Text

Requests for Relief from ASME Section XI requirements:NDE- 012 Through NDE-018
	ML20092K067
Person / Time
Site:	Duane Arnold
Issue date:	09/15/1995
From:	Franz J; IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	Russell W; NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NG-95-2236, NUDOCS 9509250210
	Download: ML20092K067 (54)
	v • d • e

{{#Wiki_filter:- IES Utilities Inc. 200 First Street S.E. Nw P.O. Box 351 Cedar Rapods IA 52406-0351 Telephone 319 398 8162 Fax 319 398 8192 UTILITIES John E Franz, Jr. Vbce President, Nuclear September 15,1995 NG-95-2236 Mr. William T. Russell, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station PI-37 Washington, DC 20555-0001

Subject:

Duane Arnold Energy Center Docket No: 50-331 Op. License No: DPR-49 Requests for Relief from ASME Section XI Requirements: NDE-012 through NDE-018

References:

1) Letter from J. Franz (IES Utilities Inc.) to W. Russell (NRC), NG-94-3888 dated November 4,1994 2) Letter from G. Kelly (NRC) to L. Liu (lES) dated November 30,1994, Request for Additional Information on Relief Request File: A-100, A-286b, A-351

Dear Mr. Russell:

In Reference 1,IES Utilities Inc. submitted requests for relief from certain ASME Code requirements. Your Staff asked that we revise these requests using guidance provided in Reference 2. We have revised the previously submitted relief requests (NDE-012 through NDE-015) accordingly. In addition, we have identified the need for three new relief requests (NDE-016 through NDE-018). The relief requests and supporting information are included as an attachment. We request approval of the reliefs by March 15,1996 in order to support examination scheduling for our next refueling outage, currently planned to begin in October,1996.

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. Mr. William T. Russell September 15,1995 ,. NG-95-2236 Page 2 ' Should you have any questions regarding this matter, please contact this' office. Sincerely, N- .hn F. Franz Vice President, Nuclear Attachment JFF/CJR/smz NWwa\\1.lcensing\\NG-95\\95-2236 cc: C. Rushworth L. Liu (w/o) L. Root (w/o) ) B. Fisher (w/o) G. Kelly (NRC-NRR) II. Miller (Region III) NRC Resident Office. Docu 1 ) l I l l i

~ _. 1 Attachmsnt to. NG-95-2236 DUANE ARNOLD ENERGY CENTER Page 1 of 52 l 2 10-YEARINTERVAL ND REQUEST FOR RELIEF NO.NDE-012 I' ' SYSTEM / COMPONENT (S) FOR WHICH RFI IFF IS REOUESTED j ' HEA-CC-08 (1 through 4) Residual Heat Removal (RHR) Heat Exchanger Integral Attachment Welds EXAMINATION CATEGORY C C. ITEM (S) C3.10 11 ' CODE REOUIREMENT ' Section XI (1980 W81. ADD), Table IWC-2500-1 Category C-C, Item C3.10 requires a surface examination of essentially 100% of weld length once during the ten year interval. 111 CODE REOUIREMENT FROM WHICH RFI IFF IS REOUESTED . Reliefis requested from performing essentially 100% of the weld length for HEA-CC-08 (1 through 4). IV BASIS FOR RFI.IFF The design of the support does not allow access to the entire length of weld as required for the code examination. In order to perform the surface examination of the inaccessible portion of 14" on each support, the RHR heat exchanger would be required to be supported by alternate supports while the bolts were removed to allow access for the examination. The dose rates in this area are 50 to 70 mr/hr. Examining the 14" of weld for each support has only a small potential for increasing plant j safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure. V ~ LTERNATE EXAMINATIONS A IES Utilities Inc. proposes to perform a surface examination of the accessible 82.5% of the weld length for each of the four welds (HEA-CC-08, I through 4). The examination coverage specified in Code Case N-460 will be utilized. VI JUSTIFICATION FOR THE GRANTING OF RFI IFF To perform an examination of the inaccessible 14" of weld length, the RHR heat exchanger would be required to be supported by alternate supports while the bolts were removed to allow access for i the examination. Performing this activity in order to examine the additional 14" results in only a small potential for increasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure. VII IMPI FMENTATION SCHEDULE '. This relief request will be implemented during the 2"d Ten Year Interval.

Ettachm::nt to NG-95-2236 i Page 2 of 52 I CC-8(011-0* CC-8(02)-90' I I-CB-6 CC-8(03)-180* CR-5 CC-8(04)-270* O F l .( N L 4 1 RB021 _,CC-8 __=_______s_._ _ _ - _ _ g,g. /033_*_____ y 7-f i i i J. I CA-4 O 180* + ue, = - CR-11 3 /3 A CA-3 I CC-7 RB022 j j /032 j 3 r g 90 SECTION R-A ,,7 g i ~ CR-18 CB-2 2 SHELL - REACTOR WATER i TUDE - COOLINC WATER CA-1 / N 52, 1 1/8" STUDS l l RHR HEAT EXCH A B HER HEB-FIGURE NO. 2.1-01 DRRWING RELEASE RECORD REV ORTE PREPARED REVIEWED APPROVED PURPOSE 1 4-26-es SAL Srt RCr1 ISO'S FOR 2nd 10 YEAR PLAN 2 1*1%-90 W T @s%. Iso's To cno roarser as rca Nc-es-ers e 3 S/2 *f14 OA (<b (zske W REVISED PER ISI INSPECTION WALKOOWN 6 m

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m - = Attachmnnt to l NG-95-2236 i i ' DUANE ARNOLD ENERGY CENTER. Page 4 of.52 l ~ " 10-YEAR INTERVAL' 2 - REQUEST FOR RELIEF NO. NDE-011 l l I - SYSTEM / COMPONENT (S) FOR WHICH RFT IFF IS REOUESTED RBA-J007 Recirculation Bypass weld ~ EXAMINATION CATEGORY B-1 ITEM (S) B9.11 11 ~ CODE REQUIREMENT ' Section'XI (1980 W81 ADD), Table IWD-2500-1 Category B-J, Item B9.11 requires a volumetric examination which includes essentially 100% of weld length once during the ten year interval. . 111 CODE REOUIREMENT FROM WHICH RFI IFF IS REOUESTED 'Reliefis requested from' performing essentially 100% of the weld length for Recirculation ' Bypass Weld RBA-J007.. IV BASIS FOR RFI IFF The weld is a tee-to-flange configuration which limits the volumetric (UT) examination to a one-sided exam from the tee side. In addition, the tee configuration limits the one-side examination to 85% of the weld length.. In order to perform a radiograph of the weld, the recirculation system would be required to be drained, thus increasing exposure to personnel by a factor of 1.7 (50 mr/hr vs 29 mr/hr) for a total of 120 mr for the additional 15% coverage. This is the additional exposure for the examination, installation and removal ofinsulation and shielding; it does not include any additional exposure resulting from the time spent performing valve line-ups or system draining. Examining the additional 15% of weld length has only a small potential for increasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure to perform the radiography. ) -V ALTERNATE EXAMINATIONS IES Utilities Inc. proposes to' perform volumetric examination of the accessible weld, obtaining a total of 85% coverage for this weld length. The examination coverage specified in Code Case N-460 will be utilized. VI- - JUSTIFIC ATION FOR THE GRANTING OF RFI IEF To perform the additional 15% of weld length the Recirculation System would be required to be drained, thus increasing exposure to personnel. Examining the additional 15% of weld length has only a small potential for increasing plant safety margins and a very disproportionate impact on expenditures of plant Emanpower and radiation exposure to perform the radiography. Vil, IMPI FMENTATION SCHFnULE - This relief request will be implemented during the 2"' Ten Year Interval. This weld was included in the Refueling Outage (RFO) 8 Summary Report. kil ~ ,C'..

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f c: f.c7a 515 Aldo Avenue 3_ f, g 7 3 San a Clara. CA C5050 / / 406-960-7333 c ace at REPORT OF ULTRASONIC CAllBRATION S-T Examinertlevel .Q Aeview t Levei / Z E s aminer s tev b Aulnoriteo InsDeClor 1 bbJ -) 3 ~ '7 Customer UW-h k-Mi*d l ! o j i N'l l ReCal Due?-]h-? 7 SU CaOne h C C A P Instrument /Vf)fI~EC l.? / O SIN instrument U.Af2E~ S/N ,2 /) ReCat Due b ~ E~E 7 j N /A SIN N /A ReCaf Due N /N Aecorder N [4 M/A SIN N /A ReCat Due Recorcer VEATICAL LINEAAITY CHECK Check Completed bv i F. sic = A6 i ice so so ro ao so ao 2o so io f Z s*omat a So 4/r vc E Jo _L 5 e /5 to S l i W Sqnal 2 snail equal 50% of Signat 1 witnen s 5% of full scale. F Q. AMPLITUDE CONTAOL LINEA AITY CHECK Check Comoteted b s.=,....... _i, se 55O acce,..uce nos n.. i .. i. as aos .os e4 i. es Sa xxY Ko w sc,un varue DX -w, s no xxY \\ S.gnal amptituce must f ail witnen listeo values SEAACH UNITS SINC 77.S~l/ Mfg //AMM//cType 8!!4/- Size,8 6 Freg. [ 8 hf/b_ index _35 Angie /6# l M!A Angle // M!M N!A N!A N!A M f g. Type Size Freq. MA !.iden S/N O proceoute llI~l-l! Ae, 5 Date E~ 7 ~.V 7 Fiela Change l 2 E Date 3-17 ' N 7 - 3-g g-67 FC w g fa Do Cal. Block Type P/M SfGMfh'7"S1N POSE 9 Ret. Rets. Nn n // Temp. 70 f verificationtRef. Bik. A0A'fPA s SIN 2. M 7' O 3~1 Ret. Rets. / ' 2 "M/' Temp. 70"f I rfomr45 DAC CAL. CH ECK /m / 4J 4.- TIME INSTRUM ENT SETTINGS Q Y8lA 'A W to / g7 .ho@ POYo y cGo 9S1.' Z Q. Digital 8 9'E d / 5 / '[ s pfp gplgg f,c or/ y Ga,n s /5 2% 6 ~ i gf<7gg Jf.o = //* S. "'!*Y* ' S 'I S efo r /5 Y7 )/o01 5o=5" @;ry a ons y,,, Re,ect j ggy gl) 2 !.cta/SYa D* * *

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i Attachman't'to-. l NG-95-2236 DUANE ARNOLD ENERGY CENTER Page 12 of 52 2* 10-YEAR INTERVAL. REQUEST FOR RELIEF NO.NDE-014 I SYSTEM / COMPONENT (S) FOR WHICH RFI TFF IS REOUESTED f . RBA-J012 Recirculation Bypass Weld. j l . EXAMINATION CATEGORY B-1 ITEM (S) B9.I 1 - 11 . CODE REOUIREMENT - Section XI (1980'W81 ADD), Table IWB-2500-1 Category B-J, Item B9.11 requires a volumetric examination l which includes essentially 100% of weld length once during the ten year interval. l l .III . CODE REOUIREMENT FROM WHICH RFI TEF IS REOUESTED - l Y Reliefis requested from performing essentially 100% of the weld length for Recirculation Bypass Weld RBA- - - ' J012. t IV ~ BASIS FOR RFLIFF . This weld is a valve-to-weldolet configuration which limits the volumetric examination coverage to 76% of the weld length. In order to perform a radiograph of the weld, the recirculation system would be required to be. drained, thus increasing exposure to personnel by a factor of 1.7 (50 mr/hr vs 29 mr/hr) for a total of 435 mr ! for the additional 24% coverage. This is the additional exposure for the examination, installation and removal - ofinsulation and shielding; it does not include any ' additional exposure resulting from the time spent performing valve line-ups or system draining. Examining the additional 24% of weld length has only a small -potential for increasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure to perform the radiography. V.. ALTERNATE EXAMINATIONS l IES Utilities Inc. proposes to perform volumetric examination utilizing the required 45* shear supplemented with a 70' Refracted Longitudinal exam of the accessible weld, obtaining a total of 76% coverage for this

v. eld. The attemative examination coverage specified in Code Case N-460 will be utilized.

~ VI) JUSTIFICATION FOR THE GRANTING OF RFI TEF ~ - Examining the additional 24% of w -Id length would require draining the Recirculation System which would result in increased exposure to personnel. This additional examination has only a small potential for .. increasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and L radiation exposure to perform the radiography. iVII' > IMPI FMENTNI' ION SCHFDULE ' - This relief request will be implemented during the 2"d Ten Year Interval. RBA-J012 was included in the b

Refueling Outage'(RFO) 8 Summary Report.

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Attachment to NG-95-2236 i Page 14 of 52 REPORT NO.: GE Nuc/ese Energy RESOLUTION SHEET l R-192 C-E - UT-101 erv. 1 ran wo. N/A j PROJECT: DUANE ARNOLD ,. crou. : N/A nev. BUA ren wo. M /A M/A sev. 8_/A rna no. M/A NDEuEWCD: O ur O cr 5 or O vT kEttRtut ATf DM systru: weLomo: REA-TOlt @cancuurteswnAt \\/ALVE To vict n-o-LET Otoacrrvo<=At Oomen 4/A councunAnow: EXAumER: H. 6dHLDRTT mnX cat sMest woJs> C-li%, C -t 19 ExAumEn: M/A trvet All EXAumen: M/A tevet M

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- Attiad{$ ment' to NG-95-2236 Page 16 of 52 "IS E AJo. M -190 ULTRASONIC EXAMINATION DATA SHEET GE Nuc/ ear Energy (MANUAL PIPING) SITE: DUANE ARNOLD UNIT: 1 REPORT NO. R-l?9 PROJECT NO: CT-662 CAllBRATION SHEET NO. C - I t '2 PROCEDURE: Ci*"T" 8 0 ~L REV A. FRR ^/ / A MATERIAL TYPE: O Cs S Ss C OTHER iti s c ExAu SURFACE O iD E OD ] cy,7,u. p,,, u EXAM SURFACE TEMP Fo r gg, g, THERMOMETER S/N / S? o 2. 3 CTART TIME o F o S' Ax AL SCAN SENSITIVITY 47 de OF/2 CIRC SCAN SENSITMTY SF d8 FINISH TIME kuie 2I l 7~ D C. W, REFERENCE lA) e id k L, REFERENCE

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v v 6 / INDICATION L Gn) FROM REF W Gn) FROM REF MAX SWEEP READING ^ EXAM AMP SCANNING Lg Lm L W W W % DAC SW, sw sw2 2 1 m 2 ANGLE t /ll) Reco p b st har 2'ovWr e.4 7;cas 3 - 61 4t* i i . v l . m ~% "*y!fh 0 # u 1 j g.y... i 'ct gp 1 y 1 on (J,tef.o.l,-f bu e-f;, Comnen,ewY REMARKS st/o Esp m g r%ggommes on,gfgggg Cow /;c u,p.oba Croc s ea,v s 'a 's.+ sr >< s lo n < 4 c.o tJ e 11 t' k o w n) e airl /) /) a YW 2Z' 9-17 9a M.O 2C 7.IV40 Enemin.r Level Date lRevbwed Page 3 of g Level Date C .-g_ 7-up-to it//A Examiner Level Date Reviewed Title Date ' pg g3 g,p r% Ni'h m...~,; 9-://-i)

l Attachment to NG-95-2236 Page 17 of 52 'CS T tJ 0 RQ-o 9 0 ULTRASONIC EXAMINATION DATA SHEET GE Nuc/ ear Energy (MANUAL PIPING) i SITE: DUANE A8NOLD UNIT: I REPORT NO. k-17 V PROJECT NO: CT-662 CAllBRATION SHEET NO. C - /19 PRocatouRE.Cc.ur- / o 2 nEv 2. FnR s/a MATER AL = DCS E ss OOmER e/f o g EXAM SURFACE O to @ Oo EXAM SURFACE TEur Po y OI ~ WELD ID~- THERMOMETER S/N /702 START TIME o ?,rr AXIAL SCAN SENSmVITY do d5 O9/O FIN &SH TIME CIRC SCAN SENSITIVITY /= 0 48 L, REFERENCE u/c #/ T O d. W, REFEREN M h/e /cl O1t 1. WITH FLOW PERFORMED INDICATIONS g YES NO YES NO

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NG-95-2236 Page 18 of 52 t i ULTRASONIC CAllBRATION DAM SHEET GE Nuc/ ear Ene/0/ (MANUAL EXAMINATION) SITE: DUANE ARNOLD UNIT: I CAUBRATION SHEET NO. C -118 PROJECT NO: CT-662 LINEARITY SHEET NO. L. -OOs Procedure No. 6E-vr- /02. Rev. 2-F R R N o.: t//n Instrument //f?AafM)?4mrR /Vgy. -)S 31 4 5 7 - /,$ 4 f Manuf actur.f w.g S.rt.1 N.. Search Unit NOA 2s' Lumuz 4C*N K24 932 w e r.,,e crue., sin. re.a. Aaow u.*e s.ri.i No. Cable AC - / 7 4' d' 1 Typ. Length C.nn.ct.re Calibration Standard IT-/7 55 52 ** 79 'F Serial No. M.t.rt.1 Thickne se Temp. 1 Couplant a m # c n. 27-9974 Thermometer /802-Dr.nd Seich No. Seri.8 No. DAC INSTRUMENT SETTINGS ( f eres ri I i DAC Construction Sensitivity ) M so

1) O *- #2 I Gain - Axial Scan 34 dB Gain - Axial Scan

?d dB \\ Gain - Circ. Scen W dB Gain - Cire. Scan P yo dB h Freq. Ma @ 8 s Rep Rate Arsb ) u N Range <f 80 Resolution FeneD a ^ E OW"P W Delay /O, o Damping DOS i 1 2 3 4 5 6 7 8 9 to SWEEP Filter 8/ A *-o Reject C FF Scale Range: 0-10 = #5 Jack p(R oT FIELD SIMULATOR: N/d S/N: N/A CAUBRATION VERIFICATION REFLECTOR [ INITIAL CALIBRATION VERIFICATION TIMES MAX AMP, gg TIME 07Jf f SWEEP [ FINAL VERIFICATION

HO WELDS EXAMINED REPORT NO.

TIME /

84 - Jo i 2.

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F lAttaclrument t@ NG-95-2236 Page 19 of 52 ULTRASONIC CAllBRATION DATA SHEET GE Nuc/ ear Energy (MANUAL EXAMINATION) SITE: DUANE ARNOLD UNIT: I CAllBRATION SHEET NO. C -/19 PROJECT NO: CT-662 LINEARITY SHEET NO. / - OOr Procedure No. G E-ui- /o E Rev. 2-F R R N o.; /U / 4 Instrument R R4v71/ e A m e R LA SR-7 5 3 Nr9-f rug wenureeturer u.aw seri i No. Search Unit MA R ' N 'C 'U '4 " Wan. 70 */#A E'OLL9 u.nuv.ctor., sia. Fr. Aaew uade

s. ries No.

Cable (R RC -I H L' J Typ. Length Connectors Calibration Standard Tf- / ~/ .55 . r.1 'N *F serial No. ueteriet TNckne.e Temp. Couplant ul7 Race' 2r g1>4 Thermometer 6CE 4 Brand Batch No. Serial No. DAC INSTRUMENT SETilNGS '00 a l l I i I I i l l DAC Construction Sensitivity d #b"O I I Gain - Axial Scan /,0 dB Gain - Axial Scan IC dB u o P 70 Gain - Cire. Scan 60 dB Gain - Cire. Scan 60 dB so Freq. ka'f* Rep Rate f u er> ""8* ~ So Resolution F/xc0 D to Sweep 883 Delay 9% Damping Dv AL 1 2 3 4 5 6 7 8 9 1o Filter F/i to Reject OFF SWEEP Scale Range: 0-10 =

l. 0" Jack ts' R MT j

FIELD SIMULATOR: ^11 A S/N: N/A CAUBRATION VERIFICATION REFLECTOR [ INITIAL CALIBRATION VERIFICATION TIMES M AX. AM P. jg TIM E M SO / ? SWEEP [ ~h FINAL VERIFICATION 09#' WELDS EXAMINED REPORT NO. TIME / l 884-70 f 2. Q-l~/S COMMENTS: MON G. l i ik P.$ M. Outa em ma _. ?'= W $, iW ~( g {< (?)/ {pW ? ~ II ~ J 4 1A'1 xfutu9' s-r-a 10 Ken M 4 6 2c v.mo \\ / Examiner Lev.1 Date Rev6. Level Date N/A A//4 A//) 1SO" l em. min.c L.v.i o.l. Mvi.'.d ost. w rmu nn 4,..j,' i..k i %.. l } ;i f) I %.nf

Attachment to NG-95-2236 f i Page 20 of 52 LMT-uTx2 10/79 Location hAE c I ***' Lambert

MacGill e Thomas,Inc.

Repo m No. w - s s e i Testing e Engineering e Service e Training c.1,3,, g, _,f 1,, f,o 3 i b' 515 Aldo Avenue >b8 /^ -OFV Santa Claro. CA 95050 408-980-9333 Date /.,/_. /- P 7 Page / _ of / ,,,4 p. REPORT OF VISUAL AND ULTRASONIC EXAMINATION q f Description hr Size Y" Material SS S /N ( s)A/)-A/-//O-/22-F6 ,i c A 1 ocp 1 3 r * ** '*R**1'*c P 't w \\ (. Location b/t V WEL L Preparation A s wa L deb Temp 7.2 *ic" W-a.* f1 j .;l0 f Examiner /Leve,1 7# - Er==-iner/ Level N 8. 8 E Review /Leve1AMW/ 2M/GE~ Authorized Inspector 0.I

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'h@ W S'-N Customer N E Testor 1 NOB 7"E'c /3/DS/N /// 2 g[A S/N N[A A /A-S/N N lA U Recorder 1 W/A S/N A//A-2 f Tranaducer D, b f . /d mMAFMan/ N!A p 4h1M g'/j 4 gfj M 3 E N Couplant A/P/7~6#/ Cable /A 'c nA Y Marker N[A Photo g/A T /OA/Rh 6 / ~ - /y/ / Rev. 8_ #c / 3 P Calibration Procedure / R Examination Procedge [ / 7~ - 4// Rev, I #C / 3 Recording Procedure ///A Rev. A//A f Calib. Bik. FC 3 5"9 Temp. d 8 8 8 Ref. 0 // Amp. EON Sweep 4.O L Ref. Gain 8 M S O Damp. O /~/~- Reject OFF Gate /- /O A / V I Alarm N/A Mag. Tape Count N[l-Chart N/A Cal. Check Time /.2 3 2 No tr9M S Cal. Re f. B 1k g.M 7 037Re f. Re fl. /.3 ",sp Amp. 78I Sweep Position 4f,0 F,0 Sean cain 7o/71 Ref. owg. /, 2- /t Re3.et Lev.1Asus M Report Lev.1AhME rr-E NAD = No Apparant Disc. L = Linear G = Geometry S = Spot M = Multiples X Scan Type Disp. Scan Type Disp. Scan Type Disp._ 'l A N/A. M/A-> . M /A l N/k N /A N/A N/A N/L N /A N 1 m J An/ NLosef M/A. 1 45"bew L N/A 13 2 PA grow y/4 i a 45*,,w A g/A 14 I 3 ?Wfd se/ NAh 9 N /A M)A 15 4 'll c e w hah LD ? 16 E

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Attachment to NG-95-2236 Page 21 of 52 M I-C Locaison Lambert

MacGill
Thomas,inc.

C.< No v - a T. o D s Testing. Engineenng. Service e Training /E4 - 0 3 u

oo No.

515 Aldo Avenue y_f_y7 g,,, San *o Claro. CA 95050 / / 408-980 9333 a.ce oi REPORT OF ULTRASONIC CAllBRATION E /./.4-Examinertlevel

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/2" Review t Levet Z Exammersleve C / b O. 4 O Customer h 6 4-b-% 7 Autnonzec inspector O' //l Recal Oue 5 R 7 Su Caose l2 'r n A X snstrument A/ORiEC /3iD son ~ N/A SIN N/A ReCal Due N/A instrument N !N Recorcer N/A SIN A/ /N RdCal Due N/A SIN M/A ReCal Due NIA Recorcer VERTICAL LINEARITY CHECK Check Completed by s s,.. i. = es re .e m a ie Z MG=aL 2 E3 Nf s/O 3g 3O .;L 5 ,2 C, ($ /O f W Signal 2 shall equal 50% of Signal I withm = 5% of full scale. l AMPLITUDE CONTROL LINEARITY CHECK Check Completed by 5

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accan manas ses n i..e in w u as w ee es = = es - W ac vat vatut .m NO 2C YYY _O XYY Po Segnal amositude must f ail witnen tisleo values. SEAACH UNITS b Site.3750.3 7sfren.], S$1Ns. Incen.3 Angw US Sr tMtg Aurvar* T/udype S LJ ^ MlA-MlA. N/A rren. M lA N/A 8A A Msg. rype Size laaen Angle i o h Procedure U7~#/ Rev 8 Date J-7-F7 Field Change / 3 Date 3 - 2 7*I'7 ICI-3-19-81 Hi3 s 1. /* / f* E /a Da b S oY Cal. Block Type S C G M f N I~ StN WO 3 5 9 Ret. Rett. No r-r JJ Temp. venticat,oniner. eln. RoMPA s SIN L M7"n 3 7 Res. Rets. / } 2 % P. Temo. b?? OAC CAL CHECK

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~ Attachm3nt-to l NG-95-2236 DUANE ARNOLD ENERGY CENTER Page 22 of 52 2* 10-YEAR INTERVAL s REQUEST FOR RELIEF NO.NDE-015 I. SYSTEM / COMPONENT (S) FOR WHICH RFI IFF IS REOUESTED j CUB-F004 Reactor Water Cleanup (RWCU) Weld EXAMINATION CATEGORY B-F. ITEM (S) B5.130 11L CODE REOUIREMENT- - [ Section XI (1980 W81 -ADD), Table IWB-2500-1 Category B-F, Item B5.130 requires a volumetric i examination which includes essentially 100% of weld length once during the ten year interval. 111 CODE REOUIREMENT FROM WHICH RFI IFF IS REOUESTED 1~ i Reliefis requested from performing essentially 100% of the weld length for RWCU Weld CUB-F004. l IVE - BASIS FOR RFI IRF This weld is a elbow-to-valve configuration which limits the volumetric (UT) coverage to a one-sided exam. This results in approximately 70% coverage of the weld length. In order to perform a radiograph of the weld, the RWCU System would be required to be drained, which would result in an increase in exposure to personnel by a factor of 1.7 (17 mr/hr vs 10 mr/hr) for a total of 70 mr for the additional - 30% coverage. This is the additional exposure for the examination, installation and removal of insulation and shielding; it does not include any additional exposure resulting from the time spent performing valve line-ups or system draining. Examining the additional 30% of weld length has only a small potential ofincreasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure. V ALTERNATE EXAMINATIONS IES Utilities Inc. proposes to perform volumetric examination of the 70% weld length. The alternative examination coverage allowed by Code Case N-460 will also be used. .VI JUSTIFICATION FOR THE GRANTING OF RFI IFF To perform an examination of the additional 30% of weld lengtii, the Reactor Water Cleanup System would be required to be drained, thus increasing exposure to personnel. The benefit of examining the additional 30% has only a small potential ofincreasing plant safety margins and a very disproportionate l impact on expenditures ofplant manpower and radiation exposure to perform the radiography. . VII IMPI EMENTATION SCHFDULE l This relief request will be implemented during the 2"d Ten Year Interval. This weld was included in the - Refueling Outage (RFO) 9 Summary Report. A w-r-r--

1 E w e ro ru - cn-1 e[ 3 BP10002

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- H0H INTEGRAL Q

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m s st>s m uta s u s NG-95-2236 Page 24'of 52 I Loca tion f)E A C ~ Lambert

MacGill
Thomas,Inc.

ss-e Re,om o. Testing

Engineering
Service e Training ce1 No.mys Time 205 h

515 Aldo Avenue 3 *"- -d" j Santa Clara. CA 95050 408-980-9333 Date /o gg Page I of { REPORT OF VISUAL AND ULTRASONIC EXAMINATION f De s cription f/_ /t/Af/4" Size // # Ma te ria l, SS S/N(s) [_ U S- / F - N E Loca tion _ STEAM TUMNFL Preparat1on As fevNp Temp 95"f Examiner / Level 5 Ex miner / Lev 1 A TA T'"E neview/ Level M d /8 ( so - ti cf 44 h. % -.. *ds _. 4* - 6tA1C N Authorized Inspector 'f 8 Customer C Tester 1 NCRTfc /,El-b S/ l{r 7 2 Al A S/N jVA U Recorder 1 lv A S/N Ar4 2 A/ A S/N xA \\ Transducer 14"# R64 f 6mz d # /0/#7_ 2 NA p K 3 NA . At A E tl Couplant $4$$ Cable 6 4Nc /rs/ Marker A/A Photo /V4 T P Calibration Procedure (17 4// Rev. 7 Fr 2. R Examination Procedure Lt T" Ql Rev. T /:"C - 2. O C Recording Procedure (IT Lll Rev. $ fd - 2 C Calib. Blk. 90 3 5 9 Temp. 9$#8 Re f.IMAbrtg Amp. Sdk Sweep 2..d e[# L pef. Gain LJ 7 d{, Damp. OCS Roject Off' Gate /, (- /0 dW Alarm N# Nag. Tape Count NA Chart A/A Cal. Check Time 2069 I g Cal.Ref.Blk.h03$'l Ref. Refl.io NhTCA Amp, hd /c Sweep Position 2. 6 M, U Scan Gain $'/d$ Ref. Dwg. l.2-d 6 Reject I,evel N4 Report Level M M BC. E NAD = No Apparant Disc. L = Linear G = Geome try S = Spot M = Multiples X l Scan Type Disp. Scan Type Disp. Sean Type Disp. A N 1 l-tonn group NAD, 1 N A._ NA 13 N A N A 2 xf a NA 6 e 14 I 3 ll C. U) nan 9 15 ~ N 4 11 /*r (A) N40 10 16 28//ZAd# IV A D 11 17 A CW iv.ocu nap 12 V sr 18 V 6 gg.w w Scan Description of Indications S l 50 000' L.Ecs THM So y gg (_ o ) b $ WA005 V b l Y CAN f/C C$ N 'Q S } ll Lt MI TED TO W ELO ANO UA Gld WY. Fibo ec-c

NG-95-2236 Page 25 of 52 tur-urC i ee 1 b Location j Lambert

MacGill
Thomas,Inc.

uw rime s Ca, No Testing. E ngineering. Service. Training ne w JE L - C@ __ 515 Aldo Avenue g, _. g _ g g j Santa Clara. CA 95054 408-980 9333 pase / o' / REPORT OF ULTRASONIC CALIBRATION FOR. g Revie <L.e, M I N ///rr D 4r Ir F Z Examinertleves Ao '/ ExaminerILevel Yn S /h / ~~ Customer e t. Authorized inspector ' /4 f j -v instrument /VOA Tf<* lAl-A SIN l6 ReCal Due /2 ~/ ~SS SU Cabin f 'A A'C k n instrument /VA SIN A/ A ReCat Due NA Recorder Al A SIN A/ A ReCat Due NA Check Completed by r/ VERTICAL LINEARITY CHECK F= seon at i ion so so to no so ao ao 2o to Z snomst n

i s

-16 av t s, 21 2 c. -n is /O w d S,gnal 2 shall ecual *0% of Signal 1 within 5% of full scale 7 l E Check Completed by Wl'f i Q AMPLITUDE CONTROL LINEARITY CHECK .. m sn.. n m _e s, m .e oc accier nanoe eos as i..a is i no now u i. ee .ow u. ee W scsunL v ALui )DJ Hn ?ro XXX M* XYY Ker Signal amplitude must f all within issled values. SEARCH UNITS Y.5 SIN ///d/l/2 Mfg. E/IA Type 4 4/ Size _ i 8 Freq.[INA-Inden Angle ^/// Angte //A NA utg. /V /1 Troe N // Size NA Frea. N' A inden SIN Couciant M T 6 E d-Batch Nct 0 b- -N Field Change [d 1 Date /8 - [* - T 9 Procedure UI N f Rev. Date O. V0'E 0 $0 S S*f Ref. Rett. E A /W N /f Terrp. Cal. Block Type 1 lff SEC-SIN VerificationtRef. Stk. Id/WA S SIN d 'E O Ref. Refl. A/G ON2V Temp. k6#[ DAC CAL. CH ECK INSTRUMENT SETTINGS 10 QC C '( 49 RO 36 2 o 0* Anjm D'9 *' e le se h NA 47 afb N ll 4Qjal' ' 6 gg g t[ g h/ 5% eD f .u inn L y.g E 2 ) f "$ 4 l Delay ,p O Reject Off 2 Damp. 2 4 6 8 10 Freq gg videoIF6tt. 4 3,7 ,7 l.0i /.4 f /. h'~ 1RD b "" R *

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L Attachment to NG-95-2236 Page 26 of 52 DUANE ARNOLD ENERGY CENTER l 2 10-YEAR INTERVAL I ND REQUEST FOR RELIEF NO. NDE-016. 1 SYSTEM / COMPONENT (S) FOR WHICH RFI IFF IS REOUESTED RHB-3002 Residual Heat Removal (RHR) Weld i EXAMINATION CATEGORY B-1 ITEM (S) B9.31 i 11 CODE REOUIREMENT ) Section XI (1980 W81 ADD), Table IWB-2500-1 Category B-J, item B9.31 requires a volumetric and surface examination which includes essentially 100% of weld length once during the ten year interval. i III CODE REOUIREMENT FROM WHICH RFI IFF IS REOUESTED - Reliefis requested from performing volumetric examination of essentially 100% of the weld length for - RHR Weld RHB-J002. IV ' ' BASIS FOR RFI.IFF i This weld is a branch connection-to-weldolet configuration which limits the volumetric (UT) coverage to a one-sided exam. This results in approximately 75% coverage of the weld length. Performing a radiograph of the weld would require the RHR System to be drained, which would increase exposure to personnel by a factor of 1.7 due simply to the pipe being empty (340 mr/hr vs 200 mr/hr) for a total of l40 mr for the additional 25% coverage. This is_ the additional exposure for the examination, i installation and removal ofinsulation and shielding; it does not include any additional exposure resulting from the time spent performing valve line-ups or system draining. Examining the additional 25% of weld length has only a small potential for increasing plant safety margins and a very 1 disproportionate impact on expenditures of plant manpower and radiation exposure. i V ALTERNATE EXAMINATIONS IES Utilities Inc. proposes to perform volumetric examination of the 75% weld length. The alternative examination coverage allowed by Code Case N-460 will also be used. VI J_USTIFICATION FOR THE GRANTING OF RFI IEF To perform an examination of the additional 25% of weld length, the RHR System would be required . to be drained, thus increasing exposure to personnel. Examining the additional 25% of weld length has a ' only a small potential ofincreasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure to perform the radiography. Vil IMPI FMENTATION SCHFDULE This relief request will be implemented during the 2"' Ten Year Interval. This weld was included in the Refueling Outage (RFO) 13 Summary Report. 1 .l

lA@BecG~ mink to NG-95-2236 P ga 27 of 52 s - E

J wa.dhe: MR..

2 REPORT NO.: 7; ;;q E N' EXAMINATION

SUMMARY

SHEET ~ y GE Nuclear Energy m o2 L. I PROJECT:_DJ)AJERfiOJ.D PROCEDURE:_UT DArc.JQ2VO REV:.,_0._._ F RR: _N/A 1DX36 Task: 1FJPV [^g SYSTEM: RHR 2182.1 REvt 2_ FRR: N/A N/A WELD NO.: RHB-J002 N/A N/A REV: N/A FRR: CONFIGURATION? PIPE TO BRANCH CONNECTION N/A EXAMINER: D HEBERT LEVEL: ti O MT E P,T E UT O VT EXAMINER? H. KOMPF1 lFN LEVEL: It E CIRCUMFERENTIAL EXAMINER: N/A LEVEL: N/A.. O LONGITUDINAL 0 OTHER N/A DATA SHEET NO.(S): ou-o73 CAL SHEET NO.(S): Cu-o74 3 74 CM-075 PT-013 Dunng the manual ultrasonic exarrunaten of RHB-J002, no recordable indicatens as per ASME Section XI or NUREG 0313 were detected utahzeng a 43* shear wave search unit No examination was performed downstream due to the branch connection. A supplemental 60' RL examination was performed, to increase required Code examination coverage, and resulted in no recordable indications. A liquid penstrant examination was performed prior to the ultrasonic examination resulting in no recordable indications. Examined 75% of the Code required volume. I ) O ex^u cometric E eAnratov exAmmeo ecxetAm m comueursi O ex^" cog *,commm e

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MCdMbTes3R 15@ NG-95-2236 Page 30 of 52 I s..... M. ULTRASONIC EXAMINATION DATA SHEET ' GENuclear Energy (MANUAL PIPING) SITE:_QUANE ARNOLD UNIT: 1 I CAllBRATION SHEET NO.:_C M-074 _ PROJECT NO.: 1DX36 TASK:1FJPV DATA SHEET NO.: DM-073 PROCEDURE NO.: UT-DAC-102VO REVISION: 0 FRR. N/A SYSTEM: RHR EXAM SURFACE TEMP: 74

F COUPLANT:

HUMEX EXAM START: 10:50___ WELD ID: R HB.J002 THERMOMETER $1N: 145795 BATCH NO.: 94165 EXAM END: 11 03 SEARCH UNIT: 45' / SHR EXAMINATION SURFACE: DID E OD MATERIAL TYPE: O CS a SS OTHER N/A Lo

REFERENCE:

TOP DEAD CENTER AXtAL SDAN SENSITIVITY (dB) 56.0 Wo

REFERENCE:

WELD CENTERLINF CIRC SCAN SENSITIVITY (dB) 63.0 PERFORMED INDICATIONS BRANCH CON ~ YES NO YES NO co w oneur 1 WITH FLOY/ X X { 2 AGAINSTFLOV/ l j l l l l l AX1AL: X p i e X j X t { 3 UPSTREAM o CIRC CW: CENTERUNE 4 DOWNSTREAM X w 6 UPSTREAM X X { 6 DOWNSTREAM CIRC CCW: X 7 L-WAVE BASE METAL X p,,, 8 0THER _ N/A X MAX l lNDICATION L (in) FROM REF W (in) FROM REF SWEEP READING EXAMINATION AMP i ( I L1 L MAX L-2 W.1 W-MAX W-2 SW1 SW. MAX SW-2 % DAC NRI N/A REMARKS: Scans nerformed at osin level below reauired scannino sensitivity in order to maintain a 10-30% avernoe ID noise level. No examination was performed downstream due to the branch confiouration. The upstream examination was limMed to L*= 2.4" to 7.2" due to adjacent circumferential weld, overlay, and weld 10 plate. (Refer to Exam plan.) / ' A !) 19-Zh H b2[-9[ 0 3 -36 0 ( n -- NER LEVEL DATE UTlWTY LEVEL il DATE 51045-b e J-# 74" PAGE: 4 OF: 8 " ~ GE REVIEWED BY LEVEL DATE ANilRt; $ 4w / DATE v 1

atcwusosamwr sas> NG-95-2236 Page 31 of 52 1 [ m..$..r....m .M ULTRASONIC EXAMINATION DATA SHEET -GE Nuclear Energy-(M ANUAL PIPING) SITE:JUANElsRNOLD UNIT: 1 CAllBRATION SHEET NO.:_ C M:075__ _ _._ _ PROJECT NO. 1DX36 TASK:1FJPV l DATA SHEET NO.: DM-074 PROCEDURE NO.: UT-DAC-102VD REVISION: 0 FRR N/A SYSTEM:.RHR EXAM SURFACE TEMP: ._Z4

F COUPLANT:

HUMEX EXAM START: 11:05 WELD ID: RHB J002 THERMOMETER $!N: 145795 BATCH NO.: _94165 EXAM END: 11:10 SEARCH UNITr 60* / RL EXAMINATION SURFACE: OID EOD MATERIAL TYPE: O CS E SS OTHER NIA Lo

REFERENCE:

TOP DEAD CENTER AX1ALSCAN SENSITIVITY (dB) 77.4 Wo REFERENCE! WFLD CENTERLINE CIRC SCAN SENSITNITY(dB) N/A PERFORMED INDICATIONS BRANCH CON. YES NO YES NO COMONENT l X X 1 WITH FLOW l l l AXtAL: l X i , 2 AG AINST FLOW p i 3 UPSTREAM X t { 4 DOWNSTREAM 0 ,,t, CIRC CW: CENTEWNE X w j X { 6 UPS1 REAM CIRC CCW: 1 6 DOWNSTREAM X 7 L-WAVE BASE METAL X p,pg 8 OTHER N/A X MAX INDif;ATION L (in) FROM REF W (in) FROM REF SWEEP READING EXAMINATION I~' NO. L1 L-MAX L-2 W-1 W-MAX W-2 SW.1 SW-MAX SW-2 % DAC NRI J N/A REMARKS: Scans nerformed at caln level below remared scanism sensitivity in order to maintain a 10 30% avernoe 10 noise level No examination was performed downstream due to the branch confiauration. The upstream examination was limited to *L*= 2 4" to 7.2" due to adiacent circumferential weld, overlay, and weld 10 plate. (Refer to Exam plan) r f\\ 0 6'> lSY [ y2.9-9C k0 330AT w LEVEL DATE UTILITY LEVEL 81 DATE 8 *h

Y iT / 7r-PAGE-10F: 8 GE REVIEWED BY LEVEL DATE ant! REVIE f

DATE

Attachment to NG-95-2236 Page 32 of 52 3 RECORD OF NONDESTRUCTIVE EXAMINATION LIQUID PENETRANT PT-1 b TRAVELER NO INDEX ITEM A CMAR NO A MIF STEP DCP/PMP NO T4 70 r T mp. GIR NO A ISI NO aso39 AR NO A M6 - TOO 2. DWa. OR ISO NO l.2.- /4 COMPONENT OR SYSTEM THICENESS, 9dd PROCEDURE No 2162.1 REV 2-ACCEPT STD

6. 7. % 7 4

BLACK LIGHT INTENSITY (pW/cm ) A 2 LIGHT METER ID/DUE DATE REINSPECTION INITIAL INITIAL INSPECTION REMARKS i INSPECTION REMARKS REINSPECTION DEFECT ) ITEM DEFECT CODE

1 CODE
4 ACC REJ (SIZE / LOCATION)

ACC REJ (SIZE / LOCATION) l l E "Lr AN j ~l h T l l j 1 e s 1 ODEFECT CODE LA - LAMINATION, O - OTHER P - POROSITY, R - ROUNDED, LI - LINEAR INDICATION, ]- (IDENTIFY) MM4( Weld Examined COMMENTS / SKETCH kk Previous Inspection Data Review o S Yes O No O HA Inic. PENETRANT MATERIALS: Magnaflux MATERIAL TYPE BATCH 6f(C-5 %L o7/( CLEANER ML- //M6 BBLCO3 PENETRANT 5XD-NF 90Fo7A DEMONR R#8-3ooz. ~ k -k8 [ l EXAMINER: dAAHld/ J KEVEL/DATEI 330M REVIEWED BY: =% Lt.vt.L I SI /DATE ni M-M 9J' REVIEWED BY: g_ i Lo s) mISmx w E 6r 9 P.,. o o.A. rorm 2I62.1-1 <0c. 343

Attachm:nt to NG-95-2236 Page 33 of 52 ULTRASONIC CAllBRATION DATA SHEET 9 y GE' Nuclear Energy (MANUAL EXAMINATION) SITE:_DUANE ARNOLD UNIT: 1 CALIBRATION SHEET NO.: CM-074 PROJECT NO.: 1DX36 TASK: 1 FJPV LINEARITY SHEET NO.: L-015 PROC,EDURE NO.: UT-DAC-102VO REVISION: 0 FRR: N/A instrument STAVELEY S C 136 66l Search Unit KRA K10900 50" 1 50 um. _ 45'I SHR 40" mensecu. sen. see een ancemoos ino e,a w e

o.

Cabla RG-174 6' 2 Type Longes No etconnecem / Calibration Standard IE-54 SS 980" 70 v SenalNo. Malenal Thesansen Terest Couplant HUMEX 941es Thermometer 14579s EsMR h senes peo. Type DAC INSTRUMENT SETTINGS l DAC Construction Sensitivity LIL, 1O M O TC W FN Gain - Axial Scan 49 0 Gain Axial Scan 49 0 g g g pl l l l l l A 80, M 70 i \\ l i I Gain -Cire. Scan 56 2 Gain -Cire. Scan 56 2 p g L \\ g 1 \\ Pulse 222 ns Range 5 00-T 40 \\ 8/ Damping 500 ohrns Delay M U 30 g C D 3 E Rep Rate 4 0 KH7 Velocity .126 in/us E 10 Fitter 2 Sweep N/A Frequmy 9 ?M MHz Resolution N/A SWEEP: 0 - 10 = 5 o' O ocria e met ^'r^ta av orr aack On AT Field Shnulator ROMPUS S/N! CAL-RHOM421 CAUBRATION VERIFICATION LEC NEAR SDH FA DH INITIAL CALIBRATION TIME 0828 VERIFICADON TIMES I FI'4AL VERIFICADON TIME 13 01 9 0 WELCS EXAMINED REPORT NO. COMMENTS: RHB-J002 195039 N!A ffh / 3-3*T[ X)-L# F }I~ 3-2S-if h kWNER LEVEL DATE UTtuTY LEVELill DATE _ 36b i 8464-PAGE:_Z OF:_.R__ u. _== ~r. sEvE3 ' =n _ - a" mes - >

== Attachment to WG-95-2236 Page 34 of 52 ULTRASONIC CAllBRATION DATA SHEET i@. .. W. is ~ GE Nuclear Energy (MANUAL EXAMINATION) SITE: DUANE ARNOLD UNIT: 1 CAllBRATION SHEET NO.: CM-075 PROJECT NO.: 1DX36 TASK: 1FJPV LINEARITY SHEET NO.: L-015 PROCE, DURE NO.: UT-DAC-102VO REVISION: 0 FRR: N/A instrument STAVELEY SONIC 138 7661 ^ Meest No. Senal Peo. H4 '>(~% Mohn 3 50 uut __ 60*/RL so" 029 Search Unit HARfSON12 m sa. Aa wu ir n Cahia 2fRG.174) 2(61 4 i r,. t.ae na e c=a.a Calibration Standard ir.s4 ss eso-70 v Sensi ten, umeensa Ttusen.as T.mp. Couplant Himary e41as Thermometer 14s7es smam T,,. DAC INSTRUMENT SETTINGS DAC Construction Sensitivity Gain. Axial Scan 77 4 Gain. Axlal Scan 77 4 g g -l l l l l A 60 M 70 i I I I Gain. Cire. Scan N/A Gain. Circ. Scan N/A P g 50 Pulse 100 ns Range 5 00* g U 30 Damping 500 ohms Delay no>- D 20 MN VM Nm Rep Me f 10 Filter i Sweep N/A Frequency 5 00 MHz Resolution N/A SWEEP: 0 -10 = ODEPTH $ METAL PATH Reject OFF Jack 5m WT Field Simulator: ROMPUs SM CAL-RHOM421 CAUBRATION VERIFICATION DE: N/ 13.3 t FINAL VERIFICATION Tine! WELDS EXAMINED REPORT NO. COMMENTS: RHB.J002 195039 N/A i n ,C' /1/ / p //-//7If ?>-2r-4bEI OWw J36-if uru7v uve. gg

== uve. o= I// 6 M.IY 1/LL WL J-ans-PAoe: e oF:1 mm o.7 --c e y_ _. _ _._ m., -.1

Attcchmsnt to NG-95-2236 Page 35 of 52 DUANE ARNOLD ENERGY CENTER 2* 10-YEAR INTERVAL ' R.EQUEST FOR RELIEF NO. NDE-017 I I SYSTEM / COMPONENT (S) FOR WHICH RFI IFF IS REOUESTED RBB-J006 Recirculation Bypass Weld l EXAMINATION CATEGORY B-1 ITEM (S) B9.11 11 CODE REOUIREMENT Section XI (1980 W81 ADD), Table IWB-2500-1 Category B-J, Item B9.11 requires a volumetric and surface examination which includes essentially 100% of weld length once during the ten year interval. Ill ' CODE REOUIREMENT FROM WHICH RFI IFF IS REOUESTED Reliefis requested from performing volumetric examination of essentially 100% of the weld length for j Recirculation Bypass Weld RBB-J006. IV BASIS FOR RFLIFF l This weld is a pipe-to-tee configuration which limits the volumetric (UT) coverage to a one-sided exam. This results in approximately 84% coverage of the weld length. Perfomiing a radiograph of the weld would require the Recirculation System to be drained, which would increase exposure to personnel by a factor of 1.7 due simply to the pipe being empty (170 mr/hr vs 100 mr/hr) for a total of 140 mr for the additional 16% coverage. This is the additional exposure for the examination, int tion and removal ofinsulation and shielding; it does not include any additional exposure resulting fa.a the time spent peiforming valve line-ups or system draining. Examining the additional 16% of weld length has only a small potential for increasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure. V ALTERNATE EXAMINATIONS IES Utilities Inc. proposes to perform volumetric examination cf the 84% weld length. The alternative examination coverage allowed by Code Case N-460 will also he used. VI JUSTIFICATION FOR THE GRANTING OF RFI IFF To perform an examination of the additional 16% of weld length, the Recirculation System would be required to be drained, thus increasing exposure to personnel. Examining the additional 25% of weld length has only a small potential for increasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure to perform the radiography. Vil IMPLEMENTATION SCHFDULE This relief request will be implemented during the 2*' Ten Year Interval. This weld was included in the Refueling Outage (RFO) 13 Summary Report.

Attachmsnt to NG-95-2236 Page 36 of 52 Sm _...'iik fiGE;NuciaarEn_ rg....yg REPORT NO.: ..=.x. EXAMINATION

SUMMARY

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Attachment to NG-95-2236 Page 38 of 52 e.r .... {E s ULTRASONIC EXAMINATION DATA SHEET GE NuclearEnergy' (MANUAL PIPING) SITE:_ DWWEARNOLD UNIT: 1 EPORT NO. WOO CALIBRATION SHEET NO.: CM-052 PROJECT NO.: 1DX36 TASK:1FJPV DATA SHEET NO.: DM-051 PROCEDURE NO.: UT-DAC-102VD REVISION: 0 FRR N/A SYSTEM: EECIRCULATION EXAM SURFACE TEMP: 72 'F . COUPLANT: HOMEX EXAM START: 16:26__ WELD ID: R DB-J006 THERMOMETER SIN: 145795 BATCH NO.: 94165 EXAM END: 16.30 l SEARCH UNIT: 45' / SHR EXAMINATION SURFACE: OID EOD MATERIAL TYPE:O CS s SS OTHERe N/A Lo
~~REFERENCE:~~
TOP DEAD CENTER AX1AL' SCAN SENSITIVITY (dB) 47.0 Wo REFERENCEi WFt n CENTERLINE CIRC SCAN SENSITIVTTY(dB) 57.0 PERFORMED INDICATIONS TEE YES NO YES NO couPouEnv f f 1 WITH FLOW X { { l X l AXIAL: y : AGA!NSTFLOW i i i g X t i i { 4 DOWNSTREAM 0 3 UPSTREAM X X [ CIRC CW:
~~'U X~~
cENTEWNE { 6 DOWNSTREAM 6 UPSTREAM X X CIRC CCW: X 7 L-WAVE BASE METAL X PIPE 8 OTHER _N!A y COMPONENT MAX INDICATION L (in) FROM REF W (in) FROM REF SWEEP READING EXAMINATION s AMP O. L1 L MAX L-2 W-1 W MAX W-2 SW-1 SW MAX SW-2 % DAC ( 8) NRI N/A REMARKS: j{o exarnination was performed dcen.:.e,r, due to the Tee rxntsuisu n. u Scans nerformed at osin level below required scannino sensMivRv in order to maintain a 10-30% avernoe ID noise levet. f Sf_ p-z#e .I 3.zon c 4M./Ll/- (sar LEVEL DATE LE d all' WI DATE M ~ f1' 7d' PAGEL.1_. 0F: 7 GE REVIEWED BY LEVEL __ ' DATE ~ ANil REVM*ew [ DATE
Attachment to NG-95-2236 Page 39 of 52 i
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ULTRASONIC EXAMINATION DATA SHEET 1 ) GENoclear Energy (MANUAL PIPING) l ~ l REPORT NO.:_lM0A2 SITE: DUANE ARMQLD UNIT: 1 CAllBRATION SHEET NO.:ly 053 PROJECT NO.: 1DX36 TASK: 1FJPV l DATA SHEET NO.:_DM-052 UT-DAC-102VO REVISION: 0 FRRt N/A PROCEDURE NO.: SYSTDt: REClRCULATION EXAM SURFACE TEMP: 72 'F COUPLANT: HUMEX EXAM START: 16 46 WELD ID: RBB-J006 THERMOMETER $lN: 145795 BATCH NO.: 94185 EXAM END: 16 50 SEARCH UNIT! _80* / RL EXAMNATION SURFACE: Olo EOD MATERIAL TYPE: O CS a SS OTHER! N/A La REFERENCEr TOP DEAD CENTER AXIALSCAN SENSITMTY(dB) 78 8 Wo REFERENCEr WELD CE A TERl!NE CIRC SCAN SENSITMTY(dB) N/A PERFORMED INDICATIONS TEE YES NO YES NO came=T 1 WITH FLOW X X { 2 AGAINSTFLOW l i J l ^*'AU X F X t { 3 UPSTREAM 0 CIRC CW: C8"'"' 4 DOWNSTREAM X w 5 UPSTREAM X { 6 DOWNSTREAM CIRC CCW: X 1 T L-WAVE BASE METAL X p,py 8 OTHER N/A X MAX INDICATION L (in) FROM REF W (in) FROM REF SWEEP READING EXAMNATION AMP II~8I L-1 L MAX L-2 W1 W-MAX W-2 SW-1 SW MAX SW-2 % DAC NRI fJ/A a REMARKS: ei----c ral 60* RL exe. -# 1,i. was n-iiermed to ;m-eee exar.Jr L. covermoe. r A ex...be, was 's.,d 4Gw. e.em due to the Tee connouretian. A f lf I i D.LIW/ E 3zoAs-ME flkd 4-34r 97 D PAGE10F: 7 1 oc neviewco eY level. [DAte ANil @"'/ DATE ,.,,,m,
Attachment to NG-95-2236 i ~ Page 40 of 52 RECORD OF NONDESTRUCTIVE EXAMINATION } LIQUID PENETRANT PT-1 [ CMAR NO MlA MIF STEP Mlh DCP/PMP NO N/A TRAVELER NO Nlb INDEX ITEM NJA GIR No hllh ISI NO 19504% AR NO Mlh Te: p. (c'2. r COMPONENT OR SYSTEM RER-3*OO(o DWG. OR ISO FO l. 2. -Zj A THICKNESS. 3'M PROCEDURE NO 2162.1 REV 1 ACCEPT STD 6.7./47 MN LIGHT METER ID/DUE DATE MlA PLACK LIGHT INTENSITY, (pW/cm ) AllA i 8 I INITIAL INITIAL INSPECTION-REINSPECTION INSPECTION REMARKS REINSPECTION REMARKS ITEM DEFECT DEFECT CODE
~~CODE' ACC REJ (SIZE / LOCATION)~~
ACC REJ (SIZE / LOCATION) No RscoR.D404-c. l l Rbb I. kilA Sc DICATre nic. NlA NIA N/A I N/A sm f. MlA I l ufA - ' DEFECT CODE P - POROSITY, R - ROUNDED, LI - LINEAR INDICATION, LA - LAMINATION', O - OTHER (IDENTIFY) ] COMMENTS / SKETCH foO % Weld Examined Previous Inspection Data Paviewed [ Yes O No O Init. PENETRANT MATERIALS: Magnaflux I MATERIAL TYPE BATCH CLEANER SKfl-M C 93Ko I k. PENETRANT SML).lf/$ @ ALFA 3 ( DEVELOPER RRb-hlF 9nCo1P a6 EXAMINER: b
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s fmg b. w 4[3 f9I~ REVIEWED BY: LearL III SIGN DATE g, o. *. % M94,- ,f '/ - REVIENED BY: ^"'I S'a*= messp i o.A. Fo 2162.1-1 (Oct.'94) Pag of 7
IRML'WelTF tCo NG-95-2236 Page 41 of 52 ULTRASONIC CALIBRATION DATA SHEET m; y GE Nuclear Energy (MANUAL EXAMINATION) SITE:__DUlsNE ARNOLD UNIT:_1 CAllBRATION SHEET NO.:_CM 152 PROJECT NO.: 1DX36 TASK 1FJPV l LINEARIT1r SHEET NO.: L-015 PROCEDURE NO.: UT-DAC-102VO REVISION: 0 FRR: N/A Instrument STAVELEY SONIC 136 7661 u, uoo.i = s= Search Unit MBA D19642 75" W Aaewuco.R 45* / SH 95" usz. iac m io .a. uoni u.os.co., s.. N. se. e. Cable RG-174 6' 2 Type Longm No etConnectors s Calibration Standard IE-57 SS .337" 68 y seral No. Metenal Thecknees Tony Couplant HUMEX 9416s Thermometer 145795
~~typ, astch No.~~
benal No. DAC INSTRUMENT SETTINGS 100 DAC Construction Sensitivity 90 4/R .t O NC7C}tf 5 1 i a Gain - Axial Scan 40 6 Gain - Axial Scan 40 6 I l f\\ l ' ' l l l l l P k I I I I I Gain - Cire. Scan 50 0 Gain - Cire. Scan 50 0 60 L (\\ 50 8/fI Pulse 222 nm Range 2_00" 4o U \\ Damping 500 ohrns Desay 227" , gg7 E Rep Rate 4 0 kH7 Velocity .124 in/us 10 l N Filter 2 Sweep N/A Frequency ? ?S MHz Resolution N/A SWEEP: 0 10 " O oerra a meta'r^'" %m OFF ua oa Er Fleid Sirnulator ROMPUS S/N CAL-RHOM-021 CAUBRATION VERIFICATION REFLECTOR: NEAR SDH FAR SDH IN111AL CALIBRATION TIME 08:55 VERIFICATION TIMES MAX AMPUTUDE: 24 % 10% 4 S 8 08 15 47 N/A Fir 4AL VERIFICATION TIME 18 25 6 WELDS EXAMINED REPORT NO. COMMENTS: 1 RBB-J006 195043 N/A 8 i A! o -zau - t ins c %MWam 4-a w LEVELitig f, DATE NER LEVEL TE UTI /u - Y PAGE:_f _, OF! 7 + .. / DATE ANil REVIEW DATE GE REVIEWED BY LEVEL
NG-95-2236 Page 42 of 52 y ? ULTRASONIC CAllBRATION DATA SHEET .g GE Nuclear Energy (MANUAL EXAMINATION) SITE: DUANE ARNQLD_ UNIT: 1 CALIBRATION SHEET NO.:_CfA.Q.5.3 l PROJECT NO.: 1DX31 TASK: 1FJPV LINEARITY SHEET NO.: L-015 PROCEDURE No.: UT-DAC-102VO REVISION: 0 FRR: N/A Instrument STAVELEY SONIC 136 7661 u.nue.co., uw.i Na s.n.i No HARISO H4029 7/ sex 50)in 3 50 ung 60* / RL_ 60" Search Unit u.nocw.,Nic s.,e No. so. e.., anowum. inc nno e oni Cable 2(RG-174) 2(6') 4 T yp. L.ngtn No. of conn.ctors / Calibration Standard tE-57 Sili. 337" 68 r 6.nal No. u.t.nal Theckn.ss T.,rp. Couplant HUMEX 94165 Thermometer 145795 D.tch No. 3,nal No 1yp. DAC INSTRUMENT SETTINGS DAC Construction Sensitivity y 79 j l l 80l l l l Gain Axial Scan 78 8 Gain-Axial Scan 78.8 A p i l l l l i I I Gain. Cire. Scan N'A Gain. Circ, Scan N'A g Pulse 100 ns Range 1.00" T 40 U 30 Damping 500 ohms Delay 728" Rep Rate 2 0 KHr Velocity .232 in/us Filter 1 Sweep N/A SWEEP: 0 -10 = Frequency 5 00 MHz Resolution N/A J O DEPTH $ uETAL PATH OFF M SR ET Field Simulator: ROMPUS S/N: CAL.RHOM.421 CAllBRATION VERIFICATION REFLECTOR: NEAR SDH N/A INITIAL CALIBRATION TIME 09:22 VERIFICATION TIMES MAX AMPLITUDE: 80% N/A S P: 60" 16 4 .j FINAL VERIFICATION TIME 18:20 WELDS EXAMINED REPORT NO. COMMENTS: RBB-J006 195043 N/A r A [) M /E. +Mr o -2 & I smr R' LEVEL DATE UTI LEVEL il: RF,VI DATE N [ 4 PAGE: 7 OF: 7 t GE REVIEWED BY LEVEL ' DATE ANil REVIEW { "'"j DATE
PIPE FLOH ) TEE 2 2 C I O a \\ g E e1 Q as4 Z 7 (IN.) ~ 2 '(IN.) 9a 5 -2 -2 E R COU1=0.8371 COU2=0.5468 Y(IN.) _g _g g g i y(IN.) ggg x I SET l l SET I DEP I l DEP 50 l MP l I Mp Ch[ l TOF l l TOF MG l FAN l_ l FAN d$% l GATE I I CATE I STEP I I STEP 8 Eb'I T MAMERAY UTILITY LEFT RIGHT TOP l PRINT EXIT i EXIT f ( n e.LA ION AA . i _3 c.16B..* 6 l 14;43.:j CAL. s
Attachment to NG-95-2236 I DUANE ARNOLD ENERGY CENTER. Page 44 of 52 _ 2* 10-YEAR INTERVAL l . REQUEST FOR RELIEF NO.'NDE-018 l l I: SYSTEM / COMPONENT (S) FOR WHICH RFT iFF IS REOUESTED 1 ~ HEA'-CB-2 Residual Heat Removal (RHR) Heat Exchanger Nozzle Weld l 'l ' EXAMINATION CATEGORY C-B. ITEM (S) C2.21 .l i 11 CODE REQUIREMENT ) ~ Section XI (1980 W81' ADD), Table IWC-2500-1 Category C-B, Item C2.21 requires a volumetric and surface 1 - examination which includes essentially 100% of weld length once during the ten year interval. r 1 - lil ' CODE REOUIREMENT FROM WHICH RFT.iFF IS REOUESTED - I eliefis requested from performing volumetric and surface examination of essentially 100% of the weld length R ' for RHR heat exchanger weld HEA-CB-2, ,IV ' BASIS FOR RELIEF This weld is a nozzle-to-shell configuration which limits the volumetric (UT) coverage to a one-sided exam. . The nozzle is located next to the tube sheet flange which further limits the volumetric examination coverage, resulting in approximately 71 % UT coverage of the' weld length. Performing a radiograph of the weld requires . draining the RHR System and removing the pipe or opening the tube sheet to provide access to the inside _ diameter. (Removal of the tube sheet is not an option because several tubes would be required to be removed along with the tube sheet.) Draining the pipe increases the dose rates in the area by a factor of 1.7 (20 mr/hr vs 12 mr/hr). This results in additional personnel exposure of 50 mr to obtain the radiograph, including the installation and removal ofinsulation and shielding. In addition, removing the pipe from the nozzle would require the pipe to be cut in two places and then rewelded which would take about 102 hours. Additional examinations would then be needed for the welds that reattach the pipe to the system. The total dose for the project would be approximately 2 R. The additional 29 % coverage would provide only a small potential for increasing plant safety.while greatly increasing expenditures of plant manpower and radiation exposure. .V ALTERNATE EXAMINATIONS 1 IES Utilities Inc. proposes to perform volumetric examination of the 71% weld length. The alternative examination coverage allowed by Code Case N-460 will also be used. VI JUSTIFICATION FOR THE GRANTING OF RET 3FF i ' Examining the additional 29% of weld length would require draining the RHR System and removing the pipe. This would greatly increase personnel radiation exposure while providing only a small potential for increasing plant safety.' ^VII IMPI FMENTATION SCHFnULE This relief request will be implemented during the 2"d Ten Year Interval. This weld was included in the L Refueling Outage (RFO) 13 Summary Report.
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Attcchm:nt to NG-95-2236 Page 47 of 52 m m,. 1 hh kl- $E&y;l;^ f I ~~ I w EXAMINATION
~~SUMMARY~~
SHEET REPORT NO.: 2 Nuclear Energy tesosa PROJECT: DUANE ARNOLD PROCEDURE: UT-DAC401VO .REV: Q._ FRR: N/A JDM - [3 A SYSTEM: HEAT EXCHANGER A WELD NO.: HEA-CB-2 .J/A i t4/A CONFIGURATION:A072L E - SHELL B'A REV: N/A FRR: N/A N/A "'^ EXAMINER? E.MAZYCK LEVEL: it j E MT opt E UT O vi EXAMINER? P. MicHELSON LEVEL: 11 O CIRCUMFERENTIAL l EXAMINER? N/A LEVEL: N/A O LONGITUDINAL E OTHER NO771 f* SHELL DATA SHEET NO.(S):. DM-oo3 CAL SHEET NO.(S): cu-oos MT-002 Dunng the mr.nual ultrasonic examination of HEA-CB-2, no reportable indications as per ASME Section XI were detected utilizing a 4S' shear wave st ore n irnit. This examination was performed from the shelli side of the weld only due to the nozzle to shell configuration. The ultrasonic examination was restricted in the proximity of the adjacent flange weld. A magnetic particle examination was performed resulting in no reportable indications. The magnetic particle examination was restricted to.30" from the weld too from L = 24.0" to L = 29.3* due to the proximity of the flange weld, Composite ultrasonic examination coverage of HEA-CB-2 is 71% of the Code required volume. i j l O ExAu courLETE E,AnTiAtty Exam.Eo gEx. cam a cO ueNTsi O g,gEIN COMBINATOON wtTH ADomoNAL DATA SP8ETE N#A NO.OF REcoflDABLE WDICATioNs. O ccMPAmEn To: Orse 5 :: aEconTw: rex e2.o4g.os4 5 No cuANoE TOTAL cosE ExAMMATloN RESuLTs ;, ,E acchr 4ABLE EPTABL[ REPO9 TABLE MolCATIONs. 0 010_ *AAN REM Un kC N/El h Y 3 4-9C" & f,{,f yq[ I b/ Y
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PAGE 1 0F: 6 GE REVIEWED BY LEVEL DATE ANilREViQN / DATE 4 j S J
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NG-95-2236, Requests for Relief from ASME Section XI requirements:NDE- 012 Through NDE-018

Contents

Text

Subject:

References:

Dear Mr. Russell:

SUMMARY

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SUMMARY

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SUMMARY

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