IR 05000400/1986043
| ML18004A341 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/15/1986 |
| From: | Collins T, Cooper W, Hosey C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18004A338 | List: |
| References | |
| TASK-2.B.2, TASK-2.F.1, TASK-3.D.3.3, TASK-TM 50-400-86-43, IEC-80-14, IEIN-80-22, IEIN-81-07, IEIN-81-26, IEIN-81-7, IEIN-82-18, IEIN-83-05, IEIN-83-14, IEIN-83-5, IEIN-83-59, NUDOCS 8607300138 | |
| Download: ML18004A341 (19) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 JUl. Cs tSS6 Report No.:
50-400/86-43 License No.:
CPPR-158 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris
Inspection Conducted:
June 9-13, 1986 Inspectors: ~
T.. Collins T. Cooper Accompanying Personnel:
C.
H. Bassett C.
M. Hosey r>-
,Date Signed
" 7-l< cP4 Date Signed Approved by:
C.
M.
H ey, ection Chief 7 /
ate Signe Division of Radiatio Safety and Safeguards SUMMARY Scope:
This routine, announced inspection was in the area of radiation protection including organization and management controls, training and qualifications, internal and external exposure controls, control of radioactive materials, facilities and equipment, program for maintaining radiation exposure as low as reasonably achievable (ALARA), solid radwaste systems, transportation of radioactive material, inspector followup items, and IE Information Notices.
Results:
No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. L. Willis, Plant General Manager
- J. L. Harness, Assistant Plant General Manager
"J.
R. Sipp, Manager, Environmental and Radiation Control
"J.
W. McDuffie, Supervisor, Radiation Control
- A. Poland, Project Specialist, Radiation Control
"D. L. Beidelman, Senior Specialist, ALARA
'D.
C. Whitehead, Operations Quality Assurance (QA) Supervisor
"C.
K. Wright, Specialist Regulatory Compliance Other licensee employees contacted included radiation control foremen and health physics technicians.
NRC Resident Inspector G. Maxwell, Senior Resident Inspector S. Burris, Resident Inspector
~Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 13, 1986, with those persons indicated in Paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings.
Licensee
. representatives acknowledged the inspection findings and took no exceptions.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
4.
Organization and Management Controls (83522)
The inspector reviewed the assignment of responsibilities for the management and implementation of radiation control, chemistry and environmental control programs.
Implementation of the programs at the plant is assigned to the Manager, Environmental and Radiation Control (E&RC).
Other groups in the corporate structure are assigned responsibilities for assistance, review and offsite programs.
The responsibilities of Manager, E&RC and the E&RC organization are consistent with FSAR Section 12.5. /
b.
Responsibilities for the programs are assigned in various documents at both the corporate and plant level.
At the corporate level, the relevant documents are the
"Conduct of Nuclear Operations Manual,"
which was approved at the Executive Vice President level, and the
"Radiation Control and Protection Manual," which was also approved at the Executive Vice President level.
The
"Radiation Control and Protection Manual" states that the Manager, E&RC is responsible for the health.physics program.
The
"Conduct of Nuclear Operations Manual" contains the Corporate Health Physics Policy Statement, which was approved by the company President, and the Corporate ALARA Program.
The "Radiation Control and Protection Manual" includes the Respiratory Protection Policy Statement.
'.
At the plant level, the programs are implemented by a
series of procedures contained in the Plant Operations Manual, and include Administrative Procedures (AP), Plant Program Procedures (PLP),
Plant General Orders (PGO),
E&RC Procedures (ERC),
and Health Physics (HPP),
Chemistry (CRC),
and Dosimetry (DP)
Procedures.
The APs and PLPs assign responsibilities to member s of the plant staff, consistent with the corporate documents.
No violations or deviations were identified.
Facil'ities (83527)
FSAR Section 12.5.2 describes the facilities to be used in conjunction with the radiation protection program.
The inspector toured the facilities with licensee representatives and reviewed the status of the following facilities:
(1)
Portable instrument calibration The facility is functional and has two Cs-137 calibration systems.
Other calibration sources are being obtained.
A licensee representative stated that a neutron calibration source would not be procured; neutron survey instruments will be sent to the vendor for calibration.
(2)
Equipment decontamination Decontamination equipment has been received and is in place.
However, the equipment decontamination facility will be relocated to service the hot machine shop.
This facility is incomplete.
(3)
Respiratory protection device cleaning
-
The facility for cleaning, sanitizing and surveying respiratory protection equipment has been designated but the equipment has not been installed.
This facility is incomplete.
(4)
Laundry - Washers and dryers have been received and are in place.
However, the equipment has not been connected.
This facility is incomplet /
'R I
(5)
First aid room - First aid facilities for treating potentially contaminated pati ents are being re 1 ocated.
Thi s fac i l ity i s incomplete.
(6)
Change room and personnel decontamination Separate facilities for men and women were provided and complete.
However, some modifications.will be made as the result of changes to other adjoining facilities.
(7)
Respirator fitting A fit-testing booth and associated equipment to perform quantitative testing is installed and operable.
The licensee is conducting respirator fitting for employees.
(8)
Body Burden Analyzer The facility is set up and includes two Body Burden Analyzer chairs, each with a computer-based analyzer.
The licensee is conducting baseline analyses of employees at present.
b.
In reviewing the control point to the Radiation Control Area (RCA),
a licensee representative informed the inspector that changes were planned in the area to improve the traffic flow and control at the RCA entrance.
These changes will involve relocation of walls and doors.
The inspector stated to licensee management that these changes should be completed prior to establishing the RCA in anticipation of fuel loading to minimize both confusion in the traffic flow and cleanliness problems within the RCA.
This was acknowledged by licensee management.
C.
As part of the respiratory protection program, air-supplied devices may be used.
A licensee representative informed the inspector that the breathing air connections and manifolds and air hoses would be equipped with distinctive fitti,ngs which are not used at any other point in the plant.
This should preclude connections of other equipment or tools t'o breathing air systems.
The fittings are onsite and will be installed in the future.
No violations or deviations were identified.
Equipment (83525, 83526, 83527)
The licensee has a partial supply of devices and accessories onsite for the respiratory protection program.
These include Self-Contained Breathing Apparatus (SCBA),
spare air cylinders, different models of respirators, air supply hoses, and air manifold assemblies.
Additional quantities are on order or will be procured, including air-supplied hoods and respirator filters.
A licensee representative stated that the projected inventory would be available prior to fuel loading.
The inspector reviewed the projected inventory and had no further questions at this time.
b.
FSAR Section 12.5.2 discusses equipment and instrumentation for air sampling and radiation surveys.
The inspector reviewed the inventory
on-hand and discussed planned inventory levels with licensee representatives.
The general types of instruments described in the FSAR were on-hand or being procured, with quantities generally in excess of the levels listed in the FSAR.
C.
The inspector reviewed the inventory of temporary shielding materials, such as lead bri'cks, lead sheets and lead blankets.
These materials are onsite.
Additionally, the procedures have been prepared and issued for the installation of temporary shielding (HPP-015).
d.
The licensee has,ordered temporary ventilation units which will provide fi 1 tered exhaust from r adi ol'ogi cal ly control 1 ed areas.
These uni ts have not been received.
No violations or deviations were identified.
7.
Internal Exposure Controls (83525)
The internal exposure control program was reviewed for adherence to ANSI N343-1978 and Regulatory Guide 8.9.
A whole body counting system is available and has thyroid, lung, and lower torso counting capabilities.
Dosimetry procedure DP-103, Personnel Whole Body Counting states that all personnel who require entry into bioassay areas must participate in the bioas'say program.
Bioassay area is defined by the licensee as an airborne radioactivity area, potential airborne radioactivity area, or any other area where unencapsulated radioactive material is present in a form and quantity such that the area has significant potential for becoming an airborne radioactivity area (generally greater than 50,000 dpm/100 cm~).
These licensee employees must receive a baseline whole body count and, at a
minimum, an annual count.
The inspector determined by discussion with licensee representatives that all personnel who require entry into bioassay areas have not yet received their baseline whole body count.
Licensee personnel informed the inspector that the required baseline whole body counts would be performed prior to fuel load.
No violations or deviations were identified.
Respiratory Protection Program (83525)
The respiratory protection program was evaluated on the bases of training program, medical qualification, procedures, equipment, engineering control and maintenance program.
The licensee respiratory program is addressed in Procedure AP-512 entitled
"Use of Respiratory Equipment" and PLP-510
"Respiratory Protection Program."
During the course of this inspection, it was determined that the responsibility of the respiratory protection program,is placed with the Manager of Environmental and Radiation Control.
Day-to-day activities will be the responsibility of the Project Specialist.
At the time of this
inspection, Radiation Control technicians were assigned the responsibility for operation of the quantitative respirator fitting equipment, in addition to being responsibl e for pr ocurement, testing, survei 1 lance, and in a
general sense, issuance of respirators.
. Decontamination and sanitizing of used respirators is to be performed on site.
Respiratory protection training is not given to all radiation workers.
Those individuals who may be expected to use respiratory protective equipment and supervisors who direct workers requiring respirators are given training.
The training consists of a lecture, visual aids, and practice in donning and removal of respirators.
A written examination is given at the conclusion of this training.
Medical examinations are performed by a
licensed physician.
Medical certification for all respirator users is required annually.
There appears to be adequate numbers of respirators'or the start-up phase of this unit.
The licensee has purchased approximately 1300 respirators which includes 85 self-contained breathing units and 120 breathing air bottles.
The licensee has purchased a breathing air system to fill breathing air bottles on site.
This system was not operational at the time of the inspection, however, the licensee informed the inspector that a
vendor representative was scheduled to be onsite during the week of June 10, 1986, to begin startup of the system.
No violations or deviations were identified.
9.
Procedures Review (33522, 83523, 83524, 83525, 8356, 83527, 83528, and 86740)
The following procedures were reviewed for technical adequacy and adherence to NRC regulatory requirements:
AP-502 AP-504 AP-506 AP-509 AP-510 AP-512 AP-513 AP-514 AP-520 DP-001 DP-003 DP-004 DP-005 DP-009
ALARA SUBCOMMITTEE
ADMIN CNTRL fOR LOCKED HI RAD AREAS
CONDUCT OF OPERATIONS-RC
ALARA IMPROVEMENT PROGRAM
RADIATION EXPOSURE BUDGETING 1"
USE OF RESPIRATORY EQUIP.
RADIOLOGICAL DEFICIENCY NOTICES
ALARA JOB EVALUATIONS
RC/ALARA REVIEW OF PLANT PROCEDURES
DOSIMETRY ISSUE
PERSONNEL EXPOSURE INVESTIGATION
.UPDATING DOSE RECORDS
CALC.
OF NEUTRON DOSE
TLD BADGE EXCHANGE
DP-010 DP-011 DP-012 DP-100 DP-103 DP-110 DP-113 ERC-104 ERC-110 HPP-005 HPP-020 HPP-030 HPP-035 HPP-060 HPP-064 HPP-066 HPP-067 HPP-069 HPP-103 HPP-111 HPP-113 HPP-115 HPP-116 HPP-120 HPP-121 HPP-122 HPP-123 HPP-124 HPP-125 HPP-126 HPP-127 HPP-128 HPP-129 HPP-130 HPP-131 HPP-150 HPP-300 HPP-302 HPP-305 HPP-306 HPP-307 HPP-308 HPP-310 HPP-353
, HPP-453, HPP-461 HPP"467
1
2
0
1
1
0
1
1
1
0
0
0
0
1
0
~
0
0
0
0 SPECIAL DOSIMETRY ISSUANCE TERM. /DEACTIVATION OF EMPLOYEES DOSE LIMIT EXTENSION AUTHORIZATION SKIN DOSE FROM CONTAMINATION PERSONNEL WHOLE BODY COUNTING COL.
& HANDL. OF SAMP.
FOR BIOASSAY UPDATING WHOLE BODY COUNT RECORDS CONTRACT E&RC TEC QUAL & TRNG E&RC KEY CONTROL SCHEDULING ROUTINE ACTIVITIES RADIATION WORK PERMITS MAT. RELEASE FROM A RESTRICTED AREA POSTING/BARRICADING RAD AREAS RADIATION & CONTAMINATION SURVEYS CALC. & DOCUMENTATION OF MPC HOURS PREP AND ANALYSIS OF AIR SAMPLES COLLCT. -PART/IODINE AIR SAMPLES COLLECT/ANAL. OF NOBLE GAS SAMPLES CURIE DETERMINATION IN R.A.M.
PACKAGING OF COMPACTABLE WASTE RECEIPT OF RAD. MATERIAL CLASS.
OF RAD MATERIAL FOR SHIPMENT CLASS OF RAD MATERIAL FOR BURIAL SHMT OF EMPTY RAD MATERIAL PACKING SHMT OF INSTRUMENTS
&. ARTICLES SHMT OF LIM QUAN OTHER THAN DISPOSAL SHMT OF LSA-TYPE A TO BARNWELL SC SHMT OF LSA-TYPE B TO BARNWELL SC SHMT OF TYPE A TO BARNWELL SC SHMT OF TYPE B TO BARNWELL SC SHMT OF HWY RT CONT.
TO BARNWELL SC SHMT OF LSA-TYPE A TO RICHLAND, WA SHMT OF LSA-'TYPE A OTHER THAN DISP
~
SHMT OF TYPE A OTHER THAN DISPOSAL SHMT OF TYPE B OTHER THAN DISPOSAL RECEIPT/SURV:NEW FUEL/SPEC.
NUC.MAT QUANT/QUALIT FIT TESTING SELECTION & ISSUE OF RESP.
EQUIP.
CLEANING/DISINFECTING RESP.
EQUIP.
MAINT/INSP/INVEN OF RESP EQUIP LEAK TESTING RESPIRATORS/FILTERS TEST BREATH AIR-GRADE D/RADIOISOTOPE OP.OF EAGLE SCBA FILLTING SYS.
OPERATION OF THE EIC RO-2 and RO-2A OPERATION OF EBERLINE 6112
,OPERATION OF EBERLINE E-130 OPERATION OF EBERLINE E-520
PLP-501
ALARA PROGRAM PLP-510
RESPIRATORY PROTECTION PROGRAM PLP-511 1 'AD CONTROL 5 PROTECTION PROGRAM SIC-004
SIC-102
SIC-104
SIC-105.
SIC-109
CALIBRATION OF SRPD CALIBRATION OF EBERLINE 6112 B
CALIBRATION OF R0-2, RO-2A CALIBRATION OF EBERLINE E-520 CALIBRATION OF EBERLINE E-130 The 'nspectors suggested corrections, changes, and additions to several procedures which were acknowledged'y the cognizant supervisors.
No violations or deviations were identified.
10.
Solid Radwaste Processing and Disposal (84522)
The inspector discussed the plans for solid radwaste processing and disposal with licensee representatives and was informed by licensee management that an onsite mobile solidification system was to be contracted from Chem Nuclear Systems, Inc. (CNSI).
The inspector reviewed the approved contract between CPL and CNSI which appeared to be adequate for initial set up and operation of the mobile solidification system.
The inspector stated that prior to installation and operation of the system,
CFR 50.59 would require that the licensee perform a safety evaluation to assure that an unreviewed safety question did not exist.
The inspector stated that the safety evaluation would be reviewed during future solid waste inspections.
During a tour of the waste processing facility, the inspector noted that the waste compactor was located in close proximity to a
heavily trafficked areas.
The inspector also noted that no enclosure had been constructed around the compactor nor was there adequate ventilation for conducting compacting operations safely.
A licensee representative stated that the intent was not to use the waste compactor as designed, but was to transport low-level radwaste to a vendor who would compact the waste for the facility.
The inspector stated that sending low-level waste to a vendor for compacting was adequate, however, prior to use of the licensee's compactor, design changes should be incorporated to enclose the compactor and install adequate ventilation.
The licensee acknowledged the inspector
'
comments and stated that this would be reviewed.
The inspector reviewed the licensee's waste solidification system as described in the FSAR, Section 11.4.
The inspector stated that it appeared that use of the present system would create a large increase in the volume of radwaste shipped offsite for burial.
The increase would be due to the use of cement in solidification of spent ion exchange resins.
The inspector stated that the licensee should review the feasibility of solidification process, as designed, from an economic standpoint as well as a
volume reduction standpoint.
The inspector stated that this area would remain as
an inspector followup item to be reviewed during future inspections (50-400/86-43-01).
The licensee informed the inspector that other methods for disposal are being evaluated and that there is a contract with Chem Nuclear Systems, Inc.
to provide a solidification process if it is decided CNSI's process is to be used.
No violations or deviations were identified.
Transportation of Radioactive Material (86740)
CFR 71.5 reqquires a
licensee to prepare shipments of radioactive material in accordance with Department of Transportation (DOT) regulations.
The inspector reviewed the procedures the licensee will use to prepare and transport radioactive material to a licensee burial facility.
The inspector also verified that the licensee is a registered user for NRC packages which they intend to use for shipping radioactive material.
CFR 20.311 requires a licensee who transfers radioactive waste to a land disposal facility to prepare all waste so that the waste is classified in accordance with 10 CFR 61.55 and meets the waste characteristic requirements of
CFR 61.56.
It further establishes specific requirements for conducting a quality control program and for maintaining a manifest tracking system for all shipments.
The inspector reviewed appropriate plant procedures for the packaging, classifying, and tracking of radioactive waste shipped to low-level waste buri al fac i 1 ities.
The inspector reviewed and discussed with licensee representatives the methods to be used to assure that waste was properly classified, met the waste forms and characteristics required by
CFR 61 and met, the disposal site license conditions.
The inspector reviewed training records of the personnel (RC Technicians)
assigned the task of packaging and shipping radioactive materials.
The training of the RC Technicians appeared to be adequate.
"Generation of Radwaste,"
requires licensees to provide training to all personnel who process, package, and ship radioactive material for transport.
Radwaste Operators have not received any training in the areas of packaging and shipment of radioactive material.
The inspector informed licensee management that this item would remain as an inspector followup item and would be reviewed during subsequent inspections.
(50-400/86-43-02)
No violations or deviations were identified.
Radiation Monitoring System (RMS) (83526)
The inspector discussed with licensee representatives the status of the area radiation monitors (ARM).
The inspector
'was informed that 75 out of 101
area radiation monitors have been installed, functionally tested and calibrated.
FSAR Section 11.5.2.3 and 12.3.4 requires the ARM to be operational prior 'to fuel loading.
Licensee representatives stated that the RMS would be completed prior to fuel load.
The inspector informed licensee representatives that thi s item would remain as an inspector followup item and would be reviewed during subsequent inspections.
(50-400/86-43-03)
No violations or deviations were identified.
Training and gualifications (83523)
The qualifications of 23 licensee health physics technicians, 13 contract health physics technicians and four health physics foreman were reviewed against ANSI 3. 1-1979 draft criteria. 'his was accomplished by records review and discussions with cognizant licensee personnel.
The technician staffing appears to be adequate to support a
single unit PWR.
Health physics management stated that health physics technicians on staff with little prior experience at an operating power plant are being sent to one of the licensee's other sites for additional training and experience.
The inspector reviewed the licensee's General Employee Training (GET)
programs,
,Levels I, II, and III.
The program appeared to meet the recommendations of Regulatory Guide 8.27.
The program is a combination of lecture, testing, and practical factors training.
The inspector reviewed the resume of the individual responsible for presenting GET Level I and II training, and determined that the instructor appeared to have adequate health physics experience and educational background.
Any changes made to the health physics portion of the GET must be approved by the ESRC Manager.
No violations or deviations were identified.
External Occupational Exposure Control and Personal Dosimetry (83524)
The licensee's external exposure control and personal dosimetry program was reviewed against criteria contained in:
CFR 20, "Standards for Protection Against Radiation" Licensee Proposed Technical Specification 6.0, "Administrative Controls" FSAR Chapter 12, "Radiation Protection Program" Shearon Harris Radiation Protection Program Manual The licensee's performance relative to these criteria was determined by discussions with selected numbers of the radiation protection staff, tours of. the facilities, and review of procedures and representative records.
The dosimetry group is one of four groups making up the Health Physics organization.
The dosimetry foreman reports to the Radiation Control Superviso The Thermoluminescent Dosimeters (TLD) dosimetry system i s a
Panasonic system with dosimeters designed for beta, gamma and neutron whole body monitoring and extremity dosimetry.
At the time of the inspection, the licensee had approximately 2,000 TLDs onsite and available for use.
The dosimetry procedures were reviewed for adequacy, detail and clarity.
CFR 20. 101(b)(3)
requires the licensee to determine an individual's documented occupational dose to the whole body on an NRC Form 4 or equivalent record prior to permitting the individual to exceed the limits of 20. 101(a).
The necessary documentation for NRC Form 4's is currently being completed by the licensee.
The inspector reviewed evaluations performed by the licensee's architect/engineer (A/E) in response to a
licensee concern dealing with unplanned occupational exposures associated with incore instrumentation in the reactor containment building.
Three shielding evaluations have been performed, which included incore detector and drive cable dose rates, normal refueling shielding analysis and a ten-year refueling shielding analysis.
These analyses are detailed in letters from Ebasco Services Incorporated to the licensee; EB-C-19418 dated September 4,
1985; EB-C-19822 dated December 13, 1985 and EB-C-19938 dated January 28, 1986
~
At the time of the inspection, the licensee was still in the process of evaluating the recommendations made by Ebasco.
However, licensee management stated that the proposed shielding modifications would be completed prior to fuel load.
The licensee's control of radiation levels in the subject areas and implementation of controls to maintain exposures associated with the subject systems ALARA was identified as an inspector followup item to be reviewed during future inspections (50-400/86-43-04).
The inspectors noted during plant tour s of the Maste Handling Facility and the Auxiliary Building that numerous doors have not yet been installed to control access to high radiation areas which may be as required by Technical Specification 6. 12 after plant startup.
The licensee informed the inspector that a Field Change Request (FCR)
No. AS-9613, Revision 1, dated June 6,
1986, has been written to complete the installation of doors for areas which have been identified as potential high radiation areas.
The inspector determined that 40 doors out of 134 still have not yet been installed.
The inspector stated that this item will remain as an inspector followup item and would be inspected during subsequent inspections (50-400/86-43-05).
No violations or deviations were identified.
ALARA Program (83528)
The inspector reviewed the applicable procedures implementing the licensee's ALARA program for adequacy and scope.
Based on that review, the licensee's efforts appeared consistent with FSAR commitments and Regulatory Guide 8.8 guidance.
The licensee's onsite engineering group has developed an ALARA design guide which will provide design personnel with guidance for design and
modifications of radioactive systems to ensure that occupational radiation exposure will be ALARA.
On January 17, 1986 and March 4, 1986, the Corporate Health Physics group performed system walkdowns in an attempt to identify ALARA problem areas.
The items identified during these walkdowns are currently under.review by plant management, or are in the process of being corrected.
No violations or deviations were identified.
16.
Inspector Fol 1owup Item (92701)
(Closed) IFI 85-40-01, IE Circular 80-14 Cross Contamination of Potable and Demineralized Water Systems.
The inspector reviewed licensee procedure CRC-001 which addresses sampling both potable and demineralized water systems on a quarterly frequency to determine that radioactivity is not present in these systems.
(Closed)
IFI 85-16-32, TMI Item II.B.2:
Plant Shielding to Provide Access to Vital Areas.
The shielding review concluded that no additional shielding was required since the plant was designed to mitigate major design basis events without requiring outside access.
Dose rates in the control room and the technical support center were estimated to be less than the limit specified by'UREG-0737 for areas requiring continuous occupancy.
(Open)
IFI 85-16-16, TMI Item II.F. 1.3:
Containment High Range Radiation Monitors.
The inspector verified the installation of these monitors in accordance with NUREG-0737 criteria.
However, calibration of the monitors had not taken place at the time of the inspection.
(Closed)
IFI 85-16-28, TMI Item III~ D.3.3:
Improved Plant Iodine Instrumentation Under Accident Conditions.
'The inspector verified that equipment was available for in-plant iodine monitoring and that training programs were in place for instruction of station health physics personnel addressing this, subject.
17.
IE Information Notices and Circulars (92717)
The following IE Information Notices were reviewed to ensure receipt and review by appropriate licensee management.
81-07, Control of Radioactive Contaminated Material 83-14, Dewatered Spent Ion-Exchange Resin Susceptibility to Exothermal Chemical Reaction 83-05, Approval for Disposal of Very Low-Level Radioactive Waste 80-22, Breakdowns in Contamination Control Programs
82-18, Assessment of Intakes of Radioactive Material of Workers 81-26, Placement of Personnel Monitoring Devices for External Exposure 83-59, Dose Assessment for Workers in Non-Uniform Radiation Fields 18.
Allegation Followup (990j.4)
a.
Allegation Alleger stated that the licensee is storing and/or burying nuclear waste onsite.
Discussion During the reivew of this allegation, the inspectors found that the licensee holds a
byproduct material's license number 32-23027-01, allowing possession of sealed, slab, and solid radioactive sources at the facility.
The licensee had dedicated approximately 120 acres on the owner controlled property for the burial of non-radioactive wastes.
Although the first 20 acres to be used has been designated, no burial has taken place at the site.
~Findin The allegation was not substantiated.
b.
Allegation Alleger stated that the licensee was falsifying NRC Form-4's.
Discussion The inspector requested that a dosimetry technician detail the process used to issue a TLD to a new licensee employee.
The technician stated that if the new employee indicated that he had prior exposure, the employee would be requested to fill out and sign a
TLO Issue Sheet.
The employee would also be requested to fill out information release forms for facilities where the prior exposure was received.
The release forms would be mailed to the facilities to obtain the individuals'rior exposure history.
When the exposure history was received by the licensee, a
NRC Form 4 would be completed.
The new employee would then be called back to the Dosimetry Office and asked to verify that the information contained on the NRC Form 4 was complete and accurate.
If the new employee agreed that the information was complete and accurate, the employee would be asked to sign the form indicating certification of the information.
Because the alleger was a cur rent licensee employee, the Form-4 was completed first, when exposure data was received from prior employers,
a TLD issue sheet was completed when the indvidual was to be required to wear a TLO.
l The. inspector selectively reviewed NRC Form-4's on file and determined that NRC Form-4's were completed as required.
~Findin The allegation was not substantiate l Q
~