ML19269D020

Forwards Inservice Insp Rept Performed by Westinghouse Electric Corp on 780928-1027.Includes Owners Data Rept & Class I & II Components & Piping Info

ML19269D020
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	01/19/1979
From:	Wandke N COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 7902260591
Download: ML19269D020 (22)

Text

Commonwealth Edison

-g Zion Generating Station Shiloh Blvd & Lake Michigan Zion, Ilkncis 60099 Tetephone 312/746-2084 January 19, 1979 Mr. Jamea G.

Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr. Keppler:

Enclosed please find a report of inservice inspection performed at Commonwealth Edison Co., Zion Unit 1 from September 28, 1978 through October 27, 1978.

This report is submitted to you in compliance with the requirements of Article IWA-6000 of Section XI of the ASME Boiler and Pressure Vessel Code 1974 Edition as required by Zion Technical Specification 4.3.4.C.

If there are any additional questions, please contact Mr.

R. E. Shannon at Zion Station.

Sincerely, Q

E,

'le 1 El Wandke Superintendnet Zion Station RES/kn cc:

J. J. Marianyi w/o att.

e JJ N 2 41979 78022605Ff/

INSERVICE INSPECTION REPORT FOR ZION UNIT el NUCLEAR POWER STATION 101 SIIILOH EOULEVARD ZION, ILL'NOIS 60099 FOR COf t!ONWEALTl! EDISON CO.'!PANY 101 SHILOI! DOULEVARD ZION,. ILLINOIS 60099 REPORT DATE:

JANUARY 1979 CO51MERCIAL SERVICE DATE:

DECEMBER 31, 1973 OPERATING CAPACITY:

1050 MWe Performed by:

WESTINGIIOUSE ELECTRIC CORPORATION Nuclear Service Division Inspection Service P.O.

Box 2728 Pittsburgh, Pennsylvania 15230 O

INDFX O

TAB ISI Certificate - Owner Certificate and Owner's Data Report..... A Summary............................... B

...C Examination Program.

Exami na ti on Resul ts......................... D Examinations Performed Other Than By Westinghouse NSD........ E I r. d i c a t i o n s............................. F Certifications and Quali fications.................. G Examination Procedures....................... H I

Reactor Vessel Inspection Tool Data......

O, e

e O

O 1

1

Sheet 1 of 3 FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules Commonwealth Edison Company, 101 Shiloh Boulevard, Zion,_IL 60099

1. Owner (Name and Address of Owner)

Zion Station

2. Plant (Name and Address of Plant)

1. Plant Unit 1

4. Owner Certificate of Authorization (if required >

N/A

5. Commercial Service Date 12131/73 6. National Board Number for Unit see list below for_ cach component or appurtenance

7. Coinponents Inspected Manufacturer Component or Manufacturer or Installer State of National Appurtenance or Installer Serial No.

Province No.

Board No.

ts10-0144-R.V. Head Babcock & Wilcox 51-52 74870 N-184 R.V.

Internals Westinghouse N/A N/A N/A PZR. Manway Westinghouse 1001 U121653 N868-41 Loop 1 S/G Westinghouse 1061 U121643 6827 Loop 2 S/G Westinghouse 1083 U121640 6821 Loop 3 S/G Westinghouse 1084 U121641 6822 Loop 4 S/G Westinghouse 1062 U121642 6826 Loop 2 R.C. Piping Westinghouse N/A N/A N/A Loop 4 R.C.

Piping Westinghouse N/A N/A N/A Loop 1 14" RHR Pip'ina M. W.

KellocTg N/A N/A N/A Loop 3 10" SIS Piping M. W.

Kellogg N/A N/A N/A Loop 1,2,3,4 8" RHR Pipirr; M. W.

Kelloqq N/A N/A N/A PZR 6" Safety Piping M. W. Kellogg N/A N/A N/A Loop 2 3" RTD Piping M. W. Kellogg N/A N/A N/A Loop 2&4 2"

Drain Heachr M. W. Kellogg N/A N/A N/A Common 2" Drain Header M. W. Kelloga N/A N/A N/A Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is Sta in. x 1I in.,

(2) information in items I through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorJed at the top of this form.

10017 This forrn (E00029) rnay be obtained from the Order Dept., ASME. 345 E. 47th St., New York, N.Y.

Sheet 2 of 3 FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules Commonwealth Edison Company, 101 Shiloh Boulevard,_ Zion,_IL 60099

1. owner (Name and Address of Owner)

Zion Station

2. Plant (Name and Address of Plant) l N!b

3. Plant Unit

4. Owner Certificate of Authorization (if required) see list below for each 12/31/73 6 National tioard Number for uni,

5. Commercial service 02:e component or appurtenance

7. Components inspected l

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or installer Serial No.

Province No.

Iloard No Loop 2&J 2'

RTD Piping M. W.

Kellogg N/A N/A N/A Loop 2 2"

Fill Line M. W. Kellogg N/A N/A N/A Loop 2 2"

Seal Inject M. W. Kellogg N/A N/A N/A Loop 2 lis" SIS DIT Line M. W. Kellogg N/A N/A N/A 13 "

Loop 4 5

Press. Equal.

M. W. Kellogg N/A N/A N/A Loop 3 10 " SI Welded Support M. W. Kellogy N/A N/A N/A Var. Loop 1, Supports M. W.

Kellogg N/A N/A N/A

~

Var. Loop 2, Supports M. W.

Kellogg N/A N/A N/A Var. Loop 3, Supports M. W.

Kellogg N/A N/A N/A Var. Loop 4, Supports M. W. Kellogg N/A N/A N/A Var. Lbop 2 Press. Dolting M. W. Kelloga N/A N/A N/A Var. Loop 3 Press. Bolting M.

W.

Kellogg N/A N/A N/A Var. Loop 4 Press. Bolting M. W. Kellogg N/A N/A N/A R.C.

Pump 2 Bolting Westinghouse N/A N/A N/A R.C.

Pump 4 Support Westinghouse N/A N/A N/A R.C.

Pump 2 Flywheel Westinghouse N/A N/A N/A Note: Supplemental sheets in form of lists, sketches or drawings may be used provided (I) sire is H'a in. x 11 in.,

(2)informarion in items I through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

10017

.This form (E00029) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N Y.

4

Sheet 3 of 3 FORM NIS 1 OWNERS

• DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules 101 Shiloh Boulevard, Zion, IL 60099

1. Owne, Commonwealth Edison Company, (Name and Address of owner; Zion Station

2. Plant (Name and Address of Plant)

N/A 1

4. Owner Certificate of Authoriza' ion (if required)

3. Plant Unit See list below for each

5. Commercial Service Date 12/31/736. National Board Number for Unit component or appurtenance

7. Components inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No.

Province No.

Board No.

Yar. Loop 1 Valve Boltinq Darling N/A N/A N/A Var. Loop 2 Valve Bolting Darling & Velan N/A N/A N/A Var. Loop 3 Valve Boltina Darling N/A N/A N/A Var. Loop 4 Valve Boltiny Darling N/A N/A N/A Volume Control Tank Westinghouse CWECSATVC-1 N/A N/A V.C.T.

Supports Westinghouse N/A N/A N/A V.C.T.

Bolting Westinghouse N/A N/A N/A CVCS 6" Butt Welds M. W. Kellogg N/A N/A N/A SIS & C V C S 8' Butt Welds M. W. Kellogg N/A N/A N/A RHR 12"h14" Butt Welds M. W.

Kellogg N/A N/A N/A Note: Supplemental sheets in form of lists sketches, or drawings may be used provided (1) size is 8% in. x 11 in (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

10017 This form (E00029) rnay be obtained frorn the Order Dept., ASME, 345 E. 47th St., New York, N.Y.

4

FORM NIS-1 (liack)

8. Examination Dates 9-28-78 to10]27/78 9. inspection intervai from 12-31-73i12/31/83

10. Abstract of E xaminations. Include a Int of examinations and a statement soncerning status of work required for current interval.

Reforence Tab. C

11. Abstract of Conditions 'oted RCferenCO Tab. B

12. Abstract of Corrective Measures Recommended and Taken Reference Tab. B We certify that the stattments made in this report are correct and the examinations and corrective mea-sures taken conform to the rules of the A$MI: Co e e on.\\1 C/gM,

,.Mt.

b?

/7 19 79 signed Edison Co.r.pany g3y Date SFafii~on" SuperFitendent

~

u Owner Certificate of Authoritation No. (if applicab!c)

N/A Expiration Date N/13 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National floard of Hoiler and Pressure Vessel Inspectors and/or the State or Province of Illinois and employcJ byTadCrd hm IDi10f of iia rtford, Conn.have insoccted the components described in this Owners' Data Report dunng the period

~9;2 8;7 8~-

to 10~-27-78

, and s: ate that to the best of my knowledge and belief, the Ow ner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of.ne ASA Code Section XI.

Ily signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Data Report F u r t h e rm ore, neither the inspector nor hn employer sha!! be liable in any manner for any personalinjury or property dam.ge or a loss of any kind arising from or connected with this inspection.

1. ' */ E ' 7 f 19 Date Commissions (([

/N f

Inspector' signa t ure National lloard, State. Provins e and No.

G

.e

Pagei Ct"'CNin ' H ?!0509 f.""' * :.Y ZIC!i G: LEAR ft B STAT:P, u!,n I RETOELPiG Om:E C';E : F.-IV IliiECICL WECTI.T; EWMT:3's 5?iWf.

s\\

INTRCDuri_'ma_ _ _

An intmice etadnatia' cf Class 1 and Class 2 ccernents and Dicirg, includir.9 in.e em:inat.icn cf ene reacter coolant :ur.o f'y-teel, ws cor, ducted at the ZION 597?0:i L:d7 i frcr. Senteder 28,197C, to Octtter 27, 1973.

The exaninc tier. were ::erf:.ed in eccordarr:e.ith 2n appre.ed Exminatien Prc. am, y

located ur.cer TAB C.

Examinatica prccedurer were ap?reved prier to the examinatiens, and certificction d:cumente relati,e t: eersoncei, equi; ent ar:d raterials here reviewed ar.:! detemined te be satisfactcry.

Inspectier.s, witnenir.c and surveillance of the exe.ninations and related actNities were can:'u:ted by ::ersonnel fr:r : The Hertford Steam Eoiler Inscec-tion ar.d Inte-er,ce Comany: Th:- LW ted Stitcs Nxletr Re2e:atory Ccriss.icn:

Zion Statien Ovality Assurance and Technical Etaff; and W: stir.; house M5D Cuality Assurance.

RESUL_T S -

E$ts.ir.atior:s resulted f r. a totEl of thirty-three recorcable indicaticas.

being noted on tre basis of pro:cdure recordirG crittric, which generally cre core criticD1 than specified AL"E Secticn XI Accc-annce standards. All of thes?

indicaticr.s were treated.=:nd disc 05itioned by DR (Discrepancy Record) cction and the dispositier:s have been satisfied.

A sumary of the indications is as folleE:

A.

(Eighteen) were for superficial surf ace concitionr. - eleven of J.ich were removed by light buf'ing cr.d Dien:iing with a fiaoper wheel during investi-gation, ardi seven of which were dispcsitioned as acceptable.

9

. n= a.- >

B.

(Eleven) were related to '.oase b01 tir.g on six ban;. r5 ond five crifice ihnces. ~he tralt$g was rc::rcued to recsirea vcl.es and where ap-ncs lochirg ruts arx! cr "kek-r.:nt* vas t.; sed to pren n: recurrence.

Additio7 ally, tSe pro;tr tcre..e 3s ver fied en t e remir. ire; iifteen orifice i

flan;es of t%> Oertincnt P.TD, RH't and Pressure Equalization lines.

)

C.

(Twe) of the ind!:3ti:ns are rehted to srubbers; c c w:th a oceleted reservoir arc cne w..ere the sn;;bber had been rmcvec for functional testine (co<e ed by separcte cr.g toi, havir.: only the ett:ch cnt to the lir.e. which prtryted the "recordaaie indic;tien". The sn m cr tas been reir.rulled.

The depleted reserv.3ir was due t; leJ. age past tr.e valve bcdj thres set'., which has teen rechced by e nw usi.

D.

(One)

'.r. icatica is f r "1;.ne snins" On cae of three surnort i:?.dc Of RC h o "C".

This cendition is caused by 19ral ctatracticn dur.rg transition ta cc'.d shutdown. Tir5tness of the shins were verified during the subsecuent hat.hutdenn ccr.cition duri.; the system leakege t':st.

E.

(Cne) snail (75" of O!C) accepteble rid wali indicaticn 1:as notec for weld CLT-1-4203-27 (weld 27 en Skett'. C;E-1-ta03, B" RF, cold leg).

This weld was fornerly identified as weld 29 en CKE-iS8 and has been monitored each refueling catage since occcatdie.r.id r.cil indicatiets were noted durin:

preservice e:a"atice.s.

Current monicorir,p of the p:v,icu:1y reca-ced indications ir.dicated no ac;reciable changes (other than not, Sove) and none that could be attributed to grcwth. All indications were evciuated as being well witnin the acccD*.2nce limits of IW3-3003 of AS':E Section XI.

Nrther investigatien of this weld (Ci,T-1-tJG3-27) by uhrasenics ard ID visual er racM;;reshic rete.c:s will be conducted during the next scheduled refueling outage to detemine final dis sition.

5:ecific data relative to the above indications are located under TA3 F of the outcge re?crt.

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A:ditienally two valve packing lens w:-re detected durine tte systen len test c:M.cted by Zion S' *ticn : s:r 21.

Or.e lenk w.! c:rrt:ted by tightening the ac6 f ng.f ant ').e et%r v5: : rrer'M ry cc-il.*g tSe packing ard tigM.cning.

ecific inicmation is lcceted under TA3 E cf tre

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cutage reprt.

EL'N UJ F.5 Exe:inatiens were conducted to revie,i is ra h cf the en-irition zcre as wn prac tical, within germtric, ret 01 :rt cd ana e.c-icd li~'.y.-ict.c.

i ilhen the v n: aired ultrcsonic enn1:etion vcire or t.rea cD,d r.rt be ev.a-3 ned 100.., the e).:r:instien was errsid2rs d to Oc nrtui (T VQ "e sn n:ta:..

Cener611y W.Us tre noted at fitti :g-to-fittir.g, esc'b'.ic: (S5 c:.?' air.ed ar. der 1.I"ITt'JICNS) and ir, e.reas 'etiere integrally weldM supp;rts,1 g; cr hangers, et c., e c:iur.e access to sc:.e part of the e.c.ination crti.

i)lt as;-ic encinaticns t% produced greater tnan reference level scnsi-tivity, fro, > eflecters that are characteristic d r.etsliurci:0 structure or the I.D. ar.d or 0.D. sur4ces of ar. f r were ccknadedged only. E arples of areas that generally prcduce such pecmetric inaicatier.s are es follcas:

(1)

I.C. welc prep or rect Inf - the crorn neri5y :;r tee.

(2)

The I.D. radius of tJ'e tube sheet cm the channel head to tute sheet ucid cf stcc gar.srct:rs, nen e.xc mir.c fr:e the tubesheet side.

( 2.)

The retailurgical structure of the cast. r,aterid s.

(4)

Fesponses from the threnc arers of bolting.

LIN T

• T I0':3 Sr.c of the arrarmements and details ce the pipir.; system and covenents were desiencd ard fabricated Wore the access and excmir+ tion recuirmencs of Section 7.I of the 1971 Ccde could be applied; car.seauently some examinations are linited er r.ct practical due to gecretric cordiguration or accessicMity.

Generally these limit. tion. exir,t at all fitting to fitting joints suto as eitc3r to tee, e%cw to valve, reducer to val.'e, etc., where geccetry and scactimes surface cencition prer.lude uitrasonic coupling or access for the required scan length.

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(*.e fitting cr cc;ooper,t cannot be ste-i fically quantified cc. 6t h; 15%.

Areas eere tewiete en~inati:r c' M cf tne regi.c. ci valtc.e cf area could not he achieved are indicate' b.r a FA? (ptriinT) not?. tion On the em.intri' Gt sheet, and the li ti:9; caste is r.oted.

The princbal basis fcr PATS is to ic'entify the f';:hility to exanine 100%

of the re.'airen bne et31. vol r.e for the 1 T distance beycnd the edge of the welo. on a :1: irg er cm x rcnt.

us a,s es t.re ( 3..

ui trascrn.c exc mmon o' a pipe to ei'w asseviy, where scanning on tnc intrades of the t'bn czuses de-cc@lir.; of Me round tern er.d (2) a pi e to anre er valve assembly, where scanr.ing the entire vele.e on the fitting or comper.ent side is lir.ited by confiprhfon.

The resul ting coverzga is such that examinatica cf the weld,' heat affected zone.rnd base retal for i "T" cr, tna pipe side cim be achievec by Scannir; frtm the pipe side of tne weld.

Ar. in.ie:er-irate covercoe of the base metal on the fitti77 cr cciponent side ray be scnieved durir.c this pipe side 1:can dependir.c on ne calibrated swcep Ten.th, atter.t. etic.n, joint configure-icn. etc.

However, the vehrce en the. fitting er comconent side acr.iti..nally carr.ot be

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scanned cc 4;etely for transverse indications as ret;uired by Ccde.

In either case.107.' of this 1 "T" volume cannn be assured, tr.us a PAR is required as a disclairrer to hl$ino satisfied cada requ rements, cibeit the intent is satisfied to the extert practical.

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COMMONWEALTH EDISON COMPANY ZION NUCLEAR POWER STATION UNIT #1 REFUELING OUTAGE III-IV INSERVICE INSPECTION All items listed below were examined, as indicated, in accordance with the requirements of the Plaat Technical Specification Section 4.2.1 and to the requirements of Section Xi of the ASME Boiler and Pressure Vessel Code, up to and including Summer,1975, Addenda to the extent practical with the access provided and the limitations of component geometry.

Program IWB-2600 Examination Sketch

_ Item Reference Area and Extent of Examination Procedure Reference U/T P/T V/T CWE Reactor Vessel 8

1-1300 1

Bl.2 Closure Head Meridional Weld #1. 47 Examine 5" to 6" from 0 refer-ence (adjacent weld 46).

8 1-1300 2

Bl.2 Closure Head Meridional Weld #2. 47 Examine 5" to 6" from 0 refer-ence.

(adjacent weld #6).

8 1-1300 3

Bl.2 Closure Head Meridional Weld #3. 47 Examine 5" to 6" from 0 refer-ence (adjacent weld #6).

8 1-1300 4

Bl.2 Closure Head Meridional Weld #4. 47 Examine 5" to 6" from 0 refer-ence(adjacentweld#6).

5' Bl.2 Closure head ring to disc weld 47 8

1-1300

1. 5.

Examine 0" to 7" CW from 0 reference (centerline of stud hole #19).

8 1-1300 6

Bl.3 Closure Head to flange weld #6. 47 Examine from 183.5" to 367" from 0 reference. (centerline of stud hole #19 to centerline of Stud hole #37.

8 1-1300 7

Bl.11 Conoseal Bolting.

Examine assembles at locations 74, 75, 76, 77 & 78.

k )k 87/88 1-1200 8

Bl.15 Reactor Vessel Internals (refer-ence separate program located under Tab 1.1 and ISI-88) 1

~

Program IWB-2600 Examination Sketch Item Reference Area and Extent of Examination Procedure Reference

()

U/T P/T V/T CWE Pressurizer 9

B2.ll Manway Bolting.

Examine bolts 8

1-2100 B5 thru B8.

Steam Generators 10 B3.1 Channel Head to tubesheet weld 47 8

1-3100 1-1.

Examine from 177" to 184" C.W. from 0 reference. (centerline of hotleg nanway).

11 B3.1 Channel head to tubesheet weld 47 8

1-3100 2-1.

Examine from 247" to 254" C.W. from 0 reference (center-line of hotleg manway).

12 B3.1 Channel head to tubesheet weld 47 8

1-3100 3-1.

Examine from 103" to 110" C.W. from 0 reference (center-line of hotleg manway).

13 B3.1 Channel head to tubesheet weld 47 8

1-3100 4-1.

Examine from 237" to 244" C.W. from 0 reference. (center-line of hotleg manway).

14 B3.3 Steam Generator #2 Nazzle to 205 11 8

1-4200 safe end welds.

Examine welds SDM and 6DM.

15.,

B3.10 Steam Generator #1 Manway Bolt-8 1-3100 ing.

Examine bolts 1-5 thru

~~

1-8 and 1-21 thru l-24.

16 B3.10 Steam Generator #2 Manway Bolt-8 1-3100 ing.

Examine bolts 2-5 thru 2-8 and 2-21 thru 2-24.

17 B3.10 Steam Generator #3 Manway 8

1-3100 Bolting.

Examine bolts 3-5 thru 3-8 and 3-21 thru 3-24.

18 B3.10 Steam Generator #4 Manway Bolt-8 1-3100 ing.

Examine bolts 4-5 thru 4-8 and 4-21 thru 4-24.

O s

Program IWB-2600 Examination Sketch Item Reference Area and Extent of Examination Procedure Reference U/T P/T V/T CWE Associated Auxiliary Piping 8

1-4101 19 B4.5 Loop #1 14" R.H.R. Take-Off.

205 Examine welds 16 and 17.

20 B4.5 Loop #1 8" R.H.R. Hot Leg.

205 8

1-4103 Examine welds 3,4,5,6,7 and 8.

21 B4.5 Loop. #2 R.C. Pipe.

Examine 205 11 8

1-4200 weld 7.

22 84.5 Loop #2 R.C. Pipe.

Examine 205 8

1-4200 welds 8 and 9.

23 B4.5 Loop #2 8" R.H.R. Cold Leg.

205 8

1-4203 Examine weld 27.

24 B4.5 Loop #3.

10" Accumulator S.I.S.205 8

1-4301 Examine welds 7,8,10,11 and 12.

8 1-4303 25 B4.5 Loop #3 8" R.H.R. Cold Leg.

205 Examine welds 7,8,9,10,11, 12 and 13.

26 B4.5 Loop #4 R.C. Pipe.

Examine 205 8

1-4400 weld 10.

27 B4.5 Loop #4 8" R.H.R. Hut Leg.

205 8

1-4402 Examine welds 3,4,5,6 and 7.

28 B4.5 6" Pressurizer Safety.

Examine 205 8

1-4502 welds 6 and 7.

29 B4.5 6" Pressurizer Safety.

205 8

1-4503 Examine welds 5 and 6.

Branch Connections 11 8

1-4205 30 B4.7 Loop #2 4"83" R.T.D. Return Examine weld 1(BC).

31 B4.7 Loop #2 2" Drain.

Examine 11 8

1-4212 weld 1(BC) 11 8

1-4410 32 B4.7 Loop #4 2" Drain.

Examine weld 1(BC) 0 9

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Program IWB-2600 Examination Sketch Item Reference Area and Extent of Examination Procedure Reference U/T P/T V/T CWE Socket Welds 33 B4.8 Loop #1 2" Drain.

Exanine 11 8

1-411 2 welds 25,26,27,28,29.30 and 31.

34 B4.8

. Loop #2 2" R.T.D. Take-Off Hot 11 8

1-4208 leg.

Examine welds 1,2,3,4,5, and 6.

35 B4.8 Loop #2 2" Fill.

Examine 11 8

1-4211 welds 2,3,4, and 5.

36 B4.8 Loop #2 2" Drain.

Examine 11 8

1 4212 wel ds 3,4,5,6,7,8,9,10,11,12, 13,16,17,18,19,20,21,24,25,26, 28,29,30,36 and 37.

37 B4.8 Loop #2 2" & 1 1/2" Seal In-11 8

1-4213 jection.

Examine welds 3,4,5,6,7, 8 and 9 38 B4.8 Loop #2 1 1/2" S.I.S. Bit ine.

11 8

1-4215 Examine welds 21,22,23,24,25,26, 27 and 28.

39 B4.8 Loop 82 1 1/2" S.I.S. Bit Line 11 8

1-4216 Examine welds 2,3,6,7,8,9,10 and 11.

40 B4.8 Loop #3 2" R.T.D. Take-Off 11 8

1-4307 Hot L eg.

Examine welds 9,10, 15,16,17 and 18.

41 B4.8 Loop #4 1 1/2" Pressure Equali-11 8

1-4412 zation.

Examine welds 28,29,30, 31,32,33,34 and 35.

Integrally Welded Supports (1) 42 B4.9 Loop #3 10" Accumulator S.I.S.

11 8

1-4301 Examine H6.

Supports and Hanaers 43 B4.10 Loop #1 2" Fill.

Examine Hl.

8 1-4111 44 B4.10 Loop #1 2" Drain.

Examine 8

1-4112 H6 thru H14.

ll 45 B4.10 Loop #2 10" Accumulator S.I.S.

8 1-4201 Examine H1 thru H6.

l0

Program IWB-2600 Examination Sketch Item Reference Area and Extent of Examination Procedure Refersnce O

U/T P/T V/T CWC Supports and Hangers (cont'd.)

46 B4.10 Loop #2 8" R.H.R. Cold Leg.

8 1-4203 Examine H1 thru H23.

47 B4.10

. Loop #2 3" CVCS Letdown.

8 1-4207 Examine H1 thru H19.

48 B4.10 Loop #2 2" Fill.

Examine Hl.

8 1-4211 49 B4.10 Loop 83 10" Accumulator S.I.S.

8 1-4301 Examine H1 thru H6.

50 B4.10 Loop #3 8" R.H.R. Cold Leg.

8 1-4303 Examine H1 thru H13.

51 B4.10 Loop #3 8" R.H.R. Cold Leg.

8 1-4304 Examine H1 thru H16.

52 B4.10 Loop #3.

2" Fill.

Examine 8

1-4310 H1 and H2.

O.

53 B4.10 Loop #3 1 1/2" S.I.S. Bit Line.

8 1-4314 Examine H1 thru H16.

54 B4.10 Loop #3 1 1/2" S.I.S. Bit 8

1-4315 Line.

Examine H1 thru H14.

55 B4.10 Loop #4 10" Accumulator S. I.S.

8 1-4401 Examine H1 thru H7.

56 B4.10 Loop #4 8" R.H.R. Hot Leg.

8 1-4402 Examine H1 thru H5.

57 B4.10 Loop #4 8" R.H.R. Cold Leg.

8 1-4403 Examine H1 thru H9.

58 B4.10 Loop #4 2" Fill.

Examine 8

1-4409 H1 and H2.

59 B4.10 Loop #4 2" Drain.

Examine 8

1-4410 H8 thru H16.

Pressure Retaining Boltino (Ref.1-4700) 60 B4.12 Loop #2 8" R.H.R. Cold Leg.

8 1-4203 Examine Flange #1-bolts 1 thru 12.

et

Program IWB-2600 Examination Sketch Item Reference Area and Extent of Exed nation Procedure Reference U/T P/T V/T CWE Pressure Retaininq Bolting (cont'd.) (Ref.1-4700) 61 B4.12 Loop #2 2" & 1 1/2" Seal In-8 1-4213 jection.

Examine Flange #1-bolts 1 thru 4.

Flange d2 -

bolts 1 thru 8.

62 B4.12 Loop #3 8" R.H.R. Cold Leg.

8 1-4304 Examine Flange di-bolts 1 thru 12.

8 1-4306 63 B4.12 Loop #3 4" & 3" R.T.D. Return.

Examine Flange #1-bolts 1 thru 8.

8 1-4307 64 B4.12 Loop #3 2" R.T.D. Take-Off Hot Leg.

Examine Flange #1-bolts 1 thru 8.

~

8 1-4308 65 B4.12 Loop #3 2" R.T.D. Take-Off Cold -

leg.

Examine Flange #1-bolts 1 thru 8.

h 8

1-4312 66 B4.12 Loop #3 2" & 1 1/2" Seal Injec- -

tion.

Examir.e Flange #1-bolts 1 thru 4.

Flange #2 - bolts 1 thru 8.

8 1-4313 67 B4.12 Loop #3 2" Pressure Equaliza-tion.

Examine Flange el-bolts 1 thru 4.

,6'8 B4.12 Loop #4 2" Pressure Equalization. -

8 1-4412 Examine Flange #1-bolts 1 thru 4.

Reactor Coolant Pump 1-5100 69 B5.1 Loop #2 Flange Boltina.

Exam-15 ine bolts 2-B1 thru 2-B24.

8 1-5100 70 B5.3 Loop #2 Flange Bolting.

Exam-ine bolts 2-B1 thru 2-824.

8 1-5100 71 B5.5

' Loop #2 Support Components.

Examine ?A, 28, and 2C.

m O

lb

Examination Sketch Program IWB-2600 Item Reference Area and Extent of Examination Procedure Reference U/T P/T V/T CWE Reactor Coolant Pumo (cont'd.)

8 1-5100 72 B5.9 Loop #2 Seal Housing Bolting.

Examine bolts 2-B1 thru 2-B12.

8 1-5100 73 B5.9 Loop #2 Flywheel.

41 Pressure Retainino Boltina 8

1-6100 74 B6.1 Loop #2 Loop Stop Valve 8001B 15 Examine bolts 1 thru 24.

8 1-6100 75 B6.1 Loop #2 Loop Stop Valve 8002B 15 Examine bolts 1 thru 24.

8 1-6100 76 86.1 Loop #2 Loop Stop Valve 8001C 15 Examine bolts 1 thru 24.

Valve Bonnet Bolting (Ref.1-6300) 8 1-4103 77 B6.9 Loop #1 8" R.H.R. Hot Leg.

Examine 16 bolts on Valves 8949A O

and 8736A.

8 1-4104 78 B6.9 Loop #1 8" R.H.R. Col d l eg.

Examine 16 bolts on Valve 90010.

79 B6.9 Loop #2 10" Accumule ;r S.I.S.

8 i-4201 Examine 16 bolts on Valve 8956B.

80 B6.9 Loop #2 8" R.H.R. Cold Leg.

8 1-4203 Examine 16 bolts on Valve 90028.

8 1-4207 81 B6.9 Loop #2 3" CVCS Letdown.

Examine 4 bolts on Valve 8085.

8 1-4301 82 B6.9 Loop #3 10" Accumulator S.I.S.

Examine 16 bolts on Valve 8956C.

8 1-4302 83 B6.9 Loop #3 8" R.H.R. Hot Leg.

Examine 16 bolts on Valves 89498 and

.8736B.

(

8 1-4303 84 B6.9 Loop #3 8" R.H.R. Cold Leg.

Examine 16 bolts on Valve 9001C.

O

/)

Program IWB-2600 Examination Sketch p

Item Reference Area and Extent of Examination Procedure Reference U/T P/T V/T CWE Valve Bonnet Bolting (cont'd.)

8 1-4401 85 B6.9 Loop #4 10" Accumulator S.I.S.

Examine 16 bolts on Valve 8956D.

8 1-4402 86 B6.9 Loop #4 8" R.H.R. Hot Leg.

Examine 16 bolts on Valve 8949C.

8 1-4a03 87 B6.9 Loop #4 8" R.H.R. Cold Leg.

Examine 16 bolts on Valves 9001 A and 9002A.

O O

i4

?

Program IWC-2600 Examination Sketch item Reference Area and Extent of Examination Procedure Reference Steam Generator 8

2-1100 88 C1.1 Stub barrel to tube sheet weld 47 1-2.

Examine from 120" to 129" C.W. from 0 Reference. (center-line of hotleg manway).

Volume Control Tank 8

2-1200 89 C1.1 Upper head to shell weld 1.

205 Examine from 0" to 6" C.W. from 0 reference. (centerline of man-way).

8 2-1200 90 C1.1 Lower head to shell weld 2.

205 Examine from 0" to 6" C.W.

from 0 reference. (centerline of manway).

11 8

2-1200 91 C1.3 Integrally welded support.

Examine WS-1.

2-1200 h

92 C1.4 Manway Bolting.

Examine 15 bolts B1 and B2.

8 2-1200 93 C1.4 Manway Bolting.

Examine bolts B1 thru B16.

Circumferential Butt Welds 8

2-2502 94 C2.1 14" & 12" R.H.R. Take-Off.

205 Examine welds 17,18,19,40, and 50.

8 2-2530' 95 C2.1 8" S.I.S. & CVCS System.

205 Examine welds 6,8,18 and 19.

8 2-2533 96 C2.1 6" CVCS Charging Pump suction 205 Examine welds 27 and 33.

(1) Done.r.s substitute to volumetric examination.

O If

l COMMONWEALTH EDIS0N COMPANY ZION UNIT #1 REACTOR VESSEL INTERNALS EXAMINATION PROGRAM REFUELING OUTAGE CORE III-IV Drive Rod Assembly Survey Prior to the Drive rod assemblies being unlatched from the RCC assemblies, an alignment check sha11 be performed in accordance with the requirements of Procedure ISI-87 Rev. O, dated December 31, 1975.

The location of any " bowed" assemblies, the approximate displacements and the direction of bowing shall be recorded on the core arrangement sketches of Appendixes A, B, C and D.

Reactor Vessel Internals The areas listed below shall be examined as required by the Plant technical Specification and to Section XI of the ASME Boiler and Pressure Vessel Code, up to and includino Summer,1975, Addenda, utilizing remotely operated under-water television systems in accordance with Procedure 151-88 Rev. O dated December 31, 1975.

Prerequisites s

(a) The Reactor Vessel upper internals assembly shall have been placed in the storage stand in the refueling canal.

(b) The three (3) drive rod assemblies noted as displaying the greatest displacement following the completion of the above survey shall be removed and placed in the storage racks on the side of the refueling canal.

(c).The core fuel assembly unloading sequence determined by Zion Unit #1

._ Refueling Procedure shall have been completed and the manipulator crane shall be available to provide access.

(d) The manipulator crane monorail hoist and polar crane shall be availa-ble to handle the T.V. fixture.

Examination The individual areas of the upper internals assembly, the lower internals the control rods, and the Reactor Vessel detailed in Appendix E shall be examined in accordance with Procedure 151-88 Rev, 0, dated December 31, 1975.

11

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