ML17334B711
| ML17334B711 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/03/1998 |
| From: | Fitzpatrick E ILLINOIS POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:0980Z, AEP:NRC:980Z, NUDOCS 9804130147 | |
| Download: ML17334B711 (3) | |
Text
CATEGORY 1 REGULAT Y INFORMATION DISTRIBUTI YSTEM (RIDS)
ACCESSION NBR:9804130147 DOC.DATE: 98/04/03 NOTARIZED: NO FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
AUTH.NAME ;"
AUTHOR AFFILIATION FITZPATRICK,E.
Illinois Power Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET 05000315
SUBJECT:
Requests approval IAW 10CFR50.55(a)
(3) to use alternative rules of ASME Section IX Code Cases 2142-1
& 2143-1 in lieu of requirements of 10CFR50.55a(c) for purpose of welding procedure
&, performance qualification.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code - GL-89-04 NOTES:
E RECIPIENT ID CODE/NAME PD3-3 LA STANG, J INTERNAL: AEOD/SPD/RAB NRR/DE/EMEB
'OGC/HDS2 RES/DET/EMMEB COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD3-3 PD NUDOCS -ABSTRACT RES/DET/EIB COPIES LTTR ENCL EXTERNAL: LITCO ANDERSON NRC PDR NOAC D
E
. NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 13 ENCL'
indiana Michigan Power Company 500 Circle Drive Buchanan, MI 491071395 IHOIAiM NICHI6'AN PQWM April 3, 1998 AEP:NRC:09802 Docket No.: 50-315 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Stop 0-Pl-17 Washington, D.C. 20555-0001 Gentlemen:
Donald C.
Cook Nuclear Plant Unit 1 USE OF ASME SECTION IX CODE CASES 2142-1 AND 2143-1
Reference:
- Letter, Robert A.
- Capra, NRC, to Irene M.
- Johnson, Commonwealth Edison Company, "USE OF ASME CODE, SECTION IXg CODE CASES 2142 1 AND 3143 1I BYRON STATIONS UNIT 1,
AND BRAIDWOOD STATION, UNIT 1 (TAC NOS.
M97495 AND M97496)", dated June 1,
1997 Approval is requested in accordance with 10 CFR 50.55a(a)(3) to use the alternative rules of the American Society of Mechanical Engineers (ASME)Section IX Code Cases 2142-1 and 2143-1 in lieu of the requirements of 10 CFR 50.55a(c),
for the purpose of welding procedure and performance qualification.
The use of these code cases was previously approved for use at the Byron and Braidwood stations (see reference).
The use of Alloy 690 type filler materials is necessary in the fabrication and installation of Cook Nuclear Plant unit 1
replacement steam generator lower assemblies.
Weld filler materials that will be utilized for these applications are UNS W86152, matching shielded metal arc welding electrode for Alloy 690, and UNS NO6052, the companion solid wire filler metal used for gas metal arc and gas tungsten arc welding processes.
The materials are classified as F-No.
43 for weld procedure and performance qualification and will be procured in accordance with a nuclear grade procurement program.
Industry studies have shown the Alloy 690 materials to have superior corrosion resistance when compared to Alloy 600 that was used in older steam generators.
The use of UNS W86152 and UNS N06052 weld materials is preferred in order to match the corrosion resistance of the Alloy 690 base metal for welding applications, and have been used on several different steam generator fabrication and installation projects.
The weld materials provide an acceptable level of quality and safety because of their-'superior corrosion resistant properties; therefore, the requirements of 10 CFR
$0.55a(a)(3)(i) are satisfied.
Using these code cases permits the use of a large number of. existing w'elding procedures and performance qualifications, elimin'ating the burden of separate welding procedures for non-code welding materials; therefore, the requirements of 10 CFR 50.55 (a) (3) (ii) are satisfied.
9'804i30i47 980403 PDR ADOCK 050003i5" P
U.S. Nuclear Regulatory Commission Page 2
AEP: NRC: 098 0Z Fabrication of the unit 1 replacement lower assemblies has been proceeding at a pace to meet a delivery of the first assembly in the fall of 1999.
To maintain our fabrication schedule, we request approval to use code cases 2142-1 and 2143-1 by May.29, 1998, prior to installation of the first unit's divider plate in the channel head.
Sincerely, E.
H. Fitspatrick Vice President
/vlb c
A. Abramson A. B. Beach MDEQ -
DW &RPD NRC Resident Inspector J.
R.
Sampson