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| | number = ML061990634 | | | number = ML061990634 |
| | issue date = 07/24/2006 | | | issue date = 07/24/2006 |
| | title = Duane Arnold, RAI, Proposed Amendment to Revise the Limiting Condition for Operation 3.10.1 | | | title = RAI, Proposed Amendment to Revise the Limiting Condition for Operation 3.10.1 |
| | author name = Spaulding D W | | | author name = Spaulding D |
| | author affiliation = NRC/NRR/ADRO | | | author affiliation = NRC/NRR/ADRO |
| | addressee name = VanMiddlesworth G D | | | addressee name = Vanmiddlesworth G |
| | addressee affiliation = Nuclear Management Co, LLC | | | addressee affiliation = Nuclear Management Co, LLC |
| | docket = 05000331 | | | docket = 05000331 |
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| =Text= | | =Text= |
| {{#Wiki_filter:July 24, 2006Mr. Gary Van MiddlesworthVice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785 | | {{#Wiki_filter:July 24, 2006 Mr. Gary Van Middlesworth Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONALINFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 (TAC NO. MD0293) | | DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 (TAC NO. MD0293) |
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| ==Dear Mr. Van Middlesworth:== | | ==Dear Mr. Van Middlesworth:== |
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| Your letter of March 1, 2006, submitted a proposed amendment to revise the limiting conditionfor operation 3.10.1, to allow ancillary testing to occur during the evolutions associated withperforming the American Society of Mechanical Engineers Code Class I leak test of the reactor pressure vessel, at the Duane Arnold Energy Center. We are reviewing this information, and find that we need additional information as shown in theenclosed request for additional information (RAI). I discussed this RAI with Tony Browning of your organization on July 18, 2006, and he agreed to respond within 30 days of receipt of this RAI. Please contact me at (301) 415-2928 if you have questions.Sincerely,/RA/Deirdre W. Spaulding, Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-331 | | Your letter of March 1, 2006, submitted a proposed amendment to revise the limiting condition for operation 3.10.1, to allow ancillary testing to occur during the evolutions associated with performing the American Society of Mechanical Engineers Code Class I leak test of the reactor pressure vessel, at the Duane Arnold Energy Center. |
| | We are reviewing this information, and find that we need additional information as shown in the enclosed request for additional information (RAI). I discussed this RAI with Tony Browning of your organization on July 18, 2006, and he agreed to respond within 30 days of receipt of this RAI. Please contact me at (301) 415-2928 if you have questions. |
| | Sincerely, |
| | /RA/ |
| | Deirdre W. Spaulding, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331 |
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| ==Enclosure:== | | ==Enclosure:== |
| RAIcc w/encl: See next page Mr. Gary Van MiddlesworthJuly 24, 2006Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785
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| | RAI cc w/encl: See next page |
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| | Mr. Gary Van Middlesworth July 24, 2006 Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONALINFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 (TAC NO. MD0293) | | DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 (TAC NO. MD0293) |
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| ==Dear Mr. Van Middlesworth:== | | ==Dear Mr. Van Middlesworth:== |
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| Your letter of March 1, 2006, submitted a proposed amendment to revise the limiting conditionfor operation 3.10.1, to allow ancillary testing to occur during the evolutions associated withperforming the American Society of Mechanical Engineers Code Class I leak test of the reactor pressure vessel, at the Duane Arnold Energy Center. We are reviewing this information, and find that we need additional information as shown in theenclosed request for additional information (RAI). I discussed this RAI with Tony Browing of your organization on July 18, 2006, and he agreed to respond within 30 days of receipt of this RAI. Please contact me at (301) 415-2928 if you have questions.Sincerely,/RA/Deirdre W. Spaulding, Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-331 | | Your letter of March 1, 2006, submitted a proposed amendment to revise the limiting condition for operation 3.10.1, to allow ancillary testing to occur during the evolutions associated with performing the American Society of Mechanical Engineers Code Class I leak test of the reactor pressure vessel, at the Duane Arnold Energy Center. |
| | We are reviewing this information, and find that we need additional information as shown in the enclosed request for additional information (RAI). I discussed this RAI with Tony Browing of your organization on July 18, 2006, and he agreed to respond within 30 days of receipt of this RAI. Please contact me at (301) 415-2928 if you have questions. |
| | Sincerely, |
| | /RA/ |
| | Deirdre W. Spaulding, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331 |
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| ==Enclosure:== | | ==Enclosure:== |
| RAIcc w/encl: See next page DISTRIBUTION
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| :PUBLICLPL3-1 R/FRidsNrrPMDSpauldingRidsNrrLATHarris RidsNrrDorlLpleRidsOgcRpRidsAcrsAcnwMailCenterRidsRgn3MailCenterRidsNrrDorlDprALewinJGilmerTBoyceADAMS Accession Number: ML061990634OFFICENRR/LPL3-1/PMNRR/LPL3-1/LANRR/LPL3-1/BCNAMEDSpauldingTHarrisLRaghavan DATE07/21/0607/20/0607/24/06OFFICIAL RECORD COPY REQUEST FOR ADDITIONAL INFORMATIONRELATED TO THE PROPOSED AMENDMENT TOREVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1DUANE ARNOLD ENERGY CENTERDOCKET NO. 50-3311. LCO 3.10.1 Rev 3.1a would allow testing in Mode 4 with average reactor coolanttemperature drifting greater than 200 F as a result of decay heat. Primary containment requirements are relaxed in LCO 3.10.1 Rev 3.0 with the reasoning in the technicalspecification (TS) Bases that average reactor coolant temperature is greater than 200 F as aresult of testing and not due to significant decay heat. Please explain why it is acceptable to be in Mode 4 (with average reactor coolant temperature greater than 200 F) vice Mode 3 with the presence of decay heat contributing to an increase in the average reactor coolant temperature.2. LCO 3.4.7 "RCS Specific Activity," is normally not required in Mode 4 because the reactor isnormally not pressurized. Please provide justification for not including LCO 3.4.7 under LCO 3.10.1 Rev 3.1a requirements when in Mode 4 with average reactor coolant temperaturegreater than 200 F.3. The Bases for TS 3.10.1 Rev 3.1a discusses conducting other unnamed testing while the TS 3.10.1 Rev 3.1a specifically mentions conducting only inservice leak or hydrostatic tests and control rod scram time tests. Please elaborate on the intent of the TS and Bases as written with regards to "other testing."4. The use of the verbiage "as a consequence of" in the LCO under TS 3.10.1 Rev 3.1a couldresult in steady state Mode 4 with reactor coolant temperature > 200 F even though testing is over and no longer being conducted. This seems to be the reasoning for eliminating the statement in the Bases for TS 3.10.1 Rev 3.0 which states that normal Mode 4 requirementsare in effect immediately prior to and immediately after LCO 3.10.1 operations. Please elaborate on what would require returning to normal Mode 4 requirements after testing is completed.
| | RAI cc w/encl: See next page DISTRIBUTION: |
| | PUBLIC LPL3-1 R/F RidsNrrPMDSpaulding RidsNrrLATHarris RidsNrrDorlLple RidsOgcRp RidsAcrsAcnwMailCenter RidsRgn3MailCenter RidsNrrDorlDpr ALewin JGilmer TBoyce ADAMS Accession Number: ML061990634 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC NAME DSpaulding THarris LRaghavan DATE 07/21/06 07/20/06 07/24/06 OFFICIAL RECORD COPY |
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| | REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331 |
| | : 1. LCO 3.10.1 Rev 3.1a would allow testing in Mode 4 with average reactor coolant temperature drifting greater than 200 F as a result of decay heat. Primary containment requirements are relaxed in LCO 3.10.1 Rev 3.0 with the reasoning in the technical specification (TS) Bases that average reactor coolant temperature is greater than 200 F as a result of testing and not due to significant decay heat. Please explain why it is acceptable to be in Mode 4 (with average reactor coolant temperature greater than 200 F) vice Mode 3 with the presence of decay heat contributing to an increase in the average reactor coolant temperature. |
| | : 2. LCO 3.4.7 RCS Specific Activity, is normally not required in Mode 4 because the reactor is normally not pressurized. Please provide justification for not including LCO 3.4.7 under LCO 3.10.1 Rev 3.1a requirements when in Mode 4 with average reactor coolant temperature greater than 200 F. |
| | : 3. The Bases for TS 3.10.1 Rev 3.1a discusses conducting other unnamed testing while the TS 3.10.1 Rev 3.1a specifically mentions conducting only inservice leak or hydrostatic tests and control rod scram time tests. Please elaborate on the intent of the TS and Bases as written with regards to other testing. |
| | : 4. The use of the verbiage as a consequence of in the LCO under TS 3.10.1 Rev 3.1a could result in steady state Mode 4 with reactor coolant temperature > 200 F even though testing is over and no longer being conducted. This seems to be the reasoning for eliminating the statement in the Bases for TS 3.10.1 Rev 3.0 which states that normal Mode 4 requirements are in effect immediately prior to and immediately after LCO 3.10.1 operations. Please elaborate on what would require returning to normal Mode 4 requirements after testing is completed. |
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| ENCLOSURE Duane Arnold Energy Center cc: | | ENCLOSURE Duane Arnold Energy Center cc: |
| Mr. J. A. StallSenior Nice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. M. S. RossManaging Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. R. E. HelfrichSenior Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. W. E. WebsterVice President, Nuclear Operations Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420John BjorsethSite Director Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324Steven R. CatronManager, Regulatory Affairs Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324U. S. Nuclear Regulatory CommissionResident Inspector's Office Rural Route #1 Palo, IA 52324Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville RoadLisle, IL 60532-4351Mr. M. WarnerVice President, Nuclear Operations Support Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. D. A. CurtlandPlant Manager Duane Arnold Energy Center 3277 DAEC Rd. | | Mr. J. A. Stall Regional Administrator, Region III Senior Nice President, Nuclear and Chief U.S. Nuclear Regulatory Commission Nuclear Officer Suite 210 Florida Power & Light Company 2443 Warrenville Road P. O. Box 14000 Lisle, IL 60532-4351 Juno Beach, FL 33408-0420 Mr. M. S. Ross Mr. M. Warner Managing Attorney Vice President, Nuclear Operations Florida Power & Light Company Support P. O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408-0420 P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. R. E. Helfrich Senior Attorney Mr. D. A. Curtland Florida Power & Light Company Plant Manager P. O. Box 14000 Duane Arnold Energy Center Juno Beach, FL 33408-0420 3277 DAEC Rd. |
| Palo, IA 52324-9785Mr. R. S. KundalkarVice President, Nuclear Engineering Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Daniel McGheeUtilities Division Iowa Department of Commerce Lucas Office Buildings, 5th Floor Des Moines, IA 50319Chairman, Linn CountyBoard of Supervisors 930 1st Street SW Cedar Rapids, IA 52404}} | | Palo, IA 52324-9785 Mr. W. E. Webster Vice President, Nuclear Operations Mr. R. S. Kundalkar Florida Power & Light Company Vice President, Nuclear Engineering P. O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408-0420 P. O. Box 14000 Juno Beach, FL 33408-0420 John Bjorseth Site Director Daniel McGhee Duane Arnold Energy Center Utilities Division 3277 DAEC Road Iowa Department of Commerce Palo, IA 52324 Lucas Office Buildings, 5th Floor Des Moines, IA 50319 Steven R. Catron Manager, Regulatory Affairs Chairman, Linn County Duane Arnold Energy Center Board of Supervisors 3277 DAEC Road 930 1st Street SW Palo, IA 52324 Cedar Rapids, IA 52404 U. S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1 Palo, IA 52324}} |
Letter Sequence RAI |
|---|
TAC:MD0293, Use of TS 3.10.1 for SCRAM Time Testing Activities (Approved, Closed) |
|
MONTHYEARNG-06-0250, Technical Specification Change Request (TSCR-078): Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities, Affected Technical Specifications: Section 3.10.12006-03-0101 March 2006
Technical Specification Change Request (TSCR-078): Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities, Affected Technical Specifications: Section 3.10.1
Project stage: Other
ML0619906342006-07-24024 July 2006
RAI, Proposed Amendment to Revise the Limiting Condition for Operation 3.10.1
Project stage: RAI
NG-06-0516, Response to Request for Additional Information Related to Proposed Amendment to Revise Limiting Condition for Operation 3.10.12006-08-17017 August 2006
Response to Request for Additional Information Related to Proposed Amendment to Revise Limiting Condition for Operation 3.10.1
Project stage: Response to RAI
ML0629903782006-11-0202 November 2006
TSTF-484 LAR SE
Project stage: Other
ML0703804842007-02-0505 February 2007
Technical Specification, System Leakage and Hydrostatic Testing Operation
Project stage: Other
ML0635204082007-02-0505 February 2007
Issuance of Amendment, System Leakage and Hydrostatic Testing Operation
Project stage: Approval
2006-07-24
[Table View] |
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Category:Letter
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024
Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)
NG-23-0010, Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-12-0606 December 2023
Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule
NG-23-0009, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023
Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule
ML23201A0872023-08-0303 August 2023
Audit Plan in Support of Review of License Amendment
NG-23-0006, Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-05-23023 May 2023
Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update
ML23137A1672023-05-11011 May 2023
Submittal of 2022 Annual Radiological Environmental Operating Report
NG-23-0004, 2022 Annual Radioactive Material Release Report2023-04-25025 April 2023
2022 Annual Radioactive Material Release Report
NG-23-0003, 2022 Annual Exposure Report - Form 5s2023-04-21021 April 2023
2022 Annual Exposure Report - Form 5s
NG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023
10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report
NG-23-0001, 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report2023-03-27027 March 2023
2023 Annual Decommissioning and Spent Fuel Management Funding Status Report
L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023
and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)
ML22361A1022023-02-24024 February 2023
Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities
ML22339A0012022-12-22022 December 2022
Acceptance of Requested Licensing Action Amendment Request for Common Emergency Plan
IR 05000331/20220032022-12-13013 December 2022
NRC Inspection Report No. 05000331/2022003 (Drss)
ML22285A0072022-10-13013 October 2022
NRC Analysis of NextEra Energy Duane Arnold'S Decommissioning Funding Status Report, Docket No. 50-331
IR 05000331/20220022022-07-13013 July 2022
NRC Inspection Report Nos. 05000331/2022002(DNMS) and 07200032/2022002(DNMS)
ML22090A1922022-05-26026 May 2022
Letter to B. Coffey, FPL from M. Doell - Duane Arnold Post Shutdown Activities Report Review Letter
ML22132A2872022-05-24024 May 2022
ISFSI DQAP Approval Letter
ML22111A0332022-05-20020 May 2022
Operating License Page Correction Letter to B. Coffey, Florida Power and Light, from M. Doell
NG-22-0055, Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan2022-05-20020 May 2022
Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan
ML22089A0492022-05-12012 May 2022
Sfmp Review Letter
NG-22-0053, 2021 Annual Radiological Environmental Operating Report2022-05-0606 May 2022
2021 Annual Radiological Environmental Operating Report
NG-22-0052, Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative2022-05-0404 May 2022
Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative
IR 05000331/20224012022-04-27027 April 2022
Decommissioning Security Inspection Report 05000331/2022401
NG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 02022-04-26026 April 2022
Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0
NG-22-0049, 2021 Annual Radioactive Material Release Report2022-04-26026 April 2022
2021 Annual Radioactive Material Release Report
L-2022-068, NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 22022-04-25025 April 2022
NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 2
ML22066A7632022-04-25025 April 2022
ISFSI-Only Emergency Plan License Amendment Approval
NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 02022-04-13013 April 2022
Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 0
NG-22-0047, Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2022-04-11011 April 2022
Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool
NG-22-0042, Registration of Independent Spent Fuel Installation Storage Casks2022-04-0808 April 2022
Registration of Independent Spent Fuel Installation Storage Casks
NG-22-0041, and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report2022-03-31031 March 2022
and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report
NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022
2021 Annual Exposure Report - Form 5s
NG-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022
Registration of Independent Spent Fuel Installation Storage Casks
ML22080A1822022-03-22022 March 2022
Letter to B. Coffey from M. Doell - Duane Arnold ISFSI QAPD RAI Letter
L-2022-012, Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3)2022-03-16016 March 2022
Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3)
ML22059A7462022-03-10010 March 2022
ISFSI-Only Physical Security Plan License Amendment Approval
NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022
Registration of Independent Spent Fuel Installation Storage Casks
IR 05000331/20220012022-03-0404 March 2022
Subject: NRC Inspection Report Nos. 05000331/2022001(DNMS) and 07200032/2022001(DNMS)
NG-22-0021, Registration of Independent Spent Fuel Installation Storage Casks2022-02-24024 February 2022
Registration of Independent Spent Fuel Installation Storage Casks
ML22007A2722022-02-11011 February 2022
Cover Letter - NRC Duane Arnold Exemption Issuance
NG-22-0014, Registration of Independent Spent Fuel Installation Storage Casks2022-02-10010 February 2022
Registration of Independent Spent Fuel Installation Storage Casks
ML22028A2822022-02-0303 February 2022
Defueled Physical Security Plan License Amendment Approval
ML22033A0802022-02-0202 February 2022
Supplement to License Amendment Request (TSCR-188): Proposed Change to the Physical Security Plan for the Post-Shutdown and Permanently Defueled Condition
IR 05000331/20210012022-01-25025 January 2022
NRC Inspection Report Nos. 05000331/2021001(DNMS); 07200032/2021001(DNMS); and 07200032/2021002(DNMS) - Duane Arnold Energy Center
ML21172A2172022-01-21021 January 2022
Issuance of License Amendment to Adopt ISFSI-Only Technical Specifications
NG-22-0009, Registration of Independent Spent Fuel Installation Storage Casks2022-01-20020 January 2022
Registration of Independent Spent Fuel Installation Storage Casks
NG-22-0001, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister2022-01-0606 January 2022
Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister
NG-21-0038, Registration of Independent Spent Fuel Installation Storage Casks2021-12-22022 December 2021
Registration of Independent Spent Fuel Installation Storage Casks
NG-21-0035, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-12-10010 December 2021
Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister
2024-01-25
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML22005A0862022-01-0404 January 2022
1-4-2022 Email Communication to Duane Arnold Regarding Its ISFSI Related Exemption Request on Supplemental Information Needed
ML21335A0712021-12-0101 December 2021
Request for Additional Information - Duane Arnold Energy Center ISFSI Only Emergency Plan
ML21335A0702021-12-0101 December 2021
Cover Letter to B. Coffey from K. Conway - Duane Arnold Energy Center RAI Re License Amendment Request for ISFSI Only Emergency Plan
ML21250A3002021-09-0808 September 2021
Defueled Physical Security Plan RAI Cover Letter
ML21006A4052021-01-0606 January 2021
NRR E-mail Capture - Final RAI - Duane Arnold - Post-Shutdown Decommissioning Activities Report
ML20316A0212020-11-10010 November 2020
NRR E-mail Capture - Final RAI - Duane Arnold - Duane Arnold Amendment for Proposed Defueled EP and EAL Scheme
ML20153A3772020-05-28028 May 2020
NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center Quality Assurance Topical Report (FPL-3) - EPID L-2020-LLQ-0002)
ML20141L8132020-05-19019 May 2020
NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center (DAEC) - Exemption Request for Security Training Requirements Due to COVID-19 Pandemic - EPID L-2020-LLE-0042 to 45, L-2020-LLE-0051
ML20133K0482020-05-14014 May 2020
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML20127H8662020-05-0505 May 2020
NRR E-mail Capture - Duane Arnold Energy Center (DAEC) - Request for Additional Information (RAI) - Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 1O CFR 50.75(h)(1)(iv) - EPID L-2020-LLE-0011
ML19280A0352019-10-0404 October 2019
NRR E-mail Capture - Final - RAI Related to License Amendment Request (TSCR-182) for Proposed Changes to the Emergency Plan for Permanently Defueled Conditions at Duane Arnold Energy Center (DAEC) - L-2019-LLA-0075
ML18283B0522018-10-0909 October 2018
NRR E-mail Capture - Final Second Round - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420
ML18255A2922018-09-11011 September 2018
NRR E-mail Capture - Draft Second Round - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420
ML18247A2002018-08-21021 August 2018
E-Mailed Request for Information for Duane Arnold, Dated 08/21/18 (DRS-M.Holmberg)
ML18166A2982018-06-15015 June 2018
NRR E-mail Capture - Draft Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420
ML18088A0102018-03-28028 March 2018
NRR E-mail Capture - Final RAI for Duane Arnold (DAEC) 5th-10 Year ISI (RR-05)
ML18058A0522018-02-27027 February 2018
Enclosurequest for Additional Information (Letter: RAI Regarding Florida Power and Light/Nextera Decommissioning Funding Plan Updates for St. Lucie, Units 1 & 2; Seabrook Station; Duane Arnold Energy Center; and Point Beach, Units 1 and 2)
ML18037B0032018-02-0606 February 2018
NRR E-mail Capture - Draft Request for Additional Information - Duane Arnold Energy Center (DAEC) - License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, ECCS-Operating - EPID L-2017-LLA-0288
ML17347A8752017-12-12012 December 2017
NRR E-mail Capture - Second Round of Request for Additional Information - Duane Arnold Energy Center (DAEC) - LAR to Adopt TST-542, Revision 2, Reactor Pressure Vessel Water Inventory Control - CAC No. MF9829
ML17277A3652017-10-0404 October 2017
NRR E-mail Capture - Final Request for Additional Information - Duane Arnold - Application to Revise Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control - CAC No. MF9829
ML17240A0082017-08-25025 August 2017
NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center (DAEC) - Fifth Ten Year Service Inspection Interval - Relief Request No. RR-04, Rev. 0 - Proposed Alternative for Seal Weld Procedure Qualification - MF937
ML17220A3332017-08-0808 August 2017
NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center - Relief Request No. RR-03 - Alternative Requirements for Nozzle Inner Radius and Nozzle-To-Shell Welds - CAC No. MF9374
ML17159A7962017-06-0707 June 2017
17 Duane Arnold Energy Center - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg)
ML17068A0632017-03-0808 March 2017
NRR E-mail Capture - Final - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - Revision to Staff Augmentation Times in the Duane Arnold Energy Center (DAEC) Emergency Plan (Eplan) - MF8390
ML16333A4622016-11-28028 November 2016
NRR E-mail Capture - Final Request for Additional Information - Duane Arnold Energy Center - LAR - SFP Criticality - MF7486
ML16326A0092016-11-18018 November 2016
NRR E-mail Capture - Request for Additional Information Re. Nextera/Fpl LAR to Adopt TSTF-545 - CACs MF8203, MF8204, MF8208, and MF8209
ML16313A0742016-11-0808 November 2016
NextEra Audit Plan Nov 2016 (DAEC SFP Criticality LAR)
ML16075A0032016-03-14014 March 2016
NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center - LAR to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specifications 2.1.1, Reactor Core Safety Limits - MF6618
ML16074A3142016-03-14014 March 2016
NRR E-mail Capture - Second Round RAIs - Duane Arnold Energy Center - LAR (TSCR-143) to Extend Containment Leakage Test Frequency - MF6619
ML16022A0092016-01-21021 January 2016
NRR E-mail Capture - Request for Additional Information - LAR to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report - MF6617
ML16021A0122016-01-21021 January 2016
Request for Additional Information by the Containment & Ventilation Branch and PRA Licensing Branch License Amendment Request - Extension of the 10 CFR 50 Appendix J Containment Type a & Type C Test Intervals
ML16014A6962016-01-0707 January 2016
E-Mail: Duane Arnold, MOD/50.59 Inspection Request for Information (Jsp)
ML16005A6082015-12-24024 December 2015
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ML15175A0652015-06-23023 June 2015
Ltr. 06/23/15 Duane Arnold Energy Center - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information Inspection Report 05000331/2015003 (Axd)
ML14057A7562014-02-25025 February 2014
14 Duane Arnold CDBI Request for Information
ML14031A1462014-01-29029 January 2014
Update to NextEra Energy Duane Arnold, Llc'S Response to NRC Request for Additional Information Associated with Near-Term Task Force Recommendations
ML13323B4432013-11-26026 November 2013
Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation
ML13255A1982013-09-16016 September 2013
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ML13175A3932013-06-27027 June 2013
Request for Additional Information for Review Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
ML13154A5112013-06-0404 June 2013
Rai'S Following Ifib Analysis of NextEra Energy'S 2013 Decommissioning Funding Status Reports for Duane Arnold Energy Center and Point Beach Units 1 and 2
ML12107A0592012-04-11011 April 2012
NRR E-mail Capture - ME7246 - DAEC - Request for Additional Information (RAI) Relief Requests NDR-R003, R010, R011, R014, R015
ML12056A0502012-03-12012 March 2012
Enclosure 4 - Recommendation 2.3: Flooding
ML12056A0482012-03-12012 March 2012
Enclosure 2 - Recommendation 2.1: Flooding
ML12056A0472012-03-12012 March 2012
Enclosure 1 - Recommendation 2.1: Seismic
ML12056A0492012-03-12012 March 2012
Enclosure 3 - Recommendation 2.3: Seismic
ML12056A0512012-03-12012 March 2012
Enclosure 5 - Recommendation 9.3: Emergency Preparedness
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Request for Additional Information Amendment to Change Emergency Action Levels
ML12011A0602012-01-0404 January 2012
NRR E-mail Capture - ME6508 - DAEC - Emergency Action Level (EAL) Changes
ML1132105812011-11-28028 November 2011
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ML11147A1142011-06-0808 June 2011
Request for Additional Information Regarding License Amendment Request for Approval of Cyber Security Plan
2022-01-04
[Table view] |
Text
July 24, 2006 Mr. Gary Van Middlesworth Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 (TAC NO. MD0293)
Dear Mr. Van Middlesworth:
Your letter of March 1, 2006, submitted a proposed amendment to revise the limiting condition for operation 3.10.1, to allow ancillary testing to occur during the evolutions associated with performing the American Society of Mechanical Engineers Code Class I leak test of the reactor pressure vessel, at the Duane Arnold Energy Center.
We are reviewing this information, and find that we need additional information as shown in the enclosed request for additional information (RAI). I discussed this RAI with Tony Browning of your organization on July 18, 2006, and he agreed to respond within 30 days of receipt of this RAI. Please contact me at (301) 415-2928 if you have questions.
Sincerely,
/RA/
Deirdre W. Spaulding, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
RAI cc w/encl: See next page
Mr. Gary Van Middlesworth July 24, 2006 Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 (TAC NO. MD0293)
Dear Mr. Van Middlesworth:
Your letter of March 1, 2006, submitted a proposed amendment to revise the limiting condition for operation 3.10.1, to allow ancillary testing to occur during the evolutions associated with performing the American Society of Mechanical Engineers Code Class I leak test of the reactor pressure vessel, at the Duane Arnold Energy Center.
We are reviewing this information, and find that we need additional information as shown in the enclosed request for additional information (RAI). I discussed this RAI with Tony Browing of your organization on July 18, 2006, and he agreed to respond within 30 days of receipt of this RAI. Please contact me at (301) 415-2928 if you have questions.
Sincerely,
/RA/
Deirdre W. Spaulding, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsNrrPMDSpaulding RidsNrrLATHarris RidsNrrDorlLple RidsOgcRp RidsAcrsAcnwMailCenter RidsRgn3MailCenter RidsNrrDorlDpr ALewin JGilmer TBoyce ADAMS Accession Number: ML061990634 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC NAME DSpaulding THarris LRaghavan DATE 07/21/06 07/20/06 07/24/06 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331
- 1. LCO 3.10.1 Rev 3.1a would allow testing in Mode 4 with average reactor coolant temperature drifting greater than 200 F as a result of decay heat. Primary containment requirements are relaxed in LCO 3.10.1 Rev 3.0 with the reasoning in the technical specification (TS) Bases that average reactor coolant temperature is greater than 200 F as a result of testing and not due to significant decay heat. Please explain why it is acceptable to be in Mode 4 (with average reactor coolant temperature greater than 200 F) vice Mode 3 with the presence of decay heat contributing to an increase in the average reactor coolant temperature.
- 2. LCO 3.4.7 RCS Specific Activity, is normally not required in Mode 4 because the reactor is normally not pressurized. Please provide justification for not including LCO 3.4.7 under LCO 3.10.1 Rev 3.1a requirements when in Mode 4 with average reactor coolant temperature greater than 200 F.
- 3. The Bases for TS 3.10.1 Rev 3.1a discusses conducting other unnamed testing while the TS 3.10.1 Rev 3.1a specifically mentions conducting only inservice leak or hydrostatic tests and control rod scram time tests. Please elaborate on the intent of the TS and Bases as written with regards to other testing.
- 4. The use of the verbiage as a consequence of in the LCO under TS 3.10.1 Rev 3.1a could result in steady state Mode 4 with reactor coolant temperature > 200 F even though testing is over and no longer being conducted. This seems to be the reasoning for eliminating the statement in the Bases for TS 3.10.1 Rev 3.0 which states that normal Mode 4 requirements are in effect immediately prior to and immediately after LCO 3.10.1 operations. Please elaborate on what would require returning to normal Mode 4 requirements after testing is completed.
ENCLOSURE Duane Arnold Energy Center cc:
Mr. J. A. Stall Regional Administrator, Region III Senior Nice President, Nuclear and Chief U.S. Nuclear Regulatory Commission Nuclear Officer Suite 210 Florida Power & Light Company 2443 Warrenville Road P. O. Box 14000 Lisle, IL 60532-4351 Juno Beach, FL 33408-0420 Mr. M. S. Ross Mr. M. Warner Managing Attorney Vice President, Nuclear Operations Florida Power & Light Company Support P. O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408-0420 P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. R. E. Helfrich Senior Attorney Mr. D. A. Curtland Florida Power & Light Company Plant Manager P. O. Box 14000 Duane Arnold Energy Center Juno Beach, FL 33408-0420 3277 DAEC Rd.
Palo, IA 52324-9785 Mr. W. E. Webster Vice President, Nuclear Operations Mr. R. S. Kundalkar Florida Power & Light Company Vice President, Nuclear Engineering P. O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408-0420 P. O. Box 14000 Juno Beach, FL 33408-0420 John Bjorseth Site Director Daniel McGhee Duane Arnold Energy Center Utilities Division 3277 DAEC Road Iowa Department of Commerce Palo, IA 52324 Lucas Office Buildings, 5th Floor Des Moines, IA 50319 Steven R. Catron Manager, Regulatory Affairs Chairman, Linn County Duane Arnold Energy Center Board of Supervisors 3277 DAEC Road 930 1st Street SW Palo, IA 52324 Cedar Rapids, IA 52404 U. S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1 Palo, IA 52324
