ML042880234

Request to Use Later ASME Code Edition and Addenda

ML042880234
Person / Time
Site:	Perry
Issue date:	10/04/2004
From:	Myers L FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PY-CEI/NRR-3835L
Download: ML042880234 (2)

Text

FENOC FirstEnergy Nuclear Operating Company 76 South AMain Street Akron, Ohio 44308 Lew W. Myers 330-384-3733 Chief Operating Officer Fax: 330-384-3799 October 4, 2004 PY-CEI/NRR-3835L United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Perry Nuclear Power Plant Docket No. 50-440 Request to Use Later ASME Code Edition and Addenda Ladies and Gentlemen:

Pursuant to 10 CFR 50.55a(g)(4)(iv), and as clarified in NRC Regulatory Issue Summary (RIS) 2004-12, 'Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section Xl," the Perry Nuclear Power Plant (PNPP) staff hereby requests Nuclear Regulatory Commission (NRC) approval to use portions of a later edition and addenda of Section Xl of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,(B&PV Code).

The request is detailed in Attachment 1 and is accordance with the September 30, 2002 Nuclear Energy Institute (NEI) white paper titled "Standard Format for Requests from Commercial Reactor Licenses Pursuant to 10 CFR 50.55a."

There are no regulatory commitments contained in this letter or its attachments. If you have questions or require additional information, please contact Mr. Henry Hegrat, FirstEnergy Nuclear Operating Company, Fleet Licensing, at (330) 315-6944.

Very truly yours, for Lew W. Myers

Attachment:

1. .10 CFR 50.55a Request Number-IR-053 i ;

• cc: NRC Project Manager NRC Resident Inspector NRC Region Ill

. . .  : . . Ao(-(-7

Attachment 1 PY-CEI/NRR-3835L Page I of I 10 CFR 50.55a Request Number: IR-053 Proposed Use of Subsequent ASME Code Edition and Addenda In Accordance with 10 CFR 5055a(g)(4)(iv)

1. ASME Code Component(s) Affected All ASME Class 1, 2 and 3 Piping Systems within the scope of the Perry Nuclear Power Plant's (PNPP's) ASME Section Xl boundary. Note that the provisions of this request will be used for portions of PNPP's Class 3 Emergency Service Water system and will be available for use on other Class 1, 2, or 3 piping systems. _ _

2. Applicable Code Edition and Addenda

PNPP is in its second 10-year inservice inspection interval and the 1989 Edition of ASME Section Xl is the code of record for the inservice inspection program.

3. Proposed Subsequent Code Edition and Addenda PNPP proposes to use the rerating requirements of paragraph IWA-4312 of the 1995 Addenda.

4. Related Requirements The related requirements of IWA-4311 and IWA-5000 of the 1995 Addenda, both referenced within IWA-4312, will be used. When a IWA-5213(a) system leakage test is required for rerating, the hold times specified in limitation 10 CFR 50.55a(b)(2)(xx) will be used. Although the 1995 Addenda is not specifically referenced in the limitation, the limitation's hold times will be used because the hold times of the 1995 Addenda are the same as those of the 1997 Addenda and later editions and addenda for which the limitation is applied. Finally, the definition of rerating within IWA-9000 of the 1995 Addenda (not previously included in the Code) will also be used. There are no other related requirementsfr n rerating.

5. Duration of the Proposed Request The rerating provisions of IWA-4312 and identified related requirements will be utilized through the remainder of PNPP's second 10-Year inspection interval (November 18, 1998 through November 17, 2008).