ML20206M240
| ML20206M240 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 04/14/1986 |
| From: | Bausch H, Danesh P WYLE LABORATORIES |
| To: | |
| Shared Package | |
| ML20206M077 | List:
|
| References | |
| 57688-1, 57688-1-RC, NUDOCS 8704200070 | |
| Download: ML20206M240 (60) | |
Text
o WYLE usannaams scacc saavcas a smius onov, ENGINEERING Wyle Report No. 57e88-1
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CsFis41 HILLSIDE AVENUE NORCO, CALIFORNIA REPORT 91740 Wyle Job No.NES-576 A R AREA CODE 714-7374071 TwX 9143321204 TELECOPY (714) 7374078 Customer P.O. No.14 92F-FOO1 FO Task 6 Total Poges this Report 41 Date: 4/ /85 Revision A October 15, 1985 Revision B January 23, 1906 r
Revision C EVALUATION OF ENVIRONMENTAL Apr 14, 1986 QUALIFICATION AND AGING ANALYSIS OF CONTROL VALVES FOR USE IN SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION O -
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- i PREPARED BY- r b dual ~
VERIFIED bye ^^2 APPROVED bye 415 QUALITY ASSURANCE:
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Report No. 57688-1
- LABORATORIES SCIENTIFIC SERVCES & SYSTEMS GROUP Page No. i
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wJ REVISIONS Rev.No. Date Pages Affected Preparw Reviewer QA PE Cm'vh of Changes A 10-15-8: 7, 10, 12-14, 17, g y Incorporated customer com-32, 33, 35 [b f.
gg ments B 1-23-86 4, 5, 7, 10 & 34 Incorporated customer com-f.D -
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,,3 ments C '+-14-86 10, 13, 15, 24, 27- Incorporated customer 23, 30-34, 37-38, 40-41 fj/// pp 3Y comments t
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REPORT NO M.onmmis u scame sovers a sysmas onow
.- s WESTEAN OPERATIONS, NORCO FACluTY , ,, , 2 (v)
TABLE OF CONTENTS Page No.
1.0 SCOPE............................................................... 3 1.1 O bj ec t i v e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0
SUMMARY
............................................................ 3 3.0 APPLICABLE QUALIFICATION STAND ARDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 AND DOCUMENTS 4.0 EQ UIPM ENT D ESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5.0 DEFINITION OF SERVICE CONDITION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 6.0 EVALU ATIO N APPRO AC H . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 6.1 O p e rabili t y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
- 6. 2 R a d i a t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 O 6.3 Th e rm a l Agin g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
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i 6.4 Cy cli c Ag in g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 7.0 EV ALU ATIO N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 7.1 Ope ra b ili t y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
- 7. 2 R a d i a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 7.3 Th e r m a l Agin g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 7.4 Cycli c Ag ing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 8.0 CO N C LU SIO N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 9.0 R EF ER EN C ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 TA BL E 1, AG IN G M ATRIX . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 FIGURE 1, ACCIDENT TEM PER ATURE PROFILE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 FIGURE 2, ACCIDENT TEM PER ATURE PROFILE FOR FWIV . . . . . . . . . . . . . . . . . . . . . 43 FIGURE 3, ACTIVATION ENERGY DISTRIBUTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44 C
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REPORT NO-aAmenatones aceamPC SEIMctS & SYSTiest enoup WEBMtN oPERADoNE NoRCO PACERY 3 0 ~
1.0 SCOPE This document was prepared by Wyle Laboratories for Bechtel Corporation (BEC) for equipment to be used in the South Texas Project Electric Generating Station.
1.1 Objectives The purpose of this document is to provide a) an evaluation of the qualification of ,
the equipment identified in Paragraph 4.0, b) an analysis to up and determine the qualified life of the equipment, and c)identify grade replacement the qualification intervals for age-sensitive parts. -
2.0
SUMMARY
, The drawing of each valve was reviewed. Age sensitive components were identified.
The effects of radiation, thermal and cyclic aging on these components were analyzed. Radiation damage levels available in the literature did not support the ,
qualification of valve components containing Teflon and Delrin material, and electronic parts, for radiation level specified in paragraph 5. Table 1, Aging Matrix, presents the summary of the analysis. ! l, 3.0 APPLICABLE QUALIFICATION STANDARD AND DOCUMENT O o IEEE 323-1974 " Standard for Qualifying Class IE Equipment for Nuclear Power Generating Station."
o IEEE 627-1980 " Standard for Design Qualification of Safety Systems Equipment Used in Nuclear Power Generating Stations."
o Bechtel Specification 4A479ES1018, Rev. 2, " Specification for the Environmental Qualification of Safety-Related Electrical and Mechanical Equipment for the Houston Lighting and Power Company South Texas Project l Electric Generating Station."
i o Wyle Laboratories Western Test and Engineering, Quality Assurance Manual,
, 380 Rev. D dated 15 April 1984. l 1
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. s Mm_ seeweesacasasmausonow 57688-1 WESTMN OPERAM NoeCO PACluTY 4
) Revision B gi 4.0 EQUIPMENT DESCRIPTION Valve Tag. No. Valve Type BlWL-FV-4919 1" Globe, Active B2WL-FV-4919 CIPS-FV-4461 C2PS-FV-4461 BIPS-FV-4456 B2PS-FV-4456 CIPS-FV-4452 C2PS-FV-4452 BIPS-FV-4466 B2PS-FV-4466 BIRC-FV-3652 1" Ball, Active B2RC-FV-3652 NICC-FV-4526 1" Globe, Non-Active N2CC-FV-4526 NICC-FV-4525 N2CC-FV-4525 O' NICC-FV-4524 N2CC-F V-4524 NICV-PCV-Oll5 1" Ball, Non-Active
't N2CV-PCV-Oll5 BlIA-FV-8565 2" Ball, Active B21A-FV-8565 BlWL-FV-4913 3" Globe, Active B2WL-FV 4913 AIED-FV-7800 A2ED-FV-7800 AIEW-FV-6914 A2EW-FV-6914 1 BIEW-FV-6924 B2EW-FV-6924 CIEW-FV-6934 C2EW-FV-6934 BIRC-FV-3651 3" Ball, Active B2RC-FV-3651 O
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57688-1 S
umanames seemeumacessemius=
3 WBfMN OPERAM NOSCO PACIUTY Revision C
%.0 EQUIPMENT DESCRIPTION (Continued)
Valve Tag. No. Valve Type NICC-LV-4501 3" Globe, Non-Active i
'/ BIRM-FV-7603 4" Globe, Active I B2RM-FV-7653 CIRM-FV-7659 s C2RM-FV-7659 CI AF-FV-7515
, C2AF-FV-7515 L BI AF-FV-7516
'\- B2AF-FV-7516 i AI AF-FV-7517 i A2AF-FV-7517 a~
AlEW-FV-6935 A2EW-FV-6935 BIEW-FV-6936 O B2EW-FV-6936 CIEW-FV-6937 C2EW-FV-6937 A 1 MS-FV-7412 A2MS-FV-7412 AIM 3-FV-7422 A2MS-FV-7422 BIMS-FV-7432 B2MS-FV-7432 B1 MS-FV-7442 B2MS-FV-7442 NIUI-FV-4500 N2UI-FV-4500 N IRM-LV-7651 4" Globe, Non-Active
- s. N2RM-LV-7651 NICV-FCV-0110B 4" Ball, Non-Active N2CV-FCV-0110B NICV-FCV-OlllB i
N2CV-FCV-OlllB N ICV-FV-3127 N2CV-FV-3127 N ICV-FV-3381, ,
i N2CV-FV-3381 O i t 7
57688-1 m OPERAM NotCO PACluTY 5 o vienn a c ;
,N 4.0 EQUIPMENT DESCRIPTION (Continued)
Valve Tag. No. Valve Type
'NICC-LV-4501 3" Globe, Non-Active N2CC-LV-4501 BIRM-FV-7663 4" Globe, Active
.' B2RM-FV-7663 S CIRM-FV-7659 C2RM-FV-7659 CI AF-FV-7515
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C2AF-FV-7515 BI AF-FV-7516 B2AF-FV-7516 Al AF-FV-7517 A2AF-FV-7517 AIEW-FV-6935 A2EW-FV-6935 BIEW-FV-6936 B2EW-FV-6936 O CIEW-FV-6937 C2EW-FV-6937 AIMS-FV-7412 A2MS-FV-7412 AIMS-FV-7422 A2MS-FV-7422 BIMS-FV-7432 B2MS-FV-7432 BlMS-FV-7442 B2MS-FV-7442 NIUI-FV-7518 NIRM-LV-7651 4" Globe, Non-Active N2RM-LV-7651 NICV-FCV-0110B 4" Ball, Non-Active
< N2CV-FCV-0110B NICV-FCV-OlllB N2CV-FCV-OlllB NICV-FV-3127 N2CV-FV-3127 NICV-FV-3381 N2CV-FV-3381 O ,
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i REPORT NO umanamans scame ss=cs: a svsuus enou, WESTERNOPERATloNE NOACOPACIUTY 6
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4.0 EQUIPMENT DESCRIPTION (Continued)
Valve Tag. No. Valve Type .
AIFW-FV-7141 18 x 16 x 18 Gate !
A2FW-FV-7141 Active 1 l
AIFW-FV-7142 '
A2FW-FV-7142 AIFW-FV-7143 A2FW-FV-7143
, AIFW-FV-7144 A2FW-FV-7144 5.0 DEFINITION OF SERVICE CONDITION BEC has specified the following environmental condition (Ref.1):
Normal Condition Accident Condition Pressure (psig) 0 1.6 Temperature (OF) 135/50 240 See Figure 1 O' Radiation (Rads)
Gamma 1 x 107 (40 years) 8 x 106(180 days)
Relative Humidity 80 % 100 The FWIV shall be required to operate under the following harsh environmental condition:
Normal Condition Accident Condition Pressure (psig) 0 5.8 Temperature (oF) 104/29 335 (see Figure 2)
Radiation (Rads) 200 3.5 x 105 (40 years) (180 days)
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57688-1 wasvuwopenAncess sooncoFAcany 7 Revision B 6.0 EVALUATION APPROACH The valves are grouped into active and non-active. For non-active valves, the qualification concerns are age sensitive non-metallic materials which could i
compromise the pressure boundary of the valve. For active valves, the actuator and electrical accessories are also included in the evaluation.
J 5
The valve and actuator are evaluated based on mechanical and electrical equipment qualification requirements of Bechtel Specification 4A479ES1018, Rev2. The 1
environmental requirements for mechanical equipment is to determine the effects 4
of time / temperature aging and radiation on non-metallic materials such as the i gasket and 'O' rings. The electrical components are evaluated to determine
, operability in specified environment, the effects of radiation, and thermal and j cyclic aging.
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- 6.1 Operability 4
This evaluation compares the results of type testing of electrical components with STP's qualification level. If qualification test levels do not envelope the STP's level, then manufacturer's published environmental parameters for these components will
- O be reviewed. The results of type test and this review are combined to demonstrate electrical component operability in the specified environments.
4 6.2 Radiation j The approach for evaluating and upgrading radiation qualification is:
4 j 1. Review the valve drawings and data sheet and identify all components made of 2
organic materials.
! 2. Obtain the auditable radiation damage threshold of the organic material.
4
- 3. Review the qualification test report and identify the test level.
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- 4. Compare the test level and STP's requirement.
- 5. If radiation test level does not envelop the requirement, identify the material ,
, with lowest radiation damage threshold level.
- 6. Calculate a period during which the effects of radiation on component of valve and actuator is insignificant.
6.3 Thermal Aging For many organic materials, it is known that the degradation process can be defined by a single temperature-dependent reaction that follows the Arrhenius equation
, (Ref. 2 and 3):
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6.3 Thermal Aging (continued) k = A exp (-(Ea/kBT)) (1) where, k = reaction rate A = frequency factor exp = exponent to base e Ea = activation energy kB = Boltzmann's Constant (8.617 x 10-SeV/K)
T = absolute temperature It is further noted that, for many reactions, the activation energy can be considered to be constant over the applicable temperature range. Life is assumed to be inversely proportional to the chemical reaction rate (Ref. 2 and 4). In terms of life, and af ter converting to Napierlan base logarithms, equation (1) becomes:
In (life) = (Ea/kB)(1/T) + Constant (2)
Equation (2) has the algebraic form:
y = mx + b, where, y = In(life) x = 1/T m = Ea/kB, constant for single dominant reactions b = constant The constants, m and b, can be estimated by fitting the experimental data in the form of In(life) versus 1/T to the above simple linear relationship.
Equation (1) can be transformed into a form which yields an acceleration factor to define a given amount of thermal degradation. The form is:
- t1/t2 = exp ((Ea_ ( 1 - 1 )) (3)
KB T1 T2 O
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REPORT NO- I uno==ss sc=m e.us a svinw ow wsmRN oPERAfioNS, NoRCO FACluTY , 9 l v
l 6.3 Thermal Aging (continued) l where, t1 = accelerated aging time at temperature T1 t2 = normal service time at temperature T2 !
T1 = accelerated aging temperature (OK)
T2 = normal service temperature (OK)
Equation (3) can be used to derive the accelerated aging times for materials with known activation energies.
The Arrhenius model of aging will be used in the following manner to calculate the qualified life of the components of valve and actuators.
- 1. Identify the non-metallic materials used in each component of the valve actuators.
- 2. Obtain for each material available Arrhenius plots from Wyle Aging Library.
- 3. Obtain aging temperature and duration from test reports.
- 4. Calculate qualified life with Equation 3.
- 5. If a component was not thermally aged, calculate the expected life of the organic material with Equation 2. Divide expected life by 2 to obtain age insensitivity period.
6.4 Cyclic Aging The effect of cycling on electromechanical components will be evaluated by reviewing published data. The cyclic aging evaluation will be performed as follows:
- 1. Obtain the design load and number of cycles required from Bechtel Specification.
- 2. Obtain number of cycle and test condition that each component was tested to.
- 3. Compare test parameters to cycle requirements.
- 4. Determine the effects of cycling aging.
The radiation, thermal and cyclic aging insensitivity periods are enveloped to determine the qualified life of each component.
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57688-1 Musaamaans ses,,mcmancasamason , 10 WESTMN oPHAfloNE.NotCO FACIUTY r3 Revision C
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7.0 EVALUATION The drawing and data sheet for each valve was reviewed. For non-active valves, the age sensitive parts that compromise the pressure boundary of the valves were identified. For active valves, safety related electrical components were also identified. Table 1, Aging Matrix, lists all the components that are made of non- .
metallic or have non-metallic parts, and presents the results of aging and radiation ;
analysis. The radiation, thermal and cyclic aging insensitivity periods were l enveloped to determine the qualified of each component.
7.1 Operability Each active valve except for item 17 of Table I has a solenoid valve and limit switch. These two components are part of valves located outside containment.
However, item 17 has a solenoid valve but its qualification is not part of this task.
The limit switches are Namco Series EA180. A certificate of compliance (COC) for Namco Series EAISO Limit Switch is part of Reference 5. This COC refers to a Namco qualification test report (Ref. 6) as a reference. .Namco data sheet for EA180 switches (part of COC) shows a ambient service temperature of -200 to 90 0 C for switches. Reference 6 states Series EA 180 Limit Switches were tested to IEEE 323-74 Loss of Coolant Accident (LOCA) temperature and pressure profile.
The switches performed satisfactorily in LOCA environment. The maximum temperature and pressure reached during test were 3400F and 70 PSI. The data v presented in these two references demonstrate the operability of Namco Series EA 180 limit switches for STP's temperature and pressure profile, Figure 1 and 2.
The solenoid valves are ASCO Models HV A-206-330-$u, HV A-206-3S t -Su, NP8321 A2E and NP8321 A6E. The COC provided for these valves in Reference 5 shows these valves were exposed to LOCA condition as specified in Figure 1 of IEEE-382-1972. The valves performed their function satisfactorily during the LOCA test. IEEE 382-1972, Figure 1, envelops the requirements of STP. Therefore, operability of these valves for STP's temperature and pressure profile, Figure I and 2, was demonstrated.
7.2 Radiation Table I lists the radiation damage threshold level for organic materials. Asbestos, Graphite are minerals and are not affected by specified radiation. Therefore, radiation has insignificant effects on packing, packing rings and gaskets made of Graphite, Grafoil(made of Graphite) or asbestos. The following paragraphs explain the analyses in detail, where detail explanation was necessary.
7.2.1 Item 2, Table I contains four age sensitive parts. Review of this valve's drawing shows that the failure of the stem gasket and seat ring do not compromise the pressure boundary of the valve. The seat ring helps the valve ball rotate easier and prevents leakage from high to low pressure side. The valve's " cup" prevents leakage to the outside environment should stem gasket degrade and allow leakage. These two parts, the gasket and the seat ring, are considered not safety related and O exempt from qualification rquirements. The valve's 'O' ring and cup are made of EPR and Tefzel. Reference B identifies 3 radiation damage levels for EPR. Table 3 lists these levels.
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REPORT NO- 07b88-I ueonarones acaemnc senveces a systress enour westenN OPsAATIONE NORCo FACluTY pg ,,o II o
TABLE 3 EPR RADIATION DAMAGE THRESHOLD Radiation Level (Rad) Damage Utility 2.0E6 Incipient to Nearly always Mild usable 8.0E7 Mild to Of ten satisfactory moderate 8.0E8 Moderate to Limited Use Severe Tefzel is tolerant to high radiation dose. Table 4 shows the effect of radiation levels on Tefzel (Ref. 9).
TABLE 4 TEFZEL RADIATION DAMAGE LEVEL Radiation Level (Radd Tensile, PSI Elongation, %
0 5100 300 7.0E6 5200 250 5.0E7 4500 95 1.0E8 4200 55 2.0E8 4200 25 3.0E8 4400 15 5.0E8 2700 10 The total integrated dose (TID) required including 10% margin is 1.98E7 Rads.
The data presented in Table 3 and 4 shows that EPR 'O' ring and Tefzel cup are affected by this dose level. However,it is judged that this degradation will not affect the ability of the 'O' ring and cup to perform their safety-related function.
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""*"*""""*"******""' 12 wastammopenAnom woncopaenny Revision A 7.2.2 Item 4, Table 1,is similar to item 2, except the " cup"is made of asbestos and Teflon (TFE). Since the cup material is a blend and not a chemical compound, each material is addressed separately. Asbestos is a mineral and not affected by .
specified radiation level. Teflon is sensitive to radiation. Teflon's radiation damage threshold is 1.7E4 (Ref. 12). The radiation damage threshold of Teflon is significantly'less than the accident level. The cup will significantly degrade during the accident and, therefore is ryot qualified for this application.
l 7.2.3 Item 9, Table 5 contains an EPDM diaphragm. Reference 20 presents the result of various studies done on the effects of radiation on EPDM material. Table 5 shows the change in mechanical properties as total dose increases.
i TABLE 5 EPDM RADIATION DAMAGE LEVEL Dosage (Rads) Elongation Change Tensile Change Compression Set Change
. 1.0E6 - - No Change 5.0E7 52% - -
1.0E8 63 % 21 % -
2.0E8 - 50% -
- Table 5 shows EPDM has kept about 50% of its mechanical properties after exposure to 1.0E8. Therefore, it is concluded that EPDM can perform its function after exposure to 1.98E7 Rads.
7.2.4 The air regulator, item 11.5, Table 1 contains two radiation sensitive materials, Buna-N and Delrin (Polyacetal). Buna-N is used as diaphragm. Buna-N's radiation damage threshold is 2.0E6 Rads. Reference 2) presents the results of various studies done on the effect of radia%~ on Bona-N. Buna-N was all right up to about 4.0E6 in the static test. Its ten.ile strength and elongation properties were affected at a dose level higher than 5 x 107 Rads.
Delrin was irradiated up to 6.0E6 Rads. Significant degradation was observed at a dose level above 1.0E6 (Ref. 20). Delrin is the weak link material in the air regulator. The air regulator is required only for normal service application.
Therefore, the radiation insensitivity period is:
106 radiation threshold lx10 normal radiation m 40 years = 4 years 1 40 years O
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37688-1
- ' wesinnuossamucocorm 13 Revision C j
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i 7.2.5 The diaphragm, item 12.2 of Table 1, is made of Buna-N/ Nylon. Buna-N is considered to perform the primary function and Nylon performing a supportive function. The expected life of Buna-N is 5 years. The total integrated dose i including margin that Buna-N diaphragm is exposed to during its 5 years service life is 1.0175E7. The data presented in paragraph 7.2.5 indicates that TID of 1.0175E7 l l do not degrade the diaphragm to a point where it cannot perform its safety related ,
- function. l 7.2.6 Item 17.6, Table 1, is a pressure transducer. This pressure transducer is a diaphragm type transducer with bonded strain gage. The transducer assembly contains electronic circuit for its amplifier. The transducer is not radiation hardened per manufacturer (Ref. 21). Radiation causes increase in leakage currents, spurious 1 signal, and change in calibration. Reference 22 cites mild to moderate damage i
starting at a dose level below 1.0E4 Rads for bonded strain gage. The most radiation sensitive electronic component of the transducer is the integrated circuit 1 (IC) used as an amplifier. The radiation damage threshold for IC's varies from 1.0E3 i to 10E4 (Ref. 23). The transducer is only required for normal operation. The I
required normal dose for the pressure transducer, including 10% margin, is 220 Rads in 40 years. This radiation dose does not affect the performance of the transducer in 40 years.
7.3 _A_ginan 1'
The valve packing and gasket are made of Graphite and Asbestos. These two i materials are non-organic and insensitive to time / temperature aging. Gaskets made of Asbestos and Stainless Steel (30455) are also age insensitive. The following shows how each material was analyzed. This analysis takes into account the effects of the a) normal and b) accident temperature. This analysis assumes the components containing or made of organic materials are stored per manufacturer
- j. recommendation and used during recommended shelf life. Therefore, aging analysis is based on in-service temperature.
j ltem 2.1, Table 1 is an 0-ring made of Ethylene Propylene Rubber (EPR). Equations
! 2 and 3 are used to calculate 'O' rings expected life. The worst case normal service
, temi erature is 1350F. The accident temperature profile shows temperature is at 240(F for 4 minutes. The accident temperature drops 1900F within 6 minutes and stavs at this temperature for 7 days. It is judged that the 'O' ring does not experience the maximum accident temperature since it is protected by the valve bcdy, and the duration at 2400F is short. The accident temperature used in the
-alculation is 1900F since the valve is exposed to this temperature long enough for
! che 'O' ring temperature to reach the steady state of 1900F. Therefore, using
! temperature of 1900F in the calculation to determine the affects of the accident on
'O' ring is conservative.
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57688-1 sc=ene es=ces a sysme ew 34
( woman openAnom peosco PAouw Revision A 7.3 A, A (Continued)
The EPR Arrhenius parameters are:
5 = Ea = 15524.1267 (Ref. 7)
Kg I = -29.8774 the constant of equation (2) (Ref. 7) t1 = t2 exp (15524.1267 ( 1 -
1 Tl T2
, tl= Life at accident temperature t2= The equivalent life at 1350F T 1=The accident temperature,1900F T 2= Normal service temperature 1350F 1 - 1 7 days = 2T Exp (15524.1267 ( E E))
t2= 380 days at 1350F Required life at normal temperature = 40 x 365 = 14600 days Total life required = 14600 + 380 = 14980 days The expected life of EPR is: In(life) = 15524.1267 - 29,g774 T where T = 330.2K or 1350F Expected life = 27.7E6 hours or 1.154E6 days The EPR expected life far exceeds its required life. "therefore, EPR is not significantly affected by time / temperature aging in 40 years f i O i
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g--- ses mac semicas a avswus ee, 57683-1 WESTERNoPERADoNE NoACoFACERY I5 I 1
'V Revision C 7.3.1 Item 4.3, Table I is made of Asbestos and Teflon (TFE). Teilen is the weak link materlat of the gasket. The age sensitivity of this gasket was based on the affect of time / temperature on Teflon.
7.3.2 Item 9.6, Table I is an Asco solenoid valve HVA-206 model. Reference 15 contains the materials list and their activation. The seat material for this valve is either Viton or EPDM. Reference 14 cites an activation energy of 0.96 for Viton and EPDM. The weak link material of the valve is Viton or EPDM. This model valve was thermally aged for 13.25 days at 2500F as part of a nuclear environmental qualification (Ref.15). The qualified life of this valve was calculated to be 11 years for use in the South Texas Project. 7.3.3 Item 13.6, Table 1 is an Asco solenoid valve, model NP832 with Viton seat. This valve has Class H coil similar to Model HVA206. This valve was thermally aged for 100 hours at a temperature of 2980F (Ref.19). An anomaly was observed during thermal aging. Reference 19 contributes the anomaly to high aging temperature and not matrial degradation. The qualified life of this valve was calculated to be 14 years for service in the South Texas Project. 7.3.4 Item 17.5 is a Parker Seal, Poly Pak seal. PolyPak seal is a combination of an 'O' ring and lip-type seal. This seat is made of Polymyte. Polymyte is a Parker packing material. Arrhenius parameters for this material were not available for this analysis. Reference 24 concludes that PolyPak physical property retention was excellent after 70 hours of aging at a temperature of 3020F. PolyPak activation energy is assumed to be 1.0. Figure 3 is the distribution of various age sensitive material activation energies (Ref. 3). This figure shows a mean value of 1.15 eV for activation energies. It also shows a greater number of organic materials have activation energies equal or larger than 1.20. Therefore, the activation energy
- assumed for PolyPak is conservative.
PolyPak is not significantly affected by time / temperature in 40 years, based on above thermal aging test and assumed activation energy. l 7.4 Cyclic Aging The electromechanical components of the valves are Asco valves and Namco limit switches. A number of anticipated cycles for valves and limit switches were not specified by reference 1. Therefore, this analysis is limited to identifying the qualification level specified by references 6,14 and 18. Table 6 lists the qualification level for Asco valves and limit switches, O
/Y _
M --- _: sen macsemisasm a=w REPORT NO- 57688.1 westsaw openAnom monco rAcam ,,, , 16 TABLE 6 ASCO VALVES AND LIMIT SWITCHES QUALIFICATION LEVEL PART DESCRIPTION No. CYCLES REFERENCES Asco Valves 20,100 14 Model HVA-206 Asco Valves 40,000 18 Model NP-8321 Namco Limit 100,000 6 Switches Model EA180 0 4 !O l I 1 i
/7
57688-1 REPORT NO-umana==s sc===csancesasewow 17 westenNopenADoNE,NoACo FACluTY paos no Q Revisio, A
8.0 CONCLUSION
The aging mechanisms considered in this report are radiation, time / temperature and cyclic. Some of the valve components were made of materials or parts sensitive to radiation. The radiation damage level available in the literature do not support the qualification of these components for specified STP level. Teflon material and electronic parts were found radiation sensitive. Gaskets made of Asbestos and Teflon and FWlV valve pressure transducers were found to contain these material / parts and thus not qualified for this application. Table 7 lists these , components. TABLE 7 UNQUALIFIED COMPONENTS Table 1 Item No. Component Description 4.3, 5.4, 6.4 and Asbestos and TFE 8.4 Cup 17.6 Pressure Transducer O 20
37688-1 wasvann openAnosa,nonco pacam I8 O y/ Revision C
9.0 REFERENCES
- 1. Bechtel Energy Corporation Task Description No. 4026EQl.
- 2. "IEEE Guide for the Statistical Analysis of Thermal Life Test Data" IEEE 101-1972, Library Code 265-80.
- 3. " Review of Equipment Aging Theory and Technology." 5.P. Carfagno and R.J.
Gibson, Franklin Research Centr, Electric Power Research Report No. EPRI-NP-1558, Library Code 600-82.
- 4. Handbook of Engineering Fundamentals, 3rd Edition, O.W. Eshbach and M.
Sanders, pp 1284, John Wiley & Sons 1975, Library Code 247-80.
- 5. " Static Bend Test with Dynamic Flow for W-K-M Type 70-18-9 Control Valve with MED/LR G DTR Actuator", Becht! Energy Log 14926-8026-01103-BWV and 14926-4026-01103-BWV.
l 6. " Qualification of Namco Controls Limit Switch Model EA-180 to IEEE Standard O 323-74, 344-75 and 382(72)", Attachment 15 to FQP Rev. B, Bechtel Log M-237-0177-0. (Part of Fisher Valve Package).
- 7. " Wires and Cords for Original Equipment Manufacturers," General Electric Company, No. WCC-2, Library Code 185-79A.
- 8. Selection Guide to Organic Materials for Nuclear Enginering," M.H. Van de Voorde, European Organization for Nuclear Research CERN 72-7, Library Code 4
431-81.
- 9. "Tefzel ETFE Fluoropolymer: Temperature Rating and Functional Characterization," DuPont Publication A-84539, Library Code 211-79A.
10." Rite Pak Packing," Crane Packing Company, Bulletin No. P-3023, 11." Military Specification on Wire, Electrical, Insulated, High-Temperature," Mil-W-16878D (Navy), April 3,1978, Library Code 218-79A. 12." Report on the Effect of Radiation on Electrical Insulating Materials," C.L. Hanks and D.J. Hamman, REIC Report No. 46, June,1969, Battelle Memorial Institute, Library Code 299-80.
- 13. Design Guide for Reactor Cover Gas Elastomer Seals. Atomics International, l
Division of RockwellInternational.
- 14. Test Report No. AQR-67368/Rev. O, " Qualification Report of Automatic Switch O Company Catalog NP-1 Solenoid Valves for Safety-Related Applications in Nuclear Power Generating Stations".
{ c2 /
57688-1 Monames i.a sc===csemicasasme=om 19 A westeRNOPERAfloNE NoRCoFACUTY U
9.0 REFERENCES
, (Continued)
- 15. " Studies Identify Problems and Strengths of Collector Seals and Sealing Compounds," Solar Engineering, August,1981, Library Code 624-82.
16." Preliminary Data Report - Testing to Evaluate Synergistic Effects from LOCA Engironments," Frank V. Thome, Sandia Laboratories, No. SAND 78-0718, April, 1978, Library Code 334-80. 17."The Effect of Nuclear Radiation on Elastomeric and Plastic Materials," R.W. King, et al., Battelle Radiation Effects Center, REIC Report No. 21, September 1,1961, Library Code 286-80.
- 18. Qualification Test of Solenoid Valve by Environmental Exposure to Elevated Temperature, radiation, wear aging, seismic simulation, vibration endurance, accident radiation, and loss of coolant accident simulation", Isomedix Test Report AQS216781TR.
19.DuPont U.L. File No. 66288, August 30,1977, Library Code 163-78A. 20." Radiation Effects on Organic Materials in Nuclear Plants," M.B. Bruce and M.V. O Davis, EPRI Report No. NP-2129, Library Code 506-81 A.
- 21. Telephone Contact Report between Shayan Pazargadi of Wyle Laboratories and Petr Van Yessen of Consolidated Controls Corp. dated 4/25/85.
22." Radiation Effects State-Of-The-Art 1964-1965," Radiation Effects Information Center, #38, June 30,1965, Library Code 398-80. 23."What Happens to Semiconductors in a Nuclear Environment?", David K. Myers, Fairchild Camera and Instrument Corporation, Electronics, March 16, 1978, Library Code 227-79.
- 24. Parker Seals Technical Bulletin 88 dated March 5,1985.
O , l 1
REPORT NO-umanames sc==we senacts a smsus eaa, wasnow openAnows,woeco rAcuny , , , 20
- TABLE 1 AGING MATRIX EXPLANATION The Table has seven (7) columns. An explanation of each column heading follows:
i
- 1) Item No.
Listed by hierarchy: 1.0 Valve 1.1 Components 1.1.1 Parts of Component
- 2) Valve Type and Tag No.
This column contains the valve tag No. and its type
- 3) Part Description This column describes the component or parts of the components
- 4) Non-Metallic Material, Arrhenius Parameters This column specifies the materials. The Arrhenius parameters, Ea (eV), S (Slope), and I (Intercept) are identified in this column. If the material is not l organic, the column only specifies the material. The source of Arrhenius parameters are referenced in the paranthesis.
l
- 5) Radiation Damage Threshold This column specifies the level of gamma radiation at which the component or material is susceptible to degradation. If the component has been irradiated, the level appears in this column and radiation damage threshold of constituents materials are not entered in this column. The source of the radiation threshold level is referenced in parenthesis. If a material or component is not sensitive to specified radiation,"NRS"is entered in this column.
l 6) Quallfled Life 1 The radiation, thermal and cyclic aging insensitivity periods are enveloped to determine the qualified life. This column specifies the qualified life. A blank in i this column means the item is not qualified. j 7) Remark This column provides supplemental information. ; Abbreviation NRS = Not Radiation Sensitive O 1
R:: port No,5',w 1 Page No. 21 4 Revision C i AGING MATRIX 4 j Item Valve Type Part Descriptkm Non-Metallic Material Radiation Damage Qualified Remarks No. Tag No. Arrhenius Parameters Threshold (Rads) Life l
- Years l
1.0 1" Globe 40 Non-Active 1.1 NICC-FV-4526 Gasket 304SS and NRS 40 N2CC-FV-4526 Flexitalic Asbestos NICC-FV-4525 N2CC-FV-4525 - NICC-FV-4524 - 1.2 N2CC-FV-4524 Packing Graphite NRS 40 j - Grafoil GTR \ j !.3 Packing Ring Grafite NRS 40 1625 Grafite i 2.0 1" Ball ! Non-Active i N !CV-PCV- ) O!!5 3 2.1 N2CV-PCV- 0-Ring EPR 1.0E6 40 See Para. j 0115 5 = 15524.1267 (Ref8) 7.2.1 ! l = -29.8774 * ! (Ref 7) j 2.2 Gasket Stem Teflon N/A N/A Not a pressure N/A boundary part l i See Para 7.2.1 4 NRS = Not Radiation Sensitive N/A = Not Applicable N k i
._ ._~ __ __ _ _ _ . _ _ _ . _ .. .__ _ _ __ __. .
~
Report No,i . l Page No. 22 j Revision C AGING MATRIX
! Item Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks j
No. Tag No. Arrhenius Parameters Threshold (Rads) Life j Years , l 1 j 2.3 Cup Tefzel 7.0E6 40 l 5 = 10452.59004 (Ref 9) i I = -13.33866 (Ref 9) ) I 2.4 Seat Ring Teflon N/A N/A Not pressure i N/A boundary part See Para 7.2.1 3.0 4" Globe 40 Non-active NIRM-LV-7651 ' N2RM-LV-7651
- 3.1 Gasket 30455 and NRS 40 l Flexitalic Asbestos i
j 3.2 Packing Graphite NRS 40 { Grafoil GTR j 3.3 O-Ring EPR 1.0E6 40 Same as item J 2.1 S = 15524.1267 (Ref.3) l' E = 29.3774 (Ref.7) 1 3.4 Backup EPR 1.0E6 40 Same as Item l 2.1 Ring S = 15524.1267 (Ref.6) E = -29.3774 (Ref.7) 4 3.5 Packing Grafite NRS 40 ] g
- Ring
~
Riport No. 37O
%/
Page No. 23 Revision C AGING MATRIX Item Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks No. Tag No. Arrhenius Parameters Threshold (Rads) Life Years 4.0 4" Ball 40 Non-Active NICV-FV-3127 N2CV-FV-3127 4.1 0-Ring EPR 1.0E6 40 Same as item 2.1 S = 15524.1267 (Ref.8) I = -29.3774 (Ref.7) 4.2 Gasket Stem Teflon N/A N/A Not a pressure boundary part 4.3 Cup Asbestos & TFE 1.7E4 See paragraph 5 = 19575.54576 (Ref.12) 7.2.2 & 7.3.1 I = -27.12214 (Ref.11) 4.4 Seat Ring FIL-TFL N/A N/A Not a pressure boundary part 5.0 4" Ball 40 Non-Active N ICV-FCV-011IB N2CV-FCV-011IB 5.1 Seat Ring FIL-TFL N/A N/A Not a pressure boundary part g S
Report No. 37688-1 . Page No. 24 l i Revision C l AGING MATRIX l i Radiation Damage Qualified Remarks l Item Valve Type Part Description Non-Metallic Material Arrhenius Parameters Threshold (Rads) Life j No. Tag No. Years EPR 1.0E6 40 Same as item 5.2 0-Ring 2.1 5 = 15524.1267 (Ref.8) ] I = -29.8774 - (Ref. 7) l Teilon N/A N/A Not a pressure 5.3 Gasket-Stem boundary 1 $ Same as item j 5.4 Cup Asbestor & TFE 1.7E4 (Ref.12) 4.3, see para t S = 19575.54576 7.2.2 & 7.3.1 1 = -27.12214 (Ref.1!) I l 1, I i
!Q i
i ,
l O O n-Rtport No. Siv.8-1 Page No. 25 Revision C i AGING MATRIX i i I Item Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks l No. Tag No. Arrhenius Parameters Threshold (Rads) Life .i Years i
! 6.0 4" Ball 40
) Non-Active l N ICV-FCV-l 0110B i l N2CV-FCV-1 0110B Seat Ring FIL-TFL N/A N/A Not a pressure ) 6.1 beundary part. 1 i 56 me as item j 6.2 0-Ring EPR I.0E6 40 2.1 5 = 15524.1267 (Ref.8) i I = -29.3774 1 (Ref.7) i 6.3 Gasket Stem Teflon N/A N/A Nat a pressure j boundary part. i } 6.4 Cup Asbestos &TFE I.7E4 Same as item j S=19575.54576 (Ref.12) 4.3, see para.
!=-27.I2214 7.2.2 & 7.3.1
] (Ref. I!) 7.0 3" Globe Non-Active N ICC-LV-4501 l N2CC-LV-4501
~
V '- R; port No. 376T3-1 9 age No. 26 Re<ision C AGING MATRIX Item Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks No. Tag No. Arrhenius Parameters Threshold (Rads) Life Years 7.1 Gasket 304SSand NRS 40 Flexitalic Asbestos - 7.2 Packing Graphite NRS 40 Grafoil GTR 7.3 Packing Ring Graphite NRS 40 1625 GF 8.0 4" Ball 40 Non-Active NICV-FV-3331 N2CV-FV-3331 3.1 Seating Ring FIL-TFL N/A N/A Not a pressure boundary part. 3.2 0-Ring EPR I.0E6 40 Sanne as item 2.1 5 = 15524.1267 (Ref.8) I = -29.3774 (Ref.7) 8.3 Casket Stem Teflon N/A N/A Not a pressure boundary. 3.4 Cup Asbestos &TFE 1.7E4 Sarne as (Ref.12) ite n 4.3, see para 7.2.2
% anci 7.3.1
'N
Report No. L :-! Page No. 27 Revision C AGING MATRIX ltem Valve Type Part Description Non-Metallic Materiel Radiation Damage Qualified Remarks No. Tag No. Arrhenius Parameters Threshold (Rads) Life Years 9.0 1" Globe 40 Active 9.1 BlWL-FV-4919 Gasket 304S5 and NRS 40 B2WL-FV-4919 Flexitalic Asbestos CIPS-FV-4461 C2PS-FV-4461 9.2 BIPS-FV-4436 Packing Graphite NRS 40 B2PS-FV-4456 Grafoil CIPS-FV-4452 9.3 C2PS-FV-4452 Gasket Asbestos NRS 40 BIPS-FV-4466 B2PS-FV-4466 9.4 Diaphragm EPDM 1.0E6 40 See para 7.2.3 S = 17024.15987 (Ref.8) 1 = -36.76409 (Ref.13) 9.5 Limit Switch 204E6 22 Namco, EA- (Ref. 6) 180-21302 9.5.1 'O' Ring EPDM 40 5 = 17024.15987 1 = -36.7409 (Ref.13) C - - - __ _ __ _ ._ _ . . ,
O O n Report No. 57L_41 Page No. 28 . Revision C AGING MATRIX Item Yalve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks No. Tag No. Arrhenius Parameters Threshold (Rads) Life Years 9.5.2 Gasket Silicon Rubber 22 S = 11515.47633 I = -21.925 (Ref.15) 9.5.3 Contact Asbestos Filled 40 Block Phenolic S = 12551.209 I = -20.023 (Ref.16) 9.5.4 Contact Asbestos Filled 40 Carrier Phenolic S = 12551.209 I = -20.023 (Ref.16) 9.6 Solenoid valve 205E6 11 See Para Asco HVA-206- (Ref.14) 7.3.2 331-3U i 9.6.1 Coil Tube Nomax 410 0.96 (Ref.14) 9.6.2 Magnet Wire Polythermalcze l 1.16 (Ref.14) xk
Os _ Rtport No. 57,% J Page No. 29 . Revision C - AGING MATRIX ltem Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks No. Tag No. Arrhenius Parameters Threshold (Rads) Life Years 9.6.3 Cross over Noma 410 Barrier Ea=0.96 eV (Ref.14) 9.6.4 Lead wire Silicon rubber insulation Glass braided Ea=1.08 eV (Ref.14) 9.6.5 Seat EPDM 1.0E6 Seat material Ea=0.94 eV (Ref.8) is EPDM or (Ref.14) Viton 10.0 3" Globe 40 Active BlWL-FV-4913 10.1 B2WL-FV-4913 Gasket 30455 and NRS 40 AIED-FV-7300 Flexitallic Asbestos A2ED-FV-7800 10.2 Packing Graphite NRS 40 Graphoil 10.3 Gasket Asbestos NRS 4D Diaphragm Case k u
O O ' O l Report No. 57688-1 i Page No. 30 Revision C l AGING MATRIX i i 1 [ ltem Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks j No. Tag No. Arrhenius Parameters Threshold (Rads) Life j Years i j 10.4 Diaphragm EPDM 1.0E6 40 Same as item 9.4
) S = 17204.15937 (Ref.8) j 1 = -36.76409 J (R ef.13) ? ! 10.5 1.imit switch 204E6 22 Namco EAISO- (R ef.16) 21302 ; 10.5.1 'O' ring EPDM 40 5 = 17204.15937 I = -36.76409 (R e f.13) a i 10.5.2 Gasket Silicon Rubber 22 5 = 15515.47663 1 = -21.925 (Ref.15) ,
i 10.5.3 Contact block Asbestos Filled 40 - 1 Phenolic ' l 5 = 12551.209
- I = -20.023 i (Ref.16) 10.5.4 Contact Asbestos Filled 40 Carrier Phenolic 5 = 12551.209
! l = 20.02 3 j (Ref.16)
. ~.
_. - - ---r, ,,. O O O
~
~
Report No. 57688-1 Page No. 31 Revision C AGING MATRIX ltem Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks No. Tag No. Arrhenius Parameters Threshold (Rads) Life Year: 10.6 Solenoid valve 205E6 11 Same as Asco HVA-206 (Re f.14) Item 9.6
-381-5u 10.7 O-Ring EPR I.0E6 40 Same as item 2.1 S = 15524.1267 ~(R e f.8)
I = -29.8874 (R ef.7) 10.8 Backup ring EPR I.0E6 40 5 = 15524.1267 (Ref.8) 1 = -29.8874 (R ef.7) 10.9 Packing ring Graphite NRS 40 1625 GF 11.0 Globe 3" Active A IEW-FV-6914 11.1 A2EW-FV-6914 Gasket 304S5 and NRS 40 BIEW-FV-6924 Flexitallic Asbestos B2EW-FV-6924 C IEW-FV-6934 C2EW-FV-6934 11.2 Packing Ring Graphite NRS 40 Gratoil GTR
Report No. 5 (d s) Pcge No. 32 Revision C AGING MATRIX Item Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks No. Tag No. Arrhenius Parameters Threshold (Re,ds) Life Years 11.3 Limit switch 204E6 40 Same as Namco EA!S0- (Ref.16) item 9.5 21302 + 11.4 Solenoid valve . 203E6 40 Sam'e as Asco, HVA-206- (Ref.14) item 9 9 - 380-5u ,
!!.5 Air Regulator 4 See Para 7.2.4 WKM 11.5.1 Diaphragm Buna-N 2E6 5 -
S = 7343.953 (Ref.17) I = -14.294 (Ref.13) i1.5.2 Intervalve Polyacetal 6.0E5 40 Guide and S = 11025.973 (Ref. 3) Venture I = 19.655 (Ref.19) 11.6 Gasket, Dia- Asbestos NRS 40 phragm Case 11.7 Casket, 304 SS and Asbetos NRS 40 11.3 Packing Ring Graphite NRS , 40
- 1625 GF '
/
12.0 4" Glob / 40 Active .
Report No. 37688-1 ,
... Page No. 33
_ AGING MATRIX p l Item Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks .,
- No. Tag No. Arrhenius Parameters Threshold (Rads) Life Years i 12.1 BIRM-FV-7663 Gasket 30455 and Asbestos NRS 40 B2RM-FV-7663 Flexitallic C IRM-FV-7659 12.2 C2RM-FY-7659 Diaphragm Buna-N/ Nylon 1.0E6 3 See para 7.2.6 A IEW-FV-6935 S = 7843.958 (Ref.18)
A2EW-FV-6935 1 = -14.294
- (Ref.13) 12.3 BIEW-FY-6936 Limit Switch 204E6 22 Same as item B2EW-FY-6936 (Namco, (Ref.16) 9.5 CIEW-FV-6937 EA180-21302)
C2EW-FV-6937 12.4 Solenold valve 205E6 11 Same as item l HVA-206-381- (Ref.14) 9.6 j Su 12.5 Air Regulator 4 Same as item j WKM 73-68-1 11.5 4 12.6 'O' Ring EPR I.0E6 40 i S = 15524.1267 (Ref.8)
. I = -29.8774 (Ref. 7) 12.7 Backup ring EPR 1.0E6 40 ; 5 = 15524.1267 (Ref.8) i i = -29.8774 ! (Ref. 7)
[D Report Nw 57Ljt Page No. 34 , 4 Revision C AGING MATRIX i Item Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks No. Tag No. Arrhenius Parameters Threshold (Rads) Life Years 12.8 Packing ring Graphite NRS 40 1625 GF 13.0 4" Globe Active 13.1 CI AF-FV-7515 Gasket 30455 and NRS 40 C2AF-FV-7515 Asbestos BI AF-FV-7516 13.2 B2AF-FV-7516 Packing Ring Graphite NRS 40 l AI AF-FV-7517 Grafoil GTR A2AF-FV-7517 . 13.3 AIMS-FV-7412 Gasket, Asbestos NRS 40 A2MS-FV-7412 Diaphragm Case ] AIMS-FV-7422 ,
- A2MS-FV-7422
- 13.4 A2MS-FV-7422 Diaphragm Buna-N/, Nylon 2.0E6 5 S=7843.958 BIMS-FV-7432 i B2MS-FV-7432 !=-14.294
. B IMS-FV-7442 (Ref.13) 13.5 B2MS-FV-7442 Limit Switch 204E6 22 Same as item NIUI-FV-4500 Namco (Ref.16) 9.5
. N2UI-FV-4500 EA180-21302 l 13.6 Solenoid valve 200E6 14 See Para. 4 Asco NP8321 A2E) (Ref.18) 7.3.3 3 i k N 1
O O O I Report No. 57688-1 Page No. 35 Revision A q AGING MATRIX 4 Item Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks ! No. Tag No. Arrhenius Parameters Threshold (Rads) Life Years 13.6.1 Coil Tube Nomax 410 . 0.96 eV . (Ref.14) . 13.6.2 Magnet Wire Polythermaleze 1.16 eV (Ref.14) . 13.6.3 Cross over Nomax 410 l Barrier Ea=0.96 eV (Ref.14) i .i 13.6.4 Lead Wire Siirun Rubber Insulation Glass Bralded Ea= 1.08 ! (Ref.14) 13.6.5 Seat Viton ! Ea-0.96 (Ref.14) 13.7 Air Regulator 4 Same as Item i WKM 11.5 .l
o O O Report No. 5768A 1 AGING MATRIX l i Item Valve Type Part Description Non-Metallic Material Radiation Damage Qualified t No. Tag No. Remarks Arrhenius Parameters Threshold (Rads) Life i Years I
- 13.8 'O' Ring EPR 1.0E6 40 See item 2.1 5 = 15524.1267 (Ref.8)
- I = -29.8774 (Ref.7) i l '
13.9 Backing Ring EPR 1.0E6 40 - See item 2.1 3
' 5 = 15524.1267 (Ref.8)
I = -29.8774 (Ref.7) ] 13.10 Packing Ring Graphite NRS 40 j 1625 GF { 14.0 la Ball Active ! BIRC-FV-3652 j B2RC-FY-3652 1
- 14.1 Seat Ring Tefzel 7.0E6 40 Not a pressure i
S = 10452.59 (Ref.9) j boundary part 1 = -13.33866 . (Ref.9) 14.2 'O' Ring EPR { 1.0E6 40 See item 2.1 Tallpiece S = 15524.1267 (Ref.8) I = -29.8774 (Ref.7) 1 i 14.3 Gasket Stem Tefzel 7.0E6 40 Not a pressure S = 10452.59 (Ref.9) boundary part I = -13.33866 (Ref.9)
~
I
O O O Report Ns. 57688-1 Page No. 37 Revision C ] AGING MATRIX i Item Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks
, No. Tag No. Arrhenius Parameters Threshold (Rads) Life Years 14.4 Cup Teizel 7.0E6 40 See item 2.3 5 = 10452.59 (R ef.9) i i = -13.33366 4 (R ef.9)
. 14.5 Actuator 40 Bettis CB520 SR 30l2 14.5.1 Solenoid Valve 200E6 14 Same as item Asco NP8321 A (Ref.18) 13.6 2E 14.5.2 Limit Switch 204E6 22 Same as item i E A 130-32302 (Ref.16) 9.5 i and EA180-l 31302 j 14.5.3 Regulator Metallic NRS 40 Fisher 95H 14.5.4 Filter Metallic NRS 40 Fisher 254F i l 2
O (~) O Report Na 57LJ1 i Page No. 38 - Revision C ] AGING MATRIX 4 Item Yalve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks No. Tag No. Arrhenius Parameters Threshold (Rads) Life Years 15.0 2" Ball Active BilA-FV-8565 , l B21A-FV-8565 15.1 Seat Ring Tefzel 7.0E6 Not a pressure
; 5 = 10432.59 (Ref.9) boundary part I = -13.33866 (Ref.9) 15.2 'O' Ring EPR 1.0E6 40 See item 2.1
- 5 = 15524.1267 (Ref.8)
I = -29.8774 i (Ref.7) 15.3 Gasket Tefzel
- Stem S = 10432.59 7.0E6 Not a pressure I = -13.33366 (Ref.9) boundary part (Ref.9)
) 15.4 Cup Tefzel
! S = 10432.59 7.0E6 40 See item 2.3 j 1 = -13.33866 (Ref.9)
(Ref.9) 1 15.5 Actuator Metals C 40 Bettis CB 420 SR 8012 i x
'N
/ V,#N R: port Nw 5768 Page No. 39 Revision C AGING MATRIX ltem Valve Type Part Description Non-Metallic Material Radiation Damage Qualified Remarks No. Tag No. Arrhenius Parameters Threshold (Rads) Life Years 15.5.1 Solenoid Valve 200E6 14 Same as item Asco NP8321 A6E (Ref.19) 13.6 15.5.2 Limit Switch 204E6 22 Same as Item Namco EA180- (Ref.14) 9.5 31302 and EA180-32302 15.5.3 Regulator Metallic NRS 40 Fisher 95H 15.5.4 Filter Metallic NRS 40 Fisher 254E 16.0 3" Ball 40 Active -
B IRC-FV-3651 B2RC-FV-3651 16.1 Seat Ring Teizel 7.0E6 Not a pressure S = 10452.59 (Ref.9) boundary part I = -13.33866 (Ref.9) 16.2 'O' Ring EPR 1.0E6 40 See item 2.1 Tailpiece S = 15524.1267 1 = -29.8774 (Ref.7) 16.3 Gasket Tefzel 7.0E6 40 Not a pressure Stem S = 10452.59 boundary part I = -13.33866 (Ref.9)
Report Ns. 37688-1 Page No. 40 Revision C AGING MATRIX Item Valve Type Part Description Non-Metallic Material Radiation' Damage Qualified No. Tag No. Remarks Arrhenius Parameters Threshold (Rads) Life Years i 16.4 Cup Telzel 7.0E6 40 See item 2.3 S = 10452.59 ' I = -13.33866 4 (Ref.9) 16.5 Actuator 40 i Bettis CB725
; SR8012 16.5.1 Solenoid 200E6 14 Same as Item Valve (Ref.18) 13.6
- Asco INP8321 A2E 16.5.2 Limit Switch 204 22 Same as item Namco, EA180- (Ref.16) 9.5 31302 and EA180-32302 1 16.5.3 Regulator Metallic NRS 40 Fisher, 45H 16.5.4 Filter Metallic NRS 40 Fisher, 254F 17.0 18 X 16 X 18 Gate Valve Active
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MAMCO CONTROLS f*F1M"TFIES THAT SWITCEES FURNISHED HAVE BEEN IWNUFACTURED, LTIPECIED,
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-May 15, 1986 Wyle Ref: 57688 l Bechtel Ref: ST-UL-YB-99 i Bechtel Energy Corporation P.O. Box 2166 ,
Houston, Texas 77252 Attention: Technical Document Control Section l
Subject:
TSC 14926-EQO1EQ, Task No. 6 (4026EQ1) ,h !
Reference:
Bechtel Package No. 15775 *g g%NB00 Gentlemen: . Enclosed in accordance with subject Task are one (1) reproducible and three 1 (3) copies of Wyle Laboratories' Engineering Report 57688-1, Revision C, dated . April 14, 1986. Your (referenced) coments have been incorporated, except as ll explained below: I. Reference Bechtel Coment Number 2: A. A copy of the Certification of Compliance (C0C) found in Reference 5 is attached to this letter. The report cited . l in this COC was found as part of the Fisher Control Valve l documents (See Reference 6). B. Reference 18 is the Qualification Report for the ASCO Solenoid Valve. II. Reference Bechtel Comments Number 3 and 5: Test data was not available to Wyle to determine the effects of 1.98E7 rads (nomal + accident + 10%) on the teflon used as binding material. The published radiation threshold for teflon is 1.7E4 rads. The required radiation level is higher than the threshold level by a factor of 1000. Since available data indicates teflon degrades significantly at higher dose levels, we cannot qualify the valve cup based on available data. I Very truly yours, fE LA RA S
..;iyao'p-
obert R. Houser Contracts Manager RRH/ce cc: Ms. Mary Chambers ..s. enc 1. 1841 Hillside Avenue, Norco. Cattfomia 91760 (714)737-o871 TWx 910-3321204 Telecopy 714-735-4030
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ST-UL-YB-106 Bechtel Energy Corporation Wyle Ref 57688 P.O. Box 2166 Houston, Texas 77252 Attention: Ms. Mary Chambers /Mr. Sarkis Gharakhanian
Subject:
TSC 14926-EQ01EQ, Task No. 6 (4026EQ1)
Reference:
Bechtel Coments, Package 16818, Transmitted via Datafax from Mr. Sarkis Gharakhanian on 6-26-86 Gentlemen: The following information is provided in response to Bechtel Comment 1 in the referenced document: In general, 106 the radiagion threshold damage for Teflon is taken as 1.7 x ergs /gm (1.7 x 10 rads) based on observations reported by Collins, C.G. and Calkins, V.P. in " Radiation Damage to Elastomers, Organic Liquids, and Plastics," APEX-261, General Electric Company, Cincinnati, Ohio, Atomic (~'s Products Division, Aircraft Nuclear Propulsion Department, September 1956. i ' V Additional data reported by Harrington suggest that the tensile strength decreased by 40% after a dosage of 3 x 10 rads while the elongation decreased by 93%. At these dose levels, Teflon becomes a very brittle substance tion Fields,(Harrington, Part I: Robert, " Plastics and Elastomers for Use in Radia-1956). Effects of Gama 3rradiation," HW-44092, November 30, Since the particular application in this case consists of micron-size Teflon that t particles embedded in Asbestos yarn, it is reasonable to anticipate 3 x 10ge Asbestos / Teflon cup is not adversely affected by dosages up to rads since the Teflon particles themselves provide no structural strength to the Asbestos yarn. Asbestos itself being a silicate mineral is not adversely affected by this dosage. Based upon these data, a revised threshold limit of 3 x 106 rads may be used for the cup design in minimumdosageof1.04x10ghisapplication. This exceeds the required rads as specified in the Bechtel comment. At levels in excess of 3 x 100 rads, the elongation of Teflon will further degrade to zero, the polymer will become very " crumbly" and the individual particles will most likely lose any remaining cohesiveness resulting in cup deterioration. Very truly yours, E LABORA IES m m a e n nn m Dj g (g g [j yf @ 4 e t R. ser ,lp: 1.1 e Contracts Manager
# 14926 $0lltH ffM5 PA0ltCT RRH/tp PROCllREMENT l
1841 Hillside Avenue, Norco. Califomia 91760 (714)737-0871 TWx 910-3321204 Telecopy 714 735 4030
I f 1 r t l l l REFERENCE # 198 SOURCE : MEQ -1 i I l l [
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- Embricants . Labricanon . E dadaa Efects ~
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O V October 16, 1986 Robert O. Bolt, Ph.D. Relationship of Maximum Transient Temperatures to Dropping Point and Flash Point: Extra Reference South Texas Project Mr. E. A. Goldenberg I T - Bechtel Power Corporation MECHANICAL. Mail Stop 50/5/B41 EQUIPMENT P.O. Box 3965 94119 QUALIFICATION San Francisco, California REFERENCE a 2.46 Attention: Mr. Mehdi Fard g TA% i of g f
Dear Mr. Goldenberg:
You asked for our recommendations on the above subjects. s Transient Temperatures One should not use a maximum transient temperature that closely approachesFire the dropping point for grease or flash point safety considerations are involved with flash lubric ation. point. It seems reasonable to specify a limit of 85% of the flash point or dropping point of fresh material for the maximum transient in tem- the perature. We suggest this be included, where appropriate, MDS's. This specification provides leeway for small changes in droppingCh points and flash points. This severe with severe thermal exposure and/or radiolysis. Adherence to relubrication in condition is rare. by equipment builders or lubricant suppliers will prevent excessive lubricant deterioration that would cause problems. Additional Reference Data on base oils are given in MDS 1 from earlier Chevron Research work. Enclosed are tables from this effort fromThe whichworkthe wascited for data were taken. The final report was in 1951. 55 Culloden Pk. Rd. . San Rafael, CA 94901. (415) 453-6095
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Mr. E. A. Goldenberg Attn: Mr. Mehdi Fard October 16, 1986 Fairchild Engine and Airplane Company, an Air Force contractor. I It was on a NEPA (Nuclear Energy Powered Aircraft) project,and ( California (later Chevron) Research was subcontractor. Sincerely, pv u ROB:msr Encl. - Data Tables California Research- 1 NEPA Project 1951 r_ - ..=.....s ..
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1 . ..e - .. . '- En0331.7 bec: E. A. Goldenberg l B. x. Dilodare Bechtel Power Corporation { '. M. Fard Engews-Consieuctors r Fdty Beaw Street San Francesco C4Wo'naa ye,# Age,ss P o Bos 3965. San Ftencsco. CA 94'9 l October 28, 1986 i Mr. J. G. Carroll 88 Valley Avenue Martinez, CA. 94553
Subject:
Houston Lighting and Power South Texas Project, Job No. 14926 Critical Review of SIP IAlbricants
Dear Jim:
i Thank you for the information you provided during the telephone conversation of October 27, 1986. This information will be used in part to evaluate the 1
. capabilities of lubricants in transient tenperature environment. ,
1
.The enclosed record of conversation is provided for you'r verification. Please sign at the concurrence block provided below and return the letter to us.
Your response by November 11, 1986 is greatly appreciated.
, Thank you again for yoiar assistance. Should you have any questions, please M contact Baldwin Toy at (415) 768-6015.
Very truly yours, O 1
.Q 4 .
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E. A. Goldenberg Manager, Equipment Qualification Group
/W/BKIVEAG:lsb Encl.: Telecon of October 27, 1986, Transient Tenperatures for Lubricants.
cc: Dr. R. O. Bolt 55 Culloden Park Road San Rafael, CA. 94901 Concurrence Signature Date O Mlol/JGCl w.s
**+ + o L: 9;isp,7 Bechtel Power Corporation Engeeers-Construe:o's
- Fifty Beale Street San Francisco. Califorma Meet AcRfress: P o Bon 3965. San Francisco. CA 94"9 October 28, 1986 Mr. J. G. Carroll 88 Valley Avenue Martinez, CA. 94553 l Houston Lighting and Power l
Subject:
South Texas Project, Job, No.14926
, Critical Review of SIP Ialbricants Daar Jim:
Thank you for the information you provided during the. telephone conversation of October 27, 1986. This information will be used in part to evaluate the capabilities of luoricants in transient tesperature environment. The enclosed record of conversation is provided for your verification. . Please sign at the concurrence block provided below and return the letter to us. Your response by Novencer 11, 1986 is greatly appreciated. f Thank you again for your assistance. Should you have any questions, please contact Baldwin Toy at (415) 768-6015. i ( Very truly yours, hME. A. Goldenberg Manager, Equipment Qualification Group Br/MF/BKD/EAG:1sb Encl.: Telecon of October 27, 1986, Transient i Tenperatures for Lubricants. 4 cc: Dr. R. O. Bolt 55 Culloden Park Noad San Rafael, CA. 94901 Concurrence Signature Date _ . M101/JGC1 sC.4 i 4 _,,.n,__,_,-, m.,,,,-- -,--,,---,.-_n_,,,,,,,e-,m,--,,,
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En033t? . ( ) TELEPHONE y . , CALLS ( ) Pc Baldwin Toy oF SFO-EQG STP YO/27/86 JOB NO. TIME TO # J. G. Carroll Consultant 14926 3:35 pm ITEME OF OtSCUSSION ACTION REQ *D. (INCLUDE NAMES & DATES) ITEM: Discussion of letter, R. Bolt to E. A. Gold enberg, dated 10/16/86, regarding Transient Tempera tures. The 85% limit of the flash point or droppir g point is really a general " rule of thumb". For c ils, due to fire safety considerations, 85% of the flash point would be the limit for the transient temperature. However, for the gr eases, l _ the 85% of the dropping point limit could l be' extended if the time interval were not to exceed approximately 30 minutes and providing leakage, if any, were to be conta ined. 004612 75) j
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