ML20150B285
| ML20150B285 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/19/1978 |
| From: | Parker W DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20150B281 | List: |
| References | |
| NUDOCS 7811010162 | |
| Download: ML20150B285 (17) | |
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Final Construction Deficiency Report CD-369-370/78-07 McGuire Nuclear Station Units 1 & 2 Oc tober 19, 1978 I
1.0 INTRODUCTION
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 letter addressed to Mr. J. P. O'Reilly, USNRC, dated September 1,1978 The interim report outlines evaluation of the problem, investigative activities required to define the problem and corrective action being pursued by Duke Power
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Company to resolve the discrepant material certification data.
The final report is 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 laboratory testing 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 each support forging.
An engineering evaluation of each support forging was then developed, utilizing these physical properties, to establish the adequacy of the 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 finding could be symptomatic of reduced material fracture toughness.
The Charpy V-Notch impact test is generally specified by the engineer as a quality con-trol measure to assure that considerable impact toughness is available to accommodate a design dynamic service condition, at service temperature.
Duke's review of the test results concluded that forgings which possessed Charpy V-Notch energies below specification would be evaluated for their intended service by establishing the fracture toughness required to prevent brittle fracture and comparing this value with the actual fracture toughness of the forgings.
To assist in this effort, Duke retained the services of Failure Analysis Associates of Palo Alto, California, an internationally recognized engineering and metallurgical consulting firm.
Lakeside Bridge and Steel Company, supplier of the support forgings, retained Mr. Helmut Thielsch, of Cranston, Rhode Island, a similarly recognized consulting metallurgical engineer, to independently evaluate the fracture toughness of the support forging materials.
The results of this effort, as well as Duke's engineering evaluation, 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 the requirements of ASME Specification SA-540, Grade B23, Class 4, supplemented with 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%
i Minimum Reduction of Area = 45%
Surface Brinell Hardness = 285 min., 363 max.
2 Charpy V-Notch Impact * = 25** ft-lbs at 50 F
- Supplemental Requirement of Duke Specification MCS-1117.00-2 l
- 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, 32 steam 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 final machined. Heat treatment was accomplished in 33 heat treatment lots. All members 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 material certifications, as described in the interim report, led to a decision to initially conduct a limited confirmatory test program of the forging materials.
The lower column trunnions were selected for testing because they represent the bulkiest forging pieces with the least forging reduction, in addition to being easily accessible to remove samples.
The lower trunnions for Units 1 and 2 were fabricated in seven (7) heat treat lots.
Samples were removed and tested from representatives of each heat treat lot.
Two (2).fu11 size tensile specimens and three (3). standard Charpy V-Notch impact specimens were tested from each sample.
Results of the tests were as follows:
_2 -
fiumber of Lower Trunnion Samples Complying SG Lower RCP Lower With Specification Material 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
l BHN 277 to 321 285 to 311 6
C 0 50 F (ft-lbs) 11.6 to 19.3 11.7 to 15 0
y 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 the extended phase of the testing program and its relationship to the forging i
fabrication process and total population, fiumber of fiumber of Fabrication Number of Heat Forging Type Material Heats Heat Treat Lots Treat Lots Tested Lower Trunnions 5
7 7
_ _j Upper RCP Trunnions 1
4 4
l Upper SG Trunnions 3
4 4
Clevises 3
14 8
l 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 32.3 y -
.9
A limiting condition for operation required by the McGuire Nuclear Station Technical Specifications is that primary Containment average tempgrature in the Containment lower compartment shall be between 100 and 120 F.
Charpy i
V-Notch test temperatures of 800f for forgings at the base of a column and 110 f for forgings adjacent to the components were conservatively 0
specified for the test program. Tests at 50 Of were run for use in correl-4 lating test results to vendor supplied material certifications.
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a 3.0 CORRELLATION OF TEST RESULTS WITH VENDOR PATERIAL CERTIFICATIONS l
A review of the test data and certified data received from Ajax for each part was conducted to establish the degree of corre11ation.
A strong correllation l
exists between the certified and tested data for tensile strength, Brinell F
Hardness area reduction, and elongation. The tested yield strengths range from 16 ksi above to 30 ksi below the certifie ' values.
The average variation
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was 8 ksi below the certified value.
No correi'.ation could be established be-j tween the certified and tested Charpy V-Notch data.
,s 3.1 COLUMN CLEVIS
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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
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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 part satisfy 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
t specified. Tests range from 84.9% to 109.9% of the minimum specified.
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b)
Certified tensile strengths range from 111.9% to 118.4% of the maxi-i
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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 parts satisfy the average / minimum requirements.
Sample test results indicate that no parts satisfy the specification requirements.
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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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.
l 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 minimum specified. Test results are 103.3% of the minimum specified.
c)
All certified data from Charpy V-Notch tests satisfy the average / minimum requirements.
Sample test results for the material satisfy the minimum but not the average specified requirements, but does satisfy both of these 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 RCP and SG trunnions and the lower trunnions were tested.
However, for the column clevises 8 of 14 heat treat lots had samples tested, and for the column pins,
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one of four heat treat lots had samples tested.
In order to determine values for 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 correlation was valid, Brinell hardness values were obtained from all parts (including all trunnions, pins, and clevises), in place.
A relationship between Brinell hard-ness values and yield and tensile strengths exists and has been documented for typical 4340 material which possessed similiar mechanical properties and passed through the Ajax facility from January 1976 to July 1977 (see Figures A and B). ASME Specification SA-370, Table 3, outlines the same correlation over a much wider range of tensile strengths.
The Brinell values indicated that the yield and tensile strengths for the tested and untested clevises and pins 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 certified values for the yield and tensile strengths.
As previously stated, no correlation between the vendor certified and tested Charpy V-Notch data was established. The rough correlation between Charpy V-Notch values and Brinell hardness values was judged to be too inaccurate to use.
Hence,Charpy V-Notch values at a 95% confidence level were established for all untested parts (see Reference 1, Section 6.0).
Based on the above techniques, the following values are assigned to the untested clevises and pins:
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9 Clevises' Pins
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f 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 31.0 0
y C 91100F(ft-lbs) 19.0 32.0 y
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 to function as pinned - pinned members.
The columns have limited freedom of ro-tation to accommodate movement of the supported component during thermal contraction 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 McGuire Nuclear Station.
In each loop there are four (4) steam generator and three
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(3) reactor coolant pump support columns.
The loads applied to each of these seven (7) support columns are different depending upon their location.
The original 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 pump column no. 2 (see Figure C).
The following summarizes the maximum column loads:
LOAD COLUMN (KIPS)
RCP 1 873 RCP 2 2146 RCP 3 1284 SG 1 996
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SG 4 797 I
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It is apparent from this summary that the six (6) of the seven (7) columns in each loop were designed with considerable strength margins when compared with 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 particular column 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 RANGES Service 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
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3.0 are summarized as follows.
Yie.ld Strengths f_orging Type (KSI) j i
RCP Lower Trunnions 111.8 j
102.0 SG Lower Trunnions
> 117.9 RCP Upper Trunnions 136.7 SG Upper Trunnions
> 110.6 Pins 105.5 Clevises
' Comparisons of these. summaries demonstrate that the forgings possess mechanical properties 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 forgings has be.en taken, The stress levels in the forgings comply with the allowable structural acceptance criteria delineated in Section 5,5.14 of the McGuire Nuclear Station final Safety Analysis Report, 4.3 FRACTURE TOUGHNESS The failure behavior of structures under monotonic loading may be characterized
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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 and are not subject to brittle fracture failure, a standard value of the absorbed energy in the Charpy V-Notch impact test was specified.
It is recognized that the actual performance of steel components in a particular application and of a particular design may be completely unrelated to the actual Charpy V-Notch toughness 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 impactive loads. Subsequent tests of un-notched specimens indicated that the material does indeed exhibit ductile behavior (see Reference 2), and would provide totally 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 of linear elastic fracture mechanics (LEFM).
As the normal loads and associated stresses in the forgings are very low (well below the endurance limit) and the environment in which the forgings exist is non-corrosive, cracking or flaw generation by fatigue or stress corrosion will not occur. Hence, the relevent 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 forgings and 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 size for a through thickness crack is 0.023 inch by 26 inches long for the RCP-2 lower 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 inches for the RCP-2 lower trunnion at the edge of the pin hole.
However, only 0.5 inches'from the pin hole the critical elliptical flaw size increases to 0.37 x 0.19 inches, for the buried elliptic flaw.
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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 Reference 1, figure 3.4c) were also developed as a function of location from the clevis or lower trunnion pin hole,'and fracture toughness (KIC); conservatively utilizing the worse case stress gradient.. This character of flaw would be the most commonly occurring type.
This analysis is used to conservatively establish pennissible 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 the Charpy 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-1 fined by a factor of 3.0.
If the forgings contain no flaws with dimensions in excess of those defined by 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 with respect to internal flaws, a detailed ultrasonic examination program was con-ducted. The forged parts examined were those parts for which Charpy V-Notch test results were less than the original specified values.
A review of the test data indicated that only the lower column trunnions and the column clevises would require examination. However, because of the easy accessability of these parts in Unit 2, it was decided. that all lower trunnions and column clevises would be examined initially regardless of the tested Charpy V-Notch data; while only one sample of each heat lot, for the lower trunnion and column clevis, would be examined in Unit 1.
A detailed examination of all remaining parts 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 are those identified as critical areas in Section 4.3.
In addition, the remaining portion of each part was thoroughly examined to the extent possible, based on the part external geometry.
The ultrasonic equipment was calibrated to ac-2 curately 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, representatives of 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%ofalldetected The 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 edge and was ' oriented 900 to the critical plane.
The majority of the flaws are oriented such that their major dimension is parallel 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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.7 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 inches j
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(0.125 x 0.25 inches, one of the three flaws defined above) with the majority The trunnion material had detectable d
i of the clevises having no detectable flaws.
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flaws, but generally in the range of.001 to 0.005 inches,
9 The forging material is exceptionally clean material possessing only very small internal flaws.
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6.0 COMPARIS0N OF CRITICAL CALCULATED FLAWS AND ACTUAL FLAWS 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-formation only in. Reference 1.
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As stated in Reference 1, the techniques of linear elastic fracture mechanics when used to determine critical flaw sizes to cause failure give conservative In addition, the use of the highest stressed part (for all trunnions values.
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's for the lower trunnions further add conservatism to the calculated critical i
Hence, if all flaws discovered in the forgings are less than the flaw 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, and the calculated critical flaw size for the pin hole edge area.
For the lower trunnion, the smallest critical semi-elliptical flaw is defined to be 0.115" 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
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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 the calculated critical flaw size.
For the column clevises, the smallest critical 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
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flaw area is never larger than 1 to 3 and is generally much smaller than l
to 10.
Therefore, all parts examined contain no flaws larger than the calculated critical flaw size.
7.0 SAFETY IMPLICATIONS The subject forgings function as primary load transfer members of the support system of the steam generators and reactor coolant pumps in Units 1 and 2 of the McGuire Nuclear Station.
They function in this capacity during all normal conditions 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 condition they will perform their intended function, provided no flaws exist which exceed 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 critical flaw 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 of these forgings.
8.0 CORRECTIVE ACTION All remaining lower trunnion and column clevis forgings of Unit I are being ultrasonically examined.
If flaws in excess of those defined in Section 4.3 are discovered, the parts will be replaced.
All parts, tested to date, are qualified for service in accordance with evaluation contained herein and there-fore remain in place.
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AJAX FORGING $. CASTING CO.
GaAts 4340 FIGURE A IC N5f L E STRE.NGTH i
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Page 12 10/17/78
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i T
hh C
1
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<. g A g % h 4 4 3
~
2 i
r 4p$qqqsp:a b 3
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%.s.....Q.,eEA@a....t,/,.6., %e.1. _0$s 9$w V
r 1.--
.y m y e...,-
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2a.!,,t 192 sq 4('lFS.
f3*L G.g.ff', [hhd6bbb T'
e 7
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3401 bb5Ichh{E sj,
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m TABLE 1 Lower Trunnions Radial Distance Allowabic*
Equivalent Equivalent From Pin Orientation Critical Buried Elliptic Elliptical Dim.
Circular Dia.
Hole Edge to Critical Plane Flaw Size Part Indi-Areg)
(in.)
(in.)
(in.)
(Deg.)
(in.)
(in No.
cation 4-1-8 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 1.5 29
.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 1.5 2
.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.74 4-1-18 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.74 2
.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.
~
15-t 3
t i+
.a 2
....m
_______.___1____.__a__.___________,__._m.._.2.m
.rma
- 2. mm w
am 1
4 E
. e O.
5 i F '
I'.:
s TABLE 2 Column 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.
8
% )
i k
h 4-c 2. w.. i.
w
.m
______,__k,
..y.y.
.se 2 h 54 L M4 4
REFERENCES 1.
" Flow Analysis for Components of Steam Generator and Reactor Coolant Pump 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-540 Grade B23 Alloy Steel in Support Columns for Steam Generators and Pumps, Units 1 and 2, McGuire Nuclear Power Station, Duke Power Company," Report No.1785, Helmut Thielsch, Consulting Metallurgical Engineer, September 16, 1978.
wemmer e
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