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| | issue date = 09/19/2008 | | | issue date = 09/19/2008 |
| | title = Acceptance of Requested Licensing Action Relief Request and Supporting Amendment to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination | | | title = Acceptance of Requested Licensing Action Relief Request and Supporting Amendment to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination |
| | author name = Chawla M L | | | author name = Chawla M |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = | | | addressee name = |
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| | docket = 05000255 | | | docket = 05000255 |
| | license number = DPR-020 | | | license number = DPR-020 |
| | contact person = Chawla M L, NRR/DORL, 415-8371 | | | contact person = Chawla M, NRR/DORL, 415-8371 |
| | case reference number = TAC MD9265, TAC MD9266 | | | case reference number = TAC MD9265, TAC MD9266 |
| | document type = Code Relief or Alternative, Letter | | | document type = Code Relief or Alternative, Letter |
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| =Text= | | =Text= |
| {{#Wiki_filter:September 19, 2008 Vice President, Operations Entergy Nuclear Operations Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 | | {{#Wiki_filter:September 19, 2008 Vice President, Operations Entergy Nuclear Operations Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| PALISADES PLANT - ACCEPTANCE OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST AND SUPPORTING AMENDMENT TO EXTEND THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL FOR REACTOR VESSEL WELD EXAMINATION (TAC NOS. MD9265 AND MD9266) | | PALISADES PLANT - ACCEPTANCE OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST AND SUPPORTING AMENDMENT TO EXTEND THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL FOR REACTOR VESSEL WELD EXAMINATION (TAC NOS. MD9265 AND MD9266) |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
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| By letters dated July 21, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082040342), Entergy Nuclear Operations, Inc. (ENO) submitted a relief request (RR) and a supporting license amendment request (LAR) (ADAMS Accession No. ML082030796) for the Palisades Plant. The proposed RR would extend the third inservice inspection interval, for reactor vessel pressure retaining welds, examination category B-A and B-D, until December 12, 2015. The supporting LAR would add a new license condition that would direct ENO to submit the information and analyses requested in Section (e) of the final Title 10 of the Code of Federal Regulations (10 CFR) 50.61a (or the proposed 10 CFR 50.61a, given in 72 FR 56275 prior to issuance of the final 10 CFR 50.61a) to the U.S. Nuclear Regulatory Commission (NRC). | | By letters dated July 21, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082040342), Entergy Nuclear Operations, Inc. (ENO) submitted a relief request (RR) and a supporting license amendment request (LAR) (ADAMS Accession No. ML082030796) for the Palisades Plant. The proposed RR would extend the third inservice inspection interval, for reactor vessel pressure retaining welds, examination category B-A and B-D, until December 12, 2015. The supporting LAR would add a new license condition that would direct ENO to submit the information and analyses requested in Section (e) of the final Title 10 of the Code of Federal Regulations (10 CFR) 50.61a (or the proposed 10 CFR 50.61a, given in 72 FR 56275 prior to issuance of the final 10 CFR 50.61a) to the U.S. Nuclear Regulatory Commission (NRC). |
| | | The purpose of this letter is to provide the results of the NRC staff=s acceptance review of these requests. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. |
| The purpose of this letter is to provide the results of the NRC staff | | The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. NRC letter dated August 19, 2008 (ADAMS Accession No. ML082210210), requested supplemental information needed for acceptance of requested licensing action. |
| =s acceptance review of these requests. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. | |
| The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. NRC letter dated August 19, 2008 (ADAMS Accession No. ML082210210), requested supplemental information needed for acceptance of requested licensing action. | |
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| Consistent with Section 50.90 of 10 CFR, an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | | Consistent with Section 50.90 of 10 CFR, an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. |
| Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of 10 CFR, the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. | | Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of 10 CFR, the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. |
| The NRC staff has reviewed your application and the supplemental information provided in your letter dated August 14, 2008 (ADAMS Accession No. ML082540053), and concluded that it Vice President, Operations does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. If you have any questions, please contact me, at (301) 415-8371. | | The NRC staff has reviewed your application and the supplemental information provided in your letter dated August 14, 2008 (ADAMS Accession No. ML082540053), and concluded that it |
| Sincerely, /RA/
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| Mahesh L. Chawla, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255
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| cc: See next page | | Vice President, Operations does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. If you have any questions, please contact me, at (301) 415-8371. |
| | Sincerely, |
| | /RA/ |
| | Mahesh L. Chawla, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255 cc: See next page |
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| ML082480100 OFFICE DORL/LPL3-1/PM DORL/LPL3-1/LA NRR/DCI/CVI/BC DORL/LPL3-1/BC NAME MChawla BTully MMitchell LJames DATE 09/ 11 /08 09/ 10 /08 09/ 11 /08 09/ 19 /08 Palisades Plant cc: Supervisor Covert Township P. O. Box 35 Covert, MI 49043 Office of the Governor P. O. Box 30013 Lansing, MI 48909 U.S. Nuclear Regulatory Commission Resident Inspector's Office Palisades Plant 27782 Blue Star Memorial Highway Covert, MI 49043 Michigan Department of Environmental Quality Waste and Hazardous Materials Division Radiological Protection Section Radiological Assessment Unit Constitution Hall, Lower-Level North 525 West Allegan Street P.O. Box 30241 Lansing, MI 48909-7741 Michigan Department of Attorney General Special Litigation Division 525 West Ottawa St. Sixth Floor, G. Mennen Williams Building Lansing, MI 48913 Senior Vice President Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995 Vice President Oversight Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995 Senior Manager, Nuclear Safety & Licensing Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995 Senior Vice President and COO Entergy Nuclear Operations 440 Hamilton Avenue White Plains, NY 10601 Assistant General Counsel Entergy Nuclear Operations 440 Hamilton Avenue White Plains, NY 10601 Manager, Licensing Entergy Nuclear Operations Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530}} | | ML082480100 OFFICE DORL/LPL3-1/PM DORL/LPL3-1/LA NRR/DCI/CVI/BC DORL/LPL3-1/BC NAME MChawla BTully MMitchell LJames DATE 09/ 11 /08 09/ 10 /08 09/ 11 /08 09/ 19 /08 Palisades Plant cc: |
| | Supervisor Senior Vice President and COO Covert Township Entergy Nuclear Operations P. O. Box 35 440 Hamilton Avenue Covert, MI 49043 White Plains, NY 10601 Office of the Governor Assistant General Counsel P. O. Box 30013 Entergy Nuclear Operations Lansing, MI 48909 440 Hamilton Avenue White Plains, NY 10601 U.S. Nuclear Regulatory Commission Resident Inspector's Office Manager, Licensing Palisades Plant Entergy Nuclear Operations 27782 Blue Star Memorial Highway Palisades Nuclear Plant Covert, MI 49043 27780 Blue Star Memorial Highway Covert, MI 49043-9530 Michigan Department of Environmental Quality Waste and Hazardous Materials Division Radiological Protection Section Radiological Assessment Unit Constitution Hall, Lower-Level North 525 West Allegan Street P.O. Box 30241 Lansing, MI 48909-7741 Michigan Department of Attorney General Special Litigation Division 525 West Ottawa St. |
| | Sixth Floor, G. Mennen Williams Building Lansing, MI 48913 Senior Vice President Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995 Vice President Oversight Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995 Senior Manager, Nuclear Safety |
| | & Licensing Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995}} |
Letter Sequence Acceptance Review |
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MONTHYEARML0825400532008-08-14014 August 2008
Response to Request for Additional Information Concerning Authorization to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination
Project stage: Response to RAI
ML0822102102008-08-19019 August 2008
Supplemental Information Needed for Acceptance Requested Licensing Action Relief Request and Supporting Amendment to Extend Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination
Project stage: Other
ML0824801002008-09-19019 September 2008
Acceptance of Requested Licensing Action Relief Request and Supporting Amendment to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination
Project stage: Acceptance Review
ML0901208962009-02-11011 February 2009
Evaluation of Relief Request to Extend the Third 10- Year Inservice Inspection Interval for Reactor Vessel Weld Examination
Project stage: Other
ML0902204422009-02-11011 February 2009
Issuance of Amendment Change to In-Service Inspection Interval.
Project stage: Approval
2008-08-19
[Table View] |
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Category:Code Relief or Alternative
MONTHYEARML21299A0032021-10-28028 October 2021
and Waterford Steam Electric Station, Unit 3 - Approval of Request for Alternative EN-20-RR-003 from Certain Requirements of the ASME Code
ML20365A0012021-01-19019 January 2021
Relief Request 5-8 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles
ML20282A7642020-10-16016 October 2020
Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant - Relief Request 5-8 for Alternate Repair of Reactor Closure Head Penetration Nozzles
ML20275A3432020-10-0101 October 2020
Verbal Authorization for Proposed Alternative (RR 5-8) Reactor Vessel Closure Head Penetration Repairs
ML20272A1662020-09-30030 September 2020
Attachment 3 - Framatome Document No. ANP-3876, Revision 1Q1NP, Response to NRC Request for Additional Information of Palisades Relief Request Number RR 5-8, Repair of Reactor Pressure Vessel Head Penetration, Inservice Inspection Program,
ML20267A3872020-09-23023 September 2020
Relief Request Number RR 5-8, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations
ML20267A3882020-09-23023 September 2020
Attachment 1 - Relief Request Number RR 5-8, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations
CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020
Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)
ML19254A6032019-09-19019 September 2019
Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1
CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019
Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1
ML18128A0672018-06-0808 June 2018
Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4
CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017
Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1
ML21067A4982017-09-0707 September 2017
Relief Request No. RR 5-4 Proposed Alternative, Weld Reference System
ML17194A8072017-08-14014 August 2017
Relief Request No. RR 4-25 Limited Coverage Examinations During the Fourth 10-Year Inservice Inspection Interval
ML17137A0282017-06-29029 June 2017
Relief Request Number RR 5; 5 Proposed Alternative, Under-Vessel Leakage Examination
ML16096A2692016-06-0606 June 2016
Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1
ML16022A1072016-02-0101 February 2016
Relief Request Number RR 4-23- Proposed Alternative Concerning ASME Code Depth Sizing Requirement
ML15320A2442015-11-25025 November 2015
Relief Request Number 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-Year ISI Interval for ISI Related Activities
PNP 2015-073, Forwards Response to Request for Additional Information Regarding Relief Request Number RR 4-22 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination2015-09-17017 September 2015
Forwards Response to Request for Additional Information Regarding Relief Request Number RR 4-22 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination
PNP 2015-075, Submittal of Relief Request Number RR 4-23, Proposed Alternative Concerning ASME Code Depth Sizing Requirement2015-09-16016 September 2015
Submittal of Relief Request Number RR 4-23, Proposed Alternative Concerning ASME Code Depth Sizing Requirement
CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015
Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division
PNP 2015-024, Requests Relief of Proposed Alternatives for the Fifth 10-Year Inservice Test Interval2015-05-19019 May 2015
Requests Relief of Proposed Alternatives for the Fifth 10-Year Inservice Test Interval
PNP 2015-022, Relief Request Number RR 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-year ISI Interval for ISI Related Activities2015-04-29029 April 2015
Relief Request Number RR 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-year ISI Interval for ISI Related Activities
ML14199A5572014-08-13013 August 2014
Relief Request Number RR-4-19, Proposed Alternative to the Requirements of ASME Code Case N-638-4
ML12258A3522012-09-26026 September 2012
Relief from Certain Requirements of the ASME Code Case N-77-1 for the Fourth 10-Year Inservice Inspection Interval
CNRO-2008-00035, Follow-up to Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10CFR50.48(c), National Fire Protection Association Standard NFPA 8052008-11-20020 November 2008
Follow-up to Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10CFR50.48(c), National Fire Protection Association Standard NFPA 805
ML0824801002008-09-19019 September 2008
Acceptance of Requested Licensing Action Relief Request and Supporting Amendment to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination
ML0726304272007-09-21021 September 2007
Relief, Request Relief No. 1 - from Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Requirements for Repair of Pressurizer Nozzle Penetrations
ML0719002512007-09-12012 September 2007
Relief Request 1 for the Repair of Reactor Vessel Closure Head Penetrations
ML0716201362007-09-12012 September 2007
Relief Request 2 for ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations
ML0716302482007-05-31031 May 2007
Request for Relief from ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Vent Line Penetration
ML0709200292007-04-30030 April 2007
Request for Relief from ASME Code Regarding Weld Reference System, Relief Request No. RR 4-11
ML0617103642006-07-0303 July 2006
Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 - Use of ASME Code Case N-513-2
ML0607902512006-04-0303 April 2006
Request for Relief from ASME Code, Section XI, Requirements for Repair of Pressurizer Nozzle Penetrations
ML0607900612006-04-0303 April 2006
Request for Authorization to Use Alternatives to ASME Code, Section XI, IWA-3300, IWBb-3142.4, IWB-3420, and IWB-3613 for Reactor Pressure Vessel Head Penetration Repair
ML0608003192006-04-0303 April 2006
Request for Authorization to Use Alternatives to ASME Code, Section XI, IWA-4120 for Reactor Pressure Vessel Head Penetration Repair
ML0605800602006-03-21021 March 2006
Request for Authorization of Relief Request Number 1 for Certain Requirements in ASME Code, Section XI, Code Case N-638-1
ML0601201042006-01-27027 January 2006
Request for Authorization to Extend the Third 10-Year ISI Interval for Reactor Vessel Visual Examination, MC6546
ML0532002962005-11-29029 November 2005
Request for Authorization to Extend the Third Inservice Inspection Interval for Reactor Vessel Weld Examination
ML0520706392005-08-17017 August 2005
Revised Relief Requests 28, 30, and 31 for 3rd 10-year Pump and Valve Inservice Testing
ML0436504802005-01-18018 January 2005
Relief Request to Use Code Case N-661, and Safety Evaluation
ML0430901912004-11-0808 November 2004
Relief, ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations
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Verbal Authorization of Relief from ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations
ML0419103642004-09-14014 September 2004
Relief, Third 10-Year Interval Inservice Inspection Program Plan
ML0422402492004-08-0909 August 2004
Request for Relief from ASME Section XI Code Requirements for Repair of Pressurizer Nozzle Penetrations
ML0401607382004-02-26026 February 2004
Prairie, Units 1 and 2, Kewaunee, Point Beach, Units 1 and 2, Palisades, Re Request for Alternatives to ASME Section XI, Appendix Viii, Supplement 10
ML0311505002003-05-19019 May 2003
Risk-Informed Inservice Inspection Program TAC No. MB4420
ML0306906292003-03-20020 March 2003
3/20/2003, Palisades, Relief, Re Third Inservice Inspection Interval Program
ML0207202292002-03-0101 March 2002
Relief Code, Relief Request for Alternate ASME Code, Section XI, Risk-Informed Inservice Inspection Program
ML0207201452002-02-27027 February 2002
Code Relief, Request for Relief from ASME Code Requirements for Inservice Inspection Pressure Test Program (Relief Request PR-07)
2021-10-28
[Table view]
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
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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
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Request for Withholding Information from Public Disclosure
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American Nuclear Insurers, Notice of Cancellation Rescinded
PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023
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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
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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
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Text
September 19, 2008 Vice President, Operations Entergy Nuclear Operations Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530
SUBJECT:
PALISADES PLANT - ACCEPTANCE OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST AND SUPPORTING AMENDMENT TO EXTEND THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL FOR REACTOR VESSEL WELD EXAMINATION (TAC NOS. MD9265 AND MD9266)
Dear Sir or Madam:
By letters dated July 21, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082040342), Entergy Nuclear Operations, Inc. (ENO) submitted a relief request (RR) and a supporting license amendment request (LAR) (ADAMS Accession No. ML082030796) for the Palisades Plant. The proposed RR would extend the third inservice inspection interval, for reactor vessel pressure retaining welds, examination category B-A and B-D, until December 12, 2015. The supporting LAR would add a new license condition that would direct ENO to submit the information and analyses requested in Section (e) of the final Title 10 of the Code of Federal Regulations (10 CFR) 50.61a (or the proposed 10 CFR 50.61a, given in 72 FR 56275 prior to issuance of the final 10 CFR 50.61a) to the U.S. Nuclear Regulatory Commission (NRC).
The purpose of this letter is to provide the results of the NRC staff=s acceptance review of these requests. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review.
The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. NRC letter dated August 19, 2008 (ADAMS Accession No. ML082210210), requested supplemental information needed for acceptance of requested licensing action.
Consistent with Section 50.90 of 10 CFR, an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of 10 CFR, the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.
The NRC staff has reviewed your application and the supplemental information provided in your letter dated August 14, 2008 (ADAMS Accession No. ML082540053), and concluded that it
Vice President, Operations does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. If you have any questions, please contact me, at (301) 415-8371.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255 cc: See next page
ML082480100 OFFICE DORL/LPL3-1/PM DORL/LPL3-1/LA NRR/DCI/CVI/BC DORL/LPL3-1/BC NAME MChawla BTully MMitchell LJames DATE 09/ 11 /08 09/ 10 /08 09/ 11 /08 09/ 19 /08 Palisades Plant cc:
Supervisor Senior Vice President and COO Covert Township Entergy Nuclear Operations P. O. Box 35 440 Hamilton Avenue Covert, MI 49043 White Plains, NY 10601 Office of the Governor Assistant General Counsel P. O. Box 30013 Entergy Nuclear Operations Lansing, MI 48909 440 Hamilton Avenue White Plains, NY 10601 U.S. Nuclear Regulatory Commission Resident Inspector's Office Manager, Licensing Palisades Plant Entergy Nuclear Operations 27782 Blue Star Memorial Highway Palisades Nuclear Plant Covert, MI 49043 27780 Blue Star Memorial Highway Covert, MI 49043-9530 Michigan Department of Environmental Quality Waste and Hazardous Materials Division Radiological Protection Section Radiological Assessment Unit Constitution Hall, Lower-Level North 525 West Allegan Street P.O. Box 30241 Lansing, MI 48909-7741 Michigan Department of Attorney General Special Litigation Division 525 West Ottawa St.
Sixth Floor, G. Mennen Williams Building Lansing, MI 48913 Senior Vice President Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995 Vice President Oversight Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995 Senior Manager, Nuclear Safety
& Licensing Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995
