ML20009A944

Submits Response to NUREG-0313,Revision 1,re Problem of Intergranular Stress Corrosion Cracking for Bwr,Asme Class 2 & 3 Pressure Boundary Piping.All Piping Will Be Ferritic or L-grade Austenitic Stainless Steel

ML20009A944
Person / Time
Site:	Hope Creek, 05000355
Issue date:	07/07/1981
From:	Mittl R Public Service Enterprise Group
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
REF-GTECI-A-42, REF-GTECI-PI, RTR-NUREG-0313, RTR-NUREG-313, TASK-A-42, TASK-OR GL-81-03, GL-81-3, NUDOCS 8107140525
Download: ML20009A944 (2)

Text

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O PSEG Public Service Electric and Gas Company 80 Park Plaza, T16D Newark, N.J. 07101 201/430-8217 Robert L. Mitti July 7, 1981 General Manager - Licensing and Environment m {Q-] f 19, 8 .

Mr. Darrell G. Eisenhut, Director Division of Licensing Uf h(t. -

-1 7 '3190 Office of Nuclear Reactor Regulation - M C Washington, D. C. 20555 o.s.%M g

Dear Mr. Eisenhut:

\

HOPE CREEK GENERATING STATION DOCKET NOS. 50-354 AND 50-355 RESPONSE TO IMPLEMENTATION OF NUREG-0313 REV. 1 (GENERIC TASK A-42)

(GENERIC LETTER 81-03)

On September 28, 1979, we forwarded our response to NUREG -

0313 on the use of austenitic stainless steel in all ASME-Nuclear Class I stainless steel process piping for the construction of Hope Creek Generating Station, Units 1 and

2. Additionally in 1980, we changed the safe ends on both units to a type 316L material and to a new design. This replacement eliminated the thermal sleeves that are welded to the pressure boundary and form crevices.

To meet the requirements set forth in revision 1 of this document, we have given considerable attention to the problem of intergranular stress corrosion cracking (IGSCC) fev BWR, ASME Nuclear Class 2 and 3 pressure boundary piping. Our response to NUREG - 0313,'Rev. 1 is as follows:

1. All ASME Nuclear Class 2 and 3 process piping used in the constr'1ction of Hope Creek Generating Station, Units 1 and 2 will be f' citic steel or L-grade type austenitic stainless r al conforming to ~ the NRC position in Part III. i.

This measure satisfi a the requirements and eliminates the actions called for in the NRC position in Parts III.B and III.C.

1,601

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]O A107140525 810707 PDR ADOCK 05000354 A PDR The Energy People

o Mr. Darrell G. Eisenhut . 7-7-81

2. Since all ASME Nuclear Class 2 and 3 pressure boundary piping meets the guidelines of Part III of NUREG -

0313, Rev. 1, no augmented inservice inspection or leak detection requirements beyond those specified in 10 CFR 50.55 a(g), " Inservice Inspection Requirements" and the plant Technical Specifications for leakage detection are necessary as stated in the NRC position in Part IV.A.

We believe that.the above mitigation measuros'will minimize the susceptibility to stress corrosion cracking of austeni-tic stainless steel in the reactor coolant pressure bound-ary and ' other ASME III Class 2 and 3 process pressure boundary piping, and fitting material. We will continue to monitor the results of the NRC pipe crack study group, and evaluate any further findings for their applicability to the Hope Creek Generating Station.

We will continue our survey of existing equipment vendors to ascertain whether they are providing any ASME III Class 2 or 3 stainless steel piping that is not in compliance with the guidelines stated in Part III. To date, no

" nonconforming" pipe has been found. We expect to complete t'.is survey by January, 1982. We will provide the results of the survey at that time.

Very truly yours, hf }

CC: Mr. Boyce H. Grier - Region I Office OT 03 01/03-E