ML19329E631
| ML19329E631 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 07/10/1978 |
| From: | Bacon J CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8006160412 | |
| Download: ML19329E631 (3) | |
Text
,'
ef/3l']
~,
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-329/330 REC: BOYD R S ORG: BACON J L NRC DOCDATE: 07/10/78 CONSUMERS PWR DATE RCVD: 07/13/75 DOCTYPE: LETTER NOTARIZED: NO
SUBJECT:
COPIES RECEIVED FORWARDING CERT OF SVC SHOWING SVC OF AMEND NOS 46 & 47 TO APPL LTR 1 ENCL 1 CONSTRUCTION PERMITS AND OPERATING LIC, CONSISTING OF REVISION 10 & 11 TO THE FINAL SAFETY ANALYSIS REPT, SERVED UPON U.S.
EPA, CHICAOO, IL.
.ET-AL.
PLANT NAME: MIDLAND - UNIT 1 MIDLAND - UNIT 2 REVIEWER INITI AL:
XJM DISTRIBUTER INITIAL: N,
- o*o************
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
CERTIFICATE OF SERVICE (DISTRIBUTION CODE B008)
FOR ACTION:
B
- uEF LWR #4
- W/ ENCL LIC ASST LWR #4 LA**W/ ENCL INTERNAL:
(QEG FILE **W/ ENC NRC PDR**W/ ENCL EXTERNAL:
LPDR'S MIDLAND, MI**W/ ENCL ACRS CAT A**W/O ENCL i
THIS DOCUMENT CONTAINS POOR QUAUTY PAGES
)e ISTRIBUTION:
LTR 5 ENCL 5
$IZE: IP+1P CONTROL NBR: T"$IY300y ') '
)*o000*****************************
THE END 8006160 k[2
A
\\
. s 5i Q
-) o..
i Judd L. Bacon
/
Managing Attomey
, ],
]
I
~/
General offices: 212 West Michigan Avenue, Jackson, Michigan 49201 e Area Code 517 7881366 July 10, 1978 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Att:
Roger S. Boyd i,.
" - hn.... _,,.
, 3 j f,[ %.,(il j
MIDLAND PROJECT DOCKET NOS. 50-329, 50-330 OPERATING LICENSE APPLICATION Gentlemen:
Enclosed is a Certificate of Service of copies of Amendment No. 46 (Revision 10 to the Final Safety Analysis Report) and Amendment No. 47 (Revision 11 to the Final Safety Analysis Report) to the Company's ap-plication for construction permits and operating licenses for Midland Unit Nos. 1 and 2, covering service upon Mr. Robert B. Chatterton, Super-visor of Midland Township; Mr. Daniel Ranck, Chairman of the Midland County Board of Commissioners; Mr. Phillip F. Gustafson, Manager, En-vironmental Statement Proj ect. Argonne National Laboratory; Executive Office of the Governor of Micnigan; and U.S. Environmental Protection Agency.
.Yours very truly,
/
0*OY V
i
1 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
CONSUMERS POWER COMPANY
)
Application for Reactor
).
Docket No. 50-329 Construction Permit and
)
Docket No. 50-330 Operating License
)
)
CERTIFICATE OF SERVICE Amendment No. 46_(Revision 10 to the Final Safety Analysis Report) and Amendment No. 47 (Revision 11 to the Final Safety Analysis Report) to Consumers Power Company's Application for Reactor Construction Permit and Operating License for Midland Plant Unit Nos. 1 and 2 have been served today upon the following persons by deposit in'the United States mail:
U.S. Environmental Protection Agency Mr. Robert B. Chatterton Federal Activities Branch Supervisor of Midland Township Region V Office 928 Clarence Court, Route 7 Attention: EIS Coordinator Midland, Michigan 48640 230 South Dearborn Street Chicago, Illinois 60606 Mr. Daniel Ranck, Chairman Midland County Board of Executive Office of the Governor Commissioners Division of Intergovernmental Midland County Courthouse Relations Midland, Michigan 48640 2
Lewis Cass Building Lansing, Michigan 48913 Mr. Phillip F. Gustafson, Manager Environmental Statement Project Argonne National Laboratory 9700 South Cass Avenue Argonne, Illinois 60439 k
WY ust
@tf/
Alice R. Ginsburgh 6/
Attorney Consumers Power Company Dated: July 10, 1978 g
4 i
4 T'
.~..,
r-a
/s
(%
i rM.. v.
y, ~. l
)
., p :~ -,,...
-.. } -
~~ ~w -w m
c 4
= p *. ad
/,.
^u
- g
.j' U~'"~*
i j
lff h
simia i t e. nc.swu Yke l' est.i.nr Q
cc.r,a cui,:.n: iv., vie.: r nua n
- a. ;.,csso., rxeurn.mC1
- Area Co Ja G17 700.OZ3 O
June 29, 1910 bt ilm.re 114-76
\\
13CC: M,Ca c tle'v e r r'.
s Y
Ci,kuha:N.-
JI.cr.c 'n
,j,
.'A re:c ror of.iucitt.r lic ; 'tcr &_gnit.L;.en L,.h.
. A.c--
- c
\\
?.i i r..
1.fr k er Ocyd, Director P/,l err.-
Divi ci on of fro,je::t.::c.u.~cun*;
JJZ:Grituf;i U1 ilueleo.r iter;ule.tery Cc malsalon 19,c;;chj k
' hoinint,L on, 12:; EGSM D:.J.:111er i
..aIs,o;. d tw3.. Js.
,r.,
u
..t _
DOCQ!i' MO 50- Jr, 50-330 h3GJi31 FDE AUDif10: AJ, li!ro!WSIO:!-
Pi;0PRII./2tJ:( 123OKA?lo.! r J 0:!S
'211.:. :
GW5.6
..:r.lC Ai,:
55;22
! aca cc.ent s,. to the C:;quy 's op,ulic.ation for ec>::';truc tion ;;er::1.tc c.d optr;tirl;.:._c enrec con',alaud I;evi;ica ',' to thc 2 in 11 i'/ fety /M 2y.-sis
.u.1.,..,.
In i:cv::cle n ;', 20 indict.;,c0 that our rer ps:ne to c.;rtr ir "EC Ee':nc.nn fv., Ada li,1co:U. I:u.'rr trion una propr.i et ary in n:.ture c2>:1 t cu.trl be ceL.r;;cd vi:. se m.te covn':
re tuulos.t m five ( ?) c mien of rourcn3cn t > tco fol.LotinG ICC
.. c regt.est", fur E.iditiciv.:.'. j uforr. anon.
31.J O ( h..':.l. 6)
T,enign of Absorber !r.terial
.'C,1. 1 3 (!:..].6)
Cornerva tica :.f !.ini:cm Un$.creaate6 J s,r*:af. !: M!. '
2 ;, i,....,.i ( ;4... 1, e )
t.,.i._
..a...,.., e 2.,
o.,tc o s,
2?,1,16 (h.2.. 3)
Fu;l I'cd n cun
.c d 3.
n.,. (.p.
....)
J.L a.s u,_. M *.
r
.i s a w-
.s s..<.
a.r.
.1, c, 2 =...,., u.a e
> j,...a...G..*..
v ; '.~..rs e..m-Fl. uw...v cir;;:
Pe rec.ut:.
in:.t thcac a rmen:ca 1:..: i,: ::c] d :^rc:,
no3 dr 14 lon.rc ri in :::ccrd." to '; c h wie: p aviciouc c.~
1C.. 2. I; '
- },.-
'c c :clxir eit p q :.co.: ', e ce: ; '
O ra:
rhia' JD-
. !c:
- .- mer r. v n:,
..r c
t to ;r. Withi:uld i rc4" i. il ic f.' F; 3 7m c
. '. ' ', i r
'9
- fcf :lh; TSP i
. ~
- -~~
-~.,s
~
... ~..
%g
.. *s g.,F*.***,
3
,ie,
}.
't..="
~s s
I
}
Babcock &MScox AFFIDAVIT OF JAMES E. TAYLOR A.
My name is James H. Taylor.
I am Manager of Licensing in the Nuclear Power Generation Division of Babcock & Wilcox, and as such I am authorised to execute this Affidavit.
B.
I am familiar with the criteria applied by Babcock & Wilcox to determine whether certain information of Babcock & Wilcox is proprietary and I am familiar with the procedures established within Babcock & Wilcox, particularly the Nuclear Power Generation Division (NPGD), to ensure the proper application of these criteria.
C.
In determining whether a Babcock & Wilcox document is to be classified as proprietary information, an initial determina-tien is made by the unit manager who is responsible for originating the document as to whether it falls within the criteria set forth in Paragraph D hereof.
If the information falls within any one of these criteria, it is classified as proprietary by the originating unit manager.
This initial determination is reviewed by the cognisant section manager.
If the document is designated as prcprietary, it is reviewed again by Licensing personnel and other management within NPGD as designated by the Manager of Licensing to assure that the regulatory. requirements of 10 CFR Section 2.790 are met.
D.
The following information is provided to demonstrate that the provisions of 10 CFR Section 2.790 of the Commission's regulations have been considered:
(i)
The information has been. held in confidence by the Babcock & Wilcox Company.
Copies of the document are clearly identified as proprietary.
In addition, whenever Babcock & Wilcox transmits the information to a customer, customer's agent, potential customer or regulatory agency, the transmittal requests the recipient to hold the information as proprietary.
Also, in order to strictly
0~
a 3
4 Babcock &Vii!cox AFFIDAVIT OF JAMES H. TAYLOR (Cont'd) limit any potential or actual customer's use of proprietary information, the following provision is included in all proposals submitted by Babcock & Wilcox, and an applicable version of the proprietary provision is included in all of Babcock &
Wilcox's contracts:
" Purchaser may retain Company's Proposal for use in connection with any contract resulting therefrom, and, for that purpose, make such copies thereof as may be necessary.
Any proprietary information concerning Company's or its Suppliers' products or manufacturing processes which is so designated by Company or its Suppliers and disclosed to Purchaser incident to the performance of such contract shall remain the property of Company or its Suppliers and is disclosed in confi-dence, and Purchaser shall not publish or otherwise dis-close it to others without the written approval of Company, and no rights, implied or otherwise, are granted to pro-duce or have produce.d any products or to practice or cause to be practiced any manufacturing processes covered thereby.
Notwithstanding the above, Purchaser may provide the NRC or any other regulatory agency with any such proprietary information as the NRC or such other agency may require; provided, however, that Purchaser shall first give Company written notice of such proposed disclosure and Company shall have the right to amend such proprietary information so as to make it non-proprietary.
In the event that Company 'cannot amend such proprietary information, Purchaser shall, prior to disclosing such information, use its best efforts to obtain a commitment from NRC or such other agency to have such information withheld from public inspection.
Company shall be given the right to participate in pursuit of such confidential treatment."
(2)
T j
Babcock &Wilcox AFFIDAVIT OF JAMES H. TAYLOR (Cont'd)
(ii)
The following criteria are customarily applied by Babcock & Wilcox in a rational decision process to determine whether the information should be classified as proprietary.
Information may be classified as proprietnry if one or more of the following criteria are met.
a.
Information reveals cost or price information, commercial strategies, production capabilities, or budget levels of Babcock & Wilcox, its customers or suppliers.
b.
The information reveals data or material concerning Babcock & Wilcox or customer funded research or development plans or programs of present or potential competitive advantage to Babcock & Wilcox.
c.
The use of the'information by a competitor would decrease his expenditures, in time or resources, in ddsigning, producing or marketing a similar product.
d.
The information consists of test data or other similar data concerning a process, method or component, the application or which results in a competitive advantage to Babcock & Wilcox.
e.
The information reveals special aspects of a process, method, component or the like, the exclusive use of which results in a competitive advantage to Babcock &
Wilcox.
f.
The information contains ideas for which patent protection may be sought.
The document (s) listed on Exhibit "A",
which is attached hereto and made a part hereof, has been evaluated in acccrdance with normal Babcock & Wilcox procedures with respect to classification and has been found to contain informaticn which falls within one or more of the criteria enumerated above.
Exhibit "B"3 which is attached hereto (3)
0 Babccck&Wi!cox AFFIDAVIT OF JAMES H. TAYLOR (Cont'd) and made a part hereof, specifically identifies the criteria applicable to the document (s) listed in Exhibit "A".
(iii)
The document (s) listed in Exhibit "A",
which has been made available to the United States Nuclear Regulatory Commission was made available in confidence with a request that the document (s) and the information contsined therein be withheld from public disclosure.
(iv)
The information is not available in th,e.open literature and to the best of our knowledge is not known by Combustion Engineering, EXXON, General Electric, Westinghouse or other current or pctential domestic or foreign compe-titors of B&W.
(v)
Specific information with regard to whether public disclosure of the information is likely to cause harm to the competitive position of Babcock & Wilcox, taking into account the value of the informatin to Babcock & Wilco.x; the amount of effort or money expended by Babcock & Wilcox developing the information; and the ease or difficulty with which the informatiod could be properly duplicated by others is given'in Exhibit "B".
E.
I have personally reviewed the document (s) listed on Exhibit "A"
and have found that it is considered proprietary by Babcock
& Wilcox because it contains information which falls within
~
one or more of the criteria enumerated in Paragraph D, and it is information which is customarily held in confidence and pro.-
tected as proprietary infcrmation by Babcock & Wilcox.
This report comprises information utilized by Babcock & Wilcox in its business which afford Babcock & Wilcox an opportunity to obtain a competitive advantage over those who may wish to know or use the information contained in the document (s).
,/O,
/,
/
/*r..,
,../
r -"
JAME3 E. TAYLOR a
G d
Babecek&Wi!cox State of Virginia)
)
SS.
Lynchburg City of Lynchburg)
James H. Taylor, being duly sworn, on his oath deposes and says that he is the person who subscribed his name to the foregoing statement, and that the matters and facts set forth in the statement are true.
-1
. - /.,
/
/.
/.n n,,,'~.
..,j.
James H. Taylor Subscribed and sworn before me this 9
day of Q o M 1978.
/
il4 0Yzeb Notary Public in and for theAity of Lynchburg, State of Virginia My Commission Expires t/t#t/ 2.-C/9fd
//
\\
I (5)
EXHIBIT B
]
L.)
r Proprietary Nature of Material in Exhibit A Applicable Item Question No.
Description of Material Criteria I
231.10 Expressions used to describe c,d swelling, conductivity, thermal expansion, and gas release of absorber materials II 231.13 Calculated value's of clad c,e strain for control compo-nents III 231.16 Fuel rod stre'ss evaluation c,e IV 231.14, Results of post-irradiation b,c,d Tables 253 examination of Oconee-1 fuel assemblies V
231.22 Dimensions and constants e
of.the fuel rod springs Specific information with regard to potential harm to BSW by disclosure of this material includes the following developmental costs incurred on each of the.above items.
Item Costs (dollars)
I
>90,000 II
>50,000 III
>60,000 IV
>2,000,000 V
>60,000 4
,n Y
QUESTIO:!:
231.10 Please list the numerical values and equations, along with their (4.2.1.6) reference sources, for the pertinent ther=al-physical properties used in
-the design of the Ag-In-Cd and A1 0 -3 C absorber materials.
A mini =u=
3 3 4
list of pertinent properties should include melting point, swelling,
~
thermal conductivity, thermal expansion and gas release.
Also list the calculated expected values for end-of-life swelling and gas release and compare these to the maximum allowable design values under normal and off-normal conditions ; i.e., Conditions I through IV.
RESPONSE
(?roprietary Information)
I.
The following are the properties for A1 0 -3 C as functions of temperature 23 4 burnup, and density where applicable.
Melting Point:
The melting point used is the lower melting point of the mixrures' components.
Since the constituents are not chemically combined, the lower melting Point gi.ves con'scrvative estimates in the analysis. Thus, the melting point used is 3700 F (melting point of Al 0 ),
23 s
Source:
R. P. Elliott, Constitution of Binary Allovs, First Supplement, 1965.
Swelling:
The suelling of A1 0 -3 C results from fast neutron irradiation damage 9 3 4 of the alumina and thernal neutron irradiation absorption by the 3 C.
To yield 4
a conservative design, the swelling of both types of materials uns added to gain' a total pellet swelling. Thus, the interactions between the B C particles and 4
the alumina were not considered in the model.
The swelling curve used may be i
described by:
-21 AV/V(%) = 1.2 x 10 x (nyt) for B burnup < 80%
-21 0
AV/V(%) = 8 + 1.2 x 10 x (nyt) for 3 burnup > 80%
Sources:
1.
R. J. Burian, E. O. Fromm, and J. E. Gates, "Effect of High Boron Burnups and Zirealoy-2",
BMI 1627 (1963).
Dispersions in A1,03 onBfCandZrB 9 2.
W. A. Ranken, 7. G. Frank, G. W. Kc11 holt, "Effect of Fast Neutron Irradia-tion on Alumina and Yttria", LA-DC-72-535, (1971).
Thermal Conductivity:
Since the thermal conductivity of the alumina is about 40% lower than the condectivity of B C, the addition of the small amounts 3 C 4
4 should, if it'has any effect, slightly increase the conductivity.
To be con-servative, the values for alumina were used for the alumina-boron carbide pellets.
This curve is corrected as a' function of pellet density.
The expressions are:
k=hD-20)/dhkJ00.,where D is the percent theoretical density and kl00% " II 1
4 1 -2.225x10~1
-0 2
- T 4-7.587 x 10-T T + 3.639 x 10 T - 2.715 x 10 6.050 x 10 where h,00% = BTU /hr. ft F/ft and T = Or.
2
O c
J. F. Lynch, C. R. Ruderer and W. H. buckworth (Ed.) " Engineering J,
Scurcc:
Properties of Sclected Ceramic Materials", American Ceramic Society, Columb,us, Ohio, 43218, (1966).
The thermal expansion rates of the two constituents Themal E:cpansion_:Since the alumina has a higher rate of expansion and were compared.
comprises the =ajority of the caterial, its rate was chosen for the The coefficient of ther=a alumina-boron carbide pellets and is conservative.
expansion for alucina is a = 4.4 x 10-6 in/in F.
J. F. Lynch, C. G. Ruderer, and W. H. Duckworth (Ed.), " Engineering Source:
Properties of Selected Ceramic Materials", A=erican Ceramic Society, Columbus, Ohio, 43218, (1966).
Calculations using data from the cited reference indicate'a-Gas Release:
maximum release of 95% and a minimum release of 20%.
R. J. 3arian, E. O. Fromm, J. E. Gates, "Effect of High Boron Sourec:
Dispersions in Al 02 3 and 2ircaloy-2", BMI-Burnups on B C and ZrB2 1627,-(1963)
The following are the properties for Ag-In-Cd as functions of temperature II.
and burnup:
Melting coint:
1427 F C. R. Tipton, Jr., ed., Reactor Handbook, second edition, Vol.1,
~
[
Source:
\\
USAEC, 1960.
Swelling:
The suelling of Ag-In-Cd results from irradiation damage (void A
fomation, etc.) and by transmutation of the constituent clements.
- linear fit of available data was made resulting in the equation:
'AV/Y(%) = 7.11 x 10-22 x (nyt)
(nyt) = thermal fluence Anderson, W. K. and Theilacksr, J.
S., " Neutron Absorber Source:
Materials for Reactor Control", USAEC, 1962.
Thermal Conductivity:
A fit to available data was done to obtain the following model for thermal conductivity:
i 1.266 x 10-S 2 + 3.259 x 10-9T3 - 5.715 x k = 30.46 + 3.043 x.10-2T T
10-13 "
BTU /hrft F T
T=
F Bettis Technical Revicu, Reactor Metallurgy, WAPD-BT-6 Source:
a = 12.5 x 10-6 ofy Linear Coef ficient of Thermal E:<oansion:
Anderson, W. K. and Thcilacker, J. S., "Noutron Absorber Source:
Materials,for Reactor Control", USAEC, 1962.
Q III.
These properties are used to determine that melting does not occur and the end of life internal pressure and clad strain criteria are not exceeded. For all control components, analyses have been perfor=cd to show that pellet melting does not occur.
Pellet swelling and gas release calculations have been perfor=cd to deter =ine end of life pressures.
For the control rod and axi-al power shaping rods these Pressures are insignificant. For the burnable poison rod the end-
~
of-life pressure is significant but remains below system pressure.
Clad strain is discussed in Section 4.2.1.6.3.
il e
O S
4 e
-e
+
1 6
4
Q V
QUESTION:
231.13 Please demonstrate that the use of minimum unirradiated strength values (4.2.1.6) for the control rod and burnable poison rod cladding alloys is con-servative under all postulated reactor conditions; e.g. demonstrate that the increased strength due to irradiation is not affected by a decrease in ductility.
Please discuss the bases for the 1% and 3% strain limits for 304SS and Zircaloy-4 cladding, respectively.
Show hcw these limits are consistent with analytical and test results, as stated in FS AR acetion 4.2.1.6.3.
Please list and briefly describe the control component examinations mentioned in FSAR section 4.2.1.6.4.
RESPONSE
(Proprietary information)
Cladding Stress-Strain Limits These stress intensity limits are based on the minimum unirradiated material strength.
These are conservative because strength of both materials increases with irradiation.
Cladding strain limits are applied to ensure that strain capability of the cladding is not exceeded by strain due to abosrber expansion.
These strain limits take into account the loss of ductility of the material under irradiation.
For 304 stainless steel cladding the strain limit is 1%.
Research has shown that the ductility of this clad will remain greater than 1% total elongation throughout the lifetime specified for the control rods which is the limiting control component with 304 stainless steel clad.
For Zirealoy-4 cladding the strain limit is 3T.
The burnable poison rod, which is the only control cenponent using this clad, is designed for ene cycle only.
It will receive much less irradiation than the control rods and thus will experience less ductility loss.
The calculated strain values and safety =argins,for the contrcl components are as follows:
' ontrol Component Clad Strain C
Allowable Calculated Component Strain Strain Margin Control Rod 1%
.99%
1%
Axial Power 1%
0 oo Shaping Rod Burnable 3%
1.62%
85%
Poison Rod Control components have been visually examined following up to tuo cycles of operation in the reactors at the Duke Power Oconce Station.
B&W destructive examinations on one burnable poison rod assembly (end-of-cycle 1) and one axial power shaping rod (end-of-cycle 3) are in progress.
The axial power shaping rod contains Ag-In-Cd and theref ore, Will yield information which is ayplicable to the control rod.
The test results will be used to evalualc the analytical results.
e
QUESTION:
231.16 Please provide nu=crical values for fuel rod stresses caused by (a)
(4.2.3.1) pressure differential (b) ovality bending, (3) thermal, and (d) grid loads for the worst case Condition I through IV events.
Provide numerical.
evidence to support the assertion that differential fuel rod growth and flow-induced vibration stresses do not affect these worst case stresses.
RESPONSE: (PROPRIETARY INFORMATI3S) l
~~'
~
... Internal Fuel Pin Pressure -
a.
Pressure Evaluation Maximeq internal fuel rod pressures are calculated as a function of burnup using the TACO computer code.
TACO is an internal pressure and temperature distribution code and is discussed in Subsection 4.2.1.3.
The internal pressure calculated for the hot fuel rod is shown in Figure 4.2-7.
The hot rod power history (i.e., radial peaking factors versus burnup) is shown in Figure 4.2-8 and was determined by envel-oping "the maximum radial power factors obtained from fuel cycle physics calculations at various burnups.
Thus, the radial power factor applied throughout the burnup was that of the hot rod although no single rod will experience the maximum radial peak during its entire core life.
The calculations arc based on design power unich is necessary to obtain realistic values of burnup and other burnup re-lated parameters; e.g., irradiation growth, fission gas release, and cladding creep.
Fuel red di=cnsions, pellet densities, and the axial peaking factors input to tce code are given in Table 4.2-6.
Conser-vatism in the thermal-physical data, determination of pouer peaking factors, and other input parameters associated with these pressure calculatior.s are discussed in Subsection 4.2.1.3.1.
b.
Stress Evaluation The fuel rod cladding is subjected to external and internal pressure, thermal gradients, grid loads, ovality induced loads, vibration, and differential fuel rod growth.
The fuel rod cladding stress analysis is based on several conservative assumptions that increase the actual margins of safety over the calculated margins.
Section III of the ASME 3 oiler and Pressure Vessel Code is used as a guide in classifying the stresses into various categories, assigning appropriato limits to thes2 categories and combining the stresses to determine the stress intensity.
Present design criteria require that the internal pressure does not exceed system pressure during normal opera' tion.
This ensures that cladding stresses due to the pressure differentici are always compressive during normal operation.
The following stresses were addressed in the analysis:
1.
Pressure differential stresses 2.
Ovality bending stresses
.l, g
3.
Thermal stresses 4.
Grid load stresses The resulting stresses for conditions I, II, and III are su=marized as follows:
The worst case is found to be in the clad laner surface Stress at Radial Hoop Axial Shear Clad ID o
a "z
T 0
pressure
-450 psi -21,75Spsi -11,104 psi ovality
- 2,181 psi thermal
- 4,213 psi - 4,213 psi grid load
- 3,786 psi - 5,488 psi 1592 psi Stress intensity S = c2 - o3 where c2 > c2 > J3 without shear stress Stress intensity S = M(c2 - c 3) 2 +4 r2 with a shear stress The resulting stress intensities for the various stress categories are:
primary membrane (averaged throudh wall)
~
S = 19,008 psi
~'
primary plus bending S = 23,489 psi
, primary plus secondary S = 31,648 psi Differentini fuel rod growth (o = 7 887 psi) and flew induced 145 psi) stres!es we,re analyzed and found not vibration (c
=
to z
effect the worst case stresses because the summation of the axial stress (o.,) is the middle stress (o2) of the three principle stresses and will not be counted in calculating stress intensity.
In addition, the flow induced vibration stress is of small magnitude and is of no significance.
Internal and external pressures, thermal gradients, and grid loads were determined and analy::cd si=ultaneously.
Conservative cladding dimensions were used.
The worst case conditions for this analysis ucre found to occur at beginning-of-life (30L).
Long-term creep ovality stresses are addressed in the creep collapse analysis.
The primary c:embrane stress uns found to be less than two-thirds of the miniaua specified unirradiated yield strength and all strecacs
~
were less then the minimum specificd unitradiated yield strength.
In all cases the margin is in excess of 30*.
- on.o2 03 represent orthor,onal stresses which are not necessarily principle stresses
g y
PROPRIETARY TABLE 2 OCONEE-1 NON-DESTRUCTIVE PIE PROGR!al SIR 0fARY OF RESULTS TilROUGH TWO CYCLES O
Average fuel rod growth 0.3%
0 Average assembly grcwth 0.2%
0 Holddown spring preload within as-built tolerance range O
Rod bow less than 15% closure in 95% of the cases O
Average rod creepdown approximately 3 mils
~
o Average assembly bow 0.2 inch e
t 3
e.
Q
~,
PROPRIETARY TABLE 3 sum!ARY OF DESTRUCTIVE TEST FHASE RESULTS OCONEE-1, END-OF-CYCLE 1 0
No evidence of defects or significant fretting 0
Average rod creepdoim approximately 2 tills 9
Fuel densification as predicted by model 0
Internal pressure decreased 15%
l{
0 Fission gas release less than 1%
0 Cladding tensile strength at 125% of unirradiated value 0
Cladding total elongation at 80% of unirradiated value e
e
- O g m$
(-
,m
~
0 QUESTION; e
231.22 Please provide the dimensions and spring constants for the upper and (4.2) lower plenum springs and show quantitatively that the resistance to s
creep and relaxation of the spring alloy is sufficient to withstand the worst postulated flux, temperature, and stress conditions.
RESPONSE
(Proprietary Information)
The dimensions of the upper and lower fuel rod springs are sum =arined below:
Upper spring - Material = SS302 Wire Dia d =.062 in.
~
Outside dia OD =.360in.
Number of active coil N = 27,,
Lower spring - Material = A - 286 Wire dia =.075 in.
Outside dia OD =.360 in.
Number of active coil U = 17
~~
The spring constants were calculated by using the following equation:
4 K = Gd3 where G:
shear modulus gg n d: wire dia D = OD - d n:
number of active coil The calculated noninal spring constants are:
Upper spring 26.63 lb/in Lower spring 103.52 lb/in An elastic-plastic analysis of the fuel rod springs was performed.
This analysis accounted for temperature, fluence, fuel column weight, and irradiation growth.
Permanent set in the springs was determined for the 36 month design life accounting for plastic set, irradiation relaxation and thermal creep.
The results were a permanent set of the upper spring of % 0.9 in. and of the louer spring of 0.1 in.
Since the upper spring does not support the fuel column, its set is acceptabic.
The set of the lower spring was determined not to cause a significant displacc. ment of the fuel stack.
Post-Irradiation Examination af ter one cycle of fuel rods containing lower springs showed littic or no settling of the bottom of the fuel column.
This supports the analytical results.
[
-=
,,,,,