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| | number = ML120120318 | | | number = ML120120318 |
| | issue date = 01/17/2012 | | | issue date = 01/17/2012 |
| | title = Duane Arnold Energy Center - Request for Additional Information Amendment to Change Emergency Action Levels | | | title = Request for Additional Information Amendment to Change Emergency Action Levels |
| | author name = Feintuch K D | | | author name = Feintuch K |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Wells P | | | addressee name = Wells P |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 January 17, 2012 Mr. Peter Wells Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785 DUANE ARNOLD ENERGY CENTER -REQUEST FOR ADDITIONAL INFORMATION RE: AMENDMENT TO CHANGE EMERGENCY ACTION LEVELS (T AC ME6508) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 17, 2012 Mr. Peter Wells Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785 |
| | |
| | ==SUBJECT:== |
| | DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION RE: AMENDMENT TO CHANGE EMERGENCY ACTION LEVELS (TAC ME6508) |
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| ==Dear Mr. Wells:== | | ==Dear Mr. Wells:== |
| By letter dated May 31, 2011 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 111540279 [package]), NextEra Energy Duane Arnold, LLC (the licensee) requested an amendment to the operating license for the Duane Arnold Energy Center (DAEC) to revise their emergency plan. Specifically, the licensee requested prior approval for a number of changes to their emergency action levels (EALs), which are actually contained in their emergency plan implementing procedures but are considered an integral part of the DAEC emergency plan and is controlled accordingly. The NRC staff has determined that it needs additional information to complete its review. On January 4, 2012, the NRC staff transmitted a draft Request for Additional Information (RAI) (ADAMS Accession No. ML 12011A060) and discussed the draft RAI with Mr. Thomas Byrne, a member of your staff in a conference call on January 10, 2012. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. Enclosed please find the final RAI items. Your staff agreed that you can provide your response within 30 days of the date of this letter. Please feel free to contact me if you need further clarification of the RAt Sincerely, Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331 | | |
| | By letter dated May 31, 2011 (Agencywide Document Access and Management System (ADAMS) Accession No. ML111540279 [package]), NextEra Energy Duane Arnold, LLC (the licensee) requested an amendment to the operating license for the Duane Arnold Energy Center (DAEC) to revise their emergency plan. Specifically, the licensee requested prior approval for a number of changes to their emergency action levels (EALs), which are actually contained in their emergency plan implementing procedures but are considered an integral part of the DAEC emergency plan and is controlled accordingly. |
| | The NRC staff has determined that it needs additional information to complete its review. On January 4, 2012, the NRC staff transmitted a draft Request for Additional Information (RAI) |
| | (ADAMS Accession No. ML12011A060) and discussed the draft RAI with Mr. Thomas Byrne, a member of your staff in a conference call on January 10, 2012. |
| | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. |
| | Enclosed please find the final RAI items. Your staff agreed that you can provide your response within 30 days of the date of this letter. Please feel free to contact me if you need further clarification of the RAt Sincerely, Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331 |
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| ==Enclosure:== | | ==Enclosure:== |
| As Stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION DUANE ARNOLD ENERGY CENTER LICENSE AMENDMENT REQUEST TO REVISE EMERGENCY PLAN DOCKET NO. 50-331 By letter dated May 31,2011 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 111540279 [packageD, NextEra Energy Duane Arnold, LLC requested an amendment to the operating license for the Duane Arnold Energy Center (DAEC) to revise their emergency plan. Specifically, the licensee requested prior approval for a number of changes to their emergency action levels (EALs), which are actually contained in their emergency plan implementing procedures but are considered an integral part of the DAEC emergency plan and is controlled accordingly. The licensee stated that the license amendment request was for revision of selected EALs and not the entire EAL scheme. However, in effect, the licensee actually submitted their entire EAL scheme and is therefore the scope of this review, i.e., the acceptability of the proposed EAL scheme to meet the standards of 10 CFR 50.47 and the requirements of 10 CFR Appendix E. In addition, the staff noted numerous changes to the previously approved EAL scheme that were not specifically noted as those requiring prior NRC approval. These changes were also reviewed as part of this license amendment due to the importance of ensuring an acceptable EAL scheme is in place as all offsite actions are predicated on timely and accurate EAL classifications. DAEC's letter stated that the current DAEC EAL scheme is based on generic development guidance from Nuclear Energy Institute (NEI) document entitled NEI-99-01, "Methodology for Development of Emergency Action Levels," Revision 4, January 2003, (ADAMS Accession No. ML041470143). Since 1992, numerous enhancements and clarification efforts have been made to the generic EAL development guidance resulting in the most recent document, NEI 99-01, Revision 5, "Methodology for Development of Emergency Action Levels," (ADAMS Accession No. ML080450149), which was found to be acceptable for use as generic EAL development guidance by the Nuclear Regulatory Commission (NRC) staff by letter dated . February 22, 2008 (ADAMS Accession No. ML080430535). The proposed EAL scheme was developed using the generic development guidance from NEI 99-01, Revision 5 with numerous differences and deviations based upon design criteria applicable to the site as well as licensee preferences for terminology, format, and other licensee-desired modifications to the generic EAL scheme development guidance provided in NEI 99-01 Revision 5. Attached are the requests for additional information (RAJ) items to facilitate the technical review being conducted by the Operating Reactor Licensing and Outreach Branch staff. Timely and accurate response to these draft RAls is requested. Enclosure Section 3.0 of Enclosure 1, "Evaluation of Proposed Change" the last sentence in the last paragraph states that any changes to the approved ICs [initiating conditions) and EALs will be made in accordance with 10 CFR SO.S4(q). It is the expectation of the staff that changes to the EAL basis information and operating modes will be controlled in the same way as any changes to the approved ICs and EALs. Please explain the rationale for not controlling the EAL Basis Document, as a whole, in accordance with 10 CFR SO.S4(q) or revise this statement accordingly. EAL RU2.2: The use of "offscale high" readings for EAL thresholds is problematic as it is difficult to differentiate between failed instrumentation and actual plant conditions. Please explain how you will differentiate between the two, in the time allowed, for EAL declaration purposes and how this wording will not result in erroneous declarations, or revise accordingly. EAL RA2: The staff requires further justification for the removal of the level threshold previously approved for EAL RA2.3. The proposed justification for the change is confusing in that it uses a calculation as a basis for the change when in fact there are three unique EAL thresholds expected for this EAL. One is based upon a valid Hi-Rad alarm from 9178, a valid reading> 100 millirem/hr from RM-9178, and indication of lowering fuel pool water level from L1-3413. Redundancy is expected for this EAL due to the significance of the concern and the availability of instrumentation. Please provide further justification that supports this revision, or revise accordingly. EAL RA3: Please explain why the Secondary Alarm Station is used as a threshold for this EAL as this EAL only requires either the Control Room, and either the Central Alarm Station or Secondary Alarm Station, not both (typically). Please justify or revise accordingly. EAL CG1: The staff noted an apparent typographical error in the IC. In addition, the staff recommends developing this EAL using the table as provided in the endorsed EAL scheme development guidance as it aids in clarifying the logic for this EAL, however, the staff has no technical opposition to the proposed format and wording. Also, please move the wording " .. .for 30 minutes or longer" from the bulleted list of conditions provided in CG 1.2 to the threshold for "RPV level cannot be monitored." This is a known error in the guidance document which will be corrected in a future revision. EAL EU1: Please provide basis information related to how security events at the ISFSI [independent spent fuel storage installations] are classified. EAL HU2.1: Note that consideration of"... adjacent areas" was removed as history had shown this to be an area of confusion throughout the nuclear industry and resulted in a delay in classification in some cases. EAL HA 1: Please be aware that the areas of concern are expected to be areas where equipment necessary for safe operation, shutdown, and/or cooldown are located AND where the equipment is at risk from the given hazard. For example, not all areas are susceptible to vehicle crashes, high winds, tornados, or turbine blade failure. Please ensure to consider this when developing the list. | | As Stated cc w/encl: Distribution via Listserv |
| -EAL HA2: Please provide the list of areas applicable to this EAL. 10. EAL Please revise the list of areas applicable to this EAL to ensure consistent, and accurate, EAL declaration. Only those areas that contain equipment that must be operated locally for safe operation. safe shutdown, or safe cooldown should be listed. If an area does not contain equipment that must be operated locally. then consideration for not including this area should be given. Note that the need to operate the equipment is not a threshold, i.e., the impediment to access an area, developed as per the above guidance. is the expectation for this EAL. Also. consider adding guidance information that allows the decision-maker to use reasonable judgment when considering declaring this EAL. For example, a small CO2 bottle leaking in a large room/area may not warrant declaration. | | |
| Januasy 17, 2012 Mr. Peter Wells Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785 DUANE ARNOLD ENERGY CENTER -REQUEST FOR ADDITIONAL INFORMATION RE: AMENDMENT TO CHANGE EMERGENCY ACTION LEVELS (T AC ME6508) | | REQUEST FOR ADDITIONAL INFORMATION DUANE ARNOLD ENERGY CENTER LICENSE AMENDMENT REQUEST TO REVISE EMERGENCY PLAN DOCKET NO. 50-331 By letter dated May 31,2011 (Agencywide Document Access and Management System (ADAMS) Accession No. ML111540279 [packageD, NextEra Energy Duane Arnold, LLC requested an amendment to the operating license for the Duane Arnold Energy Center (DAEC) to revise their emergency plan. Specifically, the licensee requested prior approval for a number of changes to their emergency action levels (EALs), which are actually contained in their emergency plan implementing procedures but are considered an integral part of the DAEC emergency plan and is controlled accordingly. |
| | The licensee stated that the license amendment request was for revision of selected EALs and not the entire EAL scheme. However, in effect, the licensee actually submitted their entire EAL scheme and is therefore the scope of this review, i.e., the acceptability of the proposed EAL scheme to meet the standards of 10 CFR 50.47 and the requirements of 10 CFR Appendix E. |
| | In addition, the staff noted numerous changes to the previously approved EAL scheme that were not specifically noted as those requiring prior NRC approval. These changes were also reviewed as part of this license amendment due to the importance of ensuring an acceptable EAL scheme is in place as all offsite actions are predicated on timely and accurate EAL classifications. |
| | DAEC's letter stated that the current DAEC EAL scheme is based on generic development guidance from Nuclear Energy Institute (NEI) document entitled NEI-99-01, "Methodology for Development of Emergency Action Levels," Revision 4, January 2003, (ADAMS Accession No. ML041470143). Since 1992, numerous enhancements and clarification efforts have been made to the generic EAL development guidance resulting in the most recent document, NEI 99-01, Revision 5, "Methodology for Development of Emergency Action Levels," (ADAMS Accession No. ML080450149), which was found to be acceptable for use as generic EAL development guidance by the Nuclear Regulatory Commission (NRC) staff by letter dated |
| | .February 22, 2008 (ADAMS Accession No. ML080430535). |
| | The proposed EAL scheme was developed using the generic development guidance from NEI 99-01, Revision 5 with numerous differences and deviations based upon design criteria applicable to the site as well as licensee preferences for terminology, format, and other licensee-desired modifications to the generic EAL scheme development guidance provided in NEI 99-01 Revision 5. |
| | Attached are the requests for additional information (RAJ) items to facilitate the technical review being conducted by the Operating Reactor Licensing and Outreach Branch staff. Timely and accurate response to these draft RAls is requested. |
| | Enclosure |
| | |
| | -2 |
| | : 1. Section 3.0 of Enclosure 1, "Evaluation of Proposed Change" the last sentence in the last paragraph states that any changes to the approved ICs [initiating conditions) and EALs will be made in accordance with 10 CFR SO.S4(q). It is the expectation of the staff that changes to the EAL basis information and operating modes will be controlled in the same way as any changes to the approved ICs and EALs. Please explain the rationale for not controlling the EAL Basis Document, as a whole, in accordance with 10 CFR SO.S4(q) or revise this statement accordingly. |
| | : 2. EAL RU2.2: The use of "offscale high" readings for EAL thresholds is problematic as it is difficult to differentiate between failed instrumentation and actual plant conditions. Please explain how you will differentiate between the two, in the time allowed, for EAL declaration purposes and how this wording will not result in erroneous declarations, or revise accordingly. |
| | : 3. EAL RA2: The staff requires further justification for the removal of the level threshold previously approved for EAL RA2.3. The proposed justification for the change is confusing in that it uses a calculation as a basis for the change when in fact there are three unique EAL thresholds expected for this EAL. One is based upon a valid Hi-Rad alarm from RM 9178, a valid reading> 100 millirem/hr from RM-9178, and indication of lowering fuel pool water level from L1-3413. Redundancy is expected for this EAL due to the significance of the concern and the availability of instrumentation. Please provide further justification that supports this revision, or revise accordingly. |
| | : 4. EAL RA3: Please explain why the Secondary Alarm Station is used as a threshold for this EAL as this EAL only requires either the Control Room, and either the Central Alarm Station or Secondary Alarm Station, not both (typically). Please justify or revise accordingly. |
| | S. EAL CG1: The staff noted an apparent typographical error in the IC. In addition, the staff recommends developing this EAL using the table as provided in the endorsed EAL scheme development guidance as it aids in clarifying the logic for this EAL, however, the staff has no technical opposition to the proposed format and wording. Also, please move the wording |
| | " .. .for 30 minutes or longer" from the bulleted list of conditions provided in CG 1.2 to the threshold for "RPV level cannot be monitored." This is a known error in the guidance document which will be corrected in a future revision. |
| | : 6. EAL EU1: Please provide basis information related to how security events at the ISFSI |
| | [independent spent fuel storage installations] are classified. |
| | : 7. EAL HU2.1: Note that consideration of"... adjacent areas" was removed as history had shown this to be an area of confusion throughout the nuclear industry and resulted in a delay in classification in some cases. |
| | : 8. EAL HA 1: Please be aware that the areas of concern are expected to be areas where equipment necessary for safe operation, shutdown, and/or cooldown are located AND where the equipment is at risk from the given hazard. For example, not all areas are susceptible to vehicle crashes, high winds, tornados, or turbine blade failure. Please ensure to consider this when developing the list. |
| | |
| | - 3 |
| | : 9. EAL HA2: Please provide the list of areas applicable to this EAL. |
| | : 10. EAL HA32: Please revise the list of areas applicable to this EAL to ensure consistent, and accurate, EAL declaration. Only those areas that contain equipment that must be operated locally for safe operation. safe shutdown, or safe cooldown should be listed. If an area does not contain equipment that must be operated locally. then consideration for not including this area should be given. Note that the need to operate the equipment is not a threshold, i.e., |
| | the impediment to access an area, developed as per the above guidance. is the expectation for this EAL. Also. consider adding guidance information that allows the decision-maker to use reasonable judgment when considering declaring this EAL. For example, a small CO 2 bottle leaking in a large room/area may not warrant declaration. |
| | |
| | Januasy 17, 2012 Mr. Peter Wells Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785 |
| | |
| | ==SUBJECT:== |
| | DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION RE: AMENDMENT TO CHANGE EMERGENCY ACTION LEVELS (TAC ME6508) |
|
| |
|
| ==Dear Mr. Wells:== | | ==Dear Mr. Wells:== |
| By letter dated May 31,2011 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 111540279 [package]), NextEra Energy Duane Arnold, LLC (the licensee) requested an amendment to the operating license for the Duane Arnold Energy Center (DAEC) to revise their emergency plan. Specifically, the licensee requested prior approval for a number of changes to their emergency action levels (EALs), which are actually contained in their emergency plan implementing procedures but are considered an integral part of the DAEC emergency plan and is controlled accordingly. The NRC staff has determined that it needs additional information to complete its review. On January 4, 2012, the NRC staff transmitted a draft Request for Additional Information (RAI) (ADAMS Accession No. ML 12011A060) and discussed the draft RAI with Mr. Thomas Byrne, a member of your staff in a conference call on January 10, 2012. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources Enclosed please find the final RAI items. Your staff agreed that you can provide your response within 30 days of the date of this letter. Please feel free to contact me if you need further clarification of the RAJ. Sincerely, IRA/ Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-331 | | |
| | By letter dated May 31,2011 (Agencywide Document Access and Management System (ADAMS) Accession No. ML111540279 [package]), NextEra Energy Duane Arnold, LLC (the licensee) requested an amendment to the operating license for the Duane Arnold Energy Center (DAEC) to revise their emergency plan. Specifically, the licensee requested prior approval for a number of changes to their emergency action levels (EALs), which are actually contained in their emergency plan implementing procedures but are considered an integral part of the DAEC emergency plan and is controlled accordingly. |
| | The NRC staff has determined that it needs additional information to complete its review. On January 4, 2012, the NRC staff transmitted a draft Request for Additional Information (RAI) |
| | (ADAMS Accession No. ML12011A060) and discussed the draft RAI with Mr. Thomas Byrne, a member of your staff in a conference call on January 10, 2012. |
| | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources Enclosed please find the final RAI items. Your staff agreed that you can provide your response within 30 days of the date of this letter. Please feel free to contact me if you need further clarification of the RAJ. |
| | Sincerely, IRA/ |
| | Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-331 |
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| |
|
| ==Enclosure:== | | ==Enclosure:== |
| As stated cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 Resource RidsNrrPMDuaneArnold Resource RidsNrrLABTully Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDssStsbirsltsb RidsRgn3MailCenter Resource RidsOgcRp Resource PTam. NRR I I ADAMS ACCESSION No'.-120120318 OFFICE NRRlLPL3-1/PM NRRlLPL3-1/LA NRRlLPL3*1/BC*Acting NRRlLPL3*1/PM NAME KFeintuch BTully SWilliams KFeintuch DATE 01/11/12 01/13/12 01/17/12 01/17/12 OFFICIAL RECORD COpy | | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| }} | | PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 Resource RidsNrrPMDuaneArnold Resource RidsNrrLABTully Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDssStsbirsltsb RidsRgn3MailCenter Resource RidsOgcRp Resource PTam. NRR ADAMS ACCESSION No'.- 120120318 I |
| | OFFICE NRRlLPL3-1/PM NRRlLPL3-1/LA NRRlLPL3*1/BC*Acting NRRlLPL3*1/PM NAME KFeintuch BTully SWilliams KFeintuch DATE 01/11/12 01/13/12 01/17/12 01/17/12 I |
| | OFFICIAL RECORD COpy}} |
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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
ML1201203182012-01-17017 January 2012
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
Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies.
2024-07-12
[Table view]
Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
ML24163A0012024-08-0505 August 2024
LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review
ML24193A2432024-07-12012 July 2024
– Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan
ML24149A2862024-06-12012 June 2024
NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
NG-24-0004, 2023 Annual Radiological Environmental Operating Report2024-05-0808 May 2024
2023 Annual Radiological Environmental Operating Report
NG-24-0003, Submittal of 2023 Annual Radioactive Material Release Report2024-04-24024 April 2024
Submittal of 2023 Annual Radioactive Material Release Report
ML24072A0292024-03-29029 March 2024
Nextera Energy Duane Arnold, Llc. Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)
NG-24-0002, 2023 Annual Exposure Report - Form 5s2024-03-0606 March 2024
2023 Annual Exposure Report - Form 5s
NG-24-0001, 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update2024-03-0606 March 2024
2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update
L-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-23-0001, 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report2023-03-27027 March 2023
2023 Annual Decommissioning and Spent Fuel Management Funding Status Report
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
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
ML22066A7632022-04-25025 April 2022
ISFSI-Only Emergency Plan License Amendment Approval
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
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-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022
Registration of Independent Spent Fuel Installation Storage Casks
NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022
2021 Annual Exposure Report - Form 5s
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)
2024-09-04
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 17, 2012 Mr. Peter Wells Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION RE: AMENDMENT TO CHANGE EMERGENCY ACTION LEVELS (TAC ME6508)
Dear Mr. Wells:
By letter dated May 31, 2011 (Agencywide Document Access and Management System (ADAMS) Accession No. ML111540279 [package]), NextEra Energy Duane Arnold, LLC (the licensee) requested an amendment to the operating license for the Duane Arnold Energy Center (DAEC) to revise their emergency plan. Specifically, the licensee requested prior approval for a number of changes to their emergency action levels (EALs), which are actually contained in their emergency plan implementing procedures but are considered an integral part of the DAEC emergency plan and is controlled accordingly.
The NRC staff has determined that it needs additional information to complete its review. On January 4, 2012, the NRC staff transmitted a draft Request for Additional Information (RAI)
(ADAMS Accession No. ML12011A060) and discussed the draft RAI with Mr. Thomas Byrne, a member of your staff in a conference call on January 10, 2012.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
Enclosed please find the final RAI items. Your staff agreed that you can provide your response within 30 days of the date of this letter. Please feel free to contact me if you need further clarification of the RAt Sincerely, Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
As Stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION DUANE ARNOLD ENERGY CENTER LICENSE AMENDMENT REQUEST TO REVISE EMERGENCY PLAN DOCKET NO. 50-331 By letter dated May 31,2011 (Agencywide Document Access and Management System (ADAMS) Accession No. ML111540279 [packageD, NextEra Energy Duane Arnold, LLC requested an amendment to the operating license for the Duane Arnold Energy Center (DAEC) to revise their emergency plan. Specifically, the licensee requested prior approval for a number of changes to their emergency action levels (EALs), which are actually contained in their emergency plan implementing procedures but are considered an integral part of the DAEC emergency plan and is controlled accordingly.
The licensee stated that the license amendment request was for revision of selected EALs and not the entire EAL scheme. However, in effect, the licensee actually submitted their entire EAL scheme and is therefore the scope of this review, i.e., the acceptability of the proposed EAL scheme to meet the standards of 10 CFR 50.47 and the requirements of 10 CFR Appendix E.
In addition, the staff noted numerous changes to the previously approved EAL scheme that were not specifically noted as those requiring prior NRC approval. These changes were also reviewed as part of this license amendment due to the importance of ensuring an acceptable EAL scheme is in place as all offsite actions are predicated on timely and accurate EAL classifications.
DAEC's letter stated that the current DAEC EAL scheme is based on generic development guidance from Nuclear Energy Institute (NEI) document entitled NEI-99-01, "Methodology for Development of Emergency Action Levels," Revision 4, January 2003, (ADAMS Accession No. ML041470143). Since 1992, numerous enhancements and clarification efforts have been made to the generic EAL development guidance resulting in the most recent document, NEI 99-01, Revision 5, "Methodology for Development of Emergency Action Levels," (ADAMS Accession No. ML080450149), which was found to be acceptable for use as generic EAL development guidance by the Nuclear Regulatory Commission (NRC) staff by letter dated
.February 22, 2008 (ADAMS Accession No. ML080430535).
The proposed EAL scheme was developed using the generic development guidance from NEI 99-01, Revision 5 with numerous differences and deviations based upon design criteria applicable to the site as well as licensee preferences for terminology, format, and other licensee-desired modifications to the generic EAL scheme development guidance provided in NEI 99-01 Revision 5.
Attached are the requests for additional information (RAJ) items to facilitate the technical review being conducted by the Operating Reactor Licensing and Outreach Branch staff. Timely and accurate response to these draft RAls is requested.
Enclosure
-2
- 1. Section 3.0 of Enclosure 1, "Evaluation of Proposed Change" the last sentence in the last paragraph states that any changes to the approved ICs [initiating conditions) and EALs will be made in accordance with 10 CFR SO.S4(q). It is the expectation of the staff that changes to the EAL basis information and operating modes will be controlled in the same way as any changes to the approved ICs and EALs. Please explain the rationale for not controlling the EAL Basis Document, as a whole, in accordance with 10 CFR SO.S4(q) or revise this statement accordingly.
- 2. EAL RU2.2: The use of "offscale high" readings for EAL thresholds is problematic as it is difficult to differentiate between failed instrumentation and actual plant conditions. Please explain how you will differentiate between the two, in the time allowed, for EAL declaration purposes and how this wording will not result in erroneous declarations, or revise accordingly.
- 3. EAL RA2: The staff requires further justification for the removal of the level threshold previously approved for EAL RA2.3. The proposed justification for the change is confusing in that it uses a calculation as a basis for the change when in fact there are three unique EAL thresholds expected for this EAL. One is based upon a valid Hi-Rad alarm from RM 9178, a valid reading> 100 millirem/hr from RM-9178, and indication of lowering fuel pool water level from L1-3413. Redundancy is expected for this EAL due to the significance of the concern and the availability of instrumentation. Please provide further justification that supports this revision, or revise accordingly.
- 4. EAL RA3: Please explain why the Secondary Alarm Station is used as a threshold for this EAL as this EAL only requires either the Control Room, and either the Central Alarm Station or Secondary Alarm Station, not both (typically). Please justify or revise accordingly.
S. EAL CG1: The staff noted an apparent typographical error in the IC. In addition, the staff recommends developing this EAL using the table as provided in the endorsed EAL scheme development guidance as it aids in clarifying the logic for this EAL, however, the staff has no technical opposition to the proposed format and wording. Also, please move the wording
" .. .for 30 minutes or longer" from the bulleted list of conditions provided in CG 1.2 to the threshold for "RPV level cannot be monitored." This is a known error in the guidance document which will be corrected in a future revision.
- 6. EAL EU1: Please provide basis information related to how security events at the ISFSI
[independent spent fuel storage installations] are classified.
- 7. EAL HU2.1: Note that consideration of"... adjacent areas" was removed as history had shown this to be an area of confusion throughout the nuclear industry and resulted in a delay in classification in some cases.
- 8. EAL HA 1: Please be aware that the areas of concern are expected to be areas where equipment necessary for safe operation, shutdown, and/or cooldown are located AND where the equipment is at risk from the given hazard. For example, not all areas are susceptible to vehicle crashes, high winds, tornados, or turbine blade failure. Please ensure to consider this when developing the list.
- 3
- 9. EAL HA2: Please provide the list of areas applicable to this EAL.
- 10. EAL HA32: Please revise the list of areas applicable to this EAL to ensure consistent, and accurate, EAL declaration. Only those areas that contain equipment that must be operated locally for safe operation. safe shutdown, or safe cooldown should be listed. If an area does not contain equipment that must be operated locally. then consideration for not including this area should be given. Note that the need to operate the equipment is not a threshold, i.e.,
the impediment to access an area, developed as per the above guidance. is the expectation for this EAL. Also. consider adding guidance information that allows the decision-maker to use reasonable judgment when considering declaring this EAL. For example, a small CO 2 bottle leaking in a large room/area may not warrant declaration.
Januasy 17, 2012 Mr. Peter Wells Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION RE: AMENDMENT TO CHANGE EMERGENCY ACTION LEVELS (TAC ME6508)
Dear Mr. Wells:
By letter dated May 31,2011 (Agencywide Document Access and Management System (ADAMS) Accession No. ML111540279 [package]), NextEra Energy Duane Arnold, LLC (the licensee) requested an amendment to the operating license for the Duane Arnold Energy Center (DAEC) to revise their emergency plan. Specifically, the licensee requested prior approval for a number of changes to their emergency action levels (EALs), which are actually contained in their emergency plan implementing procedures but are considered an integral part of the DAEC emergency plan and is controlled accordingly.
The NRC staff has determined that it needs additional information to complete its review. On January 4, 2012, the NRC staff transmitted a draft Request for Additional Information (RAI)
(ADAMS Accession No. ML12011A060) and discussed the draft RAI with Mr. Thomas Byrne, a member of your staff in a conference call on January 10, 2012.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources Enclosed please find the final RAI items. Your staff agreed that you can provide your response within 30 days of the date of this letter. Please feel free to contact me if you need further clarification of the RAJ.
Sincerely, IRA/
Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 Resource RidsNrrPMDuaneArnold Resource RidsNrrLABTully Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDssStsbirsltsb RidsRgn3MailCenter Resource RidsOgcRp Resource PTam. NRR ADAMS ACCESSION No'.- 120120318 I
OFFICE NRRlLPL3-1/PM NRRlLPL3-1/LA NRRlLPL3*1/BC*Acting NRRlLPL3*1/PM NAME KFeintuch BTully SWilliams KFeintuch DATE 01/11/12 01/13/12 01/17/12 01/17/12 I
OFFICIAL RECORD COpy
