ML092720824

Idaho State University, Minor Wording Change for License R-110, Revision 7

ML092720824
Person / Time
Site:	Idaho State University
Issue date:	09/17/2009
From:	Crowell P Idaho State University
To:	Duane Hardesty Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML092720824 (2)

Text

September 17, 2009 U.S. NRC Public Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Attention: Mr. Duane Hardesty, Program Manager

Subject:

Minor Wording Change for License R-110, Revision #7.

STATE UNIVERSITY

Dear Mr. Hardesty:

Attached is a minor wording change to Table 3 of the Technical Specification to Facility License R-1 10, as previously discussed. Revision #7 request, dated September 4, 2008, was submitted to account for a change in the instrument readout for the start- up Channel

1. 1. That channel reads in Percent of Full Scale on the present (old, original) control Office of Research console, and in Counts per Second on the new console. The two readings are equivalent 921 South 8th Avenue, in detector response, and otherwise the two consoles use the same detectors, same Stop 8130 instruments, and the same readings on the console, as well as have the same connections Pocatello, Idaho to the reactor. By modifying the wording of Table 3 of the Technical Specifications, as 83209-8130 shown on the attachment, this will allow use of either console.

Physical Address:

The planned console transition, though appearing simple and straightforward, cannot be 1010 South 5th St.

Bldg 11, Room 205 guaranteed to be accomplished in one action which would be expected to occur on the day that the NRC would date the license revision letter. Therefore, the minor change requested in Table 3 will allow us the option of returning to the original console while correcting any issue that might be discovered when the new console is initially connected.

Should you have any questions, please refer them to the Reactor Administrator, Dr. Jay Kunze, at 208-282-4147..

Sincerely, Pamela L. Crowell, Ph.D.

Vice President of Research Affirmation:

I certify that the foregoing is true and correct:

+1 Z-2-011 Executed on q-2_1-c*c September, 2009. Signature *.

c:Mr. Duane Hardesty, Project Manager US NRC, w/attachment, Mail Stop 0-12-D 03 Mr. Greg Schoenebeck, NRC Inspector, w/ attachment, Mail Stop 0-12 D-03 Phone: (208) 282-2714 Fax: (208) 282-4529 www.isu .edu/research ISU Is An Equal Opportunity Employer

ýOD

Table 3.1 Reactor control and safety systems set-p int specifications.

SAFETY CHANNEL SET POINT FUNCTION Nuclear Safety Channel No. 1 Unit A) 5% of Full Scale Scram at levels (Startup Count Rate Channel) OR below the set points Low Power Unit B) 0.5 counts/second Nuclear Safety Channel No. 2 Scram at power (Log Power Channel) 6 Watts > 6 watts High Power (120% of licensed power)

Nuclear Safety Channel No. 2 Scram at source levels (Log Power Channel) 3.0x10" 3 amps > 3x10 1 3 amps Low Power Reactor Period 5 seconds Scram at periods < 5 seconds Nuclear Safety Channel No. 3 Scram at power (Linear Power Channel) 6 Watts > 6 Watts High Power (120% of licensed power)

Nuclear Safety Channel No. 3 Scram at levels (Linear Power Channel) 5% of Full Scale Setting <5% of full scale setting Lower Power Manual Scram Scram at operator option Area Radiation Monitor

• 10 mR/hour Alarm at or below level set to meet requirements of 10 CFR 20 Unit A is the original console, made and assembled about 1960.

• Unit B is the new (2009) all solid state electronic control console.

One or the other of these units will be in service any time the reactor is operating.

3.3 Limitations of Experiments Applicability This specification applies to experiments installed in the reactor and its experimental facilities.

Objective To prevent damage to the reactor or excessive release of radioactive materials in the even of an experiment failure.

Specification

a. Experiments containing materials corrosive to the reactor components or which contain liquid or gaseous, fissionable materials shall be doubly encapsulated.

AGN-201 Technical Specifications, Rev. 7 RSC Approval: September 2, 2008 NRC Approval: Page IIof 31