ML20065K028: Difference between revisions

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Latest revision as of 07:24, 6 January 2021

Forwards TS Change Request 238 to License DPR-50,relocating Detailed Insp Criteria,Methods & Frequencies of Containment Tendon Surveillance Program to FSAR & Providing Direct Ref to Existing Tendon Surveillance Program in TS
ML20065K028
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 04/11/1994
From: Broughton T
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20065K032 List:
References
C311-94-2004, NUDOCS 9404190108
Download: ML20065K028 (2)


Text

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GPU Nuclear Corporation M Nuclear m:3tr*

Middletown, Pennsylvania 17057-0480 -1 (717) 944-7621 j Writer's Direct Dial Number:  ;

(717) 948-8005 April 11, 1994 C311-94-2004 U. S. Nucit r Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Dear Sir:

Subject:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 '

Technical Specification Change Request No. 238:

In accordance with .10 CFR 50.4(b)(1), enclosed is Technical Specification Change

. Request (TSCR) No. 238.

Also enclosed is a Certificate of Service for this request, certifying service to the chief' executives of the township and county in which the facility is . located, as well as the designated official of the Commonwealth of Pennsylvania, Bureau of Radiation Protection.

The purpose of this TSCR is to request that the TMI-l Technical Specifications be.

. revised to relocate the detailed inspection criteria, methods and frequencies of the containment tendon surveillance program to the FSAR and provide a direct reference to the existing tendon surveillance program in the Technical Specification. This change is consistent with the content of the Babcock and Wilcox Owners' Group Revised Standard Technical Specifications, Revision 0, dated September'28, 1992, Section 3.6.1.2 for containment tendon surveillance requirements.

Pursuant to 10 CFR 50.91(a)(1), enclosed is our analysis, applying the standards .

in 10 CFR 50.92 to make-a determination of no significant hazards considerations.

As stated above, pursuant to 10 CFR 50.91(a), we have provided a copy of this 9404190108 940411-

  1. c PDR ADDCK 05000289 )

.,L- P PDR GPU Nuclear Corporation is a subsidery of General Pubhc Utihbes Corporabon k L

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C311-94-2004 Pag 6 2 of 2 1

letter, the proposed change in Te'ch'nical Specifications, and our analyses of significant hazards considerations to Mr. Robert J. Barkanic, the designated l

. representative of the Commonwealth of Pennsylvania, j Sincerely, H bhM" T. G. BrougMton 1 Vice President and Director, TMI

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DJD/ pip

Enclosure:

1) Technical Specifications Change Request No. 238
2) Certificate of Service for Technical Specification Change Request No. 238 cc: Reginn I Adr.iinistrator l TMI-l Senior Project Manager TMI Senior Resident Inspector

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