ML19254A782

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Responds to IE Bulletins 79-01 & 01A Re Environ Qualification of safety-related Electrical Equipment Inside Reactor Bldg.No stem-mounted Limit Switches or Solenoid Valves Planned for Use
ML19254A782
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 07/13/1979
From: Trimble D
ARKANSAS POWER & LIGHT CO.
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
1-079-7, 1-79-7, NUDOCS 7908170371
Download: ML19254A782 (46)
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$b ARKANSAS POWER & LIGHT COMPANY POST OF FICE BOX 551 LITTLE HOCK. ARKANSAS 72203 (50 4 371-4000 July 13, 1979 1-079-7 2-079-9 Mr. K. V. Seyfrit, Director Office of Inspection G Enforcement U. S. Nuclear Regulatory Comm.

Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

Subject:

Arkansas Nuclear One-Units 1 6 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 1E Bulletin Nos. 79-01 and 79-01A (Files: 1510.1, 2-1510.1)

Gentlemen:

In response to IE. Bulletins 79-01 and 79-01A, the fellowing is provided.

Attached is a summary of environmental qualification for both ANO-1 and ANO-2.

We do not now use or intend to use any of the stem mounted limit switches of the type discussed in IE Bulletin 79-01 or Automatic Switch Company solenoid valves of the type discussed in IE Bulletin 79-01A at our facilities.

Very truly yours, bY$f David C. Trinble Manager, Li nsing DCT/JTE/gp Attachment q908003 7'/

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t Summary Att0-1 Environmental Qualification of Safety-Related Electrical Equipment Inside The Rec tor Building During the time frame in which ANO-1 was designed, equipment procured, and constructed, no general environmental qualification standards existed.

Specifically, the bulk of ANO-1 design and procurement was complei,ed previous to the issuance of IEEE 323-1971. As such, the licensing requirements for ANO-1 did not require conformance to any specific environmental qualification requirements or the qualification of desig-nated Post Accident Monitors.

However, engineering practice during this period considered environ-mental qualification although not necessarily to the degree of sophis-tication we now place on qualification based on our evolution on appro-priate learning curves.

Environmental Qualification requirements for ANO-1 equipment was specifi-ed on the Purchase Order Specification when the equipment was procured.

Engineering judgment was the basic rule which prevailed when determining qualification requirements due to the lack of industry, etc. standards.

As such, we interprete the ANO-1 environmental qualification require-ments as those which were required on the Purchase Order Specification.

In responding to IE Bulletin 79-01 for ANO-1, we have researched our Purchase Orders and reported the specifications found there as the

" Environmental Qualification Requirements." Due to the massive documents requiring research, not all of the Purchase Order equirements have been identified.

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a Efforts are still underway to identify all Purchase Order requirements nd will be forwarded to you. However, even in those cases, we have iaentified qualification reports and have reported such, valess otherwise specified, all qualification test reports are available in the offices of Arkansas Power & Light, Little Rock, Arkansas.

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1. On Electric Cable All control, power, and some instrument cable was supplied by the Okonite Cable Compa.,y and uses Okonite insulation. Pre-aged cable samples were exposed to a total integrated dose of 2.8 x 107 rads and subjected to a LOCA environm'ent consisting of the following:

(1) Steam autoclave at 60 psig,153 C (07F) = 12 hrs. ,

with chemical spray of fla0H, fla2S0 2 3, KOH, Boric Acid.

(2) Steam Autoclave at 5 psig,107 C (225 F) = 7 days with chemical spray.

(3) Steam autoclave at 120 psig,177 C (350 F) = 10 hrs.

but no voltage under (3).

Test results are documented in Okonite Engineering Report fio. Il0E.

The remaining instrument cable is triaxal c sle supplied by Bcston Insulated Wire & Cable Co. (BIW). This cable has been certified ; y BIW to a temperature of 122F and 75 psia (75% relative humidity) for periods of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> once a year (during reactor building leak rate test). Radiation certification for a 40 year integrated radiation exposure of 2.8 x 107 rads at a radiation level of 100 rads /hr has also been verified by BIW.

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2. Valves and Valve Operation For The Containment Isolation System (CIS), Sample Containment Isolation System (SCIS), and The Decay Heat Removal System (DHRS).

Only valve actuators are classified as IE equipment. Two types are supplied in the above systems, Limitorque Type SMB and Rotork Type flAI . The Limitorque SMB's have been extensively tested with results summarized in Franklin Institute Reports F-C3341 and F-C2232-01.

Figure 3, pages 3-5 of the former (Attachment 1) shows the test envelope. In addition, the second report documents a 7-day test in which a borated spray with a pH of 7.67 was applied. Radiation n

exposure of 2 x 10' rads was applied to the A-C motor actuators.

The Rotork Type NAl operators are used in the CIS and DHRS are specially tested subinersible operators. Radiation aging to 2 x 108 rads was performed except for seals and "0" rinos which received 6 x 107 rads. Test report tio. TR.116 documents qualification. The test profile was:

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Time Pressure (psig) Temperature (F) 0 - 10 sec 0 - 80 140 - 300 10 sec - 5 min 80 300 - 380 5 min - 3 hr 67 380 - 330 3 hr - 5 hr 67 - 0 330 - 60 2 days delay, then second cycle 0 - 10 sec 0 - 67 60 - 280 10 sec - 5 min 67 280 - 380 5 min - 3 hr 64 380 - 330 3 hr - 6 hr 64 - 100 330 - 270 6 hr - 4 da 100 - 30 Approx 250 4 da - 36 da Approx 20 Approx 250 Water spray was applied after 5 min in both cycles of the test.

The operator was cycled 35 times during the test. After the second test cycle, the operatcr was completely submerged for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The operator functioned properly at the beginning, middle and end of the six-hour test.

A supplemental test on a Rotork operator is documented in Report TR-178, Rev. 1. This test consisted of 30 days of submerged operation in a solution of sodium hydroxide, boric acid and sodium thiosulfate with a pH of 10.5. Test chamber pressure was cycled 0-70 psig in 10 seconds twice and long term pressure was at least 15 psig. This test was run at 50F.

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3. Containment Cooling Units - The only Class IE parts are the main cooling fan motors and damper motors.

The bypass motors are manufactured by General Electric and have been verified by G.E. to operate properly at temperatures and pressures of 286F and 59 psig saturated steam for the required time of 4 sec.

The cooling fan motors are manufactured by Reliance and were tested by Joy Mar.ufacturing Co. as part of a Joy axivane fan unit. The test program is detailed in a report entitled " Qualification Test of a Fan and Motor Designed for Service in Nuclear Containment."

The prototype was pre-aged thermally and seismically. All materials of construction were selected to be capable of withstanding 109 rads. Radiation aging was not done. The unit was subjected to two sequential long term tests, each of which began with five temperature /

pressure cycles from ambient to approximately 80 psig/300F over a period of 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />. The first test was followed by 7 days at 15 psig/200F. The second test was followed by 11 days at approximately 20 psig/200F. Combinations of chemical spray including boric acid, sodium hydroxide, sodium thiosulfate and potassium hydroxide were injected individually and in combination throughout the entire long term test. Additionally, a series of short term transient tests were run wherein chamber pressure was raised from 0 to 80 nsig in 8-10 seconds. Motor internal pressure equalized with external pressure within 12 seconds for all modes of operation.

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4. Electrical Penetration Assemblies (EPA)

The penetration assemblies are manufactured by Conax and have undergone extensive testing as recorded in Conax Corporation Report No.'s IPS-48, ER-1097 and IPS-27. The prototype assemblies were subjected to a LOCA environment consisting of 325F, 85 psig with saturated steam and a chemical spray of 1900 ppm Boron for two hours as documented in Re,oort No. IPS-48. In a separate test (Report No. ER-1097), a thermal analysis comprised of exposure to 565F saturated stean for one minute was performed.

In a final test (Report No. IPS-27), radiation qualification of the conductors and sealant used in the assemblies was conducted. The test module first underwent a two-hour hold at 325F in a steam / air / environment followed by an integrated dose of 1 x 108 rz.ds . Afterwards, the test samples successfully passed a He leak test.

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5. Reactor Coolant Flow Transmitters The coolant flow transmitters are Bailey Model BY 3X41-A. The Bailey Transmitters were subjected to a LOCA test of ?4-hours duration followed by a gamma radiation test. The test unit was subjected to temperatures and pressures greater than 286F and 60 psig saturated steam for the first 8-10 minutes. The temperature and pressure were maintained at a level of at least 150F ane! 5 psig for the remainder of the test. The radiation environment consisted of exposure to 200 rads /hr until the total accumulated gamma dose exceeded 2 x 104 rads. Test results are documented in Babcock and Wilcox topical report 10003A-Rev. 4.

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6. Reactor Coolant Pressure Transmitters Two ty ,es of pressure transmitters are t: sed in the reactor coolant systc.a, Fisher & Porter Model 50Ef1 and Foxboro Model EllGH-liiM2.

Radiation Qualification of the Fisher & Porter Model is documented in Fr anklin Institute Report F-C2815. The test units qualified in this report were exposed to Co-60 irradiation for 53 hours6.134259e-4 days <br />0.0147 hours <br />8.763227e-5 weeks <br />2.01665e-5 months <br />, yielding a total integrated dose of 5.7 x 10 6 rads. Fisher and Porter has also verified that when radiation hardened transistors are substituted and teflon capacitors are replaced with radiation resistant high temperature capacitors as in Af;0-Unit 1, transmitter will function properly to at least a cumulative gamna radiation dose of 10 7rads.

LOCA testing is summarized in Fisher & Porter Report DP-2204-51 006 during which the units were subjected to the pressure-temperature profile shown in Figs. I and 2 of this report (Attachments 2 & 3).

The Foxboro Model was qualified by the same testing procedure used for the Bailey Model in Section 5 of this report. Maximum temperatures and pressures obtained during testing were 288F and 90 psig. The integrated dosage for the test was 2.4 x 104 rads.

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7. Reactor Coolant Temperature Element The temperature elements utilized are Rosemount RTD-17764. Qualifi-cation was accomplished as reported in Babcock and Wilcox Topical Report 10003A Rev. 4. The temperature test was performed during a calibration procedure during which the unit was submergea in a silicone oil bath of a inaximum temperature of 600F. Pressure test-ing was performed to a level of 3125 psig with helium for two minutes while mounted in a test apparatus simulating the actual equipment mounting. Submersion testing of the connecting head was achieved by pressurizing a test sample to a level of 80 psig followed by a 45 min immersion in water for evidence of leakage. All materials in the connection head have been selected for use at temperatures of at least 240F.

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8. __ Linear Neutron Flux Monitor (Excore)

The neutron flux monitors are supplied by the Bailey Meter Company and are used to monitor the reactor power level. Envi ronmental testing was accomplished by subjecting a sample unit to the following pressure-temperature profile. The ambient temperature was increased at approximately 50F/hr until the temperature of the detector reached 212F. After 911owing the steam-air mixture to stabilize, the pressure was increased to 150 psig by a nitrogen loading tank and maintained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Qualification procedures and results are detailed in BAW Topical Report 10003A, Rev. 4. These monitors are not necessary once the reactor is tripped,

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T !!'E QUAL. 00C. g RE0'D- PARAMETER SPEC. _ __,_ QUAL. METHCJ* ___,,Ef**R _,

, _Rf[ES ITEM EQUf *""iT CC50RIPTIC3 _

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Temp. (OF) 122  %# 3 3 tred samples Ccntral__C;tble 30.7 ,,_

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7 Radiation 2.8x10 rals._ 2.8x107 rads Polyviny1_ Chloride. Jacket _. _

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To m;i . ( F) 122 307 Sequential en aged _.sampics. ._

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  • ie, separate effects sequential etc.

This list is a comilation of items by compcnent. Co not list the sa::e type of component rnore than once. **Plcase attach typed lists of reference dccurents Use limiting envircn.wnt where core than one applies.

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CO PLNIT .NN',E : Arkansas Nuclear One - Unit 1 2 CC

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gg ENVIRC ? Erit (LOCATIO!J) D TIME QUAL. DCC.

ITEM EQu'!PEM CESCRIPTIC*4 REQ'D. P M ff:ETER . SPEC. QUAL. l'E Tl!03* REF** REMARKS 2 Centain=cnt Isolation Valve Short Tern Contain cnt _ _ . _ _ . _ _ _ _ Radistica aging .of. 2x1Q8 rads _.

Temp. ff) 286 370 S_p_qu.gg ia l 3. 4. s was_yerformed ical.s_and_0-fand0eraters a) Anchor / Darling Cate Valve Press. (psia) 74 85 Te s t

  • rings were aged with 6x10 Rotork_7fA1._Syo.Ipsser II

__ _l C 01r _._ _ .. _ 100% rads *Eorated cpray was.used....

3 ation 7 20tgjt.lfNA12 3 %3g dA N10 _Ja d_1_ in a searate test {ref 5) _

Chen. cce Note I ra t= 10. 5 *

)_ Ancho;-/D rling.Cate Valyc _ Shy t_ Tern _.__ Containment , _ _ _ . _ _ . __ ____ _ _ _ _ _ _ _ , ,

_ 6, 7_

  • Borated Spray was used_i,n Limitorque SMS 10 Temp. ( f) 2S6 34 0 Sequential a.separato test._(ref._7) _ _,

i Press. (psia) 74 120 Test

  • _ ._.
Rel. Ilum. 100'. 100'.

Radiation 2.Sx107 rads 2x103 rads -

l Chem. See Note 1 pji&67 __ _ _ . _ _ _ _ _ _ _ _ _ ____

d. _ . Vcla:t_f.ngincerir.g Catc._Valv' h _Icrn__

t _ __ Containment _ _ . _ _ _ . _ . _ _ . . . _ _ _ . _ . _ _ __ _ _ _ _ _ _ , _ .,_ _ _ _ __ _ _ _ _

7__

Ter. ,. (OF) 2S6 340 Sequent ia_1. . *Lorated Spray _was used in

_ _ _ _ Limiterc,uc.5M3 _D00-2 _ _ 6 . _ 7_. .

Press. (psia) 74 120 ._Tes t

  • a. separate test (re f. _ .7)

Limitercac SM3 - 000-5 _ _ _ _ _ _ _ _ __.

LimiJprge S'43 - 000 del. Hun. __,yg g.g _,, _.

g g3.,. _ _ _ , , , _ _ _ _ . _ _ _ _ _ _ . _. _ _ _ _ _ , _, _ _ _ _ _

Radlation ,Bx10..

7 rads _ _ _ 2x10 rads _

3 Chem. See Note I 'nH=7.67

-'- - Cu r j . . _ r . . . . _ i_- ;r_ f. . c . .---;

!!c n rv _t Comnany Containment 6,7 6

  • Borated Spray was used ir. a d) _, ,

Butterfl, Valve Short Tern T c:"p . ("f) 2S6 340 Sequential .t n *@ f m D Press. (psia)- - - 74 120 Tcst* ,

Limitorque SM3-3 Rel. Hum. 100. 1005 Radiation 2.8x107. rads 2x10S rads Chem. Sec Note 1 p!!=7.67

_a- --

._.=. _. .; ..-.

  • ic, separate effects sequential, etc.

This list is a conpilatico of items by component. Do not list the saa type of component more than once. **Pleasc attach typed iists of reference docurTnts Use limiting environment where uere than one applics.

s L

PLANT W.E:___Arkinsas Nucicar One - Unit 1 T3 03 N

E%'IR0hMENT (LOCATICN) m TIMt QUAL. CCC. n liEM , _ EQu!NENT DESCRIPTICN REQ'O. _ _ . PORN,ET ER SPEC. _ QUAL._ P.ETHOD* REF" REftARKS M e) IH z:ci Dahl (ITT) Batterfly Valve 6,7 *Borsted Spray was used in Cent _a in.m.en. t___

' Li_1+orcce SMB-3 Shcrt Ter: Ten. ("f) 796 340 Sequential a senarate test (ref. 7) _

Pre n. (psia) 74 10 ,,.c s t ,. _._

Hel. hun. __10 y

_ . _ . _ _ _ _ _ _ . . . ._ I w . -

RaJ iation 2x108 rads 2.Sx107 rads l

UC"- See Note 1 pE=7.67 _[_'___

_[___. _ . _ _ _ _ _ _ _ . _ _ .

_fl . lHr:ciDa.h1_(ITTlG1cycValv e _ _ . _ _ _ _ _ _._Containnent . __. __ _ . . _

6,7.. *Borsted Spray was used in ILimitorcue SMS-CCO-2 Short Ter= T ap . ff) 236 340 _ , _ , , , _ Sequential _ ,_

a,s_cparate test (ref. 7) ,,

I Press. (psia) 74 120 Tost * ^

  • Rel. Hum. 100'e 100'.

7 Radiation 2.8x10 rads 2x108 rads Chem. Sec Note 1 pH=7.67 3 Sanple Systcm Contain=cr+ Containment , _ _ , _ .

Sequential 6,7 *Borsted Spray was used in Isclation Valve Long Term Tem;) . ( f) 236 340 Te s t* a separate test (rc#. 7). _

EIU55' (psi 3) 79 120 f . _ ,_ . [VelanEncinceringCateValve Rel . Hm. 100*6 100% , _

7 3 dadia ti c9 2.8x10 rads 2xiO rads

- ..__ q.Liti J - - - crcue

- SMB-000-5 _

1 Chem. Boric acid spra" pH=7.67 l 4

Decar Heat Re~ oval Ictdcwn Lon;_I.crm Conta i r.r en t__ __ . _ _ _ _ . _ _ __ ..________.l.Radiationagingof.2x108 rads yalre_ Ten. ( f) 2S6 370 Sequential 3,4,5 l was performed,_ scals and Press. (ps' 74 85 Test. 7 C-rings _wgre aged.with.f>;10 1 lvg a a ngc[in;_ i Rel. H W- 1001 __10 0', rads.

7

, R;Lotk Tyne N\1 Radiatinn 2.Sx10 rads 2x108 rads *Borsted Spray was used in a e _ , _, _ _ _ _ _ _) __ . ._ _E. b E9'__. __ . - . __Bor!- _ ucid sprat _ pH-10.5._._._ _____._.____._ _.._ ...._._,. separate, test _,(ref,5)._ ,.

$ $ " t This list is a comilation of items by corr.ponent. Do not list the sace type of component n: ore than once.

use limiting envircnnent where nwre thaa one applies.

QcP e b $i fer cc docurents t

, . g .....a.

_ p e8 _ e _ e e > I'#

9 a _

f

  • "h #&, '\$ 0

IL AN T N/.".E : /rkar u s Vx lear Cre - Unit I ---

p c0 N

I Efr/IF.0MtENT (LOCATICN) C T!!!E QUAL. C0C. N ITEM EQUIPMEr.T DESCRIPT!C1 ___ ___ REQ'D- P/,RNjET ER SPEC. QUAL. METHOD

  • REF** RE" ARKS CO 5 Containment Cooling Leng Term Containment S Spray included combinations Unit _Agply Fa, Terp. ( F) 296 300 _ Sequential of borie ;g Sedium_Hrdro,xi_de

._Iry_J';1nu fa c tur er_Gorpany. css. bs M _

74 95 Test , , _ . , _ , , . _. , Sodium _ Thiosulfate and .

Model 42-26-1770 Rel . Hm- 1001 100's

_ _ .'otmic Hydroxide _ _ _ . _ _ _ .

Reliance Motor (TEAO) Radiation 2.8x10 rads 9x103 rads g 1 OfD{ '

Chem. ~

6 C::tni:=cnt_ Coo ling _L'u __ _ . Short _ Tem ___ ____Containmen. 9 Short term-no radiation Camper _ Operator .

Tnp. ( F)

._. 2S6 ____ . . . . __2 8 6 . __ __ _ . Test.. . _.. __

    • *
  • I 'P#*I ## N #

Press. (psla) 71,3 74 R"I U"- 1001 100%

_ _ _ _ . . _ _ Concral_ Electric._ _ _ . .

._. __. 5BQ5631Y Radiaticn - -

Chow 7 E!cetrical Peactratigo ter1 Term C.oc t a inm en t __ . . . . . _ _ . _ _ _ _ _ _ _ . .10,11,12._ _ _ _ _ _ . _ _ _

Tec'p . OF) 300 325 Separate

_ _ __ Asscnblics

!Conax2325?076 Press. (psia) S0 100 Effects _ _ _ . ___ _ _ . _ _ _ . _ . _ _ . _ _ _ _ _ .

Ccnu 2325-3077 Rel. Hu.. 1001 1001. Test Chemic _ solution was .1900_..___

Cqnax_23 5 4205 E3'II*lI"3 3x106 rads 1x103 rads __

pra Boron.

Chem.

Boric acid snra) Boric ccid_gpv_ _ _ _ . _ _ . . . _ _ . _ . . . _

1 8  ! Reactor Ccolant Flow Contain;;c"+

Transmitt er T er.p . ( F) 2S6 296 Scruential 13 Press. 1p513) 74 85 Tr st Eailev Meter Company Rel. Hum. 100". 1001 7

BY 3X41-A Radiation 2 dx10 rads 5x104 rads Che"- Sec Note 1 N/A , _ , _ - . . . _ . . . . . . . .. ..

This list is a cotr,ilation of items by component. Do not list the same type of component more than once. **Please *ie, separate ef fects sequcntial, etc.

attach type.1 ists of reference docu:wnts U .2 limi ting envircn. cut where core than one applies.

O e

T L AN! NN'C : Ariar.sas Nuclear One - Unit 1 5 CD

~

ON l- ENVIRONMENT (LCCATION) N

~

TIME GUAl. . 00C.

SPEC. MET:10D* REF" RfruRKS CO ITEM EQ'J:PMENT CESCRIPTICN REQ'D- PAR A".E T E R. QUAL.

N Short Tern Provfides._a. trip _ function __ g 9 _Qgac_ty_Ccolant__P_re s sure Ccntail ent ____ _._

Transmitter Tcao. ( f) 2S 6 31S Sequential 13 in the short tern. Should Press. (psia) 74 105 Test not see chc=tcal spray. ,.

Rel. Hun

  • 10 0 *= 100** Radiation equ:i1 to norral _... .

.__a) __ Foxhoro E11CM-1N'!2 Radiation 2.Sx10 rads! 7 2.4x10 rads 4 7,rgg3 n Fox 5cro E11CM-SAE1 Chem. geg sn c i l yf3 __

__b_) _ . Fischer and Porter SCEN Contain cnt. _ _ . . _ . _ _ , _. _ _ _ _ . _ _ _ _ _ _ . . _ _ _ . . _ . . . .. _ _ _ _ _ . .

Temp. ( F) 2S6 320 . Separate 14,15,16 Provides trip function Press. (psia) 74 90 Effects .hort term. Will not sco Rel. Hum. 100"4 100". Test -he=1 cal spray. Actual.

7 Radiation 2.Sx107 rads 1x10 rads ___ ______ _.

radiation . dosage .cqual _to N.'r z:..____

- r.orral_ operating _ dosage ___ ____

. __ .=r-- _ _ -- __ __ __ _ ___ ___

3 sctor_Ccolant____ _ Containment,_ . __ _. . . _ _ . _ _ _ _ _ . . _ _ _ _ _ _ . _ _

10_ . _ _ _ _ . . _ . . ...

Iemp. (o-} r 286 600F Separate 13 Siliconc rubber cicctrical Tceperature Element Press. (psia) 74 3140 Effects insulation was radiation tested 8

Rel. Hum. 100's 100?. Test to 1x10 rads.

j Rescro.mt RTD-177Gy Radiation 2.Sx10 7 r ds 1x108 rads Chem. See Note 1 N/A i

11 Linear Neutron Flux Monitor 13 v

_B_a_i l.e.m_M_e_t er Cornany m Te_nv_. _( f_). _ _ _ ._S

_ e c No t_ _e_ _2__. _21_2_ _ _ __ __ _ .. . _ _ _ _ _ . _ . . _ _ , _ _ . . , ._ .,

Neutrcn Flux Monitor Press. (psia) 165 _ , _ _ _ _ , , , _ _ _

Rel . Ilum- __ ._

100",

Ra di a t i oi.

Chem,

-]Ah _ _ _ _ . . . . _ . . . . . . . . . . . .

  • ie, eparate ef fects sequential, etc.

This list is a ccepilatica cf items by component. Do not list the sane type of coc.penent more than once. **Please attach typed ists of reference docwrents Use limiting ccvironnent where nr.re than one applier, b

p,c r_,. -.. , .

e - y c r ..y ., .

'p.

e . .j e ..#

No tes:

1. These devices are required for short terr. opera tion only (i .e. ,

within the first ninute af ter an accident), and therefore would not be affected by chemical spray.

2. The power range detectors are not required for LOCA protection.

These dectors are provided for protection against abnormal power excursions and are required to function within the first 15 seconds following an excursion. Therefore, because of the short-tern actuat-ing time and the protection afforded by the detector well, the power range det ectors will not be exposed to a hostile environment prior to perforning their protec tive function, o ', a '?

000 Q {

References

1. Okonite Eng,ineering Report No. 110F, " Nuclear Qualification Tests on Insulating Compounds."
2. Boston Insulated Wire and Cable Company letter, " Specification for Instrtenentation and Special Cable for Arkansas Power T, Light Company, Arkansas Nuclear One."
3. Rotork NA Equipment Specification Manual, " Valve Actuators for Nuclear Service."
4. Potork Technical Report TR 116, " Qualification Records for Type NA Valve Actuators (Nuclear Class IE),"
5. Rotork Rechnical Report No. NQR 030-TR178, " Submersion Test of Type NA Actuator."
6. Franklin Institute Report F-C3441, "Qualificatisn Test of I.initorque Valve Operators in a Simulated Reactor Containment Post-Accident Steam Environment."
7. Franklin Institute Report F-C2232-01, " Test of a 1.imitorque Valve Operator under a Simulated Reactor Containment Post-Accident S t eam Environment."
8. Joy Axivane Fan Test, " Qualification Test of a Fan and ?!otor Designed for Service in Nuclear Containment."
9. General Electric letter, December 6, 1971,
10. Conax Corporation Report No. IPS-48, Prototype Test Report of Penetration Assembiies."
11. Conax Corporation Repcct No. ER-1097, "Thernal Analysis of Steam Jet Impact on Penetration Enclosure."
12. Conax Corporation Rerort No. IPS-27, " Gamma II radiation of Eapton Insula-ted Conductors and n'olysuflone Scalant in Conax Electrical Feedthrough Assembly."
13. Babcock and Wilcox Topical Report BAW-100033, Rev 4, " Qualification Testing of Protection System Instrutmentation," . January, 1976.
14. Franklin Institute Research 1.aboratories Report F-C2815, " Qualification Te tr of Differential Pressure Transmitters linder Nuclear Irradiation"
15. Fisher 6 Porter I.etter, April 30, 1973.

16 Fisher 6 Porter lingineerin' Report *DP-2204-51-n06, "Special liigh Temperature Stean Application."

n.n -O LeQ) u U /_ i )

SUMMARY

ANO ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT INSIDE CONTAINMENT Equipment which is located inside containment and required to be ope ra tional following a postulated LOCA or MSLB is listed in FSAR Section 3.11.1, paragraphs A and B. The integrated LOCA Temperature - Pressure profile for ANO-2 is considerably more severe than the MSLB Temperature - Pressure profile defined in accordance with the CSB Interim Evalur. tion Mcdel .

The peak MSLB temperature exceeds the peak LOCA temperature f or a short period of time. However, heat transfer calculations indi-cate that component internal temperatures are lower for MSLB than LOCA due to the short life time of the high MSLB temperatures.

Therefore qualification of equipment to the LOCA spectrum is more severe than qualification to the MSLB spectrum and will justify qualification for MSLB.

The required qualification envelope is defined in Section 6.2 of the ANO-2 FSAR. Figure 6.2-8 shows the DBA pressure profile, Fig ure 6. 2-13 shows the DBA temperature profile and Figures

6. 2-26 and 6. 2-27 shca the spray pH envelope. Those require-ments are the u ao for all of the equipment although some equipment may roc have to operate during all phases of the accident (e.g., hydrogen reccmbiners and containment isolation valves). The required integrated lifetime radiation dose, in-7 cluding a LOCA, for all of the equipment is 3.3 x 10 rads unless oEierwise stated in the summa ry . Because of the conservatism O' a 90-U!U LiJ

of the calculations which determined the above requirements, addi-tional margin was not always a requirement.

Unless otherwise specified, all qualification test reports are available in the offices of Arkansas Power and Light, Little Rock, Arkansas.

A. Category I-A - Short Term Operability Required

1. Pressurizer Pressure Sensor - See B.6 below.
2. Steam Generator Pressure Sensor - See B.8 below
3. Valves and Valve Controllers for the SIS, CIS and CSS -

Only valve actuators are classified as IE equipment.

The safety injection tar? isolation valves do not have to change position and thus actuator qualification is not required. However, the actuators are Limitorque type SMB's which are qualified for post LOCA service.

Two *ypes of valve operators are supplied for containment isola tion valves. All CIS motor operators are Limitorque type SMB. These operators have been extensively tested on numerous occasions under cond tions much more severe than the ANO-2 requirements. Figure 3, page 3-5 of Franklin Institute Report F-C3441 (attachment 1) shc ,s the te s t e n-velope. In addition, Franklin InstitutO 7epart F-C2232-01 documents a 7-day test in which a borated s_ '_ay with a pH 8

of 7.67 was applied. Radiation exposure of 2 1 10 rads was applied to the a-c motor actuatort .

,, ,, 3 0 .{ b, [ 'l 4

The second type of CIS valve operator is a direct acting solenoid valve supplied by Target Rock Corp. (TRC). A prototype valve was irradiated tc 3. 3 x 10 rads and then subjected to a steam / air atmosphere with the f ollowing pr ofile (100% relative humidity) :

Time Pressure (psig) Temperature (F) 0 - 10 sec 0-70 ambient to 300 10 sec - 5 min 70-104 300 - 340 5 min - 3 hr 104 340 3 hr - 5 hr 104-0 340 to ambient 5 hr - 10 hr Repeat 0 - 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> sequence 10 hr - 14 hr 25 250 14 hr - 30 da 0 200 An additional test, f ollowing a similar test profile, was performed on another TRC valve of the same type with the addition of borated water to the steam (boric acid, sodium thiosul f a te and sodium hydroxide - pH 10,5 ) . Each test had a minor malfunct an, neither of which was directly a t tribu table to the adverse enviromnent. A careful re-view of TRC reports 1500 and 1827B concl led that the TRC valves are acceptable for containment isolation service after coils which may have been manufactured with a defect are replaced with coils manuf actured by a revisea process which eliminated the potential defect (kink in wire). These coils have been replaced in valves used at ANO-2.

re , 0 7CG G .. d L/J

There are no valve actuators associated with the containment spray system inside the containment (see B.12 below for a discussion of the contain.,ent sump isola tion valves) .

4. Electrical Cables and Pe.ietration Assemblies - See B.13 below.
3. .

B. Ca teg ory I-B - Long Te rm Ope rabilit/ _ Required

1. Containment Sump Level Sensors - These are float operated reed switch type units supplied by GEMS /DeLaval. Radiation exposure prior to environmental test was 2 x 10 rads. The un '.t underwe nt two tests, one long term and a subsequent short te rm test under more severe conditions.

Time Tem pe ra tu re (F) Pressure (psia) Ilumidi ty 0 to 10 sec 70 to 280 A tm to 63 100S 10 sec to 3 hr 282 59 100%

1 to 1-1/2 hr 282 to 150 59 to 13.5 100%

  • 1-1/2 hr to 14 da 150 13.5 100%
  • (During this period, the failure of a vacuum control valve and a heater caused the pressure to drop to 3 psia and the tem-perature to drop to 95F respectively at the 6 th and 2 96 th hour. The first incident lasted overnight and the second lasted 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.)

In addition to the above, the same sensor was exposed to steam and chemical spray as follows:

0lb t?

Time Tempe ra ture (F) Pressure (psig) Remarks 0 to 8 min 70 to 300 A tm t o 5 6 Steam and chemical spray (15,000 ppm boric acid with sodium hydroxide added to obtain 10.5 pH) 8 min to 4 hr .98 2 55 i5 Intermittent steam and chemical spray.

These results are documented, respectively, in Franklin Insti-tute Report F-C3834 2 nd Isomedix Report " Environmental Expo-sure of Liquid Level Sensor" dated 'ovember 1975.

2. vontainment Spray Headers - No Class IE parts.
3. Containment Cooling Units - The only Class IE parts are the main cooling fan motors and the bypass damper motors.

The cooling f an motors are manufactured by Reliance and were tested by Joy Manuf acturing Co. as part of a Joy axivane fan unit. The test program i; detailed in a report entitled

" Qualification Test of a Fan and Motor Designed for Service in Nuclear Containment".

nin 7Q7 C '_ l L //

+

The prototype was pre-aged thernally and seismically. All materials of construction were selected to be capable of withstanding 10 9 rads. Radiation aging was not done. The unit was subjected to two sequential l ong te rm te s t s , each of which began with five temperature / pressure cycles from ambient to approximately 80 psig/300F over a period of 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />. The first test was followed by 7 days at 15 psig/

200F, The second test was followed by 11 days at approxi-mately 20 psig/200F. Combinations of chemical spray including boric acid, sodium hydroxide, sodium thiosulfate and potassium hydroxide were injected individually and in ecmbination through-out the entire long te rm tes t. Additionally, a series of short te rm transient tests were run wherein chamber pressure was raised from 0 to 80 psig in 8-10 seconds. Motor internal pressure equalized with external pressure within 12 seconds for all modes of operation.

In addition, environmental qualification testing wa s per-formed on the bypass damper motor. The bypass damper motor is manuf actured by Baldor and is totally enclosed and fan cooled. The Baldor motor was radiation aged to 1 x 10 5 rads and was then subjected to randem bi-axial seismic testing in accordance with IEEE 344-1975. Due to the location of the bypass damper motors within the containment and since they will have performed their intended function prior to being subjected to post-LOCA radiation levels, radiation aging the motor to 1 x 10 5 rads is conservative.

023 2hb

rolicwing radiation aging and seismic testing, the motor was placed in the test chamber and the temperature was raised to 120F for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. After this soaking period, the motor was verified to be operable and was then subjected to a temperature / pressure transient frca 0 psig/120F to approximately 60 psig/300F within 60 seconds. The motor was operated for periods of 15 seconds at 30 seconds into the transient and again at 60 seconds into the transient. The steam flow into the chamber was terminated following the second f unc tional test and the test chamber environment was allowed to reach approxi-mately 0 psig/300F and the motor was again verified to be fu nc tional . These results are documented in Wyle Test Report No. 58315.

Since the bypass damper motors are only required to be functional for less than 2.5 seconds f ollowing a LOCA or MSLB, the environmental test of the Baldor motor adequately qualifies it for use as a bypass damper motor.

4. Containment Recirculation Fans - These are Joy axivane fans qualified as in B.3 above.
5. Hydrogen Roccmbiners - The hydrogen reccabiners are Westinghouse units which thermally recombine hydrogen and oxygen by the use of electric heating coils. The environ-mental qualification program consisted of a series of tests, some of which were run on a prototype reca biner and the 700 C (_l 'U L//

n

balance of which we re run on production ccmponents. Because the reccmbiners have no moving parts, this combined program was deemed acceptable.

The recanbiners are manualli energized some time after a LOCA. Conservative calculations indicate that the rec em-biners will not be required earlier than 3 days post LOCA (see FSAR Section 6. 2.5 ) .

Spray tests on a prototype unit were performed with sodium tetraborate and sodium hydroxide at a pH of 10. S te am and air were applied to raise the ambient temperature to 225F.

Ambient temperature is not a significant parameter as the internal temperature is above 1200F for all modes of operation.

Individual production components we re tested for radiation 8

resistance, 2 x 10 rads; long te rm temperature and pressure, 70 psig for four hours followed by 22 days at 20 psig/155F ambient; and a long te rm s pray te s t, 10 days at a pH of 10.

The test results are documented in Westinghouse proprietary report UCAP-7709-L, Supplements 1, 2, 3 and 4. These units are identical to Westinghouse units supplied to numerous utilities for use inside containments on at least 28 nuclear plants.

82B 00

_g_

6. Pressurizer Pressure Sensors - There are two types of pressure transmitters. The high pressure trip utilizes Foxboro EllGM transmitters. The low pressure trip utilizes Rosemount 1153-GA9 tran smi t te r s. Both the Foxboro model and the entire 1153-A series were qualified by sequential te s ting as documented in Uyle Test Report No. 26304 Rev. 1 and its corresponding supplement. The transmitters were irradiated rate of 1 (106) rads per hour to a total integrated dose of 3.7 (10 ) rads. Following irradiation, seismic testing was performed in accordance with IEEE 344-1975 ( bia::ial, randomwave form) over a frequency range of 1. 25 to 35 HZ in the horizontal and vertical axes. The seismic tendam motion for each horizontal axis was excited separately, b .t each one was excited simultaneously with the vertical axis. A total of five Operating Basis Earthquake (OBE) Fests and two Safe Sht t-down Earthquake (SSE) te s ts (all of thirty seconds durations were performed in each axis. Final testing consisted of exposure to a pressure / temperature profile of 100% relative humidity for a simulated LOCA as shown in Fig ure 3, page 21 of the above report (attachment 2).

During the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the tr _ profile the transmi tte rs were subjected to chemical spray composed of an H3 B0 3 - N OH mixture of pH equal to 11.

7. Pressurizer Level sensors - These are Rosemount 1153 HAS discussed above in B.6.

023 501

8. Steam Generator Pressure Sensors - These are Rosemount 1153 GA9 discussed above in B.6.
9. Steam GenerO fo Level Sensors - These Rosemount 1153 DA4 discussed above in B.6.
10. Containment Pressure Transmitters - These are Rosemount Model 1153 GA7 discussed in B. 6.
11. Containment Radiation Monitors (PAM) - At the present time radiation detectors are undergoing qualification. In the interim, monitoring of post LOCA radiation can be acccm-plished using shielding calculations discussed in FSAR 12.1. 2. 7 and handheld radiation detectors outside contain-ment at specified locations. This method (described in detail in our letters f rom Daniel H. Uil liams to J. F. Stolz dated August 31, 1978, and September 14, 1978) will remain in plant procedures until our permanent Post Accident Radiation Monitors are acceptably qualified.
12. Associated Valvas and Piping - The only Class IE ccmponents not previously discussed are the containment sump isolation valve actuators and two pressurized vent valves which are d-c Limitorques.

b23'

' L c.O9

The containment sump isolation valve actuators are specially tested submersible Rotork Type NA1. Radiation aging to 8

2 x 10 rads was performed except for seals and "O" rings which received 6 x 10 7 rads. Rotork Technical Report No.

iR 116 documents qualification.

The test profile was:

Time Pressure (psig) Temperature (F) 0 - 10 sec 0 - 80 140 - 300 10 sec - 5 min 80 300 - 380 5 min - 3 hr 67 380 - 330 3 hr - 5 hr 67 - 0 330 - 60 2 days delay then second cycle 0 - 10 sec 0 - 67 60 - 280 10 sec - 5' min 67 280 - 380 5 min - 3 hr 64 380 - 330 3 hr - 6 hr 64 - 100 330 - 270 6 hr - 4 da 100 - 30 Approx 250 4 da - 36 da Approx 20 Approx 250 Gater spray was applied af ter 5 min in both cycles of the test. The operator was cycled 35 times during the test. Af ter the second test cycle, the operator was comple tely submerged for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The operator functioned properly at the beginning, middle and end of the six-hour test.

0121 '03 e

A .iupplemental test on a Rotork operator is documented in Rott rk Technical Report TR-178, Rev. 1. This test consisted of 30 days of submerged operation in a solution of sodium hydro)ide, boric acid and sodium thiosulfate with a pH of 10.5. Test chamber pressure was cycled 0-70 psig in 10 seconds twice and long term pressure was at least 15 psig.

This t ist was run at 50F.

T ,e d-c Limitorque valves are used in the pressurizer ECCS vent line. They are required to be operable only in the event of a small break in order to allow a minimum flow through the core.

The actuator is a standard SMB except that a d-c motor is used. A limited test was run on a pre-aged d-c operator.

The operator was subjected to 340F f or 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> f ollowed by 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 330F, 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at 310F and 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> at 212F.

This is documented in Limitorque Corporation Test Laboratory Te st No. B-0 0 09 da ted 4-3 0-7 6. Radiation qualification of the d-c motor is 1 x 10 rads. This is acceptable because the source tenn for small LOCA's is 3 to 4 orders of magnitude lower than for a large LOCA.

13. Electrical Cable and Penetration Assemblies - Penetration assembly qualification has been documented in Amphenol Test reports #123-1247 and #123-2045 Rev. A.

' a 3, n

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  • d '1 4

Following irradiation to a total integrated dose of 1 x 108 rads, the test modules (EPAs) were subjected to a LOCA environ-ment of maximum temperature and pressure of 309F - 63 psig saturated air for 25 hrs. The pH of the steam vapor was adjus ted until a pH value of 10. 5 wa s obtained. Based on the test data for irradiation and LOCA the EPAs fully meet the qualification requirements.

Electrical power cable (low and medium voltage) and some control cable required to remain functional post LOCA were supplied by Anaconda Wire and Cable Company. Franklin Institute Report F-C3341 documents qualification of ener-gized cable under sbnultaneous exposure to radiation, steam and chemical spray. The test samples were pre-aged to 5 x 10 rads with thermal exposure to 250F for 7 days. The LOCA simu-lation profile was as follows:

Time Pressure (psig) Temperature (F) 0 - 30 sec 0 - 40 75 - 266 30 sec - 3 hr 40 - 105 266 - 340 3 hr - 6.5 hr 75 320 6.5 hr - 4 da 15 250 4 da - 13 da + 15 hr 5 210 Chemical spray of 3000 ppm boron as boric acid buf fered with sodium hydroxide to a pH of 9.5 was applied throughout the above LOCA test. Irradiation of 1 x 10 0 rads was applied u d !,05

during the LOCA test. Post test aging to simulate long term exposure was also conducted. An additional 5 x 10 rads was applied over 5 days at 75F and 0 psig. Then the cables were subjected to an additional 47 days at 200F/O psig and the same chemical spray noted above.

A subsequent test was perf ormed to IEEE-323-1974 standards including radiation exposure to 2 x 10 8 rads and exposure to 346F and 113 psig for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, with the spray pH in the 9-11 range. This test is documented in Franklin Test Report F-C4350-3.

The balance of the control cable and ali c oaxial cable re-guired for post-LOCA operation was supplied by Raychem Corp.

The control cable was subjected to numerous tests involving pre-aged ( thermal and radiation) and non-aged samples. Radi-ation aging was to 1 x 10 8 rads on some s amplc s . Transients to 370F/65 psig were accomplished. The cable was subjected to temperatures above 3 60F (maximum 370F) for twenty-four (24) hours, and pressures above 54 psig (maximum 75 psig) for twe n ty- five (25) hours.

Test duration was approximately 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br />. Specimens were irradiated as well as being immersed in a boric acid solution buf fered to a pH of 7-8. Raychem report EM#517A provides this doct. mentation. Raychem has also supplied

copies of tests run for other utilities and these are available either at the plant site or at Bechtel in San Francisco.

Coaxial cable was subjecFed to a very similar test progran.

Water pH was also 7-8. Peak values of temperature and pres-sure were on the order of 360F and 80 psig.

The cable was subjected to temperatures above 340F for eig h t (8) hours (maximum 413F) and continuously above 360F for over five (5) hours, and pressures abcve 52 :sig (maxim um 7P psig ) for over seven (7) hours and continuously above 58 psig for over five (5) hours. Results are documented in Raychem test report EM#518A.

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EtiVIRCTENT (LCCATICN) C TIM QUAL. DCC.

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!!E!! EquirMENT DECCRIPTICN _ FEQ'D- PARf,"ETER SPEC. QUAL. METHOD

  • REF** REP' ARKS O

! '. ;ilve opera t ers for SIS, Contairment

__a7_,__ ,,Qf ,a-J Css short Ter, Tc p. ( F) 2s9 MO secuentiat* 1, 2_ _ , _ _ _ , _

i t- c) Liettorque TvN Press. (psla) 60 17n ,,7g3 t ,_, . , , , , , _ , , , _ , , . _ , , , _ , , _

c'n n PCI H#- I CO *, 1001

  • Bo ra t ed spray wa s u sed. _._

Radiation 3.3x!c7 2xic8 rads in a separate test ( re f . _7 Chem. , p gg

_ _ ; _ _ lj a r.;c t_ R,oc k Corpo ra t i on Cr ' t r cr.t

!c o;ercid valves Short Term Tc:p. (#f) 39 340 Scquential* 3, 4 *BeratcJ spray was uscJ

, i .- Y .p a t t e rn Press. (psla) 09 120 Test in a separate test (ref.4)

Rel. Hum. j eg;; Inc, a Radiation 3 3x10' rads

_ _ _ _ _ _ _ .__. _ _3.3x10 7 Sodium Q droxide r.oric aci!

- Chen. g g,gg pH =I O . S Sodium Thiosulf.Itc Solutim u_ __ _ _ . _ _ _ _

__ L _ ._ . Cz tlir. e nJ En. L soi l a t i o n lor:' Tern Containmat . . _ _ _ _ _ _ _ . _ _ . _ . _ _ _ _ _ _ _ _ . _ _ . ____. _Radiatiert aging of.2xlM Va l re f e ra to rs Temp. ( F) :sg 370 Sequential

  • 5, 6 .. rads wa s perferiacJ, Seal s . . _

c p e ort,_b pdu ETC55- (PSIU) 63 s e, lest- _ _ _ .

a .d 0-rir!;s were :tged with p . ____, ECI HW- 1r++ 100'. _ , _ , ,__, _ _ _ ,

m in rads _

l Radlation _3.h107 h.108rp *r. orated sprgy .as.u<c4 in a Chem- eua n et pH sc" arete test same

~ % n u_.; al. _ ._=10.5

.soluucn as a,am(ref.6).u. _ _ . . . _ _ _ ,

,___'.____. I'ra.ir.arls r Dnt_ hire 'c' P er- Co;tain-ent _ _ _ _ Test y1s_run on a prc-aged

'

  • c.rgt,r* _

.(c nly_ fo t. Trm. ( F) 2S9 Mn _Jpquential 7 operator.

S

,__ 3-c Ri _itorme Tec S'm-0 scall breat-- Pre 5S- (PSIJ) 69 lIS Test __ . _ _ _ _ _ _ _ _ . . _ _ _ _ _

.I LCCA) Rel. U"'- 10um 100'. _ __. . . ____ _. _ _._

{ Ra dia tion. 3.3x107 lxto7 rads U"- PH=10,5(r:caical -

! Sis list is a corpilaticn of items by component. Do not list the sane type of component more than once. *ie, separate ef fects sequential, etc.

the limi tir,1 enst rcnwnt where core than one a,1 plies. **Please attach typed flits of leference docuzents

. +Fcs: Mcident Spray pH ranges from 8.9-11.

i e

TilN!BlHD 800i

FLA?ei T./ZE : 2 O

ENVIRCC:ENT (LCCATICN)

TIME QUAL. CCC.

ITEPI __ E'd'J!?!ENT DESCRIPT!CN PEQ'D- PAPf?ETER SPEC. GUAL. ftETHOD* REF** REfMRKS N

riectrie,I Pc-erration Long Term Centairnent w

.__s_qquer c ia l . _L ,9,_,_,__

lu c911:1_ M c nJ 2 iti:n.. Terr. ( F) 20 309 Test __ _ _ _

r 'er Press. (psia)

Lw!}x voitarc smo 3~ -naulc.

's cr iim voltage 7sn m : 69 M Rel Ilum-w ._ inns 200.

rij , vntttcc r4 .n G r, m WG Radiation gg/ jgg 8 T < t r r : p g iy . :c, y;c Chem. m, j g , % j ,,y pg_gn,s Nw+.e w _. -N_ a'

  • L_ jre cr an! Control Cable i ,,.:;_ T.c= nt . . _ . _ _ _ _ . _ _,_. Sequential 10. 11 , rests were donc on. pre _. -

.r aconh Nire and Cable Co. ._ _Temp.

Cont(a ir.g:F ) ,e t- .___346.__.___ .. Test _ _ . _ . _ . _ _ nged.sa ples...___

_ a. ) -entrol Cahle Press. (psia) 6 n. 125 Ethvler.c Propylene Rubber Rel. llum. loc 1 1001 in nt, tion, Radiaticn 3.3x10 8 2x10 rads

!b r.i1en .f ack et Chem.  !

g____. __ ._ _. _ _ , _ _ . _ _

p_I_l .l__OS__ no- i n a L _ _ _N !=_9 _11____

_ hl_ __. LP' cl.12;' PoicI_C1kle i onc Tem cont a i rne n t _ . , . _ _ _ _ _ _ _ _ ._, , _ _ _

_ Sequential 10, 11 icsts were done onyre- __

IF.tFvler.o Prepvlene Rubber Temp. (UF) 39 3M __Tes . . iged.sa ples trsul.1tinn. Press. (psia) c,9 125

._ U; p len .fac L et R0l IIUS- 100". 10 n'.

Radiation 3,3g n 7 2xin rads 8

Chem. p!!=10. 5 (nomi na l

_ _p_rp 9 _11 i -

. .!iun Uni t,cc Power rable __l en: Te m Centainr_ cat._ _ Scquent ia l 10 mil rests were done on pre .

EtScelenn Pronviene Rubber Ierp. ( f) 289 3:1.6 _ _ _ _ Test.._ ._ . _ _ . aged _ samples

.t m u t_ ice, Press. (psia) en 12s - ~ ~ ~ ~" ~

hlorinite.1ralvetlwlene Rel. lium. jno, a 10a, M et Radiation 3.3x10 7 y g8 g_ _ _ _ _ _ _ _ , _ , , _,

Chem,

_ _ _ _ ___. pil=10. 5 (nomina l p}I=9-11__ _ _

_ _ _ _ , _ _ _ , _ , _ . , . = _ , _ _ ____

Ihis list is a corpilation of itees by component. Do not list the same type of cocponent recre than once. *ic, separate ef fects sequential, etc.

Use limiting environrent where tsare than one applies. C b Dd ""

Uv/$] s co,,ng

DJ PLA?iT NidE: ~~

-3 B.7 CC ENVIRC: DENT (LCCATION) g TIliE QUAL. CCC. C ')

ITEM E_quirMENT CESCRIPTICl4 __ REQ'D. PAR / METER SPEC. QUAL. METHCD* REF** RE!! ARKS Containment Sequential 12 Radiation aging of lxt03 A .-en!M ,~t Centrol Cable f.ent Term layc !' c 1.f_2 ra. Tc7 (UF) 289 370 Test rads was donc on some rt..-trol Jacket Press. (psia) 69 80 7,,,

ac1. imm. 100

  • _ 10 C . __. __ ._ __._ __. _ . _ _ . . . . . . _. _ . _ _ _

Radiation 3,3y3n 7 Iv10 ro d s._

Chen. ,Hm10. 5 (nom i na l ) nu = 7_S _ _ _ _ . __. _ _ _ . _ _ _ _ .

7___ C u x i al_D b;s. . _ _ _ _ _ _ _ . . I.o r1 Term Containment Sequential 13 Temp. ( F) ;gg 370 yycjc3_ Corp. Ic:s3 coaxial ,.

cs w_ __ - -.- - _ _.

Press. (psia) go

.__ catt_e nt trol Jacket with 39 2 lavers of inmlation of E0l ' NS- 100". 10 T.

i:asolin R arJ Alkanc-Inide Radiation 3,3xio? __1x) 8g_rd ._ . . _ _ . _ . _ _ _ _ _ _ _ . _ . . . _ _ _ _ .

rH TE [.I .. __._ _____EI_10.51ronirg!; _ ,_ y 7-8 1

R H'drnten Reco+ i re rs  !.on .: Term Cortainrent Separate ,_ 1.j_,,_,_. Temper,ature_is unimportant as

':est inchouse l!vdrocen Ter p. ( F) 289 -

Effects the internal terperature is . , _

g, Press. (psia) cg 65 Th . abn : 1200 F for all. r.edes of EUI 100** _ 10 T* operation.. . , _ _ _

.b_'- .__ . _ _ . _ _ _

Radiation 3 3gn 7

2nn 8 rads Testin was done on individual Chem. .,1b 10. s tn_ogg nH = 10 c onp.c o e n t s .

9 gn .iin ent % p I.cvel t.on Tern i C or t a_i.nn nnt __

Sequential 15. 16 __.___._ _ ___ _

f=r e Ten. ( F) 289 K 0_ _ _ _ Jett _ _ _ _ _ _ _ _ _ _

c- poe T v,1 Press. (psia) 69 71 c1 W-3610; Rel . Ilum. 10n.a I c 0 *. _ _ , _ _ _ __ _ , _ _ , , _ _, , _ _ ,

Radiation 7 2x10 rads 3 Jx10 Chem. p!!alL i(n.gnin31 __plj _= _10. 5_ , _ _ _ _ _ _ _ _ _

  • le, separate effects, sequential, etc.

This list is a co pilation of items by component. Do not list the same type of component more than once. **Please attach typed lists of teference docu:nents Use limi ting environ.acnt where on;re than one applies.

m

&J&< .

05.9 3.T, FL A..I !./s;:E : )

1

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4.*-' m 4

- r-- ms EtiVI'107.'tEffi (LCCATICN) i TIME QU/,L .

e ITEM Equ!FMEtiT CESCRIPTICU CCC. c N!

REQ'D. PARNIETER SPEC. QUAL. ItETitCD* REF**

In R.r s s da per r:otors RE!%RKS m 2,5 . .,3 nd s c mty n ent 17

_ ge.,ucntial . Test conducted _on pre-blPr Nrt M3p Tc m. ( F) 39 300 Test ved rotor.

1/ 3 1:P 16n vac. 3 phice~ Press. (psla) 75 69

,..n t o r ICI E'- Functions before.being sub-10ai l oci - . . . . jected to LOCA enviro.went.

Radiation _

jyjn sra d s Chem.

Radia tic, equal to r,ormal . __.

_ _ _ _ _ ,n=In.r,(rnnin g

_ _ _ plant operating levels. __

Il Contain~. cat Rceirculation  !.cn; Term Containment 16

_ Sequential ._ S ray inclu.!cd cemhinatiens L .. ard.. Fan W

  • ors __ _ . _. 3 3C 53 - - - - 5C #
  • im b ivane I.ans Press. (r.sta)

Go o

.___:s__._...-__. - .- ---

lhdroxide, SoJinn Thio-cet :2_:r. 1770 EPI II"*

10 T. 100'. . _ , _ . . s ul fa t e a nd l'o ta s s iun Reliarce Motor (T!AO) 150/ Radiation 3,3_x I c ! _._ _9x3 08 ra'ds livd ro x_i de .

- U I'2L

_ . . . _ bN:!_b NE b____.--- __ _ - - - . - - - - - - - - - . -

,__1 2 lii Preunre Tranc .itters 10 - Tern Centainment Sequential 19, 20 Spray was a ll 3M3 - NaOH Fc 6,ra I 11r.'! Terp. (UF) 2g9 301 Tes t nixture Press. (psia) 69 71 Rel. Ilum.

~

100*. 100*.

Radiation 3,3xto? 3.7x10 rads Chem. p!!= 10. 5 (ncmi na ll _ pli = 11 17 I m - P r c u a_.r. c a r.J I'ressure ,

1ong Tern Con ta i r. .cnt Sequential 19, 20

)fevel - Transnit ters Tec'p . ('F) 289 331 Test

'n, m ,..-. :i;jels , 1153 ILE Press. (psla) 69 71 11M G39 Rel. Ifun. 100*. Irai f i u ra, Radi a t f or. 3.3x10 7 3.7x107 rads 1153 D u Chem. pH=10. 5 (nomi na l ' p!! = 11

.e- - = .: _ ._: : .. .= :

This list is a corpilation af iterr by compon7nt. Do not list the sace type of component rnore than once. s a t 1, e t Use limiting envircn.aent where rnre than one applies. . yr'{ chfecs{j 9

9

PLR I % E: _

EtWIRCfJ'ENT (LOCATION)

TIME c^

Q'JA L . CCr. ,

ITEM EquirMEr.T CESCRIPTION ' '

REQ'D- PAR /J'ET E R SPEC. CUAL. t'E T HCD

  • REF** REMARKS

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This list is a comilation of item by conyonent. Do not list the san? type of com.ponent c: ore t .an once. lje[{

eff Use limiting envirenrent where r.s;re than one applies.

s{ cQ r t alfr !c docurents O

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Franklin Institute Report F-C3441, " Qualification Test of Limitorque Valve Operators in a Sinulated Reactor Containnent Post-Accident Steam Environment."

2). Franklin Institute Report F-C2232-01, " Test of a Linitorque Valve Operator Under a Simulated Reactor Contairment Post-Accident Steam and Chemical Environnent."

3). Target Rock Corporation R port 1500, " Environmental Test Report on TPC Model 72V Type, 1" 'Y' Pattern Solenoid Motor Valve Per Provisions of TR Test Procedure Ifl383."

4). Target Rock Corporation Report IS2 /B, "Environnental Test Report on TRC Model 75G-002, 1" 'Y' Pattern Solenoid S tor Valve Soft Seated, liigh Pressure Version Per Provisions of TR Test Procedure Jl674."

5). Rotork Technical Report No. TR116, " Qualification Records for Type NA Valva Actuators (Nuclear Class IE) ."

6). Rotork Technical Report No. NQR 050 -TR178 "Subnersion Test of Ty pe NA Actuator."

7). Linitorque Corporation Report No. B-0009, " Qualification Type Test Report I.initorque DC Valve Actuators for Nuclear Power Station Service Conditions."

S). Anphenol Report I'123-1247 of " Loss of Cooiant Accident Testing of Unit ized lieader Penetration Assemblies. '

9). Amphenol Report l'123-2045 Rev. A "Special Prototype Radiation and Environrental (1.0CA) Tes t s o f Med i um a r.d Low Vol t a ",e El ec t r i c Penetration Assenbly."

10). Franklin Institute Report F-C3341 "Long Tern Testing of Electrical Cables Under SimultaneNs Exposure to Gamma Radiation, Stean and Chemical Spray."

11). Franklin Institute Report F-C4350-3 " Tests of Electrical Cables Subjected to Thernal Aging, Gamma Radiation, and a Loss of Coolant Accident Simulation."

12). Raychem Report #517A "The Effects of Radiation and Aging on Flantrol Insulated I' lire."

13). Raychem Report #51SA "The Effects of Radiation and Aging on a Coaxial Ca bl e . "

14). ilestinghouse Proprietary Report 1-l CAP-7709-L, Supplements 1,?,3 and 4,

" Electric Ilydrogen Recembiner for itR Containme ts.

15). Franklin Institute Report F-C3S34 " Supplementary Test of a Liquid Level Sensor Under Conditions Simulating a 1.oss-of-Coolant Accident witt in the Containment of a Nuclear Power Cenerating Station."

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16). Isonedix Report " Environmental Exposure of Liquid Level Sensor."

17). Wyle Labs Report d58315, " Loss of Coolant Accident (LCCA) Test on 3 Phase Electric Notor for Bechtel Power Corporation."

18). Joy Axivane Fan Test " Qualification Test of a Fan and Motor Designed for Service in Nuclear Containment."

19). Nyle Test Report #26304 rev. I " Environmental Qualification Test Report on Foxboro Model EllAil, F 6 P Model 50EP1041 and 13D2496 and Rosemount Model 1153CA9 Transmitters."

20). Supplement to Wyle Test Report #26304 Rev. 1.

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