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Issue date | Title | Topic | |
---|---|---|---|
IR 05000003/2007010 | 13 May 2008 | Official 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, 2008 | Boric Acid Offsite Dose Calculation Manual Condition Adverse to Quality Annual Radiological Effluent Release Report Through-Wall Leak Unidentified leak |
IR 05000003/2009008 | 19 October 2009 | Official Exhibit - ENT000343-00-BD01 - Indian Point Nuclear Generating Units 1, 2 & 3 - NRC Inspection Reports Nos. 05000003/2009008; 05000247/2009008 and 05000286/2009008 | |
IR 05000247/2009002 | 14 May 2009 | Official 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 05000247/2010001 | 3 March 2010 | Official Exhibit - ENT000344-00-BD01 - Annual Assessment Letter - Indian Point Nuclear Generating Units 2 and 3 (Reports 05000247/2010001 & 05000286/2010001) | Dissimilar Metal Weld |
IR 05000247/2012008 | 19 April 2012 | Official 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 05000247/2013009 | 5 July 2013 | Official 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 05000247/2013010 | 19 September 2013 | Official 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 05000247/2014001 | 4 March 2015 | Official 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 05000271/2011011 | 22 December 2011 | Official 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 05000271/2012008 | 20 April 2012 | Official 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 05000286/2011004 | 7 November 2011 | Official 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 05000327/2010004 | 12 December 2011 | Official 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 Sta | 3 March 2004 | 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 Station)(Mar. 3, 2004) (NRC in 2004 | Boric 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 2005 | 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) | |
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 2009 | Official 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 2011 | 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) | 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 2011 | 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) | 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 2011 | 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) | 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 2013 | 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) | |
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 2013 | 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) | |
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 2013 | OFFICIAL 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 2013 | Official 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 Application | 24 February 2011 | 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 Application | Aging Management |
ML080070040 | 4 January 2008 | Indian Point - Exhibit 1 to NRC Staff'S Motion to Strike the Superceding Request for Hearing and Petition to Intervene. | |
ML080070044 | 4 January 2008 | Indian Point - Exhibit 2 to NRC Staff'S Motion to Strike the Superceding Request for Hearing and Petition to Intervene. | |
ML080920555 | 28 March 2008 | Mary Lampert'S Email Re Question for Number of Copies Per Party by Email to the Board and All Parties | |
ML092870154 | 13 October 2009 | Exhibit 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 | |
ML092870206 | 13 October 2009 | Exhibit 2 - Affidavit of Robert L. Palla Concerning the State of New York'S Motion for Partial Summary Disposition of NYS Contention 16/16A | Probabilistic Risk Assessment Large early release frequency |
ML092870215 | 12 October 2009 | Exhibit 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 16/16A | High winds Probabilistic Risk Assessment License Renewal Affidavit |
ML092870265 | 13 October 2009 | Exhibit 4 - NRC Staff'S Response to the State of New York'S Statement of Material Facts Not in Dispute | Affidavit |
ML092870274 | 13 October 2009 | Exhibit a - Resume of Stephen F. Lavie | |
ML092870289 | 13 October 2009 | Exhibit B - Statement of Professional Qualifications of Robert L. Palla | Probabilistic Risk Assessment B.5.b Significance Determination Process Large early release frequency Severe Accident Management Guideline License Renewal Affidavit |
ML092870335 | 13 October 2009 | 2009/10/13-Exhibit C - NUREG-1437, Volume 1 - Generic Environmental Impact Statement for License Renewal of Nuclear Plants | License Renewal Hardened vent Backfit |
ML092870361 | 13 October 2009 | 2009/10/13-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 Comment | Probabilistic Risk Assessment |
ML092870433 | 30 November 2005 | Exhibit E - Nuclear Energy Institute-05-01 Rev. a - Nuclear Energy Institute - Severe Accident Mitigation Alternatives (SAMA) Analysis - Guidance Document | Safe Shutdown High winds Large early release frequency Earthquake Fire Protection Program |
ML092870444 | 30 November 2002 | Exhibit 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 Basis | Probabilistic Risk Assessment |
ML092870586 | 13 October 2009 | Exhibit G - Fact Sheet - Probabilistic Risk Assessment | Probabilistic Risk Assessment Significance Determination Process Earthquake |
ML092870592 | 13 October 2009 | Exhibit 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 Applications | Probabilistic Risk Assessment |
ML092870631 | 13 October 2009 | Exhibit J - NUREG/BR-0184 - Regulatory Analysis Technical Evaluation Handbook - Final Report | Probabilistic Risk Assessment Chernobyl Fuel cladding Scaffolding |
ML092870640 | 13 October 2009 | Exhibit K - NUREG/CR-6613, Vol. 1, SAND97-0594 - Code Manual for MACCS2 - User'S Guide | |
ML092870644 | 13 October 2009 | Exhibit L - NUREG/CR-6853 - Comparison of Average Transport and Dispersion Among a Gaussian, a Two-Dimensional, and a Three-Dimensional Model | |
ML092870672 | 13 October 2009 | Exhibit M - Statement of Professional Qualifications of Joseph A. Jones, PE | |
ML092870677 | 13 October 2009 | Exhibit N - Statement of Professional Qualifications of Nathan E. Bixler | Probabilistic Risk Assessment Finite Element Analysis |
ML092870678 | 9 January 2008 | Exhibit O - Aermod Implementation Guide | |
ML092870679 | 13 October 2009 | Exhibit P - EPA Aermod: Latest Features and Evaluation Results | |
ML092870685 | 26 October 2004 | Exhibit R - Aermod: a Dispersion Model for Industrial Source Applications. Part II: Model Performance Against 17 Field Study Databases | |
ML110600900 | 3 January 2011 | Official 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 | |
ML12094A068 | 29 March 2012 | Entergy Pre-Filed Hearing Exhibit ENT00331K, Appendix C - Geophysics Borehole Part 1 | |
ML12334A342 | 28 October 2011 | Official 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 | |
ML12334A474 | 11 August 2011 | Official 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 . |