ML20071K153

Forwards Responses to Formal Questions Developed by NRC Staff & LANL Review Team, Per 820409 Request

ML20071K153
Person / Time
Site:	05000083
Issue date:	04/23/1982
From:	Diaz N FLORIDA, UNIV. OF, GAINESVILLE, FL
To:	John Miller Office of Nuclear Reactor Regulation
References
NUDOCS 8204270483
Download: ML20071K153 (57)

Text

NUCLEAR FACILITIES DIVISION COLLEGE UNIVERSITY OF FLORIDA

', OF DEPARTMENT OF NUCLEAR ENGINEERING SCIENCES

. 102 NUCLEAR REACTOR BUILDING

'. ENGINEERING GAINESVILLE, FLORIDA 32611 AREA CODE 904 PHONE 392-1429 April 23, 1982 Office of Nuclear Reactor Regulation to U.S. Nuclear Regulatory Commission d D Washington, D.C. 20555 O 1 Attention: James R. Miller, Chief MO Standardization and Special Projects Branch .

[ APR 27 jgg [8 Division of Licensing [ glaam my albeiE ar. nag gg  %

Re: University of Florida Training Reactor \ 8 Facility License R Docket No. 50-83  %

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Dear Mr. Miller:

As requested in your letter of April 9, 1982, the enclosed package contains our written response to the attached formal questions developed by the NRC Staff and the LANL team involved in the review of the UFTR SAR for license renewal of our 100 KW Argonaut-tyne reactor (UFTR). These responses are submitted in narra-tive and tabular form as requested. Where necessary for ease of presentation, supporting information is included in attachments te the main response text.

Please note that some copies are of poor quality but represent the best available copies of original documents.

The enclosure consists of:

1. Three (3) signed originals and nineteen copies of this letter of transmittal.

2. Twenty-five (25) copies of the response to questions with all attach-ments and table of contents.

Sincerely,

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Nils J. Diaz &

Director of Nuclear Facili ies N3D:Imc

Enclosures:

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im NILS J. DIAZ, DIRECTOR (904)392-1406 EQUAL EMPLOYMENT OPPORTUNITY / AFF'RMATIVE ACTION EMPLOYER

UNIVERSITY OF FLORIDA TRAINING REACTOR (UFTR)

FORMAL QUESTIONS RELATED TO LICENSE RENEWAL

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1. In what position does the solenoid-operated dump valve fail?

2. Specify the location for the exposure rate vs power shown.in Fig.12-2.

How is Fig. 12-2 related to Fig. 12-37

3. provide the reference for the 200:1 atmospheric dilution factor allowed by the Nuclear Regula tory Commission.

4. What is the mechanical sequencing and procedure followed after a vent system radioactivity alarm?

.5. Is the diesel generator currently in the UFTR electrical system? If so, -

is it started manually or automatically?

6; What is the pressure differential be' tween the primary and secondary coolants in the heat exchanger? How would heat exchanger leakage be detected?

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7. Is a reactor thermal calibration routinely performed?

8. Is the reactor room maintained at a negative pressure? What is the pressure?

9. Is it possible to dump liquid radwaste inadvertently into the sanitary sewer system.from the retention system by a single-point failure or by personnel error?

10. Describe the radiation protection staff including their minimum quali-fications (training and/or previous experience). . Indenti fy the number and responsibilities of personnel and the lines of communication between them.

11. Summarize your general radiation safety procedures.. Identify the minimum frequency of surveys, action points (levels), and appropriate responses.

12. Identify the generic type, number, and operable range of each of the portable Health Physics instruments routinely availabic at the reactor installation. Specify the frequency of calibration.

13. provide protocols for monitoring program, including bio-assay and in vivo e counting capabilities.

14. Describe calibration procedures for the in-house portions of the personnel monitoring program. Describe any Quality Assurance tests for the l

commercially supplied portions.

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15. Identify any administrative exposure limits and anticipated actions if these levels are exceeded. Also, identify the operational constraints that are placed on personnel entering potential radiation /high radiation '

or contaminated areas.

16. Summarize the quantities of liquid and solid radioactive waste resulting from reactor operations for the last 5 yr (gross activity of each physical form at times of release or shipment for each year).

17. We need a 5 yr list by year of personal exposures, visitor exposures and environmental survey data for onsite and offsite programs.

18. Describe the composition of reactor staff.

19. Summarize the operating history of the UFTR 'over the last five years.

Include hours of operation, total MW hours and U-235 burnup.

20. Provide a chronological summary of the major modifications made to .the UFTR which could affect safe operation of the reactor.since it was first licensed in 1959. _.

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l RESPONSES TO FORMAL QUESTIONS DEVELOPED BY NRC STAFF AND LANL REVIEW TEAM University of Florida Training Reactor

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Engineering and Industrial Experiment Station Nuclear Facilities Division

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DEPARTMENT OF NUCLEAR ENGINEERING SCIENCES College of Engineering

[ University of Florida l Gainesville

RESPONSES TO FOPEAL QUESTIONS DEVELOPED BY y NRC STAFF AND LANL REVIEW TEAM No. of Pages Item Primary Response to Questions 1-14

_ ATTACHMENT A (Question 2) 2 ATTACIGENT B (Question 3) 5

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ATTACIRENT C (Question 3) 9

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ATTACIDENT D (Question 9) 3 ATTACIDENT E (Question 10) 1 ATTACHMENT F (Question 10) 11 ATTACIDENT G (Question 11) '

5 ATTACIDENT 11 (Question 14) 2

RESPONSES TO FORMAL QUESTIONS RELATED TO LICENSE RENEWAL FOR UNIVERSITY OF FLORIDA TRAINING REACTOR

l. To be closed, the dump valve solenoid 2UST be energized. A de-energization will result in the dump valve opening; it fails open. If after opening, the dump valve were to be suddenly reclosed, the resultant water hammer would " pop" the rupture disc and all reactor water would drain out of the core and into the primary pit. This would shut down the reactor due to the large reactivity worth of the moderator.

2. The reference for Figure 12-2 does not specify a location where the exposure rate was recorded for various UFTR power levels (0, 10, 40, 75, 100 Kw). This Figure 12-2 was only included to verify the expected linear variation of expo-sure rate with increasing reactor poyer level and has no direct relation to Figure 12-3. Since there is no location specified in Figure 12-2, a new Figure 12-2 has been generated and is included here for the same purpose - to demon-htrate/ verify the general linearity of exposure rate with reactor power for a fixed location. Revised Figure 12-2 and supporting data is included on separate ---

pages designated Attachment A (Question 2).

3. The dilution of UFTR cf fluent is two-part - first, the 250 cfm of air withdrawn from the reactor room is diluted by 12,000 cfm of outside air. Next, the 200

~ to one atmospheric dilution factor is applied to the vertically rising plume from the stack. This is noted in Section VI - D of currently applicable Tech-nical Specifications. Additionally', an adjustable alarm is set up with level commensurate with reactor power to alert the operator to any unusual radiation condition in the stack, and a non-adjustable alarm is always in readiness to alert the operator in the event of an abnormal high stack condition. Addition-ally, the Radiation Control Department monitors the area surrounding the UFTR with film badges which are changed on a monthly basis.

This 200:1 dilution factor goes back nearly 20 years to the early years of Argonaut operation when these reactors were sometimes registering Ar-41 measure .

ments exceeding MPC. Several reactors applied for and received 200:1 dilution fac tors; some of these reactors, including the UFTR, still have this 200:1 dilu-tion from the old AEC granted as part of the license amendment increasing rated power operation from 10 kw to 100 kw. The key communications documenting this 200:1 dilution factor are enclosed as Attachment B to Question 3.

The 200:1 atmospheric dilution was originally requested as part of the Applica-tion for increasing UFTR rated power from 10 kw to 100 kw as outlined in the attached letter from Uhrig to Lowenstein (AEC) requesting the required amend-ment 8 t Facility License R-56 for the UFTR. The letter and the first four (4) pages of the application for amendment to License R-56 where the request for a 200:1 atmospheric dilution factor is delineated are included as Attachment B (Question 3) . The 200:1 dilution factor requested as part of the UFTR facility license amendment at the bottom of page 3 is marked as Docket No. 50-83, this amendment dated August 21, 1963 was addressed in supplemental letters dated October 4, 1963 and October 22, 1963.

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I As indicated on Page 2 of the letter answering amendment-related AEC questions dated October 4, 1963 from Robert E. Uhrig, Head, Department of Nuclear Engineer-l ing to Saul Levine, Chief, Test and Power Reactor Safety Branch, Division of Licensing and Regulation, USAEC concerning Docket No. 50-83, and the request I for approval of 200:1 atmospheric dilution factor, Uhrig states:

l "In order,to provide ourselves with assurance that the dilution factor requested was realistic, we have recently taken additional measurements of the amount of Argon-41 being discharged into the a tmosphere. These measurements, which were taken in the stack I exhaust, show substantial agreement (within 15%) with our previous measurements and calculations which were included in our application of August 21, 1963."

The letter dated October 22, 1963, corrects two errors contained in the October 4, 1963 letter concerning the location of the air intake vent on the south half of the main roof of the Nuclear Sciences Building and the distance from the I UFTR and the tower where meteorological data were taken (1400 feet from UFTR, not 400 feet) . Neither point is directly related to the 200:1 dilution re-quest; however, the vent location should have aided the hazards analysis concerned with the license amendment.

This amendment, as requested, was approved as Amendment No. 8 to the UFTR Facility License No. R-56 on January 28, 1964. The approval letter, Amend-I ment No. 8 itself, a Notice of Issuance (dated 28 January 1964) of the Facility License Amendment and the Amendment-related Hazards Analysis performed by the Test and Power Reactor Safety Branch of AEC are included as Attachment C I (Question 3).

4. There have been no vent system alarms due to abnormal conditions of radioacti-I vity. Normal forseeable conditions at the UPTR indicate a low probability of an abnormally high radioactivity level in the stack effluent. Also, there is an absolute filter in the vent line to remove any particulate matter from the vent before it is discharged. The occurrence of a valid alarm requires shut-I ting down the reactor and the vent system and evacuating the facility if need indicates. In the event of a vent system alarm, first a check is made to see if it is a valid alarm; for example, to determine if the variable setting alarm I is set for 100 Kw operation and not 10 watt during a full power run. If the alarm is determined to be valid (assumed so whenever the GGA inctalled full power rating alarm sounds), then the reactor is shut down and the vent system I is shut down. Basically then, in the event of a vent system radioactivity alarm, the vent system must be secured. Next a determination must be made as to why the vent system alarmed to include checking possible experiments in place and checking for air particulates. Evacuation is ordinarily used only I if there is a possibility of airborne contamination which may then affect the reactor cell. If the vent system is shut down, this will automatically scram the reactor.

5. At present, several selected, critical electrical systems and components in the UFTR can be powt ced from an emergency electrical bus. Basically all sys-tems essential to the facility are tied to the diesel generator to include all instrumentation syatems, the security system (except for the security system battery charging system which will soon be connected also since all material and parts a re now-on hand) , the cooling system, and the vent system but not 2

l I including the crane system due to the power levels required by the crane system.

In the event of loss of normal electrical power to this emergency bus, the diesel generator will automatically start, supplying power to this bus. The l

diesel is not an exclusive component of the UFTR systems in that it provides I power for the emergency bus of the adjacent Nuclear Science Center. The UFTR is simply tied in to it as an additional safeguard for security systems.

6. The difference in water head between primary and secondary systems is approxi-mately three feet, with the pressure of the secondary water being the higher.

Actual pressure at the lowest point in the system is about 5 psi. A primary I pressure of 7 psi will " pop" the primary rupture disc, shutting down the reac-tor. The heat exchanger is nuclear rated, stainless steel. Because of the higher pressure on the secondary side, leakage would be from the secondary, into the primary. A continuous purification loop of about 0.8 gpm has resis-I tvity cells monitoring water quality before and after purification. Typical resistivity is about one megohm-cm. Tech Spec requirements on resistivity are that it must be at least 0.4 megohm-cm. A readout and visual alarm in the I control room displays information from these two sensors. Since the take-off for the purification loop is just downstream of the heat exchanger, any secon-dary water intrusion into the primary (even a pin-hole leak) would immediately I show up as a lowered resistivity level and visual alarm on the monitoring in-strument. In addition, as part of the weekly UPTR check-out procedure, a sample is taken and counted after evaporation to confirm that there is no leak-age through the heat exchanger; that is, to confirm no primary to secondary I leakage.

7. On an annual basis, a calibration check of reactor instrumentation is performed I- using a calorimetric heat balance procedure. Before the heat balance is per-formed, a voltage check is made of all power supply and operating voltages of the nuclear instrumentation; a calibration check is made of the primary flow I meter using manufacturer's instructions; and a calibration check is made of the temperature recording system involving the thermocouples of the primary system. Temperature system calibration is to about two-tenths of a degree Fahrenheit. This is a considerably better accuracy than that generally attri-I butable to a thermocouple system.

8. All doors into the reactor room are scaled with " closed cell" rubber gasketing.

Since the vent system is withdrawing 250 cfm of air from the room, there is a slight negative pressure in the room. The gasketing and the air removal assure a pressure differential; this negative pressure has been measured by the UP Physical Plant's Division who adjusted the inlet damper to increase negative I pressure. With 250 cfm air flow, a slight negative pressure (ap .

was determined. min

~1/4" H 2O)

9. From the UPTR, it is not possible to inadvertently dump radioactive liquid into the sanitary sewer system. In general, although it is possible to pump water out of the rad-waste storage system, the effort requires considerable valve I alignment at a point within the UFTR controlled access area. The retention tank is under control of the Radiation Control Office; the Radiation Control procedure (Technique #21) contains instructions for sampling and discharging the contents of the waste holdup tanks; see Attachment D (Question 9) .

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10. All reactor operators are trained in IIealth Physics. All UFTR Operating Staff are qualified by Radiation Control in writing to the effect that they are l capable of discharging radiation protection duties typically assigned in the UFTR to include:

I a. Taking Samples

b. Routine Radiation Monitoring l Outside of routine monitoring, the UFTR Staff members rely upon Radiation Control within the UF Environmental Health and Safety (Ell &S) Division to I provide independent (of line responsibility on UFTR) radiological services.

The minimum qualifications (training and/or previous experience) for each of I the radiation control protection-related positions with the ElI&S Division are outlined below:

I a. Radiation Control Officer This position directs the university's radiation safety program which includes a medical center and engages in inservice teaching. This posi-I tion reports to the Director of Ell &S. The minimum qualifications are:

Ph.D with two years professional experience in radiation control or M.S.

in IIcalth Physics with 5 years experience,

b. Radiation Control Technician I. Graduation f rom an accredited four-year college or university with major course work in radiological health or in one of the physical or natural sciences.

Experience as a technician in radiological health may substitute on a year-for-year basis for the required college training.

Concerning the radiation protection staff within the UF EII&S Division, the number and responsibilities of personnel and the lines of communication between them are identified as follows:

a. Number and organization as part of Ell &S Division please see the organizational chart of the tT EII&S Division labelled I Attachment E (Question 10). The dark lines show the organization of the Radiation Control Department in relation to the rest of the Division.

Numbers indicate the number of personnel.

b. Responsibilities of Padiation Control Staff Position descriptions for the Radiation Control Officer, Radiation Control I

1 Technicians and the Secretary are designated Attachment P (Question 10) .

Accounting, office and clerical support for the Radiation Control Depart-ment are provided by the E!!&S accountant, staff assistant and secretary.

c. Lines of Communication Lines of communication are as indicated by the organizational chart referenced previously as Attachment E (Question 10).

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11. Radiation safety primarily deals with weekly surveys to minimize occurrences of areas of contamination, weekly surveys to monitor air quality, adherence to

{ SOPS to preclude creation of radiation problem areas, evaluation of experi-ments to preclude radiation problems, etc. The applicable procedures are lengthy. For detailed information regarding this subject, the procedures can be studied for a complete understanding.

Radiation safety procedures are designated as Division D procedures for UPTR Radiation Protection, Control and Operations. There are seven (7) Division D

[ procedures designed to assure that exposures are maintained as low as reason-ably achievable:

UFTR Radiation Protection and Control

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UFTR-SOP-D.1 UFTR-SOP-D.2 Radiation Work Permit

3. UFTR-SOP-D.3 Personnel Monitoring UFTR-SOP-D.4 UFTR Radiation Protection Weekly Survey

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5. UFTR-SOP-D.5 Primary Equipment Pit Entry .

6. UFTR-SOP-D. 6 Removing Irradiated Samples from UFTR Experimental Ports

7. UFTR-SOP-D.7 Primary Resin Change These 7 procedures are summarized in Attachment G (Question ll).

{ 12. Portable survey (Health Physics) instruments routinely available at the UFTR consist of one cach of the following instruments:

1. PNR4 Bonner Ball neutron detector, O - 5,000 mr/hr;

[ 2. Geiger Counter, E-140, 0 - 50 mr/hr;

3. Cutic Pie, 740-F, 0 - 25,000 mr/hr;

4. Teletector, 6112B, 0 - 1000 R/hr;

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Pancake detector, RM-14, 0 - 50,000 cpm; APD AIM-3BL, O - 30,000 cpm.

Calibration checks are conducted at 3 month intervals using approved sources to determine actual radiation response.

13. The Radiation Control Office and the Nuclear Engineering Sciences Department

[ have a complete set of bio-assay and n vivo counting capabilities. The NES Department has a whole body counter (at the Nuclear Research Field Building) for in vivo, whole body radiation evaluation of body burden. In addition, bio-

[ assay capabilities are available to include sample collecting, preparation and counting of urine, feces, and blood. In addition, a thyroid cavity count-ing system specifically for iodine takeup is available and in use as necessary.

[ 14. Radiation Control performs and certifies all instrument calibration for the in-house personnel monitoring program. There is also a personnel moni-toring program based on film badges administered and controlled by the Radia-

[ tion Control Department.

The procedure for calibrating self-reading pocket dosimeters is presented as Attachment H (Question 14).

Film badges supplied by the commercial vendor are periodically exposed (approxi-

{ mately quarterly) to known quantities and specified types of radiation as a quality assurance test.

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15. Title 10, Code of Federal Regulations part 20 establishes requirements here.

Additionally, Florida is an agreement state and also imposes controls. There h are normally no areas of the UFTR wherein a person may be unknowingly subjected to significant radiation exposure. Before any operation is undertaken where there may be radiological involvement, precautionary measures (including radia-tion surveys) are taken and the operation is performed within the purview of a Radiation Work Permit, if necessary.

I This question is partially answered in the response to Question 11. However, we do establish further administrative exposure limits in-house for operations at the UFTR that are expected to produce significant exposures. For operations con-I nected with the UFTR, this control is established through the Radiation Work Permit (RWP). Essentially, when a pre-set control limit is reached based upon Federal, State or UFTR requirements and prior planning, then individuals are I removed from the radiation exposure potential and given other duties in the interim period.

16. The UFTR normally releases to the holding tanks ~1.5 liters of primary coolant per week due to waste from primary sampling. Over the last 5 years, additional releases have occurred one or two times per year. There has been no. detectable alpha activity released from the UFTR. Allowing for decay in I the holding tanks (characteristic Na-24-dominated half life of 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />), .,_

the actgvity from the UFTR in the holding tanks is always reduced to less than 1 x 10 pCi total beta-gamma activity diluted to an average concentration I of less than 3 x 10-11 pCi/ml before release to the environment.

The volumetric quantity and activity of UFTR releases directly from the UFTR with dates of release to the holdup tanks are summarized in Table Q16-1.

Table Q16-1 I UFTR Liquid Waste Release to Holdup Tanks Reporting Year Release Date of Release Activity Level Quantity

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Sept 1, 1976-Aug 31, 1977 78E 1.51/ week 4.93x10 llCi/ml

-6 Sept 1, 1977-Aug 31, 1978 781 1.52/ week 2.1x10 Ci/ml

-6 2101 Nov. 17, 1977 3x10 Ci/ml Sept 1, 1978-Aug 31, 1979 781 1.52/ week 6.17x10~ pCi/ml 1981 Apr. 25, 1979 1.26x10~ tci/ml 1851 Nov. 27, 1979 6.58x10~ pCi/ml Sept 1, 1979-Aug 31, 1980 781 1.51/ week 7.34x10~ pCi/ml l 176E Apr. 22, 1980 1.08x10~ UCi/ml Sept 1, 1980-Aug 31, 1981 -6 78E 1.51/ week 2.85x10 pCi/ml 551 Apr. 9, 1981 1.35x10~ UCi/ml 771 June 23, 1981 4.65x10 1Ci/ml 6

I The liquid effluent discharged into the holding tanks comes from come twenty in laboratories within the Nuclear Sciences Center as well as from the UFTR com-plex. The total yearly volume rel.:ase as well as the monthly activity (UCi/mlS)

.for the holdup tanks is presented in Table Q16-2.

Tabic Q16-2

I Liquid Waste Release from UFTR/ Nuclear Sciences Complex Reporting Year Total Release Volume Monthly Activity (UCi/ml )

1976-77 279,200 September 76 NR*

-8 October 76 7.0 x 10

-8 November 76 6.0 x 10 December 76 NR January 77 NDA**

February 77 NR s March 77 NR April 77 3.0 x 10~

May 77 NR June 77 NR _g --

July 77 3.0 x 10 August 77 NR 1977-78 340,500 September 77 5 x 10' October 77 NR

.lB November 77 December 77 NR 4 x 10

_g January 78 NR _g February 78 8 x 10 March 78 NR April 78 NR _g

. May 78 8 x 10 June 78 NR July 78 NDA

-8 August 78 2 x 10 1978-79 645,000 September 78 NR October 79 NR November 78 NR

_g December 78 3 x 10 January 79 NR February 79 NR

-8 March 79 1 x 10

-8 j April 79 5.5 x 10,g l May 79 9 x 10 I June 79 July 79 August 79 NDA NDA NR Continued next page.....

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I Reporting Year 'Ibtal Release Volume Monthly Activity (p ci/nl) l 1979-80 618,000 September 79 2 x 10~

October 79 NR November 79 NDA December 79 NDA

-8 January 80 1.7 x 10 February 80 NDA March 80 NR April 80 NDA May 80 NR June 80 NR July 80 NDA August 80 NDA 1980-81 1,060,000 September 80 NDA October 80 NDA November 80 NR December 80 NDA

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, January 81 2 x 10 February 81 NDA March 81 NDA

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April 1981 NDA May 81 NDA June 81 NDA July 81 NDA

. August 81 NDA

• NR u No Release in this Month

• *NDA = No Detectablg Activity in the release for this Month (Minimum Detectable Activity = 2.4x10 pCi/ml) l l

There has been very little solid radioactive waste released or shipped from the UFTR for the last 5 reporting years. When solid waste is generated (clothes, rags, etc.), it is allowed to decay below detectable activity levels as certified by the Radiation Control Office. It is then disposed i of as normal waste. Some few small activated items which might eventually be released as waste are currently stored in the UFTR complex in shielded l containers. Even the primary coolant resins, which are replaced at approxi-i mately 18 month intervals, are stored temporarily in the UFTR complex; al-l though they typically register 30 mR on contact, the resins decay to back-ground levels in a few months and have then been disposed of as ' -" nary l waste as certified by the Radiation Control Office.

The only solid waste released and shipped from the UFTR was some irradiated steel pipes and other steel parts which had been stored here since under-going irradiation. These were encased in drums and turned over to Radiation Control (September 4, 1931) to be shipped offsite to Washington State in l November, 1981. The waste form is steel piping / parts and the primary acti-vity is due to Cobalt-60. Further details on this solid waste are presented I in Table Q16-3.

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Table Q16-3 Solid Waste Released and Shipped fron UFTR*

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Container Size Contents Radioactivity Activity 3

Barrel 7.5 ft Sand and Irradiated 25 mci 150 mR 55 gal drum 800 lbs. Steel Piping / Parts Primarily Co-60 Q surface I 30 mR 0 3 ft.

Barrel 7.5 ft Steel Piping / Parts in 25 mci 80 mR I 55 gal drum 800 lbs. Solid Concrete (ccment) Primarily Co-60 0 surface 30 mR

@ 3 ft.

Barrel 4.1 ft Steel Piping'/ Parts in 5 mci 50 mR 55 gal drum Solid Concrete (cement) Primarily Co-60 @ surface I

30 mR 0 3 ft. .-

• Shipped to Washington State by Nuclear Engineering Company, Inc. (now U.S. Ecology),

I P.O. Box 7246, Lexington, Ky. , 40207, on November,1981.

17. Individual personal exposure data related to the UPTR in summarized in Table Q17-1 for the past five calendar years. This exposure data refers to indivi-duals working at the UFTR over an extended period of time either as an operator, I researcher, student, staff member, etc. and who were issued film badges to record exposures. This data does not apply to short-term experimenters and researchers, short-term student involvement with the facility nor to occasional or one-time visitors for whom film badges were not issued.

I Table Q17-1 Number of Individuals in Exposure Interval Number of Individuals in Each Range Whole Body Exposure Range (rems) 1977 1978 1979 1980 1981 No measurable exposure 4 8 5 2 6 Measurabic exposure less than 0.1 7 2 3 7 2 0.1 to 0.25 1 0 0 1 2

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L Visitor activity is controlled to avoid exposure. Visitors to the UPTR are not issued film badges. Ordinarily visitors are issued one or two pocket dosimeters (whose dose results are recorded in a dosimeter log) if there is a possibility that they will be exposed to a measurabic dose during their time in the UPTR cell. Since many visitors are conducted on tours and given p 1ceture/ demonstrations where there in little likelihood of exposure, no dosi-L_ meters are issued to such visitors since they would have no exposure. For purposes of the dosimeter / exposure log .aaintained at the UFTR facility, a

_ visitor is anyone not issued a film badge but who might be expected to receive a measurable exposure. Records are kept of other visitors to the facility but not in the dosimeter / exposure log.

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For the last five (5) years the dosi-meter log records for visitor exposure are summarized in Table Q17-2. It

{ should be noted that, of those assigned dosimeters, only about 20% receive any measurable exposure as recorded in the UPTR dosimeter log.

_ Table Q17-2

_ Dosimeter Log Exposure Records for UPTR Visitors I Reporting Year Number of Visitors (Excluding Staff &

Number with Non-Zero Exposure

• Exposure Limits (mR) .

Badged Personnel sept, J976-Aug, 1977 429 82 1-5 1 9 1 20 I* 1 1

23 27 1 32 1 42 Sept, 1977-Aug, 1978 142 42 1-5 2 10 Sept, 1978-Aug , 1979 142 17 1-5 Sept, 1979-Aug, 1980 53 8 1-4 sept, 1980-Aug, 1981 201 35 1-3 I 1 1

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• Those with non-zero exposures recorded in Tabic Q17-2 are primarily researchers and other laboratory assistants and experimenters who were involved in reactor-related work for a brief period of time for a research project, laboratory course or other experimental work.

Environmental film badges are distributed at various locations external to the I UFTR Building facility. These seven (7) badges serve as an environmental monitor o f UPTR operations. The dose data results f.>r Badges Al-A7 for the last five (5) calendar years is reproduced in Table Q17-3.

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Table Q17-3 Environmental Badges Yearly Totals (mren)

Badge ID 1977 1978 1979 1980 1981 -

Al M 30 M 70 110

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A2 M M M 40 50 A3 M 10 M 20 10 A4 M M M 20 10 A5 M M M 70 50 A6 M M M 30 30 A7 M M M 20 20 These badges are checked each month and the results in Table Q17-3 represent a cumulative total of the 12 month exposure records for the last five (5) yearn.

According to the firm providing the analysis of the UPTR environmental survey I film badges, exposures below minimum quantity measurable in any vonth are recorded "M. " There fore, an "M" in the monthly reports equals less than 10 millirems X or gewima, 40 millirems hard beta, 20 rtillirems fast neutron, or I 10 millirems thermal neutron. "M" in cumulative total columns (yearly) as recorded in Table QL7-2 means all previous current exposures for the year in question have been minimal. Therefore, cumulative totals equal sum of non-minimal readings for badges returned for processing and reported to date.

18. The UPTR organization chart, presented in Figure 1 following p. 32 of the Technical Specifications submitted as part of the UPTR Safety Analysis Report, I shows the UPTR organization, including the Reactor Safet.y Review Subcommittee and the Radiation Control check, audit, and review interactions as well as the I,evel 1 responsibility of the University of Florida President and the I Chairman of the rinclear Engineering Sciences Department for the UPTR.

ing to Figure 1 showing UPTR organization, the composition of the UPTR staff Refer-is as follows:

I,cVel 2: Director of tJuclear Facilities Level 3: Reactor Manager Level 4: Operating Staff Operators

1. Senior Reactor Operator (Class A) - Full Time Permanent Employee i 2.

3.

Reactor Operator (Class B) - Full Time Permanent Employee Reactor Operators (Class B) - Part Time

a. one 1/2-time employee

b. one 1/3-time employee 11

I As indicatcd in the UFTR Safety Analysis Report, the Director of tiuclear Facilities and the Reactor Manager are in complete charge of the reactor facility, the scheduling and supervision of experiments using the reactor, tha control of the reactor fuel, the keeping of logs and records, and the maintenance of the physical condition of the facility. They are also re- .

sponsible for liaison with regulatory bodies and for coordinating the teach-ing and research programs within the facility.

The Director of tiuclear Facilities has line responsibility over the Reactor Manager and is directly responsible for the conduct of operations of the reactor facility. The Reactor Manager reports to the Director of tiuclear Facilities and has direct supervision over the operations, maintenance and record keeping of the UFTR. The Director of tiuclear Facilities and the Reactor Manager select operator-technicians and supervise their training.

The Reactor Manager enforces operating procedures and regulations and has the power to authorize operations or experiments in accordance with facility regulations, when certified.

The Director of tiuclear Facilities aqd the Reactor Manager basically direct and coordinate the ef forts of all Level 4 staff members in the operation of the UFTR facility.

19. The operating history of the UFTR for the last five reporting years (September -

1, 1976 - August 31, 1981) is summarized in Tabic Q19-1 which includes IIours of Operation (hours of reactor key-on time), Total Energy Generation (tiegawatt-flours) and Average U-235 Mass Fissioned as well as Consumed (Grams):

. Table Q19-1 Recent (Five Year) UPTR Operating !!istory (September 1, 1976 - August 31, 1981)

IIours of Operation

• Energy U-235 11urnup *

• Year Dato Key-on-Time Generation Fissioned Consumed (IIours) (MW llours) (grams) l 1 Sept 1, 1976-Aug 31, 1977 615.5 26.388 1.171 1.375 2 Sept 1,1977-Aug 31,1978 919.0 26.376 1.217 1.428 3 Sept 1, 1978-Aug 31, 1979 313.9 9.079 0.419 0.492 4 Sept 1, 1979-Aug 31, 1980 301.43 9.800 0.452 0.531 5 Sept 1, 1980-Aug 31, 1981 603.65 15.201 0.701 0.823 Y#' Sept 1, 1976-Aug 31, 1981 2753.48 Total 85.844 3.96 4.65 l *The IIours of Operation (Key-on-Time) entry does not include significant amounts of time for set-up, check-out and removal of experiments, etc. Knen this time is in-cluded, the flours of Operation (Utilization Time) entry is increased by approximate-ly 50%.

• *Durnup isgeported on a yearly basis for both grams of U-235 fissioned (given that 4.614 x 10 gas of U-235 fission per Kw-hr of energy generation) and for grams of U-235 consumed (given that a multiplicative factor of 683/582 more grams are con-I sumed than are fissioned per Kw-hr of energy generation due to parasitic neutron capture in U-235 conversion to U-236) .

12

E As a further indication of recent operation and utilization of the reactor, UFTR Yearly Average Operations History for the last five (5) years is sum-l marized as follows:

I Key-on-Time = 550.7 Hours / year Energy Generation = 17.57 MW-hrs / year U-235 Burnup (Fission) = 0.792 gms U-235 fissioned / year I U-235 Burnup (Consumption) = 0.930 gms U-235 consumed / year.

20. A chronological summary of the major rodifications made to the UFTR which I could affect safe operation of the reactor since it was first licensed in 1959 is presented in Table Q20-1.

Table Q20-1 UFTR Major Modifications - Chronological Summary Item No. Date , Modification 1 prior to 1965 Addition of high density barytes concrete shielding I '

to reactor structure to provide for upgrading Iower from 10 kw to 100 kw. Also, replacing movable con- --

crete shield frame to minimize damage during moving.

2 November, 1969 Sand removed from beneath reactor core. Wet sand had led to electrolytic corrosion between steel and aluminum piping under reactor core.

3 January, 1970 20% core removed and shipped to National Lead; many elements contained warped plates.

4 July, 1970 Provision made for exhausting experimental equipment I gases into core vont system to filter particulates and to monitor activity of gases released.

5 July, 1970 I Excess reactivity authorized up to 2.3% Ak/k by a license amendment.

6 September, 1970 New control console installed with new, solid state nuclear instrumentation.

7 August, 1970 All primary piping replaced from pit to core. New fuel boxes made with added height to mininize water I overflow, water outlet lines from fuel boxes in-creased from one inch to two inches to minimize water overflow.

8 November, 1971 Scram point without secondary coolant reduced from 20% power to 1% power.

9 July, 1972 Primary and secondary temperature monitoring system I installed with high temperature scram set down to 160*F, subsequently reduced further to 155*F.

10 February, 1973 Safety Channel #2 modified with independent high voltage Scram circuit designed and put into opera-tion.

Table 920-1 Continued.....

Item No. Date hbdi fica t i on 11 October, 1973 Primary flow measuring system installed in reactor

fill line (with analog presentation of flow and ad-J justable low flow scram Ioint).

12 October, 1973 Domineralizer pump (primary purification loop) in-I 13 October, 1973 stalled to permit continuous purification of primary water.

Conductivity / resistivity cell added to ronitor resis-tivity of circulating primary water. Control room resistivity bridge modified to permit reading primary resistivity into and out of demineralizer.

14 October, 1973 Primary purification loop demineralizer changed from small Barnstead cartridges to large resin holder to increase capability and time between changes.

15 October, 1973 Diffuser installed in primary coolant tank to climi-nate vortex'and air suction due to primary pump suc-tion. Primary pump replaced with one capable of 60

. gpm flow.

16 October, 1973 Installation of nuclear-rated (N-stamped) heat ex- ~~

changer for cooling of primary system.

17 October, 1973 bbdification to secondary flow scram system (scram set at 1 kw) to permit key change-over of logic from well water (scram at 60 gpm) to city water (scram at 8 gpm).

18 August, 1974 East-West Through Port drilled as experimental access.

19 November, 1975 Authorized SNM reduced in quantity from 7.802 kgm contained U-235 to 4.82 kgm contained U-235.

20 February, 1976 Drilled and tapped 12 cach 10-24 holes in top of

'I cach fuel box for friction sealing of fuel box to prevent overflow.

21 September, 1977 Water level (sump) alarm installed in primary equip-ment pit to warn of water Icaks.

22 June, 1978 Back Flow Preventer installed in City Water line as per Natianal Plumbing Code.

23 September, 1978 Modification of control blade motor drive circuits f to permit complete de-energization of motors when reactor is not operating; this greatly extends motor I 24 February, 1979 life. Fbtors are of a type no longer manufactured.

Final installation of smoke and fire monitoring sys-tem in reactor cell.

25 June, 1981 Installed console alarm to monitor Pu-De cource use in the reactor.

26 July, 1981 Provided emergency electrical bus power to vital UPTR equipment, in event of power lons.

I 14

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Table QE-1 I EXPOSURE LEVEL READINGS TAKEN 23 MARCH 1982 0 11:50 a.m.

WITil VICTOREEN CUTIE PIE MODEL 740-F, #2418 -

Exposure Level Exposure Level Power Level (Location X ) (Location X )

(kw) (mr/hr)* y (mr/hr)* 2 0 0.0 0. 0 10 0.5 1.0 40 2.5 6.0 75 5.5, 12.0 100 7.5 17.0

• Locations X7 and X 2are indicated on the attached overhead schematic (Fij Q2.-2) --

of the UFTR. Both sets of readings were taken at approximately five (5) feet above floor Icvel. General linearity of the variation of exposure rate with reactor power is shown in Figure Q2 .L.

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4 ATTACIIMENT C l

(guestion 3) il l

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T M2$ ,

.t g g.g UNITED GTATES j.

5 .

%)

ATOMIC ENERGY COMMISS!ON .

- */ WASH WCTON 25. D.C. .

L'w( .e p* ' n.  :

l nacket 50ro83 . .

DL13:FE .

NAN 81954

-5.-. ,: -

l '

University of Florida ,

College of Engin2ering Cainesville, Florida ,

j-

.I Attention: Dr. Pobert E. Unrig, Ecad ,

• Depart =ent of Iuclear Engineering I Gentie'nen: ,

..JRrannaitted herewith is' Anandrant ro. 8 to Licence Ro. R-56, as cr2nded, issued to the University of Flo--ida this date. Tac atandment authorizen an increacc in the power leval of the ,

University's Argonaut-typo nuclear reactor located on thc canpun in  ;

'"'Gainesville, Florida from 10 kilo'..atts to 100 kilo.atts (ther-41 ),

'I as describad in the application for licence amend ent dated Iqust 21, 1963 and supplenental letters dated October i f,1963 and October 22,*  ;

e E 1963 g

A copy of a notice of this action, which has becc nutnitted to g

the Office of the Federal Ec31cter for filin;; and publication, and ,

j a copy of the staff hacarda analynic are attacacc.

!e f

Sin:crely yours,

/*

f }

,{'_>y( ,. -; . s;VO Saul Levine, Chief Test & Power Reactor Safety Branch ,

Division of Licensing and Regulation I

Enclosurec: b>

1. Atendment No. to License Eo. R-56

2. Eazardo Analyci-3 Notice to Office of the Federal Regicter g .

N 4' W G' 5 * ,$..c

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q<@ q I , N\ d a

! 3. .

C-1

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E. o * ' 's..

• UNITED STNTES s p f py)%?; ATOMIC ENERGY COMMISSION L. WALH INGTON. D.C. 20545 s* ,NJ)p.'.

,,, ,g g e UUIVZ2SITY OF FARIDA DOCIET EO. 50 83 10!E!!C'GIIT TO . FACILITY LICEUSE License I!o. R-56 Anendment Io. 8 l

3 License I;o. R-56, as enended, issued to the University of Florida, in hereby g further enanded in the follovirq respects:

1. In cadition to the activities previously cuthorized by the cc--incion in License I:o. R756, cc cranded, the University of Florida is cuthorized to operate the University's /csonant-type reactor located in Cainesville,

! Florida, et power levels up to 100 hilowatts (thernal), es described i in the University's application for crend:ent dated 1u3nst 21,1963 and cupple=2ntal letters dated October 4, 1953 cnd October 22, 1963'.

2. In cddition to other reportin3 requirc:ents, the University of Florida shall subsit as promptly as practicable, but not later than 60 days efter attaining tha 100 kilowatt porar level, c written report to the Co ission of the results of the follo.rirG =cacuretants:

A. maw n excess reactivity of the fccility, not includirG the vorth of control rods or cny crporinents; ,

B. Pressure, flow rates, and inlet cnd cutlet te=paratures in the primry and seco.@ / loops; C. Maxi =ua fuel elenent temperature; .

1 D. 'lunparature coefficient of reactivity; E. Radiation levels in the reactor roon; cnd tegon-41 concentrations in the reactor cell, cnd in the unrestricted F.

creas cajacent to the reactor cu_idirc.

3. Tais caendment is effectiva es of the date of issuan c. .

FOR TE2 /TCIIC EIE3GY CC'GISSION

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/ Scul II:vina, Chief Test & Povar Reactor Safety Branch Divisisc of Licensins and Re3ulation I Date of Issuance: rM-)G

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K0TICE OF ISSUA CE 07 FACILI?? LIC2' S2 EEIEE'?.~2 I THE UNIVZRSITi' 07 F103IDA DCCKET NO. 50-83 Please take notice that the Atenic Enercy Cc W ccion hac iccued, effective as of the date of issuance, Anend ent so. 8, cet forth balov, to Facility Licence no. R-56, as a=anded. Tne c=endcent authorizec the University of Florida to in-cresco the naxinun povar level of the University's Argonaut-type nuclear reactor located on the canpus in Gainesville, norida, fron 10 to 100 kilowatts (thernal),

as described in the application for licence r enicant dated August 21, 1963 and supple = ental letters dated October 4, 1963 and October 22, 1963.

Tac Co-?csion has found that:

(1) Tne application for anendrant conplies with the requirenants of the Atonic Energy Act of 1934, ac c= ended, and the Co. ission's regula-tions cet forth in Title 10, Chapter 1, CFR; .

(2) Operation of the reactor in accordance with the licence as crended vill not present undue hazard to the health and safety of the public I and vill not be ininical to the co=0n defence and secu-ity; .~

(3) Prior public notice of proposed issuance of this anandcant ic not-- ,

required since the crendrant does not involve significant hazard ,

considerations different from those previoucly_ evaluated.

- ~

Within fifteen (15) day: from the date of publication of thic notice in the Federal Resicter, the applicant c2y file a request for a hearing, and any person those interest n27 be affected by thic procccLing nay file a petition for leave to intervene. Recuests for a hearing and patitions to intervena chall be filed in l accordance with the provisions of the Co- 'csion'c " Rules of Practice," 10 CFR 2.

If a request for a hearing or a petition for leave to inte vene is filed within the 1

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2-time preceribed in thic notice, the cow::sion vill iccue a notice of hearirg; or an appropriate order. -

Ibr furthcr details with respect to thic c andnant, cce (1) a related hazards analysis prepared by the ibst & Pouar Reactor Safety Eranch of the Divicion of Licensins and R?sulation and (2) tha licencea's application 'for licenso cra+-nt dated Ausuat 21, 1953 and cupplerantal letters dated October 4, 1953 and 0:tober 22, 1953 Traich are available for public inspec- .

tion at the CoWcaion'c Public Docurant Roo=,1717 H Street, U. U., Washington, [

D. C. Acopyofites(1)abover.aybeobtainedatthaCo:nission'sPublic Docurant Roon, or upon request, addreccad to the Atcaic Energy Co _ icsion, Washieston, D. C., Attention: Director, Division of Licencirs and Regulation. ..

F03 TES ATOMIC F:E GY CCMMISSION

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[Scul Invina, Chief Test & Po.ter Reactor Safety Eranch Division of Licencirc and Regulation Dated at Ger=antown, Faryland this p' h day of OW/ , 1954.

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Licence I!o. R-56 Arand=2nt I?o. 8 License I:3. R-56, cs tranied, incued to the U..iversity of Florida, is hereby further anended in the follouin;; respects:

1. In addition to the activities previously authorised by the Cc=nission in License Ko. R-56, as arandad, the University of Florida is nuthorised to operate the University's Ar;;onaut-typa reactor located in Cainesville, Florida, et power leVals up to 100 kilowatts (ther:21), as describad in the University's

• application for an:nd ent dated Au;;uct 21, 1953 cud supple 2antal letters dated October 4, 1953 and Octcbar 22, 1953,

2. In cddition to other reportin;; recreirc Onts, the Univercity of Florida shall submit as prongt?J cs practicablo, but not later than 60 days after attainirs the 100 kilowatt pouer level, a v:-itten report to the Co-f csion -

of the results of the followins neasu e ant:: ,

A. Maxirca excess reactivity of the facility, not includirG tha vorth of control rods or any expericants; E. Fressure, flou rates, and inlet and outlet tcuperatures in the pri_2ry and secondary loops; C. M7vf c.m fuel elecent tea crature; '..

D. Ta:perature coefficient of reactivity; E. Radiation levels in the reactor ro =; and F. Ar on-41 concentrations in the reactor cell, cnd in the unrestricted areas adjacent to the reactor buildin;;.

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3. 'fais c andmant is effective as of the date of issu:.nce.

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Ey a;, plication cranindnts dated August 21, 1963, October 4,1963, and cetober 22, 1963 I poucr, the of level University of Florida its Arconaut reactor has requested frca 10 Ku to 100authorization to incrcace Kv. Tne incroace in powerthe maximum level vill require modificationc of the reactor cooling cyctc=0 and instrumentation.

These tcdifice. tion: and the operating procedures propoced to reduce hazards to an acceptable level arc diccucccd in thic analycic.

EVALUATIO:i .

Tne UFTR prinary cooling cycten vill be nodified to give a 100 KV heat removal capacity by replacing the present 10 Cpm pump bith a 20 cpn pua and by replacing the present restricting orifice by a larger orifice. Tne increace in flow rate in the todified systcc vill alco increace the rate of reactivity incertion ac water raderation is added during reactor startup. Ecwever, the water reactivity addition '

tdes place when all control rods are incerted c.nd therefore the inercased rate createc co additioaal hazards.

The capacity of the cocondary cooling cycten vill be increased by utilizing the exicting dump tan't as a supplenantary heat exchat;cr. Tnis vill be accogliched by placing a cufficient length of aluminum tubins into 0the ding tank to provide the requircd cooling capacity. Mater at 40 poic ani 7G F vin enter the tubing and be diccharged to a storn acuer.. If a rupture of tha tubin; chould occur, the prescurc I differential between the cocondary coolant in the tubc and the pricary coolant at o.tcospheric proccu-c in the tan'c vould prcvent ficcioa products in the tan'c water fron entering the cocondary coolant and bcins dicchar;cd to the stor cever. We

• believe that the cooling cycter can bc :codi;fied in the ennnar deceribed without affectins the cafety of operation.

Tcc coolnnt inlet te=?crature vill be clichtly lovar and the average and outlet -

to pe=turen vill be cli@tly hicher at 100 KV operation than at 10 Ku operation.

icccuce the reactor hcc a neGativo temperatu~e cocfficient, the cli@t increace in coolent torparc.ture and the resultin; cli@t incrcaco in fuel te=porature VH1 .

I averc;2not cause any adverse reactivity effectc. The fuel tecperature during steady ctate ope = tion or durins locc of coolant followed by a ceran VM' tot be cignificantly creater at 100 Kv than for 10 Ku oparation and at the higher power it vill still not ,

be hish enough to cause fuel plate datase. Tncrofore, we believe that the clichtly hisher tesperaturcs in the reactor at 100 Kv o;c= tion vill not cause an unsafe condition.

I Tne compensated ion cha=hers vill be decencitic:d to enable then to to used at the higher

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poucr levels. Tcis vill be done by wrapping tha chambers in cadmium or noving then further fron the fuel. Only one chatber at a tine vill be decencitized to that the effect of the chance can be calibrated against the other cha:fccr. In addition to I .

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.'., ,J 1 na eru;ca, the w.fcty channeln vin have their ceran cettin~a rained by a factor r ten to endale the. reactor to operato at ten tinea the prccent raxirav;a power

.n,.'.. Ma balicvo ths.t these chan;cc vin not affect cafety of operation.

.:fdition to incroacing the taxicnu pouar level, the cpplicant propoccc to increace -

c - :ce.ctor o;nratin; tina. Tac increased povar level and operc. tire; ti:r.a vin 1 ur: ace the yearly encrcy output by a factor of 200 and, concaquently, vin incrcace

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Iicansa naad: cut; tha applicant hac requc ted t.pproval of usa of a dilution factor 6: 200 to calculate concentrations of Argon 41 to which an individucl in an unrestricted hecauce the reactor is located in free. outcid2 the reactor building t;.y be c:goned. depression acrs c. group o m.reful, independent evaluation of the doce fron Arcon van e de. Our anl of the Icar

• ndic (a.tes which, that Laced on vaathereven if it byinapplicant, data furniched assuned tha.tannunption is a conservative for thic site), an individuf. rcr.inirs adjacent to the rcactor building for a whole there 10 year vcv'.d not receive c. dose crecedine; the yearly allowable dose litit specificd -_ _

Durins 90% of the year there vin be cu ficient air novenant over In10CF4part20.nu buildin3 to carry the activity a.;ay frca the vicinity of the building rapidly and. . _ _ _

in various directions, so that the done contribution durinC thic period at any cac point nu311cib'.e. . Cur analycia indicatea that c1thou~h the individual adjacent to the 1r:aldf ng would be expeced to a yearly doce hip.cr than that for 10 Ku operation, it ic

.<c'- likely that any individual vill be c;gcced to yearly avera ;o dosas creater than ,

au obtained by bains cubnerced in an infinit : cloud of cc:2cus a terial with a omcubratica cqual to the linit spacifica in 10 CF2 Parb 20. W believe that q;aa-41 vill be the only radioactive casecuc efflu.mt of ci~nificance during nmal

ratien. Since the doce from thic inotopa la tolerabic, va have conciuled that

.bcre vill be na undue radiatica hacard frou ca.caous ch'luant frca operation of the racility at 100 Ev.

ne mxitr. credible accident for thic reactor was previously pontclated to be an

.cataat=couc addition of all the 0.6% delta k/k ex cas reactivity availabic, vith the reaultinc excurcion caucing li*.tle drage to the re;.ctor and no releaca of ficcion

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I":e'lta k/k and the mxinu- credible accident pontula.ted previouuly vill not differ for 100 Kw operation. Wera vill be a hicher hc';.t c;.acration rate and a higher

'isaion product inventory at 100 Ku opcration. Although va.bclieve that ficu blocka:;e ,

n 6. chamcl is highly unlikely va hava pontelated c. flow blecha;c leading to a fuel plate nultdova. If fuel n21 tad or fission products ware releacad frca c d:cagcd. fuel cic ant tha ficcion products vculd probably be reta.inad in the primry coolant. Hovaver, even

• f it were an;u cd that ficsion products frcn a fuel pit.to vare ralcaced from the ai;dirJ, the doses vould not exceed tha criteria of 10 CFR part 100.

.itb0cch dose rates around tha reactor du-irc 100 KV operation vill be ten titen those -

>t 10 Ku, va believe that with proper health physics control, ds:cc to individuals verkh; in tha reactor roon can be caintained less than the allomble quarterly coses pecified in 10 CF% Part 20.

Tne applicant vill use a ctcpulce apprcach to 100 Kv cperation. "na stepulce pro;mn

.ill inv01/c cprc. ting the reactor for ninitun periods of 4 houn, each at succeacive

);ver leveic or 25, 50, and "($ Ku prior to opc= tion at 103 Kv. After cach increace in pomr icve'., the applicant will neanvre terparaturen, terparature coefficients of r,cctivity and radiation leveln around the reactor, vill tonitor Arcon-41 activity, I

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a-7. vill c..'.1Lrc.te the ion chanters to verify tha values predicted in the Ihzardc

&.r...zy Report c3 tr.:.nded. We belicve that the procedurca to be used during increace to 100 IGt provide rcaconabic accure.nce that the health and cafety of the public vill

.o'; b : cad 2ructed.

a rope barrier and a t~irning cicn vill be placed just I Dit.rin;; opamtion cide above the reactor roon 20inlet Dt, door. We reactor operator vill nonitor entmnce -

to the rcon and vill rectrict entmuce to those sho have a necd to be there. This will add accurar.cc that no personnel vill receiva quarterly doccc above 10 CFR, I Part, 20 limit.s.

COIA v1c authorized to take nodifications in the coolin3 cysten and inctnnantation of its ib;;onaut rcactor cinilar to those dcccribcd above in order to raice the taxinun pouer level, initially by a otcpwice approach, to 100 Tct. The UCIA training l reactor achieved 100 Mt opemtion in Nove:ber,' 1963 F. acured cysten paracoters j vere very cloce to thoce predicted. Eo adverce carcty effects from hichar power

! operation vere evident.

.C._O:.CIESION .

l In view of the foregoing, we cenclude that the ircreace in power level does not i

involve cigr_1 fica.ut hazard considamtions differact from those previously evaluated and that the University of Florida Trainin3 Reactor can be oparated at povar levels up to r. maxitu of 100 KV vithout resulting in any undue hazard to tha health and ..

cafety of the operatirc parnonnel and concral public.

FOITiiE 150:CC E?l.GY CC:02SSION l ;i .

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RADIATION CO:1TROI,TECilNTQUE G21 INSTRUCTIONS FOR SM1PLING Int!D DISCllARGING WASTE IIOLDUP TANKS I. PURPOSE: -

To establish a proccdure for the reci rculation, sampling, and di.scharging waste water contained in the Nucicar Science Center waste holding tanks.

II. PREREQUISITES:

A. Keys to padlock which secures gate to holding tank and to room 110 NSC.

B. Piping system clingram (attached)

C. 100 ml container D. Rubber gloves '

III. ' PROCEDURE:

A. Recirculation of Tank

1. Obtain key to room 110 USC and to the gate of the holding tank facilities from room 212 NSO.

I 2. , Check the w'ater 3cvel in the tanks by rcroving the small red plate (located on the north side of each pump housing) and

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looking into tank.

I NOTE: 1he tank Inuut be pumped before the water level riscs to within three feet of the top of the tank.

3. To circulate the contents of a tank, close either valve E2 or

-valve W2 (discharge valves to sewage system). Open valve El or valve W1 depending on which tank is to be circulated.

4. Proceed to room 110 NSC and locate the holding tank pump breaker box. Verify that punp ruin circuit breakers are in the ON posi-I tion (red indicator 3 amp should light) . Turn the purp nelector switch to Uf,ST or EAST depending on which tank is to be circu-lated. The groen indicator lamp shoald light. If the green indicator larp does not 3ight, verify that the main circuit breaker in ON, then push the kESET button (on the purap control-1er to the IcEt and below the pump selector switch) .

Allow the pump to operate until the equivalent of twice the tank volume has circulated (about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) .

B. Sampling tank contents

1. Af ter proper circulation, a sarrple can be collected using a 100 tal sample container. Pill the saraple container by opening the sara-pling valve (circulating p ep running) located near valve W1 or El. Af ter the sample has been obtained, the purp selector switch D-1

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can be turned off.

2. Analysis of the sample shall be performed using Radiation Con-'

trol Technique #7.

C. Emptying west tank and rerouting flow to cast

1. 'After the sarpling analysis has been completed, assure that the lll e

concentration is within the limits specified by the MCP tables before aligning th'e system to puqp into the canpus sewage system.

I 2. To' empty the west tank and reroute flow to the cast tank, open valve A by turning the wrench handle until indicator reads OPEN, shut valve B by turning handle indicator reads CLOSED. Open valve W2, close valve W1. Close valve E2, open valve El, turn on the west pump as instructed in III A.4 of this procedure.

The pumping of the west tank is automatically terminated when the tank is empty.

D. Ezptying east tank and rerouting flow to vest -

1. See III C.1

2. To empty the east tank and reroute the 510w to the west tank, open valve B by turning the wrench handle until the indicator reads OPEN, shut valve A by turning the handle until the indi-cator reads CLOSED. Open valve E2, close valve El. Close valve W2, open valve W1. Turn on the east purp as instructed in III A.4. The pumping of the east tank is automatically termi-nated when the tank is capty.

IV. RECORDING:

A. Liquid sample analysis

1. Record the results obtained having performed the liquid sample sapple analysis outlined in Radiation Control Technique #7 on the proper radiation control form.

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I ATTACIIMENT E '

(Question 10)

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a DIRECTOR-1 t

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Post Control & Fire P2diation Control Coordinator Biological Safety Occtmational Safety F C C'A T N?' I R.C. Officer Unit Manager -

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R.C* '*"cchnician Pcst Control Building Post Control Industrial Accir'.cnt Prov.

' Supervisor Inspector Supervisor ,

Hygienist Officer 3* "" ,,','

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Clerk IV

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ATTACEDEIC F (Question 10)

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e-I ADMlillSTRATIVE AND PROFESSIONAL CLASS SPECIFICATION STATE UNIVERSITY SYSTEM CLASS CODE TITLE RADIATION CONTROL OFFICER DESCRIPTION

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Develops, implements and administers University-wide safety progran.

Reviews radiation safety procedures, equipment, facilities, and training of individuals prior to using radiation sources to assure compliance with Federal, State, and University codes, rules, and regulations (e.g.,

U.S. Nuclear Regulatory Commission, State Department of Health and Rehabilitative Services, Food and Drug Administration, Department of Health, Education and Velfare, Environmental Protection Agency). De-velops and conducts training programs for potential users of radiation sources. ,

. Consults with potential radiation users and evaluates all proposed pro--

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' 'cedures which' involve the use of radioactive materials and radiation producing devices. This includes a review of experimental procedures, --

safety equipment, radiation detection techniques, radioactivity receipt and disposal. Evaluates from a radiation safety standpoint all pro-posals to use radioisotopes, radiation producing devices, electronic product radiation, and radiation generating devices. Approves or dis- ,,

(, - approves such proposals (i.e., disapprove proposed project because radiation safety practices as described in the experimental procedures are unsafe). Serves as a voting member and secretary of the University's official radiation control committees (University-wide Radiation Control Committee, Human Use 'of Radioisotopes Committee, U.F. Training Reactor Su bcommi t tee) . Evaluates complex and of ten unique research hazards by applying radiation safety principles. Deals with all levels of the administration, faculty, staff, and students and must be able to work well with all of them. ,

Analyzes ef fectiveness of radiation control program in reports to super-visors, develops policies and precedures to improve effectiveness, and sets proper goals and priorities for the radiation control program.

. This includes programs such as personnel monitoring, raterials safe-guarding, emergency procedures, inventory control, and waste disposal.

Coordinates Radiation Control Department functions with Occupational Health and Safety Department's responsibilities to be consistent with all operations of the Envirenmental Health and Safety Division.

Has authority to stop any radiation use procedure which is a serious -

potential radiation safety hazard.

Responsible.for complete knowledge of State and Federal regulations which relate to radiation protection at a university. Interprets ap-plicabic codes, rules, and regulations relative to radiation safety.

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i AtP CLASS SPECIFICAT10:1

,. SUS RADIATI0rl C0!! TROL OFFICER Maintains records as specified in Federal nnd State regulations as well as conditions of licenses issued to the University for the possession and use of radioisotopes and radiation producing devices. Maintains such records and assures their accuracy.

Controls all orders, receipts, and deliveries of radioactive materials and radiation producing devices to insure University compliance with applicable codes and regulations.

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HIiliHUM Q U A L i F I C A T I O !! S .

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Ph.D. rsin Radiological llealth.with two years professional experience in radiation control programs of H.S. in llealth Physics with five years professional experience in radiation control prmrans. Practical ex-perience t,hould include 6 broad background in radiet_ie'in pr<.n.-ci. ion, radiation detection and biological effects, and overall accepted' health

'. physics practices.

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3. d.weau:. . h.~ :nt- New ,. ,;.p t. hJg E ;-i 7 j.--s .

1 2

!! 9-55 7 N'A' 4[15. Fend Cod:f-:6./c n:y ltecne

4. Sectim::

Ad.::TnIc tro tI Ya__AffaI r . - N.'*_W -- .

Clns Cod.- Cbu Tit'e M-T " N'G.'N.- _ .. m are ~a 3.,:.:p Nau. I 17. -

=

Envir : me.2Lihabit.J. sa-t ,' # Ic J e

" here .W . . '. 'I' A W..: : IP '

.h.5.S.h:ioru r:5 M ;*.v~t r~*-al r, o ,,1

~-

c.u.. M'd.';- -- - jg U S.E ~.52535 ,

R M ietico centrei Technici ~.

6.Co my:~.

-  ! CODt. 7. Ci:y: . ,  : COOT H P . - -

. ' _. y.:M' '-

Alachua - . 5.( "' R . " - ' *

.l r.M.. _ , Ca i n esvi l l s /. mM jp. Io  : ' -' ? ".+

18. Dates zal Respe:unt.hu:s:

.we.m l

wm._,.w m.,

sor '

.: n:

..:. ->L * '

, Time d ... . v .,  ;

.g. ,

y. 3. .. . . . .,.

.,.r... . . ,

. , _ ,e . f ,,t g A .L

. a .,

',3I "-g'. :. ,. ,.

10 .e y.cnducts radiation pratection r:enitoring to casure that no radiatic, t-erker or 'the ce.ner I

publIc !s ever ,cxpcsed to- hamful .leni.; !ng radiation. (P.eg.:iar) . w. .- -

3

. +..

10 ,

insp-: cts radiation facilities to identify the presanmof truae. fen.Liu ecats.=:in:2t!co. 6

,- [ Regular) ~ . -

' - v.f.W - :. < .

.-n. .

.: . Y:

-+ , ~ ,.; c.v..::.. ;.b : .:..:,.-. _. "..

_ n .. . r, ; . : = -

, =

s

. .. . .e.

l10 ycordinates radiation protection activities in the flu: lear reactor crea cr.d th'e I;uclear sub-critical facility. (Regular)  ; - e -' -- - - >

, ,

. w .c n--  ; *

._; . -i ).

\ .

,1 1: .

l 10 Controls use of radioactive cources and vdifies that they ME used by' qualified persons..

bqular) ._

o i 10

{.allbrates

. urvey Instruments radiction detection in prc;sr torking ifnitre: ents crder. and (Periodic) Is respond $1o for tz,_inthining portabic

~ '

s .

.u .. . 4 .

i. . e. . :. .. ..

logi nuc1 car detectica Instre :entationpgeonstrates radiatien ' " safoty \

t'echrJ.que.s innd 'ccndu

. \

. (Periodic)' iJ M5' Ccadu ts leak test cnalysis 'en saaled radicactive raurce to dat=t pessible rolius of' hadicactive raterials into tha envirc unt. (Per!od!c) .

(1 5 yaintains records of surveys, tests, and evaluaM: ens for eximi= tie- by Florida .* yr::ar:

cf Health ced Rehabilitative Services officiais. (Regular) , -

ll4 Determines radiation ex;e.ure of perscas involved with radicactivity. (Pericdic) . . ' . . .

'h fj eceives, stcres, and dicpenses radioactiv- nterials being respensth!c for dete=Ining that they are safo and leak free. (Regular) ,

3 Pevims f laventories of radioactive ::ater!ci sub=:! ted by invs-tigotcrs to insure er,tplian tjith their proposals cnd that the quantitles do not exceed lic -nsed qu.cntitics. (Resular2 b

3 vonsults i Regular) with potentici radioisotope users and advises then of radiation safety procedgro

---Sco Attackd Shet---

P? C-1 ATTACH ADDITION A1. SHEI.TS 1F NECESS ARY TO PROPERLY DESCRIBE THE f OSIT10 J

,P-**4 % ^NS ***swe=e maw a =,.sm sw%ser. w .wmW=vwvee ws., >A,w . n --. . . ---.--"I'9-**'r*"5*-- '

i - - - -

1P f f V. F* t i e' C C P Y 2. O L U t- . C C P W J. C. .f L 6. f4 C O P Y A. C A N ARY F-3

L -

or 1 ime ,

l Serves in the absence of the Radiation Control Of ficer.

L3 collects environmental samples for determining amount of radioactivity in air and water wi thin controlled v;ork areas. (Periodic)

, 't

~2 Coordinates radioactive waste disposal and shipmant of aaterial with long decay hal f-lives to approved burial grounds. (Regular) .

P,aintains pocket dosir>2try records to prevent radiation t;orkers frozn exceeding the maximum permissible exposure. (Periodic)

Performs bioassay analysis for detecting possible ingestion of radioactive materills by radiation workers. (Periodic) u2 Developes budget estimates and supply requirements. (Occasional)~ ,

I Directs decontamination. operations arid advises departmental personnel en techniques and proper procedures. (Occasional)

I Performs,dther related safety and security tasks as required. (Occasional) en-I e

4

• e g

I . .

l e i

e I .

e e

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e y-4

. . . '. a- -__

t > pt tw. i nur. Sect. S/S:ct. reit.n m,

- '; DEPARTf.ENT OF ADZNISTRATION

= - - - - - . -

DtVIS!ON OF PERSONNEL  :

om(.oa-c* u:w.e imc:

' ,,m m.i afsn.;

p + )

,i , ~

POSmON DESCRPTION -

P"I bW . r.ws euu ,.ca~ z . z. - - a-2,;wa u p.;.c:.

. +% r 6% m-c a- +w.,ev.2-sw . . .%. _

._y.,j,_ ,_,,7,,,g._ ,,,. ,,

Sbad:a nas ta be cor. dmd by A:;ency I'nwand OSc r l CODE [ A !.mpfop: Nex:

1

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% - * .7 *.e..-e.4-..-.

s e, sm. g . , . [l p_sn 3.4 . ,. n 3 r. 4 r ,-. 4 (-( ,q . ..

2. im. ..a n.

u r ym iu. -.'iTETU~'Po.ma sur.,

, tw=. . g 'rg. . g .u =m coJ.: 10.sut

-vg;--w.p. c- 1 8 Uniwesity c4 !?hrica 'W g 9 E. rb M. . .wn . . . -- :. 1"> ' - - - - - -

L lbn:u r. = t 1 w ra./ 3. . .c._. tH,^E i *- . und Co;. n:,. ecc ye m ;33 -t. n e t.uc-nq

.=;..wl v-..,pD

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4. S,:ctun:

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em. a ra R v=y . v. , : r. r,, g, Radiation

5. suwctm.: .

Control Technician.

~

r. c. :L 6.T;. - ,

- ce- 9 t. 5- - . . . _ . . - . .

t .:..

6. County; --';* M + '- a_C  : ~_. q-' & , ,, 7. O ry : .- * , , . , com: Pv

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t.1 chua W S.. , cal m :r m

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ya .

, : . '.d. r.M,N . '. : < " . d.;d. , .. . ./.'.Y. .'h . - '. . . > .x 1: . :>._. ..a... . _.. -

E. I:E/ u.w 7. -.% ,d I w. r::n.

...g....

l .,15Tim::verb..=1 r~M &. .n. +.

... ~..

m.p ctncti:. ! ~;ac' ' a cn c ,:; -- : .'. c'-W ~^ .---- ;,-ma :5 ca=tacn to r.nnc:a th: t r-W ntion ver.karc er rd:r n2 th-+ cared 1,..*1.* n cm uut'ur.necessarilj c=p::r el to .1M -ing or ror-

• Wy - M ' * ' r,. (= ;--' *~ ) I, s . . _

• ". i , W -.

- :. . -e.~ .,

. > . :. ' l. . . ., .

l I .i:.6. :T.r :.ceca-f .

h ia

' +.sm

. ?

r:

Wiit~ M : n

.dlatica fc:Hity i=.

=ctic:  ; to JZ-W-ld'7 tb- N e w M p ro

-B :%,-::...i w'119 15 c re:d! cchit cc:f -W.ica r.na to enanza th:t radic.:cth. iwt:aM f.a rdntal=5 . '.

vithi.n State r.ed.rd c 1 stiful!;wli. .(rd.ic' ar) ( M O 1:0:':) -

a ,. , .

. t t .' . ,  :' .u -

I 13 p2:Imm refieJ.ca teeecPn 1up-cthes S niret:r- '-o prear.:t r:4htien to. em: 0 co. :'1 ' -~ u.',th Stata (lC~)-50) L:33 Echr:1.(21 c?n) n.-wncina. (r.gder) .

pa s- -

f .

r.icro.::.a m ernr.: ~. 30 - ,. LACF.D. uni.ntich - ti a rirytted electrua t ' mc=pe 2 - 31-. . . ... . . . :. ". . .

. re'" - g: C'E tolin , ..

.  ; f ' -

.}'

an 1 7tien1 y e.p .:- O r. . ~ ." , . - . . (Dme.21J balcal,. Vat:r.ri::wi) ' -- ',/-

fault:ca Z :4:.y cabinn5 - 5 .. i. flc - *c0? Ic - 9 -.-

I~ Ultr;.-Violut cahh.ut - bha Nica:'td - - c.*initir2 *- G. ' . I .'. ~ . r '_ 3 .

l ..

Lm~.~u t==.t= n r W~i=n ==f 't7 t=^^^ ' . m L'^ '~ " ""~~ " "' E " "'

• L=&L==

l13 radicAv1n t.at .:rbia uith deconatz.2ticca o verite.m t;rp :a c.2 F;;tabh :=d fi d ~

d vc u d.bn Ghetien 1:st:c:,mt:2 tion. (?r-kdh) .

~ .. . -

Purfor=s b alth A. ica 't';On aar.Y: fat-3 tith th. t: .a or re MMot m; c:a ce.aloa 10

,l r- ' 8 r. -hiv > ror.::ca at Cher.'_a vaachbg ro9pital ma th% Cri w e'.llo Vet *rren F "~

Ibapital cuch ans (=pl:c) 1) *i~' M's c" he. gi'.2-1 c"" ' n.s to t%. circ t=4 .

re.r;Ap=ent of radio &:~titM P*.thatU 2) PD8 E*;l IM.I21 MO 7' N D M b f F03D N cni i u::-t sying c...O &<Cu'-c. art.iaatira for patinntil that hnWiz .

c t:w3cracy nat=.tctivo irphata - .

b, pare.:n. int rcuiz <tiw b? zr l t3 - - -

C, thrn,htic c'c.".i of r':S13id ';;'PM

[d' 31 I::n: g.m=y =c-m o-wien fer reliuticn cracaltics -

~

h CGntinCw't cn nttac' rfd che-at

)

D!' C.1 ATTACH ADDITIO.N A1. SHEETS IF t'f CES a HY s T O PROPE Rt.Y DESr. RIME T Hr: PO'.tTIO J

...-%.,-~3-w..~,--.,..-.v.n-..1..rn.v.,~,.---.4 e-- s w .-

OPT I . .t T C C C P F 2. f L L E - C O P y 3. C a f ( re - C O P , 4 C4.AHf

).'

5 . r.

o. .

L. ,

'5. IEatics and Retponsibilitieu continued:

[

] S of 5 Tina 6 Perforas bioassay for detection possible internal contamination'. (regular)

1) Radio-urinanalysis with I.iquid Scintillation Coenter

2) Thyroid rtonitor with Multi.--Chc:utal 7.nalyzer

3) Wale body counter 2 Advises depart =.ntal personnel on radioisotopa handling 1.cchniques as to type of decay, energy of decay, proper instrumentation for particular radioactive caterial being selected, including deconta.,1 nation operations.

(.

l 10 Calibrates radiation detection instrucents and Inintains sa ne. (periodic) e Receives, stores, and issues radioactive naterials bhi,ng " responsible for deteH"ing that they are handled in a safe runner. . (periodic)

I 2 Maint'*"n inventory of and conducts leak tests on sealed sources 'to detect posgj.ble' release of radioactive Interials into the environraent. .(periodic) s.

2 Asst:nas other related safety and security tasks as assigned by the Padiation Control Officer and the Director of the Environnental Healt.h and Safety Division'.

I '

1 (oCCasin M )

Takes wat2r and air serples and analyzes them to deter nine the amount of .

radioactivity present in the environment. (periodic)

[ .

Controls .tssua,c- or radioactive sotuces and verifies that they are used 1 -

I 1 by qualified perr.cnnel.

L

=

P=h tains dosinet y records to preclude radiation workers from exceeding the ::ay.intet pn- 2 ssible exposure. (occasional)

I 1 Cont ols radi.cactive- vaste disposal and ships naterials with long half-lives

- to a ?cderally approved burial ground. (periodic) e m

e 6

I .

I "

g

, . m a t. u.- i L u n w  ;

s

' b '

• - Ikpt. Ir.v. I s,:ct.

DEPARTMENT OF ADMINISTR ATION ' - Ikr. sl2ct j Ps.nea t,

r. ' DIVISIOid OF PEHSONNEL .i^ Cbu Code;

-~ ^

-~  : -~

l t::cc;.we Dat;;~--~A~A,,p: owe d t,j Dr.c;

. 3 POSITION DESCRIPTION ,

'- ~

- u=4.e ;w,.,.m.acm::sw v.s.o s.,a .:.t;.w;.

w w- 1:w- - '; -- - www mes y,,

..,.u .

g .m mw.,..m.g.y ,

, m ,.

Sh2JeJ am; ra be compr e ted by Ayrcy Pmonc:1 Oi5::t l CODE U L Dnpbyee Nwe:

1. Dep2c;nent: (N

h. E &I ~ 's.

, ..i:%

.k._.DEIs IOfLOY,_ IE.LM.-1CE}_ tiff ~

'm u'4COIdOU It + E n~-h'T.4

2. Dakon: j. [.. Itttu:2.m Ca.6 310. Sh2: a L nf. Iur. . c d.H c J 3. ro.i:i:2Nw

, ":I'nd fm:m ( hm. ,$ " -W ".l Un I Y a r*;I tv o f Fi tri .d.aa_

3. Par m :

,henct. > N e ,. ; p14.nua p t n, tty , . . . y ;. !!5. Fr:d Cod:H6. A;::cy Illecti :Duc-l ' -.Wh l 77 lt E20S

_AdnIn I 5trntIYe AfinIrs N. 'e.' . . ' fl.T. . h%.-. .' 7' -? ' W <-I'.3I [ -.-: m . -i',;7.c,;71

4. S.:cuorn I w ..n Nm, ~ si 17. CLm Cofe -"-~~~~---~~

'Cindid: ' - - '

, Envirenental Realth c Safety Div.

H s. subueno i:

Me ^dP

,V.gm.t  ; n.:..

-dRE

%v.3.L-. r- .t..m.. .%. ~ w~ .. %_. .w. . . %. ._ h .

I 6. Radiatica Coa:ay: Centrol r. hd. Servicu *;".r..,.c%js. #.N -

4.pDL 7. City:

- s 3- . .-  : wn y g..: .. 3 CO D .- G; g P . ',

Alachua cainesvlile . - -.: L.a . -- . o - - - - . .-

ms'.

(l e

4d y3._;,

'"s *'-r; j; o -

• p m -; - m. _ n n e.ac.aw.~w-.%  ::,fr e; wwwww - anyg.e - _ , .

. _ . _~" g i8. D(Je$ 2nd RCGOC.nDM.tS: '

~

.'., n -

+

l' g, g . .

.. x .. .  :. . . -. . .  :. K . i" . ..- -. .~. . , .y -] . .-

Tur.e; - r c. , g,.,:4. , p;..,.gj. 7.< ,g,, ,q_. _.

,- , _ .7 13 centrole rcdioactiva uaste disposal cad ships mtcrial uith ichg inif- [vis Yo cpproved creas. (R2 sular) ..:.. ..

. .;.. .,. .,,, ....a - .* .,.g . ..

~. ; , ; ,3 .r ., -

, -i 13 Perfor--s radiat!cn protection Inspect!cns to insure that ra wrker cn the pu5tle is cym t

Lg .

c:qcsed to haredul icnicing radiatica and that all radioactive c:aterial is handled in cen;11ance with State cnd .sdaral regulatiana. (negular) --

g. ,

p 12 Acccepif ahes redidtIcn facility inspecticas to :Irbatif'/ tin pr5-n. .9 of r mv51c -

tl .

transferable centasnination and Insure sufo 'lovels of Icnizing radiation frca fix-d '

seurces. (Regular) ,

. . n. - : . . . . . . . . . .. -

.I I 9 lbintains dest =etry records to preclude rcdicticn t Ork- r ; fre ; emeding the r:axicati permissible expo ure. (Periodic) ' '

- - - - # d l 9 Controls issuaned of redisctiva sources and varf fles that they cro used by c;ualified

, percon , (Periodic) - - -

i.

i e.,9 p7 Paintains Inventory of cnd ccaduct: Icak te:sts en seal:d scurces te ade::t possibla release of radicactiv: reaterials into ths enviren ent. (FericG& .

.y.

, q7 Der..nstrates rcdiatica safety techniques end assists in classes involving rch-che sources and nuclear dat*:ction instrttr. ntation, (Periodic)

. 7 Receiv-s, stores, cnd insces rcdic::ctive ratericle being rech:mibic for deter =Ining 3

that they cre handled in a saio ranner. (Resular)

I

$ Calibrates radiatien detection instrtrents cnd is responsible for keepin ; portable surg

'j reaters in proper vorhini crder. (Resulor)

, la Assumes other related dare*y cnd security tasks as assigned by the F.2diation Control l[

t t

Officer and the Director of tha Enviremmntal Ibalth cnd Safetj Div!=1cn. (Occasicaal) i 4 Directs decentaminatico cperatiens end advises depart =.ntal perscnnel en techniques end I,

prcper procedures. (Occasicnal) ~

) ----S.m A t ta ched Sh ee t----

- UP ol ATTAcil ADDITION AL EHErTS IF MECESSM1Y TO PHOPEHLY DESCRlrE THE PostTlO'J

!i e- -.. - , , - _ - w ., e , - - m m .-+-r % -- - - - -< - - >-- e .+ - - * * "

l c o n s. v. n o r c o p y 2. e. wr c c e r a. c. .> t t r* . c on v cum l

F-7 .

~ / -

' 'triespons i b i 1 i t i es (cont.)

'3 Maintains inventory of and perform; pariodic inspections of f acilities using-devices i which produce non-ionizing radiation. (Periodic) 2 Performs bicassay analysis for detecting possible ingest. ion of radioactive elements )

by. radiation workarc. (Periodic) 1 i

1 Ta'<es environrental samples for determining the amount of radioactivity in air and water samples. (Periodic) ,

l l

E. ..- .

d g.

I * .

I l

e l . A I

s N

.gl.

l Y

1 i

9 I .

I i .

I Y-8

~'^ GTATE OF FLOHIDA l{

1

• . "tyt. b .. m. ~. t. s/ sect. Poited.3 DEPARTMENT OF ADMINISTRATION cthu,o&: ' 4~ - =

DIVISION OF PERSONNEL

-1:eca.e D :e; A;p ,,a gince.

"'"I T

POSmON

?ypwriter DESCRIPTION e: = ' ,---, mmmm o, p w,wv .~ n v ., o s, + - e:- . n , _ mme.muwnsn_ (_ g., g, ,,,.44pm,p , ,

S se.:2 areas :o be cora;&:<d by Aunty I'erscnnel Of6cer l CODE ( 8.1 ##n Nana:

l  ; ,q.,c, K.w . tl l

1. Departatent. '

Divinion of Univ < rcities (- - - _ . rebara _ _ . _L. Stevemon

! ,.f., ,

Fnse:: ? .'.: - 2 Ntr

2. De. .n:

i. L. -

Univercity of Florida ~

'I fh 9. Irr.%nion

>>7 -lCca:0 b_O. .25ci'l11. .. { Pay j P.c:. i t2 E1670

3. 1.o rea u. , hy t*.*v , ih4. Fud;et EnTy ,. (15. I und Cod:'!b. Ap y UfecG: Me

> ;z=inist ative Affal: a -

.k .

- ,.'_ -l ,1 - - c a - - -

t_

I 4. Seebon:

h. e se n t New. . . . s017.

Om Coh G u hd: __

l'nviron.3. ental Health G Safnby -9.-- .~,dP

5. Satuct:ox niolcgic;.t1 SaEcty l h s.nt , N:w -

f 500'13 Secretary III Ij h. . .d i'.*._t.io_ D Cont cl P. F'diolocicN'=#

• * ' ~

- m d S.

6. Coun:y: d)D L . 7. Ctry: . CODEf P

~~w :- -:.= . .:.:. .: R .

W; ho - -

Alach'.'a Caina.svill's w e.

> C.! l

->.c.s # w ,e:.c,.3 w.a u % u m .c,..P.: U c_ m,,.._ _ _ . _ , - __ m _

I1 l e.-. - - - ar.J Regonn:Jnns; g

18. Duues ,

4 .

This Ix:mition providen secretarial nupport for two unita - Radiation Centrol and nadiolcgical Ee:vicen anc the Liological safety Unit, _ _ _

20 Wto and transcrib., dictation; handlo and typo routine correcpondenco,' requisitions ~

nna rinatons type caterial f6r reports and cancales ::aintain achedule of activitics for Radiction control Of ficer : M Diolcr;ical refety Officer; cchedulo ccrrittee

- ceetinga, type and dintrihete minute:4; preparc doct cents and info.. ation caterial for r . gnus *.<1de distributica; receive telephoae calls ed answer questicna related

, to the cmaration cf both cait=.

Maints.in end entd.ilish no need arie:es, filing nyete:2 for both talta to insura 12 nccountability for location of Radiation Centrol licene.2, reguirtlona, presc:al and I: reinted doc.::>-nts for usara of radioactiva catorinlo, exposure records for past and fl present cyploye+a, vasto di sposal ranifests and recorda, ctato and federal sittac-linea for biolodic51 rem arch, ce:mr:1 co respondence and natert.C o for su iver11ty t cc==1tt ws. .

i i

lf G 1 eep curreat' e$:posura records,. log fila bMgeu for deli : ry to univeralty p-:rsonnal -

j  ;

at:d cc~,ailo infor:satica frc:t these recorda upon requent.

4

,1 j

30 Pr-acesa purch:sa crd :rn frc=2 rsans, carg.uswido, of radioactiva r.ater' M nnd ensur2

?

,1 i

that estrbli:fmd procedcres are follo' red ed records nre cccurata and cu.rrent.

b share re-ceptionict dutica ith ot2:er Secre'ary 7?I: greeting and routing grent'

![

t

[ l lo cr.d ctnientn, answerits phons :a and taking wsnas ea.

i 2 1 :2ir.tain 73 Indga reports r -J nr%r: .

i i'

Schedulo chort cours.pn cna preparn related c.::,terial na requented.

h[ 5

, 1 Schedule travel and preparc reirburcemnt vouchera for ctnff in both enito. -

d D

c E, 2 Dally pici--up nra Chtribution of call for riiLG Division.

E

""3""^t"u-e S ^3"lat cnd fill in, "honen'r neca3"r7' in ""7 ^2*" 2 th" '"vl"i"' "d

$5J 1 i s  ;

1 }

o . _" W .. . ~ ATTACH ADDITICPAL SHE ETS IF NFCESS ARY -TO PROPEHLY DESCumE M FO5 MON = . - . _

c ri.> r 6. e t r L C O P r 2. r w t - c o.a v 3 rvti9.rort4 ce..4sa E F-9

~

v , DEPAnik INT OI: ADM!NISTkATIOtj ^ r

• "- D"'. Snt- Sisect. Pou:.w. No

{ Eur.

I - DIVISION OF PERSONNEL

't '

i cLus c.a n: et

--~~.-- m-

, a;;;:oma p y fonc i a .rturu put:

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-*.4.r. w ,- ~.+ .

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- ,. (Regular) In pects radiation .- fa

llities to Identify the preneccrof tn=re. Led.zie centa=:Icat!ca.. 5.:

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c; .~t-d

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:v w a.g w . - : .  : .. .

. . - . . : . r . .:- .y. 21-.

10 1 . , gentrais .

Laoguicr) c ;c of radioactive sources and ve.;1f!cs that they arE cred by'q.:alified persen-a

' 10 galibrates redletien detectico I,'dtre ent: and I; responsiS!c for umintaining rarteble

.,urvey instrc::ents in prcper nrking ceder. (Periodic) ' '

s. . .:. ,. - ~p. i . .v. . . . - .

s ..k. . . ,,

j ljgo 9 , .

in.%1..!d'*e.althPhysicst d I ,gi nuclear detection instrc=entatien.p::enetrates (PeriedlP)' ' " *'il rddiatien scinty techn s .: - .

p

.1 5 ycnde:ts leak test analysis.en sealed radicact!v, sem c a to deter ;m-..ihi3 re.it m of..

I!! 5 radicactive raterials into th-s envirc::ent. (Parfodh.) , .'

I -

7laintains rer.crd ; ci surveys, teste, and evaluaticas fer c:d_ !.,:ti = fr/ Ficrida C.part;:"

cf ihmith cnd Rehabilitative Services officials. (Herular) ~ .

4 Deter:n nca radiatica egosure of persens 1.hYelved ulth radioactMty (Ferichic) g '4 fjeceive s, stores, and dicpenses radica:tiv- r:aterials being responsih!c for deter =1ning y . that they are safe and leak free. (Regular) , , , ,

3 Tjay1ws inventories of radicactive ::aterial subs:ltt:3 by inva-t!gators to inwre ccmih l, ylth their proposals and that th. quantitles do not erm.d IIc--sed gf.rntitles. (aegula; 3

i on3Olt3 Regular) with pctential radIOIncto.C uscr3 and advises thm of radiation safety proc d{r l --Sco A t t a ch- d Sh: e t----

MC.1 ATTACtl ADDITIOT 1. SH E ETS t r T.TCES';t,HY TO PHOPE R!.Y DE SChlP.E lif E POS!ilO'J

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I nuclaar \ d=tection Instrc.:=r.tation..(Pe riodic)' i2 \ ..

2 _ . . . .. -

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5~~ ycnducts bk test analysic cn scale!! radicactivs dsurce to c te pz- l FA reNaa of I

y5 radicactive r aterials into ths enviren=ent. (Periodic) l 1laintains record 3 of surveys, tests, cnd evakti=ns for czie.in=tiw, by 7:cr:dz wport=..

cf Hnalth and Rehabilitative Servicca officiais. (Recular} - - .

. .. a.,.. ,_

i 4 Detemines radiaticn expsure of persens liwolved with radicactivity.. (FericIdic) 4 fjeceks, store-s, and dic;nntes radicactiv mt : rial.~, being resdens151.2 far deter =Ining

.that they are saio and leak free. (Regular) ,

l . . .

3 Ijr. views inventarles of radicactive ::aterial ta::!:ted by invc:tigatcr2 to inaure ccep11:

ylth their prc;csals and that th. qu.antitles do not exceed IIcensed qt2ntitles. (P.23ala; I

I3 qcasults 1 Regular) with pctential redloisotcpe users end adybs thm of radiatb safety precede y' P?C 1 -Sco Attach- d shut-ATTACt! ADDITIC J Al. SHEE TS f f T.'ECES57,3Y TO PHOPEfiLY DE SCHtHE T!!E FOstTtON n n. . ,,c. m w . - _. ~ . ,, m . --<.~e - -- --.:- v.~ ~-- - " --"-

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l' ATTACilMENT G lg l (guestion 11) l l

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SUMMARY

OF DIVISION D RADIATION SAFETY-REIATED PROCEDURES The following paragraphs highlight the significant radiation safety-related

~

procedures applicable to and in effect at the UPTR.

UPTR-SOP-D.1 UFTR RADIATION PROTECTION AND CONTROL is the overall radiation I safety procedure governing UPTR ALARA efforts. As indicated in SOP-D.1, these l procedures establish techniques and standards within the guidelines of USNRC Rules (

_ and Regulations, Title 10, Part 20, " Standards for Protection Against Radiation" l (Reference 1) and the Florida Division of Health's " Control of Radiation Hazard [

Regulations" as amended March 19, 1972, Chapter 10D-56, (Reference 2) and the  :

University of Florida's " Radiation Control Guide" revised January,1979 (currently  !

in process of revision) . Exposure limits fall into three categories:

[ 1. External Exposure L_

Maximum permissible exposures used at the , University of Florida are set forth 7 below:

L_.

a. Maximum Permissible Occupational or Restricted Area Exposure:

(1) Whole body; head and trunk; active blood-forming {

organs; lens of eyes; or gonads. . . . . . . . . . . . . . . . . . 75 mrems/ week or 1000 mrems/ calendar quarter ,

(2) Extrcmities...................................... 500 mrems/ week or -

6000 mrems/ calendar  ;

quarter i r

(3) Sk in o f whole body. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 400 mrems/ week or  !

_ 5000 mrems/ calendar l quarter l l

~

b. Maximum Permissible Non-Occupational or Unrestricted Area Exposure and '

Maximum rermissible Exposure to Minors is: f Whole body; head and trunk; active blood-forming

_ organs; lens of eyes ; or gonads. . . . . . . . . . . . . . . . . . . . . . . 10 mrems/ week {

r Specific approval to operate under the more liberal State (F1. Div. of Health, I Ch100-56) or Federal (10CFR20) Regulations must be obtained for each such oc-casion from the Radiation Control Committee. These more liberal limits are as  ;

follows:

- a. Maximum Permissible Occupational or Restricted Area Exposure:

(1) Whole body; head and trunk; active blood-forming I

_ organs; lens of eyes; or gonads . . . . . . . . . . . . . . . . . . 1- 1/4 rems per calendar quarter (2) Hands and forearms; feet and ankles.............. 18-3/4 rens per

calendar quarter I

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(3) Sk i n o f body . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-1/2 rems pe r

. calendar quarter

b. Maximum Permissible Non-Occupational or Unrestricted Area Exposure and Maximum Permissible Exposure to Minors: _

i l

Whole body; head and trunk; active blood-forming organs; lens of eyes; or gonada....................... 125 mrems per calendar quarter

2. Concentrations above background ia

a. Air - See References 1 and 2.

b. Water - See References 1 and 2.

NOTE: Concentration may be averaged over periods not greater than 30 days.

3. Transferable Surface Contamination: ,

2 The maximum permissiblg transferable conta nination is 100 dpm/100 cm for beta-gamma or 50 dpm/100 cm for alpha. If an object exceeds these limits, it must be decontaminated to a level less than or equal to the above limits or the contami- -

nation be suitably contained by bagging or an equivalent nethod prior to trans-ferring the object from the UFTR Cell to any other area.

The following radiation safety-related surveys are performed on a routine weekly basis within the UFTR Cell:

1. Swipe Survey

2. Water Sampics

3. Instrument Checks

4. Ai.r Samples

5. Heta-Gamma Radiation Field Survey

6. Check of the Decontamination Room.

In addition, further radiation safety-related surveys are required as follows:

1. Supervision of the transfer of irradiated samples or experiments to or from the UPTR.

2. Itaking area beta-gamma and neutron radiation level surveys after major shielding alterations.

I 3. Supervision of insertion or removal of experiments in or out of UFTR experimental ports.

I UFTR-SOI -D. 2 RADIATION WORK PERMIT is a procedure which governs work or operations in the UPTR which are of such a nature that radiation hazards, actual or 1x>tential, are involved; it is required that a properly executed Radiation Work Permit (RWP) be available at the work control point to serve as a guide for safe operations.

The following criteria are uned to determine the need for an PWP:

G-2

i II

, 1. If it is anticipated that a worker could receive greater than 25 percent I of the quarterly radiation exposure limit as specified in 10 CFR 20.

i

2. Airborne activity expected or measured about MPC liraits as specified in l 10 CFR 20. -

2

3. Contamination expecged or measured in excess of 20,000 dpm/100 cm beta or 2,000 dpm/100 cm alpha.

4. Working within the core area with shielding blocks removed.

The kWP is legal record; when an individual signs his name on the RWP, he is  ;

signifying that he is cognizant of all information contained therein relative

{

to working conditions, hazards, protective equipment, and special instructions, '

and that he will comply _.

UP rR-SOP-D . 3 PERSONNEL MONITORING requires that personnel monitoring (dose) equipment be worn or carried by

1. 1;ach individual who enters a restricted area under such circumstances that he receives, or is likely to receive a dose in any calendar quarter in excess of 25 percent of the applicable value specified in UPTR-SOP-D.1, I .C.1 or Appendix I of UPTR-SOP-D. l . ' i

2. Each individual under 18 years of age who enters a restricted area under such circumstances that he receives, or is likely to receive, a done in any calendar quarter in excess of 5 percent of the applicable value specified in UFTR-SOP-D.l.

3. Each individual who enters a high radiation area.

and that RWIt; be properly prepared as required by SOP-D.2.

l UFTR-SOP-D.4 UPTR RADIATION PROTECTION WEEKLY SURVEY requires performance l and recording of results of a weekly radiation protection survey (on all

. operable systems, even if shut down) to include l 1. Monitoring of surface contamination in the cell by taking random swipes and record iny, results. Swipes will be representative of approxinately 100 square centimeters of turface area, t

4

2. Sampling of Airborne part iculate contamination using a high volume air sampler for approximately twenty minutes or ten cubic meters.

1

3. Obtaining water samples (3) from the reactor staff for determination of

{ gross activity.

The final three Division D SOPS address situations less frequently encountered in UPTR operations.

UFTR-00P-D.5 PRIMARY EQUIPMENT PIT ENTRY requires that

1. At least 15 minutes must elapse af ter shut down f rom power operation at 1 kw or above before entry into the Primary Equipment Pit to allow time i

for N-16 decay.

I G-3

2 The reactor be maintained in the shutdown mode with personnel in the pit unless maintenance requires otherwise; in which case, the proper blado co figurations must be maintained. These limits are not applicable if all the fuel is removed from the core.

I 3. All personnel entering the primary equipment pit must adhere to external exposure limits.

4. Appropriate anti-C clothing be worn for entry if water is visible in the pit until it is determined that no surface contamination exists.

UFTR-SOP-D . 6 REMOVING IRRId)I ATED SAMPLES FROM UFTR EXPERIMENTAL PORTS re-quires I 1. A reactor operator and a radiation control qualified person to remove irradiated samples from the core.

2. Gloves to be worn while transferring irradiated materials from the core.

3. Samples containing liquid or volatile materials not to have their outer plastic coverings removed in the UPTR.

4. Use of the center vertical port transfer shield plug to allow the renoval -

of samples from the core while operating at power.

5. Adherance to the following radiological limitations:

a. An unshielded sample with a radiation level less than 1.5 Rem /hr at one foot may be removed from the reactor or the rolling pig.

b. A sample removed from the central vertical port into the rolling pig may remain in the pig if the radiation level is less than 200 mrem /hr

'" at the surface of the pig.

'l c. A sample removed from the reactor into a fuel transfer cask may remain

,E in the cask if the radiation level is less than 200 mrem /hr at the sur-I face of the transfer cask.

d. Samples with Radiation levels of 200 mrem /hr or less at the surface of the transfer container may be removed from the UFTR cell with the re-actor operator's approval and registering in proper form and the UFTR Irradiated Materials Transfer Iog.

c. Sanples exceeding 1.5 Rem /hr at one foot or 200 mn/hr at surface of I rolling pit or fuel transfer cask shall be replaced in reactor for decay to acceptable limits. If it is necessary to transfer samples exceeding these limits, the Radiation Control Officer or his designated representative may authorize the transfer.

UPTR-SOP-D.7 PRIMARY RESIN CHANGE requires that I 1. External 6-Y radiation levels be measured prior to resin change to insure personnel do not exceed limits as per UFTR-SOP-D.l.

2. Personnel handling spent resin prior to sealing for disposal wear appro-priate anti-C clot hing.

G-4

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3. A controlled area be set up to contain spent resins until resins are

scaled for disposal.

) 4. A resin sample be obtained for future analysis.

i 5. Spent resins be scaled and labeled for transfer to nadiation Control for l disposal.

6. An RWP be utilized.

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, RADIATIO:: CO : TROL TECIIN1QUU C17 IIISTRUCTIONS FOR CALIBRATII;G SELF PSADII:G POCi;ET DOSDSTERS I I. PURPOSE:

To establish a standard procedure for calbirating self reading -

pocket dosimeters.

II. PREREQUISITES:

A. Direct reading pocket dositeters to be calibrated.

B. Dosimeters charger C. Calibrated CS -137 or Co -60 source I D. Source and instrument holder calibration board E. Timer s

F. Methanol and Q-tip swab I

G. Radiation Control Pocket Dosimeter Calibration form RC10G .

III. PROCEDURE:

A. Clean dosineter electrode with swab and nothanol.

B. Zero the dosimeter using the dosimeter charger.

C. Confirm that transient movement of the dosimeter pointer when I disconnected from the charging source does not exceed 5 percent of full scale for dosineters with ranges in excess of 500 mR.

I D. Calculate the tima and distance required to give the dosimeter an exposure reading betwecn 1/2 - 3/4 of full scale.

E. Place the dosimeter in the calibration board at the calculated distance. With the source at the center e>; pose the dosineter for the deternined amount of time.

I F. Record the dosimeter serial number and/or control number on Pocket Dosimeter Calibration form. Record actual exposure and indicate exposure reading. The total error of the measurement I of the 95 percent confidence level shall not exceed + 12 percent of the full scale value (12 percent of 250 mR is 30 mR) .

I C. Recharge (zero) the dosimeter and place in an area where the exposure rate is less than 0.02 InP/hr.

After 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> read and record the indicated drift, any discharge I

II.

that has occurred should not exceed 2 percent of full scale.

(2 percent of 250 nR is 5 mR) .

IV. RECORDING:

Enter results in mR on form RC105.

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V. Frequency,:

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! Frequency of calibration should be quarterly, r;ot'to execed 4

rronths when pocket dositeeter is used as the prime racans of personnal

! rnonitoring, and se:ai--annually when in conjunction with personnel r:onitoring i badges.

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- - . _ - - _ _ _ _ . _ . . . - - - - _ . . . . - . - _ - - .