|
|
Line 1: |
Line 1: |
| {{Adams | | {{Adams |
| | number = ML20246E110 | | | number = ML20247H321 |
| | issue date = 08/17/1989 | | | issue date = 09/13/1989 |
| | title = Insp Rept 50-112/89-01 on 890525-26.Violations Noted.Major Areas Inspected:Mgt Organization,Reactor Operations & Maint Logs,Internal Audit & Review Program,Radiological Controls, Emergency Preparedness & Physical Security | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-112/89-01 |
| | author name = Baer R, Wilborn L | | | author name = Beach A |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Egle D |
| | addressee affiliation = | | | addressee affiliation = OKLAHOMA, UNIV. OF, NORMAN, OK |
| | docket = 05000112 | | | docket = 05000112 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-112-89-01, 50-112-89-1, NUDOCS 8908290011 | | | document report number = NUDOCS 8909190289 |
| | package number = ML20246E098 | | | title reference date = 08-31-1989 |
| | document type = INSPECTION REPORT, NRC-GENERATED, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO EDUCATIONAL INSTITUTION, OUTGOING CORRESPONDENCE |
| | page count = 9 | | | page count = 1 |
| }} | | }} |
|
| |
|
Line 19: |
Line 19: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:, . - - . | | {{#Wiki_filter:.__ - _ _ |
| ., | | , .. |
| --
| | (% |
| =;
| | . |
| '
| | - |
| ' | | - t W'i - |
| l a.) < c
| | - |
| . + s t . :. | | , |
| '
| | SEP il 3 !989' |
| Mn' b
| | .. |
| '
| | .-In-Reply Refer To: . |
| ,, | | _ |
| APPENDIX'B
| | Docket:. 50-112/89-01'. |
| | i The-USiversity of Oklahoma |
| | ,LATTNi Dr. Davis M. Egle l Director,lAMNE |
| | .J 865 Asp Ave., Room-212 |
| | . Norman,' Oklahoma 73019 |
| , | | , |
| s =U.S.' NUCLEAR REGULATORY COMMISSION REGION IV-
| | Gentlemen: |
| ,
| | Thank you for'your ' letter of. August 31, 1989, in' response to our letter and Hotice of. Violation dated August 18, 1989. We have reviewed your reply.and ifind it responsive to the' concerns raised in our Notice of Violation. We will-review the implementation of your corrective actions during'a future inspection-to determine that full compliance has been achieved and will be maintained. |
| ( NRC.' Inspect 1on Report: 50-112/89-01 Operating. License: R-53 Docket: 50-112 Licenseei- University of Oklahoma 865 Asp Ave., Room 212
| | |
| : Norman,' Oklahoma . 73019 Facility Name: AGN-211P, Research Reactor (100 KW)
| | Sincerely, |
| Inspection At: University of Oklahoma, Norman, . Oklahoma Inspection Conducted: May 25-26, 1989 o
| | ; |
| Inspector: bwt G i
| | ,r. |
| , Lorenzb WiWorn, Radia tion Specialist . Date Facilities Radiological'l Protection Section-l Accompanied By: ' Ronald E. Baer, Chief, Facilities Radiological Protection Section
| |
| ;Approvedi hM Ronald E Baer, Chie{, Facilii.ies Radiological Date'
| |
| &!!7 h Protection Section (
| |
| Inspection Summary Inspection Conducted May 25-26, 1989 (Report 50-112/89-01)
| |
| ' Areas Inspected: Routine, unannounced inspection of the licensee's management organization, reactor operations and maintenance logs, internal audit and review program, radiological controls, emergency preparedness, physical
| |
| . security, nuclear materials safeguards, and transportation of radioactive
| |
| . material Results: . The NRC. inspector determined that the licensee had not operated the
| |
| .AGN-211P research reactor during the period covered by this inspectio The licensee had removed fuel from the reactor, shipped the fuel to a L
| |
| Department of Energy facility, and dismantled the reactor.
| |
|
| |
|
| l-l 6908290011 890818
| | A. Bill Beach, Director Division of Radiation Safety and. Safeguards cc: |
| . {DR .ADOCK0500g2 l | | ' The . University of Oklahoma ATTN: Dr. E. H. Klehr, Chairman Reactor Safety Committee |
| o.
| | '865 Asp Avenue Norman,- Oklahoma 73019 bec to DMB (IE01) |
| | bec: |
| | R. Martin Inspector (s) |
| | C:RPSB-DRSS T. Michaels, NRR Project Manager DRP Lisa Shea, RM/ALF .I RIV File MIS Coordinator RSTS Operator DRS l" B. Beach, DRSS C:FRPS l RPB-DRSS |
| | ' |
| | ( |
| | RIV:FRPS C:FRPS , C:RPB D SS i LW11 born / sir RBaer x.BMurray beach T 9/p/89 9 /P/89 9 // F/89 9 / 17./ 8 9 i |
| | L- 8909190289 890913 5 4 |
| | [ PDR ADOCK.05000112 |
| | * " |
| | / |
| | u. . .. - - - - - |
| | Z@k7 4 |
|
| |
|
| .. , | | . _ _ _ _ - _ - - _ _ _ _ - |
| -____ __ -- _ _ _ _ - - - _ _ - - - - - - - - - - - - _ - - - - _ - - - - - - ---_- u
| | . |
| | ' |
| | Jr 'f g r.y.vf 9' |
| | d , |
| | ,d#e _....,.Sh k e |
| | - |
| | -- |
| | , ibm |
| | .n , |
| | ' |
| | coq p. |
|
| |
|
| - _
| | .> |
| _ _ _ _ _ _ - _ - -
| | 3 _ , |
| . 4 | | University of Ok[ahoma b |
| ' * | | ~~~ |
| , | | ' SCHOOL oF AEROSPACE AND |
| | .CECHANICAL ENGINEERING 86s Asp Avenue, Room 212 Norman, oklahoma 73019 o601 4 |
| , | | , |
| | pos)325.s011 August 31,1989 Mr. A. Bill Beach, Director Division of Radiation Safety and Safeguards US Nuclear Regulatory Commission - Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington,TX 76011 d Re: Docket: 50-112/89-01 |
| | |
| | ==Dear Mr. Beach:== |
| | The following is presented in reply to the Notice of Violation for the 25-26 May 89 NRC inspection of the University of Oklahoma Operating License R-53. |
| | |
| | A. Authority to Dismantle a Facility The University admits the facility was dismantled ahcI the fuel had been shipped off-site, butpnar to receipt of NRC approval of our submitted Dismantling and |
| | . Decommissionmg Plan. It was our interpretation that since the reactor would not be ; |
| | refueled nor operate again that we could undertake certain activities while personnel were available to do such. As noted by your inspector, these activities, although premature,were conducted in a were made as work progressed. pro?er manner and that simultaneous safet associated with the tank assembly have been retained on site for NRC inspection. |
| | |
| | None of these materials will be released until NRC issues the termination order. |
| | |
| | Only one item, the fine control rod, was found to contain any residual radioactivity |
| | [ identified by gamma spectroscopy as Co-60: 4 mR/hr surface,0.1 mR/hr at one |
| | , |
| | meter). This item will be disposed of by Radiation Safety along with other low level radioactive waste from the University at an appioved low level radioactive waste disposal site. The dismantling and decommissioning plan was approved by NRC letter dated 5 June 89 and operations s ecified in this submission are presently being conductedin compliance in the plan the Radiation Safety Office. |
| | |
| | B. Reactor Safety Committee Composition The University admits that for the period specified the composition of the Reactor Safety Committee was not in compliance with Technical Specification 6.2 as approved by Amendment No.12 to Facility License No. R-53. The fuel was shipped off-site on |
| | ' 20 April 86 and the reactor director left the University for other employment that summer. It was our erroneous impression that with the fuel and director gone that |
| | .. |
| | 7g 07-g-g % M Soe %erio SPP' u |
| | |
| | . _ ____ -________ _ _ |
| | e |
| | ! * |
| | .',, 2 August 29,1989 |
| | ] M .. |
| | compliance with the committee com osition requirement was no longer necessary. |
|
| |
|
| Within the areas inspected, five violations were identified (failure to properly compose a reactor safety committee, paragraph 4; failure to conduct semiannual reactor safety committee meetings, paragraph 4; fa11ure to provide emergency planning training, paragraph 8; failure to conduct annual audits, paragraph 6; and failure to obtain proper authority to dismantle a facility, paragraph 3. Even though the licensee had dismantled the reactor without receiving NRC approval, it appeared that dismantling activities were conducced in a proper manner with no risk to the public health and safety i
| | The requirement for a Reactor Safe Committee was deleted from the new Technical Specifications approved b NRC letter dated 5 June 89. |
| ,
| |
| I l
| |
| i
| |
| -__- _.~- _
| |
|
| |
|
| - _
| | C. Reactor Safety Committee Meetings , |
| - ._ - --
| | The University admits that subsequent to its 28 March 88 meeting, the Reactor Safety Committee did not meet semi-annually as required in Technical Specification 6.2.6. |
| '
| |
| J . . , . %
| |
|
| |
|
| p
| | As mentioned in paragraph B. above, it was our erroneous impression that with the fuel and the reactor director gone that meetings were not necessary and that the Radiation Safety Officer should proceed with the Dismantling / Decommissioning task. |
| ' DETAILS Persons Contacted.
| |
|
| |
|
| L * B. Walker, Associate Dean, College of. Engineering
| | ' New Technical Specification 6.2 approved by NRC letter dated 5 June 89 eliminates the need for a Reactor Safety Committee as an administrative control. |
| *P. Skierkowski g Radiation ' Safety Officer E. N. Stone, Deputy Chief of Operations, University of Oklahoma. Police:
| |
| Department S..Long, Norman Fire Department
| |
| * Denotes tho.se present during the exit interview on May 26, 198 .. Followup on Previously identified Inspection Findings (92701)-
| |
| (Closed) Violation (112/87C1-01): Failure to Record Radioactive Contamination Survey Results in Proper Units - This violation was identified in NRC Inspection Report 50-112/87-01 and involved the failure
| |
| :
| |
| to reco.rd the results of radioactive contamination-surveys of the Nuclear Engineering Laboratory in the required terms of disintegrations. per unit time or in curies. The. licensee had revised the= laboratory survey report
| |
| ~
| |
| form to reflect the proper units for the liquid. scintillation survey '
| |
| result (Closed) Violation (112/8701-02): . Failure to Revise / Update the Letter of Agreement - This violation was identified in NRC Inspection Report 50-112/87-01 and involved the failure to'have a current letter of agreement between the licensee and the Norman Municipal Hospital required by the licensee's Emergency Preparedness-Plan. The NRC inspector noted that'the licenses had obtained a letter from the Norman Regional Hospital dated Apr11 7, 1987, renewing the written agreemen (0 pen) Violation (112/8701-03): Failure to Provide Emergency Response Training - This violation was identified u NRC Inspection Report 50-1:?/87-01 and involved the failure to provide training in radiation safe ^.y and the facility emergency procedures to individuals from the University Police and Norman Fire Department who would respond to an emergency at the facility. The licensee's response to the violation stated that training would be provided prior to December 31, 1987. The NRC inspector noted from discussions with the University Police and Norman Fire Department personnel that the University Police personnel had been provided training in radiation safety and the facility emergency procedures, but the Norman Fire Department personnel had not been provided with such training. This is considered a repeat violatio (See paragraph 8.) ] Status of Facility The AGN-211P research reactor has not been operated since April 24, 198 The NRC issued Amendment No.12 to Facility License No. R-53 on March 8, 1988, converting the license to possession-only status and the facility to
| |
| _ _:__ _ _ L . - - -
| |
|
| |
|
| - _ _ _ _ .
| | D. Audits The University admits that audits required by Technical Specification 6.2.8.E were not performed subsequent to the final Reactor Safety Committee meeting of 28 March 88. The requirement for subsequent audits was deleted from the new Technical Specifications approved by NRC letter dated 5 June 1989. |
| . .
| |
| ' *
| |
| .
| |
| .
| |
| i
| |
| '
| |
|
| |
|
| i a mothball status. The licensee shipped the reacter fuel on April 20, f 1988, to a Department of Energy approved recipient and the console and L
| | E. Fmergency Response Training A trainin (program for radiation safety and facility emerg procedures for the Norman hire Department is being initiated by the Univers: Radiation Safety as part of the Umversity's NRC road License program. |
| support equipment were dismantled during the period May 18, 1988, through July 13, 1988. -The licensee submitted to the NRC on October 25, 1988, an application for a license amendment to approve a Dismantling and Decommissioning Plan for the University of Oklahoma research reactor. The plan had not been approved by the NRC at the time this inspection was conducte The licensee's dismantling included such activities as follows:
| |
| Removal of reflector element *
| |
| Removal of the reactor control rods and drive housin Removal of the fuel element support grid plat Disassembly and removal of the reactor consol Removal of the reactor support structur Removal of the demineralized tank and resin bed *
| |
| Draining of the reactor poo CFR Part 50.82 states, in part, that a licensee may apply to the Commission for authority to surrender a license voluntarily and to decommission the facility. Each application for termination of the license must be accompanied, or preceded, by a proposed decommissioning plan. If the decommissioning plan demonstrates that the decommissioning will be performed in accordanct with the regulations and not inimical to the health the safety of the oublic, and after notice to interested persons, the Commission will approve the plan and issue an order authorizing the decommissionin The licensee's dismantling of the reactor and associated reactor components (decommissioning the facility) prior to submitting a decommissioning plan and receipt of an' order issued by the Commission authorizing the decommissioning is considered a violation of 10 CFR Part 50.82. (112/8901-01) Organization and Management Controls The NRC inspector reviewed the organization and managements controls to determine compliance with Technical Specification (TS) The current organization was verified to be consistent with the current reactor facility status. Although the Dismantling and Decommissioning Plan had not received final NRC approval, the licensee had initiated implementation of the plan to include the administrative organizatio The TS Figure 1, " Administrative Organization of the OU Reactor,"
| |
| specified a Reactor Director staff position; however, subsequent to the l shipment of the reactor fuel and dismantling of the reactor facility, the position of Reactor Director was abolished. The Radiation Safety Officer had taken over all responsibility of the dismantled reactor facilit {
| |
| After NRC approval of the Dismantling / Decommissioning plan, the Radiation j Safety Officer will maintain responsibility through decommissioriing and i clean up of the reactor sit l
| |
|
| |
|
| i L_._-_______.. . _ _ - - - - _ _ .
| | Office (seewillAttachment This rogram be part o A)f training conducted on a continuing basis by the Ra Safe Office. |
|
| |
|
| _
| | incerely, hph. |
| ____ _____ - _ _
| |
| .. .
| |
| ; :. '..
| |
| !- 5 L
| |
| , .
| |
| .The: status'of Reactor Supervisor, licensed operators, membership and.
| |
|
| |
|
| , meetings of the RSC, and other matters'concerning supervision of the reactor facility were examined. . The minimum staffing requirements were verified to be present during fuel handling operations. Subsequent to the
| | Davis M.Egle [ |
| ' shipment of the reactor. fuel, the licensed operators were terminated ana the RSC ceased conducting meeting The NRC inspector reviewed the minutes of the RSC and verified that the committee had met quarterly and reviewed matters related to the reactor from the previous' inspection until March 28, 1988. TS 6.2.1 states, in part, the RSC_ shall- be comprised of not less than four members appointed .
| | Director DME/rb Enc: Attachment A cc: Dean D.C. Crynes Dean G.B Walker Dr. Paul Skierkowski , |
| by the Vice-President for Administrative Affairs, two of whom will be the Radiation Safety Officer and the Reactor Director. Since the abolishment / termination of. reactor staff positions, the RSC could not be .
| | j |
| composed as required by,the TS. The licensee's failure to properly compose a RSC during the period from March 28, 1988, to May 25, 1989, is considered a violation of TS 6.2.1 (112/8901-02).
| | - |
| | l |
| | ! |
| | - ------ -- _ _ _ -- |
|
| |
|
| TS 6.2 6, states, in part, the chair shall be appointed by the Vice-President for Administrative Affairs. The chair shall be responsible to call the committee into session at least semiannually and shall make assignments as necessary to the members of the committee. The RSC chair's failure to call the committee into session semiannually during the period March 28,z 1988, to May 25, 1989, is considered a violation of TS 6. (112/8901-03)
| | - |
| .No deviations were identified in this are . Operation and Maintenance Logs The NRC inspector noted that the reactor had not operated during the period covered by this inspectio The NRC inspector reviewed the reactor maintenance logs to determine compliance with TS 6.21(g) for the period January 31, 1987, to March 28, 1988, and TS 4.2 for the period March 28, 1988, to May 25, 198 All maintenance activities appeared to have been conducted in a manner consistent with the TS requirements and administrative procedure No violations or deviations were identifie . -Internal Reviews and Audits
| | - -_- |
| | -) . |
| | ;& ;. x |
| , | | , |
| The NRC inspector reviewed the licensee's review and audit program to determine compliance with 10 CFR Part 50, and TS 6.18 for the period January 31, 1987, to March 28, 1988, and TS 6.2 for the period March 28, ,
| | .,q'; ,g. |
| l 1988, to May 25, 198 . TS 6.2.8 states, in part, that the duties of the RSC shall include an audit performance at least annually of the reactor staff of the areas facilities manual (procedures) maintenance logs and test procedures, surveillance tests, and physical security pla _ _ _ _ _ -
| |
| l
| |
| .
| |
| ., .
| |
|
| |
|
| The NRC inspector determined that the Reactor Safety Committee had not performed an annual audit of the reactor staff in the areas of the facilities manual (procedures), maintenance logs and test procedures, surveillance tests, and physical security plan during the period March 28, 1988, to May 25, 1989. The licensee's failure to perform such an annual audit is a violation of TS 6.2.8.E (112/8901-04). Radiological Controls The NRC inspector reviewed the licensee's radiation protection program to determine compliance with 10 CFR Parts 19.11, 19.12, 19.13, 20.101, 20.104, 20.201, 20 202, 20.203, 20.207, 20.401, 20.403, 20.405, 20.408, 20.409, and 50.54(q).
| | ; ; |
| | Y unimity ofonwma ms - |
| | ses Asp.nsom.112 Normen,Omahams 73010 |
|
| |
|
| .The NRC inspector reviewed records, interviewed personnel, made observations, and performed independent survey Personnel Monitoring The NRC inspector reviewed the licensee's personnel radiation exposure records for the first quarter 1987 through the first quarter 1989, and noted that all neutron exposures were recorded as O mrem and the maximum beta / gamma exposure was 125 mrem per quarter, with an average of 18 mrem per quarter. This review included the personnel exposure records for personnel involved in the fuel handling during the fuel transfer and shipment operations. The exposures associated with this. operation averaged less than 12 mre No violations or deviations were identifie Radiation Monitoring Instrumentation The licensee's portable radiation monitoring instrumentation calibration program appeared to satisfy the recommendations of NRC Regulatory Guide 8.21 and ANSI Standard N323-1978. Calibration records were found to be up-to-date and accurat The licensee's on-hand stock of portable radiation monitoring instruments appeared adequate to support facility radiological surveys. The licensee's completed facility radiation survey records were reviewed and found to be well documented. The NRC inspector conducted confirmatory measurements (beta gamma) of radiation and found that the results were in agreement with the licensee's most current result No violations or deviations were identifie Radioactive Releases The NRC inspector reviewed the licensee's analysis of the reactor shield tank water prior to release to the sanitary sewerage syste Samples were taken at various depths in reactor shield tank. The j l
| | - pos)as tots 123: August 1989 Mr. Steve Long: |
| :
| | Training officer. |
|
| |
|
| mg .
| |
| _ | | _ |
| o ,
| | Norman Fire Depart:nent |
| y, .;
| | '411.E. Main-Norman, OK- 73071 Dear Mr. Long The Nuclear' Regulatory' Commission conducted an inspection of our ! |
| | -Nuclear' Reactor Facility on.25-26 May.1989. In conjunction with this ') |
| | inspection they visited with you.concerning our Emergency Preparedness Plan.- It appears.that we have been deficient in coordinating-such Ltraining with the Norman. Fire Department. |
|
| |
|
| ' | | Although the Nuclear Reactor Facility has been dismantled and the-fuel-chipped to the Department of. Energy, we.still maintain numerous.other labs which utilize radioactive materials.in research. Although none |
| licensee's analysis =for alphs, beta., tritium, and gamma radionuclides indicated concentration levels below the units specified for unrestricted areas in 10 CFR Part-20, Appendix No violations or deviations were identifie Surveys
| | , |
| !-
| | .cf these are'of.the level'of'the reactor and require an Emergency Pre- l paredness' Plan, we do; maintain Emergency Procedures under our Nuclear ' |
| Tne NRC inspector reviewed radiation and contamination survey records regarding surveys performed by the licensee's staff to determine compliance with 10 CFR Part 20 and agreement with the licensw's procedures. The licensee's staff had performed a radiation sud-contamination survey on the reactor' shield tank after drain'.ng. All surveys were documented according to department procedures. The survey results revealed no areas with radiation levels in excess o the regulatory limit The NRC inspector noted that the licensee had used a Geiger-Mueller tube type of laboratory instrument to perform alpha and beta radiation contamination'ecunting. The background count rate was approximately 54 counts per minute and the system efficiency ha been determined to be approximately 4.6 percent for alpha radiation. The NRC inspector discussed with licensee-representatives that with a releast limit of 20 disintegrations per minute-(dpm) for alpha radiation and 200 dpm for beta' radiation that a more efficient counting system would be desirable. The licensee-stated that all material being released for unrestricted usage and the final release survey of 'the reactor laboratory facility would be-swiped for removable radioactivity. These swipes would-be counted on a instrument capable of determining separately the alpha and beta radioactivit No violations or deviations were identifie . Emergency Preparedness The NRC inspector reviewed the emergency preparedness program to determine agreement with commitments made in the Emergency Preparedness Pla CFR Part 50.54(q) requires that a licensee authorized to operate a research reactor shall follow and maintain in effect an emergency plan.
| | Regulatory Consnission license for these activities. 'Since the Norman' |
| | Fire Department.would'be the' responder.for'certain emergencies in these facilities it would be beneficial if we. coordinated training in |
| | : radiation safety'and'the' facility emergency procedures. |
| | |
| | 'As'a start I would like to invite you..and any others you may chose to 1 attend our Radiation Safety for Laboratory Personnel training session. |
| | |
| | - A syllabus for the program is attached. This program covers the , |
| | ibasics of radiation safety for lab personnel working'with radioactive |
| | . |
| | l |
| | ; materials and would also be applicable to personnel responding to an emergency. After this program is completed I would suggest that we meet to discuss further training and coordination in this area. ) |
| | Thank you for your-assistance in this matter and I look forward to working with you in this training need. Should you have any questions p please contact me at 325-1015. |
|
| |
|
| L I- The issuance of Amendment No.12 to Facility License No. R-53, dated March 8, 1989, granted the licensee an exemption from 10 CFR 50.54(q),
| | sincerely, l |
| which required an emergency plan for non power reactor The Emergency Plan had been properly implemented, except during the period from January 31, 1987, to March 8, 1989. Section 10.1 of the Emergency Plan addressed training that would be provided to individuals with emergency response responsibilities and stated that the University Police and Norman Fire Department shall be trained on annual basis in radiation
| | ' |
| - _ _ _ _ _ - _ _ _ _ - _ _ _
| | Paul Skierkowski, Ph.D. |
|
| |
|
| -- - | | Radiation Safety Officer ; |
| .
| | s l |
| ,
| | ! |
| | ! |
| | . _ _ - _ . - _ - _ _ ._- _ _ - - _ _ _________ _ m |
|
| |
|
| safety and the Nuclear Engineering Laboratory facility emergency procedures. The NRC inspector's discussions with representatives of the University Police and Norman Fire Department revealed that three role call-training sessions had been conducted for the University Police personnel, but there had been no training provided to the Norman Fire Deps-tment personnel with emergency response responsibilitie The failure to provide the required training to all personnel is a violation of 10 CFR Part 50.54(q) (112/8901-05).
| | _ |
| | - |
| | .. . . |
| | ' |
| | .. .. |
| | . |
| | The university ofOklahoma m0-906 Aap, Room 112 " RADIATION SAFETY FOR LMj0RATORY PERSONNEL" r ,ven, Oldshome 73019 , |
| | , vis tots in accordance with Nuclear Regulatory Commission requirements (10CFR19), all individuals working in an area involving exposure to radiation or radioactive materials nnst be instructed in the health protection problems associated with exposure to such, in precautions or procedures to minimize exposure, and in the purpose and function of protective devices employed. |
|
| |
|
| Neither the applicable University Police nor the applicable Norman Fire Department personnel had received the required training during the January 26-30, 1987., NRC inspection; therefore, this is considered a repeat violatio No deviations were identifie . Physical Security The NRC inspector reviewed the implementation of the licensee's physical security program to determine agreement with commitments specified in the Physical Security Pla The NRC inspector noted that the Physical Security Plan had been updated on August 31, 1988, to reflect that the nuclear f uel had been shipped from the facility and.the console disabled and power remove The physical security program appeared to be implemented in accordance with the Physical Security Plan which clearly defined responsibilities and response requirements. Additionally, the required surveillance tests were being performe No violations or deviations were identifie . Nuclear Materials Safeauards The NRC inspector reviewed the licensee's special nuclear materials receipt, inventory, and accountability program to determine compliance with 10 CFR 70.53 and the conditions of the facility licens The accountability procedures and practices, records and material status reports were found to be implemented. As noted in paragraph 3, the licensee had transferred all reactor f uel to a Department of Energy approved recipient.
| | If you have not attended this training program in previous years at this Universi-ty and will be working with radioactive materials or radiation producing devices, you should plan to attend ONE of the sessions below. To assist in preparation of handouts etc., please call the Padiation Safety Office at S-1015 or send your name to NEL 111 and indicate which session you will attend. |
|
| |
|
| l No violations or deviations were identified.
| | The sessions will be held in the Seminar Room at the Northeast end of the second floor of NEL. Enter the north door (Asp St. side) of NEL and go to the end of the hallway at the top of the stairs. |
|
| |
|
| l l 11. Transportation (Fuel Shipments)
| | DATES - TIMES Monday, September 11, 1:15 pm - 4:45 pm Thursday, September 14, 1:15 pm - 4:45 pm Friday, September 15, 8:15 am - 11:45 am j i |
| l The NRC inspector reviewed the licensee's management-controlled program for radiological and nuclear safety in the receipt, packaging, and delivery to a carrier of radioactive materials to determine compliance with 10 CFR Part 71 and 49 CFR Parts 100-177.
| | ** ATTEND ONLY ONE SESSION ** I If you have any questions please call the Radiation Safety Office at 5-1015. |
|
| |
|
| E___________
| | COURSE SYLLABUS I. Introduction to Radioactivity and Terminology A. Radioactivity - definition, types and properties B. Units of measurement - quantities of radioactivity and radiation exposure C. Detection of Radiation - systems and applications II. Biological Riska from Ionizing Radiation . |
| | A. Possible health effects of exposure to radiation I 1. Prompt effects 2. Delayed effects 3. Genetic effects III. Radiological Safety A. Principles of protection from external exposure B. Principles of protection from contamination and internal expcisure C. Radiation emergency procedures for laboratory accidents D. Waste disposal E. The worker's right to know and options F. Prenatal radiation exposure G; The As _L,ow As Reasonably Achievable (ALARA) concept Instruction will include lecture, audiovisual presentations and demonstrations. |
|
| |
|
| . _ _ . .
| | _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ |
| _ _ _ _ - - | |
| , .
| |
| $ ,' / .h'
| |
|
| |
|
| The NRC. inspector noted from review of appropriate shipping manifests, checklists, radiation survey records, and material accountability forms for a fuel shipment on April 20, 1988, that all requirements had been me No violations or deviations were identifie . Exit Briefin The NRC inspe: tor met with the licensee representatives denoted in paragraph I of this report at the conclusion of the inspection on May 26, 1989. The NRC inspector summarized the scope and findings of the inspection. The licensee committed to counting contamination smears for alpha and beta, separately, for the final decommissioning plan radioactive contamination survey s
| | _ _ _ - _ - - - _ - |
| | . |
| | '' |
| | THE UNIVERSITY OF OKLAHOMA INTEROFFICE COMMUNICATION |
| | ' |
| ! | | ! |
| l l | | ' |
| l l- l l | | r, Users of Radioactive Material n.,, August 18, 1989 safety Training pr,. Radiation Safety 3 3,y,__{or New Personnel In-order to provide the NRC required safety training for personnel working ) |
| l
| | with radioactive material or working in an area invo).ving exposure to radi- l ction, we will again be conducting the program on " RADIATION SAFETY FOR |
| !
| | , |
| | LABORA'!ORY PERSONNEL." The sessions will be conducted in the Personnel j l Services Seminar Room, NEL 215, on l |
| | ' l Monday, September 11, 1:15 pm - 4:45 pm i i Thursday, September 14, 1:15 pm - 4: 45 pm Friday, September 15, 8:15 am - 11:45 pm |
| | ** ATTEND OttLY CEfE SESSICRI ** |
| | Enclosed is an announcement concerning the program for dissemination to y:ur personnel. Also enclosed is a listing of all the persons in your de-partment who have received the safety orientation in the past. The train-ing program is designed for your new personnel who have not previously at-tanded such at this institution. |
| | |
| | ' |
| | If you have personnel under your supervision who will be attending the training program, please give us a call at 5-1015 or write the name(s) |
| | below and return this memo as soon as possible to Radiation Safety NEL 112 (this will help us in preparing the appropriate number of handouts). Thank you for your cooperation. |
| | |
| | Lab Director Name: STEUC Lon G , |
| | Noamow Fac e b e f T. |
|
| |
|
| ( .. - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - - _ . ________-__ _______ _ ___ _ _
| | Individuals who will be attendino : |
| | i Name Social Security # Which session? |
| | . |
| | % |
| | 90-02S |
| | _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ |
| }} | | }} |
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20073B9901991-06-18018 June 1991 Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors ML19327B1471989-10-12012 October 1989 Advises That Matls Containing Residual Radioactivity Transferred for Disposal Via Low Level Waste Sys IR 05000112/19890011989-09-13013 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-112/89-01 ML20247B0711989-08-31031 August 1989 Responds to Violations Noted in Insp Rept 50-112/89-01 on 890525-26.Corrective Action:Training Program for Radiation Safety & Facility Emergency Procedures for Norman Fire Dept Being Initiated by Radiation Safety Ofc ML20246E0941989-08-18018 August 1989 Forwards Insp Rept 50-112/89-01 on 890525-26 & Notice of Violation.Recognizes That Receipt of Licensee possession- Only License Resulted in Greatly Reduced NRC Requirements Re Reactor Facility ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20244D2041989-06-0505 June 1989 Forwards Order Authorizing Dismantling of Facility & Disposition of Component Parts in Response to 881025 Application.Environ Assessment & Finding of No Significant Impact & Safety Evaluation Also Encl ML20235Z5661989-03-0909 March 1989 Forwards Addl Info Re Licensee Plan for Decommissioning,Per Request.Biographical Sketch of Author Included ML20205L2151988-10-25025 October 1988 Forwards Application for Amend to License R-53 to Approve Encl Physical Security Plan.W/O Encl ML20150D8641988-03-18018 March 1988 Informs of Relocation of NRR to Rockville,Md.Official Mailing Address Still Remains Same & Project Managers Have New Locations & Phone Numbers.Ts Michaels Still Lead Project Manager for Facility & a Adams Will Serve as Backup ML20196J3701988-03-0808 March 1988 Forwards Amend 12 to License R-53 & Safety Evaluation.Amend Authorizes Possession,But Not Operation,Of Univ of Ok AGN-211P Research Reactor & Includes Tech Spec Changes Requested in Application ML20149L6531988-02-18018 February 1988 Advises That Licensee in Process of Transferring Fuel Back to DOE Possession,Per Telcon.Work Should Be Completed by End of May,Depending on Speed of Paper Work ML20148K3151988-01-21021 January 1988 Forwards Revised Security Plan in Response to D Carlson Request ML20236S2451987-11-19019 November 1987 Forwards Updated Tech Specs for Ou Agn 211-P Reactor Per Conversation W/Nrc.Requests That Facility Be Exempt from 10CFR50.54 (R) Since No Critical Operations Will Be Allowed & Exempt from Maintaining Requalification Program ML20236F6621987-10-26026 October 1987 Informs That J Pellet Replacing R Cooley as Section Chief of Operator Licensing Section in Div of Reactor Safety, Effective 871025 IR 05000112/19870011987-09-0303 September 1987 Ack Receipt of 870414,0529 & 0720 Ltrs Informing NRC of Steps Taken to Correct Violtaions Noted in Insp Rept 50-112/87-01.Addl Info Re Violation a Provided in Adequate to Resolve Concerns,Per 870617 Telcon ML20237J5141987-07-20020 July 1987 Responds to Violation a Noted in Insp Rept 50-112/87-01. Updated Lab Survey Rept Showing LSC Efficiencies for H-3 & C-14 Encl Per Telcon W/Baer.Understands That Response to Violations B & C Acceptable ML20215C2591987-06-11011 June 1987 Advises That Standardization & Non-Power Reactor Project Directorate Now Under Div of Reactor Projects Iii,Iv & V & Special Projects,Ofc of NRR Due to Recent Organization of NRR ML20214W1981987-05-29029 May 1987 Responds to NRC Re Violations Noted in Insp Rept 50-112/87-01.Corrective Actions:Ltr from Norman Region Hosp Obtained & Sent w/ Which Indicates That Emergency Need Will Be Responded to ML20214H0441987-05-20020 May 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-112/87-01.Requests Addl Info Re Listed Violation from 870316 Notice of Violation ML20209D2621987-04-14014 April 1987 Responds to NRC Re Violations Noted in Insp Rept 50-112/87-01.Corrective Actions:Application for Mod of Tech Specs to Be Completed & Sent to NRC by 870901,including Request for Mod or Deletion of Emergency Plan ML20207S7041987-03-16016 March 1987 Forwards Insp Rept 50-112/87-01 on 870126-30 & Notice of Violation ML20202J1121986-04-0101 April 1986 Forwards Matls Balance Rept for Oct 1985 - Mar 1986 ML20210H9041986-03-27027 March 1986 Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactors & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address ML20136G3971985-08-12012 August 1985 Informs That 850516 Request for Amend of Requalification Training Program Unacceptable,Per 10CFR55,App a & Generic Ltr 83-12A.New Request Should Be Submitted Addressing Listed Required Conditions IR 05000112/19850011985-07-25025 July 1985 Forwards Safety Insp Rept 50-112/85-01 on 850430-0602.No Violations or Deviations Noted ML20100B4081984-11-30030 November 1984 Informs That Emergency Plan Fully Implemented,Emergency Procedures Written & Approved & Training Program W/Fire & Police Personnel Initiated ML20093P2001984-07-24024 July 1984 Ack Receipt of Ltr Approving Emergency Plan.Plan Implementation Begun.Requests Extension for Completion Until 841130 ML20082M7781983-12-0101 December 1983 Submits List of Errors Noted During Review of NUREG-0996. Errors Do Not Affect Conclusions Reached in SER ML20072G6171983-06-20020 June 1983 Forwards Revised SAR Update & Review, & Tech Specs for 20-yr Renewal of License R-53 ML20077D1391983-06-17017 June 1983 Advises That Univ Operating Under Approved Rev to Reactor Operator Requalification Program,Per NRC ML20072N0481983-05-27027 May 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/83-01.Corrective Actions:Check of Flow Rate for Water Purification Sys Procedure Reviewed for Relevance & Implementation ML20071H7871983-05-16016 May 1983 Informs of C Jensen Appointment as Director of Facility ML20079M2451983-02-17017 February 1983 Advises That C Jensen Has Been Appointed as Interim Director of Univ Nuclear Reactor ML20079L4081983-02-14014 February 1983 Advises That All Future Correspondence Re License R-53 Should Be Directed to D Egle ML20071C2061983-02-14014 February 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/82-01.Corrective Actions:Copies of Reactor Safety Committee (RCS) New Charter Will Be Forwarded to Region Iv.Rcs Audit Function Redefined ML20064F8811983-01-0404 January 1983 Forwards Revised Operator Requalification Program,To Be Substituted for Mar 1982 Submittal ML20070N4241982-12-15015 December 1982 Forwards Procedures to Suppl Responding to Notice of Violation for IE Insp Rept 50-112/82-01 ML20070N4171982-12-10010 December 1982 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/82-01.Corrective Actions:Change in Sprocket on Safety Rod Drive Will Be Treated as Unreviewed Safety Question & Requalification Program Will Be Revised ML20069M4301982-10-27027 October 1982 Submits Public Version of Status of Emergency Plan,Due 821103.Plan Submitted on 820420 Complies W/Requirements.No New Plan Need Be Developed or Submitted ML20067B5721982-10-11011 October 1982 Forwards Requalification Program for Univ of Ok,For Approval ML20054L3881982-06-16016 June 1982 Ltr to All Research & Test Reactor Licensees Requesting That Reg Guide 2.6 (for Comment) & ANSI/ANS-15.16 (Draft II Dtd 811129) Be Used to Meet Requirement of Final Amend to 10CFR50.54(r) Re Emergency Planning.Fr Notice Encl ML20051J8631982-05-0606 May 1982 Forwards Final Segment of SAR Required to Obtain Renewal of License R-53 ML20052D5851982-04-20020 April 1982 Forwards Public Version of Emergency Plan,In Support of 20-yr Renewal of License R-53 for AGN-211 P Reactor ML20042B8321982-03-28028 March 1982 Forwards Addl Info Re Application for 20-yr Renewal of License R-53 for AGN-211P Reactor ML20042C0581982-03-24024 March 1982 Forwards Eia Supporting Renewal of License R-53 ML20052G2631982-03-23023 March 1982 Forwards Requalification Program for Univ of Ok AGN-211P Reactor ML20049J3711982-03-12012 March 1982 Forwards Incomplete Application for 20-yr Renewal of License R-53.Remaining Matls to Be Submitted in 2 Wks.Security Plan Withheld (Ref 10CFR2.790) ML20040H4831982-01-0404 January 1982 Responds to NRC 811207 Ltr Re Violations Noted in IE Insp Rept 50-112/81-01.Corrective Actions:Clarified Procedure Requiring All Exploratory Changes in Sys Be Reviewed by Reactor Safety Committee Prior to Evaluation ML20009C7261981-06-15015 June 1981 Submits Annual Rept for Jul 1980-June 1981 for License R-53 1991-06-18
[Table view] Category:NRC TO EDUCATIONAL INSTITUTION
MONTHYEARIR 05000112/19890011989-09-13013 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-112/89-01 ML20246E0941989-08-18018 August 1989 Forwards Insp Rept 50-112/89-01 on 890525-26 & Notice of Violation.Recognizes That Receipt of Licensee possession- Only License Resulted in Greatly Reduced NRC Requirements Re Reactor Facility ML20244D2041989-06-0505 June 1989 Forwards Order Authorizing Dismantling of Facility & Disposition of Component Parts in Response to 881025 Application.Environ Assessment & Finding of No Significant Impact & Safety Evaluation Also Encl ML20196J3701988-03-0808 March 1988 Forwards Amend 12 to License R-53 & Safety Evaluation.Amend Authorizes Possession,But Not Operation,Of Univ of Ok AGN-211P Research Reactor & Includes Tech Spec Changes Requested in Application ML20236F6621987-10-26026 October 1987 Informs That J Pellet Replacing R Cooley as Section Chief of Operator Licensing Section in Div of Reactor Safety, Effective 871025 IR 05000112/19870011987-09-0303 September 1987 Ack Receipt of 870414,0529 & 0720 Ltrs Informing NRC of Steps Taken to Correct Violtaions Noted in Insp Rept 50-112/87-01.Addl Info Re Violation a Provided in Adequate to Resolve Concerns,Per 870617 Telcon ML20215C2591987-06-11011 June 1987 Advises That Standardization & Non-Power Reactor Project Directorate Now Under Div of Reactor Projects Iii,Iv & V & Special Projects,Ofc of NRR Due to Recent Organization of NRR ML20214H0441987-05-20020 May 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-112/87-01.Requests Addl Info Re Listed Violation from 870316 Notice of Violation ML20207S7041987-03-16016 March 1987 Forwards Insp Rept 50-112/87-01 on 870126-30 & Notice of Violation ML20210H9041986-03-27027 March 1986 Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactors & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address ML20136G3971985-08-12012 August 1985 Informs That 850516 Request for Amend of Requalification Training Program Unacceptable,Per 10CFR55,App a & Generic Ltr 83-12A.New Request Should Be Submitted Addressing Listed Required Conditions IR 05000112/19850011985-07-25025 July 1985 Forwards Safety Insp Rept 50-112/85-01 on 850430-0602.No Violations or Deviations Noted ML20054L3881982-06-16016 June 1982 Ltr to All Research & Test Reactor Licensees Requesting That Reg Guide 2.6 (for Comment) & ANSI/ANS-15.16 (Draft II Dtd 811129) Be Used to Meet Requirement of Final Amend to 10CFR50.54(r) Re Emergency Planning.Fr Notice Encl ML20148U1781981-02-17017 February 1981 Forwards Revised NRC Region 4 Organization Chart,Effective 810227 ML20137G4721971-06-23023 June 1971 Advises That Presence & Irradiation of Explosives in Reactor Must Be Evaluated Due to Potential for Damage to Reactor. Evaluation Requested Establishing Operating Restrictions,Max Quantity of Explosives Allowed in Facility & Form 1989-09-13
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARIR 05000112/19890011989-09-13013 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-112/89-01 ML20246E0941989-08-18018 August 1989 Forwards Insp Rept 50-112/89-01 on 890525-26 & Notice of Violation.Recognizes That Receipt of Licensee possession- Only License Resulted in Greatly Reduced NRC Requirements Re Reactor Facility ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20244D2041989-06-0505 June 1989 Forwards Order Authorizing Dismantling of Facility & Disposition of Component Parts in Response to 881025 Application.Environ Assessment & Finding of No Significant Impact & Safety Evaluation Also Encl ML20150D8641988-03-18018 March 1988 Informs of Relocation of NRR to Rockville,Md.Official Mailing Address Still Remains Same & Project Managers Have New Locations & Phone Numbers.Ts Michaels Still Lead Project Manager for Facility & a Adams Will Serve as Backup ML20196J3701988-03-0808 March 1988 Forwards Amend 12 to License R-53 & Safety Evaluation.Amend Authorizes Possession,But Not Operation,Of Univ of Ok AGN-211P Research Reactor & Includes Tech Spec Changes Requested in Application ML20236F6621987-10-26026 October 1987 Informs That J Pellet Replacing R Cooley as Section Chief of Operator Licensing Section in Div of Reactor Safety, Effective 871025 IR 05000112/19870011987-09-0303 September 1987 Ack Receipt of 870414,0529 & 0720 Ltrs Informing NRC of Steps Taken to Correct Violtaions Noted in Insp Rept 50-112/87-01.Addl Info Re Violation a Provided in Adequate to Resolve Concerns,Per 870617 Telcon ML20215C2591987-06-11011 June 1987 Advises That Standardization & Non-Power Reactor Project Directorate Now Under Div of Reactor Projects Iii,Iv & V & Special Projects,Ofc of NRR Due to Recent Organization of NRR ML20214H0441987-05-20020 May 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-112/87-01.Requests Addl Info Re Listed Violation from 870316 Notice of Violation ML20207S7041987-03-16016 March 1987 Forwards Insp Rept 50-112/87-01 on 870126-30 & Notice of Violation ML20210H9041986-03-27027 March 1986 Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactors & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address ML20136G3971985-08-12012 August 1985 Informs That 850516 Request for Amend of Requalification Training Program Unacceptable,Per 10CFR55,App a & Generic Ltr 83-12A.New Request Should Be Submitted Addressing Listed Required Conditions IR 05000112/19850011985-07-25025 July 1985 Forwards Safety Insp Rept 50-112/85-01 on 850430-0602.No Violations or Deviations Noted ML20054L3881982-06-16016 June 1982 Ltr to All Research & Test Reactor Licensees Requesting That Reg Guide 2.6 (for Comment) & ANSI/ANS-15.16 (Draft II Dtd 811129) Be Used to Meet Requirement of Final Amend to 10CFR50.54(r) Re Emergency Planning.Fr Notice Encl ML20148U1781981-02-17017 February 1981 Forwards Revised NRC Region 4 Organization Chart,Effective 810227 ML20149K1911980-05-0707 May 1980 Generic Ltr 80-38 to All Nonpower Reactor Licensees Re NPR Physical Protection Requirements.Summary of Certain NPR Physical Protection Requirements Encl & Should Aid in Determining Safeguards Requirements Applicable to Facility ML20137G4721971-06-23023 June 1971 Advises That Presence & Irradiation of Explosives in Reactor Must Be Evaluated Due to Potential for Damage to Reactor. Evaluation Requested Establishing Operating Restrictions,Max Quantity of Explosives Allowed in Facility & Form 1989-09-13
[Table view] |
Inspection Report - - 1989001 |
---|
|
|
Text
.__ - _ _
, ..
(%
.
-
- t W'i -
-
,
SEP il 3 !989'
..
.-In-Reply Refer To: .
_
Docket:. 50-112/89-01'.
i The-USiversity of Oklahoma
,LATTNi Dr. Davis M. Egle l Director,lAMNE
.J 865 Asp Ave., Room-212
. Norman,' Oklahoma 73019
,
Gentlemen:
Thank you for'your ' letter of. August 31, 1989, in' response to our letter and Hotice of. Violation dated August 18, 1989. We have reviewed your reply.and ifind it responsive to the' concerns raised in our Notice of Violation. We will-review the implementation of your corrective actions during'a future inspection-to determine that full compliance has been achieved and will be maintained.
Sincerely,
,r.
A. Bill Beach, Director Division of Radiation Safety and. Safeguards cc:
' The . University of Oklahoma ATTN: Dr. E. H. Klehr, Chairman Reactor Safety Committee
'865 Asp Avenue Norman,- Oklahoma 73019 bec to DMB (IE01)
bec:
R. Martin Inspector (s)
C:RPSB-DRSS T. Michaels, NRR Project Manager DRP Lisa Shea, RM/ALF .I RIV File MIS Coordinator RSTS Operator DRS l" B. Beach, DRSS C:FRPS l RPB-DRSS
'
(
RIV:FRPS C:FRPS , C:RPB D SS i LW11 born / sir RBaer x.BMurray beach T 9/p/89 9 /P/89 9 // F/89 9 / 17./ 8 9 i
L- 8909190289 890913 5 4
[ PDR ADOCK.05000112
/
u. . .. - - - - -
Z@k7 4
. _ _ _ _ - _ - - _ _ _ _ -
.
'
Jr 'f g r.y.vf 9'
d ,
,d#e _....,.Sh k e
-
--
, ibm
.n ,
'
coq p.
.>
3 _ ,
University of Ok[ahoma b
~~~
' SCHOOL oF AEROSPACE AND
.CECHANICAL ENGINEERING 86s Asp Avenue, Room 212 Norman, oklahoma 73019 o601 4
,
pos)325.s011 August 31,1989 Mr. A. Bill Beach, Director Division of Radiation Safety and Safeguards US Nuclear Regulatory Commission - Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington,TX 76011 d Re: Docket: 50-112/89-01
Dear Mr. Beach:
The following is presented in reply to the Notice of Violation for the 25-26 May 89 NRC inspection of the University of Oklahoma Operating License R-53.
A. Authority to Dismantle a Facility The University admits the facility was dismantled ahcI the fuel had been shipped off-site, butpnar to receipt of NRC approval of our submitted Dismantling and
. Decommissionmg Plan. It was our interpretation that since the reactor would not be ;
refueled nor operate again that we could undertake certain activities while personnel were available to do such. As noted by your inspector, these activities, although premature,were conducted in a were made as work progressed. pro?er manner and that simultaneous safet associated with the tank assembly have been retained on site for NRC inspection.
None of these materials will be released until NRC issues the termination order.
Only one item, the fine control rod, was found to contain any residual radioactivity
[ identified by gamma spectroscopy as Co-60: 4 mR/hr surface,0.1 mR/hr at one
,
meter). This item will be disposed of by Radiation Safety along with other low level radioactive waste from the University at an appioved low level radioactive waste disposal site. The dismantling and decommissioning plan was approved by NRC letter dated 5 June 89 and operations s ecified in this submission are presently being conductedin compliance in the plan the Radiation Safety Office.
B. Reactor Safety Committee Composition The University admits that for the period specified the composition of the Reactor Safety Committee was not in compliance with Technical Specification 6.2 as approved by Amendment No.12 to Facility License No. R-53. The fuel was shipped off-site on
' 20 April 86 and the reactor director left the University for other employment that summer. It was our erroneous impression that with the fuel and director gone that
..
7g 07-g-g % M Soe %erio SPP' u
. _ ____ -________ _ _
e
! *
.',, 2 August 29,1989
] M ..
compliance with the committee com osition requirement was no longer necessary.
The requirement for a Reactor Safe Committee was deleted from the new Technical Specifications approved b NRC letter dated 5 June 89.
C. Reactor Safety Committee Meetings ,
The University admits that subsequent to its 28 March 88 meeting, the Reactor Safety Committee did not meet semi-annually as required in Technical Specification 6.2.6.
As mentioned in paragraph B. above, it was our erroneous impression that with the fuel and the reactor director gone that meetings were not necessary and that the Radiation Safety Officer should proceed with the Dismantling / Decommissioning task.
' New Technical Specification 6.2 approved by NRC letter dated 5 June 89 eliminates the need for a Reactor Safety Committee as an administrative control.
D. Audits The University admits that audits required by Technical Specification 6.2.8.E were not performed subsequent to the final Reactor Safety Committee meeting of 28 March 88. The requirement for subsequent audits was deleted from the new Technical Specifications approved by NRC letter dated 5 June 1989.
E. Fmergency Response Training A trainin (program for radiation safety and facility emerg procedures for the Norman hire Department is being initiated by the Univers: Radiation Safety as part of the Umversity's NRC road License program.
Office (seewillAttachment This rogram be part o A)f training conducted on a continuing basis by the Ra Safe Office.
incerely, hph.
Davis M.Egle [
Director DME/rb Enc: Attachment A cc: Dean D.C. Crynes Dean G.B Walker Dr. Paul Skierkowski ,
j
-
l
!
- ------ -- _ _ _ --
-
- -_-
-) .
- & ;. x
,
.,q'; ,g.
- ;
Y unimity ofonwma ms -
ses Asp.nsom.112 Normen,Omahams 73010
- pos)as tots 123: August 1989 Mr. Steve Long:
Training officer.
_
Norman Fire Depart:nent
'411.E. Main-Norman, OK- 73071 Dear Mr. Long The Nuclear' Regulatory' Commission conducted an inspection of our !
-Nuclear' Reactor Facility on.25-26 May.1989. In conjunction with this ')
inspection they visited with you.concerning our Emergency Preparedness Plan.- It appears.that we have been deficient in coordinating-such Ltraining with the Norman. Fire Department.
Although the Nuclear Reactor Facility has been dismantled and the-fuel-chipped to the Department of. Energy, we.still maintain numerous.other labs which utilize radioactive materials.in research. Although none
,
.cf these are'of.the level'of'the reactor and require an Emergency Pre- l paredness' Plan, we do; maintain Emergency Procedures under our Nuclear '
Regulatory Consnission license for these activities. 'Since the Norman'
Fire Department.would'be the' responder.for'certain emergencies in these facilities it would be beneficial if we. coordinated training in
- radiation safety'and'the' facility emergency procedures.
'As'a start I would like to invite you..and any others you may chose to 1 attend our Radiation Safety for Laboratory Personnel training session.
- A syllabus for the program is attached. This program covers the ,
ibasics of radiation safety for lab personnel working'with radioactive
.
l
- materials and would also be applicable to personnel responding to an emergency. After this program is completed I would suggest that we meet to discuss further training and coordination in this area. )
Thank you for your-assistance in this matter and I look forward to working with you in this training need. Should you have any questions p please contact me at 325-1015.
sincerely, l
'
Paul Skierkowski, Ph.D.
Radiation Safety Officer ;
s l
!
!
. _ _ - _ . - _ - _ _ ._- _ _ - - _ _ _________ _ m
_
-
.. . .
'
.. ..
.
The university ofOklahoma m0-906 Aap, Room 112 " RADIATION SAFETY FOR LMj0RATORY PERSONNEL" r ,ven, Oldshome 73019 ,
, vis tots in accordance with Nuclear Regulatory Commission requirements (10CFR19), all individuals working in an area involving exposure to radiation or radioactive materials nnst be instructed in the health protection problems associated with exposure to such, in precautions or procedures to minimize exposure, and in the purpose and function of protective devices employed.
If you have not attended this training program in previous years at this Universi-ty and will be working with radioactive materials or radiation producing devices, you should plan to attend ONE of the sessions below. To assist in preparation of handouts etc., please call the Padiation Safety Office at S-1015 or send your name to NEL 111 and indicate which session you will attend.
The sessions will be held in the Seminar Room at the Northeast end of the second floor of NEL. Enter the north door (Asp St. side) of NEL and go to the end of the hallway at the top of the stairs.
DATES - TIMES Monday, September 11, 1:15 pm - 4:45 pm Thursday, September 14, 1:15 pm - 4:45 pm Friday, September 15, 8:15 am - 11:45 am j i
- ATTEND ONLY ONE SESSION ** I If you have any questions please call the Radiation Safety Office at 5-1015.
COURSE SYLLABUS I. Introduction to Radioactivity and Terminology A. Radioactivity - definition, types and properties B. Units of measurement - quantities of radioactivity and radiation exposure C. Detection of Radiation - systems and applications II. Biological Riska from Ionizing Radiation .
A. Possible health effects of exposure to radiation I 1. Prompt effects 2. Delayed effects 3. Genetic effects III. Radiological Safety A. Principles of protection from external exposure B. Principles of protection from contamination and internal expcisure C. Radiation emergency procedures for laboratory accidents D. Waste disposal E. The worker's right to know and options F. Prenatal radiation exposure G; The As _L,ow As Reasonably Achievable (ALARA) concept Instruction will include lecture, audiovisual presentations and demonstrations.
_ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ _ - _ - - - _ -
.
THE UNIVERSITY OF OKLAHOMA INTEROFFICE COMMUNICATION
'
!
'
r, Users of Radioactive Material n.,, August 18, 1989 safety Training pr,. Radiation Safety 3 3,y,__{or New Personnel In-order to provide the NRC required safety training for personnel working )
with radioactive material or working in an area invo).ving exposure to radi- l ction, we will again be conducting the program on " RADIATION SAFETY FOR
,
LABORA'!ORY PERSONNEL." The sessions will be conducted in the Personnel j l Services Seminar Room, NEL 215, on l
' l Monday, September 11, 1:15 pm - 4:45 pm i i Thursday, September 14, 1:15 pm - 4: 45 pm Friday, September 15, 8:15 am - 11:45 pm
- ATTEND OttLY CEfE SESSICRI **
Enclosed is an announcement concerning the program for dissemination to y:ur personnel. Also enclosed is a listing of all the persons in your de-partment who have received the safety orientation in the past. The train-ing program is designed for your new personnel who have not previously at-tanded such at this institution.
'
If you have personnel under your supervision who will be attending the training program, please give us a call at 5-1015 or write the name(s)
below and return this memo as soon as possible to Radiation Safety NEL 112 (this will help us in preparing the appropriate number of handouts). Thank you for your cooperation.
Lab Director Name: STEUC Lon G ,
Noamow Fac e b e f T.
Individuals who will be attendino :
i Name Social Security # Which session?
.
%
90-02S
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _