Text

Updates 820611 Response to NRC 810526 Safety Evaluation & SA Varga Re Equipment Qualification
	ML17334A444
Person / Time
Site:	Cook
Issue date:	11/03/1982
From:	Hunter R; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton; Office of Nuclear Reactor Regulation
References
	AEP:NRC:0578H, AEP:NRC:578H, NUDOCS 8211090146
	Download: ML17334A444 (196)
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ACCESSION NBR;8211090146 DOC ~ DATE: S2/11/03 NOTARIZED!

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Cook Nuclear Power Plant~ Unit 1~ Indiana L

50 316 Donald C ~

Cook Nuclear Power Plant~ Unit 2~ Indiana 8

5000316 AUTH BYNAME AUTHOR AFFILIATION HUNTERiR ~ ST Indiana L Michigan Electric Co.

RECIP ~ NAME, RECIPIENl AFFILIATION DENTONgH ~ RE Office of Nuclear Reactor Regulationg Director

SUBJECT:

Updates 820611 response to NRC 810526 safety evaluation SA Varga 820503 ltr re equipment qualification, OISTRIBUT N, CODES A04SS C

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INDIANA 5 MICHIGAN EiECTRIC COMPANY P. O. BOX 10 BOWLING GREEN STATION HEW YORK, N. Y. '10004 November 3, 1982 AEP:NRC:0578H Donald C. Cook Nuclear Plant Unit Nos.

1 and 2

Docket Nos. 50-315 and 50-316 License Nos.

DPR-58 and DPR-74 UPDATE TO EQUIPMENT QUALIFICATION RESPONSE Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

This letter and its Attachments are an update of our submittal No. AEP:NRC:0578B, dated June 11, 1982.

That submittal responded to the NRC's Safety Evaluation Report issued on May 26,

1981, and to Mr. Steven A. Varga's letter of May 3, 1982.

A description of the Attachments to this letter follows:

(1)

Attachment A. Revised Summer Sheets Pages CI4-1, -2, -3 (Unit 1), CI6-1, -2, -3 (Unit 2),

and CI10-1, -2, -3 (Units 1 and 2) are the qualification summary sheets for Continental Wire Cable, Items 83075 and 83077.

In reviewing the operating time qualification for these cables, it was determined that the test report previously quoted for these cables (Ref 833) was not totally adequate, in that the test, had lasted for only 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months .

Since the same cables had also been qualified under Conax Corporation's Test Reports No.

IPS-326 and No. IPS - 327 (total test duration 91S days),

we are revising the summary sheets to indicate qualification under the more complete test.

Pages CP9-1, CP9-3, CPll-1 and CP11-3 (Unit 1) and CPll-1 and CP11-3 (Unit 2) reflect newly received information on Kerite Cable, Item 83127.

Page TC10-1 (Unit 1) is being submitted to incorporate minor editorial corrections.

(2)

Attachment B. Re uired Time uglification Anal sis This attachment constitutes equipment qualification reference packet 863. It replaces Item "R" attached to the 821109014b 821103 PDR ADOCK 05000315 P

PDR

Mr. Harold R. Den AEP:NR~; 0578H AEP:NRC:0578B submittal. This attachment was revised to include more detail and new information.

(3)

Attachment C. Reference List The list of references has been revised, primarily to account for changes due to the FSAR update.

(4)

Attachment D. U er Com artment Tem erature This attachment replaces Attachment 9 of the AEP:NRC:0578B submittal.

This attachment was revised to account for changes due to the FSAR update.

(5)

Attachment E. General Notes This attachment replaces Attachment No.

15 to AEP:NRC:0578.

It is being replaced to incorporate changes due to the FSAR update.

A copy of this submittal including all of the attachments is being transmitted to your Consultant, the Franklin Research Center.

This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours,

/os R. S. Hunter Vice President cc.'ohn E. Dolan - Columbus M. P. Alexich R.

W. Jurgensen W. G. Smith, Jr.

Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.

NRC Resident Inspector at Cook Plant - Bridgman C. J.

Crane Franklin Research Center

Attachment A to AEP:NRC:0578H Donald C.

Cook Nuclear Plant Unit Nos.

1 and 2

Update to AEP:NRC:0578B Revised Summary Sheets

HALD C. COOK NUCLEAR PLANT UNIT NO.

1 OCE

0. 01 L

E DP-8 EQUIPMENT DESCRIPTION SYSTEM: Ygg tong PLAtlT tD NO: Y/3$Iogg PARAfdETER Operating Time Temperalure

('F)

ENVIROtlMENT SPEC.

DOCUMENTATION REF.~

QUAL SPEC.

QUAL

)ii-it-NO la I tV, IR IO7 QUALIFICATION METHOD QQNp 1 bl97tos OUTSTANDltlG ITEMS g-I S5 75=

95-P7-COMPONEN T: rNSTf(QntENr CABLE MAtlUFACTURER:goplTINCNTRL hlOD EL tlUhlBER:XTEPIlW SO75 FUNCTION: YJlgroUS

'I ACCURACY: SPEC: NII DEhlON: Np Pressure (PSIA)

Relative Humidity (%)

Chemical Spray Z6

~ 2 l00

@gyOt

$ pv AM I7 tf 107 33 tp, lrr-Iy7 33 tv A l7 l7o-rfb-(i r RR,+

SERVICE: YAgtOuS Radiation (106 rads)

/0

/Db 33 6'h; LOCATION. O>egg Cours r~ms'LOOD LEVEL ELEV:

ABOVE FLOOD LEVEL: M4

'Documentation Reterences:

Aging (years)

Submergence svkMc+

i tlotes:

5

.Vgrtrit page 'Z+- l

From Reference

>33 FIRL Test Report F-C 2935, excerpt from Type of Test:

Sequential Gamma Radiation Steam 0.45 HRad/Hr, 10.0 l1Rad 340 F ; 100 psig ;

2 Hrs.

160,F i 0

20 Hrs.

Item >3075, 3077; Continental Hire 8 Cable Co.

Page CI4-2

Reference 817 Conax Corporation Test Report IPS-326 Phase I t 250 F ; 12 psig for 1 Hr Phase II:

190 F ; 12 psig for 201 Hrs

Submerged during Phase II in 2500 ppm boron solution.

Reference 418 Conax Corporation Test Report IPS-327 Phase I

Phase II :

Phase III:

Submerged 340 F; 12 psig for 1

Hr 250 F; 12 psig for 5 Hrs 190 F; 12 psig for 21 Hrs during Phase III in 2500 ppm boron solution.

Page CI4-3

0

DONALD C. COOK NUCLEAR PLANT UNIT tlO. 2 DOCKET NO. 50-316 LICENSE NO. DPR-li E QUIPfhEHT DESCRIPTIOti SYSTEfh: VARIOUS(S PLANT ID NO: VARtOuS COhlPONEHT: IIVS7'fr'MMFN1 MSLE htAIIUfACTURER:coA/VIA/Eh/T wee Aha CABLE ce.

hlOD EL NUhlBER:~gag 4'~7~

PARAhlETER Operating.

Time Temperature Pressure (PSIA)

Relative Humidity (%)

EHVIROfiMEHT SPEC.

DOCUhlEHTATIOH REF.e QUAL.

QUAL SPEC.

4. H~e '74.4 8 let/

g36

$ +3 lo7 J(7 Cf tel %~

43 rV~ISq ss

)'7q $ 'bq 3E QUALIFICATION METHOD GO&LI%04'rd~

s~<<e<<e r<< I OUTSTANDING ITEMS h/or e See Rel CS 4

3 ss-rqzfo ro2-fp+ygq fob-ivy nS-/74X4'.

ol S'I Zo+ &'f 227 gjk5 FUtICTION: VQRIOMS ACCURACY: SPFC: A/A DEfhON:yA SERVICE: VARIOLAR+

LOCATION. cry'F coW AIREh/7" Chemical Spray Radiation (106 rads)

Aging (years) h/4 k6'e>fP A/A 4oro<<.

17~I%

Se~<<~sr.

I FLOOD LEVEL ELEV: A/g ABOVE FLOOD LEVEL:yg

'Documentation

References:

Submergence vA s<<l,~eJ rW Notes:

17~I%

0 g

A I

rage cr'4-I

~ ~

From Reference 833 FIRL Test Report F-C 2935, excerpt from Type of Test:

Sequential Gamma Radiation Steam 0.45 MRad/Hr:g 10.0 MRad 340 F ; 100 psig ;

2 Hrs.

16O, F:

g 20 Hrs.

Item 83075, 3077; Continental Mire 8 Cable Co.

4 F

"C 4

I Page CI6-2

~ P

Reference 817 Conax Corporation Test Report IPS-326 Phase I s

250 F ; 12. psig for 1 Hr Phase II; 190 F

~ 12, psig for 201 Hrs

Submerged during Phase II in 2500 ppm boron solution.

Reference 818 Conax Corporation Test Report IPS-327 Phase I

Phase II :

Phase III:

Submerged 340 F; 12 psig for 1 Hr 250 F ; 12 psig for 5 Hrs 190 F ; 12 psig for 21 Hrs during Phase III in 2500 ppm boron solution.

Page CI6-3

~+

ALD C. COOK NUCLEAR PLANT UNIT NO.

1

~

I t

DOCKET NO. 50-315 LIC NO DP -8 EgUIPMEHT OESCRIPTIOH SYSTEM: V/IRIOUS PARAhlETER OperaHng Time ENVIRONMENT SPEC.

EQUAL}

) $.)No I

DOCUhlEN REF SPEC.

IOI TATION t)UAL.

gUALIFICATION METHOD C oNI81%/}1 I0/tf OUTSTANDING ITEMS 25-i PLANT ID HO: V/lglouS CQMPONE HT:Tr/sTRHrvlENT.

CABLE MANUFACTURER:Conmrt/pNrpL MODEL NUMBER'v Em %30/7 FUNCTION: vJRlouS ACCURACY'PEC:iVR OEhlOH' j)

SERVICE: V/)RIOTS Temperature

('F)

Pressure (PSIA)

Relative Humidity (5)

Chemical Spray Radiation (106 rads)

+30 24 'Z

)oo

>Soo Liras I

IO I 07 I07

)D7 No/0'7

/f'3 I7 /P

/7/

/f'3

/7 lg

/t/4.

LOCATION: Ook 0C

~ 'n4 FLOOD LEVEL ELEV:

ABOVE FLOOD LEVEL: /tJA

'DocumentaUon

References:

Aging (years)

Submergence NA NA Holes:

page CI I0

From Reference

~33 FIRL Test Report F-C 2935, excerpt from Type of Test:

Sequential Gamma Radiation Steam 0.45 thRad/Hr, 10.0 MRad 340 F ; 100 psig g

2 Hrs.

16O,F '

20 Hrs.

Item 83075, 3077; Continental Mire

8. Cable Co.

Page CI10-2

Reference 817 Conax Corporation Test Report IPS-326 Phase I t 250 F ; 12 psig for 1 Hr Phase II; 190 F

~ 12 psig for 201 Hrs

Submerged during Phase II in 2500 ppm boron solution.

Reference 818 Conax Corporation Test Report IPS-327 Phase I

Phase II :

Phase III:

Submerged 340 F; 12 psig for 1 Hr.

250 F

~ 12 psig for 5 Hrs 190 F ; 12 psig for 21 Hrs during Phase III in 2500 ppm boron solution.

Page CI10-3

DONALD C. COOK NUCLEAR PLANT UtIIT NO. 2 DOCKET NO. 50-316 LICENSE NO. DPR-74 E QUIP MENT DESCRIPT! ON SYSTEM: VPRIOuS PLANT ID HO: VITRIgMS COhlPONENT: ljl/STRfAMENT ABLE MANUFACTURER:coaV'I/rlEA/lgL WIM PhlD C'est.P co.

h!OOEL NUhtBER:pe~ 43p77 FUtiCTION:QPLIOQS ACCtJRACY: SPEC: h/Q DEhION:A/A SERVICE: yg+Ogc LOCATION'AT~I~E-co v.

HE FLOOD LEVEL ELEV: A/4 ABOVE PL000 LEVEL:p/g

'Documentation Relerences:

PARAMETER Operating.

Time Temperature (oF)

Pressure (PSIA)

Relative Humidity (%)

Chemical Spray Radialion (10 rads)

Aging (years)

Submergence ENVIRONMENT SPEC.

OOCUhlENTATION REF.'UAL SPEC.

QUAL.

4. No~e4 74.4H I'Tq 1%~

)c? l IT~i%~

~4.O

. )o7 g,('. 9, It+.7 Ilail%~

f OO iO n/A 5~I~ el h/A Notes:

I'7~1fp l oO

)07

~'~l'I'v,w h/A QUALIFICATION METHOD Cogmob> ~

+Sy ~+/Olt Ss~.e

~inst OUTSTANDING ITEMS A/owe.

See Rek. ~t'.3 ts r5

>7 20 $3 74-'illXg/)~lg tos X30 IVS-jan% X+;.

t7'f-I 50 X'4.

t<9-l'IIuSp t92-20ox]s',r6 202 203 Sp 0

A G

I

'LD IM j

page CALO

From Reference 833 FIRL Test Report F-C 2935, excerpt from Type of Test:

Sequential Gamma Radiation-Steam 0.45 NRad/Hr:g 10.0 NRad 340 F ; 100 psig ;. 2 Hrs.

0 160,F

~

0 g 20 Hrs.

Item 83075, 3077; Continental

>lire 5 Cable Co.

A I

Page CI10-2

Reference 817 Conax Corporation Test Report IPS-326 Phase I s

250 F; 12 psig for 1 Hr Phase II; 190 F

~ 12 psig for 201 Hrs

Submerged during Phase I'I in 2500 ppm boron solution.

Reference 818 Conax Corporation Test Report IPS-327 Phase I

Phase II :

Phase III:

Submerged 340 F ; 12 psig for 1 Hr, 250 F ; 12 psig for 5 Hrs 190 F ; 12 psig for 21 Hrs during Phase III in 2500 ppm boron solution.

L Page CI10-3

DONALD C. COOK HUCLEAA PLANT UNIT HO. I DOCKET NO. 50-3I5 LICENSE 0

DP EQUIPhlEtIT DESCRIPTIOH YSTEM: ~qrl'o~~6od phrs I l~ ~]q gP I.5 fr'uf g.~~

~~P ty.s~~

((

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~~A/ou E.~~

~~~ EQ+ ~~~~

~~FLOOD LEVEL ELEV: 4/h ADOVE FLOOD LEVEL: p/o~~

~~'Dncumentatlen~~

~~References:~~
Submergencn g-corn +
5 vLN(apl 5 pro 0 tlales:
7C Erg, JP>V('~
AJouC tsj0 page F T-/
540 520
PMASE r COMBINED THERMAL AND RADIATION AGING (50 MEGARAOS GAMMA RADIATION)
PMASE; ZE SIMULTANEOUS STEAM/CHEMICALSPRAY/RADIATIONEXPOSURE (I50 MEGARAOS GAMMA RADIATION) 346'F/II3 psig WITHIN 3 TO 5MIN.
335 F/95psig 3I5 F/69pslg (MASK m, STEAM ANO CHEMICAL-SPRAY EXPOSURE (No GAMMA RADIATION) n'- 250 E
WI-2oo 280'F/70 pslg (min)
VlITHIN10 SEC.
DAILY 265'F/28 psig IINSULAT(oN R ES ISTANCE MEASUREMENT 2I2~F/Opsig I22 F(50 C)MAXIMUM l40 l22 CABLES AT ROOM CONDITIONS DURING RELOCATION OF TEST VESSEL TO OUTSIDE OF THE RADIATION HOTCELL.
PREHEAT To l40'F MAXIMUM Q+
IMMEDIATELYPRIOR To TEST (ONCE PER
'WEEK STARTING AT 5 DAYS 77 DAYS 7DAYS lo 3
5 SEC HR HR e
HR HR l5 HR 4 DAYS TIME~
23 DAYS IOO DAYS Figure l.
Spec)f)ed Temperature, Pressure and Rad)at)on Test Prof)1e
DONALD C. COOK NUCLEAR PLANT UNIT HO. I DDCI{ET HO. 50-315 LICENSE O. DP-EQUIPMENT DESCRIPTIOH SYSTEM: vpgrous PLANT IO NO: <Ag I o vs'ARAhlETEA Operallng Time Temperature
('F)
ENVIRONMENT SPEC.
>>F. 2 QUAL SPEC.
QUAL.
/oZ DOCUMEtITATIOH AEF 'UALIFICATION hlETIIOD
~Mi'n4ioW 58puEgAR f-OUTSTAtIDIIIG ITEMS AJou K 8+CZ g
7~
COMPONENT: tow <r ~I<
MANUFACTURER:pre R r<E hlODEL NUMBER: lkm g Qf Q7 F0 flCTIOH:o~g~ c.uC />>
ACCURACY: SPEC:
~4.
DEMOH:
Pressure (PSIA)
Relative llumldlly(%)
Chemical Spray Rf.l
~odo f/~E l.ly ~F. fi Pk
/P/
$ 5 ~ll ltd pzz~
/cr3 loZ log j'L
&o&F g~ ~ $I 7L-SERVICE: Prov'~ g/4~l<
ld~W fO Fd
/-rrr LOCATIOH: M~M~
FLOOD LEVEL ELEV:
Gl>'BOVE FLOOD LEVEI-: fEJ
'Dncumenlallen
~~References:~~
Radlatlnn (100 rads)
Aging Submergenca
+OO p+
/oS Holes:
7C SGPug,~pl A-L p
CPI/-/
84O 520
PHASE I COMBINED THERMAL AND R ADIATION AGING (50 MEGARADS GAMMA RADIATION) gR 3)5 F/69pstt).
PHASE 0 SIMULTANEOUS STEA M/CHEMICAL-SPRAY/RADtATIONEXPOSURE (l50 MEGARAOS GAMMA RADtATION) 346 F/It3 ps)a WITHIN 3 To 5MIN.
335 F/95pslg PHASE m STEAM AND CHEMICAL-SPRAY EXPOSURE (NO GAMMA RADtATION) 265 F/28pstg
@INSULATION RESISTANCE MEASUREMENT
< 250 P-
+ 200 l40 l22
~ t l22iF (50 C) MAXIMUM kdO~C'j 70pstg (tnln)
WITHINIO SEC.
DAILY CASLES AT ROOM CONDITIONS DURING RELOCATION OF TEST VESSEL To OUTSIDE OF THE RADIATION HOTCELL.
PREHEAT To I40iF MAXIMUM O+
IMMEDIATELYPRIOR TO TEST 2I2'F/0 psig 80NCE PER WEEK STARTING AT 5 DAYS 77 DAYS 7 DAYS 10 3,5 SEC HR HR 8
II HR HR I5 HR 4 DAYS TIME~
23 DAYS IOO DAYS I
F)gure 1.
Spec)f)ed Temperature, Pressure and Rad)at)on Test Prof)1e
E tlUIP tlEt(T OESCRIPTIOH SY ST Ehl: lh//~trv~
PLANT t0 HO: QQ,tfrrl>
COhlPOHEtlT: Pal%'v hlAtlUFACTURER: ]Czv/4~ 4
~
'.I00EL NUhlBER: /$m Rh '3/I+
FUIICTION:
P~ weal CeC/SL ACCURACY: SPEC:
rr/+
DEhlOH:
PAttAthlETER Operating Time Temperature (of)
Pressure (PSIA)
Relative Humidity (%)
Chemical Spray DOttALD C. COCK NUCLEAR PLAtlT UNIT tl0. 2 Ett VIRCttMEHT SPEC.
Qf I Ioo ZP<
PPe f I'IfQo aorrc Aczf g.f'a g UAL.
SPEC.
gUAL.
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IISP~/p L>>
74
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/I es-//
IOL Ioj 7(
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Sa R+W VE-P~ l/2 90 t//Z Cth/h -N V
/I$, r/9 t/4
~rv vS zz.~-q3r vg 4,o-c3 cygne V/
gog aos VI r
5ERVICE: PW u,/ P~<~
4 ~Qvp ~oy~rr LOCATIOtl: XEt Co ~'rt~g~
Radiation (10 rads)
Aging (years)
QOQ
]a+
7C 5>)u~DjM fL000 LEVEL ELEY:
ABOVE fLOOO LEVEL: p/r3
~ Oocumentation Reterences:
Sf CTErTB hr.
Submergence 5r/gw~ywg-gpf Qg II7 Holes:
EnJ. Rivi~
h//os<
5~
+Et gC
S
PHASE X COMBINED THERMAL AN0 RADIATION AGING
{50 MEGARAOS GAMMA RADIATION)
PHASE fI SIMULTANEOUS STEAM/CHEMICAL-SPRAY/RADIATIONEXPOSURE (I50 MEGARAOS GAMMA RADIATION) 346'/II3 pslg WITHIN 3 TQ 5MIN.
PHASE ZZ, STEAM ANO CHEMICAL-SPRAY EXPOSURE (NO GAMMA RADIATION) 320 QIR 335'F/95 psig 3I5 F/69pslg W< 250 Z4I+ 200
~ ~
l22 F(50iC)MAXIMUM 280'Fl 70psig (min)
WITHINIO SEC.
Qj) DAII.Y QiiNsULATION 265'F/28pslg RESISTANCE MEASUREMENT 2I2i% psig ONCE PER WEEK STARTING AT 5 DAYS I40 I22 CABLES AT ROOM CONDITIONS DURING RELOCATION OF TEST VESSEL TO OUTSIDE OF THE
=
RADIATION HOTCELL.
PREHEAT TO l40iF MAXIMUM Q+
IMMEDIATELYPRIOR TO TEST 77'DAYS 7DAYS IO 3
5 SEC HR HR 8
II HR HR l5 4 DAYS TIME~
23 DAYS IOO DAYS F)gure 1.
Spec)fjed Temperature, Pressure and Rad)at)on Test Profj1e
0
o I:. r;t)t).<;:Ill:I),;,'.* nl I)IIII;tl).I
. 1 r:ii).
',i 'S i.tcr:rtsr no.
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')ocumentaliuir fteferences:
Aging (years)
Submcrgcrrce notes:
Sugurdi'K Vacge TClo-I
'a E
3 all t
I I 4
Ey 4
~ l$
Attachment B to AEP:NRC:0578H Donald C.
Cook Plant Unit Nos.
1 and 2
Update to AEP:NRC:0578B Required Time qualification Analysis l
Vt
RLCAN Kt-Ec7 C
AMERICAN ELECTRIC POP/ER SERYICE CORPORATION WE'R 5YSTE DATE:
~~SUBJECT:~~
August 19, 1982 Class IE Electrical equipment in Harsh Environment Required Time Qualification Analysis FROM<
To<
L. F.
Caso NRC IE Bulletin 79-01B Central File This memorandum addresses
-the qualified time for electrical devices inside the reactor containment for which the duration of the qualification test was less than the required time during which the device may be called upon to operate following a Design Basis Event (DBE).
The first thing to consider is that the relevant parameters are not the required operation time versus the test duration, but rather the post accident environment profile versus the test profile.
What is required is that the equivalent intensity test environment envelops with margin (108) the required post-accident environment.
Figure I, FSAR figure 5.3-10 App.N, and extrapolation to figure 022.9.1 (FSAR Appendix Q), attached, show the D. C. Cook Plant post-accident reactor containment environment.
Figure I shows tne water temperature following a LOCA accident and flooding of the containment; Figure 022.9.1 shows the air temperature during worst case conditions (steam line break).
According to Figure I, equipment flooded after a Loss of Coolant Accident (LOCA) will see an initial temperature of approximately 250oF.
Approx'mately one half-hour later, water temperature will be reduced to 160 F.
After ten hours, the water temperature will be reduced to approximately 106.5 F.
Air temperature at 100,000 seconds (approximately 28 hrs.) following a LOCA will be about 148 F and decreasing very rapidly (see FSAR appendix N, figure 5.3-10).
SLB temperatures, though initially higher (328 F), decrease more rapidly than LOCA temperatures and therefore represent less of a long term challenge to the operation of the electrical devices.
Figure 022.9-1 of Appendix Q to the FSAR shows a temperature decrease to approximately 225oF'fter one minute, hold there for about 600 sec.,
then again decrease very rapidly so it will be about, 175 F after 1000 sec.
(about 17 Min.).
Type tests under which the electrical equipment in IHTRA SYSTEM
question has been qualified (referenced in the qualification summary sheets) demonstrated the ability of the subject equipment to operate in the abnormal post-accident containment environment.
The postulated inside containment environment after 28 hrs.
(as discussed above).,
does not rep'resent a
challenge to the electrical'evices (cable and cable terminations material) since they are rated at 90'C (194'F).
Hydrogen skimmer fan motors and hydrogen recombiners are located in the upper compartment.
Upper compartment temperatures after 28 hrs. are about 110'F (see figure 14.3.3.10 and 14.2.5.-9 attached)
Arrhenius analysis done for the D.
C.
Cook Plant electrical penetrations (see letter of 7/31/81, from C.
H. Shih to L. F.
Caso) predicts that the elect'rical penetrations should last indefinitely in the inside containment post-accident environment.
Arrhenius analysis were also performed for those electrical cables for which we had Arrhenius plot information.
Ne assumed a forty-year life at 110'F plus a Design Basis Accident (DBA); we further assumed a final ambient temperature of 120'F after the accident.
The Arrhenius analysis results are summarized below:
Device
~
Component Calculated Life After DBA Req 'd.
Oper.
Time Test Duration CI2 CX3 CX8 CPI2 CP5 Rockbestos Cable Samuel Moore Cable Cerro Wire 6 Cable Cyprus Cab' Anaconda Cable 839 years 402 years
~ 377 years 74 years 48 years NA 30 days 4 mos.
3 mos'e 1 yr.
30 days
.20 days 13 days 4 mos.'0 days Attachment l hereto lists all the devices for which the required time of operation is longer than the test duration.
The component materials for each device have also been listed.
Of particular importance in this list. regarding the ability of the components to function for the required time of operation are the component materials and the length of qualification tests.
Bulletin 79-01B appendix C. table Cl shows that Ethylene Propylene Rubber (EPR) has a potential for significant aging after 10 years.
Attachment I shows that the following items use EPR insulation:
Plant Unit
.2 Item CC-4 Test Req 'd.
9.5 days" 14 days Comments Difference between test duration and required oper.
time not sig nificant
i
Plant Unit Test Duration Req 'd.
Comments conszderxng the margin between the test environ ment and the DBA environment.
1,2 CI3 CI5 CI9 CP2 1 month 1 month 7 days 4 months 4 months 30 days Arrhenius analysis yields calculated life after DBA of 402 years.
Same as CI3 Outside contain-ment environment only.
Arrhenius Analysis yields calculated life after DBA of 74 years.
1 2
2 1
2 1
CP3 CP1 CP4 CP12 CP5 CP13 7 days 20 days 13 days 30 days 1 year 1 year Outside containment environment only.
Arrhenius analysis calculated life after DBA of 74 years.
Arrhenius analysis yields a conser-vatively estimated life after DBA of 4S years.
CP7 7 days 30 days Arrhenius analysis yields calculated life after DBA of 74 years.
CPS 130 days 1 year Outside containment (radiation only environment) aualified for 200 mrads.
Items
~~CP1, CP10, and CP12 appearing in Attachment I~~
(also with EPR insulat'ion) need not be justified since the test duration for these items was equal to or greater than the required time of operation.
Considering the tests by which these devices have been qualified, the environment in which they will function, and the Arrhenius analysis that have been performed, it is my conclusion that these devices are qualified for their required time of operation.
Attention is hereby called to the two items in Attachment I qualified by very short tests (in one instance, without a test).
These items are listed below.
Plant unit Itnltl Test Duration Req'd.
Comments CI-14 No Test 1 day Outside containment environment 1,2 TI-10 40 1/2 Hrs.
4 months Outside containment, No radiation environ-ment CI-14 is a crosslinked-Polyethylene (XLPE) insulated cable rated for 190oF used outside containment only. The high Energy Line Break (HELB) environment this cable will see (230 F for 15 secs.)
probably will not raise the temperature at the surface of the cable up to its rated 190oF. Also, Bulletin 79-01B appendix C, table Cl allows credit to XLPE insulation for 10 Mrads and 40 years of life.
TI-10 was tested for 40 1/2 hours.
This test more than demonstrates the ability of the termination to survive the HELB environment outside the reactor containment.
Therefore, I conclude that items CI-14 and TI-10 are qualified for their application outside containment.
The Kerite Company does not Divulge the Chemical composition of its cable.
For this reason.
some discussion on why this cable is qualified for its application inside containment is warranted.
Kerite Company cable, summary sheet 5 CP-ll (AEP item ",3127),
was qualified bv a 7 1/2 days test.
This cable serves the Containment Recirculation Fan (CRF) motor that is required to operate following a LOCA.
The LOCA environment at D. C.
Cook Plant, as previously discussed, will be 148oF 4g ~xsi~
after 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months .
The cable was qualified for 325oF for 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months and 228oF for 7 days.
Radiation qualification amounts to 200 Nrads.
Clearly, the cable testing time did not last one year.
However, the severity of the test was greater than that of the postulated accident environment since after 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months ambient temperature will be well below cable temperature rating.
The CRF (Hydrogen skimmer) motors nameplate Full Load Amps (FLA) -is 88 amps.
The cable 40 C ambient rating in the D. C. Cook installation configuration is 119 amps.
This indicates we have ample margin in this application and do not expect to overheat the cable from its load duty. These motors are not operated during start up, normal plant operation, or shutdown conditions.
They are operated only during surveillance testing or after an accident.
Cable temperatures will therefore be low, i.e., mild aging conditions.
The remainder of the devices, in Attachment I are comprised of materials with good aging characteristics and have been tested for a sufficient length of time (by comparison with the D. C.
Cook past-DBA environment profile. Therefore, the general arguments initially developed in this review memo can be readily applied to them.
Considering the information included in the qualification summary sheets, where the post-accident environment for the.
devices in Attachment. I (except as noted) are presented, the Arrhenius analysis performed for some of these devices, and the engineering review performed herein, I conclude that these devices are qualified to operate in their locations after an accident for the required length of time.
F.
Caso LFC:mb Approved J.
M. Intrabartola
Attachments
~
~
~
1.
List of equipment for which the Test Duration was less than the Required Time of Operation.
2.
Figure I.
Water temperature inside D. C. Cook Huclear Plant Post-Accident Reactor Containment 3.
Figure 14.2.5.<<9, FSAR 4.,
Figure 14.3.4.10, FSAR Compartment Temparature.
Design Basis Accident Long Term Temperature Transient.
6.
Electrical Penetrations Arrhenius Analysis.
7/31/81 from C.
H. Shih to L. F. Caso.
Electrical Cable Arrhenius Analysis.
Letter of A.
Letter of 9/23/81 from E. A. Howard/R.
M. Hayes to L. F. Caso.
B.
Letter of 10/5/81 from L. F. Caso to E. A. Howard.
C.
Letter of 10/8/81 from E. A. Howard/R.
M. Hayes to L. F. Caso.
7.. Input Information for the Performance of the Arrhenius Analysis in Item 6 above:
A.
Letter of 8/5/81, L. F.
Caso to C.
H. Shih.
B.
C.
Letter of 8/7/81, L. F.
Caso to C.
H. Shih.
Letter of 8/27/81, L. F. Caso to R.
N. Hayes.
8.
'Raychem Corporation Heat Ag'ing Study of NCSF Compound.
Report SEDR-2001 o'f 8/10/78.
9.
Kerite Cable A.
Memo of September.
28, 1982 from L. F.
Caso to 79-01B Central File B.
Letter of September 21, 1982 from N.
H.
Dube to T. J. Massar.
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As of the time of this update (July, 1982),
no figure for the 4.6 ft2 break is available. It is expected to include such figure in a future update.
~~However, as Table~~
.14.2.5-4 indicates, the differences between the'.4 ft2 and the 4.6 ft2 breaks results are small.
NIN STEAN LINE BREAK DONALD C.
COOK NUCLEAR PLANT FSAR l3370-I
%00 OOUSLE-EHOEO
~~BREAK, I % FT l02p~~
~~POWER, 0/0 AUX FEED FAl NRE, NRST LARGE BREAK SPRAY TURHS OH BECK FAHS TURN ON 2~~
g 200
'5
~.
LOWER COMPARTHEHT
.1
~
I
(
UPPER CCHPARTMEHT P
0
-'-IQO 200 300
%00 600 600 700 800 900 V<ME.{SECONOS)
~
~ ~
Figure 14.2.5-9 Compa'~ent Temperatur'e l
July, 1982
~
C 220 200 DESIGH BASIS ACCII)FHT (VHIFORH FLOP DISTRIBUTIOH TO ICE OED CASE)
ISO LOITER COIIPARTHEHl
'o 160 p
- <<Iqo i5 Ul Pc R COIIPARTIIEHT STAGHAHI iUIIP ACIIVE SUIIP I20 I00 UPPER COHPARt'uEHT RESIDUAL.SPRAY TEIIPERATURE SUIIP RECIRCULATIOH STARTS SPRAT TEliPERATURE 80 IO I00 l000 I0,000 TfhIE (SECOtlDS)
I00.000 I,000,000 J'
~ ~
I
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Fjqul e 14.3.4.10 Design Oosis Acci(lenl Long Term Temperature Tionsienl K.:>
~ ~
~II
AMERICAN ELECTRIC POWER SERVICE CORPORATION p)Q AN Eg I
oiTF:.
July 31, 1981 5UBJEcTt Electrical P enehrations g~c,uM 8 g~ ~~
wR-A~A~ 5 OWER 5v5IE'Raw C.
H. Shih TO-L. F.
Caso According to the Arrhenius equation described in your letter to me dated July 17,
~~1981, C.~~
W. Yi has estimated the life time equivalence.
His memo is attached.
It contains a
detailed analysis, using both the Arrhenius equation, and the so-called "10 degree C" rule.
As one can see, both predicted long life times.
The 1.1 year time required is well exceeded.
A few observations are made as follows:
1.
The 10 C rule is far more conservative than the Arrhenius prediction.
Using the coefficient of 19718, one would find that at around 100d F, the life time is halved for every 10 C increase of temperature.
It 0
can be shown that below such a temperature leve',
the Arrhenius equation gives a much longer equivalent life.
2.
The long life (10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ) predicted by the Arrhenius 18 equation does not have any practical significance.
The result simply means that the material should last indefinitely at 106.5 F.
This is not a surprise be-
'cause this post accident temperature is not a high temperature.
(only about 40 F above room temperature).
Even ordinary material snould not "fail" at this temperature.
3.
The Ar~henius equation itself predicts a longer time, 3 x 10 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .
Since the IPS-326 and 327 tests were not performed till the material failed, the t~o'tests did give a relatively shorter life time equivalence, 2 x l0 hours.
The life time equation is expressed in logarithm. It is supersensitive to tempe ature.
As the equation shows that at 340 F, the mate ial would last less than one day.
On the other hand, at room temperature 68 F,,it would last 10 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
L. F.
Caso July 31, 1981 Page 2
Chin has the detailed computer printout and is familiar with the computational procedure.
Should you need more help, please call him or me.
'~'.
H. Shih CHS:jll Attachment ceo S ~
H B. J.
C.
W.
T. E.
Horowitz w/attachment Ware Yi King
4~
s A p<C*"~ -ic -
~ 'r AMERICAN ELECTRIC POY/ER SERYICE CORPORATION
~A
+WER ssy&~<
Ta:
July 30, 1981
~
E 5UBJEcTz Equivalent Age Calculations of D. C.
Cook Plant Electrical Penetrations FROMM TO-C. H. Yi C.
H. Shih Zn response to L. F. Caso's memos of July 16 and 17,
~~1981, the equivalent age of the D.~~
C.
Cook Plant electrical penetra-tions is calculated based on the given Arrhenius equation and the temperature profiles of ZPS-326 and IPS-327 tests and of reactor containment during the post-accident period.
From the mathematical viewpoint, if a certain test is con-ducted at temperature Tl and the material fails afte" Ll hours, then the equivalent life at reference temperature T f can be derived as follows:
If L = 10 is given, then (B/T-C)
L
= L 10 (1/T f 1/Tl) ref 1
where L = expected life in hours B,
C = constants, 19718 and 43.208 respectively T = absolute temperature in i(elvin Thus, if the test is conducted for htl hours, the equivalent age at reference temperature will be:
Equi.
Age = htl 10 ref 1
Tota'qui.
Age =
.E ht.
10 'ef B ( 1/T
. 1/T. )
i=1 With the given temperature profiles of ZPS-326 and ZPS-327
~~tests, then the equivalent ages of the subject material at 106.5 F~~
are as follows:
Test Duration Totzl Equivalent Ace ZPS-326 ZPS-327 Combined 202 hours0.00234 days 0.0561 hours 3.339947e-4 weeks 7.6861e-5 months 24 hours 226 hours0.00262 days 0.0628 hours 3.736772e-4 weeks 8.5993e-5 months 
2. 92 x 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months (3. 33 2.08 x 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months (2. 3 I 2.08 x 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months (2.37 IHT RA-SYSTEM x 10 years) 9 x 10 years) x 10 years)
C. H. Shih July 30, 1981 Page 2
To illustrate the validity of above calculations, let' consider the test lasted for one hou-at 340 F as indicated at the beginning of IPS-327 test:
-Expected life at 340 F (444.1 K)
= 15..56 hours6.481481e-4 days 0.0156 hours 9.259259e-5 weeks 2.1308e-5 months A e of one hour 1
0643 Expected life T5.56
~~and, the equivalent age at 106.5 F (314.4 K) = 2.07 x 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .~~
0 0
18 Expected life at, 106.5 F = 3.22 x 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 0
19 Equivalent a
e 2.07 x 10 0643 18 Expected life 3.22 x 1019 Thus, both calculations show agreement although the total equivalent ages at 106.5 F for both tests are astronomical.
Furthermore, it can be shown that the contribution in aging by the one hour exposure at 340 F is 'dominant as shown below:
E uivalent a
e at 106.5 F for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months test at 340 F
Total equivalent age from IPS-327 test 18 2 07 x 10 995 2.08 x 10 To examine the case further, a widely used 10 C rule is applied to calculate the equivalent ages that is, for every increase of 10 C, the life of material is halved.
he results are shown below:
Test IPS-326 IPS-327 Combined Total Equivalent Age at 106.5 F
(
nZ ~t. 2(T.
T
)/10)
Duration i=1 i 202 hours0.00234 days 0.0561 hours 3.339947e-4 weeks 7.6861e-5 months 9190 hours (1.05 years) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 10910 hours (1. 25 years) 226 hours0.00262 days 0.0628 hours 3.736772e-4 weeks 8.5993e-5 months 20100 hours (2.29 years)
Also, the equivalent age for the one hour exposure at 34C F
0 8020 hours0.0928 days 2.228 hours 0.0133 weeks 0.00305 months Eauivalent ace at 106. 5 F
8020 735 0
Total ecniva ent age from 99-27 test 109'0
C.
H. Shih July 30, 1981 Page 3
Again, the age contribution by the one hour exposure at 340 P to the total equivalent age at 106.5 P is dominant as shown above.
Although the 10 C rule is not equivalent to the Arrhenius equation, it can be a good approximation to it over a limited temperature range.
As a conclusion, the equivalent age of the electrical penetrations exceeds well beyond 1.1 year criteria based on the Arrhenius method with. the given temperature profile infor-mation of IPS-326 and IPS-327 tests.
If you have ques tions, pleas e let me know.
CHY:jll
AMERICAN ELECTRIC POWER SERVICE CORPORATION
<ss<CAN Es.E'C> l~
OATEs September 23, 1981 SUSiECTs ArrheniuS AnalySiS OWER SYSTG C ~ 'Iv Pi>>
oft 0 3
/pe-aJ ~~
FROMs Tos E. A. Howard/R.
M. Hayes L. F.
Caso Enclosed is a revised list of the devices and their cal-culated lives at Tset
= 120 degrees Fahrenheit.
Listed are those numbers which produced the shortest life at the LOCA Profile given.
Also enclosed are printouts'f all LOCA and Test Profiles used.
Figures 1 and 2 are examples of how two of the six LOCA Profiles were reached and the other four were done in the same manner.
Test Profile data came from previously given data from your office.
These data files are similarly created and stored on the computer.
The ARAN program used to do the calculations and an explanation of it should already be in your possession.
If you need further information or more detailed documenta-tion, please contact me in Columbus at extension 1054.
F'
) ~~~Jng Ql~ ~ coul& '
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Computer Program ARAN Arrhenius Analysis of remaining life of a component after a thermal shock.
The Arrhenius Equation is of the form B
A Life = 10 T where T = an exposure temperature (absolute scale)
By testing a material at various temperatures, T., for various amounts of time, dt
, accelerated thermal aging occurs.
To compare aging j'ates at different temperatures, B
A 1
Life at Tl = L(T1) = 10 BA 2
Life at T2 = L( 2)
= 10 (2) so, testing at T2 for time dt2 gives an eauivalent aging dtl at Tl such that
(- A)
B T
10 dtl = dt2
(- A)
T2 10 B(-
)
1 1
Tl T2 dt2
~
10 (3)
Zf we use one reference temperature, T, to compare agp.ing at any other temperature and then test the material at n tempera-tures T, each for a time dt, then the eauivalent life at reference temperature, T
n B(
)
1 1
L(T) =
Z dt..
10 o
T T.
j1 3
(4) if the material is then subjected to some temperature profile, such as a normal operation followed by a LOCA, aging occurs,
which will shorten the remaining life at T
The remaining 0
life at T
= L (T) 0 r
0 N
B(-
)
1 1
L (T) =L(T) -
Z ~t..
10 o
T T.
r 0
0
..1 7
7=
where N = the number of temperature steps from the time the material was first installed unti3. the end of the LOCA.
After the LOCA, the temperature settles down to some
~~TSET, and the remaining life at TSET, for'safety reasons, must be known.~~
N
~vsse 1
1 L (TSET)
= Lr(T
)
10 o
(6)
Program ARAN calculates the expected life at T by looking 0
at a test temperature profile performed by the manufacturer and converting this accelerated aging to equivalent life at T The LOCA prof'3.e is then converted, one step at a time, into equiva-lent life at T
. If the LOCA profile equivalent life at T
0 0
exceeds the test profile equivalent life at T at any step, a
message will be displayed indicating failure during LOCA.
3:f not, the remaining life at T after the LOCA will be 0
converted to life at the settled temperature, and this will be displayed.
The mentioned LOCA profile is to include the time before an actual LOCA (i.e.,
the material may have operated, for 10 years at some average temperature T ), then a set of tempera-tures (T
, dt
) during a LOCA, then sett3.ed down to TSZT.
ARM 7'
prints out the expected life at TSET, un3.ess ailure occurs before or during the LOCA.
Using ARAN:
The program reauires three inputs from the user:
1.
The test temperature 'profile 2.
The LOCA temperature profile 3.
The Arrhenius Parameter, B.
1.
The Test Temperature Data File:
The user creates a test temperature data file which will give ARAN the necessary information to establish total life at T
This looks like:
100 NOT 110 120 130 Tl, htl T2( ht T3, where NOT = Total number of temperature steps during the test.
Each set of of the data (T, ht
)
goes on one line, and the las t line file contains T<OT, Lt..OT
~
T =
K, ~t = hours.
2.
The LOCA Temperature Data File; I
The user also creates a
LOCA temperature data file, giving ARAN information about the temperature history of this material, from installation through LOCA to the settled temperature, TSET.
100 NOL 110 120 130 TA( htl T2 (
ht2 Last
e r I trr
NOL = Dumber of temperature steps to which the mate ial is subject.
Each set of (T., ht.)
goes on one line.
The 3
3 1st (TA, ltA), is the Average Temperature before the LOCA and the time of operation before the LOCA.
The rest are the LOCA temperature profile, broken into disc ete steps.
T =
K, 6t = hours.
o 3.
The Arrhenius Parameter, B.
By staged temperature
~~tests, the manufacturer establishes the Arrhenius Parameters A~~
& B (see Eq.
(1) ).
Because we are relating time at one temperature to time at another tempe ature, the Parameter A drops out and only B is needed Qq.
(3),).
t I
<S<C~N E~ZC ~+I 4MERIC4H ELECTRIC POWER SERVICE CORPOR4TIOH OWER SYSTEM October 5,
1981 E
suaaacT: Arrhenius Analysis for D. C. Cook Plant Class XE Cable
$ o~ ' ~
g t'. p L. F.
Caso TO!
E. A. Howard Columbus As per our telephone, conversation of 10/2/81, attached find the post-accident temperature profile outside the reactor containment to be ~~~ on the Arrhenius analysis for cable CZ-4.
EI>M Attached also find Arrhenius plots for cables CI-3, CX-9, and CP-12.
Should you have any questions, please do not hesitate to call me.
APPROVED
~~~ 4 L. F, Caso cc, J.
M.
ZNT ARTOLA
/
R.
Hayes Columbus S.
H. Horowitz T. E. King IHTRA SYST 6Li
rc 1
10 TEMPERATURE AT 10 SECONDS IS 230'F t1RlfI STEAN STOP YALVE CLOSES 0
0
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Firjijre 0-27 liest Steam Enclosure Hain Steam I i>>>> Pr>> il: (I lrment 3).
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ENGINEERING DEPT,
~ /AMERICAN ELECTRIC POWER SERYICE CORP.
~
BROADWAY HEW YORK DATE COMPANY PLANT SHEET BY G.O U JEC-Of i.
Extra olation to FSAR Fi j
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LONG-TIME AGING DATA
rr
/
LONG TINE AGING DATA IEEE-383-1974 and Nuclear Regulatory Commission Guide 1.131 require that aging data be developed to establish the long-term performance characteristics of an insulation.
A suggested method for accomplishing this is the Arrhenius technique which consists of placing insulation samples in an air oven for var'ious times at elevated temperatures and measuring the change in a significant insulation property (usually elongation).
The time to reach a predetermined value of elongation is then plotted on semilog graph paper vs the reciprocal of absolute temperature in degrees Kelvin.
An analysis of the Arrhenius data should demonstrate that the insulation will provide a service life at its normal rated operating temperature (90'C) commensurate with the design life of the installation.
This latter figure is no~lly taken to be 40 years.
Rome has developed Arrhenius aging data on the insulation compounds
'ecommended for generating station applications and this data is shown on the accompanying Arrhenius plot.
Time to reach 50% of original elongation was selected as the basis for the aging plot.
Tests on insulation compounds with 50% retained elongation indicate that both the physical and electrical properties are more than adequate for satisfactory performance, thus the test criteria are very conservative and provide a considerable margin of safety.
In developing the Azzhenius plot for Rome-EPR and Rome FR-XLP insulations it was noted that ext apolating the plots to operational temperature ratings results in considerable discrepancies in terms of life.
In fact, the extrapolated life obtained is less than actual proven operating experience of older insulations still in service today.
This apparent paradox is one of the subjects currently being studied by an IEEE Working Group which has been created to evaluate long time aging characteristics of insulation compounds.
Other ways to evaluate the concept of aging are addressed in the Supplement of the Forward of IEEE Std. 323-1974 which was issued in
~~November, 1975.~~
A portion of this Forward reads as follows: "It is acknowledged that the state-of-the-art regarding aging for some Class IZ equipment is more advanced than others.
It is expected that known technoLogy will be used in any aging program.
Optionally (and partic-ularly where the stateof-the-azt is limiting), aging as pazt of the, qualification program may be addressed by operating experience,
~~analysis, combined, or ongoing qualification".~~
~~This Supplement acknowledges that~~
~~aging, as part of a qualification program, may be addressed by operating experience,~~
~~analysis, type tests and/or any combination of these methods.~~
t
4 To assist in its aging cyalification program, Rome has obtained cable with But l rubber i s
'n ulati.on that was removed from service after 15 years of operation.
Anal si y 's of the condition of the insulation shows that it has lost an insignificant amount of its original tensile strength and elongation indicating that the cable 'bl xs cap e of providing many more years of service.
Other cables with Butyl rubber insulation have been identified in seservice and are stall providing satisfactory performance in electric utility generating stations after more than 20 years Again referring to the accompanying
~~graph, data obtained from the same Butyl rubber corn und po formulation as used on the aforementioned cables is also shown as an Arrhenius plot.~~
Examination of the curves shows that the new Rome-EPR and Rome PR-XLP insulations take greater than I
7 times and 5 times longer respectively, to reach 50% retention of original elongation than does the Butyl insulation compound.
On the basis of this corn arison and p 'nd the proven operating experience with Butvl rubber, it is lo ical to e g
xpect a life of over 40 years for Rome-EPR and Rome FR-XLP insulations under normal operating conditions.
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L'<glH00 FOR OETERMIiMING 40-YBR EQUI'lALENT AGING Aging is a phenomenon that all materials inevitably are confronted with.
Just as some people "age" at ditterent rates, different materials "age" at different rates.
when oosed with the problem of aging a material to a 40-year equivalent life condition, the i r st determination to be made is at what rate does the ma<<erial age;
'One acceotable method of determinin~ this is to age th material at a minimum. of three temperatures, one of which is 136oC and the other two a
least 10 C apart (r r.
IE=E Std.
383-1974, Paragraph 2.3.2).
The resultant retention ot elongation data can then be evaluated using t!ie Arrhenius technique.
This technique will supply an equation wi h
a defined
~~slope, or rate of change, depicting time (to loss of elongation) versus~~
-emperature.
Once this rate of aging has be n es-ahlished, one,.eeds only "o know. the anticipated ambient temperature for the 40-ye r life period to determine an equivalent aging exposure.
Mhen an Arrhenius aging plot line has been deteriiined for a material (see ex mple at-ached),
one need only to draw a para.tlel line through the desir d
40-year ambient temperature point to establish an equivalent aging line.
Any point on this new line now defines equivalent
<<ime/temperature aging parameter for the given material that simulates 40-year life at this particular ambient temperature.
For the examp'le
~~attached, 60oC was chosen as the anticipated 40-year ambient.~~
The equivalent aging line sho~s that approximately 6i0 hrs.
or 27 days 9 1i0oC or 7 days 9
121oC both would result in equivalent aging for this material to simulate 40 years aging to 60oC.
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RlQAH ERE'C) Ri AMERICAN ELECTRIC POWER SERYICE CORPORATION OATE: October 8, 1981 OWER SY5~C 5UgJFcTa Arrhenius Analyst.s FROMM TOr E. A. Howard/R. M. Hayes L. F. Caso As per our telephone conversations and your letter dated 10/5/81, attached find the most current list of devices and their respective calculated lives after the LOCA at 120 F. This list includes the following updates: 1) Devices 16 and 17 use of upper compartment curve. One run with TA = 110 F (LOCA file L22.9.1U) One run with TA = 80 F (New LOCA file L22.9Ul) 2) All assumed values of B equal to 6000 were changed to the lowest B of 5747 to be conserva-tive. 3) New LOCA file created for cable CI-4 (LCI4.2) and used in the run. 4) New B of 6812 calculated and used for CI-3, CI-9 in runs on files CI-3.2 and CI-3.3. 5) New test file created for CP-12 and new B coeffi-cient of 6640 used. Also attached is a copy of the ARAN program requested, the new files created for this latest update, and a summary report of work to date on this project. Any questions may be directed to R. M. Hayes on ext. 1048 in Columbus. I .r E. A. Ho~ard EAH/RMH:j11 Attachments cc: C. H. Shih C. Yi ('. '.:.. ~" R. M. Hayes I IHT R A-SY ST E M
Table I Device Coe fficient B Test Profile LOCA Profile Calculated Life After LOCA at 1 2 0F(Hours) 1 1 1 2 1 3 1 4 1 5 1 6 1 8 1 9 2 0 6 6 9 3 6 2 6 4 (a)5747 6 8 1 2 ( I ) 5 7 4 7 u 1 5 7 4 7 5 7 4 7 6 8 1 2 u ) 5 7 4 7 {i) 5 7 4 7 (a ) 5 7 4 7 (< 1 5 7 4 7 ( > ) 5 7 4 7 (I ) 5 7 4 7 ) 5 7 4 7 ( i ) 5 7 4 7 ( i > 5 7 4 7 ( L ) 5 7 4 7 (, ) 5 7 4 7 ) 5 7 4 7 (1 ) 5 7 4 7 6 6 4 0 CI2. 2 CI8 ~ 2 CI1. 2 CI3 ~ 2 CI4. 2 CI5 ~ 2 CP 1 ~ 2 CI3 ~ 3 CP 11 ~ 2 CP 1 3 ~ 2 CP 4 ~ 3 CP 4 ~ 2 TI1 ~ 2 TI1 ~ 5 C P 1 0 F 1. 2 F 1. 2 H1 ~ 2 H1 ~ 2 TI5 ~ 2 TP 1 ~ 2 CP 1 2 L2 2. 9. 2L L22.9.2L L1 3. 1L L2 2. 9. 2L LC1 4. 2 L22.9.2L L1 3. 1L L22.9.2L L22.9.2L L22.9.2L L2 2. 9. 2L L2 2. 9. 2L L2 2. 9. 2L L2 2. 9. 2L L2 2. 9. 2L L2 2. 9. U1 L2 2. 9. 1 U L2 2. 9. U1 L2 2. 9. 1 U L22.9.2L L2 2. 9. 2 L L22.9.2L 7, 3 5 2, 9 2 2 3, 3 0 2, 7 2 5 29, 5 6 8 3, 5 2 8, 3 0 3 Failed before LOCA* (<) 1 8 8, 8 2 1 1, 9 0 0, 1 4 2 5 F 9 2 4 F 6 0 9 5 4 9, 0 4 2 4 19, 9 0 2 1, 2 34, 9 5 3 8 5, 5 7 1 1 8 1, 6 6 0 1, 8 4 6, 5 6 0 8 8 3, 1 2 9 1, 2 0 9, 9 2 2 1, 0 5 6, 4 2 7 1 3 9, 7 4 7 Fai1 e d before L0 CA ** 5, 9 6 2 1 4 5, 8 7 6 6 5 1, 1 3 1 +i y.~ Hote s:
S e e explanation in text.
Used forcomparisonpurposes(
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Repor t: Arrhenius Analys is The Arrhenius Analysis of the remaining life of a com-ponent after a thermal shock was continued as more information was received from New York. Many of the devices were not furnished with specific B coefficients and some did not have an established LOCA profile which we could work. Therefore, after two sets of correspondence and many runs of the ARAN program, the enclosed list, Table is the most current and complete in information. Documentation on all LOCA profile data files, test profile data files, and the ARAN program were furnished. The desired results were those which produced the lowest number of hours of remaining life. These were obtained using the lower compartment curve on graph 22.9.2 and using the lowest B obtained of 5747. Devices 16 and 17 were upper compartment
~~devices, therefore, the upper compartment curves on the graphs were necessary.~~
Attached to this report are two sample calculations of the remaining life of a component. One calculation is for a device that survived a LOCA and the other is for one that failed during plant operation. ~ The reason that the CZ4-2 cable failed the test is because there wasn't sufficient test data to show it would last the life of the plant, 40 years, and therefore might not survive a LOCA at some time during plant operation. E. A. Howard
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lq(iCak CalCu.(>%'io~ oY 4RP Q (roqro.~ Qv)cc. ~ 4 CZ, ~ 2. 7 c.5% Vzo~ i i c. ' m 5, 2. L.oc. A V~oR.h a: l Z: Z, 3. Z 4 Coo.~+; aizr y: 5 7+ l Yz,si YeeQ;<c, Da>a L c)c Q %poli(c. 0>> 'sr. < g = ~.~ t '( ) d" Z = Q 'nr. Z9,4 ')C; d-'~ ioR 'hr. Vp, = 3)4.33 K ') Ahp = BSo4j;oo 4r~ ~ o = 4o~r j 6-,=.ol'a 7 38< K ) r, = -40 ~ ~-'.~= . SoaS ~r. '5ri SR Wro~ Co~~kar yr ops-em g g. P ~: YcOt +r o i lc. ~ 6C zg>-g- ~, ) "+ sa> x l ~io 3SS. 3'7 hr~. 1 s(s~ "v. (0 ST47 %73 5 " gal.K <o c .84 v>+7 ( 3 l~"M. ~a~op )aQ W lo i
~ \\ l ~ ROC Q i 3q I Uioo l p ~7g~ 7g+ lD ~ ~( so~ g f~ Vl+7 < 3a3 ~ pi<'53 3So+oO ~ I.O c = . oo l8 = (),ZS'7R -4iZ 38)
P ~
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\\ 6 4 a~3.~ 57+7 Woo ~ Wi \\d ' -+) 378 f-S.<~ic + Wr~. l 6 ( ~7a-~- K4g+ 10 S7+7 ( ~ ooZZ2 ~ 10 gg3oy g8[ 33 iC lo = 4-. 8 x io , ~(~,-.- ~,~) $ 0 5741 4 3aa~X. ~~hei< ) . ooa2 78 k 10
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IS ARAa rR~ . 0 r CZLCIUS~",P20.0, "HOURS" //)
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~~. (25), I(25),L Z(25),LTI(25) '7 REAu LTI,Ia"-,LI."E,LlCO,LEilGaH 0 PR:i," iilPai~:lAi". OP .S.:ILZ"; IiiPU, S~~
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~~0 DC 1~~
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'I~ AMERICAH ELECTRIC POWER SERVICE CORPORATION >> C a N E'. KC > C
~~SUBJECT:~~
August 5, 1981 Arrhenius Analysis to extend test duration to required operating times plus a margin. OWE'R 5v 5T5 FROMs Tos L.F. Caso C. H. Shih p+w 63 AHu.J ~W 7 a. Please find attached a list of cables, cable terminations, pump motors, fan motor and heater installed at D.C. Cook Plant for which the required operating times (Column
~~4) are less than the test durations (Column 6).~~
~~Xt is requested that you apply the Arrhenius Analysis to these devices so as to extend the test durations to a minim of the required operating times plus 10% margin.~~
~~Attached, also are the required operating time references (Column 5),~~
and the environmental test profiles (Column 7). The cable material are listed in Column 3 of the device list. The insulation is listed first followed by the jacket material (Insulation/Jacket Material). The material associated with the acronyms given in Column 3, are as follows: XLPE Cros linked Polyethylene CSPE Clorosulphonated Polyethylene EPDM Ethylene Propylene Rubber EPR
, Ethylene Propylene Rubber EP Ethylene. Propylene Rubber HTK - Synthetic Rubber (HIgh*+~~"~ ~<ss< j' FR Fire Retardant Okoprene Neoprene (Synthetic Rubber) Okonite - Ethylene Propylene Rubber Okolon Hypalon Okogard Ethylene Propylene base thermosetting compound Okotherm Silicone Rubber The instrument cable terminat'on materials are a combination of the instrument cable material and the splicing material which follows: (a) Chemelex adhesive Sealant RTVW (product data sheet attached) (b) Raycnem WCSF -115-6-N + Heat Shrink IHT RA-SY STEM
(c) Burndy Connector YSV14 (d) Raychem WCSF-070-12-N Heat Shrinkable Tubing or WCSF-200-12-N The power cable termination materials are a combination of the power cable materials and b, c, and d (above). Please be advised that the present schedule for submitting this information is 8/13/81 to the Nuclear Safety and Licencing Section of AEPSC and 8/27/81 to the N.R.C. Your cooperation in realizing these schedules will be greatly appreciated. F. Caso LFC:deh Attachments Approved: J.N. Intrabartola cc: S.H. Horowitz T.E. King C.A. Ramjohn E. Welz
DEI/ICE %PS 7<"Vi I.illC/I}8J E'l c/9 P4vZ~J~I gL.PE/csPs XLPE/HYpnLoe CzrH HyP~L II PERU/iC:L + oui,i~ n~'s I/vi " 4 Ploaipf/~
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~ L q '~ ~ AMERICAN ELECTRIC POWER SERVICE CORPORATION <piC4N ~h C' WK'R 5ygf ~ AusvsT, 7, /fg/ SU BlECT-FROM* C. H-SWH PL~A>E 'PI<0 <+CLASSED, ARRffMIUS PLOTS Fag CA,BLE ~y~~igLg ~><<TII=I<> BE~A ~ THEsE: pL.ops 4gE'o SUPPL&tE4ti 087~ 7RA~MifTZi) z~ y~~ in'y 68'77ER <8 AuSU 7'Sil'7Z/ REcPO~7iuC /RiZHZM(u~ AH4LYSIS. F68 uO>Bed CORRGSPoHD 7O COLORS 2, OF 'AfE PG'ytc8 L'AGE t4IHKH lAAS WgahlNMI~Q +0 gg~ p~iagggy: CZZ. Cgg C PI42 CABLE HATaRl4t XLF'E (OCrsSLltVKBD F<LTEfHYLEPlE) ~ Pa -gL.t'koeiiE $'8TH YLEHE PgaPYLZrCZ ~ggLL Ol(OGAtLP(ETklYLENL: PR>PYCBM Q+5o [H~g+g5gzp~G o ~ ) Apnea ver 3/7 RA&~~a~ r ,/ j~ ar~wl I w
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F '1 P ilp c j 00,000 AIR OYEN AGING ARRHENIUS PLOT TIME TO 40% RETENTION OF ELONGATION I0,000 ? 1Q O~0+~ 1000 IOO C3 0 lA O 0O 0 O !A O 0 C nO CO IO 24 22
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7. ~ ~ ROCKBESTOS FIREHALL III @g @c~Q ~ I + ~ ~ ! ~ I I ~ I ~ I I i i "i I ~ ~ ~ ~ ~ ~ ~ ~ 40 YRS -). j--I I I I I I ~ l ~ I I i ( I I i il L i 1 ~ I i ~ 100~000 L 4 ~ i VVi ~. ~ I-a. I- -e I I ~ i I I f ~ ~ ~ i ~ ~ i ~ ~ ~ ~, L-, I I' ~ ~ I ~ I ~
~~%'RLTEHTB5~~
--,GF: EL.URGAT.ION ~ il ~ ~ (Has. ) ~ i ERICH I i I ~ E LFE-'; ~ ~,I o,o ~ 4 ~ L . l . i.... ~ I + I ~ l .I TmI-- ~ ~ ~ ~ ~ I ~ I ~ l I I i ~ ~ I ~ ~ i i ~ ~ ~ ~ ~ I pe P ~ g a. 0 V (I ~ c '~ U Q (I 4U Ja4 4 0 'h -.'~ ~ 850 U 4cU L L v 1 c ~ I i I I i I ~ ~ I ~ ~ I c I I.l ~ 'i ~ i ~ ~ i ~ ~ ~ l I: I j pl P l I I' I i f I / ~ l I ~ ~ i i i ~ ~ ~ i i ~ ~ ~ I ~ i I i + I i i ~ I I... 4 ~ ~ ~ I I I ~ I' ~ l i. !.L. i ~ I f ~ i I i I I' I I I I I j ~ ~ i ~ i ~i C) TH< Roc-ascrZc~ co 30Lfi ($77. gZVISZb gI V. 2+(~g. QQ 00 260 2'0 220 00 IP5 Icv ] 50'-. 9 0 '(', (,,( A~(') (5-76)
RUCKBES TOS F I REllALL I I I (IRRADIATIOtl CURED) 7. @<- Q ~ c"S K <0 YRS, 00,000 (HRS,) '3, 0 0 I ~ ~ ~ \\ I ~ s ~ ~ I I I I I e I I i ~VS, SERVICE LIFE f I i I ~ I ~ e I 'ONVERSION OF';ARR(ENIUS PLOT ~ ~ ' S EMULATED,GO'R, AGING (,.'. I
~~OPERA I~~
~~G TENPERATURE / l / e A/ i~~
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~~/< g.s / / Q / IW V '/ I I //', i .s s I s I l I I I I '0% RETE,'ETIO'l OF ELOHGATION IJ<<I V Mt ~ g f'l ~ w J~~
~~',850 100~~
< ~ I I I I I i I ~ I I I I 0 I. I l I I I I ,I I I I l I I I i o sI s 0 ZIIO 2<ID 2 I'I Z~LI - '0 I<<<I ('c) RcxlcSE'sTos ac ~ v<<7, igTz'< II I <st 150 I.. ( ~it l,I.I'. 1 90
7. ROCKBESTOS FIREHALL III 40 YRS ~ ~ r r I I I I l I I,},' v ~ I ~ I I 1 I I i .J t Ii~ I i .I I ~... I I v ~ I ~ ~ ~ ~ r It"; r r 100, 000 i::/ I IGKRRSI ONI OF, g lsaRHENISS FLOT t }TQ I i t ~ ~ l } I (Has. ) I ~ l ~ I ~ ~ ~ ~ ~ .1. Z++ e ~vppem<RE: l I I". i r I }SEfNI E LIT } ~ I ~ g ~ ~ } ~ r I ~ r ~ ~ I I i I I }: 10,0 ~l ~ ~ I ~ ~ r ~ r r ~ I ~ ~ r }. I-I j ~ W I I ~ t I I p o N ~ i0 Z v 2 CANE?.EC C AMERICAN ELECTRIC POWER SERVICE CORPORATION OWER SYSTE August 27, 1981 susiecT? Arrhenius Analysis 44PmI ~~~ 7c FROM?'. F. Caso TO? R. M. Hayes Please find enclosed the additional information you requested to complete the Arrhenius Analysis for the devices listed in my letter to C. H. Shih, dated 8/5/81. Table 1 lists the device locations (in or out of containment), 5 TA, TSET and TA. LOCA profile is the same for all devices in the containment (022.9-1, 2). ~st roof'le for CP10 is enclosed. Test profiles fori'CPg TP ,~<411'nd N2 are not available. Note however, thaW these devices are all outside the containment..,/~ ~I,( <~+pg>> 4J I Table 52 lists the manufacturer, insulation and jacket materials for the instrument and power cables. This table would help in identifying the Arrhenius plots with their associated cables. Please note that the Arrhenius plot previously identified with CI8 is incorrect. The plot for this cable (Cerro Wire & Cable Company) is also enclosed. LFC/jal APPROVED J. M. INTBAB RTOLA cc: T. . King S. H. Horowitz H. N. Scherer, Jr. Columbus C. H. Shih E. Welz C. Ramjohn IN T.". 5Y 5T E M
Ps je cr I /0 ~P ( I /o// l4 5'p I F / 8 / t IN Cou7awvEs 40 AS //0 r Q/7iSl& CcvtT. OVrSip< Cou. Ou7-s>DE CoN7 oui.slDE CoMT oui-SIp8 CouT /iV CoNAIHy.m ovT'lDG'OP ( ~ ouT-'sioj Coul. IN-CoWAaw" to65 p /t0 F ON-StvE CoNT, IN-CO> iAtplv&i Ihl-CoeAiuHGN Oui-51'OplT, OUTSiDE'oeT'o@ Xp l)o'F Io& 5'F tlat'F LOC,ATTACH k4A SEi 7~~7 = /o6 ~ S < 7p = ll> FcR DEVIL.S ouiS(DE Cag7AigR&lT.
C~ I +4N U t=A cd RES 2' vLATlo> SAc.~~i gZ pS/cs Z~ N/ PE/hPr'~~ EPPES ~ 8"P4'/Pl + CZ C'Z'0 ~easy.'( Pjcmm ] ~ pc/,. Fc Qk~M{g Ok~/5 FJM~A ok~ig-c /' D~~il~c eel< ee // ~C4'g~ Q Z. 5 ~ Pd&cnf Zpf~~4</Md I c'< 8 '(~no-Ma aM Mal(e w. gZFS//CS PZ CSF'E wsP" x/.ez//+~~- EPDH iVg~ QPZ~=c. N4.pE s,~= Ok~//dp PM ~MjaNP~ EPR N ze" P~ gkPIG M" grcuc(, g/~Apts ~>J c/>-:c d E P//~p+ //rgb+ ct'2 cp /9 F~(~ QdP'i( gp+ f~k sir'>c I c,p ZP/// P/p~
geP ZJ. Ouaii ~ 'ed by I"ouedix Corp. 'Zest Report of'ovem-ber 19'75'Ff i SMit, K d't steara chemical spray Test Profile: .2 - ~ 3 lf"ads/hr, 200 lWads 346C'F, 113 psig =or 5 hrs 265 F, 28 psig for 4 days 215oFy 2 ps3.< for 26 do ys Chemical Spray- ~ 3000 op+ ooron as ooric acid ~z so U. "0 1 'il"tfl ~ 06 ~ l"olar sod' os~ fate Q~v, Bred "~ th sod i'M hydrozid to a PE of 9 o ll.
6. (ROCKHESTOS FjRE'IIALL jj CERES pJI~E g QABlE j o g$,<jj ~ t ~ 1 e o ~ w ~s: ~ ~ ~ 1 ~ L ~:l ~ s I..e I ~ ~l, I 40 YRS L' ~ I iCOHVERS IOH OF, I I ~ l ': I s / Il ~ > ~ ~ 00,000 (Has. ) I o s ED-.~O. 2;..AEiJj"16. ~ ~ 'AT S-I "ii) --l 'ron hC ~"' ~ ~ e ~ ~ sr +<PERATjjjG,TE ERATO.I. 'I-I~ --' '- -l 1 ~ 1SI ~ 1 I j I e~ I ~ I ~ ~ I lA ~ ~ I I j al l ~ I ~ ~ -I ~ ~ I 602-: RETEHTIOIN.. .OF.ELOIlI A I IOIH-.-- SERVICE I j I I II I I l o A ~ ~ ~ ~ LIFE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ 1 ~ 1 e 1 1 j(, 1>> ~ ~ t I 1 f 1 I %J ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~s l. I ~ j~ j '~ ~ ~ aa--> ~ ~ s o ~ ~ 1 .. ~. ~ ~ ~ ~ I ~ 1 ~ ~ g>> C4 r'r g r a o s , j. s ~ o e 1 I ~ 1 s ~ I I e I I e a 0 V V V V ss >> y v oe ~ oe sa+u '.5 ~ 850 u>> g < X \\r vr o.l 1 ~ v C ~ s I ~ e I I II i+jj+s ~ ~ ~ ~ ~~ ~ ~ ~ 1 e ~ ~ O ~ l ~ ~ e I t I e I e ~ e ~ ~ ~ I ~ I ~ ~ j ~ ~ ~ t ~ 1 ~ 1 ~ ~ I ~ ~ ~ ~ a ~ ~ I l ~ ~ I 1 j ~ ~ ~ I ~ ~ ~ ~ o I 1 t ~ I ~ o ~ ~ s I I e e 1 I j I I e ~ ~ e ~ ~ ~ ~ I l a I I 1 ~ a ~ ~ ~ I I ~ I ~ ~ 1 ~ ~ ~ ~ ~ l I ~ ~ ~ a ~ ~ ~ ~ ~ --I--I I I ' ~ 1 ~ I ~ e I ~ ~ ~ I a ~ ~ ~ ~ ~ ~ ~ ~ I> ~ ~ 'I s ~ ~ ~ ~ ~ ~ ~ e o ~ ~ o l~ ~ ~ e -.( I I I ~ ~I-300 260>>60 i@0 2>>v'OO 160 l60 g5 pliO l>>0 IQo 90 80 60 ('c)' ~
rl
Ra@chem Energy Division Report" At)aJ>>'t "~1 < R ')OhA'D C. CKC LUCLEA( AltT)'(l t'P" F => r ~ ~ Pg, /( ( ' Peg'w IC (l > ~ ~ .a ta J~VC " ' a. c 1'JJI P I J !i-iiTQT Ui'D.EYE . 'qgi.ED: E. G. SECT. F1LE: /itic: HEAT AGING STUDY OF MCSF COMPOUND -'- Pages
~~Enclosures:~~
Report Number: EDR 2001 Date: 10 August 1978 Tested by; Signature: Prepared by: David D. Nyberg Approved by: n blaga g Signature Raychem Corporation Energy Division 'Report may only be used unchanged.
ABSTRACT Radiation crosslinked slabs of WCSF compound and MCSF 070/250 tubing were subjected to oven aging in air at
~~136oC, 150oC, 162oC and 175oC.~~
Based on an Arrhenius analysis of the oven aging data, the time to 50% retention of original elongation plotted on semilog paper against the reciprocal of absolute temperature in degrees Kelvin yields a predicted service life for NCSF compound of 40 years at a continuous operating temp-erature of 91oC.
CONTENTS SECTION TITLE PAGE 2. 3. 4. 5. ~0b 'ective Test Procedure
2. 1 Specimen Preparation 2.2 Oven Aging Test Results

3. 1 Retention of Elongation=
~~3.2 Arrhenius Thermal Plot 3.3 Calculation of Heat of Activation Conclusions Tables s'. 1 0'ven Aging Oata - MCSF Compound 6. Ficiures 6.1 Oven Aging Oata - MCSF Compound 6~~
~~6. 2 Arrhenius Thermal Plot - MCSF Compound 7~~
~~1. 08 JECT.IVE To assess the thermal oxidative resistance of radiation cross-linked slabs of MCSF compound by oven aging of specimens in air at 136oC,~~
~~150oC, 162oC and 175oC.~~
~~2. TEST PROCEDURE~~
2. 1 S ecimen Preparation

Standard, pelletized, virgin WCSF compound was used.
Slabs (6" x 6") were compression molded. Thickness was 75 12 mils. The slabs were crosslinked by radiation to the same crosslink density as MCSF tubing. Two Die 0 specimens from each slab were tested for tensile strength, ultimate elongation and ten-sile stress at 50>> and 100% elongation (crosshead speed 2 inches per minute). The stress-strain values from this were averaged and used as the original values to which the heat aged samples were compared. 1 Forty three (43) slabs were prepared. Standard deviations for tensile strength, ultimate elongation and tensile stress at 50" and 100>> elongation were calculated based on the original data from the two-Oie 0 specimens from each slab. Slabs were dis-carded if the above original stress-strain values were outside the mean value ~ twice the standard deviation for that value. From the acceptable slabs (41), Oie 0 specimens were cut and all combined. Five Oie 0 specimens were chosen at random from the combined lot to provide one data point for the heat aging study. The original cross-sectional area of the specimens (pre-measured) were used to calculate the stress-strain pro-perties after heat aging.
A few specimens of WCSF 070/250 plant production tubing were included in this oven aging study to allow some comparison to the slab data. The tubing was recovered prior to heat aging. Three specimens of recovered tubing were used to calculate an average original value for the stress-strain properties of interest. As with MCSF compound, five speci-mens were used for each data point. 2.2 ~OA i Forced air type Blue H ovens were used for heat aging at
~~136oC, 150oC, 162oC and 175oC.~~
The ovens were calibrated with a L2 point recording thermocouple set-up at 12 differ-ent zones in the oven chamber. The temperature was monitored regularly with a single thermocouple permanently assigned to each oven. The temperature variation was less than ~2" of the specified exposure temperature in degrees centigrade. The specimens in groups of five were hung vertically from the oven tray utilizing metal clips and hooks in the con-ventional Raychem manner. 3. TEST RESULTS
~~3. 1 Retention of Elon ation The property of prime interest in this study was retention of original elongation which is a measurement of flexibility (or lack of brittleness).~~
Both slabs and tubing oven aged at essentially'qui valent rates with a reduction of tensile strength and with a slow increase in tensile stress (modulus) or sti ffness.
The retention of original elongation versus time was plotted during the oven aging periods at the four different temperatures. ln Table 5. 1 the time (hours) to various percent retentions of original elongation are tabulated and this data is presented in graphical form in Figure 6. 1. 3.2 Arrhenius Thermal Plot In order to construct the Arrhenius thermal plot in Figure 6.2, we chose an end-point for retention of original elongation of 50". The four experimental points for 136oC,
150oC, 162oC and 175oC yield a reasonably straight line predicting a service life of 40 years at a continuous operating temperature of 91o based on a conventional Arrhenius analysis of the time to 50" reten-tion of elongation plotted on semilog paper against the recipro-cal of absolute temperature in degrees Kelvin.
3.3 Calculation of Heat of Activation From the slope of the Arrhenius thermal plot, the heat of acti-vation for the thermal oxidation of WCSF compound was calculated to be 29 kcal/mole for the end-point of 50" retention of origi-nal elongation. This was calculated using the following equa-tions: b = 2.303 (logyp tg - log],p tg) 1 1 Tz T<
Heat of Activation = a H act = R x b where tq = time to endpoint (100,000 hours) t~ = time to endpoint (1000 hours) Tq = oC + 273 corresponding to tq T> = oC + 273 corresponding to tq b = LH act/R R 1.98 cal mole C 4. CONCLUSIONS On the basis of the oven aging study described in this report and the use of a conventional Arrhenius analysis of the data, it is concluded that the useful service life of radiation crosslinked MCSF compound is predicted to be 40 years at a continuous operating temperature in excess of 90~C. The heat of activation for the thermal oxidation of MCSF compound was calculated to be 29 kcal/mole.
5. TABLE
~~5. 1 OVEN AGING OATA -~~
MCSF COMPOUNO Oven Temperature, oC TIME (hours) to Various Levels of Retained Elongation 905 80>> 70'X 60>> 50% 40>> 30>> 20>> 10>> 7 136 1 470 1230 2700 4500 6020 7510 9810 150 35 107 331 960 1570 2030 2600 3230 4720 162 12 30 130 350 521 637 744 876 1100 175 4 20, 112 154 194 228 279 361 450
~ g ink t l I 'O" .~ 'C. - ~ CI .pra~mpqp=~@...
~0 ~A 10 9 8 1 6.2 Arrhenius Thermal Plot - MCSF Compound 3 100,000 I ~ I I I I I I I ~ I I ~ I I ~ I ~ I I ~ ~ \\ I I ~ I I I ~ I t I I ~ ~ I I ~ I I ~ I ~ 10,000L-- 9 8 I ~ I 'I ~ I ~ I I ~ I I ~ ~ ~ I I I ~ I I I I I I I I ~ I I I I I I I ~ I ~ I ~ ~ ~ I ~ I ~ I ~ I I I I I I I ~ ~ I ~ I I I 4 5 1,000L 9. 8 1 I ~ I I ~ I I I ~ ~ I ~ ~ I ~ I 4 5 3 100L 2.1 2.2 2.3 2.6 2.7 2 ~ I
508JECTc ~p(cAN Kt gc AMERICAN EI.ECTRIC POYtER SERVICE CORPORATION ~BR SYS'+ September 28, 1982 The Kerite Company Cable Environmental Qualification FROM> TO-L P. Caso 79-81B Central Pile The attached letter from the Kerite Company dated 9/21/82 should be made par~of our equipment qualification document reference.numbers~63 68,78 and 72.. 2.4/LFC:jal APPROVE J N BARTOLA L F. Caso
the kerit:e company 49 Oay Street Seymour, Connecticut 08483 (203) 888-2591 MallAilCorrespondence To: P.O. Box 452 Seymour, Connecticut 06483 September 21, 1982 American Electric Power Service Corpor'ation 2 Broadway New York, NY I0004 ATTENTION: T.J. MASSAR'- ELECTRICAL ENGlNEERlNG DIVISION
~~Dear Sir:~~
~~SUBJECT:~~
~~DONALD C. COOK NUCLEAR PLANT Q $~4 ~j~~~jE~~
~~REFERENCE:~~
~~QUALI F I CATI ON UPDATE~~
~~g7v,~~
~ ~ Me have enclosed LOCA profile (excerpted from,"Tests of Electrical Cables Under Simultaneous Exposure to Gamma Rad4gion, Steam and Chemical Spray %bile Electrically Energized" - March,i 1985'l Final Report NiF-C4020"2, Figure I) which describes a 100-day test conducted by the Franklin institute Research Laboratories. This test provided a sodium borate chemical spray with a pH of 10.5 for 100 days continuously. The attached profile and the following results are offered as documentation of Kerite insulation and jacket materials'Long-Term" {three months) immersi'on performance in a sodium borate solution. The two cable samples (tested'n referenced report) are representative of each I/C which form the 3/C cable. Both samples (aged and unaged) are described as follows: I/O, g6 AUG, 65 mi I HTK (N-98) insulation and 65 mi I FR (HC-711) jacket. Each sample was irradiated to 200 megarads while installed in the autoclave. ln suirInary, both cables maintained their electrical loading (1000v ac, 50 amps) throughout the test. Each cable passed the 5 minute voltage with" stand test of 80 volts. ac per mi I of conductor insulation. This test was performed after completion of--the LOCA exposure and prior to disassembly of the test vessel while the cables were still'n 'the mandrel.
&2M Very truly yours, THE KERiTE COMPANY American Electric Power Corp. September 21, 1982 We trust that this is sufficient information to enable. you to answer the inquiry of the NRC. Froel the office of: Signee: C.A. Lundy Hetropolitan Sales Hanager PL N rma H. Oube inistrative Sales Assistant CAL/NHO/ss Enc 1osure
340 320 PHASE X COMBINED THERMAL AND RADIATION AGING (50 MEGARADS GAMMA RADIATION) PHASE XK SIMULTANEQUS STEAM/CHEMICAL-SPRAY/RADIATIONEXPOSURE (l50 MEGARADS GAMMA RADIATION) 346 F/II3psig WITHIN 3 TO 5MIN. 335 F/95palg 3I5'F/69 prig 'HASE 3K STEAM AND CHEMICAL SPRAY EXPOSURE (NO GAMMA RADIATION) LI~ 250 + 200 l22iF(50iC)MAXIMUM 280'F/TOpsig (min) VllTHINIO SEC. OAII.Y Q INSULATION 265oF/28psig RESISTANCE MEASVRKMKNT 2(2~ F/0 prig Ql}ONCE PER WEEK STARTING AT 5 DAYS l l40 l22 O(R ~ ~ CASLKS AT ROOM CONDITIONS DURING RELOCATION OF TEST VESSEL TO OUTSIDE OF THK RADIATION HOTCELL. PREHEAT TO I40iF MAXIMUM Q IMMEDIATELYPRIOR TO TEST 7T DAYS VDAYS IO ~ 3.5 SEC HR HR 8 II HR HR l5 HR 4 DAYS TIME~ 23 DAYS IOO DAYS F)gure ). Spec)fied Temperature, Pressure and Radkat)on Test Profle
8 (
Attachment C to AEP:NRC:0578H Donald C. Cook Plant Unit Nos. 1 and 2 Update to AEP:NRC:05788 Reference Lists
1
Document References Cited in IE Bulletin 79-01B Conax Corp. Test Report IPS-234 2. Conax Corp. Test Report IPS-62 3. 4 ~ 5. 6. 7. 8. 9. 10. Conax Corp. 'Zest. Report 'IPS-137 Conax Corp. Analysis Report IPS-324 FIRL Test Report F-C3341 FIRL Test Report F-C3694 Kerite Co. Report on the effects of Gamma Rad. and Autoclaving on Kerite power and control cables Conax Corp. Test Report IPS-348 FIRL Test Report F-C4033-1 FIRL Test Report F-C3683 Isomedix Corp. Test Report of &lay, 1976 12. Cerro Nire and Cable Test Report of Hay, 1976 13. Westinghouse-Canada Test Report CNAPD-332 14. FIRL Test Report F-C4033-,3 15. Nestinghouse-.Canada Test Report CWAPD-326 16. 17. Limitorque Corp. Test Lab. Project '="600456 Conax Corp. Test Report IPS-326 18. Conax Corp. Test Report IPS-327 19, 20. Conax Corp. Test Report IPS-329 Nestinghouse Corp. Test Report NCAP-7709-L, Suppl. 2 21. Westinghouse Corp. Test Report NCAP-7829 '22. 23. 24.. 25. Limitorcue Corp. Test Report -;,600198 Limitorque Corp. Test Report,
~~5600376A, Limitorque Corp.. Test Report~~
'600461 Isomedix Corp. Test; Report of 'November, 1975
( ~ ~ 8
26. Foxboro Test Report TE-3.013 27. Westinghouse Electric Corp. Communication NS-PLC 5023 dated 4/26/78 from T. N. Anderson Westinghouse to E. G. Case NRC 28. Wes inghouse Electric Corp. Test Report NCAP-9157 29. 30. 31. Automatic Switch Co. Report AOS 21678/TR Westinghouse Electric Corp. Communication NS-TNA-1950 Boston Insulated Wire Test No. 730212 32. Boston Insulated Wire Test No. 75C008 33. PIRL Test Report P-C-2935, Excerpt from 34. Rockbestos Products: Qual. of Firewall III Class IE Electric Cables .35. 36. PIRL Test Report F-C 3016 PIRL Test Report P-C 4350-3 37. Okonite Co. Qual. of Okoguard Ethylene-Propylene Rubber Insulation for Nuclear Plant Service (5-2-77) 38. Cyprus Statement of 6-16-76 39. Cyprus Statement of 9-14-76 40. 41. 42. 43. 44. 45. 46. 47. 48. 49 Cyprus Report No. 3525 Cyprus Report'o. 3658 Cyprus Statement of 6-16-76 Qual. of Namco Controls Limit Switch PIRL Test Report F-C 3271 Conax Test Report lPS-339 Conax Test Report IPS-349 Lette" of 6-21-71 from W. P. Herarueter, Customer Service Lab. Bklyn., N. Y. to A. H. Statton, Boston Edison Co. Lette of 4-17-80 from J. ~t. Allen (Hobil Oil Corp.) to Allen "eibleman (i4iEP) Okonite Co. Qual.-of Okonite Ethylene-Propylene Rubber Znsulation fbi Nuclear Plant Service 7-3-78
I ~ S
50. Westinghouse Corp.WCAP 8541 Topical Report, Environmental Testing of Foxboro Transmitters 51. ITT/Barton Product Bulletin 288A/289-2 and Technical Manual 505-4 (A) 52. ITT/Barton Product/Bulletin GI-23-3 53. ITT/Barton Product/Bulletin GS-2A-ICIE 54. Foxbozo Product Spec. PSS-2A-1B3A 55. Westinghouse Corp. Spec. 677271 56. Fisher Control Co. Oper. Test of Fisher Type 546 Electro Pneumatic Transducer 57. Auto, Switch Co. Catalog No. 30 Bulletin 8300,
~~8302, 8315 58.~~
Auto Switch Co. Catalog No. 30 Bulletin 8316 59. AEPSC NS&L Calculation DC-N-6420-2 60. 61; Elect. Penetration Analysis Flood-up Tube Qualification Packet 62. Instr. Cable Term Qual. 63. Required Time Qual. Analysis 64. Containment Spray Pump Motor 65. Environmental Qual. Class IE cable for outside containment service. 66. Westinghouse Electric Corp. Communications NS-TMA-2120 67. Westinghouse Electric Corp. Communications NS TMA-2441 WCAP 9885. 68. Electrical Cable Submergence Qualification 69. 70. 71. 72. Acton Test Report 16013-2 of July 6, 1981< Letter of 4/18/80 From Robert Henry of Kerite to L. F. Caso-AEP I Conax Corp. IPS-325 Chemical Spray pH Qualification 73. EC Pl-2-00-04 Arrhenius Calc. on Barton Transmitters
S ecified Environment Document References EE Division Ref, No. 102 102 103 103 103 Parameter Temperature Temperature Pressure Pressure Pressure Reference FSAR App. N Fig. N13.13 1 N13.13-2 FSAR Figs 14.3e4-11,-12 (Ul) FSAR Figs. 022.0-1,-2 FSAR Figs. 14.2.5-9,-10 Westinghouse Letter AEW 6504, Fig. 162 W Letter AEW 6504 Figs 1&2 FSAR 14.3.4 (U1) Device Desi nation Elect. penetr-ations Hydrogen Recomb. IMO-315
~~316, 325, 326 VMO-101)102 QCM-250 Air Recirc.~~
Fan NRV valve L. Sw's. IMO-51, 52, 53, 54 IMO-128 ICM-111, 129 NM0-151, 152, 153 Elec. Pen. Hydr. Recomb. Air Recirc. Fan IMO-51, 52, 53, 54 IMO-128 ICM-111, 129 IM0-315, 316, 325 326 VM0-101, 102 QCM-250 NM0-151, 152, 153 NRV L. SW's 104 Chemical Spray FSAR Fig. 14;3. 4-6 (U1) NRV L. SW's 105 106 Radiation Radiation NSSL Review calculation SF Merger AEP-NRC-0578 Dated 10/6/81 ,Letter of 12/16/81 =" from: C. Ramgohn to: S. M. Toth All inside containment equipment All outside containment equipment
Ref. No. 'arameter Documentation Reference Device Desi nation 107 108 109 110 Temper atur e Pressure Required Operating Time Required Operating Time Required Operating Time FSAR Fig. 14.4-6-8 (U1) Letter of 1/20/82 From: K. Vehstedt To: L. F. Caso FSAR Table 7.5-2 Letter of 4/14/75 9/29/75 From:.J. Tillinghast AEP To: K. Kneel<<VRC All outside containment equipment VM0-101, 102 QCM-250 Electrical Penetrations Hydrogen Recomb. Air Recirc. Fan motors IM0-51, 52, 53, 54 IMO-128 ICM-111, 129 IMO-315. 316. 325 326 Outside contain-MOV valves 112 113 114 115 118 116 117 Chemical Spray Tech. Spec 3/4-5, 3/4-5.6 Chemical Spray Letter of 1/10/78 From: S.J. Milioti To: J. Feinstein Chemical Spray Letter of 4/23/82 From: T. Durando To: L. F, Caso Elec. Penetration Hydr. Recomb. Inside cont. valve (except VMO's NMO's) Air Recirculation fan motor VM0-101,102 NM0-151,
~~152, 153 118 Required Letter of 4/14/82~~
~~'rom: K. Vehstedt To '. L. F. Ca so Outside contain-ment Pump Motors NRV Lim. Sw's ,NM0-151,~~
~~152, 153 ICM-305, 306~~
Attachment D to. AEP:NRC:0578H Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Update to AEP:NRC:0578B Upper Compartment Temperature
/ le,~
Contrary to what is stated in Section 3.3 of the NRC Equipment gualification Safety E~aluation Report, the maximum upper compartment temperature is not 130 F. The worst-case temperature transients for a h1SLB are given in Section 14.3.4 (Unit II) in the updated FSAR. The peak upper compartment temperature is approximately 150 F. The worst-case temperature transients for a LOCA are given in Section 14.3.4 (Unit I), Figures 14.3.4-11 and 14.3.4-12. The pea) upper compartment temperature from Figure 14.3.4-12 is approximately 150 F. This value is higher than the 130 F given in the NRC SER as the maximum temper-0 ature. In response .to an NRC question during a telephone conversation on this topic, the analyses of the containment response to LOCAs and. MSLBs did account for operation of the air return fans.
g'
Attachment E to AEP:NRC;0578H Donald C. Cook Plant Unit Nos. 1 and 2 Update to AEP;NRC:05788 General Notes
GENERAL HOTES l. Any one piece of equipment may be qualified by more than one test report. For instance, it may be qualified for steam environment by one report, for chemical spray environment by another, and for radiation environment by still another report. In a case like this, the qualification chart will list the different test reports and will specify, for each report, the qualification method used for that test (simultaneous, or sequential testing). For the case where a parameter has been qualified by test but the range attained during testing fell short of the required levels in the specified D. C. Cook plant environment, engineering analysis may have been used to explain why the environmental quantities achieved during testing are adequate for the application at hand. In these instances we call the equipment qualified by "Combination Method". This device has been used mainly to explain "Operating Time" and "Chemical Spray" qualifications. In some instances our devices have not been tested at all, however because they are required to operate in a relatively mild post-accident environment (e.g. outside containment) and because we know of devices qualifi.ed for a much harsher environment using similar or some generic type material; we have called these devices qualified by "Engineering Revie~ Methods". According to this logic, electrical devices that will be submerged following an accident inside containment, have been qualified as follows: a. Equipment is protected against submergence by floodup tubes: cable and cable terminations at the containment penetrations (Engineering Review Method). b. Equipment has been qualified for submergence but the submergence test did not include a radiation test (Combinat'on Method). c. Equipment has been qualified for LOCA and MSL3 and has been immersed after these tests as requ'red by IEEE 383-1974 (Engineering Review Method).
2. 'he limit switches, along with their cable and their cable terminations, for. the valves listed belo~ have been deleted from Attachments 2 and 3 to our submittal AZP:NRC:00356 ('"Aaster List Ho. 2").
These 'imit switches are used'for valve position indication only; that is, they are not used in the valve control circuit and are, therefore, no t needed for the operation of the valve.
I 0
Valve Zneide Containment Location Outside Containment HRV-211 212 221 222 231 232 241 242 213 223 233 FRU-210 220 230 240 VCR-11 21 101 102 103 104 105 106 107 X X X X X X X X X X X X X X X X X X Z X X X X For the valves outside containment, valve position can be readily verified. Those inside containment (VCR') are ccntainment isolation valves; a redundant containment isolation valve located outside the containment, in series with the one inside the containment, will serve as a backup device., The position of the valve outside containment can be verified.- 3. Inside the containment, the LO'CA pressure profile consists of an initial peak and a long-term peak after the ice melts out. The maximum caLculated initial peak is 14.4 psig across the operating
~~deck, as stated in Unit 2 FSAR Section 14.3.4.~~
The long-tera peak is shown in Figures 1 and 2 of Westinghouse letter AEVi-6504 to AEPSC (Ref. 103).6 For the Cook Plant, the calculated minimum ice mass is 2.13 X 10 lbs. or 1098 Lbslbasket. The value is intermediate to the cases pictured and gives a long term peak or 12 psig. in tne equipment qualification charts, the symbol "HA" means "not applicable. " 5. The bounding values given in the specified environment column give a very conservative description of the adverse environment for two reasons.
First, each bounding value may come from a different analyzed accident

case, so that typically all the worst values are not calculated to occur during the same postulated scenario.

Also, some of the ecuipment referenced to a specific chart may be subject
to only some of the adverse environment parameters or to much less severe calculated values of some parameters. 6. Equipment required due to changes in emergency operating procedures after January 14, 1980 (the issue date of IE Bulletin 79-01B) is not always included in this submittal. The cut-off date was agreed to by members of your staff at the February 7, 1980 clarification meeting in Glen Ellyn, Illinois.
NOTE OH VALVE NOTOR OPERATORS The valve operators previously listed below were qualified for operation in a radiation environment. See letter of 7/17/80 from J. J. Oliver - Limitorque, to L. F. Caso - AEP (Ref.
~~74).~~
~~These valves~~
however, are equipped with brakes and the brakes were not part of the assembly when the valves were qualified for radiation,

However, postulated failure of the brakes due to high radiation levels will not prevent the valves from opening.
~~See letter of 11/2/81 from T. Durando of the Piping and Valves Section to L. F. Caso of the Electrical Generation Section (Ref.~~
~~74).~~
VALVE ICN-311 321 L30-340 350 360 361 362 COL'QKViZ These valves would only be operated if the RHR spray system was employed. The RHR spray system is back up containment pressure suppression system and the Cook safety analysis as reported in the FSAR demonstrates that is not needed for LOCA or HELB mitigation. These valves are used during the switchover from the ECC injection phase to EEC recirculation.
~~However, the~~
. sequence of their operation as defined in emergency operating procedures limits the time of their exposure prior to thei" operation to only a very short time. LM-910 911 These valves are used "to terminate the suction of the charging pumps from the RWST once ECC'witchover to to rec'rculation has been accomplished. They are protected aga'nst exposure to post-LOCA recirculation flow by a check valve.
0
NOTES ON CABLE TERMINATIONS Calculated containment temperature 2.78 hours after a LOCA is 185 F and decreasing (Figure 14.3.4-17, Unit I). This long term environment does not pose a challenge to the mechanical or electrical quality of the termination. 230 F for ten seconds and 11.5 psig for 0.1 seconds will not challenge the mechanical or electrical quality of the termination. Environmental qualification for the control cable termination at the solenoid operated valves which serve the air-operated.con-tainment isolation valves (the VCRs) is not needed for the following reason. Energization of the solenoid is necessary to keep the containment isolation valves open. If the valves were open at the time of the accident, a containment isolation signal would de-energize the solenoid, closing the valves. If the valves were closed, they would remian closed. No matter what the initial valves'osition is at the time of the accident, no failure of the cable termination will succeed in energizi.ng the solenoid and opening the valves, when the containment isolation signal and/or the control switch in the control room'has been actuated to close the valves. Note 1 on valve motor operators pertains also to the termination at the motors serving the valves listed.
NOTES ON CABLES Instrument cable for the following instruments inside containment is not in floodup tubes in either Unit I or Unit 2. a. h1ain steam flow transmitters: MFC-110, 111,
120, 121,

130, 132,

140, 141 8I 142 b.
~~Pressurizer pressure transmitter: NPS-153 c. Reactor Coolant System narrow range temperature transmitters: NTP-110,~~
111, 120,

121, 130, 131,

140, 141,

210, 211, 220

230, 231,

240, 241.
Placing these instrument cables in floodup tubes is not necessary for the following reasons. The MFC's and the NTP's will only be used for actuati'on of protecti've systems immediately after the accident, long before their cable becomes submerged. NPS-153 provides an additional monitoring functi'on to that already provided by NPP-151,
~~152, and 153 which have their cables protected by floodup tubes.~~
2. 3. Control cables for the following equipment inside containment is not in floodup tubes in Unit 1 only. Containment isolation valves (VCR's} listed in General Note 2. Operation of these valves (closing them) will take place immediately after the accident, long before the cable will be submerged. Postulated cable damage (because of submergence or otherwise) is not capable of re-opening these valves. Calculated containmgnt temperature 2.78 hours (10,000 seconds) after a LOCA is 385 F and decreasing (Figure 14,3.4-17, Unit )). The electrical cable is rated for continuous operation at 194 F (90 C). Therefore the containment environmental temperature 0 after 2.78 hours does not represent a challenge to the mechanical electrical quality of the cable.
r
NOTE. ON INSTRKKNTS Lists A-J, vhi,ch are referenced on the equipment qualification
~~charts, are attached.~~
(ATTACHMENT TO NOTES ON INSTRUMENTS ) LIST A Engineered Safeguards Actuation Containment Phase A isolation Actuation 'AAain Steam Isolation Actuation Reactor Trip Actuation in Steam - Normal System Monitoring Unit 1 Only Unit 1 Only Both Unit 1 & 2 Both Unit 1 & 2 Both Unit 1 & 2 LIST B Engineered Safeguards Actuation Containment Phase A Isolation Post Accident Monitoring Reactor Trip Actuation Hain Steam Normal System Monitoring Remote Shut-down Monitoring Both Unit 1 & 2 Both Unit 1 & 2 Unit 2 Only Both Unit 1 & 2 Both Unit 1 & 2 Both Unit,l & 2 LIST C Engineered Safeguards Actuation Containment Phase A Isolation Actuation Post Accident ?/onitoring Hain Steam Isolation Actuation Hain Steam Normal System Monitoring Remote Shut-down Monitoring Both Unit 1 & 2" Both Unit 1 & 2 Unit 2 Only Both Unit 1 & 2 Both Unit 1 & 2 Both Unit 1 & 2 LIST D Engineered Safeguards Actuation Containment Phase A solation Actuation <win Steam solar.='on Actuation Main Peedwater Isolation Actuation Reactor Trip Actuation Reactor Coolant Normal System Monitoring Unit 1 Only Unit 1 Only Both Unit 1"'&' Both Unit 1 &'.2 Both Unit 1 2 Both Unit 1 & 2 LIST E Engineered Safegu"rds Actuation Containment Phase A Isolation Actuation Remote Shut-down Monitoring Reactor Coolant Normal System Monitor'ng Both Unit 1 & 2 Both Unit 1 & 2 Both Unit 1 & 2 Both Unit 1 2
4 t
LIST F Engineered Safeguards Actuation Containment Phase A Isolation Actuation Post Arcc ident Honitoring Containment Phase B Isolation Actuation Containment Spray Actuation Hain Steam Isolation Actuation Both Units 1 & 2 Both Units 1 & 2 Unit 2 Only Both Units 1 & 2 Both Units 1 & 2 Both Units 1 & 2 LIST G Post Accident Monitoring Containment Phase B Isolation Actuation Containment Spray Actuation Hain Steam Isolation Actuation Unit 2 Only Both Unit 1 & 2 Both Unit 1 & 2 Both Unit 1 & 2 LIST H Post Accident Monitoring L~fain Feedwater Isolation Actuation Reactor Trip Actuation . ain Feedwater Ltormal System Monitor"'ng Unit 2.Only Both Unit 1 2 Both Unit 1 & 2 Both Unit 1 & 2 LIST J Reactor Trip Actuation Post Accident Monitoring Remote Shut>>down Monitor'ng Reactor Coolan" Normal System Monitoring Both Unit 1 & 2 Unit 2 Only Both Unit 1 & 2 Both Unit 1 & 2
J V ~>}}

ML17334A444

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