ML20214L120

Responds to 870422 Questions Re Licensee Decommissioning Plan.Diagram of Facility Organization for Decommissioning Provided.Rr Riley Resume & Radiation Control & Safety Manual Encl

ML20214L120
Person / Time
Site:	05000538
Issue date:	05/22/1987
From:	Oliphant V MEMPHIS STATE UNIV., MEMPHIS, TN
To:	Alexander Adams Office of Nuclear Reactor Regulation
Shared Package
ML20214L124	List: ML20214L120 ML20214L127
References
NUDOCS 8705290198
Download: ML20214L120 (9)

Text

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3 p MEMPHIS STATE UNIVERSITY MEMFHIS. TENNESSEE 38152 Office of the Vice President Telephone:901/454-2991 for Advancement and continuing Education s-s May 22, 1987

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Mr. Alexander Adams', Jr., Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Project.s Office of Nuclear RJactor Regulation United Staten Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

RESPONSE TO QUESTIONS REGARDING MEMPHIS' STATE UNIVERSITY'S DECOMMISSIONING PLAN (Docket No. 50-538)

The following is submitted in response to your questions dated April 22, 1987 regarding our Decommissioning Plan:

1. "Please provide a diagram that depicts the facility organization for decommissioning. Show the interface between the Institute for Resource Management (IRM)'and Memphis State University (MSU) . "

RESPONSE

President - MSU

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l Rad!ation Safety --

VP for Advancement & --

Director'- Security Committee Continuing Education y Safety Services i

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Radiation Safety Officer / Project Manager for Decommissioning I

, Institute for Resource Management Direct line of authority (IRM) ----Advisory / Assistance Capacity 9

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An EqualOpportunity/Afirmative Action University 1

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i Mr. Alexander Adams, Jr.

Page 2 May 22, 1987

2. "Please provide background information on IRM and MSU decommissioning staff by submitting resumes."

RESPONSE

i Attached please find a resume for Mr. Robert Riley who is the only L Memphis State University employee likely to be participating in l any way with regard to decommissioning and eventual dismantling l and removal of the reactor. Resumes for I.R.M. personnel have-been requested, but have not been received at this time. These will be forwarded upon receipt.

l 3. "Please discuss.the mhnagement policies and features of the organizational structure that will ensure that all operations will be carried out under the concept of ALARA (As Low As Is Reasonably Achievable)." ,

RESPONSE

Memphis State University operates under regulations established by the Tennessee Department of Public Health, Division of Occupational and Radiological Health and the Nuclear Regulatory Commission. To aid in insuring compliance, the University has incorporated the Memphis State University Radiation Control and Safety Manual into the University Operating Procedures. I have included a copy of this manual for your review. It should also be noted that all operations will be reviewed in advance.

4. "Please describe your industrial safety and hygiene program.

! What provisions have been made for response to industrial l accidents?"

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RESPONSE

Memphis State University employs a staff of five full-time safety personnel who are devoting 100% of their time to safety related matters. Additionally, Memphis State University has obtained l

agreements with . local agencies for transport and treatment of injured personnel. The Memphis Fire Department _will transport any ,

injured worker, even if contamination'is present. The City of Memphis Hospital has agreed to treat' any patient, even if contamination is present.

5. "What is the present status of your fuel?"

! RESPONSE l

l l The reactor fuel has been returned to D.O.E. and has been transported to Oak Ridge National Laboratory for storage.

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Mr. Alexandar Adamo, Jr.

Page 3 May 22, 1987 6.. "Please provide the history of the reactor, if anye before it was placed into operation at MSU."

RESPONSE

The reactor was obtained from Argonne National Laboratory. We have no information regarding its history at that facility.

7. "Please submit for review your proposed Technical Specifications for decommissioning."

RESPONSE

i The Thermal Column Tank and Graphite Reflector Cylinder will be removed and placed on paper mats on the reactor room floor. Swipe surveys will be taken inside and outside of each as well as on the bottom of the reactor vessel which will be exposed at this point.

Having done this during the defueling process it is not expected that any contamination will be found. The four securing bolts which attach the vessel to the floor will be removed and the base of the vessel will be swiped for contamination detection. At this point the reactor is ready for loading once approval for release is obtained.

8. "Please submit for review an Environmental Report that I describes the environmental effects of the decommissioning l process. Identify any potential offsite environmental problems that could arise from the dismantling project and describe the means employed to prevent any unacceptable offsite releases."

i l RESPONSE There is no anticipated Environmental Impact associated with the decommissioning of this reactor. During the defuelling process, all areas of the reactor vessel were surveyed for contamination.

l No detectable contamination was found then; and although we will l be utilizing more sensitive equipment, it is not likely that any contamination will be found. There is no anticipated public exposure and we expect no release of solid, liquid or airborne contamination.

9. "After dismantlement, where will the reactor be stored until the license is terminated?"

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! RESPONSE l After dismantlement the reactor vessel and components will remain l

in the reactor room (Room 140 A2) .

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Mr. Alexander Adams, Jr.

Page 4 May 22, 1987

10. " Estimate the occupational exposure that will be received by personnel in the process of dismantling the reactor."

RESPONSE

All personnel involved in the decommissioning will be supplied with TLD's to monitor any exposure received during dismantlement.

It is expected that no exposures above background will be found.

11. " Indicate how direct and accurate measurements of surface contamination (in CPM) will be made and converted to DPM/100 square cm. Identify those instruments to be used which are sensitive enough to measure in the micro-R/ hour range."

RESPONSE

A cut-out of 100 square cm. will be used to insure area of swipe and the meter to be used (a F. A.G. Nuclear Survey Meter,-Model F-40-Calibrated to 2 micro-R/ hour) reads directly in micro-R/hr.

12. " Describe how inaccessible areas (pipes, ducts, drains) will be surveyed for contamination."

RESPONSE

After dismantlement there are no known inaccessible areas on this reactor vessel.

13. " Indicate the contamination limits which will be employed when disposing of equipment as radioactive waste. Verify that you will comply with the criteria of Regulatory Guide 1.86 as a minimum."

RESPONSE

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There will be no waste generated during dismantlement or removal of the reactor vessel and components with the possible exception of swipes and paper mats. These will be included in our next shipment of radioactive waste if activity requires it.

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14. " Indicate the quantity of solid waste which will be generated i and where it will be disposed. Describe the means to be l utilized for treating liquid effluents, if any are 1 generated."

RESPONSE

Again, it is not expected that any waste will be generated except as noted above.

Mr. Alcxander Adams, Jr.

Pzgo 5 May 22, 1987

15. "If the defueled reactor is to be released for unrestricted use, please provide the procedures that will be followed to insure that the internal and external reactor components meet the criteria of Regulatory Guide 1.86 and the limit of 5 micro-R/ hour or 10 mrem / year above background at 1 meter from the surface."

RESPONSE

The vessel will be in four main parts: the reactor vessel, the Thermal Column Tank, the Graphite Reflector Cylinder and the Drive Rod Assemblies. Each will be resurveyed inside and outside to detect the presence of any contamination. We will be using a F.A.G. Nuclear Survey Meter Model F-40 which will be calibrated to 2 micro-R/hr. All components will remain in this disassembled state until final approval for removal from N.R.C. is received.

16. "Please provide your plan for the survey that will be submitted to the NRC to support termination of the license."

RESPONSE

Prior to dismantlement a survey of the reactor room will be performed to establish a baseline for reference. During dismantlement each component of the reactor will be surveyed for fixed and removable contamination using a Ludlum Model 3 Survey Meter with Alpha Probe, a Ludlum Model 3 with a thin window pancake probe, and a F.A.G. Model F-40 Nuclear Survey Meter. The F. A.G. meter will be calibrated by I.R.M. to 2 micro R/hr. After dismantlement a total building survey will be performed using the previously noted instruments plus a Ludlum Model 3 Survey Meter with a Bonner Ball. Readings will be made at floor and 1 meter from floor levels throughout the building and outside the building adjacent to the reactor room at the wall and at 1 meter from the wall. This building survey will be repeated after the reactor is removed by I.R.M. which will be as soon as final approval from N.R.C. is received.

Please contact Bob Riley at 901-454-4672 if there is any further

-information you may need to facilitate an expeditious completion of this decommissioning process. Thank you for your assistance in this effort.

Sincerely, M. [

Van N. Oliphabt Vice President Advancement and Continuing Education kc Attachments pc: See next page

n Mr.- Alexander Adams, Jr..

Page 6

- May 22, 1987 pc w/o attachments:'

Mayor of the City of Memphis ,

sCity Hall - Room 700 125 North Main Memphis, TN 38103 I

Tennessee Department-of Public Health ATTN: Director, Bureau of Environmental Health Services Cordell Hull Building Nashville, TN 37219 Attorney General Supreme-Court Building Nashville, TN 37219 Ms. Kathryn Hookanson Legal Counsel-Memphis State University Memphis,.TN 38152 Ms. Susan C. Short Office of General Counsel The State University and Community College System of Tennessee 1161 Murfreesboro Road Nashville, TN 37219 l

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ROBERT R'. RILEY, JR.

4200 Buford Ellington Drive South Memphis, TN. 38111 Home phone: 454-0028 office phone: 454-2256 PERSONAL Date~of Birth: March 23,-1948 Marital Status: Married Height: 5.'10" Weight: 190 lbs.

Health: Excellent PROFESSIONAL EXPERIENCE January, 1985 - Present Environmental / Radiation Protection Officer, Memphis State University Memphis, TN. 38152 Assists faculty in matters con-cerned with radiation or radio-active materials, performs radiation surveys; maintains records and ensures compliance.

Responsible for chemical safety and compliance with " hazard communication" and " employee right-to-know laws.

April, 1982 - January, 1985 Radiation Safety Officer Memphis State University Memphis, TN. 38152 Assists faculty in matters con-cerned with radiation or radio-active materials,-performs radiation surveys; maintains records _and ensures compliance.

August, 1981 - April, 1982 Safety Inspector-Memphis State University Memphis, TN.- 38152 .

Performs safety inspectio,ns, provides technical assistance investigates accidents, maintain records, conducts training sessions and attends safety committee meetings.

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Robert R. Riley, Jr.

Resume: Page 2

-January, 1980 - August, 1981' Teacher Klondike Elementary School Memphis, TN.

Extensive recordkeeping, con-tinual communication with individuals of-various ages-and_ backgrounds,and planning

& instuction in all disci-plines.

August, 1977 - December, 1979 Student Memphis State University Memphis, TN. 38152 Participated _in the Resident Intern Program (RIP) which is an honors program designed to provide a wider scope in the preparation of elementary teachers; Student Teaching -

Spring 1979 (Ridgeway Elem.),

and Fall 1979 (Hamilton Elem.).

October, 1972 - August, 1977 Firefighter Memphis Fire Department Memphis, TN. .

Qualified operator of 75 ft.

junior aerial, periodic inspections of community businesses, schools, plants, emergency medical treatment, search and rescue and all forms of fire suppression.

January, 1970 - August, 1972 Heavy' Construction Boston, Massachusettes Rough carpentry,Jpile driving welding-and acetylene torch.

August, 1967 - August, 1969 Personnel Specialist United States Army .

Two years active duty and four-years inactive; Secret clearance issued- 11-13-67 per D.O.D. N.A.C.C.,' Honor- l able discharge (Aug. 73).  :

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Robert R. Riley, Jr.

Resume - Page 3 EDUCATION:

Memphis State University, Memphis, TN.

M.S. (1985),1 Major: Technical Education and Training Memphis State University, Memphis, TN.

B.S.E. (1979), Major: Elementary Education with an endorsement in Early Childhood Education Shelby State Community College, Memphis, TN.

A.A.S.-(1978), Major: Fire Science and Safety Technology, cum laude MEMBERSHIPS / ACCOMPLISHMENTS Member of M.A.T.D. - Mid-South Association of Trainers and-Developers (April, 1982).

Participated in six (6) one hour workshops on microcomputers-Memphis-State University Familiar with Basic, Command and Executive languages and applications for the Xerox Sigma 9, Univac.and Apple and IBM / Zenith Computers (Fall, 1982).

Qualified as First Aid Instructor and qualified in C.P.R.

(Spring, 1982).

Member of American Society of Safety Engineers (Sept., 1982).

Elected Secretary of American Society of Safety Engineers, West Tennessee Chapter (June, 1984).

Present instructing at Memphis State University, College of Engineering Technology, course number 3386, Occupational Safety (September, 1984).

Elected Vice President of American Society of Safety Engineers, West Tennessee. Chapter (June, 1985).

Attended the Radiation Safety Officers Training Course offered by the University of Texas Health Science Center at San Antonio, Texas. This 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> course was-tx) prepare junior health physicists and other radiation safety personnel to serve as institutional or organizational Radiation Safety Officer (January, 1983).

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