ML18347A681
| ML18347A681 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/06/1976 |
| From: | Bixel D Consumers Power Co |
| To: | Purple R Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18347A681 (7) | |
Text
consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 April 6, 1976 Director of Nuclear Reactor Regulation Att:
Mr Rob~rt A. Purple, Chief Operating Reactor Branch No 1 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255*, *LICENSE DPR PALISADES PLANT -
CORRECTIONS TO ALLOWABLE TUBE WALL DEGRADATION ANALYSIS Our letter of February 12, 1976 transmitted a request titled "Analysis To Determine Allowable Tube Wall Degradation for Palisades Steam Generators."
Following submission of that report, a number of errors have been observed and corrections made by letter dated March 22, 1976.
This letter corrects an additional error (which was discussed previously with members of your staff).
The following pages have been revised correcting this error:
Title Page Sheet 13 Sheet 14 Figure A.18 Figure A.19 Figure A.19A (New Page}
The border has been marked where changes are attached.
David.A. Bixel Assist~nt Nuclear Licensing Administrator CC:
JGKeppler, USNRC 3490
I.
.NUCLEAR POWER SYSTEMS COMBUSTION ENGINEERING, li'JC.
COMPONENTS ENGINEERING Chattanooga, Tennessee
,ANALYSIS TO DETERMINE ALLOWABL~ TUBE WALL DEGRADATION FOR PALISADES STEAM GENERATORS P. L..Anderson J. w. Bass
- w. Q_. Gurley J. w. Hiestarid J. P. Houstrup D. s. Cassell
- w. J. Heilker F. P. Hill, Jr.
January 29, 1976 Revision 1, March 5, 1976 Revision 2, March 30, 1976
c*
COMBUSTION-ENGl.ERING, INC.
NUMBEass-21.
SHEET
/.3 OF----
DESCRIPTION __
.,_P_A_L_I~,S_A_D_E_S_S_T_E_AM G_E_N_E_R_A_T_O_R __
- a.
LOCA + SSE - Bend Region (Cont'd)
The corresponding axial and hoop pressure stresses are:
PRi 2.2 ksi 0Axial = Tt: =
and PRi 0 8 = -:r- = 4.4 ksi The resultant stress intensity is formed by the com-bination of.the total compressive bending stress and
- the tensile hoop pressure stress. Figure A.19A pre-sents the stress intensities determined for the
- healthy tube geometry and a 64% degraded tube.
Re~
sults for the degraded tube indicate a stress intensity of 74.3 ksi.
The specified Appendix F faulted condition allowable
- for membrane stress is Smemb ~-.7 Su= 2.4 Sm= 56 ksi The membrane plus bending allowable is taken as s
= f x s memb + bend s
memb where f 8 is the appropriate shape factor shown in Figure A.21.
From this figure for the degraded tube with an axial membrane stress of 6.1 ksi and f's = 1. 44
~ -
COMBUSTION EN.EERING, INC.
NUM.
SHEET~--=/~~'----OF--~--
PALISADES STEAM GENERATOR_
DESCF?IPTION -
~--~-___________________________ _;._ ________
~
- a.
LOCA + SSE - Bend Region (Cont'd)
The corresponding allo*1rable membrane plus bendi.ng stress int~n~ity is s
= i.44(56) = ao.6 k~i memb + bend wh~ch exceeds the elastically calculated stress in the degraded tube.
The results of the elastic LOCI\\, -t-SSE analysis are summarized in Figure A.19.
- b.
NRC Staff (Knight's) Criteria...:.. st*raight Region The controlling criteria for the vertical straight tube spans is Number 2 in Figure A.20, which requires a factor of 3. to exist between normal operating.
pressure differentials and the ultimate strength of the tube material; This would neem to be overly conservative since the principal behind it is taken from Section III which is a construction code.
The In~ervice_Inspection Code, Sectio~ XI tends to be more realistic and would seem more appropriate for criteria-of this type however, it offers *no specific guidance at this time.
In spite of the aforementioned conservatism, the tubes are shown to possess a capacity for sustaining 64% degradation and still meet the required safety margins.
~*
. ~
'1 tu
~
t;
~
~
- ~
~
2.0.
/,0 LOCA *.J1-1AKINtj BcNIJlll6.!'rlft:.ss f',q1.1sA1JE.S TU.BG Row //()
Noo~ 16 0 1....t::::==------i--------1--------+---------r-----------lt--------T---------i-----
.0.30*
.090
.Jzo*
olS'O
.IBO
.210
//ME * (s~c)
~
e
.SuMMARY EL/lSTlt: STtel:SS" AN41.VS/~
WtJ~sr eAse ruoa ~ow 110 I/EAi.THY Ttltlt:
STRESS lOADJN6
. /J/1~/iC Tll)N LtJ[A
.4i<1Al
,e19;er; FACTION LOCFI AJ(tAl...
Sll/IK/Nt:,
PRcSSVJ?E "AXIAL HOOP SSE St:1sMie
/IXIAL t =.olf8 111 Ro =
- 315'" IA!
'2 Z = ~0175 IN~
- .fT~GSS_
(KS!)
- +/- ZtJ.()
,+/- 2.0 2.2..
. 4.4
- !. J.. O*
t ::-
- 01128 /Al.
'6~ ~ IJEt;R,t/OE!)
TUB~.* tfo =.31/l/Z9* IN
~
~ = * {J{)Sf 1 111""
La A IJ //IJ'f ST/?t:SS ST KESS 0/RECT/CJlt/
,. (Ks!)
Loc,tJ AX/Ill
+/- 58.6 RA~E,C/ICTIOIJ LOCA
,t}K 11/l t
~9 S/l,l/k IP4 At I Ill 6,/
. PJ! E ~.J 1.1/?E.
H(JtJP IZ.2
.S$£ J'ct.S MIC
,4X/Al
+/- R.9
- A.19 r~v. a
,. -c-*..,--......>1-*
- COMBI'D S'I'TIESS IN'l'ENSJTY A
P,*
B R, HEALTHY TUf3E Stress ( ks:L)
Loading
'rype of Stress Point A Po:Lnt B LOCA Rarefaction M
LOCA Shating crz = +/- -
+23.0
-23.0 z
SSE Seismic (Fi-Po)Ri 2.2 2.2 Oz =
2t
+
+
Pressure (Pi-P0 )Ri
+ 4.4
+ 1~
- l~
00 =
t Or = -Po
- 0.77
- o*. 77 Point A Point B Stress Intensity
[23+2.2-(-0~77)]==26.0 C-23+2.2-(4.4)] =2~.2 6!~% DEGRADED TUBE Loading LOCA Rarefaction LOCA Shaking SSE Se:i.smic i:'rcssure
'l'ype Oz =
. Oz ao =
Or =
of Stress
+/- M
-z (P1_-Po)Ri 2t (Pi-Po)Rj t
-P 0 Point A Stress (ksi)
Point.f:\\
Point B
+67.4
-67. l~
+ 6.1
+ 6.1
+12.2
+12.2
- 0.77
- 0.77 Po:i.nt* :B S~rcss Intensity [ 6-r. 4+6.1-( -o. rn J = Ihi r -67. 11+6.1- ( 12. 2) J== -r3. :>
=
I