Letter Sequence Approval |
---|
|
|
MONTHYEARML15292A1612015-11-23023 November 2015 Staff Review of Netco Report Net-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels Project stage: Approval ML15288A4022015-12-0404 December 2015 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML15288A2122015-12-0404 December 2015 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML15288A1402015-12-0404 December 2015 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance 2015-11-23
[Table View] |
|
---|
Category:Letter
MONTHYEARML24011A1982024-01-12012 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 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 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency 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 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 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 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) 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 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 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 ML23194A0442023-07-11011 July 2023 Clarification for Indian Point Energy Center License Amendment Request, Independent Spent Fuel Storage Installation Physical Security Plan ML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23171B0432023-06-23023 June 2023 Letter - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML23118A0972023-06-0606 June 2023 06-06-23 Letter to the Honorable Michael V. Lawler, Et Al., from Chair Hanson Regarding Holtec'S Announcement to Expedite Plans to Release Over 500,000 Gallons of Radioactive Wastewater from Indian Point Energy Center Into the Hudson River ML23144A3512023-05-25025 May 2023 Clementina Bartolotta of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3522023-05-25025 May 2023 Loredana Bidmead of New York E-Mail Against Treated Water Release from Indian Point Site ML23144A3412023-05-25025 May 2023 Dianne Schirripa of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23144A3472023-05-25025 May 2023 David Mart of Blauvelt, New York Email Against Treated Water Release from Indian Point Site ML23144A3402023-05-25025 May 2023 Melvin Israel of New York Email Against Treated Water Release from Indian Point Site ML23144A3542023-05-25025 May 2023 Terri Thal of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3532023-05-25025 May 2023 John Shaw of New York Email Against Treated Water Release from Indian Point Site 2024-01-09
[Table view] |
Text
~p.R REG(/<'. UNITED STATES
~"\;
"" "'"o.,. NUCLEAR REGULATORY COMMISSION
! ~0 WASHINGTON, D.C. 20555-0001
<(
~ ~
~ ~ November 23, 2015
,,_-? ~o
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 NO. 2 - STAFF REVIEW OF NETCO REPORT NET-300067-01, "CRITICALITY SAFETY ANALYSIS OF THE INDIAN POINT UNIT 2 SPENT FUEL POOL WITH CREDIT FOR INSERTED NEUTRON ABSORBER PANELS" (CAC NO. MF5282)
Dear Sir or Madam:
On August 26, 2013, a Category 1 public meeting was held between Entergy Nuclear Operations, Inc. (Entergy), the licensee for Indian Point Nuclear Generating Unit No. 2 (IP2), its consultant, NETCO, and the staff of the Nuclear Regulatory Commission (NRC) in Rockville, MD, for the purpose of discussing Entergy's long-term spent fuel pool (SFP) management program. As discussed in the meeting summary (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML13256A079), the SFP management program focused on the development of a new SFP criticality safety analysis (CSA) for IP2 that would no
!onger take credit for the existing Boraflex panels but will take credit for newly designed neutron absorbing panels. While the new neutron absorbing panels had not reached final design, the CSA would be bounded by its design parameters. The program included submittal of a CSA that would be reviewed and accepted by the NRC staff, which would form the basis for a subsequent license amendment application that would seek NRC approval for the new neutron absorbing panels and revised technical specifications for the IP2 SFP.
By letter dated November 13, 2014, as supplemented by letters dated January 28, February 19, and August 14, 2015 (ADAMS Accession Nos. ML14329A194, ML15036A029, ML15062A206, and ML15261A536, respectively), Entergy submitted NETCO Report NET-300067-01, "Criticality Safety Analysis of the Indian Point 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels," for NRC review and approval.
The NRC staff reviewed the NETCO Report with the understanding that Entergy intends to submit a future license amendment referencing this report. By letter dated June 29, 2015 (ADAMS Accession No. ML15148A403), the staff issued a request for additional information (RAI) to which the licensee responded on August 14, 2015.
The report and RAI review covered both the licensee's depletion and criticality calculations using the review guidance provided in Division of Safety Systems Interim Staff Guidance 2010-01, "Staff Guidance Regarding the Nuclear Criticality Safety Analysis for Spent Fuel Pools". As part of the depletion analysis, the NRC staff reviewed (1) the depletion code validation, and (2) the selection of bounding fuel assembly and depletion conditions, which included the following modeling considerations:
- Fuel and moderator temperature
- Assembly power and operating history effects
- Hafnium flux suppression insert usage
- Axial burnup profile specification As part of the criticality analysis, the NRC staff reviewed (1) the criticality code validation, (2) the normal condition calculations, (3) the accident condition calculations, and (4) the bias and uncertainty analysis, which includes consideration of manufacturing tolerance uncertainties.
In Section 10, "Summary," of NETCO Report NET-300067-01, the licensee summarizes: (1) allowable fuel loading, (2) absorber panel requirements, (3) fuel requirements, and (4) reactor operation limits. These areas summarize the acceptable design parameters, operational practices, and corresponding limits that define the scope of the CSA performed in NETCO Report NET-300067-01.
Additionally, based on the licensee's RAI response, the NRC staff has identified several areas where further verification and discussion will be needed as part of a future license amendment application referencing NETCO Report NET-300067-01. These are as follows:
(1) Verification that the neutron absorber insert will be appropriately monitored.
(2) Verification that the neutron absorber insert installation will be procedurally controlled and that one insert type will be used as discussed in the RAI 1 response. Verify that all allowed fuel storage configurations during neutron absorber insert installation will be bounded by the CSA.
(3) Verification that any future changes to the control rod design will be appropriately captured in existing processes for changes to the facility as discussed in the RAI 15, part c response.
(4) Verification that the onsite part length control rods, as discussed in the RAI 15, part c response, are or will be appropriately controlled to ensure that they are not used in the IP2 SFP.
(5) Verification that the curve fit equation is updated consistent with the discussion in the RAI 20 response.
(6) Verification that appropriate administrative controls exist limiting the number of rods (i.e. 36) allowed to be stored in failed fuel canisters as discussed in the RAI 23 response.
(7) Verification that fuel reconstitution administrative controls, as discussed in the RAI 26 response, are appropriate and consistent with the CSA.
(8) Verification that plans for allowing missing panels are consistent with the CSA which assumes no more than "one out of every 36 cells is missing an absorber panel" as
discussed in the RAI 29 response. There should be either a discussion describing how it will be ensured that this assumption is met when installing inserts, or a discussion describing why the installation procedure would bound this assumption.
Based on its detailed review, the NRC staff finds that the CSA methodology is acceptable for use at IP2 and would meet the requirements of Title 10 Code of Federal Regulations (10 CFR) 50.68, "Criticality accident requirements," and General Design Criterion 62, "Prevention of criticality in fuel storage and handling," of 10 CFR Part 50, Appendix A, after verification of the eight areas discussed above. Any deviation from the design parameters and operational practices in a subsequent IP2 license amendment application would necessitate re-evaluation of the applicability or acceptability of the CSA methodology presented in NETCO Report NET-300067-01. The staff has no further technical concerns at this time.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247 cc: Distribution via Listserv
ML15292A161 *by memo OFFICE DORL/LPLl-1 /PM DORL/LPLl-1 /LA DSS/SRXB/BC OGC DORL/LPLl-1 /BC NAME DPickett KGoldstein CJackson EWilliamson TTate DATE 10/29/2015 10/29/2015 9/23/2015 11/19/2015 11/23/2015