ML19259C760

From kanterella
Jump to navigation Jump to search
Responds to IE Bulletins 78-12,12A & 12B.C-E Generic Rept Re Atypical Weld Matl in Reactor Pressure Vessel Welds Is Satisfactory Response
ML19259C760
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 06/27/1979
From: Gary R
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
TXX-3005, NUDOCS 7908150134
Download: ML19259C760 (1)


Text

.  %/

'l.

TENAS UTILITIES GENERATING CO.TIPANY 2001 BR Y AN TO W ER D ALLAS. TE LAS 75 201 June 27, 1979 TXX-3005 R J CARY

  • ?Zl'J."  :".1,'."

Mr. Karl V. Seyfrit, Director U. S. Nuclear Regulatory Commission Region IV RIV 611 Ryan Plaza Dr. , Suite 1000 Occket No. 50-445/IE Sulletin 73-123 Arlington, Texas 76012 50-445/IE Sulletin 73-125 COMANCHE PEAX STEAM ELECTRIC STATION 1981-83 2300 MW INSTALLATION RESPONSE TO NRC IE BULLETINS 73-12,78-12A, & 78-12B FILE NO: 10115

Dear Mr. Seyfrit:

In response to NRC IE Bulletins 78-12,73-12A, and 73-12B, we offer the following:

We have reviewed Combustion Engineering's Generic Report on the subject bulletins, entitled " Atypical Weld Material in Reactor Pressure Vessel Welds."

In establishing the adequacy of the report, we were advised by Westing-house that in previous discussions among themselves, Combustion Engineering and the NRC, it was agreed that information required by these bulletins would be presented on a generic basis. That is, no efforts would be required to identify which weld wire and flux combinations were used on a particular weld on a particular vessel as long as all combinations used by Combustion Engineering in manufacturing each vessel were in compliance with ASME Code Scecifications.

Wich this understanding, we have reviewed the report's responses to apclicable bulletin requirements and find tnem satisfactcry. Furthermore, we have obtained sample weld wire heat number, flux type and lot informa-tion from surveillance weldment data, and have verified that it is covered by the generic report documentation.

Westinghouse has performed a similar review which supports our conclusion tnat the generic report satisfactorily re; resents data for our specific vessels.

If you have any further questions, please advise.

Very truly yours, R.f w$'

J. Gary' RJG::la cc: U. S. Nuclear Regulatory Commission g,[gq7f'tf}[i Office of Inspection and Enforcement Division of Reactor Construction Inspection Wasnington, D. C. 20555 7 908150 /13 $/