Text

Insp Rept 50-458/85-73 on 851028-1101.Deviation Noted:Senior Radiation Protection Technicians Not Provided W/Proper Training.Violation Noted:Qualification Matrix for Technicians Not Updated for Period in Excess of 8 Months
	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: ML20151N654; ML20151N662; ML20151N667; ML20151N671;
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)
	v • d • e

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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)

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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

Inspector: h #

H. Chaney( ladiation Speciali

12.!3kI

Date

Facilities Radiological Protection Section

Approved: 9

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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 48

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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

! 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). General Electric

. . . _ _ _ _ _ _ _ . _ . _ . _ _ _ _ _ _. _ _ _ . _ _ . . _ _ _ _ . _ _ _

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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. '

8. 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

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()per a t i onal DA Manual ,

' 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 t .g t i ve Procedures (ADM).

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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IIILE BEYISION 901E [

Radiation Protection Section Procedures (RSP)

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1 RSP-0001, Tracking and Trending Radiological

I Occurrences O 06/02/85 ;

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l RSP-0003, Personnel Qualification for the

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Radiation Protection Section 3 08/12/85 -

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 l

Radiological Areas 1 06/27/85 t

RSP-0202, Radiation Protection Calibration

Program 1 06/09/85

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RSP-0203, Personnel Monitoring 1 08/02/G5 >

PSP-0206, Prenatal Radiation Exposure Policy 2 06/21/85

RSP-0209, Control and Calibration of Radiation !

Protection Equipment 2 06/07/85 l

RSP-0212, Drywell Entry 1 07/02/05

PSP-0213, Control and Handling of Radioactive I

Materials 1 06/21/85 i

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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 !

Controlled Areas 2 06/11/85 l

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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 l

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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 ,

CRDM Removal and Maintenance 1 05/19/85 l

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IIILE 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 = _ _ .

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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IIILG BEMISION DOIE

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RHP-OO25, Dicassay Sample Collecti'an 1 06/23/85

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. RUP-OO27, Occupation Exposure Records

i 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 i

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RHP-0107,-Spirometry Testing O 06/25/84

Station SupJort Manual l

I Training _ Administration Procedures (TAP). Section 5 t

4 T A P - 5 -- O O i , Training Department Organization O 01/16/85

TAP-5-OO2, Training and Qualification of

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Training Department Instructors O 06/18/85

TAP-5-OO3, Training Facilities and Equipment O 01/29/85

TAP-5-OO4, Training Library and Reference

Materials O 01/29/85 i

-TAP-5-OO7, Teaining Records and Documentation O 01/16/85 >

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 r

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TMP-6-OO5, Student Evaluation O 03/07/85

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.- en- , , - , - - - . , .,,,,,,,-wrn,,,w,- ,.,-,-.n,,,., .-.._,,-,w- ,,-,-,,-r,_,..,,,,,...,.n., - ,.,n .

n..,,,,,g..,,--n-,nmyn,p~,-n., -. ,

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IIIL_q 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

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IIIl=E BEMISION D6IE

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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

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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

GET 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)

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IlILE SEYISIOtj D61C

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. 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

ML20151N671

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