ML20072Q536
| ML20072Q536 | |
| Person / Time | |
|---|---|
| Site: | 05000148 |
| Issue date: | 12/17/1990 |
| From: | NUCLEAR ENERGY SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20072Q535 | List: |
| References | |
| NUDOCS 9012260044 | |
| Download: ML20072Q536 (73) | |
Text
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l DECOMMISSIONING PLAN FOR THE UNIVERSITY OF KANSAS 1
TRAINING REACTOR O
Prepared For:
THE UNIVERSITY OF KANSAS I
Prepared By:
i 1rIE.N NUCLEAR ENERGY SERVICES,INC.
SHELTER ROCK ROAD DANBURY, CONNECTICUT 06810
- A=n8e 38aafge e
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TAllLE OF CONTENTS PAGE
- 1.
SUMMARY
OF PLAN .
. . ..... .. . . ......... . .. 1-1 1.1 Introduction . . .. . . . .. ... ... . . .. .. .. 1-1 1.2 B a c k gro u nd . . . . . . . . . . . . . . . ... .... . ............ ..... 1-1 1.2.1 Reactor Facility De scription . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.2.2 Reactor Description . . . . . . . . .... ................ ... .. 1-1 1.2.3 Operating License History . . . . . . . . . . . . . . . . . . . . . . . .. 1-5 1.3 Decommissioning Program Elements . . . . . . . . . . . . . . . . . . . . . . . . . .. 1-5 1.3.1 Selected Method . . . . . . . . . . . . . . . . . . . .......... .. .. 1-5 1.3.2 Estim at ed Cost . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .... ... 1-5 1.3.3 Availability of Fu nds . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... 1-5 1.3.4 Major Tasks and Schedules . . . . . . . . . . . . . . . . . . . . . ..... .. . 1-5 1.3.5 Program Quality Assurance . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... 1-6 1.3.6 Execu tive Engineer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 1.3.7 Final Radiation Survey P%n ............. .... ........ .. 1-7 2.
CllOICE OF DECOMMISSIONING ALTERNATIVE AND DESCRIPTION OF o ACTIVITIES IN VOLV ED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2- 1 tj 2.1 Decom mis sioning Alternative . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.2 Decommissioning Activities, Tasks and Schedules . . . . . . . . . . . . . . . . . . . 2-1 2.2.1 Activi'ie s and Tas ks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2- 1 2.2.2 Schedule.......................................... ... 2-4 2.3 Decommissioning Organization And Responsibilities . . . . . . . . . ... .. 2-4 2.4 Traini n g Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 -7 2.5 Contractor A s sistance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-8 2.6 Radioactive Materials Unrestricted Release Criteria . . . . . . . . . . . . . . . . . 2-8 2.7 Decontamination and Decommissioning Documents . . . . . . . . . . . . . . . . . . 2-9 3.
PROTECTION OF OCCUPATIONAL AND PUBLIC HEALTH AND SAFETY . 3-1 3.1 Facility Radiological S tatus . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3- 1 3.1.1 Facility Operating History . . . . . . . ........................, 3-1 3.1.2 Current Radiological Status of Far.ilit) . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.2 Radiation Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-6 3.2.1 Ensuring that Occupational Radiation Exposure Are As Low As Reasonably Achievable (ALARA) . . . . . . . . . . . . . . . . . , . . . . . . . . 3-6 3.2.2 Health Physics Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-11 !
3.3 Radioactive Waste Management . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-12 1 3.3.1 Fuel Di spo s al . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3- 12 l
3.3.2 Radioactive Waste Processing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-12 O 3.3.3 Radioactive wasie DisPosai . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-i s i
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TABLE OF CONTENTS (Continued)
O PAGE 3.3.4 General Industrial Safety Program . , ,,.. . .. ... . 3-19 3.3.4.1 General Provisions . ....... . .. .... . .... . 3-19 3.3.4.2 Industrial Hygiene Requirements . .. . . .. 3-19 3.3.4.3 Niedical Surveillance Program . . . . . . . .. . .. . 3-20 3.3.4.4 Hearing Conservation Program . ................. 3-20 3.3.4.5 Respiratory F otection Program . ........ ....... 3-21 3.3.5 B a sic S a fe Prac tic e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-21 3.3.5.1 Fire Protection . . . . . . . . . . . . . . . . . . . ............ 3-22 3.3.5.2 Tools and Equipment ... .................. ..... 3-22 3.3.5.3 l loisting Devices . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-22 3.3.5.4 Personal Protection . . . ................ ....... 3-22 3.4 Accide nt A n alyse s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-2 2
- 4. PROPOSED FINAL RADIATION SURVEY PLAN ....... .............. 4-1 4.1 I n trod u c t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4- 1 4.2 Pn lim i n ary S u rve y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4- 1 4.3 Final Survey Procedures . . . . . . . . . . . . . . . . . . . . . ................. 4-1 4.3.1 B u ildi n g S u rve y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4- 1 4.3.2 Instrumentation and Methods for Contaminated Surface Surveys . .
4.3.3 Documentation . . . . . . . . . . . . . . . ...................... .
4-6 4-6
- 5. UPDA':ED COST ESTIhiATE AND P OF FUNDS . . . . . . . . . . . . . .................................. . . . . . . . . .LAN FOR ASSURING 5-1 AVAILABILITY 5.1 Cost Estimate Summary including Assumptions . . . . . . . . . . . . . . . . . . . . . 5-1 5.2 A s s u m p tio n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 --t 5.3 Availability of Funds . . . . . . . . . . . . . . . ........................... 5-4 6.
TECHNICAL AND ENVIRONhiENTAL SPECIFICATIONS IN PLACE DURING D ECO M M I S S ION I NG . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6- . .1. .
7.
QUALITY ASSURANCE PROVISIONS IN PLACE DURING DECOM MIS S IONING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7. - 1 7.1 Or g an i za t ion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-1 7.2 Quality As surance Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 7-1 7.2.1 Scope ................................................. 7-1 7.2.2 Decommission Contractors Quality Assurance Program . . . . . . . . . 7-2 7.2.3 A ppli ca bili ty . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . 7-2 7.2.4 R e cords and R e port s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-3 7.2.5 A u di t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7- 4 8.
PHYSICAL SECURITY PLAN PROVISIONS IN PLACE DURING m
DECOM MI S S IONING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .8-. .1 REFERESCES ii
l A
V TABLE OF CONTENTS (Continued)
PAGE TABLES 2-1 Estimated Occupational Exposure, mrem ... .. ......... .... ....... 2-3 3-1 10 CFR 20 Radiation Exposure Limits for a Radiation Worker . . . . . . . . . . . .. 3-9 During a Calendar Quarter 3-2 Administrative Limits For Whole Body Dose . . . . . . . . . . . . . ...... ........ 3-9 3-3 Expected Volume of Solid Radioactive Waste Generated Du..ng KUTR Decommissioning Activities . . . . . . . . . . . . . . . . . . . . . .... .............. 3-14 3-4 isotopes Potentiall Characteristic . . .y Present at the KUTR and Their Principal Decay
................................................3--18 4-1 Alpha, Beta-Gamma, and External Radiation levels in KUTR Room, Burt Hall, including Floor and Lower Wall Surfaces . . . .......... ................. 4-5 4-2 Typical Minimum Detection Capabilities for Various Survey Instruments . . . . . . . 4-7 5-1 University of Kansas Research Reactor Decommissioning Cost Estimate . . . . . . 5-2 i
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1 TABLE OF CONTENTS (Continued)
EAGE FIGURES l-1 Reactor Site at KU Campus . .... .. . ..... . ... ... . 1-2 1-2 Nuclear Reactor Building, Lower-Level Flmr Plan . .. ..... . ...... 1-3 1-3 Nuclear Reactor Building Upper-Levet Floor Plan . . .. ... . 1-4 2-1 Program Schedule - Niajor Activities and Tasks . . . ... .. .. . .. . . 2-5 2-2 Organization Structure During Decommissioning Program . . .... ... 2-6 3-1 Top View of the Reactor . . . . . . . . . . . . . . . ...... ..... .... .. 3-2 3-2 Enlarged Top View of the Reactor . . . . . . . . . . . . . .. ... ..... ........ 3-3 3-3 Map of Reactor Ta nk Floor Level . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
3-4 Contact Dose Rates Within the Region of the Thermal Column External to the 3-4 g
Reactor Tank and the Contract Do Pons . . . . . . . . . . . . . . . ......
. . . se.....................
Rates on the Outer Surface .. 3 i of the B 3-5 Map of Concrete Core Bore Samples . . . . . . . . . . . . ................. .... 3-7 4-i Measurement Made in a Typical Survey Block . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-3 4-2 Example of Maximum Observed Beta-Gamma Dose Rate and Direct Alpha Beta-Gamma Points in a Survey Unit ............................, ..... . . . 4-l l
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iv
CHAPTER 1 O 1.
SUMMARY
OF PLAN 1.1 Introduction The Wiversity of Kansas intends to dismantle its lightwater-moderated and light water-coolc e -type nuclear training reactor (KUTR) and to terminate its possession-only license No. ) ': I.ll radioactive materials above unrestricted release limits will be removed from the site to a licensed disposal rnilhy and the site and remaining facility will be released by the U.S.
Nuclear Regulatory Commission (NRC) for unrestricted use by the (Jniversity.
1.2 Background
1.2.1 Reactor Facility Description The KUTR is located in a building on the western edge of the main campus of the University of Kansas at Lawrence. Lawrence is situated on the banks of the Kansas River in the northeast corner of the State of Kansas, approximately midway between Kansas City and Topeka. Figure 1-1 shows the location of the reactor site on the Kansas University campus. Figures 1-2 and 1-3 show the ground level and upper level layout of the KUTR building.
The KUTR and the reactor building share no facilities orequipment with other buildings on the campus except for utilities including electricity, gas, water, compressed air and sewer system.
1.2.2 Reactor Descriotion O The KUTR is an open-pool-type heterogeneous assembly. The core was rnoderated and cooled by light water and was reflected by graphite on three faces and by water on the top, bottom and one face. The fuel elements were of uranium-aluminum alloy clad with aluminum. The fuel was enriched to approximately 93% U-235.
The reactor core was located to on: side near the bottom of a 6.600 gallon tank. The tank is cylindrical at the top and formed with a rectangular pocket on one side near the bottom of the tank to accommodate the core.
The core was composed of thirteen standard fuel elements and three control rod fuel elements, containing a total of 2.5 kg fully enriched uranium.
The structure around the reactor core includes four 6 in, diameter beam ports, a thermal column measuring 4 ft X 5 ft X 6 ft, a shield aank measuring 7.5 ft in diameter and 20 ft high, and a pneumatic conveyor.
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NI 1 AHI A 5497 9 figure 1-3 Nuclear rector building, upper-level f loor pl.in Source: Univ sity of Kansas SAR
Currently, the reactor contipuration includes the aluminum tank (dry), graphite thermal column. beam tubes and beam port plugs and concrete biological shield in-place. The actisated control nxis and sheaths, grid plate assembly (the core support structure), alummum ang's and stamleu steel bolts are stored in the shielded vault in the hot lab (see Figure 1-2). The nonactivated neution detection chambers; control nxl drive motors, magnets, armatures, rai drive extension nxis and guide tubes have also been remosed from the reactor and are stored in the reactor facility.
All nuclear fuel elements and source material have been shipped off-site or transferred to a state license. All unirradiated nuclear fuel element assemblies were shipped to the Oak Ridge National Laboratoly at Oak Ridge, Tennessee on January 6,1986. All irradiated nuclear fuel element assemblies were shipped to the Savannah River Plant at llarnwell, South Carolina in two shipments on January 28,1986 and on February 2,1986. The only residual radioactivity at the facilit) is in certain of the activated components of the reactorincluding portions of the core support structure, aluminum tank wall and biological shield concrete in the region near the core kication.
1.2.3 Doerating License History The KUTR was initially authorized to operate at power levels up to 10kw. In 1971, after approximately 8600 kw-hours of operation, the reactor was authorized to operate at 250kw for short penods. The total thermal energy generated from startup in June 1961 through June 1983 was about 24,(XX)kw-hours.
Of that amount,15,300 kw-hours was after the higher power (peak) authorization. From 1961 through 1977, the reactor was operated primarily as a traming reactor.
From 1978 to cessation of operations in June,1984, the reactor was primarily used for experimentation and demonstration. Since June,1984, the reactor has been effectively shut down.
1.3 Decommissioning ProcratILElements 1.3.1 Srketed Method The University intends to remove all residual radioa: tive materials from the site, verify the absence of residual radioactivity, terminate the Possession-Only License and release the site for unrestricted use.
l.3.2 Estimated Cost The estimated cost of this program, including disposal of all wastes, is $490,000 in 1990 1.3.3 Availability of Funds The State of Kansas is committed to providing the funding for this dismantlement program.
1.3.4 Maior Tasks and Schedules The major tasks of this program include:
- 1. Initial radiation survey of equipment, structures and areas
- 2. Removal of reactor aluminum tank
- 3. Removal of activated concrete of biological shield 4 Removal of beam ports and pneumatic tube 5.
O Packaging, shipping and disposal of irradiated and contaminated material, equipment and rubble at a low level radioactive waste repository 1-5
h Final radiation survey of facility O
- 7. Final report preparation Approval of the decommissioning plan via issuance of a Decommissioning Order by the U.S. Nuclear Regulatory Commissian is anticipated by November,1991. The University of Kansas personnel will prepare a technical bid specification and request proposals from experienced contractors. After the bids have been reviewed by KU management staff, a Decommissioning Contractor (DC) will be selected so that work can proceed on or about July 1,1992. It is expected that the Onal radiation survey and application for license termination will occur by (January 15, 1993).
1.3.5 Procram Ouality Assurance The decommissioning contracto* DC) will be chartered with the responsibility of performir he preparatory engineering, d ' ammissioning w ork, waste packaging and disposal and final radi n survey. The DC will be requed to implement his own radiological control program and quality assurance program, flowever, tile University of Kansas will conduct its own overcheck of the DC's programs to ensure that the wor 6 is performed in a safe and controlled manner.
The University's overcheck program will be denned in a Quality Assurance Program Plan which will include:
1.
Review of contractor's operating personnel health and safety training program
- 2. Review of DC's radiological control program including ventilation, instrument usage and calibration, personnel monitoring and area monitoring procedures
- 3. Review of DC's work procedures with regard to public health and safety and the principles of ALARA
- 4. Audit of contractor records including training, radiation surveys, instrument calibration and shipping data
- 5. Independe.it check of area radiation levels and surface contamination Ic . ls
- 6. Approval chain of documentation to be submitted to the NRC.
1.3.6 lhegutive Engineer The University intends to utilize the services of an Executive Engineer (to be selected) who
- 1. Coordinate University review of decommissioning contractor (EC) de'uments
- 2. Approve DC documents, as trquired, on behalf of the University
- 3. Monitor the work performance of the DC
- 4. Prepare periodic progress and schedule reports, field change reports, radiation survey overcheck reports, and waste shipment summaries
- 5. Exercise control of the work via his authority to cease operations if the wori is not being performed in accordance with approved procedures
- 6. Assist the DC where possible to ensure safe and efficient performance of the program.
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O i.3.7 eiaei amaietion servev nise After completion of the program tasks as listed in Section 1.3.4, the DC will perform a thorough radiation survey of the physical area and structures within the licensed facility boundary.
The survey will be in accordance with NUREG/CR-2082, ":iclitoring for Compliance with Termination Survey Criteria."
The limits of acceptance for unrestricted reler of the facility and for termination of the Possession-Only License are as follows:
1.
Surface contamination shall be below the limits specified in Table 1," Acceptable Surface Contamination Levels," of U.S. NRC Regulatory Guide 1.86," Termination of OperatinF License for Nuclear Reactors."
- 2. Residual radioactivity shall not cause area dose levels to exceed 5 p Rem /hr above background at I m bove the surface of the radioactive materials.
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CilAPTER 2
- 2. CllOICE OF DECOMMISSIONING ALTERNATIVE AND DESCRIPTION OF ACTIVITIES INVOLVED 2.1 Decommissionine Alternathe The University of Kansas has selected the DECON method of decommissioning for the research reactor at Lawrence, Kansas. The definition of this alternative is as follows:
DECON is the removal from the facility site of all fuel assemblies, source material, radioactive tission and corrosion products, and all other radioactive and contaminated materials having activities above unrestricted release levels.
in the case of the KUTR, the facility housing the reactor is the nuclear reactor building (see Figures 1-2 and 1-3). The reactor is contained in the room at the south end of the building. The material to be removed to achieve termination of the Possession-Only License is located in the reactor room, the adjacent hot lab on the lower level and in the upper level radiation lab storage area.
The facility also contains active laboratories, offices and classrooms in addition to the reactor, Therefore, during the dismantlement program, precaution will be taken to preclude unauthorized access to contmiled areas, to prevent the spread of airborne contamination and to prevent any direct radiation hazards to personnel.
2.2 Decommissionine Activities. Tasks and Schedules 2.2.1 Activities and Tasks
- O Since the fresh fuel and spent fuel have already been disposed of and since the coolant in the reactor system has been discharged, the program work will commence with the removal of residual radioactive material. The major activities comprising the program are as follows:
Activity Number Descriotion Contractor INe-Deployment Phase:
1 initial Radiation Survey of Equipment, Structures and Areas 2 Preparation of Program Work Procedures and Program Control Documents -
3 Design of Containment Barriers and Controlled Ventilation System Contractor Post-Deployment Phase:
4 Contractor Mobilization 5 Installation of Containment Barriers and Controlled Ventilation System 6 Removal of Pool Liner and Remaining Pool Internals O 7 Removal of Activated and Contaminated Concrete i
2-1
Activity Nig Descriotion g
8 Removal of Beam Tubes, Pneumatic Tubing and Miscellaneous Piping and Materials 9 Packaging and Shipping of Radioactive Waste 10 Facility and Equipment Cleanup 11 Perform Final Radiation Survey 12 Final Report 1%paration The activities involving personnel radiation exposure are listed in Table 2-1 together with the estimated occupational exposures.
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O Table 2-1 Estimated Occupational Activity Exoosure. m&Em Decontaminate Equipment 48 Prior to Removal Remove Thermal Column Door 22
& Remaining Graphite Blocks from within Thermal Column
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Remove Aluminum Reactor Tank 284 Remove Divider Plate & Chamber 160 Pockets Remove Reactor Box Walls 160 Reactor Tank Aluminum Floor 120
. Set-up and Breakdown 46 Scaffolding, as required to Support Reactor Tank Removal O
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Core Bore Beam Tubes, Remove, 27 Segment and Package Remove Pneumatic Tube Assembly 1 of Activated / Contaminated Materiais &
Concrete Remove Thermal Column Lining 38 Set-up Lower Reactor Tank Region 21 Transport Cart for LSA Material Egress through Thermal Column Door Opening Breakup, Remove and Package 882 Activated Concrete from inside of Reactor Walls and Floor Cut and Package Activated 81 Control Rod Blades, Grid Plates, Bolts and Angles JOB TOTAL: 1890 mrem O
2-3
As noted in Section 3.1.2, the residual radioactise insentory at KUTR is not large.
O Therefore, the expected radiation dose dunng the dismantling program will be relatively small. The residual inventory is concentrated m the pool liner activated concrete and beam ports in the vicinity of the core hicatbn. Removal of the beam ports by concrete bonng is a remote activity which will mimmize esposure. Liner removal and activated concrete removal will require the presence of l equipment operators within the biological shield in proximity to the material being removed.
Ilowever, local shielding can be utilized to reduce the dose contribution. The work area within the biological shield will be enclosed in a contamination control envelope serviced by a i llEPA unit such that the work area will be maintained under a negative pressure relatise to the l
surrounding environment. The llEPA section will be k>eated so as to draw air across the work piece l away from the operators. These steps will result in the occupational exposure being As Low As l Reasonably Achievable. I 2.2.2 Schedule The major activities and tasks are shown in Figure 2-1. The total program durati >n, from receipt of the Decommissioning Order until completion of the Final Radiation Survey is ferty six (4M weeks. It is expected that the Decommissioning Order will be received on or about Nos ember 1991. i I
2.3 Decommissioning Organization And Responsibilities The organization for the management of the reactor facility during the decommissioning program is shown in Figure 2-2. The organization is consistent with that defined in Amendment No.15 to Facility Operating License No. R-78 which authorizec possession, but not operation, of the University of Kansas reactor. $
Two levels of authority are provided, as follows:
Level 1: The individual responsible for site administration, including licensing Level 2: The individual responsible for safe accomplishment of the reactor decommis-sioning program.
Responsibility for the decommissioning program shall be witSin the chain of command shown in Figure 2-2.
O u
' n .v O O O Ist em!WER5fif SF EANSAs .
PRIstavitA Pe0 JECT Pt AenE8 M P W I StTE m aim M. 19 29:38 DECisert1518erer. or as MitAKw eEM tot Em545 MAC7W MC35Bl$11MfGE - 3CIRMIS I
. . . . . . . . . .. . ACT l WI TT M9tRIPf le. . .. . . . . . . . . et 83 2S 27 33 39 IF 24 Of ACilVIIT 19 W W PCT M5 FtWT SOEButE .NE JUL JIE JWL AuE 31 to 28 7e e5 37 39 26 ate AaE ate Aus SE P MP MP sfP 005 ott Mt 92 SF SF 97 92 92 92 ST 97 ett 32 97 92 97 92 92 92 92 Prepare Westentag Presselsene ..-~ - .. ----
40m 35
- DEC fimblitse $tte
- B5905 3
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- 88305 3
- Perfore Confernstory Amdsettom Server
- 8t999 2
- Cemetract CCE ever fame
- 8389G 3
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94005 1
- Ammese femusual Colume Seer and Cemetract CG * -
95308 8
- e.>
8 w = aete Espropommt Prior to ammoval *
- Seges t
- Set ID Cuttleg Statlan and foot Espityment
- 95tes 3
- Amme== Tank 9teteler F1ste S amm med Demo. Pachet
- 85829 8
- Ammswo.
esFr Possumette Ties Asemmbly -
)
Amme e theruel Colums Etelag
- 35F38 I * -
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- SSite 3
- Amme== Activated Cancrete fm Imolais lesdt
- 07199 IS * -- ---- - . - ~
Care Sure Smase Tiene
- 95118 5-
- Clean Iqp and W amenate Tank Amstse
- ST298 8
- Comenct Fleet Andfattoo Serwey
- 99003 9 -
Propero Final Wessestag asport
- 99290 5
- Shty one Despose of Cantantestas* 8teterials
- 33100 F
- f 6ael Site Cleamep
- 89400 2
- Site M iltratten
- es3co 5
- Figure 2-1 Program Schedule - N jor Act ivit ies and Task s
O Chancellor Level 1 l Executive Vice Chancellor l Vice Chancel of Research, Grauuate Vice Chancellor of Studies and Public Academic Affairs Service Director Dean Research, Health and -
Safety School of Engineering g l
ety Officer -
Committee on Radiation -
"fo*m th Radiation Safety Services Reac r Executive Engineer 6
Line of Responsibility
. . . . . . Communication Only Decommissioning o Contractor Figure 2-2 KU Organization Structum During Decommissioning Program g
N 2-6
O V Rady uon Melv Officu The Radiation Safety Officer (RSO) heads the Radiation Safety Service and supervises a profess anal staff. 'is person is a qualified health physicist who shall maintain proficiency in radiatica safety e a he Decommissioning Contractor tDC) during decommissioning activities.
The RSO will ad :he Reactor Director about all matters regarding radiation monitoring and radiation safety Anng decommissioning activities.
The RSO will direct his health physics staff to perfonn independent radiation monitoring audits over the DC health physics staff dunng decommissioning activities and final release survey.
- Nuclear Reactor Committee The Nuclear Reactor Committee, as constituted by Amendment No.15 to the KUTR license, shall monitor facility decemmissioning actisities. This may be accomplished via an independent review and audit of the decommissioning operations by a qualified individual designated b; ine Nuclear Reactor Committee. The audit shall include radiation safety controls, implemntation of approved procedures, instrument calibrations, personnel certification, and all asociated records.
Executive Engign The Executive Engineer will assist the Reactor Director in providing overall contractual direction to the Decommissioning Contractor. The Executive Engineer will be from a nuclear engineering finn who will prepare demolition bidding documents, review bids, and schedule the hg work in accordance with the on-going needs of the University. Th Executive Engineer will supervise the worker safety traiGig and will provide the following services:
1.
Review and approve contractor work procedures and program documents to ensure confonnance to the bid specification
- 2. Continuously monitoi contractor's performance L msure satisfactory execution of the w .rk
- 3. Review and approve all radiation work permits
- 4. Approve and administer all changes and additions to the contractor's contract
- 5. Routinely report on program progress to the Reactor Director Decommissionine Contractor The Decommissioning Contractor shall be an experienced nuclear D&D firm who will be responsible for actual field perfonnance of the dismantling program. The contractor shall be responsible for preparation of detailed work procedures; radiological monitoring and control of his own work; safe removal of all radioactive materials, including demolition, packaging and shipping; performance of the final radiation survey; preparation of the final report in rupport of the license termination application to the U. S. Nuclear Regulatory Commission.
2.4 Trainine Procram o The training program for all personnel directly involved with accomplishment of the d decommissioning program will include:
2-7
1.
O General Emolovee Trainine in compliance with 10 CFR 19.12 for all personnel involved with radioactive materials or in the vicinity of radioactive materials. The radiation safety program will include personnel monitoring, radiation surveillance and monitoring, controlled areas and ventilation, access controls and Health Physics administrative controls.
- 2. Resoiratory Protection Trainine in accordance with the requirements of ANSI >
2-88.2, NRC Reg Guide 8.15, NRC NUREG-0041 " Manual of Respiratory Protection," and 29 CFR 1910.134.
- 3. Liearing Conservation Training to meet the requirements of 29 CFR 1910.25.
4.
Ilazard Communication Trainine to meet the renirements of 29 CFR 1910.1200.
Radiological and demolition-induced hazards ill be reviewed together with precautionary measures.-
- 5. Technical Training including mockup simulation or pre-performance briefings to -
ensure proper equipment usage and achievement of ALARA. Topics will include decontamination, material segmentation and demolition, and- packaging and shipping.
The training will be conducted by personnel qualified in the program contents. The instructors will include the Radiation Safety Officer, the Executive Engineer and others as determined by the Reactor Director.
2.5 Contractor Assistance As noted in Section 2.3 the University intends to hire two outside organizations, i.e., the O
. Executive Engineer and the Decommissioning Contractor. The prece" .of the program by which the University wille ensure that health. and safety will be maintained throughout the
' decommissioning program include:
- 1. Pre-phmning of all work activities via written and approved procedures
- 2. Executive Engineer overcheck to ensure that all work is accomplished in accordance with approved procedures-
? Executive Engineer's authority to stop work at any time and without c uestion should he believe work is not being performed in accordance with approvec; procedures or if he sees a condition that could comp orrise worker or pubhc health and safety
' 4. - Assurance of satisfactory erperience on the part of the Decommissioning Contractor -
- 5. Training of the Decommissioning Contractor's staff.
- 16. Periodic audits of program performance by-the Radiation Safety Officer and the p Nuclear Reactor Committee
~ 2.6 Rndinactive Materials Unrestricted Release Criteria :
h Decontamination and Decomrpissioning Documents The Radioactive Materials Unrestricted Release Criteria limits for surface contamination A shall be below the limits specified in Table 1," Acceptable Surface Contamination Levels," of W-USNRC Regulatory Guide 1.86," Termination of Operating License for Nuclear Reactors."
,t t
2-8c
O V The residua! radioactivity shall not cause area dose levels to exceed 5 microRem/hr above background at I m above the surface of the activated materials.
The final survey will be in accordance with NUREG/CR-2082, " Monitoring for Compliance with Termination Survey Criteria."
2.7 Dnentamination and Decommissioning Documents The Decommissioning Contractor will be responsible for preparing and implementing the following Decontamination and Decommissioning Documents during the performance of this project.
- 1. Quality Assurance Program
- 2. Radiological Control Procedures
+
Radiation Work Permit Procedure a
Surface Contamination Control Survey Procedure Airbome Radioactivity Control Procedure Calibration & Maintenance of Survey Instruments Procedure Radioactive Check Source Accountability Procedure O 3 Radioactive Waste Procedures Radioactive Waste Packaging Procedure llandhng, Storage and Shipping of Radioactive Materials Procedure Solidification of Radioactive Liquids Procedure
- 4. Health, Safety and Emergency Procedures General Industrial Safety Procedure
- Health and Safety Procedure Housekeeping Procedure
+
Emergency Action Procedure Waste Transportation Emergency Procedure
- 5. Work Procedures Construction of Contamination Control Envelope (CCE) Procedure O -
^iumiaurt Tank Removai erocedure 2-9 l
Surface Decontamination Procedure h Activated and Contaminated Concrete Removal Procedure Removal of Beam Tubes and Pneumatic Tube Procedure Final Site Radiation Survey Procedure Final Site Clean-up Procedure i
9 9
2-10
CHAPTER 3
~A 3.
PROTECTION'OF OCCUPAT!ONAL' AND PdBLIC HEALTH- AND SAFETY
~ 3.1 Facilitv Radiolocical Status -
3.1; l Facility Ooerating HistnIX The reactor was operated from 1961 through June,1984. A review of the annual operating -
reports and interviews with the reactor management staff indicate there were no unusual events including no radioactive spills within the facility not radioactive releases from-the facihty. The only remaining system beyond the biological shield is a drain linc running beneath the reactor room floor to the equipment room hold up tank, The entire piping run is accessible via an open pipe chase beneath the floor. The KU staff personnel surveyed the drain line and the sample results from the hot lab drain and drain pipe to hold-up tank ascertained no contamination to be present.
3.1.2 _ Drrent Radiological Status of Facility Figure 3-1 shows a plan view of the reactor core configuration and its relationship to the
. beam tubes and the pneumatic' tube. Figure 3-2 shows an enlarged top view of the reactor core '
configuration and its relationship to the beam tubes and pneumatic tube assembly, tThe entire core support structure and the ion, source and fission chambers have been removed.
Area Dose Rates -
The area dose levels within the d;y reactor tank at floor level are shown in Figure 3-3.
- ]%
=
- Figure 3-4 shows the contact dose rates within the region of the thermal column external to the reactor tank and the contact dose levels on the outer surface of the beam ports. Measurements were
.made.widran Eberline Ionization Chamber, Model RO2.-
' Surface Contamination -
There was low level surface contamination on the graphite bl'ocks located 'within _the ,
thermal column region, therefore, low level surface contamination is present in the thermal column area. There is no surface contamination on the inner surface of the reactor tank.
Activation -
.. . Material sam ales in the form of aluminum coupons and concrete borings were taken from -
the reactor tank wal and floor in the vicinity of the core. Approximately 30E(1.6 ft3 ) of the
= aluminum lineris activated with a totalestimated activity of 1.96 pCi's. The pCi's were calculated L based on a linear correlation between the net epm /g of sample #5 (calculated by KU personnel) and the laboratory measured isotopic concentration analysis results of aluminum sampic #5 in pCi/g
, -(predominant isotope.was Co60). The assumption was rnade to set up a linear correlation between "the KU determined net cpm /g results of samples 1,2,3,4 & 6 to the known sample #5 net cpm /g and pCi/g to calculate me remalning samples pCi/g res'.'Its based on a linear relationship _..
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$1 AP OF REACTOR TANK FLOOR 1 EVEL M = N-3-5 .
.I 2 '- .\t' Halfway into Assembly (vertically) 10 14 -:: Middle - Halfway into Assembly e 8- At Bottom of South Wall
~~j 3-5 h. I j
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PLAN VIEW
'All Dose Rate Readin )s in mR/hr L(Readings taker; on N; arch 9,1989)
Survev instrument --
'. Measurements taken with an Eberline Ionization Chamber, Model R02..
Figure 3-3 i - Area Dose Rates Within the Dry Reactor Tank at Floor Level h p-7: 3 t
i MAP OF TilERM AL COLUMN 1.O N Instruments 1.8\2.4 p
East Wall Core (3' out from 5 5
' Core on Wall)-
6 Equal Distance '
from Core Dose Rate stays the same Beam Portq ' 6 8~ 6 4.0 _3.4 ' % 6 5.0 4.6 4.5 $
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. Core PLAN VIEW
'All' Dose Readings in mR/hr
- (Readings taken on May _12,l1989)
Survev instrument-Measurements taken with an Eberline Ionization Chamber, Model R02.
Figure 3-4
- Contact Dose Rates Within the Region of the Thermal Column External to the Reactor Tank -!
' and the Contact Dose Rates on the Outer '
Surface of the Beam Ports ;
.yg .\
l l
G.,
Example: (Concentration of Co60 in. Aluminum sample #3, Linear Correlation)
.(KU results (Laboratory results samp. #3 & #5) samp #5)
(50 cpm /g avg.) X (3.09 E-5 uci/g) = 7.3E-5 Ci/g (21 epm /g) kample #3 results)
(KU results samp. #5)
Of the core supportstructurrs removec i the reactor tank, only the grid plates, bolts and
- aluminum angles show indication of radioactm 9 is predominantly Cobalt 60. Their estimated activity is as follows:
Activity hem Weicht. Ibs (mci) i Grid Plates (2) 18 0.03 i Bolts (20) and Aluminum Angles (2) 5 0.5 8 The samples obtained from the lead shielding and graphite stringers that were located in the thermal column mgion are somewhat activated. The estimated activity of the lead shielding is 1.40
.pCi in approximately ten (10) ft) of lead. The estimated activity of the graphite is 2.28 Ci in g ,
- approximately one hundred and twenty (120) ft3 of graphite. There was no indication of alpha activation. '
Core samples were taken of the activated concrete as shown on Figum 3-5. . An analysis of -
the samples indicates low levels of activation as determined by laboratory analyses of the concrete .
core samples. The same type of assumption was made for the concrete com sample #3 with respect to sample. #2 with known net epm /g & Ci activity by correlating the net epm /g and pCi/g to determine total activity as calculated for the activated aluminum. Based on the laboratory results an 3
. estimated .008% (15 ft ) of the total volume of the concrete shield is activated with a total estimated' activity of 4,865 pCi's.
3.2 ~ Radiation Protection 3.2.1 Ensurinc that Occunational Radiation Exoosure Are As = Low As Reasonablv- ;
Achievable (ALARA)
The Universityi of Kansas- administration, through its . Radiation Safety Office, has established a policy for the campus of minimizing all radiation exposures to ALARA. This requirement will be transmitted to the Decommissioning Contractor who will be required to prepare an ALARA Plan specific to the decommissioning of the KUTR; The plan shall demonstrate
. knowledge of the source of radiation during dismantling, pre-)lanned mitigation 'of the source impact, pre-planned-minimization of the duration of personne. exposure to the source and the protection of personnel during their exposure. The ALARA Plan'shallinclude, as a minimum, the infonnation hsted below.
, , _. _ . ~ . .-
1 MAP OF REACTOR TANK Reactor Box N g
,, steg ,
g PLAN VIEW 1 14.5" from Step 4 14.5" from Step O.
- 27.5" from Floor 27 "" from Floor 2.5" from Step 3- from Step 31.5" from Floor dead center ca Floor
~
2 r 15" fro p
[7 N h
/
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' x L
@g, w g ELEVATION VIEW Figure 3-5 Map Of Concrete Core Bore Samples 3-.7
1 l
l Description of Worker Training - All personnel working on this project and in the vicinity O
of the reactor room will be given instructions in radiation safety prior to the commencement of their work activities. There shall be three types of training:
- 1. Non-radiation workers
- 2. Radiation workers directly involved in handling activated or contaminated materials and entering radiation areas
- 3. Persons directing the activities of radiation workers The training program will follow the guidelines of the institute for Nuclear Power Operations General Employee Training Program. OSHA hazardous environment protection training shall also be provided with emphasis on dust ingestion prevention, noise mitigation and handling of heavy loads.
Additional briefings and practical training will be performed as required to review work procedures, equipment usage, radiation control requirements and specific hazards associated with certrin procedural steps. Records of each individual training will be maintained by the DC on the job site Administrative Controls - Three areas of radiological control are pertinent to this dismentling program including:
- 1. Personnel radiation exposure limits
- 2. Radiation work permits O
- 3. Surface contamination area isolation.
The personnel radiation exposur limits are established in 10 CFR 20, Standards for Protection Against Radiation. They are summarized in Table 3-1.
O 3-8
h'
- Table 3-1 10 CFR 20 Radiation Ewosure Limits for a Radiation Worker Durine a Calendar Ouarter h
Maximum Ai!owable Bodv Element BaQ! ation Exoeg,(e. mrem
(
Whole body, gonads, 1,250
. blood forming organs, lens of eye.-
Hands and forearms, 18,750 feel and ankles
- Skin of the whole body 7,500
'Under no circumstances shall the limits of Table 3-1 be exceeded.
' Because of the nature of the work and the relatively low radiation fields anticipated during-
. this decommissioning program, the work can-be accomplished with much lower radiation dose to the workers. *"herefore, the administrative limits shown in Table 3-2 will be adhered to throughout this program, g Table 3-2 8 Administrative Limits For Whole Body Dose
-Maximum Dose, mrem -
Non-radiation workers Radiation Period: ' and Visitors 1 J.S_ .
1 Daily 20 .100 1Weekiy 50 250.
Calendar Quarter - -100. 500 Visitors and non-radiation workers must be es::orted by a radiation worker whenever they; enter a controlled'areaso Although tiiere is no public exposure expected due to the decommissioning program for the
_ KUTR, the decommissioning contractor shall ensure that the limits for pubic exposure specified in 4
a10 CFR 20.-105, Permisslble Levels of Radiation in Ucrestricted Areas, are not exceeded.
"101 1 L--_____--______-________--_. _ _
O Radiation Work Permits will be prepared to assure that the radiological . .,ar hazardous work conditions associated with a specific activity or group of activities are well-defined; that all necessary preparations and plant conditions have been established; and that all required personnel protective measures are clearly specified. All Radiation Work Permits shall be approved by the Executive Engineer and by the Reactor Safety Of6cer. Work within a radiation or controlled area cannot commence without an approved Radiation Work Permit. Should radiological or hazardous conditions change significantly during the performance of an activity under a Radiation Work Permit, then it is incumbent on the decommissioning contractor's field supervisor to stop the work and initiate a revision to the permit which reflects the changed condition.
As a minimum, all RWPs shall contain the following information:
1.
Radiation and contamination mapping based upon current radiological surveys, analytical results, and calculations
- 2. Explicit description and survey of the available work area (e.g., contaminated areas,
" clean" working areas, examination area. low dose waiting areas, hot spots, etc.)
- 3. Access requirernents to control the spread of contamination from contaminated to
" clean" working areas and methods employed to minimize exposure to all personnel 4 Description of the methods to identify and mark all removed items, and note their place or origin, their contamination and radiation levels, and any other pertinent raciological information
- 5. Description of packaging contaminated wastes in appropriate containers (as prescribed by NRC and DOT regulations and radwaste disposal site criteria) g 6.
Explicit description of the protective clothing and respiratory equipment required 7.
Listing of work area monitoring requirements necessary to detect changes in the radiological conditions
- 8. Lisiing of trquired personnel dosiraetry and protective devices
- 9. Re ,uiremente for Radiation Control Technician (RCT) coverage (continual, intermittent, on-call, or not required)
- 10. Description of the work to be performed including estimates of time required 11.
Requirements for additional information (pre-job briefings, additional training, ALARA briefings, etc.)
- 12. As addendum to the RWP, personnel entry logs shall be maintained to document entry and egress from areas governed by the RWP and to track accumulated exposure for ongoing work All work involving the demolition of contaminated materials or potentially contaminated material shall be performed within a contamination controlled envelope (CCE). The CCE shall be maintained at a negative pressure telative to the environment outside the CCE during the time that physical demolition or handling of the material is occurring. The exhaust from the CCE will be through a HEPA unit to ensure retention of potential contamination. All personnel entries into and exits from a CCE shall be made at a contamination control point which shallinclude a step-off pad, replaceable floor covering (paper or plastic) for contamination contro!, personnel radiation 3-10
O monitoring equipment, and repository for used anu<ontamination clothing. All equipment or materials to be removed from a CCE and intended for unrestricted use shall be surveyed and verified that the limits of Table 1 in NRC Regulatory Guide 1.86 are met before being released from the control point. If the limits are exceeded then the material or equipment shall be decontaminated before being released.
Plannine -In planning the details of the decommissioning program, the general sequence to be followed will be the removal of the most activated material first. This serves two important ALARA purposes:
1.
Retains the inherent shielding of the biological shield during removal of the activated material, and 2.
Minimizes the period of exposure of the work force to the htrgest segment of the radioactive inventory.
Soecial Techniaues and Practices - The decommissioning contractor will be encouraged to utilize local shielding where appropriate to reduce exposure fields. A separate HEPA exhaust system shall be maintained at the point of demolition to further minimize the potential spread of contammation.
All demolition activities involving the potential for airborne contamination shall be accomplished with workers using appropriate respiratory protection equipment.
The decommissioning contractor has the responsibility for reflecting ALARA concepts in the detailed planning of the program and for the day-to-day implementation of ALARA principles Q in the accomplishment of the work. The Executive Engineer and the Reactor Safety Officer will reflect the University's res aonsibility for ensuring the achievement of ALAR A via their approval of program documents incluc ing Radiation Work Permits. The Executive Engineer will also monitor the decommissioning contractor's performance to ensure that program requirements are adhered to.
3.2.2 Health Physics ProRGm The implementation of the health physics program during the decommissioning campaign will be the responsibility of the decommissioning contractor. Approval and monitonng of the contractor's program will be performed by the University 'f Kansas' Radiation Safety Officer. The contractor will be responsible for:
- 1. Preparation of a health and safety plan 2.
Provision of a full time health physics staff to perform all survey, monitoring and radiological control functions 3.
Selection of appropriate instrumentation for radiation and contamination surveys and for personnel monitoring
- 4. Calibration, testing and maintenance of the instrumentation 5.
Monitoring of effluent discharges from contamination control envelopes.
Health and Safety Plan - This document shall include a description ot aie controls to be exercised to minimize personnel exposure including stipulation of radiation exposure limits to Q workers and non-radiation worker personnel; personhel dosimetry including film badges, self-reading pocket dorimeters, extremity TLDs and tracking of radiation exposures; internal 3-11
radiological monitoring including bio-assay and excretion analysis: identification and monitoring of controlled areas including radiation areas, controlled surface contamination areas, airborne h
radioactivity areas, and radioactive materials areas; radiological survey techniques and frequencies; reuiratory protection including engineering controls and respirator use; air monitoring and t ust control; contamination control; and satisfaction of OSHA requirements.
For the measteement of area dose levels near background, a ratemeter with a 2 inch by 2 inch Nal detector shall be used. Air ionization chambers will be used to measure exposure rates above 0.1 mR/per hour. An ionization chamber with a remote telescoping extension will be available for high radiation area measurements should the need occur Fixed contamination shall be measured with a GM probe for beta-gamma contamination and a scintillation probe for alpha contamination. SCpc surveys for loose contamination shall be measured with laboratory equipment or with appropriate GM and scintillation probes.
A written procedure for the calibration and maintenance of survey instruments shall be prepared by the decommissioning contractor, it shall identify the staff responsibilities for instrument control and records. The procedure shall also deOne pre-use instrument check requirements, protection and storage ofinstruments, and calibration requirements. A!! instruments used for surveys shall be calibrated at no greater an interval than six months and after every instrument repair.
The contractor shall prepare an airborne radioactivity control procedure which shall define how compliance will be attained with the provisions of 10 CFR 20, Appendix B, Table II, Respiratory Protection Requirements and Use. The procedun shall deOne air sampling techniques and frequencies; the calculation of beta-gamma and alpha concentration in the air samples; the use of portaole and continuous air monitors; air sampling of the environment outside the centamination control envelopes; and maintenance of air sampling records. The procedure shall also define the a
W limits and conditions under which full-faced respirators or hoods shall be worn; airborne limits for alpha and beta-gamma beyond which personnel will not be allowed entry into the area; respirator maintenance and decontamination; and the operation of HEPA-protected contamination control envelopes. All demolition activities which have the potential of creating airbome radioactivity shall be performed within a contamination control envelope (CCE). Whenever work activities are occurring inside a CCE, a HEPA exhaust system, sized for at least three CCE volume air changes per hour, shall be in continuous operation exhausting from the CCE. In addition, HEPAs shall also be utilized to control known airbome generatmg activities such as burning or scabbling on contaminated materials so that a separate exhaust can be taken at the point of generation within a CCE.
3.3 Radioactive Waste Manacement 3.3.1 Fuel Discosal l
1 All nuclear fuel has been shipped from the site. The irradiated fuel was transported in two shipments to the Savannah River Plant in the Model 700 cask, USA /5942/B( )F on January 28, 1986 and February 2,1936. The unitradiated fuel was shipped to Oak Ridge on January 8,1986.
l 3.3.2 Radioactive Waste Processing l
Since all systems at KUTR am dry, the only source of radioactivity during decommissit ing will be the solid waste associated with the concrete and metallic structure of the reactor facility. Thir radioactivity will evidence itself in three radwaste forms: a W
l 3-12 l
- 1. Airbome particulates
- 2. Solids
- 3. Some contaminated liquids from cutting operations The airborne particulates will be generated during the mechanical demolition of the concrete biological shield and the mechanical cutting of the alun:inum tank and the beam tubes.
This contamination will be controlled within a CCE by local HEPAs.
The solid radioactive waste will be comprised of the reactor tank material concrete biological shield and the integral metals of the beam ports, pneumatic assembly, thermal column liner and reinforcing bar. This material will be cut into segments which will be packaged in LS A boxes for shipment to a low level radioactive waste repository. The expected volume of solid radioactive wastes is shown in Table 3-3.
i
/
O O
3-13
)
i Table 3-3 Exoected Volume of Solid Radioactive Waste
- a-Generatedj2unnE.KUTR Decommissionine Activities Radioactive Waste Volume, Ft3
'Descriotion (Includina Packaa_ino_i -
- 1) Poly Sheeting from inside of 96
' Thermal Column Door & Graphite -
Blocks
'2) - Activated Aluminum Liner- -
-96 (50 Ft3 w/ packaging efficiency)
Beam Tubes (4 - 6 fong X 6" diameter segmented in half)
Pneumatic Tube Assembly (Segmented)
' 3) . Thermal Column Lining & Reinforcing 96 Bar.
_g; R
4)- Activated Concrete from Reactor- 96 Shield '
5): : Angles,1 Bolts, Control Rod Blades, 192
- and Grid Plate Assembly?
+ ,
~
rh i-.
~
576 Ft3
( ~'
- NOTEi - All radwaste: generated during decommissioning activities (i.e., dn:ss out materials--
anti C's,'bootics, gloves, respirator cartridges, etc.,-and all contaminated materials:
fgenerated from disassembly of all CCE's and final clean-up of site) will not generate -
additional radwaste containers,'but will be packaged in the void spaces of the listed" radwaste containers.
0; 3-14
, _ = _ _ - _ _
__ _ - . _ = . . ..
Liquid contamination may be generated during certain evolutions w here cooling water must be supplied to a cutting tool. The volurne will be small and will be processed manually. That is, the liquid will be mopped up and manually solidified in a LLW drum for disposal at a burial facility.
No existing plant system will be required or utilized in the processing of the radioactive waste. The temporary systems are limited to the airbome controlled ventilation llEPA exhaust systems and the manual solidification of contaminated lic, ands.
3.3.3 Radioactive Waste Disposal The DC shall pn pare a procedure for Ha'dling, Storage and Shipping of Radioactive Materials with a section specincally on Radioactive Waste Disposal. This section shall contain the provisions of 10 CFR 20.311, Transfer for Disposal and Manifests and 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste, and applicable disposal site license conditions for processing and disposal of low-level radioactive wastes shall be met.
- 1. Radioactive Material Shiomen Manifest (Provisions of 10 CFR 20.311)
The Radioactive Material shipment manifest shall include the following:
1.'l A completed radioactive material shipment record with each shipment of Low Specific Activity (LSA) Radioactive Material.
1.2 Utilize the U.S. Ecoloay, Inc. Radioactive Material Shipment Manifest g for radwaste shipmenti to the Richland, Washington disposal site.
Q 1.3 Radioactive Material Shipment Record should contain the following in-formation:
- 1) Shipment Number - From the Radioactive Material Shipment Log.
- 2) Shipment Date - The date the shipment leaves the KUTR facility.
- 3) Carrier - The name of the carrier transporting the shipment.
- 4) Driver signature -The signature of the driver picking up the ship-ment.
- 5) Number of Packages - The total number of packages in the ship-ment.
- 6) Total Activity - The total activity (in curies or millicuries) of all packages in the shipment.
- 7) Total Weight - The total gross weight (in pounds) of all packages in the shipment.
- 8) Total Volume -The total volume (in cubic feet) of all packages L in the shipment. The volume is based on the external physical t
dimensions of each package.
p
- 9) Proper Shipping Name/ Identification Number- Check the space next to Radioactive Material, LSA, NOS, UN 2912.
3-15
- 10) Enter the total number of pages.
O Il) Consignee - The organization receiving the shipment.
- 12) Contact - The individual within the receiving organization re-sponsible for receipt of the shipment.
- 13) Address - The delivery address for the shipment.
- 14) Telephone Number - The telephone number of the receiving or-ganization.
- 15) License Number - The radioactive materials license number of the receiving organization.
- 16) Exclusive Use Vehicle - Check: Yes
- 17) Item Number - The serial number of each individual package.
- 18) Material Description - A brief description of the material.
- 19) Radionuclide - List each radionuclide present in the material.
- 20) Activity mci - The activi y, t in millicuries, of each listed radionuclide if activity is less than the lowest level detectable (LLD), that shall be noted and the LLD Identified.
- 21) Physical Form - Enter: Solid h
- 22) Chemical Form - The most prevalent chemical form of the mate-rial: metallic oxides, toluene, specific acids or bases, etc.
- 23) Type Package - Enter: Strong-Tight
- 24) Package Weight - The total gross weight in pounds of the pack-age,
- 25) Package Volume -The volume in cubic ft of the package based on the ext:rior dimensions.
- 26) mR/hr item Surface - The maximum dose rate on contact with the surface of the package.
- 27) mR/hr Package Surface - The maximum dose rate on contact with the surface of the pack9ge.
- 28) mR/hr Package 1 meter - The maximum dose rate at any point I meter from the package surface.
- 29) dpm/100 cm2 Alpha - The maximum loose surface Alpha con-j taminatior on the surface of the package. If less than 22 dpm/100 cm2, may be entered as < 22.
- 30) dpm/100 cm2 Beta-Gamma - The maximum loose surface Beta-Gamma contamination on the surface of the package, if less than 220 dpm/100 cm2, may be entered as < 220.
4 3-16
h 31) Label - Enter: Radioactive LSA - No Label Required
- 32) The signature of the KU representative.
- 33) Date - The date the certification is made.
2.
Waste Classification (Provisions of 10 CFR 61)
The criteria for waste classification for low-level waste disposal is con-tained in 10 CFR 61. The significant radionuclides generated as a result of neutron activation are shown in Table 3-4. In addition the KUTR contains a very small quantity of stainless steel, present in componer ts such as grid suppon plate bolts. It is concluded that the radioactive wastes from the K UTR can be classified as Class A.
Class A wastes do not need to be segregated for disposal, providing they meet the stability criteria described in paragraph 61.56 of the regulation (i.e., wastes do not structurally degrade and affect the overall stability of the disposal site through lump.
ing, collapse, etc). The type of waste container to be used to package the LS A mate-rials is a 4'x 4'x 6', B-25 (96 ft )3and the estimated volume of LSA materials to be generated incliing packaging is listed in Table 3-3 in Section 3.3.2.
The radioactive waste from the KUTR decommissioning will meet these cri-teria because they will be in solid form (aluminum liner, concrete and other metal components). To further comply with the regulations, the containers will be filled so that voids will be kept to a minimum for ensuring structural stability when over-burdened or when other packages are placed over them. The estimated waste vol-q umes include packaging (4'x 4'x 6', B-25 container,96 ft )3 are listed in Section
- b. 3.3.2.
The activity concentrations of the aluminum liner, concrete and other metal components waste that are activated can be found in'Section 3.1.2.
1 L'
V l
Table 3--4 l Isotones Potentially Present at the KUTR and Their Principal Decav Characteristics Decay IEQlb. Half-Life Mode C-14 5730 y p- \
Mn-54 303 d EC(a), 7 Fe-59 45d p ,y Co-57 270 d EC,y Co-58 71.3 d p+, EC, y g,; Ni 7.5x104 y EC,y Co-60 5.26 y p ,y Ni-63 92 y p ,y Cs-134 2.05 y p ,y h Cs-137 30.0y_ p , EC, y Ce-144 284 d p , EC, y Eu-152 12 y p , p+. EC, y (a) Electron Capture.
O l
3-18
A D 3.3.4 General Industrial Safety Program The General Industrial Safety Program (GISP) for the decommissioning project shall pertain to and fulfill the requirements of the federal Occupational Safety and Health Administration 10SilA) as presented in 29CFR1910 (as revised) and the requirements imposed by tha Decommissioning Contractor.
3.3.4.1 General Provisions All personnel shall comply with the requirements of this program for all DC work activities.
Supervisory personnel shall be responsible for taking corrective actions concerning occupational hesin, safety, and environmental deficiencies resulting from their operations.
Deficiencies or violations which endanger " life" or " limb", as determined by the DC, shall be immediately corrected and work shall not proceed until such corrective measures are in place.
On a weekly basis, the Executive Engineer along with the DC shall perform safety inspections of the DC's operations and equipment to assure compliance with the requirements of ths program and all applicable state, federa) , local, and KU regulations. Documentation shall be
.naintained in a daily log book by the Executive Engineer and the DC for all safety and health inspections performed. Any safety violations will be identified, recorded in the log 1,ook and the corrective actions taken immediately. The following items will be specifically addressed during these weekly inspections as a minimum:
- 1. ~fntegrity of CCE's
- 2. Proper Maintenance of Step-Off-Pads
- 3. HEPA Performance 4 Raowete Packaging
- 5. Air Monitor Performance
- 6. Radiation Work Permits
- 7. Hearing Protection
- 8. Barricades
- 9. Safety Signs
- 10. Scaffolds
- 11. Tripping Hazards
- 12. Storage of Combustible Materials
- 13. Lifting Devices 4 3.3.4.2 Ini trial Hvgiene Reaukements All work performed under the DC supervision shall ensure that personnel exposures to
-(V~N toxic or harmful physical agents do not exceed the limits specified by (1) subpart Z of 29CFR 1910, 3-19
i or(2)the current threshd limiting values of the American Conference of GovernmentalIndustrial Hygienists (ACGlH).
e Personnel may be rec uired to c ear xrsonal monitoring devices in order to assure compliance with the above. All such devices s Tall be supplied and maintained by the DC.
3.3.4.3 Medical Surveillance Procram The Medical Surveillance Program is established for all workers who may be W occupationally exposed to radiological or hazardous chemical agents and is implemented by the DC. A baseline health assessment shall be completed for each individual worker by a licensed Medical Doctor. The baseline health assessment shall include the following:
1.
Pre-deployment medical examination, int ding pulmonary adequacy and audiometne response 2.
Up-to-date Fomi 4 occupational radiatin exposure history
- 3. Pre-deployment Bioassay After completion of the project, post-performance bioassay and post-performance audiometric response tests will be required.
Personnel health assessment records shall be maintained on file with the DC site Radiation
- Protection Department and shall be maintained in accordance with federal requirements for ir.clusion of exposure data, including appropriate update frequency and access privileges. These mcords are available for inspection by KU and the Executive Engineer at any time and become the property of KU upon completion and termination of the project. a W
Non-routine medical treatment or emergenc nearest and most convenient location including ony medical treatment shall be performed at the site facilities if available. Off-site medical treatment of personnel shall be L hospital or emergency clinic. performed at a facility licensed to handle such cases, for example In cases of personnel injury transportation shall be of the most expeditious available, for example, private automobde or ambulance service.
The worksite shall be monitored for health hazards associated with the work environment,
~ including chemicals that may be present in liquid, dust, fume , mist, vapor, or gaseous forms.
Physical hazards such as noise, presse, vibration, and illumination shall also be monitored and controlled.
3.3,4.4 Hearing Conservation Program The hearing' conservation pro
' of 85 dB( A) or greater (as an 81 hour9.375e-4 days <br />0.0225 hours <br />1.339286e-4 weeks <br />3.08205e-5 months <br />, gram shall apply to all workers who are exposed to noise levels time-weighted average exposure) 'Ihis program will include:
1.
Noise monitoring in areas where the levels exceed 80 dB(A) 2.
Audiometric testing for all workers (as pan of the medical surveillance program) to determine baseline hearing performance before exposure and test results after exposure
- 3. Personnel training and education 4 Recordkeeping
- 5. Hearing protection devices
.g 3-20
l l
1 I
l O Personnel assigned ta ks in known noise--hazardous areas 2.90 dB(A) shall be enrolled in the hearing conservation progtam prior to beginning of work. Other personnel may be required to participate after monitoring reveals that their 8-hour, time weighted average exposure exceeds 85 d B( A).
Noise control measures, including the requirement to wear hearing protection equipment, shall be determined by the DC after appropriate noise monitoring is completed throughout Burt llall and the immediate area surrounding the facility.
Records sh ll be maintained that document the following:
- 1. All noise monitoring conducted
- 2. Employee training
- 3. Control measures implemented
- 4. Protective equipment issued.
3.3.4.5 Resniratory Protection Procram The Respiratory Protection Program shall be written in compliance with ANSI 2-88.2, NRC Regulatory Guide 8.15. IOCFR20.103 and OSHA requirements.
The guidelines governing the Respiratory Protection Program shall include the following:
- 1. Written standard operating procedures governing and use of respirators O 2. ^,sisameat or resnoasibiiiiies
- 3. Types of records 4 Training of employees and supervisors
- 5. Qualitative testing
- 6. Work area surveillance
- 7. Medical surveillance
- 8. Special respirator use problems and limitations
- 9. Maintenance and repair of respirators All respirator protection equipment utilized shall meet the requirements of Mine Safety and Health Administration (MSHA) and or National Institute fro Occupational Safety and Health (NIOSH) approved respiratory protection equipment.
All respiratory protection equipment shall be stored and maintained such that it is protected from outside contamination and damage, and routinely inspected.
3.3.5 Basic Safe Practices Basic safe practice is the responsibility of each individual worker. The DC shall provide the tools and equipment necessary to provide the workers with a safe work environment to perform the Q different decommissioning tasks.
3-21
3.3.5.1 Fire Protection Fire protection devices such as portable Type A and B/C fire extinguishers shall be mad:
available by the DC in key locations of the Reactor Room to serve the various cutting stations anc decommissiomng activmes.
Flammable and combustible liquids in quantities greater than one gallon shall be kept in approved metal safety cans. An approved safety can is one which is approved by Factory Mutualor Underwriters Laboratory.
Combustible material quantities shall be kept at a practical minimum and combustible products shall not be allowed to accumulate to the extent of creating a fire hazard as detemiined by the DC. All flammable materials shall be stored a minimum of ten feet from all buildings in a neat and orderly manner in an area designated by KU.
3.3.5.2 Tools and Eculoment All tools and equipment shall be in good condition for use during decommissioning activities. Wheels, belts, cutters, etc.. shall be properly guarded and abrasive wheels and rotating blades shall not be operated in excess of manufacturer's rated or recommended speeds. Scat folding, rigging and staging shall be inspected and conform to the applicable sections of 29CFR1910 and 29CFR1926.
3.3.5.3 Hoistine Devices The Hoisting Devices used by the DC for decommissioning activities (including KU's fuel handling monorail hoist) shall comply with the applicable manufacturer's specifications and e
limitations applicable to equipment operation. Hoisting loads, operating speeds, and special hazard wanings shall be adhered to along with applicable OSHA requirements.
3.3.5.4 Personal Protection All safety equipmen, and apparel shall be furnished by the Decommissioning Contractor.
Personnel are required to wear h'ad protection equipment (hardhats, helmets) when there is a possible danger of head injury from impact, flying or falling objects, or electrical shock and burns.
Hardhats / helmets (i.e., MSA or equivalent for Rad Con work) shall be worn in any area where personnel are working off ground level on a ladder, platform, lift or any such device. This requirement shall apply to all personnel within an area identified and posted as a hardhat area by the Decommissioning Contractor, Hardhats / helmets for protection against the impact of falling objects shall meet the requirements of ANSI Z89.1, Safety Requirements for Industrial Head Protection, latest edition.
Approved eye and face protection meeting the requirements of ANSI Standard 487.1 shall be worn whenever machines or operations present potential eye or face injury from physical or chemical agents.
3.4 Accident Analyses Since all nuclear fuel has previously been shipped off site and since the residual radioactive inventory is very small, there is negligible probability for an accident to occur that could significantly affect occupational or public health and safety during decommissioning activities.
3-22
l
)
CHAPTER 4 l l
O 4.
rRorosen six^t R^oi^rios st <Rvsv ni as 4.1 introduction l
A Onal radiation survey of the facility under NRCjurisdiction will be conducted in order to ensure that the DECON area satis 6es the unrestricted release criteria for radioactive material.
The final radiation survey will be conducted after all other decommissioning activities have been completed.
The detailed plan for the Gnal radiation suney will depend on:
1.
The details of the dismantling / decontamination process
- 2. The results of radiation surveys during that process 3.
The radiological history and other specific characteristics of the KUTR facility 4 The results of the preliminary survey 4.2 Preliminary Survey As stated in NUREG/CR-2082 a brief preliminary radiation survey will be made in order to formulate plans for an efficient, comprehensive survey Before designing the preliminary survey, decisions wil. be made concerning logical divisions of the KUTR room. A minimum number of 30 measurements will be made in each survey unit, and each survey unit should cover an area of at most 30 m2. Dimensions of the survey units will be obtained so that a scaled drawing of each unit can be prepared prior to the tennination radiation survey. The KUTR site has been under a penodic Os survey program and indoor radiation and contamination surveys during operation. Because of this data base, current survey data may be incorporated into the preliminary survey data ifit meets the criteria of NUREG/CR-2082. The preliminary survey ensures the presence of grid markers for locating and recording preliminary measurements. The preliminary survey will aid in deciding how to sample the site; that is, whether by random sampling, stratined random sampling, systematic sampling, or other methods.
4.3 Finst Survey Procedures 4.3.1 Buildine Survey As stated in NUREG/CR-2082 for the final radiation survey, each survey unit is divided into two subunits: (1) lowcr surfaces comprised of floor surfaces, wall surfaces up to a height of 2 m, and any other surface easily accessible to a surveyor standing on the floor, and (2) overhead surfaces comprised of ceiling surfaces, wall surfaces more than 2 m above the floor, and all other surfaces not described in (1). A HEeA unit will be installed in the existing reactor room ventilation system to maintain a negative pressure in the room. This system will serve as a secondary CCE to eliminate the possibility of release of airborne radioactive materials to the atmosphere (in case of a failure of the CCE over the reactor tank during decommissioning activities). The internal surface of the existing n actor room ventilation system will be surveyed for internal contamination up to and including the ventilation exhaust to the atmosphere.
The floors and lower walls will be divided by a rectangular grid system such as that shown in Figure 4-1. The smaller blocks formed in this manner are referred to as " survey blocks," and the O guided by the following rules: corners of the survey blocks are called " grid points.
4-1
1 1
CHAPTER 4 0 4.
PaoroSro eix^t a^oi^rios Suavev etix 4.1 Introduction A Gnal radiation survey of the facility under NRCjurisdiction will be conducted in order to ensure that the DECON area satis 0es the unrestricted release criteria for radioactive material.
The Gnal radiation survey will be conducted after all other decommissioning activities have been completed.
The detailed plan for the Onal radiation survey will depend on:
- 1. The details of the dismantling / decontamination ss
{
- 2. The results of radiation surveys during that process 3.
The radiological history and other specific characteristics of the KUTR facility
- 4. The n sults of the preliminary sursey l
4.2 Preliminary Survey As stated in NUREG/CR-2082 a brief preliminary radiation survey will be made in order to formulate plans for an efficient, comprehensive survey. Before designing the preliminary survey, decisions will be made concerning logicaMivisions of the KUTR room. A minimum numberof 30 measurements will be made in each survey unit, and each survey unit should cover an area of at most 30 m2. Dimensions of the survey units will be obtained so that a scaled drawing of each unit p)
(_
can be prepared prior to the termination radiation survey. The KUTR site has been under a periodic survey program and indoor radiation and contamination surveys during operation. Because of this data base, current survey data may be incorporated into the preliminary survey data if it meets the criteria of NUREGiCR-2082. The preliminary survey ensures the presence of grid markers for locating and recording preliminary measurements. The preliminary survey will aid in deciding how to sample the site; that is, whether by random sampling, stratified random sampling, systematic sampling, or other methods.
4.3 Final Survev Procedures 4.3.1 Buildine Survey As stated in NUREG/CR-2082 for the final radiation survey, each survey unit is divided into two subunits: (1) lower surfaces comprised of Door surfaces, wall surfaces up to a height of 2 m, and any other surface easily accessible to a surveyor standing on the Door; and (2) overhead surfaces comprised of ceiling surfaces, wall surfaces more than 2 m above the floor, and all other surfaces not described in (1). A HEPA unit will be installed in the existing reactor room ventilation system to maintain a negative pressure in the room. This system will serve as a secondary CCE to eliminate the possibility of release of airborne radioactive materials to the atmosphere (in case of a failure of the CCE over the reactor tank during decommissioning act;vities). The internal surface of the existing reactor room ventilation system will be surveyed for internal contamination up to and including the ventilatien exhaust to the atmosphere.
The Goors and lower walls will be divided by a rectangular grid system such as that shown in Figure 4-1. The smaller blocks formed in this manner are referred to as " survey blocks," and the corners of the survey blocks are called " grid points." The choice of the particular grid system is O. guided by the following rules:
4-1
1.
No survey block should measure less than 1 m on a side. Survey blocks ofless than 1 9 m on a side would require an impractically large number of measurements in the buildings.
2.
No survey block should measure more than 3 m on a ude. Survey blocks larger than 3 m on a side could lead to large uncertainties as to the precise location of the contamination.
- 3. There should be at least 30 blocks in the population according to the equation 3.1 in NUREG/CR-2082.
The radiological conditions to be characterized on the lower surfaces include alpha contamination i els (by direct reading), beta-gamma dose rates at I cm above the surface, external gamma radiatio. ;vels at I m above the floor, and removable alpha and beta contamination levels.
At I m aoove the center of each survey block, the extemal gamma radiation level is measured. At the surface in each survey block, five direct measurements each of alpha contamination levels, beta-gamma dose rates, and gamma radiation levels will be made at uniformly spaced points in a 1 m2 area in the center of the survey blocks as shown in Figure 4--2. (if the entire survey block has an area of approximately 1 m2, then the " comer" measurements shown in the I m2 area in Figure 4-2 are moved 30 cm toward the center of the block.) For each type of measurement, the average value and the local variability in this 1 m2 area can be estimated. For an area of only 1 m2, five alpha or beta-gamma measurements will be used to yield an estimate of the average in that area. The survey block is next scanned with a G-M meter (open window), the point showing where the maximum reading (if any)is located; and each type of measurement (including smear samples of measurements of transferable alpha and beta contamination levels)is made at this
" beta-gamma maximum point." a W
The manner of data recording for a building survey is illustrated by the headings in Table 4-1. The following minimum data are needed:
- 1. Survey block numbers, identifiable on a scale drawing, and a) the building name or number; b) the building floor number; c) the surfaces surveyed; I d) types of measurements and tne units (dpm/100 cm2, millirad /h, and/or R/h; mGy/h and microGy/h).
- 2. Name of surveyor taking measurements, date of survey, location data relative to the grid coordinates, and log book pages for original data
- 3. Surface smears, plaster chips, etc., taken, and the indoor block number from where they were taken, the container number, and whether matched to any air readings
- 4. Type, model number, calibration data, sensitivity limit, and any other information needed about th: portable survey instruments to interpret the data obtained with these instruments and to ensure quality control on the data so obtained
- 5. When the block surveyed is below the sensitivity of the instrument, the fact that such a measurement was made will be included as a significant datum g
4-2
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Measurement Made in a Typical Survey Block l 1
1 4-3
f 9
ORNL-DWG. 80-17790 l I i: TYPICALLY ~ 2m- :l 1 I I t: 1m :! l <
, _+_____________.+_
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l* DIRECT MEASUREMENT OFu, p- Y, I l AND Y LEVELS AT SURFACE l Figure 4--2 (See NUREG/CR-2082)
Example of Maximum Observed fletn-Gamma Dose ,
Rate and Direct Measurement of a, B-y and y Levels in a Survey Illock 1
44
.., _ -- . . . - - .- . . . - . . _ _ . = - - .- . . - . - . .
1 Table 4-1 (See NUREG/CR-2082)
Alpha, Beta-Gamma, and External Radiation Levels 1 in KUTR Room, Burt Hall, including Floor and 1.ower Wall Surfaces l Directly measured Directly measured contamination at {
Survey contamination surface at External center of block maximum beta-aamma coint l
block Beta-gamma dose radiatiokamma Beta-gamma dose 1 m abovelevel Alpha rate at 1 cm Alpha floor (dpm/100 cm2) rate at 1 cm I (millirad /hr) (dom /100 cm 2) (R/hr)
(millirad /hr) t A2 100 0.05 100 0.45 3 NAa j 100 0.08 NRb 4 0.08 NA i 200 0.13 NR 0.13 NA i 5 210 0.13 NR 0.13 6 50
'NA 0.13 NR 0.13 NA 7 160 0.05 NR. O.10 NA 8- 220 0.15 270 9 0.23 NA 100 0.15 210 10 210
.023 NA 0.15 - NR 0. ; NA i1 100 0.15 NR 0. NA 12 120 0.15 NR 0.1 NA 13 120 0.28 120 0.28 NA-B 1- 210 0.05 NR .05 NA 2 150 0.10 '
I I 3 160 10 -40 4 220 0.10 0.18 160 h 8. 35 5 260
'60 \/ 6 45 1.8 0 40 6 210 0.1 '
3.5 50 7 150 8
0.50 75 280 0. 21 9
1.5 70 160 0. I60 2.8 100 10 :290 0.2 3.0 130-11 260 .25 210 0.35 12 120 150 0. '0 110 13 0.70 130 150 0.75 220 14 160 0. NR 0.15 NA C1 30 0.05 NR 2 110 0.05 NA 0.09 NR 0.09 35 3' 7 0.08' NR
~4 0.15 40-0.13 140 0.35 '60 5 O.15 130 1.3 80 6 120 0.13 290 7
1.3 75-140 ~ 0.13 80 8
0.30 70 220 - 0.30 280 3,5 9 50 260 0.08 200 0.65 10 55-110 0.11 270 0.20 55 11- 210 0.15 260 0.33 12 90 170- 0.15 100 13 0.20 85 170 0.40 210 1.0 170 aNA = not applicable bNR = no reading taken l l
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4.3.2 O
Instrumentation and Methods for Contaminated Surface Survevs As stated in NUREG/CR-2082, determining instrumentation to be used in the decommissioning activities, isotopes of concern must b'e identified. Those isotopes that may be l present as contamination are listed in Table 3-4 in Section 3.3.3. The instruments to be used in the l radiation surveys will be selected on the basis of the type and level of radiation anticipated as a result of reviewing KUTR historical data, the decontamination process, and the results of the preliminary survey.
l Both the direct and indirect (wipe) monitoring methods will be used to obtain a complete l assessment of the surfaces being examined during the termination survey For direct methods of l surface monitoring, the scanning speed will be slow enough to ensure a source detection probability I of at least 507c. When surface activity is deMeted, the probe will be held stationary for a i
quantitative measurement and the instrumem rea;
- will be averaged over 100 cm2 and compared to Table 1 of NRC Regulatory Guide 1.86 for tr . disposition of the area being surveyed. I The amount of removable radioactive material will be determined by wiping representative l portions of the surface being surveyed with soft absorbent material and applying uniform moderate pressure. Efforts should be made to standardize, as much as practical, the procedure for taking the '
wipe.
Instrument Selection -The instruments used for direct and indirect monitoring of surface contamination will be capable of measuring surface activity at the guide levels specified in Table 1 of NRC Regulatory Guide 1.86. Instruments will be tested and calibrated in accordance with the specifications contained in the American National Standard," Radiation Protection insuumentation Test and Calibration," ANSI N323-1977, or the most recent revision. 3 W
Table 4-2 lists the detection capabilities of the various types of survey instruments that could be used to support decommissioning activities.
4.3.3 Rocumentation As stated in NUREG/CR-2082, proper documentation of every as 3ect of the program is necessary for future reference to the decommissioning survey. The DC sha 1 maintain an accurate mapping of the reactor room and surrounding area within this decommissioning project for future review and verification by a regulatory inspector.
Instrument measurements and analytical results will include the following data:
- 1. Location of the measurement or sample
- 2. Date or dates of measurements or sample collection
- 3. Measured concentration of the specific nuclides in pCi/m3 or mBq/m3 for air samples; pCi/g or mBq/g for soil samples
- 4. Analytical error at 957c confidence level should be reported for all analy-ses e
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l O rabie 4-2 Typical Minimum Detection Capabilities for Various Survey Instruments Sudace Types Nuclide Instrument or Method Detection Levels Soil Gross ZnS scintillator a 102 pCi/cm2, source depenaent Alpha Gross Thin-walled, shielded 500 - 5.000 pCl/cm2, Beta gamma Pancake G-M Emax a 0.15 MeV Nai detector 500 - 5 x 10s pCi/cm2 ton chamber / micro Rem a 103 pCi/cm2 meter Facilit Gross ZnS scirr .fator a 100 pct /cm2 floors,y walls, Alpha equipment Thin Nat or CaF2 a 30 pCi/cm2, for alpha delay x-rays Proportional chamber a 50 pCl/cm2 O very sio* scaa oa surface Gross Thin-walled, shielded a 30 pCl/cm2 Beta gamma G-M a 1 mg/cm2 Nat a 500 pCL/cm2 Pressurized ion 50 - 50,000 pCi/cm2 chamber Air ionization 500 - 5,000 pCl/cm2 chamber Intrinsic germanium 30 - 3,000 pCi/cm?
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5.
O Name of surveyor, sampler, or analyst
- 6. Analysis date
- 7. Instrument specifications and calibration data
- 8. Confidence level, standard error, etc. attached to analytical results
- 9. Name of person verifying results The actual net measured values (including negative values) and their associated errors will be reported. For values lower than the lower limit of detection (LLD), the LLD will be provided.
Whenever possible, values lower than the LLD will be reported in the following manner:
Example See NURFG/CR-2082):
11.I 18.5 pCi/L or mBq/L or 7.4 18.5 pCi/g or mBq/g.
The following supplementalinfonnation will be included with the radiation measurements and analytical results report for inclusion in the final report:
- 1. Description of survey and sampling equipment
- 2. Survey and sampling procedures, including sampling times, rates, and volumes 4
- 3. Analytical procedures h
Calculation methods
- 5. Calculation of the lower limit of detection
- 6. Calibration procedures
- 7. Discussion of the program for ensuring the quality of results The data will be presented so that the radiological condition of the site is completely and accurately depicted and the radiological condition of the site can be ascertained without further analysis and manipulation of the data.
A report will be written and submitted to the NRC on the Final Radiation Survey as required by NRC Regulatory Guide 1.86. The report will include a description of the survey methods, mstruments, analyses, and an evaluation of the results.
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CHAPTER 5 0 5.
cro^Tso FUNDS cost ssTiu^Ts ^xo e'^x von ^ssuaixo ^v^r'^nt'rTv os 5.1 Cost Estimate Summary Including Assumotions The estimated cost for performing the decommissioning of the KUTR is approximately 5490,(XX) as shown in Tatle 5-1. In general. the work consists of removing the aluminum reactor tank, floor, reactor box, divider plate, chamber pockets and all activated & contaminated concrete from shield structure, and shipping the debris to a nuclear waste disposal facility. The estimate is broken down into the specific tasks, described in detail in Section 2.2. The basis of the estimate is as follows:
1.
Labor and Burden - Union labor rates (1990) for Topeka, Kansas were used.
2.
Equipment Usage - Equipment usage includes rental and operating cost of con-struction equipment. It also includes power tools, scaffolding, and consumables such as drill bits, concrete saw blade; etc.
- 3. Material - Consumable materials prices are based on available data and vendor quotes.
4 Subcontract -- Subcontract costs were estimated for:
l Medical Examinations !
Laboratory Isotopic Analyses
] .
Laboratory Bioassays Transportation of Radioactive Materials to U.S. Ecology's Handford, WA Burial
. Facility
- 5. Labor, Equipment, and Consumables Costs - Decommissioning Contractor's Overhead and Profit included the following markups:
157c On Craft Labor and Burden 157c On Purchased Equipment 157c On Rental Equipment i57c On Purchased Consumables O
5-1
Table 5-1 O
UNIVERSITY OF KANS AS RESEARCH REACTOR DECOMMISSIONING COST ESTIMATE ACTIVITY COST '
Contractor Pre-Deolovment Phase I:
1.0 Material Analysis KU 2.0 Decommissioning Plan Preparation KU L- 3.0 Achieve Decommissioning Order KU 4.0 Preparation of Documents - $36,000 l.
Contractor Post-Deolovment Phase 11:
1.0 Site Mobilization 1.1 Travel in $1,700 1.2 Mobilize Equipment $7,200 1.3 General Employee Training (GET) $6,200 2.0 t-Confirmatory Radiation Survey included in DC Staff Costs g.
3.0 Set Up Work Areas 3.1 Staff Office included in DC Staff Costs 3.2 Storage Area $400
- 3.3 Anti-C Change Room Facility $3,300 L 3.4 install Temporary Power Service $1,300 L 3.5 Construct CCE Over Reactor Tank $4,500 L 3.6 Modify _ Reactor Room Existing HVAC $7,800 4.0 Decontaminate Equipment Prior to Removal $400 L
5.0 Removal of Activated Material and Components -
5.1 Setup and Test Cutting Equipment $8,900 5.2 Setup cutting Station _
$6,700 5.3 Remove Thermal Column Door and Remaining Blocks $8,900 5,4 Construct CCE Door at Thermal Column Opening $1,700 -
5.5 Install HEPA at Thermal Column Door $2,600 5.6 Segment, Remove and Package Aluminum Tank, $20,000 Floor. Reactor Box, Divider Plant and Chamber Pockets
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5-2
O' Table 5-1 (Cont.)
' ACTIVITY COST 5.7 Remove, Segment and Package 5.7.1 Core Bore Beam Tubes $3,000 5.7.2 Pneumatic. Tube Assembly $600 5.7.3 Thermal Column Lining $13,000 6.0 Setup Lower Tank Region Transport Cart $2,400 for Waste Material Egress Through Thermal Column Opening 7.0 Remove Activated Concrete 7.1 Breakup, Remove and Package $37,500 Activated / Contaminated Concrete from
. Walls and Floor 7.2 Cleanup and Decontaminate Tank _ Region $400 8.0 Perform Confirmatory Survey of Drain to Holding Tank $300
.n 9.0 Perform final Radiation Survey included in DC V
Staff Costs 10.0 Cut, Package, Ship and dispose of Activated / $23,100
. Contaminated Materials and Components 11.0 Prepare Final Decommissioning Report IrM Jded in DC Staff Costs-12.0 Final Site Cleanup
$800 13.0 Site Demobilization -$4,000 Undistributed Cost - Phase I and 11 = $242.800
-Sub-Total Cost = $445,500
+ Contingency (10%) = $44,500 Total Cost Phase I and ll = $490.000
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6.
O Uedistributed Costs - includes the following:
Executive Engineer's Labor, Per Diem, Rental Car and Airfare Decommissioning Contractor's Staff Plus Per Diem and Rental Car 15% On Purchased Health Physics Supplies and Equipment 15% On Small Tools Purchased
- 7. Contingency - A 10% contingency is recommended and is included in this esti-mate.
5.2 Assumotions Assumptions used in this estimate are listed below:
1.
The University of Kansas will contract an Executive Engineer to represent KU and assist the Reactor Director with the functions described in Section 2.3.
2.
The DC will have access to the use of the fuel handling hoist.
- 3. All spent fuel is already disposed of by others.
- 4. Free power and utilities will be made available to the DC.
5, The nuclear waste disposal fee used in this estimate is $72.11/ft3 in 1990 dollars for U.S. Ecology's Hanford, WA Burial Facility. h 6.
Sufficient trailer, storage and parking space will be previded by KU near Bun Hall.
7.
The decommissioning will be carried out continuously f.ata : tart to completion.
- 8. The Room.
DC will have unrestricted and anencumbered access to Burt Hall & the Reactor 5.3 Availability of Funds The State of Kansas is committed to providing the funding for this dismantlement program.
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CHAPTER 6 6.
TECHNICAL AND ENVIRONNIENTAL SPECIFICATIONS IN PLACE DURING DECON1N11SSIONING The University of Kansas (KU) has previously submitted a letter of application for amendment No. l$ dated September 23,1986, addressed to the NRC pursuant to 10 CFR 50.90, for changing the status of KU's operadng license No. R-78, Docket No. 50-148 to a " possession only" status. The letter included a copy of The University of Kansas proposed changes to their Technical Specifications to support the KU amendment change to a " possession only" status. The NRC sent a letter in response dated January 28,1987 converting the KU operating license is a
" possession only" status in accordance with the KUTR Technical Specifications. Therefore, th' same Technical Specifications will be ir. place and adhered to during the decommissioning activities.
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1 Cil APTER 7 O 1 OUAUTY ASSURANCE PROVISIONS IN PLACE DURING DECONIN11SSIONING The Decommissioning Contractor (DC) will be chartered with the responsibility of performing the preparatory engineering, decommissioning w ork, w aste packaging and disposal and final radiation sursey. The DC will be required to perform his own radiological control program and quality assurance program. However, the University of Kansas will coaduct its own overcheck of the DC's programs to ensure that the work is performed in a safe and controlled manner.
7.1 Organization The DC is rrsponsible for implementation of his own QA and radiological program. The DC will be responsible for his personnel to adhere with the written procedures or DC will stop the work activities. The KU Reactor Director will conduct his own overcheck of the DC's QA and radiological programs to ensure that the work is performed in a safe and controlled manner. The Reactor Director may delegate these overchecks of the DC to the Executive Engineer or a designate to verify procedural compliance.
The procedures for the KUTR decommissioning plan activities will be written by the DC, and will Se reviewed Ly the KU Reactor Committee and the Executive Engineer.
Responsibility for the Reactor Facility is within the chain of command shown in the organizational chart in Figure 2-2 in Section 2.3. -
7.2 Duality Assurance Program f 7.2.1 Scope O The Decommis,ionins Coetractor wiii de resnoe idie for erenerins aad imeiementins ihe following documents for the Quality Assurance Program applicable to the DC's workscope for controlling the decontamination and decommissioning of the KUTR:
- 1. Quality Assurance Manual
- 2. Radiological Control Procedures Radiation Work Permit Procedure Surface Contamination Control Survey Procedurr Airbome Radioactivity Control Procedure Calibration & Maintenance of Survey Instruments Procedure Radioactive Check Source Accountability Procedure
- 3. Radioactive Waste Procedures Radioactive Waste Packaging Procedure Handling, Storage and Shipping of Radioactive Materials Procedure Solidification of Radioactive Liquids Procedure
- 4. Health, Safety and Emergency Procedures Genera Industrial Safety Procedure Health and Safety Procedure 7-1
Housekeeping Procedure h
Emergency Action Procedure Waste Transportation Emergency Procedure
- 5. Work Procedures Aluminum Tank Removal Procedure Activated and Contaminated Concrete Removal Procedure Removal of Beam Tubes and Pneumatic Tube Procedure Suriace Decontamination Procedure Cc.nstruction of Contamination Contri Envelope (CCE) Procedure Final Site Radiation Survey Procedure Firul Site Clean op Procedure 7.2.2 [ht, .aissioning Contnetors Ouality Assurance Manual Tae DC shallinclude the following information in his Quality Assurance Manual:
1 Responsibility and Scope
- 2. Organization h
- 3. Documentation 4, Design Control
- 5. Procurement Control
- 6. Document Control
- 7. Material Control
- 8. Process Control
- 9. Inspection
- 10. Test Control
- 11. Control of Measuring and Testing Equipment
- 12. Corrective Action
- 13. Quality Assurance Records
- 14. Audits 7.2.3 Acolicability This QA program is applicable during the performance of any decontamination and decommissioning activities through the completion of the DC's work scope and the project.
7-2
O 7.2.4 Records and Reports Accurate and complete records and repons shall be maintained by KU of the perfonnance and completion of all activities which may result in exposure of workers or the public to radiation or other hazardous / toxic materials.
- 1. Records Records which will be maintained during DECON activities are listed below.
Health and Safety Related Activities:
Radiation work permits Work procedures Radiation survey reports Contamination survey reports Airborne survey reports Environmental survey reports Counting data on air samples, smears, and gamma spectrum analysis O .
instrumeni caiibrations Source inventory and storage Radioactive material inventory and storage
. Shipment records Waste disposal - surveys and records Package certifications / records Incidents and accidents Personnel Records Bioassay analyses Personnel exposure records Individual dosimeter readings as related to daily tasks and work procedures Respiratory protection qualifications (medical clearance and fit test)
Audiogram results Training records O .
Visitor logs and exposure information 7-3
- 2. Repons O
Repons pertaining to DECON activities shall be written and submit ted to the proner authonties pursuant to Regulatory Guide 1.86.
7.2.5 AyLju i
' Upon issuance of decommissioning activity procedures, the Decommissioning Contractor QA personnel will perfonn periodic audits prior to, during, and after decommissioning activities to ensure compliance with the requirements with this plan. The Executive Engineer or Reactor Director designee will perfonn an independent audit as an overcheck of the DC. The respective Audit programs willinclude but not be limited to:
The Decommissionine Contractor's Audit Procram -
- 1. Review of DC's operating personnel health and safety training program
- 2. Review of DC's radiological control program including ventilation, instrument usage and calibration, personnel monitoring and area monitonng procedures
- 3. Review of DC's work procedures with regard to public health and safety and the principles of ALARA 4 Audit of contractor records including training, radiation surveys, instrument cali-bration and shipping data The University of Kansas Audit Procram - O
- 1. Review of DC's operating personnel health and safety training program 2,
Review of DC's radiological control program including ventilation, instrument usage and calibration, personnel momtoring and area monitoring procedures 3,
Review of DC's work procedures with regard to public health and safety and the principles of ALARA
- 4. Audit of contractor records including training, radiation surveys, instrument cali-bration and shipping data
- 5. Independent check of area radiation levels and surface contamination levels
- 6. Approval chain of documentation to be submitted to NRC l
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Cil APTER 8 e
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8.
PIIYSICAL SIONING SECURITY PLAN PROVISIONS IN PLACE DURING DECOMMIS__.
in the referenced letter from the NRC, addressed to The University of Kansas, dated January 28,1987 in section 6 of this document.in the conclusion a statement is made by the NRC"The staff concludes that amendment of this license to a possession-only status is appropriate and that there is ao longer any requirement to maintain implementation of the Physical Security Plan" During decommissioning activities all accesses to the reactor room will be limited to those personnel required to perform the program. During off hours all entrances and exits to the reactor room will be locked, in addition, each entrance will be posted to keep inadvertent access of personnel from entering the decommissioning work c%.
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REFERENCES 1.
C.F lloloway, J.P. Witherspoon, H.W. Dickson, P.M. Lantz, and T. Wright, " Monitoring for Compliance With Decommissioning Termination Survey Criteria"(prepared for the Nuclear Regulatory Commission by Oak Ridge National Laboratory), NUREG/CR-2082 (ORNL/HASRD-95), July 1981, 2.
3 U.S. Nuclear Regulatory Commission. " Termination of Operating Licenses for Nuclear l Reactors," REGULATORY GUIDE 1.86, June 1974 3.
Code of Federal Regulations," Standards for Protection Against Radiation," 10 CFR Part 20, Revised as of January 1990.
4.
Code of Federal Regulations," Licensing Requirements for Land Disposal of Radioactive Waste," 10 CFR Part 61, Revised as of January 1990.
5.
' U.S. Nuclear Regulatory Commission," Safety Evaluation Report related to the renewal of the operating license for the research reactor at the University of Kansas, Docket No.
50'-148," NUREG-1051, (prepared by Office of Nuclear Reactor Regulation), May 1984.
6.
Letter from Gene A. Budig, Chancelor, University of Kansas, to C.O. Thomas, Chief, USNRC, September 23,1986, Application for Amendment No.15 to The University of Kansas Facility Operating License No. R-78, Docket No. 50-148 for conversion oflicense g to Possession-Only status.
U 7.
Letter from Herber: N. Berkow, Director, USNRC, to Dr. Harold Rosson, Reactor Director, University of. Kansas, November 6,1986, NRC review of University of Kansas Possession-Only Amendment Application.
8.
Letter from Dr. Harold F. Rosson, Reactor Director, University of Kansas, to Herbert N.
'. Berkow, Director, USNRC, November 24,1986, Responses to quesuons from the USNRC letter from Herbert N. Berkow, Director, USNRC, to Dr. Harold Rosson, Reactor Director, University of Kansas, November 6,1986.
9.
Letter from Frank J. Miraglia, Director, USNRC, to Dr. Harold Rosson, Reactor Director, University of Kansas, January 28, 1987, Issuance of Amendment No.15 to Facility Operating License No. R-78, The University of Kansas - Conversion of License to Possession-Only Status.
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