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| Issue date | Title | Topic | |
|---|---|---|---|
| A08995, Rev 1 to Auxiliary Initiation Event Analysis | 14 September 1990 | Rev 1 to Auxiliary Initiation Event Analysis | |
| B12020, Summary of Results of Haddam Neck Probabilistic Safety Study | 31 March 1986 | Summary of Results of Haddam Neck Probabilistic Safety Study | |
| B12480, Const Design Info Submittal:New Switchgear Bldg Const. W/38 Oversize Encl | 30 April 1987 | Const Design Info Submittal:New Switchgear Bldg Const. W/38 Oversize Encl | Hot Short Safe Shutdown Tornado Missile Safe Shutdown Earthquake Operating Basis Earthquake Nondestructive Examination Emergency Lighting Tornado Generated Missile Earthquake |
| B12619, Bimonthly Progress Rept 5:New Switchgear Bldg Const | 31 July 1987 | Bimonthly Progress Rept 5:New Switchgear Bldg Const | Fitness for Duty |
| CY-85-062, Rev 2 to Steam Generator Tube Sleeving & Plugging | 22 January 1986 | Rev 2 to Steam Generator Tube Sleeving & Plugging | Shutdown Margin |
| CY-86-031, Rev 1 to 4.10.1(D) Inservice Insp of Steam Generator Tubes (Acceptance Criteria) | 8 May 1986 | Rev 1 to 4.10.1(D) Inservice Insp of Steam Generator Tubes (Acceptance Criteria) | |
| ML093430794 | 31 October 1981 | Evaluation of Indian Point 3 Nuclear Power Plant. | High Radiation Area |
| ML100321545 | 31 October 1981 | Evaluation of Indian Point Station Unit No 2. | Nondestructive Examination Temporary Modification |
| ML17251A481 | 28 February 1989 | Ultrasonic Indication Sizing Technique Development. Related Info Encl | Hydrostatic |
| ML17258A375 | 31 August 1981 | Evaluation of Robert E Ginna Nuclear Power Plant. | |
| ML17279A191 | 7 April 1987 | Comparision of Electrical Design of Wye Pattern Globe Valve Actuator W/Ball Valve,Hanford 2 & River Bend Design. Five Oversize Drawings Encl | |
| ML17347A797 | 16 June 1988 | Seismic Hazard Data Prepared for Resolution of USI A-46. | Earthquake |
| ML17347A798 | 16 June 1988 | Radiological Data Prepared for Resolution of USI A-46. | Safe Shutdown Earthquake Earthquake Backfit |
| ML17347B462 | 31 December 1989 | App a to USI A-46 & Generic Ltr 87-02. | Safe Shutdown Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Backfit |
| ML18008A031 | 31 July 1989 | NTH-TR-01 Decrease in Heat Removal by Secondary Sys. | Safe Shutdown Rod Drop Event |
| ML18092B497 | 3 April 1987 | S-C-E500-NSE-0675-R-1, Justification for Operation of All Three Units at Artificial Island at Increased Power During Hope Creek-Keeney Line Outage. | |
| ML18093A179 | 19 June 1987 | Installation of Trip-A-Unit Protection Scheme Suppl Info Salem & Hope Creek Generating Stations. | |
| ML18094A355 | 30 April 1989 | Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. | Safe Shutdown Earthquake |
| ML18130A395 | 10 November 1983 | VEPCO North Anna Power Station & Surry Power Station Compliance W/10CFR50.49(b)(2). | |
| ML18139B819 | 31 March 1982 | Nine-Month Response to NRC Ltr Dtd 801220 on Control of Heavy Loads for VEPCO North Anna Units 1 & 2. | Control of Heavy Loads |
| ML18139B925 | 30 June 1982 | PWR Safety & Relief Valve Adequacy Rept for North Anna Units 1 & 2. | Loop seal Stroke time |
| ML18139C010 | 31 August 1982 | PWR Safety & Relief Valve Test Program,Porv Block Valve Adequacy Rept for Vepco,North Anna Unit 1 & Unit 2. | Stroke time Control of Heavy Loads |
| ML18139C291 | 30 April 1982 | Evaluation of Online Boron Analyzers, Final Rept | Boric Acid High Radiation Area Grab sample |
| ML18141A468 | 20 January 1984 | Safety Parameter Display Sys SAR for NUREG-0696 Computer Project,North Anna & Surry Nuclear Power Stations. | Boric Acid Shutdown Margin Reactor Vessel Water Level Fuel cladding |
| ML18151A135 | 28 August 1987 | Rev 1 to SPDS SAR for VEPCO NUREG-0696 Computer Project, North Anna & Surry Nuclear Power Stations. | Fuel cladding |
| ML19327B401 | 31 July 1989 | Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. | |
| ML20005G421 | 28 February 1989 | Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation. | Hydrostatic |
| ML20023D146 | 27 August 1982 | Rev 0 to Assessment of Stitch Weld Strength in HVAC Ductwork Const,Lasalle County Station Units 1 & 2. | |
| ML20023D213 | 25 August 1982 | Rev 1 to LaSalle County Station Technical Proposal, Including Scope of Work,Work Plan to Accomplish Independent HVAC Review,Organization Chart & Resumes of Personnel Assigned to Project.List of Matl Specs for HVAC Const Encl | Coatings Nondestructive Examination Liquid penetrant Scaffolding |
| ML20023E221 | 15 March 1983 | Priority Concerns of Licensed Nuclear Operators at TMI & Oyster Creek & Suggested Action Steps, Final Rept | |
| ML20023E223 | 28 February 1983 | Review of Current & Projected Expenditures & Manpower Utilization for Gpu Nuclear Corp. | |
| ML20024B306 | 30 April 1983 | Determining Portion of Regulatory Burden on Indian Point 3 Capital & O&M Expenditures 1976 - 1986:10-Yr Cost Projection Also Included. | Hydrostatic Probabilistic Risk Assessment |
| ML20028F728 | 8 August 1977 | Control Complex Bldg High Strength Bolting Operation Insp & Testing Checkoff Sheet | |
| ML20040D776 | 15 January 1982 | 180-Day Rept in Response to IE Bulletin 80-11 for Dresden Nuclear Power Station,Units 2 & 3. | |
| ML20040D780 | 15 January 1982 | 180-Day Rept in Response to IE Bulletin 80-11 for Quad Cities Nuclear Power Station,Units 1 & 2. | |
| ML20040H493 | 4 February 1982 | Vent Stack Reanalysis Rept. | |
| ML20041E351 | 31 January 1981 | Evaluation of Jm Farley Nuclear Plant. | Coatings |
| ML20041E352 | 31 January 1981 | Evaluation of El Hatch Nuclear Plant. | Packing leak |
| ML20041F269 | 12 March 1982 | Licensing Review Group II Position Papers, Vol IV | Safe Shutdown |
| ML20042C128 | 24 March 1982 | BWR Control Rod Drive Sys Vessel Inventory Makeup Rate Aspects of NUREG-0619. | Safe Shutdown Reactor Vessel Water Level Fire Barrier Earthquake |
| ML20052A254 | 8 April 1982 | Public Version of Emergency Operations Facility. | |
| ML20052F247 | 6 July 1980 | Draft Revision 1 to Rept & Safety Evaluation of Browns Ferry Unit 3 Partial Scram Failure of 800628. | Loop seal Half scram Hydrostatic Scram Discharge Volume |
| ML20054D854 | 30 April 1982 | Paleomagnetic Investigation of Pre-Missoula Gravels,Pasco Basin & Vicinity,Wa. | |
| ML20054F070 | 30 April 1982 | Bryon/Braidwood Stations - Units 1 & 2,Inadequate Core Cooling Detection Sys Summary Status Rept | Safe Shutdown Fuel cladding |
| ML20054L493 | 15 June 1982 | Pressurizer & Safety Relief Line Piping & Support Evaluation & Action Plan, Interim Rept | Loop seal |
| ML20054L579 | 25 June 1982 | Probabilistic Evaluation of High Pressure Liquid Challenges to Safety/Relief Valves in Zion,Byron/Braidwood PWR Plants | |
| ML20054L667 | 30 June 1982 | PWR Safety & Relief Valve Adequacy Rept for Surry Units 1 & 2 | Loop seal |
| ML20055D893 | 30 June 1990 | Fracture Mechanics Evaluation:Haddam Neck Pressurizer | |
| ML20055G495 | 31 July 1990 | Decommissioning Financial Assurance Certification Rept | |
| ML20058G348 | 31 October 1993 | Nonproprietary VIPRE/WRB-1 DNBR Thermal Limit for Westinghouse Fuel Types, for Oct 1993 |