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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217P0761999-10-0606 October 1999 Non-proprietary, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20206C9461999-04-30030 April 1999 1:Final Cycle 16 Freespan ODSCC Operational Assessment ML20154H0121998-09-30030 September 1998 Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion) ML20151V8341998-09-30030 September 1998 Non-proprietary Rev 2 to NSA-SSO-96-525, Jm Farley Nuclear Plant Safety Analysis IR Neutron Flux Reactor Trip Setpoint Change ML20236Y1121998-07-31031 July 1998 Voltage-Based Repair Criteria 90-Day Rept ML20216J6851998-03-16016 March 1998 Revised Pages 58 & 59 to Fnp,Units 1 & 2,Power Uprate Project BOP Licensing Rept ML20197B6391997-12-18018 December 1997 Rev 1 of Jfnp - Unit 1 Pressure Temperature Limits Rept ML20197B6471997-12-18018 December 1997 Rev 1 to Jfnp - Unit 2 Pressure Temperature Limits Rept ML20199G1871997-11-19019 November 1997 Non-proprietary NSD-SAE-ESI-97-647 to SNC Response to NRC RAI on Beloca ML20217Q4211997-08-31031 August 1997 Alternate Repair Criteria 90 Day Rept ML20149K1031997-07-23023 July 1997 Rev 0 to Jm Farley Nuclear Plant Unit 1, P/T Limits Rept ML20149K1051997-07-23023 July 1997 Rev 0 to Jm Farley Nuclear Plant Unit 2, P/T Limits Rept ML20148R7621997-05-31031 May 1997 Spent Fuel Rack Criticality Analysis Using Soluble Boron Credit ML20141D9721997-05-13013 May 1997 Jm Farley Unit 1 Alternate Plugging Criteria Return to Power Rept ML20135C9811997-02-14014 February 1997 Power Uprate Project BOP Licensing Rept ML20198E8431996-12-31031 December 1996 Non-proprietary Rev 1 to NSA-SSO-96-525, Jm Farley Nuclear Safety Analysis IR Neutron Flux Reactor Trip Setpoint Change ML20137N3991996-12-31031 December 1996 10CFR50.46 ECCS Evaluation Model 1996 Annual Rept HL-6136, L* Criterion for Farley Unit 2 - Non-Proprietary1996-07-25025 July 1996 L* Criterion for Farley Unit 2 - Non-Proprietary L-96-158, Rev 2 to Jm Farley Nuclear Plant Units 1 & 2 Licensing Rept for TS Changes Associated W/Revised Core Limits,Revised Trip Setpoints & Inclusion of RAOC Control Strategy1996-05-31031 May 1996 Rev 2 to Jm Farley Nuclear Plant Units 1 & 2 Licensing Rept for TS Changes Associated W/Revised Core Limits,Revised Trip Setpoints & Inclusion of RAOC Control Strategy ML20108D4901996-04-19019 April 1996 Nonproprietary Version of Development of L* Criteria for Farley Unit 2 ML20097C3351996-01-31031 January 1996 Interim Plugging Criteria 90 Day Rept ML20086S4161995-07-31031 July 1995 Interim Plugging Criteria 90 Day Rept. Unit 2 ML20084J6621995-05-18018 May 1995 USI A-46 Summary Rept,Jm Farley Nuclear Plant Unit 1 ML20024J3441994-10-0505 October 1994 1 Cycle 12 IPC Assessment & Projected EOC-13 Slb Leakage. ML20071K9411994-07-31031 July 1994 Pressurizer Safety Line Piping & Support Evaluation Under Safety Valve Discharge Loading Jm Farley Units 1 & 2 ML20059H5211994-01-14014 January 1994 2 Cycle 9 IPC Assessment & Projected EOC-10 Slb Leakage ML20141M3571992-05-31031 May 1992 Pressurizer Safety Line Piping & Support Evaluation Under Safety Valve Discharge Loading,Jm Farley Unit 1 & Unit 2 ML20079M9151991-11-11011 November 1991 Industry Survey in Support of License Renewal Rulemaking Response Jm Farley Nuclear Plant,Alabama Power Co ML20217C4191991-03-31031 March 1991 Criticality Analysis of Farley Units 1 & 2 Fresh & Spent Fuel Racks ML20070L8451991-03-14014 March 1991 Joseph M Farley Nuclear Plant Simulator Certification Rept 1991 ML20062F9671990-11-30030 November 1990 Evaluation of Indication in J Farley Unit 2 Steam Generator C Upper Shell to Transition Cone Girth Weld ML20214S2331987-02-28028 February 1987 Demonstration of Conformance of Jm Farley Units 1 & 2 to App K & 10CFR50.46 for Large Break Loca ML20207G5651986-12-29029 December 1986 Crdr Summary Rept, in Response to NUREG-0737,Suppl 1 ML20210K4501986-09-30030 September 1986 Joseph M Farley Units 1 & 2 Safety-Related Motor-Operated Valve Differential Pressures for Auxiliary Feedwater Sys ML20210K4171986-08-31031 August 1986 Joseph M Farley Units 1 & 2 Safety-Related Motor-Operated Valve Differential Pressures for HPCI Sys ML20209D0391986-06-30030 June 1986 Demonstration of Conformance of Jm Farley Units to App K & 10CFR50.46 for Large Break Locas ML20133B2871985-09-16016 September 1985 Containment 5-yr Tendon Surveillance Rept, Vols 1 (Rept) & 2 (Data) ML20137M0331985-08-19019 August 1985 Inryco Post-Tensioning Div Jm Farley Nuclear Plant Anchor Head Investigation Operating Metallurgical Div Investigation 20617 ML20101S6761985-01-31031 January 1985 Design Process of Farley Status Tree Monitoring Sys Displays ML20101S6841985-01-31031 January 1985 Safety Analysis Background for Farley Units 1 & 2,Critical Safety Function Status Tree Monitoring Sys ML20092P3231984-06-29029 June 1984 Reg Guide 1.97, 'Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant & Environs Conditions During & Following Accident,' Compliance Rept ML20092G8961984-04-30030 April 1984 Fracture & NDE Evaluations for Closure Flange Regions of Comanche Peak Units 1 & 2 ML20087P8591984-03-30030 March 1984 Reg Guide 1.97 Compliance Rept, Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant & Environ Conditions During & After Accident, Vols 1-4 ML20087P7821984-03-21021 March 1984 Summary Rept,Nuclear Criticality Reanalysis for 4.3 W/O Fuel in New Fuel Storage Rack ML20080T2851984-01-25025 January 1984 Table of Pressurizer Design Data. Related Info Encl ML20087P9931983-12-31031 December 1983 Control Room Design Review Task Analysis Guideline ML20087P9911983-11-30030 November 1983 Control Room Design Review Survey Development Guideline ML20087P9871983-09-30030 September 1983 Human Engineering Principles for Control Room Design Review ML20087P9841983-07-31031 July 1983 Control Room Design Review Implementation Guideline ML20064G7521982-12-31031 December 1982 Boron Concentration Reduction in Boron Injection Tank, Jm Farley Nuclear Plant,Units 1 & 2. Proposed Tech Specs Encl 1999-04-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P0761999-10-0606 October 1999 Non-proprietary, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217G0361999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20212E7451999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Hcgs,Unit 1.With Summary of Changes,Tests & Experiments Implemented During Aug 1999.With ML20216E4941999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Jmfnp.With ML20210T2161999-08-0606 August 1999 Draft SE Supporting Proposed Conversion of Current TS to ITS for Plant ML20211B2011999-08-0404 August 1999 Informs Commission About Results of NRC Staff Review of Kaowool Fire Barriers at Farley Nuclear Plant,Units 1 & 2 & Staff Plans to Address Technical Issues with Kaowool & FP-60 Barriers ML20210R6031999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20196J3791999-06-30030 June 1999 Safety Evaluation of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs. Rept Acceptable ML20209G0661999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With L-99-267, Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With L-99-023, Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with ML20206G7471999-05-0404 May 1999 Safety Evaluation Accepting Corrective Actions Taken by SNC to Ensure That Valves Perform Intended Safety Functions & Concluding That SNC Adequately Addressed Requested Actions in GL 95-07 L-99-020, Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20206C9461999-04-30030 April 1999 1:Final Cycle 16 Freespan ODSCC Operational Assessment L-99-161, Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20205N0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20204D7271999-03-15015 March 1999 ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jm Farley Nuclear Generating Plant,Unit 1 ML20207M6421999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20203A2651999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20199D8611999-01-12012 January 1999 SER Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20199E6591998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20206C8081998-12-31031 December 1998 Alabama Power 1998 Annual Rept ML20198K4091998-12-18018 December 1998 COLR for Jm Farley,Unit 1 Cycle 16 ML20198B2561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20195E2281998-11-16016 November 1998 Safety Evaluation Authorizing Relief Request for Second 10-year ISI Program Relief Request 56 for Plant,Unit 1 ML20195C9681998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20155E0271998-10-29029 October 1998 SER Approving & Denying in Part Inservice Testing Program Relief Requests for Plant.Relief Requests Q1P16-RR-V-3 & Q2P16-RR-V Denied Since Requests Do Not Meet Size Requirement of GL 89-04 ML20154B6121998-10-0101 October 1998 Safety Evaluation Granting Second 10-year ISI Requests for Relief RR-13 & RR-49 Through RR-55 for Jm Farley NPP Unit 1 ML20151V8341998-09-30030 September 1998 Non-proprietary Rev 2 to NSA-SSO-96-525, Jm Farley Nuclear Plant Safety Analysis IR Neutron Flux Reactor Trip Setpoint Change ML20154H6001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20154H0121998-09-30030 September 1998 Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion) ML20197C8991998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20237C5471998-08-20020 August 1998 Suppl to SE Re Amends 137 & 129 to Licenses NPF-2 & NPF-8, Respectively.Se Being Supplemented to Incorporate Clarifications/Changes & Revise Commitment for Insp of SG U-bends in Rows 1 & 2 for Unit 2 Only ML20236Y1121998-07-31031 July 1998 Voltage-Based Repair Criteria 90-Day Rept ML20237B1891998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20237A2181998-07-24024 July 1998 Jm Farley Unit 2 ISI Rept Interval 2,Period 3 Outage 1, Refueling Outage 12 ML20236U6141998-07-23023 July 1998 Safety Evaluation Authorizing Use of Alternative Alloy 690 Welds (Inco 52 & 152) as Substitute for Other Weld Metal ML20236R8671998-07-0909 July 1998 Safety Evaluation Concluding That Southern Nuclear Operating Co USI A-46 Implementation Program Has Met Purpose & Intent of Criteria in GIP-2 & Staff SSER-2 on GIP-2 for Resolution of USI A-46 ML20236M5981998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20154H0461998-06-30030 June 1998 Technical Evaluation Rept on Review of Farley Nuclear Plant IPEEE Submittal on High Winds,Flood & Other External Events (Hfo) ML20248M3121998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20247F3631998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20217D2591998-04-21021 April 1998 Safety Evaluation Accepting Licensee Proposed Alternative Re Augmented Exam of Reactor Vessel Shell Welds for Plant ML20247E8851998-03-31031 March 1998 FNP Unit 2 Cycle 13 Colr ML20217H3191998-03-31031 March 1998 Safety Evaluation Accepting Proposed Changes to Plant Matl Surveillance Programs ML20216D5941998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20217D4081998-03-24024 March 1998 Safety Evaluation Accepting Proposed Changes to Maintain Calibration Info Required by ANSI N45.2.4-1972 ML20216H6731998-03-17017 March 1998 SER Accepting Quality Assurance Program Description Change for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20216J6851998-03-16016 March 1998 Revised Pages 58 & 59 to Fnp,Units 1 & 2,Power Uprate Project BOP Licensing Rept ML20216D9811998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Jm Farley Nuclear Plant,Units 1 & 2 1999-09-30
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to the spent fuel pool 10 days after the emergency shutdown.
- 3. 1C5'E component cooling water temperature.
Results:
No. of Total Spent Fuel Cooling Trains Heat Load Pool Bulk Operation (108 Bru/hr) Temperature (*F)
- 1 30.384 158 2 30.384 131 i The computer code BPCOL is'used to analyze the natural l circulation cooling of the spent fuel in the event of a loss of all external means of cooling for the spent fuel pool. BPCOL is a proprietary program of NAI. The code is based on the assumption that boiling takes place near the top of the fuel channel. BPOOL evaluates the saturation properties of the
, coolant on the basis of the static pressure at the top of the storage racks. These properties include water density, temperature, and steam density.- The steam is assumed to separate and flow out of the pool. 13ut water at the saturation j temperature corresponding to the pressure at the top of the racks flows downward to the inlet of the storage racks. The' static pressure at this location is higher than the pressure at the top of the storage racks and as a result the fluid is subcooled as it enters the fuel assembly. The fluid becomes less dense as it passes up the fuel channel. Near the top of I the fuel channel the fluid reaches saturation conditions and net boiling occurs. The computer code, BPOOL, assumes a loss of all external means of cooling, but it should be noted that the Farley spent fuel pool cooling system is redundant and single failure-proof.
Under normal conditions, voiding between fuel assemblies is highly unlikely because these spaces are not sealed to keep out water.
l Holes are provided at the top and bottom of each inner can to permit a definitive flowpath for circulation of water in these spaces.
III.l.5.(4) Potential Fuel and Rack Handling Accidents l The high-density poison racks are of a free-standing design, l utilizing bottom support pads, resting on the flocr of the spent fuel pool. The installation of the high-density racks will include removal of the existing 13-in. center storage i
racks. The high-density racks will be installed dry' since E l there is no fuel in the storage pool. l l The following is a sequence of events for installing the high-density poison racks.
Phase I Install and test a temporary crane for handling the existing racks and the high-density racks. The 8204260 g III-7 AMEND 3 4/82 Corrected page
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