ML112371939

Reed College Responses to RAIs Dated August 15, 2011

ML112371939
Person / Time
Site:	Reed College
Issue date:	08/15/2011
From:	Krahenbuhl M Reed College
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC ME1583
Download: ML112371939 (5)

Text

REED COLLEGE REED RESEARCH REACTOR LICENSE NO. R-112 DOCKET NO. 50-288 RESPONSES TO THE REQUEST FOR ADDITIONAL INFORMATION DATED AUGUST 15, 2011 REDACTED VERSION*

SECURITY-RELATED INFORMATION REMOVED

• REDACTED TEXT AND FIGURES BLACKED OUR OR DENOTED BY BRACKETS

REED COLLEGE REACTOR FACILITY 3203 Southeast August 15, 2011 Woodstock Boulevard Portland, Oregon Document Control Desk 97202-8199 U.S. Nuclear Regulatory Commission telep..one Washington, DC 20555-0001 503/777-7222 Docket: 50-288 fax License No: R-112 503/777-7274 RE: Clarifications in Response to phone calls on July 7, 2011, and July 15, 2011 email

....... @reed.edu The following are clarifications requested in phone calls on July 7 and July 15.

.. , The responses reference the numbering from the original request for additional http://reactor.reed.edu information.

RAI 7. Please make a statement regarding the use of stainless steel clad fuel.

The RRR is a water-cooled, water moderated TRIGA reactor loaded with NRC qualified TRIGA fuel. The core is currently loaded with stainless steel clad "original" fuel as described in NUREG -1282.

RAI 11. Please clarify the core support structure is suitable for use of the requested license.

The core structure was visually inspected July 18, 2011 to verify the condition.

During the inspection there were no visible signs of corrosion, cracking or deformation of the core support structure. Images obtained during the inspection are attached. The condition of pool, core structure, and fuel is observed and noted in the daily start up and shutdown as part of normal operations. The core support structure is deemed acceptable for continued use over the requested license period.

RAI 40. Change the Safety Limit to be consistent with NUREG 1537 part 1.

The safety limit has been set to 1150 1C.

RAI 18. Change the range of the pH to NUREG 1537 part 1 section 5.4 vs. being consistent with NUREG 1537 part I appendix 14.

The pH range has been changed to 5.5 to 7.5 as suggested in NUREG 1537 part 1 section 5.4.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on I ZSZ) d/

Melin a P. Krahensbuhl, Ph.D.

Director, Reed Research Reactor.

Figure 1. Lower grid plate - Reed Figure 2. Legs - Reed Research Reactor