ML20101B083
| ML20101B083 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/01/1992 |
| From: | Woodard J SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9205050267 | |
| Download: ML20101B083 (3) | |
Text
..
Southern Nucles' Operating Company
- Pot.t Crfce Bon !?DS
[ht.inngham, Abbama 35201 Telephone 205 868 fo86 k
~
L Southern Nudear Operating Company 1 o, w ooo,,,
vce riesvent g,e southern ebcfric systern Riley Project 1
1992 Docket No. 50-364 U.S. Nuclear Regulatory Commission
/TTH: Document Control Desk Washington, D.C.
20555 Joseph M. Farley Nuclear Plant - Unit 2 Steam line Break leakaae Analysis of the Interim Pluaaina.0fiteria Gentlemen:
By letter dated A)ril 1, 10 ', the Nuclear Regulatory Commission issued Amendment 87 to tie Unit 2 operating license regarding the steam generator tube interim plugging cr teria. By letter dated March 27, 1992, Southern Nuclear Operating Company agreed to several additional requiraments included L
in the amendment safety evaluation.
Attached is information concerning unexpected inspection findings and steam line break predicted leakage as iequired by the safety evaluation.
If there are any questions, please advise.
Respectfully submitted, A
wh
,J.
. Woodard s
Attachment cc:
Mr. S. D. Ebneter Mr. S. T. Hoffman Mr. G. F. Maxwell c,..
.2 n j,J -
I 9205050267 920501
\\"
PDR ADOCK 05000364
{l P
pyp
s+
T s
4 4
L P
i I
t 8
Interim Plugging Criteria Analysis l
F r
t i
k 1
r i '
l j
.1 i-T V
i P
-'; h
.,y,.,,,k-wrw.ww,,,,--3.,-,
,,, - ~
6-r a U m.
.--m m.-a.mm,,,m _,., _,,m e_,,~.m.
.,m.,v,,
, % w.,
1, NRC Reauesi The licensee shall inform the Staff, prior to Cycle 9 operation, of any unexpected inspection findings relative to the assumed characteristics of the flaws at the tube support plates.
This includes any detectable circumferential indications or detectable indications outside the tube support plate thickness.
.Smithern Nuclear Response The characteristics of the bobbin and RPC inspection results were typical of that found in earlier tube support plate inspections of the f arley steam generators. That is, no abnormal degradation, such as circumferential1y oriented indications, was found in the 1992 Unit 2 inspection, furtharmore, no indications at tube support plates were identified which had cracks extending outside the tube support plates by either bobb.a or RPC inspections.
2.
NRC Reouest The Staff's approval of the proposed interim repair limit is contingent on the licensee's being able to demonstrate that acceptance of all indications satisfying the 1.0 volt criterion will not create potential for leakage in excess of the 1.0 gpm licensing basis for a postulated steam itne break (SLB) occurring at E00 9.
The licensee is requested to subinit the results of the SLB leakage analysis prior to restart from the eighth refueling outage.
Southern Nuclear Response Steam generator C, with highest voltage indications left in service, is the limiting steam generator for the SLB analysis.
The projected SLB leakage is essentially zero, i.e., approxin:ately 10" gpm.
lf As previously discussed with the Staff, indications above 1.0 valt l
which were left in service (no RPC flaws) were not included in SLB leakage analysis.
l
'