ML19338C185
| ML19338C185 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Oconee, Arkansas Nuclear, Turkey Point, Crystal River, Quad Cities, Rancho Seco, Zion, Midland, 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 | |
| ML19338C176 | List: |
| References | |
| NUDOCS 8008050635 | |
| Download: ML19338C185 (5) | |
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UNITED STATES
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AUG 141978 MEMORANDUM FOR: Brian K. Grimas, Assistant Director for Engineering &
Projects, DOR Darrell G. Eisenhut, Assistant Director for Systems &
Projects, 00R Domenic B. Vassallo, Assistant Director for Light Water Reactors, DPM
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FROM:
Victor Stello, Jr., Director, Division of Operating
. Reactors, NRR l
SUBJECT:
B&W REACTOR VESSEL WELD MATERIAL DEVIATING FROM SPECIFICATIONS We were informed on August 4,1978, that a chemical analysis of a 4
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 S&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 B&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 cooldown 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 (x27435) is Branch, D0R (x28060); Mort Fairtile, Operating Reactors Branch #4, DCR the lead project manager.
- DOR will transmit a letter addressed to Met Ed for both units.
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AUG ? 41978 The leao technical reviewer is Warren Hazelton, Engineering Branch, DOP.
(x280LO); Hort Fairtile, Operating Reactors Branch v4, DDR (x27435) is the leaci proiect manager ano he will coordinate any needed coMacts with the nuclear steam systeu suppliers.
The reactor vessel inaterial specification deviation is " relevant anc material new infornation" in regaro to the requirements for intominq
. Licensing and Appeal Boards per NRR Office Letter No.19 of July t, 1978.
We understand tnat Hidland I and TI11-2, botn in LWR 74, DPit, hve a neen for Boarn notific.1 tion. The.rer1aining licensees, all assigned to 00?,
do not nave any sitting Boards at this time.
6figinal sianed by!
Victor Stello, Jr., Director Division of Operatino Reactors Of fice of Nuclear Reactor Regulation
Enclosures:
A.
Sample Ltr. for EF.!
-NSSS Licensees or Applicant.
-B.
Sanple Ltr. for }; or CE Licensees 4
cc w/ enclosures: See next page 1
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Docket No.:
-AUG I4 573 ADDRESSEES 1
s Gentlemen:
RE: REACTOR VESSEL ATYPICAL WELD MATERIAL This letter confirms our telephone conversation with your staff of August 14, 1978.
. The NRC was advised by Babcock & Wilcox (B&W) on August 4,1978, that a chemical analysis 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 4.
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 / temperature limits, you are taking to ensure reactor vessel integrity in the event that the atypical weld wire was used, t
2.
Your: assessment as to the continued safe operation of your facility 4
' based on these interim measures, and
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Your commitment that these measures will continue in force pending the resolution of this issue.
4 Your submittal should be three signed originals plus 37 additional copies.
. Sincerely, Branch Chief 1
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4 The potential reactor vessel material specification deviation is
" relevant and material new information" in regard to the requiesments for infoming Licensf rig and Appeal Boards per NRR Office Letter No.19 of July 6.1978.- We understand that Midland 1 and THI-2, both in LWRf4. opt 4. have a need for Board notification. The remaining licensees, all assigned to DOR, do not have any sitting Boards at this time. The letter to the Midland 1 Itcensee may be altered to suit specific needs, f
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t Originci signed by1, Victor Stallo, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation j
Enclosure:
- As stated 4
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SEE PREVIOUS YEELLOW FOR ADDITIONAL CONCURRENCES M:J4P:00R D:yR 054 Mt VStMll BA.W A
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