IR 05000289/1989006

Insp Rept 50-289/89-06 on 890403-07.No Violations Noted. Major Areas Inspected:Implementation of Radiation Protection Program

ML20246C370
Person / Time
Site:	Three Mile Island
Issue date:	04/27/1989
From:	Shanbaky M, Thomas W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20246C364	List: IR 05000289/1989006 ML20246C360
References
50-289-89-06, 50-289-89-6, NUDOCS 8905090352
Download: ML20246C370 (5)

Text

_ _ _ _ _ - _ _ _ _ _ _ _

. ..

U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /89-06 Docket N j License N DPR-50 Priority Category C Licensee: GPU Nuclear Corporation i P. O. Box 480 1 Middletown, PA 17057 j l

Facility Name: Three Mile Island Nuclear Station, Unit 1 1 I

Inspection At: Middletown, Pennsylvania  ;

!

Inspection Conducted: April J-2,1989 ]

..  :

Inspectors:

'

~

[ #

/ date 4/8f Wal'ter V.' Thomas , R(di'ati'off Sp6ciafi st Approved by: M. .

Mohamed M. Shanbaky, Chief, FRPS,FRSSB

//27 l'f

~' dat(

Inspection Summary: Inspection on April 3-7, 1989 Areas Inspected: Routine, unannounced inspection of the licensee's I implementation of the radiation protection progra Results: Within the scope of this inspection, no violations were identifie l l

8905090352 890427 gDR ADOCK0500pgrg9

. _ _ _ _ - _

.

,

.

-

..

DETAILS Individuals Contacted 1.1 Licensee Personnel J. Donnachie, Radiological Engineer

• D. Ethridge, Manager, Radiological Engineering J. Fornicola, Manager, TMI, QA Modifications / Operations

• Heysek, Licensing Engineer D. Hosking, Manager, Operations QA

• C. Incorvati, QA Audits Manager

• G. Lodde, Manager Radiological Health

• A. Palmer, Manager Radiological Controls Field Office 0. Perry, Dosimetrist L. Poppenwimer, Engineering Associate R. Rolph, Group Radiological Controls Supervisor

• R. Shaw, Director, Radiological Controls and Industrial Safety 1.2 NRC Personnel

• W. Thomas, Radiation Specialist, Region I

• L. Thonus, Acting Resident Inspector

• Denotes tho;e present at Exit Briefing 2.0 Purpose The purpose of this routine inspection was to review the Licensee's implementation of the Radiation Protection Program. Specific areas of the program which were inspected included:

-audits and appraisals of the program, ~^

-changes in the program since the last inspection,

-training and qualifications of personnel,

-external exposure control,

-internal exposure control,

-control of radioactive materials and contamination surveys and monitoring,

-maintaining occupational exposures ALARA 3.0 Audits and Appraisals Audits of the Radiation Protection Program are performed by the TMI Quality Assurance organization. The onsite organization reports directly to the Office of the President GPU Nuclear through the Corporate Director Quality Assurance. A good interface exists between QA and Radiological Controls. QA audited Radiological Controls a total of 46 times during i

i

- _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - _ _

_ _

-

.

,

1988. These audits resulted in 12 minor deficiencies, most of which were corrected on the spot. . Another system which is used by the licensee is ,

l

'

the Quality Deficiency Report (QDR) system. This system is a system which '

was established to identify minor program deficiencies. The QDR was adequately implemented during 1988. Three Quality Deficiency Reports (QDRs) have been issued since August 1988 of which 2 remain ope An Annual Quality Assurance Assessment report is generated for. Unit I by the QA organization. The last annual assessment was reviewed by the inspector and it was noted that the Radiological Controls response and actions have been timely and appropriate in meeting commitments for corrective action .0 Changes A major change in the TMI organization is in the process of implementa-tion. With the major cleanup effort at TMI 2 nearing completion, the radiological control functions for Units 1 and 2 are being combined under one director. Personnel, equipment, programs, and procedures affecting occupational radiation protection will not change. Overall, this consoli-dation of effort will strengthen the radiation protection program by shortening the lines of communication within the Radiological Controls organizatio .0 Training and Qualification The licensee has implemented a cross training program for the Radiological Controls technicians and supervisors from Units 1 and 2. This training program will be complete by June 30., 1989. Presently technicians are rotated between Units 1 and 2 on a five week basis. All technicians also attend a formal training session once per week to assure updates on procedural and job changes. At the present time all Radiological Controls Technicians are qualified to meet ANSI 18.1 (1971).

6.0 External Exposure Control TMI uses the Panasonic UD 802 Dosimeter modified for TMI for personnel external exposure measurements. This dosimeter meets the 10 CFR 20.202 requirements including NVLAP qualification. In addition, estimated dosages are measured with direct reading dosimeters and are corrected to the TLD Badge Readings at the end of each badge period (monthly). Current management and administrative controls of external radiation exposure meets the dose limits of 10 CFR 20.101 and are designed to conservatively maintain external exposures ALARA. Adequate records and reports of external exposures are maintained by the licensee. The inspector verified that timely notifications of external exposures are made to individuals in compliance with the regulatory requirements of 10 CFR 20.401.

. - _ _ - _ _ - - _ _ - _ _ - _

_ _ _-_ _ __

.

. . l

-

. i

_

,

7.0 Internal Exposure Control The inspector determined that the assessment of individual intakes of radioactive materials, utilizing the Fast-Scan Whole Body Counter, is used to verify the adequacy of the air sampling and respiratory protection programs. The licensee also possesses a lay-down whole body counter called an Accu-Scan which is presently being converted from a sodium iodide detection system to a lithium drifted germanium detector syste The new Accu-Scan will be operational by June 1989. When the Accu-Scan becomes operational it will be added to the present calibration schedule of once per week and daily source check schedule of three times per da A monthly QA verification check will also be performed in accordance with procedure 9100-ADM-4246.01, " Operation, Calibration and Quality Assurance of the Canberra Whole Body Counting Systems".

The licensee utilizes process and other engineering controls to the extent practicable to limit concentrations of airborne radioactive material In addition the licensee makes extensive use of administrative controls to limit intakes of radioactive materials and maintains a followup record of all positive whole body count determinations. The licensee's respiratory protection program is conducted in rempliance with Regulatory Guide 8.15 " Acceptable Programs for Respiratory Protection". The licensee's records, reports, and notifications of positive internal depositions of radioactive materials meet regulatory requirement .0 Control of Radioactive Materials and Contamination, Surveys and Monitoring The inspector determined that required surveys and monitoring activities are performed once per shift, or as required by area work activity and are noted on the plant maps at the Radiological Access Control Poin Overall, it was determined that the control of radioactive materials and contamination at Unit I was adequate and met regulatory requirement .0 Maintaining occupational Exposures ALARA The licensee has adopted a goal of 200 person-rem for calendar year 198 This will include a goal of 75 person-rem for the operations activities and 125 cumulative person-rem for balance of plant for the remainder of the non-outage year. The licensee makes extensive use of proven industry developed methods for controlling out-of-core radiation sources and fields, and is actively involved in maintaining a removable contamination free plant interior area. All workers are aware of and involved in the ALARA program, which is administered by Radiological Engineering. The comparison of previous years ALARA goals and actual exposures with the industry averages indicates that Unit 1 exposures are below the industry average. The licensee continues to implement a good ALARA program at Unit _ _ _

_ __

. .

,

.

.

s 10.0 Exit Meeting The inspector met with the licensee representatives (denoted in Section 1 of this report) at the conclusion of the inspection on April 7,198 The inspector summarized the purpose, scope, and findings of this inspectio 'e l

_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _