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Category:Memoranda
MONTHYEARML23356A0212023-12-0101 December 2023
American Nuclear Insurers, Secondary Financial Protection (SFP) Program
ML23103A2742023-04-25025 April 2023
04-25-23 - Letter to the Honorable Charles Schumer, Et Al., Responds to Concerns Regarding Holtec Decommissioning International'S Plans to Release Effluents at the Indian Point Energy Center
ML21232A2342021-08-20020 August 2021
Memo - Revised Transcript for Public Meeting Held on July 29, 2021, in Tarrytown, Ny, Re IP Energy Center Post-Shutdown Decommissioning Activities Report
ML21056A0772021-04-0707 April 2021
Memo to File: Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Indian Point ISFSI (Docket: 72-51)
ML20104A3882020-04-13013 April 2020
Tasking in Response to the Concerns Pertaining to Gas Transmission Lines at the Indian Point Nuclear Power Plant Follow Up Activities Agency Level
ML20104A7232020-04-13013 April 2020
Tasking in Response to the Concerns Pertaining to Gas Transmission Lines at the Indian Point Nuclear Power Plant; Follow Up Activities; Office Level
ML20099F7752020-04-0909 April 2020
Report Transmittal Memo to the Commissioners, from: Margaret M. Doane
ML20058E3542020-02-27027 February 2020
Tasking Memo to Dskeen Re Concerns Identifed in Report Pertaining to Gas Transmission Lines
ML20056F0952020-02-13013 February 2020
Concerns Pertaining to Gas Transmission Lines at the Indian Point Nuclear Power Plant
ML18046B4412018-02-23023 February 2018
Review of Updated Final Safety Analysis Report, Revision 7
ML17271A0532017-09-29029 September 2017
2017 Summary of Annual Decommissioning Funding Status Reports for Reactors in Decommissioning
ML17180A5032017-09-21021 September 2017
04/19/2017 Summary of Teleconference with Entergy Nuclear Operations, Inc., Concerning Request for Additional Information Pertaining to the Indian Point Unit Nos. 2 and 3 License Renewal Application
ML17157B5422017-06-20020 June 2017
Conference Call on 2nd Round RAIs - Final
ML17128A3352017-05-23023 May 2017
Summary of Telephone Conference Call Between the NRC and Entergy Concerning RAIs Pertaining to IP2 and IP3
ML17060A6602017-04-12012 April 2017
Potentially Cost-Beneficial SAMAs
ML17082A3112017-04-11011 April 2017
Summary of Clarification Call with Entergy Regarding Follow-Up RAIs on ISG-2012-02
ML16336A4992017-01-18018 January 2017
Notice of Significant Licensing Action
ML17052A3002017-01-11011 January 2017
Security Exclusion Zone Acoustic Tag Detection Study, 9 November 2016
ML17052A3092017-01-11011 January 2017
Atlantic Sturgeon Distribution Memo
ML16088A2042016-03-28028 March 2016
Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template)
ML16088A2052016-03-28028 March 2016
Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations
ML15190A2912015-07-22022 July 2015
070115, Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Safety Review
ML15139A1952015-05-19019 May 2015
Special Inspection Team Charter - Indian Point Nuclear Generating Unit 3 - Water Accumulation in Safety-Related Switchgear Room Following Deluge of Main Transformer Fire
ML15107A1752015-04-28028 April 2015
041615, Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Environmental Review
ML15091A0972015-04-0101 April 2015
Figures from Indian Point Quarter 3 2014 Groundwater Monitoring Report - Part 4
ML14344A9652014-12-18018 December 2014
Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Environmental Review
ML14269A1972014-10-0303 October 2014
LTR-14-0463-1 - Proposed Comments to the Federal Energy Regulatory Commission'S Draft Environmental Impact Statement Algonquin Incremental Market Project (Docket No. CP14-96-000)
ML13256A0432013-09-10010 September 2013
Request for Additional Information to Entergy Nuclear Northeast, Indian Point Units 2 and 3, Regarding NTTF Recommendation 9.3 Phase 1 Staffing Assessments Submittal
ML13218A0862013-08-0808 August 2013
Notice of Forthcoming Meeting with Entergy Nuclear Operations, Inc. and Netco to Discuss the Goals and Objectives of the Long-Term Spent Fuel Pool Improvement Program for Indian Point Unit 2 and 3
ML13102A1242013-04-15015 April 2013
Summary of April 11, 2013, Telephone Conference Call Between NRC and Entergy Entry of Indian Point Nuclear Generating Unit No. 2 Into the Period of Timely Renewal
ML12361A1552012-12-26026 December 2012
Summary of Entergy Drop-In on December 19, 2012
ML12296A9292012-10-23023 October 2012
Memo Draft Request for Additional Information for Indian Point Units 1 and 2 Memo
ML12215A2482012-09-17017 September 2012
Summary of Conference Call Held on June 4, 2012, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning the Reactor Vessel Internals Program at Indian Point Nuclear Generating Station, Units 2 and 3
ML12213A0612012-08-0101 August 2012
8/16/12 Forthcoming Conference Call with NextEra Energy and Florida Power & Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Protocol
ML13196A2202012-06-0606 June 2012
Memo from B. Balsam, NRR and D. Logan, NRR to J. Susco, NRR on Summary of Section 7 Consultation Activities Related to the National Marine Fisheries Service'S Final Rule to List the Atlantic Sturgeon
ML12137A0602012-05-29029 May 2012
Nuclear Regulatory Commission'S Analysis of Entergy Nuclear Operations, Inc. Decommissioning Funding Status Report for Indian Point Nuclear Generating Station, Units 1, 2 & 3; and Pilgrim Nuclear Power Station
ML1122701452011-08-30030 August 2011
Summary of Conference Call Between NRC and Entergy Nuclear Operations, Regarding Non-EQ Inaccessible Medium-Voltage Cable Program for Indian Point Units 2 & 3
ML11201A3062011-07-29029 July 2011
Summary of Telephone Conference Calls Held on June 20, June 22, and June 29, 2011, Regarding the Ongoing Endangered Species Act Consultation for the Proposed Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal
NL-11-093, Clean Water Act Section 401 Water Quality Certification Waiver2011-07-29029 July 2011
Clean Water Act Section 401 Water Quality Certification Waiver
ML1118703442011-07-0606 July 2011
Memorandum and Order (Ruling on Pending Motions for Leave to File New and Amended Contentions)
ML1115704052011-06-0606 June 2011
Notice of Meeting with Entergy Operations, Inc., to Discuss Implementation of Quality Oversight and Verification Programs at Entergy Sites Including Actions Being Taken to Enhance Effectiveness
ML11102A0062011-05-0909 May 2011
01/12/11 Summary of Telephone Conference Call Between Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning the Final SEIS for the Proposed License Renewal of Indian Point, Units 2 and 3
ML1110909492011-04-25025 April 2011
Notice of Meeting G20110221/EDATS:OEDO-2011-0226- with the State of New York Attorney General'S Office (the Petitioner) Requesting Action Under 10 CFR 2.206 Regarding Fire Protection at Indian Point
ML1110909052011-04-22022 April 2011
NRC and Entergy Nuclear Operations, Inc. Held a Category 1 Public Meeting on April 18, 2011, to Discuss the Shortnose Sturgeon
ML1110103962011-04-11011 April 2011
Notice of Forthcoming Meeting with Entergy Nuclear Operations, Inc. to Discuss the License Amendment Requests to Permit the Transfer of Spent Fuel from the Indian Point Unit 3 Spent Fuel Pool to the Unit 2 Spent Fuel Pool
ML1109803932011-04-0808 April 2011
Forthcoming Meeting with NRC and Entergy Operations, Inc
ML11223A0412011-03-23023 March 2011
Memorandum from J. Boska, NRR to T. Quay, NRR on Review of 10 CFR 2.206 Petition on Gas Pipelines Near the Indian Point Reactors
ML1107504052011-03-21021 March 2011
Notice of Meeting with Entergy Operations, Inc., to Discuss Fleetwide Submittal for Proposed Technical Specification and Quality Assurance Program Manual Changes Related to Unit Staff Qualification Requirements
ML1029106182010-10-14014 October 2010
Documentation of Telephone Conversation Between Mr. David Lochbaum Regarding Follow-Up Questions Related to NRC Letter Dated July 28, 2010 (ML102040807)
ML0931701682009-11-17017 November 2009
Summary of Teleconference Call Held on 11/3/09 Between the U.S. NRC and Entergy Nuclear Operations, Inc., Concerning Meteorological Data Used for the Severe Accident Mitigation Alternative Analyses
2023-04-25
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 SPECIAL INSPECTION TEAM CHARTER May 19, 2015 MEMORANDUM TO: Arthur L. Burritt, Manager Special Inspection Team Thomas C. Setzer, Team Leader Special Inspection Team FROM: Ho K. Nieh, Director /RA Michael L. Scott for/
Division of Reactor Projects Raymond K. Lorson, Director /RA James M. Trapp for/
Division of Reactor Safety
SUBJECT:
SPECIAL INSPECTION TEAM CHARTER -
INDIAN POINT NUCLEAR GENERATING UNIT 3 - WATER ACCUMULATION IN SAFETY-RELATED SWITCHGEAR ROOM FOLLOWING DELUGE OF MAIN TRANSFORMER FIRE In accordance with Inspection Manual Chapter (IMC) 0309, Reactive Inspection Decision Basis for Reactors, a Special Inspection Team (SIT) is being chartered to evaluate water accumulation in the Unit 3 switchgear room following deluge of a #31 main transformer fire which occurred on May 9, 2015. The decision to conduct this special inspection was based on meeting one deterministic criteria, and the event representing a preliminary conditional core damage probability in the 4 E-6 to 2 E-5 range for Unit 3.
The SIT will expand on the inspection activities started by the resident inspectors immediately after the event. The team will review Entergys organizational and operator response to the event, equipment performance and design, and the licensee casual analyses, as applicable.
The team will collect data, as necessary, to refine the preliminary risk analysis. The team will also assess whether the SIT should be upgraded to an Augmented Inspection Team.
The inspection will be conducted in accordance with the guidance contained in NRC Inspection Procedure 93812, Special Inspection, and the inspection report will be issued within 45 days following the exit meeting for the inspection.
A. Burritt, T. Setzer 2 The special inspection will commence on May 19, 2015. The following personnel have been assigned to this effort:
Manager: Arthur L. Burritt, Chief Reactor Projects Branch 2 Division of Reactor Projects Team Leader: Thomas C. Setzer, Senior Project Engineer Reactor Projects Branch 2 Division of Reactor Projects Full Time Members: Sarah C. Rich, Senior Resident Inspector (Acting), Vermont Yankee Reactor Projects Branch 5 Division of Reactor Projects Full Time Member: Roy L. Fuhrmeister, Senior Reactor Inspector Engineering Branch 3 Division of Reactor Safety
Enclosure:
Special Inspection Team Charter
ML15139A195 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP RI/DRS NAME TSetzer/ALB for ABurritt/ALB HNieh/HKN RLorson/JMT for DATE 5/ 18 /15 5/ 18 /15 5/ 19 /15 5/ 19 /15 Special Inspection Team Charter Indian Point Nuclear Generating Unit No. 3 Water Accumulation in Safety-Related Switchgear Room Following Deluge of a #31 Main Transformer Fire May 9, 2015
Background:
On May 9, 2015, at 5:50 p.m., Indian Point Unit 3 experienced an automatic reactor trip as a result of a failure of the #31 main transformer. A Notification of Unusual Event (UE) was declared at 6:01 p.m. for an explosion or fire within the stations Protected Area. The fire was initially extinguished by the stations deluge system. The fire then reignited and was extinguished by both the site fire brigade and two offsite fire departments who responded to the event. The UE was exited at 9:03 p.m.
The reactor trip was uncomplicated. All control rods inserted into the reactor core, and all safety systems responded as designed. The NRC Resident Inspectors responded to the site and independently confirmed that the plant was in a stable, safe condition.
After the reactor trip, Unit 3 was placed in Mode 4, Hot Shutdown, with normal offsite electrical power available and decay heat being removed by the residual heat removal system. Unit 2 continues to operate at 100 percent power.
During the event, approximately 1 to 2 of water accumulated in the safety-related switchgear room. The switchgear room is risk significant as it contains all trains of safety-related 480 volt power. If the switchgear is lost, other alternate sources of power can be used to safely maintain the plant shutdown.
Basis for the Formation of the SIT:
Brief Description of the Basis for the Assessment:
The Inspection Manual Chapter (IMC) 0309 review concluded that one of the deterministic criteria in Enclosure 1 of IMC 0309 was met. The criterion met was for the significant, unexpected system interaction between the fire protection deluge system and the safety-related switchgear room.
Using the Indian Point Standardized Plant Analysis Risk (SPAR) models, a Region I Senior Reactor Analyst conducted a preliminary risk analysis. The estimated conditional core damage probability (CCDP) for Unit 3 was in the 4 E-6 to 2 E-5 range.
Based upon satisfying the deterministic criterion and the estimated CCDP values for Unit 3 being in the 4 E-6 to 2 E-5 range per the SPAR models, the reactive inspection response is within the No Additional Inspection to Special Inspection overlap to the Special Inspection to Augmented Inspection Team overlap range for Unit 3. A SIT is being initiated to gather information available from the event and to verify that immediate corrective actions were appropriate.
Enclosure
2 Objectives of the Special Inspection:
The SIT will expand on the inspection activities started by the resident inspectors immediately after the event. The team will review Entergys organizational and operator response to the event, equipment performance and design, and the licensee casual analyses, as applicable.
The team will collect data, as necessary, to refine the preliminary risk analysis. The team will also assess whether the SIT should be upgraded to an Augmented Inspection Team.
To accomplish these objectives, the team will:
- 1. Develop a complete sequence of events including follow-up actions taken by Entergy;
- 2. Review and assess the equipment response to the fire resulting in water accumulation in the switchgear room. This assessment should evaluate the system response against the plants design and regulatory requirements to assess the adequacy of the equipment design and maintenance;
- 3. Review and assess operator and fire brigade performance in identifying and isolating the sources of water into the switchgear room, including review of procedures, logs, and communications (internal and external);
- 4. Review and assess the effectiveness of Entergys response to the water intrusion.
This includes overall organizational response, failure modes and effect analysis developed for the equipment challenges, and interim and proposed longer term corrective actions;
- 5. Review Entergys evaluations of pertinent industry fire-fighting operating experience and evaluation of potential precursors relating to the potential for water accumulation, including the effectiveness of any actions taken; and
- 6. Collect data necessary to refine the existing risk analysis and document the final risk analysis in the SIT report.
Guidance:
Inspection Procedure 93812, Special Inspection, provides additional guidance to be used by the SIT. Team duties will be as described in Inspection Procedure 93812. The inspection should emphasize fact-finding in its review of the circumstances surrounding the event. Safety concerns identified that are not directly related to the event should be reported to the Region I office for action.
The Team will conduct an entrance meeting and begin the inspection on May 19, 2015. While on site, the Team Leader will provide daily briefings to Region I management, who will coordinate with the Office of Nuclear Reactor Regulation to ensure that all other parties are kept informed. A report documenting the results of the inspection will be issued within 45 days following the final exit meeting for the inspection.
This Charter may be modified should the team develop significant new information that warrants review.
Enclosure
