Text

Regulatory Audit License Amendment Request Regarding Fueled Experiments for the Pulstar Research Reactor (EPID L-2022-NFA-0004) License No. R-120; Docket No. 50-297
	ML23171B001
Person / Time
Site:	North Carolina State University
Issue date:	06/20/2023
From:	Hawari A; North Carolina State University
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	EPID L-2022-NFA-0004
	Download: ML23171B001 (1)
	v • d • e

bv Nuclear Reactor Program Campus Box 7909 Department of Nuclear Engineering 2500 Stinson Drive https://nrp.ne.ncsu.edu/ Raleigh, NC 27695-7909 919.515.7294 (voice) 919-513-1276 (fax)

June 20, 2023

U.S. Nuclear Regulatory Commission Document Control Desk Washington,DC

SUBJECT Regulatory Audit RE: License Amendment Request Regarding Fueled Experiments for the PULSTAR Research Reactor (EPID L-2022-NFA-0004)

License No. R-120 Docket No. 50-297

Please find updates to Attachments 1, 2, and 3 submitted on 13 March 2023 [ML23075056]

regarding the license amendment request (LAR) for fueled experiments at the NC State University PULSTAR reactor attached. Attachment 4 submitted on 13 March 2023 [ML23075056] is not changed.

If you have any questions regarding this report or require additional information, please contact Gerald Wicks, Acting Manager of Engineering and Operations, at (919) 515-4601 or wicks@ncsu.edu.

I declare under penalty of perjury that the forgoing is true and correct. Executed on 20 June 2023.

Sincerely,

Ayman I. Hawari, Ph.D.

Director, Nuclear Reactor Program

Enclosures:

Attachment 1 [6-19-23]: Technical Specification Amendment 19 Line Changes and Justification Attachment 2 [6-19-23]: Technical Specifications Amendment 19 (affected pages with change bars)

Attachment 3 [6-19-23]: Technical Specifications Amendment 19 (affected pages clean copy)

Attachment 1 [6-19-23]:

Technical Specification Amendment 19 Line Changes and Justification

Technical Specification Amendment 19 Line Changes and Justification 13 March 2023 and 19 June 2023

Changes to the Technical Specifications for the North Carolina State University PULSTAR Reactor are described below. Each change is noted along with justification of the change.

1. TS Cover Page: Amendment number and date were updated.

Amendment number was updated to reflect the new revisi on being submitted. Date for the last update to the TS documentation is changed to reflect the latest submission date.

2. Table of Contents updated.

Table 3.8-1 and Figure 3.8-1 were removed from list of figures and tables.

Page number for Table 3.6-1 was updated.

3. Document Headers - all pages with changes Headers on all pages with changes were updated to reflect the current revision number and date.

4. TS Page 2 - Definition of Fueled Experiment

The definition of fueled experiments was clarified to specify the irradiation of fissile materials and exclude common reactor applications of fissile materials such as detectors. This change clearly defines the fueled experiments as separate from reactor operation or monitoring using the NRC Glossary definition of fissile materials (last updated March 31, 2021).

Detectors, here, are considered off -the-shelf and not fueled experiments themselves.

Sealed sources would be limited to neut ron sources used in reactor operations.

Naturally occurring elements are assumed to not be fueled experiments.

Clarity added to indicate fuel used in operation of the reactor is that of the PULSTAR reactor.

List of points broken into individual bulleted elements for clarity.

5. TS Page 2 - Spacing Adjustments

With the additional wording added to TS 1.2.9 e, spacing was adjusted to TS 1.2.7 through 1.2.10 to fit the text on page 2.

6. TS 3.5: Radiation Monitoring

Applicability This specification applies to the availability of radiation monitoring equipment which must be operableting during reactor operation.

Objective To assure that radiation monitoring equipment is available for evaluation of radiation conditions in restricted and unrestricted areas.

Specification The reactor or vented fueled experiment shall not be operated nor shall irradiated fuel or irradiated fueled experiments that are not contained in a properly sealed and approved shipping container be moved within the reactor building unless the radiation monitoring equipment listed below and in Table 3.5-1 is operatingble.(1)(2)(3) (7)

a. Three fixed area monitors operating in the Reactor Building with their setpoints as listed in Table 3.5-1.(1)(3)(4)

b. Stack pParticulate and stack gas building exhaust monitors continuously sampling air in the facility exhaust stack with their setpoints as listed in Table 3.5-1.(1)(3)(4)

c. The Radiation Rack Recorder.(5)

d. Vented fueled experiment exhaust gas radiation monitor continuously monitoring the experiment exhaust gas.(7) c.e. Vented fueled experiment flow rate monitor continuously monitoring the experiment exhaust gas flow.(7)

The word operable in the applicability statement and specification statement were changed to operating as defined in TS 1.2.15 to require the listed equipment to be operating during reactor operation.

The specification statement was changed to require monitoring for vented fueled experiments.

Changes to TS 3.5 now include the movement of irradiated fuel and fueled experiments within not just the reactor pool but also the reactor building. This adds th e requirement for radiation monitoring to be operable during such activities. The operability of such monitors ensures that during an accident scenario, confinement and other emergency actions will automatically occur. As an exception and for consistency with current standards, irradiated fuel within a sealed shipping container is excluded (see ANSI 15.1 standard).

The names of the gas and particulate monitors are updat ed to better correlate with Table 3.5-1. There is not intended change of the purpose.

Additional conditions for radiation monitoring for vented fueled experiments are added to specifically ensure the rate of release at the experiment is monitored at known conditions (flow rate) during the vented fueled experiments. The addition of these monitors will ensu re the operational conditions are known and will isolate any potential experimental impact on the reactor settings.

Line spacing adjustments were made to TS 3.5 to fit the text to page 19.

7. Table 3.5-1: Required Radiation Area Monitors

The setpoints for the entire facility are not changed fro m the current TS and are based on the analysis of the dose to the public as performed in the facility Emergency Plan and the ANSI/ANS 15.16-2008 standard. The current analysis shows that our annual facility releas es will be significantly below the 10 C FR 20 10 mrem annual dose constraint. Therefore, no change to the setpoints is made.

With the addition of fission gases from vented fueled experiments, the stack gas monitor is expected to see a combination of halogen and fission gas nuclides, not just Ar-41. However, Ar-41 and Co-60 still are applicable to current operations and are conservative even for fueled experiments. Fission product AEC values are higher than those for Ar-41 and Co-60. Therefore, using Ar-41 and Co-60 AEC for the setpoints is conservative.

8. TS 3.5: Radiation Monitoring - Footnotes

Footnote (2) moved from page 19 to page 20 for formatting purposes. Spaced adjusted on pages 19 and 20 between text lines to accommodate the additional wording.

9. TS 3.5: Radiation Monitoring - Footnotes

The specifications of monitoring of vented experiments is limited to when the experiment is in operation.

These conditions allow reactor operat ion without vented experiment monitoring when such experiments are not operating and not installed.

10. TS 3.5: Radiation Monitoring - Bases

The bases for TS 3.5 were updated to reflect the wording and description in the actual TS. As such the abbreviation of the Safety Analysis Report is defined and the particulate and gas monitors are described as stack particulate and stack gas monitors in keeping with the language in the TS.

Additional description of the setpoints in Table 3.5-1 is given. The levels used to define the Alert points is founded in the site Emergency Plan Section 5.1 and the definitions of a notification of unusual event for the site. Justification for the continued use of the Ar-41 and Co-60 AEC values as the standard is given.

Spacing was adjusted to fit the text on page 20.

11. TS 3.6: Confinement and Main HVAC Systems

Additional conditions for the operability of the confinement and HVAC systems were included to cover fueled experiment movement and also broaden the scope from the pool area to the reactor building as a whole.

Additional wording to update the TS wording in compliance with the ANSI 15.1 standard providing an exception for sealed material in a shipping container.

Additionally, a blank line following this paragraph was removed to improve the layout on the page.

Line spacing adjustments were made to TS 3.6 to fit the text to page 21.

12. TS 3.6: Confinement and Main HVAC Systems - Footnotes

A historical typo which incorrectly references the wron g table is corrected to reference Table 3.5 -1 which contains the radiation monitoring equipment.

13. TS 3.8: Operations with Fueled Experiments

The wording was updated to provide a single limit for al l fueled experiments. By defining a fission rate, samples with higher mass must be irradiated in lowe r fluxes. Samples with lower masses may be irradiated at higher fluxes. As a result of simplifying to a single fission rate, Table 3.8-1 and Figure 3.8-1 are no longer needed and are removed.

Line spacing adjustments were made to TS 3.8 to fit the text to Page 26.

14. TS 3.8: Operations with Fueled Experiments

The requirement to operate in confinement during a fueled experiments is not needed to ensure public dose requirements are within reason. Restrictions are in plac e based on TS 3.8 d which require the site total released public dose to be less than 10 mrem. Further, the practice of standard operation with confinement running reduces the number of emergency systems in place if an accident were to occur. Based on the analysis of the proposed fueled experiments, the release will remain well within the 10 CFR 20 administrative limit and do not require confinement to be operating.

Confinement and radiation monitoring must be operable according to TS 3.5 and 3.6, and to avoid repetition, the redundant wording was removed.

15. TS 3.8: Operations with Fueled Experiments

TS 3.2 provides the maximum experiment worths, and to avoid repetition, the redundant wording was removed.

16. TS 3.8: Operations with Fueled Experiments

d.b. Specification 3.7 pertaining to reactor experiments shall be met with the exception that encapsulation is not required for vented fueled experiments, and vented fueled experiments may allow for the release of gaseous airborne activity. Vented fueled experiments shall be designed to prevent interaction with reactor components or pool water.

Based on the analysis of both encapsulated and vented experiments, all potential releases produce doses well within the 10 CFR 20 annual dose constraint. As a resu lt, previous restrictions which required encapsulation of all experiments is broadened here to allow for vented fueled experiments while still maintaining all other requirements for experiments at the reactor. Vented experiments are restricted t o only allow for gaseous airborne activity and not particulate releases, further ensuring doses are kept minimal.

The intention from TS 3.7 of avoiding interaction with the reactor components or pool water was added to provide clarity that even without encapsulation, vented fueled experiments must still ensure reactor component and pool water safety. Wording of the vented experiments was also updated to consistently reference vented fueled experiments.

Airborne activity was changed to gaseous airborne activity in the proposed Specification 3.8 b to describe releases allowed from vented fueled experiments.

17. TS 3.8: Operations with Fueled Experiments

Review of experiments is required using both procedures currently in place within TS 6.2.3 and 6. 5, and to avoid repetition, the redundant wording was removed.

Based on the analysis for the fueled experiments complete d for this LAR, the impact from fueled experiments is bounded by the fission rate in these proposed TS and potential releases are minimal. As such, each experiment may be reviewed under the standard procedures.

Additionally, the formatting of this point was improved to provide clarity to readers.

Terminology was updated to reflect the definition of fueled experiments given in the TS.

Fueled experiments will be further restricted from th e currently approved TS to not included gaseous fuel materials.

The bases for this requirement is that the pool water mu st not boil. For fueled experiments which are outside the pool water, the temperature of the experiment will not impact potential boiling of the pool water.

The radiation monitoring in place and required by TS 3.5 provide coverage of potential releases for encapsulated experiments. For vented fueled experiments, additional monitoring of the exhaust is required to provide notification of any unusual event at the experiment location.

Experiment requirements are in TS 3.2 and 3.7, and to avoid repetition, the redundant wording was removed.

The limit on dose release including credible fueled expe riment accidents is set at the 10 CFR 20 annual dose constraint of 10 mrem in keeping with ALARA principles.

18. TS 3.8: Operations with Fueled Experiments

Table 3.8-1 and Figure 3.8-1 were removed as the data was simplified to the description in TS 3.8 a.

Pages 27 and 28 were intentionally left blank after the figure and table were removed to maintain the formatting of the TS document.

19. TS 3.8: Operations with Fueled Experiments - Bases

The bases of TS 3.8 are kept the same as the logic applied is consistent with the currently approved TS. The change in reference to the sections required for the ap proval and review of fueled experiments is updated to reflect the change in the TS 3.8.

20. TS 4.4: Radiation Monitoring Equipment

4.4 Radiation Monitoring Equipment

Applicability

This specification applies to the surveillance requirements for the area and stack effluent radiation monitoring and vented fueled experiment exhaust gas radiation and flow monitoring equipment.

Objective

The objective is to assure that the radiation monitoring equipment is operable.

Specification

a. TChannel calibration of the area and stack monitoring systems shall be calibrated performed annually but at intervals not to exceed fifteen (15) months or after replacement, repair, or modification of the monitoring system.s.

b. The setpoints of the area and stack monitoring systems shall be verified weekly, but at intervals not to exceedten

b. (10) days.

c. Channel calibration of the vented fueled experiment exhaust gas radiation and flow monitors shall be performed prior to initial operation of the experiment and annually, not to exceed fifteen (15) months, thereafter while the experiment is installed in the reactor or after replacement, repair, or modification of the monitoring system(s).

d. The setpoints of the vented fueled exhaust gas radiation and flow monitors shall be verified weekly, but at intervals not to exceed ten (10) days if the ve n t e d f ue l e d e xp e r i me nt i s installed in the reactor.

e. Channel checks shall be performed for the following:

Area and stack radiation monitors prior to fi rst start of reactor operation of the day.

Vented fueled experiment exhaust gas radiation monitor prior to first start of operation of the experiment of the day.

Vented fueled experiment flow rate monitor prior to first start of operation of the experiment of the day.

f. Channel tests shall be performed monthly, but at intervals not to exceed six (6) weeks, for the following:

Area and stack radiation monitors.

Vented fueled experiment exhaust gas radiation monitor if the vented fueled experiment is installed in the reactor.

Vented fueled experiment flow rate monitor if the vented fueled experiment is installed in the reactor.

Applicability updated to include the new conditions for the vented fueled experiment exhaust gas radiation and flow monitoring equipment when the experiment is installed in the reactor.

The calibration of the area and stack monitoring systems was changed to be a channel calibration to clearly stipulate that the whole of the channel should be calibrated. Channel calibration following replacement, repair, or modification of the system was added to Sp ecification 4.4.a. This change is consistent with guidance given in ANSI 15.1-2007 Section 4 for surveillance testing of TS required systems.

Clarification wording added to address specifically the setpoints of the area and stack monitoring systems.

Channel calibration of the required channels for the vent ed fueled experiment (i.e. radiation monitoring and flow monitoring) are required prior to initial operatio n of the experiment to ensure operability and then annually in accordance with other similar surveillances of similar systems. Channel calibration following replacement, repair, or modification of the system was a dded to Specification 4.4.c. This change is consistent with guidance given in ANSI 15.1-2007 Section 4 for surveillance testing of TS required systems.

Setpoints for the vented fueled experiment exhaust gas radiation and flow monitoring required to be checked.

Channel checks of the radiation and flow monitors for vented fueled experiments shall be completed prior to use of the experiment. If the experiment is not going to be operated, then these checks are not required.

Channel check and test requirements were added to reflect the recommendations in NUREG 1537 Appendix 14.1 and ANSI 15.1-4.7.1 standards. Channel tests are made to be monthly in agreement with NUREG 1537 for radiation monitoring systems.

Bases were updated to reflect the additions to the TS. Ve nted fueled experiments were defined to be installed in the reactor when they are both in place and able to be used to provide clarity for the applicability of the respective TS.

Font size of TS 4.4 were updated to allow for cleaner formatting.

Line spacing adjustments were made to TS 4.4 to fit the text to Page 35.

21. TS 4.5 Confinement and Main HVAC and TS 4.6 Primary and Secondary Coolant:

Due to the added text in TS 4.4, TS 4.4, 4.5, and 4.6 were repaginated to appear on pages 35, 36, and 37.

Page numbers and text for TS 4.5 and 4.6 remain the same.

Attachment 2 [6-19-23]:

Technical Specifications Amendment 19 (Affected pages wit h change bars)

Appendix A

Technical Specifications for the

North Carolina State University

PULSTAR Reactor

Facility License No. R-120

Docket No. 50-297

Amendment No. 19

Date: June 19, 2023

Appendix A Amendment 19 Technical Specifications June 19, 2023

FIGURES

Figure 2.1-1: Power-Flow Safet y Limit Curve......................................................................... Figure 5.2-1: NCSU PULSTAR Reactor Site Map................................................................. Figure 6.1-1: NCSU PULSTAR Reactor Organizational Chart...............................................

TABLES

Table 3.2-1: Reactivity Limits for Experiments....................................................................... Table 3.3-1: Required Safety and Safety Related Channels..................................................... Table 3.5-1: Required Radiation Area Monitors...................................................................... Table 3.6-1: Required Main HVAC and Confinement Conditions...........................................

ii

Appendix A Amendment 19 Technical Specifications June 19, 2023

1.2.7 Control Rod: A control rod is a neutron absorbing blade having an in-line drive which is magnetically coupled and has SCRAM capability.

1.2.8 Excess Reactivity: Excess reactivity is that amount of reactivity that would exist if all control rods (and Shim Rod) were full y withdrawn from the point where the reactor is exactly critical (keff=1).

1.2.9 Experiment

Any operation, hardware, or target (excluding devices such as detectors, foils, etc.) that is designed to investigate non-routine reactor characteristics or that is intended for irradiation within the pool, on or in a beam tube or irradiation facility, and that is not rigidly secured to a core or shield structure so as to be a part of their design. Specific categories of experiments include:

a. Tried Experiment: Tried experiments are those experiments that have been previousl y performed in this reactor. Specifically, a tried experiment has similar size, shape, composition and location of an experiment previously approved and performed in the reactor.

b. Secured Experiment: A secured experiment is any experiment, experimental facility, or component of an experiment that is held in a stationary position relative to the reactor by mechanical means. The restraining forces must be substantially greater than those to which the experiment might be subjected by hydraulic, pneumatic, buoyant, or other forces which are normal to the operating environment of the experiment, or by forces which can arise as a result of credible malfunctions.

c. Non-Secured Experiment: A non-secured experiment is an experiment that does not meet the criteria for being a secured experiment.

d. Movable Experiment: A movable experiment is one where it is intended that all or part of the experiment may be moved in or near the core or into and out of the reactor while the reactor is operating.

e. Fueled Experiment: A fueled experiment is an experiment which irradiates fissile material. Fueled experiments exclude the following:

i. Fissile material not subjected to neutron fluence ii. Detectors containing fissile material iii. Sealed sources iv. PULSTAR reactor fuel used in operation of the reactor.

1.2.10 Experimental Facilities: Experimental facilities are facilities used to perform experiments. They include beam tubes, thermal columns, void tanks, pneumatic transfer systems, in-core facilities at single-assembly positions, out-of-core irradiation facilities, and the bulk irradiation facility.

Appendix A Amendment 19 Technical Specifications June 19, 2023

3.5 Radiation Monitoring Equipment

Applicability This specification applies to the availability of radiation monitoring equipment which must be operating during reactor operation.

Objective To assure that radiation monitoring equipment is available for evaluation of radiation conditions in restricted and unrestricted areas.

Specification The reactor or vented fueled experiment shall not be operated nor shall irradiated fuel or irradiated fueled experiments that are not contained in a properly sealed and approved shipping container be moved within the reactor building unless the radiation monitoring equipment listed below and in Table 3.5-1 is operating.(1)(2)(3)(7)

a. Three fixed area monitors operating in the Reactor Building with their setpoints as listed in Table 3.5-1.(1)(3)(4)

b. Stack particulate and stack gas building exhaust monitors continuously sampling air in the facility exhaust stack with their setpoints as listed in Table 3.5-1.(1)(3)(4)

c. The Radiation Rack Recorder.(5)

d. Vented fueled experiment exhaust gas radiation monitor continuously monitoring the experiment exhaust gas.(7)

e. Vented fueled experiment flow rate monitor continuously monitoring the experiment exhaust gas flow.(7)

Table 3.5-1: Required Radiation Area Monitors Monitor Alert Setpoint Alarm Setpoint Control Room 2 mR/hr 5 mR/hr Over-the-Pool 5 mR/hr 100 mR/hr West Wall 5 mR/hr 100 mR/hr Stack Gas 1000 Ar-41 AEC(6) 5,000 Ar-41AEC(6)

Stack Particulate 1000 Co-60 AEC(6) 5,000 Co-60 AEC(6)

(1) For periods of time, not to exceed ninety days, for maintenance to the radiation monitoring channel, the intent of this specification will be satisfied if one of the installed channels is replaced with a gamma-sensitive instrument which has its own alarm audible or observable in the control room. Refer to SAR Section 5.

Appendix A Amendment 19 Technical Specifications June 19, 2023

(2) The Over-the-Pool Monitor may be bypassed for less than two minutes during return of a pneumatic capsule from the core to the unloading station or five minutes during removal of experiments from the reactor pool. Refer to SAR Section 5.

(3) Stack Gas and Particulate are based on the AEC quantities present in the ventilation flow stream as it exits the stack. Refer to SAR Section 10 for setpoint bases for the radiation monitoring equipment.

(4) May be bypassed for less than one minute immediatel y after starting the pneumatic blower system.

(5) During repair and/or maintenance of the recorder not to exceed 90 days, the specified area and effluent monitor readings shall be recorded manually at a nominal interval of 30 minutes when the reactor is not shutdown. Refer to SAR Section 5.

(6) Airborne Effluent Concentrations (AEC) values from 10 CFR Part 20 Appendix B, Table 2.

(7) Monitors for vented fueled experiments are only required to be operating while the experiment is in operation.

Bases

A continued evaluation of the radiation levels within the Reactor Building will be made to assure the safet y of personnel. This is accomplished by the area monitoring system of the type described in Section 5 of the Safet y Analysis Report (SAR).

Evaluation of the continued discharge air to the environment will be made using the information recorded from the stack particulate and stack gas monitors.

When the radiation levels reach the alarm setpoint on any single area, or stack exhaust monitor, the building will be automatically placed in confinement as described in SAR Section 5.

To prevent unnecessary initiation of the evacuation confinement system during the return of a pneumatic capsule from the core to the unloading station or during removal of experiments from the reactor pool, the Over-the-Pool Monitor may be bypassed during the specified time interval. Refer to SAR Section 5.

Stack gas and stack particulate setpoints are based on the Notification of Unusual Event Emergency Action Level (EAL) for potential released nuclides including Ar-41, Co-60, and fission products. Fission product AEC values are higher than those for Ar-41 and Co-60. Therefore, using Ar-41 and Co-60 AEC for the setpoints is conservative.

Appendix A Amendment 19 Technical Specifications June 19, 2023

3.6 Confinement and Main HVAC Systems

Applicability

This specification applies to the operation of the Reactor Building confinement and main HVAC s ystems.

Objective The objective is to assure that the confinement system is in operation to mitigate the consequences of possible release of radioactive materials resulting from reactor operation.

Specification The reactor shall not be operated nor shall irradiated fuel or irradiated fueled experiments that are not contained in a properly sealed and approved shipping container be moved within the reactor building unless the following equipment is operable, and conditions met:

Table 3.6-1: Required Main HVAC and Confinement Conditions Equipment/Condition Function

a. All doors, except the Control To maintain reactor building Room, and basement corridor negative differential pressure (dp).(1) entrance: self-latching, self-closing, closed and locked.

b. Control room and basement To maintain reactor building corridor entrance door: self-negative differential pressure.(2) latching, self-closing and closed.

c. Reactor Building under a negative To maintain reactor building differential pressure of not less than negative differential pressure with 0.2" H 2O with the normal reference to outside ambient.(3) ventilation system or 0.1" H2O with one confinement fan operating.

d. Confinement system Operable(4)(5)(7)

e. Evacuation system Operable(6)

(1) Doors may be opened by authorized personnel for less than five minutes for personnel and equipment transport provided audible and visual indications are available for the reactor operator to verify door status. Refer to SAR Section 5.

(2) Doors may be opened for periods of less than five minutes for personnel and equipment transport between corridor area and Reactor Building. Refer to SAR Section 5.

Appendix A Amendment 19 Technical Specifications June 19, 2023

(3) During an interval not to exceed 30 minutes after a loss of dp is identified with Main HVAC operating, reactor operation may continue while the loss of dp is investigated and corrected. Refer to SAR Section 5.

(4) Operability also demonstrated with an auxiliary power source.

(5) One filter train may be out of service for the purpose of maintenance, repair, and/or surveillance for a period of time not to exceed 45 days. During the period of time in which one filter train is out of service, the standby filter train shall be verified to be operable every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months if the reactor is operating with the Reactor Building in normal ventilation.

(6) The public address s ystem can serve temporarily for the Reactor Building evacuation system during short periods of maintenance.

(7) When the radiation levels reach the alarm setpoint on any single area, or stack exhaust monitor, listed in Table 3.5-1, the building will be automatically placed in confinement as described in SAR Section 5.

Bases

In the event of a fission product release, the confinement initiation system will secure the normal ventilation fans and close the normal inlet and exhaust dampers.

In confinement mode, a confinement system fan will: maintain a negative pressure in the Reactor Building and insure in-leakage only; purge the air from the building at a greatl y reduced and controlled flow through charcoal and absolute filters; and control the discharge of all air through a 100 foot stack on site.

Section 5 of the SAR describes the confinement system sequence of operation.

The allowance for operation under a temporary loss of dp when in normal ventilation is based on the requirement of having the confinement system operable and therefore ready to respond in the unlikely event of an airborne release.

Appendix A Amendment 19 Technical Specifications June 19, 2023

3.8 Operations with Fueled Experiments Applicability

This specification applies to the operation of the reactor with any fueled experiment.

Objective

The objective is to prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure.

Specifications

Fueled experiments may be performed in experimental facilities of the reactor with the following conditions and limitations:

a. T he fi ssi on rat e for fueled experiments is limited to 2x109 fission/sec.

b. Specification 3.7 pertaining to reactor experiments shall be met with the exception that encapsulation is not required for vented fueled experiments, and vented fueled experiments may allow for the release of gaseous airborne activity. Vented fueled experiments shall be designed to prevent interaction with reactor components or pool water.

c. Each type of fueled experiment shall meet the following items:

i. Meeting license requirements for the receipt, use, and storage of fissile material.

ii. Physical form shall be solid or liquid.

iii. Limiting the thermal power generated from the fissile material for experiments within the pool water to ensure that the surface temperature of the experiment does not exceed the saturation temperature of the reactor pool water.

iv. Radiation monitoring for detection of released fission products at the exhaust of vented fueled experiments.

d. Credible failure of any fueled experiment shall not result in releases or exposures in excess of 10 percent of the annual limits established in 10 CFR Part 20.

Appendix A Amendment 19 Technical Specifications June 19, 2023

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Appendix A Amendment 19 Technical Specifications June 19, 2023

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Appendix A Amendment 19 Technical Specifications June 19, 2023

Bases

NUREG 1537 provides guidelines for the format and content of non-power reactor licensing. Guidelines on operating conditions and accident anal ysis for fueled experiments are given in NUREG 1537. These guidelines include (1) actuation of engineered safet y features (ESF) to prevent or mitigate the consequences of damage to fission product barriers caused by overpower or loss of cooling events, (2) use of ESF to control of radioactive material released by accidents, (3) radiation monitoring of fission product effluent and accident releases, (4) accidental analysis for loss of cooling or other experimental malfunction resulting in liquefaction or volatilization of fissile materials, (5) accident anal ysis for catastrophic failure of the experiment in the reactor pool or air, (6) accident anal ysis for insertion of excess reactivity leading to fuel melting, and (7) emergency plan activation and classification.

The limitations given in Specification 3.8 ensure that (1) fueled experiments performed in experimental facilities at the reactor prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure, (2) radiation doses to occupational personnel and the public and radioactive material releases are ALARA, (3) adequate radiation monitoring is in place, and (4) in the event of failure of a fueled experiment with the subsequent release of radioactive material, the resulting dose to personnel and the public at any location are well within limits set in 10 CFR Part 20.

Fueled experiments are reviewed, approved, and documented as required by Specifications 6.2.3 and 6.5. This includes (1) meeting license requirements for the receipt, use, and storage of fissile material, (2) limiting the amount of fissile material to ensure that experimental reactivity conditions are met and that radiation doses are well within 10 CFR Part 20 radiation dose limits following maximum fission product release from a failed experiment or vented release, and (3) limiting the thermal power generated from the fissile material to ensure that the surface temperature of the experiment does not exceed the saturation temperature of the reactor pool water.

Appendix A Amendment 19 Technical Specifications June 19, 2023

4.4 Radiation Monitoring Equipment

Applicability

This specification applies to the surveillance requirements for the area and stack effluent radiation monitoring and vented fueled experiment exhaust gas radiation and flow monitoring equipment.

Objective

The objective is to assure that the radiation monitoring equipment is operable.

Specification

a. Channel calibration of the area and stack monitoring s ystems shall be performed annuall y but at intervals not to exceed fifteen (15) months or after replacement, repair, or modification of the monitoring system.

b. The setpoints of the area and stack monitoring systems shall be verified weekly, but at intervals not to exceed ten (10) days.

c. Channel calibration of the vented fueled experiment exhaust gas radiation and flow monitors shall be performed prior to initial operation of the experiment and annually, not to exceed fifteen (15) months, thereafter while the experiment is installed in the reactor or after replacement, repair, or modification of the monitoring system(s).

d. The setpoints of the vented fueled exhaust gas radiation and flow monitors shall be verified weekl y, but at intervals not to exceed ten (10) days if the vented fueled experiment is installed in the reactor.

e. Channel checks shall be performed for the following:

i. Area and stack radiation monitors prior to first start of reactor operation of the day.

ii. Vented fueled experiment exhaust gas radiation monitor prior to first start of operation of the experiment of the day.

iii. Vented fueled experiment flow rate monitor prior to first start of operation of the experiment of the day.

f. Channel tests shall be performed monthly, but at intervals not to exceed six (6) weeks, for the following:

i. Area and stack radiation monitors.

ii. Vented fueled experiment exhaust gas radiation monitor if the vented fueled experiment is installed in the reactor.

iii. Vented fueled experiment flow rate monitor if the vented fueled experiment is installed in the reactor.

Appendix A Amendment 19 Technical Specifications June 19, 2023

Bases

These systems provide continuous radiation monitoring of the Reactor Building with a check of readings performed prior to and during reactor operations. Weekly verification of the setpoints in conjunction with the channel checks, monthly channel tests, and annual calibration is adequate to identify long term variations in the system operating characteristics. Vented fueled experiments shall be considered installed in the reactor when they are placed in the experiment location and operable.

4.5 Confinement and Main HVAC System Applicability

This specification applies to the surveillance requirements for the confinement and main HVAC s ystems.

Objective The objective is to assure that the confinement system is operable.

Specification

a. The confinement and evacuation s ystem shall be verified to be operable within seven (7) days prior to reactor operation.

b. Operability of the confinement system on auxiliary power will be checked monthly but at intervals not to exceed six (6) weeks.(1)

c. A visual inspection of the door seals and closures, dampers and gaskets of the confinement and ventilation systems shall be performed semi-annuall y but at intervals not to exceed seven and one-half (71/2) months to verify they are operable.

d. The control room differential pressure (dp) gauges shall be calibrated annually but at intervals not to exceed fifteen (15) months.

e. The confinement filter train shall be tested biennially but at intervals not to exceed thirty (30) months and prior to reactor operation following confinement HEPA or carbon adsorber replacement. This testing shall include iodine adsorption, particulate removal efficiency and leak testing of the fil ter housing.(2)

f. The air flow rate in the confinement stack exhaust duct shall be determined annually but at intervals not to exceed fifteen (15) months. The air flow shall be not less than 600 CFM.

Appendix A Amendment 19 Technical Specifications June 19, 2023

(1) Operation must be verified following modifications or repairs involving load changes to the auxiliary power source.

(2) Testing shall also be required following major maintenance of the filters or housing.

Bases

Surveillance of this equipment will verify that the confinement of the Reactor Building is maintained as described in Section 5 of the SAR.

4.6 Primary and Secondary Coolant Applicability

This specification applies to the surveillance requirement for monitoring the radioactivity in the primary and secondary coolant.

Objective

The objective is to monitor the radioactivity in the pool water to verify the integrity of the fuel cladding and other reactor structural components. The secondary water anal ysis is used to confirm the boundary integrit y of the primary heat exchanger.

Specification

a. The primary coolant shall be analyzed bi-weekl y, but at intervals not to exceed eighteen (18) days. The analysis shall include gross beta/gamma counting of the dried residue of a one (1) liter sample or gamma spectroscopy of a liquid sample, neutron activation anal ysis (NAA) of an aliquot, and pH and resistivity measurements.

b. The secondary coolant shall be anal yzed bi-weekly, but at intervals not to exceed eighteen (18) days. This analysis shall include gross beta/gamma counting of the dried residue of a one (1) liter sample or gamma spectroscopy of a liquid sample.

Bases

Radionuclide anal ysis of the pool water samples will allow detection of fuel clad failure, while neutron activation analysis will give corrosion data associated with primary system components in contact with the coolant. Refer to SAR Section 10.

The detection of activation or fission products in the secondary coolant provides evidence of a primary heat exchanger leak. Refer to SAR Section 10.

Appendix A Amendment 19 Technical Specifications June 19, 2023

[6-19-23]:

Technical Specifications Amendment 19 (affected pages clean copy)

Appendix A Amendment 19 Technical Specifications June 19, 2023

Appendix A

Technical Specifications for the

North Carolina State University

PULSTAR Reactor

Facility License No. R-120

Docket No. 50-297

Amendment No. 19

Date: June 19, 2023

Appendix A Amendment 19 Technical Specifications June 19, 2023

FIGURES

Figure 2.1-1: Power-Flow Safet y Limit Curve......................................................................... Figure 5.2-1: NCSU PULSTAR Reactor Site Map................................................................. Figure 6.1-1: NCSU PULSTAR Reactor Organizational Chart...............................................

TABLES

Table 3.2-1: Reactivity Limits for Experiments....................................................................... Table 3.3-1: Required Safety and Safety Related Channels..................................................... Table 3.5-1: Required Radiation Area Monitors...................................................................... Table 3.6-1: Required Main HVAC and Confinement Conditions...........................................

ii Appendix A Amendment 19 Technical Specifications June 19, 2023