ML20154A689
| ML20154A689 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/10/1998 |
| From: | Chock A ALTRAN CORP. |
| To: | |
| Shared Package | |
| ML20154A663 | List: |
| References | |
| 96227-TR-03, 96227-TR-03-R00, 96227-TR-3, 96227-TR-3-R, NUDOCS 9810020402 | |
| Download: ML20154A689 (26) | |
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STRUCTURAL DYNAMIC ANALYSIS OF CONTAINMENT COOLING SYSTEM REACTOR BUILDING TRAIN "A" AND TRAIN "B" SUPPLY AND RETURN PIPING Technical Report No. 96227-TR-03 l
Revision 0 prepared for:
Wolf Creek Nuclear Operating Corporation Wolf Creek Nuclear Plant February,1998
. ~
Altran Corporation 200 High Street Boston, MA 02110 (617) 330-1130 FAX: {617) 330-1055 96227.10-SET 9810020402 980928 PDR ADOCK 05000482 P
PDR i
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d Report Record Document No.: 96227-TR.o3 Rev No.: O O2 Nuclear Safety Related Yes X No No. of Sheets (includes Att. A. B C. D. E F)
G. H)
K M 2.
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SUBJECT:
Structural Dynamic Analysis of Containment Cooling System Reactor Building I
j Train "A" and Train "B" Sunolv and Return Piping Wolf Creek Nuclear Plant REV. DESCRIPTION: Revision 0: Oriainal Issue COMPUTER RUNS (identified on Computer File Index):
Yes X N/A Error reports evaluated by:
D. GussM Date: dMSS w
Impacted by error reports:
No _X Yes (if yes, attach explanation)
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_A. Patel DESIGN VERIFICATION:
Required X
Not Required Performed by:
S. Greer v
Date:
b 4-Method of design verification: X Design Review AlternateCalculations (Attached)
Qualification Test (Data /Results Attd.)
Comments resolved by:
O 0 N[O Date:
I' Y ~
Date:
1 N f8 Design verifier concurrence:
/
m,
-,v, APPROVED FOR RELEAS l
{
M Date:
8' PROJECT MANAGER:
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l ENGINEERING MANAGE Date:
1 - /o - f[
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Eissa 96227.10 I
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Computer File Index Doc. No. 96227-TR 03 By:
D. Gosso Date: 2/05/98 y
Rev.No. O Chk: S. Gunta Date: 2/05/98 s
e-u PROGRAM NAME:
ADLPIPE VER.NO.: 4F7B RELEASE DATE:
2/9/96 HARDCOPY LOCATION:
Attachment A USERNAME*: cfhammer DIRECTORY *:
KEYWORDS: ASME C12.1974 l
DEADWEIGHT. THERMAL AND VIBRATION Run Output File Name/
No.
Descrintion Inout File Name*
Dater: Time O
1.
Train "A" Return wlferk7b.out 9/24/97 08:59:39 Deadweight, Thermal, Thermal Accident and Water Hammer (Column Closure) 2.
Train "B" Return trubret.out 2/05/98 08:14:38 Deadweight, Thermal, Thermal Accident Column Closure Time History and Condensation Induced Time History 3.
Train "A" Return wiferk7a.out 1/21/98 10:38:49 Deadweight, Thermal, Thermal Accident, Water Hammer (Condensation Induced) l
- indicates optionalinformation, if the input scho is not printed on the output file, the input file shall be identified and retained separately.
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Techzical Report No. 96227-TR-03 o
Revision 0
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TABLE OF CONTENTS Title Page.............................................
1 D
Report Record Sheet.......
}
Computer File Index........................
......................2 3
Table of Contents.........................
co
........................... 4 1.0 OBJECTIVE AND SCOPE...............
..6 1.1 Objective...................
6 1.2 Scope............
6 2.0 EVALUATION METHODOLOGY & ACCEPTANCE CRITERIA 7
2.1 Method of Analysis...............
7 2.2 Analytical Model........
9 2.3 Acceptance Criteria 9
3.0 RESULTS & DISCUSSION 11 3.1 Discussion 11 3.2 Piping................................................
11 3.3 Pipe Supports.............
12 3.4 Fan Cooler Nozzles......
12 3.5 Containment Penetrations...................
12 4.0 INPUT DATA................................
12 5.0 CONCLUS ION.............................................
13
/
6.0 REFERENCES
14 ATTACHMENTS A - Pipe Stress Summaries for Train A and B Return Line A-1 to A-52 B - Pipe Support Load Summaries for Train A and B Return Lines.......................
...... B-1 to B-315 C - Waterhammer Loads.....
C-1 to C-Il D - ADLPIPE ComputerInput Listings for Train A and B Return Lmes.......................
D-1 to D-35 E - Piping Drawings........................... E-I to E-3 F - Train A and Train B Supply Line Comparison to the Return Line................................... F-1 to F-11 G - Containment Cooler Evaluation...'.
G-1 to G-43 H - Integral Welded Attachment Evaluation.............. H-1 to H-46 k
96227.10 SE1 4
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Revision 0 e
u LIST OF TABLES & FIGURES
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Table 1 Piping Load Combinations / Acceptance Criteria......
20 P
Table 2 Pipe Support Load Combination / Design Basis Acceptance Criteria.
. 20 Table 3 Pipe Support Load Combination / Operability Acce 20 3
Pipe Stress Summary.....................ptance Criteria 4.;
Table 4 21 Table 5 Containment Penetration Stress Summary.........
21 Table 6 Train "A" Return Line Pipe Support Function.....
22 c,
Table 7 Train "B" Return Line Pipe Support Function.......
23 Table F-1.0 Train "A" Comparison of Supply and Return Line....
.... F-3 Table F-2.0 Train "B" Comparison of Supply and Return Line.........
F-6 Table F-3.0 Supply and Return Line Pipe Properties...............
F-8 i
Table F-4.0 Peak Differential Pressures.......
F-9 Table G-1.0 Nozzle Load Summary for Containment Coolers.......
..... G-2 Table H-1.0 Integral Welded Attachments (IWA)....
.... H-3 Figure 1 Stress Isometric Train "A" Return Line 24 Figure 2 Stress Isometric Train "B" Return Line...........
25 Figure 3 Waterhammer Pressure Pulse...................
26 0
O 96227.10 SET 5
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e Techrical Report Nr. 96227-TR-03 Revision 0 Oeu 1.0 OBJECTIVE AND SCOPE 1,1 Obiective
}
The purpose of this evaluation is to perform a structural analysis of the Containment
{'
Cooling system, Reactor Building Train "A" and Train "B" Return lines and Supply lines at the Wolf Creek Nuclear Plant. The Train "A" and Train "B" Return structural dynamic analysis is based on elastic principles using the ADLPIPE computer Code [8]'. From the results of the Train "A" and Train "B" Return lines, a qualitative assessment of the Train "A" and Train "B" Supply lines was made.
A waterhammer event has been postulated to occur due to the simultaneous occurrences of a Loss of Coolant Accident (LOCA) with Loss of Offsite Power (LOOP). This scenario as described in USNRC Bulletin 96-06, Ref.1, results in steam formation in the coolers.
Dunng this event, two possib> waterhammers have been postulated to occur due to
- 1) condensate void collapse and 2) column closure. Both of these result in a column closure wate-henma which occurs afier resumption of flow from pump restart. The moving flow impacts the :tationary water resulting in a column closure waterhammer.
This loading results in a transient pressure wave which travels through the system.
f Altran has performed a structural assessment of the subject piping system to "x
determine the ability of the piping system (pipe, supports, equipment nozzles, and penetrations) to withstand such loadings, maintain the integrity of the pressure boundary, and ensure the piping will continue to pass flow.
1.2 Scope Train "A" The Supply line piping of Train "A" starts at Reactor Building Penetration P-71 and terminates at the inlet nozzles to Containment Coolers SGN01 A and SGN01C.
The Return line piping of Train "A" starts at Containment Coolers SGN01A and SGN01C and exits the Reactor Building through Penetration P-73.
Train "B" The Supply line piping of Train "B" starts at Reactor Building Penetration P-28 and terminates at Containment Coolers SGN01B and SGN01D.
5 [ ] Indicates reference number from Section 6.0 96227.10 ser 6
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~h-Altras Cerporation Technical Rep;rt No. 96227-TR-03 a
Revision 0 O 'u The Return line piping of Train "B" starts at Containment Coolers SGN01B and SGN01D and exits the Reactor Building through Penetration P-29.
The piping and support configuration for the containment cooling system Train "A" -
Return line and Train "B" Return line are shown in Figure 1 and Figure 2, y
6, respectively. The piping consists of 14",10", 8" and 6" Schedule 40 carbon steel pipe.
2.0 EVALUATION METHODOLOGY & ACCEPTANCE CRITERIA This section of the report discusses the analytical modeling details, applied loadings, and acceptance criteria.
2.1 Method of Analysis The structural dynamic analysis is performed using the commercially available code ADLPIPE, Ref. 8. It is a general purpose piping analysis code used widely by the nuclear industry.
Once the time-history unbalanced wave forces are determined for each straight run of piping, they are applied to a structural model of the piping system using the ADLPIPE program.
The piping system structurr5 medel constructed for this analysis is represented by an ordered set of data whic! nutaerically describes the physical systems.
1 Node point coordinates and incremental lengths of the members are determined from spatial geometric drawings. N geometrical properties along with the modulus of elasticity, E, are speedied for er.a element. The supports are represented by stiffness matrices which defme restraint characteristics of the supports. The well-known equations of motion can be written in matrix form as:
M {R) + C {i} + K {x} = (f(t)}
(3.1)
Where:
C = damping matrix
{x}
= displacement vector M = mass matrix
{x}
= velocity vector K = stiffness matrix
{R}
= acceleration vector
{f{t)} = vector of applied forces The natural frequencies and associated mode shapes can be obtained by solving the characteristic equation:
96227.10 SET 7
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Techrical Report No. 96227-TR-03 i
p Revision 0 O,u det. lAI-M Kl = 0 (3.2)
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Where:
M'
= inverse of the mass matrix 1
I
= identify matrix j
A
= scalar eigenvalue i
Each eigenvalue 1, = e,2 of Equation (3.2) determines a natural frequency, and the associated eigenfunction {$,} is the mode shape. The matrix & whose columns are the eigenvectors {@,) is called the modal matrix.
Matrix Equation (3.1) represents the dynamic equilibrium of the masses of a three-i i
dimensional structure with applied forces in any or all of the coordinate directions.
Equation (3.1) can now be transformed into modal coordinates by defining the i
following linear transformation:
{x} = ${q}
(3.3)
\\
Where:
(q)
= modal coordinates l
l 4
= modal matrix
{x}
= 4 (q}
(3.4)
O Applying Equations 3.3 and 3.4 and normal mode theory, the actual time responses of the structure for the ith mass direction are:
x(t)
=E4,,,q,(t)
(3.5) i a
A(t)
=E$3,4,(t)
(3.6) a 2,(t)
=E$3q,(t)
(3.7) a The solution is conducted in two parts. The first part is to find the frequencies and mode shapes ofa three-dimensional structure. The second part takes the modal data, generates and solves the modal differential equations which result from time varying applied internal forces.
The time-history internal forces and displacements are then input into a series of post-processing programs used to determine the maximum forces, moments, and l
displacements that exist at each end of the piping elements and the maximum loads for the piping supports. The results are saved on magnetic media for future use in piping stress analysis and support load evaluation.
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2.2 Analvtient Model A
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2.2.1 Piping Model
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M The piping systems were coded in the ADLPIPE Computer Code, Ref. 8, and was subjected to loadmgs ofDeadweight (D), maximum operating pressure (P),
column closure waterhanur.er (CCWH), condensation induced waterhammer pulse (CIWH), together with thermal normal (THERM NORM) and thermal accident (THERM ACCD) conditions. The waterhammer event was evaluated as a time history dynamic analysis. The technique used to qualify the waterignouer is based on determmation of the piping system response to known time dependent forces to calculate resulting stresses and loadings. The response of the piping system is computed by normal mode superposition technique. For the time history dynamic analysis, a modal damping value of 2% was used. The coding of the piping system was in accordance with the as-built isometrics of l
Ref. 3.
2.2.2 Support Details Piping supports were included in the model, based on the support function O
shown on the support drawings [3]. Table 6.0 and 7.0 provide the hanger numbers, ADLPIPE node point and pipe support function for Train "A" and Train "B" retum lines respectively. Stiffness values used were in general agreement with values from the support calculations.
2.3 Accentance Criteria The piping and pipe support systems were evaluated in accordance with the Wolf Creek Design Criteria for UFSAR Design Basis and Functionality acceptance (2].
Since the concurrent combination of seismic and LOOP /LOCA is not included in the UFSAR design basis and the seismic event will not cause the waterhammer, they are not combined in this analysis.
Th'e loading combinations used for the evaluation of the Train "A" and Train "B" Return lines are as outlined in Table 1. The thermal case, under the LOCA ambient condition, denoted as Thermal Accident (THERM ACCD)is considered a faulted event. In accordance with the requirements of the ASME III, Appendix F Code, thermal loading for one time fauhed events need not be evaluated for pressure boundary components. However, as a point of reference only, stresses were calmistal and compared to ASME acceptance criteria. The pipe support acceptance criteria is based on the evaluation of all loadings, including THERM ACCD. The design basis acceptance criteria is based on meeting AISC Code [4], stress allowables, with consideration of the 1.33 stress increase considered for occasional loadings. The 96227.to ser 9
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F pipe support - design basis - acceptance criteria is shown in Table 2.
For the evaluation of any pipe supports that do not meet the design basis acceptance criteria, an operability acceptance criteria is utilized in accordance with the guidelines y
recommended in USNRC IN95 09, Ref. 5, which endorses the use of USNRC GL91-18, Ref. 6. GL91-18 provides guidance for the resolution of degraded and non-
.o
- o conforming conditions and/or operability. Section 6.13 of Ref. 6 (Part 9900 -
Technical Guidance) provides requirements for Piping and Pipe Supports. This, in turn, endorses the use of Appendix F of the ASME Section III Code [7]. The requirements for the evaluation and loading were as agreed upon by Wolf Creek. This l
acceptance criteria is shown in Table 3.
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Revision 0 O 'e 3.0 RESULTS & DISCUSSION The results of the piping qualification for the containment cooling system Reactor Building 3
Train "A" and Train "B" are outlined below.
\\
2 0) 3.1 Di=coulon The Train "A" Return line was qualified for the condensation induced waterhammer event in Altran Report %227-TR-02 [13] with the results of the analysis included in the appropriate **=chments at the end of this report. The Train "A" Return line was analyzed for the column closure waterhammer event in this report.
The Train "B" Return line evaluation for the column closure wate nammer event and the condensation induced waterhammer event were qualified in this report with the results provided in the attsdoucia section at the end of this repart. The results of the Train "B" Return line loading conditions analyzed here supersede the results from Altran Calculation 94100-C-02 [11].
The two watesero.uer pressure pulses are applied to a structural model of the piping system. The ADLPIPE [8] computer code is used, and the pressure pulse is applied as a time history load in a dynamic evaluation. The analytical technique computes the piping system response to the time dependent forcing functions. The response of the s
piping system is computed by the normal mode superposition technique. The piping models are shown in Figure I and Figure 2. The segment loading is determined by assuming that the pulse is initiated at the elbow at the end of the horizontal run and that the load propagates in each direction from this location. Forces will offset at opposing changes in direction when the pressure wave reaches the opposite ends of a segment. The pressure pulse will reflect off the free surface at the water to steam interface. The resulting segment forcing functions are shown in Attachment C.
3.2 Bams The piping system structural evaluation was performed in accordance with the requirements of the ASME III, Subsection NC Code [9] and in accordance with the FSAR regarements for WCNP [2] as outlined in Section 2.2 and 2.3. A piping stress resuhs summary table for the highest loaded location in the Train "A" Return line and the Train "B" Return line models are shown in Table 4. All piping stresses are within the Code allowables and meet the acceptance criteria of WCNP FSAR requirement stress limits. A summary of the Train "A" and Train "B" Return lines pipe stresses for each Code equation are included in Attachment A. The assessment ofthe Train "A" and "B" Supply lines is included in Attachment F.
96227.10 SET ll
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W In the Train "A" Return line model, Hanger R013 was considered " inactive" in the
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model. In addition, the Train "B" Return line model Hanger R001 was considered
]
" inactive" for the qualification of the line.
s j
3.3 Pine Sunnorts 0)
The resulting pipe support loads for deadweight (D), thermal accident (THERM ACCD), column closure waterhammer (CCWH) and condensation waterhammer (CIWH) were obtained from the ADLPIPE evaluation. A combination of is considered as the fauhed loadmg condition and the pipe supports were qualifie this combined loadmg. Quahfication was based on load ratings to previously qual loads and ensuring that the support component interaction ratios are within the acceptable limits. A detailed evaluation of the supports are found in Attachment B.
In addition, several pipe supports from Train "A" and Train "B" were welded to the pipe pressure boundary, commonly known as integral welded attachment.
The evaluation of the integral welded attachments are provided in Attachment H.
3.4 Fan Cooler Nozzles All stresses of attached piping at the nozzle are well below allowables and the integnty of the nozzle is still sida k+i A comparison of the calculated nozzle loads
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to allowable loads is provided in Attachment G. In addition, the cooling coilings have been reviewed for the one time loading event and found acceptable.
3.5 Containment Penetrations The stresses for the different loadmg conditions for the piping attached to the Reactor Building penetrations are within Code allowables. In general, penetrations are more rigid and stronger than the attached piping, and therefore, the integrity of the penetration is not compromised. The stresses at the penetration are shown in Table 5.
4.0 INPUT DATA The ADLPIPE piping models of the containment cooling system piping for Train "A" and Train "B" Return lines were developed based on the isometric drawings provided by Wolf Creek [3]. The computer model of the Train "A" Return line piping geometry is shown in Figure 1. The computer model of the Train "B" Return line piping geometry is shown in Figure 2.
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5.0 CONCLUSION
4 The results of the ADLPIPE computer analyses have demonstrated that the Wolf Creek l
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Nuclear Plant Containment Cooling system Reactor Building Train "A" and Trai a
which are illustrated in Figure 1 and Figure 2, respectively are adequately designed M
withstand both waterhammer pressure pulse events postulated to occur.
The piping, supports, penetration, and cooler nozzles have each been satisfactorily evaluated for these i
waterhammer events. In addition, the Train "A" and Train "B" Supply lines, support l
penetration and cooler nozzles are acceptable based on a comparison to the Return lines.
For the Train "A" and Train "B" Supply and Return lines, the piping stresses meet the Wolf Creek acceptance criteria for an emergency condition. All pipe supports meet the des acceptance criteria for this loading condition.
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Tech ical Report No. 96227-TR-03 o
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i,.0 REFERENCES
\\
i 1.
USNRC Bulletin No. 96-06, " Assurance of Equipment Operability & Containment Integrity j
g During Design Basis Accident Conditions," September 19,1996.
2 m
2.
Updated Final Safety Analysis Report (UFSAR), Wolf Creek 3.
WolfCreek Drawings A. PipingIsometrics l
Train "B" M-13GN02(Q) Rev.02 Contamment Cooling System Reactor Building Train "B" (Supply and Return Lines)
M-13GN02 Rev.03 Containment Cooling System Reactor Building Train "B" (Supply i
and Return Lines)
M-23GN02 (Q) Rev.7 Contamment Cooling System Reactor Building Train "B" (Supply and Return Lines)
M-15GN02 (Q) Rev. 5 Hanger Location Dwg. Containment Cooling System Reactor Building Train "B" (Supply and Return Lines)
- . q
()
Train "A" M-15GN01 (Q) Rev.5 Hanger Location Dwg. Containment Cooling System Reactor Building Train "A" (Supply and Return Lines).
i B. HangerDrawings Train "A' Sunniv Line Tag. No.
Hanger No.
Drawing No.
I l
CM1 l
HM1 R001 C002 1-GN01-C002/231 (Q)
M-16GN01 Rev.1 H002 0-GN01-H002/232 (Q)
M-06GN01 Rev. I C003 1-GN01-C003/232 (Q)
' M-16GNO1 Rev. 2 C004 CO16 1-GN01-C016/242 (Q)
M-16GN01 Rev. 5 1\\
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TechIlcal Report No. 96227-TR
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Tag. No.
Hanger No.
Drawing No.
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R002 0-GN01-R002/242 (Q)
M-06GN01 Rev. O g
R003 1-GN01-R003/252 (Q)
M-16GNO1 Rev. 5
.c C009 to H004 C010 CO11 CO12 R007 C013 R008 C014 Train "N Retum Line Tag No.
Hanger No.
Drawing No.
R011 1-GN01-R0ll/251 (Q)
M-16GN01 Rev. 5 R012 1-GN01-R012/251 (Q)
M-16GN01 Rev. 3 C015 A
1-GN01-C015/251 (Q)
M-16GN01 Rev. 3 R010 d
1-GNOl-R010/252 (Q)
M-16GN01 Rev. 6 H005 1-GN01-H005/252 (Q)
M-16GN01 Rev. 4 C018 1-GNOl-C018/252 (Q)
M-16GN01 Rev. 4 H007 1-GN01-H007/252 (Q)
M-16GN01 Rev. 3 R009 l-GN01-R009/252 (Q)
M-16GN01 Rev. 2 R014 1-GNOl-R014/252 (Q)
M-16GN01 Rev. 5 H006 1-GNOl-H006/252 (Q)
M-16GN01 Rev. 2 C019 l-GN01-C019/252 (Q)
M-16GN01 Rev. 5 R005 1-GNOl-R005/252 (Q)
M-16GN01 Rev. 3 R004 1-GN01-R004/242 (Q)
M-16GN01 Rev. 5 C017 1-GN01-C017/242 (Q)
M-16GNO1 Rev. 2 C008 1-GN01-C008/232 (Q)
M-16GN01 Rev. 6 C007 1-GN01-C007/232 (Q)
M-16GNO1 Rev. 4 H003 1-GN01-H003/232 (Q)
M-16GNO1 Rev. 2 C006 1-GN01-C006/231 (Q)
M-16GN01 Rev. 6 C005 1-GN01-C005/231 (Q)
M-16GN01 Rev. 2 i
waar.to-in 15
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Train "B" Sunolv Line
}
Tag No.
Hanger No.
Drawing No.
CO24 1-GN02-C024/241 (Q)
M-16GN02 Rev. 4 m
R014 0-GN02-R014/251 (Q)
M-06GN02 Rev.1 R012 0-GN02-R012/251 (Q)
M-06GN02 Rev.1 R010 0-GN02-R010/241 (Q)
M-06GN02 Rev.1 C027 0-GN02-C027/251 (Q)
M-06GN02 Rev.1 CO26 0-GN02-C026/251 (Q)
M-06GN02 Rev.1 I
C022 0-GN02-C022/231 (Q)
M-06GN02 Rev.1 C010 0-GN02-C010/241 (Q)
M-06GN02 Rev. 2 C002 1-GN02-C002/231 (Q)
M-16GN02 Rev. 2 R008 1 GN02-R008/242 (Q)
M-16GN02 Rev. 3 C006 1-GN02-C006/231 (Q)
_ M-16GN02 Rev. 3 C008 1-GN02 C008/232 (Q)
M-16GN02 Rev. 3 R006 0-GN02-R006/252 (Q)
M-06GN02 Rev.1 R004 1-GN02-R004/242 (Q)
M-16GN02 Rev. 3 C020 0-GN02-C020/252 (Q)
M-06GN02 Rev.1 C018 0-GN02-C018/252 (Q)
M-06GN02 Rev.1 C014 0-GN02-C014/242 (Q)
M-06GN02 Rev.1 p/
0-GN02-C012/242 (Q)
M-06GN02 Rev. I CO12 w
R002 0-GN02 R002/231 (Q)
M-06GN02 Rev. 2 C004 1-GN02-C004/231 (Q)
M-16GN02 Rev. 4 C016 1-GN02-C016/252 (Q)
M.16GN02 Rev. 2 Train "B" Retum Line Tag No.
Hanger No.
Drawing No.
C001 1-GN02-C001/231 (Q)
M-16GN02 Rev. 4 C003 1-GN02-C003/231 (Q)
M-16GN02 Rev. 5 R001 1-GN02-R001/231 (Q)
M-16GN02 Rev. 3 C005 1-GN02-C005/231 (Q)
M-16GN02 Rev. 3 C007 1-GN02-C007/232 (Q)
M-16GN02 Rev. 2 C009 0-GN02-C009/242 (Q)
M-06GN02 Rev. 4 C011 1-GN02-C011/242 (Q)
M-16GN02 Rev. 3 C013 1-GN02-C013/242 (Q)
M-16GN02 Rev. 6 R003 1 GN02-R003/242 (Q)
M-16GN02 Rev. 3 R005 1-GN02-R005/252 (Q)
M-16GN02 Rev. 2 H001 1-GN02-H001/252 (Q)
M-16GN02 Rev. 2 R007 1-GN02-R007/252 (Q)
M.16GN02 Rev. 4 96227.1o sti 16
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o Revision 0 Tag No.
Hanger No.
Drawing No.
Col 5 1-GN02-C015/252 (Q)
M.16GN02 Rev 4 l
x C017 1-GN02-C017/252 (Q)
M-16GN02 Rev. 3 m
C019 l-GN02-C019/231 (Q)
M-16GN02 Rev. 7 01 R009 l-GN02-R009/241 (Q)
M-16GN02 Rev. 2 CO21 1-GN02-C021/241 (Q)
M-16GN02 Rev. 3 ROIS 1-GN02-R015/251 (Q)
M-16GN02 Rev. 2 CO28 1-GN02-C028/251 (Q)
M-16GN02 Rev. 2 CO25 1-GN02-C025/251 (Q)
M-16GN02 Rev. 2 R013 1-GN02-R013/251 (Q)
M-16GN02 Rev. 7 4.
American Institute of Steel Construction, " Manual of Steel Construction," Eight Editi 1980, AISC Chicago.
5.
USNRC IN95-09: "Use ofInappropriate Guidelines & Criteria for Nuclear Piping and Support Evaluation & Design."
6.
USNRC GL91-18, "Information to Licensees Regarding Two NRC Inspection Manual i
Sections on Resolution ofDegraded & Nonconforming Conditions and Operability."
Q 7.
ASME B&PVC Section III, Appendices.1989.
l %J 8.
ADLPIPE, " Static & Dynamic Pipe Stress Analysis," Version 4F7B, Research Engineers Yorba Linda, CA.
9.
ASME,Section III, Subsection NC, Div.1,1974 with Addendum through 1976.
10.
WCNOC Station Procedure CN-3.01 11.
Altran Corporation Calculation No. 94100-C-02, " Structural Dynamic Analysis of ESW System Waterhammer," Rev.1, June 1995.
12.
Altran Corporation Technical Report No. %227-TR-01, " Containment Fan Cooler Respon to a Simultaneous LOCA and LOOP Event," Rev. 2, February,1997.
13.
Altran Technical Report No. %227-TR-02, " Structural Dynamic Analysis of Containment Cooling System Reactor Building Train "A", Rev 0, April,.1997.
l gg
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Techrical Report No. 96227-TR-03 m
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14.
Bechtel Calculations for Wolf Creek Nuclear Plant.
a g
- a. Calc. No. GN01-3 Rev. O Hgr. 0-GN01-H002-232 (Q) Train A Supply a
- b. Calc. No. GN01-35 Rev. 4 Hgr. 0-GN01-C016/242 (Q) Train A Supply
- o Hgr. 0-GN01-C007/242 (Q)
- c. Calc. No. GN01-1 Rev. 3 Hgr. 0-GNOl-C003/232 (Q) Train A Supply Hgr. 0-GN01-C006/231 (Q) Train A Retum Hgr. 0-GNOI-H003/232 (Q) Train A Return Hgr. 0-GN01-C007/232 (Q) Train A Return Hgr. 0-GN01-C002/231 (Q) Train A Supply Hgr. 0-GN01-H002/232 (Q) Train A Supply
- d. Calc. No. GN01-12 Rev. 4 Hgr. 0-GN01 R003/252 (Q) Train A Supply Hgr. 0-GNOl-R005/252 (Q) Train A Return Hgr. 0-GN01-R002/252 (Q) Train A Supply Hgr. 0-GNOl-R004/252 (Q) Train A Return
- e. Calc No. GN01-2 Rev. O Hgr. 0-GN01-R002/242 (Q) Train A Supply f.
Calc No. GN01-14 Rev.1 Hgr. 0-GN01-H005/252 (Q) Train A Return
- g. Calc No. GN01-28 Rev. 4 Hgr. 0-GN01-R010/252 (Q) Train A Return
- h. Calc No. GN01-27 Rev.1 Hgr. 0-GN01-C015/251 (Q) Train A Return
- i. Calc No. GN0138 Rev.1 Hgr. 0-GN01-R012/251 (Q) Train A Return
- j. Calc No. GN01-32 Rev. 2 Hgr. 0-GNOl-ROI1/251 (Q) Train A Return I
- k. Calc No. GN01-39 Rev.1 Hgr. 0-GN01-H006/252 (Q) Train A Return 1.
Calc No. GN01-40 Rev. 2 Hgr. 0-GN01-R014/252 (Q) Train A Return
- m. Calc No. GN01-30 Rev.1 Hgr. 0-GN01-R009/252 (Q) Train A Return
- n. Calc No. GN01-22 Rev. 2 Hgr,0-GN01-H007/252 (Q) Train A Return
- o. Calc No. GN02-1 Rev. 2 Hgr. 0-GN02-C001/231 (Q) Train B Return
- p. Calc No. GN02-3 Rev.1 Hgr. 0-GN02-R001/231 (Q) Train B Return Hgr. 0-GN02-R002/231 (Q) Train B Supply
- q. Calc No. GN02-6 Rev. 3 Hgr. 0-GN02-R003/242 (Q) Train B Return r.
Calc No. GN02-8 Rev 4 Hgr. 0-GN02-C005/231 (Q) Train B Return
- s. Calc No. GN02-8-W Rev. O Hgr. 0-GN02-C005/231 (Q) Train B Return t.
Cale No. GN02-8-W-A Rev. O Hgr. 0-GN02-C005/231 (Q) Train B Return
- u. Calc No. GN02-12 Rev.1 Hgr. 0-GN02-C007/232 (Q) Train B Return
- v. Calc No. GN02-12-W Rev. 4 Hgr. 0-GN02-C007/232 (Q) Train B Return
- w. Calc No. P-GN02-14 Rev. 4 Hgr.1-GN02-C015/252 (Q) Train B Return
- x. Calc No. P-GN02-19 Rev. 5 Hgr.1-GN02-R005/252 (Q) Train B Return y Calc No. GN02-10 Rev. 3 Hgr. 0-GN02-C003/231 (Q) Train B Return
- z. Calc No. GN02-10-W Rev. O Hgr. 0-GN02-C003/231 (Q) Train B Return aa. Calc No. GN02-25 Rev.1 Hgr. 0-GN02-R009/241 (Q) Train B Return Hgr. 0-GN02-R010/241 (Q) Train B Supply ab. CalcNo. GN02-25-W Rev. O Hgr. 0-GN02-R009/241 (Q) Train B Return l
ac. Calc No. GN02-27 Rev. 2 Hgr. 0-GN02-C019/231 (Q) Train B Return l
96227.10 SET 8
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Revision 0 0:
Hgr. 0-GN02-C022/231 (Q) Train B Supply s;
ad. Calc No. GN02-27W Rev.0 Hgr.1-GN02-C019/231 (Q) Train B Return ae. Calc No. GN02-29 Rev. 2 Hgr. 0-GN02-H001/252 (Q) Train B Return g
af. Calc No. GN02-32 Rev. 3 Hgr. 0-GN02-C011/242 (Q) Train B Return l
2 Hgr. 0-GN02-C012/242 (Q) Train B Supply M
ag. Calc No. GN02-34 Rev. 4 Hgr. 0-GN02-C013/242 (Q) Train B Return Hgr. 0-GN02-C014/242 (Q) Train B Supply ah. Calc No. GN02-34-W Rev. O Hgr. 0-GN02-C013/242 (Q) Train B Return al. Calc No. P-GN02-39 Rev. 5 Hgr.1-GN02-C009/242 (Q) Train B Return aj. Calc No. GN02-41 Rev. 3 Hgr. 0-GN02-C021/241 (Q) Train B Return ak. Calc No. GN02-41-W Rev. O Hgr.1-GN02-C021/241 (Q) Train B Return al. Calc No. P-GN02-43 Rev. 3 Hgr.1-GN02-R007/252 (Q) Train B Return am. Calc No. GN02-45 Rev.1 Hgr. 0-GN02-R015/251 (Q) Train B Return an. Calc No. GN02 45 W Rev. O Hgr. 0-GN02-R015/251 (Q) Train B Retum ao. Calc No. GN02-45-W-A Rev.0 Hgr. 0-GN02-R015/251 (Q) Train B Return
.15.
Wolf Creek Nuclear Operating Corporation, Piping Class Summary, MS-01, Rev. 40, plus Design Document Change Notice dated 2/3/97.
16.
Wolf Creek Nuclear Operatmg Corporation, Piping Class Sheets, MS-02, Rev. 42 plus Plant Modification Package Change Notice, PMP No. M-753-W-MS-02-40.01.
17.
" Design of Welded Structures," by Omer W. Blodgett, The James F. Lincoln Arc Welding Foundation,1982.
18.
Bergen-Paterson Pipe Support Corp., Catelog No. 77NFR1 for Nuclear Service'ASME Section HI Subsection NF.
19.
Grinnell Corporation DRS/LCD Package Rev.15.
20.
ALTRALUG, "A Program for the Design and Analysis of Welded Piping Attachments,"
Altran Document No. 92117-UM-02, Version 1, Users Manual, May 1992.
I 21.
ASME Section IH, Division 1, Nuclear Code Case N-318-3, " Procedures for Evaluation of the Design of Rectangular Cross Section Attachments on Class 2 or 3 Piping," Approval Date: September 5,1985.
I 22.
R.C. Rodabaugh, " Review ofASME Code Cases N-122 and N-318-Lugs on Straight Pipe,"
for PVRC Design Division Committee on Piping, Pumps and Valves, August 1990 Draft.
l 23.
AISC, " Manual of Steel Construction," Seventh Edition,1970.
i 24.
PD STRUDL Version 0496.
i 96227.to su 19 I
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Load Condition Load Combination Stress Allowable ASME Section IU
' Normal Dwt + P 1.0Sh EQ 8 o
Emergency Dwt + P + WH 1.8Sh EQ9 l
co Thermal Thermal or THERM Sa EQ 10 ACCD Thermal + Normal Dwt + P + (Thermal or Sa +1.0Sh EQ.11 1
THERM ACCD)
Table 1 - Piping Load Combinations / Acceptance Criteria Where:
Dwt = Pipe selfweight WH = LOOP /LOCA waterhammer(Colunm P = Pressure 1
Closure or Condensation Induced)
THERM ACCD = Thermal Thermal = TLermal Normal Accident from LOCA Sa = f(1.25Sc + 0.25Sh)
/
Load Condition Load Combination Stress Allowable Stress Criteria Faulted Dwt+WH+ THERM ACCD 1.33S S is AISC Code allowable Table 2 Pipe Support Load Combination / Design Basis Acceptance Criteria Load Condition Load Combination Stress Allowable Code Reference Faulted Dwt+WH+ THERM ACCD App Flimits ASME Sect. III 1
Table 3 Pipe Support Load Combination / Operability Acceptance Criteria O
/
96227.io su 20
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Technical Report No. 96227-TR-03 7
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Load Load Data Calc.
Stress Allow Int.
0 Condition Combination Point Stress Criteria Stress Ratio 0)
(psi)
(psi)
Normal Dwt + P 1000 6,953 1.0Sh 15,000 0.47 Emergency Dwt + P + WH 1000 26,988 1.8 Sh 27,000 1.00 Train "A" Thermal THERM 2690 23,162 Sa 22,500 1.03 Return Line ACCD Thermal +
THERM 2690 25,248 Sa + 1.0 37,500 0.67 Normal ACCD + Dwt.
Sh
+P Train "B" Normal Dwt + P 215 6,717 1.0 Sh 15,000 0.45 Return Line Emergency Dwt +P+WH I10 24,584 1.8 Sh 27,000 0.91 Thermal THERM 75 12,095 Sa 22,500 0.54 ACCD Table 4 Pipe Stress Summary Penetration Dwt Pressure WH THERM Stress Allow Int.
No.
Stress Stress Stress ACCD Summation Stress Ratio (psi)
(psi)
(psi)
Stress (psi)
(psi)
(psi)
Train "A" P 73 5,352 1,602 20,035 6,515 33,504 45,000 0.75 Return (N.P.1000)
Line Train "B" P-29 2,180 1,598 10,379 1,691 15,848 45,000 0.35 Return (N.P. 5)
Line Table 5 Containment Penetration Stress Summary O
96227.10-sti 21
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Tech 11 cal Report No. 96227-TR-03 o
Revision 0 o
y Table 6.0 Train "A" Return Line Pipe Support Function a)
Pipe dupport Node Point Pipe Support Function
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Hanger No.
(NP)
R= Rigid J) cn C005 1200 RX and RY C006 1340 RX and RY H003 1380 RY C007 1420 RX and RY i
LOOS 1455 Lateral Rigid C008 1460 RY C017 (1) 1540 RX, RY, RZ R004 1570 RX and RZ R005 1630 RX and RZ C019 1710 RY C019 1715 Lateral Snubber C018 1775 RY C018 1780 Lateral Snubber H005 1900 RY R010 1980 RX R010 1985 Z Snubber C015 2040 RX and RY R012 2070 X Snubber and Y Snubber R0ll 2110 Z Saubber H006 2570 RY R014 2610 RX R014 2615 Z Snubber R009 2720 RX H007 2740 RY NOTE: (1) Integral Welded Anachmant (IWA) c 96227.10 SFT 22
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Revision 0 3
Table 7.0 Train "B" Return Line Pipe Support Function 2
Pipe Support Node Point Pipe Support Function 0
Hanger No.
(NP)
R = Rigid C001 40 RX and RY 01 C003 57 RX and RY R001 65 RZ (inactive)
C005 85 RX and RY C007 100 RX and RY C009(1) 117 RX,RY,RZ C011 140 RY, Lateral C013 160 RY, Lateral
.R003 172 Lateral R005 187 RX and RZ H001 215 RY R007 (1) 217 X Snubber C015 223 RY and RZ C017 240 RY and RZ C019 320 RY and RZ R009 335 RZ C021 (1) 347 RX, RY, RZ ROIS 390 RX C028 399 RY and RZ CO25 407 RY and RZ R013 (1) 409 X Snubber NOTE: (
ntegralWelded Attachment (IWA) i (D
96227.10 SET 23
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".~1 Altra3 C:rporatim 31 Tech ical Report No. 96227-TR-03 U
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AIR COOLER "If AND '0" RETURN UNES'
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TRAVEL SPEED, C =2300 ft/sec i
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