IR 05000284/1989001
| ML20247G521 | |
| Person / Time | |
|---|---|
| Site: | Idaho State University |
| Issue date: | 03/30/1989 |
| From: | Baer R, Chaney H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20247G514 | List: |
| References | |
| 50-284-89-01, 50-284-89-1, NUDOCS 8904040258 | |
| Download: ML20247G521 (13) | |
Text
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _.
-
_
_ _ _ _ - _ _ _ - _ _
. _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _
_-
l
.
.
.
.....
.
l APPENDIX B U.S.; NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-284/89-01 License:
R-110 Docket: 50-284-Licensee:
Idaho State University (ISU)
Pocatello, Idaho 83209 Facility Name:
ISU Lillibridge Engineering Laboratory - AGN 201-M (5 Watt)
Inspection At:
ISU Campus, Bannock County, Pocatello, Idaho Inspection Conducted:
February 26 through March 1, 1989 Inspector-J/.iit:2MS H.'D. Chaney, Senior Radiation Specialist Date Facilities Radiological Protection'Section Approved:
.F/ bib /$
R.'Baer, Chief, Facilities Radiological Date
'
Protection Section Insrection ' Summa ry Inspection Conducted February 26 - March 1, 1989 (Report 50-284/89-01)
Areas Inspected:
Routine, unannounced inspection of the licensee's management organization, operations and maintenance logs, internal audit and review program, reactor operations, operator requalification program (ORP),
qualifications and training, surveillance requirements, experiments, fuel handling, nuclear materials accountability and safeguards, radiation protection program, emergency preparedness, and Physical Security Plan (PSP).
Results: The licensee's overall program appears to be adequate and no programmatic breakdowns were identified in the areas reviewed.
The NRC inspector observed improvement in the areas of administrative control, procedures, radiological surveys and posting, and dosimetry maintenance.
Within the areas inspected, three violations (ORP implementation, paragraph 4.d; two examples of a failure to fully implement the Emergency Preparedness Plan (EP), paragraph 4.i; and two examples of a failure to fully implement the PSP, Attachment to this report.
No deviations were identified.
Enclosure contains PROPRIETARY INFORMATION.
Decontrolled when separated from attachments.
h
Q
-
_ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ - _ _ _ -
_ _ _ _ _.
l
'
. _ _ _ - _ _ - _
_ _ _ _
_- ____- _ - _
______ _ _
.
..
.
...
.
DETAILS 1.
Persons Contacted Licensee
- V. Charyulu, Dean, College of Engineering
- D. F. Harmon., Professor of Physics & Reactor Safety Committee-(RSC) Member
- D. Levinskas, Radiation Safety Officer (RS0), Reactor Supervisor, SR0
- Denotes. personnel in attendance at the exit meeting on March 1, 1989.
2.
Follow-up on Previous Inspection Findings (92701 and 92702)
(Closed) Violation (284/8701-01):
Reactor Administrator / Qualifications -
This item was previously discussed in NRC Inspection Report 50-284/87-01 and involved the licensee's failure to ensure that the person assigned the duties of RA satisfied the qualifications established by the Facility Operating License Technical-Specification (TS) 6.2.
The NRC inspector examined the licensee's implementation of the corrective actions committed to in their April 10, 1987, response to the violation.
The licensee's implementation of corrective actions (appointment of Dr. A. Wilson as RA, and request a change to the TS so that the position will not require the RA to hold an NRC SRO license) appears to be adequate to prevent a recurrence of the violation in the future.
(Closed) Violation (284/8701-02):
Posting of High Radiation Areas --This item was previously discussed in NRC Inspection Report 50-284/87-01 and involved the licensee's failure to properly post a high radiation area as required by 10 CFR Part 20.203(c).
The NRC inspector examined the licensee's implementation of the corrective actions committed to in their April 10, 1987, response to the violation. The licensee's implementation of corrective actions (posting of the areas of concern and procedurally implementing a prestartup check of posting) appears to be adequate to prevent a recurrence of the violation in the future.
(Closed) Violation (284/8701-03): Annual Report Submittal - This item was previously discussed in NRC Inspection Report 50-284/87-01 and involved the licensee's failure to submit the TS 6.9 I annual report of activities in a timely manner. The NRC inspector examined the licensee's implementation of the corrective actions committed to in their l..
April 10, 1987, response to the violation.
The licensee's implementation of corrective actions (development and posting of a scheduling reference l
board) appears to be adequate to prevent a recurrence of the violation in the future.
t Enclosure contains PROPRIETARY INFORMATION.
Decontrolled when separated from attachments.
.
_ __-_ - _ _ ______.
_
_ _
_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _
__ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ -
.
.
.
.
.
...
(Closed) Open Item (284/8701-04):
Procedures Update - This item was previously discussed in NRC Inspection Report 50-284/87-01 and involved the. licensee's self identification (RSC audit) of weaknesses in administrative control and documentation of procedures. The NRC inspector examined the licensee's procedures and found them to be clearly indexed and exhibiting signatures and dates of approval.
(Closed) Open Item (284/8701-05):
Pocket Dosimeters - This item was previously discussed in NRC Inspection Report 50-284/87-01 and involved the licensee's lack of a pocket dosimeter response check program that met industry standard ANSI N13.5-1972 or NRC Regulatory Guide (RG) 8.4 guidance. The NRC inspector examined the licensee's pocket dosimeter response check procedure and determined that it adequately resolved the NRC's concerns in this area.
(Closed) Open Item (284/8701-06):
Neutron Radiation Survey - This item was previously discussed in NRC Inspection Report 50-284/87-01 and involved the licensee's lack of a neutron radiation survey of the reactor facility during reactor operations. The NRC inspector examined the neutron surveys conducted on November 5, 1987, and again on January 27, 1989.
The surveys identified several areas of neutron radiation around the perimeter of the AGN vessel and at shielding gaps.
Neutron radiation dose rates in the reactor laboratory and near the AGN reactor were below 100 millirem per hour. All dose rates (neutron and
-
gamma radiation) were less than 2 millirem in unrestricted areas surrounding the laboratory.
(Closed) Open Item (284/8701-07):
Incorporation of ANSI' 15.8-1973 and NRC RG 2.5 Attributes - This item was previously discussed in NRC Inspection Report 50-284/87-01 and involved the licensee's need to improve documentation of quality assurance and control aspects of equipment testing and maintenance.
The NRC inspector examined operation and maintenance logs and noted improvement in documentation of operational and maintenance test activities.
(Closed) Open Item (284/8701-08):
Posting of Current NRC Form 3 and Emergency Phone Numbers - This item was previously discussed in NRC Inspection Report 50-284/87-01 and involved the licensee's aged NRC Form 3's and emergency recall lists posted throughout the facility and other ISU locations.
The NRC inspector examined current postings of the 10 CFR Part 19.11 required documents and found them to be current.
3.
Open Items Identified During This Inspection An open item is a matter that requires further review and evaluation by the NRC inspector. Open Items are used to document, track, and ensure adequate follow-up on matters of concern to the NRC inspector.
The following open items were identified:
Enclosure contains PROPRIETARY INFORMATION.
Decontrolled when separated from attachments.
lo _
_ _ _.. _ _ _ _ _ _.
_ -_
_
>
. _ _ _ _.
.
-
. _ _
_ _.
_ _.
- _ _ _ _ _ - _
.. '... '.
.
Open Item Title See Paragraph 284/8901-04 Tracking Annual &
4.d Quarterly Operator Activities 284/8901-05 Operator Requal. Tests 4.d 284/8901-06 Experiment Approval 4.f Documentation 284/8901-07 Neutron Dosimetry 4.g 284/8901-08 NRC Form 5 4.g 284/8901-09 RSC Audits 4.h 284/8901-10 Reactor Laboratory 4.1 Fire Protection 284/8901-11 Access Key and Material Controls Attachment 1
Class II Research and Test Reactor Operations (40750)
Background The reactor has been operational at ISU since October 1967. The reactor operating history for 1987 and 1988 are as follows:
Year Operating Hours Kilowatt-Hours 1987 160 200 1988 154 180 (estimate)
a.
Organization and Management The NRC inspector reviewed the licensee's staff, staff qualifications, and functional positions for compliance with the requirements of Section 6.0 of the TS. The licensee's organization was found to comply with the requirements of TS 6.1, 6.1.1, 6.1.3, 6.1.4, 6.1.5, and 6.1.8.
Currently, the RSO is also occupying the position of reactor supervisor.
The RSO holds an NRC senior Enclosure contains PROPRIETARY INFORMATION.
Decontrolled when separated from attachments.
- _ _ _ _ _ - _ _ _ _ - - _ _
_ _ _ _ _ _ _ _ - _ _
.
.
.-
.
...
.
operator's license (May 1988). The. licensee.has submitted a change
'to Section 6.0 of the TS to eliminate the need for the RA to hold an NRC operating license.
No violations or deviations were identified.
b.
Logs and Records The NRC inspector examined the licensee's operating, maintenance, and radiological survey logs and records for compliance with the requirements of 15 6.10.
Logs and records completed during the period February 1987 through February 1989 were reviewed (the period since the last inspection of this area - February 4-6,1987).
The logs were found to be detailed and showed a neater appearance /
condition over that found during the last inspection of this area.
The licensee adequately resolved the NRC inspector's observation, previously identified in NRC Inspection Report 50-284/87-01, concerning log line-outs and changes.
Logs and records were'being.
appropriately stored and protected.
No violations or deviations were identified.
c.
Procedures The NRC inspector examined the licensee's procedures for operating and maintaining the reactor, conducting surveillance and calibrations, and conducting experiments to determine compliance
-
with the requirements of Sections 6.5 and 6.6 of the TS.
The NRC inspector determined that the licensee had developed 2 reactor operating (startup/ shutdown) procedures, 8 surveillance /
maintenance / calibration proceoures and 20 proceduralized experiments for conducting reactor associated activities. The licensee was noted-to have implemented a periodic review of existing procedures and was drafting a RSC approved administrative procedure for controlling procedure development, approval, indexing, and revisions. The licensee's records for 1987 and 1988 regarding the following procedures were examined by the NRC inspector:
o SP-1, Safety Channel #1 Check, Calibration, and Trip Verification o
SP-2, Safety Channel #2 Check, Calibration, and Trip Verification i
o SP-3, Safety Channel #3 Check, Calibration, and Trip Verification o
SP-4, Shield Tank Water Level Interlock Calibration o
SP-5, Shield Tank Water Temperature Interlock Calibration Enclosure contains PROPRIETARY INFORMATION.
'
Decontrolled when separated from attachments.
..
.
.
_ _ _ _ _ _ _
- _ _ _ _ _ _ _ _ _ _ _
- _ _ _ _ - _ _ _ - -..-
. _ _ _ _ - -.
_
__
.
-
_
_ _ -
__ -
--_. -.
.
.
.-
,
...
.
o SP-6, Seismic Displacement Interlock Calibration and Test o
MP-RS1, Performance Test of Direct Reading Pocket Dosimeters o
MP-1, Control Rod Maintenance Procedures o
OP-1, Reactor Start Up and Shut Down On February 27, 1989, the NRC inspector observed the licensee modify thermal column shielding and verified compliance with TS 3.4.C.1 and 2 concerning type of shielding required during reactor operations.
No problems were identified with the licensee's performance of the procedures.
The NRC inspector observed the operation of the reactor safety systems referenced in TS 2.2.a; 3.2.c.1, 2, and 3; and 3.2.d.
No violations or deviations were identified.
d.
Staff Training and Operator Requalification Training The NRC inspector examined the licensee's training programs for laboratory / reactor workers and the requalification of reactor operators to determine compliance with the requirements of 10 CFR Parts 19.12 and 55.59.
The NRC inspector observed licensee reactor operations on February 27 and March 1, 1989.
The reactor operators were noted to be familiar with the reactor, and complied with all applicable procedures and license conditions.
The NRC inspector reviewed the licensee's radiological safety training for personnel frequenting the reactor laboratory and determined that the licensee satisfies the requirements of 10 CFR Part 19.12 through the student participation in one or more graduate level reactor engineering and experiment courses (601 and 602). The NRC inspector discussed with the RSO, course content and the guidance L
contained in NRC RG 8.13, " Instruction Concerning Prenatal Radiation Exposure," and NRC RG 8.27, " Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear Power Plants."
The licensee currently has five licensed operators (three operators and two SR0s).
Currently, only the two SR0s (RA and the Reactor Supervisor) are active. Only one of the reactor operator licenses is expected to be active between now and the end of the 1989-1990 school year.
The NRC inspector examined the licensee's NRC approved ORP (February 1974), and supporting records that implement the requirements of 10 CFR Part 55.59(c).
The licensee's documentation of each operator's participation in the ORP was found to be in disarray and only one SRO's file (RA was complete).
Enclosure contains PROPRIETARY INFORMATION.
Decontrolled when separated from attachments.
l l
_ - _
__ -____ _ ____._
-_
_ _ - _ _ _ _ _ _
_ - _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _
__
l
..
.
.
,
.
...
.
Neither the licensee's ORP nor any other of the licensee's documents clearly identified how the licensee tracked and documented the following ORP activities:
o Lectures - When operators do not participate in either of the two graduate level courses (601-602).
o On-The-Job-Training - The required 10 operations of the reactor per year.
o Quarterly Operating Activities - To comply with the requirements of 10 CFR Part 55.53(e) and (f).
o File - Content and organization of ORP files.
The NRC inspector was able to extract sufficient information'to determine that the licensee's operators had satisfied the 10 CFR Part 55.53(e) requirements for reactor operation to maintain their license active.
The licensee is aware of the operators that have not performed sufficient operations during each quarter to maintain their license active; these operators had not operated the reactor.
The NRC inspector discussed with licensee representatives the need for the licensee to develop administrative controls over the ORP files and implement an operator matrix that will identify completion of each ORP and 10 CFR Part 55.53(e)/(f) item.
The licensee was noted to have a procedure for requalification of an operator whose license had become inactive.
There was no indication that this-procedure had ever been used, even though at least two currently licensed operators had let their license lapse due to inactivity.
This is considered an open item pending licensee development of administrative documents to control implementation of the ORP.
l (284/8901-04)
The licensee's requalification tests given to one SR0 were reviewed to determine compliance with the requirements of 10 CFR Parts 55.59, 55.41, and 55.43. Tests for 1987 and 1988 were determined to marginally (number of questions and variance in questions) meet the subject comprehensiveness outlined in 10 CFR Parts 55.41 and 55.43. Testing of the only other SRO was satisfied by his completion of the NRC administered SRO examine in 1988. The licensee indicated that future tests will utilize the test question bank made up of NRC administered operator and SR0 licensing test questions. This is considered an open item pending licensee reevaluation of operator tests.
(284/8901-05)
10 CFR Part 55.59(c) requires, in part, that "A facility licensee shall have a requalification program reviewed and approved by the Commission." TS 6.3 of the ISU Facility Operating License, Amendment 3, requires, in part, that "All licensed reactor operators shall participate in requalification training as set forth in 10 CFR Part 55.
In Section 4.b of the licensee's NRC approved reactor Enclosure contains PROPRIETARY INFORMATION.
Decontrolled when separated from attachments.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
__ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _
_ _ _. _ _ _ _ _ _ _ _,
.
.
...
..
.
ORP, it states, in part, that "In addition to the written examination, a member or members of the RSC will observe the operation of the reactor by each licensed operator and senior operator at least once during each calendar year... A report of the observation of this operating experience by the member of the Reactor Safety Committee will be reported at the next meeting of the Safety Committee and will be made a permanent part of the licensee's file."
l The NRC inspector determined on March 1, 1978, that the licensee's RSC had not performed observations on one SRO and one reactor operator since April 1987 and May 1988, respectively. Both individuals had current NRC operator licenses.
The failure to implement the ORP is considered a violation of 10 CFR Part 55.59(c).
(284/8901-01)
No violations or deviations were identified.
e.
Surveillance The NRC inspector examined records and iogs describing the conduct of TS related surveillance to determine compliance with the requirements of Section 4 0 of the TS.
The licensee's records indicated that all required surveillance (preoperational, daily, semiannual, annual, and biennial) were completed for 1987 and 1988 time period.
The following TS required surveillance were reviewed:
TS Item Frequency Dates 4.1.a, Determination of Safety annual 01/27/87 and Control Rod Reactivity 10/15/87 Worth Determination annual 4.2.a, Control Rod Scram Time annual 09/11/87 l
09/06/88 4.2.b, Control Rods and Drive biennial 09/11/87 Inspection 09/06/87 4.2.g, Period, Count Rate, and annual 08/28/87 i
l Power Level Measuring 01/11/88 l
Calibration 07/14/88
'
01/20/89 The following surveillance were also verified to have been performed at the required frequency:
TS 4.1.c, " Verification of Experiment Reactivity Worth" TS 4.3a, " Shield Tank Structure Inspection" Enclosure contains PROPRIETARY INFORMATION.
Decontrolled when separated from attachments.
_ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _
- ___ _ __ __ - ____ _ ___- __ _ _
._
.
.
.
...
..
.
TS 4.4.a. " Portable and Fixed Radiation Survey Instrument Calibration" TS 4.4.c, " Radiological Surveys of the Reactor Laboratory" No violations or deviations were identified, f.
Experiments The NRC iray.?ctor 2ined the licensee's development, review, and approval of reactor experiments to determine compliance with the requirements of Sections 3.1, 3.2(a through h), and 3.3 of the TS.
The NRC reviewed 20 proceduralized experiments and observed the licensee conduct 2 experiments involving reactor operations. The licensee has not conducted any new experiments since 1984.
The NRC inspector discussed with the licensee the need to provide, on each experiment procedure, the revision, date, and signature of the approving authority as recommended in industry standard ANSI N401-1974 and NRC RG 2.4.
This is considered an open item pending licensee action.
(284/8901-06)
No violations or deviations were identified.
g.
Radiation Protection The licensee's radiation protection program was reviewed to determine compliance with the requirements of Sections 3.4, 4.2.1, and 4.4 of the TS; and the requirements of 10 CFR Part 20.5, 20.101, 20.102, 20.103, 20.202, 20.203, 20.401, 20.407, 20.408, and 20.409.
The NRC inspector examined exposure records, facility surveys, and radiation protection instrument calibration and response test records. The NRC inspector found the licensee's surveys and response tests to be well documented. The calibration status for portable survey instruments is indicated by a label which is in response to a NRC observation noted during the last inspection of this area.
The licensee had procured a neutron dose rate meter (calibrated and response checked using a heavy water moderated californium 252 source).
The licensee had performed a neutron survey of the reactor facility during reactor operations in response to the NRC inspector's
-
observation during the last inspection of this area. The NRC inspector discussed with licensee representatives the shortcomings of their vendor supplied personnel neutron dosimetry.
The use of NTA (nuclear type A) film is not recommended by NRC RG 8.14, " Neutron Dosimetry," due to its insensitivity to low energy neutrons.
Since the licensee's reactor fission spectrum has a significant amount of
low energy neutrons, the NRC inspector requested that the licensee l
evaluate their current neutron dosimetry to the guidance contained in l
NRC RG 8.14 and ANSI N319-1976. This is considered an open item pending the licensee's evaluation of their personnel nuetron dosimeters.
(284/8901-07)
Enclosure contains PROPRIETARY INFORMATION.
Decontrolled when separated from attachment _ - __ - __- _ _
- _ _ _
- _ _.
-
_ _ _ _
--
.
.
.
...
,.
.
The NRC inspector noted that the licensee is exempted from issuing the personnel radiation exposure reports upon termination of an individuals work or studies at ISU as referenced in 10 CFR Parts 407, 408 and 409, since they'are licensed pursuant to Sectico 104c of the Atomic Energy Act and 10 CFR Part 50.21(c) and 10 CFR Part 40 exempts facilities so licensed.
The licensee was noted to be using the dosimetry services of a vendor accredited in accordance with the requirements of 10 CFR Part 20.202(c).
The NRC inspector also noted that the licensee utilizes both the vendors exposure documentation and their own records to satisfy the requirements of 10 CFR Parts 20.102 and 401.
The NRC inspector noted that several dosimetry records that satisfy the requirements for documenting personnel exposure to radiation on a quarterly basis as set forth in 10 CFR Part 401(a) (Form NRC-5,
" Current Occupational External Radiation Exposure"), were in error in that a separate racord was not being utilized for different types of exposures (d.sle body, skin, and extremities). The NRC inspector requested the licensee to evaluate their two dosimetry record systems to determine agreement with the guidance contained in NRC RG 8.7 and ANSI N13.b-1966 for maintenance of dosimetry / exposure record systems. The licensee had sufficient information available in their exposure records to determine accurately a persons current and allowable remaining exposure.
This is considered an open item pending licensee evaluations of their personnel exposure record system.
(284/8901-08)
No violations or deviations were identified, b.
Audits and Committees The NRC inspector examined the licensee's audits and activities of the RSC to determine compliance with the requirements of Sections 6.4, 6.7(b)
G.8, and 6.10.2(i) of the TS.
The NRC inspector examined meeting minutes of RSC meetings held since April 3, 1987, through December 13,1988 (four meetings).
The RSC typically review procedures, emergency preparedness, physical security, audit assignments, and reactor operations. The NRC inspector notea that at the April 1987 RSC meeting, a professor was assigned the responsibility of performing the biennial Facility EP and PSP audit and review of implementing procedures.
During the following May 24, 1988, RSC meeting, both areas were vaguely addressed in the meeting minutes, but there was no documentation of the audit's findings.
The NRC inspector discussed with licensee representatives (at the exit meeting) his concern that the findings addressed in this report and those of the last inspection of ISU operations, indicate that facility audits are not comprehensive enough to verify licensee
1 Enclosure contains PROPRIETARY INFORMATION.
Decontrolled when separated from attachments.
- - - _ _ - _ - - _ _ - -
_ - _.
. -
- - __ - - _ _ _ _ - _ _ - - _ _ _ - _ _ _
_ - _ _ _ - _ -
_ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ - _ _ _
.
.
.
...
..
.
Il compliance with the Facility Operating License and TS, and the applicable requirements of 10 CFR Parts 19, 20, 50, and 55. The NRC inspector noted that audits were not always performed by persons having expertise in the areas being audited. This is considered an open item pending licensee actions to improve the comprehensiveness of RSC audits.
(284/8901-09)
No violations or deviations were identified.
1.
Emergency Preparedness The licensee's emergency preparedness program for the ISU facility was examined to determine compliance with the requirements of Sections 6.4.3 and 6.6 of the TS; and Revision 3 to the NRC approved ISU EP, dated May 21, 1985; and 10 CFR Parts 50.54(q) and (r).
The NRC inspector examined the licensee's changes to the EP, training of personnel; performance and critiques of EP drills during 1985, 1986, and 1988; and maintenance of EP response equipment. All equipment was accounted for, properly stored, and periodically inventoried using a checklist.
The following violations were identified in this area:
10 CFR Part 50.54(q) requires, in part, that "A licensee authorized to possess and/or operate a research reactor.
shall follow and maintain in effect emergency plans...."
a.
Section 6 of the EP requires, in part, that " University personnel who would be involved in a nuclear incident will be tested by annual drills."
b.
Section 6 of the EP also requires, in part, that "The Emergency Preparedness Plan shall be audited by the Reactor Safety Committee at least once every two years."
The NRC inspector determined on February 28, 1989, that there was no evidence showing that:
(1) the licensee had conducted a drill of the EP during 1987; and (2) the licensee had audited the EP since 1985. The licensee believes the conducting and critiquing of the EP drills constituted as an audit.
The failure to perform a drill in 1987 or audit of the EP from 1985 through 1988 are each considered a violation of 10 CFR Part 50.54(q).
(284/9801-02)
The NRC inspector noted that during the crit'.,ue of the September 17, 1988, EP drill, it was identified by the Pocatello Fire Department that the reactor laboratory needed a manual fire alarm.
This was endorsed by the RSC during their December 13, 1988, meeting. The licensee is pursuing installation and tying in of a manual fire alarm to the Lillibridge Building central fire alarm system.
The NRC Enclosure contains PROPRIETARY INFORMATION.
Decontrolled when separated from attachments.
_ _ _
._____- _ ___
_ - _ _ _ _ _ _ _ - _ _ _ _ -
_ _ _ _ _ _ _
____
.
.
-
.
..
inspector discussed with the RA and Reactor Supervisor the guidance presented in ANSI /ANS 15.17-1981, " Fire Protection Program Criteria for Research Reactors." The NRC inspector noted that the Lillibridge Engineering Building alarm system was not tied into the Pocatello City master fire alarm system or to any other campus system; the
building was not staffed on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> basis, and that there were no smoke or thermal detection devices in the reactor laboratory. A fire during off hours would only be found by a passersby or the roving ISU security patrols.
The NRC inspector discussed the need for the licensee to evaluate their fire protection program for the Lillibridge Engineering Building. The NRC inspector evaluated the amount of combustible materials in the reactor laboratory.
Even though the laboratory was not devoid of combustible items, material was situated away from the reactor for the most part. This area is considered an open item pending further licensee actions regarding the current fire protection program for the reactor laboratory.
(284/8901-10)
No deviations were identified.
j.
Reports The NRC inspector reviewed the licensee's annual reports for the years 1986 and 1987 to determine compliance with the requirements of Section 6.9.1 of the TS.
The licensee had submitted the required annual reports of facility activities and operations as required by the TS.
No violations or deviations were identified.
5.
Physical Security (81431)
The NRC inspector examined the licensee's implementation of the PSP, Revision 1, dated January 21, 1981, to determine compliance with the requirements of Section 2.C(3) of the Facility Operating License, Sections 5.2 and 5.3 of the TS; and the requirements of 10 CFR Part 50.54(p).
In accordance with 10 CFR Part 2.790(d), the material concerning the PSP are exempt from disclosure.
Therefore, this material is discussed in the Attachment to this Appendix and will not be placed in the Public Document Room.
No deviations were identified.
6.
Plans, Procedures, and Reviews (81401)
l The NRC inspector examined the licensee's review and approval process for changing their PSP to determine compliance with the requirements of Facility Operating License Condition 2.C(3) and 10 CFR Part 50.54(p).
Enclosure contains PROPRIETARY INFORMATION.
l Decontrolled when separated from attachments.
!
!
i
- - _ - - _ - _ -. - _ _ _ _ _ - _ _ _
-
I
_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
!
.
.
L
~
.
.,
.
)
l In accordance with 10 CFR Part 2.790(d), the material concerning the PSP are exempt from disclosure.
Therefore, this material is discussed in the Attachment to this Appendix and will not be placed in the Public Document Room.
No deviations were identified.
7.
Special Nuclear Material Control and Accountability (85102)
The NRC inspector examined the licensee use, control, and accountability of special nuclear material (SNM) for compliance with the requirements of NRC SNM License No.1373, expiration date May 30, 1992; the requirements of Facility Operating License Conditions 1.G, 2.B(2), and 2.C; and the guidance contained in NUREG/BR-0006, revision 2, " Instructions for Completing Nuclear Material Transaction Reports."
The NRC inspector verified the licensee's possession of no more than 700 grams of SNM in the form of enriched uranium-235. The NRC inspector noted that other inventories of SNM (subcritical fuel assembly and 2 plutonium-239/ beryllium neutron sources - approximately 19 grams total),
specifically covered under the NRC SNM license, were being used, stored, and controlled in accordance with the conditions of the SNM license. The licensee's radium / beryllium reactor startup neutron source is licensed under their 10 CFR Part 150 State broadscope license.
The NRC inspector noted that the licensee had provided a better description (by photographs) in their accountability procedure of the makeup of the approximately 28 grams of SNM in the form of AGN fuel fragments.
This was done in response to an NRC inspector concern raised during the last inspection of this area.
Records and inventories were found in good order. The Attachment to this Appendix also discusses an NRC inspector concern regarding safeguarding of the licensee's SNM.
No violations or deviations were identified.
8.
Exit Interview The NRC inspector met with the licensee representatives denoted in paragraph 1 on March 1, 1989, and summarized the scope and findings of the inspection as presented in this report.
Enclosure contains PROPRIETARY INFORMATION.
Decontrolled when separated from attachments.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _