Category:Unfiltered
Jump to navigation
Jump to search
(previous page) (next page)
This category is meant to manually exclude a page from the automatic import function. This will allow you to make the format the way you want it to look like without it being undone or you may correct actual typo is a source document when you find it appropriate. Please try to leave a summary comment to prove that this was done.
Pages in category "Unfiltered"
The following 200 pages are in this category, out of 609 total.
(previous page) (next page)E
I
J
- JAFP-07-0088, James A. FitzPatrick, Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 3
- JAFP-08-0006, Application for Amendment to Technical Specifications Regarding Diesel Fuel Oil, Lube Oil, and Starting Air Consistent with TSTF-501 and Diesel Fuel Oil Testing Program Consistent with TSTF-374
- JAFP-09-0025, James A. Fitzpatrick - Request for Exemption from 10 CFR 50 Appendix R Section III.G.2 Requirements Based on Manual Actions
- JAFP-13-0115, Application to Revise Technical Specifications for Technical Specification Low Pressure Safety Limit
- JAFP-17-0030, Submittal of 2017 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes
- JAFP-17-0083, Report of Full Compliance with March 12, 2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
- JAFP-19-0077, License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences
- JAFP-20-0046, License Amendment Request for Adoption of TSTF-478-A, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Using the Consolidated Line Item.
- JAFP-20-0080, Application to Revise Surveillance Requirement (SR) 3.5.1.6
- JAFP-20-0083, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule
- JAFP-21-0008, Supplement to Application to Revise Surveillance Requirement (SR) 3.5.1.6
- JAFP-21-0027, 1OCFR20.2206(b) Personnel Radiation Exposure Report for 2020
- JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation
- JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..
- JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
- JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements
M
N
- NEI 99-02
- NL-21-0634, Request to Eliminate Automatic Main Steam Line Isolation on High Turbine Building Area Temperature
- NRC Generic Letter 1981-38, Storage of Low-Level Radioactive Wastes at Power Reactor Sites
- NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification
- NRC Generic Letter 1988-14
- NRC Generic Letter 2003-01, Control Room Habitability
- NRC Generic Letter 77-01, Intrusion Detection Systems Handbook
- NRC Generic Letter 77-02, Fire Protection Functional Responsibilities
- NRC Generic Letter 77-03, Transmittal of NUREG-0321, "A Study of the Nuclear Regulatory Commission Quality Assurance Program"
- NRC Generic Letter 77-04, Shipments of Contaminated Components From NRC Licensed Nuclear Power Facilities to Vendors & Service Companies
- NRC Generic Letter 77-05, Nonconformity of Addresses of Items Directed to the Office of Nuclear Reactor Regulation
- NRC Generic Letter 77-06, Enclosing Questionaire Relating to Steam Generators
- NRC Generic Letter 77-07, Reliability Of Standby Diesel Generator Units
- NRC Generic Letter 78-01, Correction To Letter Of 12/15/77
- NRC Generic Letter 78-02, Asymmetric Loads Background & Revised Request For Additional Information
- NRC Generic Letter 78-03, Request For Information On Cavity Annulus Seal Ring
- NRC Generic Letter 78-04, GAO Blanket Clearance For Letter Dated 12/09/77
- NRC Generic Letter 78-05, Internal Distribution Of Correspondence - Asking For Comments On Mass Mailing System
- NRC Generic Letter 78-08, Enclosing NUREG-0408 RE Mark I Containments, and Granting Exemption from GDC 50 and Enclosing Sample Notice
- NRC Generic Letter 78-09, Multiple-Subsequent Actuations of Safety/Relief Valves Following an Isolation Event
- NRC Generic Letter 78-10, Guidance On Radiological Environmental Monitoring
- NRC Generic Letter 78-11, Guidance on Spent Fuel Pool Modifications
- NRC Generic Letter 78-12, Notice of Meeting Regarding "Implementation of 10 CFR 73.55 Requirements And Status of Research..."
- NRC Generic Letter 78-13, Forwarding of NUREG-0219
- NRC Generic Letter 78-14, Transmittal Of Draft NUREG-0219 For Comment
- NRC Generic Letter 78-15, Task Action Plan for Category A Technical Activity No. A-36, "Control of Heavy Loads Near Spent Fuel"
- NRC Generic Letter 78-16, Request for Information on Control of Heavy Loads Near Spent Fuel Pools
- NRC Generic Letter 78-17, Corrected Letter On Heavy Loads Over Spent Fuel
- NRC Generic Letter 78-18, Corrected Letter On Heavy Loads Over Spent Fuel
- NRC Generic Letter 78-19, Enclosing Sandia Report SAND 77-0777, "Barrier Technology Handbook"
- NRC Generic Letter 78-20, Enclosing – "A Systematic Approach to the Conceptual Design of Physical Protection Systems for Nuclear Facilities"
- NRC Generic Letter 78-21, Transmitting NUREG/CR-0181 Concerning Barrier & Penetration Data Needed for Physical Security System Assessment
- NRC Generic Letter 78-22, Revision to Intrusion Detection Systems and Entry Control Handbooks and Nuclear Safeguards Technology Handbook
- NRC Generic Letter 78-23, Manpower Requirements For Operating Reactors
- NRC Generic Letter 78-24, Model Appendix I Technical Specifications and Submittal Schedule for BWRs
- NRC Generic Letter 78-26, Excessive Control Rod Guide Tube Wear
- NRC Generic Letter 78-27, Forwarding of NUREG-0181
- NRC Generic Letter 78-28, Forwarding pages omitted from 07/11/78 letter
- NRC Generic Letter 78-29, Notice of PWR steam generator conference
- NRC Generic Letter 78-30, Forwarding of NUREG-0219
- NRC Generic Letter 78-31, Notice of Steam Generator Conference Agenda
- NRC Generic Letter 78-32, Reactor Protection System Power Supplies
- NRC Generic Letter 78-34, Reactor Vessel Atypical Weld Material
- NRC Generic Letter 78-35, Regional Meetings to Discuss Upgraded Guard Qualifications
- NRC Generic Letter 78-36, Cessation of Plutonium Shipments by Air Except in NRC Approved Containers
- NRC Generic Letter 78-37, Revised Meeting Schedule & Locations for Upgraded Guard Qualifications
- NRC Generic Letter 78-38, Forwarding of 2 Tables Of Appendix I, Draft Radiological Effluent Technical Specifications, PWR, and NUREG-0133
- NRC Generic Letter 78-39, Forwarding of 2 Tables of Appendix I, Draft Radiological Effluent Technical Specifications, BWR, and NUREG-0133
- NRC Generic Letter 78-40, Training & Qualification Program Workshops
- NRC Generic Letter 78-41, Mark II Generic Acceptance Criteria for Lead Plants
- NRC Generic Letter 78-42, Duplicate of GL-78-40
- NRC Generic Letter 79-01, Interservice Procedures for Instructional Systems Development – TRADOC
- NRC Generic Letter 79-02, Transmitting Rev. to Entry Control Systems Handbook (SAND 77-1033), Intrusion Detection Handbook (SAND 76-0554), and Barrier Penetration Database
- NRC Generic Letter 79-03, Offsite Dose Calculation Manual
- NRC Generic Letter 79-04, Referencing 4/14/78 Letter – Modifications to NRC Guidance "Review and Acceptance of Spent Fuel Pool Storage and Handling"
- NRC Generic Letter 79-05, Information Relating to Categorization of Recent Regulatory Guides by the Regulatory Requirements Review Committee
- NRC Generic Letter 79-06, Contents of the Offsite Dose Calculation Manual
- NRC Generic Letter 79-07, Seismic (SSE) and LOCA Responses (NUREG-0484)
- NRC Generic Letter 79-08, Amendment to 10 CFR 73.55
- NRC Generic Letter 79-09, Staff Evaluation of Interim Multiple-Consecutive Safety-Relief Valve Actuations
- NRC Generic Letter 79-10, Transmitting Regulatory Guide 2.6 for Comment
- NRC Generic Letter 79-11, Transmitting "Summary of Operating Experience with Recalculating Steam Generators, January 1979" NUREG-0523
- NRC Generic Letter 79-12, ATWS – Enclosing Letter to GE, with NUREG-0460, Vol. 3
- NRC Generic Letter 79-13, Schedule for Implementation and Resolution of Mark I Containment Long Term Program
- NRC Generic Letter 79-14, Pipe Crack Study Group – Enclosing NUREG-0531 and Notice
- NRC Generic Letter 79-15, Steam Generators-Enclosing Summary of Operating Experience with Recirculating Steam Generators, NUREG-0523
- NRC Generic Letter 79-16, Meeting Re Implementation Of Physical Security Requirements
- NRC Generic Letter 79-17, Reliability of Onsite Diesel Generators at Light Water Reactors
- NRC Generic Letter 79-18, Westinghouse Two-Loop NSSS
- NRC Generic Letter 79-19, NRC Staff Review of Responses to I&E Bulletins 79-06 and 79-06a
- NRC Generic Letter 79-20, Cracking in Feedwater Lines
- NRC Generic Letter 79-21, Enclosing NUREG/CR 0660, "Enhancement of on Site Emergency Diesel Generator Reliability"
- NRC Generic Letter 79-22, Enclosing NUREG-0560, "Staff Report on the Generic Assessment of Feedwater Transients in PWRs Designed by B&W
- NRC Generic Letter 79-23, NRC Staff Review of Responses to I&E Bulletin 79-08
- NRC Generic Letter 79-24, Multiple Equipment Failures in Safety-Related Systems
- NRC Generic Letter 79-25, Information Required to Review Corporate Capabilities
- NRC Generic Letter 79-26, Upgraded Standard Technical Specification Bases Program
- NRC Generic Letter 79-27, Operability Testing of Relief and Safety Relief Valves
- NRC Generic Letter 79-28, Evaluation of Semi-Scale Small Break Experiment
- NRC Generic Letter 79-29, Transmitting NUREG-0473, Revision 2, Draft Radiological Effluent Technical Specifications
- NRC Generic Letter 79-30, Transmitting NUREG-0472, Revision 2, Draft Radiological Technical Specifications
- NRC Generic Letter 79-31, Submittal of Copies of Response to 6/29/79 NRC Request
- NRC Generic Letter 79-32, Transmitting NUREG-0578, "TMI-2 Lessons Learned"
- NRC Generic Letter 79-33, Transmitting NUREG-0576 - Security Training and Qualification Plans
- NRC Generic Letter 79-34, New Physical Security Plans (FR 43280-285)
- NRC Generic Letter 79-35, Regional Meetings to Discuss Impacts on Emergency Planning
- NRC Generic Letter 79-36, Adequacy of Station Electric Distribution Systems Voltages
- NRC Generic Letter 79-37, Amendment to 10 CFR 73.55 Deferral from 8/1/79 to 11/1/79
- NRC Generic Letter 79-38, BWR Off-Gas Systems – Enclosing NUREG/CR-0727
- NRC Generic Letter 79-39, Transmitting Division 5 Draft Regulatory Guide and Value Impact Statement
- NRC Generic Letter 79-40, Follow-up Actions Resulting from the NRC Staff Reviews Regarding the TMI-2 Accident
- NRC Generic Letter 79-41, Compliance with 40 CFR 190, EPA Uranium Fuel Cycle Standard
- NRC Generic Letter 79-42, Potential Unreviewed Question on Interaction Between Non-Safety Grade Systems and Safety Grade Systems
- NRC Generic Letter 79-43, Reactor Cavity Seal Ring Generic Issue
- NRC Generic Letter 79-44, Referencing 6/29/79 Letter Re Multiple Equipment Failures
- NRC Generic Letter 79-45, Transmittal of Reports Regarding Foreign Reactor Operating Experiences
- NRC Generic Letter 79-46, Containment Purging and Venting During Normal Operation – Guidelines for Valve Operability
- NRC Generic Letter 79-47, Radiation Training
- NRC Generic Letter 79-48, Confirmatory Requirements Relating to Condensation Oscillation Loads for the Mark I Containment Long Term Program
- NRC Generic Letter 79-49, Summary of Meetings Held on 9/18-20/79 to Discuss Potential Unreviewed Safety Question on Systems Interaction for B&W Pl
- NRC Generic Letter 79-50, Emergency Plans Submittal Dates
- NRC Generic Letter 79-51, Follow-up Actions Resulting from the NRC Staff Reviews Regarding the TMI-2 Accident
- NRC Generic Letter 79-52, Radioactive Release at North Anna Unit 1 and Lessons Learned
- NRC Generic Letter 79-53, ATWS
- NRC Generic Letter 79-54, Containment Purging and Venting During Normal Operation
- NRC Generic Letter 79-55, Summary of Meeting Held on October 12, 1979 to Discuss Responses to IE Bulletins 79-05C and 79-06C and HPI Termination Criteria
- NRC Generic Letter 79-56, Discussion of Lessons Learned Short Term Requirements
- NRC Generic Letter 79-57, Acceptance Criteria for the Mark I Containment Long Term Program
- NRC Generic Letter 79-58, ECCS Calculations on Fuel Cladding
- NRC Generic Letter 79-60, Discussion of Lessons Learned Short Term Requirements
- NRC Generic Letter 79-61, Discussion of Lessons Learned Short Term Requirements
- NRC Generic Letter 79-63, Upgraded Emergency Plans
- NRC Generic Letter 79-64, Suspension of All Operating Licenses
- NRC Generic Letter 79-65, Radiological Environmental Monitoring Program Requirements – Enclosing Branch Technical Position, Revision 1
- NRC Generic Letter 79-66, Additional Information Re 11/09/79 Letter on ECCS Calculations
- NRC Generic Letter 79-67, Estimates for Evacuation of Various Areas Around Nuclear Power Reactors
- NRC Generic Letter 79-68, Audit of Small Break LOCA Guidelines
- NRC Generic Letter 79-69, Cladding Rupture, Swelling, and Coolant Blockage as a Result of a Reactor Accident
- NRC Generic Letter 79-70, Environmental Monitoring for Direct Radiation
- NRC Generic Letter 80-01, NUREG-0630 "Cladding, Swelling and Rupture - Models for LOCA Analysis"
- NRC Generic Letter 80-02, Quality Assurance Requirements Regarding Diesel Generator Fuel Oil
- NRC Generic Letter 80-03, BWR Control Rod Failures
- NRC Generic Letter 80-04, IEB 80-01 Operability of ADS Valve Pneumatic Supply
- NRC Generic Letter 80-05, IEB 79-01b Environmental Qualification of Class 1E Equipment
- NRC Generic Letter 80-06, Issuance of NUREG-0313, Rev 1, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure"
- NRC Generic Letter 80-07, Information Regarding the Program For Environmental Qualification of Safety-Related Electrical Equipment
- NRC Generic Letter 80-08, IEB 80-02 Inadequate Quality Assurance for Nuclear Supplied Equipment
- NRC Generic Letter 80-09, Low Level Radioactive Waste Disposal
- NRC Generic Letter 80-10, Issuance of NUREG-0588, "Interim Staff Position on Equipment Qualifications of Safety-Related Electrical Equipment"
- NRC Generic Letter 80-100, Appendix R to 10 CFR 50 Regarding Fire Protection-Federal Register Notice
- NRC Generic Letter 80-101, Inservice Inspection Programs for Prestressed Concrete Containment Structures
- NRC Generic Letter 80-102, Commission Memorandum and Order of May 23, 1980 (Referencing IEB 79-01b Supplement 2 - q.2 & 3 - Sept 30, 1980)
- NRC Generic Letter 80-103, Fire Protection - Revised Federal Register Notice
- NRC Generic Letter 80-104, Orders on Environmental Qualification of Safety Related Electrical Equipment
- NRC Generic Letter 80-105, Implementation of Guidance for USI A-12, Potential for Low Fracture Toughness and Lamellar Tearing on Component Supports
- NRC Generic Letter 80-106, Report on ECCS Cladding Models, NUREG-0630
- NRC Generic Letter 80-107, BWR Scram Discharge System
- NRC Generic Letter 80-108, Emergency Planning
- NRC Generic Letter 80-109, Guidelines for SEP Soil Structure Interaction Reviews
- NRC Generic Letter 80-11, IEB 80-03 Loss of Charcoal From Standard Type II, 2 Inch, Tray Absorber Cells
- NRC Generic Letter 80-110, Periodic Updating of FSARS
- NRC Generic Letter 80-111, IEB 80-17 Supplement 4, Failure of Control Rods to Insert During a Scram at a BWR
- NRC Generic Letter 80-112, IEB 80-25 Operating Problems with Target Rock Safety Relief Valves
- NRC Generic Letter 80-113, Control of Heavy Loads
- NRC Generic Letter 80-12, IEB 80-04 Analysis of a PWR Main Steam Sine Break with Continued Feedwater Addition
- NRC Generic Letter 80-13, Qualification of Safety Related Electrical Equipment
- NRC Generic Letter 80-14, LWR Primary Coolant System Pressure Isolation Valves
- NRC Generic Letter 80-15, Request for Additional Management and Technical Resources Information
- NRC Generic Letter 80-16, IEB 79-01b Environmental Qualification of Class 1E Equipment
- NRC Generic Letter 80-17, Modifications to Boiling Water Reactor Control Rod Drive Systems
- NRC Generic Letter 80-18, Crystal River 3 Reactor Trip From Approximately 100% Full Power
- NRC Generic Letter 80-19, Resolution of Enhanced Fission Gas Release Concern
- NRC Generic Letter 80-20, Actions Req. From OL Applicants of NSSS Designs by W and CE Resulting From NRC B&O Task Force Review of TMI2 Accident
- NRC Generic Letter 80-21, IEB 80-05 Vacuum Condition Resulting in Damage to Chemical Volume Control System Holdup Tanks
- NRC Generic Letter 80-22, Transmittal of NUREG-0654 "Criteria For Preparation and Evaluation of Radiological Emergency Response Plans and Prepared
- NRC Generic Letter 80-23, Change of Submittal Date for Evaluation Time Estimates
- NRC Generic Letter 80-24, Transmittal of Information on NRC "Nuclear Data Link Specifications"