Proposed Tech Specs Amend Suppl Modify SR 4.4.5.2e Re Rotating Pancake Coil & 4.4.5.4a.13 Reference to non-current MethodologyML20078N184 |
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Site: |
Catawba |
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Issue date: |
01/27/1995 |
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From: |
DUKE POWER CO. |
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To: |
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Shared Package |
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ML20078N165 |
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References |
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NUDOCS 9502150166 |
Download: ML20078N184 (2) |
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Category:TECHNICAL SPECIFICATIONS
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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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[Table view] |
Text
\
- REACTOR COOLANT SYSTEM
' SURVEILLANCE REQUIREMENTS (Continued)
' 1) All nonplugged tubes that previ'ously had detectable wall penetrations (greater than 20%),
- 2) Tubes in those areas where experience has indicated potential problems, and
- 3) A tube inspection (pursuant to Specification 4.4.5;4a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this sha'l be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
- c. For Unit 1, in addition to the 3% sample, all tubes for which the alternate plugging criteria has been previously applied shall be inspected in the tubesheet region.
- d. The tubes selected as the second and third samples i('f required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided: i
- 1) The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found, and
- 2) The inspections include those portions of the tubes where imperfections were previously found.
- e. For Unit 1, implementation of the interin steam generator tube / tube support plate elevation plugging limit fr 0715 requires a 100%
bobbin probe inspection for all hot leg tube support plate intersections and all cold leg intersections down to the lowest cold 58" MW# les tube support plate with outer diameter stress corrosion cracking pAoM ATTMasb -(00 500) indications? An inspection using the rotating pancake coil yAGE (RPC) probe is required in order to show operability of tubes with flaw like bobbin coil sinami - litudes orantar
" '- ^ - #
than 1.6 vo't but i.i.1 u r aL w7 ,val E " - '-" ;) l l a< m < t hma r r, r r, .....tn
. J""]'.ID.
c.1i y.",y.
"U. L"'
,, . = /The"rt
'P !"N 4 n '"= '
n resuiu are to ersivates to establish'Inat tne princ' pal indications can be e characterized as 00 SCC.
The results of, each sample inspection shall be classified into one of the following three categories:
Q1ggn Insnection Results C-1 1.ess than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective. 4 l
l CATAWBA - UNITS I & 2 3/4 4-13 Amendment No. (. Unit 1)
. Amendment No. (Unit 2) i p pg AD CK O O Op P
J
REACTOR COOLANT SYSTEM
.. SURVEILLANCE REQUIREMENTS (Continued) 17..h is verifie o result in total primary to secondary leakage less than iHhe-gpm Lincludes operational and accident leak-f* *
- 1?[$U54?iif'IliU ?? I& 5 I'
l 'h'EJ;rTI?T'LTLZ,'["lMIM? l!"l2h"~r.'$
T vr LLLTi2 hidi Eid-e,k iikg'I1I I T ~1I~~
~
r ,r , ,, , ,
- 2. A tube can remain in service with a bobbin coil signal amplitude greater than 1.0 volt but less than 2.7 volts provided a rotating pancake coil (RPC).. inspection does not detect degradation.
- 3. Indications of degradation with a flaw type bobbin coti signal amplitude of equal to or greater than 2.7 volts will be plugged or repaired.
pas 2RT MRhodth98 Certain tubes as identified in WCAP-1349(, Rev.1, will be 4 N "" excluded from appiteation of the Interim Plugging Criteria t.imit 966'E as it has been determined that these tubes may collapse or deform following a postulated LOCA + SSE Event. ;
- b. The' steam generator shall be determined OPERASLE after' completing the
.- corresponding actions (plug or repair all tubes exceeding the repair
- limit.and'al tubes containing through-wall cracks) required by Table 4.4-2. ~ For Unit 1, tubes wit 3 defects below F* fall under the alternate tube plugging criteria and do not have to be plugged.
4.4.5.5 Ranaris *
. a. Within 15 days following the comp'letion of each inservice inspection of steam generator tubes, the number of tubes rept. ired in each steam generator shall'be reported to the Coemission in a Special Report pursuant to Specification 6.9.t;
- b. The complete results'of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to
/ Specification '6.9.2 within 12 months following the completion of the inspection. This Special Report shall include:
, 1) Number and extent of tubes inspected, I
l CATAWBA - UNITS 1 & 2 3/4 4-16a Amendment No. (Unit 1)
Amendment No.1 (Unit 2) w-=- --