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| Issue date | Title | |
|---|---|---|
| ML20129E715 | 14 October 1996 | Defueled SAR for Rancho Seco |
| NRC Generic Letter 1994-02 | 11 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 1992-04 | 19 August 1992 | NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F) |
| NRC Generic Letter 1990-06 | 25 June 1990 | NRC Generic Letter 1990-006: Resolution of Generic Issue, Power-Operated Relief Valve and Block Valve Reliability, and Generic Issue 94, Additional Low-Temp. Overpressure Protection for Light-Water Reactors, Pursuant to 10 CFR 50354 (F) |
| ML20245E944 | 31 January 1989 | Forwards Proposed plant-specific Backfit for Improved Auxiliary Feedwater Sys Reliability Analyses for Required Improvement in Secondary DHR Capability at Plant |
| ML20154N796 | 23 September 1988 | Provides Evaluation of B&W Document 47-1159091-00, Design Requirements for Diverse Scram Sys & ATWS Mitigation Sys Actuation Circuitry |
| NRC Generic Letter 1988-11 | 12 July 1988 | NRC Generic Letter 1988-011: NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations |
| NUREG-1231, Forwards NUREG-1231, SER Re B&W Owners Group Plant Reassessment Program. NRC Unable to Reach Final Conclusion on Acceptability of Human Factors Portion of Program. Consideration of NRC Recommendations Requested | 6 November 1987 | Forwards NUREG-1231, SER Re B&W Owners Group Plant Reassessment Program. NRC Unable to Reach Final Conclusion on Acceptability of Human Factors Portion of Program. Consideration of NRC Recommendations Requested |
| ML20236D319 | 7 October 1987 | Rev 0 to Radiological Environ Monitoring Program Manual |
| ML20215L711 | 31 May 1987 | TMI Action - NUREG-0737 (11.D.1) Relief & Safety Valve Testing Rancho Seco,Unit 1, Informal Technical Evaluation Rept |
| ML20247F487 | 24 March 1987 | Transcript of 870324 Investigative Interview W/Rp Oubre in Rancho Cordova,Ca |
| ML20212F250 | 3 March 1987 | Forwards Verification of RELAP5-FORCE Hydraulic Force Calculation Code & Other Addl Info Re NUREG-0737,Item II.D.1,per NRC 861216 Request.Results of as-built Reanalysis Scheduled for Apr 1987 |
| ML20214Q442 | 5 September 1986 | Responds to Violation & Deviation Noted in Insp Rept 50-312/86-21.Corrective Actions:Auxiliary Feedwater Flow Indicators Will Be Upgraded to Safety Grade Prior to Restart,Per NUREG-0737,Item II.E.1.2 |
| ML20206N596 | 7 August 1986 | Notice of Violation from Insp on 860602-0711 |
| ML20210T839 | 7 May 1986 | Partial Response to FOIA Request for NRC 1986 Draft Action Plan for Reevaluation of B&W Plant Safety & NRC Repts Responding to Review Items as Result of 851226 Accident. Forwards Documents Listed in App a |
| ML20151Z287 | 29 January 1986 | Proposed Tech Spec Changes,Correcting Typos,Inadvertent Omissions & Grammatical Inconsistencies Originating from Previous Amends |
| ML20137L591 | 10 September 1985 | Response Opposing Jf Doherty 850611 Petition for Show Cause Order Requesting NRC to Institute Consolidated Proceeding Per 10CFR2.202.Certificate of Svc Encl |
| NRC Generic Letter 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
| ML20126C851 | 31 March 1980 | Safety Evaluation Supporting Amend 29,to License DPR-54 |
| NRC Generic Letter 1979-56 | 30 October 1979 | NRC Generic Letter 1979-056: Discussion of Lessons Learned Short Term Requirements |
| NRC Generic Letter 1979-50 | 10 October 1979 | NRC Generic Letter 1979-050: Transmittal of Document on the Basis for Emergency Actions Levels |
| ML093421045 | 9 August 1979 | Requests Utils Provide Description of Methods to Verify That Offsite Power Sys & Onsite Distribution Sys Are Capable of Automatically Restarting & Maintaining All Required Safety Loads in Event of LOCA or Loss of Onsite or Offsite Power |