ML19338D989: Difference between revisions

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422 Sourn Cnuncu Sruzz .gnuntoriz N. C.2e24a
422 Sourn Cnuncu Sruzz .gnuntoriz N. C.2e24a g\ ~11 July 15, 1989 WI W AM O. PAR M ER, J R.
                                              -
g\ ~11 July
* 15, 1989 WI W AM O. PAR M ER, J R.
Vice Patsiotwv                                                    TettPMNE; knE4 704 Straa. Paoovetion                                                            373-4083 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II                                            -
Vice Patsiotwv                                                    TettPMNE; knE4 704 Straa. Paoovetion                                                            373-4083 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II                                            -
101 Marietta Street, suite 3100-i
101 Marietta Street, suite 3100-i
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Re: RII:WPK.
Re: RII:WPK.
50-413/80-10 50-414/80-10 l
50-413/80-10 50-414/80-10 l
                                                                                                                  !


==Dear Mr. O'Reilly:==
==Dear Mr. O'Reilly:==
I l
I l
Please find attached a response to Infraction No. 413/80-10-01 which was identified in the above referenced Inspection Report. Duke Power Company does not consider any information contained in this inspection report to be proprietary.
Please find attached a response to Infraction No. 413/80-10-01 which was identified in the above referenced Inspection Report. Duke Power Company does not consider any information contained in this inspection report to be proprietary.
V ry truly yours
V ry truly yours uw            /$. aA-William O. Parker, Jr.
                  -
                                ,
uw            /$. aA-William O. Parker, Jr.
RWO:ses                                                                                          !
RWO:ses                                                                                          !
I cc:      G. F.      Maxwell NRC - Catawba Nuclear Station                                                            l l
I cc:      G. F.      Maxwell NRC - Catawba Nuclear Station                                                            l l
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DUKE POWER COMPANY                                                              t
DUKE POWER COMPANY                                                              t
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CATAWBA NUCLEAR STATION                                                                  ,
CATAWBA NUCLEAR STATION                                                                  ,
Response to Infraction No. 413/80-10-01 Infraction:
Response to Infraction No. 413/80-10-01 Infraction:
As required by 10CFR 50, Appendix B Criterion V and as implemented by Duke Power Company (DPC) Topical Report " Duke 1-A" Section 17, paragraph 17.1.5, " Activities
As required by 10CFR 50, Appendix B Criterion V and as implemented by Duke Power Company (DPC) Topical Report " Duke 1-A" Section 17, paragraph 17.1.5, " Activities affecting quality shall be prescribed by . . . drawings . . . and shall be accom-plished in accordance with those .        .    . drawings." Duke ~ pipe support drawing CN-AA-131, Revision 6 requires a S/16" fabrication fillet weld size.
                                    .
affecting quality shall be prescribed by . . . drawings . . . and shall be accom-plished in accordance with those .        .    . drawings." Duke ~ pipe support drawing CN-AA-131, Revision 6 requires a S/16" fabrication fillet weld size.
Contrary to the above, on May 29, 1980, the fabrication fillet weld size for safety-related pipe support No. 1-ARN-3839, fabricated in accordance with CN-AA-131, was noted to be less than 1/4" in one area.
Contrary to the above, on May 29, 1980, the fabrication fillet weld size for safety-related pipe support No. 1-ARN-3839, fabricated in accordance with CN-AA-131, was noted to be less than 1/4" in one area.


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As a result of this infraction, a reinspection program was conducted to deter-mine whether or not a significant problem exists in the area of component support weld. size. During this reinspection effort, 300 component support welds were reinspected by experienced, senior welding inspectors. Results of the reinspection were evaluated by Quality Assurance; the evaluation included a second reinspection by Quality Assurance of selected welds.                                It was concluded r
As a result of this infraction, a reinspection program was conducted to deter-mine whether or not a significant problem exists in the area of component support weld. size. During this reinspection effort, 300 component support welds were reinspected by experienced, senior welding inspectors. Results of the reinspection were evaluated by Quality Assurance; the evaluation included a second reinspection by Quality Assurance of selected welds.                                It was concluded r
that no significant fillet veld size problem exists in the fabrication or inspection of component support welds. This action was completed July 2,'1980.
that no significant fillet veld size problem exists in the fabrication or inspection of component support welds. This action was completed July 2,'1980.
,
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Latest revision as of 12:35, 31 January 2020

Responds to NRC 800623 Ltr Re Violations Noted in IE Insp Repts 50-413/80-10 & 50-414/80-10.Corrective Actions:Insp of Component Support Welds Initiated
ML19338D989
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 07/15/1980
From: Parker W
DUKE POWER CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19338D977 List:
References
NUDOCS 8009240298
Download: ML19338D989 (2)


Text

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422 Sourn Cnuncu Sruzz .gnuntoriz N. C.2e24a g\ ~11 July 15, 1989 WI W AM O. PAR M ER, J R.

Vice Patsiotwv TettPMNE; knE4 704 Straa. Paoovetion 373-4083 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II -

101 Marietta Street, suite 3100-i

-Atlanta, Georgia 30303 l

Re: RII:WPK.

50-413/80-10 50-414/80-10 l

Dear Mr. O'Reilly:

I l

Please find attached a response to Infraction No. 413/80-10-01 which was identified in the above referenced Inspection Report. Duke Power Company does not consider any information contained in this inspection report to be proprietary.

V ry truly yours uw /$. aA-William O. Parker, Jr.

RWO:ses  !

I cc: G. F. Maxwell NRC - Catawba Nuclear Station l l

l 1

i see9 w t2 ?f

g J

\

DUKE POWER COMPANY t

+

CATAWBA NUCLEAR STATION ,

Response to Infraction No. 413/80-10-01 Infraction:

As required by 10CFR 50, Appendix B Criterion V and as implemented by Duke Power Company (DPC) Topical Report " Duke 1-A" Section 17, paragraph 17.1.5, " Activities affecting quality shall be prescribed by . . . drawings . . . and shall be accom-plished in accordance with those . . . drawings." Duke ~ pipe support drawing CN-AA-131, Revision 6 requires a S/16" fabrication fillet weld size.

Contrary to the above, on May 29, 1980, the fabrication fillet weld size for safety-related pipe support No. 1-ARN-3839, fabricated in accordance with CN-AA-131, was noted to be less than 1/4" in one area.

Response

9 Pipe support No. 1-ARN-3839 was nonconformed in accordance with DPC Quality Assurance Procedure Q-1 (NCI 8629). The weld in question was evaluated by Design Engineering and found to be acceptable. This action was completed on July 15, 1980.

As a result of this infraction, a reinspection program was conducted to deter-mine whether or not a significant problem exists in the area of component support weld. size. During this reinspection effort, 300 component support welds were reinspected by experienced, senior welding inspectors. Results of the reinspection were evaluated by Quality Assurance; the evaluation included a second reinspection by Quality Assurance of selected welds. It was concluded r

that no significant fillet veld size problem exists in the fabrication or inspection of component support welds. This action was completed July 2,'1980.

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