ML17324A921

Qualification Test Program for Terminal Blocks,Nuclear Environ Qualification. Supporting Documentation Encl

ML17324A921
Person / Time
Site:	Cook
Issue date:	02/28/1982
From:	WYLE LABORATORIES
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Shared Package
ML17324A922	List: ML17324A921 ML17334A967
References
45603-1, 45603-1-RA, NUDOCS 8606030013
Download: ML17324A921 (106)

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Qualification Test Program for Terminal Blocks TEST REPORT 45603-'f NUCLEAR ENVIRONMENTAL QUALIFICATION Prepared for ON-M B PENIAL PROOUC P.O.Box 468 Bowling Green, Ohio 43402 (diA)ASK-V4~3 FE8., 1982 Prepared by WYLE LABORATORIES BbOb0300i3 Bb0529 PDR ADOCV, 05000315 Page No.XII"6 Report No.45603-I (:ification Plan No.45386-1 Page No.I REVISION A SCOPE This document has been prepared by Wyle Laboratories for Marathon Special Products, hereinafter referred to as the equipment supplier, for equipment used in various nuclear power generating stations.Ob ectives The purpose of this gualification Plan 1s to present the approach, methods, philosophies, and procedures for qual1fying Fixed Barrier Terminal Blocks (Series l500 NUC and 1600 NUC)and Power Stud Blocks (Series 142 NUC), assembled and/or manufactured by Marathon Special Products, for use in various nuclear power generating stat1ons.The devices shall be qualified for use w1th metallic terminal lugs (uninsulated) and housed 1n a metal enclosure with a gasketed door.Nuclear environmental qual1fication of any safety-related device to meet the intent of IEEE 323-1974 is usually a three-step process, i.e., 1)radiation exposure;2)ag1ng;and 3)design basis event qualification (seismic, and, for equipment inside containment, LOCA).The purpose of the first two steps is to put the sample equ1pment to be used for qualification into a condition that represents the worst state of deterioration that a plant operator will permit prior to taking corrective action, i.e., its end-of-qualified-life condition.

The next step demonstrates that 1t st111 has adequate integrity remaining to withstand the added environmental stresses of specified design basis events and still perform its safety-related functions.

It is 1ncumbent on the equipment supplier to assure that the components and materials contained 1n the equipment actually placed into service are the same as those qualified.

A 1 icab le vali f ication Standards S ec1f1cations and Oocuments o IEEE 323-1974,"IEEE Standard for Oualifying Class 1E Equipment for Nuclear Power Generating Stations" o IEEE 344-1975,"IEEE Recomended Practices for Seismic gualification of Class 1E Equipment for Nuclear Power Generating Stations" o NUREG 0588 o Reg.Guides 1.89 and 1.100 o."Beaver Valley Power Station-Unit No.2, J.O.No.12241-O.F.E.No.10080-C.O.No.6289, Ouquesne Light Company, Environmental gualification Testing of Marathon 1500 Ser1es Terminal Blocks," Letter, S.L.Chapin, Jr.(Stone 5 Webster)to H.Black (Marathon), dated August 22, 1980 WYLE LABQRATOAlES Huntsville Fac>hty FOfllJ I10t 2 her OCI It Repor".No.45603-1 Quali'.>tion Plan'No.<5386-1 Page No.2 REVISION A SCOPE{CONTINUED)

Applicable Qualification Standards, Specifications, and Documents Continued Document No.251/140,"Aliens Creek NGS Unit No.1, Class 1E Terminal Blocks Test Condition," Letter, J.Tana (EBASCO)to H.Black (Marathon), dated October 1, 1980"Beaver Valley Power Station-Unit No.2, J.O.No.12241-O.F.E.No.10080-C.O.No.6289, Purchase Order No.2BV-821, Terminal Block Qualification Testing," Letter, S.L.Chapin, Jr.(Stone Webster)to J.keglewitsch (Marathon), not dated Document No.AC-ES-MA-01,"Aliens Creek NGS Unit No.1, Class 1E Terminal Blocks, Revision Seismic Spectra," Letter, J.Tana (EBASCO)to H.Black (Marathon), dated October 14, 1980 Commonwealth Edison Environmental Accident Profiles and Seismic Curves, Letter, O.C.Lamken (Cemon-wealth Edison)to C.G.Poplin (Wyle), dated October 14, 1980 Commonwealth Edison Test Parameters for Joint Quali-fication Program, Marathon Terminal Blocks, dated September 11, 1980 Letter, O.C.Lamken, Comonwealth Edison, to G.Endicott, Wyle, dated February 9, 1981 E ui ment Descri tion The test specimens to be supplied by the equipment supplier shall consist of three (3)Terminal Block Assemblies, each consisting of the following items: o Two (2)Marathon Fixed Barrier Terminal Blocks, Series 1600 NUC, Type 1612929, 600 Volts, 75 Amperes, 12 Point Dimensions:

9"L x 2"W x 1-3/16"H Weight: Approximately 1 pound o Two (2)Marathon Fixed Barr ier Terminal Blocks, Series 1500 NUC, Type 1512929, 600 Volts, 75 Amperes, 12 PoiRt Dimensions:

8-1/4"L x 2"W x 1-3/16"H Weight: Approximately 1 pound WYLE LABORATORIES Huntavlll~F acii<ty fOQI 1109 r htv Ocl 10 Qual i Page No.XII-8 Report: No.45603-1 rtion P'lan No.45386-1 Page No.3 REVISION A SCOPE (CONTINUEO)

Equi ment Descri tion{Continued) o Two (2)Marathon Power Stud Blocks, Series 142 NUC, Type 1423589, 600 Volts, 3 Circuits, 1/4-20 Studs Dimensions:

2-3/4"L x 2-7/8"W x 1-3/4"H Weight: Approximately 1 pound o One (1)Type 4 NEMA Enclosure, Hoffman, Single-Door, Part No.A20H20ALP Dimensions:

20" x 20" x 6" Weight: 38 pounds o One (1)NEMA Mounting Panel, Hoffman, Part No.A-20P20 Dimensions:

17" x 17" Weight: 9 pounds o Cable conduit (2), metallic, 1-1/2" I.O., 90o bend, mounted to the top panel of the NEMA enclosure o Cable, Delco, f8 AWG, Teflon insul ation, 4-inch sections (not to be qualified, for test purposes only)o Terminal Lugs, ring-tongue, copper/tin plated, uninsulated, f8 AWG barrel: 1)2)For 1512929 and 1612929 Blocks:.190-inch hole For 1423589 Blocks:.270-inch hole The Terminal Block Assemblies shall be preassembled by the equipment supplier per the following:

Jumper wires shall be prepared, using comercially available crimping machinery, to assure uniform termin'al lug/cable connection.

Each end of each 4-inch cable section shall be stripped to bare wire per standard coomercial practice.Uninsulated metallic terminal lugs shall be attached to each bare end of each wire.The terminal blocks and power stud blocks shall be attached to the appropriate mounting panel, using commercially available bolts, nuts, and washers, as shown in Figure 2.WYLE LABORATORIES Hunlswllo Fscif<ty RSM ll00 2 An OCI 79 I e Page No.XZZ-9 Report No.45603-1 guali't~on rlan ao.4odub-1 Page No.4 REVISION A SCOPE (CONTINUED)

Equi ment Oescri tion (Continued) 3)Each Type 1512929 or 1612929 terminal block sha1l require ten (10)pumper wires.Each Type 1423589 power stud block shall require one (1))umper wire.The wires shall be installed on each block per the wiring diagram(s) depicted in Figure 1.When connected as shown, two (2)separate series circuits occur through each block.These circuits parallel each other for the ent1re length of each block (f.e., one circuit utilizes odd-numbered terminals, the other circuit ut11izes even-numbered terminals).

During installation, terminal screws/nuts shall be tightened fn accordance with the equipment suppl1er's recomnendatfons, as follow, to s1mulate actual installation procedures.

o Even number series circuit (reference Figure 1)shall be torqued to 25 (8,-5)1nch-pounds.

o Odd number series circuit (Reference Figure 1)shall be hand tightened until snug, then tightened an additional I/8 to 1/4 turn.4)The cable condufts shall be affixed to the top panel of the NEMA enclosure, using standard conduit mounting hardware.5)Two (2)'/4-inch drain holes shall be dr1lled fn the bottom panel of the NEN enclosure fn diagonally opposite corners.In addition to the ftems specfffed above, the equipment supplfer shall furnish the followfng:

o Three (3)"duney" NEHA enclosures shall be required to allow for accident (l.OCA)chamber ca11brat1on.

o'erminal lugs, ring-tongue, copper/tfn plated, uninsulated, N AWG, uncrfmped, quantity (TBD)**TBO~To Be Determined WYLE LlLBCAATONEI Hunlavllle FoCIIQ ryastoatH aetio l

Page No.XII-10 Report No.45603-1 Qual1'tion Plan No.45386-1 Page No.5 REVISION A SCOPE (CONTINUEO)

Qualification Se uence Qualification shall be performed in the following sequence.It is con-sidered that the radiation exposure and the aging effects on the equipment are cumulative and result in the same effects as simultaneous exposure experienced while operational in a nuclear power plant.Baseline Functional Tests Radiation Exposure Functional Test Thermal Aging Functional Test Vibration Aging Functional Test Sei sm1c Qual if ication Functional Test Accident Qual1fication Functional Test Post-Test Inspection Radiation prior to thermal aging 1s normally a more severe test sequence.Tests sponsored by the NRC and reported by Sandia Laborator1es in Report No.SANO-79-092CK have shown that radiation may sensitize some polymers, which causes them to degrade to a greater extent when followed by thermal aging.The report states that the mechanistic postulate is that radiation-cleaved bonds, in the form of radicals, react with oxygen to g1ve degradation products, including perox1des.

The peroxides are chemically weak links which are susceptible to thermal cleavage.This thermal perox1de cleavage gives more radicals which, in the presence of oxygen, lead to more degradation and more peroxides.

Test S ecimen Confi urations The test specimens shall be received by Wyle Laboratories in the configuration presented in Paragraph 1.3.At various stages of the test program, minor modifications to the 1niti al configuration shall be requi~ed.The following presents these modifications as they apply to the test sequence.Conf1 uration A Functional Tests V1bration A in Seism1c ualif ication and Accident ualif ication This designation refers,to the original test specimen configuration, as descr1bed in Paragraph 1.3.WYLE ULBOAATOAlES Huntsville Fwihty FOttl t le g le Oct 79

Page No.XXI-11 Report No.45603-1{,'ification Plan No.45386-1 Page No.6 REVISION A SCOPE{CONTINUED)

Configuration 8 (Radiation Exposure The jumper wires installed on each Terminal Block Assembly shall be removed and replaced by uninsulated metallic terminal lugs uncrfmped) which are identical to those used on the jumper wfres.Appropriate terminal screws/nuts shall be tightened to the torque values specified fn Paragraph 1.3.Conff uratfon C Thermal A fn Same as Configuration 8, except all mounting panels{with terminal blocks attached)shall be removed from their respective enclosures.

Each vacant enclosure and each terminal block/mountin panel combination sha cons u e a su asse WYLI LABORATORIES Huntsville Faciaty fan%1100 f her Oci l0 Page No.XII-18 Report No.45603-1 Oualification Plan Ho.45386-1 Page No.13 REVISION B 3.0 3.4 3.4.1 UALIFICATION PROGRAM (CONTINUEO)

The desired qualified life of the subject equipment is 40 years.The desired qualified life for components is also 40 years.Mhere 40-year qualified 1]fe for components is not demonstrated during the test pro-gram, a shorter qualified life shall be established and the component assigned a maximum maintenace-replacement interval no greater than its qualified life.Each component in the subject equipment has been reviewed for function and age-related failure mechanisms which could affect its function.A matrix, Table I, has been prepared which defines the components, manu-facturer ratings, materials, service conditions, and aging mechanisms.

A literature search of Wyle's Aging Library has been utilized to obtain auditable aging data.This data was used to define artificial aging procedures.

The aging mechanisms to be addressed for this equipment are time-temperature effects and humidity effects.Time-Tem erature Effects For many materials normal temperature conditions coupled with time create an aging mechanism known as time-temperature effects.The significance of these effects is strongly dependent on the type of material under consideration.

In general, materials may be classified in one.of three broad categories:

1)Organic materials (i.e., polymers, lubricants, etc.)2)Inorganic materials (i.e., ceramics, minerals, etc.)3)Metallic materials It can be shown that the deterioration due to time-temperature effects is insignificant for inorganic materials since these materials exhibit no permanent changes in geometry or properties for the time period under consideration (Reference I).Similarly, time-temperature effects are judged to be insignificant for metallic materials during the same time fr'arne.In contrast, it is known that time-temperature aging effects can result in significant deterioration of many organic materials.

As noted in Reference 2,"The exposure of polymers to the influence of environmental factors over a period of time generally leads to deterioration in physical properties." WYLE LABQAATQRIES Huntlvlll~Facility Page No.XII-19 Report No.456O3-1;ification Plan No.<=.386-1 Page No.14 REVISION A UAL IF ICATION PROGRAM (CONTINUEO)

Time-Tem erature Effects (Continued)

The present state-of-the-art will allow for artificial acceleration of the time-temperature effects associated with organic materials by increasing the temperature.

Therefore, the aging of these components shall be based on their organic materials.

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 (References 3 and 4): k A exp (-(Ea/k8 T))where, k reaction rate A*frequency factor exp exponent to base e Ea*activation energy k8 8oltzmann's Constant 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.Equation (1)can be transformed into a form which yields an acceleration factor.The acceleration factor is defined as tp/t1.The equation is: tp/t1 exp (-(Ea/k8)(1/T1

-1/Tp))where, t1*accelerated aging time at temperature T1 tg*normal service time at temperature Tp exp exponent to base e Ea=activation energy (eV)k8 Boltzmann's Constant (8.617 x 10-5 eV/%)T1 accelerated aging temperature

(%)Tp=normal service temperature (oK)The transformation of the reaction rate form of the Arrhenius equation to an acceleration form is accomplished as follows: ALE LABORATORIES HuntsvllQ Faclllty FORM 1109 2 llcv tkl~%

Page No.XII-20 Report No.45603-1 ification Plan No.45386-1 Page No.15 REVISION A 3.0 3.4.1 UAL IF ICATION PROGRAM (CONTINUFO)

Time-Tem erature Effects{Continued)

Life is assumed to be inversely proportional to the chemical reaction rate (References 3 and 4).In terms of life, and after converting to Napierian base logarithms, Equation (1)becomes: ln (life){Ea/k8){1/T)+Constant Equation (3)has the algebraic form: y mx+b where, y*ln (life)x 1/T m Ea/k8, constant for single dominant reactions b constant (3)(4)The constants, m and b, can be estimated by fitting the experimental data in the form of ln (life)versus 1/T into the above simple linear relationship.

The derivation of an acceleration factor is accomplished by taking the difference between any two points of the linear relationship.

Thus, if we substitute t for life into Equation (3), we obtain: ln t (Ea/k8)(1/T)

+Constant For the set of points (tl, Tl), Equation (5)becomes: ln tl (Ea/k8)(l/Tl)

+Constant For the set of points{tp, Tp), Equation (5)becomes: ln tp*(Ea/k8)(1/Tp)

+Constant Subtracting Equation (6)from Equation (7)yields: ln tp-ln tl (Ea/k8)(1/Tp)

+Constant-(Ea/k8)(1/Tl)

-Constant Simplifying and rearranging of Equation (8)yields: ln (tp/tl)*-(Ea/k8)(1/TI

-I/Tp)(5)(6)(8)~(g)W YLE LABOAATOAlES Huntawll~Faahty f0%I ll09 0 Ate Oct 19 Report No.45603-,1 lification Plan'to.45386-1?age No.16 REVISIO~A UAL'I CAT ION PROGRAM (CONT a'(UEO)Time-Tem erature Effects (Continued)

Taking anti log ari thms yi elds: t2/t1 exp (-(Ea/kg)(1/TI

-1/T2))Equation (10)is the same as Equation (2).(10)The acceleration factor (t2/t1)is the reciprocal of the time compres-sion factor, (t1/t2).Taking the reciprocal of Equation (10)yields: t1/t2*exp ((Ea/kg)(1/T1

-1/T2))Solving Equation (ll)for t1 yields: tl t2 exp ((Ea/kg)(1/Tl

<<)/T2))(12)Equation (12)can be used to derive the accelerated aging times for materials with known activation energies.In many cases, it is not practical to independently accelerate the time-temperature effects of each organic material.In this case a determination i m material has the lowest ac va on ener.e time-t rat r a acce era e ase u on the lowes activation ener for L." 9"" I material is accelerated to at least the equivalent degradation as that to be encountered during the qualified life.The conservatism of basing accelerated aging on the lowest activation energy is demonstrated as follows: The acceleration factor (t2/t1)of Equation (10)is greater than 1, for a constant activation energy, when the accelerated aging temperature T1 is greater than the normal service temperature T2.Mith T1 greater than 72, the term (1/T1-1/T2)is negative.This negative multiplied by the negative in the exponent results in a positive exponent.A positive exponent, in turn, results in an acceleration factor greater than 1.The acceleration factor versus (1/T)for various activation energies is plotted in Figure 45.Since the slope of each plot is proportional to the activation energy, per Equation (4), it is shown that a lower activation energy causes a lower slope.Thus, for a given accelerated aging temperature, different activation energies cause different acceleration factors, assuming that the normal service temperature is the same.This is demonstrated in the following example.WYLK ULBDRATQAlES Muntsvlllo Facility f0'IN 2 Hv Oci 1$

Page No.'ZZ-22 Report No.45603-1 lification Plan No.45386-1 oage No.17 REVISION A 3.0 3.4.1 UALIF ICATION PROGRAN (CONTINUED)

Time-Tem erature Effects (Continued)

EXAMPLE: Assume that a system consists of four (4)materials which have aact uatTon energies of 0.4, 0.8, 1.0, and 2.0 ev.It is assumed that each material is normally at a service temperature of 30OC for a quali-fied life of 40 years.It is further assumed that accelerated thermal aging shall be performed at 50oC.If the accelerated aging program is based upon the material with an activation energy of 1.0 eV, the following results: The relationship for the curves of Figure 1 is generated from Equation (10)and is defined as: t2/t1*exp (-(Ea/k8)(1/T1-1/T2))(13)Substituting Ea*1.0 eV, T1.*323oK, T2 M 303oK, into Equation (13)yields an acceleration factor of approximately:

t2/t1 es 11 (14)Thus, for a normal service time of 40 years (t2 40), the accelerated aging time from Equation (14)is: t1 40/ll 3.64 years (15)Therefore, using the accelerated thermal aging program of 50oC for 3.64 years, the equivalent demonstrated normal service times at 30oC for the other materials with activation energies of 0.4, 0.8, and 2.0 eV can be calculated using Equation (13).Thus, for Ea 2.0 eV, t2 3.64 exp (-(2.0/8.617-5)(1/323

-1/303))t2-418 years For Ea 0.8 eV, (16)(17)t2 3.64 exp (-(0.8/8.617 x 10-5)(1/323

-1/303))(18)t2*24.3 years For Ea*0.4 eV, t2 3.64 exp (-(0.4/8.617 x 10-5)(1/323

-1/303)t2=ga4 yearS (1g)(20)(21)WYLE LABORATORIES Htanisville F00slily FORM ill@2 ltev Otl lg E

page Ho.XZZ-23 Report.No.45603-1 r<-'cation olan Np, 45386-1?age No.18 REVISION A 3.0 3,4.1 UALIF ICATION PROGRAM (CONTINUED)

Time-Tem er ature Effects (Continued)

Thus, it is seen that materials with activation energies less than 1.0, upon which the aging program was based, are underaged by the accelerated aging of 50oC for 3.64 years.In order to assure the demonstration of a 40-year service time for all materials, the lowest activation energy should be chosen.Sasing the accelerated aging program on the lowest activation energy of 0.4 eV results in the following:

Substituting Ea*0.4 eY, T1*323ok, T2*303oK, into Equation (13)yields an acceleration factor of approximately t2/t1 2.6 Thus, the aging time is: t1 40/2.6~15.4 years (22)(23)Recheck1ng the other materials for adequate aging results in the follow-ing for an accelerated aging program of t1~15.4 years, T1~323oK, T2*303oK For Ea 0.8 eV, t2 103 years For Ea~1.0 eV, t2*165 years For Ea~2.0 eV, t2~1,768 years (24)(25)(26)Thus, it has been demonstrated that basing an accelerated thermal aging program on the lowest activation ener gy, when the baseline temperatures are ceraen, provides the conservatism desired.ENO OF EXAMPLE For components with time-temperature-related aging mechanisms, the aging was based upon ava1lable.aud1table aging data.Where adequate informat1on was available, a determinat1on of age sensi-tivity was performed to determine the qualified life goal.Those 1tems found to be age insens1tive are noted in the column entitled"Aging WYLK ULBORATORlES Huntly'Be Fsclaly fOQI 11N l Acr OC11$

Page No.XZZ-24 RePoxt No.45603-1 lification Plan No.45386-1 Page No.19 REVISION A 3.0 3.4.1 UAL IF ICATION PROGRAM (CONT INUEO)Time-Tem erature Effects (Continued)

Mechanisms, Time-Temperature Effects," Table I.A reference was made for the conclusion of age insensitivity.

These references are to para-graphs in this document which)ustify the conclusion, reference docu-ments, or other basis, such as inorganic materials.

For organic materials, a determination was made as to whether the material can be qualified for a 40-year life.This was done by using the normal service temperatures for the baseline temperature.

For each organic material, the applicable Arrhenius uation was evaluated, using the baseline temper ure, as emons ra e y e o ow ng example: The Arrhenius equation.Equation (3), is repeated: ln (life)(Ea/kB)(1/T)

+Constant (27)A substitution shall be made for the applicable slope'and constant and the equation evaluated, e.g., for laminate XXX, Item 1.1.6, Table I, for mechanical properties, the Arr en us curve s: ln (life)~14101.11669 (1/T)-24.3612882 For a baseline temperature of 135oF (57.2oC): T=57.2oC+273oC*330.2oK life=greater than 10,000 years (28)(29)(30)It is concluded that this laminate, XXX, can be qualified for 40 years at a baseline temperature of 57.2oC.Based on a baseline temperature of 135oF, which shall be experienced for over 99%of the desired qualified life, pro)ected lives of the remaining organic materials considered in this qualification program are: Material Pro ected Life Years Phenolic (Genal 4000)1.47 mi 1 lion Phenolic (G.E.12968)2.75 million Neoprene 42.2 The applicable Arrhenius equation refers to the equation which is most appropriate to the material application when more than one equation is known.For components with time-temperature-related aging mechanisms, the aging was based upon available auditable aging data, as noted in Table I.WYLE ULSORATORlES Huntsville FICil>ty FBI 1109 t Aev Ocl)'I Page No.XZE-25 Reccr No.45603-1 lification Plan No.45386-1 Page No.20 REVISION A 3.0 3.4.2 UALIF ICATION PROGRAM (CONTINUEO)

Humidit Effects 3.5 Humidity effects are not considered to be an aging mechanism for terminal block assemblies.

The ability of the equipment to perform within its relative humidity environment shall be demonstrated when safety-related functions are tested during the design basis accident.A in Anal sis 3.5.1 Time-Tem erature Effects The time-temperature effects can be accelerated by increasing the-temperature, as explained in Paragraph 3.4.1.A review of the materials indicates that the neoprene gasket utilized in the Type 4 NEMA enclosure will require the greatest amount of thermal aging.In order to avoid excessive thermal degradation of the terminal block specimens, the mountin panels (with terminal blocks attached)shall be removed from e r respec ve enc osures an erma a nde endent of the vacant enclosures.

This corresponds to on gurat on , escr e n aragrap It is desirable to thermally age the equipment in one (1)environmental chamber.Therefore, the maximum a in tern erature has been based on the lowest rated tern erature or neo rene em...a e 3.5.1.1 NEMA Enclosure Subassemblies 3.5.1.2 3.5.2 for the vacant NEMA enclosures, a review of the materials indicates that the material with the lowest activation ener is the neo rene Item 1.4.2, Table I, with a va ue o.e , ase on mec an ca properties (Reference 8).Calculations based on this value, the baseline temperatures presented in Paragraph 2.1.1, and a pro5ected qualified life of 40 years, yield a thermal aging time of 44 da s 1 056 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> at 1200C.Terminal Block/Mountfn Panel Subassemblies For the terminal block/mounting panel subassemblies, the material with the lowest activation ener is the NEMA Grade XXX laminate, Item 1.1.6, a e c as a va ue o., ase on mec an cal properties' erence.a cu at ons based on this value, the baseline temperatures presented in Paragraph 2.1.1, and a pro)ected qualified life of 40 years yield a thermal aging time of 18.5 days (443 hours0.00513 days <br />0.123 hours <br />7.324735e-4 weeks <br />1.685615e-4 months <br />)at 120oC Functional Test The equipment shall be converted to Configuration A, Paragraph 1.5.1, and functionally tested per Paragraph 3.2.WYLE LAQDAATOAlES Huntsville Fscmty Rm>>N?Ac Oct 19 item No.1.0 TABLE I.AGING HATRIX ITEH ANO HANUFACTURER Assembly, Harathon Term1nal Blocks, NEHA Type 4 Enclosure, Terminal Lugs, Cable Conduits (2)Terminal Blocks (2), Harathon Fixed Barrier, Series 1500 NUC (Nuclear Grade), Type 1512929, 12-Point, 600 Volts, 75 Amperes HANUFACTURER'S RATING EN V IROIB4ENTAL AND OPERATIONAL HATER I ALS ACTIVATION ENERGY (eV)APPLICATION TIHE-TEHPERATISE EFFECTS AGING HECHANI SHS RADI AT ION OAHAGE THRESHOLD 1.1.2 IIO-32 Insert, P/N 9743805 1.1.3 Connector, P/H 9064121 1.1.4]10-32 Masher-Head Hach1ne Screw, P/N 9743307 1.1.5 i4-40 Pan-Head Screw 1.1.6 Harking Strip,.060 Thick, P/N 9795012 1.1.1 Ho)ded Block, P/N 9783612 150oC 140oC Cellulose Phenolic, G.E.Type P-4000 Brass, COA Alloy 360 Brass, COA Alloy 260 Brass, COA Alloy 360 Stainless Steel NEHA Grade XXX Laminate 1.59(Ref 5)NAS(Para 3.3 1.21(Ref 7)2.7 x 106 (Ref 6)1.2 Terminal Blocks (2), Harathon Fixed Barrier, Series 1600 NUC (Nuclear Grade), Type 1612929, 12-Point, 600 Volts, 75 Amperes 150oC SAHE AS ITEN 1.1 1.2.1 Holded Block, P/N 9740612 150oC LEGEND: NAS Not Age Sensitive; X Ha r1al is sensit1 e to the ag1ng mechanism.

I teja Ho.TABLE l.AGING HATRIX (COHTINUEO ITEH AND HAHUFACTURER HANUFACTURER'S RATING EHVIRDQIEHTAL AND OPERATIONAL HATER IALS ACTIVATION ENERGY (eV)APPL I CAT ION TlHE-TEHPERATURE EFFECTS AGlHG HECHAH I SHS RADI AT lOH OAHACE THRESISL 0 1.2.2 NIO-32 Insert, P/N 9743805 1.2.3 Connector, P/N 9064121 S~as Itew 1.1 1.2.4 1.2.5 1.2.6 1.3 i10-32 Masher-Head Hachine Screw, P/N 9743307 l4-40 Pan-Head Screw, P/H 9784035 Harking Strip,.050 Thick, P/H 9795112 Termainal Blocks{2), Harathon Power Stud Block, Series 142 NUC (Nuclear.Grade), Type 1423589, 3 Circuits 140oC 150oC 1.3.1 Holded Block, P/H 9703613 150oC B.E.I12968 General Purpo Phenolic Holding Caapound 1.67(Ref 5)2.7 x 106 (Ref 6)1.3.2 1.3.3 Screw, Self-Tapping, P/N 9782508 Connector Asseebly, P/H 9513130 Steel NAS(Para 3.3 I)1.3.3.1 Stud, I/4-20 KC Thread, P/H 9711606 1.3.3.2 Connector, P/H 9513113 LEGEND: HAS Hot Age Sensitive; X~Ha ariel is sensiti Brass Copper, CDA Alloy 260~to the aging aachanisa.

V h Os'0.d d II II~~0 X H I H Ul~Ol W 0 Ul I TABLE l.AGING HATRlX (CONTlKUEO l TEH AND NAHUFACTURER Asseahly Enclosure, Hoffaan, HEHA l'ype 4, Single-Door, 20" x 20'6", P/H A20H20ALP Body, Door, Hinges, Hinge Pins, Clamps, Clamp Screws, Hasp.Staple, Gasket Retaining Strip, Feet Gasket Gasket Adhesive HANUFACTURER'S RAT SHG ENVSRONHENTAL AHD OPERAT lONAL Steel SSATERlhLS ACT 1 VATlOH ENERGY (eV)SSAS(Para 3.1.05(Rer e)Hot Safety Related APPL1 CAT 10N TlME-TEKPERATURE EFFECTS AGlHG HECHANLSW RAD1 AT lON DAHACE THRESHOLD 2 x 106{Ref 6)Paint Enclosure Hounting Panel.Hoffman, 17" x 17"~P/N A-20P20 Terminal Lugs, IB ASSG, Uninsu1 a ted Cable Conduits (2), 90oBend, l-l/2" 1.D.Acrylic Steel Hetallic HAS(Para 3.3 HAS Hot Age Sensitive; X~Ha rial Ss sensiti e to the aging aochanisa.

&H lh I Ol O Ch I

'I Item No.2.0 3.0 TASLE l.AGING HATRIX (CONTINUED ITEH AND HANUFACTURER Asseably, Harathon Teralnal Blocks, NEHA Type I Enclosure, Cable, Teralnal Lugs.Cable Condults (2)Assembly, Harathon Teralnal Blocks, NEHA Type 4 Enclosure, Cable, Terelnal Lugs, Cable ConduIts (2)HANUFACTURER'S RATING ENVIRONMENTAL AND OPERATIONAL SANE AS ITEH 1.SAHE AS ITEH 1.HATER I ALS ACTIVATION ENERGY (eV)APPLICATION TIHE-TEHPERATURE EFFECTS AGING HECNANI SHS RADI AT ION OAHAGE THRESHOLD LEGEND: NAS Not Age Sensltlvel X~Ha rial$s sensftt to the aging aachanIaa.

Attachment 4 to AEP:NRC:0775AE SCEW Sheet TC-13 Revisions gsslcAN E s Egg.+Ic AMERICAN ELECTRIC POWER SERVICE CORPORATION"OWER SYSTEM.th DATE>May 21, 1986 D.C.Cook Units 1 5 2 SCEW Sheet TC-13 Revisions I'ROMs TOs R.G.Heurich CEEQF gOOOOA The following changes were made to SCEW sheet TC-13, for both units, as a result of the NRC audit.1)Added Penn Union and Marathon as the manufacturer.

These are the two types of terminal blocks used at D.C.Cook 2)Added model numbers a)6000 series (Penn Union)b)1600 series (Marathon) 3)Changed system from"various" to"see attached list".The attached list contains all the device systems where the marathon and Penn Union terminal blocks are found.4)Deleted qualification document reference CEEQFP63K.

Test report lasts longer than what the TB's will see in an accident outside containment 5)Added qualification document reference CEEQF845C.

CEEQFP45C contains the qualification test report for Marathon terminal blocks.6)Added qualification document reference CEEQFP46.CEEQFg46 replaces CEEQFg45 for Penn Union terminal blocks.Conax report IPS-349 (846)includes radiation while Conax report IPS-339(sos'45) does not.7)8)For aging, changed qualification document reference CEEQFg177 to In'177A (Penn Union)and to k45C (Marathon).

For qualified environmental temperature,"384 F" was o ss added f'r Marathon Terminal Block.9)For qualified environmental pressure,"94.7" PSIA qas added for Marathon terminal block.10)For qualified environmental chemical spray,"2000ppmB pH 8.5-10.5" was added for Marathon terminal block.IHT R A-SY ST EM 11)For qualified environmental radiation dosage,"200 Mrad was added for Marathon terminal block.12)Changed qualification method from"combination" and"simultaneous" to"sequential" (for perating time to radiation) 13)Deleted the following outstanding items.a)"see Ref.63K" for operating time b)"see Ref.72" for chemical spray 14)Add CEEQFP45 as a supplementary information packet (along with CEEQFg45A).

The proce'dure 3 for the Marathon Terminal Block Qualification Test Report explains each environmental qualification category.All other changes are administrative.

R.G.Heurich Approved R.C.Carruth RGH:rd:52.27 Attachments cc.W/0 Attachments T.0.Argenta/S.

H.Horowitz L.F.Caso/J.V.Ruparel D.N.Turnberg/J.

R.Anderson K.J.Munson

~~P SCEW Sheet P TC-13 TC-13 Unit 1 2 Revision No.5 4 Date May 21, 1986 May 21, 1986 DONALD C.COOK NUCLEAR PLAIIT UNIT NO.1 DOCKET NO.SO-315 LICENSE NO DP~EQUIPMENT DESCRIPTION SYSTEM:$P~pe~lZ~/7 PLANT ID NO: g 9 COMPONENT:

('ABI.E.1'k RNIIN/IT cocM sANUFACTURER:

~)P<<<<<<~~'yet v+3ke<MODEL NUMBER:@(ptXO Cere&6)1(cpQQQCAd FUNCTION: chslE cocvNF.c T ION gl yc~/~c.c}roc/c-ACCURACY: SPEC: N1II DEMON.rVh SERVICE: ggcc'T7ikH' cl'sr LOCATION: o vys/oF Cs//fd/+mS~g FLOOD LEVEL ELEV:/I/~ABOVE FLOOD LEVEL:/IIW PARAMETER Opera0ng Time Temperature (F)Pressure (PSIA)Relative Humidity (%)Chemical Spray Radiation (106 rads)Aging (years)Submergence ENVIRONMENT SPEC.Z6.2 Q NA NA QUAL/"/mai~Q A/5')ZS+fOO gybe tf~c P)I'1.0"IP.aaoag(c>>1 r$R.5-c}5 cQ ZO b)zcm DOCUMENTATION REF.'PEC.QUAL.>io 4zC 1(}7'(" c')}16 ,]o p$5c r)lg(/o7$5'c b)$56 q)]7/')p QUALIFICATION METHOD g~~a~f}~~lg, t/CVI[lC f~cNII3cvtrcg c c>vI, nlrb OUTSTANDING ITEMS N 0/i/C<<fpV~l(d'-Documentation Relerences:

Notes:/, c.prlI p<<.,')l<<t I Z<<(o'I 1'I ll Ill<<q P<l (I<<t t jap IFB Z.FX(-Tag 4f~a1 6'9~ac cZ:-~(=~~v g.~y I<<<<]-~'(W<<A+a 4'\/I'v f 5.'~~c she eavtrocseatal quattftoattoa pare+taco provided oa this SCSV have been~btataed frou reAreooo doouaeots, weh as test repoc'ta aa4 the fata.The'Wsttadheuse Ovaere Croup (kOO}hu uadertckeo

~prodrsa to address poteattal wporbeate4 steaa releases outside ooatataseat as a result of a~ats steaa ltoe break ccith steaa deaerator o-tube uooovery.Opoa ooaplettoa of the VOO study these perueters asy requtre revtstoa.Coattaued operattoo of tbe D.C.Cook pleat peodtad ooeprettoa of this~CArt has bees tusbtfted hy letter Do.tapcaaccnrrsK, dated ludust 3, 19et (K.p.ttexteh (OCCo}to n.a Deatoa (VN:}J.~

Unit 81 SCEW Sheet: TC-13 Function: Control Cable Termination at Terminal Box Device Served~MEL P Device Served~MEL P FMO-211 FMO-212 FMO-221 FNO-222 FMO-231 FMO-232 FNO-241 FNO-242 FRV-210 FRV-220 FRV-230 FRV-240 WMO-711 WMO-713 WMO-723 WNO-725 WMO-715 WMO-717 WMO-721 WMO-727 IMO-910 IMO-911 QMO-225 QMO-226 CMO-419 CMO-429 IMO-255 IMO-256 IMO-262 IMO-263 IMO-270 17 18 19 20 21 22 23 24 25-26 27 28 30 31 32 33 35 36 37 38 41 42 43 44 49 50 61 62 64 65 66 IMO-275 IMO-360 INO-361 IMO-362 IMO-310 IMO-312 IMO-314 INO-320 IMO-322 IMO-324 IMO-330 IMO-331 IMO-340 IMO-350 IMO-210 IMO-211 IMO-220 IMO-221 IMO-212 IMO-222 INO-215 IMO-225 ICM-250 ICM-251 ICM-260 ICM-265 ICM-305 ICM-306 I CN-311 ICM-321 67 68 69 70 79 80 81 84 85 86 89 90 91 92 101 102 103 104 105 106 107 108 204 205 206 207 208 209 210 211 I

~+4~$x DONALD C.COOK NUCLEAR PLANT UNIT NO.2'.FQUIPMENT DESCRIPTION PARNhETER ENVIRONMENT SPEC.QUAL SPEC.QUAL DOCKET NO.50-316 QOCUh1 f NTATION REF.o QUALIFICATION METHOD LICENSE NO.DPR.7i OUTSTANDING ITEMS'os o~~>>'SYPH<:~6 PrQceSO fo COMPONENT:Cotta@

~Th'RHNAA()H MANUFACTURER:.

Q)~IfsraOW MODEL NUMBER.4i'h

~g e 4)l~~ioS FUNCTION:CON)(6C<

~~AT~Rgruat.I)t ()I-k ACCURACY: SPEC gA DEMON:)IA SERVICE:$6'8'~CD'I()czcr LOCATION: OuVSIt)F-CofJTArrh)4&i FLOOD LEVEL.ELEV:

HA ABOVE FLOOD LEVEL: HA Operating.

Time Temperature (oF)Pressure (PSIA)RetatiIre Humidity (%)Chemical Spray Radiation (106 rads)AalnC (years)Submergeace 4/'c,'p'Jriios~)A/5 g)3tc<)Iz<.7 e 4~too 25oo PPM 8 pR'f-Ie)paI o)~O b)goD;HA/rO/67/o('C 5C)e(.5g ca/77 ILIA 1)r I o Q Ect U&lT/At~COm8S<pm()Nr, NA NaNF.eA NOHF Aotd E NA J o~o oDocumentatlon Relereaces:

Notes:>>r.'39 poteattal wperbeate4 steaa releases outetde oootatoeeot as a result of~aala stesa ltoo break uttb stesa aeoerator 0-tube uooovery.Cpoo ooap4ttoa of the 000 study those parassters aay requtro revtetoo.Coattaued operattoa of the 0.C.Cock tlaat peodtog ooaplettoo of thts~ffbrt haa bees Juatifted hy letter IO.tat>IRCgorlSKo date4 tuCuat 3, I9al (K.t.itoateh (LICCo)to t, a, neatoa (IK)).~I;:~$jplomow4ncy

~<</oc mo,['io~P<<o'er<:h s/gg j50>2, ICC-.'fOg>>~

Mfa j Quoo~f=~col+The eovtroweotat Ouattfteatiea pareaeteoa prevtde4 oo this 5CCV have bees~htatoe4 free referoaoo deouaeats, weh as test reports ao4 the tain.The Veettaabouse ovoera Croup (NO)has uodertskeo a prodraa to address j)III W~a>o rr.vP oleo~me~>w<<J)O(oc.li4 w es 4 f~to 4'et+~+'te Ool,(<<ve~no4'c~g Lkioq)chic<<eh~I<<t (<<Wo goo)d~I-W, Co is.-!.n~I~Ix)8.v+sjaSjS Page-f Unit 82 SCEW Sheet: TC-13 Function: Control Cable Termination at Terminal Box Device Served FRV-210 FRV-220 FRV-230 FRV-240 FMO-211 FMO-212 FMO-221 FMO-222 FNO-231 FMO-232 FMO-241 FMO-242 WMO-712 WMO-714 WMO-724 WMO-726 WMO-716 WMO-718 WMO-722 WMO-728 IMO-910 IMO-911 QMO-225 QMO-226 CMO-419 CMO-429 IMO-255 IMO-256 IMO-262 IMO-263 INO-270 IMO-275 52 27~MEL P 17 18 19 20 25 26 27 28 29 30 31 32 34 35 36 37 39 40 41 42 44 45 46 47 52 53 64 65 67 68 69 70 Device Served IMO-360 IMO-361 IMO-362 IMO-310 IMO-312 IMO-314 IMO-320 IMO-322 IMO-324 IMO-330 IMO-331 IMO-340 IMO-350 IMO-212 IMO-222 IMO-221 IMO-220 IMO-210 IMO-211 IMO-21 5 IMO-225 ICM-250 ICM-251 ICN-260 ICM-265 ICM-305 ICM-306 ICM-311 ICM-321 MCM-221 MCN-231~MEL P 71 72 73 82 83 84 91 92 93 96 97 98 99 108 109 110 111 112 113 114 115 107 208 209 210 211 212 213 214" 215 216

\

Attachment 5 to AEP:NRC:0775AE Conax Electrical Penetration

, FOflM'074(C)

'NGINEERING DEPT.AMERICAN ELECTRIC POWER SERVICE CORP.1 RIVERSIDE PLAZA COLUMBUS, OHIO OAT COMPANY PLANT SHEET~OF~B~+~CK~~G.O.SUSJECT~~+

FORM OE4(c)'NGINEERING DEPT.AMERICAN ELECTRIC PONER SERVICE CORP.1 RIVERSIOE PLAZA COLUMBUS, OHIO OAT COMPANY PLANT SHEET r OF G.O.SUBJECT aa'PW aP'-3 P S Was'-az Q a C M~aP-F~/~Ms~a c~~~4~~~mw-rK~P~-WN S.Q~m~.AA,+PL~>SC.W~~C~M F AMERICAN ELECTRIC POWER Service Corporation l Riverside Plasa.f6(4)223-1000 P.O.Box l663I Colvmbvs.Ohio 43216-663l May 13, 1986 Mr.S.J.Medwid Conax Corporation 2300 Walden Avenue Buffalo, NY 14225 RE: D.C.Cook Nuclear Plant Penetration Equipment Qualifications

Dear Mr.Medwid:

Please provide a quotation to provide documentation which certifies the penetrations purchased on our purchase order 06878-821-1 (copy attached)to Conax teat report IPS-234.The purchase order was for equipment shroud penetration assemblies per Conax sketch 2SK-665-03.

These assemblies are similar to the containment penetrations proVided by Conax in that similar parts and pressurizing capability were provided with the shroud assemblies.

Test report IPS-234 is used to establish the environmental qualification of our containment penetrations.

If there are any questions, please let me know.Very truly yours, L.P.DeMarco Generation and Telecommunication Division Approved C.Carrut LPD:rd:50.90

'c.T.0.Argenta/S.

H.Horowitz L.F.Caso J.V.Ru arel urn erg.R.n erson K.J.Munson Attachment 6 to AEP:NRC:0775AE Penetration Wire Similarity AMERICAN ELECTRIC POWER SERVICE CORPORATION P owE'e svstE+DA Apr'26, 1986

SUBJECT:

Environmental Qualification of Kapton Insulated Wire Pene.ration Feed through Extension Wire FROM<TO: J.A.Pria CEEQF II'13 Penetration feedthrough extension wire at DCC Nuclear Power Plant includes pow'er, control and instrument cable.The feedh~trough extension wire is all manufactured by Haveg and supplied to us by Conax Corporation (the manufacturer of DCCNP electrical penetrations).

The feedthrough ertension wire is a stranded Kapton insulated wire.A stranded gIOAWG Haveg, Kapton insulated penetration ertension wire was tested under Westinghouse test report CWAPD-332 (CEEQF F13).Kapton feedthrough wires in Conax penetrations were also tested under Conar test reports IPS-234 (CEEQF III1)a penetration with 37$10 AWG conductors, and IPS-62 (CEEQF INI2)ten penetrations with conductor sizes ranging from tsIIO AWG to 1000MCM.Haveg Kapton insulated wires are part of the Conax Seal Assemblies (pigtails) and have been tested (24 ISI12 AWG, 20 tlI16 AWG, 8 III18 AWG)under Conar test reports IPS-409 and IPS-409.1 (CEEQFl/75).Foxboro instruments with Conar seal assemblies equipped with f16 AWG Kapton insulated wire instrument cable pigtails have been tested under Wyle test report 45592-4 (CEEQF tI149)~INTRA~SY STEM

Based on the results of test reports referenced above and the variety of the samples tested we, therefore, conclude that the power, control ana instrument Kapton insulated penetration

'xtension wire installed at DC Cook plant are environmentally qualified.

Approved Q+'Mr<K R~C~Carruth JAP:rd:50.21 cc.T.0.Argenta/S.

H.Horowitz L.P.Caso/J.V.Rupax'el" D.N.Turnberg/J.

H.Anderson

Attachment 7 to AEP:NRC:0775AE Foxboro Transmitter Test Configuration

~p)@AN 6 Qfgp AMERICAN ELECTRIC POWER SERVICE CORPORATION

+WKR SVSTE.DATEs SUBJECTS May 14, 1986 D.C.Cook Units 1 5 2 Technical Review of Differences in Tested and Installed Configuration of Foxboro Pigtails FROMM TOs K.J.Munson-EGS R.G.Vasey-NS&L During the recent NRC audit of the DCCNP Environmental Qualification Program, it was noted that the DCCNP installed configuration of the Foxboro instrument pigtail condulet per PDS-1/41 under RFC-01-2827 E 02-2828 was physically different than the tested configuration by the vendor in Wyle Test Report 45592-4.The tested configuration utilized a small 1/4" weep hole at a low point on a flexible metal conduit protecting the Foxboro instrument seal assembly pigtails.The veep hole was used to drain condensation near the instrument which may have accumulated inside the flex conduit during the simulated DBA test (see attached sketches).

The DCCNP installed configuration incorporated the use of a sealtite flexible conduit plus the sealing of both the entrance and exit of the flexible conduit with an RTV silicone sealant.No provisions for a weep-hole were made for the DCCNP specific design.The applicable plant design standard for the installation of the instrument, pigtails, flex conduit, splice box, and pigtail splices is shown on drawing PDS-1341 (attached).

The sealtite flexible conduit used in the installation is tradenamed Liquatite and manufactured by the Alflex Co.The plastic covering over the flexible metal conduit is made of a Polyvinyl Chloride (PVC)material.According to the manufacturer, the Liquatite flex conduit has not been environmentally qualified.

The hypothesized failure mode of the D.C.Cook configuration is that the PVC jacket on th'e flex conduit may fail during an accident near any elevated point on the conduit and allow steam to enter and condense.The condensation vould them"pool" at the conduit low points, thereby subjecting the pigtails to possible submergence.

The following paragraphs of this memo address this concern.IH T RA-SY ST EM Through conversations with Foxboro, it has been determined that the intent of the weep-hole was to avoid the"backing-up" of condensate from the chemical spray into the Integral Junction Box used in one of the two tested configurations.

The integral junction box houses a terminal block which is known to be susceptible to leakage currents when exposed to chemical spray solution.The weep-hole design was carried-over to the second configuration which was used at D.C.Cook.The second configuration incorporates an internal instrument splice to a Conax seal assembly.with no Integral Junction Box or terminal block installed.

Therefore, the"backing-up" of condensate near the instrument seal assembly in the D.C.Cook configuration was of no significant concern.Additionally, in both tested configurations the metal flex conduit looped back up after the weep hole and was routed down to a penetration at the bottom of the test chamber.The bottom end of the flex conduit was sealed which created a potential for the"pooling" of chemical spray condensate during the test.In this respect, the tested configuration is similar to what is hypothesized in the D.C.Cook Plant configuration.

The potential for pigtail submergence failure is much less of a concern for the D.C.Cook configuration due to the following reasons: 1).It is not likely that the D.C.Cook sealed flex conduit configuration would fail in such a way as to create a harsher chemical submergence environment for the pigtails than what was tested.The type of submergence in the speculated D.C.Cook case involves a steam condensate and is not associated with containment flooding conditions.

The steam condensate should theoretically be at a pH value which is less severe than the chemical spray exposure during the test.2)The Kapton-insulated pigtail wires of the Conax Seal assembly are individually protected by the application of a heat shrinkable polyolefin jacket.The heat shrink tubing jacket significantly improves the ability of the pigtail wires to withstand chemical submergence by adding a protective layer of material over.the Kapton insulation.

Where applied, the protective layer of heat shrink reduces the exposure of the Kapton insulation to the condensate.

The typical failure of Kapton insulated wire is due to an abrasion of the insulating material during installation combined with the effects of the chemical solution.The potential for abrasion or other mechanical damage of the Kapton insulation during installation at D.C.Cook has been essentially eliminated by the application of the heat shrink jacket.

1 5)The test report configuration, which exposed the Kapton insulated pigtails to the test chamber environment via the 1/4inch weep hole, demonstrates the ability of the pigtail wires to withstand harsh chemical conditions even without a protective heat shrink jacket.In conclusion, we believe that the omittance of the weep-hole in the flex conduit near the instrument in the D.C.Cook configuration does not have a detrimental impact on the environmental qualification of the instrument, seal assembly or seal assembly pigtails.In addition, we believe that there is no significant functional difference between the tested and the D.C.Cook installed configurations of the foxboro instrument pigtail conduits.Approved G&.X p R.C.Carruth K.J.MUNSON KJM:rd:50.95 cc.T.0.Argenta/S.

H.Horowitz L.F.Caso/J.V.Ruparel D.N.Turnberg/J.

R.Anderson J.G.Feinstein-NS 5 L R.Shoberg/W.

G.Sotos-I&C NW No.REE-86-07-1/Reslog 860501 1 2 0 Page No.I1-21 Report No.45592-4 PAGE NO 16 TEST PROCEDURE NO.45592-2 Revision A TRANSM TTER E"-C.RI"AL/NECHANICA INTERFACES 12.1 Reauirements 12.l.1"lectr'al Interfacina The Kapton pigtails protruding from the Conax sta'nless steel feed-through shall be protected using 1/2" flexible metal conduit.The conduit shall be attached to the transmitter interface by means of the conduit interface connector on each of the conductor seal assem-blies.The unattached end of the conduit shall be permanently affixed to the side of the mounting bracket assembly to minimize any delete-rious effects on the interface due to handling.CAUTION: When connecting the flexible conduit to the midlock cap, Do NOT allow the cap to rotate.Rotation will damage integ"ity of the midlock cap seal.The three (3)transmitters supplied with integral junction boxes shall be equipped with 18" of flexible metal conduit in the same manner as those f'ittings with the Foxboro-supplied Conax electrical conductor seal assemblies.

However, the conduit will not be installed until the pre-LOCA transmit er test setup.In addition, a 1/4" weep nole shall be drec in the condu'at, the lowest point o i"s arc to facilitate drainace of accumulated chemi"a'pray, steam condensat'on, etc., during the acc'dent simulation.

12.1.2 Mechanical In=erfac'nc Inlet supply pressure adaptors shall be pendently attached tc the transmitters usi.".g the Swagelok fittings suppl'ed by the manufacturer.

The supply'ines shall be made from 3/8" ski."'ess steel tu"'ng with one end flared and ecuipped with an AN lare'tting.Ti:e opposite end shall be debu"red and left untouched to acce"t the Swagelok compression

='-.g.12.2 Procedures 12.2.1 Electrical Interfacxn A.Direct Transmitter In ut 12.2.1.1 Cut a piece of 1/2" f'exible metal conduit approximatelv 18" in leng.h.12.2.1.2 Install two (2)st aight flexible conduit fit='ngs, one (1)on each end of the conduit.NOTE: The f'tting at the end farthest from the midlock cap should also contain a stra'n relief adaptor.N YLE LABORATORlES Huntsville F acti t ty fCRM 105~1 ttev Oct:9

Page t/o.II-22~Report No.45592-4 pg~QQ~f~c'0~9 1/2""-~~CcncU==./:2'MCUN HlG K5~4 KA?TCN)I oZGTA-M 18)1 16 ABG SGL:-D I I I f I I I/g//r~~r/3./4" rF.P;-:OX.~~geX

~~

~~Page No.II-23 Report to.45592-4 PAGE.'JO.L;A wc'cT PPClC<J m+JQ 4+v2 2 V (4 vatic a'4~6/32 ACL.J..JG I I I II I//I SCRE'iJ~'4~N Ar~~~1~~4 I~..:GURZ 2A.=:-C.RASCAL A.'i:KCHA:JACAL IiaJS~ALLATZQfAS

Page'io.Il-24 Repor't No.45592-4 Pace No.1VB Test Procedure No.45592-2 This page iaterticra3.'y lert blank.

Paae No.II-25 Report No.45592-4 This page intentionally left blank.WYLE LABORATORIES Huntsv>ll~Fac>ltty

~~Page t)o.ll-26 Report No.45592-4 PAGE NO 13 TEST PROCEDURE NO.45592-~V TRA."ISA TTER:-E".RI.=A, NECHAA:A:.

INTERFACES (Cont nued).2.1.3 Dr'll a 1/4"~eep ho'e approximatelv

." from the t=ansmit er inter=ac connectc NOTE: Re erence."-igure 2 for the remaining steps.12.2.1.4 Drill a 6/32 screw clearance hole in the mounting bracket assembly" as snown.12.2.1.5 Place a 4" piece o-Ravchem sleeving over the Kapton pigtails approx'-mately 16"-20" from the transmitter to ac-as a strain relief point.12.2.1.6 Carefully feed the pictails and C6nax stainless steel feedthrpugh into the flexible conduit.12.2.1.I Attach the conduit fitting to the Conax interface fitting.Before tightening the interface, rotate the conduit until the weep hole is positioned as shown.not distu"bed.

~~12.2.l.9 At tach the co ncu't to the mounting bracket assembly~sing 6/32" hardware (screw, nut and)ock washer)and a conduit mourting strap.Tighten tne stra'n relief adaptor around the Raychem sleeve installec in step 12.2.1.5.3.2.2.1.8 Tighten the interface connections and arc the flexible conduit around to the mounting bracket while insurinc t'".a the ECSA is 12.2.1.10 Photograph the transmitter to document the installation of the electrical interface protection.

12.2.1.11 Repeat s eps 12.2.1.1 through 12.2.1.10.'or each transmitter.

B.Intecral Junction Box Input 12.2.1.1 Cut a piece of 1/2" flexible metal corcuit approximately 1S" in length.12.2.1.2 Install two (2)stra'ght lexible conduit f ittings, one (1)on each end of the conduit.NOTE: The f't ing at, the end arthest from the.-box input should also contain a strain re'ief adaptoz.12.2.1.3 Drill a 1/4" weep ho'e approximatelv 9" from ti:e ansmitter irter-face connector.

12.2.1.4 Dzill a 6/32" sc e'>>clearance no'e in the mount'ng bracket assemb'y.12.2.l.5 Place a 4"='ece o.Ra:oh~a sleev'nc ove the Kacton pigtails approxi-mate'v 16"-20" from the transmit=er to act as a stra'.".relxe=oir.=.WYLE LABORATORIES Hur!Sville F acii<ly fOAM>05~7<ci Page No.I I-27 Report No.45592-4 PAGE NO 19 TEST PROCEDURE NO 45~9"-2 L>>TRANSMITTER:

EC RICAL')AC:-DY CA I 1.=RFACES (Continued) 1.I'~>>~~V Attach the conduit fi ting to the J-box input.Before tighteninc the interface, rotate the conduit until the weep hole is.ositioned a-the lowest point of the arc.1".2.1.7 Carefully feed the pigtails into the flexible conduit until thev erte the J-box.Install a noninsulated crimp spade lug to each lead and connect them to the+terminal within the J-box.12.2.1.8 Tighten the interface connections and arc the flexible conduit arounc to the mounting bracket.12.2.1.9 Attach the conduit to the mounting bracket assembly using 6/32" hardware (screw, nut and lock washer)and a conduit mounting strao.Tighten tne strain relief adaptor around the Raychem sleeve installed in step 12.2.1.5.12.2.1.10 Photograph the transmitter to document the installation of the electrical interface protection.

12.2.1,11 Repeat steps 12.2.1.1 through 12.2.1.10 for each transmi.er with integral junction box inputs.12.2.2 Nechanical Inter acin 12.2.2.3.Cut a piece of 3/8" stainless steel tubing and debur" each end.12.2.2.2 Flare one end and slip on a 3/8" stainless steel"B" nut.12.2.2.3 Bend the tubing as shown in Figure 2.12.2.2.4 Place the Swagelok compression nut.and fitting over the unflared end of the tubing.Connect the tubing to the remaining section of the Swagelok fitting mounted on tne inlet por=(s)of he transmit=er as shown in Figure 2 using standard Swagelok orocedures.

12.2.1~5 Position the tubing as shown in Figure 2 and tighten'~e fitting(s>

12.2.2.6 Attach the tubing to the mounting bracket assembly using 6/32 nardware (screws, nuts and lock washers)and a 3/8" tube mounting strap-2.2.2.7 Photograph each t ansmit er to document the installation of the mechanical interface.

12.2.2.8 Reoeat steos 12.2.2.1 through 12.2.2.7 fo" each transm tte WYLE UL8ORATORlES fpas i05<P Acr OCi 4 I Page l'{o.Jl-88 Report tto.45592-4 PAGE NO TEST PROCEDURE NO, 45"2-2"-8:-SS~RK/LEAK TES.Recui ements:-essure Tes" A"-ressure Test shall be per ormed"n each transmitter to, the ess e integrity of the seals.A"ressure medium of"", gas ous nitrogen shall be applied to the tzansmittez input pressure ports using a high-pressure regulator as shown in Figures 3 and 3A.The applied pressure shall be monitored using a 0.1%F.S.pressure gauge.During this test, voltage shall not be applied to the transmitter.

The applied pressures shall be supplied to the transmitters in the following manner foz a duration of not less than 1 minute: o The differential pressure transmitter shall have both pressure input ports pressurized simultaneously to the cozresponding overpressure listed below: Model No.Overoressure

{si)N-E13DM-ZIN1 N"E13DH-HT.:!1 N-E13DH<<X Hl 3000 4:"00 4:00 0 The gauge pressure transm-ters shall have their single pzessure input, port pressurized to the corresponding overpzessu e listed belo~: Model No.Cveroressure

{si)N-E11GM-HIE2 N-EllGH-ETN2 4000 4500 All body seals shall be leak checke=us'g chlorine-free bubble solu ion, and any seal leakage from a transmitter shall be evaluated by tne Lead Customer.Leak Test A Leak Test shall be performed, where specified, during a'1 Funct'onal.ests with the exception of the Baseline and Post-LOCA Tests.To ver-fy the pressure integrity of the seal, a pressure medium of dry gaseous ni tzogen shall be a"oed to he transm't er inpu oressure oort(s)using the Marotta System as shown in Figure 4.The appl'ed pressure shall be monitored usinc a 0.li F.S.pr ssure gauge.Du n tnis est, input voltage sha'ct be a=,"ed to the tra.".styit=er.

WYLE LABORATORIES Hunlaville F aCility f QRM 1054 F Rex OCI 7%

e'O.)5ORO hE SERIES PRESSURE 0 DZtt~PRESSURE TRANSXITTXR SEAL ASSEMBLY (BY MFR)NOTES)1~CONDQLET TO SE SUPP RTID tROX CONDUIT OR STRQCTQRt OTSRR TEM INSTRQXRNT 2~SEAL ENTRANCE C EXIT Ot CONDQLET NITH APPROVED RTV SILICONE CRQLKZNC COMPOUND 3, FOR TABULATION OF TRANS MZTTERS SEE SHEET 2 OF THIS EDS 4.MINIMUM OF 2" OVERLAP BETWEEN END OF HEAT SHRINK AND CONDUCTOR BEFORE SHRINKING 5, TERMINATE INSTRUMENT CABLE 5"-COUPLING SHIELD.2'0"-MIN 03 s"-SEALTITE CONNECTOR 418 4"-FLEXIBLE CONDUIT~8 403 (2)418 ANG KAPTON PIGTAILS MITH HEAT SHRINKABLE POLYOLEFIN JACKET (SY mR>RIGID.CONDUIT (IF REQ')4090'47o" q-'COO>LIBG LOCKNUT~~/VSCIIRI INCi/gaf j~q Q8I3 coNPqcEr doX rl+~FOR SPLlCK DETAIL'5 8.)MSTg.'EE'H,'BOFF THg.u@opt~l 5 STAQ PAR~.I fierce C.c eauI r III5Qlh7 Irg6 gQ54 lug I OCa'her/ah 8fwS Iw gFf'fg rO 8/~y Its FOR USE IN NUCLEAR PLANT ONLY I g~~eel-kF27 oa-2taf-INDIANA 8 MICHIGAN ELECT Co.D.C.COOK NUCLEAR PLANT PDS-1341-4 REVISION-4~I I-lO-85 ELECTRICAL PLANT SECTION PLANT DESIGN STANDARD FOXBORO NE SERIES TRANSMITTER CONNECTION DETAILS DR.5.K, CH.DATE-9-8)APP D AMERICAN ELECTRIC POWER SERVICE CORP COLUMBUS>OH.

I~EDS 343+SH 1 OF C~~~~QXXEtZFKXM~E&X<&EK'SG'KWXKRR o~~

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4 INSTRUCTIONS P REPARATION 1.Confirm that the kit selected is designated for the intended terminations (STP or STQ).Ensure that the cable and feedthrough conductor diameters are within the ranges specified in Table A of this PDS or the kit's label.2.Remove all felted asbestos or braided)acketing material from the insulation in the splice area.Splice sealing sleeve (part J)will not seal to braided or woven surfaces.3.Cut the end of the cable off square.Remove)acket material, tapes', fillers, shield foil and binders for a length of 3.5 inches from the end.';Cut the end of the feedthrough.wire off square.'ntwist.the vires as required'o install'ubing.

5.-Re@love'dirt;:grease and'other contMinants from the.eabl'e")acket...and all insulated conductor areas which vill make contact with components of the kit with a rag dampened, but not saturated, in an approved solvent such as alcohol or acetone..INSTAiLLAtTiON 1.Slide the conductor shims, Part R (not shown in Fig.A)over the Kapton insulated wires.Align with the insulation cutback.SHRINK ZN PLACE.2.When cable)acket shimf'art G,'is supplied, install shim over the multi-conductor coaoe)acket.Align to within l/4" of the cable)acket cutback.SHRINK IN PLACE.3.Slide the outer sealing sleeve, Part K, over the multi-conductor cable)acket.DO NOT SHRINK..4.'-Thread each Kapton'insulated conductor through.a leg of.the, Conductor Sealing Breakout, Part E.Ensure that the large open end faces the splice area.DO NO/SHRINK.~<1~/%<<<

I~~+~~p/8df>/g dggpdd'8CF SPCJ CPA'Pl(C&rC vr IREE (pg.gf/t//drfh..6f'dsg~

g~.g~y)5.Slide one splice sealing sleeve, Part J, over each Kapton'insulated conductor except for th~erain conductor.

DO NOT SHRINK.NOTE': Splice sealing sleeves are not used on the drain wire.6.Strip 1/4" of insulation from the end of the cable conductors, shield wire and feedthrough wires."~ZSF r~a~eiWC riser r Cr c.lNDIANA 8 MICHlGAN ELECT Co.D.C.COOK NUCLEAR PLANT PDs-/3+~-EL ECTRICAL P L ANT SECTION PLANT DESIGN STANDARD R V l I I.IO-85$48alo P'E f'/Rr/$I I41$%(/ac P Cy'~m O'C 7 PCm P<~~/sds y APP D,, DR.CH.55 DATE//'-8-F>AMERICA LECTRIC POWER SERVICE CORP.COLUMBUS)OH.

I-2-EDS-ZfZ-I SH.4.OF C

'l~~0 I a 7.Complete crimp connections between the cable conductors and the feedthrough wires using a Burndy YSV14 connector and the appropriate crimping tool.Ensure that wire is visible through holes in sleeve.Examine each connection area for sharp edges and protruding wire strands.Remove....

these with abrasive cloth or a file.8.Center splice.sealing sleeves, Parts J, over each connection area.SHRINK IN PLACEBO 9~Slide the breakout body over the splice sealing sleeves.Ensure that Parts J do not;protrude into the breakout legs'HRINK IN PLACEBO 10'enter the outer sealing sleeve, Part K, over the assembly such as that it covers the breakout and overlaps the cable$acket by 3" or overlaps the shim, when used.SHRINK IN PLACE.CAUTION: DO NOT FLEX UNTIL COMFORTABLE TO TOUCH.KIT REM6VAL INSTRUCTlONS If the installed kit must be removed, the following procedure may be used to prevent conductor damage: l."-Warm the" outer sealing, sleeve with,.a.torch or heat gun..Using.-t, a razor or sharp knive, score Part K longitudianally over its entire length at a depth of approximately 50 to 755 of its'hickness.

Do not scar cable acket.2~Gradually heat the entire surface of the sleeve.Using pliers, peel away sleeve along the cut area while continuing to apply heat.3~This process can be repeated for each component of the Raychem splice kit~however, care must be taken not to damage the cable.Remqye,as much of the old adhesive.as possible prior to.'installating.a.'jiew k'it'.", sCrt+~dn sy INDIANA 9MICHIGAN ELECT Co.D.C.COOK NUCLEAR PLANT PDs-tS g/-REVI SIO'11-10-85 ELECTRICAL PLANT SECTION PLANT DESIGN STANDARD~xgo+o Wa Sc-I~Ci Qrleze I r 7 FR cry~~~g yeda gP7A/c J'H.DATE/i-8'-f APP D DR.hMFPtP.'AM Pl clTRIC POWER SERVICE CORP.COLUMBUS,OH.

I-2 EDS-8<3.l SH.5 OF C

'RFC Nos.DC-01-2827

&I:-02-2828 A aicabae Instruments BLP" 110 BLP-lll BLP-aa2 BLP-120 BLP-121 BLP-122 BLP-130 BLP-131 BLP-132 BLP-140 QLp-141'LP-142 MFC-aaG" MFC-111 MFC-120 MFc-121 MFC-130 MFC-131 MFc-a4'0 MFC-141 NLP-151 NLP-152 NLP-153 BLI-110 BLI-120 BLI-130 BLI-140 r FFC-210 FFC-211 FFC-220 FFC-221~'.FFC 230'FC-231 FFC-240 FFC-241 IFI>>05.1'IFI-052 IFI-053 IFI-054 IFI-310 IFI-320 NPP-151 NPP-152 NPP-153 NPS-153 NPS-121 NPS-122 MPP-210 MPP-211 MPP-220 MPP-221 MPP-230 MPP-.231 MPP-240 MPP-241 MPP-212'PP>>222 MPP-23/MPP-242'~'~~it;~".:".i 8 i.f~.i'w, l.~ag~"r iv.t:,'~s j~~.'-'"ri i~>>'w~'.~I ae." i'(r'g~~~~'.'{4T" ic!.:.);;" e'~w.<~,~~~i~~,~~..4 FOR USE, IH NUcLEAR PLANT QMLf INDIANA 8 MICHIGAN ELECT Co.D.C.COOK NUCt EAR PLANT P DS-'l34.l-I ELECTRICAL PLANT SECTION PLANT DESIGN STANDARD REVISIO-I~1l-IO-8 FOXBURO NE SERIES TRANSMITTER CONNECTION DETAILS APP D DR.S.K CH DATE 4" I9-9$AMERICAN ELECTRIC POWER SERVICE CORP.COLUMBUS)OH.

I-2-EDS-)43-I SH.6 OF6

~'E Attachment 8 to AEP:NRC:0775AE Limitorque Issues eglCAN e LOCI"<c AMERICAN ELECTRIC POWER SERVICE CORPORATION

~K Pl"owe R s Ysteth OATEN April 18, 1986 SUBJECT>Donald C.Cook Nuclear Plant Unit No.2 Condition Reports 2-3-86-295, 310, and 323 Limitorque Internal Wiring Jumpers FROMM TO<D.E.van Deusen B.A.Svensson The subject Condition Reports (C/Rs)point out the use of jumper wires which were not qualified for harsh environment, and were located inside Limitorque switches.A review was performed by the Electrical Generation Section (memo from K.J.Munson to J.G.Feinstein dated 4/09/86)with the following key findings: 1.The unqualified jumper wires removed from 2-WM0-714,-724, and-726 have been identified as outdoor control wire taken from cable having item numbers 314, 315, or 316, purchased under specification DCCEE-159-QCN.

2.All three valves (green (A)train)listed in (1)have redundant back-up valves (2-WM0-718,-722, and-728, respectively) in the red (B)train.All of the jumper wires in the back-up valves were inspected and found to be fully qualified.

3.Valve 2-WMO-714 and its back-up (2-WMO-718) are located in an area which will not be affected by a HELB.These valves are to be removed from the Environmental Qualification List.It should be noted that the plant has replaced these Class IE jumper wires (specified in the subject C/Rs)with Class IE wires qualified for harsh environment.

Based on the study performed on a HELB outside containment (FSAR section 14.4), there are no breaks postulated in the section of the Steam Supply to Auxiliary Feedwater Pump Turbine piping which is located in the same compartment as valves 2-WMO-724 and-726.As such, these valves will not be subjected to the harsh environment of a pipe break during a postulated HELB outside containment.

INTRA SYSTEM

~~Based on this information, we believe that the Class IE jumper wires in question did not pose a threat to the health and safety of the public, nor did it create an unreviewed safety question as defined in 10 CFR 50.59.It is concluded, therefore, that this situation is not reportable under 10 CFR 50.73.D.E.van Deusen Approved by J.G.Feinstein, Manager Nuclear Safety&Licensing pm cc: M.P.Alexich/J.

G.Feinstein/R.

G.Vasey R.C.Carruth/L.

F.Caso/K.J.Munson J.C.Jeffrey/R.

L.Shoberg/W.

G.Sotos A.A.Blind-Bridgman J.D.Allard-Bridgman DC-N-6947 AEP:NRC:9470 MEMOSB:LIWJ.mern 4

~~ci l~gsCAN E Lf Cp AMERICAH EI ECTRIC PO>ER SERVICE CORPORATIOH OWE.R SYStE DAT&SUSJECT$FROMM TO<March 21, 1986 D.C.Cook Un i ts E Notice 86-03, C/R 2 03 86 295 MOV Operability with Control Pire K.J.Munson-EGS D.E.VanDeusen-NS&L~FILE p ppp p(GW AIT No.9445~~DA~~EQ Uncertaintie~

~pSsi~+X o~Gg-HUG IE Notice 86-03 identifies potential problems with the environmental qualification of the internal control wiring in the limitorque motor operators.

C/R 2-03-86-295 reports that a jumper wire was found during the MOV walkdown which was not listed as an acceptable environmentally qualified wire in my memo to the plant dated 1/9/86.The purpose of this memo is to determine typical valve operability in light of the control wire qualification uncertainties.

The control wiring in question is located completely within the Ltmitorque operator's limit switch compartment and is used to interconnect torque and limit switches.For D.C.Cook, terminal blocks are not installed or used inside the compartment.

Instead, field cable is directly terminated onto the switches with internal jumper wiring providing any additional interconnections.

The MOV control circuit voltage is ungrounded 220VAC or 250VDC.The postulated control wire failure modes are open-circuits, single-wire grounds and wire-to-wire shorts which, depending on the circumstances explained below, may cause inadvertent or incorrect operation of the associated MOV.Open circuits or high resistance connections are normally attributed to incorrect termination of the control circuit wiring and will generally not occur as a result of extreme environmental conditions, The internal wiring of an MOV is protected by the limit switch compartment cover from direct spray impingement during an accident which could theoretically loosen a control wire and create an open circuit.Circuit shorts and grounds (including both high impedance/leakage current or low impedance/direct short conditions) may hypotehtically occur as a result of gross electrical insulation breakdown or as a result of insulation leakage currents sufficient to cause misoperation of the valve control circuit.For the DCCNP control voltage levels, gross electrical breakdown could only occur on direct conductor-to-conductor or conductor-to-ground contact.Electric arc-over is highly unlikely at low voltage levels during normal operation of the MOV.Direct shorts are possible only where conductor breakthrough occurs as a result of'severe cable insulation IHT RA~SY ST EM 1

damage.Such damage could only occur when substantial insulation embrittlement due to high radiation doses combines with mechanical wear or when extremely high temperatures softens the ulation to the point of conductor exposure.Based on the ieve gene eneric properties of possible jumper wiring at DCCNP, we bel that this type of extreme degr adation should not occur under specified accident conditions.

The configuration of the individual control wires within the limit switch compartment greatly minimizes the probability of the ln vl ndividual conductors achieving contact with grounded components

~W or o r other exposed conductors.

Most jumpers are less than a fe inches long, especially between limit switch termination poin s.t Excess wire is normally kept to a minimum with the majority of wires taking a direct path between terminal points thus r'educing the likelihood of electrical contact.The general construction of the limit switch and torque switch insulating blocks also reduces the exposure of possible electrical contacts with receded terminal points.Although conductor breakthrough should not occur, sufficient insulation degradation may cause changes in the individual wire insulation resistances for severe environments.

While such changes could result in the wire's inability to adequately pass a high voltage withstand test performed as part of the qualification (e.g.IEEE-383), these changes are unlikely to cause significantly low conductor-to-conductor or conductor-to-ground Insulation Resistance (IR)values necessary to cause MOV failure or misoperation.

The physical wire separation mentioned above creates long leakage current paths which effectively insure that low IR valves will not occur.Further reducing the probability of MOV misoperation during an accident is that a large percentage of installed jumper wiring is environmentally qualified wire as explained in my memo to A.A.Blind-DCCNP dated 1/9/86.(Attached)

Additional justification for safe continued operation is the fact that the DCCNP MOV control circuit voltages are ungrounded.

Ungrounded or"floating" voltage systems typically allow a single conductor to ground fault without having an impact on the control circuit.Only when two simsultaneous conductor-to-ground (i.e.conductor-to-conductor) faults occur would there be a chance for misoperation of the MOV.The possibility of spurious operation of MOV's due to short circuits is also minimized by AEP~s design philosophy of double breaking of the control circuit.The double break concept requires control contacts to be located at both polarities of the actuating circuit.With this configuration and ungrounded control voltages, a short circuit to ground of a single internal jumper wire of the MOV cannot cause a spurious operation of the valve.

Finally, it should be noted that in the unlikely event that wire degradation effects MOV operability, remote valve repositioning can be accomplished from the valve control center.Manual actuation of the motor contactor can adequately reposition the affected valve assuming the VCC is accessible luring the post-DBE.K.J.Munson KJM/ris/47.3 Approved C.arruth w/Attachments cc.T.0.Argenta/S.

H.Horowitz L.F.Caso/J.V.Ruparel D.N.Turnberg/J.

R.Anderson J.G.Feinstein/D.

VanDeusen-NSKL R.F.Kroeger/D.

Cooper-QA IE Notice 86-03/AEP:NRC:9419 File EpicŽA.pc~AMERICAH ELECTRIC POWER SERVICE CORPORATIOH

+wan svstE+January 9, 1986 sublfcTc D~C~Cook Units 1 Limitorque Valve M.0.Jumper Wiring Environmental Qualification J.gunson A.A.Blind-D.C.Cook We have been notified of a potential unresolved problem at other utilities with the environmental qualification of jumper wiring inside the limit/torque switch compartment of limitorque motor operated valves.The normal procedure during installation at DCCHP was to use a qualified wire, however this practice was not sufficiently documented; Therefore, some uncertainty exists as to the type and manufacturer of the internal jumper wiring.Since all qualified components are required to be fully documented, an inspection of the jumper wiring of all limitorque valves that are on the EQ list is necessary.

The inspection involves noting the gauge of the wire and the type of insulating material.It is suspected that most jumper wires will be a solid/l12 Awg wire with an asbestos braided material surface taken from the older control cables having item nos.3092, 3093, 3119 through 3123.Exceptions to this wire type and descriptions need to noted.Pending the outcome of the inspection, it may be necessary to replace the existing jumper wiring with a single known qualified wire which can be better documented for qual i f ication purposes.Me have identified 78 HOV's (14 inside containment) in Unit 1 and 72 MOV's (13 inside containment) in Unit 2 which are EQ listed and need to be addressed.

Attached is a listing of these HOV's including plant locations.

If you have any questions, please call me at extension 2158 or+'p'JN/ris/43.95 Approved////i,i"li i,/R.G.Carruth T.0.Argenta/S.

H.Horowitz J.R.Anderson/D.

N.Turnberg L.F.Caso/J.V.Ruparel R.Kroeger/D.

Cooper J.Feinstein W.G.Smith, Jr.-Bridgman J.Allar d-D.C.Cook-,A%a-sv s T a CC I Requested is the inspection of these valves and an estimate of the manhours it will take to replace the existing jumper wiring with a single known qualified wire if necessary.

AMERICAH EI.ECTRIC POWER SERVICE CORPORATIOH

<pl C A>t I.4 q~"'e P O~E R~yS DATKt SUSJKCTc April 9, 1986 D.C.Cook Units 1 E 2 Limitorque MOV Walkdown C/R Nos.2-03-86-295/310/323 FROMM Tac K.J.Munson-EGS J.G.Feinstein-NS&L The jumper wires removed from 2-WM0-714,-724,-726 have been identified as outdoor control wire taken from cable having item nos.314, 315 or 316 purchased under specification DCCEE-159-QCN.

These are a 4, 7 or 12 conductor cables having 7 strands of 818 Awg.wire with a nominal 20 rails of clear polyethylene insulation and 10 mils of color-coded PVC conductor jacket material applied directly over the polyethylene insulation.

The wires and cable are rated for continual use at 75 C.The cables were purchased N-grade from either Triangle/Plastic Wire 5 Cable, Essex, Collyer Wire 4 Cable or Paige Electric.Three individual jumper wires were taken from each valve and were used in an identical wiring application as follows: Point-to-Point Wir in A rox.Len th a)46 to 56 b}53 to 58 c)43 to 57 4 to 5 1/2 inches 11 inches 6 1/2 to 8 inches The three jumper wires are shown marked-up on the attached wiring drawing which is typical for all three valves.Jumper wire denoted a)above connects two limit switch contacts at the low-side polarity of the control voltage bus.Jumper wire denoted b)above connects a torque switch contact with a limit switch contact near the high-side of the control voltage bus.Jumper wire denoted c)above connects a torque switch contact with a limit switch contact at the high-side of the control voltage bus.See the attached copy of valve circuit elementary dwg.which is typical for all three valves.2-WMO-724 and 2-WMO-726 are green (A)train valves which feed essential service water to the 2-AB and 2-CD emergency diesel generators, respectively.

These valves open automatically when the EDG is running or can be opened by control switch.The redundant back-up to these two valves are red (8)train valves 2-WMO-722 and 2-WMO-728 which provide essential service water to the 2-AB and 2-CD EDG's, respectively.

All four valves are located in an HELB area pipe tunnel north of the 2-CD EDG.2-WMO-714 is a green (A)train exit valve from the 2E containment spray heat exchanger.

The redundant back-up is a red (B)train valve from the 2W Containment Spray Heat Exchanger.

Both of these valves are located just east of the passenger elevator at elev.621 ft.in the aux.buiI'ding at approximately 30ft.north of an HELB area pipeway which is on the opposite side of a poured concrete wall.2-WMO-714 and 2-WMO-718 are not in an HELB area and are to be removed from the list of equipment required to be environmentally qualified.

During the walkdown of valves 2-WM0-718, 2-WMO-722 and 2-WM0-728, no unqualified jumper wires were found.Therefore, the opposite train valves of 2-WM0-714, 2-WMO-724 and 2-WMO-726 were fully qualified with no jumper wire qualification uncertainties.

Additionally, all of the above valves are located outside containment and could be subjected to a HELB which peaks at 230 F and would have a duration of only seconds.Radiation doses are low and are not a concern.According to one wire manufacturer, polyethylene is extruded at temperatures above 300 F which can be considered the approximate melting point of this material.This is in agreement wi$h the)ypical temperature specifications for polyethylene of 75 C (167 F)normal continuous operation, 90 C (194 F)emergency opgration for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> per year over several years and 150 C (302 F)short-circuit operation for very short durations in seconds or less.Therefore, it is highly unlikely that the polyethylene insulation on the found jumper wires would melt and expose their conductors when subjected to an outside-containment HELB temperature environment.

K.J.Munson KJM/ris/49.23 Approved.'-Carruth w/o Attachments cc.T.O.Argenta/S.

H.Horowitz L.F.Caso/J.V.Ruparel D.N.Turnberg/J.

R.Anderson IE Notice 86-03/AEP:NRC:9419 File (w/attach.)

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• I/>!<nmeler ad<uslmanr ol lurq<.e Sh>li~<ns<<eS I'<" I.J<re i O.ur~I><ole!Is carve p~IIs I<urn d~.n>,,-Mna,w HOW LIMITORQUE OPERATES QUE bility.Basically, it is a d device.It controls all shipboard water-tight any position or location and can readily be adapted to existing cquipmcnt.

It can bc actuated by many power erw>rem ir>cludin<l electricity, hydraulic pressure, air, or 0 Limitorque is hr more than a valve actuator.It also controls and limits the opening and closing travel ot the valve.Proper valve seating is very important in automatic valve operation bccausc most valves are damaged when thev are improperly seated, or by meeting a foreign obstruc-The nccts I be mcl source this m Lochai aW 8XKAW MHK SREAX,,-~VT~>Z E CO~%A SalMac~10 TEMPERATURE AT 10 SECONDS IS 230'F LsJ OC I/O Ls J 6 la J I h.4C O 4.HAIN STEN STOP YAl.VK CLOSES 0 0.10.20 t=sh t<(]2 4 6 Tlt'1E AF'TER BRrAK (SECONDS)Figurc 9-27"cst Stcam Enclosure Hafn Steam~L<nc Greek (Elencnt 3), Pressure-8 10 AMERICAN ELECTRIC POWER Service Corporation 1 Rivcrsidc Plaza i'614)223-1000 P.O.Box 16631 Columbus.Ohio 43216-6631 May 6, 1986 Mrs Joe Drab Limitorque Corporation 5134 Woodall Road Lynchburg, Virginia 24506

Dear Mr Drab:

As we'ave previously discussed, one of the latest environmental qualification uncertainties involves the Use of"T-drains" on Limitorque actuator motors~Needed from Limitorque is a clarification on the qualification requirements for the use of T-drains.Specifically, the following concerns need to be addressed:

1.In which Limitorque environmental qualification test reports were T-drains installed on motors?2.What are the T-drain requirements with respect to inside versus outside containment building valve motor operators?

We understand that Limitorque haa qualified actuators with and without T-drains installed in the motors.Do you" consider the T-drains to be an absolute qualification requirement or a design enhancement, especially since some actuatora were qualified without T-drains?If required, do you recommend that all actuator motors have T-drains installed, even where T-drain holes are not available?

4.What are the specific technical reasons for the installation of T-drains?Can there be plant-specific actuator configurations in which T-drains are not required.For example, would it be possible for the condensate to drain off through other avenues.

Please provide us with as much detail as possible in you" response If you have any questions, give me a call a.(6,14)223-2158'.J.unson Assoc.Engineer AEPSC Approved C arrut KJM:rd cc.T.L.D~A~J~M~:50.62 0.Argenta/S.

H.Horowitz R.Caso/J.V.Ruparel N~Turnberg/J.

R.Anderson A.Blind-Bridgman Allard/L.Van Ginhaven-Bridgman Marracco-MED

Attachment 9 to AEP:NRC:0775AE Cable Acceptance Criteria

AN f gPcp AJAER)CAH ELECTRIC POWER SERVICE CORPORATIOH DATSUN Nay 16, 1986 P++Esl SvS~~+susyan<Insulation Resistance on EQ Instrument Cables FROAI>TDR M.J.Finissi R.L.Shoberg/E.

K.Legg, Jr.As a result of the recent NRC audit on our Equipment Qualification (EQ)files, we must document the minimum insulation resistance on our EQ instr'ument cables to ensure that the leakage current will not adversely affect the current loop during an accident.The Electrical Generation Section is supplying the I&C Section with the insulation resistances such that the effects from the leakage current can be determined.

Attached is a table containinig the minimum insulation resistances gather'ed from the appropriate EQ test reports.This listing of instrument cables is not complete and as the information is obtained, it will be forwarded to the I&C Section for review.If you have any questions, please call.M.J Finissi Approved/!~ii'J..Anderson Approved i".+/A4&R..Carruth NJF:rd:52.9 cc.T.0.Argenta/S.

H.Horowitz L.F.Caso/J.V.Ruparel D.N.Turnberg/J.

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