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Category:CONTRACTED REPORT - RTA
MONTHYEARML20098C4961995-07-0707 July 1995 Technical Evaluation Rept on IPE Front End Analysis, for Plant Units 1 & 2 ML20097J7621995-07-0505 July 1995 Technical Evaluation Rept on IPE Front End Analysis L-95-004, TER on Third 10-Yr ISI Program Plan:Commonwealth Edison Co, Quad Cities Station,Units 1 & 21995-06-30030 June 1995 TER on Third 10-Yr ISI Program Plan:Commonwealth Edison Co, Quad Cities Station,Units 1 & 2 ML20097J7661995-06-30030 June 1995 Final Rept, Technical Evaluation Rept on IPE Submittal Human Reliability Analysis, Rev 1 ML20097J7631995-06-27027 June 1995 Technical Evaluation Rept on IPE Back-End Analysis ML20098C5401994-09-30030 September 1994 Technical Evaluation Rept of Plant IPE Back-End Submittal, Revised Final Rept ML20098C5601994-08-31031 August 1994 Technical Evaluation Rept of IPE Submittal Assessment of Human Reliability Analysis,Final Rept, for Plant Units 1 & 2 ML20029C5161993-08-31031 August 1993 Technical Evaluation Rept Pump Valve IST Program Quad Cities Station Units 1 & 2. ML20044C1981993-01-31031 January 1993 High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide for QUAD-CITIES Station,Units 1 and 2 ML20065U4191990-12-31031 December 1990 Trip Rept:Onsite Analysis of Human Factors of Event at Quad -Cities 2 on 901027 (Hi-Hi IRM Scram from Hot Standby) ML20064A4631990-02-28028 February 1990 Technical Evaluation Rept on Response from Comm Ed to Generic Ltr 88-01 Concerning Quad Cities Station,Unit 1 ML20064A4781990-02-28028 February 1990 Revised Final Technical Evaluation Rept on Response from Comm Ed to Generic Ltr 88-01 Concerning Quad Cities Station, Unit 2 ML19332B6141989-10-31031 October 1989 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 ML20151X3481988-03-31031 March 1988 Conformance to Reg Guide 1.97:Quad Cities 1 & 2 ML20237J3191987-08-31031 August 1987 Conformance to Reg Guide 1.97:Quad Cities-1 & -2, Interim 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 ML20216B9261987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Quad Cities 1 & 2, Informal Rept ML20214H1151986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Quad Cities Station Units 1 & 2, Supplementary Technical Evaluation Rept ML20141D2431985-09-30030 September 1985 Technical Evaluation Rept,Second Interval Inservice Insp Program for Quad Cities Nuclear Power Station,Units 1 & 2 ML20136G3401985-07-10010 July 1985 Review of Licensee & Applicant Responses to Generic Ltr 83-28,Item 1.2, 'Post-Trip Review:Data & Info Capabilities,' for Quad Cities Station,Units 1 & 2, Technical Evaluation Rept ML20134P9851985-06-30030 June 1985 Conformance to Generic Ltr 83-28 Items 3.1.3 & 3.2.3 for Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad-Cities Units 1 & 2 ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20127E3731985-03-15015 March 1985 Shutdown DHR Analysis,Quad Cities Case Study, Draft Rept ML20076F2331983-06-0101 June 1983 Control of Heavy Loads (C-10),Quad Cities Station Units 1 & 2, Technical Evaluation Rept ML20079Q7061983-05-18018 May 1983 Monitoring of Electric Power to Reactor Protection Sys for Quad Cities Nuclear Power Station,Units 1 & 2, Technical Evaluation Rept ML20079P5231983-02-0707 February 1983 Selected Operating Reactor Issues Program Ii,Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20076B6381982-09-27027 September 1982 ECCS Repts (F-47),TMI Action Plan Requirements,Quad Cities Units 1 & 2, Technical Evaluation Rept ML20083L7911982-09-17017 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20071K2771982-07-23023 July 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts, Technical Evaluation Rept ML19258A0701982-03-31031 March 1982 Degraded Grid Protection for Class IE Power Sys,Quad Cities Station,Units 1 & 2, Preliminary Informal Rept ML20054C3691982-03-31031 March 1982 Degraded Grid Protection for Class IE Power Sys,Quad Cities Station,Units 1 & 2, Informal Rept ML20041D6441982-02-28028 February 1982 Adequacy of Station Electrical Distribution Sys Voltages, Quad Cities Station,Units 1 & 2, Informal Rept,Revision 1 ML20040F9951981-10-23023 October 1981 Control of Heavy Loads, Technical Evaluation Rept ML20126M3641981-06-11011 June 1981 Equipment Environ Qualification,Quad Cities Unit 1, Final Technical Evaluation Rept ML20003D8531981-03-31031 March 1981 Safety Evaluation of Inservice Testing Program, Interim Rept ML19247E2021981-03-23023 March 1981 Adequacy of Station Electric Distribution Sys Voltages, Quad Cities - Units 1 & 2,Dockets 50-254 & 50-265, Informal Rept ML20004D9801981-01-31031 January 1981 Equipment Environ Qualification, Final Draft Technical Evaluation Rept ML20004D9811981-01-31031 January 1981 Equipment Environ Qualification, Final Draft Technical Evaluation Rept ML19341B0791980-12-31031 December 1980 Adequacy of Station Electric Distribution Sys Voltages, Quad Cities,Units 1 & 2. ML20002A7561980-10-27027 October 1980 Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Engineered Safety Features Reset Controls for Quad Cities 1 & 2. ML20008F2911980-06-30030 June 1980 Simulation of Quad Cites 1 Cycle 1 Operation W/Armp Code Sys. ML19270G8511979-04-12012 April 1979 Fire Protection in Operating Nuclear Power Stations, Quad-Cities Stations 1 & 2 SER Review. ML20084B6121972-06-22022 June 1972 Rept of Preliminary Investigation Failure of Hanger Bolts on Suppression Chamber Suction Header at Quad Cities Nuclear Station,Unit 2 ML20210A6331972-06-22022 June 1972 Draft Failure of Hanger Bolts on Suppression Chamber Suction Header at Quad Cities Nuclear Station Unit 2..., Preliminary Investigation Rept.Related Info Encl 1995-07-07
[Table view] Category:QUICK LOOK
MONTHYEARML20098C4961995-07-0707 July 1995 Technical Evaluation Rept on IPE Front End Analysis, for Plant Units 1 & 2 ML20097J7621995-07-0505 July 1995 Technical Evaluation Rept on IPE Front End Analysis L-95-004, TER on Third 10-Yr ISI Program Plan:Commonwealth Edison Co, Quad Cities Station,Units 1 & 21995-06-30030 June 1995 TER on Third 10-Yr ISI Program Plan:Commonwealth Edison Co, Quad Cities Station,Units 1 & 2 ML20097J7661995-06-30030 June 1995 Final Rept, Technical Evaluation Rept on IPE Submittal Human Reliability Analysis, Rev 1 ML20097J7631995-06-27027 June 1995 Technical Evaluation Rept on IPE Back-End Analysis ML20098C5401994-09-30030 September 1994 Technical Evaluation Rept of Plant IPE Back-End Submittal, Revised Final Rept ML20098C5601994-08-31031 August 1994 Technical Evaluation Rept of IPE Submittal Assessment of Human Reliability Analysis,Final Rept, for Plant Units 1 & 2 ML20029C5161993-08-31031 August 1993 Technical Evaluation Rept Pump Valve IST Program Quad Cities Station Units 1 & 2. ML20044C1981993-01-31031 January 1993 High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide for QUAD-CITIES Station,Units 1 and 2 ML20065U4191990-12-31031 December 1990 Trip Rept:Onsite Analysis of Human Factors of Event at Quad -Cities 2 on 901027 (Hi-Hi IRM Scram from Hot Standby) ML20064A4631990-02-28028 February 1990 Technical Evaluation Rept on Response from Comm Ed to Generic Ltr 88-01 Concerning Quad Cities Station,Unit 1 ML20064A4781990-02-28028 February 1990 Revised Final Technical Evaluation Rept on Response from Comm Ed to Generic Ltr 88-01 Concerning Quad Cities Station, Unit 2 ML19332B6141989-10-31031 October 1989 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 ML20151X3481988-03-31031 March 1988 Conformance to Reg Guide 1.97:Quad Cities 1 & 2 ML20237J3191987-08-31031 August 1987 Conformance to Reg Guide 1.97:Quad Cities-1 & -2, Interim 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 ML20216B9261987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Quad Cities 1 & 2, Informal Rept ML20214H1151986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Quad Cities Station Units 1 & 2, Supplementary Technical Evaluation Rept ML20141D2431985-09-30030 September 1985 Technical Evaluation Rept,Second Interval Inservice Insp Program for Quad Cities Nuclear Power Station,Units 1 & 2 ML20136G3401985-07-10010 July 1985 Review of Licensee & Applicant Responses to Generic Ltr 83-28,Item 1.2, 'Post-Trip Review:Data & Info Capabilities,' for Quad Cities Station,Units 1 & 2, Technical Evaluation Rept ML20134P9851985-06-30030 June 1985 Conformance to Generic Ltr 83-28 Items 3.1.3 & 3.2.3 for Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad-Cities Units 1 & 2 ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20127E3731985-03-15015 March 1985 Shutdown DHR Analysis,Quad Cities Case Study, Draft Rept ML20076F2331983-06-0101 June 1983 Control of Heavy Loads (C-10),Quad Cities Station Units 1 & 2, Technical Evaluation Rept ML20079Q7061983-05-18018 May 1983 Monitoring of Electric Power to Reactor Protection Sys for Quad Cities Nuclear Power Station,Units 1 & 2, Technical Evaluation Rept ML20079P5231983-02-0707 February 1983 Selected Operating Reactor Issues Program Ii,Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20076B6381982-09-27027 September 1982 ECCS Repts (F-47),TMI Action Plan Requirements,Quad Cities Units 1 & 2, Technical Evaluation Rept ML20083L7911982-09-17017 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20071K2771982-07-23023 July 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts, Technical Evaluation Rept ML19258A0701982-03-31031 March 1982 Degraded Grid Protection for Class IE Power Sys,Quad Cities Station,Units 1 & 2, Preliminary Informal Rept ML20054C3691982-03-31031 March 1982 Degraded Grid Protection for Class IE Power Sys,Quad Cities Station,Units 1 & 2, Informal Rept ML20041D6441982-02-28028 February 1982 Adequacy of Station Electrical Distribution Sys Voltages, Quad Cities Station,Units 1 & 2, Informal Rept,Revision 1 ML20040F9951981-10-23023 October 1981 Control of Heavy Loads, Technical Evaluation Rept ML20126M3641981-06-11011 June 1981 Equipment Environ Qualification,Quad Cities Unit 1, Final Technical Evaluation Rept ML20003D8531981-03-31031 March 1981 Safety Evaluation of Inservice Testing Program, Interim Rept ML19247E2021981-03-23023 March 1981 Adequacy of Station Electric Distribution Sys Voltages, Quad Cities - Units 1 & 2,Dockets 50-254 & 50-265, Informal Rept ML20004D9801981-01-31031 January 1981 Equipment Environ Qualification, Final Draft Technical Evaluation Rept ML20004D9811981-01-31031 January 1981 Equipment Environ Qualification, Final Draft Technical Evaluation Rept ML19341B0791980-12-31031 December 1980 Adequacy of Station Electric Distribution Sys Voltages, Quad Cities,Units 1 & 2. ML20002A7561980-10-27027 October 1980 Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Engineered Safety Features Reset Controls for Quad Cities 1 & 2. ML20008F2911980-06-30030 June 1980 Simulation of Quad Cites 1 Cycle 1 Operation W/Armp Code Sys. ML19270G8511979-04-12012 April 1979 Fire Protection in Operating Nuclear Power Stations, Quad-Cities Stations 1 & 2 SER Review. ML20084B6121972-06-22022 June 1972 Rept of Preliminary Investigation Failure of Hanger Bolts on Suppression Chamber Suction Header at Quad Cities Nuclear Station,Unit 2 ML20210A6331972-06-22022 June 1972 Draft Failure of Hanger Bolts on Suppression Chamber Suction Header at Quad Cities Nuclear Station Unit 2..., Preliminary Investigation Rept.Related Info Encl 1995-07-07
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20098C4961995-07-0707 July 1995 Technical Evaluation Rept on IPE Front End Analysis, for Plant Units 1 & 2 ML20097J7621995-07-0505 July 1995 Technical Evaluation Rept on IPE Front End Analysis L-95-004, TER on Third 10-Yr ISI Program Plan:Commonwealth Edison Co, Quad Cities Station,Units 1 & 21995-06-30030 June 1995 TER on Third 10-Yr ISI Program Plan:Commonwealth Edison Co, Quad Cities Station,Units 1 & 2 ML20097J7661995-06-30030 June 1995 Final Rept, Technical Evaluation Rept on IPE Submittal Human Reliability Analysis, Rev 1 ML20097J7631995-06-27027 June 1995 Technical Evaluation Rept on IPE Back-End Analysis ML20098C5401994-09-30030 September 1994 Technical Evaluation Rept of Plant IPE Back-End Submittal, Revised Final Rept ML20098C5601994-08-31031 August 1994 Technical Evaluation Rept of IPE Submittal Assessment of Human Reliability Analysis,Final Rept, for Plant Units 1 & 2 ML20029C5161993-08-31031 August 1993 Technical Evaluation Rept Pump Valve IST Program Quad Cities Station Units 1 & 2. ML20044C1981993-01-31031 January 1993 High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide for QUAD-CITIES Station,Units 1 and 2 ML20065U4191990-12-31031 December 1990 Trip Rept:Onsite Analysis of Human Factors of Event at Quad -Cities 2 on 901027 (Hi-Hi IRM Scram from Hot Standby) ML20064A4631990-02-28028 February 1990 Technical Evaluation Rept on Response from Comm Ed to Generic Ltr 88-01 Concerning Quad Cities Station,Unit 1 ML20064A4781990-02-28028 February 1990 Revised Final Technical Evaluation Rept on Response from Comm Ed to Generic Ltr 88-01 Concerning Quad Cities Station, Unit 2 ML19332B6141989-10-31031 October 1989 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 ML20151X3481988-03-31031 March 1988 Conformance to Reg Guide 1.97:Quad Cities 1 & 2 ML20237J3191987-08-31031 August 1987 Conformance to Reg Guide 1.97:Quad Cities-1 & -2, Interim 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 ML20216B9261987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Quad Cities 1 & 2, Informal Rept ML20214H1151986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Quad Cities Station Units 1 & 2, Supplementary Technical Evaluation Rept ML20141D2431985-09-30030 September 1985 Technical Evaluation Rept,Second Interval Inservice Insp Program for Quad Cities Nuclear Power Station,Units 1 & 2 ML20136G3401985-07-10010 July 1985 Review of Licensee & Applicant Responses to Generic Ltr 83-28,Item 1.2, 'Post-Trip Review:Data & Info Capabilities,' for Quad Cities Station,Units 1 & 2, Technical Evaluation Rept ML20134P9851985-06-30030 June 1985 Conformance to Generic Ltr 83-28 Items 3.1.3 & 3.2.3 for Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad-Cities Units 1 & 2 ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20127E3731985-03-15015 March 1985 Shutdown DHR Analysis,Quad Cities Case Study, Draft Rept ML20076F2331983-06-0101 June 1983 Control of Heavy Loads (C-10),Quad Cities Station Units 1 & 2, Technical Evaluation Rept ML20079Q7061983-05-18018 May 1983 Monitoring of Electric Power to Reactor Protection Sys for Quad Cities Nuclear Power Station,Units 1 & 2, Technical Evaluation Rept ML20079P5231983-02-0707 February 1983 Selected Operating Reactor Issues Program Ii,Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20076B6381982-09-27027 September 1982 ECCS Repts (F-47),TMI Action Plan Requirements,Quad Cities Units 1 & 2, Technical Evaluation Rept ML20083L7911982-09-17017 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20071K2771982-07-23023 July 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts, Technical Evaluation Rept ML19258A0701982-03-31031 March 1982 Degraded Grid Protection for Class IE Power Sys,Quad Cities Station,Units 1 & 2, Preliminary Informal Rept ML20054C3691982-03-31031 March 1982 Degraded Grid Protection for Class IE Power Sys,Quad Cities Station,Units 1 & 2, Informal Rept ML20041D6441982-02-28028 February 1982 Adequacy of Station Electrical Distribution Sys Voltages, Quad Cities Station,Units 1 & 2, Informal Rept,Revision 1 ML20040F9951981-10-23023 October 1981 Control of Heavy Loads, Technical Evaluation Rept ML20126M3641981-06-11011 June 1981 Equipment Environ Qualification,Quad Cities Unit 1, Final Technical Evaluation Rept ML20003D8531981-03-31031 March 1981 Safety Evaluation of Inservice Testing Program, Interim Rept ML19247E2021981-03-23023 March 1981 Adequacy of Station Electric Distribution Sys Voltages, Quad Cities - Units 1 & 2,Dockets 50-254 & 50-265, Informal Rept ML20004D9801981-01-31031 January 1981 Equipment Environ Qualification, Final Draft Technical Evaluation Rept ML20004D9811981-01-31031 January 1981 Equipment Environ Qualification, Final Draft Technical Evaluation Rept ML19341B0791980-12-31031 December 1980 Adequacy of Station Electric Distribution Sys Voltages, Quad Cities,Units 1 & 2. ML20002A7561980-10-27027 October 1980 Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Engineered Safety Features Reset Controls for Quad Cities 1 & 2. ML20008F2911980-06-30030 June 1980 Simulation of Quad Cites 1 Cycle 1 Operation W/Armp Code Sys. ML19270G8511979-04-12012 April 1979 Fire Protection in Operating Nuclear Power Stations, Quad-Cities Stations 1 & 2 SER Review. ML20084B6121972-06-22022 June 1972 Rept of Preliminary Investigation Failure of Hanger Bolts on Suppression Chamber Suction Header at Quad Cities Nuclear Station,Unit 2 ML20210A6331972-06-22022 June 1972 Draft Failure of Hanger Bolts on Suppression Chamber Suction Header at Quad Cities Nuclear Station Unit 2..., Preliminary Investigation Rept.Related Info Encl 1995-07-07
[Table view] Category:RESEARCH AND TECHNICAL ASSISTANCE REPORTS
MONTHYEARML19258A0701982-03-31031 March 1982 Degraded Grid Protection for Class IE Power Sys,Quad Cities Station,Units 1 & 2, Preliminary Informal Rept ML20054C3691982-03-31031 March 1982 Degraded Grid Protection for Class IE Power Sys,Quad Cities Station,Units 1 & 2, Informal Rept ML20041D6441982-02-28028 February 1982 Adequacy of Station Electrical Distribution Sys Voltages, Quad Cities Station,Units 1 & 2, Informal Rept,Revision 1 ML20003D8531981-03-31031 March 1981 Safety Evaluation of Inservice Testing Program, Interim Rept ML19247E2021981-03-23023 March 1981 Adequacy of Station Electric Distribution Sys Voltages, Quad Cities - Units 1 & 2,Dockets 50-254 & 50-265, Informal Rept ML19341B0791980-12-31031 December 1980 Adequacy of Station Electric Distribution Sys Voltages, Quad Cities,Units 1 & 2. ML20008F2911980-06-30030 June 1980 Simulation of Quad Cites 1 Cycle 1 Operation W/Armp Code Sys. ML19270G8511979-04-12012 April 1979 Fire Protection in Operating Nuclear Power Stations, Quad-Cities Stations 1 & 2 SER Review. 1982-03-31
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20098C4961995-07-0707 July 1995 Technical Evaluation Rept on IPE Front End Analysis, for Plant Units 1 & 2 ML20097J7621995-07-0505 July 1995 Technical Evaluation Rept on IPE Front End Analysis L-95-004, TER on Third 10-Yr ISI Program Plan:Commonwealth Edison Co, Quad Cities Station,Units 1 & 21995-06-30030 June 1995 TER on Third 10-Yr ISI Program Plan:Commonwealth Edison Co, Quad Cities Station,Units 1 & 2 ML20097J7661995-06-30030 June 1995 Final Rept, Technical Evaluation Rept on IPE Submittal Human Reliability Analysis, Rev 1 ML20097J7631995-06-27027 June 1995 Technical Evaluation Rept on IPE Back-End Analysis ML20098C5401994-09-30030 September 1994 Technical Evaluation Rept of Plant IPE Back-End Submittal, Revised Final Rept ML20098C5601994-08-31031 August 1994 Technical Evaluation Rept of IPE Submittal Assessment of Human Reliability Analysis,Final Rept, for Plant Units 1 & 2 ML20029C5161993-08-31031 August 1993 Technical Evaluation Rept Pump Valve IST Program Quad Cities Station Units 1 & 2. ML20044C1981993-01-31031 January 1993 High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide for QUAD-CITIES Station,Units 1 and 2 ML20065U4191990-12-31031 December 1990 Trip Rept:Onsite Analysis of Human Factors of Event at Quad -Cities 2 on 901027 (Hi-Hi IRM Scram from Hot Standby) ML20064A4631990-02-28028 February 1990 Technical Evaluation Rept on Response from Comm Ed to Generic Ltr 88-01 Concerning Quad Cities Station,Unit 1 ML20064A4781990-02-28028 February 1990 Revised Final Technical Evaluation Rept on Response from Comm Ed to Generic Ltr 88-01 Concerning Quad Cities Station, Unit 2 ML19332B6141989-10-31031 October 1989 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 ML20151X3481988-03-31031 March 1988 Conformance to Reg Guide 1.97:Quad Cities 1 & 2 ML20237J3191987-08-31031 August 1987 Conformance to Reg Guide 1.97:Quad Cities-1 & -2, Interim 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 ML20216B9261987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Quad Cities 1 & 2, Informal Rept ML20214H1151986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Quad Cities Station Units 1 & 2, Supplementary Technical Evaluation Rept ML20141D2431985-09-30030 September 1985 Technical Evaluation Rept,Second Interval Inservice Insp Program for Quad Cities Nuclear Power Station,Units 1 & 2 ML20136G3401985-07-10010 July 1985 Review of Licensee & Applicant Responses to Generic Ltr 83-28,Item 1.2, 'Post-Trip Review:Data & Info Capabilities,' for Quad Cities Station,Units 1 & 2, Technical Evaluation Rept ML20134P9851985-06-30030 June 1985 Conformance to Generic Ltr 83-28 Items 3.1.3 & 3.2.3 for Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad-Cities Units 1 & 2 ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20127E3731985-03-15015 March 1985 Shutdown DHR Analysis,Quad Cities Case Study, Draft Rept ML20076F2331983-06-0101 June 1983 Control of Heavy Loads (C-10),Quad Cities Station Units 1 & 2, Technical Evaluation Rept ML20079Q7061983-05-18018 May 1983 Monitoring of Electric Power to Reactor Protection Sys for Quad Cities Nuclear Power Station,Units 1 & 2, Technical Evaluation Rept ML20079P5231983-02-0707 February 1983 Selected Operating Reactor Issues Program Ii,Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20076B6381982-09-27027 September 1982 ECCS Repts (F-47),TMI Action Plan Requirements,Quad Cities Units 1 & 2, Technical Evaluation Rept ML20083L7911982-09-17017 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20071K2771982-07-23023 July 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts, Technical Evaluation Rept ML19258A0701982-03-31031 March 1982 Degraded Grid Protection for Class IE Power Sys,Quad Cities Station,Units 1 & 2, Preliminary Informal Rept ML20054C3691982-03-31031 March 1982 Degraded Grid Protection for Class IE Power Sys,Quad Cities Station,Units 1 & 2, Informal Rept ML20041D6441982-02-28028 February 1982 Adequacy of Station Electrical Distribution Sys Voltages, Quad Cities Station,Units 1 & 2, Informal Rept,Revision 1 ML20040F9951981-10-23023 October 1981 Control of Heavy Loads, Technical Evaluation Rept ML20126M3641981-06-11011 June 1981 Equipment Environ Qualification,Quad Cities Unit 1, Final Technical Evaluation Rept ML20003D8531981-03-31031 March 1981 Safety Evaluation of Inservice Testing Program, Interim Rept ML19247E2021981-03-23023 March 1981 Adequacy of Station Electric Distribution Sys Voltages, Quad Cities - Units 1 & 2,Dockets 50-254 & 50-265, Informal Rept ML20004D9801981-01-31031 January 1981 Equipment Environ Qualification, Final Draft Technical Evaluation Rept ML20004D9811981-01-31031 January 1981 Equipment Environ Qualification, Final Draft Technical Evaluation Rept ML19341B0791980-12-31031 December 1980 Adequacy of Station Electric Distribution Sys Voltages, Quad Cities,Units 1 & 2. ML20002A7561980-10-27027 October 1980 Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Engineered Safety Features Reset Controls for Quad Cities 1 & 2. ML20008F2911980-06-30030 June 1980 Simulation of Quad Cites 1 Cycle 1 Operation W/Armp Code Sys. ML19270G8511979-04-12012 April 1979 Fire Protection in Operating Nuclear Power Stations, Quad-Cities Stations 1 & 2 SER Review. ML20084B6121972-06-22022 June 1972 Rept of Preliminary Investigation Failure of Hanger Bolts on Suppression Chamber Suction Header at Quad Cities Nuclear Station,Unit 2 ML20210A6331972-06-22022 June 1972 Draft Failure of Hanger Bolts on Suppression Chamber Suction Header at Quad Cities Nuclear Station Unit 2..., Preliminary Investigation Rept.Related Info Encl 1995-07-07
[Table view] |
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ij? .y U.S.g$E under. Contract No. DE-AC07-761001570
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I d.. ,4 DEGRADED GRID PRO *'lCT10st FOR CLASS 1E POWEP SYSTEMS l .
QUAD CI!!E$ STATION, UNIT #105. 1 AND 2
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.i- Docket no. 50-254 and 50-265 g .
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March 1982 y% '
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',*' E8Mi Idaho, Inc. -
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AtSTRACT, -
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.- ' This EG4G Idaho, Inc. ' report reytews the fasce" ; tibility of the saf ety-bC . re14ttd electrical equipner,t,, at the Quad Cities Station, to a sustained
""h,- - . Qgeadation of the offsite power sources. ,, 3 __
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.* JThis report is suppited as part of the *$elpetec operating Reactor Isb Program fIII)" being conducted for tt. E5. Nuclear Regulatory Cp (i- etskton; Office of Seeleer Re6ctor Regulatten, Divisin of Licensing, by N'- EG04 Ida%. Tac., Reliability sad $tatistics Brr.h.
s 7 - J Hh U.S. nuclear Reputatory Coudssion funded the work mder Authortra-g*N e
ttoe.98A 30-19-01-06.
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'A ~ I ' DEEroCD GRIO PROTECT 10p FOR CLA'55.1E POWER SYSTDt5 c ..,.-
k.:,...s WAS CITIES STAtton, .$tti MGS.1 AND 3
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. ? . h ,. u .On June 3.'1977, [ht M C Tequested Comenwealth Edison (CE) to assess IM;N at' electrical oestpoent at the Quad P.C';?
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'9 'd(susestibility of the safethrtla$jtp)gradet nprei:tles toofa the suttained offsite selttge' "
en$tts energency power systant.. The 3 3p *(y,.w'gt if, ' .
1sti.str.'eentained three pas M be compared.s After. '
with'tiklen the current dreign of the plent lag the'corrent dttip to tee staff post-c,fe ' f ,.tFSS 'G Wes required te g'1therj'grop0Sd eDdificathms to satisfy the post-p Wi M W ad criteria.or,feraigh.an anel 1 t(substantfate that the er.isting (actifty design has eguivalekt:$3p4bi it es,.. ,e ,
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".M,.YR rest,anded 'tefthe W 34 'pr'oeletd tthpnJely 27, 1977.2 detailsCE proposed desig m
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?3uneW,1, Q,7, ? ,. ' .f.iCations en . % Drafte19thnical specifications were '
tied es Oct o- @
, 5jt desry 1,198t,ober ' ad replacff28,'19thsty s Theteiwere a submittalpodified of nsrchby a subet5.tal of 4,1982.
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abillity of the system modifications to protect the safety-related equipment
{p'.i from'a, sustained degradetion of the offsite , grid voltage are:
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L General Gettyn Critseien 17 ( D C.17) ' Electrical Power Systems,'
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of 10 CFR 90 >. .
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[, 2. IIIE Standard 279-1ST1,'
. nuclear Power Generatteg it$ tiers'.'gr Protection Systems for y - -
K i- 3. IEEE 5tandard 306-197 i Class 1E fower Systems for Nuclear Power
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syste.s and Ews-t (s0 m). y Ratings for Electrical Power te , ,,
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. This section prowb, in Subsection 3.1. a brief description of the
,3 C , SE $$ ting underval pr9tection at the Quad Cities Station; in Subsec-
- *, ' . $1em 3.Z, a descr let gf the licensee's proposed scheme for the second
? I 1 Nyal undervoltage protect %en; and, in $sbsection 3.3, a discussion of how p, ps systas meets the design base criteria. . ,
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,. .tue serpoltage relays t3 ese.n. 41wv c1Es 1E bus. They are arranged in a li ~% * ,.
r, L . " c.,rei two Nf two logic schk that tentes complete 1_oss of voltage. .The W their leste circuitry staFt the diesel generator, initiate loac-
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ed trip the incaming p lina. breaker.
&.y.% % Mesisting logic circuitry of the undervoltsge protection system disable the lead-shed featues e,4cs the diesel generators are sup-
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p'y p ,, free48814\).9n0%er $4ftfVects ofset a degraded of andereeltage geld relaps'eqindition,'.the to each of the a160V licensee has Class it proposed
% ; beses..VEach set will bp cgspeised ef tue. solid-state undervoltage relays
@. ~ that ' 99 m taherent ties delay of seven seconds. arranged in a two-out-of-
[ g ', two ' Nc2Hime atth essectated amails y relays,and a timer added to the
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- . 10gIC circuitry. .'like Seppe t of the Second-level protection jJ,f ,. , relays,W1 be 3800f f S with a 19ee de{ay of 5 minstas. Should the taro 4 m itepe relays re, main,tr for 5 sinates, orrif a toCA signal eccurs k,. 3 % der that $ ante per$ed. Wiesel is started and the undervoltage egetral rosa, the h ing line breakers isted te i:.y 6 98 bGi' ;breat '
dre .') sheddiag~
ta slesed when the voltage and hsed is Salt 42 tad frequency finally fromthethediesel dieselgenerator .
"are shtisfactery. De lesswef-voltg~
- relays function as before, GN' r0 h,3
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1e61h6dd%;SSb 3 ed Sp the 7 of the. diesel generator breaker.
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' PedpoC*J eboges te the Statlee's techn3 cal specifications, meding the L.+o# '$araefflasce reestrements, aliadsele Meits.for the setpoint and ties delay, and itsHttag monettiens for operat6es,for th b%?,9 'ama {t(PS;aere furnished by the liceasse.I c '.N y -.M-E ;e second-levet underboltage r .
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P MN#tstesslos. ftest[siesNtonEf'theSCstaffle'tteel tw uired
{k, Y ~het t S-secess mesiItage of protectten sA The letter stipelates other criteria that the undervoltage for the onsite power systes C
.3-y~bepresh)eet.
protect es seest'aset. . Each crftertes ~1s ' restated beten fallowed by a dis-i< cussist referdlas the Itcensee's aseglianci.with that criterion. .
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b;, J.u *The selection of ve.1tepe end. ttee Setpoints shall be deterr.ined
~
V y^ . 4 kW from an analysis o the es1tege requirements of. the safety-related A,e ,s . 4 3.ls&ds at all ansite syster ' distribution levels."
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- Mi'The licensee's proposed Setpoia"t of h840V at*the a160V bus is
%.,3 * *"J.?p6.05 of the noter assinal voltage rating of 4kV. This voltage p N , .. f5etpoin
'p? plated.g2was che$en Df ter.e system voltage
'd .+ The t%es deley alIows ' operator actionanalysis to improve was thecom-
, . -l e, +y ,,1g ,9, 1 ,,,gg,. The,tiae,# slay is defeated immediately Should a 6.'* *G q ' ~ g.:- *r - 1.0CA signal occur. . ~ -
'The voitage pr6teetten shall include co1oc(de'nce logic to pre- ,
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5.' < ,' Thereis*ae.laesce(ISteFeelayforhadervel'tegeprotection speeld en acejdent 41pai ha presort. .The Class it bus will A7..is.
M:,:L.' be ready fer wptfor te. #1esel-generater,pedct before the we ~$ c..< (Af 4 dieselIs up te speed A
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distereences frge Peasttag the enerailab11 tty'of the offsite t
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1 .ff '; . i 1 ' , Tha 4 6ce... ,n6ee's Scept$ed infataus tiet delay of 5.6 seconds is
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<emw aaneres or I ndicates the 3.P & 3 safegg-reh ,te8'e nipa 4;7 ^
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- setpoint and
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seats of IEEE Standard f76-19T1." ,
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f..!' The licensee has stated that the circuits associated with the I.[r -
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. undervoltage relays aset the, applicable reamirements of IEEE - '
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Standard 276-W11. " '
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- 6. "The Techatcal Specifications shall include'lietting conditions
- , for operations. Surveillance reevirements. trip setpoints with W 1* i .'~ ', - sinimum and assissa iteits. and allowable values fer the second- .
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The ItceRset*S preposal for technical specification changes includes all the required items, The. voltage setpoint, witn the
'f b.f ' maxioud allowab1h }1eit Jacluded, .is $917V. A high setpoint is i '-C needed to assure adequate voltages te all. Class' IE equipment.
. ;4, % NP/'"h;.The louest busjottage.avaig~ leTherefore to*$ht.un6ervoltage relays, as oetermined by'CE,?is 18407. .lf both uncervoltage T/Y1 . Q relay s,etpoints .drifte( ta the apper lialt, tpurious trips of the offsite source degito operatten af Ahe'undervottage reinys tould
,. v.p *(g,#, , , 'pg h .. occur. It is (p*,jkely that both setggists wouit drift to the
,b s W%h the proposed setpoint and
- '_ d, upper toleronces Itait cesgerrently.
are4cceptable.Therefore,(ag The Ita14 conditions for W 'j- operation, the serveillance requiredents.:the channel test 3tyP f p flf t
.gt d,: frequency and the calibration freeuency are included in the technical spec'figations,iand while apt is conformance with the y C sedel tachalent specifications, de',aset the criterie of the
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3% f +)' The second JRC staff, post}, ion requires"that '&e system design c.uto-4+ $cally prevent:1es6-shedflog of the amargen~cy buses wee t%e onsite The load-shedding must
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.,te reinstat.d are supplyti poserAR.411 me.c..maeu t.ke.t,uenced rs are trip,edleads.
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- " 1 T 3*M The itcassee has es#tftM.the Quad Cities Station to incorporate this W? .t i la the circutt essig lead-shed is' blocked by an auxiliary et the diesel gaaere.g. ner et ' it breaker.. - e rt.
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._ dird W. staff position rege' ires that certain test requeasents to the '.echnical specifications., These, teilts were to demonstrate g~ Y'. H-functitmaal operabilj yfant ?beependenpir of the onsite power sources
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The
., J kPe' are te staulata less of offsite(power, la enjunction sith a simulatedduring sh to be performed at b)est once per.18 ag(aths r',j 1,,b4 , .y - injection actest%s.stgaat and to siumletelaterruption and subse-T 9f ' reconnect 10s (ensite"g#mqr edigrees.' These tests verify the proper q ' rk , . . g et, ton of the load-shed systant,"the load-shed bypass idhan the emergency ep' . < gesqrators are ampplyfog poser to their respective buses, and that p;. ' :f,, As so adverse tateraction betpoem the assits and offsite power w T,, % v. -4~ 4 w x.y 3,
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b,3 "h, Tha testing pr. propose' d ,by the licentee comply with most of 3'~ g - positten. Leed.
- ing en the' trip of eff51te'powerris tested.
\ #. 3 109, este ttpe die 6411gener4 tor it- sepplying the safety buses,
,, 6' c ted. A slemlated lesi ef ,the' diesel generator and subsequent load-i% ey and'1oad-sequencing esce the diesel generator is b6ck on-line is (tesses. A less ~ef the diesel g'enerator prohtbits automatic restart-id,y"' c *
.ifhe load sequenter is esktrolled by a contact of -the diesel generator
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er, and therefore ky design .vtripping of the diesels penerator breaker ft [ reset the 16ad de,dding and.the_ toad sequencing circustry. The time d .',1;; .
. .1furetion of the test will verify that there is no interaction between the
, _ 1<^- pffafM and the onsite power sources and that the load-shed bypass circuit
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11.',YIK1'CM.1J1977, d 'Veltape Ratings for Elect. rte power Systems and Equip-
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