ML20062H690
| ML20062H690 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/25/1980 |
| From: | Halapatz J Office of Nuclear Reactor Regulation |
| To: | Gamble R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20062H675 | List: |
| References | |
| NUDOCS 8008210255 | |
| Download: ML20062H690 (6) | |
Text
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UNITED STATES 1
y, NUCLEAR REGULATORY COMMISSION c,
,/
I wasamotos o. c. oses g,, [
JUN 2 51950 ME.v0RANDUM FOR:
R. M. Gamele, Sec:1cn Leacer, Component Integrity Section, Materials Engineering Branch OE FROM:
J. Halacat:, Materials Engineer, Materials Engineering 3 ranch, DE
SUBJECT:
EXPRESSION OF DIFFERING PROFESSIONAL OP!NION IN THE MATTER OF TiiE ADEOUACY OF SEQUOYAH UNIT ONE WELD ORAWBEAD REPAIR OF PRESSURIZER RELIEF PIPE Attention is called to an inaccuracy in the memorandum, Gamble to Halacat:, dated June 23, 1980, sucject " Expression of Differing Professional Opinion in tne Matter of :ne Adecuacy of Secuoyah Unit One Weld Drawcead Recair of Pressuri:er Relief Pipe." The inac:uracy exists in the sentence, "Further, in February, Mr. Denton famed a management review group to discuss your views with you; nowever, you pre-ferred not to discuss inis matter witn :nem a: that time."
The rnatter of i teres:, in fact, was discussed with Jim Knign:, wne icentified him-self as re:: resenting :ne management review grcue (Schroeder and Ross). In addition.
ne ma :er was discussed in a subsequent meeting of Knight, Pawlicki, Gamole, and Hala::at:, wni n lec t: the attacned draft memorandum wnien was distributec to attencees of an internal NRC meeting wnien precedec the meeting with TVA nele on Maren 13, 1980.
The comercmise reacnec in :ne meeting with TVA, vi:.. that in situ metallography of
- ne pr0cuction repair would be perfcmec and :nat the repair would be re-raciographed, simply acxnowlecged reservations about what had been done up to that point to cualify ne reoair.
I reiterate the safety implication involved in :nis matter, vi:.,
na: failure of tne repaired picing canno :e isolated, wnicn as a :Onsecuence, coulc leac to an uncentrollec blowoown of the reactor c0clant systern. The environment wnicn will te experienced by the repair will be a calculated 0.2::om max. oxygen bearing steam ra:Mer : nan.005::cm oxygen reactor c:olant water. SWR pipe crack experience and
- ne lacx of corrosion cata in.2pom oxygen cearing steam suggest caution in ac:ect-ance Of :ne recair. I finc :ne results of the in situ metallograpny perfomed and
- ne re-raciograony inc:nclusive in su::corting ne repair.
While I recogni:e One unoccularity of my ex:ression of a minority oeinion in this matter, I acci: to an incredible dislike Of T'11-2 type scenarios. I am aware :na:
management must make jucgment in this tatter. Given the ::nsecuences of failure, newever, I sugges simply inat we take ano:ner closer look :: provice that acced assurance.
00munication :nrougn memoranda, as in :nis case, often excludes nuances wnien con-tribute to ne statement of a position. I will censicer myself privilegec : discuss.
6008210255
o R. M. Gam:le
- 3, ;...~ 0 in a meeting of those 1:enti#iec in :ne distribution, the matter of the Sequoyan
'Jni: One nel: erawbeac repair of tne pressurizer relief pipe.
-12 N~
f Joseph Halapat:
Materials Engin
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Ofvision of Engineering l
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