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Technical References
Technical reference concerning the pressurized-water reactor sump performance issue. (GSI-191)
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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
|
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
|
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
|
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
|
03/12/08 |
Technical Letter Report on WCAP-16530-NP, Evaluation of Post- Accident Chemical Effects in Containment Sump Fluids to Support GSI-191
|
02/25/08 |
Technical Letter Report on Evaluation of Long-Term Aluminum Solubility in Borated Water Following a LOCA
|
12/21/07 |
WCAP-16530-NP, Evaluation of Post Accident Chemical Effects in Containment Sump Fluids to Support GSI-191
|
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
|
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
|
09/13/06 |
Technical Letter report Survey on Leaching of Coatings Used in Nuclear Power Plants, Argonne National Laboratory
|
01/20/06 |
Additional Results of Chemical Effects Tests in a Simulated PWR Sump Pool Environment
|
09/16/05 |
Chemical Effects/Head Loss Testing Quick Look Report, Test 1 and 2
|
07/15/05 |
Integrated Chemical Effects Testing Results and Implications to Date
|
05/19/05 |
Archival Materials from the Integrated Chemical Effects Testing (ICET) Program
|
04/11/05 |
Technical Report on Characterization and Head-Loss Testing of Latent Debris from PWR Containment Buildings
|
04/11/05 |
Screen Penetration Test 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
|
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
|
10/01/07 |
Salem Nuclear Generating Station, Audit Report Analyses Required for the Response to Generic Letter 2004-02
|
07/16/07 |
North Anna Power Station; Audit Report Analyses Required for the Response to Generic Letter 2004-02 and GSI-191 Resolution
|
06/26/07 |
Waterford Unit 3; Audit Report Analyses Required for the Response to Generic Letter 2004-02 and GSI-191 Resolution
|
05/29/07 |
Oconee Nuclear Station; Audit Report Analyses Required for the Response to Generic Letter 2004-02 and GSI-191 Resolution
|
05/16/07 |
San Onofre Nuclear Generating Station Units 2 and 3; Audit Report Analyses Required for the Response to Generic Letter 2004-02
|
05/02/07 |
Prairie Island Nuclear Generating, Audit Report Analyses Required for the Response to Generic Letter 2004-02
|
04/24/07 |
Millstone Nuclear Power Station Unit 2; Audit Report Analyses Required for the Response to Generic Letter 2004-02
|
02/07/07 |
Watts Bar Unit 1; Audit Report Analyses Required for the Response to Generic Letter 2004-02 and GSI-191 Resolution
|
01/26/06 |
Fort Calhoun; Pilot Plant Audit Report Analyses Required for the Response to Generic Letter 2004-02 and GSI-191 Resolution
|
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
|
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.
|
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
|
02/28/08 |
GSI-191 Chemical Effects – Argonne National Laboratory Technical Letter Report
|
09/27/07 |
Letter forwarding Draft Guidance for Review of Licensee responses to GL 2004-02 to NEI
|
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
|
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
|
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". |
|