ML17067A341

Purdue University - Non-Power Reactor Closeout of Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, for the Purdue University Research Reactor, Docket No. 50-182 (CAC No. A11010)

ML17067A341
Person / Time
Site:	Purdue University
Issue date:	04/17/2017
From:	Alexander Adams NRC/NRR/DPR/PRLB
To:	Townsend C Purdue University Research Reactor
Montgomery C, NRR/DPR/PRLB, 301-415-3398
References
CAC A11010, GL-16-001
Download: ML17067A341 (3)

Text

April 17, 2017 Clive Townsend, Reactor Supervisor Purdue University School of Nuclear Engineering 400 Central Drive West Lafayette, IN 47907

SUBJECT:

PURDUE UNIVERSITY - NON-POWER REACTOR CLOSEOUT OF GENERIC LETTER 2016-01, MONITORING OF NEUTRON-ABSORBING MATERIALS IN SPENT FUEL POOLS, FOR THE PURDUE UNIVERSITY RESEARCH REACTOR, DOCKET NO. 50-182 (CAC NO. A11010)

On April 7, 2016, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16097A169), to address the degradation of neutron-absorbing materials (NAM) in wet storage systems for reactor fuel at power and non-power reactors.

For the non-power reactors, GL 2016-01 requested that licensees provide facility-specific information related to the use of NAM. This information was needed by the NRC staff to verify continued compliance through licensee implementation of effective methods for monitoring of reactor fuel in wet storage so as to detect and mitigate any degradation or deformation of NAM when credited in the facility licensing or design basis for criticality control of fuel in wet storage.

On November 14, 2016, Purdue University submitted a response to GL 2016-01 (ADAMS Accession No. ML16320A167) for the Purdue University Research Reactor. The NRC staff conducted a review of your response to GL 2016-01 and determined that your facility does not credit the use of NAM in the facility licensing or design basis for criticality control of fuel in wet storage. Based upon the information you submitted in response to GL 2016-01 and the results of the NRC staff review, the NRC staff has determined that the submission addresses the information requested in GL 2016-01. No further information or action is requested regarding this matter.

Sincerely,

/RA/

Alexander Adams Jr., Chief Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation cc: See next page

Purdue University Docket No. 50-182 cc:

Ms. Leah Jamieson, Dean of Engineering Purdue University School of Nuclear Engineering 400 Central Drive West Lafayette, IN 47907 Mayor City of West Lafayette 609 W. Navajo West Lafayette, IN 47906 Mr. John H. Ruyack, Manager Epidemiology Res Center/Indoor & Radiological Health Indiana Department of Health 2525 N. Shadeland Ave., E3 Indianapolis, IN 46219 Mr. Howard W. Cundiff, P.E., Director Consumer Protection Indiana State Department of Health 2 North Meridian Street, 5D Indianapolis, IN 46204 Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611 Dr. Robert Bean, Director Purdue University Radiation Laboratory School of Nuclear Engineering 400 Central Drive West Lafayette, IN 47907-2017

ML17067A341; *concurred via email OFFICE NRR/DPR/PRLB/PM NRR/DPR/PROB/LA* NRR/DPR/PGCB/BC NRR/DPR/PRLB/BC CMontgomery SStuchell NAME NParker (AGarmoe for) AAdams DATE 4/7/17 4/7/17 4/17/17 4/17/17