ML17334A482

Requests Expeditious Approval to Use Provisions Noted in 1980 & 1983 Editions of ASME Code,Section 11 Re Temp Requirements for Components Constructed of Austenitic Steel, for Inservice Insp During Spring 1984 Refueling Outage

ML17334A482
Person / Time
Site:	Cook
Issue date:	09/02/1983
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0070K, AEP:NRC:70K, NUDOCS 8309070386
Download: ML17334A482 (5)

Text

a REGULA I u~e Y AFO<~A T I UN 0l s r HINDU T Io ~ sY . "l (R IDS)

ACCESS IOr>> NSR: 83090'/038i3 DOC. DA 1'F: 85/09/02 Nu t AR IZED: NO DOCKET 0 PACIL:00-310 l)one o C. Cook >t>>r ear Power Pi ant, Uni t I Indiana I I >I 030010935 30-316 f>anal>i C. Cook >4>>r.lear Power Plant, Ilnit 2, Indiana 0 ILOQ3 AU I i). l'JAb>E Aurr OR AFF I < I A T16rJ ALEX I CH hl. P

~ [ndiana 8 tlinhioan Electric Co.

REC IP. NA lRE REC IPIEN I A-F ILIA IONT DBNTON.H.R. Office of Nuclear Reactor leeaulation, Director

SUBJECT:

Neauests exoeoitious paoroval to use orovisions noted in 1980 8 1983 edi t ions of AsflE Codeisection 11 re temP reuuirements for comt.nnents constructea of austenitic steeli for inservice inso d<ir ino Sorina 1984 refuel ina outaae ~

01STRIBU1ION CODF: A047S COPTFS hECEIVEV:LTR ENCL SIZE:

TITLE: OR Submittal: Inservice. Insnect ion/rest in'OTES:

REC IP IEI~ T Coprrs HE,C IP IEN T COPIES ID CODE INAt>E LrrR ENCL 10 CODE/NArlE LTTR ENCL 1'JRR ORB 1 BC 0 1 II'> TERViAL: FLD/HDS5 NRR/uE/r~EB IS NOH/DE/~lrEH 14 04 hGiu3 EXTERNAL: ACRS 10 1< LPDh 03 rJRc PDik'>> 1 rJSIC 05 T IS 1 tOIAL Nun BER uF COVIES IettJU11eEII: LTr e 27 FNCL

INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 432I6 September 2, 1983 AEP: NRC: 0070K Donald C- Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 INSERVZCE INSPECTION REQUEST TO USE LATER EDITIONS OF THE ASME CODE Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

This submittal is made pursuant to Title 10 of the Code of Federal Regulations, Part 50.55a (g) (4) (iv), and requests approval to use the provisions noted in the 1980 and 1983 editions of the ASME Code, Section XZ, regarding the temperature requirements for components constructed entirely of austenitic steel materials.

Indiana 6 Michigan Electric Company is presently required to comply with the-ASME BGPV Code, Section XZ, 1974 edition through summer 1975 addenda, foz the first ten year inspection interval for both Units 1 and

2. Sections IWB-5222 (a) and IWC-5220 (a) of the 1974 edition of the Code require that the system hydrostatic test pressure for Class 0 1 and 2 systems be performed at a test temperature not less than 100 F. The temperature limitation in the 1974 Code is intended for ferritic steels.

These steels have a ductile to brittle transition temperature and must be tested at temperatures that guard against unstable crack growth.

Austenitic stainless steels, unlike ferritic steels, do not have a ductile to brittle transition temperature, and maintain their fracture toughness to very low temperatures.

Subsequent to the 1974 edition, later Section XI Code editions have increasingly clarified the intent of the code that the test temperature requirement applies only to fezritic materials. In the 1980 edition for Class 2, and the 1983 edition for Classes 1, 2 and 3, austenitic stainless steels are specifically excluded fzom a test temperature requirement. Therefore, we request approval to follow these later editions of the ASME Code for inspection of the austenitic stainless steel materials.

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~10 8309070386 830902 PDR ADOCK 050003l5 G PDR

Mr. Harold D. D n 2>>

Upon receiving the requested approval, the system hydrostatic test temperature at the Donald C. Cook Nuclear Plant for systems comprised entirely of austenitic 0

stainless steels will be ambient temperature> but no lower than 50 F. We wish to make use of the ambient temperature standard for Unit No. 2 during Spring 1984 refueling outage and would appreciate early processing of this request.

This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, P. exich Vxce President MPA/cern cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff E. R. Swanson, NRC Resident Inspector Bridgman

Mr. Harold D. D n AEP:NRC:0070K bc: J. G. Feinstein/T. Satyan Sharma H. N. Scherer, Jr./S. H. Horowitz/R. C. Carruth R. F. Hering/S. H. Steinhart/J. A. Kobyra R. W. Jurgensen R. F. Kroeger J. F. Stietzel - Bridgman J. B. Shinnock D. Wigginton, NRC - Washingtong DE C.

AEP:NRC:0070K DC"N-6015-1