IR 05000192/1989002
| ML18285A699 | |
| Person / Time | |
|---|---|
| Site: | 05000192, University of Texas at Austin |
| Issue date: | 07/13/1989 |
| From: | Chaney H, Murray B NRC Region 4 |
| To: | University of Texas at Austin |
| Shared Package | |
| ML18285A704 | List:
|
| References | |
| IR 1989002, IR 1989004, NUDOCS 8908010232 | |
| Download: ML18285A699 (18) | |
Text
APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-192/89-02 License: R-92 50-602/89-04 Construction Permit: CPPR-123 Dockets: 50-192 50-602 Licensee: University of Texas (UT)
College of Engineering Department of Mechanical Engineering Nuclear Engineering Programs Austin, Texas 78712 Facility Name: Docket 50-192: Nuclear Engineering Teaching Laboratory Taylor Hall (TRIGA Mark I)
Docket 50-602: Nuclear Engineering Teaching Laboratory Balcones Research Center (TRIGA Mark II)
Inspection At: Taylor Hall and Balcones Research Center, Austin, Travis County, Texas Inspection Conducted: May 31 through June 1, 1989 Inspectors: r/* *?;i f.Chaney, Senior Radiation Specialist Facilities Radiological Protection Section Accompanied By: Blaine Murray, Chief, Reactor Programs Branch Division of Radiation Safety and Safeguards Approved: ( y ?//
/.Baer, Chief, Facilities Radiological Date Protection Section Inspection SummarJ.
lection Conducted May 31 thro June__ _L__j 989 ( Reports 50-l 92/89-:-02_i 50-6U2/89-04)
Areas Inspected: Routine, announced, preoperational inspection of the licensee's radiation protection (RP), physical security, and emergency preparednes r programs; the installation and testing of radiological controls equipment at the Balcones Research Center TRIGA Mark II facility and the preparations being made for the defueling and transferring of the fuel and cobalt 60 irradiator from the Taylor Hall TRIGA Mark I facility to the Mark II f aci 1 it Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment . ..
Results: Within the areas inspected, no violations or deviations were identified. Ten new open items were identified during this inspectio Significant work remains to be completed regarding the areas reviewed during this inspection. Radiation monitoring instrumentation was being installed, calibration procedures were being developed, emergency preparedness supplies and instrumentation were being procured, and physical security equipment was being installed and teste Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment . ..
DETAILS Persons Contacted UT
- D. Klein, Director, Nuclear Engineering Teaching Laboratory (NETL)
- J. Howell, Chairman, Mechanical Engineering Department
- H. Marcus, Chairman, Nuclear Reactor Committee
- T. Bauer, Assistant Director, NETL
- 8. Bryant, Radiation Safety Officer
- Denotes attendance at exit interview on June 1, 198 . Licensee_Actions__to Previous I_ns_pection Findin__gs (Closed) Open Item (192/8802-01): Response Check of Pocket Dosimeters -
This item was previously discussed in NRC Inspection Report 50-192/88-02, and involved the licensee's lack of a pocket doimeter response check program that satisfied the guidance contained in NRC Regulatory Guide (RG) 8.4 concerning frequency of response checking. The NRC inspectors examined the licensee's draft pocket dosimeter rsponse check procedure (SRV-14.4) and surveillance matrix, and determi0d that the licensee's response check program satisfied the guidance contained in NRC RG (Closed) Open Item (602/8802-02): TRIGA Mark II Biological Shield Survey/Test - This item was previously discussed in NRC Inspection Report 50-602/88-02 and involved the NRC's concern over the licensee's development of a biological shield survey that incorporated the guidance contained in NRC RG 2.1 and ANSI/ANS-6.3.1-1980 (formally ANSI Nl8.9-1972). The NRC inspector examined the licensee's operational Acceptance Tests, part 6 .c, and found that the licensee had taken action to close this ite . Open_ __Items !dentified Du_ring _This _In SQection An open item is a matter that requires further review and evaluation by the NRC inspector. Open items are used to document, track, and ensure adequate follow-up on matters of concern to the NRC inspector. The following open items were identified:
Qpen Item Title See_ Para_g_ra.2_h 602/8904-01 Organization and Staffing 4 602/8904-02 Staff Qualifications and Training 5 Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment . ..
602/8904-03 Procedures, Audits, Reports and 6 Surveillances 602/8904-04 External and Interna 1 Radiatior 7 Exposure Control 602/8904-05 Radioactive Material (RAM) and 8 Contamination Control 602/8904-06 Radiation Protection Facilities 9 602/8904-07 liquid and Gaseous Effluents 10 602/8904-08 Emergency Preparedness 11 602/8904-09 Physical Security and Safeguards 12 192/8904-10 Taylor Hall Oefueling and Irradiator 13 Transfer 4. Balcone_s TRJ:GA_Mark II Facility_Staff_i_ng __and_.Ocganization The NRC inspector examined the licensee's organizational structure for agreement with the guidance contained in RG 2.2 and industry standard ANSI/ANS-15.1-1982; and licensee's commitments contained in the September 1984, Safety Analysis Report (SAR) Sections 9.1 and 9.4.2, and Sections 11, 12, and 13 of NRC NUREG-1135, "Safety Evaluation Report (SER)
related to the construction permit and operating license for th research reactor at The University of Texas;" and the draft Technical Specifications (TS) dated August 14. 198 The NRC inspector determined that the licensee had hired a new director for the Balcones NETL TRIGA Mark II facility (Balcones facility). The new director has previous research reactor management experience. The current two-man staff at the Balcones facility will be increased by adding an additional licensed operator, instrument technician, and a health physicist (HP). The licensee iL experiencing difficulty in hiring a suitably experienced HP. The NRC inspector discussed, with the assistant director of the NETL, the NRC's concern over the reporting chain-of-command for the Balcones HP in relation to the UT Radiation Safety Office. The NRC inspectors discussed, with the assistant director and the director of the NETL, the need to ensure that the HP 1 s activities were not governed exclusively by operational/research pressures and goal The NRC inpector noted that several key RP programs and implementing procedures are awaiting completion due to the lack of a facility staff H Due to the large size and complexity of the Balcones facility, the lack of a full time HP available to or on the Balcones facility staff, will be considered an issue to be resolved prior to issuance of a facility operating licens Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment The NRC inspector also pointed out to licensee representatives, the confusion presented in the draft TS, SER, and the SAR concerning the title of the Balcones facility oversight group (four different titles given).
The licensee stated that documents should reflect the Nuclear Reactor Committee for the title of the oversight group, which is also the TS referenced titl This area is considered an C!P._r:1 item (602/8904-01) pending the hiring of a full time staff HP for the Balcones Research Cente No violations or deviations were identified.
5. Balcones Facili!_y_Staff Qualifications___and Traini The NRC inspector examined the licensee's staff qualifications and staff training programs to determine agreement with the requirements contained in 10 CFR Parts 19.12 and 20.206, and the guidance contained in industry standard ANSI/ANS-15.4-1977, and Sections 8.2.5 and 10.1.5 of the SA The NRC inspector determined that the licensee had not completed development of training programs for the Balcones facility staff other than licensed operators. The NRC inspector discussed, with the assistant director of the NETL, the requirements of 10 CFR Parts 19.12 and 20.206 concerning RP training of personnel authorized unescorted access to radiologically restricted areas of NRC licensed facilitie This area is cons i dered an QB item (602/8904-02) pending licensee:
Development of staff and facility user training that impleents the requirements of 10 CFR Parts 19.12 and 20.20 No violations or deviations were identified.
6. Procedure?._LAudits.0orts ,__ and __Survei 11 ances The NRC inspector examined the licensee's procedures and surveillance schedules for the Balcones facility to determine agreement with the requirements of the draft TS, and agreement with the commitments contained in Sections 8.3, 8.4, and 10 of the SAR and Sections 11, 12. and 13 of the SER. The licensee had finalized nearly all required implementing procedures needed to support the RP program as described in the SAR and SER. Attachment 2 to this report lists the procedures reviewe The licensee's procedures are contained in the Orerations Manual which is comprised of two parts (Procedures and Information). The Procedures Section is comprised of six procedural areas: 1) Special Conditions (SPCL); 2) Administrative Activities (ADM); 3) Reactor Operations (OPR); 4) Surveillance Actions (SRV); S) Experiments (EXP); and 6) Miscellaneous Laboratory Procedures and General Rule Summary (MISC).
ADM-1.0 establishes control ovtr procedure development, change, review, and approva 1 .
Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment The NRC inspector discussed with the licensee the need to include more details in the procedures that implement the RP program. The NRC inspector found that radiological instrument calibration procedures (licensee and vendors), for the most part, did not contain enough detailed instructions to ensure that instruments can detect radiation or radionuclides at the levels specified by the TS and/or committed to in the SAR and SER. None of the calibration procedures had been verified at the time of this inspection. Several QPR and SRV procedures (OPR-3.0, 11 Air Confinement System Operation;" OPR-9.0, 11 Movement of Fuel Elements or Control Followers;" SRV-1.0, 11 Facility Equipment;" SRV-4.0, "Fuel Inspection and Measurement;" SRV-13.0, "Air Confinement System Surveillance;" and SRV-14.0, "Radiation Monitoring Systems") did not include radiation exposure controls (v-4.0), definitie instructions as to what response range is acceptable f, r ;quired RP instrumentation (OPR-9.l and SRV-3.0), quality control equ1. 'rnents (SRV-1.0), or quantitative values for limiL :rl tolerances ;sRV-1.0, 13.0, and 14.0).
Overall, many ADM, SRV, and QPR pr0ceau,. di not contain sufficient i
detail to ensure that the user cou)d complete the tasks in an acceptable manne The licensee had established a matrixed schedule of TS, Emergency Plan (E-Plan), and Physical Security Plan surveillance This is considered an C?l2__n item (602/8904-03) pending:
(ompletion of RP program implementing procedure Providing more detaied gl'ic:a11ce for procedures involving RP activitie No violations or deviations were identified.
7. Externa 1 and J.nterna 1 Exposure _Contra 1 s The NRC inspector reviewed the licensee's program for administration and control of personnel exposure to external (whole body and extremity) and internal radiation to determine agreement with the requirements of 10 CFR Parts 20.101, 20.103, 20.202, and 20.203; and agreement with the commitments contained in Sections 8.5.1 and 10.3 of the SAR, and Section 12.5 of the SER, and the guidance contained in NRC Inspection and Enforcement Information Notices (IEIN) 81-26 and 83-5 The NRC inspector examined the licensee's procedures for the administration of the Balcones facility dosimetry program (ADM-7.0 and SRV-14.1) and found them to lack enough specific information. The procedures need to be expanded to include more information. The licensee had not evaluated the suitability of their current personnel neutron dosimetry (film) for accurately measuring the expected neutron spectrum at the Balcones facility. This concern was previously discussed in NRC Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment Inspection Report 50-602/88-02 and is being tracked as Open Item 602/8802-01. Procedures were not available for review that specified the radiological controls and radiation exposure controls to be used during beam port experiments. None of the licensee's RP procedures address issuance and use of extremity dosimetry, or the eva1udLion and placement of multiple whole body dosimetry when personnel are in nonuniform gamma/neutron radiation field The licensee's dosimetry program is accredited in accordance with the requirements of 10 CFR Part 20.202(c).
Procedure ADM-7.0, "Radiation Protection - Personnel," references the need to periodically review exposure records to insure agreement with good ALARA principles. Procedure ADM-7.0 appears to be an after-the-fact ALARA approach instead of reviewing planned work activities to ensure that ALARA practices are utilized to reduce personnel exposure The licensee does not expect any significant airborne radioactivity during normal operation of the facility. The licensee will be continuously monitoring the facility environs for particulate airborne radioactivity, and the exhaust ventilation/purge system effluent for Argon 41 gas (Sections 11.2.2 and 12.6.1 of the SER).
This area is considered an 9_pen item (602/8904-04) pending:
Completion of personnel dosimetry program imp1centing procedure Implementation of the guidance cor i ained in NR: ltINs 81-26 and 83-59 into the personnel dosimety and exposure control progra Resolving Open Item 602/8802-01 concerning personnel neutron dosimetr Development of a proper ALARA progra No violations or deviations were identified.
8. Radioactive Material and Contamination Control_ and MonitoriQ_g The NRC inspector examined the licensee's inventory of RP instruments, operating procedures; held discussions with the facility assistant director to determine the status ot kAM and contamination control programs and RP instrument procurement and calibration; and examined the methods to be routinely employed to monitor the facility, support systems, and miscellaneous equipment for radiation and contamination. SAR Sections 6.3.l and 10 and SER Section 12 contain licensee commitments concerr i ng the above noted program The licensee's task matrix indicated that radiological surveys will be periodic .. 11v performed on either d quarterly or semiannual basis, but no Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment detailed procedures or survey maps were available. The licensee's surveys included alpha and beta/gamma contamination surveys and area beta/gamma radiation surveys.
Portable dose rate measurement and counting room equipment were not available for examination during this inspection. The NRC inspector noted that the licensee's inventory does not include a portable high range (5-50 rem/hour) ion chamber type dose rate instrument. The NRC inspector discussed with the licensee the need to ensure that the RP instrument inventory at the Balcones facility does not include instruments that are also utilized to meet the E-Plan instrument inventory for the Taylor Hall facility.
The NRC inspector discussed with the facility assistant director the methods to be employed to monitor for contamination on personnel exiting the reactor/experimentation areas and the methods to be used to analyze smear and airborne samples. The NRC inspector expressed concern 1) over the licensee's proposal to utilize a hand held beta/gamma radiation instrument to perform personnel contamination surveys and 2) that swipes and air samples would be analyzed utilizing beta liquid scintillation methods. The NRC inspector discussed with the licensee the advantages of using automated personnel friskers and high efficiency automated alpa/beta proportional laboratory counters for swipe and air sample analysis.
The NRC inspector determined that the licensee's calibration procedures for portable, fixed, and laboratory instruments were in draft form and did contain sufficient instructions to meet the criteria in ANSI N323-1978 concerning portable instrument calibration source selection and identification, before and after checks, establishment of a periodic response check value, and documentation of results. Current procedures do not provide for the establishment of alarm setpoints and the periodic verification of these set points. Procedure SRV-14 (draft) indicates that semiannual calibrations can span as much as 15 months between calibrations whichisriot in agreement with industry practices. This same procedure referenced a vendor operating manual for use in calibrating the airborne Argon-41 radioactivity monitor. The above procedure did not provided for the verification that the monitor would detect a minimum detectable concentration of 2 x 10 * microcuries per milliliter of Argon-41 airborne gaseous radioactivity as referenced in vendor literature.
The NRC inspector noted that certain fixed area radiation monitors, especially those adjacent to the beam ports, were not located in a good position to provide accurate information concerning radiation levels from the beam ports. The facility assistant director stated that the positioning of several monitors would be reevaluated when beam port work/experiments were undertaken and, if necessary, detector cables would be extended to allow better positioning of the detectors so that gamma dose rates attributable to the beam port would be better known by experimenters and control room personnel. The NRC inspector noted that Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment the TRIGA Mark II reactor Data Acquisition and Control unit allows for additional reactor shutdown signals to be inputted, such as from beam port shield position indicators or area radiation monitor setpoints. The NRC inspector discussed the need to ensure that operational and experimental procedures (especially beam port experiments) reference the deficiencies in area radiation detector positioning. The licensee had not completed operational or calibration procedures for the airborne radioactive particulate monitor installed on the upper level of the reactor ba This area is considered an opn item (602/8904-05) pending:
Completion of RP instrument procurement, including portable high range dose rate monitoring instrumen Completion of instrument operating nd calibration procedure Incorporation into procedures, warnings concerning limitations of the fixed position area radiation monitoring yste Evaluation of current practices for survey f ng of peronnel for contamination and the qualitative and quantitative analysis of swipes and air sdrnple No violations or deviations were identified.
9. Radiaio11 rrite_ction Facili_ties at thP Balc_ones Fility The NRC inspector examined the licensee's Balcones facility for agreement with the description, construction, and equipment placement as described in Sections 3.4.9.4, 5.2, 6.2, 6.2.2, 6.3.l, 6.4.2, 6.4.3, 10.l.4, and 10.2.1 of the SAR, and Sections 3.0, 5.1, 5.3, 6.2, 9.3, 9.6, 10.3, 11.2.2, and 12.6 of the SE Due to the size and complexity of the Balcones facility, the licensee's program for control of byproduct and RAM was examined to determine agreement with the criteria contained in NRC Inspection Manual Part 9900:
11 10 CFR Part 50, By-product Material Produced in Non-Power Reactors, 11 dated August 23, 1988; NRC Memorandum, 0. Crutchfield to NRC Regional Offices, Subject: Regulatory Responsibilities for By-Product Materials in Non-Power Reactors, 11 dated March 8, 1988; and NRC Inspection and Enforcement Manual Chapter 2882, "Transfer of NRC License Files to Agreement State(s), 11 dated December S, 198 The licensee indicated that the boundary for byproduct and reactor associated RAM would be the reactor bay on the first and second floors of the Balrones facility, and the reactor control room and associate rooms on the third floor, adjacent to the reactor bay. Facility room numbers had not been assigned as of this inspection. The remainder of the facility Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment (west of the east stairway alcove on the third floor, and all areas other than the reactor bay on the remaining floors) would come under the Texas State Bureau of Radiation Health jurisdiction (10 CFR Part 150 Agreement State).
The reactor coolant purification and tooling system was evaluated to determine agreement with the guidance contained in NRC Bulletin 80-10,
"Contamination of Nonradioactive System and Rsulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment." The NRC inspector examined the procedure (OPR-2.0) and engineered features (valve isolation and differential pressure) designed to prevent cross-contamination of the closed loop chilled water supply (this is also isolated from facility potable water). The NRC inspector discussed with the licensee the need to ensure that the makeup water hookup is procedurally controlled and periodic verifications are performed to verify that the system is properly isolated or disconnected when not required for makeup purposes. "Primary coolant" to secondary coolant {chilled water)
cross-contamination via the heat exchanger will be adequately controlled by differential pressure (greater than one pound per-square-inch more pressure on clean side than "primary" side), pressure alarms, and procedural controls. The licensee stated that the reactor coolant and purification system drawings in Figure 5.1 of the SER will be revised to depict as built conditions.
The licensee 1 s filtered exhaust ventilation sytem installation and preoperational testing was examined for agreement with the guidance in NRC RG 1.52, 11 Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants.11 Although RG 1.52 does not address research reactor ventilation systems, it can be used for general guidance in assuring that the Balcones facility 1 s high efficiency filtration (HEPA) system is satisfactorily installed. The Balcones facility filtered ventilation system and argon purge system are designated engineered-safety-systems in Section 6 of the SER. Current 1 icensee startup testing schedule includes isolation signal and valve testing, and balancing of exhaust and supply ventilation systems for contamination and airborne radioactivity control in various facility areas, but does not include inplace inspection and testing of the HEPA filter system. The NRC inspector discussed with the licensee the need to provide suitable assurance that the filtration system is properly installed and will filter particulates as intended, and that the guidance concerning the design, construction, and testing of filter units as contained in industry standards ANSI/ASME N509-1975 and NSl0-1975 (referenced by RGs 1.52 and 1. 140) should be utilized. The licensee stated that the ventilation system diagrams in Figures 6-7 and 6-P f the SAR will be revised to depict changes and as-built conditions.
The NRC inspector discussed with the licensee the methods to be utilized in communicating between the reactor control room and experimental areas within the reactor bay. Section 9.3 of the SER references an intercom Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment system, but the licensee has not decided on whether portable radios or a hard wired intercom system will be used. Currently, only a one way (control room and administrative office initiated) phone paging system is availabl The control room, instrument and electronic maintenance room, auxiliary support system room, filtered ventilation room, coolant purification room, radiological counting room, radioactive waste collection room, administrative offices, class rooms, and sanitary facilities were examine This area is considered an open item (602/8804-06) pending:
lnplace inspection and testing of the HEPA filtration uni Addressing of positive reactor coolant makeup source isolation in operational procedure Development of a byproduct/RAM control and inventory progra Installation of suitable two way communications between the reactor control room and the lower level of the reactor ba No violations or deviations were identified.
10. Solid__ Radioac tive Waste , Li_g__uid , __and Gaseous _Eff luents The NRC inspector examined the licensee's radioactive waste and effluent control programs to determine compliance with the requirements of the draft TS and 10 CFR Parts 20.106, 20.301, and 20.303; and agreement with the commitments contained in Section 6.3.1 of the SA Liquid and gaseous effluent controls were reviewed. The reactor will not routinely generate any liquid effluents other than accidental spills of reactor coolant. These liquids will be disposed of in accordance with 10 CFR Parts 20.301 and 20.303 requirements. All other effluents will be generated from byproduct sample preparation and analysis areas and will be collected in a specially designed liquid waste system located on the first level of the facility (Section 6.3.1 of the SAR). The liquid radioactive waste system will be under Agreement State jurisdiction. Gaseous effluents due to reactor operation are extensively discussed in Sections 6.3.1 and 6.5 of the SAR, and Section 11.2.3 of the SER and are expected to be significantly below 10 CFR Parts 20.103 and 20.106 limits for restricted and unrestricted areas. Quarterly calculations of Argon-41 and particulate radioactivity releases will be performed by the licensee to verify conformance with TS requirements on gaseous release limit Neither of the continuous airborne monitors (CAMs) for particulate or Argon-41 are installed and operational (Sections 6.2 of the SAR and SER).
Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment The particulate CAM is instrumental in initiating a reactor bay ventilation isolation signal, but current draft procedures do not address setting of signal alarm setpoints or how to derive the Radioactive waste disposal and shipments will be handled by the UT Radiation Safety Office under the Agreement State licens This area is considered an p item (602/8804-07) pending:
Installation and calibration of the particulate and Argon-41 CAM No violations or deviations were identified.
11. Emergency Prepfaredness The licensee's emergency preparedness program was examined to determine compliance with 10 CFR Parts 50.54(q) and (r}, and the Emergency Plan (E-Plan) dated September 1984 (submitted to the NRC on November 9, 1984).
Currently, the licensee's E-Plan is being carried as an open item in Section 1.5 of the SER due to lack of implementing procedures and letters of agreemen The licensee had not initiated familiarization training of personnel expected to respond to emergencies at the Balcones facility (police, medical/rescue, and fire).
The NRC inspector determined that the licensee had developed and issued E-Plan implementing procedures (SPCL-1.0 and 2.0) that provide for a emergency recall list, organizational development, and emergency response to reactor accidents at the Balcones facilit The NRC inspector discussed with the licensee the need to conduct a full scale exercise (scenario to involve police, fire, medical, and UT Radiation Safety Office personnel) of the Balcones facility E-Plan prior to bringing spent fuel to the facility. At the exit meeting, the licensee agreed to performing a full scale exercise of the Balcones facility E-Pla The licensee had not completed procurement and stocking of E-kits at the Balcones facility at the time of this inspection. The equipment list in Procedure SPCL-2.2 appeared to included instruments currently being used to satisfy Taylor Hall (TRIGA Mark I facility) emergency preparedness requirements. See paragraph 8 of this report concerning RP instrument The licensee had not completed procurement and stocking of E-Kits for the Balcones facilit Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment This area is considered an _op_ Hem (602/8904-08) pending:
Familiarization training for E-Plan support agencie Procuring and stocking the Balcones facility E-Kit Conducting a full scale E-Plan exercis Completion of all letters of agreement with supporting agencie No violations and deviations were identified.
12. Physical_Security The NRC inspector reviewed the censee's Balcones facility for agreement with the NRC approved Physical Security Plan (PSP) for the Balcones facility dated August 14. 1989. The material discussed in this paragraph is considered Proprietary Information and is reported in Attachment 1 to this repor No violations or deviations were identified.
13. T_ay .1°-.! 1,_aJ _F.ueJ __ _n_q _ o_b] t _6_Q_ Ir:rd iator __ Mov_erTJe nt The NRC inspector discussed with the facility assistant director, the preparations for defueling, fuel transfer, and cobalt 60 irradiator transfer to the Balcones facility from the Taylor Hal The NRC inspector toured the Taylor Hal 1 facility ind observed reactor and associated equipment status. The NRC inspector noted that the handling tool for the cobalt 60 irrauiator sources (ection 6.4.3 of the SAR) was broken. The NRC inspector discussed with the licensee the need to ensure that the cobalt 60 source handling tool would adequately hold on to sources as they are removed from the reactor and placed into suitable shieldin The NRC inspector also discussed with the licensee the preparations being made for removal and transfer of the TRIGA Mark I fuel elements to the Balcones facility. The procedures for this work are in early draft form and will be reviewed by the NRC at A later date prior to start of the defuelin This area is considered an open item (192/8804-10) pending:
Development of TRIGA Mark I defueling and transfer procedure Development of TRIGA Mark I facility Cobalt 60 irradiator transfer procedure and repair of handling too Conducting training for all personnel involved in fuel and source handling/transfe No violations or deviations were identifie Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment . Exit Interview The NRC inspector met with the licensee representatives identified in paragraph 1 of this report at the conclusion of the inspection on May 1, 1989. The NRC inspector summarized the inspection findings. The licensee committed to the following:
Conducting a full scale exercise of the Emergency Plan with scenario development to include police, fire, medical, and RP agencie Conducting a full lockdown of the Balcones facility to verify the ability to control access to physical security area Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment ..
- ,t ATTACHMENT
-* - --2 TO NRC INSPECTION REPORTS 50-192/89-02 50-602/89-04 DOCUMENTS REVIEWED TITLE REVISION DATE NUREG-1135, Safety Evaluation Report 00 05-85 Safety Analysis Report, University of Texas 00 09-84 Technical Specifications DRAFT 11-84 Emergency Plan DRAFT 09-84 Physical Security Plan 00 08-14-85 Special Nuclear License (SNM) 180 01 05-08-89 Balcones Research Center, TRIGA Mark II Operations Manual 00 04-88 SPCL-1.0, Emergency Call List 00 10-87 SPCL- Telephone Threat 00 10-87 SPCL-1.2, Facility Access List 00 04-88 SPCL-2.0, Emergency Response 00 05-87 SPCL- Emergency Classification 00 04-88 SPCL- Emergency Equipment & Supplies 00 04-88 SPCL-3.0, Physical Security 00 05-87 SPCL-3.1, Security Classification 00 10-87 SPCL-3.2, SNM Inventory Estimate 00 04-88 Administrative Procedures ADM-1.0, NETL Procedure Outline and Control 00 04-88 ADM-4.0, Personnel Qualifications 00 04-88 ADM-5.0, Experiment Authorization 00 07-88 ADM-7.0, Radiation Protection - Personnel 00 10-88 AOM-8.0, Radiation Protection - Material 00 10-88 AOM-10.0, Emergency Response 00 10-88 AOM-11.0. Physical Security 00 10-88 O_peration _Procedure_s OPR-1.0, Operation Support Systems 00 04-88 OPR-2.0, Pool Water System Operation 00 10-88 OPR-3.0, Air Confinement System Operation 00 10-88 OPR-3.1, Reactor Room HVAC System Operation 00 10-88 OPR-3.2, Argon Purge System Operation 00 10-88 Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment **
Attachment 2 -2-TITLE REVISION
- **-* --******---*-,,-* DATE OPR-3.3, Abnormal Conditions 00 10-88 OPR-9.0, Movement of Fuel Elements 00 10-88 OPR-10.0, Movement of Experiment Facility 00 10-88 Surveillance Procedures SRV-1.0, Facility Equipment DRAFT SRV-2.0, Rod Urive Inspection, Maintenance 00 10-88 SRV-3.0, Control Rod Inspection, Maintenance 00 10-88 SRV-4.0, Fuel Inspection and Measurement 00 10-88 SRV-12.0, Pool Water System Surveillance 00 10-88 SRV-13.0, Air Confinement System Surveillance 00 10-88 SRV-14.0, Radiation Monitoring System DRAFT SRV-14.1, Personnel DRAFT SRV-14.2, Area DRAFT SRV-14.3, Paticulate DRAFT SRV-14.4, Arqon-41 DRAFT SRV-14.5, Survey Meters DRAFT Miscellaneous
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Laboratory
- *---- -* .. . .. ... - -* *-*- . .-.,---, *- * ,.
Procedures MISC-1.0, Alpha/Beta Proportional Counter DRAFT MISC-2.0. Ge Gamma Spectroscopy DRAFT Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment I July 13, 1989 In Reply Refer to:
Dockets: 50-192/89-02 50-602/89-04 University of Texas College of Engineering Department of Mechanical Engineering Nuclear Engineering Program ATTN: Bernard W. Wehring, Director Nuclear Engineering Teaching Laboratory Austin, Texas 78712 Gentlemen:
This refers to the inspection conducted by Mr. H. D. Chaney of this office during the period May 31 through June l, 1989, of activities authorized by NRC Facility License R-92 and Construction Permit CPPR-123 for the University of Texas facilities located at Taylor Hall and the Balcones Research Center, and to the discussion of our finding5 with you and other members of the University staff at the conclusion of the inspectio Areas examined during the inspection included the radiation protection, physical security, and emergency preparedness programs; and associated equipment installation and testing. We also reviewed your preparations for defueling, fuel transfer, and the cobalt 60 irradiator transfer from the Taylor Hall to the Balcones facility. Within these areas, the inspection consisted of selective examination of representative records, interviews with personnel, and observations by the NRC inspector. The inspection findings are documented in the enclosed inspection repor In accordance with 10 CFR Part 2.790(d), the documentation enclosed concerning your Physical Security Plan (Attachment 1) is exempt from public disclosur Therefore, Attachment 1 will not be placed in the Public Document Roo Within the scope of the inspection, no violations or deviations were identified.
e,080,AD2OC2K 090113 05000192 Pt F'[IC Q
RIV:FRPS C:FRPS C:RPB D:DRSS C:TPS D:ORP
- HDChaney/hdc *REBaer *BMurray *ABBeach *WCSe1dle *JLMi 1 hoan
/ /89 / /89 / /89 I /89 I /89 I /89
- Previously Concurred Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment I niversity of Texas Should you have any questions concerning this inspection, we will be pleased to discuss them with yo
Sincerely, Original signed by:
P. Gwynn, for :
James L. Milhoan, Director Division of Reactor Projects Enclosures:
1. Appendix - NRC Inspection Report 50-192/89-02 50-602/89-04 2. Attachment 1 - Proprietary Information 3. Attachment 2 - Documents Reviewed cc w/all enclosures:
University of Texas College of Engineering Department of Mechanical Engineering Nuclear Engineering Program ATTN: Tom L. Bauer, Supervisor Reactor Operations Nuclear Reactor Laboratories Austin, Texas 78712 cc w/enclosures 1 and 3:
Auburn Mitche11 Office of the Governor P.O. Box 12428 Austin, Texas 78711 Texas Radiation Control Director bee w/enclosures l & 3: 0MB (IEOl)
A. Adams, NRR Project Manager *DRP Lisa Shea, RM/ALF *MIS Coordinator
- RSTS Operator *DRS bee w/all enclosures:
R. Martin 8. Beach B. Murray R. Baer 0. Chaney RPB/DRSS RIV File
- w/766 Enclosure contains PROPRIETARY INFORMATIO Decontrolled when separated from attachment.