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) Final Construction Deficiency ReportCD-369-370/78-07

McGuire Nuclear Station Units 1 & 2Oc tober 19, 1978

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1.0 INTRODUCTION

1

Pursuant to the requirements of 10CFR50.55(e), this final construction deficiency |report summarizes the resolution of the subject vendor material certification !discrepancies. An interim report was previously transmitted to the United States |

Nuclear Regulatory Commission, Region II, by Mr. W. O. Parker, Jr. 's letterIaddressed to Mr. J. P. O'Reilly, USNRC, dated September 1,1978|

The interim report outlines evaluation of the problem, investigative activitiesrequired to define the problem and corrective action being pursued by Duke Power

]Company to resolve the discrepant material certification data. The final reportis designed to supplement the interim report and complete the investigation,

|evaluation and corrective action necessary to assure that the physical properties '

of the support forgings are compatible with design service requirements.

Duke Power Company has conducted an extensive inplace sampling and laboratorytesting program (described in detail in Section 2.0) on the support forgings.Review of early test results which indicated poor correllation of Charpy V-Notch

_!impact test results with vendor supplied material certifications required es-calation, of what was originally a limited test program, into a comprehensive '

program sufficient to independently certify the physical properties of eachsupport forging. An engineering evaluation of each support forging was thendeveloped, utilizing these physical properties, to establish the adequacy ofthe forging to perform its design service functions.

The results of the comprehensive material testing program indicate that sev-eral of the support forgings exhibit Charpy V-Notch energies below the mini- -

num required by original specification. This fact, in itself, does not in-dicate that a performance deficiency is present. However, such a findingcould be symptomatic of reduced material fracture toughness. The CharpyV-Notch impact test is generally specified by the engineer as a quality con-trol measure to assure that considerable impact toughness is available toaccommodate a design dynamic service condition, at service temperature.Duke's review of the test results concluded that forgings which possessedCharpy V-Notch energies below specification would be evaluated for their -

intended service by establishing the fracture toughness required to preventbrittle fracture and comparing this value with the actual fracture toughnessof the forgings. To assist in this effort, Duke retained the services ofFailure Analysis Associates of Palo Alto, California, an internationallyrecognized engineering and metallurgical consulting firm. Lakeside Bridge andSteel Company, supplier of the support forgings, retained Mr. Helmut Thielsch,of Cranston, Rhode Island, a similarly recognized consulting metallurgicalengineer, to independently evaluate the fracture toughness of the support -

forging materials. The results of this effort, as well as Duke's engineeringevaluation, is summarized in Section 4.0.

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2.0 PHYSICAL TESTING PROGRAM AND RESULTS

The material from which all forgings are manufactured id E-4340-H (Chrominum-Nickel-Molybdenum). The forgings were fabricated in accordance with therequirements of ASME Specification SA-540, Grade B23, Class 4, supplementedwith the requirements of Duke Power Company Specification No. MCS-1117.00-2, _.

original issue dated October 9, 1972. The combination of these twn specifi-cations required forging physical properties as follows:

Minimum Yield Stress = 120,000 psi".

Ultimate Tensile Strength = 135,000 psi ,

Minimum Elongation = 13%

iMinimum Reduction of Area = 45%

Surface Brinell Hardness = 285 min., 363 max.2Charpy V-Notch Impact * = 25** ft-lbs at 50 F

* Supplemental Requirement of Duke Specification MCS-1117.00-2|

** Average of 3-specimens with on one specimen

exhibiting Charpy energies below 20 ft-lbs.

There are 336 steam generator and reactor coolant pump column support forg-ings in Unit 1 and Unit 2 of McGuire Nuclear Station. These forgings con-sist of 112 column clevises, 24 reactor coolant pump upper trunnions, 32steam generator upper trunnions, 56 lower column trunnions and 112 connect-ing pins, as described in the interim report.

The pieces were forged from 10 material heats, heat treated, then finalmachined. Heat treatment was accomplished in 33 heat treatment lots. Allmembers of a heat treat lot came from one material heat. One set of phy-sical tests was required per heat treat lot.

Duke's investigation of the discrepant data present in vendor supplied materialcertifications, as described in the interim report, led to a decision toinitially conduct a limited confirmatory test program of the forging materials.The lower column trunnions were selected for testing because they representthe bulkiest forging pieces with the least forging reduction, in addition -

to being easily accessible to remove samples. The lower trunnions for Units1 and 2 were fabricated in seven (7) heat treat lots. Samples were removedand tested from representatives of each heat treat lot. Two (2).fu11 sizetensile specimens and three (3). standard Charpy V-Notch impact specimenswere tested from each sample. Results of the tests were as follows:

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fiumber ofLower TrunnionSamples Complying

SG Lower RCP Lower With SpecificationMaterial Property Trunnion Range Trunnion Range Out of 7

Y.S.(psi) 101,950 to 131,900 111,750 to 128,800 4

U.T.S. (psi) 129,800 to 159,850 142,200 to 159,850 6

EL (%) 13.0 to 17.5 13.0 to 14.5 7

j.

RA(%) 38.6 to 55.7 40.8 to 4~.0 3<

|BHN 277 to 321 285 to 311 6

C 0 50 F (ft-lbs) 11.6 to 19.3 11.7 to 15 0y

Review of this data resulted in a decision to extend the testing program to in-clude the other forging geometries. The following is a summary table of theextended phase of the testing program and its relationship to the forging i

fabrication process and total population,

fiumber of fiumber of Fabrication Number of HeatForging Type Material Heats Heat Treat Lots Treat Lots Tested

Lower Trunnions 5 7 7 _ _j

Upper RCP Trunnions 1 4 4

| Upper SG Trunnions 3 4 4

Clevises 3 14 8

| Pins 1 4 1.

Results of testing the clevises, upper trunnions and pins were as follows:

RCP Upper SG Upper,

Material Property Trunnions Trunnions Clevises Pins'

Y.S.(psi) 117850-136550 136650-146550 112050-136300 110600

U.T.S.(psi) 144550-160400 154300-162150 139050-160200 139500 -

El (%) 17.0-19.5 17.5-19.0 16.5-18.0 16.0

RA(%) 56.0-64.5 59.9-64.5 52.4-61.5 55.5

BHN 285-331 321-321 - 285-321 285 ,

0 16,7-71.3 31. 3 , -C*@80f(ft-lbs) --- ---y ,

C *@ 110 F (ft-lbs) 38.7-85.7 65.3 ,75.3 19.0-73.0 32.3y

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A limiting condition for operation required by the McGuire Nuclear Station! *

Technical Specifications is that primary Containment average tempgraturein the Containment lower compartment shall be between 100 and 120 F. Charpy

iV-Notch test temperatures of 800f for forgings at the base of a columnand 110 f for forgings adjacent to the components were conservatively0 ,

specified for the test program. Tests at 50 Of were run for use in correl-4

lating test results to vendor supplied material certifications. .7

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a 3.0 CORRELLATION OF TEST RESULTS WITH VENDOR PATERIAL CERTIFICATIONS .,

| A review of the test data and certified data received from Ajax for each partwas conducted to establish the degree of corre11ation. A strong correllation

| exists between the certified and tested data for tensile strength, Brinell ,

FHardness area reduction, and elongation. The tested yield strengths range .

from 16 ksi above to 30 ksi below the certifie ' values. The average variation;

{ was 8 ksi below the certified value. No correi'.ation could be established be-j tween the certified and tested Charpy V-Notch data. >

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3.1 COLUMN CLEVIS ,

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| a) Certified yield strength range from 100.3% to 125.6% of the maximum-

,

-

specified value. Test results range from 93.4% to 113.6% of the,

minimum specified.;

b) Certified tensile strengths range from 101.6% to 124.2% of the minimum - -d

i specified. Test results range from 103% to 118.7% of the minimum; '

specified.,

j c) All certified data for the Charpy V-Notch tests indicates the partsatisfy the average / minimum requirements. Sample test results in- j'

dicate that 25% of the heat treat lots satisfy the specification j;

requirements..

3,2 LOWER TRUNNIONS _-

a) Certified yield strengths range from 104.3% to 110.8% of the minimum j

tspecified. Tests range from 84.9% to 109.9% of the minimum specified. j

j b) Certified tensile strengths range from 111.9% to 118.4% of the maxi- ;i

)mum specified. Test results range from 96.1% to 116.7% of the mini--

mum specified. , i'

c) All certified data from the Charpy V-Notch tests indicate the partssatisfy the average / minimum requirements. Sample test results indicatethat no parts satisfy the specification requirements.

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3.3 UPPER TRUNNIONS ,

a) Certified yield strengths range from 100.6% to 119.7% of the minimum .

specified. Test results range from 98.3% to 122.2% of the minimum,

specified,

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b) Certified tensile strengths range from 104.7% to 120.4% of the min-inum specified. Test results range from 107.1% to 120.1% of the min-imum specified.

c) All certified data and sample test data from the Charpy V-Notch tests,

satisfy the average / minimum requirements. |

3.4 PINS

a) Certified yield strengths range from 104.8% to 118.5% of the minimum*

specified. Test results are 92.2% of minimum specified,

b) Certified tensile strengths range from 107.8% to 117.7% of the minimumspecified. Test results are 103.3% of the minimum specified.

c) All certified data from Charpy V-Notch tests satisfy the average / minimumrequirements. Sample test results for the material satisfy the minimumbut not the average specified requirements, but does satisfy both ofthese requirements at the minimum service temperature level (800F).

3.5 ACCEPTABILITY OF CORRELATION

As stated in Section 2.0, samples from all heat treat lots for the upper RCPand SG trunnions and the lower trunnions were tested. However, for the columnclevises 8 of 14 heat treat lots had samples tested, and for the column pins, . . _ . ~

one of four heat treat lots had samples tested. In order to determine valuesfor the yield and tens'ile strengths for the untested heat treat lots, the ven-dor data to test data correlation was utilized. To verify that this correlationwas valid, Brinell hardness values were obtained from all parts (including alltrunnions, pins, and clevises), in place. A relationship between Brinell hard-ness values and yield and tensile strengths exists and has been documented fortypical 4340 material which possessed similiar mechanical properties andpassed through the Ajax facility from January 1976 to July 1977 (see FiguresA and B). ASME Specification SA-370, Table 3, outlines the same correlationover a much wider range of tensile strengths. The Brinell values indicatedthat the yield and tensile strengths for the tested and untested clevises andpins were in the same range (105,500 to ll3,500-Y.S. ,128,000 to 143,000-T.S.)and confinned the correlation between the test data and the vendor certifiedvalues for the yield and tensile strengths.

As previously stated, no correlation between the vendor certified and testedCharpy V-Notch data was established. The rough correlation between Charpy V- -

Notch values and Brinell hardness values was judged to be too inaccurate touse. Hence,Charpy V-Notch values at a 95% confidence level were establishedfor all untested parts (see Reference 1, Section 6.0).

Based on the above techniques, the following values are assigned to the untestedclevises and pins:

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Clevises' Pins~ ,

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Y.S. (psi) 105,500 to 113,500 110,600 |l

U.T.S. (psi) 128,000 to 143,000 139,500 j'

C 0 80 F(ft-lbs) 17.0 31.00

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C 91100F(ft-lbs) 19.0 32.0y

EL(%) 17.2 to 18.2 16.0

RA (%) 57.3 to 59.0 55.5

4.0 ENGINEERING EVALUATION OF FORGING MATERIALS ,

The reactor coolant pump and steam generator support columns are designed tofunction as pinned - pinned members. The columns have limited freedom of ro-tation to accommodate movement of the supported component during thermalcontraction or expansion of the reactor coolant system. The columns are de- i

signed for axial loadings which result from normal and abnormal operation,postulated pipe repture accidents, and the concurrence of an OBE or SSE.

4.1 COLUMN DESIGN LOADINGS!

There are four (4) identical reactor coolant loops in each unit of McGuireNuclear Station. In each loop there are four (4) steam generator and three ^ --

(3) reactor coolant pump support columns. The loads applied to each of theseseven (7) support columns are different depending upon their location. Theoriginal structural design utilized the maximum column load only and there-fore a single geometry for each forging piece was fabricated, for simplicity.

The maximum column load is 2146 kips for reactor coolant pumpcolumn no. 2 (see Figure C). The following summarizes the maximum columnloads: .,

LOAD

COLUMN (KIPS)

RCP 1 873>

RCP 2 2146

RCP 3 1284 .

SG 1 996 |)

SG 2 2004 ;,

SG 3 822i

SG 4 797 .

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It is apparent from this summary that the six (6) of the seven (7) columnsin each loop were designed with considerable strength margins when comparedwith their actual service loads.

The maximum column loads are a result of the assumption that, during normal a'

operation of the unit, the worst loss-of-Coolant Accident for a particularcolumn occurs simultaneously with the Safe Shutdown Earthquake. Furthermore, .

the peak support column loads occurring for each event are combined by ab- :!solute sunnation, thereby conservatively assuming that the events are phased

such that the peak support loads for each event happen to coincide.

4.2 SERVICE STRESS LEVELS AND ALLOWABLE STRENGTHS _.-

The nominal stress level ranges in each of the forgings, corresponding to ',

their service loads, are as follows. ,

.

NOMINAL STRESS RANGESService Condition j

'

(KSI)

Reactor Coolant Steam

Forging Type Pump Generator |

Lower Trunnions 38.2 - 94.0 34.9 - 44.0. . -

. - -;

Upper Trunnions 33.5 - 82.4 28.5 - 35.9

Pins 15.8 - 38.9 17.9 - 20.5 ;

Clevises 32.5 - 79.8 26.6 - 37.3 1

!

Yield strengths exhibited by the forgings, as discussed in Section 2.0 and ]

3.0 are summarized as follows. ..

i

Yie.ld Strengths 1

f_orging Type (KSI) ji

RCP Lower Trunnions > 111.8 j

> 102.0SG Lower Trunnions

> 117.9-

RCP Upper Trunnions

> 136.7SG Upper Trunnions

> 110.6Pins

> 105.5 -

Clevises

' Comparisons of these. summaries demonstrate that the forgings possess mechanicalproperties which are sufficient to qualify them for their intended service. ,

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In addition, no credit for the dynamic mechanical properties of the forgingshas be.en taken, The stress levels in the forgings comply with the allowablestructural acceptance criteria delineated in Section 5,5.14 of the McGuireNuclear Station final Safety Analysis Report,

4.3 FRACTURE TOUGHNESS

The failure behavior of structures under monotonic loading may be characterized~

by two limiting cases, brittle fracture and fully plastic instability (i.e.limit load). As described in Section 4.2, the yield strengths of the forgings -

are sufficient to ensure a safe margin against fully plastic failure. To en-sure that the forgings exhibited entirely tough and ductile properties andare not subject to brittle fracture failure, a standard value of the absorbedenergy in the Charpy V-Notch impact test was specified. It is recognized that

the actual performance of steel components in a particular application and ofa particular design may be completely unrelated to the actual Charpy V-Notchtoughness behavior of small section cut from one or several heats of steel;however, materials are basically selected and specified on the basis of speci-

( fic rechanical test properties (see Reference 2).

The Charpy V-Notch test results for the column clevises and lower trunnion in-dicated that the parts may exhibit low ductility when subjected to impactiveloads. Subsequent tests of un-notched specimens indicated that the materialdoes indeed exhibit ductile behavior (see Reference 2), and would providetotally acceptable service under all loads defined in Section 4.1. However, -

to fully detennine if the forgings possess sufficient ductility, it was de-cided to analyze the brittle fracture failure mode using the techniques oflinear elastic fracture mechanics (LEFM). As the normal loads and associatedstresses in the forgings are very low (well below the endurance limit) andthe environment in which the forgings exist is non-corrosive, cracking orflaw generation by fatigue or stress corrosion will not occur. Hence, therelevent failure mode is brittle fracture from pre-existing cracks. The anal-ysis methods, which are described in Reference 1, utilize the techniques of .

LEFM to characterize the stress and ductility values for the support forgingsand determine the maximum postulated flaw permissible and its associated geom-etry and critical plane location.

The results of the analysis indicate that the smallest critical crack sizefor a through thickness crack is 0.023 inch by 26 inches long for the RCP-2lower trunnion located in the radius area (see Reference 1, figure 3.4a).The critical crack size for a through thickness crack for the RCP-2 lower ,

trunnion located at the edge of the pin hole is 0.040 inch by 4 inches long.

The critical flaw size for a semi-elliptic flaw was found to be 0.231 x 0'.115 inchesfor the RCP-2 lower trunnion at the edge of the pin hole. However, only 0.5inches'from the pin hole the critical elliptical flaw size increases to 0.37x 0.19 inches, for the buried elliptic flaw. 1

i

The critical flaw size for a semi-elliptic flaw for the RCP-2 lower column ..clevis was found to be 0.342 x 0.171 inches at the edge of the pin hole.

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The critical major axis flaw sizes for buried elliptic flaws (see Reference1, figure 3.4c) were also developed as a function of location from the clevisor lower trunnion pin hole,'and fracture toughness (KIC); conservatively utilizingthe worse case stress gradient.. This character of flaw would be the mostcommonly occurring type. This analysis is used to conservatively establishpennissible flaw sizes in regions remote from the most highly stressed areas.As expected, permissable flaw sizes grow rapidly for locations other than . . ,

innlediately adjacent to the pin holes. The static fracture toughness (KlC) I

(see Reference 1, Section 6.2) was conservatively obtained based on theCharpy V-Notch test data. Subsequent testing of material from the lower,

trunnion indicates that the calculated KIC is only 57.5% of the tested value.This would cause the calculated critical flaw size to be conservatively de-

1fined by a factor of 3.0.

If the forgings contain no flaws with dimensions in excess of those definedby LEFli techniques, the parts will possess sufficient toughness and ductility ;

for their intended service.

5.0 ULTRASONIC EXAMINATION OF FORGINGS

To ascertain the overall quality of the material used in the forged parts withrespect to internal flaws, a detailed ultrasonic examination program was con-ducted. The forged parts examined were those parts for which Charpy V-Notchtest results were less than the original specified values. A review of thetest data indicated that only the lower column trunnions and the column - - - -

clevises would require examination. However, because of the easy accessabilityof these parts in Unit 2, it was decided. that all lower trunnions and columnclevises would be examined initially regardless of the tested Charpy V-Notchdata; while only one sample of each heat lot, for the lower trunnion and columnclevis, would be examined in Unit 1. A detailed examination of all remainingparts in Unit 1, that warrant inspection,is presently underway.

Each trunnion or clevis was thoroughly examined using straight, angle and surface .

beam to determine if flaws existed in the areas of concern. These areas arethose identified as critical areas in Section 4.3. In addition, the remaining

portion of each part was thoroughly examined to the extent possible, based onthe part external geometry. The ultrasonic equipment was calibrated to ac-

2curately define all flaws of 0.010 x 0.5 (.005 inches ) inches or greater.

A review of all the test results obtained to date (100% Unit 2, representativesof heat treat lots Unit 1) for these lower trunnions and column clevises, ,

indicates that- approximately j0% of the parts contain no detectable flaws(i.e. less than 0.0005 inches ). Intheregaining60%,95%ofalldetectedThe largest flaw found was 1.0"flaws are less than or equal to .005 inches .x 0.5". However, this flaw was located over 7 inches from the pin hole edgeand was ' oriented 900 to the critical plane.

The majority of the flaws are oriented such that their major dimension isparallel to the outer surface of the clevis or trunnion (90 from the critical .

plane). The flaws appear' to have no detectable dimension in the thickness _

direction. This would tend to indicate that the flaws were originally gas bub-bles trapped in the steel when the billet was poured and flatten during the

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The flaws appear to be randomly located with only three (3)forging process.flaws located within two inches of the pin hole (. flaws were 0,25 x 0.25, 0,4

;

x 0,4, 0,25 x 0.125 inches). !

The clevis material was found to have only one flaw greater than .005 inchesj.

21

| i(0.125 x 0.25 inches, one of the three flaws defined above) with the majorityThe trunnion material had detectable di

of the clevises having no detectable flaws. 2 1flaws, but generally in the range of .001 to 0.005 inches , 9.'

The forging material is exceptionally clean material possessing only very smallinternal flaws. q

J6.0 COMPARIS0N OF CRITICAL CALCULATED FLAWS AND ACTUAL FLAWS l

As stated in Section 3.3 and 4.2, the upper RCP and SG trunniens and the column,

pins possess mechanical properties sufficient both in strength and ductility |to qualify them for their intended service. Hence, the determination of pre-existing flaws in this forging material is not required as the brittle fracture |

failure mode is impossible. The critical flaw sizes were calculated for in-;

I

formation only in. Reference 1..~

As stated in Reference 1, the techniques of linear elastic fracture mechanics |

when used to determine critical flaw sizes to cause failure give conservativeIn addition, the use of the highest stressed part (for all trunnionsvalues.

or clevises) to define the buried elliptically shaped critical flaw, the use- - -

of the highest normal stress at all locations around the clevis and trunnion '

pin holes and trunnion and clevis radii, and the conservatively calculated KIC'sfor the lower trunnions further add conservatism to the calculated critical i

Hence, if all flaws discovered in the forgings are less than theflaw sizes.calculated critical flaw, brittle fracture from the pre-existing flaw is>

impossible.

6.1 LOWER TRUNNIONS |

The radius areas of the trunnions were examined and no flaws were detected.

The following table of flaws shows the detected flaw size, the location, andthe calculated critical flaw size for the pin hole edge area. For the lowertrunnion, the smallest critical semi-elliptical flaw is defined to be0.115" x 0.231" . It is important to note that no flaws were detected ;

at the pin hole edge. Only those flaws greater than 0.070" x 0.070" are ~|j

considered relevant and are therefore shown in Table 1.

6.2 00LUMN CLEVISES !

The radius areas of the<tolumn clevises were examined and no flaws were de-tected, ,

I*

The following table of flaws shows the detected flaw size, the location, and .l'

the calculated critical flaw size. For the column clevises, the smallestcritical semi-elliptical _ flaw is defined to be 0,171" x 0.342", It is im-

portant to note that no flaws were detected at the pin hole edge. .

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Only those flaws greater than0.1"x 0.1"are considered relevant and are there-i

fore shown in Table 2.

6.3 CONCLUSION.

'

; As the tables in Section 6,1 and 6.2 indicate, that for the lower trunnions -.

: and clevises, the ratio of the detected flaw area to the calculated critical~

flaw area is never larger than 1 to 3 and is generally much smaller thanl to 10. Therefore, all parts examined contain no flaws larger thanthe calculated critical flaw size.

7.0 SAFETY IMPLICATIONS .

The subject forgings function as primary load transfer members of the supportsystem of the steam generators and reactor coolant pumps in Units 1 and 2 ofthe McGuire Nuclear Station. They function in this capacity during all normalconditions and serve to mitigate the consequences of any faulted condition.The worse case safety consequences have been reviewed with the following con-clusion. If the support columns are subjected to the faulted loading conditionthey will perform their intended function, provided no flaws exist whichexceed the critical flaw sizes outlined in Section 4.3 All of the Unit

2 forgings and a selected sample of Unit 1 forgings have been shown, by ultra-sonic examination, to be free of flaws approaching the applicable criticalflaw sizes. As discussed in Section 5.0, the ultrasonic examination of the .

remainder of the forgings is currently ongoing. The forging material properties - e

are structurally compatible with their service requirements. The safe opera-tion of McGuire Nuclear Station is not impaired or jeopardized by the use ofthese forgings.

8.0 CORRECTIVE ACTION

All remaining lower trunnion and column clevis forgings of Unit I are beingultrasonically examined. If flaws in excess of those defined in Section 4.3are discovered, the parts will be replaced. All parts, tested to date, arequalified for service in accordance with evaluation contained herein and there-

fore remain in place.

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AJAX FORGING $. CASTING CO.GaAts 4340 '

FIGURE A IC N5f L E STRE.NGTHi

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Z25 235 245 255 265 275 285 295 30s 315 325 335 34-5 355 365 ji

BRINELL HARDNESS NUMBER ||I

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9 - Duke Field Brinell Testsfor Clevises.

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3 - Laboratory Brinell Tests{for Clevises.

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Page 12. 10/17/78

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TABLE 1 .

Lower Trunnions;

.

RadialDistance Allowabic*

Equivalent Equivalent From Pin Orientation Critical Buried EllipticElliptical Dim. Circular Dia. Hole Edge to Critical Plane Flaw SizePart Indi-

Areg) (in.) (in.) (in.) (Deg.) (in.)(inNo. cation4-1-8 1 .049 N/A* .25 1.573 90 .l.16 x .58

2 .049 N/A .25 3.240 90 2.40 x 1.20"

3 .047 .30 x .20 N/A 5.503 90 > 3.0 x 1.5"

4 .049 N/A .25 4.898 90 > 3.0 x 1.5"

5 .097 .45 x .275 N/A 6.454 90 > 3.0 x 1.5"

G .049 N/A .25 7.488 90 > 3.0 x 1.5"

7 .031 N/A .20 4 .51 5 90 > 3.0 x 1.5"

8 .069 .35 x .25 N/A 4.079 90 > 3.0 x 1.5"

9 .049 N/A .25 3.465 90 2.58 x 1.29"

10 .094 40 x .30 N/A 2.986 90 2.20 x 1.10"

11 .069 .35 x .25 -N/A 4.854 90 > 3.0 x 1.5"

12 .063 .40 x .20 N/A 5.739 90 > 3.0 x 1.5"

13 .076 .35 x .275 N/A 5.665 90 > 3.0 x 1.5"

14 .373 .95 x .50 N/A 5.820 90 > 3.0 x 1.5"

4-1-11 28 .141 .45 x .40 N/A 4.666 90 > 3.0 x 1.529 .177 .50 x .45 N/A 5.356 90 > 3.0 x 1.5 !"

30 .118 .50 x .30 N/A 5.435 90 > 3.0 x 1.5"

31 .126 N/A .40 1.123 0 .98 x .49"

4-1-9 1 .055 .281 x .25 N/A 6.433 90 > 3.0 x 1.52 .196 N/A .50 5.765 90 > 3.0 x 1.5"

3 .373 1.00 x .475 N/A 7.558 90 > 3.0 x 1.5"

4 .393 1.00 x .50 N/A 7.519 90 > 3.0 x 1.5"

.016 .20 x .13 .143 2.523 0 1.48 x .744-1-18 1 '

2 .01 3 .182 x .091 .129 3.792 90 2.56 x 1.28"

4-1-24 1 .01 3 .182 x .091 ' 'o 2.543 0 1.48 x .742 .010 .160 x .080 .ii3 2.543 0 1.48 x .74"

3 .010 .160 x .080 .113 .2.1 21 0 1.20 x .60"i

1-1-17 1 .071 N/A .30 7.536 90 > 3.0 x 1.5

? See Reference 1.'

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TABLE 2Column Clevises .

#

Radial Allowabl e*Distance

Equivalent Equivalent' From Pin Orientation Critical Buried Elliptic

'

.

Indi- Area Elliptical Dim. Circular Dia. Hole Edge to Critical Plane Flaw Size-

No. cation (in2) (in.) (in.) (in.)~ (Deg.) (in.)Part

4-2-32 1 .025 .25 x .125 N/A* 1.143 90 94 x .47..

1.

O'See Reference 1.

O N/A - Not Applicable.

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. REFERENCES

- 1. " Flow Analysis for Components of Steam Generator and Reactor CoolantPump Suppo.-ts," Report No. FAA-78-09-4, Failure Analysis Associates, ~ ~ -

October 14, 1978.2

2. " Evaluation of Integrity of Forged Trunnion . Sections of ASME SA-540Grade B23 Alloy Steel in Support Columns for Steam Generators andPumps, Units 1 and 2, McGuire Nuclear Power Station, Duke PowerCompany," Report No.1785, Helmut Thielsch, Consulting MetallurgicalEngineer, September 16, 1978.

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