ML19225D037
| ML19225D037 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/13/1979 |
| From: | Taylor J BABCOCK & WILCOX CO. |
| To: | Reinmuth W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19225D031 | List: |
| References | |
| NUDOCS 7908030619 | |
| Download: ML19225D037 (2) | |
Text
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Babcock &Wilcox go.e, c..... s,m At tach:::ent A P.O. Scir 12C, Lyn: Pet.rg. Va. 24 505 Docket No. 50-346 Teleonone: (s00 384 5 n t License No. 57F-3 Serial No. 1-74 May 31, 1979 March 13, 1979 Mr. Wayne G. Reinmuth Office of Inspection and Enforce =ent U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Response to IE Sulletin Nos. 78-12 and 73-12A i
Dear Mr. Reinmuth:
Enclosed for your information are three (3) copies of our report entitled, " Records Investigation Report Related to Off-Chen_stry Welds in Material Surveillance Specimens and Responses to Bulletin 78-12 and 78-12A Supplement", which we have prepared for our customers in order to facilitate their responses to the bulletins.
The report is basically divided into three (3) parts: (1) an introduction and su==ary of the weld wire issue; (2) general information to support the con-clusions we have reached; and (3) specific responses to the information. requested by the bulletins.
Appendices containing copies of 35h chemical analysis requirements and weld filler wire qualification tests are included as supporting information.
The information in the appendices has been selected based on your request at a January 16, 1979 meeting in Mt. Vernon, Indiana.
This report describes the investigations that were made as a result of discovering an off-chemistry condition in a reactor vessel surveillance specimen for the Crystal River 3 (CR-3)
Project.
The purpose of the records investigation was to determine the cause and extent of the mixed weld wire prcblem.
The investigation also included a review of test results from actual reactor vessel production weld seams to the extent these welds could be investigated, and from ceactor vessel surveillance
=aterial tests.
The investigation covered the period from 1966 through November 1978.
In accordance with IE Bulletin.78-12A, cur respense is given on a generic basis and no attempt was =ade to cortclato specific weldments with heats at filler wire.
q 9 08 0 3 0 6CS
~
440 106 The Rsreck & Wilecz Comcany / Estathned 1867
Babcock &VMcox 2-Mr. Wayne G. Reinmuth March 13, 1979 The records investigation provides considerable support for the hypothesis ti.at the presence of atypical chemistry conditien in the Crystal River 3 surveillance block is an isolated event involving a small annunt of material in one heat of wire.
The general conclusion reached as a result of the investi-gation of the atypical weld wire discove-is that it is very unlikely that other similar conditions c)
- in any reactor pressure vessel welds.
Furthermore, the tp practices which have evolved over the years and which are currently in effect virtually eliminate the possibility that a vessel fabricated today might contain off-chemistry weld materials.
If you have any questions concerning the enclosed material, please contact me (Ext. 2817) or William R. Speight (Bxt. 2902) of my staff.
Very truly yours James H. Taylor Manager, Licensing JHT/fw cc:
R. B. Borsum - B5W Rep. Bethesda Offica
Enclosures:
As stated e
W 440 107
Babcock & Wilcox
%,,c -...
cm :
P.o. Box 1260. Lyncheurg. Va. 245c5 kt No 0-346 Tefe nm (ex 3sesm License No. NPF-3 Serial
'o. 1-74 May 31, 19 79 May 24,1979 D8-79-45 Mr. C. R. Domeck Nuclear Project Engineer Toledo Edison Coreany 300 Madison Avenue Toledo, OH 43652
Subject:
Davis-Besse Nuclear Generating Station - Unit I Response to NRC - IE Bulletin 78-1?S Re ference: Larry Haigh/TECo telecopy to R. C. Luken/B&W - dated 5-18-79.
Dea r Mr. Domeck:
To assist Mr. Haish in respondir g to the NRC-IE Bulletin 78-123 mgarding the mcords investigation mlated to the "off-chemistry" welds in material surveillance specimens B&W pmvides the folicwing:
A.
Record of Filler Wim Qualification Test WF 182-1, copy enclosed.
This mcord is applicable to the Linde it-Mo-Ni wim (heat nr. 821T44) and Linde 80 Flux (lot no. 8754) contination for the follow 1ng ferritic welds in the Davis-Besse 1 reactor vessel w closum head:
1.
W R-1 Mk 170 interrudi ate sheil to Mk 171 lower shell.
2.
WR-35 Mk 181 lower head dutchman to Mk 6 lower head.
3.
WH-7 Mk 22 closure head f1ange to Mk 24 closure head center di s c.
B.
Record of Filler Wire Qualification Test - WF 232, copy enclosed.
This record is applicable to the RACO Mn-Mo-Ni wire (heat no. 8T3914) and Linde 80 flux (lot no. 8790) combination for the following ferritic welds in the Davis-Besse 1 reactor vessel:
AA0 108 The Babcock & wdcos company / EstachsMd 1867
Babcock &Wilcox LUKEN TO DOMECX MAY 24, 1979
- 1. W R-2
& 169 no: Eke belt to & 170 intermediate shell.
2.
W R-34 Mk 171 lower shell to Mk 181 lower head dutchman.
3.
W R-12 Mk182-1 inlet no::le between "X-Y axis" to & 169 no::le belt.
& 182-2 inlet no::le between "W-Z axis" to Mk 169 no::le belt.
W 182-3 inlet no::le beheen "W-X axis" to Mk 169 no::le belt.
Mk 182-4 inlet no::le between "Y.Z axis" to Mk 169 no::le, bel t.
C.
The folicwing welds are non-ferrous (Inconel) deposits to ferritic base metal or non-ferrous (Inconel) welds between Inconel and stainless teel pa rts. As such, they am not within the scope of reporting required by NRC Bulletin 78-123.
1.
WR-53 Mk 89-1 no::le safe end to Mk 176-1 core flood no::le "Y-axi s" This weld is en Inconel weld of the stainless steel safe end to the Inconel buttemd end of the core flood no::le.)
2.
WR-52 Inconel buttering to the terminal end face of the Mk 176-1 -2 com flood no: les for attachment of safe ends
- as noted in Item 1 above.
3.
WR-46 14k 92 thru 118 Instrument no::les (Inconel) to MK 6 lower head.
(The weld is an Inconel alloy deposi t).
4.
WK-25 Mk 43 th ru 53 control rod housing bodies to Mk 24 closum head center disc.
(This is a Incenei alloy weld between the Inconel control red housing bodies to the ferritic closure head,
- 5. VH-9 Mk67 centrol rod housing adaptor flange (stainless steel) to Mk 43 thru 55 centrol red housing bodies (Inconel).
(This weld is mde using Inconel filler wim).
Test reports for the heats of wim for the above welds are not attached to this letter. However, the test reports are,on file in the Quality Assurance Departmnt of our Mt. Vernon, Indiana r.anufacturing plant, as required by ASME Sec. III code.
440 109
Babcock &Wilcox LUKi1 TO DCMECX MAY 24, 1979 If you requint further clarification of the above infonnation, please advise.
Very truly yours.
geu' ~
R. C. Luken Service Manager RCL:vi t cc:
D. J. CELACROIX D. A. LEE T. D. MURRAY L HIAGi f
e 9
e e
e 440
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