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MONTHYEARML17264B0451997-09-19019 September 1997 Rev 3 to 86-1234820-03, Low Temp Overpressure Analyses Summary. ML17265A6891997-06-30030 June 1997 Rev 1 to Calculation 96190-C-68, Pressure Locking Analysis for Valve(S) 871A/B. ML17264A9261997-06-10010 June 1997 Low Temp Overpressure Analyses Summary Rept, Calculational Summary Sheet 86-1234820-01 ML20132A3921996-12-13013 December 1996 Press Release I-96-81, NRC Staff Proposes to Fine Rg&E $100,000 for Alleged Violations at Ginna Nuclear Plant ML20129B7031996-10-22022 October 1996 Press Release I-96-69,informing That NRC Has Rescheduled Meeting W/Officials of Rg&E to Discuss Latest Systematic Assessment of Licensee Performance at Gnpp ML20128M2981996-10-15015 October 1996 Press Release I-96-68, NRC Staff Rates Ginna Good in Three Areas & Excellent in One Category on Latest SALP Rept ML17264A6131996-08-0202 August 1996 Rev 0 to Verification of Pressure Locking Analysis Program Preslok. ML17264A2651995-11-16016 November 1995 Gamma-Body Offsite Dose Calculation. ML17264A6111993-12-23023 December 1993 Rev 1 to Valve Thrust Calculation for 6x4x6 Class 300# Anchor Darling Gate Valve,857A,B & C & 860A,B,C & D. ML20085M5451991-11-11011 November 1991 Responses to NUMARC Aquatic Resources Survey & Socioeconomic Question in Support of NRC License Renewal Rulemaking ML17262A4511991-04-10010 April 1991 Devonrue Calculation Re Plant Atmospheric Relief Valve (ARV) Area Ambient Temp rise-revised Methodology ML17262A4531990-06-0505 June 1990 Devonrue Calculation Re Plant Turbine Driven Auxiliary Feedwater Pump Area Ambient Temp Rise ML17251A4791989-04-14014 April 1989 Prv Block Valve Thrust Calculation. ML20237D7901987-12-10010 December 1987 Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary IA-86-445, Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 8201311986-07-28028 July 1986 Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 ML20203H2851986-07-28028 July 1986 Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 ML20132D2121985-06-24024 June 1985 Human Factors Engineering Dcrdr In-Progress Audit,Re Ginna Nuclear Power Plant ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML17256A8381982-03-23023 March 1982 Slide Presentation from 820323 Meeting Re Steam Generator Repair Activities at Facility ML17261A5941966-09-16016 September 1966 Package of Incomplete Brookwood Project Requirement Outline Repts Re Instruments & Equipment 1997-09-19
[Table view] Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARML17264B0451997-09-19019 September 1997 Rev 3 to 86-1234820-03, Low Temp Overpressure Analyses Summary. ML17265A6891997-06-30030 June 1997 Rev 1 to Calculation 96190-C-68, Pressure Locking Analysis for Valve(S) 871A/B. ML17264A9261997-06-10010 June 1997 Low Temp Overpressure Analyses Summary Rept, Calculational Summary Sheet 86-1234820-01 ML17264A6131996-08-0202 August 1996 Rev 0 to Verification of Pressure Locking Analysis Program Preslok. ML17264A2651995-11-16016 November 1995 Gamma-Body Offsite Dose Calculation. ML17264A6111993-12-23023 December 1993 Rev 1 to Valve Thrust Calculation for 6x4x6 Class 300# Anchor Darling Gate Valve,857A,B & C & 860A,B,C & D. ML17262A4511991-04-10010 April 1991 Devonrue Calculation Re Plant Atmospheric Relief Valve (ARV) Area Ambient Temp rise-revised Methodology ML17262A4531990-06-0505 June 1990 Devonrue Calculation Re Plant Turbine Driven Auxiliary Feedwater Pump Area Ambient Temp Rise ML17251A4791989-04-14014 April 1989 Prv Block Valve Thrust Calculation. 1997-09-19
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Text
20&97-3 (12/g&)
I ~
CALCULATIONAL
SUMMARY
SHEET (CSS)
DOCUMENT IDENTIFIER 86-1234820-01 TiTLE LOW TEMPERATURE OVERPRESSURE ANALYSES-
SUMMARY
REPORT PREPARED BY: REVIEWED BY:
NAME N.VASUDEVAN NAME + Q PE2/-gE ~
SIGNATURE ~ SlGRATURE TITLE Principal Engineer DATE 6/9/97 .DATE
@ /0 cosT cENTFR 41p1p REF. PAGE(s) 32b TM STATEMENT: REVIEWER INDEPENDENCE PURPOSE AND
SUMMARY
OF RESULTS:
This document is a complete replacement of Revision 00.
Framatome Technologies inc., performed the low temperature overpressure event analyses for the Rochester Gas and Electric (RGE) R.E.Ginna Nuclear Power Station, after the steam generators were replaced with BI/l-designed generators. fn this effort, a spectrum of LTOP events to bound all possible operational configurations is analyzed and the results compared to Appendix G limits and the RHR pressure limit.
The most limiting mass addition case is a case with one charging pump turned on when the primary system is at 60'F with one RC pump running. This case resulted in a peak reactor vessel pressure of 554.3 psia which is the Appendix G limit at this temperature.
The most limiting heat addition case is with the primary system at 60'F, with an initial pressure of 329.7 psia. One RC pump is turned on with the secondary system at a temperature of 50'F higher than the primary. The peak reactor vessel pressure in this transient is 551.3 psia which is below the Appendix G limit of 554.7 1
The limiting event for the RHR system occurs at 280'F, when two RHR pumps are running with a capacity of 2000 gpm total. in this heat addition case, the peak RHR system pressure reached is 663.7 psia compared with an allowabie of 674.7 psia. YENDOR'S DOCUMENT REYIEW lg APPROVEO SUBMIT FINALOOCUMENT Bp MANUFACZUR',NO MAyPROCEEO
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