ML20073A228
| ML20073A228 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/31/1991 |
| From: | Jonathan Brown, Knous W, Rosten R NUTECH ENGINEERS, INC. |
| To: | |
| Shared Package | |
| ML20073A188 | List: |
| References | |
| COE-118-021, COE-118-021-R00, COE-118-21, COE-118-21-R, NUDOCS 9104230109 | |
| Download: ML20073A228 (110) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ ~
.j[k ~
CoE-118-021 March 1991 Revision 0 l
EVALUATION OF QUAD C' TIES PENETRATION BELLOW.5 I ASSEMBLIES LEAKAGE dATi:S l 1
Prepared for:
Commonwealth Edison Company 4
Prepared by:
NUTECH Engineers, Inc.
Westmont, Illinois Prepared by:, / '
Raymond W. Rosten, P.E.
Issued by: EflD1h. dM h JiMa'#W N. Brown, P.E.
Reviewed.by: WWilliam S. Knous Date: M S7.I%l 9104230109 9to439 fDR ADOCK 05000234 PDR l
l i
~J TABLE OF CONTENTS Title Eags T7BLE OF CONTENTS . . . . . . . . . . . . . . . . . . . . . . 11 EXECUTIVE
SUMMARY
. . . . . . . . . . . . . . . . . . . . . . iii PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . .1 HISTORY OF BELLOWS AT QUAD CITIES . . . . . . . . . . . . . . . 1 BACKGROUND OF X-25 PENETRATION . . . . . . . . . . . . . . . . 2 METHOD OF ANALYSIS . . . . . . . . . . . . . . . . . . . . . . 2 INPUT DATA . . . . . . . . . . . . . . . . . . . . . . . . . . 3 MAJOR ASSUMPTIONS / DESIGN INPUT . . . . . . . . . . . . . . . . 3 RESULTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 CONCLUSIONS . . . . . . . . . . . . . . . . . . . . . . . . . . 6 TABLES Table 1 - !al.'.ows Assembly Flaw Data . . . . . . . . . . . . . 6 Table 2 ou.nmary of Bellows Flaw Model Loading Data . . . . . 7
- ATTACHMENTS Attachment 1 - Quad Cities Bellows Assembly Sketch Attcchment 1 - Quad Cities Bellows Finite Element Model Calculation Attachment 3 - Quad Cities Bellows Leakage Flow Calculation Attachment 4 - Commonwealth Edison Phot ographs of X-25 Bellows Attachment 5 - Finite Element Model Depicting Bellows Flaw Details Attachment 6 - Design Input Log l
l COE-118-021 HUTEEH EN0lNEERS
'I ,
EXECUTIVE
SUMMARY
Flexible metallic bellows in Pressure Suppression System line 1-1605-18"-LX at Unit 1 penetration X-25 were found to have flaws during the Q1R11 outage Integrated Primary Containment Leak Rate Test (IPCLRI). Although the X-25 flaws resulted in higher than hictorical IPCLRT leakage, the "as-left" IPCLRT leakage was within permissible limits. The X-25 bellows were replaced during the Q1R11 outage significantly increasing the IPCLRT margin.
CECO requested NUTECH prepare calculations to assess the impact et potential flaw growth during the next eighteen month fuel cycle following Q1R11, and the resulting leakage.
This report discusses the following subjects e History of bellows at Quad Cities e Background information relative to Penetration X-25
- Method of analysis
- Major assumptions
- Results
- Conclusions NUTECH's assessment has resulted in the-following conclusions:
- If the flawed bellows at penetration X-25 had been left in-place-and all identified flaws grew by 3/16", the-predicted-leakage rate contributed =by X-25 during the next "as-found" IPCLRT would be within IPCLRT allowables.
- If there is a bellows which currently is not leaking through its. outer surface,-butLis postulated to have 200 flaws emerge at the start of the cycle and grow to 3/16" at the end of the cycle, the' predicted leakage rate during the next "as-found" IPCLRT would be within IPCLRT allowables.
-COE-118-021 NIUTECH
-lii- ENCANEERS
.i PURPOSE This report documents the results of NUTECH's evaluation of Quad cities flexible metallic bellows leakage and its affect on primary containment leakage rate (see Attachment 1 for bellows sketch). NUTECH has evaluated the leakage characteristics of bellows with transgranular stress corrosion cracking (TGSCC) flaws that could have grown during one fuel cycle. The evaluation consists of a finite element model of the bellows assembly (Attachment 2) and a leakage flow calculation (Attachment 3). The evaluation addresses the following questions:
- 1. Will the leakage from a " worst-case" bellows assembly, modeled after the removed X-25 penetration bellows, also be within limits, allowing for crack growth due to TGSCC, and calculating leak rates for the IPCLRT at the end of the next fuel cycle?
- 2. Will the potential leakage from remaining bellows assemblies due to TGSCC be within 10CFR50 Appendix J limits until the next Integrated Primary Containment Leak Rate Test (IPCLRT)?
HJSTORY OF BELLOWS AT OUAD CITIES Since 1984, CECO has been implementing an aggressive program of inspection and replacement (when required) for Primary Containment flexible metallic bellows elements. Four bellows assemblies have been replaced at Quad Cities Station and one has been permanently removed at Dresden Station due to indications of increasing leakage rates. In addition, several other bellows assemblies were replaced as part of the Dresden Unit 3 reactor recirculation system piping replacement effort in 1987. In 1990, Ceco developed a comprehensive plan to improve bellows performance and life. expectancy by identifying failure mechanisms and implementing inspection programs to identify if, and when future failures might occur.
There are two basic replacement methods that have been utilized:
a) a like-for-like approach in which the existing bellows elements are removed and replaced with components which are essentially identical to the originals, and b) a " clam shell" replacement in which the original bellows elements are removed and replaced with new elements which are assembled in-situ, thus avoiding the need to remove the process pipe. CECO has qualified the latter replacement method by prototype test, as required by ASME Code Case N-315.
Over the years, CECO has performed several (1984, 1990 & 1991) metallurgical examinations to evaluate bellows failures at both Quad Cities and Dresden Stations. In each of these investigations, failure of the bellows elements was attributed to TGSCC. No evidence of fatigue crack growth however been observed. The corrosive species responsible for crack initiation COE-118-021 NUTECH Eb4EMNEERS
. . - .. . _ _ _ _ _ . _ _ _ - - _ _ . . .______._m __
i
')
has recently been identified as chlorides, fluorides and sulfides. The source of this material has been variously attributed to initial fabrication, original construction, or to other mechanisms that could be occurring during plant life which would result in the transport and concentration of these materials on the bellows surfaces. It has been consistently observed that TGSCC initiates on the bellows inner. surface. .
BACKGROUND OF X-2 5 PENETRATION '
During the Q1R11 IPCLRT, the flexible metallic bellows at penetration X-25 exhibited significant leakage. Upon further inspection, it was determined that there were flaws (crack-like indications and pinholes) in the bellows. A special test, performed to determine the amount of leakage from the X-25 bellows assembly, revealed that the leakage rate was 137.4 scfh.
The bellows was determined to be unrepairable and a replacement bellows was installed. Metallurgical examination of the removed bellows determined that the cause of the flaws is TGSCC. The removed bellows was inspected for flaw length, Width, orientation, and quantity, l
Ceco personnel performed PT inspections of six other bellows
)
assemblies and found two minor surface indications in one of the '
bellows. Although the X-25 bellows was leaking during the l IPCLRT, the IPCLRT was successfully completed with adequate "er-left" leakage margin.
METHOD OF ANALYSIS NUTECH constructed a. finite element model to evaluate the response of bellows elements with varying size flaws to applied
, loads.
The model-reflects the latest data assembled by field
- personnel and at Argonne National Lab for the X-25 bellows -
(See-Table 1 for bellows flaw data.) The model was subjected to loads experienced during the IPCLRT (pressure). Crack propagation due to TGSCC attack over the course of one fuel cycle was also included.
The model was used to calculate the extent of flaw opening (i.e.,
fish-mouthing) under pressure. The geometry of the resulting flaw opening was used to-perform a separate leakage flow calculation.
The leakage flow calculation utilized an orifice as a model, taking into account the flaw area calculated by the finite
~
element model (see Attachment 3 for details =of-the flow model).
Flow rates were calculated for a range of flaw lengths that envelope the observed flaws on penetration X-25. Calculated flows are as follows:
- 1. First, the leakage model was baselined utilizing the known X-25 bellows leakage (137.4 scfh). Actual flaw sizes, configuration and number as indicated by-field personnel /Argonne Lab, were utilized in the model as COE-118-021 04UTE[H 1 EtNMt4EERS !
l 2 - _ - _ ~_.
y_
'l the initial condition (pre-test). Input from the finite element model was then used to calculate flaw area under the IPCLRT condition. Leakage flow was calculated and compared to the known leakage.
- 2. A second finite element model of the X-25 bellows was used to reflect flaw growth over the span of one fuel cycle. The new flaw area was calculated under IPCLRT conditions. From this data, leakage flow at the end of the fuel cycle was calculated.
- 3. A third model was used to reflect a large number of hypothetical subsurface flaws that pinhole immediately after plant start-up and grow over a fuel cycle to result in 3/16" flaws. This model was then subjected to the IPCLRT condition to obtain flaw areas and the combined leakage rate for these small flaws was determined.
Finally, the leakage information calculated was compared to the recent IPCLRT-data and LLRT requirements to assess the impact of flawed bellows in the various configurations described above.
INPUT DATA The following conditions were used as input to this analysis:
IPCLRT Conditions Pressure:- 48-50 psig L Temperature: 80-100'F l
l LIn additien, data.on-bellows flaws as reported from the Station and-fromfthe Argonne inspections is presented in Tables 1 and 2, and Attachment 4. The input is summarized in the following assumptions / design inputs.
L MAJOR ASSUMPTIONS / DESIGN INPUT l-
- 1. The crack growth rate used is 3/16" per fuel cycle (18 L months). (This rate was derived from two sources:. a) an
-independent fracture mechanics analysis performed by others for CECO used the results of a recent EPRI-Report (RP-5064S) on stress corrosion crack growth rates to predict 0.1864 inches per cycle, b) the largest observed flaw on X-25 would
! have grown at a rate of 0.1832 inches per cycle if' flaw L . initiation started in 1977 - the date when leakage was first-detected.) This rate is used to predict flaw size at.the
! end.of a fuel cycle. Failure analysis results indicate that-L the crack propagation is due-to the TGSCC process only and
-that no mechanical fatigue is involved.
l
- 2. Flaw orientation has been assumed to be predominantly in the axial direction. This is supported by the results of PT and visual examination of the bellows.
- l. COE-118-021 NUTE[H ENGHEERS
.. - - ._. _ - - - . . - ~ .
'k l
.]
- 3. Flaws are assumed not to interact with each other. The TGSCC mechanism is non-preferential and therefore can initiate randomly on the material surface. Since the flaw size (width) is very small, and the flaws grow axially, the probability of flaws joining together is negligible.
- 4. Each flaw (other than pinholes) is modeled as a rectangularly shaped flaw with tapered ends. See Attachment 5 for finite element model drawings.
- 5. Only the outer ply of the two-ply bellows is modeled. The inner ply is assumed to behave with the actions of the outer ply and the flaw is assumed to have the same configuration on both the inner and outer plies. This assumption is conservative for the flow model because the flow losses attributable to the inner bellows are being ignored.
- 6. Movements of the drywell will not affect the width of the flaws. This is justified due to the axial orientation of l the flaw and that deflection of the drywell at Penetration l X-25 is in the lateral direction. These bellows assemblies are tandem-style, which effectively translate lateral E
displacement to axial displacement. Therefore, drywell lateral motion is equated to an axial movement of the bellows. The lines of force due to axial displacement at the bellows are parallel to an axial flaw and therefore do not contribute to changes in flaw shape.
- 7. The contribution of leakage from the pinholes is small when compared to the total leakage due to flaws in the bellows assembly. -This is supported by the evaluation made in Attachment 3 and actual observed leakage during snoop testing of the X-25 bellows.
RESULTS
- The analytical' result predicted by the flow model for the leakage rate through the X-25 bellows assembly at IPCLRT conditions was approximately 44.7 SCFH. The relative contributionaof leakage rates predicted by the model from the various flaw sizes considered corresponds with the observed bellows leakage during the test. Therefore, the model is representative of the bellows with respect to its prediction of relative leakage rate to flaw size.
Due to the nature of the crack geometry, size, and superposition across a curved surface, it is difficult to
-determine the actual flow area through the flaw. Also, because of the irregular form of the flaw, the flow is not fully developed. For these two reasons, the flow model results were correlated to the actual bellows test data by proportioning model results up to the test data.
It can be observed that the relationship between mass discharge through flaws, as predicted by the model, and flow COE-118-021 i
area is approximately linear at similar test conditions.
This observation can lead one to conclude that an accurate prediction of flow increase due to crack growth can be obtained by multiplying the observed or measured leak rate by a ratio of the increased flow area to the original flow area. Therefore, using this argument, increases in flaw areas (calculated from Attachment 2) will result in a leakage flew rate of 215 SCFH at the end of a fuel cycle.
Similarly, the leakage flow rate for the growth of a number of pinholes over a fuel cycle was calculated to be 78.6 SCFH.
e The leakage flow calculations for each case result in flows that are within the Safety Limit at the end of the next fuel cycle. Results are tabulated below:
CALCULATED
- PRIDICTED *
- LEAKAGE CALCULATED IPCLRT MARGIN PREDICTED CASE RATE FLOW fWT4/ DAY 1 fAeo. J) SATETY KAPGIN (a) (b)
- 1. X-25 IPCLRT 215 SCFH 0.44 wtt/ day -0.02 wt%/ day 0.23 wt%/ day Condition
- 2. 3/14" Pinholes 18.6 SCFH 0.16 wtt/ day 0.26 wt%/ day 0.51 wtt/ day IPCLRT r a d tfon IPCLRT Margin was calculated by the following method:
IPCLRT Result (0.6096% wt/ day) -
As found X-25 data (0.2808%
wt/ day) = Adjusted IPCLRT Result (0.3288% wt/ day)
Maximum Allowable Leakage (% wt/ day) 10CFR50 Appendix J Limit 0.75% wt/ day Safety Limit 1.00% wt/ day (489.6 SCFH)
The Appendix J Limit represents the maximum allowable "As-Left" condition after IPCLRT performance while the Safety Limit represents the Technical Specification operability Limit.
- Calculated Leakage Rate (SCFH) x 0.2 %
,, ay -(al v:%/ day
- 0.75% wt/ day - 0.3288% wt/ day = 0.4212% wt/ day (Adjusted IPCLRT Margin) 0.4212% wt/ day - (a) = (b) 1.0% wt/ day - 0.3288% wt/ day = 0.6712% wt/ day 0.6712% wt/ day - (a) = (b)
COE-118-021 _ _ _ _ _ _ _ _ _ - _ _ _ _ = _
- . ~~
'41
~
CONCLUSIONS Primary containment integrity will be maintained within the maximu.a allowable leakage limits assuming:
e the possibility of flaws in another penetration bellows assembly, e leakage similar to that of the replaced X-25 bellows, and e flaw growth for one fuel cycle.
Additionally, Primary Containment leakage integrity will also be maintained assuming:
e a bellows assembly has 200 subsurface flaws, e pinholes form at the beginning of the fuel cycle, and e the pinhole flaws grow by means of TGSCC to a length of 3/16" at the end of the fuel cycle.
l COE-118-021 NUTELH Et40lNEERS
l- J1 l --
- , l TABLE 1 Bellows Assembiv Flav Data U)
Flaw Lencth Flaw Width Ouantity 1.7" 0.010" 1 0.5" 0.001" 3 0.187" 0.001" 36 0.001" 0.001" 200 l
")
Reference NUTECH Communication Records TJW-91-056 and l RWR-91-024. Note that the original data transmitted to l NUTECH (RRR-91-024) stated that there are nine (9) flaws and thirty'(30) 3/16" flaws.
0.5" The latest data I from-field observations'(TJW-91-056) indicate that there are 4 major leaks. In addition to the large flaw,-3 leaks were felt by hand. Therefore, 6 flaws-in the 0.5" category have been re-assigned to-the 3/16" category because they did not exhibit significant leakage _as-did the major leaks.
k I,
e.
l l
i l -COE-118-021 F41UTE[H ENGHEERS
. ~. .. . . - . . . . _ . . - . = . - ..
- ;; ^ ^ .
- 1ABLE 2 Susunary of' Bellows' Flaw Model Loading Data
' Initial' F1aw 'P1 ant' Flaw
' Load Case Description ~ Flaw Length: Growth Quantity Condition Orientation
- 1. -Baseline Bellows Model Using'As-; 1.7" None 1 IPCLRT- Axial
~.found f X-25 Flaw Data [See' O.5" None. 3 (48 psig 9 Axial.
Table"1] at IPCLRT 0.187" None 36 90*F) ' Axial' Conditions.
- 2. Worst Case Bellows Model Using X-25 1.7" 0.187" 1 IPCLRT Axial Bellows during Flaw Data with 3/16" Growth 0.5" 0.187" 3 (48 psig 9 Axial-
.IPCLRT for Each flaw-at IPCLRT 0.187" 0.187" 36 90*F) Axial.
Condition. 0.001" 0.'187" 200 Axial
- 3. Pinholed Bellows Bel _ lows Model Using TGSCC 0 0.187" 200 IPCLRT Axial during IPCLRT Crack Growth for a large- (48 psig 9 Quantity of Pinholes at- 90*F)
IPCLRT Conditions.
1 i
l
.. Z mg l
I f
m N ..
! IA COE-118-021 Attachment 1 QUAD CITIES BELLOWS ASSEMBLY SKETCH COE-118-021 NUTE[H ENGNEERS
O O
E >-
(4 ,,
s s
& _9
- \
= a 2
w ~
% NI u) u E CH 4
%>d b e w d W $
y N D k% 5 W $M >
%s R d A 3 U) E
% %) e S e a
" - a .g . w
- Q q U
_ . m ;s ,
f A O k .
a s l
u c, i i
// (M ls. !!
- 9 / /-- M ,I"$
a l I cd e
'l Q) --> %,
! t, ,
i :
J*h! _
\ b b i }' \\ % .
r s __
s El ,%i A-! :\ s v
S N
!= es
.:g s s =1 kd g$
u EW gS
i .
Attachment 2 QUAD CITIES BELLOWS FINITE ELEMENT MODEL CALCULATION 1
COE-118-021 NUTEEH ENGNEERS
FILE NO: COE118,0200,01
'. Nuntu . CALCULATION PACKAGE PROJECT NO: COE-118
,, ,,, C ALC. NO:- COE118. 02 00,01 PROJECT N AME: CLIENT:
Quad Cities Nuclear Power Commonwealth Edison Company Station Unit #1 C ALCUL AT'JN TITLE:
Determination of Longitudinal Crack Areas and Perimeter Lengths for the Quad Cities Unit 1 Bellows at Penetration X-25 PROBLEM $TaTEMENT OR OSJECTIVE OF THE C ALCVLATION-See Page 3 DOCUMENT AFFECTED REVISION PROJECT ENGINEER NAME AND INITIALS REVISION PAGES DES CRIPTION APPROVAL /DATE OF PREPARER 8 & CHECKERS 0 1- 41 Initial Issue hasl b6J " ' ' ' ' ' ~ . s#
?la h 3 --
fp e sp2M, PAGE 1 OF Mi QPNE 3 2,1.1 REV0
nutoch Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118.0200.01 OWNER COMMONWEALTH EDISON COMPANY _.
CLIENT COMMONWEALTH EDISON COMPANY TABLE OF CONTENTS PAGE NO.
INTRODUCTION 3 METHODOLOGY 4 ASSUMPTIONS 7 DETERMINATION OF AREAS AND PERIMETER LENGTHS 8 Calculations for 3/16" x 0.001" Crack 9 Initial Condition ILRT Condition Calculations for 1/2" x 0.001" Crack 12 Initial Condition ILRT Conditions Calculations for 1.7" x 0.010" Crack 17 Initial Condition ILRT Conditions Calculations for Pinhole with 3/16" Growth 22 Initial Condition ILRT Conditions Calculations for 3/16" x 0.001" Crack with 3/16" Growth 24 Initial Condition ILRT Conditions Calculations for 1/2" x 0.001" Crack with 3/16" Growth 28 Initial Condition ILRT Conditions Calculations for 1.7" x 0.010" Crack with 3/16" Growth 33 Initial condition ,
ILRT Conditions
SUMMARY
38 REFERENCES 40 REVISION 0 PAGE 2.
PREPARED BY/DATE PDB 3 4 S OF 4/
CHECKED BY/DATE g %4/gf
nutoch Chicago, Illinois 1
PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118.0200.01 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY INTRODUCTION The purpose of this calculation is to determine areas and perimeters of various cracks in a bellows convolution of the Quad Cities Unit 1 X-25 penetration type. The areas and perimeters will be determined for use in leakage calculations that will in turn be used to evaluate the condition of bellows.
Longitudinal (axial) cracks on a bellows convolution have been modeled using finite element methods and are of three basic dimensions. The dimensions utilized are based on flaws that were observed on the X-25 bellows that has recently been replaced, and include:
- 1) 1.7" long, 0.010" vide
- 2) 1/2" long, 0.001" wide
- 3) 3/16" long, 0.001" wide (Ref. 9)
The cracks will also be modeled such that each will grow 3/16" in length over a fuel cycle (Ref.d ), which brings the total number of dimensions modeled to six. In addition to the different dimensions, two different conditions for the bellows will be used to find areas and perimeters, which are:
- 1) Initially Measured, Undeflected condition
. 2) Integrated Leak Rate Test Conditions (48 psig, 90*: )
(Ref. 8)
The first undeflected condition areas are calculated only to provide a comparison to the deflected areas, not as input to the flow calculations.
A final surmary of the results is presented on Table 1.
REVISION O PAGE 3 PREPARED BY/DATE pog32/.9/ OF #/1 CHECKED BY/DATE 2 &6
nutech Chicago tilinois l
PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118.0200.01 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY METHODOLOGY A finite element model composed of plate elements formulated in three dimensional space was used to represent the X-25 type bellows.
symmetry in the axial and circumferential directions was utilized such that a 90' model of a half convolution cross section comprised the model (see Figures 1 and 2). Boundary conditions at the edges of the half convolution cross section and the O' and 90' model edges simulate the bellows convolution.
The cracks are placed near the 45' point where the mesh is considerably more dense than other areas in the model. The cracks were assumed to be at the crest of the bellows (Refs. 9 and 10) which dictates modeling only half the crack length (i.e., the middle of the crack is open at the top of the symmetric model).
The crack geometries are obtained from Reference S. Three initial geometries are used that are representative of the "as-found" conditions in bellows X-25. Cracks of 1.7 inches, 0.5 inches and 3/16 inches are modeled with thicknesses of 0.010", 0.001" and 0.001" respectively. Models with these cracks were then loaded with 48 psig (Ref. 8) internal pressure to simulate conditions during the Integrated Leak Rate Test (ILRT).
The three crack geometries were then lengthened by 3/16" to represent TGSCC growth over the course of a fuel cycle. Also, a pinhole model of zero length was assumed to grow 3/16". These new crack geometries were then loaded again with ILRT conditions.
The various geometry and loading combinations brought the total number of finite element computer runs to six. Three " pre-growth" ILRT runs and three " growth after fuel cycle" ILRT runs. After each run, the widened crack areas and perimeter lengths were determined by geometric means on the deflected (loaded) model. Deflected crack widths at various points were determined as well as associated deflected lengths along the cracks. These were combined to obtain deflected areas and perimeters of the cracks. These areas and perimeters are summarized in Table 1. Also included in Table 1 are the undeflected (unloaded) crack areas and perimeters for comparitive use.
REVISION O PAGE 4 PREPARED BY/DATE pogy.s3 9j OF 'l 1 CHECKE0 BY/DATE A- Js:,/p
'& ^'
o i :n n O ~ 'o I m m r 2
" *g E I 8 x > e m m o h
. _. 2 ;';
O m Z y
- o O O a s
, ,. - -g j O
{.
~ i s y
$ S O O >O
" z z o Q2Fl N & '
m m G_
2 or i
> > m t~ t- m w O $ $ c Z
~
~~
GEO%TRIES FRXt1 REF ' ~(
li w'. . . - y m m o a
~ ~ o
_ o_ m r
o o o o 1 O O g =rg I. i 0 NO g, E - 27.6 E6 pri .
"7 i O- -
G = /0,6E6 ac !
z '
i 2
- *--asty- -
/v = o.3c5 i ;;;
z 1 1 9 !
O.%!"
i' o
- O l
,- U I
- y ,.- 5; 1 l, o
\
' ta g i O f s
! Om i m >
-2 FIGURE .1 - SIDE VIEW OF MODEL CROSS SECTION WITH !.
$q GEOMETRIES AND MATERIAL PROPERTIES l l ,
l' f
nutoch Chic % lilinois UNIT *I PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO, CO E 118.0200.01 OWNER _ COMMONWEALTH EDISON COMPANY CUENT COMMONWEALTH EDISON COMPANY
> l 5* m
? t M 6
- i. <
H a ) l3 u m .
,....--~
n Q W , ,, vf }f (~g a_yCd.s'}'m[3 4 i IQ-j' a
,jg a ,<- -A.- -e d . -_. . ;j g
\ L1 x <g ! :\ -
r
< i < \ ;;:1 g,'w^"g ge -6.l
~
)
p w .
H
^
' f ^
j$
n W
j: h' _ , , $
a z*,e ~N. w~y
,7
// ,
u k
- " c r~; ;,* %. ;
O
/m / ..
t p
- "u!P 4 n
,9 jy ym m
O n;l r e
lllI l p, le n
- 111
++ t
- - n 12
. il![l.i.i m
- . - _.. a a >~
'c; j H ab I
!v 9 H m b b_
_ _ _ _ _ . _ _ _ . _ _ _ _ . . _ _ . _ . . _ _ _ _ _ . . _ . . _ . _. . _ _ . , _ _ Jg REVISION O I l PAGE b '
PREPARED BY/DATE p g 3.p ,q)
CHECKED BY/DATE KS/X/7)
1 nutoch Chicago, Illinois PROJECT-- QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118.0200.01 OWNER COMicONWEALTH EDISON COMPANY CLIENT- COMMONWEALTH EDISON COMPANY ASSUMPTIONS
- 1. The bellows was in its undeflected stress free state during the initial measurement of the-crack size and was at an ambient temperature of 90'F, 2.- The cracks are assumed to be rectangular in shape except near the-ends where they' taper to a point.
- 3. Thezbellows' convolutions behave ac the outer ply only since the inner ply will not resist prassure-as leakage progresses.
4.; Movements of the drywell will notieffect the width of the longitudinal crack; therefore, effects on area from these displacements will be negligible, g 'S 4
Crack'in X-Y Plane has Width in Z Direction d tuows S
} -
D=; j ,k >.
/.
Equivalent Axial Movement-Effective displacement in X-direction does not effect Z-direction-crack width.
- 5. 'The bellows'. convolutions behave as a linear elastic model.
'6. The crack dimensionsLare approximate -(Ref. 13).
.7.-- The effects of the phantom cracks-due to symmetry boundary
= conditions has a: negligible effect on the crack areas and
-perimeters due to the small size of the crack compared-to the L bellows-diameter.
'~
1 .
-REVISION- 0 PAGE 7 PREPARED BY/DATE- p{)g 3 y A /
OF s'!
CHECKED BY/DATE A 54v7 /-
nuteCh
. Chicogo, Illinois PROJECT _ QUAD CITIES NUCLEAR POWER STATION UNIT *1 FILE NO. COE118 0200 01 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY DETERMINATION OF CRACK AREAS AND PERIMETER LENGTHS The following calculations determine crack areas and perimeter lengths for the various conditions described earlier. The crack areas are calculated by summation of the smaller elements (rectangles and triangles) shown in Figures 3 through 8 The rectangular elements areas are approximated as follows:
Designated Element Areas of the Crack opening fi ELEMENT ELEMENT 6 2 2 w3 Radially wi Outward from Bellows Area of Element 1=fixwi Since w i is slightly larger than w2, the area for Element 1 is slightly copservative. However, since the widths do not vary by concernable amounts. The calculated areas are adequate values for the intended purpose of these calculations. The triangular elements are calculated using basic geometric principals and are precise.
REVISION 0 -
PAGE S PREPARED BY/DATE pg 3.g, 4/ V1 OF CHECKED BY/DATE A 3/ 4'/ n
-- - .- - .- _ _ _ _ . - - . _ . ~ , - .
a nutech Chicego, Illinois UNIT *l PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO. COE118.0200.01 OWNER COMMONWEALTH EDlSON COMPANY CLIENT COMMONWEALTH EDISON COMPANY Calculation for 3/16" x 0.001" Crack with Constant Length Initial Conditions:
Note: The following lengths and widths are retrieved from the undeflected Algor model (see reference J ). See page it for designation of the Element Numbers.
Element Length Width Number 1 w i := 1 .2 1 '0.050910' 'O.001123' 2 1 := ,0.025459, it) w := ,0.001134, in 3 L3 := 0.025466 in W3 := 0.001140-in Calculation of the Area of the Crack Opening:
a := w - l '0.000057 2 i i i a= ,0,000029, in ai = Area of each rectangular element for i th element a3 = Area of triangular element . .
. g3 .
Where, .d := L3 cos asin
. .L3 2. .
a3 := d - a3 = 0.000015.in l
2 A = Total area of crack opening A := ((Za) + a3) 2 2 -
A = 0'.000201.in ,
Calculation of the Perimeter of the Crack Opening:
P = Perimeter of opening P := ((21) + L3) 4 P = 0.407 in REVISION O PREPARED BY/DATE PDB 3 50-4/ PAGE op 4I CHECKED BY/DATE A 9//4/f/
nutcch Chicago, Illinois -
UNIT *I PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO. cnriin nSon ni OWNER COMMONWEALTH EDISON COMPANY CLIEN7 COMMONWEALTH EDISON COMPANY Calculation for 3/16" x 0.001" Crack with Constant Length ILRT Conditions:
Note: The following lengths and widths are retrieved from the deflected Algor model (see reforence ! ). See page iI for designation of the Element Numbers.
Element Length Width Number 1 w i := 1 .2 1 'O.050912' 'O.001176' 2 1 := 0.025467, in w := ,0,001179, in 3 L3 := 0.025467 in W3 := 0.001175 in Calculation of the Area of the Crack Opening:
a := w 1 'O.00006' 2 i i i a= ,0,00003, in ai = Area of each rectangular element for i th element a3 = Area of triangular element '
W3 Where, d := L3 cos asin L3 2
W3 2 a3 := d. - a3 = 0.000015 in 2
A = Total area of crack opening A := ((Ea) + a3) 2 2
A = 0.00021 in l
Calculation-of the Perimeter of the Crack Opening:
P = Perimeter of opening P := ((21) + L3) 4 P = 0.407-in REVISION O PREPARED BY/DATE Pog,3 2/, qf PAGE K OF CHECKED BY/DATE A /ff/y 9
l nutech Chicm, Illinois 1
l UNIT *l ;
PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO. COE118.0200.01
~ OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY j
J
)
l i E l o h ;
l n
._ a g
h lg ll i
._ . _ . ___ _ _6,j . _ .
W g
@ i s
- ~ - - ~ . _ _ . _ . _ ,
u
.4
- 4 hx b' N @
bs H
'Q l'hN _ . . . _ . _ , ,
_._ _ ._ __ _ j -
s\ T He N
\
E se H MN N }2 QM N'
- .. _ _ _ NN -
12.g - :
_~t__
y 3- ,
4 }c u %
v M
k H k
- _ . - . - - . .-.-- .- _m G
REVISION O PREPARED BY/DATE
~
PAGE //
P0b 3-26 4l q7 CHECKED BY/DATE hk/7/ .
nutcch Chicago, Illinois UNIT "I PROJECT OUAD CITIES NUCLEAR POWER STATION FILE NO, COE118.0200,01 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY Calculation for_0.500" x 0.001' Crack with Constant Length Initial Conditions Note: The following lengths and widths are retrieved from the undeflected Algor model (see reference 2. ). See page ' .
for designation of the Element Numbers.
Element Length Width Number 1 w i := 1 . 5 1 '0.050918' '0.001123' 2 0.050919 0.001134 3 1 := 0.050919 in w := 0.001147 in 4 0.050919 0.001143 5 0.050917, ,0,001140, 6 L6 := 0.025467 in W6 := 0.001226.in i
i
(
l 1
REVISION o PAGE I ~a PREPARED BY/DATE PDg 3.jg,4 OF N/
CHECKED BY/DATE A S/g fej
k
- nut @ch Chicago, Illinois I
UNIT 'l I 1
PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO. COE118.0200.01 OWNER COMMONWEALTH EDISON COMPANY i
CLIENT COMMONWEALTH EDlSON COMPANY 0.500" x 0.001" with Constant Length, Initial Conditions 1
Calculation of the Area of the Crack Opening: I a := w l '0.00005T i i i 0.000058 2 a= 0.000050 in ai = Area of each rectangular 0.000058 element for i th element ,0.000058, a6 = Area of triangular.eleme.nt '
W6 '
Where, d := L6 cos asin L6 2
W6 -
a6 := d -
2 2
a6 = 0.000016 in A = Total-area of crack opening A := ((Za) + a6) - 2 2
A = 0.00061.in Calculation of the Perimeter of the Crack Opening:
P-= Perimeter of opening P := ((El) + L6) - 4 P = 1.12 in i
REVISION O PAGE I PREPARED BY/DATE PD6 3 2f 4/
OF QI
- j. CHECKED BY/DATE p 4N/7/ _
. .. . .. .. ~. ._. -. - _ - - . -
. nutech Chicago, Illinoli j
UNIT "i PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO.
1 .0200.01 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY Calculation for 0.500" x 0.001" Crrek with Constant Length ILRT Conditions Note: The following lengths and widths are retrieved from the deflected Algor model (see reference 1 ). See page g for designation of the Element Numbers.
Element Length Width Number 1 w i := 1 .5 1 'O.050916 'O.001426' 2 0.050915 0.001423 3 1 := 0.050915 in w := 0.001418 in
- 4 0.050914 0.001373
'~
5 ,0,050910, ,0.001319, 6 L6 := 0.025473 in W6 := 0.001327 in HEVISION O
^ '
PREPARED BY/DATE Ppg 3Q(.4/
OF CHECKED BY/DATE p. Mg Ay
nutcch
'. Chicago. Illinois UNIT 'l Pron CT OUAD CITIES NUCLE AR POWER STATION pgg gg, COE118.0200.01 OWNER COMMONWEALTH ED3ON COMPANY CLIENT COMMONWEALTH EDISON COMPANY -_
0.500" x 0.001" with Constant Length, ILRT Conditions Calculation of the Area of the Crack Cpening a := w 1 '0.000073' i i i 0.000072 2 a= 0.000072 in ai = Area of each rectangular 0.00007 element for i th element ,0.000067, a6 = Area of triangular.eleme.nt '
W6 '
Whero, d := L6 cos asin
. .L6 - 2. .
a6 := d -
2 2
a6 = 0.000017 in A = Total area of crack opening A t= ((Za) + a6) 2 2
A = 0.000742 in Calculation of the Perimeter of the Crack Openingt P = Perimeter of opening P := ((II) + L6) 4 P = 1.12 in REVISION O PREPAMD BY/DATE ppP 3 2(,.q/
OF.
CHECKEf) BY!DATE g five/
l l __
I nLiteC1 Chicago, Illinois i
- UNIT 'l PROJECT OUAD CITIES NUCLEAR POWER STATION FILE No. Co t t 18.0200.01 l
OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY
___.7__._.~.._..,_.--_,_._.3~__7__.,.__.._-___,_.-__
i .
p
/ ; n Cd
- 4 i . ,
sc O N
i o i !
! H
.3 8
n
'o y '
t
_y . ,
3 ll p -
I 6
--)... i
=
1 r
t
.- N I
)
1 i U i
W i
g
-+-
j ; , j.
r 0
- I, 4, ! .
+ 8..
H
(~rf..i ; M E
i v
4 .' . .j '
- N i i 'M l f 4
T H
_q. i w tr) N
! D l , ;
yy i , e i N Q y.t l (m f, j__ . < _ . . . _
.8 g
7 ,
'^ '
t 1- ; ._ p M ii .. 1 f
t- t
,t
(
) ~h 1 f _.4 .e
-n -
J. _ _.
ca M
D w H D h I
REVISION O PAGE Ib PREPARED BY/DATE PDBS-X,-9/ ,j; CHECKED BY/DATE N %f/9/ . . .
nutech Chicago, Illinois UNIT 'l PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO.
j OWNER COMMONWEALTH EDISON COMPANY CUENT COMMONWEALTH EDISON COMPANY _
Calculation for 1.700" x 0.010" Crack with Constant Length Initial Conditions:
Not he o((owing lengths and widt.hs are retrieved from the undeflected Algor model (see reference J ). See page "
for designation of the Element Numbers. I l
Element Length Width l Humber 1 w i
i := 1 . 14 1 'O.050919^ '0.010000' 2 0.050918 0.010000 3 0.050919 0.010000 '
4 0.050919 0.009700 5 0.050918 0.009941 6 0.050919 0.010001 7 0.050919 0.010000 8 1 := 0.050918 in w := 0.010000 in 9 0.059750 0.009999 10 0.059750 0.009999 '
11 0.059749 0.010000 12 0.059751 0.010000 13 0.059749 0.010000
, 14 ,0.059751, ,0,010000, 15 L15 := 0.119604 in W15 := 0.010000 in REVISION O PREPARED BY/DATE 3p?)f.Q/ ' j7 g;'
CHECKED BY/DATE ,J2 flCA, OF
nutcch Chicago, Illinois UNIT 'l !
PROJE CT QUAO CITIES NUCLEAR POWER STATION FILE NO. COrsio 0?On ni OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY l
l 1.700" x 0.010" Crack, Initial Conditions l l
Calculation of the Area of the Crack Openings l a := w 1 '0.000509' i i 1 0.000509 1 0.000509 l ai = Area of each rectangular 0.000494 element for i th element 0.000506 2 a= 0.000509 in 0.000509 0.000509 a15 = Area of triangular element ' "
0.000597 1 f W15 0.000597 Where, d := L15.com asin 0.000597 L15 2
0.000598 W15 O.000597 a15 := d 0.000598 2
a15 = 0.000597.in A = Total area of crack opening A := ((Za) + a15) 2 2
A = 0.010475 in Calculation of the Perimeter of the Crack opening:
P = Perimeter of opening P := ((E1) + L15) 4 P = 3.542 in REVISION C PAGE / ,,
PREPARED BY/DATE p; e J.24.#/ g CHECKED BY/DATE ,ft 1/l(//f
nutech Chicago, Illinois UNIT "I PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO. COE118.0200.01 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY Calculation for 1.700" x 0.010" Crack with Constant Length ILRT Conditionst ,
Note: The following lengths and widths are retrieved from the deflected Algor model (see reference 2 ) . See page '.
for designation of the Element Numbers.
Element Length Width Number 1 w i := 1 . 14 1 '0.050910' '0.014814' 2 0.050919 0.014785 I 3 0.050918 0.014749 4 0.050921 0.014621 5 0.050918 0.014488 6 0.050923 0.014343 7 0.050919 0.014198 8 1 := 0.050920 in w := 0.013941 in 9 0.059749 0.013687 10 0.059746 0.013333 11 0.059742 0.012977 12 0.059740 0.012616 13 0.059736 0.012240 14 ,0.059735, ,0.011843, 15 L15 := 0.119622 in W15 := 0.011415.in i
. I REVISION g PREPARED BY/DATE PAGE 19 ppgf.jg I J',* 544 hj OF CHECKED BY/DATE
nutech Chicago, Illinois UNIT *I PROJE CT QUAD CITIES NUCLEAR POWER STATION FILE NO, COE M 8,0200,01 OWNER _ COMMONWEALTH EDISON COMPANY CUENT COMMONWEALTH EDISON COMPANY 1.700" x 0.010" Crack, ILRT Conditions Calculation of the Area of the Crack Opening:
a := w 1 '0.000754' i i 1 0.000753 0.000751 ai = Area of each rectangular 0.000745 element for i th element 0.000738 2 a= 0.00073 in 0.000723 0.00071 a15 = Area of triangular element "
0.000818 0.000797
' W15 "
Where, d := L15 con asin 0.000775 L15 2
0.000754 W15 O.000731 a15 := d. - 0.000707 2
a15 = 0.000682 in A = Total area of crack opening A := ((Za) + a15) 2 2
A = 0.022335 in Calculation of the Perimeter of the Crack Opening:
P = Perimeter of opening P := ((21) + L15) 4 P = 3.542 in REVISION C) ,
PREPARED BY/DATE Ppg 3.y,.4; j OF CHECKED BY/DATE
- 4Y/7f
. riutcch Chicago, Illinois UNIT 'l PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO. COE118.0200.01 OWNER COMMONWEALTH EDISON COMPANY CUENT COMMONWEALTH EDISON COMPANY 3 ,. . 7.
i!-
- I
?
[ l l l 'l f'
- }- .. r. - , . .
.l _j-
, .,i ,! .. q ,
)
is J,pj > ,'
f I f ! - -
. se t l l ;
t
}. L, ,
l o 4
1 4,Q'f @i4hl 4
- i i i i
! i (
j ,' ,,
j 7 -4 ,l ! l j
. --~ . f ])~7j7 i i
,L - .
<.4 .4 , .,. ., ; ,
I a i (g c 4 1 j l } 'j' --Q' 4 s j _4 ,
, i
}
l J p _.!. j_ ! i l si
- 1 1 i
a ..
( !. .
1
.o a
i
, *j cy I I i , . ,
, #> > - i
. t t.
I i
~li
- +
-k.._ ..
- ,i j - ,_ m _. _
r f
/ 1-.
i.
l.
e,, ql . # ., _, ,
l l.
.l l l' i l 4
i , w
- f. f ]- - ..
- f. j. { ,
I
- s I
f i ' ' W 4
j^
(
i
< - _ f,
. 9 ,i . .,1 _
- n. h 1 i .
u-
{
3 r-4.4_ - , .
l i
j {
i
- I a l' i
...L - ;
j_ ,
j #
h a i-
,,i - - -~ l : - '_ ,4 6 i j
.j ' ,
'j
}
j;-l j g 6 l
+
- f, i
g I
, 1 j1 1 i ..
d' " * ' '
T' j
~
i w
a -
-g e ..
a- p4 7 . . ,_ ,
(i i -
=_:/ .
V : i N g f,
--+~ yw !
l J . . a . . . 1, m j- ' . h. I ..- l H r-r _. ;.. 1 . l- - q~ . .. _ e .
~1:;7.'. - -m., ,
l @ g g , .
~=(= g
~
,E t'
- j. J . - - - m. .. . ..., , _
,4 ,
4.2 J ,- n 4; .._ . x,
~J .- s . - g T- ~. 3 g.,,,. -
.. + . - , -
p N
- - - ..~-.., ,. ,-
2 f ~<- - - i- _., _ ,
-_._ . r ~
p a _- n j x
'" " * * - - ' + - . . , - _ ...Q H..z. - - . m }[~.[-
~ .
J* lh 4 ~ ~ be crest J
. , . - - . - - - . - . _ . - - - . . - . .__ R REVISION O PAGE M I PREPARED BY/DATE fg 3.g 9/
0F CHECKED BY/DATE A,3/4/7) I
. . - . = - _ - . . - , . . . - . - . - - - - - . . , . . . . . , , ,. , - , , . -
n nutech Chicag0, Illinois i f PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118 0100.01 l OWNER COMMONWEALTH EDISON COMPANY CLIENT. ... COMMONWEALTH EDISON COMPANY l Calculation for Pinhole with a 3/16" Gr.gwth (x 0.001" Wide) Initial Condition Values for-area and-perimeter are equal to 3/16" x 0.001" crack I with constant length. See page 9 of this calculation. ILRT Conditient f Values for area and perimeter are equal to 3/16" x 0.001" crack ; with constant length.- See page !o of this calculation. ! t I l
=
REVISION o PAGE 22.
-PREPARED BY/DATE pg 32j,9j OF Y/
CHECKED BY/DATE g //gfq,j
9 nutoch Chicago, Illinois j i UNIT"I PROJE CT QUAO CITIES NUCLEAR POWER STATION,,gg go, COE M 8.0200.01 q I OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY Calculation for 3/16" x 0.001" Crack
............................................... with 3/16". Growth Initial Conditions Note: The following lengths and widths are retrieved from the undeflected Algor model (see reference 4 ). See page."
for designation of the Element Numbers. Element Length Width Number 1 w i := 1 .4 ; 1- '0.050918' 'O.001124' i 2 0.050919 0.001134 3 1 := 0.050919 in w := 0.001147 in 4 ,0.025459, ,0,001143, 5 L5 := 0.025466.in W5 := 0.001141 in { l REVISION O ,, PREPARED BY/DATE PPS 3 24-4/ h', OF CHECKED 8Y/DATE ,y 7/M /', / _m.
4 nutcch Chicago, Illinois j UNIT 'l PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO, COE118.0200.01 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY l l l 3/16" x 0.001" with 3/16" Growth, Initial Conditions l Calculation of the Area of the Crack Cpening:
)
a := w 1 'O.00005'T I i i i 0.000058 2 a= 0.000058 in l ai = Area of each rectangular ,0.000029, , element for i th element a5 = Area of tr ~. angular elen,ent ' WS ' Where, d t= L5 cos asin -- L5 2 W5 a5 := d - 2 2 a5 = 0.000015 in A = Total area of crack opening A := ((Za) + a5) - 2 2 A = 0.000434 in Calculation of the' Perimeter of the Crack Opening: P = Perimeter of opening P := ((Z1) + L5) 4 P = 0.815<in REVIsl0N O
~
PREPARED BY/DATE PAGE PO$ J.;6.Q) OF NI CHECKED SY/DATE
<fL 1/[(/7/
nutech Chicago, Illinois UNIT *I PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO, COE118.0200.01 OWNER COMMONWEALTH EDISON COMPANY CLIENT _ COMMONWEALTH EDISON COMPANY Calculation for 3/16" x 0.001" Crack with 3/16" Growth ILRT Conditions tiote: The following lengths and widths are retrieved from the deflected Algor model (see reference - ). See page .7 for designation of the Element tiumbers. Element Length Width 11 umber 1 w i := 1 .4 1 '0.050914' 'O.001292' 2 0.050914 0.001292 3 1 := 0.050914 in w := 0.001287 in 4 ,0.025456, ,0,001244, 5 L5 := 0.025470 in W5 := 0.001213 in
~
REVISION O PAGE PREPARED BY/DATE PolJ.J/ y/ f7 //4/en OF - CHECKED SY/DATE e
nutech Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER T ON FILE NO. OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY 3/16" x 0.001" with 3/16" Growth, ILRT Conditions Calculation of the Area of the Crack Opening: a := w 1 'O.000066" i i i 0.000066 2 a= 0.000066 in ai = Area of each rectangular ,0,000032, element for i th element a5 = Area of triangular.eleme.nt ' WS ' Where, d := LS cos asin
. -LS 2 .
a5 := d - 2 2 a5 = 0.000015 in A = Total area of crack opening A := ((Za) + a5) 2 2 A = 0.000488-in Calculation of the Perimeter of the Crack Opening: P = Perimeter of opening P := ((E1) + LS) 4 P = 0.815 in i REVIGION C .., PAGE - PREPARED BY/0 ATE PDS S2H/ af CHECKED BY/DATE /7 V6/ci
nutoch Chicago, Illinol ; 1 UNIT "i l PROJE CT QUAD CITIES NUCLEAR POWER STATION FILE NO. COE 118.0200.01 I OWNER COMMONWEALTH EDlSON COMPANY CLIENT COMMONWEALTH EDISON COMPANY
=
7 _7 ,
- - - - _ - - - . , - i j .i l $
m _1l 1 4._ i
' } ll
; m .
6
! l l F
> i ! , ,,
\ . I ; 3
~4__.- .. _ ..{,. [ ,
g < . ii 3 l ! 2 1 0 , ~~ -.__ -.- g_ -. g . _ _ . . W s 4 i 9- .- ,
- s 4 w g..,._ _ ,,_ , j _
! l
]
l ! ,& S , I 4
~
I 1 i p f e..
. . _ _ , _ . , _ _ . . . - . _ . _ _ . _ _ y - --
y
- - ];. t M ,
j e N ch j ,T Mw _@ , _A
! N
~ _ , . _ . _ _ . _ . . . _ , _._ . _ , _ j .. s._
j
, 4. -
e g ; 1 = .
~ _ _ _ ___ -l ; y , ;
y~ v .
- -a -. - .- _____ _
y n
~___ _ _J___J__.._ .g. ,
y m W M m cc 5
- la V
REVISION .O PAGE 27 PREPAR'iD BY/DATE PDS 3.X,-(/ YI OF
' CHECV'.D BY/DATE ; g J/ A g j
..i.._ ,_...;. ,.A.__-....-..-_.._,.._.-_.._. ...-..;,_,..
. . . .u .m .m , - . . . . , - , , - , , - - - _ , _ . . , _ . - , ,
nutcch Chicago, Illinois UNIT 'l PROJECT _ QUAD CITIES NUCLEAR POWER STATION FILE NO. OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY Calculation for 0.500" x 0.001"
................................................ Crack with 3/16". Growth Initial conditions:
tiote : The following lengths and widths are retrieved from the undeflected Algor model (see reference !' ). See page il for designation of the Element 11 umbers. Element Length Width 11 umber 1 w i := 1 .7 1 'O.050918' 'O.001123' 2 0.050919 0.001134 3 0.050918 0.001147 4 1 := 0.050919 in w := 0.001143 in 5 0.050919 0.001140 6 0.050918 0.001226 7 ,0.025460, ,0,001226, 8 L8 := 0.025467 in WB := 0.001224 in O 1 REVISION PREPARED BY/DATE PAGE 13 PDr3 324 9) 7 OF. CHECKE0 BY/DATE fu I/N/f/
nutech Chicago, Illinois PROJECT OUAD CITIES NUCLEAR POWER NAT FILE ON NO. OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY 0.500" x 0.001" with 3/16" Growth, Initial conditions Calculation of the Area of the Crack Cpening: a := w 1 'O.00005T i i 1 0.000058 0.000058 2 l ai = Area of each rectangular a= 0.000058 in element for i th element 0.000058 0.000062 i 0.000031, ) a0 = Area of triangular .eleme.nt gg . . Where, d := L8 cos asin L8 2 '~ W8 a0 :=d-2 2 a0 = 0.000016 in A = Total area of crack opening A := ((Za) + a8) 2 2 A = 0.000798 in Calculation of the Perimeter of the Crack Cpening: P = Perimeter of opening P := ((E1) + LB) 4 P = 1.426 in i l l R E VISION O - PAGE PREPARED BY/DATE Pp3 J g.9/ ,, OF j CHECKED BY/DATE l@ 3/;,f /cf
nutcch Chicago, Illinois UNif*l PROJECT OUAD CITIES NUCLEAR POWER STATION FILE NO. COE118.0200.01 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY Calculation for 0.500" x 0.001" Crack with 3/16" Growth i ILRT Conditions: Note: The following lengths and widths are rgtrieved from the deflected Algor model (see reference 0 ). See page ??. for designation of the Element Numbers. Element Length Width Humber 1 w i := 1 ... 7 1 O.050917' '0 001567'
- ' 2 0.050917 0.001563 3 0.050917 0.001558 ,
4 1 := 0.050916 in w := 0.001512 in l 5 0.050913 0.001461 6 0.050916 0.001400 , 7 0.025455 0.001398 l l . 1 8 L8 := 0.025474-in W8 := 0.001346 in 4 REVISION O M
~
PAGE PREPARED BY/DATE fy)3 y.,;g;-4f CF I CHECKED BY/DATE /2 //g/yj_. e + .a , - . c , ----...,en, ,ne..., ,- , . , . , , , ---s. ..a-- r.,m,-..,1,,,,~-,,e--e,. .- ,,.,---,,,w,- ,,,w,._, , . - . - - -
. . _ _ . . _ _ . . . .__.____...__.___..._m_ m___. _ _ _ _ ._ ___. _ _ _ .._ __ . - _ _ _ . _ . _
i
~
nutech Chicago, Illinois l UNIT "I ! PROJECT QUAD CITIES NUCLEAR POWER STATION FILE NO. OWNER COMMONWEALTH EDISON COMPANY CUENT COMMONWEALTH EDISON COMPANY l 0.500"x 0.001" Crack with 3/16" Growth, ILP.T Conditions Calculation of the Area of the Crack Cpening: a := w 1 " 0.00008' i i i 0.00000 0.000079 2 ai = Area of each rectangular a= 0.000077 in element for i th element 0.000074 0.000075 !
,0.000036, a0 = Area of triangular. element i gg . .
Where, d := L8 cos asin
. .L 8 2. .
i j g I a0 := d - I 2 J 2 a0 = 0.000017 in A = Total area of crack opening A := ((Za) + a8)-2 2 A = 0.001036 in Calculation of the Pe.ilreter of the Crack Cpening: P = Perimeter of opening P := ((E1) + LB) 4, P = 1.426 in REVISION ,
-C ,
PREPARED BY/DATE Poo*3 X 4/ Op "I CHECKEO BY/DATE y 44(/ef
r nutoch , Chicago, Illinsis ! 6
- UNIT *\
PROJECT OVAD CITIES NUCLEAR POWER STATl0N FILE No. COE118.0200.01 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY e (
. . ~ .
_ . b, _ .
,t 1
[ 4 j l I i ;$ 5 t l [ !
)
- j. 1r ll
> .l \
?
f '8C 3 l' e ' o h . 1 y N. -j ' (
-l- y4 '
... y _j
.l l i b i i ! ,!3
, ),
) l i ! #
1 i F f
. _ .4' .
- i i 1 q 4 9- _;. ,,
~ . f f f I e
h j l ! L ! T w I i
. -j - h
+.
I 4 : W v4 g
.9 - _
q._. j ig i , i i. a ! ! 4 m j. i ; ! ! i-
, l ! 1 I i 1 A 4...< -m , - - _ . . ,,
* !! 1 l j\ tue
. . , . ,, _w f l I 4 f !S N l i .
i f. - 4
]
3
.,h, . _-. - - -- 4_ . . ,
... _ , [
. ,[_ L[.
3.. 4 l g i /- Q 3" l ! t
- - .J . .-._ _ i _ _.__j .. _1[ , ;
l
!$s H i
I i i- ._,e N _f y- . . . - I I. l R
- n
, y -- .
-p_p I
f_ ._ _._I. I W ',
. j Q-3 H
g xL- s v4
, . . . - ~ . . - . , ~ _ . _ . . , . _
; i $g .
l !
^~
f.. -l
^ p- y, l 1 ,
eu
- ~- . - _ .__.._; _ __ - '
7 _-. . . 7 .
- ]v s)jc -6
,-~~- ~ ~ ,_ __.
_ , . _ _ ---{,~-
- g*
_.__.q-._._._______ q y .- rn
.-._ ~ ,
y3373; ( _ _J _ -
- c. 3Q w
$ e H v , _ . . _ ~ . . , . . . . . , _ . ~ , _ . _ - . _ _ _ . . _ _ _ . s V) p h L REVISION O PAGE 32 PREPARED BY/DATE PDS J W fj g OF CHECKED BV/DATE d #/t4/f/
t. t . .- , - . -.-.-_-.-.-._;,-_..._,_..__ .
nutcch Chicago, Illinois UNIT 'l PROJECT QUAD CITIES NUCLEAR POWER STATION FILE No. COE M.0200.01 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY Calculation
...................... for 1.700".x
................................. 0.010" Crack with 3/16" Growth j Initial Conditiones Note: The following lengths and widths are retrieved from the deflected Algor model (see reference 6 ) . See page 17 for designation of the Element Numbers.
Element Length Width Number 1 w i := 1 . 16 1 '0.050919' '0.010000' 2 0.050919 0.010000 3 0.050918 0.010000 4 0.050919 0.009970 5 0.050918 0.009941 6 0.050919 0.009970 7 0.050918 0.010001 8 0.050920 0.010000 9 1 := 0.059749 in w-:= 0.010000 =in 10 0.059750 0.009999 11 0.059750 0.009999 12 0.059749 0.010000 13 0.059750 0.010000
. 14 0.059749 0.010000 15 0.059751 0.010000 16 ,0.059749, ,0,010000, 17 L17 := 0.101960 in W17 := 0.010001 in ,
4 a REVISION C ,, PAGE PREPARED BY/DATE PD3 3.gq/ OF CHECKED BY/DATE ,)t J/,4/q
nutech Chicago, Illinois l UNIT *l PROJE CT OUAD CITIES NUCLEAR POWER STATION FILE NO. OM W.0200.01 OWNER COMMONWEALTH EDISON COMPANY , CLIENT COMMONWEALTH EDISON COMPANY , 1.700" x 0.010" Crack with 3/16" Growth, Initial Conditions Calculation of the Area of the Crack Cpening: a := w 1 '0.000509' i i i 0.000509 0.000509 ai = Area of each rectangular 0.000500 element for i th element 0.000506 2 a= 0.000500 in 0.000509 0.000509 a17 = Area of triangular element ' " 0.000597 W17 ' 0.000597 Where, d := L17.com asin . 0.000597 L17 2 0.000597 W17 O.000598 al? := d 0.000597 2 0.000598 2 ~ 0.000597 ' al? = 0.000509 in A = Total area of crack opening A i= ((Za) + a17)-2 2 A = 0.018713 in Calculation of the Perimeter of the Crack Opening P = Perimeter of opening P := ((21) + L17) 4 P = 3.949 in REVISION Q PAGE 50 PREPARED BY/DATE )g 34.q) OF N CHECKED BY/DATE .ht V;4/7j
. nutech Chicago, Illinois UNIT *I PRonCT QUAD CITIES NUCLEAR POWER STATION FILE No. COE118.0200.01 OWNER COMMONWEALTH EDISON COMPANY CUENT COMMONWEALTH EDISON COMPANY Calculation for 1.700" x 0.010" Crack with 3/16" Growth ILRT Conditions Note: The following lengths and widths are retrieved from the deflected Algor model (see reference 6 ). See page it for designation of the Element Nwnt.ers.
Element Length Width Number 1 w i := 1 . 16 1 'O.050918' 'O.016992' 2 0.050919 0.016945 3 0.050918 0.016891 4 0.050921 0.016711 5 0.050919 0.016528 6 0.050922 0.016304 7 0.050918 0.016081 8 0.050921 0.015733 9 1 := 0.059747 in w := 0.015387 in 10 0.059745 0.014926 11 0.059741 0.014469 12 0.059737 0.014007
. 13 0.059734 0.013536 14 0.059730 0.013051 15 0.059728 0.012547 16 ,0.059725, ,0,012011, 17 L17 := 0.101989 in W17 := 0.011426 in REVISION g PREPARED BY/DATE PAGE E6 POB F 2M/ - ~~I OF CHECKED DY/DATE g f/;g
o nutech Chicago, Illinois UNIT 'l PRO.lE CT - QUAD CITIES NUCLEAR POWER STATION FILE No. cor t i a.0200.01 OWNER COMMONWEALTH EDISON COMPANY CLIE NT COMMONWEALTH EDISON COMPANY 1.700" x 0.010" Crack with 3/16" Growth, ILRT Conditions Calculation _of the Area of the Crack opening: a := w 1 '0.000865' i i 1 0.000863 0.00086 ai = Area of each rectangular 0.000851 element for i th element 0.000842 2 a= 0.00083 in 0.000819 0.000801 a17 = Area of triangular element ' 0.000919 1
' W17 '
O.000892 i Where, d := L17 com asin 0.000864 L17-2 0.000837
- W17 O.000809 al?
- = -d - 0.00078 -
2 0.000749 2
- 0.000717
- al? = 0.000582 in A = Total area of crack opening A := ((Ia) + a17) 2 2
A = 0.027759 in Calculation of the Perimeter of the Crack opening: P = Perimeter of opening P := ((Z1) + L17) 4 l P = 3.949=in_ l REVISION C ,_,
^U '
PREPARED BY/DATE ' POS 3 24-4/ a OF l CHECKED BY/DATE JC 34de s L . -
.~. - - .. . - ~.-. - - - - -.- .
- /
4 nutech Chicago, Illinois 9 PROJECT QUAD CmES NUCLEAR POWER STATION UMT #1 FILE NO. .COE118 0200 01 OWNER COMMONWEALTH EDISON COMPANY Cl. LENT COMMONWEALTH EDISON COMPANY StHMARY 4 The results are listed in Tables la and ib. The significant results are the ILRT conditions only. Initial areas and perimeters are added for comparative purposes. It should be noted that the " Pre-Growth" 3/A6" condition and the " Growth After Fuel Cycle" condition is the . same. J \ REVISION O PAGE.lS_. PREPARED BY/0 ATE g f 4 4/ OF- @ CHECKED BY/DATE p h,V/el
nut @ch Chicag0, Illinois i PROJECT ,0UAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. __COEi18 0200.01 OWNER __t0MMONWEALTH EDMON COMPANY CLIENT COMMONWEALTH EDISON COMPANY TABLES la AND lb AREA BUMMJhalIl
" PRE-GROWTH" CONDITIONS Crack Length / Loading Area (in ) 8 Perimeter (in) 3/16" Initial 2.01 E-4 0.407 3/16" ILRT 2.10 E-4 0.407 0.5" Initial 6.10 E-4 1.12 0.5" ILRT 7.42 E-4 1.12 1.7" Initial 16.5 E-3 3.54 1.7" ILRT 22.3 E-3 3.54 (la)
" GROWTH AFTER FUEL CYCLE" CONDITIONS Crack Length / Loading Area (in ) 8 Perimeter (in)
- 0" + 3/16" Initial 2.01 E-4 0.407
- 0" + 3/16" ILRT 2.10 E-4 0.407 3/16" + 3/16" Initial 4.34 E-4 0.815 3/16" + 3/16" ILRT 4.88 E-4 0.815 0.5" + 3/16" Initial 7.98 E-4 1.43 0.5" + 3/16" ILRT 10.4 E-4 1.43 1.7" + 3/16" Initial 18.7 E-3 3.95 1.7" + 3/16" ILRT 27.8 E-3 3.95 (1b)
*Also listed for " Pre-Growth" Conditions.
REVISION 0 n PAGE s ' PREPARED BY/DATE P08344/ or y/ CHECKED BY/DATE @ 7/l4/9f
nutech Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT si FILE NO. __ COE110.0200 01 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY
REFERENCES:
- 1. Algor Computer Model " Quad Cities Unit #1: Bellows at Penetration X-25 with 3/16" x 0.001" Crack at ILRT Conditions." Dated 3/25/91, 1125 P, File No.: COE118.0200.01,
- 2. Algor Computer Model " Quad Cities Unit #1: Bellows at Penetration X-25 with 1/2" x 0.001" Crack at ILRT Conditions." Dated 3/24/91, 10:50 P, File No.: COE118.0200.01.
- 3. Algor Computer Model " Quad Cities Unit #1: Bellows at Penetration X-25 with 1.7" x 0.010" Crack at ILRT Conditions." Dated 3/25/91, 8:36 P, File No.: COE110.0200.01.
,/ ei !!!ti in -
- 4. Algor Computer Mode Quad Cities Unit #1: Bellows at Penetration X-25 with 3/16" x 0.001" Crack,at ILRT Conditions." Dated 3/26/91, 7 49 A, File No. COE118.0200.01.
- 5. Algor computer Model " Quad Cities Unit #1: Bellows at Penetration X-25 with 1/2" x 0.001" Crack with 3/itl" Growth at ILRT Conditions." Dated 3/25/91, 9:45 P, File No. COE118.0200.01.
- 6. Algor Computer Model " Quad Cities Unit #1: Bellows at Penetration X-25 with 1.7" x 0.010" Crack with 3/16" Growth at ILRT Conditions." Dated 3/25/91, 8:36 P, File No. COE118.0200.01,
- 7. Pathway Bellows Drawing "18" Tandem Expansion Joint Assembly; Quad Cities Unit 1 & 2, Item X-25" Drawing No. 8052, Rev. O, File No. COE118.0160.
- 8. Updated FSAR for Quad Cities Unit #1, HUTECH Library.
- 9. NUTECH Communication Record by Ray Rosten, " Meeting on Quad Cities Bellows Leakage." Dated 3/22/91, No. RWR-91-024, File No. COE118.0001.
- 10. System Materials Analysis Department Repo:c on Inspectdon of the X-25 Drywell Penetration Bellows at Quad Cities Station, No.
M-1243-91 dated 3/12/91, File No.: COE118.0160.
- 11. Mark's Standard Handbook for Mechanical Engineers 7th Ed.
REVISION 0 l g g PREPARED BY/0 ATE (93 jgj 4 0F W CHECKED BY/DATE (t 4<Ne
nutech Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT *1 FILE NO, COE118.0200 01 1 OWNER COMMONWEALTH EDIRON COMPANY CLIENT COMMONWEALTH EDISON COMPANY
- 12. Computer Program Verification Document, File No. QA !
SJ0. SOFT.165.9.0.
)
- 13. Nures - Algor finite Element Analysis Software, Version 9.0, No. 2.165.9.0. File REVISION O PAGE W
_ PREPARED BY/DATE pp3 fg.9/ OF 47 CHECKED BY/DATE @ J/l4/./
= . :_ . _ . _ - - -
1 . 1 I Attachment 3 QUAD CITIES BELLOWS LEAKAGE TLOW CALCULATION COE-118-021 t4UTEEH Et40lt4EERS
l
' flLt No: COE118.0200.02 Hu , CALCULATlON PACKAGE PMosicTNo- m .118 l
amieese, e CALC.NO: COE118.0200.02 PROJECT H AME: CLitNT: 1 Quad Cities Nuclear Power Commonwealth Edison Company 2 station Unit #1 C ALCUL ATION TITLt 2 Dwtermination of Flow Rate Through Observed and Postulated Cracks. PROBLLM STATEMENT OR OBJECTIVt OF THE CaLCULATICN: The objective of this calculation is to determine the flow rate through an observed crack, postulated pinhole cracks and projected cracks (after growth) in the X-25 penetration bellows at Quad Cities Unit 1 during 1LRT conditions. Leak rates are calculated from an analytical model, representing compressible, choked flow through a thick walled orifice located in a wall of intinite area with a discharge coefficient based upon crack wall roughness. DOCUMENT AFFECTED REYlSION PROJECT ENQiNEth NAME AND IN:TIALS REvill0N PAGES DESCRIPTIC#N APPROVAL /DATE OF PREPARER 8 & CHECAtRS o 1-:- Initial leeue .Mbg h N
&mf)iA &j( ('. dJ*uS 321-H 8cJ N NE 3 2,1.1 REV 0
~- .-
i nutech Chicago, Illinois PROJECT _ QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118.0200 02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO. 1.0 PURPOSE ,- 2.0 METHODOLOGY ?
~
3.0 NOMENCLATURE 4.0 ANALYTICAL MODEL UTILIZING COMPRESSIBLE FLOW THROUGH A THICK WALLED ORIFICE LOCATED IN A WALL OF INFINITE AREA ' 5.0 ANALYTICAL MODEL FOR FLOW RATE THROUGH " PINHOLE" CRACKS WITH LAMINAR AND TURBULEhT COMPRESSIBLE FLOW _; 6.0 PREDICTION OF LEAKAGE RATES AT ILRT CONDITIONS DUE TO CRACK GROWTH AFTER ONE FUEL CYCLE
7.0 REFERENCES
REVISION 0 - PAGE ' PREPARED BY/DATE '1%/;-y;.p ~~ 0F CHECKED BY/DATE ; r/S-34
nutoch Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE 118.0200.02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY 1.0 PURPOSE This calculation will attempt to quantify the leakage through the observed cracks in bellows penetration X-25 at Quad cities Unit
- 1. Additionally, the calculation will determine a worst case leak rate to be expected through postulated " pinhole" cracks.
Finally, the calculation will determine the leak rate during ILRT uenditions after the observed cracks have been allowed to grow 3/16" in length. 2.0 METHODOLOGY Modeling the leakage through the observed cracks will be attempted utilizing an analytical method based upon compressible, choked flow through a thick walled orifice located in a wall of infinite area with a discharge coefficient based upon crack wall roughness. Thermodynamic and hydraulic parameters utilized within-the models are based upon conditions inside the bellows during the integrated leak rate test (ILRT) at 49 psig and 90*F. The resistance coefficients were calculated utilizing measured crack geometries and quantities such as crack opening under load determined by finite element methods. The model results will be benchmarked against a cumulative measured crack leakage flow rate from bellows penetration X-25 at Quad Cities Unit 1 of 137.4 SCTH. The analytical method will be applied to the 3 major crack sizes in an attempt to predict the observed flow rate. This model was selected because of its accurate representation of actual flow conditions and geometries. Section 4 of this calculation will present the results of the leakage rates through the cracks predicted by the analytical method for three different populations of crack sizes. The three crack sizes based on length are: 1.7 inches 0.5 inches 3/16 (.1875) inches Section 5 of this calculation will determine the worst case leak rate expected from the cracks characterized geometrically as
" pinholes". This section uses two analytical methods to model the " pinholes" which bound the flow regimes (i.e. laminar and turbulent, choked). The method giving the largest flow rate is selected.
REVISION 0 PAGE s PREPARED BY/0 ATE py/3.p.9, 7 CHECKED BY/DATE m/3.p . ,,
?
nutech
. Chicago, Illinois I
PROJECT _ QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. _ COE118.01QO 02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY section 6 of this calculation will present r. methodology along with a justification for scaling the measured leak rate through observed cracks during a recent ILRT to a future ILRT. The future ILRT will be performed at the end of a fuel cycle where the leakage is postulated to occur through a similar population of cracks as observed above that have been allowed to grow a specified amount as predicted by fracture mechanics. REVISION 0 m PAGE > I PREPARED BY/DATE g/3,7,' % OF
~~
l CHECKED BY/DATE o /;.;g
nutoch Chicago, Illinois s l PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1. FILE NO. COE118.0200.02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY 1 1
)
3.0 NOMENCLATURE REVISION O ~ PE ' PREPARED BY/DATE q9/y3'7' 0F 7 CHECKED BY/DATE 2',/.;2.a
nutOch Chicago, Illinois PROJECT QUAD CITIES NUCLEAR PO'WER STATION UNIT #1 FILE NO. COE 118,0200.02 l OWNER COMMONWEALTH EDl10N COMPANY I CLIENT COMMONWEALTH EDISON COMPANY No m CLATURE Q = Volumetric flow rate outside the bellows O G = Mass flow rate t = Temperature inside the bellows 1 I l P = Pressure outside of bellows- l 0 i P = Pressure-inside of bellows l 1 a = Crack area D = Hydraulic diameter h A = Hydraulic area h R = Wall / crack roughness a. f = Friction factor 1 = Depth of crack V = Width of crack n = Polytropic index C = Flow' discharge coefficient d C = Temperature in degrees Celsius P = Density of air at standard temperature and pressure o REVISION g , PAGE o l PREPARED BY/DATE pd /3,pg.g __ l CHECKED BY/DATE p / 7 2:; N l l
nutech Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118 0200,02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY p = Density of air inside bellows 1 4 = Absolute viscosity k = Specific heat ratio v = Sonic velocity s Re = Reynolds number R = Ideal gas constant AP = Actual pressure ratio ratio CP = Critical pressure ratio ratio 1 = Friction coefficient REVISION o , PAGE PREPARED BY/DA1E g h.3h 0F M ~~ CHECKED BY/DATE =c:/j 2 74,
- nut @ch
, Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118.0200.02 .
OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY 4.0 ANALYTICAL MODEL UTILIZING COMPRESSIBLE FLOW THROUGH A THICK WALLED ORIFICE LOCATED IN A WALL OF INFINITE AREA REVISION 0 l PAGE PREPARED BY/DATE g/3 29 1 '7 0F CHECKED BY/DATE s /2 27 '#
nutoch Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118.0200 02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY BASELINE CALCULATION FOR ILRT CONDITICNS l I PURPOSE l The purpose of this calculation is to determine flow rate through various postulated cracks in the X-25 bellows at Quad Cities Unit 1. II ASSUMPTIONS
- 1. The area at the entrance to the crack is equal to the area at the exit of the crack.
l
- 2. The mest restrictive losses occur at the outer bellows ply, )
therfore the annulus between plys is at ILRT pressure and all I losses can be attributed to one bellows ply. 1
- 3. Due to the irregular shape of the crack opening, all the models will utilize an area based on the hydraulic diameter of the opening. 1
- 4. The model used for this calculation is based on compressible, choked flow through a thick-walled orifice located in a wall of infinite area.
III INITIAL CONDITIONS
- 1. Pressure and temperature in the containment is a constant at 49 psig and 90F, respectively=per reference 1,
- 2. Pressure and temperature outside the containment are at standard atmospheric conditions.
- 3. The calculation has been performed three times for crack lengths of 1.7, 0.5, and 0.1875 inches. In addition, an idealized flow rate (i.e., discharge coefficient = 1.0) for-the 1.7 inch crack was calculated.
- 4. A uniform wall thickness of 0.0351 inches exists for all cracks.
REVISION o PAGE PREPARED BY/DATE g /,. 3 9 ._ CHECKED BY/DATE ks /b a d.
nutsch Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. - COE118.0200.02 OWNER COMMONWEALTH EDISON COMPANY CLIENT. COMMONWEALTH EDISON COMPANY IV CALCULATION For the 1.7 inch crack A. Determination of Flow Conditions The following is a list of parameters to be used in throughout this calculation. P= := 49 psig ILRT guage pressure (Ref 1) 1 P := 0 psig guage pressure 0 (outside containment) P := 14.7-psia atm P := P +P P = 63.7-psia ILRT abs. pressure 1 1 atm i P := P +P P = 14.7 psia Abs. pressure 0 0 atm 0 (outside ent.) 5 5 P = 4.3932 10 -Pa P = 1.0138 10 Pa 1 0 lb kg Density 0 90 F &- p := 0.313- p = 5. 01 - 49 psig (Ref 2) 1 3 1 3 ft m 1 := 0.035 in -4 Bellows wall 1 = 8.89 10 4 m thickness (Ref 9)
-6 R := 5 10 m Wall Roughness a (Ref 7) i REVISION g p 7 PREPARED BY/0 ATE 7-m/7 3,9', 0F CHECKED BY/0 ATE. 91/3129
nutech Chicago, Illinois e PROJECT OUAD CITIES NUCLEAH POWER STATION UNIT #1 Fil.E NO. COE118.0200.02 . OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY t := 305.37 K ILRT containment temperature 1 (Ref 10) 2 m R := 287- Gas Constant 2 (Ref 10) sec K
-5 a := 1.87 10 Pa see Absolute Viscosity (Ref 5) 9 90F, 32.2C k := 1.4 Ratio of constant pressuie to constant volume (ReRef Next, the conditions for choked flow to exist will be checked by comparing the actual pressure ratio to a critical pressure ratio.
Critical Pressure Ratio (for compresible nozzle flow): k
. . k-1 CP := CP = 0.5283 ratio .k + 1, ratio (Ref 5, page 348)
Actual Pressure Rati : P O - AP := AP = 0.2308 ratio P ratio 1 CP > AP , therefore the flow is choked. (Ref 5, page 348) REVISION p PAGE ;, PREPARED BY/DATE q /3 7,9 _' CHECKED BY/DATE gs'/7.i? c/
! nutech l.. Chicago, Illinois l l PROJECT QUAD CITIES NUCLEAR POWER STAT lON UNIT #1 FILE NO. COE118.0200.02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY Due to the crack configuration, a hydraulic diameter will be calculated in order to determine the Reynold's number for the flow through the crack. Hydraulic Diameter Determination:
-3 2 -5 2 a := 22.335 10 in a = 1.441 10 m Crack Area (Ref 3) p := 3.542 in p = 0.09-m Crack perimeter (Ref 3) a -4 D := 4-- D = 6.4067 10 m Hydraulic dia h p h (Ref 4) 2 l D h -7 2 A := n- A = 3.2237 10 m Are based on h 4 h hydraulic dia.
(Ref 4) B. Calculating-the discharge coefficient for a thick-walled deep orifice L -The discharge coefficient (Cd) will be determined from the coefficient of fluid resistance (f). The coefficient of fluid resistance will be determined using Table 2-2 of Reference 6, the Reynold's number (Re), the relative wall roughness (Rr), and friction coefficient (A) . 1 i REVISION- - O PAGE ' 4. l PREPARED BY/0 ATE g/. 7 g . l .CHECKEb SY/0 ATE tc :/ 7.p. y
nutsch Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118,02OO.02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY since the flow has been determined to be choked, the velocity of the medium is sonic. Thus, the velocity (Vs) through the crack is: 0.5 m V := 'k'R t V = 350.2823- (Ref 5, Eq 11.3) s , 1, s sec Reynold's Number: D h 4 Re := p V Re = 6.0124 10 (Ref 5, page 153) 1 s u Relative Roughness: R a R := R = 0.0078 (Ref. 6, page 80) r D r h Based on the ratio of the wall thickness or crack depth (1) to the hydraulic diameter, the initial coefficient of fluid resistance (fo) can be obtained from Reference 6. 1 Ratio := Ratio = 1.3876 D h Therefore, f := 1.62 (Ref 6, page 174) 0 The friction coefficient (1) is the friction res'istance of a segment of relative unit length and can be obtained from Table 2-2 of Reference 6. X := 0.032 (Ref 6 page 80) REVISION g > p PREPARED BY/DATE g/gg.gr OF
~ ~ '
CHECKED BY/DATE P;/ F)7. m
l nut @ch
. Chicago, Illinois j i
l
- PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118.0200.02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY coefficient of fluid resistance:
i f := f +1- - f = 1.6644 (Ref 6 page 174) 0 0
.h.
Discharge coefficient (accounting for losses in the nozzle): 1 i_ C := C = 0.7751 (Ref 6, page 35) d 0.5 d f t I C. Mass Flow Rate (for choked flow): 1 l k-1 ' 0.5 2 2k' G := C A 9 P (Ref 6, page 35)- d h ,k + 1 ,
,k v 1, 1 1, l -4 kg l G = 2.5383 10
(' cac lb kg i p := 0.0764- p = 1. 2 2 2 9 + -- (Ref 2, O psig, 60 F) l- 0 3 0 3 i ft m l i G 3 Q := -4 m 0 p Q = 2.0757 10 0 0 sec l REVISION I' PAGE PREPARED BY/DATE g/3,g. g ,7 CHECKED BY/DATE 50/71?-9 {
nutech Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT *1 FILE NO, COE118.0200.02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY 3 ft Q = 26. 3686-O hr Final Flow (Standard) For 1.7" Crack D. Maximum Flow Rate for Idealized Conditions For idealized flow conditions, the disharge coefficient is assumed to be O. The resulting idealized flow rate (without exit losses) would represent the maximum flow rate as modeled in this calculation. C := 1.0 d 1
. . k-1 .. .
0.5 G := C A p P d h ,k + 1, , ,k + 1, 1 1,
-4 kg G = 3.2748 10 se G 3 Q := ft 0 9 Q = 34.0186 (Standard) 0 0 hr REVISION g PE lb PREPARED BY/DATE gA. 7;. ,' 0F ?7 CHECKED BY/DATE In/r.2 3 9,
nut @ch Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT *1 FILE NO. COE118 0200 02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY For the 0.5 inch Crack i For the 0.5 inch crack, steps A, B, & C will be repeated to l calculate it's respective flow rate. All variables not specifically listed remain unchanged from those used in the 1.7 inch crack flow rate calculation above. l A. Determination of Flow Conditions Critical Pressure Ratio: k
. . k-1 l CP := CP = 0.5293 ratio ,k + 1, ratio I
Actual Pressure Ratio: P i 0 AP := AP = 0.2308 ; ratio P ratio 1 CP > AP , therefore the flow is choked. Hydraulic Diameter Determination:
-4 2 -7 2 a := 7.42 10 in a = 4.7871 10 m Crack Area -
(Ref 3) p := 1.12 in p = 0.0284 m Crack edge - (Ref 3) a -5 D :=4- D = 6.7314 10 m h p h RtVISION O PAGE lb MtEPARED BY/DATE g r. :r " 0F 37 CtttCKED BY/DATE sr sp.27 41
nutech Chicago, Illinois PROJECT _ QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118.0200 02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY 2 D h -9 2 A := n- A = 3.5584 10 m h 4 h B. Calculating the discharge coefficient for a thick-walled deep orifice Fluid Velocity: 0.5 m
'k R t V := V = 350.2823-s , 1, s see Reynold's Nu.ber:
D h 3 Re := p V Re = 6.3168 10 1 s u Relative Roughness: R a R := R = 0.0743 r D r h REVISION ( PAGE
/
PREPARED BY/DATE g/33,9, l OF CHECKED BY/DATE Jo/7,27 3,
nut @ch l Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. __ COE118.02OO.02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY Coefficient of Fluid Resistance: 1 Ratio := - Ratio = 13.2075 D h Therefore, f := 1.55 (Ref 6 page 174) 0 1 := 0.0831 (Ref 6 page 80) NOTE: It is necessary to perform an interpolation / extrapolation for the values of R and Re to obain A from Table 2-2. r f := f + l- f = 2.6475 0 0
.h 1
C := C = 0.6146 d 0.5 d f C. Mass Flow Rate (for choked flow) 1
. . k-1 .. .
0.5 G := C h - P P d h ,k + 1 ,,k + 1, 1 1
-6 kg .
G = 2.2215 10 sec l REVISION ; p l PREPARED BY/DATE g M g,9' 0F 7" CHECKED BY/0 ATE try/t.p.9
I nutoch Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. __ COE118.0200,02 OWNER COMMONWEALTH EDlSON COMPANY CLIENT COMMONWEALTH EDISON COMPANY lb kg p := 0.0764 - p = 1. 2 2 2 9 - 0 3 0 3 ft a G 3 Q : = -- -6 m 0 p Q = 1.8166 10 - 0 0 sec l 3 1 it 1 Final Flow Q = 0. 2 308- (Standard) For 0.5" Crack 0 hr l REVISION [ PAGE PREPARED BY/DATE gb-2411 0F T7 CHECKED BY/DATE (c:/t,2 7 0
. . . . _ . _ . -. . - - . . . . - . ~ - -
I nutech Chicago, liknois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COEile 0200.02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY For the 0.1875 inch crack For the 0.1875 inch crack, steps A, B, & C will be repeated to calculate its respective flow rate. All variables not specifically listed remain unchanged from those used in the 1.7 inch crack flow rate calculation above. A. Determination of Flow Conditions Critical Pressure Ratio: k k-1 l 2 i CP := CP = 0.5283 i ratio ,k + 1, ratio l Actual Pressure Ratio: P O AP := AP = 0.2306 ratio P ratio 1 CP > AP , therefore the flow is choked. Hydraulic Diameter Determination:
-4 2 -7 2 a := 2.1 10 in a = 1.3548 10 -m Crack Area -
Ref 3 p := 0.407 in p = 0.0103 m Crack perimeter Ref 3 a -5 D :=4- D = 5.2423 10 m h p h REVISION O, PAGE 9 PREPARED BY/DATE gf.M 0F
~~
CHECKED BY/DATE :r /t. ?; >
-n-,-
nutach Chicago, Illinois e PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO COE110 0200 02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY 2 D h -9 2 A := n- A = 2.1584 10 m h 4 h B. Calculating the discharge coefficient for a thick-walled deep orifice: Fluid Velocity: 0.5 2 m
'k R t V := V = 3.5028 10 s , 1, s sec Reynold's Nu.ber:
D h 3 Re :=g V Re = 4.9196 10 1 s u Relative Roughness: R a R := R = 0.0954 r o r h ' l l REVISION $ ' PAGE -
'REPARED BY/DATE "
3gf M-h 0F
'~
'ECKED BY/DATE 9 r/3 2 7 *-
nutech i Chicagoilllinois l l PROJECT QUAD CIT!ES NUCLEAR POWER STATION UNIT #1 FILE NO.- COE118 0200 02 l OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY- _ Coefficient of Fluid Resistance: 1
-Ratio := - Ratio = 16.9583 )
D h I Therefore, f := 1.55 (Ref 6, page 174) i 0 1 := 0.0964 (Ref 6, page 60) NOTE: It is necessary to perform an interpolation / extrapolation fer the values R and Re to obtain A from Table 2-2. r f := f +1 f = 3.1648 0 D
,h, 1
C := C = 0.5604 d 0.5 d I C. Mass Flev Rate (for choked flow): I
. . k-1 ,, .
0.5 G := C A P- P d h ,k + 1 ,,k + 1, 1 1,
-6 kg G = 1.2286 10 see REVISION g p 33 PREPARED BY/DATE Mdy-h 0F 7 CHECKED BY/DATE P t/7.p. 'u
nutech Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #.1 FILE NO. COE118 0200 02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY lb kg p := 0.0764 9 = 1. 2 2 2 9 - 0 3 0 3 ft m G 3 Q := -6 m 0 p Q = 1.0047 10 0 0 sec 3 ft Final Flew Q = 0.1276 (Standard) Fer 0,1875" Crack 0 hr 9 REVISION g- _ - l PAGE - ! PREPARED BY/DATE g f, p.9, __ CHECKED BY/DATE pr /7. p. <,,
nutoch Chicago, Illinois 4 PROJECT OUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118.0200;02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY V. SUMMATION OF LEAK RATES CRACK SIZE NO O RELATIVE 3 (inches) VOLUMETRIC FLOW RATE (f t /hr) e g VOLUME (f t /hr) 1.7 26.3686 1 26.3686 0.5 0.2308 3 .6927 0.1875 0.1276 36 4.5936 Pinhole 0.0658 200 13.16 (see Calc. COE118.0200.02, Section 5) Total w/ Pinholes Qt = (26.3686) + .6927 + 4.5936 + 13.16
=
44.815 f t /hr 3 Total w/out Pinholes Qt = (26.3686) + .6927 + 4.5936
=
31.655 f t /hr 3 1.7 in. crack percentage of total w/ Pinholes 68 4[g 5 x 100% - 58.8% 1.7 in. crack percentage of total w/out Pinholes
" ~ '
31.655 O.1875 in, crack percentage of total w/out Pinholes 100 - 14.5% 3 55 REVISION 0 i PREPARED BY/0 ATE %bh.3,3 E] CHECKE0 BY/DATE 4cs 'l 3.n.3
nutech Chicago, liknois i PROJECT OUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. ,_CDE1.18 0200.02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY VI. CONCLUSION The objective of this calculation was to determine the flow rate from the postulated cracks in the X-25 bellows. The success with which this was accomplished can only be realized by carefully considering the results for each crack in relation to the total leakage, as well as the basis for the governing assumptions. Section V tabulates the resulting flow rates for varying crack size and the respective number of cracks found. The most important determination made from this data is that the large (1.7 inch) crack contributes almost 59% of the total leakage if pinhole leakage is considered and over 83% of total if the pinholes are neglected. The next largest contributor of measurable size is the family of 0.1875 in, cracks, which are responsible for just 14.5% of the total leakage w/out pinhole leakage. Since the number of pinhole leaks is an approximation based on a quadrant average, it is reasonable to neglect it in prediction of overall percentage of leak rates. The significance of the large cracks contribution to the total leakage indicates that any future predictions of leakage may be approximated based on the large cracks alone given that ratio of the number of the small cracks (L 5 0.5") to the number of the large cracks is s 10. Additionally, a worst case bounding value of leakage through the large crack (1.7") was calculated. Section IV.D calculates the flow rate based on an ideal fluid resistance coefficient ( C,) of 1. The resulting flow rate increases 24% over the actual predicted value. The differences that exist between the measured flow rate of 137.4 f t /hr and the theoretical values do not invalidate the 3 model used for this analysis. It must be noted that the irregular outline of the cracks do not lend themselves to accurate prediction of areas. Also, due to the nature of the crack geometry, it is reasonable to assume that flow profiles are not fully developed. These two facts suggest that the actual flow area be corrected in some manner. This calculatior accounts for these effects by utilizing a flow area based on the aydraulic diameter of the openings. Results from calculations utilizing the actual crack were considerably higher than the measured leakages. Although lower than the measured values, the calculation yields reproducible leakages, representing the varying percentage of leakage contribution from the various crack sizes. REVISION 0 - PAGE > c PREPARED BY/DATE gegh% OF 7 CHECKED BY/DATE $ $ /y.? 7 c.,
nutoch Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. - COE110.0200,02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY 5.0 ANALYTICAL MODEL FOR FLOW RATE THROUGH
" PINHOLE" CRACKS UTILIZING LAMINAR AND TURBULENT COMPRESSIBLE FLOW REVISION O PAGE ~'o PREPARED BY/DATE p/379,q, '
CHECKED BY/DATE Syr F i
J nutoch Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. _ COE118,0200 02 l OWNER COMMONWEALTH EDISON COMPANY l l CLIENT- COMMONWEALTH EDISON COMPANY l PURPOSE To conservatively determine the flow rate from Transgranular Stress Corrosion Cracks (TGSCC) with a geometry described as " Pinholes." I INPUT / ASSUMPTIONS
- 1. " Pinholes" modeled conservatively as a thick walled circular orifice in an infinite wall with a throat diameter D = 0.001 in.
= 0.0000254 m (Ref. 12).
- 2. Discharge Coefficient, C, for orifice chosen ideally high at 1.0.
- 3. Integrated Leak Rate Test (ILRT) Conditions Apply Inside Ccntainment, Pressure, P = 49 psig - 4. 39 x 10' E (abs. )
3 m3 Tempera ture, T 1- 9 0* F - 550'R (Ref.1) Densi ty, p3 - 0.313 ft'
-5.01 M m' (Ref. 2)
Ra tic of Specific Heats Ecr air k - 1.4 (Re:. ~
- 4. Number of Pinhole Cracks, N = 200 (Ref. 12)
- 5. Sonic (Choked) Flow REVISION 0 p _-
PREPARED BY/0 ATE p,/3 M OF
~i CHECKED BY/DATE f e r/3 2;. +
l nutech Chicago, Illinois I PROJECT _ QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE1 R0200.02 l OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY CALCULATION Tor sonic conditions, the mass flow rate is given by G-C 2
)a!; 1 2 f---p3 P 1 (Ref 6) where a is the crifice throa t area- { ( . 0000254m) 3 - 5. 07 x10'1*m' 2 2 G - 1. 0 1;4 5. 01
- 4 . 3 9 x 105
- 5. 07 x 10'l ( ,
) n..h a _
G - 5.15 x 10-7 U sec Volumetric flow rate at standard conditions, Q, densi ty of air a t scandard condi tions, p, - 1. 22 2 m p# . .$. 5 .15 x 10 ,[ 1 )) 3 6 0 0 - 5. 3 6 x 10-2 SCFH
- p. 1.222 \.3048)
Total (Worst Case) Leak Rate from all " Pinholes" O,., - N O, - 2 0 0 5 . 3 6 x 10 -2 = 11 SCFH REVISION O PAGE M PREPARED BY/DATE
%'M'h 0F CHECKED BY/DATE se rg . j p. 9
nut @ch
., Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. _ COE118.0200.02 OWNER COMMONWEALTH EDISON COMPANY CLliNT COMMONWEALTH EDISON COMPANY Now try laminar flow:
For laminar flow, the mass ficw rate is given by G- ' (Ref.14, Section 3. 2. 2 ) [5 R4 (P* - Po') t where: 9 ie the gravitational conversion constant - 32.2 lbm<ft lbf ' sec' D is the pinhole throat diameter = 0.001 in - 0.0001 f t. P le the inside Bellows P: essure - 49 psig - t lb # lb # 63.7 - 9,172.8 in' fc*
, P is the standard atmospheric pres.sure-14.7 psia - 2,116. 8 o
A p la t 9 0* F) is the viscosity of gas - 0.0187 centipoises - lbm
- 1. 2 56 x 10 5 f t see (Ref. 2) t is the length of the leak path = 0.035 in = 0.0029 f t (Ref. 9) 1S R is the gas constant - 53.34 (Ref. 8)
-Tt is the inside Bellows Temperature - 90*F = 550*R (Ref. 10 ) .
REVISION 0 PAGE 22 PREPARED BY/DATE g/ 7.p;, q, y sefft.jp.4,
~
CHECKED BY/DATE
nutech Chicago, Illinois PROJECT J; WAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. CoE11e 0200.02 l OWNER ,_ QOMMONWEALTH EDISON COMPANY
- CLIENT COMMONWEALTH EblSON COMPANY I g , _32. 2 (n ) (4. 82 x 10*D) (7 9,6 b9,417. 6 0) - 1. 4 2 x 10*' N#
256 (1.256 x 10**) ( .003) (53. 34) (550) sec units 5 " see po . 016 4 - a t t - 60* F and a tmospheric pressure (Ref. 2) volumet:ic ficw : ate a t standa:d condi tions, 0, p, f . (1. 37 X 10*')
- 3 6 00 . 06 4 6 SCF#
p, .0764 0 7, - N
- Co - 2 0 ')
- 0 . 0 6 4 6 = 13 SCr#
CONCLUSIONS for determining the flow rate from the " pinholes," the laminar flow case gives a larger-flow rate than the turbulent flow case, REVISION O PME D PREPARED BY/DATE yp,/,;s. - 0F 77 CHECKED BY/0 ATE sa /? ,p
- - . - . - . - . . . _ . . - - - . - . -. - _.-_.._ .- - -.-......_- ..- -.- ~ ... - _.- -_
i-nutech Chicago, Illinois PROJECT _ QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. _ COE118.0200.02 OWNER COMMO3 WEALTH EDISON COMPANY. CLIENT _.COMYONWEALTH E\)ISON COMPANY 6.0 PREDICTION OF LEAKAGE RATES AT ILRT CONDITIONS DUE TO CRACK GROWTH AFTER ; ONE FUEL CYCLE l REVISION O ^ PAGE r PREPARED BY/DATE g )3 % il 0F ?7 CHECKED BY/DATE cc,y r. 2 :
- _ _ . . _ . . _ . _ _ . . _ _ _ - - - - -- - - - - - - - - - -- ~ ~ -
nutech Chicago, Illinois PROJECT QUAD CITl[S NUCLEAR POWER STATION UNIT Ji FILE NO. COEii8.0200 02 OWNER. COygtNEgpt ril EDISON COMPANY CLIENT __COMMUNWEALTH EDISON COMPANY PtmPOSE The purpose of this section is to determine a relationship between volumetric flow rata and crack area. Once the relationship is defined, the hypothetical volumetric flow rate for the postulated increased crack growth will be determined. METHODOLOGY The flow through the 1.7" crack during ILRT condition was calculated to be approximately 26.4 SCTH and for each of the medium size cracks with a length of 0.5 inches, was predicted to be approximately 0.231 SCTH. For the 3/16" cracks during ILRT condition, the flow was calculated to be approximately .128 ScrH. Additionally, the flow through the 200 pinhole flows was conservatively estimated at 13 ScrH total. Using the observed crack population (Reference 12) modified by Reference 13, the flow through all cracks can be calculated as follows: QToi
" Qi , + 3 Qo s + 3 6 Q3 a + Qt otu rmatu where Q = G pa (The subscripts correspor.d to the four different crack lengths.)
= 26.4 +3 (.231) + 36 (.128) + 13 = 44.7 SCTH This total does not match the observed ILRT flow rate of 137.4 SCTH.
Because each of the flow rate contributions from the different crack sizes came from the same correlation (except the pinhole leak rate), the assumption la made that each calculated crack flow rate deviates from the actual by the same constant of proportionality which is 137.4/44.7 = 3.07. REVISION 0 - PAGE r - PREPARED BY/DATE %/2.:r % OF U CHECKED BY/0 ATE set /3.n.tr
nutech Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1__ FILE NO. __ COE118.0200 02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY Adjusted with the proportionality constant, the actual leak rate through the crack is more closely represented by the following valuest CALCULATED SEALED NUMBER TOTAL LEAXAGE FOR CRACK SIZE LEAX FOR LEAX PER OF EACH CRACK SIZE SCTH , CRACK SCTH CRACK SCFH CRACKS (Qtotu strou opom) 1.7" 26.4 81.0 1 81.0 0.5" 0.231 709 3 2.13 3/16" or 0.128 .393 36 14.11 l .1875" Pinholes 0.065 .200 200 40.00 i TOTAL MEASURED 137.3= 137.4 SCFH The expression used to determine the mass discharge through a crack is given by (Reference 6): G*C dAa ( 1) $ Ps P3 It is apparent from this exprension that the last two parameters are independent of the crack size. Furthermore, comparison of G between ILRT tests at the same containment conditions allows pi and P to be treated as constants. The two remaining parameters. C, and A, were tabulated as follows: l 1.7" 0.5" 3/16" = 0.1875" C, 0.775 0.613 0.562 A. (m2) 3.22 x 10 4 3.56 x 10* 2.2 x 10 4 C, - A, -2.4987 x 10 4 2.182 x 10 4 1.236 x 10 4 where C,-is proportional to the square root of depth /hydrau.lic diameter of the crack. As shown in this table, % changes in C, are small compared to % changes in A. (for changes in corresponding crack i lengths). This result is depicted by the change in the product of C, A as it more- closely follows the percent change in A than that of C,. i 1. REVISION O .- p PREPARED BY/DATE g f.n,9' 0F 7-l _ CHECKED BY/DATE rer/h./ 2 9 l L _. _- . _ _ . _ _ . - _ . . _ _ _ . _
nutech Chicago, Illinois PROJECT QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COEiiB 0200.02 ) , OWNER COMMONWEALTH EDlSON COMPANY l CLIENT COMMONWEALTH EDISON COMPANY Therefore, one can conclude that the change in mass flow discharge through the crack varies nearly linearly with the change in A, or D 2, Since the volumetric flow rate, Qo, is directly proportional to the l mass flow discharge, one can conclude that Qo also varies nearly ' linearly with the change in A or D Hence, as an approximation, one can use the percentage change in ar,2ea of the cracks after one fuel cycle to predict the appropriate leak flow rate as follows, Qiu weo,.. " Oru wemo,.* + Qtu wrmo,,, (% change in area) i In order to prevent accumulated error from change in C,, the above expression must be utilized per crack size. The precent change in area per crack size is given by:
# ####
- Area af ter Growth - Area before Grcwth Area before Growth From Ref. 1 and 2 l
INITIAL CRACK AREA BEFORE AREA AFTER % CHANGE IN SIZE GROWTH (in ) 2 GROWTH (in ) 2 AREA 1.7" 22.3 x 10d 27.8 x 10'8 .247 or 24.7% 0.5" 7.42 x 10 10.4 x lodd .402 or 40.2%' 3/16" or 0.1875 2.10 x 10 4 4.P8 x 10 1.32 or 132% Pinhole
- 2.10 7 x 10 d *
- Area before growth of pinhole for this evaluation is taken as-approximately 0 in. 2 Over a fuel cycle, the cracks are por.tulated to grow 3/16" (Ref. 12).
l l l REVISION O p q PREPARED BY/DATE 9p/3.,3,9/ " OF l CHECKED BY/DATE ;cyf.f 7 9
nutech Chicago, Illinois I I PROJECT _ QUAD CITIES NUCLEAR POWER STATION UNIT #1- FILE NO. _ COE118.0200 02 4 3 l OWNER COMMONWEALTH EDISON COMPANY ' CLIENT COMMONWEALTH EDISON COMPANY i l l Therefores CRACK SIZE BEFORE CRACK SIZE AFTER j GROWTH GROWTH O NAL^m3cao m SCFH 1.7" 1.89" 101 0.5" 0.688" 2.97 3/16" or 0.1875" 0.375" 32.7 Pinhole 0.1875" 78.6* SCALED TOTAL 215 SCFH
*This value represents the scaled leakage through a 3/16" crack t
calculated previously multiplied by 200 cracks. Therefore, the predicted total measured leak rate after crack growth is 215 SCFH. CONCLUSION Analytically, it has been shown that the volumetric flow rate varies nearly linearly with the hydraulic area (for with the hydraulic diameter squared). l REVISION "O -- p PREPARED BY/DATE g/3.n,% OF ^l' CHECKE0 BY/DATE cer/; /7 9
nutech
. Chicago, Illinois PROJECT _ QUAD CITIES NUCLEAR POWER STATION UNIT #1 FILE NO. COE118.0200 02 OWNER myMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY
7.0 REFERENCES
REVISION 0 . , PAGE PREPARED BY/DATE g f3,3, ,, l OF r-CHECKED BY/DATE ;cf/p. p, _
nutech Chicago, lihnois PROJECT _ QUAD CITIES NUCLE /\BfQWER STATION UNIT #1 flLE NO. __ COE118.0200 02 OWNER COMMONWEALTH EDISON COMPANY CLIENT COMMONWEALTH EDISON COMPANY, REFERDiCES
- 1. " Temporary Procedure 6653", Bellows Leakage Measure.ments; dated l 3/4/91; Nutech file No. COE118.0160. i
- 2. Cranes Technical Paper No. 410,
- 3. Nutech calculation COE118.0200.01, " Determination of longitudinal Crack Areas for the Quad Cities Unit 1 Bellows at Penetration X-25".
l
- 4. Marks Standard Handbook for Mechanical Engineers, Eighth Edition. I
- 5. Introduction of Fluid Mechanics, Second Edition, J. John and W. 1 Haberman; Prentice Hall.
- 6. Handbook of Hydraulic Resistance, Second Edition, 1970, Nutech file No. COE118.0160.
- 7. Calculation of Leak Rates Through Cracks in Pipes and Tubes, EPRI Research Project 1757-19, NP-3395. Nutech file no. COE118.0160.
- 8. Fluid Mechanics, decond Edition, F. M. White, 1986 McGraw-Hill, Inc.
- 9. Drawing 8052, " Pathway Bellows Drawing 18", Tandem Expansion Joint
, Assembly; Quad Cities Units 1 & 2", Rev. O, Nutech file no.
COE118.0160.
- 10. Reactor Containment Building Integrated leak Rate Test, Quad Cites Nuclear Power Station Unit 1, dated November 14-15, 1989; 04 83H/02142, Nutech file no. COE118.0160.
- 11. CEGB 376/047, " Simple methods for predicting Gas Leakage through Cracks", D. J. Ewing, MA, PhD; Central Electricity Generating Board.
- 12. Meeting on Quad Cities Bellows Leakage, Nutech Communication Record RWR-91-024, dated March 22, 1991; Nutech file no. COE118.0001,
- 13. Nutech Communication Record TJW-91-056; "Drywell Penetration X-25 Bellows Replacement COE-118", dated March 25, 1991; Nutech file no.
COE118.0001.
- 14. Document No. TID-20583;" I4akage Characteristics of Steel Containment Vessels and the Analysis of Leakage Rate Determinations" ,
1 1964;Nutech File No. COE118.0160. l REVISION O '~ PAGE PREPARED BY/DATE pf N- f/ OF CHECKED BY/DATE g,s/7.p.9
Attachment 4 COMMONWEALTH EDISON COMPANY PHOTOGRAPHS OF X-25 BELLOWS COE-118-021 F4UTE[H EN01t SEERS
g - a m -. - -
..g -
i I
. c ,
'e _ ,e
+ i.-
, ;.1
. : s, w
, as i '~ s;,: ;'. '
i h ~ 1
} + ;h '
1 i t
~
s y J.'.s 4 ?' .. . ;r y
.t 4.
!"=,
l ', . , l j s A: . :: g
+
< Fjl *
.e r n .4 Q, ;r I
# 'wh . .
*p 4 ay '
#pu 1, nf 'U r
. l;K;f f;! ' } s.
[ } %i[' n.
- 4. y l-i q \ ,,;
j, a e
,7
~
Q i j (gr,,.c
'jyj;py- '
~
\ ,
, 5), . .
^ t" g (
Q u , . y i$
,=4,. f i
{ :--.. ' s _ iv . *;;, a f y I vert n ; . 5.
. I ;4 ...
- o
. ,g . '
,A'$? '
y
~
"" AE -
y, . , W W. W:nwssk::*0me
- . . .. . - . , m . ,. % .
- . .,, n
* # ,,j 2{
,. -- - -- a --~ - - " = -
^--& --
4 9 s ' - - - - T~r
- est r- 5 w t* '78 - fr
~ #
- r. (J, e
W* s , V
, h,g.
- n -<
1 i
',f', L
, . I__< *
*%h 5
l l i i l l 1 l 1 l {
- l 4
I l i I 9 i i 1
) l u.f 8.i l; ;/
- I +
a ..Y. p x-,'tf k i ?'
> > c .s
.l'
'>; El
.,4 _g ii >
r A u 1 Y e i7 i
\. 1 l l 1 1 l Attachment 5 i FINITE ELEMEin MODEL DEPICTING BELLOWS DETAILS i l l e l l COE-118-021 t4UTEEH [N04t40ERS
CONCENTRATED i MESH AREA NEAR CRACK . i
' c]3* ,
/
1 Uu -US Lo=-153 La= 13 R= 0 LC 1/ SU1LW13.14 FiIc:be16 91/03/24 19:02 OBLIQUE VIEW SHOWING QUARTER MODEL OF HALF CONVOLUTION
l* 1- ; !. l l l l w , , < *
- an ,./" ,/'
\
?
s ( \ g 4 o
,o 1 5
\ s
\
Y r
- N a'"
~
,o %,
k 9, g s s M Ys
\
o l
. l
-_____-_-.______--I
- l J
' j l
I w l 1
.n..,,.~n--.,--- . . . . . . - . . , . - . . . . . ....,,,.,.n.y , , n-Y .,
' ' .' i? ?
j t
~
\
p 'f 4'
'r j , j W t'l, l j W h c e
,/ ,
/
O .) /, %q ' ,
,' ,/,
W 4 fQ j'r ' / N; i
% Q >A J,/
// ) '
J' % . s
, ')
* ') < V i M },,t Y /.- J.* % / ) ,
) ! l 1 .l
,' ~ 'y O
r=
,,4, ,'ft j/_
A
,/ x
\T
/ g j ses ,. A >
_, jr i f l j $ m g ;' ,/," ' >
, ,i ,/
)'
l ,. / , _% / .i Q
- / s / j /
9 '. l,/ _k,' ., ,' / - ,'
\f u ge.. . , a-
, ,y v. < ,- ,.~
- +, i i
/
s 'B g, # # / m y,r [ ,. g.d -
-i n%#
,.y ,,)p/ 6 b(M' pa m' N \s s- /, i j
h .e' w Y. . - .y?
.4 fs7 sas W --i s
Gyg if; w\*M
, ./ '.
35 2A ,6 vgso_
.o . -
.1 - -
n
-r..
j . . AQ s<L.c B S X. xe y ,':s -
. y; gN /23 ..
n g , r, ,~N/
\ _a' 3, n.p yg; x, 8 ;
,.j n
r
,.k 7* , Q ,A'j y]w,.- 'g. . F
\.\.t[h K,g ,h
./ \ .
s Y V,f,,/ h,i , s. " .,- s y s i
~
y p', y ^{< , ,, g, s> g 3p ~ e,,
'%sg[&
. t~/ .}w.f(.'Ylf 9
./, x,e / % \/ ~ > ,^19 fnf r f., -
x nxs m.- [ ,/ ,/ 38:j ,fK -,/
-\.,)
, . xk
' ' h.[,g';Ic h,%;e, f m n ,',- m , w .,- N , n ,hv.
'N Yi ' g-H +
y, ," Q , m7 ,/ . '/x % t' t/
; V x f.- > O f m p1 s ,
N,.
,r Ny / -
j', ,,' 1 - ,
, / y <
y,- ./ g
?
y- <,s ',x , Oy j' ,.e, ,-'\ m; QQ O @ s' / ,'* MM
. '\/
@ \ ' s / \. ,,./.o ,, CA O M eq
'\ , / ,/ ,\. f/ *=* D O' {.n . //\, ,f
/
, r' j ,. ' S?!'
y
\s/ r
/,s F f\ \ /,r
/ ,//v//
/
,X;g ,a" .'/
G r,/. ,. ,r \/ '\ .r
,4 y M /,/ f'N 'O'y x u -
,/,/.ss .
& . /lgV /?
O fy
- e. .- . - --. . . - .
l l l 1 i l i I I l l
$i -
I g.$. , 6.,,3 c, '$.':, ..
. !:' * 't ,7 f
. er
, e i i
i l 4m t. s \ , . , , . i 1
+-+ ea r r
l i j j.# 4 t
,(si. '
t -r 4 , : " ((i- - t c..
;t , + ' .I '*' < . , - . .
s e 4 -% . iyffy g;&c; , J ' h
._ , m;q{g t<;Qp n.y, 3 xdLh,_%u I
l Attachment 5 tit 1ITE ELEMENT MODEL ) DEPICTING BELLOWS DETAILS l COE-118-021 84UTE[H Et4folt4EERS
- _ _ __ _. . . _ . .- --. - .-. - -- . _.. - . . . . _ _ - . . . - . __ - . . - =
- i. [
I
- l 4
~ t l / / /^ .! ,
/
/ / l /
#% '%cx
%q
/ / / l / l / ll j l i j i
/
s' - I 93,__ l / l / l
/
l
,- /
I
/,
,.~-
t SUiDM 3.14 FiIc be16 31/03/Z419:82 LC 1/ 1 ma=US Lo=-153 La= 13 R= 0 j l f t ' i' ! I' I OBLIQUE VIEW SHOWING QUARTER MODEL OF HALF CONVOLUTION i
4 i I t y s o \ \ Y \
\
o . o \ j g s b 8 ~ \ l \ > 0 7
\
s \
, / ,p e/ ,,,/ ,..# y# , - -
l l 1 .
- a 4
w.mw- --aww m ,.----------w- - - _. - - - - - - - - - - - - - - - - - - - -- .--- -- - - -- -v.-------- - - , - - - - - - - - - - - - w..--------. 8' we
,r;; ^ @
u g
,, ,,,3,Y ( ,*' ,e E M k_ _s ,,
-,f.: - -.- /j ' ".,,.x, ,- /
J~'., Y
, 1
-,2
=J f l
, <f ? ' , ' ' ,-
}.f ^/ Q r.
, y <
,,- , s
\ ,'
p.
/ *'
..~N o ~* '
w ' H O - , \ ' 1 Q <: / s, - s _/ ww .. / t ,a a ~ ,,_ > O } ? jrf ,
, p
' ' A_[;
-\
./, x ,.
jj M a: A /ie
- ,e s' y
L 5 .,0 f W
^ '
- S '(@ Q <k 's', / ', , a 4 4 \' / ' N' / '~~
L
'b.
a', ,'f)i;.$~,. .- />' .N \m' .j(*y . v~:*2 / )-t .i' /n,'
;# e,4*Q ;
v,,
;( N,
-' , '/
/ s,t
.N .A,.+f e' g ,, g y N,s ,\ N' ,.
, u Q
' =
.i . y 7l ' y
% ,s
,/ n +.~ ., ,
cN - A, g & - Q /'- ; ^.,/,/W-
': j:
y m% ,x 1, ',; g f
- y
/< <.
/s - x p 4,7
-,my. ; $,g.:
/ .
. <, w ~ @
w~ s 1 s N s _ ' e
% .' > 4.-
Nf(- ', sp) ' s' yf/
]Q ,.
; ,x
, y4 M
",' j
)Q~; ,- ,
y
/
,< /'\X/ kg, b~* ' jf-g,.*l g
/ ^ * ' -)y ' N @
,i
/
.,/
/
/ 'N ,, '
,,Ay ,/' -
,,l X x; / l/ /r/R.y. ',
}
ew j e , J f f y% / , /. ,
,h
/ ,/ / Q'%
g
/y% y'
,/ ,,
j
,/
D W
/ ', f / l% / 7; '
,' ,1 / ,- 7q 7, ' ===
x 7 - / / ,
, p ,,
y a u
. ,/ j' , ,. ,y' M- @ .,
y e' / / y l'% .*
/
f
/
,/ ff
) s')
y ena een 61 O N
/,/ ,f '
/ /
,/ N y' .[,0
_/ f t O p
< . ,. a $.
/ ,! . / l,l/ , ,,
<. p &
/ r. O
/
i
,/ / //
i >; es m
/
l ,/ <,f,t a-s Y [ f) ~
\/
a c.um._.___._____.._..___...__._.._.._.__> ei G k 4
.,.a,
i
~
s_ l
-x ..
i % DEFLECTED (LOADED) MODEL ' (BLUE) i _ i
. . _ . 1 UNDEFLECTED MODEL _ _
(GREEN) , . b %
-4 1
i j 's: SUIDM 3.14 File:be16 91/03/24 19:02 LC 1/ 1 Uu=US Lo=-128 La= 18 R= 0 J OBLIQUE VIEW EXTREME CLOSE-UP SHOWING CRACK EXPANSION DUE TO LOADING
---_ - _ - _ _ _ _ _ _ _ - _ .J
le e, I Attachment 6 DESIGli IllPUT LOG COE-118-021 HUTEEH ENHHEERS
o ? i I i , i i DESIGN INPUT LOG Unique Document No: COE-118 ' ! File No: CoE118.0150 ! i Revision No: 0 ! Date: 3/26/91 t t l Client: commonwealth Edison Company Project No: COE-118 Project Name: Quad Cities Bellows Leakage j Des. Input? Rev. or File Responsible i Document'No. Title or Subject Y/N Date Number PE Approval Date ! t j ! Mircellaneous ; 3/77/Tl l { Mark's Standard Handbook for Mechanical Engineers, Eighth Edition Y 1970 ()
/
ppg f
) $
l 5 Mark's Standard Hadbook for Mechanical Y t Engineers, Seventh Edition l Handbook'of Hydraulic Resistance, Y COE118.0160 . Second Edition, a4evised and Augmented; ! I.E. Idelchik; Hemisphere Publishing i' corporation
- Introduction to Fluid Mechanics, Second Edition, J. John and Y COE118.0160 Ilf3/
{ W. Haberman; Prentice-Hall, Inc. l Standards of the F.xpansion Joint of Y 1960 NUTECH Library kDD "l4 }9l . l Manufacturer's Association, Inc., ! , Fifth Edition, including 1985 Addenda < t Fluid Mechanics, Second Edition, Frank M. White, McGraw-Hill Book Company Y 1986 COE118.0160 h k 7 g<g , 7 0483H/0219 Reactor Containment Building Integrated Y 11/14/89 COE118.0160 [Mr ' Leak Rate Test h g l M-1243-91 System Materiale Analysis Department Heport on Inspection of the X-25 Dryweli Y 3/12/91 COE118.0160 [bb l Penetration Bellows at Quad Cities Station > t CR 87946 Design Report Articulated Expansion Joint per ASME Boiler and Pressure vessel Code Section III, Class MC Y 3/05/91 COE118.0160 UhhNh@ g.g4j j i i I t
- I I
- Asterisk designates preliminary input data- f DIL-COE118 Page 1 of
- 1
g ,o s DESIGN INPUT LOG Unique Document No: COE-118 File No: coE118.01so Revision No: O Date: 3/26/91 ~ Client: Commonwealth Edison Company Project No: coE-118 Project Name: ouad Cities sellows Leakaoe
-----------------------------------------------------------------------------------------=__ ___ - =--------------------
, Des. Input? Rev. or File Responsible Document No. Title or Subject. Y/N Date Number PE Approval Date l Temporary Procedure 6653, Bellows Leakage Measurements Y 3/04/91 COE118.0160 h */f27!T I Updated FSAR for Quad Cities Y NUTECH Library 5-D4 Meetino Notes RWR-91-024 Meeting on Quad Cities Bellows Leakage Y 3/22/91 CoE118. COO 1 P"Ders CECE 376/047 Simple Methods for Predicting Gas Y I Leakage Flow Through Cracks Crane's Technical Paper No. 410 Y Q $~t7'1k Crane's Technical Paper No. 410M Y J-77-$ Fracture Mechanics Evaluation Y 3/14/91 CoE118.0160 (unapproved copy) NP-3395 Calculation of Leak Rates Through Cracks in Pipes and Tubes Y COE118.0160 hh 8$-U-M EPRI Research Project 1757-19 TID-20583 Leakage Characteristics of Steel containment 1964 )~N'h vessels and the Analywl af Leakage Rate Y COE118.0160 _b I' Determinations
, Calculations i
COE118.02OO.01 Determination of Loogitudinal Crack Areas for the Quad Cities Unit 1 Y O COE118.02OO.01 h 2 29-11 Bellows at Penetration X-25 i 1
- Asterisk designates preliminary input data DIL-COE118 Pa<;p- 2 of *
= - . _
o ,o - i DESIGN INPUT LOG Unique Document No: COE-118 File No: COE118.0150 Revision No: O Date: 3/26191 { Client: Ccenonwealth Edison Coscany Project No: COE-118 Project Name: e2ad Cities Bellows Leakaoe
..._--_____----_-_-_-_-----____-___-_____--__-____---___---.-__--__-----__---__---__---__-...._-------=---- =.__--_---._-_
Des. Input? Rev. or File Hesponsible 1 Document No. Title or subject Y/N Date Number PE Approval Date i j Telecons l CJJ-91-006 Characterization of Observed Crack in Y 3/25/91 CwE053.OOO1 ! X-25 Bellows Elements bO TJW-91-056 Drywell Penetration X-25 Bellows Replacement COE-118 Y 3/25/91 COE118.OOO1 hp i Y-7[-il Drawinos EOS2 Pathway Bellows Drawing 18* Tandem Y
- Expansion Joint Assembly; Quad Cities O COE118.0160
{ J- ]7. yp l tsnits 1 & 2 Item X-25 i i Computer Models l Quad Cities Unit #1, Bellows at Penetration X-25 with 3/16 x .001-Y 3/25/91 COE118.02OO.02 hhWM $.27-if , Crack at ILRT Conditions Algor Computer Model " Quad Cities Y 3/25/91 COE118.02OO.01 - 3 7,7.y Unit #1: Bellows at Penetration X-25 with 3/16' x 0.001- Crack at ILRT g f"D8 Conditions.* Algor Computer Model
- Quad Cities Unit #1: Bellows at Penetration X-25 Y 3/24/91 COE118.02OO.01 % & Pts 3-7J41
-with 1/2 .x 0.001" Crack at ILRT Conditions."
Algor Computer Model " Quad Cities Y 3/25/91 COE118.02OO.01 - V Unit #1: Bellows at dextration X-25 with 1.7* x 0.010" Crack at ILRT gg Conditions.-
- Auterisk designates preliminary input data DIL-COE118 Page 3 of a
^
' O ."
a i DESIGN INPtlT ,t0G Unique Document No: _.coc-118 File No: cOEI18.0150 ReJision No: 0
- Date
- 3/26/91 j . _____________________________________________-________-__________---____________________---- --- __----- =-_=________-_______
, Cllent: Conunonwealth Edison Company . _ , _ Project No: COE-118 Project Name: ouad Cities sellows Leakaw Des. Input? Rev. or File Responsible Document NO. Title or '.ubject 4/W Date Number PE ".;;; eval Date A 6. M
! Algor Computer Mo6el -Quad Cities Unit #1: Bellows ac Penetration ' X-25 Y 3/26/91 COE118.02OO.01 () 3-z7-11 l with 3/16 x 0.001 Crac!c with 3/16-Crowth at ILRT Conditions.- } Algor Comrater Model -Quad Cities Y 3/25/91 CDE118.02OO.01 d 3-17 9) j' Unit #1: Bellows at Penetrati-en X-25 hM with 1/2 x 0.001 Crack with 3/16-Crowth at ILRT Conditions.- Algor Computer Model -Quad Cities Y -} Y2118. 0200.01 Unit #1: Bellows at Penetration X-25 _;4 ;M , S-ZMJ 4 ? with 1.7 x 0.010 Crack with 3/16- g l Growth at ILRT Conditions." I f Computer Program Verification Document, Y O QASJO. SOFT.2.165.9.0 0 E 3-M l i Algor Finite Element Software, Version 9.0 QM l Nures - Algor Finite Element Y O 2.165.9.0 d-l Analysis software, version 9.0 l) 3,pgI r i l l i i i i I l
- Anterisk designates preliminary input data l DIL-COE118 Page 4 of *
. + . - -- . - _ _ - _ _ - _ _ - - - _ - _ _ _ - -}}