 February 2007
Request for Withholding Information from Public Disclosure - Holtec International
Project stage: Withholding Request Acceptance
ML0704003662007-02-27027 February 2007
Request for Withholding Information from Public Disclosure - Global Nuclear Fuel - Americas, LLC 1/24/07 Affidavit
Project stage: Withholding Request Acceptance
ML0705902302007-03-0505 March 2007
Request for Additional Information - License Amendment Request Onsite Spent Fuel Storage Expansion
Project stage: RAI
ML0708201972007-03-15015 March 2007
H. Floyd Gilzow, State of Missouri Department of Natural Resources, Letter to C. Lyon, NRC, Cooper Nuclear Station - Request for Withholding Information from Public Disclosure
Project stage: Withholding Request
NLS2007012, Non-Proprietary Version of Response to Request for Additional Information Regarding License Amendment Request for Onsite Spent Fuel Storage Expansion2007-04-17017 April 2007
Non-Proprietary Version of Response to Request for Additional Information Regarding License Amendment Request for Onsite Spent Fuel Storage Expansion
Project stage: Response to RAI
NLS2007040, Affidavit Requesting Withholding from Public Disclosure Regarding Response to Request for Additional Information to Support NRC Review of License Amendment Request to Increase Capacity of Onsite Spent Fuel Storage at Cooper2007-05-0404 May 2007
Affidavit Requesting Withholding from Public Disclosure Regarding Response to Request for Additional Information to Support NRC Review of License Amendment Request to Increase Capacity of Onsite Spent Fuel Storage at Cooper
Project stage: Response to RAI
ML0714903152007-05-23023 May 2007
Response to Informal RAI Regarding Spent Fuel Pool Expansion Amendment Request
Project stage: Other
NLS2007056, Revised Page from Holtec International Non-Proprietary Report2007-07-26026 July 2007
Revised Page from Holtec International Non-Proprietary Report
Project stage: Request
ML0721300052007-08-28028 August 2007
Letter and Federal Register Notice of Environmental Assessment and Finding of No Significant Impact Onsite Spent Fuel Storage Expansion
Project stage: Other
ML0721300232007-09-0606 September 2007
License Amendment, Issuance of Amendment No. 227 Onsite Spent Fuel Storage Expansion
Project stage: Approval
2007-04-17
[Table View] |
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Category:Letter
MONTHYEARML23334A2012024-01-0303 January 2024
Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements
ML23311A1122023-11-0909 November 2023
Project Manager Assignment
ML23311A2082023-11-0909 November 2023
Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV
IR 05000298/20230032023-11-0202 November 2023
Integrated Inspection Report 05000298/2023003
IR 05000298/20234012023-11-0101 November 2023
Cyber Security Report 05000298/2023401 Public
ML23264A8052023-10-11011 October 2023
Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
ML23233A1882023-09-0505 September 2023
Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting
IR 05000298/20243012023-09-0101 September 2023
Notification of NRC Initial Operator Licensing Examination 05000298/2024301
IR 05000298/20230052023-08-21021 August 2023
Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter
IR 05000298/20230022023-08-0808 August 2023
Integrated Inspection Report 05000298/2023002
IR 05000298/20234022023-08-0303 August 2023
NRC Security Inspection Report 05000298/2023402
ML23214A2742023-08-0303 August 2023
Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information
IR 05000298/20234202023-08-0101 August 2023
Security Baseline Inspection Report 05000298/2023420
ML23173A0862023-06-26026 June 2023
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401
IR 05000298/20230102023-05-17017 May 2023
Biennial Problem Identification and Resolution Inspection Report 05000298/2023010
IR 05000298/20234032023-05-0404 May 2023
Security Baseline Inspection Report 05000298/2023403
ML23129A2822023-04-20020 April 2023
Submittal of Revision 31 to Updated Safety Analysis Report
ML23102A0282023-04-19019 April 2023
U.S. Nuclear Regulatory Commission Presentation at the May 8, 2023, Brownville Village Meeting
IR 05000298/20230012023-04-17017 April 2023
Integrated Inspection Report 05000298/2023001
ML23060A1582023-03-0808 March 2023
Design Basis Assurance Inspection (Programs) Inspection Report 05000298/2023001
IR 05000298/20220062023-03-0101 March 2023
Annual Assessment Letter for Cooper Nuclear Station Report 05000298/2022006
ML23041A1622023-02-10010 February 2023
Licensed Operator Positive Fitness-for-Duty Test Request for Additional Information
IR 05000298/20220042023-01-30030 January 2023
Integrated Inspection Report 05000298/2022004
IR 05000298/20220112022-12-23023 December 2022
License Renewal Phase 4 Inspection Report 05000298/2022011
ML22286A2072022-11-30030 November 2022
Issuance of Amendment No. 272 Revision to Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
IR 05000298/20220032022-10-27027 October 2022
Integrated Inspection Report 05000298/2022003
ML22304A0052022-10-26026 October 2022
Surveillance Capsule Location (Re-insertion Into the Reactor Vessel)
IR 05000298/20223022022-10-20020 October 2022
NRC Initial Operator Licensing Examination Approval 05000298/2022302
ML22276A1562022-10-0505 October 2022
Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information
IR 05000298/20224022022-09-29029 September 2022
NRC Security Inspection Report 05000298/2022402 (Full Report)
IR 05000298/20220052022-08-18018 August 2022
Updated Inspection Plan for Cooper Nuclear Station (Report 05000298 2022005)
IR 05000298/20223012022-08-10010 August 2022
NRC Examination Report 05000298/2022301
IR 05000298/20220022022-07-28028 July 2022
Integrated Inspection Report 05000298/2022002
ML22200A2772022-07-21021 July 2022
Correction to Proposed Inservice Testing Alternative RS-01, Revision of Error in Safety Evaluation
ML22152A1232022-07-18018 July 2022
Issuance of Amendment No. 271 Request for Exception from Certain Primary Containment Leak Rate Testing Requirements
IR 05000298/20224012022-06-29029 June 2022
Security Baseline Inspection Report 05000298/2022401
IR 05000298/20224032022-06-28028 June 2022
Security Baseline Inspection Report 05000298/2022403
IR 05000298/20220102022-06-16016 June 2022
Triennial Fire Protection Inspection Report 05000298/2022010
ML22140A1612022-06-0808 June 2022
Proposed Inservice Inspection Alternative RR5-01 Revision 1
ML22147A1122022-06-0101 June 2022
NRC Initial Operator Licensing Examination Approval 05000298/2022301
ML22111A1382022-05-13013 May 2022
Proposed Inservice Testing Alternative RS-01, Revision 0
IR 05000298/20220012022-04-28028 April 2022
Integrated Inspection Report 05000298/2022001
IR 05000298/20224042022-04-13013 April 2022
Material Control and Accounting Program Inspection Report 05000298/2022404 - (Public)
ML22084A6032022-04-0404 April 2022
Notification of NRC Evaluations of Changes, Tests and Experiments Inspection 05000298/2022002 and Request for Information
ML22090A2892022-04-0101 April 2022
John Larson'S Invitation to Participate in the 8th Nuclear Regulatory Commission'S Workshop on Vendor Oversight
ML22045A0012022-03-31031 March 2022
Proposed Inservice Inspection Alternative RI5- 02 Revision 3
IR 05000298/20210062022-03-0202 March 2022
Annual Assessment Letter for Cooper Nuclear Station (Report 05000298/2021006)
IR 05000298/20210042022-01-24024 January 2022
Integrated Inspection Report 05000298/2021004
ML21350A0582021-12-21021 December 2021
Withdrawal of an Amendment Request
ML21340A2362021-12-20020 December 2021
Issuance of Amendment No. 270 Adoption of Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements
2024-01-03
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24010A1172024-01-10010 January 2024
NRR E-mail Capture - Cooper Nuclear Station - LAR Dfo Tank Inspection RAI Issuance
ML24010A0902024-01-0404 January 2024
RAI - 10120-R1 - Final Dfo Tank Inspections LAR
ML23352A2472023-12-18018 December 2023
NRR E-mail Capture - Cooper Nuclear Station - Relief Request RC3-02 Drywell Head Inspection RAI Issuance
ML23257A2192023-09-14014 September 2023
NRR E-mail Capture - Cooper - Final RAI LAR to Adopt TSTF-551, Revision 3
ML22276A1562022-10-0505 October 2022
Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information
ML22208A0642022-07-26026 July 2022
Notification of Inspection and Request for Information for NRC Inspection Report 05000298/2022004
ML22179A3152022-06-28028 June 2022
Notification of Post-Approval Site Inspection for License Renewal (Phase 4) (NRC Inspection Report 05000298/2022011) and Request for Information
ML22010A2632022-01-10010 January 2022
NRR E-mail Capture - Cooper - Final RAI Relief Request RR5-01 Revision 1
ML21321A3742021-11-10010 November 2021
NRR E-mail Capture - Cooper - Final RAI Alternative Request RI5-02 Revision 3
ML21258A2632021-09-15015 September 2021
NRR E-mail Capture - Cooper - Final RAI Alternative Request RS-01
ML21109A2222021-04-15015 April 2021
Email with RFI Document for CNS PIR 2021012
ML21026A3112021-01-27027 January 2021
Notification of NRC Design Bases Assurance Inspection (Team) (NRC Inspection Report 05000298/2021010) and Initial Request for Information
ML20315A3922020-11-10010 November 2020
Email 11-10-2020 - Cooper EP Prog Insp RFI
ML20203M3692020-07-21021 July 2020
NRR E-mail Capture - Cooper - Final RAI License Amendment Request for Approval of EAL Scheme Change (EPID L-LLA-2020-0028)
ML18306A5582018-10-30030 October 2018
Notification of Cyber Security Inspection(Nrc Inspection Report 05000298/2019410) and Request for Information
ML18060A0272018-02-28028 February 2018
Enclosurequest for Additional Information (Letter to J. Shaw Request for Additional Information Regarding Nebraska Public Power District'S Decommissioning Funding Plan Update for Cooper Nuclear Station ISFSI)
ML18037B0002018-02-0606 February 2018
NRR E-mail Capture - Cooper Nuclear Station - Final RAI Relief Requests RR-02 and RR-03 (EPIDs L-2017-LRR-065 and -066)
ML18025C0042018-01-25025 January 2018
Notification of NRC Design Bases Assurance Inspection (Teams) (05000298/2018011) and Initial Request for Information
ML18024A3752018-01-24024 January 2018
NRR E-mail Capture - Cooper Nuclear Station - Final RAI LAR to Adopt TSTF-542 (CAC MG0138; EPID L-2017-LLA-0290)
IR 05000298/20170032017-11-13013 November 2017
NRC Integrated Inspection Report 05000298/2017003 and Independent Spent Fuel Storage Installation Inspection Report 07200066/2017001
ML17177A2432017-06-26026 June 2017
Notification of NRC Design Bases Assurance Inspection (Programs) (05000298/2017007) and Initial Request for Information
ML17024A3292016-12-15015 December 2016
NRR E-mail Capture - Rec 2.1 Seismic: Cooper'S SFP Evaluation
ML16335A0152016-11-29029 November 2016
NRR E-mail Capture - Cooper Nuclear Station - Formal Request for Additional Information Concerning License Amendment Request to Adopt TSTF-425 Revision 3
ML16112A2732016-04-21021 April 2016
Notification of NRC Triennial Fire Protection Baseline Inspection (05000298/2016008) and Request for Information
ML15107A2542015-05-0404 May 2015
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report
ML15051A4872015-02-20020 February 2015
Notification of NRC Component Design Bases Inspection 05000298/2015007 and Initial Request for Information
ML13323A1052013-12-0404 December 2013
Interim Staff Evaluation and Request for Additional Information, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
ML13304B4182013-11-0101 November 2013
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
ML13256A0822013-09-12012 September 2013
Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
ML13246A3482013-08-29029 August 2013
Draft Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
NLS2013082, Letter Requesting Information from the United States Army Corps of Engineers to Provide Response to March 12, 2012 Letter Regarding Enclosure 2, Recommendation 2.1, Flooding2013-08-22022 August 2013
Letter Requesting Information from the United States Army Corps of Engineers to Provide Response to March 12, 2012 Letter Regarding Enclosure 2, Recommendation 2.1, Flooding
ML13155A0112013-06-0303 June 2013
Request for Additional Information Email, 2013 Decommissioning Funding Status Report
ML13144A5202013-05-24024 May 2013
Request for Additional Information Email, Decommissioning Funding Status Report
ML13133A0802013-05-24024 May 2013
(Redacted) - Request for Additional Information, Review of License Renewal Commitment NLS2009100-1 - Core Rim Plate Bolts
ML13095A1602013-04-0404 April 2013
Email, Draft Request for Additional Information - Review of License Renewal Commitment NLS2009100-1 - Core Rim Plate Bolts
ML13059A3452013-03-0808 March 2013
Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation
ML13053A3422013-02-22022 February 2013
E-mail, Draft Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation
ML12338A2642012-12-0303 December 2012
Email, Round 3, Request for Additional Information, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and SRs
ML12312A2812012-11-14014 November 2012
Request for Additional Information, License Amendment Request to Adopt National Fire Protection Agency (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
ML12283A4002012-10-0909 October 2012
Email, Draft Request for Additional Information, License Amendment Request to Adopt National Fire Protection Agency (NFPA)-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
ML12251A0582012-09-0606 September 2012
Request for Additional Information, License Amendment Request, Round 2, Revise Technical Specifications to Implement a 24-Month Fuel Cycle and Adopt TSTF-493, Revision 4, Option a
ML12235A2522012-09-0505 September 2012
Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio
ML12205A2162012-08-10010 August 2012
Request for Additional Information, Round 2, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements
ML1217400512012-06-21021 June 2012
List of Questions for Supplement to Complete Acceptance Review, License Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
ML12157A5412012-06-11011 June 2012
Second Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Value Inservice Testing Program
ML12159A2992012-06-11011 June 2012
Request for Additional Information, Relief Request RI-07 from ASME Code Requirements for Residual Heat Removal Shell Circumferential and Nozzle to Head Welds, Fourth 4th 10-Year Inservice Inspection Interval
ML12153A0642012-05-31031 May 2012
Notification of Inspection (NRC Inspection Report 05000298/2012005) and Request for Information
ML1213905092012-05-18018 May 2012
Email, Draft Request for Additional Information, Second Round, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval
ML1213905112012-05-18018 May 2012
Draft Request for Additional Information, Second Round, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval
ML1213205752012-05-11011 May 2012
Request for Additional Information, Relief Request RI-07 from ASME Code Requirements for Residual Heat Removal Shell Circumferential and Nozzle to Head Welds, Fourth 4th 10-Year Inservice Inspection Interval
2024-01-04
[Table view] |
Text
March 5, 2007 Mr. Stewart B. Minahan Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST - ONSITE SPENT FUEL STORAGE EXPANSION (TAC NO. MD3349)
Dear Mr. Minahan:
By application dated October 17, 2006, Nebraska Public Power District (NPPD, the licensee) requested the U.S. Nuclear Regulatory Commission (NRC) staff approval of an amendment to the Cooper Nuclear Station technical specifications to increase the capacity of the spent fuel storage pool.
The NRC staff has reviewed the information provided in your submittal and determined that additional information is required in order to complete its review. Questions in the enclosed request for additional information (RAI) were discussed in telephone calls with Mr. R. Rogers, et al., of your staff on December 7, 2006, and February 15 and 21, 2007. During a discussion with Mr. Rogers on February 27, 2007, it was agreed that NPPD would provide a response by April 10, 2007, to this RAI.
The NRC staff considers that timely responses to RAIs help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296.
Sincerely,
/RA/
Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
Request for Additional Information cc w/encl: See next page
ML070590230 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NAME FLyon LFeizollahi DTerao DATE 3/5/07 3/5/07 3/5/07 Cooper Nuclear Station cc:
Mr. Ronald D. Asche Mr. H. Floyd Gilzow President and Chief Executive Officer Deputy Director for Policy Nebraska Public Power District Missouri Department of Natural Resources 1414 15th Street P.O. Box 176 Columbus, NE 68601 Jefferson City, MO 65102-0176 Mr. Gene Mace Senior Resident Inspector Nuclear Asset Manager U.S. Nuclear Regulatory Commission Nebraska Public Power District P.O. Box 218 P.O. Box 98 Brownville, NE 68321 Brownville, NE 68321 Regional Administrator, Region IV Mr. John C. McClure U.S. Nuclear Regulatory Commission Vice President and General Counsel 611 Ryan Plaza Drive, Suite 400 Nebraska Public Power District Arlington, TX 76011 P.O. Box 499 Columbus, NE 68602-0499 Director, Missouri State Emergency Management Agency Mr. Paul V. Fleming P.O. Box 116 Licensing Manager Jefferson City, MO 65102-0116 Nebraska Public Power District P.O. Box 98 Chief, Radiation and Asbestos Brownville, NE 68321 Control Section Kansas Department of Health Mr. Michael J. Linder, Director and Environment Nebraska Department of Environmental Bureau of Air and Radiation Quality 1000 SW Jackson P.O. Box 98922 Suite 310 Lincoln, NE 68509-8922 Topeka, KS 66612-1366 Chairman Mr. Donald A. Flater Nemaha County Board of Commissioners Radiation Control Program Director Nemaha County Courthouse Bureau of Radiological Health 1824 N Street Iowa Department of Public Health Auburn, NE 68305 Lucas State Office Building, 5th Floor 321 East 12th Street Ms. Julia Schmitt, Manager Des Moines, IA 50319 Radiation Control Program Nebraska Health & Human Services R & L Mr. Daniel K. McGhee Public Health Assurance Bureau of Radiological Health 301 Centennial Mall, South Iowa Department of Public Health P.O. Box 95007 Lucas State Office Building, 5th Floor Lincoln, NE 68509-5007 321 East 12th Street Des Moines, IA 50319 February 2007
Cooper Nuclear Station cc:
Mr. Keith G. Henke, Planner Mr. John F. McCann, Director Division of Community and Public Health Licensing, Entergy Nuclear Northeast Office of Emergency Coordination Entergy Nuclear Operations, Inc.
930 Wildwood P.O. Box 570 440 Hamilton Avenue Jefferson City, MO 65102 White Plains, NY 10601-1813 Mr. Kevin V. Chambliss, Director of Nuclear Safety Assurance Nebraska Public Power District P.O. Box 98 Brownville, NE 68321 February 2007
REQUEST FOR ADDITIONAL INFORMATION RELATED TO ONSITE SPENT FUEL STORAGE EXPANSION COOPER NUCLEAR STATION DOCKET NO. 50-298 I. The following questions are provided from the Health Physics Branch (IHPB):
- 1. In Section 9.4 of the Holtec Report, you state that the calculated dose rate adjacent to the new fuel racks (if they are completely filled with freshly discharged fuel) would be unacceptably high.
1-a. Provide the current radiation dose rates for those accessible areas adjacent to the area (including any accessible areas below the spent fuel pool (SFP)) where the new fuel racks will be installed.
1-b. For these same areas, provide the calculated dose rates from the proposed new racks (1) if the new racks are completely filled with freshly discharged fuel and (2) if the outer rows of the new racks are loaded with fuel, which has decayed for at least 5 years.
1-c. Provide the number of outer rows, which will be filled with aged fuel to ensure that the dose rates in potentially-occupied areas adjacent to the SFP do not exceed the current radiation dose rates for these areas.
- 2. Provide the expected maximum dose rate above the SFP.
- 3. Describe any radiation surveys that will be performed (from the pool rim or by divers in the pool) to map dose rates in the SFP prior to dive operations.
- 4. Provide a description of any sources of high radiation that may be in the SFP during diving operations for minor modification of the beam segments. Discuss what precautions (such as use of TV monitoring, additional lighting, tethers, use of physical barriers between the divers and high-radiation sources, fuel shuffling, etc.) will be used to ensure that the divers will maintain a safe distance from any high-radiation sources in the SFP. Discuss how you plan to alert divers (e.g., by use of continuous voice communication with the divers) in the event that they inadvertently enter an area of high radiation or if they exceed their predetermined dose limit while performing work in the SFP. Discuss the use of multiple dosimeters on divers who will be working in the SFP. Discuss how divers will be monitored for contamination when they exit the SFP.
- 5. In Section 9.4 of the Holtec Report, you state there are continuous airborne monitors for airborne activities available in the immediate vicinities of the pool.
Describe how these monitors are utilized in the SFP area during the Refueling Floor Operations, including diving operations and SFP rack installations.
- 6. Discuss the removal, decontamination, and disposal of the storage racks for the control rod blades and the drum platform from the shipping cask storage area.
- 7. Discuss how the storage of the additional spent fuel assemblies in the SFP will affect the releases of radioactive gases from the SFP. Specifically address the potential increased releases of Kr-85, I-131, and tritium from the SFP.
- 8. Discuss how the storage of additional spent fuel assemblies in the SFP will affect the release of radioactive liquids from the plant as a result of any expected increase in the change-out frequency of the demineralizer resins for the SFP.
II. The following questions are provided from the Engineering Mechanics Branch (EEMA):
- 1. As noted in Section 1.3 of the Holtec Report, [t]he existing swing bolts are used to fasten the platform to the pool floor rendering them into a fixed appurtenance to the pool slab.
Please provide a summary of the stress analysis of the swing bolts and swing bolt anchorages to the pool slab for the loads transmitted by the Rack A fuel rack and platform. Please provide a drawing showing the anchorage pattern.
- 2. Section 2.1 of the Holtec Report notes that: [a]lthough both rack modules are freestanding, and thus may slide during a seismic event, any significant membrane strains in the pool liner are prevented by the presence of the platforms. As a result, the maximum strain sustained by the liner during a seismic event is assumed to be less than the ultimate strain for the liner material (austenitic stainless steel, ultimate strain $0.38).
Please provide a summary of the stress analysis of the 2 inch thick by 2 -1/2 inch wide cask restraint ring shown in Section 3711 of Burns & Roe Drawing 4288 for the loads induced by Rack B.
- 3. Section 2.2 of the Holtec Report notes that: [b]ecause the platforms are not an integral part of the rack, their stress analysis and structural qualification are not addressed in this licensing report.
Please provide a summary of the stress analyses for the Rack A and B platforms. Please provide the drawings for the platforms.
- 4. Section 8.4 of the Holtec Report documents that a modal analysis was performed on the SFP floor, and: it was determined that the first mode frequency in the vertical direction is 35.4 Hz, which is larger than 33 Hz and, thus, in the rigid range. Therefore, seismic amplification due to slab flexibility is not an issue. These results justify development of equivalent static loads using the zero period accelerations as multipliers.
Table 8.3.1 of the Holtec Report indicates that an uncracked section modulus was used for this computation. Please discuss the appropriateness of using an
uncracked section modulus to calculate the fundamental frequency of the SFP floor.
How does the calculation for the fundamental frequency of the SFP floor consider the static mass of the SFP water? This load does not appear to be listed in Table 8.5.1 of the Holtec Report. Section 2.3.3.2.4 of the Cooper Nuclear Station Updated Safety Analysis Report notes that the SFP contains about 2.1 million pounds (2,100 kips) of water.
- 5. Please discuss any nonconformances that are related to material degradation issues (concrete, rebar) in the SFP.
- 6. Table 6.7.1 of the Holtec Report specifies 4 percent damping for Operating Basis Earthquake (OBE) and 5 percent damping for Safe Shutdown Earthquake (SSE) as input data for the rack seismic analysis. Table 1 of NRC Regulatory Guide 1.61 specifies 2 percent damping for OBE and 4 percent damping for SSE for welded steel structures. Please discuss the appropriateness of the damping values used in the analysis.
III. The following questions are provided from the Steam Generator Tube Integrity and Chemical Engineering Branch (CSGB):
The proposed change revises TS 4.3, Fuel Storage, to reflect the addition of fuel storage capacity in the SFP by adding up to two additional storage racks. The increased fuel capacity involves use of the Metamic neutron absorbing material.
The staff has conditioned prior acceptance of the Metamic material for use in SFPs upon a coupon sampling program (e.g., Clinton, Arkansas Nuclear One) to ensure performance consistent with that described in the engineering reports.
An acceptable coupon sampling program has the following attributes:
C The size and types of coupons are similar in fabrication and layout to the proposed application, including welds or mechanical fasteners and proximity to stainless steel.
C The technique for measuring the initial B4C content of the coupons is described.
C Scratches and other surface anomalies on the coupons simulate as-installed conditions of Metamic panels.
C Justification of the frequency of coupon sampling is provided.
C Tests to be performed on coupons are specified; e.g., weight measurement, measurement of dimensions (length, width and thickness),
and B4C content and acceptance criteria.
- 1. Provide a detailed description of your coupon sampling program.
- 2. Please describe the scope of the receipt inspections performed on the Metamic panels to establish a baseline. In addition, discuss who will perform these receipt inspections and where they will be performed.
- 3. Please discuss the surface preparation or anodizing process that will be used on the Metamic panels? In addition, what cleaning process will be used to ensure sufficient removal of surface contaminants? Please note, the surface preparation for the coupons is to be similar to what is used on the Metamic panels.
- 4. Please discuss how the Metamic panels are to be attached to the new spent fuel racks (welding, mechanical fasteners, etc.). If the Metamic panels are to be welded, what welding process will be used and what weld filler material will be used?
- 5. Given that Metamic is a new material for SFP applications, we request that you submit the results of each surveillance to the staff. The reporting requirements should be addressed in your surveillance program. The reporting requirements should include the baseline inspection results and the results of all subsequent inspections (i.e., visual, length, width, thickness, weight, and neutron absorption).
