Text

Dismantling Plan
	ML20235J701
Person / Time
Site:	05000087
Issue date:	07/08/1987
From:	; WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	;
Shared Package
ML20235J693	List: ML20235J691; ML20235J701; ML20235J711; ML20235J740;
References
	0151N, 151N, PROC-870708, NUDOCS 8707150696
	Download: ML20235J701 (61)
	v • d • e

e WESTINGHOUSE NUCLEAR TRAINING REACTOR LICENSE R-119 DOCKET NO. 50-87 DISMANTLING PLAN 1.0 PLAN BACKGROUND AND MANAGEMENT In accordance with 10CFR50.82, this Dismantling Plan is submitted to support the Westinghouse Electric Corporation's request for authority to surrender License R-119 voluntarily and to dismantle the Westinghouse Nuclear Training Reactor Facility and dispose of its component parts.

This Plan describes the organized means by which all radioactive or contaminated components will be removed and the Facility will be decontaminated.

Furthermore, this Plan will l

provide reasonable assurances that the dismantling of the Facility and the disposal of its component parts will be performed in OQ accordance with the Code of Federal Regulations and will not be inimical to the common defense and security or to the health and safety of the public.

4 The format of this Plan follows the outline proposed by the NRC l

Standardization and Special Projects Branch and includes information on the facility operating history, the current radiological status of the the Facility, the dismantling alternatives under consider-

ation, the dismantling organization and responsibilities, the regulations and regulatory cuides and standards that will guide the dismantling activities, and the training and qualifications of the WNTR dismantling staff.

Furthermore, the Plan will describe the dismantling occupational and radiation protection programs, the dismantling and decontamination tasks and schedules, the conduct of safeguards and physical security plans, radioactive materials and waste management, technical and environmental specifications, and the proposed termination radiation survey plan.

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I In anticipation of dismantling operations, the special nuclear f-x.y material of the Westinghouse Nuclear Training Reactor h'a s been removed f rom the Facility and shipped to the Department of Energy facilities under the NTR Facility Operating License and in accordance with Department of Energy, Nuclear Regulatory Commission, and Department of Transportation require-ments.

In order to ship the SNM configured as the fuel element followers attached to the control rods, the NTR control rods were disassembled according to the procedures used for annual fuel element inspection and stored to reduce the radiation levels on the reactor room ALARA.

Per 10CFR50.59 assessment, storage and shipment of the activated components of the control rods and graphite rods represents no unreviewed safety question and these will be shipped under the current license as radioactive waste in order to keep radiation levels during the dismantling effort at the NTR Facility ALARA.

The Nuclear Training Reactor dismantling ef fort will be managed by the Westinghouse staff responsible for the conduct of the R-119 license.

Per the NTR Technical Specifications, the Manager of the Nuclear Training Reactor will be responsible for the safe conduct of operations at the Facility.

The Facility organization will consist of the Training Reactor Coordinator and the Reactor Lead Engineer and Radiation Safety Officer.

The Reactor Safeguards Committee will continue to serve as a review and audit committee, with a sub-committee designated to review the dismantling plan, procedures, and implementation thereof.

All activities associated with the dismantling effort will be performed by Westinghouse Electric Corporation personnel.

Extensive Westinghouse resources experienced in health physics procedures and policies, licensing issues, decontamination procedures, radiological engineering, radioactive waste handling and shipment will be available to support the NTR staff in its dismantling efforts.

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1.1 Summary Description The Westinghouse Nuclear Training Reactor License R-119 was originally issued on January 28, 1972 and has been amended nine times.

Amendment 6 reflected the changes necessitated by the reduction of NTR SNM inventory to below the formula quantity for SNM of high strategic significance.

Amendment 8 renewed the operating license until January 28, 2002.

An application for a Possession Only license was submitted to the NRC on June 19, 1987.

This application reflects the f act that all SNM has been sent to a Department of Energy facilities for recovery and revises the technical spec' ications to eliminate those specifications associated with. actual operation and to include only those specifications necessary for adequate radiation monitoring.

The Westinghouse Nuclear Training Reactor was originally constructed as the Westinghouse Critical Experimental Station (CES) in the late I

1950's.

The construction permit to build the CES in Waltz Mill, Pennsylvania was issued by the Atomic Energy Commission on October 21, 1957.

The AEC CES Facility License' CX-ll was issued on June 17, 1958 and criticality was first achieved on June 23, 1958.

The CES was used to conduct low power physics tests and experimental apparatus environmental studies and its maximum power. level was limited to 100 watts.

The reactor was moved to Zion IL in 1971 and relicensed as the Westinghouse Nuclear Training Reactor License R-119.

As shown on Figure 1,

the Westinghouse Nuclear Training Reactor Facility is located in Zion, IL within the Westinghouse Nuclear Training Center (WNTC).

Figure 2 indicates that the NTR Facility is located in the southwest corner of the WNTC building.

As part of

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Westinghouse Training and Operational Services, the NTR Facility was I

used only as a training facility for Commercial power plant operators.

The NTR Facility is maintained as a restricted area by O

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Westinghouse and includes the reactor room, the control room, the

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Health Physics lab, a machine shop, a classroom, and an office area.

The control room, the Health Physics lab, the machine shop, the briefing room and the of fice areas are classified as restricted areas but are not radiation areas.

The reactor room is currently considered a High Radiation Area because of its use as a storage area for byproduct material.

When the reactor room contained the NTR SNM, it was also a Controlled Access Area.

Per the NTR submission for the a Possession Only license, the reactor room is currently a Radioactive Materials Area and will continue to be labeled as a High Radiation Area until sufficient radioactive materials is removed or packaged.

The reactor room is a concrete block building with steel beam supports, approximately 27 feet square and 27 feet high.

The reactor itself is a light-water moderated, graphite-reflected pool-type reactor containing no irradiation experiment beam ports.

Reactor support systems include a

moderator purification and heating

system, a

reactor instrumentation air system, a reactor water level indication system, Q

and a source drive system.

The original R-il9 license limited peak steady state power level to 10 kilowatts and total integrated power to 200 kilowatt-hours per year.

In 1981, under Amendment 6, the reactor was reconfigure to

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limit the amount of fuel to less than the formula quantity for strateg h special nuclear material.

Peak steady state power continued to be limited to 10 kilowatts.

For most training f

l operations, internal operating procedures have limited power to less than 100 watts.

As Table I indicates, the annual integrated power for the NTR under the R-119 license between 1972 and 1987 ranged f rom 56.3 kw-brs to 13.4 kw-brs, and average integrated operating level has been 30.86 kilowatt-r.ours per year.

Total integrated power of the reactor fuel was 459.7 kw-brs.

The power levels at which the NTR operated was insufficient to heat the fuel or its coolant.

Indeed, total burnup of the NTR fuel, af ter 25 years of service, has been calculated to be much less than 1.0 gram.

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As the following paragraphs will support, the radiation levels in the NTR have consistently been extremely low, most often being statistically indistinguishable f rom background measurements.

It is i'

anticipated, therefore, that the dismantling of the NTR Facility components will be quite straightforward.

All fuel has been removed and activated control rod parts, previously disassembled in order to ship the f uel rod followers, and graphite rod reflector parts have

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been stored for packaging and shipping to radwaste burial in order to keep the reactor room radiation levels ALARA.

Prior to dismantling

efforts, all non-essential, uncontaminated support equipment will be removed from the reactor room.

Upon approval of this Dismantling Plan, the NTR Staff will dismantle the reactor internals.

If necessary, possible and prudent, the NTR staf f will initiate soap and water decontamination procedures.

Any material that does not meet the criteria of Reg Guide 1.86 for surf ace contamination or 5 pR/hr above background at one meter for radiation levels will be discosed of as radioactive waste.

All radiation and contamination surveys will be conducted with calibrated instrumentation of appropriate sensitivity.

When all radioactive or contaminated components have been removed f rom the

Facility, remaining components and the Facility itself will be subjected to a radiation survey that will validate its acceptance for submittal to NRC inspection for free release.

l Currently, the selected dismantling option for the NTR Facility is

.the release of the Facility for unrestricted use.

Westinghouse,

however, is conducting a feasibility study for converting the Facility into a decontamination center and, therefore, may apply for Part 30 license for the area the NTR Facility now occupies.

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The NTR Facility dismantling effort will be accomplished by using

,- 3) the extensive experience and resources of Westinghouse Electric Corporation.

The NTR staff will be supported by specific expertise available throughout the Westinghouse Electric Nuclear Energy Systems and Services Divislons.

This expertise includes, but is not limited to, experienced Health Physics personnel, experienced radiological engineering expertise, experienced decontamination and radwaste shipment personnel, and experienced licensing and j

i saf egua rds personnel.

The total cost for dismantling the NTR j

Facility is estimated to be less than $500,000 and will be completely funded by Westinghouse.

The collective dose equivalent for the dismantling ef fort is estimated to be less than 100 Mrem.

The final radiation survey plan divides the Facility into three sections based upon the probability of the existence of contamination.

Sections will be divided into grids of 3 meter x 3 j

meter, 2 meter x 2 meter and 1 meter x 1 meter respectively.

In Sections I

II, where contamination has historically been (v) nonexistent, approximately 30% of the grids will be randomly surveyed.

Additional details of the survey procedures are given in Section 8.0 of this dismantling plan.

Section III consists of the reactor room.

Areas such as the floor, reactor tank, dump tank and lower walls have the highest potential for contamination.

These areas will be sectioned into 1 meter by 1 meter grids and each grid will be surveyed and surveyed as in Section I.

Vertical surfaces above 2 meters, and overhead surfaces, will be surveyed with uniform, but larger grid spacings.

The final survey will assure that radiation level; within the facility are below 5 pR/hr above tackground at 1 meter f rom the surface and contamination levels are within the cuidelines of Regulatory Guide 1.06.

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-1.2 Facility Operating History Since 1972, the NTR has been used to train reactor operators and engineers in the fundamental theoretical principles of reactor operation.

Prior to 1969, the reactor license limited maximum power to 100 watts and, as a training f acility, this 100 watt power limit was administratively continued for most experiments.

The Reactor was a lifetime core and, at the final shipment, the total activity of the fuel was estimated to be 1.8 curies.

Further indication of the low fuel activation is that when not located in the reactor tank, reactor fuel was stored dry in the reactor room, and routine training experiments involved the manual loading and unloadirg of fuel elements by trainees.

In order to use the NTR as a tra,ning facility, it has always been in Westinghouse's best interert to limit the potent.ial for fission product buildup in order to keep the radiation levels experienced by the trainees as low as pos4ible.

Additionally, the NTR was used to teach sound radiation protection practices and thus, attention to ALARA techniques were inte.Jrated into the daily activities of the Facility staff.

During daily training sessions, students used portable survey instrument; when working in_ the reactor room and step-off pads at the the t eactor room entrance to ensure that no contamination would be transmitted outside the reactor room.

As -Table I indicates, the annual integrated power for the NTE since 1972 ranged from 56.3 kw-brs to 13.4 kw-brs.

The average int.. grated power level for this same time f rame was 30.6 kilowatt-hot.rs per l

year.

Total integrated power of the reactor f uel was 459.7 kw-brs.

At 10 kw, peak thermal neutron flux in the core was 4.08 E10 neutrons per square centimeter-second.

At 100 watts, the efore, peak thermal neutron flux per square centimeter-second was 1.08 E8 neutrons per square centimeter-second.

There has been no detectaale release of radiation to the environment during the operating history of the NTR.

There have ieen no

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radiation spills and thare are no areas of high contamination.

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During student training sessions, there were two instances of a g

dropped fuel element since 1972.

One of these instances occurred on March 1,

1979 and one on November 23, 1981.

Neither incident resulted in any damage to the f uel element involved and no leakage or Facility contamination occurred.

No fuel will be onsite during the dismantling operation

and, therefore, there will be no probability of a fuel-handling radiological accident.

1.3 Radiological Status Of The NTR Facility The radiation levels and contamination levels of the NTR Facility l

have consistently been extremely low.

In most cases, radiological surveillance data is statistically indistinguishable f rom background measurements.

Figures 3 through 4 and Tables I through V are dis-cussed in the f.011owing paragraphs to illustrate the radiological status of the NTR Facility from an historical perspective.

The radioactive inventory of the NTR is divided into two categories, l

based on the potential sources of radiation.

The first category is the radioactivity potentially induced by neutron activation of the reactor tank, the reactor structure and components, the reactor dump tank, or other adjacent structures and the second category is the radioactive material deposited on the surf aces of the reactor and its support systems.

Estimates of the radioactive inventory can be arrived at by considering the constituent elements of the material in question and calculating the duration of exposure to the neutron flux and the energies of the incident neutrons.

Direct measurements, however, are generally more reliable and will be used extensively in this report.

The composition of the reactor materials and the operating q

characteristics of the Nuclear Training Reactor Facility suggest that the potential for significant radioactive inventory within the Facility due to direct neutron activation is very small.

The potential for neutron activation of the reactor tank, the reactor 8

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components, the reactor dump tank, or other adjacent structures is very low because the reactor tank, the reactor dump tank, the reactor core internal support structures, and the majority of the piping systems within the reactor room are made of aluminum comprising over 98 percent aluminum-27 (see Table II).

Aluminum-27 has a low neutron absorption cross-section and, if activated, a short half-life for beta decay.

Aluminum-28 beta decays to the stable nuclide, Si-28.

Similarly, the potential for a_ significant radioactive materials inventory due to radioactive contamination in the NTR or its support systems is also extremely small.

There have been no fuel cladding failures during the history of the NTR operation and thus, no radioactive fission products have been circulated through the core or reactor support systems f rom this source.

Furthermore, periodic surveillance of water quality and water purity have consistently indicated that no corrosion of the reactor components has occurred and no activated crud particles have been present in the core.

O Contamination surveys of the reactor room and Health Physics lab are taken monthly.

During each month, five smears are taken in the Reactor Room and two are taken in the Health Physics lab.

Each smear consists of a 100 square centimeter area with results reported for the entire smear.

Table III is a summary of contamination surveys taken f rom February, 1986 throujh May, 1987. As indicated, monthly surveys indicate a maximum altha reading of 0.5 cpm /100 square cm.

The maximum beta readings between February 1986 and May 1987 was 37 cpm /100 square cm.

All readings were well below the Facility administrative limits of 4.2 cpm /100 square cm for alpha (

10 dpm/100 square cm) and 50 cpm /100 square cm for beta ( 200 dpm/100 square cm).

Figure 3 is an illustration of a recent contamination survey of the NTR reactor room.

The numbers 1 through 7 on Figure 3 indicate the approximate location where data was taken.

Results of this survey are reported on Figure 3A and demonstrate that no contamination is present in either the reactor room or the Health Physics lab.

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l.3.1 Reactor Core Radiological Status

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The Westinghouse Nuclear Training Reactor used light-water moderated,

- g raphite-ref lected,

water-shielded highly enriched i

uranium.

The reactor core consisted of 19 standard fuel elements and 5 cadmium control rods with fuel element followers located in an i

19 foot high x 8 foot diameter aluminum tank.

The core was arranged in an hexagonal configuration (called the N24S core) surrounded by twenty cylindrical graphite reflectors.

A top view of the reactor configuration is shown in Figure 5.

This figure shows the top core plate, as well as the fuel element elevator located in the center of six in-core storage locations.

The reactor tank is an 8 foot diameter x 19 foot high aluminum tank approximately 0.37 inch thick.

The f.tructural components within the tank are the upper and lower grid plates, and fuel and control rod shroud tubes, and an extended shroud tube for normal sealed source location.

The reactor tank and its components are made of Type 6061-6T aluminum.

As outlined in Table II, Type 6061-6T aluminum comprises 97.9% Al-27, 0.6% Si-28, 0.28% Cu 63,65, 1.00% Mg 24,25,26, and 0.2% Cr 52,53 (ref erence ASME Section II).

The upper grid plate is one inch thick and contains 93 3 inch diameter position holes.

The lower grid plate is 44 inches below the upper grid plate and is 4 inches thick at its edges, 6 inches thick in the i

center and has 144 position holes.

An aluminum shroud tube extends i

between each position hole on the upper plate and corresponding l

lower grid plate.

Five of the aluminum shroud tubes extend above the upper core plate and beneath the lower core plate.

These shroud tubes were used to guide the control rods and fuel followers through the core.

During reactor operations, the reactor tank was shielded f rom the core by approximately three feet of water at the sides and five feet of water at the bottom.

Five feet of water shielded the top of the core with an additional five feet up to ground level.

Figure 6 is a one-line diagram of the reactor tank assembly, indicating tank materials and outside dimensions.

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Recent radiation area surveys taken in the reactor tank indicate that the radiation hot spots in the reactor are located near steel bolts holding the reactor segments together.

As Figure 7 indicates four recent radiation readings inside the reactor tank.

The hottest location inside the reactor tank measures 82.9 p-R/ hour.

Other materials located within the reactor tank during reactor operation include the nuclear instruments and cabling, the water level indication instrumentation and piping, and the aluminum source guide tube.

The nuclear instrumentation includes two Wood Model G-10-20 BF-3 proportional detectors and four Westinghouse CIC chambers and associated standard cabling.

Nuclear instrumentation cabling is coaxial copper wire protected by PVC casing.

The water level indication system uses and aluminum tube inside the tank connected to copper tuting outside the tank.

The guide tube for the source is a 10 feet high aluminum shroud tube located outside the reactor core within the reactor tank.

Ten feet directly above the reactor tank -is an iron platform used to support the control rod I

drive motors and ma] net carriages.

Reactor room air samples surveys are taken monthly.

A high volume Staplex air sampler with a 4 inch filter paper is used in the I

reactor room for approximately one hour.

Each sample is counted af ter a decay period of approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

As listed in Table IV, monthly measured alpha activity between January, 1986 and May, 1987 ranged from 2.13 E-13 to 6.52 E-13 pCi per milliliter.

Beta-gamma activity during the same period ranged f rom 1.33 E-12 to 1.04 E-11.

These activities are within levels expected f rom natural radioactive materials present in the air.

The alpha and beta-gamma activity were well within the limits of 10CFR20 Appendix B Table 1.

Reactor water samples are also taken on a monthly basis.

For each sample,1000 ml of water is taken f rom the reactor tank, evaporated i

down, and counted for both alpha and beta-gamma activity.

Between January 1986 and May 1987, alpha activity in the water ranged 11 w

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I between 0.0 dpm/1000 mi and 0.125 dpm/ml.

Beta-gamma activity dur-O y

.ing the same period ranged from 0.0 dpm/1000 m1 to 19.6 dpm/1000 ml.

l Specific data is tabulated in Table V.

Technical specifications i

1 also require that water resistivity be greater than 200,000 ohm-cm when averaged over a two-month period.

I 1.3.2 Radiological Status Of The Reactor Dump Tank The NTR was a pool-type reactor with no forced cooling flow and was operated at poweri, that _ produced no f uel or water heating.

Water within the core could be dumped to a surrounding reactor dump tank as an auxiliary method of shut down.

When the reactor was shutdown, the moderator could be stored in the dump tank.

When the reactor water needed to be heated for moderator temperature coefficient measurements, the water.. was circulated f rom the dump tank through a mechanical heater located in the Facility machine shop.

Also located in the Facility machine shop is a demineralized used to periodically purify the water.

Water returning from a support system could be directed only to the dump tank.

Inside the dump tank is a fill system used to refill the reactor tank.

The reactor dump tank is a 12 foot diameter, 24 foot deep aluminum-lined concrete tank.

The aluminum lining of the dump tank is made of Type 3003 aluminum, comprising 98.6% Al-27, 0.12% Cu-63 and Cu-65, and 1.2% Mn-55, as listed on Table II.

The reactor tank is eccentrically positioned below ground level and at the closest i

1 spot, is separated from the dump tank by approximately 6 inches.

At the widest

spot, the sepa ratior, between the two tanks is l

1 approximately 3.5 feet.

1 Water is transferred from the reactor tank to the dump tank by means i

of the Moderator Dump System.

The Moderator Dump System is simply two air-operated valves (a ten-inch and a one-inch valve) that open i

on a manually generated signal from either the control board or the C\\

Q reactor room.

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The Reactor Moderator Fill System is a two-ended system used to

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transport reactor water f rom the reactor dump tank to the reactor tank..To refill the reactor tank, the water is pumped using the moderator-fill pump.

The moderator is pumped through aluminum piping and one or both of two gate valves.

The operation of the gate valves is conducted from the control board through a pneumatic Jcontrol system.

The moderator-shield water system and the reactor tank-reactor dump tank relationship is schematically illustrated in Figure 8.

As

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figure 8 indicates, the majority of the materials within the confines of the reactor dump tank are made of aluminum.

There is, however, a one-inch steel dump valve, a ten-inch steel dump valve, f

and a stainless steel canned motor and fill pump within the dump tank.

Figure 7 indicates recent radiations measurements taken inside the dump tank.

All readings within the dump tank are currently less than 20 pR/hr.

1.3.3 Reactor Moderator Purification / Heater System The Reactor Moderator Purification / Heater System, illustrated in Figure 9, is used to circulate water f rom the dump tank to either a demineralized or heater and then back to the dump tank.

The system was only operated when the reactor was shutdown.

The moderator purification / heater pump is located at the bottom of the dump tank.

The demineralized and heater for this system are located in the machine shop.

The system also includes a wire screen filter and a 5 micron mechanical filter.

Both filters are located upstream of the demineralized.

As noted on Figure 9, piping associated with this system located within the reactor room is made of aluminum and piping located within the machine shop is stainless steel.

A radiation survey of the demineralized indicated an on-contact reading of 15.6 pR/hr.

A smear survey of the inside and outside

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of the demineralized, the pre-filter for the demineralized, the i

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e moderator fill

pump, demineralized pump, dump tank bottom and 10-inch dump valve yielded results less than the lower limits of detectability.

Actual data from this survey is available in the NTR

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Facility files.

As shown in Figure 4, area radiation levels it, the machine shop are approximately 19.3 pR/hr.

1.3.4 Reactor Air System m

The Reactor Air System is used to operate the pneumatic valves associated with the Reactor Dump System, the Reactor Moderator Fill l

System, and the Water Level System.

An air compressor and receiver l

are located in the machine shop and a ballast tank, regulator, and

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assorted valves are located in the reactor room.

Air is distributed to the Fill and Dump valves in the reactor dump tank through copper tubing. A schematic of the Reactor Air System is shown in Figure 10.

A recent on-contact reading of the air-compressor receiver tank l

yielded less than 20pR/hr.

1.3.5 Dump Tank Sump System The Dump Tank Sump System is used to collect inleakage ground water from beneath the dump tank bottom.

Ground water is syphoned through tygon tubing by a vacuum pump located in the Facility machine shop.

An aluminum standpipe at the bottom of the dump tank supports the tygon tubing.

Figure 11 illustrates the Dump Tank Sump System Configuration as well as recent area radiation survey results.

An on-contact reading of the sump collection can yielded less than 15 pR/hr.

l.3.6. Machine Shop The machine shop is 27 long x 18 feet wide x 27 feet high room located next to the reactor room.

The machine shop contains the air compressor and receiver, the demineralized, the heater, the sump vacuum pump, and the electrical boxes for NTR Facility electrical 0151N

distribution.

The machine shop is only connected to the reactor f

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L room through a 24 inch x 12 inch channel for piping and cabling connections and through a 20 inch x 8 inch ventilation system air vent.

The high bay of the machine shop contains the Facility ventilation equipment, including air intake, filter, heating and cooling coils, humidifier, air ducts and air exhaust.

Air is vented through this system into the Reactor Room.

The ventilation system for the NTR Facility is isolated f rom the ventilation systems for the remainder of the Westinghouse Nuclear Training Center, i

I 1.3.7 Control Room, Health Physics Lab, Classrotm, Office Area l

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The remaining sections of the NTR Facility are isolated f rom the Reactor Room except through normal doors and hallways.

The Health j

Physics Lab contains counting instrumentation cnd associated setup

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equipment, j

Semi-annually, a contamination smear sampling is taken of the-entire j

Facility.

The locations of the most recent semi-annual contamina-I tion survey are shown on Figure 12.

The results of the last semi-annual smear survey, taken April 2, 1987, are shown on Figure 12, A,B,C.

Radiation readings for these areas are included on Figure 4.

1.4 Dismantling Alternative Westinghouse Electric is seeking authority to surrender License R-119 and to secure use of the f acility with no requirements for a license.

It is our intention to remove all radioactive fluids, radioactive waste, and other materials having radioactivity levels above accepted unrestricted levels from the Facility.

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I 1.5 Dismantling Organization and Responsibilities

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The organization for the dismantling of the WNTR will be essentially I

the same as the-organization responsible for the the R-119 license

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and the safe operation of the Facility in compliance with federal l

and license requirements.

Personnel experienced in reactor operation and radioactive material handling will be responsible for j

all dismantling activities.

Figure 13 indicates the organizational structure.

The following paragraphs describe each position's responsibility.

Per the NTR Technical Specifications, the Manager of the Nuclear Training Reactor is responsible for the safe conduct of operations at the Facility.

The NTR Manager will serve as the Dismantling Manager and be responsible for the overall planning and direction of the dismantling operation.

The NTR Manager is responsible for planning the day-to-day dismantling operations and is responsible for these operations being conducted in a safe manner and within the prescribed limits of the Facility

license, federal and state regulations, and Westinghouse regulations.

The NTR Manager reports directly to the Manager, Training and Operational Services West, Westinghouse Nuclear Services Integration Division.

The Training Reector Coordinator is responsible for the implementation and administration of the dismantling plan and procedures.

He is responsible for overseeing daily dismantling activities, maintaining dismantling activity record s,

and j

dismantling staf f training.

The Training Reactor Coordinator also serves as the NTR Security Officer and is responsible for the j

implementation of the NTR Security Plan, j

f The Reactor Lead Engineer is responsible for the operation and maintenance of the NTR Facility equipment, including the reactor components and reactor support systems.

He is very f amiliar with the construction of all reactor hardware and components.

The Lead Engineer will contribute significantly to the planning of the 16 w

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- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _

n dismantling activities and he will be responsible for the direct V

supervision of those assigned to work on dismantling procedures The Lead Engineer is responsible to conduct dismantling activities in accordance with procedure and to keep radiation exposure as loy as reasonably achievable.

The NTR Lead Engineer will also serve as the Radiation Safety Of ficer during the dismantling.

He will be responsible for ensuring that all radiation protection procedures associated with the dismantling effort are implemented.

4 The Reactor Safeguards Connittee will continue to serve as a review and audit committee during the dismantling.

The RSC includes, per Technical Specifications, at least four scientists or engineers. wha are not involved in the line organization responsible for reactor I

operations and represent at least one half of the Committee membership.

The RSC includes persons with experience in reactor operations, reactor physics, health physics, and reactor facility management and licensing.

Each member is required to have a minimum of five years industrial experience and three years of active participation in his nuclear oriented discipline.

The RSC reviewn the dismantling plan, the safety and radiation considerations of all dismantling procedures and the implementation and records thereof.

1.6 Regulations. Regulatory Guides and Standards The dismantling operations will be governed by the relevant federal and state regulations, regulatory guides, and standards associated with nuclear research reactor dismantling.

These include the following:

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U.S.

Nuclear Regulatory Commission Docket No.

50-87 Facility Operating License No. R-119 Westinghouse Nuclear Training Reactor 10CFR50 Domestic Licensing of Production and Utiization Facilities 10CFR20 Standards for Protection Against Radiation 10CFR30 Rules of General Applicability to Domestic Licensing of Byproduct Material 10CFR73 Packaging and Transportation of Radioactive Waste 49CFR Department of Transportation Regulation governing.the transportation of Radioactive Materials.

U.S. Atomic Energy Comniission Regulatory Guide 1.86 U.S.

Nuclear Regulatory Commission Guidance and Discussion of Requirements for an Application to Terminate a Non-Power Reactor Facility Operating License The Westinghouse Nuclear Training Reactor will be dismantled and submitted for free release per the requirements specified in the above documents.

Specifically, the NTR Facility and its components will be dismantled and disposed of such that components remaining within the Facility at the time of the final radiation survey will be within the contamination limits specified in Regulatory Guide 1.86 and within 5 pR/hr above background at one meter f rom the surface.

All dismantling operations will be conducted in accordance with l

approved written procedures and will be executed in such a manner as to comply with the principles of ALARA in minimizing radiation I

exposure to the the dismantling operation workers.

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1.7 Training And Qualifications I

The training program for the NTR Dismantling will be written by the

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NTR Facility staff, reviewed by the Reactor Safeguards Committee and 18 l

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approved by the NTR Manager.

The training program will include-radiation training for those non-NTR staff personnel assigned to work in areas subject to radiation control and task-specific training to minimize the potential for personnel exposure or injury during completion of assigned tasks.

All procedures will be reviewed with assigned personnel prior to actual implementation.

Records of training and certification of these individuals are maintained by the Training Reactor Coordinator.

The Reactor Lead Engineer will ensure that any individual erking on the NTR dismantling is trained to accomplish his assigned task, and that the equipment and working area is maintained and controlled so as to assure safe working conditions.

The qualifications of the personnel assigned to dismantling tasks will be verified prior to implementation of the task by the NTR Manager.

Personnel participating in the dismantling operation will either be members of the NTR staff, employees of the Westinghouse Nuclear Services Integration Divison or experienced subcontractors of this Division.

2.0 OCCUPATIONAL AND RADIATION PROTECTION PROGRAMS 2.1 Radiation Protection Program The Radiation Protection Program for the Dismantling of the NTR will be in accordance with the Radiation Program implemented as part of the R-il9 operating license.

The responsibility for proper control of radiation hazards at the NTR Facility rests with the NTR Manager and the Facility staff.

Radiation protection policies and procedures are established in accordance with Westinghouse corporate health physics standa rds and include procedures for Personnel Monitoring, Personnel Dose Limitations, Environmental Monitoring, Radiation and Contamination

Surveys, and Radioactive Material

]

Handling.

0151N l

1

-_________________________J

2.1.1 Personnel Monitoring t

All NTR staff personnel and parsonnel assigned to extended dismantling work ef forts will be issued TLD beta-gamma and neutron sensitive badges, or equivalent dosimetry, and a direct readout ion chamber dosimeter.

These radiatien monitors are to be worn whenever personnel are in the NTR Facility.

Readout dosimeter will be read daily by the individuals to whom they are issued or as dismantling procedures dictate.

Total accumulated gamma dose f rom the readout dosimeter will be recorded weekly.

These checks will be utilized to monitor personnel exposure with reference to the established NTR daily and weekly working limits.

The TLD badges are sent quarterly to an outside agency for processing and reading.

The results are returned and recorded on the the individuals of ficial accumulated quarterly and lifetime dcse record kept on file.

Current records are posted in the NTR Facility.

When handling radioactive materials NTR personnel wear TLD finger rings that will be reac and recorded quarterly.

Monitoring of internal exposure for above normal body burden of radioactive l

materials is accomplished by periodic bioassays of individuals on the NTR Facility staff.

This test will be accomplished at the conclusion of the dismantling or approximately once per year.

Each person exiting the Reactor Room will be monitored for possible external radioactive contamination.

The spread of contamination is controlled through the use of step-off pads and a portable frisker.

2.1.2 Personnel Dose Limitations l

External dose limitations are based on the 10CFR20 requirements for limiting whole

body, skin, and extremity exposure.

The NTR permissable working limits are reduced administrative 1y to 100 mrem daily whole body exposure and 300 mrem weekly exposure, 625 mrem 20 w

0151N

j, daily extremity exposure and 1825 mrem weekly extremity. exposure, and 250 mrem daily skin exposure and 750 mrem weekly skin exposure.

Any exposure. in ' excess of the daily or weekly working limits is

)

reported promptly to the Radiation Safety Engineer and the NTR Facility Manager who conduct an inquiry into the circumstances of

-the exposure and how to prevent reoccurrence.

Results of the inquiry are to be reviewed by the Reactor Safeguards Committee.

During the operation of the NTR Facility, no actual exposures over t

the NTR administrative limits occurred.

^

2.1.3 Environmental Monitoring The NTR Facility is monitored through the use of area monitors, portable survey instruments, and periodic contamination surveys.

The portable radiation monitoring instruments available at the NTR Facility include:

i Eberline E'-530 0.1 mr/hr to 200 mR/hr O

)

Eberline E-120 0.1 mR/hr to 50 mR/hr l

Eberline PAC-1SA 50 cpm to 2000K cpm

/

Jordan Radector III 0.1 mr/hr 10.100 kR/hr Technical Associates MicroR Meter 0.5 pR/hr to 4500 pR/hr i

i These instruments are calibrated semi-annually in accordance with Technical Specifications.

All members of the NTR Facility staff are j

f amiliar with the use and operation of the radiation monitoring instruments.

When the instruments are placed in service, the user will have predetermined the type of radiation expected and the O

21 0151N

. p) -

estimated level.

A qualitative check of instrument response is made

(,

using; a. radioactive test source.

The user also observes the calibration sticker on the instrument to ensure that it was calibrated is within the required period.

The NTR Health Physic lab is equipped with the following instrumentation which are capable of measuring the radioactive contamination levels in air and water and the removable contamination on a smear.

B-y NMC Proportional Counter Converter, Model PCC 11T i

which is connected to a NMC Decoder Scaler, Model 05-2.

Alpha Eberline SAC-4 The.NTR Facility is monitored for

air, water, and surface j

contamination on a monthly basis in accordance with its Technical

-(j Specifications.

Results of these surveys are summarized in Tables III through V of this plan.

NTR Facility contamination limits are j

set at 200 dpm beta-gamma activity or 10 dpm alpha activity per 100 2

cm of smear area. As the summary of contamination smear data found on Table III indicates, NTR contamination levels have been consistently quite

low, most often being statistically indistinguishable f rom background.

Smears may be sent off site for counting by equivalent instrumentation.

I The concentration of airborne radioactive material in the Reactor Room is measured monthly and has not exceeded levels specified in 10CFR20 Appendix B.

Monthly samples taken of the moderator / shield I

water also consistently indicate no significant contamination.

I l

Water quality is also measured monthly and has consistently i

1 indicated that no impurities and no fission product activity has existed in the moderator.

Periodic resin samples (see Table IV) also indicate no fuel failure and contamination in the purification

>O system ion excnanger resin.

22 w

0151N

- - Y

In order to isolate any possible contamination to the confines of g

the Reactor Room, each person exiting the Reactor Room is monitored using a Eberline RM-15 with an HP-210 probe.

All radioactive materials handling operations are performed under the direction of a licensed NTR staf f - member.

The dismantling

' procedures and guidelines to be followed are dictated by type and quantity of the radioactive material being handled.

The NTR radiation protection

program, including the monthly radiation surveillance program will continue throughout the

)

dismantling operation.

Additional monitoring of the Facility will be made during the dismantling phase to ensure a complete radiation record of the operation is obtained and documented.

The monitoring will also identify radiation levels and surface contamination areas and permits proper posting of the areas.

Protective clothing will be used, based on identified and anticipated conditions, and the work to be done.

During the dismantling, the Radiation Safety Engineer will be responsible for ensuring all personnel working in the radiation area are properly clothed and badged.

The NTR Coordinator will be responsible for ensuring that a complete set of radiation records, including personnel and survey records, are secured and maintained.

Packaging low-level radioactive waste for transport and burial will adhere to 10CFR71, 10CFR20, and 49CFR, and the standards set forth by the Westinghouse Electric Corporation

" Radioactive Shipment Checklist".

The packaging and shipping of these wastes will be coordinated with the Westinghouse of fice of the Director of Nuclear Energy Systems Licensing, Saf eguards and Safety.

2.2 Industrial And Safety Hygiene Program The Industrial and Safety Hygiene Program implemented at the Westinghouse Nuclear Training Reactor complies with the Westinghouse Electric Corporation Industrial Hygiene and Safety Guidelines.

23 w

0151N

gN Westinghouse will take all necessary precautions to assure the safe b

completion of the dismantling operation.

The NTR Facility Manager is responsible for assuring that safe working conditions are maintained and that the personnel in the working area are properly protected.

The NTR Manager will review and approve all operations that employ hazardous materials as defined by OSHA regulation, and will ensure that the procedures for dismantling are adeqate to control airborne debris and hazardous material.

The Reactor Lead Engineer will be responsible for carrying out the dismantling operations in a safe manner in conformity with approved procedures.

2.3 Contractor Assistance The dismantling of the NTR and decontamination of the NTR Facility will be accomplished by the NTR staff.

The schedule and specific task procedures will be planned and writtten by the NTR staff.

Specific detailed procedures for significant operations will be written by the NTR staff, reviewed by the Reactor Safeguards g3V Committee, and approved by the NTR Manager.

The NTR staff will define, in writing, health, safety, and radiation requirements for each significant operation.

For the dismantling operation and for radioactive shipments and radioactive waste burial, the NTR staff will have the option of utilizing the expertise of other Westinghouse departments.

In particular, the NTR staff may utilize the services of Westinghouse License administration and the expertise of the Westinghouse Decontamination, Disposal, and Recycle Facility.

2.4 Cost Estimate And Funding The complete cost of the dismantling operation will be funded by Westinghouse Electric Corporation.

To date, the Corporation has spent approximately $200,000 to defuel the reactor and ship the SNM to Savannah River for reprocessing.

Further ccsts for dismantling l

the reactor, shipping its radioactive components for burial, licen-V sing and audit reports is anticipated to be approximately $250,000.

j 24 w

0151N l

fm 3.0 DISMANTLING TASKS AND SCHEDULES U

The NTR Dismantling Operation will include those tasks required to remove all radioactive components f rom the def ueled NTR Facility such that any components remaining within the Facility at the time of the final radiation survey will be within the contamination limits' of Regulatory Guide 1.86 and below 5

pR/ hour above background at one meter.

3.1 Tasks Prior to actual dismantling ef forts, the NTR Facility will be devoid of all Special Nuclear Material.

Fuel has been shipped to the Department of Energy for reprocessing, sealed neutron sources were donated to the Department of Energy, and control rods and graphite reflectors have been dismantled and prepared for shioment to radwaste burial to keep the radiation levels in the NTR Iacility as low as reasonably achievable.

The Facility has been stripped of all

.,D

!U unrelated, non-reactor equipment such as tables, chairs, pictures, and tools.

The actual dismantling ef f ort will involve dismantling the reactor core structure, including the upper and lower core plates and disassembling any equipment that does not mect the established criteria for free release.

These components will be shipped for radwaste burial and remaining components will be verified as meeting the f ree release criteria.

Phase One of the dismantling effort will commence with the submission of the Dismantling Plan to the NRC.

Phase One of the dismantling effort will include the pre-dismantling tasks of developing the detailed procedures for dismantling operatons.

During Phase One, the NTR staf f will evaluate the ef festiveness and ef ficiency of using the Westinghouse DDR Facility vs. making direct radwaste shipments f rom the NTR Facility.

Additionally during this Phase, NTR staf f will define the exact requirements and procedures for the final r,adiation survey plan.

Detailed procedures will be f

2e

-0151N

)

1 l

written for each significant dismantling operation. and these procedures will be submitted to.the Reactor Safeguards Committee for their review and concurrence.

Final dismantling procedures will be

. approved by the NTR Facility Manager during Phase One.

i Phase Two of the dismantling operation will begin after NRC approval of the. Dismantling Plan.

During Phase Two, the specific dismantling j

tasks will be performed.

This will require unbolting and separation of the Reactor Components.

No cutting, burning or grinding is.

anticipated. Specific tasks for the Dismantling operation include; i

1.

Electrical Disconnection of Nuclear Instrumentation and removal of associated wiring.from the Reactor Tank 2.

Removal of Nuclear Instrumelitation and Support Brackets from the Reactor Tank 3.

Removal of the Extended Source Tube f rom the Reactor Tank 4.

Removal of the Control Rod Shroud Tubes from the j

Reactor Tank j

1 5.

Disassembly and Removal of the Fuel Elevator and Incore Storage Racks from the Reactor Tank 6.

Removal of Water Level Indication System from the Reactor Tank.

7.

Disassembly and Removal of the Lower and Upper Core Plates and Fuel Shroud Tubes 8.

Disassembly and Removal of Valves and Piping Systems in the Dump Tank 9.

Shipment of all radioactive waste for proper disposal 26 0151N L____________-.-____________

l During Phase Two all radioactive components will be removed in v.

accordance with procedures, packaged for radwaste shipment, and shipped to approved recipients.

As the dismantling plan is implemented, the radiation levels found in the individual systems will dictate which components must ' be shipped f rom the Facility as radwaste.

The above nine specific tasks are the current best estimate of the scope of radioactive materials in the Facility.

Should radiation surveys of materials in the facility subsequent to the perf ormance of these tasks indicate radiation levels above the criteria for free release, appropriate steps will be taken to dismantle and ship those components.

Phase Three of the dismantling plan will be the systematic

]

radiological survey of all remaining Facility components.

j Appropriate action will be taken to decontaminate the Facility wherever necessary until all radiological surveys meet the criteria for f ree release and termination of the Facility license.

A final radiological survey will be performed with adequate grid coverage and sampling to allow a statistical analysis of the data.

This analysis will become part of the final report.

When the data from the statistical radiological final survey meets the criteria of q

Regulatory Guide 1.86 and radiation levels are below 5 pR/ hour above background at one meter, the NTR staff will request an NRC

)

regional confirmato*y survey and audit.

Upon the NRC's approval of the final radiation retults, it is anticipated that the Commission a

will terminate license R-119.

3.2 Schedule With the submission of this dismantling plan to the the NRC for approval,. the NTR staff will begin Phase One of the dismantling i

operation.

The NTR staf f will ascertain the extent of the use of other Westinghouse f acilities for support with radwaste shipment and disposal and will write detailed procedures for the dismanling operation and subsequent shipments.

These procedures will be l

O 21 y

l 0151N

= - - _ _ _ _ - _ _ - _ _ _ _ _ _

reviewed by the Reactor Saf eguards Committee.

Updates or changes to the plan will be submitted to the NRC for incorporation into the original Dismantling Plan.

Upon approval of the Dismantling Plan by the NRC, the NTR Manager will approve the final dismantling procedures.

Subsequent. to approval

_of.

the NTR Dismantling Plan by the Commission, Phase Two of. the dismantling operations will commence.

It is currently anticipated that these operations will be completed essentially in the order presented in the previous section.

Phase Two will terminate with the shipment of all radioactive waste f rom the Facility.

It is anticipated that Phase Two of the dismantling will require approximate 4 to 6 weeks of dedicated ef fort.

Periodic routine radiation surveys will be an integral part of Phase Two and, in f act, determine the actual scope of Phase Two.

Phase Three will be the final radiation surveys of the Facility q

documenting the readiness of the Facility and its remaining

)

(

components for f ree release and termination of the R-119 license.

As described in Section 8 of this Plan, the entire Facility will be j

statistically sampled, surveyed, decontaminated, and re-surveyed to ensure that the facility can meet the requirements.of Regulation Guide 1.86 and is below 5 pR/ hour above background at one meter.

The culmination of Phase Three will be the final NRC regional audit.

It is currently anticipated that Phase Three of the program will require approximately three weeks of concentrated effort.

A schedule of milestones is given in Figure 14.

I It is anticipated that the dismantling of the Westinghouse Nuclear j

Training Reactor will be accomplished prior to December 31, 1987.

3.3 Task Analyses i

1 1

There are no special health and safety considerations required in dismantling the reactor core and components due to the low radiation Q

levels as-shown in Figure 7.

Normal NTR radiation safety precautions will be utilized throughout the dismantling process.

28 0151N

3.4 Safe Storage There will be no requirement for Safe Storage since all l

radioactivity has been or will be removed from the Facility 4.0 SAFEGUARDS AND PHYSICAL SECURITY l

All Special Nuclear Material has been removed from the NTR Facility.

A new Physical Security Plan ( Appendix B) was submitted to the NRC as part of a " Possession Only" license amendment.

This plan will remain in effect throughout the dismantling process.

)

5.0 RADIOLOGICAL ACCIDENT ANALYSES No radiological accident analysis is required since all reactor fuel has been removed from the NTR Facility.

O 6.0 RADI0 ACTIVE MATERIALS AND WASTE MANAGEMENT l

/

6.1 Fuel Disposal All reactor fuel has been shipped of f site to DOE Facilities under the present NTR operating license.

I 6.2 Radioactive Waste Processing No gaseous or liquid radioactive wastes are present in the NTR Facility or expected to be generated during the dismantling process.

Most of the solid radioactive byproduct materials composed of irradiated stainless steel and graphite will have been shipped to a burial waste site for disposal.

Any reactor components which do not meet the free release criteria established in this plan will be 29 0151N

transported to a low level radioactive materials burial site in accordance with NRC and DOT regulations.

All radioactive materials l

will be handled by experienced Westinghouse personnel in accordance with written procedures.

7.0 TECHNICAL AND ENVIRONMENTAL SPECIFICATIONS Technical Specifications for the NTR license have been amended for the

" Possession Only" Facility License.

These Technical Specifications (Appendix A) will remain in ef fect during the dismantling of the reactor and Facility.

8.0 PROPOSED TERMINATION RADIATION SURVEY PLAN The final radiation survey plan divides the Facility into three sections based upon the probability of contamination (See Figure 15).

Results of surveys conducted throughout the life of the Facility indicated that no contamination has ever existed within the Facility.

Fuel inspections and smear surveys were used to confirm the consistent integrity of the fuel clad.

iherefore no alpha contamination has been experienced due to Uranium or fission products within the Facility.

Water, air and smear surveys have consistently yielded results which indicate that no contamination was present in the facility.

The final survey will use a formalized procedure based on a sampling inspection plan to assure adequate coverage of the Facility and guarantee that unrestricted use of the Facility will not cause a radiation hazard to the public.

Section I will include the briefing room, console room, reactor l

of fice and wash room / shower f acility.

This section has the lowest l

potential for contamination since the functions performed in these areas did not involve radioactive materials.

The areas of Section I will be divided into 3 meter by 3 meter grids, and approximately 30%

of the grids will be selected f or survey.

Grid selection will be i

30 0151N 1

1

randomly distributed throughout each room of the section.

Each g~.s U

selected grid will be divided into 1 square meter regions.

Five of the one square meter regions in each selected grid will be surveyed as per Figure 16.

Five evenly distributed beta / gamma and alpha surveys will be taken on each region surveyed as shown in figure 16.

These five surveys will be used to determine the " Maximum" and

" Average" contamination levels as per Regulatory Guide 1.86.

A smear sample of 100 square centimeters will be taken at the center of each of the surveyed regions in the selected grid.

These smears will indicate that the " Removable" contamination levels are below the guidelines established by Regulatory Guide 1.86.

A gamma survey will be conducted 1 meter f rom the center of the grid and will be limited to 5 y R/hr above background.

Section 11 will. include the machine shop, hallway, HP lab and the janitor closet.

Although, historical radiological data indicates no contamination in these areas, the work performed in these areas occasionally involved handling of radioactive materials.

Section

/~N Q

II will be divided into 2 meter by 2 meter grids and approximately 30% of the grids, selected at random, will be surveyed.

Each grid will be divided into one square meter regions with two diagonal regions surveyed as in Section I.

A gamma survey will be conducted 1 meter f rom the surf ace at the center of the selected grid.

Section III consists of the Reactor Room.

Areas such as the floor, reactor tank, dump tank and lower walls have the highest potential for contamination.

These areas will be sectioned into 1 meter by 1 meter grids and each grid will be surveyed as in Section I.

Vertical surfaces above 2 meters and overhead surfaces will be surveyed with uniform, but larger grid spacings.

Smears for each section will be taken and counted for beta / gamma and alpha.

Limits for removable beta / gamma contamination will be 200 dpm/100 square cm. and 20 dpm/100 square cm for alpha as per Regulatory Guide 1.86.

)

{

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0151N j

l (g~D All instruments used for these surveys will be currently calibrated in accordance with approved NTR calibration procedures.

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FIGURES NUMBER TITLE 1

Map of. Local Area i

2 WNTC and NTR Facility Building 3

Smear Sample Survey for NTR Facility (6-2-87) 3A Smear Sample Log Sheet (6-2-87) 4 Area Radiation Survey of NTR Facility

-)

i 5

Top View of NTR Core 6'

Reactor Assembly

?

Reactor Assembly Radiation Survey 8

Reactor Assembly - Materials

/'

9 Moderator Purification / Heater System 10 Reactor Air System 11

.00mp Tank Sump Arrangement 12 Semi-Annual Smear Sample Survey for NTR Facility 12A,B,& C Smear Sample Log Sheet (Semi-Annual 4-2-87) 13 NTR Staff Organization O

0151N

FIGURES

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NUMBER TITLE 14 Tentative Dismantling Schedule 15 Final Facility Survey Map 16 Section Grid Surveys O

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e FIGURE-15 i.

3 meters 1 meter e

e e

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?

s SECTION GRID SURVEY CONFIGURATION l

FIGURE-16 l

'l 4

)

f TABLES V

NUMBER TITLE I

Operational Power History II composition of Aluminum Utilized in NTR q

i l

III Monthly facility Smear 'Results Summary

]

l 1

IV.

Air Survey Sample Results Sumary j

V Reactor Water Survey Results Sumary VI Demineralized Resin Survey Sumary O

l l

I 1

O i

)

n O

Operational History

\\)

1972-19E6

/

This is a summar> of the integrated power and.run hours.for the NTR since it was licensed (R 119) on.Jen 2E, 1972.

REPORTIN3 YEAR RUN TIME INTEGRATED POWER HOURS

( Pb.'-HP S )

1972 931 28.559 1973 760 18.260 l

1974 245 14.200 1975-564 13.377

\\

.1976 1014 29.72.-

1977

'2042 46.43F j

1978 14f5

??.230 1

(

1979 1851 45.045 1980 1929 50.900 1981 1422 24.7 a

1922 2419 56.'289

]

1983 1329 28.500 1984 1530

?2.440 1995 1529 21.430 1986 566 15.735 l

1987 49 0.857

{

l TOTALS 19725 459.741 1

O

)

TABLE I J

l

=

'. (

COMPOSITION OF ALUMINUM UTILIZED IN NTR Reactor Tar # made f r on, a l umi num 60 61-T6 wh i ch c ons i t s of Al-27 98.60%

A6 sorption cross section C[ =

.233 Si-28

.60%

Absorption' cross section CT =

.171 Cu-63,65

.28%

Absor p t i on eross see t i on CPf = 2.750 Mg-24 1.00% ' Absorption eross section CFf =

.063 I

Cr-52

.20%

Absor p t i on c r os s s e c t i on CT, = 3.1 1_

j Dunc Tank is mace cf Aluminum 300? which consists of:

A1-27 98.60%

Abs or p t i on eros s see t i on C( =

.233 g

j section C[ =

3.780 Cu-63,65

.12%

Absorption cr os s Mn-55 1.20%

Abs or p t i on er os s section C[ = 13.3

.3'l

)

1

!\\

TABLE II

i V

i E

&U O

O.

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TABLE V

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E 234I R

N SI I I

l l

O 4

APPENDICES i

i A

NTR Technical Specifications for " Possession Only" i

B NTR Physical Security Plan while Dismantling C

Environmental Report i

i O

4 I

l l

Ck

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

ML20235J701

Text

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