App 5B to Davis-Besse PSAR, Descriptions of Load Factors for Shield Bldg & Containment Internal Structure Design.ML19319C275 |
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Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
08/01/1969 |
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From: |
TOLEDO EDISON CO. |
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References |
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NUDOCS 8002110750 |
Download: ML19319C275 (4) |
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Category:PRELIMINARY SAFETY ANALYSIS REPORT & AMENDMENTS (PSAR
MONTHYEARML19317F5571970-05-12012 May 1970 Amend 5 to PSAR ML19319B3351970-04-29029 April 1970 Amend 4 to PSAR ML19319C2731969-08-0101 August 1969 Chapter 5 of Davis-Besse PSAR, Containment. Includes Revisions 1-8 ML19319C2681969-08-0101 August 1969 Chapter 13 to Davis-Besse PSAR, Initial Tests & Operation. ML19319C2751969-08-0101 August 1969 App 5B to Davis-Besse PSAR, Descriptions of Load Factors for Shield Bldg & Containment Internal Structure Design. ML19319C2511969-08-0101 August 1969 Suppl 1 to Davis-Besse PSAR, Formal Questions from Div of Reactor Licensing & Applicants' Responses;Informal Questions from Div of Reactor Licensing & Applicants' Responses; & Discussion of Items in ACRS 700820 Ltr. ML19319C2541969-08-0101 August 1969 Chapter 8 to Davis-Besse PSAR, Electrical Sys. Includes Revisions 1-8 ML19319C2561969-08-0101 August 1969 Chapter 9 to Davis-Besse PSAR, Auxiliary & Emergency Sys. Includes Revisions 1-8 ML19319C2581969-08-0101 August 1969 Chapter 10 to Davis-Besse PSAR, Steam & Power Conversion Sys. Includes Revisions 1-8 ML19319C2631969-08-0101 August 1969 Chapter 11 to Davis-Besse PSAR, Radwastes & Radiation Protection. Includes Revisions 1-8 ML19319C2651969-08-0101 August 1969 Chapter 12 of Davis-Besse PSAR, Conduct of Operations. Includes Revisions 1-8 ML19319C2691969-08-0101 August 1969 Chapter 14 to Davis-Besse PSAR, Safety Analysis. Includes Revisions 1-8 ML19319C2701969-08-0101 August 1969 Chapter 15 of Davis-Besse PSAR, Tech Specs. Includes Revisions 1-8 ML19319C2721969-08-0101 August 1969 Chapter 4 of Davis-Besse PSAR, Rcs. Includes Revisions 1-8 ML19319C2891969-08-0101 August 1969 Chapter 3 to Davis-Besse PSAR, Reactor. Includes Revisions 1-8 ML19319C2741969-08-0101 August 1969 App 5A to Davis-Besse PSAR, Design Bases for Structures,Sys & Equipment. ML19319C2761969-08-0101 August 1969 App 5D to Davis-Besse PSAR, Justification for Yield Reduction Factors (0-Factors) Used in Determining Yield Strength of Shield Bldg & Containment Internal Structures. ML19319C2781969-08-0101 August 1969 Chapter 7 of Davis-Besse PSAR, Instrumentation & Control. Includes Revisions 1-8 ML19319C2771969-08-0101 August 1969 Chapter 6 of Davis-Besse PSAR, Engineered Safety Features. Includes Revisions 1-8 ML19319C2801969-08-0101 August 1969 Chapter 1 of Davis-Besse PSAR, Introduction & Summary. Includes Revisions 1-8 ML19319C2811969-08-0101 August 1969 App 1A of Davis-Besse PSAR, Technical Qualifications. ML19319C2821969-08-0101 August 1969 App 1B of Davis-Besse PSAR, QA Program. ML19319C2831969-08-0101 August 1969 App 1C of Davis-Besse PSAR, Project Staff. ML19319C2841969-08-0101 August 1969 Chapter 2 of Davis-Besse PSAR, Site & Environ. Includes Revisions 1-8 ML19319C2851969-08-0101 August 1969 App 2A to Davis-Besse PSAR, Lake Restricted Areas. ML19319C2861969-08-0101 August 1969 App 2B to Davis-Besse PSAR, General Meteorology. ML19319C2871969-08-0101 August 1969 App 2C to Davis-Besse PSAR, Geology,Seismology,Subsurface Conditions & Preliminary Foundation Design Criteria, Dtd 690718.Prepared for Util Per General Direction of Bechtel Corp ML19319C2881969-08-0101 August 1969 App 2D to Davis-Besse PSAR, Hydrological Surveys for Davis-Besse,Locust Point Region,Part I General Studies, Part II Currents & Dilution. Prepared for Util 1970-05-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 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 Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20195D0001998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With ML20237E3171998-08-21021 August 1998 ISI Summary Rept of Eleventh Refueling Outage Activities for Davis-Besse Nuclear Power Station ML20237B1681998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236U5011998-07-23023 July 1998 Special Rept:On 980624,Unit 1 Site Damaged by Tornado & High Winds.Alert Declared by DBNPS Staff,Dbnps Emergency Response Facilities Activiated & Special Insp Team Deployed to Site by Nrc,As Result of Event ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A4121998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20196B5221998-05-23023 May 1998 10CFR50.59 Summary Rept of Facility Changes,Tests & Experiments Dbnps,Unit 1 for 960602-980523 ML20236E7581998-05-19019 May 1998 Rev 0 to Davis-Besse Unit 1 Cycle 12 Colr ML20236N7501998-04-30030 April 1998 Rev 2 to Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit ML20247F6721998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Davis-Bess Nuclear Power Station,Unit 1 ML20249A4141998-04-30030 April 1998 Revised Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20217P8041998-04-0707 April 1998 11RFO OTSG ECT Insp Scope ML20216B4041998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Davis-Besse 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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D-B APPENDIX 5B DESCRIPTIONS OF LOAD FACTORS FOR SHIELD BUILDING AND CONTAINMENT INTERNAL STRUCTURE DESIGN The following are descriptions for load factors used in the design equations in Section 5.2.2 5, and in Section 5.2.3 1 Dead Load:
The dead load factor for the shield building design will be 1.0 in combination with the other factored loads. The reason for using this load facter instead of those suggested by ACI-318-63 code is that the code is written for general types of construction. Since the dead weight of the shield building can be accurately determined because of its simple geometric configuration, a load factor of 1.0 is justified.
A factor ef 1.0 is also justified for the internal structure 3 since the most unpredictable dead loads such as the major equipment loads are excluded from the dead load, and considered separately. During operating and shutdown conditions the centainment internal structure will be investigated according to ACI-318-63 code, and the dead load factor vill be 7
15
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2 Live Load:
The live load that would be present along with accident, seismic and wind loads would produce a very small portion of the stress at any point. Also, it is extremely unlikely that the full live load would be pr ssent over a large area at the time of an unusual occurrence. For these reasons a low load factor is felt to be justified and live load will be considered together with dead load at a load factor 1.0.
3 Earthouake Loads:
For the maximum probable (smaller) earthquake of 0.08 g ground
, acceleration, a factor of 1.25 is used in combination with the other factored loads in designing both the shield building and the containment internal structure. The selection of this load factor is in agreement with past and current practice of concrete containment design for nuclear power plants and also the ACI-318-63 code. Under the condition of maxi =um possible (larger) earthquake of 0.15g ground acceleration a factor of 1.0 vill be used both for the shield building and the containment internal structure.
y 0354 M
5B-1 Amendment No. 3
D-B l
The fat e of unity is consistent with the loading condition '^
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which i to demonstrate no loss of function under a maximum possible (larger) loading condition.
k Wind Load:
The shield building vill be designed to withstand the vind load and the associated pressures. The design load factor vill be 1.25 in combination with the other factored loads in accordance with the ACI-318-63 code.
5 Tornado Load:
The shield building vill be designed to withstand the tornado load and the associated pressure differential vi,sout loss of function. A load factor of 1.0 vill be used and is consistent with the loading condition and vill demonstrate no loss of func-tion under a maximum hypothetical condition.
6 Temnerature Load:
The shield building and the containment internal structure vill be designed for ther=al loads (temperature gradients) in combina-tion with the other factored loads. Accurate extremes can be determined in establishing the temperature gradient through walls, do=e, and slabs. Therefore a thermal load factor of unity with variations of + 5 percent and + 10 percent may be used for the shield building and containment internal structure respectively.
The variations in load factors are consistent with the degree of structural complexities in the relative structures, and are considered in the same category as dead loads.
7 Loss of Coolant Accident Lead:
The steel containnent vessel practically isolates the shield building from the reactor coolant systems and therefore eliminutes significant pressura and temperature loads on the shield building during an accident. However, small pressure buildups and tempera-ture changes do occur in the annulus during the accident. These vill be taken into account in design. The load factor for LOCA vill be 1.0 in co=bination with the other factored loads. The shield building vill also be analyzed for one and one-half times the LOCA load for no loss of function. (
8 Equipment Load:
The equipment loads in the containment internal structure are separated from the dead load so that more reasonable load factors can be assigned to the equipment dt a weight. A factor of 1.5 is used for equipment load during operating and shutdown condi-tions in accordance with the ACI-318-63 code. Otherwise, a factor of 1.25 is assigned to allow for inaccuracy resulting 3 from weight calculations and load distributions. For the case of ,
I:.aximum possible (larger) earthquake, a factor of unity is assigned to the equipment load.
g 5B-2 03E5
D-B p 9 Miscellaneous Loads: -
During a loss of coolant accident, the containment internal structure will be subjected to such accident loads as pressure, thermal, missile, jet force, and piping anchor loads. Load factors are assigned to different load sources in loading combi-nations as shown in Section 5.2.2.3. The losd factors are assigned recognizing the degree of accuracy available in determining the loading and also the unlikely combination of simultaneous load occurrences.
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