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Category:Legal-Exhibit
MONTHYEARML15337A3522015-11-17017 November 2015 Official Exhibit - NYS000582-00-BD01 - Diagram of Strength Vs Amplitude by Dr. Richard T. Lahey ML15337A3372015-11-11011 November 2015 Official Exhibit - ENTR00726-00-BD01 - Track 2 Hearing Exhibit List ML15337A3322015-11-0505 November 2015 Official Exhibit - ENT000726-00-BD01 - Entergy Track 2 Hearing Exhibit List ML15337A3352015-11-0505 November 2015 Official Exhibit - RIVR14001-00-BD01 - Riverkeeper Tailored Track 2 Exhibit List ML15337A3362015-11-0505 November 2015 Official Exhibit - NRCR10001-00-BD01 - NRC Staff Track 2 Exhibit List ML15337A3332015-11-0404 November 2015 Official Exhibit - NYSR25001-00-BD01 - NYS Revised Tailored Exhibits List Relevant to Track 2 Contentions ML15337A3312015-11-0303 November 2015 Official Exhibit - NRC000230-00-BD01 - Corrections to Prefiled Testimony NRC000168 and NRC000197 ML15337A3262015-10-29029 October 2015 Official Exhibit - ENT000722-00-BD01 - Supplemental Testimony of Entergy Witnesses Nelson Azevedo, Timothy Griesbach & Randy Lott ML15337A3292015-10-29029 October 2015 Official Exhibit - ENTR16001-00-BD01 - Entergy Revised Exhibit List ML15337A3242015-09-23023 September 2015 Official Exhibit - NYS000576-00-BD01 - Pre-Filed Supplemental Testimony of Richard T. Lahey Re Contentions NYS-25, NYS-26B/RK-TC-1B & NYS-38/RK-TC-5 ML15337A3072015-09-0909 September 2015 Official Exhibit - NYS000573-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2962015-09-0909 September 2015 Official Exhibit - NYS000570-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-26B/RK-TC-1B (Public, Redacted) (September 9, 2015) ML15337A2832015-09-0909 September 2015 Official Exhibit - NYS000563-00-BD01 - Pressurized Water Reactor (PWR) Systems, USNRC Technical Training Center, Reactor Concepts Manual, Pages 4-1 to 4-28 ML15337A2952015-09-0909 September 2015 Official Exhibit - NYS000569-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-26B/RK-TC-1B (Public, Redacted) (September 9, 2015) ML15337A2942015-09-0909 September 2015 Official Exhibit - NYS000568-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York in Support of Contention NYS-25 (Public, Redacted) (September 9, 2015) ML15337A2932015-09-0909 September 2015 Official Exhibit - NYS000567-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-25 (Public, Redacted) (September 9, 2015) ML15337A3042015-09-0909 September 2015 Official Exhibit - NYS000571-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of David J. Duquette in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2972015-09-0909 September 2015 Official Exhibit - RIV000164-00-BD01 - NUREG-1740, ACRS, Voltage-Based Alternative Repair Criteria: a Report to the Advisory Committee on Reactor Safeguards by the Ad Hoc Subcommittee on a Differing Professional Opinion (2001) ML15337A3062015-09-0909 September 2015 Official Exhibit - NYS000572-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2822015-09-0909 September 2015 Official Exhibit - NYS000566-00-BD01 - Figure 1 for Supplemental Reply Testimony of Dr. Richard T. Lahey ML15337A3142015-09-0404 September 2015 Official Exhibit - ENTR00615-PUB-00-BD01 - Entergy'S Statement of Position Re Contention NYS-25 (Embrittlement) - Redacted ML15334A2842015-08-10010 August 2015 Official Exhibit - ENT000687-00-BD01 - NRC, Safety Evaluation Report, Topical Report on ASME Section III Piping and Component Fatigue Analysis Utilizing the Westems Computer Code (WCAP-17577, Revision 2) (Undated) ML15335A2932015-08-10010 August 2015 Official Exhibit - NRCR00104-00-BD01 - on Yee Statement of Professional Qualifications (Revised) ML15337A2642015-08-10010 August 2015 Official Exhibit - NRC000196-PUB-00-BD01 - NRC Staff'S Initial Statement of Position on Contention NYS-25 (Reactor Vessel Internals) ML15337A3192015-08-10010 August 2015 Official Exhibit - ENT000698-PUB-00-BD01 - Entergy'S Revised Statement of Position Regarding Contention NYS-38/RK-TC-5(Safety Commitments) (Aug. 10, 2015)Redacted ML15337A3202015-08-10010 August 2015 Official Exhibit - ENT000699-PUB-00-BD01 - Redacted Revised Testimony of Entergy Witnesses Nelson Azevedo, Robert Dolansky, Alan Cox, Jack Strosnider, Timothy Griesbach, Barry Gordon, Randy Lott, and Mark Gray Regarding Contention NYS-38/RK ML15337A3172015-08-10010 August 2015 Official Exhibit - ENT000678-PUB-00-BD01 - NL-07-140, Letter from F. Dacimo, Entergy, to NRC Document Control Desk, ?Reply to Request for Additional Information Regarding License Renewal Application? (Nov. 28, 2007)Redacted ML15337A2652015-08-10010 August 2015 Official Exhibit - NRC000197-PUB-00-BD01 - NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, and Gary Stevens on NYS-25 and NYS-38/RK-TC-5 ML15337A2412015-08-10010 August 2015 Official Exhibit - NRCR00147-00-BD01 - NRC Staff'S Revised Statement of Position on State of New York and Riverkeeper'S Joint Contention NYS-38/RK-TC5 (Revised) ML15335A2902015-08-10010 August 2015 Official Exhibit - NRC000222-00-BD01 - IP3 FSAR Rev. 04 Chapter 3 (2011) (Excerpt) ML15334A2632015-08-10010 August 2015 Official Exhibit - ENT000648-00-BD01 - M. Mitchell, Chief, Vessels and Internals Integrity Branch, Response to Non-Concurrence Regarding Safety Evaluation for Topical Report MRP-227 Pressurized Water Reactor Internals Inspection and Evaluat ML15337A2622015-08-10010 August 2015 Official Exhibit - NRC000228-00-BD01 - Indian Point Unit 2 Technical Specifications 3.1.4 ML15337A2452015-08-10010 August 2015 Official Exhibit - NRC000227-00-BD01 - Gary Stevens Statement of Professional Qualifications ML15337A2632015-08-10010 August 2015 Official Exhibit - NRC000229-00-BD01 - Indian Point, Unit 3 Technical Specifications 3.1.4 ML15335A2192015-08-10010 August 2015 Official Exhibit - ENTR00031-00-BD01 - Curriculum Vitae of Alan B. Cox ML15335A2112015-08-10010 August 2015 Official Exhibit - ENTR20186-00-BD01 - Curriculum Vitae of Mark A. Gray ML15337A3162015-08-10010 August 2015 Official Exhibit - ENT000616-PUB-00-BD01 - Testimony of Entergy Witnesses Nelson F. Azevedo, Robert J. Dolansky, Alan B. Cox, Jack R. Strosnider, Timothy J. Griesbach, Randy G. Lott, and Mark A. Gray Regarding Contention NYS-25 (Embrittleme ML15337A2782015-08-10010 August 2015 Official Exhibit - NRC000168-PUB-00-BD01 - NRC Staff Testimony of Dr. Allen Hiser, Dr. Ching Ng, Mr. Gary Stevens, P.E., and Mr. on Yee, Concerning Contentions NYS-26B/RK-TC-1B and NYS-38/RK-TC-5 ML15337A2712015-08-10010 August 2015 Official Exhibit - NRC000223-00-BD01 - IP3 FSAR Rev. 04 Chapter 14 (2011) ML15337A2592015-08-10010 August 2015 Official Exhibit - NRC000224-00-BD01 - IP3 FSAR Rev. 04 Chapter 16 ML15337A2442015-08-10010 August 2015 Official Exhibit - NRCR00161-00-BD01 - NRC Staff Testimony of Dr. Allen L. Hiser and Mr. Kenneth J. Karwoski Concerning Portions of State of New York and Riverkeeper, Inc. Joint Contention NYS-38/RK-TC5 (Revised) ML15334A2822015-08-10010 August 2015 Official Exhibit - ENT000680-00-BD01 - Curriculum Vitae of Barry M. Gordon ML15335A2912015-08-10010 August 2015 Official Exhibit - NRCR00118-00-BD01 - Indian Point Unit 3 Technical Specifications (Excerpt) (Revised) ML15334A2282015-08-10010 August 2015 Official Exhibit - ENT000634-00-BD01 - Entergy, IP2, FSAR Update, Revision 25 (2014) (Excerpts) ML15335A2822015-08-10010 August 2015 Official Exhibit - NRC000220-00-BD01 - Pressurized Water Reactor Owners Group (PWROG) Presentation Slides, Industry and NRC Coordination Meeting Materials Programs Technical Exchange: Clevis Insert Bolt Update, (June 2014) ML15337A2692015-08-10010 August 2015 Official Exhibit - NRC000169-00-BD01 - NRC000169 - Indian Point, Unit 2 Technical Specifications (Excerpt) ML15337A2602015-08-10010 August 2015 Official Exhibit - NRC000226-00-BD01 - Jeffrey C. Poehler Statement of Professional Qualifications ML15335A2732015-08-10010 August 2015 Official Exhibit - NRC000183-00-BD01 - NRC Inspection Manual, Inspection Procedure 71013, Site Inspection for Plants with a Timely Renewal Application (Sept. 25, 2013) ML15335A2202015-08-10010 August 2015 Official Exhibit - ENTR00184-00-BD01 - Curriculum Vitae of Jack R. Strosnider ML15335A3012015-08-10010 August 2015 Official Exhibit - NRC000206-00-BD01 - Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 25, Chapter 14 - Safety Analysis (2014) 2015-09-09
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United States Nuclear Regulatory Commission Official Hearing Exhibit ENT000299 Entergy Nuclear Operations, Inc. Submitted: March 29, 2012 In the Matter of:
(Indian Point Nuclear Generating Units 2 and 3)
ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #: ENT000299-00-BD01 Identified: 10/15/2012 Admitted: 10/15/2012 Withdrawn:
Rejected: Stricken:
Other:
July 28, 2011 Michael B. Kaplowitz Westchester County Board of Legislators, District #4 800 Michaelian Office Building White Plains, NY 10601
Dear Mr. Kaplowitz:
I am responding to your letter dated June 2, 2011, to the U.S. Nuclear Regulatory Commissions (NRCs) Chairman Gregory B. Jaczko requesting that emergency preparedness requirements for the Indian Point Energy Center be extended to a 50 mile radius around the facility. Your request, co-signed by seven other Westchester County legislators, was made in response to the recent events in Japan, which suggested that the emergency planning requirements around the Indian Point Energy Center merited enhancement.
As you know, state and local officials have detailed plans to protect public health and safety in the event of a radiological release within a 10-mile radius emergency planning zone (EPZ). A 50-mile radius ingestion pathway for emergency planning is also established to protect individuals from radiological material that could be ingested and concentrated in the food chain.
The 10-mile EPZ was established in the late 1970s based on research showing the most significant impacts of an accident would be expected in the immediate vicinity of a plant and therefore any initial protective actions, such as evacuations or sheltering in place, should be focused there. Put another way, the projected radiation levels would not be expected to exceed Environmental Protection Agency (EPA) protective action dose guidelines (i.e., 1 rem to the body or 5 rem to the thyroid) beyond 10 miles under postulated accident scenarios. Reviews of emergency preparedness in response to terrorist actions conducted following the events of September 11, 2001, validated the adequacy of this planning area. It should be noted that the size of the established EPZs are not limits, but rather provide for an emergency planning framework that would allow expansion or contraction of response efforts based on actual and projected radiological conditions.
During a domestic radiological event, the NRC, amongst other emergency management organizations, would be performing dose calculations using radiation dose projection models that analyze release paths from power reactors as well as take into account meteorological conditions to project radiation doses. While the NRCs role is not to make a protective action recommendation to the applicable State or county governments, we independently assess dose projections and would confer with appropriate State and county governments on our assessment results.
M. Kaplowitz 2 The 50-mile evacuation recommendation that the NRC made to the U.S. Ambassador in Japan was based on our assessment of the conditions as we understood them at the time.
Specifically, there were preliminary indications of reactor fuel damage at three of these reactors and severely degraded conditions in one or more spent fuel pools at the six-unit facility. Since communications with knowledgeable Japanese officials were very limited and there was a large degree of uncertainty about plant conditions at the time, it was difficult to accurately assess the potential radiological hazard. The U.S. emergency preparedness framework provides for the expansion of emergency planning zones as conditions require. Acting in accordance with this framework, and with the best information available at the time, the NRC determined that the recommendation made to the US Ambassador in Japan was a prudent, conservative course of action. It was not based on the specific radiological conditions that existed at that time, but rather on a conservative assessment of radiological conditions that could possibly exist given the limited information available.
In the event of a radiological emergency at a nuclear power plant in the United States, we would have substantially more information available to us regarding the condition of the reactors, their containment structures, and the spent fuel pools. This is due, in part, to the active presence of NRC resident inspectors at the sites and the well-established communication protocols amongst the state and local decision makers, plant personnel and NRC emergency responders that are evaluated during biennial radiological emergency exercises. We would clearly be able to make more precise and well-founded recommendations regarding the appropriate protective actions needed to protect individuals in the vicinity of the facility.
The events at the Fukushima Dai-ichi site were unique in that the facility experienced one of the strongest earthquakes in recorded history, was struck by a large tsunami, and lost all onsite and offsite electricity necessary to power its nuclear safety equipment for several weeks. All U.S.
nuclear power plants are built to withstand external environmental hazards, including earthquakes, tsunamis, and flooding. Even those plants that are located outside of areas with extensive seismic activity are designed for safety in the event of such a natural disaster. The NRC requires that safety-significant structures and systems be designed to take into account the most severe natural phenomena historically reported for the site and surrounding area -
even very rare and extreme earthquakes, tsunamis, and flooding. Thus, the NRC is confident that the robust design of these plants makes it highly unlikely that a similar event could occur in the United States.
Going forward, the NRC will be evaluating the lessons learned at Fukushima Dai-ichi as they apply to the safety of existing power reactors as well as the adequacy of emergency planning guidance and policy in the United States. Recently, there were several recommendations regarding enhancing emergency preparedness published in the NRCs Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. At this time, however, the agency
M. Kaplowitz 3 considers our existing emergency preparedness framework and regulations to provide reasonable assurance of adequate protection of public health and safety in the event of a radiological emergency at all U.S. power reactor facilities, including Indian Point.
Sincerely,
/RA/
William M. Dean Regional Administrator
M. Kaplowitz 3 considers our existing emergency preparedness framework and regulations to provide reasonable assurance of adequate protection of public health and safety in the event of a radiological emergency at all U.S. power reactor facilities, including Indian Point.
Sincerely,
/RA/
William M. Dean Regional Administrator Distribution: G20110488/LTR-11-0371/EDATS: SECY-2011-0386 PUBLIC S. Bush-Goddard, OEDO SECY W. Dean, RI OCA D. Lew, RI OPA R. Lorson, RI R. Borchardt, OEDO R. Barkley, RI M. Virgilio, DEDR RIDSEDOMAILCENTER RESOURCE M. Weber, DEDMRT RIDSSECYMAILCENTER RESOURCE D. Ash, DEDCM RIDSOGCMAILCENTER RESOURCE N. Mamish, AO RIDSOCAMAILCENTER RESOURCE S. Burns, OGC RIDSOCFOMAILCENTER RESOURCE J. Wiggins, NSIR RIDSNRROD RESOURCE E. Leeds, NRR RIDSRGN1MAILCENTER RESOURCE SUNSI Review Complete: RSB (Reviewer=s Initials)
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