ML20138D035
| ML20138D035 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/16/1985 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML19344C066 | List: |
| References | |
| NUDOCS 8510230147 | |
| Download: ML20138D035 (3) | |
Text
Mlachacal T
o <- I e4 L i
(
SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria a.
As used in this Specification:
1.
Imperfection means an exception to the dimensions', finish or contour of a tube from that required by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be
(
considered as imperfections.
2.
Dearadation means a service-induced cracking,
wastage, wear or general corrosion occurring on either inside or outside of a tube.
3.
' Degraded Tube means a tube containing imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation.
4.
% Degra'dation means the percentage of the tube wall thickness affected or removed by degradation.
5.
Defect means an imperfection of such severity that it exceeds
(
the plugging limit. A tube containing a defect is defective.
6.
Pluagina limit means the imperfection depth at or beyond which the tube shall be removed from service d is equal to 40% of the nominal tube wall thickness.(NoTr 1 7.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.
8..
Tube Inspection means an inspection of the steam generator tube
(
from the point of entry (hot leg side) completely around the A.
U-bend to the top support of the cold leg.
N011 # li Th r e A*Eu hd does.uA hoW 4o 4ks_ nose d 4ubac..
in Aba 4.M &ecA vanns 46a (.id*taches W6m 4 ho_ -4em _
cE46 4.h and ovutA ab.a 4tu 4uho Ants uch kit
(.
'alard 4 h dtwealfv ahmia. N [ oaa vrau bdae M M
t gua6m, =, cat =4j.
9510230147 851016 3
/
PDR ADOCK 05000395
(
p PM SUMER - UNIT 1 3/4 4-14 m
D 9
.___--~,-.-ee-w-n
~,--%
emw---em
~.
.. ~.
~. - -.
r l
3 4
h, en nm j
TABLE 4.4-2 N
4 rei y
i i
m o=
i STEAM GENEnATOn TUSE INSPECTION n
C o
- lc o
I r-f U
1ST SAMPLE INSPECTION 2ND SAM *LE INSPECTION 3nO SAMPLE INSPECTION g
l j
1 Sempio Sies non.n Aciion need ne==
Acinea need newei n iinn naisi. ired
-l l
j A sminismen el C-1 None N/A N/A N/A N/A
- m 5 Tehes per S. G.
e4 Rese#
C-2 Plug 4petective tiees C-1 a a,h N/A N/A i
emi inspect MW PlugWestive stees C-1 Noneor m p Ae,4 25 eines in this S. G.
C-2 and inspect e&fielonel C-2 Plugilielective autus 45 embes in stels S. G.
g ;
Perform action for C-3 C-3 result of first 4!
i semple 9 i Perform action ser gl e,s
}
C-3 C-3 result of first N/A N/A g i 1 i 1
a e
C-3 anspect all j. An easier m
y this S. G.,
S. G.s are 00 ens N/A N/A t !
factive tubes and C-1
-\\ i
)
escia eeher S. G.,in inspect 25 tubes Some S. G.s Perferne action for.
N/A N/A C-2 but no C-2 result of second H,
p addielenet g
1 Prompt notification S. G. are j
l to Nnc purement C-3
'O se 10 CFR 50.72 mi
,,,,,,,,,,,,,,,i,,
- g (b)2(1) and S. G. is C-3 each S. G. and plusi 10 CFR 50.73(a) deseceive aulus.
i i
Y I
2(11)
Prompt noillicopen N/A N/A f
to Nnc pureusen W
se 10 CFR 50.72
' ?
l*
(b)2(1) and 10 CFR 50.73(a)2(ii) f t
,, 3 g w.ie,. N is me
,*e, of sisem - e,s in me
..nd n is d. ni.neet. si.e.n -e.e,s inspecien a
ing en inspeciion i
3
% AffAtt SY AsRc AfftevEb SLEEV/NG METHo b a
T i
- -. ~
A TTAcn wnr I
se3J3 v
8s REACTOR COOLANT SYSTEM BASES
(
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be main-(
The program for inservice inspection of steam generator tubes is based tained.
on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage j
or progressive degradation due to design, manufacturing errors, or inservice
(#
conditions'that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube
~
degradation so that corrective measures can be taken.
)
The plant is expected to be operated in a manner such that the secondary i
coolant will be maintained within those chemistry limits _found to result in
~
negligible corrosion of the steam generator tubes.
If the secondary coolant
~
chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking. The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system j
(prie.ary-to-secondary leakage = 500 gallons per day per steam generator).
Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads t
l
(
imposed during normal operation and by. postulated accidents. Operating plants l
have demonstrated that primary-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown. Leakage in excess of this limit will require plant shutdown and an l
unscheduled inspection, during which the leaking tubes will be located and plugged.
I Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.
However, even if a defect should develop in service, it
- P.*'M ill be found during scheduled. inservice steam generator tube examinations.
M*" "w?kggi:;g will'be required for all tubes with imperfections exceeding 4he-t piogghg ikit # 40% of the tube nominal wall thickness.
tube inspections of operating plants have demonstrated the capability to
(
reliably detect degradation that has penetrated 20% of the original tube wall thickness.
l
)
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Commission l
i pursuant to 10 CFR 50.72(b)2(1) prior to resumption of plant operation. Such
(
cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional l
\\
eddy-current inspection, and revision of the' Technical Specifications, if necessary.
B 3/4 4-3
=
M W-
- SIMIER - UNIT 1 l
r.j e
-,,Y-
,y,,., _,
-,--..,-----.--,-.------eg
,%,.__,.,,,yy__.__,.,---__,,pn,.._
%w.
,,.,,i,.-,..,.--.-,-h,.._...__,_.,m..._,
-._-.w._,,w,um-.,