DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 6, Engineered Safety Features (Redacted)
L-13-176, Generic Safety Issue 191 Resolution Plan
0CAN090901, Arkansas, Units 1 and 2, Generic Letter 2004-02 Final Supplemental Response to Request for Additional Information
AEP-NRC-2013-45, Path Forward for Resolution of GSI-191
AEP-NRC-2011-31, Disposition of Temp-Mat Fibrous Insulation in Units 1 and 2 Containments with Respect to Generic Letter 2004-02 Concerns
CNL-15-009, Resolution of Generic Safety Issue 191
CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
CP-201300670, Closure Options for Generic Safety Issue 191 (GSI-191), Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance
CP-200700024, Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses
CP-200801606, Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a
CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 45
0CAN122001, Final Response to NRC Generic Letter 2004-02
CNL-14-114, Resolution of Generic Safety Issue (GSI)-191
3F0209-02, Response to Request for Additional Information, Regarding Response to Generic Letter 2004-02
ET 08-0053, Corporation Response to Request for Additional Information Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
HNP-13-053, Submittal of Path Forward for Resolution of Generic Safety Issue (GSI) - 191
ET 13-0017, Operating Corporation Proposed Path to Closure of Generic Safety Issue - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance
HNP-08-015, Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors
HNP-09-011, Response to Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
HNP-08-037, Second Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
L-08-036, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
L-13-224, Notification of Closure of a Commitment Related to the Generic Safety Issue 191 Resolution Plan for the (DBNPS)
L-20-162, Supplemental Response to NRC Generic Letter 2004-02
L-13-157, Generic Safety Issue 191 Resolution Plan
L-2009-085, Response to NRC Request for Additional Information Supplemental Information Provided Previously on NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents At.
L-2009-084, Response to Nrc'S Request for Additional Information
L-2009-062, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
L-2013-163, Path Forward for Resolution of GSI-191
L-2008-160, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
L-2009-179, Updated Supplemental Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
L-2007-155, Request for Extension of Completion Date of the Generic Letter 2004-02 Actions
L-2008-033, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
L-2017-210, Updated Final Response to NRC Generic Letter 2004-02
L-2009-063, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
L-2008-030, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
L-21-101, Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02
L-2008-138, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
DCL-08-059, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (Revision 1)
L-PI-09-025, Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch 14x14 Vantage+ Fuel
L-10-111, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pwrs.
LIC-08-0021, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
L-PI-15-019, Closure for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
L-PI-07-093, Request for Extension of Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
L-PI-08-021, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
L-2008-137, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
LIC-13-0058, Proposed Resolution Path for Closure of Generic Letter (GL) 2004-02 and Generic Safety Issue (GSI) 191, Pressurized Water Reactor Sump Performance
LR-N08-0043, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
L-08-321, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
LR-N12-0124, Salem Generating Station, Units 1 and 2 - Attachment 1 to LR-N12-0124, Generic Letter 2004-02, Updated Supplemental Response for Salem Regarding Generic Letter 2004-02
LIC-08-0107, Notice of Completion of Corrective Actions Taken in Response to Generic Letter 2004-02 and Response to Request for Additional Information
NL-08-2173, Supplemental Response to NRC Generic Letter 2004-02
RC-09-0134, Response to Request for Additional Information for Generic Letter 2004-02
NL-08-0818, Generic Letter 2004-02 Response Extension Request
W3F1-2013-0027, Closure Option for Generic Safety Issue - 191
W3F1-2008-0069, Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
ULNRC-05989, Path Forward for Resolution of GSI-191
RC-09-0060, Response to Request for Additional Information for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
NRC 2017-0045, Updated Final Response to NRC Generic Letter 2004-02
NL-08-1195, Generic Letter 2004-02 Response Extension Request
SBK-L-18010, Updated Final Response to NRC Generic Letter 2004-02
RS-13-134, Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02
NRC 2008-0013, Supplemental Response to Generic Letter 2004-02, Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
PNP 2013-041, Supplemental Information to Generic Safety Issue-191 Closure Option
NL-08-1155, Supplemental Response to NRC Generic Letter 2004-02
NOC-AE-13002986, Enclosure 4-3 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 3 Engineering Casa Grande Analysis, Page 161 of 260 Through End
NL-07-2245, Generic Letter 2004-02 Response Extension Request - Chemical Effects
NL-13-012, Closure Option for Generic Safety Issue - 191
NL-07-1969, Generic Letter 2004-02 Response Extension Request
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 6.0 - Engineered Safety Features, Pages 6.3-1 - 6.9-2
SBK-L-13093, Path Forward for Resolution of GSI- 191
NL-16-109, Indian Point, Unit 2, Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 6, Engineered Safety Features
NOC-AE-13002954, Pilot Submittal and Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191
RNP-RA/13-0048, Path Forward for Resolution of GSI-191
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features
NOC-AE-13003043, Enclosure 5 - Response to NRC Supplemental Information Items
NL-08-1228, Supplemental Response to NRC Generic Letter 2004-02
W3F1-2010-0032, Response to Request for Additional Information Regarding Final Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ULNRC-05481, Response to Request for Additional Information Regarding Response for NRC Generic Letter 2004-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
NOC-AE-07002240, Supplement 3 to the Response to Generic Letter 2004-02
NL-08-0818, Vogtle, Units 1 and 2 - Generic Letter 2004-02 Response Extension Request
NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 6 - Engineered Safety Features
NL-08-0670, Supplemental Response to NRC Generic Letter 2004-02
NOC-AE-16003366, First Set of Responses to April 11, 2016 Requests for Additional Information Regarding STP Risk-Informed GSl-191 Licensing Application
NL-08-1583, Generic Letter 2004-02 Extension Request for Completion of Chemical Effects and Closeout of GL 2004-02
RNP-RA/08-0124, Response to Request for Additional Information NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
NL-08-0551, Final Supplemental Response to NRC Generic Letter 2004-02
SBK-L-08033, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
NOC-AE-08002372, Supplement 4 to the Response to Generic Letter 2004-02, (TAC Nos. MC4719 & MC4720)
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 6 Through Chapter 7
NL-13-0953, Proposed Path to Closure of Generic Safety Issue-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance
NL-07-1777, Supplemental Response to NRC Generic Letter 2004-02
NOC-AE-15003267, Comment (1) of Wayne Harrison and Michael P. Murray on Draft Regulatory Guide DG-1322 - Risk-Informed Approach for Addressing the Effects of Debris on Post-Accident Long-Term Core Cooling
NL-09-138, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
RS-16-081, Revision to Closeout Documentation for Resolution of Generic Letter 2004-02 (Generic Safety Issue (GSl)-191)
SBK-L-08136, Final Response and Notice of Completion for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
RNP-RA/08-0026, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ONS-2014-024, Closure Option 1 Response for Generic Safety Issue (GSI)-1 91, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance in Resolution of Final Issues Related to Generic Letter (GL) 2004-02, Potential Impact of Deb
NOC-AE-14003105, Third Set of Responses to April, 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Licensing Application
RS-15-283, Units 1 and 2 - Closeout Documentation for Resolution of Generic Letter 2004-002 (Generic Safety Issue (GSI)- 191)
NRC 2007-0085, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1)
NL-13-0954, Proposed Path to Closure of Generic Safety Issue-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance
RC-13-0006, Path Forward for Resolution of General Safety Issue (GSI)-191, Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance
3F0208-05, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
3F1207-02, Request for Extension of Completion Date for Corrective Actions and Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized.
SBK-L-21049, Revision to Updated Final Response to NRC Generic Letter 2004-02
LR-N13-0148, Generic Letter 2004-02 In-Vessel Downstream Effects Resolution
L-2013-168, Path Forward for Resolution of GSI- 191