IR 05000458/1987015

Insp Rept 50-458/87-15 on 870622-26.No Violations or Deviations Noted.Major Areas Inspected:Radiation Protection Program,Including External Occupation Exposure Control, Personnel Dosimetry & IE Info Notices

ML20235U632
Person / Time
Site:	River Bend
Issue date:	07/16/1987
From:	Chaney H, Murray B, Scott H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20235U607	List: IR 05000458/1987015 ML20235U605
References
50-458-87-15, IEIN-80-22, IEIN-81-26, IEIN-82-18, IEIN-82-31, IEIN-82-42, IEIN-82-43, IEIN-82-51, IEIN-83-14, IEIN-83-33, IEIN-83-52, IEIN-83-59, IEIN-83-64, IEIN-83-67, IEIN-83-68, IEIN-83-73, IEIN-84-15, NUDOCS 8707220541
Download: ML20235U632 (7)

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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-458/87-15 License: NPF-47 Docket: 50-458 Licensee: GulfStatesUtilities(GSU) l P. O. Box 220 St. Francisville, Louisiana 70775 l Facility Name: River Bend Station (RBS)

Inspection At: River Bend Station, St. Francisvilie, Louisiana j

Inspection Conducted: June 22-26, 1987 Inspectors: (]hfu?- /ll)AO4 7//Wh7

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H. D. Chaney, Radi~atiorf Specialist, Facilities Ddte '

g Radiological Protection Section

'Waa;81 u Jhs/r7 H. ScottVRadiation Specialist, Facilities Date Radiological Protection Section Approved: @bftc24/L4tB44/

B. Murray, Chief, Fac/lities Radiological 7/k '87 Date

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Protection Section Inspection Summary Inspection Conducted June 22-26, 1987 (Report 50-458/87-15)

Areas Inspected: Routine, unannounced inspection of the licensee's radiation protection program including external occupational exposure control and personnel dosimetry; internal exposure control and assessment; control of radioactive materials and contamination, surveys, and monitoring; facilities and equipment; occupational exposures during extended outages; and licensee's action concerning certain NRC Information Notice Results: Within the areas inspected, no violations or deviations were identifie PDR ADOCK 05000458 G PDR

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DETAILS Persons Contacted GSU

• J. Deddens, Senior.Vice President, RBNG T. Plunkett, Plant Manager

• P. D. Graham, Assistant Plant Manager

• R. B. Stafford, Director, Operations Quality Assurance (QA)

• J. W. Cook, Lead Licensing Engineer

• E. M. Cargill, Supervisor,. Radiological Programs D. L. Davenport, Security Manage E. L. Glass, Instruments and Controls Foreman

'W. Hardy, Radiation Protection Supervisor C. L. Fantacci, Radiological Engineering Supervisor'

'R. E. Horn, Nuclear Training Department Representative J. Spivey, QA Engineer E. R. Oswood, Senior QA Engineer R. R. Tunstall, Radiation Protection Foreman A. D. Wells, Radiation Protection Foreman (Dosimetry)

B. Spell, Health Physicist (Dosimetry)

W. Eisele, Radiological Health Supervisor (Dosimetry)

R. C. Albert, Radiation Protection Technician (RPT)

C. A. Lewis, RPT C. J. Edwards, RPT C. D. Jacobs, RPT B. G. King, RPT P. A. Lefort, RPT T. R. Sloan, RPT Others  ;

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• Jones, NRC Resident Inspector J

• Denotes those present at the exit interview on June 26, 198 . Inspector Observations The following are observations the NRC inspector discussed with the licensee during the exit interview on June 26, 1987. These observations .

are not violations, deviations, unresolved items, or open items. These observations were identified for licensee consideration for program )

improvement, but the observations have no specific regulatory requiremen ]

The licensee stated that the observations would be reviewe Dosimetry Technicians: The rotation of RPTs into the dosimetry aroup on a monthly basis is not condusive to maintaining quality control I

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over the processing of dosimetry or the maintenance of personnel qualifications on the complex dosimetry syste Training Records: The training records maintained by the Nuclear Trai.ning Department for Radiation Protection Department personnel do not contain documentation of specialized vendor training received by several RPT foremen. These records also contain outdated and incomplete qualification /on-the-job training records for several RPT foreme . Program Areas Inspected .

I The following program areas were inspected. Unless otherwise noted, the inspection was completed and revealed no violations, deviations, j unresolved items, or open items. Notations after a specific inspection item are used to identify the following: I = item not inspected or only I

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partially inspected, V = violation, D = deviation, U = unresolved item, and 0 = open ite Procedure Program Area and Inspection Requirements 83724 External Occupational Exposure Control and Personal Dosimetry 02.01 - Audits and Appraisals 02.02 - Changes 02.03 - Planning and Preparation for Outages 02.04 - Personal Dosimetry (see paragraphs 4 and 5 for specific comments)

02.05 - Administrative. Controls 02.06 - Records, Reports, and Notifications 83524 External Occupational Exposure Control and Personal Dosimetry 02.01 - Physical Controls 02.02 - Administrative Controls 02.03 - Personal Dosimetry 83725 Internal Exposure Control and Assessment 02.01 - Audits and Appraisals 02.02 - Changes 02.03 - Planning and Preparation for Outages - 1 02.04 - Assessing Individual Intakes of Radioactive Materials 02.05 - Engineering and Administrative Controls 02.06 - Respiratory Protection Equipment 02.07 - Records, Reports, and Notifications

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.83525 Internal Exposure Control and Assessment

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02.01 - Administrative Controls 02.02 - Engineering Controls 02.03 - Respiratory Protection Equipment 02.04 - Air Sampling for Assessing Individual Exposure 02.05 - Bioassays 83526 Control of Radioactive Materials and Contamination, Surveys, and Monitoring 02.01 - Area Radiation and Airborne Radioactivity Monitors 02.02 - Portable Survey, Sampling, and Contamination Monitoring Instruments 02.03 - Protective Clothing and Equipment 02.04 - Radioactive Material and Contamination Control 02.05 - In-Plant Surveys 'and Monitoring 83726 Control of Radioactive Materials and Contamination, Surveys,-

and Monitoring 02.01 - Audits'and Appraisals 02.02 - Change .03 - Surveys and Monitoring 02.04 - Radioactive Materials and Contamination Controls 83727 Facilities and Equipment 02.01 - Facility Changes 83729 Occupational Exposure During Extended Outages 02.01 - Audits and Appraisals - 1 02.02 - Changes - I 02.03 - Planning and Preparation 02.04 - Training and Qualification of New Personnel - 1 02.05 - External Exposure Control - I 02.06 - Internal Exposure Control - I 02.07 - Control of Radioactive Materials and Contamination, Surveys, and Monitoring - I 02.08 - Maintaining Occupational Exposure ALARA - I

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4 Personal Dosimetry Program The NRC inspectors conducted a review of the licensee's personal dosimetry program. The licensee uses a state-of-the-art, computerized, multiple-element thermoluminescent dosimeter (TLD) system. The TLD system is ,

supplemented by the use of self-reading pocket dosimeters (SRD) between  !

TLD processing periods. The licensee's TLD system is currently certified  ;

in all eight categories identified in the National Voluntary Laboratory Accreditation Program (NVLAP). .

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The TLD is a four element Panasonic design, model 802 AS. Two elements are natural lithium (Li-6) borate granules and two are calcium sulfate granules of 15 milligram per square centimeter (mg/cm2) nominal' thicknes The filtration over the.four elements of the TLD, including that contributed by the hanger, is as follows:

ELEMENT FILTRATION (mg/cm2)

1 14 (m 2 310 (ylar)

mylar, plastic 3 310 (mylar, plastic 4 1000(lead, plastic The licensee's badge (TLD and holder) approximates the density of tissu The badge has been calibrated to provide dose equivalents for gamma, beta, and neutron radiation. The licensee also employs a single element lithiun borate " chip" in a finger ring (Panasonic 807 model badge) for measuring dose to the fingers / hand, and the standard badge (802 AS) for other extremity monitoring. The licensee is currently analyzing the data from a beta radiation energy spectrum study that was conducted in various arcas of the plant. This data will be used to validate the beta exposure response of the TLD syste The NRC inspectors reviewed experience resumes of personnel assigned to the dosimetry program. The NRC inspectors discussed with the licensee the need to provide a stable staff concerning personnel responsible for the dosimetry program so that TLD processing and training are maintained at a high quality. The licensee is currently rotating RPTs through the dosimetry group on a monthly basi l No violations or deviations were identifie !

5. Skin Contamination / Hot Particle Dose Assessnent The NRC inspectors reviewed the licensee's program for the prevention and assessment of skin dose from radioactive contamination. The licensee's i program includes detailed contamination surveys of plant areas with:

special large area high particulate retention smears, 100 percent i monitoring of laundered protective clothing (coveralls), and the use of I high sensitivity (Eberline PCM1) personnel monitors for monitoring personnel exiting radiologically controlled area l The licensee's program was developed using several industry referenced documents and NRC Inspection and Enforcement 16 formation Notice (IEIN)86-23. The licensee's assessment program included the following features:

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The licensee's program for handling personnel skin dose assessment is contained in Radiological Health Procedure 0030, " Calculation of Dose

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Assessment From Skin Contamination," Radiation Protection Procedure (RPP) 0018, " Personnel Decontamination," and RPP-0043,

" Personnel Contamination Monitoring."

Contamination is primarily measured with a beta / gamma frisking probe (Eberline HP 210 equivaler.t) having an approximate 15.5 cm2 detection area. The resulting readings (counts per minute) are converted to disintegrations per minute (10 percent efficiency), and averaged over

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the size of the contaminated area. Dose equivaler.ts are calculated on a 1 cm2 area, unless more definitive knowledge is known about the contaminated area. The licensee had included specific instructions for the use of portable radiation detection instrument The assessment only evaluates the beta component of contamination; gamma component exposure is regarded as providing a negligible dose contribution when evaluating significant doses due to beta exposur The assessment is equated to the dose at the basal layer of skin depth (7 mg/cme ),

An attempt is made to perform on radionuclides identification or contamination / hot particle The licensee is planning to perform detailed contamination surveys during major outages. The licensee will be taking samples inside of major components for the determination of plate out of fission product The licensee's skin dose assessment program appears to have incorporated the information in IEIN 86-2 No violations or deviations were identifie . NRC Inspection and Enforcement Information Notice Review The NRC inspectors reviewed the licensee's program for reviewing and implementing the information contained in NRC IEIN The licensee's actions concerning the following IEINs were reviewed:

8C-22 81-26 82-18 82-31 82-42 82-43 82-51 83-14 83-33 83-52 83-59 83-64 83-67 83-68 83-73 84-15 84-24 84-28 84-40 84-59 84-60 l 84-61 84-72 85-06 85-42 85-60 85-87 85-92 86-22 86-23 86-24 86-30 86-32 86-42 86-43 86-44 86-46 86-103 The licensee's actions were considered acceptable for all IEINs reviewe No violations or deviations were identifie ,

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? 7 p Exit Interview 1 1 ~

l The NRC inspectors met with the NRC resident inspector and licensee l-representatives denoted in aaragraph 1 on June.26,1987, and summarized the scope and findings of tie inspection as presented in this report.

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