ML19199A513
| ML19199A513 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/14/1978 |
| From: | Stello V Office of Nuclear Reactor Regulation |
| To: | Eisenhut D, Grimes B, Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19199A512 | List: |
| References | |
| NUDOCS 7905030115 | |
| Download: ML19199A513 (5) | |
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UNITEo STATES
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WASHINGTON. D. C. 20555
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AUG 141973 MEMORANCUM FOR: Brian K. Grimes, Assistant Director for Engineering &
projects, 00R Darrell G. Eisenhut, Assistant Director for Systems &
Projects, 00R Domenic 3. Vassallo, Assistant Director for Light Water Reactors, OpM FRCM:
Victor Stello, Jr., Director, Division of Operating Reactors, NRR
SUBJECT:
B&W REACTOR VESSEL WELO MATERIAL DEVIATING FRCM SPECIFICATIONS We were informed on August 4,1973, that a chemical analysis of a specimen of reactor vessel weld material fabricated by B&W indicated that the silicon and nickel content differed from that specified.
It is possible that some of this weld material may have been used in 12 vessels. The NRC and B&W are investigating this potential problem expeditiously and hope to be able to resolve it.
Seven vessels are in B&W NSSS plants, three in W plants and two in GE plants. The enclosed letter should be sent to the 3&W, W and GE NSSS licensees or applicant as soon as possible:
- Three Mile Island 1/2 Oconee 3 Crystal River 3 Rancho Seco 1 Arkansas 1 Midland 1 Browns Ferry 1 Turkey point Quad Cities 2 Zion 1/2 The purpose of these letters is to ensure the timely use of conservative interim heatup and cooidow. curves until the licensees or applicant can perform a more detailed analysis of the effects of the use or potential use of the improper weld material in the subject vessels.
The lead technical reviewer is Warren Hazelton, Engineering Branch, COR (x2SC60); Mort Fairtile, Operating Reactors Branch #4, COR (x27435) is the lead project manage.
- 00R will transmit a letter addressed to Met Ed for both units.
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AUG *1 c?g The potential reactor vessel material specification deviation is
" relevant and material new information" in regard to the requirements for infoming Licensing and Appeal Boards per NRR Office Letter No.19 of July 5,1978. We understand that Midland I and TMI-2, both in LWRi4, OPf1, have a need for Board notification. The recaining licensees, all assigned to 00R, do not have any sitting Boards.at this time. The letter to the Midland I licensee may be altered to suit specific needs, s
0$iginal sig:ied ty[
Victor Stello, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation
Enclosure:
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t0c SEE PREVIOUS YEELLOW FOR ADDITIONAL CChCURRENCES AQpP:CCR 0:COR}
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u 2-AUG ' 4 97a The Icau technical reviewer is Warren Hazelton, Engineering 8rancn, 00R (x280W); Hort Fairtile, Operating Reactors Branch 6, 000 lx27436 ) is the lean project rnanager anc he will coordinate any needed coef. acts wi n the nuclear steam systec. suppliers.
The reactor vessel nieterial specification ceviatiori is " relevant anc
- Daterial nEw inforiation in regard to the requirtTeats for infoming Licensing and Ac;:eol doarcs per NRR Of fice Letter No.19 of July t.,
1978.
We unoerstand tna:.4idlanc 1 and THI-2, botn in LWR 4, CPM, h e a neen for Boar ' noti fic.ition.
The re'1aining licensees, all assigned to 00",
do not nave any si tting Boards at this time, higi:ral312:80DTI Victor Stello, Jr., Director Division of Operatino Reactors Of fice of Nuclear Reactor Reg:.:lation
Enclosures:
A.
Sample Ltr. for E6.:
NSSS Licensees or Applicant B.
Sample Ltr. for W or CC Licensees cc w/ enclosures: See next page
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AUG 141978 cc: Central File NRR Reading ORB Reading E3 Reading OI&E (3)
V. Noonan R. Reid M. Fairtile W. Hazelton R. Klecker s
J. P. Knight
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WASHINGTON, D. C. 20555
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UIS ADDRESSEES
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Gentlemen:
RE: REACTOR VESSEL ATYPICAL WELD MATERIAL This letter confirms our telephone conversatica with your staff cf August 14, 1978.
The NRC was advised by Sabcock & Wilcox (3&W) on August 4,1978, that a chemical analyris of an archive weldment performed as part of the program for evaluation of reactor vessel material properties indicated that the nickel and silicon content of the weld material were outside the specified range.
It has been determined that the weld filler wire used for that particular weld was atypical.
As of this date, it is not known whether or not this atypical weld wire was used in the manufacture of your reactor vessel.
Therefore, we request that you provide the following information to us by Friday, August 18, 1978 (a telecopy of your response is adequate):
1.
What interim measures, such as revised pressure /teucerature limits, you are taking to ensure reactor vessel integrity in the event that the atypical weld wire was used, 2.
Ycur assessment as to the continued safe operation of your facility baseo on these interim measures, and 3.
Your commitment that these measures will continue in fc. ce pending the resolution of this issue.
Your submittal should be three signed originals plus 37 additional copies.
Sincerely, Branch Chief e
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