ML20133E740
| ML20133E740 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/31/1996 |
| From: | Belair R, Mason D COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20133E738 | List: |
| References | |
| BRW-96-951-M, BRW-96-951-M-R, BRW-96-951-M-R00, GL-90-05, GL-90-5, NUDOCS 9701130136 | |
| Download: ML20133E740 (10) | |
Text
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FRON: COMED DG 4?H FLOOR FAM Ho.:
6306637199 13-31-96 10:17 P.02 Exhibit c NEP-12-02 Revision 4 s
Page 1 of 2 COMMONWEALTH EDISON COMPANY CALCULATION TITLE PAGE CALCULATION NO BRW-96-951-M PAGE NO.: 1 x
SAFETY RELATED REGULATORY RELATED NON-SAFE'iY RELATED l
CALCULATION TITLE:
i Flaw Evaluation of Une 1SX93AA 8' per Generic Letter 90 05 Guidance STAT ION / UNIT: Brai0 wood Unit 1 SYSTEM ABBREVIATION: SX EQUIPMENT NO.: pun.
PROJECT No.: F usa i
REV: 00 STATUS:
Appro. cd QA SERIAL NO. OR CHRON NO. N/A DATE:_
PREPARED BY:D W-MAMk.hlN-DATE: /3-J/-96 c ' %v pdc &
nisiht REVISION
SUMMARY
initial Revision
)
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}
i l
ELECTRONIC CALCULATION DATA FILES REVISED:
(Name ext /sherdato/ hour. mirWerificatjon memod/ remarks) i l
DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION YES NO X 4
REVIEWED BY
- d' DATE: [ SI[ 9 h enwu
- uowv v
REVIEW METHOQ*-MT ALLE17 DsHGM 9 6hetv COMMENTS (C. NC OR CD-
^//C f
}
n iz/3//9 G APPROVED BY I
DATE:
- p. v. mec.E 9701130136 961231 PDR ADDCK 05000456 P
PDR Faae 1 DEC 31 '96 12:19 6326637199 PA3E.22
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Exhibit C NEP-12-02 Revision 4 Page 2 of 2 COMMONWEALTH EDISON COMPANY CALCULATION REVISION PAGE CALCULATION NO. BRW-96-951-M PAGE NO.: 2 REV:
STATUS:
QA SERIAL NO. OR CHRON NO. N/A DATE:
PREPARED BY:
DATE:
REVISION
SUMMARY
ELECTRONIC CALCULATION DATA FILES REVISED:
(Name ext / size /date/ hour; min / verification method / remarks)
DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION YES NO REVIEWED BY:
DATE:
REVIEW METHOD:
COMMENTS (C, NC OR Cl):
APPROVED BY:
DATE:
Page 2
Exhibit D NEP-12-02 Revision 4 i
COMMONWEALTH EDISON COMPANY CALCULATION TABLE OF CONTENTS PROJECT NO. N/A CALCULATION NO. BRW-96-951-M REV. NO. 00 PAGE NO.
3 DESCRIPTION PAGE NO.
SUB-PAGE NO.
TITLE PAGE 1
REVISION
SUMMARY
2 TABLE OF CONTENTS 3
.1.0 PURPOSE / OBJECTIVE 4
2.0 METHODOLOGY AND ACCEPTANCE 4
CRITERIA 3.0 ASSUMPTIONS 4
4.0 DESIGN INPUT 4
1
5.0 REFERENCES
4 6.0 CALCULATIONS 5-7 7.0
SUMMARY
AND CONCLUSIONS 8
ATTACHMENTS A.
NDIT BRW-96-255 A1-A2 i
Pace 3
Exhibit E NEP-1242 Revision 4 COMMONWEALTH EDISON COMPANY l CALCULATION NO.
BRW-96-951-M PROJECT NO.
N/A PAGE NO. 4 l 1.0 PURPOSE / OBJECTIVE: An 8" x 6" reducer off line 1SX93AA-8" contains a through-wall flaw.
Based on Design input 4.1, there is a single flaw which is characterized as a pinhole flaw of length (diameter) 1/8", That is, a non-destructive examination of the general area around the flaw yielded no other flaws within the separation criteria (as provided in Reference 5.2) of 2 tm,n which violate the minimum wall requirements. Due to the localized degradation, the flaw is not indicative of erosion, but may be due to localized corrosion. The purpose of this calculation is to evaluate the structural integrity of the flawed reducer.
2.0 METHODOLOGY AND ACCEPTANCE CRITERIA: The flaw evaluation is performed per the methodology provided in Generic Letter (GL) 90-05. Per the generic letter, the methodology may be applied to Class 3 moderate energy piping such Service Water and may only be applied when the flaw is found during plant operation. Line 1SX93AA-8" meets these limitations.
GL 90-05 provides two methodologies for flaw evaluation. This evaluation uses the "Through-Wall Flaw" approach. By limiting the stress intensity factor "K" resulting from the flaw under the applied loads to the fracture toughness of the piping material,35 ksi(in)" for ferritic steel, flaw stability and structural integrity are " reasonably assured".
3.0 ASSUMPTIONS
None.
4.0 DESIGN INPUT:
4.1 NDIT BRW-96-255 dated 12/30/96.
4.2 Piping Line List for 1SX, Rev. 48.
4.3 Piping Design Table 105BB Rev. F dated 12-31-84, 4.4 Piping Stress Report 1SX-04 Rev. 03D, EMD-048997.
5.0 REFERENCES
5.1 ASME Boiler and Pressure Vessel Code, Section Ill, " Rules for Construction of Nuclear Power Plant Components," 1974 Edition through Summer 1975 Addenda.
5.2 Generic Letter 90-05 dated June 15,1990.
5.3 Byron /Braidwood Stations Units 1 and 2 Piping Design Specification, Rev. O dated 12-03-92.
6 l REVISION NO.
00 l
Exhibit E NEP-1242 Revision 4 4
COMMONWEALTH EDISON COMPANY CALCULATION NO.
BRW-96-951-M PROJECT NO.
N/A PAGE NO. 5 l
6.0 CALCULATIONS
Per Reference 5.2, the stress intensity factor "K" resulting from the flaw under the applied loads is given by:
K = (1.4) (s) (F) (3.1416 x a)"5 where:
a=
half the flaw length (in).
s=
stress at the flawed location due to combined deadweight, pressure, thermal expansion and safe-shutdown earthquake loading conditions (psi).
F=
geometry factor = 1 + (A) (c) + (B) (c)2.s + (C) (c)' 5 c=
a / (3.1416 x R)
R=
mean pipe radius (in) 2 A=
-3.26543 + 1.52784 r- 0.072698 r + 0.0016011 r' 2
B=
11.36322 - 3.91412 r + 0.18619 r - 0.004099 r' r
C=
-3.18609 + 3.84763 r - 0.18304 r + 0.00403 r' r=
R / tmin tm.o = Code-required minimum wall thickness (in)
Per Reference 5.1, NC-3640; (PDo) t ;n =
+A where:
(2)(S + Py)
A=
erosion / corrosion allowance (in)
P=
intemal design pressure (psi)
Do =
outside diameter of pipe (in)
S=
maximum allowable stress in material at the design temperature (psi) y=
coefficient having a value of 0.4 except that, for pipe with a D./tmin ratio of less than 6, the value of y shall be taken as:
d y=
where:
d+Do d=
inside diameter of pipe (in) l REVISION NO.
00 l
?
Exhibit E NEP-1242 Revision 4 COMMONWEALTH EDISON COMPANY CALCULATION NO.
BRW-96-951-M PROJECT NO.
N/A PAGE NO. 6 l From 'bes f n 2n p+ 4. / -
W am be s
/sxq3AA-8" A puolv en -L.
2"x G" hdue.ar ups+rm o.! valve IsyIsoA From vedy Lp+ 4.4 F/PsY.s model ;
y.W+
Ge..+ype i 6.62S"opu.28c"4Ll.
M Geo.d L
- 8. G25oc x.322 "Q, yp<.
f,...,
,i..
_ c Yr',
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'4 s;,
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y e>
e r%,%
Q"
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, ?)
Fr.
Desien Lpu+ 4.4 F/Psy3 ou4pa4,
usu reassac 12C esb
.Sn = IS", 000 f s 's Se =IC ocor=i i&, 5 _
$a Y Yo 0 9$O
' ' gg j733 O
N. F.
So ggg jj 53A 983 2/97-3068 cp REVISION NO.
00 I
Exhibit E NEP.12-02 R;visiin 4 COMMONWEALTH EDISON COMPANY CALCULATION NO.
BRW-96-951-M PROJECT NO.
N/A PAGE NO. 7 M D-36@ < st 5 (caserwnf use. Nf Q Pip f,,c,q
%,n Referenz f. l i 3
/2s m2o
+ A = L.:..cnem. izscc. sis)c""#
- pp Emin =
2(S+ Py) zos.ow+nsc.q) + 0 = 0 275"
~
wgm y =. q, 3 = I5,ompsi
- use o{mean%f 34 ruses S^ N f* '9l'"l10L Y"-
( "S' C r. w P B,(Fr. M.5. I, A pr.1. r. l}
l of kn,,1; redaaer fi& ( 8 56)w,g),t A*Oi f*r Etf. 5.3.
"'"'*g. 7I" ' " k '"' r from Reh<su e. 5.2. ; 3y,**T1.re 3 -Wall f/w " A eyras L L
Q.,= (8. G25,3r2 )/2. =. 4.1SI5 "; % =(C.625.280.)/2 = 3. I725" in= Wlmt = 0. I&I5/o, o3 G" = ljf 3; rm = 2.t72Gfo.o2,S"= ll5y;.,
au r a llf.4.
2 = 0. ISG 3 ", hsle els% he mesure t as ~}/g " wI,,*d w uI,( k ';za',.
eawrve&cly us<.'2 ' as %-e.,, or 2 dc"ali:. kle,3 ns a h*gke k nsM.
E i
cy *
- Wb.m>3.I,n,)=.0167 Qq 2/Q.1414 ~R) =,/163/(3.I416 4.1615) =, O I2.o; c
/
A = -3 2Gs43 + 1 sz,84C!!s.4) o,z'980's 4F+ ool' 0 4i
+ 81L 3
- ACE 8 e targo.g 3.s
= I 665. 5 g = //.36327 -3.9/4126/5A.)+. IPCl9 O/5M.)*.co4a99 Cl/54f
.u
- ~n.,
+ :m.s
- u n,.,
= - 4(2Go. I C = -F.18609 + 3.Fl743 6/5.4 ). I83o46/5.Cz4. eo yo3 (ffgA,)3
- 3.:.
. wy, o
- z m.s
,,,.,3. 3
= 4/ / 76. G' Q = I 4 (1665. 6.)(.oI20)+(-Llz6o. l )(.0120)**+(4196.5j.0 820)"
= 3. I2.,
Q = l + (I4GC. C.)(.o157)'# + (-42 Go. ))(olG7)' ' +(2lt9 g. Syajgyy.c
= 4.15 : :. ua F= Qls-
~
K = l.4 (30G8 psi)(4.I5f3.IlllGro./SG3f'
= /249t ps;cing' < 36, coo sW (k Gnu sul) r REVISION NO.
00
Exhibit E NEP-12-02 Revision 4 COMMONWEALTH EDISON COMPANY CALCULATION NO.
BRW-96-951-M PROJECT NO.
N/A PAGE NO. 8/
'61uI 7.0
SUMMARY
AND CONCLUSIONS: The calculated stress intensity factor "K"is less than the critical stress intensity factor (fracture toughness of the material) for ferritic steel,35 ksi(in)". Therefore, the flaw stability and structuralintegrity meet the guidelines of 90-05 and are considered acceptable.
k l REVISION NO.
00 l
o J
NUCLEAR DESIGN INFORMATION TRANSMITTAL X Safety Related Originating Organization:
O Non-Safety Related X Comed NDIT No BRW-95 255 0 Regulatory Related O Otner(specify):
Station: Braidwopf Unit (s): 1 Page 1' of
?
Design Change Authority No.: None System Designation: SX To: DV Radice SEC Eno
SUBJECT:
Characterization of Flaw in Essential Service Water 1A iner Drain in 1SX93AA 0 Mu h nell Fife de.ed astiQ f 12@ %
- reparbr Position P p ers, i
/[
Date ure Dua. POmma ihuw Lw
' 'I i - n4 Reviewer Position Reviewers Signature Date Status of Information: x Approved for Use O Unverified O Engineering Judgment Method and Schedule of Verification for Unverified NDITS:
N/A.
i Description of Information:
This NOIT provides the following physical characteristics of the through wall flaw and surrounding basemetallocated in the 6'X 8" reducer in line 1SX93AA of the Braidwood Unit 1 Essential Service Water System:
- 1. Size of flaw; 2 Wallthickness at various locations surrounding flaw.
W'#*
- %b~AD%
"a oo i
ATTMHeyspr7 A FAGE AI Purpose of issuance:
The above information is to be used as input to the flaw evaluation associated with the structuralintegrity determination of the flawed piping.
Source of Information:
Foeld measurements utilizing ultrasonic measurement equipment and ruler.
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! Distribution:
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NDIT File - original; B Acas - SEC Eng: D. Mason - SEC Eng; D. Christiana - SEC Eng: G. DanieII-SEC Eng.
Letter File Number: ED-96-1126-BRW t
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