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| =Text= | | =Text= |
| {{#Wiki_filter:April 21, 2021 | | {{#Wiki_filter: |
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| ==SUBJECT:==
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| ENTERGY NUCLEAR OPERATIONS, INC., INDIAN POINT NUCLEAR GENERATING STATION UNITS 1 AND 2 - NRC INSPECTION REPORT NO.
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| 05000003/2021001 AND 05000247/2021001
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| ==Dear Mr. Vitale:==
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| On March 31, 2021 the U.S. Nuclear Regulatory Commission (NRC) completed an inspection under Inspection Manual Chapter 2561, Decommissioning Power Reactor Inspection Program, at the permanently shutdown Indian Point Nuclear Generating Station Units 1 and 2. A combination of on-site and remote inspection activities (in-office reviews) were performed as a consequence of the COVID-19 public health emergency (PHE) during this inspection period. The inspection examined activities conducted under your licenses as they relate to safety and compliance with the Commissions rules and regulations, and the conditions of your licenses. The inspection consisted of observations by the inspectors, interviews with site personnel, and a review of procedures and records. The results of the inspection were discussed with Mr. Richard Burroni, Director Special Projects on March 31, 2021, and are described in the enclosed inspection report. No findings of safety significance were identified.
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| In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter, its enclosure, and your response, if any, will be made available electronically for public inspection in the NRC Public Document Room or from the NRC document system (ADAMS), accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.
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| Current NRC regulations and guidance are included on the NRC's website at www.nrc.gov; select Radioactive Waste; Decommissioning of Nuclear Facilities; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's Website at www.nrc.gov; select About NRC, Organizations & Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information'). You may also obtain these documents by contacting the Government Printing Office (GPO) toll-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required. Please contact Katherine Warner (610) 337-5389 if you have any questions regarding this matter.
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| Sincerely, Anthony Dimitriadis, Chief Decommissioning, ISFSI, and Reactor Health Physics Branch Division of Radiological Safety and Security Docket Nos. 05000003 and 05000247 License Nos. DPR-5 and DPR-26 cc w/encl: Distribution via ListServ Enclosure: Inspection Report Nos. 05000003/2021001 and 05000247/2021001 w/Attachment
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| =EXECUTIVE SUMMARY=
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| Entergy Nuclear Operations, Inc.
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| Indian Point Nuclear Generating Station Units 1 and 2 NRC Inspection Report Nos. 05000003/2021001 and 05000247/2021001 An announced decommissioning inspection was completed on March 31, 2021 at Indian Point Units 1 and 2. A combination of on-site and remote inspection activities were performed over this period. Certain inspection activities (in-office reviews) were conducted remotely as a consequence of the COVID-19 public health emergency (PHE) during this inspection period. The inspection included a review of organization and management at the site, design changes and modifications, maintenance and surveillance, self-assessments, audits, corrective actions, spent fuel safety, and decommissioning performance and status. The inspection consisted of observations by the inspectors, interviews with site personnel, a review of procedures and records, and plant walk-downs. The U.S. Nuclear Regulatory Commissions (NRC's) program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC)2561, Decommissioning Power Reactor Inspection Program."
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| Based on the results of this inspection, no findings of safety significance were identified.
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| ii
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| =REPORT DETAILS=
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| 1.0 Background IP-1 was a pressurized water reactor that was granted a 40-year Operating License in 1962, and was permanently shut down in 1974. Pursuant to the June 19, 1980 Commission Order Revoking Authority to Operate Facility and the Decommissioning Plan for Indian Point Unit No. 1, approved by the NRC in an Order, dated January 31, 1996, the reactor remains in a defueled status.
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| IP-2 was a pressurized water reactor that was granted a 40-year Operating License in 1973. On February 8, 2017, Entergy Nuclear Operations, Inc. (Entergy) notified the NRC of its intent to permanently cease power operations at IP-2 by April 30, 2020 subject to operating extensions through, but not beyond 2024 (Agencywide Documents and Access Management System (ADAMS) Accession Number: ML17044A004). On May 12, 2020, Entergy certified cessation of power operations and the permanent removal of fuel from the IP-2 reactor vessel (ADAMS Accession Number: ML20133J902). On May 13, 2020, the NRC notified Indian Point that the NRC would no longer perform its oversight activities in accordance with the Operating Reactor Assessment Program and that oversight would be conducted under the provisions outlined in IMC 2561 Decommissioning Power reactor Inspection Program (ADAMS Accession Number: ML20134H943).
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| IP-1 and IP-2 are physically contiguous and share systems, such as the integrated liquid waste system and the air handling system; and facilities, such as the chemistry and health physics laboratories. IP-1 also contains radioactive waste processing facilities that provide waste processing services for both units. Radiological effluent limits are met on an overall site basis and specific operating limits and surveillance requirements for effluent monitoring instrumentation, including stack noble gas monitoring, are discussed in the Offsite Dose Calculation Manual (ODCM).
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| IP-1 is currently in the SAFSTOR, Co-Located with Operational Unit, No Fuel in the Spent Fuel Pool Phase and IP-2 is currently in the Post Operation Transition Phase of decommissioning as described in IMC 2561. Inspection activities conducted during this quarter under Inspection Procedure (IP) 71124.04, Dose Assessment and IP 60845 Operation of Inter-Unit Fuel Transfer Canister and Cask System as part of the Reactor Oversight Process will contribute to the completion of IP 83750, Occupational Radiation Exposure and IP 60801, Spent Fuel Pool Maintenance, Surveillance, and Safety at Permanently Shutdown Reactors, respectively for this calendar year.
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| 2.0 Unit 1 Safe Storage (SAFSTOR) and Unit 2 Post-Operation Transition Performance and Status Review 2.1 Inspection Procedures 37801, 40801, 60801, 71801, 83750, 86750
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| ====a. Inspection Scope====
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| In-office reviews of information supplied by Indian Point were performed during the inspection period. The inspectors performed on-site decommissioning inspections on January 4 - 7, 2021 and March 1 - 4, 2021 supplemented by in office reviews and periodic phone calls. The inspection consisted of observations by the inspectors, interviews with site personnel, a review of procedures and records, and plant walk-downs.
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| The inspectors performed inspection activities under Inspection Procedure (IP) 71124.04, Dose Assessment and IP 60845 Operation of Inter-Unit Fuel Transfer Canister and Cask System as part of the Reactor Oversight Process this quarter. As previously stated, this effort will contribute to the completion of IP 83750, Occupational Radiation Exposure and IP 60801, Spent Fuel Pool Maintenance, Surveillance, and Safety at Permanently Shutdown Reactors, respectively for this calendar year. Inspection activities conducted during this quarter for Unit 3, the inspectors considered the shared systems and programs with the shutdown units and reviewed selected areas accordingly.
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| The inspectors performed a continuous inspection of applicable activities during the inspection period, including document reviews and interviews with plant personnel to determine whether licensee procedures and processes were in compliance with regulations and guidance associated with 10 CFR 50.59. The inspectors sampled and performed a high level review of several engineering calculations regarding spent fuel pool events and interviewed IPEC personnel focusing on the continued implementation and validity of the assumptions made in the calculations.
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| The inspectors performed a continuous inspection of applicable activities during the inspection period, including document reviews and interviews with IPEC personnel to determine if associated audits and self-assessments had been completed, and ensured issues were identified and corrected in accordance with IPECs corrective action program (CAP). The inspectors reviewed a representative selection of CAP documents to determine if a sufficiently low threshold for problem identification existed, if follow-up evaluations were of sufficient quality, and if IPEC assigned timely and appropriate prioritization for issue resolution commensurate with the significance of the issue.
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| The inspectors interviewed personnel responsible for maintenance rule implementation and reviewed the maintenance rule program and procedures, including performance criteria and monitoring of systems and components that support spent fuel safety. The inspectors reviewed changes to the IP-2 systems, structures, and components (SSCs) scoped into the maintenance rule program since the unit shut down.
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| The inspectors verified that management oversight was adequate for the Post-Operation Transition phase of decommissioning for Unit 2 and that the decommissioning organization and changes to the operating unit organizations responsibilities was appropriately implemented upon Unit 2s cessation of operations. The inspectors reviewed the plans for the sites Phase 1 organization to be implemented after the planned Unit 3 shutdown scheduled for April 30, 2021. The inspectors attended decommissioning planning meetings, as available, and met periodically with IPEC management.
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| Inspectors evaluated the licensees program of controlling storage of radioactive materials pursuant to 10 CFR 37.
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| On January 21, 2021, the inspectors toured infrequently accessed areas in the IPEC utility tunnel, which consists of components and systems common to all three units, including city water and fire water piping.
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| ====b. Observations and Findings====
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| The inspectors determined that no changes required prior NRC approval. The inspectors reviewed a change that removed language in the Defueled Safety Analysis Report (DSAR)that required Fuel Storage Building Air Filtration System (FSBAFS) to be running during normal movement of fuel in Unit 2. License Amendments 211, 229, 238, and 241 removed the requirement for the FSBAFS to be operational as long as the fuel has had an 84-hour decay period. Therefore, Entergy removed the requirement for FSBAFS to be operating, but retained that it must be functional and must be capable of being manually placed into operation in the event of a fuel handling accident, if not already operating.
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| The inspectors determined that issues had been identified and entered into the CAP and evaluated commensurate with their safety significance. The inspectors verified that audits and self-assessments reviewed were performed by qualified individuals independent of the organization being audited and that management reviewed the audits and associated corrective actions.
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| The inspectors noted that there were no systems, structures, or components scoped into the maintenance rule program for IP-1. The inspectors note that 10 CFR 50.65(a)(1)states, in part, for a nuclear power plant for which the licensee has submitted the certifications specified in 50.82(a)(1) or 52.110(a)(1) of this chapter, as applicable, this section shall only apply to the extent the licensee shall monitor the performance or condition of all structures, systems, or components associated with the storage, control, and maintenance of spent fuel in a safe condition As there is no fuel left in the Unit 1 spent fuel pools, the maintenance rule does not apply to any of its SSCs. The inspectors reviewed Entergys supplemental maintenance rule basis document for Unit 2 systems following permanent shutdown and defueling operations. The inspectors noted that IPEC significantly reduced the SSCs scoped into the maintenance rule program for IP-2 after the unit shut down. The inspectors verified that IPEC had followed the scoping criteria outlined in 10 CFR 50.65(b) and the performance criteria were acceptable for any scoped in SSCs.
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| The inspectors discussed the planned Phase 1 organization to be implemented after the planned Unit 3 shutdown in April, 2021. The inspectors noted that the Phase 1 organization contained all of the major groups necessary for Post-Operation Transition and that IPEC plans to implement a training plan to close any qualification gaps prior to the reorganization. The inspectors interviewed IPEC personnel in charge of the training program and sampled several program and functional areas to gain reasonable assurance that the site was adequately assessing training needs to ensure that the future organization did not have major functional design gaps.
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| The inspectors determined through observation of infrequently accessed areas that IPEC had maintained material condition of SSCs in those areas.
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| ====c. Conclusions====
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| Based on the results of this inspection, no findings of safety significance were identified.
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| 4.0
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| =====Exit Meeting Summary=====
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| On March 31, 2021, the inspectors presented the inspection results to Mr. Richard Burroni, Director, Special Projects, and other members of Entergys organization. No proprietary information was retained by the inspectors or documented in this report.
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| A-1
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| =SUPPLEMENTARY INFORMATION=
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| PARTIAL LIST OF PERSONS CONTACTED
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| : [[contact::R. Burroni]], Director, Special Projects
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| : [[contact::B. Bryant]], General Manager Plant Operations
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| : [[contact::R. Walpole]], Director - Regulatory Assurance and Performance Improvement
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| : [[contact::S. Stevens]], Radiation Protection Manager
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| : [[contact::M. Mirzai]], Regulatory Assurance Manager
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| : [[contact::T. Chan]], NSSS Supervisor
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| : [[contact::G. Dahl]], Regulatory Assurance
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| : [[contact::J. Doroski]], Senior Health Physics/Chemistry Specialist
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| : [[contact::A. Eng]], Regulatory Assurance
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| : [[contact::L. Fitzsimmons]], Radiation Protection Technician (BHI Contractor)
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| : [[contact::W. OBrien]], Radiation Protection Supervisor
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| : [[contact::C. Patterson]], Dry Fuel Storage
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| : [[contact::J. Breban]], Senior Security Supervisor
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| : [[contact::W. Scholtens]], Radwaste Specialist
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| : [[contact::F. Spagnuolo]], Manager- Outage
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| : [[contact::M. Trott]], Reactor Engineer
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| : [[contact::K. Alfieri]], Training Superintendent
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| ITEMS OPEN, CLOSED, AND DISCUSSED
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| None
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| LIST OF DOCUMENTS REVIEWED
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| Procedures
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| 2-AOP-FH-1, Fuel Damage or Loss of SFP Level, Revision 10
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| 2-SOP-11.1, Ventilation System Operation, Revision 69
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| 2-SOP-17.12, Spent Fuel Handling Machine and Spent Fuel Pit Operations, Revision 24
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| EN-DC-150, Condition Monitoring of Maintenance Rule Structures, Revision 14
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| EN-DC-204, Maintenance Rule Scope and Basis, Revision 4
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| EN-RW-102, Radioactive Shipping Procedure, Revision 19
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| EN-RW-104, Scaling Factors, Revision 13
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| EN-RW-105, Process Control Program, Revision 5
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| EN-RW-106, Integrated Transportation Security Plan, Revision 6
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| IP-EP-120, Emergency Classification, Revision 14
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| Audits and Reports
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| IP3LO-2020-0078, Pre-NRC Inspection Assessment for 2021 RP Inspection Areas, and Periodic
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| RP Assessment Requirements, January 29, 2021
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| QA-4-2020-IP-1, Engineering (Design Control) Audit, March 9, 2020 through May 19, 2020
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| QA-14-15-2019-IP-1, Combined Radiation Protection and Radwaste, September 20, 2019 through
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| October 29, 2019
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| QA-19-2020-IP-1, Training, January 30, 2020 through March 9, 2020
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| Enclosure
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| Condition Reports
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| CR-HQN-2021-00029
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| CR-IP2-2019-02563
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| CR-IP3-2019-01118
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| CR-IP3-2020-01838
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| CR-IP3-2021-00195
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| Miscellaneous
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| Indian Point Energy Center Supplemental Maintenance Rule Basis Document for Unit 2 Systems
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| Following Permanent Shutdown and Defueled, Revision 0
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| Indian Point Unit 2 Defueled Safety Analysis Report
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| IP-CALC-18-00064, IPEC Zirconium Fire Calculation, Revision 1
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| IP-CALC-18-00066, Shine Dose to Exclusion Area Boundary and Control Room from Spent Fuel
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| Pool during SAFSTOR, Revision 1
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| IP-CALC-19-00032, Evaluation of Spent Fuel Pool Boil Off Time, Revision 0
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| IP-CALC-20-00013, IP2 Spent Fuel Pool (SFP) Time to Boil with Reduced Water Inventory
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| (Security Plan Input), Revision 0
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| IP-RPT-18-00078, IPEC Report for the Review of Accident Analysis and NRC Regulations in
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| Support of Decommissioning, Revision 0
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| Maintenance Rule Expert Panel Meeting Minutes, dated March 3, 2020
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| Process Applicability Determination From, DSAR Section 3.10.3 revision, dated October 5, 2020
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| U2-DSAR-2020-002, October 21, 2020
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| Unit 2 and 3 System Operation Decommissioning Presentations
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| LIST OF ACRONYMS USED
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| ADAMS Agencywide Document Access Management System
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| CAP Corrective Action Program
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| DSAR Defueled Safety Analysis Report
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| Entergy Entergy Nuclear Operations, Inc.
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| FSBAFS Fuel Storage Building Air Filtration System
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| IMC Inspection Manual Chapter
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| IP Inspection Procedure
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| IPEC Indian Point Energy Center
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| IP-1 Indian Point Unit 1
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| IP-2 Indian Point Unit 2
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| IP-3 Indian Point Unit 3
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| NRC Nuclear Regulatory Commission
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| ODCM Offsite Dose Calculation Manual
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| PHE Public Health Emergency
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| QA Quality Assurance
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| SAFSTOR Safe Storage
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| SSC Structures, Systems, and Components
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| Enclosure
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