|
|
| (4 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML17100A128 | | | number = ML17100A128 |
| | issue date = 04/11/2017 | | | issue date = 04/11/2017 |
| | title = Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment of Inter Unit Transfer of Spent Fuel (CAC Nos. MF8991 and MF8992) | | | title = Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment of Inter Unit Transfer of Spent Fuel |
| | author name = Pickett D V | | | author name = Pickett D |
| | author affiliation = NRC/NRR/DORL/LPLI | | | author affiliation = NRC/NRR/DORL/LPLI |
| | addressee name = | | | addressee name = |
| Line 9: |
Line 9: |
| | docket = 05000247, 05000286 | | | docket = 05000247, 05000286 |
| | license number = DPR-026, DPR-064 | | | license number = DPR-026, DPR-064 |
| | contact person = Pickett D V, NRR/DORL/LPL1, 415-1364 | | | contact person = Pickett D, NRR/DORL/LPL1, 415-1364 |
| | case reference number = CAC MF8991, CAC MF8992 | | | case reference number = CAC MF8991, CAC MF8992 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 4 | | | page count = 4 |
| | project = CAC:MF8991, CAC:MF8992 | | | project = CAC:MF8991, CAC:MF8992 |
| | stage = Supplement | | | stage = Acceptance Review |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511 0249 .\.pril 11, 2017 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 |
| | .\.pril 11, 2017 Vice President, Operations Entergy Nuclear Operations, Inc. |
| | Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511 0249 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 -SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: AMENDMENT OF INTER-UNIT TRANSFER OF SPENT FUEL (CAC NOS. MF8991 AND MF8992) | | INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 - |
| | SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: AMENDMENT OF INTER-UNIT TRANSFER OF SPENT FUEL (CAC NOS. MF8991 AND MF8992) |
|
| |
|
| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| By letter dated December 14, 2016 (Agencywide Documents Access and Management System Package Accession No. ML 16355A066), Entergy Nuclear Operations, Inc. (the licensee) submitted a license amendment request for Indian Point Nuclear Generating Unit Nos. 2 and 3. The proposed amendment would revise the technical specifications to relax existing restrictions involving the U.S. Nuclear Regulatory Commission's (NRC's) previous approval for the inter-unit transfer of spent fuel assemblies from the Unit No. 3 to the Unit No. 2 spent fuel pool. The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the 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. Consistent with Section 50.90 of Title 1 O of the Code of Federal Regulations (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 1 O CFR addresses the content of technical information required. | | By letter dated December 14, 2016 (Agencywide Documents Access and Management System Package Accession No. ML16355A066), Entergy Nuclear Operations, Inc. (the licensee) submitted a license amendment request for Indian Point Nuclear Generating Unit Nos. 2 and 3. |
| | The proposed amendment would revise the technical specifications to relax existing restrictions involving the U.S. Nuclear Regulatory Commission's (NRC's) previous approval for the inter-unit transfer of spent fuel assemblies from the Unit No. 3 to the Unit No. 2 spent fuel pool. The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the 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. |
| | Consistent with Section 50.90 of Title 1O of the Code of Federal Regulations (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. | | This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. |
| The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. | | The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. |
| In order to make the application complete, the NRC staff requests that the licensee supplement the application to address the information requested in the enclosure by April 26, 2017. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. | | In order to make the application complete, the NRC staff requests that the licensee supplement the application to address the information requested in the enclosure by April 26, 2017. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of |
| If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. | | |
| The information requested and associated time frame in this letter were discussed with Mr. Robert Walpole of your staff on April 7, 2017. If you have any questions, please contact me at (301) 415-1364 or by e-mail to Douglas.Pickett@nrc.gov. | | any further information needed to support the staff's detailed technical review by separate correspondence. |
| Docket Nos. 50-24 7 and 50-286 cc: Distribution via Listserv | | The information requested and associated time frame in this letter were discussed with Mr. Robert Walpole of your staff on April 7, 2017. |
| | If you have any questions, please contact me at (301) 415-1364 or by e-mail to Douglas.Pickett@nrc.gov. |
| | Sincerely, |
| | ~I Douglas V. Pickett, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-24 7 and 50-286 cc: Distribution via Listserv |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
|
| |
|
| Request for Supplemental Information Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR SUPPLEMENTAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING INTER-UNIT TRANSFER OF SPENT FUEL ENTERGY NUCLEAR OPERATIONS. | | Request for Supplemental Information |
| INC. INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NOS. 50 247 AND 50 286 The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclar Reactor Regulation (NRR), staff has completed its acceptance review of Entergy Nuclear Operations, lnc.'s license amendment request (LAR) dated December 14, 2016 (Agencywide Documents Access and Management System Package Accession No. ML 16355A066), that would relax restrictions related to the inter-unit transfer of spent fuel assemblies between Indian Point Nuclear Generating (Indian Point) Unit No. 2 and Unit No. 3 spent fuel pools. In accordance with NRR Office Instruction LIC 109, "Acceptance Review Procedures," the staff has found the application to be unacceptable, with the opportunity to supplement. | | |
| This is primarily due to unresolved non-conservatisms related to the Unit No. 2 spent fuel pool technical specifications. | | REQUEST FOR SUPPLEMENTAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING INTER-UNIT TRANSFER OF SPENT FUEL ENTERGY NUCLEAR OPERATIONS. INC. |
| In order to proceed with the NRC staff's review, the following deficiencies will need to be addressed: | | INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NOS. 50 247 AND 50 286 The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclar Reactor Regulation (NRR), |
| (1) The shielded transfer canister (STC) LAR provides inadequate justification for loading spent nuclear fuel from Indian Point Unit No. 3 into the STC because it does not consider the effect of fuel assembly grid spacer expansion as a physical change to the fuel during irradiation. | | staff has completed its acceptance review of Entergy Nuclear Operations, lnc.'s license amendment request (LAR) dated December 14, 2016 (Agencywide Documents Access and Management System Package Accession No. ML16355A066), that would relax restrictions related to the inter-unit transfer of spent fuel assemblies between Indian Point Nuclear Generating (Indian Point) Unit No. 2 and Unit No. 3 spent fuel pools. In accordance with NRR Office Instruction LIC 109, "Acceptance Review Procedures," the staff has found the application to be unacceptable, with the opportunity to supplement. This is primarily due to unresolved non-conservatisms related to the Unit No. 2 spent fuel pool technical specifications. In order to proceed with the NRC staff's review, the following deficiencies will need to be addressed: |
| (2) The STC LAR provides no justification for loading fresh unpoisoned fuel with a maximum 5.0 weight percent (wt%) enrichment of U 23 5 into the Indian Point Unit No. 2 spent fuel pool (SFP) Region 1-2, as it does not address the current Indian Point Unit No. 2 Technical Specification 3.7.13 limitation on loading fresh unirradiated fuel into the Indian Point Unit No. 2 SFP Region 1-2, nor does it consider the effect on the interface with Indian Point Unit No. 2 SFP Regions 1-1, 2-1, and 2-2. (3) The STC LAR provides no justification that misleading one or more fresh unpoisoned fuel assemblies with a maximum 5.0 wt% enrichment of U 2 3 5 into the Indian Point Unit No. 2 SFP Regions 1-1, 2-1, and 2-2 would meet Title 10 of the Code of Federal Regulations Section 50.68 regulatory requirements for subcriticality margin. Enclosure | | (1) The shielded transfer canister (STC) LAR provides inadequate justification for loading spent nuclear fuel from Indian Point Unit No. 3 into the STC because it does not consider the effect of fuel assembly grid spacer expansion as a physical change to the fuel during irradiation. |
| | (2) The STC LAR provides no justification for loading fresh unpoisoned fuel with a maximum 5.0 weight percent (wt%) enrichment of U23 5 into the Indian Point Unit No. 2 spent fuel pool (SFP) Region 1-2, as it does not address the current Indian Point Unit No. 2 Technical Specification 3.7.13 limitation on loading fresh unirradiated fuel into the Indian Point Unit No. 2 SFP Region 1-2, nor does it consider the effect on the interface with Indian Point Unit No. 2 SFP Regions 1-1, 2-1, and 2-2. |
| | (3) The STC LAR provides no justification that misleading one or more fresh unpoisoned fuel assemblies with a maximum 5.0 wt% enrichment of U2 35 into the Indian Point Unit No. 2 SFP Regions 1-1, 2-1, and 2-2 would meet Title 10 of the Code of Federal Regulations Section 50.68 regulatory requirements for subcriticality margin. |
| | Enclosure |
|
| |
|
| ==SUBJECT:==
| | ML17100A128 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DSS/SNPB/BC DORL/LPL 1/BC DORL/LPL 1/PM NAME DPickett LRonewicz RLukes JDanna DPickett (RGuzman for) (RGuzman for) |
| INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 -SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: AMENDMENT OF INTER-UNIT TRANSFER OF SPENT FUEL (CAC NOS. MF8991 AND MF8992) DATED APRIL 11, 2017 DISTRIBUTION:
| | DATE 04/10/2017 04/10/2017 04/10/2017 04/10/2017 04/11/2017}} |
| Public LPL 1 R/F RidsNrrDorl RidsNrrDorlLpl 1 RidsNrrLALRonewicz RidsRgn1 MailCenter RidsACRS_MailCTR RidsNrrDssSnpb KWood, NRR TSetzer, R-1 RidsNrrPMlndianPoint RGuzman, NRR RidsACRS_MailCTR ADAMS Accession No.: ML 17100A128 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DSS/SNPB/BC DORL/LPL 1/BC NAME DPickett LRonewicz RLukes JDanna (RGuzman for) DATE 04/10/2017 04/10/2017 04/10/2017 04/10/2017 OFFICIAL RECORD COPY DORL/LPL 1/PM DPickett (RGuzman for) 04/11/2017}}
| |
Letter Sequence Acceptance Review |
|---|
|
|
MONTHYEARNL-16-118, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel2016-12-14014 December 2016
Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel
Project stage: Other
ML17100A1282017-04-11011 April 2017
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment of Inter Unit Transfer of Spent Fuel
Project stage: Acceptance Review
NL-17-044, Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Amendment of Inter-Unit Transfer of Spent Fuel2017-04-19019 April 2017
Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Amendment of Inter-Unit Transfer of Spent Fuel
Project stage: Request
ML17115A0482017-04-26026 April 2017
Acceptance of Requested Licensing Action Amendment of Inter-Unit Transfer of Spent Fuel
Project stage: Acceptance Review
ML17197A0002017-07-17017 July 2017
Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel
Project stage: RAI
ML17219A1062017-08-10010 August 2017
Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel - Shielded Transfer Canister Requests for Additional Information
Project stage: RAI
NL-17-102, Response to Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel2017-08-16016 August 2017
Response to Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel
Project stage: Response to RAI
ML17261B1902017-09-18018 September 2017
Request for RAI Response Due Date Extension License Amendment Request for Inter-Unit Transfer of Spent Fuel (CAC Nos. MF8991 and MF8992)
Project stage: RAI
ML17267A0002017-09-22022 September 2017
E-mail from R.Guzman to R.Walpole Indian Point Unit Nos. 2 and 3 - Request for RAI Response Due Date Extension License Amendment Request for Inter-Unit Transfer of Spent Fuel
Project stage: RAI
NL-17-115, Response to Request for Additional Information Re Inter-Unit Transfer of Spent Fuel, Attachments 1, 2, 3 (non-proprietary Version of Report HI-2094289, Rev. 9) and 7 Enclosed2017-10-0202 October 2017
Response to Request for Additional Information Re Inter-Unit Transfer of Spent Fuel, Attachments 1, 2, 3 (non-proprietary Version of Report HI-2094289, Rev. 9) and 7 Enclosed
Project stage: Response to RAI
ML17289A6552017-10-0202 October 2017
Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9
Project stage: Other
ML17298B6472017-10-25025 October 2017
10/25/17 E-mail from M. Mirzai to R. Guzman Inter-Unit Transfer of Spent Fuel LAR - Clarification Response Following Teleconference on October 19, 2017
Project stage: Meeting
ML17300A1742017-10-27027 October 2017
10/27/17 E-mail from M. Mirzai to R. Guzman Inter-Unit Transfer of Spent Fuel LAR - Updated Clarification Response Following Teleconference on October 19, 2017
Project stage: Meeting
ML17316A0022017-11-27027 November 2017
Request for Withholding Information from Public Disclosure (CAC Nos. MF8991 and MF8992; EPID: L-2016-LLA-0039)
Project stage: Withholding Request Acceptance
ML17316A0012017-11-27027 November 2017
Request for Withholding Information from Public Disclosure (CAC Nos. MF8991 and MF8992; EPID: L-2016-LLA-0039)
Project stage: Withholding Request Acceptance
ML17316A0002017-11-27027 November 2017
Request for Withholding Information from Public Disclosure (CAC Nos. MF8991 and MF8992; EPID: L-2016-LLA-0039)
Project stage: Withholding Request Acceptance
ML17320A3542017-12-22022 December 2017
Issuance of Amendments Amendment of Inter-Unit Transfer of Spent Fuel (CAC Nos. MF8991 and MF8992; EPID L-2016-LLA-0039)
Project stage: Approval
2017-04-11
[Table View] |
|
|---|
Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
IR 05000003/20240022024-08-0606 August 2024
NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002
PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024
Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0
ML24171A0122024-06-18018 June 2024
Reply to a Notice of Violation EA-24-037
ML24156A1162024-06-0404 June 2024
Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
IR 05000003/20240052024-05-21021 May 2024
and 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation
ML24128A0632024-05-0707 May 2024
Submittal of 2023 Annual Radiological Environmental Operating Report
L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024
HDI Annual Occupational Radiation Exposure Data Reports - 2023
ML24116A2412024-04-25025 April 2024
Annual Environmental Protection Plan Report
ML24114A2282024-04-23023 April 2024
Annual Radioactive Effluent Release Report
L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024
Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)
ML24080A1722024-03-20020 March 2024
Reply to a Notice of Violation EA-2024-010
IR 05000003/20240012024-03-20020 March 2024
NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only)
ML24045A0882024-02-22022 February 2024
Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments
ML24053A0642024-02-22022 February 2024
2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report
IR 05000003/20230042024-02-22022 February 2024
NRC Inspection Report Nos. 05000003/2023004, 05000247/2023004, 05000286/2023004, and 07200051/2023004 and Notice of Violation
ML24011A1982024-01-12012 January 2024
ISFSI, Notice of Organization Change for Site Vice President
ML23342A1082024-01-0909 January 2024
– Independent Spent Fuel Storage Installation Security Inspection Plan
ML23353A1742023-12-19019 December 2023
ISFSI, Emergency Plan, Revision 23-04
L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023
Proof of Financial Protection 10 CFR 140.15
ML23326A1322023-12-0505 December 2023
Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan
ML23339A0442023-12-0505 December 2023
Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan
ML23338A2262023-12-0404 December 2023
Signed Amendment No. 27 to Indemnity Agreement No. B-19
ML23356A0212023-12-0101 December 2023
American Nuclear Insurers, Secondary Financial Protection (SFP) Program
ML23242A2772023-11-30030 November 2023
NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs
ML23338A0482023-11-30030 November 2023
ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28
ML22339A1572023-11-27027 November 2023
Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E
IR 05000003/20230032023-11-21021 November 2023
NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003
ML23100A1252023-11-17017 November 2023
Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement
ML23100A1172023-11-17017 November 2023
NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition
ML23050A0032023-11-17017 November 2023
Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage
ML23100A1432023-11-16016 November 2023
Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286)
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
ML23064A0002023-11-13013 November 2023
NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments
ML23306A0992023-11-0202 November 2023
and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7)
ML23063A1432023-11-0101 November 2023
Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50
ML23292A0262023-10-19019 October 2023
LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI
ML23289A1582023-10-16016 October 2023
Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit
ML23270A0082023-09-27027 September 2023
Registration of Spent Fuel Casks
ML23237A5712023-09-22022 September 2023
09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River
ML23242A2182023-09-12012 September 2023
IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286)
ML23250A0812023-09-0707 September 2023
Registration of Spent Fuel Casks
ML23255A0142023-08-31031 August 2023
LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report
IR 05000003/20230022023-08-22022 August 2023
NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002
ML23227A1852023-08-15015 August 2023
Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme
ML23222A1442023-08-10010 August 2023
Registration of Spent Fuel Casks
ML23208A1642023-07-26026 July 2023
Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater
ML23200A0422023-07-19019 July 2023
Registration of Spent Fuel Casks
ML23235A0602023-07-17017 July 2023
LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River
2024-09-18
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23171B0442023-06-23023 June 2023
Enclosure - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment
ML22292A2402022-10-21021 October 2022
RAIs for Master Dtf Agreement on IP1 IP2 10 18 2022
ML22103A2442022-04-13013 April 2022
Attachment - Request for Additional Information - License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme for Permanently Defueled Condition for Indian Point Energy Center
ML22104A0352022-04-13013 April 2022
Request for Additional Information Related to Exemption Request from Emergency Planning Holtec Decommissioning International, LLC Indian Point Energy Center
ML22006A0452022-01-0505 January 2022
PSDAR RAIs Final
ML21337A2952021-12-0303 December 2021
Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (E-mail Dated 12/3/2021)
ML21183A1602021-06-30030 June 2021
Update Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (06/30/2021 E-mail)
ML21138A9412021-05-18018 May 2021
Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (05/18/2021 E-mail)
ML21112A2672021-04-22022 April 2021
Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (Public Redacted Version)
ML21019A5672021-01-19019 January 2021
Second Round Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device
ML21013A0152021-01-12012 January 2021
Draft Request for Additional Information (E-mail Dated 1/12/2021) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device
ML20268C2352020-09-24024 September 2020
Request for Additional Information (E-mail Dated 9/24/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device
ML20233B0152020-08-20020 August 2020
Request for Additional Information (E-mail Dated 8/20/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device
ML20190A2342020-07-0808 July 2020
Request for Additional Information - Application for Order Consenting to Transfers of Control of Licenses (07/08/2020 E-mail)
ML20190A1502020-06-25025 June 2020
(06/25/2020 E-mail) Draft Request for Additional Information Application for Order Consenting to Transfers of Control of Licenses
ML20106F2492020-04-15015 April 2020
E-mail (04/15/2020) Request for Additional Information Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic
ML20070J7902020-03-10010 March 2020
Request for Information to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000286/2020012
ML19045A6252019-02-14014 February 2019
Request for Additional Information - Proposed License Amendment Request Regarding Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool - 2/14/19 E-mail from R.Guzman to M.Mirzai
NL-18-053, Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension2018-07-18018 July 2018
Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension
ML18155A4842018-06-0404 June 2018
Request for Additional Information Regarding Relief Request IP3-ISI-RR-11, E-mail from R.Guzman to C.Mackaman
ML18143B6792018-05-23023 May 2018
Request for Additional Information Regarding LAR for One-Time Extension of the Containment Leakage Rate Test - Email from R.Guzman to M.Mirzai
ML18094B0922018-04-0505 April 2018
Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59)
ML17296A2352017-10-23023 October 2017
Request for Additional Information -10/23/17 E-mail from R.Guzman to R.Louie Cyber Security Plan Milestone 8 Implementation Schedule (CAC Nos. MF9656, MF9657, MF9658; EPID: L-2017-LLA-0217)
ML17277B5482017-10-0303 October 2017
Request for Additional Information - Relief Request IP2-ISI-RR-20 Regarding Weld Examination
ML17219A1062017-08-10010 August 2017
Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel - Shielded Transfer Canister Requests for Additional Information
ML17200A0852017-07-19019 July 2017
Request for Additional Information Regarding the Connection of Non-Seismic Boric Acid Recovery System to RWST Seismic Piping
ML17197A0002017-07-17017 July 2017
Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel
ML17170A2862017-06-27027 June 2017
RAI Set 2017-06
ML17103A4182017-04-25025 April 2017
Baffle Bolt Rais. Requests for Additional Information for the Review of the Indian Point License Renewal Application (TAC Nos. MD5407 and MD5408)
ML17088A4052017-04-20020 April 2017
Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-3 (CAC Nos. MD5407 and MD5408)
ML17088A3272017-04-19019 April 2017
Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408)
ML17100A1282017-04-11011 April 2017
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment of Inter Unit Transfer of Spent Fuel
ML17046A2312017-03-0808 March 2017
Request for Additional Information for the Review of the Indian Point License Renewal - Set 2017-01
ML16232A1192016-09-12012 September 2016
Request for Additional Information for the Review of the Indian Point Nuclear Generating Units Nos. 2 and 3, License Renewal Application Environmental Review - Severe Accident Mitigation Alternatives (CAC Nos. MD5411 and MD5412)
ML16138A1942016-07-25025 July 2016
Request for Additional Information for the Review of License Renewal Application, Set 2016-01
ML16139A0302016-06-10010 June 2016
Request for Additional Information Regarding Conditional Exemption from End-of-Line Moderator Temperature Coefficient Measurement
ML16112A2262016-04-26026 April 2016
Request for Additional Information Regarding Relief Request IP2-ISI-RR-02 Alternative Examination Volume Required by Code Case N-729-1
ML16041A5782016-02-18018 February 2016
Request for Additional Information Related to License Amendment Request Regarding Moderator Temperature Coefficient Measurement Change
ML16005A6292016-01-14014 January 2016
Request for Additional Information Regarding Relief Request IP2-RR-19
ML16013A0642016-01-13013 January 2016
NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097)
ML15341A1662015-12-0707 December 2015
NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349)
ML15148A4032015-06-29029 June 2015
Request for Additional Information Regarding the Spent Fuel Pool Criticality Analysis
ML15156B2742015-06-16016 June 2015
Request for Additional Information Regarding Request to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test
ML15125A0972015-05-0606 May 2015
Request for Additional Information Regarding License Amendment to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test
ML15071A1012015-05-0404 May 2015
Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-01 (TAC Nos. MD5407 and MD5408)
ML15103A2592015-04-28028 April 2015
Request for Additional Information Regarding the Proposed License Amendment to Extend the Containment Type a Leak Rate Testing Frequency to 15 Years
ML15104A5412015-04-22022 April 2015
Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412)
ML15072A4172015-03-17017 March 2015
Request for Additional Information Regarding Extension of the Containment Type a Leak Rate Testing Frequency to 15 Years
ML14329B2452015-02-18018 February 2015
Request for Additional Information for the Review of the Indian Point Nuclear Generating Units 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412)
CNRO-2015-00008, Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company2015-02-18018 February 2015
Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company
2023-06-23
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
.\.pril 11, 2017 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511 0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 -
SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: AMENDMENT OF INTER-UNIT TRANSFER OF SPENT FUEL (CAC NOS. MF8991 AND MF8992)
Dear Sir or Madam:
By letter dated December 14, 2016 (Agencywide Documents Access and Management System Package Accession No. ML16355A066), Entergy Nuclear Operations, Inc. (the licensee) submitted a license amendment request for Indian Point Nuclear Generating Unit Nos. 2 and 3.
The proposed amendment would revise the technical specifications to relax existing restrictions involving the U.S. Nuclear Regulatory Commission's (NRC's) previous approval for the inter-unit transfer of spent fuel assemblies from the Unit No. 3 to the Unit No. 2 spent fuel pool. The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the 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.
Consistent with Section 50.90 of Title 1O of the Code of Federal Regulations (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.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRC staff requests that the licensee supplement the application to address the information requested in the enclosure by April 26, 2017. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of
any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated time frame in this letter were discussed with Mr. Robert Walpole of your staff on April 7, 2017.
If you have any questions, please contact me at (301) 415-1364 or by e-mail to Douglas.Pickett@nrc.gov.
Sincerely,
~I Douglas V. Pickett, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-24 7 and 50-286 cc: Distribution via Listserv
Enclosure:
Request for Supplemental Information
REQUEST FOR SUPPLEMENTAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING INTER-UNIT TRANSFER OF SPENT FUEL ENTERGY NUCLEAR OPERATIONS. INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NOS. 50 247 AND 50 286 The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclar Reactor Regulation (NRR),
staff has completed its acceptance review of Entergy Nuclear Operations, lnc.'s license amendment request (LAR) dated December 14, 2016 (Agencywide Documents Access and Management System Package Accession No. ML16355A066), that would relax restrictions related to the inter-unit transfer of spent fuel assemblies between Indian Point Nuclear Generating (Indian Point) Unit No. 2 and Unit No. 3 spent fuel pools. In accordance with NRR Office Instruction LIC 109, "Acceptance Review Procedures," the staff has found the application to be unacceptable, with the opportunity to supplement. This is primarily due to unresolved non-conservatisms related to the Unit No. 2 spent fuel pool technical specifications. In order to proceed with the NRC staff's review, the following deficiencies will need to be addressed:
(1) The shielded transfer canister (STC) LAR provides inadequate justification for loading spent nuclear fuel from Indian Point Unit No. 3 into the STC because it does not consider the effect of fuel assembly grid spacer expansion as a physical change to the fuel during irradiation.
(2) The STC LAR provides no justification for loading fresh unpoisoned fuel with a maximum 5.0 weight percent (wt%) enrichment of U23 5 into the Indian Point Unit No. 2 spent fuel pool (SFP) Region 1-2, as it does not address the current Indian Point Unit No. 2 Technical Specification 3.7.13 limitation on loading fresh unirradiated fuel into the Indian Point Unit No. 2 SFP Region 1-2, nor does it consider the effect on the interface with Indian Point Unit No. 2 SFP Regions 1-1, 2-1, and 2-2.
(3) The STC LAR provides no justification that misleading one or more fresh unpoisoned fuel assemblies with a maximum 5.0 wt% enrichment of U2 35 into the Indian Point Unit No. 2 SFP Regions 1-1, 2-1, and 2-2 would meet Title 10 of the Code of Federal Regulations Section 50.68 regulatory requirements for subcriticality margin.
Enclosure
ML17100A128 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DSS/SNPB/BC DORL/LPL 1/BC DORL/LPL 1/PM NAME DPickett LRonewicz RLukes JDanna DPickett (RGuzman for) (RGuzman for)
DATE 04/10/2017 04/10/2017 04/10/2017 04/10/2017 04/11/2017
