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NUREG Series Publications

Document Number	Description
NUREG/CR-6917	Experimental Measurements of Pressure Drop Across Sump Screen Debris Beds in Support of Generic Safety Issue 191
NUREG/CR-6916	Hydraulic Transport of Coating Debris
NUREG/CR-6914	Integrated Chemical Effects Test Project Consolidated Data Report Test #1 Data Report Test #2 Data Report Test #3 Data Report Test #4 Data Report Test #5 Data Report
NUREG/CR-6915	Aluminum Chemistry in a Prototypical Post-Loss-of-Coolant-Accident, Pressurized-Water-Reactor Containment Environment
NUREG/CR-6913	Chemical Effects Head-Loss Research in Support of Generic Safety Issue 191 Appendices
NUREG/CR-6912	GSI-191 PWR Sump Screen Blockage Chemical Effects Tests: Thermodynamic Simulations
NUREG/CR-6902	Effects of Insulation Debris on Throttle-Valve Flow Performance, A Subtask of GSI-191
NUREG/CR-6885	Screen Penetration Test Report
NUREG/CR-6877	Characterization and Head-Loss Testing of Latent Debris from Pressurized-Water-Reactor Containment Buildings
NUREG/CR-6874	GSI-191: Experimental Studies of Loss-of-Coolant-Accident-Generated Debris Accumulation and Head Loss with Emphasis on the Effects of Calcium Silicate Insulation
NUREG/CR-6873	Corrosion Rate Measurements and Chemical Speciation of Corrosion Products Using Thermodynamic Modeling of Debris Components
NUREG/CR-6868	Small-Scale Experiments: Effects of Chemical Reactions on Debris-Bed Head Loss
NUREG/CR-6808	Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance, USNRC, February 2003
NUREG/CR-6773	Integrated Debris-Transport Tests in Water Using Simulated Containment Floor Geometries
NUREG/CR-6772	Separate-Effects Characterization of Debris Transport in Water
NUREG/CR-6771	GSI-191: The Impact of Debris Induced Loss of ECCS Recirculation on PWR Core Damage Frequency
NUREG/CR-6762, GSI-191	Technical Assessment: Parametric Evaluations for Pressurized Water Reactor Recirculation Sump Performance (Report LA-UR-01-4083, Rev. 1 by LANL), Volumes 1-4, USNRC, August 2002 Volume 1 Volume 1, Appendix A Volume 2 Volume 3 Volume 4
Instructions for obtaining NUREG/CR-6224 Correlation Software	Instructions for obtaining "NUREG/CR-6224 Correlation and Deaeration Software Package" from the NRC Public Document Room. The software package has been developed for NRC staff to perform confirmatory analysis in computing head loss and air bubble generation across debris-covered PWR sump screens. If licensees desire to use it for design purposes, the software package needs to be independently qualified and verified in accordance with NRC quality assurance requirements.
NUREG-1862	Development of a Pressure Drop Calculation Method for Debris-Covered Sump Screens in Support of Generic Safety Issue 191
NUREG-1861	Peer Review of GSI-191 Chemical Effects Research Program
NUREG-1650, Rev. 2	The United State of America 4th National Report for the Convention on Nuclear Safety

Test Reports

Date	Description
08/19/08	Technical Letter Report on Evaluation of Head Loss by Products of Aluminum Alloy Corrosion Memo Report
03/12/08	Technical Letter Report on WCAP-16530-NP, Evaluation of Post- Accident Chemical Effects in Containment Sump Fluids to Support GSI-191 Memo Report
02/25/08	Technical Letter Report on Evaluation of Long-Term Aluminum Solubility in Borated Water Following a LOCA Memo Report
12/21/07	WCAP-16530-NP, Evaluation of Post Accident Chemical Effects in Containment Sump Fluids to Support GSI-191 Memo Report
02/15/07	Technical Letter Report on Follow-on Studies in Chemical Effects Head-Loss research: Studies on WCAP Surrogates and Sodium Tetraborate Solutions, Argonne National Laboratory Memo Report
11/30/06	Letter Report on Supplemental Leaching Tests of Insulation and Concrete for GSI-191 Chemical Effects Program, Center for Nuclear Waste Regulatory Analysis Memo Report
09/13/06	Technical Letter report Survey on Leaching of Coatings Used in Nuclear Power Plants, Argonne National Laboratory Memo Report
01/20/06	Additional Results of Chemical Effects Tests in a Simulated PWR Sump Pool Environment Memo Report
09/16/05	Chemical Effects/Head Loss Testing Quick Look Report, Test 1 and 2 IN 05-26: Results of Chemical Effects Head Loss Tests in a Simulated PWR Sump Pool Environment
07/15/05	Integrated Chemical Effects Testing Results and Implications to Date Memo Program Background Test #1 Conditions and Observations Test #2 Conditions and Observations Test #3 Conditions and Observations Test #4 Conditions and Observations Implications of ICET Program Results
05/19/05	Archival Materials from the Integrated Chemical Effects Testing (ICET) Program Archival Material ICET Archival Material for Industry Testing Addendum on ICET for PWR ECCS Recirculation
04/11/05	Technical Report on Characterization and Head-Loss Testing of Latent Debris from PWR Containment Buildings Memo Report
04/11/05	Screen Penetration Test Report Memo Report
03/30/05	Test Plan: Characterization of Chemical and Corrosion Effects Potentially Occurring Inside a PWR Containment Following a LOCA

Trip Reports

Date	Description
06/24/08	Staff Observations From January 2008 Trip To the PCI/Alten Test Facility To Observe Head Loss Testing For Wolf Creek And Callaway Plants
06/15/08	Trip Report for In-Vessel Tests at Continuum Dynamics Incorporated
04/30/08	Staff Observations of Testing for Generic Safety Issue 191 During February 12 and February 13 Trip to the Alden Test Facility for PCI Strainer Tests.
11/08/07	Staff Observations Of Arkansas Nuclear One, Unit 2, Strainer Testing For Generic Safety Issue 191 During August 13–14, 2007, Trip To Fauske And Associates
03/08/07	Staff Observations of Testing for Generic Safety Issue 191, Trip to the ALION Hydraulics Laboratory
03/08/07	Trip Report Regarding Staff Observations from Trip to Fauske & Associates Incorporation of Additional Plant Inputs in the Chemical Effects Spreadsheet
12/14/06	Staff Observations of Diablo Canyon Power Plant Strainer Testing for Generic Safety Issue 191 During December 14-15, 2006, Trip to Continuum Dynamics, INC.
09/17/06	Trip Report Regarding Staff Observations of Sump Strainer Testing Performed by Control Components, Incorporated (CCI)
08/17/06	Trip Report Regarding Staff Observations of Testing for Generic Safety Issue 191 at Alion Hydraulics Laboratory
06/26/06	Foreign travel trip report regarding NRC staff observation of sump strainer head loss testing performed by Atomic Energy of Canada
05/12/06	Trip Report Regarding Staff Observations of Strainer Installation During May 12, 2006, Trip to Indian Point 2
04/28/06	Trip Report Regarding Staff Observations of Flume Testing at ALION Hydraulics Laboratory
04/27/06	Trip Report Regarding Staff Observations of Testing for Generic Safety Issue 191 to Fauske & Associates
03/08/06	Trip Report Regarding Staff Observations of Flume Testing of a Prototype Portion of the Proposed Replacement Suction Screen Design for the Comanche Peak Steam Electric Station
02/24/06	Trip Report on Staff Observations of Alion Hydraulics Laboratory Plant-Specific Testing
01/18/06	Trip Report Regarding Staff Observations of Scaled Flume Testing of the Point Beach Nuclear Plant Proposed Replacement Suction Strainer Design
08/29/05	Trip to Continuum Dynamics Inc., to Observe Testing of Fort Calhoun Station Strainers
07/28/05	Trip Report Regarding Staff Observations of Testing Performed on Diablo Canyon Plant-Specific Sump Strainer Design
03/17/05	Trip to Alden Research Laboratory Inc., to Observe Test Facilities and Testing of Performance Contracting, Inc.(PCI) Pressurized-Water Reactor (PWR) Suction Strainer
01/05/05	Trip Report Regarding Staff Observations of Testing for GE Nuclear Energy Active Suction Strainer

Audit Reports

Date	Description
12/03/07	Indian Point Nuclear Generating Unit Nos. 2 and 3 - Staff Audit of Corrective Actions to Address Generic Letter 2004-02 Letter Audit Report
10/01/07	Salem Nuclear Generating Station, Audit Report Analyses Required for the Response to Generic Letter 2004-02 Audit Report
07/16/07	North Anna Power Station; Audit Report Analyses Required for the Response to Generic Letter 2004-02 and GSI-191 Resolution Letter Audit Report
06/26/07	Waterford Unit 3; Audit Report Analyses Required for the Response to Generic Letter 2004-02 and GSI-191 Resolution Letter Audit Report
05/29/07	Oconee Nuclear Station; Audit Report Analyses Required for the Response to Generic Letter 2004-02 and GSI-191 Resolution Letter Audit Report
05/16/07	San Onofre Nuclear Generating Station Units 2 and 3; Audit Report Analyses Required for the Response to Generic Letter 2004-02 Letter Report Appendix IV
05/02/07	Prairie Island Nuclear Generating, Audit Report Analyses Required for the Response to Generic Letter 2004-02 Letter Report
04/24/07	Millstone Nuclear Power Station Unit 2; Audit Report Analyses Required for the Response to Generic Letter 2004-02 Letter Audit Report
02/07/07	Watts Bar Unit 1; Audit Report Analyses Required for the Response to Generic Letter 2004-02 and GSI-191 Resolution Letter Report
01/26/06	Fort Calhoun; Pilot Plant Audit Report Analyses Required for the Response to Generic Letter 2004-02 and GSI-191 Resolution Letter Audit Report Appendix II
06/29/05	Crystal River Unit 3; Pilot Plant Audit Report Analyses Required for the Response to Generic Letter 2004-02 and GSI-191 Resolution Cover Letter Crystal River Audit Report Crystal River Audit Report Appendices

GSI-191 Phone Call Interactions

Date	Description
03/31/08	Phone Call Summary with Alion on October 31, 2007, and November 29, 2007, to discuss sump strainer head loss test specification. NRC Staff Questions for October 31, 2007 - Phone Call with Alion NRC Staff Questions Reformatted Into Three Topical Areas Alion Responses to NRC Staff Questions Reformatted Into Three Topical Areas NRC Staff Questions Supplemented and Including Alion Testing Facility (VUEZ) Site Visit Comments NRC Staff Questions with Problem Statements
03/27/08	Phone Call Summary with Alion on October 31, 2007, and November 29, 2007, to discuss sump strainer head loss test specification.
03/13/08	Summary of Phone Call with Licensees Concerning Sump Strainer Head Loss Testing.
02/20/08	Summary of Phone Calls with Performance Contracting, Inc. (PCI)/AREVA/Alden to Discuss Head Loss Test Protocol, Held May to Sept. 2007.
02/01/08	Phone Call with PCI - Alion Regarding Sump Strainer Head Loss Testing.
10/30/07	Summary of Phone Call with Alion to Discuss Sump Strainer Head Loss Test Specification.

Miscellaneous

Date	Description
03/28/08	Revised Guidance for Licensee Responses to Generic Letter 2004-02 NRC Staff Review Guidance Regarding Generic Letter 2004-02 Closure in the Area of Strainer Head Loss and Vortexing Coatings Review Guidance NRC Staff Review Guidance GL 2004-02 Chemical Effects
02/28/08	GSI-191 Chemical Effects – Argonne National Laboratory Technical Letter Report Technical Letter Report on Evaluation of Chemical Effects; Studies on Precipitates Used in Strainer Head Loss Testing
09/27/07	Letter forwarding Draft Guidance for Review of Licensee responses to GL 2004-02 to NEI Guidance for Strainer Head Loss and Vortexing Guidance for Coatings Guidance for Chemical Effects
05/16/07	Temporary Instruction 2515/166 Revision 1 "Pressurized Water Reactor Containment Sump Blockage"
01/04/07	Alternative Approach for Responding to the Nuclear Regulatory Commission Request for Additional Information Letters Regarding Generic Letter 2004-02
12/05/06	Audit Plan for Verifying the Adequacy of Licensee Responses to Generic Letter 2004-02
11/16/06	Briefing on Resolution of GSI-191, Assessment of Debris Accumulation on PWR Sump Performance
03/24/06	WCAP-16530-NP, Evaluation of Post Accident Chemical Effects in Containment Sump Fluids to Support GSI-191 Technical Letter Report
10/13/05	Draft NRC Staff Review Guidance for Evaluation of Downstream Effects of Debris Ingress into the PWR RCS on Long Term Core Cooling following a Loca
08/25/05	Trip Report Regarding Staff Obsevations of Testing Performed on Diablo Canyon Plat-Specific Sump Strainer Design
06/30/05	Nuclear Regulatory Commission Staff Responses to Industry Questions on Generic Letter 2004-02 (Questions and Answers)
03/17/05	Trip to Alden Research Laboratory Inc., to Observe Test Facilities and Testing of Performance Contracting, Inc. (PCI) Pressurized-Water Reactor (PWR) Suction Strainer Trip Report PCI Test presentation
04/04	Shaffer, C.J., et. al., "GSI-191: Experimental Studies of Loss-of-Coolant-Accident-Generated Debris Accumulation and Head Loss with Emphasis on the Effects of Calcium Silicate Insulation".
04/04	"PWR Containment Sump Evaluation Methodology - Baseline Evaluation," by Nuclear Energy Institute
11/03	Johns, R.C., et. al., "Small Scale Experiments: Effects of Chemical Reactions on Debris-Bed Head Loss,"
02/03	"The Impact of Recovery From Debris-Induced Loss of ECCS Recirculation on PWR Core Damage Frequency," Technical Letter Report LA-UR-02-7562 (by LANL)
01/02	"GSI-191: Thermal Hydraulic Response of PWR Reactor Coolant System and Containments to Selected Accident Sequences," Technical Letter Report LA-UR-01-5561 (by LANL, rev. 1).
12/01	"GSI-191: Separate-Effects Characterization of Debris Transport in Water," Technical Letter Report LA-UR-01-6882 (by LANL)
11/01	"Development of Debris Generation Quantities in Support of the Parametric Evaluation," Technical Letter Report LA-UR-01-6640 by LANL)
10/01	"GSI-191: Development of Debris Transport Fractions in Support of the Parametric Evaluation," Technical Letter Report LA-UR-01-5965 (by LANL)
09/28/01	RES Proposed Recommendation for Resolution of GSI-191-“Assessment of Debris Accumulation on PWR Sump Performance Attachments to this Memorandum under ML012750414: Technical Assessment Summary for GSI-191, Assessment of Debris Accumulation on PWR Sump Performance. Rao, D., et. al., GSI-191: Parametric Evaluations for Pressurized Water Reactor Recirculation Sump Performance, LA-UR-01-4083, Los Alamos National Laboratory, Los Alamos, New Mexico, August 2001. Buslik, A., Risk Considerations and Benefits Associated with GSI-191, Assessment of Debris Accumulation on PWR Sump Performance,. U.S. NRC, August 8, 2001. Feld, S., Cost Analysis for GSI-191, .Assessment of Debris Accumulation on PWR Sump Performance,. U.S. NRC, August 14, 2001. Marion, A. (NEI), Letter to Mayfield, M. (NRC), Comments on NRC Contractor Draft Report, LA-UR-XXX, GSI-191: Parametric Evaluations for Pressurized Water Reactor Recirculation Sump Performance, August 31, 2001. RES responses to NEI comments. Apostolakis, G. (ACRS), Memo to Travers, W. (EDO), Generic Safety Issue-191 Assessment of Debris Accumulation on PWR Sump Pump Performance, September 14, 2001.
08/01	"GSI-191: Summary and Analysis of US Pressurized Water Reactor Industry Survey Responses and Responses to GL 97-04," Technical Letter Report LA-UR-01-1800 (by LANL)
04/18/01	"Jet Impact Test - Preliminary Results and Their Application," OPGN Engineering Report, File N-REP-34320-10000.
12/14/99	"Pressurized Water Reactor Debris Transport in Dry Ambient Containments - Phenomena Identification and Ranking Tables," LA-UR-99-3371
12/14/99	"Pressurized Water Reactor Debris Transport in Dry Ambient Containments - Phenomena Identification and Ranking Tables," LA-UR-99-5111
08/28/98	Safety Evaluation by the Office of Nuclear Reactor Regulation Related to NRC Bulletin 96-03, Boiling Water Reactor Owners Group Topical Report NEDO-32686-A, "Utility Resolution Guidance for ECCS Suction Strainer Blockage".