IR 05000456/1987034
| ML20236B043 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/16/1987 |
| From: | Grant W, Greger L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20236B030 | List: |
| References | |
| TASK-2.F.1, TASK-TM 50-456-87-34, 50-457-87-32, IEIN-86-041, IEIN-86-046, IEIN-86-103, IEIN-87-003, NUDOCS 8710230305 | |
| Download: ML20236B043 (13) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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REGION III
Reports No. 50-456/87034(DRSS) 50-457/87032(DRSS)
Docket Nos. 50-456; 50-457 Licenses No. NPF-72; No. CPPR-133 Licensee:
Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name:
Braidwood Station, Units 1 and 2 Inspection At:
Braidwood Site, Braidwood, Illinois Inspection Conducted:
September 21-30, 1987 c.+.ypJ/
W.B.Grantje lO//4/f7 Inspector:
Ddte !
Accompanying Inspector:
M. A. Kunowski O,7.
-<rl Approved By:
L. R. Greger, :hief
/0//fM7 Facilities Radiation Protection Date '
Section Inspection Summary Inspection on September 21-30, 1987 (Reports No. 50-456/87034(ORSS);
No. 50-457/87032(DRSS))
Areas Inspected:
Routine unannounced inspection of the operational radiation protection program for Unit 1; the solid, liquid, and gaseous radwaste program for Units 1 and 2; and a portion of the Unit 2 startup radiation survey; including:
organization and management control; training and qualification; exposure control; radiation protection procedures; ALARA activities; control of radioactive material; status of radwaste systems; status of certain TMI action plan items; and a review of the licensee's action concerning Information Notices No. 86-41, 86-46,86-103, and 87-03.
Results:
No violations or deviations were identified.
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DETAILS
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1.
Persons Contacted
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- R. Aker, Radiation / Chemistry Supervisor J. Anspaugh, Health Physicist
- P. Barnes, Supervisor, Regulatory Assurance
- R. Bedford, Regulatory Assurance
- L. Davis, Assistant Superintendent, Technical Services
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- E. Fitzpatrick, Station Manager J. Jasnosz, AR/PR Coordinator J. Kielbasa, Radiological Engineer /ALARA l
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- D. O'Brien, Services Superintendent l
J. Petro, Operating Engineer
- F. Rescek, Health Physics Supervisor, Nuclear Services E. Roche, ALARA Coordinator
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- C. Schroeder, Services Superintendent, Dresden D. Shamlin, Lead Foreman P. Stanczak, Technical Staff
- M. Takaki, Regulatory Assurance
- M. Vonk, Lead Health Physicist
- K. Weaver, Startup Health Physicist
- W. Kropp, NRC, Senior Resident Inspector
- T. Taylor, NRC, Resident Inspector
- T. Tongue, NRC, Senior Resident Inspector The inspectors also contacted several other licensee personnel, including technicians, engineering assistants, foremen, and members of the technical staff.
- Denotes those present at the exit meeting on September 30, 1987.
2.
General This inspection, which began at 9:30 a.m. on September 21, 1987, was conducted to examine the operational radiation protection program, status of radwaste systems, licensee actions on previous inspection findings, and status of certain TMI action plan items.
3.
License Action on Previous Inspection Findings (Closed) Open Item (456/85014-HH; 457/85014-HH):
Commercial storage of low-level radioactive waste not generated by the utility at power reactor sites.
Braidwood has no plans for a commercial storage building or for commercial storage of low-level waste.
This issue which was raised in
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Generic Letter GL-14 is considered closed.
(Closed) Open Item (457/86002-08):
Complete installation, procedures, and training on use of post-accident noble gas effluent monitors per l
NUREG-0737, Item II.F.1.1.
Preoperational testing and calibrations have been completed; procedures and training have been completed.
See Section 12
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i, (0 pen) Open Item (456/86002-01; 457/86002-01):
TLD calibration facility needs to be built.
Construction of the TLD calibration facility has
begun on the 433' level of the Service Building.
Completion of j
construction is anticipated by the end of 1987.
The completed TLD
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calibration facility will be reviewed during a future inspection.
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4.
Organization and Management Controls The inspectors reviewed the licensee's organization and management controls for the radiation protection and radwaste programs including changes in the organizational structure and staffing, effectiveness of procedures and other management techniques used to implement these programs, experience concerning self-identification and correction of l
program implementation weaknesses, and effectivenesses of audits of these
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programs.
Audits are discussed in Section 5.
Since the last radiation protection inspection in June 1987, several organizational changes have been made, including:
A Rad / Chem Technician (RCT) has been upgraded to HP Foreman.
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are currently six HP foreman, jj Two contractor engineering assistants have been added to the ALARA
group.
The Health Physicists (HPs) meet daily to discuss problem areas and the status of various projects.
The Rad / Chem Supervisor meets every morning with the Station HP, ALARA Coordinator, Lead Foreman, and others to discuss the plan of the day.
In addition, the station plan of the day meeting, during which work to be done and support services and equipment required are discussed, is attended by a Rad / Chem representative.
Due to Unit 1 startup Radiation Protection (RP) activities, the RP staff
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has been augmented by approximately 26 contractor radiation protection personnel, including two foreman and a site supervisor.
No violations or deviations were identified.
i 5.
Audits and Appraisals The inspectors reviewed station Quality Assurance (QA) audits and surveillance of the radiation protection and radwaste programs conducted since the last radiation protection inspection.
Extent of the audits and surveillance, qualifications of the auditors, and adequacy of corrective actions were reviewed.
A QA audit (Report No. QAA-20-87-17), conducted during May 1987, reviewed the radiation / chemistry program.
There were two findings, two observations, and one comment concerning record keeping, procedural adherence, and attention to detail by the RCTs.
The lead foreman
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discussed " attention to detail" with all the RCTs individually.
Subsequent QA surveillance and observations by the lead foreman and the lead HP indicated improvement.
The extent of the audits and the qualification of the auditors appear adequate.
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Approximately ten QA surveillance performed of the radiation / chemistry and radwaste programs since June 1987 were reviewed by the inspectors.
Most surveillance were conducted for radioactive material shipments, radiological area access controls and applicable procedural surveillance requirements.
Responses to audit and surveillance findings appear timely and technically sound.
No violations or deviations were identified by the inspectors.
6.
Radiation Protection Procedures The inspectors reviewed the following radiation protection procedures to determine if they are consistent with regulatory requirements and good health physics practice.
No problems were noted.
BwRP 1120-2, Revision 2 Routine Plant Surveys BwRP 1140-1, Revision 2 Radiation Work Permit Program BwRP 1210-2, Revision 2 Exposure Review and Authorization BwRP 1220-5, Revision 3 Comparison of Personnel Dosimetry Results BwRP 1250-5, Revision 0 Filter Surveys BwRP 1280-3, Revision 2 Process Radiation Monitor Gas Grab Sampling BwRP 1280-5, Revision 0 Temporary and/or Aii.ernate Sampling Methods for General Atomic Process Radiation Monitors
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BwRP 1280-15T1, Revision 0 Atmospheric Tritium Calculation Form BwRP 1280-9, Revision 3 Process Radiation Monitor Particulate Filter and Iodine Cartridge Replacement BwRP 1310-1, Revision 2 Selection, Issuance, and Control of Radiological Respiratory Protection Equipment BwRP 1310-2, Revision 2 Maintenance and Care of Respiratory l
Protection Equipment BwRP 1310-12, Revision 3 Operational of Model TDA-50 Quantitative Aerosol Tester BwRP 1340-1, Revision 2 Personnel Monitoring for Internal Radioactive Contamination BwRP 1350-3, Revision 0 Calibration and Operation of Eberline Model RAS-1 Air Sampler
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BwRP'1350-8, R9 vision 0 Operatio~n andiCalibration of the
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Eberline.Moc.el;AMS-} Continuous A1r
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BwRP 1380-4, Revision'1 Calculation of MPC-h6urs and Organ
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f Dose Based on,WBC'Dat f
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BwRP 1410-1, Revis, ion 26 Protective Cibthfim,,'l I
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BwRP1460-3,Rev'ici8c:2'
Operation and Calibration of the IRT
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BwRP 1460-5, Revision 0 Surveying.ProtbctiveClothindUsing
the IRT acm-110 B
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l BwRP 1480-2, Revision 1 Personal External Contamination Surveys (HandHeldProbey i
BwRP 1520-4, Revision 4 Surveying Radioactive Material Shipments
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BwRP 1520 8, Revision 0 Survey and lease of Non-Radioactive
Waste from Radiologically Controlled q
Areas b
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f BwRP 1520-10, Revision 0 Scaling Factor Determination fjwRP 1540-1, Revision 1 Classification of Radioactive Waste for Near-Surface Burial
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BwRP 1750-5, Revision 0 Auxiliary Building Vent Stack Effluent Dose Rate Determination BwRP 1750-6, Revision 0 Radioactive Liquid E1fluents Dose Rate Determination BwRP 1750-6T4, Revision 0 Liquid Release Tanks Monthly i
j Compliance Verification 7.
TraigngandQualifications The inspectors reviewed the training and qualifications aspects of the licensee's radiation protection, radwaste, and transportation progr w,
including:
changes in responsibilities, policies, goals, programs, and methods; qualifications of newly hired or promoted radiation prot.ection personnel; and provision of appropriate radiation protection, redwaste, and transportation training for station personnel.
Also reviewed were management techniques used to implement these programs and experience concerning self-identification and correction of program implementation weaknesses.
l The station plans to continue using contractor personnel to augment the RP staff through Unit 2 startup.
Selection af contracted RP technicians includes a review of the technicians' resumes to determine conformance
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to ANSI /ANS 3.1 criteria for responsible technicians, and telephone L
interviews with the radiation protection or0anization of the plants where 1:
the individuals previously worked.
Resumes cf selected contractor I -
RP technicians currently employed at the station were reviewed by the i
inspectors.
All senior technicians appear to meet or exceed the
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technician selection criteria in ANSI /ANS 3.1.
Junior technicians not
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meeting ANSI 3.1 appear to have training and experience commensurate with
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their assigned duties.
After selected technicians report onsite, they must pass (minimum score 80%) a radiation protection screening exam
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consisting.of 25 multiple choice / calculational problems covering generic health physics topics.
The individuals then complete general employee i
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and site specific training, respiratory protection training, and an
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overview of applicable station Administrative and Radiation Protection Procedures.
Procedure overview training lasts about one day and is presented by the station's training department.
Inspectors selectively reviewed training and exam records; no problems were noted.
The inspectors reviewed the RCT training, retraining, and certification j
programs.
Initial RCT training consists of 18 weeks of classroom and m
on-.the-job (0JT) training conducted at the licensee's Production Training
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Center and at the station.
The station training department tentatively plans on expanding the OJT aspects of the training a couple weeks.
During 1987, the station established and began implementation of a-
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continuing training' program for RCTs.
Each RCT is scheduled for I
two weeks of continuing training per year which consists of informal, 1-3 hour duration, sessions covering various radiation protection related topics.
The station is developing lesson plans and procedure based instruction guides to improve and efficiently track the program's implementation.
In addition, the station recently initiated a required reading program for all RCTs covering various subjects of interest
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including NRC Information Notices, INP0 good practices, and licensee
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procedures.
Required readings are usually recommended by the training department or RCTs and must be approved by the Rad / Chem Supervisor.
New topics on the reading list must normally be completed by all RCTs within j
30 days.
Reading list completion is audited by the station's training
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department on a quarterly basis.
No problems were noted.
l No violations or deviations were identified.
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8.
External Exposure Controls j
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The inspectors reviewed the licensee's external exposure control and
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personal dosimetry programs, including:
adequacy of facilities, l
equipment, personnel, and procedures; adequacy of the dosimetry program to
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meet routine and emergency needs; and required records, reports, and
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notifications.
The licensee currently uses both vendor-supplied film badges and an
in-house TLD system for personal, primary dosimetry.
Whole-body TLD l
badges are assigned to station personnel and selected contractors.
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Vendor-supplied film badges are assigned to non-CECO personnel for
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whole-body monitoring, and to CECO and non-CECO personnel, as needed, for extremity monitoring and for whole-body neutron monitoring.
No j
exposures significantly above detectable levels have been reported.
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yQ addition, for each two-week badge period, the'_ licensee exposes (spikes)
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17 TLD badges and 17 whole-body: film. badges to specified doses of gamma q I;
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av) beta radiation. JThe 34 badges are then. processed with'the badges
[.rpsigned:to persons onsite.during'the badge period.
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After the badges are
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processed..the reported doses"for_-the spiked badges are statistically Lh/
--compared to.the administered doses. 'The inspectors reviewed selected
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records of the~ comparisons';.no significant-problems were noted.
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Q The inspectors inspected the Rad / Chem portable survey meter calibration f!!'
facility.' Beta / gamma Vurvey meters are calibrated with a Shepherd
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sc'el cqlibratogloaded with. a nominal 400-curie source and a nominal 130.ai%.trie soursce ofjesium-137.
Portable neutron meters are tp calibratedwitfdhe*,vyjatermoderated,cali_fornium-252 source.
Source
G calibrdfons :spd checks are performed by RCTs; electronic calibrations and checks are,perforred by Instrument Maintenance personnel.
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inspectote. reviewed-scurce calibration records fer selected high-range and lod-ra,nge ionization chambers, RM-14 and PRM-6 ratemeters with G-M-detectorsvand 6112 Teletectors with G-M ' detectors.
The source check of
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t Jeletector and use of several' survey meters by RCTs were also observed.
The-inspectors verified the operability.of friskers located throughout the station,.and of-various survey meters stored in the licensee's opeyatiuhal support center in theiservice building.. Meters in use. beyond
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the calibration due-dates were not observed.
No problems were identified.
l.t sf Self-deding pencil dosimeters are used for whole-body, secondary dosimetry.
.The' range of most of the dosimeters is 0-200 mR, but dosimeters with wtder franges are available.
After receipt of dosimeters from the vendor or beforeIuse of dosimeters that have been in storage for more than six months, the licensee subjects them to six acceptance tests designed tejidentify defective dosimeters.
Every six months, thereafter, the erformance af the dosimeters is verified with a check of drift and a p/eckofaccuracyusingasealedsource-ofcesium-137.
The inspectors
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c revie'wed selected records. of acceptance tests and performance
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' verifications; no problemt were noted, i
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An electronic, alarrring dosimetry system is currently in place at the
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st,ation for use during entry into high radiation areas.
The inspectors
reviewed selected records of calibrations of these dosimeters; no problems were noted.
The licensee is also currently evaluating another vendor's system.
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'Nei; violations or deviations were identified.
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9.
" Internal-Exposurt control and Assessment Theinbpectorsreviewedthelicensee'sinternalexposurecontroland i
assessment programs, including:
changes in facilities, equipment, a
personnel, respiratory protection training, and procedures affecting i
internal exposure control and personal assessment; determination whether engineering controls, respiratory equipment, and assessment of individuals
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i intakps meet regulatory requirements; planning and preparation for maintenance tasks including ALARA considerations; required records,
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reports, and notifications; and effectiveness of management techniques used to implement these programs and experience concerning self-identification and correction of program implementation weaknesses.
The licensee uses Self-Contained Breathing Apparatus (SCBAs) to limit internal exposure to persons working in areas with a real or potential problem from airborne radioactivity.
SCBAs and spare SCBA bottles are stored in approximately ten locations throughout the station for routine and emergency use during fires and fire brigade training, respiratory training, containment and confined space entry, and activation of the station emergency plan.
The inspectors accompanied an RCT on a weekly surveillance of SCBAs.
The intpectors observed the RCT verify the availability and operability of SCBAs in the operations support center, the control room, and a fire brigade cage in the turbine building.
The~ surveillance appears to have been performed in accordance with Procedure BwRP 1310-4, Revision 3.
No problems were noted.
Baseline Whole Body Counts (WBC) for CECO employees and contractors have i
been completed.
The WBC computer converts Maximum Permissible Body Burden (MPBB) to MPC-hours when the prescribed investigation level j
(3% MPBB for a single isotope; 5% MPBB total) is reached.
The
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conversion has been proceduralized and will be included in CEC 0's Standard Radiation Protection Procedures.
No violations or deviations were identified.
10.
Control of Radioactive Materials and Contamination The inspectors reviewed the licensee's program for control of radioactive materials and contamination, including:
changes in instrumentation, equipment, and procedures; effectiveness of survey methods, practices, equipment and procedures; adequacy of review and dissemination of survey data; effectiveness of methods of control of radioactive and contaminated materials; and management techniques used to implement the program and experience concerning self-identification and correction of program implementation weaknesses.
The licensee has an adequate number of whole body friskers (IPM-7)
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located at the exits of the Auxiliary Building 401' and 426' levels, at the exit from Unit 1 Fuel Handling Building, and at the exit from the l
Radwaste Building.
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Locations for the contaminated tool storeroom, the contaminated tool and equipment decontamination room, and the personnel decontamination room have been designated and construction is in progress.
No violations or deviations were identified.
11.
Maintaining Occupational Exposures ALARA The inspectors reviewed the licensee's program for maintaining occupational exposures ALARA, including:
changes in ALARA policy and i
procedures; worker awareness and involvement in the ALARA program; and
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establishment of goals and objectives, and effectiveness in meeting them.
Also reviewed were management techniques used to implement the program and experience concerning self-identification and correction of j
program implementation weaknesses.
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Two contractor engineering assistants (EAs) have been added to the ALARA group staff.
One contractor EA is the Contamination Control Coordinator
who supervises about 20 full-time contractor laborers doing decontamination.
The other_EA is a trainee who performs administrative ALARA functions.
ALARA awareness meetings have been held with all station work grnps and d
contractor supervisors.
The Station ALARA Review Committee has been i
meeting biweekly instead of monthly during startup of Unit 1.
Committee minutes for 1987 to date were reviewed by the inspectors; no problems were noted.
i The photofile of plant systems and equipment is complete.
The photofile i
is to be indexed and stored on a laser disc for use in maintenance and repair activities.
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Simulated radiological jobs have been conducted using step-off pads, protective clothing, and simulated external radiation and contamination.
Some minor problems were noted and corrected by the licensee.
Future radiological practice jobs will be video-taped for use during subsequent training sessions.
No violations or deviations were identified.
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NUREG-0737 Item II.F.1.1, High Range Noble Gas Effluent Monitors
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Section E.30.1 of Appendix E to the FSAR describes the post-accident high range noble gas effluent monitoring system.
The system consists of a General Atomic Wide Range Gas Monitor (GA WRGM) for the auxiliary building vent and area monitors (compensated for loss of low energy j
gamma radiation) mounted external to each of the four main steam lines
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upstream of the safety and relief valves.
The inspectors reviewed the status of the Unit 2 high range noble gas effluent monitors.
Preoperational testing, calibration, and procedures have been completed.
RCT training in the operation of these monitors has also been completed.
Records of calibrations and RCT training were selectively reviewed; no problems were noted.
This item is considered closed.
13.
Unit 1 Startup Tests The inspectors reviewed the results of a startup survey for Unit 1 which was conducted July 8-9, 1987.
BwSU PS-33 Radiation Surveys during Power Ascension conducted at 7% power.
j Test results were reviewed; no l
problems were noted.
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Since startup surveys made at Byron 1 and 2 showed that neutron dose levels exceeded acceptance criteria at several Radiation Base Points (RBP), Startup Test BwSU-PS-33 was changed by a Test Change Request (TCR)
to eliminate the test acceptance criteria for RBPs where neutron dose levels are measured.
Neutron radiation measurements taken during the startup test will be used by RP personnel to make neutron dose maps.
The Corporate engineering study (AIR-6-85-0020) discussed in the Byron Inspection Reports No. 50-454/87034(DRSS); No. 50-455/87032(DRSS) will include resolution of the neutron streaming problem at Braidwood.
This matter was discussed during the exit meeting and will be reviewed during a future inspection.
(456/87034-01; 457/87032-01)
No violations or deviations were identified.
14.
NRC Information Notices The inspectors reviewed the licensee's internal responses to selected NRC Information Notices.
The licensee's evaluations, conclusions, and actions appear appropriate and adequate.
The following notices were
reviewed.
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No. 86-41_:_
Evaluation of Questionable Exposure Readings of Licensee i
Personnel Dosimeters.
For each two-week badge period, the licensee compares the individual's film or TLD badge reading with the individual's self-reading dosimeter readings.
If the readings differ by at least l
100 mrem, and is greater than 130% or less than 65% of the film or TLD reading, the licensee conducts an investigation.
No. 86-46:
Improper Cleaning and Decontamination of Respiratory Protection Equipment.
The licensee has included in the lesson plans fcr annual RCT retraining a vendor-supplied video tape that demonstrates the proper disassembly and cleaning methods for the vendor-supplied equipment.
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Only manufacturer-approved cleanser is used during cleaning.
No. 86-103:
Respirator Coupling Nut Assembly Failures.
The licensee uses Ultra-Vue respirators; however, the coupling nut used with the licensee's respirators are the original-design, sonic-bonded type, not the new and now discontinued, snap type, with which the Pilgrim Station experienced several' failures.
No. 87-03:
Segregation of Hazardous and Low-Level Radioactive Wastes.
The licensee has procedures for radwaste packaging that direct personnel to segregate hazardous and radioactive wastes.
A list of chemicals unacceptable for packaging with radwaste is included in the procedures.
15.
Unit 1 Containment Area Monitor l
Recently, the licensee has experienced spurious spikes on two redundant area monitors, 1RE-A011 and 1RE-AR012.
The monitors are intended to
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respond to high containment radioactivity.
According to the licensee's l
procedures, the alarm setpoint of the monitors is 100 mR/hr.
After the
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setpoint is reached the isolation signal closes the normal and mini-flow
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containment isolation valves.
On September 29, 1987, and on October 2,
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1987, a spike on 1RE-AR012 occurred of sufficient intensity to generate
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the~ containment isolation signal. ~All containment-isolation' valves were closed!at the time of the spikes.
The licensee is investigating to determine the cause of the~ spikes.
NRC resident inspectors will track-the licensee's investigation.
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No violations or deviations were identified.
.16.
Solid Radioactive Waste The= inspectors reviewed the licensee's. solid radioactive waste management program, including:. determination whether changes to equipment and procedures were in accordance with 10 CFR.50.59;' adequacy of. implementing procedures to properly classify and' characterize waste,
' prepare' manifests, and mark packages; overall performance of.the process control and quality assurance programs; adequacy of required records,
. reports,'and notifications; and experience concerning identification and.
correction of' programmatic weaknesses.
The licensee's facilities for collection, concentration, solidification, packaging, and shipment of solid radioactive waste are nearly complete; testing of.these systems is in progress.
The Stock solidification system is being removed..The station plans on utilizing contractor service to process spent resins-and concentrates.
A Dry Active Waste (DAW) sorter station has been established to segregate
" clean" DAW.
A sorting table and monitor has been located on the 383' elevation of the auxiliary building in the former Stock drumming area.. A small amount of DAW has been generated to date.
There have been no shipments of DAW to burial sites.
No violations or deviations were identified.
17.
Liquids and Liquid Radioactive Wastes The inspectors reviewed the licensee's reactor liquids and liquid radwaste management programs, including:
determination whether changes to equipment and procedures were in accordance with 10 CFR 50.59; determination whether reactor liquids meet chemical and radiochemical requirements; determination whether liquid radioactive waste effluents were in accordance with regulatory requirements; adequacy of required records, reports, and notifications; determination whether procers and
' effluent monitors are maintained, calibrated, and operated as required;
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and experience concerning identification and correction of programmatic l
weaknesses.
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Licensee facilities for the collection, storage, and release of liquid i
radioactive waste are complete.
Liquid releases are being made; I
approximately 1.6 million gallons of liquid waste was released during l
September 1987.
The inspectors reviewed selected records of liquid l'
effluent sampling and the semiannual effluent report for the first
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l half of 1987.
Pathways sampled and analyses performed appear to comply with the requirements of Technical Specification Table 4.11-1.
No problems were noted.
No violations or deviations were identified.
18.
Gaseous Radioactive Waste-The inspectors reviewed the licensee's gaseous radwaste management program, including:
determination whether changes to equipment and procedures were in accordance with 10 CFR 50.59; determination whether gaseous radioactive waste effluents were in accordance with regulatory requirements; adequacy of required records, reports, and notifications; determination whether process and effluent monitors are maintained, calibrated, and operated as required; and experience concerning identification and correction of programmatic weaknesses.
Construction and testing of licensee facilities for the collection and storage of gaseous radioactive waste has been completed.
Procedures for processing gaseous radwaste are complete.
The waste gas storage tanks are being used to collect waste gas; however, no gaseous radwaste releases have been made to date.
No violations or deviations were identified.
19.
Transportation of Radioactive Materials The inspectors reviewed the licensee's transportation of radioactive materials program, including:
determination whether written implementing procedures are adequate, maintained current, properly approved, and acceptably implemented; determination whether shipments are in compliance with NRC and 00T regulations and the licensee's quality assurance program; determination if there were any transportation incidents involving licensee shipments; adequacy of required records, reports, shipment documentation, and notifications; and experience concerning identification and correction of programmatic weaknesses.
Records of radioactive material shipments made during 1987 were reviewed.
In 1987 to date the licensee has made 12 shipments of small sources and process samples shipped as excepted radioactive material, limited quantity, to other licensees and to contractor laboratories.
No problems with shipment documentation and quality control / assurance were
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identified.
Shipments of radioactive material appear to have been made j
in accordance with the requirements of 49 CFR 170-179, and the l'icensee's transportation procedure BwRP 1520-1, Revision 3, Offsite Shipment of Radioactive Material.
I No violations or deviations were identified.
20.
Exit Meeting The inspectors met with licensee representatives (denoted in Section 1)
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at the conclusion of the inspection on September 30, 1987.
The scope and the findings of the inspection were summarized.
The inspectors also l
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discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the-inspectors during the inspection.
The licensee identified no such documents / processes as
. proprietary In response to certain matters discussed by the inspectors, the licenseo:
a.
Acknowledged the inspection comments concerning the RCTs procedural adherence and attention to detail.
(See Section 5)-
!
b.
Acknowledged the inspectors comments concerning the open item on neutron streaming.
(See Section 13)
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