ML19317D799

Replacement Pages for Modified Technical Specification 3.5 of Renewed Facility Operating License No. R-75 of the Ohio State University Research Reactor

ML19317D799
Person / Time
Site:	Ohio State University
Issue date:	11/06/2019
From:	Kauffman A Ohio State University
To:	Xiaosong Yin Document Control Desk, Office of Nuclear Reactor Regulation
References
EPID L-2018-LLA--0231
Download: ML19317D799 (4)

Text

.0 THE OHIO STATE UNIVERSITY College of Engineering Nuclear Reactor Laboratory 1298 Kinnear Rd Columbus, OH 43212 reactorQosu edu reactorosu edu 06-November-2019 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Xiaosong Yin One White Flint North 11555 Rockville Pike Rockvllle MD 20852-2738

Subject:

Replacement Pages for Modified Technical Speclflcat_ion 3.5 of Renewed Facility Operating License No. R-75 of The Ohio State University Research Reactor (EPID NO. L-2018-LLA--0231)

The proposed changes to Section 3.5 of The Ohio State University Research Reactor (OSURR) Technical Specifications (TSs), in a letter to the NRC dated 27-August-2018, result In renumbering of all s.ubsequent pages in C_hapter 3 of the TSs. To eliminate this disruption to the page numbering of Chapter 3, we have attached two pages to replace page 15 ofthe May 2008 revision of the OSURR TSs; these pages are number 15 and 15A, and they leave the page numbering the same for the remaining pages of the May 2008 TSs revision. In addition, a replacement TSs cover page dated November 2019 has also been attached.

If you have any questions on this matter, please contact me at kauffman.9@osu.edu or at 614-688-8220.

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

Executed on 06-November-2019.

Sincerely, Andrew Kauffman Assoc. Director, OSU Nuclear Reactor Laboratory 1298 Kinnear Rd Columbus, OH 43212

APPENDIX A TO RENEWED FACILITY OPERATING LICENSE NO. R-75 Technical Specifications and Bases for The Ohio State University Pool-Type Nuclear Reactor Columbus, Ohio Docket No. 50-150 November 2019

3.5 Ventilation Systems 3.5.1 Nonnal Operations Applicability: This specification applies to ventilation equipment required for nonnal operations, which is only the exhaust fan.

Objective: To specify needed ventilation equipment for nonnal operations.

Specification: The exhaust fan shall be operating when the reactor is operating.

Bases: An operating exhaust fan is necessary to meet the requirements for confinement, as specified in Section 3.4.

3.5.2 Emergency Operations Applicability: This specification applies to ventilation equipment related to emergency operations, which includes all heating, ventilating, and air conditioning systems that exhaust from the restricted area to the outside environment.

Objective: To specify a means to quickly tum off all heating, ventilating, and air conditioning system~ that exhaust from the restricted area in order to isolate the building for emergencies.

Specification: Any heating, ventilating, and air conditioning systems that exhaust from the restricted area to the outside environment shall have the capability to be shut off from a single switch in the control room.

Bases: In the unlikely event of an emergency situation involving the release of fission products or other airborne radioactivity, a means. must be available for shutting off ventilation fans and rapidly isolating the building. Section 8.4.4 of the SAR includes an analysis of fission product release.

3.6 Radiation Monitoring Systems and Radioactive Effluents f

3.6.1 Radiation Monitoring Applicability: This specification applies to the availability of radiation monitoring equipment that shall be operable during reactor operation.

Objective: To ensure that monitoring equipment is available to evaluate radiation levels in restricted and unrestricted areas and to be consistent with the ALARA principle.

Specification:

OSURR License No. R-75 15

(1) When the reactor is operating, the building gaseous effluent monitor shall be operating and have a readout and alarm in the control room. It may be used in either the "normal" mode or "sniffer" mode.

(2) When the reactor is operating, the following area radiation monitors (ARMs) shall be operating and have both local and control room readouts and alarms.

a. pool top

b. primary cooling system

c. beam port/rabbit area

d. thermal column area (3) Portable survey instrumentation shall be available whenever the reactor is operating to measure beta-gamma exposure rates and neutron dose rates.

OSURR License No. R-75 15A