ML20136F294
| ML20136F294 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/30/1984 |
| From: | ABB IMPELL CORP. (FORMERLY IMPELL CORP.) |
| To: | |
| Shared Package | |
| ML20136F274 | List: |
| References | |
| 01-0300-1292, 01-0300-1292-R00, 1-300-1292, 1-300-1292-R, NUDOCS 8601070334 | |
| Download: ML20136F294 (72) | |
Text
l Trojan Nuclear Plant- Mr. Steven A. Varga Docket 50-344 Attachment License NPF-1 December 31, 1985 l (Q)
X Reference 10 1
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TROJAN NUCLEAR POWER PLANT MODIFICATION AND STRESS ANALYSIS REPORT FOR THE PRESSURIZER SAFETY AND RELIEF YALVE ;
SMALL-BORE PIPING SYSTEM l
, Prepared for:
Portland General Electric Company 121 Southwest Salmon Street Portland Oregon 97204 Prepared by:
Impe11 Corporation 350 Lennon Lane .
Walnut Creek, California 94598 Impell Report No.01-0300-1292 Revision 0 O e501070334 851231 June,1984 DR ADOCK 05000344 p
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APPROVALCOVERSHEET i
Trojan Nuclear Power Plant Modification and Stress Analysis '
Docunent
Title:
Report for the Pressurizer Safety and Relief Valve Small Bore Piping Control Number: n1-nann-1242 l
Client Portland General Electric Job No. 0300-018 Project Troian Nuclear Power Plant Revision Record Rev. No. Daa Prepared Reviewed A m ved 0 41lgy f -
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CERTIFICATION The undersigned, a registered Professional Engineer, competent in the field of piping stress analysis, certifies that to the best of his knowledge and belief the analysis calculations for the subject piping system as presented in this Stress Report comply with the requirements of the Design Criteria and the applicable portions of the ASME Boiler and Pressure Yessel Code,Section III, Nuclear Pouer Plant Components. This report meetin Nuclear Power Piping, and ANSI B31.1, Power Piping.g the intent of ANSI B31.7, Piping System: Pressurizer Safety and Relief Valve Small Bcre Piping Lines Plant: Trojan Nuclear Power Plant gg0fESStog l+ f Ws **
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TABLE OF CONTENTS O
Page Report Approval Cover Sheet i certification (i 1.0 Introduction 1 -1 2.0 System Description 2-1 3.0 System Qualification Criteria 3-1 4.0 Analysis Methodology 4-1 4.1 Load Cases 4-1 4.2 Class 1 Branch Connection Stress Evaluatien 4-3
- - 4.3 Class 2 and 3 Piping Stress Evaluation 4-3 5.0 Analysis Results 5-1 5.1 Class 1 Branch Connection
('J~'s N Stress Evaluation 5-1 5.2 Class 2 and 3 Piping Stress Evaluation 5-3 5.3 Support Loading 5-3 6.0 Conclusion 6-1 7.0 References 7-1 Appendix A: Mathematical Models A-1 Appendix B: Computer Program Description B-1 Appendix C: Support Load Sunnaries C-1 i
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4 Report No. 01-0300-1292 !
Revision 0 l l
l.0 INTRODUCTION This report, prepared by Impe11 Corporation, describes the stress analysis for the Pressurizer Safety and Relief Valve Small Bore-Piping System of the Trojan Nuclear Power Plant. The purpose of this work is to assist Portland General Electric Company (PGE) in meeting the requirements of NUREG-0737,Section II.D.1. The NUREG requires a plant-unique: verification of the function and integrity of the reactor coolant system safety, relief, and block valves, in conjunction with associated piping and support systems. The large-bore piping (portion of this system) analysis is described by Impe11 stress report No.
01-0300-1291 (Reference 7.4d). Loads from that analysis are transmitted thru the branch connections to the small-bore piping. These transmitted loads required the evaluation of the small-bore system as described by this report.
The qualification of the small-bore piping was divided into two tasks:
Task 1. As-designed Analysis:
- 'me as-cesigneTsmall-bore piping system was analyzed with the modified as-design large-bore system loading. This is identified as Task 2 of the large-bore stress report, which describes the addition Q
b of the Slug Diversion Device's (SDD's) and associated analysis.
Task 2. As-built Analysis:
The as-built small-bore piping system was analyzed with the modified large bore as-built system loading. This is described as Task 3 of the large-bore stress report. Note that the SDD drain lines, as described by Section 2 cf this report, remain Es-designed.
Section 2 of this report provides a description of the small-bore piping lines. Section 3 describes the system qualification criteria; the code criteria and applicable design input. Section 4 provides analysis methods and ANSI B31.7/B31.1 code combinations. Section 5 summarizes results. A copy of the as-built math models and support load summaries are provided in the
- Appendices of this report.
The work has been performed in accordance with the Impe11 Quality Assurance Program, which complies fully with applicable regulatory requirements and industrial codes and standards.
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Report No. 01-0300-1292 Revision 0 O
V 2.0 SYSTEM DESCRIPTION The Trojan Pressurizer small-bore S/RV piping lines are attached to the large-bore S/RV discharge pioing, They function as sample, drain, and vent lines to 2.0-1, Figure the large-bore are: piping. The system as shown on the schematic drawing Pressurizer Sample Line (Analysis RC-02): This 3/4-inch single line connects upstream of the relief valves, it is defined as a ANSI B31.7 class 2 seismic class 1 line.
Loop Seal Drain Lines (Analysis RC-03): These three 3/4-inch lines connect upstream of the safety valves, draining back thru the large-bore piping to the pressurizer relief tank. They are defined as ANSI B31-7 class 2 seismic class 1 piping upstream of valve 8093, and ANSI B31.7 class 3 seismic class 2 downstream.
Slug Diversion Device (SDD) Drain Lines (Analysis RC-04): These four 3/4-inch lines connect the bcttom of the SDDs to the pressurizer relief tank back thru the large-bore piping. They are defined as ANSI B31.7 class 3 seismic class 2 piping.
O O
Safety Valve "C" Vent Line (Analysis RC-05): This single 3/4-inch line vents downstream of the PSV8010C Safety Valve. It is defined as a ANSI B31.7 class 3 seismic class 2 pipe.
Pressure Point "449" Line (Analysis RC-06): This single 3/4-inch line connects downstream of the Relief Valve SDD. It is defined as a ANSI B31.7 class 3 seismic class 2 line.
Relief to Pressure Tank Line: This 4-inch line connects upstream of the pressurizer relief tank.
It is defined as ANSI B31.7 class 3 seismic
- class 2 piping.
The first five linas are analyzed for the large-bore transmitted loading. The last line is not arialyzed as branch movement.t are negligible. Note that ANSI B31.7 specifies ANSI B31.1 for design and qualification of cluss 2 and 3 piping. Seismic class 2 piping is non-seismic and therefore no seismic analysis is performed.
A complete description of the attached large-bore piping system with functions defined is included in the large-bore pipe stress report (Reference 7.4d).
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SCHEMATIC 0F THE TROJAN PRESSURIZER S/RV LARCE-BORE AND SMALL-80RE PIPING S e O O
Report No. 01-0300-1292 Revision 0 i A
b 3.0 SYSTEM QUALIFICATION CRITERIA The codes of record for the Trojan Nuclear Power Plant small-bore piping are the ANSI B31.7 Nuclear Power Piping,1969 Edition including all addenda
- through 1971 for the class I branch connections, and the ANSI B31.1 Power Piping,1973 Edition for the class 2 and 3 piping. The computer analysis code checking uses ASME Boiler and Pressure Yessel,Section III,1974 Edition equations. Modification (i.e., stress intensification factors) to these equations have been made to insure code of record intent has been met.
An exception to the code of record has been used for branch connection stress intensification factor (SIF) due to unavailable code ruling in ANSI B31.1.
The ASME B&PV Code,Section III,1974 Edition Sumer '74 Addenda is used to calculate this SIF.
The main design documents for qualification are the Analysis Design Criteria, Revision 0 (Reference 7.2a), Revision 1 (Reference 7.2b), Additional Design Criteria (Reference 7.2c), Revision 2 (Reference 7.2d), and Revision 3
, Reference (7.2e). These represent the as-designed and as-built design input.
These design criteria are used for code stress. evaluations. Support G qualifications are not included in this work scope. Support loads, for all V small-bore piping systems analyzed are reported in Appendix C for PGE review and approval.
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Report No. 01-0300-1292 Revision 0 r.
O 4.0 ANALYSIS METHODOLOGY The small bore piping lines were analyzed by either conservative hand calculations, or the Impell proprietary Computer program SUPERPIPE. A Description of this program is provided as Appendix B of this report.
Analyses RC-02, RC-03, RC-04 (Phase II), and RC-06 were analyzed by the computer program. While analyses RC-04 (Phase I) and RC-05 were analyzed by the hand methods, due to their simple configurations.
A mathematical model of each piping line was developed and is shun ir Appendix A, of this report. They include the final as-built destyn input provided by Section 3 references, of the report. Analytical model.e were then developed which represent the mass and stiffness effects a' !:a .
system.
Evaluations of all significant static and dynamic loading conditions were then perfomed to determine internal forces and moments, and support reactions. All load case results are entered into the code stress evaluations: Class 1 for the applicable branch connections (on large-bore Class I piping), and Class 2, 3 for the remainder.
p 4.1 Load Cases V Four load case analyses were performed: two static cases for gravity and thermal ' expansion loadings, one response spectum or equivalent static (for hand calculations) for seismic loading, and one equivalent static
! for all large-bore branch induced movements.
4.1.1 Gravity Analysis The effect of gravity on the piping system was detemined by static analysis. The mass of the piping components, valves, insulation and (conservatively) pipe fluid were considered.
4.1. 2 Themal Expansion Thermal expansion analysis was perfomed for the two enveloping
!. load cases : maximum themal expansion induced branch movements plus either ambient or design temperature small-bore thermal expansion. The results of these two cases were conservatively enveloped for code compliance.
Cold springing of supports SR/304 and SR/301 was analyzed to match large-bore branch connection movements. The results of this applicable cold spring loading (analysis RC-02 only) are algebraically summed with the above load cases, i
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Report No. 01-0300-1292 Revision 0 0
4.1. 3 Seismic Analysis
' Seismic analysis was performed by the modal response spectrum analysis technique. This utilizes response acceleration spectra as the input loading. The mass of the piping components, valves, piping contents, and insulation are considered in forming a mass matri . All rigid restraints and snubbers are considered while fomdating the stiffness matrix.
Once these matrixes are fomed, the frequencies and mode shape for -
all significant modes of vibration below 33Hz are detemined.
After the frequency is determined the corresponding modal spectral acceleration is then taken from the Section 3 referenced design input (of this report). Using these spectral accelerations, the characteristic response for each mode is found. Using these results the maximum displacement response of each mode is calculated for each mass point.
The square-root-of-the-sum-of-the-squares (SRSS) method is used to combine the effects for different modes and different seismic directions, except for the closely-spaced modes. These closely spaced modes are combined by absolute summation, as specified by the " grouping method" described in Regulatory Guide 1.92. ,
After the joint displacements are calculated, the individual member forces, moments, and support reactions are obtained by using the member stiffness properties.
Two seismic runs were performed; North-South with vertical OBE seismic excitation, and East-West with vertical OBE seismic excitation. Results of these runs are enveloped in absolute value. SSE loading is obtained by multipling the OBE results by a factor of 1,67 (Reference 7.2c).
4.1. 4 Branch Movements The large-bore piping branch movements (Reference 7.4c) are analyzed by equivalent static analysis. Movements in each direction are analyzed separately then combining absolutely. '
Branch movements from the valve thrust (Safety or Relief Valves) load cases, and the large-bore thermal operating modes are analyzed. A co3plete discription of each of these load cases are provided in the large-bore pipe stress report (Reference 7.4d).
Branch movements from large-bore gravity sag, and seismic inertia are negligible and not evaluated.
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1 Report No.- 01-0300-1292 Revision 0 O l 4.2 Class 1 Branch Connection Stress Evaluation The Class 1 branch connection stress evaluations were perfonned to ANSI B31.7 rules to show that each of the stress limitations of B31.7 Divisions 1-704 " Pressure Design of Components" and 1-705 " Analysis of Piping Components" are satisfied (ANSI B31.7 Divisions 1-704 and 1-705 correspond to ASME Section III Subarticles NB-3640 and NB-3650 respectively). The applicable Code Equations with corresponding service conditions and loadings are presented in Table 4.2-1. A description of service conditions, loading, and definition of symbols are provided in the large-bore stress report (Reference 7.4d).
4.3 Class 2 and 3 Piping Stress Evaluation Class 2 and 3 piping stress evaluation was perfonned per ANSI B31.1 rules to show that each of the stress limitations of B31.1 Paragraphs 104
" Pressure Design of Components", and 102.3 " Allowable Stresses and Other Stress Limits" arc satisfied (ANSI B31.1 Paragraph 104 corresponds to ASl1E Section III Subsubarticle NC-3540 and Paragraph 102.3 corresponds to NC-3650. Since the Code Equation numbers for stress evaluation are not explicitly mentioned in B31.1-1973 Edition, the corresponding Code 3 Equations 8 through 11 of ASME Section III NC-3650 are used for discussions). The applicable Code Equations with corresponding service '
conditions and loadings are presented in Table 4.3-1. A description of service conditions and loadint1s is summarized below (Refer to the Code for the definition of symbols).
Design Condition For the Design Condition, the pennissible pressure should not exceed the pressure P calculated with Code Equation 4 of B31.1 Paragraph 104.1.2 and the stresses due to sustained loads calculated with Code Equation 8 of NC-3652.1 (corresponds to 831.1 Paragraph 102.3.2) should not exceed 1.0 S.h The design conditions are specified by the design documents referenced in Section 3 of this report.
Normal and Upset Conditions For Normal and Upset Conditions, the stress range due to thermal expansion calculated with Code Equation 10 of NC-3652.3 (corresponds to 831.1 Paragraph 102.3.2) should not exceed AS , or the sum of stresses due to sustain loads and stress range due' to thermal expansion calculated with Code Equation 11 of NC-3652.3 (corresponds to B31.1 Paragraph
.102.3.2) should not exceed the sum of Sh andA S . Additionally for Upset Condition, the pennissible pressure shouTd not exceed the pressuro O
4-3
Report No. 01-0300-1292 Revision 0 0
P calculated with Code Equation 4 of B31.1 Paragraph 104.1.2 by more than 105 and the stresses due to occasional loads calculated with Code Equation 9 of NC-3652.2 (corresponds to B31.1 Paragraph 102.3.3) should not exceed 1.2 Sh .
The load cases included in Code Equation 9,10 and 11 evaluations are:
Weight of piping system - Equation 9 and 11 OBE (One-half the range) - Equation 9 Hydrodynamic load due to relief valve openings - Equation 9 Themal expansions (Normal and Upset) - Equations 10 and 11 Emergency Condition For Emergency Condition, the pemissible pressure should not exceed the pressure P calculated with Code Equation 4 of B31.1 Paragraph 104.1.2 by more than 505 and the primary stresses due to occasional loads calculated with Code Equation 9 of NC-3652.2 (corresponds to 831.1 Paragraph 102.3.3) should not exceed 1.8 Sh -
The load cases included in Code Equation 9 evaluation are:
Weight of piping. system OBE (One-half the range)
Hydrodynamic load due to both safety and relief valve openings (Envelope of both runs)
Faulted Condition For Faulted Condition, the permissible pressure should not exceed the pressure P calculated with Code Equation 4 of 831.1 Paragraph 104.1.2 by more than 1005 and the primary stresses due to occasional loads calculated with Code Equation 9 of NC-3652.2 (corresponds to B31.1 Paragraph 102.3.3) should not exceed 2.4 Sh-The load cases included in Code Equation 9 evaluation are:
Weight of piping system SSE (One-half the range)
H(ydrodynamic load Envelope of both due to both safety and relief valve openings runs)
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l Report No. 01-0300-1292 Revision 0 TABLE 4.2-1 CLASS 1 PIPING CODE EQUATIONS AND LOAD COMBINATIONS B31.7 Paragraph 1-705 Service Condition Code Equation Load Combination (3)(4) Allowable Design (1) 9 Pressure (Design) + Gravity + 1.5 Sm OBE + R/V Open Emergency (1) 9 Pressure (Emergency) + Gravity + 2.25 Sm OBE + Envelope (R/V Open &
S/V Open)
Faulted (l) 9 Pressure (Faulted) + Gravity + 3.0 Sm SSE + Envelope (R/V Open &
S/V Open)
Normal & Upset 10 Pressure (Nomal & Upset) + OBE + 3.0 Sm( }
R/V Open + Themal (Nomal
& Upset) + Transient (ATj &
hv lTa-Tl} b Normal & Upset 11 Pressure (Nomal & Upset) + OBE + ---
R/V Open + Thermal (Normal
& Upset) + Transient (AT), AT2 &
lTa-Tl} b Nomal & Upset 12 Themal (Nonnal & Upset) 3.0 S,(2)
Nomal & Upset 13 Pressure (Normal & Upset) + 3.0 S,(2)
Gravity + OBE + R/V Open +
Transient (lTa-Tl) b Normal & Upset 14 K, x Eqn 11 (K, depends on Eqn 10 Cumulative results) Usage Factor
- s1.0 NOTES: (1) Pressure checks are perfomed by calculating the allowable design pressure (P) with Code Eqn. 2 of B31.7 Paragraph 1-704.1.2. The limits are P for Design Condition,1.5P for Emergency Condition and 2.0P for Faulted Condition.
(2) Code Eqns.12 and 13 need to be satisfied if Code Eqn.10 stress exceeds the limit 3 Sm-4 4-5 t
Report No. 01-0300-1292 Revision 0 O
TABLE 4.2-1 CLASS 1 PIPING CODE EQUATIONS AND LOAD COMBINATIONS a
NOTES: (3) OBE and valve actuation (R/V Open or S/V Open) were summed by the (Contd) SRSS technique based on References 7.ld and 7.6b.
(4) The thermal expansion associated rith safety valve opening is defined as an emergency condition by Reference 7.6a. Therefore, it is not used for code compliance.
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Report No. 01-0300-1292 Revision 0 O
v TABLE 4.3-1 CLASS 2 & 3 PIPING CODE EQUATIONS AND LOAD COMBINATIONS ASME NC-3650 III Service Condition _ Code Equation Load Combination (4) Allowable Design (2) 8 Pressure (Design) + Gravity Sh
^
Upset (2) 9 Pressure (Upset) + Gravity +
OBE + R/V Open 1.2 Sh Emergency (2) 9 Pressure (Emergency) + Gravity +
OBE + Envelope (R/V Open & 1.8 Sh S/V Open)
Faulted (2) 9 Pressure (Faulted) + Gravity +
SSE + Envelope (R/V Open & 2.4 Sh S/V Open) p a Normal & Upset 10 Thermal (Normal & Upset)
SA Nomal te Upset (3) 11 Pressure (Design) + Gravity + S +S Thermal (Normal & Upset) h A NOTES: (1) Code Equation numbers are not explicitly mentioned in B31.1 -
1973 Edition, Paragraph 102.3. The corresponding Code Equations 8 through 11 of ASME Section III NC-3650 are used.
(2) Pressure checks are perfonned by calculating the allowable design pressure P with Code Equation 4 of 831.1 Paragraph 104.1.2. The
' limits are P for Design Condition,1.1P for Upset Condition,1.5P for Emergency Condition and 2.0P for Faulted Condition.
(3) Either Equation 10 or Equation 11 should be satisfied.
(4) OBE and valve actuation (R/V Open or S/V Open) were sunened by the SRSS technique based on References 7.1d and 7.6b, or conservatively absolutely summed.
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Report No. 01-0300-1292 Revision 0 0
5.0 ANALYSIS RESULTS 5.1 Class 1 Branch Connection Stress Evaluation The two analyses RC-02 and RC-03 are conrected to the large-bore class 1
, piping (upstream of the safety or relief valves). Therefore complete stress evaluation of these branch connections included both run and branch pipe stresses.
5.1.1 Primary Stress Intensity The primary stress intensities as determined by Code Equation (9) of 1-705.1 are within Code allowables. A summary of maximum intensities and comparison to the applicable allowable for each I
service condition are shown below:
Maximum Primary Stress Intensity O Location Service Condition Stress Intensity (PSI)
Primary . Allowable _ Ratio RC-02 Design 10,991 24,120 .46 DCP 123 Emergency 11,487 36,180 .32 Faul ted 13,475 48,240 .28
, RC-03 Design 20,458 24,120 .85 Envelop of Emergency 22,359 36,180 .62 DCPs 13A,49A, Faulted 27,581 48,240 .57 and 84A 5.1.2 Consideration of Normal and Upset Conditions The satisfaction of primary-plus-secondary stress intensity and peak stress intensity :*ange as verified by Code Equations (10),
(11), (12), and (13) of 1-705 are within the allowables. No explicit verification of the branch connections upstream of safety valves (analysis RC-03 DCP's 13A, 49A, and 84A) was required since the thermal transients associated with the safety valve actuation '
are defined as an emergency case and relief valve transients are not applicable.
5-1 I
Report No. 01-0300-1292 Revision 0 A sumary of the maximum stress intensity ranges and cumulative usage factors are provided below for branch DCP 123 (Analysis r RC-02):
Stress Intensities Stress Intensity Range (PSI)
Code Equation Calculated Allowable Ratio 10 110,400 50,000 1.84(1) 12 22,360 60,000 .37 13 50,400 60,000 .84 Note: (1) Although the Equation (10) stress limit is exceeded the results are acceptable by satisfying Equations (12) & (13). The calculated stress for equation (10) is for the run pipe only but satisfaction of Equations (12) & (IT) includes both run and branch stresses. Since the stress exceeds 0.0mSm = 102,000, Xe = 3.33 for fatigue evaluation.
highest peak primary-plus-seconda stress The correspondinfCode intensity range Equation 11) and maximum cumul tive usage factor is. f i
Sp = 253,800 (PSI)~
Sal t = 422,580 (PSI)
Maximum Cumulative Usage Factor = 4.00 Cycles Allowed = 25 l
The maximum cumulative usage factor is based on 100 cycles of relief value discharge. By review of the plant history (References 7.4c and 7.4d) a revised estimate of 25 actuation over the 40 year plant life.was made.
Therefore, to maintain system qualification, the number of relief valve actuations should be monitored during the remaining plant life.
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Report No. 01-0300-1292 '
Revision 0
.5.2 Class 2 and 3 Piping Stress Evaluation The minimum allowable internal design pressure.for straight pipe, as determined by Code Equation (4) of 104.1.2 is greater than the specified design pressures.
The pipe stresses, as verified by Code Equations (8), (9), (10), and (11) l 1
of NC-3650 are within allowables. A sununary of the maximum stresses and ratio of calculated to allowable stress is provided below.
Code Equation / Calculated - Allowable 4 Analysis Service Condition Stress (PSI) Stress (PSI) Ratio (8) Design RC-02 3,142 15,900 .20 (9) Upset 9,563 19,080 .50 (9) Emergency 9,563 23,620 .33
. (9) Faulted 14,263 38,160 .38 (10) Normal & Upset 26,969 27,475 .98 RC-03 (8) Design 4,439 15,900 .28 (9) Upset 6,187 19,080 .32 (9) Emergency 6,834 28,620 O (9) Faul ted (10) Normal & Upset 9,552 24,145 38,160 27,475
.24
.25
.88 RC-04(1) (8) Design 4,029 15,900 .25 (10) Nomal & Upset 11,751 27,475 .43 RC-05(1) (8) Design 1,394 15,900 .09.
(10) Nomal & Upset 10,146 27,475 .37 RC-06(l) (8) Design 2,296 15,900 .14 (10) Normal & Upset 25,789 27,475 .94 Note: (1) Analyses RC-04, RC-05, and RC-06 are seismic class 2. Therefore, only Equations (8) and (101 are evaluated.
5.3 Support Loading Support load combinations were based on the following table. They are included as Appendix C, and were transmitted to PGE for their review and approval (Reference 7.4f). All loading is in the plant global coordinate system, as shown by the math models contained in Appendix A.
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Report No. 01-0300-1292 Revision 0 O
Set Name (1) Service Condition Load Combination (2)(3)(4)
NORM Normal Gravity + Thermal Expanison +
, Thermal Branch Movements + Cold Spring Movements UPST Upset Gravity + Therwal Expanison +
Thermal Branch Movements + Cold Spring Movements + OBE Seismic
+ Relief-Yalue Thrust Branch Movement EMER Emergency Gravity + Thermal Expanison +
Thermal Branch Movements + Cold Spring Movements + OBE Seismic
+ Envelop of Valve Thrust Branch Movements (Relief or Safety Valve)
FLTD Faulted Gravity + Thermal Expanison +
-Thermal Branch Movements + Cold N Spring Movements + SSE Seismic s + Envelop of Valve Thrust Branch Movements (Relief or Safety Valve)
Notes: (1) Set Names correspond to those used in Appendix C.
(2) OBE and Yalve Thrust (Relief or Safety Valve) loads are summed absolutely except for as-built analysis RC-03. These RC-03 loads are summed by the SRSS technique, based on Reference 7.1d.
(3) Analyses RC-02 and RC-03 are seismic class 1 piping, and therefore include seismic loads. Analyses RC-04, RC-05 and RC-06 are seismic class 2 piping, and therefore do not include seismic loads. Maximum loads reported for these seismic class 2 piping are for the upset service leval.
(4) Cold spring movements are for analysis RC-02 only.
1 5-4
Report No. 01-0300-1292 Revision 0 0
6.0 CONCLUSION
As discussed in Section 5, all small-bore Pressurizer Safety and Relief Yalve piping lines meet the requirements of the System Qualification Criteria, and the applicable sections of B31.7 and B31.1 Codes. The pressurizer sample line class 1 branch connection is qualified for 25 actuations of the relief valve.
To maintain system qualification the number of relief valve actuations should be monitored during the remaining plant life.
All piping and supports are as-built except for the SDD Drain Line, as shown by Appendix A drawing RC-04.
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i Report No. 01-0300-1292 i Revision 0 I
7.0 REFERENCES
7.1 Codes
- a. ANSI B31.7, Nuclear Power Piping,1969 Edition, including all addenda through 1971 (Code of Record for Class 1 Piping).
- b. ANSI B31.1, Power Piping,1973 Edition (Code of Record for Class 3 Piping).
- c. ASME BAPV Code,Section III, Nuclear Power Plant Components,1974 Edition, including all addenda through Sumner 74 (For Class 3 Branch Connection SIF).
- d. NUREG-0484, Methodology for Combir.ing Dynamic Responses, Rev. 1.
- e. NUREG-0800, Standard Review Pla9 Section 3.7.3 Seismic Subsystem Analysis, Rev. 1.
7.2 Design Criteria / Input Data !
- a. Trojan Nuclear Pressurizer Blowdown Piping Analysis Design Criteria, O Revision 0, transmitted to Impell by PGE Letter RLS-415-82, dated April 2, 1982.
- b. Trojan Nuclear Plant Pressurizer Blowdown Piping Analysis Design Criteria, !
Rev.1, transmitted to bpell by PGE Letter RLS- 489-82, dated April 21, !
1982. i
- c. Trojan Nuclear Plant Pressurizer Blowdown Piping Analysis Additional Design Criteria, transmitted to Impell by PGE Letter RLS-554-82, dated May -
7, 1982.
- d. Trojan Nuclear Plant Pressurizer Blowdown Pipe Analysis Design Criteria for Final Stress Report, Revision 2, transmitted by PGE Letter RLS-124-84, I i
dated January 20, 1984. '
l
- e. Trojan Nuclear Plant Pressurizer Blowdown Pipe Analsyis Design Criteria I
' for the Final Stress Report, Revision 3, transmitted by PGE Letter RLS-390-84, dated March 27, 1984.
7.3 Final Safety Analysis Report l
Trojan Nuclear Power P1 ant, through Amendment 34.
f O
7-1 v--v v .---n -,- , --.--,-w- , - ,-- , , ,- , - - , -. . - . . = - - - - - - - . , - ,
Report No. 01-0300-1292 Revision 0 pJ 7.4 Impe11 Problem Files, Reports and Letters Related to the Pressurizer S/RV Piping System
- a. Impe11 Pipe Stress Analysis Calculation File No. 0300-018-RC-01, Revision 0 (as-designed results).
- b. Impe11 Pipe Stress Analysis Calculation File No. 0300-018-RC-02 through RC-06, Revision 0 (as-design results).
- c. Impe11 Pipe Stress Analysis Calculation File No. 0300-018-RC-01, Revision 1 (as-built results).
- d. Impell Report No. 01-0300-1 291, Revision 0, " Trojan Nuclear Power Plant Stress Analysis Report for the Pressurizer Safety and Relief Yalve Large-Bore Piping System".
- e. Impell Pipe Stress Analysis Calculation File No. 0300-018-RC-02 through RC-06, Revision 1 (as-built results).
- f. Impell Letter 0300-018-018, dated May 25,1984, " Transmittal of Small Bore Resul ts" .
7.5 Drawings
- a. Piping Isometric Drawings:
RC-2501R-29-650, Revision 8 RC-60l R-2-651 , Revision 8 RC-2501R-12-650, Revision 14 RC-601R-2-653 , Revision 1 RC-601R-2-654 , Revision 1 RC-60lR-2-655 , Revision 1 1C-601R-2-656 , Revision 1 WC-60lR-2-650 , Revision 6 RC-601R-2-652 , Revision 1
- b. Valve Drawings:
- PGE 6478-MIR(2)-231-3
- PGE M113A-16-5
- c. Other Drawings:
- PGE Pipe Support Details Listed in PGE Letter RLS-124-84, dated January 20, 1984
~
O 7-2
k Report No. 01-0300-1292 Revision 0
. O 7.6 Other References
- a. EPRI Letter (From A.J. Wheeler) to Utility Technical Contacts and Pi)ing Subcommittee Members, dated November 5,1981: S/RV Piping
, Su> committee, October 29, 1981, Meeting Agenda and Suggested Additional Note for the Load Combination and Acceptance Criteria Table.
- b. WCAP-10105, Westinghouse Report, " Review of Pressurizer Safety Valve Performance and Observed in the EPRI Safety and Relief Valve Test Program", June 1982.
4 a
1 O
O l 7-3
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I APPENDIX A MATHEMATICAL MODEL l
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l Report No. 01-0300-1292 Revision 0 1 O APPENDIX B C0WUTER PROGRAM DESCRIPTION SUPERPIPE: Version ISB,15C, and 16A l
SUPERPIPE is a general-purpose piping program which perfoms comprehensive l structural analyses of linear elastic piping systems for dead weight, themal !
expansion, seismic time-history or spectra, arbitrary force time-history, and other loading conditions. Analyses are performed to ASME requirements for Class 1, 2, and 3 systems.
The program has various features for user ease in defining the piping system.
These include automatic generation of node coordinates and curved segments or elbows, automatic cartesian / polar coordinate transfomation (translation /
rotation), built-in data (including stress indices) for standard material properties, and piping schedules. The program also has various plotting capabilities, and extensive diagnostic error and warning messages aid in checking the model.
In addition to the basic capabilities for performing dead weight, thermal expansion, seismic response spectrum, and anchor movement analyses, SUPERPIPE offers a number of more sophisticated features -for specialized piping analyses. These include:
- a. Analysis with multiple response spectra for piping supported at numerous levels within a building and, therefore, subjected to independent loading (different spectra) at each level,
- b. Modal superposition or direct-integration techniques of time-history analysis for shock loads associated with steam hammer and water hammer effects in piping systems, or other arbitrary force time-history loadings.
- c. Analysis with multiple acceleration time history for situations in which a piping system is subjected to independent motions at each support, and in which the effect of phase relationships between these motions is important.
Static or dynamic equilibrium equations are fomulated using the direct stiffeess met. hod, in which the element stiffness matrices are fomed according te virtual work principles and assembled to fonn a global stiffness matrix for the system, relating external forces and moments to joint displace-ments and rotations. Six degrees-of-freedom may be specified at each joint of the global system for both static and dynamic analyses.
O B-1 s v ---* * - , - - - , - . - - . - . - - - -.-- ,.- , _ _ ____.,_ ___._____.____ __
Report No. 01-0300-1292 Revision 0 O
The program has a number of element types which may be used in any combina-tion. These include:
- 1. Straight pipe
- 2. Curved pipe
- 3. Valve
- 4. General beam
- 5. Flexible coupling
- 6. Arbitrary stiffness matrix Static equilibrium equations are solved using Gaussian reduction techniques on the compacted stiffness matrix. For dynamic problems, the equilibrium equations may be solved using either step-by-step direct integrations of the coupled equations of motion, or by first calculating natural frequencies and '
mode sha motion. pes and transforming Natural the mode frequencies and system into aare shapes set calculated of uncoupledusingequations the of deteminant search technique.
The program has been thoroughly tested and verified for a comprehensive set of sample problems, including extensive comparison with several publicly-available programs and ASME benchmark problems. All verification analyses have been documented in accordance with established Impe11 Nuclear Quality Assurance procedures.
O .
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l APPENDIX C COMPONENT LOA 0 SUMMARIES l
- Analysis RC-04 through RC-06 Pages C-2 through C-7 Analysis RC-02 Computer Output Sequence Wo. 83/06/14. 08.57.27 Pages 26 through 33.
Analysis RC-03 Computer Output Sequence No. 84/05/23. 08.25.35. ;
Pages 256 through 278.
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IMPELL PR00LEP '3L'aCIA oc *3 PrV. I ,
, SUPPORT LOAD
SUMMARY
Supr0RT LOAD SUMMAPY 4 i
CHECMIhr PEGI0t3 INDICATOP = rutt (ALL SUPPGPTS) i ) 1 00TFUT DETAIL IP DICAT(R = DETL (DETAILED FRINTOUT) ;
COMMENTAPY INDICAT05 = COWM (Co*NENT AR Y TO FE PPINTED) ).
i LOAD CASI INDICATOR = CLCC (P E-USE PR EVIOUS C ASES) ;
PPESSURE DISTRIOUTIOk INDICATOP = CLPP (N0 DISTRIPUTICh5 TO DE SPECIFIED) i TEMPERATURE DISTRIHUTIDM INDICATOP = OLOT tr10 DISTRIffUTIONS TO BE SPECIFIED) ) ,
)-
DESIGN CHECF COPPENTARY i
)
l CRAV GRAVITY THMI THERWAL F I'P F THP; THERNAL E 6PC F }
- CHET SEISFIC CBE IAEFTIA
, SP'S t 'SE + SSE RAM 1 l FTHE SAFETY VALVE THPUST ANCHOR MOTION
- Sv00 SRSS i OPET + FTHE 1 }
} SVSS SRSS ( STET + FTHE 1 l A0PM C#4V + THMI + TPw?
j LPST .GRAV + OFFT + TbM1 + YHr2 ) l j frof G#AV + SV0P
- TFPI
- THF0
- FLTC GRAV
- SVSS + THMI + THPF
! A i
=
o il i
4 L
y.
~. .;
x d IttPFLL CCRPCP ( s1 PAGE 2?P 'g [
SUPERPIPE VER$1CN 16Ao If/L1/P?$ SYSTEP IPPELL:- No!- P4/C5/23.'CP 25 3*e u t.
, FGr Tp0JAN NUCLEAP STATION g 1* FELL rPOPLE9 J3'erts . PC.c3 PEv. 1 .
LOCP !EAL DPAIN LINE5 ,
L jI LOAD SET SPECIFIC 2 TION -) ;
TET CO*P NAPE .TvFF LIST OF CA$rt IN GPCUP TITLE e
" )' !
I i
.I
' y5 GRAV 0FLT. GPAV [
THM1 0Fli THM1 3.
THM2 DFLT THP2 '
( -t i OPET OFLT ceFT SSET OFLT *StT g, i-FTHE OFLr FTFE t NCPT OFLT GRAV THP1 THP2 NORFAL CONDITION l UPST OFLT CPAV 0FFT THF1 THP2 UPSET CONDITION )
i ENRG CFLT G9AV SVCD TNP1 TH'? EMERGENCY CONDITION i ) !
! FLTD DFLT GRAV SVES THP1 THP2 FAULTED CONDITION J
+
i j J 2 .
. 8 4
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1 . ._ ._ ._ _ - .. . _.
. ._ ~ > - . - . - . - ,. .-.
3 IMPELL CORP [ w iCN n o
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PAGE 259
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SurEEPIPr VERSICN 16Ao II/p!/838 SYSTEM IPPELL - N0!
R4/05/23. PP.25.'5.'
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(s PGE 750JAN NUCLEAR STATION
. IMPEL L 'PROPLEM 53*(01P - PC-03 PEV. 1 , r)
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DET AILS OF SUPPCRTS FOR TFIS SurMARV b *
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SUPP SUPP R Y Z SUPP DIFN INCL DIR. COS. WRT GLOBAL APES r NAME LOCN C00rD ' COCPD COORD TYPF -CODE AMIS F Y 7 (FT3 fFT) (F7) )~
)
,49A 49A t
'7.724 116.75e -?7.sei ANCH G L OB '
35 ?? -41. Pal 115 500 -!P.tGC CONF Y 45 45 -42.224 115.! ' * -37 333 4NUD Y ) i 55 55 -42.224 11".5:'t -95.5UP SNGL F 7C 75 -42.224 11 E . 5.' f -33.271 CONF Y 75 75 -42.22* 115 5'*- g
-32.**R ? NGL F 85 PS -42.224 115 5P: -31.50C SNUP Y 95X 95 -42.224 114.*17 -3'.800 ' NGL F .I
- 52 9M -42.22* 114.*17 -3!.501 5NCL 7 )
ifGN l i e. -42.224 111.25( -3f.500 ShGL F ,
1002 16L -42.224 111 25* -30 5*5 ENGL 7 1:57 11' -42.224 1r5.'54 -33 500 SNGL M )
195Y 17" -42 22* 1:!.?$a -3 a.m ir. ' NGL Y i 1:52 1.% -42 22* 1C*.354 -3*.5CC. ' NGL 7 115 115 -42.724 It?."Po .-3;.5CO CONF Y )
140 141 -43.224 103 50C -26 25e ANCH GLOG 15uY 156 -37.P48 119 5"? -36.PPC SNGL Y 157:2 15t -37.8ap 11s .5 * *< -3 s . a ti; SMcL' 7 )
17C 17, -32 597 119.50* -35.75C SPUP Y 1*C 1** -?2.857 115.5'1' -35 19C CONF Y 20G 26G -32.557 115 50.' -33.000 SNGL M 13a 13A *1.S:7 116.75 -?".625 APCP CLOD P44 84A -43.4?2 118.75' -33 125 aNCH GLOS
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- 7s PGE TF0JAN NUCLEAR STATION IPPFLt rPretrM t3rq91R . oc-f3 FEV. 1 ,) L LOOP SEAL CRAIN LINES 7' .
1 SUPPOP T Ln AD FUPVAPV ,
SUPP SUFP CUPP 2ipt REFLLY RESULT ANIS LOAD LOAD NAME LCCN TYPE COTE TvrE LOAD LNIT TYFE N-AVIS SET Y-ANIS SET 7-AMIS SET 40A 40A #NCH GLC0 h, FORC fLP) CLCD 90.P3 FLTDEM*) 7.63 SSETfM.)
3 31.R2 FLT0tP+)
77.6* EMP6 3 Fee AHA'645 -
73.6, e,r7 4.57 3,,a CBET 29.25 SSET FTHE 2e.10 EMRG 7 ppgp.gg pqty 55.17 THP2 2r.07 UP97 l 54.P4 NORM )
17.51 OBET 34.R1 SSET -1.to FTbE 2.59 THM1 20.** OPET -4 57 OPrY 2 56 NORM n .13 FTHE -7.63 SSET .ps )
FTHE
-12.?R FLTD
-15.39 E*PG
.32 GRAV -1".5P UP'T .83 GRAY )
.32 CPAV -20.07 GPAV .f3 GRAV 0 13 FTHE -PP.07 GPAV =.PR FTHE
-9.42 THP1 g
-2A.07 N0cM -13.35 T'dMP
-9 74 kOPM -32.EP THP2 -13.3? NORP
-2'.84 Opri -3R.6* THP1 -17.51 OPET
-3 9.5 m UrST -99.73 NOPM -28.25 SSET )
-32 56 EPRG -63 39 UPST -30.P9 UPST
-?4.81 S$rT -63.40 EPaC -30.91 EMAG '
-45.73 FLTDtM-1 -66.42 FLTDtM-f -42.63 FLTD(Mal )
( MOPT (LP.Fil GLOP 32.77 FLTDEM*) 22.58 FLTDEP*) 151.01 ILTDtM*1 24.63 S$rY 1P.65 EPPG 130.99 LMcG y
22.04 .FMPG 17 12 UPST 136.86 UPST 22.81 L'PS T 11 17 SSET 118 6R N0dM 14.75 CDET 10.43 NOPM 115.96 THM2
'3 P.66 THM2 I t'.17 THwl 45."2 THM1 P.07 NOPP 6 6a CBET 30 36 SSET 1.95 FTHE 4.18 FTFE 1P.18 OBET )
.'6 GRav 11 12 FTHE
- 4 GPAV .2.72 GREV
.55 CPAV y 2.72 NORM
.58 CPAV 2.72 GRAV
-1.9? FTHE -4.7P FTHE
-2.o* THP1 -6.6* CPET )
-3.54 NOPP -11 17 9507 -11 12 FTHE
-la.7* OPET -54.!K NORP -15.46 UPST
=18.2" UDST ~54.12 THw2 -1P.1P OPET j
-1R.41 FPPG -6r.7e Urs? -18.59 EMRG
-24.c3 trrv -62.;r EPDG -2".61 FLTD
-M.24 rLTCfP-? -75.21 FLTDtw-7 -!C.t* SSET(M-9 DiPP (Irl GLOD NEGLIG1BLE o
t #
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s I PPELL C03FoiwriON PAGE 261 SUPERPIFE VEPSICA 168, It/91/f28 SYSTEP IPPELL = AOS 84/!5/22. EP.25.35. #)
PGE TP0JAN NUCLEAR STATION. '
1"PELL PPOBLre :3'"t14 - PC**3 PFV. 1 LOOP !E4L DeAIN LINES D 3 SupPorf LOAC SUPPany trtNTD.)
~
SUPP SUPP SUPF DIPh PEstfLT P ESitLT ' . A FIS LOAD LOAD LOAD hAME LOCN TYPE -CODE TYFE 11N T T TYPE N-AYTS sri y-ATIS $tt 7-AFIS SET
)
4*A ECONTD.)
POTN (OAD) GLOB NEGLIGIDLE 35 35 CONF V FOPC (LB) GLOR - 12. ., a cppy
~12 3* Goay
-12.*9 NOPM ')
-12.P9 NCem
-12.?* UPST y
-12.G9 Up*T
-12.r.9 EA*G
-12.T* EM9G
-12.C9 FLTD )
-12.to FLTDir-1 DISP (IP) GLOP .'62 FLTDtM*3 2 430 FLTDtM*3 .313 FLTDEM*l
. 05 4 EMPG 2.42" EPRC .10T EM*G
. 93 7
- Sri 2 424 flPST .1L5 UPST y
. 93 6 FTPE 2 455 THM1 .085 THM1
.034 UPST 2.415 NOPM .f94 NORP
.*P2 08ET 2.21'8 "vH'? ."17 SSET
.f! ? h0PM .'1' $$ET .r10 ceET }
. r10 THM1 609 6DET .008 FTHE
.*f t GPAV .?O4 FTHE
.A*1 GPAV )
. ?2 2 CPFT .fDR FTHE
. '3 6 FTHE .618 OBFT
.t? 7 SSET .c04 FTFE .*1T SSET
}
. col A0pH .or* OrrT .422 THMP
.(9 3 THMP .?ra UPST .423 NORP
.11 ? bPST .ftm EroG )
.435 UFST
.13 3 r*FC .ct" S$Et .436 EMRG
.142 FLTDtP-3 ."16 FLTDIP-l .442 FLT0tM-9
)
45 45 !AUD Y FOPC (LP1 GLOP P.32 FLTDtP*3 '
7."5 SSET A.!" EM*G 4.76 CPET '
4.7A tlPC T 2 . * *, FTPE
. .- - ~ .. r L'
f- s
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SUPERPIrf VEPSIO*J 168, !!/P1tP38 SYSTEP TEPELL - NOS PAGE 262 >
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$dPPOWT LnAD FUPMARY (CtNTD.3 SUPP SUFP EUPP DIES >5CSULT PESULT AVIS LOAD LOAD LOAD 1
NAME LOCN TYPE L.0E TYPE l'N I T TTPE W-AFIS SFT T-ANIS SET 7-AXIS SET l'
4%
ICONfD.3 -2.45 FTHE
-4.76 UP!T )
-4.76 0 BET
-5.35 EMPG
-7.a$ ggry )
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DIse (INI GLOB '4P FLTDfM*) 2 281 .110
)
THPitM*) FLT0tM*)
.f4 4 EVPG ?.2 74 FLTD .1*6 EMRG
. 02 " SSET 2.274 EPPG .1C5 UPST
. P2 6 UPST P.274 UPST .r*A THM1
}
. t2 6 FTHE 2.2 74 NORM .De7 NORM
.rl e OBET ?.137 TbFP .G12 SSET
- .faa NOPM .tO7 OBET
} ,
.008 THP1 .QC4 FTHE
.01 2 OBET .404 FTHE
.f? 6 FTHE .967 OBET
)
.029 SSET .a37 GRAV .112 $$ET
.09 1 NORM .3C7 h0RM .368 THM2
.**? THPP .at7 GPAV .369 NORM }
.10P t'P*T .0P7 UPST .377 UPST
.12P EMPG .C'7 EMPG .377 EPPG
.130 FLTDtM-) . c f.7 FLTDEF-1 .382 FLT0tM.) )
55 55 SNSL M FOPC ILD) GLOP 127.01 FLT0tM*)
!?!.26 SSET A9 1
- EPPG P 1. r,4 UPST
- c.64 CDET 3r.62 FTHE y 71.22 NORM 21 72 THP1
-3a.62 rTHE g
-65.64 OEt T
-tr1 2F SSET -
-18 4.6 F bOPP #
-!
- 6.6 6 THF2
-??7.3C Leet -
-r3 4.5 a ryeG #
-?7?.4* rtTDr*-3 DISP t i t. ) GLCP 1.a(7 FLT0tP+) .11R FLT0fM*) #
a
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n d ISPELL C09FO--+ ION SUPERFIFE VE R f lCf1 16A, 1(#f!/038 SYSTEM IPPELL - NOS O PAGE 263 O rg 34/(5/23. GR.25 35. ^
p FGE T S 0JA'J huCLE A P 'TATf0N <g
[MPELL PRODLEM t30Cn1P - PC-03 REV. 1 '
LOOP TEAL D#AIN LINE%
D %
SUPPOST LOAC MUPPARY (CCNTD.3 SUPP SUPP SUPP D1Ph PESULT PESULT ARIS LOAD LOAO LOAD NAPE L OC P; TYPE Cone TYPE UNIT TYPE N-ANIS SET Y-ANIS SET 7-ANIS SET i )
55 (ConTD.) 1.P96 EMRG .11s EMRG 1.894 UDST .112 UPST
)
1.P'3 THP2 .106 THM1 1.877 N0*M .tr$ NOPM 1.R55 )
THP1 812 SSET
. r,2
- SSET .at7 CBET
.C17 OPET .0*4 FTHF
.nm7 FTHE )
.807 FTFE
.(1E GRAY .004 FTHE
."16 NORP .r07 ORET
)
.'16 GRAV .912 SSET
.917 OBET .235 THM2
.r?* SSET .236 NORP
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.t?3 UP!T .244 UPST
.t9= EMPG .245 EMRG
.P46 FLTDtP-1 .249 FLT0fM-> )
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-?4.11 GRAV
-24 11 h0PP )
-24.11 ho*P
-24 11 Ur!T g
-24.11 UPti
-24.11 EMSG
-24.11 EPRG g
-24.11 FLTD
-24 11 FLTDtP-1 PISP ( I P') CLCB .1r* FLT0tP+1 1.5 06 FLTDtP+1 .127 FLTDeM+3
.0f 7 F"PG 1 4** EPPG .123 EMPG
. Pa ? UPFT 1 498 UPet .322 UPST y
. nt? 4
- SET 1 4a% THP2 .115 THP1
.c04 N08M 1.4PM hC#P .114 NORP
.er 4 ~ THM2 1 122 TH"1 .f12 SSET
. ir 3 CPFT .*2t 95ET .397 OBET
.t'? FTHE . *12 OPET .104 FTHE
.*:= FTHE
.'t2 rTHE .**4 FTHE
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.'** eSFT .*t= FTFE .a12 SSET i
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SUPP SUPP St PP DIFn PESULT RESUL1 AVIS LOAD LCAD LOAD NAME LOCN TTPE CCCE TVFE UNIT TYFC F-AFIS SET Y-AXIS SET Z-ARIS SET
)
7*
> (CONTD.) .005 NORP . .012 ORET .074 THM2 )
.005 TPP1 .P12 Urst .075 NORP
.PG7 UDST .r13 Empg . 0P2 UPST
.03P EPPG .?2C SSET .3R3 EMRG )
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-11 75 FTHE
-19.86 OPET
~21.66 UPET
)
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-?3 1 A SSET
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.atr OBET .0P4 FTHE )
.PS4 FTHE
, .PO4 FTHE j
.007 OBET-
.r*4 FTPE .012 SSET
.ill Unef ..r*E THM2 ,
.41' GPET .051 NORP
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.r17 SSET .r*9 EMRG ,
J o
.__ _ m . . __ _ _ _ _ _ _ _ _ _
N
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es IniELL CCRFL--< Og
- SUPERFIFE VERSICN 16Ao !!/31/938 9' STEP IPPELL - Nos d PAGE 265 J
ry R4#e5/23. 09 25.?". '
{g PGE 150JAN htlC LE A P !TATION 1MPELL PROFLEM J30001P - RC-C3 REV. 1 rg LOOP !EAL ODAIN LINFt
$~ sq SUPP02% LO AD f 0MP ARY (CCNTD.)
-} SUPP SUFP SUPF LIph RESULT RESULT AFIS }
LCAD LOAD LOAD NAME LCCN TYPE CCDE TTPr UNTT TYPE X-ANI! SET Y-Anis SET 7-ANIS SET .
J 4' TS (CokTD.) .017 FLTDfM-9 7 .064 FLTDtM-7 ) ,
FCaC (LB1 FLOP 52.!2 FLTDfM*)
5t.42 SSET f 33.58 EM*G 3C.1* CPET )
3P.18 UPST 14.11 FTHE
-14.71 FTHE }
-30 1* UP?T
$ -3r.1* OBET
-33.** ENRG )
-51.42 SSET
-52 52 FLTDtP->
)
DISP GIN) GLOP . 03 " FLTDfM*l .997 THP2(M+3 .135 FLTDEM*3
. r3 5 EMRG 9a4 FLTD .130 [*RG
. d3 8 UPST 994 frog .12* UPST
)
- 9a THM1 .a94 UPST .123 THP1
. P2
- NOPM 494 NORM .172 NORP
. 01 3 THM2 y
.365 THP1 .054 THM2
. *t e $$ET ."12 SSET 9P6 CPET .Ctf CBET y
.f03 FTHE .PO4 FTHE
.ar? FTHE .at? GRAV .Lc4 FTHE
.*36 OPET .ro2 NORP .707 OPET
.ter LPST . ESP GRAV .P9P UPST ) .
i
.607 EP80 .PC2 UPST .0C9 EMRG '
.PCS SSET .Pr? EPoG . PIP ? SET '
. !!
- FLTDtM-3 . r '. P FLTDir-1 .*14 FLTDfM-t )
- 5F *$ S P. G L N FC8C (LF) CLCP 21.** FLTDir.)
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1?.! 1 !$ET
- .*? THF1 n.F ' N0**
7 .1
- cpFT 7.** FTHE
n ag I MP E L L C OR PL--*'! O N SUPERPIPE VEPSION 164. If/31/8?s Sv$7FM IPPFLL - ROS c .
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r.
SUPP SLFP ! OPP DIPS D Ef t:LT PF9LLY ANIF LOAD LosD NAME LOCN T 'f P E CODF LOAD TYRE UNIT TYPE F-ARIS SET Y-ANIS SET a 2-ANIS SET t
- 52 ICONTD.) .12 CRAV '
.12 GRAV
-1 15 THP2
,- -1.27 N08M
-2.C* FTHE
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)
PISP f i P!) GLOP .694 FLTDfM*)
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- .683 NORM
.841 THP1 r
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( 160.M6 EMRG ) ,
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) ;
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.77 GRAV
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.693 N0PM g
.f41 THP1 100N 1 . SNGL M I !
FDPC (LP) CLOP 1(.43 FLTDEM+3 18 29 CSET 63* EMRG I 6 29 UPRT !
6.16 CBET 44 FTHE )
.12 GPAV
.! ? GRAY
.32 NORM
.44 FTHE
-# .15 OPET
-1".2* RSET
-12.27 THM2
-14.39 NOPM
-14.51 THM1. I +
-?P .5 5 UPtf
-2 e.5 7 EPRG
~74 6 9 FLTDtMal DISP (IM3 GLCP .42P FLTDip )
42P EMpG 42M UPST
.428 THP2 427 NOPP *
.a25 THP1
)
1 *N 7 1.r (NCL 7 FOPC (LP) G L C r-
.lf.P2 FLTDtM+)
1".51 SSET '
6.65 EMRG [
F.54 UPST 6.33 OPET i 1 19 FTHE
.24 GRAV
.24 GRAY ,
.?4 WOoM
-1.19 FTHE
.i
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I'MPELL CORPCL-m409 ' J PAGE 218 S UPECPIPE VtRS!ch 16A, 1(/01/P3t Sv$fEW IP7 ELL - N0? ,
P4/05/23 08 25.?9.' .r) ,
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LOOP SEAL DRAIN LINES 'l D tr SUPPCD T LO AD CUPP ARY (CCNTD.)
St1PP SUPP ?UFP CIPE et-LLT RESULT AFIC- LOAD LOAD L040 TAPE LOCN TYPE CODE TYFE UNIT TYPE x-AWIS SET Y-AXIS SET' 2-ANIS- SET T
1"s2 (C0hTD.)
( -
-6.30 00CT ,
-1*.51 SSET ,
=
-19.90 THM2 '
-13.68 NORM i
-33.97 THM1
-39.97 UPST t
-40 98 EMPC ,
-44 26 FLTD(P-3
( ,
CI!P (INI GLOR 428 FLTDeM.) -
3
.42P EPRG i
.428 UPMT 428 THF7 3*
. .427 NOPP
.*25 THM1
)
1C5u Igs T N ;L y FCPC (LB) GLOB 27.50 FLTD(M*)
23 6* FPRG )
??.69 LPS?
18 10 THPP y
17 0" N08d 8.48 ? SET 5.' F CBET I 1.96 THF1 - ) '-
.11 FTHE
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" .6 P OPET y t
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- .5* FLTDt4-1 !
DISP f i r. ) GLOP NFCLIGIELE #!
i i
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l
o
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SUPERPIPE VERSIC4 16A, jf/E1/F38,373'EP IPPELL - NOS' O' PACE 2b9
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P' SUPP SUpr SLPP DIRh RESULT RESULT Avis LOAD LOAD LOAD
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