ML19248D351
| ML19248D351 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 08/07/1979 |
| From: | NEW YORK, STATE UNIV. OF, BUFFALO, NY |
| To: | |
| Shared Package | |
| ML19248D349 | List: |
| References | |
| NUDOCS 7908150647 | |
| Download: ML19248D351 (43) | |
Text
.'
A ANNUAL REPORT OF THE NUCLEAR SCIENCE AND TECIUOLOGY FACILITY APRIL 1,1978 THROUGH MARCH 31, 1979
. a,,. <,, (
%.5 f e.0 ** O s 7 9 0 815 0 d /'7
i INTRODUCTION The utilization of the Nuclear Science and Technology Facility (NSTF ) in the instructional programs of the University has continued at about the same level as the last fiscal year. Although the reactor operation was resumed in mid-July, 1978, additional repair to the cooling tower necessitated further reactor shutdown of two months. Altogether the total reactor down time during the 1978-79 fiscal year is almost six months.
Under these trying circumstances, the faculty and student research programs have continued well, in spite of the resignetion of Mr. Charles C. Thomas, the former Director and an active researcher in the area of radiation chemistry.
Interaction of the NSTF with other institutions has increased somewhat. With the incoming Acting Director, who has a joint appointment with the academic unit, the level of the facility utilization by the instructional programs is expected to increase rapidly. Currently, a vigorous discussion is under way with various academic units regarding the drastically-increased level of cooperation in the area of research. Several resecrch proposals have been prepared and submitted to various agencies for possible future support.
Contrary to their originally expressed intention of paying the entire fabrication cost for the new fuel, the Department of Energy (DOE) has only paid a small fraction of it.
Separately from the fuel cos t, the expenditure for spent fuel element shipping is to be paid by DOE as per the original contract. The NSTT is currently operating smoothly with the new fuel elements in the core, ar che necessary major repair work seems now behind us.
Barring unexpected future dif ficulties, the e:111ty should be able to operate the reactor for the next fifteen to twenty years without further refueling.
EdWiiO
4 INSTRUCTIONAL PROGRAMS The NSTF has an important role in both the undergraduate and graduate programs of (1) the Department of Engineering Science, Aerospace and Nuclear Engineering, (2) the Department of Biological Sciences, (3) the special majors program in Radiation Protection, and (4) miscellaneous graduate medical programs such as at Roswell Park Memorial Institute.
NSTF personnel are extensively involved in teaching courr
_ these programs.
In addition, the facility and facility personnel are heavily involved in thesis and independent study projects.
NSTF course instruction activities range from full responsibility for courses, to limited contributions through lectures and use of the facility with the assistance of facility personnel. These activities for the 1978 79.tcademic year are presented in Table 1.
The number of courses utilizing the fucility is somewhat less than in previous years as a result of the prolonged reactor shutdown (six months) during the fiscal year.
The level of activities was also af fected by the depe.rture of Mr. Charles Thomas as the Director in July, 1978, and the transient faculty situation within the Department of Engineering Science, Aerospace and Nuclear Engineering. However, it is expected that course offerings and enrollments will return to normal during the coming academic year. The estimated number of students who were involved in various aspects of academic activities at NSTF for the fiscal year is one hundred twenty (120).
bbWU1.
Independent study projects involved widely diverse topics.
During the fiscal year, projects have included ga=ma-ray spectroscopy of pool water, radium detemination in environmental samples, and thermal neutron dosimetry with TLD system.
During the current year, the Faculty of Engiaeering and Applied Sciences had accreditation visitations by Engineering Council for Professional Development (ECPD) teams who examined various engineering programs, including the Nuclear Engineeri I program on this campus. Although the results of the accreditation visitation and the ECPD recommendation on Nuclear Engineering curriculum have not been received, the preliminary comment made by the visitation team was that increased collaboration between the NSTF and the Nuclear Engineering was possible, and indeed highly desirable.
Since the Acting Director assumed the post in late July of 1978, he Las contacted various academic units to discuss closer collaboration between the NSTF and respective academic programs. Departments such as Physics, Chemistry, Nuclear Medicine, Biology, and Geology have been contacted.
Also, continuing discussions are being carried out with the Faculty of Natural Sciences and Mathematics and the Faculty of Engineering and Applied Sciences in an effort to er'ance their utilization of, and participation in, NSTF activities and services.
In the forthcoming year, it is expected that such ef forts will continue and will be extended to other academic units, such as Roswell Park Memorial Institute, the Medical School, etc.
-3 bO2262
TABLE 1 NSTF COURSE INSTRUCTION ACTIVITIES Course No.
No. of NSTF Staf f Fraction Taught Facili y and Title Students Instructor Member By NSTF Staff Usace NuE 464, Environ-9 W. Y. Chon L. Het. v 0.8 1 recitation / week mental Reactor 1-3 hours / week full semester Techniques Biology 499 4
A. K. Bruce F. Thomas 0.5 Two 3-hour lectures Independent Study L. Henry 0.2 per week. Later two 3-hour labs per week.
Biology 600 1
A. K. Bruce F. Thomas 0.6 1 recitation per Problems week.
One-three hours per week full semester.
NuE 507, Nuclear 6
M. N. Haas 1.0 Three one-hour Reactor Safety lectures / week.
Full senester.
NuE 421, Nuclear 12 W. Y. Chon 1.0 Tour Engineering Systems NuE 422, Applied 9
W. Y. Chon 1.0 Facility Heat Nuclear Design Exchanger System Studies NuE 559, Thesis 6
%, Y. Chon 1.0 ens 501, Inde-2 W. Y. Chon 1.0 pendent Studies Biophysics 1
M. N. Haas 1.0 Van de Graaff Medical School Usage Bio 461/661, Bas ic 70 A. K. Bruce F. Thomas 0.1 2 Labs plus Radiation Science L. Henry speciri features per week t:022' 63
ACADEMIC RESEARCH SUPPORT In spite of the proLmaged reactor down-time, the facility utilization in academic research projects has not declined greatly. These projects are shown in Table 2.
The relative increase in thermohydraulic-type research topics reflects the new inclusion by the facility of an Electric Power Research Institute /SUNY-Buf falo research project on " Alternate ECCS Studies". The project is one of the largest nuclear safety studies on a United States university ca= pus, the biannual research budget for 1979-80 calendar years being $245,854. Two post-doctoral research fellows and several graduate students have been supported through this project during the fiscal year.
In addition to the facility support of SUNY/Buf falo academic research projects, the facility cooperates with other universities and colleger In the past, facility use in these projects was not reimbursed fully; fu:1 costs of the projects were not recovered. This particular practice has been rectified during the fiscal year, however. While the current NSTF policy for the inhouse (SUNY/ Buffalo) research support remains flexible, it has been decided to recover the full costs of service as well as the fuel-depletion for academic research support of outside (other than SUNY/Buf falo) universities. All the services, except for some transient cases, were provided an a real-cost basis.
Institutions using the facility include the University of Rochester, University of Cincinnati, and University of Texas.
( UO).'.U yl
During the fiscal year, four re ma ch proposals were prepared in preliminary forms and submitted to various agencies, such as DOE, NRC, and SERI. The fields of research suggested in these proposals are hydrothermal stability of high-level nuclear waste, advanced canister design for vitrified and ceramic waste forms, and new solar collector performance studies. Negotiations have continued between the agencies while final proposals were readied, based on the interim feedback received f ran them.
Professor Harry Suprinick of Engineering, and Professor Rossman Giese, Jr., of Geological Sciences, will be active participants when the proposed projects are eventually supported. Dean &Jwayne Anderson of Natural Sciences and Mathematics will be a special consultant to one of these projects.
692265
_s_
TABLE 2,
ACADEMIC RESEARCH PROJECTS Department Student Faculty Member Project Description Degree and Status Engineering L. Henry W. Y. Chon neat Transfer in PU1. STAR M.S. in Progress Science Fuel Elements Engineering J. Bednarek W. Y. Chon Four Region Model for M.S. in Progress Science Reflood Heat Transfer 2ngineering J. Toloue W. Y. Chon Steam-Water Condensation M.S. in Progress Science Efficiency Engineering A. Adams W. Y. Chon Reflood Heat Transfer M.S. in Progress Science Regimes Engie.: aring D. Ormsby W. Y. Chon Acoustic Augmentation in M.S. in Progress Science Isotope Separation Engineering J. Bondre W. Y. Chon Oscillatory Reflood Heat Ph.D. in Progress Science Transfer Engineering L. Green W. Y. Chon Bi-Coolant Solar Collector M.S. in Progress Science Performance Medicine J. Robin J. Ambrus In-Vivo Analysis of Ga in Ph.D. in Progress (RPMI)
M. Hender-Mice son Geological D. Borden D. Hodge Uranium, Thorium, Sciences Potassium Analysis of Rocks Biology R. Byrnes A.K. P.*uce Thermal Neutron Dosimetry M.S. in Progress with TLD system Biology A. Abramowitz A.K. Bruce Radium Determination in B.S.
Mei-Yao Pei Environmental Sa:oples M.S.
in ?rogress Biology E. Ekeocha A. K. Bruce Ga==a Ray Spectroscopy B.S.
S. Al tman of Pool Water ISOA,'Zb6
TABLE 3 FACILITY USE BY OTHER INSTITUTIONS Institution Facility Use University of Cincinnati Isotope Facility Three (3) insertions 1128 hours0.0131 days <br />0.313 hours <br />0.00187 weeks <br />4.29204e-4 months <br /> SU'iY at Binghamton Pnetnatic Conveyor Seven (7) insertions 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> University of Texas Van de Graaff Three (3) hours b'Ob$sj?
FACILITY OPERATIONS The facility shutdown that began in the previous fiscal year continued into the ciarent period. Early in 1978, all the spent fuel was shipped to Idaho and the new fuel purchased from Westinghouse Canada was received. Af ter the remaining active fuel was stored ir the hot cell, repair of the piping proceeded.
Installation of the new pipe proceeded rather rapidly; however, several events caused delays that were not entirely anticipated. One delay.
caused by the need to fabricate an entirely new plenum. This was brought about by the higher than anticipated activity of the old plenum. Another delay resulted from dif ficulty in welding a cover plate over one of the abandoned return ports to the pool.
It was found that the shelf in the pool liner had suffered corrosion, and new aluminum plates had to be fabricated and installed. After filling the pool, leak tests revealed a crack in a weld, and further delay resulted.
Following successful leak tests, the reactor was re-assembled and achieved criticality on June 26th. A period of calibration and testing followed. Normal three-shif t operation began on July 7th,1978.
On December 14, a gross failure of the cooling tower gear box occurred. A replacement gear box was not stocked by the vendor, and it took seven weeks to obtain a replacement. The tower was returned to operation on February 14th. During this period some low power operation and short high power operation was possible.
I5NA$4M The monthly operating history follows:
Month Doerating Hours Megawatt Hours April 1978 0
0 May 0
0 June 28.0 4.4 July 375.7 771.4 August 488.7 903.2 September 497.7 788.7 October 445.8 870.0 November 244.6 473.5 December 172.6 297.9 January 1979 32.7 19.2 February 245.3 469.7 March 490.7 943.3 TOTALS 3021.8 5540.3 Optimum utilization of the facility with the present three-shift, five-day-a-week schedule would pro uce approximately 10,000 megawatt-hours.
i The actual yearly power generation si..:e 1970 is listed below.
Fiscal Year Mezawatt Hours 78-79 5,540 77-78 5,809 76-77 8,303 75-16 6,845 74-75 5,357 73-74 5,774 72-73 5,526 71-72
,,879 70-71 10,229 bb [kl50 ACADEMIC RESEARCH Academic departments using the facility arn as follows:
Chemistry Dr. Allendorf I hour Van de Graaff irradiation Physics Dr. Brinks Student lab and counting room Biology Dr. A. K. Bruce Conference room - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Pncusatic conveyor - 36 insertions - 4.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Use of 10 Ci PuBe source Medical Chemistry Dr. Bardos Pneumatic conveyor - 1 insertion - 30 minutes Anthronolotv B. Herbert Pneu=atic conveyor - 32 insertions - 73 minutes Geoloey Dr. Hodge Ppqunatic conveyor - 43 insertions - 43 minutes Roswell Park Memorial Institute Dr. Ambrus Pneu=atic conveyor - 1 insertion - 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Thermal column - 26 insertions - 44 b ors Isotope facility - 5 insertions - ?) hours veterans Administration Hospital Dr. Jung Van de Graaff irradiations - 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> Many of the above activities also involved extensive use of laboratory space and equipment. i ; q ?.r, (
3,>,
u v
e EDUCATIONAL SERVICES This category represents services in support of course activities.
Extensive use of classroom and laboratory space was also made in this connection.
3 insertions into the thermal column 3 insertions into the pneumatic conveyor 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> use of the suberitical reactor 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> reactor tie-up for student instruction.
FEDL?AL AGENCIES - GRANTS Naval Research Laboratory Reactor tie-up time 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> Reflector use 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Core space 8397 hours0.0972 days <br />2.333 hours <br />0.0139 weeks <br />0.0032 months <br /> (Basically NRC-sponsored FWR material testing) UD '. 'Ff;'1,
GOVERNMENT AGENCY SERVICES The increase experienced in this category ove; the past several years continued during the period. Additional funding of the Naval Research Laboratory (NRL) project was obtained by Dr. Martin N. Haas to further the irradiation research on reactor vessel material. The funding for the current fiscal year was $120,000, bringing the total funding so far to $310,000.
In addition, a new experiment was designed as part of projected research which uses the reactor core reflector space. The new research program will study the rate effects on neutron irradiation damage. The exper' mental facility was built and tested at NSTF. Further experbnental work is anticipated in support of this effort, which may result in a long-term test program.
ACCOUNTABILITY Dr. M. N. Haas was assigned the responsibility cf accountability officer. This position entailed the accountability of all special nuclear material in possession by the university under the federal license. A revised accountability program was subsequently instituted to incorporate the latest federal regulations on control management. The existing burn-up code was expanded into a suitable accountability document. W!T/2
PUBLIC AFFAIRS AND PROFESSIONAL ACTIVITIES The facility staff was active in a number of professional and community service organizations.
Dr. M. N. Haas participated as a member of the Advisory Board to the New York State Legislative Commission on Energy Systems. This involved participation in a number of study reviews on energy matters for the State of New York.
Dr. W. Y. Chon, the Acting Director, has been involved in many public debates on nuclear safety and power, both on this campus and elsewhere. Two papers based on EPRI/SUNY-Buffalo Alternate ECCS Program were presented at the Anra al American Nuclear Society meeting, and ASME Winter Annue l Meetirg, as follows:
(a)
W. Y. Chon (with N. S. Liao, C. Addabbo and R. Duf fey),
" Steam Binding Reduction Through Condensation With Top Injection or Spraying", ASME Winter Annual Meeting, December 10-15, 1978, San Francisco.
Published in ASME Symposium Series, " Topics in Two-Phase Heat Transfer and Flow", pp. 115-121, 1978.
(b)
W. Y. Chon (with C. Addabbo and N. S. Liao), "Ef fects of Bottom Injection Location on Reflood Characteristics",
American Nuclear Society,1978 Annual Meeting, June 18-22, 1978, San Diego. Ah5 Transactic.ts, Vol. 28, pp. 392-393, 1978.
692273
- 15 _
As in the past, the facility has provided tours for visitors and a number of community groupo. Although this activity was ibnited due to the prolonged shutdown, the facility tours have been quite active during the report period. The breakdown is given below.
AFFILIATION NUMBER DATE Visitors from Mainland China 5
10/4/78 Students fran Erie Coccunity College 11 10/16/78 Students from Erie Community College 12 10/23/78 Students from Brockport 11 10/27/78 Students, Alternate Energy Systers Class 9
11/16/78 Stadents from Brockport 18 11/16/78 Students, SUNY/ Buffalo 5
11/20/78 Physics Club of Kanmore West Senior High 18 11/30/78 Electrical Workers Apprentice Class, Syracuse 44 12/1/78 Biology Students, State University College 14 12/5/78 Boy Scouts and Parents 8
12/7/78 Niagara University Students 11 12/13/78 Students, City Honors School 21 1/5/79 SUNY/ Buffalo Onployee Tour 9
2/6/79 Alternate Energy Systems (Rachel Carson College) 16 2/15/79 Engineering Week 2
2/20/79 Engineering Week 8
2/21/79 Engineering Week 15 2/23/79 GS^274 AFFILIATION NUMBER DATE Visitors from Korea 2
2/28/79 College of Math Sciences 4
2/28/79 Williamsville United Methodist Church 18 3/4/79 Visitors from Korea 4
3/9/79 Kenmore Presbyterian Church " Outrigger Club" 17 3/17/79 YMCA Indian Guide Program 11 3/20/79 East High School 11 3/21/79 304 4
i : n '.:'.o y >, r-
~ut r ( wy REGULATORY AGENCY INSPECTIONS Routine reviews of the NSTF are made by various agencies to ensure compliance with state and federal regulations and license conditions. NSTF activities are inspected by the New York State Health Department, the New York State Deparbnent of Environmental Conservation, and various sub-groups of the U. S. Nuclear Regulatory Commission.
A routine unannounced NRC inspection was corducted on July 19-20, 1978.
All aspects of facility operation were reviewed. Two infractions were found. One was a failure to calibrate the area and ef tluent radiation monitors on the prescribed schedule, and the other was a lack of a written procedure for the use of our isotope production facility.
Both infractions were immediately corrected.
Another unannounced NRC inspection occurred on July 26, 1978. This inspection was directed toward facility security. Again two infractions were reported. The first infraction was due to a failure to test the facility security system elect.ronics during the period that the reactor was down for repair. The second infraction involved the punch-clock records that document the fact that security of ficers are touring the facility as required.
The records were not complete or properly labeled to ensure proper inter-pretation. The first problem was due to the unusual status of the facility, and administrative controls should prevent it from happening again. Changes in campus security procedures should prevent reoccurrence of the latter infraction.
, g y. ru..,
D.s 4. i, ( (J FINANCIAL The financial data for the NSTF is presented in Table 4 As might be expected from the prolonged reactor chutdcwn, the facility finished the year with a deficit of approxt=ately $66,498.95 on an accounts-receivable basis.
During this report period, the lost reactor operation tLne was about six conths, about the same as in the previous fiscal year. With the repairs to both the primary piping system and the cooling tower fan drive shaft now complete, it is expected that the forthcoming fiscal year will Le a fruitful one financially. The expected increase in research volume, as well as clo-ely-regulated service cost structure, should help ensure a successful financial operation in the future.
t bfM"877 TABLE 4 FINANCIAL REPORT NUCLEAR SCIENCE AND TECHNOLOGY FACILITY STATE ACCOUNT #55155 (From 3/31/79 Budget Condition Report)
Item Budgee Expenditure and/or Free Balance Encumbrance 1.
Salaries and Wages a.
Teaching (0.56 FTE)
$ 18,216.00
$ 26,964.79 (8,748.79) b.
Non-Teaching (5.39 FTE) 81,373.00 78,974.47 2,398.53 c.
Ove rt ime, Holiday, and Inconvenience 3,739.00 178.67 3,560.33 d.
Salary Transfers (2,013.00)
(2,012.59)
(.41) e.
Temporary Services 1,320.00 98.16 1,221.84 f.
Pending 2,013.00 2,012.59
.41 9
Total Salaries and Wages 104,648.00 106,216.09 (1,568.09) 2.
OTPS 22,516.00 23,543.45 (1,027.45) 3.
Expendable Account Total 127,164.00 129,759.54 (2,595.54) 4 Recharges 1,810.00
.00 1,810.00 Account Totel
$128,974.00
$129,759.54 (785.54)
INCOME REIMBURSABI.E ACCOUNT #91118 (From 3/31/79 Budget Condition Report)
Item Appropriation Expenditure and/ar Free Balance Encumbrance 1.
Salaries aad Wages a.
Non-Tcaching '14.05 FTE)
$150,184.00
$149,824.64 359.36 b.
Overtime, Holiday, and Inccavenience
.,700.00 1,534.78 165.22 c.
Temporary Services 31,446.00 22,049.96 9,396.04 Total Salaries and Wages 183,330.00 173,409.38 9,920.62 2.
OTPS 62,866.00 58,412.87 4,453.13 Total Account
$246,196.00
$231,822.25 S
14,373.75 GS2278 TABLE 4 (continued)
INCOME Deposits as of 3/31/79.
.$ 145,612.94 Accounts Receivable 3/31/79..
19,710.36 S
165,323.30 NET INCOME (Based on Expenditures and Encumbrances)
($
66,498.95)
TOTAL EXPENSE
SUMMARY
STATE AND REIMBURSABLE ACCOUNTS Item Appropriation Expenditure and/or Free Balance Encumbrance 1.
Salaries and Wages
$287,378.00
$279,625.47 8,J52.53 2.
OTPS (Includes Retnbursable State Benefits) 85,382.00 81,956.32 3,425.68 3.
Recharges 1,310.00
.00 1,810.00 TOTAL
$375,170.00
$361,581.79 13,588.21
$3bN203 ANNUAL REPORT OF THE RADIATI4 N PROTECTION DEPARTMENT STATE UNIVERSITY OF NEW YORK AT BUFFAID Radiation Data January 1, 1978 - December 31, 1978 Financial Data: April 1, 1978 - March 31, 1979 Report Date: June 29, 1979 Alan K. Bruce, Radiation Safety Of ficer Mark A.
Pierro, Radiation Protection Manager 14214..U.,,,,,SO Howe Research Laboratory, Room 15, Rotary Road, Buffalo, New York O
,-.4 Tel (716) 831-5451
RADIATION PROTECTION DEPARTMENT ACTIVITIES The Radiation Protection Department (RFD) is responsible for all aspects of radiation safety on the SUNY at Buf falo campuses.
Incividuals provided radiation protection services are those faculty staff members engaged in the use of radiation producing equipment and/or radioactive materials in the course of their research or teaching.
Padiation producing equipment includes dental X-Ray units, elec tron microscopes and X-Ray dif fraction units.
The RPD also supervises radiation safety at the Nuclear Science and Technology Facility (NSTF) which houses a rescarch reactor, an electron accelerator, and a radioisotope production facility.
Possession and use of radioactive materials at SUNY at Buffalo are authorized under separate licenses by the New York State Department of Health and the United States Nuclear Regulatory Commission.
The RPD ptogram is based on insuring compliance with regulations set forth by these licenses.
DEPARTMENT WORKLOAD AND PERSONNEL The RPD in 1978 consisted of an averaged total of 5.99 full time staf f members.
During the year, two Radiation Safety Monitors and one Senior Radiation Safety Monitor were hired.
Because these people were not erployed tor the full year, the Department was understaffed and had dif ficulty meetir.g 1978 workload demands.
Table I shows the relative time spent on various tasks asscciated with the SUNY at Buf falo Radiation Protection Program.
_ 1-NUM
TABLE I RADIATION PROTECTION DEPARTMENT WORKIDAD Position Major Duties Workload (FTE)
Manager 1.
Adminis tra tion
- 0. 6 2.
Consultation 0.1 Mark A.
Pietro 3.
License Revision and Renewal 0.1 4.
User Approval 0.1 5.
Training 0.1 1
Radiation Safety Records 1.
Records Maintenance
- 0. 4 Clerk 2.
Written Correspondence and Reports
- 0. 2 M.
Karen Thomas 3.
Isotope Approval
- 0. 2 4.
Telephone Correspondence
- 0. 2 1
Senior Radiation 1.
Laboratory Radiation Survey
- 0. 4 Safety Monitor 2.
Sample Analysis
- 0. 2 3.
Radioisotope Receipt
- 0. 2 Ferenc A.
Tibold 4.
Waste Program 0.1 5.
X-Ray Equipment Survey 0.1 1
Senior Radiation 1.
NSTF Radiation Proteccion
- 0. 7 Sa fe ty Monitor 2.
Sample Analysis 0.05 3.
Training 0.05 Louis G.
Henry, J r.
4.
Waste Program 0.1 (Hired 3/2/78) 5.
Computer Programing 0.1 1
Radiation Safety Monitor 1.
Laboratory Rad'7 tion Survey 0.6 2.
Sample Analys.is
- 0. 2 Neil M.
Barss 3.
Radioisotope Receipt 0.1 (Hired 2/16/78) 4.
Waste Program 0.05 5.
Film Badge Service 0.05 1
Radiation Safetv Moni')r 1.
Laboratory Radiation Survey 0.6 2.
Radioisotope Receipt
- 0. 2 Charles A.
Gentile 3.
Sample Analysis 0.1 (Hired 11/6/78) 4.
Waste Program 0.1 1., q N N h da
, <s
TABLE I (continued)
Position Maior Duties Workload (FTE)
Laborer 1.
Processing Radioactive Waste
- 0. 9 2.
Associated Record Keeping 0.1 Ga ry F. Majewski 1
Radiation Safety Officer Alan K.
Bruce 1.
Consulting, Special reports, new methods, adminis tra tion 0.45 Other services not involving Deoartment FTE's NSTF Supplied Services:
Purchasing 0.25 Electronic Repair /Mcintenance 0.25 Telephone - Receptionist 0.15 0.65
' 00 N's 3
A.'
CAMPUS LABORATORY SURVEYS In 1978, there were 120 authorized campus radioisotope laboratories with 93 Senior Investigators (Principal Investigators) and approximately 320 Associate Investigators (graduate students, faculty, staff, etc.).
The RPD approved 16 new Senior Investigators, set up 16 new campus radioisetope labs, a1d de-commissioned 7 labs in 1978.
Each radioisotope laboratory has a classification based on quantity and type of radioactive material used.
The frequency of radiation protection surveys required depend on this classification.
Table II is a breakdown of the camous laboratory survey requirements.
The RPD performed 445 campus laboratory surveys during the year.
The survey procedure involves: wipe testing areas of radio-isotope use for removable surface contamination; direct radiation monitoring; updating associated laboratory records such as radioactive materials inventory, changes in personnel, changes in experimental protocol, etc.; insuring the proper disposal of radioactive waste materials; and conductirg laboratory personnel interviews on radiation safety.
00NA01
~
TABLE II CAMPUS IABORATORY SURVEYS No. of Required Labora tory Labs Required Survey Surveys Classification (1978)
Frecuency (per year)
A 52 2/ year 72 8
31 4/ year 92 C
19 1/ month 108 D
18 2/ month 288 TOTAL 120 560 Determined by multiplying the survey frequency by the number of laboratories.
This value has been corrected for those labs that were classified as inactive which do not require surveys and for new labs starting up during the year, therefore, not requiring the full number of surveys in one year.
B.
BASIC RADIATION SAFETY TRAINING COURSE New York State Department of Health requires that all users of radioactive,aterials demonstrate knowledge of radiation safety.
In order to meet the requirement, a short training course has been designed. The course consists of twenty hours of lecture and class demonstration, with a training manual and handout material provided by the RPD.
Due to the manpower shortages, the 3asic Radiation Safety Training course was not presented in 1978.
C.
RADIGISOTOFE RECEIPT A total of 670 radioisotope packages were received and processed by the RPD in 1978. All rcdioisotope orders must be approved by the R?D.
The quantity and type of radioactive material must not exceed the limits authorized for the user.
All packages are delivered first to the RPD where they are checked for removable L'.. #. %Eb contamination and/or excessive radiatica levels.
Inveniory control tags are affixed to the vial (s) and the necessary paperwork is completed.
Arrangements with either the User or Campus Delivery are then made to transfer the radio-active material.
D.
RADIOACTIVE WASTE DISPOSAL The RPD processes for disposal all liqu'.d at.d solid radioactive waste generated by the SUNY at Buffalo campus laboratories.
Waste container; are supplied by the RPD to all Users.
When filled, the containers att delivered to the RPD radioactive waste processing area in the Howe Research Laboratory.
The waste processing equipment includes an enclosed compactor for dry waste and a fume hood for solidifying liquid waste.
The area located directly above the processing area stores up to 300-55 gallon steel drums awaiting shipment to a commercial burial site.
The RPD also provides this service to authorized individuals at the Affiliated Hospitals (Roswell Park Meuorial Institute, Buf falo General, Children's, Millard Fillmore, Veteran's Administration Medical Center, Meyer Clinical Center, and Erie County Labs) oi. a cost recovery basis.
Table III shows a breakdown of the radioactive waste shipments in the fiscal year 1978.
E.
X-Rav ECUIPMENT SAFETY PROGRAM SUNY at Buf falo Radiation equipment (X-Ray diffiraction devices, Fluroscopes, electron microscopes, Therapy, radiographic and dental X-Ray machines, and an electron accelerator) must be inspected for ccmpliance with radiation safety guidelines set no by the New York State Department of Health.
Such inspections are carried out only by Certified Radiation Equipment Safety Officers ':RES0's).
The RPD has 3 staf f members who hold CRESO certification.
Because the University installations are inspected on a bi-annual basis, no Radiation Protection surveys were required in 1978.
(j((,j' 3&f(,
j TABLE III RADIOACTIVE WASTE SilIPMENTS, FISCAL YEAR 1978-1979 3
TOTAL TOTA L MATERIAIS TRANSPORTATION TYPE OF WASTE VOIllME ACTIVITY COFT AND EURIAL TOTA L SilIlttENT NO.
DATE ISV **
ANIMAL SOLID (CuFt)
(Curies)
ONLY COST ONLY COST
- 78-1 4/25/78 105 11 34 1125 0.076
$ 4,105.00
$ 3,878.00
$ 7,983.00 78-2 5/10/78 90 10 50 1125 0.086 4,640.00 3,878.00 8,518.00 78-3 9/6/78 81 11 53 1125 0.066 4,709.00 5,596.00 10,305.00 78-4 1/18/79 100 14 36 1125 0.342 4,372.00 5,641.00 10,013.00 78-5 2/14/79 97 21 32 1125 2.211 4,297.00 5,858.00 10,155.00 TOTAIS 473 67 205 5625 2.780
$ 22,12 3. 00
$24,851.00
$46,974.00
- This shipment represents waste collected and processed during Fiscal 1977-1978.
Due to inadequate funds in Fiscal Year 1977, this shipment was delayed until 4/25/78.
Liquid Scintillation Viale C
CO 7:
M CC
~n F.
EDUCATIONAL ROLE A number of students enrolled in Bio /463/663 - Padiation Protection, participated in surveys of canpus and NSTF laboratories, along with RFD personnel.
In addition, a number of students in Bio /499 - Independent Study, performed projects under the direction of RPD staff members.
These activities provide experience of value to those anticipating a career in these areas.
Some cf the projects have beet. substantial value to our basic knowledge of local problems.
They are of ten projects RPD staff would work on if sufficient t bne were available.
Purther information is included in the NSTF Annual Report.
G.
PERSONNEL RADIATION EXPOSLTES Personnel monitoring equipment is issued'to the following individuals who are likely to receive exposures to ionizing radiation:
(1) Individuals involved in the production or short lived isotopes at the dSTF (account #19339),
Individuals employed at the NSTF (account 19300), (3) Campus security personnel who patrol the NSTF (account 19317), (4) Individuals involved in special projects related to radiation research (account 19334) (5) Individuals working with radioactive material on the SUNY at Buffalo campuses, and (6)
Individuals working with radiatica producing equipment on the SUNY at Buf falo campuses (accounts 19301 - 19357).
An investigation is conducted into any exposure in excess of the Radiation Protection Guide (RPG).
In addition, when accumulated exposure indicates a probability of exceeding 'he RPG's for the period in question, an investigation is conducted to determine the cause and to correct the situation.
Table IV shows a su= mary of Personnel Radiation Exposures.
4 63388
_ 3
h onE IV
SUMMARY
OF CAMPUSES RADIATION EXP0EURES TOTAL ACCOUNT WB TOTAL ACCOUNT WE AVG. # OF USERS EXPOSURE FOR 1978 AVG. # OF USERS EXPOSURE FOR 1978 A CCOU'iT Per Month
( Rera)
ACCOUNT Per Morth (Rem)
- 19339 5
4.437 19319 7.92 0.589 19300 50.75 15.C'l 19320 2
0.013 19317 67.90 0.458 19322 3.17 0.023 19334 29.90 1.483 19323 7
0 29413 2
0 19324
- 8. 5 0
29424 1
0 19325 3.33 0.011 19307
- 5. 9 0
19329 9.33 0.519 19308 6
0.192 19332 44.8 3.11 19311 1
0 19333 8.08 0.143 19321 5.01 0.052 19335 2.17 0
19326 2
0 19337 4.92 0.022 19327 1.92 0
19340 7.32 0.521 19328 8.75 0.026 19341 8.08 0.082 19:30 4
0 19342 2.36 0
19331 2.58 0.104 19343 1
0 19336
- 3. 5 0.012 19345 4
0 19338 7
0 19347 3.08 1.1.17 19346 10.58 0
19349 7.17 0
193'4 1
0 19350
- 2. 7 0.027 19351 1
0 19352 2
0.128 29437 3
0 19353 4
0.032 75607
- 1. 5 0
19355 2
0 19301 3.42
- 0. 16 1 19356 3
0 19302
- 3. 5 0.031 19357 4
0 19303 13.66 0.212 19316 1
0 19304 3
- 0. 0 16 19305 1.92 0.019 193 %
4.67 0
19310 3.92 0.035 19312 5.83 0
19313 11.92 0.011 19318
- 5. 4 0
Monitored Monthly Moni tored ;'eek tv
$$)' l<? b()
H.
RELEASES TO THE ENVIRONS Table V represents the routine and non-routine releases of radioactive material to the air from the NSTF's building stack and power house stack.
Argon-41 is produced as a result of neutron interaction with naturally ocurring gases dis-solved in the reactor pool water.
Cs-138 is a particulate fission product.
They are a function of reactor operation, power and time.
The remaining nuclides represent losses from radioisotope production and experimental ir-radiation facilities (such as the Pneumatic Conveyor System ar d the in core Isotope Facility).
All are substantially below permissible release levels.
Table VI represents the release of racioactive material to the sanitary sewer from the drains and sinks in the NSTF, containment building, and reactor pool water.
They are collected in waste holding tanks and assayed prior to discharge to the sewer.
The levels are substantially below maxium release values, both in total quantity and concentration.
I.
PLANNED DIRECTIONS NR COMING YEAR To continue to meet constantly changing requirements imposed by regulatory and other external organizations within the resources availab1.e, numerous alterations of procedures are necessary.
These changes fall into the general categories of waste disposal, bicassay procedures, and record-keeping.
(a) Waste Handling - Procedures to ensure that all waste containers are properly packaged and assayed prior to transport to RPD are being instituted.
Each container will be assayed and certified by an RPD monitor prior to transfer to our processing area by Campus Delivery.
(b) Waste Discosal - Rapidly escalating prices for transport and burial of radioactive waste require that all alternative methods of disposal be considered.
- lo -
GD;:530
TABLE V SLEMARY OF 1978 AIR RELEASES MAX CONCENTRATION AVG ANNUAL
- 7. OF TOTAL Ci AT POINT OF RELEASE CONCENTRATION PERMISSIBLE NUCLIDE RELEASED (uCi/ml)
(uCi/ml)
LIMIT Routine Releases
-5
~0 Powerhouse Stack Ar-41 2.09 x 10 6.2 x 10 2.39 x 10 2 x 10~
~0 Building Stack Ar-41 8.04 1.1 x 10 9.18 x 10" 4.6
-2
-0
-2 Building Stack Cs-138 6.4 x 10
- 1. 4 x 10' 7.28 x 10 7.3 x 10 Non-Routine Releases
-5 At-41 2.34 5.32 x 10
- 2. 6 7 x 10~
6.7 x 10
-5
-13
-3 Au-198 1.25 x 10 5.62 x 10~
- 1. 43 x 10 1.4 x 10
~4
-2 Br-82 3.92 x 10 8.1 x 10" 4.47 x 10~
1.1 x 10 Pd-109 1.4 x 10' 4.8 x 10~
- 1. 6 x 10~
8 x 10~
692231
TABLE VI
SUMMARY
OF 1978 LIQUID WASTE RELEASES MAX CONCENTRATION AVG ANNUAL
- 7. OF TOTAL Ci AT POINT OF RELEASE CONCENTRATION MAX PERMISSIBLE NUCLIDE RE LEASED (uCi/ml)
(uCi/ml)
CONCENTRATION
-5
-2 Ag-110m 9.3 x 10-1.57 x 10 5.37 x 10~
5.97 x 10
-6 Co-58 2.3 x 10~
3.69 x 10 1.31 x 10-3.28 x 10'
-5
-7
~
Co-6 0 7.2 x 10~
1 x 10 4.19 x 10 4.19 x 10 '
-5 Cs-134 4.6 x 10
- 7. 46 x 10~
2.68 x 10' 8.93 x 10'
-6
-2 I-131
- 5. 4 x 10
1.14 x 10 3.12 x 10' 5.2 x 10
-5 La-140
- 7. 9 x 10 1.68 x 10~
4.6 x 10~
6.57 x
- 1. J '
-6 Mn-54 1.3 x 10-1.14 x 10 7.26 x 10' 1.82 x 10'
-5
-1 Sb-124 1.5 x 10~
3.14 x 10
- 8. 61 x 10~
1.16 x 10 Unidentified
-3
-6
-6 Beta 1.5 x 10 3 x 10 7.5 x 10 8.33 TOTAL VOLLME RELEASED IN 1978:
51,822 gallons
_o TOTAL CURIES RELEASED IN 1978:
3.73 x 10 '
Af ter dilution by Sanitary Sewer
!jjjk*
)g g
- 10b -
To arrive at op timum solutions, we will work with OPI and UBSFA to minimize costs within acceptable levels set by regulations pertaining to suca materials.
This will require the cooperation of Enviremental Health and Safety and the Maintenance Department.
(c) Record Keeping - Frequent reports are required of a wide variety of data pertaining to waste and radioisotope inv ento ry.
Current procedures should be converted to a computer-based system such that more rapid retrieval is possible.
(d) Trainine Courses - The need for training of new employees in basic safety methods is essential.
Current staf fing should allow this to be reinstituted in the near future.
In addition, other methods of presenting materials, such as the use of teaching machines are being considered as a supplement.
(e) Bioassay - Recent regulations requiring thyrcid bioassay for radioactive users have become effective.
Measurements were initiated in the fall of 1978 and continue.
With data now being collected, the methods will be refined and become a part of standard procedures.
J.
NSTF REACTOR REPAIR OPERATIONS 1.
In t roduc ti on on October 7, 1977, the SUNY at Buffalo, Pulstar Nuclear Reactor was shut down due to a leak in the primary coolant outlet pipe.
The leaking section o f pipe, which carried primary coolant water from the reactor tank to the heat exchanger, was buried in concrete beneath the reactor containment vessel when the Fac'lity was constructed, and hence cculd not be accessed for repair.
Extensive modifications, including new primary piping and new reactor support structures, were therefore required.
These modifications were commenced subsequent to the final spent fuel shipment on March 10, 1978.
This report cc nstitutes a review of the radiation protection procedures in-plemented duri: t the repair operation as well as the resultant radiation exposures.
6%T33 II.
Ove rview A.
Personnel Involved - The repair operations were performed and monitored by a variety of individuals.
Included were members of the Operations Department, Research Department, and Radiation Protection staffs.
Employees of the Joseph Davis Company and Peabody Testing Company were also involved. All workers were considered to be
" occupational", and hence, exposure guidelines were based on the maximum occupational dose limits; as specified in 10CFR and Part 16 of New York State Sanitary Code.
All oersons without prior nuclear experience were given an appropriate indoctrication wi.n regards to basic radiation techniques and consequences o ' radiation exposure.
B.
Hazards - Three basic types of radiological hazards were encountered in the operation:
1.
External high radiation fields 2.
Removable radioactive contaminatien 3.
Airborne radioactive material It was the responsibility of the RPD to ensure that appropriate measures were taken to minimize each of these hazards.
Radiation exposures to all workers were maintained to below 307. of the applicable expt sure guidelt,es.
With the exception of one employee of the Peabody Testing Company, who was only 17 years of age. 3,..j~.7, q m
No individual became sign,1ficantly contaminated.
Ne individual received any appreciable uptake of radioactive material.
C.
Eauipment 1.
Instrumentation (a ) variety of portable and laboratory radiation measuring devices were utilized during the project.
Included in these were:
(1) End and Side Window Geiger Survey Meters (Victore=1 Thyac III, and SU-14's).
(2) Ion Chamber Survey Meters (Victoreen Radector III's, 440, Panoramic)
(3) Thin, End Window Geiger Smear Counters (with background shields).
(4) Canberra-Beckman " Low B" Proportional G/B Smear Counter.
(5) Canberra "8100" Multichannel Analyzer, in conjunction with Ge-Li and NaI detectors.
(6) A specially modified Radector III survey meter with a remote ion chamber " probe".
(7) "High Vol" Air Sampler 2.
Dosimeters - Several different personnel dosimeters were used including:
(a) Civil Defense type self-reading pocket chambers; issued on an as needed basis.
(b) Victoreen-362, pocket chambers; a standard issue to all personnel.
(c) Searle Whole Body (X,B,7,N) clip on film badges; issued to all personnel.
These badges provided a legal record of whole body exposures.
(d) Searle Thermoluminescent Dosimeter (TLD) ring extremity dosimeters (X,B,7); issued to all personnel for which an extrenity dose in any calender quarter, could reasonably be anticipated to approach 900 mrem.
These dosimeters also provided legal record of exposure.
a (e) Victoreen TLD Whole body (X,5,7) clip on badges.
These badges could be read at any time using an in-house TLD analyzer.
Each worker active in the repairs was issuec one of these badges to I.5 0.1. D b be read on a weekly basis.
In addition, "special issue" badges were wo rn a t the discretion of RPD monitors to determine exposures from a specific event such as " hot" transfers.
(f) Victoteen TLD ring extremitr dosimeters (X,S,v).
These rings were also "in-house", and were issued on the same basis as the in-house whole body badges.
3.
Anti-Contamination Protective Clothing Various types of protective clothing were worn to preclude radioactive contamination of the workers.
This included:
(a) Yellow plastic boots, which were fitted ov?r the workers shoes.
These were re-used when possible, but discarded if damanged.
(b) Hip waders (standard fishing type). On occasion during the process of reactor disassembly, workers entered the tank while one to two feet of contaminated water remained inside.
Waders were worn on such occasions.
(c) Red plastic gloves (re-usable)
(d) Disposal latex (Tru-Touch) gloves.
Generally used as a backup inside the heavier red gloves.
(e) Cotton work gloves.
These gloves were used mainly in low con-tanination situations, and when handling rough or sharp reactor components which would likely tear the plastic gloves.
(f) Cloth coveralls.
These coveralls were worn whec working in the reactor tank over the werkers " street clothes".
The sleeves and cuffs were sealed inside the workers boots and gloves by wrapping them with masking tape.
When necessary pockets, zippers, and other closures were also sealed with masking tape.
These coveralls were frequently checked for contamination and were washed as necessary.
(g)
Plastic coveralls.
On occasion plastic coveralls were used in lieu of cloth to provide better protection fran wa ter borne contamina tion.
(h) Paper hats (or hoods).
These were used to preclude contamination of workers heads by rubbing against contaminated surfaces.
Various combinations of these protective clothings were worn at the discretion of the RPD staf f member (s) present.
Said staff member (s) also decided which combination of radiation dosimeters was to be worn and where they should be worn.
f :,9^= ? * > q o "b b 4.
Respiratory Protective Equipment Air samples drawn at various times during the repair project indicated that at no time was a worker required to enter en area which would require the use of respiratory protective equipment to comply with the requirements of 10 CFR 20.103.
However, to maintain worker exposures to airborne radioactive material as low as possible, workers were required to wear one of three respiratory protective devices (at the discretion of Radiation Safety Monitors).
(a) Scott Air Packs with 30 minute air tanks.
These units are self contained, forced supply respirators which provide full face protection.
Proper use of these respirators was explained to all Operations Department workers by a representative of the campus Enviromental Health and Safety Department.
Each member of the Department was also examined by a physician and certified for respirator use.
(b) Comfo-II half face respiratore with type "H" filter cartridges.
Each Operations Department worker was issued one of these respirators, and was required to keep it in his possession whenever opsrations were being performed which could potentially produce airborne contamination.
Joseph Davis and Peabody Testing Company employees were also issued this type of respirator and were required to wear them at the discretion of the attendant Radiation Safety Monitor.
(c) Paper dust masks; paper surgical masks were worn at times to preclude ingestion of dust caused by grinding and welding operations.
D.
Contamination Control Radioactive contamination was controlled quite successfully during the repair operations.
Contamination levels in " clean" areas remained normal throughout the operation.
Reactor Component contamination levels (removable) varied from 200 to 600,000 DPM/100 cm.
Components which required machining or other modifications were decontaminated via standard procedures.
Other components were either sealed in plastic bags, or simply stored on Kraft paper in special " contaminated equipment areas".
Tools and equipment were similarly stored, or decontaminated as required.
A special area between the control room and the reactor bridge was roped off and used to suit and unsuit personnel entering or leaving the reactor tank.
Workers were helped into anel out of cheir protective clothing by a Radiation Safety Monitor or his designee.
After unsuiting, a preliminary contamination check was performed oc the control deck.
The vorker was then immediately escorted outside the containment for a geiger survey in a low background area.
E.
External Radiation Exposures The radiation exposures of all individuals were maintained well below applicable maximum exposure guidelines.
A total of approximately 10 man-Rems of exposure were expended.
Exposures were reviewed on a daily basis, and work assignments were rotated to more equitably distribute the exposure among the workers.
An effort was made (successfully) to minimize the exposure to the younger workers as much as possible.
III.
Scope of Operation As stated earlier, the reactor repair operations were quite extensive.
Considerable modification or replacement of reactor support structures and primary coolant piping were required.
The reactor was first completely disassembled by the Operations Department.
Repairs and testing were then performed by the Joseph Davis and Peabody Testing Companies, with assistance from the Operations Department.
The reactor was then re-assembled by the Operations Department.
Subsequent to this reassembly, hydrostatic tests indicated that the system was nct leak tight.
The reactor was therefore, disassembled a second tLne.
Replacement welds 6$2238 were then performed, and the reactor system was again reassemble The following is a brief outline of the work performed.
A.
Initial Disassembly - Disassembly of the reactor commenced March 10, 1978.
All active components were removed from the tank by the Operations Department.
Various levels of water were maintained in the tank as the disassembly porceeded to provide shielding for the workers.
Radiation surveys were performed before each step of the disassembly to allow the attendant Radiation Safety Monitor to assign protective clothing, dosimeter, respiratory protective equipment, and stay tbne requirements.
Samples were drawn as necessary to monitor airborne radioactive material concentrations.
At times a specially fabricated lead shield was placed over the fuel grid plate to provide additional shielding. Worker stay times varied from a few minutes to a few hours.
Each comoonent was stored in a pre-arranged locatiot..
Some components were stored in the thermal column, the dry chamber, or in the beam tube Other components were stored behind e specially fabricated storage parts.
concrete block wall on the neutron deck.
Fuel assemblies were stared in a tank inside the Hot Cell. The reactor control blades were stored in a fuel transfer cask on the neutron deck.
Once the removable components were transferred fram the tank, a wash down of the tank liner and beam tube biological shield penetrations was pe r f o rmed.
While a comprehensive decontamination could not be performed, contamination levels were grossly reduced.
This phase of the operation was completed by March 24, 1978.
4 692239 B.
Tank Liner Testing - The next phase of the operation was a thorough testing and examination of the reactor tank liner (aluminum).
Dye penetrant test were performed on all the liner welds by two employees of the Peabody Testing Company.
Both of these workers had previous nuclear experience.
One of the workers, however, was only 17 years old.
Severe restrictions were therefore placed on his activities.
His exposure was limited to 10 millirem.
In addition to the dye penetrant tests, ultrasonic tests were performed to survey the liner for thickness changes.
These tests were performed by two of the Peabody Company employees and by members of the Operations Department.
A large corrosion induced occlusion was discovered on the liner shelf, necessitating subsequent replacement of the shelf liner.
The testing phase was completed in two days.
C.
Weldine Operations - With the liner testing complete, the actual repair operations commenced on March 28, 1979.
This work was performed by the Joseph Davis Company.
Nine welders and welding assistants were used.
None of these workers had prior nuclear experience, and hence. they were given an initial indoctrination with regards to radioactive protective procedures and methodolicies and the consequences of radiation exposure.
An ef fort was made to insure that the Davis Company employees were constantly under the surveilance of a radiation protection, or Operations Department staff member.
Work completed by the Davis Company workers included:
1.
Installation of a new plenum and core support with supporting legs.
2.
Installation of new primary inlet and outlet piping.
8-GE300
3.
Closure of abandoned primary piping liner penetrations.
4.
Installation of a new shelf liner.
5.
Closure of abandoned beam tube recirculation penetrations.
6.
Repair of a weld crack on beam tube number four.
7.
Repair of a seam on the dry chamber nose piece.
of abandoned demineralizer return tank penetrations.
8 ure This work was completed by May 8, 1978.
At this time,
.61 Davis 'Jompany equipment was checked for contamination and cleaned as required before being released for use outside the !acility.
All Davis Company employees were debriefed and t'.eir radiation exposures were explained to them.
D.
Reassembly - The next step undertaken was reassembly of the reactor by the Operations Dc partment.
Some minor modifications were made on re-assembly to make any further disassembly easier, should it become necessary.
The Facility machinist was involved in the reconnection of the reactor control blades to their drive extensions.
By May 18, 1978, the reactor was reassembled and transfer of the fuel assemblies back into the tank was begun.
E.
Second Disassembiv - Subsequent to reassembly and fuel transfer, hydrostatic tests indicated the existance of a leak or leaks somewhere in the reactor coolant boundry.
Hydrophonic testing was employed in an attempt to locate the leaks.
Possible leaks were found around one of the abandoned primary return penetration closures and around the abandoned primary outlet penetration closure.
A second disassembly was performed.
Experience gained in the first I
reactor disassemoly, and structural modifications made during reassembly G$f301 19 -
allowed this disassembly to procede smoothly and quickly.
The disassembly was started on June 5, 1978 and was completed on
.. n e 8, 1978.
F.
Additional Welding Operatic s - Replacement velds were made on the leak sites by Davis Company employees.
A new cover was fabricated and installed over the primary return closure.
Work was hampered by malfunctioning welding equipment.
This work was completed by June 12, 1978.
Upon completion, the workers were briefed and their equipment was checked for contamination as before.
G.
Second Reascembly - Reassenbly was again accomplished by the Operations Department and the Facility machinist.
This phase of the p-oiect was completed by June 20, 1978.
Instrument checkouts were performed and the reactor achieved criticality on June 26, 1978.
IV.
Conclusions - Some conclusions may be drawn as a result of the repair operations:
1.
All reactor components are repairable or replaceable; i. e.,
it is demonstrated that the reactor may be disassembled and reass embled completely.
2.
Deterioration of the reactor system at present is negligible.
3.
The incorporation of the TLD dosimetry system is both desirable and achievable. bOh202
TABLE VII FINANCIAL REPORT RADIATION PROTECTION DEPARTMENT (from 4/23/79 Budget Condition Report)
STATE ACCOUNT NO. 55170 ITEM BUDGET EXPENDITURES FREE BAIANCE 1.
Salaries and Wages a.
Non-Teaching (5FTE)
$65,054.00
$57,942.28
$ 7,111.72 b.
Overtime 3,467.00
.00 3,467.00 c.
Transfers 6,349.00 6,349.75
.75 d.
Temporary Service 4,700.00 4,700.00
.00 e.
Pending 6,349.00 6,349.00 (0.75)
Total Salaries and Wages
$73,221.00 S62,642.28
$10,578.72 2.
OTPS
$24, 842. 00
$24,912.18 (82.78)
Expendable Account Total
$ 98, 06 3. 00
$87,554.46
$10,495.94 INCOME REDfBURSAbLE ACCOUNT No. 91120 Salaries and Wages a.
Non-Teaching (1FTE)
S 9,317.00
$ 8,436.46 880.54 b.
Temporary Service 6,000.00 118.90 5,881.10 Total Salaries and Wages
$15,317.00
$ 8,555.36 S 6, 761.64 2.
OTPS
$ 36, 56 8. 00
$ 12, 06 0.14 S 9,267.01 Expendable Account Total S51,885.00
$15,240.85
$ 16, 028. 6 5 G3;:303