ML20056F849

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Forwards TS Change Request 232 to License DPR-50 to Accomodate Limited Fuel Reconstitution Based on NRC-approved Generic B&W Topical Rept BAW-2149,per GL 90-02,Suppl 1
ML20056F849
Person / Time
Site: Crane Constellation icon.png
Issue date: 08/26/1993
From: Broughton T
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20056F850 List:
References
C311-93-2119, GL-90-02, GL-90-2, NUDOCS 9308310208
Download: ML20056F849 (2)


Text

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GPU Nuclear Corporation E e Nuclear "n = "*

Middletown, Pennsylvania 17057-0480 (7171944-7621 Writer's Direct Dial Number:

I (717) 948-8005 i

August 26, 1993 l

C311-93-2119 i

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Dear Sir:

Subject:

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

Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request (TSCR) No. 232 Generic Letter 90-02, Supplement 1 - Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications In accordance with 10 CFR 50.4(b)(1), enclosed is Technical Specification Change Request No. 232.

Also enclosed is the Certificate of Service for this request certifying service to the chief executives of the township and county in which the facility is i

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 accommodate limited fuel reconstitution based on NRC-approved generic Babcock & Wilcox Topical Report BAW-2149, " Evaluation of Replacemert Rods in BWFC Fuel Assemblies."

The proposed Technical Specification revision is consistent with the guidance contained in NRC Generic Letter 90-02, Supplement 1, dated July 31, 1992.

The model Technical Specification wording in Generic Letter 90-02, Supplement 1 is also reflected in the Standard Technical Specifications for Babcock and Wilcox type plants, as recently issued by the NRC i

(NUREG-1430).

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GPO Nuclear Corporation is a subsidiary of General Public Utilities Corporation

C311-93-2119 Page 2

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Pursuant to 10 CFR 50.51(a)(1), enclosed is our analysis, applying the standards in 10 CFR 50.92 to make a determination of no significant hazards considerations.

l As stated above, pursuant to 10 CFR 50.91(a), we have provided a copy of this letter, the proposed change in Technical Specifications, and our analyses of significant hazards considerations to Richard R.

Janati, the designated representative of the Commonwealth of Pennsylvania.

Sincerely, l

T. G. Brou ton Vice President and Director, 1MI-I TGB/DJD/amc

Enclosures:

(1)

Technical Specification Change Request No. 232 (2)

Certificate of Service for Technical Specification Change Request No. 232 l

cc: Administrator, Region I TMI Senior Resident inspector l

TMI-l Senior Project Manager l

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