ML20217R357

Application for Amend to License R-95,requesting Listed Changes Be Made to Listed Pp & Sections

ML20217R357
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	08/20/1997
From:	Tehan T RHODE ISLAND, STATE OF
To:	Mendonca M NRC (Affiliation Not Assigned)
Shared Package
ML20217R358	List: ML20217R357 ML20217R360
References
NUDOCS 9709050094
Download: ML20217R357 (2)

Text

r TATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS RHODE ISLAND ATOMIC ENERGY COMMISSION Nuclear Science Center South Ferry Road Narragansett, R,1. 028821197 August 20, 1997 Docket No. 50-193 1

Mr. Marvin Mendonca, Senior Project Manager l

Non-Power Reactors, Decottonissioning and Environmental Project Directorate Division of Reactor Projects - III/IV/V U.S. Nuclear Regulatory Commission Washington,.D.C. 20555 l

Dear Mr. Mendonca:

This letter is an update to our request for an amenchnent of the RIAEC license L by changes to the Technical Specifications. Upon completion of a review of the l-

-rechnical Specifications, the RINSC staff requests the following additional.

changes.

1. page 29 Section - 3.7.1 Radiaticu Monitoring Systems FROM- 3. The reactor shall not be continuously

• operated without a minimum of one area radiation monitor (Table 3.2.8) on the " ground floor level" of the reactor building and one area monitor (Table 3.2.6) over the reactor pool (reactor bridge) operating and capable:of warning personnel of high radiation levels.

To: 3. The reactor shall not be continuously

• operated q without a minimum of one area radiation monitor '

/

(Table 3.3. 8) . on the exoerimental level of the '

reactor building and one area monitor (Table 3.2.6) over the reactor pool (reactor bridge) operating and capable of warning personnel of high radiation levels.

Basis for Change:

Make this paragraph consistent with-Table 3.2. ({ -

2. page 62 Section 6.8 Reporting Requirements FROM: b. Any significant variation of measured values from a corresponding predicted or TO . b. Any significant variation -of measured values from a corresponding predicted or oreviousiv measured value of

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e safety related oneratino characteristics occurrina durina coeration of the reactor.

Basis for Change:

Correct omission from a change made in Admendment #21

3. page 66 section 6.9 Plant Operating Records Delete paragraph g.

Basis for Change:

The paragraph is repeated from page 65.

Enclosed are the new Technical Specifications pages. If there are any questions regarding these changes, you can reach me at (401) 789 9391.

Sincerely.

Terry Tehan Director cc: Tom Dragoun, U.S. NRC, Region 1 1

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