ML20078P192

Viewgraphs Entitled Mitigation of Intergranular Stress Corrosion Cracking

ML20078P192
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Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	10/28/1981
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ML20078P191	List: ML20078P192
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FOIA-83-401 NUDOCS 8311070033
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{{#Wiki_filter:_ _ - _ l M i DATE: OCTOBER 28, 1981

SUBJECT:

MITIGATION OF IGSCC AGENDA: 4 INTRODUCTION 8 IGSCC PHENOMENA 8 CRACK HISTORY 6 IHS1 PROCESS - LW~ % N %=A c 5 JAFAN EXPERIENCE 6 EFRI PROGRAM t SHOREHAM 8 PHASE 1 e PHASE 2 INTERFERENCES EQUIPMENT CRAFT SUPPORT 4 COST e COST /EENEFIT G SCHEDULE t OXYGEN CONTROL TECHN10UES g1 33 830810 HAFNER83-401 PDR b'.--

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SUMMARY

OF STRESS INDEX FACTORS l SHOREHAM e WELDS BELOW FACTOR 1.0 LDOP A 24 LOOP B 12 e WELDS FACTOR 1.0 To 1.1 LOOP A 11 LOOP B 7 e WELDS FACTOR 1.1 To 1.2 LOOP A 2 LOOP B 1 e WELDS FACTOR 1.2 To 1.3 LOOP A 3 LOOP B 4 e WELDS FACTOR 1.3 To 1.61 LOOP A 1 LOOP B 2 l10TE: TABULATION ONLY COVERS WELDS FOR IHS1 CONSIDERATION

l lHSI JAPANESE PLANTS FUKUSHIMA 2 AFTER OPERATION MAY 1979 FUKUSHIMA 5 40 0F 12" BEFORE Om RATION 8/77 10 0F 22" AFTER OPERATION 31 0F 28" FUKUSHIMA 6 BEFORE OPERATION 10/78 FUKUSHIMA 4 BEFORE OPERATION 11/77 HAMA0KA 2 BEFORE OPERATION 10/77 TOKAI 2 BEFORE OPERATION 14/77 G NO CRACKS DETECTED TO DATE OH IHS1 WELDS l E

UNITED STATES PLANTS C0MMITMENT TO IHSI CONTRACTOR l SUSOUEHANNA 1 AND 2 IHI ZIMMER IH1 De 9 J _ %. b

• 2 1

PHASE 1 COMPLETE (L ] LA SALLE 1 AnD 2 FERMI 2 PEACH BOTTOM 2 AND 3

BWR ISGCC OWNERS GROUP lHSI PROJECT RESULTS SIGNIFICANT IGSCC BENEFIT EXISTS FOR IHS1 TREATED PIPE e FACTOR OF 10 IMPROVEMENT OVER REFERENCE =)p fm u 4o p. o t PROCESS VARIABLES OPTIMlZED 5 LABORATORY TEST e RESIDUAL STRESSES ARE MADE COMPREHENSIVE ON PIPE ID OF IHSI TREATED PIPE COMPRESSIVE STRESSES MEASURED FOR 4 INCH, 10-INCH AND 16 INCH PIPE ANALYSIS PREDICTS COMPRESSIVE STRESSES t NO ADVERSE EFFECTS OBSERVFD FROM IHS1 TREATMENT f MOCK-UP DEMONSTRATES FEASIBILITY e PROCESS PARAMETERS ESTABLISHED

NEDV-25146-4 s Table 3-6 PIPE TEST LAB RESULTS in. PIPES lcad* Pipe Identification CenJition MPa (ksi) Hga_t No. Status 71 pes Tested belou Stress Level Causing Plastic Shakedown cf kesidus! Stress A. RS-01-2 F(ference 194 (2E.1) 0463t 1st Tailure - 6C7 cycles h 2nd Failure - 204 accit sonal cycles RS-08 IHS1 194 (2 8.1) 0-336 On test - 6020 cyt }csD RS-09 Reference 194 (26.1) Ml929 1st Tallure 1665 cycles RS-10 1HSI 194 (29.1) M1999 On test - 1666 cycles RS-ll Reference 194 (28,1) 181190 1st Failure - 655 cycles 1 RS-12 IMS! 194 (28.1) 181190 On test - 1362 cycles RS-13 IHS1 (ung:cund) 194 (28.1) 04236 On test - 15S2 cycles E4-03A Reference 211 (30.6) 04F36 1st failure - 573.veles 2nd failure - SbJ rysles RS-07 IHSI 211 (3C.6) 0483E On test 6406 rysle* RS-03 LTS 211 (30.6) 04836 ist Failurt - 909 cycles C 2nd Failurc - 3251 cycles RS-04 LTS - IEsl ll (30.t) 04E 3t On test - f+00 ryrles 2 Pipes Tested at Stresses Caustnr Plast te Shakedesm of Residual Stres, E4-Ot Rc' er enc e 228 (33.1) D4636 18t Failure - 158 rscles 2nd Failure - 170 cycles RS-02-2 IHS! 225 (33.1) 04836 Failed - 472 cstics E4-02 16 Cycles + IHSI 226 (33.1) 04836 Failed - 1206 cvries i RS-Cl-1 Reference 254 (36.9) 04836 railed - 165 ru le* RS-02-1 lHS1 254 (36.9) 04836 Failed - 2 io n r.: s. 127 cy41e. RS-OL Reference 259 (37 6) M1989 Failed - 153 cvtle, RS-35 INFl 259 (37.6) M1999 failed - 421 systrs 'Inslucen internal pressure stre s Does not snelude 6ST cycles curing whar t pape was underloaded 33?. 'LTS - Low tennerat ure sensit s rstion 3-19 ~ ~

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.hvL as 7..v w-- 500 : 50*C 1. Pipe Oute: Surface Te=perature 2. Mini =u= Throui;h-Wall Tc:pera:ure Dif f erence (AT) 300*C 3. Minicus Vi2th of Zone F.eated to LT Mini =u: 1.5 5 (R = F.adius and Thi'cknes s ) t - 4. Mini =u: Distance f rc= Weld Center := Ecundary 15== (0.6 in.) or t/2 (whichever is larger) of LT Mini:u: 0.7 :2/c secenes 5. M =.=u:..nea:=g .1=e ther=21 diffusiv :y, (o t = vall thickness) 3 to 4 kH: 6. Fre:;uency 3 E Mini =u= 7. Indu :ica Ceil Lenj;th (E = pipe radius, t= vall thickness) 0.5 =/see 8. Mini u= Vater velocity O p e.

t 6-4 80 g E q g,c q ?. i -~ 3x 200 2 2 N U 20 A 100 /. N O O d 20 f too c-3 o O AXt AL STRE SS O A2IMUTH z 9 6 HOOP STRESS O AZIMUTH 200 g E 40 0 AX t AL STRLS$ 90 A2IM UT h ~ 3@ U A HOOP STRESS 90 A ZIM UT H E e s 60 '00 g C O l I l l 1 J l 'm u 80 -- 0.8 0.0 0.4 0.2 0 0.2 0.4 0.0 0.8 lin.) l I I I I I I 1 2.0 1.5 1.0 0.5 0 0.5 1.0 1.5 2.0 iem) g DISTANCE F ROM FuslON LINE ' ld 14-02, 4-Inch, As elt ed, Inside Surface Figure 3-6. -e Residual Stress, Strain Cage Residual Stress Data D si e

t 8 e l (_ IN DUCTCN Colt ] '.N E L e r l I T d AXlAL 90 0 h 0 ~ O HOOP 93 d AXI# L 0 b 0 to O HOOPO f +- im w C to O 23[- / 3 / 100 1 e t / 2 2 33 6 / b-4 o /- pg z E O 4o / O E M SO OM ( U c O u 63 8 o v ago u I I I I I I l I 70 1.5 1.0 0.5 00 0.5 1.0 1.5 2.0 2.5 3.0 J.5 len.) 1 I I I I f I I l i I I I I g i 4.c 3.0 2.0 1.0 0 o 1.c 2.0 3.c 4.0 5.c $0 2.c s.O EO tem) DISTANCE F ROn' WELO FUSION Li'iE l Figure 3-5. Weld I4-03, 4-Inch, tield + IH5I, Inside Surface Residual Stress, Strain Cage Residual Stress Data I I E l t J 1 6 k L

o o. l WFLD W SS ALLOYEDO go 400 ? ~ 3 m O C* A Ziu UT s 2 e 5 0 90 AZivuTH 200 5 O 180* AZlVUT H h E ~ d 270 A 2 t M UT H h N u n 3 100 E z z 2: 9 O 200 G w E 4: O E w soo a O O u u I l l I l 'l I l l l_ { I 400 g 5.0 4.0 3.0 2.0 1.0 00 to 2h 3D 40 5.0 (m.) 12.7 102 7.0 5.0 2.5 00 25 5.0 71 102 12.7 tem) DISTANCE F ROM FUSION LINE Figure 3-11. Weld 10-6, 10-Inch, As-Welded. Alley 600 - 304 SS, Inside Surface Residual Hoop Stress, Strain Cate Residual Stress Data 4 e -

] i I i 1 i l l l i WELD A L LO Y 600 / 33433 ~ 00 r CG C 2 L 9 -,200 2 y 70 9 w O O ,o r 70 ~ 7M 2 } 5 4 3* 2 d O U O U 63 '.c O c AztMUTH m o 40C p, w <j so O 93 AziMuTu E 8 O iso AzwuTu ~ u im I I l I l l I ) I I 120 3.0 2.0 1.0 0 0 1.0 2.0 3.0 4.C lin.) l 1 I i 1 1 1 1 l l 9.C 6.0 3.0 0 0-3.0 E.0 w.0 (cm) DIST ANCE FROM F USION LINE Figure 3-14. L' eld 10-7, 10-Inch, Ueld + IH5I, Alloy 600 - 304 SS Inside Surface Hoep Stress, Strain Cage Residual Stress Data ge l

~ w-15 O 20* AZivuTH.caouso .s0 go o siO* AzivuTH.usonouso ? 3 i O 200 AZIMuT H, GROUND g,o z Q 250* AZIMUTH.uNGnOUND O o 40 a a ~ 0 z 5 v. 20 0 0 g 20 r> I 5 N 40 o d 5 z G 9 m m 60 O { 10 - 80 8 o O I I 15 O 0.2 0.4 OE CE 1.0 1.2 1.4 6 (m.) 0 0.5 1.0 1.5 2.0 2.5 2.0 3.5 4.0 (cml DISTANCE F ROM F uSION LINE Figure 3-19. Veld 16-01, 16 Inch, As-Welded, Inside Surface Axial Residual Stress, Strain Cage Resideal Stress Data ~. e

v i i WELD 60 40 O 80* AZIMUTH. GROUND. 10 0 2 2 2 e O 350 A 24 M LIT H. UN G R OUN D o O 170 A ZI MUT H, UN G R OUND 200 9 8 7'O A ZIM UTH, G R OUN D 6 m 2o r 100 0 'O ~ _f 100 } 20 { o o G S U 200 G U ~ e U ~I 3CX) u i ! i l I I I l I g 1.0 0 ' 1.0 2.0 3.0 4.0 5.0 6.0 lin.) l 1 1 I I I l I I l 3.0 0 0 3D 60 9.0 12.0 15.0 fem) DIST ANCE F ROPA F UStON LINE Figure 3-22. Weld 16-02, 16 Inch, Welded + IHSI, Inside Surface Residual Hoop Stress, Strain Cage Residual Stress Data e O ,o h

4 - o SNPS IHSI WELDS ~ SNPS CAtlDIDATE WELDS 90 (PHASE 1) 4 INCHES AND LARGER i t 3 j IHSI NOT FEASIBLE 4 ACCESSIBILITY 1 'e APPL 1CAEILITY / t{ 4 i ( 1 lHSI WELDS FEASIBLE y l 7ct 1 I. I

) 4 TABLE 3-1 SPECIFICATION OF IHS1 EQUIPMENTS i Di=ension Weight Quan-Capacity WxLxH in Ib. tity 1 1 Receiver panel 2'-2"x3'-8"x5'-6" 1,100 1 4160V 'i 5'x5'x5'-4" 4,400 1 750KVA 4160/3300v a 7 2.Transfor=er a t 3 Motor panel 5'x4'-1"x7'-10" 3,300 1 4'-S"dx6' 10,000 1 400KVA rating 10:in. 4 Motor-Generator set 800Vx16x3600H: jj u h g 5 Main Circuit panel 4'x4'-8"x6'-8" 2,200 1 l ~ 2'-8"x3'-4"x7'-8" 1,800 1 ec 6 Control panel 1 u. 7 Sub-control panel 2'x1'8"x4' 260 1 1 8 Selecting panel 6'x2'x4'-8" 550 1 9 High frequency 2'x1'-6"x2'-6" 330 4 2500KVA, 800Vxid" condenser J 10 High frequency l'-6"x1'-S"x1'8" 330 4 2500KVA, 800Vx16 transfor=er 11 Heating coil 4"6 % 28"! t l l 12 Co-axial cabic 2"4 x 200' 1 4 170' 2 3 200' 2 1500Vx500Ax3600Hz c a I Z w 13 Ficxible cable 1-1/2"dx46'x4P 330 4 1500Vx3000Ax3600H: x oa l (. 14 Header for cooling l ' - 6 "x1 ' -6 "x1 ' - 8" 4 vater 15 Hose for cooling 1-1/2"d x 47' 4 2"d x 40' vater l 16 Header for coil l'x2'x8'x2P 60 6 i cooling 1 17 Tank for MC cooling 6'x6'x6'-8" 2,200 1 1500 gal. a I Y 18 Tank for coil ditto 2,200 1 1500 gal. a cooling 1 u l j 19 Pu=p for M' .ooling I'-6"x5'x2' 660 1 80 gal./ min.x70 psi 0 5.5kvx220Vx60H: e 20' Pu=p for coil 2'x5'x2' 900 1 185 gal./=ai.x130psL c c 30kvx220Vx60H: g ,o cooling J 2x Pu=p =otor panel 2'x1'x3' 1 l Cont'd on next page. t - - -- - -., ~..

Dimension Weight Quan-Capacity NO-IEC L' x L x H in Ib. tity e [y 22 Tc=perature recorder '2'x2'x2'-4" 70 2 6 pens 5E 120Wx110Vx16 53 %? 23 Ther=occuple 1 set CA (alumel-chro=el) U -a E @ s5 24 Co=pensating wire 1 set 25 Du==y spool 24"4 x 6' 3,300 1 26 Cc==unication syste: 1 set PCV ** PCV PCV +4 IHSI Head-quarters ~ .8 27 Control cable e w 25 Junction box l'x2'x6" 4 1 l l s 9 l i I. 1 I l i

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o O LONG ISLAN D LIGI-{ TING CO M PANY 7 sr q w ' SHOREH AM NUCLE AR POWER STATION , <. w a..c., : r.. P.O. E4O X 618. N ORT H C O U N T R Y e4 0 A D

• W A DIN G RIVE R, N.Y 117182 SNRC-727 July 7, 1982 Mr. Harold R.

Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Com:nission Washington, D.C. 20555 InductionHeatinhStress Improvement Prograr Shorehar Nuclear Power Station - Unit 1 Docket No. 50-322

Dear Mr. Denton:

This letter is to inform you that the Induction Heating Stress Improvement (IHSI) Process will be perfcrmed on selected welds in the Recirculation System and the Reactor Water C1can-Up System at the Shoreham Plant. This process will substantially improve the resistance of welded Type 3C4 material to stress corrosion cracking as demonstrated by research programs in Japan and in the United States. The IHSI process and various aspects of the benefits derived were discussed at a meeting earlier this year with your staff in Rethesda. LILCO has contracted with Ishikawajima - Harima Heavy Industries Company Ltd. for equipment and services required to perform IHSI. An informal meeting was recently held at the Shoreham site with representatives from Hartford Steam Boiler Insurance and Inspec-tion Company and J. Higgins, Resident Inspector, NRC to discuss LILCO's plans for implementation of IHSI at Shoreham. Our present schedule calls for the arrival of personnel and equipment in July, at which time training and set up will commence. Impicmentation of the process on the selected we3dc is scheduled tc start on August 2, 19S2. Documentation concerning the IHSI prccess (i.e., procedures, records, etc.) will be available at the site for review at your convenience, if required. If you have any questions regarding this matter, please let us know. Very truly yours, ch. \\%pv S oO / i 624 J. L. Smitn "anager, Special Projectr Shoreham Nuclear Power Station CKS:mp cc: J. Higgins All parties _ c~ m r ~ ~ ~ .c. sc. s hhC C.- e.

~

1. 3 LONG ISL AND LIGHTING COM PANY 7 ""CO.

SHOREH AM NUCLE AR POWER STATION ____f n.o u P.O. H O X U1 Ei, N OHT H C OU N T R Y RO A D e W A DING RIVCft. N.Y.11792 SNRC-727 July 7, 1982 Mr. Harold R. Denton, Director Of fice of Nuclear Rcactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Induction Heating Stress Improvement Program Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Dear Mr. Denton:

This letter is to inform you that the Induction Heating Stress Improvement (IHSI) Process will be rerformed on selected welds in the Recirculaticn System and thc Reactor Water Clear.-Up System at the Shoreham Plant. This process will substantially improve the resistance of welded Type 3C4 material to st: ess corrosion cracking as demonstrated b) research programs in Japan and in the United States. The :HSI process and various aspects of the benefits J:erived w';re discussed at a mee-ing earlier this year with your staff in Eerhesda. LILCO has contracted with Ishikawajima - Harima Heavy Industries Company Ltd. for equipment and services required to perform IHSI. An informal meeting was recent]y held at the Shcrchat site with representatives fror Hartford Steam Boiler Insurance and Inspec-tion Company and J. Higgins, F.e s id ent Inspector, NRC tc discuss LILCO's plans for implementation of IHSI at Shoreham. Our present schedule calls for the arrival of personnel and equipment in July, at which time training and set up will ccmmence. Imple. mentation of the process on the selected we3ds is scheduled to start on August 2, 1952. Documentation concerning the IHEI process (i.e., procecures, recorcs, etc.) will be available at the site for review at your convenience, if required. If you have any questions regarding this matter, please let ur know. Very truly yours, s q.h. N hw S OD / y FM J. L. Smith

• anager, Special Projects Shcrcham Nuc3 car Power S ta t i or.

Ci:S : mp cc: Higgins 'u l perties , ab 7" P by /.DO2F s ^ ^ i:'g3

LONG !SLAND LIGHTING COM PANY /. ?,.'..a ' >(T4 ,.y .....',s.. SHOREHAM NUCLE AR POWEH Sl ATION .9 ?- o. P.O. HO x 61 t*, N O F'T H C O U NT H Y H O A D. W A * ) N G HIV L H. N.Y.117 92 July 7, 1982 SNRC-727 's c. Harold R. Denten, Director Office o f ';uclear Re acte r Regulation U. S. !;u clear Regulatori Ccmmission Washington, D.C. 20555 Induction Heating Stress Improvement Program Shoreham Nuclear Power Station - Unit 1 Docket r;o. 50-322

Dear Mr. Denton:

'I h i s letter is to inferr you that the Mur t ion Heating Stress Imprccement ( I H S.' ' Process will be :crferne? c:. se'.ccted welds in tne T.ecirculaticn System and the Reactor Uater Clean-Up System at the Shcrehar Plant. This nrocers 'till substantiall'. Improve the resistance cf welded Type 3C4 ~:aterial to stress cerrcsicn crer:.'.nq ar dcmenstrated by research programs in .~ a p a n and in the u n i te:: Ftates. Thc 1HEI proccss and varicus aspects of thc benefite derived were discussed at a meeting earlier this cear with ycur staff in Bethesda. LILCO has contracted with Ishikawajima - Harima Heavy Industries Ccmpan) Ltd. for equipment and services required to perform IHSI. Im informal meeting was recently held at the Shoreham site with representatives from Hartford Steam Boiler Insurance and Inspec-tion Co.mpany and J. Higgins, Resident Inspector, NRC to discuss LILCO's plans for implemcntation of IHSI at Shoreham. Our present schect.le calls for the arrival of personnel and equipment in July, at thicr timc tral. rc t_nd set up will ec=ence. Implementation of the process cr. the selected welds is scheduled to start on August 2, 1932. Documentation concerning the IHS1 process (i.e., procedures, records, etc.) wil) be available at the site for review at your convenience, if required. I If you have any questions regarding this matter, please let us know. Very trulv..v o u r s, J q-%.  %~M l %.us.-- \\ J. L. Smith Mr.na g er, Special Projects Shorehar !:uclear Power Station u :. :. cc: J. -!i p c i n t I. 1 r rt :.:: ^ Oek .b}}