ML20247F580

From kanterella
Jump to navigation Jump to search
Rev 2 to Reg Guide 1.99,Task Me 305-4, Radiation Embrittlement of Reactor Vessel Matls
ML20247F580
Person / Time
Issue date: 05/31/1988
From:
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
TASK-ME-305-4, TASK-RE REGGD-01.099, REGGD-1.099, NUDOCS 8907270187
Download: ML20247F580 (10)
v • d • e


Text

_ _ _ _ -. _..

Revistors 2 c(g,/%g REGULATORYGUIDE U.S. NUCLEAR REGULATORY COMMISSION Msy 1908

. $*s

.n

    • .s GFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.99 (Task ME 305-4)

RADIATION EMBRMTLEMENT OF REACTOR VESSEL MATERIALS A. INTRODUCTION tion requirements in 10 CFR Part 50 have been cleared under OMB Clearance No. 3150-0011.

)

General Design Criterion 31, " Fracture Prevention of Reactor Coolaat Preuure Bcundary." of Appendix A " General Design B. DISCUSSION Criteria for Nuclear Power Plants," to 10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities," requires, in Some NRC requirements that necessitate calculation of radia-part, that the reactor coolant pressure boundary be designed with tion embrittlement are:

sufficient margin to ensure that, when stressed under operating, maintenance, testing, and pastulated accident conditions, (1) the

1. Paragraph V.A of Appendix G requires the effects of neutron boundary behaves in a nonbrittle manner and (2) the probability radiatian to be predicted from the results of pertinent radiation effects of rapidly propagating fracture is minimized. General Design studies. This guide provides such results ir. the form of calculative Criterion 31 also requires that the design reflect the uncertainties procedures that are acceptable to the NRC.

in detennining the effects of irradiation on material properties.

Append;x G, " Fracture Toughness Requirements," and Appendix

2. Paragraph V.B of Appendix G describes the basis for setting f

H. " Reactor Vessel Material Surveillance Prognun Requirements,"

the upper limit for pressure as a function of temperature during which implement, in pan, Crtterion 31, necessitate the calculation heatup and cooldown for a given service period in terms of the of changes in fracture toughness of reactor vessel materials caused predicted value of the adjusted reference temperature at the end by neutron radiation throughoet the service life. This guide describes of the service priod.

general procedures acceptable to the NRC staff for calculating tne effects of neutron radiation embrittlement of the low-alloy steels

3. The definition of reactor vessel beltliae given in Paragraph currently used for light-water-cooled reactor tusels.

H.F of Appendix G requires identification of re;iens of the reactor vessel that ere predicted to experience stafficient neutron radiation The calculative procedures given in Regulatory Position 1.1 of embrittlement to be considered in the selection of the most lisaiting this guide are not the sane as those given in the Prerwized Thermal material. Paragraphs HLA ond IV.A.1 specify the additional test Shock rule (l 5041, "Fraeture Toughness Requirements for Pro.

requirements for beltline enaterk.ls that supplement the requirements tection Against Pressurized Therwal Shock Events," of 10 CFR for reactor vessel materials generally.

Part 50) for calculating RTPTS, the reference temperature that is to be compared to the screening criterion given in the rule. The

4. Paragraph II.B of Appendix H incorporates ASTM E 185 information on which this Revision '2 is based may also affect the by reference. Paragraph 5.1 of ASTM E 185-82, "Stancard Prac-basis for the PTS rule. The staff is presently considering whether tice for Conducting Suneillance Tests for Light-Water Cooled to propose a change to $ 50 61.

Nuclear Power Reactor Vessels" (Ref.1), requires that the materials to be placed in surveillance be those that may limit operation of The Advisory Committee on Reactor SLfeguards inas been con-the reactor during its lihtime, i.e., those expected to have the highest sulted concerning this Fuide and has concurred in the regulatory adjusted reference temperature or the lowest Charpy upper-shelf position.

energy at end oflife. Both measures of radiation embrittlement must be considered. In Paragraph 7.6 of ASTM E 185-82, the require-Any information collecuon activities mentioned in this regulatory ments for the number of capsules and the withdrawal schedtde are guide are contained as requiremees in 10 CFR Part 50, which pro-beed on the calculated amount of radiation embrittlement at end vides the regulatory hsis for tMs guide. The information collec-of life.

8907270187 880531 PDR REGGD 01.099 R PDR USNRC REGULATORY G'JIDES The guides are issued in the foitowing ten broad divisions:

Regulatory Guides are issued to describe and make available to the pu blic methods acceptable to the N RC staf f of implementing

1. Power Reactors
6. Proeucts specifsc parts of the Cc'nmission's regulations, to dehneate tech-
2. Research and Test Reactors
7. Transportation niques used by the strff in evaluating specific problems or postu.
3. Fuets and Maternalc Facilit6es
8. Occupatio-nal Haaith lated accidents or to provide guidance to apolicants. Regulatory
4. Environroentti and Siting
9. Antitrus' ahd Financial Review Guides are nol substitutes for regulations, and compliance vAth
5. Materials and Plant Protection 10. General them is not required. Methods and solutions different from those set out in ttle guides will be acceptable if they provide a basis for the fmdingt fequisite to :ne issuance < r continuance of a permit or Copies of issued guides may be purchased from the Government ilCense W the Commission.

Printing Off 6ce at tree current GPO pr6ce. Information on current GPO pricss may be obtained by contacting the Superintended of This guide was issued afterconskforation s f con.fnents received from Doruments. U.S. Government Printing Of fica, Post Office flox the public. Comments and sugvest40rs tor improvements in these 37082, Washington, DC 20013-7082, telephone 002)275 2060 or guMos are encouragad at all times, and guides wif t be rev6 sed, as (202)275 2171.

appropelate, to accommodate cotoments art to reflect new informa-tton or empfrience.

Issued guloes mov Osu e purchased from the National 't schnical Written commentr may to suthnrtted to toe Rules and Procedures information Fc/vice on a standing order basis. Details on this Efeach, DRR ADM, V.E Nuclear s4egulatory Comrmssion, service may be obtained by writing NTIS, 5285 Port Royal road, Washington, Dd 2055b.

Springf6 eld VA 22161.

j The two measures of radiation embrittlement used in this gude Guthrie's derived formulas (Ref. 2) a-e 28'F for welds and 17'F are obtained from the results of the Charpy V-notch impact test.

for base metal despite extensive efforts to find a model that reduced Appendix G to 10 CFR Part 50 requires that a full curve of absorbed the fitting error. Thus the use of surveillance data from a given energy versus temperature be obtained thtuvgh the duc wbrittle reactor (in place of the calculative procedures given in this guide) requires considerable engineering judgment to evaluate the credibil-trtnsition temperature region. The adjustn. of ti trence temperature, ARTNDT, is defined in Appenoa J as tw..:mpera-ity of the data and assign suitable margins. When surveillance data ture shift in the Charpy curve for the irradiated material relative from the reactor in question become available, the weight given to that for the unirradiated material measured at the 30-foot-pound to them relative to the information in this guide will depend on the energy level, and the data that formed the basis for this guide were credibility of the surveillance data as judged by Abe following 304oot-pound sbift values. The second measure of radiation criteria:

embritdement is the decreate in the Charpy upper-shelf energy level, which is defined in ASTM E 185-82. This Revision 2 updates the

1. Materials in the capsules should ba those judged most likely cniculative procedures for the adjustment of reference temperature; to be controlling with regard to radiation embritdement according i

however, calculative procedures for the decrease in upper-shelf to the recondrendations of this guide.

j energy are unchanged because the preparatory work had not been

(

completed in time to include them in this revision.

2. Scatter in the plots of Charpy energy versus temperature for the irradiated and unitradiated conditions should be small enough De basis foi Equation 2 for ART DT (in Regulatory Position to permit the determination of the 30-foot-pund temperature and j

N 1.1 of this guide) is contained in publications by G. L Guthrie (Ref.

the upper-shdf energy unambiguously.

l

2) and G. R. Odette et al. (Ref. 3). Both of these papers used surveillance data from commercial pav.er reactors. The bases for
3. When there are two or more sets of surveillance data from l

their regression correlations were different in that Odette nude one reactor, the scatter of ARTNDT values about a best-fit line j

greater use of physical models of radiation embrittlement. Yet, he drawn as described in Regulatory Position 2.1 normally should be two papers contain similar recommendations: (1) separate correla-less than 28'F for welds and 17'F for base metal. Even if the fluence tion f.metions should be used for weld and base metal, (2) the fune-range is large (two or more orders of magnitude), the scatter should tion should be the prcduct of a chemistry factor and a fluence factor, not exceed twice those values. Even if the data fail this criterion (3) the parameters in the chemistry factor should be the elements for use in sbin calculations, they may be credible for determining j'

cepper and nickel, and (4) the fluence factor should provide a trend decrease in upgr-shelf energy if the upper shelf can be clearly deter-curve slope of about 0.25 to 0.30 on log-log paper at 10" n/cm2 ndned, fo!!owing the definition given in ASTM E 185-82 (Ref.1).

(E > 1 MeV), steeper at low fluences and flatter at high fluences.

Regulatory Position 1.1 is a blend of the correlation functions

4. The irradiation temperature of the Charpy specioens in the presened by these authors. Some test reauor data were used as capsule should match vessel wall ten.perature at the cladding / base a gui/ n establishing a cutoff for the chemistry factor for low-metal interface within 125'F.

copper n.aterials. The data base for ReFulatory Position 1.2 is that given by Spencer H. Bush (Ref. 4).

5. The surveillance data for the correlation monitor material in the capsule should fall within the scatier band of the data base for The measure of fluence used in this guide is the number of that naterial.

neutrons per square centimeter having energies greater than I million electron volts (E > 1 MeV). The differences in energy spectra at To use the surwillance data from a specific plant instead of the surveillance capsule and the vessel inner surface locations do Regulatory Position 1. one must develop a relationship of ART DT N

not appear to be great enough to warrant the use of a damage furu to fluence for that plant. Because such data are limited in number tion such as displacements per atom (dpa) (Ref. 5) in the analysis and subject to scatter, Regulatory Position 2 describes a procedure of the surveillance data base (Ref. 6).

in which the form of Equation 2 is to be used and the fluence fac-tor therein is retained, but the chemistry factor is determined by llowever, the neutron energy spectrum does change significantly the plant surveillance data. Of several possible ways to fit such data, with location in the vessel wall; hence for calculating the attenua-the method that minimizes the sums of the squares of the errors tion of radiation embrittlement through the vessel wall, it is was chosen somewhat arbitrarily. Its sse is justified in part by the necessary to use a damage function to determine ARTNDT versus fact that "least squares" is a common method for curve fitting.

radial distance into the wall. The most widely accepted damage func-Also, when there are only two data points, the least squares method tion at this time is dpa, and the attenuation formula (Equation 3) gives greater weight to the point with the higher ARTNDT: his ginn in Reguhtory Position 1.1 is based on the attenuation of dpa seems reasonable for fitting surveillance data, because generally naugh the -essel wall.

the higher data point will be the more recent and therefore will repre-xnt more modern procedurcs.

Sensitivity to r cutron radiation embrittlement may be affected by elements other than copper and nicitel. The original verum and C. HEGULATORY POSITION Revision 1 of this guide had a phosphorus term in the chemistry factor, but the studies on which this revisica was based found other

1. SURVEILLANCE DATA NOT AVAILABLE elenents such as phosphorus to be of secondary importance, i.e.,

including them ir. the an:Jysis did not produce a significantly bet-When credible surveillance data from the reactor in geestion ter fit of the dats.

are not available, calculation of neutron radiation embrittleraent of the beltline of reactor vessels oflight-water reactors should be based Scatter in the data base used for this guide is relapvely signifi-on the procedures in Regulatory Positions 1.1 and 1.2 within the cant, as evidenced by he fact that the standard deviations for limitations in Regulatory Position 1.3.

1.99-2

1,1 Adjusted Reference Temperature Here, oj is the standard deviation for the initial RTNDT. If a NDT or the nuterial in question is measured value of initial RT f

The adjusted reference temperature (ART) for each material in available, oj is to be estimated from the precision of the txt method

[ )h

(~

the beldine is given by the following expression:

11 not, and generic mean values for that class of material are used, oj is the standard deviation obtained from the set of data used to ART = Initial RT DT + ARTNDT + Margin (1) establish the mean.

N Initial RTNDT s the reference tempertuare for the unirradiated The standard deviation for ARTNDT, OA,is 287 for welds and i

material as defined in Paragraph NB-2331 of Section IU of the 17T for base metal, except that oA need not exceed 0.50 times ASME Ik.iler and Pressure Vessel Code (Ref. 7). If measured values the mean value of ART DT-N NDT or the material in question are not available, f

of initial RT generic mean values for that class' of material may be used if there 1.2 Charpy Upper-Shelf Energy are sufficient test results to establish a mean and standard devia-tion for the class.

Charpy upper-shelf energy should be assumed to decrease as a function of fluence and copper content as indicated in Figure 2.

ARTNDT s thc mean value of the adjustment in reference Linear interpolation is permitted.

i temperature caused by irradiation and 6hould be calculated as follows:

1.3 Limitations ARTNDT = (CF) f(0.28 - 0.10 log f)

(2)

Application of the 4tregoing procedures should le ribject to the following limitatio m CF (T) is the chemistry factor, a function of copper and nickel content. CF is given in Table i for welds and in Table 2 for base

1. The procedures apply to those grades of SA.302,336,533, j

metal (plates and forgings). Linear interpolation is permitted. In and 508 steels having minimum spe fied yield strengths of 50,000 d

Tables 1 and 2 "wJght-percent copper" and " weight-percent psi and undrr and to their welds and heat-affected zones.

nickel" are the best-ertimate values for the matetial, which will normally be the mean of the measured values for a plate or forging

2. The procedures are valid for r nominalirradiation temperr.tre or for weld samples made with the weld wire heat number that of 5507. Irradiation below 525T should be considered to pro-matches the critical vessel weld. If such values are not available, duce greater embrittlement, and irradiation above 5907 may be f-the upper limiting values given in the material specifications to which considered to produce less embrittlement. The correction factor used f

the vessel was buik my be used. If not available, conservative should be justified by reference to actual data.

(v estimates (mean plus one standard deviation) based on genetic data may be csed if justification is provided. If there is no informadon

3. Application of these procedures to fluence levels or to cop-available,0.35% copper and 1.0% nickel should be assumed.

per or nickel content beyond the v.nges given in Figure I and Tables i

The neutron fluence at any depth in the vessel wall, f(10" n/cm2 I and 2 or to materials having chernical compositions beyond the E > 1 MeV), is determined as follows:

range found in the data bases used for this guide should itjustified j

f " fsurf (e -0.24x)

(3) i

2. SURVEILLANCE DATA AVAILABLE I

where fsurf(10" n/cm, E > 1 MeV) is the calculated value of l

2 the. miron fluence at the inner wetted surface of the vessel at the When two or more crediole surveillance data sets (as defined

]

location of the postulated defect, and x (in inches)is the depth into in the Discussior,) become available from the reactor in question, the vessel wall measured from the vessel inner (wetted) surface.

they may be used to determine the adjusted reference temperature A'ternativdy, if dpa calcula: ions are made rs part of the fluence and the Charpy upper shelf energy of the beltline materials as analysis, the ratio of dpa at the depth in question to dpa at the inner described in Regulatory Positions 2.1 and 2.2, respectively.

surface may be substituted for the exponential attenuation factor in Equation 3.

2.1 Adjusted Reference Temperature The fluence factor, f.28 - 0.10 log f, is determined by calcula-The adjusted reference temperature should be obtained as 0

tion or from Figure 1.

follows. First, if there is clear evidence that the copper or nickel content of the surveillance weld differs from that of the vessel weld,

" Margin"is the qvanuty, T, that is to be added to obtain con-i.e., differs from the average for the weld wirr heat number servative, upper-bound values of adjusted reference temperature associated with the vessel weld and the surveillance weld, the i

(

for the calculations required by Appendix G to 10 CFR Part 50.

measured values of ARTNDT should be adjusted by multiplying

]

them by the ratio of the chemistry factor for the venel weld to that

{

for the surveillance wc!d. Second, the surveillance data should be j

fitted using Equation 2 to obtain the relationship of ARTNDT to

)

Margin = 2 V oj + of (4) fluence. To do so, calculate the chemistry factor, CF, for the best j

NDT y its corresponding I

fit by multiplying each adjusted ART b

f(

fluence factor, summing the producu, and dividing by the sum of eth1 e 7e he sqwes e

nce MR ne msung vawe w a een h

ty se efpe f e gu(

w oi for tme metal.55y the ASW Standard spentramm.

entered in Equation 2 will give the relationship of ARTNDT to 1.99-3

I TAB 121 CifEMISTRY FACTOR FOR WELDS, 'F i

l Nickel, Wt-%

Cop %

per, Wi-0 0.20 0.40 0.60 0.80 1.00 1.20 0

20 20 20 20 20 20 20 0.01 20 20 20 20 20 20 20 0.02 21 26 27 27 27 27 27 0.03 22 35 41 41 41 41 41 0.04 24 43 54 54 54

$4 54 0.05 26 49 67 68 68 68 68 0.M 20 52 77 82 82 82 82 0.07 32 55 85 95 P5 95 95 0.08 36 58 90 106 108 108 108

(

0,09 40 61 94 115 122 122 122 0.10 44 65 97 122 133 135 135 0.11 49 68 101 130 144 148 148 0.12 52 72 103 135 153 161 161 0.13 58 76 106 139 162 172 176 0.14 61 79 109 142 168 182 188 0.15 66 84 112 146 175 191 200 l

0.16 70 88 115 149 178 199 211 0.17 75 92 119 151 184 207 221 0,18 79 95 122 154 187 214 230 0.19 83 100 126 157 191 220 238

.0.20 88 104 129 160 194 223 245 0.21 92 108 133 164 197 229 252 4

0.22 97 112 137 167 200 232 257 I

0.23 101 117 140 169 203 236 203 0.24 105 121 144 173 206 239 268 0.25 110 126 148 176 209 243 272 0.26 113 130 151 180 212 246 276 0.27 119 134 155 184 216 249 280 0.28 122 138 160 187 218 251 284 0.29 128 142 164 191 222 254 287 0.30 131 146 167 194 225 257 290 0.31 136 151 172 198 228 260 293 0.32 140 155 175 202 231 263 2%

0.33 144 160 180 205 234 2o6 299 0.34 149 164 184 209 238 269 302 0.35 153 168 187 212 241 272 305 0.36 158 172 191 216 245 275 308 0.37 162 177 1%

220 248 278 311 0.38 166 182 200 223 250 281 314 0.39 171 185 203 227 254 285 317 0.40 175 189 207 231 257 288 320 fluence that fits the plant surveillance data in such a way as to to obtain mean values cef shift, ARTNDT. La calculating the margin, minimize the sum of the squares of the errors.

the value of oA may be reduced from the values givec in the last paragraph of Regulatory Position 1.1 by an amount to te decided To calculate the margin in this case, use Equation 4; the values on a case-l.y-case insis, depending on where the measurrd values given there for oA may be cut in half.

fall relative to the mean calculated for the surveillance materials.

If this procedure gives a higher value of adjusted reference temperature than that given by using the procedures of Regulatory 2.2 Charpy Upper-Shelf Energy Positian 1.1, the surveillance data should be used if this procedure gives a lower value, either may be used.

The decrease in upper-shelf energy may be obtained by plot.

ting the reluced plant suseillance data on Figure 2 of this guide For plants having surveillance data that are credible in all respects s.nd fitting the data with a line drawn parallel to the existing lines except the the material does not represent the critical material in as the upper bound of all the data This line should be used in the vessel, the calculative procedures in this guide should be used preference to the exis*.ing paph.

1.99-4

f 1i:

TABLE 2 CHEMISTRY FACTOR FOR BASE METAL. 'F

...-m (j Copper, Nickel, Wi-%

Wi-%

0 0.20 0.40 0.60 0.80 1.00 1.20 0

20 20 20 20 20 20 20 0.01 20 20 20 20 20 20 20 0.02 20 20 20 20 20 20 20 0.03 20 20 20 20 20 20 20 0.04 22 26 26 26 26 26-26

-0.05 25 31 31 31 31 31 31

'O.06 28 37 37 37 37 37 37 0.07 31 43 44 44 44 44 44 0.0R 34 48 51 51 51 51 51 0,09 37 53 58 58 58 58 58 0.10 41 58 65 65 67 67 67 0.I1 45 62 72 74 77 77 77 0.12' 49 67 79 83 86 86 86 0.13 53 7I 85 91 96 96 0.14 57 75 91 100 105 106 106 0.15 61 80 99 110 115 117 117 0.16 65 84 104 118 123 125 125 0.17 69 88 110 127 132 135 135 0.18 73 92 115 134 141 144 144 0.19 78 97 120 142 150 154 151 0.20 82 102 125 149 159 164 165 0.21 86 107 129 155 167 172 174 0.22 91 112 134 161 176 181 184 0.23 95 117 13E 167 184 190 194 0.24 100 121 143 172 191 199 2M s

1 104 126 14'8 176 199 208 214

(/. 0.25 0.26 109 130 151 180 205 216 221 0.27 114 134 155 184 211 225 230 0.28 119 138 160 187 216 233 239 0.29 124 142 1M 191 221 241 248 0.30 129 146 167 194 225 249 257 0.31 134 151 172 198 228 255 266 0.32 139 155 175 202 231 260 274 0.31 144 160 180 205 234 264 282 0.34 149 164 184 200 238 268 2%

0.35 153 168 187 212 241 272 298 0.36' 158 173 191 216 245 275 303 0.37 152 177 196

't20 248 278 308 0.38 166 182 200 223 250 281 313 0.39 171 185 203 227 254 285 317 0.40 175 189 207

_ 231 257 288 320

3. REQUIREMENT FOR NEW PI ANTS D. IMPLEMENTATION For beltline material.s in the reactor vessel for a new plant, the The purpose of 'his section is to provide infornration to applicants content of sesidual elemene such as copper, phosphorus, sulfur, and licensees regarding the NRC staff's plans for using this i

and vanadium should be controlled to low levels.* The copper con-regulatory guide. Except in those cases in whwh an applicant pro-tent should be such (Ntt the ca:culated adpted reference temperature poses an acceptable ahernative method for complying with specified I

at the 1/4T position in the vessel wail at end of life is less than portions of the Commission's regulations, the methods described

{

200'F. In selecting the optimum amount of nickel to be used, its in this gukle will be used as follows:

deleterious effect on radiation enibrittlenere should be balanced against its beneficial metallurgical effects and its tendency to lower

1. The methods described in Regulatory Positions 1 and 2 of g

the initial RTNDT.

this guide will be used by the NRC staff in evaluating rJ1 predic-4

  • hw mm udunnauon. we or Anestis tc AS'!M 5tarulard Specirwaem A SD 4Ref. 8).

G and H to 10 CFR Part 50.

1.99-5

2. Holders of licenses and permits should use the methods Technical Specifications in or6er to contir.ue to satisfy the described in this guide to predict the effect of neutrou radiation on requirements of Section V of Appendix G, ?O CFR Part 50.

reactor vessel nwer;als as required by Paragraph V./. of Appen-dis O to 10 CFR Part 50, unless they can justify the use of dif-3 The recommendations of Regulatory Position 3 are essen-Jerent methods. The use of the Revision 2 methodology may result tially unchanged f om those used to evaluate construction permit in a modification of the pressure-temp:rature limits contained in applications docketed on or after June 1,1977.

O O,

1.99 6

REFERENCES

1. American Society for Testing and Materials, "Standed Prac-
5. American Society for Testing and Materials, " Standard Prec-tice for Conducting Survestlance Tests for Light-Water Cooled tice for Characterizing Neutron Exposures in Ferritic Stee!s in

,Q Nuclear Power Reactor Vessels," ASTM E 185-82, July 1982.*

Terms of Displacement per Atoa (DPA)," AS7M E 693-79, j

August 1979.*

2. G. L. Guthrie, "Charpy Trend Curves liased on 177 PWR D'Aa
6. W. N. McElro3, " LWR Presure Venel Surveillance Dosimetry Points,"in " LWR Pressure Vessel Surveillance Dosimetry im -

Improvement Prograrn: LWR Power Reactor Surveibance provement Program," NUREG/CR-3391, Vol. 2, prepared by Physien-Dosimetry Data Base Cornpendiunt," NU1LG/

Hanford Engineering Development Laboratory, HEDI TME CR-3319, prepared by Hanford Engineering Development 83-22. April 1984.**

Laboratory, HEDI<TME 85-3, Angust i985.**

3. G. R. Octette et al., " Physically Besed Regression Correlations
7. American S ciety f Mechanical Engineers,Section III, of rmtrittlement Data from Reactor Pressure Vessel

" Nuclear Power Plant Components," of ASME Boiler ami Surveilbince Programs," Electric Power Research Institute, Pres *ure Fesstl Code, New York (updated frequent'y).it NP-3319, January 1984.t

8. American Society for T: sting arul Materials, "Statxlard Specification for Pressure Vessel Plates, Alloy Steel, Quended
4. S. H. Bush, " Structural Materials for Nuclear Pewer Plants,"

and Tempered, Manganese-Molybdenum and Manganese.

in Journal of Trsting oruf Evaluation, American Society for MolybdenureNickcl," ASTM A 533/A 533M-82, September Testing and Materials, November 1974.*

1982.*

4 i

t

\\

R'7

  • Ognes may be dunrul fran :tr American Sowty im Tesung and Materals 1916 Ran Suert. Phihujetphia, PA 19iO3.
    • Copra may be or4mred from that Superimemics.t of IMenments. U.S. Government Printma Offre. Pimt Ofrre ikin 37'182, Kaninrton. DC 200117082.

N'opies may be duned frmn the Elatric Power Rexatch Innmne. 3412 lhuview Aesnue. hio Atto. CA 94%4.

f tCorers may be obinant inun er Aneracan Socery of Mchamcal Pgurtrs,345 E 47th Stacet. New York, NY 10017, i.9 M O

Y e'

-i. p

.T i.

p g

h;'

g.G g ' ~ 3%.h ..n:.: p" c Y $;,k., v E.; ~;' W," M m= C- ='. / ,<.* =5 -: .*/,m /ga. - s '~- , ps *f. ". ' " ~ ~ -fq,", ~ .a ,t ~ ,,,a.**Y, 4* p 'W

  • p Y

/ e-y 1 s s ,-4 .-r-v*- i.- w a ,.g,W e 'e> '.,,-v5,., "' - .a s, s. ./" - ,..,,"o*,'. ? #' ' ', .m.. 'M.. ec,, A * '\\ p [_- Y f- .y. '. V ?A s.*** .-= c- -I 51 3;;- Q'Q, s f V s - n s 2 g ",,3,.

5
-:.c'G-
-r p

-b s

  • s q*

b ' ' ' ^ ,~3 "y p ~~~ ,U 0TE ( m, yT g faQ .m*Y,,.' .~. ~"' ^*se L - ** e e e. 5- = - = f.-. 'Y g '604 T d j g g;

.m.. -

10,,. j ' e-c 1*- 1 s 9 ,.s q ,,a" 6 C y .e *;

    • f,,
  • )

e s s .**[,,,***

  • =

6* ,,*"Y .e** b C-r ,A,, , '.. - '/; + j+s ^"' J,,*.-a - s ,,ek ~, /, s.* f~ / n. - / / c Y 'p ,,e { ,*

  • 1' s

s w* , /n.- s a ./ "*,,/ / , ' '"Y "". p

Q:s.- _

p a'.n*'**' , a-T*i.-r.,,J,4 g ,,a ' ~

    • E$'hi.-

'i,^- s - c; y 4.'n.- ,e e\\ 9 p 0 / ~ ^'. S S e TI ' 5 iii 2 4:- y*0

  • d,,g[h.@ -

s-; ,,,,..g 'g, 5=: sif.,,,, '; E.. ..e**' ~5 ",,s,-1-f.. f. 4's-y** / e g, er s,,,.C, s 1 3 T [ g. p ? s .s,- "f ; s N :.;: '%, b W '"..y.g. n ,,p a#*** ,f y- ,y o** ,a*" . o 0 age ,d-6 .u, 'T' ~" .s.A*,a.s',, 4 p. .c ,,.e**,. h pe s

  • "' j '"#

t 'p l-p - p- ,;. -r'st L.. e;. 3 }. A*. -r i t -w ,1, ~ -e s

  • pod -

5,,., **** J -A'[w 'Y..);d '.,,A ,-g ,e 2- ...J' E ^ p.m1 - r C.i ,],,. - $s ~ W.h. pa

  • W i

.n go

T);dg'Igk{g in'~ih %~"M?{ I "-~.)) M.."[0ft[ H'T

  • ~ L M

A4 tH. tL Ip_.1_ T% pia. i m ,v q 'pd g 44 k.#4, 2 m l t 7 L'. ~** + . r r;+r kt..n 4.n-u ,+ tgg yp 4 ggh MjMi pMpij jgtgg{.

  • a t:t =

unt: t*cw

g.:nb.p@tyf-q =4

- m ig .d.t 4 e p2L_ 2:.:::M., - N t tt 'ttct.ur ; t:T mtt" c. k ~~' l 4 ig.g. _gta ge 7r q.pq..n_g.._=g gi.is

y. g m

g= L 4 _ g s gi l ',el a a u a t ih.... 1.

r., tp

,t h.r 'r 79 & ) 1 a. .,t Gh 79h,ty {. yq -f f...t j [y...} b F.. _+M j}.. g^.--- b 1' ]. ;,1 p . J t IJ ..._} . 4, 4 -J L!

k.,W !.,t 1 4 L

m e ( y g,..- g g .Q. 7 1 w 1 ); 1 m t v r wru u.m r s 3 4=te g i?WEifj R .i i r if u i 4 p g a .- 4 q h itE iih i 1 4ksEMid55 E N iAI ik Ill IIE !!E!n If :tE b $dhi li@ M4 FEE 35fTfEiE#E E !!!! h$$!iNMbli4,S l E!!! Eiii WiflMUMF SEEHii @! i$Ei$iEEi

  1. pdAMMvpEri-+-;.,: e s pAahd; bqp;eh

,ip +tw

4 3

s t

w and w

w g .hn i = n .N._N!!MNI'N b NII IIII h NN N, Ij$fIk i [b ikk k!I hMNa.5i N t m e 0

GCt!

b M ( g 3 w e n ... fp g .,}{.; ..?1,,':1; ,it {= ..$ N. e t.'}h.p;.,t+.yh T a \\,m _~___ q4 1 p n 7 w .= y 77 g.. yt+;.pt-t y L* y; 4 s H% a% p.- 7..,:..g g pg ; t.p +:g imf4 %.e w y 7;p:#q + i. .4. ,. a,.L, 3 L4.,4sy [.9 i ,ht. }4 ot4 _.L ..m

4. +.

.u . +, r .r..r D p ..j..NEi .etm.r. r. U [.h..i. 5., . Q,C ot b ,&p . {gt y ,4 +te&~ 4 7g , a.. J ,g w .4 _.1. ___..

p. a.u..g, 4

.. @ 4.t.g# ._4.y... 1 u. m g4.. _r_ 7 t p_ rt* w_ 4 c f ..f 5 f. a i6' -...h. g I., 3 i.. d.... ~ .a 4 [; 4 . p g jf [ 3 3.4.g 13 g q M} .g. l q .j .t. trit iiil Hf~- / Ti if Li I 1 MM d-l ^itT T "o 'E o o m o ml J

  1. si H if !

i i iW W Ni ib Wi pi M o 11 l 5 ,f, rTp7 t' p.- p@ Fg 14+, w-D 1 o m yJ y. -p 34 .j t 1 i A 4 CD 'd W do d d d d!

s! fil hr[sifNif iOi lh!.i@ ini E

t t 2 .,J (9 N N v-w o-ijnj!)r YiINd' I % !!EiNfdh lie # !!## 14N "a

mu..Ntm 5

6An-8 s...;s. ppt @t.ta.. tH o ..t: ... n o i!*!N#M NEtif.rQ..EE.a? E,*n,.in d o e oiE F..i. E.,- i 4w n88 N t4 A 4 cc 2: o o o o o 6 in pId o4.g au ijn ny dd p:.F

  • r!-h 3...e g+fT g..:rukw+fH+y.w[E,r

= nit nt at. nM h l'. n m+ t g un att._ - +. - 1m ah dr: i.i ml 3'gt-tf. =-.= .=, a:w n.. T +tte x

  • +y hn h:.ri. T![ ity *i].p *R.::

din :P; t .t.. 1 ,c t.

w..u-

.xx ? un. '.h. ; i --T-$ P- 'Th h.$$~ ,..f,p".

  • !TI hi: 1ltT ". * * *1M~4frT1 t{p

..+ 4,. e,-~ o-.. c..- 1,- w th[1' ' 11d

  • 77;itj 'ig t. fir 7 'I g

R1r.;f+;,+ 4,r.; M' ' ;.H F tM -tt+ T 4 h. + ' ~ - + ~ tt+ t-t-a +f 3#M g4gtp *x 'irn;m!j "o i1 iT 'qn:.M

g..

7w'T K -Z' :7 PC p.i-T4% n{M..te.:.11..H.u 2: O dit.tM mt a-u = m a. x o o o o o o N CD LD 4 M N 1003Jad 'ASJau3 pays u! assaJaa0 sJ 1.99-9

I-REGULATORY ANALYSIS A ccpy cf the regubion analysis pnpered for this R*Eulatory a fee at the Canmission's Public Dxument Pann at 1717 H Street Guide 1.99, Revision 2 is available for inspection and copying for NW., Washington, DC, under Regulatory Guide 1.99, Revision 2. I k G1 i 1 l J l i e O l i i 1.99-10

REFERENCES

1. American Society for Tening and Materials, " Standard Prac-
5. American Society for Testing and Materials, " Standard Prac-

/ i tice far Con &cting Survei'lara Tests for Light-U'er Cooled tice for Charactenzing Neutron Exposures in Ferritic Steels in (j Nuclaar Power Reactor Vessels," ASTM E J 85-82, July 1982.* Terms of Displacements per Atom (DPA)," ASTM E 693-79, August 1979.* 1 2, G. L. Guthrie, "Charpy Trend Curves Based on 177 PWR Data

6. W. N. McElroy, " LWR Preaure Vessel Surveillarice Dosimetry Points," in " LWR Pressure Vessel Surveillance Dosimetry 1*

Improvement Program: LWR Power Resear Surveillance provement Program," NUREG/CR-3391, Vol. 2, prepared by Physics-Dosimetry Data Base Compendirn," NUREG/ Hanford Engineering Developmem Laboratory, HSDL-TMi: CR-3319, prepared by Hanford Engineering Development E342, April 1984.** Laboratory, HEDL-TME 85-3 August 1985."

3. G. R. Odette et al., " Physically Based Regression Con relations
7. American Society of Mechanical Engineers, Section III, of Embrittlement Data from Reactor Pressure Vessel

" Nuclear Power Plant Components," of ASME Boiler and Surveillance Programs," Electric Power Research Ifastitute, Pressure Vessel Code, New York (updated frequently).tt NP-31419, January 1984.t

8. American Society for Testing and Materials, " Standard Specification for Pressure Vessel Plates, Alloy Steel, Quenched
4. S. H. Bush, " Structural Materials for Nuclear Power Plants,"

and Tempered, Manganese-Molybdenum and Manganese-in Journal of Testing and &oluation, American Society for Molybdenum-Nickel," ASTM A 533/A 533M-82, September Testing and Msterials, November 1974.* I?82.* l' i \\ t I l i I l 4 1 l ll ( ** ) S

  • Copra may be ohuiumd from the Amencan Socrety for Teanng and Matenals.1916 Race Street. Philadelphia, PA 19103.
    • Capes may be obtainod from the Supermtendent of Documents, U.S Government Pnnung Office. Post omcc twa 37082, Warington. DC 20013 7082.

tCopies nay be otemed from the Electne Power Research insutute. 3412 Mdivew Avenue. Pah Alto, CA 94Al. p ttCopies nur be ootaged from the Anencan Sixvty of Mechanical Engmeers. 345 E. 476. Street, New York, NY 10017, il 1.99-7 -A L-

2 &J 'i " S w== p r:34t=N ** - :.pa= p: - =i= =-a = = hh -

=

EkEb#MNid5 5fb kb MP MWiE =

== :~.===~t. =====~=1=:===- m===. p._ = es.;_ h. N=~2.========= =m= -=== 3,,=_ =.._g = ;= =_. p: r= = =_ = } E2 = = -~y~~ m --- m - l, l .l didIN$f $!E$$$$$$$!$$$N$$ SE:E EEE E4Ei EEE IEE =3;Ei}E==E55-WhE "EE 7--

-t=, =*-=
j

~ l n= _m H+- ___.l_-== [_ _[L-v.' {' ' l___-_ -- N l [ , ; i I I l- ~ I a ' _ ] c-- io a i! lN " [$ L __ -

  • ~T S

~~hi a#iMa M=E *EE!E=. 3- += =4E=t iss= =E###r, ,4 .ii - = -=.. L st.. 6 re shs=E= =E giEEsia

=== N===;,ga =.n=I=..=.... n -- dW}ss#E % = w +- - : g =.p=.== -. =. =. _. _- - _ :==r :, - = =~a~ = _ -p I xcu - + -.. - - ~ = r- "*~ 1 s e'-'-'+"" l e ........__..a. l 5E E E=~E N $ N ;'N55 ~ a t== p_ e = s a i = = r e s =i = e s e = M _. _ _ g g ._g - 3: -g=== y_ : ~ _ _ E o M a .q=. = _3.=___~,. .2 3 -- -- 3<:. 1 _Q I c e I g

  • -t 4,

--... I I - N u 1 c p l [ 7 s a r -4. - H _ w, c s I t _g _ _ _ _ _._ a _ i i ~ .l y$ y s 1i ' l- : 1 5 f L -EE-E=, f { l

=,st bW Mtt i==+ -

1 l ' 6JKiM-/# 315% jy EEE EEM-4E Et@, Er t=sst 5#ahj=~ : =-ET- :EQ We[ =. = = -=== -=Et=_=. _:==,

= = = : = =.=: -

m =fE4Ei=E3E -==T==== n==-p. a = t =

== O =.-

=:4

-::=m-n ~p=p= =,....- o =4, 4::t= :-

== = i . i +-+l I 4 "E MYN s i l MI 'Ib5Nb NN M=b. [g?;- p:Er= =- =. T~. EE- := EEE ~ F= 5 HEE 5:E==~EEE E2 Q C' E =35 = 3 333E h== m-.f_~~. - ~ =- Ch.,_-=gg:g=E gr =j3. :g 3 ~~--4==u m

==- . J- _ -q- '.... l. l - t I i_. I l l 4 y ~ l I _7 I ' _& [ Y( L l 1 4 i 1 lj t., i3 4 i i i n __i - t e.' R i6. v. n. n. m o'os. e. n. Y e <g j W83 8"Nd l 3 Sot ot o-gr o 1,99-8 4

IW! muh F % # f i'li i t O nti..

i!!

!-h i!fN ! 'jI, 8 ui i swii ,i I i1 fD J i' I, 7 i itI-i;- t !' 6 + 9 > t.I l$ i 5 ?> .W%%* fp' @!wY t l [' d 1 i ,}:j: r hpg"'n,t, dnb t' t, p[t ,.." h '0' ij!,!! ,.N si i hi: n i a# it'> l 1 g-

' 4 l

ff :.' Idj 1iI:!l; 4' i t-i!g! ~1,' i 'a Il ~. fl1Ji } s 1 i,.' l i" q [ ,k m' 3 ..'l' g 'I+ ~ a "a 2 a. I N ~ 3 i f .e ,da- ~ - ~ T ~ 2 ~ D N I 's _ 1 ~ T 2 ~ ~ 1 0 R t, "o* @ b,. p .i. f* 1 jin" h j. 4,jhi 9 A d.fH' n 0 ,k.3 1"

i' i -;

rM !jl t" e pn 3. 4 I l ,j-l9 !,i gf# ihjH' 8's t" b ..i[9 !iI h 1 h-1 hi" r I 8 o e i" l { Tl f Ji j! ~ i)3k" P,i ;j 7 n a j !i" ' l j i s e .' 1:c, th -- 6 se 1 j r ) p d s ~ V x i e 5 j>!.

Ull ini'Mx

.St int 4 % N e E il k" !k; g" h n h: 1 M e t y!b @' Wi i- ,Mt [ d enij ? /%f% l oU h jti" ilmiq i j n H!!i' r,$,f n." iH a h i n' .,!gi mh! iiI !ri+ 4 1 t _a" - 4 2,

!!tii i
jll,

{II.+ .;il' h i'-Pn, E n 1f ( i O 0 l t o 3 t ,l a l e-l-i m u ylq c q 3 ll / E l L - n n i ~ ,4}p. e, i e ~ 2 c s n U e ~ a,,e,' - 7 h l f u r e o ~ T F r o i! - t 'p,,* e - ~ ca ~ F 2 -.s. =- - ~ ib c $%ti i :. 1 0 i! i, l" i :'i., i i Nn D$d$"" k#d* hyy":. J n M!' W ", m,W! i : i aL p l tnHnyn!!jHu i p d 1 e i I 9 u!! u i iii it [ ,!t 8 F ,2 !.i! !4i' i i; 4 i j' 1 1 iIiiihlitI' i {' I! {[ 7 } l'a FR ! t,' 6 U G i .-) l M' 5 I F i ' N,p,,+%1. nm > 4! h [k f.t cnApimIi' ' n n"' ,!:$h I [' h ll3b i . i + lU'j- !q,T, ppi{' [' j;r : atli i ,I; ii .y1-,:M l 4 ioI m HI tl Y .l.' ep.. l.{ g .i htI ' H/' -Il 4 I 3 ~ E }'* t L,iJi r l - e '8 2 ll. p t' ,j eld's - i!' fL s j e3i ~ i' i I f 1 .l _ v,k "0 ~ .I I- - a-1 s i O g I 0 5 0g 8*a6 5 3 2 3, 1 2 1 1 - cR S 1 5tE eE$- r$k \\

I e r -r;;;; ;;t;;;g;p.;p;;- 4; : _;++.77744

g 1Q+

+-

Mit:+p;:ttw -+46;"+

' / q] t;;;g 4bg: n 1 1 tr.j t$t1::. l

tl
t..

t + t"+ t+ -;4-i

J+

. 1't4t k+t_ "*.";n.'.tt.+%r:t+1r_xx 4t+ F-A_7 ..__. _t..# l 1 +1 o I e .+++ ---~ ++tr44}} ff-- ---fi- - jp 4 =n tq p-=:=:;- hiy I- $45 siij$ lEf43 }4 W @ 3 NV = ~~ ~'~ +t: :Agn-pp-hp;. gdgt. ftrp

ar:

n =::;r

j in:

t_4=.]. r b 1:a tr2 6 ~ ..rc w t{4 th $7mt:' ' f

t. 14 h
J i j
N.

tt+ tt Lt n Ntt; :t-Mt.r-munt::n T: u .::".:1::: itd'. .td:t t4 $d :nt;. tg.,t = M , J. i -:::;f++ t*:lt; +T~.+4:q

t.
$x 4 +{+:.g L.

4., +++. 7 . x.g. g"+4-.9m$- q.+ + +

1 L

,4 ,p_. ~ y m + 4

v. -

-.1 ..'t+tj[,tf.R.- - f---{.. J f - y ~-H,I.p. .....4. ..g ,o. of + 7. p 37 {_. g._ __; _.y,. g p. [L(.y ..}..y ___ y _ t._..L g . p.g ) _ _] a h. y q l .4

g. 4..j

_ g 3 i l 1. g u ..t...l... _+.__-- t i n

t. o

.J,T i l 1 1 o,. i o [ t1 p t Le =. eg

g
3 W +

n . 4 p . p 3 . (1O M 1hi: 4U-1 4=tMiMi Mi iii h fi-in& Ji }i ici.K E e ill 4 ildhi di~ MMF $ Ed M llMdi EMI M 1M0 E U H. i.+1 pt tu : tjp 24u.r 1r usehr gItui pd..,(edtgf il: q;:r up:. d>ntrt.t. g 4

==v
tt:

g m te.

m.. m a,

t.rtt .rt. m. 4 o e e

ngMt.

E g n ..a = 4_-.- ; fI3.. tg 1.cgih:.;:tgL + u t=

$i h. Mggy n

l -:!n,;.g.f p $ nk ttr

n L

>1 o ] !p#

.,j!.y:

itIW ++ n rt..

+t

. [~.i,. ~~ jtd d

a;;

A t 4 4' t:. g+4.e.{+t Y.g' 9, py9w:"11:. g5 y4 w u p ,,p.. Hr .. n. f y !X t4 d !Mit FiMWW s di @ {11 9 si % Hilt iin u V

m.e.}k<.4 Q:F:j:Y__$j!...,t., p a. '.3 Ei.h.tti, jji (y.ie i.lH@ ii.f.@.

b 5 l @. W. g L s t t .. tt[r anyt; m: 7 7 .y C m tr ig:t= h g;ny+3 Lgt = ;m a;: m

+31$

uf ~- aft C; q g n:N"

r~

.k.I[N M;Ot-t: f? MZCCC3,r 01: L :MM,.:t1t77 \\.

t

.t. tite,J 4_ O y 4.. m. i, +.A.a,. ~:: 7 ~ 4.c .J.4y,4, + t,

_., q_;. _

Tty-t; t+2;., J. qm; !n!. + ....n m 4._ Z g -H. -.- .,.. _..o.y 9 ,e .L4,.4.,- ~., i e.it_ 'd 3 m 4 ...m y1 +,.e .e. A. ..i _ [+ r m m f' f_ ....+ ..__ h.cn

a...

3m.,; v.9.. n e i.,

g. u p

__-._, j _.y {L .g. ,p% .., e J 34.- u. r y h g a. L._ . 9, ,u.. g y_ g p .._ q.f [] L __q.------ t.g m +H 4. e- .e .h o-F r-r-v- rt r-h-g o l . y y.. g g[. . L} Jg g gp p.{ 4 4u t

  • . ar 4 g a_

7 ..+. q. .. gg{. g.[.jp j py. . _.g,. _,4 gm gp h_, _ ___ g g'l i. y g g 4 l m j 4 t ! ii Nh # i id 4H4 HH - F 5 ij

i 4
y. k... q.. ;'al i. ;+. 4. t pt n

Q omo m o_

m. =.n.

y.g 7 q u, 6 6 6 6: .c si :.!! Flij 44M idi !ili iM ini c n _a n. o ijiFi!!fcr w oo i: =.. .. f m!E+nd c. _#:. - i:4 as.&1! ' lid'..lii.. ma,. n -w

. SI! id..He m

= c w a it.ics ;..

$r. 11;;?
: m u

tij; it? *~ Q

2:

.;; 1?rt] {i !1t11;jn

1M JtN:O

.J . t* tt*! itit:ttil 0 '17 *1.. l- +%+.Jffy. 4t! 3 w< 1 .;ucrt+r E TtEty-

  1. 4p m e-eoe o m o-
g., ww-

..+++e M - : "*; '!;;.+4 WJ M4 4Tmn# 4t! #ti j ptr ti.4 <w q co q N - gL R...m 2 o c o 6 6 el 7 W IId 4Ip. n e e ,; u H .u. a m !"m r#UI m. o mt ..'#t ".h.. r t* ...._..--t' - aju. {H..i ]g+t....m. o. --i .... m.. = - +r: h f n a.il.t ip,2p3 !!n.. g. i L:n.I.Ln m-... p,2.:_.n p.t._4==....,:m t t t arr . ~ n. . y.. - g . p.. m c

. n'T ::n : r;:. :m ::Tr n :-
~

aft-z.t: Or uh.t m.mr :m mt4t;:t t::: .py+ tm ntt:nf.p pt:1r x2xtr

jn.m
:=
  • tmt.:

u m.a::tn: 4:: 3 4 w.. C 4tt A.e ,+ + J.4 ... +- T.

t. i t.y _r_-.4--e_

.... +., +., i.,4,s. + m,.,,,. i*rrrv.,n' @... .uA 1 +*. A .,y,.,,.44 o,_ m., y 4 tr .++., .,_.+.. t+ +t1 b+ .%,4 ne +. ~ rt1[ .a .+ n x o o o o o o O O m 4 to N e- [ tuaaJad 'A6aeog }leys u! eseaJaPG \\ \\ 1.99-9

REGULATORY ANALYS.S A copy of the regulatory snalysis prepared for this Regulatory a fee at the Commission's Public Document Room at 1717 H Street Guide 1.99, Revision 2, is available for inspection and copying for NW., Washington, DC, under Regulatory Guide 1.99, Revision 2. O O 1.99-10 _}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20247F580&oldid=3897423"