ML20054E418
ML20054E418 | |
Person / Time | |
---|---|
Site: | Oyster Creek |
Issue date: | 06/08/1982 |
From: | Barrett D FRANKLIN INSTITUTE |
To: | Persinko D NRC |
Shared Package | |
ML20054E419 | List: |
References | |
CON-NRC-03-79-118, CON-NRC-3-79-118, TASK-03-02, TASK-3-2, TASK-RR TER-C5257-402, NUDOCS 8206110193 | |
Download: ML20054E418 (49) | |
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WIND AND. TORNADO LOADINGS (SEP, III-2) m- .
JERSEY CENTRAL' POWER.AND B GHT COMPANY OYSTERTCREEKENUCLEAR GENERATING STATION- -
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4 TECHNICAL EVALUATION REPORT 4
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WIND AND TORNADO LOADINGS (SEP, III-2) 1 JERSEY CENTRAL POWER AND LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION 1
1 NRC OOCKET NO. 50-219 MC PROJECT C5257 NRC TAC NO. 41606 FRC ASSIGNMENT 14 NRC CONTR ACT NO. NRC-03-79-118 FRC TASK 402 i
l Prepared by Franklin Research Center Author: D. J. Barrett
, 20th and Race Street R. Agarwal 1 Philadelphia, PA 19103 FRC Group Leader: D. J. Barrett
- i
'j Prepared for Nuclear Regulatory Commission Washington, D.C. 20555 Lead NRC Engineer: D. Persinko l
i June 8, 1982 This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, ex-pressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.
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_ . . . Franklin Research Center A Division of The Franklin Institute The Beniamen Frankhn Parmway. Phila.. Pa 19103(215)448-1000
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iJ l1 i) l CONTENTS l
Section Title Page 1 INTRODUCTION . . . . . . . . . . . . . 1
.1 1.1 Purpose of Review . . . . . . . . . . . 1 I
i 1.2 Generic Issue Background . . . . . . . . . 1 1
- . 1.3 Plant-Specific Background . . . . . . . . . 1
'l l 2 REVIW CRITERIA. . . . . . . . . . . . . 4 k
.j 3 TECHNICAL EVALUATION . . . . . . . . . . . 7 j 3.1 General Information . . . . . . . . . . 7 3.2 Reactor Building . . . . . . . . . . . 10 3.3 Ventilation Stack . . . . . . . . . . . 12 4 CONCLUSIONS . . . . . . . . . . . . . '14 -
5 REFERENCES . . . . . . . . . . . . . 16
- j. APPENDIX A - REACTOR BUILDING DESIGN REVIEW CALCUIATIONS l APPENDIX B - VENTIIATION STACK DESIGN REVIN CALCUIATIONS l
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TER-CS257-402 i
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, This Technical Evaluation Report was prepared by Franklin Research Center i
under a contract with the U.S. Nuclear Regulatory Commission (Office of l Nuclear Reactor Regulation, Division of Operating Reactors) for technical assistance in support of NRC operating reactor licensing actions. The l technical evaluation was conducted in accordance with criteria established by the NRC.
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- 1. INTRODUCTION
. I, l.1 PURPOSE OF REVIEW In the Systematic Evaluation Program (SEP), licensees are required to establish the ability of Class I structures to safely withstand a high wind or tornado strike. Af ter conducting an appropriate investigation, licensees g report the conclusions in a safety analysis report (SAR). The purpose of the present review is to provide a technical evaluation of the SAR prepared by the Jersey Central Power and Light Company (JCP&L) for the Oyster Creek Nuclear Generating Station [1] .
1.2 GENERIC ISSUE BACKGROUND Some operating nuclear plants were designed on the basis of local l building codes which did not consider the effects of the high wind speeds of tornadoes. Since the construction of these plants, research has led to an understanding of the various phenomena that occur during a tornado strike, and this knowledge has been incorporated into the definition of a design basis tornado (DBT) in Nuclear Regulatory Guide 1.76 (2]. Due to the concern regarding the extent to which older nuclear plants can satisfy DBT licensing
- criteria, the Nuclear Regulatory Commission (NRC) , as part of the SEP, 3
initiated Topic III-2, " Wind and Tornado Loadings," to investigate and assess the structural safety of existing designs against current requirements.
Licensees are required to prepare an SAR addressing the concern of SEP l Topic III-2. The SAR should identify the limiting elements of the structural I
design and specify the loading conditions and threshold wind speeds at which buildings and components fail. As part of Assignment 14, Franklin Research Center (ERC) is assessing the adequacy and accuracy of the SARs. Typical items that are reviewed are the tornado load calculations and combinations, the structural acceptance criteria, and the method of analysis. In order to verify the conclusions on structural strength, an independent tornado analysis on a sample of Class I structures and components is also conducted.
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1 0 1.3 PLANT-SPECIFIC BACKGROUND l.l The review of the Oyster Creek SAR was begun in April 1982. Prior to a
i that time, JCP&L responded to NRC requests for information by providing
) architectural-engineering structural drawings. Additional sources of
- information were a JCP&L letter on the SEP structural topics (3] and the plant l final safety analysis report (4] . The conclusions stated by JCP&L in the SAR 3 are summarized in Table 1. Correspondence with NPC [5] established the j reactor building and ventilation stack as the priority review structures.
1 The original wind loading criteria of the Oyster Creek structural systems were the structural load provisions of the American Standard Association codes
- that were in effect at the time of plant design. These provisions called for j a graded wind load of 30 psf at a 30 ft elevation, to 45 psf at elevations above 100 f t. The structural acceptance criteria permitted stress levels at a -
33-1/3% increase over code allowables. The criteria for this review are t
,, stated in Section 2 of this report.
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j Table 1. Summary of Conclusions from Oyster Creek Topic III-2 SAR*
1 Wind Pressure Class I Structures M (ps i) j Reactor Building Exterior Concrete Walls 300 2.0
'I Reactor Building Insulated Metal Siding 160 0.53
.] Reactor Building Roof Decking 280 0.96 1 Reactor Building Steel for Craneway
'j Enclosure 190** 0.68 i Control Room - North Wall 160 0.53 Remainder 300 2.0 Intake Structure 300 2.0 Ventilation Stack 180 2.0 Battery Room (interior room)
Diesel Generator and Oil Tank Vaults 300 2.0 j *The table lists tne various Class I structures with their respective j maximum permissible wind velocity and depressurization values. The
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allowable stresses do not exceed 90% of yield for reinforcing steel and 85%
of the ultimate concrete strength and include the combined effect of dead loads plus normal operating loads.
pl ** Based on siding drag - without siding steelwork can withstand 300 mph.
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1 2. REVIEW CRITERIA
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The intent of code regulations is to ensure the safety of systems vital to the safe shutdown of a reactor. The General Design Criteria (GDC) of 10CFR50, Appendix A [6] regulate the designs of these safety systems; in particular, GDC 2 requires that structures housing safety-related equipment be able to withstand the effects of natural phenomena such as tornadoes. The j design basis must consider the most severe postulated tornado an well as the combined effects of tornado, normal, and accident conditions.
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Regulatory Guide 1.76 defines a DET in terms of the parameters of maximum l
wind speed, maximum differential pressure, rate of pressure drop, and core l
1 radius, given with respect to geographical location. The specified magnitudes of tnese regional parameters are the acceptable regulation levels, but additional analysis may be performed where appropriate to justify the selection of a less conservative DBT. In Reference 7, the NRC established the tornado parameters to be used in the SEP study of the Oyster Creek plant.
.; Regulatory Guide 1.117 [8] assists in the identification of structures
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? and systems that should be protected from the effects of a DBT. This regulatory position is elaborated in the Standard Review Plan (SRP), Section 3.3.2 (NUREG-0800) (9]. The analysis presented in this report is of a representative sample of safety-related structural systems at the Oyster Creek plant.
With the dynamic pressure and air flow assumptions from the SRP, Section 4
3.3.2, and with the aid of Reference 10, a velocity-pressure distribution model can be constructed from the DBT characteristics. The actual forces acting on a structure can be calculated from this model augmented by the experimental data reported in References 11 and 12. These forces arise from
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wind-induced positive and negative pressures as well as from differential pressures.
l! An additional tornado load is the impact of wind-borne missiles against
- 1 l structures. The potential missiles are identified in the missile spectrum of the SRP, Section 3.5.1.4 (13], while the particular missiles to be included 1
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I in this study were identified by the NRC as part of the SEP assignment (7].
j References 14 and 15 assist in the determination of the structural effects of missile impact, while the guidelines of the SRP, Section 3.3.2 indicate acceptable combinations of impact effects with the loads resulting from wind I,
and differential pressures.
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Since the DDT is considered an extreme environmental event, tornado-induced loads are part of the loading combinations to be used in extreme j environmental design (see Article CC-3000 in the ASME Holler and Pressure i Vesnel Code (16] and the SRP, Section 3.8.4 (17]). The structural ef fects of these loading combinations are determined by analysia; stresses are calculated either by a working stress or ultimate strength method, whichever la q appropriate for the structure under consideration. The ASME Code specifica-
, tions for an extreme environmental event permit the application of reserve j strength factors to allowable working stress design limits, and also permit t
local strength capacities to be exceeced by missile loadings (concentrated loads) provided that this causes no loss of function in any safety-related i systems.
- i The sources of criteria described above and other source documents used in the evaluation are listed below:
NRC Regulatory Guide 1.76, " Design Basis Tornado for Nuclear Pcwer l Plants " (2]
NRC Regulatory Guide, 1.117, " Tornado Design Classification" (8]
NUREG-0 800, Standard Review Plan Section 3.3.2, " Tornado Loadings " [9]
Section 3.5.1.4, " Missiles Generated by Natural Phenomena" (13]
i Section 3.5.3, " Barrier Design Procedures" (18]
j Section 3.8.1, " Concrete Containment" (19]
Section 3.8.4, "Other Seismic Category I Structures" (17]
Section 3.8.5, " Foundations" (20]
I l AISC Specification for Design, Fabrication and Erection of Structural
! Steel for Buildings (21]
l ACI-318-77, " Building Code Requirements for Reinforced Concrete" (22]
! ASME Boiler and Pressure Vessel Code,Section III, Division 2 (ACI-3 5 9) ,
! " Standard Code for Concrete Reactor Vessels and Containments" (16]
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- f NRC/SEB, " Criteria for Safety-Related Masonry Wall Evaluation,"
Structural Engineering Branch (1981) [23]
'4 ACI-307-79, " Specification for the Design and Construction of Reinforced
- Concrete Chimneys" [24] .
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. 3. TECHNICAL EVALUATION 3.1 GENERAL INFORMATION j The structures included in this review are the ventilation stack and the reactor building. These structures are classified seismically as Category I Nuclear Safety Related. The plan of the building arrangement and an isometric
.l j drawing of the Oyster Creek site are shown in Figures 1 and 2.
i The DBT characteristics taken as a basis for analysis are (unit abbreviations are from the SRP, Section 3.3.2) :
j Maximum wind speed 250 mph Maximum pressure drop 1.5 psi Rate of pressure drop 0.6 psi /sec Core radius 150 ft.
1 These enaracteristics yield a dynamic pressure of 160 psf. For applica-
] tion of this pressure to external flat surfaces of structures, the shape j coefficients are 0.80 for windward walls (positive pressure) , 0.50 for leeward l
l walls (suction), and 0.70 for roofs (suction) . The shape coefficient for the cylindrical ventilation stack is 0.70. Gust factors for tornado loadings are
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taken as unity.
4 The design basis missiles are C and "F from the Standard Review Plan, Section 3.5.1.4 missile spectrum, t1 Missile C: Steel rod: 1-in diameter, 3-f t length, 8-lb weight, 220 l'
I ft/sec velocity; strikes at all elevations.
Missile F: Utility pole: 13.5-in diameter, 35-f t length,1490-lb
, weight, 147 ft/sec velocity; strikes in a zone limited to l' 30 ft above grade.
{ The full effects of a tornado are experienced by the main structural l
members only if the skin of the building (walls, panels, roof decks, etc.) can properly transmit the associated loadings. For the purpose of analysis, the
{ most conservative circumstances of integrity or failure of these elements are assumed. For instance, a steel roof deck may fail when subjected to the DBT differential pressure. However, even thougn the roof deck failure provides l
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.j venting, the tornado loads are still assumed to exist so that the strength of
l other, stronger structural elements can be analyzed.
.j For most structures, a wind flow field acting at an angle to the surfaces of a building is not as demanding as a frontal attack because the elements l resisting lateral forces are oriented and framed so that the effects of
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,] adjacent wall loadings are uncoupled. Likewise, the action of windward face
- pressure and leeward face suction are uncoupled when their actions are
] resisted by separate structural elements. The most conservative loading cases
,! are chosen accordingly.
i The goal of analysis is to identify a structure's weakest members and to establish the threshold wind speed at which these members fdil the structural -
acceptance criteria (17] . This wind speed limit rating depends on the i
f postulated loading conditions. Once a limiting member-is identified, the loading conditions used to determine subsequent limiting members are in come i
cases modified to account for failure of the weaker member. Therefore, l conclusions about the streng th of structural components are, based on a l supposition of sequential failure.
The following are typical assumptions for the structural modeling in
, this report:
- 1. No snow load exists during a tornado strike. -
- 2. Thickened floor slabs can be used to transmit lateral loads.
- 3. Connections are designed in accordance with good engineering practice.
- 4. Unless noted otherwise, steel roof decking is assumed to remain intact.
L
. Additional assumptions are identified on the calculation sheets (s ee t
- appendices).
! 3.2 REACTOR BUILDING 3.2.1 Evaluation f
! The reactor building is primarily a reinforced concrete structure with the exception of a steel roof deck, which is supported by structural steel framing. Tne high point of this building is at elevation 169 f t 3 in, while i
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I TER-C5257-402
-; adjacent grade is at elevation 23 f t. The reactor building can be divided
. j, into two sections: the' main _section, which is below the service floor level
^
(elevation 119 f t 3 ini~, and -the service floor enclosure (above elevation 119 f t 3 in) .
~
1 .
The exterior of the main section consists of thick reinforced concrete i ,
' walls framing into the concrete floor slabs, beams, and columns. These q elements were examined for the critical load case of differential pressure
/ I
- loads. Each panel is assumed to transfer loads in the horizontal direction to j the nearest columns and in the vertical direction to the adjacent thickened
- - , floor slabs. The analysis of the panels can be found on pages A-12 through
- A-14 of Appendix A. Since the vertical section showed adequate reserve moment capacity, the capacity of a horizontal section was not calculated.
The concrete columns of the main section were checked for stability and l capacity. The critical members were chosen on the basis of the smallest section and least reinforcement.' The members selected were columns A-1 and
-l A-4 (see building . plan on pp.ge A-2) . The dead and live loads on the columns 5 ,
~ 'I .
' were trken as those values reported in Reference 4. The wind loads acting on
} the wall panels adjaceni: to the columns are transferred to the columns as reactions, producing moments in the columns. The columns are taken as supported between successive beam and floor slabs. The column analysis and l
calculation are given on pages A-1 through A-11.
- h. The service floor enclosura consists of insulated metal wall panels and
'1 UK 16-16 Q roof sections supported by a framework of columns and trusses. To 4
analyze the capacity of the roof uteel, the steel deck is assumed to remain intact. Also, wnen examining the capacity of the columns, it is assumed that the metal panels do not fail. The analysis of the structural steel elements of the service floor enclosure are presented on pages A-15 through A-21.
c.
-i 3.2.2 Conclus ion l
l]1 The reinforced concrete elements of the main section can safely withstand l
{ the tornado loadi.ngs. The limiting elements of the roof steel are the 12B19 i
- beams,. whicn have limit ratings of 0.131 psi (61 mph) for differential t
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i TER-C5257-402
't i
~l pressure, 26.7 psf .(102 mph) for totaado dynamic pressure, and 16.8 psf (68 f
-j sph) for high wind' dynamic presantc. The limiting elements of the roof
- 1 .
.l supports are the north and south sidersteel' columns which have a limit rating l of 1.07 psi (174 mph) for differential pressure, but can withstand the full 6
tornado and high wind dynamic presscres.
~
.l '
3.3 VENTIIATION STACK 3.3.1 Evaluation The ventilation stack is an unlined, free-standing axisymmetric reinforced concrete structure. The top of the stack is at elevation 391 f t with grade at elevation 23 ft. The outer diameter at the top is 9 f t 6 in with 6-in-thic< concrete. The outer diameter at the top of the foundation (elevation -3 f t) is 31 f t 8-3/4 in with 18-in-thick concrete. For
'l calculation of the diameter of the stack at intermediate sections, it is assumed that the outer surface is smooth. In the event of a tornado strike, the stack can be subjected to pressure as high as 112 psf, corresponding to a j 250 mph tornado and 0.7 shape factor.
The stack has been analyzed by a working stress design technique. This j method is given in the American Concrete Institute Code (ACI) 307-79 [24].
i Two sections, one at 233 f t and the other at 278.1 ft below the top of stack, were found to be the most critical. These sections were reanalyzed by i
increasing the allowable stresses in reinforcing steel to its yield strength
! (fy) and in concrete to 0.85 times the compressive strength (f'c). The stack analysis is given on pages B-1 through B-4 in Appendix B.
The section at 338.2 f t below the top of stack has three openings. For
- the purpose of analysis, the openings were grouped to form one equivalent gj .
opening, with an opening angle of 8 = 49.8*. Also, the sectica at 386.5 f t es below the top of stack, which is below grade, has two openings. These two openings were also grouped for the purpose of analysis yielding an equiv-alent opening angle of S = 42.l*. Additional reinforcement is provided around each opening. Analysis shows that even under the conservative assump-f tion of grouping the openings together, these sections are not the most
') 1 critical.
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TER-C5257-402 l
{ The foundation pedestal is hexagonal in shape with each side measuring 18
.j f t 7-1/2 in. The pedestal is a reinforced concrete block 7 f t thick, and f rests on a soil with a bearing capacity of 13 ksf. To determine the
, resistance to overturning moment, the axial stress due to the dead weight of q the stack and concrete pedestal, plus the flexural stresses due to the wind
- forces, were balanced against the soil bearing capacity. These calculations i
! are shown on pages B-5 to B-6.
3.3.2 Conclusion i
It was found that the stack cannot withstand the full tornado dynamic pressure. Using the allowable stresses in reinforcement and concrete, j according to ACI 307-79 [2 4] , it was found that the sections at 233 f t and 278.1 f t below the top of stack were limiting and can withstand a tornado dynamic pressure of only 48.8 psf at a 138 mph wind speed. Tne section at 278.1 f t below the top of the stack was found to be the limiting section when the code allowable stress was increased to 0.85 f'c in concrete and yield stress in reinforcing steel. For these increased stress levels, this section
, can withstand tornado dynamic pressure of 68.6 pef at a 164 mph wind speed.
The equilibrium model for the stack foundation shows that the foundation was not the limiting design component. The stack foundation can resist an overturning movement due to a dynamic pressure of 93.7 psf at a 191 mph wind speed.
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4
- 4. (DNCLUSIOtB
, The results of the tornado structural analysis for the reactor building and ventilation stack are summarized in Table 2.
I j
j Table 2. Strength Summary of the structural Components Analyzed
}
]j Wind Speed Structure Element
- Cause of Failure ** (mph)
Reactor Building 12B19 Roof Beams 3 68 2 61 1 102
) North and South Side 2 174 g Steel Columns d Concrete Walls and - -
1 Columns "
.I Ventilation Stack *** Concrete Shaft 1 13 8 (When analyzed by ACI 307-79 allowables)
Concrete Shaft 1 164
- (When analyzed
.j with increase in i allowable stresses) i i Concrete Foundation 1 19 1 1
. *The first element identified for each structure is the limiting element.
.i Additional elements that have been found to be inadequate are subsequently 1 lis ted. Note that this table does not imply that all inadequate elements have been identified or that entries are listed with respect to the most critical loading combination. Structural details not included in this
- l review are windows, doors, and roof decks.
- Key: 1 = tornado dynamic pressure; 2 = differential pressure; 3 = high wind dynamic pressure. Tangential wind speeds are listed for differential pressure failures.
- The resistance of the stack to circumferential stresses cannot be determined because the placement of the hoop reia.forcement is not known.
- 1 UUUU Franklin Research Center
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I TER-CS257-402 4
l It is pointed out that the roof deck itself was not analyzed but that the underlying structural support, the 12819 roof beams, were included in this
! study. Also, while the wall panels were not analyzed, the panel fasteners, girts, and panels of a comparable siding system reviewed in a previous study i (25] were found to have limited tornado loading resistance (limiting element failed at 48 mph wind speed for tornado differential pressure).
While not specifically reviewed, an additional area of concern is the control room, which is located on the east side of the turbine building (see
, Figure 2). The north and south walls of the control room are exposed to the atmosphere. The south wall and part of the north wall are constructed of reinforced concrete block, a structural component which typically has limited tornado resistance. The common wall (west) between the turbine building and the control room is also constructed of concrete block and has glass panels tnat will be subjected to differential pressure loadings with failure of the
- skin of the turbine building.
1 A comparison of Table 1 with Table 2 and the above comments shows that for other than the concrete structures, the strengths claimed for structural
- l. components in the Oyster Creek SAR are in conflict with and greater than the strengths found by the analysis presented herein.
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TER-C5257-402 1
-i f 5. REFERENCE 1
- 1. I. R. Finrock (JCP&L)
I4tter with Attachments to W. Paulson (NRC)
Subject:
Oyster Creek Nuclear Generating Station Systematic Evaluation Program May 7, 1981 Docket No. 50-219
]
) 2. " Design Basis Tornado for Nuclear Power Plants" NRC, April 1974 Regulatory Guide 1.76
- 3. I. R. Finrock (JCP&L)
Letter with Attachments to D. L. Zieman (NRC)
Subject:
SEP Structural Topics December 7,1979 Docket No. 50-219
- 4. Oyster Creek Nuclear Generating Station Final Safety Analysis Report
- 5. D. J. Barrett (FRC)
Informal Technical Communication to D. Persinko (NRC)
Subject:
Comments of the Change of Scope: Tasks 401 and 402
.;: April 7, 1981 i
i 6. Code of Federal Regulations, Title 10, Part 50 Appendix A, " General Design Criteria" l
, 7. E. J. Butcher (NRC)
} Letter to S. P. Carfagno (FRC)
Subject:
Tentative Work Assignment P April 23, 1981 I
, 8. " Tornado Design Classification"
} NRC, Rev. 1, April 1978 l Regulatory Guide 1.117
- 9. Standard Review Plan Section 3.3.2, " Tornado Loadings" NRC, July 1981 NUREG-0800 f 10. Mcdonald, J. R., Mehta, K. C., and Minor, J. E.
" Tornado-Resistant Design of Nuclear Power Plant Structures" Nuclear Saf ety, Vol.15, No. 4, July-August 1974
.j.
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- 11. " Wind Forces on Structures"
~
New York: Transactions of the American Society of Civil Engineers,
! Vol. 126, Part II, 1962
-l ASCE Paper No. 3269 l
- 12. " Building Code Requirements for Minimum Design Loads in Buildings and
' 'j Other Structures"
. New York: American National Standards Institute,1972 j ANSI A58.1-1972 i
i 13. Standard Review Plan i Section 3.5.1.4, " Missiles Generated by Natural Phenomena" j NRC, July 1981
] NUREG-0800 i
- 14. Williamson, R. A. and Alvy, R. R.
"Dopact Effect of Fragments Striking Structural Elements"
.j Holmes and Naruer, Inc.
Revised November 1973 i
) 15. " Full-Scale Tornado-Missile Impact Tes ts" i Palo Alto, CA: Electric Power Research Institute, July 1977 Final Report NP-440, Project 399 I
- 16. ASME Boiler and Pressure Vessel Code,Section III, Division 2 .
,f
, " Standard Code for Concrete Reactor Vessels and Containments"
{ New York: American Society of Mechanical Engineers,1973 ACI-359 4 17. Standard Review Plan Section 3.8.4, "Other Seismic Category I Structures" l NRC, July 1981
^
- 18. Standard Review Plan Section 3.5.3, " Barrier Design Procedures" i
NRC, July 1981 i NUREG-0800 1
.] 19. Standard Review Plan j Section 3.8.1, " Concrete Containment"
'j NRC, July 1981 NUREG-0800
- 20. Standard Review Plan Section 3.8.5, "Founda tions" NRC, July 1981 NUREG-0800 O
ULO Franklin Research Center acm .on w n . Fr.nanin a,.
.._.:. ..i ._;....~...u..._.-.._- . - . - _ . - . - - . _ . . - - - ~ . . . - - . - . - - ~ . .
4 TER-CS257-402
- 21. Specification for Design, Fabrication and Erection of Structural Steel for Buildings New York: American Institute of Steel Construction,1978
- 22. " Building Code Requirements for Reinforced Concrete" De troit: American Concrete Institute,1977 l ACI 318-71
- 23. Criteria for Safety-Related Masonry Wall Evaluation NRC, Structural Engineering Branch, 1981
- 24. " Specification for the Design and Construction of Reinforced Concret.(
Chimneys" American Concrete Institute,1979 ACI 307-79
- 25. FRC Technical Evaluation Report
- Wind and Tornado Loadings, Robert Emmett Ginna Nuclear Power Plant" December 2, 1981 TER-C5257-400
}
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I APPENDIX A I
REACTOR BUILDING DESIGN REVIEW CALCULATIONS A
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Franklin Research Center A Division of The Franklin Institute 1
The Bengmm Frankhn Parmway. Phda . Pa. 19103 (215) 448 1000 1.
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Title REAC. Tog. E,0lLbIMG - R Ell & . Cg N C . - &ELN SEWIc6 F L. ELEV 111'y 1
1 l New FtND TH E Ac;ruht. MONENTS trp THE j coLO M tJS
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Sc ic nc.e. We.utrc\ A 7.is x-e Ec d Le vEj j d > 35" 4
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- 9. I, i 10 59
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Now we. find the a llc wo ble. axic) lea d Pm Ecc ba la nced cond ition
, born gre.sst on k* O. 8 5 Ic, (0. 85 Ab) D
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1 FORM CS-FRC-81
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- 3 x 4
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x x
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! % x 1
910 : 7 8. 03 >< - 2 4 9. lo + 2 71. 4 4 ( 2 g. 2_; _(;g _ gy) x .
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i 1
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! 0= 7 8.o3 x ' - 35 5. 2 8 >c - / o s o ro . / 6 1
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2 (78.os)
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=
576.68 x,ps 1
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= /b O. 5 9 $195 i; FORM CS FRC-81 i
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3.Division,of ._Th,e Frankhn insutute 4PR/L ,teF2.EIf
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= Il03.] tb-o.6S(14.14) . IS(MG.8
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'h g . jtD[ C. Da R n. Date 8EAcToA BLDCr. - CAPACIT'l trP C.at. .
Skue ca1.upra sEc TInJ, Hhs INcREM Eh REJMFWCwENT.
Fog 29 bars of
- 11 (9 bars insicad of 7 )
T= (2,i.55, 4o) + 6 eo.4 + 2 ir. 44 (is -3) x B il.1 + 2,144 ( 18 - x )
x Os
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= 7 o /. 4- 8 M= 29 496. 76 + /s(2 s 12 A .e ) 332. 40. 76 x in ch M = 2 77o / " f* > hlcct
= qu.4nx-p
,, 0K FORM CS-FRC-81
4 i #h " *'0 25 c.515 7- ol '* 4 '! U ] Franklin Research Center o. .
o.,, =a n o.i.
y A D.ivision,of
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! ^?:3?l"i.["k'"!"',%iEY Rh MDt. 'c chf3 3/r Title REACTGR 60ILbtMG - &ACT C I>E likt L SEC, CAfC. .
FRDM 9hs srgwa Gsousrgy 6 :. l. 3 713l X 10 N 6
7-s)
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-)- $$ = 2*}. 13113t xti3
/7-t
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= f o fg F A 6 ( 2 '2)
\ UO T [3 '2 (2'A) l {I7 ';t)
,l STL EGUILIBRIUM T'f T= k S t. $ + $ 3' '. -(2- Q -
2 (, . 0/ ;<-
1
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. . . = . ~ . - - . . . . - . . .... . .: - . . . . - . . . w , :.- . . .
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O = 0'W t II1
=SI-(.(17- I'l22 22- 2 73%(2.-
- Vl =
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= 43 bli k. '4.
1 CktA CIT'l 0F HALL hiHE N INWEL Pkc2 TENStru l lM M = 43 -(,17 Jc-}V '> Q' '112. k-0, k .
~
.', HALL ALSo
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SECnrh, 55 PEheTrK SUILbtMG- HAS HIGuGL
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i Inst >E THc 8vlLDING , &A. WE iAMkh c.Arg '
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FORM CS-FRC-81
_. 1
I
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A 3.D.ivision,of Th,eenFranklin.
. . i Inst,2tute gf
- i
- - ._ .. io3 IL 4&
b REACTOR. SulL3>lMG ~ STEEL abo 4E SERVits FLOOQ 5 LEV ll9.G '
bTEE.t_ ( 0LUMN k N AL1515 .
East & West 6ide More Cn+1 col
_ H is he.c A Aio l Load. '
s
- All c.o l u m ns a re l4 W150 -
To FIMb THE MIAL Lo e orJ catuuMS, TAkE WT. 50 MEEL INTRuc Dead Wemh+ of S+eet in Ma\f Truss Member Lenafb W%it t_ength Wetsh4 JL 6x4e % Sv. s- 41.2. 232s.2
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l JL ', e 4 x % 55'. 6 - 47.2. 252s.2 i
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- Eb 13 8 ' x 2 2 2. (, 638 4i 4 JL 4 4 3 x 3/8 13.o 's Z 17,o 4 r,9. 2.
JL 4 y 3 = '/4 /s.s'n 2 II. to 3 zo. 2.
I 14 d'o f 23'b" Gl O I d i s . 2.
t
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%A s = {4 S 82. b lbs.
/4. 9 rip:
To m oeur Frg. Rmf OEcketdG AL;o /-b /*'- c u r .2 k '.+s FOL hx1 AL O Fp , y,s e 20xy t
FORM CS-FRC41
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O 2.6 -C 5? 5 7-01 '"*A -Ib O. J Franklin Research Center i BY Date W k'd Date R ev. Date An.Division
- r, - of Th,e Fran,klin ~.. . Inst.itute
.,. i ici RA APRIL Rt. MLf 4-82.
r.oe RfACTOR. BulLMJG STEEL AEoVE SEAvfCE FL. ELEV.119 5 '
UN0nce her j q Unbcoced heght b 141'- I '- l19'.5" . s/ 's " > 12 fb = &,s '
I c$ co\urnn kt - 2l' 6" Mo
- = (o s, \
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A Dmsson,of
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MLS 692.
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REACTOR SurLyNCr - STEEL 680VE SEMICS FL. E l. E V. If1 5'
- Arial Load -
20 kifs
- $1. - 0. 4 3 k.ss' f
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o h.94
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hs ' 20. 99 ( \ ~ 0. 025) = 20.46 h LA . y I
N= $b T , D.0 AGM 1900) = .5184.53 Jc. inch 1
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3,s. yg
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p =2 3.2.5 2.J U q
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FCRM CS-FRC-81 yw , . . . , , _ . - - , _ . - - - - - - -.---- -- - - - - - - - -
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A Division of The Frankhn inst 2tute t l ry, a.a w r,.,iama P.,mee, Na . Pe 19iC3 h h [
Tatte REACTOR SUILbMG. - STEEL A8096 SGltVICE FLk. St.EV II9 5' HM LHEck- CTEEL Cat UNAS &N NVP-TM b Scum st>E .
IldI5L ww '
c'i k4 = S 7 E y L2- , 7 0 7 g r2. 5 4_. C -c61 Yu ( ~ .{.
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= 10 I i 0
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FORM CS.FRC.81
l
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.; N J Franklin Research Center
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FORM CS-FRC-81
- - . . - .... .. . .. - ....- . - .. .. . . . . . . . - . . - . - . > - . . - - - - - - . . . = - .
) ,
/< ,i4* Pro ect Page
.i O2 G- C5 25 7-ol 4 -20
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. , w. Ins,t,it,ute
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q
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= 3 9 7 x. ft i
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/
M= WD B
W= M (2 8 U 9D , , 059 e/fr
.(23 23)
= s)c Ib / 4+
'A Prc ssu re- , 19 .. s. 6 z p.s4 8'l l " 8.9/7 ASSaMPT10N MS Is 'TRUE IF ME AssuboE n!b T AlvF JEcktNG-1 perSS NOT FML. AN.b AU. L#b /S TAblSPEARE) i To /1 811 1
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/
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FGEx:y = l9
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= 2 110Th,w q r R
l .', TOTA 1 MLehtk6LE ff& UUAE STA,.
CfunT =- $ b 2 + 3 + 2 !S I
=
Il 75/ %
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FORM CS-FRC-81
-,,.~,,n,... .,- .,.n,-- - , , , - . . . - - . . - - -.._.-:.. . - - - - -
i .
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i 1 APPENDIX B i
j I
VENTILATION STACK DESIGN REVIEW CALCULATIONS 1
I l
i i
1
.I i
.I "b
Franklin Research Center A Division of The Franklin institute j The Bensman Franklin Parkway, Phila.. Pa. 19103 (215) 441,-1000 1
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_ --:---~ n - - --~~~c--,~-n,,r-- -, - . - -
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A.) SrR.Ess 1a cru c.ae.rf_ MT. svTsu1>& pt.t+1sreA k i o 2rf' FrA. sr4ck. f'= frrnpi.
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THE sta ck. kre ELE V 391 0 i
THE GRk3E IS AT ELEV 23'0"
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kT CrRAbe O. b Is 30' S'/s A+1b &T WMe NT ELE 4-3' O b- IS 11 ' 7 % , I% " THICK. CndCEE TE HE A ssuME %E tivTEL. SuiLFktE rp ST%k GrRhDUhlLY l AtJD sM rrTH L'/ CFrhtXrEr .
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..a__. . _ _ .
1 I
2 Project Page j
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R n.
av D C Date Date
] A n.Devtsion,of
% - Th.e Franklin
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i rio.
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coucRETE stack - o'/sreg casek.
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FORM CS-FRC 81
i l ] Franklin Research Center 02.Cr _ c.52S7- 0 l 66 Title
^ W E b'2"W"MY kh MR?LYg1 h 5f[
- CxNCAETE CT M DNSTEL c.K&&k l
1 j DtSTA9CE W micass of DIA wie es res:t steel MOMENT Eaurvatsur To to FT sver,m waa, surE A IMMEA- MEA IML ChikcITYM1; K PMun l
j ll'l 73++
4/P
- (o oo 1646o4 I4 W0ft 40 2. 6 02. 2_ 62 O' dz 33 /
ll42c'1941 '7 D D l~l 5565' f(,3s15 as 4s $504 11 612C' 4c72_
i i 111 TS9 l t. T.n l9 2526 l'i 9193 32 11 7Foi 277 6l 25' 31 413
-l 2.02. 922. % ro 24 $+g l14 rg; So . Io 973C 6747 (,I 75^ 35 35 li 233.0 16 0 22 M t 2o 975l 27 62. IZ753 37t-t 42 S* 34 12_ /
l; 17T-l 12 rt 25 ITT1 23175'T 21 ff 19503 2d 63 5 6 34 25 /
f Slf-(54 3 13 r0 2.7 109) 2.f.1424 S E l 't 2.102f 461T 6( C' 377ft /
32.3 17t1 li 70 27 7n1 2.4. EEC 4 6 3 * (, 12.135 f60 $8 7 Tl 51
~151 17 i j 2o ro ?'l l.1257 2(, 0123 46 0 4270 9+3 63 25* 4244 i
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