ML19326A130
ML19326A130 | |
Person / Time | |
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Site: | Davis Besse ![]() |
Issue date: | 10/23/1978 |
From: | TOLEDO EDISON CO. |
To: | |
Shared Package | |
ML19326A128 | List: |
References | |
NUDOCS 8002030010 | |
Download: ML19326A130 (1) | |
Similar Documents at Davis Besse | |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20207E8011999-05-19019 May 1999
[Table view]Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20217P8041998-04-0707 April 1998 11RFO OTSG ECT Insp Scope ML20196B8771996-12-16016 December 1996 First Amended & Restated Master Decommissioning Trust Agreement Dtd as of 961231 Between Toledo Edison Co & Mellon Bank ML20196B8951996-12-16016 December 1996 First Amended & Restated Master Decommissioning Trust Agreement Dtd as of 961216 Between Cleveland Electric Illuminating Co & Mellon Bank ML20134D7821996-05-0808 May 1996 Rev 1 to Instrument Drift Data Analysis Methodology & Assumptions ML20091S4311995-08-31031 August 1995 USI A-46 Seismic Evaluation Rept. W/61 Oversize Drawings ML20138J1411994-02-28028 February 1994 Rev 0 to IPEEE,A-46 & Design In-Structure Response Spectra for Selected Bldgs at Dbnps ML20067D3311993-08-31031 August 1993 Technical Evaluation Rept,Evaluation of B&Wog Pressurizer Surge Line Thermal Stratification Program to Address NRC Bulletin 88-11 ML20091P5721991-10-31031 October 1991 Reactor Containment Bldg Integrated Leak Rate Test Including,Type A,B & C Periodic Test Results ML20070Q1911991-03-25025 March 1991 NRC Form 474 Simulation Facility Certification ML20058L1891990-08-0101 August 1990 Dcrdr Human Engineering Discrepancy Repts 1988 Summary Addendum 1,Vol 1 ML20006E3671990-01-11011 January 1990 Toledo Edison Co Mark-BZ Fuel Assembly Seismic & LOCA Analysis. ML20094J0841989-12-0808 December 1989 Investigation of Acoustic Leak Monitoring for NRC Region Iii. Info Partially Deleted ML19324C1761989-10-30030 October 1989 Hpi/Makeup Nozzle Weld Overlay Repair Contingency Plan. ML19327B0161989-10-11011 October 1989 Cycle 7 LOCA Limits. ML20245K6751989-08-0202 August 1989 Rev 2 to Review 18 Month PM Items for Diesel Generator & Evaluate Extension to 30 Months ML20151Z1941988-08-11011 August 1988 Rept on Reactor Vessel Continuous Vent Line Performance, ML20234F2501988-01-0606 January 1988 Rev 3 to App R Compliance Assessmemt Rept ML20147C0851987-12-0101 December 1987 Fifth Refueling Outage Executive Summary. Related Documents Encl ML20237J9781987-08-24024 August 1987 Performance Indicators for Davis-Besse Nuclear Power Station,Salp 6,Weekly Rept 3 for Period Ending 870824 ML20214J1891987-05-0505 May 1987 Rev 2 to App R Compliance Assessment Rept ML20206J5001987-03-31031 March 1987 Dcrdr Special Study Plans for Davis-Besse ML20212G7461987-01-0707 January 1987 Rept of Emergency Evacuation Review Team on Emergency Response Plans for Perry & Davis-Besse Nuclear Power Plants ML20214E0761986-11-17017 November 1986 Auxiliary Feedwater Calculation Summary ML20211E0651986-09-26026 September 1986 Transient Assessment Program Rept,Davis-Besse Unit 1 Reactor Trip on High Flux,840302 ML20214T7501986-09-11011 September 1986 DB Small-Break LOCA Analysis Assumptions Evaluation ML20154Q6531986-02-28028 February 1986 Westinghouse Owners Group Position on Davis-Besse Event ML20141E6691985-11-30030 November 1985 B&W Owners Group Action Plan for Review of 850609 Davis-Besse Transient ML20138H4891985-11-25025 November 1985 Rev 17 to Seismic Category I Piping Sys Support & Hanger Discrepancies ML20136H0951985-11-15015 November 1985 Revised Davis-Besse Reactor Protection Sys Single Failure Analysis ML20137H3971985-11-12012 November 1985 Rev 16 to Seismic Category I Piping Sys Support & Hanger Discrepancies Summary Rept ML20137S9031985-10-29029 October 1985 Toledo Edison Davis-Besse Nuclear Power Station Unit 1 Seismic Category I Piping Sys Support & Hanger Discrepancies,Summary Rept ML20209H5861985-10-28028 October 1985 Rev 3 to Course of Action ML20137S8241985-10-22022 October 1985 Rev 14 to Seismic Category I Piping Sys & Hanger Discrepancies,Summary Rept ML20209H6481985-10-15015 October 1985 Rev 3 to Auxiliary Feedwater Pump Turbine Overspeed Trip Throttle Valve Problem ML20138J4811985-10-15015 October 1985 Seismic Category I Piping Sys Support & Hanger Discrepancies ML20133M9911985-10-0808 October 1985 Rev 12 to Seismic Category I Piping Sys Support & Hanger Discrepancies,Summary Rept ML20133K9881985-10-0404 October 1985 Independent Mgt Assessment of Toledo Edison Davis-Besse QA Program ML20138A9411985-09-24024 September 1985 Rev 10 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20132E4471985-09-17017 September 1985 Rev 9 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20137C3021985-09-0909 September 1985 Toledo Edison Co Davis-Besse Nuclear Power Station Course of Action Rept ML20137M5431985-09-0909 September 1985 Vols 1 & 2 of Davis-Besse Course of Action ML20135D7421985-09-0303 September 1985 Rev 7 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20133K9941985-08-30030 August 1985 Rept of Assessment of Actions at Davis-Besse Resulting from 850609 Loss of Feedwater Event ML20134Q0161985-08-27027 August 1985 Rev 6 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20137U3061985-08-16016 August 1985 Rev 5 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20134B8371985-08-0909 August 1985 Rev 4 to Safety-Related Piping Sys Support & Hangar Discrepancies, Summary Rept ML20133M3261985-07-26026 July 1985 Rev 3 to Safety-Related Piping Sys Support & Hanger Discrepancies,Summary Rept ML20126L9021985-07-0505 July 1985 Rev 1 to Action Plans 5,6 & 7, Steam & Feedwater Rupture Control Sys Trip/Msiv Closure 1999-05-19 Category:TEXT-SAFETY REPORT MONTHYEARML20217K1231999-10-14014 October 1999
[Table view]Revised Positions for DBNPS & Pnpp QA Program ML20217D5441999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20210Q8541999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20209E6231999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20195F4871999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20207F4351999-05-0404 May 1999 Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504 ML20206M6341999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Davis-Besse Nuclear Station,Unit 1.With ML20205M2931999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Davis-Besse Nuclear Power Station.With ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206B0101998-12-31031 December 1998 1998 Annual 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Nuclear Power Station,Unit 1 ML20216C5131998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20202D3721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20199G6321998-01-26026 January 1998 Rev 1 to Davis-Besse Unit 1,Cycle 11,COLR ML20198R4771998-01-13013 January 1998 SER Approving Second 10-year Interval Inservice Inspection Program Plan Requests for Relief for Davis-Besse Nuclear Power Station,Unit 1 ML20198K7931997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20217K6401997-12-31031 December 1997 1997 Annual Rept First Energy ML20203A3931997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Davis-Besse Nuclear Power Plant,Unit 1 ML20198S5371997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Davis-Besse Nuclear Power Station ML20217H7701997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20216H3261997-08-31031 August 1997 Monthly Operating Rept for August 1997 for DBNPS ML20217K0241997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Davis Besse Nuclear Power Station,Unit 1 1999-09-30 |
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DB-1 SAFETY EVALUATION The as-measured one pump coastdown curva determined for the Davis-Besse Nuclear Fower Station Unit No.1 Reactor Coolant Pumps is more restrie-tive than the design coastdown curve which was used in the original safety analyses. For Fuel Cycle 1 prior to the removal of orfice rod assemblies (ORA) it was not necessary to change the nuclear parameter limits because the effect of the actual coastdown curve was more than offset by the excess reactor coolant flow. For Cycle 1 af ter the removal of ORA, 5% of the 8% excess flow is being used to compensate for the lower flow through the core. A new analysis has been therefore been performed using a more restrictive pump coastdown curve. This new
analysis results in the changes to the Reactor Core Safety Limit Curve (Figure 2.1-1 of the Technical Specifications), the Reactor Ptotection System Instrumentation Trip Setpoints (Table 2.2-1 and Figures 2.2-1 and 2.2-2) and associated bases. Also, the maximum Reactor Coolant Eat Leg Temperature was reduced for DN3 Margin (Table 3.2-1). These new Techni-cal Specifications, determined by performing the appropriate Safety Analysis using the more restrictive pump coastdown curve, are mora conservative than the previous specifications and do not present any unreviewed safety questions.
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