ML20151N671
| ML20151N671 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 12/03/1985 |
| From: | Chaney H, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20151N659 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-2.F.2, TASK-TM 50-458-85-73, NUDOCS 8601030049 | |
| Download: ML20151N671 (15) | |
See also: IR 05000458/1985073
Text
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APPENDIX C
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-458/85-73
License: NPF-40
Docket:
50-458
Licensee: Gulf S'tates Utilities (GSU)
ATTN: William J. Cahill, Jr.
,
Senior Vice President
River Bend Nuclear Group (RBNG)
P.O. Box 2951
Beaumont, Texas 77704
Facility Name: River Bend Station (RBS)
Inspection At:
River Bend Station, St. Francisville, Louisiana
Inspection Conducted: October 2
through November 1, 1985
12.!3kI
Inspector:
h
H. Chaney( ladiation Speciali
Date
Facilities Radiological Protection Section
- &[J[f3
Approved:
9
E
~
B. Murray, Chief, Fac ities Radiological Protection
Date
Section
Inspection Summary
Inspection Conducted October 28 through November 1, 1985, (Report 50-458/85-73)
Areas Inspected:
Routine, unannounced inspection of the licensee's radiation
protection (RP) program, including: organization and management controls, RP
staff training and qualifications, and the ALARA program; actions on previous
inspection findings; and implementation of certain NUREG-0737 requirements.
The inspection involved 41 inspector-hours onsite by one NRC inspector.
Results: Within the areas inspected, two violations and one deviation were
identified.
(see paragraph 4).
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8601030049 851230
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DETAILS
1.
Persons Contacted
GSU
- W. Cahill, Jr. , Senior Vice President', RBNG
- J. Deddens, Vice President, RBNG
- T. Plunkett, Plant Manager
- T. Crouse, Manager, Quality Assurance (QA)
- P.
Tomlinson, Director, Quality Services
- P. Graham, Assistant Plant Manager
- E. Cargill, Radiological Programs Supervisor
- B. Hey, Licensing Engineer
- S. Desai, Chemistry Group Engineer
- R. Coppo, Senior Projects Mechanical Engineer
- R. Horn, Nuclear Training Department (NTD) Representative
- J. Spivey, QA Engineer
- K. Suhrke, Manager, Projects Planning and Coordination
- D. Seymour, Compliance Analyst
J. Cadwallader, Emergency Planning (EP) Supervisor
S. Marino, NTD Training Assistant
D. Gipson, Assistant Plant Manager
C. Rohrman, RP/ Chemistry Training Coordinator
C. Edwards, Senior Radiation Protection Technician (RPT)
T. Sloan, Senior RPT
K. Varnado, RPT
R. White, RPT
Others
- D. Chamberlain, NRC Senior Resident Inspector
J. Grant, Test Engineer Consultant
T. Loudenslager, EP Consultant
D. Simpson, EP Consultant
- Denotes those present at the exit interview on November 1, 1985.
The NRC inspector also interviewed several other licensee
employees including QA/QC, training, chemistry, and RP personnel.
2.
Licensee Actions on Previous Inspection Findings
(Closed) Open Item (458/8406-25):
NUREG-0737, Item II.F.1-2,
Plant Effluent Sampling - This item has been previously discussed in NRC
Inspection Reports 50-458/84-06, 85-05, and 85-53.
Based on the
licensee's completion of sample line deposition studies for the Fuel
Building, Radwaste Building, and Main Plant Stack Ventilation airborne
radioactivity samplers, this item is considered closed.
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3.
RP Program Organization and Management Controls
The NRC inspectors examined the organization and staffing of the
licensee's RP organization to determine compliance with the Final Safety
Analysis Report (FSAR) Sections 12.5.1.1, 13.1.2.1.3, and 13.5
commitments; and the requirements of 10 CFR Parts 20 and 50, and the
Facility Operating License Technical Specifications (TS) 6.2.1, 6.5.1.2,
6.8.1, and 6.11.1; and the recommendations of NRC Regulatory Guides
(RG) 1.33, 1.8, 8.8, and NUREG-0731.
The NRC inspector reviewed the current organization assignments and staff
positions for compliance with the FSAR and TS.
Recent staff changes
within the licensee's RP program were reviewed.
The NRC inspector also
reviewed position descriptions contained within the plant operating
procedures, RP staff resumes', conducted interviews with selected RP staff
members, and observed conduct of operations involving RP supervisors,
technicians and staff specialists.
Recent changes to RP program
implementing procedures were reviewed. The licensee's assignment of
responsibilities for RP program implementation and conduct of RP
operations were reviewed. The NRC inspector discussed with the Supervisor
of Radiological Programs (SRP) (equivalent to RG 1.8 Radiation Protection
Manager - RPM) the qualifications of the RP Supervisor to function as the
backup SRP/ RPM. The NRC inspector determined the RP Supervisor's
qualifications satisfied the FSAR commitments in Section 12.5.1.1.
The
NRC inspector reviewed RP group shift logs and observed RP supervisors
making tours of work areas.
The NRC inspector reviewed Station
Administrative procedures, RP program procedures, QA procedures, and the
Station Support Manual.
Procedures / documents reviewed are listed in
Attachment 1 to this report.
The NRC inspector reviewed QA procedures for licensee audits, corrective
action tracking, qualification of audit personnel, and reporting of audit
findings to management.
The latest QA audits of RP and NTD activities
were reviewed.
The response to audit findings appeared to be timely.
The NRC inspector reviewed the licensee's RP organization, including
staffing for the backshift, and the Radwaste group.
The NRC inspector
discussed with licensee representatives the day-to-day supervision of the
radiation protection technicians (RPT) assigned to the radwaste group and
the controls over them to ensure that their knowledge of general plant
conditions and training is kept up to date.
The NRC inspector noted to
the licensee that the total number of RPTs (approximately 22) appeared to
be marginal in that there appeared to be no margin for RPT retraining time
or coverage for unexpected jobs.
The NRC inspector determined that
routine use of overtime would be necessary for accomplishing routine RP
duties during plant start-up and power range testing.
Licensee
representatives indicated that personnel were aware of the overtime needs
and that necessary work would be accomplished without exceeding TS 6.2.2
requirements involvic.g the use of overtime.
No violations or deviations were identified.
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4.
RP Organization Staff Qualifications and Training
The NRC inspector examined the qualifications of the licensee's RP
organization to determine compliance with commitments in the FSAR
Section 12.5, 13.3-7, and 13.5; and the requirements of 10 CFR Part 19.12, TS 6.3.1, and 6.4.1; and the recommendations of RGs 1.8, 8.2,
8.8, 8.27, and those of NUREG-0761.
The NRC inspector reviewed the licensee's RP staff's qualifications based
on personnel resumes', interviews, and training records.
The licensee's
training facilities were inspected, lesson plans and training procedures
were reviewed, and requalification training was observed.
NTO staffing
and instructor qualifications / training were reviewed. The NRC inspector
reviewed the qualifications of a newly hired instructor that will be
responsible for RPT and chemistry technician training programs. The NRC
inspector discussed with licensee representatives the current status of
Emergency Preparedness training for RPTs and the cross training of
radiochemistry personnel in certain RP fundamentals so the radiochemistry
technicians could perform limited RPT duties during radiological
emergencies.
Qualification of RPTs has been previously discussed in NRC Inspection
Reports 50-458/84-06, 85-05, and 85-35. TS 6.8.1.a and 6.11.1 establish
the requirements for development and adherence to the aforementioned
procedures.
The NRC inspector was given the names of eight RPTs, on October 28, 1985,
that the licensee considered to be qualified as Senior RPTs, and therefore
satisfied established qualification criteria. The NRC inspector
determined that the eight Senior RPTs satisfied the ANSI /ANS 3.1,
paragraph 4.5.2 criteria for RPT.
However, licensee records (RBS -
Radiological Programs Section Technician Qualification Matrix print-out) as
of October 28, 1985, indicated that all eight Senior RPT were deficient in
completion of the training required by RSP-0003, paragraph 5.2.4, which
states:
"An employee is designated as a Senior Radiation Protection
Technician after completion of the requirements listed for Junior and
Senior Technician. . . ." Attachment 3 to RSP-0003 contains a detailed
listing of the necessary training for both Junior RPT and Senior RPT. The
licensee indicated that some of the apparently missed training was due to
a backlog of completed training that needs to be entered into the matrix
data files. The NRC inspector selected one Senior RPT for review of
completed training.
The NRC inspector determined on October 31, 1985,
that neither the RP Section's nor the NTD records could provide
verification that the Senior RPT had comoleted Drywell Entry training as
required by Attachment 3 to RSP-0003.
This is an apparent violation
involving failure to provide specified training (458/8573-01).
RSP-0003 also requires that RP Section maintained training records contain
specific documents and that these documents be maintained current
by the Radiological Engineering Supervisor or his designee (paragraph 7.3.1).
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The NRC inspector determined on October 31, 1985, that the training
records for the eight Senior RPTs were not being kept current, in that
documentation of completed training, physical exams, and dosirretry records
referenced on Attachment 1 to RSP-0003 were missing for personnel that had
been employed at RBS for upward of 9 months. Also, NTD records showed
that training had been completed for certain lesson plans, but the RP
Section's records indicated no training had been received.
This is an
apparent violation involving the failure to comply with procedures
(458/8573-02).
The FSAR Section 13.2.1, " River Bend Station Staff Training Program,"
establishes the licensee's commitment to provide certain training as
matrixed in Figure 13.2-1 of the FSAR to RPTs.
The FSAR commits the
licensee to provide initial plant staff and subsequent plant staff
training in Boiling Water Reactor (BWR) technology.
This BWR training is
described in Section 13.2.1.3.3 of the FSAR, and consists of a four week
long course (designated B7) on the design and operating details of
components and systems at RBS.
The NRC inspector determined on October 31,
1978, by a review of NTD records, that out of the eight Senior RPT
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previously referenced, only one had been provided the BWR technology
course referenced in the FSAR.
This is an apparent deviation from
commitments to the NRC (458/8573-01).
Licensee representatives indicated that the subject training was thought
to have been satisfied by an internal RP Section training module involving
plant systems walk downs.
The subject plant systems walk-downs did not
appear to involve the comprehensiveness of the FSAR course description and
therefore did not appear to the NRC inspector to be a suitable alternative
to the FSAR committed to training. The NRC inspector noted to the
licensee at the exit meeting that a similar FSAR training deficiency was
identified during a May 1985 Operations QA Group audit (GSUS/HPRP-85/05)
and addressed in QA Finding Report number P-85-06-011-D.
This audit
finding involved the failure of the RP Group to initiate training waivers
for committed training for personnel based on experience or equivalent
training. The NRC inspector noted to the licensee that evidently the
corrective action was not comprehensive enough to identify similar
deficiencies or prevent future deficiencies of this nature.
5.
ALARA Program
The NRC inspector reviewed the licensee's ALARA Program to determine
compliance with the requirements of 10 CFR Part 20.1(c); the commitments
in the FSAR Section 12.1.1 and 12.5.1.1; and the recommendations of NRC
RGs 8.8, 8.10, 8.19, and NUREG-0761.
The NRC inspector noted that since RBS had just recently received their
low power operating license and had nc,. performed any work involving
significant radiation exposure, there was very little in the way of actual
ALARA program implementation.
The NRC inspector reviewed the ALARA program administrative procedure,
implementing procedures, GSU management ALARA policies, ALARA staff
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qualifications, RBNG design engineering interface with RBS ALARA staff,
outage planning, proposed trending of ALARA concerns, ALARA reports to
RBNG managers, ALARA committee meeting minutes, ALARA committee
membership, assignment of ALARA program responsibilities, ALARA training
for nuclear engineers and outage planners, radiation worker ALARA
training, and general RBS staff ALARA training.
The NRC inspector noted
that the ALARA program, as set forth in the FSAR, appeared to be
implemented.
The NRC inspector discussed with licensee representatives
the proposed exposure goals for RBS power ascension testing and the basis
for the 6.5 man-rem goal for 1985.
The NRC inspector noted that the ALARA
staff was establishing a photographic library of system components and
areas for use in planning work operations.
The NRC inspector noted to the
licensee at the exit meeting that there appeared to be very little
training provided, other than that provided in GET I & II, to plant
engineers and planners on the effective implementation of ALARA criteria
during system engineering and job review. ALARA staff members indicated
that specific ALARA training for nuclear engineers and other plant staff
personnel was being considered.
The NRC inspector discussed with licensee representatives the interface of
the RP group personnel with outage coordinators early in the planning
stages of scheduled outages and also emergency outages for equipment
repair.
No violations of deviations were identified.
6.
Post Accident Sampling System (PASS)
The NRC inspector reviewed the current status of the PASS in regards to
satisfying Operating License Attachment 1 conditions for exceeding five
percent rated power.
Licensee's representatives stated that the PASS
system had been acceptance tested and the results reviewed by the Joint
Test Group.
However, the PASS system had not been turned over to the
plant operating sta'ff as of this time.
The NRC inspector determined that
one portion of the acceptance testing (obtaining of a reactor coolant
sample) had not been performed due to a lack of pressure on the primary
coolant system.
This portion of the acceptance testing will be completed
when suitable plant pressure is obtained during low power testing in the
near future.
The NRC inspector emphasized to the license at the exit
meeting the importance the NRC is placing on the operability of PASS
during full power license considerations.
The licensee stated that PASS
would be turned over to the plant staff and that a demonstration of PASS
operability would be provided to NRC Region IV personnel during the week
of November 11, 1985.
The NRC inspector reviewed the licensee's progress to eliminate the
numerous uncontained mechanical joints in the PASS system (see NRC
Inspection Report 50-458/85-70, Open Item 458/8422-05).
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is providing a redesigned sample cooling and isolation valve module that
will eliminate some mechanical fluid boundaries.
The licensee reaffirmed
the scheduled completion date of within 100 effective full power days.
No violations or deviations were identified.
7.
Reactor Startup Radiation Shielding Surveys
The NRC inspector reviewed the licensee's activities for conducting the
radiation survey of the reactor biological shield and other plant areas
during reactor startup and power ascension testing to determine compliance
with FSAR Section 14 commitmants and the recommendations of NRC RG 1.68.
The licensee had completed the zero power surveys and is awaiting further
reactor power increases to allow completion of the startup survey
procedure.
During this inspection period, reactor power was less than one
percent.
No violations or deviations were identified.
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Exit Interview
The NRC inspector met with the licensee's representatives and the NRC
resident inspector identified in paragraph 1 of this report at the
conclusion of the inspection on November 1, 1985.
The NRC inspector
summarized the scope and the results of the inspection.
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ATTACHMENT 1
TO NRC INSPECTION REPORT
50-458/85-73
DOCUMENTS J,EVIEWED
IIILE
REVISION
Q81E
Biver Bend Naclear Procedures Manual (RDNP)
RDNP-001, Preparation, Revision, Approval
and Control of Procedures and
Manuals
0
10/12/84
RDNP-OO2, Responsibilities and Authority
O
10/12/84
RDNP-OO4, Reporting Requirements
0
10/12/84
RDNP-OO5. Training Procedure and Respon-
sibilities
0
10/12/84
RDNP-010, Design and Modification Control
1
05/17/85
RDNP-014, Radiological and Industrial
Safety
0
10/12/84
RBNP-016, Resolution of Audit Findings and
Inspection Reports
0
10/12/84
RDNP-018, Outage Planning and Management
O
10/12/84
RDNP-020, Policy Statements and Management
Directives
0
10/12/84
PS/MD 1,
Gulf States Utilities ALARA
Policy Statement
03/07/85
PS/MD 2,
River Bend Station Respiratory
Protection Program Policy
Statement
03/07/85
PS/MD 3,
Responsibility for Overall River
Bend Station Operations
04/12/85
PS/MD 6,
Promulgation of RDNG Performance
Parameters
10/07/85
RDNP-024, Radiation Protection Plan
1
06/10/85
RDNP-025, Posting of Regulatory Matter
O
05/29/85
RDNP-028, River Dend Station Performance
Monitoring Program
O
10/02/05
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IIILE
GEy1SION
DGIE
()per a t i onal DA Manual
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' Oual i ty Assurance Directi ve-10
Audits
2
09/10/84.
Operations Quality Proced.ures and In s t ruc t i_on s (OAP/OAI)
OAP-1.2, OA/OC Organization. Responsibilities
and Duties
0
02/17/84
OAP-1.3, Indoctrination, Training Qualification
and Certification of Duality Assurance
Audit / Surveillance Personnel
3
05/07/05
OAP-1.D, Procencing Corrective Action Reports
to Nanagement
1
07/03/84
OAP-1.10, Reporting of Status of Open Items
to Management
2
07/24/85
OAP-1.14, Quali ty Assurance Tracking of
Ouality Concerns
1
09/24/85
OAP-1.15, Processing of Quality Assurance
Finding Reports
0
07/03/84
OAI-2.1, Audit Performance and Reporting
2
10/30/85
OAI-2.3, Planning. Scheduling, and Reproting
OA Garveillances of Plant Activities
0
08/15/84
QAI-2.10
Inupection Planning
2
09/03/85
Gtatinn Operatino Manual
GdM11Ls_t .g t i ve Procedures (ADM).
t
ADM- OOO 1,
Station Staff Organization.
Responsibilities and Authorities
2
05/03/05
ADM-OOO3, Development, Control and Use of
Procedures
7
09/07/05
ADM-0007, Selection. Training, Qualification
and Evaluation of Plant Staff
Personnel
2
04/20/85
ADM-0024, Conduct of Technical Gtaff Acti vi ti es
1
12/21/84
ADM-0025. Conduct of Radi at 2 on Prot ection
Gervices
2
07/20/85
ADM-0039
ALARA Program
1
05/25/85
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BEYISION
901E
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Radiation Protection Section Procedures (RSP)
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RSP-0001, Tracking and Trending Radiological
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Occurrences
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06/02/85
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RSP-0003, Personnel Qualification for the
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Radiation Protection Section
3
08/12/85
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RSP-0004, Preparation of Radiation Protection
Department Reports
0
07/13/85
.RSP-0200, Radiation Work Permits
1
06/11/85
RSP-0201, Respiratory Protection Program for
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Radiological Areas
1
06/27/85
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RSP-0202, Radiation Protection Calibration
Program
1
06/09/85
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RSP-0203, Personnel Monitoring
1
08/02/G5
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PSP-0206, Prenatal Radiation Exposure Policy
2
06/21/85
RSP-0209, Control and Calibration of Radiation
Protection Equipment
2
06/07/85
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RSP-0212, Drywell Entry
1
07/02/05
PSP-0213, Control and Handling of Radioactive
I
Materials
1
06/21/85
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Radiation Protection Procedures (RPP)
RPP-0003, Control & Leak Test of
Radioactive Sources
2
06/27/85
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RPP-0005, Posting of Radiologicall y
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Controlled Areas
2
06/11/85
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RPP--0006, Radiological Surveys
2
07/05/85
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RPP-0007, Dasic Radioactivity Counting
1
07/02/85
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RPP-OO13. Survey Instrument Response Testing
1
06/18/85
RPP-0018, Personnel Decontamination
1
08/24/85
RPP-0020, Selection and Use of Protective
Clothing
1
07/14/85
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RPP-0023, Radiological Precautions for
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CRDM Removal and Maintenance
1
05/19/85
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REVISION
DOIE
RPP-0024, . Radi ol ogi cal Precaution for
Underwater Operations
1
07/02/85
RPP-0033, Setup and Operation of General
Atomics' Portable Continuous
Atmospheric Monitor
0
07/12/85
RPP-0034, Operation of the General Atomics
Digital Radiation Monitoring System
CRT Display Terminals
0
02/16/85
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RFP-0035, Calibration of Digital Radiation
Monitoring Process Monitors
0
03/11/85
RPP-0049, Emergency Equipment Inventory
1
06/28/85
RPP-0050, Response to Abnormal Radiological
Conditions
2
07/14/85
RPP-0064, Use of Lapel Air Samplers
1
06/19/95
RPP-0065, Use of. Multiple Dosimetry Devices
1
07/24/85
RPP-OOO9, Operation and Calibration of
the Eberline RO-2/2A
1
07/05/85
RPP-0091, Operation and Calibration of
the Teletector - 6112 B/D
1
07/25/85
RPP-0092, Calibration of the RADECO
Model H-809
1
07/13/85
Radiation Health Physics Procedures (RHP)
RHP-0001, Operation of the Panasonic
Automatic TLD Reader
2
06/17/85
RHP-0008, Dose Determination and Reporting
2
07/28/85
RHP-0012, Issue and Use of the Pocket
Dosimeter
1
07/02/85
RHP-0015, Operation of the Helgeson
Do-It-Yourself In-Vivo Counting
System
1
07/13/85
RHP-0017, Calculation of Internal Doses
1
07/22/85
RHP-0018, Dicassay Sample Analysis
1
07/05/85
RHP-0019
Quantitative Mask Fit Testing
1
07/05/85
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BEMISION
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RHP-OO25, Dicassay Sample Collecti'an
1
06/23/85
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. RUP-OO27, Occupation Exposure Records
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and Reports
1
07/01/85
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-RHP-OO40, ALARA Cost Benefits Evaluation
2
06/15/85
- RHP-OO42, ALARA Pre-Job Review
2
06/25/85
RHP-OO43, ALARA Post-Job Review
2
06/15/85
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RHP-OO44, ALARA Exposure Tracking
2
06/24/85
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RHP-OO45, ALARA Design Review
2
06/15/85
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RilP-OO46, ALARA Reports
2
06/24/85
RHP-OO47, ALARA Committee
2
06/27/85
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RHP-0107,-Spirometry Testing
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06/25/84
Station SupJort Manual
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Training _ Administration Procedures (TAP). Section 5
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T A P - 5 -- O O i , Training Department Organization
O
01/16/85
TAP-5-OO2, Training and Qualification of
Training Department Instructors
O
06/18/85
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TAP-5-OO3, Training Facilities and Equipment
O
01/29/85
TAP-5-OO4, Training Library and Reference
Materials
O
01/29/85
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-TAP-5-OO7, Teaining Records and Documentation
O
01/16/85
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TAP-5-OO9, Training Interfaces
O
01/29/85
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Trainino Methodolooy Procedures (TMP). Section 6
TMP-6-OO2, Design and Development of Training
j
Programs and Instructional Materi al s
O
01/29/85
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TMP-6-OO3, Training Program Implementation
O
01/14/85
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TMP-6-OO4, On-The-Job Training
O
G1/16/85
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TMP-6-OO5, Student Evaluation
O
03/07/85
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OE$IS100
DGIE
Tr a i n ij331 Prooram Procedures (TPP), Section 7
TPP-7-013, tiech an i c a l Training Program
O
O2/07/85
TPP-7-Ot6, Radiation Protection Personnel
Training
O
O2/07/85
TPP-7-018, General Employee Training
1
09/23/05
TPP -7-026, General Gystems Training
O
O2/07/85
General Emplnvee Trainino Lesson Plans (GET)
Qr ipn t a t i on
GE T-OO 4--2,
Radiation Protection Training
2
11/11/83
GET-OO7-2, Overview of Plant Operating
Procedures
2
11/11/83
GET Level I
GET-010-1, Introduction to River Dend
Station
1
08/28/85
GET -015-0, Emergency P1an
O
09/17/04
GET-016HJ', Dasic Radiation Training
O
09/21/84
GET Level II
GET-020-1, Administrati ve Radiological Controls
1
OG/26/G5
(Gite Specific)
GE T--021 - 1,
Practicol Application
1
08/28/85
GET Level III
GET-030-1, Respiratory Protection
1
09/06/G5
GET Regttal i fi ca t i on Trainino (GETR)
GETR-100-0, GET-I Requalification Trainiog
O
09/16/05
GETR~200-0, GET-II Requalification
O
09/16/05
GETR-30a-0, GET-III Requalification
O
09/17/G5
.o
.
.
IIIl=E
BEMISION
D6IE
Spec _iltl Pur_ pose TratAiAq
-
GET-050-0, Site Specific Training for Select
Personnel
O
06/25/05
Radiation Protection _Techni_cian Lesson Plans (RPT)
RPT-011, Dosimetry
1
06/21/G4
RPT-012, Dosimetry Laboratory
0
09/27/83
RPT-024, Air Sampling
O
11/15/83
RPT-025, Air Sampling Laboratory
0
11/15/03
RPT-026. Radiation Surveys
1
07/23/84
RPT-027, Radiation Survey Laboratory
0
11/17/93
RPT-032, Radiological Work Coverage
0
10/26/93
Olhor Documents Reviewed
Memorandum (Draft), KES-560- 05, Subject: River Bend Outage Management
Goals and Objectives,.cAted September 4,
1985
.
General Employee Training Tetts:
.GETR-I, 10-R1
0
09/27/85
.GETR-II, 20-R1
O
09/27/85
.GETR-III, 30-R1
O
09/27/GS
.GET-II, 02-05
0
09/18/85
I,
II and III Student Manual
Training Records of:
. Maintenance Department Personnel (2)
. Radiation Department Personnel (15)
Training Department Instructor Resumes: 3
. Contracted Employees
RDS Radiological Programs Section Technician
Dualification Matrix
10/28/85
Radiation Protection Section Personnel Resumes: 36
. Supervisor-Radiological Programs
. Radiation Protection Supervisor
. Radiological Health Supervisor
. Radiological Engineering Supervisor
.Gr.
Health Physicist
. Health Physicist (2)
. . . .
IlILE
SEYISIOtj
D61C
~
. Radiation Protection Specialist (2)
.ALARA Coordinator
. Radiation Protection Foreman (4)
. Radiation Protection Technician (22)
ALARA Recordu:
.ALARA Suggestions
.Open ALARA Committee Action Items and Engineering Evaluation
Action Requests (EEAR)
.05-070 (EEAR 85-207)
.G5-071 (EEAR 85-209)
.85-074 (CEAR 85-0215)
.85-075 (EEAR G5-0214)
ALARA Photographic Library of Plant Systems and Areat
Rivr-r Bend Statico Final Safety Analysis Report Amendment 16
RDS Operations 04 Audits:
.GSUS/HPRP-05-05, File Codo 015.2.6.4
06/17/05
.GSUO TRNG-85/07, File Code G15.2.6
07/31/05