ML20127M034
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Category:CONTRACTED REPORT - RTA
MONTHYEARML19332B6141989-10-31031 October 1989
[Table view]Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept ML20246B8151989-04-30030 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML20214Q8981987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept ML20214R0681987-04-30030 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 ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog ML17334B0721987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. ML20214R7431987-03-31031 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 ML20214R8651987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final Informal Rept ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20214R2161987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Haddam Neck & Millstone 1,2 &3, Informal Rept ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20210Q4481987-01-0909 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 ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML20207S5201986-11-30030 November 1986 Technical Evaluation Rept for River Bend Station on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc) ML20207S5231986-11-30030 November 1986 Technical Evaluation Rept for Gessar II Responses for Resolution of Humphrey Safety Concerns (Hsc) Re Mark III Containment Sys ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20211E9641986-10-31031 October 1986 Rev 3 to Conformance to Generic Ltr 83-28,Item 3.1.3 & 3.2.3,Braidwood Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station ML20215M8911986-10-20020 October 1986 Technical Assistance for Preservice Insp, Monthly Ltr Rept for Aug & Sept 1986 ML20215K4591986-09-30030 September 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Waterford Unit 3,Washington Nuclear Plant Units 1 & 3 ML20207S5071986-09-30030 September 1986 Technical Evaluation Rept for Grand Gulf Nuclear Station on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc) ML20245A4481986-09-30030 September 1986 Revised Draft Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1 ML20206H1441986-09-0202 September 1986 Direct Containment Heating Analysis W/Contain Computer Code, Ltr Rept ML20204G1921986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components),South Texas 1 & 2,Virgil C Summer 1,Trojan & Yankee Rowe ML20205E3711986-07-31031 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 ML20205E3991986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) Ginna,Haddam Neck,Millstone 3 & Harris 1 ML20212M2761986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Arkansas 1 & 2,Calvert Cliffs 1 & 2,Crystal River 3 & Davis-Besse 1 ML20244E1901986-07-31031 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 ML20207F1591986-07-0808 July 1986 Energy Technology Engineering Ctr Technical Assistance to NRC for Preservice Insp, Monthly Ltr Rept for June 1986 1989-04-30 Category:QUICK LOOK MONTHYEARML19332B6141989-10-31031 October 1989
[Table view]Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept ML20246B8151989-04-30030 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML20214Q8981987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept ML20214R0681987-04-30030 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 ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog ML17334B0721987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. ML20214R7431987-03-31031 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 ML20214R8651987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final Informal Rept ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20214R2161987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Haddam Neck & Millstone 1,2 &3, Informal Rept ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20210Q4481987-01-0909 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 ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML20207S5201986-11-30030 November 1986 Technical Evaluation Rept for River Bend Station on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc) ML20207S5231986-11-30030 November 1986 Technical Evaluation Rept for Gessar II Responses for Resolution of Humphrey Safety Concerns (Hsc) Re Mark III Containment Sys ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20211E9641986-10-31031 October 1986 Rev 3 to Conformance to Generic Ltr 83-28,Item 3.1.3 & 3.2.3,Braidwood Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station ML20215M8911986-10-20020 October 1986 Technical Assistance for Preservice Insp, Monthly Ltr Rept for Aug & Sept 1986 ML20215K4591986-09-30030 September 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Waterford Unit 3,Washington Nuclear Plant Units 1 & 3 ML20207S5071986-09-30030 September 1986 Technical Evaluation Rept for Grand Gulf Nuclear Station on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc) ML20245A4481986-09-30030 September 1986 Revised Draft Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1 ML20206H1441986-09-0202 September 1986 Direct Containment Heating Analysis W/Contain Computer Code, Ltr Rept ML20204G1921986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components),South Texas 1 & 2,Virgil C Summer 1,Trojan & Yankee Rowe ML20205E3711986-07-31031 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 ML20205E3991986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) Ginna,Haddam Neck,Millstone 3 & Harris 1 ML20212M2761986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Arkansas 1 & 2,Calvert Cliffs 1 & 2,Crystal River 3 & Davis-Besse 1 ML20244E1901986-07-31031 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 ML20207F1591986-07-0808 July 1986 Energy Technology Engineering Ctr Technical Assistance to NRC for Preservice Insp, Monthly Ltr Rept for June 1986 1989-04-30 Category:ETC. (PERIODIC MONTHYEARML19332B6141989-10-31031 October 1989
[Table view]Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept ML20246B8151989-04-30030 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML20214Q8981987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept ML20214R0681987-04-30030 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 ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog ML17334B0721987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. ML20214R7431987-03-31031 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 ML20214R8651987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final Informal Rept ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20214R2161987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Haddam Neck & Millstone 1,2 &3, Informal Rept ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20210Q4481987-01-0909 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 ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML20207S5201986-11-30030 November 1986 Technical Evaluation Rept for River Bend Station on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc) ML20207S5231986-11-30030 November 1986 Technical Evaluation Rept for Gessar II Responses for Resolution of Humphrey Safety Concerns (Hsc) Re Mark III Containment Sys ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20211E9641986-10-31031 October 1986 Rev 3 to Conformance to Generic Ltr 83-28,Item 3.1.3 & 3.2.3,Braidwood Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station ML20215M8911986-10-20020 October 1986 Technical Assistance for Preservice Insp, Monthly Ltr Rept for Aug & Sept 1986 ML20215K4591986-09-30030 September 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Waterford Unit 3,Washington Nuclear Plant Units 1 & 3 ML20207S5071986-09-30030 September 1986 Technical Evaluation Rept for Grand Gulf Nuclear Station on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc) ML20245A4481986-09-30030 September 1986 Revised Draft Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1 ML20206H1441986-09-0202 September 1986 Direct Containment Heating Analysis W/Contain Computer Code, Ltr Rept ML20204G1921986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components),South Texas 1 & 2,Virgil C Summer 1,Trojan & Yankee Rowe ML20205E3711986-07-31031 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 ML20205E3991986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) Ginna,Haddam Neck,Millstone 3 & Harris 1 ML20212M2761986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Arkansas 1 & 2,Calvert Cliffs 1 & 2,Crystal River 3 & Davis-Besse 1 ML20244E1901986-07-31031 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 ML20207F1591986-07-0808 July 1986 Energy Technology Engineering Ctr Technical Assistance to NRC for Preservice Insp, Monthly Ltr Rept for June 1986 1989-04-30 Category:TEXT-PROCUREMENT & CONTRACTS MONTHYEARML19332B6141989-10-31031 October 1989
[Table view]Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept ML20248E2191989-08-16016 August 1989 Mod 16,reflecting Return of Equipment to Tva,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20248E2121989-08-16016 August 1989 Notification of Contract Execution,Mod 16,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20247R3851989-05-16016 May 1989 Notification of Contract Execution,Mod 15,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn,For Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20247R3941989-05-16016 May 1989 Mod 15,extending Period of Performance,Providing Addl Work Re Training for NRC Inspectors & Supervisors,Changing NRC Project Officer & Adding TVA Project Manager & Increasing Contract Ceiling & Funding to Use of TVA Reactor.. ML20246B8151989-04-30030 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20155B7391988-06-0101 June 1988 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Telephone Co ML20155B7531988-06-0101 June 1988 Corrected Mod 1,restoring Funds That Was Deobligated & Providing Final Increment of Funding to Contract,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee, Pilgrim & Seabrook Resident Sites ML20150D9001988-03-17017 March 1988 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Telephone Co ML20150D9091988-03-17017 March 1988 Mod 1,deobligating Funds from Total Obligated Amount of Contract & to Correct FIN Number,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML20149F1311988-01-11011 January 1988 Notification of Contract Execution: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee & Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20149F1691988-01-11011 January 1988 Contract: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20236T7371987-11-24024 November 1987 Notification of Contract Execution,Mod 7,to Dresden & Perry Simulator. Contractor:Ge ML20236T7461987-11-24024 November 1987 Mod 7,extending Period of Performance Through 880930,adding Addl GE Simulator to Contract & Scheduling Four Simulator Courses Through FY88,to Dresden & Perry Simulator ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML20236P2051987-08-10010 August 1987 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Main Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Bell Telephone Co ML20236P2181987-08-10010 August 1987 Mod 1,increasing Total Amount of Contract,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Main Yankee, Pilgrim & Seabrook Resident Sites ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML20214R1561987-05-29029 May 1987 Mod 12,providing Incremental Funds & Increasing Ceiling,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20214R1481987-05-29029 May 1987 Notification of Contract Execution,Mod 12,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML20214R0681987-04-30030 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 ML20214Q8981987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept ML20206S7131987-04-0808 April 1987 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Bell Telephone Co ML20206S7871987-04-0808 April 1987 Mod 1,changing Billing Address as Result of NRC Reorganization,To Local Telephone Svc for Yankee Rowe, Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog ML20206G0811987-04-0808 April 1987 Notification of Contract Execution,Mod 6,to Dresden & Perry Simulator. Contractor:Ge ML20206G6381987-04-0808 April 1987 Mod 11,recognizing Administrative Changes Due to NRC Reorganization,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20206G5861987-04-0808 April 1987 Notification of Contract Execution,Mod 11,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Brown Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20206G2681987-04-0808 April 1987 Mod 6,changing Project Officer Address Due to NRC Reorganization,To Dresden & Perry Simulator ML17334B0721987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. ML20214R2161987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Haddam Neck & Millstone 1,2 &3, Informal Rept ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20214R8651987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final Informal Rept ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 1989-08-16 |
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.e I MONTHLY HIGHLIGHTS FOR JULY 1983
" Safety Evaluation of Core-Melt Accidents:
CESSAR-FDA, Westinghouse Standard Plant-FDA" (FIN M BNL Principal Investigator: W. T. Pratt (FTS 666-2630)
NRC Technical Monitor: J. F. Meyer, Reactor Systems Branch NRC Project Manager: J. F. Meyer, Reactor Systems Branch 1.-PROGRESS TO DATE:
Work on this contract continues at a relatively low level of effort.
- 2. PROBLEMS OR DELAYS:
None.
- 3. MILESTONES:
No problem areas.
4 NEXT REPORTING PERIOD:
Work will continue.
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