Text

2 Main Steam Monitoring Procedure 7-Day Data Evaluation
	ML17194B557
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Site:	Dresden
Issue date:	05/09/1983
From:	; SARGENT & LUNDY, INC.
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	5486-23, EMD-043449, EMD-43449, NUDOCS 8305200301
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SARGENT Be LUNDY ENGINEERS, CHICAGO

'~*,

DRESDEN - 2 MAIN STEAM MONITORING PROCEDURE SEVEN-DAY DATA EVALUATION 8305200301 830513 PDR ADOCK 05000237 S

PDR CECo., 5486-23 Cale. No.: EMD-043449 May 9, 1983 Rev. 00 Page 1 of 39

r -

SARGENT Be LUNDY ENGINEERS CHICAGO Dresden-2 CECo, 5486-23 EMD-043449 May 9, 1983, Rev. 00 Page 2 of 39 1.0 2.0 3.0 4.0 5.0 6.0 7.0 Table of Contents INTRODUCTION..............*..................

5 1.1 Test Objectives.........................

5 1.2 Monitored Events.*.......*.........*....

5 TEST RESULTS.*****.*************.****.**.*.*.

2.1 Test Anomalies CONCULSIONS PIPIHG THERMAL EXPANSION EVALUATION 4.1 Hanger Readings.........................

4.2 4.3 Snubber Piston Readings.................

Measured Piping Movement SAFETY-RELIEF VALVE DISCHARGE EVALUATION.....

CONTINUOUS MONITORING EVALUATION.............

REFERENCES ******.**.*.***************.***.*..

6 7

8 10 10 11 12 14 15 16

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SARGENT 8: LUNDY ENGINEERS CHICAGO Dresden-2 CECo, 5486-23 EMD-043449 May 9, 1983, Rev. 00 Page 3 of 39 Table 1:

Table 2:

Table 3:

Table 4:

Table 5:

Table 6:

Table 7:

Table 8:

Table 9 :

Figure 1:

Figure 2:

Figure 3:

Figure 4:

Figure 5:

Figure 6:

Figure 7:

Figure 8 Figure 9:

Figure 10:

Figure 11:

Figure 12:

Figure 13:

Tables Test Matrix Thermal Displacement Test Data SRV Actuation Test Data Force Calibration Summary Hot Walkdown vs:. Hardwired LVDT *Thermal Dis-placem~nt Measurenents MS Variable (Constant and Spring) Support Thermal Movements MS Snubbers Thermal Movements Thermal Analyses Input Data SRV Actuation Snubber Loads Figures MS Line B, LVDT Measured Thermal Movements vs.

Expected HS Line C,* LVDT Measured Thermal Movements vs.

Expected MS Line D, LVDT Measured Thermal Movenents vs.

Expected MS Line B, SRV/B Actuation Maximum Responses MS Line B, SRV/E Actuation Maximum Responses MS Line c, SRV/C Actuation Maximum Responses MS Line D, SRV/D Actuation Maximum Responses MS Line c, Piping Displacement vs. Temperature MS Line B, Piping Displacement vs. Temperature Oscillograph Plot of SRV/B Actuation Oscillograph Plot of SRV/C Actuation Oscillograph Plot of SRV/D Actuation Oscillograph Plo_t of SRV/E Actuation

SARGENT 8c LUNDY ENGINEERS CHICAGO EMD-043449 Dresden-2 CECO, 5486-23 May 9, 1983, Rev. 00 Page 4 of 39 Rev.

00 Issue Summary Calculation No.:

EMD-043449, Rev. 00 File No.:

EMD-043449 Date Signatures Prepared: <I h11JJ

s. E. Azzazy 5/9/83

~'71/llt~

~

D. E. Olson Reviewed:- 9/J.eL*

II. s. Chun Approved:

Date: S"-ct-83 Date: :5-1,~3 Date: #3 Date: o/9110 Date:

s1?n::.

Date:

)1J/._t:J

- .-~

SARGENT 8c LUNDY ENGINEERS CHICAGO Dresden-2 CECo, 5486-23 EMD-043449 May 9, 1983, Rev. 00 Page 5 of 39

1.0 INTRODUCTION

The purpose of this document is to present the results of the main steam monitoring procedure.

The collected data is tabulated herein along with the associatec data evaluations and conclusions.

1.1 Test Objective The objective of the monitoring procedure was to determine the cause of the five snubber failures that were experienced on the main steam piping.

~

This procedure was performed in accordance with the requirements of the NRC Confirmatory Action Letter dated March 17, 1983 (Reference 1).

1. 2 Monitored Events This test was performed according to Dresden-2 special procedure SP 83-4-52 (Reference 2).

This procedure required that the main stea~ system be monitored from the beginning of plant startup until a stable power operation condition was reached.

The test matrix indicating the specific data points that were monitored is included as Table 1.

The monitoring was divided into three events, as described below.

a)

Piping Thermal Expansion Piping expansion was monitored from ambient conditions prior to startup, until the piping reached normal operating temperature.

Piping movement was monitored along with hanger readings, snubber piston readings, and snubber

Dresden-2 CECo, 5486-23 EMD-043449 May 9, 1983, Rev. 00 Page 6 of

39 behavior during expansion.

b)

SRV Discharge Piping and snubber response was monitored during the Operability Check of the main steam safety relief valves.

Response was monitored with the Reactor at low pressure and at rated pressure.

c)

Continuous Monitoring The response of the main steam system was

~

monitored continuously from the beginning of startup until stable power operation was attained.

The purpose of the continuous monitoring was to record the response of the systen in the event that any unexpected transients occurred in the system during power ascension.

2.0 TEST RESULTS Figures 1 through 7 depict the type of instrumentation and their locations on the main steam piping.

These

. fi<Jures also depict the maximum m~asured responses..

Note that the placement philosophy and instrumentation functions are described further in "Dresden-2 Instrumen-tation Requirements for the Main Steam Lines" (Reference*

3).

Table 2 summarizes the piping expansion movements, as measured by the LVDT's.

These movements are graphically illustrated in Figures *=a and 9.

Table 3 oontains the piping response resulting from SRV actuation at a reactor pressure of 940 psig.

The snubber loads have

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Dresden-2 CECo, 5486-23 EMD-043449 May 9, 1983, Rev. 00 Page 7 of 39 been tabulated in terms of compression and tension loads.

The individual snubber calibration curves were used to interpret the readings on the oscillograph plots.

Table 4 documents the calibrations that were used.

Copies of the 0-graph plots that show the piping SRV response are included as Figures 10 through 13.

Results of the hanger and snubber hot and cold walkdowns are given in Tables 6 and 7.

2.1 Test Anomalies 2.1.1 LVDT vs. Walkdown Measurements Table 5 includes LVDT measurements corre-sponding to an operating temperature of 442°F.

Also included in this table are the measured displacements at the snubber locations that were instrumented with a LVDT.

As can be seen from the table, the LVDT measurements appear to overpredict the visually measured snubber displacenents by 34%.

. 2.1.2 Interchange of D-4 and D-5 As a result of the cable routing in the field, the identification numbers for LVDT's D-4 and D-5 were interchanged.

LVDT D-5 now measures vertical motion and LVDT D-4 now measures horizontal motion.

These changes have been reflected in Figures 3 and 7.

This anomaly was first noticed during

Dresden-2 CECo, 5486-23 EMD-043449 May 9, 1983, Rev. 00 Page 8 of 39 heatup when the measured piping movements appeared to deviate from expected values.

The heatup was held while a visual inspection of the piping was completed to ensure that there was no binding or interferances that could cause the problem.

It was later confirmed that the cabling for these LVDT's had been interchanged.

2.1.3 Overheated Signal Conditioner

3.0 CONCLUSION

S Force transducer B-1 was temporarily out of service when the signal conditioner for the strain gauges overheated.

The conditioner was turned off and later performed properly when it cooled down.

The force transducer B-1 functioned correctly during the SRV discharge tests.

The quick-look evaluation performed onsite during imple-mentation of the test and subsequent review of the data revealed no measured response that could be considered*

as contributing to the failure of the five main steam snubbers.

The largest meas.urea snubber load was equal to 29% of the snubber operating capacity and equal to 19% of the snubber faulted load capacity.

During thermal expansion, there was no measurable drag loads on the snubbers and there was no evidence of the snubbers locking up during thermal expansion.

In addition, there was no evidence during the test that would indicate

\\l.

Dresden-2 CECo, 5486-23 E!1D-04 344 9 May 9, 1983, Rev. 00 Page 9 of 39 the failure of a snubber

~o rEstrain a dynamic load.

Based on this, the monitored snubbers are considered to be functioning correctly.

The results of the visual walkdowns of the main steam hangers and snubbers indicated that these components were within their operating range.

Some of the measured piping thermal expansion movements were outside of their expected ranges, as were some of the piping responses to SRV discharge.

Values outside of expected were evaluated and a summary of these evaluations is given below in Sections 4.0 and 5.0.

Based on these evaluations, the main steam header piping was found to be within Code allowables* for all measured events.

Code allowables refers to piping stress design values as defined in Power Piping ANSI B31.l, 1967.

Being within code allowables includes cor.lbining stresses from all loadings that are postulated to occur concurrently

Dresden-2 CECO, 5486-23 4.0 PIPING THERMAL EXPANSION EVALUATION 4.1 Hanger Readings EMD-043449 May 9, 1983, Rev. 00 Page 10 of 39

The cold settings of all the constant support and spring hangers on the main steam B, c, & D header piping and on the safety relief valve discharge lines C & D were recorded.

The hanger readings were again recorded at an operating temperature of 460°F.

The difference between the hot and cold settings were than linearly extrapolated to obtain hanger readings correspond-ing to the design condition of 550°F.

The results of these measurements and calculations are given in Table 6.

Table 6 also compares the measured therMal move-ments to their corresponding design values.

The results of the comparison indicate that, with a few exceptions, all of the hanger movements are within their design values.

Two exceptions are constant support harfgers that move in the opposite direction, however the recorded movement is small, less than 3/16", and is considered negligible.

Note that each visual inspection was performed with a tolerance on the measurement of:!:.~".

No movements w~re reported at four of the hangers.

All four hangers had small, less*than or equal to~", design movements.

The lack of recorded movement could be due to the inability of the

.t -.

Dresden-2 CECo, 5486-23 EMD-043449 May 9, 1983, Rev. 00 Page 11 of 39 inspectors to detect small hanger movements, and/or friction within the hanger.

However, assuming that the spring hanger that showed no movement was pinned, an analysis was performed to determine what effects.it would have on the piping response.

Variable spring hanger B2-3023 on SRV discharge line D was assumed to be pinned.

A thermal expansion analysis was performed with this hanger pinned and the analysis results indicated that all piping stresses were within Code allowables.

However, the analysis also in-dicated that pinning the hanger would result in a load large.enough to fail the hanger U-bolt.

Therefore, an additional analysis was performed assuming that Hanger B2-3023 had failed.

These analyses results also showed all piping stresses to be within Code allowables.

4.2 Snubber Piston Readings Visual inspections were completed to record the main steam snubbers cold piston settings and to record the hot piston settings at 460°F.

The thermal movements indicated by the difference between the hot and cold piston readings were compared to analytically predicted thermal move-ments at 460°F.

The analytical movements were calculated by interpolating analytical results at 550°F to movements at 460°F.

The results of these comparisons are shown in Table 7.

Based on the comparison, all snubber piston movements

Dresden-2 CECo, 5486-23 EUD-043449 May 9, 1983, Rev. 00 Page 12 of 39 were within the working range of the snubbers i.e., no snubber was found to be fully extracted or contracted.

All snubber thermal movements agree closely with expected design values, and all movements were in the expected direction.

The largest exceedance of the design thermal movement was

.637".

This discrepancy is not eonsidered to be significant.

Note that snubber piston Feadings were considered accurate to within+.5".

4.3 Measured Piping Movement At several locations the piping movement, as recorded by the LVDT's, were outside of the expected range of movement.

The likely contributors to these discrepant movements are:

the use of conservative analytical assumptions concerning the RPV expansion; frictional resistance of hangers and snubbers; creep and shakedown occurring in the piping during its previous years of operation; and possibly overly conservative indications oL movements from the LVDT' s measure;-

ments, as indicated in 2.1.1.

To assess the effect of these discrepant movements; thermal expansion analyses were performed to simulate the measured behavior of the main steam piping.

The analyses assumed the main steam header piping to be at 550°F and associated SRV lines were at 135°F (containment ambient temperature).

~*

Dresden-2 CECo.* 5486-23 EMD-043449 May 9, 1983, Rev. 00 Page 13 of 39 In addition, the deflected shape of the piping was simulated by forcing the measured displacements at selected locations on the piping.

The following two analyses were perfor~ed (see Table 8).

1)

Piping movements as recorded by the LVDT's, column 1 of Table 8, were used to deflect the piping.

Since the LVDT measurements are conservative, this analysis represents a worst case.

2)

Modified LVDT movements, column 4 of Table 8, were used to develop a.more realistic deflected shape.

The LVDT readings were modified by using the thermal movements that were visually recorded during the hariger inspection at 460°F.

The hanger inspection movements were extrapolated to 538°F by adding to these movements the change in the corresponding LVDT movements between 400 and 538°F; The following was used to obtain the realistic movement:

(Piping movements as visually observed at 460°F) plus (LVDT's movements at 538°F minus LVDT's movements at 400°F).

The results of these two analyses show that all thermal expansion stresses are within Code allowables.

Dresden-2 CECo, 5486-23 EMD-043449 May 9, 1983, Rev. 00 Page 14 of 39 5.0 SAFETY-RELIEF VALVE DISCHARGE EVALUATION The main steam piping re~nses for SRV actuation at 940 psig are given in Table 3.

Both the measured piping displacements and forces were small; the forces were well below the magnitude that the test program was intended to look for (e.g., the oscillograph's were calibrated for 10,000 lb. per inch).

The

measured forces are well below the snubber capacities.

The test data indicates that the snubbers were performing properly during the SRV actuation.

Table 9 compares the measured snubber loadings to expected values.

The measured tensile loads are generally bounded by the expected values.

Measured tensile loads exceed expected values for two snubbers.

The values are exceeded by a maximum of 1,100 lbs.

The measured compressive loads also exceed expected values for two snubbers, by a maximum of 3,400 lbs.

The measured compressive loads are considered to be conservative.

Two different analyses were performed to assess the effects of the measured responses on the MS piping.

Displacement Analysis.

To determine the stress magnitude and distribution in the main steam header piping the piping was analytically forced to deflect by a magnitude equal to the measured deflections.

The calculated stresses were within Code allowables.

Modified SRV Actuation Analyses.

To further evaluate the effect of the measured loads, main steam header D, the line with the highest measured loading, was analyzed

ct *

(

Dresden-2 CECo, 5486-23 EMD-043449 May 9, 1983, Rev. 00 Page 15 of 39 with tuned SRV actuation loads.

The loads were tuned to bound all measured loads.

The calculated stresses were within Code allowables.

6.0 CONTINUOUS MONITORING EVALUATION Continuous monitoring of the Dresden-2 startup began at 2:00 p.m. on April 25, 1983 and ended when a stable power level was attained at 4:00 p.m. on April 28, 1983.

During this time no unexpected events were experienced and there were no unexpected responses of the main steam piping or snubbers.

No measurable transient responses of the piping or snubbers were recorded.

Dresden-2 CECo, 5486-23

7.0 REFERENCES

EMD-043449 May 9, 1983, Rev. 00 Page 16 of 39

1)

NRC Confirmatory Action Letter, dated 3/17/83, Docket No. 50-237.

2)

Dresden Special Procedure SP 83-4-52, "Dresden-2 Main Steam Piping System Monitoring-Phase I,"

Rev. 0.

3)

"Dresden-2 Instrumentation Requirements for the Main Stearn Lines," Sargent & Lundy File No. EMD-043070, Rev. 01, dated 4/1/83.

t -

Dresden-2

.JCECo, 5486-23

TABLE 1 TEST MATRIX

- Data*

t Plant Operatinq Ip *

! oir:t Condition or ~vent

.:N~er I Plant shutdown-take data l

just prior to cor:i.;nencing rod wi thcira~*1a.l Reactor heatup wit.~

2 reactor recirculation water te~pe=ature approx-imately 2S0°F Reactor heatup with reactor recirculation 3

water tempera~ure approx-imately 400°F ---

Reactor heatup with reactor recirculation water temperature appro:~-

imately at*rated temperature.

MSRV *A* operability check 5

(DOS 250-5) with reactor at low pressure HSRV *s* operability check

.(DOS 250-5) with reactor

at low pressure MSRV *c* operability check

. 7 (DOS 250-5) with reactor at low pressure MSRV *c* ope:-ability check 8

(DOS 250-5) wi-:11 reactor I

Er-043449 May 9, 1983, Rev. 00 Page 17 of 39 Pr+/-nci;>le Pur?-Qsc of ca.ta E!ase line data for LVOT positions Effects :* heatup on MS system Effects o! heatup on MS syste_m Ef fee ts C*f heatup on MS system

~ffects of safety relie:

valve o~_:ration on the main sta::a system Ef!ects 0: safety relief valve opc=ation on -the main ste~ sys~e:n Effects et! safety relie!

valve ope::cition on the main stea::i. system Effects vf safety relief valve operation on the at low pressure

aain stea:!l-system

~EU MSRV *E" CF=r~=ility =ha:k; !:f f.:.=ts cf s.:i=e':y !'~~!.~:

~o

'.2 '83

. (COS 'SO-S). wit:~ rea-:~r.. t *.r~lve ot:..::.=ati:l:=l er. tl:c

. at low pre*ssure

* *...--. "main stez;;:i system

"' n I. I I I

I I.

I

!jresden-2 Eco, 5486-23 E-043449 May 9, 1983, Rev. 00 Page 18 of 39 TABLE 1 (cont'd)

Data Point

~.ber 10 11

~.

I 13 14 Plant Operating.....

Condition or Event MSRV *A" operability cheek (DOS 250-5) witil reae~or

'at rated pressure MSRV *3 11 operability check (DOS 250-5) with reactor at rated pressl:re

. MSRV *c 11 operability check (DOS 250-S) with reactor at rated pressure MSRV *o" operability chec}!-

c:os 250-5) with reactor at rated. pressure MSRV *£ 11 operabili*ty check (DOS 250-5) with reactor at rated pressure Princi?le PU-"'70Se of Data Effects cf safety* relief valve ope:r-.:ion on ~~e main ste~ system Effects 0£ safety relief valve operation on the 11ain stea:i system Effects of safety relief valve op~ation on the main stea:t syste?n Effects o! safety relie!

valve op~atio:'l on the main stem systec Effects of.safety reliaf valve operation on t.~e main steam system.

~

() 0 Table 2 trj 11 n ro Thermal Displacem~nt Test Data 0

(/)

p..

ro U1 ~

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PIPING DISPLACEMENTS @ RR TEMPERATURES co "'

°'

I TRANSDUCER LOCATION 250°F 356°F 400°F 442°F 538°F 531°F VJ B3 Snubber 46 0.76

1. 33

1. 66

1. 89 2.59 2.65 C4 Snubber 50.

0.76

1. 35

1. 66

1. 90 2.61 2.73 9:

cs Snubber 51

1. 20

1. 97 2.37 2.70

3.35 3.35 C6 Snubber 44 0.63 0.92

1. 07

1. 20

1. 58 C7 V/SRV 0.24 0.07 0.12

--0. 02

-0.07

-0.09 CB H/SRV 0.43 0.82

1. 04

1. 23

1. 72

1. 82 C9 V/riser 0.21

-0.05

-fJ.07

-0.13

-0.17

-0.21 03 Snubber 53 0.60

1. 04

1. 27 1.44

1. 96 2.00 04 H/SRV

-0.56

-0.90

-1. 07

-1.17

-1. 53 bs V/SRV 0.19 0.08 0.12 0.01

-0.05

'U !It DI 06 V/riser 0.21 0.08 0.13 0.04 0.07 0.02 l.Q ro I

ID 0 t-'

VJ ID t-' """

data point:

DP2 DP17 DP3

DP9 DP4 DP14

\\D """

0 CXl \\D Hl VJ Time:

16:00 20:05 21:30 01:40 09:34 11:20 VJ

ti Date:*

4/25 4/25 4/25 4/26 4/26 4/26

\\D ro <

CS and 04 displacements not available 0

for data point 14.

0

Dresden-2 e

EMD--449

""'CECo, 5486-23

1ay 9, 1983, Rev. 00 Page 20 of 39 Table 3 SRV Actuation Test Data*

Transducer Maxima Location B-actuation:

Bl 80, -50 lbs Snubber 45 B2 400, -250 lbs Snubber 46 B3 50, -0 mils Snubber 46 C-actuation Cl 1700, -800 lbs Snubber 50 C2 550, -350 lbs Snubber 51 C3 100, -100 lbs Snubber 44 C4 75, -40 mils Snubber 50 cs 20, -5 mils Snubber 51 C6 35, -20 mils Snubber 44 C7 50, -70 mils V/SRV CB 120, -110 mils H/SRV C9 30, -20 mils V/riser D-actuation:

Dl 550, -100 lbs Snubber 53 02 2000, -4300 lbs Snubber 52 03 50, -15 mils Snubber 53 04 50, -80 mils H/SRV 05 30, -20 mils V/SRV 06 60, -60 mils V/riser E-actuation:

Bl 80, -200 lbs Snubber 45 B2 1500, -3700 lbs Snubber 46 B3 40, -40 mils Snubber 46

SRV actuation conditions were:

Rx pressure = 940 psig, Rx Recirc. 'Temperature = 531°F, time = 11:00 a.m., 4/26/83.

Also, refer to the following table, FORCE CALIBRATION SUM11ARY, for the strain gauge calibrati9n calculations.

Table 4

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FORCE CALIBRATION SUUMARY ti:I 11 n ro o en TRANSDUCER SNUBBER SNUBBER O'GRAPH TRANS. MV OUTPUT*

O'GRAPH CALIBRATION**

0.

<D NAME LOCATION SERIAL #

CAL, mV/in.

T-5K C*-5K TENSION, lb/in COMP. lb/in Vl ::l

~I 00 N Bl 45 7698 1010 597

-983 8460 5140 O'I I

N w

82 46 6994 1540 790

-313 9750 24600 Cl 50 11632 1550 808

-606 9600 12790 C2 51 7402 1270 707

-785 8980 8090 C3 44 7401 1440 712

-656 10110 10980 Dl 53 11630 1150 892

-536-6450 10730 D2 52 6988 1600 886

-225 9030 35560 Tension, lb/in

= [O'graph cal., mV/inch] x [5000 lbs/T-5KmV1

'ti

!: ti:I Compression, lb/in= [O'graph cal., mV/inch] x [5000 lbs/C-5KmV]

ni ni :::

l.Q

ro N

~

f-'

w f-' ~

0

\\.0 ~

T-5K corresponds to application of 5000 lbs tension.

t-ti 00 \\.0 w

C-5K corresponds to application of 5D00 lbs compression.

w

\\.0 -

ci

<D

- O'graph calibration numbers apply to +5000 lb range only.

0 0

(.

,,Dresden-2 1CEC0, 5486-23 Transducer B3 C4 cs C6 D3 EMD--449 May 9, 1983, Rev. 00 Page 22 of 39 Table 5 Hot Walkdown vs. Hardwired LVDT Thermal Displacement Measures Snubber Thermal Displacements*

Location LVDT Walkdown 46

1. 89

1. 5 50

1. 90

1. 5 51 2.70

1. 75 44

1. 20

1. 0 53

1. 44 1.0 (On average, LVDT measurements exceeded walkdown measurements by 34%)

Ratio LVDT/Walk

1. 26

1. 27

1. 54

1. 20

1. 44

LVDT displacements from D.P. 9 Walkdown displacements equal (HOT-COLD) walkdown results

I I

I r

I I

I I I i Dresden-2 ct:co, 5486-23 SARGENT 8c LUNDY ENGINEERS CHICAGO TABLE 6 t

D-*043449 y 9, 1983, Rev. 00 Page 23 of 39 MS Variable (Cnnstant and Spring) Supoort Thermal Movements Design Thermal Measured Thermal Mov~ments (Inch)

Suooort Line Movements at Extrapolated NUr.'lber MS SRV 550°F (Inch) at 460°F at 550°F B2-3015 A

1.25 Up

.625 Up

.789 Up B2-3016 A

.so Up

.187 Up

.237 Up B2-3017 A

.25 Up

.10 Up

.126 Up 32-3018*

A

.375 ON

.187 Up

.237 Up B2-3010 B

1.25 Up

.562 Up

.710 Up B2-3011 B

.625 Up

.20 Up

.253 Up B2-3012 B

.562 Up B2-3013 B

.375 Up

.25 Up

.316 Uo B2-3014 B

.250 Dn

.125 Dn

.158 Dn B2-3001 c

1.25 Up

.562 Up

.710 Up B2-3002** c

.so Up

.0

.o 32-3003 c

.* 437 Up B2-3004 c

.375 Up

.197 Up

.250 Up 32-3005* c

.25 On I

.062 Up

.079 Up I

B2-3006 D

1.187 Up -

.562 Up

.710 Up

a2-3007 D

.~37 Up

.125 Up

.157 Up B2-3G08** D

.18~

Up

.o

.o B2-3G09** D

.375 On

.0

.o B2-3020 c

.25 Up

.125 Up I.158 Up B2:...3021 c

.187 Up

.25

~Jp

.316 Up B2-3022 D

.562 Up

.4 Up I

.505

~p B2-2<C23**

D

.312 Up

.0

. 0 I _________ ----

Pi~e ~oved in opposite direction

- Pip~ showed no ~0vement

\\

Dresden-2 cr<:co, 5486-23 SARGENT Be LUNDY

-043449 ENGINEERS CHICAGO Table 7

~

9, 1983, Rev. 00 Page 24 of 39 MS Snubbers Thermal Movements Snubber Design Thermal Movements Number at 550°F at 460°F*

41

.426

-.346 42

-1.137

.924 43

-1.158

-.941 44 0.447

.363 45

-.684

-.556 46 1.652

1. 342 47

-1~208

-.982 48

1. 027

.834 49..

.484

.393

~-

50 1.645 1.337 51 2.269

1. 844 52

-1.389

-1.129 53 1.084

.881 54 0.853

.693 55 1.170

.951

~

56

-0.942

-.765 All movements in inches.

By linear interpolation As-Found Thermal Movements at 460° F Remarks

. 250

-1. 250 exceeds by.326

-1. 0 exceeds by.059 1.0 exceeds by.637

-.5

1. 5 exceeds by.158

-1.250 exceeds by.268

.750

. 5 exceeds by.107 1.5 exceeds by.163

1. 75

-1.0 1.0 exceeds by.119 1.0 exceeds by.307 1.0 exceeds by.049

-1. 0 exceeds by.235

Oreaden-2 CECO, 506-2)

LVIYT LV!Yr No.

Location c-11 Alona: ~nubber N5'J C-5 Alon~ snubber N51 c-6 Along snubber '411 C-7 Normal(Vertical) to the pipe nl'Ar relief valve c-B In-plane normal to the pipe near relief valve C-9 Along the vertical le~ or piping ne11r C-D-3 Alona: snubber N53 D-h Alona: the pipe neAr ~11fet.y v11lve n-5 Norm111 (Vert.1<:'11) to the pipe 'It. D-h D-IJ Along I.he vertlcAI leg of pipe n~nr sprin17, h11nv.er B2-3o*i~

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Main r01nt.

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EllD-04H49 Hay 9, 198), Rev. 00 Page 25 of 39 RPmarks

Dresden-2

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46 B

45 B

46 B

50 c

51 c

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52 D

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~y 9, 1983, Rev. 00 Page 26 of 39 SRV Actuation Loads SRV Transient SRV T~(nsient Measur d Design Loads (lbs)

Loads (lbs)

At Set Pt At 940 psig At 940 psiq Remarks

+ 828

+708*

+80

-so

}

Electromatic

+860

+736*

+400

-250 B Valve Actuates

+1615

+1382*

+80

-200 }

Electromatic

+1786

+1529*

+1500 -3700 E Valve Actuates

+1560

+1361

+1700 -800

+1822

+1453

+550

-350

+1617

+1491

+100

-100.

+1353

+1283

+550

-100

+1217

+900

+200( -4300

(+):Snubber under tension (-): Snubber under compression

Linearly extrapolated values.

1...

Dresden-2 CECo, 5486-23 Figure l_

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A1Tf1cNHE~TC Project File *. COM058.0011.0007 Test Specification No. COM-58-0a3, Rev. 0 Test Plan & Procedure No. COM-58-005, Rev. 0 PRELIMINARY TEST REPORT ON DYNAMIC TESTING OF DRESDEN 2 MECHANICAL PIPE SNUBBERS Prepared for:

Commonwealth Edison Company Prepared by:

NUTECH Testing Corporation 6830 Via del Oro.

San Jose, California 95119 Prepared b~

1 ctit~~ l2 -. J9,\\,'t,(,~ f 0.-

Date:

Tony Nathe~

Test Engineer NUTECH Testing Corporation Reviewed and Approved by

~-~~

~ert Ph.D.

Date:

Executive Director NUTECH Testing Cor2~o=r~a~t~i~o_n~~~~~~~~~

rs3os200307 030513 I PDR ADOCK 05000237

. __ S _*:-'--"--c.:~---~--~~~--

l _____ -*~-*

I I

I INTRODUCTION COM058.0011.0007 Page 2 of 17 A series of dynamic tests were performed on three mechanical pipe snubbers manufactured by Pacific Scientific, Model PSA-10.

The objective of the test program was to determine whether or not snubber damage, recently observed at Dresden 2, was caused by an excessively high dynamic loading or the consequence of a non-standard installation.

The non-standard installation incurs a moment across the snubber in addition to the dynamic loading.

The tests were performed from April 18 to April 30, 1983 at NUTECH Testing Corporation using three PSA snubbers.

This preliminary test report is intended to provide a "Quick Look" summary of the key test results.

The Final Test Report will contain a

more comprehensive description of the test conditions and observations.

Although. the results provided herein are considered final, they should be used for information only since they are undergoing final Quality Assurance review.

I I

I TEST HARDWARE COM058.00ll.0007 Page 3 of 17 The three Model PSA-10 snubbers which were dynamically tested at NUTECH Testing Corporation are listed below.

These three snubbers were provided by Commonwealth Edison Company to NUTECH Testing Corporation.

Manufacturer:

Pacific Scientific Anaheim, CA 94803 Model No.:

PSA-10 Mechanical Snubber Serial No. :

13999' 13994' 14012 The following connecting hardware was used.

Forward Bracket for Model PSA-10 No. 1801597-03 Manufacturer:

Pacific Sciehtific.

Rear Bracket for' Model PSA-10 No.. 18 01558-07 Manufacturer:

Pacific Scientific A schematic of the NUTECH Testing Corporation snubber test facility is shown schematically in Figure 1.

The method of applying a moment across the snubber is shown in Figure 2.

The moment applied across the snubber is equal to 36 inches (L) times the applied force (F).

A sketch of the test apparatus to measure the snubber deflection due to an applied moment is provided in Figure 3.

I I

I TEST PROGRAM Pre-Test COM058.0011.0007 Page 4 of 17 The snubbers were pre-tested to check their operability prior to applying the large dynamic loads.

All three uni ts could be moved back and forth manually.

The breakaway force was measured for each snubber.

At the beginning of each dynamic test, the snubber was installed in the test facility (attached to hydraulic actuator) and the lockup acceleration checked.

All three units received from Commonwealth Edison Company met these initial pre-test checks (requirements).

Test Series No. 1:

Transierit Dynamic Load This single pulse load test series was deleted since it was considered redundant with Test Series No. 2.

Test Series No. 2:

Repeated Dynamic Load In this test series the snubbers were subjected to the repeated transient dynamic load (shocks) as shown in Figure 4.

A peak dynamic load of 10 kips was initially applied.

The snubber was then checked for failure (e.g., manual travel check, break-away force, dynamic loading).

The test was then repeated,

I I

I COM058.0011.0007 Page 5 of 17 increasing the peak dynamic load in increments of 5,000 up to 28,500 lbs.

Note, the entire test series was performed without a moment.

'Test Series No. 3:

Dynamic Load with a Moment In these tests the snubbers were tested with a moment applied across the snubber, which simulates the non-standard instal-lation.

The snubber was subjected to the same series of tests as described in Test Series No.

2; however, with a moment across the snubber.

Initially, the moment was set at 500 ft-lbs (6,000 in-lbs).

Later tests in the series were performed with higher moments (up to 4,30-0 ft-lbs).

I

~t I

~.

I I

I RESULTS COM058.0011.0007 Page 6 of 17 The snubber operated successfully when subjected to a peak dynamic load as defined in Test se*ries No. 2, of up to. 28,500 lbs.

The snubber maintained all of its pre-test performance capabilities (i.e.,

manual

check, breakaway

force, lockup acceleration) after this dynamic load testing.

An applied moment of 500 ft-lbs across the snubber resulted in a.050 inch relative lateral displacement across its len~th.

This snubber, with the applied moment, was tested at various levels of the 10 cycle dynamic load (Test Series No.

2) up to 29,300 lbs.

It remained fully operable throughout the test.

The snubber subsequently passed all of the post-test checks (manual, breakaway, lockup).

A snubber was finally damaged when a 3, 000 ft-lb moment was applied.

This moment resulted in a 0.2 inch lateral displace-ment across the snubber.

The peak dynamic load applied was 9,900 lbs during the 10 cycle event which damaged the snubber.

Metal filings were found below the snubber and the snubber could not be manually stroked.

A second snubber was also tested to failure by applying a maximum moment of 4, 300 ft...,. lb which yielded a.23 inch displacement~

This snubber was tested at various dynamic loads up to 18,900 lbs with 10 cycles per event.

I I

f COM058.0011.0007 Page 7 of 17 The two snubbers tested to failure were disassembled and exam-ined.

Metal shavings averaging about one-half inch in length and one-quarter inch in width were found inside the support cylinder.

Small metal filings were also found inside the support cylinder.

The telescoping cylinder was badly gouged.

A brief list of dynamic tests performed and highlights are provided in Table 1.

Typical test data from these tests are provided in Figures 5 to 8.

I

t.

~

I I

J COM058.00ll.0007 Page 8 of 17 CONCLUSIONS The PSA-10 mechanical pipe snubber sustained, without degrada~

tion of performance, several dynamic impulse load events up to at least 29,500 lbs with 10 cycles per event.

In addition, the unit sustained these dynamic events with a simultaneous 500 ft-lb moment.

On the other

hand, the PSA-10 mechanical snubber was damaged when a moment of 3,000 ft-lb was applied across the

snubber, causing a

lateral deflection of 0.2 inch.

The damage observed in the test was similar to that noted at Dresden 2.

Note, the peak dynamic load applied in conjunction with the 3,000 ft-lb moment was 9,900 lbs.

Snubber Serial Number and Test Run No.

SN 14012 Run #2-6 SN 13994 Run #3-6 SN 13994 Run #3A.l-2 SN 13999 Run #3A.2-14 TABLE 1 MECHANICAL PIPE SNUBBER (PSA-10) DYNAMIC TEST PROGRAM Applied Test Peak Dynamic Moment Series Load, lbs.

ft-lbs.

2 28,500 0

3 29,300 500

3A.l 9,900 3,000

3A.2 14,300 4,300 End Deflection in.

0 0.05 0.20 0.23 Test Results Fully operable after testing -

no damage Fully operable after testing -

no damage Snubber failed*

Damaged internally**

Snubber failed*

Damaged internally~*

Snubber could not be moved manually, breakaway force was at least 10 times normal, lockup acceleration near pre-test.

- After the test, the snubber was disassembled and inspected.

The following damage was noted:

The support cylinder had gouged the telescoping cylinder leaving behind metal shavings or filings.

0 0 :s:

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Load Cell Rear Bracket PSA-10 Snubber

~

_ Forward Bracket

/

ISA Hydraulic f.£.-.-~--..----,

~

Vibration Actuator N...

33,000 lb. rating f----.-----.r--~---------------**-----------------------'---L---+----+-

Large Wide Flange Beam FIGURE 1 SCHEMATIC OF SNUBBER TEST FACILITY p

+

9 n

0 :s:

ltj 0 PJ U1 lQ 00 CD ' c f-'0 Of-'

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JF I fJ II SNUBBER f

f IS II IF Lever Arm 33,000 lbf.

ACTUATOR Applied Moment = Fx(36 inches)

Lever Arm FIGURE 2.

SCHEMATIC OF SNUBBER TEST FACILITY WITH APPLIED MOMENT

..;1

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0 :s:

ltJ 0 Ill U1 lQ CD CD

0 1-'0 0

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Load Cell Box.Beam Di!=tl Indicator Lateral Displacement Ilydraulic Actuator L-PSA-10 Pipe Snubber at Midstroke FIGURE 3.

SCHEMATIC OF LATERAL DISPLACEMENT MEASURING TECHNIQUE r

()

0 :s:

'ti 0 Ill U1 IQ 00 CD

0 1-'0 NI-'

0.*

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TEST SERIES 12 L

LOAD T

r t TIME

-L FIGURE 4

L = 5,000 lb~, 10,000 lbs

t

= 20 to 120 milliseconds T = to be determined

= wave shape may be sinusoidal REPEATED DYNAMIC LOAD (10 CYCLES) to f ail\\lre

()

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TIME FIGURE 5 COM058.0011.0007 Page 14 of 17 l

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HYDRAULIC ACTUATOR DISPLACEMENT AND FORCE FOR RUN i2-6 WITH NO MOMENT, SNUBBER SN 14012

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Til'IE COM058.0011.0007 Page 15 of 17

2.

T Il'IE

2.

FIGURE 6 HYDRAULIC ACTUATOR DISPLACEMENT AND FORCE FOR RUN #3-6 WITH 500 FT-LB MOMENT SNUBBER SN 13994

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COM058.0011.0007 Page 16 of 17 INCHES ~(\\J\\f\\l\\fVVVV\\f'---

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20010..

FORCE

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Til'1E Til'1E FIGURE 7 HYDRAULIC ACTUATOR DISPLACEMENT AND FORCE FOR RUN i3A.l-2 WITH 3,000 FT-LB MOMENT SNUBBER SN 13994

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TIME COM058.0011.0007 Page 17 of 17 I

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I TI!'!E FIGURE 8 HYDRAULIC ACTUATOR DISPLACEMENT AND FORCE FOR RUN i3A.2-14 WITH 4,300 FT-LB MOMENT SNUBBER SN 13999 I I j

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ML17194B557

Text

1.0 INTRODUCTION

3.0 CONCLUSION

7.0 REFERENCES

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