ML18046B013

Operation Procedure 0540-001-03,Revision 2, Palisades Nuclear Station-High Energy Line Break Evaluation Phase III, Procedures for Evaluating Structural Response of Piping Targets to Pipe Rupture Loadings.

ML18046B013
Person / Time
Site:	Palisades
Issue date:	06/06/1980
From:	Abeles J, Degrossi G, Guzj D EDS NUCLEAR, INC.
To:
Shared Package
ML18046B011	List: ML18046B009 ML18046B012 ML18046B013
References
0540-001-03, 540-1-3, NUDOCS 8111020128
Download: ML18046B013 (16)

Text

EDS NUCLEAR INC.

PROJECT INSTRUCTIONS TITLE: Palisades Nuclear Station - High Energy Line Break Evaluation Phase III Procedures for Evaluating the Structural*Response of Piping Targets to Pipe Rupture Loadings

• NO.: 0540-001-03 CLIENT/ PROJECT: Consumers Power Company JOB NO.: 0540-001-821 REVISION: 0 PREPAREO: __*~.J::J.~~~~;~4~*~*~~~~1:;~~!!!!!!!**~1~~~~~--- ~/s/ro OAT:

APPROVED: 3) ~ ~. G~.c: C(~/'(o CONCURRENCE: \'A.. ~

gional Quality Assurance Manager Date REVISION RECORD Rev. Prel)ared Approved Concurrence 1 '1 /s-/vc b. ~ ... ;

• Page 1 of 16

r.1.r!\.

\,:~I*~

EDS NUCLEAR INC.

• • \lb P~iOJ ECT ! i\]STtlUCT~ONS CU ENT I PROJECT: Consumers Power Company Revision: l.

Palisades Nuclear Station - High Energy Line Break 0540-001-03 TITLE: Pha-.se III - Procedures for Evaluating Piping Targets Page 2 of 16 TABLE OF CONTENTS Page No.

I. INTRODUCTION 3 II. DESIGN BASIS 4 III. JET IMPINGEMENT INTERACTIONS (all pipes except 5 primary loops)

IV. JET IMPINGEMENT TNTERACTIONS (primary coolant loops) 8

v. PIPE WHIP INTEPACTIONS 9 A. Energy Absorption Capc?-city 9 1 B. Steady State Load Capacity 10 C. Checking Criteria 11 VI. REFERENCES 12 TABLES 13 FIGURES 15 ATIACHMENT A 16

-~~ _ . . EDS NUCLEAR INC.

"(...,PROJECT INSTR*UCTIONS CLIENT I PROJECT: Consumef S Power Company Revision: 2

• 0540-001~03 Palisades Nuclear Station - High Energy Line Break TITLE; Phase III - Procedures for Evaluating Piping Targets Pag~ 3 of 16 I. INTRODUCTION

. The purpose of this procedure is to provide a method for evaluating piping targets for jet impingement and pipe whip interactions. The allowable loads and energies are based on ANSI/ANS-58.2 {ref. l) recommendations. The formulas require a minimum amount of material property input which is readily available from the 1974 ASME Code. This code is used instead of the code of record {USAS B3l.l, 1967) because it presents both yield and ultimate stresses as a function of temperature *

.. ~!:.-* EDS NUCLEAR INC.

'"t'i"PROJECT INSTR*UCTIONS Consumers Power Company CLIENT I PROJECT: -' Revision: I.. *

. 0540-001-0 3 Palisades Nuclear Station - High Energy Line Break TITLE: Phase III - Procedures for Evaluating Piping Targets Page 4of16 II. DESIGN BASIS A. The acceptability of t..11.e jet impingement and pipe whip inter-!

. actions on non-primary loop piping targets will be based on i t..":e follo~*~in<;

• 1

l. *Based on the range of R/t ratios for the potential piping targets, the failure mode is expected to be plastic buckling (ref. 3 , 4 , 5) *

2. The maximum allowable equivalent static jet impingement load is based on the moment at 50% of the energy absorption capacity of the target pipe prior to collapse (Sect. 6.5,Ref .l)

3. For pipe whip interactions, the target pipe shall have the capability of absorbing the total kinetic energy of the whipping pipe. The kinetic energy shall not exceed 50% of

• the energy absorption capacity of the target pipe prior to collapse (Sect.6.5,Ref.l).

4. For pipe whip interactions, the.target pipe shall have the capability of supporting the steady state blowdown loads.

The maximum steady state reaction load on the tQrget shall not excee~ 8 0 % of the maximum collapse load ( Sect. 6 . 5 , Ref._ l)

5. Yield and ultimate strengths of the target piping shall be based on the 1974 ASME code minimum values at temperature.

For the dynamic events, the values may be increased by 10%

(Sect. 6

• 3. 3 , Ref. l) *.

B. The acceptability of the jet impingement interactions on primary coolant *loop targets will be based on the ASME Code (Ref. 2) Class l piping primary stress intensity limits for emergency conditions and on the consideration of potential.

shear failure. There are no primary loop pipe whip inter-actions to consider *

.. A)-.* EDS NUCLEAR INC.

'"'?'PROJECT INSTR*UCTIONS CLIENT I PROJECT: ConslJI!lers Power Company . Revision: ~

• 0540-001-:J3 Palisades Nuclear Station - High Energy Line Break TITLE: Phase I I I - Procedure?* for Evaluating Piping Targets Page s of 16 III. JET IMPINGEMENT INTERACTIONS (all pipes except primary loops) r 1

• The maximum allowable moment on a pipe shall be based on 50% of the energy absorption capacity prior to buckling (ref. l).

This is given by the following equation:

M_

-1)

= cfZ

.cay + Ca -cr ). sl u y j

• (ref. 6) 1

.c =.a for carbon steel pipes C = .7 for stainless steel pipes where:

~ = maximum allowable moment s = elastic section modulus z = pla;:;tic section modulus cry = yield strength from AS.ME code appendices (J

u = ultimate strength from ASME code appendices The maximum allowable moment includes all loads. In order to determine the allowable moment due to jet impingement only, the moment resulting from gravity plus SSE loads must be subtracted from it as follows:

where:

M. = maximum allowable jet impingement induced moment l.

~ = moment induced by gravity plus SSE loads The moment induced by gravity plus SSE loads may be determined by one of the following methods:

l. If the seismic and gravity analyses of the target piping are available:

.. A~-- ... EDS NUCLEAR INC.

-t"'PROJ ECT INST.R*UCTIONS CLIENT I PROJECT: Consumers Power Company Revision: l.

0540-001-03 Palisades Nuclear Station - High Energy Line Break TITLE: Phase III - Procedures for Evaluatin Pi in Page 6 of 16 a) = moment at the point of jet impingement load appli~ation or b) = moment based on the largest combined pressure, gravity .and SSE stresses in the piping system (i.e. the bounding stress value for all points between terminal ends).

2. If the seismic and gravi~y analyses of the piping system are not available, the moment shall be based on the

_allowable stress limit for combined pressure, gravity and SSE loading. This limit is specified by Reference 9 as being 1.1 cr for ASME class 2 and 3 piping.

y .

The yield and ultimate strengths shall be based on ASME code minimum values at temperatures. The code of record for piping analysis 'of the Palisades plant (USAS B31.l.O -

1967) is not being used *since it does not provide these material properties at elevated temperatures. The target temperature will be assumed to be the higher of the target pipe normal operating temperature and the jet impingement temperature. To account for an increase in strength during a dynamic event, the yield and ultimate

~trengths may be increased by 10% as recommended in

• Ref. 1. Table 1 presents the static material strength values for typical carbon and stainless steel pipes over a range of temperatures (from Ref. 2). Target pipe materials, schedules and temper~tures are given in the piping class sheets and summary (ref. 11 and 12). Table 2 summarizes the cross-sectional properties of target pipes.

The maximum impingement load may be determined from the allowable moment by applying standard beam formulas as given in reference 7. The actual piping support geometry, load application point and impingement ang~e may be used when lqiown. Otherwise the load can be based on a simply supported beam loaded perpendicular to its length at mid span. The maximum support span length may be assumed to equal the 20 Hz frequency length of a sim-ply supported beam based on typical support spacing for the Palisades Plant. Table 2 gives the lengths for water and steam filled pipes.

The load may be assumed to be concentrated at the center or uniformly distributed about the center along a length equal to the jet diameter. (A concentrated load will give the mar~ conservative results) *

• .&.~ *. * . . EDS NUCLEAR INC.

"(..,PROJECT INSTR*UCTIONS

• • -*-----------~~~--~---

CLIENT I PROJECT: Consumers Power Company Revision: ~

0540-001-03 Palisades Nuclear* Station - High Energy Line *Break TITLE: Phase III - Procedures*for Evaluating Piping Targets Page 7 of 16 For a concentrated load, th~ maximum allowable impingement load equals: *

• F. = 4M.l.

l.

-.r Where:

F.l. = maximum allowable impingement load R. = span length between supports For a uniformly distributed load, the maximum impingement load equals:

4M.

l.

F. =

l. c

( R.--)

2 where:

c = length of load application

= jet di~eter or R., whichever is smaller The jet impingement interacti.on can be 'evaluated by comparing the allowable load calculated above with the equivalent static jet impingement load determined from the reference 10 procedures. The projected target area shall be pased on the O.D. of the target pipe. It will be assumed that any insulation on the pipe would be blown away by the interaction.

EDS NUCLEAR INC.

CLIENT I PROJECT: Comsumers Power Company Revision: ~

0540-001-03 Palisades Nuclear Station - High Energy Line Break TITLE: Phase III - Procedures for Evaluating Piping Targets Page 8 of 16 IV. JET IMPINGEMENT INTERACTIONS (primary coolant loops)

Since the primary coolant system is a critical system whose geometry is known, a detailed stress analysis will be performed.

The EDS SUPERPIPE program (Ref. 13) will be 1.lsed to perform elastic stress analyses of ti'e hot leg, the discharge leg, and the suction leg.

On a first level basis, the analyses will consider the impinge-ment load acting as a point load noJ:Iaal to the pipe, in a di~

rection and at a location which gives the largest stresses.

If necessa.ry, the analyses may be refined on a second level basis to consider the actual direction, application point and distribution of the jet impingement force. The SUPERPIPE pro-gram shall also he used to calculate the loads and stresses due to pressure, gravity and SSE loading.

The stress evaluation will be based on the ASME Code (Ref. 2)

Class l piping analysis evaluation of primary stress intensity

(.§!quation 9., NB-3652)_ with emergency condition stress limits.

Thi:$ equation will be used to combine the jet impingement stress-es with pre~sure, gravity and ?SE stresses. The emergency con-d+/-ti.on l+/-mit will provide a higher than design stress limit which conservatively insures that structural integrity of the target

~ipes will be maintained. The equation is given below:

where: = primary stress indices for the specific piping component p = design pressure, psi Do = outside diameter of pipe, in.

t = nominal wall thickness of pipe, in.

I = moment of inertia, in4 M* = resultant moment loading due to loads caused

.l.

by weight, SSE and jet impingement

= allowable design stress intensity value The SUPERPIPE program will be used to determine the maximum combined (_equ. C.9 )_) stresses for each target.

In addition, due to the relatively short lengths of the primarv coolant pipes, an ~ddi~io~al _hand calculat;on will be performea

~,... ;.,..~,,.,...,. :a.,.,.::ii"ai- .,~;- .,~.,l'l,.,.~m~n~ ah~.;ir -F:=a., ,,.,.,...,.

.* A)._. . . EDS NUCLEAR INC.

e -t~PROJECT INSTR*UCTIONS CU ENT I PROJECT: Consumers

, Power Company . Revision: a.

.Palisades Nuclear Station - High Energy Line Br.eak 0540-001-03 TITLE: Phase III - Procedures for Evaluating Piping Targets Pag~ 9 of 16

.V. . PIPE WHIP INTERACTIONS 1

• Two design considerations are required in evaluating a pipe whip interaction (sect. 6.6.4, ref. 1)

l. The target pipe shall have the capacity of absorbing the energy of the whipping pipe.

2. The target pipe shall have the capability of supporting the steady state blowdown loads.

A~ Energy Absorption Capacity The energy absorption capacity of the target pipe shall be based on 50% of its energy absorption capacity at buckling (ref. 1)

• This is given by the fallowing equa_tion:

E0 g___~.My

= /. 2 24R J. + (C.-2C

l. e: )M~ (ref. 8) 1 where:

E = ener<1Y absorption capacity of target pipe 0

L = pipe span Iength t = pipe thickness*

R - pipe outer radius M = yield moment = Scr y y cr y = yield strength based on ASME code appendices s = elastic section modulus M* = maximum allowable moment on the target pipe (same as Mo>

e:y

Ce: e: allowable e:y = yield strain C* =~M*

A~ . . EDS NUCLEAR INC.

-"(~PROJECT INSTR*UCTIONS CLJENT I PROJECT: consum~rs Power Company Revision: a Palisades Nuclear Station - High Energy Line Br.eak 0540-001-03 TITLE: Phase III - Procedures for Evaluating Piping Targets Page10 of 16 The above equation defines the totai energy absorption capacity of the pipe. The portion of that capacity available for pipe*whip energy absorption equals the total energy capacity minus the strain energy from gravity plus SSE loads:.

where:

.. Ew = pipe whip energy absorption capacity of the target pipe

= Strain energy of the target pipe from gravity plus SSE loading.

The gravity + SSE energy can be determined from a beam flexure strain energy formula:

(ref. 7)

The moment distribution may be based on calculated values or if unavailable may, be based on the stress limits for combined pressure gravity and ~SE loading.

The maximum allowable moment, M*, shall be based on the ASME code (ref. 2). allowable.yield and ultimate strengths at the higher of the target pipe fluid temperature or the whipping pipe fluid tenrperature. The table values may be increased by 10% to account for dynamic effects. Table 1 gives the material properties for stainless and carbon steel pipes over a range of temperatures.

If the support span length is unknown it may be based on the

• 20 Hz frequency length as given in table 2.

It will be assumed that the target pipe must absorb the total kinetic energy of the whipping pipe. The interaction will be considered acceptable if the energy absorption capacity, Ew, of* the pipe is greater than the kinetic energy of the whipping pipe at impact.

B. Steady State Load Capacity The steady state load capacity of the target pipe equals the following:

F SS

= a.a x F.l. (ref. 1)

-~}a- . .. EDS NUCLEAR INC.

"{)"'PROJECT INSTR*UCTIONS CU ENT I PROJECT: Consumers Power Company Revision: ;i.

Palisades Nuclear Station - High Energy Line Break 0540-001-03 TITLE: Phase I I I - Procedures for Evaluating Piping Targets Page 11 of 16 where F. is the maximum allowable load as calculated by the methodsigiven for jet impingement loads. The material strengths will be based on the reference 2 values and will not be increased by l:0%.

• The calculation of the steady state target load will be based on a simple beam model of the broken pipe as shown in figure 1.

The target load equals:

R_

-""T

= !_d TSS where:

t = distance from hinge to line of thrust load d = distance from hinge to target Tss = steady state thrust load The interaction will be considered acceptable if the energy criterion is met and the steady state load capacity, Fss' is greater than .*the target load, R.r*

C. Checking Criteria Checking shall be in accordance with Attachment A.

' A)._ . EDS NUCLEAR INC*

."(';"PROJECT INSTR*UCTIONS CU ENT / PROJECT: Consumers Power Company Revision: ~

Palisades Nuclear Station - High Energy Line Break 0540-001-03 TITLE: Phase III - Procedures for Evaluating Piping Targets Pagel2- of 16 VI. REFERENCES

1. Draft ANSI/ANS-58.2,."Design Basis for Protection of Nuclear Power Plants Against Effects of Postulated Pipe *Rupture,"

• November 1978.

2. ASME Boiler and Pressure Vessel Code Section III Division 1 1977.

3. Gerber, T.L., 0 Plastic Deformation of Piping Due to Pipe Whip Loading, 0 ASME paper 74-NE-l, 1974.

4: Wihoist, Merwin, and Jirsa, °Critical Plastic Buckling Parameters for Pipes in Pure Bending," ASME paper 72-Pet-29, 197Z.

5. Popov, Sharifi, and Nagarajan, "Inelastic Buckling Analysis of Pipes Subject to Internal Pressure, Flexure, and Axial Loading," presented at ASME Pressure Vessel and Piping Conferenc:e, Miami Beach, Fla., 1974.

6. EDS calculation PIPE-00.l:, "Verification of Formula for P~pe Moment capacity. " .

7. Roark, R.J., "Formulas for Stress* and Strain," Fourth.

Edition, McGraw-Hill.

8. EDS calculation PIPE-002, Rev. 1 "Verification of Formula for Pipe Energy Absorption Capacity."

9. "Palisades Nuclear Plant Criteria for Reanalysis of Safety Pipe", Bechtel subjob 12447-033, Rev 2, 11/30/79.

10. EDS Project Instructions, "Palisades Nuclear Station Hj,gh Energy Line Break Evaluation Phase III - Procedures for Determining Jet Impingement Forces and Pipe Whip Energies" 5/14/80.

11. "Piping Class Sheets for Consumers_Power Company Palisades Plant," Bechtel, 5935-M-260 Rev 8.

12. "Piping Class Summary For Consumers Power Company Palisades Plant," Bechtel, 5935-M-259 Rev 10.

l3e "SUPERPIPE" piping analysis program, version 11/15/79, EDS Nuclear, Inc.

..A~_ . ~ . EDS NUCLEAR INC.

e "1...PROJECT INSTR*UCTIONS

.. Consumers Power Company CLIENT I PROJECT: .Revision: a*

0540-001-03 TITLE: Palisades Nuclear Station - High Energy Break Phase III - P*rocedures* for Evaluatin Taraets Page 13 of _16.

TABLE 1 YIELD AND ULTIMATE STRENGTHS FOR CARBON AND STAINLESS STEEL PIPES YIELD ULTIMATE MATERIAL TEMPERATURE -* STRENGTH STRENGTH OF (ksi) (ksi)

SA-106 100 35.0 60.0 Grade B 200 31.9 60.0 (Carbon Steel) 300 31.0 60.0 400 30.0 60.0 500 28.3 60.0 600 25.9 60.0 650 25.4 60.0

. ~A-312 100 30.0 75.0 Tp304 200 25.0 71.0 (Stainless Steel) 300 22.5 66.0 400 20.7 64.4 500 19.4 63.5 600 18.2 63.5 650 17.9 63.5 SA-376 100 30.0 75.0 Tp316 200 25.8 . 75.0 (Stainless 300 23.3 73.4 Steel) 400 21.4 71.8

.500 19.9 71.8 600 18.8 71.8 650 18.5 71.8

r

• TABLE 2

-i

=i r

ro 0

cm z

. A~

f

'1~

SUMMARY

OF PIPING GEOMETRIC PIWPEltTIES 20 Hz 20 Hz - :a

-t "O

-a.*

NOMINAL ELASTIC PLASTIC SPAN SPAN :n IPE SIZI! SCllEDlJl,E O.D. I. D. WALL SECTION SECTION l.ENGTll LENGTH 0c.._

(in) (in) TlllCKNl!SS (in)

MOOUl.US ( s) 3 MODULUS (z) 3 (STEAM FILLED)

(WATER FILLED) m

£1 0 (in ) (in )

(ft) (ft) I 0 c...

3/8 Tube .375 .277 .049 .0036 .0052 3.44 3.39 m 1/2

.2 Tube 40S

.500 2.375

.370 2.067

.065

.154

.0086 .

.5608

.0124

.7609 3.97 8.94 3.92 8.40

()

2 z

BOS 160 2.375 2.375 1.939 1.689

.218

• 343

• 73ll

.9790 1.0177 1.4297 8.82 8.60 8.52 8.52 -I 3

4 6

6 160 120 BOS 120 3.500 4.500 6.625 6.625 2.626 3.626 5.761 5,501

.437

.437

.432

.562 2.8761 5.1761 12.2267 14.9806 4 .1277 7.2418 16.5955 20.7183 10.53

12. ll 14.92 14.78 10.36

11. 73 14.03 14.19*

-z.2 m 0

CJ)

CJ) ~

8 lOS 8.625 8.329 .148 8,2142 10.6363 17.44 13.82.

12 20 12.750 12.250 .250 30.0978 39.0677 21.18 -17 .16

-I ~

12 140 12.750 10.500 1.125 109,9186 152.5078 20.47 19. 71 16 30 16.000 15.250 .375 70.2786 91.5703 23.68 19. 72 18 36 80 MS 18.000 36.000 16.126 33.500

.937 1.250 203. 7710 1146.1329 273.0780 1510.1042 24.76 35.32

22. 79 .

31.06 :a ~

30 42 q.

111.-

.35,500 49,500 30,000 42 *, 000 2,750 3,750 2152,7378 5737,3183 2956,4792 7866,5625 34,33 40.58 32.75 38.63 c

• ()

-I

-0 "Do:O n>

ro m ""'

01 o rn 1--' I -*

,i;.. o m

~.

a z

(/)

-. 0

..... 0

°' w

J a .........

Ji\

" ~-

-6~ _.* ~* . EDS NUCLEAR INC.

'~PROJECT INSTR*UCTIONS

• • CLIENT I PROJ~CT: consumers Power Company Palisades Nuclear Station - High Energy Line Break Revision: ~

0"540-001-0 3 TITLE: Phase III - Procedures for Evaluating Piping Targets Page lSof 16 FIGURE l MODEL FOR CALCULATING STEADY STATE PIPE WHIP TARGET LOAD Hinge T55 = Steady S.tate Thrust Load

~ = Target Load

0540-001-03 PALISl\DES SE!' /HET..B GENERAL cnr:cKINr, CRITERIA ANALYST CHECKEF

1. Are the title, purpose, and function of the item checked adequately described?

D O!

2. Is the method clearly stated?

D 0

3. Are assu.~ptions identified? Are open items flagged for subsequent verification where D 0 necessary?

4. Are design bases and references correctly

• selected and incorporated? D D

5. Are applicable codes, standards, and reg-ulatrory requirements identified? D D

6. Can the analytical steps involved be verified without recourse to the originator? D D

7. Is each sheet identifiable to its place in the calculation/problem number? D [J 1

8. Are all markings legible, and identifiable as to purpose or function? D D*

9. Is each sheet traceabie to originator, date, and job or equivalent control number? D D

10. Does the calculation clearly reference any final computer runs used? D 0 l.l.. Do final computer runs include an input listing and output? D D

12. Are computer results reasonable based on inputs and methodology? D D

13. Are final computer runs traceable back to the calculation? D

14. Are final ccr:tputer runs identifiable by a unique number or code? fJ c Are calculation results consistent with inputs, technical procedures, and design criteria? D D

..1..6.. Are revisions clearly documented?

D ANALYST DATE CHECKER DATE Rev