ML20112G469
| ML20112G469 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/31/1984 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20112G439 | List: |
| References | |
| PROC-841031-05, NUDOCS 8501160348 | |
| Download: ML20112G469 (200) | |
Text
{{#Wiki_filter:e- - sur. -- -_
,j_ , .
1 1 j
. 1 INSERVICE INSPECTION AND TESTING PROGRAM
, QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 COMMONWEALTH EDISON COMPANY Octo6EE. 19%4
$yl ge e Pm Owe 4
- TABLE OF CONTENTS j PAGE
-1. 0 INTRODUCTION
'L.l' ' GENERAL INFORMATION....................... 1-1 1.2 SYSTEM CLASSIFICATIONS.................... 1-1
*s 12.0 INSERVICE INSPECTION PROGRAM
1.1 DESCRIPTION
OF ISI PROGRAM................ 2-1 2.2 PROGRAM TABLES............................ 2-7 A. QUAD CITIES UNIT-1 B. QUAD CITIES UNIT-2 2.3 RELIEF REQUESTS........................... 2-8 f 3 . 0. INSERVICE TESTING PROGRAM FOR SNUBBERS
- 3 .1 DESCRIPTION OF SNUBBER IST PROGRAM........ 3-1
~3.2 P ROG RAM TABLE S . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-3 A. QUAD CITIES UNIT-1 B. QUAD CITIES UNIT-2 3.3 RELIEF REQUESTS........................... 3-6 4.0 INSERVICE TESTING PROGRAM FOR PUMPS 4 .'l DESCRIPTION OF IST PROGRAM FOR PUMPS . . . . . . 4-1 4.2 PROGRAM TABLES............................ 4-2 A. QUAD CITIES UNIT-1
- 8. QUAD CITIES UNIT-2 4.3 RELIEF REQUEST 3........................... 4-5
*** .e ame e.
L .
~~
TABIA OF Coco;;.ata - continued
- e. .
PAGE 5 .0- INSERVICE .TCSTING...FROGRAM FOR VALVES
5.1 DESCRIPTION
OF IST PROGRAM FOR VALVES. . . . . 5-1 5.2 PROGRAM TABLES............................ 5-11
-A.- -QUAD CITIES UNIT-L ,
B. QUAD' CITIES UNIT-2 5.3 RELIEF REQUESTS........................... 5-13 5.4 COLD SHUTDOWN JUSTIFICATION FOR IST VALVE PROGRAM................................... 5-41 J
- i
( e l l l l t I . .. ,
...e
_ , . _ , p - - . - .m__ .. . . ,_,.. -, _,. ,%. .ww-, ,..w-_.p. ,r... w.mo-
- 1. 0- IR.TRODUCTION, . , ,
L.1 GENERAL INFORMATION The. Inservice' Inspection (ISI) and Inservice Testing
~
(IST)" Programs for -Quad Cities Nuclear Power Station, Units 1 and 2 are developed in compliance with the rules and regulations of 10CFR50.55a and Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition including the Addenda through Winter 1980. Where these
' rules' are determined to be impractical;, specific relief ,
is requested in writing. l i The Inservice Inspection and Testing Programs for Class < 1, 2 and 3 Components, Component Supports, Pumps, & Valves are applicable for the ten year interval beginning February 18, 1983 and March 10, 1983 for. Quad Cities Units 1 and 2, respectively. The upcoming ten year interval is the second inspection interval for both Quad Cities Units 1 and 2. l. 1.2 SYSTEM CLASSIFICATION
- L
- The construction permits-for Quad cities Units 1 and 2 were issued on February 15, 1967. At that time the ASME t
i Boiler and Pressure Vessel Code covered only nuclear l ' l Revision 5 1-1 ,
. DS .
i i vessels. Piping;, pumps, and valves were built primarily i to the rules of USAS B31.1.0, therefore, the station'has essentially no ASME Code Class 1, 2 or 3 designed , systems. The system classifications used as a basis for the Inservice Inspection and Testing Programs are based on theorequirements set ~forth.in'10CFR50 and Regulatory- 5 Guide 1.26 and were developed for the sole purpose of
-assigning the appropriate inservice inspection i
'~ requirements. Components within the primary coolant I pressure boundary, as defined in 10CFR50.2(v), are ! designated as ISI-Cla'ss'I while other safety related components are designated as ISI-Class 2 and 3 in accordance with the guidelines of Regulatory Guide 1.26. Pursuant to 10CFR50 paragraph (g)(1), inservice inspection requirements of Section XI of the ASME Code are then assigned to these components, within the constraints of existing plant design.
. Class Code Flagged Piping and Instrument Diagrams (P& ids) documenting the system classifications were developed to aid in the review and implementation of the subject programs. A legend explaining the class code flassinsischeme is included on the first page of the P& ids.
Revision' 2 1-2
.A
2.0 INSERVICE'-INSPECTION PROGIUui FOR COMPONENTS , 2.1 PROGRAM DESCRIPTION 2.1.1 The Inservice Inspection Program for ISI Class-l', 2 and f 3' components- meets the requirements of Sectiott XI .of them ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda. Where these requirements are determined to be impractical, specific requests for relief have been written and included in Section'- 2'. 3 . L-2.1.2 The ISI Component Program is presented in Section 2.2 in a tabular format. The components and associated requirements are listed according to ascending Code categcry and Item Numbers. The following information is included in the tables: A. Cede Category - The Section XI Examination Categories as defined in Table IWB-2500-1, IWC-2500-1, IWD-2500-1, and IWF-2500-1 for Class 1,2, and 3 components.
- 8. Item Number and Item Description - The Item Number and its description as listed in Tables IWB, IWC, IWD-2500-1, and IWF-2500-2. Applicable Item. .
d Revision 2 2-1
e . - ___ _ . _ _ _ . _ _ _ . _ . . _ _ _ _ _. numbers and. all leanu 0escriptions are listed for ; each Code Category.
.C. Section XI Exam Required lists the examination metho'd or methods. This reflects the Section XI requirements. The abbreviatione.used.are-as follows:
VOL - Volumetric per IWA-2230 SUR - Surface per IWA-2220 VT-'l -~ Visual per IWA-2211 VT Visual per IWA-2212, VT Visual per IWA-2213 VT Visual per IWA-2214 D. Relief Requests references either a specific relief request contained in Section 2.3 or references one of the Code allowed exemptions listed below. If the latter is referenced, the particular line or component has been exempted from volumetric and/or surface examination by the applicable Code paragraph. Components exempted fecm examination by Code allowed exemptions will not appear in the component tables of this program in most cases. It sh'ould be noted that section 2.3 contains some generic relief requests that are not specifically
~-
Revision 2 2-2 M M9 A
c - -- - referenced in tha tables-but apply-to the ISI Program in general. EX IWB-1220(b), lines 1-inch nominal pipe size'(n.p.s.) and less. EK IWB-1220(a), . Liquid carrying lines. 2-inch n.p.s. and less (see 2.1.3) EK IWB-1220(a), steam carrying lines 4-inch n.p.s. and less (see 2.1.3) EX IWB-1220(c), head connections, 2-inches
- - n.p.s. and less., made. inaccess.ible by CRD penetrations EX IWC-1220(b), components not required to operate above a temperature of 200*F or above a pressure of 275 psig.
EX IWC-L220(c), component connections, piping and associated valves, and vessels and their attachments that aref4 in. n.p.s. EX IWC-1220(a), lines not required during normal operating conditions but remain - flooded under static conditions at a minimum of 80% of the pressure they woulc be subjected to when required to operate. EX-8 ~IWC-1230, piping support members and piping support components encased in concrete.
* . c
- a. .
J. Revision 2 2-3
~ .
( EE-9
. IWD-1220.1, integral attachments of supports and restraints to components that are 4 in.
n.p.s. and smaller. EX-10.- IWD-1220.2(a), integral attachments of f supports and restraints in ' systems whose
~
function is not required in: support of l reactor residual heat reraoval and emergency 4 core cooling. l EX IWD-1220.2(b), integral attachments of supports and restraints where operating pressure is 275'psig or less and operating e temperature is 200*F or less. EX IWD-5223(e), open ended vent and drain lines from components extending beyond the last shut-off valve and open ended safety or relief valve discharge lines. I E. Alternate Exam lists the examination method or i methods that will be performed in lieu of the required Section XI methods when relief has been I e requested. F. Remarks - Lists general clarification remarks. 2.1.3 Pursuant to paragraph IWS-1220(a), the maximum size line break.that can be made.up by the reactor coolant makeup
- ? ~ .- . . .. .
e-
- Revision 2 2-4 - -# ~-
e
system has..been calculated to be 1.08 inches inside i diameter for liquid carrying lines and 4.16 inches for
. steam carrying lines. In applying this exemption to the program, liquid carrying. lines less than or equal to 2 inch nominal pipe size and steam carrying lines less , them or; equal to- 4.0 - inches n.p.s were exempted.
2.1.4 Table 2.1-1 lists the applicable Class 1, 2 & 3 systems which are covered in the Inservice Inspection Program. O 4
.. .a :....' . .
Revision 2 2-5
TABLE 2.1-1 LIST OF SYSTEMS INDLUDED IN THE ISI PROGRAM , SYSTEM . . . CLASS Control Rod Drive 1& 2 Residual Heat Removal (RHR) 1& 2 RER Service Water 3 Standby Liquid Control (S8LC) - 1& 2 Reactor Water Cleanup 1 Core Spray 1& 2 High Pressure Coolant Injection (HPCI) 1& 2 Main Steam 1 Feedwater. 1& 2 Diesel Generator Cooling Water 3
' i' . . .
Revision .2 2-6
-_ - _ __ _ __ ___ _ _ _ _ _ _T' _ _ __ __ __ Z1_ _
SECTION 2.2 TABLES FOR INSERVICE INSPECTION PROGRAM A. QUAD CITIES UNIT-1 1
.* 5. QUAD CITIES UNIT-2 4
4 0 4 j , Revision 2 2-7 4 M *v * '
&# = g a
~
l INSERVICE INSPECTION PROGRAM i
@Id*** _ _ _ _ - _ _ _ _ _ _ _-. _ _ _ _ _ - _ _ _
ISI - CLASS 1.2 & 3 COMPONENTS OUAD CITIES HUCLEAR POWER STATE)N I Utsi - I CLASS 1 '* 8 " 35 And.a 2 l pes. 9-17-84 CdBE HEtt gitas at m vaoM SECT at EXAa8 AftIEF ALTEllba4TE casesmar annamen ngognago agougsig g n a,, ngasams n.a w- marrasmissa w == un meACTom vassas. en.te sents weta. et.11 Circ serentiat voL cm-1 {
$1.12 Iangitudinal WOL CE-1 81.28 Ilead We:Je - .
et.21 Circu.serential woL CR-2 es t .22 meridioman Vol. Ca-2 0
#1.38 .%ent-to-Flange Weld WOL st.44 Iseed-to-Flange Wold VOL AND SUNF i
4 el.54 Sepair We:Ja N/A f l 2.B PmESSeleE BETA 80$$gsG tersJas Ist Wassgs.s 05 TIER TISAtt SEACToet WESSrt.S Bf/A , t i 5.8 FtILL PetfETSAT30sl teELDS Otr seOzst.as les WEh5Ei.S - IIASFtTT80e8 P9ILMNM S heactor Wesset 43.98 Benaale-to-Wesset tields WOL el.lte teos tle Ins 4Je 84J!us Section WOL i
- r 1
l .
k . l f e '3 ,._- __
~
INSERVICE INSPECTION PROGRAM I E**** (d' _ __ _ _ _ ts: - Ca. ASS 1.2 & 3 COMPONENTS ouAD ClllES HUCLEAR POWER STATION l UNil - 1 CLASS 1
% 2 m 1s a.*sen 2 loos. 9-17-84 coot sites sieu otscaseinou sect as exAu maur atigansAvg manug canecesw aamssen , , , , , , ,,,,33, ,,,,
pressertact 33.11s akaale-to-Wesset teelds lt/A m3.124 thaste lastde Radius Section ti/A Stsan Generators (Primary Elde) m3.134 l St.144 stoaale-to-vesset teelds senaale Inside Radius Section fA f/A
. staat Eschangers (Primary Elde) 43.15e chaste-to-vesset teelds N/A' 53.164 teoaste In.ide Radles Section N/A s-E Meets $4pmet anETALIIIslG PARTRAB. PEsettTRATICOS tsE8 Jag IN WEssats .
h4.18 Partial Penetration Welds EXTERNAL SuiIFACES te.11 Wesset esoaates . vt-2 at.12 control mod Drive teoastes VT-2 at.11 Instsumentattoa maates VT-2 pressentiser 84.2e steater Penetration Welds N/A
. B-F Wh tetTalaliteG DISStuttaa poetTAL Wrf na j heactor vess=1 SS.le helm 41 rape Stae > 4 in.
Noaale-to-Safe End Butt WclJs WOL A8ep Sugar
I ' INSERVICE INSPECTION PROGRAM N ist - CLASS 1.243 COMPO$4ENTS MAD CillES NUCLEAR POWER STATION
#*** ' " 35 UNIT - 1 CLASS 1 a desen 2 l Dele 9-17-84 Coef - ligas SECT a Exaas MLaEF ALIERNATE CAIEGear sammefa BTEM MMM MOtanEO ""E M OuES15 EXAas
- e5.11 staminal Pipe Else < 4 in. ,
Stoaale-to-Safe End mutt We1Js Suer i 55.12 stoaale-to-Saf e End Socket Wids N/A pressortaer m5.2e ahaminal F1pe Staa > 4 in. h amle-to-Safe End Butt Welds N/& 35.21 espelmal Pipe Sise < 4 in.
', teoaale-to-Safe End Butt We1Je , M/A, a5.22 seosale-to-Safe End Socket W1ds N/A Steam Generator 55.34 sh2elman ripe Stoo 1 4 to.
teoaale-to-Safe EaJ Butt W 13s N/A sti.31 stoelmat Flpe Stae < 4 to. stoaale-to-Saf e End Butt Wide M/A E5.32 teoaale-to-Safe End Socket Welds N/A meaE Eachangere 35.48 heimal Pipe Stae 14 in. maale-to-Saf e Emd 1.utt We1Js N/A~ e5.41 sousinal Pipe Stae ( 4 in. teoaale-to-Safe End mutt Welds N; A a5.42 seoaale-to-Safe End Socket Welds ee/A FI P log l a5.5e eeuetaat Ftpe Slam > 4 la. l Dissimilar statal tutt Welds a Asso Sueer SEE FIG. IWB-2504-8 n I .
c e.s,se,,,, INSERVICE INSPECTION PitOGRAM Id'*** ISI - CLASS 1.2 & 3 CO64PONENTS OUAD CITIGS NUCLEAR POWER STATION UNii - 1 CLASSI
, fleidesee 2 l Dele 4-17-84 Coef ITEed SECT 24 EMA44 M LIES A41Eftp64TE cAitcoat >==== ' ' ' " "8C"3" -
wouNito m outsis Masams E Aas n5.51 staminal Pipe Size < 4 in.
. Dissiallar sletal tutt W1ds SUkr 35,52 Dissimilar Dietal Socket Welds N/A 3-G-1 -
tassableE DETAltBIGOG N0LT880G, .
. GeesATEm Tasaat 2 in. III DI AftETER Ibaactor' Wesee1 ,
! #6.19 Closure 15ead stints SURF B6.29 Closure Studs, in place VO4 56.34 Closure Stuits, wt.en removed SUkr A400 WOt. a6.48 Threade in Flange VOL
#6.59 Closure h shers, Bushings VT-1 4
I
! pressuriser a6.6e molta and StuJa -
w/A D6.79 riange Surface, when connection
~
disassentated N/A Is6.se h ts, mushings, and h shers N/A l Steae Generators . i ' 56.99 solts and Studs N/A m6.164 Flange Surface, when connection disassembled N/A ! Isf.119 hts, Bushings, and hshers N/A escat Escanangers t:6.12e Isolts and Stiade N/A i
[~~') ,_. INSERVICE INSPECTION -PROGRAM. k O J E88*** ISI - CLASS 1.2 4 3 COMPONENIS
\d OUAD CITIES NUCLEAR POWER STATION 5 "*** * " **'
LHT-1 CLASSI asdeaan 2 lDese 9-17-c4 CODE IIEM SECT M EXAM MLIEF ALIEfte4 ATE CAIEGOftt Pamanwa 8 TEM MMIM MOUIMD ftEQUESTS EMAU -
" I s6.13e Flange Surface, when connection d$sassembled N/A 56.144 teute Bushings, and Washers N/A riping 36.15e Botta sad Studs M/A 56.169 riange Surface, when connection
[ disassembled pl/A a6.170 touts, pushings, and Washers N/A Fumpe 86.188 Isotta and StuJa VOL 86.190 Flange Surface, when connection
. disassembled VT-1 . .
86.208 Diets, Bushings, and Washers VT-1 Walves 86.210 Dotta and Studs N/A 36.220 Flange Surface, when ccer.ection ? disassentaled N/A , g6.230 Nuts, Bushings, and Washers N/A i i S-G-2 FIBF"me METAINI48G SOLTageG, 2 in. AND 1.ESS Itt DIANt'TER , f f i heactor vessen 87.10 Solts, Studs, and Nuts N/A
?
G I
,. -___;,,,,, INSERVICE INSPECTION PROGRAM I'"***
ISI - CLASS 1.2 & 3 COMPONENTS OUAD CITIES NUCLEAR POWEft ' STATION UNIT - 1 '. CLASS 1 novielen 2 l0 6,9,17-84 . Coot sit u
, , , , ,g ge,,,,g,, saci al ExAu N AugmATE CATEGORV NuumEn REOutNED HEOutsis ExAu REMARKS 4
- Pressuriser 27.20 Solts, Studs, and Nuts , M/A Steam Generators 87.30 polts, Stude, and Nuts , ,4/A
] eseat Escleangers ' l 87.40 botta, Studs, and Nota N/A Flping B7.50 Solta, Studs, and Nuts VT-1 $ riemps 87.60 Bolts, Studs, and Nuta N/A t+ Valves j B7.70 polts, Stude, and Nuts VT-1 i . CNS Mousinge B7.50 Bolts, Stude, and'Huta VT-1 MilEN DISASSEMBLED { i M-N INTECHAL ATTAC3000ENTS FOR VESSEL.S l l 14cactor Vessel 108.10 Isitegrally Welded Attaclamesits SUHF VESSEL SUPPORT SKittT3 9 SEE FIG. IWD-2500-1] l I.IFTING LUGS, STABILI2Eli LUGS SEE FIG. IWh-2500-15 : la I
1 c.,,,,,,,,,,,,,,,, INSERVICE INSPECTION ' PROGRAM i Eh. . ISI - CLASS 1.2 4 3 COMPONENTS l OUAD ClTIES NUCLEAR POWER STATION Page 1 of 15 4' MI-I - CLASS I posisten 2 - l 06, S-17-84 !' CODE IIEM ITEtt DESCHIPTION I ! CATEG0flV tammsa REQuenED ftEQufSYS EXAM MMAnt(4* f i ytessierizer { Ipe.20 Integrally Welded Attachments N/A . l I Steam Generator tsa.30 Integrally Welded Attachments 3s/A Neat. Eschangers us.49 Integrally Welded Attachments pl/A W-J PIRESSpast RETAINID0G Wi!!.DS IN FIFl80G 189.10 Hominal Flpe Slae > 4 in. B9.11 Circumferential Welds SUHF AND VOL CR-3,CR-4 89.12 langittadinal Welds SUHF AND VOI. CH-4 869.20 Nominal Flpe Size <4 in, j 89.21 Circumferential Walds SURF I 09.22 tangitudinal Welds SUHF 09.30 branch Flpe Connection Welds u9.31 Emind! Flpe Slae 1 4 in. SUHF AND VOI. CH-5 VT-2 89.32 Nominal Pipe Size <4 in. I SURF 09.40 Socket Welds N/A i i e
n
;__ _,,, ,,,, INSERVICE INSPECTION P110 GRAM
@,h* E ISI - Ct. ASS 1.2 & 3 COMPONENTS OUAD CITIES HUCLEAR POWER STATION f
LHT-I CLASS l' Rewtolee 2 lDate 9-17-84 CODE 11EM CA1EGOflY NUMBER lTgM DESCRIPTION MOulMD MOUESTS y EXAM W MMARg(S M-. K- 1 INTEGIRAL ATTACISMK0tTS I*0K PIPING, rusers Aun VALVES q Piping 3 H10.40 Integrally Welded Attaclimente SURF , $st FIG. IWu-2500-13,15 1 rumps
#10.20 Integrally Welded Attachments SURF SEE FIG. IWB-2500-13,15 i Valves
, B10.30 Integrally Welded Attachments SURF fiEE FIG. IWu-2500-13,15 i B- 8,- 1, PNESSUSE ItETAINING WEE.DS IM p-N-1 PlatP CassteGS AtaD VALVE DoolES N/A i
^
R- 8,- 2, 44110F CASl84GS AMD val.VE DODIES D-N-2 012.20 Pump Casing VT-3 CR-6 WilEN DISASSEMBLED
, I l\ ut2.40 Valve Body, Enceeding 4 in.
f Nominal Pipe Size VT-3 CH-7 Will:H DISASSEMBLCD i t n ts-N-1 IIfTEltlOtt OF ltEAC10R VESSEL. . I j aleact.or Vesuel 1 Veamet Insterior VT-3 uti.10 PER TABLE IWB-2500-1, CATEGORY D-N-) 1 __ w
Commonweeetti INSERVICE INSPECTION PROGRAM
@E888a ISI - CL ASS 1.2 & 3 COMPONENTS QUAD . - CITIES NUCLEAR POWE,R STATION
"*" ' # 15 LHT-1 CLASS I ~
Reviolon 2 l Dele ' 9-17-it4 CODE-
- eTEM SECT Xt EXAM REllEF ALTERNA15 CATEGORY HuutBER MM MSCRMM REug ,
REOulHED REQUESTS EXAM peactor vadsel (mult)
- 213.20 Interior Attachments VT-1 ACCESSIBLE WELos BI).21 Core Support Structure VT-1 ACCESSIBl.E SURFAC{S Beactor Vessel (Swal
. D13.30 Core Support Structure N/A j ' i B-0 PRESSung itETAINING WEE.06
~
, 18p CONTh08.1000 ItOUSINGS f Ileactor Vessel
$214.10 Welde in CMD pousing VOL EX-2 EX-2 APPLIED TO THESE HOUSINGS DUE TO CONFIGURATIOS i
i B-P Al.8. PetESSURE NETAINING C0068000ENTS I meactor Vousel
. '915.10 Pressure Metalning poundary VT-2 1.EAKAGE TEST l H15.11 Pressure petalning Soundary VT-2 flVDROSTATIC TEST tvenmurizer j{ B15.20 avessure lietalning uoundary N/A B15.21 Pressure kutaining pousidany ~N/A I' Steam Generatora
'8815.10 Pressure ketalailng Doundas y N/A
{ utS.)I Presuurc ketalning isoundary N/A l !1' i
c_,,,,, INSERVICE INSPECTION PROGRAM
@E8""
ISI - CLASS .1,2 & 3 COMPONENTS OUAD CITIES NUCLEAR POWER STATION UMT-1 #*** ~3* " 35 CLASS 3 Revealee 2 l Dele 9,17-84 CODE ' IIEM S CT Ma EXAM RELIEF ALTERedATE , CAIEGORY HUMBER ITEM MSCHFIM REQUIRED DEOtESIS EMAM MMW
- aleat Escanangers pl5 40 Pressure petalning houndary . .
N/A' pl% 41 Pressure Retaining Boundary M/A
, FIPIm9 815.50 Pressure Metaining poundary VT-2' l.BANAGE TEST 215.51 rpessure Metaining Boe:ndary ' VT-2 . NYDHOSTATIC TEST .
2 I gaggpg
- j B15.69 Pressure Retaining Boundary VT-2 1.EAEAGE TEST
{ ti,15. 61 Pressure Metaining Boundary VT-2 NYDROSTATIC TEST l Valves Bl$.70 Pressure Detalning Boundary VT-2 1.EAKAGE TEST M15.71 Psessure Relatning boundary VT-2 HVDROSTATIC TEST t I m-o steam csmanaion TimauG n/a i 1: ! 4 . i. 1. e. I i g. 1 i l 4 ! i . i
! i' l
l
.i -
~
c__ ,,,,, - INSERVICE' lNSPECTION PROGRAM Eh *
^tSt -- CL ASS 1.2 1 3 COMPONENTS
.. QUAD CITIES HUCLEAI) POWEf1 - STATION
'aea 25 a' 2 5 ___
tu - i ctAss 2 Rowisten 4 l Dele 9-17-ft4 CODE ITEM SECT Me EXAM ~ ftELIEF ALTEfte4 ATE CATEGORV MmR ITEM MRFIN REQUIRED ftEQUESTS EXAM E C-A PetsSSuas RETA500EteG Wett.06 588 PetESSUSE VetSSEta ! Cl.10 Shell Circumferential Welds Vol. Illitt NEAT EXCilANGER i C).20 Head Circumferential Welds VOL 5ti4R BREAT EXCilAB0Q$;R !* Cl.30 Tubesheet-to-She!! Weld bl/A i C-B PetESSuets RacTAIMiteG be0135.E wet.pS - Ib4 VSSSE8A c2'.10 toonstes in Vessel 1 3/ gin. 100minal Tt:1ckness SURF CR-8 VT-2 ftHit HEAT EXCalANQ$lt l C2.20 Mossleu (n vesset > I/ GIN. Nominal Thickness N/A R C-C IISTEGatAI. ATTAC4000E4f?S FOtt VESSEL.S, Flyt teG, PUNFS, AND VAB.VES - i l Pressure Vessels l C).10 Isitegra!!y Welded Attacliments SUHF , Rilk ilEAT EXCHANGER i j' Firing i C).40 Integrally Welded Attachments SultF 2 I
i Co INSERVICE INSPECTION PROGRAM
@Eh ISI -- Ct. ASS ' 1,2 & 3 COMPONENTS QUAD CITIES HUCt. EAR . POWER STATION Page '12 of a 15 I UNIT - 1 CLASS 2 m 2 l ode 9- U-84 CODE ITEM SECT Ma EXAM MLIEF ALTERNATE III I CATEGOftV NUMida MOtMMD 8tEQUES15- EXAM " " " I.
- j. Fu=s=
'C 3 . 's 0 Integrally Welded Attachments N/A e <
Valves j- C3.100 Integrally Welded Attachments N/A 1 a 1 I C- O Pasmaamar agTAINIteG SOLTING GREATER TRIAtt 2 in. IN DIAstETER
- i l' pressure vesselm C4.10 Botta and Stude M/A
- Piping '
s C4.20 ponts and Stude N/A j ruseps
- C4.30 Solts'and Stude N/A l
v.tves C4.40 Bolta and Studs N/A 3 l 1 C-r Plat:hSuttE NETAINittG WER.DS IN FIFIstG i C5.10 Piping Walds < Ih in. } Numinal W.11 Thickness I, C5.11 Circumferential Weld SURP
;. .C5.42 fongitudinal Wold Suur dm e-
i ca e eN., INSERVICE INSPECTION PROGRAM ,
@Ed66**
ISI - CLASS 1.2 4 3 COMPONENTS OUAD CITIES .NtJCLEAR POWER STATION UNIT - 1 CLASS 2 Revision. 2 lpete94'/-84 CODE IIEM CATEGORY 11Ett DESCRIPitON RE64 ARKS NUMSER REOLNRED REQUESIS EXAM C5,; 20 ' PipingWelde>hin. stominal Wall Thickness , C5.21 Circumferential Wald SURP AND VOt. , C5.22 longitudinal Weld N/A C5.30 Pipe trancia Connections ,- ) 95.31 Circumferential Wald SURt' CR-10 VT-4 C5.32 fongitudinal Weld N/A ) C-G PNESSans pETAINissG WEE.ps a 300 PuttPS p p VAE.VES N/A f C-M AI.8. PmES8ung RETAINsteG C006PONENTS Pressure Vessels C7.10 Pressure Retaining componente VT-2 PRESSURE TEST , C7.11 Pressuro Retaining Components VT-2 NYDROSTATIC TEST Flying C7*.20 Pressure Metaining Components VT-2 PRESSUME TEST C7.21 Pressure potmining Components VT-2 NYD80 STATIC TEST Pumps C7.30 Psesnure Betaining Components VT-2 PRESSURE TEST C7.J1 Pressure Metalning Congenent:s VT-2 NYDHOSTATIC TEST ,
[-
.R., INSERVICE INSPECTION PROGRAM
@ co M ***
ISI - CLASS 1.2 1 3 COMPONENTS OUAD CITIES NUCLEAR POWER STATION
#*** ** " 35 UHli - 1 CLASS 2 RWeten 2 lDde 9-17-84 cone nEu new pescRaenow sEcr m gxau - , en EF - Aufww pruaRus CATEGORY pauanR REQU8AED REQUESTS EXAM Valves
$7.40 Pressure Retalning Components VT-2
{RESSURETEST C7.41 Pressure Retalning Components VT-2 NYDROSTATIC TEST l 3 l 1 b e i
- . i i
II i' j, - l' i \ 1 1
.me. INSERVICE INSPECTION PROGRAM .
@ com .
Edison ISI - CLASS 1,2 8 3 COMPONENTS QUAD CITIES NUCLEAFI POWEFl STATION UNIT - 1 CLASS 3 n.wieso. 2 j o.a. v-u-us conf . stEu SECT Me EXAM MLIEF stEu OEScsuPTION ALTERNATE . CATEGOav NUMasER REQUIRED pf00ESTS DEM WS EXAM n-A SYSTEllS 30l SUFFOtt? OF REACTOR SNUTp0Nes ruseCTIOes
, N/A . _
p-b SYSTEMS IN SUProat or EMERGEteCY cokg COOLit4G, CONTAINs0ENT llEAT REMOVAL, ATHOSWISENs CLEAasur, AND REAC1Un
- RESIDUAL IIKAT REMOVAt. ,
D2.10 Pressure Retaining Comimacnts VT-2 {UthCTIONALTEST VT-2 $dYDHOSTATIC TEST D2.20 Integral Attachment
- Component Supports and Hestraints VT-3
{ D2.30 Integra! Attachment
- Hechanical and llydraulic Snubbers N/A 4
i D2.40 Integral Attachment
- Spring Type Supports N/A D2.50 Integral Attachment
- Constant Load Type Suppo*rts N/A 1
l D2.60 Integral Attachment
- - Shack Absorbers N/A
\ i
- , l-i!
3 abc SYSTEMS IN SUPlUMT OF RESIIRIAL IIEAT SEMOVAt. FitON SPENT FUE8. ti1DNAGE FOOT. N/A
}
l
INSERVICE INSPECTION PflOGRAM
@ usesnonwsouh EsN***
ISI - Ct. ASS 1,2 & 3 COMPONEl4TS QUAD CITIES NUCt. EAR POWER STATION UNIT - 2 G ASS 1 fievision 2 lDete 9-17-84 CODE ITEM - SECT Xi EXAM llELIEF ALTERNATE CATEGORY HuunER U" # REOutRED EXAM N "#N"I flEOUESTS , tl . A PRESSURS itETAINING WELh3 IN REAC1DR VESSEL pt.10 Shet! Wolds ut.11 Circumferential VOL CR-1
.a1.12 Iongitudinal VOL CR-1 -
ut.20 Head Welds al.21 Circumfere. itis! VOL CR-2 181.21 Merldlonal , VOL , CR-2 l ut.30 Shell-to-Flange Weld VOL 1 1 p1.40 llead-to-flange Weld VOL AND SukP u!.50 lie pa ir W eld s N/A 4 i Is .R FitESSUME RETAINING WELDS IN VES:iEE.S i OTHER 7tIAal NEACTOR VESSEL.S N/A l M.D FutJ. PENETRATIOeg HEI.DS OF NOZZIES IN VESSEtJi - INSPECTION 8'idx;hAN D Steacto*- Vessel D).90 Wozzle-to-Vesdal Welds VOL ' B3.100 Hozzle Inside Hadius Sect!un VOt. i s l i l 1
- f l
A I C. mss su,..N. INSERVICE INSPECTION-~ PROGRAM
@Ed"** ISI - CLASS - 1,2 8 3 COMPONENTS OUAD CITIES NUCLEAR POWER STATION d g.-1 "*** * # 3' CLASS 1 -
Revision 2 l page 9.g7;g4 CODE ITEM SECT XI EXAM RELIEF ALTERNATE CATEGOllY ligM DESCRtPM NUMBER REQUIRED pfOUESTS EXAM , REMARM$ j reassuriser j m3.lle hamle-to-Vossel Welds II/A i is3.120 maale Inside Radius Section N/A i Steam Gesnerators (Primary Sidel i t: 3.130 Mossle-to-Vessel Welds. Id/A u3.140 Nozzle Inside Radius Section II/A I { eleat Euchan<aers (Primary Sida) ! B43.150 nozzle-to-Vessel Welds N/A 03.160 stoatie Inside Madlus Section N/A l 2 ! B-Il PetESSuas NETAla0ING PARTI Al. PENE*JRATIOtt I WEI.DS Ill VESSEL.S 1 l 64.10 l'artial Poneiration Welds $XTEHHAL SUHFACES d4.11 Vessel Nozzles VT-2 l ut.12 Control Rod Drive Nozzles VT-2 j e4.13 Instrumentation Nozzles VT-2 I i Pressurtzer { ut.20 84 eater Peenetration Helds N/A ~ l* 1 . ! 5-P PltESSultE IRETAINING plSSIMII.AR MLTAL WEl.DS - i i l l. Heactor Vessel , s . i uS.10 hominet Pipo Size > 4 in. l 1
%,,,,, INSERVICE INSPECTION PROGRAM
@ I'86** iSt - CLASS 1,243 COMPONENTS OUAD CITIES NUCLEAR POWER STATION LHT-2 CLASS 1
"*** 3 " IS Revisioe - 2 l Date 9-17-84 CODE ITEM SECT XI EXAM RELIEF ALTERNAig CATEGORY NUMBER liEM MN DEMARKS REGINRED flEOUESTS EXAM Nozzle-to-Safe End putt Welds VOt. AND SUHF h5.11 Nominal Pipe Size < 4 in.
Nozzle-to-Safe End Hutt Welds SUHF
.85.12 Nozzle-to-Safe End Socket Welds
- N/A I
Pressurizer 85.20 W inal Pipe Size > 4 in. Nozzle-to-Safe End Butt Welds , f/A , n5.21 Nominal Pipe Size < 4 in.
, Nozzle-to-Safe End Butt Welds N/A M5.22 Nozzle-L9-Safe End Socket Weldr y/A Steam Generator
? B5.30 Hominal Pipe Si ze ), 4 in, j Nozzle-to-Safe End Butt Welds $4/A
, A5.31 Nominal Pipe Size ( 4 in.
, Nozzle-to-Safe End butt Welds N/A g I p5.32 Nozzle-to-Safe End Socket Welds (4/A . I uest Eucliangeru ! B5.40 Nominal Pipe Size 2 4 in. taozzle-to-Safe End putt Welds N/A j H5.41 Nominal Pipe Stue < 4 in. Mozzle-to-Sate End putt Welds N/A l 85.42 Nozzle-to-Safe End Socket Welda N/A l
\
riping n5.50 Hominal Pipe Size > 4 in. , Dissinitar Metal Hutt Welda VOL AND SOHF SEE FIG. IWu-2500-8 l
,.,____ , INSERVICE INSPECTION PROGRAM i
@ .Essesea ISI - CLASS 1.2 8 3 COMPONENTS .
-l' OUAD CITIES NUCLEAR POWER STATION
. UNii - 2 . . CLASS 1 Revisine 2 l Date 9-17-P4 CODE lEEM SECT st EXAM SEtaEF ALTEfD6 ATE CATEGOAV DemanFR i M DESCAN' M EMM REOulHED .flEQUESTS EXAM .
a5.51 teossinal P!pe Slas < 4 in.
, Dimalmilar Metal autt Welds SURF B5.52 Dissimilar Metal Socket Wolds y/A . B-G.g yes ammar pgragggges socyggen, GIBRATER T18AM 2 in. IN DIAMETEIt Beactor vesset .
86.10 Closure Need Nurs suaF 166.20 Closure Stude, in place VOL 06.30 Closure Stude, when removed SURF AND VOL
$6.40 Threads in Flange VOL l 86.50 Closure Washers, Bushings VT-1 j
Pressur1xer f 146.60 bolts and Studs H/A l* u6.70 Flange Surface, when connection j disassembled N/A
, D6.80 Nuts, Bushings, and Wastiers --
p/A Steen Generators l 86.90 Rolts and Studs N/A ! 86.100 Flange Surface, when connection I disauscombled N/A j , u6.!!0 Huts, hushings, and Washera y/A . I i locat Esclaengers ( D6.120 uolts and Studs N/A 1 l . . - \ _ _
%,,,, INSERVICE INSPECTION PROGRAM
- Edlaa ~ISI - CLASS 1,2 & 3 - COMPONENTS 4
OUAD CITIES NUCLEAR POWER STATION 5 UNIT - 2 CLASS a '5 Rs esse 2 l 0.se ,9-17-84 l CODE 81EM SECT M8 $XAM RELIEF ALTERNATg CATEGORY- MhMeF:1 STEM MSCANN ""*""^ REOulHED ftEOUESTS EXAM 26.430 Flange Surface, when connection . disassembled N/A D6.140 Nuts, Bushings, and Washers .M/A 1
- rielas B6.150 solta and Studs N/A j e6.160 Flange Surface, when connection
- disassembled N/A B6.110 Nuts, Bushings, and Washers N/5
) AM. , M6.180 Solta and Studs. VOL , D6.190 Flange Surface, when connection disassembled VT-1 M6.200 Nuts, Bushings, and Washers VT-1 h Walves h6.210 Solta and Studs N/A j , u6.220 Flange Surface, when connection j disassembled N/A D6.230 Nuts, pushings, and Washers N/A o J j B-G-2 FNESSURE METAINiteG NOLTissG, i , 2 in. AND I.ESS IN DR AMETKit
- i <
l Meactor Vessel 1 { B7.10 Bolts, Studs, and Nutu N/A I i i 1 . i
INSERVICE INSPECTION ' PROGRAM
@f**** ISI - CLASS 1,2 & 3 COMPONENTS OUAD CITIES NUCLEAR POWER STATION UHli - 2 #*** ' " **
CLASS 1 Revleien 2 l Date 9.-17-54 CODE 81EM SECT M8 EXAM flELIEF ALTERNATE ligM MSCReim CAltGORV am m a REOueRED MOUESTS EXAM rressuriser 647.20 uolta, Stude, and Nute , M/A. steam Generators 161.30 po$ts, SL:sda, and Nuts 4(/A Meat Escleangers u7.40 Solts, Studs, and Nuts IQ/A Piping i at?.50 solta, Stude, and Nute VT-1 riemps 87.60 Solts, Stude, and Nuts _ - N/A ! 4 i $ I i V.tve. ' 1 i 27.70 molts, Stude, and Huts VT-1 , 1 i a ) cuo esausInga f u?.80 molts, Stude, and Nuts VT-1 MlleN DisASSEMBE.eD li I m-u suTscuas. ArrAcumenTs rom Vessues ' Iseactor Vesset lI j us,to integranny wonded Attaci.ents , sunr vessel surrouT sutsT ; j ses r:G. INu-2soo-13 i { LIFTING LUGS, sTADILIIER LUGS j i i ses rio. INu-2500-1$ l f ..
}i i
j l-
l c - _ _ _ _ , INSERVICE ' INSPECTION PROGRAM , Ed'*** ISI - Cl. ASS 1.2&3 COMPONENTS OUAD CITIES NUCLEAR POWER STATION I
. UNIT - 2 CLASS 1 '*** ' " 15 flewle% 2 l Dele 9- 17-M COct- . ITEM SECT X8 EXAM ftELIEF CATEGOftV NUMBEE ITEM DESCRe m AlifRNATE REQUIRED fl(OUESTS EXAM ftEMARMS Pressuriser f dt.20 Integrally Welded Attacliments N/A sta.m cenerator lit.30 Integrally Welded Attachments N/A ,
t stemt Euchangers 148.40 Integrally Welded Attaclaments N/A' O-J r#Ehst. ass Instainstaso Wstus IN Partesc u9.10 teominal Pipe Size > 4 in. l 09.11 Circumferential Welds SUHF AND VOL CR-3,CR-4 09.12 tongitudinal Welds SURF AND VOL CH-4 4 1 u3 20 Nominal Pipe Size < 4 in. us.21 Circumfeaential Wolds Suur ) u9.22 fongitudinal Welds SukF i uS.30 Isranch P!pe Connection Welds u9.11 Nominal Pipe Size > 4 in. SURF AND VOL CR-5 VT-2 l u).32 Nominal Pipe Size < 4 in. SUkr j I u9.40 Socket Welds N/A < li 4 4
!i I
~
-m
u
. _ .,,, INSERVICE INSPECTION PROGRAM h ISI - CLASS 1,2 1 3 COMPONENTS OUAB) CITIES NUCLEAR POWER STATION t
Page a es 15 UHli - 2 CLASS 1 . nesien 2 lpete 9-17-84 CODE 'lVEM SECT M4 EXAM REllEF ALVERNATE CATEGORY Damansa 9,g ggygg . REQUIRED DEGUESTS EXAM ! N-E-1 548?NGhAL ATTACIIst&80TS FOR PIPIT 0G,
.-PUIIPS A400 VALVES I
FIP4pg
,840.10 Integrally Welded Attachments SURF SEE FIG. IWS-2$00-}3,45 rumpa B10.20 - latogrally Welded Attachments SUNF fiME, FIG. IW8-250,0-}3,45 Velves i B10.30 Integrally Welded Attachments SURF SEE FIG. IW8-2500-)3,45 i
4 .
, E- I,- 1, yearamangg gegyggggggg ygg.neg gag 5-N-l Histr CAS180GS A480 VALVE BODIES N/A 4
i j S- 1,-2, PMIBF CASiteGS A480 VAI.VK BODIES d B-n-2 h!2.20 Pump Castog VT-3 CR-6 WHEN DISASSEMS(.ED j j B12.40 Valve Body, Eseceding 4 in. Nominal P!pe Size VT-3 , CR-7 WilEN DISASSEMBl.ED i b {t h-N-1 IttvumIOct or NEACTom VESSEL. i j acactor vemmel i ; HIJ.10 Vessel Interior VT-3 PER TABI.E Iwa-2500-1, l 1 CATEGORY B-N-4. i . i l.
~
c INSERVICE INSPECTION PROGRAM
@f**aa-- :.ne. ISI - CL ASS 1.2 1 3 COMPONEl4TS QUAD CITIES Hl) CLEAR POWER STATION UNIT - 2 #***
CLASS 1 fievisios 2 l0.ie 9 }7-84 CODE 81EM SECT M4 EXAM RELIEF CATEGORY NUMBER IIIU E0U#I" ALTERNATE
" "*""8 MOUIRED flEOESTS EXAM se.ctor vos.et (awn:
213.20 Interior Attachments VT-l ACCESSipLE WELDS 213.21 Cora Support Structure VT-1 ACCESSIBLE SURFACF.S koactor Vessel (twa) , il13.30 Core support Structure if/A j -
' ~
0-0 PMESSuttE ILETAINileG WEI.DS III CoelTROI. NGO NOutstNGS k Reactor Wessel n14.10 Welds in Chu Nousing VOL EX-2 EX-2 APPLIED TO THESE HOUSINGS DUE 'IU ColWIGURATIOl i D-P AI.I. PRESSURE RETAINING CosttoldENTS t 14eactor Vessel t 815.10 Pressure ketaining Boundary VT-2 LEAKAGE TEST , u15.11 Pressure Metaining Soundary VT-2 jiYDROSTATIC TEST h' 1 l Pressurlaer ! 31'5.20 Pressure Retaining Boundary 14/A - 1 14'45.21 Pressure Heraining Boundary N/A i' I Stede Generators ul5.30 PreJuure Metaining Boundary N/A ul5.31 Paemuure Retaining housadasy N/A
! l ,
O"c_e, " INSERVICE INSPECTION PROGRAM ISI - CL ASS 1.2 & 3 COMPONENTS QUAD CITIES NUCLEAR POWER STATION UHli - 2 CLASS 1 **** 38 d 15 fievision 2 lpase 9-i7-a6 CODE 11EM SECT m EXAM IRELIEF Iggg ggggg,pyg ALTERedATE CAIEGORY DeuMetR MOUIRED MOUESTS EMAM EN Issat Escenangers B15.40 Pressure metalning Iboundary M/A
#15.41 Pressure antaining Doundary N/A i
P!Ping 815.50 Pressure Betalning Soundary VT-2 IEA5 AGE TEST a15.51 Pressure Retalning soundary VT-2 Ilypa0 STATIC TEST l 6 '""r"
#15.60 Pressure Betalning Soundary VT-2 1.EAKAGE TEST B15.61 Pressure petalalog boundary VT-2 .NYDROSTATIC TEST
. Walves it!5.70 Pressure Metalning Roundary VT-2 IKAEAGE TEST R15.71 Pressure Metalning Isoundary VT-2 NYl*0 STATIC TEST i
D-0 STEAst GamstuAtolt Tunless N/A I
, i l
i i 5 4 4
. i l
n
C . INSERVICE INSPECTION ' PROGRAM RSI - CLASS 1,2 & 3 COMPONENTS OUAD CITIES NUCLEAR POWER STATION
. tur-2 ctAss 2 **** in a' is Revielen 2 lpase 9.j 7 gst, CODE 11EM SECT M EMAM RELIEF ALTERNATE CATEGORV pamm*5R IVEM DESCHaPTION E REOL81M D ftEOUESTS EMAM C-A PRESSUIME NETAINIt4G WatJnS IN retESSURE VESSEI.S Cl.10 Shell Circumfereutial Welds VOL 90tR 185AT EXCH4tlGER C1.20 NeaJ Circumferential Welds VOL p R HEAT EXCHANGER Ct.30 Tubenheet-to-She11 Wald N/A C-m resSSuas usTAlegtesG soot 2La WELos ,
i IN VasSus.s - I, I C2.10 Nozales in Vessel <I4 in. ; Hominal Thickness SURr Cit-8 VT-2 C2.20 Nozzles in Vessel )I4 IN. ; Nominst Thickness N/A' ![ C-C 887-MAL ATTACM8488tTS F00t VESSEL.S, Fi riteG, PUserS, AND VALVES j Fremmears Vessels ; C3.10 Integrally Welded Attachments Suur ltttR HEAT EXL:lANGER riping C).40 tutegrally Welded Attachments SUkr s I J I lI
f c _ ,,,, INSERVICE INSPECTION Pl10 GRAM I**** ISI - CLASS 1.2 & 3 COMPONENTS OUAD CITIES NUCLEAR POWER STATION UHli - 2 Paee 12 W ls CLASS 2 Devision 2 l Dele 9-17-84 CODE 4 TEM SECT X4 EXAM MtIEF ALTEludATE CAMGORY pamR ITEM DESCR6PIM _ llEMARets MOUIRED ' REQUESTS EXAM pumpe C3.70 Integrally Welded Attachmenta y/A Valves C3.100 Integrally Welded Attachments N/A C-O ymESSuma OLETAINIteG 90LTIteG CREATER TIIA80
- p in. IN DIAssErma Pressure Vessels
, C4.10 Rolta and Stude N/A riping ! C4.20 Solta and Stude p/A Pumps ! C4.30 Bolts asul Studs vol N/A f. j valves ! C4.40 Solts and Studs N/A l i C-r PRESSURE IIKTAINII8G WEIIG IN FIPII4G r I C5.10 riping Welds <14 In. }' i; Noelnal Wall Tlatckneau C5.11 Circuaterentle! Weld SUHF C5.12 Iongitudinal Wold Suur I i
i 1 ON ____ INSERVICE INSPECTION PROGRAM IS4 - CLASS 1,2 & 3 COMPONE04TS OUAD CITIES NUCLEAR POWER STATION _
' 33 # 15 LHI-2 CLASS 2 -
flevtelee 2 j o.te 9-17-84 CODE . ITEM SECT as EXAM IRELIEF ALIEftNATE CATEGeny mamargt ' lIEM EMM MN stEQUIAED lif0ufSTS EXAas c5.2e elping Wende > b in. teominal Wall Thickness C5.21 Circumferentian Neld suar AND VOE, C5.22 tangitudinal Weld N/A i C5.30 Pipe Branch Connections
- C5.31 Circumferential tield Sump CR-10 VT-2 C'5.32 fangitudinal Weld N/A C-G ymema== MatTAINiteG WEE.uS IN yastPS Aage WA8. vets N/A i s
C-Il , AS.I. t****"" ItETAleIIIeG COstlete'asTS l i l Prasoure WeseeIa , C7.10 Pressure Metainisig Componesets VT-2 PRESSURE TEST , C7.11 Pressure hetaining Components VT-2 IIVDROSTATIC TEST l Piping C F'. 20 Pressure Metaining Cosaponesite VT-2 PRESSUleE TEST U1.21 Pressure Retaining Components VT-2 NYDNOSTATIC TEST PuePe6 C1.30 GTenneste Metaining Componciatu , VT-2 PRESSUNE TEST C1.lt Paessure Metaining Cosaponesit's VT-2 HYpHOSTATIC TEST g i e
l %. INSERVICE INSPECTION PROGRAM Eh ISI - CL ASS 1,2 & 3 COMPONENTS QUAD CITIES huCLEAR POWER STATION UNil - 2 CLASS 2 '* 84 " 35 Rev6elen 2 ]Dete 9-17-84 CODE alEM SECT M4 EXAM MLIEF ALTERNATE CATEGORY M MEA II(M DEmim I MQulRED MOUESIS EXAM {' . Walves C1.49 Pressure Retalning Components VT-2 PitBSSokg TEST C7.41 Fressure Retalning Componentu VT-2 l1YDROSTATIC TEST i 4 i f i i 1 t I
- i i
p i ! 1 l t I l ,
t k l C e a.,. INSERVICE INSPECTION PROGRAM Eh ISI - CLASS 1,2 & 3 COMPONENTS : QUAD CITIES NUCLEAR POWER STATION , i UNIT - 2 #*** 35 " 15 CLASS 3 flowision 2 l Date 9-17-84 CODE 81Et8 EECT MI EXAM ' AELIEF ALTERNATE gygg gggc, ,, M 00^8" CAIEGOftV M8 mam84 HEOUIRED 8tEOUES15 EXAss a>- A SYSTsaes su suesent or mEActon , StuTUOWel FosteCTIOst N/A C-a systemas seg sureost? or usosacEseCr coes
' COOLiteG, C000TAltestet? IBEAT REseOWAL, ATee06peewas CLEAleur, Aten ItEAC100t IIESIDUAL IIEAT REseOW4L D2.le Pressure Retalning Components VT-2 . FUt0CTIONAL TEST -
VT-2 IIYDROSTATIC TEST D2.20 Integral Attachment
- Component Supports and Restraints WT-3
~
f D2.le Integrat Attachment !
- Mechanical and Nydraulic Snubbers N/A D2.40 Integral Attachment
- Spring Type Supports N/A D2.50 Integral Attachment ,
- Constant toad Type Supports N/A 132.60 Integral Attachment "
. - Shock Absorbers g N/A f
C)-C Sv6TeJs3 Its burteetT OF RESilMaat. MEAT kapeQUAL Fle0N SPI 2ff FUEL STottAGE 190L N/A , t J p 6 M
. l i
e
~
TABLES FOR INSERVICE: INSPECTION PROGRAM OF COMPONENT SUPPORTS QUAD CITIES UNITS 1 & 2 a i 1
, o e e
.\ .
Revision.2
.~~
t
Q Ef' Eh c.___. INSERVICE INSPECTION ' PROGRAM-
- lSt - CL ASS 1.2 & 3 COMPONENTS .
QUAD CITES NUCLEAR POWER STATION
! UMT - 1 CLASS 1 Pese 1 W e-
!! Rowlelen 2 lpete 9'-17-84 i CODE IIEM sE. CT. M Ex AM AftIEF ALTERB4 ATE
- cAussoar asamwm svEm cescReveon ,,,,,,,, ., sit o ue sys . "E""""8 Exam r-A es.ATu Amo sues.a. Tres suerouTs i
2 ~F-1 Mechanical Attachments, including - i bolting VT-3 1 ] r-2 Welded Attachments N/A I ! r-3 Component displacement VT-3 . , Settings of guides and stops VT-) Misaligneesat of supports VT-) Assembly of support items VT-3 i ! r-m s.sessAm Tres sociesTs . , F-1 stechanical Attachments, including bottiog VT-3 l- ! F-2 Welded Attachments VT-3 l r F-3 Component displacement VT-3
- Settings of guides and stops VT-3 !
I f Misalignment of supixarts VT-3 - t. ! Assembly of support items VT-3 L i t I l I' F-C Costecett387 STanasuun gurgogys i 9 l I ! F-1 Mechanical Attachments, iniclu.tisig f botting VT-3 i l
; ' < t~
. i !'
l e ' 4 8 7 1 9 S a K s e R t e A e p M l E t f 2 2
~
n l e s ie o v s te e s M A 1 X E S M S A A L R O N C S G ST I T S O NT- TA. - E U _ RE S Q E PN OR l f 7 PE _ N MW OO_ O CP I _ D E 3 3 3 3 3 4 4 4 4 T 3R- - R I U T T T T T T T T T C4 A Q V V V V V V V V V _ E 2EL E R P 1CU S SN_ NS AS_ I LE. E CIT- 6 C s C I r e VI SAD b b u RI U. n E O- s S 1 N O s e p N I t i P p o s t t y
- t s r l
i H s a me o p l a N C t d r t t p c - S u U E n n oi e a p s s s n D m pt t a e s e s u r r o p e h t t c e s op p y c e g n a d p p t s m i e l i f r l m p u o u u h s g s s d ed c i t a b n a d f nf e o r a t t t o e o pl o y s c m _ A n s n y t t b i e g gl n al d d l e n nib oil m pt a e m t s s g a n t k a i s c r r n od u _ e o ei s p oh y n _ W C S M A S cS H e.
%E s d
- ME R
0 Em i e 4 2 3 l u a - - - _ B F r , F ' W R EO DG OEI CA _ C
?
il l i -
- : Iii !!!!; ! ! i! 1
_C
, . _ _ ,,,,, INSERVICE ~1NSPECTION . PROGRAM f***
ISI - CLASS 1,2 4 3 COMPONENTS QUAD CITIES NUCLEAR POWER STATION P*, 3 e UNIT - 1 CLASS 2 newesen 2 l0.i. 9-17-84
' CODE ITEas CATEGORV NUMitEn ITEe4 DESCRIPTION $' REMARMS REOueRED ltEQUESTS EXA44 r-A . PLATE Aaso suuLt. Tyre surtostTS N/A F-B LiteEAR TVPK SurtoRTS F-1 Mecitanical Attachments, including isolting VT-3 r-2 Welded Attachments VT-3 F-3 Component displacement VT-3 i' Settings of guldes and stops VT-3 Misalignment of supports -
VT-3 Assentity of support items VT-3 r-C CuesroseENT STANDAlto Surice T3 t'- l Mechanical Attachments, including 1>01 ting VT-) i , F-2 Welded Attachments VT-3 i i 3 F-3 Component displacement VT-3 , Settings of guides and stops VT-3 l Misalignment of supports VT-3 Assent 2ty at support items VT-3 I t: F-4 ' Spring type supporta VT-4 Constant load type sug> ports VT-4 Siiock absorbers VT-4 liydraulic and mechanical type snobbers VT-4 5 1 -
.c.
b INSERVICE INSPECTION PROGRAM
@ *c.,,,,,,,,,,,,,,
*= IS! - CLASS 1,2 & 3 COMPONENTS
- OUAD. CITIES NUCLEAR POWER STATION 3 #***' ' " '
> Ut4T - 1 - CLASS
#ewleien 2 l04e *-17-84 CODE- ' 4 TEM SECT M4 EMAM SELIEF ALIEne4Aig '
CATEGonV am m a . STEM MSCwim REOutRED 'pf0ufSTS EMAN ' OE I F-A PLATS Aseo sast*L Tres sorecetts 1 N/A ] r-a ' LIssuAn Tyrs sorteavs F-1 Nechanical Attachments, including bo! ting VT-3 s F- 2 Welded Attachments VT-3 '
?
P'- 3 Component displacement VT-3 Settings of guides and stops VT-3* Misattgnment of supports h-- 3 Assenhly of support items VT-3' F-C COestPOest:ge? STAsephup SurletTS s'- 1 Mechanical Attachments, including bolting VT-3 i t'- 2 Welded Attachments VT-3 l,
; r-3 Component displacement VT-3 i Settings of guides and stops VT-3 Misalignment of supports VT-3 Assembly of support items VT-3 v'- 4 Spring' type supports VT-4 =
Constant load type supports VT-4 ;
, Shock absortaers VT-4 alydraulic asid mechanical type snutatsers VT-4 i ',
c- INSERVICE ' INSPECTION : PROGRAM
'"' ISI - CLASS 1,2 & 3 COMPONENTS '
OUAD CITIES NUCLEAR POWER STATION
~
. UNIT - 2 CLASS 'l
" 5 d *
Reviseoe 2 l 0.se 4.t7_g4 CODE ITEM SECI X8 EXAM . RELIEF ALTERNATE CATEGORY M ""** R IIEM DESCAN'TW ftEMARKS REOueHED FIEQUESIS EXA44 y-A PLATS aaso seeks.t. Tres SurtenTS F-1 Mechanical Attachments, . Including bolting VT-3 Y-2 Welded Attachments N/A F-3 Component displacement VT-3 l Settings of guides and stops VT-3 l Misalignment of supports VT-) ' l 1 1 Assembly of support items VT-3 i F-R LINEAR TYPE SUPEOttTS i F-1 Mechanical Attachments, including botting VT-3 g F-2 Welded Attachments VT-) 4 s . I j F-3 Component displacement VT-3 l Settings of guides and stupe VT-3 Misalignment of supports VT-3 f j Assembly of support items VT-3 i l l lt r-C Coettoelt:as? STAa4DAND SUPT' ORTS I
- j; ~ .r- i nechante.t Attachments, inctuaing boIting '
VT-3 l
{ J c_,,,,,, > INSERVICE INSPECTION PROGRAM - I"- ISI - CL ASS ' 1,2 & 3 ' COMPONENTS i
. QUAD CITIES ' NUCLEAR POWER STATION tur 2- ctAss i
'***~ ' "
- fievisloe 2 l Date 9-17-84 CODE . IIEM - SECT MI EMAM flElitif CAVEGORY NUMBEA NE" "# ALTERNAT( I HEOUIRED M OUESIS EXAM F-2 Welded Attachments VT-3 t
F-3 Component displacement WT-3
'- Settings of guides askt stops VT-3 .
Misalignment of supports WT-3 Assembly of support items v7-3 q h-4 spring type supports vt-4 Constant load type supports VT-4 Shock absorbers vt-4 .
- l. '
i Mydraulic and mechanical type snubbers VT-( 0 lt i i i l j . i 4 !i
~
i
i , c,,,,,,,,,,,,,,, INSERVICE INSPECTION- PROGRAM ' f**** t ISI - CLASS 1,2 & 3 COMPONENTS
-OUAD CITIES NUCLEAR POWEQ STATION
.U NIT - 2 CLASS 2 Pae. 7 d a~ i
- stevissea 2 l D*8* 9'17-l*
CODE 11EM SECT M4 EMAM MLIEF ALTERNAT$ l CAIEGORY ha mmesR IIEM Mmim ""*"8 ItEOU6HED M oufSTS EXAM F-A Pl ATE A400 Sale 5J.' TVPE SurrokTS -
- N/A F-B L188EAlt TYPE SurtaORTS l
j F-1 Mechanical Attachments, including i botting VT-3 i i F-2 Welded Attacliments VT-3 j r-3 Component displacement VT-3 ? I l Settings of guides and stops , VT-3 8 { Misalignment of supports VT-3 ' , , Assembly of support itema VT-3 F-C 00stif0tlE44T STANDARD SUProstTS . r-1 Mechanical Attachments, including j boIting VT-3' l l F-2 Welded Attachments VT-3 ! t ) ! r-3 Component displacement VT-3 Settings of guides and stops WT-3
! Misalignment of supports VT-3 Assembly of support iteau VT-3 1 . ;
} r-4 Spring type supporta VT-4 i; 4 Constant 1omd type supporta VT-4 4 Shock absorbers VT-4 !: Hydraulic and Mechanical Type Snubbers VT-4
. I ,
L 1
c_,,,, INSERVICE INSPECTION PROGRAM OM*** ISI ' - CLASS 1,2 8 3 COMPONE44TS
. QUAD CITES HUCLEAR , POWER STATION -
UNIT - 2 CLASS 3 "* * # ' Rowenise 2 lDate'9-17-84_ CODE 81EM SECT Ma EXAM RELIEF ALTERNA15 CAIEGORY M m8M8R STEM EMM REOUIREO - REQUESTS EXAM " I F-A PLATE Asen suRLL Tvra surroitTS , as/A r-a usesAm Tvra sureonTs r1 Mechanical Attachments, including . botting VT-3
, o
(-2 Welded Attachments VT-3 r-3 Component displacement VT-3 Settings of guides and stops VT-3 Misalignment of supports VT-3 Assembly of support items VT-3 F-C C0064GI6FJt? STA400ARD SurlOdtTS , 11 r-1 Mechanical Attachments, including , i botting VT-3 ! I i j ry2 teelded Attachments VT-3 l: F-. 3 Component displacement VT-3
~
f Settings of guides and stops VT-3 l j, Misalignment of supports VT-3 l I l. i Assembly of support items VT-3 F-4 Spring type supports ,VT-4 Constant load type supports VT-4 ! Shocit absorbers VT ' Ilydraullc and muchanical type unubbers VT-4 i ) 5
SECTION 2.3 RELIEF REQUESTS FOR INSERVICE INSPECTION PROGRAM Revisicn-2 2-8
- - - - ^
RELIEF: REQUEST NO..CR-1 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE
, REQUIREMENTS.
The reactor vessel is designed with one circumferential and six
. longitudinal welds in the core beltline region as shown on Figure la.
3 The ASME Boiler and Pressure Vessel Code, Section XI, 1980
- Edition through tho' Winter 1980 Addenda requires a volumetric examination of 100 percent of the length of one beltline longitudinal weld and one beltline.circumferential weld each ten year interval (Code Category B-A).
Relief is requested from the above mentioned Code requirements on the basis of inaccessibility. j II.- BASIS FOR RELIEF ( Accessibility for inspection ~of these welds was not provided for in the original plant design which occurred prior to the issuance of Section XI inservice inspection requirements. As_ibdicatedonFigurela,examinationifrom'thereactorvessel outer surface is precluded due the close proximity to the c ,. . , , . , r Revisihn2 2_9
. - - . . - .- . l-
biological shield wall and obstruction by the vessel insulation. The mirror type insulation consists of interlocking panels which were not designed to be easily removable at the weld locatin s. Furthermore, the annular dimensions between t'.ne shield wall and the insulation is not sufficient to allow direct access to personnel. Access through the biological shield wall is only provided at reactor vessel nozzle locations, however, there are no nozzle penetrations in the belt line region. s Examination of the beltline region welds from inside the vessel is impeded by vessel internal design features. The core shroud, jet pumps, and various brackets welded to the vessel wall are not designed to be removable. III. ALTERNATE PROVISIONS
- Currently, it is not feasible to perform the required volumetric examinations on these beltline region welds. Because there are no accessible circumferential welds, Conusonwealth Edison will only increase the examinations of accessible longitudinal welds to achieve an examination sample equivalent to the category B-A (item Bl.12) welds for which relief is requested. . Station's procedure will be revised to ensure the performance of the alternative examinations.
i
+
REVISION 2 2-10 (
--.m _ _ _
1 RELIEF' REQUEST NO. CR-2
.I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE
' REQUIREMENTS The reactor vessel contains thirteen longitudinal welds and six. .
circumferential welds in the shell sections and bottom head which are inaccessible for examination, in addition to the beltline
, region welds addressed in Relief Request CR-1.
4 Section XI- of' the' ASME Boiler and Pressure vessel Code,1980 Edition through the Winter 1980 Addenda requires a volumetric examination of 100 percent of the length of one meridional head weld and one circumferential head weld each inspection interval 4 (Code Category B-A) . As shown on' Figure la and ib, all of the reactor vessel closure head welds are fully accessible for examination. -The bottom head
' welds, however, are inaccessible for examination.
II. BASIS FOR RELIEF - As discussed in Relief Request CR-l', accessibility for
' examination of these welds was not considered in the plant design. The bottom head welds cannot be examined because of the limited physical access, th.e inability to remove vessel
. Revision 2 2-11 L
' insulation panels, and also becausej of interference from the forest ok control rod drive and insy mmentation penetrations.
III.. ALTERNATE PROVISIONS Currently, it.is not feasible to perform the required volumetric examinations on the bottom head welds. Commonwealth Edison will, however, . keep abreast of improvements in state-of-the-art NDE techniques that could provide a viable means of examination. 4 Y
.g Redision 2 2 12
RELIEF REQUEST NO. CR-3 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE t-JREQUIREMENTS' Two Class-1 piping welds in Unit 2 and one weld in Unit 1 are . l phys'ically_ inaccessible for examination. These welds are in the Control Rod Drive System on line number 0308-4" . These welds cannot be examined because of interference from a structural _ suppor't as shown on Figure 4. Section XI of the ASME Boiler and Pressure Vessel Code, 1980
' Edition including the Winter 1980 Addenda requires that twenty-five percent of the total number of circumferential pipe welds-be volumetrically examined each ten year interval (Code Category B-J) . . ,
It is unlikely that these welds be inspectable at anytime during the plant life.: Relief is, therefore, requested from performing the volumetric examination requirements of Section XI. II. BASIS FOR RELIEF The implications of this exemption are minimal due to the fact that safety margins inherent- in the design of the subject welds are typical of those in all other welds in the Class-1 systems.
.Ex.empting,. these three, welds from the. tota.l inspection sampling a .. .. ,.
. program will have negligible statistical significance.
~
Revision 2 - 2-13
III. ALTERNATE PROVISIONS No alternate or augmented examinations'are feasible or necessary in this case. The examinations required-by IWB-5000 will, however, be conducted in accordance with the Code. J ( x . . Revision 2 2-14
"~ . RELIEF REQUESTNO. CR-4 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE
. REQUIREMENTS Each..of the lines listed below penetrates the primary containment by means of a penetration assembly similar in design to that shown in Figure-2. These Class-1 lines, due to the design of the
- penetration assembly, have one circumferential pressure retaining
. weld that is inaccessible for volumetric examination.
CRD RETURN - 0308-4" RER - 1012A&B-16", 1025-20" Rx WATER CLEANUP - 1202-6" CORE SPRAY - 1403-10", 1404-10" HPCI - 2305-10" MAIN STEAM 3001A,B,C,D-20" FEEDWATER 3204A&B-18" The ASME Boiler and Pressure Vessel Code, Section XI, 1980 Edition through the Winter 1980 Addenda requires a volumetric and surface examination on Class-1 welds (Code Category B-J).
~Since.this requirement is impractical due to plant design, relief is requested from the above stated examination requirements.
Revision 2 2-15 o --_
-II. BASIS FOR RELIEF ENsistated in 10CFR50.55a (g)(1) for plants whose construction permits were issued prior to January 1, 1971, components shall meet Section XI requirements to the extent practical. Since examination requirements for these welds did not exist at the time Quad Cities Station was designed, accessibility for their examination was not a prime consideration. Figure-2 clearly illustrates the design constraints which make it extremely impractical to the examine the subject welds by volumetric or
- surface techniques. Commonwealth Edison feels that this L consitutues a basis for relief from the volumetric examination requirements of Section XI. The safety implications of this exemption are minimal due to the fact that the safety margins in the subject welds are typical of those in all welds in the applicable systems. Since the exempted welds represent only a small fraction of the total number of circumferential, Category B-J welds in these systems (14 out of 291, and 14 out of 280, Unit 1 and 2 respectively), the
- statistical significance to the inspection sampling program due to exempting these welds is' expected to be negligible.
. . . ,7 .
, , , . . , r _ . .
..- Revision 2 2-16 4
- s. _----m-p y.-- *-~*y w -y-e-++-w g- wwvg y-ema-mex- 3epp ayw pew w .w.e99...,e--e-qw.-e,-.9, wy.-+v.--me,cg.g wy
III. ALTERNATE PROVISIONS .
, The.first pressure boundary, weld o.utside the containment on each of these process pipes will.be 5clumetrically examined, where practical, over 1007. of its length "dt$ ring each inspection interval. The examinations required by 'IW3-5000 will also be condnered. .
Station!s procedure wil'. be revised to ensure the performance of the alcernative volumeeric examinations. e, . . . . , 3. - . . Revision _ 2 ' 2-17
RELIEF' REQUEST.NO. CR-5 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The design,of certain Class-1 branch pipe connection welds calls
. for the use of reinforcement saddles. These saddles are fillet welded over the-actual pressure retaining branch pipe to main pipe' weld, completely encasing it as illustrated on Figure 3.
There are four such welds that are greater than 4 inches in diameter. '
. a .
' Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda requires that branch pipe connection welds exceeding four inches diameter be surface and volumeerically examined. Twenty-five percent of these welds are required to be examined each inspection interval (code Category B-J). .
Relief is requerted from this requirement due to the physical inaccessibility of the design. II. BASIS FOR RELIEF The fabrication of these joints precludes any type of surtee examination or meaningful volume.tric examination. Additional Revision 2 2-18
.m _
assurance of_the-continued integrity of joints fabricated in this fashion. is- afforded by th'e fact that the reinforcement saddle strengthens the joint and reduces the stresses on the internal
.s weld..
III. ALTERNATE PROVISIONS Surface examination of the saddle fillet welds will be performed in lieu of the Code required examination and a visual examination of these joints for evidence of leakage will be conducted during the pressure tests required by IWB-5000. Station's procedure will be revised.to ensure the performance of the alternative surface examination. L Revision 2 , 2-19
, + - - , , ~ . , , - - , , - - - , - = , , . . , -.__--m_ .-.. .-y.._. __-,__ y - , , , , ,- , - _ - . ___
RELIEF. REQUEST ~NO. CR-6 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS Each Quad Cities Unit has an ISI Class-1 recirculation pump in each of the two 28-inch diameter recirculation loops. These pumps function during normal reactor operation to provide forced recirculation through the core.
'The ASME Boiler and Pressure vessel Code, Section XI, 1980 Edition through the Winter 1980 Addenda requires that one of these recirculation pumps be examined visually during each inspection interval. Specifically, the area of examination includes all pump internal pressure boundary surfaces.
As discussed, in detail below, Commonwealth Edison requests relief from the Section XI examination requirement to visually examine the recirculation pump internal surfaces on the basis of impracticality. II. BASIS FOR RELIEF The basis for this relief request is predicated on the following two points:
,. ,. ,- . , ', q . .
Redision 2 2-20 M
- 1) to -complete- the subject: examination, large -
expenditures of manhours and man-rem are required with essentially no compensating increase in plant safety, and
- 2) the structural integrity af forded by the pump casing material utilized will not significantly degrade over the lifetime of the pump.
Based on data compiled from an actual recirculation pump
' disassembly, it is expected. that approximately 1000 man-hours and 50 man-rem exposure would be required to disassemble, inspect, and reassemble one pump. Performing this visual examination under adverse conditions such as high dose rate (30-40 R/hr) and poor as-cast surf ace condition, realistically, provides little additional information as to . the pump casing integrity.
The. recirculation pump casing material, cast stainless steel (ASTM A351-CF-8), is widely used in the nuclear industry and has performed extremely well. The presence of some delta ferrite (typically 5% or more) imparts substantially increased resistance to intergranular stress corrosion cracking. The delta ferrite
- also.results.in improved pitting corrosion resistance in chloride containing environments.
' . . , < . :i . .. .
Revision . 2 2-21
Commonwealth Edison feels that adequate. safety margins are inherent 'in the basic pump design and that the health and safety Dof.the-public will not be adversely effected by. performing the visual examination of the pump internal pressure boundary. surf aces only when the pumps ara' required to be disassembled for maintenance.. III. ALTERNATE PROVISIONS As stated above, it is not felt that the visual examination required by Code each ten year. interval is warranted. However, as standard maintenance practice dictates, when a pump of this type is disassembled for maintenance examination of the pump internals and internal pressure boundary surfaces will be performed, to the extent practical. 2 i
. .s , .., .
.,+. ,, .. -- ' . , . .:.. . . . r ,.
Revision . 2 2-22
. A
RELIEF REQUEST'NO. CR-7 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS In the Class-1 system. there are 51 valves which are greater ,than four inches nominal pipe size. These valves vary in size, - design, and manufacturer but are all manafactured from either cast stainless steel or carbon steel. None of the valve body casings are welded. i Section XI of . the ASME Code,1980 Edition through the Winter 1980
' Addenda requires that a visual examination of the internal pressure . boundary surfaces of one valve in each group of valves .
I of the same constructional design and manuf acturing method that - perform similar functions in the system. These examinations are required to be completed each inspection. interval. (Code l Category B-M-2) Since these examinations must be met whether or not the valves have to be disassembled for maintenance, this requirement is f considered impractical. s, , . . .,
..( . ., ..,, ,
Revision 2 2-23 f 1
- - - . - - _ . - . - - . _ = _ _ - -
II. BASIS FOR RELIEF The requirement to . disassemble primary system valves for the sole purpose of performing a visual. examination of the internal pressure boundary surfaces has only a very small potential of increasing plant safety margins and a very disproportionata impact on expenditures of plant manpower and radiation exposure. l Performing these visual examinations, under such adverse conditions as high dose rates (10 R/hr) and poor as-cast surf ace conditioni; realistically; provides little additional information as to the valve casing integrity. For_approximately 20 percent of these valves, the reactor vessel core must be completely unloaded and the vessel drained to permit disassembly for examination. The performance of both carbon and stainless cast valve bodies has been excellent in all BWR applications. Based on this . experience and both industry and regulatory acceptance of these alloys, continued excellent service performance is anticipated. 1 A more practical approach that would essentially provide an equivalent _ sampling program and significantly reduced radiation exposure to plant personnel is to inspect the internal pressure boundary of only those, valves that require .disassembly for l c,, .; s . .
, l r
Revision 2 2-24 1 _w_~~....- . - )
maintenance purposes. This;would still provide: a. reasonable , sampling of primary system values and give adequate assurance that the integrity of these components is being maintained. III. ALTERNATE PROVISIONS An examination of the internal pressure boundary surfaces will be performed, to the extent practical, each time a valve is disassembled for maintenance purposes.
. . , .'... : .. .,e:, - .
Revision 2 2-25
- m. ___. .. _ . _ . ._. . . . .
ID/0132A/ F RELIEF REQUEST NO. CR-8
- 1. IDENTIFICATION OFCOMPONEFIS AND IMPRACTICAL CODE REQUIREMENTS There are two 18' diameter nossles in the Class-2 portion of each of the j
- two RER System heat exchangers that are fabricated with reinforcement
- l saddles. .These saddles are fillet. welded over the actual pressure retaining nossle to shell weld. The configuration is shown on Figure 5. .
l
' t, J Section XI of the ASME Boiler and Pressure vessel Code,1980 Edition through the Winter 1980 Addenda requires surface and volumetric examinations of two of these four nozzle-to-shell welds in the inspection inteval. This requirement is impractical due to inaccessibility.
II. BASIS M R RELIEF The fabrication of th6se nozzle-to-shell welds precludes any type of . volumetric or surface examination. The design does, however, provide additional strength at the joint and results in lower stresses at the internal weld. Integrity of these joints will be monitored by periodic system pressure and hydrostatic tests.
.. ss. . v. . .. .
, , ,a. .
' se REVISION 2 2 26
r-- -- . - . .
# III. ALTERalATT PROVISIONS An alternative surface examination of the reinforcing ring welds will be performed and a visual examination for evidence of leakage will be conducted in accordance with the Subsection IldC-5000 requirements.
t Station's procedure will be revised to insure the performance of the alternative examinations. t 9 8
. .. ; v. .is- _,
e REVISION 2 2-27
.-. e eu, ew
RELIEF' REQUEST NO. CR-9 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS Quad Cities Station currently utilizes a calibration block which lacks documentation consistent with the requirements of current editions of the Code. The documentation requirements existing at the time of their fabrication did not require traceability to the material's chemical or physical certifications. As a result, the
-only documentation available for the existing blocks is verification of the appropriate P-number grouping.
The Section XI requirements of the 1980 Edition of the ASME Code including the Winter 1980 Addenda specify that the block will be fabricated as provided by Article III-3400, paragraph III-3411 requirements. Relief is requested'from this documentation requirements to allow the continued use of the existing calibration blocks. II. BASIS FOR RELIEF Previous inservice inspections have been performed utilizing the above mentioned block and Ies use would' provide continuity in the ISI Program. It would be impractical to f abricate a new
.e :
. .: s .
Revision 2 2-29 E s&
cal.ibration- block- in order to satisfy the-documentation-requirements of the current Code. Existing records which indicate the.appropriata material P-grouping provida adequate assurance that.the block will establish the proper ultrasonic calibration and sensitivity. Additionally, since both reactors vessels are 100% clad on the I.D. surface, there is no way to meet the requirement of verifying the acoustic properties of the bicek against the clad component. III. ALTERNATE PROVISIONS The present reactor vessel calibration block will be demonstrated to have acoustic attenuation and velocity preserties which fall within the range of straight beam longitudinal wave velocity and attenuation as found in the reactor vessel. However, since Quad-Cities Station reactor vessels are 100% clad on the I.D. Surface, this check will be completed on the clad component and - appropriate reviews made by the C.E.C.O. Level III Examiner to verify the acceptability of the block.
,s ..
Revision 2 2-29
RELIEF REQUEST NO. CR-10
- 1. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL. CODE REQUIREMENT The design of certain Class-2 branch pipe connection welds calls for the use of reinforcement saddles. These saddles are fillet welded over the actual pressure retaining branch pipe to main pipe weld, completely encasing it as illustrated on Figure 3. A3 listed in'the~ program, there ~are 40 such welds that are greater San 4 inches in diameter.
4 Section XI of the ASME Boiler and Pressure Vessel Code,1980 Edition through the Winter 1980 Addenda requires that branch pipe connection welds exceeding 4 inches diameter be surface
' examined. (Code Category C.F)
Relief from this requirement is requested due to the physical inaccessibility of the design. II. BASIS FOR RELIEF 1 The fabrication of these joints precludes any type of surfact examination.. Additional assurance of the continued integrity of
~
joints ' f abricated in ' this f ashion 'is afforded by the fact that s, Revision 2~ , 2-30 ,
e-. . . _ . _ . . _ . . .__. _. . ._ .. . . . . the reinforcement saddle strengthens the joint and reduces the stresses on'the internal weld. III. ALTERNATE PROVISIONS Surface examination of the saddle fillet velds will be performed in lieu of the Code required examination, and a visual examination of these joints for evidence of leakage will be conducted during the pressure tests required by IWC-5000. Station's procedure vill be revised to ensure the performance of the alternative surface examination. iREVISION 2 2-31 _ _ . . . . . _ . . - . _ . . . . ~ . _ u-__:.__ .
ID/Ol32A/ RET.TRF REQUEST NO. CR-ll I. IDENTIFICATION CF COMPONENTS AND IMPRACTICAL CODE REQUIREMENT Section XI of the 1980 Edition of the ASME Code including the Winter 1980 Addenda specifies that a volumetric inspection of all full penetration nozzle inside radii sections (code category B-D, item B3.100) each ten-year interval. The design of the Standby Liquid Control (SBLC) Nozzle as shown on
- Figure 6 pro *vides an inner radius geometry which is not conducive to ultrasonic inspection.
Relief is requested from this SBLC inner radius inspection due to the nozzle inside radius geometry. II. BASIS FOR RELIEF The design of the SBLC nozzle piece does not lend itssif to ultrasonic l
-inspection. 'The nozzle as shown on figure 6 has an integral socket to which the boron injection piping is fillet welded and consequently provides a geometry which will result in a meaningless ultrasonic examination.
. .-III , ALTERNATE PROVISION . , .. . , ,
i v. No alternate or augmented examinations are feasible a this time. 9 REVISION 2 2-32 - _ . . , m- w
m _ ID/0132A/ f RELIEF REQUEST NO. CR-12 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS Each Quad-Cities Unit has an ISI class 2 HPCI Turbine in the HPCI System. The ASME Boiler and Pressure vessel Code, Section XI 1980 Edition through the Wint,er 1980, Addenda requires a hydrostatic test once every inspection interval on all ISI class 2 pressure boundaries. Relief is requested from this Code requirements in order to avoid i, - damaging the turbine's labyrinth seals. II. BASIS FOR RELIEF
- The labyrinth seals used in the HPGI curbine are designed to prevent steam from leaking out of the turbine casing. . The fragile design of the -
seals is not intended to retain water under pressure. Therefore, performing a hydrostatic test on the turbine casing will permanently damage the turbine seals. III. ALTERNATE PROVISIONS
. A Sys,tes. functional test will be conducted. iro 11au.of the hydrostatic .
test. _._ EREVISIGN 2- 2-33 e - + yyv-wy- M - --+= ?yre w-- t-g v--g-m--W-+ y-59^1 T#'" '9FMr -W 'W
RX VESSEL FLANGE 8
$ b-C s -
SHELL COURSE.#4 w [5 -
~
REACTOR VESSEL
- 4 g g , q INSULATION
,_ h 4 23 - 4.75" THICx
; 4.25" CLEARANCE q 7 FOR VENTILATION
\ -
S* S* TYP! CAL REACTOR
- VESSEL N0ZZLES .*
T _ b s- e o e F\
- g k g l
;\
*. TYP! CAL REACTOR SHELL COURSE #3. ' W .g.- VESSEL CIRCUNFER--
shg / ENTIAL WELD
.. s s,
Q 3-3 A;)\ -;
\
'.- h.
s, c ..__ .. _ _ , SHELL COURSE +2 s; i .., 4 l f I [' CORE REGION
*/ -
fyNi
; - ef e Ie ;:
s s f SIOLOGICAL SHIELD m. s l l ,
, jig
* ' l
.*. s N .I ( --
( B* I TYPICAL REACTCR ll-l
- VESSE', LONGITUD!.u.
l' l
\ !
p l
-~~ --
Z" WELD (ROTATED .NT SHELL COURSE #1 & l f NV 1 e 4 d 1 4 V mg q
".* * ;. s s !.
s i BOTTOM HEAD 'i 3 ALL WELDS B 2 l d.:.
- . ,s .
REACTOR VESSEL '.'" l CONTROL Rop.CR!vE
- 1 HOUSINGS (u / ,
SUPPORT SKIRT W /.pg" .*- - j;... :.. P:
..~.
FIGURE 1.a f ~ REACTOR VESSEL 'JELD IDEilTIFICATI0li
.. ~~ - -
Ravision 2 2- 34
Head Nozzles
/
5 Typical Lifting Closure Head. Lugs All Welds B-8 l i I N I d
.f FIGURE 1.b Reactor Closure Head Weld identification
, ,~~ . . .
Revision 2 2- 35
- . *e .
O .
- - .w-,, , v ,-.,,w- .n . - - ,- .- e a -
i i l l 4 s PF
/
a=
===
-=< . . .
/
.= m=
a= =
$ a
= A E
z =
= 0 H .,
<a 2
- =,
m' . .
.)
g
\l \,m i
=
= F =
E A H
-z = / .
Z EE
,. X a / ! '*
.La
.m =
-Q; ...
==
Y f z Y f .
/; , ,. n . o ~ .
/ . =
l 5 .a. .;c
=
x a.~, . f
,' ' 5
..=
~
m x gY' ll* z .: - I =.
\ ,. ., ,
t .< .-- /
- 5 -
W,. , ., E - f
< ~
y V l :.
- m. ,. . i K ..
/ Ei
~~fff} 7 /
f'
/. / ,
a; u:
.' y
~ ~.
/ = ~
'- . C
* '. C
( s ...
/s.
~
al l f - ea
=a =-
fd 'I' / fd
=-
es w W a\ =
==
.e -
=~
=
~ ., "'
.x , "
z
.E$ e .x. . . .
== b =-
~.
va .
~
.e Revision 2 2~ 36
- - -.- . . . ..= ..-.. .---
INACCESSIBLE WELD f (PRESSURE-RETAINING) i /
- /
~
' BRANCH PIPE RUN s w 7
p - ( f V I
- REINFORCEMENT
- PLATE i
\ MAIN P!PE RUN INACCESSIBLE WELD (PRESSURE-RETAINING)
/
- . - )
/ FILLET WELDS I '
b.
/
+ . . . .
\
/ BRANCH P!PE RUN
/
l /
/ , REINFORCEMENT l' / SADDLE.
MAIN PIPE RUN FIGURE 3
' ~ TY' PES '0F' REINFORCED BRANClf PIPE -' CONNECTIONS Revision 2 2 37
I Guide , mm
- v,
~~ 4) i I
Line 0308-4'
]_
Weld # 03 - Fil (U-2)
-STRUCTURAL STEEL GUIDE PENETRATION SLEEVE ,
wg. 3 (3-317 "j-;)
#C3-518 '.-:;
~
- . LINE 0308-4" N, g t 2Q N gN N '% -
* ~
. g% , . ,
% //
. : FIGURE.4- ,
WELD 03STRUCTION DETAILS Revision 2 2 3S
~ *
-y - - . u -ww , -w.-pg- -.,,,w-, g- ,ww. ,---w. ~gs.- ., - ,,-
18" N0ZZLES' (TUBE S IDE-RHRS SERVICE ~ WATER) 4" RELIEF VALVE CONN. E I I
/ I y .
4
\ 'I/ . I S I-CLASS 3
.? ,
SU [ATC-A III ,l CLASS 2 l - , i l 1" VENT CON INTEGRALLY WELDED SHELL
, SUPPORTS CAT C-C L /i lN 1 . . .. .
RHR HEAT EXCHANGER SHELL RE!NFORCEMENT PLATE 18" N0ZZLE t 2" RELIEF (SHELL SIDE - VALVE CONN as j 1 / RHRS WATER) (A
~
l 2
,C ? . .
~
CAT C-A l (~ ._,
/
FILLET' WELDS II II I l
-l 3/8" r'I INACCESSIBLE
' CAT C-D- / CAT C-A FILLET WELD (PRESSURE RE-QE. TAIL A" TAIN!NG) CAT C-3 l'I DRAIN' CONN .
- - .EIGURE.5 :
RHRS HEAT EXCHANGERS Revision 2 2 _39
.-,m,--,.w-, - . , - , - - vwyw+,,,--ew--m-y,.,, , ,w--w- ,9.,.4 rs p-
, u .- _ , ,,
e S E ,
=
k. a s a fN 5' a N W e e N . N
~
g 8 . \ \
& 3 \'
N t N i
\t 4
}
/ / X ,
3 s/. , , + m - i , 1 e l
,, m , e _ .- =
l u E d REVISION 2 2-40 a _s _ y ,
' " w - e*= -- --% ,. . _
l
)
' 3.0 INSERVICE' TESTING' PROGRAM FOR SNUBBERS
; 3 .1 , . GENERAL INFORMATIO_N .
The. Inservice Testing ' Program for snubbers meets the requirements of subsection IWF, of Section XI of the ASME Boiler and Pres:sure Vessel Code, 1980 Edition
'through the Winter 1980 Addenda. Where the requirements .
are determined to be impractical, specific requests for relief have been written. The IST Program for snubbers is presented in Section 3.2 in a tabular format. The snubbers are listed without Code category as there is no category assigned by Section XI of the.ASME Code. The information given in the. tables is explained below.
'A. * ~ ISI Support No. - lists the number assigned to the support assembly which belongs to ISI. class 1,-2 and 3 (i~.e. structural attachments and snubbers).
B. -Tech ~ Spec' Snubber No.' -~ lists the unique number assigned to the snubber. -
- Revision 2 3-1
C .. . Snubber- Type - identifies thee snubber. type (i.e. It
= mechanical, E = hydraulic D. System - gives the'. system abbreviation (see tables 3.2L1) of. this. program for' explanation of abbreviations.
E. Test Parameters - lists the appropriate test to be performed on snubbers. These tests are referenced to the appropriate paragraph within IWF-5400. F. Remarks - gives general clarification remarks. Tables-3.2-1 list the systems and their respective PrID numbers which are covered in the Snubber Testing Program. l There are no relief requests applicable to the Snubber Testing Program.
.. .c - , . . .
Revision 2 3-2
- a
= ^ " " ^ _1.,. , ,
SECTION 3.2 TABLES FOR INSERVICE TESTING PROGRAM FOR SNUBBERS A. QUAD CITIES UNIT-1 B. QUAD CITIES UNIT-2 ?' f l I 1 Revision 2 3-3 E
. - _ . . _ . . _ . . _ . . _ , _ . _ _ . , , _ _ ~ . . . _ _ , _ _ _ _ , . _ . _ _ _ , . _ . - _ . . . . . _ . , _ . . - - _ . . . . . .
TABLE 3.2-la
. . _ LIST OF, SYSTEMS INCLUDED IN THE SNUBBER. PROGRAM FOR UNIT-1 SYSTEM REFEREJCE-SYSTEM NUMBER P&ID Recirculation (Recirc.) 0200 35-2 Control Rod Drive (C.R.D.) 0300 41 Residual-Heat Kemoval (RERS)- - ' -
1000 37 & 39
' Core Spray 1400' 36 Main Steam 3000 13-1 & 2 High Pressure Coolant Injection (HPCI) 2300 46 Diesel Generator cooling Water (DGCW) 3900 22-1 g
Revision 2 3-4 aw-- -
-3,4 , - , y,. -e - - , - - -,w-.
4 - -,,--,.w.,.4y q. - me- ,.
(. (.) A-co,,,,_,,,,, INSERVICE TESTING PROGRAM E. Ism, ggg gig g gg g p3g gg g gwp.g4ygg g ' OtlAD CilE S iMICLliAll POWEll SI Alh Ni
"'"" I ** 4 UNil -
1 i .....i.. 2 loie 9-11-84 SNUSSES VEST PARAMEltR$ l
"" $NU00(0 NO. JVrg SV5HM {,} { ,)
.NfMANKS
, IM "_ .I_ _ . . . _ . - _ _ . . .
.. ..L ._.
.._ . { 2..g.. . _.
i j 1404-W .',103 1-1 H core Spray X' X 1404-W-{03 1-2 H core Spray X X IIn03-W-103 1-3 H core Spray X X-1403-W-103 1-4 H core Spray X X i 1012A-W'101 1-5 H RilRS X X I 1012A-W-102 1-6 .H RilRS X X 10128-W2 102 1-7 H RilRS X' X 10128-W.101 1-8 H RilRS X X 0200-W-159 1-11 H Rectre (1A-202 PHP) X X 02'0-W 0 127 l-12 H Rectre (15 202 PHP) X X Recirc (IA-202 PHP) j 0200-W-107 1-13 H X X l 0200-W-129 l-14 H Rec t re (18-202 l'HP) X X
~
2 0200-W-!28 l-15 H Recirc (15-202 PHP) X X i .. 0200-W-154 1-16 H Recirc Ring Ilea.ler X X i
~
l 0200-W-143 1-17 H Recirc Ring Ileader X X 4 0200-N-110 1-18 H Recirc (IA-202 Hotor) X X 0200-H-130 1-19 H Recirc (18-202 Hotor) X X
- 0200-W-169 l-20 H Recirc X' X 0200-W-IDH 1-21 M Recirc (IA-202 PHP) X X
< NOTES: (1) Test as required by IWF 5400(11)(1)
'(2) Test'as required lay IWF 5400(13)(2) j (3) Test as required lay IWF 5400(b)(3)
' I .
)
INSERVICE TESTING PROGRAM
@c.,,we,,I'8'N Sf 4 M ult ll IES11NG (lWF-fMNH))
. (RIAD Cile S IMICI EAll POWEll STAlHifl
' *"T .2 ,_e 4, __
UNil - 1 l.ewr.iin - 2, )qpair '
,t g-84
# l' IN %3lTopi HumelR Ma eg 5V51(M
- g. g-)- Nt MANK5 .
. 02bO-H.)l1 1-22 H Rectre (IA-202 Hotor) X -
X 0200-H.}l2 }-23 H Rectre (IA-202 Hotor) X X p200-H'131 1-24 H Recirc (115-202 Hotor) X X Q200-Hd32 1-25 H Recirc (IB-202 Hotor) XI X 3035A-N-101 1-28 H Hain steam (Sky disch) X X . 1015A-Wi202 1-95 H RilRS X .' X
. ~
1015A-y-203 1-96 H RIIRS X'. X 1-43 N Recirc X X 0200-H-4.74 . Q200-H ,172 1-44 H Rectre Xi X 0200-N-175 l-45 N Recirc X. X 0200-H-174 1-46 Il Rectre X X 1-47 N Rectre X X
- Q200-H-{73 1-48 H Rectic X X 0200-H }70 l0ll-N-llt 1-49 H RilHS/llead Spray X X
'iO0 lt.-N- 101. 2 1-58 H Hain Steam X X
{ 1-63 Hain Steam X X 10Clli-H-101.1 H i i NQlgS: -(t) Test as required by !WF'5400(b)(1)
-(2) Test as required by IWF 5400(b)(2)
.(3) Test as required by IWF 5400(b)(3) f
. . ~ . . _ - . - .
l 4
.l t# l
- 2 .Y
. m-t
)
e
; NN w m
g M h i - r.r :E
~
b e e
). -
E. , 3 ,
$ g
~,.
i$ l d EF
. ~ tz e
= .=
i
- E i 1*
=kI
- NI I
O 2 "'I 1 C, C ' l 1 8 L,e+ e l. . L M M M M M M M M M M M M M M M M M M M i g$ $l '
.E~! -
z . i , yy,_k, u p . 4 W M M M M M M M M M M M M M M M M M M M M px'
= f i l .
'MWO4' ,
O NE d t
= ' h ,0- 4 4 l
ge W _f
!. ?'-
w . _E .i, _1
- = r e
a a e a a s o e e a e a G G G G 3 G U g u u w w w w w M M M M M M M l - j g M ase g g C C g C M M M M M M M M M use AA A
=* U Q = =* == * == -e M as og as as s z as as *J .= N m 9 L & 4 4 4 4 4 4 = = = = = = = = = b www 3 z *3
. = x x x x x x as s E at 3 3 is M E = maa-
.3 o .3 www f~
OCO
- OCC as 44e g com
- rx x x zz z x x x z^z z z z z z rz m. m. m.
333 ao ame sus hhh A^^
.g N ., . - ,,,
-l - g f P"= W @ C ** f m @ f Pa= W @ C =*
- W 9 0
( 4 4 4 @ P= W N. P= P= @ .e e m a=* .C
-e == == *- ** he be he 8 8 8 0 0 1 0 6 0 0 I i 0 I I 6 =8 es es*
l .$.e . ae a-o e a=> 0 . e.8* ==n. ao aan = == me ame a=+ e 3 3 :p i- ! =* Cr* P ty'
.c g !. he he la l'
I e e a 5 uw ** w wu N == .=* as a* e M e 1
. == . N. ===. . N. . . . g g g j
- m Oi
== . N. .* a* N + N == 4 e @ @ N m t.= H H N
i O - == O O O
== == , .ce C C P4C C C NC o o C C N-C
.= ** .e..,.m. N- N C. .A ^ ^
' e ,. , .o.e .C ~. m. e- - N, .. N, . . e . N, . e z err ee K
- E' z E ?." x 3 . N,K.x , x x z z z z
". e.y .e e. , s e..N NM
.=/
e www e e e i e e i e e e e e i e i 3 e e U U .O 2 a < .e < 4 < su M a 1l
.m
. msir. e m == - .-o == ** e e m m m e 4 N@ g
.m i , , ' ae
- as a-o .* .e
* -o == a* Q g 3 . - C ,O O'C+ O C C O M =
l
=> . N N vet M M et M M - * == .C =* ** ae .=* == N I . .
[. . %- y
7 C. U
- k Co, .s l , INSElWICE TESTING PR4GHAM I'l'" StuNillEll liiSING llWF-5000 l *
()tlA() Cile S tulCL EAll POWEll SIAIR)ft "M- '
'"' 0 UNil - !
- . . - . . _ _ . _ _ _ . . 8 "9;"" . 2 -lp.iie 9-}1-84 5ttleetR . lt5I l'AR AME1855 I E
$# hup 9t$ if0 sysI(M ^""
. TYrl (1) (2) l'Il 2'IO6-N-205.1 1-112 H llPCI X X 2306-N-2h3.3 l-l H llPCI X X 23p6-N-203.2 1-}l4 H llPCI ,
X- X 2306-H-203.) 1-(15 H llPCI X X 102;i-N-101 1-122 H RIIRS X X 1025-H-101 1-123 H R!!RS X X 1025-H-i.03 1-124 H- HilRS X X 1025-H-103 1-125 H RIIRS X. X, 3950-H-313.1 1-126 H DCCW X X 0328-H-2b2 1-128 H CRD (SDV) X X 0320-H-202 1-129 H CRD (SDV) X X t i _ __. _ _ _ . _ _ _ . . . _ . _ .. ._
. HoffS: . (1) Test as required by IWF 5400(b)(1) l (2) Test as required by !WF 5400(b)(2)
(3) Test as required lay IWF 5400(l.)(3) l 1
e TABIE 3.2.lb
. LIST OF SYSTEMS . INCLUDED. IN _THE SNUBBER PROGRAM FOR. UNIT-2 ,
SYSTEM REFERENCE SYSTEM NUhBER P&ID Recirculation 'Recirc.) 0200 77-2 Control Rod Drive (C.R.D.) 0300 83
~
' R,esidual Heat Remova3 (RHRS)
~
1000 79 E' 81 Reactor Cleanup (RWCU) 1200 88 Reactor Core Isolation Cooling (RCIC) 1300 89 Core Spray 1400 78
.High Pressure Coolant Injection (HPCI) 2300 87 Main Steam 3000 60-1 & 2 l
\
' ~
-L. ,
-Revision 2- 3-5 m ,y. ry -.,. ,
.' c,,, . . ,, INSERVICE TESTING PROGHAM t Eise.sne .;g g gg g gg g g gggg g ; ggwg, gyggg iJLBAll t ila ti 144N:1 Fall Pt )Willt *il Allt st1
. . . - . .m...,_
W ii - 2 i '" t: 4 1.r.r .o 2 ..se 9-I/-84 l est sus ms teumsta ,, sysegu . .
, Ed^ N5 -- ~
se masins 1404-W-103 2-1 H Core Spray X X 1404-W-103 2-2 H Core Spray X X j 1403-W-103 2-3 H Cose Speay X X q 1403-W-103 4 H Coic Spray X X 1012A-W-101 2-5 H HIIRS X X 1012A[W-102 2-6 H RilRS X X 10125-W-102 2-7 H RilRS X X 10125-W-101 2-8 H RilRS X X 0200-W-107 2-18 H Recirc (2A-202 PHP) X X l 0200-W-127 2-12 H Hecirc (2B-202 PHP) X X 0200-W-109 2-13 H Necisc (2A-2d2 PHP) X X 0200-W-128 2-14 H Recirc (28-202 PHP) X X 0200-W-129 2-15 H Hecirc (28-202 PHP) X X U200-W-154 2-16 H Hecirc Hing Ileailer X X 0200-W-143 2-17 H Rec t re Risig Ilea.ler X X 0200-H-Il0 2-18 H Hecisc X X
- 0200-N-l~lo 2-19 H Recirc X X 1 0200-W-108 2-21 H Hecisc (2A-202 PHP) X X 4
1* 0200-H-lit 2-22 H Hectre (2A-202 Hotos) X X i l' ! i 0200-N-l12 2-23 H Hecirc (2A-207 Hotos-) X X i M ES: ' (l) Test as reepstrcal lay IWF. 5400(Is)( 1 ) 1 - ) (2) Test au respai rcel lay IWF 54tHl(la)(2) i I (!) Test as respaired lay IWF $400(1,)('l) I s - - . - . ~ . - . . . - . . . - ...
4 8 m - ,
. 1, t
,4 9
. a n
ta
' [I . . . .
. 2
" r.
. c.
s M A I _H W ( l . N I Gg l . 0 glA. s i i , u 1 g t , a s ( g
, l t
P9 I m A yWm !i A s X X X X X X X X X X X X X X X X X X X X Gg wO. g
'l -
r , N I ; l s T glA g t
. i ,
S.l - ; X X X X X X X X X X X X X X X X X X X X EtC Ty l l i g N . g i . Eg i 2 g 1 Cg1 i 1 1 ) ) I
;g C .,
r V g s u o R ;ll m t u o t E A m. l H H S Ul
, 2 2 N
I 0 0 2 2 2 1 5 8 m m im s n mm a s i p mm n e m
- 2
( 2 ( a e t a a a a a a a a a a a t e e c e c e e e e e et t t t t t t t t t c c S S S h S S S S S S S S c i c) ) ) e 1 2 l _l i s i t i n C n n n n . e n n n n n en 1 l l t i ( ( ( N c c i I i i i i a a a a a a a l i i i i i
- s. a a l
a. C C *C c c n' e e
) ) )
s e 3
.U e e a C l' l I l 1
_ R R H H H H,H H t
- H H H H H H i l
i i l l R R ( ( ( 000 _ 000 4 4 4 55 5 a F. F F
= WWW
.p _.
H l l H H H H H H H H H H M H H H H H H M I I I s yyy
. a l R e la m .
. dlid
. eee u
r r r 4 5 8 2 4 5 6 1 2 6 7 8 1 2 3 6 7 8 9 0 iii 8 u uu
, m 2 2 2 4 5 5 5 6 6 6 6 6 7
7 7 7 7 7 7
- - gs sg q 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 eee
. m r r r
, s s s aaa
,, m
. t t t a
s
. s s s cE ee e TTT 5
1 1 2 1 3 2 1 l I 1 2 1 1 1 1 1 1 1 2 1 1 2
. 2 l
1 I
. ) ) )
1 2 01 6 0 0 1 0 u 0 0 0 0 0 0 0 1 t 2 1 8 1 21 ~
. 3 1 0 1 1 l 1 1 1 1 1 1 1 0 u 0 7 5 ( ( (
.- 1 1 - 1 , - - - - - - - - - - 1 l 1 1 1 ~
' - ' - ,N - t
) i t
N N -N H-H.- H - H - _ H, l t H H - H H- H
. H - H A- - N
- -A A A Bl i l C C c p D D -
5 5 5 0 0 0 0 1 7 l 1 l l 1 ! l l 1 1 S 0 02 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E 2 0 3 0 0 0 0 0 0 0 0 0 0 0 3 3 3 2 2 0 0 2 2 T 0 0 3 1 3 3 3 3 3 3 3 3 3 3 3 2 O N 6 I i r . .
f % INSERVICE TESTING Pf10 GRAM - Oc. I '8'5'"' m e. : . , . . - - - - - - - - - - . tilit listil lt il_!iltK; l iwl- .otus ) (M SAI) Olu ti tilH:1 E All IN)WEll til Alp all UNII - 2
*'" I~ ' #'
i.ew.y.o 2 f 5 '8" 9-1J-8/n
*I 5HUSSER ltSI PAN AMt H MS l II' E
$NUSSER HO IYPE SYSilm MI M Alf MS 5 0200-H-ilo 2-81 M Rectre X X 0200-N-169 2-82 H Rectre X X 1025-H-102.1 2-83 H RilRS/SDC X X 1025-H-102.1 2-84 H RilRS /St>C X X
1025-N-101 2-85 H RilRS/ Sinc X X
~
1025-N-101 2-86 H RilR3/SDC X X > 1202_Hfil5 ' 2-87 H RHCU X X 1202-H-Il5 2-88 H RWCU X X 3001BcH-101.2 2-89 H Hain Steam X X 1404-N-206.1 2-113 H Cose Sgiray X, X 2306-H-206.1 2-!!4 H Ill*C I X X 2306-N-205.2 2-115 H lit *C I X X 2305-N-211. 2 2-120 H lil'C l X X
; 2302'H-202.1 2-121 H Ill'C l . X X 1016A-N-202 2-122 H HilRS X X 1016A-N-203 2-123 H RilRS X X 1015A-N-202 2-124 H RilRS X, X 1015A-N-201 2-125 H RilRS X X i .
101515-H- 201 2-126 H RilRS X X 1015]!-ti- 20l ____.___ t 2-127 H RilRS X X
; 8eOIES: ,,(t) Test as regist red lay IWF ,5400(le)(1)
(2) Test as required lay IWF 5400(i )(2)
- j (1) Test as registred ley IWF $400(le)(l) w= w --eem- - e . - = , - - , e
__. c o.. .,,,,, INSEFlVICE TESTING PROGRAM f *8'$'* !aan ud il it 'ileg t iIwl !4Wus I (JtlAll Clid :i, tmh ll! All Pt )WEll fil Alle til UNil - 2 - s .r .. 2 lp i 9.!7-84 lt51 FAN AMillR5
*** 5NUtstR SvillM #8 M^kM5 ;
til surtoR easmett $NutetR HO. IVrt 10155-II-201 2-128 , H NilRS X' X X X 1012A-N-203.1 2-129 H RilRS X X 1404-H-207.1 2-130 M cor e: Seray i X X 1404-H-207.2 2-131 H core Spray . X X 2306-W-207 2-132 H lil'cl 2306-H-205.1 2-133 H lil'cl X' X , X X 1043B-H-101.1 2-138 H RilRSW l 1 t NOIES: ( l) Test .a s scapitryst ley IWF. 5400(li)( l ) i (2) Test ins reapai red ley IWF 5400(13)(2) (1) Test as scepaircel lay IWF $40ti(1.)( !) MMa we -
4.0 INSERVICE ~ TESTING' PROGRAM'FOR PUMPS 4.1 . GENERAL INFORMATION- , Ther Inservice' Testing Program for ISI Class 1, 2 and 3' pumps meets the requirements of Subsection IWP of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda. Where these requirements are determined to r be impractical, specific requests for relief have been written. The tables in section 4.2 list all Class 1, 2 and.3 pumps which 1 are within the scope of IWP-1100 to be tested along with the
- parameters to be measured for each pump unless reference is made to a relief request. Section 4.3 includes all relief requests referenced in the tables plus any additional relief requests that
.are generic to the pump testing program. Table 4.2-1 lists the systems and their respective PriID numbers which are covered in the pump testing program.
It should b'e noted that pump speed is not measured for synchronous type pumps per IWP-4400. Where pump suction is from a tank or the river, inlet pressure will be calculated from the measured tank or river level. Revision 2 4-1 m e.:4-, ase 4 doneWB * ,p.. g
- O
SECTION 4.2 TABLES FOR INSERVICE PUMP TESTING PROGRAM A. QUAD CITIES UNIT-1
- ~ B'. -QUAD CITIES UNIT-2 1
9
~- ;s .. , ; ,
Revision 2 4-2 k---. .
TABLE.4.2.la: ;
, . LIST .0,F SYSTEMS, INCLUDED .IN THE. PUMP PROGRAM FO,R. UNIT-1 .
SYSTEM REFERENCE SYSTEM NUMBER P&ID
, Core Spray 1400 36 Residual Heat Removal 1000 37 & 39 Residual Heat Removal Service Water 1000 37 & 39 Standby Liquid Control 1100 40
- High Pressure Coolant Injection 2300 46 Diesel Generator Cooling Water 3900 22 Diesel Generator Fuel 011 Transfer 5200 29 Revision 2 4_3 A
a3r - INSERVICE TESTING PROGRAM UNIT - 1 C . . 481- CL AQQ.1 2 & 3 PUMPS
%] [alissa " g %g QUAD' CITIES NUCt. PAR POWER STATION
_ _ ___ _ _ _ _ _ l M7_.__[7__%__4 ___ . e- o
.e fist FasAasfMAs '
ygg, ggggggg pgg, p 'e g F 6 la Alst. lisi d coeRemalti snie inst swa new states misant
; rass taas aAu ****'*" unse
- i. 1 !
4A-14GL , CORE SPRAY '2 36 E-h. No YES YES lES PR-1, PR-1 QUARTERLY 1 R- 1401.'. CORK SpetAY ,;. . 2_ 36 E-(> No YES YES YES PR-L PR-1 QUAltTEstLY I A-1002 '- RESIDUAL NEAT REMOWAL ' f 37 S-( NO YES YES YES PR-1 PR-1. QUARTE 3tLY 1 R- 1002', . - RESIDUAL NEAT RDe0W4L'i 2' 37 E-h No YES YES YES PR-1 PR-1 OUAltTERLY IC-1002.'. RESIDUAL IIEAT REnov&L , 2 37 S-k' NO YES YES YES -PR-1 PR-1 QUARTEltLY 10-4002' - RESIDUAL I4 EAT Bue0 VAL 2 37 'E-$2 MO YES YES YES PR-1 PR-1 QUARTERLY t-1001-65A RNet SERVICE MATER 3 39 f-( NO YES YES YES .PR-1 PR25 QUARTEttLY t-1001-65u RNR SERvlCE MATER 3, 39 ,r-(*. No YES YES YES 'PR-1 PR-1 oOARTERt.Y t-1001-65C ItssR SERVICE MATER ; 3 J9 ,F-1; No YES YES YES Pat-1 PR-1 OllAkTEttLY l-1001-650 ' tulu SERVICE MATER , 3 39 F-7. No YES YES YES . PH. -1 PR-l OuARTERLY STANDRY LIQUlp C0:07300) IA-IIO2 2 40 p-7j No PR-3 Pit-3 YES PR-1 PR .! QUARTERLY 116-1102 STANDRY LIQUID CostTROL' 2 40 E-7[ No PR-3 FR-3 YES PR-1 PR-1 OuARTERLY 1-2302 2 MIGet PetES Coot.Aal? Ill.3 [ % 46 A-j YES YES YES YES Pet-1 PR-1 QUARTERLY l-3903 D/G COOLING MATER .[ 3 22 A-10' No YES YES YES PR-1 PR-1 ouARTERLY ,. 1/2 NC s D/0 COOLiteG MATER 4 '3 22 A-ng NO YES YES YES '.PR-1 PR-3 QUARTERLY 1-5203 , D/GFUELDILTltAalSFER} 'NC 29 Y-)} NO PR-4 PR-4 YES , Pit-1 PR-1 QUARTERLY
- 1/2-5203) D/G Fuel. 011. TtAasSFER l' . NC 29 r-)# NO PR-4 PR-4 YES PR-1 PR-1 QUARTERLY
___- - - - .,_______________________ ____. ______- .. . _ _ - _ _ _ . . ..______. ________ _____ -___ ___ _ _ _ _ _ _ _ . I____________ l
. s i
i NOTES ., l.ubr t i .ation levels will be observed di iring each inservi ,:e test f or pumps that are designe. sucle th<,t levels can be
- ver t ile.l. TI .s core spray (1401). Iss4R ( 1002 ) . e nel - ' lie D/G fugl .31 1 t ra n
- . fer (520 l) pumps are lubri cated by snamp flodage end.
E lsea u , lubric.. ant level or pressure ameasuraman a asi not relevRai L. t
# t t A
n . 1; ; '4; .._= r TABLE 4.2.lb . LIST"OF SYSTEMS INCLUDED IN THE PUMP PROGRAM' FOR' UNIT-2
?t
. ..: . ~
. SYSTEM REFERENCE' SYSTEM' NUMBER P&ID Core Spray 1 1400 78 Residual Heat Removal 1000 79 & 81 Residual Heat Removal Service Water 1000 79 & 81 Standby Liquid Control 1100 83 High. Pressure Coolant Injection 2300 87 t
- ~ -
Diesel' Generator Cooling Water <,. 3900 - 69
.. . s
,;, . ; . ;.. ./,- ... r.r. e . .. , . > .~. . :.i . . w.
3 , ,. . .
- 1 Diesel Generator.Fust 011 Transfer 5200 29 I
. ~. . ..
5
- : w ~; ;. . .
. - ... ~ -
a
.1 m- , ~ , '( ~_
_"?y,
. .[., .. .
Revision 2 : 44
,m).
a P~ INSERVICE TESTING PROGRAM UNIT - 2 N ~' (diseR - ISO- CL ASS 6 2. & 3 ' PUMPS s . , _ __ '_1 _
'OUAD : CITIES NUCl. EAR POWER STATION l 8ET Q37__ g%g i
- 't itst ramassistas runst sunsata ruasP sanat . 2
;g
' ""8f itst
. cassemA3M . ,,,,, uti auf stein y,,,,,,,,, staama mitavat rats
. rats aAlt itaar 1
,o a ;,
=
I 24-1401 Cope SPRAY
'. 4
'2 la E-9
- 88 0 YES YES YES FA-1 PR-1 QUARTERLY 78 5-h 28-1401. CORK SPRAY 2 80 0 YES YES YES PR-1 PR-1 QUARTERLY
' ~
.2A-1002, RESIDUAL NEAT REMOVAL. 2 79 Il-( . 80 0 YES YES YES PR-1 73-1 QUARTERLY 23-8002- RESIpuAI.seEAT RENOVAL ; 2 79 too YES YES YES PR-1 i nt-1 E-(- QuAstTERLY 2C-1002A RESIDUAL EAT REMOVAL , .2 - 79 R-g 40 0 YES YES YES PR-1 PR-1 mf'tvERLY 2 D- 100,2 RESipuAL IIEAT REMOVA{. . */ 79 E-$ NO YES YES YES PR-1 'PR-1 wuAltTERI.Y l 2-1001-65A ltlla SERVICE WATER . . 3 St F-( No YES YES YES Pit-1 PR-1 QUARTEHLY
; 2-1001-658 .RIIM SEstVICE WATER 3 81 P-j. 80 0 YES YES YES PR-1 PR-1 QuAkTERI.Y 2-1001-65C ItalR SERVICE WATER , ) 81 r-1 too YES YES YES PR-1 PR-1 QUAR 7r.utY
'E 2-1001-65D Ittigt SERVICE WATER 88 P-[ No YES
'3 YES YES ,PR-l PR-1 QUARTERLY l 2A-Ilp2 ' STAasORY 8.10u80 CoseTROL 2 82 D 't NO PR-3 PR-3 YES PR-1 PR-1 QUARTEkt.Y
- 28-1102 STAaeoRY Ligulp CoefTitol. f2 82 E-f.' NO PR-3 FR-3 YES - PR-1 Pit-1 QUARTERI.Y
} 2-2302.. IIIGet PRES COOLANT IblJ . 2 67 A-j. YES YES YES YES 'PR-1 PR-1 QUARTEHLY 2-3903 u/G COOLING WATER 3 69 A-l(; No YES YES YES ~ PR-1 PR-1 QUARTERLY 2-5203 - p/G FUEL OIL TItAalSPER ., NC 29 88 0 PR-4 PR-4 YES PR-1 PR-1 QUARTERLY __-,-----~ IP-{
-- . ==. - . - - - - - - - - - - _ _ _
j . j . li 5 t .. i .' i l ) 300TE: Lubr ! . :a t ion levels w!!! be obseEved s or!ny each ineegv ice test for pumps that ar deelgnoit such ti at levaili can be E e t vertiled. Ti is core spray (1401), R:18 ( 1002 ) . and the D/G fuel oil trasi ster (52i 3) pumps are tuba lcated by pump it. vage and, , , thus, lubric. , sit lasvot or pressure measuremes e. s a s a not releve it . . I; ll ' l I ! I
.= e . N l
d
SECTION 4.3 RELIEF' REQUESTS; .POR INSERVICE P. UMP TESTING. PROGRAM J
+.
^
,., :,_ . . , . . . : t . . .: , . .- - f. .
,::::;. ..sn.. gg. < .., .. . .. .
. - , ~ : ,, y y, , , . .. s.,. .
~
b
^
l. E Revision 2 .4-5 I l
-y a- *e v w y e - ww P +-+__- s. -'--v' * --,y--w-- y-
.--..:..-.t REIIIEFREQUEST NO. PR-1 PUMP NUMBER: .All pumps.in. program .
SECTION X1 ~ REQUIREMENT: IWP-1500, Detection.of Change.
.:. ..r. m .... . . . i BASIS FOR RELIEFi Pump vibration and bearing temperature are required to be measured to detect any changes in the mechanical characteristics of a pump. This is to detect developing problems so repairs can be initiated prior to a pump becoming inoperable (i.e. unable to perform its function). The ASME Code minimum standards require measurement of the vibration amplitude displacement in mils (thousands of an inch) every three months and
. : . e m w . a .>.i. w .e.. . g . :c:. : at ,p : . ; . .:...
.. .., i .. -w au. . ,,
bearing temperatures. once per year.. - , Quad Cities Station proposes an alternate program which r . .- ;' ...is' believed totJ eimore b comprehensive than that-required .
' .b.y S.ect. .io,.n.
,XI.. ... .T.h. .is.. .progra.m..c,onsists of perform.
- g. ; ing the q.
~ "
required vibratien readings in velocity rather than mils displacement. This technique is an industry-accepted method which is much more meaningful and sensitive to small changes that are indicative of developing
. mechanical problems. These velocity measurements detect not only high amplitude vibrations that indicate a major mechanical problem but also the equally harmful low
~.
Revision.2 4-6 1
RELIEF REQUEST NO. PR-1 (CONTINUED) amplitude .- high. frequ'ency vibrations due to misalign-ment, imbalance, or bearing wear that usually go undetected by simple displacement measurements. In addition, these readings go f ar beyond the
. capabilities of a bearing temperature monitoring program, which requires a bearing to be seriously degraded prior to the detection of increased heat at the bearing housing. The vibration velocity readings on a
- schedule of once every three months achieves a much higher probability of detecting developing problems than the once per year reading of bearing temperatures. Data
..,- . a.:1. . . .; >p . i. :s. ;c. . .: . ,. . , .
;n: sc. .+, .. .:
,. . y:. . . . . . . .
gathering,.on bearing temperatures,also is not without its own problems. The enforced thirty minute run time, (i.e. IWP-3500 (b)1- three. successive readings taken at ten mi'nute intervals.that do not.. vary more than 3%),
~- -
.- :.(..; ycauses,. problems;.with, pump,s .,having. no rec i
rcul,aei on,/ test, loop.- It is easy to see that a program of bearing temperature trends and the evaluation of the results would in some cases be difficult to analyze. Improper interpretation of results could result in unnecessary pump maintenance. In addition, it is impractical to
. ,, . C
. u. . .. .
Revision'2- 4-7
RELIEF REQUEST NO. PR-1.(CONTINUED) measure. bearing temperatures on many of the pumps in.the
. program. Some specific examples.are as follows:
,' (1) - ' Core ' Spray 1(2)A,B-1401 -a pumpebearings*are-lubricated by pump flowage. Temperature of the pumped liquid would seriously affect the accuracy of trends.
(2) RER 1(2)A,B,C,D-1002 - same as above.
-e (3) RER SERVICE WATER 1(2)1001-65A.B,C,D - Bearings i
are contained in an. oil-filled reservoir. The
.. . m. .. .p. . .w s.,..;,.;
. . ;a y.m.y e x_;,,e
. . , .. . .x- . . ' . . , . .. , .
ambient temperature of the pump sp' ace is
-changeable thereby varying the start temperature of the. data. Results would be difficult if not s , ,
I' + impossible ~to trend.from test to test.
....4
- - .. y,. -
-(4)- High Pressure Coolant Injection - this pump is driven by a steam turbine which exhausts steam into the pressure suppression chamber. Extended L
I~ run times to stabilize bearing temperatures would create problems in keeping suppression pool temperatures below 'the Technical Specification limit of 95*F. ,- Revision 2 4 i l'
- e -t-- w e w w ww ~v r v-- ,,,w w ---t-r,--e--ew g wr-y e ,,-.,t--, -e--+ww--ev-w--+g--*- -w w.w w '~
- .. . ..~_._.m.... ._ .... . . . ---y . - _ .
RCLIEE REQUEST NO. PR-1 (CONTINUED)
,. ' -, (5)' Diesel Generator Cooliiig Water- 1( 2 ) ( 1/.2.)-3903 -
. Same as RER Service Water .
~
~
LDfe'ser Generatior ' Fuel' '011' Transfer 1( 2)f1/2T-520 3' ( 6.)'-
- this transfer pump pumps fuel oil from the fuel oil storage tank to the D/G fuel oil day tank.
There is no recirculation test loop for these pumps, thereby, limiting the run necessary to
-gather bearing temperature data.
e , The foregoing reasons demonstrate that the proposed
.. _. program of vibration .:measurements is a more practical
. .c - . j . g .r -.. . cgr. . y ,,. , ...: g n
.,. .s. .
7 . .3 .. method of ~et' sting- which exceeds the requirements of the ASME Code.
.~ . .
v.;. . . . ALTERNATE TESTINGi Pump vibration measurements will be taken in
. .. ,., , , . ..yibration. v.eloci,ty ..( in/sec ) . [ . The .ev.aluat; ion :o f the Leeadings will be per the attached table.
^
..:. . .. ,. ,, . ya . ,
^
e l.-
. Revision 2 4_9 D
e -*r M-*
'*s-e =- ,--wv .,---ve-v - , e -w-- -v - se+ -
+-r-m'-.n e -w--,eiy wwwv-.-vv-- w y- gew < w'e ----*-y--*-*.-y 'eg, -v- a
o- . . . g MJNABW RANdES OF VIBRATION VEEDCIW1' , 4 , p . , ,. AIERP RANGE REQUIRIE ACTIOi RANGE r -
- - IN llIGl :IN '
HIGl 8 p a rrI W :r ACCEPTABIE RANGE . VMUt3 - VMDES .VMDES : VMUES w ,
.g v Mien 0 < v,. < .15 irVsec
~
0'.to.3-in/ hec. None- .3 in/see to ,None v ),.45 in/sec iv k n .15 in/sec < v,.q.' . d to. 45 in/pec Hone .45 in/sec to None v > .75 in/sec
< .3 in/sec -
' ,, . .75 in/sec ,
; . ' g* .
,.v. Mien .3 in/sec < v,. -
O to 0.9 in/pec- Nane 0.9 to 1.5 ;None v > 1.5 in/sec
< .6 in/sec. . - .
g in/sec v hn.6in/sec<v,.]' 0 to 1.1 ishgiec None 1.1 to 1.5 lbne v > 1.5 in/sec
< l.0 in/sec .'
5 y-in/sec -
- i ,
j h re
..* } -
o
- l.
v = velocity measured in inches /second, peak.; v r = reference velocity medpurement (initial apasurement af ter installatioi or rework.
,. .4 4 * ;
3 f S { 4' e l b See ASNB 'llechnical Paper 71HfA/NPc5j Table 2. - ; ir c
- 1 l
l3, , F l l
REI;IEF" REQUEST NO. PR-2
' PUMP NUMBER: .All. pumps.in program.
~
SECTION XI. REQUIREMENT: The requirements.of IWP-3230(c). corrective' action. - . BASIS FOR RELIEF: Relief is requested from the requirements of establishing a new set of reference values following an analysis of a deviation which falls into the " Required Action Range." It is felt that using the original values as a reference will alert the testers to future
. degradation of the pump more quickly than using a new set'of reference values. Pumps which fall into the
--, . . . , r. - - c... ..; .: v. . : m. .; ., y.: n. . : ,. ,y . , < . . ., v. ;;. m.
. . _. . . e ... ,. ...
.l
" Required Action Range"-will be analyzed and will remain ,
l I , operative as long as pump operability is not impaired
,and pump performance meets Technical Specifica. tion i -
limits. Maintenance will be performed at the first
. .., .. .opportupity tp. 7,ectify the deviation.. .
ALTERNATE TESTING: Pump testing will be doubled (i.e., every 45 days) during the interim period. and a new set of reference values will be established following the correction of the deviation. Testing will then return to the original frequency (i.e. , every
- 92 days).
l Revision 2 4-11 t
f RECIEF' REQUEST No. PR-3 PUMP NUMBER: 1( 2)-1101 (SBLC) SECTION.XI~ REQUIREMENT: Measure pump inlet pressure
- p. BASIS FOR RELIEFi It is impractical to measure standby liquid control pump inlet pressure in accordance with Section XI requirements. During pump testing, the pump suction is from a test tank rather than the main standby liquid control tank. No instrumentation is provided for measuring inlet pressure, and therefore, the only means available is to correlate tank level to inlet pressure. Since these pumps are positive displacement
- . . ;. .,,.,is.: g.: .n.s ._m . y , .. . :p . ..:....s~ w 4 4. ...:.k. ;.:,:.a. .,. .= .
designs. . the measurement of inlet pressure is not . l critical in judging pump performance. Measuring the
; .. ... .,. disc,harge pressure.and.the _ , ; , flow rate is,ad. equate to detect changes in the hydraulic characteristics of the i.
. . . (. . pumps. ,; , , , , , , , , , , ;,, , .,
; j t
ALTERNATE TESTINGi Pump discharge pressure will be monitored at each inservice test. r
- . i
,. , ,u.
. ..s Revision 2 4-12 r w g -M -yow,e +9 e-$w e-w- -sw--- Mv-e. ---w-. 4 "we-
+ 4 -- v - e wwwg >y,w- --*ww-- 4 -----
RELIEF REQUES'2 NO. PR-4
. PUMP NUMBER: . r1-5203, 2 -5203, 1/2-520.3 I SECTION XI REQUIREMENT: Measure Pump-Inlet Pressure I- - BASIS FOR RELIEF: Relief is requested from the requirement of l
measuring pump inlet pressure during pump tests. This pump is utilized in transfering fuel oil from the diesel generator fuel oil storage tank to the diesel fuel oil day tank. The configuration of the piping is such that the pump is located'above the storage tank. The pump is a positive displacement gear type pump not requiring.a
. positive suction head for proper operation. Since this
.a:, : vo w. . ..
. . v. , y:;.;.,..;r. ., .g.;; . ,e. ;. q. , , , . , . . ., ,, . .
pump is a'ositive p displacement type, the discharge pressure is independent of the suction pressure and,
.therefore,- ini.et. pressure; data..is not important in
.z. . , ....a..
evaluating pump. sierformance.
,...G. -,: .p ~ . .; .p . . : . . ~ .. . . ,
ALTERNATE. TESTING: ' Pump discharge pressure will'be monitored at i each-inservice test.
.: : . r; Revision 2 4-13 w =-e.e.. . .e-.i-.m. . . ,., - , _ ., ,
e- - 5.0 INSERVICE. TESTING PROGRAM FOR VALVES ~
'5.~1.c GENERAL ~. -INFORMATION The Inservice-Testing Program for ISI C1Ikss 1, 2 and 3
'Vitives meets the requirements of Subsection IW'of l Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda. Where these, requirements are determined to be impractical, specific requests for re'.ief have been written and included in Section 5.3.
The tables in Section 5.2 list all ISI Class 1, 2 and 3 valves that.have been assigned valve categories; valves u e-s . . , _ , . . - ...~.. u ... m .,,;,. , (._ .... . :. ; ,.. . , . .. . exempt per.IWV-1200 are'not listed. The tables are organized by system in order of the assigned system
. - number...A. list of.these' systems and their respective
- PEID numbers. is given in Table 5.2-1. The following
..,,,,,information,is include.d in,the tablesp
~
.l t
A. Valve Number' lists the valve identification number as shown on the class code flagging P& ids. The first digit of the valve number indicates the appropriate unit.
.. . ~. .
.r. .,....,.,:
i Revision 2 5-1
~
Y B. P&ID and Coordinates references the class code flagged PEIDs on which the valve appears and its
. . . . coordinates.. .
C .- ' Class is.the ISI Classification of the vtive. i - Valves in nthe diesel fuel oil and air start I systems as well as some primary containment isolation valves are included in the program, even though they do not have an ISI Classification. These valves are designated as Class NC (Not Classified). , D. Valve 'Categorp indicates the category assigned to the valve based on the definitions of IWV-2200.
.y .. y ..c. .. .. v , u,
. ....,>.-1..:, q . n.; r.. .n. . . . . .. . . .
..: .- .. }
Note that the Category E valves, valves which are normally locked (or sealed) open or locked (or sealed) closed to fulfill their.. function, are not
- ?
within the scope of Subsection IWV.- They are
, . ted in....he . T. ables.for .c information only.
t
. : ... . . . y,. .
~ . . l.. .is
~.... . . . . . , -
s> E. Valve ' Size lists the nominal pipe size of .the valve in inches. F. Val've' Type lists the valve design as indicated by the following abbreviations.
. . , ,.. , . . ~ ' ,
+
Rev'ision 2 5-2
- a. .;. :: ..-. -
GATr GA GLOBE GL CHECK'. . . .. CK . SAFETY. SV RELIEF RV
~
' ELECTROMATIC RELIEF' ERV BUTTERFLY BTF STOP CHECK SCK BALL BALL RPD RUPTURE DIAPERAM EXCESS FLOW CHECK XFC G. Actuato'r Tyne lists the type of valve actuator as indicated by the following abbreviations.
..2 < ,. , %
. . / ,v, ./.; cum : . .
.v . : ...
-t p. 2 . . ,, s., -..,.. . . . , .. ,,; j. , , , . .. . . .. ..
MOTOR OPERATOR MO
. . , ,. A.1;R OPERATOR. AO 3 . . ,
SOLENOID OPERATOR- SO
..,- .. ,. . y PILO.T
- . SOLENOID., ACTUATOR..
-PS . ... ;
EXPLOSIVE ACTUATOR EXP
- - SELF ACTUATED SA MANUAL M H. Normal Positic'n indicates the normal position of the valve during plant operation. This is
;, . _ .. g .,
Revision 2 5-3
-~ --,-_r
specified as open (O), closed (C), locked open (LO), and locked closed (LC) . P I. Stroke Direction indicates the direction which an active valve must stroke -to perform. its safety function.- Also, the direction in which the valve. will be stroked to satisfy the exercising requirements of IWV-3410 or IWV-3520. This may be specified as open (O), closed (C), or both (O&C). J. Test lists the test or tests that will be performed for each valve to fulfill the requirements of Subsection IWV. The following tests and abbreviations are used:
. . ,. . .u < .: s., ., ; . ~. . . , , 7 s ..; .
. . .. >. .- q; . . y _.., ..p...,.,
Seat Leak Test (IWV-3420)
- a. .T.ype C Air Leak Test.- Primary con,tain-AT-1 . . .
ment isolation valves. The acceptance
.; - - p, ,
criter.ia for
,, ..~. . ..
this.. test. is defined
. .; . . in .
.l l
Relief Request' VR- 10 Note that 10CFR50 l Appendix J, Type A & B tests are not l included in this program even though these tests will be conducted.
. y '; .
( Revision 2 5-4 amp
- K_
- b. Excess Flow Check Valve- Test - Excess AT-2 flow check valves will be testad in accordance with the Technical Specifi-i cations requirements. For further information see Relief Request VR-9.
Full Stroke Exercise Test (IWV-3411, BT . 3412, 3413) Valve will be full stroke exercised for operability in the direction necessary to fulfill its safety function. , Partial Exercise Test (IWV-3412(a)) BTP Valve will be part-stroke exercised when 4 ..ya, ,9 ; .,.. a., .w ; .y .. . .,- q .. ,. .. . . ,
.c . . , , . . , . ,
full. stroke exercising Eiir . impractical.
.'.. i .1... . . , , . . '
+= check valve Exercise Test (IWV-3520) CT-1 Check valve will be exercised fully open,
...q.....
closed
-,- o,r .. .
both.. depen.,
. , . , . ding
. . . . . on ,the safety
' function of the valve. Verification of acceptable system flow through a valve shall be adequate demonstration of valve operability.
* * "., e .# ~ , , , , . * . * * ,
...' * . .. , ,{
Revis' ion . 2. 5-5
- > * * - eem guem - e
Relief Valve Set Point Check (IW-3510 ) CT-2 Relief.and safety valve set points will be
. . ., . . . verified' in accordance. with. IW-3510. , ,,
Explosive Valve Tests (IW-3610 ) DT
- 3 . - -Explosive-valves will- be . tested 11n , .
accordance with IW-3610. Fail-Safe Test (IW-3415 ) FST All valves with fail-safe actuators will be tested to verify proper fail-safe operation upon loss of actuator power. , Position Indication Check (IW-3300) PIT
.~.n._,
- e. .#2 ,u, .; ..: ,. e. . . ;. n j . . . , ,. . .., . .g ..4.;,.,,..;,,,,,....,...._.,. . . , . , ,,, ,
. All valves with remote ' position indicators' ' ',
will be checked to verify that remote valve indications accurately reflect valve 1
, ..y- -
. operation.' ,- ,,
. . . . . . r. [ '. ,- n . . .,. , . , ,...e v, ..,7 .....,. ,
'K. Test Mode indicates the frequency at which the above mentioned tests will be performed. The following abbreviations are used:
Normal Operation OP Tests which are conducted at least once every 3 months during normal plant operation. Revision 2' 5-6 1
Cold Shutdown CS ; Inservice valve testing at cold shutdown is valve. testing.which. commences within two - ~ hours after the plant reaches a cold shutdown
- condition but in no case later than 48 hours t after cold shutdown is> reached. This testing continues until all valves are tested or the unit is ready for start-up. Completion of all testing is not a prerequisite to plant start-up. Valve testing which is not completed during a cold shutdown shall be completed during subsequent cold shutdowns that may occur before refueling to meet the code specified testing frequency. In the 9 . p. - - -
- -h:.-;a , ; , a;,,..,..q..,..:...n.,
case..of frequent cold shutdowns, ' valve testing need not be performed more often than
- ,once.every three, months for Category A, B,
and C valves.- ,
. .e ::
, ,. ': . , . . . .r . . . - ... . .
. ,;. . .< .. .i.. ,
,g In the case df longer planned cold shutdowns, the testing need not be started within the 48 hour limitation. However, in these instances, all valve testing must be completed prior to start-up.
Note: It is expected that the required. t'esting will'normaliy be completed in 96 Revision 2 37
-e- - ----,--.---___m,,.,, _ , , _ , , . , , , _ . , . _. _ _ _
l hours following cold shutdown. However, completion of all valve testing during cold
- shutdown is.not. required if plant oper.ating conditions will not permit the. testing of specific valves..
. s In the event that a valve must be declared
, inoperable as a result of coJd shutdown testing, the applicable unit start-up limitations will be as stated in the Tech-nical Specification, Limiting Conditions for Operation. Re~ actor Refueling RR 2 , - i . .: , . . , , . y t. :c
. . t..v, . . , , . , .,, c .p .. p ...... . , .,, ,.
..e.. .
3 ,
. Tests which are , conducted during plant ,
refueling outages but not less than once .
. . . ev.erf two; years.. , .
,, a.
Evsry' 5 Yeses , 5Y !. ,:;, .. v .
. y. , . . . -
, ,, , ,,3 s.....,,
, g .;, :.. .,;.,
Tests which are' conducted'during plant refueling outages but not less than once
^
! every five years (See Article IWV-3511). Max"$tWoks' Time lists the maximum allowable full
~
L. stroke time in seconds for power operated valves in Category A or B.
?. *. .. . '. ., . : t. ...,,.> ..
J . ,, ... . . . Revision 2 5-8
M. Relief' Request references either a. specific request contained in Section 5.3 or references a Cold
. ,,. Shu.tdown Justification contained in Secti.on 5.4. ,
, Also, included in Section 5.3 are generic relief requests-that [tre not specifically referenced in 4
~ this column of the tables, . but apply to the- valve - ,
program in general. N. Remarks lists clarification remarks or indicates that a valve receives an automatic isolation signal. See Table 5.1-1 for the explanation of isolation valve groupings.
., , . ~ . . .. .e ....p. , , , . ,,,, ;,. gg. g. ..x e. ,.m . ,, .. .p i , ;., ;. . . ,. : . ;. .j .,
, # 4 e e., "
- O d
S' . ,
- r ; ,e . . i, , . a , . ;. '
, ,4... .
9 I
~' . .
.w. .
. t ., ..
s: Revision 2 5-9
TABLE 5.1-1
, , AUTOMATJC ISOLATION VALVE GROUPINGS _
Group is The valves 'i n Group.1 are closed upon any one of the following; condi,tionst
- 1. heactor low-low water level
- 2. Main steamline high radiation
- 3. Main steamline high flow
- 4. Main steamline tunnel high temperature
- 5. Main steamline low pressure Group 2: The actions in Group 2 are initiated by any one of the following conditions: ,
- 1. Reactor low water level
- 2. High drywell pressure Group 3: Reactor low water level alone initiates the following:
. . . ....l..p.e. Cleanup,.,demineralizer...sy, stent, isolation . ., ., ,
Group 4: Isolation valves l in the high pressure coolant injection system (HPCI) are closed upon any one of the
'following: s'ignals :
' ' ~
- 1. HPCI steamline high flow
- 2. .High temperature in the vicinity of,the HPCI steamline
- .c . .'.<3 .
~
. Low. reactor. preesure . .
- - 's. --.-
Group 5: Same as Group 4 except applies to RCIC.
,. . .. .., f Revision 2 5-10
SECTION 5.2 TABLES FOR INSERVICE VALVE TESTING PROGRAM A. QUAD CITIES UNIT-1
- 8. QUAD CITIES UNIT-2
;,.., .,: . w.i :. - . . ,; :. . . :.; . . . . . u . r.; . . u: sg. ,. . . . ..
. s... .e ..:,.
. ...t. .
... .e
... c. ,
.. ~
Revision 2 5-11
. . . 4 ~ ~ . . - 9 l .
~^~ .:.=. -. . . = ^ ..;._ - .
TABLE 5.2-1 J ..
- ~
LIST OF SYSTEMS INCLUDED IN THE VALVE PROGRAM UNIT-1 UNIT-2 SYSTEM REFERENCE REFERENCE SYSTEM NUMBER P&ID P&ID E Nuclear Boiler 0200 35-1 77-1 Recirculation 0200 35-2 77-2
,- Control Rod Drive 0300 41 83 Residual Heat Removal 1000 37&39 79&81 Standby Liquid Control 1100 40 2
.,,,g , , , , 120 0. ., , , . , , ,47 ,, 88
. . 7.y. . React.or .. Water. Cleanup
- g. , , , , ,
Reactor Core I'so$ation Cooling 1300 50 89 Core Spray 1400 36 78
' Pressure. Suppression ' . .
1600 3 4.- 76 46 87 High Pressure Coolant Injection '2300
..< . Main. Steam.:3 * , ."< ?
19 ': -
.. 300.. 0 3 13-161- .
'.6 0.- 1 6 2.. , ,
Feedwater 3200 15 62 3900 22 69 Service Water Instrument Air 4700 24-2 71-2 4600 25 72 Diesel Air Start Rx Sullding Equipment Drains 4800 43 85 5200 29 29 Diesel Fuel Oil
-~'-
~* , . : .r . . .,
Revision 2 5-12
t . INSERVICE TEhTING r-.hk PROGRAM EdneR ISI- CL ASS I. 2. 1 3 VALVES . UNIT. .- 1 OUAD CITIES NUCLEAR POWER STAT'lON Sv5fEtt P S as atWIStest - BAlf PAGE . ISUCI. EAR SGII.ER IllSTRUNDITATION M .35 sh, 1 2 9/17/84 1 or 36
/ r y/ jhqq s l} q -
AT-2 RR 1-263-1-15A D-5 1* AC 0.5 XFC SA O C CT-l' RR VR-9
...._.. . -- - .. _ . _ . -_-- .. .. _ a ..... ._. .
AT-2. SR i .
- 1-263-2-13A D-5 1 AC 0.5 XFC SA O C CT-1 RR VR-9 AT-2 RR 1-263-2-19A C-5 1 AC O.5 XFC SA O C CT-1' RR i _ .
VR-9 . __ . __ . . . - - =--- _ _- _-_- _.- _ _=.
. AT BR 1-263-2-17A D 1 AC 0.5 XFC SA O C CT-1. RR VR-9 AT-2, SR 1 1-263-2-11 E-5 1 AC 0.5 XFC SA O C CT-1'. RR VR-9 AT-2 RR l-220-54 .'t- 5. 6 1 AC 0.5 XFC sA O c CT-1'~ F RR VR-9 l
AT-2 RR 4 1-263-2-158 D-3 1 AC 0.5 XFC SA O C CT-1 RR VR-9 t _ AT-2 RR - 1-263 2-13R D-3 1 . AC 0.5 XFC SA O C CT-1. _R R VR-9
._-. _. .. ......==. - ==
AT-2' RR 1-263-2-17a D-3 1 AC 0.5 XFC SA O C CT RR VR-9
-_____ .-...... ... __. .__ __ . . . . _ - ......; . . . . . __ . . . ____ - -- _ _=_.._
1-263-2-19a AT-2. DR C-3 1 AC 0.5 XFC SA O C CT-1 RR , VR-9
-- _ - - _ - _ _ . . . . _ . . ......=---
-=
. AT-2J RR
- l-263-2-20A s-5 1 AC 0.5 XFC SA O C CT-1 RR
__ . _ _ _ _ .u..... ..... ...... ,...... VR-9 - _== .. ..._ ..._.. ..... 4 _... . . AT-2, RR . 1 263-2-23A C-5 1 AC 0.5 XFC SA O C CF- 1 ' RR VR-9 AT-2 RR _-.4.- 1-263-2-3th C-5 1 AC 0.5 XFC SA O .C CT-1 RR VR-9 O
- I p
r_ --m ~ INSERVICE TESTING PROGRAM UNIT - 1 Edis.R isi - cL ASS 1.2.13 VALVES, OUAD clilES NUCLEAR POWER S T ATION I T51tas P & la alusse - aAIE PAGE NUCI. EAR SOII.ER INSTRUMENTATION (cONTlHUED H.3$ gh, { 2 9117/84 2 of.36 l
/ s y/ /hqq > l} q AT-2 BR t-263-2 310 c-5 1 Ac O.5 XFc sn O c cT-1 RR VR-9
- ... . - =. ....__. - - _ - __ . _ = _ - _ _ . _ _ _ - - _..
AT-2 RR l-263-2-3tc c-5 1 AC O.5 XFc SA O c CT RR VR-9
= -
-.= __
- - . ____.- - _ _ . . . _ = = - .___ .. ......: _ . . . . . . . . . _ .. _--., .......
AT-2 RR . 1-263-2 3tti C-5 1 AC O.5 XFC SA O c CT-1 RR VR-9 _. ._. =_ ._ - -.. - AT-2 RR l-263-2-31D c-5 1 AC 0.5 XFc SA O C CT-1 RR VR-9
= -
_. .- .:_ . _ . - - - _ . _ . . - -=_- --.._ . . .... ....... . . . = - . .... .. AT-2 RR - I-263-2-27 A-5 1 Ac O.5 XFC SA O C CT-1 RR VR-9 _ -=- _ == AT-2 RR t-263-2-25 5-5 l AC 0.5 XFC SA O C CT-1, 'RR VR-9 ,
= _ ...-_.- ----= . __- --
AT-2 BR t-263-2-31J C-5 1 Ac O.5 XFC SA O d CT-1 RR va-9
- L...__ =- _.- . __ _ _ _ = _ . ... _ . . _- _ _ _ _ . . -
AT-2 RR I.263-2-31E c-5 I Ac 0.5 XFC SA O c CT-1' RR VR-9
- - .... - . _ . . = = _ _ _- _ __ - _
, AT-2 RR 1-263-2-3tK C.5 1 Ac O.5 XFC SA O c CT-1 RR VR-9
_ _ _ . . . .=_ .=--- _ . ._. . _ . - -_-_... ._ _ = --- t-263-2-235 c-5 1 ; Ac 0.5 XFC SA O C CT-1 BR VR-9
.=- _ - --
=_ _- _. == _.
AT-2'. RR
, 1-263-42A c-5 1 ~ Ac 0.5 XFC SA O .C CT-1 RR VR-9
___- _ - _ = - AT-2 BR 1-263-2-20s a-5 1 Ac 0.5 EFc SA O c CT-1" RR VR-9
.__ = ... - ........ ....... ........ . - - - ._ . . _ .. _
...___ _ _-- = :
AT-2 RR l-243-2-20c a-3 1 Ac O.5 xre SA O c c
..t___1 ..R R.....
........ .v.R-9 ........ _
_ .. _..- -~_... .. ... _.
- - - - - - - ~w.-.
- s. .
( ') r-m INSERVICE TESTING PRTEGRAM l ( ~? 7 I&see ISI- CL ASS 1. 2. & 3 VALVES UNIT ' 1 j
't./ -
QUAD CITIES NUCLEAR POWER S T ATION ' 800C1.RAR 90!!.ER INSTRUMEttTATION IU2878NUED) M-35 sh. 1 .2 9/17/84 3 of 36 () I,. 1 --
/ r y / / h y g s q -
t-263-2-23c AT-2 RR c-3 Ac o.5 Mrc SA o
-- , == -
C CT-1 3R - vR-9 AT-2. RR i 1-263-2-3tM ,c-3 : Ac o.5 Mrc SA o e cT-t RR va-9 1-263-2-3t? c-3 AT-2 an 1 AC o.5 XW: SA o e CT-1 RR VR-9 _ _ _ = -- t-263-2-3tM c-3
- AT-2 RR 1 AC o.5 Erc SA o C cT-1 na VR-9 t-263-2-3 u AT-2 BR c-3 Ac o.5 ure sA o e cT mR VR- 9
. . . . . _ _ _ _ . __.-_ _ _ _ = _
.' AT-2 at i 1-263-2-3te c-3 1 Ac o.5 xre sa o c cT-t RR vR- 9
==- _....
t 263 _a-3 : Ac xre AT-2. BR .; . _ .___- -- n o.5 sA o c cT-1 . mR vR 9 I t-263-2-3tv AT mR c-3 1 Ac o.5 xre sA o d RR vR- 9
. - _ _ _ .- - ___ .____.- - .=- .== cT-1 l l
i 1-263-2-3RR c-3 1 Ac o.5 AT mA ,- Erc SA o C CT-1 ER 1 VR- 9 i _. t-263-2-3tw AT-2 mR i c-3 1 Ac o.5 xre sA o e cr-1 mR vR- 9
.- - - - -___ - -. - . . . . . . . . _ . - =- . -._
t AT-2' 3R t-263-2-23n c-3 Ac o.5 rre sA o e cT-3 mR va- 9 , i _- + __ i 1-263-2-42R c-3 : Ac are AT-2 mR o.5 sa o c. cT-1 ' mR ,, vR- 9 _ _= _ _ 1-263-2-200 3-3 : Ac AT-2 at o.5 tre sA o e cT-1 ma - _ya ,3,__ 4 T
,n
- f. t-.a.s INSERVICE TOTING PROGsAM (N}J[dnen L/
ISI- CL ASS 1. 2. A 3 VALVES QUAD CITIES NUCLEAR POWER STATION UNIT - 1 sv5asse P 5 se navessou . sait ras!
^
REClucutRTioes M-35. Sh. 2 2 9/17/84 4 of 36 i r
/ i y/ /hqq -
> l} q -
BT CS 45 1-202-5A I>-6 1 3 28 CA MO O C PIT RR J-3,VR l '
=. _ . - - - . . . . - -
BT Cs 45 1-262-5a D-3 1 a 28 'GA MO O C PIT BR J-3,VRl: AT , BR - 1-22b44 .E-2 1 A 0.75 Ao o UU NP 1 ISMTIN ct. c yy, , , FST or . _- _=__ 1-220-45 E-1 AT. BR - A 0.75 CL 1 Ao O or
- .c RT 5 VR13 Opour 1 ISotATion rST oe l-220-67A .F-5 AT-2 BR 1 AC 0.5 XFC SA O C CT-1, F.R VR-9
--_.a-1-220-673 F.5 AT-2. BR '
1 - AC 0.5 XFC SA O C CT-1 RR VR-9 _ = _ . . ..._ ... c _ _ _ . 1-220-67C AT-2 BR - E.F-5 1 - AC 0.5 XFC SA O C CT-1 SR - VR-9
- 1-220-67D AT-2 . BR F-5 1 AC 0.5 WFC SA O 'C- CT- 1,,
RR VR-9 1-220-89A AT-2 RR E-1 1
- AC 0.5 XFC SA O C BR CT- 1. . -
VR-9 __ _ --__L-= 1-220-89n E-1 AT-2 BR 1 AC O.5 XFC SA O C CT-t, SR VR-9 t-220-67E AT-2 RR r E-5 l AC 0.5 XFC SA O C CT-I ,' RR V R-9
'= __
l-220-67F AT-2 RR l'-5 1 AC 0.5 XFC SA O C __ __ - ..=- CT-I RR , VR-9 l
\ .' -
[ . Q Ir - rm INSERVICE TfDTING PROGNAM UNIT . 1
- [h ISS - CL ASS 1. 2. A 3 VALVES .
] QUAD CITIE S NUCLEAR POWER STATION i sussias - - P 6 es arvessen - satt tast BECIRCULATIOtl (COttTitIUEnl ^ H-35 sh. 2 2 9/17/84 5 of 36
/ r y / i h e y > l ;$ q -
1-220-67c t-5 AT-2 RR 1 AC O.5 XFC SA O C CT-1 RR ,- VR-9 1-220-6784 F-5 AT-2 RR 1 AC 0.5 XFC SA O .C CT-1 RR ~" VR-9 AT-2. BR 1-263-2-6A B 1 AC 0.5 XFC SA O C CT BR VR-9
. . _ _- - ~
_...s --- 1-263-2-5A AT BR 3-7 1 AC O.5 XFC SA O C CT- 1 '.. SR VR-9 '
-_ .. _.=
_== __ 1-220-20A AT-2 RR - a-5 1 AC 0.5 XFC SA O C CT-1 RR - VR-9 _ .... . . _ _ _ . . ... aa . . -- _ 1-220-19A AT-2 RR - B-6 1 AC 0.5 XFC SA O C CT-1f SR , VR-9
. . . ... ... .=---
s _ ._ 1-220-22A D-S AT-2 RR , 1 g AC 0.5 XFC SA O C CT-1
~
RR VR-9 __.. . _. _. -.... .. =_ 1-220-2th D-S AT-2 RR. 1 - AC 0.5 XFC SA O C CT-1 RR VR-9 1-220-20e AT RR A-3 1 AC 0.5 XFC SA O C CT-1 RR. VR-9 1-220-19e AT-2 RR A- AC 1 0.5 XFC sA O e CT-1 RR ,, vR-9 1 262-2-68 B-2
- AT-2 RR .
1 AC 0.5 XFC SA O C CT-1 RR _ ... -==. , VR-9
==. - ; -
___= AT-2 BR l-262-2-5R m-2 1 AC 0.5 MFC SA O C CT-1
=- ***
RR VR-9 l-220-228 D-1 AT-2 RR 1 AC 0.5 EFC SA O C CT-1 RR .. VR-9 '
.a..
____ . _ = - _... . ... .. . . . . . . . . - - - - -
- - s.
(D c .i,6 INSERVICE ISI- CL A SS TENTING
- 1. 2. A 3 VALVES PROGRAM UNIT 1
Q J E6s.n . v OUAD CITIE S NUCLEAR POWER STATION -
- SYSHA8 P & IG MVISION - 94ft
+
Fast
,, REcIncut.ATIoss -(CONTINUED) *H-35 *Sh.2 2 9/17/84 6 of 36 2 /
l F
/ s yijh4q, // q -
- 1 i
/ /
AT-2 RR' -
- t-220-21B D-1 1 AC 0.5 XFC SA O C CT-1 -RR VR-9 1
. s i e E
O l 't i 1 . !l , i . I
~
l 1 I
- s i
a j .. I - l 1 t-1
r- s c . Cesa INSERVICE TESTING PROGRAM - - UNIT '.
@ us.menwealthOUAD CITIES NUCLEAR POWER S T ATION 1 I
. ISt - CL ASS 1 2.A 3 VALVES ,
sysitM - P 618 hivismes - BAlt FAF( , CONTitOt. ROD DRIVE M ah. 1 2 9/17/84 7 of 36 ) f $ $ an us . s ( t (177) t.0305-127 u -9 1 B 0.75 GA AO C O BT *
..= __-..... . . . . . . . == . ..... . - - - -=. _-
VR-6
- SCRAM TESTING (177) ..
1 0305-126 p-10 , , . 1 a 1.0 CA Ao C O OT
- f
........ . - - = _ - -- -___ ... ..-. =
VR-6
- SCRAM TEST 1NG
....-... .....-. ........ ... ... -- .. . . . .= - - - -
_ . . . . = - _ - f' (177) 1-0305-114 E-9 2 C 0.75 CK SA C O. CT-1 *
. . . . . _ - .--- . . . . . . . , ==.... ....... --_- _
VR-6
- SCRAM TESTING
... ...... .....--......aa.-----...
OT Cs VR13 1-u302-21A ' F- 6 2 a 1.0 CA A0 0 C rs?. Cs '30 . t-0302 ' F- 6 2 a 1.0 CA Ao c 30 VR13
-- -..-2tn -.. --. -
O sf
'C
__ ,- ==-___= t-0302-22 A .F- 5 2 a CA 30 VR13
'2 . 0 A0 O c sf ,C
--.... ....... ....--. ....... a...... . . . . . - . ....--, . . . . . . . . .-------.
RT ' i-0302-21C F-1 2' B 1.0 CA AO O C psy. CS 30 VR13 ,
.....--..... ....... . . . . . . . ...... ....... ....... ....... ....--. ...... ..-... ....u.. . . . . . . . . ......... ........ ........--...
RT . 1-0302-21D F-1 2 B 1.0 CA A0 0 C FST .- CS 30 VR13 BT 1-0302-22B F-5 2 ' B 2.0 CA A0 0 C FST, CS 30 VR13
............ ..... . ...-- ~...... ....... ....... ....... ....... ....... .--..'. .-- ... ....... ......--- ............ - .......
BT-1-0302-22C F-3 2 B 2.0 CA AO O C FST. .CS 30 VR13 BT i 1-0302-22D F-2 2 B 2.0 CA A0 0 ,C FST. CS 30 VR13 3 k
. e 0
y- } n
- 1. 3 c ith INSERVICE TEDTING PROGRAM >
g Q *? ISI- CL ASS h 2. & 3 val.VES UNIT - 1 Nd Essen OOAD ClilES NUCLIAR POWER ST A TION SysHis . P & le atvisION - SATE PAGE 1; assiouAL heat al.novAL , H.37- 2 9/17/44 s or 36
/ s y/ihogs /J q -
- i. . .
1-tool-1A a-6 2 , a 14 CA HG o o BT oP 90 VR13
............. ---.. . . _ - . .. -----_-. __- - _ ---.. ---..._ ... ...__-_ _ . . . .... - __. =._
l-toot-7m 'E-6 2 a 14 GA Ho o o av oP 90 VR13 i
-- .... . -- = = - - . .----. . . _ _ _ _ _ _ --_.. . . . _ . . . ... _ .___.. .. _- ._
l-tool.7C ' a-6 2 a 14 CA Ho o o nT or 90 VR13
....... -- _ __..- . . . - - - - - _=_ - =- --- . . . . - - . .__ _.----. .._ - ----_-.. ---. .__ _ _... --......
1-1001-10 E-6 2 a 14 CA No o o af OP 90 VR13
.......-- . __.--- ._ ..._ = =_. ...-, . - - _ - - - . ....... ...- - .. .....__ . . . . . . . . ....- ...... .........__ ..- =
l-lool.67A a.3 2 C 12 CK SA C 0 CT-l' or
...==___ =_=. ....... . . ....... . . . . . . . . .. __ _ = _ - . . . . ...-- .'..... ....... . . . . . . . . . .=== =... ___
1 2001-67a E-3 2 C 12 CK SA C
- O CT-1 oP
..........--. ..=_ =.. === _ ... --= _ - - - . . . .._... =. ....... . . . . . . . . ._ __.... .. ___..__._- _ .....
1 toot-67C a-9 2 C 12 CK SA C o CT -l '. OP
.... ..----......... ----... .._-.._ ____=_ -_--... . . . . . . . . .._ _. - - . . . . . . . . . . . . . . . . . _..... - =_____...-
I-lool-67D E-9 2 C 12 CK sA C ,'l 0 CT-1, *OP P
.......... = .=--- ........ . .... ....... ....... ........ ..--... . . . . . ...... _ - _ . , _ . .. . - __ __ - -- ...
1-1001-1254 3-5 2 , C 1 av sA C o CT-2, 5Y
.........---......-- . . . . - - - . ....... ....... ------. ...... . = _ - _ _ - _ _ - - . . . . . . _ _ - ;=-..., _
__=_ . 1-1001-125u E-5 2 C 1 av sA C . O CT-2 5Y
........___.. 2__.-.. . . . _ _ _ _ . ..___.. .______ ..__-.- ==_-_. ....... . . . . . . . ....._'. . _ _ _ . .. ....___.. . .__=- - _ _ . _ - ...
1-1001-125': } n.7 2 C 1 av sA C o CT-2 5y
= - ...--. ...-_.. .'_..... ..... . ..- . . ...==- _
_=_=_-_-- _.=_ .. 1-loot-125n E-7 2 C 1 av sa C o CT-2 SY _ --..... --..... .-- ---- .------. -- =- -u __. ---. - _=+ . . _ __ _ _ _ ___ ___ 1-toot-43A n-4 ,2 8 14 GA HG C
- C UT .oP 105 VR13
_ . _ . . _ , . _ .g. . a __ . .. ._-_. .. _... ...- - 1 1001-43a E-4 , 2 a 14 CA HQ C C BT OP 105 VR13
--... ----. ----... . . . . . . . . ...=_ ...... .... ... ....... ........ ........ ...__ - .... ....... __ __.-- _ = _ - _ . = = _ _ _ -
- l. loot-43C -u-a 2 a 14 CA no C - c uT oe 105 VR13 l-1001-430 E-8 2 8 14 GA Ho C C BT oP 105 -VR13- . .. .........__ _-...____
--.........--....... ....... -- __ _- . -.....-- .....-- ........ . . . . . . . -----. ..- _ -_== -
___==....... _-- 1-loot-6A F-5 2 E 24 aTF M IA NA
--.....---- . ...-... .....-- .------ ._---.. .==_ _- ....... ........ . . . . . . . .---. - - == .. ... _ . _- =_=-_-- .----....
1 1001-60 D-6 2 E 24 eTF M la < NA
-- -.---- ....... ...-- . ... .._ -- -- --.... .. .... ..... .. s.. . -- =..-.. . . - _ _
--__ =- ----...--
1-loot-42A B-5 2 E 14 GA H If NA -
-.....--...-- ....... .... -- .--.... -...... ....... ...= .. .... =_ -.....- ....... ...--_. --- __ ___.. ... ==.--
4
[_ . _ . . r f? A , -
.3 " ! ( '-
c.,,,,,,,,,,gli, INSERVICE TESTING PROGNAM g, ISI - Ct. A S S $. 2. & 3 VALVES.- UNIT :- 1 I QUAD CITIES NUCLEAR POWER S T A TION SYSIEM P & IB MWIS1011 - BAIE FAGE: RESIDUAI. HEAT It'EHOVAI. (CONTINUED) M .37 2 9/17/84 ,og 36
/
/ s r yl/ hon l} q 7 1-1001-428 E-5 2 E 14 GA H I.C HA
___.___..... . ....... ...._-- ._-__... .___ __ ._...__. _______ _.____. _- - -- ___._. .. . _ - . _ _ _ . __....___. ___ m ....____. 1-1001 42C ___- - C-6 2, . E 14 CA H I.C NA
. . . _ _ _ _ . . . . . .___-- =_____ ._...... -
l_1001-42D _ - - - E.6 2 E 14 CA H I.C NA-
-_ _ . _ _ . . . ..__... . _ _ _ _ _ _ . ..___4.
l_1001-66A B-3 2 E 12 GA H :D NA
. _ _ . _ _ _ _ . ____- _ _ = , . _ .
_ _ - - _ _ _ _ _ _ _.-_. . .__- ._ .= _=. . _____ ..__.__. .____ . . = . .= -_-__.. _ _ _ _ _a .___.. . -___ _ _- a === l-1001-660 E- j 2 *. E 12 GA H la
. . NA ,
- 1-1001-66C B-9 _ _ _ _ - - _=.__-
2 E 12 GA H ID
......__ =_ _ .. ===_ __- .__ -_ .______.
NA. 1-1001 66D E-9 2 E 12 GA H to NA 1-1001-15A n-2 2 E 18 GA N 14 NA
..__.._____=_ = ____ _....._ ______. .______ . ......
. . . - ..____ .. . _ . - _. .__...a 1 1001-15B _-
. _ - - _=
2 E 15 - 9 18 GA H IA NA l.1001 17A A-2 ,=__ __._ 2 E la GA H A NA l-1001-17a A-10 .2 E la _____4 ....___. ___ GA H to . NA
-_. =-=- . _ . _ _ . ___. .
..____. _.___.. ... ___ ______ ..____4 1-1001-141A D-3 2 E 2 GA H IA NA l-1001 1418 E-3 2 E 2 GA H LO
- NA 1-1001-141C u-9 2 E 2 GA
- l.1001-1488 E-9 2
E 2 GA H H ID ID NA _ _ __1.: .. __== _
--_ ______.- __ , ==_. ___
NA . l-IC01-142A _ =- == _ _ - _ _ _ _ - =_- l h-3 2 C 2 CK SA C 0 CT.1
=
...___________ _______ . _ _ . _ _ _ ____... . . . . _ _ _ . . _____ . . _ _ . . . . . ____._ _ . _ _ _ . ....___ .OP*_____ .______. . - -
l 1001 142n E l ___._____... _ . _ _- 3___.._______ 2 C 2 CK sa C O cT.I. OP*.. .
.....__. .._-_. ___ ... __ --a _____ .
l l-1001 142c . __ __ ._____,..__ __ h-9 2 C 2 CK SA C O CT-1 OP* '
....... .__ .... ___.___ . _ _ _ _ ____... ....__.. ____..., .______. __= = ---___. .-- _____
1-2001 142p _ = _ = _ - __ .. E-9 2 C 2 CK SA C O CT-1 OP* .
*0PENSTROKE VERIFIED BY PUMP TEST
( INSERVICE TESTING PROGRAM ! UNIT - 1
@conmieawenilli OUADIsiCITIES Hisen - C t. A s s I. 2. & 3 VAI.VES NUCt. EAR POWER S T A TION ST5IEM P 5 IS REVIS100f - DAlt FACE RESlouAL ucAT"staeOVAL (CONTINUED) M.39'sh. I 2 9/17/84 10 of 36 Walvt huusia [ d[ ntManus l AT-1 BR 3 1001 29A E-6 1 A 16 GA HQ C ..O BT c8 -25 J-7.VRl:
== _ - - . - - - -.. -----..- ....... .------. - - - =_ --_ .. ----.. --- --...-- ...-- L. .==..... __
AT-1 RR 1 1001-29B E-8 1 A 16 GA HQ C O BT cs 25 J-7,VRl:
-...=- . _ - - - - . . --- .......- --..... .- ..---.
. .... . =- .. -. ....... ......:.. .. === _ _ - - - _- ____
AT-1 RR I.1001-47 c-5'
.----a.
1 A 20 CA HO o&C C HT cS [ # 46 J-4,VRI: ORour 2 tsdLATIou
---- ..... -- -- . . . . . . - - . ..... __ . .- _ .i _- -- --
_ - . . - = - - - _ AT-1 RR l-1001 50 D-4 1 A 20 GA HO osc c et - cS 40 J-4,VRl: group 2 ISoLATIoM
-- . . . . - - - ....--. .......- ....... . --. --. = _ _ =
, ==--- _
. - - - _ _-==-- =
F-3 AT-1: 'BR l-1001-60 1 A 4 GA HO o&C C BT "cS
-------............. ----... ...-- .. _ = = _ -
25 J-4. VR 13 GRour 2 tso'ATron L
.---- 7 ==-- -- _------------....
AT-1 RR l-1001-63 F-4 1 A 4 GA HO o&C c HT 25 J-4,VRl' GROUP 2 Isot.ATION
....----- --- ..---. . - - - - - . . ---- .. .-----.. .-----. .....--- ..--... ....... -...... ..'-....L cs _ _ _ - . -------:.4------..
PIT RR 1-1001-68A .E-5 I c 16 cK SA c 0 cT-1' cS. c J-2 PIT RR. i 1-1001-60a E-4 i c 16 cx Sa c O cT 1 cS [ J-2
.. ...------. ,----.. ...=- _
.==_ _- .-_. ...== --_ ...
1-1001-16A
.g- 7 2 0 18 GL HO o&c 0 IIT OP 125 VR13
......--..-.... ......-- ....... .---...... _. - _=-.....--....-...
1-1001-16a 2 a la GL H0 ote o nT or 125 VR13 '
....------- . ..' A- 2. . . . . .
....-.. ._ . ------- .....-- .------- ...-- - .---. --.------ . . = = . _=_.- ._ -------.----
1-1001-laA C-6 2 u 3 GA HO c osc 07 oe 17 VR13
--...----- . .....- .....-- ---. .. - .. -- ....... ........ . - - - . . . . ,.....-- ....--- .......- _.... - - _ _ _ _ - _ -- - _ - _ _ ....a==._
t-1001. lou C-3 2 u 3 CA HO c osc nT oP 17
=
VR13
...----- . . . . . - - . ..... -------. .--.. .. . . . . - .=_ -.. _------..--- -
1-1001-19A B-8 2 B 10 GA H0 o O UT cS 125 J-6,VR13
........-.... ....--.. ---...- . . . . - - . . .------ -----.. . . . . . . . . . . . - - - . . ......... ---a. .......,. . - - - ......--.....aa.-----.--
1-1001 19tt B-2 2 8 10 GA HO o O HT CS 125 J-6,VR13 AT-1 RR l.1001-20 2 A 3 GA ,e ose c
....------. . . B-3. - - -....... . . . . . - - . .....-- . . . . ........ --...a- .......
ut OP
....--.., .25 ... ..VR13
.. ...--... ...G Ro.u.P.2..I
. .. s.oLATIow_----...
=.
I h
c uhi . INSERVICE TESTING PROGft'AM [us.n . ISI - CL ASS 1. 2. & 3 val.VES . UNIT .-~1 QUAD CIT IE S NUCLEAR POWER STATION SysttM - t & le
.L AtWessou - DAIE FAGE-
- HESIDUAI; NEAT kEHoVAL (CONTINUED) .H-23:.sh. 1 2 9/17/84 11 or.36
] s y l /h ll q s l} q ht L t-1001-21 B-3 AT - 1 RR 2 A' 3 CA' Ho O&C C BT OP 25 VR13
=--- . .. . . _ - _ . -- _. .._- _. __- . __. ._ . . . -. .._ _ .-- . ._-__..
, ORoue 2 IsoLATIow
- t. loot-22A ____- - _ _ _ _ _-___ _-__._
1-1001-22e
'C-8 E-2 2
C c' 1
.RV- - _-_._
SA _ _ -- _C .
. = -
O CT-2'
= _ _
RR 2 ,
-__--... sA I-Rv C
O CT-2. Rn AT - l 4 __ 1-loot-23A E-6 BR 2 A 10 GA Ho C C VR13 HT OP 15 l-1001-23a 'E-3 2 A AT -1. RR ~ to cA Ho r C af
^
or 15 VR13
._________--_. 4 _-__. .__- .-_ .... ._.___. -__.__. ._. ___ . . _ _ - . . ____ _..___ .__.-_.. _.
AT RR 1 1001-26A E-5 ;2 A to GA Ho C _ - _ - _ _ _ _ _ _ _ _ _ . -____- ---__ ...- _4, nT OP 15 VR13
=_... _____. .__.-_ ___ _____ _ _ _ _ _ _ _ .-____. .._-.= z. _
----=- ____
l-1001-26a AT-1 RR E-4 2 A to GA Ho C C eT OP 15 VR13
. . . - - - - . . . _ _ _ .:... .. -.:_- .. ._-___.. .-..... . _ _ - . . . . . . ...... , _ _ . _ . ....e -. .a__.--
;E-6 t-toot-2aA 2 a 16 on Ho o i .O at .cs 90 J
.= ._ _== . _______ ._.___. ---_ _. ._-____ ._____..
._-7, __.-
V R13 , t-loot-2en E-3 2 a 16 on Ho o o uT CS 90 J-7, VR13
- 1. toot-36A E-7 AT-1 RR 2 A 14 GL Ho C O&C 13 .
RT OP 60 _=_ =-.__ -__-__.-- t_ toot-36n AT-1 RR 03' 2 A 14 cb Ho C . o&C eT OP 60 VR13 AT-1 RR t-tool-37A E-7 2 A 6 GL Ho C O&C 07 OP 60 VR13 1-1001-37s AT-1 RR D-3 2 A 6 GL Ho C OEC ut OP 60 VR13 ___.______ --_ ___.-__ . ...... -__-. . . __-- . ___.___ . . _ _ _ _ _ --__--- ..- . ____. ..-..e. .-_..... ....______ _____-__ ._____-_ ..... 1-1001-34A E-7 2 A 16 CA Ho C 20&C y-l 125 VR13 1-1001-34B E-3 2 A 16 CA Ho C AT RR O&C RT OP 125 VR13
x -
- ,-w 9.
c .hii - 4 INSERVICE TESTING PROGPMM ~ UNIT - 1
. fdesea ISI - CL A SS 12.1 3 VALVES .
QUAD CITIES NUCLEAR POWER STATION ~ SV$IEM P 6 it MVtSMIN - DAIE PAGE. me.=IDUAL llEAT REMOWAL (CONTINUED) M_39. sh. 1 2 9/17/84 12 of 36
/ 1 y l lb ij ay -
a f j q -- 7 . i e geew___e_e__. *e__eee eweem.. e. geese ice _e__* eeeeee. _ee___- ee_Geem p..66f_. ._WG66. *.GGG. 8 .6 GWS. *__66Weeced_mem...____edemeeme_e_. l i_nooi au t.5 l e a ax n so un e....________ ...____ ..__.- ....... _______ _______ .______. .____.. ....___. .___... -______. ....... -_______________...______ ________ 1-iool-33n g ./g l E 16 CA H 10 NA , _ >, ....... ....... .....,t....... ...... . ....... ....---. - _---_ -..._-.. ------- --_-----..---_.- ................_. I i - e 4
% e 9
4 0 k I v e t -
- e O
~
.(
J
'c uien INSERVICE TESTING ' PROGRAM geis ist - C L A S S .1. 2. & 3 VALVES .
UNIT - 1 QUAD CITIES NUCt. EAR POWER STATION
- Sv611M -
p 6 se sigvessong - palg past
~ aestDuAl. IIEAT REMOVAL (CONTINUED) H-39' sh. 2 2 9/17/84 13 oi 36 M amusta I alMAnts
. i c c 2' l-lool-2A D-7 3 12 CK SA , O CT-1 OP ,
....._ ..... ._..... ..... . . . . . . . . . .._.... ....... ....... .....__ _...... ....... ....4.. ....... .......... ..__ ...................
1 1001 255_ g_7 3 c- 12 CK SA C O CT-k' OP-
............. ........ ....... . . _ _ . . . . ...___. ...__.. ........ ..... 4 ..._____ ....... ......,. ...__.. .......... ....._..................
!. 1. lool-2c D-2 3 c 12 CK sA c .
~
O cf.1 OP ' ' ............. . . . . . . . . ..__4.. . . . _ _ . . . ....... ....... ......._ ..... 4 ........ ... _s. ...... . ....... .________. ..............._______.. 1 1001 2D B-2 3 c 12 CK SA c O CT-1 OP __........... ........ ....... . . . . . . . . ....... ......_ ........ ......- ........ .... .. ..... . . ..__. . .......... ....... .....u......._.. 1'
~
l.2001-5A E-6 3 a 12 GL MO C , 06C DT OP 90 VR13 i .___... . . . . . . . . ....... .......__......_..... .. s 1-8001-5a E-3 -3 a 12 GL Ho e . Os.c of , OP to VI'
- 4 4
4
- 1. lool-la C-6 3 E 14 CA M Lo NA ,
............. . . . . . . . . ....... ....... ........ ....... ..._._.. ......a ........ ._ .... . . . . . . . . ....... .......... .......... _...___ .....
1 1001 1R g_6 3 E 14 GA M LO . HA , 3 C-3 3'
~
a 1 lool.lc E 14 CA M la NA 4
............. ....... ....... ....... ....__.. ....... .....___ ...... ........ ............_( ....... .......... ............___.....___.
1 1001 10 B-3 3 E 14 CA M IA HA 4 i 1-lOOI-3A D-7 3' E 12. GA M 14 ? H A .'
- ............. . . _ . . . . . . . . _ ..- ....... ........ ......_ _....... ......, ._ _.... ._...__... ..n ...... ..........-.......................
d 1-1001 3a 85 - 3 3' E 12 GA M ID HA l-8001-3C E 12 CA H la HA
...__.__...__ . . .D . 2. . . ...3 ... ....... ........ ....... ........ ....... ......__ ....___ ......a ........ .................._........__..___
l.1001 3D 32 3 E 12 CA H- ID NA
............. ..... 1 ....... ..___.. . . . . . . . . ....... ........ ....... ......__ ....... ....... ....... ....__.... ........___.........____
1-lool.201A E-6' E 14 BTr M ID' . HA I
............. ...__._ ...Nc ..._ .___... . . . _ . . . . ....... ........ ...___. ........ . . . . . . . . .. ... ........ .......................___.....__.
- l. lool.20ln E-3 Mc E' 14 nTr M in ,
ur i
............. . ..... ...... ....... ........ ....... ....... ....... ........ ....... ....... ........ .. 4......... ....................
1099-1 D-8 3 E 16 CA M LC NA' . i 1 . O t g f
~ - r
, n .: . c.
t
.m W r-m INSERVICE TESTING PROGRAM f64' us
~
UNIT - 1 gC . ISI- cL ASS h. 2. & 3 VALVES OUAD CIT IE S NUC4. EAR POWER S T ATION . SystlM ' . r3 is atMssess - salt ract STAND 8Y LIQUID CONTROL M-44 2 9/17/84 14 R 36
/
! 1-1101 15 ~c.3 1 c 1.5 CK sa c 0 cT-> cs/Ru va-5
.................... ....... ....... ....... ........ ....... ........ 4...... ....... ......, ........ .......... ........................
1 1101 16 c-3 1 c 1.5 CK sA e O 'CT.1 cs/ap va-5
............. ....... ....... ,....... ....... ........ ....... . . . . . . . . ..a.... ..... - ......, . . . . . . . - .......... ........................
~
l.1106A c-4 2 D 1.5 Exe c 0 DT- an i.1106a D.4 2, D 1.5 ExP c O DT , Ra ,, l-1101 43A D-6 2 c 1.5 CK SA C O cf.1 OP l 1 1101 438 E-5 2 c 1.5 CK SA c /O CT ,1' OP . 1 1105A C.6 2 c 1.5 RV SA C , O cf.2 SY
............. ....... ....... ........ ....... ........ ....... . . . . . . . . ....... .......~....... ........ . . . . . . . . . . .............;..........
1-11058 D-5 2 c 1.5 RV SA C' O cT.2 SY
- i. ............. ....... . ... . ........ ....... ........ ....... . . . . . . . . ....... .....e. ....... ........ .......... ..............u.........
1 1101-4 E-8 2* E 2.5 CA M . ID NA
............. .... 4. ....... ........ ....... ........ ....... ........ ....... ..... 4 .......; . . . . . . . . ........... ............e...........
1-1101-8 D-R 2 E 2.5 CA M 14 NA j 1.Il01-3A D-7 2 E 2.5 GA M ID NA j E-7 2 E 1 1101 38 2.5 GA M LO HA 1 1101 10 D-7 2 E 1 GL M 1.C . NA
............. ....... ....... ........ ....... ........ ....... ........ ....... .... 4. ........ . . . . . . . . .......... ........................
1 1101 2A D-5 2 E 1.5 Cf. M 14 i NA 1 1101-28 E-5 2* E 1.5 , CI. H ID NA
- 1 1101 22 c.4 2 E 1.5 OL M st . NA -
1 1101-98 D-4 2 E I GL M 14
- NA 1 1108 23 p.3 2 E 1.5 ct. H ED NA
............. ....... ....... ........ ....... ....... ....... ....... ...... ..... . . .....s ....... ......... ........................
1 1101-1 D 1 E 1.5 GL M to NA
'....... . . . . . . ' . ......e.
^
[ 1
P
- i INSERVICE TESTING. PROGRAM i UNIT - 1
@ Comunenweahh Edison 181 - Cl. A S S QUAD CITIES NUCLEAR POWER ST ATION
- 1. 2. & 3 val.VES l
Sv5Ithe ' F 6 IS R(WIS4001 - BAIE PAG ( nX WATER Cf.EAN-UP. M- 4 7 - 2 9/1.7/84 15 of 36
/ h q ry
] s y/ a fj q --
i AT-1. RR I.1201 2 86 1 A 6 GA Ho O .C BT OP 3G ORm P 3 ISOLATION VR13 P 1,7 RR
.. AT-1 RR 1 1201 5 B- 6 I [l A 6
CA Mo O C DT OP 30 VR13 GROUP 3 ISOLATION 3 e 9 1 l P 1 o e 4 i____ _ _ _ _ _ _ _ -
e-c .n. . comm.awahh INSERVICE TESTING PROGRAM g_, (dison ISI- CL ASS te 2. & 3 VALVES ,. QUAD CIT iti S HilCLEAR POWER S T A TION t SV5HM P & le MVIS104 - DATE PAGE REACTOR CORE ISOI.ATION COOLING M.50 2 9/17/84 16 or 36
/
VALVE NUM N R RIMARKS AT-1 RR 1-1301-16 D-2 1 A 3 GA HO O C BT OP 25 VR13 ' ORour 5 ISOLATION PIT RR
-_.... ____.. ...____. .._____ . . _ _ _ . . . ___ -. .- -= ._- -. . . - - '
AT-1 RR l-1301-17 B-3 1 A 3 GA HO O C BT OP 25 VR13 OROUP 5 ISOLATION AT-1 RR 1-1301-40 0-2 NC AC 2 CK SA C C CT 1 RR VR-8 ___.....__... ... .... . ..... . . . . _ _ _ . _ _ _ - - ___... . _____.. ._..__. .i...... ...___. ,...... . . . . . . . . I s AT-1 RR l-1301-41 D.2 NC AC B CK SA C C. CT-1 RR VR-8 ' _- ... __=_=_______ . AT-2. RR ' l-1301-15A B 1 AC .5 XFC SA O il C CT-1 RR VR-9 _____.= ... . _ . .- 2____ .. __.. .______. ___ .... . . . . . . ...- ==_- . ........ .___. _ . - - _ _ _ _ . . . ... =_ . . _ _ _ _ _ _ . . . _ _ _ - . - _ _ _ _ _
> AT-2 'RR l-1301-15n D-2 1 AC .5 XFC SA O 2. C CT-1. RR VR-9
=_----- - - - _ . . _ _ _ . . ....... . . . _ _ _ . ....__..____... ... __. . . . . _ _ . . .._,-
_____. __ = _ _ _ - _ . . . -___ __ . . . . . _ ___=____....______ i l o f
*W s e
9 0 I s 9
+
}
o
.A -
f ' Commonweallii INSERVICE TESTING - PROGRAM . Esiissa ' ISI- CL ASS 1. 2. & 3 VALVES UNIT . - 1 OUAD CITIES NUCLEAR POWER STATION systiu F 6 IS MSN - SAH PAM s m E SPRAY M.36" 2, 9/17/84 17 of 36 a
- i
/ r yf f bqq> l} q -
9 q.
;f l
CT 1 CS i 1 1402-9A C-3 i C 10 CK SA C O PIT RR J-2
= __ _______ ___ .....______ .__ __ ...._____- .__ ___ ____
CT 1 CS - 1 1402-9D C-4 1 C 10 CK SA C O Pl? RR J-2 1 1402-25A . _ . . _ _ _ _ _ - - _ - C.2 a 10 1 GA HO C of OP 15 _O - VR13
. _ . . . . . _____.. . = _ _ __
l-1402-25a ....,____ _______________ C-5 a 10 l-14a2-24A
. . = _
n-2 2 1 a 10 GA GA
.____=__
HO C O BT OP 15 VR13 M0 0 O' DT OP 15 VR13 1-1402-24B
. = - _ - ____.
B-5 2 8 10 GA Ho O O _... .._ ____ . _____. ___=_ -_ . . . . . Bf OP 15 VR13 1-1402-2RA
. C9 2 C 2 RV SA C 0 CT SY
___= .__ . . - . . ...___.. . - _ _ _ _ . . . ______ . _ _ _ _ _ _ . ;,.. .___ __.-2 .___ .._.- _ , . _ _ _ . . . . . _ _ . .. _ _ _ _ l-1402-288 D-6 2 C 2 RV SA C O CT-2 ' SY
........______. . . ... . . . . _ _ _ . _.._.__ . . _ _ . . _ s ...__ .___...
1 1402 30A C-8 2 8 1.5 GA HO O C ST OP 12 VR13.__---
._- ._.._____.. _ _ _ _ _ . ..._... . _ _ _ _ _ _ . ...____ . _ . . . _ _ _.__... ..___a. ._______ . . _ _ _ _ _ .
1-1402 380 0-7 2 a 1.5 CA HQ O D BT , OP '12 VR13 l-1402-DA E.9 2 CE 12 SCK SA C/in O CT-1 OP l.1402-8B E-6 2 CE 12 ___..._______ ___.... ._____. ........ __.__=- SCK
= _.
SA C/IA O CT.1 OP
=______________
i AT-2 RR l-1402-3th D-3 1 AC .5 xPC SA O C. CT-1 RR VR-9 __ _____. . . ,.______ ....___ _____ __ _..__.. . . _ _ _ _ . . ____. .__... .___ __ ... .. . . - - = - - -
- = . ==-. =-- ___=________ ____
. AT-2 RR 1-1402 310 D-4 1 AC .5 XFC SA O C CT-1. RR VR-9
_____.....__ .___... . ____ . . . . .. .___ ___ _ .. .___... . _ _ _ . , _ _ .______ . . _ _ _ _ . ..__ __ _ =____ __ .._ . I D3 _ . _ _ 1 1402-6A 1 E 10 GA H la NA
- . --.___.. __.. .. ..... . ..__.__ .__.... _____ __ i.
l-1402-60 D-3 1 E 10 GA H la NA 1 1402-2A G-7 2 E 12 GA H 2.C NA I i 'l I.
, . . .]
, . . , - +-
/ % .
g c amiemwahh INSERVICE TESTING. PROGAAM
- ) j 2, & 3- VALVES. UNIT - 1
- I i
g
\,. j ggs ISI - CL A SS - 1 QUAD CITIES NUCLE AR . POWER STAtlON 1
sysites - F 6 se afvisseN - Ball FAGE
'k CORE SPRAY (C000TINtJED) ' E 36 ' 2 9/17/84 is or 36 I
9 f i.
/ r gj /h q q ( {} q --
!.ji f l-1402-28 G-4 2 R 12 GA N I4 NA
\
4 1-1402-34A G-4 2 E 18 STF M IA NA ] _______.._____ ... .. - _= . ______. ..- ._____. . . . . _ _ _ .
= = _ . . __.. - ____ .- -___4, 1 1402-348 F-3 2 E 18 STF- M IA NA 1-1402-44 ==-- ._.__ _-.__
A-a 2 e e Gt. . No C c at or 60 ___ _______ . _ _ _ . _ _ _ ___ =-- .__..- - _ 2. VR-13 l-1402-4m C-7 2 m 8 GL MO C .C BT OP 60
--_ ____=_
====__ . . _ _ _ _ . . . _ _ _ - _ _
-.VR-13--
.___ __ . - - .___.__ -______ _______ _ _ _ _ _ _ _ . . = - - - . _ _ _ _ _ _ . _.=_
.__. ____________=
1-1402 13A E.9 , CE 1.5 sCx sA/M C/th O CT-1 *
...-_.________ . _ _ _ _ _ _ . _ _ _____'t - .._____ _______ .______ . _____. . _____ . _ _ . _ _ . ___._ . _ _ ___.O_P_' . ______.-
i 1 1402-13a E-6 2 cE 1.5 SCK SA/M C/la O CT 1
= _ _ _ _ _ _ - - - -
+ OPI
._____.e. __
i
- Open Stroke Verified by Pump Test e
e 8 4, i
. l i
i 1 i 1
. i
' l, F
INSERVICE TESTING PROGhlAM i
@'cRnn fasen ISI - CL ASS 1.2.13 val.VES QUAD CITIES NUCLEAR POWER STATtON UNIT - 1 SYSIEM P G 88 REVIS1000 - DAIE PAGE PRessuR1: SUPPRESSION -
N-34 sh. 1 2 9/17/84 19 of 36 V4tW( 100 M N R REMARKS
/
s 1-1601-21 C-6 NC A 18 BTF AO AT-1 RR \ C C DT OP 30 VR13 croup 2 ISOLATION / FST OP
--..... .- _ . . . . . . - __. =_ __-
~ . . . . - _ - _ _ = - _ __
AT-1 RR
- 1 1601 22 C-6 NC A 18 BTF AO C C DT OP 10 VR13 croup 2 IsoI4 TION
_ ..._ ... ..:...-- FST OP _ . . . - _ _ - . _ _ .._.... ==-- ...... ... ... .. ..._ . . . . . . . .... _=_- AT-1 RR 1 1601-55 A-6 NC A 4 GA AO O C DT VR13 OP 10 oROuP 2 ISon.ATION FST OP i
...._- . -== ___ ._-..... . _..-. . . _ _ . - . . ... _ ..._- . . . . . . . . _ _ __. . - _ -_. ..
1-1601-56 AT-1 RR D-6 NC A 18 BTF AO O C DT VR13 i OP 10 group 2 ISOI.ATION i FST OP i . . . . . _ . ....... ..._... ._..._ . ... ... . . . . _ _ . _...=- l ._. ._..... ._.._.. ._...--.. . . . . _ . . . . . ... =_... ..=_ __- - - 1-1601-57 AT-1 RR I C-9 NC A 1 08. HO u C DT VR I.1 OP 15 GROUP 2 ISOE,ATION l FST OP
--..__s
= _ -_-_ . .__ .
AT-1. RR I.1601-58 D-1 HC A 1 GI. AO C C DT OP 15 VR13 oRouP 2 ISOLATION FST OP
. _ . . . ....... . -_- .---.._ . . = . - ..._.. . .._- . ..-... . . . . - - _
=__- . ..-- _.____
AT-1 BR t-1601-59 D-7 NC .A 1 Ct. AO O DT VR13
'C OP 15 oROuP 2 ISOr.ATION FST OP
.-___--. .... .. .. _ . . . . . . - _ .-_-... . . _ _ . _ _ . . . ..... .. - ... . . ._- .. ... .... ......_-- _ = _ _ _ _ = - - _ -
AT-1 RR 1 1601 20A D-9 NC A 20 DTP AO C OEC DT CS 10 J-8,VR13 FST OP
. . _ _+ - .e.'.
..... ...... . ... .... ..._-.. ._.. . . -_... .... .. . . . . _ . --_____ -= --
= ____
AT-1 RR 1-1601-31A b-9 NC AC 20 CK SA C O&C CT-1 OP
) ..........---- . . . . . . . . ..___-. .--_... ...._... .... .. ...-- .. .--_... . . . . . . _ . .._-... . . . . . . . ._ . _ _ -
AT-1 RR l-1601-200 10 - 9 NC A 20 RTF AO C OEC 07 CS 10 J-8,VR13 p PST OP J... . .. _. ... . . .. .. _ . . - _.. ..... .._ _-=_--- - _ _ 0 6
i c R a6 INSERVICE TESTING PROGRAM [d s.n ISI- CL ASS 14 2. & 3 val.VES .. UNIT - 1 QUAD CITIES NUC[ EAR POWER STATION sysuu . P 6 le atWsme - BAtt Fast PRESSURE SUPPRESSION (CONTINUED) H-34 sh. I 2 9/17/84 20 or 36
/ r y / j h g ry AT-1 o
RR l} q - 1-1601 31a Ef-9 NC AC 20 CK SA C DEC CT-1 OP - AT-1. RR 1-1601-23 B'- 3 NC A 18 BTF AO C C BT OP , 10 VR13 GROUP 2 ISOLATION 5 FST OP
.... .... ....... ....... .. - ._ . .--.... .a..... ....-.. . . . . . . . . ... --. ..... . = --_
AT-1 RR l-1601-24 B-2 NC A 18 BTF AO C C DT OP , 10 VR13 GROUP 2 ISOLATION i PST OP
............. -- ... ---.... -_ _ =. . . - - . . . . ....... --....-- ....... .---.... ..._- ....... .-- .--- .
1 AT-1 RR l 1 1601-60 s-2 NC A 18 DTF AO C C DT OP ! 10 VR13 GROUP 2 ISOtATION FST OP
.- _ _ _ _ _ = _ _ . . . . . - - _ _ .
AT-1 RR j 1-1601-61 F-2 HC A 2 GL AO C -c BT OP 15 VR13 group 2 ISOi.ATION FST OP AT-1 RR l-1601-62 B-2 NC A 2 GL AO C C RT OP 15 VR13 GROUP 2 ISOLATION i FST OP
.--......---. . . . . - . . . ....--. . --... --..... ....... .... --_ .... .. .. 1.. . ....... ........ ....... .
i
+
AT-1 RR 1-1601-63 A-2 NC A 6 BTF AO C C DT .OP
'10 VR13 CROUP 2 ISOLATION s
FST OP _..... ......a-- - - _ _ _ _ . --....... --- ..----..---..__ AT-1 RR l-0003 C-6 NC A 2 GL AO O C* BT OP 10 VR13 GROUP 2 iso TIOh *
, FST OP
............. .--..... . . = _ - _ - _..... ....... ....... ........ ....... _2.._. ..... . . - . _ _ =- -- _ = . - . = ___ -
AT-1 RR i 1-0004 D-6 NC A 2 CL AO O d DT OP 10 VR13 GROUP 2 ISOLATION FST OP 4 ............. .- ...._ .. .. . . . . . . . ..... . ....... .-...... . . . . . . . . ; = - --.. .---- - _ _ _ _ _ _ _ __. .--........ .... __ . AT-1 RR 1-800lA C-3 NC A 0.5 GL AO O C' BT ~OP 10 VR13 GROUP 2 ISOLATION ' FST OP '
= ...---- - = . -
1
e g .~. , uilk INSERVICE TESTING PROGRAM l- @ ce==. _ Ednen ISI - Ct. A SS 1. 2. & 3 VALVES OUAD CITIES NUCLEAR POWER STAtlON UNIT - 1 51SHM ' F 610 REVIS10ll - Ball RAGE PuEssunE SUPPRESSION (CONTINUED) M-34 ., sh. 1 2 9/17/84 21 of 36 M "U [ .t. I f lifMARIts AT-1 RR . 1 80018 D-3 NC A O.5 GL AO O C BT OP 10 VR13 GROUP 2 ISOIATION FST OP AT - 1 RR ' 1-8801C D.3 NC A O.5 GL AO O C 07 OP 10 VR13 GRour 2 ISotAtrON FST OP AT - I RR I.8001D E.3 NC A 0.5 GL AO O 'C HT OP 10 VR13 group 2 ISOI.ATION FST OP .
.............. ....... ....... ............... ........ ....... .......s ....... ....... ....... ........ ;......... .......................
. AT - 1 RR 1-0802A C-3 NC A O.5 GL AO O 'C DT OP "I 10 VR13 GROUP 2 ISOtATION FST OP
.............. .s..... ....... ........ ....... ........ ....... ........ ..'..... ........ .....b. ........ .......... .......................
AT - 1 RR l-8802B D-3 NC A 0.5 GL AO O C DT OP 10 VR13 GROUP 2 ISOLATION FST OP
. ........ .....'a ........ .......... .......................
AT - 1 RR ' 1-8002C D-3 NC A O.5 GL AO, O C DT OP
- 10 VR13 GROUP 2 ISOIATION FST OP '
AT-1 RR 1 00020 ti- 3 NC - A 0.5 GL AO O C BT OP 10 VR13 GROUP 2 ISotATION FST OP 1-1601-32A E-2 NC C 18 CK SA C OEC CT.1 OP S. 1-1601-328 E-2 NC C 18 CK SA C DEC CT.! OP -
.............. ....... ....... ........ ... ... ........ ....... ........ ....... ........ ......a ....... ......... .......................
1 1601-32C E-2 NC C 18 CK SA C OEC CT.1 OP i 1-1601 32D E-2 NC C 18 CK SA C O&C CT.1 OP 1 1608-32E E-2 NC C 18 CK SA C 06C (.'.T- 1 OP - h
Y . . 9m~) c alih INSERVICE TESTING PROGRAM ISI - CL A SS UNIT - 1 gNNd [h J QUAD CITIES NUCLEAR POWER STATION
- 1. 2. & 3 VALVES ,
sVSIIM P 6 se afve580N - BAIE PAst Putssuns SuernEss10N (CONTINUED) N-34 sh. 1 2 9/17/84 22 of 36 , l
/ r yllh4y o l$ q -
k + 1 1601-32P E-2 NC C 10 CK SA C i ...._ _...__. ..._-_. ...____ ..._____ = _ O&C CT-1 OP
....- =_-.. .____-_
1-1601-334 _. . . _ _ _ . . - E-7 NC C la CK SA C 2 O&C CT-1 OP 1 1601-338 ..... _ E-7 . _ . . . = - _ - __...._.._ . t, ....... .____ _... . ..- NC C 18 CK _..=_ SA C
,.--O&C
....~
CT-1 OP , 1-1601-33C E-7 NC C 18 CK SA C _.=_ __.- OEC CT 1
. ____ _.. __ _==.... . . . _ _ . . . _..
OP 1.s601-330 ..___..
- P 7 NC C 18
=_
= . . .... ...__......
_= CK SA C O&C CT-1 OP
.===- _.._.. __ __
-.._... =_ _ . . . . . . . . . . - - _ -
- 1-16D1-33E E.7 NC, C 18 CK SA C
- ....._. ...._- - =_. _...... . . - . = - - = _ . . . . .
OEC CT 1 OP _ = . . . ._..... ..__ .. .= j 1-1601-33P E.7 NC C 18 CK SA C
. ........_-- ....._ ._.=_
O&C CT_1 OP 1-220-8tA ........ __ == Ee4 _ _ _ . . _ _ _ _ _ . . -- l NC C ==_ CK 1 SA C O CT 1 CS +
-_-..- _ . . . . . ..== _._- -. -.._... . _ _ ..___... .__._.. . . . . . . . . _ _ . . _ . . ...... .
VR-14 l-220-818 5: 4 =. -
- NC C 1 CK SA C
- - _______ ..____ ...-- __=_...
0 CT-1 CS VR-14
. = - - - _ ___.... ._____.. a __ .. . _ _ _ _ _
1-220-81C E-4 NC C 1 CK SA C i _=_ =- __
, ....__........ ...___. - __- _ ._= =_--_
O CT-1 CS VR-14 - f'
!.220-01D E5 NC C 1 CK SA C
,1 ===_ _____ ... . _ .._ .. _... . _ . - ____ O CT-1 CS VR-14 1-220-81E E-5 NC C 1 CK SA C
. _ _ _ _ _ _ . _ _ _ _ _ . . . . . . . _ _ _ _ _ . . . . _ _ _ _ _ . . . - __=____.
3 _.... - - - - - - O CF-1 CS VR-14 i 1-220-105A D-4 NC C 8 CK SA C -O'__ CT-1 CS VR-14 { __- .. ...-___ ....... . . . . _ _ . . . . _ _ _ . ..__.. .___.__ ... .__ . ____. .-___.. ______. ..______. _.........__.___..... , 1-220-105B E-4 NC C 8 CK SA C 'O CT-1 CS VR-14
.______ ....... ..____. _...... ______~..____ ._;.... ._ ___. . - _ . . . :_____. ..____..........._______.___._ '
i 1-220-105C D-5 NC C 8 CK SA C 0. CT-1 CS VR-14 h ..__.__ . __... . . _ _ _ _ . __..... ________. ._---__...... _-_..__ 4 1-220-105D D-5 NC C 8 CK SA C 0 4 CT-1 CS VR-14 1-220-105E E-5 NC C 8 CK SA C 0 CT-1 CS VR-14 j o 1 9
o T INSERVICE TESTING PROGRAM UNIT -- 1
@cuneullh %- ISI - CL ASS OUAD CITIES NUCLEAR POWER STAT,80N
- 1. 2, & 3 VALVES. ..
STSHM P 6 IS REVIS10Il - SAll PAGE I/17/04 311G41 PRESSURE CODE. ANT INJECTION "M*40 2 23 Of 30 1 AT BR l-2301-4 C-9 1 A 10 GA MO O O&C HT Cs 50 J-5,VR13 oROur 4 ISOt.ATION PIT RR - AT RR 1-2301-5 a.10 1 A 10 GA MO O O&C BT Cs 50 J-5,VR13 ___=-=__- .. . = - _.. . . . - ...-.. . . = - .= oROur 4 IsOt.AtroN
.... - -. ..._ --.a..... . . . . . . . . . . . . - -- _.......-......
1-2301-3 A-6 2 a 10 GA Mo C O af , OP 25
. . . . . . _ . - _ . - . . . . . . . . .....-.- ....... . = = .__.... .- ... . . . . _ . . . ..... _ . . . . . .
VR13 1 2301-68 A-6 2 D 16 RPD SA C O * -
*PER MANUFACTURER RECOMMENDATION 1 2301-69 A-6 2 D 16 RPD SA C O *
*PER MANUFACTURER RECOMMENDATION
_____= - -- - - - -
....... .... . - - . . . . .... _-- .- _.. _ . - - - = _ __- _
BT OP 1 2301-29 8-9 2 8 1 GL AO O C FST OP 10 VR13
.-.=. _.... ....... _ _ _ _ . ._ __ -
_ _ _ - - _ . - _ _ _ = _ - _= AT-1 RR 'OPEN STROKE VERIFIED 1 2301-34 D-7 2 AC 2 CK SA C OEC CT-1 OP/R R* .. VR-8 BY PUMP TEST AT-1 RR *OPEN STROKE VERPIED 1 2301-45 u-8 2 AC 24 CK SA C O&C CT-1 VR-S OP/RR*... SY PUMP TEST 1 2301-35 E-7 2 m 16 GA Mo C O&C at OP 120 VR13 1-2301-36 . E-9 2 a 16 GA MO C O&C ST OP 120 VR13
...... ._ .= .... - _ - - _
1 2301-6 r.2 2 a 16 oA HQ O O&C af OP 120 VR13
............... -..---- . . . . . - - . .- ....... . . _ _ . . . . ........ -__. . . . . . . . ..... =. ...... __ _- _ _
l-2301-20 E-2 2 C 16 CK SA O O CT-1 OP
......... . ....... - - - . . . . . ....... ---.. ...... _ _ - _ - ...-_= _ - - - - ........ ......: . . . . . . . . . . . . . . . . . . ......_. .......--...
1-2301-14 C-6 2 B. 4 GL M0 C O&C BT OP 26 VR13 I
-..._...._ s 1 2301 39 E-9 2 C 16 CK SA C O CT-1
- VR-7
*SEE VR-7 1-2301-40 D.7 NC C 4 CK HA C 0 CT-1 OP**.
.......-----.. ... ... . . . . - - . . ....... . -.... ....... ....... .. __ ____= . . . - . . . . ..... .
9
** Openstroke verified by pump test.
. e.
.3.e. g r' .
i c-a INSERVICE TESTING ' PROGR AM - E6sen ISl - CL ASS 1.2.43 VALVES , UNIT - 1 OUAD - CITIES NUCLEAR POWER ST ATSON - 593His P 6 IS BEVIS10Il - SAlf PA6( Hicu retEssuRE Coot.Aur lesJECT10el (CONTINUED) M-46 2 9/II/00 24 of 36
/ r yl/bqq > l} q - .
1-2301-a D.6 2 a 14 OA Ho C 0 or Oe 45 VR13 __......._..- -..._.. ..=-_ - - - - - -
. . . . _ . . .= .. ._..-_.. ....
RR ' PIT l.2301-7 D-6 2 C 14 CK SA C O CT-1 CS J-2 80PE86 STItOKE VERIFIED I-2301-74 R-8 2 CE 12 SCK SA C/to O CT-1 OP* SY PUNP TEST AT RR 1-2301-26 D-9 1 AC .5 XFC SA O C CT-1 RR VR-9
. . . . = - - -- - - _... .. -_ . . . . . . . . ........ . ... . ._ .... . ..... . . . . . . . . ___-2_... ...... . . . . _ . . .. __... . . . _ .- - . .
AT-2 RR 1-2301-27 D-9 1 AC .5 XFC SA O C CT-1 RR VR-9
.____...__... ..___ . __...__ . . . . . . . .. . - - - ... ._..._. _ .. . . . . . . . . .... _- .. .. _ =.... .....- _ . _ _
l-2301-22 u-1 2 E 16 GA M LO NA 1-2301-56 F-8 2 E 16 BTF M ID HA
-- - _ =..... . . . . . . . . ...... .__.... .- -- ....... . . . . . - - - .-= .._..... ...__.. . . . . _ _ .
. ._ ..==- . - -
=
1-2301-71 D-7 2 CE 2 SCK SA/M C/ID 0 CT-1 OP* *OPEN STROKE VERIFIED BY PUMP TEST ___..__ ........ =.. . _ - . _ - - - .. . . - - ....
. . . . . = - - -
1-2301-9 D-5 2 a 14 GA Mo o o at Oe 45 VR13
.........__.. .... --. ....... . . _ . . . . . ....... ......_ _...__. . . _ - . . . . ....= _ _ . . . . . ....... .._..___.. .= _..--
1-2301-10 E-5 2 a 12 01. No C 'C af OP 60
..._ _... . ....-_.. ...--- ___- ..... .. . . . _. ....... ...__._ ........ ....... .._.__.. .- VR1.3 _ .. =- __ .
v n - f c .nla INSERVICE TESTING PROGRAM , gg ISI- CL ASS 1. 2. & 3 val.VES . OUAD CITIES NUCLEAR POWEH S T ATION _ . . l. .- .- - MAIN STEAM N -13 sh. 1 2 9/17/84 25 or 36
/ r g j l b g ry > l} q -
AT-1 RR BTP OP . BT CS 5 J-1 GROUP 1 ISOLATION 1-203-IA F.4 1 A 20 GL AO O C FST Cs VR13 PIT RR AT-1 RR BTP OF BT CS 5 J-1 GROUP 1 ISOLATION 1-203-1B p-4 1 A 20 GL AO O C FST CS '
- VR13 PIT RR AT-1 RR '
BTP OP BT CS 5 J-1 GROUP 1 ISOLATION 1-203-lc C-1 1 A 20 CL AO O C FST CS PIT RR VR13
-_ _ = _-_
==
AT-1 RR BTP OP BT CS 5 J-1 GRO'UP 1 ISOLATION 1-203-1D D-4 5 A 20 GL AO O C FST CS i PIT RR VR13 i AT-1 RR : 1-220-1 E-4 1 A 3 GA MO C C BT OP 35 i
. . _ - __..... __..- . . . . . . . ....... . . _ . _ . . . ._ .... ..._... . _V R 13.. _.
_. GROUP _. ......__ 1 ISOLATION ___ BT *
- VR-1 *SEE VR 1 l-203-3A F-7 1 oc 6 ERV/SV PS/SA C 0 CT-2 RR VR-2
_..__...._ __ __. _-___. ... .__ .._. ....... .---- . .....__ _ . . _ . . _ _ _....._ _ . = .. ...._.
. . . . . . _ . . . .r==--- - _..__ _-_..
BT *
- 1-203-38 D-6 BC 6 VR-1 *SEE VR-1 1 ERV PS C 0 CT 2 RR VR-2
..._= . _ . . . _ . ....... _______ ....... ..._... ____.... _______ ___..... _....._ _ _ _ _ . . . ... ._ _ _ _ _ . __... . _ ___ _ __
BT *
- VR-1 *SEE VR-1 1 203 3c c-7 1 HC 6 ERV PS C 0 CT-2 RR VR-2 BT *
- VR 1 1-203 3D B-7 1 DC 6 ERV PS C O CT 2 HR *
..VR .
.. .s._EE.V_ R.1_-- =-
I ( L/M' c .nn INSERVICE TESTING PROGRAM [ des.e ' ISO - CL A SS 1. 2. A 3 VALVES . UNIT - 1 OUAD ClilES NUCLEAR POWER STATION k systees P t le BEWIEIRN - SAIE PAGE MAIN STEAM (CONTINUEDI g .13 sh. 1 2 9/17/84 26 of 36
/
i
/ i y/ /hng > l} q -
a *
- et va-1
- t-203-3e D-8 1 aC 6 eny es C 0 CT-2 na va-2 assa va-1
. __.....___.- .---__. ......_, - = - = _ - - .__- . _ . _ - - - - . . . . ______. ..._ __ . . . _ _ . . . - - - - -
t-203 4A F-a 1 C 6 Sv sa C 0 CT na va-15
. . . - - _ . -.--. = . . - - ....... ....-__ ___-2 . _ . .__-.__ . . _ - - - --... ._ _ _..--_ _-. _..
1-203 4a D-5 1 C 6 Sv SA C 0 CT-2 ma va-15
- .... _..___... ....... . _ _ _ _ _ _ . . _ _ _ = ... ...._ . ....... .___... . . . . _ _ _ . ._. .-___. . ... -
1-203-4C C-5 1 C 6 SV SA C O CT-2 mm Va.15 . ___..=_- - --- . ----- .
=. ----_-
! 1 203-40 8-5 t C. 6 SW SA. C O CT-2 mm VR-15 j ___. ...-_.--- . --... . . . . _ . . = _ _ . _ . . _ _ - . . .. ..--- _ _ . . . ...___.. r-e
- i 203-4e sv t-203-4F D-5 1 C C
6 6 sA C 0 CT-2 am va.15 ___ - =.. .=._---- ._ 1 SV SA C 0 CT-2 na va-15
- ......._=_ . .__.. . . . _ _ . . . ---.__. . . _ _ _ _ _ - _ _ _ _ _ - . _ _ _ _ _ - - = = ---- .
i-203-4G C-5 1 C 6 SV SA C 0 CT-2 mm Va-15 3 _ _ ___ = .... ..._ . . 1-203 461 a.5 t C 6 SV SA C 0 CT-2 mm VR-15 < .. -_-- - - = - ...... ........ .._= . . . _ _ _ _ .____.. _ _ _ . _ _ , ......_ . - - - . . . _ = =...... ... ... . . . . . - - i t i l i 4 n i i I' I } 4 i J t 1 4 r d 1 . 1
, .. ~
i-m INSERVICE TEDTING PROGRAM e ggs., est - CL ASS 1. 2. A 3 VALVES UNIT .1 - OUAD CITIE S NUCLEAR POWER STATION SV$ltu . P & le MVIS4008 - DAIE PAGE MAIN STRAM. {COttTINUED) y _g3 Sh. 2 2 9/17/84 27 of 36
/ r y/ /hqq > l} q " '
AT-1 RR BTP OP DT CS S J-1 OROUP 1 ISOLATION ' 1 203 2A t-7 1 A 20 GL AO O C- FST~ CS PIT RR VRl3
= _......., . _ .
AT-1 RR DTP OP
. BT CS $' J.1 GROUP 1 ISOLETION l.203-28 E.7- 1 A 20 GL AO O 'C FST CS PIT, 'AR VR13 AT-1 ,RR BTP OP .
BT CS 5 J.1 GROUP 1 ISO 6ATION 1 203 2C D-7 1 A ? GL AO O C FST VR13
', RR CS PIT .
.... - w ..._
_ AT-1 RR # DTP OP - BT CS '5 J-1 GROUP 1 ISOfITION 1-203 20 97 1 A 20 CL AO O C FST CS
- PIT RR 3
. . . . . . . __ ........ ....... -.... .4--- ...-... --..- ..'...
==...---en...--...
AT-1' RR l-220 2 E.7 1 A 3 GA M0 C C BT VR13
'OP 35 GROUP 1 ISOLATION
...---= . _.....---
AT-2 RR 1-220-17A E-8 1 AC 0.5 XFC SA O C' CT-1
---- -__ - . . = - - - _. . - . .
. .RR VR-9 AT RR 1 220-178 D-8 1 AC 0.5 XFC SA O C CT-1 RR
= .
VR-9
=--- _= ___...
AT-2 RR 1 220-17C C-8 1 AC 0.5 XFC SA O C CT-l' RR VR-9
.... ..= = -- .=_ _-- ' .
AT-2 RR
; 1 220-17D B-8 1 AC 0.5 XFC SA O C, CT-1 RR VR-9
... ---.. - .....-- .....-.. . . . - a-...- - - --- - - . . . . - - -
.. ~...
?m G ' r_m
( :: ' gegen
. INSERVICE TESTING PROGRAM UNIT - 1 ISI - CL ASS 1. 2. & 3 VALVES .
QUAD CITIE S NUCLEAR POWER S T ATION STSMit F & 19 REWIS10lf - SAIE PAGE-sIAlu STEAM (couttuuto) M -13 sh. 2 2 9/17/84 2s at 36 ;
/ t y l l b g ry / / q -
i I. AT-2 .RR
- l-220-18A E-8 1 AC .5 XFC SA O C CT-1 RR VR-9 s' 1-220-tas D-a AT-2 ,RR
- AC 1 .5 XFC SA O C, CT BR .
VR-9 i 1-220-ISC AT-2, '9R C-8 ' AC 1 .5 XFC 84 0 C., CT-1 RR , VR-9 - 1-220-180 AT-2' RR , 5-8 1 AC .5 XFC SA O C CT-l RR VR-9 _ _ _ _ _ _ . --- . _ - = _ _ _ _ _ _ _ _______ ._____'_ _2,_____ k, e +
*h 1
i i 1 . I i l t l, , b
INSERVICE TEDTING PROGRAM
@ t.au== nh [h ISI- CL ASS 1. 2. & 3 VALVES QUAD CITIE S NUCLEAR POWER S T A TION UNIT .: 1 ,
SVSHM , , F 618 9(VI$ leet - DAl PAGE ; FEEDedATER g . M - 15 ' 2 9/I7 84 29 of'36 ' i yllb qq ;-. f s , f) y / AT 1 RR , 1-220-58A E-3 1 AC 18 CK SA o C CT-1 RR VR-3 u.......... AT-1 ,RR , 1-220-588 F.3 1 AC la CK sA o O&C CT-1 RR VR.3
~
1-220-598 F-3 2 C 19 CK SA O C CT-1 RR VR-3 4 S_...... .
. AT-1 RR l-220-62A R-3 1 AC 18 CK SA 0 C CT-1 RR VR-3 AT-1 RR s 1-220-628 F.3 1 AC IS CK- SA O OLC CT-1 BR VR-3 s
.i .
?
4 Z e i t e 1
=
s' e) r-m Edman INCERVICE ISI - CL ASS TESTING
- l. 2e 4 3 . VALVES..
PROGRAM UNIT - 1
-+
OUAD CIT IE S NUCLEAR POWER 'ST AilDN tvsum P 6 le atvuuse.- eut rast stevics watte - M 22 - 2 9/17/84 3e or 36 l 3999-es A-to
/
3 r c s' / i e en sa h q q c cr.1 or l} q ' _ . _ _ . . _ ._ _____.- ...____. _ _ - - - -- ___ .______. .______ . __6_.,_. .__.__- _._. 2.__.__ .=_ -- ._____.- = ______. , 6 3999 e9 3 e e cu sa c a cT_1 or i _______-es . . . - . .___...- -- _--- . _ . ..____. ..__ __ .__ .... .__._.. . -......__.__ - - _ _ _ . a__.__. ._________ __.____._...__.____._ 1-3999 $_le
- 3 e a cK Sn e O cv-1 .or < -
.._____-se ____ . _ . - _ _ . ...___. . . _ _ _ _ _ . _____.. __.._.. ........ ....... .__x ... ....__.
--__________.4. _ ._
i 1-3999-139 3 C 6 CK SA C 0 CT-1 ,0P 3 ,
.____________ - _' A- 9___ - -_-_... -_____. -_____. -____-- -___--- -----_< -e_.-- ------ 4-----
t------ I e o e 1 -
,S e
I e 9 e f e
t [ ') r - INSERVICE TESTING . PROGRAM ISO - CL ASS 1. 2. & 3 VALVES Ud 1
- 5 O J 86ses QUAD CITIES HUCLEAR POWER STAtidN ,
i sYsnes . . t 6 se afvisses - sans rast . . I~ I
. passst. csseRaA90s sTamTilIG AIR l SERVICE AIR SYSTEM l N-25 1 2 9/17/84 31 od 36
, e l --
/ / y/ /bqq> l} q --- :
i 1-4699-121 E-9 # MC E 1.5 OA M IA NA 3 f 4699-122 E-9 NC E 1.5 GA M ta NA I 1 _..___ -_- =... _ _______ ._ = ._.. .___ - . -_
. . . . _ .._ _ _ _ _ _ _ . _.__ _. ... .... _ _ _ _ _ _ _ _ _ . _______. .- l j 1-4699-225 D-a t0C E 1.5 sat.t. M tm ,
NA g :
, 1 1-4699-123 E-9 Itc C 1.5 CK SA C O CT-1 or
-__.._ .... ...- .___ . .__ .. .__..... .___... _-___.- ... .. ....1_, ==
I-4699-196 E-9' 90C C 1.5 cK SA C e CT-Et OP - __.......____. .__.... -___... _ __.. ....__. .______. ....... . _ _ . _ _ _ . ..: . ._..a_. . _ _ . _ 1-4699-226 D-9 teC h 1.5 Ct. AD C 'O BT DP i. VR-13
. _ _ _ _ _ . . . s. .. ....___. __... ..___ . . ._. . _ _ . . . . - _ . a. ..... - . YR _16 . . . . . _ _ _ _ , . . _
r D
.F b
a m C* 3 e. e p. 9 k e
% b
, , ,4 O
w9* y m 1
m INSERVICE TESTING PROGRAM
@r-sh [ disse - ISI - CL A SS QUAD CITIES NUCLEAR POWER STATION
- 1. 2. & 3 VALVES ..
UNIT " 1 SV5IIM t 6 is . MVissou - salt PAst INsTRunzur AIR PIPING H-24 sh.'2 2 .9/17:/84 g l 32 of 36
] t y/ lh qq r f) y - - -
j ! AT 'RR , A OA AO O C BT ' OP 10 GROUP 2 ISOLATION 1-4720 D NC 1 VR13 FST . OP .
..-_____...= _ i AT - 1 ' RR ..
WC A GA AO O C- BT OP 10 VR I .) OROUP 2 1801 TION 1-4721 D 1 FST OP _ ---._ ,I
..._- .=_ _ __- _
AT-1 'RR .. .. 0.375 BALL SO C C BT OP $- VR13 GROUP 2 ISOLATION
- 1-733-1 P-7 ' NC A
== .-...._ ---.... ......-- .---- . -... . . ..__ .... . -------.--
= - _ = - - _ _ - _ .
AT -1 ': BR A 0.375 BAI.L so C C- pt OP 5 VR13 GROUP 2 ISol.ATION '! 1-733-2 ' IP-7 NC
=- -----. ..._=_ ..... =_ r. ..... .--.__ - .. _ -------
AT -l '. kR l-733-3 F-7 NC A 0.375 BALL 60 C C- nf OP S VR13 cRour 2 ISOLATION
"_--_ _=
. . . . . . . . . . _ = _ . . . = ____ ----..
AT-1" RR 1-733-4 F-7 NC A 0.375 BALL SO C C DT .OP 5 - VR13 GROUP 2 Isot.4 TION
= _ . _ ._ --.
_... . ==...- .__ ._ ....== _--
- AT-1 DR ..
VR13 l'-7 BALL SO C C DT OP 5 oRouP 2 IsotATION 1-733-5 NC A 0.375 , AFI . BR ,' . CT-1! V R-4 1-743 B-7 NC AC 0.375 CK. SA O C, RR
-... ..; = _ _ - - _ _ . _ . __- - ---.. ..
----==___ -- ---.... . . . . . . . . _ _ _ _
1-736-1 F-7 NC D 0.375 EXP O C. RF ~BR i . . _ _
=
O.375 O C DT RR l 1-736-2 _=__________ _= F-7 __ =.. NC
. .= .= D _
____ ..= . EXP _----- .....__ ___~-- C DT BR ". 1-736-3 F-7 NC D O.375 EXP O
........ .......... ...--...---== _ _ _ _ _ _-
-.........-. . .._- - - - . . .....=- -.. . . . . . . . _ =-- .. . . _ ..... ..... . .......
1-736-4 P-7 NC D O.375 EXP O C. DT .DR
--. --....s..-__--..
j - __===... .... . ... .. ..._ ... .__. F-7 0.375 EXP O C~ DT BR 1-736-5 NC D
....... . . . . L... . . . - - - . . .--..-. . ..... . -....... ........................
--...--...... .. = - --___ = = - ....- . ........
f q
i -<
, s ,0., .
r .
.len INSERVICE TESTING PROGRAM UNIT + 1 O ceaun MseR IM - C1. A S S QUAD CITIES NUCLEAR POWER STATION
- 1. 2. & 3 VALVES I
SY5Ilet ax guggaING EQUIPMENT DRAINS , F 6 84 A(VtS10It - BAIE PAGE* l (& SHARED UNIT 1/2 DIESEL CEN. AIR START PIPING) H-43 2 9/17/84 33 of 36 g
/ / - !,
/ s yllh q q >.// q -
AT-1c .RR l-2001-15 E-3 WC A 3 -GA AO C C DT OP 20 VR13 GROUP 2 ISO'ATION L FST ' OP j
-__ - _.... . - - - _ - - . -- -_. ._-----. .. --_- .-=___ -- - --_ . -
AT-1* RR . f 1-2001-16 E-3 NC A 3 GA AO C C BT OP - -20 VR13 GROUP 2 ISOLATION l FST OP l
---- ------- - - . - - - - . -__ ------ -------. ._. . - - - - = -
^
P
. AT-1' RR *
-l
!' 1-2001-3 F-7 NC A 3 CA AO C C BT 'OP VR13 GROUP 2 ISol.ATION
.20 4' FST- OP l _------ - - - - ....-- .-- ---. . . . - - - - .----. ------- ._----. 2_-- .---- --...-- .a - - - - - - - _ . . - - ---= .
~'
= - - =
AT-1 RR
- i 1 2001-4 F-7 NC A 3 GA AO C C' DT * . O. P - 20 VR13 GROUP 2 ISOLATION.
j FST Oe ' j
, 1/2-4699-46 D-9 NC E 1.5 GA M ID NA 1/2-4699/47 D-9 NC E 1.5 GA H ID NA ' "-
' 1/2-4699-225 D-8 WC E 1.5 B A t.t. M ID NA \
= _-----_ ---- . - - _ . . . . ----.-- .--- .-----_- ------- == _ _--- .------ ------- - - . - - _
1/2-4699-4e D-9 NC C 1.5 CK SA C o CT-1. OP. ,.
---......---- ___.--- . -. = _ - - _ - - ---- .------. .... -- ----__-___---- . - - - - - - _ ------- .---. --------__ _-----_------ _ . --- - - -
1/2-4699-196 D-9 NC C 1.5 CK SA C O CT-1 OP D-a a 1.5 av
-g__ __==------ -----
1/2-4699-226 . NC GL AO C 0 OP 5 VR 1 _3=
---------.... ----- . .------. ------- .------ .____ -- ._---- ------ =.--- .----- - ------- .------- .--_- .--.------ _____ _
e t O t c I t
.i
~
fw 'r-m INSERVICE TESTihtG ISI - Cl. A S S 16 2. 4 3 . VALVES- ,e PROGRAM UNIT a 1
~
\~vM '7 (d OUAD ' CITIES NUCLE AR POWER STATION n - . . - . . - . . . ,
SVSIlt0 'oggggg,'cggggg,og pygg,ogg. P 6 it REVI510el - DAlf PAGE' (UNIT 1 AND 1/2) M-29 2 9/II/84 34 of 16 ! I i e
/ / g j / A q q p l ;$ q .y 4
1-5299-5 E-4 tec c 1.5 cn sA c o' CT-1 or 1-5201 E-3 NC t 1 GA 80 c o at - OP 5 V.".13
... . _ _ _ . ...... . .___. .__.___ ...._._ . . . _ _ _ . .._____ ._____.. ___' =___ _
1-5199-155 3-5 NC E- 1 GL M :ID 6:A [ . _ _ _ _ . . . _ _ _ . ..__. .. ___..__._____---- - 1-5199-157 c5 sec c .5 CK SA c c cT-1 . OP r
=______.__.__.
j 1/2-5299-5 E4 tec . c 1.5 CK S4 c 0 CT-li ,oP , , ..._ _ = _ _ . . _ _ _ _....
.. _ -__ . . . _ _ _ . . _.-- _ _ _ _ . . ______- . _,... _ _ - = . ..._ . .. . . . . _ _ _ _ .. --. . . , . _ .
c 1/2-5201 R-3 sec h 1 GA so d; BT .oP 5 VR13 - l
- ___ .. .._ . .__ ... . . . . _ _ _ . . ____.. . _ _ _ , __ .- . . . .. _ - - - = _ . . . .= ___. . . _ _ _ _ . ..__._._____.__'.-- -
1/2-5199-151 c-5 - c .5 cK sa c 'c cT 1 *' or '* 5 _._______ . . . . _ . . . .._tec .____ . . _ _ _ _ . . . = _ _ . , _____.. _ _ . _ _ .___ .__ . ...-_ ._-- .. . == ._ __.....,___ .__ i .
- e-.
*g.
4 s
- i e
p
. .; i.
a t
* \ ,
i,* . 4 ** g 9 i
. j e-G 9
c-m -INSERVICE TE' STING PROGRAM ' Edison lSi- CL ASS 1. ' 2. & 3 ' V Al.VE S . UNIT 1 4
' QUAD CITIE S NUCt. EAR POWER ST A TION,
- systtM - .
. F 616 Attnsaem - e M E rasg .. .
cosetAIIteSNT ATHOSPIGERE 80NITOR ' j 86-641 SK. 1 2 MUM 30 *E 30 4 i t An"I So-t-2499-lk D-7 BIc A 0.5 GA So e o NR AT-1 .._ .....--. -- . VRIO
---.1VR13 30-1-2499-13 .D, tec A 0.5 OA so e o AT-1 ---------._ -. ...2f.. . .__ ... __ _-- ------- . = - ___
mR a---. vg}g--...,. yg 13 so-t-2491 2h D ,6 nec - A 0.5 ca so c- O, AT t BR VR10,VR13 p-3 --..n ___- so-t-2499-2s asc A o.5 on so e o AT-1 an VR10,VR13 . __--- .------- .. --- -------. .------ . = = _ - ._..,-- - - - - - - . , . ...--... -al--... . - . . . . - - . --- .. ... so-1-2499-3A a-7 ' uc . A o.5 cA so e -o,, AT-1 mit - VR10,VR13 so-t-2499-3s
--- . _ - - . - - - - . _ - - - . ._-_.--w .--
s-2 esc A 0.5 on so e O. AT-1 ma VR10,VR13
.------..- a... --
__ ---. ... --...-- - - . . . . . ------- .=_ -- ... ...---- ..---- -..-----. --------.. _. .... -- so-t-2499-4A m-6 see A o.5 oA so e o AT-1 ma VR10,VR13 -
------. ..- _= . ;._
.so.t-2499-4a n-3 Nc A o.5 ca so e o- AT-1 an VR10,VR13 -
-,-----------. - - - ._. :-- . _ .-- .. ---. .....-- -----..+-...-- ..... . .. ...-- -. __. - - . . . . . _
\ .
4 , 9 f' O s
. g b**
9 a
s '- - r
/ON
~
r_.ia INSERVICE TESTING PROGRAM r q O ) f6sen ISI - C L A S S 1.2. E'3 VALVES . UNIT - .1 v /~ -QUAD CITIE S NUCLEAR POWER STATION Systtag F & BS MW151001 - SATE PAGE ATMDSPNERIc Coef?AINMENT ATesOSPilERE DILLITION N-642 'Sh. 1 2 9/17/84 36 of 36
/ r y/ jhqqyl} q / ._
a l
--- __-- = --- .
Ao-1-2599-2A c-4 Mc A 1.0 OL Ao C 0- AT-1 na VR10,VRl] . - i
-----_. ------- .-----_. ---_--- -------. = --
.- a_ = _ . . . :. . ---___= ___... ----- _.. h An-1-2599-2s c-5 . Nc A c o 1.0 ob Ao 47-1
. an VRiniVR13 c-5 o' Ao-1-2599_3A
------_ - .=
Nc A 1.0 OL Ao e AT-1
--_--w an
. - - - - - - . --=
VRIO,VRl] A0-1-2599-36 c Nc A 1.0 GL Ao C 'O AT-1 ' RR . VR10,VRl]
---4._. . _ . _ - - _ . -- . - _ - - - _ . = . ------- . . - . ---i .u-----. .- ---__---- -
1-2599-23A c
--------= .
1-2599-23b c-3 Dec A 1.0 cK SA
~0-AT-1 ita
- - _ - - - - - --=-
. VR10,VR1]
u-----_- c-6 etc A 1.0 CK SA c 'O AT-1 an VR10,VRl]
--- -- .------- ----.i--
_ - - - . - -- . - - = __== -_----_. 1-2599-24A c-3 Nc A 1.0 CK SA c o AT-1 ,. an _--_. s _- . . - _ - - - - . ---- .------- ----_-- ------_. ----_-- .-_---_. ..._ -- . ..--, .: -- VR10g vR1] 1-2599-24s c-6 Ne A 1.0 cK sa e o AT-1 ' an VR10,VRl] .-
---_--- .. ._----- .. --- . - - - _ - _ . -- - . _ - - _ - - . ..-_--- .u-----. --_ - :.a ._ _ . -,-- . _ - ---- . _ - . -- _ - a _ . _
An-1-2599-4A F-3 Nc A 1.0 cl. Ao C 70 AT-1 l AR VR10,VRl]
-==---- =
Ao-1-2'.91-48 t-3 Nc A 1.0 ct. Ao e 0' AT-1 ' an VR10,VRl]
- _ - - _ . . - = - - - = = . --_---. ...--__ . - -- -_-.__- .----__. .....-- . - - _ - - - ------- - - - - - a.----- .__------_ -------- u _
rev-1-2%9-5A F-4 sec . A 1.0 cb Ao c ,o AT-1 na VR10 VR12 __-__i---_ -_-=- rev-t-2599-se E lac A no e 'o; ' 1.0 ob AT-1 RR VR10,VRl] g e O4e
.g 9 e e *r e 9 I
fa
-. . . - - - - _ _ _ _ _ - _ _ _ _ _, *4 s .. - .
s. ii , INSERVICE :TESTlNG . PROGRAM Or_m go . ISI - CL A SS ' t. 2. & 3 VALVES . UNIT .'.2 OUAD CITIES NUCLEAR POWER STATION s;sitas r 6 se afvision - shit rAst j NUC1.&AR BOtt.BR INSTRUNENTATION SH -77; Sh. 1 2 9/17/84 1or[36 s l t yl /kqq i l} q - AT-2 . RR ,., , 2-263-2-15A p-5 l' AC 0.5 Mrc SA o C CT-1 mR vR-9 < AT-2 BR i 2-263-2-13A" D-5 1 AC 0.5 XFC SA O C. CT-1 RR VR-9
.. - __ .-.6--. - _ - - . . . . ....--.- .__ . . . - -- .
. . . . . . . .== _- - = _ - -_
_ = 2-263-2 19A- C5 AC 0.5 XFC SA AT-2. RR '. ' 1 O .C CT-1 ; RR VR-9 .
-----......--. . _ _ _ _._ --=_ ---- . .... .- - . . . . . . ...... - - - . . .-.... ..-...a. . - = = a...... .... - ......... . .. .=
AT-2 - SR 2-263-2-17A' D-5 1 AC 0.5 XFC SA o Cs CT-1 y RR VR-9
= - _ . . . . . ...---. ....... .. -
__= = =_ . . - . . . . . . ....... ..---a. ....... = _.-.. ____---..
; AT-2 RR 2-263-2-11 E-5 1 AC 0.5 XFC SA o 'C #
CT-i RR VR-9
--......-.. . . . . . . . . . ..._=
l = ;_ =. ......
' AT-2 RR .
2-220-54 E .6 1 AC 0.5 XFd SA O C. . CT-1 F;R VR-9
=. - .. - ..... ...
. ..== = . . . . _= . __ _ . . - _
AT-2 i kR 2-263-2-15a D-3 1 AC' O.5 XFC ti A . O +C CT-1 / RR , VR-9 _ -- _ _ _ _ _ = = . .. .... ...... = _ . ==.. . . . . . . . ....... . . - - . . - - . .... .. ----.. -s .... .s ...- ......... ...._ _.___.. . - AT-2 RR . 2-263-2-138 ~ D-3 1 AC 0.5 XFC SA O C' CT-1 ' RR VR-9 .f
--........--. - - - .=- ...... . - - . . . .
... ..- -----... .. =
y....., ___ _ __ _ _s-- ..... AT-2' RR . D-3 2-263-2-178 ,1 AC O.5 XFC' SA 0 C- CT-1 RR VR-9
. .--- ...... e -- '
_ _ - _ . _ . ____ -..- . . - - - - _=- . ....... . . . . . . . . -==.. 4.-... ... -.. '
. AT-2 RR 2-263-2-198- C-3 . 1 . AC 0.5 XFC, SA O 'C. CT-1 RR VR-9
- --.=- . . .,-.== = -
__ -- - . = - _ -_ . _ - - - . .. AT-2 . BR 2-263-2-204 a-5 1 AC 0.5 XFd SA o C VR-9 ..
- - . . . . - ==... .,.... _ . _ _ _ _ _ _ ___ __ ......_ . . . . . . . .... -- ...---.. 2...- CT
= - . -. 1
.; " ..RR .. . . . - - . ...= . , . . .... .. .---..l.... .--.
AT-2 RR 2-263-2-23A C-5 , 1 .AC 0.5 XFC SA O C' CT-1 RR VR-9
....--.n 9 ._.....
- AT-2 RR 2-263-2-318 C-5 1 0.5 XFC SA O C' VR-9
, -- -.... ..-- ...- - . .- . AC-..... = _ _ _ -.-.--. --.-.-. .... .--. -- CT-1... .RR u-.- .---. .-- ;-...- -.-- ..--. I m __.s
' INSERVICE TESTING PROGRAlwi UNIT - ~2 O t--sik ' Edson .
ISI - CLASS h 2. & - 3 VALVES QUAD CITIES NUCLEAR P O W Eft STATI N SVSHM P & iS RfWIS4000 - DAlf PAGE NUCLEAR BOII.ER INSTRUNENTATION (CONTINUED) H-77 sh. 1 2 9/17/84 2 or 36 l yl/bqq!lj t q .. - AT RR 2-253-2-310 C-5 1 AC 0.5 XFC SA O C CT-1 RR VR-9
. _ _ ..._ . . _ _ . . . ....... ._.._. - . ... . _ _ . - ...a... . . _ - _ - _ . s-_. . . . _ - ..- _ _ _ . = .-- __. 5.__.....
AT-2? RR ' 2-213-2-31C C-5 1 AC 0.5 XFC SA 0 C CT-1 $R
=__ - - _ - - .._..
VR-9 AT-2 RR 2-25S-2-3111 C-5 .1 AC 0.5 XFC SA O C CT-1' RR VR-9
. ._ _ . ..... ...._ _ ._..._.. ...... ...__- . . .. ..._.a. ..... _.. _--- . _ _ . _ _ - _ - __=_..
AT-2 RR 2-253-2-31D 1 .AC 0.5 XFC SA O d CT-1 ' RR VR-9
- ._---_- _.. ." C-5
....__ . ... .. ._...... ._.___. . - - - - - _.... . _ _ _ _ g. . . ___. . _ . _ _ . _- _-- =._ ___.__ . _
AT RR
.A-5 AC 0.5 XFC
{253-2-27 , 1 SA O C. CT-1 SIR VR-9 ~ AT-2 ^ BR 2-263-2-25 s-5 1 AC 0.5 XFC SA o C CT-1 RR
- ___ ___ ._. .. .. . .=
i VR-9
- __ ... ___ .. ..... .__.. . . . ._ .... ._...4. ._ . .. .- -- - - _ ____. .._____ _ ____. ___ _-
AT 'r RR 2-253-2-31J C-5 1 AC 0.5 XFC SA O C CT- 1 ', RR
--=.... .
VR-9
...._ = = = _ , .. - _.... ..__..;. ..,;___ -__=_ . . = _ _ - _ _ = - ._. .__ __. ..__.._
AT-2 RR i 2-253-2-3RR C-5 1 AC 0.5 XFC SA o C CT-1 RR
- VR-9
_....__ - __... ._ . ...- _ __. . - - - - - _ . . . . __. ..a;._ _ __ . . .... ... .... . . . . . _ _ . . - __=___.. _= __-_.
, , AT-2* Ti 4
1 2-253-2-31K C-5 1 AC 0.5 XFC . SA o ,C CT-1 RP VR-9
- - - _. = = = .____ --
_3 -- .. _... ...__ . __... , __. _.. .. .._. ... .._ _ .. .. . .... . :.... . .._.- AT-2 , RR 2-253-2-238 C-5 1 AC 0.5 XFC SA O C CT-I , RR VR-9 i ______......_. ....... . ' AT-2 RR
- 2-253-42A C- 1 AC O.5 XFC SA O C
__.....__. ... .. 5 .__. -- - CT !
......'. RR VR-9
__ ..._.. - - - _......s . AT-2 DR 2-253-2-200 8-5 1 AC 0.5 KFC SA o CT-1 , .AR
.C. -
VR-9 . _ .___. ..._.== . AT-2
- RR s.)
i i 2-263-2-20C_ 1 AC 0.5 XFC SA 0 CT 1
...._......... . . _ . . . ....... __.__ _ . ...... ....... . ...... ._. ... ..C ....._ .___... .RR . . .
... ..... . .V..R.-
. 9__. .. .. ...........==== _.
I f
INSERVICE TEDTING PROGRAM
@r-.m gm R ist - C t. A s s 1. 2. A 3 val.vEs > UNIT - 2 QUAD - CITIES NUCLEAft POWER ST ATidN Sv5HM F 619 RIVtslosi - SAll PA6E htCLEAR BOILER INi'TRUMENTATION (CONTINUED) M-77 Sh. I 2. t 9/47/84 3 of 36 I t
lt y/jhqqs fj q f AT-2 RR 2-263-2-23C C-3'. 1 AC 0.5 XFC SA O C. CT-1' RR VR-9 _ _ _ _ . . . - _ = __ . ..____. .
-- ....... ~_ -. . _____ .__..... ___. .-- __ . - - - = - - - - .. . - - -- - - . _ _ . = _ _ _ _... ..
AT-2 RR 2-263-2-31H C-3' 1 AC 0.5 XFC SA O C CT-1 ' VR-9 *
.= _ .. -. ....... -...... _ _== . ....._. . . = - .
.._RR ._ __. _. .- .. . ..__ _-.._ s AT-2 RR l 2 263 2-3t? C-3 1 AC 0.5 XFC SA O C CT-1' -RR , VR-9 ,
_____... . _ _ _ _ = _- - - _ . . . ._.... . ..... ____.... ......_ ...== _... ____ .. __ .....-- __.- . AT-2 *RR 2-263-2-31N C-3 1 AC 0.5 XFC SA O C CT-1; 'RR VR-9
...... - =_ _
= =.- - - -
AT-2 RR 2-263-2-3 tts ' C3 1 AC 0.5 XFC SA O C CT-l' VR-9 =- ___. ___ .... _. . . _ _ . -. ....._. . . . ===_ =- ____.... _ _
-._...;. . ..' R R
.. . _ _ _ _ =____. ._
AT-2, 'RR 2-263-2-31P C-3 1 AC 0.5 XFC SA O C CT-1.[ RR VR _ . _ .... . _ _ _ . . . - ._ ._. . . - - -- ....... ________ .____.. _____ .. _.. __ == _. __-9_ _ . . . - AT-2 ^BR 2-263-2-33 B-3 AC 0.5 XfC SA O C CT-1 . - - -= 1 RR VR-9
= - - - - - .______
AT-2: '. R R a. . 2-263-2-31V C-3. 1 AC O.5 XFC SA O C CT-1; RR VR-9 _=. ._ - _- - AT-2 - RR 2-263-2-3RR C3 1 AC 0.5 XFC SA O C CT-1 RR VR-9 .___ _ ... ._...'. - _ __-.. ....... ......_ . . . - _ = _ _ _ =-. _ - - _ _ . . AT-2 RR 2-263-2-31W C3 . 1 AC 0.5 XFC SA O C CT RR VR-9 ____... . . .. ...__ _ .4____. .......... _==.________ -
, AT-2 RR 2-263-2-23D C-3 .
1 AC 0.5 XFC SA O ,C CT-1: RR VR-9 ....__.....__ .. . . . . . . . . ._ _ __. .....__. . ...____. ...s.__ .....__ __ .... - _ . . . . . . .=-_--_ .__ _ .__ AT-2 RR - 2-263-2-421l C 3, 1 AC O.5 XFC SA O C CT-1, RR VR-9 _....___..g.____...
. _ _ . . _ . . _..= _-
z..... _ _ _ . . _ . . . . .
. AT BR 2-263-2 20D D-3 1 AC 0.5 XFC SA O C CT
_ _ . . . . _ - . . . . ..._... . . . . _ _ . .._.. ...._.. ....... ..._. . . _ _ - . ..... ._.. _1 _ _ . . R.R.. . ...... ..V.R.- .. 9 __. - 4
. t l k
k 4
.. ,. A INSERVICE TESTING PROGRAM O r_m % ISI- CL A SS OUAD CITIES NUCLEAR POWER S T ATION
- 1. ' 2. & 3 VALVES '. UNIT '2
. systEls P & IS REWI$1011 - SAIE ' PAGE RECIRcut.ATIces . M- 7 7' th. 2 2 9/17/84 4 of.36 i r
' W&WI U11U000 [ .; .
REum5 2 07 CS 45 2-202-5A D.6 . I < R 28 GA HQ O C PIT hk J-3,VR13
--..... = - - - - _. .....-- ... --. ...a.. - - . . . . . . -
a i of - Cs 45
- 2-202-Se p.3 1 a 20 on Ho O C PIT nR J 3,VR13 I
. . . . . -- --- ....... . = - .-...- .-. --.
t AT-1.s_ RR . I 2-220-44 E- 5 1 A 0.75 ot. AO O af OP $ VR13 G W 1 IsOt.ATION C- cT -, aR FST OP ,
- __ ___= -
==....... _.. _-- .... ....
l AT-1 ,* RR VR13 2-220-45 E? 1 A 0.75 Gl. AO O C. HT OP 5 GROUP 1 ISOt.ATION FST OP , .
....-- =.. -- .
__=- .-_ ..._ _ =_ .______ .. 4 . ..... . . . . - - _ _ _ - . _ _ . - - i
. . AT-2 RR i
2-220 67A F-5 1- AC 0.5 XFC SA O C CT BR VR-9 _ _ . . . . . . . . ....... ...... .. . .. ... . - - - . . . .---... ...s.... ..._ .... -- ___ =. ....._.--..:......... AT-2* RR t 2-220-67R F-5 1 AC 0.5 EFC SA O C, CT-le , RR VR-9 i .. ........... . . - ...... = = = . . .. . - - . .
.....--. .... -- ........ ..... . . . . _ .. ...- _ __ -.. =...
t- . AT-2 RR j 2-220-47C eof-5 1 AC 0.5 NFC SA O d CT.1, .' RR
~
VR-9
.. - = --. . . . . . . . . . . . . . .....-_ -_.-_.. . . . . . . . . ....... . . . . . . ....... ....-_.. .. --
=....---.....,._.. ___
. AT-2 ItR . , i 2-220-67D F-5 1 AC 0.5 KFC SA O C CT 1. . BR
- VR-9 .
! .....--......- .s.... .. .... ___....- =_ .__ .---_- _ --- _ - ---- ..... . ---... . ._.... . . . . - _ _ _ _ . . . .- AT-2 BR '- 2 220-89A E-1 1 AC 0 . '.a KFC SA O C CT-1.. RR VR-9 i . . . . . . = . ....a.-
.... .--.... ...... .. .... ._ ... . __y ._..... . . - - - _ __-. _= ....... .--.. --_..
AT-2 ' RR 5 s 2-220-898 E-1 1 AC 0.5 (FC SA O C CT-1 '. RR. VR-9 ' ' 3
! AT-2A RR 2-220-67E E-5 1 AC 0.5 tFC SA o C- CT-1 . RR va-9
. . . . _ . - - ......_ ....... ._..... . ...... ..._ ._... .... .. ......... 2... . ...
AT-2 RR
' 2-220-67F ,
F-5 . 1 AC 0.5 EFC SA O C CT-1 ) RR VR-9 *
=
t .' .
. i 1
[. , a INSERVICE TESTING PROGRAM OF_.% i Eh tsi - C t. A S S 1. 2. & 3 VALVES ,. UNIT - 2 , QUAD CITIES HU Ci.E Ait POWER 8T ATION I susism e a se afvision - satt tast Rec RCut.ATION (CONTINUED)
- M-77 Bh 2 2 9/17/84 5 of 36
/ r yl/hqqs f/ q -
AT-2 RR 2-220-670 ,E-5 1 AC 0.5 XFC SA O C CT-1 .R R VR-9 -
.. _.... .______ . _ . . _ _ . -- -- .. . . . . . ... ...___ . - - - - ___A.....__ _
AT-2 RR 2-220-6718
. ___ _ ==
F-5 1 AC _=. == 0.5 XFC SA O F CT-1 RR VR-9
=._ . - _ _ . -- _
AT-2 'RR 2-263-2-6A 8 1 AC 0.5 XFC SA O C CT-1 *RR VR-9
._ __= . ...._ .*_-7'_ _ _ . ..- .. _. _...__- ....... ......_- . . ... ._.a.... - _ . - . . . _ . . ..___.. ... ._. _ . - _ _ . --____ .__ ...
AT-2 .BR 2-263-2-5A' '8-7 , 1 AC 0.5 XFC SA O C- CT-1 itR VR-9 4..- ._....- - - - _ . . . .a__..._ ___= ...... . _ _ _ _ ___ AT-2 lRR 2-220-20A a-5 ,-- 1 AC 0.5 XFC SA O C, CT-1 RR VR-9
- _ _ _ _ _ . . _..... ==_ =_ _ . - -__ .. -
2-220-194 b-6 1 AC 0.5 XFC SA O C- CT-1 1RR i VR-9 _._ __. _ __=_ . ___.== _.... ....... . ..w . ...... =. ,
'. AT-2; itR 2-220-22A D-8 1 AC 0.5 XFC SA O CT-l' RR VR-9
.. AT-2 .BR 2-220-21A D-9 1 AC 0.5 XFC SA O C. CT-1 .*pR VR-9
_ _ - __--- _---- _= -=_____
.._h..
-e.e__..i e g. . . ...
- g. e . . e .w ep AT-2 RR ,
2-220-208 A 1 AC 0.5 XFC SA O C, CT-1 RR VR-9
-_.._...._. . . _-__ = . . . .. _-- .._.... .__..... ._._. _ ..... .
. . . = = _ _ - . _ . . . _..
AT-2 RR ' 2-229-198 A'-3 1 AC 0.5 XFC SA O C. CT 1 ,RR VR-9 _ _ . . . . . ....._. . - _ _ .__ _ _.a _ _ . . . . . . ---- _ ..._.. . _ . _ _ _ .- - AT 2- 5.R 2-262-2-6B 'l- 2 ' 1 AC 0.5 XFC SA O C '. CT-1 .RR VR-9
.......___... . . . . . _ _ . _ _ = . -
....... .. ....._.. .._.... .....__.-...__. . . . . . _ . - ....... -_===___:-__ ___ - __ ....... __..
AT-2 $R 2-262 2-se- s-2 1 AC 0.5 XrC sA O C: CT-1 RR VR-9 AT-2' RR 2-220-228 D-l 1 AC O.5 XFC SA O
.. - __ . . . . _ . . - ___ _ . . . .... - ..._._ . _ . - - .._.... ....C ..- .C_T. _1_ ' R R.....
_- a....._ . .V...R- 9.._ - . = _ _ - - __ _-==-- 3
il! _ y_ 2 6 1.~ - a ~
- r t E
G o T A _ _ I P 6 . . N U 4 8 _. E/ I _ A7
- S1
/
- 9 i
s o i s i v2 f 9_ _ a _ _ a_ v_ . 2 _ M .N e h _ i . , f o A 'f.O y
- ls _
R ,ITA & _ _ e
- _
_ t 7 _ GST 7 OES H
- Ra_
Rs t V _ - RL R _ PlV E 2 W - TT 1_ _. O Ac_ G3 P + N&.l I l ,__ _ r T2A E I c__ . S .L i E C _ t TS UN _ - _ S _ A S o_ _ EL E C CI I T I a_ - VS C I _ s RI D _ E A S U c N Q e _ I x I D 5 _ E _ U o N I T N O c c ( A 0
. - 9 - .. O I
T 1 A. a-t u c n = i ,= ' ' * .
- c _
n c 1 i is a 0 d cE- -
= _
2 1 _ t 3 _ e o, i t 0 sy 2 - 2 - S - 2 - 1 i I: 4 , ; ' 1l
4 - 14 we,a INSERVICE TESTING PROGRAM
- 1. 2. & 3 val.VES UNIT J 2 O te th ISi - CI. A S S OUAD CITIES NUCi. EAR POWEP STATION systtu .
P & le RivtSION - BATE PAst . coleTeot. Roo DaIvg M .s 3 . 'sh. 1 2 9/17/84 7 or 36 i t taavE leuusia 4 8 aEMARits
/ ,
(177) 2-n305-127 o-9 1 a 0.75 cA Ao e o. af
- va-s : *ScAAH TESTING
. _ - = - - - ._-_ . ._ _ _ - . ._ =-- ._..
_ _ . . . _ _ . . . = = ._ - (177) - 2-0305-126 o-to- 1 a 1.0 cA Ao c 9 af * - va s asenAN TEsTIwo _ - _ . . . . . . . . _ _ = . ._ .-- _-____. .-- _ --- _ . . . _ ,
._=-. -
(171) 2-0305-114 E-9. 2 c 0.75 cK SA c d cT-L. 5 VR-6
- SCRAM TESTIllG
.--_. . --_.--- . ..- ....... . _--._ .---;_. _ _ . . . . . . _ . . . _ _ . . . ____.....:- _ == - -
DT cS
- 2-0302-21A F-6. 2 a 1.0 CA Ao o c- Es? .cs ~30 VR13 ,
-. _=___. ..-- ....--. .. .a.._ . - _ _ _ _ . ,
el BT cS 2-0302-2ta F- 6 2 a 1.0 CA Ao o (i rst cS 30 VR13
.__ -_ ... _ _=_ ..--.;- .- --_. . . . . . . . . ;,._--- .;-__--. _ _ . _ . .. -
=_- __... __. _
BT c5 2-0302-22 A ' r,5 2 a 2.0 CA Ao o c rst es 30 VR13
~
...-....- ------------ a.....---
BT US 3-0302-21C F-1' 2 B 1.0 CA A0 0 C FST CS 30 VR13 3-0302-21D F-1 2 B 1.0 CA A0 0 C FST CS .30 VR13 BT CS 2-0302-228 F-5 2 B 2.0 CA AO O , C FST CS ~30 VR13 3-0302-22C F 2 B 2.0 CA A0 0 C FST CS 30 VR13 2-0302 *2D' F-2 2 B 2.0 CA AO O C- FST CS 30 VR13 ____..... _-- _ - - - - - . ____.- ....._. ....__. ___.-.. . . . . . . . ______ -___.. .. .... ..._a, .4-.... ----...-. ..-......-__---....... e
, m ,3 INSERVfCE TESTING PROGRAM .
@ r-.ni. m ISt - Cl. A S S OUAD CITIE S NUCLEAR POWER STATION
~
- 1. 2 & 3 val.VES
. UNIT - 2 susited r 6 is afvissen - sait rAot :
RESIDUAL NEAT REMOVAF. M-79 2 9/17/84 s of 36
/ / y/ /hqq g l} q f 2-toot-7A n-6 2 8 14 G% MO O O BT OP 90 VR13 ----__ __ __ ___ _ _ _ . ----- ___=-- -
__ . . . - - - = _ - - _ 2-toot-7a E 2 a 14 GA HO O 8 BT 'OP 90 VR13
--.---.-= . ' .- 6
.. --= ------- .------. _ _----- -. -- _ __------._ -----
2-1001-7c t 2 a 14 GA HO O O BT OP '90 VR13 ! _ . _-.----... =_ . - = _ .
-_--- _ = - - - . ------- -------. ----. _ _ = _ _ _ .
.==----- _ a _ ==
l 2-to01-7D E-6 2 8 14 04 m O O DT OP '90 VR13 ; _= --.. -- - ----. u---. - _ - -- _- _.. - -...----_ . _ 2-toot-67A B- 3 , 2 C 12 CK SA c 8 CT-1 .OP
== = _ _ _ _ = _ . . . - - - . . .= __ ----. -- __ = -- -_ -... ------- : .--- .---.. ....-- .---= --------- g 2-1001-675 E-3 2 C CK SA C 0 CT-1 OP
.-.12 I
r , g
. . . . . . . .-- .....----- ------. . . . . - - . --==__ .-~ . -.__ _- - .---.---_-- --
2-toot-67c n-9 2 c 12 cn sA c 0 cr Oe ! i -------- . _- . -_ . .---.-- - .------- . - - - - - - . -- -- ... -__-l'---. .- -. .- .- - =-.. . ---- _ l' 2-1001-670 E-s 2 c 12 cn sa c o cT-1 OP
---= _ .- _ . - - . ---._ . - - . ----- _ = _ . - ____ _ _ = _ . ...... .------. . . . . .____ -----.. - -
~
2-to01-125A b-5 2 c 1 RV SA C O CT-2 J5Y -
. - - - - - - - - - - - . ... --- - _ . ----.-- .....-- .--..... ..----- . . _ - --y--- ===_ -=_ - .----------.. __ -------- .--. -
2-1001 125a E-5 2 c av SA c o cT-2. 5Y .
----- _ -= -
.=. --
= .---...- .._---- --- .------ . - - - - - - .--._ __ a - . - - - -
2-toot-125c s-7 2 c 1 av sr c o- cT-2 5v
----- -= -_ -------. ------- -_ - ...-- .. ...---- . . _-- --- -_ _ . . .------ ..---- _ _ .
2-1001-1250 E-7 2 c 1 Rv sa c 0 er-2 , SY
---.- .__... ..- __ _. ------- ------- .....-- ....... . . . . a-- -----.. ..----- . ---- _=----__ --- _ = =
2-toot-43A a-4 , 2 a 14 ch HO C C, BT OP 105 VR13 2-tootU[a E-4 2 a 14 GA HO C C st? OP
.;;---.- .s-.
105 VR13 I
------__-.... .---... - - - --- --- .--_ -- ...----. . _-... .------. ._. _- ....---. .== -._ . - - - - - -
2-to01-41c a-a 2 m 14 cA *a c c of : De '.105 VR13
- - - - - - - - - - . - - ------- =. _---- = -- == . ----- .-.----. ..--.-- ------. ._ _= .----.= _. .=- .--- -------.....-----
2-toot-43b E-a . 2 a 14 GA HO C C, DT , OP 105 VR13
------------- ----_-- ------- --- = . - - - - - - - .. ....-- . ....... .----- . --- .-- ....- . . _ - _ _ _ - _ _ - - - - - - - - - - - -
2-100t-6A F 2 E 24 BTF H ID NA
.------ .--_--, .. --= - - - . . ..... ..-------........._. __.-------
2-1001-6B B-6' 2 E 24 BTF M ID NA
- . - - _ _ _ ....... --.---.. _--- .------ .---.... ....--- .------- ....... .----... ....... ......--. ____=_- _.-- -- =- .__
2-toot-42A B-5 2 E 14 CA H I4 NA '
-----.------. .... 4. ....... ------. ....--- . - - - . - - . .....-- ----- . .. .... ..--.--. . ...-- ..;.--_ _- ___.-- ....._---_-----.---=
, .s. %
INSERVICE TESTlNG PROGRAM UNIT E2
@c-.nh f6sen ISI - CL ASS QUAD CITIES NUCLEAR POWER STATION
- 1. 2. & 3 VALVES -
3 g sysitas P & le Rivessell - self PAGE , s aEstouAE. HEAT REMOVAL (CONTINUED) M-73 2 9/17/84 9 of 36 l t gj ih q q s ]) y . 2-1001-428 E-5 2 E 14 GA M IE NA
.--- _ _ _ _ - . . - - = = - _ - -...-- ------- . . .
_=_ _- 2-1001-42C C-6 2 E 14 GA M LC NA ,
\ .... _ _ _ __....- - - . . .......-----.. .-...... ------. ----- ...;... --... - L- = . . . . . . -. _== _. .
2 1001-420 E-6 2 E 14 GA M IE NA j i 2-1001 66A B+3 - 2 e 12 GA M ID NA i .. --
= ..--- -- - 2... - - . _ _ _.= . . - - . - - . - - =___.--. ..._
I 2-ROOn-66h t 2 E 12 GA H ID NA L =--- . _ _ - - - - - - - - . - -.. .__ .... ---- ..
........ -- - -.--- ...--.----=--. =_=
2 3001-66c B-9 2 2 12 GA H ID + NA i --
= ---..--.- - --_. . -
--_.... ....-- . .-.- .--.. ..-_ _-- _ _ _ _ _ = - _ __
___a---- 2-1001-66D E-9 2 E 12 GA M ID NA .
===_ _ _ - - _.. -- --- - -.. -- _ _ _ = - - - _- =_-..
....... ... -- .------ a... .. . - - . . . . - _ - _ - ..__ =-_ _ ... .--
2-5001-15A. B-2 2 R 18 GA M ID NA _ - _== _....--- . . . - . . . . .. .. - - . . . . _ -
-- ...-..-- -----. ..- == =_ - _ _-
2-1001-158 a.9 2 E IS GA M la NA s _ __ - . = - - __ . . . _ -. -------. .... ----.. .:.---.. - - - - - - ---... .. -----_1.== _2.--.- _ e 2-1001-17A A'2 2 E to cA M :D , NA - s _ _ . - - ----- .= - . - - . . _ __- 2-1001-17a A-10 2 E 18 GA M ta NA
=- _
...-= --- ....--- l= _
=_.- -------- _ = - - --...- ; - ----
2-ROO1-141A B-3 2 E 2 GA . M ID WA
- - . - - . . ____ --.... ..= . .
. ..a.. -= --
2-1001-141R E-3 2 E 2 GA M ID NA . _..== _ . - _ . . .--... . . . - - - - . . - - = _ . . . . - . ._- .. ....--- ----... .. ..- - .--...- .. .-- _ _.___... .;..----- 2 3001-14tC B-9 2 E 2 GA M ID NA r
==_ _---=- . - . . . . . ..... . - -
- - - - - - - . . --..... .-:.-__. .--.:... a _;-.-.-- . - -
- -_-. . . . . . _ - . _ = ___=-
2-1001-141p E.9 2 E 2 GA M ID HA
.- =-_ _ -_ .... -_ _ .. . ..... --- . _. __- .- . .-. . .... . ._ _ =.- a s_
2-1001-142A h-3 2
.= .....
C
- . . . - . . . . ...- ---. . ..-- CT-1 2 CK SA C O
. *0P
.....- .= --
-- . . ......_. ... --. --- . ..-__ _==.= ___ ___-. _
2-1001-1428 Ei3 2 C 2 CK SA C G CT-l
.....___ _ ==- __=-_- - . . - - - ...__-. . .
.. _- --. --- . ..--. _-_;._-- ... . .. --- .0P - .... ... . . . - - - = = .. ... ,.. _-___
2-1001-142c u-9 2 c 2 CK SA C O' CT l ' '*0P i
- -.... __...... --.._-- ..._---- ....... . --_-... ....... 4_._ -- ___. -. . _ - - - - - . . . - __ - . - -
2-1001-142n E 2 c 2 cu sA C o- cT-1 wop.
- 1
. *0PENSTROKE VERIFIED BY .i PUMP TEST .
, .v f ,
INSERVICE TESTING PROGRAM sysages
@r-m idesen ISt - CL A SS QUAD CITIES NUGLEAR POWER S T ATION
- 1. 2. & 3 VALVliS .
UNIT .2'. i
. t 6 le AEvtsmal - BAlt tast ' '
RESIDUA!. HEAT RE3toVAI. (CONTINUED) H-s1 sh. 1 2 9/17/84 1o of 36 l
/ r y l l h g ry AT-1 o
'RR l} ,
q -1 O 2 1001-29A D6 1 A 16 cA Ho C D DT, 'CS
'25 J-7,VR13 *
--- .--- __----- .= _. - ---- - - = _ --- ------
=
AT-1 RR - i 2-1001-29s F.- 8 1 A 16 cA no C o DT CS 25 J-7, VR 13
..------ ------- --- -__ == ------ ...-- ..--
AT-1. BR . 2-1001-47 C-5 1 . A 20 QA Mo osc C DT CS 40 J-4, VR 13 amour 2 IsoLATIoM ___ - _ --- .. -- ----. ------- .------ - - - - _ ------. =_- - -
= _
AT-1 RR 2-1001-50 D-4~ 1 A 20 ca Ho osc c' at 40 J-4, VR13
, CS ORour 2 Isot.ATioN AT-1 RR F-3 i 2-1001-60 .
1 A 4 uA No osc c- BT 'CS 25 J-4, VR13 OROUP 2 ISoldfloN
- - _ _ . - = _ _ . ---.--- .------. ._ _-- .
_- - = F-4' AT-1 'BR .
- 2-1001-63 1 A 4 cA Ho osc C at 'CS 25 J-4, VR13
._____ =----- .----- . ------- ------ .
OROUP 2 ISok.ATioN PIT BR
- i 2-1001-6aA' ,
5-5 1 C 16 CK SA C 0 CT-1 CS J-2
..u PIT RR 2-1001-ses E-4 1 C 16 CK sA e d CT-1 -lCS J-2
, ------- ____ - - __, _. .------- ------- .------. ------- .=_ 2-1001-164 A-7 2 a na ct. no osc o of 'oP 125 VR13 '-
-_ __. --- ------- -------- - a. _. ----- _ -- -- _- ___
A-2 2-1001-16s 2 a Ho osc e 2-1001-18A
=- -
la cf. af oP 125 VR13 C-6' 2 a 3 GA Mo C o&C BT OP 17 VR13 2-1001-18a C:3 2 a 3 CA , Mo C O&C DT OP 17 yg13 2-t001-19A s-a 2 a- la cA Ho o o of CS 125 J-6, VR13
=______---- . _ ___--- . - - - - - . ------- -------. - _ - ------- .------. ------- .----- . -- -------- ---------. -----------------------
2-1001-198 B-2 2 8 18 CA Mo o o HT CS 125
------------- _ __ - . - - - - - - . ----- . ,- = ------_ ---- -- .------_
J-6, VR13
...---- . ...--_ ---------. - ---- _= ---
AT-1 RR 2-1001-20 B-3 2 A 3 cA Ho osc c at or 23
-. . ----- . - - - - - - . ... ------- ------_ .-----_ .------_ ------- .------ . .--- ----- VR13 ....
oRouP 2==--- Isol. =- - Arrow -
o.. . ?. .w Ow
~
INSERVICE TECTING PROGRAM ' ISI- CL ASS 1. 2. & 3 VALVES . UNIT .2-QUAD . CITIES NUCLEAR POWER - ST ATION SysMas F 6 IS etwissest - Bett FASE pastuuht senat asseovAr. Icontneassol M -91 sh.1 2 9/17/84 11 oi 36 r i J t g j l b y ty p At-1 an l$ q ,
~
2-1001-21 8-3 a 3 oA' Ho - osc c, at .or ,,25 VR13 caout 2 IsoLATIoM
---.2 . --
2-1001-221 , E-8 2 C 1 Ilv SA c o CT-2 5V
--.-- ----- ...- L - - -- - - - . . . . - -__ ___ . . . - - - ------- . . . . - - , --. - - - - . - ..'.....-----.4---------
2-toot-22a - - E-2 2 c 1 av SA C o Ct-2' 5Y - - __= __--.- = -
= ...-_----.; .--.-
AT-1 am 2-toot-23A E-6' 2 A 10 OA Mo c c_ at or 15 VR13 .
-- .2---. ---
----. _ - - a --
At-1 an ! 2-tool-23a E-3 2 A 10 on Mo e c at ' ,e o 15 VR13
-- ___ - - -. - - - - - _ . - - . = - - --
__7 AT-1 ha . 2-toot-26A. . E-5 2 A 10 on no e c. at .or 15
- __ _ _ . - - _ . ------- . __=---- . . - - - ------- .-----.- .._ . _ -... _VR13 -
. - - _ - - - - - - - - _ _ = - -
At-1 am 2-toot-26a E-4 2
.A 10 ca
------- .=-
no c
._=__=
c. at .oe
.15 VR13 _
to i' 2-t001-2ea 2 a 16 ct. No o o at
- cs
. J-7,VR13
.-- ..A~.fl.- - . _---- . _ =.--. . _.. . - -- - - _ _=_---. _
'a 2-toot.2em' E-3 2 16 on. : Ho o o at .cs 90 J-7,VR13 i
_=-_ _ _ _ = _ At-1 mm 2-toot-36A 3-7 2 A 14 on. . een c osc at oe 40 VR13 i At-1 lIn 2-toot-36a'
'_ .. ....-3D 2 .A I4 ot. No e 06c at or 60 VR13 - ----- .__... _ _ _ _ - - - _ . . . - - _ _-- ....s.-- -- ._
_ . ..-- -- . .---.-- . ~___.....
, .. AT-1 am 2-toot-37A: -E-7 . 2 A 6 GE. Mo C o&C at he 60 VR13 i AT-1 .am 2-1001-37a D-3 2 A 6 on Mo e osc at or 60 VR13 i
. --. -=_ -
. . . . . - .----.. . = _ - , - - . . - - -
-----.- . _ , - .__ _ = 4- ______
2-1001-34A AT-1 RR
- E-7 2 A 16 CA MO C 10&C BT OP 125 VR13 *
.---------... ..-- .~------ ------- ------- -----.. ------- ------ ------ .-----. ------- ----.-- --- :---- .---------------------
2-1001-34B E-3 A 16 AT-1 RR 2 CA M0 C ,
. O&C BT OP 125 VR13 i
e i
o -. ;% P INSERVICE TESTING PREGRAM STSNM Orus % ISI - Cl. A S S 1. 2. & 3 VAI.VES OUAD CITIES NUCLEAll POWER STATION
. F 6 IS MVIS1011 - BAlf UNIT PAst-2 RESIGUAL ptAt ItpeOVT.L ICONTINUED) 9/11/84 12 or 36
~
M.al sh. 1 2 4
}l l Y l h !Y.Y N / p E~/
2-1001-33A E-5 1 2 16 OA N to un
....._____.__ ....__e. ....... . . . . . _ _ . ....... ....... .....- ....... ........
....___ . . . . . . . . ....... .......... .........___...l.........
2 1001-33B E'4 1 E I- GA N 84 NA 4'. e ,
- - I
, ., - 3 v
i i ,. I a A a
~
l s I5 0 0
- e
- 1
- f-
/
q 4 0 7 INSERVICE TESTING PROGRAlWI UNIT :2
- 1. 2. & 3 VALVES
@ t-win Edison
~
ISI- CL A SS QUAD CITIES NUCLEAR POVf EFI .ST AtlON . SYSIIM F 618 1 htvisI001 - SAtt PAGE e assIDUAI. HEAT REMOVAL (CONTINUED) II*SI Bh* 2 2 9/17/84 13 or 3s VAtVI leuMelR [ attiiAK5 t - 4
.....:- ....... ........ ....... . . . . . . . - . _.... ....___ ....... ....... ........ ....... ......... .....__..___...a_....... l 2-LOO 1 2A g. c 12 CK , sA c o cT-1 OP
. . . . . _ _ _ . . . . . . ....7... .__3- _... ...____. ....... . . . . . . . . ....... ....... ....... ....... ....... ....... ...... __ .......... ___...____...
O CT-1 OP '. 2-8001-23 B-7 3 C 12 CK SA C
- 2. lool.2C D-2 3 C 12 CK SA C O CT.1 OP
......___ ... ....... ....... ........ ....... ~
2 1001 20 82 3 C 12 CK- SA c d CT-1 .OP l 2-toot-5A .E-6 3 a 12 ot. m c o&c 07 or , 90 VR13 h m c O&c DT . OP 90 VR13
=
2-toot-5s E-3 3 12 O t.
- . . . . . . . ....... ....... ....... ._..... ........ .s..... .._...__._ .___....__....____.__...
- 2. LOO 1-lA C-6 3 E 14 CA H to NA 2-toot-le B'- 6 ~ 3 E 14 CA - H th NA 3-toot-Ic C-3 3 t 14 cA H to NA .
.........____ ........ .___... .....__. ........ . _ _ . . . . .....__ ....... ....... .__.... .a___... ....... ....___... .__...........,. ........
- 2. loot-ID 3 E 14 GA H to NA .
...........;. . $. .-). ... ...__.. ____... ............... ....... . , . . . . . ....... . ... ___. .............. ...___._.
2-toot-3A D-7' 3 E 12 GA H ID NA
............. ....... ..__ .. . . . . . . . . ....... . . . _ _ . . . ....... ....... .....__. ....... ..'._....l . ..... .......... .............. .... ....
2-toot.3a B-3 3 E 12 cA. H in NA , 2-1001 3c D-2 3 ,E 12 GA H ta NA
............. ....... ....... . . . . . . . . ....... . . . . . . . . ....... ....... ....___ ....... ........ .a..__. ,......... ....__... _........._...
2 1001-30 B-2 3 E '12 GA H ta NA
...........a. ..a..... ....... . . . . . . . . ....... . . . . . . . . .......
2-tool-2otA E-6 NC E 14 HTF H ED NA E-3 2 8001-201a Nc E 14 uTF H ID HA __..... . . . . . . . . . . . . . . . ....... ........ .....__ ....... ..______ ....... .;a . . .. . ....... ....__.... ..............y.... .... e e 6
- 1. - -- - - -- . . - -
A
-y
, p .
INSERVICE TESTING PROGRAM Or a Misen ISI- CL ASS 1.~ 2. A 3 VALVE 3 ' UU S2 OUAD ClilES NUCLEAR POWEH STATION P 6 le MVisteel - DATE PAGE , SV5H&E STANDBY LIQUID CONTROt. N-82
- 2 9 / 1 7/ 84 14 of 36
] r y/ / hey o l} q -
C 1.5 CK SA C O cr.1 Cs/RR VR-5 2 1101-15 C-3 1 i ............. . . ..... ....... ........ ....... 2-1101-16 C-3 1 C 1.5 CK SA C O' CT-1 'CS/RR V R-5 g d C.4 2 D 1.5 EMP C DT RR . 2.llO6A ........ ....... ........ ...... ........ .......... . . . . . . . . _ . . . . _ . ......._. g 2 11068 D-4 2 D 1.5 EXP C , o DT RR , 2-1101-43A D-6 2 C 1.5 CK SA C O CT-1 OP g ............. ...a... ....... ......., ....... ........ ....... . . . . . . . . E-5 2 C 1.5 CK SA C 0 cr-1 OP 2-1101-43B. ....... . ...... .......... ........................ 2 1105A C-6 2 C 1.5 RV SA C O Cr-2 ;5Y ,, 2-11058 D-5 2 C 1.5 RV SA C O cr-2 5Y
....... .._..... ....... ....... . ..... e...... ._........ ........................
E-fl GA H ED NA 2 1101-4 2 E 2.5 2-1101-8 D-8 2 E 2.5 GA H tr NA
. . . . . . . . ....... ........ ....e.. ,...... .4..... ........ .......... ............... ........
2 1101-3A D-7 2 E 2.5 GA H la NA
........ ...a... . . _ . . . . .. .... ........ .......... ........................
............ ......L ....... ......., ....... ........ .......
2-1101-38 3-7 2 E 2.5 GA H la . NA
. . . . . . . ....... ........ ....... ........ ....... ....... a... .. . . . . . . . . .. .... ........ .......... .............. ... .....
2 1101 10 D-7 2 E 1 GL M If NA 2-Ilot-2A D-5 2 E 1.5 GL M 00 NA
........ ....... ........ ..._ .. ........ ....... ........ ....... ........ .......... ..............e 4.......
2 1101-28 E-5' 2 E 1.5 Ct. H lh NA
....... ....... ........ ....... . . . . . . . . ....... ........ ....... ....... ....... ..a..... .......... ........................
2 1501-22 C.4 2 E 1.5 GL. H LC NA 2 1801-98 D-4 2 E 1 GI. H 8.C HA
....... ........ ....... . . . . . . . . ....... . ....__ ....a.. ....... ....... ........ .......... ...............a........
GL H ID MA 2-1101-23 D-3 2 E l.5
...s... ....... ....... ........ .......... ..............i........_
2-1101-1 D-2 1 E 1.5 Gl. H ED NA
. - _ _ _ _ _ _ . _ _ _ _ _ y
.a . $
%m INSERVICE TESTING PROGRAM gh ISI- CL A SS t. 2. . & 3 VALVES UNIT ,. 2 OUAD CITIES NUCLEAR POWER STATION STSIEM F 6 it REVIS3000 - SAI[ PAGE kI WATER Ct.EAN-UP - M-se. 2 9/1'l/84 15 of 36 .
'anut ma .
f ll g$$' $$ f: ? neunnus AT-1 Rit 2-1205-2 B-4 1 A 6 (2A HO O C . It? OP 30 VR13 GROUP 3 ISOE TION PIT RIL AT-1 'R R VR1 'l 2-1201-5 B-6 1 A 6 rlA MO O C~ BT O,P 30 GROUP J ISOLAftON .
==__ :_.. --. - ---- .----_
l S 9 a
- g 6
9 P e O s 9 e
# 6
~
4
? O i
s s .. c _ .a INSERVICE TECTING PRTIGRAM : [h ISI - CL ASS 1.2.13 VALVES UNIT - 2 OUAD CITIES HUCLEAR POWER S T ATION
- ^ -
sesub , eam. newsme _ set nst REACTOR CORE ISOt.ATION COOT.ING M-89 2 9/17/84 16 of'36 i l l t yl/hqq r l} q -- AT-1 RR , , 2-1301-16 B-2 1 A 3 GA HG O C BT -OP 25 GROUP 5 ISOt.ATION PIT RR VR13
- AT-1 RR l
2-1301-17 a 1 A 3 GA HQ O C BT OP 25 VR13 GROUP 5 ISOLATION
=- -__._
I ' AT-1 R2 - 2-1301 D-2 NC AC 2 CK SA C C CT-1 BR VR-9
- =- --
._-____. _ _ _ _ _ . __= ___. _ _ _ _ _ _ . __
AT-1 RR 2-1301-41 0-2 NC AC 8 CK SA C , C CT 1 RR , VR
. _ . ---___ ___ _ _ _ __ _ _ .______ ..______ .___-B .-
---_- - - - - - - - -_=
AT-2 RR
- 2-1301-15A S-2 1 'AC .5 XFC SA O C CT-1 'RR VR-9
- ___. _______ ___ .___-- - ==
AT-2, RR 2-1301-158 B-2 1 AC .5 XFC SA O d CT-1' .RR VR-9
=-
O e f i-4 4
+
d
- e h
i
e % 9 IN^^ERVICE TE3 TING PREGRAM 0 c.-u [dnen ISI- CL ASS 1. 2. & 3 VALVES . UNIT - .2 OUAD CITIES NUCLEAR POWER STATIODI sys1EM ' F 6 le atvise001 - SAIE FAGE cost SPRAY M -7s 2 9/17/84 17 of 36 l t t i if / / fi y ry
~
~~ / / "-
/ o l ,.? r:/
(.'. T- i CS 2 1402-94 c 1 C to cK SA C O, PIT BR J-2 CF-1 cs
- 2-1402-98 C-4 1 c to cK sA C O PIT RR J-2 i
-~ _ ....--. ...= . ..... . _
....... .----... u. _ -_ _ _
2-1402-25A c-2 a 10 CA HO C 1
.O BT OP 15 VR13
.a'--------- l' c-s 2-1402-25n 1 m 10 GA H0 c 0 DT '15
[OP VR13 --
- --..=_ ___
2-1402-24A B-2 2 a 10 CA HG O O, BT ~OP .35 _.= - - - . - - . _ _ _ _ =- . _ _ _ .-... . -- ...._.- -- . - - VR13 2-1402-24B B-5 2' s 10 GA HG O O. BT "0P 15 VR13 2-1402-28A
--- - ___=_
c-9 2 c 2 av sa e o. cT-2 SY
. - - - - - - - =- ------. ....--. --...- . - - . . . - - _- _ _..
2-1402-2ea D-6 2 c 2 av sA c o cT-2 5Y
-- _ ._ -=_ . - -
-_--... .-. .... .-- ---=-- - ---.- _- . -
c-e 2-t402-3ea 2 a 1.5 GA HQ O C. BT OP 12 VR13
--------- - - - - - . . . -. ==_ ........ ..--...
. - - - . . . - - - . _ _== __. ._ __.- -- ._-. _ -.--- =-__ ___
2-1402-3sa - p-7 2 a 1.5 cA Ho o C BT oP 12 VR13
=---- ___
_ .=_ '_ _ _. : ____ _ __.--. a--.. - 2-1402-aA c-9 2 sex o
.. ca 12 sA
.------. .-- c/tc
- . _ . = _
cT-t s oP 2-1402-en s.-6 2 ca 12 sex sa c/ta o- cT-1 os' .---
....... .r...--. --
AT-2 RR 2-1402-3th 10-3 1 Ac .5 XPc SA o c cT-1 RR VR-9
.-----. ........ . . . - - - - . ...--- ... - - .- . . . _a----
------ =_ . - =__ ...
AT-2 BR 2-1402-3ta D-4 1 Ac .5 xPc sA o c cT-1 RR , VR-9
=-- ....--........----
2-1402-6A IM3 1 E 10 CA H la NA _=- . - - . _ ==---- ---...- ....----
= ___=- _--... . _ _ =
2-1402-68 D-3 1 E 10 GA H to NA
-.A---- - = - __ _ _ _ _ - = . _ _ .
2-I402-2A G-7 2 E 12 GA H 84 NA ',
. _ = . .. ---- .--.... .. .--.--- .. .--..-----
t t
p .% '
-8 0r m INSERVICE TEOTING PROGRAM -
gw ISI- CL AS8 1. 2. & 3 VALVES . UNIT - 2 OUAD CITIES NUCLEAR POWER S T A TIO64 SysMM F 6 IS MVIS10N - SAIE PAGE la of 3{ CORE SPRAY { CONTINUED) *H-73 2 9/17/84 l t yl /b geyo l} q - 2-1402-2s C-4 2 E 12 GA M If NA .. 2-1402-34A G-4 2 R 18 UTF M la NA . __ _ _ . ._________ ___ _= _ 2-1402-34B E-3 2 E 18 8TF M 14 NA ;
== - __ ________
2- 402-4A A-a 2 m e on. no e e at ce so VR-13 ;
~ -
2- 402-4s 2 a a on. No e e eT oe so vg_ i3 _ _ . c __7 2 1402-13A E-9 ' 2 CE 1.5 scK SA/M c/th ;O cT-1 *0P. ____ __ _ _ = 2-1402-13e E-6 2 cE 1.5 sex sA/M c/im *o cT *0P_ ___
~
__-g_ _,_-__ _ _ _ _ _ - ___ e
*0 PEN STROKE. VERIFIED BY PUMP TEST.
e 4 e e . O i e b i ;
r d' .5 INSERVICE TEOTING PR GRAM
@r_m [h ISI- CL ASS OUAD CITIES NUCLEAR POWER S T A TION
- 1. 2. & 3 VALVES .
UNIT - 2 sysnes t 6 le MWestost - BATE PAGE ; PRESSURE SUPPRESS!oN M-76 2 9/17/84 19 of'36 i t 1 j r y;thqq r /p q - AT-1 'RR . . 2-1601-21 C-6 NC A 18 BTF Ao C C, BT OP 10 VR13 otour 2 ISOLATION FST OP
.... .. -_...'.. .. =. _- . . , - __ _
. AT-t' RR .
2-1601-22 C-6 NC A la aTr Ao C C DT 'OF 10 VR13 oRouP 2 ISOLATION __ . .... __ -. -... _ ._ .__.... -__-_.. . - - . . . - - -- ... ..? __.-. _ . AT-1 'RR ! 2-1601-55 A-6 NC A 4 GA no O C RT OP 10 VR13 croup 2 IsoLATIoH i __.__ __= _ AT-1 RR 2-1601-56 o-6 NC A la aTr Ao O C" or or 'to VR13 ORouP 2 IsoLATroH ' FST OP . ! t AT-te SR l 2-1601-57 C-S HC A 1 GE. No O C BT 'OP '15 VR13 croup 2 1 SOLATION l FST -
.OP '
=== -
= -
. .._..-_ __.a_-__- ___
AT-1 BR .. 2-1601-58 p-7 NC A I ca. Ao C C' BT ' 'oP 15 VR13 croup 2 Isot.ATIoM FST OP
.... .._.. . __._. .e _
.._ ......._. 1_
AT-1 RR - 2-1601-59 D-7 NC A 1 Gt. Ao o C BT OP 15 VR13 ORouP 2 IsotlATIoH
. FST OP
_ __ _ _ _ ------. . . . . _ _ .... _ .. .- . . . _ . . .__. . . =*= - _== =__. ..___ ._
.
- AT-1 RR 2-1601-20A' D-9 HC A 20 GTP Ao C O&C BT CS 10 J-8,VR13 .
FST OP
- _...- . ... ..._ . . = = -_ _
AT-1 RR , 2-1601-314 h NC AC 20 CK sA C O&C LT OP *
. _- .... 9 --._ _ --
____-- --- z-- - - _ _ - AT-1 BR , 2-1601-20s E-9 NC A 20 BTF Ao C O&C BT CS 10 J - FST - or *
..-8,VR13
- e. -m 5 INSERVICE TECTING PROGRAM OP-.a E6 sea ISI- CL ASS 1. 2. & - 3 VAI.VES OUAD CITIE S NUCLE Aft POWER STATION UNIT 2 sistin F 6 is - afvtsame - SAIE PAGE PRESSURE SuPPRESSIOtt (CONTINUED) M.'J 6 2 9/17/84 20 of:36 f r gjjhqq r fj q -
l AT-1 BR 2 1601-3IB' E.9 sec 'AC 20 CK SA C ,O&C CT-1 *OP AT-1 .RR . 2-1601 23 B.3 NC A IS STF AO C C- ST OP 10 VR13 croup 2 ISOLATION FST OP
............. ....... . . . . . . . . ...---. .------ ....-.. . ..-.. ......- .....-- .....L- ..----- ...-.-.. ....-....- ........-------. -...-..
AT-1 RR 2 1601 24 s-2 NC A 18 BTr AO C C BT OP 10 VR13 croup 2 ISOLATION FST OP
...-............-... . . . . . . . ....... .......~....... . -.... ....... ....... ........ ......- ........ ..--...-.. ..... -.. - ............
AT-1 -$R , . 2 1601 60 - g'- 7 NC A 18 BTF AO C C' DT OP 10 VR13. ORoue 2 IsotATION FST .OP AT -RR 2 1601 61 F-2 NC A 2 GL AG C C DT ~OP 15 VR13 croup 2 IsosiTIOu FST ,DP AT.1 AR 2 1601-62 g-2 NC A 2 CL AO C C- DT OP 'Is VR13 GRour 2 ISOtiTION , rST .Oe
............. ...-... . . . . . . . ....... ....... ........ ..-.... ....-.. s...... . . . . . . . . -...... ........ .- ............................... .
AT- 1 . RR 2-1601 63 A-2 uC -A 6 etr AO C c' :7 Oe 10 .VR13 oRoue2IsothTron FST OP
............. ......a ....... ....... ....... ........ ..-.... ........ ....... ....-... ....-.. .e.'..... .......... ...............h........
AT BR 2 8803 C-6 NC A . 2 CL AO .O O- BT O. P 10 VR13 oRour 2 ISOLATION FST OP
.......-..... . 4.... ....... ....... ....... ........ ....... .. -.... ....... . . . . . . . . ....... ........ .......... ........................
A7 1 BR 2-8004 0-6 NC A 2 GL AO O C'- DT OP 10 VR13 croup 2 ISOLATION FST ,OP AT.1 'liR , 2 800lA C.3 NC A O .5 CL AO O C' BT OP 10 VR13 croup 2 ISOLATION FST OP
............. ....... ....... ........ ....... ...-.... ....... ............... .....-.. ....... .......- - . . . . . . . . . ..............ls........
l
~
# =% k.
INSERVICE TEOTENG PR$ GRAM O P_.na gi . ISI - ct. A S S OUAD CITIES NUCLEAfl POWER ST ATION
- 1. 2. & 3 VALVES UNIT - 2 sysasat P & le RtvisseN - SAIE I PAGE . . 6 PatssuRe suPPatssioet (COtiTINUED) H-76 2 9/17/84 n of 36 !
6 1
/ / y/ihqq s // q +.
\
AT-1 RR 2 88013 D.3 sec A 0.5 OL Ao o C RT OP 10 VR13 oRouP 2 IsoLATIow FST OP
, AT-3 RR 2 6801C D-3 NC A 0.5 GL Ao o C BT OP 10 VR13 ORoor 2 tsoLAfroN FST OP .............. ....... ........ ....... . . . . . . . . ....... ....... ....... ....a.. ........ ....... ........ .......... .......................
AT-1 BR . 2 8801D E.3 NC A O.5 Ct. Ao o C BT 'or 10 VR13 ORou? 2 IsoLATIoM FST OP
.............. ....... ........ ....... . . . . . . . . ....... ....... ....... ....... ....... ....... ........ .......... .............aq........
. AT-1 RR -
2 8eo2A ce) 30C A 0.5 GL Ao o C BT ~ oP 10 VR13 cRoGP 2 ISoLAtIoM FST DP AT.1 BR
..............g........
2-8802a D.3 NC A 0.5 Gt. Ao o C.
- DT OP 10 VR13 oRour 2 ISoLAftoH FST OP AT-1 RR .
2-8802C D.3 sec A 0.5 GL An o c nT OP 10 VR13 oRoGP 2 ISOLATION FST or AT.I RR . 2 8002D t.3 NC A o.5 Gt. Ao o C BT OP 16 VR13 cRour 2 tsoLA'IoM T FST OF , 2-1601 32A t-2 tec c la ex Ss c o&c cT-t or 2 16al.32a 22 He c la ex SA c o&c cT.I oe 2.tsot.32c t.2 NC c la cx sA c osc cr. ce
.............. ....... ........ ....... . . . . . . . . ....... ....... ....... ....a.. . . . . . . . - ....... .a...... .......... .......................
2 1601 320 t1 sec c la en sA c osc cT-1 or 2-1601 32E E*2 NC C 18 cK SA c o&C cT.I. or
- e
. 0 h
9 syslaag Oe- % INSERVICE ISI- CL A SS QUAD CITIES NUCLEAR POWER STATION TEOTING
- 1. 2. a 3 VALVES PROGRAM F 6 it REvisself - BAIE UNIT - 2 PAGE i>
raessume suernesstoel (CONTINUED) N-76 Sh* 1 2 9/17/84 22 or.36 j t 1 I 2-1&ot-32e -s l He t c g j / h q q e f) q --
. __ _- 2__
la cK sA ose cr-1 oe l' _. _ - _.. _ _ = = . . ____. -______. _,_. -.... . ..___ - ;__.___ .-- ____ .__ __- 2-t&ot-33A .t-7 sec e as cK sA e osc cT-1 oe 2-1601-33a E-7 NC C 18 CK SA C l ----- - _ . _ _ . O&C cT-t oe
. = - -_ ._____. _______ .
== _ __ _ ---
2-t&ot-33c s-7 sec c la cK sA e ose cT.t oe
. . . , . _ _ __ 1 - _==___
! 2.tsot_33n e_7 He c is cK sA c ose cr_1 oc i . . . - - -
......___ ___.4_____-
2-t&ot-33e E-7 Nc c le ca. sa e o&c cT-1 oe
=
=_ .. __. . _ _._ __ ___ ___.__. __ --- - ,
2-1601-33e z.7 sec c la en sa e osc cT-1 or 2-220_atA E4 He c 1 cx sA c OE cT-1 'cs _. ___ _ _ . - = __.___. . ___..+ _ _ - __ va-14 2-220. hts _=a--- c z.4 sec 1 en sA c o cr-1. cs va-14 _ _ _ _ __ __= _ 2-220-ste t-4 sec C 1 cK S4 c O __ _ ~- cT-1 CS VR-14 2 220.stD K-5 NC C 1 cK SA c O CT-1 CS VR-14 2-220-81t E-5 __-- -_ ..-= __._ * - = C 00C cK O'
= = - -
1 SA C cT- t
- cs VR-14 z.. . . . . _ _ . _ _ _ . - __- ____ _.
2-220-105A-D-4 NC 'C 8 CK SA C 0 CT-1 US VR-14 2-220-1058. E5 i NC C 8 CK SA C 0 CT dS VR-14 2-220-105C - E-5 NC C 8 CK. SA C 0 CT-l CS VR-14 2-220-105D D-5 NC C 8 CK SA C 'O CT-1 CS VR-14
.._________.- _____.~...___ _____.. ...____ ...__._ ____... .__.... _ _ _ _ _ _ . ...___ _______ _______
2-220-105E. C-5 , NC C 8 CK SA C 0 CT-1 CS VR-14 9
l..
.- ' i- .
-M I
.1 c- - _ ---ga INSERVICE TESTING PROGRAM - MT -
~2
~
ISl- CL ASS 1. 2. & 3 VALVES O_ Unen QUAD CIT IE S NUCLEAR POWER ST ATION P 6 le Mvismi - eME FEE 2 9/17/84 23 or,36 - stsitte H-- 81. utcu PREssues LOOLANT INJECTION
/ / gj /hqqs l} q -
AT-1 RR ' O O&C BT CS 50 J-5,VR13 GROUP 4 ISOt.ATION A 10 OA HO ! 2-2301-4 C-9 1 PIT RR
. . . . . . _ _ _ ...= .--. ....-
~_-_.._ _
AT-1 RR O&C BT CS 50 J.5,VR13 cRooP 4 asotITION A 10 CA HG O 2 2301 5 3-10 1 --
= _
c4 HO C O af OP 25 VR13 . 2-2301 3 A-6 2 e to
.. ..- - - - -. _. --.. 2........
*PER MANUFACTURER D 16 R.'D SA C O
', 2 2301-68 A-6 2 . RECOMMENDATiOH
._ . . . . . _ ~
? .._ -- = .- _
C O * * *PER MANUFACTURER A-E 2 D 16 RPD SA 2-2301-69 RECOMMENDATION 6
=.
1 _-- Br OP l' 8 Gt. AO O C* FST OP 10 VR13 2-2303-29 s-9 2 a 1
' VERIFIED OPEN AT-1 RR C O&C CT-1 OP/RR* VR-8 DURING PUMP-TEST ,
2 AC 2 CK SA 2-2301-34 p'- 7 AT-1 -RR *VERFIED OPEtt { O&C CT-1 OP/RR* VR-8 DURING PUNP 2 AC 24 CK SA C _. _ .._..__...'. TEST _ . _ - 2-2301-45 S , __- &8
.VR13 l 120 OA M0 C O&C BT -OP 2 2301-35 E.7 2 R- 16 _
16 CA M0 C O&C ET OP 120 VRl3 2-2304-36 E-9 2 a
=- ...=
O O&C 51 7 OP 120 VR13 . te F-2 2 a 16 CA MO 2-2301-6 ..... ....... . - -____.. . . . . . . __.... .._____ _ - - . _ _ - - - -.4..... __ -..... - - - -....... .._..... OP C 16 CK SA O O CT-1 ; 2-2301-20 E-2 2
....._=__ ..... _
2 8 4 ct. M0 C OEC BT OP 26 yg g 3..... l { 2-2304-14 C-6 ..____ _ _ _ _ _ _ ._.. . _ _ . . ....... -
~- - - - - ,
- V R-7 *SEE VR.7 !
C 0 CT-3
. . - -. CK SA -
2-2301-39 E-8 2 C 16 ........ . _ - _ - _ - . _ - _ -...__ --. ,.......____...
- =_ --=...... ... . _ _ _ . _ - __
+
C 4 (7 SA C O CT-t Op*e
- 2-2301-40 D-7 . NC
- * *0 PEN STROKE VERIFIED BY PUMP TEST 2
'r.uum'wirwrr. m e m n m y . 7-
INSERVICE TESTING PROGRAM Or-m Systsel insen - 181 - C L A S S ~1 . 2. & 3 vat.VES
' QUAD CITIES NUCLEAR POWER S T A TION F 6 se elvessess - eAvg UNIT PAst
.2 NIcss Pressure COOf. ANT INJECTION (CONTINUEpl M;-87
- 2 9/17/84 24 of 36
/ r yl /h qq s _
l} q - 2-2301-s D-6 2 a 14 CA HG C O BT OP 45 VR13 PIT RR 2-230't-7
~
D-6 2 C 14 CK SA C O CT-1 CS - J-2 .
----.. .. _ ------. =- _
---.-- - - _ - - - = _
.------ - . ._ __=_._ . _ . -
1
- VERIFIED OPEll 2-2301-74
- b-8 2 CE 12 SCK SA C/ID O CT-1 .OP* -
DURIssG PUMP TEST
-7 = =_---- .--------- =- _-- -- . = - - -
AT-2 RR N 2-2301-26 D-9 1 AC .5 XFC SA O C; CT-1 RR VR-9 ' i _ = - . ..--... ------- .------ ......----. ----------- AT-2 RR t 2-2301-27 'D-9 1 AC .5 XFC SA O C' CT-1 DR VR-9 _------ -; . . - - . . =- .. - - - - = _ _ _ - _ --=--- 2-2301-22 b'1 2 2 16 04 M LO NA _ _ _ - - . . - - - - - _- -----. - - - ....- i------- 2-2301 F-8 2 E 16 BTF M LO
.------. ----s-- ------- .. ..=-
NA __==--->- -- 2-23o1-71 b-7 2 CE a sCx' sA/n, C/to O- CT-t sea , *vERir:Ep opens . DURING P'JMP TEST
-------- ------- -------. ------- .------, ......- ------- -e== __
------ ------------- d--------
2-230t-s D-s 2 a 14 c4 sei o O at 'De 4s' VR13
.----- .. ---- -------- --- _- __---=__- ---
2-23oi-10 a-5 2 e is on. m C ;C- at Oe 6o vai3
---- -=== _ _ = _ - ------. ------- .-
,4----. ,--------. ------------ =- ==__ j i
( 1 O V o 1 O s l, l (' '! f
3_ INSERVICE TESTING PROGRAM ;
@P_i gg ISI- Cl ASS OUAD CITIES NUCLEAR POWER S T ATION
- 1. 2. & 3 VALVES
+
UNIT - 2 SYSitat F 6 IS Aivl$ son - BAIE FA6E l MAlid STEAM 'M -60 .sh. I q 2 9/17/84 25 of.36 t =
/ l y/ / h q q r l} q -
AT-1 RR
*. BTP OP i !
- BT CS S J.1 i 2-203-1A F-4 1 A 20 Ota Ao O C. FST CS VR13 oRour 1 ISOLATroN i PIT BR ,
- - . - _. .. . .. ...--. . . = = ...... ....-... ....... . . . . - - - - --..... . . . - - - -
AT-I RR ' BTP OF . , ist CS 5 J-1 GROUP 1 ISOLATION 2-203-1B D-4 1 A 20 ob Ao o O FST .CS VR13 l'I T RR ,
, AT - 1 -RR IITP - OP .
BT CS 5 J-1 GROUP 1 ISOLATION 2 203-lC C-4
- 1 A 20 Gl. AO O C; FST .CS VR13 Pl? RR .
= _ _ - _ _ :-- - --.
. . . . = . ____== .. ....... ....... ... . . ...----. ... ... ... _- . . . . . . . ......----....a.----- ..
AT*l RR
". DTP DP '
BT CS 5 J-1 GROUP 1 IS6thTION 2-203-lb h-4 1 A 20 CL An O C' FST - CS VR13 i PIT 1 BR _ _ _ - - - . = = . . . . .... .. . _- .... = . _ ..... . ... ... ___ AT-l' '. B R . 2 220-1 3-4 1 A 3 GA MO C C* Ist OP 35 VR13 oRour i Sot.ATION
- = - - - - .--.... . . _ _ . = = _ . ... --. ... .... ... --. ..--. . ..G.. - . . . . . _ __ . - - . . . . . . - - ----...... ....-..----... ___
DT I I VR-1 *SEE VR-1 2-203-34 P4 1 pc 6 ERV/SW PS/SA C O, CT-2. , RR VR-2 '
. _ _ ... ..----. ....... . . . = _ _ = - ........ . - - - - - . ... _ -.... ........ ......:
BT ~*
- VR-1 *SEE VM-l .
2-203 38 O-6 1 BC 6 ERV PS C O CT-2 ~ BR VR-2
... _ . = . ...t.... --....- ...----. ...... . . . _=.. . .. .--- .... . .....-.. .s-.... . . . . . . .. .....-- ....--.....--.-.........
2-203-3C BT :*
- VR-1 *SEE VR-1
- C-7 1 BC 6 ERV PS C O- CT-2 RR VR-2
-----...... . ......= _= ....--.. ....... ....... .-- .... ----__. ....;.. .---... ...---- . _ . .
DT **
- VR-1 *SEE VR.I h
y 2-203-3D 8-7 I .DC & ERV PS C O; CT-2 .RR VR-2 s . . f
.}
e ende ' f
=
INSERVICE TESTlNG PROGRAM systiat O %. gg ISI - CL A SS OUAD CITIES NUCLEAR POWER S T ATION
- 1. 2. & 3 VALVES P 618 atvissau - satt lT PAst
.,2
- seAIN steam (CONTINUED) -H -60 sh. 1 2 9/17/84 26 of 36 j i gl/ hey r l} q -- h BT *
- va-1 2 203-3e 0 1 ac 6 eav es e o cT an *
.__-2 - va _2____
i r-e c
-= .._____ _- _____
sa e o
'n-_.. ._______ ..__S_E_E_.V R- l _________.
=--
2-203-4A 1 6 sv. ct-2 ma- va-15 _ _ - - _ - - - _ -- . _ _ - - =______ . -- _ _ _ _ _ . .____._ _ _ - - - - c sv c 2 203-4a e t 6 sA o et-2 ma va-15
... ._ _u____ .
2 203-4e c-5 1 c 6 sv sA e o et-2 an -
= ._ _ _:. .
-- . _____ . - - - . __= -- _____ _______ a:.____ -
va_.15 2-203-40 a 1 c 6 sv sA e o et 2 na va-15 m _5__
.- . _ . = = _ - ____ -_____. __---_ ... ______ --
___.______n_____ - 2 203-4e F-e 1 c 6 av. sA e o. ct-2 ,
'It R VR-15
____-- .___.___ .______ .._____. =- ._____ .___ _______ 2-203-4r > o-5 c 6 sv sa c o. 1 et-2
. te
.______ .-- va-15
- --.-- _ -- - _==____ ___.___
2-203-40 c_5 1 c 6 sv sa c 0; et-2 - na va-15 __ __2.___ __ - - --- _____ ._____.- -
.. _______. ___ ..__. _______ . _ _ _ _ _ . . ..L_______ -- - =-- _- - .__
2-203-418 B-5 1 c 6 sv ~ SA c o 07 - an Va-15 __________a_. .__s___ _
-- ____ .______. ____.__ -______ .______ . _ _ _ ____-2 '__. -
- e.
- b
'e e
4
*e =
+
e F
. .C t .-
4 e I
f
~ . , .
3 t.R e .nh INSERVICE TESTING PROGRAM 1
@ ' disse i ISI- C L A SS QUAD CITIES NUCl. EAR POWER S T A TION
- 1. 2. & 3 VALVES -
UNIT - 2
- susuu r6m nivmou - satt tast ~
^! 9/17/84 l 'H'60 27 of*36 MAIN STEAM l CONTINUED) sh. 2 2 I q - l 1 1
/ r gijhng > l} q -
AT-1 RR DTP OP BT CS $ J-1 GROUP 1 ISOLATION E-7
; ,? 2-203-2A 1 A 20 GL AO O C FST CS i' VR13
. = - -
PIT RR
- - ~ ~ - - -
AT-1 >R HTP OP r
. DT CS $ J-l CitOUP 1 ISOLATION 2-203-28 k.7- 1 A 20 GL AO Q C FST CS VR13 lit RR
==- . =_. _
AT-1 Rh ! BTP OP DT CS - 5 J-l GROUP 1 ISOLATION 2-203-2C D-7 1 A 20 GL AO O C. FS! CS VR13
, PIT RR
_ _-=. ..... . _
.. -- .-- - . - - - = - . .
l AT ~ I RR DTP OP DT CS 5 J-1 croup 1 ISOLATION 2-2017 2D 8-7 1 A 20 GL AO O C FST - CS ygg3 , b - ___ __-_--- PIT RR '
= .. ------ _=_ .. -=_ = ... ----
AT-1 RR { 2-220-2 E-7. 1 A 3 GA MO C C OP 35 ist VR13 GWPI I M TION
== . _ _ = = . . . - - - -
AT-2 RR 2-220-17A E-S 1 AC 0.5 EFC SA O C CT-1 RR
^
VR-9 AT-2 AR 2-220-178 D-8 1 AC O.5 EFC SA O C CT-1 RR VR-9
. . . . . . .--- .. ... _ ..... ..==__ _ . . . . - - _ _ _ _ _ = _ - . . . - - . = - -
AT-2 RR 2-220-17C - C-8 i AC O.5 EFC SA - O C CT-1 ,RR VR-9
--...-- ___ _ ---.... . . . . . . . . --...-- ........ .=_- ...... . -=___ __=_--. ....... ....... . . = - = - - . -
AT-2 R'R l 2-220-17D B-S 1 AC O.5 EFC SA O C* CT-1 RR VR-9
---....- ...--.- . . . = _. ....... - - - . . . . . ....... ---... .. .... . . . . . . ...._- _- _=_ .=.....--. - . . . . . . . . _ - ....
9
s ,~y -h-INSERVICE TESTING. PROGRAM Or_u systens - th ISI - C t. A S S QUAD CITIES NUCLEAR POWER S T A TION
- 1. 2. & 3 V Al.VES .
F 6 as afvissen - satt - UNIT rase -
.2_
. Main staan scowTanusal x-so- sh. 2 2 9/17/84 as or as
/ ! gjihqq s /$ q -
AT-2 RR 2 220-ion x-a a AC .5 .rc sa o C . cT. RR . va-9 AT-2 RR 2-220-19R D-R 1 AC .5 Arc SA O C CT-1 g'
.. ... ; .= . . . . ...
RR VR-9 i NT-2 RR 2-220-ISC C-8 ,1 ac .5 Erc sa o C CT-1 RR - VR-9 2-220-180 47-2' Ita R-8 1 AC .5 Erc St. o ,C JT-1 BR
- - - - =- _ _ _ _ .
VR-9
.4-- ..... .
~ ./
e G e6 e f 4
=
w_
, ..~. ,\
unk INSERVICE TECTING PRUGRAM
@ ca %, ISI - CL ASS 12.&3 VALVES OUAD CITIES NUCLEAR POWEH ' STATION UNIT ,2 susuu r a se afvision - natt rAst rEn:owAtta H 2 . 9/17/84 29 of'34
/ yljhqqilj r q .t - ,
AT-1 RR 2-220-58A E-3 1 AC 18 CK SA O C ,, CT-1 RR VR-3
-- . ----. . . . . . . . . __..... .- ...-. 2 .... .-__.- ...- - .'.... -..-_- - --.... _-
1 AT-1, RR 2-220-58n F.3 - 1 Ac 18 CK SA O O&C Cf- l ' hk #'
-.. ........-, L --
VR-3
..b._. .- =. = - =, _ = . _ _--....
2-220-598 r.3 ' 2
. . . . -18 . -
C
..... = _-
CK SA O C CT-1 RR
. _ ~
VR-3
= =- ..._
AT-1 RR 2-220-62A E-3 1 AC 18 CK SA O C CF-1 RR VR-3
= .--.. . . . .
AT-1 RR 2-220-628 P-3 1 AC 18 CK SA O O&C CT-1 kR VR-3
-.... .....--- --- - - - _ .= .. . . . . . . . .... . ..i.-- -
_ = = _ . .__ D 4 e 9 I s 9 I z t, ,
INSERVICE TESTING PROGRAlWI Or_m sysseal gm ISI- CL ASS 1. 2. & 3 VALVES QUAD CIT IE S NUCLl! AN POWER STAit0N r & le AEWISteel - SME UNIT PAst . , sEitv Cs Watsa 'N-69 2 9/17/84 30 or 36 6
/ 1 y / /h q q r /j-q --
2-3099-86 't-9 3 C 8 CK SA C O CT-1, OP 2-1999-06 h-lO 3 C S SA C O CT-l' OF ,
- - . .------- ------- .CK 3-3999-139 A-9 3 0 6 CK SA C .O CT-1* , 'OP . .
o 4 O
=
+
9 9 g? 1 e a 4
. l O
s 4
- 9
' s 9
_& . he, wik INSERVICE TECTING PRdGRAM - Oc gg ISI- CL A SS 1. 2. & 3 VALVES OUAD CITIES NUCLEAR POWER STATION WIT .2 IV8 tite P 6 le NW1510tl - BMI PAGE ptESEL CENERATOR STARTING AIR (SERVICE AIR SYSTEM) ' M-72 2 9/17/84 31 or.36
/ r y/lhqq r l} q -
f 2-4699-121 E-9 NC E 1.5 CA M LD NA
... _..... . - - ....L.. . . . - - . . _ . .a.
2-4699-122 E-9 NC E 1.5 CA M ID , NA
- l' 2-4699-225 D-R lec E 1.5 BALL M ID NA i 1 ... . _. ._. --- _- ...... .. -- -_ . . . . . . . -_ _ _-y 2-4699 123 E-9 NC C 1.5 CK SA .C O CT-1 OP -
2-4699-196 E-9 NC C 1.5 CK SA C ,O CT-1 OP - t 2-4699-226 D-3 NC B 1.5 CL AO C O BT OP . I,TRTI--- - i
-- . . . . fjt,1,6 ___ ; }
( I i O e 4 9 i l ,
INSERVICE TESTING PROGRAM
@r_a.6 % ISI- CL A SS OUAD CITIE S NUCLEAll POWER ST A TION
- 1. 2. & 3 VALVES ,
UNIT - 2 SysHM P 6 le R(VIS4001 - SAIE PAGE IseSTatelENT AIR PIPING H-71 Sh. 2 2 9/17/84 32 or 36 j gjihqq l} q
-~ r s -
AT-1 RR . 2-4720 B-3 NC A 1 CA AO O C BT OP 10 VR13 CRM 2 ISOI.ATION FST DP
. . _._. . . _ _ _ . . __ - = - - - -:. ___ .
AT-1 RR 2-4721 D-3 NC A 1 CA AO O C BT OP 10 VR13 CROUP 2 ISOLATION FST OP ,
.=. .- .
.. - ._ =
AT-! .RR
- 2-733-1 F.7 NC A 0.375 B AI.I. SG C C hT 'OP $ VR13 cROur 2 ISOLATION AT-1 RR 2-733-2 F-7 NC A 0.375 BALL SO C C DT ,OP 5 VR13 CROUP 2 ISOLATION
-- _. == ..___. __ ___ - .. -
AT-1 ItR 2-733-3 F NC A 0.375 bat.L SO C C BT -OP 5 VR13 CROUP 2 ISOLATION
._..___.- _ . = . .
AT-1 AR 2-733-4 , F-7. NC A 4.375 B AI.1. SO C C BT ~OP $ VR13 cROur 2 ISOLATION ATal RR . 2-733-5 F-7 NC A 0.375 BALL SO C C BT OP $ VR13 GROUP 2 ISOI.ATION AT-1 RR 2-143 8-7 NC AC 0.375 CK SA O C CT-1" RR 'VR-4
.~ .__ --
_ ...... . ... .._ . u. . .. ..;_... _ _ _ _...__ ...._. 2-736-1 F-7 NC D 0.375 EXP O C trr RR
. - - . a .__. . ___ __........- .. ...__... ....... ._ ..... _L. ..._- _
..+_ =
2-736-2 F-7' NC D 0.375 EXP O C-DT RR .
...- .=___ _ _ __= _ _ - . _ . . . . . . ._..... . ..... ._ ..... . ... -- .._.
2-716-3 F-7 NC D 0.375 ExP O C srr RR
....... .. ._._- ._. .u ._. ._
2-736-4 F NC D O.375 EMP O C DT BR
.._-7
... .. .=_- _. ....... __ . .._.... . . . . . __=- ...... ...-_ =
2-736-5 F-7' NC 'D O.375 EEP O C Irr RR .
.. .. __ - _=. _ ........ ----___= . _ -- _ _ - ..._...... _ ._ - ..;-
- .'o..
, 9 I I 9 e
"_~
, .., e, .
INSERVICE TESTING PROGRAM O w[h ISI- CL ASS 1 2. & 3 VALVES OUAD CITIES NUCLEAR POWER S T ATION UNI f , 2 SVSHM t & 13 REveS804 - SAIE PAGE Rx austatNo sou!PMF.NT DAAINS N-85 2 9/17/84 33 of 36 ' 1
/ / yllb yg o l} q - !
AT- 1 RR 2-2001-15 E-3 , NC A 3 GA AO C C DT OP 20 VR13 cROur 2 ISOLATION FST OP AT-1 RR 2-2001-16 E-3 NC A 3 GA AO C C BT OP 20 VR13 cRour 2 ISOLATION FST DP 0 AT-1 RR , 2-2001-3 F-1' NC A 3 GA AG C C- BT OP 20 VR13 CROtiP 2 ISOLATION i FST OP i
=_- ------- _---- . . _ - -}}