ML19220A587

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Forwards Description of Actions Util Has Taken to Eliminate Use of All furnace-sensitized Stainless Steel from pressure- Retaining Structural Portions of Primary Coolant Sys
ML19220A587
Person / Time
Site: Crane Constellation icon.png
Issue date: 06/03/1970
From: Long C
Metropolitan Edison Co
To: John Miller
US Atomic Energy Commission (AEC)
References
NUDOCS 7904230138
Download: ML19220A587 (14)


Text

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Dear Mr. Long:

Per your recent verbal inquiry, attached is a descripticn of the c.cticns Metrecclitan Edison Octnany ua. c.i w u --. w e.. u__ va= use ci au t u rz.u u s e:. n u m a stainless steel frc= the pressure retainin;; : rue: ural portions of the pri. ary ecolant systens. En:1ccure 1 and Figures 1 thrcugh 53 document in detail these actions. Ver/ trul yours, r ,' /,e ~ ~' J J., G. Miller t =el I' attachment e, s s e 0 i ' i f&' Pp 4 ,as.e g,,\\ g s_- \\.f). ge x v, \\ S'l , ~. p r **1 .cd u / n e,. /

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,M FURNACE SENSITIZED STAINLESS STEEL "I 5, IN PR ESSUR E R ETAINL';G AND ST R UCTURA L POR TIONS y./ -u gy~ TMI No s. I and 2 g j ' Qpg PRIMA 3 Y SYSTEM As a result of problems at other nuclea r stations, Met-Ed took action in the early phases of the TMI Nos. I and 2 Projects to eliminate the use of all furnace sensitized stainless steel from the pressure retaining structural portions of the primary coolant systems. A s a result, fu rna c e sensitized stainless steel was elimuu ted from the pressure retaining struc-tural portions of the reactor vessel, pressurizer, steam generator, reactor coolant piping, and core flooding tanks. The only furnace sensitized stain-less steel used in these components is in the cladding which is not a pressure retaining structural part. The specific material and fabrication sequences being used on the Three Mile Island Units Nos. 1 and 2 to eliminate furnace sensitized stainless steel can be summarized as follows: s 1. Reactor Vessel (See Figures 1,1 A, and 13) The in-core instrument penetrations in the lower head are Inconel. a. b. The closure head control rod drive penetrations are partially Inconel and pa rtially stainless steel, but are installed after final stress re-lief of the head. The primary coolant nossles do not recuire stainless steel or Inconel c. safe-ends since the piping is low alloy carbon steel. d. The welds for penetrations of the core flooding nonsles are buttered with Inconel. The stainless steel saf e-ends and thermal sleeves a re installed after final stress relief of the vessel. 1 u cs 1 8.1 o m c o

The core stop lugs are Inconel. e. f. The flow vanes are stainless steel and are installed after final stress relief of the vessel. 2. Steam Generators (See Figure 2) The primary coolant nossles do not require stainless steel or Inconel a. safe-ends since the piping is low alloy carbon steel. b. The tubing is Inconel The drain no le is Inconel c. 3. Pressurizer (See Figure 3 ) Of the eight no :les less than four inches in ciameter, seven will a. have Inconel saf e-ends and the vent nozzle will be entirely Inconel. b. The four inch diameter spray and ten inch diameter surge no::les will be buttered with Inconel. The stainless steel safe-ends and ther thermal sleeves will be ins talled after final stress relief. The stainless steel internals (surge deflection device and pressurizer c. heaterc) "ill be inctalled after final stress relief. 4. Primary Coolant Picin2 (See Figures 4A, 4B, and 4C) Nozzles 1ess than four inches in diameter will be Inconel or have a. Inconel safe-ends except that the weld preparation of the high pres-sure injection no :les will be buttered with Inconel and the stainless steel safe-ends and thermal sleeves will be installed after final stress relief. b. The 12 inch decay heat and 10 inch surge no :les will be buttered with Inconel. The attached stainles s steel piping will be welded directly to the Inconel butter layer in the field. The reactor coolant pump inlet and disenarge safe-ends will be stain-c. less steel which will be welded to an Inconel butter layer after final stres s relief. 5. . Core Floodine Tanks (Figures 5A and 5B) a. On TMI No. 1 no les less than four inches in diameter will be carben steel with weld deposited stainless steel cladding and with an Inconel safe-end. On TMI No. 2 such no :les will be entirely Inconel. EG-079 i.

b. The 14-inch core flooding :ozzles will be buttered with Iaconel. A stainless steel safe-end will be attached to the Inconel butter layer after final stress relief. EG'~0SO _3

9 t10 TE : Il0T TO SCALE COMTROL 000 DRl72 ~ PEilE TR A T 10M nun 0ER -69 TYPE 303 SS UELD DEPOSli CLAD 0lt:G SIZE - 2.765"10 Y (SEE FIGURE IB) .N1 l / 5 il / !!l. / H 7.t_ / L7 i / - It C0t:EL L. ELD UEPOSIT BLTTi!!i;G FOR ATTACHir.G SAFE-EMO AFTER ]7 l, STRESS RELIEF u L ~ PRIMARY COOLA!!T N0ZZLE - 2 OUTLETS - 36" 10 -CORE FLOOD N0ZZLES 4 li4 Leis - 28" 10 tlUMBER 2 (NOTE: SAFE-END fl0T SIZE II.50"iG REQUIRED Sit:CE P PING IS CARB0tl STEEL CLAD ~ BASE MATERIAL-p WITH STAltiLESS STEEL) FORGINGS: j A-508-64 FLOW VANES 304 STAINLESS STEEL \\ / CLASS 2 \\ / / CC-1322 s INSTALLE0 AFTER STRESS RELIEF / / PLATE: SA-302 / GR. 8 CC-1339 CORE STOS LUGS (INC0tlEL) SHOWtl O' T OF POSIT 10tl FOR CLAhlTY lti-CORE INSTRUMENT PEtlETRAT101:S tlUMB ER 52 SIZE 3/4" SCH.160 INC0tiEL (SEE FIGURE lA) METROPOLITAtt EDISON REACTOR VESSELS TMI IE2 FIGURE 1 UbT81

9 a tic TE: TI:ESE t.RE vi.otAT C !!ELO J01:!TS TO SHOW.nSiC PRli:CiPL:' USED TO PREVE!,T SENSITIZATION OF STRUCIURAL llELOS.THESE ARE t:07 ELiCT WELD J0luT CONFIGURATIONS. N y UELO DEPOSIT - d liiCOMEL CLADDED / / CORE STOP LUGS (!NC0i!EL) (THE LUGS ARE AT THE SANE l ELEVATION AS THE FLOll vat:ES, j BUT ARE SHouN OUT OF PLANE / FOR CLARITY, WELD DEPOSIT t STAlulESS STEEL CLAD /' STAiNteSS STEEt Ft0u VANES ,/j {f MELDE0, AFTER STRESS REL!EY!'!C: TO IHE WELU UEPOSIT CLA00lGU INCONEL llELD BETUEEN BASE NETALS AND INSTRUMENT HOUSING PENETRATICN BEFORE STRESS RELIEVlNG. / INCONEL / h kl~ ih i G6"982 /jI /f c n OETAILS OF REACTOR VESSEL I-FIGURE lA

~ ltlC0tlEL BUTTERit!G STAINLESS STEEL (N0i SEi!S! T! ZED) / ,/ I- \\ a , il ~ s! INC0t!EL i!ELO DEPOSIT 1 STAINLESS STEEL CLAD 6 l' j' A I INC0tiEL WELD (HEAO-TO PEilETRATION 14 ELD) j TH!S WELD iS tiADE 1 s AFTER STRESS RELIEF. \\ + _. q_/ \\ 140 TE: THESE ARE SCHEt1ATIC WELO J01:1TS TO SHOW BASIC PRl!!C PLES US?O TO PREVENT SENSITIZATI0tt 0F STRUCTURAL MELDS.THESE ARE NOT EXACT WELO J0ltlT C0t! FIGURATIONS. REACTOR VESSEL HEAD C0t! TROL 200 DRIVE pet!ETRAT!0!! GG esa FIGURE IB

/- 35" l.D. PRli:ARY !!;LET t:022LE II) IS CAR 00:: STEEL Wlill MELD OEPOS!TED STAINLESS STEEL CLADDING 1 16" liA!; WAYS (2) ARE LOW ALLOY-I,[] 5" !!A!;0 HOLES (2) ARE LOW ALLOY-CARGON STEEL WELD BUILO-UP CAROLN STEEL WELD GUILO-U? WIT 3 7 S'd' WELO DEPOSITED STAINLESS STEEL UlTH WELD DEPOSITED STAlt;LESS STEEL CLA00ltiG d' CLADDING _ _~ / 4 k p __ 138" 1.0. / 4 \\ TUBE SHEETS (2) ARE LOW Aq All OY-CARBON STEEL U! TH WELO DEPOSITED I!iCOMEL CLADDING a= - HEADS (2) ARE LOW ALLOY CARB0!1 STEEL Wi T'i WELD DEPOSITED STAINLESS STEEL 2 [ j, CLA0 DING W 28" 1.0. PRit:ARY OUTLET t;0ZZt.ES (2) i I" OR AlH LittE IS INCONEL ARE CARBON STEEL WITH WELO DEPOSITED STAINLESS STEEL CLA00 LNG FIGURE 2 EG-0E4 SCHEi1ATIC 0F I1EROPOL ITAll-E0lS0t!'S Tiilel t it1102 STEM 1 GEt1ER ATOR 5

4" SClfECULE 120 EP1AY L !!1E t:0ZZLE (:)--, [I"SCIEDULE160VENTN0ZZLE(Il 15 CAC00M STEEL WITH WELO DEPOSITED IS INCONEL ti!Til AN INC01EL SAFE-END ,[ STAlt:LESS STEEL CLADDING AND A1 2.E" REllEF VALVE t:022LES (31-CA120:, IGCCNEL SAr..c eND Jy ',e [ STEEL t WIT:t UELO DEPOSITED STa r:: LEES il 1-STEEL CLADDING AND INCONEL O c i'El l'4. f .$3 THE STAINLESS STEEL ?LANGES A U 'g\\') O \\ WELDED ON AFTER VESSEL STRESS !ELlEF. g k. t y 16" MANUAY (1) IS CAF.PN 4 ~ STEEL WITH UF'.0 DEP03lid0 STAltiLE55 STEEL CLACCil.G f 84" I l.0. I I" SCHEDULE ISD LEVEL (5) AND SAMPLE (1) N0ZZLES ARE i WELD DEFCSITED STAINLESS STEFL CL10 CARBC?i STF~L UlTH i l hCON E t. 5AFE-6005. e THERh0WELL (1) 15 INCONEL 1 l -m- - -E-l@Ey - .- A o, 1 w r-- \\ i SHELL AND HEADS ARE CAR 00N STEEL WITH UELO DEPOSITED STAltiLESS STEEL CLADDING 'I 4' 10" SCHECULE 140 SU2GE Lit;E N0Z2LE (1) 15 CARBON STEEL WITH WELD DEFCElT D '_L I STAlt LESS STEEL CL ACDING AND !';CJNEL BUTTECING. A STAINL ESS STEEL 3 ACE-END 15 WELDED ON AFTER VESIEL STRES3 RELIEF. 6670E5 FIGURE 3 SCHEMA TI C 0F METROPOL liat -EDIS0!1'S TMl"I. TMit:2 PRESSURIZER

'M" 1.0 AN3 2'J" t.n. L ' "' t A '. i l'IP!NL lC..... SIEEL ..' ^a w /. L., CI o / ' - - / i 'N s WELD 0:P0517:0 S T A i!.L E S S 5 ! t.' L ~ [ Cs A 00 l t.G - / - ( A-371 21,20 3 L) A. STRAIGHT SECIl0'; ( TMI l ! 2) STAtt;LESS STErt SarE-ENO ATT10NE] CA23:N STEEL AFTER VESSEL 2775i3 RELlEF (51-??5 i<o: ?ci f ssNs.s s \\, > WELD DSPC!!!!3 INCCuEL / ST Alt.L E SS SIE2L BU TTE R i t;G / CLA00thG W FTx Y / - - / - / / / / - 7 }i 2h. SCHECULF 160 STAINLESS Sit:L si' d. M.: rut.Le C0!!!;ECTED TO 25" 1.0. PLPP OUTLET PIPING SAFE-END B. PIPE CONNECTICN TO REACTOR COOLANT PU"P INLET AND CUTLET (TMl I : 2) 35" 1.D. AND 23" 1.0. REACTOR C00LANT ELSO'.;S ARE CAR 00N STEEL (A-515 CRADE 70) HICH ENERGY 00!'0E0 STalt;LE 3S S TEEL CL A D 01';G ,e (SA-2t.0,TY?E 304) N /

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/ /j' /,A / / M n, / C. ELB02 (ini i T. 2) SCHEMATIC OF MET-ED'S TMl I E 2 9EACTOR C00LAt:T SYSTEM Pl?!!:G gg-(*g6 FIGURE 4A

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/ / / /. / / //) s / / / 7 .__________._.____g=.ama x WELO 0:PDSliEJ STalSL CSS i,ir.L ~ CL AUD it:0 / . l.. i 3 t / - - ... - - /.,, 't 18 lc /,, / w,m it:CC"El t:02:LES CA.CC;t: STEEL lt 00::EL SAFE-E:;D %.el (EXCEDT 0"E c?Als no:2LE IS CF 16:E CAEC'. ST:EL / I':C C t: E L SAFE-END ITFE AS USED 0:4 TMI-11 D. IllSTRCNENT sat:PLE '!E!4T 4!:0 01 AIN PEP:ETC AT ICt;S CC':' ECTION TO THE REACTOR COOLANT PIP!f.G TH?.T ARE LESS W N 4'l.0. CAR 00:4 STEEL / / / / / / / / / / / / / / / \\ WELD CEPOSITED I STAlt:LESS STEEL t- _ CL AD]!!:C l t / / / / / / ./ / / / n,'h ps-1 ) C A?.00!! STEEL / Stilt:LESS 570::. SAF -:::0 ATTAO:::3 \\'U l t,j -- ii;00;;EL GUTTERiii3 AFTER VESSEL STRESS RELIEF 1 E. 72l' SCHEOULE LEO HICH PEESSUE I"JECTIC" t:02ZL25 (I.1 C0!;NE C T I C?i TO THE REACTOR COOL A!;T P;Pli.G (TMI I ! 21 CA903:: STE!L 7 / / / / / / / / / / / / / / s t! ELD DEPOS!TED STAl!:LESS STEEL _ _ CL A 0J' 1 L G / i / / / / / / / / / / lh y L / ' s / CARB9tt STEEL / h 5-It.00:;EL BUTTE

  • lt:G F.12* S01lEDUL E 140 OECAT HE AT AND 10* SCHEDULE Ito Sc1CE Lit 1E C0 tit:EC T 101 !0 THE REACIC4 COOL A!;T P! Pit:G ( Trti i A ?)

SCHEMATIC OF MET-ED'S TMl l E 2 REACTOR CCOL.U!T SYSTEM P!?lt!G FIEURE 48 W 4.4

e N N 7 CARB0tl STEEL k',c vk;.(-( ( - [// ML. \\; w ' 44 w _ ~ . ti u v i,.,-, ,nn. i c-r ~p!<js <f,' ^ ^, ~ llELD DEPOSITED STAltiLESS STEEL CLAD 0ll1G s \\ G. RESISTAllT THERMOMETER PEllETRATl0t1 til REACTOR C00LAt!T PIPlilG (TYPICAL) (TMl I Z 2) SCHEt1ATIC OF MET-ED'S TMl ! Z 2 REACTOR COOL /!'T SYSTEi1 PIP l!!G 'f gg -gES FICURE 4C ~

2 lt:CH CEL IEF ::0'.Z:.E,UELU se FCS li ED STA ll:LdSS STEEL CLI 0 Cl.E30:: STEEL WITil iUCCI:EL SAFE-E! 0 / / U8 h g/ 16 f t:CH I.O.t1ANUAY;UELD DEPCSITED gdc 6 /> STAII;LESS STEEL CLAD CARDOM Sir:EL 94 / l' \\ UELD DEPOSIT CLAD [ OVER SEAL' J0litTS 5: PLATE At:0 HEAD (1ATERI AL IS SA-515 GR70 CAR 20t STEEL (12 Qh UliH SA-240 TYPE 304 r( RCLL-30!:DED ST!. I NLESS STEEL CL A00 l!.G t13 C 2 2 '-5 " 4 L-~m I",, r--1-- g I:0TE:IISTRL"1E!: TAT 10f! E Sat:PL I f:G !:0ZZLEE I I I IMCH ::0ZZLCS ::2,M2, :?,us, t!6 A!!D !!7 ARE UELD DEP051TED 9'-3"l.0. STA l :LESS STEEL CLAD CAR 30:: STEEL WiTH It:C0t:EL SAFE-E:.0S EXJt1PLE: ~J I17 WELD DEPOSITED Sial l:LESS STEEL CLAD CAE30t! STEEL If:C01:EL -g ttS o o r r 4 _dL P !!6 y L, e o I i II:CUl:EL WELD DEPOSITS [f 14 It:CH 1.0. OUTLET t:0ZZLE3 UELD DEPCSITED BUTTERit:G FOR UEL0ir.3 p'; . / STAlt:LESS STEEL CLA0 CARB0!! STEEL O!! SAFE-E!;0 t .f 316 STAli:LESS STEEL SAFE-E!:0(UELDED Ct: d l AFTER STRESS RELIEF CF VESSEL) I ~ FIGURE 5A 6G-0E9 SCHEMATIC OF MET-E0'S Thiel CORE FLOODit!G tat!KS

r-4 e 2 !!:C4: REl l f.c f0ZZLE: 2 SOL IO it:C0t;'.L ~ !!S r / {kC-'H/7~ 16 !::CH f.0. mat:UAlsWELD DEPOSITED STA ll:LESS STEEL CLAD CAR 30:: STEEL 9 ./ k . 1.v.,- s f uELD DEPOSIT CLAD / OVER SEAU J0lt:TS k. i' v PLATE A!:0 HEAD MATERI AL IS p ,t. m*.. SA-5IS GR 70 CAR 30U STEEL if U h H $4-240 TY?E 304 '.:12 --(-. 22-- ROLL-30f.0E0 STA II:LESS 1 -STEEL CLA00ll:3 22 '-5 " 11 3 7 ;;,, i 4 x. c - ----. u g 4 s. ,,nv,e.,i.,.c.,.n.,.,~ia,.,..,.l,,..,.,....,......--..-- .~. .s,.. un u ann :. :.e i.u ::.. I I II'CH f:0ZZLES i!2;l 3,f 4 st:5, ~ 9'-38 1. D. ' ' I:6 Al:0 !!7 ARE SOLIO lt:C0t.EL EXAMPLE: g. 4; II:C0t:EL I 1 %: s.

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