ML19329D738
| ML19329D738 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/26/1976 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8003170529 | |
| Download: ML19329D738 (2) | |
Text
_
- c. -
e m,
o ()
e-y
[.6 g "
UM E0 STATES b
M
-1 NUCLE AR GECUi'ATORY COW'IS310M f,.C.)F,$
accionI*
i
-**g$./g.f a.
230 PE ACIM HEC S f R EET. fe. W.
SunVE $1%
,$,g,,
ATuMA, GcORGit. 3J203 AUG 2 6197t, I.
i F. Jape, Reactor Inspector, Reactor Projects Section No. 2, Reactor Operations and Nuclear Suppert Branch, ILE, Eegion II THRU,dI(p.R.Herde, Chief,EngineeringSupportSectionNo.1, Reactor Constructi:n and Engineering Support Bra ch INSERVICE INSPECTION CLASo 2 PIPING, CRYSTAL RIVER 3 - DOCKET 50-302 During the baseline inspection of the Class 2 piping at Crystal River 3,
. including main steam and auxiliary feedwater piping, many ultrasonic reflectors of an undetermined nature were exhibited.
'ihe details of the reflectors and. associated analysis are contained in the following ILE inspection reports:
50-302/75-19 50-302/75-16 50-302/76-11 50-302/76-6 50-302/76-2 The reflectors appear to be gccmetrical in nature and the system has passed cold hydro. However, the reflections are coming frca the root arca of the welds, and the enact sourca has act been determined.
Beenuse cf L.e.latter two facts, it would be desirable to ultrasonically examine or radiograph three or more specific wclds in the main steam and 3
au::iliary 'feedwater lines af ter each ccmplete cycle of a specified number of service cycles (suggest 3) as a neans of assaring that no degradation occurs and to increase confidence in the baseline inspectica test data.
Ihis would provide a chronological sequence of volumetric data related to specific welds and the affect of system service conditiens on these welds.
I It is reco= mended that a' definite co=mitment be obtained frca the licensee, either a requirement be placed on the licensce via the Technical Specification.
Surveillance requirements or by some other means.
After the designated service cycles have occurred, and if the ITs2 data generated at the Y
k' ? V p
k V,
4
/
l '
80_03170$M k
J,,
,s s
' g-F. Jape AUG 2 61976 I
i i
conpletion of each cycJe doec n'at ind!.cace any degrada:.ica of the welds is occurring, then the licensca couM ba permicr.ed to revart to the AS IE Section XI inservice inspectica progrec.
q, /
.//< i ;..,#
?f S. D. Etneter, Reactor Inspector Engineering Support Secticn !!o. 1 Reactor Corstruction and Engineering Support Branch cc:
R. C. Leuis, IE:II S. D. Ebneter, IE:II A. R. Herdt, IE:II O
1
/
x
-as-
-,..m.w
?
/