Letter Sequence Request |
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Results
Other: ML20134A365, ML20135H559, ML20135H563, ML20137B356, ML20137K999, ML20137S363, ML20140H110, ML20206T734, ML20207R947, ML20212G867, ML20237G205, ML20237J227
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MONTHYEARML20074A7561983-04-27027 April 1983 Clarifies Proposed Changes in Undervoltage Protection & Reiterates Schedule for Implementation of Design Changes & Mods.Existing non-Class IE Undervoltage Relays Will Be Retained as Protection for 4,160-volt Buses Project stage: Request ML20135H5631985-08-31031 August 1985 Truth-Analysis/Action-Reaction Review of 480-Volt Essential Bus Tie Breaker Control Scheme, Final Rept Project stage: Other ML20212N6621985-08-31031 August 1985 Technical Evaluation Rept for Proposed Change to Operation of Ginna Fuel Pool Charcoal Filter Sys, Informal Rept Project stage: Request ML20137S3631985-09-13013 September 1985 Corrected Page 1 to Responding to 850614 Commitment to Perform Evaluation of Emergency Diesel Generator Control Logic Circuitry.Ltr Number Changed Project stage: Other IR 05000267/19850171985-09-13013 September 1985 Insp Rept 50-267/85-17 on 850617-0816.Violation Noted: Failure to Rept Nine Circulator Trips in 1984 & Seven Trips in 1985 & No Differential Helium Pressure Maintained When Pcrv Pressure Above 100 Psia Project stage: Request ML20135H5591985-09-13013 September 1985 Forwards Truth-Analysis/Action-Reaction Review of 480-Volt Essential Bus Tie Breaker Control Scheme, Final Rept & Provides Evaluation of Control Logic Design Project stage: Other ML20134A3651985-10-23023 October 1985 Amends Correction Portion of Item 2 (286G1A & 286G1B) in Util Re Results of Proto-Power Corp Analysis Concerning Emergency Electrical Power Sys Independence Project stage: Other ML20137B3561986-01-0303 January 1986 Informs That Design Changes Involving Emergency Diesel Generator (EDG) Control Logic Circuitry Implemented.No Single Failure Will Interfere W/Proper Operation of Redundant EDG Project stage: Other ML20137K9991986-01-14014 January 1986 Notifies That Design Changes in Emergency Diesel Generator Control Logic Circuitry Implemented,Per 850913 Commitment. Changes Assure That Failure Will Not Interfere W/Operation of Redundant Generator.Ltr Supersedes Project stage: Other ML20140H1101986-03-31031 March 1986 Submits Info Re Startup Check List for Automatic Operation of Emergency Diesel Generators,Sys Operating Procedure 92-04,in Response to NRC .Numbers Will Be Assigned to All Valves in Emergency Diesel Generator Rooms Project stage: Other ML17251A7911986-03-31031 March 1986 Reactor Containment Bldg Integrated Leakage Rate Test. Project stage: Request ML20206T7341986-07-0101 July 1986 Submits Summary & Schedule of Mods to Be Performed on Emergency Diesel Generator Control Circuitry in Response to 860515 & 21 Telcons.Mods Will Be Completed Prior to Startup from Current Equipment Qualification Outage Project stage: Other ML20213G5811986-08-0707 August 1986 Draft Review of Fort St Vrain Onsite AC 'Standby' Power Sys W/Regards to Compliance to Single Failure Criterion & Ser Project stage: Draft Other ML20212N6571986-08-19019 August 1986 Forwards EGG-PHY-7350, Technical Evaluation Rept for Proposed Change to Operation of Ginna Fuel Pool Charcoal Filter Sys, Per FIN D-6023, Review of Plant-Specific Licensing Actions for Operating Reactor Issues, Task 4-5 Project stage: Request ML20213G5641986-11-12012 November 1986 Forwards Onsite Class 1E Power Sys Design Features Review Status Rept Based on FSAR & NRC 860814 Meeting W/Licensee & Inel Draft Review of Fort St Vrain Onsite AC 'Standby' Power.... Resolution to Problems Requested Before Restart ML20212D8641986-12-24024 December 1986 Summary of 861209 Meeting W/Util Re Plant Emergency Electrical Power Sys.Fsar Commitment Re Emergency Diesel Generators revised.Marked-up Draft Rept Re Ac Standby Power Sys Encl ML20212G8671987-01-0909 January 1987 Forwards Rev a to EE-92-0008, Engineering Evaluation of Load Shedding,Load Auto Start Prohibit,Load Sequencing,Bus Tie Breaker Alignment & Generator Breaker Closing Portions of Emergency Diesel Generator Control Circuitry Project stage: Other ML20207R9381987-03-0606 March 1987 Forwards Rev 1 to EGG-NTA-7456, Review of Fort St Vrain Onsite AC `Standby' Power Sys Re Compliance to Single Failure Criterion & Ser Project stage: Approval ML20207R9471987-03-0606 March 1987 Rev 1 to Review of Fort St Vrain Onsite AC `Standby' Power Sys Re Compliance to Single Failure Criterion & Ser Project stage: Other ML20207S6271987-03-12012 March 1987 Summary of 870210 Meeting W/Util Re Emergency Diesel Generator Electrical Independence.List of Attendees Encl Project stage: Meeting ML20237G2051987-08-0606 August 1987 Concurs w/870601 Proposed Mods Re Adequacy of 1C Battery to Supply Dc Control Power to 480 Volt Ac Essential Bus 2. Submittal of Application for Amend to License Recommended Project stage: Other ML20237J2271987-08-10010 August 1987 Submits Application Fee for Re Proposed Design Changes to Supply Dc Control Power to 480 Volt Ac Essential Bus 2 & Associated Undervoltage Relays.Encl Fee Will Cover Upcoming Tech Spec Amend for Proposed Electrical Changes Project stage: Other 1986-03-31
[Table View] |
Similar Documents at Ginna |
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Category:CONTRACTED REPORT - RTA
MONTHYEARML17263B1041995-06-23023 June 1995 Technical Ltr Rept Re Third 10-yr Interval Inservice Insp Program Relief Request ML20091E2141991-10-30030 October 1991 Technical Evaluation Rept - Re Ginna Nuclear Power Plant Station Blackout Evaluation ML17262A6131991-09-30030 September 1991 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Ginna Nuclear Power Plant ML20084U9201991-01-31031 January 1991 Technical Evaluation Rept Pump & Valve Inservice Testing Program,Re Ginna Nuclear Power Plant ML20058C8581990-09-30030 September 1990 Conformance to Reg Guide 1.97:Ginna ML17261B1241990-04-30030 April 1990 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan:Re Ginna Nuclear Power Station. ML20236T9881987-10-31031 October 1987 a TRAC-PF1/MOD1 Analysis of the Ginna TUBE-RUPTURE Event on January 25,1982 ML20245C2561987-07-31031 July 1987 Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Ginna, Final Informal 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 ML17251A7301986-05-31031 May 1986 Assessment of Removal of Raised Floor & Mod to Fire Detection Zones for Plant Process Computer Sys (PPCS) Computer Room at Ginna Nuclear Plant, Informal Rept ML20205N8321986-05-0909 May 1986 Masonry Wall Design,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML17254A6371985-11-18018 November 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,Item 1.2,`Post-Trip Review:Data & Info Capabilities'For Robert Emmet Ginna Nuclear Plant,Unit 1, Technical Evaluation Rept ML20198A3351985-10-31031 October 1985 Conformance to Reg Guide 1.97,RE Ginna Nuclear Power Plant ML20210A1171985-10-31031 October 1985 Followup SEP Evaluation for Re Ginna Nuclear Power Plant ML20212N6621985-08-31031 August 1985 Technical Evaluation Rept for Proposed Change to Operation of Ginna Fuel Pool Charcoal Filter Sys, Informal Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. 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 ML20132C8201985-03-29029 March 1985 Tendon Evaluation,Re Ginna Nuclear Power Station, Technical Evaluation Rept ML20095J7001984-06-30030 June 1984 Generator Tube Rupture Event - Retran Calculations ML20082M9991983-12-0202 December 1983 Control of Heavy Loads C-10,RE Ginna Nuclear Power Plant, Technical Evaluation Rept ML20077K9861983-08-0202 August 1983 Review of Wind & Tornado Loading Responses,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML20077G0011983-07-29029 July 1983 Review of Licensee Response to Design Codes,Design Criteria & Loading Combinations,Ginna Nuclear Power Plant,Unit 1, Supplementary Technical Evaluation Rept ML20079Q7021983-03-0202 March 1983 Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20067D5321982-12-15015 December 1982 PWR Main Steam Line Break W/Continued Feedwater Addition, Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML20076B6291982-09-24024 September 1982 ECCS Repts (F-47) TMI Action Plan Requirements,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML17256B1961982-08-10010 August 1982 Control of Heavy Loads (C-10),Rochester Gas & Electric Corp,Re Ginna Nuclear Power Plant, Draft Technical Evaluation Rept ML17308A0711982-07-23023 July 1982 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication, (F-16,F-17),technical Evaluation Rept ML20027D7691982-07-15015 July 1982 Investigation of Failed Tubes from B Steam Generator of Re Ginna Nuclear Power Plant, SER App ML20063C5691982-06-23023 June 1982 Integrated Plant Safety Assessment,Ginna Plant,Sep, Technical Evaluation Rept of Draft NUREG-0821 ML20069C6041982-05-28028 May 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Technical Evaluation Rept ML20077J9301982-05-27027 May 1982 Design Codes,Design Criteria & Loading Combinations (SEP, III-7.B),RE Ginna Nuclear Power Plant, Final Technical Evaluation Rept ML17256A9751982-05-21021 May 1982 Improvements in Reactor Operator & Senior Reactor Operator Training & Requalification Programs for Re Ginna Nuclear Power Plant, Final Technical Evaluation Rept.Rept Addresses NUREG-0737,Items I.A.2.1 & II.B.4 ML20090B4781982-05-12012 May 1982 Ruptured Tube Analysis for Ginna, Technical Evaluation Rept ML17309A2701982-04-27027 April 1982 Hydrological Considerations, Technical Evaluation Rept for SEP Topics II-3.A,II-3.B,II-3.B.1,II-3.C & II-4.D ML17256A8081982-03-31031 March 1982 Structural Review of the Robert E. Ginna Nuclear Power Plant Under Combined Loads for the Systematic Evaluation Program ML17258A6101982-01-31031 January 1982 SEP Topic VI-4,Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation,Re Ginna Nuclear Power Plant, Informal Rept ML17309A2431982-01-31031 January 1982 to SEP Topic VI-4, Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation. ML17258A4021981-12-31031 December 1981 SEP Topic VII-2,ESF Sys Control Logic & Design,Ginna Nuclear Power Plant 1, Informal Rept ML20039G5011981-12-31031 December 1981 SEP Topic VII-2,ESF Sys Control Logic & Design,Ginna Nuclear Power Plant 1. ML20039A5551981-11-30030 November 1981 Electrical,Instrumentation & Control Sys Support for SEP, SEP Topic V-11.A,electrical,instrumentation & Control Features for Isolation of High & Low Pressure Sys ML17258A4281981-11-30030 November 1981 Review of Design & Operation of Ventilation Sys for SEP Plants Rochester Gas & Electric Co,Re Ginna Nuclear Power Plant, Revised Draft Technical Evaluation Rept ML17258A3571981-11-30030 November 1981 Final Evaluation of SEP Topic VI-7.C.1, Independence of Redundant Onsite Power Sys,Re Ginna Nuclear Station. ML20039A6881981-11-30030 November 1981 to SEP Topic VIII-4,Electric Penetrations of Reactor Containment,Re Ginna Nuclear Station, Informal Rept ML20039A6841981-11-30030 November 1981 SEP Topic VI-7.C.1,Independence of Redundant Onsite Power Sys,Re Ginna Nuclear Station, Informal Rept ML20039A4521981-11-30030 November 1981 Adequacy of Station Electric Distribution Sys Voltages, Palisades Plant, Informal Rept ML17258A2241981-09-30030 September 1981 SEP Topic VIII-4,Electrical Penetrations of Reactor Containment,Re Ginna Nuclear Station,Unit 1, Informal Rept ML17258A7031980-12-31031 December 1980 Seismic Review of the Robert E. Ginna Nuclear Power Plant as Part of the Systematic Evaluation Program ML17311A0071980-09-30030 September 1980 SEP Review of SEP Safety Topic VII-03,Associated W/Electrical,Instrumentation & Control Portions of Sys Required for Safe Shutdown of Ginna Nuclear Power Plant. ML17258A7001980-08-31031 August 1980 SEP Review of NRC Safety Topic III-1,Associated W/Electrical,Instrumentation & Control Portion of Classification of Structures Components & Sys for Ginna Nuclear Power Plant. ML17258A7011980-08-31031 August 1980 SEP Review of NRC Safety Topic VII-2,Associated W/Electrical,Instrumentation & Control Portions of Engineered Safety Feature Sys Control Logic & Design for Ginna Nuclear Power Plant. 1995-06-23
[Table view] Category:QUICK LOOK
MONTHYEARML17263B1041995-06-23023 June 1995 Technical Ltr Rept Re Third 10-yr Interval Inservice Insp Program Relief Request ML20091E2141991-10-30030 October 1991 Technical Evaluation Rept - Re Ginna Nuclear Power Plant Station Blackout Evaluation ML17262A6131991-09-30030 September 1991 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Ginna Nuclear Power Plant ML20084U9201991-01-31031 January 1991 Technical Evaluation Rept Pump & Valve Inservice Testing Program,Re Ginna Nuclear Power Plant ML20058C8581990-09-30030 September 1990 Conformance to Reg Guide 1.97:Ginna ML17261B1241990-04-30030 April 1990 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan:Re Ginna Nuclear Power Station. ML20236T9881987-10-31031 October 1987 a TRAC-PF1/MOD1 Analysis of the Ginna TUBE-RUPTURE Event on January 25,1982 ML20245C2561987-07-31031 July 1987 Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Ginna, Final Informal 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 ML17251A7301986-05-31031 May 1986 Assessment of Removal of Raised Floor & Mod to Fire Detection Zones for Plant Process Computer Sys (PPCS) Computer Room at Ginna Nuclear Plant, Informal Rept ML20205N8321986-05-0909 May 1986 Masonry Wall Design,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML17254A6371985-11-18018 November 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,Item 1.2,`Post-Trip Review:Data & Info Capabilities'For Robert Emmet Ginna Nuclear Plant,Unit 1, Technical Evaluation Rept ML20198A3351985-10-31031 October 1985 Conformance to Reg Guide 1.97,RE Ginna Nuclear Power Plant ML20210A1171985-10-31031 October 1985 Followup SEP Evaluation for Re Ginna Nuclear Power Plant ML20212N6621985-08-31031 August 1985 Technical Evaluation Rept for Proposed Change to Operation of Ginna Fuel Pool Charcoal Filter Sys, Informal Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. 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 ML20132C8201985-03-29029 March 1985 Tendon Evaluation,Re Ginna Nuclear Power Station, Technical Evaluation Rept ML20095J7001984-06-30030 June 1984 Generator Tube Rupture Event - Retran Calculations ML20082M9991983-12-0202 December 1983 Control of Heavy Loads C-10,RE Ginna Nuclear Power Plant, Technical Evaluation Rept ML20077K9861983-08-0202 August 1983 Review of Wind & Tornado Loading Responses,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML20077G0011983-07-29029 July 1983 Review of Licensee Response to Design Codes,Design Criteria & Loading Combinations,Ginna Nuclear Power Plant,Unit 1, Supplementary Technical Evaluation Rept ML20079Q7021983-03-0202 March 1983 Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20067D5321982-12-15015 December 1982 PWR Main Steam Line Break W/Continued Feedwater Addition, Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML20076B6291982-09-24024 September 1982 ECCS Repts (F-47) TMI Action Plan Requirements,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML17256B1961982-08-10010 August 1982 Control of Heavy Loads (C-10),Rochester Gas & Electric Corp,Re Ginna Nuclear Power Plant, Draft Technical Evaluation Rept ML17308A0711982-07-23023 July 1982 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication, (F-16,F-17),technical Evaluation Rept ML20027D7691982-07-15015 July 1982 Investigation of Failed Tubes from B Steam Generator of Re Ginna Nuclear Power Plant, SER App ML20063C5691982-06-23023 June 1982 Integrated Plant Safety Assessment,Ginna Plant,Sep, Technical Evaluation Rept of Draft NUREG-0821 ML20069C6041982-05-28028 May 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Technical Evaluation Rept ML20077J9301982-05-27027 May 1982 Design Codes,Design Criteria & Loading Combinations (SEP, III-7.B),RE Ginna Nuclear Power Plant, Final Technical Evaluation Rept ML17256A9751982-05-21021 May 1982 Improvements in Reactor Operator & Senior Reactor Operator Training & Requalification Programs for Re Ginna Nuclear Power Plant, Final Technical Evaluation Rept.Rept Addresses NUREG-0737,Items I.A.2.1 & II.B.4 ML20090B4781982-05-12012 May 1982 Ruptured Tube Analysis for Ginna, Technical Evaluation Rept ML17309A2701982-04-27027 April 1982 Hydrological Considerations, Technical Evaluation Rept for SEP Topics II-3.A,II-3.B,II-3.B.1,II-3.C & II-4.D ML17256A8081982-03-31031 March 1982 Structural Review of the Robert E. Ginna Nuclear Power Plant Under Combined Loads for the Systematic Evaluation Program ML17258A6101982-01-31031 January 1982 SEP Topic VI-4,Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation,Re Ginna Nuclear Power Plant, Informal Rept ML17309A2431982-01-31031 January 1982 to SEP Topic VI-4, Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation. ML17258A4021981-12-31031 December 1981 SEP Topic VII-2,ESF Sys Control Logic & Design,Ginna Nuclear Power Plant 1, Informal Rept ML20039G5011981-12-31031 December 1981 SEP Topic VII-2,ESF Sys Control Logic & Design,Ginna Nuclear Power Plant 1. ML20039A5551981-11-30030 November 1981 Electrical,Instrumentation & Control Sys Support for SEP, SEP Topic V-11.A,electrical,instrumentation & Control Features for Isolation of High & Low Pressure Sys ML17258A4281981-11-30030 November 1981 Review of Design & Operation of Ventilation Sys for SEP Plants Rochester Gas & Electric Co,Re Ginna Nuclear Power Plant, Revised Draft Technical Evaluation Rept ML17258A3571981-11-30030 November 1981 Final Evaluation of SEP Topic VI-7.C.1, Independence of Redundant Onsite Power Sys,Re Ginna Nuclear Station. ML20039A6881981-11-30030 November 1981 to SEP Topic VIII-4,Electric Penetrations of Reactor Containment,Re Ginna Nuclear Station, Informal Rept ML20039A6841981-11-30030 November 1981 SEP Topic VI-7.C.1,Independence of Redundant Onsite Power Sys,Re Ginna Nuclear Station, Informal Rept ML20039A4521981-11-30030 November 1981 Adequacy of Station Electric Distribution Sys Voltages, Palisades Plant, Informal Rept ML17258A2241981-09-30030 September 1981 SEP Topic VIII-4,Electrical Penetrations of Reactor Containment,Re Ginna Nuclear Station,Unit 1, Informal Rept ML17258A7031980-12-31031 December 1980 Seismic Review of the Robert E. Ginna Nuclear Power Plant as Part of the Systematic Evaluation Program ML17311A0071980-09-30030 September 1980 SEP Review of SEP Safety Topic VII-03,Associated W/Electrical,Instrumentation & Control Portions of Sys Required for Safe Shutdown of Ginna Nuclear Power Plant. ML17258A7001980-08-31031 August 1980 SEP Review of NRC Safety Topic III-1,Associated W/Electrical,Instrumentation & Control Portion of Classification of Structures Components & Sys for Ginna Nuclear Power Plant. ML17258A7011980-08-31031 August 1980 SEP Review of NRC Safety Topic VII-2,Associated W/Electrical,Instrumentation & Control Portions of Engineered Safety Feature Sys Control Logic & Design for Ginna Nuclear Power Plant. 1995-06-23
[Table view] Category:ETC. (PERIODIC
MONTHYEARML17263B1041995-06-23023 June 1995 Technical Ltr Rept Re Third 10-yr Interval Inservice Insp Program Relief Request ML20091E2141991-10-30030 October 1991 Technical Evaluation Rept - Re Ginna Nuclear Power Plant Station Blackout Evaluation ML17262A6131991-09-30030 September 1991 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Ginna Nuclear Power Plant ML20084U9201991-01-31031 January 1991 Technical Evaluation Rept Pump & Valve Inservice Testing Program,Re Ginna Nuclear Power Plant ML20058C8581990-09-30030 September 1990 Conformance to Reg Guide 1.97:Ginna ML17261B1241990-04-30030 April 1990 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan:Re Ginna Nuclear Power Station. ML20236T9881987-10-31031 October 1987 a TRAC-PF1/MOD1 Analysis of the Ginna TUBE-RUPTURE Event on January 25,1982 ML20245C2561987-07-31031 July 1987 Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Ginna, Final Informal 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 ML17251A7301986-05-31031 May 1986 Assessment of Removal of Raised Floor & Mod to Fire Detection Zones for Plant Process Computer Sys (PPCS) Computer Room at Ginna Nuclear Plant, Informal Rept ML20205N8321986-05-0909 May 1986 Masonry Wall Design,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML17254A6371985-11-18018 November 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,Item 1.2,`Post-Trip Review:Data & Info Capabilities'For Robert Emmet Ginna Nuclear Plant,Unit 1, Technical Evaluation Rept ML20198A3351985-10-31031 October 1985 Conformance to Reg Guide 1.97,RE Ginna Nuclear Power Plant ML20210A1171985-10-31031 October 1985 Followup SEP Evaluation for Re Ginna Nuclear Power Plant ML20212N6621985-08-31031 August 1985 Technical Evaluation Rept for Proposed Change to Operation of Ginna Fuel Pool Charcoal Filter Sys, Informal Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. 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 ML20132C8201985-03-29029 March 1985 Tendon Evaluation,Re Ginna Nuclear Power Station, Technical Evaluation Rept ML20095J7001984-06-30030 June 1984 Generator Tube Rupture Event - Retran Calculations ML20082M9991983-12-0202 December 1983 Control of Heavy Loads C-10,RE Ginna Nuclear Power Plant, Technical Evaluation Rept ML20077K9861983-08-0202 August 1983 Review of Wind & Tornado Loading Responses,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML20077G0011983-07-29029 July 1983 Review of Licensee Response to Design Codes,Design Criteria & Loading Combinations,Ginna Nuclear Power Plant,Unit 1, Supplementary Technical Evaluation Rept ML20079Q7021983-03-0202 March 1983 Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20067D5321982-12-15015 December 1982 PWR Main Steam Line Break W/Continued Feedwater Addition, Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML20076B6291982-09-24024 September 1982 ECCS Repts (F-47) TMI Action Plan Requirements,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML17256B1961982-08-10010 August 1982 Control of Heavy Loads (C-10),Rochester Gas & Electric Corp,Re Ginna Nuclear Power Plant, Draft Technical Evaluation Rept ML17308A0711982-07-23023 July 1982 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication, (F-16,F-17),technical Evaluation Rept ML20027D7691982-07-15015 July 1982 Investigation of Failed Tubes from B Steam Generator of Re Ginna Nuclear Power Plant, SER App ML20063C5691982-06-23023 June 1982 Integrated Plant Safety Assessment,Ginna Plant,Sep, Technical Evaluation Rept of Draft NUREG-0821 ML20069C6041982-05-28028 May 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Technical Evaluation Rept ML20077J9301982-05-27027 May 1982 Design Codes,Design Criteria & Loading Combinations (SEP, III-7.B),RE Ginna Nuclear Power Plant, Final Technical Evaluation Rept ML17256A9751982-05-21021 May 1982 Improvements in Reactor Operator & Senior Reactor Operator Training & Requalification Programs for Re Ginna Nuclear Power Plant, Final Technical Evaluation Rept.Rept Addresses NUREG-0737,Items I.A.2.1 & II.B.4 ML20090B4781982-05-12012 May 1982 Ruptured Tube Analysis for Ginna, Technical Evaluation Rept ML17309A2701982-04-27027 April 1982 Hydrological Considerations, Technical Evaluation Rept for SEP Topics II-3.A,II-3.B,II-3.B.1,II-3.C & II-4.D ML17256A8081982-03-31031 March 1982 Structural Review of the Robert E. Ginna Nuclear Power Plant Under Combined Loads for the Systematic Evaluation Program ML17258A6101982-01-31031 January 1982 SEP Topic VI-4,Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation,Re Ginna Nuclear Power Plant, Informal Rept ML17309A2431982-01-31031 January 1982 to SEP Topic VI-4, Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation. ML17258A4021981-12-31031 December 1981 SEP Topic VII-2,ESF Sys Control Logic & Design,Ginna Nuclear Power Plant 1, Informal Rept ML20039G5011981-12-31031 December 1981 SEP Topic VII-2,ESF Sys Control Logic & Design,Ginna Nuclear Power Plant 1. ML20039A5551981-11-30030 November 1981 Electrical,Instrumentation & Control Sys Support for SEP, SEP Topic V-11.A,electrical,instrumentation & Control Features for Isolation of High & Low Pressure Sys ML17258A4281981-11-30030 November 1981 Review of Design & Operation of Ventilation Sys for SEP Plants Rochester Gas & Electric Co,Re Ginna Nuclear Power Plant, Revised Draft Technical Evaluation Rept ML17258A3571981-11-30030 November 1981 Final Evaluation of SEP Topic VI-7.C.1, Independence of Redundant Onsite Power Sys,Re Ginna Nuclear Station. ML20039A6881981-11-30030 November 1981 to SEP Topic VIII-4,Electric Penetrations of Reactor Containment,Re Ginna Nuclear Station, Informal Rept ML20039A6841981-11-30030 November 1981 SEP Topic VI-7.C.1,Independence of Redundant Onsite Power Sys,Re Ginna Nuclear Station, Informal Rept ML20039A4521981-11-30030 November 1981 Adequacy of Station Electric Distribution Sys Voltages, Palisades Plant, Informal Rept ML17258A2241981-09-30030 September 1981 SEP Topic VIII-4,Electrical Penetrations of Reactor Containment,Re Ginna Nuclear Station,Unit 1, Informal Rept ML17258A7031980-12-31031 December 1980 Seismic Review of the Robert E. Ginna Nuclear Power Plant as Part of the Systematic Evaluation Program ML17311A0071980-09-30030 September 1980 SEP Review of SEP Safety Topic VII-03,Associated W/Electrical,Instrumentation & Control Portions of Sys Required for Safe Shutdown of Ginna Nuclear Power Plant. ML17258A7001980-08-31031 August 1980 SEP Review of NRC Safety Topic III-1,Associated W/Electrical,Instrumentation & Control Portion of Classification of Structures Components & Sys for Ginna Nuclear Power Plant. ML17258A7011980-08-31031 August 1980 SEP Review of NRC Safety Topic VII-2,Associated W/Electrical,Instrumentation & Control Portions of Engineered Safety Feature Sys Control Logic & Design for Ginna Nuclear Power Plant. 1995-06-23
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML17263B1041995-06-23023 June 1995 Technical Ltr Rept Re Third 10-yr Interval Inservice Insp Program Relief Request ML20091E2141991-10-30030 October 1991 Technical Evaluation Rept - Re Ginna Nuclear Power Plant Station Blackout Evaluation ML17262A6131991-09-30030 September 1991 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Ginna Nuclear Power Plant ML20084U9201991-01-31031 January 1991 Technical Evaluation Rept Pump & Valve Inservice Testing Program,Re Ginna Nuclear Power Plant ML20058C8581990-09-30030 September 1990 Conformance to Reg Guide 1.97:Ginna ML17261B1241990-04-30030 April 1990 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan:Re Ginna Nuclear Power Station. ML20236T9881987-10-31031 October 1987 a TRAC-PF1/MOD1 Analysis of the Ginna TUBE-RUPTURE Event on January 25,1982 ML20245C2561987-07-31031 July 1987 Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Ginna, Final Informal 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 ML17251A7301986-05-31031 May 1986 Assessment of Removal of Raised Floor & Mod to Fire Detection Zones for Plant Process Computer Sys (PPCS) Computer Room at Ginna Nuclear Plant, Informal Rept ML20205N8321986-05-0909 May 1986 Masonry Wall Design,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML17254A6371985-11-18018 November 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,Item 1.2,`Post-Trip Review:Data & Info Capabilities'For Robert Emmet Ginna Nuclear Plant,Unit 1, Technical Evaluation Rept ML20198A3351985-10-31031 October 1985 Conformance to Reg Guide 1.97,RE Ginna Nuclear Power Plant ML20210A1171985-10-31031 October 1985 Followup SEP Evaluation for Re Ginna Nuclear Power Plant ML20212N6621985-08-31031 August 1985 Technical Evaluation Rept for Proposed Change to Operation of Ginna Fuel Pool Charcoal Filter Sys, Informal Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. 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 ML20132C8201985-03-29029 March 1985 Tendon Evaluation,Re Ginna Nuclear Power Station, Technical Evaluation Rept ML20095J7001984-06-30030 June 1984 Generator Tube Rupture Event - Retran Calculations ML20082M9991983-12-0202 December 1983 Control of Heavy Loads C-10,RE Ginna Nuclear Power Plant, Technical Evaluation Rept ML20077K9861983-08-0202 August 1983 Review of Wind & Tornado Loading Responses,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML20077G0011983-07-29029 July 1983 Review of Licensee Response to Design Codes,Design Criteria & Loading Combinations,Ginna Nuclear Power Plant,Unit 1, Supplementary Technical Evaluation Rept ML20079Q7021983-03-0202 March 1983 Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20067D5321982-12-15015 December 1982 PWR Main Steam Line Break W/Continued Feedwater Addition, Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML20076B6291982-09-24024 September 1982 ECCS Repts (F-47) TMI Action Plan Requirements,Re Ginna Nuclear Power Plant, Technical Evaluation Rept ML17256B1961982-08-10010 August 1982 Control of Heavy Loads (C-10),Rochester Gas & Electric Corp,Re Ginna Nuclear Power Plant, Draft Technical Evaluation Rept ML17308A0711982-07-23023 July 1982 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication, (F-16,F-17),technical Evaluation Rept ML20027D7691982-07-15015 July 1982 Investigation of Failed Tubes from B Steam Generator of Re Ginna Nuclear Power Plant, SER App ML20063C5691982-06-23023 June 1982 Integrated Plant Safety Assessment,Ginna Plant,Sep, Technical Evaluation Rept of Draft NUREG-0821 ML20069C6041982-05-28028 May 1982 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Technical Evaluation Rept ML20077J9301982-05-27027 May 1982 Design Codes,Design Criteria & Loading Combinations (SEP, III-7.B),RE Ginna Nuclear Power Plant, Final Technical Evaluation Rept ML17256A9751982-05-21021 May 1982 Improvements in Reactor Operator & Senior Reactor Operator Training & Requalification Programs for Re Ginna Nuclear Power Plant, Final Technical Evaluation Rept.Rept Addresses NUREG-0737,Items I.A.2.1 & II.B.4 ML20090B4781982-05-12012 May 1982 Ruptured Tube Analysis for Ginna, Technical Evaluation Rept ML17309A2701982-04-27027 April 1982 Hydrological Considerations, Technical Evaluation Rept for SEP Topics II-3.A,II-3.B,II-3.B.1,II-3.C & II-4.D ML17256A8081982-03-31031 March 1982 Structural Review of the Robert E. Ginna Nuclear Power Plant Under Combined Loads for the Systematic Evaluation Program ML17258A6101982-01-31031 January 1982 SEP Topic VI-4,Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation,Re Ginna Nuclear Power Plant, Informal Rept ML17309A2431982-01-31031 January 1982 to SEP Topic VI-4, Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation. ML17258A4021981-12-31031 December 1981 SEP Topic VII-2,ESF Sys Control Logic & Design,Ginna Nuclear Power Plant 1, Informal Rept ML20039G5011981-12-31031 December 1981 SEP Topic VII-2,ESF Sys Control Logic & Design,Ginna Nuclear Power Plant 1. ML20039A5551981-11-30030 November 1981 Electrical,Instrumentation & Control Sys Support for SEP, SEP Topic V-11.A,electrical,instrumentation & Control Features for Isolation of High & Low Pressure Sys ML17258A4281981-11-30030 November 1981 Review of Design & Operation of Ventilation Sys for SEP Plants Rochester Gas & Electric Co,Re Ginna Nuclear Power Plant, Revised Draft Technical Evaluation Rept ML17258A3571981-11-30030 November 1981 Final Evaluation of SEP Topic VI-7.C.1, Independence of Redundant Onsite Power Sys,Re Ginna Nuclear Station. ML20039A6881981-11-30030 November 1981 to SEP Topic VIII-4,Electric Penetrations of Reactor Containment,Re Ginna Nuclear Station, Informal Rept ML20039A6841981-11-30030 November 1981 SEP Topic VI-7.C.1,Independence of Redundant Onsite Power Sys,Re Ginna Nuclear Station, Informal Rept ML20039A4521981-11-30030 November 1981 Adequacy of Station Electric Distribution Sys Voltages, Palisades Plant, Informal Rept ML17258A2241981-09-30030 September 1981 SEP Topic VIII-4,Electrical Penetrations of Reactor Containment,Re Ginna Nuclear Station,Unit 1, Informal Rept ML17258A7031980-12-31031 December 1980 Seismic Review of the Robert E. Ginna Nuclear Power Plant as Part of the Systematic Evaluation Program ML17311A0071980-09-30030 September 1980 SEP Review of SEP Safety Topic VII-03,Associated W/Electrical,Instrumentation & Control Portions of Sys Required for Safe Shutdown of Ginna Nuclear Power Plant. ML17258A7001980-08-31031 August 1980 SEP Review of NRC Safety Topic III-1,Associated W/Electrical,Instrumentation & Control Portion of Classification of Structures Components & Sys for Ginna Nuclear Power Plant. ML17258A7011980-08-31031 August 1980 SEP Review of NRC Safety Topic VII-2,Associated W/Electrical,Instrumentation & Control Portions of Engineered Safety Feature Sys Control Logic & Design for Ginna Nuclear Power Plant. 1995-06-23
[Table view] |
Text
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- 1 INFORMAL REPORT p-e y c:- i TECHNICAL EVALUATION REPORT FOR PROPOSED
/daho CHANGE TO OPERATION OF THE GINNA FUEL POOL U ~ N8flOD88-
. i CHARC0AL FILTER SYSTEM Engineering ;y ~
- . Laboratory
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OlSCLAIMER l
i This book was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Governmer.t nor any agency thereof,
! nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product or process disclosed, or represents that its use would I
not infnnge privately owned r,yhts. References herein to any specific comrnercial l
l product, process, or service by trade name, trademark, manufacturer, or otherwise,
- does not necessar'ly constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessanly state or reflect those of the United States
=
Government or ar.y agency thereof. ,
I l
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EGG-PHY-7350 i
TECHNICAL EVALUATI,0N REPORT for i
! PROPOSED CHANGE TO OPERATION OF THE GINNA FUEL POOL CHARC0AL FILTER SYSTEM DOCKET NO. 50-244 TAC NO. 59801 3 INEL Reviewers - S. W. Duce /J. W. Mandler
, NRC LEAD Reviewer - M. Fairtile l INEL PROGRAM Manager - C. L. Nalezny NRC FSV Project MANAGER - M. Fairtile
. NRC Program Manager - M. Carrington n
i Idaho National Engineering Laboratory EG&G Idaho, Inc.
August 1986 EG&G Idahr , Inc.
Idaho Falls, Idal,o 83415 i
i Prepared for the
- U.S. Nuclear Regulatory Commission Washington, D.C. 20555 l Under DOE ~ Contract No. DE-AC07-76ID01570 l
.- FIN No. D5023 i
I
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l ABSTRACT This report addresses EG&G Idaho's technical evaluation of proposed changes to Technical Specification 3.11 and 4.11 from Rochester Gas &
O. Electric Corporations R. E. Ginna Nuclear Power Plant. The specification change proposed not using the spent fuel pit charcoal adsorber system whenever irradiated fuel, moved in the fuel pit, was older than 60 days post-irradiation The conclusion is that the Technical Specification change would not involve a significant change in the type or magnitude of effluent releases from the fuel storage area at the R. E. Ginna facility.
'In addition the change involves no significant hazards considerations for the purposes of 10 CFR 100.
O O
I e
SUMMARY
On October 9,1985 Rochester Gas and Electric, licensee for the R. E.
Ginna Nuclear Plant, submitted a request for license amendment. This request addressed the frequency of use of the spent fuel pit charcoal adsorber system. This report discusses EG&G Idaho's evaluation of the propesal. The proposal was evaluated against applicable regulations (i.e., 10 CFR 100, 10 CFR 20, 10 CFR 50 Appendix I) as to the effect that the acceptance of the proposed amendment would have on the, licensees ability to meet the requirements of the regulations. Facility supplied information, FSAR drawings, and telephone conversations were used in the evaluation. Dose calculations were also performed,. The conclusion of EG&G Idaho's technical evaluation is that the Technical Specification change would not involve a significant change in the type or magnitude of effluent releases from the fuel storage area and that the change involves no significant hazards considerations for the purposes of 10 CFR 100.
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CONTENTS ..
Abetract. . . . . . . . . . . . . .,. . . . . . . . . . . . . ... . . . i S u ma ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i i Introduction. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
. Background. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -1 0
t i
Technical Evaluation. . . . . . . . . . . . . . . . . . . . . . . . . . 2 Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 1
I References. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 e
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1 TECHNICAL EVALUATION REPORT FOR PROPOSED CHANGE TO OPERATION OF THE GINNA
. FUEL POOL CHARCOAL FILTER SYSTEM
~
.. INTRODUCTION
.The purpose of this Technical Evaluation Report is to review and evaluate the proposed change to the Rochester Gas & Electric Corporation (RG&E) Ginna Station Technical Specifications 3.11 and 4.11[1] which raquire the use of the spent fuel pit charcoal adsorber system whenever irradiated fuel is being moved in the spent fuel storage pool.
l The evaluation considered the proposed change in view of the l requirements of 10 CFR 100.11, 10 CFR 20.106, 10 CFR 20 Appendix B l Table II,10 CFR 50 Appendix I, and the model Radiological Effluent
- Technical Specifications NUREG-0472.[2] Other documents used in the evaluation were a letter from D. Crutchfield (NRC) to J. Maier (RG&E) dated Sept. 24,1981;[33 a letter from D. Crutchfield (NRC) to J. Maier 1- (RG&E) dated March 3,1982;[4] a letter from G. Lear (NRC) to Sholly Coordinator dated March 31,1986;[5] RG&E's R. E. Ginna Nuclear Power
- Plant Updated FSAR Figure 9.4-2 Heating, Ventilating, and Air Conditioning
,- System - Auxiliary and Intermediate Buildings (supplied by M. Fairtile NRC); and RG&E's submittal for the proposed Technical Specification change. In addition telecons were held with license personnel, the NRC Project Manager, and EG&G Idaho personnel on July 9. 1986 and July 23,
! 1986.
4 I BACKGROUND The 2xisting Technical Specifications 3.11 and 4.11 require the use of j the spent fuel pit charcoal adsorber system whenever an irradiated fuel i assembly is being moved in the spent fuel storage pool. The objective of
! the specification is to limit radioiodine releases and subsequent doses in
! ,, the event an irradiated fuel assembly is significantly damaged while being moved in the spent fuel storage pool.
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The proposed change to Technical Specifications 3.11 and 4.11 would 4
change the required use of the spent fuel pit charcoal adsorber ta tho::e periods when the irradiated fuel being moved has decayed less than 60 days
~. since irradiation. A 10 CFR 50.91 review was performed by the NRC. Using 4 ..
the thyroid dose criteria of 10 CFR 100 for an accidental release, the NRC I performed a calculation to determine what the thyroid dose of'an individual would be in the event a 60 day post-irradiation fuel element failed and released the iodine inventory to the fuel pit. In a telecon facility personnel claimed that the calculation took no credit for any charcoal adsorber system, with the resultant dose being 0.2 rem. The NRC finding, stated in the G. Lear March 31, 1986 letter, was that the i proposed application for amendment involved no significant hazards f consideration.
Neither the NRC nor Franklin Research personnel in their review of the Radiological Effluent Technical Specifications (NUREG-0472) considered the spent fuel pit charcoal adsorber system as an effluent treatment system.
Instead, this charcoal adsorber system was considered as an internal
.' cleanup system.
TECHNICAL EVALUATION ,
- j. The evaluation of the proposed amendment reviewed the need for the spent fuel pit charcoal adsorber system to be in use to meet the.
~
requirements of 10 CFR 100, 10 CFR 20, 10 CFR 50 Appendix I, and
. NUREG-0472 for gaseous effluent treatment systems. In addition, an evaluation was made as to the need for this system to be in operation during.a' Three Mile Island type accident.
Physically the spent fuel pit charcoal adsorber system is located just upstream of the Auxiliary Building IC exhaust fan in the spent fuel storage pit area ventilation system. Its function is to remove radioiodine that may be released during irradiated fuel movement. A HEpA
] ,, filter system exists downstream of the exhaust fan and acts as the gaseous
{ effluent treatment system. ,
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s A dose calculation was made to determine what the 10 CFR 100 accident dose would be to a member of the public in the event a 60 day post-irradiation fuel bundle was damaged while being moved in the fuel storage pit. The assumptions used for this calculation and the intermediate calculations are shown in Table 1. The resultant infant thyroid dose due to a 2 hr release from the fuel storage pool was 2.09 rem. This value is in good agreement with a decay corrected dose of 1.94 rem for an unfiltered release calculated using the values reported in the Sept. 24, 1981 letter to J. Maier (RG&E). These values are larger than the 1
< 0.2 rem value calculated by the NRC and reported in the G. Lear March 31, 1986 letter. However, tbare is a question as to whether credit was taken for the charcoal filter in this calculation. If a charcoal 4
filter is asst.med in our calculations the resultant values of 0.209 and 0.194 rem,'are in good agreement with the < 0.2 rem value. Regardless of which value is correct, 2.09 rem, 1.94 rem, or < 0.2 rem, the result is 4
still the same; the resultant dose is not a significant fraction of the thyroid dose allowed by 10 CFR 100, t
Review of source term releases from other commercial nuclear generating facility fuel pool areas (i.e., NUREG/CR-2346, NUREG/CR-0715, NUREG/CR-1629, and NUREG/CR-1992) indicate that there are differences, but i
no more than approximately a factor of two between nonrefueling and refueling periods for unfiltered iodine release rates. Also the l pre-filtered release rates from fuel handling areas are typically less than three percent of the total plant release rate. This shows that l operations in the fuel storage pit can increase the iodine release rate, i
but by no more than a factor of two under normal conditions, and that l release rates from fuel handling areas are typically not a significant-fraction of total facility I-131 release rates.
Therefore, in facilities that have charcoal adsorber systems downstream of the fuel pit ventilation
- system the factor of two increase poses no significant problem as to
- i. meeting the 10 CFR 20 and 10 CPR 50 Appendix I requirenents. However, in
!> the Ginna system, where the charcoal adsorber system has always been used
.. when moving fuel in the fuel storage pit, not using this charcoal adsorber when moving fuel that is 60 days post-irradiation will probably cause i
facility iodine releases to increase. The magnitude of the increase is
unknown but, based on the source term information cited above, it will likely be within the factor of two observed at other facilities, and will probably not cause the total facility release rate to approach limits.
As the spent fuel pit charcoal adsorber system is used only as an intermediate cleanup system and is not required as the final gaseous effluent cleanup system, the requirements of the G!nna Technical Specifications do not directly apply. However, if it were deemed ,
necessary to have the system operating in the event normal gaseous
- adioiodine release rates were approaching release limits during periods when fuel older than 60 days po.. -irridation is being moved in the fuel pit, the system could be put in operation before limits are exceeded. In relation to the necessity to have the charcoal system operable during a TMI type accident, it would be helpful, but not required to have the system operating continuously. If it were deemed necessary to have the fuel pit charcoal adsorber system operating it can be put on line from the control room.
- CONCLUSION Taking into account the above discussion, a determination has been made that the spent fuel pit charcoal adsorber system is not required to be used wher irradiated fuel, which has an irradiation date that is 60 days or older, is being moved in the spent fuel storage pool. This change would not involve a significant change in the type or magnitude of e'/ fluent releases from the fuel storage area at the R. E. Ginna facility.
In addition the change involves no significant hazards consideration for the purposes of 10 CFR 10r.
e e
9 4
TA,BLE 1. 10 CFR 100 Accidental Dose Assumptions and Calculations Assumptions:
A) Iodine partition factor (water to air) 0.007 B) Iodine release from bundle to pool 0.1 C) Bundle inventory 4.23 E5 Ci at end of irradiation. Value derived from TMI Unit.2 core inventory ann core loading.
D) Facility vent flow 71,282 cfm (plant value)
E) Breathing rate 1400 m3 /y infant and 8000 m3 /y adult F) Thyroid mass 2 g infant 16 g adult G) Duration of release 2 h H) X/Q = 4.8 E-4 s/m3 I) All iodine entering the body via inhalation path goes to thyroid J) Infant thyroid gamma dose is <15 % of beta dose (prior information)
I-131 Released:
4.23 E5 Ci
- 0.007 = 2.96 E8 uCi Dilution Air:
71282 cfm
- 2 h *28320 cc/ft3 /1E6 cc/m3 = 2.422 E5 m3 Stack Average Concentration:
2.96 E8 uCi / 2.422 E5 m3 = 1.22 E3 uCi/m3 Fenceline Concentration:
1.22 E3 uti/m3
- 4.8 E-4 s/m3 = 19.7 uCi/m3 Thyroid Concentration:
Infant 19.7 uCi/m 3
/y
- 2g = 3.17 uCi/g Adult 19.7 uCi/m 3
/y
- 16g = 2.25 uCi/g Infant Beta Dose (rem):[6]
73.8*0.180 Mev*3.17 uCi/g*7.F1 d*((1-exp(-0.693*80 d/7.61 d)) = 319 Infant Beta Dose From 60 Day Old Bundle:
319
- 60 d / 8.05 d) = 1.82 rem
. Total Dose:
1.82 + (1.82 * .15) = 2.09 rem 5
, REFERENCES ,
, 1. Letter from R. W. Kober, Rochester Gas and Electric, to H. R. Denton, NRC,
Subject:
Rochester Gas and Electric Corporation, R. E. Ginna
.. Nuclear Power Plant Docket No. 50-244, dated October 9, 1985.
]
- 2. United States Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for pressurized Water Reactors, NUREG ll 0472, Rev. 3, Draft 7", September 1982.
- 3. Lett:er from D. M. Crutchfield, NRC, to J. E. Maier, Rochester Gas &
l Electric Corporation,
Subject:
SEP Topics, XV-2, Spectrum of Steam
- System Piping Failures Inside and Outside Containment XV-12, Spectrum of i Rod Ejection Accidents, XV-16, Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Outside Containment, XV-17, Steam ,
~
! Generator Tube Failure, and XV-20, Radiological Consequences of Fuel Damaging Accidents - R. E. Ginna, dated September 24, 1981.
1
. 4. Letter from D. P. Crutchfield, NRC, to J. E. Maier, Rochester Gas &
Electric Corporation,
Subject:
Ginna Nuclear Power Plart Final Safety Evaluation Report for SEP Spics XV-2, Spectrum of Steam Iystem Piping j Failures; XV-12, Rod Ejection 8.ccid6nts; XV-16, Failure of Small Lines
! Carrying Primary Coolant Outside Containment; XV-17, Steam Generator Tube l
Failure; and XV-20, Fuel Oaaaging Accident Inside and Outside Contair, ment, dated March 3,1982.
l
't
- 5. Letter from G. E. Lear, NRC, to Sholly Coordinator,
Subject:
Request for Publication in Bi-Weekly FR Notice - Notice of Consideration of Issuance t
of Amende:r.t to Facility Operating License and Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (TAC No. 60036), dated March 31, 1986.
E 6. R. E. Lapp & H. L.'Andrews, Nuclear Radiation Physics Fourth Edition, ,
l ,
p 274, Prentice Hall Inc., Englewood Cliffs, New Jersey, 1972.
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