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| ==2.0 REGULATORY EVALUATION== | | ==2.0 REGULATORY EVALUATION== |
| A section or condition was included in the facility operating licenses issued to some nuclear power plants requiring the licensee to make reports to the Nuclear Regulatory Commission (NRC) regarding violations of other sections of the operating license (typically Section 2.C). In the case of Palisades Nuclear Plant, condition 2.F of the Facility Operating License reads as follows: 2. F The licensee shall report any violations of Section 2.C (1) of this license within 24 hours to the NRC Operations Center via the Emergency Notification System with written follow-up within 60 days in accordance with 10 CFR 50.73 (b), (c), and (e). In addition to the information provided to support licensing decisions, the NRC obtains information about plant operation, licensee programs, and other matters using a combination of inspections and reporting requirements. Routine or scheduled reports that are required to be submitted to the NRC are defined in the related regulations, specific license condition, technical specification, or an NRC-approved program document. The reporting of emergencies, unplanned events or conditions, and other special cases may also be addressed within such documents by the inclusion of reporting thresholds and are also the focus of the reporting requirements in 10 CFR 50.72, "Immediate notification requirements for operating nuclear power reactors," and 10 CFR 50.73, "Licensee event report system." Changes to the reporting regulations in 10 CFR 50.72 and 50.73 became effective in January 2001 (see Federal Register Enclosure | | A section or condition was included in the facility operating licenses issued to some nuclear power plants requiring the licensee to make reports to the Nuclear Regulatory Commission (NRC) regarding violations of other sections of the operating license (typically Section 2.C). In the case of Palisades Nuclear Plant, condition 2.F of the Facility Operating License reads as follows: 2. F The licensee shall report any violations of Section 2.C (1) of this license within 24 hours to the NRC Operations Center via the Emergency Notification System with written follow-up within 60 days in accordance with 10 CFR 50.73 (b), (c), and (e). In addition to the information provided to support licensing decisions, the NRC obtains information about plant operation, licensee programs, and other matters using a combination of inspections and reporting requirements. Routine or scheduled reports that are required to be submitted to the NRC are defined in the related regulations, specific license condition, technical specification, or an NRC-approved program document. The reporting of emergencies, unplanned events or conditions, and other special cases may also be addressed within such documents by the inclusion of reporting thresholds and are also the focus of the reporting requirements in 10 CFR 50.72, "Immediate notification requirements for operating nuclear power reactors," and 10 CFR 50.73, "Licensee event report system." Changes to the reporting regulations in 10 CFR 50.72 and 50.73 became effective in January 2001 (see Federal Register Enclosure |
| -2notice on October 25, 2000 (65 FR 63769)) and included extending the allowable reporting times for licensee event reports (LERs) from 30 days to 60 days. | | -2notice on October 25, 2000 (65 FR 63769)) and included extending the allowable reporting times for licensee event reports (LERs) from 30 days to 60 days. |
| 3.0 TECHNICAL EVALUATION Section 2.F of the Facility Operating License No. DPR-20 requires the licensee to report any violations of the requirements of Section 2.C (1) of the Facility Operating License and defines the method and allowable time periods for such reports. The reporting threshold (i.e., a violation) for some of the conditions included in Section 2.C (1) of the Facility Operating License duplicates those defined in 10 CFR 50.72 and 10 CFR 50.73. However, the requirements in the Facility Operating License may have different deadlines than those defined in the regulations (following a rule change in 2001). This difference in reporting requirements has led to variations in reporting since many facility operating licenses do not contain the subject condition. For those licensees with a 30-day reporting requirement in the Facility Operating License, the condition has decreased the benefits of the rulemaking. For those cases where the current Facility Operating License requirement to report violations is also reportable in accordance with the regulations defined in 10 CFR 50.72 and 10 CFR 50.73, the NRC staff finds that the regulations adequately address this issue and the elimination of the duplicative requirement in the Facility Operating License is acceptable. Some of the conditions addressed in Section 2.C (1) of the Facility Operating License may address the maintenance of particular programs, administrative requirements, or other matters where a violation of the requirement would not result in a report to the NRC in accordance with 10 CFR 50.72 or 10 CFR 50.73. In most cases, there are requirements for reports to the NRC related to these conditions in other regulations, the specific license condition or technical specification, or an f\lRC-approved program document. | | |
| | ===3.0 TECHNICAL=== |
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| | EVALUATION Section 2.F of the Facility Operating License No. DPR-20 requires the licensee to report any violations of the requirements of Section 2.C (1) of the Facility Operating License and defines the method and allowable time periods for such reports. The reporting threshold (i.e., a violation) for some of the conditions included in Section 2.C (1) of the Facility Operating License duplicates those defined in 10 CFR 50.72 and 10 CFR 50.73. However, the requirements in the Facility Operating License may have different deadlines than those defined in the regulations (following a rule change in 2001). This difference in reporting requirements has led to variations in reporting since many facility operating licenses do not contain the subject condition. For those licensees with a 30-day reporting requirement in the Facility Operating License, the condition has decreased the benefits of the rulemaking. For those cases where the current Facility Operating License requirement to report violations is also reportable in accordance with the regulations defined in 10 CFR 50.72 and 10 CFR 50.73, the NRC staff finds that the regulations adequately address this issue and the elimination of the duplicative requirement in the Facility Operating License is acceptable. Some of the conditions addressed in Section 2.C (1) of the Facility Operating License may address the maintenance of particular programs, administrative requirements, or other matters where a violation of the requirement would not result in a report to the NRC in accordance with 10 CFR 50.72 or 10 CFR 50.73. In most cases, there are requirements for reports to the NRC related to these conditions in other regulations, the specific license condition or technical specification, or an f\lRC-approved program document. |
| In other cases, there are reports to other agencies or news releases that would prompt a report to the NRC (in accordance with 10 CFR 50.72(b)(2)(xi)). The NRC staff also assessed violations of administrative requirements that could be reportable under the current License Condition but that may not have a duplicative requirement in a regulation or other regulatory requirement. The NRC staff finds that the requirement to report such problems within 24 hours with written reports to follow using the LER process is not needed. The NRC staff is confident that the information related to such violations that is actually important to the NRC's regulatory functions would come to light in a time frame comparable to the 60-day LER requirements. | | In other cases, there are reports to other agencies or news releases that would prompt a report to the NRC (in accordance with 10 CFR 50.72(b)(2)(xi)). The NRC staff also assessed violations of administrative requirements that could be reportable under the current License Condition but that may not have a duplicative requirement in a regulation or other regulatory requirement. The NRC staff finds that the requirement to report such problems within 24 hours with written reports to follow using the LER process is not needed. The NRC staff is confident that the information related to such violations that is actually important to the NRC's regulatory functions would come to light in a time frame comparable to the 60-day LER requirements. |
| The information would become available to the appropriate NRC staff through the inspection program, updates to program documents, resultant licensing actions, public announcements, or some other reliable mechanism. The NRC staff finds that the elimination of Section 2.F in Palisades Nuclear Plant Facility Operating License DPR-20 will not result in a loss of information to the NRC that would adversely affect either its goal to protect public health and safety or its ability to carry out its various other regulatory responsibilities. | | The information would become available to the appropriate NRC staff through the inspection program, updates to program documents, resultant licensing actions, public announcements, or some other reliable mechanism. The NRC staff finds that the elimination of Section 2.F in Palisades Nuclear Plant Facility Operating License DPR-20 will not result in a loss of information to the NRC that would adversely affect either its goal to protect public health and safety or its ability to carry out its various other regulatory responsibilities. |
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| ==6.0 CONCLUSION== | | ==6.0 CONCLUSION== |
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| The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. | | The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. |
| 7.0 REFERENCE | | |
| | ===7.0 REFERENCE=== |
| : 1. NRC's model SE published in the Federal Register on August 29, 2005 (70 FR 51098). Principal Contributor: M. Chawla, I'JRR Date: November 20, 2008 November 20, 2008 Vice President, Operations Entergy Nuclear Operations Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 PALISADES PLANT -ISSUANCE OF AMENDMENT RE: ELIMINATE LICENSE CONDITION 2.F (TAC NO. MD8727) | | : 1. NRC's model SE published in the Federal Register on August 29, 2005 (70 FR 51098). Principal Contributor: M. Chawla, I'JRR Date: November 20, 2008 November 20, 2008 Vice President, Operations Entergy Nuclear Operations Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 PALISADES PLANT -ISSUANCE OF AMENDMENT RE: ELIMINATE LICENSE CONDITION 2.F (TAC NO. MD8727) |
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MONTHYEARML0812700732008-05-0505 May 2008 Application to Eliminate License Condition 2.F Requiring Reporting of Violations of Section 2.C of Operating License Using the Consolidated Line Item Improvement Process Project stage: Request ML0827404452008-11-20020 November 2008 Issuance of Amendment Eliminate License Condition 2.F Project stage: Approval 2008-11-20
[Table View] |
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Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report 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 ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML22173A1762022-06-28028 June 2022 Enclosure 2 - Holtec Palisades, LLC and Holtec Decommissioning International, LLC - Palisades Nuclear Plant Amendment to Renewed Facility Operating License ML22173A1752022-06-28028 June 2022 Enclosure 1 - Holtec Palisades, LLC and Holtec Decommissioning International, LLC - Big Rock Point Plant Amendment to Facility Operating License ML22039A1982022-05-13013 May 2022 Issuance of Amendment No. 272 Permanently Defueled Technical Specifications ML21292A1472021-12-13013 December 2021 Draft Conforming License Amendments - Palisades Nuclear Plant Renewed Facility Operating License DPR-20 and ISFSI and Big Rock Point Facility Operating License DPR-6 and ISFSI (EPID L-2020-LLM-0003) (Enclosure 2) ML21292A1482021-12-13013 December 2021 Safety Evaluation Related to Request for Direct and Indirect Transfers of Control of Facility Operating License DPR-6 for Big Rock Point and Renewed Facility Operating License DPR-20 for Palisades Nuclear Plant and ISFSI (EPID L-2020-LLM-00 ML19317D8552019-12-30030 December 2019 Issuance of Amendment No. 271 Regarding Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19198A0802019-08-20020 August 2019 Issuance of Amendments No. 269 Regarding Changes to NFPA 805 Modifications and Change to Full Compliance Implementation Date for the Fire Protection Program (Epids L-2018-LLA-0296 and L-2019-LLA-0049) ML19107A0532019-05-13013 May 2019 Issuance of Amendment No. 268 Regarding Revision to Diesel Generator Undervoltage Start Surveillance Requirement PNP 2019-004, License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b2019-03-28028 March 2019 License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b ML18346A2872018-12-12012 December 2018 Appendix a to Provisional Operating License DPR-20, Technical Specifications for the Palisades Plant, Consumers Power Company, Docket No 50-255 PNP 2018-052, Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force.2018-11-16016 November 2018 Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force. ML18170A2192018-09-24024 September 2018 Issuance of Amendment Changes to the Emergency Plan for Permanently Defueled Condition (CAC No. MG0198; EPID L-2017-LLA-0305) ML18114A4102018-06-0404 June 2018 Issuance of Amendment Regarding Administrative Controls for Permanently Defueled Condition (CAC No. MG0021; EPID L-2017-LLA-0266) ML18039A2442018-02-27027 February 2018 Issuance of Amendment License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Program Transition License Condition for Required Modifications ML17328B0332017-12-15015 December 2017 Issuance of Amendment Cyber Security Plan Implementation Schedule (CAC No. MF9523; EPID L-2017-LLA-0199) ML17128A4462017-06-21021 June 2017 Correction to License Amendment No. 235 to Correct an Error Introduced During Issuance of Renewed Facility Operating License ML17121A5102017-06-0808 June 2017 Issuance of Amendment License Amendment Request for Editorial and Administrative Changes to Technical Specifications ML17082A4652017-05-30030 May 2017 Issuance of Amendment Application to Revise Technical Specifications to Adopt TSTF 545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML16300A0302016-12-19019 December 2016 Issuance of Amendment Revision to the Requirements for Steam Generator Tube Inspections and Repair Criteria in the Cold Leg Tube Sheet Region ML16281A4982016-10-28028 October 2016 Issuance of Amendment No. 260, Revise License Condition 2.C.(4) and Technical Specifications Related to Control Rod Drive Exercise Surveillance ML16078A0682016-05-0202 May 2016 Issuance of Amendment Cyber Security Plan Implementation Schedule ML15209A7912015-11-23023 November 2015 Issuance of Amendment License Amendment Request to Implement 10 CFR 50.61a, Alternative Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML15106A6822015-11-23023 November 2015 Issuance of Amendment License Amendment Request for Approval of Palisades Nuclear Plant 10 CFR 50 Appendix G Equivalent Margins Analysis ML15103A0592015-05-18018 May 2015 Issuance of Amendment Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into Limiting Condition for Operation 3.0.3 - RITSTF Initiatives 6B and 6C. ML15055A1062015-04-22022 April 2015 Issuance of Amendment License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times ML15007A1912015-02-27027 February 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML14283A2872014-10-22022 October 2014 Issuance of Amendment Application for Technical Specification Change (TSTF-427) to Add Limiting Condition for Operation 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML13056A5142013-02-28028 February 2013 Non-Proprietary Issuance of Amendment Regarding Replacement of Spent Fuel Pool Region 1 Storage Racks ML12279A1572012-12-0505 December 2012 Issuance of Amendment Revised Cyber Security Plan Implementation Schedule Milestone 6 ML1207400812012-04-23023 April 2012 Issuance of Amendment to Extend the Containment Type a Leak Rate Test Frequency to 15 Years ML11362A4682012-01-27027 January 2012 License Amendment, Issuance of Amendment No. 246 to Revise TS Sections 3.7.16 and 4.3 Regarding Fuel Storage Criticality ML1134803032012-01-19019 January 2012 Issuance of Amendment Primary Coolant System Pressure-Temperature Limits ML1132203702012-01-19019 January 2012 Issuance of Amendment Revise Calculated Peak Containment Internal Pressure ML1118012432011-07-28028 July 2011 Issuance of Amendment Regarding Cyber Security Plan ML1115701362011-07-26026 July 2011 License Amendment, Emergency Diesel Generator Fuel Oil and Lube Oil Systems ML1101005992011-01-25025 January 2011 Issuance of Amendment Change to License Section 2.E ML1020901372010-08-23023 August 2010 License Amendment, Issuance of Amendment One-time Extension to the Integrated Leak Rate Test Interval ML1013805342010-06-0202 June 2010 License Amendment, Issuance of Emergency Amendment Control Rod Drive Exercise Surveillance ML0902204422009-02-11011 February 2009 Issuance of Amendment Change to In-Service Inspection Interval. ML0901602382009-02-0606 February 2009 Issuance of Amendment Spent Fuel Pool Region I Storage Requirements ML0833700592008-12-19019 December 2008 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing ML0829100562008-12-12012 December 2008 Issuance of Amendment Request to Support Use of M5 Alloy ML0827404452008-11-20020 November 2008 Issuance of Amendment Eliminate License Condition 2.F ML0725500572007-10-0404 October 2007 Issuance of Amendment 228 Proposal to Revise Containment Sump Surveillance Requirement to Verify Strainer Integrity ML0725307352007-10-0202 October 2007 License Amendment, Issuance of Amendment Replacement of Containment Sump Buffer (Tac No. MD5893) ML0724706672007-09-28028 September 2007 License Amendment, Implemented Alternative Radiological Source Term ML0721800242007-08-0909 August 2007 Revised Pages of Renewed Facility Operating License No. DPR-20 2023-12-27
[Table view] Category:Technical Specification
MONTHYEARPNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML22102A2482022-04-14014 April 2022 Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML21152A1112021-06-0101 June 2021 Proposed Changes (mark-up) to Palisades Plant - Appendix a Technical Specifications, and Appendix B Environmental Protection Plan Pages ML21152A1132021-06-0101 June 2021 Palisade Nuclear Plant - Proposed Technical Specifications Bases Changes RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls PNP 2019-017, Submittal of Changes to Technical Specifications Bases2019-03-21021 March 2019 Submittal of Changes to Technical Specifications Bases PNP 2018-052, Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force.2018-11-16016 November 2018 Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force. ML18270A3222018-09-27027 September 2018 Attachment 1: Description and Evaluation of Technical Specifications Changes ML18270A3242018-09-27027 September 2018 Attachment 3: Proposed Changes and Appendix a Technical Specifications Pages ML18270A3252018-09-27027 September 2018 Attachment 4: Page Change Instructions and Revised Pages, and Appendix a Technical Specifications ML18270A3262018-09-27027 September 2018 Attachment 5: Proposed Technical Specification Bases Changes PNP 2017-067, Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases2017-11-0808 November 2017 Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases PNP 2016-046, License Amendment Request for Editorial and Administrative Changes to Technical Specifications2016-11-0909 November 2016 License Amendment Request for Editorial and Administrative Changes to Technical Specifications PNP 2014-088, Report to NRC of Changes to Technical Specifications Bases2014-09-15015 September 2014 Report to NRC of Changes to Technical Specifications Bases PNP 2014-042, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c, Using the Consolidated Line Item Improvement Process2014-06-11011 June 2014 License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c, Using the Consolidated Line Item Improvement Process PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases2012-11-0909 November 2012 Report to NRC of Changes to Technical Specifications Bases PNP 2011-032, Report to NRC of Changes of Technical Specifications Bases2011-04-25025 April 2011 Report to NRC of Changes of Technical Specifications Bases PNP 2011-018, Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years2011-04-0606 April 2011 Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years ML1020105792010-07-20020 July 2010 License Amendment Request for Emergency Diesel Generator Fuel Oil and Lube Oil Systems ML0930604142009-11-0202 November 2009 Report of Changes to Technical Specifications Bases ML0913501812009-05-14014 May 2009 Supplement to License Amendment Request: Changes to Technical Specification Administrative Controls Section ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions ML0901602382009-02-0606 February 2009 Issuance of Amendment Spent Fuel Pool Region I Storage Requirements ML0827404452008-11-20020 November 2008 Issuance of Amendment Eliminate License Condition 2.F ML0822703122008-08-14014 August 2008 Report of Changes to Technical Specifications Bases ML0723203952007-08-16016 August 2007 Report of Changes to Technical Specifications Bases ML0722201032007-07-25025 July 2007 Submittal of Technical Specifications Bases Changes ML0718002162007-06-28028 June 2007 License Amendment Request: Replacement of Containment Sump Buffer ML0714501052007-05-31031 May 2007 Technical Specifications Pages Re Programs and Manuals for Steam Generator ML0631803592006-11-0606 November 2006 License Amendment Request: Realistic Large Break Loss-of-Coolant Accident ML0628303852006-09-25025 September 2006 Alternative Source Term- Proposed License Amendment ML0623000332006-08-17017 August 2006 Report of Changes to Technical Specifications Bases ML0524102132005-08-22022 August 2005 Report of Changes to Technical Specifications Bases ML0425904452004-09-0202 September 2004 Report of Changes to Technical Specifications Bases ML0421604082004-08-0202 August 2004 Tech Spec Pages for Amendment No. 217 Regarding the Relocating of the Primary Coolant System Pressure, Cold-Leg Temperature and Flow Departure from Nucleate Boiling Limits to the Core Operating Limits Report ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0330001112003-10-17017 October 2003 Report of Changes to Technical Specifications Bases ML0328900502003-10-0606 October 2003 License Amendment Request: Increase Rated Thermal Power, Response to Request for Additional Information ML0316110532003-06-0303 June 2003 License Amendment Request: Increase Rated Thermal Power ML0303805792003-01-22022 January 2003 Technical Specifications and Bases ML0231701012002-10-31031 October 2002 Report of Changes to Technical Specifications Bases ML0207201012002-03-0101 March 2002 License Amendment Request, Surveillance Requirement Frequency for Containment Spray Nozzle Inspections ML0205901512002-02-26026 February 2002 Amendment No. 207 Retechnical Specification on Spent Fuel Pool Boron Concentration ML18344A3791978-06-15015 June 1978 Proposed Technical Specification Changes on Power Distribution Limits ML18353B1461978-03-0909 March 1978 Iodine Removal System - Proposed Technical Specification Changes ML18353A8671978-02-22022 February 1978 Letter Proposed Technical Specifications Change on Heatup and Cooldown Curves for Cycle 3 Operation ML18353A8741978-02-21021 February 1978 Letter Proposed Technical Specifications Change on Steam Generator Operating Allowance ML18347A1881978-01-0303 January 1978 Proposed Technical Specifications Changes Relating to Overpressure Protection System ML18353B1451977-11-11011 November 1977 Transmittal of Technical Specification - Deletion of Annual Operating Report ML18353B1471977-11-10010 November 1977 Proposed Technical Specification Changes for Steam Generator Inservice Inspection 2023-12-14
[Table view] Category:Amendment
MONTHYEARPNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML22102A2482022-04-14014 April 2022 Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML21152A1112021-06-0101 June 2021 Proposed Changes (mark-up) to Palisades Plant - Appendix a Technical Specifications, and Appendix B Environmental Protection Plan Pages RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls PNP 2018-052, Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force.2018-11-16016 November 2018 Supplement to License Amendment Request -Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force. PNP 2011-018, Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years2011-04-0606 April 2011 Regarding License Amendment Request to Extend the Containment Type a Leak Rate Test Frequency to 15 Years ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions ML0901602382009-02-0606 February 2009 Issuance of Amendment Spent Fuel Pool Region I Storage Requirements ML0827404452008-11-20020 November 2008 Issuance of Amendment Eliminate License Condition 2.F ML0718002162007-06-28028 June 2007 License Amendment Request: Replacement of Containment Sump Buffer ML0714501052007-05-31031 May 2007 Technical Specifications Pages Re Programs and Manuals for Steam Generator ML0631803592006-11-0606 November 2006 License Amendment Request: Realistic Large Break Loss-of-Coolant Accident ML0628303852006-09-25025 September 2006 Alternative Source Term- Proposed License Amendment ML0421604082004-08-0202 August 2004 Tech Spec Pages for Amendment No. 217 Regarding the Relocating of the Primary Coolant System Pressure, Cold-Leg Temperature and Flow Departure from Nucleate Boiling Limits to the Core Operating Limits Report ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0328900502003-10-0606 October 2003 License Amendment Request: Increase Rated Thermal Power, Response to Request for Additional Information ML0316110532003-06-0303 June 2003 License Amendment Request: Increase Rated Thermal Power ML0205901512002-02-26026 February 2002 Amendment No. 207 Retechnical Specification on Spent Fuel Pool Boron Concentration ML18344A3791978-06-15015 June 1978 Proposed Technical Specification Changes on Power Distribution Limits ML18347A1881978-01-0303 January 1978 Proposed Technical Specifications Changes Relating to Overpressure Protection System ML18353B1471977-11-10010 November 1977 Proposed Technical Specification Changes for Steam Generator Inservice Inspection ML18347A1711977-09-26026 September 1977 Additional Information Relating to Power Increase Request ML18348A7651976-11-16016 November 1976 Proposed Change to Technical Specification to Modify Spent Fuel Storage Facility ML18347A5511976-10-0808 October 1976 Transmitting Proposed Change to Tech Spec Concerning Operability & Surveillance Requirements for Hydraulic Shock Suppressors ML18347A6601976-06-0909 June 1976 Re Cpc'S 5/25/1976 Event Report, Requesting Change to Tech Spec to Operation of Diesel Generator with One High-Pressure Safety Injection Pump Out of Service ML18348A7701976-03-12012 March 1976 Proposed Change to Technical Specification to Modify Requirements for Testing of Primary System Pump Combinations & for Load Testing of Diesel Generators ML18348A7751976-02-25025 February 1976 Proposed Change to Technical Specification to Delete Requirement for Operation of Fuel Pool Charcoal Adsorber After I-131 Level in Irradiated Fuel Has Decayed by Factor of 10 ML18348A7761976-01-30030 January 1976 Proposed Change to Technical Specification to Generalize Tech Spec to Allow for Reactor Refueling Without Requiring Additional Tech Spec Changes ML18348A7801976-01-30030 January 1976 Proposed Change to Technical Specification to Revise Steam Generator Tube Plugging Criteria ML18348A7861975-03-10010 March 1975 Proposed Change to Technical Specification Based on Eddy-Current Inspection of Steam Generator 2023-12-14
[Table view] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 November 20, 2008 Vice President, Operations Entergy Nuclear Operations Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 PALISADES PLANT -
ISSUANCE OF AMENDI\I1EI\lT RE: ELIMINATE LICENSE CONDITION 2.F (TAC NO.
MD8727)
Dear Sir or Madam:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 233 to Renewed Facility Operating License No. DPR-20 for the Palisades Nuclear Plant. The amendment consists of changes to the Technical Specifications in response to your application dated May 5, 2008.
The amendment would revise renewed facility operating license DPR-20 to remove license condition 2.F. The license condition describes reporting requirements for exceeding the facility steady-state reactor core power level described in license condition 2.C. (1). The proposed change is consistent with the NRC approved change notice published in the Federal Register (70 FR 67202) on November 4, 2005, announcing the availability of this improvement through the consolidated line item improvement process. A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Sincerely, Mahesh L. Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255
Enclosures:
- 1. Amendment No. 233 to DPR-20
- 2. Safety Evaluation cc w/encls: Distribution via ListServ UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 EI\JTERGY NUCLEAR OPERATIONS. DOCKET NO.
PALISADES AMENDMENT TO RENEWED FACILITY OPERATING Amendment No. 233 License No. DPR-20
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by Entergy Nuclear Operations, Inc. (ENO, the licensee), dated May 5.2008. complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application. the provisions of the Act. and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment and Paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-20 is hereby amended to read as follows:
The Technical Specifications contained in Appendix A, as revised through Amendment No. 233, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. This license amendment is effective as of the date of issuance and shall be implemented within 90 days. FOR THE NUCLEAR REGULATORY COMMISSION Lois . James, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License Date of Issuance: November 20, 2008 ATTACHMENT TO LICENSE AMENDMENT NO. RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. Replace the following pages of the Renewed Facility Operating License No. DPR-20 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT Page 3 Page 3 Page 6 Page 6
-3Pursuant to Section 104b of the Act, as amended, and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," (a) ENP to possess and use, and (b) END to possess, use and operate, the facility as a utilization facility at the designated location in Van Buren County, Michigan, in accordance with the procedures and limitation set forth in this license; END, pursuant to the Act and 10 CFR Parts 40 and 70, to receive, possess, and use source and special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; END, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use byproduct, source, and special nuclear material as sealed sources for reactor startup, reactor instrumentation, radiation monitoring equipment calibration, and fission detectors in amounts as required; END, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material for sample analysis or instrument calibration, or associated with radioactive apparatus or components; and END, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operations of the facility. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations in 10 CFR Chapter I and is subject to all applicable provisions of the Act; to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: END is authorized to operate the facility at steady-state reactor core power levels not in excess of 2565.4 Megawatts thermal (100 percent rated power) in accordance with the conditions specified herein. The Technical Specifications contained in Appendix A, as revised through Amendment No. 233, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. END shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. END shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SERs dated 09/01/78, 03/19/80, 02/10/81, OS/26/83, 07/12/85,01/29/86,12/03/87, and 05/19/89 and subject to the following provisions: Renewed License No. DPR-20 Amendment No. 233 The facility has been granted certain exemptions from the requirements of Section III, G of Appendix R to 10 CFR Part 50, "Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979." This section relates to fire protection features for ensuring the systems and associated circuits used to achieve and maintain safe shutdown are free of fire damage. These exemptions were granted in letters dated February 8,1983, July 12,1985, and July 23,1985. In addition, the facility has been granted certain exemptions from Appendix J to 10 CFR Part 50, "Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors." This section contains leakage test requirements, schedules and acceptance criteria for tests of the leak-tight integrity of the primary reactor containment and systems and components which penetrate the containment. These exemptions were granted in a letter dated December 6, 1989. These exemptions granted pursuant to 10 CFR 50.12, are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission. ENO shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Nuclear Management Company Palisades Nuclear Plant Physical Security Plan, Revision 2," submitted by letter dated May 10, 2006. F[deleted] ENP and ENO shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims. Renewed License No. DPR-20 Amendment No. 233 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 233 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-20 ENTERGY NUCLEAR OPERATIONS, INC. PALISADES NUCLEAR PLANT DOCKET NO. 50-255
1.0 INTRODUCTION
By application dated May 5,2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081270073), the Entergy Nuclear Operations, Inc., (the licensee), requested an amendment to the Facility Operating License No. DPR-20 for Palisades Nuclear Plant. The proposed amendment would delete License Condition 2.F, which requires reporting of violations of the requirements in Section 2.C (1) of the Facility Operating License. A notice announcing the availability of this proposed change using the consolidated line item improvement process was published in the Federal Register on November 4, 2005 (70 FR 67202).
2.0 REGULATORY EVALUATION
A section or condition was included in the facility operating licenses issued to some nuclear power plants requiring the licensee to make reports to the Nuclear Regulatory Commission (NRC) regarding violations of other sections of the operating license (typically Section 2.C). In the case of Palisades Nuclear Plant, condition 2.F of the Facility Operating License reads as follows: 2. F The licensee shall report any violations of Section 2.C (1) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written follow-up within 60 days in accordance with 10 CFR 50.73 (b), (c), and (e). In addition to the information provided to support licensing decisions, the NRC obtains information about plant operation, licensee programs, and other matters using a combination of inspections and reporting requirements. Routine or scheduled reports that are required to be submitted to the NRC are defined in the related regulations, specific license condition, technical specification, or an NRC-approved program document. The reporting of emergencies, unplanned events or conditions, and other special cases may also be addressed within such documents by the inclusion of reporting thresholds and are also the focus of the reporting requirements in 10 CFR 50.72, "Immediate notification requirements for operating nuclear power reactors," and 10 CFR 50.73, "Licensee event report system." Changes to the reporting regulations in 10 CFR 50.72 and 50.73 became effective in January 2001 (see Federal Register Enclosure
-2notice on October 25, 2000 (65 FR 63769)) and included extending the allowable reporting times for licensee event reports (LERs) from 30 days to 60 days.
3.0 TECHNICAL
EVALUATION Section 2.F of the Facility Operating License No. DPR-20 requires the licensee to report any violations of the requirements of Section 2.C (1) of the Facility Operating License and defines the method and allowable time periods for such reports. The reporting threshold (i.e., a violation) for some of the conditions included in Section 2.C (1) of the Facility Operating License duplicates those defined in 10 CFR 50.72 and 10 CFR 50.73. However, the requirements in the Facility Operating License may have different deadlines than those defined in the regulations (following a rule change in 2001). This difference in reporting requirements has led to variations in reporting since many facility operating licenses do not contain the subject condition. For those licensees with a 30-day reporting requirement in the Facility Operating License, the condition has decreased the benefits of the rulemaking. For those cases where the current Facility Operating License requirement to report violations is also reportable in accordance with the regulations defined in 10 CFR 50.72 and 10 CFR 50.73, the NRC staff finds that the regulations adequately address this issue and the elimination of the duplicative requirement in the Facility Operating License is acceptable. Some of the conditions addressed in Section 2.C (1) of the Facility Operating License may address the maintenance of particular programs, administrative requirements, or other matters where a violation of the requirement would not result in a report to the NRC in accordance with 10 CFR 50.72 or 10 CFR 50.73. In most cases, there are requirements for reports to the NRC related to these conditions in other regulations, the specific license condition or technical specification, or an f\lRC-approved program document.
In other cases, there are reports to other agencies or news releases that would prompt a report to the NRC (in accordance with 10 CFR 50.72(b)(2)(xi)). The NRC staff also assessed violations of administrative requirements that could be reportable under the current License Condition but that may not have a duplicative requirement in a regulation or other regulatory requirement. The NRC staff finds that the requirement to report such problems within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with written reports to follow using the LER process is not needed. The NRC staff is confident that the information related to such violations that is actually important to the NRC's regulatory functions would come to light in a time frame comparable to the 60-day LER requirements.
The information would become available to the appropriate NRC staff through the inspection program, updates to program documents, resultant licensing actions, public announcements, or some other reliable mechanism. The NRC staff finds that the elimination of Section 2.F in Palisades Nuclear Plant Facility Operating License DPR-20 will not result in a loss of information to the NRC that would adversely affect either its goal to protect public health and safety or its ability to carry out its various other regulatory responsibilities.
Therefore, the elimination of Section 2.F of the Facility Operating License DPR-20 is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment.
The Michigan State official had no comments.
-3 5.0 ENVIRONMENTAL CONSIDERATION The amendment changes recordkeeping, reporting, or administrative procedures or requirements.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding published in the Federal Register on September 9, 2008 (73 FR 52417). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCE
- 1. NRC's model SE published in the Federal Register on August 29, 2005 (70 FR 51098). Principal Contributor: M. Chawla, I'JRR Date: November 20, 2008 November 20, 2008 Vice President, Operations Entergy Nuclear Operations Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 PALISADES PLANT -ISSUANCE OF AMENDMENT RE: ELIMINATE LICENSE CONDITION 2.F (TAC NO. MD8727)
Dear Sir or Madam:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 233 to Renewed Facility Operating License No. DPR-20 for the Palisades Nuclear Plant. The amendment consists of changes to the Technical Specifications in response to your application dated May 5, 2008.
The amendment would revise renewed facility operating license DPR-20 to remove license condition 2.F. The license condition describes reporting requirements for exceeding the facility steady-state reactor core power level described in license condition 2.C. (1). The proposed change is consistent with the NRC approved change notice published in the Federal Register (70 FR 67202) on November 4, 2005, announcing the availability of this improvement through the consolidated line item improvement process. A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Sincerely, lRAI Mahesh L. Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255
Enclosures:
- 1. Amendment No. 233 to DPR-20 2. Safety Evaluation cc w/encls:
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ML082740445 Package Accession No.: ML082740429 NRR-058 OFFICE LPL3-1/PM LPL3-1/LA OGC LPL3-1/BC .A NAME MChawla /fi,..
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