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{{#Wiki_filter:PURDUEUNIVERSITYSCHOOL OF NUCLEAR ENGINEERING1 June 2012Document Control DeskUS Nuclear Regulatory CommissionOne White Flint North11555 Rockville PikeRockville, MD 20852Attn: Ms. Cindy Montgomery, Research & Test Reactors (NRR/DPR/PRLB), Mailstop 012 D20
{{#Wiki_filter:PURDUE UNIVERSITY SCHOOL OF NUCLEAR ENGINEERING 1 June 2012 Document Control Desk US Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Attn: Ms. Cindy Montgomery, Research & Test Reactors (NRR/DPR/PRLB), Mailstop 012 D20  


==SUBJECT:==
==SUBJECT:==
PURDUE UNIVERSITY -REQUEST FOR ADDITIONAL INFORMATION REGARDINGTHE PURDUE UNIVERSITY REACTOR LICENSE RENEWAL (TAC NO. ME 1594),RESPONSES TO RAIs (ML103400115 and ML103400250)
PURDUE UNIVERSITY  
-REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PURDUE UNIVERSITY REACTOR LICENSE RENEWAL (TAC NO. ME 1594), RESPONSES TO RAIs (ML103400115 and ML103400250)


==Dear Ms. Montgomery:==
==Dear Ms. Montgomery:==
Enclosed please find the responses to the Request for Additional Information regarding the PurdueUniversity Reactor License Renewal dated 6 July 2011. Included with this submission are responses toquestions 43, 51, 56, 60, and 61. Should you have any questions or require further information, pleasedon't hesitate to call me at 765.496.3573, or e-mail at jere@purdue.edu.I hereby certify under penalty of perjury with my signature below that the information contained in thissubmission is true and correct to the best of my knowledge.irector of Radiation LaboraitoriesAttachments: As described.Cc: Duane Hardesty, USNRC Project ManagerLeah Jamieson; Purdue University College of EngineeringJim Schweitzer, Purdue University REMAhmed Hassanein, Purdue NESchool of Nuclear EngineeringNuclear Engineering Building N 400 Central Drive m West Lafayette, IN 47907-2017(765) 494-5739 [ Fax: (765) 494-9570 m https://engineering.purdue.edu/NE PUR-1: Partial Response to RAIs for license renewal (ML103400115 and ML103400250)REQUESTED ADDITIONAL INFORMATION IN RESPONSE TO RAIsREGARDING THE PURDUE UNIVERSITY REACTOR LICENSE RENEWAL (TAC NO. ME 1594)43. Please describe any changes that have occurred to the PUR-1 facility since the PUR-1 SARdated July 7, 2008, was submitted to the NRC that may impact the safety conclusions of theSAR.Response:There have been no changes to the PUR-1 facility since 7 July 2008 that would impact the safetyconclusions of the SAR.51. Section 3.5 of the SAR describes emergency procedures related to the air conditioner drainfrom the condensate holdup tank. Please describe the required actions if contamination issuspected and the method to dispose of any radioactive condensate if contamination isconfirmed.Response:If contamination is suspected, the condensate water will be analyzed utilizing the same procedures thatare used for the periodic analysis of the reactor water. If contamination is confirmed, the water will beproperly disposed of by the university's Department of Radiological and Environmental Management inaccordance with federal, state and local laws, as is all of the other waste generated in work performed atthe university.56. NUREG-1537, Section 11.1.4 provides guidance for radiation monitoring and surveying. SARSection 11.1.6 addresses monthly wipe tests and water samples, but does not stipulate howthe program avoids, prevents, and remedies the occurrence and spread of contamination.Please describe specific contamination control training and a contamination control programwith provisions for recordkeeping sufficient in content and retention to support cleanup ofcontamination, maintenance, and planning for eventual decommissioning.Response:PUR-1 utilizes the Purdue University radiation safety program, as set forth by university policy and theRadiation Safety Manual (http://www.purdue.edu/rem/home/booklets/radman.pdf), which complies withrequirements of the relevant parts of Title 10 of the Code of Federal Regulations and Title 410 Part 5 ofthe Indiana Administrative Code. Initial training of reactor personnel is performed by the Department ofRadiological and Environmental Management (REM). This includes such topics as contamination controland record keeping. The reactor staff is supported by REM health physicists and technicians duringreactor operations where exposures and contamination are possible. Record keeping is maintained bothat the reactor and REM offices.60. NUREG-1537, Section 8 discusses the need for emergency electrical power systems tosystems that ensure radiation doses are maintained ALARA and are within the regulatoryPage 1 of 31 June 2012 PUR-1: Partial Response to RAIs for license renewal (ML103400115 and ML103400250)limits of 10 CFR Part 20. Please discuss pertinent design bases details related to emergencyelectrical power, such as:A. The status of the reactor ventilation system/exhaust during normal operation, and whatwould happen to the ventilation system in the event of a loss of electrical power to thefacility during operations, maintenance, or fuel handling, or in the event of an emergency.B. The reactor ventilation connections to the HVAC system for the rest of the Duncan Annexand including whether operation is continuous related to emergency electrical power.C. The conditions under which reactor ventilation system/exhaust would be isolated, andwhether it can be isolated under loss of electrical power to the facility.D. The fail position for the reactor ventilation system/exhaust dampers related to a loss ofelectrical power.PUR-1 does not have emergency electrical power. Pertinent to the question, however, we note thefollowing:A. The reactor ventilation system exhausts to the roof of the building through a HEPA filter, as notedin the SAR and responses to previous questions. In the event of loss of electrical power, fans willstop, and inlet and outlet dampers will close, which is equivalent to the isolation switch on theoperations console.B. The reactor ventilation system is separate and not connected to any other HVAC system in theDuncan Annex. Loss of electrical power will result in shutdown of the fans, and closing of the inletand outlet dampers.C. In the event of an accident in the reactor room where there is the danger of airbornecontamination, the isolation/shutdown switch would be thrown and the reactor console, whichwould shutdown the fans and close the dampers. This would be equivalent to a loss of power.D. The fail position of the ventilation system and dampers is off/closed.61. Section 13.2.1 of the SAR states that the reactor staff would evacuate the facility within 1.5minutes in the event of an accident. Please provide substantiation for this time estimate anddiscuss other pertinent details such as:A. Radiation alarms in the building to alert the occupants of events requiring evacuation.B. An evacuation plan for students, faculty and staff and whether periodic evacuation drillsare conducted to validate the stated evacuation times.C. The responsible authority that would order and direct the building evacuation in the eventin the reactor that would require an evacuation.D. The exact areas that would be evacuated in the event in the reactor that would require anevacuationE. The conditions, if any, that would require the entire building be evacuated and how longwould it take to complete the evacuation. Also, include how the evacuation is verifiedcomplete.Response:The facility boundary is the reactor room. The room itself measures approximately 30 x 40 feet, and hastwo easily accessible exits on opposite ends of the room. Therefore, 1.5 minutes is a completelyreasonable estimate for evacuation should that become a necessity. The other details are as follows:Page 2 of 3 1 June 2012Page 2 of 31 June 2012 PUR-A: Partial Response to RAIs for license renewal (M L103400115 and M L103400250)A. There is an alarm in the reactor room, and a separate alarm out in the hallway of the nuclearengineering laboratories in the Duncan Annex basement that can be triggered from inside thereactor room.B. Evacuation drills are not conducted. The evacuation plan is listed in the reactor emergencyprocedure, which all reactor operators and those granted unescorted access privileges much befamiliar with. These plans and procedures are commensurate with the size of the facility and therisks present.C. As outlined in the Emergency Plan submitted with the SAR, the Emergency Director isresponsible for determining the necessity of and making the order for building evacuation.D. The reactor room, which is the facility boundary, is the only room that would be required to beevacuated under credible emergency conditions.E. A fire in the building, or a bomb threat, are the only credible conditions that would requireevacuation of the entire building. The evacuation of the facility would be verified by the reactorEmergency Director or designated alternate. The building would be verified by university police orfire emergency personnel.Page 3 of 3 1 June 2012Page 3 of 31 June 2012 1 June 2012Document Control DeskUS Nuclear Regulatory CommissionOne White Flint North11555 Rockville PikeRockville, MD 20852Attn: Ms. Cindy Montgomery, Research & Test Reactors (NRR/DPR/PRLB), Mailstop 012 D20
 
Enclosed please find the responses to the Request for Additional Information regarding the Purdue University Reactor License Renewal dated 6 July 2011. Included with this submission are responses to questions 43, 51, 56, 60, and 61. Should you have any questions or require further information, please don't hesitate to call me at 765.496.3573, or e-mail at jere@purdue.edu.
I hereby certify under penalty of perjury with my signature below that the information contained in this submission is true and correct to the best of my knowledge.
irector of Radiation Laboraitories Attachments:
As described.
Cc: Duane Hardesty, USNRC Project Manager Leah Jamieson; Purdue University College of Engineering Jim Schweitzer, Purdue University REM Ahmed Hassanein, Purdue NE School of Nuclear Engineering Nuclear Engineering Building N 400 Central Drive m West Lafayette, IN 47907-2017 (765) 494-5739 [ Fax: (765) 494-9570 m https://engineering.purdue.edu/NE PUR-1: Partial Response to RAIs for license renewal (ML103400115 and ML103400250)
REQUESTED ADDITIONAL INFORMATION IN RESPONSE TO RAIs REGARDING THE PURDUE UNIVERSITY REACTOR LICENSE RENEWAL (TAC NO. ME 1594)43. Please describe any changes that have occurred to the PUR-1 facility since the PUR-1 SAR dated July 7, 2008, was submitted to the NRC that may impact the safety conclusions of the SAR.Response: There have been no changes to the PUR-1 facility since 7 July 2008 that would impact the safety conclusions of the SAR.51. Section 3.5 of the SAR describes emergency procedures related to the air conditioner drain from the condensate holdup tank. Please describe the required actions if contamination is suspected and the method to dispose of any radioactive condensate if contamination is confirmed.
Response: If contamination is suspected, the condensate water will be analyzed utilizing the same procedures that are used for the periodic analysis of the reactor water. If contamination is confirmed, the water will be properly disposed of by the university's Department of Radiological and Environmental Management in accordance with federal, state and local laws, as is all of the other waste generated in work performed at the university.
: 56. NUREG-1537, Section 11.1.4 provides guidance for radiation monitoring and surveying.
SAR Section 11.1.6 addresses monthly wipe tests and water samples, but does not stipulate how the program avoids, prevents, and remedies the occurrence and spread of contamination.
Please describe specific contamination control training and a contamination control program with provisions for recordkeeping sufficient in content and retention to support cleanup of contamination, maintenance, and planning for eventual decommissioning.
Response: PUR-1 utilizes the Purdue University radiation safety program, as set forth by university policy and the Radiation Safety Manual (http://www.purdue.edu/rem/home/booklets/radman.pdf), which complies with requirements of the relevant parts of Title 10 of the Code of Federal Regulations and Title 410 Part 5 of the Indiana Administrative Code. Initial training of reactor personnel is performed by the Department of Radiological and Environmental Management (REM). This includes such topics as contamination control and record keeping. The reactor staff is supported by REM health physicists and technicians during reactor operations where exposures and contamination are possible.
Record keeping is maintained both at the reactor and REM offices.60. NUREG-1537, Section 8 discusses the need for emergency electrical power systems to systems that ensure radiation doses are maintained ALARA and are within the regulatory Page 1 of 3 1 June 2012 PUR-1: Partial Response to RAIs for license renewal (ML103400115 and ML103400250) limits of 10 CFR Part 20. Please discuss pertinent design bases details related to emergency electrical power, such as: A. The status of the reactor ventilation system/exhaust during normal operation, and what would happen to the ventilation system in the event of a loss of electrical power to the facility during operations, maintenance, or fuel handling, or in the event of an emergency.
B. The reactor ventilation connections to the HVAC system for the rest of the Duncan Annex and including whether operation is continuous related to emergency electrical power.C. The conditions under which reactor ventilation system/exhaust would be isolated, and whether it can be isolated under loss of electrical power to the facility.D. The fail position for the reactor ventilation system/exhaust dampers related to a loss of electrical power.PUR-1 does not have emergency electrical power. Pertinent to the question, however, we note the following:
A. The reactor ventilation system exhausts to the roof of the building through a HEPA filter, as noted in the SAR and responses to previous questions.
In the event of loss of electrical power, fans will stop, and inlet and outlet dampers will close, which is equivalent to the isolation switch on the operations console.B. The reactor ventilation system is separate and not connected to any other HVAC system in the Duncan Annex. Loss of electrical power will result in shutdown of the fans, and closing of the inlet and outlet dampers.C. In the event of an accident in the reactor room where there is the danger of airborne contamination, the isolation/shutdown switch would be thrown and the reactor console, which would shutdown the fans and close the dampers. This would be equivalent to a loss of power.D. The fail position of the ventilation system and dampers is off/closed.
: 61. Section 13.2.1 of the SAR states that the reactor staff would evacuate the facility within 1.5 minutes in the event of an accident.
Please provide substantiation for this time estimate and discuss other pertinent details such as: A. Radiation alarms in the building to alert the occupants of events requiring evacuation.
B. An evacuation plan for students, faculty and staff and whether periodic evacuation drills are conducted to validate the stated evacuation times.C. The responsible authority that would order and direct the building evacuation in the event in the reactor that would require an evacuation.
D. The exact areas that would be evacuated in the event in the reactor that would require an evacuation E. The conditions, if any, that would require the entire building be evacuated and how long would it take to complete the evacuation.
Also, include how the evacuation is verified complete.Response: The facility boundary is the reactor room. The room itself measures approximately 30 x 40 feet, and has two easily accessible exits on opposite ends of the room. Therefore, 1.5 minutes is a completely reasonable estimate for evacuation should that become a necessity.
The other details are as follows: Page 2 of 3 1 June 2012 Page 2 of 3 1 June 2012 PUR-A: Partial Response to RAIs for license renewal (M L103400115 and M L103400250)
A. There is an alarm in the reactor room, and a separate alarm out in the hallway of the nuclear engineering laboratories in the Duncan Annex basement that can be triggered from inside the reactor room.B. Evacuation drills are not conducted.
The evacuation plan is listed in the reactor emergency procedure, which all reactor operators and those granted unescorted access privileges much be familiar with. These plans and procedures are commensurate with the size of the facility and the risks present.C. As outlined in the Emergency Plan submitted with the SAR, the Emergency Director is responsible for determining the necessity of and making the order for building evacuation.
D. The reactor room, which is the facility boundary, is the only room that would be required to be evacuated under credible emergency conditions.
E. A fire in the building, or a bomb threat, are the only credible conditions that would require evacuation of the entire building.
The evacuation of the facility would be verified by the reactor Emergency Director or designated alternate.
The building would be verified by university police or fire emergency personnel.
Page 3 of 3 1 June 2012 Page 3 of 3 1 June 2012 1 June 2012 Document Control Desk US Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Attn: Ms. Cindy Montgomery, Research & Test Reactors (NRR/DPR/PRLB), Mailstop 012 D20  


==SUBJECT:==
==SUBJECT:==
PURDUE UNIVERSITY -REQUEST FOR ADDITIONAL INFORMATION REGARDINGTHE PURDUE UNIVERSITY REACTOR LICENSE RENEWAL (TAC NO. ME 1594),RESPONSES TO RAIs (ML103400115 and ML103400250)
PURDUE UNIVERSITY  
-REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PURDUE UNIVERSITY REACTOR LICENSE RENEWAL (TAC NO. ME 1594), RESPONSES TO RAIs (ML103400115 and ML103400250)


==Dear Ms. Montgomery:==
==Dear Ms. Montgomery:==
Enclosed please find the responses to the Request for Additional Information regarding the PurdueUniversity Reactor License Renewal dated 6 July 2011. Included with this submission are responses toquestions 43, 51, 56, 60, and 61. Should you have any questions or require further information, pleasedon't hesitate to call me at 765.496.3573, or e-mail at jere@purdue.edu.I hereby certify under penalty of perjury with my signature below that the information contained in thissubmission is true and correct to the best of my knowledge.Very respectfully,Jere H. JenkinsDirector of Radiation LaboratoriesAttachments: As described.Cc: Duane Hardesty, USNRC Project ManagerLeah Jamieson; Purdue University College of EngineeringJim Schweitzer, Purdue University REMAhmed Hassanein, Purdue NE  
 
}}
Enclosed please find the responses to the Request for Additional Information regarding the Purdue University Reactor License Renewal dated 6 July 2011. Included with this submission are responses to questions 43, 51, 56, 60, and 61. Should you have any questions or require further information, please don't hesitate to call me at 765.496.3573, or e-mail at jere@purdue.edu.
I hereby certify under penalty of perjury with my signature below that the information contained in this submission is true and correct to the best of my knowledge.
Very respectfully, Jere H. Jenkins Director of Radiation Laboratories Attachments:
As described.
Cc: Duane Hardesty, USNRC Project Manager Leah Jamieson; Purdue University College of Engineering Jim Schweitzer, Purdue University REM Ahmed Hassanein, Purdue NE}}

Revision as of 14:19, 28 July 2018

Request for Additional Information Regarding the Purdue University Reactor License Renewal (TAC ME1594), Responses to RAIs (ML103400115 and ML103400250)
ML12156A364
Person / Time
Site: Purdue University
Issue date: 06/01/2012
From: Jenkins J H
Purdue University Research Reactor
To: Montgomery C K
Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC ME1594
Download: ML12156A364 (5)
v • d • e


Text

PURDUE UNIVERSITY SCHOOL OF NUCLEAR ENGINEERING 1 June 2012 Document Control Desk US Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Attn: Ms. Cindy Montgomery, Research & Test Reactors (NRR/DPR/PRLB), Mailstop 012 D20

SUBJECT:

PURDUE UNIVERSITY

-REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PURDUE UNIVERSITY REACTOR LICENSE RENEWAL (TAC NO. ME 1594), RESPONSES TO RAIs (ML103400115 and ML103400250)

Dear Ms. Montgomery:

Enclosed please find the responses to the Request for Additional Information regarding the Purdue University Reactor License Renewal dated 6 July 2011. Included with this submission are responses to questions 43, 51, 56, 60, and 61. Should you have any questions or require further information, please don't hesitate to call me at 765.496.3573, or e-mail at jere@purdue.edu.

I hereby certify under penalty of perjury with my signature below that the information contained in this submission is true and correct to the best of my knowledge.

irector of Radiation Laboraitories Attachments:

As described.

Cc: Duane Hardesty, USNRC Project Manager Leah Jamieson; Purdue University College of Engineering Jim Schweitzer, Purdue University REM Ahmed Hassanein, Purdue NE School of Nuclear Engineering Nuclear Engineering Building N 400 Central Drive m West Lafayette, IN 47907-2017 (765) 494-5739 [ Fax: (765) 494-9570 m https://engineering.purdue.edu/NE PUR-1: Partial Response to RAIs for license renewal (ML103400115 and ML103400250)

REQUESTED ADDITIONAL INFORMATION IN RESPONSE TO RAIs REGARDING THE PURDUE UNIVERSITY REACTOR LICENSE RENEWAL (TAC NO. ME 1594)43. Please describe any changes that have occurred to the PUR-1 facility since the PUR-1 SAR dated July 7, 2008, was submitted to the NRC that may impact the safety conclusions of the SAR.Response: There have been no changes to the PUR-1 facility since 7 July 2008 that would impact the safety conclusions of the SAR.51. Section 3.5 of the SAR describes emergency procedures related to the air conditioner drain from the condensate holdup tank. Please describe the required actions if contamination is suspected and the method to dispose of any radioactive condensate if contamination is confirmed.

Response: If contamination is suspected, the condensate water will be analyzed utilizing the same procedures that are used for the periodic analysis of the reactor water. If contamination is confirmed, the water will be properly disposed of by the university's Department of Radiological and Environmental Management in accordance with federal, state and local laws, as is all of the other waste generated in work performed at the university.

56. NUREG-1537, Section 11.1.4 provides guidance for radiation monitoring and surveying.

SAR Section 11.1.6 addresses monthly wipe tests and water samples, but does not stipulate how the program avoids, prevents, and remedies the occurrence and spread of contamination.

Please describe specific contamination control training and a contamination control program with provisions for recordkeeping sufficient in content and retention to support cleanup of contamination, maintenance, and planning for eventual decommissioning.

Response: PUR-1 utilizes the Purdue University radiation safety program, as set forth by university policy and the Radiation Safety Manual (http://www.purdue.edu/rem/home/booklets/radman.pdf), which complies with requirements of the relevant parts of Title 10 of the Code of Federal Regulations and Title 410 Part 5 of the Indiana Administrative Code. Initial training of reactor personnel is performed by the Department of Radiological and Environmental Management (REM). This includes such topics as contamination control and record keeping. The reactor staff is supported by REM health physicists and technicians during reactor operations where exposures and contamination are possible.

Record keeping is maintained both at the reactor and REM offices.60. NUREG-1537, Section 8 discusses the need for emergency electrical power systems to systems that ensure radiation doses are maintained ALARA and are within the regulatory Page 1 of 3 1 June 2012 PUR-1: Partial Response to RAIs for license renewal (ML103400115 and ML103400250) limits of 10 CFR Part 20. Please discuss pertinent design bases details related to emergency electrical power, such as: A. The status of the reactor ventilation system/exhaust during normal operation, and what would happen to the ventilation system in the event of a loss of electrical power to the facility during operations, maintenance, or fuel handling, or in the event of an emergency.

B. The reactor ventilation connections to the HVAC system for the rest of the Duncan Annex and including whether operation is continuous related to emergency electrical power.C. The conditions under which reactor ventilation system/exhaust would be isolated, and whether it can be isolated under loss of electrical power to the facility.D. The fail position for the reactor ventilation system/exhaust dampers related to a loss of electrical power.PUR-1 does not have emergency electrical power. Pertinent to the question, however, we note the following:

A. The reactor ventilation system exhausts to the roof of the building through a HEPA filter, as noted in the SAR and responses to previous questions.

In the event of loss of electrical power, fans will stop, and inlet and outlet dampers will close, which is equivalent to the isolation switch on the operations console.B. The reactor ventilation system is separate and not connected to any other HVAC system in the Duncan Annex. Loss of electrical power will result in shutdown of the fans, and closing of the inlet and outlet dampers.C. In the event of an accident in the reactor room where there is the danger of airborne contamination, the isolation/shutdown switch would be thrown and the reactor console, which would shutdown the fans and close the dampers. This would be equivalent to a loss of power.D. The fail position of the ventilation system and dampers is off/closed.

61. Section 13.2.1 of the SAR states that the reactor staff would evacuate the facility within 1.5 minutes in the event of an accident.

Please provide substantiation for this time estimate and discuss other pertinent details such as: A. Radiation alarms in the building to alert the occupants of events requiring evacuation.

B. An evacuation plan for students, faculty and staff and whether periodic evacuation drills are conducted to validate the stated evacuation times.C. The responsible authority that would order and direct the building evacuation in the event in the reactor that would require an evacuation.

D. The exact areas that would be evacuated in the event in the reactor that would require an evacuation E. The conditions, if any, that would require the entire building be evacuated and how long would it take to complete the evacuation.

Also, include how the evacuation is verified complete.Response: The facility boundary is the reactor room. The room itself measures approximately 30 x 40 feet, and has two easily accessible exits on opposite ends of the room. Therefore, 1.5 minutes is a completely reasonable estimate for evacuation should that become a necessity.

The other details are as follows: Page 2 of 3 1 June 2012 Page 2 of 3 1 June 2012 PUR-A: Partial Response to RAIs for license renewal (M L103400115 and M L103400250)

A. There is an alarm in the reactor room, and a separate alarm out in the hallway of the nuclear engineering laboratories in the Duncan Annex basement that can be triggered from inside the reactor room.B. Evacuation drills are not conducted.

The evacuation plan is listed in the reactor emergency procedure, which all reactor operators and those granted unescorted access privileges much be familiar with. These plans and procedures are commensurate with the size of the facility and the risks present.C. As outlined in the Emergency Plan submitted with the SAR, the Emergency Director is responsible for determining the necessity of and making the order for building evacuation.

D. The reactor room, which is the facility boundary, is the only room that would be required to be evacuated under credible emergency conditions.

E. A fire in the building, or a bomb threat, are the only credible conditions that would require evacuation of the entire building.

The evacuation of the facility would be verified by the reactor Emergency Director or designated alternate.

The building would be verified by university police or fire emergency personnel.

Page 3 of 3 1 June 2012 Page 3 of 3 1 June 2012 1 June 2012 Document Control Desk US Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Attn: Ms. Cindy Montgomery, Research & Test Reactors (NRR/DPR/PRLB), Mailstop 012 D20

SUBJECT:

PURDUE UNIVERSITY

-REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PURDUE UNIVERSITY REACTOR LICENSE RENEWAL (TAC NO. ME 1594), RESPONSES TO RAIs (ML103400115 and ML103400250)

Dear Ms. Montgomery:

Enclosed please find the responses to the Request for Additional Information regarding the Purdue University Reactor License Renewal dated 6 July 2011. Included with this submission are responses to questions 43, 51, 56, 60, and 61. Should you have any questions or require further information, please don't hesitate to call me at 765.496.3573, or e-mail at jere@purdue.edu.

I hereby certify under penalty of perjury with my signature below that the information contained in this submission is true and correct to the best of my knowledge.

Very respectfully, Jere H. Jenkins Director of Radiation Laboratories Attachments:

As described.

Cc: Duane Hardesty, USNRC Project Manager Leah Jamieson; Purdue University College of Engineering Jim Schweitzer, Purdue University REM Ahmed Hassanein, Purdue NE

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