ML20033C569
| ML20033C569 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/25/1981 |
| From: | Mears L, Poss J VAN HUFFEL TUBE CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| REF-PT21-81-531-000 PT21-81-531, PT21-81-531-000, NUDOCS 8112030440 | |
| Download: ML20033C569 (1) | |
Text
) 372-XXX
,d'L N
/
Director l p s(y f
3 Office of Inspection & Enforcement N(L q
ISOP'"%
l U. S. NUCLEAR REGULATORY COMMISSION g
0 C
Washington, D. C.
20555
- l. ~
DE09 u 83
Subject:
10CFR21 Revised Report
\\[
va %bgmo ui
Reference:
Power-Strut 10CFR21 Report Dated November 9, 1981
/
Gentlemm :
The above referenced report has been revised to include Nine MIIe Point Unit 2, as a nuclear facility potentially affected, the specific shipment and quantity of basic components (PS-9227-1/2RS) strut nute potentially affected.
On Novemba 5, 1981, Power-Strut's telephone notification under 10CFR21 to the USNRC Region 1 Duty Officer, Mr. T. Martin, included the Nine Mile Point Unit 2 facility.
The inclusion of Nine Mile Point Unit 2 was with advisement that Power-Strut records did not Indicate imposition of 10CFR21, and the referenced report would not include this facility.
Mr. Martin was further advised that Sto.a & Webster Engineering for this facility had been notified of the potential noncompliance.
A subsequent visit by L. Mears, Power-Strut Quality Manager, to the Nine Mile Point Unit 2 job site on November 11 and 12,1981, verified Stone & Webster's identification and seg.egation of the potentially nonconforming material detailed in this revised report.
During this job site visit, a review of Stone & Webster's, Nine Mile Point Unit 2, Fleid Purchasing Specification NMP2-M070A for permanent and certain nonpermanent material, verified inclusion of 10CFR21 to suppliers and subsuppliers.
Power-Strut is reviewing the requirement with agents, distributors, etc., to pass on c, stomer requi rements to the manufacturcrs.
Very truly yours, POWER-STRUT DIVISION VAN HUFFEL TUBE CORPORATION
- f M' h&
utsw
(',
James E. Poss
'awrence N. Mears /
Vice President Quality Manager JEP/LNM/sak Enclosure cc:
All w/ Enclosure A. Aga rwa l, S & W, Che r ry H i l l E. Sweeney, S & W, River Bend Job Site K. Luper, S & W, River Bend Job Site J. Carter, S & W, Boston g,
j C. Corso, S & W, Nine Mlle Point 8112030440 0
PDR ADOCK 0 ppR S
I Director Office of Inspection & Enforcement U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 l
l Subj ect 10CFR21 -- Report of Defect Related to River Bend Nuclear Power Station, St. Francisville, LA; & Nuclear Projects i
WNP #1 & 4, Hanford Works, Richland, WA l
Gentlemen:
This report describes a condition revealed as a result of Stone & Webster Engineering's initial notification of a potential noncompliance. This potential noncompliance is related to slip load values of PS-9227-1/2RS strut nuts.
A.)
PS-9227-1/2RS strut nut slip load values determined by Stone & Webster Eng;neering for the River Bend Nuclear Project could not be consistently confirmed by testing. This testing was conducted by Stone & Webster Engineering and Power-Strut Division, Van Huffel Tube Corporation.
Applicable details as required by 10CFR21, paragraph 21.21 (b) (3), are contained in the attached report.
(
l Very truly yours, PNER-STRUT DIVISION l
VAN HUFFEL TUBE CORPORATION l
Wh W
t J.es E. Poss l
Ice President aJ kW enceN.Mehrs/
quality Manager JEP/LNM/sak Attachment cc:
Regior.al Directo, USNRC, Region 1
-e-1 s
-w-wn--,,, - - - - -
,<,,-,,-w-,-,,-,,
nan,,
r--
, - - - - - - - - - - - - - - - - =
4 10CFR21 -- REPORT OF DEFECT RELATED TO RIVER BEND NUCLEAR POWER STATION, ST. FRANCISVILLE, LA; & NUCLEAR PROJECTS WNP #1 & 4, HANFORD WORKS. T.';HLAND, WA November 9, 1981 Revised November 24, 1981 NAME AND ADDRESS OF THE INDIVIDUAL OR INDIVIDUALS INFORMING THE COMMISSION:
J. E. Poss, Vice President, Power-Strut Division L. N. Mears, Quality Manager, Power-Strut Division Van Huffel Tube Corporation Dietz Road /P. O. Box 1540 Warren, Ohio 44482 IDENTIFICATION OF THE FACILITY, THE ACTIVITY, OR THE BASIC COMPONENT SUPPLIED FOR SUCH FACILITY OR SUCH ACTIVITY WITHIN THE UNITED STATES WHICH FAILS TO COMPLY OR CONTAIN A DEFECT.
1.)
Basic Component Supplied:
Power-Strut Strut Nut, Part Number PS-9227-1/2RS 2.)
r.uclear Facilities Potentially Affected:
(A)
River Bend Nuclear Station St. Francisville, LA 70775 (B)
Nuclear Projects WNP #1 6 #4 Hanford Works Richland, WA 99352 Rev.
,(C)
Nine Mlle Point Unit 2 Scriba, New York 13093 3.) Activity:
Support System Component Material IDENTIFICATION OF THE FIRM CONSTRUCTING THE FACILITY OR SUPPLYING THE BASIC COMPONENT WHICH FAILS TO COMPLY OR CONTAIN A DEFECT.
1.) Manufacturer of Basic Component:
Power-Strut Division Van Huffel Tube Corporation Dietz Road Warren, Ohio 44482
O NATURE OF THE DEFECT OR FAILURE TO COMPLY AND THE SAFETY HAZARD WHICH IS CREATED OR COULD BE CREATED BY SUCH DEFECT OR FAILURE TO COMPLY.
1.)
Nature of Defect:
Shallow depth of strut nut serrations, part number PS-9227-1/2RS 2.)
Safety Hazard:
Potential reduced load carrying capacity for slip values in shear loading (slip along axis of channel) Ref. Attachment 1-A.
Note: This noncompilance is not applicable to strut nut pullout tension values (perpendicular to axis of channel) Ref. Attachment 1-B.
THE DATE ON WHICH THE INFORMATION OF SUCH DEFECT OR FAILURE TO COMPLY WAS OBTAINED.
November 5,1981 IN THE CASE OF A BASIC COMPONENT WHICH CONTAIN5 A DEFECT OR FA!LS TO COMPLY, THE NUMBER AND LOCATION OF ALL COMPONENTS IN USE AT, SUPPLIED FOR, OR BEING SUPPLIED FOR ONE OR MORE FACILITIES OR ACTIVITIES SUBJECT TO THE REGULATIONS IN THIS PART.
CUSTOMER POWER-STRUT LOCATION PART NO.
ORDER NO.
INVOICE NO.
QUANTITY DATE SHIPPED River Bend PS-9227-1/2RS 12210-07378 8001 10,000 Ea.
11-17-80 River Bend PS-9227-1/2RS 12210-09231 0917 1,500 Ea.
12-5-80 River Bend PS-9227-1/2RS 12210-09231 1191 1,900 Ea.
4-16-81 WNP 1/4 Hanford PS-9227-1/2RS CA0650 0326 4,225 Ea.
11-12-80 Reve,Nine Mile Point 2 PS-9227-1/2RS FP012113 2122 2,000 Ea.
4-21-81 THE CORRECTIVE ACTION WHICH HAS BEEN, IS BEING, OR WILL BE TAKEN: THE NAME OF THE INDIVlCUALS OR ORGANIZATIONS RESPONSIBLE FOR THE ACTION: AND THE LENGTH OF TIME THAT HAS BEEN OR WILL BE TAKEN TO COMPLETE THE ACTION.
1.)
Corrective Action:
(A)
Identify and place on hold PS-9227-l/2RS strut nuts (B)
Responsible design organizations to review and determine the effect of noncompilance based on their appilcation of this product.
1 (C) Power-Strut Division has developed and implemented an acceptance criteria for previously produced lots and all future production.
b -
s a4.
2.)' Name of Organization Responsible for' Corrective Action:
Power-Strut Division -- ltems 1.A & l.C Responsible Design / Construction -- ltems 1.A & l.B ANY ADVICE RELATED TO THE DEFECT OR FAILURE TO COMPLY ABOUT THE FACILITY, ACTIVITY, OR BASIC COMPONENT THAT HAS BEEN, IS BEING, OR WILL BE GIVEN TO THE PURCHASERS OR LICENSEES.
Power-Strut Division, Van Huffel Tube Corporation, has conducted an in-depth review of all previously produced production lots and shipments of PS-9227's.
As a result of this review, the following has been determined:
(A) The condition of shallou serrations in PS-9227 strat nuts is isolated to a specific production lot and specific shipments.
(Ref. Locations and quantities supplied subject to regulations.)
(B) The strut nut serrations for this specilie. production lot was manufactured on a press with insufficient tonnage to produce acceptable parts on a consistent basis. All other production lots were manufactured on a press with more than sufficient tonnage to consistently produce ac.ceptable material.
i i
1 1.
l l
8 s
l f
3 L
10CFR21 -- REPORT OF DEFECT RELATED TO RIVER BEND NUCLEAR P9WER STATION, ST. FRANCISVILLE, LA; D NUCLEAR PROJECTS WNP #1 & 4, HANFORD W0hKS, RICHLAND, WA ATTACHMENT 1-A & ATTACHMENT l-B
,Novemaer 9, 1981 ST R\\ fT blLTT LohD r~
n A
L -
- fj T_
t t
E Ok6 _ k%\\ S DF (MAS \\QCL (c 7_x \\ O MD q
_r x
_ 1 _.. _ ___
q' l,'
=-
g g
I 1
LOAD l
[7_Xtx\\O M- ^'
.s ww w & _\\ h --
I s