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Category:CONTRACTED REPORT - RTA
MONTHYEARML20247N5421998-05-11011 May 1998 Technical Evaluation Rept on Pump & Valve Inservice Testing Program:Peach Bottom Atomic Power Station,Units 2 & 3 ML20094C7411995-08-0404 August 1995 Individual Plant Exam Insight Support Rept for NUREG-1150 Plants L-95-037, Evaluation of Peach Bottom Atomic Power Station Units 2 & 3 Odcm,Rev 51995-07-31031 July 1995 Evaluation of Peach Bottom Atomic Power Station Units 2 & 3 Odcm,Rev 5 ML20070N3361994-03-31031 March 1994 Release of Radionuclides and Chelating Agents from CEMENT- Solidified Decontamination LOW-LEVEL Radioactive Waste Collected from the Peach Bottom Atomic Power Station Unit 3 ML20057E5061993-09-30030 September 1993 Severe Accident Source Term Characteristics for Selected Peach Bottom Sequences Predicted by the Melcor Code ML20058F9621993-08-31031 August 1993 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Limerick-1/2 & Peach Bottom-2/3, Technical Evaluation Rept ML20028H6071990-12-31031 December 1990 Evaluation of Severe Accident Risks: Peach Bottom,Unit 2. Main Report ML20066C2721990-12-31031 December 1990 Analysis of Core Damage Frequency: Peach Bottom,Unit 2 External Events ML20028H6051990-12-31031 December 1990 Evaluation of Severe Accident Risks: Peach Bottom,Unit 2. Appendices ML20065Q3081990-11-30030 November 1990 Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Peach Bottom Atomic Power Station Units 2 & 3 ML20247N6471989-08-31031 August 1989 Analysis of Core Damage Frequency: Peach Bottom, Unit 2, Internal Events Appendices ML20247M6631989-08-31031 August 1989 Analysis of Core Damage Frequency: Peach Bottom, Unit 2, Internal Events ML20206B1581988-10-31031 October 1988 Technical Evaluation:Peco Topical Rept PECO-RMS-004 `Methods for Performing BWR Sys Transient Analysis,Peach Bottom Atomic Power Station,Units 2 & 3.' ML20245D7911988-09-30030 September 1988 Dcrdr Onsite Meeting Rept for Philadephia Electric Co Peach Bottom Atomic Power Stations,Unit 2 & 3 ML20245D6681988-09-14014 September 1988 Dcrdr Preimplementation Audit Rept for Philadelphia Electric Co Peach Bottom Station,Units 2 & 3 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 ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML20236P5111987-07-31031 July 1987 Technical Evaluation Rept Fibwr & Tcppeco Computer Programs, Final Informal Rept ML20214U0401987-06-0909 June 1987 App D & Suppl a to App D, Evaluation of Licensee-Reported Revs to Offsite Dose Calculation Manual, Technical Evaluation Rept ML20234B6291987-05-31031 May 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Peach Bottom,Unit 2.Appendices.Draft for Comment ML20234B5941987-04-30030 April 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Peach Bottom,Unit 2.Main Report.Draft for Comment ML20214R3971987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.1, 'Equipment Classification (All Other Safety-Related Components),' Peach Bottom 2 & 3, Informal Rept ML20206A2881987-02-28028 February 1987 Containment Venting Analysis for the Peach Bottom Atomic Power Station ML20212J9201986-10-31031 October 1986 Analysis of Core Damage Frequency from Internal Events:Peach Bottom Unit 2 ML20245A4481986-09-30030 September 1986 Revised Draft Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1 ML20206G8211986-05-12012 May 1986 Preliminary Draft Containment Event Analysis for Postulated Severe Accidents at Peach Bottom Atomic Power Station, for Review.Related Documentation Encl ML20140C2491986-01-0202 January 1986 Request for Info:Evaluation of Exemption Requests from 10CFR50.48 & 10CFR50,App R,Peach Bottom Atomic Power Stations,Units 2 & 3 ML20151P4161985-12-17017 December 1985 Dcrdr Validation Walkthrough Audit Results for Peach Bottom Atomic Power Station,Units 2 & 3 ML20141F6271985-09-30030 September 1985 Technical Evaluation Rept,Second Interval Inservice Insp Program,Peach Bottom Units 2 & 3 ML20128D8381985-05-15015 May 1985 Draft Review of Licensee & Applicant Responses to Generic Ltr 83-28,Item 1.2, 'Post-Trip Review:Data & Info Capabilities,' for Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20129A2411985-05-0101 May 1985 Addendum a to Technical Evaluation Rept,First-Interval Inservice Insp Program ML20126L1481985-03-31031 March 1985 Conformance to Reg Guide 1.97,Peach Bottom Atomic Power Station,Units 2 & 3 ML20115H1531985-03-22022 March 1985 Detailed Control Room Design Review In-Progress Audit Rept for Peach Bottom Atomic Power Station,Units 2 & 3 ML20106A6791984-09-12012 September 1984 Masonry Wall Design,Peach Bottom Atomic Power Station Units 2 & 3, Technical Evaluation Rept ML20106A6831984-08-31031 August 1984 Evaluation of Applicability of Nonlinear Analysis Techniques to Reinforced Masonry Walls in Nuclear Power Plants ML20106C4031984-07-31031 July 1984 Draft Vol II, Radionuclide Release Under Specific LWR Accident Conditions,Bwr,Mark I Design ML20126E6541984-07-31031 July 1984 Draft Containment Event Analysis & Estimation of Source Term Frequencies,App to NUREG-0956 ML20115D3441984-01-0404 January 1984 Data Collection & Evaluation of Proposed Spds,Peach Bottom Units 2 & 3 ML20076H3611983-08-31031 August 1983 Control of Heavy Loads (C-10),Philadelphia Electric Co, Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20080E3311983-08-18018 August 1983 Proposed Tech Spec Changes for Inservice Surveillance of Safety-Related Hydraulics & Mechanical Snubbers at Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20093J2831983-06-30030 June 1983 Technical Evaluation of Integrity of Peach Bottom,Units 2 & 3 Reactor Coolant Boundary Piping Sys ML20071N2041983-05-17017 May 1983 Control of Heavy Loads,Peach Bottom Atomic Power Station, Units 2 & 3, Draft Technical Evaluation Rept ML20072S3191983-03-11011 March 1983 Rev 1 to Proposed Design Mods & Tech Spec Changes on Grid Voltage Degradation for Peach Bottom Atomic Power Station, Units 2 & 3, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G8831982-11-24024 November 1982 ECCS Repts (F-47):TMI Action Plan Requirements,Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20079L0551982-10-31031 October 1982 Containment Purging & Venting During Normal Operation of Peach Bottom Atomic Power Station,Units 2 & 3, Draft Technical Evaluation Rept ML20076C7731982-09-10010 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20071L3801982-08-26026 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Peach Bottom Atomic Power Station, Technical Evaluation Rept ML20058H6581982-07-31031 July 1982 Socioeconomic Impacts of Nuclear Generating Stations:Peach Bottom Case Study.Docket Nos. 50-277 and 50-278. (Philadelphia Electric Company) ML20054M1531982-07-0101 July 1982 Adequacy of Station Electric Distribution Sys Voltages for Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept 1998-05-11
[Table view] Category:QUICK LOOK
MONTHYEARML20247N5421998-05-11011 May 1998 Technical Evaluation Rept on Pump & Valve Inservice Testing Program:Peach Bottom Atomic Power Station,Units 2 & 3 ML20094C7411995-08-0404 August 1995 Individual Plant Exam Insight Support Rept for NUREG-1150 Plants L-95-037, Evaluation of Peach Bottom Atomic Power Station Units 2 & 3 Odcm,Rev 51995-07-31031 July 1995 Evaluation of Peach Bottom Atomic Power Station Units 2 & 3 Odcm,Rev 5 ML20070N3361994-03-31031 March 1994 Release of Radionuclides and Chelating Agents from CEMENT- Solidified Decontamination LOW-LEVEL Radioactive Waste Collected from the Peach Bottom Atomic Power Station Unit 3 ML20057E5061993-09-30030 September 1993 Severe Accident Source Term Characteristics for Selected Peach Bottom Sequences Predicted by the Melcor Code ML20058F9621993-08-31031 August 1993 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Limerick-1/2 & Peach Bottom-2/3, Technical Evaluation Rept ML20028H6071990-12-31031 December 1990 Evaluation of Severe Accident Risks: Peach Bottom,Unit 2. Main Report ML20066C2721990-12-31031 December 1990 Analysis of Core Damage Frequency: Peach Bottom,Unit 2 External Events ML20028H6051990-12-31031 December 1990 Evaluation of Severe Accident Risks: Peach Bottom,Unit 2. Appendices ML20065Q3081990-11-30030 November 1990 Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Peach Bottom Atomic Power Station Units 2 & 3 ML20247N6471989-08-31031 August 1989 Analysis of Core Damage Frequency: Peach Bottom, Unit 2, Internal Events Appendices ML20247M6631989-08-31031 August 1989 Analysis of Core Damage Frequency: Peach Bottom, Unit 2, Internal Events ML20206B1581988-10-31031 October 1988 Technical Evaluation:Peco Topical Rept PECO-RMS-004 `Methods for Performing BWR Sys Transient Analysis,Peach Bottom Atomic Power Station,Units 2 & 3.' ML20245D7911988-09-30030 September 1988 Dcrdr Onsite Meeting Rept for Philadephia Electric Co Peach Bottom Atomic Power Stations,Unit 2 & 3 ML20245D6681988-09-14014 September 1988 Dcrdr Preimplementation Audit Rept for Philadelphia Electric Co Peach Bottom Station,Units 2 & 3 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 ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML20236P5111987-07-31031 July 1987 Technical Evaluation Rept Fibwr & Tcppeco Computer Programs, Final Informal Rept ML20214U0401987-06-0909 June 1987 App D & Suppl a to App D, Evaluation of Licensee-Reported Revs to Offsite Dose Calculation Manual, Technical Evaluation Rept ML20234B6291987-05-31031 May 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Peach Bottom,Unit 2.Appendices.Draft for Comment ML20234B5941987-04-30030 April 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Peach Bottom,Unit 2.Main Report.Draft for Comment ML20214R3971987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.1, 'Equipment Classification (All Other Safety-Related Components),' Peach Bottom 2 & 3, Informal Rept ML20206A2881987-02-28028 February 1987 Containment Venting Analysis for the Peach Bottom Atomic Power Station ML20212J9201986-10-31031 October 1986 Analysis of Core Damage Frequency from Internal Events:Peach Bottom Unit 2 ML20245A4481986-09-30030 September 1986 Revised Draft Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1 ML20206G8211986-05-12012 May 1986 Preliminary Draft Containment Event Analysis for Postulated Severe Accidents at Peach Bottom Atomic Power Station, for Review.Related Documentation Encl ML20140C2491986-01-0202 January 1986 Request for Info:Evaluation of Exemption Requests from 10CFR50.48 & 10CFR50,App R,Peach Bottom Atomic Power Stations,Units 2 & 3 ML20151P4161985-12-17017 December 1985 Dcrdr Validation Walkthrough Audit Results for Peach Bottom Atomic Power Station,Units 2 & 3 ML20141F6271985-09-30030 September 1985 Technical Evaluation Rept,Second Interval Inservice Insp Program,Peach Bottom Units 2 & 3 ML20128D8381985-05-15015 May 1985 Draft Review of Licensee & Applicant Responses to Generic Ltr 83-28,Item 1.2, 'Post-Trip Review:Data & Info Capabilities,' for Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20129A2411985-05-0101 May 1985 Addendum a to Technical Evaluation Rept,First-Interval Inservice Insp Program ML20126L1481985-03-31031 March 1985 Conformance to Reg Guide 1.97,Peach Bottom Atomic Power Station,Units 2 & 3 ML20115H1531985-03-22022 March 1985 Detailed Control Room Design Review In-Progress Audit Rept for Peach Bottom Atomic Power Station,Units 2 & 3 ML20106A6791984-09-12012 September 1984 Masonry Wall Design,Peach Bottom Atomic Power Station Units 2 & 3, Technical Evaluation Rept ML20106A6831984-08-31031 August 1984 Evaluation of Applicability of Nonlinear Analysis Techniques to Reinforced Masonry Walls in Nuclear Power Plants ML20106C4031984-07-31031 July 1984 Draft Vol II, Radionuclide Release Under Specific LWR Accident Conditions,Bwr,Mark I Design ML20126E6541984-07-31031 July 1984 Draft Containment Event Analysis & Estimation of Source Term Frequencies,App to NUREG-0956 ML20115D3441984-01-0404 January 1984 Data Collection & Evaluation of Proposed Spds,Peach Bottom Units 2 & 3 ML20076H3611983-08-31031 August 1983 Control of Heavy Loads (C-10),Philadelphia Electric Co, Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20080E3311983-08-18018 August 1983 Proposed Tech Spec Changes for Inservice Surveillance of Safety-Related Hydraulics & Mechanical Snubbers at Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20093J2831983-06-30030 June 1983 Technical Evaluation of Integrity of Peach Bottom,Units 2 & 3 Reactor Coolant Boundary Piping Sys ML20071N2041983-05-17017 May 1983 Control of Heavy Loads,Peach Bottom Atomic Power Station, Units 2 & 3, Draft Technical Evaluation Rept ML20072S3191983-03-11011 March 1983 Rev 1 to Proposed Design Mods & Tech Spec Changes on Grid Voltage Degradation for Peach Bottom Atomic Power Station, Units 2 & 3, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G8831982-11-24024 November 1982 ECCS Repts (F-47):TMI Action Plan Requirements,Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20079L0551982-10-31031 October 1982 Containment Purging & Venting During Normal Operation of Peach Bottom Atomic Power Station,Units 2 & 3, Draft Technical Evaluation Rept ML20076C7731982-09-10010 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20071L3801982-08-26026 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Peach Bottom Atomic Power Station, Technical Evaluation Rept ML20058H6581982-07-31031 July 1982 Socioeconomic Impacts of Nuclear Generating Stations:Peach Bottom Case Study.Docket Nos. 50-277 and 50-278. (Philadelphia Electric Company) ML20054M1531982-07-0101 July 1982 Adequacy of Station Electric Distribution Sys Voltages for Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept 1998-05-11
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20247N5421998-05-11011 May 1998 Technical Evaluation Rept on Pump & Valve Inservice Testing Program:Peach Bottom Atomic Power Station,Units 2 & 3 ML20094C7411995-08-0404 August 1995 Individual Plant Exam Insight Support Rept for NUREG-1150 Plants L-95-037, Evaluation of Peach Bottom Atomic Power Station Units 2 & 3 Odcm,Rev 51995-07-31031 July 1995 Evaluation of Peach Bottom Atomic Power Station Units 2 & 3 Odcm,Rev 5 ML20070N3361994-03-31031 March 1994 Release of Radionuclides and Chelating Agents from CEMENT- Solidified Decontamination LOW-LEVEL Radioactive Waste Collected from the Peach Bottom Atomic Power Station Unit 3 ML20057E5061993-09-30030 September 1993 Severe Accident Source Term Characteristics for Selected Peach Bottom Sequences Predicted by the Melcor Code ML20058F9621993-08-31031 August 1993 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Limerick-1/2 & Peach Bottom-2/3, Technical Evaluation Rept ML20028H6071990-12-31031 December 1990 Evaluation of Severe Accident Risks: Peach Bottom,Unit 2. Main Report ML20066C2721990-12-31031 December 1990 Analysis of Core Damage Frequency: Peach Bottom,Unit 2 External Events ML20028H6051990-12-31031 December 1990 Evaluation of Severe Accident Risks: Peach Bottom,Unit 2. Appendices ML20065Q3081990-11-30030 November 1990 Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Peach Bottom Atomic Power Station Units 2 & 3 ML20247N6471989-08-31031 August 1989 Analysis of Core Damage Frequency: Peach Bottom, Unit 2, Internal Events Appendices ML20247M6631989-08-31031 August 1989 Analysis of Core Damage Frequency: Peach Bottom, Unit 2, Internal Events ML20206B1581988-10-31031 October 1988 Technical Evaluation:Peco Topical Rept PECO-RMS-004 `Methods for Performing BWR Sys Transient Analysis,Peach Bottom Atomic Power Station,Units 2 & 3.' ML20245D7911988-09-30030 September 1988 Dcrdr Onsite Meeting Rept for Philadephia Electric Co Peach Bottom Atomic Power Stations,Unit 2 & 3 ML20245D6681988-09-14014 September 1988 Dcrdr Preimplementation Audit Rept for Philadelphia Electric Co Peach Bottom Station,Units 2 & 3 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 ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML20236P5111987-07-31031 July 1987 Technical Evaluation Rept Fibwr & Tcppeco Computer Programs, Final Informal Rept ML20214U0401987-06-0909 June 1987 App D & Suppl a to App D, Evaluation of Licensee-Reported Revs to Offsite Dose Calculation Manual, Technical Evaluation Rept ML20234B6291987-05-31031 May 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Peach Bottom,Unit 2.Appendices.Draft for Comment ML20234B5941987-04-30030 April 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Peach Bottom,Unit 2.Main Report.Draft for Comment ML20214R3971987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.1, 'Equipment Classification (All Other Safety-Related Components),' Peach Bottom 2 & 3, Informal Rept ML20206A2881987-02-28028 February 1987 Containment Venting Analysis for the Peach Bottom Atomic Power Station ML20212J9201986-10-31031 October 1986 Analysis of Core Damage Frequency from Internal Events:Peach Bottom Unit 2 ML20245A4481986-09-30030 September 1986 Revised Draft Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1 ML20206G8211986-05-12012 May 1986 Preliminary Draft Containment Event Analysis for Postulated Severe Accidents at Peach Bottom Atomic Power Station, for Review.Related Documentation Encl ML20140C2491986-01-0202 January 1986 Request for Info:Evaluation of Exemption Requests from 10CFR50.48 & 10CFR50,App R,Peach Bottom Atomic Power Stations,Units 2 & 3 ML20151P4161985-12-17017 December 1985 Dcrdr Validation Walkthrough Audit Results for Peach Bottom Atomic Power Station,Units 2 & 3 ML20141F6271985-09-30030 September 1985 Technical Evaluation Rept,Second Interval Inservice Insp Program,Peach Bottom Units 2 & 3 ML20128D8381985-05-15015 May 1985 Draft Review of Licensee & Applicant Responses to Generic Ltr 83-28,Item 1.2, 'Post-Trip Review:Data & Info Capabilities,' for Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20129A2411985-05-0101 May 1985 Addendum a to Technical Evaluation Rept,First-Interval Inservice Insp Program ML20126L1481985-03-31031 March 1985 Conformance to Reg Guide 1.97,Peach Bottom Atomic Power Station,Units 2 & 3 ML20115H1531985-03-22022 March 1985 Detailed Control Room Design Review In-Progress Audit Rept for Peach Bottom Atomic Power Station,Units 2 & 3 ML20106A6791984-09-12012 September 1984 Masonry Wall Design,Peach Bottom Atomic Power Station Units 2 & 3, Technical Evaluation Rept ML20106A6831984-08-31031 August 1984 Evaluation of Applicability of Nonlinear Analysis Techniques to Reinforced Masonry Walls in Nuclear Power Plants ML20106C4031984-07-31031 July 1984 Draft Vol II, Radionuclide Release Under Specific LWR Accident Conditions,Bwr,Mark I Design ML20126E6541984-07-31031 July 1984 Draft Containment Event Analysis & Estimation of Source Term Frequencies,App to NUREG-0956 ML20115D3441984-01-0404 January 1984 Data Collection & Evaluation of Proposed Spds,Peach Bottom Units 2 & 3 ML20076H3611983-08-31031 August 1983 Control of Heavy Loads (C-10),Philadelphia Electric Co, Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20080E3311983-08-18018 August 1983 Proposed Tech Spec Changes for Inservice Surveillance of Safety-Related Hydraulics & Mechanical Snubbers at Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20093J2831983-06-30030 June 1983 Technical Evaluation of Integrity of Peach Bottom,Units 2 & 3 Reactor Coolant Boundary Piping Sys ML20071N2041983-05-17017 May 1983 Control of Heavy Loads,Peach Bottom Atomic Power Station, Units 2 & 3, Draft Technical Evaluation Rept ML20072S3191983-03-11011 March 1983 Rev 1 to Proposed Design Mods & Tech Spec Changes on Grid Voltage Degradation for Peach Bottom Atomic Power Station, Units 2 & 3, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G8831982-11-24024 November 1982 ECCS Repts (F-47):TMI Action Plan Requirements,Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20079L0551982-10-31031 October 1982 Containment Purging & Venting During Normal Operation of Peach Bottom Atomic Power Station,Units 2 & 3, Draft Technical Evaluation Rept ML20076C7731982-09-10010 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20071L3801982-08-26026 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Peach Bottom Atomic Power Station, Technical Evaluation Rept ML20058H6581982-07-31031 July 1982 Socioeconomic Impacts of Nuclear Generating Stations:Peach Bottom Case Study.Docket Nos. 50-277 and 50-278. (Philadelphia Electric Company) ML20054M1531982-07-0101 July 1982 Adequacy of Station Electric Distribution Sys Voltages for Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept 1998-05-11
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20247N5421998-05-11011 May 1998 Technical Evaluation Rept on Pump & Valve Inservice Testing Program:Peach Bottom Atomic Power Station,Units 2 & 3 ML20094C7411995-08-0404 August 1995 Individual Plant Exam Insight Support Rept for NUREG-1150 Plants L-95-037, Evaluation of Peach Bottom Atomic Power Station Units 2 & 3 Odcm,Rev 51995-07-31031 July 1995 Evaluation of Peach Bottom Atomic Power Station Units 2 & 3 Odcm,Rev 5 ML20070N3361994-03-31031 March 1994 Release of Radionuclides and Chelating Agents from CEMENT- Solidified Decontamination LOW-LEVEL Radioactive Waste Collected from the Peach Bottom Atomic Power Station Unit 3 ML20057E5061993-09-30030 September 1993 Severe Accident Source Term Characteristics for Selected Peach Bottom Sequences Predicted by the Melcor Code ML20058F9621993-08-31031 August 1993 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Limerick-1/2 & Peach Bottom-2/3, Technical Evaluation Rept ML20028H6071990-12-31031 December 1990 Evaluation of Severe Accident Risks: Peach Bottom,Unit 2. Main Report ML20066C2721990-12-31031 December 1990 Analysis of Core Damage Frequency: Peach Bottom,Unit 2 External Events ML20028H6051990-12-31031 December 1990 Evaluation of Severe Accident Risks: Peach Bottom,Unit 2. Appendices ML20065Q3081990-11-30030 November 1990 Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Peach Bottom Atomic Power Station Units 2 & 3 ML20247N6471989-08-31031 August 1989 Analysis of Core Damage Frequency: Peach Bottom, Unit 2, Internal Events Appendices ML20247M6631989-08-31031 August 1989 Analysis of Core Damage Frequency: Peach Bottom, Unit 2, Internal Events ML20206B1581988-10-31031 October 1988 Technical Evaluation:Peco Topical Rept PECO-RMS-004 `Methods for Performing BWR Sys Transient Analysis,Peach Bottom Atomic Power Station,Units 2 & 3.' ML20245D7911988-09-30030 September 1988 Dcrdr Onsite Meeting Rept for Philadephia Electric Co Peach Bottom Atomic Power Stations,Unit 2 & 3 ML20245D6681988-09-14014 September 1988 Dcrdr Preimplementation Audit Rept for Philadelphia Electric Co Peach Bottom Station,Units 2 & 3 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 ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML20236P5111987-07-31031 July 1987 Technical Evaluation Rept Fibwr & Tcppeco Computer Programs, Final Informal Rept ML20214U0401987-06-0909 June 1987 App D & Suppl a to App D, Evaluation of Licensee-Reported Revs to Offsite Dose Calculation Manual, Technical Evaluation Rept ML20234B6291987-05-31031 May 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Peach Bottom,Unit 2.Appendices.Draft for Comment ML20234B5941987-04-30030 April 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Peach Bottom,Unit 2.Main Report.Draft for Comment ML20214R3971987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.1, 'Equipment Classification (All Other Safety-Related Components),' Peach Bottom 2 & 3, Informal Rept ML20206A2881987-02-28028 February 1987 Containment Venting Analysis for the Peach Bottom Atomic Power Station ML20212J9201986-10-31031 October 1986 Analysis of Core Damage Frequency from Internal Events:Peach Bottom Unit 2 ML20245A4481986-09-30030 September 1986 Revised Draft Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1 ML20206G8211986-05-12012 May 1986 Preliminary Draft Containment Event Analysis for Postulated Severe Accidents at Peach Bottom Atomic Power Station, for Review.Related Documentation Encl ML20140C2491986-01-0202 January 1986 Request for Info:Evaluation of Exemption Requests from 10CFR50.48 & 10CFR50,App R,Peach Bottom Atomic Power Stations,Units 2 & 3 ML20151P4161985-12-17017 December 1985 Dcrdr Validation Walkthrough Audit Results for Peach Bottom Atomic Power Station,Units 2 & 3 ML20141F6271985-09-30030 September 1985 Technical Evaluation Rept,Second Interval Inservice Insp Program,Peach Bottom Units 2 & 3 ML20128D8381985-05-15015 May 1985 Draft Review of Licensee & Applicant Responses to Generic Ltr 83-28,Item 1.2, 'Post-Trip Review:Data & Info Capabilities,' for Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20129A2411985-05-0101 May 1985 Addendum a to Technical Evaluation Rept,First-Interval Inservice Insp Program ML20126L1481985-03-31031 March 1985 Conformance to Reg Guide 1.97,Peach Bottom Atomic Power Station,Units 2 & 3 ML20115H1531985-03-22022 March 1985 Detailed Control Room Design Review In-Progress Audit Rept for Peach Bottom Atomic Power Station,Units 2 & 3 ML20106A6791984-09-12012 September 1984 Masonry Wall Design,Peach Bottom Atomic Power Station Units 2 & 3, Technical Evaluation Rept ML20106A6831984-08-31031 August 1984 Evaluation of Applicability of Nonlinear Analysis Techniques to Reinforced Masonry Walls in Nuclear Power Plants ML20106C4031984-07-31031 July 1984 Draft Vol II, Radionuclide Release Under Specific LWR Accident Conditions,Bwr,Mark I Design ML20126E6541984-07-31031 July 1984 Draft Containment Event Analysis & Estimation of Source Term Frequencies,App to NUREG-0956 ML20115D3441984-01-0404 January 1984 Data Collection & Evaluation of Proposed Spds,Peach Bottom Units 2 & 3 ML20076H3611983-08-31031 August 1983 Control of Heavy Loads (C-10),Philadelphia Electric Co, Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20080E3311983-08-18018 August 1983 Proposed Tech Spec Changes for Inservice Surveillance of Safety-Related Hydraulics & Mechanical Snubbers at Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20093J2831983-06-30030 June 1983 Technical Evaluation of Integrity of Peach Bottom,Units 2 & 3 Reactor Coolant Boundary Piping Sys ML20071N2041983-05-17017 May 1983 Control of Heavy Loads,Peach Bottom Atomic Power Station, Units 2 & 3, Draft Technical Evaluation Rept ML20072S3191983-03-11011 March 1983 Rev 1 to Proposed Design Mods & Tech Spec Changes on Grid Voltage Degradation for Peach Bottom Atomic Power Station, Units 2 & 3, Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G8831982-11-24024 November 1982 ECCS Repts (F-47):TMI Action Plan Requirements,Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept ML20079L0551982-10-31031 October 1982 Containment Purging & Venting During Normal Operation of Peach Bottom Atomic Power Station,Units 2 & 3, Draft Technical Evaluation Rept ML20076C7731982-09-10010 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20071L3801982-08-26026 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Peach Bottom Atomic Power Station, Technical Evaluation Rept ML20058H6581982-07-31031 July 1982 Socioeconomic Impacts of Nuclear Generating Stations:Peach Bottom Case Study.Docket Nos. 50-277 and 50-278. (Philadelphia Electric Company) ML20054M1531982-07-0101 July 1982 Adequacy of Station Electric Distribution Sys Voltages for Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept 1998-05-11
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' ATTACHMENT A EGG-RTH-7760 a
j' TECbNICAL EVALUATION REPORT.
FIBWR AND.TCPPECO COMPUTER PROGRAM 3 5
.c.
C. P. Fineman w
( Published July 1987 i
e Idaho. National Engineering Laboratory
'daho Falls, Idaho 83415 t
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Prepared for the U.S. Nuclear Regulatory Commission '
Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76100570 ,
FIN No. D6030
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AESTRACT.
The.'idabo:fIational- Engineering i.acorator3 reviewea the FIBWR anc TCPRECC computer pecgrams aeveicoed by Philadelphia Electric Company
( P ECO j ., PECO uses FIBWR'to perform steady state.. thermal-hydraulic arei de', .: f boiling water-reacters (SWRs). TCPPECO is used witn RETP.AN t ca'V r.r- :neL critical . cower ratio (CPR) in BWR:. PECO submitted these programs for Nuclear Regulatory Commission approval for use in'their in-house reload licensing analyses. The review consisted of evaluating the modifications PECO made to methods previously approved for use by
. Yankee Atomic Electric Company (YAEC). Assessment calculations made by PECO for.each code were.also reviewed. This review found the modifications PECO maae to the approved YAEC methods should not
.significantly affect the calculated results and, therefore, recommends the PECO methods be approved for.use in licensing analyses on the basis that suggested conditions and-requirements are followed,
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SUMMARY
Tris report documents the review and evaluation of the Philaceiphia ile;tric Company (PECO) computer programs FISWR anc TCP;ECC. FIBWR j taiculates the' steady state pressure drop ano flow and voic distribution: j in a boiling water reactor (BWR) : ore. TCPPECO is usec ai-h RETRAN to. I calcu' ate the critical power ratio (CPR) in BWRs. PECO ssbmitted these programs for Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation (NRR), approval for use in their in-house reload licensing analyses. NRR requested assistance from the Idaho National Engineering Laboratory (INEL) in reviewing FIBWR and TCPPEC0-. FIBWR and the RETRAN-TCPPECO methodology are based on methods previousif approved i for.use in licensing analyses of the Vermont Yankee Nuclear Power Station by Yankee Atomic Electric Company (YAEC).
The review consisted of evaluating the PECO modifications to the methods previously approved for use by YAEC. PECO assessment calculations ;
for each code were also reviewed. INEL completed this review using the information supplied by PECO in reports documenting FIBWR, the i RETRAN-TCPPEC0 methodology, and the FIBWR and RETRAN-TCPPEC0 assessment calculations and in letters to the NRC listing the changes PECO made to i j
the approved YAEC methods and responding to an NRC question on the RETRAN-TCPPECO assessment calculations.
This review found the modifications PECO made to the approved YAEC methods should not significantly affect the calculated results and, therefore, recommends the PECO methods be approved for use in licensing i analyses on the basis that suggested conditions arid requirements are -
I followed.
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'. 1 CONTENTS a B : ' ;,.\ C T .. .. .... ... . ... ... .... . . . ... .. i ;
44 sgyMaa . . .. ., . ... ... .. . . . . . . .... .. ' '
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- i. INTR 0 DUCTION ......... . . . ..... . . , ........ . ..
- 2. FIBWR CODE ;P/IEW ........... ..... . . . ............... ..2 2.1 Description of FIBWR coce and Modifications ............ ...... 2 2
2.2 FIBWR Assessment Calculations ......... ... .................. 4 1
3 2.3 Conclusion . ............... .. .... .......... ......... ....
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- 3. RETRAN-TCPPECO METH0COLOGY ............ . ... ........ .............
3.1 Description of RETRAN-TCPPECO Methodology and Code 4
Modifications ............................................. ...
6 3.2 RETRAN-TCPPECO Assessment Calculations ........................
8 3.3 Conclusion .................................................... ;
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- 4. PEACH BOTTOM 2 AND 3 TRANSIENT CPR METHODOLOGY .....................
- s. CONCLUSIONS ................................. ...................... 11 l
- 6. REF.ERENCES.......................................................... 12 FIGURES Flow diagram for TCPPECO ........................................ .. 5
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- 2. RETRAN-TCPPECO methodology for calculating transient CPRs .......... 10 1
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TECHNICAL EVALUATION REPORT
'FIBWR AND'TCpPECO COMPUTER PROGRAMS
- 1. INTRODUCTION FIBWR1 and TCPPECO2 areconsuterprogramssubmittedb) i Philadelphia Electric Company (PECO) to the Nuclear Regulatory Commission j
.(NRC) for approval for.use in their in-house' reload licensing analyses.
FIBWR calculates tnel steady state pressure drop and flow and void
. distributions in a boiling water reactor (BWR) core. lTCPPECO is combined l with the RETRAN3 code to calculate critical power ratios (CPRs) in BWRs and will be used to calculate the transient.CPR for Peach Bottom Units 2 and 3. Both FIBWR and the RETRAN-TCPPECO methodology are based on methods' previously approved by the NRC for licensing use by Yankee Atomic Electric f Company (YAEC).4- ;)
1 The Office of Nuclear Reactor Regulation (NRR) has the responsibility.
to evaluate'and review computer codes and their proposed applications.
NRR requested the Idaho National Engineering Laboratory (INEL) to provide assistance in the review of FIBWR and RETRAN-TCPPECO. Specifically, the INEL reviewed the changes made by PECO to the previously accepted methods and evaluated the acceptability of the changes. l This technical evaluation report contains the results of the FIBWR and RETRAN-TCPPECO review and assessment. Section 2 briefly describes the FIBWR code and the changes made by PECO. The results of PECO's FIBWR assessment calculations are also discussed. Section 3 presents the same information for RETRAN-TCPPECO. PECO's proposed method of calculating ,
transient CPRs is discussed in Section 4. The conclusions are summarized >
in Section 5 and the references are listed in Section 6. ;
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l 2. FIBWR CODE REVIEW his section briefly describes the FIBWR coce and identifies tho
- charges nade by PECO. The results of assessment calculations made by oECG are O so discussec. ;
2.1 Descri::tien of FIBWP Code and .'1ccifications i
DEC0 uses FIBWR to perform steady state, thermal-hydraulic analyses of BWRs. FIBWR evaluates the flow and void distribution within the reactor core oy solving the steady state, one-dimensional equations of continuity, momentum, and energy. FIBWR was developed by YAEC and made available to PECO through the Electric Power Research Institute (EPRI). The NRC reviewed and approved FIEWR for use in performing licensing calculations for the Vermont Yankee Nuclear power Station (Reference 4),
i PEC0 made only minor changes to FIBWR. According to the changes )
identified by PECO,5 only the capability to print out additional variables was added to the code. The basic models the NRC approved earlier were not changed. Therefore, the code is essentially the same as
- that previously approved for use by YAEC.
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2.2 FIBWR Assessment Calculations i l
To assess the capability of FIBWR to calculate the core support plate pressure drop and the core bypass flow, PECO compared FIBWR results to 1 data available from the Peach Bottom 2 and 3 plant process computers.
PECO provided these results for review.6 Using the ratio of the FIBWR calculated value to the process computer value (1.0 would indicate perfect agreement), PECO showed the mean of this ratio varied between 0.925 j and 1.013 for the pressure drop and 1.011 to 1.044 for the bypass flow.
This comparison showed that FIBWR adequately calculated the plant data.
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2.3 Conclusion j l
I Bet use no significant changes were made to a prev ous'y i approved coce ]
ano the RECO assessment calculations showec FIBWR could adequately calculate the Peach Bottom 2 and 3 core support plate crassure drop ano l cer: N ass flow, it is recommended that FIBWR be accepte: for licensing f ana;ysei Because the acceptability of the PECO versicr of CIBWR is basec i
-on the earlier acceptance of the YAEC version of FIBWR, any restrictions en the YAEC version of FIBWR noted in the safety evaluation report (SER) I also apply to the PECO version of FIBWR. I i
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- 3. RE RAN-TCDPECO METHODOLOGY This section briefi3 describes the RETRAN-TCPPECO methodology ard identifies tne cnanges made by PECC in developing TCPPECO. The results of assessment calculations mace by DECO are also discust.eo.
3.2 Description of RETRAN-TCDDECO Methodology anc Code Modifications PECO uses TCPPECO, in conjunction with the RETRAN code, to calculate the CPR in BWRs. The overall system response is calculated with RETRAN and these results provide the boundary conditions to a RETRAN hot channel model. The results of the RETRAN hot channel model are then input to TCPPECO to calculate the CPR. TCPPECO uses the GE proprietary GEXL correlation 7 to determine when the critical quality is reached at a specific core location. TCPPECO uses an iterative procedure to determine the CPR (see Figure 1). An initial CPR estimate is made and the boiling length and local quality are recalculated based on this estimate. The critical quality from the GEXL correlation is calculated based on the ]
recalculated boiling length and compared to the revised local quality. If f the revised local quality and the critical quality from the GEXL
. correlation agree (within a specified tolerance), the CPR is set equal to f the initial estimate. If the local quality and the critical quality do not agree, a new CPR estimate is made and the code makes another iteration. This continues until the revised local cuality and the !
critical quality converge.
PECO based TCPPECO on the YAEC code TCPYA01. The NRC reviewed and l approved the RETRAN-TCPYA01 methodology for use in performing licensing calculations (Reference 4). PECO made a number of changes to TCPYA01 in their development of TCPPECO and they identified these changes in l Reference 5. The changes include using a different interpolating routine in calculating the boiling length, changing the calculation of the thermal diameter to account for differences in the diameter of the fuel rods and the water rods, and also some input / output changes. These chances should l not result in significantly different results when compared to those calculated with TCPYA01.
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TCPPECO 13 INPUT CALCULATE TM(J) .
!. l THERMAL-MARGIN u
READ 8 TRANSIENT. 14 gg
-INPUT NO COMPARE NEW (RETRAN) - 2 XC-XJ<0.0001 CPR ;
ESTIMATED i 7 .
YES y'
CALCULATE HIN 15 l CPR(OLO)=CPR u-BEGIN _ U CPR ~
ITERATION 17 g NO-7p
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CALCULATE " YES XJ NO .
F TIME:
CALCULATE "
REVISED ENTHALPIES IS AND CALCULATE QUALITY MCPR DISTRIBUTIONS o -V CALCULATE PRINT BOILING RESULTS LENGTH (BL) o "
12 2I CALCULATE XC END VIA GEXL u
Figure 1. Flow Diagram for TCPPECO.
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3.2 RETRAN-TCPPECO Assessment Calculations- j 1
To assess the capability of RETRAN-TCPPECO to calculate boiling ;
transition., PECO compared RETRAN-TCPPECO results to data available from GE-ATLAS tests'.8,9 These results were presented in Reference 2. PECO l analyzed fifty steady state tests with RETRAN-TCPPECO. The minimum CPRs t .(MCPRs) calculated fall into the range of 0.973 to 1.053. The mean
-was 1.007 with a standard deviation of 0.019. These results indicate there is some scatter in the calculated CPRs but all of the calculated
!- steady state results are well within the GEXL MCPR limit of 1.07. The limit of 1.07 is used to account for uncertainty in the GEXL correlation by assuming boiling transition occurs if the MCPR is less than or eoual to 1.07 instead of the mathematical MCPR limit of 1.0.
For the transient tests analyzed, RETRAN-TCPPECO calculated the measured time to boiling transition within one second except for three tests. One of these tests was a flow decay at constant power (Run 112) and the other tests were flow and power increase transients (Runs 229 and 231). PECO responded to a request for additional information on these analyses in Reference 10. For Run 112, a MCPR of 1.011 was calculated at 7.75 s as compared to a time to boiling transition of 6.29 s in the experiment. PECO noted the calculated CPR for Run 112 was within the mean plus one standard deviation of the steady state calculated CPRs, 1.026, and fell below 1.026 at approximately 6.25 s. Thus, the results for Run 112 fall within the scatter of the steady state data. PECO provided a similar reason for the difference between the calculated and measured results for Run 231. For Run 229, PECO noted that, although there was a boiling transition at 4.17 s, the data indicated that the thermocouple rewet very soon after that. This occurred several times between 4.17 s and 15 s. At approximately 15.5 s boiling transition occurred and the thermocouple did not rewet. For Run 229, the calculated MCPR was 1.008 at 18.2 s but the calculated CPR fell below 1.026 at about 15.6 s. PECO stated that, based on these results and the fact that boiling transition was not sustained until 15.5 s, the calculation for Run 229 adequately :
represented the test data and was within the scatter of the steady state 6
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ressita. Thus, PECO concluded the RETRAN-TCPPECO results for these tests ept esent the test data well and do not indicate code or methodology problems even thougn MCPRs of 1.0 or less were not calculated for these
- tests.
INEL reviewed the SER for the YAEC RETRAN-TCPYA01 methodology (Reference 4) to determine how the RETRAN-TCPYA01 results for the GE-ATLAS tests compared to those discussed above. This review found the RETRAN-TCPYA01 results for the steady state tests similar to those calculated with RETRAN-TCPPECO. In addition, RETRAN-TCPYA01 did not calculate a MCPR of 1.0 or less for some of the transient tests. Although several reasons were given why RETRAN-TCPYA01 did not calculate ~a MCPR of 1.0 in these tests, the authors of the SER considered the RETRAN-TCPYA01 results acceptable because the MCPR was within the GEXL correlation MCPR limit of 1.07 for those cases where boiling transition was not calculated. Thus, the RETRAN-TCPYA01 results were accepted for reasons very similar to those presented by PECO for RETRAN-TCPPECO.
Based on the information received from PECO and our review of the YAEC ]
SER, the INEL concluded RETRAN-TCPPECO acceptably calculated the test
. results. PECO's statement that their transient analyses where boiling transition was not calculated are adequate because the results fall within l the mean plus one standard deviation of the steady state data (1.026) is acceptable and is supported by the acceptance of the YAEC results because they were within the GEXL MCPR limit of 1.07. It should be noted that f PECO also applies a MCPR upper bound of 1.07 for licensing calculations !
(Reference 10). I PECO assessed the sensitivity of the RETRAN-TCPPECO method to core I nodalization (12 axial nodes versus 24 nodes), void models (Homogeneous Equilibrium Model (HEM) versus EPRI void model), and time step size f (0.05 s maximum, 0.01 s minimum versus 0.005 s maximum, 0.001 s minimum or j a fixed time step of 0.025 s). These studies showed the calculated l results were not sensitive to these parameters over the ranges studied. f I
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a The + a ., active core nodalizations using 12 to 24 nodes would be act+0s.4L.a eitner the HEM or EPRI void model may be used, and time steps bouncec ey a max 4num of 0.05 s anc a minimum of 0.001 s woul d be accertacle for use in licensing calculations.
3.3 Conclusion Secause the changes made to a previously aporoved method should not significantly change the calculated results and the assessmer.:
calculations provided by PECO showed RETRAN-TCPPECO could adequately calculate the GE-ATLAS transient tests, it is recommended that the RETRAN-TCPPECO methodology be accepted for licensing analyses. Because the acceptability of RETRAN-TCPPECO is based on the earlier acceptance of the YAEC methodology using RETRAN-TCPYA01, any restrictions on j RETRAN-TCPYA01 noted in the SER also apply to RETRAN-TCPPECO.
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- 4. PEACH BOTTOM 2 AND 3 TRANSIENT CPR METHODOLOGY PEC0' intends to use RETRAN-TCPPECO and FIBWR to calculate the
' transient CPR response for Peach Bottom 2 and 3. The methodology proposed ,
is shown in Figure 2 which was taken from Reference 2. The methodology is based on that discussed in Section 3.1 except a check is added after the TCPPECO run is completed. This check determ_ines whether the MCPR calculated by TCPPECO is' equal to 1.07. If it is, then the transient CPR ]
4 difference is calculated. If not, the estimated hot channel power and flow are adjusted and the RETRAN hot channel model is rerun to start the
. .CPR calculation cycle again.
I PECO presented the RETRAN hot channel nodalization for Peach Bottom 2 and 3 in Reference 2. The model uses 24 axial nodes to represent the active core which.is adequate based on the sensitivity study discussed in Section 3.2. The other options and models to be used in PECO's RETRAN system and hot channel analyses were not discussed. These should be reviewed to ensure they are consistent with current modeling practices, based on the GE-ATLAS assessment calculations, or based on the sensitivity studies performed by PECO, Any exceptions should be justified.
PECO presented the results of one plant analysis using this l methodology to' calculate the transient CPR difference. The case presented was a generator load rejection without bypass transient. A MCPR of 1.07 was calculated at 1.1 s. Because tie initial CPR was 1.36, the CPR difference for the transient was 0.29. No plant data was compareo to the ;
calculation but the analysis results reviewed appear reasonable.
The methodology proposed by PECO is based on methods that are recommended for approval in this report (PECO version of FIBWR and RETRAN-TCPPECO) and are very similar to methods previously approved by the NRC. The methodology shown in Figure 2 combines these methods in a way ,
consistent with their intended use. Thus, there are no problems due to code interaction. Therefore, it is recommended that this methodology be approved for use by PECO in calculating transient CPRs provided the the RETRAN model options are reviewed as discussed above.
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BOUNDARY CONDITIONS FROM RETRAN SYSTEM LEVEL MODEL RESTART FILE CHANNEL FLOW SINGLE : RETRAN l 1
CHANNEL HOT CHANNEL FIBWR r MODEL MODEL o
RETRAN ESTIMATED RE-EDIT FOR CHANNEL BOUNDARY POWER CONDITIONS a
9 TCPPECO r
NO AC PR = 1. 07 YES V
TRANSIENT A CPR l
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i Figure 2. RETRAN-TCPPEC0 methodology for calculating transient CPRs.
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- 5. CONCLUSIONS The following summarizes the conclusions drawn # rem c'BWR ana RETRAN-TCPPECO reviews:
.1. The INEL reviewed the PECO version'of FIBWR and the RETRAN-TCPPECO methodology and recommends they be accepted for licensing analyses with th'e following restr.iction. Because the acceptability (in part) of the:PECO. versions of FIBWR'and RETRAN-TCPPECO is based on the earlier acceptance of the YAEC versions of FIBWR and RETRAN-TCPYA01, E any. restrictions on the YAEC methods noted 11 the SER also ap'ly p to the PECO methods. :
- 2. The RETRAN. hot channel nodalization (24 axial nodes) for the Peach Bottom 2 and 3 active cores is adequate based on the sensitivity study discussed.in Section 3.2. Other options and models to be used in the RETRAN system and hot channel analyses for Peach Bottom 2 and 3 were not discussed. They should be reviewed to ensure they are consistent with. current modeling practices, based on the GE-ATLAS assessment calculations, or based on the sensitivity studies performed by PECO.
Any exceptions should te justified.
- 3. The INEL reviewed the methodology proposed by PECO for calculating transient CPRs and recommends the methodology be approved for licensing use provided FIBWR and RETRAN-TCPPECO are used in accordance with the limitations noted above.
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- 6. REFERENCES 1 FIBWR: A' Steady State Core Flow Distribution Code for Boiling Water Reactors. Comouter Code Users' Manual, EPRI NP-1924-CCM,. July 1981. [
- 2. K. R. Young and S. A. Auve', Method for Calculating Transient Critical ,
Power Ratios for Boiling Wate'r Reactors (RETRAN-TCPPECO), !
PECO-FMS-0002, November 1985. l 3.- RETRAN - A Program for One-Dimensional Transient Thermal-Hydraulic Analysis of Comolex Fluid Flow Systems, EPRI NP-5-CCM, December 1978.
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- 4. Letter 0. B. Vassallo, NRC, to J. B. Sinclair, YAEC, Docket No. 50-271, September 15, 1982.
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- 5. Letter S. L. Daltroff, PECO, to D. R. Muller, NRC, " Philadelphia Electric Company In-House Reload Licensing," Docket No. 50-278, August 29, 1986. !
- 6. K. R. Young and S. A. Auve',' Steady State Thermal-Hydraulic Analysis of Peach Bottom Units 2 and-3 Using the FIBWR Comouter Code, PECO-FMS-0001, February 1985.
- 7. General Electric BWR Thermal' Analysis Basis (GETAB): Data Correlation i and Design Application, NED0-10958, November.1973.
- 8. Deficient Cooling 12th Quarterly Progress Report, GEAP-10221-12, July.1972.
- 3. Transient Critical Heat Flux - Experimental Results, GEAP-13295, l September 1972.
- 10. Letter M. J. Cooney, PECO to W. R. Butler, NRC, " Philadelphia Electric Company In-House Reload Licensing," June 10, 1987.
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