Semantic search

Jump to navigation Jump to search
Condition
Printout selection
Options
Parameters [
limit:

The maximum number of results to return
offset:

The offset of the first result
link:

Show values as links
headers:

Display the headers/property names
mainlabel:

The label to give to the main page name
intro:

The text to display before the query results, if there are any
outro:

The text to display after the query results, if there are any
searchlabel:

Text for continuing the search
default:

The text to display if there are no query results
class:

An additional CSS class to set for the table
transpose:

Display table headers vertically and results horizontally
sep:

The separator between results
prefix:

Control display of namespace in printouts
Sort options
Delete
Add sorting condition
 Issue dateTitleTopic
IR 05000003/200701013 May 2008Official Exhibit - RIV000067-00-BD01 - Indian Point Nuclear Generating Units 1 & 2 - NRC Inspection Report Nos. 05000003/2007010 and 05000247/2007010, EA-08-088, May 13, 2008Boric Acid
Offsite Dose Calculation Manual
Condition Adverse to Quality
Annual Radiological Effluent Release Report
Through-Wall Leak
Unidentified leak
IR 05000003/200900819 October 2009Official Exhibit - ENT000343-00-BD01 - Indian Point Nuclear Generating Units 1, 2 & 3 - NRC Inspection Reports Nos. 05000003/2009008; 05000247/2009008 and 05000286/2009008
IR 05000247/200900214 May 2009Official Exhibit - ENT000427-00-BD01 - Letter from M. Gray, NRC, to J. Pollock, Entergy, Indian Point Nuclear Generating Unit 2, NRC Integrated Inspection Report 5000247/2009002 (May 15, 2009)High Radiation Area
Fire Barrier
Temporary Modification
Condition Adverse to Quality
Significance Determination Process
Operability Determination
Fire Protection Program
Fire Watch
Scaffolding
Substantial potential for overexposure
Incremental Core Damage Probability Deficit
Overexposure
IR 05000247/20100013 March 2010Official Exhibit - ENT000344-00-BD01 - Annual Assessment Letter - Indian Point Nuclear Generating Units 2 and 3 (Reports 05000247/2010001 & 05000286/2010001)Dissimilar Metal Weld
IR 05000247/201200819 April 2012Official Exhibit - ENT000549-00-BD01 - Letter from R. Conte, NRC, to J. Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 - NRC Inspection Report 05000247/2012008 (Apr. 19, 2012)Boric Acid
Aging Management
License Renewal
IR 05000247/20130095 July 2013Official Exhibit - NRC000181-00-BD01 - Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 NRC License Renewal Team Inspection Report 05000247/2013009 (July 5, 2013)Boric Acid
Non-Destructive Examination
Coatings
Nondestructive Examination
VT-2
Aging Management
License Renewal
Fire Protection Program
IR 05000247/201301019 September 2013Official Exhibit - NRC000182-00-BD01 - Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 - NRC License Renewal Team Inspection Report 05000247/2013010 (Sept. 19, 2013)Aging Management
License Renewal
IR 05000247/20140014 March 2015Official Exhibit - NRC000185-00-BD01 - Letter from Arthur Burritt, NRC, to Larry Coyle, Entergy, Annual Assessment Letter for Indian Point Nuclear Generating Units 2 and 3 (Report 05000247/2014001 and 05000286/2014001) (Mar. 4, 2015)License Renewal
IR 05000271/201101122 December 2011Official Exhibit - NYS000459-00-BD01 - IR 05000271-11-011; 10/17/2011 - 12/11/2011; Vermont Yankee Nuclear Power Station; Review of License Renewal Activities.License Renewal
IR 05000271/201200820 April 2012Official Exhibit - NYS000462-00-BD01 - IR 05000271-12-008; 1/9 - 13, 1/23 - 27, and 3/19 - 20/2012; Vermont Yankee Nuclear Power Station; Post Approval Site Inspection for License Renewal 1P71003.Safe Shutdown
Fire Barrier
Coatings
Aging Management
License Renewal
EVT-1
IR 05000286/20110047 November 2011Official Exhibit - RIV000085-00-BD01 - Indian Point Nuclear Generating Unit 3 - NRC Integrated Inspection Report 05000286-2011004 (November 7, 2011)Annual Radiological Environmental Operating Report
Annual Radiological Effluent Release Report
IR 05000327/201000412 December 2011Official Exhibit - NYS000029-00-BD01 - NRC Integrated Inspection Report 05000327/2010004, 05000328/2010004, Sequoyah Nuclear Plant (Oct. 29, 2010) (Sequoyah IR)Fire Barrier
Past operability
Temporary Modification
Significance Determination Process
Maintenance Rule Program
Fuel cladding
Biofouling
Information Notice 2004-05, Official Exhibit - NYS000190-00-BD01 - NRC Information Notice 2004-05, NRC Office of Nuclear Reactor Regulation, Spent Fuel Pool Leakage to Onsite Groundwater, (Salem, New Jersey, Nuclear Power Generating Sta3 March 2004Official Exhibit - NYS000190-00-BD01 - NRC Information Notice 2004-05, NRC Office of Nuclear Reactor Regulation, Spent Fuel Pool Leakage to Onsite Groundwater, (Salem, New Jersey, Nuclear Power Generating Station)(Mar. 3, 2004) (NRC in 2004Boric Acid
Through-Wall Leak
Information Notice 2005-09, Official Exhibit - ENT000527-00-BD01 - NRC Information Notice 2005-09, Indications in Thermally Treated Alloy 600 Steam Generator Tubes and Tube-to Tubesheet Welds (Apr. 7, 2005)7 April 2005Official Exhibit - ENT000527-00-BD01 - NRC Information Notice 2005-09, Indications in Thermally Treated Alloy 600 Steam Generator Tubes and Tube-to Tubesheet Welds (Apr. 7, 2005)
Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)7 July 2009Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)
Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)29 June 2011OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)Shutdown Margin
Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)29 June 2011Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)Shutdown Margin
Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)29 June 2011Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)Shutdown Margin
Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)3 July 2013OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)
Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)3 July 2013Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)
Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)3 October 2013OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)Boric Acid
Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)3 October 2013Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)Boric Acid
LR-N11-0057, Official Exhibit - ENT000197-00-BD01 - Salem Nuclear Generating Station, Units 1 & 2 - Close-out of the NRC Audit Associated with Use of Westems Related to the Plant License Renewal Application24 February 2011Official Exhibit - ENT000197-00-BD01 - Salem Nuclear Generating Station, Units 1 & 2 - Close-out of the NRC Audit Associated with Use of Westems Related to the Plant License Renewal ApplicationAging Management
ML0800700404 January 2008Indian Point - Exhibit 1 to NRC Staff'S Motion to Strike the Superceding Request for Hearing and Petition to Intervene.
ML0800700444 January 2008Indian Point - Exhibit 2 to NRC Staff'S Motion to Strike the Superceding Request for Hearing and Petition to Intervene.
ML08092055528 March 2008Mary Lampert'S Email Re Question for Number of Copies Per Party by Email to the Board and All Parties
ML09287015413 October 2009Exhibit 1 - Affidavit of Stephen F. Lavie in Support of Nrc'S Response in Opposition to State of New York'S Motion for Partial Summary Disposition of NYS Contention 16/16A
ML09287020613 October 2009Exhibit 2 - Affidavit of Robert L. Palla Concerning the State of New York'S Motion for Partial Summary Disposition of NYS Contention 16/16AProbabilistic Risk Assessment
Large early release frequency
ML09287021512 October 2009Exhibit 3 - Affidavit of Joseph A. Jones and Dr. Nathan E. Bixler Concerning the State of New York'S Motion for Partial Summary Disposition of NYS Contention 16/16AHigh winds
Probabilistic Risk Assessment
License Renewal
Affidavit
ML09287026513 October 2009Exhibit 4 - NRC Staff'S Response to the State of New York'S Statement of Material Facts Not in DisputeAffidavit
ML09287027413 October 2009Exhibit a - Resume of Stephen F. Lavie
ML09287028913 October 2009Exhibit B - Statement of Professional Qualifications of Robert L. PallaProbabilistic Risk Assessment
B.5.b
Significance Determination Process
Large early release frequency
Severe Accident Management Guideline
License Renewal
Affidavit
ML09287033513 October 20092009/10/13-Exhibit C - NUREG-1437, Volume 1 - Generic Environmental Impact Statement for License Renewal of Nuclear PlantsLicense Renewal
Hardened vent
Backfit
ML09287036113 October 20092009/10/13-Exhibit D - NUREG-1555, Supplement 1, Revision 1 - Standard Review Plans for Environmental Reviews of Nuclear Power Plants, Supplement 1: Operating License Renewal, Draft Report for CommentProbabilistic Risk Assessment
ML09287043330 November 2005Exhibit E - Nuclear Energy Institute-05-01 Rev. a - Nuclear Energy Institute - Severe Accident Mitigation Alternatives (SAMA) Analysis - Guidance DocumentSafe Shutdown
High winds
Large early release frequency
Earthquake
Fire Protection Program
ML09287044430 November 2002Exhibit F - Regulatory Guide 1.174, Rev. 1 - an Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing BasisProbabilistic Risk Assessment
ML09287058613 October 2009Exhibit G - Fact Sheet - Probabilistic Risk AssessmentProbabilistic Risk Assessment
Significance Determination Process
Earthquake
ML09287059213 October 2009Exhibit H - Asme/Ans RA-Sa-2009 - American Society of Mechanical Engineers, Addenda to Asme/Ans RA-S-2008, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant ApplicationsProbabilistic Risk Assessment
ML09287063113 October 2009Exhibit J - NUREG/BR-0184 - Regulatory Analysis Technical Evaluation Handbook - Final ReportProbabilistic Risk Assessment
Chernobyl
Fuel cladding
Scaffolding
ML09287064013 October 2009Exhibit K - NUREG/CR-6613, Vol. 1, SAND97-0594 - Code Manual for MACCS2 - User'S Guide
ML09287064413 October 2009Exhibit L - NUREG/CR-6853 - Comparison of Average Transport and Dispersion Among a Gaussian, a Two-Dimensional, and a Three-Dimensional Model
ML09287067213 October 2009Exhibit M - Statement of Professional Qualifications of Joseph A. Jones, PE
ML09287067713 October 2009Exhibit N - Statement of Professional Qualifications of Nathan E. BixlerProbabilistic Risk Assessment
Finite Element Analysis
ML0928706789 January 2008Exhibit O - Aermod Implementation Guide
ML09287067913 October 2009Exhibit P - EPA Aermod: Latest Features and Evaluation Results
ML09287068526 October 2004Exhibit R - Aermod: a Dispersion Model for Industrial Source Applications. Part II: Model Performance Against 17 Field Study Databases
ML1106009003 January 2011Official Exhibit - PWA000018-00-BD01 - NRC Staff'S Response in Opposition to State of New York'S Motion for Partial Summary Disposition of NYS Contention 16/16A
ML12094A06829 March 2012Entergy Pre-Filed Hearing Exhibit ENT00331K, Appendix C - Geophysics Borehole Part 1
ML12334A34228 October 2011Official Exhibit - NYS000036-00-BD01 - Preliminary Notification of Event or Unusual Occurrence (PNO-III-11-015A), Monticello Nuclear Generating Plant, Unplanned Shutdown Greater than 72 Hours Due to a Loss of the Auxiliary Power Transformer
ML12334A47411 August 2011Official Exhibit - NYS000042-00-BD01 - E-mail String; August 7, 2008 2:46 PM; Subject: Risks; from: C. Jackson; to: J.J. Curry; August 7, 2008 3:02 PM; Subject: FW: Risks; from: J.J. Curry; to: C. Caputo; August 11 .