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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20204G246 | 22 March 1999 | Audit Rept on Implementation of GL 98-01, 'Year 2000 Readiness of Computer Sys at Nuclear Power Plants.' | |
| ML20151W180 | 25 August 1998 | Rev 2 to BYR98-109/BRW-98-0339-E, Base Line Ampacity Values for Std Fire Wrap Configurations | |
| ML20198L818 | 10 December 1997 | Rev 5 to Calculation 95-011, Control Room Thyroid Dose from Main Steam Line Break Event | |
| ML20198L828 | 10 December 1997 | Rev 4 to Calculation BRW-97-0798-M, Allowable Leak Rate Calculation for SG Interim Plugging Criteria | |
| ML20203J750 | 9 December 1997 | Plant Issues Matrix | Hot Short Safe Shutdown Unanalyzed Condition Boric Acid Loop seal Packing leak High Radiation Area Grab sample Offsite Dose Calculation Manual Fire Barrier Stroke time Weld Overlay Anchor Darling Emergency Lighting Locked High Radiation Area Foreign Material Exclusion Scram Discharge Volume Annual Radiological Environmental Operating Report Battery sizing Earthquake Fire Protection Program Fire Watch Downpower Reverse polarity |
| IA-97-451, Plant Issues Matrix | 9 December 1997 | Plant Issues Matrix | Hot Short Safe Shutdown Unanalyzed Condition Boric Acid Loop seal Packing leak High Radiation Area Grab sample Offsite Dose Calculation Manual Fire Barrier Stroke time Weld Overlay Anchor Darling Emergency Lighting Locked High Radiation Area Foreign Material Exclusion Scram Discharge Volume Annual Radiological Environmental Operating Report Battery sizing Earthquake Fire Protection Program Fire Watch Downpower Reverse polarity |
| ML20211H294 | 30 September 1997 | Rev 4 to Allowable Leakrate Calculation for SG Interim Plugging Criteria | |
| ML20211H302 | 30 September 1997 | Rev 2 to CR Dose for MSLB Accident | |
| ML20211H308 | 30 September 1997 | Rev 3 to Allowable Leakrate Calculation for SG Interim Plugging Criteria | |
| ML20211H321 | 30 September 1997 | Rev 4 to CR Thyroid Dose from MSLB Event | |
| ML20216F169 | 29 August 1997 | Rev 3 to CR Thyroid Dose from MSLB Event | |
| ML20216F162 | 29 August 1997 | Rev 0 to Allowable Leakrate Calculation for SG Interim Plugging Criteria | |
| ML20210P139 | 22 August 1997 | Rev 0 to BYR97-332, CR Dose for MSLB Accident | |
| ML20210P160 | 21 August 1997 | Rev 1 to ATD-0410, Allowable Leakrate Calculation for Steam Generator Interim Plugging Criteria | |
| ML20149H742 | 10 July 1997 | Rev 0 to 5.2.2-BRW-97-0667, Evaluate Tendon H4ED for Broken/Unseated Wires | |
| ML20148T728 | 27 June 1997 | Rev 4 to BWR-97-0339-M, Byron & Braidwood CR Heat Up Evaluation | Coast down |
| ML20148T742 | 25 June 1997 | Rev 4 to BRW-97-0624-M, Determination of Div 11 & 12 Miscellaneous Electrical Equipment Rooms Transient Temp Profiles Following Loss of Ventilation | |
| ML20140D390 | 12 March 1997 | Determination of 2-Dimensional Pressure Distribution on Byron/Braidwood D4 SG Tube Support Plate During Mslb | |
| ML20133K462 | 17 January 1997 | Press Release III-97-05, NRC to Hold Predecisional Enforcement Conference W/Comm Ed on Apparent Violations at Byron Plant | |
| ML20133E740 | 31 December 1996 | Flaw Evaluation of Line 1SX933AA-8 Per GL 90-05 Guidelines | Nondestructive Examination Earthquake |
| ML20129G522 | 2 October 1996 | Press Release III-96-61, Byron Nuclear Plant Rated Superior in Two Areas, Good in Two Areas in NRC Performance Assessment | Systematic Assessment of Licensee Performance |
| ML20115F368 | 3 June 1996 | Ampacity Derating for Std Fire Wrap Configurations | Fire Barrier |
| ML20115F353 | 19 April 1996 | Verification of Models for Fire-Wrapped Conduits & Cable Trays Against Test Data | Fire Barrier Thermoset |
| ML20092B161 | 4 September 1995 | Calculation of Byron D4 SG Tube Support Plate Differential Pressures During MSLB W/RELAP5M2 | |
| ML20080H523 | 23 January 1995 | Darmatt Firewrap Matl Cable Ampacity Derating Factor Calculation | Fire Barrier |
| ML20062N819 | 29 December 1993 | Battery Sizing Calculation | Battery sizing |
| ML20062N821 | 9 December 1993 | Battery Sizing Calculation | Battery sizing |
| ML20085M469 | 11 November 1991 | Responds to Aquatic Resource Questions Re NUMARC Survey in Support of NRC License Renewal Rulemaking | Weld Overlay License Renewal Scaffolding |
| ML20247R371 | 18 September 1989 | Package of Three FOIA Requests | |
| ML20155F803 | 7 September 1988 | Viewgraphs from Meeting on New Radwaste Facilities at Plants | Process Control Program |
| ML20237D790 | 10 December 1987 | Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys | |
| ML20236S442 | 20 November 1987 | Package Consisting of Requests for Addl Info Re Gpu Topical Repts TR-033, Methods for Generation of Core Kinetics Data for Retran-02 & TR-040, Steady-State & Quasi-Steady-State Methods Used in Analysis.... SPDS Meeting Summary Encl | |
| IA-87-725, Package Consisting of Requests for Addl Info Re Gpu Topical Repts TR-033, Methods for Generation of Core Kinetics Data for Retran-02 & TR-040, Steady-State & Quasi-Steady-State Methods Used in Analysis.... SPDS Meeting Summary Encl | 20 November 1987 | Package Consisting of Requests for Addl Info Re Gpu Topical Repts TR-033, Methods for Generation of Core Kinetics Data for Retran-02 & TR-040, Steady-State & Quasi-Steady-State Methods Used in Analysis.... SPDS Meeting Summary Encl | |
| ML20149H901 | 8 October 1987 | Package Consisting of Repts of Licensee Telcons to Region V Re Incidents on 871007 & 1221 | Fitness for Duty |
| ML20151M960 | 20 July 1987 | Package of NRC Administered Requalification Exam Results Summary | |
| ML20215G662 | 18 June 1987 | Package Consisting of Basic Nuclear Concepts - Lesson Objectives,Ja Dellavalle Undated Ltr & Northeast Utils, Thames Valley State Technical College Nuclear Engineering Technology Contract & Amend 1 | Post Accident Monitoring Power change |
| ML20235P046 | 23 March 1987 | Package Consisting of Draft Board Notification 87-005 Re BNL Draft Rept on Spent Fuel Pool Accidents & Viewgraphs Concerning Generic Issue 82 on Beyond DBAs in Spent Fuel Pools | Earthquake Chernobyl Fuel cladding |
| ML20215H962 | 5 February 1987 | Package Consisting of NRR Presentation to ACRS Re 870115 Technical Meeting to Consider Generic Implications of Facility Feedwater Line Failure & J Rosenthal Failure of Main Feedwater Pipe 861209 Outline | Nondestructive Examination Fatality |
| ML20211A082 | 3 October 1986 | Package Consisting of Summary Schedule Suppl & Variance Rept & Capital Project Request Summary | |
| ML20207S234 | 9 September 1986 | Affirmation Response Sheet Approving SECY-86-257, Request for Stay & Review of Appeal Board Decision in Shearon Harris Proceeding | |
| ML20207S226 | 8 September 1986 | Affirmation Response Sheet Partly Approving SECY-86-252, Commission Review of Shearon Harris Appeal Board on Environ Issues. Author Agrees W/Ofc of General Counsel Recommendation But Sees No Reason to Begin Rulemaking | |
| ML20207S232 | 8 September 1986 | Affirmation Response Sheet Disapproving SECY-86-254, Request for Hearing on Shearon Harris Exemption Request. Author Does Not Believe in Beginning Rulemaking to Change Requirement to 2-yr Rather than 1-yr Requirement | Exemption Request |
| ML20203H285 | 28 July 1986 | Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 | Hydrostatic |
| IA-86-445, Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 | 28 July 1986 | Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 | Hydrostatic |
| ML20137Q667 | 3 January 1986 | Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities | Shutdown Margin Reactor Vessel Water Level Squib Scram Discharge Volume Overtravel Fuel cladding Offsite Circuit |
| IA-85-771, Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities | 3 January 1986 | Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities | Shutdown Margin Reactor Vessel Water Level Squib Scram Discharge Volume Overtravel Fuel cladding Offsite Circuit |
| ML20132F889 | 20 September 1985 | Power Plant Exam Results Summary Sheets.Info Deleted | |
| ML20133P093 | 1 August 1985 | Rev 0 to Calculation Q-14, Calculation for Justification for Electrical Separation Between Safety-Related & Nonsafety-Related Cables When One in Free Air & Other in Raceway | |
| ML20133P046 | 1 August 1985 | Rev 0 to Calculation Q-13, Calculations for Justification of Electrical Separation Distance Between Safety-Related & Nonsafety-Related Raceways | |
| IA-85-442, Package of Operator Exam Results Summary Sheets | 18 July 1985 | Package of Operator Exam Results Summary Sheets |