ML20126L712
| ML20126L712 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/26/1981 |
| From: | Martin T Public Service Enterprise Group |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8106080207 | |
| Download: ML20126L712 (2) | |
Text
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64 JUN 0 51981 >
l Mr. Boyce R. Grier, Director U. S. Nuclear Regulatory CommissiGn
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y,g a g Office of Inspection and Enforcement I
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Region 1 y@
s' 631 Park Avenue
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l King of Prussia, Pennsylvania 19406 N cnl
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Dear Mr. Grier:
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POTENTIAL SIGNIFICANT CONSTRUCTION DEFICIENCY I
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i NO. 1 AND 2 UNITS l
f ROPE CREEK GENERATING STATION l'
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On April 22, 1931, a verbal report was made to Region 1, f
Office of Inspection and Enforcement representative, Mr.
E.
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Groenman, advisinq of a potential significant construction i
deficiency.
The following information is submitted as re-quired by 10CFR50.55(e):
1.
Description of the Deficiency:
l During on-site modification of embeds' purchased from i
Acme Steel Engineering Company of Baltimore, our Archi-g tect/ Engineer, Bechtel Power Corporation, discovered weld deficiencies contrary to the purchase specification requirements.
Subsequent inspection of 270 similar em-beds from the sane supplier found 127 that did not meet visual acceptance criteria.
This inspection revealed instances of excessive porosity, excessive undercut,and undersize fillet welds.
Sample testing of similar em-beds for sub-surface porosity by RT and destruction li (air-are gouge) tests found fillet welds with unaccept-i j
able sub-surface porosity.
Similar embeds from Acme h
Steel have already been installed and are no longer ac-li cessible for visual inspection.
2.
Analysis of Safety Implications:
J The required analysis will be cerformed and the results
!j reported to you following completion of the investiga-ll tion and test program outlined below.
,i l
3.
Demedial Actions:
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- a. All ACME, except those installed, embeds havinq shear bars, anchor lugs, anchor plates and combinations,
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thereof, shall be visuall" and T'
examined.
Melds not gf g THIS DOCUMENT CONTAHiS
$'06Ogogg7 POOR QUAUTY PAGES
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To Mr.
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!!. Crier 5/26/31 meeting visual and 9T examination acceptance cri-teria shall be reoaired.
Alternatively, embeds may.
be replaced with new conforning embeds.
A con f o rm-inq cmbed is defined as a non-ACMS embeds that has passed visual exanination.
b.
All non-ACMC enbeds having shear bars, anchor lugs, anchor plates and combinations, thereof, shall be visually inspected on a sample basis such that each affected release fro = each supolier is properly ren-resented.
If a nufficient cample of any release is not available, all accessible embeds from that re-lease will be inspected.
Adequate aanple sizes will be defined by Gochtel's Project Eng inee r.
c.
Samples of embeds which contain' excessive porosity will be tested.
The samples will include embeds which are both visually acceptable and vinually un-acceptable.
the areas of embeds showing excessive porosity shall be tehted for ultimate pull-out and shear capacity.
Shear bars.will be tested for shear, whereas anchor lugs will be tested for null-out.
d.
No additional embeds will be purchased f rom Acme Steel Engineering Company.
4.
Proiectei completion dates:
The dentructive testing crogram la scheduled for conole-tion by June 26, 1941.
The flata from the test orogran vill then be used to evaluate the acceptability of siai-
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lar embeds previously installed and to analyze the nafety implications of the problem.
Upon com.oletion of engineering analysin, a final report will be submitted to your of fice.
very truly yours, r..
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I T. J.
Martin Vice President -
Engineering and Conatruction ML:mir CC:
Office of Inspection and Cnforcement v' nivision of Reactor Construction Insnection hashington, D.C.
4 NlC 9esident Innocctor toos Creek 91t0 l
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