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| Issue date | Site | Title | |
|---|---|---|---|
| ML20206U908 | 17 December 1998 | Braidwood | Cycle 8 COLR in ITS Format & W(Z) Function |
| ML20207H641 | 22 July 1986 | Arkansas Nuclear | Advises That Arkansas Nuclear One - Unit 2 Inadequate Core Cooling (ICC) Monitoring Sys Final Design Description Will Be Withheld (Ref 10CFR2.790),per 860415 Request |
| ML20207S216 | 9 March 1987 | Arkansas Nuclear | Forwards Request for Addl Info Re Items 2.1 & 2.2.1 of Generic Ltr 83-28 & Description of Vendor Interface Program. Response to Addl Info Due within 60 Days of Ltr |
| ML20209F011 | 20 April 1987 | Arkansas Nuclear | Requests Assistance in Making Arrangements for Bnwl 870427 Site Visit to Gather Info for NRC Nuclear Plant Aging Research Program & Review Emergency Operating Procedures |
| ML20211C479 | 14 October 1986 | Arkansas Nuclear | Forwards SER Accepting Util Responses to Generic Ltr 83-28, Item 2.1 (Part 1) Re Documentation of safety-related Components Required for Reactor Trip.Item 2.1 (Part 2) Re Vendor Interface Unresolved |
| ML20211D494 | 16 October 1986 | Arkansas Nuclear | Approves Util 840830 Request to Withhold Proprietary R-84-011-P, Final Rept for Phase 1 of Arkansas Power & Light Co Inadequate Core Cooling..., from Public Disclosure (Ref 10CFR2.790) |
| ML20211G109 | 23 October 1986 | Arkansas Nuclear | Forwards Safety Evaluation Re Util 840413 & 850701 Responses to Reg Guide 1.97, Emergency Response Capability. Responses Acceptable.Requests Addl Info Re Instrument Range of RCS Pressure Instrumentation within 60 Days |
| ML20211G281 | 23 October 1986 | Arkansas Nuclear | Informs That NRC Will Be Conducting post-accreditation Review of Facilities Training Programs Beginning 861104.Exit Briefing Will Be Held 861106.Cwalina 861020 Memo Providing Specific Info Encl |
| ML20212G319 | 30 September 1999 | Corium Dispersion in Direct Containment Heating.Separate Effect Experiments with Water and Woods Metal Simulating Core Melt for Zion Reactor Conditions | |
| ML20212G328 | 30 September 1999 | Corium Dispersion in Direct Containment Heating.Theoretical Analysis of the Hydrodynamic Characteristics | |
| ML20212K292 | 2 March 1987 | Arkansas Nuclear | Provides Info Re Implementation Schedules.Due to Delays Incurred in Preparation of QA Guidance (Generic Ltr 85-06) & Extensive Time & Effort Resolving Complex Issues,Deadline Extended to No Later than 840724 |
| ML20213H007 | 13 November 1986 | Arkansas Nuclear | Advises That Site Visit Scheduled for 861202-05 to Review Design,Maint,Surveillance Testing & Reliability of Emergency Feedwater Sys.Assistance in Making Necessary Arrangements Requested.Agenda Will Be Provided by 861117 |
| ML20214S881 | 3 June 1987 | Arkansas Nuclear | Notification of 870609 Meeting W/Util in Bethesda,Md to Discuss Emergency Feedwater Sys Reliability |
| ML20215L608 | 24 October 1986 | Arkansas Nuclear | Forwards SAIC-86/3070, Technical Evaluation of Dcrdr, Arkansas Nuclear One,Unit 1, & SAIC-86/3067, Technical Evaluation of Dcrdr,Arkansas Nuclear One,Unit 2, Technical Evaluation Repts.Open Items & Need for Addl Info Noted |
| ML20216D384 | 12 July 1999 | Braidwood | Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function |
| ML20235F016 | 1 July 1987 | Arkansas Nuclear | Summary of 870610 Meeting W/Util in Bethesda,Md Re Reliability of Plant Emergency Feedwater Sys.List of Meeting Attendees Encl |
| ML20235Y032 | 21 July 1987 | Arkansas Nuclear | Forwards Request for Addl Info Supporting Util 831105,850527 & 0726 Responses to Item 2.2 (Part 2) of Generic Ltr 83-28, Vendor Interface (Programs for All Safety-Related Components). Response Requested by 60 Days of Ltr Receipt |
| ML20236J028 | 31 July 1987 | Arkansas Nuclear | Forwards Draft Safety Evaluation of Auxiliary Feedwater Sys (Generic Issue 124) Re ANO-2.Preliminary Findings Discussed at 870610 Public Meeting,Still Being Reviewed |
| ML20237J623 | 24 August 1987 | Revised Agenda for 870826 Meeting W/B&W Owners Group in Bethesda,Md to Discuss Thermal Hydraulic Testing for B&W Plants |