ML19326D480
| ML19326D480 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 09/11/1975 |
| From: | Bauman R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| References | |
| 1781, NUDOCS 8006110512 | |
| Download: ML19326D480 (36) | |
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,~.,-il General Othces: 212 West Micnigen Avenue. Jackson M,cnigen 49201. Area Coce S17 788-05S0 September 11, 1975 - %jg Aw s
v e hU N N' Mr. Roger Boyd js cc -p , b[}.-<T}'> b)
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4gNS Acting Director 2y g 'g 4 SEPP,31975
- Nuclear Regulatory Commission
_ g {>, e R Division of Reactor Licensin Q# h 42 A
"" hQ*' 40 Washington, D. C. 20555 [N % f r -"
g O W (\ MIDLAND PROJECT N DOCKET NUMBERS 50-329, 50-330 4t REGULATORY GUIDE MEETINGS FILE: 0505 SERIAL: 1781 We are attaching herewith 10 copies of the Consumers Power Company position on implementation of Regulatory Guides 1.2, 1.14, 1.31, 1.34, 1.36, 1.43 1.44, 1.50, 1.65, 1.66, and 1.71. These regulatory guides are on the agenda for discussion in the Materials Engineering Regulatory Guide meeting which is being scheduled by your staff. A position on Regulatory Guide 1.51 has not been developed since it has been withdrawn by Mr. Robert B. Minogue's July 15, 1975 letter to the Regulatery Guide Distribution List (Division 1). Please inform us of the schedule for the Materials Engineering meeting when it is established. R. C. Bauman Project Engineer THis DOCUMENT CONTAlHS pgg{3 0 06 I20 6'f R g 1UJ76 l I
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n b, t , REGULATORY GUIDE 1.2 THERMAL SHOCK TO REACTOR PRESSURE VESSELS (11/2/70) For equipment within the B&W scope of supply, the degree of partial compliance with the Regulatory Guide is as 4 follows: The following is keyed to the Regulatory Position (part C) of this guide: C.1 Data collection and research work under the PVRC/MPC, HSST program and others is still an ongoing process. C.2 The reactor vessel design for this application does not include any significant changes from previous designs which would reduce the margin of safety against brittle failure due to ECCS operation. B&W has analyzed this potential and concluded that vessel integrity is not jeopardized due to ECCS operation. C.3 Appendix G to 10' CFR 50 as published in the federal register on July 17, 1973 provides the available engineering solution and acceptance criteria for a vessel. l
",. O m.
.ntegrity"
~ ~ ' -
1,* R.G. 1.14
% actor Coolant Pump Flywhcc' (Rev. O October 27, 1971)
A,'
Introduction:
ne degree of cogliance of the reactor coolant pump flywhcci to the design,' fabricatica, and testing requ'irements of' Regulatory Guide 1.14, is given below: . B, Discussien: De reactor coolant pt p flywheels provide inertia to preclude an immediate loss-of-coolant flow following a loss of power to the pu=p motors, thereby preventing fuel damage. Because they have large masses and rotate at a speed of approximately 1200 rpm during normal reactor cperatien, a loss of flywheel integrity could result in the generation of high-energy missiles The safety and excessive vibration of the reactor coolant pump assembly. consequences of a loss of flywheel integrity could be significant because of possible dacage to the RCS, the Containment, or the ESF. . He teactor coolant pt=p flywheels are of a single geometric shape, and are unde of a tough and ductile mterial. S eir quality is closely controlled, and their service ccnditiens are not severe; therefore, the use of suitable material, and adequate design and inservice inspection, can provide a sufficiently small probability of a flywheel failure that the plant need not be designed against the consequences of such a failure. Flywheels are provided as required to obtain the required total inertia.
- De design and location of the flywheels allows removal. of the rotor from the top of the stator. A single, one-piece flywheel is mounted on the reactor coolant pump motor shaft. De thickness and outside diameter of the flywheel is detemined as required to obtain the total moment of inertia required for the pump rotating assembly.
C. Licensine Position x
- 1. He reactor coolant pump flywheels are manufactured from AS'DI As4. -70 Grade B Class 1 plate, nickel-chromium-colybdenum alloy steel.
De flywhcc1 material is produced by a vacuum melt, and degassing process to minimi:e flaws in the material and improve its fracture toughness properties. . 1
u - .
,C. Licensing Position _ . font'd)
- 3
' , The flywhccis arc. abricated and used under cond .ons that do not produco
~
. temperature erbrittlement of the mtcrial. The mecrial is examined and. .
tested to meet the following criteria:
- a. The NUT temperature of the flywheel sterial (representative of the as-finished flywheel), as obtained from the dropweight test performd in accordance with specification AST!! E-208, is no higher than ,50 ( ,
for flywheels with thicknesses of S 7/8 inches. Test results of the first flywheel show that the NUT temperature is -170 F. This is well below the specified limits.
- b. The Charpy V-notch (C y ) upper-shelf energy level in the " weak"
_ direction (hR orientaticn in plates) of the flywheel material (representative of the~ cs-finished flywheel) is at least 50 ft-lb. A minimum of three C y specimns is tested frem each plate in' accordan~ce with specificatica ASB! A-370. Test results of the f,.rst flywheel show that the Cha:py V-notch y(C ) upper-shelf energy level is 90 ft-lbs.
'Ihis is well above the specified limits. -
- c. After an extensive search in literature and published work, it was concluded that dynamic fracture toughness data (K IC dynamic-values) for ASIM-AS43 Grade B or ASDI-A508 Class IV materials in. heavy gages and at temperatures above .100 F is not available at this time.
Dynamic fracture toughness. testing in compliance with an acceptable
. method to obtain KIC (dynamic) values on ASBI-A543 Grade B or ASDI-A508 Class IV flywheel material at the flywheel operating temperature of-
- approximately 120 F would require rapid load applicaticns to rather thick specimns which at the present time are not available.
.Also XIC (dynamic) values have not be'en published on ASDI-AS43 Grade B material for heavy gages and higher temperatures, there is sufficient published KIC (dynamic) data on this material available at lower than flywheel operating temperature to establish a lower bound KIC CdY " "IC) curve in the lower temperature range.
A. K. Shoemaker and S. T. Rolfe in their paper: "Ihe Static and Dynamic . Iow Temperature Crack Toughness Performance of Seven Structural Steels" 1)' report KIC (dynamic) values for HY-S0 steel (Asn!-AS43 innterial) in Fig. A of their paper which is based on one inch thick plate I having an NUT of -120 F. Hiroshi Susukidn', Tomo:umi Ande, Ichiro ? . l l 2- :
v.-
* . C. , * .Licensind Position r 3 (Cont'd1 -
,' O. Tsuji andJoshinao Hibaru of liitsubishi Heavy Industries, Ltd., in -
their Technical Review, January 1969 report KIC (dynamic) values for Ni-Cr-hb-HY80 steel plate obtained from WOL-Tests. Data frda both above sources was used to draw a lower bo id K IC (dynamic) fracture toughness curve over the tenerature range from
-300 F to approximately -100 F. The proposed extension of this curve beyond the -100 F te=perature as shown was based on the slope of -
the KIC (dynamic) fracture toughness of Nm! A-533 Grade B Class I nnterial for which sufficient data is available. It is indicated from the plotted data that the lower bound KIC (dynamic) curve might have a steeper slope at te=peratures above -100 F as plotted in this proposal. Since test data which would support a steeper slope of the lower bound Kg (dynamic) curve is not available at this tir.e, the more conservative approach of sloping the curve similar to the establishe:'. curve for ASDI A-533 Grade B Class I material was used. The attached curve was made using the above approach and shows that this material is satisfactory in the range of the flywheel operating terperature (approximately 120 F).
- d. Each finished flywheel will be subjected to a 100 percent volu=etric ultrasonic examinatien using procedures and acceptance criteria equivalent to those specified for Class 1 vessels in the ASME Code, Section III, Nuclear Power Plant Conponents. Test results of the
'first flywheel show no reportable loss of back' reflection.
- c. 'Ihe, flywheel is flame cut from a plate and at least 1/2 in. of stock is left on the outer and bore radii for machining to final dimensiens. .
- f. Finish machined bores and surfaces adjacent to the bore, keyways, and drilled holes out to a distance equal to one-fourth of a distance from the bore out to the outer circumference will be subjected to angnetic particle or liquid penetrant examination. Procedures and acceptance criteria shall be equivalent to those spedified for Class 1 vessels in the ASNE Boiler and Pressure Vessel Code, Section III-Nuclear Power Plant Conponents.
Test results of the first flywheel showed no ' reportable indications. [ _
..-im ...<= am_m .. ...
, ,. 2, ne fc11owing e ti eria nre used in the design "" the flyuheels in order to' ~ ~ withstand the n:nnal conditicas, anticipated transients, and the design
., basis IICA.
- a. An analysis has been perfomed which shows that the corbined prima'ry stresses ,at nomal operating speed due to centrifugal forces and the 3nterference fit of the flywhcci en the shaft does not exceed 1/3 of '
the minitt..n specified yield strength.
.b. Flywheel Design Speed and Temperature - The nomal and anticipated transient conditions are used as the basis of the design.of the flyw.h'cel.
~lhe specified operating speed of these squirrel-cage induction motors is a synchronous speed of 1200 rpm less the slip inherent' to induction retors. The maxin..a speed that these motors could achieve is antici-pated to 'be tader the transient turbine trip conditien, which is less than 115 percent of the norrn1 synchronous speed. Therefore, the design speed of the flywheel is 12S percent of the normal synchronous speed of the motor, or 1500 rpm. These motors are totally enclosed, internally air cooled, and will operate at a terperature independent of Containrent te=perature. The lowest design te=perature of the fly-sheels is specified at the nomal operating temperature (about 120 F).
The NRC and industry are pursuing a program to study the possible effects of the LCCA overspeed problem. In connection with this, B5W is contributing to the centinuing effort being made on this problem (See BAN-10040 dated December 1973). Full results should be available
-at a later date. I
- c. An analysis has been perfomed which shows that the combined primary Etresses at the d'esign speed (1500 rpm), due to centrifugal forces and the " interference fit of'the flywheel on the shaft, does not exceed 1/3 of the minimum specified yield strength.
- d. The shaft and the bearings supporting the flywheel can withstand any combination of the normal operating loads, anticipated transients, the design basis loss of coolant accident and the design basis carth-quake. An analysis has been performd which verifies the adequacy of the unit under the above Ioad conditions.
- 3. He flywheel assemblies will not )e overspeed tested.
(See Section D below)
- 4. The inservice' inspection pi uforeachfl$wheelwillbedevelopedaspart of the applicant's overall inservice inspection program.
1 4
d;,SupplementaryNork O , Two additional anafyses were perfomed for these flywheels as concerns critical speeds for ductile and non-ductile fracture. -
- 1. A calculation has been performed to show the bursting speed 6f the flywheels for ductile fracture is greater than 200% of nomal operating speed.
- 2. A non-ductile stress analysis has been performed to examine stress i
concentraticns in the keyway region to detemine the stress intensity Ky for cracks of various depths. For conservatism it is assumed that
'the reactor ccolant pump motor is started up at least above freezing or +32 F (cperating temp. is 120 F). The KIC (dyna d c) n i e at n e temperature of +32 F is approximately 140 KSI4iinnTF as determined from the lower bound fracture toughness curve. The attached curve shows that the critical speed for non-ductile fracture for flaws less than 1/2 inch in length is greater than 200% of normal operating speed.
E. Conclusicas This response demonstrates co=pliance with Regulatory Guide 1.14 except in the area of overspeed testing which was addressed by the analyses included in Section D as a supple::ent to the Regulatory Guide provisions. Overspeed testing of the flywheels would provide confidence that the flywheels are satisfactory if the analytics and tests showed a marginal design. However, in this case the analytics and tests show these flywheels are satisfactory far in excess of 125% of norm 1 speed and therefore an overspeed test to 1500 RPM could provide little or no additional confidence that these flywheels are satisfactory. ..
~
References:
(1) Flywheel Integrity Report o. 34A180718 dated 2/20/75 for Midland Plant 1 (2) Seismic and LOCA Report Rev.1 No. 731!G15 dated 6/27/75 for Midland Plant 1 (3) BEU Topical Report B.W-10040, December 1973
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REGULATORY GUIDE 1.31 CONTROL OF STAINLESS STEEL WELDING - (Rev. 1 June 1973) RESPONSE TO REGULATORY POSITION The NRC's interim position on Regulatory Guide 1.31 as contained in Branch Technical Position MTEB 5-1 has been used as the current NRC requirement for Control of Stainless Steel Welding. The Midland Project construction of balance of plant components and installation of the NSS will comply with MTEB 5-1 except as noted below (1) Paragraphs la, lb and lc of the Interim Regulatory Guide are complied with to the following extent:
- a. The limits for Delta ferrite in austenitic stainless steel welding materials comply with Interim Regulatory Guide 1.31 since the upper limit of 20 percent Delta ferrite in the Interim Regulatory Guides does not apply for welds that are not heat treated after welding (Paragraph 3B), except for solution heat treatment.
Solution heat treatment, although not required after welding, is permitted in order to avoid severe sensitization.. Austenitic stainless steel welding filler materials used in the fabrication and installation of ASME Section III, Class 1, 2 and 3 components are controlled to deposit from 8 to 25 percent Delta ferrite (8.5 Ferrite Number minimum), except for 309 and 309L welding filler materials which are controlled to ; deposit from 5 to 15 percent Delta ferrite (5 to 18 Ferrite Number) and are used only for welding carbon or low alloy steel to austenitic stainless steel.
. Use of 309L welding filler material is further limited to the overlay deposit on the carbon or low alloy steel component nozzles or connecting pipe when postweld heat treatment is required.
- b. The procedure for determining the amount of Delta ferrite in each heat or lot of austenitic stainless steel welding material does not comply with the Interim Regulatory Guide. Determination of Delta l ferrite is in accordance with ASME Section III, i Division 1, Paragraph NB-2433. l
. 1 (2) Regulatory Dosition C.2 is complied with for all tests and examinations required by the applicable edition of
! the ASME Code. l l t I l
', N .
. r j
. = .
~. l
, \
l l. INTERIM REGULATORY GUIDE 1.31 (cont' d) (3) Paragraph 3a of the Interim Regulatory Guide is not complied with. Magnetic measurement of production welds for Delta ferrite is unnecessary when austenitic stainless steel welding materials are controlled to deposit 8 to 25 percent Delta ferrite (8.5 Ferrite Number minimum), based on chemistry, except for 309 and 309L welding materials which are controlled to deposit 5 to 15 percent Delta ferrite (5 to 18 Ferrite Number) based on chemistry. Three Bechtel projects are committed to measuring production welds for Delta ferrite in order to collect data and demonstrate that the welding material controls described above are more than adequate for . the purpose of avoiding microfissuring. The program for measuring production welds for Delta ferrite applies to shop fabricated components as well as field installation welds. Since this represents a sufficient number of welds for the purpose of collecting data, measurement of production welds for Delta ferrite on this project is not planned. There is no justification for requiring measurement of production welds for Delta ferrite as a test of the welding filler metal control program since that l is not the purpose of measuring production welds i for Delta ferrite. For these reasons, measurement of production welds for Delta ferrite on the Midland , Project is not planned. ' (4) , Paragraph 3b of the Interim Regdlatory Guide is complied with, except that the upper limit of 20 percent Delta . ferrite does not apply to welds that are solution heat j treated as described in la above. i i (5) Paragraph 4a, 4b and 4c are not complied with since ; measurement of production welds for Delta ferrite is not performed. , l I i I
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,- . ~ . -
b O INTERIM REGULATORY GUIDE 1.31 (cont'd) For the equipment within the B&W scope of supply, the degree of compliance with this Regulatory Guide is as follows: The attached NRC position statement dated 4/11/74 has been i used to develop this position. Basically the position required stainless steel weld filler material (except for type 16-8-2 and filler used for weld cladding) be qualified as required by the Summer 1973 addenda to the ASME code (see paragraph NB-2433) to a minimum of 5% Delta ferrite. In addition to.the code requirements filler materials must meet a 20% Delta ferrite upper limit and materials used on weld processes other than TIG and plasma arc must be qualified using chemical analysis of an undiluted weld pad sample rather than the chemical analysis of the filler prior to welding. The-second provision of the position requires testing of production welds for ferrite content using a magnetic measuring device with a certified calibration. If production tests on a component do not indicate an. average of 3% Delta ferrite on the face of the completed weld at the weld centerline, then that weld must be justified either through fatigue analysis, destructive examination of the weld or through weld repair. Destructive examination or weld repair will not be necessary where components are already purchased, and justification on the basis of reduced fatigue strength or increased inservice inspection is provided. It is not the' intent of this new position to backfit weldimaterial qualifications (which would be impossible where welds have been performed using materials which were not qualified to the present ferrite content limits, i.e. components purchased to earlier code addenda than Summer 1973). The NRC does, however, want accumulation of 4 as much production test data as possible throughout the industry. The goal-is to drop the requirement for pro-duction testing when. industry has developed sufficient data to show that such testing is unnecessary. L. m.
P , , esS"R$Q TATTA'
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o.. ./. ' ',3- . C. I l p.r it Nn : nn l'een1,',*rv. Guide 1. 31. - f-
" cod ,dl o. '
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Pentiini, i:r ti:. inn of '!Licnuent rabricatioin.. of velded auntenitic ctainlecn :deel Clauseu J , 2, 3, in couponente r,luiulsi comply uith the requirc::cuch of Se: tion Ill and Section I'. t
. of. the AS E Eoiler and Preccure Veccci Code Supp]cment.ed-
- l. . The veld filly:r ttaterials used shall ecet the acceptance tert
. . requ ii c-Inents of; Sect.ina III of the Asm:
Eoiler and Pressurc Vessc1 Cout , pt. the'follouing adc.litional requircuents: d
- n. ' Delta ferrite \ eterrainations chould be performed on undilute:d c. u deposito for cach Lot and IIcat of auctenitic stainiers steel .
veld retal '(Pa ra. y.1.',42 of Secticn )X), encept t. hat delta f erri t e -.ier. r . taluatjou:; uill not be required for !;FA-5 4 Ty; e
.l (> -fi '/ we l d i.:.. .. i ,
nor for auct( n it.ic. :Lainle::r. :,tce l v,:i ] i [ j l] :r het:11 to be unr 1 fe: veld iiiri al, . cl.n!.t ing. Delt a ferri te det ci uin, tion:. f or con at rdel.- Jurertn,
. rod or vi re f il.ler teet a l n.:ed wi t h t hega . t ungni en . : e procenn, or the planma are velding procenu may be pi edict cd i using t opplic*abl'e cunct i. tut. ion diagran, to demonst ra te conpliance u.i t h ::n.
Regulatory position for cr.ount of delt.a f erri te as :ho:en in pv:.it . .a 1 C
-b.
For all proccc::es other thcn Tin and p.laramt a rc dr.i ta ferrit e de: . r-ninat ican :. hall- be made on, undilut ed ueld depo::i t n. An accept .:bi rictbod. for achieving this criploys a ucid pa:! uade and terted in cca- . r-formance uith the a;splicable chetch ard unti:ods deneribed e in th ' u American 1lciding Society Specification. SPA-5.4. The undi.lut ed ucl.! 3' .. - _ .. _ . . Schaerrier, -::.siirica Schnen ter,; or nel <,ng n y,.,, 3 llidndbook, - Ve l . (,, pp. 240-247..
. 3mc y tcan goe;r., .. n .r : .. . [
M
, g .-..
+
m.uu ::;'. .%
. WM s .
depositt r.ho ild contain i.etween 5 an.1 20 perceat delte ferri t. , or
. itr equivalent ferrite nut.bcr.
I . 3 - c. j
' Cher.iical analynic r.hould he perforued on on lilut cd uc1d depaans,
' except uhen Ti t; or Planaa are pt. aces::m. ar uced , an indice. t et' ahoVC. '
- 2. '1he recults of the destructive and nondertructive tests required .'
her,niatory recition 1 above should be included Tent Report nr. in a Certified 'deri :3:. required by AS:C Code Sec t ion 17 I. , ?;B-2100 or ':d .'.130.
'1he precent penitions 3 and 4 are no loni cc de ined necccrary, e..d tre deleted.
Revisions to positions 5 and 6 have been unde a the new ponitionn 3 and 4. n' are ch.nzn la t Pres;ca t poni: ion ::o. 7 has he. n delete.!.
- 3. a. Product. ion u.Idn, e>. cept fillet -
s.c l . !: havii, a throa t. d ia:t . . ic,
't/.."
or ler.:, :,houId be n.:aained In v e r iI:
, Ihaf .nlcrgna t e de 1 t a f et : ii e I cv e l 3.
are pt esent , by ma;.. net in an a:a r c:nen d( v i ce: . i,.'.' J d s . 1 inch or I; teat er .in thicinent. hall h. c .:at. i n e.l e.n a 1007- b u. i n , uln re :, a c:nnplie;. plan may be used for enraa.ca tion of ucid in ll'ichnest.. The examination a Jens than 1 inch hould :hou that each .: eld cuna in: least 3~, at delta ferrite based on the 4.verar, of four test rn :c; ". ! taken on the face of t.he completed weld d ei.onit at the cen.cr:i u of ! the veld, c:nd at 1/4 ueld lent;th inturval :. . Innt ruw nt rc e di:. '- , chould not be taken at " start:. and stopn" f
..oea tions , or in ..:..!
adjacent . be; l. to the banc materialn. The avercic.e o f four In:.,t r :: .:t read-inc.c nhould not include any readin;; bel ou one percent delta ferrit e. 1l eld locationn that uhou .1 ;. o r Je.. delta t errit e nay be r eu. :;i .I, i to deternine ubether the readinr repr . enen: , a local coaliLic:.
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*the. nagn.'t ic instru:'.catn uned for c ea: inat ion of ueld padn d
- e ta f errite should have been .calibrat ed u:.ing;:.econJqya nt 1:: :-
- u: lar ahle t o - (::aLional Eureau of- Staudardn:
n t amt.t rd s , and t.o a Magne ; ., . l un. lug the proceduren shtuca in Ud] ding Counc il docu:::en , 3 972, " Calibration Proceduren for Ini. '. rune::t :. to "canure the D, cit t Ferrit.r.* Cunt cut of Austenitic St a inic m Sten) Ueld ". etat," an.1 an
.cupplercuted by proceduren shoun in AIE cpecificntion A 4.2-7/s .
b. The. upper liuit on delta ferrite chou t in I:. nul atory ponition 10 ) above need not be required for welds :1:at do not receive heat t r .: " - . uent nubsequent to uciding, nor for c annu:nabic incerta. . 4. In the. ev nt Lbat Regulatory position 3.c. abova i:
. not met, the rerg c.:t.
f product. ion volds nay be evaluated for acceptabiliLy using:
- a. ..
An analynin of servJcc regi:f rement : ( f thn u, Idment , ami c o .; ei r i . . i Of' the..c ret;a l ret ;en t.n Ui t h t he A*. W. ( :,ilo
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ci i t.cr i.t f o r f al i;,uc .[ : . .:.-! !- but. un in;,
- t. .:e:erv. Live fatigue data i h it ac.ount:. for vel.d :ae f a l t ii h hiirro Iit.nur. n, or
-b. .
-/.n e:.amina tion of the veld or uelib. t o deaa nas ra te the :ds::ence of unaccept abJe fit nures or crackr..
Uhere the production veld J r. be l.c.. the ninir.ua acenptable level of delt.- ferrite, a r.a..:pl e o f the u. ' .'
- . hall be renoved, and a metallopraph c exw i i uation or a bend tent .
chall be n:ide en a t.ransverse sect ion tothed.prer.. t eruine
. .e o r , .
absence i of excencive ficcuren. The accept..nce criteria is au l fo330un: Finr.ures 1/f>4" c6ad let :. f : ball'uo: he counted. The prenence of a ningle tear or fi:. :ure! larger t han 1/16" , or of a l
C G da:a-] n c. 1 , great er winber th.tn 3 of reize bet ween 1/64" .:n ' 1/' 6 in ray 0 2 .
.cquare inch of ucId actal ch211 -
con::ti .ute failure of the t e ::.
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c. 1:cid:. found unacceptabic chall be r< ; tired.
.:oc! ree :nined for delta f errite cc:: tent in accord nee [i h s
.. t th ptocedure ni.ov: 21 3(a) above.
An c::::aple of a suitable exa:ainct i.: 4n plan 1:. diccusce<! in
'. t. t c h: ut 1.
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)s 4 Del.t a is.rri te deter. iant ion:; uili be nr.de on the to:.pletcd nuc;. . { of all cuch reld.:. I.' hen observe.i averaf.c delt a ferrite level:. or 3% or nore are indicated, all of the ucid:, vill be con ;ide:cd accept:J.lc, and no further tentli.d'it. needed. In tha evcut that tha delta ferrite 1cve.' :n sc.: c teld In lu:. :: t.. nan an average o .... u. , a tac tal., oi; rap,u.c ena.a . u:ation or a nacre .c.:p cxaninat.lon perforned c.n transverne : id: - Lend spec:i ..ent, to deter.-: the precence of r2icrofincurer will be nc.dc. The npeciue:u. fo: 1:1ctallographic or r.:acrosecpic c.s:c:aiuntior. u111 be celec ted f re ' . the velds cr.hibitin;; delta ferrite lerclu 1rn cr than 3%' average in accon,ance uit.a lan.le It.
- 7. .
Prm?ar r h.a t .' 1 J - or In-b <,r lera. r i c h .- - (:;c. T: bin 1) Delt.: 1 ci r i tu det.crnina tiote vill b: u de on the c o.ap h i n i ni n r , :.: of :.och ueIdn, r.e'.i ec t ed in acco: din:ce .Ith Table 3 .i . 'l f ob: : vi d del t a J ci ri te ]cs e 1:. nf 3% oc worn ai e .i ud ic.: t ed 1 o: the. :.aa.pi e ve f i! . , (i.e., Col uan 2, Y.:ble 71) th entite
. .i t ch of we l d:. (i. e. , Co h:...n l),
that s l e.-
- axtple rescencat a chall be ca. :,ide . . d accepinbl e. 1f the nun.b.:r of ueld. in 1 t ha na:.0 c nl:.e h:ce na le: : than an av.:::c.r.- o f .C delta f errite equal:. or exceeda the rej ec t.Jo: J c. vel (Co] uma 3) , a u t ie velds in the batch (Column 1) 11.1 he.. to b. Janpected.
l'or uch;a having an average delta ferrite le.cl le:. . than 3%,.: :' n c i ' - neoplc c:aninat.Jan uill be per f omed on tr. :. ve. :c :..de-Lend ;ecc i.x.- . to detern:.nu th: precence of ulcrofit.cr.ren, . ir i te t til ] vi;ra ph i c c:L':';i'? tion ui1! bf ca te e spc. i: .:a . cu t f re.t tj . - ce 1.'
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A( , 3 cv e l t. loseer than an $.'. ret age 3% in accordance .rit h Table II . k. { 3. Sa :ple lorr or ba tches for ::cId . grea t.cr th nt Ene inch in thich. aijd for uelds one inch or Icus lu .i thicha:c.. uill not be e,teu.- togo;her, and will be r.acror.cepicall rn.u'Ined en a nep[ rate b t h
.. ac basin.
B. Acci : tn:v:e n::d Re i re t-i.an fet Delta'. :v"cr.rur. e i n ' n.1 .:!! c - : .. . - :u .
. - . ~ . . . . . . .
(All production volds) 3. 1.11 .:cido having an average delta ferrlic level of 3% or .:cre. . re acceptable. 2. 1.'aldo having lecc than 3% average delen ferrite chall havet r , , , .r < . side-bend
- testo taken and the ucids shall be exaulned uncrer .. .- e for fit :.'trec, or the_ueldt. chall ir- c.-
. i n ed ..:e : :.1 l og , a;d. w ' 7 ,
cm !pl.i r.3 to be in accordance with 'i.d.l. rt. I n crof.i ,:;n rj:r . , . .. duc ian t hene in::pect. ion: ; hall 1. es.ilnate1 h. the f ollo.c i n-, cr 11 et Ja : Fi .nure:. 3 /Cil:" a nd 1. . ..'<.1 no t. L e i. c..in i ed . Tir-
. pre..ence of a :;[a31u tcar or I i- ie i : . t.c:.
th:n 1/1f,", or t .f . . gre. iter nu 'l er th::n 3 of n ;J ::e b..t :e. ni J /6/ " .nid 1/16" in niy 0.2 :aju :re inch of ueld ue:.nl,
.h 11 et. :nt; tut e railure of :h, -
t c u t: . 3. 1.'ald . f ound unacceptable chall be reca ; ced and ree:4. :I n - ! i y :. '. . n . 1 l abore pr'ecedure. -
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REGULATORY GUIDE 1.34 CONTROL OF ELECTROSLAG WELD PROPERTIES (December 28, 1972) RESPONSE TO REGULATORY POSITION Balance of Plant No electroslag welding has been done and none will be permitted on balance of plant components to which Regulatory Guide 1.34 applies. For equipment within the B&W scope of supply, the degree of partial compliance with this Regulatory Guide is as follows: Electroslag welding has been used by B&W in the fabrication of the steam generators for NSS-12 and NSS-13. There are six electroslag, long seam welds in each steam generator and three in each pressurizer. Electroslag welds used to form shell courses for the steam generator and pressurizer are identified on the attached sketches. The base material for each of these vessels is carbon steel. As a result of early agreements with the NRC to conduct l production testing of electroslag welds used for joining A-533 Gr. B material for BWR vessels, B&W voluntarily conducted all weld metal tensile and impact tests on prolongations of production electroslag welds on approxi-mately 25% of the electroslag welds made on NSS steam generators and pressurizers. The notch of all charpy specimens was located on the weld centerline and the depth is at the 1/4T level. All applications of electroslag welding in these vessels involve carbon steel base metal. The results of the meci.anical testing have been well above the code minimum requirements. Since we cannot retrofit NRC Regulatory Guides to contracts made prior to the issue of the Guide, B&W has not complied with the requirement to requalify procedures and test each weld on the Consumers units. l The results of tests on prolongations fror two'electroslag l welds on one shell course used on a steam generator for NSS-12 are as follows: After a full heat treatment the i
~
- m 4 we. -
p i ' n' j. *
, a . . l REGULATORY GUIDE 1.34 (cont'd) l i
tensile strength on one weld was 80,500 psi and the CVN l impact strength at +400F was 48, 61 and 50 ft-lb. On the i other weld the tensile strength was 81,750 psi and the charpy values were 43, 60 and 40 ft-lbs. The average of I all these charpy values is 50.3 ft-lb. This data correlates ; well with that from hundreds of CVN impact tests B&W has conducted on prolongations of electroslag welds used on nuclear components. All electroslag welds are made in the vertical position. Two men, one inside and one outside the shell course, are used to check the progress of the welding and to insure that the welding procedure is followed. The weld is started in a U shaped starting fixture about six inches deep attached to the bottom of the joint. The weld stabilizes in this starting tab which is later removed. The weld receives a heat treatment which consists of a water quench from 16250F and a temper of 1150 F 0 followed by a furnace cool period. This post-weld heat treatment refines the grain of the weld and the base material heat affected zone such that it is virtually indistinguishable from the unaffected base metal. The microstructure is uniform throughout the weld. Each weld is subjected to radiographic, ultrasonic and magnetic particle inspection after heat treatment. Each plate is ordered with excess width so that test specimen may be removed after heat treatment. During quench and temper the weld prolongation and adjacent base material are buffered *by seal welding a piece of carbon steel material above the joint so that the test material is at least T d away from a quenched edge. All base material is tested by taking tensile and charpy specimens.
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,,.a. m REGULATORY GUIDE 1.36 NONMETALLIC THERMAL INSULATION FOR AUSTENITIC STAINLESS STEEL (February 23, 1973)
RESPONSE TO REGULATORY POSITION The Midland project intends to comply with the requirements of Regulatory Guide 1.36. Leachable chlorides and fluorides in nonmetallic insulation materials which ccme in contact with austenitic stainless steel shall be held to the lowest practicable level by the inclusion of the require-ments of Regulatory Guide 1.36 in the insulation purchase specifications.
,,p.
m REGULATORY GUIDE 1.43 CONTROL OF STAINLESS STEEL WELD CLADDING OF LOW-ALLOW STEEL COMPONENTS 5/73 RESPONSE TO REGULATORY POSITION For the equipment within the B&W scope of supply, the degree of partial compliance with this Regulatory Guide 1 is as follows: l B&W has analyzed the effects of high heat input, single l layer weld cladding processes on fine grain plate material j and has concluded that the incidences of minor underclad ! flows do not compromise the integrity of a vessel. This I study is presented in E&W Topical Report BAW-10013, " Study of Integranular Separations in Low Alloy Steel Heat-Affected Zones Under Austenitic Stainless Steel Weld Cladding" which is applicable to NSS-12. In addition to this study, B&W has, as an additional conservatism, taken steps.to reduce the incidence of such underclad imperfections on.NSS-13. Components of SA-508, Class 2 materials are not clad with high heat input (multiwire), single layer processes. Low heat input (single arc and dual oscillating) ! processes or multilayer processes are used. I It is our intent that Midland Construction of balance of plant components and installation of the USS will meet the restrictions of paragraph C.l.a of the Regulatory Guide. The remaining requirements of Regulatory Guide 1.43 will be ccmplied with when "high-heat-input" welding processes such as submerged arc-welding (SAW) and gas metal-arc welding (GMA) are used by Bechtel suppliers to clad SA 508 Class 2 forgings or to plate material of equivalent composition. Regulatory Guide 1.43 is not complied with when " low-heat-input" welding processes such as shielded metal-arc welding (SHAW) and gas tungsten-arc welding (GTAW) are used in the field by Bechtel or Bechtel subcontractors to clad completed welds and adjacent SA 508, Class 2 material during installation. It is noted in Part B of the Regulatory Guide that underclad cracking has not been observed in SA 508, Class 2 material welded with the " low-heat-input" processes.
~ n > n
'. REGULATORY GUIDE 1.44 CONTROL OF THE USE OF SENSITIZED STAINLESS STEEL (May 1973) -
RESPONSE TO REGULATORY POSITION The use of sensitized stainless steel is controlled in accordance ; with the Regulatory Positions of Regulatory Guide 1.44 except as described below. The control of the use of sensitized stainless steel for those items procured or contracted for after publication of the Regulatory Guide and for field fabrication and installation complies with Regulatory Guide 1.44 as described below,
- l. Regulatory Position C.1 is complied with. Cleaning procedures are specified and employed to ensure removal of harmful contaminants. Components are packaged in a manner that will result in protection from the weather, dirt, wind, water spray and any other ,
extraneous environmental conditions which may be l encountered during shipment. Protection of materials during site storage is accomplished by a combination of packing and inspection.
- 2. Regulatory Position C.2 is complied with. All grades of austenitic stainless steels (AISI 3 xx series) are required to be in the full solution heat treated condition before fabrication or assembly into com-ponents or systems. The solution heat treatment varies according to the applicable material specification.
- 3. Regulatory Position C.3 is complied with to the extent that those austenitic stainless steels that are exposed to temperatures in the range of 800 to 1500 F during hot forming are solution heat treated in sccordance with the materials specification after hot forming.
- 4. Regulatory Position C.4 is complied with. Types 304 and 316 are the only two unstabilized grades of austenitic stainless steels with a carbon content greater than 0.03 percent that are used for components of the reactor coolant and associated systems. These unstabilized austenitic stainless steels with carbon content greater than 0.03 per-cent will be exposed to reactor coolant which meets the following water chemistry requirements when above 250*F:
Chloride Content 0.15 ppm, max.. , Fluoride Content 0.15 ppm, max. l Oxygen Content 0.10 ppm, max. Oxygen scavangers such as hydrazine are used below 250*F.
.e
,w m
[ Response to R.G. 1.44 (cont.)
- 5. Regulatory Position C.5 is complied with. Furnace sensi-tized wrought austenitic stainless steels are not used in components and parts of the reactor coolant pressure boundary and associated systems.
- 6. Regulatory Position C 6 is complied with except that inter-granular corrosion testing is not routinely performed.
Welding practices are controlled to prevent significant sensitization of the base metal heat affected zone by pro-cedural control of welding heat input, limiting interpass temperature, limiting weaving and making provision for resolution heat treatment after welding in special cases. For the equipment within the B&W scope of supply, the degree of partial compliance with this Regulatory Guide is as follows: Cleaning procedures are employed to ensure removal of all con-taminants prior to any hot forming or heat treatment operations by the use of solvents or other approved methods per controlled procedures and technical instructions. A final cleaning inspection made prior to component shipment includes a thorough visual inspection with subsequent demineralized water flushing. Com-ponents are shipped in a sealed condition with moisture absorbent materials. An external means of determining humidity within the sealed component is provided. Water chemistry control is used during testing and operation to prevent an environment that may - be conducive to stress corrosion cracking. All grades of austenitic stainless steels (AISI type 3xx series) are required to be furnished in the fully solution heat treated condition before fabrication or assembly into component and system. ! The solution heat treatment varies according to the applicable material specifications. All austenitic stainless steels are furnished in accordance with applicable material specifications. The procedures of ASTM-A262 Practice E inspection are used when required by the applicable material specifications. Those austenitic stainless steels that are exposed to hot forming are subjected to the same requirements as the original furnished material after completion of hot forming. AISI Type 304 and 316 stainless steels are the only two non-stabilized grades of austenitic stainless steels with a carbon content greater than 0.03%, that were selected for components of the reactor coolant pressure boundary. All unstabilized austenitic stainless steels are specified to the solution annealed condition. Any inspection to verify susceptibility to intergranular attack is only used when included in applicable material specification. I l
. m ,
. Response to R. G. 1.44 (con't) -
The unstabilized austenitic stainless steels with carbon content greater than 0.03% used will be exposed to reactor coolant which meets the following water chemistry requirements when
. above 250F:
Chloride content 0.15 ppm (max.) Fluoride content 0.15 ppm (max.) Oxygen content 0.10 ppm (max.) Oxygen scavengers such as hydrozine are used below 250F. Furnace sensitized wrought stainless steel is not used in the components parts'of the reactor coolant pressure boundary. Whenever stainless steel cos.ponents were welded to ferritic materials, Inconel buttering of the ferritic material, followed by a stress-relief heat treatment has preceded joining of the two components with Inconel weld metal. All austenitic type stainless steels were purchased'in suitable heat treated conditions (solution anneal). To prevent significant sensitization of the base metal heat affected zone during welding, the welding procedures (current, voltage, and travel speed) were controlled to meet the following guidelines: .
- a. Limit the amount of heat input during fabrication.
- b. Limit interpass temperature.9
- c. Avoid excessive weaving.
The levels of the above guidelines are dependent on the selected welding practice. As an example, the following four welding processes are used to weld stainless steel internals. Only argon or helium gas is used as a purge gas in the welding processes.
- a. Automatic submerged arc (ASA)
- b. Gas metal arc (GMA)
- c. Gas tungsten arc (GTA) d.- Shielded metal arc (SMA)
- 1. The automatic submerged arc (ASA) is a welding process in which the heat for welding is supplied by an arc developed between the bare-metal, consumable electrode and the
m - .. . . . . I _
. ' '.Rg2 ponce to R. G. 1.44 (con ' t) workpiece. The arc is shielded by a layer of granular and fusible flux, which blankets the molten weld metal and the base metal near the joint, and protects molten weld metal from atmospheric contamination.
The automatic submerged arc welding parameters were set, so that the maximum heat input would be 90,000 joules / inch. .
- 2. Gas metal arc (GMA) is an arc welding prccess in which the heat for welding is generated by an arc between a consumable electrode and the work metal. The bare solid electrode becomes the filler metal as it is consumed. The welding area is protected from atmospheric contamination by a gaseous shield provided by a stream of inert gas or mixture of inert gases, fed through the electrode holder.
The gas metal arc welding parameters were set, so that the maximum heat input would be less than 84,000 joules / inch.
- 3. Gas tungsten arc (GTA) is an arc welding process in which she heat is produced between a nonconsumable electrode and the work metal. The welding area is protected by an inert gaseous shield.
The gas tungsten arc welding parameters were set so that the maximum heat input would be 60,000 joules / inch.
- 4. Shielded metal arc (SMA) is a welding process in which the heat for welding is generated by an arc established between a flux-covered consumable electrode and the work.
The welding area is protected from atmospheric contamin-ation by an isert gaseous shield obtained from combustion and decomposition of the flux covering. The. shielded metal arc welding parameters were set so that the maximum heat input would be 60,000 joules / inch. Periodic checks were conducted on the weld deposits by Quality Control personnel to assure that the procedures were actually followed. The weld data sheets register the heat input range for the process for each weld. The welding processes utilized by Babcock & Wilcox in manufacturing nuclear components will not cause deleterious sensitization of austenitic stainless steel. This statement is supported by the testing conducted by Babcock & Wilcox in accordance with accepted standard test procedures. Type 304 S.S. was exposed, in these tests, to a series of thermal treatment cycles that occur in our welding processes. This thermally cycled m.iterial was subsequently subjected to and passed the intergranular corrosion test described in ASTM A393.
- n -
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. . ~ . _ _
. Response to R.G. ~1. 4 4 ' (con ' t)
The excellent operating experience of PWR reactor systems containing austenitic stainless steel components provides assurance of the acceptability of these materials for their intended use. e l L
p . . .
.. i, -.
REGULATORY GUIDE 1.50 CONTROL OF PREHEAT TEMPERATURE FOR WELDING OF LOW-ALLOY STEEL (May 1973) RESPONSE TO REGULATORY POSITION The Midland project complies with the requirements of Regulatory Guide 1.50 except as described below. Exceptions for the construction of balance of plant equip-ment and the installation of the NSS: (1)
Reference:
Paragraph C.l.a of the Regulatory Guide. The Regulatory Position is complied with when impact testing in accordance with Subarticle 2300 of Section III of the ASME Boiler and Pressure Vessel Code is required. When impact testing is not required, specification of a maximum interpa'ss temperature in the welding procedure is not necessary in order to assure that the required mechanical' properties are met. The minimum preheat temperatures of Appendix D of Section III of the ASME Boiler and Pressure Vessel Code are required to be met regardless of whether impact testing is required or not. (2)
Reference:
Paragraph C.l.b of the Regulatory Guide. The Regulatory Position is not complied with since the welding procedure qualification requirements of Section III and IX of the ASME Boiler and Pressure vessel Code are considered to be more than adequate. (3)
Reference:
Paragraph C.2 of the Regulatory Guide. Current usage of low alloy steel in piping, pumps and valves is minimal and normally is limited to Class 3 construction. When low alloy steel piping, pumps and valves are used, preheat is maintained until welding is complete but not until postweld heat treatment (PWHT) is performed, since the conditions which cause delayed cracking in the weld or heat affected zone (IIAZ) are not present. l
ras 3 _ -- s
- a w -
REGULATORY GUIDE 1.50 (cont'd) (4)
Reference:
Paragraph C.4 of the Regulatory-Guide. The-Regulatory Position is complied with when the Midland responses stated above are not met. For equipment within the B&W scope of supply, the degree of partial compliance with this Regulatory Guide is as follows: Pressure boundary welds on low-alloy steel components fabricated by B&W meet the following controls on the weld process: Procedure qualifications (PQ) are performed in conformance with section IX of the ASME code. Minimum and maximum temperatures are specified on the PQ. Qualification welding is performed within a specified range above the minimum preheat temperature, usually within 100 F. On production welds, B&W maintains preheat temperatures until a post-weld heat treatment has been performed or until the preheat temgerature is increased to a temperature of from 400 to 750 F and held for a minimum of 4 hours. Experience has shown this procedure to be satisfactory for diffusion of entrapped hydrogen. Weld temperatures are monitored to ensure conformance with these procedures. l
.1J m n
- ~ -
n REGULATORY GUIDE 1.65
-MATERIAL AND INSPECTIONS FOR REACTOR VESSEL CLOSURE STUDS (October 1973)
For the ecuipment within the B&W scope of supply, the degree of partial compliance with this Regulatory Guide is as follows: Reactor Vessel Closure Stud material meets one of the material specifications listed in the Regulatory Guide. Adequate fracture toughness is assured by compliance with the fracture toughness requirements of the ASME code (prior to the Summer'1973 addenda). Specified minimum yield strengths are in accordance with Appendix G of 10 CFR 50. Measured maximum tensile strengths vary and readings slightly in excess of 170 Ksi occasionally may occur. These are allow-able providing the fracture toughness properties comply with the ASME code (prior to the Summer 1973 addenda). The operating environment is not conducive to stress corrosion cracking, and, therefore, 170 Ksi is considered a guideline tensile strength rather than an upper limit. Metal plating is not applied. Inspection is in accordance with the ASME code requirements for sizes over 4 inches. After fabrication, but before use, the reactor vessel closure studs are coated with a corrosion-resistant film to protect them in the event of exposure to a potentially corrosive " media. Before removal of the closure head, the studs are raised and secured with the closure head. After removal of the closure head, the head and studs are stored in an area within the containment well separated from the refueling canal. After any inadvertent exposure to corrosive media (borated water) spills or leaks, the closure com-ponents will be promptly cleaned up. In addition, o-ringed seal plugs and alignment studs are provided to protect the vessel flange threads.
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s *. a .. REGULATORY GUIDE 1.66 NONDESTRUCTIVE EXAMINATION OF TUBULAR PRODUCTS (October 1973) RESPONSE TO REGULATORY POSITION ASME Section III Class 1, 2 and 3 balance of plant components comply with the requirements of the ASME Code in effect at date of purchase of the component. For the equipment within the B&W scope of supply, the degree of partial compliance with this Regulatory Guide is as follows: Nondestructive examinations of tubular products in the USS scope of supply are --v' armed in accordance with the requirements of the ASME Sectio' _Je edition and addenda specified for Midland, (1968 edit. ., including Summer Addenda). Mondestructive examinations are not in compliance with the current Regulatory Guide (Summer 1975) . Nondestructive examinations for steam generator tubes were performed to the following requirements: Tubing meets ASME Section III, 1968, Summer Addenda requirements. Tubing is hydro tested to 3125 psi, with test pressure held for ten sec.onds. Tubing is 100 percent ultrasonically tested, according to ASME Section N 324.3 requirements. a) UT employs shear. wave inspection conducted in two opposite circumferential directions. b) Standard defects shall be two longitudinal notches, one on the inside surface and one on the outside surface. Notches shall have a depth equal to 3 percent'of wall thickness or 0.004", whichever is greater, and a length not exceeding 1/2 inch. The notch which produces the smaller indication shall be adopted as the calibration standard. j Each tube is 100 percent eddy current tested, as given in the ASME Code, Section III, 1968, including Summer Addenda. ! l l 1
p , i REGULATORY GUIDE 1.71 WELDER QUALIFICATION FOR AREAS OF LIMITED ACCESSIBILITY (December 1973) RESPONSE TO REGULATORY POSITION
- 1.
Reference:
Paragraphs C.1 and C2.a of the Regulatory Guide. Performance qualifications for personnel who weld under conditions of limited access, as defined in Regulatory Position C.1, are maintained in accordance with the applicable requirements of ASME Sections III and IX. Welding conducted in areas of limited access is subjected to nondestructive testing; no waiver of acceptance criteria because of the limited access is permitted.
- 2.
Reference:
Paragraph C.2 of the Regulatory Guide. Requalification is required when any of the essential variables of ASME Section IX are changed, or when any Authorized Inspector upon reviewing NDE results of a welder's work questions the ability of the welder to perform satisfactorily the requirements of ASME Sections III or IX.
- 3.
Reference:
Paragraph C.3 of the Regulatory Guide. Production welding is monitored and welding qualifica-tions are certified in accordance with Midland responses. i
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