(Revision 2), Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants
Regulatory Guide 1.140# QUERY321b2e2e6e582d763ec6b4f50803eb58
Regulatory Guide 1.140# QUERY6e8e6098e14870e6e2c4dfebdb64e5a9
Regulatory Guide 1.140# QUERY3becbff31d94c9dea5ff625567c91afd

Regulatory Guide 1.140# QUERY63d5ea34e6aa3a2e0bea4e8bf23559a9
Regulatory Guide 1.140# ERR1dd423a8697e32d6813ecd1a7aae482c
NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code
Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (within 10 Miles) Emergency Operations Facilities and Technical Support Centers
Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers
B18763, License Basis Document Change Request (LBDCR) 2-18-02 Selective Implementation of the Alternative Source Term - Fuel Handling Accident Analyses
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 14, Initial Test Program
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 10.3 Through Section 15.1
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 11.0 - Radioactive Waste Management
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report. Appendix a
RS-14-338, Byron, Units 1 and 2, and Braidwood, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26, Chapter 14 - Initial Test Program
NL-16-109, Indian Point 2 Technical Requirements Manual
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 14.0 - Initial Test Program
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 9 - Auxiliary Systems
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 9 - Auxiliary Systems
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 14.0 - Initial Test Program
NL-07-0067, License Amendment Request to Technical Specification 3.9.3, Containment Penetrations, Personnel Air Locks Doors Open During Fuel Movement
RAIO-0917-56211, LLC Response to NRC Request for Additional Information No. 109 (Erai No. 8949) on the NuScale Design Certification Application
NRC Generic Letter 90-04, Request for Information on the Status of Licensee Implementation of GSIs Resolved with Imposition of Requirements or CAs
RAIO-0318-59209, LLC Response to NRC Request for Additional Information No. 359 (Erai No. 9321) on the NuScale Design Certification Application
RAIO-0318-59292, LLC - Response to NRC Request for Additional Information No. 354 (Erai No. 9359) on the NuScale Design Certification Application
ND-19-0666, Report of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report
NL-04-162, Reply to RAI Regarding Alternate Source Term License Amendment and Transmittal of Supplemental Information
CPSES-200402431, License Amendment Request 04-011, Revision to Technical Specification (TS 3.3.3) Post Accident Monitoring Instrumentation and 3.6.8 Hydrogen Recombiners
NL-04-1746, Response to Request for Additional Information Related to Request to Revise Technical Specifications - Control Room Habitability
NRC-94-4202, Forwards Responses to NRC RAI Re AP600
IA-94-208, Partially Released Ltr Re Conversations W/Staff & Ltrs Identifying Allegations Related to Operations & TS Practices at Plant.Review Completed & Findings Documented in Encls
NRC-89-3438, Forwards Nonproprietary Draft Responses to Open Issues 42-81 of Draft SER Re RESAR-SP/90 Preliminary Design Application
RA-98-021, Submits Addl Info & Clarification in Response to Questions Raised in Re Decommissioning Plan Submitted on 970731.Attachment 1 Provides Answers to Specific Questions in & Attachment 2 Provides Environ Rept
NSD-NRC-98-5521, Provides W Responses to FSER Open Items on AP600.Summary of Encl Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status Column of Oits, Included in Table 1
NSD-NRC-97-5484, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses Is Provided in Table 1
NSD-NRC-97-5485, Forwards Responses to FSER Open Items on AP600.Summary of Encl Responses Provided in Table 1
NSD-NRC-97-5023, Constitutes Formal Consolidated Responses & Resolutions of Items Discussed in 960411 Telcon Re AP600 Design Certification
NSD-NRC-97-5111, Forwards Westinghouse Responses to Open Items on AP600 Topics for Ssar.Rais 410.244,245,246,247 & 248 Provide Addl Info Re HVAC Sys.Rai 440.337 Addresses Question on WCAP-14206 & 440.385 Addresses Question on Osu Scaling
B16431, Responds to NRC Re Violations Noted in Insp Rept 50-245/97-01 on 970101-0310.Corrective Actions:Operation of Exhaust Fan HVE-14 Was Prevented & Licensee Committed to Review Radwaste Operations in Radwaste Storage Bldg
0CAN029702, Provides Response to NRC Request Under 10CFR50.54(f) Re Adequacy & Availability of Design Bases Info
NSD-NRC-96-4859, Forwards Responses to NRC Questions Re Chapter 6 of AP600 SSAR
ST-HL-AE-2136, Forwards Revised Pages to Util FSAR Which Reflect Change in Commitment to Reg Guide 8.27 Re Radiation Protection Aspects of General Employee Training Courses
ST-HL-AE-2101, Forwards Rev to FSAR Table 3.12-1, Reg Guide Matrix, Which Revises Commitment to Reg Guide 1.133 to Show Testing & Operability Requirements for Loose Parts Monitoring Sys Contained in FSAR Rather than Tech Specs
ST-HL-AE-1674, Forwards Comments & marked-up SER (NUREG-0781) Re Operation of South Texas Projects 1 & 2
ND-22-0463, Technical Requirements Manual, Revision 19
ST-HL-AE-1480, Forwards marked-up FSAR Chapter 7 Pages Re safety-related Display Instrumentation in Response to Draft Ser/Fsar Items F 7.5-1,7.5-21 & 7.5-22.Pages Will Be Incorporated Into Future FSAR Amend
NSD-NRC-96-4902, Forwards Response to Staff Comments on AP600 Test Program
NSD-NRC-96-4905, Forwards Response to 961120 Request Re AP600 Main Control Room Radiological Consequence Modeling
ST-HL-AE-1268, Forwards Revised FSAR Questions & Responses Re Diesel Generators & Lighting Sys.Revised Info Will Be Incorporated Into FSAR Amend 49
NSD-NRC-96-4727, Forwards Three Copies of Westinghouse Response to NRC RAI on AP600 Topics
ULNRC-03290, Forwards 10CFR50.59 Annual Rept Summarizing Written Safety Evaluations of Changes,Tests & Experiments Approved & Implemented for Activities at Plant
B11111, Forwards Response to Draft SER Open Items
B10909, Forwards Remaining Responses & Corresponding FSAR Changes to 640 Series Questions Not Forwarded by Util . Responses Will Be Formally Submitted Along W/Amend 5 by 831101
ELV-02857, Responds to Deviations Noted in Insp Repts 50-424/91-07 & 50-425/91-07 on 910324-0420.Corrective actions:in-place Testing of Unit 2 Auxiliary Bldg Normal Ventilation Sys Filters Scheduled in June 1991
NRC-94-4305, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from Ltrs of 940429,0523,24,0615 & 0815. Responses Provided as Electronic Files Wordperfect 5.1 Format W/Kenyon Copy
ND-22-0922, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report
NRC-94-4259, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 & Provide Electronic Files in Wordperfect 5.1 File for RAI 230.63 Rev 2
NRC-94-4254, Forwards Response to NRC Request for Addl Info on AP600
NRC-94-4234, Forwards Westinghouse Responses to Requests for Addl Info on AP600 from Ltrs of 940428,29,0502,05,11,16,18,23,24,26,0601 & 08.Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a
NRC-94-4181, Submits Responses to NRC Requests for Addl Info Re AP600
TXX-6119, Forwards Detailed Description of 861103 Amend 60 to FSAR Addressing Listed Topics,Including Editorial Corrections & Minor Updates
W3P82-1518, Forwards Containment Purge Study,Providing Justification for Unlimited Purging During Normal Operation,Per SRP 6.2.4, Revision 1 & Associated Branch Technical Position Csb 6-4. NUREG-0737,Item II.E.4.2 Implemented,Per Util
NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks
05000445/LER-1998-005, :on 980617,functional Requirements of Hps Was Not IAW Design.Caused by Failure to Completely Evaluate FSAR Impact on Design Basis.Developed post-accident Recovery Guidance & Design Mod to Allow Use of 12 Inch Inlet Valve
NSD-NRC-98-5609, Forwards Three Copies of W Response to Open Item (Oits) 6636/Q260.140F Re AP600 SSAR Chapter 14, Initial Test Program. Response to Open Item Includes Responses to Listed Dser Open Items of Same Ltr
NSD-NRC-97-5375, Forwards Response to 970625 RAI Re Listed RAIs & Dser Open Items on AP600 SSAR Chapter 14, Initial Test Program
NSD-NRC-98-5539, Forwards Westinghouse Responses to Five Open Items Re AP600 SSAR Chapter 14, Initial Test Program, as Requested in Ltr from Staff
NSD-NRC-97-5087, Consolidates Responses & Resolutions of Items Associated W/Ssar Section 9.4.Completion of Submittal of Final Documentation Related to SSAR Section 9.4 for Application for AP600 Design Certification,Confirmed
NSD-NRC-97-5133, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period 970416-0502,including Draft of SSAR Markup for LOOP Issue & Open Item Status
ET-NRC-93-3886, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from 930126,0218,0312 & 0413 Ltrs.Westinghouse Responses to Remainder of Requests for Addl Info Contained in Will Be Provided Prior to 930529
RAIO-0719-66421, LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application
RAIO-0519-65424, LLC - Supplemental Response to NRC Request for Additional Information No. 494 (Erai No. 9548)on the Design Certification Application
RAIO-0518-60157, LLC Response to NRC Request for Additional Information No. 405 (Erai No. 9277) on the NuScale Design Certification Application
PY-CEI-NRR-2907, Report of 10 CFR 50.59 Evaluations for 2003-2005
CPSES-200501556, License Amendment Request (LAR) 05-005 Revision to Technical Specification 3.7.10, Control Room Emergency Filtration/Pressurization System (Crefs)
RAIO-1218-63854, LLC Response to NRC Request for Additional Information No. 508 (Erai No. 9621) on the NuScale Design Certification Application
RAIO-1017-56676, LLC - Response to NRC Request for Additional Information No. 193 (Erai No. 9079) on the NuScale Design Certification Application
ST-HL-AE-1509, Forwards Response to Draft SER or FSAR Item C 3.7-1 Re Seismic Design Confirming Frequencies of Floor Subsystems in Each Bldg Higher than Corresponding Limit.Encl marked-up FSAR Pages Will Be Incorporated in Future Amend
NSD-NRC-97-4932, Responds to 961217 Telephone Request for Addl Detail in Response to Open Item 293 (M9.4.8-2).Markups of Change Made to Ssar,Rev 11,specifying Filter Requirements Shown
ET-NRC-92-3777, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from 920923 & 1001 Ltrs.Transmittal Partial Response to Ltrs.Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a
NRC-94-4249, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from Ltrs 940407,15,29,0505,11,16,23 & 0608. Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a
TXX-8952, Submits Addl Info Re Air Flow Distribution Test for Iodine Absorbers,Updating 890501 Submittal for Exception to Reg Guides 1.52 & 1.140.W/one Oversize Encl
TXX-8960, Provides Advance Change to Be Included in Future FSAR Amend Re Diesel Generator Fuel Oil Strainers.Change Takes Exception to Reg Guide 1.137
TXX-9642, Forwards Detailed Description of Amend 94 to Updated FSAR for Cpses.Replacement of FSAR Figures W/Plant Process Flow Diagrams Meets Intent & Requirements of Reg Guide 1.70,rev 2
05000373/LER-1989-019, :on 890526,determined That Previous Test Results of LTS-400-16 Did Not Meet Acceptance Criteria of Reg Guide 1.52.Root Cause of Event Was That Charcoal Adsorber Efficiency of 90% Assumed
NL-25-0157, License Amendment Request: One-Time Allowance to Repair Ves Bottled Air System Valve Leakage
NL-25-0195, Emergency License Amendment Request One-Time Allowance to Repair Ves Bottled Air System Valve Leakage (NL-25-0195)