ML20065M986
| ML20065M986 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/19/1994 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20065M989 | List: |
| References | |
| C321-93-2376, NUDOCS 9404260305 | |
| Download: ML20065M986 (3) | |
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..Ee OPU Nuclear Corporation a a Nuc'le.ar
=ener388 Forked River New Jctsey 08731 o388 609 971-4000 Writer's Direct Dial Number:
C321-93-2376 April 19, 1994 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Facility Operating License No. DPR-16 l
Technical Specification Change Request No. 213 Reactor Pressure Vessel Testing - EMRV Bypass Pursuant to 10 CFR 50.90, GPU Nuclear Corporation (GPUN), operator of the Oyster Creek Nuclear Generating Station (OCNGS), Facility Operating License No. DPR-16, requests a change to Appendix A of that license.
The attached Technical Specification Change Request (TSCR)'propeses updating and clarification of Technical Specification 3.4.B.1 to be consistent with existing Specifications 1.39 and 4.3.0 (ASME Code Section XI, Article 5000 requirements). This TSCR deletes reference to the ASME Code Section XI, IS-500 ten year hydrotest inspection interval and replaces this with references
- to (1) the Technical Specification 1.39 definition for Reactor Vessel Pressure Testing and (2) the Technical Specification 3.3.A.(1) Reactor Vessel Pressure Testing limits (P/T and 250" F maximum test temperature).
This TSCR will clarify that the five electromatic relief valves' (EMRV) pressure relief function may be inoperable or bypassed during system pressure testing required by A5ME Code Section XI, Article IWA-5000, including system leakage and hydrostatic test, with reactor vessel completely solid, core not critical and Technical Specification 3.2.A (Core Reactivity Limits) satisfieu.
We request.the NRC staff to place 'an appropriate priority for a. timely review of the proposed Technical Specification change, such that th',s clarification will' be in place for the ISR outage.
26C9C" 9404260305 940419 PDR ADOCK 05000219
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I GPU Nuclear Corporation is a subsidiary of General Pubhc Utdities Corporation
C321-93-2376 Page 2 This change request has been reviewed in accordance with Section 6.5 of the OCNGS Technical Specifications, and using the standards in 10 CFR 50.92 we have concluded that these proposed changes do not constitute a significant hazards consideration.
Pursuant to 10 CFR 50.91 (b) (1), a copy of this change request has been sent to the State of New Jersey Department of Environmental Protection.
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. B^ rton V e Pr sident and Director yst-Creek cc: Administrator, Region 1 NRC Senior Resident Inspector, Oyster Creek Oyster Creek NRC Project Manager
I UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 1
In the Matter of
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Docket No. 50-219 GPU Nuclear Corporation
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1 CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No. 213, for Oyster Creek Nuclear Generating Station Technical Specifications, filed with the U.S. Nuclear Regulatory Commission..on April 19, 1994, has this day of 4/19,1994, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:
The Honorable Theodore Hutler, Jr.
Mayor of Lacty Township 818 West Lacey Road Forked River, NJ 08731 o
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afton Vi 2 esident and Director ster Creek i
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