ML17199T448

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Inservice Insp Rept for 861128-870323.Reactor Pressure Vessel & Primary Sys Piping Inspected & Corrected
ML17199T448
Person / Time
Site: Dresden 
Issue date: 05/26/1987
From:
COMMONWEALTH EDISON CO.
To:
References
NUDOCS 8712010135
Download: ML17199T448 (49)
v • d • e


Text

-~

TABLE OF CONTENTS I.

Introduction II.

Scope of Inspection NIS-1 and NIS-2 Forms Table A (ISI Inspections)

Table B (Augmented Inspections)

III.

Summary of Results, Evaluations and Corrective Actions IV.

Attachments

1. - Abbreviations V.

Examinat.ions, Tests, Replacements and Repairs Since Preceding Summary Report -*~*

~

I N

I

I*

INTRODUCTION The tenth Inservice Inspection (ISI) of Dresden Unit 2 was performed during the Fall Refueling Outage, which lasted from November 28, 1986 to March 23, 1987.

This was the first inspection of the second third of the Unit's 2nd 10-year ISI Inspection interval which commenced on March 1, 1982.

General Electric Co. was contracted to perform the non-destructive ex-

.aminations during the refuel outage.

Personnel from Commonwealth Edison's System Materiai Analysis Department (SMAD) participated in the inspection to advise on technical problems; reviewed inspection personnel qualifi-cations; reviewed examination results; and evaluated certain indications.

The Authorized Nuclear Inservice Inspector's (ANII) services were pro-vided by Hartford Steam Boiler Inspection and Insurance Company (HSB).

The ANII reviewed prosedures, personnel qualifications, instruments and.*

ma_terial certifications,. and examination results.

Other personriel in-vol~ed with ISI were W.A. Pope, who performed the weld grinding and Per-formance Contracting, Inc., who c.arried out the necessary_ insulation removal and re-installation.

All the examinations were performed in accordance with,the Unit 2 Tech-nical Specification and the ASME Boiler and Pressure Vessel Code,Section XI, 1977 Edition through the 1979 S.ummer Addenda.

II.

SCOPE OF INSPECTION NIS-1 and NIS-2 Forms Table A {ISI Inspections)

Table B (Augmented Inspections)

II.

SCOPE OF INSPECTION The ISI examinations performed were identified per A~ME Code Section XI

.. Categories in the Tables contained in the following pages.

Augmented examinations are listed but not categorized according to the ASME Code.

The tabies reflect the components examined, the methods used, and the extent of the examinations.

The tables also show the results obtained.

Indications found at above the recordable Distance Amplitude C_orrection (DAC)* were recorded and evaluated, others were considered non-recordable indications.

Speci~l tests performed include:

a.

Primary System 1131 psi Hydrostatic Test SP-87-3-48

b.

Standby Liquid Control Hydrostatic Test DOSll00-3, Rev. 9 Attachment IV should answer any questions on abbreviations used throughout this r.eport

  • FoA1 OWNER'S REPORT FOR INSERVICE.ECTIONS As required by the Provisions of the ASME Code Rules COMMONWEALTH EDISON COMPANY -

ONE FIRST NATIONAL PLAZA,

1. Owner ___

P_.O_._B_O_X_7_6_7----'-,_C_H_I_C_A~G_O~,~I~L_L_I_N_O~I~S_6_0_6~9_0~--~--~-------

(Name and Address of Owner) 2 Pl DRESDEN NUCL_ EAR POWER STATION, R.R. 1fl, MORRIS, ILLINOIS 60450 ant _________ '--_________.:._ _____ :._ ___ _:_ _________ _

(Name and Address of Plant)

3. Plant Unit ____

2 _____ 4: Owner Certificate of Authorization (if required) __

N__.:_/ A--'-----

5. Commercial Service Date 6/9/72
6. National Board Number for Unit ---=N.:....--'l=-3=-=-7 _______ _
7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No.

Province No.

Board No.

CLASS 1 & 2 BABCOCK & WILCOX co..

SYSTEMS BARBERTON, OHIO 610-0098 B0082800 N-137

\\

~

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (I) size is 8Yi in. x 11 in.,

(2) information in items 1 through 6 on this 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.

(12/82)

This Form (E00029) may be obtained from the Order\\o-elt.* ASME, 345 E. 47th St., New York, N.Y. 1001_7

\\j.

FORM NIS-1 (Back)

8. Examination Daces 11/28/86 co, 3/2-3/87
9. Inspection 1_9-terval from 3I1I82 co ' 3I1I9 2
10. Abstracc __ of Examinations. Include a *list of examinations and a statement concerning status of work required for current interval.

SEE ATTACHED TABLES

11. Abstract of Conditions Noted SEE SECTION III

... 12. Abstract of Corrective Measures Recommended and Taken SEE SECTION III We certify that the statements made in this report are correct and the examinations and corrective mea-

, sures taken conform to the rules of the ASME Code,Section XI.

... Certificate of Authorization No. (if applicable) __

N~/_A _____ Expir~tion Date __

N~/_A ______ _

Date ~-A

...... f~K~~~i =L. __

2_2-__ 19.. S7 Sigried _aJ~~-*

w er

/

By------------

CERTIFICATE OF INSERVICE INSPECTION I, :the undersigned, holding a valid commission ~sued* by the National Board of Boiler and Pres.sure Vessel Inspectors and the State or Province of** Illinois

  • and employed by Hartford Steam Boiler of Harc':i:ord. Cc,-nnecticut have inspected the compon~nts de.scribed in.this Owner's Report during the period 11/28/86 to..

3(23/87 -* - "*,and state that to the best ofmy knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirement.s of the ASME Code,Section XI.

J3y signing this certificate neither the Inspector nor his employer makes any *warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

--~-'-\\

-=~--=-.',6=-\\-'--'-l O::;_t~Q._,=--* _*.-- Commissions ----=-"\\.?~Ri~* __,.<M,_,_Q, \\'--""~"--+-",*---='I'-::--°* L---'-1 ?,_\\-'-J_---'----

Inspector's Signature National Board, State, Province, ~nd Endorsements Date _

__,J._\\A-'-'-'-~-'--"t,,=-c..* -~-'---'--~ 19 'b \\

(12/82)

  • , :~

FORM NIS-1 (Back)

8. Exaniination Dates 11/28/86 to 3/23/87
9. lnsp~ction Interval from J/i/82 co 3/i/92.
10. Abstract of Ex~inati~ns. Include a iist of examin~tions a~d ~- st~tement con~erning status of w~rk required.**
  • .for current interval.

SEE ATTACHED TABLES

11. Abstract of Conditions Noted SEE SECTION III
12. Abstract of Corrective Measures Recommended and Taken SEE SECTION III We certify that the statements made in this report are correct and the examinations and ~orrective mea-sures taken conform to the rules of the ASME Code,Section XI.

Certificate of Authorization No.. ( if applicable) ___

N-'-/_A_* _____ Expiration Date_. __ N~/_A_~-----

Date __

  • .....,A......

f~K~i~L-'--_2_2-__ 19 S7 SignedZl}~~-.

,Ow er

\\.

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a ~alid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by Hartford Steam Boiler of Hartford. Connecticut -have inspected the components described in this Owner's Report during the period 11I28 I 86

. to 3I23187

, and state that to the best qf my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied,.

concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss o( any kin_d arising from or connected with this inspection.

_* ~--

___,,_\\ _;::_~_'{,=-\\..:_.:..l o::;_bl--'tt.=--_* -- Commissions ~'-'~fk=--->Q,Q,~1~~'--+--

I --"'I'-::"'\\....--'-\\ "3;__1 ____:.4-___

Inspector's Signature National Board, State, Province, and Endorsements Date -~J~\\A~~~t,=*-~~-- 19 lb\\

(12/82).. -.-:

FORM HIS-2.0WNE~'l ~E?ORT OF ~EitAIR OA RE?UC~MENT A. R 1tqUi'9d by U\\e hoYitlonl of.iUM E ~

s.ctton XI o.-.r Commonwealth Edison Co. (C!Co)

  • Rt. #1 Morda, IL

,_..... 60450 06/01/87

....... -----~-----------

Sll':_t------ Of ______

2 Unn---------------------

W.R. f D59107

3.

Work Ptrfonned bv.. --:--~---e-r ________ _

Same

~'

°"?'l&ZallOtl P.O No.. JoO ~

.* etc.

l.

~,

ldentlflc:stfon of Svmm---=.l.:::2..;;;0..;;;0---:(..:;.R:..:.W~C:..;;U:...) ___

(*l ~licatllt c.:instrvetton CootB3 l. 1 19 6 7 Edition.

No Adden~. Code Caet _N_o-.n-.e~-

. lbl ~ficabl* Edition o1 Section XI UtJliud for R1P1in or Repfacemenu - 19.ll, S-

  • 79 Addenm. Cod* en.s _Nu.w.o.un,,.e __

ldtntifiatlon of Come>0ntnt1 RIC)airwd or Repl.ad, and RllC)l1e11ment C:lmponents

6.

~of Name of Mfn. S.r.

Nat1.

C!='N Other v..,

Repairei ASME Code

~nt Mfr.

~-

Bd.

No.

ldtnti-Built Repl.:ed.

Stamped No.

fication

. or IYGS 0t Nol Repl1eament

  • IS If/:

N/A N/A N/A N/A EPN

  • 67 Repair NO 8-12 I

N/A I

I I

7.

Oescription of Work ____ __; _______________________ _.... ____

~--.,...

a Tau Conductod:

Hydrostatic IXJ Pneumatic 0 Nominal OP.eratinQ Preuurt 0. Other []I hnsurt psi Ten. TtmQ.-* F

9.

RtmMlts Pene!:raht examine final weld surface per NDT-D iAOO'oc:aoi. "'-1ae1\\#WI c:.tJI ~to Ile~

c::i=lT1F3C~TE OF CCMPllANC::

'Ne artify tnn' me SUtltments ma in this* noon a.;ornct :ind ttlil ___

R_e_o_a_i_r ______ conforms to s.cnon XI ot ttic ASME C;)Qe.

,_°'~

/ ' ' ' ~,)1.',,,:,.

~*/VU.,.._.;~I '....J*. I, ~u

.. fl.-

p.n.r OllO.W-ll ~

,.,-,,;,,,,7..S:.il..'1!. '

Tltl8 C~rlTlF!C~TE OF INSPECTION P7

,19---

I. ttie undeniQntd. holdii-.q 1 vaJid commission is:lued by the N1tJONi Board at Soillf' and Pressuni Vessel ln~ori x1d tlle State Ill.

Hartford Steam Boiler*

°' i'rovinc:e of ino is

. lmQ4oved bv*-------------------_,,_ __ __.. ot Connect i cut

~

insoec:ud the Repair dtscribed In this Repor:t on _____ _..(*_._'-'2. __. __, 1 s ~"

~<<~

~

Jt.1lt9 that to the best at my !l:nowtedQe and b8iief, thll ropaii*or ~laament hm been c:onstrvc:Ud In iaccordana with Section XI at

~

.lSME <:.:>oe. Sy sicJni119 ltiia atrtif°ICllt9, nelths ~

Inspector nar hit emc:Moyer mabs ony wamintv, axPl"ftl9Ci °' implied, concsirn-inq th* ~ir or reolac*"*'t daaibed In this A~

Fur'Ulermcn, neitn.r tht ll\\lpee1<< nor his ami>4over wll be liable in rrv m1riner

~

Vty ~nai :injury Of PfOQerty dlmagi;;,, a*ksa of any kind arisltMJ from OI =)nnecud with thll in1P9Ctlon.

eam fi:' 1 :~,, ~1 1* r~?_: IO-n2.*

~iaiom __

1_i_;_\\_r),--\\ a._*-----....,------

!Sal*°'~ HclQtW 5a.tll

3u00f*menui lh-U In form of lln
a. Mt..a:n.. << drewln91 m.y lie u.-d provided (1) tlz* i. i~ In. X 11 In.,

informe'tlon (n 1'8m* 1 uiniu~ ' on tnis d1a reoon Is Included on -.en llleet. and 131 *edl.n.. t It numbend

.n4 ~* m.imtier of ltl*t:I la MICoraed ft ltle UM) of tf\\is form.

FOAM NIS-2 OWNER'S RE~RT OF RE?AIR OA REPLAC~MENT

~ Required ?1v 1ht Prowitlonl of AWE C4de Secfton XI e~--------------------------

,.._ __ Commonwealth Edison Co. (C!Co) 06/01/87 i

C.U~~--~~~~~~--~~~~-

R t: #1 Morris, IL

,,.._ 60450

1.

~:':' Station 2

Sh~~~~~~-0'~~~~~~~

2.,,.,,t Dresden Nuclear Unit Same (Nlrftel
3.

Work lttrlormed by

~

W.R. 11 D59105 Same (PMfnel "9o&Jr OrganlQllOft P.0 No.. JOO NO.. llC.

IACllCnNI ldantlflc:stlon of System 200 and 12 00 (Rec ire and RWCU) 5..

(*J Apc>licatlle ConstNC'tlon Code BJ l

  • 1 19 6 I Edition, No Addtndt, Code C...

None (bJ ~licabl* Edition of Section XI Utlllied for R~in °' Rlpqcomenu-1912, S-

  • 79 Addtndli, Code Cnet.

Ngne I.

ldentlf~tlon of CQmoonents Reoai...ci or Reol8C9d. and R iolecement ~nenu

~of N*m* of Mfra.. Ser.

N.i'I.

C.~N Other v.. r RtQii~

ASME Code

~nt Mfr.

No.

Bet No.

ldenti-Built A.Pieced.

Stamped No.

fication or (Yes or Nol c)~p *1 Repl1e9ment

, w1rsr WELD==I N/A N/A N/A N/A EPN 1967 Repair NO I~~.

I

.J1'-.

DB I

PDu-D23 PD7-Dll I

Pnlq-Dl4

-Kl3

7.

OescriptionofWork Overlay build-up to allow inspection by.U.T.

a Tests C.,~cild:

Hydtomtic IZJ Pneumatic 0 Nominal 0.P.MatinQ Pressu,. 0 Other !3J Prnsurw psi Tat T1m4>._ *F

9.

Rln\\M'ks P"ene'"rant examine final surface of overlav oer NDT-D i-'OQllQD!e W-ractwWI oat.~

IO Ile~

c::11T1FiCAiE OF C::MP!..IANC:::

c::::tT1F!C~TE OF lNSP~C,.ICN

  • 19.r.:... 7 I

I I. ttl* undeniqned. holdinq a valid commiuion issued by ttie NatJON!I '3oard at Soillt' Jnd Pressuni Vessel lnsoec~on and tl'le Sta~

01 !'rovinc9 of I 11 in o is Hartford Steam Boiler

,lfTl~Oyedbv--~~-~--~~~-~~~~~~-~~~~ot Connect i cut h-inlPCUd ttle--=-R_e_p_a_i_r-=----~:- ~bed In this S9')0rt on

(* I:.;_

  • 19 'c,*;

~l<<Aeol----

=----

and suu tti.i to t:M best at my knowiedQt and belief, this reoair or rwipl-=-ment ha b9en constn1ct9d In 11c:cordanc8 with Sectlon XI of tne ASME C-'dll. 9y siQni119 ttiil Cllf1ff"tean, nei~ the lnsoecwr*nar hit omQloyer maims any wernntv, IXP1'9119C1 °' ~iec;j, conairn-inq the ~Ir or !"90.l<<*ment described In di is Repon. ~urth wrmon. neither.the lrupecuw nor hit ~aver INll tie I iabl* i.n any manner

~

lf'Y ~~.~n~~rv or~

dam*agr at: j~

1'ot any kind arisl119 from rx connecua ~ttl ttll1 -~C)tetlon.

o.u t/J * :.>

~ * '

( h \\/??, \\,c;. ~'-

(:.)mmlaiom

.l L

\\ ::. I.:i,

~

---;;;....;;;~ISUx-:---.-or~Pl'tl~~--uoce.-Nc~ow-~&o.~rat-~-~-

Suoe>1emenU1 11'1.U in form o'f llns..a.u:na. M dr*wln~ may be ueea :;wovid9d (11tlZ*11 J~ In. X 11 In.,

(:Zl lftt~on 111 lt11m* 1 ~rou~ ' on ttils aaa r9POn It lncludea on ucn ltlwt, llld (:JI oadl sheet II n1.1moer.cs ano "'* n\\lmoer of sn*a Is recorded n ~

tOP of 1'111 form.

FORM NIS*2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provi1ion1 of ASME Code Section XI

-=-==============-

1.

Owner Common we a 1th Edi son Co. ( CECo)

Rt. ill Morris, IL (Nwnel

  • 60450 Oate __

M_a_,r.-c_h_2_0_, __

1_9_8_7.....-___ _

1 I

.JAOdrnal S Sh~------- of-------~

Unit ___

2-------------------~

2.

Ptant _._D~r""'e'"'s""d""-"e_.n.._N_u_c_l_e_a_r __

P_o_w_e_r __ t_a_t_1_o_n_

Same (N.me1

...!Address I

3.

Work Performed by ___

uwn e_r _________ _

63196 Same (Name)

R*pairOrgan1za1lon P.O No.* Job No.* 11c.

4.
5.

Identification of System Core <g;'.;i:~ 2-1403-12"-DX "fJ4fl" ~

1 lal Applicable Constn.iction Code BJl. 1. 0 19 67

  • Edition, None ".5--

Addenda. Code Cases _'""N...;:o_n..._e--__

lbl Applicable Edition of Section XI Utilized for Repairs or Replacements - 19ll, 4'" 7 9 Addenda, Code Cases_* ~N.... o.,D..._e,._ __

6.

Identification of Comp0nents Repaired or Replaced, and Replacement Comp0nents Name of Name of Mfrs. Ser.

Net'I.

CAN Other Year

Repaired, ASME Code Component Mfr; No.

Bd.

No.

ldenti*

Built

Replaced, Stamped No..

fication or (Yes or Nol I

Replacement Branch N/A N/A N/A N/A EPN NIA Repair NO contcn_ctiof1 Sa d e I

2-1403

-12"DX

7.
8.

Description of Work--.A~d~d"-"e_d_R_e_i_n_f_o_r_c_e_m_e_n_t_S_a_d_d_l_e_t_o_L_i_n_e __________________ _

Tests Conducted:

Hydrostatic 0 Pneumatic 0. Nomjnal 0.P.erating Pressure 0 Other !3l NDT-31 Rev. 6 (MT)

Pressure N/A psi Test Tamp. NtA °F 1 1 R 2 (v***

1)

Remarks __

H~y_d_r_o __

n_o_t_r_e~q~u_1_r_e_a_. __

R_e_p_a_1_r_d_o_e_s~n_o_t __

P_e_n_e_t_r_a_t_e _______ v_T_-__ e_v_._* _. __

i.sua

9.

(Ap~1cao1e Manutaclurer's Data A~s to De attacned)

Pressure boundarv CERTIFICATE OF COMPLIANCE 1

Rebair We cenify that the natemenu made in this rapon are correct and this _____________ conforms to Section XI of the ASME Code.

(l'IQairor.-.ptacement) f'2 **'1 *

  • (-:-}:

/U *

  • IJ_. -

STKilDAJ,.,;1ion. SvNit..

~

.3

  • 19 87 Signe~::;.;.*~/-'/~~.:.::..-~-J-.,--------=~------,,,--~

(Owner or Owner's Oesioneet

  • n111

(~*I

. CERTIF.ICATE OF INSPECTION I. the undersigned. holding a valid, commission issued by the National Board of Boiler and Pressure Vessel lnspecton and the State Ill.

Hartford Steam Boiler or Province of inois

  • employed bv--------------------------of Connecticut haveinspoc:tedthe Repair describedlnthlsReponon J-3*'t>~

"'1t (Repai11s1 or R1placement(111 and nate that to the best of my; knowledge and belief, this repair or r9plec:ement has been constructed In accordance with Section XI of the ASME Code. Sy signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or impii11d. concern*

ing*the repair or replacement described In this Report. Funhermore. neither the Inspector.nor his employer shall be liable in any manner for any *::so~l injury or proPttty ~

Q{ a f9ss o( anv kind arising from o~ connected ~th this lnsperfon.

Data l '3 <(QI

~Q,

~ \\ 0 J:: Q..;

Comm1ss1ons

- L

\\ "3 I~

OM!>8C10f'I

(S~ra-te_or_Pnm...__nca_. N&-,-lon.i--Bo.-n!l ____

tm: Suppl*m*nul sheen In form of llsu. akeu:h*. or *drawln111 may bl und provided ( 1) size Is Slii In. X 11 In.,

(2) lnformHlon In lt9m* 1 tnrou~ 4 on tnls datm rec>o" *Is lnclud.a on*eacn sh*t, and (3) eacn ah11t 11 numbered and ttie nui;nt>er of 1n*t1 11 recorded 11t tto* toP. of ttol1 form. V :!r:UIVJ; SNOIJ..3.HdSNI ISI

)

ASME f!ATEf;ORY B-A B-D COMPONENT JJHESDEN NUCL&\\R POWER STATION DECEMBER 1986.*

MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION Rx Head Merid.

CS/RB UT Seam :/15 Rx Head Circum.

CS/RB UT Seam :/IC Rx Head Flange CS/RB UT/MT Seam :/Fe Rx Vessel Long CS/RB UT Seam tfc & D" Rx Vessel Flange CS/RB UT Seam tfc Rec ire Nozzle Nll CS/DW 28" UT

.IR Rec ire Nozzle N2(

CS/DW 12" UT IR Rec ire Nozzle N2I CS/DW 12" UT IR Rec ire Nozzle Nll CS/DH 28" UT VES-NOZ.

Recirc Nozzle N2<

CS/DW 12" UT NOZ-VES Rec ire Nozzle N2I*

CS/DW 12" UT NOZ-VES UNIT HO. 21 STATE NO. B0082800. *

~I INSERVICE INSPECTION INDICA'fION SCAN PERCENT RESULTS NUMBER TYPE DAC EVALUATION NRI NRI NRI NRI e

NRI NRI NRI NRI NRI NRI e

NRI I

ASME CATEGORY B-D B-E COMPONENT JJHEsDEH NUCLEAR POWER STATION DECEMBER 1986 MATERIAL/LOCATION MEITHOD F.XTENT OF EXAMINATION RPV Head Nl8A CS/RB 6" UT IR RPV Head Nl8B CS/RB 6" UT IR RPV Head Nl8A GS/RB 6" UT NOZ-VES RPV Head Nl8B CS/RB 6" UT NOZ-VES CRD PEN 4" DW VT-2 10-51 18-51 51 26-51 30-51 34-51 38-51 42-51 Inst. PEN 2" DW VT-2 9-48 9-40 9-32 INDICA'fiON NUMBER

- UNIT HO. 21 STATE NO. B0082800 INS ERV ICE INSPECTION.

SCAN PERCENT RESULTS TYPE DAO EVALUATION Non-relevant indications due to localized gouges top head from 3000 - 600 NRI NRI NRI No leaks No leaks No leaks No leaks No leaks No leaks No leaks No leaks No leaks No leaks No leaks observed on OD of*

e e

ASViE 8A 1'Ef;ORY B-F B-G-1 UHESDEH NUCLEAR POWER STATION DECEMBER 1986 COMPONENT MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION Recirc Nozzle NlB CS-SS/DW 28" PT/UT NOZ-SE Recirc Nozzle N2C CS-SS/DW 12" PT/UT SE-NOZ Recirc Nozzle N2F CS-SS/DH 12" PT/UT SE-NOZ RPV Hd. Vent N8 CS-SS/RB 4 II PT-UT NOZ-SE RPV Head Nl8A CS-SS/RB 6" PT/UT SE-NOZ RPV Head Nl8B CS-SS/RB 6" PT/UT SE-NOZ Core Spray 2-1403-10 W-3 SS/DW 10" PT/UT P-P 2-1403-10 W-2 SS/DW 10" PT/UT P-VLV 2-1403-10 H-5 SS/DH 10" PT/UT VLV-EL Rx Vessel Threads in Flange CS/RB UT 46 Ligaments 7 II Down OD 0°-1800 Closure Washer CS/RB VT-1.

184 Washers

- INDICATION NUMBER t

1 1

1

-1.4-UNIT NO. 2J STATE NO. 00082800 INSERVICE INSPECTION

  • SCAN PEHCENT RESULTS TYPE DAC EVALUATION NRI NRI NRI NRI 2'

158 ID Root Geometry 360° 2

100 ID Root Geometry 360°

'./

e 2

70

.Intermittent Redirected Root 360° 3

100 Counterbore Intermittent 360° NRI e

NRI NRI

~

ASME

_CATEGORY B-G-2 2" Dia.

~ Smaller lJHESDEH NUCLF.AR POWER STAT;I:ON DECEMBER 1986 COMPONENT MATERIAL/LOCATION MEI'HOD EXTENT OF EXAMINATION 2"

I Rei ere Line 202B VT-1 Bolting Diameter MO 2-0202-4B DW and $mall er Recirc Line 201B VT-1 Bolting MO 2-0202-SB DW Rec ire Line 20313 VT-1 Bolting MO 2-0202-7B DW Recirc* Line 202B VT-1 Bolting 3" Blind Flange DW Rec ire Line 203B VT-1 Bolting 3" Blind Flange DW SDC Line 1001B 6" Blind Flange DW VT...:l Bolting SDC Line 1001A 2 II Blind Flange DW VT-1 Bolting CRD Line 0308 2-0301-98 DW VT-1 Bolting SDC Line 1001A MO 2-1001-lA DW VT-1 Bolting SDC Line lOOlB MO 2-1001-lB DW

.VT-1 Bolting RWCU Line 1201 MO 2-1201-2 RB VT-1 Bolting INDICATION*

  • .NUMBER UNIT NG~. 2; STATE NO. B0082800 INSERVICE INSPECTION SCAN PERCENT RESULTS TYPE DAC EVALUATION No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities r -

e e

ASME CATEr;ORY B-G-2 (Cont'd) 2" dia.

COMPONENT

.lJHESDE11 NUCLEAR POWER STATION DECEMBER 1986 MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION Iso Corid. Line 1302 MO 2-1301-2 RB VT-1 Bolting Core Spray Line 1403 2-1402-6A DW VT-1 Bolting,

Core Spray Line 1404 2-1402-6B DW VT-1 Bolting LPCI Line 1506 MO 2-1501-22A RB VT-1 Bolting HPCI Line* 2305 MO 2-2301-5 RB VT-1 '*

Bolting Na in Stm Ln 3001A AO 2-203-2A DW VT-1 Bolting Main Stm Ln 3001B AO 2-203-2B DW VT-1 Bolting Main Stm.Ln 3001C AO 2-203-2C DW VT-1 Bolting Na in Stm Ln 3001D AO 2-203-2D DW VT-1 Bolting Fd Wtr Ln 3204B 2-220-57B DW VT-1 Bolt.ing INDICATION NUMBER

-16,..

UNIT NO. 21 STATE NO. B0082800 INSERVICE INSPECTION SCAN PERCENT RESULTS TYPE DAO EVALUATION.

No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities No Abnormalities

{

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ASME CATEf;ORY B-G-2 (Cont'd) 2 II Dia.

1JHE3DEN NUCLEAR POWER STATION DECEMBER 1986 COMPONENT MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION Main Stm Ln 3001A SV-2-203-4A DW VT-1 Bolting Main Stm Ln 3001B SV-2-203-4D DW VT-1 Bolting Main Stm Ln 3001C SV-2-203-4F i:>W VT-1 Bolting Main Stm Ln 3001D SV-2-203-4H DW VT-1 Bolting CRD Flange 14-15 VT-1 Boltin.g

. *~....

14-19 II II 14-27 II II 14-31 II II 14-35 II II 14-43 II II 14-47 II 14-51 II II 22-15 II II 22-19 II II 22-23 II II 22-27 II II 22-31 II II 22-35 II II 22-39 II II INDICATION NUMBER UNIT NO. 2; STATE NO. B0082800 INSERVICE.INSPECTION SCAN PERCENT RESULTS TYPE DAC EVALUATION No Abnormalities No Abnormalities No Abnormaliti.es No Abnormalities No Abnormalities II II II II II II II II II II II II II II II II II II II II II II II II II II II II T*

t;,

J -

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ASME CATEGORY B-G-2 (CONT'D) 2 II DIA.

~ Smaller

.B-H JJHI!SDEN NUCLEAR POWER STATION DECEMBER 1986 COMPONENT MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION 1

CRD Flange 22-43 VT-1 Bolting DW 22-:-47 II II 22-51 II II 22-55 II II 30-15 II II 30-19 II II 30-23 II II 30-27 II II 30-35 II II 30-39 II II 30-43 II II 30-47 II II 30-51 II II 30-55 II II 54-15 II II 54-23 II II 54-31 II II 54-39 II II 54-47 II II Rx Head Lug @ 1800 CS/RB MT Top Head Lift Lug Rx Vessel Lug @

180° CS/RB MT

.Vessel Lug Rx Vessel Support Skirt 0-1800 MT Weld oo to 180° INDICATION NUMBER.'

UNIT NO. 2; STATE NO *.B0082800

. INSERVICE INSPECTION SCAN PEHCENT RESULTS TYPE DAC EVALUATION No Abnormalities

    • II II II II II II II II II

. II II II II II II II II II II II II II II II II II II II II II II II II II II II NRI NRI NRI r.: *

  • I; e

e

l ASME

'::!ATE[; ORY B-J

  • IJHESDEH NUCLEAR POWER STATION DECEMBER 1986 COMPONENT MATERIAL/LOCATION METHOD EXTENT OF EXAMINAT.ION SDC Line 1001A CS/DW 16" MT/UT Weld 16-K8 P-EL SDC Line lOOlA CS/DW 16" MT/UT Weld 16-K7 EL-P SDC Line 1001A CS/RB 14" MT/UT Weld 14-K3 EL-P SDC Line lOOlB CS/D\\y 6 11 MT/UT Weld 6-K9 P-FLG SDC Line 1001B CS/RB 16" MT/UT Welq.16-2A EL-EL SDC Line lOOlB CS/RB 16" MT/UT Weld 16-2B EL-P INDICAT10N NUMBER 1

1 2

1 2

3 1

2 1

2 3

4

-19.:

UNIT NO. 2; STATE NO. B0082800

. -INSERVICE INSPECTION SCAN PERCENT RESULTS TYPE DAC EVALUATION 3

75 360° OD Crown Geometry 3

100 360° ID Geometry 2

  • 75 360° ID Geometry 2

100 360° ID Geometry 3

50 360° ID Geometry 3

50 360° ID Geometry NRI 2

75 360° OD Geome*try 3

100 360° OD Geometry 3

100 360° ID Geometry 3

50 360° OD Geometry 2

75 360° ID Geometry 2

100 360° OD Geometry f'J e

~

r. -

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ASHE CATffiORY B-J (CONT'D)

DHESDEH NUCLEAR POWER STATION DECEl'*lDER 1986 COMPONENT MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION SDC Line lOOlB CS/RB 16" MT/UT Weld 16-K2 EL-P SDC Line lOOlB CS/RB 16" MT/UT Weld 16-3 EL-EL SDC Lin*e 1001B CS/RB 14" MT/UT Weld 14-K4 P-EL Main Stm Ln 3001A CS/DW 20" MT/UT Weld 20-3 P-EL Main Stm Ln 3001A CS/DW 20" MT/.UT Weld 20-K6 EL-P INDICA'fION NUMBER 1

2*

1 2

1 2

3 1

2 1

2 UNIT NO, 2; STATE NO. B0082800 INSERVICE INSPECTION.

SCAN PERCENT RESULTS TYPE DAC EVALUATION 3

75 360° *ID Geometry 3

50 360° OD Geometry 2

100 360° ID Geometry 3

100 360° ID Geometry 2

100 360° ID Geometry 2

75 360° ID Geometry 3

75 360° ID Geometry 2

60 360° ID Root Geometry 2

100 360° OD Crown Geometry 2

100 360° ID Root Geometry 3

100 360° ID Root Geometry

- *c.

/

e e

ASME*

CATEr:onY B-J (CONT'D) lJHESDEH NUCLEAR POWER STATION DECEMBETI 1986 COJiiPONENT MATEnIAL/LOCATION METHOD EXTENT OF EXAMINATION Main Stm Ln 3001A CS/DW 20" MT/UT Weld 20-K2 EL-P Feedwater Line 3204B CS/DW 18" MT/UT Weld 18-Kl EL-P SDC Line lOOlB CS/RB 16" MT/UT Weld 16-2 PEN-EL RWCU Line 1202 SS/RB 8" PT/UT Weld 8-1-A P-VLV RWCU Line 1201 SS/RB 8" PT/UT Weld 8-6-A P-VLV RWCU Line 1201 SS/DW 8" PT/UT Weld 8-20-A VLV-EL INDICAT10N NUMBER 1

2 3

4 1

2 3

4 1

2 1

1 UNIT NO. 2; STATE NO. 00082800 INSERVICE INSPECTION SCAN PERCENT RESULTS TYPE DAC EVALUATION 2.

50.

360° Counterbore Geometry.

2 125 360° ID Root Geometry 3

50 360° OD Geometry 2

100 360° OD,Crown Geometry 3

100 360° ID Root Geometry 3

100 360° OD Geometry 2

100 360° OD Geometry 2

50 360° ID Root Geometry 2

100 360° OD Geometry 2

100 360° ID Geometry 3

50 360° OD Geometry 3

50 360° OD Geometry NRI

\\

. ~*

~

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e

ASME CATEr;ony B-J (CONT'D)

COMPONENT lJHESDEN NUCLEAR POWER STATION DECEMBER 1986 MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION Main Stm Ln 3001B CS/DW 20" MT/UT

\\-Je ld 20-3 P-:EL Main Stm Ln 3001B CS/DW 20" MT/UT Weld 20-KSA EL-P Hain Stm Ln 3001B CS/DW 20" HT/UT Weld 20-K2 : EL-P Main Stm Ln 3001B CS/DW 20" MT/UT Weld 20-Kl P-EL Feedwater Line 3204A CS/DW 18" MT/UT

  • weld 18-Kl P-EL INDICA'fiON NUMBER 1

2

. 1.

2 3

4 1

2 3

4 1

2

'3 4

s UNIT NO. 2; STATE NO. 00082800 INSERVICE INSPECTION SCAN PERCENT RESULTS TYPE DAC EVALUATION 2

'. lSO 360° ID Geometry 3

6S 360° OD Crown Geometry NRI 2

200 360° OD Crown Geometry 3

so 360° Counterbore Geometry 3

12S 360° OD Crown Geometry 2

200 360° ID Root Geometry 3

200 360° OD Crown Geometry 2

60 360° OD Crown Geometry 3

50 360° Counter Bore Geometry 2

60 360° Counter Bore Geometry

.2 7S 360° ID Root Geometry 2

so 360° Counterbore Geometry 2

1.00 360° OD Geometry 3

so 360° Root Geometry 3

100 360° OD Geometry

., I

~

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ASME CATEr.:ORY B-J (CONT'D)

B-K-1 DHESDEH llUCLEAR POWER STATION DECEMBER 1986 COMPONENT MATERIAL/LOCATION H8Tl!OD EXTENT OF EXAMINATION

.Feedwater Line 3204B CS/DW 18" MT/UT weld 18-10 V;LV-P Feedwater Line' 3204C CS/DW 12

MT/UT Weld 12-5 P-P Feedwater Lirie 3204D CS/DW 12" MT/UT Weld. 12-Kl EL-P Feedwater Line 3204E CS/DW 12" MT/UT Weld 12-K2 EL-P Feedwater Line 3204F CS/DW 12" MT/UT Weld 12-K3 EL-P SDC Line 1001A CS/DW 16" MT BPC 6X-2/16X-2B SDC Line lOOlB CS/DW 16" MT BPC 6X-5/16X-5B Recirc Line 201A SS/DW 28" PT 02*01A-W-108 IWA Recirc Line 201A SS/DW 28" PT 0201A-W-109 IWA INDICATION NUMBER 1

2 1

2 1

2 1

2 1 '

UNIT NO. 2; STATE NO. 00082800 INSERVICE INSPECTION SCAN PERCENT RESULTS TYPE DAC EVALUATION 3

100 360° ID Root Geometry 3

100 360° OD Crown Geometry 2

158 360° Intermittent ID Geometry 3

158 360° Int:'.ermittent ID Geometry e 2

112 360° Intermittent ID Root Geometry 3

100 360° Intermittent ID Root Geometry 3

100 360° ID Root Geometry 2

100 360° Counterbore Geometry 3

200 360° ID Root Geometry NRI NRI e

NRI NRI

ASt*1E l'.:ATEGORY B-K-1 (CONT'D) lJH.ESDEN NUCLEAR POWER STATION DECEMBER 1986 C0!1PONENT MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION Recirc Line 201B SS/DW 28" PT 0201B-W-108 IWA Reciic Line 201B SS/DW 28" PT 0201B-W-109 IWA

  • SDC Line 1001A CS/DW i6" MT lOOlA-W-101 IWA SDC Line 1001A CS/DW 16 11 MT

. l.OOlA-W-102 IWA TSO Cond Line

i302 SS/DW 14" PT 1302-W-101. IWA Core Spray 1403 SS/DW 10" PT 1403-W-105 IWA
  • HPCI Line 2305 CS/DW 10" NT*

2305-W-106 IWA HPCI Line 2305 CS/DW 10" MT 2305-W-107 IWA Nain Steam 3001A

cs/nw 20 11 MT 3001A-W-101 IWA

~iairi Steam 3001A CS/DW 20" MT 3001A-W-102 IWA Main Steam 3001B CS/DW 20" MT 3001B-W-101 IWA

  • .* ~

INDICATION NUMBER UNIT 110 *. 2; STATE NO. 00082800 INSERVICE INSPECTION SCAN PERCENT RE3ULTS TYPE DAC EVALUATION NRI NRI NRI NRI NRi NRI NRI NRI NRI NRI NRI

~

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ASME CA'I'Er:ony B-K-1 (CONT'D)

B-N-2 1JHESDEN NUCLEAR POWER STATION

  • DECEMBER 1986 COMPONENT MATERIAL/LOCATION ME:I'HOD EXTENT OF EXAMINATION Main Stearn 3001B CS/DW 20" f:.IT 3001B-W-102 IWA Hain Stearn 3001C CS/DW 20" NT 3001C-W-107 IWA Main Stearn 3001D CS/DW 20" MT 3001-W-106 IWA Feedwater 3204 CS/DW 18" NT 3204A-W-102 IWA Feedwater 3204

~S/DW 12" MT 3204D-W-101 IWA Feedwater 3204 CS/DW 12" NT 3204E-W-102 IWA Feedwater 3204 CS/DW 12" HT 3204E-W-103 IWA Feedwater 3204 CS/DW 12" NT 3204F-:W-103

UNIT NO. 2; STATE NO. B0082800 INSERVICE INSPECTION SCAN PERCENT RESULTS TYPE DAC EVALUATION NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI

~

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ASME f".:ATEGORY B-H-2 (CONT'D)

B-N-1 &

B-N-2 B-0 B-P C-B lJHESDEN NUCLEAR POWER STATION DECEMBER 1986 COMPONENT MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION Electromatic Rehef Valve 20" VT-1 BK-7081 SDC Cooling Line lOOlB 16" VT-1 2-1001-lB Vessel Interior v

& Int. attach.

VT-1 Vessel Internals &

Attachments CRD Housing Weld SS/DW 4" UT 02-31 CRD Housing Weld SS/DW 4" UT 30'-03 CRD Housing Weld SS/DW 4" UT 58-31 CRD Housing Weld SS/DW 4" UT 30-59 Reactor Vessel VT-2 Hydro Primary System LPCI "A" Ht. Exch.

CS/RB 18"

. MT Inlet.SbL-VES LPCI II A" Ht. Ex ch CS/RB 18" MT Outlet VES-:-SDL INDICATiON NUMBER UNIT 110. 2; STATE NO. B0082800

. INS ERV ICE INSPECTION SCAN PERCENT RESULTS

'TYPE DAC EVALUATION r /

NRI NRI e

See 1H Under Summary of Re~ults, Evaluation and Corrective Action NRI NRI NRI NRI No Leakage e

NRI NRI

ASME CATEJ::;ony c-c C-F COMPONENT JJHESDEN NUCLE:AR POWER STATION DECEMBER 1986 MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION ISO Cond.

CS/RB MT West Side IWA ISO Cond Line 1303 SS/RB i2" UT/PT Weld 12-14 P-EL' ISO Cond Line 1303 SS/RB 12" UT/PT Weld 12-lS EL-P ISO Cond Line 1J02 SS/R.B 14 11

  • UT/PT Wel'd 14-7

~-Tee ISO Cond Line 1302A SS/RB 12" UT/PT Weld 12-1 RED-P ISO Cond Line 1302A SS/RB 12"

µT/PT Weld 12-3 P-EL ISO cond Line 1303 SS/RB 12" UT/PT Weld 12-10 P-EL INDICATION

  • NUMBER 1

2 3

1 2

3 1

1 1

2 3 '. UNIT NO *. 21 STATE NO. 00082800 INSERVICE INSPECTION SCAN PEHCENT RESULTS TYPE DAO EVALUATION NRI 2

100 ID Root Deometry 360° 2

so OD Crown Geometry 360° 3*

lSO ID Root Geometry 360° 3

so ID Root Geometry 360° 3

100 OD Crown Geometry 360° 2

100 ID Root Geometry 360° NRI 2

100 OD.Crown Geometry 360° 2

100 Root Geometry 360° 3

100 ID Root Geometry 360° 2

so ID Root Gc.ome try 360° 2

100 OD Crown Geometry 360° I

e e

ASHE CATEGORY C-F (CONT'D) 11-n F-A F-B DHESDEH NUCLEAR POWER STATION DECEI'.JBER 1986 COViPON EllT MATERIAL/LOCATION ME:I'HOD EXTENT OF EXAMINATION ISO Cond Line 1303 SS/RB 12 II UT/PT Weld 12-11 EL p Core Spray Line 1403 CS/RB 12" MT Weld 12-1 PMP-P Core Spray Line.

1404 CS/RB 12 II NT Weld 12-'4 P-EL*

Core Spray Line 1404 CS/RB 12 II MT Weld. 12-4 P-EL LPCI Line 1503 CS/RB 18 11 MT Weld 18-8 VLV-NOZ LPCI Line 1503 CS/RB 18 11 MT Inlet NOZ-SDL LPCI Line 1504 CS/RB 18 11 MT Weld 18-1 NOZ-VLV LPCI Line 1504 CS/RB 18" MT Outlet SDL-NOZ HPCI Line 2304 CS/RB 14" UT/MT Weld 14-15 EL'-P HPCI Line 2306 CS/RB 24" MT Weld 24-19 P-EL All Pressure Retaining Componen. s.

VT-2 Hydrostatic Test Rx Vessel Skirt VT-3

. oo t"o 180° 2A Recirc Pump Cable VT-3 CAble (support)

INDICAT-ION NUMBER UNIT t!O. 2; STATE NO. 00082800 INSERV~CE INSPECTION SCAN PERCENT RESULTS TYPE DAC EVALUATION NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI No Leakage NRI NRI

..~

e e

ASME CATliGORY F-C

  • JJHESDEH irnCLEAR POWER STATION DECEMBER 1986 COMPONENT MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION Recirc Line 201A DW 28" VT3/VT4

.201A-M-101 SUP Recirc Line 201A DW 28" VT3/VT4 201A-M-102 SUP Recirc Line 203A DW 4" VT3/VT4 203A-M-101 SUP Recirc Line 201A DW 28" VT3/VT4 201A-W-106.

SUP Recirc Line 201A DW 28" VT3/VT4

20113-22-M-107 SUP SDC Line 1001A DH 16" VT3/VT4 lOOlA-W-103 SUP SDC Line 1001B RB 16" VT3/VT4 lOOlB-M-105 SUP..

SDC Line 1001B

  • RB 14" VT3/VT4 lOOlC-14-\\{-101 SUP INDICATION NUMBER
  • -*29-.

UNIT Nq *. 2; STATE NO. B0082800 INSERVICE INSPECTION SCAN PEHCENT RESULTS TYPE DAC EVALUATION NRI NRI.

l See 112 Under Summary of Results, Evaluation and Corrective Act-NRI NRI NRI NRI NRI NRI NRI e

NRI NRI NRI NRI NRI

ASME CATffiORY F-C (CONT'D) lJHESDEN NUCLEAR POWER STATION DECEMBER l986*

COMPONENT MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION ISO Cond Line 1302 DW 14 11 VT3/VT4 1302-W-101 SUP LPCI Line 1506 DW 16 11 VT3/VT4 1506-W-102A SUP LPCI Line 1506 DW 16 11 VT3/VT4 1506-W-102B SUP HPCI Line 2305 DW 10 11 VT3/VT4 M-115ID-:-8. SUP Main Stm Ln 3001A DW 20 11 VT3/VT4 3001A-W-101 SUP Hain Stm Ln 3001A DW 20 11 VT3/VT4 3001A-W-102 SUP Main Stm Ln 3001B DW 20 11 VT3/VT4 3001B-W-107 SUP Hain Stm Ln 3001C DW 20 11 VT3/VT4 3001C-W-107 SUP Main Stm Ln 3001D DW 20 11 VT3/VT4 JOOlD-W-106 SUP Main Stm Ln 3001B DH 20 11 VT3/VT4 3001B-W-105 SUP Main Stm Ln 3001B DW 20 11 VT3/VT.4 3001B-W-103 SUP FdwtL-Ln 3204 DW 18 11 VT3/vT4 3204A-W-102 SUP Fdwtr Ln 3204 DW 18 11 VT3/VT4 3204B-W-102.SUP "A" Core Spray RB 10 11 VT-3 M-1150D-60 SUP INDICATION NUMBER UNIT HO. 21 STATE NO. 00082800 INSERVICE INSPECTION SCAN PEHCENT RESULTS TYPE DAC EVALUATION I

See 4fo3 Und~r Summary of Results~

Evaluation and Corrective Action NRI e

NRI See 4f4 Under Summary of Results, Evaluation.and Corrective Action NRI NRI NRI NRI NRI e

NRI NRI NRI NRI NRI r*

ASME CATEf;ORY F-C (CONT'D) lJHESDEN NUCLEAR POWER STATION DECEMBER 1986 COMPONENT

. MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION

.11B11 Core Spray VT3/VT4 1404-W-103 SUP II B II LPCI DW 16 11

. VT3/VT4 1519-W-102A SUP 11B 11 LPCI DH 16 11 VT3/VT4 1519-W-102B SUP ISO Cond Supply RB 14 11 VT3/VT4 1302-N-201 SUP ISO Cond Supply RB 14 11 VT3/VT4 1302 -)'!- 202 SUP ISO Cond Return VT3/VT4 1303-M-201.3 SUP RB 12 11 ISO Cond Return RB 12 11 VT3/VT4 1303-M-205 SUP ISO Cond Return RB 12 11 VT3/VT4 1303-M-206 SUP II A II Core Spray Suet.

RB 16 11

RB 16 11 YT3/VT4 1401-M-202A SUP II A II Core Spray Disch.

RB 12 11 VT3/VT4 1403-M-208 SUP II A II Core Spray Disch.

RB 12 11 VT3/VT4 1403-M-210 SUP llB II Core Spray Suet.

RB 16 11 VT3/VT4.

1402-W-201 SUP II B II Core Spray Suet.

RB 16 11 VT3/VT4 1402-M-202C SUP II B II Core Spray Disch.

RB 12 11 VT-3 1404-W-201 SUP INDICATiON NUMBER

-3'1-

. UNIT HO *. 2; STATE NO. B0082800 INSERVICE INSPECTION SCAN PERCENT RESULTS TYPE DAO EVALUATION r.-

See tf 5 Under Summary of Results, Evaluation and Corrective Action NRI

. NRI e

NRI NRI NRI NRI NRI See 4f6* Under Summary of Results, Evlauation and Corrective Act

  • NRI See 1f7 Under Summary of Results, Evaluation and Corrective Action NRI NRI NRI NRI

ASME

>>:: A'I'EG 0 RY F-C (CONT'D) lJHESDEH NUCLEAR POWER STATION DECEMBER 1986 COMPONENT MATEIUAL/LOCATION METHOD EXTENT OF EXAMINATION II B II Core Spray Disch.

RB 12" VT-3 1404-W-202 SUP II B II Core Spray Disch~

RB 12 11 VT-3 1404-M-209 SUP "B II Core Spray Disch.

RB 12" VT-3 1404-H-220 SUP II All LPCI Suction RB 14 11 VT3/VT4 1502A-H..,201 SUP II B II LPCI Suction RB 14 11 VT3/VT4

'1502B-W-201 SUP II B II LPCI Disch.

RB 18 11

  • VT3/VT4 1504-M-201 SUP llB II LPCI Disch.

RB 16 11 VT3/VT4 1504-M~205 SUP II B II LPCI Disch.

RB 16 11 VT-3 1504-M-207 SUP llB II LPCI Disch.

RB 18 11 VT3/VT4 1504-M-202 SUP II B II LPCI Disch.

RB 18 11 VT-3:

1506-~t-205, sup**

II cll LPCI Suction RB 14 11 VT-3 1507-M-202 SUP 11011 LPCI Disch.

Rll 18 11 VT3/VT4 1531-W-201 SUP INDICAT10N NUMBER

,. UNIT NO. 2; STATE NO. 00082800 INSERVICE INSPECTION SCAN PERCENT RESULTS TYPE DAO EVALUATION NRI NRI NRI NRI NRI 0

  • NRI NRI NRI NRI See :ff8 Under Summary of

~

/

e Result.

Evaluation *and Corrective Action NRI NRI

~

ASME CATEJ'.";OfiY F-C (CONT'D)

COMPONENT lJH.ESDEN ~WCLEAR POWER STATION DECEMBER 1986 MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION "D" LPCI Disch.

RB 18" VT3/VT4 1531-M-202 SUP "D" LPCI Disch.

RB 18" VT-3 1509-M-204 SUP "D" LPCI Disch.

RB 18" V.T-3 1509-N-204.l SUP "D" LPCI Disch.

RB 18" VT-3 1531-.W-209 SUP "D" -.LPCI Disch.

RB 18" VT3/VT4 1519-N-2Q5 SUP "D" LPCI Disch.

RB 18" VT3/VT4 1519-'M-206 SUP "D" LPCI Disch.

RB 18" VT/VT4 1519-H-209 SUP HPCI Suction RB 16" VT-3

. 23,01-W-202 SUP HPCI Suction RB 16" VT-3 2301-W-204 SUP HPCI Suction RB 16" VT-3 2302-W-202 SUP HPCI Suction RB 16" VT-3 2302-W-203 SUP HPCI Suction RB 14" VT-,3 2304-N-203 SUP l!PCI Supply RB 10" VT3/VT4.

2305-M-220 SUP. '

HPCI Supply RB 10" VT3/VT4 2305-M-222 SUP HPCI Supply RB 10" VT3/VT4 2305-N-223 SUP UNIT No.* 2; STATE NO. 00082800 INSERVICE INSPECTION INDICATION SCAN PERCENT RESULTS NUMBER TYPE DAO EVALUATION l -

NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI I

NRI NRI NRI See it9 Under Summary of Results, Evaluation and Corrective Action NRI ASME CATEGORY F-C (CONT'D)

JJHESDEN NUCLEAR POWER STATION DECEMBER 1986 COMPONENT.

MATERIAL LOCATION MEITHOD EXTENT OF EXAMINATION HPCI Supply RB 1011 VT3/VT4 2305-N-218. SUP HPCI Exhaust.

RB 24 11 VT3/VT4 2306-W-201 SUP HPCI Exhaust RB 24 11 VT3/VT4 2306-W-2d2 SUP HPCI Exhaust RB 24 11

  • vT-3 2305-M-216 SUP HPCI Supply RB 10 11 VT-3 2305-M-2i5

.SUP HPCI Exhaust RB 24 11 VT-3 2306-N-207 SUP llPCI Exhaust RB 12 II VT-3 2306-M,208 SUP IIPCI*Exhaust RB 1.2'.'

VT-3 2306-M-209 *SUP "A11 c.s. Disch.

RB 12 11 VT-3 1403-M-206 SUP (M.-l 150D-62)

II All c.s. Disch.

RB 12 II VT-3 1403-W-203 SUP (M-1150D-65)

'INDICATiON NUMBER UNIT HO. 2; STATE NO. 00082800 INSERVICE INSPEC'rION

~

SCAN PERCENT RESULTS TYPE DAO EVALUATION NRI NRI See #10 Under Summary of Resu~

Eva~luation.. ~nd Corrective Actl!

See #11 Under Summary of Results, Evaluation and Corrective Action NRI NRI NRI See #12 Under Summary of Results, Evaluation and Corrective Action NRI I

NRI NRI See #13 Under Summary of Results, Evaluation and Corrective Action NRI

DHESDEN NUCLEAR POWER STATION DECEMBER 1986 ASME COMPONENT CATEnORY MATERIAL/LOCATION MJ?f HOD EXTENT OF' EXAMINATION F-C (CONT'D)

II All c.s. Disch.

RB 12 II VT-3 1403-M-216 SUP II All c.s. Suction RB 16 11 VT-3 1401-M-202B SUP II A II c. s. Suction RB 16 11 v+-3 3317A-M-201 -SUP II All c.s. Suction RB 16 11 VT-3 1401-l~-204 SUP 11D11 *LPCI Disch.

RB 18 11 VT3/VT4 1519-M-208 SUP "D11 LPCI Disch.

RB 18 11 VT3/VT4 1519-N-207 SUP 11D11 LPCI Disch.

RB 18 11 VT3/VT4 1519-M-202 SUP llB II LPCI*Disch.

RB 18 11 VT-3 1506-M-203.l SUP llB II LPCI Disch.

RB 18" VT-3 1506-M.:.201 SUP II B II LPCI Disch.

RB 18 11

  • "VT-3 1506-W-206 SUP HPCI Line 2305 D\\v 1011 VT3/VT4 M-1151D-l SUP HPCI Line 2305 D\\-1 10 11 VT3/VT4 M-1151D-2 SUP HPCI Line 2305 DW 10 11 VT3/VT4 M-1151D-3. sup.

llB II G.S. Line 1401 DW 10 11 VT3/VT4 1404-M-104 SUP INDICATION NUMBER

  • ' UNIT NO *. 2; STATE NO. B0082800 INSERVICE INSPECTION SCAN PERCENT

. RESULTS TYPE DAC EVALUATION r--*

See 1114 Under Summary of

Results, Evaluation and Corrective Action NRI I

NRI NRI*

NRI NRI NRI NRI NRI I

NRI NRI NRI See 1115 Under Summary of Results, Evaluation and Corrective Action NRI

ASME CATEDORY F-C (CONT'D)

COViPONENT lJHESDEH NUCLEAR POWER STATION DECEMBER 1986 INDICATION MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION NUMBER llB II c.s. Line 1404 DW 10 11 VT3/VT4 1404-N-102 SUP II B II c.s. Line 1404 DW 10 11 VT3/VT4 1404-M-,106 SUP Recirc Line 202A DW 28 11 VT3/VT4 202A-M-to2 SUP Recirc Line 202A DW 28 11 VT3/VT4.

202A-M-103 SUP Recirc Line 202A DH 28 11 VT3/VT4 202A-M-104 SUP Re.circ Line.202A DH 28 11 VT3/VT4 202A-M-105 SUP HPCI Line 2305 RB 10 11 VT-3 2305-M-.214. l SUP HPCI Line 2305 RB 10 11 VT-3 2305-M-214.2 SUP HPCI Line 2305 RB 10 11 VT-3 2305-M-:213 SUP :

II All c.s. Disch.

RB 10 11 VT-3 1403-M-216.l

.SUP (M-1150D"".53) llA II c.s. Disch.

RB 10 11 VT-3 1403-N-216.2 SUP (M-ll50D-54)

II All c.s. Disch.

RB 10 11 VT-3 1403-W-217. SUP II A II c.s. Disch.

RB 10 11 VT-3 14.03-M-il 7.1 SUP (M-ll50D-51)

UNIT NO. 21 STATE NO. 00082800 INSERVICE INSPECTION SCAN PERCENT RESULTS TYPE DAC EVALUATION NRI NRI NRI NRI NRI NRI

.NRI NRI NRI NRI See #16 Under Surnrnar*y of Evaluation and Corrective NRI NRI f

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I I

I

Results, Action

ASME CA TEL ORY F-:C (CONT'D)

COMPONENT lJHESDEH NUCLEAR POHER STATION DECEMBER 1986 MATERIAL/LOCATION METHOD EXT.ENT OF EXAMINATION II A" c.s. Disch.

RB 10 11 VT-3 1403-M-217.2 SUP (M-ll50D-52)

II A II c.s. Disch.

RB 10 11 VT-3 1403-M-219 SUP (N-ll50D-5 7)

II All c.s. Discli.

RB 10" VT,.-3 1403-M-207 SUP CM-l 150D-6 7)

II All c.s. Disch.

RB 10 11 VT-3 1403-M-208 SUP II All c.s. Disch.

RB 10 11 VT-3 1403-M-210.SUP

(~1-3208-10)

'*'A11 c.s. Disch; RB 10" VT-3.

1403-M-:214 SUP (M-ll50D-58)

(M'" ll50D-59).

II A II c. s. Disch. '

RB 10 11 VT-:3 1403-M-216 SUP II A II c.s. Disch.

RB. 8 11

.VT-3 1406-M-201** SUP 11A11 C.S. Disch.

RB 811 VT-3 M-3208-:08.SUP.

c INDICATION NUMBER

.. UNIT llO. 2; STA'l'E NO. 00082800 INSERVICE INSPECTION SCAN PEHCENT RESULTS TYPE DAC EVALUATION NRI

.NRI NRI NRI NRI NRI NRI.

See 1fl 7 Under Summary of Evaluation and Corrective NRI r /

I Resull Action

ASME CATEr;ony F-C (CONT'D) lJHESDEN *NUCLEAR. POWER STATION DECEMBER 1986 COMPONENT MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION Various Systems Snubbers -

PSA-35/DW VT3/VT4 Snubber 7,8,9,10,11, 12,32,33,3~,50,51,52, 53,44,45,46 PSA-10/DW VT3/VT4 Snubber 47,48,41,42, 43,30,31,49 PSA-3/DW VT3/VT4 Snubber 39,40 PSA-10/RB VT3/VT4 Snubber 1304, 1305,.

1301, 1302, 1303 PSA-3/RB VT3/VT4 Snubber 2301;2303 PSA-~/RB VT3/VT4

.Snubber 2302 Jet Pump Inst.

VT3/VT4

MK-132-VS2A-5 SUP N20A DW 12 II PSA-10/DW VT3/VT4.

Snubber 24 PSA-3/DW

  • VT3/VT4 Snubber: 38 INDICATION NUMBER UNIT NO. 21 STATE NO. B0082800 INSERVICE INSPECTION SCAN PERCENT RESULTS TYPE DAC EVALUATION I

NRI I

NRI NRI NRI NRI NRI NRI See ff18 Under Summary of Results, Evaluation and Corrective Action See ff19 Under Summary of Results,.

Evaluation and Corrective Action

~

AUGMENTED.INSPECTIONS TABLE B

  • ASME CA TH:; ORY UHESDEH NUCLEAR POWER STATION DECEMBER 1986 COMPONENT MATERIAL/LOCATION METHOD EXTENT OF EXAMINATION Furnace Sensitize*

Safe Ends:

Recirc Loop "B II CS/SS-mJ 28" UT NlB NOZ-SE SS/DW 28 11 UT PS2/201-l SE-P SS/DW 28" UT Safe End CS/SS-DW 12 11 UT N2F SE-NOZ SS/DW 12 11 UT PD7/201-l P-SE SS-DW 12 11 UT Safe End CS/SS-DW 12 11 UT N2C SE-NOZ SS/DW 12" UT PD6/201-l P-SE SS/DW 12 11 UT Safe End INDICATION NUMBER 1

2 1

1 1

1 UNIT NO,. 2; STATE NO, B0082800 INSERVICE INSPECTION SCAN PEHCENT RESULTS TYPE DAO EVALUATION NRI 2

53 Root Geometry 360° 2

so Root Geometry 360° NRI NRI 2

60 Root Geometry 360° 2

60 ID Geometry 360° NRI 2

60 Root Geometry 360° 2

72 thermal Sleeve Geometry I

r /

I 360°

IIL

SUMMARY

OF RESULTS, EVALUATION AND CORRECTIVE ACTION III.

SUMMARY

OF RESULTS, EVALUATIONS AND CORRECTIVE ACTIONS The findings of the examinations and the necessary corrective action taken, assure that all components are functional and in compliance with the Dresden Unit 2 Technical Specifications and Section XI of the ASME Boiler and Pressure Vessel Code, 1977 Edition, including and up through Summer 1979 Addenda.

The following items are of particular interest as several items required corrective action:

1.

During a visual examination of reactor vessel intervals, it. was dis-covered that the dry tube plunger on IRM 18 had broken off.

A Work Request was submitted to Mechanical Maintenance Dept. to replace IRM 18's dry tube.

2.

During visual examination of Support 203A-M-101, it was noted that a nut was missing.

The missing nut was replaced under Work Request #61684.

The support was reinspected and found acceptable.

3.

During visual examination of Support 1302-W-101, it was noted that the spring can indicated an improper setting.

The spring can was re-set to correct setting under Work Request #62972.

The support was rein-spected and found acceptable.

4.

During visual examination of Support was insufficient thread engagement.

lock nuts were tightened under Work reinspected and found acceptable.

M-1151D-8, it was noted that there the turnbuckle was tightened and Request #61677.

The support was

5.

During visual examination of Support 1404-W-103, it was noted that a cotter pin was missing.

A new cotter pin was installed under Work Request #61681.

The support was reinspected and found acceptable.

6.

During visual examination of Support *1401-M~201, it was noted that there was insufficient thread engagement and loose nuts.

The nuts were tightened, and thread engagement is acceptable under Work Request #61547.

The support was reinspected and found acceptable.

7.

During visual examination of Support 1403-M-208, it was noted that there was insufficient thread engagement and a bolt missing.

A longer bolt was installed at the top and a new bolt at the bottom under Work Request #61548.

The support was reinspected.and found acceptable.

8.

During visual examinaiton of Support 1506-M-205, it was noted that there was insufficient thread engagement and a loose nut.

The loose nut was tightened and a longer bolt installed under Work Request #61679.

The support was reinspected and found acceptable.

~*

9.

During visual examination of Support 2305-M-222, it was noted that the weld at bracket showed signs of pulling away.

The support was welded completely around bracket.

The support was reinspected and found acceptable.

10; During visual examination of Support 2306-W-202, it was noted that the spring can indicated an improper setting.

The spring can was reset to correct setting under Work Request #64411.

The support

. was reinspected and found acceptable.

ll; During visual examination of Support 2306-M-204, it was noted that the support had a slight misalignment.

The* misalignment has been cor-rected under Work Request #61549.

The support was reinspected and found acceptable.

lZ~

During visual examination of Support 2305-M-215, it was noted that the support had loose nuts on base plate rod.

Loose nuts have been

. tightened under Work Request #61678.

The support was reinspected and found acceptable; 13; During visual examinaiton of Support 1403-M-206, it was noted that the base plate was: pulling away from building.

The base plate was repaired under Work Request #61683.

The.support was reinspected and fou!ld acceptable.

All the other suppor.ts on the "A" Core Spray

.line were ins.pected and foun*d acceptable.

14.

During vi$ual examination 6f Support 1403-M-216, it was noted that there was insufficient thread engagement.

Longer bolts were installed under Work Request #61729.

The support was reinspected and found acceptable.

15; Duri~g visual examination of Support M-1151D~3, it was noted that there was a loose nut on the clamp.

The loose nut has been tightened und~r Work Request #61981.

The support was reinspected and found acceptable.

16.

During visual examination of Support 1403-M-216.2, it was noted that a cotter pin was missing.

A cotter pin was installed under Work Request #62351.

The support was reinspected and found acceptable.

17~

During visual examinatio~ of Support 1406-M-201, it was noted that nuts were missing from support plate.

Repairs were completed under Work Request #26271.

This support was replaced by Support M-3208-08.

Support 1406-M-201 has been removed under Work Request #63402.

18.

During visual examination of Snubber #24, it was noted that the pipe clamp was twisted.

The pipe clamp was straightened under Work Request #61700.

The snubber was reinspected and found acceptable.

19.

During visual examination of Snubber #38, it was noted that the pipe clamp was twisted.

The pipe clamp was straightened under Work Request #61699.

The snubber was reinspected and found acceptable.

I tn

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~*

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1-1 I

(ATTACHMENT 1)

ABBREVIATIONS TEST METHOD:

- Ultrasonic UT MT PT RT VT

- Magnetic Particle Test

- Penetrant Test

- Radiographic Test

- Visual Examination EXTENT OF EXAMINATION:

BPC Branch Pipe Connection C

- Cap EL

- Elbow FL

- Flange IR Inner Radius IWA

  • - Integral Welded Attachments NOZ NOZ-VES

- No.zz le

- Nozzle to Vessel P

- Pipe PEN Penetration PMP

- Pump RED

- Reducer SDL

- Saddle SE Safe End T

- Tee VES

- Vessel VLV

- Valve W

Weldolet SCAN TYPE:

1.

Angle beam circumferential scan running above clockwise (CW) and counter-clockwise (CCW)

2.

Angle beam circumferential scan running below CW and ccw

3.

Angle beam transverse scan normal to the weld

4.

Angle beam transverse scan normal to the weld (right) the weld (left) the weld -

from above (right) from below (left)

.v (ATTACHMENT 1)

ABBREVIATIONS (Cont'd)

SCAN TYPE: (Cont'd)

5.

Base metal L-wave

6.

L-wave of the weld

7.

Inner radius scan CW and CCW PERCENT DAC:

The percent of.amplitude* of the Distance Amplitude Corrective Curve NRI:

Non-Recordable Indication MATERIAL.TYPE:

SS - Stainless Steel CS - Carbon Steel DM -

Di~similar Metal LOCATION:

DW - Drywell RB - Reactor Building TB - Turbine Building.\\

I

V.

. EXAMINATIONS, TESTS, REPLACEMENTS AND REPAIRS SINCE PRECEDING.

SUMMARY

REPORT

. I V.

EXAMINATIONS, TESTS, REPLACEMENTS AND REPAIRS SINCE PRECEDING

SUMMARY

REPORT A review of the Dresden Station ASME Section XI Repair Program Log indicates no repairs or replacements have been completed to ASME Section XI ISI items since previous Unit 2 Refuel Outage, conducted from October, 1984 to April, 1985.

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