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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20206M286 | 31 March 1998 | Final Rept, Technical Evaluation Rept on 'Submittal-Only' Review of Individual Plant Exam of External Events at Fort Calhoun Station | Hot Short Safe Shutdown High winds Ultimate heat sink Fire Barrier Tornado Missile Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Tornado-Generated Missile Tornado Missile Protection Earthquake Failure to Scram |
| ML20202B389 | 15 September 1997 | Rev 1 to, Technical Evaluation of Duane Arnold Energy Ctr Analysis of Ampacity Loads for Fire Barriers Clad Power Cables | Fire Barrier |
| L-96-034, TER on Third 10-Yr Interval ISI Program Plan:Nppd Cns | 31 March 1997 | TER on Third 10-Yr Interval ISI Program Plan:Nppd Cns | Boric Acid Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Pressure boundary leak Through Wall Leak |
| ML20134D797 | 5 September 1996 | Technical Evaluation Rept on IPE Submittal Human Reliability Analysis, Final Rept | Internal Flooding Probabilistic Risk Assessment Severe Accident Management Guideline |
| ML20134D794 | 13 June 1996 | Technical Evaluation Rept on Individual Plant Examination Front End Analysis | Safe Shutdown Mission time Internal Flooding Probabilistic Risk Assessment Severe Accident Management Guideline Fuel cladding |
| ML20134D803 | 31 May 1996 | Technical Evaluation Rept on Individual Plant Examination Back-End Analysis | Mission time Enforcement Discretion Finite Element Analysis Hardened vent Backfit |
| ML20099L374 | 30 November 1995 | Technical Evaluation Rept on Third 10-Yr Interval ISI Program Plan:Omaha Public Power District Fort Calhoun Station,Unit 1 | Hydrostatic VT-2 Incorporated by reference |
| ML20149L654 | 31 August 1995 | Plant TER on IPE Back-End Submittal | Mission time Hardened vent |
| ML20149L649 | 31 August 1995 | Plant TER on IPE Front End Analysis | Mission time Internal Flooding Probabilistic Risk Assessment Squib Hardened vent Backfit |
| ML20094P188 | 31 May 1995 | TER, Duane Arnold Energy Ctr Pump & Valve Inservice Testing Program,Rev 13,Third 10-Yr Interval | Reactor Vessel Water Level Stroke time Excess Flow Check Valve |
| ML20097F727 | 31 May 1995 | Plant Technical Evaluation on IPE Submittal Human Reliability Analysis, Final Rept | Internal Flooding Job Performance Measure Hardened vent |
| ML20097F712 | 31 May 1995 | Plant Technical Evaluation Rept on IPE Back-End Submittal | Probabilistic Risk Assessment Hardened vent |
| ML20097F687 | 18 May 1995 | Plant Technical Evaluation Rept on IPE Front End Analysis | Mission time Internal Flooding Probabilistic Risk Assessment |
| ML20070M853 | 31 March 1994 | Technical Evaluation Rept,Pump & Valve IST Program,Fort Calhoun Station Unit 1 | Boric Acid Incorporated by reference Cold shutdown justification |
| ML20063E906 | 30 December 1993 | Parametric Study of Potential for BWR ECCS Blockage Due to LOCA Generated Debris, Vol 2,Parts 1 & 2 | |
| ML112380516 | 12 November 1993 | TER to Request for TS Change,Ielp,Cipc & Cbpc,Daec. | |
| ML20083A321 | 30 June 1993 | Evaluation of Utility Response to Suppl 1 to NRC Bulletin 90-01, Technical Evaluation Rept | |
| ML20106A936 | 30 September 1992 | Trip Rept:Onsite Analysis of Human Factors of Event at Fort Calhoun on 920703 (Loss of Instrument Inverter & Subsequent Loss of Coolant) | Shutdown Margin |
| ML20127F270 | 28 September 1992 | Technical Evaluation Rept Fort Calhoun Station Emergency Diesel Generating Max Temp Operating Limits, Interim Rept | |
| ML20118C095 | 1 August 1992 | Technical Evaluation of Duane Arnold Energy Ctr Emergency Svc Water | |
| ML20100Q286 | 30 September 1991 | Auxiliary Feedwater Sys Risk-Based Insp Guide for Fort Calhoun Nuclear Power Plant | Probabilistic Risk Assessment |
| ML20082G252 | 31 May 1991 | Technical Evaluation Rept,Cooper Nuclear Station,Station Blackout Evaluation, Final Rept | Safe Shutdown Reactor Vessel Water Level Battery sizing |
| ML20081E977 | 14 February 1991 | Review of Seismic Analysis for Generating In-Structure Spectra for Fort Calhoun Unit 1 Soil-Structure Interaction, Technical Evaluation Rept | |
| ML20247J910 | 30 June 1989 | Rev 1 to Technical Evaluation Rept TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing,Fort Calhoun | Loop seal Anticipated operational occurrence Safe Shutdown Earthquake Design basis earthquake |
| ML19327A676 | 31 May 1989 | Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Cooper, Technical Evaluation Rept | |
| ML20246B815 | 30 April 1989 | Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept | |
| ML20070Q778 | 31 December 1988 | Nuclear Power Plant Sys Sourcebook,Cooper | |
| ML20070Q521 | 31 December 1988 | Nuclear Power Plant Sys Sourcebook,Fort Calhoun | |
| ML20196D878 | 18 February 1988 | Technical Evaluation Rept of Dcrdr for Iowa Electric Light & Power Co Duane Arnold Energy Ctr | |
| ML20245D149 | 6 January 1988 | Technical Evaluation Rept of Dcrdr for Fort Calhoun Nuclear Station | |
| ML20245D144 | 6 January 1988 | Final Post-Implementation Audit Rept for Omaha Public Power District Fort Calhoun Station SPDS, Technical Evaluation Rept | |
| ML20151T583 | 9 November 1987 | Technical Evaluation Rept for Spds | |
| ML20215M088 | 31 May 1987 | Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Duane Arnold, Informal Rept | |
| ML20214R068 | 30 April 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept | |
| ML20214Q850 | 30 April 1987 | Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety Related Components:Fort Calhoun-1, Final Informal Rept | |
| ML20214R743 | 31 March 1987 | Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 | |
| ML20214R958 | 31 March 1987 | Technical Evaluation Rept TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing Fort Calhoun, Informal Rept | Loop seal |
| ML20214R538 | 31 March 1987 | Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Cooper, Informal Rept | |
| ML20210Q448 | 9 January 1987 | Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept | |
| ML20209C201 | 30 November 1986 | Conformance to Reg Guide 1.97,Fort Calhoun Station, Informal Rept | Safe Shutdown |
| ML20215N598 | 29 September 1986 | Technical Evaluation Rept of Dcrdr for Cooper Nuclear Station | Emergency Lighting |
| ML20244E190 | 31 July 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Fort Calhoun,Millstone Unit 2,Nine Mile Point Unit 2 & Fort St Vrain | Safe Shutdown |
| ML20205E371 | 31 July 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) Fort Calhoun,Millstone Unit 2,Nine Mile Point 2 & Fort St Vrain, Technical Evaluation Rept | Safe Shutdown |
| ML20212A824 | 24 July 1986 | Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Cooper Nuclear Station, Supplementary Technical Evaluation Rept | |
| ML20211P068 | 17 July 1986 | Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Duane Arnond Energy Ctr, Supplementary Technical Evaluation Rept | |
| ML20206A023 | 30 April 1986 | Preliminary Conformance to Reg Guide 1.97,Fort Calhoun Station, Informal Rept | Safe Shutdown |
| ML20214G408 | 31 March 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Selected GE BWR Plants (Cooper,Dresden 2 & 3,Fermi 2 & Fitzpatrick) | |
| ML20215M504 | 31 January 1986 | Conformance to Reg Guide 1.97,Cooper Nuclear Station | Squib Fuel cladding |
| ML20151Y280 | 30 September 1985 | Second Interval Inservice Insp Program,Cooper Nuclear Station, Technical Evaluation Rept | Hydrostatic Dissimilar Metal Weld |
| ML20138G890 | 28 August 1985 | Technical Evaluation of Dcrdr for Ft Calhoun Station |