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| | issue date = 06/11/1979 | | | issue date = 06/11/1979 |
| | title = NRC Generic Letter 1979-022: Transmittal of NUREG-0560 Staff Report on Generic Assessment of Feedwater Transients in Pressurized Water Reactors Designed by Babcock and Wilcox Co. | | | title = NRC Generic Letter 1979-022: Transmittal of NUREG-0560 Staff Report on Generic Assessment of Feedwater Transients in Pressurized Water Reactors Designed by Babcock and Wilcox Co. |
| | author name = Grimes B K | | | author name = Grimes B |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
Revision as of 04:31, 14 July 2019
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Category:NRC Generic Letter
MONTHYEARNRC Generic Letter 1999-021999-08-23023 August 1999
NRC Generic Letter 1999-002: (Errata): Laboratory Testing of Nuclear-Grade Activated Charcoal
NRC Generic Letter 1983-111999-06-24024 June 1999
NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis
ML0823509351999-06-0303 June 1999
Generic Ltr 99-02 to All Holders of OLs for Nuclear Power Reactors,Except Those Who Have Permanenetly Ceased Operations & Certified That Fuel Permanently Removed from Rv Re Laboratory Testing of nuclear-grade Activated Charcoal
ML0311101371999-06-0303 June 1999
Withdrawn NRC Administrative Letter 1999-002: Operating Reactor Licensing Action Estimates
NRC Generic Letter 1999-011999-05-0303 May 1999
NRC Generic Letter 1999-001: Recent Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities
NRC Generic Letter 1998-011999-01-14014 January 1999
NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants
ML0311101601998-08-0303 August 1998
Withdrawn NRC Administrative Letter 1998-005: Availability of Summaries in Electronic Format of Technical Reports by Office for Analysis & Evaluation of Operational Data
NRC Generic Letter 1998-041998-07-14014 July 1998
NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i
NRC Generic Letter 1998-031998-06-22022 June 1998
NRC Generic Letter 1998-003; NMSS Licensees and Certificate Holders Year 2000 Readiness Programs
NRC Generic Letter 1998-021998-05-28028 May 1998
NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
NRC Generic Letter 1997-061997-12-30030 December 1997
NRC Generic Letter 1997-006: Degradation of Steam Generator Internals
NRC Generic Letter 1997-051997-12-17017 December 1997
NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques
NRC Generic Letter 1996-061997-11-13013 November 1997
NRC Generic Letter 1996-006, Supplement 1: Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions
ML0312007011997-10-0808 October 1997
Withdrawn NRC Generic Letter 1991-018, Revision 1: Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions
NRC Generic Letter 1997-041997-09-30030 September 1997
NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules
NRC Generic Letter 1997-031997-07-0909 July 1997
NRC Generic Letter 1997-003: Annual Financial Surety Update Requirements for Uranium Recovery Licensees
NRC Generic Letter 1997-021997-05-15015 May 1997
NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report
NRC Generic Letter 1995-061997-01-31031 January 1997
NRC Generic Letter 1995-006: Changes in Operator Licensing Program
NRC Generic Letter 1996-081996-12-15015 December 1996
NRC Generic Letter 1996-008: Interim Guidance on Transportation of Steam Generators
NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves1996-09-18018 September 1996
NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
NRC Generic Letter 1996-041996-06-26026 June 1996
NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks
NRC Generic Letter 1995-091996-04-0505 April 1996
NRC Generic Letter 1995-009: Supplement 1: Monitoring and Training of Shippers and Carriers of Radioactive Materials
NRC Generic Letter 1996-021996-02-13013 February 1996
NRC Generic Letter 1996-002: Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat
NRC Generic Letter 1996-031996-01-31031 January 1996
NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits
NRC Generic Letter 1989-101996-01-24024 January 1996
NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors
NRC Generic Letter 1996-011996-01-10010 January 1996
NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits
NRC Generic Letter 1995-101995-12-15015 December 1995
NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation
ML0310701501995-10-31031 October 1995
Withdrawn - NRC Generic Letter 1995-008: 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval
NRC Generic Letter 1993-031995-10-20020 October 1995
NRC Generic Letter 1993-003: Verification of Plant Records
NRC Generic Letter 1995-071995-08-17017 August 1995
NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves
NRC Generic Letter 1995-031995-04-28028 April 1995
NRC Generic Letter 1995-003: Circumferential Cracking of Steam Generator Tubes
NRC Generic Letter 1995-041995-04-28028 April 1995
NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues
NRC Generic Letter 1995-021995-04-26026 April 1995
NRC Generic Letter 1995-002: Use of Numarc/Epri Report TR-102348, Guideline on Licensing Digital Upgrades, in Determining the Acceptability of Performing Analog-To-Digital Replacements Under 10CFR 50.59
NRC Generic Letter 1995-011995-01-26026 January 1995
NRC Generic Letter 1995-001: NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities
ML0312004431994-09-0202 September 1994
Withdrawn - NRC Generic Letter 1994-004: Voluntary Reporting of Additional Occupational Radiation Exposure Data
NRC Generic Letter 1994-031994-07-25025 July 1994
NRC Generic Letter 1994-003: Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors
NRC Generic Letter 1994-021994-07-11011 July 1994
NRC Generic Letter 1994-002: Long-Item Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors
NRC Generic Letter 1994-011994-05-31031 May 1994
NRC Generic Letter 1994-001: Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators
NRC Generic Letter 1993-081993-12-29029 December 1993
NRC Generic Letter 1993-008: Relocation of Technical Specification Tables of Instrument Response Time Limits
NRC Generic Letter 1993-071993-12-28028 December 1993
NRC Generic Letter 1993-007: Modification of Technical Specification Administrative Control Requirements for Emergency & Security Plans
NRC Generic Letter 1993-061993-10-25025 October 1993
NRC Generic Letter 1993-006: Research Results on Generic Safety Issue 106, Piping and the Use of Highly Combustible Gases in Vital Areas.
NRC Generic Letter 1993-051993-09-27027 September 1993
NRC Generic Letter 1993-005: Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation
NRC Generic Letter 1993-041993-06-21021 June 1993
NRC Generic Letter 1993-004: Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f)
NRC Generic Letter 1993-021993-03-23023 March 1993
NRC Generic Letter 1993-002: Public Workshop on Commercial Grade Procurement and Dedication
NRC Generic Letter 1993-011993-03-0303 March 1993
NRC Generic Letter 1993-001: Emergency Response Data System Test Program
NRC Generic Letter 1992-091992-12-31031 December 1992
NRC Generic Letter 1992-009: Limited Participation by NRC in IAEA International Nuclear Event Scale
NRC Generic Letter 1992-081992-12-17017 December 1992
NRC Generic Letter 1992-008: Thermo-Lag 330-1 Fire Barriers
NRC Generic Letter 1992-071992-10-20020 October 1992
NRC Generic Letter 1992-007 - Office of Nuclear Reactor Regulation Reorganization
NRC Generic Letter 1983-281992-10-0707 October 1992
NRC Generic Letter 1983-028, Supplement 1: Required Actions Based on Generic Implications of Salem ATWS Events.
ML0311304121992-09-16016 September 1992
Withdrawn NRC Generic Letter 1992-006 - Operator Licensing National Examination Schedule
1999-08-23
[Table view] |
0-03 Aof REAP ,&UNITED STATES NUCLEAR REGULATORY
COMMISSION
I.. WASHINGTON, D. C. 20555 June 11, 1979 CL-7'- ci-0Lwo L; -.;z. a. I-'li,.-ALL POWER REACTOR LICENSEES Gentlemen:
Enclosed for your information is a copy of NUREG-0560 "Staff Report on the Generic Assessment of Feedwater Transients in Pressurized Water Reactors Designed by the Babcock & Wilcox Company".Sincerely, Brian K. Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors Enclosure:
NUREG-0560
cc w/enclosure:
Service Lists for B&W Power Reactor Licensees cc w/o enclosure:
All Other Service Lists I10'4, 79071806X
i --1 Mr. William J. Cahill, Jr.Consolidated Edison Company of New York, Inc.cc: White Plains Public Library 100 Martine Avenue White Plains, New York 10601 Joseph D. Block, Esquire Executive Vice President Administrative Consolidated Edison Company of New York, Inc.4 Irving Place New York, New York 10003 Edward J. Sack, Esquire Law Department Consolidated Edison Company of New York, Inc.4 Irving Place New York, New York 10003 Anthony Z. Roisman Natural Resources Defense Council 917 15th Street, N.W.Washington, D. C. 20005 Dr. Lawrence R. Quarles Apartment
51 Kendal at Longwood Kennett Square, Pennsylvania
19348 Theodore A. Rebelowski U. S. Nuclear Regulatory Commission P. 0. Box 38 Buchanan, New York 10511
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