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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
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Report No .3'h-EA.5810 _
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i[ Centunes Stagmen er Pretoes fleet l 6i' Selected Operating Reactors !ssues Program (III)
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p; W W tes Decimmenti Degreded Grid Protection for Class 1E Power Systems, Oued cities station, unit ups. I and 2 4'
<. y ag m Informal Report h
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- f. A. C. Uity I Does of Dessament i
March 1982 nsith NRC huftettual and IIRC ONtos er 00staten:
R. L . Prevatte, Division of systems Integration .
This document was prepared primenty for prehminary or internat use i nas not rec- ..
full review and approval Since there may be substanteve changes this document sho f 0 not be COnsedered final EG&G loaho. Inc Idaho Falls. Idaho 83a15 Prepared for the U.S. Nuclear Regulatory Commission Wash 6ngton, D.C.
Under DOE Contract No. DE-AC07 781D01570 NRC FIN No. A6429 l
INTERIM REPORT l
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'*f DERADED S10 MOTECTION FGt CLASS 1E POWER SYSTEMS WAS CIT'IES STATION, UNIT N05.1 ANO 2
- 1. Dodtet No. 50-254 ed 50-265 r
L March 1982 r
A. C. My g ., ,
- Relief 11 and Statistics tranch fastseer ~ Analysis Diviston l Idee. Inc.
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TAC Nos. 10047
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$$[O.N1 hts M . ha. repert'.ektems the susceptibtitty of the safety-Cities Station, to a sustained f( --
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CONTENTS
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l.0 INTit000CT10N ....................... ............. ........
h 2.0 DES IGN SASE CR I TER I A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J
, 3.0 EVALUATION .................................................. i 4
l- 3.1 tais ting thdervol tage Protection . . . . . . . . . . . . . . . . . . . . . . . . 2
? 3.2 Ihdi f ica t i ons . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3.3 Discussion ................................................ 2
}
E, 4.0 CONCLU5 100ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . s j 5.0 R EFER ENC ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3
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. MSMID stb MIOTECTIN FM C1. ASS 1E POWER SYSTEMS
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, .- - 1 94 CITitt $,$fMs. UNIT N05.1 AND 2 -
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. t Joe 19F7 he MC tad Cassenuselth Edison (t.E) to assess f*t
- 9e. tts (Y $3 electrical equipment at the Quad Cttles .te e Austelett .
egradstionoftheoffs1}esourceand laterettles effettb eps .
power systems. The letter een tret ,
trtWuh he current design of't5e plant we te h ' current design to the staff posi-tient. W . 5 edifications to satisfy the post-ttees and art e fyn19 aut ysis to substantiate that the existing
? fetility dt$ -
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% ,h;5- 5 , M ele, 4%'et v ::q::.4 $ 111t19s.
_ .W . W 9e, . 'eeMd7 27, 1977.2 CE proposed design
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E '1 ya additional details on the ell technical seecifications were stel% utre endiftee by a subsi 8
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. J4euery . ,g- a ~.esed by_a sesittel of March 4.1982.gtal of s: 2.4 *
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The.48 ., #fie,rts'S'et[iMe hlied in determining the ' accept-r ablility'ef. ' .
ediffsettees %e protect t>e safety-related equipment fH e i gustal thtles eF $ 3'effstte y'id voltage are:
- Electrical Power Systems,"
h F &_ ,F hetgs'Criterla for uselear Power P1 ants,"
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MI,;.8Crft'erla fp. Protection Systaes for 4 .ggens.' .
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3 % , & K M ass 1E Power systees for Nuclear Power
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- 4. t) iled 'in a ' letter sent to the licensee, g- ,
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.. S. '. 458 ' CW.1-19FF.?selt t4 s,.es,; see = <= =>. y natings for Electrical Power
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- 4. . p, Q*' Th testfeet. . 'fes..in,3ubsectics 3.1, a hrtef descristion of the
'pretekties at to Quod Cities Station; in Subsec-
. .; gist
) Den 3. a of the Ilconsee's proposed scheme for..-the second-t- 1evel tpderveitep protection; sed. 9n Subsection 3.3, a' discussion of how ~
the system asets he esipt base eriteris.
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l 3.1 Es11 tine taderveltase Protection. The present design utilizes
, tus edervesuge reiays a pecn sieuw usss IE bus. They are arranged in a te-out-of-tue lepic scheme that senses complete loss of voltage. The
, relays ed their egic circuitry start the diesel generator, initiate load-
, 'sheddleg, and trip the ipcoming line breaker.
, o. The entsting logic circuitry of the undervoltage protection system
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dass no4 disele the lohd-shed feature ence the diesel generators are suo-plying pener, to the Class 1E buses, e < ,
I, 3.2 thfificattees. 'To protect the Class IE safety-related equipment 7 from the en,C.e er a 0 aded grid condttien, the licensee has proposed adding another_ eet of whitage relays to each of the 4160V Class 1E
.' buses. Ea4 set will be casartsed of tuo solid-state undervoltage relays that have as inherent time delay of seven seconds, arranged in a two aut-of-tuo logic s with assectated aus111ery relays and a timer added to th(
unerveltage c circuitry, The setpoint of the second-level prots.ction
! relays ut11 be + 25 wi% a time delay of 5 minutes. Should the two g underveltagt relays r'e~ mein tripped for 5 minutes, or if a LOCA signal occurs e during het 5 minute perled, the diesel is started, and the undervoltage e condition is annectated in the centrol rpen, the incoming line breakers V
treeker is closed when the weltage ad(the frequency from the dieselare tripped, lea generater are satisfactory. The less-of-voltay relays function as before, with a setpoint of 3049V + K.
t t then the diesel generator is supplying its associated Class 1E bus, feed-Mieg is blocked by the "b" contact of the diesel generator breaker.
I Proposed deepes to the stattee's technical specifications, adding the
( serve 111eece requtrements, allenele 1toits for the setpoint and time delay,
. and limitfeg condittees for operatten for the second-level undervoltage monitors, were furnished by the licensee.7
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3.3 . The first position of the letC staff letter Irequired that a of undervettage protection for the onsite power system L, be providet. The letter stipulates' ether criteria that the undervoltage protection est meet. Each criterien is restated below followed by a dis-cession regardlag the licensee's compliance with that criterion.
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- 1. "The selection of voltage and time setpoints shall be determined free an analysis of the voltage requirements of the safety-related leeds et all ensite system distribution levels."
The licensee's proposed setpoint of 3840V at the 4160V bus is g5.01 of the stor nominal voltage rating of 4kV. This voltage setpelo was chosen after a system voltage analysis was com-pleted.j2 The time delay allows operator action to improve the voltage levels. The time delay is defeated ironediately should a LOCA signal occur.
- 2. "The voltage protection shall include coincidence logic to pre-clude spurious trips of the offsite power sources."
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i ic is arra !
i The thereby relay satislog'fying this,ged criterion. in a two-out-of-two logic scheme, !
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- The ttas delay selected shall be based on the following
- 3. !
, condittens!
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, s. 'The allegable ties delay, ing:1uding margin, shall'not exceed i
- the amateun time delay that ts assumed in the FSAR accident [
< ' enalysis.' ,
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.\ There is ee'ledged time 41ay for undervoltage protection toeld a accidset31 pal be present. The Class IE bus w111 t be fler treesttr to die' el-generator s power before the diesel ,ef,to Speed.
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V b. "The time 41ay shall minia.ze the offeet of short-duration i, . d distatecas free reductag the unavailability of the offsite,
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l The licensee's W,. stateus time delay of 5.6 seconds is j , to everride any short inconsequential grid r ,.
p' c. % altemele time eretten of a degraded voltage conottion 4 at all distribattee systes levels shall not result in f ail-
- . are of seputy systeen er components."
P' ~
is12 indicates t, ? Arovfes(the1 that to: 41 uf11 's met weltage cause analpallures my of the V .. safety-epicted t stece the nominal voltage setpoint av c ts.uftale me el tolerace of the equipment voltage 4- y rettag. 'e
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3 S 4. "The 4e1 'esetters dis 11 ateentically initiate 'the disconnec-f; .
tion 'ef ' ftpower peerees idlenover the voltage setpoint ed time,-del Mts base Does succeded."
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, A reetes of te licensee's proposal substantiates that this cri-j; '
terien is 'at; - .L-
- 1. "The wel '"jters $ ell be destped to satisfy tde require-
[?, , . seets of, n ,
279 1971.* -
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The 11cenece het sta'ted thet the circuits a'ssociated with the l
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- e. .1 meervelr5 ste e rd rWieys w i. meet the applicable, requirements of IEEE l {. -
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) 4. . "The Tec5tical W1ficelleet shall laciude Itotting conditions
..A**' , for operettens, servet19ance requirements, trip setpoints with etalmus ad esateue itse ts, and allowable values for the second-level voltegn protection monitors."
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I The liconeep's propetal fer technical spec!fication changes incloses all me reevired tems. The voltage tetpoint, with the esales 8110seble 11eit tetleded, is 1917V. A high setpoint is techd te 40eure edetuate volleges to all Class IE equipment.
The lesst, bus weltage ereigleTherefore,to the undervoltage relays, as if both undervoltage detemteed W W is 3M05.
relag setsethts hIftee to,Se upper listt apurlous trips of the offsste secree dye te operettee of uncuvoltage relays could ester. 1% te emitte.ly that 409 ints usuld drift to the 1tatt teneerrently. , the proposed setpoint and -
Gremess are eseeptele. 'listttag cenettiens for operetten. De serve 111esce trements, the changel test frequeecy eed to celterette are included in the tedeleel spectfitetfees, me 21 ast in conformance wIth the ebel teeMeal Specificettees, de seat the criteria of the stem's peettless.
The seemed MC sten posittee reguless that the systam design auto-satically leed-G eddtag of y suses once the onsite seurses are.eW ytag gener, to all leeds. The load-shedding must else be reteststos if me ses1to tredert are tripped.
< 1he Ilcessee has edifled the Quad Cttles Station to incorporate this feature to to circett ip. The lead-$ed is blocked by an auxiliary contact qf the diesel eter tirtett treaker.
The 9ffd W stgN pasItles regetres met cortain test req Jirements he added to to todetest gecificettees. These tests were to demonstrate to fell-festiesel $Ulty eed tedspeedence of the ensite power sources m 8 are te be et The te are te $helete'lem.least oncepesar of efft19e per Wtosenths duringwith can. function shutdown.
a simuisted se lejBetten eetgetteS Sigsel 4Bd D'Steelete laterruption and subse-goet recomettien er 105 peger segrep. '1hese tests vertfy the proper operetten ef.De >
ten, the 1eed-shed bypass em the energency diesel generators are , pmer *Ja.their respective buses, md that there is se therse les betwees De anstte and offsite ruwer seertes.
The testieg pr6 preposed by thie Itcensee comply with most of Utts positten. Leed-GeSteg a te trip of effsite power is tested.
Leed-enguaneteg, seen 96 mesel generator is supplying the safety buses, is tested. A.$tes18ted iges of tes diesel generator and subsequent load-shedflag 894 teed-teguengleg esce the diesel generator is back on-line is not teetee. A leeu of te Riesel generater prch161ts automatic restart-tag. The lead sequencer 13 osattelled by a contact of the diesel generator trader, ed temfere, by design, tripping of the diesel generator break e-will reset the 1eed shoestag ud the leed soevencing circuitry. The tiw diretten of the test ut11 verify that here is no interaction between the e#stte and the easite poner sources and that the load-shed bypass circuit is factioning properly.
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/ . 3 internetten ' by G, it has been determined that O . [p.f;. ' N W ge 4 L W staff position 1 All of the ed . .eriteria have been est. The setpoint f d);,e .j"f .
.It equipment from a sustained degraded "j :-O te genres, k.te/7I,M N: g, . ; ., y - .
<'9'nv M
eMfled to comply with staff posi-
%, 73(s . GBre#len of the offsite and onsite i .* , 1:b .Me yMc1
- .. A n ,; , ,1 '..>ft ,'e [, =.4 3 gg tiens
- 3. gquately test therequire-surve111mca system jf. . . .
1 40 tems and mentama limits for
- lFig. 31v- 4 % . ';'* W .pehfy state pos ition i .
' y,,k e : .,.. <. .- ^ .p technical specification ch'anges pr9peged technical specifica-l h[epy pkw ,. o. g te:4eincide with the completion of f ,$ h 'n. ' '
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..,ewsm smersency Power systems,-
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SC, " Response october 1, $o % vest for
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- p. SC, " Draft Techaleal 3 5 /.s tag tage Pro,tection,", october 28, 1981.
l 1 ye .w& :n ; g-yp}fMi i " Draft Technical Specifi-
- Deervel [~h7NWeth %, , January 6, 1982.
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I er 18.' . ten MC, 7,i,;,;ed Technical T-;. [p:t.r$N, i. ' ,eh . to lecen,d-level Undervoltage Relays,"
ja . .y. . . , . ' q,n%s$.g -
i.%fw~ g . crit m ,ower s,,ia.s .f,,,Dendi, 4
' Criteria f4r, Secteer Power Plants," to.10 CFR Part 50, 3 ing of PredecHem ad Utilization Facilities."
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- 9. 1M !?91W1.
- Criteria for Protection Systems for nuclear Peser)
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- 10. IEE Standard 308-1974 " Standard Criterta for Class IE Power Systems for Nuclear Power Gener,ating. Stations."
- 11. AltSI C04.1-1977, ' Voltage Ratings for Electric Power Systeins a..4 Equip-ment (40 NZ)." .
12, , " Adequacy of Station Electric Otstribution System Voltages. Quad
- ' Cities Station, Unit mes. I and 2,* EG44 Idaho, Inc. Informal Report (GG-EA-5323, A. Udy, March 1981.
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