ML20090K984
ML20090K984 | |
Person / Time | |
---|---|
Site: | Catawba |
Issue date: | 11/17/1983 |
From: | DUKE POWER CO. |
To: | |
References | |
A-052, A-52, NUDOCS 8405240516 | |
Download: ML20090K984 (90) | |
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r Mr. C. K. Moore Vestinghouse Electric
- P. O. Box 32817
- l Charlotte, N. C. 28232 l .i Catawba Nuclear Stationrvice Water Pump Motor SUBJECT : Nuclea E:
' CN-1318.20r
- o. er No. A-71135 j M...
M Westinghouse CH-18020-I.7
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Dear Chester:
it to Catawba Huclear Stat onhermocou Please 4 : !
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During Alex Ehrenburg'sisviswe found lower pairs. bearing tatta T .C.
pump motor inspectionbroken near the place the advise when Westinghouse
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!?/ C. J. Vylie, Chief Engineer 5,h :I II Electrical Division . ;
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i APPROVED: J. P/. Vogleyde I Alex Ehrenburg
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\ O DUKE POWER COMPANY CONSTRUCTION DEPARTMENT l CATAWBA NUCLEAR 1 & 2 P. O. sox a z a CLOVER. S. C. 2971o TELEPHoN E: AREA 403
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March 29,1979
, MEMO TO FILE i
Catawba 1-2 Nuclear Service Water Pump Motor One of the nuclear service water pump motors presently located in the No. 1 Warehouse is nonconformed and is covered by NCI #3865. The nature of the NCl will not affect the moving of the motor so it can be installed on the pump.
j Action is currently being done in accordance wlth the NCl, but minor problems are holding up its immediate completion.
N W Beam Technical Support-Electrical JWB/1wl l QgApproval l
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CI 4386 -
- 17. The 1/2 X 1 1/4" bolts used by Construction for mounting the Main control Boards are to be equivalent in strength to ASTM A-307 bolts.
These bolts should be included in the sample program of 1/2" bolts being tested under the resolutions of NCI 4495 and NCI 4496 to verify their acceptability for this safety-related application.
- 19. By: Date: v//t/79
- 20. Techn ca pproval:
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- 21. QA Approval: /C dk Date: 4-/9 79 l
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\ '% CI 4495 - /tu 1 '7. % 1/?" d h-eter be1 + t us ed 4 - the nuchar afety rc'atM c:ble tray support systems are to be equivalent in strength to ASTM A-307 bo .
appropriate design drawings have been ravised to indicate is. To veri hat all 1/2" diameter bolts used meet thi rength requirement, a random sam of each bolt size shall be secur y Construction from those bolts whic re not indentified by ap riate markings. The sample sizes shall be in a dance with B W Lo 's attached letter of 3/29/79. These samples shall then tested i ccordance with C L Ray's attached test procedure of 3/20/79. The results of this testin rogram 11 be sent to Design Engineering / Electrical Division for etermination o eptability.
- 19. By: / m_ Dat . 9/is/N'
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- 20. Te Ica Approval: t) Date: /, //, - ,
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O (V NCI 4495 - Revision 2
- 17. The h" diameter bolts used in the nuclear safety related cable tray support systems are to be equivalent in strength to ASTM A-307 bolts. All appropriate design drawings have been revised to indicate this.
To verify that all " diameter bolts used meet this strength require-ment, a random sample of each bolt size shall be secured by Construction from those bolts which are not identified by appropriate markings. The sample sizes shall be in accordance with B W Logan's attached letter of 3/29/79. These samples shall then be sent to a qualified outside testing laboratory by the Construction Department, to be tested in accordance with ASTM A-307 requirements. The results of this testing program shall be sent to the Design Engineering Electrical Division for detennination of acceptability. In order to prevent reoccurance of this problem, several changes have been implemented. First, all appropriate design documents have been , revised to specifically state the material / grade requirements for bolting materials. Second, the Purchase Requisitions for all bolting IQ materials are checked for the inclusion of applicable material / grade requirements. Third, Mill Power Supply has comitted that no vendor or material substitutions will be made without the prior approval of responsible Design Engineering personnel.
- 19. By: -
, Date:
in 80
- 20. Technical Approval: Date:
- 21. QA Approval: Date: -
/c ~ / .fec e b U GNers bm , A bl 3 N !/
i .w l
'.f .: ; . c' (' \
y:..-- m l March 29, 1979 - C (C D G Owen
Subject:
Determination of Sample Size for Catawba Electrical Bolting Material Problem File: CN-1388.00 The testing of sample bolts to make an inference about the ability of an entire lot to meet tensile strength criteria is a two part statistical problem. The first part involves the determination of an appropriate sample size, and the second part is concerned with the acceptance or rejection of the lot based upon the results of the tests. Thefollowingprocedureisproposedto1)determineanappropriatesamplesizefor each of the bolt lots in question, and 2) establish a criteria for accepting or rejecting the lot based upon the test results. In order to establish the procedure, the following assumptions must be made:
- 1) Since the number of bolt manufacturers represented in the questioned lots cannot be detemined, each lot shall be approached as an unknown quantity.
- 2) The bolts used at Catawba Nuclear Station are not significantly different from those used at McGuire Nuclear Station. This allows the use of McGuire test results to estimate physical parameters which are needed to detemine (O
sample sizes. The Catawba test results will indicate the validity of this assumption.
- 3) The accuracy qf torque wrenches used to tighten bolts is I 5% of the set value. This is used to detemine the allowable error in measuring tensile strength. The test should not' expect accuracy better than that of the wrenches used to tighten the bolts.
- 4) An acceptable confidence factor is 99% or roughly three standard deviations (3a) from the mean value.
Based upon these assumptions the following expression
- should be used to determine sample sizes 3, 2 wh;re n is the number of samples, o is one standard deviation from the mean tensile strength calculated from McGuire test results, and E is the allowable error in the i
tensile strength measurement and is based on McGuire data. This expression means that if n samples are tested, there is better than a 99% chance the estimated tensile strength for the lot will lie within the allowable error limit. l t i A M rom Introduction to Probability and Statistics, pp. 182, 197
- .p-
.... v. - . (( (< j . . j ; H Pi i D G Owen
f>? arch 29,1979 y age 2 When a tested bolt size from McGuire closely corresponds to a questioned bolt size from Catawba, the McGuire test data
- for that bolt size shall be used in calculating the Catawba sample size. When a Catawba bolt size does not correspond to a tested
- McGuire bolt size, the McGuire values which give the most conservative estimate '
j of sample size, i.e., the largest observed standard deviation and the smallest j allowable error bound, shall be used in the sample size determination. The following table will suninarize the suggested sample sizes ** for each of the questioned bolt sizes: Suggested Sample Size Confidence Bolt Size Quantity Issued 95% 99%
- 1/2" X 15/16" 107,500 - 58 1/2" X 1 3/16" 15,000 - 8 1/2" X 1 1/2" 51,000 - 45 1/2" X 1 3/4" 1,600 26 -
4 1/2" X 2" 1,000 25 l 1/2" X 2 1/4" 500 25 l( 1/2" X 2 1/2" 16.000 ysv y
- .s .
- 2.
For the 13/4, 2 and 21/4 inch bolts, a 95% confidence level is suggested to reduce the number of samples to a more realistic value. Also, the reason only eight samples were required of the 13/16 inch bolts is that the McGuire data for the 11/4 inch bolts displayed a fairly Jmall standard deviation. After testing the bolts from Catawba, a mean value for tensile strength and a standard deviation about the mean should be calculated for each bolt size. ASTM Standard A 307-76b sets the minimum acceptable tensile strength for Class A bolts
- at 8500 lbf. Acceptance or rejection of a bolt size lot should be determined by l the following procedure
- 1) Calculate a mean and a standard deviation from test data f
2 Subtract 8500 from the mean value 3 Divide the result (from 2) by the calculated standard deviation l 4 If this quotient is greater than 2, accept the lot. This gives 95% l confidence that the bolts in the lot have tensile strengths greater than the mean less 2o. ,
- 5) If the quotient is less than 2 a reject the lot or, b repeat the test using the same sample size or, c find the true percentage from a standard nonnal distribution table and determine if it is acceptable. For instance,1.645o give 90% confidence.
l
- McGuire NCI Report No. 4444
** Calculations are attached.
1, I
* '
- L.
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- f. .
l lI s 44 6 i t D G Owen March 29, 1979 l l Page 3 l
- j. If you have questions or coments on the above procedures, please notify me.
t : [ B W Logan l l ; j Assistant Design Engineer ! l l BWL/1ge l attachments l l cc: L E Suther B German i C J Hager ! i i
~
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%%W hg CALCULATIONS l For 99% confidence j Bolt size "
o E n= h . N ng=n 3n !- 1/2 X 15/16 1214 480 58 107,500 -
- 1/2 X 1 3/16 455 480 8 15,000 - -
{ 1/2 X 1 1/2 1214 545 45 51,000 - . 1/2 X 1 3/4 1214 480 58 1.600 56 -
- 1/2 X 2 1214 480 58 1,000 55 1/2 X 2 1/4 1214 480 58 500 52
- I/2 X 2 1/2 1214 480 58 10,000 - i t
} i i i ! For 95% confidence 1 ( - 2o '2 - - Bolt Size o n=
- E T .
N ng=n N+n N l 1/2 X 1 3/4 1214 480 26 1 ,600 - 1/2 X 2 1214- 480 26 1,000 25 1/2 X 2 1/4 1214 480 . 26 500 25
- ASTM Standard E 122-72, Section 5, p 1045 i
i j 4 i l i i i
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- LW95
- i i
REFERENCES ! 1. ASTM Standard A 307-76b, " Standard Specification for Carbon Steel Externally and Internally Threaded Standard Fasteners." - ' I 2. ASTM Standard E 122-72, " Standard Recomended Practice for Choice of Sample j Size to Estimate the Average Quality of a Lot or Process." j
- i. 3. William Mendenhall Introduction to Probability and Statistics, Duxbury Press, i 1971. j 4
- 4. McGuire NCI Report No. 4444.
l \ i - 1 1 ! ! l ( i i , 0 I ? 4 e i i , t i t
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( ( NCI 4495 - Addendum to Revision 2
- 17. EVALUATION OF TEST RESULTS In order to complete the statistical process of determining whether or not the sample bolts meet the mechanical strength criteria of ASTM A-307 bolts, the attached test results for each of the samples must be evaluated according to the established acceptance procedure (See B W Logan's attached letter dated 3/29/79). .
The evaluation of the test results for the 1/2" bolts is summarized in Tables I and II. For the lot of 1/2" x 15/16" bolts, a Rockwell "B" hardness test detennines whether the bolts conform to the mechanical requirements. As shown in Table I, the results indicate that the mean value is greater than two standard deviations from both the upper and lower limits of the hardness requirements. Therefore the respective sample of 1/2" x 15/16" bolts is acceptable to the standards of ASTM A-307 bolts. The remaining samples were tested in regards to their conformance to the mechanical tensile strength requirements. The evaluation of their test results is sumarized in Table II and indicates that the respective samples are also acceptable. In conclusion, the test results have determined that the subject bolts meet the mechanical requirements for ASTM A-307 bolts with a 95% confidence level. O
- 19. By: ff.udM t
h) b.t! #h Date: 3 /10 /2 i i
./
- 20. Technical Approval Date: k' //
- 21. QA Approval /[ M Date: J 25f/
! t .,
i - i' .- STANDARD REQUIRED i SAMPLE MEAN DEVIATION
" (1)-(3) (4?-(1) ACCEPTABLE 80LT SIZE 2
SIZE (1) (2) ] I,2) I,2) LOT 7 i 1/2* x 15/16" 58 92.95 2.62 69 100 9.14 2.69 YES s l -l m l o TABLE I EVALUATION OF HARDelESS TEST RESJLTS FOR 1/2" BOLTS i l l STANDARD MIN TENSILE j SAWLE MAN DEVIATION STRENGTH (L85) (15-l'3) ACCEPTABLE 80LT SIZE SIZE (1) (2) 1 [ (3) ll2? LOT ? l 1/2" x 1-3/16" 8 10825.00 738.24 8500. 3.15 YES i
- 1/2" x 1-1/2" 45 12415.55 232.04 8500. 16.87 YES
! 1/2" x 1-3/4" 26 11723.07 505.61 8500. 6.37 YES I ! e i 1/2" x 2" 25 11612.00 172.17 8500. 18.08 YES I f i 1/2" x 2-1/4" 25 13436.00 392.51 8500. 12.58 YES i, . j 1/2" x 2-1/2" 58 12484.48 111.29 8500. 35.80 YES i i .I
,' I TABLE II
[ j EVALUATION OF TENSILE STRENGTH TEST RESULTS E S i FOR 1/2" BOLTS w ..
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~vme LAW EN('NEERING TESTING Cr".MPANY ,c.- '
wa- -n em. ~... ~. (1 .,,9 1 x cHAntottE NOAfM CAAoVN4 28220 ROC M .L "B" HARDNESS INSPECTION ! REPORT OF Client: Duke Power Company Office: Charlotte Metals Pr: ject: Catawba Nucicar Station Date: February 4, 1981 Newport, South Carolina CHS 81-016 Lab. N'o. Clie t's P. O. No.: G 2494-41 Ma,thrial: Reported as Carbon Steci Externally Threaded Standard Fastner ASTM A307 (See Below) Grado A
\ o
- Heat No. Unknown a
Date Tested: 2/2/81 Procedure: In accordaned with AST!! A307-78 and ASTM E18-79 i
)
EQUIF? TENT CALIBRATION
,O i l
Average Calibration Reading
'\ j Readin93 t' Reading 7
Standard Correction, %
-[ 84.1 , 81.6 97.0 -- 87,.3 81.6 93.5 ROCWELL "B" HARDNESS RESULTS 9
LETCo. Bolt Size Average Corrected Piece No. (In) , Reading Reading Co:me n ts 1-23-81-1 1/2" x 15/16" 92.0 89 -- 1-23-81-2 1/2" x 15/16" 97.1 94 -- 1-23-81-3 1/2" x 15/16" 92.2 89 -- 1-23-81-4 ' 1/2" x 15/16" 95.6 93 -- 1-23-81-5 1/2" x 15/16" 98.3 95 -- 1-23-8*-6 1/2" x 15/16" 98.0 95 -- 1 ??-61-7 1/2" x 15/16" 97.3 94 -- g/1-2.1-01-0 1/2" x 15/16" 97.5 95 -- M 23-81-9 1/2" x 15/16" 99.2 96 -- 1-23-01-10 1/2" x 15/16" 98.0 95 --
'i, ' 1-23-81-11 1/2" x 15/16" 99.0 95 --
1-23-81-12' 1/2" x 15/16" 98.3 94 -- I ' b N1-23-81-13 1/2" x 15/16" 99.3 95 -- ( jl-23-81-14 1/2" x, 15/16" 96.5 92 --
, Page 1 of 3 ,
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ke Power Company Satawba C Nuclear Station LETCo. Job No. CHS 81-016 February 4, 1981 Page 2 of 3 ROCKWELL "B" HARDNESS RESULTS Continued LETCo. Bolt Size Average Corrected Piece No. (In) Reading Reading Comments i . 1-23-81-15 1/2" x 15/16" 97.8 93 -- 1-23-81-16 1/2" x 15/16" 96.6 92 -- 1-23-81-17 1/2" x 15/16" 95.6 91 -- 1-23-81-18 1/2" x 15/16" 100.0 96 -- 1-23-81-19 1/2" x 15/16" 99.8 95 -- 1-23-81-20 1/2" x 15/16" 98.7 94 -- 1 1 1-23-81-21 1/2" x 15/16" 100.6 95 -- 1/2" x 15/16" 95.7 90 --
/ \ 1-23-81-22 ' 1-23-81-23 1/2" x 15/16" 99.3 94 --
1-23-81-24 1/2" x 15/16" 97.5 92 -- 1-23-81-25 1/2" x 15/16" 100.7 95 -- 1-23-81-26 1/2" x 15/16" 99.0 94 -- 81-27 1/2" x 15/16" 98.8 93 -- 81-28 1/2" x 15/16" 100.2 95 -- 1-23-81-29 1/2" x 15/16" 99.7 94 -- 1-23-81-30 1/2" x 15/16" 100.0 95 -- 1-23-81-31 1/2" x 15/16" 98.2 93 -- 1-23-81-32 1/2" x 15/16" 102.8 97 -- 1-23-81-33 1/2" x 15/16" 99.7 94 -- 1-23-81-34 1/2" x 15/16" 96.3 91 -- 1-23-81-35 1/2" x 15/16" 100.3 95 -- 1-23-81-36 1/2" x 15/16" 97.2 92 -- 1-23-81-37 1/2" x 15/16" 98.5 93 -- 1-23-81-38 1/2" x 15/16" 95.3 90 -- 1-23-81-39 1/2" x 15/16" 99.3 94 -- 1-23-81-40 1/2" x 15/16" 99.8 94 -- 1-23-81-41 1/2" x 15/16" 98.2 91 -- 1-23-81-42 1/2" x 15/16" 99.2 92 -- 1-23-81-43 1/2" x 15/16" 99.2 92 -- 1-23-81-44 1/2" x 15/16" 101.2 94 -- 1-23-81-45 1/2" x 15/16" 96.8 90 --
. 1-23-81-46 1/2" x 15/16" 98.0 91 --
1-23-81-47 1/2" x 15/16" 98.0 91 -- 1-23-81-48 1/2" x 15/16" 97.0 90 -- 1-23-81-49 1/2" x 15/16" 100.2 93 -- D .
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e Power Company tr.wba Nuclear Station LETCo. Job No. CHS 81-016 February 4, 1981 Page 3 of 3 ROCKWELL "B" HARDNESS RESULTS Continued LETCo. Bolt Size Average Corrected Piece No. (In) Reading Reading Comments 1-23-81-50 1/2" x 15/16" 100.0 93 -- 1-23-81-51 1/2" x 15/16" 89.7 83 -- 1-23-81-52 1/2" x 15/16" 98.3 91 -- 1-23-81-53 1/2" x 15/16" 100.8 94 1-23-81-54 1/2" x 15/16" 102.2 95 -- 1-23-81-55 1/2" x 15/16" 90.8 84 -- 1-23-81-56 1/2" x 15/16" 102.7 96 -- 1-23-81-57 1/2" x 15/16" 101.0 94 -- 1-23-81-58 1/2" x 15/16" 102.5 95 -- Required Range........................................... 69 thru 100............. O k Inspector: Richar rris Reviewed by: Edward M. Beck, P. E. Metals Department Manager i l Respectfully submitted, LAW ENGINEERING TESTING COMPANY l 2 > f 6dX h V Larry oble, Metals Laboratory Supervisor UW ENGPEERING TESTNG CCMRWr
LAW EV. IINEERING TESTING / OMPANY
- - - ~ . a s ;/iD, p 4, s.: rp' .. u,,,,. - ~ . .
set uWUET LANE p o Box 11297 e CHARLOTTE. NOATH CAAoVNA 28220
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w> s2>2c22 % ; REPORT OF MECHANICAL TENSION TEST Duke Power Company g; Charlotte Metals Client: Project: Catawba Nuclear Station Date: February 4, 1981 Newport, South Carolina 1.ab. No. CHS 81-016 Client P. O. No.: G 2494-41 Material: Reported as Carbon Steel Externally Threaded Standard Fastener ASTM A307 (See Below) Grade A Heat No.: Unknown Date Tested: 2/3/81 Procedure: In accordance with ASTM A307-78 and ASTM A370-77 TEST RESULTS Bol Site Threads Area Ultimate Load (}L'ETC:: . (In) Per Inch. (In 2) (Lbs) ( ,/ie c e _N..o.. 13 0.1419 10 ~. ,0 1-23-81-1 1/2" x l-3/16" 0.1419 10,550 1-23-81-2 1/2" x 1-3/16" 13 1-23-81-3 1/2" x l-3/16" 13 0.1419 10,400 1-23-81-4 1/2" x l- 3,'16" 13 0.1419 12,400 1-23-81-5 1/2" x l-3/16" 13 0.1419 10,050 1-23-81-6 1/2" x l-3/16" 13 0.1419 10,250 1-23-81-7 1/2" x l-3/16" 13 0.1419 10,850 1-23-81-8 1/2" x l-3/16" 13 0.1419 11,200 8,500 Minimum 1-23-81-1 1/2" x l-1/2" 13 0.1419 12,500 1-23-81-2 1/2" x 1-1/2" 13 0.1419 12,250 1-23-81-3 1/2" x l-1/2" 13 0.1419 12,300 1-23-81-4 1/2" x l-1/2" 13 0.1419 12,150 1-23-81-5 1/2" x 1-1/2" 13 0.1419 12,500 1-23-81-6 1/2" x l-1/2" 13 0.1419 12,250 l l-23-81-7 1/2" x l-1/2" 13 0.1419 12,100 l 1-23-81-8 1/2" x l-1/2" 13 0.1419 12,000 1-23-81-9 1/2" x l-1/2" 13 0.1419 12,500 1-23-81-10 1/2" x 1-1/2" 13 0.1419 12,650 1-23-81-11 1/2" x 1-1/2" 13 0.1419 12,150 1-23-81-12 1/2" x 1-1/2" 13 0.1419 12,300 A ( \
\, M age 1 of 11 ,
M .- ( l e Power Company stawba Nuclear Station LETCo. Job No. CHS 81-016 February 4, 1981 Page 2 of 11 MECHANICAL TENSION TEST Continued Ultimate LETCo. Bolt Size Threads Area Load 2 (Lbs) Piece No. (In) Per Inch (In ) 1-23-81-13 1/2" x l-1/2" 13 0.1419 12,700 1-23-81-14 1/2" x l-1/2" 13 0.1419 12,400 1-23-81-15 1/2" x l-1/2" 13 0.1419 12,650 1-23-81-16 1/2" x 1-1/2" 13 0.1419 , 12,450 1-23-81-17 1/2" x 1-1/2" 13 0.1419 12,400 1-23-81-18 1/2" x 1-1/2" 13 0.1419 12,500 1-23-81-19 1/2" x l-1/2" 13 0.1419 12,750 1-23-81-20 1/2" x 1-1/2" 13 0.1419 12,600 1-23-81-21 1/2" x 1-1/2" 13 0.1419 12,200 1-23-81-22 1/2" x 1-1/2" 13 0.1419 12,200 1-23-81-23 1/2" x l-1/2" 13 0.1419 12,350 g'"'}-23-81-24 1/2" x l-1/2" 13 0.1419 12,800
~23-81-25 1/2" x 1-1/2" 13 0.1419 12,350 % -I+23-81-25 1/2" x l-1/2" 13 0.1419 12,300 1-22-81-27 1/2" x l-1/2" 13 0.1419 12,450 1-23-81-28 1/2" x l-1/2" 13 0.1419 12,650 1-23-81-29 1/2" x l-1/2" 13 0.1419 12,800 1-23-81-30 1/2" x l-1/2" 13 0.1419 12,150 1-23-81-31 1/2" x l-1/2" 13 0.1419 12,850 1-23-81-3? 1/2" x l-1/2" 13 0.1419 12,550 1-23-81-33 1/2" x 1-1/2" 13 0.1419 12,600 1-23-81-34 1/2" x l-1/2" 13 0.1419 12,100 1-23-81-35 1/2" x l-1/2" 13 0.1419 12,550 1-23-81 1/2" x l-1/2" 13 0.1419 12,450 1-23-81-37 1/2" x l-1/2" 13 0.1419 12,200 1-23-81-38 1/2" x l-1/2" 13 0.1419 12,150 1-23-81-39 1/2" x l-1/2" 13 0.1419 12,750 l 1-23-81-40 1/2" x l-1/2" 13 0.1419 12,100 1-23-81-41 1/2" x l-1/2" 13 0.1419 12,650 l
l 1-23-81-42 1/2" x 1-1/2" 13 0.1419 12,400 1-23-81-43 1/2" x 1-1/2" 13 0.1419 12,700 1-23-81-44 1/2" x 1-1/2" 13 0.1419 12,100 l 1-23-81-45 1/2" x 1-1/2" 13 0.1419 .12,200 Minimum 8,500 I V uw eeomanNo Ttstno cower
M
- W. '
( (
) huke Power Company Catawba Nuclear Station LETCo. Job No. CHS 81-016 February 4, 1981 Page 3 of 11 4 MECHANICAL TENSION TEST Continued Ultimate LETCo. Bolt Size Threads Area Load Piece No. (In) Per Inch (In 2) (Lbs) 1-23-81-1 1/2" x 1-3/4" 13 0.1419 11,700 1-23-81-2 1/2" x l-3/4" 13 0.1419 12,050 1-23-81-3 1/2" x 1-3/4" 13 0.1419 12,300 1-23-81-4 1/2" x l-3/4" 13 0.1419
- 12,100 1-23-81-5 1/2" x 1-3/4" 13 0.1419 11,750 1-23-81-6 1/2" x l-3/4" 13 0.1419 11,650 1-23-81-7 1/2" x l-3/4" 13 0.1419 11,700 1-23-81-8 1/2" x 1-3/4" '13 0.1419 12,300 1-23-81-9 1/2" x l-3/4" 13 0.1419 11,700 1-23-81-10 1/2" x 1-3/4" 13 0.1419 12,250 3
1-23-81-11 1/2" x 1-3/4" 13 0.1419 12,200 l 81-12 1/2" x l-3/4" 12 0.1419 11,550 l 23-81-13 1/2" x l-3/4" 13 0.1419 12,300
.l 1-23-81-14 1/2 x l-3/4" 13 0.1419 12,100 1-23-el-15 1/2" x 1-3/4" 13 0.1419 10,400 1-23-81-16 1/2" x l-3/4" 13 0.1419 11,650 1 0.1419 1-23-81-17 1/2" x 1-3/4" 13 11,550 ,
l-23-81-18 1/2" x 1-3/4" 13 0.1419 10,550 1-23-81-19 1/2" x l-3/4" 13 0.1419 11,703 , 1-23-81-20 1/2 x l-3/4" 13 0.1419 11,700 1-23-81-21 1/3" :: 1-3/4" 13 0.1419 12,200 l 1-23-81-22 1/2" x l-3/4" 13 0.1419 11,750 l 1-23-81-23 1/2" x 1-3/4" 13 0.1419 11,700 i 1-23-81-24. 1/2" x l-3/4" 13 0.1419 11,650 1-23-81-25 1/2" x 1-3/4" 13 0.1419 11,600 1-23-81-26 1/2" x l-3/4" 13 0.1419 10,700 Minimum 8,500 1 LM ENGPEERING TESTNG CCNRWf
- 1 .e
( ( \ e Power Company tawba Nuclear Station LETCo. Job No. CHS 81-016 February 4, 1981 Page 4 of 11 MECHANICAL TENSION TEST Continued Ultimate LETCo. Bolt Size Threads Area Load Piece No. (In) Per Inch (In2) (Lbs) 1-23-81-1 1/2" x 2" 13 0.1419 11,950 1-23-81-2 1/2" x 2" 13 0.1419 11,200 1-23-81-3 1/2" x 2" 13 0.1419 11,650 1-23-81-4 1/2" x 2" 13 0.1419 11,600 1-23-81-5 1/2" x 2" 13 0.1419 11,800 1-23-81-6 1/2" x 2" 13 0.1419 11,450 1-23-81-7 1/2" x 2" 13 0.1419 11,600 1-23-81-8 1/2" x 2" 13 0.1419 11,600 1-23-81-9 1/2" x 2" 13 0.1419 11,700 1-23-81-10 1/2" x 2" 13 0.1419 11,650 g 1-23-81-11 1/2" x 2" 13 0.1419 11,550
%)-23-S1-17 1/2" x 2" 13 0.1419 11,750 . ' 23-81-13 1/2" x 2" 13 0.1419 11,750 's - 21-14 1/2" x 2" 13 0.1419 11,550 f 3-23-81-15 1/2" x 2" 13 0.1419 11,700 ^j 1-23-81-16 1/2" x 2" 13 0.1419 11,650 1-23-81-17 1/2" x 2" 13 0.1419 11,750 1-23-81-18 1/2" x 2" 13 0.1419 11,600 1-23-81-19 1/2" x 2" 13 0.1419 11,450 1-23-81-20 1/2" x 2" 13 0.1419 11,150 1-23-81-21 1/2" x 2" 13 0.1419 11,650 1-23-81-22 1/2" x 2" 13 0.1419 11,750 1-23-81-23 1/2" x 2" 13 0.1419 11,600 1-23-81-24 1/2" x 2" 13 0.1419 11,500 1-23-01-25 1/2" x 2" 13 0.1419 11,700 Minumum 8,500 g %sl l
UW ENGEMNG TESTPC CCNNtr [
. , . ' . ' w= = ; 1 Power Company i /'~
( ')1wba Nuclear Station fMCo. Job No. CHS 81-016 Fcbruary 4, 1981 PI9a 5 of 11 , MECHANICAL TENSION TEST
- Continued Ultimate Area Load Bolt Size Threads 2 (Lbs)
LETCo. Per Inch (In ) Picce No. (In) 0.1419 13,600 13 12,000 1-23-81-1 1/2" x 2-1/4" 13 0.1419 1/2" x 2-1/4" 0.1419 13,500 1-23-81-2 13 1-23-81-3 1/2" x 2-1/4" .13 0.3419 13,400 1-23-81-4 1/2" x 2-1/4" 13 0.1419 13,650 1/2" x 2-1/4" 12,850 1-23-81-5 13 0.1419 1/2" x 2-1/4" 13,650 1-23-81-6 13 0.1419 1/2" x 2-1/4" 13,450 1-23-81-7 13 0.1419 1/2" x 2-1/4" 13,450 1-23-81-8 13 0.1419 1/2" x 2-1/4" 12,950 1-23-61-9 13 0.1419 1/2" x 2-1/4" 0.1419 13,700 1-23-81-10 13 14,000 1-23-81-11 1/2" x 2-1/4" 0.1419 13
-A-23-81-12 1/2" x 2-1/4" 13 0.1419 13,750 1/2" x 2-1/4" 0.34)o 33 400 I )23-81-13 (x__d23-01-14 1/2" x 2-1/4" 13 13,600 13 0.1419 1/2" x 2-1/4" 13,450 1-23-81-15 13 0.1419 1-23-81-16 1/2" x 2-1/4" 13 0.1419 13,500 1/2" x 2-1/4" 13,450 1-23-81-17 13 0.1419 1-23-81-18 1/2" x 2-1/4* 0.1419 33,200 13 13,950 3-23-81-19 1/2" x 2-1/4" 13 C.1419 1/2" x ?-1/4" 13,250 1-23-81-20 13 0.1419 13,600 1-23-81-21 1/2" x 2-1/4" 0.1419 13 13,600 1-23-81-22 1/2" x 2-1/4" 13 0.1419 1/2" x 2-1/4" 13,500 1-23-81-23 13 0.1419 13,450 1-23-81-24 1/2" x 2-1/4" 0.1419 13 1-23-81-25 1/2" x 2-1/4" 8,500 Minimum l I l LM ENGNEERNG TESTNG CCNFnt#
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l Juke Power Company l batawba Nuclear Station LETCo. Job No. CHS 81-016 February 4, 1981 Page 6 of 11 l I MECHANICAL TENSION TEST Continued
- Ultimate ;
LETCo. Bolt Size Threads Area Load Piece No. (In) Per Inch (In 2) (Lbs) 1-23-81-1 1/2" x 2-1/2" 13 0.1419 12,450 1-23-81-2 1/2" x 2-1/2" 13 0.1419 12,550 1-23-81-3 1/2" x 2-1/2" 13 0.1419 12,450 1-23-81-4 1/2" x 2-1/2" _13 0.1419 12,600 1-23-81-5 1/2" x 2-1/2" 13 0.1419 12,400 1-23-81-6 1/2" x 2-1/2" 13 0.1419 12,550 1-23-81-7 1/2" x 2-1/2" 13 0.1419 12,600 1-23-81-8 1/2" x 2-1/2" 13 0.1419 12,550 1-23-81-9 1/2" x 2-1/2" 13 0.1419 12,600 1-23-91-10 1/2" x 2-1/2" 13 0.1419 12,700 , 1-23-81-11 1/2" x 2-1/2" 13 0.1419 12,600 1/2" x 2-1/2" 13 0.1419 12,550
, ~s i-23-31-12 3-23-81-13 1/2* x 2-1/2* 13 0.1419 12,500
(' s,jl-23-81-14 1/2" x 2-1/2" 13 0.1419 12,450 1-23-81-15 1/2" x 2-1/2" 13 0.1419 12,550 l 1-23-61-16 1/2" x 2-1/2" 13 0.1419 12,600 1-23-81-17 1/2" x 2-1/2" 13 0.1419 12,600 l l-23-81-19 1/2" x 2-1/2" 13 0.1419 12,350 1-23-81-19 J/2" x 2-1/2" 13 0.1419 12,350 1-23-81-20 1/2' x 2-1/2" 13 0.1419 12,650 1-23-81-21 1/2" x 2-1/2" 13 0.1419 12,450 1-23-81-22 1/2" x 2-1/2" 13 0.1419 12,550 1-23-81-23 1/2" x 2-1/2" 13 0.1419 12,450 1-23-81-24 1/2" x 2-1/2" 13 0.1419 12,700 1-23-81-25 1/2" x 2-1/2" 13 0.1419 12,650 1-23-81-26 1/2" x 2-1/2" 13 0.1419 12.550 l l-23-81-27 1/2" x 2-1/2" 13 0.1419 12,300 1-23-B1-28 1/2" x 2-1/2" 13 0.1419 12,550 1-23-81-29 1/2" x 2-1/2" 13 0.1419 12,350 1-23-81-30 1/2" x 2-1/2" 13 0.1419 12,450 1-23-81-31 1/2" x 2-1/2" 13 0.1419 12,500 1-23-81-32 1/2" x 2-1/2" 13 0.1419 12,400 1-23-81-33 1/2" x 2-1/2" 13 0.1419 12,350 1-23-81-34 1/2" x 2-1/2" 13 0.1419 12,450 l 1-23-81-35 1/2" x 2-1/2" 13 0.1419 12,500 1-23-81-36 1/2" x 2-1/2" 13 0.1419 12,350 1-23-81-37 1/2" x 2-1/2" 13 0.1419 12,450 l Il-23-81-38 1/2" x 2-1/2" 13 0.1419 12,350 LAv ENGNEERNG TESTNG CCMAWT
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Suke Power C5mpany l l batawba Nuclear Station LETCo. Job No. CHS 81-016 February 4, 1981 Page 7 of 11 MECHANICAL TENSION TEST Continued Ultimate LETCo. Bolt Size Threads Area Load 2 (Lbs) Piece No. (In) Per Inch (In ) 1-23-81-39 1/2" x 2-1/2" 13 0.1419 12,300 1-23-81-40 1/2" x 2-1/2" 13 0.1419 12,250 1-23-81-41 1/2" x 2-1/2" 13 0.1419 12,500 1-23-81-42 1/2" x 2-1/2" .13 0.1419 12,450 1-23-81-43 1/2" x 2-1/2" 13 0.1419 - 12,450 1-23-81-44 1/2" x 2-1/2" 13 0.1419 12,500 1-23-81-45 1/2" x 2-1/2" 13 0.1419 12,300 1-23-81-46 1/2" x 2-1/2" 13 0.1419 12,500 1-23-81-47 1/2" x 2-1/2" 13 0.1419 12,600 1-23-81-48 1/2" x 2-1/2" 13 C.1429 12,400 1-23-81-49 1/2" x 2-1/2" 13 0.1419 12,450 1-23-01-50 1/2" .x 2-A/2" 13 0.1419 12,450
/' 'l-23-81-51 1/2" x 2-1/2" 13 0.1419 12,200
( ,3-?3-91-5? 1/2" x 2-1/2' 13 0,1419 12,500 1-23-81-53 1/2" x 2-1/2" 13 0.1419 12,500 j 1-23-81-54 1/2" x 2-1/2" 13 0.1419 12,450 1-23-81-55 1/2" x 2-1/2" 13 0.1419 12,550 1-23-81-56 1/2" x 7-3/2" 13 0.1419 12,650 i 1-23-81-57 1/2" x 2-1/2" 13 0.1419 12,600
, 1-23-81-58 1/2' x 2-1/2" 13 0.1419 12,500 Minimum 8,500 / } \ / 'v LM ENGNEER!NG TESTNG CCNRWf
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( y e Power Company tswba Nuclear Station LETCo. Job No. CHS 81-016 February 4, 1981 Page 8 of 11 MECHANICAL TENSION TEST Continued Ultimate LETCo. Bolt Size Threads Area Load 2 (Lbs) Piece No. (In) Per Inch (In ) 1-23-81-1 3/8" x 1" 16 0.0775 5,650 1-23-81-2 3/8" x 1" 16 0.0775 5,700 1-23-81-3 3/8" x 1" 16 0.0775 5,500 1-23-81-4 3/8" x 1" 16 0.0775 5,500 1-23-81-5 3/8" x 1" 16 0.0775 5,550 1-23-81-6 3/8" x 1" 16 0.0775 5,600 1-23-81-7 3/8" x 1" 16 0.0775 5,400 1-23-81-8 3/8" x 1" 16 0.0775 5,500 1-23-81-9 3/8" x 1" 16 0.0775 5,650 1-23-81-10 3/8" x 1" 16 0.0775 5,250 l 1-23-81-11 3/8" x 1" 16 0.0775 5,700 3/G" x 1" 10 0.0775 5,700 [}-23-81-12 j-23-81-13 3/C" x 1" 16 0.0775 5,500 s
' 'l-23-81-14 3/8" x 1" 16 0.0775 5,650 1-23-81-15 3/8" x 1" 16 0.0775 5,500 1-23-81-16 3/8" x 1" 16 0.0775 5,750 1-23-91-17 3/8" x 1" 16 0.0775 5,600 1-23-81-18 3/8" x la 16 0.0775 5,550 1-23-81-19 3/8" x 1" 16 0.07.75 5,700 1-23-81-20 3/8" x 1" 16 0.0775 5,450 1-22-81-21 3/8" x 1" 16 0.0775 5,650 1-23-81-22 3/8" x 1" 16 0.0775 5,750 1-23-81-23 3/8" x 1" 16 0.0775 5,600 1-23-81-24 3/8" x 1" 16 0.0775 5,650 1-23-81-25 3/8" x 1" 16 0.0775 5.550 1-23-81-26 3/8" x 1" 16 0.0775 5,550 1-23-81-27 3/8" x 1" 16 0.0775 5,650 1-23-81-28 3/8" x 1" 16 0.0775 5,650 1-23-81-29 3/8" x 1" 16 0.0775 5,550 l
1-23-81-30 3/8" x 1" 16 0.0775 5,750 1-23-81-31 3/8" x 1" 16 0.0775 5,400 1-23-81-32 3/8" x 1" 16 0.0775 5,600 Minimum 4,650 1
/O V
LAW ENGNEERNG TESTNG CCNAWr l l
0 r ( 1 l Mke Power Ccxnpany l batawba Nuclear Station LETCo. Job No. CHS 81-016 February 4, 1981 f 1 Page 9 of ,1 ! MECHANICAL TENSION TEST Continued Ultimate LETCo. Bolt Size Threads Area Load Piece No. (In) Per Inch (In 2) (Lbs) 1-23-81-1 3/8" x l-1/4" 16 0.0775 7,600 1-23-81-2 3/8" x l-1/4" 16 0.0775 7,400 1-23-81-3 3/8" x l-1/4" 16 0.0775 7,350 1-23-81-4 3/8" x l-1/4" 16 0.0775 7,600 1-23-81-5 3/8" x l-1/4" 16 0.0775 7,300 1-23-81-6 3/8" x 1-1/4" 16 0.0775 7,350 1-23-81-7 3/8" x l-1/4" 16 0.0775 7,750 1-23-81-8 3/8" x 1-1/4" 16 0.0775 7,650 1-23-81-9 3/8" x l-1/4" 16 0.0775 7,250 1-23-81-10 3/8" x l-1/4" 16 0.0775 7,350 1-23-81-11 3/8" x l-1/4" 16 0.0775 7,650 i 1-23-81-12 3/8" x l-1/4" 16 0.0775 7,650 i 1-23-81-13 3/8" x l-1/4" 16 0.0775 7,750 k k-23-81-14 3/8" x l-1/4" 16 0.0775 7,750 1-23-81-15 3/8" x l-1/4" 16 0.0775 7,300 1-23-81-16 3/8" x l-1/4" 15 0.0775 7,650 1-23-81-17 3/8" x l-1/4" 16 0.0775 7,550 1-23-81-18 3/8" x 1-1/4" 16 0.0775 7,650 1-23-81-19 3/8" x l-1/4" 16 0.0775 7,250 1-23-81-20 3/S" x l-1/4" 16 0.0775 7,200 1-23-81-21 3/8" x l-1/4" 16 0.0775 7,100 1-23-81-22 3/8" x l-1/4" 16 0.0775 7,750 1-23-81-23 3/8" x 1-1/4" 16 0.0775 7,350 1-23-81-24 3/8" x l-1/4" 16 0.0775- 7,400 1-23-81-25 3/8" x 1-1/4" 16 0.0775 7,750 1-23-81-26 3/8" x 1-1/4" 16 0.0775 7,700 1-23-81-27 3/8" x l-1/4" 16 0.0775 7,300 1-23-81-28 3/8" x 1-1/4" 16 0.0775 7,250 1-23-81-29 3/8" x l-1/4" 16 0.0775 7,250 1-23-81-30 3/8" x l-1/4" 16 0.0775 7,300 1-23-81-31 3/8" x l-1/4" 16 0.0775 7,500 1-23-81-32 3/8" x l-1/4" 16 0.0775 7,600 Minimum 4,650 i LAW Dr.NEERNG TESTNG CCNPA,Yf
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Duke Power Company j atawba Nuclear Station LETCo. Job No. CHS 81-016 February 4,1981 Page 10 of 11 MECHANICAL TENSION TEST Continued Ultimate IErCo. Bolt Size Threads Area Load Piece No. (In) Per Inch (In 2) (Lbs) 1-23-81-1 3/8" x 1-1/2" 16 0.0775 5,750 1-23-81-2 3/8" x 1-1/2" 16 0.0775 6,100 1-23-81-3 3/8" x 1-1/2" 16 0.0775 5,900 1-23-81-4 3/8" x l-1/2" 16 0.0775 5,700 1-23-81-5 3/8" x 1-1/2" 16 0.0775 - 6,300 1-23-81-6 3/8" x l-1/2" 16 0.0775 6,350 1-23-81-7 3/8" x l-1/2" 16 0.0775 6,450 1-23-81-8 3/8" x 1-1/2" 16 0.0775 6,050 1-23-81-9 3/8" x 1-1/2" 16 0.0775 6,100 1-23-81-10 3/8" x l-1/2" 16 0.0775 5,850 1-23-81-11 3/8" x 1-1/2" 16 0.0775 5,800 ' 1-23-81-12 3/8" x 1-1/2" 16 0.0775 6,300 81-13 3/8" x 1-1/2" 16 0.0775 5,800 d 81-14 3/8" x 1-1/2" 16 0.0775 5,900 1-23-81-15 3/8" x l-1/2" 16 0.0775 6,000 I l-27-01-16 3/8" x l-1/2" 16 0.0775 6,300 1-23-81-17 3/8" x 1-1/2" 16 0.0775 6,300 1-23-81-18 3/8" x l-1/2" 16 0.0775 5,850 1-23-81-19 3/8" x 1-1/2" 16 0.0775 5,800 1-23-81-20 3/8" x l-1/2" 16 0.0775 6,000 l 1-23-81-21 3/8" x 1-1/2" 16 0.0775 5,900 1-23-81 *c2 3/8" x l-1/2" 16 0.0775 6,250 1-23-81-23 3/8" x 1-1/2" 16 0.0775 5,950 1-23-81-24 3/8" x 1-1/2" 16 0.0775 6,350 1-23-81-25' 3/8" x 1-1/2" 16 0.0775 6,000 1-23-81-26 3/8" x 1-1/2" 16 0.0775 6,100 1-23-81-27 3/8" x l-1/2" 16 0.0775 5,900 7 1-23-81-28 3/8" x 1-1/2" 16 0.0775 5,800 l l-23-81-29 3/8" x l-1/2" 16 0.0775 6,650 l 1-23-81-30 3/8" x l-1/2" 16 0.0775 5,950 1-23-81-31 3/8" x l-1/2" 16 0.0775 6,300 1-23-81-32 3/8" x 1-1/2" 16 0.0775 6,000 Minimum 4,650
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( - WE HHRf G Duke Power Company Catawba Nuclear Station IETCo. Job No. CHS 81-016 February 4, 1981 Page 11 of 11
- P MECHANICAL TENSION TEST Continued LETCo.
Piece No. Bolt Size Ultimate _ (In) Threads Area Per Inch Icad 1-23-81-1 _In2) ( (Lbs) 1-23-81-2 3/8" x 2-1/2" 16 1-23-81-3 3/8" x 2-1/2" 16 0.0775 7,100 1-23-81-4 3/8" x 2-1/2" 16 0.0775 6,900 1-23-81-5 3/8" x 2-1/2" 16 0.0775 7,100 1-23-81-6 3/8" x 2-1/2" 16 0.0775 7,750 1-23-81-7 3/8" x 2-1/2" 16 0.0775 7,600 1-23-81-8 3/8" x 2-1/2" 16 0.0775 7,500 1-23-81-9 3/8" x 2-1/2" 16 0.0775 7,500 1-23-81-10 3/8" x 2-1/2" 16 0.0775 7,500 1-23-81-11 3/8" x 2-1/2" 16 0.0775 7,100 1-23-81-32 3/8" x 2-1/2" 16 0.0775 7,600 i 1-23-81-11 3/6" x 2-1/2" 16 0.0775 7,050 ( I 1-23-81-14 3/8" x 2-1/2* 16 0.0775 7,500 i 1-23-61-15 3/8" x 2-1/2" 16 0.0775 7,100 1-23-81-16 3/8" x 2-1/2" 16 0.0775 6,900 1-23-81-17 3/8" x 2-1/2" 16 0.0775 7,600 1-23-81-18 3/8" x 2-1/2" 16 0.0775 7.250 i! 1-23-81-19 3/8" x 2-1/2" 16 0.0775 6,800 1-23-81-20 3/8" x 2-1/2" 16 0.0775 7,300 1-23-81-21 3/8" x 2-1/2" 16 0.0775 7,500 1-23-81-22 3/8" x 2- 1/2" 16 0.0775 7,490 1-23-81-23 3/8" x 2-1/2" 16 0.0775 7,350 1-23-81-24 3/8" x 2-1/2" 16 0.0775 7,000 1-23-81-25 3/3" x 2-1/2" 16 0.0775 6,800 1-23-81-26 3/8" x 2-1/2" 16 0.0775 7,550 1-23-81-27 3/8" x 2-1/2" 16 0.0775 7,450 1-23-81-28 3/8" x 2-1/2" 16 0.0775 7,450 i 1-23-81-29 3/8" x 2-1/2" 16 0.0775 6,850 i 1-23-81-30 3/8" x 2-1/2" 16 0.0775 7,250 1-23-81-31 3/8" x 2-1/2" 16 0.0775 7,600 1-23-81-32 3/8" x 2-1/2" 16 0.0775 7,450 Minimum 3/8" x 2-1/2" 16 0.0775 7,450 0.0775 7,350 Inspector (s): grr le 4,650 Reviewed by: Respectfully Submitted, tyd (n) Edward M. Beck. P.E. Metals Department Man.ger LAW ENGINEERING TESTING CO 3 [ - -umpie. ue .., c.oo,.1 ,, 5.Pe,,,,o, _ _ _ , = -
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501 WINUET LAN geoxg7.E csAmtoTTE. NoaTH cAnouNA rs22o Q' l 1 REPORT OF CHEMICAL ANALYSIS Client: DUKE POWER COMPANY ortjee: Charlotte Metals Project: CATAWDA NUCLEAR STATION Date: February 9,1981 Newport, South Carolina Lab. No. CHS 81-016 Client P. O. No.: G2494-41 Material: Reported as Carben Steel Externally Threaded Standard Fastener ASTM A.307 (See Below) Grade A Hast No.: Unknown Data Tested: 2/9/81 Procedure: In accordance with ASTM A 307 78, ASTM A 36 77, and ASTM E 30-77
- TEST RESULTS
- LET Co. .
Elementi Pi+:e No. _C.n)1n Manaanese Phaohpw1. .5_t18ti. . .Sijiten Sire l { 0.02 x 15/16"
- - 0.13 0.40 0.02 0.18 1/2" l
q j 8159 81 9 0.15 0.51 0.01 0.01 0.16 1/2" x 1 3/16" 1!23 81-46 0.15 0.49 0.02 0.02 0.23 1/2" r 11/2" 1-23 3t.27 0.16 0.50 0.02 0.02 0.15 1/2" x l-3/4" 1 23-81-R 0.15 0.33 0.02 0.02 0.15 1/2" 'x 2" 1-23-81-26 0.15 0.4A 0.0 ' O.02 0.15 1/2" x 21/4" 1233158 0.16 C.37 0.01 0.01 0.16 1/2" x 21/2" l 23 81 32 0.12 0.29 0.01 0.01 0.13 3/8" x 3/4" 1-23 81 33 0.18 0.38 0.02 0.02 0.22 3/8" x 1" 1 23-81 33 0.21 0.84 0.02 0.02 0.44 3/8" x 11/4" 1 23-81 33 0.18 0.36 0.02 0.02 0.12 3/8" x 11/2" 1238133 0.16 0.36 0.02 0.01 0.14 3/8" x 21/2" Required A.307 -- 0.06 0.15 Required A-36 0.26
- 0.04 0.05 0.15 to 0.30 Ncter The single values are the maximum allowed in the required section.
Item 123 8133, 3/8" x 11/4" exceeds the maximum of silicon per basic material specification. Inspector (s): Larry e
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Reviewed by: Edward M. Beck, P. E. Corporate Consultant / Metals
& Respectfully submitted, .
LAW ENGINEERING TESTING COMPANY [ ] L.arry Die, Metals L.aooratory supervisor
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1.0 TITLE
Procedure for Corrective Action for Electric Penetrations which have a Marginal or Possibly Unacceptable SF Leak 6 Rate (Types A through M)
2.0 PURPOSE
To specify courses of action for Electric Penetrations which have a questionable leak rate due to low SF6 pressure readings.
3.0 SCOPE
This specification applies to Electrical Penetration Types A-M installed at Catawba Nuclear Station.
4.0 REFERENCES
4.1 CNM1361.00-6 Sh. 1 (D.G. O'Brien No. R31E5046 Sh. 1) Low Voltage Power Electric Penetration Installat ion Drawing 4.2 CNM1361.00-7 Sh. 1 (D.G. O'Brien No R31E5047 Sh. 1) Instrumentation and Control Electric Penetration Installation Drawing 4.3 CNM1361.00-8 Sh. 1 (D.G. O'Brien No. R31E5048 Sh. 1) Medium voltage Power Electric Penetrations, i 5,0 Test Equipment / Tools: 5.1 A bottle of comercial grade SF6 which has been designated for Electrical Penetration use. 5.2 Regulator, hoses or piping, and fittings to attach SF 6 bottle to , g penetration under test. 5.3 Wrenches as retilred for above. 5.4 Bottle of soap solution which may be obtained from the NDE office. 6.0 LIMITATIONS AND PRECAUTIONS: 6.1 Do not over torque the fill valve. It is fully closed when shut finger tight. I 6.2 To prevent air from 1:elng injected into pen'etrat!on. p 6.2.1 Loosely connect SF6 source to the penetration but 00 LOT open the penetration fill valve. 6.2.2 Crack open SF6 bottle supply or regulator valve and flush the fill line with SF 6' 6.2 3 Tighten all fill connections and then shut off SF6 supply or regulator valve. 6.3 Do not allow soap solution to get into the ends of the conne: tor modules and clean up all soap solution af ter using. TITLti Procedure for Corrective Action for Electric '*8/8'"""'"" Penetrations Which have a Marginal or Possibly Unacceptable Cks-1390.01-00-00 SF6 Leak Rate (Tvoes A throuah M1 ne..s.en noi o Lete' March 8, 1979 P/M /P1 "' I O f 3
( M TI~AC MM EA.J T' TD i *
.0 PROCEDURE: N ~
7.1 Pressurize the penetration assembly to 17 psig with the commercial
,' mh grade SFg specified in Section 5.0 while heeding the precautions in *
( ,/ Section 5, 7.2 Close the fill valve and remove the source of SF6 ' i , ', # ' 7.3 Using a soap solution check all fittings and welds on the pressure gauge assembly and tubing. DO NOT ALLOW SOAP SOLUTION TO GET INTO MODULE , CONNECTOR ENDS. 7.4 If a leak is found at a weld joint then a non-conforming item report should be issued. (" 7.5 If a leak Is found at the end of the fill connection then tighten the '* [3 fili valve. ,
'i NOTE '
i THl$ VALVE 15 FULLY CLOSED WHEN SHUT FINGER TIGHT. / , t ,3 , 7.5.1 If the leak has stopped: ' i\'[ J>s 7.5.1.1 Decrease the pressure to 15 psig; record the pressure. flange temperature and barometric pressure, I, s . 7.5.1.2 wait at least two (2) days minimum [three (3) days maximum) p) and record the flange tempcrature and pressure and barome.ric; \, ( V
- pressure. ., 'y;
- a. If there is no indication of pressure loss when '
H corrected for temperature and barometric pressure ' A ,i changes, then the penetration is acceptable for use, c gs,
- b. If there is an Indication of pressure loss when l 't corrected for temperature and barometric then a / ~, t
\
non-conforming item report should be issued. '( ' 7.5.2 If the leak has not stopped, the valve may be faulty and a 3,,) non-conforming item report should be issued. 's / . ( 7.6 If a leak is found in the valve body or at the valve sten a non- - I conforming Item report should be issued. ' l['
,it 7.7 If a leak is found where the pressure gauge screws into the mounting \; ,
assembly. ) 7.7.1 Decrease pressure to 3 psig, remove pressure gauge, wrap ga,uge (.' 6 3. threads with teflon tape, and re-insert gauge. s ', 1 NOTE Y-(,, THE PRECEDING STEP HUST BE DONE EXPEDITIOUSLY. k l, i , ,
) 7.7.2 Re-pressurize the unit to 17 psIg and repeat the bubble check ~
(
'}
of the p uge connection. , il\ TiTLEi Procedure for Corrective Action for Electric Penetrations Which have a Marginal or Possibly Unacceptable Mees /So"'bcohn Noi h SF6 Leak Rate (Types A through M) CNS-1390.01 00 00 '
/N_ 2 of 1 '
y.
'f.,**,f b ATTW ma,d to Y' NCZY ,e t' T, , / n Q. S (e ()
y' 8 i 7.7.2yt i
; if no furthere?caks are observed then decrease the a i. r pressureto/9psig,recordpressure,flangetempera- . , turetand barot.etric pressure and monitor for at least twoN2)' days.f k'fg' [V f{
l r
- a. fft,her'[sisno(.n,(cationofpressurelosswhen
/ ' \i ),
( ~)co hennctedthe. penetfor te.npe+ature ra t ion .'is acceptable and barometric for use. pressure, Y e., ) # 'f,. ,
- b. Iffthegaugefittingstill leaks repeat 7.7.
#( of f no leaks are pxnd by bubble check: }h t \ ' ',s 7, . I Pressociz4 (n? penetration to 17 psig with cornmercial grade SF 6 yi\ specifieds'n
(< ' Section 6p' ,.:/ection 5.0 while ' i \ hee.fing the precautions in J'i i, <
,1. 7.8.2 t !9ecrease the pr*/ssure to 15 ps hg/ record pressure, flange tempera ture and barometric pressure. V V' } ,
t i l Y ,*' M.3 kaf two (2) days minimum (three (3) days maximum) and record the
/ lI t flange temerature, pressure and tarometric pressure.
[ h 7.8.3.1 ff thEre,Is no Indicatio, of pressure loss when corrected ( > f for temperature and barometric pressure changes, then the ( ,l 's- per.etration is acceptabli for use. t' , l{' ilf 7.8.3.2 'If there is still Indication of pressure loss when corrected
/- ,3 f at,above, then contact,0esign Engineering for further instruc- / , ij tions or fisposition.
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CONSTRUCTICN dea'A.TTMINT PRC.!ECT catavba . I ) QU ALITY ASSUR ANCE TRAINING RECORD
,1, / 9 /79. . . . THis is To CIRTIFY THAT' THE CUALITY AESURANCE InAt::tNG was HELD .... cN CC.'T A i-:EE7' OA ASME Pn00E0VRE R E Y. .
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Yi - ( f .. [ 4496 - g o. J TS '/2" dia eter bits u;;d 'n the m ! ear ce#ety
- elated cable tray cupp;r' -
stems are to be equivalent in strength to ASTM A-307 bolts. All appr ate de ~ n drawings have been revised to indicate this. To verify t all 1/2" diameter bolts used meet this stre requirement, a random samp f each bolt size shall be secured by struction from those bolts which are no 'dentified by appropriate mar s. The sample sizes shall be in accordance with ' Logan's attached let of 3/29/79. These samples shall then be tested in accordan ith C L Ray' ttached test procedure of 3/20/79. The results of this testing progr all be sent to Design Engineering / Electrical Division for dete ' ation o cceptability.
- 19. By: ate: 9///h9
/'/
- 20. Techn' Approval: . _
Date:
, . I.f . - provo..
Datp- , - ,# )f
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k ' ' (, ( f , NCI 4496 - Revision 2
- 17. The b" diameter bolts used in the nuclear safety related cable tray support systems are to be equivalent in strength to ASTM A-307 bolts.
All appropriate design drawings have been revised to indicate this. To verify that all h" diameter bolts used meet this strength requirement, ; a random sample of each bolt size shall be secured by Construction from ; those bolts which are not identified by appropriate markings. The sample l sizes shall be in accordance with B W Logan's attached letter of 3/29/79. These samples shall then be sent to a qualified outside testing laboratory by the Construction Department, to be tested in accordance with ASTM A-307 requirements. The results of this testing program shall be sent to the Design Engineering Electrical Division for detennination of acceptability. In order to prevent reoccurance of this problem, several changes have been implemented. First, all appropriate design documents have been revised to specifically state the material / grade requirements for bolting materials. Second, the purchase Requisitions for all bolting materials are checked for the inclusion of applicable material / grade requirements. Third, Mill Power Supply has comitted that no vendor or material substitutions will be made without the prior approval of g p responsible Design Engineering personnel.
- 19. By: # ~- _ Date: /s/2yh
- 20. Tec ca App oval: Date: N
- 21. QA Approval: N Date: /2 Je
&e A4 . A, s., w ,.u.ii tV
March 29, 1979
}l{%
f O D G Owen
Subject:
Determination of Sample Size for Catawba Electrical Bolting Material Problem File: CN-1388.00 The testing of sample bolts to make an inference about the ability of an entire lot to meet tensile strength criteria is a two part statistical problem. The first part involves the determination of an appropriate sample size, and the second part is concerned with the acceptance or rejection of the lot based upon the results of the tests. The following procedure is proposed to 1) determine an appropriate sample size for each of the bolt lots in question, and 2) establish a criteria for accepting or rejecting the lot based upon the test results. In order to establish the procedure, the following asamptions must be made:
- 1) Since the number of bolt manufacturers represented in the questioned lots cannot be detennined, each lot shall be approached as an unknown quantity.
- 2) The bolts used at Catawba Nuclear Station are not significantly different from those used at McGuire Nuclear Station. This allows the use of McGuire g test results to estimate physical parameters which are needed to determine sample sizes. The Catawba test results will indicate the validity of this assumption.
- 3) The accuracy qf torque wrenches used to tighten bolts is 5% of the set value. This is used to determine the allowable error in measuring tensile strength. The test should not~ expect accuracy better than that of the wrenches used to tighten the bolts.
- 4) An acceptable confidence factor is 99% or roughly three standard deviations (3a) from the mean value.
Based upon these assumptions the following expression
- should be used to determine sample sizes
~ ~
35 2 n= 7 l where n is the number of samples, o is one standard deviation from the mean tensile l strength calculated from McGuire test results, and E is the allowable error in the-tensile strength measurement and is based on McGuire data. This expression means that if n samples are tested, there is better than a 99% chance the estimated tensile strength for the lot will lie within the allowable error limit.
' drom Introduction to Probability and Statistics, pp. 182, 197
~. - -
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., ( t REFERENCES
- 1. ASTM Standard A 307-76b, " Standard Specification for Carbon Steel Externally and Internally Threaded Standard Fasteners."
- 2. ASTM Standard E 122-72, " Standard Recommended Practice for Choice of Sample Size to Estimate the Average Quality of a Lot or Process."
- 3. William Mendenhall Introduction to Probability and Statistics, Duxbury Press, 1971.
- 4. McGuire NCI Report No. 4444.
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l/ _ CALCULATIONS For 99 confidence Bolt size o E n= h . N -n*" L N+n 1/2 X 15/16 1214 480 58 107,500 - 1/2 X 13/16 455 480 8 15,000 - 1/2 X 1 1/2 1214 545 45 51,000 - 1/2 X 1 3/4 1214 480 58 1 ,600 56 1/2 X 2 1214 480 58 1,000 55 1/2 X 2 1/4 1214 480 58 500 52 1/2 X 2 1/2 1214 480 58 10,000 - For 95% confidence Bolt Size o E n= h N ng=n N+n N
- 1/2 X 1 3/4 1214 480 26 1,600 -
1/2 X 2 1214- 480 26 1,000 25 1/2 X 2 1/4 1214 480 . 26 500 25
- ASTM Standard E 122-72, Section 5, p 1045 i
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q49b d f D G Owen i N March 29, 1979 - I
.Page 2 When a tested bolt size from McGuire closely corresponds to a questioned bolt size . from Catawba, the McGuire test data
- for that bolt size shall be used in calculating the Catawba sample size. When a Catawba bolt size does not correspond to a tested McGuire bolt size, the McGuire values which give the most conservative estimate of sample size, i.e., the largest observed standard deviation and the smallest l allowable error bound, shall be used in the sample size detennination, j The following table will sumarize the suggested sample sizes ** for each of the questioned bolt sizes:
Suggested Sample Size Confidence Bolt Size Quantity Issued 95% 99% 1/2" X 15/16" 107,500 - 58 1/2" X 1 3/16" 15,000 - 8 1/2" X 1 1/2" 51,000 - 45 1/2" X 1 3/4" 1,600 26 (56) 1/2" X 2" 1,000 25 (55) 1/2" X 2 1/4" 500 25 (52) 1/2" X 2 1/2" 10,000 For the 13/4, 2 and 21/4 inch bolts, a 95% confidence level is suggested to reduce the number of samples to a more realistic value. Also, the reason only eight samples were required of the 13/16 inch bolts is that the McGuire data for the 1 1/4 inch bolts displayed a fairlyJmall standard deviation. After testing the bolts from Catawba, a mean value for tensile strength and a standard deviation about the mean should be calculated for each bolt size. ASTM Standard A 307-76b sets the minimum acceptable tensile strength for Class A bolts at 8500 lbf. Acceptance or rejection of a bolt size lot should be detennined by the following procedure: 1
- 1) Calculate a mean and a standard deviation from test data l
- 2) Subtract 8500 from the mean value
- 3) Divide the result (from 2) by the calculated standard deviation
- 4) If this quotient is greater than 2, accept the lot. This gives 95%
confidence that the bolts in the lot have tensile strengths greater than the mean less 2o.
- 5) If the quotient is less than 2 a) reject' the lot or, b) repeat the test using the same sample size or, c) find the true percentage from a standard nonnal distribution table and For instance,1.645o give 90% confidence.
determine if it is acceptable.
- McGuire NCI Report No. 4444
** Calculations are attached.
i 1
i ,. ( (. It48tr ' ' ^ f) G Owen l l arch 29,1979
/ age 3 If you have questions or coments on the above procedures, please notify me.
- h. .
B W Logan l Assistant Design Engineer
- BWL/lge attachments i cc
- L E Suther B Garman C J Hager i
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'NCI 4496 - Addendum to Revision 2 ,
- 17. EVALUATION OF TEST RESULTS In order to complete the statistical process of determining whether or not the sample bolts meet the mechanical strength criteria of ASTM A-307 bolts, the attached test results for each of the samples must be evaluated according to the established acceptance procedure (See B W Logan's attached letter dated 3/29/79).
The evaluation of the test results for the 1/2" bolts is sumarized in Tables I and II. For the lot of 1/2" x 15/16" bolts, a Rockwell "B" hardness test determines whether the bolts conform to the mechanical requirements. As shown in Table I, the results indicate that the mean value is greater than two standard deviations from both the upper and lower limits of the hardness requirements. Therefore the respective sample of 1/2" x 15/16" bolts is acceptable to the standards of ASTM A-307 bolts. The remaining samples were tested in regards to their conformance to the mechanical tensile strength requirements. The evaluation of their test results is sumarized in Table II and indicates that the respective samples are also acceptable. In conclusion, the test results have determined that the subject bolts meet the mechanical requirements for ASTM A-307 bolts with a 95% confidence level.
- 19. By:
@<uda3 o
ld Vc.1.3,/ - , h Date: -3l& si
- 20. Technical Approval Date: / !
- 21. QA Approval N v42' Date: 3-23-A J
mm 6 n e o m . nn sa - ca -o s ,_an-~ <- - -
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~
O O O ~; ' STANDARD REQUIRED SAMPLE MEAN DEVIATION RANGE (13-[3) (4'l-fl) ACCEPTABLE BOLT SIZE SIZE (1) (2) [ i,2) I,2 J LOT? 1/2" x 15/16" 58 92.95 2.62 69 100 9.14 2.69 YES 7 TABLE I EVALUATION OF HARDNESS TEST RESULTS FOR 1/2" BOLTS STANDARD MIN TENSILE f SAMLE MEAN DEVIATION STRENGTH (LBS) (l'i-f 3) ACCEPTABLE BOLT SIZE SIZE (1) (2) (3) i;2) LOT ? I t i 1/2" x 1-3/16" 8 10825.00 738.24 8500. 3.15 YES 1/2" x 1-1/2" 45 12415.55 232.04 8500. 16.87 YES m 1/2" x 1-3/4" 26 11723.07 505.61 8500. 6.37 YES . 1/2" x 2" 25 11612.00 172.17 8500. 18.08 YES 1/2" x 2-1/4" 25 13436.00 392.51 8500. , 12.58 YES I. 1/2" x 2-1/2" 58 12484.48 111.29 8500. 35.80 YES - f E 7
- TABLE II e 4-EVALUATION OF TENSILE STRENGTH TEST RESULTS j
FOR 1/2" BOLTS i 5 .
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ROC WELL "B" HARDNESS INSPECTION REPORT OF i Client: Duke Power Company O Unce. Charlotte Metals Project: Catawba Noelcar Station Date: February 4, 1981 Newport, South Carolina CHS 81-016 Lab. No. Client's P. O. No.: G 2494-41 Material: Reported as Carbon Steel Externally Threaded Standard Tastner ASTM A307 (See Below) Grade A Heat No.. Unknown Date Tested: 2/2/81 Procedure: In accordaned with ASTM A307-78 and ASTM E18-79 E;**IPMENT CALIBRATION Average Calibration Reading Readings Reading Standard Corrcetion, % 84.1 81.6 97.0 87.3 81.6 93.5 ROClGELL "B" HARDNESS RESULTS t LETCo. Bolt Size Average Corrected Piece No. (In) Reading Reading Comments 1-23-81-1 1/2" x 15/16" 92.0 89 -- 1-23-81-2 1/2" x 15/16" 97.1 94 -- 1-23-81-3 1/2" x 15/16" 92.2 89 -- 1-23-81-4 1/2" x 15/16" 95.6 93 -- 1-23-81-5 1/2" x 15/16" 98.3 95 -- 1-23-81-6 1/2" x 15/16" 98.0 95 -- 1-23-81-7 1/2" x 15/16" 97.3 94 -- 1-23-81-8 1/2" x 15/16" 97.5 95 -- l 1-23-81-9 1/2" x 15/16" 99.2 96 -- 1-23-81-10 1/2" x 15/16" 98.0 95 -- 1-23-81-11 1/2" x 15/16" 99.0 95 -- 81-12 1/2" x 15/16" 98.3 94 -- j 81-13 1/2" x 15/16" 99.3 95 -- ( V A-23-81-14 1/2" x 15/16" 96.5 92 -- P qe 1 of 3 W
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\ l \ , ,le Power Company Catawba Nuclear Station 1.ETCo. Job No. CHS 81-016 February 4, 1981 P ge 2 of 3 ROCKWELL "B" HARDNESS RESULTS Continued Average Corrected ,
LETCo. Bolt Size Reading Reading __ Comments Piece No. (In) 97.8 93 1-23-81-15 1/2" x 15/16" 92 -- 1/2" x 15/16" 96.6 1-23-81-16 95.6 91 -- 1-23-81-17 1/2" x 15/16" 96 -- 1/2" x 15/16" 100.0 1-23-81-18 99.8 95 -- 1-23-81-19 1/2" x 15/16" 94 -- 1/2" x 15/16" 98.7 1-23-81-20 100.6 95 -- 1-23-81-21 1/2" x 15/16" 90 -- 1/2" x 15/16" 95.7 1-23-81-22 99.3 94 -- 1-23-81-23 1/2" x 15/16" 92 -- 1/2" x 15/16" 97.5 1-23-81-24 100.7 95 -- 1-23-81-25 1/2" x 15/16" 94 -- 1/2" x 15/16" 99.0
, s1-23-81-26 98.8 93 --
1-23-81-27 1/2" x 15/16" 95 -- 1/2" x 15/16" 100.2 s_l-23-81-28 99.7 94 -- 1-23-81-29 1/2" x 15/16" 95 -- 1/2" x 15/16" 100.0 1-23-81-30 98.2 93 -- 1-23-81-31 1/2" x 15/16" 97 1/2" x 15/16" 102.8 1-23-81-32 99.7 94 1-23-81-33 1/2" x 15/16" 91 1/2" x 15/16" 96.3 1-23-81-34 100.3 95 1-23-81-35 1/2" x 15/16" 92 1/2" x 15/16" 97.2 1-23-81-36 98.5 93 1-23-81-37 1/2" x 15/16" 90 1/2" x 15/16" 95.3 1-23-81-38 99.3 94 1-23-81-39 1/2" x 15/16" 94 1/2" x 15/16" 99.8 1-23-81-40 98.2 91 1-23-81-41 1/2" x 15/16" 92 1/2" x 15/16" 99.2 1-23-81-42 99.2 92 1-23-81-43 1/2" x 15/16" 94 1/2" x 15/16" 101.2 1-23-81-44 96.8 90 1-23-81-45 1/2" x 15/16" 91 1/2" x 15/16" 98.0 1-23-81-46 98.0 91 1-23-81-47 1/2" x 15/16" 90 1/2" x 15/16" 97.0 1-23-81-48 100.2 93 1-23-61-49 1/2" x 15/16" Lill ____ . - _ _ ___ l
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,d) e Power Company Catawba Nuclear Station LE7Co. Job No. CHS 81-016 February 4, 1981 P;ge 3 of 3 \
l ROCKWELL "B" HARDNESS RESULTS ) Continued i Average Corrected IrIto. Bolt Size Reading Reading Coments Piece No. (In) 100.0 93 1-23-81-50 1/2" x 15/16" 83 -- 1/2" x 15/16" 89.7 1-23-81-51 98.3 91 -- l 1-23-81-52 1/2" x 15/16" 94 -- l 1/2" x 15/16" 100.8 1-23-81-53 102.2 95 1-23-81-54 1/2" x 15/16" 84 -- 1/2" x 15/16" 90.8 1-23-81-55 102.7 96 -- 1-23-81-56 1/2" x 15/16" 94 --
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1/2" x 15/16" 101.0 1-23-81-57 102.5 95 -- 1-23-81-58 1/2" x 15/16" Re qu i r e d Ra ng e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 9 thr u 10 0 . . . . . . . . . . . c . Inspector: Richar . rris Reviewed by: Edward M. Beck, P. E. l Metals Department Manager Respectfully submitted, LAW ENGINEERING TESTING COMPANY l pr4-} f n oble, Metals Laboratory Supervisor Larry l l
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- REPORT OF MECHANICAL TENSION TEST harlotte &tals Duke Power Company Office:
Client: Date: February 4, 1981 ! Project: Catawb3 Nuclear Station Newport, South Carolina l Lab. No. CHS 81-016
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Client P. O. No.: C 2494-41 j Material: Reported as Carbon Steel Externally Threaded Standard 1 Tastener ASTM A307 (See Below) Grade A 1 Heat No.: Ur.known Date Tested: 2/3/81 Procedure: In accordance with ASTM A307-78 and ASTM A370-77 TEST RES"LTS_ f% Threads Area Ulti: tate lead Bolt Size k' LETCc. Piece No. (In) Per Inch _ _ (In ) 2 (Lbs) 10,900 13 0.1419 1-23-81-1 1/2" x 1-3/16" 0.1419 10,550 13 1-23-81-2 1/2" x 1-3/16" 13 0.1419 10,400 1-23-81-3 1/2" x 1-3/16" 13 0.1419 12,400 1-23-81-4 1/2" x 1-3/16" 13 0.1419 10,050 1-23-81-5 1/2" x 1-3/16" 13 0.1419 10,250 1-23-81-6 1/2" x 1-3/16" 13 0.1419 10,850 1-23-81-7 1/2" x 1-3/16" 0.1419 11,200 13 1-23-81-8 1/2" x 1-3/16" 8,500 12,500 Minirnun 13 0.1419 1-23-81-1 1/2" x 1-1/2" 13 0.1419 12,250 1/2" x 1-1/2" 0.1419 12,300 1-23-81-2 13 1-23-81-3 1/2" x 1-1/2" 0.1419 12,150 1/2" x 1-1/2" 13 12,500 1-23-81-4 0.1419 1/2" x 1-1/2" 13 12,250 1-23-81-5 0.1419 1/2" x 1-1/2" 13 12,100 1-23-81-6 0.1419 1/2" x 1-1/2" 13 12,000 1-23-81-7 0.1419 1/2" x 1-1/2" 13 12,500 1-23-81-8 0.1419 1/2" x 1-1/2" 13 0.1419 12,650 1-23-81-9 13 12,150 1-23-81-10 1/2" x 1-1/2" 0.1419 1/2" x 1-1/2" 13 12,300 l 1-23-81-11 13 0.1419 1-23-81-12 1/2" x 1-1/2" V Page 1 of 11
NCI 4% }f,,~. (- ( ' Duke Power Company Catawba Nuclear Station LETCo. Job No. CHS 81-016 February 4, 1981 Page 2 of 11 MEO!ANICAL TENSION TEST Continued Ultimate Threads Area Load LETCo. Bolt Size 2 (In) Per Inch (In ) (Lbs) Piece No. 1/2" x l-1/2" 13 0.1419 12,700 1-23-81-13 0.1419 12,400 1-23-81-14 1/2" x 1-1/2" 13 13 0.1419 12,650 1-23-81-15 1/2" x 1-1/2" 12,450 1-23-81-16 1/2" x 1-1/2" 13 0.1419 , 13 0.1419 12,400 1-23-81-17 1/2" x 1-1/2" 12,500 1/2" x 1-1/2" 13 0.1419 , 1-23-81-18 0.1419 12,750 1-23-81-19 1/2" x 1-1/2" 13 13 0.1419 12,600 1-23-81-20 1/2" x 1-1/2" 1/2" x l-1/2" 13 0.1419 12,200 1-23-81-21 12,200 1-23-81-22 1/2" x 1-1/2" 13 0.1419 13 0.1419 12,350 1/2" x 1-1/2" 12,800 1/2" x 1-1/2" 13 0.1419 D1-23-81-23 1-23-81-24 1-23-81-25 1/2" x 1-1/2" 13 0.1419 12,350 13 0.1419 12,300 1-23-81-26 1/2" x 1-1/2" 12,450 1-23-81-27 1/2" x 1-1/2" 13 0.1419 13 0.1419 12,650 1-23-81-28 1/2" x 1-1/2" 12,800 1/2" x 1-1/2" 13 0.1419 1-23-81-29 12,150 1/2" x 1-1/2" 13 0.1419 1-23-81-30 12,850 1/2" x 1-1/2" 13 0.1419 1-23-81-31 0.1419 12,550 1-23-81-32 1/2" x 1-1/2" 13 13 0.1419 12,600 1-23-81-33 1/2" x 1-1/2" 12,100 1/2" x 1-1/2" 13 0.1419 1-23-81-34 0.1419 12,550 1-23-81-35 1/2" x 1-1/2" 13 13 0.1419 12,450 1-23-81 1/2" x 1-1/2" 0.1419 12,200 1-23-81-37 1/2" x 1-1/2" 13 13 0.1419 12,150 1-23-81-38 1/2" x l-1/2" 0.1419 12,750 1/2" x 1-1/2" 13 l 1-23-81-39 0.1419 12,100 1-23-81-40 1/2" x 1-1/2" 13 l 0.1419 12,650 1/2" x 1-1/2" 13 1-23-81-41 0.1419 12,400 1-23-81-42 1/2" x 1-1/2" 13 0.1419 12,700 1-23-81-43 1/2" x 1-1/2" 13 0.1419 12,100 1-23-81-44 1/2" x 1-1/2" 13 l 0.1419 12,200 1/2" x 1-1/2" 13 1-23-81-45 8,500 Minimum
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Duke Power Company Catawba Nuclear Station LETCo. Job No. CHS 81-016 February 4,1981 . Page 3 of 11 MEDIANICAL TENSION TEST Continued Ultimate Bolt Size Threads Area Load LETCo. Per Inch (In 2) (Lbs) Piece No. (In) 13 0.1419 11,700 1-23-81-1 1/2" x 1-3/4" 0.1419 12,050 1-23-81-2 1/2" x 1-3/4" 13 13 0.1419 12,300 1-23-81-3 1/2" x 1-3/4" 0.1419 12,100 1-23-81-4 1/2" x 1-3/4" 13
- 13 0.1419 11,750 1-23-81-5 1/2" x 1-3/4" 11,650 1/2" x 1-3/4" 13 0.1419 1-23-81-6 0.1419 11,700 1-23-81-7 1/2" x 1-3/4" 13 13 0.1419 12,300 1-23-81-8 1/2" x 1-3/4" 11,700 1/2" x 1-3/4" 13 0.1419 1-23-81-9 0.1419 12,250 1/2" x 1-3/4" 13
,/}-23-81-10 t j-23-81-11 1/2" x 1-3/4" 13 0.1419 12,200 13 0.1419 11,550 '- 'l-23-81-12 1/2" x 1-3/4" 12,300 1/2" x 1-3/4" 13 0.1419 1-23-81-13 0.1419 12,100 1-23-81-14 1/2" x 1-3/4" 13 13 0.1419 10,400 1-23-81-15 1/2" x 1-3/4" 11,650 1/2" x 1-3/4" 13 0.1419 1-23-81-16 0.1419 11,550 1-23-81-17 1/2" x 1-3/4" 13 13 0.1419 10,550 1-23-81-18 1/2" x 1-3/4" 0.1419 11,700 1-23-81-19 1/2" x 1-3/4" 13 13 0.1419 11,700 1-23-81-20 1/2" x 1-3/4" 12,200 1/2" x 1-3/4" 13 0.1419 1-23-81-21 0.1419 11,750 1-23-81-22 1/2" x 1-3/4" 13 0.1419 11,700 1-23-81-23 1/2" x 1-3/4" 13 13 0.1419 11,650 1-23-81-24. 1/2" x 1-3/4" 0.1419 11,600 1/2" x 1-3/4" 13 1-23-81-25 0.1419 10,700 1/2" x 1-3/4" 13 1-23-81-26 8,500 Minimum 1
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Il . I Duke Power Company Catawba Nuclear Station LETCo. Job No. CHS 81-016 7 February 4,1981 l Page 4 of 11 MECMANICAL TENSION TEST Continued Ultimate Threads Area Load LETCo. Bolt Size (In 2) (Lbs) (In) Per Inch Piece No. 0.1419 11,950 13 1-23-81-1 1/2" x 2" 13 0.1419 11,200 1-23-81-2 1/2" x 2" 0.1419 11,650 1/2" x 2" 13 1-23-81-3 13 0.1419 11,600 1-23-81-4 1/2" x 2" 0.1419 11,800 1/2" x 2" 13 1-23-81-5 13 0.1419 11,450 1-23-81-6 1/2" x 2" 0.1419 11,600 1/2" x 2" 13 1-23-81-7 13 0.1419 11,600 1-23-81-8 1/2" x 2" 0.1419 11,700 1/2" x 2" 13 1-23-81-9 13 0.1419 11,650 1-23-81-10 1/2" x 2" 0.1419 11,550 1/2" x 2" 13 1-23-81-11 13 0.1419 11,750 1-23-81-12 1/2" x 2" 0.1419 11,750 1/2" x 2" 13 1-23-81-13 13 0.1419 11,550
- 1-23-81-14 1/2" x 2" 0.1419 11,700 1/2" x 2" 13 1-23-81-15 0.1419 11,650 1/2" x 2" 13 1-23-81-16 13 0.1419 11,750 1-23-81-17 1/2" x 2" 0.1419 11,600 1/2" x 2" 13 1-23-81-18 13 0.1419 11.450 1-23-81-19 1/2" x 2" 0.1419 11,150 1/2" x 2" 13 1-23-81-20 13 0.1419 11,650 1-23-81-21 1/2" x 2" 0.1419 11,750 1/2" x 2" 13 1-23-81-22 13 0.1419 11,600 1-23-81-23 1/2" x 2" 0.1419 11,500 1/2" x 2" 13 1-23-81-24 13 0.1419 11,700 1-23-81-25 1/2" x 2" 8,500 Minumum l
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, LETCo. Job No. CHS 81-016 l February 4, 1981 Pa9e 5 of 11 MECHANICAL TENSION TEST Continued Ultimate Area Load Bolt Size Threads LETCo. 2 (Lbs) (In) Per Inch (In ) Piece No. 0.1419 13,600 13 1-23-81-1 1/2" x 2-1/4" 13 0.1419 12,000 1-23-81-2 1/2" x 2-1/4" 0.1419 13,500 1/2" x 2-1/4" 13 13,400 1-23-81-3 .13 0.1419 1-23-81-4 1/2" x 2-1/4" 0.1419 13,650 1/2" x 2-1/4" 13 12,850 1-23-81-5 13 0.1419 1-23-81-6 1/2" x 2-1/4" 0.1419 13,650 1/2" x 2-1/4" 13 13,450 1-23-81-7 13 0.1419 1-23-81-8 1/2" x 2-1/4" 0.1419 13,450 1/2" x 2-1/4" 13 12,950 1-23-81-9 13 0.1419 1-23-81-10 1/2" x 2-1/4" 0.1419 13,700 1/2" x 2-1/4" 13 14,000 1-23-81-11 13 0.1419 1-23-81-12 1/2" x 2-1/4" 0.1419 13,750 1/2" x 2-1/4" 13 13,400 1-23-81-13 13 0.1419 1-23-81-14 1/2" x 2-1/4" 0.1419 13,600 1/2" x 2-1/4" 13 13,450 1-23-81-15 13 0.1419 1-23-81-16 1/2" x 2-1/4" 0.1419 13,500 13 1-23-81-17 1/2" x 2-1/4" 0.1419 13,450 1/2" x 2-1/4" 13 13,200 1-23-81-18 13 0.1419 1-23-81-19 1/2" x 2-1/4" 0.1419 13,950 1/2" x 2-1/4" 13 13,250 1-23-81-20 13 0.1419 1-23-81-21 1/2" x 2-1/4" 0.1419 13,600 1/2" x 2-1/4" 13 13,600 1-23-81-22 13 0.1419 1-23-81-23 1/2" x 2-1/4" 0.1419 13,500 1/2" x 2-1/4" 13 13,450 1-23-81-24 13 0.1419 1-23-81-25 1/2" x 2-1/4" 8,500 Minimum l e I -= - --
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- ll e Power Company SstawbaNuclearStation LETCo. Job No. CHS 81-016 rsbruary 4, 1981 P ge 6 of 11 .
MECHANICAL TENSION TEST Continued Ultimate Threads Area Load LETCo. Bolt Size Per Inch (In 2) (Lbs) Piece No. (In)
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13 0.1419 12,450 1-23-81-1 1/2" x 2-1/2" 0.1419 12,550 1/2" x 2-1/2" 13 1-23-81-2 0.1419 12,450 1/2" x 2-1/2" 13 1-23-81-3 0.1419 12,600 1-23-81-4 1/2" x 2-1/2" .13 0.1419 12,400 1/2" x 2-1/2" 13 1-23-81-5 0.1419 12,550 1/2" x 2-1/2" 13 1-23-81-6 0.1419 12,600 1/2" x 2-1/2" 13 1-23-81-7 0.1419 12,550 1/2" x 2-1/2" 13 1-23-81-8 0.1419 12,600 1/2" x 2-1/2" 13 1-23-81-9 0.1419 12,700 1/2" x 2-1/2" 13 1-23-81-10 0.1419 12,600 1/2" x 2-1/2" 13
- s1-23-81-11 13 0.1419 12,550 f
- 1/2" x 2-1/2" 0.1419 12,500 (s_,l23-81-12 1/2" x 2-1/2" 13 23-81-13 0.1419 12,450 1/2" x 2-1/2" 13 1-23-81-14 0.1419 12,550 1-23-81-15 1/2" x 2-1/2" 13 12,600 1/2" x 2-1/2" 13 0.1419 1-23-81-16 0.1419 12,600 1-23-81-17 1/2" x 2-1/2" 13 12,350 1/2" x 2-1/2" 13 0.1419 1-23-81-18 0.1419 12,350 1-23-81-19 1/2" x 2-1/2" 13 12,650 1/2" x 2-1/2" 13 0.1419 1-23-81-20 0.1419 12,450 1-23-81-21 1/2" x 2-1/2" 13 12,550 1/2" x 2-1/2" 13 0.1419 1-23-81-22 0.1419 12,450 1/2" x 2-1/2" 13 1-23-81-23 0.1419 12,700 1/2" x 2-1/2" 13 1-23-81-24 0.1419 12,650 1-23-81-25 1/2" x 2-1/2" 13 12.550 13 0.1419 1-23-81-26 1/2" x 2-1/2" 0.1419 12,300 1/2" x 2-1/2" 13
, 1-23-81-27 0.1419 12,550 1/2" x 2-1/2" 13 l 1-23-81-28 0.1419 12,350 1/2" x 2-1/2" 13 l 1-23-81-29 0.1419 12,450 1/2" x 2-1/2" 13 1-23-81-30 0.1419 12,500 1/2" x 2-1/2" 13 1-23-81-31 0.1419 12,400 1/2" x 2-1/2" 13 1-23-81-32 0.1419 12,350 1/2" x 2-1/2" 13 1-23-81-33 0.1419 12,450 1/2" x 2-1/2" 13 1-23-81-34 0.1419 12,500 1/2" x 2-1/2" 13 1-23-81-35 0.1419 12,350 1/2" x 2-1/2" 13 1-23-81-36 0.1419 12.450 1/2" x 2-1/2" 13 1-23-81-37 0.1419 12,350 1/2" x 2-1/2" 13 1-23-81-38 l
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3 ('~'T,hke Power Company l f'-"CatawbaNuclearStation LETCo. Job No. CHS 81-016 February 4, 1981 Page 7 of 11 . I MECHANICAL TENSION TEST Continued Ultimate Threads Area Load LETCo. Bolt Size 2 (Lbs) Piece No. (In) Per Inch (In ) I l 0.1419 12,300 l-23-81-39 1/2" x 2-1/2" 13 0.1419 12,250 1/2" x 2-1/2" 13 1-23-81-40 0.1419 12,500 1-23-81-41 1/2" x 2-1/2" 13 0.1419 12,450 1-23-81-42 1/2" x 2-1/2" .13 0.1419 - 12,450 1-23-81-42 1/2" x 2-1/2" 13 12,500 1/2" x 2-1/2" 13 0.1419 1-23-81-44 0.1419 12,300 1-23-81-45 1/2" x 2-1/2" 13 12,500 1/2" x 2-1/2" 13 0.1419 1-23-81-46 0.1419 12,600 1-23-81-47 1/2" x 2-1/2" 13 12,400 1/2" x 2-1/2" 13 0.1439 1-23-81-48 0.1419 12,450 1-23-81-49 1/2" x 2-1/2" 13 - 12,450 1/2" x 2-1/2" 13 0.1419 81-50 0.1419 12,200 9 1-23-81-51 1-23-81-52 1/2" x 2-1/2" 1/2" x 2-1/2" 13 13 0.1419 12,500 0.1419 12,500 1-23-81-53 1/2" x 2-1/2" 13 12,450 1/2" x 2-1/2" 13 0.1419 1-23-81-54 0.1419 12.550 1-23-81-55 1/2" x 2-1/2" 13 12,650 1/2" x 2-1/2" 13 0.1419 1-23-81-56 0.1419 12,600 1-23-81-57 1/2" x 2-1/2" 13 12.500 1/2" x 2-1/2" 13 0.1419 1-23-81-58 8,500 Minimum e ( l ( l l l l i t ) LAN DeGMEM TESTPC COMW#
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CT je Power Company Cotawba Nuclear Station LE'Iro. Job No. CHS 81-016 FGbruary 4, 1981 Pcge 8 of 11 MECHANICAL TENSION TEST Continued Ultimate LETCo. Bolt Size Threads Area Load Pince No. (In) Per Inch (In 2) (Lbs) l 1-23-81-1 3/8" x 1" 16 0.0775 5,650 1-23-81-2 3/8" x 1" 16 0.0775 5,700 1-23-81-3 3/8" x la 16 0.0775 5,500 ) 1-23-81-4 3/8" x 1" 16 0.0775 5,500 1-23-81-5 3/8" x 1" 16 0.0775 5,550 1-23-81-6 3/8" x 1" 16 0.0775 5,600 1-23-81-7 3/8" x 1" 16 0.0775 5,400 l 1-23-81-8 3/8" x 1" 16 0.0775 5,500 1-23-81-9 3/8" x 1" 16 0.0775 5,650 1-23-81-10 3/8" x 1" 16 0.0775 5,250 1-23-81-11 3/8" x 1" 16 0.0775 5,700 l '3-81-12 3/8" x 1" 16 0.0775 5,700 3-81-13 3/8" x 1" 16 0.0775 5,500 1-23-81-14 3/8" x 1" 16 0.0775 5,650 1-23-81-15 3/8" x 1" 16 0.0775 5,600 i 1-23-81-16 3/8" x 1" 16 0.0775 5,750 1-23-81-17 3/8" x 1" 16 0.0775 5,600 1-23-81-18 3/8" x 1" 16 0.0775 5,550 1-23-81-19 3/8" x 1" 16 0.07.75 5,700 1-23-81-20 3/8" x 1" 16 0.0775 5,450 1-23-81-21 3/8" x 1" 16 0.0775 5,650 1-23-81-22 3/8" x 1" 16 0.0775 5,750 1-23-81-23 3/8" x 1" 16 0.0775 5,600 1-23-81-24 3/8" x 1" 16 0.0775 5,650 1-23-81-25 3/8" x 1" 16 0.0775 5.550 1-23-81-26 3/8" x 1" 16 0.0775 5,550 1-23-81-27 3/8" x 1" 16 0.0775 5,650 1-23-81-28 3/8" x 1" 16 0.0775 5,650 1-23-81-29 3/8" x 1" 16 0.0775 5,550 1-23-81-30 3/8" x 1" 16 0.0775 5,750 1-23-81-31 3/8" x 1" 16 0.0775 5,400 1 1-23-81-32 3/8" x 1" 16 0.0775 5,600 Minimum 4,650 ( u, o..w =r -
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ke Power Company tawba Nuclear Station LETCo. Job No. CHS 81-016 February 4, 1981 Page 9 of 11, MECHANICAL TENSION TEST Continued Ultimate Bolt Size Threads Area Load LETCo. (In) Per Inch (In 2) (Lbs) Piece No. 3/8" x 1-1/4" 16 0.0775 7,030 1-23-81-1 0.0775 7,400 1-23-81-2 3/8" x 1-1/4" 16 16 0.0775 7,350 1-23-81-3 3/8" x 1-1/4" 3/8" x 1-1/4" 16 0.0775 7,600 1-23-81-4 0.0775 7,300 1-23-81-5 3/8" x 1-1/4" 16 3/8" x 1-1/4" 16 0.0775 7,350 1-23-81-6 0.0775 7,750 1-23-81-7 3/8" x 1-1/4" 16 3/8" x 1-1/4" 16 0.0775 7,650 1-23-81-8 0.0775 7,250 1-23-81-9 3/8" x 1-1/4" 16 16 0.0775 7,350 1-23-81-10 3/8" x 1-1/4" 7,650 3/8" x 1-1/4" 16 0.0775 1-23-81-11 0.0775 7,650 1-23-81-12 3/8" x 1-1/4" 16 16 0.0775 7,750
, 81-13 3/8" x 1-1/4" 7,750 3/8" x 1-1/4" 16 0.0775 1-23-81-14 7,300 3/8" x 1-1/4" 16 0.0775 1-23-81-15 7,650 3/8" x 1-1/4" 16 0.0775 1-23-81-16 0.0775 7,550 1-23-81-17 3/8" x 1-1/4" 16 16 0.0775 7,650 1-23-81-18 3/8" x 1-1/4" 7,250 3/8" x 1-1/4" 16 0.0775 1-23-81-19 7,200 3/8" x 1-1/4" 16 0.0775 1-23-81-20 0.0775 7,100 3-23-81-21 3/8" x 1-1/4" 16 16 0.0775 7,750 1-23-81-22 3/8" x 1-1/4" 7,350 3/8" x 1-1/4" 16 0.0775 1-23-81-23 0.0775 7,400 1-23-81-24 3/8" x 1-1/4" 16 16 0.0775 7,750 1-23-81-25 3/8" x 1-1/4" ,
3/8" x 1-1/4" 16 0.0775 7.700 i 1-23-81-26 0.0775 7.300 1-23-81-27 3/8" x 1-1/4" 16 0.0775 7,250 1-23-81-28 3/8" x 1-1/4" 16 16 0.0775 7,250 1-23-81-29 3/8" x 1-1/4" 7,300 3/8" x 1-1/4" 16 0.0775 1-23-81-30 0.0775 7,500 1-23-81-31 3/8" x 1-1/4" 16 16 0.0775 7,600 1-23-81-32 3/8" x 1-1/4" 4,650 Minimum l D
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ke Power Company , Stawba Nuclear Station l I LETCo. Job No. CHS 81-016 February 4,1981 Page 10 of 11 l
-I MECHANICAL TENSION TEST Continued '
Ultimate LETCo. Bolt Size Threads Area load 2 Piece No. (In) Per Inch lIn ) (Lbs) , 1-23-81-1 3/8" x 1-1/2" 16 0.0775 5,750 1-23-81-2 3/8" x 1-1/2" 16 0.0775 6,100 1-23-81-3 3/8" x 1-1/2" 16 0.0775 5,900 1-23-81-4 3/8" x 1-1/2" 16 0.0775 5,700 1-23-81-5 3/8" x 1-1/2" 16 0.0775 ' 6,300 1-23-81-6 3/8" x 1-1/2" 16 0.0775 6,350 1-23-81-7 3/8" x 1-1/2" 16 0.0775 6,450 1-23-81-8 3/8" x 1-1/2" 16 0.0775 6,050 j 1-23-81-9 3/8" x 1-1/2" 16 0.0775 6,100 1-23-81-10 3/8" x 1-1/2" 16 0.0775 5,850 1-23-81-11 3/8" x 1-1/2 16 0.0775 5,800 3/8" x 1-1/2" 16 0.0775 6,300 s}-23-81-12 3/8" x 1-1/2" 16 0.0775 5,800
\m_d23-81-1323-81-14 3/8" x 1-1/2" 16 0.0775 5,900 1-23-81-15 3/8" x 1-1/2" 16 0.0775 6,000 1-23-81-16 3/8" x 1-1/2" 16 0.0775 6,300 1-23-81-17 3/8" x 1-1/2" 16 0.0775 6,300 1-23-81-18 3/8" x 1-1/2" 16 0.0775 5,850 l 1-23-81-19 3/8" x 1-1/2" 16 0.0775 5,800 l 1-23-81-20 3/8" x 1-1/2" 16 0.0775 6,000 1-23-81-21 3/8" x 1-1/2" 16 0.0775 5,900 1-23-81-22 3/8" x 1-1/2" 16 0.0775 6,250 1-23-81-23 3/8" x 1-1/2" 16 0.0775 5,950 0.0775 6,350 t 1-23-81-24 3/8" x 1-1/2" 16 1-23-81-25' 3/8" x 1-1/2" 16 0.0775 6,000 1-23-81-26 3/8" x 1-1/2" 16 0.0775 6,100 1-23-81-27 3/8" x 1-1/2" 16 0.0775 5,900 0.0775 5,800 1-23-81-28 3/8" x 1-1/2" 16 6,650 1-23-81-29 3/8" x 1-1/2" 16 0.0775 1-23-81-30 3/8" x 1-1/2" 16 0.0775 5,950 0.0775 6,300 1-23-81-31 3/8" x 1-1/2" 16 6,000 1-23-81-32 3/8" x 1-1/2" 16 0.0775 4,650 Minimum /
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- 2e Poder Comhany k JtawbaiHucle'ar Station 1.ETCo.oJob No. CHS 81-016
' TGbnary 4, 1981 l k Page bl of 11 t
MECHANICAL TENSION TEST
# Continued Ultimate dc: t Load LETCo. Bolt Siz( Threads Area Piece No. (In) Per Inch (In 2) (Lbs) 1-23-81-1 3/8" x I 1/2" 16 . 0.0775 7,100 0.0775 6,900 1-23-81-2 3/8" x 2-1/2" , 16 3/8" x 2-1/2" 16 0.0775 7,100 1-27-81-3 0.0775 7,750
[ 1-23-81-4 1-23-81-5 3/8" x 2-1/2" 3/8" x 2-1/2" 16 16 0.0775 7,600 1-23-81-6 3/8" x 2-1/2" 16 0.0775 7,500 16 0.0775 7,500
. 1-23-81-7 3/8" x 2-1/2" 1 1-23-81-8 3/8" x 2-1/2" 16 0.0775 7,500 1-23-81-9 3/8" x 2-1/2" 16 0.0775 7,100 1-23-81-10 3/8" x 2-1/2" 16 0.0775 7,600 1-23-81-11 3/8" x 2-1/2" 16 0.0775 7,050 3/8" x 2-1/2" 16 0.0775 7,500 }-23-81-12 16 0.0775 7,100 l , )-23-81-13 3/8" x 2-1/2" '
6,900 L 'l-23-81-14 3/8" x 2-1/2" 16 0.0775 0.0775 7,600 , 's} 1-23-81-15 3/8" x 2-1/2" 16 , 7,250 1-23-81-16 3/8" x 2-1/2' 16 0.0775 16 0.0775 6,800
- 1-23-81-17 3/8" x 2-1/2" 7,100 1-23-81-18 3/8" x 2-1/2" 16' O.0775 16 0.0775 7,500 1-23-81-19 3/8" x 2-1/2" 7,490 1-23-81-20 3/S" x 2-1/2" 16 0.0775 16 0.0775 7,350 1-23-91-21 3/8" x 2-1/2" 7,000 1-23-81-22 x 3/8" x 2-1/2" 16 0.0775 16 0.0775 6,800 1-23-81-23 3/8".x 2-1/2" 7,550 1-23-81-24 3/8" x 2-1/2" 16 0.0775 l
16 0.0775 7,450 1-23-81-25 3/8" x 2-1/2" 7,450 1-23-81-26 3/8" x 2-1/2" 16 0.0775 16 0.0775 6,850 1-23-81-27 3/8" x 2-1/2" 7,250 1-23-81-28 3/8" x 2-1/2" 16 0.0775 l 16 0.0775 7,600 1-23-81-29 3/G* x 2-1/2" 7,450 1-23-81-30 3/8" x 2-1/2" 16 0.0775 16 0.0775 7,450 1-23-81-31 3/8" x 2-1/2" 7,350 1-23-81-32 3/8"'s 2-1/2" , 16 0.0775
' 4,650 Minimum t Inspector (s): rr le bY; . ' Respectfully submitted, j
l. [*})***d (V Edward M. Beck. P.E. Metals Department Manager l.AW ENGINEERING TESTING COMPANY
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J REPORT OF CHEMICAL ANALYSIS DUKE POWER COMPANY org;e,; Charlotte Metals Cremi Pro,hlt: CATAWBA NUCLEAR STATION Date: February 9,1981 Newport, South Carolina m, go, CHS 81016
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cli:nt P. O. No.: G2494-41 sAat: rial: Reported as Carbon Steel Extemally Threaded Standard Fastener ASTM A 307 (See Below) Grade A l1 Hest No.: Unknown Datc' Terted: 2/9/81 Procsdure: In accordance with ASTM A 307 78, ASTM A 36 77, and ASTM E 30 77 TEST RESULTS LETCo. Elements ._
, Piece No. ,C,1r h.g n Mancanese Phosehe us Sql*t S.lkg.n Size 1 59 0.13 0.40 0.02 0.02 0.18 1/2" x 15/16" Ch J10 /
0.15 0.51 0.01 0.01 0.16 1/2" x I 3/16" 1238140 0.15 0.49 0.02 0.02 0.24 1/2" x 11/2" 1238147 0.16 0.50 0.02 0.02 0.15 1/2" x 1-3/4" 123 812E 0.19 0.33 0.02 0.02 0.15 1/2" 'x' 2" 1 23-81 26 0.15 0.48 0.01 0.02 0.15 1/2" x 21/4" 1233158 0.16 0.37 0.01 0.01 0.15 1/2" x 21/2" I f23 81 32 0.12 0.29 0.01 0.01 0.13 3/E" x 3/4" b23 8133 0.18 0.38 0.02 0.02 0.22 3/8" x 1" 1238133 0.21 0.84 0.02 0.02 0.44 3/8" x 1-1/4" 1238133 0.18 0.36 0.02 0.02 0.12 3/B" ~x 11/2" 123 8b33 0.16 0.36 0.02 0.01 0.14 3/8" x 21/2" Required' A.307 - P.4 - 0.15 Raquired A 36 0.26 0.G. 0.05 0.15 to 0.30 , Nste- The single values are the n ce w ..< ,wed in the required section. itsm 123 8133, 3/8" x 11/o" exceeds the maximum of sliicon per basic materlaf specification. Inspectors): Larry e I - ' J. c Jr. Raylewed by: Edward M. Beck, P E. Corporate Consultant / Metals V, Respectfully submitted, LAW ENGINEERING TESTING COMPANY 4 CRP- _! j_ =-
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