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{{#Wiki_filter:0 INDIANA 5 MICHIGAN POWER COMPANY P.O.BOX 18 BO WL | {{#Wiki_filter:0 INDIANA 5 MICHIGAN POWER COMPANY P. O. BOX 18 I | ||
BO WL KG G R E EK STAT ION NEW YORK, N. f. 10004 October 15, 1979 AEP:NRC:00277 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 | |||
, Docket Nos. 50-3'i5 and 50-316 License Nos; DPR-58 and DPR-74 Additional Information in Response to IE Bulletin 79-01 Mr. J. G. Keppler, Regional Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforce1l.nt Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 | |||
==Dear Mr.Keppler:== | ==Dear Mr. Keppler:== | ||
This letter and its attachments supply the information requested in Mr.R.F.Heishman's letter dated September 19, 1979 which we received on September 26, 1979.This information was requested in connection with the NRC Staff review of our submittal AEP:NRC:00153 dated June 28, 1979 in response to IE Bulletin 79-01.In a telephone conversation with Mr.J.I.Castresana of our staff on October 9, 1979, a member of your staff agreed to an extension until October 19, 1979 for'the submittal of this response.RESPONSE TO ITEM NO.1 The information requested in Item No.1 is supplied in tabular form as Attachment B.The first column of.the Attachment B table lists the item number as given in Attachment A, which itself is a revision to Attachment A of the AEP:NRC:00153 submittal. | |||
Attachment A was revised to: Assign, to the equipment described, item numbers for the purpose of cross-indexing Attachments A and B;.Supply the information requested in Item 5 of the enclosure to Mr.Heishman's,letter; | This letter and its attachments supply the information requested in Mr. R. F. Heishman's letter dated September 19, 1979 which we received on September 26, 1979. This information was requested in connection with the NRC Staff review of our submittal AEP:NRC:00153 dated June 28, 1979 in response to IE Bulletin 79-01. In a telephone conversation with Mr. J. I. Castresana of our staff on October 9, 1979, a member of your staff agreed to an extension until October 19, 1979 for 'the submittal of this response. | ||
, | RESPONSE TO ITEM NO. 1 The information requested in Item No. 1 is supplied in tabular form as Attachment B. The first column of. the Attachment B table lists the item number as given in Attachment A, which itself is a revision to Attachment A of the AEP:NRC:00153 submittal. Attachment A was revised to: | ||
Assign, to the equipment described, item numbers for the purpose of cross-indexing Attachments A and B; . | |||
,e Mr.J.G.Keppler, Ditor | Supply the information requested in Item 5 of the enclosure to Mr. Heishman's,letter; | ||
Our con-clusion remains valid that all the equipment listed in Attachments A and B is adequately qualified to perform its safety-related functions. | " Delete | ||
RESPONSE TO ITEM NO.2 The methodology used to verify that the equipment items described. | , equipment items 23 and 46 because Foxboro in containment are no longer required for either instruments Engineered Safety Features actuation or long-term monitoring; It Modify the specified radiation dose for equipment items 24 and 51 to be consistent with the time requirement of FSAR Table 7.5-2; A@K QGWL '. | ||
in our response are, in fact, installed in the Donald C.Cook Nuclear Plant and are the same as the items for which qualification data exists, is based on a comprehensive equipment identification and control program that was and is used throughout the engineering, design, procurement, installation and checkout of the plant.This program provides for the assignment of a unique identification number (plant equipment number)to each item during the design phase.This identification is shown on design drawings, procurement documents, the items themselves when shipped from the vendor, receipt inspection documents, material issue records, installation inspection records and checkout and test records.gualification documentation is checked to verify that the qualifi-cation does meet requirements set forth in the engineering specifications for the item, and that the qualification is applicable to the item furnished. | g78 | ||
Verification that the item called out in design drawings was, in fact.installed is obtained by two independent sets of inspections. | )og5o 9m~ | ||
The first are the gC inspections conducted during the installation phase to verify conformance to design documents. | |||
The second are the inspections conducted prior to and during the checkout and test phase again to verify conformance to design documents and equipment operability. | ,e Mr. J. G. Keppler, Ditor l:NRC:00277 Modify the specified radi ati on dose for equi pment item 32 to be consistent with that for item 3 ; | ||
~;.Mr.J.G.Keppler, Di)or w3w NRC:00277 The list of items contained in our response was developed utilizing verified design documents and installation inspection records.During the preparation of responses to earlier NRC requests, we have performed additional in-plant inspections on certain items to verify their existence and the acceptability of qualification docu-mentation. | Correct the mi ss pel 1 i ng of a suppl i er ' name in equipment items 57 and 58 ; | ||
In each case, no non-conformances were found.RESPONSE TO ITEM NO.3 The limit switches which provide position indication of the air-operated safety-related valves inside containment are not needed to activate any Engineered Safety Features or for long-term post-accident nonitoring. | Modify i nformati on given for equi pment i tems 57 and 58 to make it consistent with statements i n the r eferenced test report ; | ||
For this reason, these limit switches are not considered part of the safeguards systems and have not been subjected to environ-mental testing.The limit switches for the air-operated containment isolation valves inside the containment are Namco Controls Models D2400 and SL4.Neither of these models was identified in IE Bulletins 78-04 or 79-01.The Plant equipment numbers for these valves are VCR-ll, 21, 101, 102, 103, 104, 105, 106 and 107.Limit switches for safety-related motor-operated valves inside the containment are part of the valve operators and are qualified under the same test r epor ts as the motors and valve operators themselves | Corr ect a typographi cal error in the specified rad i ati on dose for equipment item 59 ; | ||
.No separate model or equipment numbers are assigned to these limit switches.The test reports were identified in the AEP:NRC:00153 submittal. | I Modify the specified radiation dose for equipment items 60 and 62 to correspond with the more conservative calculation reported in Reference 30. The dose originally listed was from an earlier report which gave a calculated dose for one month only. | ||
RESPONSE TO ITEM NO.4 | These changes are essentially merely editorial in nature or. made to preserve consistency with previously submitted information. Our con-clusion remains valid that all the equipment listed in Attachments A and B is adequately qualified to perform its safety-related functions. | ||
This revision includes the replacement of the phrase"long term" in each case with a specific post-accident time period during which the equipment described is assumed to be needed for operation with respect to its safety-related function.The time period information shown does not necessarily reflect the accident scenario timing but was specified according to the additional consideration that cables, ter-minations, splices and similar components should not be the limiting devices in the operation of safety-related circuits.Very truly yours, FNB:em attachments cc: (attached) | RESPONSE TO ITEM NO. 2 The methodology used to verify that the equipment items described. in our response are, in fact, installed in the Donald C. Cook Nuclear Plant and are the same as the items for which qualification data exists, is based on a comprehensive equipment identification and control program that was and is used throughout the engineering, design, procurement, installation and checkout of the plant. | ||
This program provides for the assignment of a unique identification number (plant equipment number) to each item during the design phase. | |||
~.'r.J.G.Keppler, Director | This identification is shown on design drawings, procurement documents, the items themselves when shipped from the vendor, receipt inspection documents, material issue records, installation inspection records and checkout and test records. | ||
I'TEM EQUIPMENT DESCRIPTION | gualification documentation is checked to verify that the qualifi-cation does meet requirements set forth in the engineering specifications for the item, and that the qualification is applicable to the item furnished. | ||
Rcl;Hum;.Radiation Hr>Chem. | Verification that the item called out in design drawings was, in fact. installed is obtained by two independent sets of inspections. | ||
The first are the gC inspections conducted during the installation phase to verify conformance to design documents. The second are the inspections conducted prior to and during the checkout and test phase again to verify conformance to design documents and equipment operability. | |||
~;. Mr. J. G. Keppler, Di) or w3w NRC:00277 The list of items contained in our response was developed utilizing verified design documents and installation inspection records. | |||
SPEC, QUAL'UAL'ETIIOD+ | During the preparation of responses to earlier NRC requests, we have performed additional in-plant inspections on certain items to verify their existence and the acceptability of qualification docu-mentation. In each case, no non-conformances were found. | ||
RESPONSE TO ITEM NO. 3 The limit switches which provide position indication of the air-operated safety-related valves inside containment are not needed to activate any Engineered Safety Features or for long-term post-accident nonitoring. For this reason, these limit switches are not considered part of the safeguards systems and have not been subjected to environ-mental testing. The limit switches for the air-operated containment isolation valves inside the containment are Namco Controls Models D2400 and SL4. Neither of these models was identified in IE Bulletins 78-04 or 79-01. The Plant equipment numbers for these valves are VCR-ll, 21, 101, 102, 103, 104, 105, 106 and 107. | |||
Bol;IIum: Chem. | Limit switches for safety-related motor-operated valves inside the containment are part of the valve operators and are qualified under the same test r epor ts as the motors and valve operators themselves . No separate model or equipment numbers are assigned to these limit switches. | ||
The test reports were identified in the AEP:NRC:00153 submittal. | |||
RESPONSE TO ITEM NO. 4 We have responded to IE Bulletin 79-01A in our submittal AEP:NRC:00153A dated September 7, 1979. | |||
ITEM EQUIPMENT DESCRIPTION | RESPONSE TO ITEM NO. 5 Attachment A to this letter is a revision to Attachment A to the AEP:NRC:00153 submittal. This revision includes the replacement of the phrase "long term" in each case with a specific post-accident time period during which the equipment described is assumed to be needed for operation with respect to its safety-related function. The time period information shown does not necessarily reflect the accident scenario timing but was specified according to the additional consideration that cables, ter-minations, splices and similar components should not be the limiting devices in the operation of safety-related circuits. | ||
Very truly yours, FNB:em F. N. Bien attachments Vice President cc: (attached) | |||
~ .'r. J. G. Keppler, Director AE .FIRC:00277 cc: Norman C. Noseley - NRC R. C. Callen G. Charnoff D. V. Shaller - Bridgman R. S. Hunter R. W. Jurgensen | |||
DONALD C. COOK NUCLEAR PLANT UNITS NO. 1 & 2 ATTACHl'IENT A AEP:NRC:00277 | |||
PLANT NAMEc ENVIRONMENT (LOCATION) | |||
TIME DOCi QUAL'ETllODi I'TEM EQUIPMENT DESCRIPTION REQ'o PARAMETER SPECe QUAL, REFi~ REMARKS 1 Year L>e 0.1'<lt e Temp. (oF) 2()0 OP Press. (psia) 122 Rel. Hum. l00! 100'v Radiation 'a {)0 l00 Chem. ac3.( | |||
2000. o no 2 Electrical Year SC <ll ilto Temp. (oF) 1,3 Pe etvations P{>0 84O Press,(psia) 116 Rcl; Hum;. 100 l00 '> | |||
Radiation Hr> t)o 1.00 Chem. | |||
2000oo~al3 "0nP)>)>',!! B l Year 'Temp. {oF) | |||
Si!'!Ulo | |||
;?()0 >40 Press. (psia) gC Rel. Hum. .100" l00'00 Radiation 1'0 | |||
) | |||
Chem. ..i >)>f>'s> | |||
,".000 an:!9 E l Year Tempo (OF) i)3.lll)lle 2{'>0 Press. (psia) s5.5 127 7 Rcl. Hum. l00 j' 100$ | |||
Radiation (i(r a 150 ,".00 Chem. 2000 ppmB C'I This list is a compilation of items by component. | |||
Do not list the same type of component more than once. SHEET 1 OF 19 | |||
~ ~ | |||
Use limiting environment whore morc than one applies. | |||
~ Use ANAL> TEST. SEQ.> SIMUL.> ONGOING, or OTl!ER for entries into this space, ATTACllHENT A | |||
PLhNT NhHEI ENVIRONMENT (LOCATION) | |||
TIME DOC ITEM EQUIPMENT DESCRIPTION REQ'Do SPEC, QUAL'UAL'ETIIOD+ REF~*'EMARKS ogre C. ble- Qn(. ~ | |||
Ke ite Co. Temp. (oF) ;)C)0 ') ')5 16 month Press. (psia) 35. 5 C) 7 exposure to Rel. IIum. 3.00 lOO;! accident Radiation (~.tr. I) 12p lP.O environment | |||
'hem. | |||
of):j | |||
;)OOOPP. !13 Dl~ | |||
()') | |||
Control Cable- 1 Year ue(r ~ | |||
Temp (oF) | |||
Continental Uire 260 I.5 6 Cable Co. Press.(psia) 35 3.(~1. 7 Bol; IIum: 100 j~ 1.001m'50 Chem. 20')0 pp!ao Tl?il Y( ar Se(. n | |||
~ | |||
Temp. (oF) | |||
PRO Press. (psia) 3.21. | |||
Rel. IIum. | |||
Radiation (.< > > 1.50 Chem. ppu! | |||
OOOO tnnB | |||
.Instrument Cable- 1 Year '57 uimU1 Temp. (oF) | |||
Havrhem Cor . | |||
Press. (psia) 35 5 OII.. 7 Rel. Hum. 100g~ 100 j~ | |||
Radiation (I.(ra .,) 1 50 200 Chem. | |||
This list is a compilation of items by component. | |||
Da not list the same type of component more than once. SIIEET 2 OF 19 Use limiting environment where more than one applies. | |||
Use ANM., TEST, SEQ.> SIMUL.> ONGOING, or OTIIER for entries into this space. ATTACIIMENT A | |||
. PLANT N@gald C~ Cook Nuclear Plant Unit 1 ENVIRONMENT (LOCATION) | |||
TIME DOC QUAL'ETHOD~ | |||
ITEM EQUIPMENT DESCRIPTION REQo D PARAMETER SPEC, QUAL, i etio is. 1 Year Temp. (oF) | |||
Sogf REF~*'4 | |||
( 260 40 er to <tran(led Press. (psia) | |||
H 1o Rel. Hum. 1.00,'i Radiation (~t ., | |||
: 1) ()0 1(0 Chem. c'g ppln not .ro~.'d n r Po>rer Cable 'Eerminatio is 1 Year Sc~! ~ | |||
at motors and Temp. (oF) 260 3>>O | |||
'll dro.'en Becombiner Pres . (psia) 35.5 Rcl; Ilurn; 100;"o') | |||
Radiation (H>., 1.00'p'n 1.50 Chem. "..000 ppm.'3 1 h I Control Cable 1 Year | |||
'Eerminations- Temp. (oF) 34.0 Solid Ka ton S 19.c.ct Press. (psia) 35 5 ~ | |||
to Stranded Kapton Rcl. Hum. 100/~0 Radiation Chem. 2500 ppmD 16 1 Year Temp. (oF) 345 Press. (psia) | |||
Rcl .. Hum. | |||
Radiation(wra,, ()0 150 Chem. 25 PPgm18 rlt 'i'o($ 'i '(1 This list is a compilation of items by component. | |||
Do not list the same type of component more than once. SHEET 4 OF lg Use limiting environment where more than one applies. | |||
~ Usc ANAL'EST, SEQ.~ SIMUL.> ONGOING, or OTHER for entries into this space. ATTACHMENT A | |||
0 PLANT NAMEi ENVIRONMENT (LOCATION) | |||
TIME QUAL, DOCi ITEM EQUIPMENT DESCRIPTION REQ'D.'ARAMETER SPECo QUAL~ METHOD* REF>+ 'EMARKS 17 Control Cable l. Year Senarate 1'j, 8 Terminations- Temp. (oF) ~60 340 Stranded Ka ton s 1.iced Press.(psia) 120 Bel. Hum. 1.00,".) | |||
I[ a1.on Radiation ~i. 1 fj0 Chem. | |||
not .ro~!cl 2y()g y.;> | |||
Temp. (oF) | |||
Press.(psia) | |||
Rel.'um;. | |||
Radiation. )( | |||
Chem. | |||
18 Control Cable 1 Year Gonarate l3t, 5 j Temp. (oF) | |||
Terminations- 345 at terminal boxes Press. (psia) 84.7 35 5 Rel. Hum. 100 p~i RadlatLOQ graf ~ | |||
) 1 $0 150 Chem. ;?000 pomO ppm 1 Year Temp, (oF) 345 Press. (psia) n) | |||
Rol. Hum. 1.00'u Radiation 150 (I%i~(: | |||
Chem. 2 50( 2>)gl,"p OOOO nn>>H This list is a compilation of items by component. | |||
Do not list the same type of component more than once. SHEET 5 OF19 Use limiting environment whore moro than one applies. | |||
this ATTACHMENT A Use ANALi TEST i SEQ ~ SIMUL p ONGOING i or OTHER for entries into space. | |||
) | |||
PLANT NAME< | |||
i ENVIRONMENT (LOCATION) | |||
TIME QUAL>> DOC>> | |||
ITEM EQUIPMENT DESCRIPTIOM REQ'D>> PARAMETER SPEC>> METHOD'~ REF>* 'EMARKS 20 .1 ear 14 8 10 11 12 | |||
.Temp. {oF 345 Press.(psia) ni Rel. Hum. | |||
Rad1a tiog ira('I } | |||
~ 150 Chem. | |||
21 1 Year Temp>> {oF) | |||
Press.(psia) | Press.(psia) | ||
Rel. | Rel; Hum'.. 1 00/4 100'>> | ||
Radiation (I,;r~ I} 60 1/0 Chem ~ '-OQ ppmB 22 1 Year | |||
'Temp. (oF) | |||
Press. (psia) | |||
Rel. Hum. (Q Radiation (I jy ~ \} '60 150 Chem. | |||
Chem. | 9000 nmB 2500 pp.",sD (Deleted) (Deleted 'Deleted) (Deleted Temp. (oF) | ||
Press. (psia) | |||
Rel. Hum. | |||
RadiatioyI r.<. | |||
Chem. | |||
This list is a compilation of items hy component. | |||
Do not list the same type of component more than once. SHEET OF 19 Use limiting environment vhere moro than one applies. | |||
for entries into this space, ATTACHMENT A | |||
~ Use ANAL, TEST, SEQ.>> SIMUL.) ONGOING, or OTHER | |||
I~ ~ . ~ ~ ~ ~ L -. ' ~ | |||
~ | |||
' ~ ~ I | |||
Rel | ~ ~ I a ~ II . ~ | ||
~ I ~ ~ | |||
~ j ~ | |||
g ~ | |||
I ~ ~ | |||
C ~ ~ ~ ~ ~ | |||
~ ~ | |||
0~~ I~ II ~ ~ | |||
Do not list the same type of component more than once.Use limiting environment | ~ ~ | ||
~ I ~ ~ ~ ~ ~ | |||
~ITEM EQUIPMENT DESCRIPTION | ~ ~ ~ ~ ' ~ ~ ~ | ||
k ~ ~ | |||
. | ~ ~ ~ ~ | ||
Rcl | |||
PLANT NAME> Donald C. Cook Nuclear P1ant U it 1 . | |||
ENVIRONMENT (LOCATION) | |||
ITEM EQUIPMENT DESCRIPTION | TIME QUAL, DOCi EQUIPMENT DESCRIPTION REQ'O. PARAMETER SPEC, QUAL, METHOD~ | ||
REF>*'ru V .ve 1 da Sen. 16 o IIO o s- Temp.,(oF) .".60 SIIB- and motor contr Press.(psia) <np cable terminations Rel. Hum. 3.00'v Radiation (- I> i.) ".6 Chem. | |||
"000 n .n 13 | |||
-p-,i'np n Limitorrue Valve 1 dav Sc ilrat 8 22 0 erator Iiotors Temp. (oF) >>)0 PGO SIR-1 SIQ-2 and motor Press.(psia) 1 1 / 07 control cable termina- Rcl; Hum;; 100 "i 100'~ | |||
tions Radiation 1.-) 2~') | |||
Chem. ",000 zamB 2600 ppm Temp. (oF) | |||
Press. (p 'ia) | |||
Rel. Hu)n. | |||
. | Radiation Chem. | ||
Temp (oF) | |||
Press. (psia) | |||
FIRL Test Report F-C3683.Isomedix Corp.Test Report of May, 1976.Cerro Wire and Cable Test Report of May, 1976.Westinghouse-Canada Test Report CWAPD-332. | Rel. Hum. | ||
Radiation Chem. | |||
This list is a compilation of items by component. | |||
Do not list the same type of component more than once. gl SHEET 8 OF l Use limiting environment where more than one applies. 4 | |||
~ Usu ANAL< TEST, SEQ.) SIMUL.p ONGOING, or OTHER for entries into this space. ATTACHMENT A | |||
pr.awe Nanei Dbnald C. Cook Nuclear Plant Unit 2 .. | |||
I ENVIRONMENT (LOCATION) | |||
TIME QUALe DOC ITEM EQUIPMENT DESCRIPTION REQt D PMUQKTER SPECe QUALe METHOD* REF~* | |||
Ki h Volta e Electrical 1 Year Se arate Penetrations Temp (oF) 328.2 346. | |||
Press. (psia) 29.1 Rel. Hum. 100~ 100K Radiation(grad 60 100 Chem. 2000 ppn B 0 lca 1 Electrical Penetrations 1 ear Separate 1 3 Temp (oF) 328. 2 340 Press.(psia) 29.1 116 Rel; Hum; 100K 100K Rad ai t ion( fgra d) 60 100 Chem. 2000 ppm B 2098 ppm B Power Cable- Simul. | |||
Temp. (oF) 328.2 340 Anaconda Wire and Cable Press. (p in) 29.1 119.7 Rel. Hum. 100m lOOX Radiation( firad) 150 200 Chem. 2000 ppm B 00pmB Power Cable- 6 HOnths Seq. '6 month Kerite Co. Temp. (oF) 328.2 325 exposure in Press. (psia) 29.1 96.7 accident Rcl. Hum. 100~ 100K environment Radiation()trad) 120t 120 Chem. 200.0 ppii; .8, pram This list is a compilation of items by component. | |||
Do not list the same type of component more than once. | |||
SHEET~OF~ | |||
Use limiting environment where more than one applies. | |||
i ATTACHMENT A Use ANALP TESTP SEQ., SIMUL.) ONGOING, or OTHER for entries into this space. | |||
P?JQft NANEt Oonald C. Cook Nuclear Plant Unit.2 ENVIRONMENT (LOCATION) ' | |||
TIME QUALi DOC ITEM EQUIPMENT DESCRIPTION REQ'Di PARAMETER SPECi QUAL, METHOD+ REF~*'5 REMARKS 34 Power Cable- I year Simul . | |||
Essex Internati'onal Temp, (oF 328.2 346 . | |||
Press.(psia) 29.1 127.7 Rel. Hum. 100Ã 100K Radiation(Hrad 150 200 Chem. 2000 ppm B H 9-PII7 35 Control Cable- 1 year Seq. | |||
Continental Wire and Cable Temp (oF) 328.2 345 Company Press.(psia) 29.1 121.7 Rel; Hum;- 100% l 00'X Radia tion((frad 1 50 150 Chem. 2000 ppm 0 IIP[0 36 Instrument Cable- 1 ear Simul. | |||
Raychem Corp. Temp. (oF) 328.2 357 Press. (paia) 29.1 84. 7 Rel. Hum. 100K 100K Itadiation(grad 150 200 Chem. 2000 ppm B nH 9. -11 37 Instrument Cable- 1 year Separate 10,11 Samuel tloore 5 Co. Tempi (oF) 328.2 340 Press. (psia) 29.1 119.7 Rol. Hum. 100K 100/i Radiation Hrad 150 200 Chem. 2000 ppm.B p 0"(! | |||
This liat is a compilation of items by component. | |||
Do not list the same type of component: more than once. SHEET 10 OF 19 Use llmi.ting environment where moro than one applies. | |||
i Usu ANAL> TEST> SEQ.p SIMUL.p ONGOING> or OTHER for entries into this space. ATTACIINHNT A | |||
0 ar P nt Unit 2 ENVIRONMENT (LOCATION) | |||
TIME DOC, ITEM EQUIPMENT DESCRIPTION REQ'o PARAMETER SPEC, QUAL+ | |||
QUAL'ETHOD~ | |||
REP~~ | |||
'2 Instrument Cable- 1 year Seq. | |||
Cerro Wire and Cable Co. Temp (op 328.2 346 Press.(psia) 29.1 127.7 Rel. Hum. lOOX 100K Radiation tedllad 50 200 Chem. 2000 pptR B 39 Power Cable Terminations- 1 year Seq. 13 Solid Kapton Spliced to Temp. (oF) 328.2 340 tetrad Stranded Kapton Press.(psia) 29.1 118 Rel:. Hum; 100Ã 100K Radia tion( 60 60 Chem. Not Req'd tpm 40 Power Cable Terminations- 1 year Se . 13 Stranded Kapton Spliced to, Temp. (oF) 328.2 - | |||
340 Stranded Hypalon Press. (psia) 29.1 118 Rel. Hum. 100K 100K Radiatio Yirad ~ | |||
60 150 Chem. Not Req'd )l 9. | |||
41 Power Cable Terminations.- 1 year Seq. 13 At flotors and Hydrogen Temp. (oF) 250 340 Recombiner Press. (psia) 29.1 118 Rel. Hum. 100K 100K Radiatior(Hrad) 150 ~ | |||
150 Chem. 2000 ppm B This list is a compilation of items by component. | |||
Do not list the same type of component more than once. ~l SHEErll OZ l9 I | |||
Use limitinq environment where more than one applies. | |||
~ | |||
~ Use ANAL, TEST, SEQ.i SIMUL.p ONGOINGi or OTHER for entries into this space. ATTAC(jMENT A | |||
PLANT NAME! | |||
ENVIRONMENT (LOCATION) | |||
TIME QUAL, DOCi | |||
~ ITEM EQUIPMENT DESCRIPTION BEQ'o PARAMETER SPEC+ QUAL+ METllOD* | |||
REF~~'ontrol Cable Terminations- 1 Year Se . 13 Solid Kapton Spliced to Temp (oF 328.2 340 . | |||
Stranded Kapton Press.(psia) 29.1 118 Bel. Hum. 100K 100K Radiation(Iirad 60 60 Chem. Not Req'd Control Cable Terminations- 1 Year Se arate 14 8 Stranded Kapton Spliced Temp. (oF) 328.2 345 | |||
' to Solid XLpolyethylene Press.(psia) 29.1 84.7 Bel.. Hum; 100K lOOX Radiation(tlrad 60 150 Chem. Not Req'd A 9-10 Control Cable Terminations- 1 Year Se arate 15 8 Stranded Kapton Spliced to Temp. (oF) 328.2 340 Stranded EPR - Hypalon Press. (psia) 29.1 120 Bel. Hum. 100K 100K Radiation(flrad 60 150 Chem. Not Req'd @70 Temp. (oF) | |||
Pxess. (psia) | |||
Bel. Hum. | |||
Radiation t1rad Chem. | |||
This list is a compilation of items by component. | |||
Do not list the same type of component more than once. | |||
SHEET12 OF19 Use limiting environment where more than one applies. | |||
this ATTACllMENT A ANALt TESTe SEQ i SIMVL y ONGOING'r OTHER for entries into space. | |||
Pacer NAME< Donald C. Cook Nuclear Plant Unit 2 ENVIRONMENT (LOCATION) l TIME QUAL, DOCo | |||
~ | |||
ITEM EQUIPMENT DESCRIPTION REQ'o PARAMETER SPEC+ QUAL+ METHODS REF!* | |||
Control Cable Terminations- Ye r Separate - | |||
14 8 At Terminal Boxes Temp. (oF) 328.2 345 Press.(psia) 29.1 84.7 Rcl. Hum. 100$ 100l Radiation(Hrad 150 150 Chem. 2000 ppm B pH (Deleted' (d el e ted ) (Deleted) (Deleted) | |||
Temp. (oF) | |||
Pross.(psia) | |||
Rcl. Hum; Ra@lotion(Nrad Chem. | |||
Instrument Cable 1 Year Se arate 8i9il0illi12il4 Terminations- Temp. (oF) 328.2 345 Barton Instrument press. (psia) 29.1 84.7 Connections Rcl. Hum. 100K 100".o Rodiatio Yirad 150 150 Chem. 2000 ppm B 50 nnm | |||
)I 1 0 . | |||
Instrument Cable 1Yar 5'45 Separate 8 9 t 10 p ll 12 t t Terminations- Temp. (oF) 328.2 RTO Connections Pres . (psia) 29.1 84. 7 Rcl. Hum. 100'1o 100Ã Radiatio t1rad 150 150 Chem. 500 p 2000 ppm -B i H 9.f-'io. | |||
This list is a compilation of items by component. | |||
Do not list the same type of component more than once. SHEET~OF 19 Use limiting environment +here moro than one applies. | |||
i Uso ANAL, TEST, SEQ.i SIMUL.~ ONGOING, or OTHER for entries into this space. ATTACHMENT A | |||
PLANT Nues Donald C. Cook Nuclear Plant Unit 2 ENVIRONMENT (LOCATION) ~ | |||
TIME QUAL, DOC, ITEM EQUIPMENT DESCRIPTION REQ'Do PMUi1METER SPEC. QUAL, METHOD~ REF JI REMARKS Instrument Cable 1 Year Seq. 13 Terminations- Temp. (oF 328.2 340 At Electrical Penetrations Press.(psia) 29.1 118 Rcl. Hum. 100X 100X Radiatior{Mrad 60 150 Chem. Not Req'd | |||
)l 3.5 0 Instrument Cable 1 Year Se arate Terminations- Temp. (oF) 328.2 340 | |||
. Splices to Electrical Press.(psia) 29.1 84.7 Penetrations Rcl; Hum; 100X 100X Raaiatio Mrad) 60 Chem. 2000 ppm B 40)'0 H | |||
Hydrogen Recombiners l<onths Separate 20 Temp. (oF) 250 310 Press. (psia) 29.1 77 Rcl. Hum. 100@ 100X RaQiatior(Mrad ) 200 Chem. Not Req'd pI1 2 Fan Motors 1 Year Seq. 21 Temp. (oF) 250 320 Press. (psia) .: 29 1 89.7 Rcl.. Hum. 100X 100X Radiatio Mrad 150 200 Chem. Not. Req'd.. | |||
This list is a compilation of items by component. | |||
no not list the same type of component more than once. SHEET 140F 19 Uso limiting environment whore moro than one applies. | |||
i Uso ANAL> TEST, SEQ., SIMUL.~ ONGOING, or OTHER for entrios into this space. ATTACllHENT A | |||
PLANT NAMEq Donald C. Cook Nuclear Plant Unit 2.. | |||
ENVIRONMENT (LOCATION) | |||
TIME QUAL, DOC ITEM EQUIPMENT DESCRIPTION REQe D PARAMETER SPEC+ QUAL,= METHOD* REF~*'2 Limitorque 28 sec. Simul .. | |||
Val ve Operator Hotors- Temp. (oF) 328.2 330 SMB-00 and motor contro Press.(psia) 29.1 104.7 cable terminations Rel. Hum. 100/o 100K Radiation Chem. 2000 ppm B Limitor ue 10 min. Se . 24 Valve Operator Hotors- Temp. (oF) 250 250 | |||
%MB-000 and motor contro Press.(psia) 29.1 39.7 cable terminations Rel.'. Itum; 100K 100 jJ Radia tio Hrad 3.9 204 Chem. Not Req'd Not Req'd Limitor ue 1 da Seq. 16 Valve Operator Motor's- Temp. (oF) 250 315 SMB-land motor control Press. (psia) 29.1 84.7 cable terminations Rel. Hum. 100K 100K Radiation Hrad 26 204 Chem. 2000 ppm B 19 56 Limitor ue 1 day Separate 23 22 Valve Operator Motors - . Temp. (oF) 328.2 340 SI'$-1, SMB-2 and motor Press. (psia) 29.1 119.7 control cable terminat'ons Rol. Hum. 100K ~ | |||
100K Radiation ra 204 Chem. 2000 pp01.B 2622 ppm This list is a compilation of items by component. | |||
Do not list the same type of component more than once. SHEET 15OF 19 Use limiting environment where more than one applies. | |||
i Uso ANAL, TEST, SEQ.) SIMUL.) ONGOING, or OTHER for entries into this space. ATTACIIHENT A | |||
II 'I ~ I ~ ~ | |||
I~ | |||
~ I I~ | |||
- ~ ~ ~ | |||
~ ~ ~ ~ I ~ | |||
~ ~ | |||
I ~ | |||
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PLANT NAMEl DONALD C e COOK NUCLEAR PLA ''2 ENVIRONMENT (MCATION) | |||
TIME ITEM EQUIPMENT DESCRIPTION REQ'>> SPEC, QUAL'UAL~ METtton~ | |||
DOC REF t*'9 ITT Barton Pressure and hor Differential Pressure Temp. (oF) 30 Term SF. SEP Transmitters Press.(psia) 29.1 89.7 14.4 Models 763 f'64 Rel. ltum. 100% 100~ 0'k Radiatio Mrad .07 2.5 per 50 l>our Chem. 1.14't boric acid 1.14 'L boric acid/0 | |||
.15'- NaOU nom .17'; NaOlf 60 ITT Barton Pressure and LOCA Differential Pressure Temp. (oF) 160 320 SEQ. 30 Transmitters 4 months Press.(psia) 14.4 89.7 Models 763 f* 764 Rol; llum:. 100% 1001 Radia t ion( 40 50 1.14t boric acid 1.14 a borne acid | |||
.15% NaOll {nom), .17'4 NaOH 61 Pressure and Short MSLB Unit 1 Unit 2 Temp. (oF) | |||
Differential Pressure Term 260 328.2 360 SE 30 Transmitters 1 sec) | |||
Press. (psia) 35 5/29 8<).7 | |||
( | |||
Models 763 & 764 Rcl. llum. 100't/100% 100% | |||
Radiatiog< .04/.04 50 Chem. 1.14>> boric acid 1.14 a boric acid | |||
.154 aOh nom =.17L NaOH ITT Barton Pressure and MSLB Unit 1 Unit 2 Tempo (OF) | |||
Pressure 'ifferential 2'60 328.2 360 SE 30 Transmitters 4 months "35 5/29 1 89.7 Models 763 f; 764 Rel. Hum. '00'h/100'h 100% | |||
Radiation(M r 6/4.6 50 Chem, 1.14'f | |||
~ | |||
'boric acid 15'f Nanll no | |||
)'.14 a boric | |||
. 17'L NaOff acid This list is a compilation of items by component. | |||
Do not list the same type of component more than once. SHEET~F~9 Use limiting environment where moro than one applies. | |||
Use ANM, TESTi SEQ., SIMUL., ONGOING, or OTIIL'R for entries into this sPace. AITACttAENT A | |||
Document References Cited In Attachment A Conax Corp. Test Report IPS- 234 20 Conax Corp. Test Report IPS-62. | |||
3~ Conax Corp. Test Report IPS-137. | |||
Conax Corp. Analysis Report IPS-324. | |||
50 FIRL Test Report F-C3341. | |||
: 6. FIRL Test Report F-C3694.. | |||
7 ~ Kerite Co. Test Report 75IPCEA-27-P. | |||
: 8. Conax Corp. Test Report IPS-348. | |||
: 9. FIHL Test Report F-C4033-1. | |||
: 10. FIRL Test Report F-C3683. | |||
: 11. Isomedix Corp. Test Report of May, 1976. | |||
: 12. Cerro Wire and Cable Test Report of May, 1976. | |||
: 13. Westinghouse-Canada Test Report CWAPD-332. | |||
FIRL Test Report F-C4033-3. | FIRL Test Report F-C4033-3. | ||
Westinghouse-Canada Test Report CWAPD-326. | : 15. Westinghouse-Canada Test Report CWAPD-326. | ||
Limitorque Corp.Test Lab.Project$6004.56.Conax Corp.Test Report IPS-326.Conax Corp.Test Report IPS-327.Conax Corp.Test Report IPS-329.Westinghouse Corp.Test Report WCAP-7709-L, Suppl.2..21.Westinghouse Corp.Test Report WCAP-7829. | : 16. Limitorque Corp. Test Lab. Project $ 6004.56. | ||
22~ | Conax Corp. Test Report IPS-326. | ||
'onald C.Cook Nuclear Plant EP:NRC:00153 Submittal | Conax Corp. Test Report IPS-327. | ||
~of~ | : 19. Conax Corp. Test Report IPS-329. | ||
Donald C.Cook Nuclear Plant EP:NRC:00153 Submittal Item No.S stem s* | : 20. Westinghouse Corp. Test Report WCAP-7709-L, Suppl. 2. | ||
Donald C.Cook Nuclear Plant EP:NRC:00153 ubmittal Item No.S stem s* | .21. Westinghouse Corp. Test Report WCAP-7829. | ||
&: CO.CERRO WIRE&: CABLE COo N/A | 22 ~ Limitorque Corp. Test Report $ 600198. | ||
.CONTROL CABLE TERMINATIONS CONTROL CABLE TERMINATIONS AT TERMINAL BOXES INSTRUMENT CABLE TERMINATIONS AT | 23 ~ Limitorque Corp. Test Report $ 600376A. | ||
Donald C.Cook Nuclear Plant EP:NRC:00153 Submittal Item No. | Limitorque Corp. Test Report $ | ||
Donald C.Cook Nuclear Plant EP:NRC:00153 Submittal Item No.S stem s* | Corp. Test Report of Nov. 1975. | ||
Donald C.Cook Nuclear Plant EP:NRC:00l53 Submittal | 600461.'somedix 25. | ||
: 26. Foxboro Test Report TE-1013. | |||
Donald C.Cook Nuclear Plant EP:NRC:00153 Submittal It'em No. | 27 0 Westinghouse Electric Corp. Communication NS-PLC-5023 dated 4/26/78 from T. M. Anderson - Westinghouse to Z. G. Case - NRC. | ||
: 28. Westinghouse Electric Corp. Test Report WCAP-9157 | |||
: 29. Automatic Switch Co. Report AQS 21678/TR 30 Westinghouse Electric Corp. Communication NS-TMA-)950 Sheet 18 of 19 | |||
2.Cable and cable terminations of different manufac-turers and types listed have been used to serve the various safety related equipment inside the reactor containment, subject to the cables and the cable terminations being qualified for operation in a post-accident containment environment. | |||
SI Intermediate and low head safety injection RHR Residual heat removal, used as low'head safety injection Page 18 of 18}} | GENERAL NOTES: | ||
: 1. In situations where a qualification pressure was not explicitly stated and it was known that the test environment was steam, the saturation pressure of steam at the given test temperature was used. | |||
: 2. All chemical concentrations noted as X are weight L. | |||
19'f 19 | |||
DONALD C. COOK NUCLEAR PLANT UNITS NO. 1 L 2 ATTACHMENT B AEP:NRC:00277 | |||
'onald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s | |||
* Function No. Manufacturer T e CONTAINMENT ELECTRICAL HIGH 1-1P6, 1-1P7, CONAX CORPORATION EP-1 ISOLATION VOLTAGE (4 kv) 1-2P5, 1-2P67 1-3P7 CONTAINMENT PENE- 1-3P8, 1-4P7, TRATION 1-4P8 ALL. ELECTRICAL LOW l-lPl, l-1P2, CONAX CORPORATION EP-2 through EP-13 VOLTAGE (600:V AND . 1-1P3, 1-1P4, BELOW) CONTAINMENT 1-2P2, 1-2P3, 1-4P2 PENE I RATION 1-2P4, 1-2P7,1-2PS 1-3P1, 1-3P2,1-3P3, 1-3P6, 1-4P3,1-4P4, 1-4P5, 1-4P6,1-4I5, 1-4I7, 1-4I8,1-4C2, 1-4C3, 1-4C1,1-4I6, 1-1C4, 1-1C1,1-1C3, 1-1I5, l-lI8,1-1I7, 1-1I6, 1-2I8,1-2I5, 1-2I6, 1-2C4,1-2C3, 1-2C1, 1-2I7,1-3I8, 1-3I6, 1-317,1-3C1, 1-3C2, 1-3C4,1-3I5 ALL POWER CABLE 0 347 ANACONDA 3TC II2 AWG CU ALL .. POWER CABLE 8 399 OKONITE 1/C f2 AWG CU ALL POWER CABLE II. 3116 KERITE 3TC 810 AWG CU ALL CONTROL CABLE 8 3092 CONTINENTAL - | |||
Blidigh"'"'age | |||
*See attached list for key ga aa | |||
~of~ | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s | |||
* Function No. Manufacturer T e ALL CONTROL CABLE ¹3093 CONTINENTAL 7/C ¹19/12 AHG STRANDED CU ALL CONTROL CABLE ¹3119 CONTINENTAL 2/C ¹12 AWG SOLID Co ALL CONTROL CABLE ¹3120 CONTINENTAL 4/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹3121 CONTINENTAL 7/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹3122 CONTINENTAL 12/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹3123 CONTINENTAL 15/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹3124 CONTINENTAL 4/C ¹7/18 AWG ALL CONTROL CABLE ¹3125 CONTINENTAL 7/C ¹7/18 AHG STRANDED Ctj ALL CONTROL CABLE ¹3119 GENERAL ELECTRIC 2/C ¹12 AWG SOLID CO | |||
*See attached list for key Page ~of~ | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model ubmittal Component 'quipment or Item No. S stem s | |||
* Function No. Manufacturer T e ALL CONTROL CABLE iO'120 GENERAL ELECTRIC 4/C g 12 AWG SOLID CU ALL CONTROL CABLE GENERAL ELECTRI 7/C g 12 AWG SOLID CU ALL CONTROL CABLE GENERAL ELECTRI 12/C g 12 AWG SOLID CU ALL CONTROL CABLE t5'123 GENERAL ELECTRI 15/C PP 12 AWG SOLID CU ALL INSTRUMENT CABLE 8 3O73 RAYCHEM RG-ll/U TRIAXIAL YELLOW ALL INSTRUMENT CABLE 0 3O74 RAYCHEM RG-ll/U TRIAXIAL | |||
/1IITE 8 ALL INSTRUMENT CABLE 8 3O76 RAYCHEM RG-ll/U TRIAXIAL Bl ACK INSTRUMENT CABLE I: 3111 RG-ll/U BIAXIAL ALL. RAYCHEM ORANGE ALL INSTRUMENT CABLE 3112 RAYCHEM RG-ll/U TRIAXIAL 13LUE | |||
*See attached list for key Page ~of 18 | |||
Oonald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s | |||
* Function No. Manufacturer T e ALL INSTRUMENT CABLE 8 3O75 BOSTON INSULATED g 16 AWG TSP ALL INSTRUMENT CABLE 8 3O76 Bgl'IE )INSULATED RG-11/U TRIXIAL 10 ALL INSTRUMENT CABLE 0 3O75 SAMUEL MOORE gQ6 AWG TSP 5 CO ~ | |||
10 ALL INSTRUMENT CABLE g 3077 SAMUEL'OORE gl6 AWG TSQ | |||
&: CO. | |||
INSTRUMENT CABLE g 3077 CERRO WIRE &: g16 AWG TSQ CABLE COo 12 ALL POWER CABLE TER IINATIONS N/A SOLID KAPTON SPLICED TO STRANDED KAPTON 13 ALL POWER CABLE TERMINATIONS N/A N/A STRANDED KAPTON SPLICED TO STRANDED HYPALON ALL POWER CABLE TERMINATIONS AT VALVE MOTORS &:. | |||
HYDROGEN BECOMBINERS N/A N/A N/A "15 ALL CONTROL CABLE TERMINATIONS N/A N/A SOLID KAPTON SPLICED TO STRAIIDED KAPTON | |||
*See attached list for key Page 4 of 18 | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s | |||
* Function No. Manufacturer T e 16 ALL CONTROL CABLE TERMIHATIONS . N/A N/A STRANDED KAPTON SPLICED TO SOLID XL POLYETIIYLEHE 17 ALL CONTROL CABLE TERMINATIONS N/A N/A STRANDED KAPTON SPLICED TO STRANDED EPR IIYPALON 18 ALL CONTROL CABLE TERMINATIONS AT TERMINAL BOXES N/A N/A N/A 19 ALL INSTRUMENT CABLE TERMINATIONS AT BARTON INSTRUMENT N/A N/A N/A 20 ALL INSTRUMENT CABLE TERMINATIONS AT RTDiS N/A N/A N/A 21 INSTRUMENT CABLE TERMINATIONS AT ELECTRICAL PEHETRATIONS N/A N/A N/A 22 ALL INSTRUMENT CABLE SPLICES TO ELECTRICAL PEHETRATIONS N/A N/A N/A | |||
*See attached list for key Page ~of 18 aa | |||
~I | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stems* Function No. Manufacturer T e 23 (Deleted) (Deleted) (Deleted) (Deleted) (Deleted) | |||
*See attached list for key Page 6 ot Z8 | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s* Function No. Manufacturer T e 24 HYDROGEN RE<< REDUCE HYDROGEN COMBINERS CONCENTRATION 1-HR1, 1-HR2 WESTINGHOUSE CONTAINMENT AIR REDUCE HYDROGEN 1-CEQl, 1-CEQ2 PHY2050-1 25 RECIRCULATION CONCENTRATION AND PHY2050-2 FAN MOTORS RECIRCULATE CONTAIN-MENT AIR | |||
'26 BORON INJECTION MOTOR OPERATED IMO-51 LIMITORQUE SMB-00 VALVE BORON INJECTION MOTOR OPERATED IMO-52 L IMITORQUE SMB-00 26 VALVE BORON INJECTION MOTOR OPERATED IMO-53 LIMITORQUE SMB-00 26 4 | |||
VALVE 26 BORON INJECTION MOTOR OPERATED | |||
'VALVE IMO-54 L IMI TORQUE SMB-OQ 26 CONTAINMENT MOTOR OPERATED VALVE QCM-250 L IMITORQUE SMB-00 ISOLATION VMO-101 L IMITORQUE SMB-000 27 CONTAINMENT MOTOR OPERATED HYDROGEN CON- SUCTION DAMPER TROL AND AIR RECIRCULATION CONTAINMENT VMP;102 LIMITORQUE SMB-000 | |||
, 27 MOTOR OPERATED HYDROGEN CON- SUCTION DAMPER TROL AND AIR RECIRCULATION | |||
*See attached list for key Page 7 of~] | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Node1 Submittal Component Equipment or Item No. S stems* Function No. Manufacturer T e INO-315 LINITORQUE SMB-1 28 SI MOTOR OPERATED VALVE IMO-316 L IMITORQUE SMB-1 28 SI MOTOR OPERATED VALVE IMO-325 L IMITORQUE SMB-1 28 SI MOTOR OPERATED VALVE INO-326 . L INITORQUE SNB-1 28 SI MOTOR OPERATED VALVE MOTOR OPERATED INO-128 L INITORQUE SNB-1 29 RHR VALVE 29 CONTAINMENT MOTOR OPERATED ICM-129 L IM I TORQUE SNB-1 ISOLATION VALVE ICM-111. L Ih1ITORQUE SNB-2 29 CONTAINhiENT NOTOP, OPERATED ISOLATION VALVE ICM-305 LINITORQUE SMB-2 29 RHR AND CONTAIN- MOTOR OPERATED MENT ISOLATION VALVE ICM-306 L IMITORQUE SMB-2 RHR AND CONTAIN- MOTOR OPERATED 29 VALVE MENT ISOLATION | |||
*See attached list for key Page 8 of la | |||
0 Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s | |||
* Function No. Manufacturer T e CONTAINMENT ELECTRICAL HIGH 2-1P6, 2-1P7, 2-2P5 CONAX CORPORATION EP-1 30 ISOLATION VOLTAGE (4kV) 2-2P6, 2-3P7, CONTAINMENT 2-3P8, 2-4P7, PENETPAT IONS 2-4P8 ALL ELECTRICAL LOW VOL- 2-1P1, 2-1P2, CONAX CORPORATION EP-2 through EN3 31 TAGE (600V AND 2-1P3, 2-1P4, BELOW ) CONTAINMENT 2-2P2, 2-2P3, PENETRAT ION S 2-2P4, 2-2P7, 2-2P8, 2-3P1,2-3P2, 2-3P3, 2-3P6,2-4P2, 2-4P3, 2-4P4,2-4P5, 2-4P6, 2-4C1,2-4C2, 2-4C3, 2-1C1,2-1C3, 2-1C4, 2-4 I 5> 2-4 I 6, 2-4I7, 2-4I8,2-1I5, 2-1I6, 2-1I8,2-3I8, 2-3I7, 2-3I6,2-3I5, 2-2I8, 2-2I7,2-2I6, 2-2I5, 2-3C4,2-3C2, 2-3C1, 2-2C4,2-2C3, 2-2Cl, 2-1I7 32 ALL POWER CABLE ¹347 ANACONOA 3TC ¹2 AWG CU 33 ALL POWER CABLE ¹3116 KERITE 3TC ¹10 AWG CU 34 ALL: POWER CABLE ¹3116 ESSEX 3 TC ¹10 AWG CV | |||
*See attached list for key Page ~of~ | |||
Donald C. Cook Nuclear Plant EP:NRC:00l53 Plant Model Submittal Component Equipment or Item No. S stem s+ Function No. Manufacturer T e 35 ALL CONTROL CABLE ¹ 3092 CONTINENTAL 4/C ¹19/12 AWG STRANDED CU 35 ALL CONTROL CABLE ¹ 3093 CONTINENTAL 7/C ¹19/12 AWG STRANDED CU 35 ALL CONTROL CABLE ¹ 3119 CONTINENTAL 2/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹ 3120 CONTINENTAL 4/C ¹12 AWG SOLID CU 35 ALL CONTROL CABLE ¹ 3121 'ONTINENTAL 7/C ¹12 AWG SOLID CU 35 ALL CONTROL CABLE ¹ 3122 CONTINENTAL 12/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹ 3123 CONTINENTAL 15/C ¹12 AWG SOLID CU 35 ALL CONTROL CABLE ¹ 3124 CONTINENTAL 4/C ¹7/18 AWG STRANDED CU 35 ALL CONTROL CABLE ¹ 3125 CONTINENTAL 7/C ¹7/18 AWG STRANDED CU 36 ALL INSTRUMENT CABLE ¹ 3073 RAYCHEM RG-11/U TRIAXIAL YELLOW 36 ALL INSTRUMENT CABLE ¹ 3074 RAYCHEM RG-11/U TRIAXIAL WHITE 36 ALL INSTRUMENT CABLE ¹ .3076 RAYCHEM RG-11/U TRIAXIAL BLAC | |||
*See attached list for key Page]0 of 18 | |||
e \ ~ ~ y ~ | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s | |||
* Function No. Manufacturer T e 36 ALL INSTRUMENT CABLE ¹ 3111 . RAYCHEM RG-11/U TRIAXIAL ORANGE 36 ALL INSTRUMENT CABLE ¹ 3112 RAYCHEM RG-11/U TRIAXIAL BLUE 37 ALL INSTRUMENT CABLE ¹ 3075 SAMUEL MOORE & CO. ¹16 AWG TSP 37 ALL INSTRUMENT CABLE ¹ 3077 SAMUEL MOORE & CO. ¹16 AWG TSQ 38 ALL INSTRUMENT CABLE ¹ 3O77 CERRO WIRE & CABLE CO 416 AWG TSQ 39 ALL POWER CABLE TERM I NATIONS N/A N/A SOLID KAPTON SPLICED TO STRANDED KAPTON | |||
*See attached list for key Page ~of~ | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or It'em No. S stem s | |||
* Function No. Manufacturer T e 40 ALL POWER CABLE N/A N/A STRANDED KAPTON TERMINATIONS SPLICED TO STRANDED HYPALON 41 ALL POWER CABLE N/A N/A N/A TERMINATIONS AT VALVE MOTORS AND HYDROGEN RECOMB INERS 42 ALL CONTROL CABLE N/A N/A SOLID KAPTON SPLICED TERM I NATIONS TO STRANDED KAPTON 43 ALL CONTROL CABLE N/A N/A STRANDED KAPTON TERMINATIONS SPLICED TO SOLID XL POLYETHYLENE ALL . CONTROL CABLE N/A N/A STRANDED KAPTON TERMINATIONS SPLICED TO STRANDED EPR-HYPALON ALL CONTROL CABLE N/A N/A N/A TERMI NATIONS 'AT TERMINAL BOXES 46 (Deleted) (Deleted) (Deleted) (Deleted) (Deleted) | |||
ALL . INSTRUMENT CABLE N/A N/A N/A TERMINATIONS AT, BARTON INSTRUMENTS | |||
*See attached list for key Page 12oflg | |||
Donald C. Cook Nuc1ear P1ant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s | |||
* Function No. Manufacturer T e 48 ALL INSTRUMENT CABLE N/A N/A N/A TERMINATIONS AT RTD's 49 ALL INSTRUMENT CABLE N/A N/A TERMINATIONS AT ELECTR ICAL PENETRATIO S N/A N/A N/A 50 ALL INSTRUMENT CABLE SPLICES TO ELECTRI-CAL PENETRATIONS 51 HYDROGEN RE- REDUCE HYDROGEN COMB INERS CONCENTRATION 2-HRl, 2-HR2 WESTINGHOUSE PHY2050-1 52 CONTAINMENT AIR REDUCE HYDROGEN 2-CEQl PHY2050-1 WESTINGHOUSE RECIRCULATION CONCENTRATION AND FAN MOTORS RECIRCULATE CON-TAINMENT AIR 52 CONTAINMENT AIR REDUCE HYDROGEN 2-CEQ2 WESTINGHOUSE PHY2050-2 | |||
'ECIRCULATION CONCENTRATION AND FAN MOTORS RECIRCULATE CON-TAINMENT AIR | |||
*See attached list for key P>ge 13o 18 | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Pl ant Model | |||
'Submittal Component Equipment or Item No. S stem s + Function No. Manufacturer T e 53 BORON INJECTION MOTOR OPERATED IMO-51 L IMITORQUE SM8-00 VALVE 53 BORON INJECTION MOTOR OPERATED VALVE IMO-52 L IMITORQUE SHB-00 53 BORON INJECTION HOTOR OPERATED IMO-53 L IMITORQUE SMB-00 VALVE 53 BORON INJECTION MOTOR OPERATED IMO-54 L IMITORQUE SMB-00 VALVE CONTAINMENT ISO- MOTOR OPERATED QCM-250 L IMITORQUE SMB-00 LATION VALVE | |||
~ | |||
54 CONTAINMENT MOTOR OPERATED VMO-101 LIMITORQUE SMB-000 HYDROGEN SUCTION DAMPER CONTROL AND AIR RECIR-CULATION 54 CONTAINMENT MOTOR OPERATED VHO-102 L IMITORQUE SMB-000 HYDROGEN SUCTION DAMPER CONTROL AND AIR RECIR-CULATION | |||
*See attached list for key Page 1< or | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component'unction Equipment or I te'm No. S stem s ~ No. Manufacturer T e 55 SI MOTOR OPERATED It 10-315 L IMITORQUE SMB-1 VALVE 55 SI MOTOR OPERATED IMO-316 LIMITORQUE SMB-1 VALVE SI MOTOR OPERATED IMO-325 LIMITORQUE SMB-1 55'5 VALVE SI MOTOR OPERATED IMO-326 L IMITORQUE SMB-1 VALVE RHR iOTOR OPERATED IMO-128 L IMITORQUE SMB-1 | |||
~VALVE 56 CONTAINMENT MOTOR OPERATED ISOLATION VALVE ICM-129 L IMITORQUE SMB-1 56 CONTAINMENT MOTOR OPERATED ICM-111 L IMITORQUE SMB-2 ISOLATION VALVE 56 RHR AND CONTAIN- MOTOR OPERATED ICM-305 LIMITORQUE SMB-2 MENT ISOLATION VALVE | |||
~ 56 RHR AND CONTAIN~ MOTOR OPERATED IQ1-306 L IM ITORQUE SMB-2 MENT ISOLATION VALVE | |||
*See attached list for key PagelS of 18 | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s | |||
* Function No. Manufacturer T e 57 8 58 REACTOR COOLANT NARROW RANGE NTP-110",*111, 120, ROSEMOUNT INC. 176 KF RESISTANCE 121, 130".*131, 140+ AND TEMPERATURE 141, 21(f," 211, 220." H.E. SOSTMAN 5 CO. 118 34 B-DETECTORS 221, 230, 231, 240, 241 57 8I 58 REACTOR COOLANT WIDE RANGE TEM- NTR-110, 120, 130, ROSEMOUNT INC. 176 KS PERATURE DETECTORS 140, 210, 220, 230, AND 240 -H. E. SOSTMAN 5 .CO. 11901 B 59 REACTOR COOLANT PRESSURIZER NPP-151, 152, 153g ITT BARTON 763 PRESSURE TRANS- NPS 153 MITTERS 59 QEN4 GENERATOR .,WARROW Rma BVEL BLP-110, ill, 112, ITT BARTON 764 TRANSMITTERS 120, 121, 122, 130, 131, 132, 140, 141, 142 60 REACTOR COOLANT WIDE RANGE NPS-121, 122 ITT BARTON 763 PRESSURE TRANS-MITTERS 60 REACTOR COOLANT PRESSURIZER LEVEL NLP-151, 152, 153 ITT BARTON 764 TRANSMITTERS | |||
*See attached list for key Pago I6 of IB | |||
** In-place spares which perform no function, | |||
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s | |||
* Function No. Manufacturer T e TEQ1 GENERATOR STEAM GENERATOR 60 NARROW RANGE LEVEL BLP-110, 111, 112, ITT BARTON 764 TRANSMITTERS 120, 121, 122, 130, 131, 132, 140, 141, 142 61 REACTOR COOLANT PRESSURIZER NPP-151, 152, 153 ITT BARTON 763 PRESSURE TRANS- NPS-153 MITTERS 61 REACTOR COOLANT NARROW RANGE BLP-110, ill, 112; ITT BARTON 764 LEVEL TRANSMITTERS 120, 121, 122, 130, 131, 132, 140, 141, 142 61 MAIN STEAM MAIN STEAM FLOW MFC-110, ill, 121, 130, ITT BARTON 764 CONTROLLERS 120, 131, 140% 141 62 REACTOR COOLANT WIDE RANGE NPS-121, .122 ITT BARTON 763 PRESSURE TRANS-MITTERS 62 REACTOR COOLANT PRESSURIZER LEVEL NLP-151, 152, ITT BARTON 764 TRANSMITTERS 153 STEAM GENERATOR STEAN GENERATOR 62 NARROW RANGE LEVEL BLP-110, 111, 112, ITT BARTON 764 TRANSMITTERS 120, 121, 122, 130, 131, 132, 140, 141, 142 | |||
*See attached 1)st for key page >>Or Ig | |||
KEY TO APPENDIX B NOMENCLATURE UNDER THE SYSTEM S HEADING ALL The rationale for saying "All" under the system head-ing column is as follows: | |||
: 1. Containment Electrical Penetrations serve all elec-trical equipment inside the containment. | |||
: 2. Cable and cable terminations of different manufac-turers and types listed have been used to serve the various safety related equipment inside the reactor containment, subject to the cables and the cable terminations being qualified for operation in a post-accident containment environment. | |||
SI Intermediate and low head safety injection RHR Residual heat removal, used as low'head safety injection Page 18 of 18}} |
Latest revision as of 02:02, 4 February 2020
ML17318A366 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 10/15/1979 |
From: | Bien F INDIANA MICHIGAN POWER CO. |
To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
References | |
NUDOCS 7910250420 | |
Download: ML17318A366 (45) | |
Text
0 INDIANA 5 MICHIGAN POWER COMPANY P. O. BOX 18 I
BO WL KG G R E EK STAT ION NEW YORK, N. f. 10004 October 15, 1979 AEP:NRC:00277 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2
, Docket Nos. 50-3'i5 and 50-316 License Nos; DPR-58 and DPR-74 Additional Information in Response to IE Bulletin 79-01 Mr. J. G. Keppler, Regional Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforce1l.nt Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
This letter and its attachments supply the information requested in Mr. R. F. Heishman's letter dated September 19, 1979 which we received on September 26, 1979. This information was requested in connection with the NRC Staff review of our submittal AEP:NRC:00153 dated June 28, 1979 in response to IE Bulletin 79-01. In a telephone conversation with Mr. J. I. Castresana of our staff on October 9, 1979, a member of your staff agreed to an extension until October 19, 1979 for 'the submittal of this response.
RESPONSE TO ITEM NO. 1 The information requested in Item No. 1 is supplied in tabular form as Attachment B. The first column of. the Attachment B table lists the item number as given in Attachment A, which itself is a revision to Attachment A of the AEP:NRC:00153 submittal. Attachment A was revised to:
Assign, to the equipment described, item numbers for the purpose of cross-indexing Attachments A and B; .
Supply the information requested in Item 5 of the enclosure to Mr. Heishman's,letter;
" Delete
, equipment items 23 and 46 because Foxboro in containment are no longer required for either instruments Engineered Safety Features actuation or long-term monitoring; It Modify the specified radiation dose for equipment items 24 and 51 to be consistent with the time requirement of FSAR Table 7.5-2; A@K QGWL '.
g78
)og5o 9m~
,e Mr. J. G. Keppler, Ditor l:NRC:00277 Modify the specified radi ati on dose for equi pment item 32 to be consistent with that for item 3 ;
Correct the mi ss pel 1 i ng of a suppl i er ' name in equipment items 57 and 58 ;
Modify i nformati on given for equi pment i tems 57 and 58 to make it consistent with statements i n the r eferenced test report ;
Corr ect a typographi cal error in the specified rad i ati on dose for equipment item 59 ;
I Modify the specified radiation dose for equipment items 60 and 62 to correspond with the more conservative calculation reported in Reference 30. The dose originally listed was from an earlier report which gave a calculated dose for one month only.
These changes are essentially merely editorial in nature or. made to preserve consistency with previously submitted information. Our con-clusion remains valid that all the equipment listed in Attachments A and B is adequately qualified to perform its safety-related functions.
RESPONSE TO ITEM NO. 2 The methodology used to verify that the equipment items described. in our response are, in fact, installed in the Donald C. Cook Nuclear Plant and are the same as the items for which qualification data exists, is based on a comprehensive equipment identification and control program that was and is used throughout the engineering, design, procurement, installation and checkout of the plant.
This program provides for the assignment of a unique identification number (plant equipment number) to each item during the design phase.
This identification is shown on design drawings, procurement documents, the items themselves when shipped from the vendor, receipt inspection documents, material issue records, installation inspection records and checkout and test records.
gualification documentation is checked to verify that the qualifi-cation does meet requirements set forth in the engineering specifications for the item, and that the qualification is applicable to the item furnished.
Verification that the item called out in design drawings was, in fact. installed is obtained by two independent sets of inspections.
The first are the gC inspections conducted during the installation phase to verify conformance to design documents. The second are the inspections conducted prior to and during the checkout and test phase again to verify conformance to design documents and equipment operability.
~;. Mr. J. G. Keppler, Di) or w3w NRC:00277 The list of items contained in our response was developed utilizing verified design documents and installation inspection records.
During the preparation of responses to earlier NRC requests, we have performed additional in-plant inspections on certain items to verify their existence and the acceptability of qualification docu-mentation. In each case, no non-conformances were found.
RESPONSE TO ITEM NO. 3 The limit switches which provide position indication of the air-operated safety-related valves inside containment are not needed to activate any Engineered Safety Features or for long-term post-accident nonitoring. For this reason, these limit switches are not considered part of the safeguards systems and have not been subjected to environ-mental testing. The limit switches for the air-operated containment isolation valves inside the containment are Namco Controls Models D2400 and SL4. Neither of these models was identified in IE Bulletins 78-04 or 79-01. The Plant equipment numbers for these valves are VCR-ll, 21, 101, 102, 103, 104, 105, 106 and 107.
Limit switches for safety-related motor-operated valves inside the containment are part of the valve operators and are qualified under the same test r epor ts as the motors and valve operators themselves . No separate model or equipment numbers are assigned to these limit switches.
The test reports were identified in the AEP:NRC:00153 submittal.
RESPONSE TO ITEM NO. 4 We have responded to IE Bulletin 79-01A in our submittal AEP:NRC:00153A dated September 7, 1979.
RESPONSE TO ITEM NO. 5 Attachment A to this letter is a revision to Attachment A to the AEP:NRC:00153 submittal. This revision includes the replacement of the phrase "long term" in each case with a specific post-accident time period during which the equipment described is assumed to be needed for operation with respect to its safety-related function. The time period information shown does not necessarily reflect the accident scenario timing but was specified according to the additional consideration that cables, ter-minations, splices and similar components should not be the limiting devices in the operation of safety-related circuits.
Very truly yours, FNB:em F. N. Bien attachments Vice President cc: (attached)
~ .'r. J. G. Keppler, Director AE .FIRC:00277 cc: Norman C. Noseley - NRC R. C. Callen G. Charnoff D. V. Shaller - Bridgman R. S. Hunter R. W. Jurgensen
DONALD C. COOK NUCLEAR PLANT UNITS NO. 1 & 2 ATTACHl'IENT A AEP:NRC:00277
PLANT NAMEc ENVIRONMENT (LOCATION)
TIME DOCi QUAL'ETllODi I'TEM EQUIPMENT DESCRIPTION REQ'o PARAMETER SPECe QUAL, REFi~ REMARKS 1 Year L>e 0.1'<lt e Temp. (oF) 2()0 OP Press. (psia) 122 Rel. Hum. l00! 100'v Radiation 'a {)0 l00 Chem. ac3.(
2000. o no 2 Electrical Year SC <ll ilto Temp. (oF) 1,3 Pe etvations P{>0 84O Press,(psia) 116 Rcl; Hum;. 100 l00 '>
Radiation Hr> t)o 1.00 Chem.
2000oo~al3 "0nP)>)>',!! B l Year 'Temp. {oF)
Si!'!Ulo
- ?()0 >40 Press. (psia) gC Rel. Hum. .100" l00'00 Radiation 1'0
)
Chem. ..i >)>f>'s>
,".000 an:!9 E l Year Tempo (OF) i)3.lll)lle 2{'>0 Press. (psia) s5.5 127 7 Rcl. Hum. l00 j' 100$
Radiation (i(r a 150 ,".00 Chem. 2000 ppmB C'I This list is a compilation of items by component.
Do not list the same type of component more than once. SHEET 1 OF 19
~ ~
Use limiting environment whore morc than one applies.
~ Use ANAL> TEST. SEQ.> SIMUL.> ONGOING, or OTl!ER for entries into this space, ATTACllHENT A
PLhNT NhHEI ENVIRONMENT (LOCATION)
TIME DOC ITEM EQUIPMENT DESCRIPTION REQ'Do SPEC, QUAL'UAL'ETIIOD+ REF~*'EMARKS ogre C. ble- Qn(. ~
Ke ite Co. Temp. (oF) ;)C)0 ') ')5 16 month Press. (psia) 35. 5 C) 7 exposure to Rel. IIum. 3.00 lOO;! accident Radiation (~.tr. I) 12p lP.O environment
'hem.
of):j
- )OOOPP. !13 Dl~
()')
Control Cable- 1 Year ue(r ~
Temp (oF)
Continental Uire 260 I.5 6 Cable Co. Press.(psia) 35 3.(~1. 7 Bol; IIum: 100 j~ 1.001m'50 Chem. 20')0 pp!ao Tl?il Y( ar Se(. n
~
Temp. (oF)
PRO Press. (psia) 3.21.
Rel. IIum.
Radiation (.< > > 1.50 Chem. ppu!
OOOO tnnB
.Instrument Cable- 1 Year '57 uimU1 Temp. (oF)
Havrhem Cor .
Press. (psia) 35 5 OII.. 7 Rel. Hum. 100g~ 100 j~
Radiation (I.(ra .,) 1 50 200 Chem.
This list is a compilation of items by component.
Da not list the same type of component more than once. SIIEET 2 OF 19 Use limiting environment where more than one applies.
Use ANM., TEST, SEQ.> SIMUL.> ONGOING, or OTIIER for entries into this space. ATTACIIMENT A
. PLANT N@gald C~ Cook Nuclear Plant Unit 1 ENVIRONMENT (LOCATION)
TIME DOC QUAL'ETHOD~
ITEM EQUIPMENT DESCRIPTION REQo D PARAMETER SPEC, QUAL, i etio is. 1 Year Temp. (oF)
Sogf REF~*'4
( 260 40 er to <tran(led Press. (psia)
H 1o Rel. Hum. 1.00,'i Radiation (~t .,
- 1) ()0 1(0 Chem. c'g ppln not .ro~.'d n r Po>rer Cable 'Eerminatio is 1 Year Sc~! ~
at motors and Temp. (oF) 260 3>>O
'll dro.'en Becombiner Pres . (psia) 35.5 Rcl; Ilurn; 100;"o')
Radiation (H>., 1.00'p'n 1.50 Chem. "..000 ppm.'3 1 h I Control Cable 1 Year
'Eerminations- Temp. (oF) 34.0 Solid Ka ton S 19.c.ct Press. (psia) 35 5 ~
to Stranded Kapton Rcl. Hum. 100/~0 Radiation Chem. 2500 ppmD 16 1 Year Temp. (oF) 345 Press. (psia)
Rcl .. Hum.
Radiation(wra,, ()0 150 Chem. 25 PPgm18 rlt 'i'o($ 'i '(1 This list is a compilation of items by component.
Do not list the same type of component more than once. SHEET 4 OF lg Use limiting environment where more than one applies.
~ Usc ANAL'EST, SEQ.~ SIMUL.> ONGOING, or OTHER for entries into this space. ATTACHMENT A
0 PLANT NAMEi ENVIRONMENT (LOCATION)
TIME QUAL, DOCi ITEM EQUIPMENT DESCRIPTION REQ'D.'ARAMETER SPECo QUAL~ METHOD* REF>+ 'EMARKS 17 Control Cable l. Year Senarate 1'j, 8 Terminations- Temp. (oF) ~60 340 Stranded Ka ton s 1.iced Press.(psia) 120 Bel. Hum. 1.00,".)
I[ a1.on Radiation ~i. 1 fj0 Chem.
not .ro~!cl 2y()g y.;>
Temp. (oF)
Press.(psia)
Rel.'um;.
Radiation. )(
Chem.
18 Control Cable 1 Year Gonarate l3t, 5 j Temp. (oF)
Terminations- 345 at terminal boxes Press. (psia) 84.7 35 5 Rel. Hum. 100 p~i RadlatLOQ graf ~
) 1 $0 150 Chem. ;?000 pomO ppm 1 Year Temp, (oF) 345 Press. (psia) n)
Rol. Hum. 1.00'u Radiation 150 (I%i~(:
Chem. 2 50( 2>)gl,"p OOOO nn>>H This list is a compilation of items by component.
Do not list the same type of component more than once. SHEET 5 OF19 Use limiting environment whore moro than one applies.
this ATTACHMENT A Use ANALi TEST i SEQ ~ SIMUL p ONGOING i or OTHER for entries into space.
)
PLANT NAME<
i ENVIRONMENT (LOCATION)
TIME QUAL>> DOC>>
ITEM EQUIPMENT DESCRIPTIOM REQ'D>> PARAMETER SPEC>> METHOD'~ REF>* 'EMARKS 20 .1 ear 14 8 10 11 12
.Temp. {oF 345 Press.(psia) ni Rel. Hum.
Rad1a tiog ira('I }
~ 150 Chem.
21 1 Year Temp>> {oF)
Press.(psia)
Rel; Hum'.. 1 00/4 100'>>
Radiation (I,;r~ I} 60 1/0 Chem ~ '-OQ ppmB 22 1 Year
'Temp. (oF)
Press. (psia)
Rel. Hum. (Q Radiation (I jy ~ \} '60 150 Chem.
9000 nmB 2500 pp.",sD (Deleted) (Deleted 'Deleted) (Deleted Temp. (oF)
Press. (psia)
Rel. Hum.
RadiatioyI r.<.
Chem.
This list is a compilation of items hy component.
Do not list the same type of component more than once. SHEET OF 19 Use limiting environment vhere moro than one applies.
for entries into this space, ATTACHMENT A
~ Use ANAL, TEST, SEQ.>> SIMUL.) ONGOING, or OTHER
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PLANT NAME> Donald C. Cook Nuclear P1ant U it 1 .
ENVIRONMENT (LOCATION)
TIME QUAL, DOCi EQUIPMENT DESCRIPTION REQ'O. PARAMETER SPEC, QUAL, METHOD~
REF>*'ru V .ve 1 da Sen. 16 o IIO o s- Temp.,(oF) .".60 SIIB- and motor contr Press.(psia) <np cable terminations Rel. Hum. 3.00'v Radiation (- I> i.) ".6 Chem.
"000 n .n 13
-p-,i'np n Limitorrue Valve 1 dav Sc ilrat 8 22 0 erator Iiotors Temp. (oF) >>)0 PGO SIR-1 SIQ-2 and motor Press.(psia) 1 1 / 07 control cable termina- Rcl; Hum;; 100 "i 100'~
tions Radiation 1.-) 2~')
Chem. ",000 zamB 2600 ppm Temp. (oF)
Press. (p 'ia)
Rel. Hu)n.
Radiation Chem.
Temp (oF)
Press. (psia)
Rel. Hum.
Radiation Chem.
This list is a compilation of items by component.
Do not list the same type of component more than once. gl SHEET 8 OF l Use limiting environment where more than one applies. 4
~ Usu ANAL< TEST, SEQ.) SIMUL.p ONGOING, or OTHER for entries into this space. ATTACHMENT A
pr.awe Nanei Dbnald C. Cook Nuclear Plant Unit 2 ..
I ENVIRONMENT (LOCATION)
TIME QUALe DOC ITEM EQUIPMENT DESCRIPTION REQt D PMUQKTER SPECe QUALe METHOD* REF~*
Ki h Volta e Electrical 1 Year Se arate Penetrations Temp (oF) 328.2 346.
Press. (psia) 29.1 Rel. Hum. 100~ 100K Radiation(grad 60 100 Chem. 2000 ppn B 0 lca 1 Electrical Penetrations 1 ear Separate 1 3 Temp (oF) 328. 2 340 Press.(psia) 29.1 116 Rel; Hum; 100K 100K Rad ai t ion( fgra d) 60 100 Chem. 2000 ppm B 2098 ppm B Power Cable- Simul.
Temp. (oF) 328.2 340 Anaconda Wire and Cable Press. (p in) 29.1 119.7 Rel. Hum. 100m lOOX Radiation( firad) 150 200 Chem. 2000 ppm B 00pmB Power Cable- 6 HOnths Seq. '6 month Kerite Co. Temp. (oF) 328.2 325 exposure in Press. (psia) 29.1 96.7 accident Rcl. Hum. 100~ 100K environment Radiation()trad) 120t 120 Chem. 200.0 ppii; .8, pram This list is a compilation of items by component.
Do not list the same type of component more than once.
SHEET~OF~
Use limiting environment where more than one applies.
i ATTACHMENT A Use ANALP TESTP SEQ., SIMUL.) ONGOING, or OTHER for entries into this space.
P?JQft NANEt Oonald C. Cook Nuclear Plant Unit.2 ENVIRONMENT (LOCATION) '
TIME QUALi DOC ITEM EQUIPMENT DESCRIPTION REQ'Di PARAMETER SPECi QUAL, METHOD+ REF~*'5 REMARKS 34 Power Cable- I year Simul .
Essex Internati'onal Temp, (oF 328.2 346 .
Press.(psia) 29.1 127.7 Rel. Hum. 100Ã 100K Radiation(Hrad 150 200 Chem. 2000 ppm B H 9-PII7 35 Control Cable- 1 year Seq.
Continental Wire and Cable Temp (oF) 328.2 345 Company Press.(psia) 29.1 121.7 Rel; Hum;- 100% l 00'X Radia tion((frad 1 50 150 Chem. 2000 ppm 0 IIP[0 36 Instrument Cable- 1 ear Simul.
Raychem Corp. Temp. (oF) 328.2 357 Press. (paia) 29.1 84. 7 Rel. Hum. 100K 100K Itadiation(grad 150 200 Chem. 2000 ppm B nH 9. -11 37 Instrument Cable- 1 year Separate 10,11 Samuel tloore 5 Co. Tempi (oF) 328.2 340 Press. (psia) 29.1 119.7 Rol. Hum. 100K 100/i Radiation Hrad 150 200 Chem. 2000 ppm.B p 0"(!
This liat is a compilation of items by component.
Do not list the same type of component: more than once. SHEET 10 OF 19 Use llmi.ting environment where moro than one applies.
i Usu ANAL> TEST> SEQ.p SIMUL.p ONGOING> or OTHER for entries into this space. ATTACIINHNT A
0 ar P nt Unit 2 ENVIRONMENT (LOCATION)
TIME DOC, ITEM EQUIPMENT DESCRIPTION REQ'o PARAMETER SPEC, QUAL+
QUAL'ETHOD~
REP~~
'2 Instrument Cable- 1 year Seq.
Cerro Wire and Cable Co. Temp (op 328.2 346 Press.(psia) 29.1 127.7 Rel. Hum. lOOX 100K Radiation tedllad 50 200 Chem. 2000 pptR B 39 Power Cable Terminations- 1 year Seq. 13 Solid Kapton Spliced to Temp. (oF) 328.2 340 tetrad Stranded Kapton Press.(psia) 29.1 118 Rel:. Hum; 100Ã 100K Radia tion( 60 60 Chem. Not Req'd tpm 40 Power Cable Terminations- 1 year Se . 13 Stranded Kapton Spliced to, Temp. (oF) 328.2 -
340 Stranded Hypalon Press. (psia) 29.1 118 Rel. Hum. 100K 100K Radiatio Yirad ~
60 150 Chem. Not Req'd )l 9.
41 Power Cable Terminations.- 1 year Seq. 13 At flotors and Hydrogen Temp. (oF) 250 340 Recombiner Press. (psia) 29.1 118 Rel. Hum. 100K 100K Radiatior(Hrad) 150 ~
150 Chem. 2000 ppm B This list is a compilation of items by component.
Do not list the same type of component more than once. ~l SHEErll OZ l9 I
Use limitinq environment where more than one applies.
~
~ Use ANAL, TEST, SEQ.i SIMUL.p ONGOINGi or OTHER for entries into this space. ATTAC(jMENT A
PLANT NAME!
ENVIRONMENT (LOCATION)
TIME QUAL, DOCi
~ ITEM EQUIPMENT DESCRIPTION BEQ'o PARAMETER SPEC+ QUAL+ METllOD*
REF~~'ontrol Cable Terminations- 1 Year Se . 13 Solid Kapton Spliced to Temp (oF 328.2 340 .
Stranded Kapton Press.(psia) 29.1 118 Bel. Hum. 100K 100K Radiation(Iirad 60 60 Chem. Not Req'd Control Cable Terminations- 1 Year Se arate 14 8 Stranded Kapton Spliced Temp. (oF) 328.2 345
' to Solid XLpolyethylene Press.(psia) 29.1 84.7 Bel.. Hum; 100K lOOX Radiation(tlrad 60 150 Chem. Not Req'd A 9-10 Control Cable Terminations- 1 Year Se arate 15 8 Stranded Kapton Spliced to Temp. (oF) 328.2 340 Stranded EPR - Hypalon Press. (psia) 29.1 120 Bel. Hum. 100K 100K Radiation(flrad 60 150 Chem. Not Req'd @70 Temp. (oF)
Pxess. (psia)
Bel. Hum.
Radiation t1rad Chem.
This list is a compilation of items by component.
Do not list the same type of component more than once.
SHEET12 OF19 Use limiting environment where more than one applies.
this ATTACllMENT A ANALt TESTe SEQ i SIMVL y ONGOING'r OTHER for entries into space.
Pacer NAME< Donald C. Cook Nuclear Plant Unit 2 ENVIRONMENT (LOCATION) l TIME QUAL, DOCo
~
ITEM EQUIPMENT DESCRIPTION REQ'o PARAMETER SPEC+ QUAL+ METHODS REF!*
Control Cable Terminations- Ye r Separate -
14 8 At Terminal Boxes Temp. (oF) 328.2 345 Press.(psia) 29.1 84.7 Rcl. Hum. 100$ 100l Radiation(Hrad 150 150 Chem. 2000 ppm B pH (Deleted' (d el e ted ) (Deleted) (Deleted)
Temp. (oF)
Pross.(psia)
Rcl. Hum; Ra@lotion(Nrad Chem.
Instrument Cable 1 Year Se arate 8i9il0illi12il4 Terminations- Temp. (oF) 328.2 345 Barton Instrument press. (psia) 29.1 84.7 Connections Rcl. Hum. 100K 100".o Rodiatio Yirad 150 150 Chem. 2000 ppm B 50 nnm
)I 1 0 .
Instrument Cable 1Yar 5'45 Separate 8 9 t 10 p ll 12 t t Terminations- Temp. (oF) 328.2 RTO Connections Pres . (psia) 29.1 84. 7 Rcl. Hum. 100'1o 100Ã Radiatio t1rad 150 150 Chem. 500 p 2000 ppm -B i H 9.f-'io.
This list is a compilation of items by component.
Do not list the same type of component more than once. SHEET~OF 19 Use limiting environment +here moro than one applies.
i Uso ANAL, TEST, SEQ.i SIMUL.~ ONGOING, or OTHER for entries into this space. ATTACHMENT A
PLANT Nues Donald C. Cook Nuclear Plant Unit 2 ENVIRONMENT (LOCATION) ~
TIME QUAL, DOC, ITEM EQUIPMENT DESCRIPTION REQ'Do PMUi1METER SPEC. QUAL, METHOD~ REF JI REMARKS Instrument Cable 1 Year Seq. 13 Terminations- Temp. (oF 328.2 340 At Electrical Penetrations Press.(psia) 29.1 118 Rcl. Hum. 100X 100X Radiatior{Mrad 60 150 Chem. Not Req'd
)l 3.5 0 Instrument Cable 1 Year Se arate Terminations- Temp. (oF) 328.2 340
. Splices to Electrical Press.(psia) 29.1 84.7 Penetrations Rcl; Hum; 100X 100X Raaiatio Mrad) 60 Chem. 2000 ppm B 40)'0 H
Hydrogen Recombiners l<onths Separate 20 Temp. (oF) 250 310 Press. (psia) 29.1 77 Rcl. Hum. 100@ 100X RaQiatior(Mrad ) 200 Chem. Not Req'd pI1 2 Fan Motors 1 Year Seq. 21 Temp. (oF) 250 320 Press. (psia) .: 29 1 89.7 Rcl.. Hum. 100X 100X Radiatio Mrad 150 200 Chem. Not. Req'd..
This list is a compilation of items by component.
no not list the same type of component more than once. SHEET 140F 19 Uso limiting environment whore moro than one applies.
i Uso ANAL> TEST, SEQ., SIMUL.~ ONGOING, or OTHER for entrios into this space. ATTACllHENT A
PLANT NAMEq Donald C. Cook Nuclear Plant Unit 2..
ENVIRONMENT (LOCATION)
TIME QUAL, DOC ITEM EQUIPMENT DESCRIPTION REQe D PARAMETER SPEC+ QUAL,= METHOD* REF~*'2 Limitorque 28 sec. Simul ..
Val ve Operator Hotors- Temp. (oF) 328.2 330 SMB-00 and motor contro Press.(psia) 29.1 104.7 cable terminations Rel. Hum. 100/o 100K Radiation Chem. 2000 ppm B Limitor ue 10 min. Se . 24 Valve Operator Hotors- Temp. (oF) 250 250
%MB-000 and motor contro Press.(psia) 29.1 39.7 cable terminations Rel.'. Itum; 100K 100 jJ Radia tio Hrad 3.9 204 Chem. Not Req'd Not Req'd Limitor ue 1 da Seq. 16 Valve Operator Motor's- Temp. (oF) 250 315 SMB-land motor control Press. (psia) 29.1 84.7 cable terminations Rel. Hum. 100K 100K Radiation Hrad 26 204 Chem. 2000 ppm B 19 56 Limitor ue 1 day Separate 23 22 Valve Operator Motors - . Temp. (oF) 328.2 340 SI'$-1, SMB-2 and motor Press. (psia) 29.1 119.7 control cable terminat'ons Rol. Hum. 100K ~
100K Radiation ra 204 Chem. 2000 pp01.B 2622 ppm This list is a compilation of items by component.
Do not list the same type of component more than once. SHEET 15OF 19 Use limiting environment where more than one applies.
i Uso ANAL, TEST, SEQ.) SIMUL.) ONGOING, or OTHER for entries into this space. ATTACIIHENT A
II 'I ~ I ~ ~
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PLANT NAMEl DONALD C e COOK NUCLEAR PLA 2 ENVIRONMENT (MCATION)
TIME ITEM EQUIPMENT DESCRIPTION REQ'>> SPEC, QUAL'UAL~ METtton~
DOC REF t*'9 ITT Barton Pressure and hor Differential Pressure Temp. (oF) 30 Term SF. SEP Transmitters Press.(psia) 29.1 89.7 14.4 Models 763 f'64 Rel. ltum. 100% 100~ 0'k Radiatio Mrad .07 2.5 per 50 l>our Chem. 1.14't boric acid 1.14 'L boric acid/0
.15'- NaOU nom .17'; NaOlf 60 ITT Barton Pressure and LOCA Differential Pressure Temp. (oF) 160 320 SEQ. 30 Transmitters 4 months Press.(psia) 14.4 89.7 Models 763 f* 764 Rol; llum:. 100% 1001 Radia t ion( 40 50 1.14t boric acid 1.14 a borne acid
.15% NaOll {nom), .17'4 NaOH 61 Pressure and Short MSLB Unit 1 Unit 2 Temp. (oF)
Differential Pressure Term 260 328.2 360 SE 30 Transmitters 1 sec)
Press. (psia) 35 5/29 8<).7
(
Models 763 & 764 Rcl. llum. 100't/100% 100%
Radiatiog< .04/.04 50 Chem. 1.14>> boric acid 1.14 a boric acid
.154 aOh nom =.17L NaOH ITT Barton Pressure and MSLB Unit 1 Unit 2 Tempo (OF)
Pressure 'ifferential 2'60 328.2 360 SE 30 Transmitters 4 months "35 5/29 1 89.7 Models 763 f; 764 Rel. Hum. '00'h/100'h 100%
Radiation(M r 6/4.6 50 Chem, 1.14'f
~
'boric acid 15'f Nanll no
)'.14 a boric
. 17'L NaOff acid This list is a compilation of items by component.
Do not list the same type of component more than once. SHEET~F~9 Use limiting environment where moro than one applies.
Use ANM, TESTi SEQ., SIMUL., ONGOING, or OTIIL'R for entries into this sPace. AITACttAENT A
Document References Cited In Attachment A Conax Corp. Test Report IPS- 234 20 Conax Corp. Test Report IPS-62.
3~ Conax Corp. Test Report IPS-137.
Conax Corp. Analysis Report IPS-324.
50 FIRL Test Report F-C3341.
- 6. FIRL Test Report F-C3694..
7 ~ Kerite Co. Test Report 75IPCEA-27-P.
- 8. Conax Corp. Test Report IPS-348.
- 9. FIHL Test Report F-C4033-1.
- 10. FIRL Test Report F-C3683.
- 11. Isomedix Corp. Test Report of May, 1976.
- 12. Cerro Wire and Cable Test Report of May, 1976.
- 13. Westinghouse-Canada Test Report CWAPD-332.
FIRL Test Report F-C4033-3.
- 15. Westinghouse-Canada Test Report CWAPD-326.
- 16. Limitorque Corp. Test Lab. Project $ 6004.56.
Conax Corp. Test Report IPS-326.
Conax Corp. Test Report IPS-327.
- 19. Conax Corp. Test Report IPS-329.
- 20. Westinghouse Corp. Test Report WCAP-7709-L, Suppl. 2.
.21. Westinghouse Corp. Test Report WCAP-7829.
22 ~ Limitorque Corp. Test Report $ 600198.
23 ~ Limitorque Corp. Test Report $ 600376A.
Limitorque Corp. Test Report $
Corp. Test Report of Nov. 1975.
600461.'somedix 25.
- 26. Foxboro Test Report TE-1013.
27 0 Westinghouse Electric Corp. Communication NS-PLC-5023 dated 4/26/78 from T. M. Anderson - Westinghouse to Z. G. Case - NRC.
- 28. Westinghouse Electric Corp. Test Report WCAP-9157
- 29. Automatic Switch Co. Report AQS 21678/TR 30 Westinghouse Electric Corp. Communication NS-TMA-)950 Sheet 18 of 19
GENERAL NOTES:
- 1. In situations where a qualification pressure was not explicitly stated and it was known that the test environment was steam, the saturation pressure of steam at the given test temperature was used.
- 2. All chemical concentrations noted as X are weight L.
19'f 19
DONALD C. COOK NUCLEAR PLANT UNITS NO. 1 L 2 ATTACHMENT B AEP:NRC:00277
'onald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s
- Function No. Manufacturer T e CONTAINMENT ELECTRICAL HIGH 1-1P6, 1-1P7, CONAX CORPORATION EP-1 ISOLATION VOLTAGE (4 kv) 1-2P5, 1-2P67 1-3P7 CONTAINMENT PENE- 1-3P8, 1-4P7, TRATION 1-4P8 ALL. ELECTRICAL LOW l-lPl, l-1P2, CONAX CORPORATION EP-2 through EP-13 VOLTAGE (600:V AND . 1-1P3, 1-1P4, BELOW) CONTAINMENT 1-2P2, 1-2P3, 1-4P2 PENE I RATION 1-2P4, 1-2P7,1-2PS 1-3P1, 1-3P2,1-3P3, 1-3P6, 1-4P3,1-4P4, 1-4P5, 1-4P6,1-4I5, 1-4I7, 1-4I8,1-4C2, 1-4C3, 1-4C1,1-4I6, 1-1C4, 1-1C1,1-1C3, 1-1I5, l-lI8,1-1I7, 1-1I6, 1-2I8,1-2I5, 1-2I6, 1-2C4,1-2C3, 1-2C1, 1-2I7,1-3I8, 1-3I6, 1-317,1-3C1, 1-3C2, 1-3C4,1-3I5 ALL POWER CABLE 0 347 ANACONDA 3TC II2 AWG CU ALL .. POWER CABLE 8 399 OKONITE 1/C f2 AWG CU ALL POWER CABLE II. 3116 KERITE 3TC 810 AWG CU ALL CONTROL CABLE 8 3092 CONTINENTAL -
Blidigh"'"'age
- See attached list for key ga aa
~of~
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s
- Function No. Manufacturer T e ALL CONTROL CABLE ¹3093 CONTINENTAL 7/C ¹19/12 AHG STRANDED CU ALL CONTROL CABLE ¹3119 CONTINENTAL 2/C ¹12 AWG SOLID Co ALL CONTROL CABLE ¹3120 CONTINENTAL 4/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹3121 CONTINENTAL 7/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹3122 CONTINENTAL 12/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹3123 CONTINENTAL 15/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹3124 CONTINENTAL 4/C ¹7/18 AWG ALL CONTROL CABLE ¹3125 CONTINENTAL 7/C ¹7/18 AHG STRANDED Ctj ALL CONTROL CABLE ¹3119 GENERAL ELECTRIC 2/C ¹12 AWG SOLID CO
- See attached list for key Page ~of~
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model ubmittal Component 'quipment or Item No. S stem s
- Function No. Manufacturer T e ALL CONTROL CABLE iO'120 GENERAL ELECTRIC 4/C g 12 AWG SOLID CU ALL CONTROL CABLE GENERAL ELECTRI 7/C g 12 AWG SOLID CU ALL CONTROL CABLE GENERAL ELECTRI 12/C g 12 AWG SOLID CU ALL CONTROL CABLE t5'123 GENERAL ELECTRI 15/C PP 12 AWG SOLID CU ALL INSTRUMENT CABLE 8 3O73 RAYCHEM RG-ll/U TRIAXIAL YELLOW ALL INSTRUMENT CABLE 0 3O74 RAYCHEM RG-ll/U TRIAXIAL
/1IITE 8 ALL INSTRUMENT CABLE 8 3O76 RAYCHEM RG-ll/U TRIAXIAL Bl ACK INSTRUMENT CABLE I: 3111 RG-ll/U BIAXIAL ALL. RAYCHEM ORANGE ALL INSTRUMENT CABLE 3112 RAYCHEM RG-ll/U TRIAXIAL 13LUE
- See attached list for key Page ~of 18
Oonald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s
- Function No. Manufacturer T e ALL INSTRUMENT CABLE 8 3O75 BOSTON INSULATED g 16 AWG TSP ALL INSTRUMENT CABLE 8 3O76 Bgl'IE )INSULATED RG-11/U TRIXIAL 10 ALL INSTRUMENT CABLE 0 3O75 SAMUEL MOORE gQ6 AWG TSP 5 CO ~
10 ALL INSTRUMENT CABLE g 3077 SAMUEL'OORE gl6 AWG TSQ
&: CO.
INSTRUMENT CABLE g 3077 CERRO WIRE &: g16 AWG TSQ CABLE COo 12 ALL POWER CABLE TER IINATIONS N/A SOLID KAPTON SPLICED TO STRANDED KAPTON 13 ALL POWER CABLE TERMINATIONS N/A N/A STRANDED KAPTON SPLICED TO STRANDED HYPALON ALL POWER CABLE TERMINATIONS AT VALVE MOTORS &:.
HYDROGEN BECOMBINERS N/A N/A N/A "15 ALL CONTROL CABLE TERMINATIONS N/A N/A SOLID KAPTON SPLICED TO STRAIIDED KAPTON
- See attached list for key Page 4 of 18
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s
- Function No. Manufacturer T e 16 ALL CONTROL CABLE TERMIHATIONS . N/A N/A STRANDED KAPTON SPLICED TO SOLID XL POLYETIIYLEHE 17 ALL CONTROL CABLE TERMINATIONS N/A N/A STRANDED KAPTON SPLICED TO STRANDED EPR IIYPALON 18 ALL CONTROL CABLE TERMINATIONS AT TERMINAL BOXES N/A N/A N/A 19 ALL INSTRUMENT CABLE TERMINATIONS AT BARTON INSTRUMENT N/A N/A N/A 20 ALL INSTRUMENT CABLE TERMINATIONS AT RTDiS N/A N/A N/A 21 INSTRUMENT CABLE TERMINATIONS AT ELECTRICAL PEHETRATIONS N/A N/A N/A 22 ALL INSTRUMENT CABLE SPLICES TO ELECTRICAL PEHETRATIONS N/A N/A N/A
- See attached list for key Page ~of 18 aa
~I
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stems* Function No. Manufacturer T e 23 (Deleted) (Deleted) (Deleted) (Deleted) (Deleted)
- See attached list for key Page 6 ot Z8
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s* Function No. Manufacturer T e 24 HYDROGEN RE<< REDUCE HYDROGEN COMBINERS CONCENTRATION 1-HR1, 1-HR2 WESTINGHOUSE CONTAINMENT AIR REDUCE HYDROGEN 1-CEQl, 1-CEQ2 PHY2050-1 25 RECIRCULATION CONCENTRATION AND PHY2050-2 FAN MOTORS RECIRCULATE CONTAIN-MENT AIR
'26 BORON INJECTION MOTOR OPERATED IMO-51 LIMITORQUE SMB-00 VALVE BORON INJECTION MOTOR OPERATED IMO-52 L IMITORQUE SMB-00 26 VALVE BORON INJECTION MOTOR OPERATED IMO-53 LIMITORQUE SMB-00 26 4
VALVE 26 BORON INJECTION MOTOR OPERATED
'VALVE IMO-54 L IMI TORQUE SMB-OQ 26 CONTAINMENT MOTOR OPERATED VALVE QCM-250 L IMITORQUE SMB-00 ISOLATION VMO-101 L IMITORQUE SMB-000 27 CONTAINMENT MOTOR OPERATED HYDROGEN CON- SUCTION DAMPER TROL AND AIR RECIRCULATION CONTAINMENT VMP;102 LIMITORQUE SMB-000
, 27 MOTOR OPERATED HYDROGEN CON- SUCTION DAMPER TROL AND AIR RECIRCULATION
- See attached list for key Page 7 of~]
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Node1 Submittal Component Equipment or Item No. S stems* Function No. Manufacturer T e INO-315 LINITORQUE SMB-1 28 SI MOTOR OPERATED VALVE IMO-316 L IMITORQUE SMB-1 28 SI MOTOR OPERATED VALVE IMO-325 L IMITORQUE SMB-1 28 SI MOTOR OPERATED VALVE INO-326 . L INITORQUE SNB-1 28 SI MOTOR OPERATED VALVE MOTOR OPERATED INO-128 L INITORQUE SNB-1 29 RHR VALVE 29 CONTAINMENT MOTOR OPERATED ICM-129 L IM I TORQUE SNB-1 ISOLATION VALVE ICM-111. L Ih1ITORQUE SNB-2 29 CONTAINhiENT NOTOP, OPERATED ISOLATION VALVE ICM-305 LINITORQUE SMB-2 29 RHR AND CONTAIN- MOTOR OPERATED MENT ISOLATION VALVE ICM-306 L IMITORQUE SMB-2 RHR AND CONTAIN- MOTOR OPERATED 29 VALVE MENT ISOLATION
- See attached list for key Page 8 of la
0 Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s
- Function No. Manufacturer T e CONTAINMENT ELECTRICAL HIGH 2-1P6, 2-1P7, 2-2P5 CONAX CORPORATION EP-1 30 ISOLATION VOLTAGE (4kV) 2-2P6, 2-3P7, CONTAINMENT 2-3P8, 2-4P7, PENETPAT IONS 2-4P8 ALL ELECTRICAL LOW VOL- 2-1P1, 2-1P2, CONAX CORPORATION EP-2 through EN3 31 TAGE (600V AND 2-1P3, 2-1P4, BELOW ) CONTAINMENT 2-2P2, 2-2P3, PENETRAT ION S 2-2P4, 2-2P7, 2-2P8, 2-3P1,2-3P2, 2-3P3, 2-3P6,2-4P2, 2-4P3, 2-4P4,2-4P5, 2-4P6, 2-4C1,2-4C2, 2-4C3, 2-1C1,2-1C3, 2-1C4, 2-4 I 5> 2-4 I 6, 2-4I7, 2-4I8,2-1I5, 2-1I6, 2-1I8,2-3I8, 2-3I7, 2-3I6,2-3I5, 2-2I8, 2-2I7,2-2I6, 2-2I5, 2-3C4,2-3C2, 2-3C1, 2-2C4,2-2C3, 2-2Cl, 2-1I7 32 ALL POWER CABLE ¹347 ANACONOA 3TC ¹2 AWG CU 33 ALL POWER CABLE ¹3116 KERITE 3TC ¹10 AWG CU 34 ALL: POWER CABLE ¹3116 ESSEX 3 TC ¹10 AWG CV
- See attached list for key Page ~of~
Donald C. Cook Nuclear Plant EP:NRC:00l53 Plant Model Submittal Component Equipment or Item No. S stem s+ Function No. Manufacturer T e 35 ALL CONTROL CABLE ¹ 3092 CONTINENTAL 4/C ¹19/12 AWG STRANDED CU 35 ALL CONTROL CABLE ¹ 3093 CONTINENTAL 7/C ¹19/12 AWG STRANDED CU 35 ALL CONTROL CABLE ¹ 3119 CONTINENTAL 2/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹ 3120 CONTINENTAL 4/C ¹12 AWG SOLID CU 35 ALL CONTROL CABLE ¹ 3121 'ONTINENTAL 7/C ¹12 AWG SOLID CU 35 ALL CONTROL CABLE ¹ 3122 CONTINENTAL 12/C ¹12 AWG SOLID CU ALL CONTROL CABLE ¹ 3123 CONTINENTAL 15/C ¹12 AWG SOLID CU 35 ALL CONTROL CABLE ¹ 3124 CONTINENTAL 4/C ¹7/18 AWG STRANDED CU 35 ALL CONTROL CABLE ¹ 3125 CONTINENTAL 7/C ¹7/18 AWG STRANDED CU 36 ALL INSTRUMENT CABLE ¹ 3073 RAYCHEM RG-11/U TRIAXIAL YELLOW 36 ALL INSTRUMENT CABLE ¹ 3074 RAYCHEM RG-11/U TRIAXIAL WHITE 36 ALL INSTRUMENT CABLE ¹ .3076 RAYCHEM RG-11/U TRIAXIAL BLAC
- See attached list for key Page]0 of 18
e \ ~ ~ y ~
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s
- Function No. Manufacturer T e 36 ALL INSTRUMENT CABLE ¹ 3111 . RAYCHEM RG-11/U TRIAXIAL ORANGE 36 ALL INSTRUMENT CABLE ¹ 3112 RAYCHEM RG-11/U TRIAXIAL BLUE 37 ALL INSTRUMENT CABLE ¹ 3075 SAMUEL MOORE & CO. ¹16 AWG TSP 37 ALL INSTRUMENT CABLE ¹ 3077 SAMUEL MOORE & CO. ¹16 AWG TSQ 38 ALL INSTRUMENT CABLE ¹ 3O77 CERRO WIRE & CABLE CO 416 AWG TSQ 39 ALL POWER CABLE TERM I NATIONS N/A N/A SOLID KAPTON SPLICED TO STRANDED KAPTON
- See attached list for key Page ~of~
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or It'em No. S stem s
- Function No. Manufacturer T e 40 ALL POWER CABLE N/A N/A STRANDED KAPTON TERMINATIONS SPLICED TO STRANDED HYPALON 41 ALL POWER CABLE N/A N/A N/A TERMINATIONS AT VALVE MOTORS AND HYDROGEN RECOMB INERS 42 ALL CONTROL CABLE N/A N/A SOLID KAPTON SPLICED TERM I NATIONS TO STRANDED KAPTON 43 ALL CONTROL CABLE N/A N/A STRANDED KAPTON TERMINATIONS SPLICED TO SOLID XL POLYETHYLENE ALL . CONTROL CABLE N/A N/A STRANDED KAPTON TERMINATIONS SPLICED TO STRANDED EPR-HYPALON ALL CONTROL CABLE N/A N/A N/A TERMI NATIONS 'AT TERMINAL BOXES 46 (Deleted) (Deleted) (Deleted) (Deleted) (Deleted)
ALL . INSTRUMENT CABLE N/A N/A N/A TERMINATIONS AT, BARTON INSTRUMENTS
- See attached list for key Page 12oflg
Donald C. Cook Nuc1ear P1ant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s
- Function No. Manufacturer T e 48 ALL INSTRUMENT CABLE N/A N/A N/A TERMINATIONS AT RTD's 49 ALL INSTRUMENT CABLE N/A N/A TERMINATIONS AT ELECTR ICAL PENETRATIO S N/A N/A N/A 50 ALL INSTRUMENT CABLE SPLICES TO ELECTRI-CAL PENETRATIONS 51 HYDROGEN RE- REDUCE HYDROGEN COMB INERS CONCENTRATION 2-HRl, 2-HR2 WESTINGHOUSE PHY2050-1 52 CONTAINMENT AIR REDUCE HYDROGEN 2-CEQl PHY2050-1 WESTINGHOUSE RECIRCULATION CONCENTRATION AND FAN MOTORS RECIRCULATE CON-TAINMENT AIR 52 CONTAINMENT AIR REDUCE HYDROGEN 2-CEQ2 WESTINGHOUSE PHY2050-2
'ECIRCULATION CONCENTRATION AND FAN MOTORS RECIRCULATE CON-TAINMENT AIR
- See attached list for key P>ge 13o 18
Donald C. Cook Nuclear Plant EP:NRC:00153 Pl ant Model
'Submittal Component Equipment or Item No. S stem s + Function No. Manufacturer T e 53 BORON INJECTION MOTOR OPERATED IMO-51 L IMITORQUE SM8-00 VALVE 53 BORON INJECTION MOTOR OPERATED VALVE IMO-52 L IMITORQUE SHB-00 53 BORON INJECTION HOTOR OPERATED IMO-53 L IMITORQUE SMB-00 VALVE 53 BORON INJECTION MOTOR OPERATED IMO-54 L IMITORQUE SMB-00 VALVE CONTAINMENT ISO- MOTOR OPERATED QCM-250 L IMITORQUE SMB-00 LATION VALVE
~
54 CONTAINMENT MOTOR OPERATED VMO-101 LIMITORQUE SMB-000 HYDROGEN SUCTION DAMPER CONTROL AND AIR RECIR-CULATION 54 CONTAINMENT MOTOR OPERATED VHO-102 L IMITORQUE SMB-000 HYDROGEN SUCTION DAMPER CONTROL AND AIR RECIR-CULATION
- See attached list for key Page 1< or
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component'unction Equipment or I te'm No. S stem s ~ No. Manufacturer T e 55 SI MOTOR OPERATED It 10-315 L IMITORQUE SMB-1 VALVE 55 SI MOTOR OPERATED IMO-316 LIMITORQUE SMB-1 VALVE SI MOTOR OPERATED IMO-325 LIMITORQUE SMB-1 55'5 VALVE SI MOTOR OPERATED IMO-326 L IMITORQUE SMB-1 VALVE RHR iOTOR OPERATED IMO-128 L IMITORQUE SMB-1
~VALVE 56 CONTAINMENT MOTOR OPERATED ISOLATION VALVE ICM-129 L IMITORQUE SMB-1 56 CONTAINMENT MOTOR OPERATED ICM-111 L IMITORQUE SMB-2 ISOLATION VALVE 56 RHR AND CONTAIN- MOTOR OPERATED ICM-305 LIMITORQUE SMB-2 MENT ISOLATION VALVE
~ 56 RHR AND CONTAIN~ MOTOR OPERATED IQ1-306 L IM ITORQUE SMB-2 MENT ISOLATION VALVE
- See attached list for key PagelS of 18
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s
- Function No. Manufacturer T e 57 8 58 REACTOR COOLANT NARROW RANGE NTP-110",*111, 120, ROSEMOUNT INC. 176 KF RESISTANCE 121, 130".*131, 140+ AND TEMPERATURE 141, 21(f," 211, 220." H.E. SOSTMAN 5 CO. 118 34 B-DETECTORS 221, 230, 231, 240, 241 57 8I 58 REACTOR COOLANT WIDE RANGE TEM- NTR-110, 120, 130, ROSEMOUNT INC. 176 KS PERATURE DETECTORS 140, 210, 220, 230, AND 240 -H. E. SOSTMAN 5 .CO. 11901 B 59 REACTOR COOLANT PRESSURIZER NPP-151, 152, 153g ITT BARTON 763 PRESSURE TRANS- NPS 153 MITTERS 59 QEN4 GENERATOR .,WARROW Rma BVEL BLP-110, ill, 112, ITT BARTON 764 TRANSMITTERS 120, 121, 122, 130, 131, 132, 140, 141, 142 60 REACTOR COOLANT WIDE RANGE NPS-121, 122 ITT BARTON 763 PRESSURE TRANS-MITTERS 60 REACTOR COOLANT PRESSURIZER LEVEL NLP-151, 152, 153 ITT BARTON 764 TRANSMITTERS
- See attached list for key Pago I6 of IB
- In-place spares which perform no function,
Donald C. Cook Nuclear Plant EP:NRC:00153 Plant Model Submittal Component Equipment or Item No. S stem s
- Function No. Manufacturer T e TEQ1 GENERATOR STEAM GENERATOR 60 NARROW RANGE LEVEL BLP-110, 111, 112, ITT BARTON 764 TRANSMITTERS 120, 121, 122, 130, 131, 132, 140, 141, 142 61 REACTOR COOLANT PRESSURIZER NPP-151, 152, 153 ITT BARTON 763 PRESSURE TRANS- NPS-153 MITTERS 61 REACTOR COOLANT NARROW RANGE BLP-110, ill, 112; ITT BARTON 764 LEVEL TRANSMITTERS 120, 121, 122, 130, 131, 132, 140, 141, 142 61 MAIN STEAM MAIN STEAM FLOW MFC-110, ill, 121, 130, ITT BARTON 764 CONTROLLERS 120, 131, 140% 141 62 REACTOR COOLANT WIDE RANGE NPS-121, .122 ITT BARTON 763 PRESSURE TRANS-MITTERS 62 REACTOR COOLANT PRESSURIZER LEVEL NLP-151, 152, ITT BARTON 764 TRANSMITTERS 153 STEAM GENERATOR STEAN GENERATOR 62 NARROW RANGE LEVEL BLP-110, 111, 112, ITT BARTON 764 TRANSMITTERS 120, 121, 122, 130, 131, 132, 140, 141, 142
- See attached 1)st for key page >>Or Ig
KEY TO APPENDIX B NOMENCLATURE UNDER THE SYSTEM S HEADING ALL The rationale for saying "All" under the system head-ing column is as follows:
- 1. Containment Electrical Penetrations serve all elec-trical equipment inside the containment.
- 2. Cable and cable terminations of different manufac-turers and types listed have been used to serve the various safety related equipment inside the reactor containment, subject to the cables and the cable terminations being qualified for operation in a post-accident containment environment.
SI Intermediate and low head safety injection RHR Residual heat removal, used as low'head safety injection Page 18 of 18