IR 05000112/1987001: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
Line 1: Line 1:
{{Adams
{{Adams
| number = ML20207S709
| number = ML20214H044
| issue date = 02/26/1987
| issue date = 05/20/1987
| title = Insp Rept 50-112/87-01 on 870126-30.Violations Noted:Failure to Maintain Records in Proper Units,Failure to Provide Emergency Planning Training & Failure to Maintain Ltrs of Agreement
| title = Ack Receipt of 870414 Ltr 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
| author name = Baer R, Murray B
| author name = Yandell L
| 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 = 50-112-87-01, 50-112-87-1, NUDOCS 8703200200
| document report number = NUDOCS 8705270256
| package number = ML20207S705
| document type = CORRESPONDENCE-LETTERS, NRC TO EDUCATIONAL INSTITUTION, OUTGOING CORRESPONDENCE
| document type = INSPECTION REPORT, NRC-GENERATED, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 4
| page count = 8
}}
}}


Line 19: Line 18:


=Text=
=Text=
{{#Wiki_filter:7 --
{{#Wiki_filter:r
  . ..
  [
APPENDIX C U.S. NUCLEAR REGULATORY COMMISSION REGION IV,
. .,
-
MAY' 2 01987 In Reply Refer-To:
~NRC Inspection Report: 50-112/87-01 License: R-53 Docket: .50-112 Licensee: University of Oklahoma 865 Asp Ave., Room 212 Norman, Oklahoma 73019 Facility Name: AGN-211P, Research Reactor (100W)
Docket: 50-112/87-01
      <
- The University of Oklahoma ATTN: -Dr. Davis M. Egle Director, AMNE 865 Asp Avenue, Room 212 Norman, Oklahoma 73019 Gentlemen:
Inspection At: University of Oklahoma, Norman, Oklahoma
-Thank you for your letter of April 14, 1987, in response to our letter and the attached Notice of Violation dated March 16, 1987. Your response was also discussed during a' telephone-conversation between Mr. Craig Jensen and Mr. Ron Baer of this-office on April 24, 1987. As a result of our review, we find that additional information is needed. Specifically, the response directed in Appendix A, " Notice of Violation," transmitted with our letter of March 16, 1987, requires that the University of Oklahoma provide a written statement or explanation in reply, for each violation regarding: (1) the reason for the violation if admitted, (2) the corrective steps which have been taken and'the results achieved, (3) the corrective steps which will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
 
Your letter of April 14, 1987, did not contain the required information for the violations. listed below:
Restatement of Violation A 10 CFR Part 20.401(b) requires that each licensee shall maintain records in the same units used in this part.
 
10 CFR Part 20.5 states that " radioactivity is commonly, and for purposes of the regulations in this part shall be, measured in terms of disintegrations per unit time or in curies." As described in 10 CFR Part 20.201(b), surveys are an evaluation of the radiation hazards incident to the production, i use, release, disposal, or presence of radioactive material or other sources of~ radiation under a specific set of conditions.
 
The NRC inspector determined on January 29, 1987, that surveys of the Nuclear Engineering Laboratory to determine radioactive contamination levels performed during the period January 1, 1985, through December 31,
~1986, were not recorded in terms of disintegrations per unit time or in
, curies.
 
-
-
Inspection Conducted: January 26-30, 198/  I Inspector:
f l V:FRPS C:FRPS C:RPSB
Rf E. 3aer, Radiation Specialist, Facilities 2/I Date '
'
      /
REBaer;df BMurray LAYande S/k/87 J /f /87 f /p /87 l
Radiological Protection Section-Approved: (llAdOl/l dAi(#1   8[b[b7 Date '
 
B. Murray, Chief,' Facilijties Radiological Protection Section Inspection Summary Inspection Conducted January 26-30, 1987 (Report 50-112/87-01)
8705270256 870520    1
Areas Inspected: Routine, unannounced inspection of the licensee's organization and management controls, operations and maintenance logs, records, operator requalification program, radiation protection, radioactivity releases, transportation, emergency planning, physical security plan, nuclear material safeguards, and an allegatio Results: Within the areas inspected, three violations were identified (failure to maintain records in proper units, paragraph 8; failure to provide emergency planning training, and failure to maintain letters of agreement, paragraph 13).
 
ADOCK 0500 gDR
 
_
,- , ,-
.The University of Oklahoma 2 Summary of' Licensee's Response to Violation'A The~ licensee acknowledges the requirements'of 10 CFR Part 20.401(b)
requiring licensee's to maintain records in specified units and that records for posting radiation fields [20,203(b) and (c)], airborne radioactivity concentrations [20.103], radiation levels in unrestricted areas [20.106], releases to the sanitary sewerage system [20.303], and survey swipes of packages [20.205] are being complied with. The licensee '
contends that neither the regulations nor any regulatory guide specifically specifies any units or action levels (standard) for lab swipes. Therefore,.in the absence of a standard, their-procedure .
. identifies the presence of contamination and sets an appropriate level for corrective action.
 
NRC Evaluation of Licensee's Response The licensee denies the apparent violation. However, the licensee's response implied that the violation did occur, but no reason is given for its occurrence. The licensee did not address corrective measures to be taken to prevent further violations and when full compliance will be achieved. The licensee has provided no basis for withdrawal of the violation; therefore, the violation remains as proposed.
 
Restatement of Violation B 10 CFR Part 50.54(q) requires that a licensee authorized to operate a research reactor shall follow and maintain in effect an emergency plan.
 
Your emergency plan requires the reactor staff to review the plan annually to ensure it was up-to-date.
 
The NRC inspector determined on January 29, 1987, that the letter of agreement with the Norman Municipal Hospital, which is contained in your plan, had expired on October 31, 1984.
 
Summary of Licensee's Response to Violation B The licensee acknowledged that the letter of agreement was out-of-date, but contends that the emergency plan was not implemented is an incorrect observation. It is the licensee's position that there is much more to the emergency plan-than the letter update and they believe the emergency plan has been implemented. The licensee also stated the apparent violation should be an item of noncompliance, not a violation.
 
The licensee's response included an updated letter of agreement and stated that they are presently in compliance with the regulations.


8703200200 870316 2 PDR ADOCK 0500
NRC Evaluation of Licensee's Response The licensee neither admits nor denies the apparent violation. It is implicit in the licensee's response that the violation did occur. No reason is given for its occurrence. The response states that the letter


_ __
T
__--_--__-z---.- _ _ _ __----- _ __ _ -- _-- _ - _ __
  . . .
:. . .-
The University of Oklahoma 3 of agreement was out-of-date and an updated letter was attached. The licensee did not address corrective measures to be taken to prevent further violations and when full compliance will be achieved. The updated letter from the hospital does not contain an expiration date. The.
      '.
i L
DETAILS l~ Persons Contacted
  * M. Egle, Director, School of Aerospace, Mechanical and Nuclear Engineering
*C. M. Jensen, Reactor Director and Senior Reactor Operator
*P. Skierkowski, Radiation Safety Officer M. C. Smith, Radiation Safety Technician K. A. Messana, Safety Inspector, Department of Public Safety D. McGhee, Captain, Norman Fire Department The NRC inspector also. interviewed other licensee and City of Norman employees including police officers and fireme * Denotes those present during the exit interview on January 30, 198 . Status of Facility The AGN-211P reactor was operated approximately 40 times between January 11, 1985, and April 24, 1986. The reactor has not been operated since April 24, 1986. The licensee no longer offers courses of instruction in the School of Nuclear Engineering or performs research in nuclear technology which would require the operation of the reactor. The licensee has discussed with the NRC procedures for "mothballing" the reacto . Organization and Management Control The NRC inspector reviewed the organization and management controls to determine compliance with Technical Specification (TS) The current organization was verified to be consistent with TS Figure 4,
" Administrative Organization of University of Oklahoma Reactor AGN 211P"-
except for the positions of Reactor Supervisor and Reactor Staff. The TS allows the Reactor Director to also serve as the Reactor Supervisor. The status of licensed operators, membership and meetings or the Reactor Safety Committee (RSC), and other matters concerning supervision of the reactor facility were examined. The NRC inspector noted that the position of Reactor Director had been filled by the only qualified senior' reactor operator presently on campu The NRC inspector reviewed the minutes of meetings conducted by the RSC and verified that the committee had met quarterly since thelprevious inspection and reviewed matters related to the reactor. It was verified that records reflected attendance by designated committee member The following items were routinely reviewed by the committee:
  . _ _ _ - _ _ - _ _ - - _ _ _ _ _ - _ _


    -  -
licensee stated that the apparent violation should be an item of noncompliance, not a violation. An item of noncompliance is a violation; therefore, the violation remains as proposed.
      - .
-. ,
  ,  ,
    ,
f
      -  4
. . . . ,
  % v    *
      '  N 3-
; ,     ,
        -
~.      .
Reactor Surveillance. Logs  *
  ~
    ' Facilities Manual .
>.  -
    . Fuel Element _ Inspection and Inventory
  '
Reactor Maintenance Log-Requalification Program-Physical. Security Pla Emergency Plan . .
Reactor Operations and Sample-Irradiation Logs
. <-
  -
Reactor; Experiments
  ,
No violations'or' deviations were identifie ?_  14; Operation and Maint$ nance' Logs
    ~
  .The NRC. inspector reviewed the following logs for the period January 1,
=
  .1985, through January 27, 1987, to determine compliance with'TS 3.1, 3.2,
  !3.3,3.4,4.2,-o.21(g),anoo.21(n).


~  ~
Restatement of Violation C 10 CFR Part 50.54(q) requires that a licensee authorized to operate a research reactor shall follow and maintain in effect an Emergency Plan.
i ~~
 
!
Section 10.1 of your Emergency Preparedness Plan states that individuals with emergency response responsibilities such as the University Police and Norman Fire Department shall be trained on an annual basis in radiation safety and the facility emergency procedures.
    : Reactor Operations Log Reactor Maintenance Log-All maintenance and~ operations activities appeared to have been conducted
 
      ~
The NRC inspector determined on January 29, 1987, that training in radiation safety and the facility emergency procedures was not being received by all individuals from the University Police and Norman Fire Department who would respond to an emergency at the facility.
1,
' '
in.a manner consistent 1with the TS requirements and administrative
{  ' procedures.


I No'violationshar deviations were identified.
Summary of Licensee's Response to Violation C The licensee stated that the university radiation safety office conducts annual training for police and fire personnel. The persons that attend are generally the higher grade officers with training responsibility within their own departments. The licensee does not have jurisdiction over these departments and feel they have completed their obligation to the emergency plan. The licensee's emergency response procedure requires that a knowledgeable and trained individual is called and responds during an emergency. The reactor facility is in the process of being mothballed and the licensee plans to request that the emergency plan be modified or deleted.


; Procedures e  EThe NRC inspector reviewed operating and surveillance procedures to
NRC Evaluation of Licensee's Response The licensee neither admits nor denies the apparent violation. The licensee does not propose any corrective action to ensure that support personnel are adequately trained to respond in an emergency nor action to prevent further violations. Therefore, the violation remains as proposed.
,  . determine compliance with the requirements of TS 3.4, 4.1, 4.2,-and 6.12.


L'-  The reactor operations manual contained procedures for:
. _ _ _ _ . .__ _ _ _ _ _ _ _ _ _ _ . _ __ _ _. _ _ . _ _ _ _ _ _ _ _ _ _- _.
i
  *
    " Normal Startup, Operation and Shutdown of the AGN-211 Reactor
  *
Reactor Startup,-Operation and Shutdown L'og
  *
;    Completion of the-Irradiation Request Form
  *
Experiment Request
  '*'
(    iProcedure for Core Rearrangement
;
L-
,
  .The surveillance activities log contained the procedures and logs for:
  *
I    Low Water Level Switch Interlock Test
  *
Temperatcre Interlock ~
  *
ll    Circulation Pump Interlock
  *' ' Water Conductivity-Meter Calibration i
  *'
l    Air-Water Monitor. Adjustment
  *
High Voltage'DC: Power Supplies Calibration
  ~
[  *
!  ~
  , *-
Low Power and Period Meter Calibration
!    Linear Power Channel Calibration
'  *
Neutronic Power Calibration l
l-i t . ,
- .
S  i


  . . . .
  .. - _ _ - - _ _ - - _ - - _ _ _ . - _ _ _ _ _ _ _ _
. .. .
. . .
. . .
The University of Oklahoma      4 Please provide the supplemental information within 20 days of the date of this letter.
Sincerely, ORIGINAL SIGNED BY:
Lawrence A. Yandell, Chief Radiological Protection and Safeguards Branch cc w/ enclosures:
The University of Oklahoma ATTN: Dr. E. H. Klehr, Chairman Reactor Safety Committee 865 Asp Avenue Nerman, Oklahoma 73019 The University of Oklahoma ATTN: Dr. C. Jensen, Reactor Director AMNE 865 Asp Avenue Norman, Oklahone 73019 bcc to DMB (IE01)
bcc dist, by RIV:
RPB      E. H. Johnson, DRSP RSB      RPSB RSTS Operator      MIS System R. D. Martin, RA    RIV File R. E. Baer      H. N. Berkow, NRR B. Murray      L. A. Yandell R. L. Bangart      R. E. Hall M. E. Emerson
- _ _ - - - _ - - _ _ _ - . _ _ - _ _ . _ _ _ - - - _ _ ____ _-_______-__ ____ ____ ___ _ _ _ _ - _ _ _ _ - _ _ _ _ - _ _ - - _ _    - _ - -
4 .
. .
.      -,
''
.      m, @@ Mll.
T/re    plE2M LL University ofOftfahoma    }j SCHOOL OF AEROSPACE, MECHANICAL ANO NUCLEAR ENGINEERING 865 Asp Avenue, Room 212 Norman. Oklahoma 73019 (405) 325 5011 April 14, 1987 Mr. J.E. Gagliardo, Chief Reactor Projects Branch USNRC - Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011 Docket: 50-112/87-01 License: R-53 O
==Dear Mr. Gagliardo:==
The following letter is in reply to the inspection of 'fr. R.E. Baer and _
  .
  .
the notice of violation sent by your office dated March 16, 1987.


Safety and Control Rod Surveillance
I want to make some general observations concerning the inspection and the discrepancies that were found. I have been involved with at least 5 inspections of AGN type reactors and no inspector or set of inspectors ever spent more than 2 days at the f acility. Especially one for which the last inspection showed no items of non-compliance, no violations, had not operated during the 10 month period prior to the inspection, sud whose total operating time during the two year period between it.spections was less than the time spent by the inspector at the f acility.
  -
Emergency Evaluation Horn Test Security Alarm System Test The NRC inspector verified that limits regarding excess reactivity, control and safety rod worths, scram capabilities, and safety systems were not exceeded. The records of surveillance test results did not indicate any unusual condition No violations or deviations were identifie . Records The NRC inspector reviewed the licensee's records 'for ' reactor operations, reactor component changes /replecement, and calibrations. The licensee had replaced the four control rod drive motors in .lulv 1985, in acenrdance  ,
with an. approved procedure. The licensee had not made any facility modifications during the inspection perio No violations or deviations were identifie . Operator Requalification Program The NRC inspector reviewed the licensee's reactor operator requalification training program for compliance with 10 CFR.Part 55, Appendix A. The NRC inspector reviewed training documents for the currently licensed operator and previously licensed individuals to determine agreement with the requalification program approved by the NRC on February 23, 193 The NRC inspector noted the last training session was held on April 25, 1986, at which time the three licensed reactor operators were in attendance. Since April 25, 1986, the 1icensee has lost the services of two of these reactor operator Records indicate the reactor was last operated on April 24, 198 No violations or deviations were identifie . Radiation Protection 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, and 20.409 and 50.54(q).


The NRC inspector reviewed records, interviewed personnel, made observations, and performed independent survey CFR Part 20.401(b) requires that each licensee shall maintain records in the same units used in this part, showing the results of surveys required by 20.201(b), . . . ."  10 CFR Part 20.5(a) states that h si -
The second item that concerns me is the way in which the region of fice has conducted its evaluation of the report by Mr. Baer. At his exit interview, Mr. Baer indicated that he considered your violation A to be a violation, which we disagree with. while your violations B and C he considered
    .
to be discrepancies or items of non-compliance, with.which I concurred. With ,
that in mind, we set out to correct those deficiences that he found. Ihe i
,
decision to upgrade those items to violations was not _ warranted and I believe
'
to be incorrect.


  . . .
The following are specific replies to the list of violations:
A. As stated in the Notice of Violation, it is acknowledged that 10CFR Part 20.401(b) requires that "the Licensee shall maintain records in the same units used in this part, showing the results of surveys required by $20.201(b)."
 
j  $20.201(a) also states that "when appropriate (our emphasis) such
, evaluation includes a physical survey of the location of materials and l
'
equipment, and measurements of levels of radiation or concentration of radioactive material present."
 
%
    ()
SP
 
_. _- - --  .-. - _ - - . ~ . _ . . .
. ;, .
  *
  .-
e        ,
'
M April 14, 1987
,
Page Two
        <
  $20.201(b)(2) requires that each license make surveys as are reasonable under the circumstances to evaluate the extent of radiation hazards that may be present.


radioactivity is commonly, and for purposes of the regulations in this part shall be, measured in terms of disintegrations per unit time or in curie The NRC inspector reviewed radiation and contamination survey records of surveys performed to satisfy the requirements of 10 CFR Part 20.201(b),
In keeping with our commitment to ALARA, this licensee conducts very
during the period January 1,1985, through December 31, 1986, in rooms 106 and 107 of the Nuclear Engineering Laboratory (NEL) building. The NRC inspector determined that smear surveys taken to detect removable contamination were recorded in counts per minute. It was also noted that the licensee's procedures did not include a method for converting counts per minute into disintegrations per minut The NRC inspector stated that failure to maintain records in the same units used in 10 CFR Part 20.5 was considered an apparent violation of 10 CFR Part 20.401(b). (112/8701-01)
;. detailed surveys of laboratories. These " surveys" incicie, as appropriate, i  either measurements of radiation fields in mR/hr using calibrated survey i meters and/or swipe tests to determine the presence of radioactive j  contamination.
The NRC inspector reviewed the course outline, lesson plans, and viewed video tapes of the training program, " Radiation Safety for Laboratory
  , Personnel." The NRC inspector verified that individuals were receiving the training required in-10 CFR Part 19.12 and recommended by Regulatory Guide 8.1 . Radioactive Releases The licensee does not maintain a detailed environmental surveillance program (e.g. collection and analysis of water, soil, and vegetation samples). There are no specific license requirements that such a program be maintaine A licensee representative stated that no liquid effluent releasas have been made since the last inspection. The licensee's operation records indicate that gaseous releases are within 10 CFR Part 20 limit No violations or deviations were identifie . Transportation (Fuel Shipments)
The NRC inspector verified that there had been no fuel shipments since the previous operational inspectio No violations or deviations were identifie . Nuclear Materials Safeguards The NRC inspector reviewed the nuclear materials inventory program to determine compliance with 10 CFR Part 70.53. The NRC inspector reviewed the accountability procedures and practices, records and material status report The procedures, practices, and records were found to be well implemented. Responsibilities and response requirements were defined clearly and understood, and appropriate test procedures were being used.


m
A description of our procedure for swipe tests may be of value in  '
'
understanding our position. To determine the presence of radioactive
,  contamination.:which,would not produce a radiation field, i.e. an mR/hr field that could be detected in an area survey, .we take "Q Tip" swipes of physical
:  locations such as bench tops, sinks, floors, doors, etc. These swipes are I c- analysed in a liquid scintillation counter along with standards and background samples. The standards are used to verify instrument performance. The policy


in evaluating the swipe results (as. printed out by the instrument in cpe) is  -
  -
  -
]-.: .
that a sample giving a count rate of pwice background or greater requires
;  attention, i.e. decontamination. It is our premise that if the standards
;  verify efficiency performance for the instrument, a comparison of sample and i  background eps values is a valid indication of the presence or absence of radioactive contamination.
 
~
!
l 10CRF20 is specific (in units of mR/hr, uCi or dpa) for posting of i
radiation fields [20.203 (b) and (c)], determining concentrations of radioactive materials in air in restricted areas [20.103], permissible levels of radiation in unrestricted areas [20.106], releases of licensed material to l
a sanitary sewerage system [20.303] and survey swipes of received packages of licensed materials [20.205]. Our systems comply, with these requirements -
including compliance as to units of radiation measurement.


The licensee had not received or shipped any radioactive materials s_ince
However, neither 10CFR nor any Regulartory Guide detail specifics for lab swipes in any units as to " action levels." Contrast this, for example, with 20.205(b)(2) which specifies the limit of removable contamination in
  -
    ,,
the previous inspectio No violations or deviations were identifie . Physical Security Plan The NRC inspector reviewed the implementation of the licensee's physical security program through visual examinations, review of records, and
microcuries per 100 square centimeter of package surf ace. In other words  , if an absolute radiation unit standard (dpa or uCi, etc.) exists, then such conversion would be appropriate.
~ discussions with appropriate faculty and campus security, personnel. The review indicated that the physical security plan was being implemented, responsibilities and response requirements were defined clearly and understood, and the required tests were being performe No violations or deviations were identified.


,   .
It is oor contention that, in the absence of a standard, our procedure, as previously stated, identifies the presence of contamination and sets an appropriate level for corrective action. And the accuracy of such action is verified by analyzing standards along with the test samples, as previously    ,
1 Emergency Planning
described. To convert from cpu to dpm or uCi would be a meaningless (and in   '
.The NRC inspector reviewed the emergency preparedness program to determine agreement with commitments made in the Emergency Preparedness Pla The licensee fully implemented,the Emergency Preparedness Plan in November 1984 and the emergency notification list was updated on March 7, 198 CFR Part 50.54(q) requires that a licensee authorized to operate a research reactor shall follow and maintain in effect an' emergency pla Section 10.4, of the Emergency Preparedness Plan states, '.'The' Emergency Plan shall be revised and updated as required based on drill results or changes in the. facility and shall be reviewed annually by the reactor as required based on drill results or changes in the facility and shall be reviewed annually by the reactor staff to ensure the plan is adequate and up to date." Section 3.1 addresses assistance from offsite organizations and states " Written agreements with-these organizations are included in Appendix A to this plan."
consideration of the large number of samples we take, a non-productive and very time consuming) task which would not give any better indication of the presence of contamination nor give a radiation unit to compare to a standard since a standard does not exist.


The NRC inspector determined on January 28, 1987, that the letter of agreement with the Norman Municipal Hospital dated November 15, 1983, expired on October 1, 1984. The NRC inspector stated that failure to review and update the letter of-agreement with the Norman Municipal-Hospital was an apparent violation of requirements of 10 CFR Part 50.54(q). (112/8701-02)
. _ _ _ , _ _ _ _ _ . _ . _ . _ _ _ _ _ _ . _ _ _ _ _ - _ _ _ _ _ _ _ . _ _
Section 10.1, of the Emergency Preparedness Plan addresses training that will be provided to individuals with emergency response-responsibilities and states that the University Police and Norman Fire Department shall be trained on an annual basis in radiation safety and NEL facility emergency procedure _
    -
rc  +
 
    ,
  - . ._ . . - _ _ . . . .-   _ _ _ _ ._ __
,
,_.S.
    - +
 
# .: . .
. :. . '
  >
.
w .
  ...
t 7-
: . . ,
      .
''
     '
M April 14, 1987
  .The NRC inspector reviewed the video tape prepared by the licensee which
.Page Three     .
  : addresses the facility emergency procedures. The NRC inspector also-
        ~
  '
' '
q discussed with representatives of the University _ Police and the Norman
We therefore do not believe, we are in violation and request that you
      '
,
Fire Department the-training being received. The NRC inspector determined ~
~ reexamine our procedure of lab survey / swipe methods to determine whether or
on January 29,.1987 that training in radiation safety and the NEL facility emergency procedures were not being received by all individuals from the University Police and Norman Fire Department who would respond to an emergency at the NEL facility. The NRC inspector discussed with licensee representatives the training _ requirements contained in the Emergency s Preparedness Pla The licensee stated that training.had been provided to selected individuals in the' police and fire departments. However, other individuals who might be-required to respond to emergenc situations had not received the required training. The failure to provide the required training to all personnel is an apparent violation-of-10 CFR Part 50.54(q). (112/8701-03)
; not ,it is in fact ameting the intent of the regulations. Should reexamination result in affirmation of your previous position we .would request that you
^
; establish;a regulatory standard so we_ will be able to set ~ action guidelines in   ,
14. - dllegation (4-86-A-109)
response to the results._we will obtain by performing the conversions you would require.
The NRC h'ad received a copy- of the Oklahoma Observer newspaper article from the' licensee which' had alleged that personnel working near the
 
'
,
University of Oklahoma reactor had: (a) received radiation overexposures during the past 10-20 years, (b) radiation exposures in adjacent rooms
,
,
were above the regulatory limits, and (c) the reactor staff failed to lock -
We appeal this violation and feel that we are in compliance at this
a room directly above the reactor while the reactor was in _ operation.
<
time.


''
;
~
B. Although the letter was out of date, your contention that the emergency
The NRC inspector reviewed selected reports, radiation survey records',
[ plan was not implemented is an incorrect observation. There is much more to the emergency plan than the letter update and we feel the emergency plan has
, environmental radiation dosimeter results, person'el n radiation exposure
. been implemented and that this should be an item of non-compliance not a
: histories, and reactor operation logs for the period' July 1971 through December 1986:     #
  , violation.
p Allegation, Part (a)    , I
 
,  The NRC inspector's review of radiation exposure histories and li  environmental radiation dosimeter results indicated the. highest recorded exposure was less than 750 millirem / year for personnel
An updated letter is attached and_ we are in compliance at this time. _
  - C. The Radiation Safety Office has annually conducted training for police and fire personnel and the University Safety office participates in the annual i and most monthly tests of the evacuation system. The persons that attend are generally the higher grade officers .with training responsibility.within their own departments. The reactor facility and the Radiation Safety office have also produced and distributed a video explaining the precautions and problems j. that any be encountered at the facility during an emergency. Wh have also
: extended our services in the training of these personnel. We feel that since we have no jurisdiction over these departments that.we have completed our i
obligation to the emergency plan.
 
Since it is obviously impossible to guarantee that every person is j trained, even if we had compulsory means to do so, the emergency response i procedures detail that some person from the emergency call list must be i
contacted. This is to insure that a knowledgeable and trained individual is
'
'
*
at' the site during an emergency. In addition to the person from the reactor staff, the procedure details that the Radiation Safety Office must be notified. This again is an attempt to insure that a trained individual is present during any eme rgency.
assigned to wear radiation dosimetry, and less than 120 millirem / year for areas monitored by environmental radiation dosimeters. The NRC inspector was not able to substantiate this portion of the allegatio Allegation, Part (b)
 
The AGN-211P reactor is located below grade level in the NEL building. The NRC inspector's review of facility records indicated that rooms adjacent to the reactor facility did not increase in radiation levels as a result of reactor operations. The NRC inspector was not able to substantiate this portion of the allegatio e
Although we do not feel we are in non-compliance or violation, this item will be corrected. As was stated to the inspector and discussed previously with NRC of ficials in Region IV and Washington D.C.,  the reactor facility is the process of being mothballed, hence, the reason it has not been operated in over a year. The application for modification of the technical specifications will be completed and sent to the NRC by September 1,1987. As part of that application, we will request that the emergency plan also be modified or deleted, deleting the requirement for this training. In the interim, the fuel has been removed and is secured in the fuel storage facility where it will be kept during the mothball period.
_
 
  .
.- - - - . -.- - _ - - - - -_- - - .-.-. - ..--.
    ,. v- - - -     -
 
y    s - q- ,
e ' '. . . *
m
. .
        ,
  .
s, s93  A
M April 14, 1987
                  .c
       *
.::*. , 'a .     ;-
Page Four We..will be in full compliance when the NRC issues new technical
          .\. ,' ,_
       -
            .y
specifications for the mothballed reactor.
            *: ) ;;-  ,  ~, ~
 
  ;u y'       .: . , ~        ~
If you have any questions concerning the above, please contact me at (405) 325-1754.
  . ] ; ),;r       a  ,k        . \:
        .v  [t'' '
s y*
G }g;&,_j  L { i;
  ~
        '
  }
        '
8  '


            -
Sincerley y rs,
                  ,,
    .
o -r [ ,>
    %
Craig .J sen React r Di ctor cc: Davis M. Egle, Director, ANNE v
CMJ/sj b
    .
      -.
.
Attachment e


  -
i E
i s-                /
;
        (
i l
        . , ,        ,
!
/> $      y
l
          '
!
          . t _ '
l
Q  '
,
hM    Allegation, Part-(c)V S \:    h.'    d, , s
w,- **'H* *
< .
        , ; \  :)      \y .
                  -
t    The licensee had includsd 'in th- reactor startup, . operation,/anh '        '
shutdownlog'acheckoffline$em"storageroom(NEL-214) locked"and
  .y
  . the reactor ope *ator had the oaly key which allows access irito .this
'7- -
  -
room The NRC'(inspcctor's,y(view of reactor logs . indicated tLe s
storige room.hid been lock!d prior to reactor operations. The NRC          r inspe'ctor was' jat able to Yubstantiate this portjoi of the allegatio Q,
      ,
3.,    s .s :! ;.
              ,
e j'      i-15~. Exit Interview    v


                    ''
          , ;y,      ,.
                  (e
       ,
       ,
          '
*
..,; -
  .
  .
,
 
y  1  e      .
  ?
    -The NRC inspector met with licensee representatives at the conclusb n ofs, '          (
  '(q
  -
  -
the inspection on January 30, 1987. The' NRC inspector' summarized ,the          3 }:
      ._
scope and findings of the inspectio s  A ,  4
NORMAN REGIONALHOSPITAL
    - ..    $x  s
      .
'
April 7, 1987   -
        .), '
Mr. Craig Jensen University of Oklahoma 865 Asp, Room 212 Norman, Oklahoma 73019
q
: Re: Services and use of Norman Regional Hospital facilities in the event of a radiological incident at the University of Oklahoma.
            - '  '
 
              ,
o-
K .
 
u'\  x-
==Dear Mr. Jensen:==
      ~
      ,
          '' !g~
ll    ;t      c      ,
          '      ~
,            j      'n
;
-
-
'
By this letter, Norman Regio'nal Hospital agrees to provide emergency
            '4    .<
-
                "
care and other necessary services to the University of Oklahoma in the event of the implementation of the " UNIVERSITY OF OKLABONA RADIO 1DGICAL EMERGENCY PREPAREDNESS PLAN". The emergency care specific to a radia-tion disaster will be provided in accordance with Normen Regional
                  --(
-
      %            v w j ,
Hospital's radiation disaster plan, and in accordance with our regular Emergency Department services.
y TE      '
      . i    s- ( i
      [\ \      :
cg            k 4 Yjg- U n
s ,,\    y
      ,o % ,
W
          \\ .
        \
b      '\J
                  '
                  '
'
,        \      j    )
%                t    !.
^


.'
i
c
!
,
This agreement will be effective issuediately and remain in force as long l as the parties are in agreement. In the event Norman Regional Hospital
s,
!
  [. ..
desires to terminate this agreement, a 60 day written notification will I be provided to the University of Oklahoma.
    '
 
it ,     ,
Sincere 1 ,
; .
 
a           ,
  '
P ,
M l' ay
    ,i ,
'[CraigW.
Jl  t c( .g  s ,; ,  <    ,
 
s
, Admini t stor ones
  ,-  ., ,
  .
e  4
                -
                    ,
            ,
      '% g'     i  i f
s
      ,
        ,
              '
e t
    ,'         .
                  '
    \    -    ,
x
                  . -
s


#
J CWJ: dig ec: Marge Rosenfelt Bruce Smith
i 1' 4 j, _ v  l  s s* s  c  1 T  'I  ,          T
       <
                  ' \
  *
          -
  . .
       '
y          %
    , - --, . ,  -
            ,, ...,-m  . - - , .  - , . - m
}}
}}

Revision as of 12:06, 19 January 2021

Ack Receipt of 870414 Ltr 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
ML20214H044
Person / Time
Site: 05000112
Issue date: 05/20/1987
From: Yandell L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Egle D
OKLAHOMA, UNIV. OF, NORMAN, OK
References
NUDOCS 8705270256
Download: ML20214H044 (4)


Text

r

[

. .,

MAY' 2 01987 In Reply Refer-To:

Docket: 50-112/87-01

- The University of Oklahoma ATTN: -Dr. Davis M. Egle Director, AMNE 865 Asp Avenue, Room 212 Norman, Oklahoma 73019 Gentlemen:

-Thank you for your letter of April 14, 1987, in response to our letter and the attached Notice of Violation dated March 16, 1987. Your response was also discussed during a' telephone-conversation between Mr. Craig Jensen and Mr. Ron Baer of this-office on April 24, 1987. As a result of our review, we find that additional information is needed. Specifically, the response directed in Appendix A, " Notice of Violation," transmitted with our letter of March 16, 1987, requires that the University of Oklahoma provide a written statement or explanation in reply, for each violation regarding: (1) the reason for the violation if admitted, (2) the corrective steps which have been taken and'the results achieved, (3) the corrective steps which will be taken to avoid further violations, and (4) the date when full compliance will be achieved.

Your letter of April 14, 1987, did not contain the required information for the violations. listed below:

Restatement of Violation A 10 CFR Part 20.401(b) requires that each licensee shall maintain records in the same units used in this part.

10 CFR Part 20.5 states that " radioactivity is commonly, and for purposes of the regulations in this part shall be, measured in terms of disintegrations per unit time or in curies." As described in 10 CFR Part 20.201(b), surveys are an evaluation of the radiation hazards incident to the production, i use, release, disposal, or presence of radioactive material or other sources of~ radiation under a specific set of conditions.

The NRC inspector determined on January 29, 1987, that surveys of the Nuclear Engineering Laboratory to determine radioactive contamination levels performed during the period January 1, 1985, through December 31,

~1986, were not recorded in terms of disintegrations per unit time or in

, curies.

-

f l V:FRPS C:FRPS C:RPSB

'

REBaer;df BMurray LAYande S/k/87 J /f /87 f /p /87 l

8705270256 870520 1

ADOCK 0500 gDR

_

,- , ,-

.The University of Oklahoma 2 Summary of' Licensee's Response to Violation'A The~ licensee acknowledges the requirements'of 10 CFR Part 20.401(b)

requiring licensee's to maintain records in specified units and that records for posting radiation fields [20,203(b) and (c)], airborne radioactivity concentrations [20.103], radiation levels in unrestricted areas [20.106], releases to the sanitary sewerage system [20.303], and survey swipes of packages [20.205] are being complied with. The licensee '

contends that neither the regulations nor any regulatory guide specifically specifies any units or action levels (standard) for lab swipes. Therefore,.in the absence of a standard, their-procedure .

. identifies the presence of contamination and sets an appropriate level for corrective action.

NRC Evaluation of Licensee's Response The licensee denies the apparent violation. However, the licensee's response implied that the violation did occur, but no reason is given for its occurrence. The licensee did not address corrective measures to be taken to prevent further violations and when full compliance will be achieved. The licensee has provided no basis for withdrawal of the violation; therefore, the violation remains as proposed.

Restatement of Violation B 10 CFR Part 50.54(q) requires that a licensee authorized to operate a research reactor shall follow and maintain in effect an emergency plan.

Your emergency plan requires the reactor staff to review the plan annually to ensure it was up-to-date.

The NRC inspector determined on January 29, 1987, that the letter of agreement with the Norman Municipal Hospital, which is contained in your plan, had expired on October 31, 1984.

Summary of Licensee's Response to Violation B The licensee acknowledged that the letter of agreement was out-of-date, but contends that the emergency plan was not implemented is an incorrect observation. It is the licensee's position that there is much more to the emergency plan-than the letter update and they believe the emergency plan has been implemented. The licensee also stated the apparent violation should be an item of noncompliance, not a violation.

The licensee's response included an updated letter of agreement and stated that they are presently in compliance with the regulations.

NRC Evaluation of Licensee's Response The licensee neither admits nor denies the apparent violation. It is implicit in the licensee's response that the violation did occur. No reason is given for its occurrence. The response states that the letter

T

. . .

The University of Oklahoma 3 of agreement was out-of-date and an updated letter was attached. The licensee did not address corrective measures to be taken to prevent further violations and when full compliance will be achieved. The updated letter from the hospital does not contain an expiration date. The.

licensee stated that the apparent violation should be an item of noncompliance, not a violation. An item of noncompliance is a violation; therefore, the violation remains as proposed.

Restatement of Violation C 10 CFR Part 50.54(q) requires that a licensee authorized to operate a research reactor shall follow and maintain in effect an Emergency Plan.

Section 10.1 of your Emergency Preparedness Plan states that individuals with emergency response responsibilities such as the University Police and Norman Fire Department shall be trained on an annual basis in radiation safety and the facility emergency procedures.

The NRC inspector determined on January 29, 1987, that training in radiation safety and the facility emergency procedures was not being received by all individuals from the University Police and Norman Fire Department who would respond to an emergency at the facility.

Summary of Licensee's Response to Violation C The licensee stated that the university radiation safety office conducts annual training for police and fire personnel. The persons that attend are generally the higher grade officers with training responsibility within their own departments. The licensee does not have jurisdiction over these departments and feel they have completed their obligation to the emergency plan. The licensee's emergency response procedure requires that a knowledgeable and trained individual is called and responds during an emergency. The reactor facility is in the process of being mothballed and the licensee plans to request that the emergency plan be modified or deleted.

NRC Evaluation of Licensee's Response The licensee neither admits nor denies the apparent violation. The licensee does not propose any corrective action to ensure that support personnel are adequately trained to respond in an emergency nor action to prevent further violations. Therefore, the violation remains as proposed.

. _ _ _ _ . .__ _ _ _ _ _ _ _ _ _ _ . _ __ _ _. _ _ . _ _ _ _ _ _ _ _ _ _- _.

. . .

The University of Oklahoma 4 Please provide the supplemental information within 20 days of the date of this letter.

Sincerely, ORIGINAL SIGNED BY:

Lawrence A. Yandell, Chief Radiological Protection and Safeguards Branch cc w/ enclosures:

The University of Oklahoma ATTN: Dr. E. H. Klehr, Chairman Reactor Safety Committee 865 Asp Avenue Nerman, Oklahoma 73019 The University of Oklahoma ATTN: Dr. C. Jensen, Reactor Director AMNE 865 Asp Avenue Norman, Oklahone 73019 bcc to DMB (IE01)

bcc dist, by RIV:

RPB E. H. Johnson, DRSP RSB RPSB RSTS Operator MIS System R. D. Martin, RA RIV File R. E. Baer H. N. Berkow, NRR B. Murray L. A. Yandell R. L. Bangart R. E. Hall M. E. Emerson

- _ _ - - - _ - - _ _ _ - . _ _ - _ _ . _ _ _ - - - _ _ ____ _-_______-__ ____ ____ ___ _ _ _ _ - _ _ _ _ - _ _ _ _ - _ _ - - _ _ - _ - -

4 .

. .

. -,

. m, @@ Mll.

T/re plE2M LL University ofOftfahoma }j SCHOOL OF AEROSPACE, MECHANICAL ANO NUCLEAR ENGINEERING 865 Asp Avenue, Room 212 Norman. Oklahoma 73019 (405) 325 5011 April 14, 1987 Mr. J.E. Gagliardo, Chief Reactor Projects Branch USNRC - Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011 Docket: 50-112/87-01 License: R-53 O

Dear Mr. Gagliardo:

The following letter is in reply to the inspection of 'fr. R.E. Baer and _

.

the notice of violation sent by your office dated March 16, 1987.

I want to make some general observations concerning the inspection and the discrepancies that were found. I have been involved with at least 5 inspections of AGN type reactors and no inspector or set of inspectors ever spent more than 2 days at the f acility. Especially one for which the last inspection showed no items of non-compliance, no violations, had not operated during the 10 month period prior to the inspection, sud whose total operating time during the two year period between it.spections was less than the time spent by the inspector at the f acility.

The second item that concerns me is the way in which the region of fice has conducted its evaluation of the report by Mr. Baer. At his exit interview, Mr. Baer indicated that he considered your violation A to be a violation, which we disagree with. while your violations B and C he considered

.

to be discrepancies or items of non-compliance, with.which I concurred. With ,

that in mind, we set out to correct those deficiences that he found. Ihe i

,

decision to upgrade those items to violations was not _ warranted and I believe

'

to be incorrect.

The following are specific replies to the list of violations:

A. As stated in the Notice of Violation, it is acknowledged that 10CFR Part 20.401(b) requires that "the Licensee shall maintain records in the same units used in this part, showing the results of surveys required by $20.201(b)."

j $20.201(a) also states that "when appropriate (our emphasis) such

, evaluation includes a physical survey of the location of materials and l

'

equipment, and measurements of levels of radiation or concentration of radioactive material present."

%

()

SP

_. _- - -- .-. - _ - - . ~ . _ . . .

. ;, .

.-

e ,

'

M April 14, 1987

,

Page Two

<

$20.201(b)(2) requires that each license make surveys as are reasonable under the circumstances to evaluate the extent of radiation hazards that may be present.

In keeping with our commitment to ALARA, this licensee conducts very

. detailed surveys of laboratories. These " surveys" incicie, as appropriate, i either measurements of radiation fields in mR/hr using calibrated survey i meters and/or swipe tests to determine the presence of radioactive j contamination.

A description of our procedure for swipe tests may be of value in '

'

understanding our position. To determine the presence of radioactive

, contamination.:which,would not produce a radiation field, i.e. an mR/hr field that could be detected in an area survey, .we take "Q Tip" swipes of physical

locations such as bench tops, sinks, floors, doors, etc. These swipes are I c- analysed in a liquid scintillation counter along with standards and background samples. The standards are used to verify instrument performance. The policy

in evaluating the swipe results (as. printed out by the instrument in cpe) is -

-

that a sample giving a count rate of pwice background or greater requires

attention, i.e. decontamination. It is our premise that if the standards
verify efficiency performance for the instrument, a comparison of sample and i background eps values is a valid indication of the presence or absence of radioactive contamination.

~

!

l 10CRF20 is specific (in units of mR/hr, uCi or dpa) for posting of i

radiation fields [20.203 (b) and (c)], determining concentrations of radioactive materials in air in restricted areas [20.103], permissible levels of radiation in unrestricted areas [20.106], releases of licensed material to l

a sanitary sewerage system [20.303] and survey swipes of received packages of licensed materials [20.205]. Our systems comply, with these requirements -

including compliance as to units of radiation measurement.

However, neither 10CFR nor any Regulartory Guide detail specifics for lab swipes in any units as to " action levels." Contrast this, for example, with 20.205(b)(2) which specifies the limit of removable contamination in

,,

microcuries per 100 square centimeter of package surf ace. In other words , if an absolute radiation unit standard (dpa or uCi, etc.) exists, then such conversion would be appropriate.

It is oor contention that, in the absence of a standard, our procedure, as previously stated, identifies the presence of contamination and sets an appropriate level for corrective action. And the accuracy of such action is verified by analyzing standards along with the test samples, as previously ,

described. To convert from cpu to dpm or uCi would be a meaningless (and in '

consideration of the large number of samples we take, a non-productive and very time consuming) task which would not give any better indication of the presence of contamination nor give a radiation unit to compare to a standard since a standard does not exist.

. _ _ _ , _ _ _ _ _ . _ . _ . _ _ _ _ _ _ . _ _ _ _ _ - _ _ _ _ _ _ _ . _ _

-

- . ._ . . - _ _ . . . .- _ _ _ _ ._ __

,_.S.

. :. . '

.

...

. . ,

M April 14, 1987

.Page Three .

~

' '

We therefore do not believe, we are in violation and request that you

,

~ reexamine our procedure of lab survey / swipe methods to determine whether or

not ,it is in fact ameting the intent of the regulations. Should reexamination result in affirmation of your previous position we .would request that you
establish;a regulatory standard so we_ will be able to set ~ action guidelines in ,

response to the results._we will obtain by performing the conversions you would require.

,

,

We appeal this violation and feel that we are in compliance at this

<

time.

B. Although the letter was out of date, your contention that the emergency

[ plan was not implemented is an incorrect observation. There is much more to the emergency plan than the letter update and we feel the emergency plan has

. been implemented and that this should be an item of non-compliance not a

, violation.

An updated letter is attached and_ we are in compliance at this time. _

- C. The Radiation Safety Office has annually conducted training for police and fire personnel and the University Safety office participates in the annual i and most monthly tests of the evacuation system. The persons that attend are generally the higher grade officers .with training responsibility.within their own departments. The reactor facility and the Radiation Safety office have also produced and distributed a video explaining the precautions and problems j. that any be encountered at the facility during an emergency. Wh have also

extended our services in the training of these personnel. We feel that since we have no jurisdiction over these departments that.we have completed our i

obligation to the emergency plan.

Since it is obviously impossible to guarantee that every person is j trained, even if we had compulsory means to do so, the emergency response i procedures detail that some person from the emergency call list must be i

contacted. This is to insure that a knowledgeable and trained individual is

'

at' the site during an emergency. In addition to the person from the reactor staff, the procedure details that the Radiation Safety Office must be notified. This again is an attempt to insure that a trained individual is present during any eme rgency.

Although we do not feel we are in non-compliance or violation, this item will be corrected. As was stated to the inspector and discussed previously with NRC of ficials in Region IV and Washington D.C., the reactor facility is the process of being mothballed, hence, the reason it has not been operated in over a year. The application for modification of the technical specifications will be completed and sent to the NRC by September 1,1987. As part of that application, we will request that the emergency plan also be modified or deleted, deleting the requirement for this training. In the interim, the fuel has been removed and is secured in the fuel storage facility where it will be kept during the mothball period.

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

e ' '. . . *

. .

.

M April 14, 1987

Page Four We..will be in full compliance when the NRC issues new technical

-

specifications for the mothballed reactor.

If you have any questions concerning the above, please contact me at (405) 325-1754.

Sincerley y rs,

.

%

Craig .J sen React r Di ctor cc: Davis M. Egle, Director, ANNE v

CMJ/sj b

.

-.

.

Attachment e

i E

i l

!

l

!

l

,

w,- **'H* *

,

..,; -

.

?

-

._

NORMAN REGIONALHOSPITAL

.

April 7, 1987 -

Mr. Craig Jensen University of Oklahoma 865 Asp, Room 212 Norman, Oklahoma 73019

Re: Services and use of Norman Regional Hospital facilities in the event of a radiological incident at the University of Oklahoma.

o-

Dear Mr. Jensen:

-

By this letter, Norman Regio'nal Hospital agrees to provide emergency

-

care and other necessary services to the University of Oklahoma in the event of the implementation of the " UNIVERSITY OF OKLABONA RADIO 1DGICAL EMERGENCY PREPAREDNESS PLAN". The emergency care specific to a radia-tion disaster will be provided in accordance with Normen Regional

-

Hospital's radiation disaster plan, and in accordance with our regular Emergency Department services.

i

!

This agreement will be effective issuediately and remain in force as long l as the parties are in agreement. In the event Norman Regional Hospital

!

desires to terminate this agreement, a 60 day written notification will I be provided to the University of Oklahoma.

Sincere 1 ,

'

M l' ay

'[CraigW.

, Admini t stor ones

.

J CWJ: dig ec: Marge Rosenfelt Bruce Smith

<

. .