ML20107N095

Forwards Corrections & Clarifications to Tech Specs in Renewed License R-81 Re Terminology Concerning Safety Limits Operational Setpoints.Addl Fee Should Not Be Required Due to Listed Reasons

ML20107N095
Person / Time
Site:	05000054
Issue date:	11/06/1984
From:	Ruzicka W UNION CARBIDE CORP.
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8411140398
Download: ML20107N095 (2)

Text

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e UNION CARBIDE CORPORATION MEDICAL PRODUCTS OMSION P. O. BOA 324. TUXEDO. NEW YORK 10997 TELEWONE NI JM8ER: (914)351-2131 November 6, 1984 The Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Division of Licensing Gentlemen:

Union Carbide submitted to the NRC an R-81 License renewal application on May 23, 1980. On September 28, 1984 the NRC's Division of Licensing issued Union Carbide a renewed R-81 License.

Upon review of the new license Technical Specifications Union Carbide has noted four areas where corrections or clarifications .are needed. These items are described in Exhibit I attached.

These four items consist of one typographical error and three clarifications of terminology regarding safety limits and operational setpoints. Union Carbide expressed its ' views on this terminology issue in a March 23, 1984 letter to the Commission.

Union Carbide has not forwarded and does not believe an additional licensing fee is required because:

1. the requested changes are in effect a final detail of the license renewal process upon which the appropriate licensing fee has been submitted,

2. the changes are minor in nature, clarifications, or section placement corrections, and

3. the attached terminology clarifications were expressed to the NRC prior to the September 1984 re-issurance of the license.

Sincerely, WGR:js fr)6G2%&

W. G. Ruzicka

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0 Attachment Manager, Nuclear Operations f

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NOTARIAL SEAL- /

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EXHIBIT 1 Technical Specification Change Request License No. R-81, Docket No. 50-54

1. Section 2.1.1 - Specifications Delete: 1) The maximum steady power level under various flow conditions shall be less than or equal to 5 MW (nominal).

Add: 1) The safety limit shall be 14 MW at 1800 gpm primary coolant flow rate.

2. Section 2.1.1 - Specifications Delete: 3) Flow shall not be less than 1600 gpm for power above 250 KW.

3. Section 2.1.2 - Specifications Delete: 1) The maximum reactor power level shall be 500 KW Aod: 1) The safety limit shall be 6.7 MW

4. Section 3.5.1 - Specifications Delete: See Section 3.3.5 Add: See Section 3.5 Reasons for Requested Changes Change 1) The maximum steady state operating power level of 5 MW is a Limiting Safety System Setpoint ano it is covered in Section 2.2.1 Specification 2. The safety limit, as defined in Section 1.0 " Definitions" and 10 CFR 50.36, is 14 MW at 1600 gpm. This fact is already covereo in Sections 2.1.1 " Basis" where it refers to Section Al of Appendix 2 of the Safety Analysis Report.

' Change 2) The 1800 gpm flow requirement above 250 KW is a Limiting Safety System Setpoint and it is covered in Section 2.2.1

' Specification 3.

Change 3) The maximum power level in the natural convection mode of operation is a Limiting Safety System Setpoint and it is covered in Section 2.2.2 Specification 1. The safety limit, as defineo in Section 1.0 " Definitions" and 10 CFR 50.36, is 6.7 MW in the natural convection mode. This fact is already covered in Sections 2.1.2 " Basis" where it refers to natural convection burncut as being 6.7 MW.

Change 4) Typographical error.