ML19281A142

From kanterella
Jump to navigation Jump to search
Responds to IE Bulletin 78-12, Atypical Weld Matl in Reactor Pressure Vessel Welds. C-E Has Not Used Suspect Weld Wire Heat.Proposes Revision of Bulletin
ML19281A142
Person / Time
Site: Waterford Entergy icon.png
Issue date: 11/30/1978
From: Aswell D
LOUISIANA POWER & LIGHT CO.
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
LPL-10199, NUDOCS 7903060602
Download: ML19281A142 (2)


Text

.

..q]Q

-(

l_0UISIANA 242 ouAnONoe smeer POWER & L1GHT P O BOK 6008

  • NEW ORLEANS LOU!SIANA 70174 (504) 366-2345

'f N N dvs $

November 30, 1978 t

o L ASWELL Vee Pres'fet-Power Productm LPL 10199 3-A1.01.04 Q-3-A20.03.12 Mr. Karl V. Seyfrit, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement, Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382 IE Bulletin 78-12 dated September 26, 1978

REFERENCE:

Combustion Engineering letter LD-78-079 dated November 3, 1978.

Dear Mr. Seyfrit:

In order to respond to the requirements of the subject bulletin, C-E was requested to provide the pertinent information.

C-E advised that based on the best information available at this time, C-E's Chattanooga shops have not used any of the suspect weld wire heat in the fabrication of any reactor vessels, but to comply with the bulletin as written, C-E will require an additional 10 to 12 months.

In the reference letter, C-E suggested the subject bulletin be revised to require-1)

Confirmation that the particular heat / lot of weld wire identified in Bulletin 78-12 has not been used in the manufacture of R. V. Pressure vessels provided by Combustion Engineering.

2)

Provide the NRC with a description of C-E's quality control procedures regarding the procurenent, testing, and use of weld wire and flux.

3) As part of regularly scheduled andits at C-E's Chattanooga manufacturing facility, under the Large Component Vendor Inspection Program, the NRC can obtain further assurance that quality control procedures are indeed effective and that tests are fully documented.

790aw o6o2

...,N.

Mr. Karl V. Seyfrit,

  • November 30, 1978 Page 2 We believe that this approach will fully respond to the concerns of the subject bulletin.

LP&L's fuel loading date is bby, 1981, therefore, we request a timely response to C-E's proposal, for if C-E's approach is not adequate. LP&L may require 3 to 4 months (beyond C-E's 10 to 12 months) for review and processing of the large amount of documentation associated with our reactor vessel.

Yours very truly, D.

L. Aswell DLA:RSS smd cc:

Mr. E. Blake Mr. W. M. Stevenson

_