ML20155H156
| ML20155H156 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/07/1980 |
| From: | Campbell E, Jordan H WYLE LABORATORIES |
| To: | |
| Shared Package | |
| ML20155H119 | List: |
| References | |
| 45390-1, NUDOCS 8605130345 | |
| Download: ML20155H156 (100) | |
Text
_,
9510- AXGAC03-G0 60-9 902 I
QUALIFICATION TEST REPORT FOR A 20" TYPE 9200 BUTIERFLY VALVE WITH BETTIS ACTUATCR FCR FISHER CONTROLS COMPANY 205 SOUTH CENTER STRIET MARSHALLTOWN, IOWA 50158
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O 8605130345 860507 PDR ADOCK 05000424 E
PDR O
P 9010- AXG ACO 3-G 0'60- 9 983 j
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f Test Report i
REPORT NO.
453 " -l f
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WYLE JOB NO. 453o0 i
j CUSTOMER I
P.O.NO.
220272
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PAGE i of 1A PAGE REPORT l
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1, November 7, 1980 DATE SPECIFICATION (S)
See Paraaraph 5.:
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i 1.0 CUSTOMER O~
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P. o. B x 190, 205 South Center Street, Marshalltown, Iowa t0158 ADDRESS 20" Type 9200 Butterfly Valve with Bettis Actuator z.0 TEST SPECIMEN FJ. IP0l?lx0022 3.0 MANUFACTURER Fisher 2cntrols ccmpany 4.0
SUMMARY
Cne 20" Type 9200 autterfly Valve with a Bettis Actuator, hereinafter referred I
to as the test iten, was subjected to four (4) temperature transients and seat leakage tests, as described in Section I of this report. The test iten cor,rlied j
with all specified requirements without exception. The tests were performed l
in accordance with Feferences 5.1 and 5.2.
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M Ala. Professional Eng.
- *""' *a'm* *.*w' "w,+ a' "v "" * '"e*w. * *-= c "e, a cm STATE OF ALABAMA 1
pe, ';;. 7913 N
COUNTY OF MADISON f" PREPARED BY Pchert A.
Hall
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HUNTSVILLE. ALABAMA l
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c 9G10- AXG ACO 3- 00 60 'l
' G 'l PAGE NO.
11 TEST REPORT NO.
45390-1
5.0 REFERENCES
5.1 Fisher Purchase Order 220272 5.2 Fisher Document, Test PGF.M/FGS 14A2 6.0 CUALITY ASSURANCE All test equipment and instrmentation used in the performance of this test program sere calibrated in accordance with Wyle Laboratories' Wality Assurance Policies and Procedures Manual, which conforms to the applicable portions of ANSI N-45.2, 10 CFR 50, Appendix B, and Military Specification MIL-C-45662A.
Standards used in performing all calibrations are traceable to the National Bureau of Standards.
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WYLE LABORATORIES f4ufttsville Facility
i 9510-AXGADO3-5060-9 980 PAGE NO.
I-l TEST REPORT NO.
45390-1 SECTION I THEFMAL TRANSIENTS AND SEAT LEAKAGE TESTS 1.0 PEO"IREMEtr*S The valve assembly shall be placed in a preheated 200'F dry even for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the temperature allowed to stabilize. The valve assembly shall be criented in the oven with the inlet side up and the disc horizontal.
The blind flange on the inlet side of the valve shall be secured in such a fashion as to let the even environment be in contact with T-ring.
The cutlet side of the valve shall have a blind flange and spool piece secured to it and vented to the atmosphere.
When the stabilization is completed, the test valve asce=bly shall be removed frem the 200*F oven and placed as rapidly as possible in a second even preheated to 400'F in the same orientation. After the valve asse=bly has been placed in the oven, the oven temperature shall be brought back to 4CO*F as rapidly as possible and held for 15 minutes.
Cpen ec=pletion of the 400'T temperature spike, the blind flange of the valve assembly inlet shall be made air tight. The oven temperature
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shall be reduced to 125'F and stabilized for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Cnce temperature has been stabilized, the inlet spool piece and blind flange assembly shall be pressurized with air to 2.5 psig for 15 minutes.
The seat leakage shall be measured and recorded.
Folicwing the tests outlined above, the oven temperature shall be reduced to 100*F and stabilized for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Once the temperature has been stabilized, the inlet speci piece and blind flange assembly shall be pressurized with air to 2.5 psig for 15 minutes.
The seat leakage shall be measured and recorded.
2.0 PFCCEOCRIS The test item was placed in a temperature controlled oven and the even temperature stabilized at 200'F ; 3*F forll~ hours. The valve tempera-ture stabilized at 199.4*F.
The test item was removed from the oven and placed in another even, which was pre'-conditioned to 400*F 13'F.
The oven temperature was re-established at 400'T i 3*F and maintained for 15 minutes. The test item was pcsitioned such that the inlet side was up, the disc hori: ental and the T-ring seal exposed to the oven environment. The test item temperature at the end of the 15-minute test was 218'F.
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HuntsviHe Feedity
9510- AXG ACO3-50 60- 9 907 PAGE NO. I-3 TEST REPORT NO. 45390-1 APPE; DIX I CIRCUIAR CHARTS
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-9G10- AXGAC03-5068-9 995 PAGE NO. I_11 TEST REPORT NO. 45390-1 APPE!;0 X :::
OATA 5HIET i
J WYLE LABORATORIES Muntsville F4Cihty i
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~ 9510- AXUACO3-50 68-9 997 PAGE NO. I-13 TEST REPORT NO. 45390-1 APPC; DIX IV
!!;53L7.C;TATIC I I;UIPPI!C SHEET
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9510-AX5AC03-5068-9 999 PAGE NO. I-15 TEST REPORT NO. 45390-1
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APPENO!X V FISHER OOCL' MENT TEST PGTO!/FG3 14A2
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- 9010- AXGAC03-G060- 9 501 Rev. A i
Attachment A-5 to Vogtle Qualification Report, FQP-11A Isomedix Radiation Exposure Certification Letter, Feb. 3, 1981
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9510- AXGACO3- 0060- 9 G02 A
na a m m oix February 3, 1981 Mr. Steve Hanzlik Fisher Controls Company P.O. Box 190 Marshalltown, Iowa 50158
Dear Mr. Hanzlik:
This will summarize parameters pertinent to the irradiation of one (1) 20" butterfly valve and actuator and two (2) each of 20" spools and blind flanges, as per your Purchase Order
- 220409.
This is Wyle Job #45088.
The unit was exposed for a total of 189 hours0.00219 days <br />0.0525 hours <br />3.125e-4 weeks <br />7.19145e-5 months <br /> at~a dose rate of 0.49 megarads and received a dose of 90 megarads.
It was
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then removed from the irradiator, tested by Fisher Controls personnel, and placed back into the radiation field for 206 hours0.00238 days <br />0.0572 hours <br />3.406085e-4 weeks <br />7.8383e-5 months <br /> at a dose rate of 0.49 megarads receiving an additional 100 megarads.
This was the same unit previously exposed to 11 megarads (see July 22, 1980 certification to E. Campbell, Wyle Labs).
Hence the total dose from all exposures was 201 megarads.
Dosimetry was performed using Harwell Red 4034 Perspex desi-
=eters, utilizing a Bausch and Lamb Model 710 spectrophoto-meter as the readout instrument.
This system is calibrated directly with NES, with the last calibration being Nove=ber 11, 1980.
A copy of the dosimetry correlation report is available upon request.
Irradiation was conducted in air at ambient te=perature and pressure.
Radiant heat from the source heated the samples somewhat, but the temperature did not exceed 100 degrees F, as indicated by previous measurements on an oil solution in the same relative position.
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loomedix Inc.
- 25 Eastmans Acac. marscDaay. New Jersey 07C54. (200 887 2666 l
9G10-AXGACO3-5068 el 503 Fisher Controls Company February 3, 1981 Irradiation was initiated on December 12, 1980 and was completed on December 23, 1980.
Very truly yours, ISOMEDIX, INC.
/
David P. Constantine Production Manager DC:ns cc:
Mr. G. Diet::
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loomedix tric.
- 25 Eastmans Acac. marsiepany. New Jersey 07054. e23H 887-2666 I
e 9510- AXG AC0 3-50 60- 9 G09 Rev.
A k
Attachment A-6 to Vogtle Qualification Report, FQP-11A NA-30 Continental Mechanical Aging Test Report No.92-395 f,
9 M38J6
9G10- AXGACO3-G060- 9 500 m.
NA-30 iA fl5H23=
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M-d 6" Type 9200 Butterfly Valve ary g#~ ' ' ' #3 '7
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Cvele Test Report No.92-395 ir MA35HALLTCWN. ICWA PAGE
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I THE TABI.E EEI.CW SECWS THE RE7ISION I.I7EL OF EACH PAGE OF THIS CCCCE'iT.
A REVISION OF 2IS PAGE '4II.L BE MADE WEEN A.'E PAGE OF THIS CCCZENT IS
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REVISD.
WHEN REFERRING TO SIS DCCCE'iT, SPECITT SE REVISION I. EVE'. OF THIS PAGE.
PACE RIV!S!CN PAGE RIVIS!ON PAGE Rrl!S!CN NI.*M2ER LT,~:.*.
NLM ER LT/IL NLMER
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9510-AXGACO3-G060 #1 UO6 naren si, Ayeo CONTINC: CAL DI*.TS103 Ctrl WilsLn Page 1 of 2 Ek 30, hE.$3 I
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i TEST REPORT No.92-395
SUBJECT:
CYCi.E TEST ON 6" TYPE 9200 VALVE PUTPOSE:
To deter =ine cycle life of seat, bushings, shaf; packing, etc. on Type 9200 adjustable tee ring valve.
EQUIPMENT:
6" 150# Type 9200 adjustable tee ring valve with EPT seat, graphite bronze bushings, and preforned ribbon grafoil packing 480-30 POP actuator 164A Switching valve Cycle box Torque transducer BLH Recorder PROCEDURE:
See Figure I for counting and piping used.
The valve was cycled every 20 seconds, opening against 150 psig pressure differential on each cycle. Zero pressure dif,ferential was maintained in the open position.
The packing was tightened only enough to obtain a seal at 150 psig for the first 10,000 cycles after which the packing nuts were tight-
{
ened to approxi=ately 110 inch-pounds.
}
The seat was adjusted to caintain bubble tight shut-off at 150 psig pressure differential.
RESULTS:
Seat -
The first T-ring installed lasted 16,000 cycles, requiring adjustment every one to three thousand cycles. The second T-ring installed lasted 25,000 cycles, requiring adjust =ent every cne to six thousand cycles.
Packing The packing required adjustnent every one to two thousand cycles for the first 10,000 cycles and every two to five thousand cycles for the re=ainder of the test.
Total c:=pression of the packing was approxi=ately 35*.
The packing was in good condition after 50,000 cycles.
Bushing The bushing showed no appreciable wear after 50,000 cycles. The projected bearing stress was 5,450 psi.
Shaft The shaft showed no appreciable wear after 50,000 cycles.
The shaft stress exceeded code allovable str'ess by 25~.
. Torque Calculated torque was 820 inch-pounds.
As the*first T-ring vore the torque increased fres 630 inch-pounds initial torquo to 1,170 inch-pounds.
The second T-ring had an initial torque of 495 inch-pounds and a maxi =un torque of 810 inch-pounds.
l I
c 9G10-AXGACO3-G048-4 G07 FISEER CONTECLS COMP.UY tt2rch 31, 1976 CONTINENTAL DIVISION Tect R':psrt #92-3C
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, Rev. A k
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ABSTRACT A 6" Type 9200 adjustable tee ring valve with EPT seat, graphite bronze bushings and prefor=ed ribbon grafoil packing was cycle tested for 50,000 cycles to deter =ine the cycle life of the various components.
Based on the test results, the mini =um life of the various components should be as follows:
Metallic parts - greater than 50,000 cycles Grafo11 packing - greater than 50,000 cycles E.P.T. T-ring - greater than 12,000 cycles The packing and seat should be checked for leakage and adjusted every one thousand cycles.
.J WRITTEN BY:
["
e CARL D. WILSON:kac APPROVED BY y MAM k Job No. CD76-5 Dis t.
EDL-5 4
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9510- AXGAC03-5060,,f_t,,,,,, ],0 5(
CONTINENTAL DIVISION pg 4 g Tcct Rspset #92-39 Carl Wilson Page 2 of 2
- A._30_, Pt;a __3._, Ra A
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1 CONCLUSIONS:
Based en the resluts of this test, the mini =um life of the various ec=ponents should be as follows:
Metallic parts - greater than 50,000 cycles Grafoil packing - greater than 50,000 cycles E.P.T. T-ring - greater than 12,000 cycles The packing and seat should be checked for leakage and adjusted as necessary every one thousand cycles.
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A Attachment A-7 to Vogtle Qualification Report TQP-11A Fisher Lab Proble's 1685-3, Report 11
" Determination of Activation Energies for Nuclear Service Elastomeric Materials" 4
Dated August 31, 1981
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II REPORT I
PAGE _
CONFIDENTIAL DATE 8-31-81 sino?.EUIy*eI.se LABORATORY REPORT l
To I.ABORATORY REPORT
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DETERMINATION OF ACTIVATION ENERGIES FOR Date DO NOT REPRODUCE NUCI. EAR SERVICE ELASTOMERIC MATERIALS ABSTRACT Activation energy, a parameter defining the time / temperature interrelation-ship via the Arrhenius rate equation, was determined for nine elastomeric materials presently used in Fisher nuclear service valves and accessories.
Major material types tested were ethylene propylene rubber, nitrile rubber, neoprene and Viton.
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9G10- AXG ACO 3-G0 60- 1 S i di FISHER CONTROLS COMPANY MARSHALLTOWN. IOWA k
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1685-3 REPORT PAGE 8-31-81 DATE LABORATORY REPORT l
INTRODUCTION Of the many predictive models for long-ters thermal aging of organic material, the most generally accepted 1, 2, 3, ** is the Arrhenius reaction rate equation, 4
$ = Ae dt The terms of this equation are defined as:
h=therateofreductioninsomepropertywithtime A = a constant k = the Boltzmann constant = 8.6168 x 10~5 eV/*K T = absolute temperature, in *K
$ = the Activation Energy of the aging reaction, in eV In order to establish confidence in our accelerated aging techniques for quali-fication of nuclear service valves actuators, and other appurtenances, a study was made to determine the actual activation energies for nine materials using as specimens actual parts wherever possible. Up to this time, we have used factors for general organic materials which have been considered conservative.
The test plan was carried out in much the same manner as suggested in the documenti, attached to the letter requesting this study.
If
- Superscript numbers refer to items listed in Reference Section.
M40A2
9510-AXUACO3-G068-9 G1D FISHER CONTROLS COMPANY MARSHALLTOWN IOWA II REPORT 3
PAGE 8'31~81 DATE LABORATORY REPORT TEST PROCEDURE Materials Tested A summary of the materials tested is given in Table 1.
In general, the materials can be divided into 4 material groups:
A. Ethylene propylene rubber (EPDM) products B. Nitrile rubber (NBR) products C. Neoprene (CR) gisket material D. Viton or fluorelastomer products.
These materials are representative of the major elastomeric components used in Fisher's nuclear service butterfly talves, actuators and regulators.
l
/I Specimen Preparation l
Items 1 & 2 Extruded T-ring stock was obtained from the supplier in 50 foot lengths (for both cross-sections) and cut into 8" lengths.
Items 3. A & 5 0-ring specimens were ordered from existing stock and were aged and tested as whole 0-rings.
Item 6 l
Size 60 molded diaphragms were ordered from stock and test specimens cut l
from the flat sections of these diaphragms.
Item 7, 8 & 9 l
Sheet stock was obtained from our local supplier. This is the same stock i
that is used to cut th nrious diaphragms and gaskets cited in Table I.
I Specimens for Muller' hri t Test were cut out of the diaphragm sheet stock and tensile bar " ppt,cch were die cut from the gasket stock.
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9510-AXDACO3-5068 e.
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1685-3 11 REPORT 4
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PAGE l
DATE 8-31-81 LABORATORY REPORT Oven Asing Specimens were aged in circulating air ovens in accordance with ASTM D573-67, " Standard Test Method for Rubber Deterioration in an Air Oven".
I No attempt was made to control or to add humidity to the oven air. For i
the record, a calculation was made to approximate the relative humidity at the aging temperature.
If room temperature air at 100% relative humi-dity were heated to 200*F (the lowest aging temperature), the relative l
l humidity would be 0.7%.
It is, therefore, safe to state that at all aging l
l conditions, the relative humidity was less than 1%.
l The aging temperatures were selected, based on past experience, literature sources, etc., to produce the desired amount of property degradation in a minimum of one day to a maximum of 30 days.
In general, this amounted to 3 temperatures for each sample spaced 25'F apart. Using the recommended ASTM D1349 temperatures with spacing of 25'C would have spread the test f
times out considerably. An attempt was made to obtain 4 different exposure.
times at each temperature. For most materials this meant a total of 13 data sets (1 control + 3 temperatures x 4 times) with four replicates in each set.
Physical Testing All Items Hardness data was obtained on all specimens. Tests were run according to ASTM D2240 using Durometer Type "A" where possible.
In some instances where "A" readings were extremely high, Type "B" readings were obtained and converted to "A" reading using a standard conversion chart.
Items 1 & 2 L
Tensile tests were run using wedge action grips and the following test l
conditions.
Item 1 Item 2 Test Machine Instron Tinius-Olsen Test Speed 20"/ minute 3"/ minute Initial grip separations 1"
2" Maximum extension 17" 6"
M40A4
9510- AXG ACO3-G0 60 '.
G17 FISHER CONTROLS COMPANY MARSHALLTOWN, IOWA
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PROB.
1685-3 11 REPORT 5
PAGE 8-31-81 DATE LABORATORY REPORT i
Items 3, 4 & S Tensile tests for the 0-ring specimens were performed in accordance with j
ASTM D1414-78 " Testing Rubber 0-Rings" using Scott Tester and standard 0-ring test fixture.
Items 6, 7 & 8 The diaphragm materials were tested for burst strength as described in i
ASTM D751-73 " Testing Coated Fabrics" (Section 15.3) using Mullen Tester.
l 1
Item 9 The neoprene gasket material was tested for tensile properties using ASTM D412-75 " Standard Test Methods for Rubber Properties in Tension". Scott l
Tester was used with standard can action grips.
l
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Treatment of Data Data for each set was averaged and generally each property was plotted versus log time, resulting in a curve for each temperature. Then, at a certain degree of physical degradation (usually a value close to the mid-range of the data was picked) the times to reach the stated degradation was obtained. The activation energy was calculated using regression analy-l sis to obtain the best fit to the expression:
Int =A+f(f)
The resulting slope was $/K, and the activation energy $ was obtained by multipying the slope by the Boltzmann constant, K = 8.6168 x 10~5 eV/*K.
The same results could also be obtained graphically by plotting the data on log time vs reciprocal of absolute temperature and finding the resulting slope.
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M40A5
e 9G10-AXGACO3-5060 e G1B FISHER CONTROLS COMPANY MARSH ALLTOWN, IOWA 1685-3
(
PROB.
11 REPORT 6
PAGE 8-31-81 DATE LABORATORY REPORT DISCUSSION OF RESULTS The test results are summarized in Table II. Here the calculated Activation Energies are given for all the materials tested. Also listed are the tempera-ture range of the oven aging and the properties tested to determine the activa-tion energies. Only valid results are included in this table.
In some cases, such as Item 7, a nitrile / nylon diaphragm material, there was not a significant change in burst strength to use for a valid determination.
Due to the nature of the tests and the inherent variability of elastomeric material there was considerable data scatter. However, when several data points are plotted for each aging temperature, the effect of the scatter is considerably reduced.
In most cases, at least two properties were used to determine the activation energy, and in these cases the agreement was reasonably good.
(
In the Appendix, the average value and the standard deviation is listed for all the aging temperature / time conditions for all nine materials tested. Also given are plots of each property versus log time, and Arrhenius plots of log time vs reciprocal absolute temperature for each material. These latter plots are presented to establish a visual degree of the conformance of the data to the Arrhenius relationship. The actual activation energies were calculated using linear regression curve fitting to the same Arrhenius equation which is more accurate than the graphical technique.
The object of this study was to establish a minimum (most ccuservative) activa-tion energy for Fisher valves and components for use in qualification testing.
Due to impracticality of aging elastomeric parts to their end of life condition at normal use temperatures, an accelerated aging step is included in almost every qualification test. The aging conditions are established using the Arrhenius rate equation and require knowledge of the actual activation energy or if more than one elastomer is involved, the lowest activation energy value.
In Table III, the average and minimum activation energy values are listed for the four major types of materials tested. For valves and components contain-ing either EPDM or nitrile rubbers it is apparent that an activation energy of
$ = 0.79eV would be conservative. There is a high probability that the actual activation energy is higher.
To further establish the validity of the test results, activation energy values from the literature are listed in Table IV along with results from this study.
With the possible exception of the Viton 0-ring material which was quite high
(
in this study, all tested materials agree quite well with literature values.
Even if the literature values are used for Viton, the.79eV minimum is still very conservative.
M40A6
9G10- AXGAC03-3060 et U19 FISI-IER CONTROLS COMPANY MARSHALLTOWN, IOWA 1685-3 PROB.
II REPORT 7
PAGE 8-31-81 DATE LABORATORY REPORT CONCI.USIONS 1.
The Arrhenius rate equation is a valid method for predicting time / temperature effects in elastomeric materials.
2.
For materials used in Fisher valves and accessories, the use of an activa-tion energy of 0.79 eV to establish qualification aging parameters would be conservative.
(The lower the activation energy, the longer the simulated aging time at any given aging temperature.)
3.
Exposing specimens in a circulating air oven appears to be a valid technique for accelerating the elastomeric aging process.
RECOMMENDATIONS
- r 3s 1.
As the materials chosen for this study were the major elastomeric components used in Fisher nuclear service valves and accessories, the minimum activa-tion energy found (0 = 0.79eV) should be used to establish aging parameters via Arrhenius equation for future qualification testing.
I W. H. Haslett Evaluation & Analysis B
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9G10- AXGAC03-G068-4 G20 FISHER CONTROLS COMPANY MARSHALLTOWN, IOWA k
PROB.
1685-3 REPORT 11 PAGE 8
DATE 8-31-81 LABORATORY REPORT REFERENCES 1.
Educational document by Floyd D. Jury, "Using the Activation Energy Concept for Accelerated Aging of Elastomeric Materials". August 25, 1980 2.
M. L. Blaketon, et al, "The Testing of Elastomers for Channel Seal Plugs in a Steam Generating Heavy Water Nuclear Reactors", 8th International Conference on Fluid Sealing, September 11-13, 1978.
3.
T. C. P. Lee, et al, " Thermal Stability of Elastomeric Networks at High Temperatures", Journal of Applied Polymer Science, Vol.10, pp 1831-1836, (1966) 4.
R. R. Dixon, " Constructing an Arrhenius Plot with Only One Data Point",
SPE - Annual Technical Conference, May 1981g 5.
H. A. Pfisterer, et al, " Assessing the Performance of 011 Resistant Vulcanizates at High Temperatures, J. Elastomers & Plastics, Vol. 7, No. 4, pp 427-55 (October '75).
6.
Dupont literature 7.
J. Mandel, et al, " Measurement of the Aging of Rubber Vulcanizates",
Rubber Chemistry & Technology - National Bureau of Standards, Nov 8-13, 1959 - International Rubber Conference, Washington, D.C.
8.
E. A. Salazar, et al, " Physical and Chemical Stress Relaxation of a Fluoro-elastomer", J. of Applied Polymer Science, Vol. 21, pp 1597-1605 (1977).
9.
K. T. Gillen "A Method for Combined Environmental Accelerated Aging",
Sandia Laboratories Report SAND-78-0501C.
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r-Table.I SUttlARY OF HATERtAI.S TESTED t CONDITIONS, AND TESTS RUN D'
X L1 Material
.b Test Max.
Item Reference Specimen
. Tests Temps.'
Test c
'f No.
Test Material No.
Part No.
Description Run
(*F)
Times (Days)
L1 1
Small cross-section 06AC K1241605553-Tensile 250 30.
(1"xl") EPDM T-rings (UIt.Elong) 275 14 to -
2 i
used in Type 9280 Extruded stock Hardness 300 7
8" length 2
1.arge cross-section 06BC KI106405553 8" length of Tensile 250 30 (7/8"xl") EPDH T-extruded cross-(Ill t. Elong) 275 14
{
rings used in Type section liardness 300 7
r.
9280 3
Nitrile rubber 0-050F 1R752806562 0-ring Tensile 200 30 21 "x2'4"x t /8" (Ult.Elong) 225 30 rings, as used in (DS-52-4) 4 Types 667 & 470 liardness 250 14 275 7
4 Viton 0-rings, as 065E IN332506382 0-ring Tensile 475 30 used in Types 667NS, (DS-52-5) 1-7/8"x2-1/8"xt/8" (Ult.Elong) 500 21 470 and 95 liardness
$25 7
250
- 10 5
EPDtl 0-rings, as 06511 10A3329X012 0-ring Tensile 215 14 used in Type 9280 (OS-52-7) 2-3/16"x2-3/8"x3/32" (Ult.Elong) 300 7
l'a rdness 325 4
6 Nitrile / Nylon dia-0220 2E859702202 pieces cut from Mullen Burst 225 30 phrauns, as used in (FHSl7E44) molded diaphragm Hardness 250 14 NS actuators (Size 60) 275 7
7 Nitrile / Nylon dia-0205 18798102052* pieces cut from Mullen Burst 225 30 phragms, as. used in (IMS 17E 39) 17E39 stock-Ilardness 250 14 67FR regulators 275 7
ann 7
8 Viton/ Dacron dia-0233 IV107802332* pieces cut from Mullen Burst 425 30 phragms, as used in (IMS17E53)
.17E53 stock Hard ness 450 14-67FR regulators 475 7
9 Neoprene gaskets, 0301 1C128003012* tensile bars cut Tensile
'225 30 as used in 67FR (Itts l 7Cl) from 17Cl stock (Ult.Elong)
-250 14 regulator liardness 275 7
2 Typical finished part number Problem 1685-3 s
9010- AXG AC03-D068 el G22 Problem 1685-3 Report 11
(
Table II - Summary of Test Results ACTIVATION ENERGY STUDY Temperature Range Activation Energy )
Property eV (Kcal./gmole Tested Material Descriotion
(*F) 1.
EPDM Extruded T-rings 250 - 300 1.07 (24.8)
Elongation 1/2" x 1/2" section 1.04 (23.9)
Tensile Strength 0.95 (22.0)
Hardness 2.
EPDM Extruded T-rings 250 - 300
.80 (18.5)
Elongation 7/8" x 1" section
.81 (18.6)
Tensile Strength
.84 (19.4)
Stiffness
.92 (21.1)
Hardness 5.
EPDM 0-rings 250 - 325 1.38 (31.9)
Elongation 2 3/16" x 2 3/8" x 3/32" 1.22 (28.1)
Hardness 3.
Nitrile Rubber 0-rings 200 - 275 0.88 (20.3)
Elongation 21/8" x 21/2" x 1/8" 6.
Nitrile / Nylon Diaphragm Material 225 - 275 0.80 (18.3)
Mullen Burst Str.
(FMS17E44) 0.79 (18.2)
Hardness 7.
Nitrile / Nylon Diaphragm Material 225 - 300 0.94 (21.8)
Hardness (FMS 17E39)
Could not determine Mullen Burst Str.
9.
Neoprene Gasket Material 225 - 275 1.00 (23.0)
Elongation (FMS-17Gl) 1.02 (23.4)
Hardness 4.
Viton 0-rings 1 7/8" x 2 1/8" x 1/8" 475 - 525 2.06 (47.5)
Elongation 1.81 (41.7)
Hardness 8.
Viton/ Dacron Diaphragm Material 425 - 475 1.35 (31.1 )
Mullen Burst Str.
(FMS 17E53) 1.35 (31.2)
Hardness
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Ws10- AXG AC0 3-5 0 68-9 523 Problem 1685-3 Report 11
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Table III Activation Energies For Material Types Material Average Value Minimum Value A.
EPDM 1.00 eV 0.80 eV B.
Nitrile Rubber 0.85 0.79 C.
Neoprene 1.01 1.00 0.
Viton (1) Viton alone 1.94 1.81 (2) Viton/ Dacron 1.35 1.35 (Dacron probably controlling)
ALL TESTS 1.11 0.79 I
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Table IV Summary of Literature Data Activation Energy Property Reference Material Type e, (eV)
Tested Number EPDM 0.93 Elongation 4
0.93 Elongation 4
1.05 F
Elongation 5
Hardness Modulus LTensile Strength 0.83 - 1.32 Tensile Strength 6
0.95 Hardness 2
Compression Set Volume Change
.l.02 f
Elongation This Study LensileStrength T
Hardness
(
0.84 Hardness & Modulus This Study 1.30 Elongation, Hardness This Study Nitrile Rubber 1.30 Elongation 4
1.31 Elongation 4
0.80 - 0.96 Elongation 7
0.96 - 0.98 Elongation 5
0.88 Elongation This Study 0.795 Burst Str., Hardness This Study 0.94 Hardness This Study Neoprene 1.16 Elongation 4
1.27 Elongation 4
0.84 Elongation 7
0.91 Elongation 8
1.01 Elongation, Hardness This Study Viton (Fluroelastomer) 1.05 Seal 4
1.55 Stress Relaxation 8 6
1.34 1.94 Elongation, Hardness This Study Dacron (Polyester) 1.27 Te'nsile Strength 4
1.35 Burst Str., Hardness This Study r
/pkg l
8-31-81
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Problem 1685-3 Report 11 k
APPENDIX Table of Contents Material Page Number Figure Numbers 1.
EPDM T-Ring (1/2" x 1/2" section)
A-1 A-1, 2
(-
2.
EPDM T-Ring (7/8" x 1" section)
A-2 A-3, 4 l-3.
Nitrile Rubber 0-Ring A-3 A-5, 6 4.
Viton 0-Ring A-4 A-7, 8 5.
EPDM 0-Ring A-5 A-9, 10 6.
Nitrile / Nylon Diaphragm (FMS 17E44)
A-6 A-11, 12 l
7.
Nitrile /NylonDiaphragm(FMS17k39)
A-7 A-13, 14 8.
Viton/ Dacron Diaphragm (FMS17E53)
A-8 A-15, 16 i
9.
Neoprene Gasket Material (FMS17GI)
A-9 A-17, 18 l
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M38K1
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' 9G10- AXD ACO3-50 68-9 GG3 Arrhenius Rate Equation Calculations k
The Arrhenius rate equation as referened in IEEE 382 can be expressed as follows:
f(
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f
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e = service life g
t - test duration 2
T - service temperature 3
T test temperature 2
$ = activation energy K = Boltzman's constant = 0.8617 x 10 4 eV/K Values determined by the aging segment of the Wyle Test Report No. 45088-1, Fisher Lab Problem 1685-3, Report 11, and Bechtel Specification K5AC03, Appendix EA, result in the following numbers:
t = 28.5 days 2
T = 126 'F = 325 K 7
T = 227.8 'F = 382 K 2
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M38K2
9510- AXGACO3-G060- 9 G59 ARRHENIUS ACCELERATED-AGING RULE TEWERATURE CALCULATION of MAXIMUM-ALLOWABLE NORMAL-SERVICE TEWERATURE to ASSURE FOUR-YEAR LIFE OF NUCLEAR-SERVICE EQUIPMENT ELASTOMERIC MATERIALS (Limited to ethylene propylene T-rings and graphoil packing)
This calculation is based on an accelerated-aging high-temperature test con &cted by Fisher Controls Company. The test temperature was held constant at 227.8'F for the complete 28.5-day test. The four-year life esiculation, below, utilizes the activation energy constant for ethylene propylene (0.79 eV) which is the most limiting of the regular nuclear-service butterfly-valve material s.
The unknown-time fom of Arrhenius accelerated-aging equation is given below:
m e
1 1
K T1 T2 t1 = (t2)e
(
where:
$ (activation energy constant) = 0.79 eV K (Boltzman's constant) = 0.8617 x 10-4 ti (normal service-tenperature life) = 4 years = 1461 days t2 (test & ration) = 28.5 days T1 (maximum allowable service temperature) = unknown T2 (test temperature) = 227.8'F Rearranging the equation to the inverse-temperature fom:
1=1+ bins T1 T2 9
t2 Substituting above values into equation:
1_,
1
, 0.8617 x 10-4 1461 in T1 382 0.79 28.5 Solving for the four-year life tenperature:
T1 = 328.17'K = 131.3*F
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N20-3/ 2
r 9G10-AXGACO3-5068 el G55 Rev. 4 ATTACHMENT A-9 to V0GTLE QUALIFICATION REPORT, FQP-11A Effects of Gamma Radiation Exposure to 200 Mrads on 20 Inch Type 9220 Valve with Bettis Actuator
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UG6 OfS?m30 TION RD,,iUCTED FISHER CONTROLS COMPANY Project 7seco7 MARSHALLTOWN. IOWA
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1685-3
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REPORT 8
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DATE 2-17-81 LABORATORY REPORT EFFECTS OF GAMMA RADIATION EXPOSURE TO 200 Mrads ON 20" TYPE 9220 VALVE WITH BETTIS ACIUATOR ABSTRACT The SNUPPS environmental test valve (20" Type 9220 with Bettis T420B-SR2) was exposed to a total of 200 Mrads of Cobalt-60 (gamma) radiation. Testing was performed af ter completion of the qualification testing per FQP-19 without changing or readjusting the T-ring.
A dramatic increase in air leak rate occurred between 10 Mrads and 100 Mrads exposure over the entire test range (2.5 psid to 75 psid). With the addition of another 100 Mrads, the leak rate at the low AP again increased sharply.
However, at the high end of the AP range there was es-sentially no further change in leak rate.
INTRODUCTION 1.0 - This report covers work performed at Isomedix Inc., Parsippany, New Jersey on the SNUPPS Envirornental Test Valve. The test valve was a 20" Type 9220 with a Bettis T-420B-SR2 actuator and associated appurtenances.
Prior to this test sequence, the valve assembly had undergone the entire test sequence described in Fisher Controls Environmental Qualification Plan FQP-19 (reference 1) up to, but not including, the post-DBE (Design Basis Event) Radiation Exposure Test (see Section 9. 3, p. 28, of above mentioned document).
In addition, the valve assembly was subjected to an extra thermal exposure of 400*F for 15 minutes in an air oven, in accordance with FCS 14A2 (reference 1).
The testing reported here essentially completes the intent of FQP-19 and extends the radiation testing by an additional 100 Mrads. The procedures were modified somewhat due to factors described below, fid c.
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9G10- AX5 AC03-50 68-9 557 FISHER CONTROLS COMPANY MARSHALLTOWN, IOWA 1685-3 k
PROB.
8 REPORT 2
PAGE 2-17-81 DATE LABORATORY REPORT During the post-DBE functional testing (Section 9.2,19P-19), the Versa valve remained in the exhaust mode (the f ail-safe position) thus preventing the opening of the test valve. Since the remaining tests were for information only, it was decided to eliminate :the stroking time tests and to monitor leak rates only in determining radiation effects.
Also, since no test chamber was available at Isomedix, the leak rates were determined at ambient conditions instead of at 120*F as called for in FQP-19. This necessitated running an additional baseline leak test prior to irradiation. There was no readjustment of the EPDM T-ring nor f
had there been since the post-thermal aging adjustment early in the testing sequence.
In other words, the elastomeric seal ring had been adjusted for zero leakage at 75 psid and ambient temperature after a 50 day thermal and humidity aging sequence and then the valve assembly had undergone (1) 10 Mrads of ga=ma radiation, (2) seismic vibration testing, and (3) a design basis event (DBE) which consisted of a 30 day loss-of-coolant-accident (LOCA) simulation, and now, with this study, two additional doses of gamma radiation (90 Mrads and 100 Mrads) with-out touching the T-ring adjustment.
TEST PROCEDURE 2.0 - A complete description of the SNUPPS environmental test valve can be found in FQP-19 Rev. F (reference 1).
The condition of the valve assembly at the start of this test sequence and details of prior testing can be found in Wyle Labs Test Reports No. 45088-1 and No. 45390-1 (references 2 and 3).
The test valve was
9G10- AXGACO3-5060 '
GGB FISHER CONTROLS COMPANY MARSHALLTOWN, IOWA 1685-3
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8 REPORT PAGE 3
DATE 2-17-81 LABORATORY REPORT shipped directly from Wyle Labs, Huntsville, Alabama to Isomedix Inc., Parsippany, New Jersey. The two spool flanges had been removed prior to shipment.
PREPARATION FOR TESTING 2.1 - The two spool flanges with blind flanges already attached were rebolted across the test valve. The bolting was torqued to 540 f t-lbs, which was the same torque used previously at Wyle Labs.
BASELINE LEAK TEST 2.2 - Throughout this test sequence the valve assembly was oriented in the
{'
same manner as in the LOCA chamber (i.e., the disc was horizontal with the inlet side up).
(See Figure 3.)
The inlet air line was connected from a portable air compressor through a regulator to the top blind flange. The outlet air line was connected to the bottom blind flange with the other end submerged in water.
Air leak rates were measured by noting the time required to displace a known quantity of water with air when an inverted water-filled container was held over the end of the outlet air line. This technique worked well for all the baseline leak tests.
One problem was encountered with the test setup regulator in that its maximu= output was about 35 psig. To obtain leak rates above 30 psig, the regulator was removed from
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the inlet air line and the inlet pressure was " controlled" using a needle valve located st. the compressor volume tank.
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9510- AXGACO3-G 0 68
'l GU9 FISHER CONTROLS COMPANY MARSHALLTOWN. IOWA
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1685-3 REPORT 8
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DATE 2-17-81 LABORATORY REPORT PREPARATION FOR RADIATION EXPOSURE (90 Mrad Dose) 2.3 - The two blind flanges were removed from the inlet and outlet spool flanges to prepare the valve assembly for irradiation. The two spool flanges were lef t on the valve. At this point the valve assembly was turned over to Isomedix for radiation exposure.
RADIATION EXPOSURE 2.4 - The radiation exposure of 90 Mrads equivalent air dose was carried out as described in FGS14Cl (reference 4) and as reported in Isomedix letter
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dated February 3, 1981 (see Appendix C).
POST-RADI ATION LEAK TESTS 2.5 - On completion of the radiation exposure the valve assembly was removed from the radiation chamber and the two blind flanges were reinstalled.
Air leak tests were run using the same technique described in Paragraph 2.2. However, at high flow rates the technique was modified to a dry-fill measurement.
(i.e..
The outlet air flow was collected in a collapsed plastic bag. The time to inflate the bag to a known volume was measured.)
Also, at the high leak rates it became obvious that the pressure drop in the outlet air line was significant.
Hence, the pressure (P ) at the outlet blind flange was measured for several tests and these 2
values were plotted to obtain correction factors for the other leak tests.
(See plot in Appendix A.)
PREPARATION FOR SECOND RADIATION EXPOSURE (100 Mrad Dose) 2.6 - The procedure was identical to that described in Paragraph 2.3.
9510- AXGACO3-G060- 9 G60 FISHER CONTROLS COMPANY MARSHALLTOWN, IOWA PROB.
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REPORT 8
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DATE 2-17-81 LABORATORY REPORT RADIATION EXPOSURE l
2.7 - The radiation exposure of 100 Mrads equivalent air dose was carried out as described in FCS14C2 (reference 5) and as reported in Isomedix letter dated February 3,1981 (See Appendix C).
POST-RADIATION LEAK TESTS 2.8 - On the completion of the radiation exposure, the valve assembly was removed from the radiation chamber and the two blind flanges were reinstalled.
Air leakage was measured by two techniques:
(1) the water displacement technique described in paragraph 2.2 and (2) using an orifice well flowmeter. The calibration curves for the orifice sizes used are included in Appendix B.
INSPECTION 2.9 - At the completion of the leak testing, the two spool flanges were removed and the valve assembly inspected for visual damage. The valve disc was rotated to the open position by applying air pressure directly to the actuator cylinder.
(i.e., Bypassing the solenoid and the Versa valve.)
3.0 - DISCUSSION OF RESULTS AIR LEAK RATE TESTS 3.1 - The air leak rate test results for the baseline test and the two post-radiation tests are stanmarized in Table I.
The individual data sheets for each test are included in Appendix A.
In Figure 1, the leak rates are
U 9510- AXGAC03-5068-9 561 FISHER CONTROLS COMPANY MARSHALLTOWN. IOWA
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1685-3 REPORT 8
PAGE 6
DATE 2-17-81 LABORATORY REPORT plotted versus the differential pressure for all three runs.
(The use of log-log plot is for convenience only and is not otherwise significant.) The four different curves for the 200 Mrads data represent four different " fresh starts" (i.e., start-ing at zero pressure and increasing P1 incrementally).
Both post-radiation tests (100 Mrad & 200 Mrad total dosage) showed a pronouced leakage increase over the entire pressure range as compared with the baseline test (10 Mrad level).
Addition-ally, for the 200 Mrad test there was a certain amount of instability in the 10 to 20 psig inlet pressure range with the leak rate starting high and then dropping down to a lower level in a matter of minutes. This was probably due to a slight movement of the disc into a more favorable position in the seal ring.
For 30 psid and above the leak rates af ter 100 Mrads and 200 Mrads were practically identical.
In Figure 2, the leakage at 2.5 psid is plotted versus total radiation dose.
Here again, there is the obvious radiation effect, but compared with the SNIJPPS post-DBE leakage criteria (reference 1) only the 200 Mrad test exceeds the allowable leakage level.
If this test had been performed at 100*F instead of less than 70*F it might well have been within the allowable level.
VISUAL INSPECTION 3.2 - The entire valve assembly was visually inspected for obvious damage.
There was much rust and scale on almost every surf ace. Very little of the original paint was intact. A photograph of the general condition of the valve assembly is shown in Figure 3.
Actually most, if not all, of the degradation reported here was due to the thermal / humidity aging and the LOCA simulation.
1
9G10- AXGACO3-G060- 9 562 FISHER CONTROLS COMPANY MARSHALLTOWN. lOWA
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1685-3 8
REPORT 7
PAGE 2-17-81 DATE LABORATORY REPORT Removing the spool flanges revealed much evidence of corrosion on the valve internals.
Figure 4 is a photo of the inlet side of the disc showing much rust and scale. Also, Figure 5 is a close-up of the scale and debris that was in the sealing area, first noticed when the valve was stroked open. The only damage to the T-ring was a small cut in one of the " rub" areas near the shaf t (see Figure 6).
There was some wear,but it was not really excessive for the 1000 plus open/
close cycles the valve had been subjected to.
There was a very pronounced
" permanent set" to the T-ring due to the disc pressing into the rubber T-ring
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throughout most of the test sequence.
(See Figures 7 and 8).
Again, this phenomenon was not due to radiation exposure alone, but to the sum total of the thermal / humidity aging, the LOCA simulation and the radiation.
CONCLUSION 4.0 - While the test sequence was performed for information only, it is important to note that af ter 100 Mrads total radiation dose, the leak rate at 2.5 psid was still within the SNUPPS acceptance criteria for the post-DBE leakage as specified on Page 39.1 in EQP-19 (reference 1).
Also, after 200 Mrads, the 2.5 psid leak rate was only moderately larger than this same acceptance level, which was specified for 100*F.
Had the post-200 Mrad test been performed at 100*F instead of less than 70'F, the actual leakage would have been less and probably would have been close to the allowable 2944 cc/ minute.
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9G10- AXGAC0 3-G 0 60- 9 G63 FISHER CONTROLS COMPANY MARSHALLTOWN, IOWA PROB.
1685-3
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8 REPORT PAGE 8
DATE 2-17-81 LABORATORY REPORT It is also important to note that there was a dramatic radiation effect, with the greatest change occurring in the 10 to 20 psid range between the baseline (10 Mrads) and the 100 Mrads dose.
RECOMMENDATION 5.0 - In the past, 10 Mrads of radiation dosage was considered a safe maximum level for valve or appurtenances containing elastomeric materials (including Ethylene-propylene rubber [EPDM]). The results of this test sequence would tend to substantiate this 10 Mrad limit.
In any application where a f
valve might receive greater than 10 Mrads total radiation, the customer should be cautioned that a certain loss of pressure retaining properties would be expected.
h*
W.H. Haslett Evaluation & Analysis Department
9510-AXGAC03-5068-9 569 FISHER CONTROLS COMPANY MARSHALLTOWN. IOWA
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PROB.
1685-3 REPORT 8
PAGE 9
DATE 2-17-81 LABORATORY REPORT REFERENCES 1.
Fisher Controls Environmental Qualification Plan, FQP-19, Rev. F, dated April 14, 1980 modified by " Change of Scope to P.O. 217770" - dated October 28, 1980.
Further modified by Fisher Controls Test Program FGS14A2, dated October 28, 1980. Referenced to P.O. No. 220272, Test Part No. 1R0101X0022.
2.
Wyle Laboratory Report No. 45088-1, dated November 21, 1980.
3.
Wyle Laboratory Report No. 45390-1, dated November 7, 1980.
4 Fisher Controls General Specification FGS 14C1, Rev. A dated November 20, 1980.
" Subcontracted Services,1somedix Inc. Environmental Perfomance Testing (90 Mrad) 20" Type 9220 with Bettis T420B-SR2".
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5.
Fisher Controls General Specifications, FGS 14C2, Rev. A., dated November 20, 1980.
" Environmental Performance Testing 100 Mrad Radiation Exposure 20" Type 9220 with a Bettis T420B-SR2".
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T 9G10-AXGACO3-5068-9 577 erra. 10e3-3 R3p.
8 APPENDIX B Calibration Curves for Orifice Gauge
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9510- AXG AC03-UO60- 9 G70
[.
. FISHER GOVERNOR COMPANY MARSHALLTOWN. IOWA PROB.
1285
(
REPORT 10 PAGr 1
, ~
DATE 2-24-69
~
LAB'ORATORV REPORT CALIliRATION CURVES FOR'2" ORIFICE WEI.L I
Calibration tests were conducted for nine orifices in the 2" orifice well flommeter at inlet pressdres fmm inches water column to 10 psig.
e The following orifice sizes were checked:
6 1
.0 25;. 25;.1875;.250;.3125;,
375;.500;.625; and.750.
Cubes appear on Eigures 1 thru 18 respectively.
..../..The. 4.1.r flows-) vere. metered by means"6f a shdrp-edged crifice in the 2" c.,......
flow line.
e'c.$w cm a Paul E. Heckman Research Department O
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9510-AXGAC03-G068 'i Gul Pr b.
1685-3 R p.
8 k
APPENDIX C
(.
Isa edix Letter Report, dated Feb. 3, 1981
(
9510-Ax5AC03-5068 '.
502 4
g3
\\..'
/
Il
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~..
ISO MtIDIX k
February 3, 1981 Mr. Steve Hanzlik Fisher Controls Company s
P.O. Box 190 Marshalltown, Iowa 50158
Dear Mr. Hanzlik:
This will summarize parameters pertinent to the irradiation of one (1) 20" butterfly valve and actuator and two of 20" spools and blind flanges, as per your Purchase Order (2) each
$220409.
This is Wyle Job #45088 The unit was exposed for a total of 189 hours0.00219 days <br />0.0525 hours <br />3.125e-4 weeks <br />7.19145e-5 months <br /> at a dose rate of 0.49 megarads and received a do'se of 90 megarads.
then removed from the irradiator, It was tested by Fisher controls personnel, and placed back into the radiation field for 206 hours0.00238 days <br />0.0572 hours <br />3.406085e-4 weeks <br />7.8383e-5 months <br /> at a dose rate of 0.49 megarads receiving an additional
(-
100 megarads.
This was the same unit previously exposed to 11 megarads (see July 22, 1980 certification to E. Campbell, Wyle Labs).
Hence the total dose from all exposures was 201 megarads.
Dosimetry was performed using Harwell Red 4034 Perspex dosi-meters, utilizing a Dausch and Lomb Model 710 spectrophoto-meter as the readout instrument.
This system is calibrated directly with NBS, with the last calibration being November 11, 1980.
available upon request.A copy of the dosimetry correlation report is Irradiation was conducted in air at ambient temperature and pressure.
Radiant heat from the source heated the samples somewhat, but the temperature did not exceed 100 degrees F, as indicated by previous measurements on an oil solution in the same relative position.
l i
Isomedix tric.
- 25 Eastmans Road, Parsippany, New Jersey 07054. (201) 687-2666
7G10- AXGACO 3- 0068-1 GG3 i
February 3, 1981 6
~2-
\\
Fisher Controls Company 12, 1980 and was Irradiation was initiated on December 1980.
completed on December 23, Very truly yours, ISOMEDIX, INC.
L' David P. Constantine Production Manager DC:nsMr. G. Dietz
.cc:
4 s
07054. (201) 887 2GG6 25 Eastmans Road. Parsippany, New Jersey isomedix Inc.
9510-AXGAC03-5068-M_
50'l
[
ATTACHMENT A-10 to V0GTLE QUALIFICATION REPORT, FQP-11A Correspondence Relevant to NOA #4, NA-29 (see Attachment A-2)
~
n N19-11/ 10
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? 10- AX5e 1 *~ p,8 ei USG TRANSMITTAL. FORM FOR SUPPLIER DOCUMENTS J. I fh onin
' STATUS
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CC: D.
it.- REVISE AND RESUBMIT.. WORK MAY PROCEED SUBJECT TO R.
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E) 3._ _ REVISE _AND RESUBMITm WORK MAY NOT PROCEED.,
Nt
() - (NFORMATION O EY.
f1 - RESUBMIT.- NOT ACCEPTABLE FOR MICROFILMr WORK MAY PROCEED 3 - StPERSEDED.BY.LATER SUBMITTAL V - VOID
.(
) - DRAWING INVQICE. PAYMENT CODE DATE DUE PLAN VOOTLE-UN 18t2 PKG. NO. 22859
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FQP-11A B
N/A [ QUALIFICATION REPORT FQP-11A
.( ENV. SUPP. TO FQP-11C 8: 115
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IECHTEL POWER CORPOR ATION El Monte, ca. 9YN)4 4808 TERuiNAL ANNEX,P.O.s0x sosso, LOS ANGELES,CA 900s0
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95,10- AXG AC0 3-G 0 60- 4 506
~ DISTRIBUTION TO: FOR: REVIEW INFO.
V0GTLE ELECTRIC JOB NO.
GENERATING PLANT 9510
- MECHANICAL HVAC EQUIPMENT TAG N1.
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- CONTROL SYSTEMS T
- ELECTRICAL WIRING CONDUIT
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9G10- AX5 AC03-5068-9 588 1
(FIstMR memorandum
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To:
Doug Pothast From:
Jon Whitesell ec:
John Dresser Dave Stanze cate:
May 9, 1985 i
subect:
Qualification Plan FQP-11A l
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l Enclosed are three (3) copies of the following documents: Bechtel's Transmittal Fonn (Log No. 9510-AX5AC03-5068-3) dated 2-27-85 concerning the status of FQP-11A, a one page excerpt from Fisher Controls letter dated 5-2-83 to Mr. Bob Albrecht, Bechtel Power Corporation, Gaithersburg, Maryland which was in response to Bechtel's Transmittal No. 28089 and concerns the actuator-to-bracket mounting bolts, and Bechtel's letter to D.
Pothast dated 7-7-83 which indicates that Bechtel concurs with the Fisher resolution about the bolting. Also enclosed are three (3) copies of relevant excerpts from Qualification Reports FQP-23-B1 and FQP-23-B15 relating to the Wyle Seismic Test Reports for SNUPPS produc-tion valve-actuator configurations.
These reports show that no actuator bolting problems were experienced with properly-matched valve-actuator assemblies as sold.
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This correspondence will be referenced and included in the soon-to-be revised Qualification Plan FQP-11A.
F
x 9010-Ax0AC03-G068-9 589 Mr. Bob Albrecht Page 3 May 2, 1983 NOA 84 Problem 1:
Following is an expanded reiteration of information furnished in NA-29.
Since the information is already available in the referenced SNUPPS documents, no change should be required in NA-29.
The seismic test sequence was performed on the environmental test valve onlj for the purpose of providing seismic aging for the T-ring seal, since the same actuator and an identical body had both previously been properly seismically qualified.
(The Bettis actuator was subjected to 160 bi-axial test runs at inputs to 3.0 g's and frequencies from 1 to 40 Hz as described in Wyle Test Report 44500-11 and Fisher Report FQP-23-B15.)
(An identical 20" valve body with a Bettis T316B-SR2-M3-12 actuator that was much smaller and lighter than the environmental valve actuator, was seismically tested during 179 test runs at inputs up to 4.5 g's and frequencies from 1 to 40 Hz as described in Wyle Test Report 44500-7 and Fisher Report FQP-23-Bl.)
Consequently, the seismic aging sequence initiated on the environmental test valve, to age the T-ring seal, was started with inputs to 4.5 g's without recognizing the great added strain that the heavy actuator would be placing on the mounting bolts.
As recorded on N0A #4, page IX-13 and IX-14 of Wyle Report 45088, actuator-to-mounting bracket and mounting bracket-to-body bolts loosened repeatedly during the first 59 test runs. With the large Bettis T-4208-SR2-12 actuator on the relatively small 20" valve body, input amplification was so great that the bolts mentioned were yielding during the 4.5 g input loading.
Input levels were thereaf ter limited to 3.0 g's for the rest of the test sequence, to prevent damage to the unit.
However, once again, this seismic sequence was only for T-ring seal aging purposes and was not a legitimate seismic test on the rest of the assembly because the body and actuator components had already been satis-factorily qualified by the test mentioned, and because of the irregular size combination of body and actuator assembled for the enviornmental test.
Rationale for the selection of the environmental test valve components is presented in Section 2.0 of the environmental qualification Report FQP-23-A.
Problem 2:
(See introductory note for Problem 1 above. No change required for NA-29.
The seismic qualification testing of the actuator was complete and satisfactory, as described in Wyle Report 44500-11 and Fisher Report FQP-23-B15.
160 bi-axial test runs were performed at inputs to 3.0 g's and frequencies from 1 to 40 Hz.
There was no problem with the tubing during this test program.
However, the excessive amplification during the first 59 runs of the environmental sequence performed to seismically age the environmental test valve T-ring seal, plus the remaining 110 test runs to 3.0 g's, plus the initial 160 test runs (during the actuator seismic qualification) caused fatiguing of the tubing at the tubing connection and created the leakage noted in paragraph 10 of N0A #4.
As stated
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in NA-29, the leakage did not affect capability of the valve to perform its safety-mode function.
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Bechtel 3ower Corporation Engineers - Constructors 15740 Shady Grove Road Gaithersburg, Maryland 20877 1454 301 - 258-3000 Mr. D. Pothast i
Fisher Control International, Inc.
0 7 583 205 South Center Street Marshalltown, Iowa 50158 File: J-605A, M-236. M-237 Bechtel Job Number 10466 SNUPPS Project Environmental Qualification Documentation FQP-23A Ref:
1.
Fisher Letter Dated 5/2/83
Dear Mr. Pothast:
F Reference 1 transmitted Fishers resolutions to the Bechtel comments to the subject report. Bechtel concurs with the Fisher resolutions with the exceptions noted below:
A.
The statement provided in NOA #4, Problem 2 should be included in the Fisher resolution.
Fisher should identify that the failure
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of the tubing was a result of the excessive fatigue incurred as a result of the seismic aging of the actuator during the environmental test plus the previous seismic qualification testing of the same actuator.
B.
Additional analysis is required to assure that the cracking of the Hoffman junction box will not occur following a seismic event.
Fisher should compare the accelerations experienced by the environmental test specimen to those experienced by the 18 inch and 36 inch seismic test specimen (test valves XV and XVI). Also, if the junction box had been seismically qualified by previous testing (ref. Fisher response to N0A #4, problem 2) then this should be identified. If neither of the above actions provide a satisfactory resolution then Fisher should be prepared to provide the maximum length of unsupported cable the junction box conduit interface will tolerate.
Fisher is directed to revise the subject report incorporating the resolutions Bechtel has accepted. A response to items A and B above is requested within two weeks of the date of this letter.
Very truly yours, D. R. Quattrociocchi JU:ek Project Engineer Systems cc:
N. A. Petrick
9G10- AXSACO3-5060- 9 591 RIv._A
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ATTACHMENT 2 to SNUPPS QUALIFICATION REPORT FQP-23-B1 Wyle Dynamic Test Report No. 44500-7 Dated October 16, 1979 (Includes Revision A, dated December 6, 1979)
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M37F2
9510- AXGAC03-50 60- 9 592 SEISMIC TEST PROGRAM ON A 20" TYPE 9220 VALVE WITH A BEM IS MODEL T-3165-SR2-M3-12 ACTUATOR SPECIMEN 1 PROJECT 79WA02
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FOR FISHER CotCROLS COMPANY, INC.
f 205 SOUTH CENTER STREET MARSHALLTOWN, IOWA 50158
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S in Section 7.0 1.0 CUSTOMER Fisher Controls Company, Inc.
ADDRESS 205 South Center Street, Marshalltown, Iowa 50158 l
2.0 TEST SPECIMEN 20" Type 9220 valve (Serial No. BF23'3774) with a Bettis Model T-316B-SR2-M3-12 Actuator Fisher Controls Company, Inc.
3.0 MANUFACTURER i
4.0
SUMMARY
A 20" Type 9220 Valve with a Bettis Model T-316B-SR2-M3-12 Actuator, hereinafter called the specimen, was subjected to a Seismic Simulation Test Program as required by the Fisher Controls Company, Inc., Purchase Order Number H-212262 and the Fisher Controls Company Seismic Qualification Plan FQP-23, Revision 5.
This test program was performed on August 21 and 22,1979.
The test program consisted of resonance search testing and single frequency (sine beat) testing in each of two test orientations. Additionally, the specimen was tested for leakage and a position deviation cycle was performed prior to and after the simulated seismic excitation. The specimen was instrumented with accelero-j meters and was electrically and pneumatically powered and monitored for functional operation during the test program.
The specimen demonstrated sufficient integrity to withstand, without compromise of structure, electrical function, or mechanical function, the prescribed simulated seismic environment.
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9510- AXGAC03-5068-9 599 Rev.
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ATTACHMENT 2 to 4
SNUPPS QUALIFICATION REPORT FQP-23-B15 I
i Wyle Dynamic Test Report No. 44500-11 Dated January 21, 1980 t
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9510- AXUACO3-5068-9 U95
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SEISMIC TEST PROGRAM CN A 36" TYPE 9220 VCE WITH A BETTIS MCCEI.
T-4203-SR2-M3-12 ACTtATOR SPECIMEN XV PRCJECT 79WA02 FCR FISHER CCNTRCLS CCMPANY, INC.
205 Sct.*ni CENTER STREET MARSHA.LTCWN, ICWA 50158
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9G10-AX5AC03-5060 el 596 SEISMIC ~ SIMULATION M ~"*F
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Test Report 44500-11 g
REPORT NO.
44500-04 WYLE JOB NO.
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January 21, 1980 DATE
. g SPECIFICATION (S) 4hf[
4 in Section 7.0 1.0 CUSTOMER Fisher Centrols Company, Inc.
ADDRESS 205 South Center Street, Marshalltown, Iowa 50158 2.0 TEST SPECIMEN 36" Type 9220 Valve (Serial No. BF241001) with a Bettis Model T-420B-SR2-M3-12 Actuator 3.0 MANUFACTURER Fisher Controls Coc:pany, Inc.
4.0
SUMMARY
A 36" Type 9220 Valve with a Bettis Model T-420B-SR2-M3-12 Actuator, hereinafter called the specimen, was subjected to a Seismic Simulation Test Program as required by the Fisher Controls Company, Inc., Purchase order Number H-212262 and the Fisher Controls Company Seismic Qualifiation Plan FQP-23, Revision 6.
This test program was performed on December 12 and 13,1979.
i The test program consisted of resonance search testing and single frequency (sine beat) testing in each of two test orientations. Additionally, the specimen was tested for leakage prior to and after the simulated seismic excitation. The speci-men was instrumented with accelerometers and was electrically and pneu utically powered and monitored for functional operation during the test program.
The specimen demonstrated sufficient integrity to withstand, without compromise of structure, electrical function, or mechanice.1 function, the prescribed simu-lated seismic environment.
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ATTACHMENT 5 Includes:
Fisher Qualification Report FQP-llAB-7 (BPC Log # X5Ac03-5151-2)
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V0GTLE ELECTRIC JOB NO.
- MECHANICAL GENERATING PLANT 9510 HVAC EQUIPMENT TAG NO.
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