ML20155K526

Forwards Response to Question 12 of Kn Jabbour 870731 Request for Addl Info Re Performance Testing of Relief & Safety Valves,Per NUREG-0737,Item II.D.1.Response to Question 8 Transmitted W/Util

ML20155K526
Person / Time
Site:	Catawba
Issue date:	06/14/1988
From:	Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8806210258
Download: ML20155K526 (35)

Text

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,J DUKE POWER GOMPANY P.O. DOX 33180 CHARLOTTE, N.o. 28242

'HALH.TUGKER TELEPlf0NE rwa emesson=T (7o4) 073-4531 auctuan ,moovenon June 14, 1988 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555

Subject:

Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 NRC Request for Additional Information on Performance Testing of Relief and Safety Valves Gentlemen:

Dr. K. N. Jabbour's letter of July 31, 1987 transmitted a request for additional information regarding the performance testing of relief and safety valves (Item II.D.1 of NUREG-0737). These questions were based on Duke Power Company submittals dated October 26, 1983 and February 3, 1984. Duke Power provided responses to all questions other.than Question No. 8 per my April 29, 1988 letter. Please find attached the response to Question No. 12 which was inadvertently left out of the April 29, 1988 submittal. A response to Question No. 8 was transmitted per my May 31, 1988 letter.

Very truly yours, tal B. Tucker JGT/32/sbn xc: Dr. J. Nelson Grace, Regional Administration U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. P. K. Van Doorn NRC Resident Inspector f

Catawba Nuclear Station 1 \

8806210258 880614

• PDR ADOCK 05000413 P DCD

t t Question 12(a):

Provide a detailed description of the methods used to perform the structural analysis. Identify the computer programs used for the analysis and how these programs were verified. The verification effort should include comparisons to EPRI/CE data or another benchmarked code.

RESPONSE

Catawba Units 1 & 2 The structural analysis of the piping was performed using the SUPERPIPE computer program. Static Loads are analyzed by the direct stiffness method. A stiffness matrix is derived from the geometry of the piping and its components. Gravity loads and other distributed loads are included exactly by the program. In static analysis for. thermal expansion considerations, hot and cold temperatures are specified and the program automatically determines the coefficients of expansion by interpolation of material property tables. Static analysis load cases considered in the analysis include effects for gravity, thermal, and seismic anchor movements.

The dynamic analysis consisted of a response spectrum analysis for seismic inertia loads and a force time history analysis for the valve discharge. For the response spectrum analysis,1%

damping and the grouping method for modal combination was used.

Mass point spacing is explained in Question 12B.

Direct integration force time history analysis was used for evaluation of S/RV discharge events. In the direct integration analysis, the damping matrix is given as:

[c] = o([m] + /3 [k]

in which.

[m] = Mass Matrix

[k] = Stiffness Matrix o< . g = Factors which control the amount of damping

c-

. i The SUPERPIPE program required that two frequencies (F , F,) and two corresponding damping ratios ( A , X ) be specifidd where:

3 2 F ;, F2 = Lower and upper response frequencies of the piping system.

h 9 ,h 2 = C rresponding damping ratios to frequencies F, and F2 '

In the analysis, a damping ratio of .0. at 10 H2 and 100 HZ were specified.

Computer Programs used in Piping Analysis and Pipe Support Design:

a) Program: SUPERPIPE Author: Impell Corporation (formally EDS Nuclear. Inc.)

455 North Wiget Lane Walnut Creek, California 94598

Description:

SUPERPIPE is a computer program for the structural analysis and code cocoliance evaluation of piping systems, with particular emphasis on Class 1, 2, and 3 nuclear power piping designed to meet the requirements of the ASME Boiler and Pressure Vessel Code,Section III.

Verification: The SUPERPIPE program has been bench-marked against the EDS program PISOL, NUPIPE, and 9IPESD. This program has been verified by bench-marking to an ASME sample problem, by cocparison to detailed analysis performed manually, by conparison to results achieved using similar programs, as described above, and by comparison to results achieved using the previous version of SUPERPIPE. The bench-mark problems specified in NUREG CR-1677 have been evaluated using this program and the results have been transmitted to the NRC.

The thermal-hydraulic analysis for the Catawba SRV qualification was performed using RELAP5/MCOI CYCLE 14. EPRI report NP-2479, "Application of RELAP5/MC01 for calculation of Safety and Relief Valve Discharge Piping Hydrodynamic Loads", released in December 1982, confirmed the applicability of RELAP5/MC01 for the analysis of pressurizer relief line discharge loads. A post-processor called REFCRC converted the hydrodynamic transient data into a force-tine history format for input into the SUPERPIPE conputer program.

. i Code MCAUTO STRUDL Author: McDonnel Douglas Architectural Engineering and Construction Co.

Box 516 St. Louis, MO 63166

Description:

Large scale general purpose finite element program for structural analysis.

Extent and Limitation of its application: MCAUTO STRUDL is used to perform static elastic analysis of pipe supports.

Verification: MCAUTO STRUDL has been verified by comparison of the results with either hand calculations, closed form solutions found in standard text books or solutions from other programs.

Code: GTSTRUDL Author: GTICES Systems Laboratory Department of Civil Engineering Georgia Institute of Technology Atlanta, GA 30332

Description:

Large scale general purpose finite element program for structural analysis.

Extent and Limitation of its application: GTSTRUDL is used to perform static elastic analysis of pipe supports.

Verification: GTSTRUDL has been ver!.thd by comparison of the results with either hand calculatiora closed form solutions found in standard text books or solutions from other programs.

Code: BASEPLATE Author: Jeff Swanson Design Associates International 4105 Lexington Avenue North Arden Hills, MN 55112

Description:

The program BASEPLATE is a preprocessor /postprocessor to the Stardyne Computer Code for the specific purpose of analyzing flexible baseplates.

Extent and Limitation of its application: The BASEPLATE program is used to analyze support baseplates.

s .

Verification: Control Data Corporation has verified BASEPLATE in accordance with their quality assurance program utilizing a comparison of program results to hand calculations, published analytical results, or another program which has similar capabilities.

Code: BASEPLATE II Author: Richard S. Holland Ernst. Armand, and Botti Associates, Inc.

60 Hickory Dr.

Waltham, MA 02154

Description:

The program BASEPLATE II is a preprocessor /postprocessor to the ANSYS and Stardyne Computer Code for the specific purpose of analyzing flexible baseplates.

Extent and Limitation of its application: The BASEPLATE II program is used to analyze support baseplates.

Verification: TL2 Control Data Corporation has verified BASEPLATE II in accordance with their quality assurance program utilizing a comparison of program results to hand calculations, published analytical results, or another program which has similar capabilities.

Code: ANSYS Author: Swanson Analysis Systems Inc.

PO Box 65 Houston, PA 15342

Description:

Large-scale finite-element program for structural, heat transfer, and fluid-flow analysis. ANSYS performs linear and nonlinear elastic analysis of structures subjected to static loads (pressure, temperature, concentrated forces and prescribed displacements) and dynamic excitations (transient and harmonic).

The program considers the effects of plasticity, creep, swelling and large deformations.

Transient and steady-state heat transfer analyses consider conduction, convection, and radiation effects. Coupled thermal-fluid coupled thermal-electric, and wave-motion analysis capabilities are available. Structural and heat transfer analyses can be made in one. two, or three dimensions, including axisymmetric and plane problems.

Extent and Limitations of its application: The ANSYS computer program is used to perform static elastic finite element analysis on pipe support baseplates. ANSYS was used only in conjunction with BASEPLATE II.

Verification: The ANSYS program has been verified by a comparison of test problems with analytical results published in literature and hand calculations.

Code: STARDYNE Author: STARDYNE Project Office System Development Corporation 2500 Colorado Avenue Santa Monica, CA 90406

Description:

Finite element static and dynamic structural analysis. QA STARDYNE static analysis will predict the stress and deflections resulting from pressure, temperature, concentrated forces and enforced displacements. Dynamic analysis will predict the node displacements, velocities, accelerations, element forces and stresses from transient, harmonic, random or shock excitations. STARDYNE is user oriented, containing automatic node and element generation features that reduce the effort required to generate input. Plots of the original model and deformed structural shapes help the user evaluate results.

Contour plots show surface stress for two-dimensional elements.

The program creates time histories of element forces and stresses, and of node displacements, velocities, and accelerations.

Extent and Limitations of its application: The STARDYNE computer program is used to perform static elastic finite element analysis on pipe support baseplates. STARDYNE was used only in conjunction with BASEPLATE and BASEPLATE II.

Verification: The Control Data Corporation verified the computer program by a comparison of test problems with analytical results published in literature, hand calculations, or another program which has similar capabilities.

Question 12(b):

provide a description of nethods to model supports, the pressurizer and relief tank connections, and the safety valve bonnet assemblies and PORV actuator. Identify the time step and the mass point spacing used in the analysis model for various pipe sizes. Give the rationale for the choice of computation time step and mass point spacing.

RESPONSE

Catawba 1 & 2 Types of supports modeled in the analysis include rigids, springs, and snubbers. The supports restrain only translation of the supported point. The supports were assumed to be rigid relative to the pipe. Rigid supports were active for gravity, thermal, and dynamic load cases, whereas, springs are active only for gravity and snubbers active only for dynamic load cases.

The pressurizer is modeled as a beam with nozzles connected to the centerline of the pressurizer by rigid members.

The connection to the pressurizer relief tank is modeled as a rigid lateral and torsion support, and as an axial support with a stiffness based on the stiffness of the tank. No bending support is modeled due to the relatively higher stiffness of the pipe conpared to the tank. Also, since the 12"/ relief valve discharge line passes through the tank shell, additional supports are included in the model to represent the go des inside the tank.

For the PORV sctuators, the moments of inertia were calculated based upon the fundanental frequencies. The total weight of the valve body + actuator was lumped at the centroid of the valve assembly. Safety valve bonnets are modeled as rigid members with the total weight of the valve body + bonnet lumped at the

! centroid of the total valve assen61y.

l l

I i

i For the mass point spacing, a mass point is placed at each data point on the piping model, and if necessary additional mass points are placed automatically between data points by the SUPERPIPE computer program, thus subdividing lengths of pipe between data points. If a long length of straight pipe is vibrating, each mode of vibration will contain a number of equally spaced nodes, and each length of pipe between nodes vibrates as a simple span beam. Hence, for a frequency of vibration, f,, the simple span beam length will be 1,, where 1, = ( E )0.5 (Qa)0.25 2f, w If a simple lumped mass idealization is used, and if an accurate determination of the mode shape and frequency is required for a simple span beam of this length, then the mass spacing should be no larger than S,, where S,= 0.5 1, The permissible maximum spacings are computed or specified at the time the component dimensiens are specified.

With a frequency of f = 30 cps, the following table gives the mass point spacings, 5, used in the analysis model.

Pipe Size l Schedule l "S," (Inches) 1 I l l 3/4" l 40 l 27 I I 3" l 160 l 49 I I 3" (Insulated) l 160 l 43 l l 6" l 40 l 65 I I 6" I 160 l 64 I I 12" l 40 l 88 l l 12" l xs  ! 89 A time step of .002 seconds was used in the structural analysis, which is consistent with the output from the thermal hydraulic analysis.

Question 12(c):

provide an identification of the load combinations performed in the analysis together with the allowable stress limits. Differentiate between load combinations used in the piping upstream and downstream of the valve and for the supports. Explain the mathematical methods used to perform the load combinations. If the load combinations and methods differ from those suggested in Reference 3, discuss how the load combinations used satisfy the FSAR commitment for the piping and supports. Identify the governing codes and standards used to determine adequacy of the piping upstream and downstream of the valves and the supports.

RESPONSE

Load combinations for the piping and supports are as shown in the following tables:

Table 1.0 - Load Combinations and Stress Criteria for Upstream (Class 1) piping.

Table 1.1 - Load Combinations and Stress Criteria for Downstream piping (ANSI B31.1).

Table 1.2 - Load Combinations and Stress Criteria for Supports, Restraints and Anchors.

Table 1.3 - Codes and standards governing pipe support design.

These combinations are consistent with Reference 3 except the Safety and Relief Valve Transient load case used for all Service Levels is equivalent to the SOTg case used in Reference 3 only for faulted. This is a simpler and more conservative approach.

Downstream piping is ANSI B31.1, but is qualified by load combinations and allowable stress limits of more conservative ASME (Class 2/3).

TABLE 1.0 Load Combinations and Stress Criteria for Upstream (Class 1) Piping LOAD COMBINATION CRITERIA

1. Eq. 9 (Design) Pressure < 1.S S

+ Weight ISME SeE. III

+0BE Inertia Subsection NB

+ Relief Valve Transient

2. Eq. 9 (Faulted) Pressure < 3.0 S

+ Weight ISME Se!. III

+SSE Inertia Subsection NB

+ Relief Valve Transient

3. Eq. 10 Pressure < 3.0 S

+ Weight ISME Se! III

+ Thermal Expansion Subsection NB

+0BE Inertia

+0BE Seismic Anchor Movements

+ Relief Valve Transient

4. Eq. 12 Thermal Expansion < 3.0 S ASME Se,c. III Subsection NB

5. Eq. 13 Pressure < 3.0 S

+ Weight ISME Se!. III

+0BE Inertia Subsection NB

+ Relief Valve Transient NOTES: 1) Resultant moments for Weight Loads, Occasional Loads, and Thermal Expansion Loads are combined per code equations.

2) Occasional loads are OBE Inertia. OBE Seismic Anchor Movements.

Relief Valve Transient. SSE Inertia, and SSE Seismic Anchor Movements. Occasional loads are unsigned. In Equation 9 (Design). OBE Inertia and Relief Valve Transient loads are absolutely summed. In Equation 9 (Faulted). SSE Inertia and Relief Valve Transient loads are absoultely summed. For Equation 10. OBE Inertia. OBE Seismic Anchor movements, and ,

Relief Valve Transient loads are absolutely summed. For Equation 13. OBE Inertia and Relief Valve Transient loads are absolutely summed.

I

3) Relief Valve Transient = Maximum absolute value load from PORV discharge transient and Safety Relief Valve discharge transient.

' TABLE 1.1 Load Combination and Stress Criteria for Downstream Piping (ANSI B31.1)

LOAD COMBINATION CRITERIA

1. Eq. 8 Pressure $ 1.0 S h

+ Weight ASME Sec. III Subsection NC

2. Eq. 9 (Normal) Pressure i 1.2 S h

+ Weight ASME Sec. III

+0BE Inertia Subsection NC

+0BE Seismic Anchor Movements

+ Relief Valve Transient

3. Eq. 9 (Faulted) Pressure < 2.4 S h

+ Weight ASME Sec. III

+SSE Inertia -

Subsection NC

+SSE Seismic Anchor Movements

+ Relief Valve Transient

4. Eq. 10 Thermal Expansion <S

+0BE Seismic Anchor ISME Sec. III Movements Subsection NC

5. Eq. 11 Pressure \,

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TABLE 2.&

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rf ., UNIT 1 >

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DOWNSTREAM PIPING (CLASS 2/3) s !) ; / ,af )-

p i e' MAXIMUM STRESSES .I J' t

i m' COMPONENT JOINT STRESS ALLOWABLE c' CONDITION _

< t)F.SCRIPTION NAME RESULTS STRESS FATIO Eq. 8 (Sustained),'S,112" Elbow. 86 6903 15900 '

0,434 [

)

Eq. 9 (Upr.et) i6'"x1" Branch 37AA 16252 19080 0.852 Eq. 9 (Faulted) #

6YsihBranch 37AA- 27253 38160 0.714 ,

i 8 ,

+

Eq. 10 (Thermal -( d I Exp.) , M 'i'." Reducer 107 31559 27350 1,15 4*

j [,.' ,

(See' .i ,, << ,

't < ,

Note 1) > >

l ,

, , 3 ,

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Eq. 11 (Sustained , I , 11

+ Thermal Exp.) 6*x4" Re'ducer 107 36794 4325C i, 0.851 I .(

s-(

1 n' st

'q

,, e .\

Notes: 1) Acceptabf 'since Eq. 11 is satisfied. / 'l

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UNIT 2 ;!

UPSTREAM PIPING (CLASS 1)

MAXIMUM STl'.E$SES j /  !

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' COMPONENT JOINT STRESS ALLOWABLE ..

CONDITION DESCRIPTION NAME RESULTS STRESS i - *1t1TIP

, g/ ,r y

Eq. 9 (Design) I' 22418 6" Elbow 31 24120 ' ' 0. 3.19 .

i Eq. 9 (Faulted) 6" Elbow 31 31900 48240 0.F) / ,

t 4 .s '

Eq. 10 6"x3" 98 f. 75370 48480 1.555*

Reducer / /j i (See Note ,,1) ,

Eq. 12 6"x6"x3" 96 '32401

, 48240 0 672

/ ,

TEE .

' i i Eq. 13 6"x3"' 99 47387 48480 Gf977 i Reducer itsage 6"x6"x3" 96 u = .042 1.0 0.042 ' '

TEE

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• Note 1: Acceptable since equations 12 & 13 are satisfied.

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TABLE 2.3 3

i 5 UNIT 2 i.

DCW1 STREAM PIPING ( ANSI B31.1)

MAXIMUM STRESSES CCHPCt4ENT JOINT STRESS ALLCWABLE CCt10ITICt1 DESCRIPTICN NAME MIOLTS STRESS RATIO Eq. 8 (Sustained) 6"x4" 107 10564 15900 0.664 Reducer Eq. 9 (Upset) AWTT 51 18898 19080 .990 valve

/ y 0.737 Eq. 9 (Faulted) AWTT 37 28136 38160 6

valve ,

j' cf Eq. 10 (Thermal 6"x4" 107 24625 27350 9.900

. !' ,r(, Exp.) ,

Reducer No'te s : 1) AWTT - As-Welded Tapered Tra' m utica Joint.

,\ *

/

6

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1 Page 1 of 1 TABLE 2.4 UNIT 1 S/R APPLIED LOADS AND CAPACITIES DUKE CLASS A SUPPORTS (UPSTREAM OF SAFETY RELIEF VALVE)

WORST APPLIED RATIO OF APPLIED DCP S/R NUMBER LOAD CASE LOAD (KIPS) LOAD TO CAPACITY S/R TYPE 57AA 1-R-NC-1611 FAULTED 19.8 .840 SNUBBER 111B 1-R-NC-1619 FAULTED 0.61 .161 SNUBBER 122A 1-R-NC-1620 FAULTED 0.80 .308 SNUBBER 130A 1-R-NC-1621 FAULTED 2.0 .769 SNUBBER 104A 1-R-NC-1622 FAUL7ED 3.1 .704 SNUBBER 978 1-R-NC-1623 FAULTED 2.7 .870 SNUBBER 32AA 1-R-NC-1625 FAULTED 11.3 .741 SNUBBER 96 1-R-NC-1633 FAULTED 4.0 .645 SNUBBER 99A 1-R-NC-1634 NORMAL 0.58 .877 CONSTANT SPRING 113A 1-R-NC-1635 FAULTED 4.8 .417 SNUBBER 115A 1-R-NC-1636 FAULTED 3.3 .769 SNUBBER 115A 1-R-NC-1637 FAULTED 5.8 .735 SNUBBER 117A 1-R-NC-1638 NORMAL 0.68 .917 CCNSTANT SPRING 127B 1-R-NC-1639 FAULTED 4.1 .833 SNUBBER 127A 1-R-NC-1640 NORMAL 1.2 .926 CONSTANT SPRING V9A 1-R-NC-1642 FAULTED 0.78 .781 SNUBBER V9A 1-R-NC-1643 FAULTED 0.53 .529 SNUBBER V13A 1-R-NC-1644 FAULTED 1.0 1.000 SNUBBER V13A 1-R-NC-1645 FAULTED 1.0 1.000 SNUBBER V17A 1-R-NC-1646 FAULTED 0.76 .750 SNUBBER V17A 1-R-NC-1647 FAULTED 0.71 .709 SNUBBER SA 1-R-NC-1651 FAULTED 14.3 .763 SNUBBER 31A 1-R-NC-1653 FAULTED 2G.4 .862 SNUBBER 44A 1-R-NC-1655 FAULTED 34.3 .917 SNUBBER

Page 1 of 2 TABLE 2.5 UNIT 1 S/R APPLIED LOADS AND CAPACITIES ANSI B31.1 CCOE SUPPORTS (DOWNSTREAM OF SAFETY RELIEF VALVE)

WORST APPLIED RATIO OF APPLIED DCP S/R NUMBER LOAD CASE LOAD (KIPS) LOAD TO CAPACITY S/R TYPE 78A 1-R-NC-1591 UPSET 11.6 .741 RIGID 72B 1-R-NC-1592 UPSET 11.8 .877 RIGID 76A 1-R-NC-1593 UPSET 20.9 .690 SNUBBER 71A 1-R-NC-1594 UPSET 11.3 1.000 SNUBBER 72A 1-R-NC-1595 NORMAL G.96 .617 VARIABLE SPRING 78AA 1-R-NC-1596 UPSET 11.1 .735 RIGID 78C 1-R-NC-1597 UPSET 22.1 .005 SNUBBER 80A 1-R-NC-1598 UPSET 16.9 .943 RIGID 83A 1-R-NC-1599 FAULTED 28.5 .813 RIGID 70A 1-R-NC-1600 NORMAL 2.6 .707 CONSTANT SPRING 68C 1-R-NC-1601 UPSET 11.8 .990 SNUBBER 688 1-R-NC-1602 UPSET 7.6 .794 SNUBBER 66A 1-R-NC-1603 UPSET 22.3 .962 SNUBBER-64C 1-R-NC-1604 UPSET 7.5 .758 SNUBBER 64C 1-R-NC-1605 UPSET 5.0 .893 RIGID 64B 1-R-NC-1606 UPSET 5.9 .870 RIGID 628 1-R-NC-1607 UPSET 17.5 .909 SNUBBER 62A 1-R-NC-1608 NORMAL 5.1 .833 CONSTANT SPRING 60AA 1-R-NC-1609 UPSET 7.8 .775 SNUBBER 60A 1-R-NC-1G10 UPSET 2.3 1.000 RIGID 27A/13B 1-R-NC-1613 UPSET 0.15 (LOCAL X) .179 RIGID U ET 0.05 (LOCAL Z) .179 RIGID 398B 1-R-NC-1615 FAULTED 8.1 1.000 SNUBBER 138D 1-R-NC-1616 FAULTED 3.4 1.000 SNUBBER

Page 2 of 2 TABLE 2.5 UNIT 1 S/R APPLIED LOADS AND CAPACITIES ANSI B31.1 CCOE SUPPORTS (DOWNSTREAM OF SAFETY RELIEF VALVE)

WORST APPLIED RATIO OF APPLIED DCP S/R NUMBER LOAD CASE LOAD (KIPS) LOAD TO CAPACITY S/R TYPE 17A 1-R-NC-1617 UPSET 1.3 .870 SNUBBER 14B 1-R-NC-1618 UPSET 4.6 .980 SNUBBER 21D 1-R-NC-1624 UPSET 2.4 .893 SNUBBER 118 1-R-NC-1626 FAULTED 4.7 .351 SNUBBER 11A 1-R-NC-1627 NORMAL 1.3 .026 CONSTANT SPRING 14A 1-R-NC-1628 FAULTED 2.3 .G55 SNUBBER 14A 1-R-NC-1629 FAULTED 1.4 .610 SNUBBER 37A 1-R-NC-1630 NORMAL 2.7 .962 CCNSTANT SPRING 39AA 1-R-NC-1631 FAULTED 2.8 .667 SNUBBER 518 1-R-NC-1632 NORMAL 2.3 .962 CONSTANT SPRING 13eA 1-R-NC-1641 NORMAL 3.9 .870 CONSTANT SPRING 17B 1-0-NC-1648 FAULTED 7.6 .855 SNUBBER 37XX 1 - R - M'.' - 164 9 FAULTED 12.2 .923 SNUBBER 143N 1 -R -NC - 1650 FAULTED 3.8 .885 SNUBBER 13A 1-R-NC-1652 FAULTED 8.4 .901 SNUBBER 140 1-R-NC-1654 FAULTED 6.9 .855 SNUBBER 51A 1-R-NC-1656 FAULTED 6.4 1.000 SNUBBER 137 1-R-NC-1657 FAULTED 3.9 .781 SNUBBER 382Y 1-R-NC-2208 FAULTED 4.9 .613 SNUBBER 57A 1-R-NC-2209 U? SET 16.6 1.000 SNUBBER

Page 1 of 1 TABLE 2.6 UNIT 2 S/R APPLIED LOADS AND CAPACITIES DUKE CLASS A SUPPORTS (UPSTREAM OF SAFETY RELIEF VALVE)

WDRST APPLIED RATIO OF APPLIED OCP S/R NUMBER LOAD CASE LOAD (KIPS) LOAD TO CAPACITY S/R TYPE 5A 2-R-NC-1667 FAULTED 14.3 .962 SNUBBER 31A 2-R-NC-1674 FAULTED 20.4 1.000 SNUBBER 32AA 2-R-NC-1675 FAULTED 11.3 .926 SNUBBER 64A 2-R-NC-1680 UPSET 20.8 .833 SNUBBER 57AA 2-R-NC-1681 FAULTED 16.3 .070 SNUBBER 96 2-R-NC-1687 FAULTED 4.0 .625 SNUBBER 127B 2-R-NC-1688 UPSET 2.4 505 SNUBBER 127A 2-R-NC-1689 NORMAL 1.2 .926 CONSTANT SPRING 130A 2-R-NC-1690 FAULTED 2.0 .588 SNUBBER V17A 2-R-NC-1691 FAULTED 0.35 (LOCAL X) .455 SNUBBER FAULTED 0.48 (LOCAL Z) .625 SNUBBER 97B 2-R-NC-1693 FAULTED 2.7 .840 SNUBBER 99A 2-R-NC-1694 NORMAL 0.58 .009 CONSTANT SPRING 1118 2-R-NC-1695 FAULTED 0.61 .190 SNUBBER 113A 2-R-NC-1696 FAULTED 4.8 .448 SNUBBER 117A 2-R-NC-1697 NORMAL 0.68 .909 CCNSTANT SPRING 115A 2-R-NC-1698 UPSET 2.9 (LOCAL X) .526 SNUBBER UPSET 0.47 (LOCAL 2) .535 SNUBBER 122A 2-R-NC-1699 FAULTED 1.6 .472 SNUBBER V13A 2-R-NC-1700 FAULTED 0.33 (LOCAL X) .375 SNUBBER vtJLTED 0.38 (LOCAL 2) .431 SNUBBER V9A 2-R-NC-1705 FAULTED 0.34 (LOCAL X) .452 SNUBBER FAULTED 0.40 (LOCAL 2) .535 SNUBBER 104A 2-R-NC-1707 UPSET 2.5 .325 SNUBBER

Page 1 of 2 TABLE 2.7 UNIT 2 S/R APPLIED LOADS AND CAPACITIES ANSI B31.1 CCOE SUPPORTS (DOWNSTREAM OF SAFETY RELIEF VALVE)

WORST APPLIED RATIO OF APPLIED DCP S/R NUMBER LOAD CASE LOAD (KIPS) LOAD TO CAPACITY S/R TYPE IIB 2-R-NC-1668 UPSET 2.7 .474 SNUBBER 13A 2-R-NC-1669 FAULTED 8.4 .730 SNUBBER ibA 2-R-NC-1670 FAULTED 1.4 (LOCAL X) .775 SNUBBER FAULTED 2.4 (LOCAL Z) .775 SNUBBER 148 2-R-NC-1671 UPSET 4.6 .806 SNUBBER 17A 2-R-NC-1672 UPSET 1.3 .665 SNUBBER 17B 2-R-NC-1673 UPSET 6.7 .7C7 SNUBBER 37XX 2-R-NC-1676 FAULTED 10.3 1.000 SNUBBER 37A 2-R-NC-1677 NORMAL 2.7 .901 CONSTANT SPRING 39AA 2-R-NC-1678 FAULTED 2.8 .610 SNUBEER 3988 2-R-NC-1670 UPSET 6.2 .787 SNUBBER SIA 2-R-NC-1682 FAULTED 6.0 1.000 SNUBBER 51B 2-R-NC-1683 NOFMAL 2.3 .909 CONSTANT SPRING 57A 2-R-NC-1684 UPSET 15.6 .962 SNUBBER 21D 2-R-NC-1685 UPSET 3.4 .568 SNUBBER 11A 2-R-NC-1686 NORMAL 1.3 1.000 CONSTANT SPRING 137 2-R-NC-1692 FAULTED 3.2 .917 SNUBBER 138A 2-R-NC-1701 NORMAL 3.9 .926 CONSTANT SPRING 382Y 2-R-NC-1702 FAULTED 4.4 .602 SNUBBER 138C 2-R-NC-1703 FAULTED 3.4 .775 SNUBBER 140 2-R-NC-1704 FAULTED 6.9 .536 SNUBBER 143N 2-R-NC-1706 UPSET 3.0 1.000 SNUBBER 60A 2-R-NC-1708 FAULTED 3.2 .680 RIGID l

i l

l

Page 2 of 2 TABLE 2.7 UNIT 2

$/R APPLIED LOADS AND CAPACITIES ANSI B31.1 CCOE SUPPORTS (DOWNSTREAM OF SAFETY RELIEF VALVE)

WORST APPLIED RATIO OF APPLIED DCP S/R NUMBER LOAD CASE LOAD (KIPS) LOAD TO CAPACITY S/R TYPE 60AA 2-R-NC-1709 UPSET 7.8 .714 SNUBBER 62A 2-R-NC-1710 NORMAL 5.1 .909 CONSTANT SPRING 62B 2-R-NC-1711 UPSET 18.3 .980 SNUBBER 64D 2-R-NC-1712 UPSET 5.3 .735 RIGID 64C 2-R-NC-1713 FAULTED 8.0 .629 SNUBBER 64A 2-R-NC-1714 FAULTED S.2 1.000 RIGID 66A 2-R-NC-1715 UPSET 21.6 .901 SNUBBER 688 2-R-NC-1716 FAULTED 8.0 .571 SNUBBER 68C 2-R-NC-1717 UPSET 11.8 .8 13 SNUBBER 70A 2-R-NC-1713 NORMAL 2.6 .926 CCNSTANT SPRING 78AA 2-R-NC-1719 NORMAL 2.7 .962 RIGID 78A 2-R-NC-1720 UPSET 11.9 .787 RIGID 76A 2-R-NC-1721 UPSET 20.9 .840 SNUBBER 728 2-R-NC-1722 UPSET 11.8 .752 RIGID 72A 2-R-NC-1723 NORMAL 0.96 .800 VARIABLE SPRING 71A 2-R-NC-1724 UPSET 11.3 .930 SNUBBER 78C 2-R-NC-1725 UPSET 22.1 .990 SNUBBER 80A 2-R-NC-1726 UPSET 17.3 .900 RIGID 83A 2-R-NC-1727 UPSET 23.2 .855 RIGID 27A/138 2-R-NC-IS53 UPSET 0.15 (LOCAL X) .179 RIGID UPSET 0.05 (LOCAL 2) .179 RIGID

Question 12(e):

Provide a sketch of the structural model showing lumped mass locations, pipe sizes, support locations and application points-of fluid forces.

RESPONSE

Masses are lumped at points of discontinuity and at a maximum spacing of "S " in straight pipe as explained in question 12(b).

Sketches showTng discontinuity points, pipe sizes, and support locations are found on the following drawings:

Figure 1 - Unit 1 (3 sheets)

Figure 2 - Unit 2 (3 sheets)

Application points of fluid forces are found on the following drawing:

Figure 3 - Units 1 and 2 (3 sheets) l

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/ FLUID FORCES &

APPLICATION PTS.

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Question 12(f):

Provide a copy of the structural analysis report.

RESPCNSE:

A surrmary of the results of the structural analysis has been provided in this report. Due to the large volurne of computer printouts and drawings, it is not practical to provide a copy of the structural analysis report. Details are available at the Duke Power general office.

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