ML20027A866
| ML20027A866 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Susquehanna, Limerick, 05000000 |
| Issue date: | 07/20/1982 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Palladino N NRC COMMISSION (OCM) |
| Shared Package | |
| ML20027A667 | List: |
| References | |
| TASK-AS, TASK-BN-82-70 BN--82-70, NUDOCS 8208060366 | |
| Download: ML20027A866 (4) | |
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4 July 20,1982 i
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i MDORANDUM FOR: Chairman Palladino Commissioner Gilinsky l
Consissioner Ahearne Consissioner Roberts l
Commissioner Asselstine t
FROM:
Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
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SUBJECT:
INF05.:N ITEM - SUSQUEHANNA STEAM ELECTRIC STATION.
UNITS * & 2 - DIFFERING PROFESSIONAL OPINION RELATED TO SENSITIZATION OF BWR STAINLESS STEEL WELDMEN'S (Board Notification No. 82-70 )
In accordance with present NRC procedures regarding Board Notifications, the enclosed information is being provided for your information as constituting new information relevant and material to safet;y issues.
This information is generic and has applicability to all dockets with boiling water reactors.
The staff is currently in the pmcess of trying to satisfactorily resolve a differing professional opinion (DPO) that relates to the adequacy of welding procedures used during fabrication of BWR reactor vessel interrals.
Specifically, General Electric (and/or their subcontractors) have used welding procedures that pemitted heat input leveis Pt could cause i
sensitization of heat affected zones of type 304 stainless steel. The tem " sensitization" is used here to mean that the welded joint would not pass specified ASTM tests, and therefore, would not be in conformance with specific regulatory positions of Regulatory Guide 1.44.
The intent and purpose of Regulatory Guide 1.44 is to ensure that the pmbability of deleterious intergranular stress corrosion cracking is law.
Because sensitization is one of the three factors (high stress, corrosive envimnment, and sensitization) that must all be present to cause intergranular stress corrosion cracking, it is clearly desirable to use welding procedures and other process contmls to pmvent it. Nevertheless, the staff'also believes that even with stringent process specifications, sensitization may not be precluded. Therefore, in addition to evaluating the possibility of sensitization, the staff also considers the probable level of the other Contact-Janis Kerrigan, ONRR XA Copy Has Been Sent to PDR!
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The Comedssion July 20,1982 two necessary factors for cra; king-stress level and environment corrosiveness.
Wille the aggressiveness of BWR water chemistry on sensitized austenitic stainless steel is still the subject of NRC stu@, the staff's past position has been that both of these factors are relat1<ely low at the heat affected areas of welds in BWR internals. Given the limitations of inservice inspection presently invoked for reactor internals, it is not possible to preclude the existence of crtcking; however, the staff's judgnent at this time is that the probability of cracking and reactor internals leading to a significant failum is low. The one possible exception to this is the recent cracking found in core spray spargers and related internal piping. Cracks h' ave been found in Oyster Creek, Peach Bottom 1. Brunswick 1 and possibly in Pilgrim 1.
The staff has detemined that the cracking in the affected components does not constitut:: a serious safety concern.
T It is the belief of the party offering this DP0 that a review of welding procedures currently used in SWR fabrication and inservice inspection pmcedures used at currently operating plants, would demonstrate the need for specific inservice inspection of. vessel internals. It is also the person's belief that it is not an issue involving an insnediate safety concern, but one which needs resolution to assure long-term integrity of sensitized BWR components.
Attached are internal NRC memoranda which discuss the subject DPO. We will continue to actively pursue this matter and notify you of final resolution.
ORIGINAL SIGNED BY:
Darrell G. Eisenhut. Director Division of Licensing Office of Nuclear Reactor Regulation Attachments:
NRC Memoranda regarding Differing Professional Opinions cc: ASLB DISTRIB W ON ECY OPE See Attached OGC Board Service List l
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1 CISTRIBUTION OF 3 CARD NGTIFICAT CN Susquehanna Units 1&2/COMM C:cket No. EC-357/3E8 A RS FE3ERS Leonard Bickwit, Esq.
Dr. Robert C. Axtmann Sanuel J. Chilk Mr. Myer Eendar Dr. Max W. Carbon Glirn 0. Eright, Esq.
Mr. Jesse C. Ebersole Cr. 2:hn H. Euck Mr. Marcld Etharingter.
Stephen F. Eilperin, Esq.
Dr. William Kerr Jines P. Gleason, Esq.
Cr. Harold W. Lewis Thcmas S. Moore, Esq.
Dr. J. Carson Mark Dr. Paul W. Purdom Mr. William M. !!athis
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Dr. Cade W. Poeller Mr. Ecbert W. *dler Dr. Davic Okrent Mr. Thor,as M. Garusky Dr. Milton S. Plesset Mr. Thcmas J. Halligan Mr. Jeremiah J. Ray Dr. Judith H. Ochnsrud Dr. Paul G. Shewman Ms. Colleen Marsh Dr. Chester P. Siess G. Rhodes Mr. Cavid A. Vard Jay Silberg, Esq.
Mr. DeWitt C. Scith Bryan A. Snacp, Esq.
Susquehanna Ensircnmental Advocates Atcaic Safety and Licensing Scarc Panel Atomic Safety and Licensing Appeal Panel Cocketing and Service Section Document Iianagement Branch l
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