Rev 1 to 'Evaluation of Diablo Canyon Power Plant Reactor

, Report Issued:Revision 1

Report 420-85.687

PACIFIC GAS AND ELECTRIC COMPANY

DEPARTMENT OF ENGINEERING RESEARCH

EVALUATION OF DIABLO CANYON POWER PLANTREACTOR VESSEL MATERIALS BY THE NRC

PRESSURIZED THERMAL SHOCK SCREENING CRITERIA

Prepared By: Approved By:

M. D. SULLIVAN, Consultant R. D KE , Senior Welding Engineer

W.C. upervising MetallurgicalEngineer

pe %23 Cg., 0500027500gg 860i~7

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„gQQCH'gR

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Revision IReport 420-85.687

SUMMARY

The Diablo Canyon reactor pressure vessel beltline materials have been evaluated

according to the Nuclear Regulatory Commission's Pressurized Thermal Shock (PTS)

Rule. Reference Temperature for Pressurized Thermal Shock, RTPTS, has been

calculated for each weld metal and base metal in the beltline region for neutron

fluences from 1017 n/cm2 through 40 effective full power years design life.

RTPTS for all materials is less than the PTS Rule screening limit of 270F for

base metal and longitudinal welds, and 300F for circumferential welds. With the

present design basis out-in-in fuel loading pattern, Unit 1 could operate for 80

effective full power years, and Unit 2 could operate for 128 effective fullpower years before reaching the PTS Rule screening limit. Since all materials

meet the screening criteria, neither a flux reduction program nor additional

analyses are required to comply with the PTS Rule.

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TABLE OF CONTENTS

PAGE

UMMARY ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~S

TABLE OF CONTENTS

LIST OF TABLES ..................................".................. ii).

LIST OF FIGURES ................................................... iv

1 ~.0 INTRODUCTION ................................................. 1

2.0 PTS RULE SCREENING CRITERIA .................................. 3

3.0 EVALUATION OF DCPP MATERIALS ................................. 5

3.1 Weld Metal Compositions ................................. 5

3.2 Weld Metal Initial Reference Temperature, RTNDT ......... 8

3.3 Base Metal Compositions 8

3.4 Base Metal Initial Reference Temperature, RTNDT ........ 9

3.5 End Of Life Fluence 9

3 .6 Prospected RTPTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ 10

4.0 CONCLUSIONS .................................................. 11

5 .0 REFERENCES 13

APPENDIX A: PTS RULE CALCULATIONS FOR DIABLO CANYON UNIT 1

REACTOR VESSEL MATERIALS

APPENDIX B: PTS RULE CALCULATIONS FOR DIABLO CANYON UNIT 2


A-1

B-1

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LIST OF TABLES

PAGE

TABLE 1 Diablo Canyon Reactor Vessel Beltline Region SubmergedArc Weld Materials 14

TABLE 2 Diablo Canyon Unit 1 Submerged Arc Weld Deposit AnalysesFor Reactor Vessel Beltline Region ....................... 15

TABLE 3 Diablo Canyon Unit 2 Submerged Arc Weld Deposit AnalysesFor Reactor Vessel Beltline Region ....................... 16

TABLE 4 Diablo Canyon Unit 1 Reactor Vessel Beltline RegionPlate Materxal ........................................... 17

TABLE 5 Diablo Canyon Unit 2 Reactor Vessel Beltline RegionPlate Material ........................................... 18

TABLE 6 Summary of PTS Rule Evaluation of RPV Beltline Materialsfor Da.ablo Canyon Unit 1 ................................. 19

TABLE 7 Summary of PTS Rule Evaluation of RPV Beltline Materialsfor Diablo Canyon Unit 2 ................................. 20

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LIST OF FIGURES

PAGE

FIGURE 1 RTPTS As A Function of Neutron Fluence For DCPPUnit 1 Reactor Vessel Materials ........................ 21

FIGURE 2 RTPTS As A Function of Neutron Fluence For DCPPUnit 2 Reactor Vessel Materials ........... ............ 22

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1.0 INTRODVCTION

Pressurized Thermal Shock (PTS) is the term used to describe an upset event in a

Pressurized Water Reactor which produces a severe overcooling of the inside

surface of the reactor vessel wall, concurrent with or followed by

repressurization. The steep temperature gradient through the wall creates high

tensile stresses, which when coupled with the tensile stress due to internal

pressure could cause cracks to propagate from preexisting defects.

The ability of the pressure vessel to withstand a PTS event is dependent on the

fracture toughness of the materials, and the location, size, and orientation of

any flaws which may exist in the vessel. For a given material, fracture

toughness generally decreases with decreasing temperature and increasing neutron

fluence. Because of the dependence on fluence, a severe PTS event which occurs

after the vessel has experienced significant irradiation is more likely to cause

unstable crack growth than if the same event occurred early in the vessel life.

The NRC has developed screening criteria[1), herein called the PTS Rule, to

identify reactor vessels which may, at some time in the plant life, have

inadequate toughness to safely withstand a PTS event. The measure of fracture

toughness used in the PTS Rule is Reference Temperature for nil-ductilitytransition, RTNDT. RTNDT is based on the temperature at which the material

exhibits a change from ductile to brittle behavior in the dropweight and Charpy

V-notch tests. A low RTNDT indicates that the transition from ductile to

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brittle behavior occurs at a low temperature and is generally indicative of high

toughness. A high RTNDT indicates that the material can behave in a brittle

manner even at high temperature, and generally indicates low toughness. The

procedure for determining the initial RTNDT is given in ASME Boiler and Pressure

Vessel Code, Section III, Paragraph NB-2331.

The PTS Rule predicts the change in RTNDT as a function of neutron fluence for a

material of a given composition. When the reference temperature is calculated

by the PTS Rule equation, it is called RTPTS to distinguish it from a measured

value of RTNDT. When the predicted RTPTS exceeds the screening limit, neutron

fluence must be reduced so that the screening limit is not exceeded, or

additional analyses must be performed to verify that adequate fracture toughness

exists through the end of life.

The PTS Rule became effective on July 23, 1985 and requires for all operating

Pressurized Water Reactors that projected values of RTPTS from the present time

to the expiration date of the operating license be submitted for all beltline

materials.

In this report the Diablo Canyon Units 1 and 2 reactor vessel materials are

evaluated by the PTS Rule. Values of RTPTS are calculated for each of the

baseline materials through 40 Effective Pull Power Years (EFPY) of operation.

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2.0 PTS RULE SCREENING CRITERIA

The PTS Rule screening criteria consist of two equations which estimate the

adjusted reference temperature, RTPTS, as a function of weight percent copper

and nickel, fast neutron fluence and initial reference temperature, RTNDT.

RTPTS is the lower of the values calculated by both equations.

Equation 1 is as follows:

RTPTS = I + M + [-10 + 470Cu + 350CuNi] f

Where: "I" is the initial reference temperature, RTNDT, of the subject

material measured as defined in ASME Code, Section III, Paragraph

NB-2331. When a measured value for submerged arc weld metal is not

available, a generic value which is a function of submerged arc flux

type must be used. For all DCPP weld metal, the generic value is -56F.

"M" is the margin to be added to account for uncertainties in the

values of initial RTNDT, copper and nickel content, and the

calculational procedure. When the RTNDT is a measured value, M equals

48F. When it is estimated, M equals 59F.

"Cu" and "Ni" are the best estimates of weight percent of copper and

nickel in the material.

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"f" is the best estimate of fast neutron fluence at the clad/base metal

interface, in units of 10 neutrons/cm

Equation 2 is as follows:

RTPTS = I + M + 283 f

Equation 2 is the upper bound of the Regulatory Guide 1.99, Rev 1[2] curve and

is independent of material chemistry. For all materials in the DCPP reactor

vessels, Equation 1 gave the lower RTPTS, so all values reported here are

calculated by Equation I/1.

The PTS Rule requires that RTPTS be calculated for each plate, forging and weld

in the beltline region. The beltline region is defined as the part of the

vessel that directly surrounds the effective height of the active core, and

other adjacent regions that experience significant fluence. At DCPP, the

beltline region includes only the intermediate, and lower shell courses and the

lower portion of the upper shell course. The remainder of the vessel does not

experience sufficient fluence to be considered in evaluating the most limiting

materials.

The PTS Rule establishes an upper limit on RTPTS of 270F fox. base material and

longitudinal welds and 300F for circumferential welds. When RTPTS for a

material is less than the screening criteria, the material is considered to have

adequate toughness to prevent brittle fracture during a pressurized thermal

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shock event. When a material exceeds the screening criteria, additional action

by the owner is required to ensure that the material has adequate fracture

toughness during the period of the operating license.

3.0 EVALUATION OF DCPP MATERIALS

The material properties used in this evaluation were obtained from PGSE report

"Properties of Reactor Vessel Material For Diablo Canyon Units 1 and 2" [3].

This report is the result of an extensive search of fabrication records from

Combustion Engineering, Westinghouse, and the surveillance program reports of

other utilities. Data tables from the above referenced report are also included

in this report for convenience.

3.1 Weld Metal Compositions

Table 1 identifies the submerged arc wi.re heat number, flux type and lot number

for all beltline welds. This information was obtained from Combustion

Engineering records.

Both submerged arc {SAW) and shielded metal arc (SMAW) processes were used to

fabricate the vessel, but the submerged arc process was used predominantly. SMAW

was normally used for rewelding the root pass after backgouging and for repairs.

A review of the SMAW deposit compositions shows that copper content for allwelds was <.04 wt%, and nickel content was approximately 0.5 wtZ. These low

copper and nickel weldments suffer an insignificant shift in RTNDT during

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the plant lifetime relative to the submerged arc welds. For a weld of the above

composition, an RTNDT shift of only 21F is predicted by the PTS Rule. Because

of the small RTNDT shift, SHAW welds are not of concern, and are not further

discussed in this report.

Host of the submerged arc weld deposit chemistry data were obtained from

Combustion Engineering records. In most cases, CE performed chemical analyses

on either a test weldment used to qualify the combination of submerged arc wire

and flux, or on a production weldment. Analyses results were reported in the

Metallurgy and Materials Laboratory (MML) Log Book. Other analyses were

obtained from DCPP surveillance capsule weldments and surveillance capsule

weldments of other utilities.

Tables 2 and 3 list all available chemical analyses for the weld metal in the

beltline region weld seams for Unit 1 and Unit 2 respectively. Except where

noted, the analyses are of deposited weld metal made with a copper coated weld

wire of the noted heats and flux lots. In most instances the tested weld

deposits were made with the same type of flux and in some instances, with the

same lot of flux as the Diablo Canyon welds.

Tables 6 and 7 are the best estimates of the mechanical and chemical properties

used to predict radiation-induced RTNDT shift by the PTS Rule. To arrive at

these estimates for weld metal chemical composition, the data in Tables 2 and 3

were evaluated using the following criteria to determine the compositions most

representative of the vessel welds.

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Weld metal analysis obtained from a DCPP reactor vessel weld seam was judged to

be the most representative and was used in preference to all other data. Ifmore than one vessel weld analysis was available, a mean value was used.

Analyses obtained from the DCPP surveillance capsule weldments were judged to be

the next most representative and were used in preference to all data except

vessel weldment analysis. Surveillance capsule welds were made at the same time

and with the same welding procedure specification and base plates as the reactor

vessel weldments and were judged to be representative of the vessel welds made

with that wire heat. When both vessel and surveillance capsule data were

available, a mean value was used.

In the absence of the above data sources, a mean value of all available groove

weld data for that wire heat was used. The mean values are not considered as

representative as the vessel weld or surveillance capsule weld data because of

the unknowns about the welds from which the analyses were made.

The intermediate and lower shell longitudinal welds in Unit 1 were made with

Heat 27204 and Linde 1092 flux, the same as used in the Unit 1 surveillance

capsule weldment. For these welds, the composition reported in WCAP 8465,

"Diablo Canyon Unit 1 Reactor Vessel Radiation Surveillance Program [4] was

used.

The composition of the Unit 1 upper shell longitudinal weld made with Heats

12008/27204 was obtained from the Mihama Unit 1 surveillance capsule report[5].

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For the tandem heats of 21935/12008 in Unit 2, chemical analyses were available

both from the surveillance capsule weldment and from three coupons taken from an

intermediate shell longitudinal weld. These four data points were averaged.

The copper and nickel values for Heats 13253, 10120 and 21935 are averages

of all available deposited weld metal data given in Tables 2 and 3.

3.2 Weld Metal Initial Reference Temperature (RTNDT)

Dropweight and Charpy tests were not routinely performed for reactor vessel weld

metal in the period when the DCPP vessels were fabricated. In more recent

vessels, these tests were required by the ASME Code. For DCPP vessels, only the

weld metal in one test weldment per vessel was tested in this way. Combustion

Engineering performed dropweight and Charpy tests on weldments made from Heats

27204/12008 for Unit 1, and Heats 21935/12008 for Unit 2. When weld metal

dropweight tests were not performed, initial RTNDT had to be estimated in

accordance with the PTS Rule. All of the DCPP weldments were made with either

Linde 1092, 0091, or 124 flux. For these materials, the estimated RTNDT is

-56F. RTNDT for'these materials is given in Tables 6 and 7.

3.3 Base Metal Compositions

The reactor vessel shell plates for both units were supplied by Lukens Steel to

ASTM A 533 Grade B, Class 1, with additional requirements of ASME Code, Section

III, Code Case 1339-2. The compositions of the shell plates were determined

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from Lukens Steel or Combustion Engineering material test reports. The elements

required by the ASTM material specification were reported, but in most cases

copper was not because it was not controlled by specification. Copper contents

were obtained from the ladle analysis by Lukens Steel Company as reported to

Westinghouse[6]. Chemical compositions of the upper, intermediate, and lower

shell plates are given in Table 4 for Unit 1 and Table 5 for Unit 2.

3.4 Base Metal Initial Reference Temperature (RTNDT)

At the time the DCPP reactor vessels were constructed, ASME Code did not require

both dropweight and transverse Charpy testing of base plate. Therefore RTNDT

values were not readily available, but had to be pieced together from data from

Combustion Engineering and Westinghouse. Combustion Engineering provided

~ dropweight test results for all the .shell plates and Westinghouse performed

transverse Charpy tests for the intermediate and lower shell plates. When

transverse Charpy data were not available, an estimate was made from the

Combustion Engineering longitudinal Charpy data according to the method given in

NUREG 0800, NRC Standard Review Plan, Section 5.3.2 [7]. Tables 6 and 7 show

RTNDT values of the shell plates for Units 1 and 2 respectively.

3.5 End Of Life Fluence

Maximum end of life (EOL) fluences at various locations in the beltline region

were obtained from Westinghouse[8,9] and are the most recent estimates of

fluence at the end of 40 EFPY at stretch capacity of 3565 MWt for the design

basis out-in-in core loading pattern.

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The maximum fluence at any location in each vessel is 2.9 x 10 n/cm and19 2

occurs at the lower and intermediate shell plates, the lower to intermediate

shell circumferential weld, and some of the longitudinal welds in the lower

shell. Both units have approximately the same fluence at the same locations

relative to the core. The difference in fluence between longitudinal weld

locations in a shell course is due to the distance of the welds from the corners

" of the core. Welds which are closer to the fuel at the corners of the core will

experience higher fluence.

3.6 Projected RTPTS

RTPTS was calculated by Equation 1 of the PTS Rule for each plate and weld in

the upper, intermediate and lower shell courses for a fluence range of 10»

n/cm2 through end of life at 40 EFPY. Tables 6 and 7 list the material

properties, EOL fluence and EOL RTPTS for all materials in the beltline region.

None of the beltline materials in either unit exceeds the PTS screening limit

during the 40 EFPY design life of the plants. In Unit 1, the maximum RTPTS of

217F occurred in one of the lower shell longitudinal welds, 3-442C, made with

submerged arc wire Heat 27204. In Unit 2 the limiting material is one of the

intermediate shell plates, B5454-2. Figures 1 and 2 plot RTPTS versus fluence

from 1017 n/cm2 through end of life at 40 EFPY for Units 1 and 2 respectively.

The difference, in percent, between the fluence needed to reach the RTPTS

temperature limits and the fluence reached at end of the 40 EFPY design life is

defined as the margin to the PTS screening limit, and is useful as a measure of

life remaining after 40 EFPY. Margin is calculated as follows:

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Margin, % = Fluence 8 PTS Screenin Limit - Fluence 8 EOL X 100Fluence 9 PTS Screening Limit

Considerable margin exists for all materials in both Unit I and Unit 2. For

Unit 1 the margin for most materials is greater than 90%. The exceptions are

the lower and intermediate shell longitudinal welds, which have a 56% and 69%

margin respectively. For the limiting lower shell longitudinal weld, the EOL

fluence could increase from the current 2.9 x 10 n/cm to 6.55 x 10 n/cm

before the screening limit is reached. This is equivalent to more than 80 EFPY

of operation.

For Unit 2 the margin for most materials is also greater than 90%. The limiting

intermediate shell plates have a margin of 69% which is equivalent to 128 EFPY

of operation before the screening limit is reached.

4.0 CONCLUSXONS

The PTS Rule evaluations of the reactor vessel beltline materials for both

Diablo Canyon Units show that the projected RTPTS at the end of 40 EFPY for allbase metal and weld metal is less than 270F and therefore meets the NRC PTS Rule

screening criteria. For Unit I, a margin of at least 90% exists for allmaterial except two longitudinal welds in the intermediate and lower shells. The

margins for these welds are 69% and 56% respectively. With the present design

basis'ut-in-in fuel loading pattern, Unit I could operate for 80 EFPY before

reaching the PTS Rule screening limit for the most limiting weld.

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For Unit 2, the margins are greater. The limiting materials are two

intermediate shell plates for which the margin is 69K. Unit 2 could operate

128 EEPY before reaching the PTS screening limit for the most limiting material.

Since all materials meet the PTS Rule screening criteria, neither a flux

reduction program nor further analyses are required.

i

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6.0 REFERENCES

h

l. "Analysis of Potential Pressurized Thermal Shock Events", NuclearRegulatory Commission, 10CFR Part 50, Final Rule, Federal Register, Vol 50,No 141, July 23, 1985, pp. 29937-29945.

2. Regulatory Guide 1.99 Revision 1,- "Effects of Residual Elements onPredicted Radiation Damage To Reactor Vessel Materials", April 1977.

3. Sullivan, M.D., "Properties of Reactor Pressure Vessel Materials For DiabloCanyon Units 1 and 2. PGandE Report. 420-85.427, August 1985.

4. Davidson, J. A., et al., "Pacific Gas and Electric Company Diablo Canyon

Unit 1 Reactor Vessel Radiation Surveillance Program", WCAP 8465, January1975.

5. Mihama Unit 1 Surveillance Test Report, Kobe Technical Institute, September1973.

6. Letter, J. A. Soltesz, Lukens Steel Co., to S.E. Yanichko, WestinghouseElectric Co., December 1973.

7. NUREG 0800, USNRC Standard Review Plan, Section 5.3.2 "Pressure-TemperatureLimits", Branch Technical Position MTEB 5-2, "Fracture ToughnessRequirements", Revision 1, July 1981.

~

~

~ ~

~

8. "Diablo Canyon Unit 1 Flux Reduction Program For Reactor Vessel Integrity",WCAP 10878, November 1985.

9. "Diablo Canyon Unit 2 Flux Reduction Program For Reactor Vessel Integrity",WCAP 10780, November 1985.

0485a/dk3

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Report 420-85.687

TABLE 1

DIABLO CANYON REACTOR VESSELBELTLINE REGION SUBMERGED ARC WELD MATERIALS

Weld LocationSubmerged Arc

Wire Heat/T e Plux T e Plux Lot

UNIT 1

Upper Shell Long. Welds1-442 A,B,C

Upper Shell to Inter.Shell, 8-442

Inter. Shell Long. Welds2-442 A,B,C

Inter. Shell to Loweri Shell, 9-442

Lower Shell Long. Welds3-442 A,B,C

27204/12008B4 Modified

13253B4 Modified

27204B4 Modified

21935B4 Modified

27204B4 Modified

Linde 1092

Linde 1092

Linde 1092

Linde 1092

Linde 1092

3714

3774

3724

3869

3774

UNIT 2

Upper Shell Long. Welds1-201 A,B,C


Inter. Shell Long. Welds2-201 A,B,C

Inter. Shell to LowerShell, 9-201

Lower Shell Long. Welds3-201 A,B,C


21935B4 Modified


10120B4

33A277B4

Linde 1092

Linde 1092

Linde 1092

Linde 0091

Linde 124

3869

3889

3869

3458

3878

0485a.l/dk2

TABLE 2

DIABLO CANYON UNIT 1

SUBMERGED ARC WELD DEPOSIT ANALYSESFOR REACTOR VESSEL BELTLINE REGION

Chemical Composition, Wt 7Data

Wire Heat No. Flux e/Lot No. Source 6 C Mn S Si Cr Mo P Ni Cu

27204

12008

27204/12008

272042720427204272042720427204272042720427204

Bare Wire Only(2)

Bare Wire Only(2)

Linde 1092/3724

Linde 1092/3774Linde 1092/3774Linde 1092/3774Linde 1092/3774Linde 1092/3724Linde 1092/3791Linde 1092/ 2

Linde 124/ Z

Linde 1092/3714

(7)

(7)

D5207D5395D5401D5414D5212D5805D6491(8)D6492(8)

(3)

.21

.13

.18

.17

.05

.075

.16

.16

.14

1.81

1.92

1.16

1.091.221.081.021.001.11

1.36

.010

.015

.007

.011

.010

.009

.010

.010

.009

.08

.08

.21

.28

.27

.14

.12

.23

.15

.025. .45

.07

.07

.07

.05

.05

.05

.05

.08

.04

.06

.54

.54

.46

.51

.51

.53

.50

.52

.54

.48

.010

.013

.013

.016

.011

.013

.013

.012

.016

.99 .13

.97 .19

.82 .321.00 .241.10 .22.96 .18.99 .271.00 .19

.32

.31.98 .21

.014 1.07 .12

132531325313253

Bare Wire Only(2)Linde 1092/3791Linde 1092/3833&

3774

(7)(4)(5)

.15

.26

.10

1.831.331.27

.015

.014

.011

.06

.18

.29

.04

.022

.015

.45

.44

.45

.013

.023

.017

.72 .07

.74 .27

.71 .23

21935219352193521935

Bare Wire Only(2)Linde 1092/3869Linde 1092/3889Linde 1092/3889

R2495D7279D7569D7524

.20

.17

.11

.13

2.00

1.371.38

.008 .05 --- .54 .012

.010 .016

.010 .16 --- .53 .014

.011 .14 --- .55 .016

.71

.68

.13

.20

.13

.21

X7 mCD CD00

M

O

1. Mihama, Unit 1 Surveillance Test Report, Kobe Technical Institute, September 1973.2. Copper plating not included.3. Diablo Canyon Unit 1 Reactor Vessel Surveillance Program, WCAP-8465, January 1975.4. Donald C. Cook Unit 1 Reactor Vessel Surveillance Program, WCAP-8047, March 1973.5. Salem Unit 2 Reactor Vessel Radiation Surveillance Program, WCAP-8824, January 1977.6. Combustion Engineering Metallurgy And Materials Laboratory: RXXXX - Bare wire Analysis; DXXXX - Weld Deposit Analysis.7. Supplier CMTR.8. Built-up Weld Pad.

POO wI

coOl(Xlco

~ c

TABLE 3

DIABLO CANYON UNIT 2SUBMERGED ARC WELD DEPOSIT ANALYSESFOR REACTOR VESSEL BELTLINE REGION

Wire Heat No. Flux T e/Lot No.Data

Source 2

Chemical Composition, Wt 7

C Mn S Si Cr Mo P Ni Cu

21935

12008

21935/1200821935/1200821935/1200821935/12008

219352193521935

101201012010120

Bare Wire Only(1)

Bare Wire Only(l)

Linde 1092/3869Linde 1092/3869Linde 1092/3869Linde 1092/3869

Linde 1092/3889Linde 1092/3889Linde 1092/3869

Bare Wire Only(1)Linde 0091/3458Linde 0091/3999

R2495

(5)

(6)2-201B(4)2-201B(4)2-201B(4)

D7524D7569D7279

R2832D11335D10505

.20

.13

.13

.12

.15

.13

.11

.17

.14

.15

.13

2.00

1.92

1.321.451.471.40

1.381.37

1.961.151.09

.008

.015

.010

.011

.010

.011

.011

.010

.010

.011

.007

.009

.05

.05

.22

.14

.13

.15

.14

.16

.08

.16

.20

.06

.03

.04

.03

.03

.09

.54 .012

.51 .010

.47 .017

.57 .019

.58 .018

.57 .019

.55 .016

.53 .014.016

.51 .008

.47 .011

.49 .011

.71

.99

.83

.90

.76

.90

.68

.03

.03

.13

.13

.22

.23

.21

.22

.21

.13

.20

.04

.04

.04

33A27733A27733A27733A27733A27733A27733A27733A27733A27733A27733A27733A277

Bare Wire Only(1)Linde 124/3878Linde 124/3932Linde 0091/3922Linde 0091/3922Linde 0091/3977Linde 1092/3869Linde1092/3889Linde 80/8651Linde 80/8692Linde 0091/3922Linde 0091/3922

R2533D7565D11326D7947

. D7948D9217D7417D7514D7416D8583

(7)(3)

.16

.073

.12

.14

.12

.16

.14

.11

.065

.066

.13

1.941.291.221.121.021.09

1.27

1.421.061.05

.012

.011

.011

.009

.009

.012

.011

.010

.012

.010

.009

.013

.05

.33

.36

.18

.21

.18

.14

.46

.27

.20636

.0

.0

.55 .010

.52 .016

.43 .013

.51 .013

.50 .013

.49 .017.015

.49 . .015.015

.53 .015

.50 .016

.55 .014.19.18

.12

.32

.18

.30

.23

.23

.32

.27

.32

.27

.14

.24

1. Copper plating not included2. Combustion Engineering Metallurgy and Materials Laboratory: RXXXX - Bare Wire Analysis; DXXXX - Weld Deposit Analysis.3. Calvert Cliffs Unit 1 Surveillance Report, Battelle Columbus Laboratories, 12/15/80,4. CE Report, Core Samples from DCPP Unit 2 Vessel Weld 2-201B, Job No. D51186, 4/30/73.5. Supplier CMTR6. Diablo Canyon Unit 2 Reactor Vessel Surveillance Program, WCAP-8783, December 1976.7. Joseph M. Parley Unit 1 Reactor Vessel Surveillance Program, WCAP-8810, December 1976.

m x7fD

U0th

0

O~I

coOlChoo

TABLE 4

DIABLO CANYON UNIT 1 REACTOR VESSEL BELTLINE REGION PLATE MATERIAL+

Component/Piece No.

Upper Shell

PlateCode Heat No. Mn

COMPOSITION (Wt.P S Si Ni Mo Cu

454-01A454-01B454-01C

Intermediate Shell

B4105-1B4105-2B4105-3

C2624-1C2624-2C2608-2B

.21

.20

.21

1.30 .010 .0131.25 .008 .0151.31 .010 .017

.25 .56 .47 .12

.26 .57 .48 .12

.22 .56 .45 .14

454-02A454-02B454-02C

Lower Shell

B4106-3B4106-2B4106-1

C2793-1C2854-2C2884-1

.20

.18

.25

1.33 .011 .0121.32 .013 .0151.34 .013 .015

.25 .46 .46 .10

.23 .50 .46 .13

.21 .53 .45 .14

454-03A454-03B454-03C

B4107-2B4107-3B4107-1

C3131-2C3131-1C3121-1

.24

.19

.25

1.32 .010 .0131.38 .010 .0131.36 .011 .014

.23 .56 .46 .12

.26 .56 .46 .12

.24 .56 .48 .13

ASTM A533, Grade B, Class 1, with additional requirements ASME Section III, Code Case1339-2.

Al (D

0Vl

0

O~I

00OlCXl(XI

TABLE 5

DIABLO CANYON UNIT 2 REACTOR VESSEL BELTLINE REGION PLATE MATERIAL<

Component/Piece No

PlateCode Heat No. Mn

COMPOSITION (Wt. X)P S Si Ni Mo Cu

Upper Shell

213-01A213-01B213-01C

B5453-3B5011-1RB5453-1

C5162-2C4377-1C5162-1

.22

.20

.22

1.46 .012 .015 .24 .60 .581.39 .015 .015 .24 .65 .521.41 .014 .015 .21 .60 .58

.11

.11

.11

Intermediate Shell

213-02A213-02B213-02C

Lower Shell

213-03A213-03B213-03C

B5454-1B5454-2B5454-3

B5455-3B5455-2B5455-1

C5161-1C5168-2C5161-2

C5176-1C5175-2C5175-1

.21

.25

.23

.23

.22

.21

1.30 .010 .015 .19 .62 .461.38 .012 .016 .21 .59 .551.32 .013 .015 .20 .62 .45

1.34 .010 .014 .20 .62 .561.40 .011 .018 .19 .56 .561.38 .010 .018 .19 .56 .56

.15

.14

.15

.10

.14

.14

ASTM A533 Grade B, Class 1, with additional requirements of ASME Section III, Code Case1339-2.

TABLE 6

SUMMARY OF PTS RULE EVALUATION OF RPV BELTLINE MATERIALSFOR DIABLO CANYON UNIT 1

Vessel MaterialWeld Wire Heat/Flux Lot XCu

InitialXNi RTNDT,F M(B),F

EOL(»— Fluence

N/cm2 RTPTS F

Margin toPTS RuleLimit (E)

Upper Shell Long. Welds 27204/12008 .191-442 A,B,C Linde 1092/3714

.97 -20 48 5.1 x 1017 92 997


13253 .25Linde 1092/3774

.73 -56(a) 59 6.0 x 1017 83 99X

Inter. Shell Long. Welds 272042-442 A,B,C Linde 1092/3724

.21 .98 -56(a) 59 2.0 x 1019 197 69X

Inter. Shell to LowerShell, 9-442

21935 .18 .68 -56(a) 59Linde 1092/3869

2.9 x 1019 160 917.

Lower Shell Long. Welds 272043-442 A,B,C Linde 1092/3774

.21 .98 -56( ) 59 2.9 x 1019 217 567

Upper Shell PlateB4105-1B4105-2B4105-3

.12 .56

.12 .57

.14 .56

28(D) 599(D) 59

14(D) 59

6.0 x 1017 120101112

99X99X99X

Intermediate Shell PlateB4106-1B4106-2B4106-3

.14 .53

.13 .50

.10 .46

-10 48- 3 4830(D) 59

2.9 x 10»143160

Lower Spell PlateB4107-1(C)B4107-2B4107-3

.13 .56 15

. 12 .56 20

.12 .56 -22

484848

2.9 x 1019 165161119

A. Generic value from PTS Rule.B. From PTS Rule.C. Limiting base material by PTS Rule equation.D. Estimated per NUREG 0800E. Percent of fluence to'TS screening limit remaining at end of design life (40EFPY)

Margin = (Fluence at PTS Rule screenin limit) - Fluence at end of desi n life X 100Fluence at PTS Rule screening limit

F. WCAP 10878, "Diablo Canyon Unit 1 Flux Reduction for Reactor Vessel Integrity", November, 1985.

94X95X97X

93794X97X

m x70) I0

O

O~1

00VlChco

TABLE 7

Vessel MaterialWeld Wire Heat/Flux Lot XCu 7Ni

InitialRTNDT,F

SUMMARY OF PTS RULE EVALUATION OF RPV BELTLINE MATERIALSFOR DIABLO CANYON UNIT 2

EOL(F)Fluence

M(B),F N/cm2

Margin ToPTS Ru]e

RTPTS,F Limit <

CoI

I

21935Linde 1092/3889

Upper Shell Long. Welds 21935/120081-201 A,B,C Linde 1092/3869


.22 .85 -50 48

.18 .68 -56(a) 59

6.0 x 1017

6.0 x 1017

72

58

99X

99X

Inter. Shell Long. Welds 21935/120082-201 A,B,C Linde 1092/3869

.22 .85 "50 48 1.8 x 1019 184 757.

Inter. Shell to Lower 10120Shell, 9-201 Linde 0091/3458

.04 .03 -56(a) 59 2.9 x 1019 15 99X

Lower Shell Long. Welds 33A2773-201 A,B,C Linde 124/3878

.26 .19 -56(a) 59 1.8 x 1019 155 887

Upper Shell PlatesB5453-1B5453-3B5011-1R

.11 .60

.11 .60

.11 .65

28 485(D) 590( ) 59

6.0 x 1017 1069490

99799X997

Intermediate Shell PlatesB5454-1B5454-2(C)B5454-3

Lower Shell PlateB5455-1B5455-2B5455-3

.15 .62 52

.14 .59 67

.15 .62 33

.14 .56 "15

.14 .56 0

.10 .62 15

484848

484848

2.9 x 1019 224228205

2.9 x 10»159141

69X69X79X

94792X977

A. Generic value from PTS Rule.B. Margins (M) from PTS rule evaluation.C. Limiting base material by PTS Rule equation.D. Estimated per NUREG 0800.E. Percent of fluence to PTS screening limit remaining at end of design life (40 EFPY)

Margin =(Fluence at PTS Rule screenin limit - Fluence at end of desi n life X 100Fluence at PTS Rule screening limit

F. WCAP 10780 "Diablo Canyon Unit 2 Flux Reduction for Reactor Vessel Integrity", November, 1985.

300

250~ -RT AT 40 EFPY

PTS

intermediate and LowerShell Long WeldsHeat 27204(217F)

200B4107-1

Lower SliellPlate (165F)

NtLI

150

a(0

I- 100

B4105-1UpperShell Plate(120F)

B4106-3IntermediateShell Plate(160F)

50

Upper ShellLongitudinal WeldsHeats 27204/12008

Upper to Intermediate (92F)

Shell Circ WeldHeat 13253 (83F)

Intermediate toShell Circ Weld LowerHeat 21935(160 F)

1710

18 19

FLUENCE, N/CM

Figure 1. RTPTS As A Function of Neutron Fluence For DCPP Unit" 1 ReactorVessel Materials

2010

250 ~ -- RTpTs At 40 EFPYB5 454-2Intermediate Shell Plate(228F)

200MILLLlKG

n 150

I-~ 0.

K

100

B5453-1Upper Shell Plate(106F)

Upper and IntermediateShell Long WeldsHeat 21935/12008(184F)

B5455-2Lower Shell Plate(159F)

Lower ShellLong WeldsHeat 33A277(155F)

50Upper to IntermediateShell Circ WeldHeat 21935(58F)

Intermediate to LowerShell Circ WeldHeat 10120(15F)

17 019

FLUENCE, N/CM

Figure 2. RTpTs As A Function of Neutron Fluence For DCPP Unit 2 Reactor Vessel

Materials

10 10

APPENDIX A

PTS RULE CALCULATIONS FOR DIABLO CANYON UNIT 1


A-1

485a.8/dk4

0

APPENDIX A

~RT TS FOR DCPP UNIT 1 RPV MATERIALS

HEAT 8

NICKEL COPPER INITIALWT X WT X RTNDT M(1)

FLUENCE,NEUTRONS/CM

X 10» RTPTS, F

27204 .98

Intermediateand Lower ShellLongitudinal Welds

.21 -56F 59F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.006.55(2)7.008.009.00

10.00

49596570757881848789

107119129136143149154159164197217219237251264270275285294302

(1) Margin used in PTS Rule Equation.2) Fluence at PTS Rule Limit.

A-2

485a.8/dk4

APPENDIX A

~RT TS FOR DCPP UNIT 1 RPV MATERIALS (cont'd)

HEAT //NICKEL COPPER INITIALWT Z WT X RTNDT M(1)

FLUENCE,NEUTRONS/CM2

X 10» RTPTS, F

21935 .68

Intermediate toLower ShellCircumferential Meld

.18 -56F 59F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.007.008.009.00

10.0031.07(2)

37444952555860626466798895

100105110114117120145160161174184194202209216222270


A-3

485a.8/dk4

APPENDIX A

RT TS FOR DCPP UNIT 1 RPV MATERIALS cont'd

HEAT 8

NICKEL COPPER INITIALWT Z WT 7o RTNDT


X 10» RTPTS, F

13253 .73

Upper toIntermediate ShellCircumferential Weld

.25 -56F 59F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.007.007.66(2)8.009.00

10.00

52636975798387909295

114127137145152159164170174210231234252268281293300303313322


A-4

485a.8/dk4

HEAT /I

NICKEL COPPER INITIALWT % WT R RTNDT


X 10»

APPENDIX A

~RT TS FOR DCPP UNIT 1 RPV MATERIALS cont'd

RTPTS, F

27204/12008 .97

Upper ShellLongitudinal Weld

.19 -20F 48F .01.02.03.04.05.06.07.08.09.10.20.30

'.40.50.60.70.80.90

1.002.002.903.004.005.006.006.87(2)7.008.009.00

10.00

69788488929598

101103105121132140147153159163168172201220221237250261270271280288296


A-5

485a.8/dk4

APPENDIX A


HEAT /lNICKEL COPPER INITIALWT R WT Z RTNDT M(1)

FLUENCE,NEUTRONS/CM

X 10» RTPTS, F

B4105-1

Upper ShellPlate

.56 .12 28F 59F .Ol.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.007.008.009.00

10.0035.28(2)

107111114116118120121122123125132138142145148151153155157171180181189195200205210214217270


A-6

485a.8/dk4

0

APPENDIX A

RTPTS FOR DCPP UNIT 1 RPV MATERIALS cont'd)

HEAT //

NICKEL COPPER INITIALWT % WT R RTNDT


X 1019 RTPTS, F

B4105-2

Upper ShellPlate

.57 .12 59F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.007.008.009.00

10.0049.76(2)

8892959799

101102104105106114119123126129132134136138153162163170177182187191195199270

1) Margin used in PTS Rule Equation.2) Fluence at PTS Rule Limit.

A-7

485a.8/dk4

APPENDIX A

RTPTS FOR DCPP UNIT 1 RPV MATERIALS cont'd

HEAT 8

NICKEL COPPER INITIALWT % WT % RTNDT


X 1019 RTPTS, F

B4105-3

Upper ShellPlate

.56 .14 14F 59F .Ol.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.007.008.009.00

10.0024.30(2)

97102105108110112114115116118127133138142146149151154156173184185194202208214219224228270


A-8

485a.8/dk4

APPENDIX A


HEAT /I

NICKEL COPPER INITIALWT R WT Fo RTNDT M(1)

FLUENCE,NEUTRONS/CM

X 10» RTPTS, F

B4106-1

IntermediateShell Plate

.53 .14 -10F 48F .01.02~ 03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.007.008.009.00

10.0047.58(2)

626670727476787981829197

102106109112115117120137147148157164171176181186190270


A-9

485a.8/dk4

APPENDIX A


HEAT /I

NICKEL COPPER INITIALWT Z WT % RTNDT M(1)


X 10» RTPTS, F

B4106-2


.50 .13 -3F 48F .Ol.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.007.008.009.00

10.0061.94(2)

667174767880818284859398

103106109112115117119134143144152159165170174179183270


A-10

485a.8/dk4

(

APPENDIX A


HEAT f/

NICKEL COPPER INITIALWT X WT Z RTNDT M(1)


X 10» RTPTS, F

B4106-3


.46 30F 59F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.007.008.009.00

10.0093.87(2)

104107110111113114115116117118123127130133135137139141142153160160166171175179182185188270


A-11

485a.8/dk4

APPENDIX A


HEAT /I

NICKEL COPPER INITIALWT X WT R RTNDT M(1)

FLUENCE,NEUTRONS/CM

X 10» RTPTS, F

B4107-1

Lower ShellPlate

.56 .13 15F 48F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.007.008.009.00

10.0039.76(2)

859093959799

100102103104113118123127130133135137140155165166174181187193197202206270

1) Margin used in PTS Rule Equation.) Fluence at PTS Rule Limit.

A-12

485a.8/dk4

APPENDIX A


HEAT N

NICKEL COPPER INITIALWT Z WT R RTNDT M(1)


X 10» RTPTS, F

B4107-2

Lower ShellPlate

.56 .12 20F 48F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.007.008.009. 00

10.0050.87(2)

8892959799

101102103104106113119123126129'32134136138152161162170176181186191195198270

( 1) Margin used in PTS Rule Equation.2) Fluence at PTS Rule Limit.

A-13

485a.8/dk4

APPENDIX A

~RT TS FOR DCPP UNIT 1 RPV MATERIALS (cont'd

HEAT //NICKEL COPPER INITIALWT Z WT % RTNDT M(1)


X 10» RTPTS, F

B4'107-3

Lower ShellPlate

.56 .12 -22F 48F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.90

1.002.002.903.004.005.006.007.008.009.00

10.00102.41(2)

46505355575960616264717781848790929496

110119120128134139144149153156270


A-14

485a.8/dk4

APPENDIX B

PTS RULE CALCULATIONS FOR DIABLO CANYON UNIT 2


B-1

0485a.9/dk5

APPENDIX B

~RT TS FOR DCPP UNIT 2 RPV MATERIALS

HEAT //NICKEL COPPER INITIALWT. X WT. X 'RTNDT M )


X 10» RTPTS

21935/12008 .85

Upper andIntermediate ShellLongitudinal Welds

.22 -50 F 48 F .01,02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901.001.802.002.903.004.005.006.007.007 33(2)8.009.00

10.00

44536065697275788183101113122130136142148152157184190210212229243256267270276285294


B-2

0485a.9/dk5

APPENDIX B


HEAT kl

NICKEL COPPER INITIALWT. % WT. % RTNDT M


X 10» RTPTS,

33A277 .19

Lower ShellLongitudinal Weld

.26 -56 F 59 F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901.001.802.002.903.004.005.006.007.008.009.00

10.0014.59(2)

404853576164666871738797104110116121125129132155159176177191203213222230237244270


B-3

0485a.9/dk5

APPENDIX B

RT TS FOR DCPP UNIT 2 RPV MATERIALS (cont'd

HEAT 8

NICKEL COPPER INITIALWT. R WT. X RTNDT M


X 10» RTPTS F

21935 .68

Upper toIntermediate ShellCircumferential Weld

.18 -56 F 59 F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901.001.802.002.903.004.005.006.007.008.009.00

10.0031.07(2)

37444952555860626466798895100105110114117120141145160161174184194202209216222300


B-4

0485a.9/dk5

APPENDIX B


HEAT /INICKEL COPPER INITIALWT. Z WT. Z RTNDT M


X 1019 RTPTS F

10120 .03

Intermediate toLower ShellCircumferential Weld

.04 '56 F 59 F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901.001.802.002.903.004.005.006.007.008.009.00

10.00)999.00(2)

101011ll111212121414151516171819192020

300


B-5

0485a.9/dk5

APPENDIX B


HEAT //NICKEL COPPER INITIALWT. X WT. g RTNDT M(

FLUENCE,NEUTRONS/CM

X 10» RTPTS,

B5453-1

Upper ShellPlate

.6 28 F 48 F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901.001.802.002.903.004.005.006.007.008.009.00

10.0058.05(2)

9599101103105106108109110111118123127130132135137139141152154162163170176181186190193197270


B-6

0485a.9/dk5

APPENDIX B


HEAT 8NICKEL COPPER INITIALWT. % WT. % RTNDT M~


X '10» RTPTS F

I

B5453-3

Upper„ ShellPlate

.6 59 F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901.001.802.002.903.004.005.006.007.008.009.00

10.00

83878991939496979899106ill11511812012312512712914014215015)158164169174178181185


B-7

0485a.9/dk5

HEAT /INICKEL COPPER INITIALWT. R WT. 7.'TNDT M~

FLUENCE,NEUTRONS/CM

X 10»

APPENDIX B

~RT TS FOR DCPP UNIT 2 RPV MATERIALS cont'd)

RTPT

B5011-1R

Upper ShellPlate

.65 0 F 59 F .Ol.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901.001.802.002.903.004.005.006.007.008.009.00

10.0071.09(2)

78828587899092939495102107111114117120122124126137139148149156162167172176180183270


B-8

0485a.9/dk5

APPENDIX B


HEAT 8

NICKEL COPPER INITIALWT. % WT. Z RTNDT M(

FLUENCE,NEUTRONS/CM

X 1019 RTPTS

B5454-1


.62 .15 52 F 48 F ~ 01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901.001.802.002.903.004.005.006.007.008.009.009.32(2)

10.00

127132136139141144145147149150160167173177181185188190193209212224225235244251257263268270273


B-9

0485a.9/dk5

APPENDIX B

~RT TS FOR DCPP UNIT 2 RPV MATERIALS (cont'd

HEAT /INICKEL COPPER INITIALWT. % WT. R RTNDT M(

FLUENCE,NEUTRONS/CM

X 10» RTPTS,

B5454-2


.59 .14 67 F 48 F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901. 001.802.002.903.004.005.006.007.008.009.009.37(2)

10.00

139144148151153155156158159160170176181185189192195197200214217228229238246252258264268270273


B"10

0485a.9/dk5

HEAT 8

NICKEL COPPER INITIALWT. Z WT. % RTNDT M~


X 10»

APPENDIX B


RTPTS,

B5454-3


.62 .15 33 F 48 F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901.001.802.002.903.004.005.006.007.008.009.00

10.0013.80(2)

108113l)7

„120122125126128130131141148154158162166169171174190193205206216225232238244249254270


B"11

0485a.9/dk5

<o

V L

APPENDIX B


HEAT 8NICKEL COPPER INITIALWT. Z WT. X'TNDT M


X 10» RTPTS,

B5455-1

Lover ShellPlate

.56 .14 -15 F 48 F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901,001.802,002.903.004.005.006.007.008.009.00

10.0048.2(2)

57626568707274757678879398102106109111114l)6131133144145154162168174179184188270

(1) Margin used in PTS Rule Equation.) Fluence at PTS Rule Limit.

B"12

0485a.9/dk5

HEAT //NICKEL COPPER INITIALWT % WT R RTNDT M )

FLUENCE,NEUTRONS/CM

X 1019

APPENDIX B


RTPTS

B5455-2

Lower ShellPlate

.56 .14 0 F 48 F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901.001.802.002.903.004.005.006.007.008.009.00

10.0037.83(2)

72778083858789909193102108113117121124126129131146148159160169177183189194199203270


B-13

0485a.9/dk5

APPENDIX B


HEAT uNICKEL COPPER INITIALWT. % WT. Z RTNDT M


X 1019 RTPTS F

B5455-3

Lower ShellPlate

.62 15 F 48 F .01.02.03.04.05.06.07.08.09.10.20.30.40.50.60.70.80.901.001.802.002.903.004.005.006.007.008.009.00

10.00106.45(2)

80838688899092939495101105109112114116118120122132134141142148154158162166169172270

(1) Margin used in PTS Rule Equation.(2) Fluence at PTS Rule Limit.

B-14

0485a.9/d

Documents

Rev 1 to 'Evaluation of Diablo Canyon Power Plant Reactor