ML18092A711
| ML18092A711 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1985 |
| From: | Flach W, Howell W SOUTHWEST RESEARCH INSTITUTE |
| To: | |
| Shared Package | |
| ML18092A710 | List: |
| References | |
| NUDOCS 8508160356 | |
| Download: ML18092A711 (323) | |
Text
{{#Wiki_filter:-*- . SOUTHWEST RESEARCH INSTITUTE Post Office Drawer 28510 6220 Culebra Roa.d *
- San Antonio, Texas 78284
. 1984 INSERVICE EXAMINATION OF SELECTED CLASS 1 AND CLASS 2 COMPONENTS AND SYSTEMS OF SALEM GENERATING STATION, UNIT 2 VOLUME *1
- FINAL REPORT WITH APPENDICES \
SwR I Project 7255 \
** Prepared by Public Service Electric and* Gas Company 80 Park Place P. 0. Box 570 * ..
Newark, New Jersey 07101 March 1985
- Prepared by W. Mark Howell Wayne*. T.. F ch
*. Project Engineer . Director . . .
Inspection Engineering Section Departmen Cit Engineering Seriices
. ** /.Department of Engineering Services *Quality Assurance Systems
- .
- and Engineering Division
- I
( 85081'60356 850723
~DR
*
- I
.. ! ADOCK 05000311
.PDR
- An ABSTRACT inservic;- examination (ISI) of selected Class 1 and Class 2*components of Public Service Electric and Gas Company's (PSE&G) Salem Generating Sta-tion, Unit 2, was performed during the December 1984 refueling outage*
These examinations constituted the second ISI performed at Salem Unit 2 and the second ISI of the first 40-month period of commercial operation. The components were examined in accordance with the "Examination Plan for the 1984 Inservice Examination of Salem Generating Station, Unit 2 .... including any chang.es made during the ISI as approved by PSE&G. The nondestructive examinations were performed using visual (VT).,. liquid penetrant (PT), and manual ultrasonic (UT) techniques. The VT examina-tions of bolting on valve 22-RH-4 and the UT examination of Reactor Coolant Pump Flywheel No. 23 revealed indications which were reported to and dispositioned by PSE&G personnel' using a Customer Notification Form. Both indications were resolved as acceptable after evaluation by PSE&G personnel. The UT examinations also revealed geometric reflectors. No other reportable indications were observed during this ISI
- iii
- TABLE OF CONTENTS VOLUME I--FINAL REPORT.WITH APPENDICES LIST OF ABBREVIATIONS
- v I. INTRODUCTION * * * *
- i. * * ..... .. ~- l A. Examination Areas * * * * * * * *
- 1 B. Summary of Examination Results ****** *z-C. Radiation Exposure * * ******* 3 D. Equipment * * * * * * * * * * * * * * * *
- 4 II.
SUMMARY
OF THE INSERVICE EXAMI:NATION ......
. : 5 A. Explanation of Field Data Records * * * * .s B. Summary of Nondestructive.E:icaminations * * * * *
- 5 APPENDICES A* Class 1 Weld Identification Drawings B. Class 2 Weld Identification Drawings
- c. Southwest Research Institute Nuclear Projects Operating Procedures VOLUME II--APPENDICES (Cont'd)
D. Southwest Research Institute Nondestructive Testing Procedures E. Ultrasonic Calibration Block Drawings F. Certificates of Personnel Qualifications G. Material and Equipment Certifications H. Customer Notification Forms VOLUME III--FIELD DATA Class 1 Components and Systems Reactor Coolant System Residual Heat Removal System Safety Injection System Reactor Coolant Pumps
- v
*?;.- .
TABLE OF CONTENTS (Cont'd) VOLUME III--FIELD DATA (Cont'd) Class 2 Components and Systems Steam Generators Chemical Volume Control Tank Letdown Heat Exchanger Regenerative Heat Exchanger Residual Heat Removal Heat Exchanger Feedwater System
- Chemical and Volume Control System Main Steam System Pressurizer Relief System Valves
- Calibration Records 190000 Series
.250000 Series 360000 Series 370000 Series vi
- ASME CNF LIST OF ABBREVIATIONS
.,- American_Society of Mechanical Engineers Customer Notification Form ISI Inservice Examination NDE Nondestructive Examination
- ~-.*_;_
NDT Nondestructiva.Testing NQAPM Nuclear Quality Assurance Program Manual* PSE&G Public Service Electric and Gas Company PT Liquid Penetrant Examination. QA Quality Assurance SwRI Southwest Research Institute UT Manual Ultrasonic Examination VT Visual Examination vii
-:ro:.
- Public Service Electric and Gas Company P.O. Box 236 Nuclear Depart~I\,
. -r: ""
Hancocks Bridge. New Jersey 08038 r December 19, 1984 Mr. Steven w. Richter Southwest Research Institute Post Off ice Drawer 28510 6220 Culebra Road, San Antonio, TX 78284
Dear Mr. Richte.r:
1984 OUTAGE PLAN UNIT 2 SALEM GENERATING STATION We have reviewed the Southwest Research (SWRI) Outage Plan
- you submitted for use during the second refueling outage of Unit 2. This plan is approved for use and fulfills our requiremen~s for the first inspection period.
During our review, the following significant items were noted and require no further action by SWRI at this time.
- 1. Welds 14RH1211-15, 16, 17 and 8SJ1254-4, 6SJ1242-ll, 4SJ1294-S, 3SJ1292-9 were included in the Class 1 portion of the plan to satisfy NRC Circular 76-06/79-17 commitments.
- 2. Welds 8CV2201-19, 26, and 34 were-included in the Class 2 portion of the plan to satisfy NRC Circular 76-06/
79-17 commitments *
. 3. Weld 6PR 2202-1 was included because it was not performed last outage.
- 4. A surface exam on weld 29-RC-1210-3/14-RH-1211 was included to satisfy commitments made on PSE&G CAR
#84-011.
The Energy People
- 95*21 68 175 Ml 12-83
- Mr.
s.
- s. w. Richter
£*
; ~
2 12/19/84. The ultrasonic examinations of #23 and #24 Reactor coolant Pump flywheels will be performed by removing the r inspection cover only. No flywheels are scheduled to be removed this outage. By removing the inspection covers enough of the flywheel surface is exposed to satisfy the examination requirements of Reg. Guide 1.14. The examination plan has been- changed to indicate this examination will be performed with the flywheels. in* place. Thank you for your cooperation and if you have any questions, please don't hesitate to call.
- very truly yours, Louis Lake ISI Engineer
- LFL~m BCvbon Rogocenski Dick Skibinski Jim Cash
OPS~G -* Salem Generating Station TO: F. Meyer Manager-Nuclear Site Maintenance FROM: D.A. Perkins* Station QA Engineer s*JBJECT: REVIEW OF THE SWRI UT EXAMINATION DATA FOR UNIT II 2ND REFUELING ISI EXAMINATIONS DATE: December 28, 19.84 OUR REF: SQAM #84-061 The SQAE review of the SWRI UT Examination Data for Unit II 2nd Refueling ISI Examinations has resulted in the following which
.need clarification. The following information will be provided to SWRI. *
- RHR 14RH1211-7 150900 IND NOS. 1, 2, 4 & 6 No.
No. OK. 3 OK Plot Angle 38° should be 45° 5 Plot angle 48° should be 58° indication now plots 5/16n into I.D~ wall (weld zone) No.
- 7 Plot angle 41° should be 58° indication now plots 7/16" into I.D. wall (weld zone)
- 14RH1211.:.15 151800 IND NOS. 1, 2, 4 OK No. 3 Plot angle is 52° should be 58° indication now plots-1/4" into I.D. wall (weld zone)
- 14RH1211-16 151900 IND NOS. 1, 2, 5, 6, 7, 8, & 10 OK No. 3 OK_ Plot angle 39° should.be 45° No. 4 Metal path versus the plot, are not in agreement to support resolution call of I.D. geometric
- No. 9 OK Plot angle is 54° should be 58° Summary record missing resolution record sheet nos.
- 14RH1211-17 151950 IND. NOS. 1, 5, 6, 8 & 9 OK No. 2 Plot angle 44° should be 58° normally this would plot out to the bottom quarter of the weld but the faqt it was dampen at top surface near side, it would lead you to call it a mode converted signal The Energy People
M.£MO TO F. .MEYEP Pc.9e 2 No. 3 Plot angle 53° should be 58° indicatioi no~ plots 3/16" into I.D. wall (weld zone)
. No. 4 ..--OK Plot angle 45 ° should be 58 ° .
No. 7* OK Plot agrees .with mod~ conversion call
- 8SJ1252-4. 16785*0 IND NO. 1 OK Plot angle 50° should be 43° Nos. 2' 4 & 6 OK No. 3 OK Plot angle 38° should be 43° No. 5 OK Plot angle 54° should be 59° No.* 7 Ok Plot angle 53°' should be 59°
- GSJ-1242-11 171450 IND NOS. 1, 2, 4 ~ & 5 OK No. 3 & 7 Metal path agrees with mode conversion call No. 6 Metal path plots to I.D. which does not explain how the indications can be dampen at surf ace No. 8 OK Plot angle 54° should be* 59°
- 2LHEX-l 275210 IND NO. 1 Plot angle 38° should be 44° indication now plots
~/32n into I.D. wall (weld zone)
Nos. 2 1 3, 5 & 7 OK (in addition they are outside area of interest) Nos. 4, 6, 8, 9 & 10 OK Comment about surf ace wave damping on all recorded indica-tions should exclude IND~ 6, 8 & 10 *
*
- 2RHE-l
- 275300 IND NOS. 1, 2 & 3
- nRedirected she~r~ is not a satisfactory explanation for resolution
- 2RHE-5 275340 IND NO. 1 Original examination was found with 60° The relock was performed with a 45° --why.the difference. There has been no resolution oi plot for indication No.* l 60°.Relook plot angle 30° should be 46°. Indication.
now plots 7/32 °. into I ~D. wall *(weld. zone) No .. 2 &: 3. OK
- 14BF2231-17 330530 IND No. 1 OK Plot angle 49° should be 43°
- 14BF2231-18 330550
- .IND NO. 1 No. 3
&. 2 OK Are new tranverse indications examinations They were not observed during 4/84 examination, -nor PSI There is an error in the sununary record remarks ..
examination was performed from downstream side *. The
!-'..£~*~=* TO F. M.EYER Pc:;t:: 3
- 8CV2201 360360 IND NO. 1 & 2 OK There is an error on the r8look examination record sheet no.
710010. Indication IR & 2R "L" numbers should be switched.
,Jb~
WD:rc Q_c__Q~i-- C J. Zupko C.P. Johnson File
-. ~
0 PSltG
- TO:
F. Meyer FROM: D.A. Perkins St~tion QA Engineer
SUBJECT:
co:;PARISON REVIEv;" OF PSI/ISI DJ..TA OF UNIT II 2t-~:) REFUELING ISI UT EXAMINATIONS DATE: *Ja~uary 2i, 1985 OUR REF: SQAM #85-006 The following is a review requested by L. L~ke of the rec~nt SWRI UT data sheets generated during the Unit II 2nd refueling outage* ISI examinations, with the PSI .data sheet* of the same areas:
'.")
Examination Area Comments 29RC-1210-3/14-RH-1211 Dimensional differences Crown Height Crown Wiqth W~ld Length
- PSI 'l/16" 7 /8" 54 3/4" ISI Flush 3 1/2" 65" Examination Differences - PSI - 45°T on Weld CW/CCW ISI - 45°T No on the weld scan due to weld conf i9uration., scanned main: run*.*
14RH 1211-7 14RH 1:211-15 Dimensional differences in* crown height 14RH 1211-16 PSI Recording 1/32 to 1/16 and ISI recording flush~ 14RH 1211-17 No comments 8-SJ-1252-4 Exam limitation differences PSI exam limitations 12" to 23" upstream due* to inaccesability.of floor and wall, this limitation was not a factor in ISI exam-ination. ISI indication* #6 141% was not observed during PSI (ind. dampens) PSI indication #2 178% 10" in length was*not* observed during ISI (ind. dampens) The Energy Peopie
F. Meyer
- t-s~--::::*~~-:1 4-SJ-1294-5 No corrunents 3-SJ-1292-18 PSI data was not co~tained in supplied*
data 21-STG-STBSA Di.:' f ere nee in sea:: are .=1s PS 1 0 L 0 -15 11 12 0 ° ( 141 11 11 0 -15 11 2 4 0 ° ( 2 8 3 1 0 -15 11 11 Tot al .45. I s 1 0 ° 0" - 3 9" 1 73" - 20 3 11 302" - 332 " Tot al 9 9 '.' Weld length* 425" code* re juires at least 20~ U:nifcrrnl:1 dis-tributed among :three arec.s around the vessel circi.,;.mference Category C-A - 32-MSN-2211-1* Dimensional differences Weld Length Crown Height PSI 180 1/16 ISI 182 3/4 Flush 2-CVCT-2 Difference in scan areas
*PSI 81"100" 184"-203" 275 l/2"-9 "')../2" ISI 115"-135"-190"-210" 257"-277" 2LHEX-1 Difference in scan areas PSI 20"-25" 40"-45" ISI 10"-15" 40"-45" 2RHE-l Difference in scan areas PSI 0"-2" 8"-10" 23"-25" ISI 0"-2" 5"-7" 9"-11" Difference in exam limitations - PSI has none, ISI has exam limitation l" W on cap side.
2RHE-5 Difference in scan areas PSI 0"-2" 8"-10" ISI 0"-2" 5"-7" Difference in exam lirniations PSI has none, ISI has exam limitation*l" Won cap side 21-RHRHEX-OUT Dimensional differences Weld Length
- PSI 63" ISI 61"
F. ~eyer T. ;.~ :.:.c-_.::.: ~ . PSI & 1S1 .,- - 12/84 !~o exarr. limita:.ior, IS 1 4/84 No exam downstream due to weld overlay yet the scan r~c0rd sheet 48,0002 i~dicat~s it ~5E sca~~e~ do~~s~r~a~ 14BF 2231-17 Difference in exam limitatio~s PSI & ISI 12/84 No exam limitations ups":.ream lSl 4/S.; 1~0 E::* am upstrear.: duE to v.*E:10 O\ er lay J.imt:c;-,sional di :f .: ~:re n c es c r ov.-r. v.* id th PS I l = I 4 11 I Sl 1 3/ 4 11 14-:ff 2231-18 Difference ir; e>:arr, 1-.mitaticr:s PSI & ISI 12/84 No exam limitations do..,.;ristream ISI 4/84 Exam limitations downstream due to weld overlay 8-CV2201-19 Dimensional differences Thickness Up Center Down PSI .l .16 .13 ISI .15 .22 .18 8-CV 2201-27 PSI data was not contained in supplied data
- 8-CV 2201-36 8-MS 2212-1 6PR-2203-6 No comment*
No comment Dimensional differences Thickness Up Center Down PSI .27 .34 .28 ISI .31 .39 .. 32 6 PR-2202-1 Dimensional differences Weld Length PSI 20 5/8" ISI 11 15/16 Thickness Up Center Down PSI .28 .33 .27 ISI .30 .40 .29 The above review has revealed two major areas of concern, they are as follows:
- 1. Differences in the PSI scan area and the ISI scan areas on 21-STG STBSA, 2CVCT-2, 2LHEX-l, 2RJE-l, 2RHE-5. The purpose of PSI examination is to establish a baseline for future ISI exam-inations, therefore its imperative that ISI examinations be conducted in the same areas that were examined during the PSI.
- 2. Differe:-.c-es cb~cerr.s; ln dimE:::-,s1or,s from the PSl/lSI cc.ta causes SE'*eral are we looking at the same wel~, ar~ there other
_j_~_e::::*~~*.=.:-:Cl~~ :..:-. ri.*.:...::.~*....::-*.:.:-:-.*:..:.:.E v..~:-. ic:-.. c..:-e :-.c..:. G~ LC.S\' -:.cc.:..:...:::.:..:. rorverify. There shoula b; an explanatior. from SWRJ on the differences in the e:*:c.~. l.:..:::.:.tc:t.:..c -;s ct:.r.:..:-.g PSI, ::::1 12/s.; c. :d 1.s:;: .;/5.; o~. \.:E::ld~ }.;::,~22:5:-: 14BF223l-17 a~j 14BF2231-18. JI;~
- WD:rc C B. Brandt L. Lake File
{'
/.,.--.\*
.1
.'. I
*' *. \ ,. . I
, ,,.~.
I.
- \ .... ,... *:-*-
. 'c:. *. : ,:. ', ~.... ( .,
... EXAMINATION* PLAN CHANGES
~ITE ; SALEM GENERATING S'i'ATION, UNIT 2 PAGE NO. L OF SWRI SPONSOR C~ANGE PAGE DATE AREA AFFECTED l)ESCRIPTION OF CHANGE AND REASON FOR CHANGE REP. REP.
NQ: .. NO.
' *tJ.ALS INITIALS.
i I
/: G!k( ~~ It+ c* ih:Yil lf~L. ~ "l*fv<-l1fl1C. lr :irJTl{v;_ c--...l~Slttl\ . ~J f 1.-1) t-lJS. i -CV- 2:20/-. ;J.{ ~,,; /\ * - ,,
*vi,!...,
.. ,b 1.JERf. :.~/~!:117i.\.~~
*.. 'i wm 1
vvr<..
- I I
(. I *51'-cv- :i.201 *2G o/
-3<j- 11\.1
- fli..A t..f. oF i-(\(-1}0/**2f-. AN>> -*)'-{- f-f')ff.C11V~L.. 11 1*
i I' .. No. 26 LJnS KEhflcE..[) tUE TO L.llC.K. or Ace e.ss ANIJ M.39
' "'ifl~ l\i.P~f\Cfi) 6CC'll 1115c oF A RESr/?/flJ.JI 11U 7U?.F:. ,C:f.NC E-
>--* C.rtANGsE. wl\S mtt[)f: VJ,Tt-\ iH£. cvl\lCL(RR.fNCf. oF PsEiG.* *---*-
- 2. i~c-~f 12_ R*=Ac-TOf.. Co c.IL Ar. . ,.. Ert1P F1.-~- r!l1 £.icAr"' 11\1 AT /L'f\.I ,* JAS
. DELETE]) A
('
* )crRFl/CE. ff£il_ ~ (
' WHEf.L.~ J.lf- PrriP-fuJ, 21-PmP- ~JIlli't1 lii.J fl TI eN I~ . Ak?T REGv,R£D FM THE.
' * ~
*rLvJ F'-'lwrl££1.. EitfJ/h1N4 'T/otJ. 1~£F~l?£AI<'<.:-
*1,,. , , . ,._ - _,,,n .-.1/!i - , "'*-**" ,,1.:;1/(
~*~* iN PLf/CE 11"\:"f..._ ....
~- '"' " ' I ..... ~ -"
- ~, "'. . ~ .
r {)SAIA c. Ri;t:a, Gi, 1oe Al'-/- i. 3: 111/fkg<f I/ £(~ ~Nc-.P.ni1 vl ./-l:_~*K* Df\(11\Tf<.">N i l..VAS Hl\OE.D TD fl..C)ctDV/{£ t.oo- "30 /(0 _ IAA1/#- ~ 2*/?N,:-f -/
, 2-A?l/~--- S-- h~1S i)E.V1/JTt 01\J WA.S AbDED -re> AU(>W /HE
()tJ..:.i, ._;_ Wll~ D- *i ~' 1Rl- NI )T- ~0-)0 !11.o . .kv.i r...Foin £ r Rit ~.~ I
~ . £\(JI 1'¥11 N f.1{ 70 R. i;c i..'> R..D ONLV
'J-I . *. . .. '-""' .,. . ,.,,, /r . ***~
LI- ,. J'lflr'bt (_;'AFE.W 11\1 J e c..*n ei \\i *Wa..J>*3}f-SJ - /J.92:.. 1.K'i.vltS Sv 85 TI 7 iA Tt.=.iJ (."ol. U1/'/tl pvt.
. *>*Sj ~ i2q2 ~ 9 *.
l/-5J-/2~2- ~ . -. 9 W/15 WRAPPE.b
- IAP W1Tt\ H~RT TRrlci:. A1\Jt, i IVf\C(tS'Slfl,lf"
'~ r,.
.'~'r
*~.:.. . . . . . ...
~~-- .. .. ..
~~ *'
~ - ~ .....-t._.......... ,_,. ld ,._, -*-*~ .... -'-** "<l h;.c*-.-*.1~,..l_._\'h;.,.!....,__J..t- ..... Jo.!1.'.. . .;r:.~..,:;;.-WA~~~*~:,.;.i;...;:.<;,;~.~ ..._.~ **"* '.. * ' -~ "**- * .: . ....:. ~*-- ,.,.:;.; ~.;. .*..,. . .
, , _.:,.* .:.Lt.*<<:~c :.1-..:J.~.,:~.:.. .*.~.;_;_L ~* * - ......;_f.; .. :. : *. ..
*..J **
EXAMINATION *PLAN CHANGES Sl:rE , .SALEM GENERATING STATION, UNIT 2 PAGE NO. *-=(_~--
' ..
- SWRI SPONSO~
I C~~~~~ D~~E .PAGE AREA AFFECTED REP. REP. '; . ~~~'. .. . NO. DESCRIPTION OF CHANGE AND REASO~ FOR C~ANGE INITIALS INITIALS
, . -z;
. ~
/'l{'r.(lJl 3 REACTOR. Coo._ AN 1 ~-.:c; T~.fl~ A.SviRff1ct. c~l'VA I lvf:iTh) t-J ( PTJ. h1J:l:; At~[)E..A"'* *ft'tmw* uvl!.
1q-R.c-l.1\o-3/,Y-Rh-121 I* r()~ {~K~t\iC.\-1 C'.otJl\)cC"TICr..J Zi.FC-\JJ,0-:ft~-(./J.dtt I
\.)J/iH A L-------~~---*-----------'-----~s~*v~~-r~-A~~...;___~*k~~~~~n\-'~~~A~T~i~~1 ~_*=S~o_____________.. ---~-* -~-*-
. :o. (6b2.Wm---:{:::__;_ 1__fJ:...:...~=f_.<i_~T...:....v_'i?._C_c_t:>_L_A_~J...:....T_/_~*-'-11-'tl~P_l_*_.*_,_*F:_,L::.....v._.v.=u.w1:-l,_, E~E~L=. . .,. . .t=.=-. . :.'t(A. . .:.;1 1~1 AJ=l" "A.-=-i"i.....,,...,,1M"""5=--_,_;-l_,A~V=£'-=13;.;....E-=.E'-'-N*'--"-p_,r_,,0'--'*7_-_ *{!Ill!/ ~wtf-.
i'
;pr.~
.1 '"'
1 ,.- j: "
\r ....
- I. . .,. .,.1-;....._-1-~--l-:.__;_--1------------'---f-.:-.:-:-.:....!...:.:...!__~::..::.::!:!.ll!.L!...L::.!...::.=-_!.....~~~
Hl h1f,1 G<Jµc;J0£t<f111DfJ~ flf£t/£J-J7/I) . ...::::__ l/ S"' .EL llr*111u/l __...__--""'--=....:..c..~r-----t----i Tull~*J.:.__'v-..:.:.f.:J:.:.:.T_T.:_H!..!.. m~t~-------~---+---'---i----11
! : :*' ,
- S:__..:....n.:..:.1
..:..:i
.j~*,~"* *.,~-;* it{*'.-.* *u'~';,*[*(~'1-*;__*~--~-*
**-<, .;(~ :/;:~
..; : ( '
- l - - " -..
-~-1---'----1-----.,.------~
~----- *-
-. : :. . r ~ ~ , * *. . ,. ..
*- EXAMINATION PLAN CHANGES SITE 1 -SALEH GENERATING STATION, UNIT 2 PAG.E NO.
j Cl ,*: 3 SWRI SPONSOR lcHANGE .PA~E DAT~ Af FECTED
""~I)
'* DESCRIPTION OF CHANGE AND ftEASON FOR CHANGE REP. REP.
NO* NO. INITIALS INITIALS
..tJ(,,.JfX. . . ... ,,,.
-~, AfAh b Rc.P' Fl-'t'Wl-!£:b'. \' VE L-E.T£.b _1-11:or E l')tA.r<F (,;<)(! - G/13 ri~A~ i . t\J--1() ~ IAM1-H l:j)ve
""' *: /
'{5* .,.,,...,, ..
~DU -0/.22:;' lJi::>t, '-<l '
I
-~ .
z-H ~PIY/ P- FLW .l3- flhP--FLc:J /
~- i-l hCE*) :'JKv(_c01Al(E I
~j(*- (, /2-s i>E.v 1 (", rl'-L't-1) ~.:L::~ r-4 j::'-tl.L \IEE C1-k1 f,1U1 Tl o,V fCK F L'r I.A:* 1 i; G" LS. t:,x >J tvi 1111 El\ Iv ii/Kt
' IA/c. ('(\.AL I) f.JdT v. 5£. ( -fi IS CA Lt ~-i~fi I 10 >J /3£.CfttA.SE TH( - ---- CJ-\L.. 1*:, Lo c_ 1< 15 CL1{D_ (ooO-h (2 -:_ f<. E. VI::, : ;, t* i I .A~
\:-'-EI) ~ ('1i'<
(
-.J 1-\ LE l'VI l_,lµ i'"I l ISJ. , J,_l 51_),/f\,',.:: R__ lq <;:~-
I :_ *-*** -- i j' JV
';f. -
9 L-.q..:r .-1fhJ i' 10 1-* R-11 c c- " i ,)/*_ (~'\,J(.J;.l\d rl L'1 r I~ ((Cr) RcF i::x.An11"-iATfv1'1 t--ffivE P Ec.-11.1 .---O" ~ <7') l'OAIC.-~ I l(((I:/ bJW'K'
)-* /(( F -1. l /rJTI'-- 1...Art: P-- i Iv *n-J.IE:. TEAi VEA 6(_ /Iv 5/Jt:.---:c I re) iv
- z. - le r-- -1 t s flt.-<-< (1-i ls 1 lNIE:RvftL Ai- Tf-1.c l<.E a_ u Ii-~ T" of- P<;E/G
' " .,. ":J~.: :
I "
;,\
,- I I' *.*.-
LJ.*~.:;..:. :.* ..-,__.,...., ~ * - ,., _ _ ,.£ .. ~ ...... ,..., *
- _ . , . . . . ~.*~ -
***** # - -- *-*** -- "" -*** -- ... --* -*- ...-*--** ***-* **~ *- --- - ..
- ~-
I . INTRODUCTION
- During the December 1984 refueling outage, Southwest Research Institute (SwRI) personnel performed nondestructive examinations (NDE) of selected components for Public Service Electric and Gas Company (PSE&G) at Salem Generating Station, Unit 2. The examinations constituted th_e second such inservice examination (ISI) performed at Salem Unit 2 and the second ISI of the first 40-month period of commercial operation.
A. Examination Areas The ISI was performed in accordance with the following documents: Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1974 Edition with Addenda through Summer 1975. SwRI Document 84-PEG-SGS-1/2-1-0: "Project Plan for the Nonde-
- structive Examination Activities to be Performed at Salem Generat-ing Station, Units 1 and 2," dated May 1984.
SwRI "Examination Plan for the 1984 Inservice Examination of Salem Generating Station, Unit 2," dated November 1984
- swRI Nuclear Quality Assurance Program Manual (NQAPM), with all applicable changes.
- u. s. NRC Regulatory Guide 1.14, "Reactor CoolantPump Flywheel Integrity," Revision 1, August 1975.
Representative samples of the following components and areas were examined with NDE techniques. Class 1 Reactor Coolant System Residual H~at Removal System Safety Injection System Reactor Coolant Pumps Class 2 Steam Generators Chemical Volume Control Tank Letdown Heat Exchanger Regenerative Heat Exchanger Residual Heat Removal Heat Exchanger Feedwater System
- Chemical and Volume Control System 1
Class 2 (Cont'd) ***,. Safety Injection System Main Steam
. System Pressurizer Relief System Valves
,B. Summary of Examination Results The NDE activities were performed using visual (VT), liquid penetrant (PT), and manual ultrasonic (UT) techniques~ Each examination was con-ducted in accordance with standard SwRI nondestructive testing (NDT) proce-dures which were written to comply with the requirements of the pertinent sections of the ASME Boiler and Pressure Vessel Code and the SwRI NQAPM.
A copy of each applicable-SwRI NDT procedure is included in Appendix D. SwRI operating procedures for weld joint identification marking on nuclear power plant piping, recording data during VT and PT examinations, and recording search unit location and maximum signal amplitude during UT examinations are included in Appendix c. .*-
- During the VT examination of the bolting for valve 22 RH 4, one indication was observed and reported to PSE&G on Customer Notification Form (CNF) 84-2-001. The indication was evaluated as insignificant by PSE&G personnel and the CNF was closed out without reexamination.
An in-place examination of reactor coolant pump (RCP) flywheels, as.* specified in u.s. NRC Regulatory Guide 1.14, Article C, was performed on RCP flywheel Nos. 23 and 24. During the UT examinatio.n from the top sur-
~ace of flywheel No. 24, one indicationwas observed and reported to.PSE&G on CNF 84-2-002.. The indication was resolved as an acceptable lamination having no throughwall depth and no areas.with a 100-percent loss of back-wa11.* No reportable indications were observed on RCP flywheel No. 23.
UT examinations were performed on five Class 2 Category C-A vessel welds: 21-STG-STBSA, 2-CVCT-l, 2-LHEX-l, 2-RHE-l, and 2-RHE-5. Category C-A examinations are required to cover 20 percent of the circumferential weld, uniformly distributed among three areas around the vessel circum~ ference. The 20 percent requirement is applicable for both the PSI base-line examination and the ISI. For each of the Class 2 vessel examinations performed in this ISI effort, the 20-percent baseline examination area was not repeated. Each affected weld will be rescheduled for examination in the next refueling outage. Copies of the CNFs generated during this ISI and descriptions of the disposition of each CNF are located in Appendix H. No other reportable indications were observed during the examinations. In addition to the examinations performed by SwRI personnel, VT exam!~* nations of selected Class 1, Class 2, and Class 3 hangers were performed and reported separately by PSE&G. 2 I
- The SwRI Quality Assurance (QA) Section was represented on site by the SwRI QA Representative who was present for approximately 50 percent of the examination .Period. The QA Representative performed the appropriate duties
. outlined in Paragraph 3.3.1(4), "Onsite SwRI Quality Assurance Activities,"
of the Project Plan.
- The SwRI examiners were qualified and certified in accordance with SwRI Nuclear Quality Assurance Procedures 11-1 and 11-2 which incorporate
- the guidelines of SNT-TC-lA of the American Society for Nondestructive Testing. A copy of each individual's certifications is included in.Appen-dix F. Included in Appendix G are copies of the certifications for the ultrasonic instruments, transducers, couplant, and marking pencils used during the examinations.
- Drawings of the basic calibration blocks used during the ultrasonic system calibrations are located in Appendix E.
C. Radiation Exposure Radiation exposure encountered during the ISI was of fundamental con-cern to the SwRI personnel involved in the daily examination activities. SwRI personnel took the necessary pre.cautions to minimize overall exposure and consequently received the minimum dosage practicable while performing the selected. examinations. The following listing details the approximate radiation exposure levels associated with various examination areas
- Area Exposure Level*
- CONTAINMENT Annulus Area
- 0-50 mR/hr Inside Bioshield 10-1000 mR/hr Pressurizer Enclosure 50-1500 mR/hr Refueling Deck 0-20 mR/hr Regenerative Heat Exchanger Room 50-500 mR/hr Steam Generator 10-100 mR/hr AUXILIARY BUILDING Chemical Volume Control Tank 20-200 mR/hr Letdown Heat Exchanger 10-100 mR/hr Residual Heat Removal Heat Exchanger 10-100 mR/hr Mechanical Penetration Area 0-10 mR/hr Charging Safety Injection Pump Rooms 0-20 mR/hr Main Steam Penetration Area 10 mR/hr
- 3
Equipment
- 1. Sonic FTS MK I Sonic FTS MK I UT instruments were used to perform the manual ultrasonic examination of selected components. They also served to deter-mine the characteristics and properties of the components by measuring the transmission and attenuation of ultrasound. The Sonic FTS MK I instrument is a lightweight portable unit powered by a rechargeable battery and util-izes transistorized circuits and a cathode-ray tube to give a video.display representation of the test data.
Instrument calibration certifications for the Sonic FTS MK I are located in Appendix G.
- 2. Transducers Various brands, sizes, types, and frequencies of ultrasonic trans-ducers (search units) were used to perform the examinations. Transducer frequencies of 1.5, 2.25, and 5.0 MHz were used. The 2.25- and 5.0-MHz transducers were used on carbon steels, and the 1.5- and 2.25-MHz trans-ducers were used on stainless steels, as specified in the procedure. For information on the actual transducer used for any specific examination, consult the data sheets and referenced calibration sheets in the field data volume.
4
- r-.
II. SUMMA.RY OF THE INSERVICE EXAMINATION This section of the report provides a discussion of the field data records and a summary of the NDE activities performed. A. Explanation of Field Data Records The results of the NDE activities and calibrations performed by SwRI personnel were recorded on standard SwRI forms. These completed documents constitute a portion of the Inservice Examination Report. The original* records are retained in the SwRI Data Storage Facility, and copies are pro-vided herein for completeness. The field data records for each weld or area are assembled into a pack~ age preceded by a summary sheet. The examination areas and summary sheet numbers correspond to those listed iri the Summary Table. A general expla-nation* of the individual field data forms follows. The instruments used in performing UT examinations were cali-brated prior to use, then verified again both duririg and upon
,, completion of the examinations at specified intervals. The cali-bration parameters were recorded on the calibration record sheet specified in the applicable NDT procedure. The documented cal!- *
- bration and calibration verification provide imme:4iate assurance that the examinations were perform~d using properly calibrated instruments.
The results of UT examinations were recorded on the data record sheets specified in the appropriate NDT procedure. The informa-tion documented ori these forms describes the parameters associated with those indications which were greater than the recording levels specified in the applicable NDT procedures. When required, the size~ location, and nature of reflectors were determined by analyzing the indication parameters recorded on the forms described above. The analysis is documented on SwRI Indica-tion Resolution Record Sheets, which are included as a part of each data package *. VT and PT.Examination Record Sheets were used to record the results of those examinations. The equipment and/or materials used in VT and PT examinations are also identified on the record sheets. B. Summary of Nondestructive Examinations The. following section of this report is the Summary of Nondestructive Examinations Table (Summary Table). The Summary Table provides informat.ion and results. for the NDE activities performed during this ISL* The Explana-. tion of Summary Table Format on the next page describes each of the ele-ments of the summary tables. Weld identification figures for Class 1 and Class 2 systems are.located in Appendices A and B, respectively. 5
N I ll
. II N c; l ASrif.. ASH[ SHI! I SllHHAllY R S E II
- ll:Cl XI SlCJ XI 1<IE'LU NUtlllf.11 l\t*IU/011 f.XAll. f'HIJCtl>Ulll Slll'.r I E I II I:.
11,EH NU CAIGY EXAlllNAJIUN Alll-A lllUHH ICA1 IUN Ht flllll> rm./tU-. v. IUIHlllH
- C c; H fl llf:HllHK S
------- -------------------------------------- ------- -------- - - - - -The------------------------------------
remarks column is used to describe any pertinent features of the exami-nation such as limitations, report-able results, CNFs, ~tc. Ultrasonic calibration blocks are also listed .
*here.
The results of the examination are indicated in these columns. The absence of indications equal to or greater than th~ appropriate re-cording level is shown by an "X" in the "NOREC" column. The presence of nonrelevant indica-tions or indications which are equal to or greater than the recording level but less than the evaluation level is indicated by an "X" in the 11 1NSIG 11 column. The presence of ultrasonic
*indications shown to be the result of a geo-metric feature of the examination area is in-dicated by an 11 X11 in the "GEOM" column. The presence of indications deemed reportable to the customer are indicated by an 11 X11 in the 11 0THER 11 column. *
../ This column references the examination summary sheet
.which serves as a cover sheet for the data package and lists the data record numbers, the examiners, and any pertinent remarks.
This column lists the applicable SwRI NOT procedure used for the examination. The NOE method used during the examination is listed in this column. Each examination area is list~d in this column. D~tails of the weld identification system are contained in Appendices A and B. The ASME SECTION XI ITEM NO. and CATEGORY of the examination area are listed in these columns. Explanation of Summary Table Format
SALEH GENERATING STATION,; UNIT. 2 lq8q INSERVICE EXAMINATION CLASS 1 COMPONlNlS PAGE 7 REACTOR COOLANT SYSfEM
N I 0 ASHE ASHE 0 NG T SECT XI SEC r XI SWRI SUHHARY R s E It lifLD NUHOER AND/OR EXAM. PROCEDURE SHHT E I 0 E ITEH NO CATGY EXAMINATION AREA IDENTIFICATION 29-RC-1210 [PSE&G #2q"*2RCIOOOJ HETllOD . N0 0 /HEV 0 NUMBER (SEE FIG. A*3b) --------- -------
c G MR
*.- -- HE HARKS
--~---------------------------------------------
B-J 29-RC-1210-3/lll-RH-1211 PT 200-1/Sb 082800 1 14 _IN. BRANCH CONNECTJON x - LIMITED EXAHINATION DUE 10 THE DEV. ii PROXIMITY Of ADJACENT 1" UTOL b00-3/bl )( BRANCH CONNECTIONS. NO UTOW UTOH DEV. 15 x .. SCAN ON WELO DUE TO THE WELD UT'IS 'x - - - CONFIGURATION. PT WAS PER-UTll!>T )( FORMED AS A SUPPLEMENTAL EXAM* INATION 0
***BASIC CALIBRATION BLOC_l<u*
0 2
- lli?-SS-.H-S AH
SALEM GENERATING STATIONi UNIT 2
- 1q84 INSERVICE EXAHlNATION CLASS l COMPONENTS PAGE 8 RlSJOIJAL 11EAT REHOVAL SYSTEtl
~-------
N I 0 . ASHE ASHE 0 N G T SECT XI SHT XI SWRI
SUMMARY
R S E H HELO NUMBER ANO/OR EXAH 0 PROCE.OURE SHEET E I UE J TUI NO CA Tia' EXAMINATION AREA JOENTIFIC~TION METHOD N0 0 /REV 0 ~llMBER C G H R RE HARKS lq-RH-1211 lPSE&G #l4"-2RHl-OOOJ (SEE FIG.-------- A-bl) --------- -------
--------------~--------~------------------------
A-J lq-RH-1211-7 UTOL b00-3/61 l50qoo ELBOW TO PIPE x - UT45 DEV *. 1S - xx-UHST x UTbO - )( x -
***BASIC CALIBRATJON BLOCK***
14-SS*lbo-1.qoo-18-SAH 1:1-J fll*RH-1211*15 VALVE TO PIPE UTOL UTOH b00-3/bl DEV. 15 151800 )( x
- NO EXA~INATION FROM THE UP-STREAM SIDE DUE 10 THE VAi.VE UT45 - x CONFIGURATION." EXAMINATION UHST x SCHEDULED IN ACCORDANCE WllH UT60 - xx- IE BULLETINS 76*0b ANO 79-17.
***BASIC CALIBRATION BLOCK***
l4*SS-l60*l.400-7R-SAH B-J 14-r<li-12ll*lb UTOL b00-3/bl 151900 x PI PE TO ELBOW EXAHINATION SCHEDULED IN AC-UT45 DEV. 15 - xx- CORDANCE HITH IE RULLETINS UT45T x - 76-0b ANO 79*17. UTbO - x )( -
***BASIC CALIBRATION RLOCK***
1q~ss-160-1.400-78-SAH aq.s fl-J l4-IHl*l2ll-l 7
-xx UTOL b00-3/bl 151'150 ELBOW TO PIPE UTq5 UTLIST DEV. 15 )( )( - EX4HINATION SCHEDULED JN AC-COROANCF WITH IE BULLETINS UTbO - )( x-lb-Ob ANO iq .. 1 7 *
***BASIC CALIBRATION BLOCK***
14-SS-l60*l.40U-78-SAH .
I* SALEH GENERATl~G STATION,* UNll 2 l98q INSERVICE EXAMINATION CLASS* 1 COMPONENTS PAGE 9 SAFETY INJECTION SYSTEM
N I o*
ASl1E 0 N G T ASHE SWRI SUl1HARY R s E H SECT XI SECT XI WELD NUMBER ANO/OR EXAtt. PROCEDURE SHEET ITlH NO CATGY E I 0 E ' EXAMINATION AREA IOENTIF ICAT ION
~-SJ-1252 lPSE&G #8"-2SJl025J HETllOD A*6~,
N0 0 /REV, NUMBER CSEE FIGS.-------- 70) t G H R RE11ARlEV. 15 167850 x x
- LIMITED EXAMINATION '.F.ROH TllE UT45 urq5T x
)(
UPSTREAM SIDE DUE TO TttE f'IWX-IMl TY OF WELD 8*SJ-1252-3. EXAMINATION SCHEOULEO IN AC-UThO - x x - CORDANCE WITH IE BULLETINS 76-06 ANO 79*17.
***BASIC CALIBRATION RLOCI<***
a-ss-xx-.ebo-21-sAH 6-SJ-12qz (PSE&G #b""2SJl05lJ *(SEE FIG. A-73)
SALEH GENERATING STATION~ UNIT 2 1q54 INSlRVICE EXAHINATION CLASS l COMPONENTS PAGE to REACTOR COOLANT PllMPS CSEE FIG. A-109)
~---------
N I 0 ASHE 0 N r. T ASHE SHRI SllHHARY R s E H SECT XI SECT XI HELO NUHUER ANO/OR EXAH. PROCEDURE SHEET E I 0 E* ITlH NO CATGY EXAHINArION AREA IOENTIFICATION.
------- --------------------------------------- -------- --------- ------- c- - - - -
METHOD N0 0 /REV. NllHRER G H R REMARKS
------- PUMP MOTOR FLYWHEELS ------------------------------------
NONE RG 1.14 24-PMP-FLH IJTOL bOO-b/22 252100 - - - x SEE CNF 84-2-002. LAMINAR UT45 DEV 0 8 x - INDICATION. INVESTIGATION. WITH ANGLE aEAM UT REVEALED NO THRUllGHHALL 'oEPTH ANO NO AREA WITH 100% LOSS OF RACK~ HALL WAS RECORDED. INOILATION ACCEPTED BY PSl&G PER 1Hl GUIDELINES OF USNRC REGllLATOHY GUlOE 1.114 0 FLYWHEEL WAS EXAHINEV JN PLACE ANO UT WAS PEHFORMEO ON ALL EXPOSED SUR~ FACES.
***BASIC CALiaRATIUN BLOCK***
7-CSCL-50-SM1 NONE UTOL bOO-b/22 252200 x EXAMINATION WAS PERFORMED JN UT45 DEV. 8 x ACCORDANCE WITH USNRC UEGllLA-TORY GUIDE 1 0 14 0 FLYWHEEL WAS EXAHJNEO IN PLACE ANO UT WAS PERFORMED ON ALL fXPOSEO SURFACES.
**~ffASIC CALIRRATJON RLOlK***
7.. cscL-50-SAH
SAL.EM GE.NlRATING STATION, UNIT 2 198Q INSERVICE EXAMINATION* CLASS 2 COMPONENTS PAGF. 1l SIEAH GENERATORS (SEE FIGS. B-1, 2, lt 4)
N 1 . 0 D N G T ASHE ASHE SWRI
SUMMARY
R S E H SE.CT XI SfCT XI WELD NUMBER ANO/OR EXAM. PROCEDURE :;HE.El E I OE ITEM NO CATGY EXAMINATION AREA. IDENTIFICATION METtlOO N0 0 /REV. NllMRER C G MR REMARKS CIRCIJrlFERENTIAL. WELDS -------- --------- ------- ------------------------------------ cl .*1 C-A- 21-STG-STRSA UTOL b00-15/57 27090-0 x EXAMINED 20% '(90") nf WELO STUB BARREL TO SHELL A llTOW UT45 UT45T DEV. 10
)(
)(
X- * - OISTRIUUTEO AMONG THHEE AREAS. ISi SCANNING AREA DID NOT RE~. PEAT THE BASELINE EXAMJNATlON UTbO )( AREA.* WELD WILL BE HESCtlf.- UTbOT *X DIJLEO FOR EXAMINATION IN THE NEXT REFUELING OUTAGE,
.***8ASIC CALiaRATION BLOCK***
PL-3-CS-51-SAH NOZZLE-TO-VESSEL WELDS c1.2 .C-8 J2-MSN-22 ll-1 UTOL b00-15/57 273300 x LIHITEO EXAMINATION FROM THE HEAD TO NOZZLE UTOW OEV. 10 x HEAD SJOE DUE TO INSULATION UT115 )( SUPPORT BOLTS *. NO EXAHINATJUN lJT45T x FROM THE NOZZLE SIDE DUE TU UTbO x THE NOZZLE CUNFIGURArioN. llTbOT. x
***BASIC CALIBRATION RLOCK**-*
PL*CS-4 0 5-68-SAM
SALEM GENERATING STATION, UNIT *2 1984 INSERVICE EXAMINATION CLASS 2 COMPONENTS PAGE 12 r.llEMICAL VOLUME CONTROL TANK (SEE FIG. R-5)
~------
N I 0 0 N G T AS11E ASHE SHHI
SUMMARY
R S E H Sf.CT XI SlCT XI HELO NUMBER ANO/OR EXAM. PROCEDURE SHEET E I OE ITEM NO CAlGY EXAMINATION AHEA IDlWTif ICATIO~ HETllOO NO;/REV. NUMBER C G H R HEMAHKS
------- ------- ------------------------------*------~--
CIRCUMFERENTIAL WELDS --------* --------- ------- ------------------------------------ cl. l C-A 2-CVCT-2 UTOL b00-26/5 275030 x EXAMINED 20% (bO") OF HELO
.SHELL TO LOWER HEAO UT45. DEV. I x - DISTRIBUTED AMONG THREE* AREAS.
lJT45T x ISi SCANNING AREA 010 NOl RE-PEAT THE RASELINl EXAMINATION AREA.* HELD WILL BE RESCHE-DULED FOR EXAMINATION IN lHE "EXT REFUELING OUTAGE.
***BASIC CALIDRAllON BLOCK***
PL*SS-.250-97-SAM INTEGRALLY HELOEO SUPPORTS CI. J
- c-c 2-cvcT-2vs-u2
- PT 200-1156 275040 x - ~ - LIHITF.O EXAMINATION OUE TO VESSEL SUPPORT DEV. 4 J*BEAH SUPPORT LEG.
SALUt GLNERATING STAT ION,' IJNIT 2 lq64 INSERVJCE EXAMINATION CLASS 2 COMPONENTS PAGE t ~ LETOOWN HEAT EXCHANGEHS (SEE FIG. B-8)
N I 0 0 N G T ASME ASHE SWRI SUHHARY R S E H SECT XI SECT XI Wf.LI) NUMBER AND/UR EXAM. PROCEDURE SHEET E I OE ITEM NO CATGY EXAMINATION AREA IDENTIFICATION HETUOD NO./REV. NUMBER C G 11 R RF MARKS CIRCUMFERENTIAL WELDS -------- --------- ------- -------------------*----------------
Cl.1 C-A 2-LHEX*I UTOL OOO*:B/7 275210 x EXAMINED 20% Cl5"J dF. WELO FLANGE TO SHELL llTOW DEV. l x DISTRIBllTEO AMONG THREE ARtAS. UTllS - xx- NO EXAMINATION FROM THE FLANGE UT45T x SIDE DUE TU THE FLANGE CONFIG-UTM URATION. ISi SCANNING AREA 010 NOT REPEAT THE RASELJNE EXAMINATION AREA. WELD WILL BE RESCHEDULED FOR EXAMINAlION lN THE NEXT REFUELING OUTAGE.
***BASIC CALIBRATION RLOCK***
PL-SS-.750-85-SAH
'I SALEH GENERATING ~TATION, UNIT 2
. 1q5q INSERVICE EXAMINATION CLASS 2 COMPONENTS PAGE Iq REGENERAlIVE HfAT EXCHANGER CS£E FIGURE B-10)
N 0 0 NG T ASHE ASHE SWRI
SUMMARY
R S f *t SECT XI SECT XI WELO NUMBER ANO/OR EXAH 0 PROCEDURE:. SHE.ET E I OE ITEH NO CATGY EXAHINAflON AREA IOENTIFICATION HHHOO N0 0 /REV 0 .~UMBER C G H R REMARKS
------- ------- CIRCUMFERENTIAL HfL~S ---------------*~-------------------
c1.1 C-A 2-RHE-1 UTOL b00-30/lb 275300 x *. EXAl'HNEO 20% Cb") OF WHO 015-CAP TD SHELL UTBH DEV. 1, 8 x - TR!BUTED AMONG THRE.E AfiEAS. lJT'tS
- x LIHITEO EXAHINATillN FROM Htf UT45T x CAP SIDE DUE TU lHE CAP CON-UTbO x F IGURATJON. ISi SCANNING AREA DID NOT Rf PEAT THF BASELINE EXAMINATION AREA.
- WELU WILL BE RESCHEOULtO °FOR EXAMINATION IN THE NEXT REFUELING OUTAGE,
***RA~IC CALIRRATIUN RLO[K***
9.s-ss-x-.1so-Rb~SAH Cl.I C*A 2*RHE-5 SHELL TO CAP UTOL b00":"30/lb 275340 x - -.- EXAMINED 20X (b") Of HELO DIS-UTOH
.llT45 UT4ST OEV. 1, 8 x
- x x *
)( - TRIBUTED AMONG THREE AHEAS.
LIHITED EXAMINATION fROH THE UTbO . )( CAP SIDE DUE TU THE CAP CON-FIGURA TJON. ISi SCANNING ARtA 011> NOT REPEAT THE RASELINE EXAMINATION ARE~. WHO HILL BE RESCHEDULED FOR EXAHINAJJON IN THE NEXT REFUELING OIJTAGE.
***BASIC CALIBRATION BLOCK***
9 0 S*SS*X* 0 750*8b*SAH
SAi.EH GENERA TING STATIONi llNIT 2 19dq INSERVICE EXAMINATION CLASS 2 tUHPUNENlS PAGE 15 RESIDUAL llEAf REMOVAL llEAT EXCHANGER (SEE FIGS. A-11,* 12)
N I 0 0 NG T ASHE ASHE SHRI
SUMMARY
R s E H SE.Cf XI SECT XI WELD NUMBER ANO/OR EXAH. PROCEDURE SHEET E I n E ITOl*NU CAlGY EXAMINAflUN AREA IOEIH If JCATlllN METttOD NO./REV. NUMl\F.R c G H R RE HARKS NOZZLE-TO-StlELL HELllS c 1. 2 C-B 21-RHR~EX-OUT UTOL bOO-H/7 21sqoo x LIMITED EXA~INATION fROM THE 1 urow DEV. 1 x SHELL SIDE DUE TO THE PRUXJMI-llT45 x TY OF THE FLANGE CIRCUMFEREN-UT4ST x TIAL HELO AND SUPPORT PLATtS. lJThO x NO fXAHINATION FROM THE NOZlLf
. SIDE DUE TO THE NOZZLE CONFIG-URATION.
***RASIC CALIBRATION BLOCK***
PL*SS-.750*85-SAM
I SALEH GENERATING STATION! UNtJ 2 1964 INSERVICt EXAMINATION CLASS 2 COMPONENTS PAGE 16 fEEl>WATER SYSTEM N I 0 0 N G T ASHE:: ASHE SWRI
SUMMARY
R s E H SECT XI. SECT XI HELO NUMBER ANO/UR EXAM. PROCEDURE SHH T E I 0 [* ITEM NO . CATGY EXAHINATIUN AREA IOENTIFICATION HETtlOO c RE HARKS N0 0 /REV * . NIJHf.llR G H R 14-BF-2231 (PSE&G #l4"-2BFI017J (SEE -------- FIGS~ 8*14, --------- 15) c2.1 C-G 14-Bf-2231-11 UT45 b00-3/bl 330440 x ANGLE BEAH SCANS PE::RFOHMED PIPE TU ELBOW UT45T OEV. 15 .X FRUH THE llPSTREAH Sll>E ONLY IJlbO x TO COHPLETE THE EXAHINATION REQUJREHENT, ALL OTHER SCANS WERE PERFORMED DURING THE APRIL 1984 OUTAGE AND. REPORTED IN THE SALEH UNIT l SPECIAL REPORT o*TED OCTOBER 19R4.
***BASIC CALIRRAllON ALOCK***
lb-CS*l60-l.bl0-34-SAH C2. I C-G 14-UF-2231-17 UT45 b00-3/bl 330530 - - x- ANGLE BEAM SCANS PERFORHED PIPE TO ELHUW UT45T DEV. 15 X FROM TliE UPS TRE AH S Il>E ONL V UTbO x 10 COMPLETE THE EXAMINATION REQUIREMENT. ALL OTHEk SCANS WERE PERFOHHEO OURING THE APRIL 1984 OUTAGE AND REPORTED IN THE SALEH UNIT 2 SPECIAL REPORT OATED OCTOBER 198q,
***BASIC CALlBHAllUN BLOCK***
lb~CS*lbO-l,blQ-3ij*SAH c2.1 C-G 14-UF-2231-18 UT4S b00-3/bl 330550 x- ANGLE HEAH SCANS PERfORHEO ELBOW TO PIPE UT45T DEV. 15 - X FRO" THE OOWNSTREAH SIOE ONLY UTbO x. - *- - TO COMPLETE THE EXAMINATION HfQUlREHENT, ALL OTHER SCANS
*wfRE PERFORMED DURING THE APHJL l98U OUTAGE ANO REPOHTEO IN THE SALEH llN IT 2 SPEC JAL HEPOkT OAJEO OCTORER 1984.
***BASIC CALIBRATION BLOCK***
16*CS-lb0-1.bl0*3q-SAM
SALEH GENERATING STATION, UNIT 2 1984 INSERVICE EXAMINATION CLASS 2 COMPONENTS PAGE l7 CHEMICAL ANO VOLUME CONTROL SYSTEM
*--------- N I 0 ASHE 0 N G T ASHE Si'IRI SllHHARY R s E H SECT XI SECT XI WELD NUl'IDER ANO/OR EXAM~ PROCEDUHE SHEET ITEM NO E I 0 E CATGY EXAMINATION AREA IOENTIF ICA T ION c G, 8-cv-2201 IPSE&G #8"-2SJll09]
HETHOO N0 0 /REV 0 NIJMBER (SEE FIGS. e-20. 21. 22) ------- H R RF MARKS C2. l C-F a-cv-2201-19 . UTOL p !PE TO ELtrnw 800-3~/?.8 360190 x- EXAMINATION SCttfOULED IN AC-Ufll5 l>EV. Jq x - CORDANCE WllH IE RULLETJNS UTllST x 'Tb-06 AND 79-17 0
***BASIC CALIBRATION ALOCK***
a-ss-10-.1110-211~sAH C2 l 0 C-F 8-CV-2201-27 llTOL 800-36/26 160270 x PIPE TO ELBOW EXAMINATION SCHEOULEO IH AC-llT45 DEV. Jq x- CORDANCE WITH If BULLETINS UTllST x - 76-06 AND 79-17.
***BASIC CALIBRATION 8LOCK***
R-ss-10-,1110-24-SAH C2 .1 C-F 6-CV-2201-36 IJTOL 800-36/28 360360 x LIHlfED EXAMINATION FROM THE TEE TO VALVE UT45 DEV. 14 - x UPSTREAM SIDE DUE TO THf PkOX-UT45T x- IMl TY OF A WELDED PIPE SUP-PORT, NO EXAMINATION FRU'1 Ttlf DO~NSTREAM SIDE DUE JO THE VALVE CONFIGURATION. EXAMINA-TION SCttEOULEO IN ACCOHOANCt WITH IE BULLETINS 7b-O& AND 79-17.
***"ASIC CALIRRAllON BLOCK***
s-ss-110-.JlO-Q4-SAM .
SALEH GENERATING STATION, UNIT 2 l96Q INSERVICE EXAMINATION CLASS 2 COMPONENTS PAGE 16 HAIN STEAM SYSTEM N I 0 ASHE ASHE 0 N G T SWRI
SUMMARY
R 5 E H SECT XI SE.CT XI *WELD NUMBER ANDI OR EXAM. ITEM NO PROCEDURE SHEET f I 0 E
------- ------- --------------------------------------- -------- --------- ------- c- - -,.. . -
CATGY EXAMINATION AREA IOE:NTIFICATION 8-HS-22Q2 (PSE&G #8"-2HSll58l METHOD (SEE FIG. U*J8) N0 0 /REV 0 NUMBER G R RE HARKS
-----------------------------------~-- -----~-.
C2.4 c-o 8-HS*22Q2-2FB VT 900-1/50 382515 x - FL ANG[ BOLTING VT PERFORMED ON 12 SlllDS ANO 24 NUTS (100%) IN PLACE. IJTO 600-36/6 x - UTO PERFORHEO ON J STUDS JN lJEV. l PLACE. UTO 600-3715 x UTO ANO UT45 PERFORMED ON J IJTQ5 DEV. 5 x NUTS IN PLACE.
***BASIC CALIBRATION BLOCK***
1 0 625-8*S-CS*8Q-SAH 1 0 625-6-N*CS-92-SAH 8-MS-2212 [PSE&G #8"*2HS106JJ (SEE FIG. B-41) c2.1 C-G 8-MS-2212-1 WEl.OOLET TO ELBdW UTOL 600-3161 384000 x NO EXAMINATION FROM THE UP-UTOW DEV. 15 x STREAM SIDE DllE TO THE WELDO-UT45 x - LET CONFIGURATION. . UT451 )( U160 )(
***BASIC CALIBRATION RLOCK***
s-cs-a~o-.906-Q6-SAH
SALEM GENERATING STATION, UNIT 2 lqaq INSERVICE EXAMINATION CLASS 2 COMPONENTS PAGE 19 PHESSllRIZER RELIEF SYSTEM N I 0 0 N G T ASHE* ASME SWRI
SUMMARY
R s E H SECT XI SE.CT XI WELD NUMB EH ANO/OR EXAM. PROCEDURE SHEET E I 0 E llfM NO CAlGY EXAMINATION AREA lOENTIFICATION HETttOO NO.lt<EV, NllHf\ER c G MR RE HARKS 6-PH-2203 (PSE&G #6"*2PRlOOSJ (SEE FIG, 0*51) C2
- t C-f b*PR*2203-:b UTOL 800*36126 500870 x ELBOW TO ELBOW UT45 DEV. 111 x UTllST x Urt<f\ASIC CALIBRATION BLOCK***
b-SS-40-.2R7*2b*SAM b-PH-2202 (PSE&G #b"-2PR1003J (SEE FIG, 8*52) c2.1 C-F b-PR-2202*1 llTOL 800*36/28 501000 x REDUCER TO PIPE IJT45 DEV. 111 x UTllS.T x
***BASIC CALIRRATION RLOCK**~
b*SS-110*,287*26-SAM
I SAL.EH GENERATING STATION~ U~IT 2 1984 INSERVICE EXAMINATION CLASS 2 COMPUN~NTS PAGE 20 VALVES N I 0 0 N G T ASHE ASME SHRI
SUMMARY
R S E H SECT XI Sl::CT XI HELO NUMBER ANO/OR EXAH 0 PROCEDURE SHEET E I 0 E ITEH NO CATGV EXAMINATION AREA IDENTIFICATION MEHIOI> NU /REV NUMBER C G H R REHARKS BOLT ING 0 0 C4 2 0 c-o 21 MS 12 VT 900-1/50 bo1qoo x VT PERFORMED ON b STUDS ANO ON LJNF. 8-HS*2212 b NUTS (IOOX) IN PLACE. (SEE FIG. 8-111) UTO b00*3b/b x- UTO PERFORMED ON 2 ST~DS IN DEV 0 I PLACE. UTO b00-37/5 x UTO ANO UT45 PERFORMED ON 2 UT45 DEV. 5 x NUTS IN Pl.ACE.
***BASIC CALIRRATJON RLOCK***
1.12s-a-c~-B7-SAH l 0 l25*R-N*CS-l01*SAH c-o 22-RH*ll VT 900-1/50 b02ll50 - - - x SEE CNF 84-2-001. ONE VT IN-ON LINE l4-RH-222q DICATION ON STUD N0 0 14. IN-
<SEE FIG. B-5q) DICATION HAS EVALUATED AS AC-CEPTABLE BV PSE&G ANO NO REEX-AHINATlON WAS PERFORMED. VT PERFORHEO UN 20 STUOS* ANO 40 NUTS (100%) IN PLACE.
IJTO b00-3blb x- - - UTO PERFORMED UN 2 STllOS IN DEV. l PLACE. UTO b00-37/5 x UTO AND UT45 PERFOHHEO ON 4 UT45 OEV 0 5 x NUTS IN PLACE.
***BASIC CALl8RATION BLOCK***
1.12s-e-N-cs-101-sAH 1.12s-e-s-cs-10J-SAH
APPENDIX A . CLASS 1 WELD IDENTIFICATION DRAWINGS .
* .l
- -* _..; . . ." - :...*"'."* -*it.,.* - ... ,. - **. :- .. ~
- APPENDIX A CLASS l WELD IDENTIFICATION DRAWINGS
*
- Table of Contents Figure Title Page Symbols for Weld Identification . A-iv Examination Area Identification System A-v
- A-l Reactor Pressure Vessel A-1 A-2 Reactor Pressure Vessel A-2 A-3 Reactor Pressure Vessel Closure Head A-3, A-4 Control Rod Drive ilousing A-4 A-5 Pressurizei * ** A-5 A-6 Steam Generator No. 24 A-6 A~7 Steam Generator No. 23 A-7 A-8 Steam Generator No. 22 A-8 A-9 Steam Generator No. 21 A-9 A-10 12-CV-1243, 3-CV-1243 A-10
.A;...11 3-CV-1243 A-11
" A-12* 3...;CV-1241 A".""12 A-13 3-CV-1231, 1 of 2 A-13
- A-14 3-CV-1231, 2 of 2 .A-14 A-15 3-CV-1275 A-15 A-16
- 2-CV-1275. A-16 A-17 6-PR-1205 A-17 A-18* . 6-PR-1204 .A-18 A-19 6".""PR-1203 A-19 A-20 4-PR-1200 A-20 A-23 3-PR-1207 A-21.
A-24 3-PR-1206 A-22 A-25 14-PS".""1231 A-23 A-26 4-PS-1231, 1 of 2 A-24 A-27 4-PS-1231, 2 of 2 A-25 A-28 4-PS-1211 A-26 A-29 31-RC-1240* A-27 A-30 31-RC-1230 A-28 A-31
- 31-RC"."'1220 A-29 A-32 31-RC-1210 *A-30 A-33 *29-RC-1240 A"'."'31 A-34 29-RC-1230. A-32 A-35 29-RC-1220 . A-33 A-36 29:...RC-1210 A-34.
A-37 . 27 .5..;.RC-1240 .. *A-35 A-38 *27.5-RC-1230 A-36
*A-39 27 .5-RC-1220 . A-37 A-4o* 27 .. 5-RC-1210 A-38
~ .. ,.: A-41
.*A-42 3-RC-1243 3-RC-1233 .. .' ..:;::'.,)
A-39
. A-:40.
* "A-f, l
-~
\" *f.*--:0
-- : -- ... '
- i;,. * *~'...*-
.*~:;:-- -,5*:~ .
.- .... :--- -- *-::_-;- *-**;~'"".""" .
APPENDIX A
.CLASS 1 WELD IDENTIFICATION DRAWINGS r-Table of Contents (Cont'd)
Figure Title Page A-43 3-RC-1223 A-41 A-44 3-RC-1213 A-42 A"."'45 2-RC-1244 A-43 A-46 2-RC-1242 A-44
- A-47 2-RC-1241 A-45.
A-48 2-RC-1234 A-46 A-49. 2.-RC-1232 A-47 A-50 2-RC-1231 A-48 A-51 2-RC-1224 A-49 A-52 2-RC-1222 A-50 A""".53 2-RC-1221 A-51 A-54 2-RC-1214 A-52 A-55 2-RC-1212 . A-53
. A-56 2-RC-1211 A-54 A-57 l-RC-1241, l-RC-1242, l-RC-1243 A-55 A-58 1.;,.RC-1231, l-RC-1232, 1-RC-1233 A-56 A-59 l-RC-1221, 1-RC-1222, l-RC-1223 A-57 A-60* 1-RC-i211, 1-RC-1212, l-RC-1213 A-58 A-61 14-RH-1211 A-59 A-62 12-SJ-1251 A-60 A-63 10-SJ-1241 A-61 A-64 10-SJ,-1231 . A-62
- A-65 10-SJ-1221 A-63 A-66
- 10;;.SJ-1211 A-64 A-67 8-SJ-1262, l of 2 A-65 A-68 8-SJ-1262, 2 of 2 A-66
- A-69 8-SJ-1252, l of 2 A-67 A-70 8-SJ-1252, 2 of 2 A-68 A-71 8-SJ-1245 A-69 A-72 8-SJ-1235 A-70 A-73 6-SJ-1242 A.-71 A-74 6-SJ-1241, l of 2 A-72.
A-75 6-SJ-1241, 2 of *2 A-73 A-76 6-SJ""".1232 A-74 A-77 6-SJ-1231, 1 of 2 A-75 A-78 6-SJ-1231, 2 of. 2 A-76 A-79 6-SJ-1222 A-77 A-80 6-SJ-1221 A-78. A-81 6-SJ-1212, l of 2 A-79 A-82 6-SJ-1212, 2 of 2 A-80 A-83 6-SJ-1211 A-81 A-84 4:-SJ-1293, 4-SJ-1295 A-82 .
\
\
A-ii i*
~~- *i
~~ . -~
* -- -~CLASS APPENDIX A 1 WELD IDENTIFICATION DRAWINGS
~able of Contents (Cont'd)
Figure Title Page A-85 4-SJ-1294 A-83 A-86 . 4'."'"SJ-i282 . A-84 A-87 4-SJ-1272 A-85 A-88 3-SJ-1292 A-86 A-89 2-sJ-1249 , 1 of 2 A-87 A-90 2..:.sJ-1249, 2 of 2 A-88 A-91 2-SJ-1247 A-89 A-92 2-SJ-1239 A-90 A-93 2-SJ"."'1237 A-91
- A-94 2-SJ-1229, 1 of 2 A-92 A-95 2-SJ-1229 , 2 of 2
. A-93 A-96 2-SJ-1228, 1 of 2 A-94 A-97 2-SJ-1228 , 2 of 2 *
. A-95
" A-98 2-SJ-1219 A-96 A-99 . 2-SJ".'"1218, 1 of 2. A~97 A-100 2-SJ-1218, 2 of 2 A-*98 A-101 l.5-SJ-1242, 1 of 2 A-99 A-102 l.5-SJ-1242, 2 of 2 A-100 A-103 l.5-SJ-1232; 1 of 2 A-101
. A-104 l.5-SJ-1232, 2 of 2 A-102 A-105 l.5-SJ-1222, 1 of 2 A-103 A-106 l.5-SJ-1222, 2 of 2 A-104
. A'."'"107 l.5-SJ"."1212, 1 of 2 A-105 A-108. l.5-SJ-1212, 2 of 2* A-106.
A-109 Reactor Coolant Pumps A-107
- .,. A-iii
.. \
. .1
~~ *-~,~ _*~ .~*
~*
-~ ... ..-
l_*_____ Bend
- -{(!) @~Lins Continuation Branch Catmecti011, Raquiras .
l ~ti011 With Brauch _ _ _ _ _ _ _ Line Shown in Dcta:U Penetl:'llti011 of iiall, Floor, acc. . Lina No. Branch Connecti011, Requiras
;-* Ezaminaci011 With Branch
_ _ _.,.** *.___ _ Lin* Shown 011 Another Isom.cric
---)-"_..<"---Pipe Lug(s)
Lina Sizs
'1' Branch Cotmecti011, Does Not
--....c6;...;.____
I
---~*-----Require E:uminati011 p1pe Restraint, Not "1elded
_ _ _**.__ _ Butt Weld _ _ _ _ _ _ _ Pipe Support, Welded T (]-------Cap E) Pump . 4 .Class Boundary Clus~sY .,
-c.......,.Raducer AI B-
)::::( Coupling, Socket Welds
- "\ Socket Weld
--~'-,::;;;;;+--Coupling,
,.._ Butt and Sockee W"elds Reliaf Elbow
~Valve, Check
_....:,n::;O:::;W::_-;:!11- now Diracei011
~Valve, Globe
- - - f - Line Break
---{><---Valve, Other slMBOLS FOR WELD IDENTIFICATION A-iv
,~'.:::.-"' >-~~
~;;
- 1. -
Vessels Examination Area Identification System For Vessel examination area, the following format is used: A-B-C where: *A is the number "2" and denotes Salem Unit 2 except for nozzles and SteamGenerators. For nozzles, A is the same as the connecting line size. For Steam Generators, A is the same as the Steam Generator number. where:.* B denotes the vessel, as follows: PZR - Pressurizer PRN Pressurizer Nozzles RPV Reactor Pressure Vessel RPVCH Reactor Presure Vessel Closure Head RCN Steam Generator Nozzles
. STG Steam Generator where: C is a unique number or letter identifying the examination area. For RPV circumferential, .meridional, and longitudinal
*welds, C is the same number*that Westinghouse-assigned to the weld. C ends in IRS for inside radius section examination areas.
Examples: 2-RPV-2042A T...._*__________ unique Number (Westinghouse number) T -
------------Unit 2 Reactor Pressure Vessel 21-STG-25.
T*T. T_.- --
--~~~~~~~~~~~~steam Generator No. 21 Unique Number Steam Generator 4
N-t.:_3
/
1 -TPR. _-T_R_S_.*_ _ _ _ _ _ *Inside Radius *Section
--~~~~~~~~~~~~-Nozzle for 4-in. Line Unique Number Pressurizer Nozzle A-v.
. -~
... , ~
'i. ~*-* .': i~
; ~I
.t"~
- 2. Piping For piping welds, the foll_owing format is used:
AA-BB-CDEE-F~(-G) where: AA denotes the nominal pipe diameter of the line. ., where:. BB denotes the ptp~ng system associated with the line ,*i (determined by PSE&G valve nomenclature),* as follows: BF Steam Generator Feed. CS Containment Spray CV Chemical and Volume Control System MS - Main Steam PR - Pressurizer Relief* PS Pressurizer System RC - Reactor Coolant RH Residual Heat Removal SJ Safety Injection where: c has the following options:
*where:
- where:
1 2 EE Class 1 examination areas
. Class 2 examination. areas*
D is the integer 2 and denotes Salem Unit 2. is two integers asigned to assure uniqueness. For the Main Reactor Coolant Loops, the first integer correlates with the loop number and the second integer is zero. where: F is assigned to assure uniqueness- and to ~esignate the type
- of weld as follows:
a *. If only a one- or two-digit integer appears~ this indi~
- cates a circumferential weld. The welds are numbered consecutively in the direction of flow. Where the direction of flow is ambiguous, a flow direction is a~sumed.
- b. _For other than circumferential welds,*except branch
_connections, two letters are added to the circumferen-tial weld number which either intersects the weld (in the case of the longitudinal welds) or is *upstream from the component, as follows: FB - Flange Bolting LU - Longitudinal Seam Weld Extending Upstream
- _LD - Longitudinal Seam Weld Extending Downstream PL - Pipe Lug-. (Welded).*..
PS
- Pipe Support (Welded)
..-\.'i
' *j
/
*A-vi
.* ..Ji.*_* .
. . ~ ...
.I I
- SC - Support Component .Portion of A Welded Pipe Support PR Non-Welded Pipe Restraint where.r G-is an integer assigned when there is more than one compo-nent [see (2) above] of one type or a longitudinal weld between successive circumferential welds. This number in-
- creases either sequentially from the upstream weld or clock-wise from Lo, a standard reference location used for piping_
(see examples). On double seamed elbows, the weld located along the outside radius is denoted by the letter "O", and the weld located_along the inside radius is denoted by the letter "I". Example: AA.:.BB-CDEE-8
.. AA-BB-CDEE-7PL-3 AA-BB-CDEE-7PL-1 AA-BB-CDEE-7PL-2 AA-BB-CDEE-7 For branch connections exceeding 1-in. diameter nominal pipe size for Class 1. and 4-in. diameter nominal pipe size for Class 2, both. the main run and branch line are identified and separated by a diagonal slash (/). _To locate the branch connection,. the upstream circumferential weld on the main run is also identified.
Example: 29-RC-1210-2/14-RII~llll is the branch connection from the line 29-RC-1210 downstream from weld Number 2 which connects line 14-RII-1211.
\
- A-vii
,p_
'~~ ... ,. . *,*\
- .~.~. .t<_:~*::t
.:~
' .. ~ .
. ---~-,----- --------- *--,-*~---------, ----;--
i.
- 3. Pumps The RC pump examination areas are each identified by a two-digit number which ~deritlfies the pump number, i.e., 21, 22, 23, or 24. Follow-ing the pump number are the three letters "PMP".used with the RC pump iden-tification and a group of numbers and/or letters making each area uniquely numbered. rhe RH pumps are identified similarly except that the three letters are "RHR".
Example: l-~-~-W~~~~~~~~Unique T 2 letters (flywheel)
- _ Reactor Coolant Pump
""-~~~~~~~~~~~~-Reactor Coolant Pump No. 21
\
\
*:.. _-::.... * *t
*.****/ *' **
oo I f!rv-'tH 2. j*
~
Z-Rl'V-Bt'l 2.
.2.-KPV-111-2.C 2.-RPV-1'112.B J____t----'----r--~~*--=----2_-R_r_v--l~11_.~_c~~-----_2_-R_r_v-_l~1~1-~._a_*__ --1
--2.-RPV-3112.C~ 2.-RPV-3*11*2/f -.-
J_______. ~~Q0_ ..** ______ 27_Q°_ _______ ?IO" ___-*-l-~;:::~ 90'
~5-C~Cl.-42-SAH l l-CSCl.-5 3-SAH ---~_-l{PV-.ll*H.
/ ..
9-CSCI.~ 54-SAH l h l l-CSCl.-62-SAH l-Rrv -l*l*Ht~ :> - t(l'\H113C
! - ~l'V-1-t *Hi! - 2-1\1'\i-l-H ~-U>
~-l~PV-H*1*u- 2.-Rij,V-1-t *1.iE
_PSl!4G No: Reuclor hestmre Veasel PSD4G Pwg: Thlcknoss: __ _
*~-----------~----------.----~-----ti Sl*ll I No: lt~actor l'reasure Veusel Bauic Cal. Blk. 1 See Above* l'lguro: A-1 1_~; !:.~.,:L .: .* : *- __. ~.:. *. .ri- ** -**-"
/
,/
)L0° l'l-RC-122.0-1 . 1eo* 2.1-RC-1230-1 o*
I 'H.!;-({( -122.0-5 21.5-KC-IZ.30-S I I
-r . ,._____..
1 17.S-Rl-l 210-5 21.s-Rc-12*1015 I 85-S/6" _J___ l'H~l-1210-1-- ~ 4__ :' ~ Q'j ~ :* @. ~2Ht:-1210-) 2H'(N*1Z10*l((*;/1_ _*_ __._,____ ,_,,___-1--11--1---..-1----1f-&------1~2'1-WM210-U!S
'lf.5- ftCN-lllO-J~S -Z1.5-RCtMZ10 IRS 2l5-RCN-1220-IlS 2.1.5-RC.N-1230-IRS 2.'l-RCN-122.0-US-**--- ---*-2.'t-RCl.J- I l 30- IRS
*lll-CSCl.-11-SAH (lllS Secttona) 2.112-SS-11-SAH (Nozzle-to-Safe Enda) 1*1.-cs1a.-l.0-16-SAM (No:t:do-to-Sufe Enda).
-r::-:::-:::-:~-=--~-~~~~~~~-.-::-~-.-~-~~~~~~~~~~~~-1 l'SU4G Ho: Reactoa- l'n:ueuro Vetted l'SD*G Pwa: ---- fbld.noss:--
Swll I tlo: llcuctoa- l'a-cuoua-e Vc11uil 1 Baatc Cal. Olk. a Soo Abovo* Plsuro: A-l
i i 1 (Top Vat:.w) 1 I <too 2-RPVCH-&11*l.B--* 8 I! ***4-*-- ft ti - '
*!, I .. __..-- l1rnt1& LuG.
2.-R PVCM-11tC.C----~ m e g
---Z. -RPVCH-1-l-t (,b I
2- RrVcH-lttt £
- -100°.
[ :t.a.-J_ _....__.__ 'l- Ri>VCH-PATCH I rn.:11 l (L n1. sq. fll.- .I.mo,)
'l.-IWVCH-111l8--/
l ..
*7-CSCL-50-SAH (Clooure lleud Meridional.Welde) 9.561-7-8-CS-59-SAH (Nute) 1-1.125-8-CS-60-SAH (Studs.and Ligaments)
I , PSUfHi No: RPV Clooure lleud PSIHlG Pwa: --- 8wll I No: IWV Clooure lleud Da1tia Cd. Blk. 1 See. Above* Plguro :. A-l
.\ "':.:
! ... :~;~*;. *:
'~.-
.L t-..2r:._. c," *' *~ .* ' ' I ;,
- _, ~ ' *** * (
.I I
I I PSIH&G No:Control Rod Ddve lhmge. PSBliG DWI:----- hlclness : __ .... _ Swill No: Control ltod Prive Henge. Bade Cal. Blkd CRD-SS/IH-.625"'."'81-SAH Plguro: A-4
/ *
/
_). 2.- P?.R-rtlTCH I 2.-PZR-C lRC-()lJH
<D* 5'/'\.l5")
~-PRN-1201- IRS z-rzR-LONl~ D t-PR-1203-1 I (A** -u* OR -31. 1*) *.
z-ru~~c1Rt co
*(D"151.0011)
I kPR~J-1203-IRS SHELL () I i-('R-1201-1 I 2.-P'ZR-LONG C. I (/\*&f1S* ill\. HC..s*) I SHELL C !-P!R-CIRC BC t-PR-12.05-1 I (0" 12.1. SC."J
. i-PSN-12.31-JRS ~
. 1..11 I Z-PZl{-LONG B 1-PRN-12.00-.IR'.i SH£LL f\ (f'*,. -3* 0 Ok- 2.E.I") I 2-P?.R-f.JRC f\B I (I)"' 1'13.00 ") I 2_-PIR-LONG II 1-PS-1231-33 (ti** tl8* Olt +'l 2 .1*) I I
--~-PZR-MB I-lb SUELL A 2.-PlR-lIRC Lllll I ((); (;,1 .... 5 ")
I I /
*5-CSCL-42-S.UI (Circ *. & Long. Welds) . /,--
Pl.-l.5-cs...:.65-SAH (Skirt Weld) 11 -P~N-11~1-IRS----- -----* . 14-SS-140-1.25-77-SAH (Nozzle) Ul-CSCL-84-SAH (Nozzle lllS) 4-SS-160-.551-28-SAH (Safe-Ends) 4 * .5-SS-XX-1.0-71-SAH (Safe Ends) 6-SS-XK-1.5-64-SAH (Safe Enda)* rse~G No: Pressurizer rsegG Owg: Wat hae. 44S2D51 fla 1ckne55: Swll I No: l'restmrh:er Bade Col. Jtlk. 1 . See Above* Pigure: , A-5 ,
' . ., ; . ~.' ~' . .. ..
/
/
/
SUELL I> 31-STG-12.iO-lRS. SUELL C l.'t-STG-12.40 -IRS 3t-RC-,2:to -1. TRRNSITJON 2.1-RC-12:10-5 CON::
. 315° - - - SllEU. D 2t- STG-Of'18(8omJJG)
.SUELL It 2:f-STG-:CMB{Bom"o)
STUD Oil RRl::L LowEn lfEAO * ~~[ CUISiS I 1una: s11£E1 ,-2.1-s TG-uns GI-. B*- - 21*- s n. - PRICH 1
............._ -, .._2t- s rG -r1nct12.
*5-CSCL-42-SAH(Ctrc. Welda)
IR-CSCJ.-84-SAH(Inner Radtua Section Wolds) 7~CSCL-50-SAM(Innur Radius Section Welds) 2.312-SS-37-SAH(Nozzle-to-Safo ~nd Welds) PSIHlG No: Stoaw Generator 124 PSD*G Dws Z 1098J17(11ot lase. Fla.) blcknoss: - - - - - - - - - Swll I No: Stea1u Generator 124 Basic Cal. Blk.1 Seo.Abov~* Pl guro: A-6
- *c" ;.:
.* .: . *{.~,").*' ~
~ ~L~g~ .,_...~._,_.;> ;~.
-~
_) .) Ii'I i SUELL I> 31-STG-12.30-:- IRS .SUELL C
'2.'l- STG- 12.30 -IRS 31-RC'.""" 1230 .-1 TRANSJTJON CONE l'l-RC-12..30 - 5 Ourur MA,.WAV SHEU. 0 385° - - - - - -135°.
SUELL ll 23-STG-IHR(BoLtlJJG) STUD DllRR£L
~r lUllf SUEEl.I ,.-_.:.ll-STG-UHS
- LowE:R *HERD - CU*SSI _
GI--... El- - l3- s Tti -P/llCU I
..__ -:-- ~ TG -l'iaJCl-t 2.
*.5-CSCL-42-SAH(Ctrc. Uelda)
Ill-CSCJ.-84-SAH(Inner Rudiua Section WeldB) 7-CSCL-.50-SAHJ(Inner Rudtuo Section Welda) 2.312-SS-37-SAH(Nozzle-to-Safe End Welda) PSl!l1G No: Stea1u Generator 123 PSIHIG Pwg: 1098Jl7 Wat hoe. Fla. 'hlcknoss: ---------------~ Swll I No: Steam Generator IJ23 Daatc C8l, IUk, a See Above* Pigure: A-7 I ;.- !.-'-~.:;:_. - *, -** :'. '. ,..._
/
/
St-If LL l> 31-STG- 12.20- IRS .SHELL C 1.'\- STG- n..'l.0-IR.S 31-RC-12..20 - I TflllNSJ 1 JON Cot£ ll-RC-12.20 - 5 SUELL 8 315° - - - - - -1'35° 2.2. - STG -OH8(8oLT1t1G) SUELL ll
'" l2.-STG- IHB(6oa.11a.a)
.STUO 811 URE.L 1u1u; S11£E1 . . --tl-s TG -un s LowER l~EAD Q El* - tl- s T~ --1*11TCll I
~ * - t.2.- ~T
31-STG-12.10-IRS 51 l[ll (
'2.'l-STG-11.IO-:r~s
. 31-RC-12.IO-I TflflNSl TION l'l-nc- 12J0:-5 CONE 315° - - - -*--135° SHELL 0 21- STG-OM6(8oLTIUG)
SUELL A
.ir.i'* 21-STG-IHB(60Ll1ua)
Ii"" Sl"UU 011 RR£L
~[
CLASS 8 lUIU~SilfEl ~ -l.1-SIG-UITS EJ-- - 21-ST~-PllTCHI
*5-CSCL-42-SAM(Circ. Uelde)
Q
----- -...._ l.1- ~ilG --f'IHCIH
- lll-CSCl.-84-SAl!-l(Inner lladiue Section Ueldu) 7-CSCJ..-.50-SAH(Inner lladiue Section Welde) 2.l12-SS-l7-SAH(Nozzle-to-Safe End Welde
- l'SH&G Ho: Stemn Gruieq!fOf 12
. Swll I Ho: Steu111 Generator 121 PSD!lG Dwg: 1098.J h clcnoss: ...-...------- ..-..-....
Basic Cal. Blk. a* See Above* Flgure;A-9
~*. * ' ...., *- .\ :., ** .,. > - ,:,_,_.;,_., * * * * ' * *
,: .* t.'. ~* ....**
*l.112 11 (12") .
l.00011 (4.5 11 ) . 0.418 11 (311 )
*12-SS-160-1.238-21-SAH l-SS-160-.451-10-SAH 4.5-SS-XX-J.0-71-SAH
*l>-SlflfC: f!-2cvr - . cvrro
- 1
*SwRI: 12-CV-1241 3-CV-1243 3
Pago I of 2
~*--*~~-~~~~~~~-.-~~--~~~~~~~~.,--........,,~--,.-~~~~~~~~~~~*
l)SIHHi Ho: *Soo Abovo PSUl\G Pwa:RC-2-3/19,CV-2-3/2
". :Ind.le. rirt. Tunlic.l lalclno:u: See Above Swll I No: *Seo Above Dade Cal. Olk. a See Above . 111 guro: A-10
\.;::_
* ~*.
., J
1 . l
~
~
l'ngo 2 of 2
- i1*lll Ho: l-C:V-1241 Daotc Col. Blk.; l-SS-160-.4~1-10-SAH Plg11ro: A-11 i ."
i..:. ,.i,;,.,;;:__1;..~r- ~.-: *.*.. ...;:, .. .. ~.: .** ,. . ~ **** - * * * *- ~. ~.. ** - * - - * --~ .: ;*_ **'- * * *
- c ** * ** ..... .. ~ ..:__ : ...:: ' ::.:..;. .._:. ..... . . .
/
,.,,/*
\
,o Cf L.:"99') _..,.
~
-~)
PSU4G No; l"-2CV1000 rsn4G nws: cv-2-l Sht. 2 hlcknoss: 0.43811 SwHI .No: 3-CV-1241 Oaatc Cal. Dlk.i l-SS-160-.451-30-SAH Piguro: A-12
._)',
\ *.*:~
. "~:.
t ~ j ; !.,,:,,;; ,, ....
)
\
lI i . 'i. 1*ugo I of 2 PSDQf; No; l 11 -2CV1066 PSHllG Owg; CV-2-3 Slat.* 2 fhlcknoss: 0.438 11
\ ....
Swlll No: l-C:V-1231 . Daetc Cal. Blk.s l-SS-160~.451-lO-SAH Piguro: A-ll
,.-1, ... '
. / ' ~~
/
- \
.'15"
- . 'r '" .',:*
I~ I 11 lb
.~ .
,,.'Z, 1ffl II rsuau No: l"-2cv1066 rsngG Dwg: CV-2-3 Sht. 2 hlckness:
- h1lll No: l-CV-1211 Basic Cal. Dlk.1 l-SS-l60-.4Sl-l0-SAM 11ignro: A-14
* - ....1 - -, -
~£l
*""*l,.J ispR I
~s
.~
. .... ~ 6 I
- Pagu I of 2
- _1_*s_n_lir._._N_o_:_2_*0_-2_c_v_1_1s_6_ _ _ _ 11 sH4 r. llw a : c v l / 2 6, nc_ l / 13 h l ck nos & : o_.l_4_4_"_ _ __.,._
Swttl No: 2-CV-1275 Daalc Cal. Ulk.r N/A 11 1 gurc: A-15 l - , .
.L ** .. !;!.. . ... . . . '-* .
/ '
- r .
I-' . CJ\
- (EL. l~8'-o")
Paco 2 of 2 1*s11n(i No: 2 11 -2CVI 156 PSll4G Pwg: RC-2-3 Sht. 13 hlcknoss: 0.344 11 SwHI No: 2-CV-1275 llaelc Cal. Blk. I 'N/A Plguro: A-16
. /.,**.
) * * ...
s 3
*,.}.;._**
....:r N
8 i . 1 * /,
,../* . I lt 9 I I
I: I 1'
' . (. *..t)* I I.
.lff:-l:>'l I
*6-SS-160-.764-25-SAH 6-liS-IX-l.~-64-SAH
~:.
PSUliG No: 6 11 -2PS10l6 PSH4G. llwg: llC-2-l Sbt.l h cl Hess zo .. 119"(160), 1.2011 (n)_._ Swttl No: 6-PR-1205 Dnalc Cal. Blk.1 See Above* Plguro: A-17
. {*~.
~I
.. \ . "::'
.. i 8
I I I I I
-L
*6-SS-160-.764-25-SAM 1**
6-SS-Xl-1.5-64-SAH PSUQG No: 6"-2PS10l5 PSD4G Pwg: RC-2-l Sht. 3 Tb clnoss: 0.119"(160 1 1.lO"(IX)
- Swhl No: 6-rR-1204 Doalc Cal. Olk. I 'Seo Above* Pl1uro: A-18
t: .... *
.2.. p~ . .
.* 'a KJI- - - - - - - -1 I
~
f6 f3.10 ,v Sp l'I i: I!.
\§ ..~
06~ I 1. I I I I I I I
-I I
111 46-SS-160-.764-25-SAH 6-SR-Xl-1.5-64-SAH PSDijG No: 6"-2PSI034 PSDllG Dwa: RC-2-l Slat. s Swill No: 6-l'R-1203 Oaeic Cal. Olk.a See Above* 1:1guro: A-l 9
/ ~.
./ :_..
_../
.\ '
(ll) I I I.
>I N
p
-~*
/*"
P.-.cssutltc.r PSIJ~G No:. 4 11 - 21'Sl026 PSDIG Pwg: RC-2-l Sht. S lalcknoss :.Sll" SwRI No: 4-l'R-1200 Daste Col. Olk.a 4-SS-160-.553-28-SAM Plsuro: A-20
. \ *~ *':II'.#'-*
* )
Revised August 1984 * (II*) r - ---l 1*-PR-1200
/
i~ /
. ,,~. . 1,> /
- r" ", ,_ - /
- - - - - -c:]~ .!- _r--.t l
.* . L__)t-~
2
.N
~
I I
'I
;fr* 0 rr .
((l.~* 1!;l'-Z 1 'J r~uqG Uo; l"2VSI020 l1 SllllG Dwa: llC-2-J Sht. s Tlald.no:uz .410
!i 11 u 1 11 o : J -1* n- 1 2 u1
---* D IW I c
- 4u- l 0-SAH.
C.. l
- Olk * * *1 -SS-I 6f)-. 1=1auro:
.. A-21*
\ ' .._
/
*\
\_
Revised August 1984 (El."-ISS'-1 11) - _ _ _ _ 112.. P.-cssutlzc..-
\ --===---
Cfl.-..J~l'-2.?
----------------.-----------"----Jfhldnoss:
l'b_*11_1&r._.~u_,_*_1*_*-_2_1*s_1_0_2_1_ _ _ _ 1*su4G Uwg: llC:-2-l ShJ. s .438 11 1
~wttl Uo: l-rn-1206 Uuulc Cal. IUk.; l-SS-160-.4~1-lO=-SAH 11 igurc; A-21.--
~ . : . . ~- :
..1 . ..~.t: ....... ,,, *. - *"-*! " **;** '.*:,,,
*. /
0 . ~- . U2.3 Steqh) Gcu~r"tot
,1.. '
( l r* I I 11 \, .1 .J~* 1 (Ouftc.. td Wt.14) . i i. Bu,d (\I.} lEl.,1*)
.. l,SIUIG Nox 1~11-2PSIOl6 PSD4G Pwg: HC-2-l Silt. 2 Thie noss: L 250" *
'r **~ ~~~~~~~~~~~-*
SwRI No; 14-PS-12ll Rueic Cul. Olk.a 14-SS-140-1.25-17-SAH Plguro: A-25
l. (Sbca.f I of Z.)
'..J Jr*
i I t' \ _..,,, 1..........
,~..!i~
lo .. 0t () lopl) 10 (El.1'1 J PSUllG No: 4 11 -2PS1000 rsugG Dwg: RC-2-l Sht. 6 hlclnoss: 0.531 11 Flguro: A-26
./
Swill No: 4-PS-1231, Shuot I Baotc Cal. Dlk.: 4-SS-160-.551-28-SAH
~' .
i al
.'15
~
I I I I
~ --p .
- s. ,
.. <' \ J, p:.. .
I N l.n . dvt ... l!i.¥p I\\ (Sl1ce.t 2. of 2.) rsn&G No: 4 11 -2Ps1000 PSHCG Dwg: RC-2-l Sht. ~ and 1 Thickness: O.Sll" SwUI No: 4-PS-1231, Sheet 2 llaeiC Cal. Ulk.: 4-SS-160-.553-28-SAH Piguro: A-27
I
.\. '";
2.~ *
,N
~
**.a.
l'SIHW No: 4"-2PS1001 rse4G Dwg: RC-2-l Sht. 6 laickness: 0.531" Swill No: 4-l'S-1211 Figure: A-28 Saolc Cal. Blk.: 4-SS-160-.553-28-SAH *
\ '. **~
U-2.t Ste.tb~. Genc.v~to..-
-1\2.+
Rene.tor Coolo"t AIMp
~0°([11.)
(El:** 6L'-S') PSl!ll(i No: l 1"-21lC 10 IO 1 l Sll4G llwa: llC l Sht. 2.
~~~~--~~~~~--~11~~--~~~~~....;;.._--~---------~
Th lckno!U: 2 .:..1~" Ml n. Wa 11 SwRI No: ll~"C-1210 Buote Cal. DJk.a 2.312-SS-17-SAH (plate) Plgtiro: A-29
~tl3 Stc.Qtu C.e~c.rAfor-
~ ff. '2..3 N co R'!qCtor Coolant fump PSU4G Ho: ll"-2RC1007 PSll4G Dwg: RC-2-J Sht. 2 hlcknoss: 2.495" Min. Wall
*-~~~~~~~~~~~-
S wlll No: 31-UC-1230 Daoic Cal. Dlk.s 2.312-SS-37-SAH (plate) I' l guro: A-30 *
/ :;-_.
-~._)
\
l
. It 2.2.
#2-lc .
feoctor
- Coola11t Pu1np .
I ..1
- 1 .
*1. ' 'r*N j ' . ~-.
j
- j SwRI No: ll~R~-1220 Daatc Cal, Blk.1. 2.112-SS-~7-SAH (plate) . Plguro a A-Jl t
;. - ,..: .* ' . . .. * ..i ....... _....... .... '~.*--** . . . - ' * ' .. :. . ~> .**;*..* ':.*..:.*~ *~**'~.: .. /.. .
/
\ ' ~ .: -
Ui.1 .ft1..I Rc!odoY c..ol1mt tlHn r S"fecu*1 Genet"ato.- _. (' \
'--t i
'ti_
PSU~G No: ll"-2RC1001 PSB~G Dwa: RC-2-3 Slat. 1 hlcknoss: 2.495" Min. Wall SwRI No: ll-RC-1210 Baute Cal. Olk. 2.ll2-SS-l1-SAH (plate) Pigure: A-12 *
.\ *.~-
- ~. 4
)...:~*~*;:_ __ ' ._ ** ..,~ - .** ** -- -* - - * *. *
.M*li S1e:o111 Ge..,(,~oto1r PSUQG No: 29'°-21lC1009 PSDllG Pwa: RC-2-3 Sbt. 2 fhlcknoas :2. 33511 ~Un. Wo 11 SwRI No: 29-RC-1240 Oootc Col. Blk.s 2.ll2-SS-l7-SAH (plate) lilgure: A-11
'.. . . -* ' (I!. .'. ' ' ' ~
/
,d"f'.
~~.
-:r-PSH'G No: 29"-2RCJ006 PSUgG Pwg: RC-2-3 Sht. 2 fhlckness: 2.335" Mln. Wall
. SwRI Ho: 29-RC-1230 8aa1c Cal. Olk.a 2.l12-SS-l7-SAH (plate) Plguro: A-34 * *
\ .***~
*j I. 'j ..*
I j
/
* )
~l-1..1..
II I! *. I rsn*G No: 29"-2RCI001
'I .....
SwPf Ho: 29-RC-1220 Baste Cal. Blk. 1 2. 312-SS-17:-SAH (plate) II l guro: A-15
PSD~G No: 29"-2RC1DOO rsnaa Dws: RC-2-3 Sht. 1 fh cknoss: 2.335" Min. Wall SwRI No: 29-RC-1210 Baatc Cal. Dlk.1 2.l12-SS-J7-SAH (plate) f i gurG: A-16
ReQc.tor . Coo le.mt
.: ... . fu*ur Brolo~icol Sl,1 ~let MK-ltC-,'1-Sll VSD4G No: 27.S"-2RC-IOIJ h cknoss: 2.215" Nin. Wall
.,\ -*** figure: A-37 SwRI No: 27.S-RC-1240 Buote Cal. Dlk.1 2.312-SS-37-SAH (plate)
' r- --
l t : *. ,;..<:: .. . :....!..:<. ... _~ .;
A PSU4G No; 27.S"-2RC-1008 PSUGG Dwa: RC-2-3 Sht. 2 Wall SwRI Ho: 27.S-RC-1230 Buuic Cal. Olk.~ 2.ll2-SS-l7-SAH (plate) . 11 1guro: A-18 *
\ ,*-. ..
- -.~* ....
I jt2.2 . Ret\c.1"011 Coolcml-Pu1rip PSDGG No: 27.S"-2RC-JOOS PSOQG Owg: RC-2-l Sht. ~ h cknoss: 2.215" Min. Wall Swill No: 27.5-llC-1220 Daetc Cal. Blk.a 2.312-SS-31-SAH (plate) I' 1 guro: A-39 ~ - ., t ~ - . -'* ' . . ' ' . ~ - ' ' -
"/
ttll
~c.Qc.tot Caolaht *.
foh,r
- 6ioloctic."I S"ierct tU:.-ftt-~'l-SLI PSH'G No: 27.S"-2RCJ002 hlcknoss: 2.215" Min. Na l
\
j.~ . - *.- .,.. *
'* ~ : t, '
.) SwRI No: . 27.S-RC-1210 Basic Col. Olk.a 2.ll2-SS-l7-SAM (plote)
.. *,, /.)
- i
<£1*10.)*
.. "~~
I* i I J ; ..* l i IO * '8 . (.. . ,t ll Sp~ 1*su1u; No: l 11 -2HCI I02 1* S 11 ll G Uwll : RC 3 S la t
- I 2 fhlc Hess: 0.438 11
\ **~ Swill Ho: l-HC-1243 Daotc Cal. Bl~.: 3~SS-160-.451-30-SAM Figure: A-41
_:_p_;"'
~* ,;"" ..:,...,
-~*.. '
.: :_, ;. .L.. ~.::~:-~-~.:-.:.....~.~ . ., ~ .'. ':.::. __,.,.,_: .: ..... :. .., * , ' * . '* ~~ :.1. I,., , ~--*~* . . .. ,
/
-- - --l 2.-~c-12.34 ao lji:l\
_IS *--'~-ill*I~ rsn4G No: l"-2RC1077 PSU4G Dwg: RC-2-3 Sht. 16 fhlclrnoss: 0.438 11 SwRI No: l-RC-12ll aaotc Cal. Dlk. i 3-SS-H~0-.451:-30-SAM 11 l guro: A-.42
'.,.)
- t ")
(Et.,1'h o'~
,_,Atf ... ' ' '
i PSD4G Dwg: RC-2-3" Sht. II ness: 0.438"
,\ ..,..
SwRI No: l:-llf.-1221 Daolc Col. Dlk.1 . 3-SS-160-.451-]0-SAH Plauro: A-41.
. ::.;,.,.\_ - I * , ...:~** * *,;. ~. . "' . .:. " .~-- ;_,' ~--* .. *'* - . ~-". - .
- --------------------....---------------~ .. -~ ..
,, *** t
.r.
,/'f'f .
II PSOliG Dwg: RC-2-3 Slat. 15 la ckness: O. 438 11
. SwRI No: l-RC-1211 Baaic Cal. Blk.: 3-SS-160-.451-10-SAH lfiguro: A-44 *
. ~* Jt.:. ....*,,:_.. . ' . ._). ~- "" " *.* * **
.* ) * ,
. 00 /I' al'J* ..
i*-:.,,,.. B 6
- - .,.t::. - - - - - -
c1D'!.~ .... , ,. i"¥",,,. PSU~G No:2"-2RC1099,Jl00,1103 PSDGG Pwg; RC-2-3 Sht. 12 hlcknoss: 0.344" Sa.Ill No: 2-llC-1244 Busic Cal. Blk. 2_-SS-160-. 110-19-SAM 111 guro: A-45 I
.~.
z.o lf-KC-28
. 2..t
'1.2.
2.3
,,ff>
l- - - I
..J -
- - -l I
,,,it"*~
3-RC-12.13 ,.. 3
~ ~i .. ~c .
f-- - '.1 ~ '4?1 2?.s-RC:12_.40-*-f . rsegG No: 2"-2Rc111s
- 1111 PSOtlG Dwg: RC-2-3 Sht. 12 blcknoas: 0.144" Daste Cal. Olk. 2-SS-160-.310-~9-SAH Plguro: A-46
\ >>-....
- ' . .. -*~
L'
/
* )
l'SIHlG No: 2"-RCl!IO PSDllG lh"lg: RC-2-l Sht. 19 hlcknoss: 0.344" SwRI No: 2-RC-12~1 Daatc Cal. Dlk.1 2-SS-160-.330-39-SAH 11 l a:ura: . A-41 ' i * .*.o*,,* p .*. *
/
/
-~
"h I
I
- *,I'
'I 0
,, 6 J---,
J-- rSH6G No: 2"~2RCI074.l07S,J]01 !_S_ll_4_G_D_w_c_*:_R_C_-_2_-_l~Sh_t_.~1_6_*~~~h_lc_k_n_o_s_s_:_o_._3_4~4-"~~~~~~-* SwUl No: 2-RC-1214 'Uaoic Cal. Blk.1 2-SS-160-.330-39-SAH Fl1uro: A-48 * *
\
- _t *... ~*--- -
I
-~.- '!
'* ./ *. '
- 15 f-.
I 1 TE-i-loe 1'1-11 tE ..1llfa 1*s11taG No: 211 -llCIOBl, lOBl PSDIU; Dwa: RC-2-3 Slat. 16 Tla{cknoss: 0.344" Swill No: 2-llC-1212 Baeic Cal. Blk.1 2-SS-160-.ll0-'.ll9-SAH Plguro: A-49 I ...~. - -.~* ~ -
/
I **. I-- - --
,rfi' .
,,:;-~.tti:?
PSU4G No; 2"-RC1087 PSD'G Dwa: RC-2-3 Sht. 17 blcknoss:0.344 11 Swill No: 2-llC-12ll Daste Cal. Dlk.1 H/A l'lguro: A \ ..,...
./.,
/
-/
I I .
*15
~
I I
*I
, L:f.,'J5
---J
?
;()- --:f 1-RC-12.21
'L I.
i Ll.. 1-l{c- t2.23 rs"'o No:2"-2RCI049 1050 1105 PSHGG Pwa: RC-2-l Sht. 11 rhlclrnoss: 0. 34411 Swttl No: 2-RC-1224 Daatc Cal. Dlk.1 2-SS-160-.ll0-19-SAH Plgu1ro: A-51
- '*. L ; ;~ ....
/
/
-2~~*~,lfl..1.0~3-r I
I I I
.--J.1!i I
I I I I~:\ I~ -'n-1200 TE-1-2.18
---11 8 . b
~ l.n o. a*muw No; 2 -2Rc1os1, ioss 11 rsn*G nws: ac-2-1 Sht. 11 hicknoss: 0.144 11
~h*llf No: 2-llC-1222 :Daatc Cal. Blk.: 2-SS-160-.ll0-19-SAH
*'***j
* )
__ -J ..-1~**"' g~ t.. . ; ~ i'
. 0 31-RC.jJ-~ - ~ ,--
- I j--- - j.
~,11 .
i ' i,,: tr .
. l.11 t'\
*~ g
.. i1:"
t f\C ..1t
/
I i l. co0-~..t * !. J;. I i
,,Jof_,..;
(1'o vr"ili PSll4G Nu: 2"-21lCJ060 PSlllUi Dwa: llC-2.-3 Sht. 17 rr1a1 clnoss: o. 344" Sa.Ill No: 2.:.1u:- 12 21 Dao le Col. Olk. z N/A Picuro: A-51 '
**, .. ;.I';....:.
,/
\
* .. _(fl.103-l
\ ' *j (ll.... ,,.
. 'L~
l'SIHHi No: 2-21lC1026,1027.ll06 PSl!QG Pwg; llC-2-l Silt. 15 fblclrnoss: 0.344 11 Swill No: 2-llC-1214 Dasie Cd. Olk.; 2-SS-160-.330-39-SAM Piguro: A-54 *
* --~
=--*
i. i
/
*. _/
I I
. * /
i i . l:--_ i\ . l'l.s-RI\-- -
. ~-11.10--i I .
1 i I . .. .~- J l(j,jf/
*._ :ft l'SIHW No: 2 11 .:.2nc1010, 1012 SwRI No~ 2-RC-1212 Duaic Cul. Blk. a 2-SS-160-.330-39-SAH Piguro: A-55 . '
I : . l_.~.3.:.'.22 ;!,',.!.. .* if:~:-' ... ..: ~ . h ., . . . t.*
./
1' ~I..
~c. ,l
\. *,1 i
' lo i
I t' ~, l ,,
'J a I i1 .. ll (th ;
c,,~ . 8t* I f
'8'
\
*~ . '/
z1,~c I . . 'Ii _f c'b,'lal (lo ~ . btcu (qtto\' hl:
%l) 1*snr.r. Ho: 2"-2RC10l9 PSllllG Pws: RC-2-l Sht. 17 ffhiclnoss: 0.344 11 Swll I Ho: 2-llC-1211 Daste Cal. Blk.1 H/A IPiguro: A-56 ..
'/
' Ji
\J1 PSU~fl Ho: Soo Abovo* PSUGG.Pwg1 RC-2~1 Sht. 12 Thickness: 0.250"
*-~~~~~~~~~~~~-*
Swll I No:
- Soo Abov o
- Daalc Cal. Blk. a N/A Plguro: A_;.57
- 'l 5
1-RC.-12.33*--,. 1 \ t I .6----1-ac*121z. 3 3
-l£1.'lb')
PSUijG No: *soo Above PSDGG Dwa: RC-2-l Sht. 16 h ckness: 0.250" SwDI No: *soo Abovo Baute Cal. Blk.1 N/A Plguro: A-58 *
\ *,~
.' -.... --~*
~
- t*SlllUi Nos: l 11
~2RCI046 111 .. 2RCI047 1 11 -2RC10~8
*SwRI Nu:1; l-llC-12 21 l-RC-1222 *1-nc-1221
~.i1..t i;l!6
~
I 5 r-----"'."""_J_~
.I 1-1tc.-1i11 t I
I I l i.
'- - -~-&.--a-I t l t ---1-Rc-11'2.2 1 . ifF*.*.
- 1-*1tc-11.23---1>1
*~ .
3 3
)
2. PSH4G No; *Soo Abovo P.Sll4G Pw1: llC-2-3 Sht. 11 h cknoss:
*~------'----------------------------:~
Swill No:
- Soo Abovo Daste Cal. Olk.a. H/A A-59
.... i.:'
~* *' '
1: .,, t 1l-
/
Dl'."1i 3 I'"~ PSUgG Hoi *Soo Above PSUIG Dwg: RC-2-l Sht. 15 hlckness: 0.250" Swill No: *Seo Above lootc Cal. Blk.1 H/A 1a 1 guro: A-60
\ *oi'**
- - _~
..... *~~ ** *
., ./
* )
l-- _z.1-Rc-1210 __. --l 1
.. i.1-sJ-15'1 *'
i j _. -,_,... . . _ J-* --~~ - 1'(.-SJ"-11.I'
/I .
z.-sJ--f218l--LJI .. iac.-i. .
- 2. ....
'i' A
11-RC.-8
.... ~
?> '1-l.?s*
1
~ ~
I . l . . \\;.-',
.'15l- {>-:"
') J- - - - - 7.
'-'~
ll
' '1~ . ./'?.s ID I ,
~'~ t li . , h Thickness: 1.406"
~>Sl!fali No: 14"-2RlllOOO PSD4G Owg: RH-2-3 Sht. 4 14 -IUI- l 211 Dasie Cal. Blk.; 14-SS-160-1.40~78-SAM 111guro: A-61 Jo' ,1-,
.J *~-.L:.2-: ... ~ --**. *. .*' ..... ..
/
~O'l'K:
For the preservice examination this syete11 was designated as safety tnjectton(SJ). For subeequent ineervice examinations this 1e redesignated as residual heat rewoval(BH). l J- v'*
"- J
~ ... ft
.. . . . s, PSH~G No: 12"-2RlllOS1 PSBllG Dwg: Rll-2-3 Silt. 2 fflaicknosa: 1.312" Swill No: 12-IUI -1251 Basic Cal. Blk. z 12-SS-160-1.283-21-SAM 'Figure: A-62
- ~
}
*"'r'
*7 .,* -
.' \ ,*
~ ..
~lt
~~~
2.0
~-. - - -{ (E1,q7*)
2'1. 5-RC-1140 ..
- I I
I I. 2.
' I li I
- .. l.
PSlllt(i No; l0 11 -2S.Jl039 blcknoss: 1.125" Sw~I No: . 10-SJ-1241 Daste Cal. Blk.: 10..:ss-160..;1.119-22-S.\M Flguro: A-63
~~~~-~~~-~-----~----------
"/ . . *- . - - _
./
. \' *::' ' ',., ~ *;
~-
I l P>
. I
*.* ~
..;r:"
£,:;;'5-
- -!fl.',, '
I l l. PSl!IHi No: 10-2S.Jl038" PSUllG llwg: Rll-2-3 Slat. l hickness: 1.125" Sw"I No: 10-SJ-1211 Dasie Cal. Dlk.: 10-SS-160-:1.119-22-SAM figuru: A-64
I . -.)
) 11 -s1-s1 I
I - - -:--:--
' I ..\
{f]."' 11- l }-r r ' i. 1/
~/
l'Sll4G No: l0 11 -2SJ1037 PSlHlG Dwg: RU 2-l- S_,t. hlcknoss; l.125" Swtt I No; 10-5~-1221 Boote Cal. Blk.1 10-SS-160-1.119-22-SAH lllaure A-65
*v
_,"".. ,:\~*.. ; .,*; .. _, __ :.. *-.
I . \ . 1 I
*, \
. ,.r_;r.r>--: .
-<,t;*
I I . _J l- -- - - PSIHW No: J0"-2SJJ036. PSIHlG Pwg: Rll 2 Sht. J hlcknoss: J.125"
*-~~~-~~~~~~~~-*
SwRI No: 10-SJ-1211 Buuic Cal. Blk.: 10-SS-160-1.119-22-SAH I' i guro: A-66 * .
. \ . ; ~ '."'
. r._~ :*-~::.:. . -*-* .. :, '
11
.\
. ~,.. ~*
IN ,:
~'*
- rsu4G No1 8"-2SJ1021 PSUGG Dws: IUl-2-3 Slat *. 3 hlcknoss: 0.875"
~wll f No: l!l-S.J-1262 Pautc Cal. Olk.: 8-ss~xx-.860-21-SAH Plgura: A..:61 i .* :~::-j *__ ._
.J _,,!,,.'_J~"""' :,. . ~.; . .*;:'. : . ,.__. . - .... - . -*~,*-.:. l * .
_/ l1 ago 2 of 2 l1 SUfaG No; 8"-2SJI027 PSIUiG Pws: Rll-2-3 Slat. 3 hlclrnoss: o. 875" SwHI No; 8-SJ-1262 Oauic Cal. Blk.i 8-SS-Xl-.860-23-SAH P l Buro : A-68 .
*\' i Pogo l of 2 rsunG No: 0"-2SJ102s PSlUUl Owg: Rll-2-3 Stat. l hlctno11: 0.876"
- SwRI No: 8-SJ-1252 Boole Cal. Rik.a 8-SS-XX-.860-21-SAH P 1 guro: A-69
*~
/
\
8 11 -2SJ1025 PSCflG Pwg: Rll-2-3 Sht. I blckness: o. 785 11 Sadl I No: 8-SJ-1252 llaetc Cal. Blk.: 8-SS-IX-.860-21-SAH Pigure: A-70 >' ~- -
. -~.
I I '
.,. rsuatG No:* 811 -2sJ1262 PSH&G Dwg: Rll-2-3 Sht. 2 hlckness.: o .875 11 i'* -:**}<.
'**'~*'"~,:~'::... J
- S&dll No:
8-SJ-124 5 Dasie Cal. Blk.: o-ss-xx-.860-21-SAM
* * ;_ .... * ,..: - **~ *~ J ;..,:; ..
Pigure: A-71
~--------------------------------- -
/
NO'fE: For the preeervice exa111inution thie system was deatgnated as aafety injection(SJ). For aubuequent inservice examinatione this is redesignated as reeidual heat removal(IUI). PSIHiG No: 8 11 -28.11261 PSU~G Dwg: RU-2-l Sbt. 2 hiclrnoss: 0.875" Swill No: 8 - RH -* l 2 l 5 Baalc.Cal. Blk.: 8-SS-XX-.860-23-SAM l'lguro: A-72
\ ,'.'"'
t .. '.
/
6 r61t4G No: 6"-2SJIOSI rsn110 Pwa :. nu-2-1 Sht. 4 Thie noss: 0.719" Swttl No: 6-SJ-1242 'Basic Cal. Olk. I 6-SS-160-. 764-25-SAH P1 guro: A-1l
. Et"""a
. J9'J a>ago l of 2 rscnG No: 6"-2SJ1110 PSHQG llwg: Rll-2-3 Sht. 2 hlcknos5: 0.719" Swill No: 6-SJ-1241 Dasie Cal. Blk.1 6-SS-160-.764-25-SAH 111 suro: A-74 ..
\ .,..
*>I w
16 1s e41 ...sJ .. ,~
. "6 Paa:o 2 of 2 PS"4G No: 6"-2SJJl70 h cknoss: 0.719"
. \ . Swill No: 6-SJ-124) Daste Cal. Olk.a 6-&S-160-.764-25-SAH . 111guro: A-75
--**.,. *..,. ~. :.,.
rSU4G No: 6"-2SJIOSO PSl!llG Dwa: Rll-2-3 Sht. l hlcknoss: 0.719" SwHI No: 6-SJ-1232 Daatc Cal. Blk.: 6-SS-160-.764-25-SAH l'iguro: A-76 *
- c$!P.' .*
fl..'JS
;f{
v I ' . .. Page l of 2 6-RH-121s}-
*..,c,' rlcf 8,.
PSfi~fa No: 6 11 -2SJ1171 rse~G Dwg: .RH-2-l Sht. 2 Thicknoss: 0.719" SwltJ No: 6-IUl'.-1211 Dasie Cal. Blk.: 6-SS-160-.764-25-SAH Figure: A-77 j ' . ~*-* ,.,;:l,.:,,., < c ' *-J., ,,~ ;,_'__,, 1 *' * -' ...... ; .. .
.* /' (EL-9 I
- B)~
Page 2 of 2 PSH4G No: 6 11 -2SJl171 PSBllG Pwg: Rll-2-3 Sbt. 2 fhlcknoss: 0.719" SHlll No: 6-SJ-l2ll Baste Cal. Blk.1 6-SS-160-.764-25-SAH PJ.gure: A-78
/
* .iif.
~'
l'~ II \'I
,~,
y l'Sl!fa(i No: 6 11 -2SJJ028 PSHllG Pwa: Rll-2-3 Sht. 3 hlckness: 0.719" Swill No: 6-SJ-1222 Daotc Cal. Dlk.1 6-SS-160-.764-25-SAH Pl guro: A-79
~
PSUGG No: 6"-2SJ1173 PSD*G Dwa: RU- .:3 S*t. 3 bicknoss:
*---------~----~--~------
SwRI No: 6-SJ-1221 Baste Cal. Blk.& 6-ss...:160-.764-25-SAH A-80
........ - . ~ -* *'
*.*~
© (i:- . .
J...L ""
. ~3~
I i 1
- . d'Jf'.
1'. * ~
~.!!"
Puge 1 of 2 PSl!&G No: 6"-2SJ1026 P$84G Dwg: hicknoss: 0.719" SwRI No: 6-SJ-1212 Baste Cal. Blk.:
- 6-SS-160-.764-25-SAM Figuro: A-81 *
. *~ ~ '
/
,/
,._ 10. ... s J-1~
&.;:11
~
00
*o Page 2 of 2 1*sur.G No: 6"-2SJ 1026 PSl!&G Dwg: Rll-2-3 Sht. l hicknoss: 0.719" Swill No: 6-SJ-1212 Basic Cal. Blk.:* 6-SS-160-.764-25-SAM P lguro: A-82 *
- ~ ~; ..: :...
I; I
.' ~ - . ,/
I. _._1*s_u_._n_N_o_:_._6'_'-_2_S_Jl_l_7_2_ _ _ _ PSUllG Owg: Rll-2-l Sht.. 4 r*1atcknoss: -~-*'-7..... 19_ _ _ _ _._*_. 1
~~* , .. Swill No: 6-S.J-1211 Boele Cal. Dlk.1 6-SS-~60-.764-25-SAH Plguros A-81 I
I ~' .. ' -* *:
/
/
* .* ,1
- r (X) .
N
- PSl!llG: 411 -2SJ1042 4"-2SJ1011
*SwRI: 4-SJ-1291 4-SJ-1295 PSll"H No: *Soo Abovo blcknou: 0. 531' Swill No: *Soo Above> Daeic Cal. Blk.1 4-SS-160-.55l-28~SAH
*, 'r*,,* ,,.** .
'A *-..._
I 1-i-
..J,'1 tL
- r ailf' uf1l st:*'* - a,1
()') w
,,,s r.
,,s ,,, 1q 41
~*ot*'
f.ti'trfi 0 *
.l
*4-SS-160- ._553-20-9,\U 4-SS-11-.609-2)-SAH i*snGG No: 4 -2SJ10 9 11 PSUQG Ow1: hlckness&.531"(160),.674"(XX)
SwRI Ho: 4-SJ-1294 Hoste Cal. Blk.1 See Above* 11 lguro 1. A-85
- r* ~** *.
{ .. '~:* I . , *.
. .~-Si:;~~.-* . . . . '. ,,' ..:.. . . ..... . .. .:
*4-SS-XX-.689-27-SAH 4-SS-160-.551-28-SAH l3 r
It lsPr* PSll~G No: 4 11 -28.11046 rsegG Dwg: nu-2-3 Sht. 6 hlcknoss:.s11 11 (160),.674 11 (XX) SwHI No: 4-SJ-1282 llaeic Cal. Olk.a See Above* figuro: A-06 *
.1: .... '
ll (El"- l5 1-'t1-zo ltro l'ra
"'~ 'I
- t. 15 Ii
*4-SS-160-.551-28-SAH 4-SS-XX-.689-27-SAH PSUllCi No: 411 -2SJIO PSl14G Pws: Rn-2:..3 Sht. 5 noss:.531"(160),.674"(Xl SwRI No: 4-SJ-1272 Daoic Cal. Dlk.1 Seo Above* 111 guro: A-87
/
/
*l-SS-160-.451-30-SAH l-SS-11-.600-41-SAH PsegG No: l"-2SJJ012 PSll4G Dw~: RU-2-3 Sht. flalcknoss: .438"(160), .600"(XX)
.j Swill No: l-SJ-1292 Baute Cal. Blk.; .See Above* 11 l guro: A-88
/
)
I .
~
00
. "-J Pago I of 2 PSHQG No: 2"-2SJI 116 PSDllG Dwgl Rll-2-3 Sht. ll'l hlcknoss: 0.344" 61dll No: 2-SJ-1249 Bouie .Cal. Blk.1 2-SS-160-.330-39-SAH Pl1uro: A-89 ,! . " ~
Puce 2 of 2 1*sUQG No: 2 11 -28.)) 116 SwRI No: 2-SJ-l249 Uaatc C~l. Blk.1 H/A a: i gure: A-90 *
/
17 II,
'I
-~I
'II) 8 ..-{El."' 811)
~
t PSUQG No: 2 11 -2SJ1061 PSUl&G Dws: Rll-2-3 Sht. 11 noss:.144 11 SwRI No: 2-SJ-1247 Baelc Cal. Ulk.& 2-SS-160-.330-39-SAM Plguro: A-91
/
i i l* I
-I
\0 0
t..4-
- l. r-'ll~
(t:l-* PSl!fl(j No: 2 11 -2SJ1048 PSllGG Dwg: Rll-2-l Slat. 13"14 lalclcnoss: .144 11 i I.
.. <r**:.: __
L.;.L __ . '. - *<* .. ~- Swltl No:
)
2-SJ-1219 .taste Cal. Dlk. 1 2-SS-l~O-. 330-39-SAH F 1 guro: A-92
.\
ll\
..1,r.-
,.,.j
'.'-~
6 rsn40 No: 2"-2SJ1020 PSD4G Dwg: RU-2-l S t. 11 h cknoss: .344 11 Swill No: 2-SJ-1217 Baetc Cal. Dlk.1 2-SS-160-.ll0-39-SAH Pl guro: A-91
/
16 Page l of 2 PSDllG No; 2 11 - 25.Jl l l 5 PS~4G Pwa: Rll-2-3 Sht. 1 fhickness: O.144 11 Swill No; 2-SJ-1229 Daste Cal. Olk.; 2-SS-160-.330-39-SAH Pi guro: A-94
/
. ~lo 8tP' .
\SJ 16' ~\'?
is n~' (~('- ** 'f
. 103.
~
43 4.(>> 1-1 .pl .,' *31
! :r> .., to I
33
'°w,. ~6
{ ",, ~6 l'~**; ()tPJ
~
{/ Pago 2 of 2 PSIHlG No: 2*.1 -2SJ1115 PSUUJ Dwa: Rll-2-3 Sht. 131U4 noss: 0.34
~-----------'------------
S wll I No: 2-SJ-1229 Boote Col. Blk.a 2-8S-160-.ll0-l9-SAH A-95
- .. -~ ...~2
- A
, S ~,'l I I'"
../1/
J
'). ..... / '
15 (f' v I} I f.;s" Pag6 I of 2 PSll4G Ho: 211 -2SJJ047 PSl!llG Dwg: hlcknoss: 0.3 SwRI No: 2-SJ-1228 Baste Cal. Blk.1 2-SS-160-.330-39-SAH l'iguro: A-96
\
/
(El. '\8 1 i _\
©
. l'ugo 2 of 2 rsnqo No: 2"-2SJI047 PSDllO Pwa: h clnes&: 0.344" SwUI No: 2-SJ-1220 Daste Cal. Olk.a 2-SS-160-.ll0-l9-SAH Flguro: A-91
- ~ ; .,_,,_ - ' ':
* . * . i.!".
/
/
© PSl!ilG No: 2 11 - 2SJ 111 l PSelG Pwg: RU-2-3 Sht. llC14 fhicknoss: 0.344 11 SwUI No: 2-SJ-1219 Baeic Cal. Blk.: 2-SS-160-.ll0-39-SAH Pl l(Uro: A-98
,.._ \@ ~El.SR') ';/"-:"
.ft;.;* 21-sr-zs-o-
; t-f'.:<i- -
I~ j.. J;:--.....t-~--1. ~El."l'I~&.')* 3
. (~*> .**l- f };\.J-it*'
f}t Posa 1 of 2 2;- SJ".: Z52. 1*su40 No: 211 -2sJ1022 i>SDllG llwg: Rll-2-3 Sht. 19*121 la ckness: o.344" Swttl No: 2-SJ-1218 Baste Cal. Olk.a 2-SS-160-.ll0-39-SAH 11 l guro: A-9!>
/
A (II*) 8'" lo * (:--,,_-~ j~ 8 ll
'114 l~
Pugo 2 of 2 l1 SlHlG No: 2 11 -2SJJ022 PSUi&G Dws: Rll-2-l Sht. 19421 fblcknoss: 0.344 11 s,.au No: 2-SJ-1218 Basic Cal. Olk.; 2-SS*l60-.ll0-l9-SAM l'igure: A-100
\ *~ . :-*~.;' _/ *. :
- ,* 1 I _,.~
>~ '
/
s
~El. 80 -&/)
1
'I Pogo I of 2 l'SHQG No: l~l/2"-2SJIOJ6 PSUCG Dwg: RU-2-3 Sht. 7 b clrness: .281"
- swnl No: 1.s~sJ-1242 Daste Cal. Dlk.1 N/A 1: l gure: A-101
(
/
40 ii 41 4-1' 1?.5 '
.. ~c..1i'
*~
1o 'l
,.**\A 11
..ar s 1'" 1 (f.r Pugo 2 of 2 PflllllG No: l-1/2 11 -2SJ1016 PSOllG Dwg: Rll-2-3 Sbt. 7 fbicknoss: 0.2811'
~~~~~~~~~~~~-*~~~~---~~-~~~~--~~~~~--~~~~~~-
S wHI No: J.S-SJ-1242 Daeic Cal. Olk.a N/A 11 lsnro: A-102
. '.,/
I {~ttlJ (oss*V 2l to
£~t.
{ 11 1 lo . 8 ta 11.,
,s
~
~
-f-~
l\
. l~
l1..s1 It
,,fil IO
~
, 1 "I&,
h cknos1:.2a1 SwRI No: 1.5-SJ-1232 Buote Cal. Blk.1
- N/A L '
./. ~**
- l'ugo 2 of 2 PSHQG No: l-1/2 91 -2SJIOJS PSDtiG llwg: Rll 'fla!cknoss: O.
Sw~I No: l.S-SJ-1232 Dusic Cal. Dlk.1 N/A A-104
*.~;
,.J" '
, \ .,.
f-
*a'
~1J
. ~jt'* t~*v
.t!/"" .
Jft..r;.
.f: 1P 5 i1.s i1
;t,lt, 16
~1v (1*,s - it
. . . ,1-)
lJ , . . Paso I ot' 2 1- " tl*s
.t.J11 a*su~o No: l-l/2 -2SJ10ll 11 PSUl&O Dwa: Rll-2-3 S t. rhlckness: .281 11 Swill No: l.S-SJ-1222 Daetc Cal. Olk.& N/A.
- aitguro: A-105 1 *,
./.
I~
. ;r J1
~)~
.f-1..1, ti z*S I
~
J\1. ( ) 0,rid 11-
~I
\.
.\I P>
....I ~ l'ogo 2 of 2 rsu~o No: J-l/2"-2SJlOJl PSllllG Pwa: Rll hlcknoss: 0.281" Swll I No: l.5-SJ-1222 Baste Cal. Dlk.1 N/A 11 l gnro: A-106
.***)*
/
~
0 lJ1 ~- rsn1w No: n-1 211 -2sJ1014 PSDllG Dwg: Rll-2-l Sht. 11 S~Rl No: n.5-SJ-1212 Daoic Cal. Blk.s N/A I; lguro: A-101
** A-6
.A ' sJ ... 3
- .... It,
... 7 /;
Pago 2 of 2 l'SIHH; No: l-l/2"-2SJ1014 PSllllG Dwg: RI hlcknoss: 0.281 11
*-~~~~-~~~--~~~~1 Swill No: 1.S-SJ-1212 daaic Cal. Blk.: N/A 111 guro: A-108
.. ~ .
PUMP No. 22 . PUMP No.l4 (t..111' 31-RC-IZ1ta f aol' 8o'-TUIG- - - (l"\ f11ctt) STG ~
- 1. ff 2.1 i
2.1-rHP-LllGS-3 21-mr-LUGS-Z (Lu1£ 2lS-KC.-12W) T~ RPV ToRPV ToRPV ToRPV (L1N~ 2.7.5-l!C*f ZIO) (l111i. 2.7.5-:J<<:-12.30) 21-PtlP-LUGS-2 23-rHr-UJGS-Z 23-fttr-LIGS-3 f ftOH *
- faott
~- ST& S{G-
*#-..--~ #2.1 .2.'a - - - - -
(L111£ 31-RC-IZIO) (Lu*~ 31-RC-IZ30) PUMP No. 2.I PUMP N~.23 l'SIUUi Ho: R~actor f.oolant Puma*s PSD40 Pw1: N/A (dlagra11 only) h ck n es 1 : ----------------
,*: 1'"";" SwRI No: lleactor Coolant l'ii1111>>e Ba*dc Cal. Blk.1 4.S-. 75-8-CS-70-SAH Plgure: A-109
,/'. \t;, .... : ..
I: ~_,,;1 ... --~-
APPENDIX B CLASS 2 WELD .IDENTIFICATION DRAWINGS
- APPENDIX B
_ CLASS 2 WELD IDENTIFICATION DRAWINGS Table of Contents Figure Title Symbols for Weld Identification B-iii Examination Area Identification System B-iv B-1 Steam Generator No. 24 B-1
.B-2 Steam Generator No. 23 B-2 B-3 Steam Generator No. 22 B-3 B-4 Steam Generator No. 21 B-4 B-5 Chemical and Volume Control Tank B-5 B-6 Excess Letdown Heat Exchanger B-6 B-7 Head Tanks B-7 B-8 Letdown Heat Exchanger B-8 B-9 Reactor Coolant Filter B--9 B-10 Regenerative Heat Exchanger B-10 B-11 Residual Heat Removal Heat Exchanger No. 21 B-11 B-12 Residual Heat Removal Heat Exchanger No. 22 B-12 B-13 14-BF-2241 B-13 B-14 14-BF-2231, 1 of 2 B-14 B-15 14-BF-2231, 2 of 2 B-15 B-16 14-BF-2221 B-16 B-17 14-BF-2211 B-17 B-18 8-CS-2225 B-18 B-19 8-CS-2215 B-19 B-20 8-cv-2201, 1 of 3 B-20 B-21 8-CV-2201, 2 of 3 B-21 B-22 8-cv-2201, 3 of 3 B-22 B-23 6-CV-2212 B-23 B-24 6-CV-2211 B-24 B-25 6-CV-2201 B-25 B-26 34-MS-2241 B-26 B-27 34-MS-2231 B-27 B-28 34-MS-2221 B-28 B-29 34-MS-2211 B-29 B-30 32-MS-2241. B:-30 B-31 32-MS-2231 B-31 B-32 32-MS-2221 B-32 B-33 32-MS-2211 B-33 B-34 30-MS-2241 B-34 B-35 30-MS-2231 B-35 B-36. 30-MS-2221 B-36 B:-37 30-MS-2211 B-37 B-38 8-MS-2241 thru 8-MS-2245, 6-MS-2246 B-38 B-39 8:-MS-2231 thru 8-MS-2235, 6-MS-2236 B-39 B-40 8-MS-2221 thru 8-MS-2225, 6-MS-2226 B-40 B-i
r* APPENDIX B
-CLASS 2 WELD IDENTIFICATION DRAWINGS Table of Contents (Cont'd)
Figure Title Page B-41 8-MS-2211 thru 8-MS-2215, 6-MS-2216 B-41 B-42
- 6-MS-2247, 6-MS-2237, 6-MS-2227, 6-MS-2217 B-42 B-43 6-MS-2231, 1 of 2 B-43 B-44 6-MS-2231, 2 of 2 B-44 B-45 6-MS-2211 B-45
. B-46 12-PR-2201, 1 of 2 B-46 B-47 12-PR-2201, 2 of 2 B-47 B-49 6-PR-2205 B-48 B-50 6-PR-2204 B-49 B-51 . 6-PR-2203 -B-5*o B-52 6-PR-2202 B-51 B-53 6-PR-2201 B-52 B-54 14-RH-2224 B-53 B-55 14-RH-2214 B-54 B-56 14-RH-2212, 1 of 2 B-55 B-57 14-RH-2212, 2 of 2 B-56 B-58 8-RH-2274 B-57 B-59 8-RH-2273 B-58 B-60 8-RH-2253 B-59 B-61 8-RH-2226, 1 of 2 B-60 B-62 8-RH-2226, 2 of 2 B-61 B-63 8-RH""".2216, 1 of 2 B-62 B-64 8-RH-2216, 2 of 2 B-63 B-65 14-SJ-2224 B-64 B-66 14-SJ-2214 B-65 B-67 12-SJ-2269 B-66 B-68 12-SJ-2252, 1 of 2 B-67. B-69 12-SJ-2252, 2 of 2 B-68 B-70 8-SJ"'."2262, 1 of 2 B-69 B-71 8-SJ-2262, 2 of 2 B-70 B-72 8-SJ-2252, 1 of 2 B-71 B-73 8-SJ-2252, 2 of 2 B-72 B-74 8-SJ-2225 B-73 B-75 8-SJ-2215 B-74 B-76 8-SJ-2215 B-75 B-77 6-SJ-2203, 6-SJ-2204 B-76
- B-78 Charging Pump No. 23 B-77 B-ii
l..__ _ Bend
--{~ ~l--Line Concinuacion Branch C01111eccicu, Requires .
l Examinaticu With Branch _ _ __.______ Line Shewn in Decail Penetr.1Cicu cf Wall, noor, ecc. . Line No. Branch C01111eccion, Requires . T_____ Line Examiliaticu With Branch Shown cu Anocher Is0111i1Cric
--~)~<;..._-Pipe Lug(s)
Line Size
'T'I
--.....j~.__;i...._._Pipe Restraint, Noc Welded Branch Connection, Does Noc
_ _ __.** * .___ _ Require Examinacicu
---.a*---- Buct: Weld _ _ _ _ _ _ _ Pipe Support, Welded T
01------Cap 4 Class Boundary
-8 P=P Class %ass Y
'r
_ _ _)=!+--+---Coupling, Socket Welds
----~)+-----Socket Weld ----ip~ . .*--- Coupling, Bucc and Socket Welds l---
Tee
*~~. Rel'iaf
_ _.:.,fi::;O:.;W:_-;=:!1- now Direccicu
.~Valve, Globe
____,)f1:-_ _ _ Line Break
~.,.._Valve, Other SYMBOLS FOR W"ELD IDENTIFICAXION
- B-iii
Examination Area Identification System .J
- 1. Vessels For Vessel examination area, the following format is used:
A-B-C
*where: A is the number "2" and denotes Salem Unit 2 except for nozzles and Steam Generators. For nozzles, A is the same as the connecting line size. For Steam Generators, A is the same as the Steam Generator number.
where: B denotes the vessel, as follows: PZR Pressurizer PR..~ Pressurizer Nozzles RPV Reactor Pressure Vessel RPVCH Reactor Presure Vessel Closure Head RCN Steam Generator Nozzles STG* Steam Generator where: C is a unique number or letter identifying the examination area. For RPV circumferential, meridional, ~nd longitudinal welds, C is the same number tI:tat Westinghouse assigned to the weld. C ends in IRS for inside radius section examination areas. Examples:
.T.,-.________________________
2-RPV-2042A unique Number (Westinghouse number) Rea.ctor Pressure Vessel Unit 2 T 21-Ts=-r_s.----~--~-
- , Unique Number Steam Generator
--------------------------~steam Generator No. 21 4 03 RN-T. .
1 _-TP. _ -_T_R_
...S:::::::::_-_-_-_ Inside Radius Section Unique Number Pressurizer Nozzle
.....~----------~----------~Nozzle for 4-in. Line B-iv
- 2. Piping For piping welds, the following format is used:
AA-BB~CDEE-F-(-G) where: AA denotes*the nominal pipe diameter of the line. where: BB denotes the piping system associated with the line (determined by PSE&G valve nomenclature), as follows: BF Steam Generator Feed CS Containment Spray CV Chemical and Vol~me Control System MS Main Steam PR Pressurizer Relief PS Pressurizer System RC Reactor Coolant RH Residual Heat Removal SJ Safety Injection where: C has the following options: 1 Class 1 examination areas 2 Class 2 examination areas where: D is the integer 2 and denotes Salem Unit 2. where: EE is two integers asigned to assure uniqueness. For the Main Reactor Coolant Loops, the first* integer correlates with the loop number and the second integer is zero. where: F is assigned to assure uniqueness and to designate the type of weld as follows:
- a. If only a one- or two-d1git integer appears, this indi-cates a circumferential weld. The welds are numbered consecutively in the direction of flow. Where the direction of flow is ambiguous, a flow direction is assumed.*
- b. For other than circumferential welds, except branch connections, two letters are added to the circumferen-tial weld number which either intersects the"weld (in the case of the longitudinal welds) or is upstream from
.the component, as follows:
FB Flange Bolting LU - Longitudinal Seam Weld Extending Upstream LD - Longitudinal Seam Weld Extending Downstream PL - Pipe Lug (Welded) PS - Pipe Support (Welded)
SC - Support Component Portion of A Welded Pipe Support PR - Non-Welded Pipe Restraint where:,--G is an integer assigned when there is more than one compo-nent [see (2) above] of one type or a longitudinal weld between successive circumferential welds. This number in-creases 'either sequentially from the upstream weld or clock-wise from Lo, a standard reference location used for piping (see examples). On double seamed elbows, the weld located along the outside radius is denoted by the letter "O", and the weld located along the inside radius is denoted by the letter "I". Example: AA-BB-CDEE-8 . AA-BB-CDEE-7PL-3 AA-BB-CDEE-7PL-1 AA-BB-CDEE-7PL-2 AA-BB-CDEE-7 For branch connections exceeding 1-in. diameter nominal pipe size for Class 1 and 4-in. diameter nominal pipe size for Class 2, both the main run and branch line are identified and separated by a diagonal slash (/). To locate the branch connection, the upstream circumferential weld on the main run is also identified. Example: *29-RC-1210-2/14-RH~llll is the. branch connection from the iine 29-RC-1210 downstream from weld Number 2 which connects line 14-RH-1211. B-vi
'-....-2.1-STG - SOUll ~
I[ SllELL f> I
.'ill[LL C
/
/ ---.:: .
TIUINSI TION ',.__ 2.1- S TG--TC.SC
" " -2.t-STG-MB'lO .
/ COi£
' / C6oLTUJG)
--32..-MSN-2211-1. "' "'-,._ '2.1:--5T&-SRTC SllELL 0
/ .
'l'/00
\ __ 2-"l- -STG-MBZ.70 (flo*-TltJG)
SllEL L ll STUD '--2.'t-ST&-STOSR UrrER I 1£Ao Dll RP.Et CLRS~ 2 CLA'>S I runE SllHl ---2.1-STG-T5Sl0
*l'L-3.-CS-51.-SAH (t;ti-c. Helde)
J 1lrCS-4. 5-80-SAH (No:i:d e-to-Vouool Uelds)
- l. 250-8-11-CS-100-SAH l1 Sl!llG No: Sttuun Guuerutor 1124 PSIH'G DHIP1098Jl7 Wat hoe ** Fla.) 'fhldnoss: ---------'---
~~~~~~~~~--~~"---"---~
S111l I No: Steum Cu11er;1to1- /J24 Baaic Cal. Dlk.1 Seo Above*
r*1*
'---23-STG -SlllJll ~
SI II'. Lt () ]I
.'>llEl.L C MANWAJ' /
/"' -2J-SJG-NB'\O TllllNSJ HON *****--23-ST&-TCSC
' / (6oLTUJG) COl'E .
to N I @-- -31..-MSN-2.231-l SllELL D
"--23-ST&-Sl\TC
/
z.*100
\ _ _ 2*:t-5TG-HB2.70 SllEl.L II
(()o&..TIH<>) STUii *'- STG-51USll Urr>ER I 1£Ao DllRREI_
--23-STG-T5S.IO
"'l'I.-3-CS-51-SAH (Clrc. Ueldu) l'l.-CS-4. 5-88-SAH (Nozde-to-Vesael Welda)
- 1. 250-U~B-CS-100-SAtt l'Sll~G No: Stoa111 Generator 121 PSl!IU1 Pwg: 1098Jl7(Wat hoe, Fla. "fh ldnoss:
Swll I No: Steu111 Generator 121 Bauic Cal~ Blk.s See Above"' Pl guro: B-2
I( SllELL I>
.4)1 l[ll c
/
TRllNSJ TJON *,'---22.- s T&-TCSC.
,, "' "' ..- l.2.- 5 TG -MB'IO CONE
' / (6oLTINO)
~--- --32..-M5N-2221-I '-22.-ST&-5l\TC
/\_~J SllELL 0 U.-STG-MB270 SUELL ll i.*10° (f3o'-TIN~)
s TUU*""' .....___ 2.2- sT G - s10sn Dlll\REt
-~[CLAU I
- _ TUUF _*_SllHi
_ _ ---z2.:-5TG-T5Sl0. 1 1 fJ D
*l>i.-l-CS-51-SAM (Ctrc. Weldu) 111.-CS-4. 5-88-SAM (Noule-to-Vceoel Welda) 1.250-H-O-CS-100-SAH PSt:l&G No: Steu111 Gener utoc 122 p SI! ti 0 Ow 8 : 1098.Jl 1 !.;;.W;;...at~*h~o.._e..._
* .._.F_.l'""'a,...~f_h_l_c_k_n_o_s_1_:__________ --_-_-_-_-_--_-_-_-_------*
!il~ll I No: Steu111 Generator 022 Bode Col. Blk *. a See Above* Plguro~ B-l
~
."'-- 5 Tfr - SOIJI I
.'illf: LL I> ]I . ~
o* !ill[l.l c
,, /
TRllNSJ HON "-- S T6'-TCSL
, ,, " - 2.l-STG-NB4tO CON=:
' / 160LT1NO)
@}- -- 3l.-M5N- 2-2.11 ~l SHELL 0
."-- ll-ST&-SDTC
/
ll- STG-MBZ.70 .SllElt A (()oL-TING) STUD "--ll-STG-STOSR UPPER 1-11:.m OllRREt
~[- TUil£ Sll£El ----- 21-'STG-lSSTO CLA\5 t - * - - - - -
- Cl []
*flrl-CS-51~SAH (Ctrc *. Welda) l'lrC:S-4. 5*-80-SAH (Noz z lc-to-Veaaol Welda) ._!. 250-ll-ll-CS-IOO-SAH PS~~G No: Steam Generator 121 PSUflG Dwg: 1098Jl7(Watghse,Flo. 'la 1elm0 SS : ----------~
S11lll No: Steam Generator 121 Bade Cul, Blk. 1 Seo Above* ltlguro: B-4
1 - - - - - - - 2.-CVCT- I CL - CulT,ltLIN~ Of Q tlA11wAY)
~~-CVCT-MWV-NUTS b:I I
Ln 2.-CVCT-2VS-7
- 2-CVCT-MWY-BOLTS 2.-C.VCT-2VS-3 2.-CVCT-lVS-5 ---1 2-cvcr-zvs-1--* * - - - 2. -CVCT- 2..
2.-CVCT-2VS-2. --z.-cvc r-2vs-0
*l'l.-SS-.250-97-SAH (Ve1u.iel Shell) 1.125-0-N-CS-101-SMI (Nute)
*1.125-6-U-CS-107-SAH (Holte)
PSHQG No: Chum. & Vol. Control 'l'k, PSl!IUi Dwg: --- hlcknou: 1-1 811 -Bolting Swll 1 No: Chem.& Vol. Control 'l'k. Uaatc Cal, Diie., a See Above* Plguro: B-5
~
NoTE; Vc!;5El- 11> OJ 1<0011 NEICT To RllE lltlJ> llccu*101...,rol\ ~f 2. 3
~-£LHEX-2.
2.- £.LHE X-l
-Lo , 2-EUIEX-NUTS
~- . - 3*
1
- J
.l------------------- £1."'BZ.'
(tJorE: VESS~L 2-£Uf£X-STUDS Ill lla~ll-OIJT/IL
*9. 5-SS-. 750-86-SAH (Vesoel Shell) ro51TIOIJ) 1.625-8-S-CS-98-SAM (Studs)
- 1. 625-IJ-N-CS-92-SAH (Nute) l'SBl\G No.: Exceue l.tdwn. lieut Ex. l'SH&G Pwg: -- *r11lclrnoss =1-5 8" Nute & Doi a' Swll I* No: ~xcceo Ltdwn. lieut l!x. Daoic Cal. Dlk. 1 See Above* Flguro:o-6
Vt:.uT I
* - - - - 2 . .. EllEHtT*----*
CTYr.)
~2.HIT-j. l
~-- -2. 11 Exi11PT-*---
2."1-lff:I (T\'P.) 23-llT-1 No. No. No. No. 21* 2-3 24 2.2-2J-tH-2 t'.Z-HT-2. lHIT-~ _ _ /2'1-llf-2 \ 0l *- I" E.. i:.,.r1 ***
- 2.JWRLlo l""iWl~LL (HP.)
~'LV/ll(,l, I L--[><J
,-L*
l><J---1,L (El.;< llO') (><J--J,L To l<t*. 1>11.. 111 T 11111<. PSllllG Pwa: --- 'fb l clrno u: --- SHlll No: lfo11J 'l'unko Bode Cal. Olk, a 6-SS-10-.140-45-SAH
Hore: Vu~fl. 1~ 1tJ TllE Ro m EAST 0
&)F THE WE.ST STIURWELl..
CLASS 2.1CLASS3
<)~-- ----(>
2.-LHEX-I-I I I I ii - : ll b:l I 00
-----------"----- £l. a 88'
{Non: lie. ~SEL IS "' l-LHEX-2. llo1u1.ol.IT/IL Posi Jl.:>,J) l'SDQt; No: l.utdown lieut Exchanger PSBllG Uwg: -- hlclnoss: 1 211 (veeocl), 22" Jta. Swll I No: l.utdown Uuat l!xcluma;em: Bade Cal. Bllt. 1 Pl.-SS-. 750-0S-SAH P 1 guru: B-8
'L. -R.C f - 5VS li111.u 8 VS l-Rt:f-13VS T111tu ILVS
- _J.....:. __ '
*-- -I I
1----- **
---Vii'.O~EL c_;11t1*11u'i (Su T11r V1Ew) lTOP VIEW) w*
PSIJIHi No; llcuctor Coolunt ft lter PSCQG Dwa: __ hlclrnoss: 14" dla. (veuuel) Si.ll I No; lleuctor Coolant lll I tcr Bade Cal. Blk. I 14-SS-lO'-. 250-96-SAH 11 l cure: B-9 ...........--.1.......................-............a............-...................._...........................................................~
Our 2-RHE-3il 2.-RHE-2 I I SunL A I IJon: Vusu." 111 Root* ~&lllL Sul'IOAV W1LDI c::.,..,.r 8a l ,r IJEKT TO /lcct1flllLAJOfl Eo11H1w1e P.,1 le Lnu1 HD llccu1. tJo.21. 2-~HE-7 f2.-RH£-5 l.-RHE*C.-*~ 2-RHE-8
' \ I td I SHILL 8 f-'
0 I ( ' l. 2.-RHE-12
-2.-fUIE-'\ 2-RllE*llt 1 ~2-Rt1£-13 SHlLL c I
' I 2:RUE*IO- I I I I
I I IM t +Our l'SUltG No: Resenerutive lleot Ex. PSl?4G llwg: --- 1*r1a1 dnoss: --- Swlt I Ho: ltegenerattvo lieut Ex. DauJc Col. Dlk. a 9. 5-SS-. 750-06-SAH
No. 2.1 CldS5 J CLllSS 1 U-KMRl"IEX-IVS-----
*1*1.-ss-. 150-05.-SAH (Veoocl Welda) l.115-0-fi-C.S-99-SAH (Studo) *1-1/0 11 - Studo
- l. )JS-8-N-C.S-l04-SAH (Nuto) 1-l /8" - Nuts l'Sllllfl Ho: mm llc1.1t li:xchanacr 121 PSUGG Pwg: --- Thlclness: See Above*
*-~~~~~~~~~~~~~~---~~~~~~--..--~~~~~--,-~* ~h~lll Ho: lt!lll llt!a t li:xchanacr I 21 BoaJc Cal. Blk.1 Soe Above* 11 i guro: 8-11
CldSS J td cus 1 I I-' N
*1'1.-SS-. 750-85-SAH (Veooe 1 Waldo) 1.175-8-S-CS-99-SAH (Studu) *1-1/8" - Studo
_b 175-8-tl-CS-104-SAU (Nutu) l-l/8 11 - llut11 l'SDUl Ho: Hllll lieut Exchanger 122 PSDllf1 Pwg: -- lalclrnoss: Seo Above* Swll I Ho: llllll lleot Exchanger 122 Bade Col. Dlk. 1 Seo Above* l'lguro: 8-12
*14-CS-80-.760-35-SAM *0.750 11 (14 11 -80) 14-CS-120-1.14-36-SAM 1.094" (14 11 -120) 16-CS-160-1.610-14-SAH l. 594 11 (16""."'160)
PSll&G No: 14"-2DP1019 PSl!&G Dwg: SGF-2-3 Sht. 4 Thickness: See Above:* SwRI No; . 14-UP-2241 Basic*Cal. Ulk.: See Above* Pi gurc: D-13
*l/1-CS-80-. 760-35-SAM *O. 7.'.>ll' 1 (14"-30) 14-CS-120-1.14-36-SAH 1. 094" (14"-120)
~6-CS-160-1.610-34-SAM 1.594 11 (16"-160)
Page 1 of 2
.. ~il!ll G Nu : 1 4 II - 2 DF l 0 1 1 11snnG owg: sGr-2-3 Sht. 1 Thickness: See Above:*
Swill No: 14-DF-2231 Basic Cal. Blk.: See Above* 11 i gure: 8 _14
1'1 td j'1 I Ln
*14-CS-du-.7bu-J5-Si\H 14-CS-120-1.14-36-SAM *O. 750 11 (14"-80) 16-CS-160-1.610-14-SAU 1.094 11 (14"-120)
Page 2 of 2 1.594 11 (16 11 -160) PSl!lj(: No: H"-2Ulll017 PSfl&G Dwg: SGF-2-3 Sht. l Thickness: See Above* SwUl No: 14-BP-2231 '.Basic Cal. Blk. : See Above* Piguro: B-15
lb
*14-CS-80-.760-35-SAM 14-CS-120-1.14-36-SAU *O. 750"(14"-80) 16-CS-160-1.610-34-SAH 1.094 11 (14 11 -120) 1.594 11 (16 11 -160)
I' s l!ll (j N(I : I " II - 2 D1: I 0 I 5 PSU&G Dwg: SGF-~-3 Sht. 5 Thlcknoss: See Above:* SwHI No: 14-ttF-2221 Busic Cal. Blk.: See Above* figuro: B-16
~iJ 11fS j_ ,.,. 11f5 5te.tll'~tor Gt11tr 15* !"' .
~o. 1so 11 (14 11 -ao) l.094"(14 11 -120) l.594"(16"-160)
*14-CS-80-.760-35-SAM 14-CS-120-1.14-36-SAH 16-CS-160-1.610-34-SAM l'Sl!llG No: 14"-28111013 PSE&G Dwg: SGF-2-3 Sht. 3 Thickness: See Above*
Swlll No: 14-UF-2211 II l gure: D-17
s,f/ t~C tp I I-' 00
*6-SS-40-.330-44-SAM 6-SS-60-.464-32-SAM l'SIHW No: 6"-2SJ1423 rsn&G Dwg: Rll-2-2 Sht. a Thickness : o. 32211 (40) ,o. 500 11 (60)
SwRI No: 6-CS-2225 Baoic Cal. ilk. : See Above* Figure: B-18
*8-SS-40-.330-44-SAM 8-SS-80-. 484-32-SAM
~~~~~~---,.--~~~~~~~~~~~~~-.-=-~~~~~~~~~~~~~~*
l 1 Sl!l~G No: 8 11 -2S.JH24 PSIHlG Dwg: Rll-2-2 Sht. 5 Thickne.ss:o.322 11 (40),0.50011 (80)
- -~~~~~~--~~~~~~~
~ii~ll l No: 8-CS -2 215 ~aelc Cul.Blk.: Sae Above:* P i g u r o : n-19
tJj I N 0
- 0
- 14 8 11 ( 8 II - 10)
*8-SS-10-.140-24-SAM 0
- 2 5 0 II ( 8 11 - 20) 8-SS-20-.268-33-SAM 0.322 11 (8 11 -40) 8-SS-40-.330-44-SAM
~PSB&G Dwgs: CV-2-2 Sht.6 Page I of 3 *rsE&G No: 8"-2CV1020, 8 11 -2SJ100J/1005/1109 Rll-2-2 Shts.
' 6ti 8 PS~&G No: See Above* PSB&G Dwg: See Above* Thickness: See Above:*
S1~1ll No: 8-CV-2201 Basic Cal.Dlk.: See Above* Figure: B-20
*
- Revised October 1984 *
© b;j I
N I-'
*8-SS-IO-.B40-24-SAM *0.148"(10) tl-SS-4D-.3J0-44.,.SAM 0.322 11 (40) llrSS-110-. l18ft-31-SAH 0 * .500'1 (80)
*PS1!4G Dwgs: CV-2-2 Sht. 6 llll 2 sh ts . 6 &8 l'ilgo 2 of 3 -'l'SI!&(; No: 8"-2CVI020, 8 11 -2SJ100l/1005/1109 PS I! II G No : Sc e Abo v o
- PSfl4G Owa: Seo Above* Thickness: See Above:*
Sulll No: 8-CV-2201 aasic Cal.Dlk.1 Sec Above* Pl gure: B-21'
b:I I N N
* *8=-SS-10-.140-24-SAM 8-SS-40-.330-44-SAM
*PSE&G Dwgs: CV-2-2 Sht. 6 Page 3 of 3 *PSE&G No: 8"-2CV1020, 8' 1 -2SJ1003/1005/ll09 Rll-2-2 Shts. 6 &8 PSl!&G No: See Above* PSE&G Dwg: See Above* Thickness: See, Above*
Swill No: 8-CV-2201 iasic Cal. lUk. l aee Aboveis. Figure: B-22
(th.,,.
. -1~
t>l I N w
*6-SS-40-.2(17-26-SAH *.28011-(40) 6-SS-80-.432-68-SAH .412 11-(00)
P S 1111 Ci No : 6 11 - 2 CV 11 24 P S l!fl 0 ll wg : CV 2 Sh t
- 6 'fhlcknoss: See Above;*
~~~~--~~~~~~~
Swill Ho: 6-CV-2212 Baetc Cal. Dlk.1 Bee Above* Pl gutc: n-23
(£1~ I
*11'1~
b:l I N ~
*6-SS-10-.140-45-SAH 6-SS-80-.412-68-SAH PSl!llG Ho: 6 11 -2CVl121 PSH4G Dwg: CV-2-2 Sht. 6 h I ck nos s : 0.134 1' (10) ,o. 432 11 80)
Swill No: 6-f.V-2211 pau!c Cal. Blk.z Seo Above* Fl guro: B-24
- 1' tp I
N lrl s I'S I! II ti No : 6 11 - 2 SJ l I 0 8
- I I I 0 PSP.&G Dwg: Rll-2-2 Sht. 8 'fhickness: 0.134 11 Swill No: 6-CV-2201 Jhrnic Cal'. Jilk.: 6-SS-lQ-, 140-45-SAM foiguro: n-25
PSIJ fjG No: 34"-2MS1020 PSl!&G Ol~g: MS-2-3 Sht. 5 Thickness: 3.314 11 Hin. Wall Swill No: ~aaic Cal. Blk.1 3x6-CS-26 (SwRI)/PL-J-CS-51-SAM fligurc: 8-26 34-MS-2241
bj I N -....J PSU&G No: 34 11 -2MS1012 rsn&G Dwg: MS-2-3 Sht. 4 Thicknass: 3.314 11 Min. Wall SwRI No: 34-MS-2231 Basic Cal. Blk. I 3x6-CS-26 (SwRI) /PI.-3-CS-51-SAM Figure: B-27
b:l I N 00 PSl!&G No: l4 11 -2MSJ028 rsn&G Owg: MS-2-3 Sht. 2 Thickness: 3.314" Min. Wall S wIll No : 3 4 - Ms - 2 2 2 l *Basic Cal. Ilk. 1 3x6-CS-26 (SwRJ)/l'l.-3-CS-51-SAH
l,Sl!liG No: 34"-2MSl004 rse&G "w~: MS-2-3 Sht. l Thickness 1 3. iH4" '}Un. Wall Swlll No: 34-MS-2211 Basic Cal. Blk; 3x6xCS-26 (Swlll)/,PL-3-CS-51-SAM Figure: 8-29
b:l I w 0 PSIHIG No: 32 11 -2MS1019 PSB8G Owg: MS-2-3 Sht. 5 Thickness: 1.07311 Hin. Wall Swill No: 32..:Ms-2241 iaaic Cal. Dlk.: 32-CS-XX-1.618-47-SAM
p s I! 11 G H() : 3 2 II - 2 Ms l 0 I l rSll6G Owg: MS-2-l Sht. 4 Thlcknoss: 1.07311 Mln. \lall SwUI No: 32-MS-2231 Bnllic Cal. Ill k. I PL-1. 5-CS-65-SAH 11 l uure: 11-ll
td I w N rsu~G No: l2"-2MSID27 rsn&G Dwg: HS-2-l Sht. l l'l'hlcknoss: }.07311 Hln. llall Daaic Cal. DU.* a PL-l.5-CS-65-SAH 11 1 guru: u-12
w
?
~
. I l-1-.1
'.J to I
w w
-~~~~-~~~~*~~~~~-----~~~~~~~~~~~~-,--.--,-.....,---,-~~-,-~~~~-
l'Sl!llG No: 12 11 - 2MS I 002 PSIHlG Owg; JIS-2-l Slat. 1 IThlclrnoss:-1.01111 Hin. Wall
*~~~~~~~~~-~~~~
Sw"I No: l2-MS-22JJ Buote Col. Blk.; PL-l.5-CS-65-SAM Pi gurn: 0-33
PSl!liG No: l0"-2MS1017 PSHliG Uwg: MS-2-5. Sht. 5 hldnoss: 1.007" Hin. Hall . SwRI No: lO-M~-2241 Buote Cal. BU.* I PL-1. 5-CS-65-SAH 11 i ft u a* o : 0-14
b:l I w \J1 l'SIHHi No: 30"-2*1SICHHI PSlHHi Dwg; MS-2-l Sht. 4 'l'hlclrnoss: 1.007" Hin. Wall
~~~~-*-~~~~~~~~~~~------~-~~~~,-~~~~~-*
S11lll No: 30-MS-2231 Boote Cal. Blk. 1 PJ.-l * .5-CS-65-SAM 1: l s:uro; B-3.5
l.it*r 7 lu 9
?fl
'~ .,,i;,,
0 11 Sl!4G No: l0 11 -2MSl025 PSl!IHl Owg: HS-2-l S.ht. l
*~~~~~~~~~~~~-&-~~~~~
'l'hlcknoss: 1.00711 Htn. Uoll Swttl No: lO-HS-2221 Baeic Cal. Dlk. 1 l'l.-l.5-CS-65-SAH 1: I a:un.1: D-16 .
<!)
PSllllG No: J0 11 -2MSIOOI PSl!~G llwa: MS-2-l Slat. I . 'fblcknoss: 1.001 11 Hin. llall SwHI No: lO-HS-2211. Baste Cal. Blk.; PL-l.S-CS-65-SAH a: i gau*o: B-31
- b:I I
w 00
*6-CS-80-. 41211-49-SAH *o. 412 11 (6 11--00) 8-CS-160-.906-46-SAH o. 906 11 (8"-160) 1.625-0-S-CS-89-SAH l.625"(Studa) 1.625-0-H-CS-92-SAH l. 625 11 (Nute)
*rsr.&G No: 8 11 -2MSllSS 8 11 -UISllS8 *8 11 -2MSll61 8 11 -2MS1164 8 11 -2MSll67 6 11 -2HSl492
*swnl No: 8-*IS-2241 8-MS-2242 8-*iS-22U 8-~ts-2244 8-MS- s a:JIS-2246 rsu~~ Ho: Soo Abovo* PSH4G Pwg: HS-2-1 Sht. 5 __ f!£!.clo_*~s 5: Soo Abovo *
~~~~~~~~~--~~~-*
Sw"l No: Soo Ahovo* Buatc Cal. Blk.; Su~ Abovo* 11 l guro: 0-38 *
*6-GS-80-.43211-49-SAH *o. 412 11 (611-80) 6-GS-160-.118-69-SAH o. 718 (611-160) 11 8-GB-160-.906-46-SAH o. 90611 (811-160) 1.625-8-S-CS-89-BAH l.62511 (8tuds) l.625-0-B-CS-92-SAll 1. 62511 (Nuce)*
VSfl&G No: Soo Above
- rsuaG owg: MS-2-l sht. 4 Thlcknoss: Soo Abovo:*
Swill No: Soe Abovo* Baalc Cal. Blk.& See Abovo* r: l guro: B-39
td I .i:-- 0
*6-CS-80-.432-49-SAH *0.43211 (611 -80) 6-GS-160-.718-69-SAH 0.118 11 (6 11 -160) 6-CS-160-.906-46-SAM 0.906 11 (8"-160) l.625-0-S-GS-89-BAH 1. 625"(Studu) l.625-8-N-CS~92-SAH 1. 625 11 (Nuts)
"'PSllliG Ho: 8 11 -2MS1198 8 11 -2MS1201 8 11 -2MSl204 8 11 -2MS1207 8 11 -2MS1210 6 11 -2MS1498 SwiflNOT"" 11-ns-=-:rnr - 8-its-2223 8-MS-2224 8-MS-2225 6-MS-2226
_ai._s1_H_H_i_N_o_:__s_e_e_A_b_o_v_o_*_ _ _ _ _ 1-P_s_u_r._L:_1_>w_c_*:_i1_s_-_2_-1_s_1_1t_._2____ (1*1~~~ Imo s !I : s oo Abovo ~--- th11ll No: Soo Above* 11iu11 ro: D-40 Basic Cal. Blk.1 Seo Above*
/
/
/
/
rsunG .No: Soo Abovo* rsu&G Pwu: MS-2-l Sht. I Thlcknoss: Soe Abovo:* Swill No: Seo Ahovo* 1: l guro: B-41
- Daoic Cal. Blk.a Geo Above*
c~r , _.
*pso~G No: 6"-2MSJ186 6 11 -2MSl246 6"-2MSJ138 6"-2MS1091 *swnl No: 6-MS-2247 6-MS-2237 6-MS-2227 6-MS-2217 ~~~~--*~--~~~-~-~~--------~~~~~~--y--~-,,.---~-~~-~-~-~-*
_P_Sl_!l_IG_,_N_o_:_s_o_o_A_l_io_v_o_*_ _ _ _ _ PSlllHi llwg :*tS-2-l Sh ts. l, 2, 4, S l't'h l clrnoss: 0. 432 11 Swill No: Seo Ahovo* Daeic Cal. Dlk.1 6-CS-80-.432-49-SAH ll1igu1*0: D-42
_s-1~e",(ii.) J ~/e.ld oJI /4-S 5 o'~ 3 SwRI No: 6-MS-2231 Daoic Cal. Blk.r 6-CS-80-.432-49-SAH l'l guro: D-41
~ii~lll No: 6-f.IS-2211 Dueic Cal. Olk.I 6-C0-80-.412-49-SAH. Fi11111*0: U-44
'\
/
*. i*},y
*-~~l~-'~~~~~~~~~~~~~~~~~~~-.==-~~~~~~=--~~~-,---
11 l'Sl!liG No: 6 -2MS1056 PSIHW Pwg: MS-2-2 Sht. I l'hlclrnoss: 0.432 11 Swill No: 6-*ts-2211 Boote Cal. Blk.1 6-CS-80-.432-49-SAH H guro: B-45
i 1aago I of 2 l1 Sl!llG No: 12 11 -2PlllOIO PSDl&G Owe: llC-2-l Slit. l hlclnoss:
~~~~~~~~~~~~-*
Swill No: 12-PR-2201 Baetc Cal. Dlk.z 12-SS-OOS-.500-66-SAH a:tguro: B-46
IS IZpa
"'I
*A 12-SS~ BOS-. 500-66--SAM *0.40611 (12 11-BOS) 1.250-8-S-SS-90,,.SAM
- 1. 25011 (Studu)
Pug e 2 of 2 1. 250-8-N-SS-93-SAH 1. 250 11 Nuts _1_s1_:Ii_'G_N_o_:_1_2:._*11_-_2_P1:._n:_o_;_1_,0_ _ _ _ _r_s_c_&_G_D_w_c_:_n_c_-_2_-_l_S_h_t_._l_ _ _ ..T_h_i~~~-~. _s_s_:_s_e_e_A_bo_v_e_*_ _ _ __ 1 1 Swttl No: 12-PR-2201 Basic Cal. Blk.: See Above* Figure: 8-47
I *) (f.l.1St S ,_,. 6*-:::::;;~;:::------
~ Ps ..3
\()1 PS l!ll G H o : 6 11 - 2 P ll l fl 0 4 PSB4G Dwg: llf.-2-l Sht. 5 'fhld.noaa: 0. 280 11 Swill No: 6-PR-220S Buote Cal. Olk.; 6-SS-40-.287-26-SAH Fl guro: B-49
- * ~-'fl .... *5f s')
iPs
'1 1
l'Sll&G Ho; 6 11 - 2Pll I 006 PSUG Dwg; RC-2-l Slat. 3 Thlcknoss: 0.280" SwRI Ho: 6-~ll-2204 Buote Cal. Blk *. 1 6-SS-40-.287-26-SAH Plguro: B-so*
b:I I Ul 0 l'Sl!llCi No: 6"-21'1l100S rseco Pwa: ac-2-1 Sht. l Thickness: 0.280 11 Sa*lll No: 6-l'll-2201 Boote Cal. Ulk.1 6-SS-40-.287-26-SAH 111 cu ro: U-51
i] . 3 J_
- 0 B *-*-
'l
----*~----*r 5
'l ..
.. 1, ..* l (f.l.111')--...
l-- - - --- -- -- - __ , ,. / .- t-PR- Z'.'.O I l1 !il!l1Ci No; 6 11 - 21'R I 001 l'Sll4G hwu: RC-2-l Sht. 1&5 Thlc~nos*: 0.280"
------------~* ---~~~~--~--..~----- ~1~ll I No: lluoJc Cal. Blk. 6-SS-40-. 287-26-SAH 11 l1:ul"o: 11-52 6-l'lt-2202 &
Revised August 1984 td I I.JI N
*11-:i!i-40-. 21i7-26-!iAU 6-S!i-80-.412-bO-SAH
'"0.280"(6 11 -40) 0.412 11 (6 11 -80}
rstt~G Uwc: hC-2-l Sht. l~S
- i II II I uII ; 6 -1' ll - "l. 211 I 11111.1 I c Cul. Olk. & Suo Abovo*
t:;OtsJ:P'¥"\MUM-:ISI t==n*-atW'r?Y MM'"a.'C:I "nt Revised January 1985 tp I Lil w
/f "
. ize (i f'l ~~'. it,,,
"ll1-fHi-40-. ld0-7!HSAll B"" l
,,r n
*O. 430 11 (14 11-40) 1.125-U-!H.iS**!) I-SAii 1.125" (StuJu)
- l. I 25-0-u-s:HJ4-SAll l .125 11 (tl11t u)
_11 _!i_111_i,;_11_0_:_*_**_"_-_:.!1_11_1_11_1o_i_ _ _ _ ~-sn_f.,_*_uw~.!.. ~!!!-~.- ~-- ~h! :._! ___ J_rl_il_c_~!'e ss-:-suo -,._.._:*.':'u" _ __ 1: l 1111ro: u-54 Ouulc Cul. Ulk. I Suu AhovuA
- !;f;-n : o.rn :r, ,,
'll_I
*"""'IV Oil!; I "'>SIR *111~ :tJOlllf I* H Z - II 11 "' H MiCCQZ . . aPW6JiW . .
- o rr I 11 " !:
¥1:11\oqy OO!J : f; !: o" '1 :> f I.* r
- 1 *rs t:..:.z-1111 : :h*(f :J~li!S*I *-----'-(.~!!.!~!~!I:.!!t_I_:_o~~~~~!!: *--
("l"ll) .. ~ll *t llVS-'16-SS-tl-U-!;l l "l cnrn:ts) .. ~n*t UVG-16-SS-S-O-*!a; I* I to'l-.. '1 I) ..nn *o
- llVS-6l-UC'1°-0'1-SG-'ll¥
. ~:m::Al'.1!Cltf.. ~C::::- ... ;:::::siWWW::::.:..~!:'~T~IJttt:t!...,. ... =:::zCCU:::.....,-.--~ir..;:a:a:a::::U::X:.~i&O~J)t(f!d!!!&t£S:ilW<CL4JSm_AE.9Ji"'**~*****-... *** .. *.....
b:I I lJl lJl 1'.J
*nu-2-2 sa.t. 1 l'agu l of 2 llll-2-l Sht. 4 ~14-SS-40-.418-79-SAH o. 41811 (14 11-40) @
14-SS-160-1.400-78-SAH 1. 406" (14 11-160) PSUllG No: 14 11 -2Rlll001 PSll4G Pwg: Soe Abovo' rhlcknoss: See Above:* Swll I No: !4-llll-2212 Dasie Cal. Blk. J Soe Above* 1:1guro: D-56
THIS SECTION OF PIPING IS LOCATED IN PIPE CHASE .. td I 1.11 °'
- ':)')
/.,
.,..6 (f.L*.
*Rll-2-2 Sht;. 7 Page 2 of 2 IUl-2-3 Sht. 4 PSl!~G No: l4 11 -2lllll00l PSIHlG Dwg: See Above* hi clrne s s: 0.438 11
*-~~~~~~~~~~~~*
SHlll No: 14-llll-2212 Piguro: B-57 Daeic Cal. Blk.: 14-SS-40-.438-79-SAH
3 b:l I . l.n
*8-SS-40-.330-44-SAM 8-SS-80;484-32-SAM 11 s1:nG No: 8 11 -21u11020 PSB&G Dwg: Rll-2-2 Sht. 1,2. Thi ck nos s: o. 322 11 ( 40) ,0. 500 11 (80)
SHlll No: 8-Rll-2274 Daatc Cal. Olk.: Sac Above* Pignare: B-58
(l 13 bJ I Ln 00 PSllll'1 No: 8 11 -21llll016 PSl!llG Owe: Rll-2-2 Slit. 1 2 blcknoss: 0.322 11 Swill No: 8-llll-2273 11lgurc: D-59 Daolc Cal. Blk.1 0-SS-40-.130-44-SAH
*8-SS-40-.ll0-44-SAM 8-SS-80-.484-32-SAM
_1_'s_*u_&_n_u_o_*~B-"_-_2n_11_1_0_14~~~..,....-*-P-s_n_go~o_w_u_:_1_u1_-_2_-2~s_h_t_._1~,_l~-~r_h_l_ck_*_*u_s_s_:_o._1_22~",_(4_0_)_.o_._so_o_ 11 c_a_o)~- swn1 No: 8-llll-2251 Baste Cd. Olk.a Seo Above* lliguru: B-(>O ..
b:I I CJ' 0
*8-SS-80-.484-32-SAM *0.500 11 (8 11 -80) 8-SS-40-.330-44-SAM 0. 322 11 (8"-40) 12-SS-80S-,500-66-SAM o.soo11 (12 11 -8os)
Page I of 2 *8"-2Rll1003, 1004, 1005 PSl!fiCi No: Seo Above* PSlHlG Dwg: Rll-2-2 Sht.
- l Thickness: See Above:*
S wIll No : 8 - IUI - 2 2 2 6 Basic Cul. Olk.; See Above* fl cure: B-61
*8-SS-80-.484-32-SAM *0.50011 (8 11 -80) 8-SS-40-.330-44-SAM 0.322 11 (8 11 -40)
Page 2 of 2 *8"-2Rlll003, 1004, 1005 rsnnG No: See Above* PSll~G Dwg: Rll-2-2 Sht. 1 Thlclrnoss: See Above:* Swill No: 8-llll-2226 Basic Cal. Dlk,: See Above* ll i guro: B-62
b:J I °' N
*8-SS-80-.484-32-SAM *0.50011 (8 11 -80)-
8-SS-40-.330-44-SAM 0. 322 11 (8 11 -40) l2-SS-80S-~500-66-SAM 0.500 11 (12"-80S) Page l of 2 *8 11 -2n111010.1011.1oso PSfl~G No: Sec Above* . PSF.llG Dwg: llll-2-2 Slit. 2 Thickness: See Abovo:* S&~lll No: 8-llll-2216 Haeic Cal. Blk.; See Above* Pi guro: B-63
/
5i r 11
*8 -2Rlll010 1011 1050 1Vz2.
*
- 11) . . (l" Page 2 of 2 v 11s1!1\G No: See Above* PSll&G llwg: Thickness: 0.322" s1.,lll No: 8-llll-2216 Dasie Cal. Olk.: 8-SS-40-.330-44-SAM 11 lguro: D-:-64
PSl!r.n No: l4 11 -2S.110l4 PSl!liG Dwg: Rll-2-2 Sht. 3,7 l'fhlclrness: 0.438" Swill No: 14-SJ- 2224 Basic Cal. Dlk.1 14-SS-40-.438-79-SAH lllguro: D-65
b:J I °' \Jl l1 Sl!l\(i No: 14 11 -2SJIOlS PSIHU: lhqp llll-2-2 Sht. 3 7 fhlckuoss: 0.438"
~-----~.~~--~~~-*
Swill No: 14-SJ-2214 1: l uuro :B-66 Basic Cal. Blk.1 14-68-40-.418-79-SAH
- Psa:r.r. No: l2"-2SJI001 hiclrness: 0 377 ..
Sw~I No: 12-SJ-2269 Pi gure: B-67 BaeJc Cal. Blk.: 12-SS-40-.377-31-SAM
© THIS POR-TION *oF PIPING LOCATED IN PIPE CHASE. NOTE: For the preservice examination this system was designated as safety injection (SJ). For subsequent inservice exaruinationi this is rcdesignated os residual beat removal(Rll).
*12-ss-40~.111-11-sAM *0.377 11 (12 11 -40) 12-SS-OOS-.500-66-SAH O. 500"(12"-00S)
Page l of 2 1 s l!li G N0 1
- 1 2 II - 2 H11 l 0 0 6
- l 0 4 9 rsn&G Dwg: Rll-2-2 stat. 1 Thickness: See Above:*
SH Ill Nu: 12-IUI -2252 Pi gure: R-60 Basic Cal. Olk.: See Above*
b:l I b1\/ °' 00
...,8 I
, (~I*
NOTE: For the preservice examination thia system wae designated as safety injection(SJ). For uubaequent inservice examinations 12 this is redesignatcd aa residual heat removal(IUI). jl
*12-SS-40-.377-31-SAM *O. 37711 (12"-40) l2-SS-80S-.500-66-SAM 0. 50011 (12 11 -808) 12-SS-160-1.283-21-SAM Pa ~ 2 of 2 1. 312 11 (12 11 -160)
PSl!lllj No: 12"-2Rlll006, 1049 PSIHW Dwg: Rll 3 Sht. 2 bickness: See Above:* S wIt I No : 1 2 - IUI - 2 2 5 2 Pigure: 8-69 Basic Cal. Dlk.: See Above*
Brs
'Z
*Rll-2-2 Sht. I Page I of 2 Rll-2-l Sht. l
~~~~~~~-y--~--~~~~~~~~~~~-.-=~-:-~~~ ~~~~~~~
PSl!&G No: 8"-2SJl295 PSE&G Dwg: See Above* Thickness: 0.322" S wll I No :. 8 - SJ - 2 2 6 2 Basic Cal. Blk.z 8-SS-40-.330-44-SAM Fi 1?uro: B-70
b;j I -...J 0 Puce 2 of 2 *RU-2-2 Sht. I *6-SS-40-.330-44-SAM Rll 3 Sht. 3 6-SS-IX-.660-23-SAM rsn&G No: s~-2SJl295 Th l clnoss: 0.122 11 (40) .o.875"(XX) SHlll No: 8-SJ-2262 Dade Cul. Olk.& 8120 Above* 1: l r. au* 0 : n- 71
*1t11-2-2 Sbt. 2 Pogo 1 of 2 1111-2-1 Sht. 1 l'Sl!l\G No: 8 11 -28.JI 294 Thickness: O.l22" *Swill tto: 8-SJ-2252 Daste Col. Dlk.1 8-SS-40-.110-44-SAH 1: i guro: B-72
t;d I N
,..,5 1~ *8-SS-40-.330-44-SAM *Rll-2-2 Sht. 2
.:: l-*
(~ Page 2 of 2 8-SS-XX- .860-23-SAM llll-2-3 Sht. I
~~~~~~~~-.-~~~-~-.,.~~~~~~~-.-=-c:--:-~~~~~~~'--~~~
PSl!llG No: 8"-2SJ 1294 PSE&G Dwg: See Above* Th l ckness: 0.322"(40),0.875 11 (XX) m-~~~~~--~~~~~~~ s,~lll No: 8-S.J-2252 llueic Cal. Blk.; See Above* Pigure: B-7J
NO'fE: For the preeervice examination this system was designated as oafety injection(SJ). For subsequent inservice examinations thia is redesignated as residual heat rcn1oval(Rll). )* *
. floor-1 o" 1u11*fl (Jtl
*r*t 1
*8-SS-40-.310-44-SAH 8-SS-80-.484-]2-SAH
___r_s_u_ri_G__ N_o_:_*_s_*_*-_2_s_J_1_0_1_;;1_______ 1 11_su_ &_G llwg: Rll-2-2 Sht. 1,0 l'h i ck nos s :o. 322 11 (40) ,O. 500" (80) Swill No: 8 -nu .- 2 2 2 s Fl gurc: B-74 Basic Cal. Olk.: See Above*
NOTE: For the preservice exami-nation this system was designated as safety injection(SJ). For sub-sequent inservice examina-tions this is redesignated as residu81 heat removal(RII) r
- Puge l of 2 *8-SS-4()....330-44-SAM e-ss~eo-.~84-32-SAH l'SC&G No: 8 11 -2S.Jl029 PSIHW Dwg: Rll-2-2 Sht. 2,5 Thickness :o.32211 (40) ,0.50011 (80)
Swill No: 8- IUI - 2 215 11 i g u re : B-75 Basic Cal. Dlk. Saa Above*
10 b:I io6f:I I -....I 1..11
-...... :fz,,
1-ir.s c ii.6
. 'Js.
*8-SS-40-.330~44~sAH Page 2 of 2 o~ss-oo~.484~J2~sAH PSE&G No: 8° 1 -2S.JI029 PSC&G Owg: Rll-2-2 S t . 2 5 'fhicknoss =o 12211 4a o.500 BO Swltl No: 8-SJ-2215 Basic Cal. Blk.: See Above* F i g u r c : . B.,- 76 '
611 - 2 S.Jl 008 ~ 'f "*
,.. "l 6-S.J-2204 PSl!fiG No; Soo Abovo
- rsnu: nws: Rll-2-3 Sht. s Thicknoss: o. 719 ..
llaulc Cul. Dlk.i 6-SS-160-.764-25-SAH I . * **
*l. 250-8-N-CS-105-SAH (Hut) l.250-8-N-CS-107-SAH (Stud)
PSl!llG No: ll~ci1). Charging l'ump 123 PSDllG Pwg :_____ Tblclrnoss: HA SHll I No: llecJ p. Charctl1g Pump '21 Dade Cul. Dlk. 1 Seo Above* 11 l guro: B-78
APPENDIX C SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURES
- APPENDiX C SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURES Table of Contents Procedure Number Title
*IX-FE-101-2 Deviations to Nuclear Projects Operating Change 1 Procedures IX-FE-103-2 Weld Joint Identification Marking on Nuclear Power Plant Piping IX-FE-110-1 "Black Light" Intensity Measurements IX-FE-116-0 Recording Data from Direct Visual, Liquid Change 4 Penetrant, and Magnetic Particle Examinations IX-FE-117-2 Recording Indications from Ligaments, Bolting, ' . Change 1 Piping, and Vessel Weld Examinations IX-FE-119-0 Measuring and Recording Search Unit Data
-~ During Ultrasonic Examinations* of Pressure Vessel Welds X-FE-101-2 Onsite NDE Records Control XIII-AG-101-2 Control of Nuclear Inspection Equipment and Materials XVII.;,.AG-101-1 Data Storage and Retrieval Change 1
- C-i
CHANGE 1 .. SOUTHWEST RESEARCH INSTITUTE IX-FE-101~2 NUCLEAR PROJECTS March 1984 OPERATING PROCEDURE Page l of 6 Title DEVIATIONS TO NUCLEAR PROJECTS OPERATING PROCEDURES EFFECTIVITY ANO APPROVAi. Revision 2 of this procedure became effective on Nov* 2
- 1981 . This procedure consists of the pages and changes listed below.
Page No Change Date Effective 1 1 March 1984 2 through 5 0 November 1981 6 1 March 1984 SA \
~A-p-p-ro-v-al-s--------------------------------------------------------~~\,i\j Written By fit . Date Technical Review Date
-/.~~ ~*
/'l-,.,e LJ.'j.~
8' 'f Manager of Q.A. Date Date SwRI Ferm QA-40S-O
- - 3~'#,
~ffi
SOUTHWEST* RESEARCH INSTITUTE
~~~.
f~tf;._:. ,i} NU<;LEAR PROJECTS OPERATING PROCEDURE IX-FE-101-2 October 1981 Page 2 of 6 DEVIATIONS TO NUCLEAR PROJECTS OPERATING PROCEDURES 1.0 PURPOSE 1.1 The purpose of this.operating procedure is to establish guidelines and controls for deviations to Nuclear Projects Operating Proc.e-dures. 2.0 SCOPE AND APPLICATION 2.1 This procedure applies to Nuclear Projects-operating Procedures~ 2.2 Deviations written in a~cordance with this procedure shall be applicable only to the specified plant and examination area described in the Procedure Deviation, SwRI Form FE-4-3 (sample attached). 2.3 Deviations written in accordance with this procedure do not con-stitute permanent changes.or revisions to the appl'icable pro-cedures. 2.4 This procedure meets the requirements of SwRI Nuclear Quality Assurance Program Manual (NQAPM). 3.0 RESPONSIBILITY 3.1 The Director of the Department of Engineering Services, or his designated alternate within the Quality Assurance Systems and . Engineering Division, shall. be responsible for the initiation of this procedure. 3.2 Qualification of deviations to operating procedures shall be the responsibility of the Director of the Department of Engineering Services, or his designated alternate. 3.3 The Assistant Manager of the Technical Activities Group, Team Supervisor, or other cognizant persons using the procedure shall be responsible for initiating the request for a deviation to the operating procedure. 3.4 The Department Director, or his designated alternate, shall be responsible for approval of operating procedure deviations. 3.5 The Manager of Quality Asaurance, or his designated alternate, shall be responsible for reviewing and approving proposed devia-tions to operating procedures against the requirements of this procedure. *
- SOUTHWEST RESEARCH INSTITUTE l§~, .
L~** :.~.., 1I
- _lo:,,
M NUCLE-AR PROJECTS OPERATING PROCEDURE IX-:-FE-101-2 October 1981 Page 3 of 6 4.0 PROCEDURE 4.1 The Assistant Manager of the Technical Activities Group, Team Supervisor, or other cognizant persons who require a deviation to a Nuclear Projects Operating Procedure shall be responsible for initiating a Procedure Deviation, SwRI Form FE-4-3. Deviations may be required due to changing technology, applicable code changes or interpretations, plant or component design, customer requirements, or special cases. If the procedure deviation is initiated by a telephone call from the field, and -the requestor is not available to sign the request, his name shall be typed in the "Requested By" block.
':'.(
4.2 _The Assistant Director .of the Department of Engineering Services, or his designated alternate, shall assign responsibility for pre-paring the procedure deviation.
- 4.2.1 The Procedure Deviation, SwRI*Form FE-4-3, shall have, but not be limited to, . the following information:
(1) (2) Site Procedure Number (3) Procedure Section and Page (4) Deviation Number (5) Date Requested
)
(6) Examination Area(s) and Specific Outage Affected by Deviation( s) (7) Deviation Required (8) Justification for Deviation(s). 4.2.2 Deviation numbers shall be assigned by the Manager of the Support and Administration Section," or designated alter-nate, and shall be in numerical sequence beginning with "l" for each procedure revision. 4.3 The procedure deviation shall be qualified by either field use, laboratory verification, or review by a qualified Level III individual, under the dir_ection of the Director of the Department of Engineering Services or his designated alternate. SwRI Fnrm QA-3 2*
SOUTHWEST RESEARCH INSTITUTE IX-FE-101-2 October 1981
~~~
~~* ,, ~;)
NUCLEAR PROJECTS OPERATING PROCEDURE I * - ""'- Page 4 of 6 4.4 Upon qualification in accordance*with Paragraph 4.3, and veri-fication that the procedure deviation is in compliance with the applicable code/other requirements, the person conducting the technical review shall sign the deviation. 4.5 The Manager of Quality Assurance, or his designated alternate, shall verify that the deviation is in compliance with this proce-dure and sign the procedure deviation as reviewed and approved and forward it to the Department Director, or his designated alter-nate. 4.6 If approved, the Department Director, or his designated alternate, shall sign the procedure deviation and forward it to the* Support and Administration Section for reproduction, copy distribution, and filing of the original document. 4.7 The final deviation shall carry the signatures as follows: (1) Requested By. Requester, if available to sign. If he is not available, his name shall be typed in the "Requested By" block. (2) Technical Review. A technical review shall be conducted by a person having an adequate understanding of the requirements and intent of the deviation, who does not administratively report to the author, and is a represent-ative of the same group that performed technical review of the affected procedure. (3) Approved By. Manager of Quality Assurance, or his designated alternate.
* (4) Approved By. Department Director, or his designated alternate.
4.a* The requesting team supervisor may use the Procedure Deviation of the Nuclear Projects Operating Procedure upon receipt of the final approval and site approval of the deviation. 4.9 The deviation number shall be recorded in conjunction with the appropriate Nuclear Projects Operating Procedure number on all records requiring the recording of the procedure number. 4.10 A copy of the Procedure Deviation, SwRI Form FE-4-3, shall be attached to the applicable procedure when conducting examinations in accordance with the deviation. SwRI Form QA 3 2*
- IX-FE-101-2 SOUTHWEST RESEARCH INSTITUTE October 1981 Lt~.
- 11. n1"
.~u
-~-
NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 6 5.0 RECORDS 5.1 Operating procedure deviations and any other documents generated in accordance with this procedure controlling the perform~nce of onsite critical services shall be retained for the period spec-ified in the contract wit~ the Client. These records shall be indexed, filed, and maintained in the Data Storage Facility of the Quality Assurance.Systems and Engineering Division. 5.2 A copy of the approved Procedure Deviation, SwRI Forni FE-4-3, shall be forwarded to the Manager of Quality Assurance for the* historical file *
- SwRI Form QA 3 2*
CHANGE 1 IX-FE-101-2
~~ PROCEDURE DEVIATION March 1984 Page 6 of 6 I
I I. L *, ..:_ J~ r . .'ri ..,, SITE: PSI ISi 0 0 I PROCEDURE/REVISION NO. DEVIATION NO. DEVIATION PAGE NO.: DATE REQUESTED: EXAMiNATION PERIOD: OF: SECTIONISI AFFECTED: PROCEDURE PAGEISI: OF:
~ EXAMINATION AREAISI AFFECTED:
Q
=
0
~
u IM
=
Q
~
z
- ! CEV1AT1__pN: It is reQuested that the paragraphls~ shown below in the above procedure/r9Viszon be deviated from as follows luse exact
~ wording proposed, additional sheets may be used if necessary1:
a. IM Q IM
~
Q 0
=
IM z< 0 IM
~
Q JUSTIFICATION: Reason change is necessary and what it is intended to accomplish I use additional sheets if necessaryl:
=
w Q i.n 0 w
- i
=
IM _S_w_R_l_F_O_R_M__ F_E_-4-4------------------------------------~------------------------------------------------__.I
- SOUTHWEST RESEARCH INSTITUTE
. IX-FE-103-2 NUCLEAR PROJECTS OPERATING PROCEDURE October 1981 Pa e 1 of 6 Title ,--*
WELD JOINT IDENTIFICATION MARKING ON NUCLEAR POWER PLANT PIPING EFFECTIVITY ANO APPROVAL Revision 2 of this procedure became effective on Nov* 16, 1981, This procedure consists of the pages and changes listed below. Page No Change Date Effective 1 through 6 November 16, 1981 SA Approvals ~ Date Date
~~ /Uv.~
/~
- Manager of Q.A-.
*~J SwRI Form QA-406-0 r Date
.///
7/~/
SOUTHWEST RESEARCH INSTITUTE
,--NUetEAR PROJECTS OPERATING PROCEDURE IX-FE-103-2 October 1981 Page 2 of 6 WELD JOINT IDENTIFICATION MARKING ON NUCLEAR POWER PLANT PIPING 1.0 PURPOSE This procedure describes the weld joint identification marking of nuclear power plant piping, attachments and components.
2.0 SCOPE AND APPLICATION (1) The method of locating weld joints and marking the respec-tive identification numbers and zero reference points (Lo) adjacent to the welds is described herein. (2) Nuclear power plant piping shall be marked with an electric qr pneumatic engraver, low stress punch, or marking pencil as specified by the customer. 3.0 2.1 Applicable Documents SwRI Nuclear Quality Assurance Program Manual (NQAPM). RESPONSIBILITY (1) The Director of .the Department of Engineering Services within the Quality Assurance Systems and Engineering Division shall be respon-sible for preparation, review, and approval of this procedure. (2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM in effect on the date this procedure is approved. (3) Marking .equipment and methods described in this procedure shall be approved by the customer before use. (4) The examiner.shall be responsible for implementing the requirements of this procedure. SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE IX-FE-103-2 October 1981 -
- ,- NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 6 4.0 PROCEDURE 4.1 General In addition to the* requirements of this procedure, the policies, practices, and rules of the nuclear plant shall be followed in the execution of the marking operation.
4.2 Personnel ( 1) Personnel marking piping and components shall have sufficient instruction and experience in use of the equipment and application of the techniques as specified by the Project Manager. (2) Personnel shall have received appropriate training and indoctrination for proper control of radioactive materials if the marking is to be conducted after-the plant has been in operation *
- 4.3 Equipment (1)
(2) The equipment to be used shall be a commercial electric or pneumatic engraver, low stress punch, or marking pencil. The engraver's tip shall be manufactured of commercial-grade diamond or tungsten carbide material. 4*4 Weld Joint Identification (1) The area to be marked shall be free of weld spatter, rust, rough surfaces, or any other condition which would prevent clear marking. (2) Each weld joint shall be marked on the main run pipe with the appropriate identification number. (3) The L0 reference mark (-0-) for each weld shall be located in accordance with Paragraph 4.6 of this procedure. (4) The depth of weld joint identification marking and zero reference (L 0 ) marking shall not exceed the limits established by the customer *
- SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE rNUet.:EAR PROJECTS OPERATING PROCEDURE IX-FE-103-2 October 1981 Page 4 of 6 (5) If weld joint inaccessibility prevents use of the equipment or methods described iD. this procedure, other zero reference or weld joint identification number locations may be used as considered necessary and acceptable by the Team Supervisor or Inspection Engineer. Under these circumstances, the provi-sions of Paragraph 4.6 will not apply and a description of the zero reference used shall be entered on the examination record for that weld joint. 4.5 Weld Joint Identification Number.Placement (W.J.I. No.) (Figure 1) To the extent practicable, weld joint identification numbers shall be located adjacent to the zero reference point (L 0 ), but outside the examination area. 4.6 Determination of Zero Reference Location on Welds The following rules shall be observed in determining the zero reference location (L 0 ) on circumferential, longi~~dinal and branch connection piping welds and welded piping lugs and piping supports. If more than one rule is applicable, the lowest numbered rule shall be applied. The term "horizontal component" relates to any pipe positioned at other than 90° from the horizontal *. (1) Rule 1. For any pipe having a horizontal component at the* weld, use the top centerline of the pipe. (2) Rule 2. If a.pipe is vertical at the weld (no horizontal component) and the weld i~ either an dbow-to-Z or a Z-to-elbow, where Z is any piping component other than an elbow, use the centerline of the outside radius of the elbow. (3) Rule 3. If a pipe is vertical at the weld (no horizontal componen~) and the weld is a pipe-to-pipe, elbow-to-elbow, Z-to-pipe, or pipe-to-Z, where Z is any piping component other than an elbow, use an extension of the centerline of the outside radius of the elbow above the weld. (4) Rule 4. If in Rule 3 there is no elbow above the weld, use an extension of the centerline of the outside radius of the elbow below the weld. SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE lt~~'
~(rr~*.\)
NIJCLC-AR PROJECTS OPERATING PROCEDURE IX-FE-103-2 October 1981 Page 5 of 6 (5) Rule 5. If Rule 3 or Rule 4 cannot be used because no elbows are visible, choose the most convenient location. When referring to Rule 5, describe the method for establishing L0 on the examination record. (6) Rule 6. For branch connection piping welds (sweepolet, weldolet, etc.) and for welded lugs. and pipe supports, use the upstream intersection of the weld and the centerline of the branch connection, lug, or support, as appli~able. (7) Rule 7. For a longitudinal weld intersecting a cir-cumferential weld, use the junction (near or inside edge of the circumferential weld) of the longitudinal with the circumferential.
- 5.0 ACCEPTANCE STANDARDS The weld will be considered suitably marked after the personnel per-
- forming the marking has verified that:
(1) (2) The zero reference mark (-0-) is located in accordance with Paragraph 4.6 and 4.4(5). The weld identification number is the same as shown on the proper isometric drawing contained in the Examination Plan. (3) The zero reference mark (-0-) and the weld joint identification number are legible and are within the depth limits established by the customer *
- SwRI Form OA*J 2*
LONGITUDINAL SEAM WELD i BRANCH CONNECTION CIRCUJ.IPERENflAL \YELD FIGURE 1
SOUTHWEST RESEARCH INSTITUTE IX-FE-110-1 NUCLEAR PROJECTS August 1981
- OPERATING PROCEDURE Page 1 of 5 TI tie "BLACK LIGHT" INTENSITY MEASUREMENTS EFFECTIVITY ANO APPROVAL Revision 1 of this procedure became effective on 8/18/81 . This procedure consists of the pages and changes listed below.
Page No
- Change Date Effective 1 through 5 0 August 18, 1981 SA I // )
/"-'
Approvals Written B~~~ Data Data
./ *~ //O,-'..
0/11/st '?3' 1
- - Manager of
~
25::..rcc..-~ SwRI Form QA-40S-0
. ._ r:-- Data
'h..11 Date
SOUTHWEST RESEARCH INSTITUTE NUCLEAB PROJECTS OPERATING PROCEDURE IX-FE-110-1 August 1981 Page 2 of 5 "BLACK LIGHT" INTENSITY MEASUREMENTS 1.0 PURPOSE This procedure provides the information and detailed steps necessary to ensure the proper measurement of the "black light". intensity for exami-nations ~tilizing a "black light~" 2.0 SCOPE This procedure shall be *for the measurement of the "black light" intensity utilizing a Blak-Ray J-221 Long Wave Ultraviolet Intensity Meter. 2.1 Applicable Documents The following documents form a part of this procedure: 3.0 (1) (2) RESPONSIBILITY SwRI Nuclear Quality Assurance Program Manual' (NQAPM).
.The applicable SwRI Nuclear Projects Operating Procedure for examinations requiring "black light."
(1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible for the preparation; review, approval, and control of this procedure. (2) The Project Manager shall be responsible for the implementation of . this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan *
.(3) The examiner shall be responsible for implementing the requirements of this procedure.
(4) The Manager of the Support and Administration Section, Quality Assurance Systems and Engineering Division, shall be responsible for storage of records generated in accordance with this procedure
- SwRI Form QA-3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-110-1 August 1981 Page 3 of 5 4.0 PROCEDURE 4.1. Personnel Personnel measuring "black.light" intensity shall be certified in accordance with the personnel certification requirements of the SwRI Nuclear Projects Operating Procedure to be used with the exami-nation requiring the "black light."
4.2 Equipment The following equipment shall be utilized for measurements: (1) Blak-Ray J-221 Long Wave Ultraviolet Intensity Meter with sensor cell. (2) J-223 Extension cord (4 foot). (3) 50107 Contrast Filter
- 4.3 Measurement The "black light" intensity at the surface under examination shall be determined:
( 1) At least every 8 hour.s. (2) Whenever the work location is changed. NOTES The meter face shall be vertical for all readings and meter zero verification. The meter.zero shall be checked with the sensor cell 1.mplugged. If the reading is not "O," the screw below the scale shall be used to adjust the scale to zero *
.The examiner* shall ensure that the sensor cell and filter faces are clean before measurements are taken, since any film of dust, oil or other sedi-ment may affect the reading.
The Blak-Ray J-221 Long Wave Ultraviolet Intensity Meter shall be utilized as follows: (3) Plug the extension cord into the top of the meter housing with the red and black plugs aligned with their corresponding holes for proper polarity. SwRI Form QA-3-2
SOUTHWEST RESEARCH INSTITUTE NUCLE;\R PROJECTS OPERATING PROCEDURE IX-FE-110-1 August 1981 Page 4 of 5 (4) Repeat step (3) plugging the extension cord into the sensor cell. ( 5) Select the "B" scale by moving the switch on top of the meter housing to "B. " (6) Darken the area and place the sensor cell directly on the sur-face to be examined. (7) After the "black light" has warmed up for a minimum of five minutes, place the "black light" 16 inches (nominal measure-ment) from the sensor cell. (8) Observe the "B" scale. If the needle is pegged, the "black light" shall be moved back, up to a maximum of 22 inches (nominal measurement), until a reading can be taken. NOTE The "B" scale range is from 10 to 60. To obtain a reading in microwatts per square centimeter, multiply the reading by 100. For example, if the reading is 20, multiply 20 by 100 to obtain 2,000 microwatts per square centimeter. (9) Another reading shall be taken with the 50107 contrast filter over the sensor cell and the "black light" located the same distance as the first reading. (10) Subtract the second reading from the first. The difference shall be a minimum of 800 microwatts per square centimeter. (11) If the second reading on the "B" scale remains at 10 or below, the switch on top of the meter housing shall be moved to "A"; a reading shall be obtained from the "A" scale with the filter over the sensor cell. The "black light" remains at the same distance as during the first reading. NOTE The "A" scale range is from 0 to 12. To obtain a reading in microwatts per square centimeter, multiply the reading by 100. For example, if the reading is 8, multiply 8 by 100 to obtain 800
~icrowatts per square centimeter.
SwRI Form QA-3*2
- ~
SOUTHWEST RESEARCH INSTITUTE NUCL;_AR PROJECTS OPERATING PROCEDURE IX-FE-110-1 August 1981 Page 5 of 5 (12) Repeat step (10). The distance, during an examination, from the "black light" to the examination surface shall not exceed the distance at which the "black light" intensity was measured. 5.0 RECORDS The difference of the two.readings and the distance from the "black light" to the sensor cell during the reading shall be recorded on the applicable SwRI Examination Record. -~
- SwRI Form OA-3-2
~.
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-116-0 July 1980 Page 1 of 8 RECORDING DATA FROM DIRECT VISUAL, LIQUID PENETRANT, AND MAGNETIC PARTICLE EXAMINATIONS PURPOSE This procedure provides the technical information and detailed steps
- required for recording data from direct visual, liquid penetrant, and magnetic particle examinations. * -
SCOPE AND APPLICATION Data from direct visual, liquid penetrant, and magnetic particle exam-inations of components, welds, heat-affec.ted zones, and adjacent base material be recorded in accordance with this procedure.
" Applicable Documents
- The following documents form (1)
(2) a part of this procedure as SwRI Nuclear Quality Assurance Program Manual (NQAPM). SwRI Nuclear Projects Operating Procedures for the examinations being conducted. RESPONSIBILITY (1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible for the preparation, review~ approval, and control of this procedure. (2) The Manager of the Nuclear Field Services Section, Department of Engineering Services, shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicabl~ SwRI Project Plan. Cll c l!!
~
- SwRI Form QA*3*1
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS
- OPERATING PROCEDURE IX-FE-116-0 July 1980 Page 2 of 8 (3) The examiner shall. be responsible for implementing the requirements of this procedure.
(4) The Manager of Support Services, Quality Assurance Systems and Engineering Division, shall be responsible for the storage of records generated in accordance with this procedure. PROCEDURE REQUIREMENTS (1) Personnel utilizing this procedure shall be certified in accordance with Nuclear Quality Assurance Procedure NQAP 11-1, "Special Pro-cess Control," and the Winter 1977 Addenda to Section XI of the ASME Boiler and Pressure Vessel Code, as applicable. (2) Examinations shall be conducted as required by the applicable SwRI Nuclear Project~ Operating Procedures. S.O PROCEDURE s.1 Weld Length Weld length, when required, shall be measured with a steel mea-suring tape and the distance recorded in inches and common fractions to the nearest 1/16 inch. Circumferential and Nozzle-to-Shell Welds Weld length shall be measured along the weld centerline. s.1.2 Longitudinal Welds Weld length shall be measured along the weld centerline. The weld length shall be 12 inches when only 12 inches of the longitudinal weld is required to be examined. Branch Connection Welds, Lugs, Supports and Other Similarly Welded Attachments with Fillet Type Weld Surfaces
~
Weld length shall be measured on the component surface at the junction of the weld fusion line and the component surface, i.e., vessel or J c
.~ .
.. .; pipe surface.
~ >
SwRI Form QA*3-l
CHAJ.'l'GE 4 SOUTHWEST RESEARCH INSTITUTE IX-FE-116-0 NUCLEAR PROJECTS September 1983 - OPERATING PROCEDURE Page la of 8 TI tie
- RECORDING DATA FROM DIRECT VISUAL, LIQUID PENETRANT, AND MAGNETIC PARTICLE EXAMINATIONS EJ=FECTIVITY ANO APPROVAL Revision 0. Ch . 4of this procedure became effective on 28 SEP 83 . This procedure consists of the pages and changes listed below.
Page No Change Date Effective la 3 June 1983 1 0 August 1980 2 2 December 1981 3-5 0 August 1980 6 4 September 1983 7 0 August 1980 8 2 December 1981 Aoprovals Date Technical Review Date
~.<~
15~, ~'1:,~ /ef?J' Date Date f/z~3 ~P.7p SwAI Form QA-lOB-0
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-116-0 July 1980 Page 3 of 8 5.2 L" Measurements "L" measurements shall be recorded in inches and common frac-tions, to the nearest 1/16 inch.
"L" measurements for components with a flow direction, other than branch connection and nozzle-to-shell, shall be made clockwise looking in the direction of the flow. Branch connections and nozzle-to-shell measurements shall be made clockwise; as viewed at angle perpendicular to the component to
- which the branch connection or nozzle is welded. Measurements for compo-nts without a flow direction shall be made clockwise as viewed from above the vertical component or clockwise as viewed from an identified end of a horizon-tal component. The end of the horizontal component referenced to determine clockwise shali be recorded in the "REMARKS" section of the applicable SwRI 1---;..:......
- Examination Record.
"L" measurements for longitudinal welds shall be made along the centerline from Lo *
"L" measurements shall be made clockwise* as viewed from the top side of the stud, bolt, nut or washer; or as viewed from an identified end of the component. "L" measurements far other nan-welded components, e.g.,
cladding patches, shall be made from an Lo as described on the appropriate SwRI Examination Record. s.2.1 Circumferential, Nozzle-to-Shell and Longitudinal Welds Datum ~ Lo to geometric center of the indication. Measurement along the weld centerline using one of the following methods: (1) Measurements shall be made directly from Lo using a steel measuring tape. (2) Marks shall be made and labeled every 5 inches as measured from Lo using a steel measuring tape. Measurements shall be made from these marks using a 6-inch steel rule or a steel measuring tape. (3) The steel measuring tape shall be affixed to the weld centerline with zero at Lo. Measurements shall then be made directly *
- SwRI Form QA-3-1
~
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-116-0 July 1980 Page 4 of 8 Branch Connection Welds Datum~ Lo to geometric center of the indication. Measurements* along the weld fusion line on the component surface, i *. e., pipe surface using one of the following methods: (1) Measurements.shall be made directly from Lo using a steel measuring tape. (2) Marks shall be made and labeled every 5 inches as measured from Lo* using a steel measuring tape. *Measurements shall be made from these marks using a 6-inch steel rule or steel
. measuring tape *.
Lugs, Supports, and Other Similarly Welded Attachment With Fillet Type Weld Surfaces Datum ~ Lo to geometric center of the indication. Measurements shall be made along the fusion line on the component surface, i.e., pipe or surface using one of the following methods: (1) (2) Measurements shall be made directly from Lo using a steel measuring tape. Marks shall be made and labeled every 5 inches as measured
- t~ from Lo using a steel measuring tape. Measurements *shall 0 ~
~
be made from these marks using a 6-inch steel rule or steel measuring tape.
..a:. *;;: Studs, Bolts, Nuts, Washers and Other Non-Welded Components ii *c:.t:." Datum= Lo.to geometric center of the indication. Measurements I-be made directly from Lo with a steel measuring tape or 6-inch steel . .3 "W" Measurements d "W" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch.
SwRI Form QA*3*1
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-116-0 July 1980 Page 5 of 8 5~3.1 Circumferential, Nozzle-to-Shell and Longitudinal Welds Datum = weld centerline to the geometric center of the indi-
"W" measurements shall be made perpendicular to the weld centerline a 6-inch steel rule or steel measuring tape.
Branch Connection Welds
- Datum = junction weld fusion line and the component surface to
'-'-""'~"e geometric center of the indication. The component surface used to deter-mine Wo shall be identified in the "REMARKS" section of the applicable SwRI Record. "W measurements shall be made perpendicular to the weld using a 6-inch steel rule or steel measuring tape.
Supports and Other Similarly Welded Attachments With Fillet Type Weld Surf aces Datum = junction weld fusion line and the component surface to
- the geometric center of the indication. The component surface used to deter-mine Wo shall be identified on the applicable SwRI Examination Record. "W" measurements shall be made perpendicular to the weld fusion line using a 6-inch steel rule or steel measuring tape.
Studs, Bolts, Nuts, Washers, and Other Non-Welded Components Datum = Wo to the geometric center of the indication. "W" measurements for studs or bolts with heater holes, nuts, and washers shall be made with a steel measuring tape or 6-inch steel rule from the top edge of the bore or heater hole and continue down the component. "W" measurements for studs or bolts without heater holes shall be made with a steel measuring tape or 6-inch steel rule from the top center of the component. Measurements for other types of non-welded components, e.g., cladding patches, shall be made from Wo determined by the examiner and described on the appropriate SwRI Examination Record. 5.4 Indication Types Indications shall be recorded on the applicable SwRI Examination Record as rounded, linear, or as a group of rounded indications. Further information about the indication shall be recorded under the "REMARKS" section Jl *{ of the*applicable SwRI Examination Record. r: .. S! * '
~
- SwRI Form QA-3*1
CHANGE 4 SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-11.6-0 September 1983 Page 6 of 8 5.4.1 Rounded Indications A rounded indication shall be an indication which is less than three times as long as it is wide. 5.4.2 Linear Indications A linear indication shall be an indication which is equal to or greater than three times as long as it is wide. s.4.3 Group of Rounded Indications The size of the area and the number of rounded indications required to be recorded, when applicable, shall be as stipulated in the applicable SwRI Nuclear Projects Operating Procedure. 5.5 Indication Size The size of an indication shall be measured to the nearest 1/32 inch with a 6 inch steel scale or steel measuring tape. s.5.1 Rounded Indications Round indications or indications closer to being round than ellip-tical shall be measured at the maximum diameter. Elliptical indications shall be measured across the maximum length and maximum width. s.s.2 Linear Indications Linear indications shall be measured along the length of the indication. 5.6 Abbreviations Appropriate abbreviations (listed below) which describe the indi-cation location with respect to Wo shall be entered on the applicable SwRI Examination Record with the measurements. SwRI Form QA 3-2
- ~
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-116-0 July 1980 Page 7 of 8 (1) Up - U (2) Down - D (3) Clockwise - CW (4) Counterclockwise - CCW (5) Vessel side - V (6) Lug or support side - L or S (7) Pipe Side - P (8) Other symbols with descriptions entered in the "Remarks" section may be used as approved by the Team Leader. RECORDS
- Required records shall be specified in the applicable SwRI Nuclear Pro-Operating Procedure.
Permanent documents generated in accordance with this procedure shall be stored and retained as a portion of the examination report. The examination F=:::::;:==!report shall be stored by the Manager of Support Services, Quality Assurance
.1 I
Systems and Engineering Division, in the Data Storage Facility for the period specified by the contractual agreement with the customer *
- SwRI Form QA*3*1
I SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-116-0 July 1980 Page 8 of 8 EFFECTIVITY !--...+;;~Revision 0 of this Operating Procedure beca~e effective in July 1980. Revision 0 consists of the pages, changes and revisions listed below. Change Revision Effective Date 0 0 July 1980 SwRI Form QA*l*l
- - SOUTHWEST RESEARCH INSTITUTE CHANGE 1 IX-FE-117-2 NUCLEAR PROJECTS November 1982 OPERATING PROCEDURE Page 1 of 17 Titfe RECORDING INDICATIONS FROM LIGAMENTS, BOLTING, PIPING AND VESSEL WELD EXAMINATIONS ErFECTIVl'N ANO APPROVAi.
Revision 2 of this procedure became effective on 12 I 9 I 8 2 . This procedure CQnsim of the pages and changes listed below. Page No Olange Cate Effective 1 to 2 1 November 1982 3 to 17 0 September 1982 SA Ai:ii:irovals Cata Technical Raview 11;2q/g2 ,-<L_A: -/~
- Manager of a.A.
c
/
CHANGE 1 SOUTHWEST RESEARCH INSTITUTE IX-FE-117-2 November 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 17 RECORDING INDICATIONS FROM LIGAMENTS, BOLTING, PIPING AND VESSEL WELD EXAMINATIONS
- 1. PURPOSE This procedure specifies the methods and techniques for measuring and recording.search unit location and maximum signal amplitude data during ultrasonic examination of ligaments, bolting, piping welds, CRD housing welds, vessel welds less than 2-1/2-inches when the 1974 ASME Code applies, and vessel welds 2-inches and less when the 1977 ASME Code applies.
- 2. SCOPE AND APPLICATION Recording search unit location and maximum signal amplitude data for straight- and angle-beam ultrasonic examinations of ligaments, bolting, welds, heat-affected zones, and adjacent base material using manual, contact, and pulse-~cho techniques shall be in accordan~e with this procedure.
2.1 Applicable Documents (1) Southwest Research Institute Nuclear Quality Assurance Program Manual (NQAPM) (2) The SwRI Nuclear Projects Operating Procedures for the ultrasonic examinations being conducted
- 3. RESPONSIBILITY (1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible for the preparation, review, approval, and control of this procedure.
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan. SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE IX-FE-117-2 September 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 17 (3) The examiner shall be responsible for implementing the requirements of this procedure. (4) The Mana~er of the Support and Administration Section, Quality Assurance Systems and Engineering Division, shall be responsible for storage of records generated in accordance with this procedure. 4* PROCEDURE REQUIREMENTS (1) Personnel utilizing.this procedure shall be certified in
. accordance with SwRI NQAP*11-1, Special Process Control.
(2) Examinations shall be conducted as required by the applicable SwRI Nuclear Projects Operating Procedures. 5* PROCEDURE Weld length, nontransverse "L" and transverse W measurements for circumferential welds shall start at Lo. Measurements.for components with a flow direction shall be made clockwise, looking in the direction of flow.* Measurements for components without a flow direction shall be made clockwise as viewed from above for a vertical component or clockwise as viewed from a~ identified end of a horizontal component. The end of a horizontal component referenced to determine clockwise shall be recorded in the REMARKS section_of the applicable SwRI Examination Record. Weld length, nontransverse '.'L" and transverse W" measurements, for longitudinal welds shall be made along the weld centerline from Lo. Weld length, nontransverse "L" and transverse W" measurements, for fillet-type attachment and branch connection welds shall start at Lo and shall be made clockwise. Clockwise shall be determined by viewing the weld perpendicular to the component to which the branch connection or fillet-type attachment is welded.
"L" measurements for angle beam examination conducted from the heater hole and straight beam examination of bolting components shall be made clockwise as viewed from above the component or clockwise as viewed from an identified end of the component. W" measurements for straight-beam and angle-beam heater hole examina-tions shall be made* from the edge of the bore or heater hole of an identified end or the center of an identified end to the incident
_point of the search unit *
- !;iwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-117-2 September 1982 Page 4 of 17 "L" measurements for angle beam examination of nuts from the outer surface shall be made from the outer edge of an identified end. "W" measurements for angle beam examination of nuts shall be made clockwise as viewed from an identified end.
-NOTE The examiner shall refer to Appendix A for recording requirements pertaining to specific codes called out by the applicable SwRI Nuclear Projects Operating Procedure.
5.1 Weld Length Weld lengths, if applicable, shall be measured with a steel mea-suring tape recording distances in inches and comm.on fractions to the nearest 1/16 inch. 5.1.1 Circumferential Welds Circumferential weld lengths shall be measured along the centerline of the weld bead from Lo. 5.1.2 Longitudinal Welds (1) Longitudinal weld lengths shall be measured along the centerline of the weld bead from Lo. (2) When only a portion of a longitud~nal weld is required to be examined; e.g. in piping, the weld length shall be the portion of the weld required to be examined. * - 5.1.3 Branch Connection Welds Branch connection weld lengths shall_ be measured on the examination surface at the junction of the weld and the examination surface. 5.1.4 Lugs, Supports, and Other Similar Welded Attachments with Fillet-Type Weld Surfaces Fillet-type weld lengths shall be measured on the exami-nation surface at the junction of the weld and examina-tion surface. SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE JX-FE-117-2 September 1982 Page 5 of 17 5.2 Amplitude Movements (1) Signal amplitude shall be recorded as a percent of dis-
- tance amplitude -correction (DAC) at the primary reference level. The percent of DAC shall be determined from Sketch 1.
(2) Maximum signal amplitude shall be attained by search unit manipulation. (3) Amplitudes of signals shall be measured in decibels (dB) above or below DAC by adjusting the gain control until the peak indication amplitude coincides with the DAC line. 5.3 **L" Measurements, Nontransverse Scans for Angle Beam
.... - (1) "L" measurements shall be recorded. in inches and common fractions, to the nearest 1/16 inch *
- (2) 5.3.1 Measurements shall be made as required by Ap.p.endix A.
Circumferential and Longitudinal Welds Datum .. Lo to axial center of the search unit. Mea-surement will be made along the weld centerline using one of the following methods: (1) Measurements shall be made directly from Lo using a steel measuring tape *. (2) Marks shall be made and labeled every 5 inches from Lo using a steel measuring tape. Measure-ments shall be made from these marks using a 6-inch steel rule or a steel measuring tape. (3) The steel measuring tape shall be affixed to the weld centerline with zero at Lo. Measurements shall then be made directly. 5.3.2 Branch Connection Welds _Datum .. Lo*to axial center of search unit. Measurement shall be made on the examination surf ace at the weld and examination surf ace junction using one of the following methods:
- SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE. NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-117-2 September 1982 Page 6 of 17 * (1) Measurement shall be made directly from Lo using a steel measuring tape. (2) Marks shall be made and labeled every 5 inches from Lo using a steel measuring tape. Measurements shall be made from these marks using* a 6-inch steel rule or a steel measuring tape. 5.3.3 Lugs, Supports, and Other Similar Welded Attachments with Fillet-Type Weld Surfaces Datum = Lo to axial center of search unit. Measurement shall be made on the examination surface at the weld and examination surface junction using one of the following methods: (1) Measurement shall be made directly from Lo using a steel measuring tape. (2) Marks shall be made and labeled every 5 inches from Lo using a steel measuring tape. Measurements shall be made from these marks using a 6-inch steel rule or a steel measuring tape. 5.4 "L" Measurements, Transverse Scans for Angle Beam (1) "L" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch. (2) Measurements shall be made as required by Appendix A. 5.4.1 Circumferential and Longitudinal Welds Datum = weld centerline to axial center of search unit.
"L" measurements shall be made perpendicular to the weld centerline using a 6-inch steel rule or steel measuring tape.
5.4.2 Branch Connection Welds Datum ~ junction of the examination surface and the weld to the axial center of the search unit. "L" measurements shall be made perpendicula~. to the weld fusion line using a 6-inch steel rule or steel measuring tape. SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE
~ ~* N-UCLEAR PROJECTS OPERATING PROCEDURE IX-FE"."'117-2 September 1982 Page 7 of 17 5.4.3 Supports and Other Similarly Wefded Attachments with Fillet-Type Weld Surfaces Datum m junction of the examination surface and weld to the axial center of the search unit. "L" measurements shall be made perpendicular to the weld fusion iine using a 6-inch steel rule or steel measuring tape.
5.5 "L" Measurements for Straight Beam Datum Lo to the axial center of the search unit. "L" measure-
- 11 ments shall be recorded in inches and common fractions to the nearest 1/16 inch.
5.5.1 Straight-Beam DAC (1) "L" Measurements shall be made as required by Appendix A*
- 5.5.2 (2) Measurements shall be made as described in 5.3.1, 5.3.2, and 5.3.3, as applicable.
Straight-Beam Lamination (1) "L" measurements shall be made within 1/4 inch of each edge of the laminar-type reflector as speci-fied by the applicable SwRI Nuclear Projects Oper-ating Procedure along with measurements taken from successive scans across the reflector in increments no greater than 1 in~h. A laminar reflector may require measurements for two areas as required by the applicable SwRI Nuclear Projects Operating Procedure. (2) Measurements shall be made as described in 5.3.1, 5.3.2, and 5.3.3, as applicable. 5.6 "L" Measurements for Bolting (1) "L" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch. (2) Measurements shall be made as required by Appendix A*
- SwRI Form QA 3*2
SOUTHWEST R-ESEARCH INSTITUTE
,-- NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-117-2 September 1982 Page 8 of 17 5.6.1 Angle-Beam from Inside Bolting Heater Holes and Straight Beam for Bolting Datum a clockwise around the outer surf ace from Lo to the axial center of search unit. "L" measurements shall be made using a steel measuring tape or 6-inch steel rule.
5.6.2 Angle-Beam from the Outer Surf ace of Nuts Datum ~ outer edge on an identified end to the axial center of the search unit. "L" measurements shall be made using a 6-inch steel rule or steel measuring tape. 5.7 "L" Measurements for Ligaments (1) "L" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch. (2) Measurements shall be made as required by Appendix A. Datum = 0° of the vessel clockwise to the axial center of the search unit. 5.8 "W" Measurements, Nontransverse Indications for Angle Beam (1) W" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch. (2) Measurements shall be made as required by Appendix A. 5.8.1 Circumferential and Longitudinal Welds natum = weld centerline to the incident point of the search unit. "W" measurements shall be made perpen-dicular to the weld centerline using a 6-inch steel rule or steel measuring tape. 5.8.2 Branch Connection Welds Datum = junction of examination surf ace and weld to the incident point of the search unit. "W" measurements shall be made perpendicular to the weld fusion line using a 6-inch steel rule or steel measuring tape. SwRI Fonn CA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-117-2 September 1982 Page 9 of l7 5.8.3 Supports and Other Similarly Welded Attachments with Fillet Type Weld Surf aces Datum = junction of examination surface and weld *to the incident point of the search unit. W" measurements shall be made perpendicular to the weld fusion line using a 6-inch steel rule or steel measuring tape.
5.* 9 "W" Measurements, Transverse Indications, for* Angle Beam (1) W" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch. (2) Measurements shall be made as required by Appendix A. 5.9.1 Circumferential and Longitudinal Welds Datum ~ Lo to the incident point of the search unit. Measurements shall be made along the weld centerline using one of the following methods: (1) Measurements shall be made directly from Lo using a steel measuring tape. (2) The steel measuring tape shall be affixed to the weld centerline with zero at Lo. Measurements shall then be made directly. (3) Marks shall _be made and labeled every 5 inches from Lo using a steel measuring tape. Measurements shall be made from these marks using a 6~inch steel rule or steel measuring tape. 5.9.2 Branch Connection Welds Datum ~ Lo to the incident point of the search unit. Measurements shall be made on the examination surface at the junction of the examination surf ace and weld using one of the following methods: (1) Measurement shall be made directly from Lo using a steel measuring tape. (2) Marks shall be made and labeled every 5 inches from Lo using a steel measuring tape
- Measurements shall be made from these marks using a 6-inch steel rule or a steel measuring ~ape.
SwAI Form QA 3*2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-117-2 September 1982 Page 10 of 1.7 5.9.3 Supports and Other Similarly Welded Attachments with Fillet-Type Weld Surfaces Datum
- Lo to the incident point of the search unit.
Measurements shall be made on the examination surface at the junction of the examination surface using one of the following methods: (1) Measurement shall I be made directly from Lo using a steel measuring tape. (2) Marks shall be made and labeled every 5 inches from Lo using a steel measuring tape. Measurements shall be made from these marks using a 6-inch steel rule or a steel measuring tape. 5.10 "W" Measurements for Straight Beam Datum= W0 to the.axial center of the search unit. "W" measure~ ments shall be recorded in inches and common fractions to the nearest 1/16 inch. 5.10.1 . Straight-Beam DAC (1) Measurements shall be made with a 6-inch steel rule or steel measuring* tape. (2) Measurements shall be made as required by Appendix A. 5.10.2 Straight Beam Lamination
. (1) Measurements shall be made with a 6-inch steel rule or steel measuring tape.
(2) "W" measurements shall be made to the edges ofthe laminar type reflector as specified by the appli-cable SwRI Nuclear Projects Operating Procedure. A laminar reflector may require measurements for two areas as specified in the applicable SwRI Nuclear Projects Operating Procedure. 5.11 "W" Measurements for Bolting (1) '"W" measurements shall be recorded in inches and common SwAI Form CA 3*2 (2) fractions to the nearest 1/16 inch. Measurements shall be made as required by Appendix A.
SOUTHWEST RESEARCH INSTITUTE IX-FE-117-2
~ ~NU~LEAR PROJECTS. OPERATING PROCEDURE September 1982 Page 11 of 17 5.11.l Angle-Beam from Inside Bolting Heater Holes Datum
- edge of the heater hole or bore on an identified end to the incident point of the search unit *
. 5.11.2 Angle-Beam from the Outer Surface of Bolting Datum :::1 clockwise around the outer surface from W0 to the incident point of the search unit.
5.11.3 Straight-Beam for Bolting Datum :::1 center of an identified end or edge of the heater hole or bore to the ~xial center of the search unit. 5.12. W" Measurements for Ligaments (1) "W" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch.
- 5.13 (2) . Measurements shall be made as required by Appendix A.
Datum :::1 edge of seal surf ace and inside surf ace of the vessel to the axial center of the search unit.
- Metal Path Measurements 5.13.1 Angle Beam (1) Metal path measurements shall be recorded in inches and decimal fractions.
(2) Metal path measurements shall be made.at the max-imum amplitude point and at each "L" location where "W" measurements are made. 5.13.2 Straight Beam 5.13.2.1 Straight-Beam DAC (1) Metal path measurements shall be recorded in inches and decimal fractions. (2) Metal path m~asurements shall be made at the maximum amplitu~e point and at each "L" location where "W" measurements are made. SwRI Form QA 3*2
SOUTHWEST RESEARCH INSTITUTE IX-FE-117-2 . September 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 12 of 17 5.13.2.2 Straight-Beam Lamination (l) Metal path measurements shall be recorded in inches and decimal fractions. (2) Each point requiring "L" measurements shall require metal path measurements. These shall be made at the points where the amplitude of the intermediate indication equals 50% of the initial back reflection and is accompanied by a 50% loss of back reflection. Measurements shall also be made at any area of total loss of back reflfi!ction as specified in the procedure. 5.14 Crown Width and Height for Fillet Welds 5.15 The crown height and width for fillet welds shall be measured as shown in Sketch 2. Examination Limitations Scanning liuiitations shall be recorded as required by 5.15.1 and 5.15.2. "W measurements shall be made to the search unit exit point and "L" measurements shall be made to the axial center of the search unit. 5.15.1 Straight Beam Limitations encountered during performance of the straight-beam lamination examination shall be recorded in accordance with the following: (1) When the lamination examination can be performed from both sides of the weld, the limitations should be recorded on che lamination examination record as "none." (2) When a weld cannot be examined from one side due to configuration, the limitations should be recorded as "no examination on the (up, down, CW, CCW, etc.) side due to configuration." SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE
,-- NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-117-2 September 1982 Page 13 of 17 (3) When a partial examination is performed from one side or the other of a weld, the limitations for the lamination examination record should ref er to the angle beam examination record. The reference to the angle beam examination may be recorded as "same as angle beam" or "see angle beam limitations."
Limitations shall be recorded for straight-beam DAC calibrations. The maximum limitation in the W" direction shall be recorded. The minimum point and the maximum point of the limitation shall be recorded in the "!." direction. 5.15.2 Angle Beam Limitations shall be recorded for angle-beam examina-tions. For examinations which utilize two angles the limitations of the search unit with the larger limita-tions shall be recorded. The maximum lilnitation in the "W" direction shall be recorded. The minimum point and the maximum point of the limitation in the "L" direc-tion shall be recorded. 5.16 Abbreviations Appropriate abbreviations (listed below) which describe the search unit location with respect.to the weld centerline or edge shall be entered on the applicable SwRI Examination Record with the measurements. (1) Up - U (2) Down - D (3) Clockwise_- CW (4) Counterclockwise - CCW (5) Vessel side - V (6) Lug or support side - L or S (7) Pipe side - P (8) Other symbols with descriptions entered in the REMARKS section may be used as approved by the Team Supervisor. SwRI Ferm QA 3*2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE IX-FE-117-2 September 1982 Page 14 of 17
- 6. RECORDS Required records shall be specified in the applicable SwRI Nuclear Projects Operating Procedure.
Documents generated in accordance with this procedure shall be stored and retained as a portion of the examination report. The examination report shall be stored by the Manager of the Support and . Administration Section, Quality Assurance Systems and Engineering Division, in the Data Storage Facility for the period specified by the contractual agreement with the customer. SwAI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE IX-FE-117-2 September 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 15 of 17 APPENDIX A 1974 CODE RECORDING REQUIREMENTS Wmax 50% Wz Required "L" Positions L1 50% 1max X* 1z 50%
- *Metal path also required 1977 CODE RECORDING REQUIREMENTS Wmax . 100% Wz Required "L" Positions 11 50%
11 100% Lmax X* X* X* 12 100% 12 50%
- *Metal path also required.
SwRI Form QA 3*2
Percent DAC of an amplitude below DAC~ which must be increased in amplitude by the .dB number change to equal DAC, is read in the column on the left. For example, an indication is increased in amplitude by 13 d:s to equal the DAC curve; therefore, the indication is 22 percent of DAC. Percent DAC of an amplitude above DAC, which must be decreased in amplitude by the d:s number change to equal DAC, is read in the column on the right. For example, an indication is decreased in amplitude by 13 d:s to equal the DAC curve; therefore, the indication is 447 percent of DAC *. SKETCH 1
IX-FE-117-2
- September 1982 Page 17 of 17*
CROWN HEIGHT FILLET WELD ( ) CROWN WIDTH VESSEL SY.ETCH 2
SOUTHWEST RESEARC.H INSTITUTE IX-FE-119-0 TI tie NUCLEAR PROJECTS OPERATING PROCEDURE Measuring and Recording Search Unit Data During Ultrasonic Examinations February 1981 Page l of 16 of Pressure Vessel Welds EFFECTIVITY AND APPROVAL Revision 0 of this procedure became effective on 2 /17/ 81 . This procedure consists of the pages and changes listed below. Page No Oiange Date Effective 1 through 16 0 Z/17/Si SA Approvals Written Bv. {/ ~ Date Technical* Review D_:t~ o// #/(7
¥?17 ;..,._/~*
- ~~ ~/vte;,-h?(
Manager of O.A. Date t/JL Cognizant Director
~/11/,) /Jtii~ 1ft;,,;J. rf'fffrW ~UJIF
/ff'(
SOUTHWEST RESEARCH INSTITUTE IX-FE-119-0 February 1981
~ NUCLEAR PROJECTS OPERATING PROCEDURE
~
Page 2 of 16 MEASURING AND RECORDING SEARCH UNIT DATA DURING ULTRASONIC EXAMINATIONS OF PRESSURE VESSEL WELDS l.Q* PURPOSE This procedure provides the technical information and detailed steps required for measuring and recording search unit location and signal amplitude data during ultrasonic examinations of pressure vessel welds. 2.0 SCOPE AND APPLICATION (1) This procedure provides a uniforni set of guidelines for recording search unit location and signal amplitudes. (2) This procedure is applicable to straight- and angle-beam exami-nations of clad or unclad pressure vessel welds, heat-affected zones, and adjacent base material using manual, contact and pulse-echo ultrasonic techniques.
- 2.1 Applicable Documents 1 The following documents, as applicable, form a part of this procedure:
(1) Southwest Research Institute (SwRI) Nuclear Quality Assur-ance Program Manual (NQAPM). (2) The applicable SwRI Operating Procedures for the ultrasonic examinations being conducted. (3) ASME Boiler and Pressure Vessel Code, Section XI, 1974 Edi-tion, With Addenda through Summer 1975, "Rules for Inservice Inspection of Nuclear Power Plant Components." 3.0 RESPONSIBILITY (1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible for the preparation, review, control, and approval of this procedure. SwRI Form OA-3*2 *
- SOUTHWEST RESEARCH INSTITUTE IX-FE-119-0 February 1981
~ NUCLEAR PROJECTS OPERATING PROCEDURE
~
Page 3 of 16
*(2) The Project Manager shall be responsible f~r the implementation of this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan.
(3) The examiner shall be responsible for implementing the require-ments of this procedure. (4) The Manager of Support and Ad~nistration Section, Quality Assurance Systems and Engineering Division, shall be responsible for storage of records generated in accordance with this procedure. 4.0 PROCEDURE REQUIREMENTS I
;I (1) Personnel utilizing this procedure shall be certified in accor-dance with Nuclear Quality Assurance Procedure NQAP 11-1, "Special
- (2)
Process Control." Examination shall be conducted as required by the applicable SwRI Operating Procedures. 5.0 PROCEDURE Weld length, nontransverse "L," and transverse "W" measurements for circumferential welds shall be made.along the weld centerline starting at Lo and be made clockwise as viewed from above a vertical vessel, or clockwise as viewed from an identified end of a horizontal vessel. The end of the horizontal vessel used as a reference shall be recorded in the "REMARKS" section of the applicable SwRI Examination Record. Weld length, nontransverse "L," and transverse "W" measurements for longitudinal welds shall be made along the weld centerline starting from Lo. Lo for longitudinal welds in vessels shall be the centerline of the intersecting circumferential weld at the top end of the longitudinal weld. For longitudinal welds in horizontal vessels, an end of the vessel shall be designated as the top and the location recorded in the "REMARKS" section of the applicable SwRI Examination Record. Weld length, nontransverse "L," and transverse "W" measurements for nozzle-to-shell welds shall start at Lo and be made clockwise for examina-tions from the outside surface and counterclockwise for examinations from the inside surface. Clockwise or counterclockwise shall be determined by viewing the weld from a position which is perpend~cular to the vessel
- surface.
SwRI Form QA-3*2
SOUTHWEST RESEARCH INSTITUTE IX-FF;-119-0 February 1981
*~ NUCLEAR PROJECTS OPERATING PROCEDURE *~ Page 4 of 16 "L" measurements for vessel-to-flange welds examined from the seal surface shall start at Lo and be made clockwise as viewed from above the vessel. "W" measurements shall be made from the junction of the flange seal surface and the inside surface of the vessel.
- Weld length, non transverse "L," and transverse* "W" measurements for fillet type attachment welds shall start at Lo and be made clockwise.
Clockwise shall be determined by viewing the weld from a position which is perpendicular to the vessel surface. 5.1 Weld Length and Reference Points Weld lengths, if required, shall be measured with*a steel measuring tape and the distance recorded in inches and common fractions to the nearest 1/16 inch. 5 .1.1 Circumferential Butt Welds (1) Reference points with a maximum spacing of 10 inches shall be drawn on the weld centerline. The reference points shall be laid out from a point coinciding with 0° of the vessel. (2) Each reference point shall be identified on the vessel in inches from.Lo. 5 .1.2 Longitudinal Welds (1) Reference points with a maximum spacing of 10 inches shall be drawn on the weld centerline. The reference points shall be laid out from the centerline of the intersecting circumferential weld. (2) Each reference point shall be identified on the vessel in inches from Lo. 5 .1. 3 Nozzle-to-Shell Welds ( 1) Two reference circles shall be drawn around each nozzle. The radii of the circles shall be the number of inches from the nozzle centerline, expressed in whole numbers. The location of the 0° azimuth and radii of the circles shall be recorded on the SwRI Examination Record. SwRI Form QA-3-2
- SOUTHWEST RESEARCH INSTITUTE IX-FE-119-0 February 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 16 NOTE The radius of a reference circle can be cal-culated by measuring the circumference of the nozzle boss and dividing this distance by 6.28. This result is the radius of the nozzle (measured to the outside surface). The dis-tance from the nozzle boss to the reference circle plus the radius of the nozzle equals the reference circle radius.
I (2) The inner reference circle shall be located within 1/2 inch of the weld centerline. The outer reference
*-***** circle shall be located so that the scan area is
~;
encompassed within it. (3) The 0°, 90°, 180°, and 270° azimuth shall be marked on the inner reference circle of all nozzles. Every 30 degrees of azim'1th shall be marked for nozzle welds with a radius greater than 4 inches. Nozzle welds with a radiu's greater than 12 inches shall be marked in 15° increments and those with a 24-inch radius shall be marked in 5° increments. Radial lines extending to the outer reference circle shall be drawn through each azimuth marked. The azimuth points and radial lines shall be used to maintain the correct search unit orientation and not for measurements. (4) Every 10 inches around the inner reference circle shall be marked and identified on the vessel. The reference points marked every 10 inches shall be utilized for measurements. 5.1.4 Support and Other Similarly Welded Attachments with Fillet Type Weld Surfaces When the examination is pe.rformed from the vessel, weld lengths shall be measured on the vessel surface at the junc-tion of the weld and the vessel. When the examination is performed from the support or other similarly welded attach-ment, weld lengths shall be measured on the attachment surface at the junction of the weld and the attachment. SwRI Form OA*3*2
SOUTHWEST RESEARCH INSTITUTE IX-FE-119-0 February 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 16 (1) Reference points with a maximum spacing of 10 inches shall be drawn. on the vessel or attachment surface. (2) Each reference point shall be identified on the appropriate surface in inches from Lo. 5.2 Amplitude Movements (l) Maximum signal amplitude shall be attained by search unit manipulation. (2) Using the gain control, determine the number of decibels (dB) required to adjust the maximum signal amplitude to coincide with the distance amplitude correction (DAC) curve. Once the number of dB above or below the* primary reference level has. been de'termined, the percent of DAC shall be obtained from Sketch l. 5.3 "L" Measurements, Nontransverse Scans for Angle Beam (1) "L" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch. (2) "L" measurements shall be made to the percentages of DAC required by the applicable SwRI Operating Procedure at the maximum amplitude point, at the end points of the indication as determined by 50% of DAC, and measurements taken from successive scans in increments no greater than 9/10 of the search unit dimension for each recordable indication. 5.3.l Circumferential, Longitudinal, and Nozzle-to-Shell Welds Datum = Lo to axial center of the search *unit. Measure-ments will be made along the weld centerline using one of the following methods: (1) Measurements shall be made directly from Lo using a steel measuring tape. (2) The steel measuring tape shall be placed on the weld centerline with zero at Lo. Measurements shall then be made directly from the steel tape. SwRI Form QA-3-2
- SOUTHWEST RESEARCH INSTITUTE IX-FE-119-0 February 1981 NUCLEAR PROJECTS OPERATING PROCEDU~E Page 7 of 16 (3) Measurements shall be made, using a steel measuring tape, from the reference points established in accordance with Paragraph 5.1.
5.3.2 Supports and Other Similarly Welded Attachments with Fillet Type Weld Surfaces ~ Datum = Lo to axial center of the search unit. Measure-ments shall be made along the junction of the examination surface and the weld using one of the following methods: (1) Measurements shall be made directly from Lo using a steel measuring tape. (2) The steel measuring tape shall be placed on the examination surface at the weld fusion line with zero at Lo. Measurement shall then be made directly from the steel tape. (3) Measurements shall be made, using a steel measuring tape from the reference points established in accordance with Paragraph 5.1. 5.4 "L" Measurements, Transverse Scans for Angle Beam (1) "L" measurements sh al 1 be recorded in inches and .common fractions to the nearest 1/16 inch. ( 2) "L" measurements shall be made to the percentages of DAC required by the applicable SwRI Operating Procedure at the maximum amplitude point at the end points of the indication as determined by 50% of DAC, and measurements taken.from successive scans in increments no greater than 9/10 of the search unit dimension for each recordable indication. 5.4.1 Circumferential, Longitudinal, and Nozzle-to-Shell Welds Datum = weld centerline to axial center of search unit.
"L" measurements shall be made perpendicular to the weld centerline using a 6-inch steel rule or steel measuring tape .
- SwAI Form OA-3-2
. SOUTHWEST RESEARCH INSTITUTE IX-FE-119-0 February 1981 NUCLEAR PROJECTS OPERATING PROCEDURE
_Page 8 of 16 5.4.2 Supports and Other Similarly Welded Attachments with Fillet Type Weld Surfaces Datum = junction of examination surface and weld to axial center of search unit. "L" measurements shall be made perpendicular to the weld fusion line using a 6-inch _steel rule or steel measuring tape; 5.5 "L" Measurements for Vessel-to-Flange Welds Examined From Seal Surface "L" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch.
"L" measurements shall be made to the maximum amplitude point, at the end points of the indication as determined by 50% of DAC, and from successive scans in increments no greater than* 9/10 of the search unl.t dimens_ion for each recordable indication.
Datum = Lo to axial center of the search unit. Measurements shall be made along the junction of the flange seal surface and inner surface of the vessel" using one of ,'the following methods: - (1) Measurements shall be made directly from Lo using a steel. measuring tape. ( 2) Measurements shall be made using a steel measuring tape from the reference point established in accordance with Paragraph 5.1. 5.6 "L" Measurements for Straight Beam Datum = Lo to the axial center of the search unit. "L" measure"" ments shall be recorded in inches and common fractions to the nearest 1/16 inch. 5.6.1 Straight Beam DAC ( 1) "L" measurements shall be made to the percentages.of DAC required by the applicable SwRI Operating Pro-cedure at the maximum amplitude point, at the end points of the indication as determined by 50% DA9, SwRI Form QA-3-2
- SOUTHWEST RESEARCH INSTITUTE IX-FE-119-0 February 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 16 and measurements taken from successive scans in increments no greater than 9/10 of the search unit dimension for each recordable indication.
( 2) "L" measurements shall be made as described in 5. 3 .1 and 5.3.2, as applicable. 5.6.2 Straight Beam Lamination ( 1) "L" measurements shall be made to the edges of the laminar type reflector as specified by the applicable SwRI Operating Procedure along with measurements taken from successive scans across the reflector in increments no greater than 1 inch. A laminar reflector may require measurements from two areas, as
- (2) required by the applicable SwRI Operating Procedure .
"L" measl!rements shall be made as described in 5.3.1 and 5.3.2, as applicable.
5.7 "W" Measurements, Nontransverse Indications for Angle Beam (1) "W" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch. (2) Each point requiring "L" measurements shall have "W" measure-ments made to the maximum amplitude point (Wmax>, the point of minimum metal path reading for 50% of DAC (W1) 1 and the point of maximum metal path reading for 50% of DAC (W2). 5.7.1 Circumferential, Longitudinal, and Nozzle-to-Shell Welds Datum = weld centerline to the incident point of the search unit. "W" measurements shall be made perpendicular to the weld centerline using a 6-inch steel rule or steel measuring tape. 5.7.2 Supports and Other Similarly Welded Attachments with Fillet Type Welded Surfaces Datum = junction of examination surface and weld to the incident point of the search unit. "W" measurements shall be made perpendicular to the weld fusion line using a 6-inch steel rule or steel measuring tape. SwRI Form QA-3-2
SOUTHWEST_ RESEARCH INSTITUTE IX-FE-119-0 February 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 10 of 16 5.8 "W" Measurements, Transverse Indications, for Angle Beam ( 1) W" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch. (2) Each point requiring "L" measurements shall have "W" measure-ments made to the maximum amplitude point (Wmax), the point of the minimum metal path reading for 50% of DAC (W1), and the point of maximum metal path reading for 50% of DAC (W2). 5.8.1 Circumferential, Longitudinal, and Nozzle-to-Shell Welds Datum = Lo to the incident point of the search unit. Mea- ~ surements shall be made along the weld centerline using one of the following methods: (1) (2)
"W" measurements shall be made directly from Lo using a steel measuring tape. **
The steel measuring tape shall be affixed to the weld centerline with zero at Lo. Measurements shall then be made directly. (3) "W measurements shall be made, using a steel measur-ing tape, from the reference points established in 5 .1. 5.8.2 Supports and Other Similarly Welded Attachments with Fillet Type Weld Surfaces Datum= Lo to the incident point of the search unit. Mea-surements shall be made from Lo along the junction of the examination surface and weld with a 6-inch steel rule or steel measuring tape. 5.9 "W" Measurements for Vessel-to-Flange Welds Examined from Seal Surface Datum = junction of flange seal surface and inner surface of the vessel to the axial center of the search unit. "W measurements shall be made using a 6-inch steel rule or steel measuring tape . SwRI Form OA-3-2
- - SOUTHWEST RESEARCH INSTITUTE IX-FE-119-0 February 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 11 of 16 "W" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch. "~' measurements shall be recorded at the positions required by 5. 7(1) and 5. 7(2) except "W" measurements shall be made only at_ the Wmax position. The 50% W1 and 50% W2 positions shall not be recorded.
5.10 "W" Measurements for Straight Beam Datum = Wo to the axial center of the search. unit. :11 w11 mea-surements shall be recorded in inches and common fractions to. the nearest 1/16 inch. 5.10.1 Straight Beam DAC (1) Each point requiring "L" measurements shall have "W" measurements made to* the maximum amplitude point (Wmax), the point (W1) at 50% of DAC located toward Wo from Wmax and the point (W2) at 50% DAC located the farthest from Wo. (2) Measurements shall be made with a 6-inch steel rule or steel measuring tape. 5.10.2 Straight Beam Lamination ( 1) "~' measurements shall be made to the edges of the laminar type reflector as specified by the appli-cable SwRI Operating Procedure and each point requiring "L" measurements. (2) "~' measurements shall be made with a 6-inch steel rule or steel measuring tape. 5.11 Metal Path Measurements 5:11.1 Angle Beam ( 1) Metal path measurements shall be recorded in 'inches and decimal fractions to an accuracy within 2% of full screen width .
- SwRI Form QA-3-2
SOUTHWEST RESEARCH INSTITUTE IX-FE-119-0 February 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 12 of 16 (2) Each point requiring "L" measurements shall have metal path measurements taken at the maximum ampli-tude point <Wm.ax), the minimum metal path reading for 50%.of DAC (W1), and the maximum metal path reading for 50% of DAC (W2). 5 .11. 2
- Straight Beam 5.11.2.1 Straight Beam DAC (1) Metal path measurements shall be recorded in inches and decimal fractions to an accuracy within 2% of full screen width.
(2) Each point requiring "L" measurements shall have meta.l path measurements taken at the maximum amplitude point (Wmax>, the point (W1) at 50% of DAC located toward Wo from Wmax and the point (W2) at 50% DAC the ~arthest from Wo. 5.11.2.2 Straight Beam Lamination (1) Metal path measurements shall be recorded in inches and decimal fractions to an accuracy within 2% of full screen width. (2) Each point. requiring "L" measurements shall require metal path measurements made to the points where the intermediate indi-cation equals the remaining back reflec-tion and at the points, if any, of total loss of back reflection. 5.12 Crown Width and Height for Fillet Welds The crown height and width for fillet welds shall be measured as shown in Sketch 2. 5.13 Examination Limitations Scanning limitations shall be recorded as required by 5.13.1 and 5.13.2. "W measurements shall be made to the search unit exit SwRI Form OA*3*2
- SOUTHWEST RESEARCH INSTITUTE IX-FE-119-0 February 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 13 of 16 point and "L" measurement shall be made to the axial center of the search unit.
5.13.1 Straight Beam Straight-beam lamination scans shall be conducted only in the areas through which the sound beam will travel in the angle beam examination; therefore, limitations shall only be recorded for areas scanned by the angle beam and not scanned by the straight beam. Limitations shall be recorded for straight-beam DAC calibrations. The maximum limitation in the 11W" direction shall be recorded. The minimum point and the maximum point of the limitation shall be recorded in the "L" direction
- 5.13.2 Angle Beam Limitations shall be recorded for angle-beam calibrations.
For examinations which utilize two angles the limitations of the search unit -with the larger limitation shall be recorded. The maximum limitation in the "W" direction shall be recorded. The minimum point and the.maximum point of the limitation in the "L" direction shall be recorded. 5.14 Abbreviations Appropriate abbreviations (listed belOw) "'?hich describe the search unit location with respect to the weld".ceriterline or edge shall be entered on the applicable SwRI Examination Record with the measurements. ( l) Up - U (2)* Down - D (3) Clockwise .:.cw (4) Counterclockwise - CCW (5) Vessel side of centerline - V
- SwRI Form QA*3*2
SOUTHWEST_ RESEARCH INSTITUTE IX-FE-119-0 February 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 14 of 16 (6) Lug or support side - L or S (7) Other symbols with descriptions entered in the "Remarks" section may be used as approved by the Team Supervisor. 6.0 RECORDS Required records* shall be specified in the applicable SwRI Operating Procedure. Permanent documents generated in accordance with this procedure shall be stored and retained as a portion of the examination report. The examination report shall be stored by the Manager of Support and Administration Section, " Quality Assurance Systems and Engineering Division, in the Data Storage Facility for the period specified by the contractual agreement with the customer. SwRI Form ClA-3-2
- DAC vs. dB *conversion Chart IX-FE-119-9 February 1981 Page 15 of 16
%DAC dB %DAC 100 0 100 90 1 112 80 2 125 70 3 141 63 4 159 56 5 178 50 6 200 45 7 224 40 8 251 36 9 282 32 10 316 28 11 355 25 12 400
- 22 13 447 20 14 501
,, 18 15 562 16 16 631 14 17 708 13 18 794 11 19 891 10 20 1000 Percent DAC of an amplitude below DAC, which must be increased in amplitude by the dB number change to equal DAC, is read in the column on the left.
For example, an indication is increased in amplitude by 13 dB to equal the DAC curve; therefore, the indication is 22 percent of DAC. Percent DAC of an.amplitude above DAC, which must be decreased in amplitude by the dB number change to equal DAC, is read in the column on the right. For example, an indication is decreased in amplitude by 13 dB to equal the DAC curve; therefore, the indication is 447 percent of DAC. SKETCH 1
IX-FE-119-9 1 February 19816 Page 16 of Yesse) SKETCH 2
SOUTHWEST RESEARCH INSTITUTE X-FE-101-2 NUCLEAR PROJECTS OPERATJNG PROCEDURE November 1982 Page 1 of 6 Title ONSITE NDE RECORDS CONTROL EFFECTIVliY ANO APPROVAL. ReYision two of this procaclure became effective on 12/9/82 . This procedure comim of the pages and changes listed below. Page No 01ange Date Effective Accrovals Date Cate' ll/2'i/a2
- Sw"I l'orm QA-a.QS-0 /
I Date
/<:, /J* ,_
t..
SOUTHWEST RESEARCH INSTITUTE X-FE-101-2 November 1982 NUC_LEAA PROJECTS OPERATING PROCEDURE Page 2 of 6 ONSITE NDE RECORDS CONTROL
- 1. PURPOSE This procedure describes the onsite control processes for nondestructive examination records (data) generated in the field during preservice (PSI) and inservice (ISI) examinations. -
- 2. SCOPE AND APPLICATION 2.1 This procedure describes the flow of data records used to document the results of nondestructive examinations performed.
Data records include original data sheets, summary sheets, resolution sheets, strip charts,- magnetic tapes, video tapes, and other information as defined by the Inspection Engineer or Team Supervisor. 2.2 This procedure provides guidance to personne_l of the NDE Field Services Section who are assigned the responsibility of 2.3 preparing, reviewing, or otherwise using data records while in the field performing a preservice or inservice examination. Functional steps are provided in this procedure to explain the flow of the records.
- 3. RESPONSIBILITY
- (1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be respon-sible for the preparation, review, approval, and control of this procedure.
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicable *swRI Project Plan. (3) The Inspection Engineer shall be responsibie for implementing the requirements of and ensuring compliance with this procedure. (4) The Manager of the Support and Administration Section, Quality Assurance Systems and Engineering Division, shall be responsible for'storage of records generated in accordance with this procedure. SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE X-FE-101-2
- November 1982 NU_CLEAR PROJECTS OPERATING PROCEDURE Page 3 of 6 4*
- PROCEDURE 4.1 Original Data Sheets (1) Original data sheets, are to be serialized either at SwRI or at the site.
(2) Original data sheets shall be filled out at the examination location and during the examination time. (3) The filled-out original data sheets shall be returned to the team staging area (office, trailer, etc.) on a periodic basis (at meai time, at the end of the day, upon leaving controlled areas) during an !SI or a PSI, and an entry shall be made into a daily log indicating that the examinations have been performed. * (4) The original data sheets shall then be placed into the To-Be-Reviewed File. (5) The review process is performed as follows: (a) The original data sheets shall be checked for completeness, accuracy, and consistency of the data. (b) If clarification or correction of any entry on the original data sheets is required, the original data sheets shall be returned to the examiner. (c) After clarifications or corrections, if any, have been made and initialed by the examiner, the reviewer shall sign each original data sheet which does not contain indications requiring evaluation/resolution. (6) The original data sheets which have been reviewed and signed shall be moved to the To-Be-Summarized File. See Paragraph 4.1(9). (7) Original data sheets which contain indications requiring evaluation/resolution shall be placed in the To-Be-Resolved File *
- SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE X-FE-101-2
~
November 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 6 (a) Original data sheets in.the To-Be-Resolved File which document visual or surface examinations shall be handled as follows: (1) The Original data sheets shall be reviewed, signed by the reviewer, and used to generate a Customer Notification Form (CNF). (The CNF shall be completed according to NQAP 13-1.) * (2) Copies of original data sheets shall be made and attache4 to the CNF. (3) A log shall be maintained of CNFs issued and their status. (4) The original data sheets are then placed in the To-Be-Summarized File. See Paragraph 4.1(9). (8) (b) Original data sheets in the To-Be-Resolved File which document ultrasonic examinations shall be used to resolve the indications according to Paragraph 4.3 and shall then be processed as specified in Paragraphs 4.1(5) and 4.1(6). When a computer is used to record results and generate summary sheets, data shall be fed into the computer. The computer will generate the summary sheets at the completion of all required examinations of an examination area. (9) If the computer is not used to generate summary sheets, data placed in the To-Be-Summarized File shall be summarized according to Paragraph 4.2 and filed with the suuimary sheet in the original data volumes. 4.2 Summary Sheets (1) Summary sheets, are to be serialized either at SwRI or at the site. (2) Summary sheets shall be completed for each examination area. In certain cases (stu4s, nuts, etc.), one summary sheet may be used for more than one examination area
- SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE. X-FE-101-2 November 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 6 (3) Summary sheets shall be completed prior to the conclu-sion of site activities for each examination area for which examination requirements have been completed. (4) Summary sheets shall be filed with the data in the original data volumes. 4.3 Resolution Sheets (1) Resolution sheets, are to be serialized either at SwRI or at the site. (2) The Level II or Level III examiner shall take the steps necessary to resolve the ultrasonic indications and complete a resolution sheet describing the results of his analysis. Any additional documentation required to support the resolution shall be attached. (3) Original data sheets and resolution records with indica-tions requiring no further action shall be placed in the
- -*** (4)
To-Be-Reviewed File and processed as specified in Para-. graphs 4.1(5) and 4.1(6). Data with indications requiring further action shall be handled in a manner established by the Director of the Department of Engineering Services. 4~4 Strip Charts, Magnetic Tapes, Video Tapes (1) Strip charts, magnetic tapes, and video tapes being generated during mechanized ultrasonic examinations shall be identified with*a sequence number and with. the examination areas for which they contain data. (2). During the resolution of any indications, the strip charts and tapes may be used by the Level II or Level III examiner, as needed. (3) The strip charts and tapes are then prepared for transmittal to SwRI.
- 5. RECORDS 5.1 Prior to departing the site at the completion of a preservice or inservice examination, the original data package with the exception of strip charts, magnetic tapes, and video
- SwRI Form QA3*2
SOUTHWEST RESEARCH INSTITUTE ~-FE-101-2
~ovember 1982 NUCLEAR PROJECTS OPERATING PROCEDURE
!Page 6 of 6 tapes shall be reproduced and. a copy(ies) shall be transmitted to the appropriate sfte personnel. At no time will data be reproduced-for this transmittal before the required examinations for a particular area are complete, the data has been reviewed, and the summary sheets have been completed.
5.2
- After completion of site activities (or at other times deemed appropriate by the Inspection Engineer or Team Supervisor), the original data package shall be transmitted to SwRI in accordance with the latest revision of SwRI Nuclear Projects Operating Procedure XVII-AG-101.
SwRI Form QA 3-2 J
SOUTHWEST RESEARCH INSTITUTE XIII-AG-101-2
- Title NUCLEAR PROJECTS OPERATING PROCEDURE CONTROL OF NUCLEAR INSPECTION EQUIPMENT AND MATERIALS September 1982 Page 1 of 12 EFFECT1V1TY AND APPROVAL Revision 2 of th is procedure became effective on lO / 4 / 8 2 . This procedure consists of the pages and .
changes listed below. Page No Change Date Effective 1-12 0 September 1982 SA Approvals Date Technical Review
- SwRI Form QA-408-0
.Date Cognizant Director ... /.""
*~
Date
SOUTHWEST RESEARCH INSTITUTE XIII-AG-101-2 September 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 12 CONTROL OF NUCLEAR INSPECTION EQUIPMENT AND MATERIALS
- 1. PURPOSE 1.1 The purpose of this operating procedure is to provide control for the storage, inventory, issue, shipment, and return to stock of examination equipment and materials.
- 2. SCOPE AND" APPLICATION 2.1 The scope of this procedure is the control of nuclear examination equipment to ensure the integrity of equipment and materials used during the examination of nuclear power plant components. See NPOP VII-AG-102 for control of Search Units.
2.2 Controls are further required to ensure that maximum utilization is made of available equipment, i.e., equipment is not "lost" in the Radiation Control facility, delayed or misplaced during transit from job site to maintenance shops, or allowed to remain out of circula-tion for long periods of time while being used for research and development projects. The flow chart illustrates the control and process of nuclear inspection equipment (Attachment 1). 2.3 This procedure is applicable to, but not limited to, control of the
*following equipment and materials:
(1) Ultrasonic Examination Materials and Equipment (2) Plastic Wedges (3) Penetrant Examination Materials (4) Magnetic Particle Examination Materials and Equipment (5) Eddy Current Examination Equipment and Standards (6) Mechanized Examination Equipment (7) Data Acquisition Systems 2.4 The following documents form a portion of this procedure as applicable. 2.4.1 SwRI Nuclear Quality Assurance Program Manual (NQAPM). 2.4.2 SwRI Radiological Health and Safety Manual. SwRI Form QA 3-2
- XIII-AG-101-2 SOUTHWEST RESEARCH INSTITUTE
- NUCLEAR PROJECTS OPERATING PROCEDURE September 1982 Page 3 of 12
- 3. RESPONSIBILITY 3.1 The Vice President of the Quality Assurance Systems and Engineering Division shall designate one or more secure areas to be used for equipment and materials storage as control facilities.
3.2 Control facilities shall be operated by a Stock Clerk and an Equip-ment Clerk. The Stock Clerk will be under the supervision of Inven-tory Control Traffic Manager who will be responsible for inventory storage and issue of examination materials. The Equipment Clerk, under the supervision of the Supervisor, Administration Control, will be responsible for inventory, storage, issue and retrieval of controlled equipment. 3.3 Responsible users, such as Team Supervisors, shall be responsible for compiling a list, using SwRI Form SS-17 Equipment Control/ Shipping List (Attachment 2), of equipment and materials required for each'job or project. They shall be responsible for shipment of the equipment to the job site, security while at the job site, reshipment upon completion of the job, documentation of faulty equipment, and turn-in of equipment and unused materials
- 3.4 The Division Health Physicist or his representative shall be respon-sible for accepting equipment and materials returned from an. inser-vice examination, its decontamination, and returned to its proper storage facility.
3.5 The Assistant Manager, Technical Activities Group, or his alternate shall be responsible for providing minimum maintenance turnaround time and for providing current certifications as required for nuclear examination equipment. 4* PROCEDURE 4.1 New Equipment 4.1.1 Newly purch~sed or fabricated critical equipment shall be inspected in accordance with SwRI Operating Procedure VII-AG-101 prior to being routed to the appropriate control facility *
- SwRI Form QA 3-2
XIII-AG-101-2 SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE September 1982 Page 4 of 12
- 4.1.2 An identification number (serial number) will be assigned to noncapital equipment which.does not have a manufacturer's serial number.
4.1.3 Upon completion of proper identification, new equipment will be listed on the control-facility inventory records. 4.1.4 Once new equipment is properly identified and inventoried, it will be issued to the appropriate maintenance facility for an operational check and certification in accordance with NQAPM Procedure NQAP .10-1. The maintenance facility will return the equipment, along with copies of certifi-cations generated, to the control facility. The new equip-ment may then be issued for nuclear inspection work. 4.2 Equipment and Materials Issue 4.2.1 When it is determined that equipment and/or materials are to be removed from the appropriate control facility, with the exception of equipment routed through the maintenance facil-ities (Paragraph 4.6.3), the Team Supervisor or Responsible User will compile a list of required equipment an~ materials needed using Form S~-17. The responsible supervisor"shall complete each blank at the top portion of the form with no exceptions. On the second part of the form, he will list quantity and nomenclature of each item of equipment or materials required and indicate those which require certifications. 4.2.2 When the Team Supervisor or Responsible User has initiated Form SS-17, he may assign any technician to draw and pack the equipment. The technician will present Form SS-17 to the appropriate control facility, and the Clerk will issue the material or equipment. The Clerk will enter appropriate serial number and estimated replacement cost of each item on Form SS-17 as the equipment is issued. He will also supply copies of appropriate certifications as required. 4.2.3 When requested equipment and materials have been issued, the technician will sign each Form SS-17, indicating that he has received the items for the responsible supervisor, and shall notify the QA Section so they can review the equipment and certifications. SwRI Form QA 3-2
- XIII-AG-101~2
*soUTHWEST RESEARCH INSTITUTE
- NUCLEAR PROJECTS OPERATING PROCEDURE September 1982 Page 5 of 12 4.2.4 The Equipment Clerk will distribute Form SS-17 as follows:
(1) Copy 1 (white): Forward to the Division Shipping Agent (2) Copy 2 (yellow): Give to the person receiving the equipment (3) Copy 3 (pink): Retain for control purposes (4) Copy 4 (goldenrod): Will be given to QA when QA inspection is required. If a QA inspection is not required, this copy will be destroyed. 4.3 Equipment Packing and Shipping 4.3.1 If the equipment and/or materials are to be shipped from the Institute grounds, the technician .will pack each item in numbered shipping containers. He will then enter the container number in the appropriate Box No. space on Form SS-17
- 4.3.2 If the eq~ipment is to be shipped by freight, a box count must be made and each box must be weighed. Shipping labels must be completed and affixed to each shipping container.
4.3.3 When the packing has been completed, the technician will return Copy 2 of Form SS-17 to the responsible supervisor who retains this copy for accountability of equipment while in his possession. 4.3.4 If equipment is to be shipped by freight, the responsible supervisor will contact the Requisitioning Agent, who will arrange for shipping and for the proper shipping documents td be completed. 4.3.5 The responsible supervisor will review Form SS-17, with special emphasis placed on ensuring that appropriate certi-fications are available for each item that requires certification. 4.4 Onsite Control 4.4.l The Team Supervisor o.r Project Engineer shall assume responsibility for the security of equipment once it has been drawn from the control facility. At the job site, he will obtain a secure area to be used for equipment storage
- SwRI Form QA 3-2
XIII-AG-101-2 SOUTHWEST RESEARCH INSTITUTE September 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 12 and will arrange for issue of the equipment or materials as the work load demands. He will ensure that equipment placed into onsite storage after use is dry and clean and.that any equipment damaged or found to be inoperative or out of toler-
. ance is tagged with a Form SS-19, "Hold Tag", to indicate its condition (Attachment 3).
4.5 Decontamination 4.5.1 Equipment being returned from an inservice inspection must be delivered to a radiation control area immediately upon return to the Institut.e. This equipment will be controlled in accordance with SwRI Radiological Health and Safety Manual, Paragraph 5.2.
- 4.6 Equipment/Material Turn-in 4.6.l Upon completion of a project or the return to the Institute of equipment used off the grounds, the equipment will be returned to the control facility. (See Paragraph 4.6.2 when returning from an inservice examination.) As each item is checked in, the Equipment Clerk will enter the date in the Date Returned block of copy 3 of the Form SS-17. He will also initial in the Date Returned block of copy 2 of the Form SS-17 when requested.
4.6.2 Expendable materials such as Penetrant Examination Material and Magnetic Particle Examination Materials will be returned to the stock room. When the Stock Clerk can determine that the material has not been used and identifying data is avail-able to trace the material to the appropriate certificates and to the original purchase order, he will credit _the appropriate job site by processing an appropriate store requisition. 4.6.3 Equipment and material being returned from an inservice examination must be delivered to a radiation control area immediately upon return to the Institute. The Health Phys-icist representative will inventory equipment and material and acknowledge responsibility for it. Equipment and mate-rial that is not contaminated or that is decontaminated will be returned to the appropriate storage facility according to 4.6.1 and.4.6.2 above. Equipment that cannot be decontami-. nated will be stored in the appropriate control area and the Health Physicist representative will inform the Assistant SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE XIII-AG-101-2
- NUCLEAR PROJECTS OPERATING PROCEDURE September 1982 Page .7 of 12 Director, Engineering Services Division, and the Equipment Control Clerk in writing of-the nomenclature and the serial number of the equipment, and the site the equipment came from.
4.6.4 The Equipment Clerk will check each item for disposition. Equipment requiring repair, cleaning, or recertification/ recalibration within the next 30 calendar days will be taken to the appropriate maintenance facility.
- 4.6.5 When repair and/or certification is completed, the item will be returned to the control facility and placed in stock for reissue.
4.7 Special Issue Requirements 4.7.1 Occasionally it will be* necessary for a Team Supervisor who is in the field to request that equipment be checked out and sent to him. When this circumstance arises, he will contact. the Examination Activities Coordinator or his alternate and make his needs known. The Examination Activities Coordi-nator or his alternate wil,l initiate Form SS-17 and draw, pack, and ship the equipment. He will perform the review and enclose Copy 2 of Form SS-17 in the shipping container so that the Team Leader will have a record of what was actually shipped. 4.7.2 If equipment is to be shipped from one job location to another without returning to the Institute, a packing list will be made using Form SS-17. One copy will be retained by the responsible person making the shipment, one copy will be enclosed with the shipment, and one copy will be returned to the control facility at the Institute. The responsible supervisor will review the Form SS-17 to ensure that certifi cates were included as required. 4.8 Lost or Destroyed Equipment 4.8.1 In the event any item other than normally consumable mate-rials is lost or destroyed while it is signed out of the control facility, the responsible supervisor will initiate a memorandum addressed to the Assistant Director, Engineering Services Division, with a copy to the Manager of Support and Administration and the Supervisor, Administration Control. The memorandum will identify the equipment and describe the circumstances involved with its loss or destruction *
- SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE XIII-AG-101-2 September 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 8 of 12 4.9 Recall of Equipment for Recalibration 4.9.l When notified that a particular piece of equipment is due recalibration, the Equipment Clerk will determine the loca-tion of the equipment by reviewing his equipment inventory records. If the equipment is located within the stock room, he will take the equipment to the appropriate certifying facility. When the equipment has been issued, he will notify the Assistant Manager, Technical Activities Group, or other responsible supervisor by completing a Form SS-42 (Attachment 4). The Activity Coordinator or responsible supervisor will ensure* the equipment is sent to the Equip-ment Clerk on or before the recalibration date. The Equip-ment Clerk will then take it to the appropriate certifying facility.
- Note: If a particular piece of equipment is being used in a non-critical application, it need not be returned until completion of the project.
- 5. RECORDS 5.1 Copy 3 of Form SS-17 shall be maintained by the control facility for
*a minimum of six months after the last item on the form was turned ill*
5.2 SwRI Form SS-42 may be destroyed upon return of equipment to the stock room *. 5.3 The Equipment Clerk will maintain a file of current equipment cer-tification records. An adequate number of copies will be included for issue during equipment issue. SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE XIII-AG-101-2 September 1982.
Page 9 of 12-New Equipment Equipment Control r----- 1 r - - - -, Inventory I r-----, I '~-,.....~~ I : Radiation : I Equipment I
- I Maintenance Storage )1111.-1-----11 Co ntro 1 I I* I I Laboratory I I_ _ _ _ _ _J I I I I I Issue I L-- __ J I
L
--~ _l_J o-------
Equipment User i Attachment 1
- SwRI Form QA 3-2
XIII-AG-101-2 SOUTHWEST RESEARCH INSTITUTE.
.. September 1982
~ .
NUCLEAR PROJECTS OPERATING PROCEDURE Page 10 of 12 PACI! o~ PAG!S EQUIPMENT CONTROL I SHIPPING LIST I DATE PllOaCT NO. ISIT! l DAT! lllQUlll!D SHIP,.ING METHOD llHPONSl&I SUl'UYISOll APPllOX. R!TURN DATE
)oQ SUIAL ~o COST Cl
..~
llETURN DAT! Z:t ca am: NUlllllft NOllENCl.ATUftl
*= §g INll!NTOftl!ll R!TURN!D I
RECEIVED IY'. 1 T'OTAL COST AUDITED !IY 1w1tt 'o** ****?** This Form is a 4 copy form, Page 1 is white, Page 2 is yellow, Page 3 is pink, and Page 4 is goldenrod. Attachment 2 SwRI Form QA J-2 SAMPLE FORM
1*-- SOUTHWEST RESEARCH INSTITUTE XIII-AG-101-2
- NUCLEAR PROJECTS OPERATING PROCEDURE September 1982 _
Page 11 of 12 HOLD 0 DO NOT USE a: o~ z 0 en c IM a: Attachment 3
- SwRI Form QA 3-2 SAMPLE FORM
.~ ...
XIII-AG-101-2 SOUTHWEST RESEARCH INSTITUTE
, ... I
*~ k W/ /./
NUCLEAR PROJECTS OPERATING PROCEDURE September 1982 Page 12 of 12 *
~ ' ...
RECALIBRATION NOTICE TO* I FllOM. IOAT!. THI !GUU'tlDT LISTID Ill.OW WLI. II! cm ll!CAL.llllA T10N A9 lllllCAT!D l'\.U91 lllETUllN THIS !QUll'llUT TO TMI rou*llCllT llOOM AS SOOM AS l'OSlllLI ITl!ll SllllAI. NIMAll lll!C.llJlllAT1Cll DAT! LOCATION i i Recalibration Notice
~ -.*
(SwRI Form SS-42) i :*.-:."' *. Attachment 4 f ,_
- It!!."-*- **- .*** *-- SAMPLE FORM l
SOUTHWEST RESEARCH INSTJTUTE CHANGE 1 NUCLEAR PROJECTS XVII-AG-101-1 OPERAT1NG PROCEDURE June 1982
- Page 1 of 7 Title DATA STORAGE AND RETRIEVAL EFFECTIVITY ANO APPROVAL Revision 1 of this procedure became effective on 2/10/81 . This procedure alnsists of the pages and dianges listed below.
Page No Change Date Effective 1 1 6/22/82 2 0 2/10/81 3 1 6/22/82 4-7 0 2/10/81 '\ *'t' SA _\ Apcrovais Date (
~i/~¥.J( \
- J'!.is'J i Manager of a.A. Date Cognizant c~" /
~ ~ .
f{ f4~ .:i-~/
/-
SOUTHWEST RESEARCH INSTITUTE XVII-AG-101-1 January 1981 ~ NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 7 DATA STORAGE AND RETRIEVAL
1.0 INTRODUCTION
1.1 Purpose This procedure establishes a system for the control and the storage of data for nuclear power plant components classified by ANSI N45.2.9, "Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants ... This operat-ing procedure satisfies the requirements of Appendix B to 10CFRSO, Criterion XVII and the SwRI Nuclear Quality Assurance Program Manual *. Scope and Application 1.2.1 The scope of this procedure is limited to the documentation of nuclear power plant examinations performed by NDE Field Services, Quality Assurance Systems and Engineering Divi-sion, and to other documentation as designated by the Vice President, Quality Assurance Systems and Engineering Div.ision. 1.2.2 This procedure applies to the Data Control Clerk, Team Supervisors, Inspection Engineers, and all other personnel who enter documents into and receive them from the Data Storage Facility. 1.2.3 Other divisions of the Institute may store quality assur-ance records for nuclear power plants in the Data Storage Facility. Once these records have been entered in the facility~ they will be controlled according to this procedure. 1.3 Responsibility 1.3 .1 The Manager of Support and Administrative Services within the Quality Assurance.Systems and Engineering Division shall be responsible for the implementation and control of this procedure.
- SOUTHWEST RESEARCH INSTITUTE CHANGE 1 XVII-AG-101-1 NUCLEAR PROJECTS OPERATING PROCEDURE June 1982 Page 3 of 7 1.3.2 The Data Control Clerk of Support and Administrative Ser.;;; !
vices shall be responsible for controlling; filing, and ; maintaining documentation covered by this procedure in the**--, Data Storage Facilities. The Data Clerk shall assume this
- responsibility when documents are received in accordance--
with Paragraphs 2.1, 2.2, and 2.3. 1.3.3 Team Supervisors, Inspection Engineers, and other personnel compiling documentation shall be responsible for ensuring completeness and accuracy of documentation being entered into the Data Storage Facility (see Section 2.0). 1.3.4 The Manager of Support and Administrative Services, or a representative, shall routinely review Section performance against the requirements of this procedure. 1.3.5 The Manager of Quality Assurance, or a designated repre.:0.- sentative, shall routinely audit performance against the requirements of this procedure and shall rep.art the results of such audits to the 'Manager of Support and Administrative . Services and the Vice President, Quality Assurance Systems and Engineering Division. 1.4 Data Storage Facility Description The Data Storage Facility for SwRI-retained qua~ity assurance records is located in Building 139. The construction of the facility in Building 139 is concrete block with steel vault door. The facility has a temperature control device to regulate tem-perature and humidity. 2.0 PROCEDURE 2.1 Examination data and related material being sent to SwR! will be listed on Form SS-1, Records Transmittal and Receipt. Upon completion of the form and its arrival with the data at the Institute, they will be delive_red to the Data Control Clerk *
- SwRI Form QA 3-2
. . .I -*-~~; ... ' ...... t,.".
__ *SOUTHW~ST- RESEARCH INSTITUTE XVIi-AG-101-1 January 1981
~* NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 7 2.2 _Upon receipt of the data, the Data Control Clerk will use the trans-mittal form as a checklist to ensure that all material listed has been received. The Data Clerk will inventory the data by preparing a listing of Summ~ry Sheet numbers or by entering the Summary Sheet number on a weld table. The Data Clerk will also ensure that each Examination Data Sheet listed on each Summary Sheet is in the Data Package. In those cases where a Summary Sheet is not used or has not been prepared at the time of receipt 0£ the data, the Data Clerk will prepare a listing showing the serialized number of each da_ta sheet received. The completed inventory will be filed in Section A of the file system. In addition, the Data Control Clerk will ensure that all documentation to be stored contains the
- following:
(1)- Reactor Site Name 1.- ( 2)
- (3)
Date of Record Entry
' Description of Materia!. Analog and video tapes and strip charts will identify the examination to which they relate and will be numbered. This information is entered by the Team Supervisor, t~e Inspection Engineer, or their designated alternates_.
The Data Control Clerk will then enter the data into the Data Storage Facility. 2.3 PSI and ISI reports, other nuclear power plant examination reports, examination plans, etc., relating to a particular reactor will be furnished to the Data Control Clerk by the Report Coordinator. 2.4 Other records designated by the Vice President, Quality Assurance Systems and Engineering Division, as authorized for storage in the Data Storage Facility, will be-furnished to the Data Control Clerk. 2.5 Items being removed from the Data Storage Facility shall be signed out. Original field data will be returned to the Data Storage Facility at the end of each* day. If this data needs to be used after normal working hours, special arrangements will be made with the Data Control Clerk. Other items may be signed out for the
period required. The individual withdrawing data or other material i
I shall be responsible for its safekeeping and return. I SwRI Form QA-3-2
'i,.
- SOUTHWEST RESEARCH INSTITUTt XVII-AG-101-1 .
" NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of]).>
- 2. 6 The Data Storage Facility will be maintained in a neat and orderly ,
manner. Records will be inside file cabinets or bookcases~ Loose . l papers, drawings, etc.; shall be placed in folders, binders, or , envelopes for filing. ' 3.0 RECORDS 3.1 The Data Control Clerk will maintain an up-to-date list of records covered by th is procedure and a list of their respective locat.ions. 3.2 Data maintained in the Data Storage Facility will be retained for the periods indicated in Appendix A or according to written instructions furnished to the Data Control Clerk at* the time the records are placed into the Data Storage Facility. The period of retention will in no circumstances be shorter .'than the time specified in the applicable contract. *-** .
'/*' I 3.3 Project Managers should review the records in the Data Storage Facility relating to closed projects to determine their ultimate dispositioning; i.e., return of records to client upon termination
- of contract, continuous storage in the Data Storage Facility, etc.
Dec is ions should be coordinated with the appropriate Director, and the Data Control Clerk should be notified in writing. The Data Control Clerk will comply with the written instructions.
. $.*. r: :
- . ~
i t-* ! .
- SwRI Form QA-3*2
SOUTHWEST RESEARCH INSTITUTE XVII-AG-101-1 January 1981
*~' NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 7 ~
APPENDIX A The following is a list of documentation and its retention periods as main-tained by Data Control in the Data Storage Facilities. Record Type Retention Period (1) PSI, ISI, and other examination reports, which Lifetime include: Personnel certifications Search unit, material, and instrument
*certifications Zero reference location I
(, Weld identification isometric drawings /,/- Calibration standards Nondestructive testing procedures (2) PSI, ISI, and other examination data, which Lifetime include: , (I Original data* Video tapes Analog tapes Eddy current data Eddy current tapes Strip charts Equipment calibration sheets \ Record Type Retention Period (3) PSI, ISI, and other examination plans Lifetime (4) Photographs relating to nuclear power plants As determined by the Project Manager (5) Logs, drawings, and summaries created by Lifetime
- ' field crews during an ISI or PSI (6) General information that would be of value Lifetime in conducting future ISis
. :SOUTHWEST -- RESEARCH INSTITUTE h NUCLEAR PROJECTS OPERATING PROCEDURE . . '<<
January 1 ~81 Page ?:~6.f */~* (7) Copies of procedures; .Personnel,. material, and Destroy 6 months after instrument certifications; and other report issuance of Final data Report (8) Other general information that*will not provide Destroy after 2 years valuable information in conducting future ISis
** ' * ..l. .... *~,.
!' 1 2 **.i ...:.:. I ~- ~:J:
*swRI Form ClA-3-2}}