IR 05000302/1982014

IE Insp Rept 50-302/82-14 on 820607-11.No Noncompliance Noted.Major Areas Inspected:Followup on Previously Identified Matters,Training,Air Sampling,Whole Body Counting & Plant Tour

ML20055A031
Person / Time
Site:	Crystal River
Issue date:	06/24/1982
From:	Barr K, Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20055A020	List: IR 05000302/1982014 ML20055A019
References
50-302-82-14, NUDOCS 8207150408
Download: ML20055A031 (6)

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'g UNITED STATES 8($ o NUCLEAR REGULATORY COMMISSION g e REGION il 101 MARIETTA ST., N.W., SUITE 3100 o,

% g[ ATLANTA, GEORGIA 30303

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JUN 2 51982

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Report No. 50-302/82-14 Licensee: Florida Power Corporation 320134th Street, South St. Petersburg, FL 33733 Facility Name: Crystal River Docket No. 50-302 License No. DPR-72 Inspection at CrystaMi r site near Crystal River, FL Inspector: h J. B. Kahle nu, is

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(b 6) du at Signed Approved by: / M'h K. P. Barr', ~Section Chief 6M/ v D6te $1gned Technical Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on June 7-11, 1982 Areas Inspectad This routine, unannounced inspection involved 42 inspector-hours on site in the areas of followup on previous identified matters, training, air sampling, whole body counting, and plant tou Results Of the five areas inspected, no violations or deviations were identifie KOhhohh2 PDR

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REPORT DETAILS Persons Contacted Licensee Employees

• Q. B. DuBois, Assistant Plant Manager

• J. Cooper, Nuclear QA/QC Manager

• J. Wright, Nuclear Licensing Support Specialist

• G. Ruszala, Chemistry and Radiation Protection Manager

• C. Brown, Nuclear Compliance Supervisor

• S. Mansfield, Nuclear Compliance Auditor G. Perkins Plant Health Physicist G. Cranfield, Health Physics Supervisor S. Lashbrook, Health Physics Supervisor R. Browning, Health Physics Supervisor Other licensee employees contacted included three technicians and one office personne NRC Resident Inspector ,

• T. Stetka B. Smith

• Attended exit interview Exit Interview The inspection scope and findings were summarized on June 11, 1982, with those persons indicated in paragraph 1 abov . Licensee Action on Previous Inspection Findirigs Not inspecte . Unresolved Items Unresolved items were not identified during this inspectio . Health Physics Appraisal and Other Followup Items (Closed) IFI 80-89-10, Contamination of nonradioactive system and resulting potential for unmonitored, uncontrolled release of radio-activity to environment. This item was discussed in inspection report no. 50-302/81-2 The licensee has established a program for moni-toring the storm drains. An examination of the results showed no indication of radioactivity in the liquid or radioactive contamination on the surfaces of the storm drain .

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2 (Closed) IFI 78-22-04, Potential for saturating GM tube process moni-tor This item was discussed in inspection report no. 50-302/81-2 The item was originally identified as 78-22-03 in inspection report no. 50-302/78-2 An examination of the licensee's test results showed that when a large source was brought near the detector very quickly (radiation intensity at the detector rose very rapidly) the instrument pegged. The design of the alarm circuit is such that the alarm must be reset and can only be reset when the meter reading is below the alarm setpoint. The tests further showed that the detector showed a saturation effect when the radiation intensity was increased very slowl The meter would read up to a maximum value then slowly decrease slightly as the radiation intensity increase The results showed that the value where satura-tion began was well above the alarm setpoint and the meter did not decrease below the alarm setpoin The inspector had no further question (Closed) IFI 80-25-31, Development of an acceptable records systems for health physics. This item was discussed in inspection report no. 50-302/81-27. The licensee has prepared a single document that outlines the records retention and maintenance program, AS-01, Administrative Services Document Control / Records Mangement Procedur Fireproof cabinets for storage of personnel radiation protection records are in place. The old records have been microfilmed and are being placed in the computer syste The inspector requested that several exposure records of terminated employees, present on-site

employees. contractor personnel, contamination surveys, body count results. etc. , be retrieved to demonstrate the licensee's ability to j, retrieve records. These records were retrieved within a few minutes i

and it appeared that the operators were familiar with what records were in the computer system and the procedure for retrieving. It appeared that the radiation protection records system met the requirements of ANSI N13.6-1966 (R1972), Practice for Occupational Radiation Exposure Records System. The inspector had no further question (Closed) IFI 80-25-389, Incorporation of ANSI N323-1978 into plant calibration procedures. This item was dicussed in inspection report nos. 50-302/81-27 and 50-302/81-08. Discussions with licensee repre-sentatives and a review of the licensee's calibration procedures revealed that the applicable requirements stated in the above ANSI standard have been incorporated into the calibration procedure The inspector examined the new calibration facility in the turbine building and discussed with the supervisor the program for calibrating the radiation protection instrument All the technicians have respon-sibility for calibrating all instruments. The supervisor trains each technician with regard to calibration. The supervisor explained the program for training the technicians and the record system to show the training status of each technician with regard to each instrument. The inspector had no further question _ _ _ _ _ -

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3 (Closed) IFI 80-25-42, Frisker setpoints and frisker stations. This item was dicussed in inspection report no. 50-302/81-08. The inspector verified that the friskers have been modified to remove the hand adjust frisker alarm setpoint contro The hand adjust control has been

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replaced with a mechanism which requires the use of a screwdriver to make an adjustment. This prevents easy adjustment of the setpoint.

The inspector had no further questions, (Closed) IFI 80-25-43, Calibration facility and training for calibra-tion technician This item was discussed in inspection report nos. 50-302/81-08 and 50-300/81-27. See paragraph 5.d abov (Closed) IFI 80-25-44 Estaolishment of a formal ALARA program. This item was discussed in inspection report no. 50-302/81-08. A formal ALARA program has been established. Procedures MI-10, ALARA Philosophy for Occupational Radiation Exposure and AI-1600, ALARA Program, have been instituted to implement the program. During the week of the inspection, an ALARA Specialist was hired to devote 100 percent of his time to that positio Previously, the Nuclear Licensing Support Specialist was acting in the positio Discussions with licensee representatives indicated that the program has full management support and ALARA considerations will be given to all work where there is a potential for radiation exposure. Guidelines for review and followup have been established. The inspector had no f urther questions (Closed) IFI 80-25-45, Real time computing system for ALARA concern This item was discussed in inspection report nos. 50-302/81-08 and 50-302/81-2 Licensee representatives explained the system for entering data into the HP-1000 computer system and how it can be retrieved for ALARA reviews, followup and other considerations. They stated that it would probably be mid-1983 before all the older records would be fully transferred to the new system. The inspector had no further question . Training The inspector attended the radiation protection training sessions that are given to new employees before they are permitted to enter the plant on an unescorted basis. This same training is given to the permanent workers as annual retraining. The program covers security, industrial safety, fire protection, quality assurance and radiation protection safety and was presented by a senior radiation protection technicia The sessions were a combination of video tape and live presentations with the instructor emphasizing the main points at the end of each presentatio A comprehensive test was given at the end of each session. The training material was well presented with a practical approach towards the type of information that the workers need to know to perform their jobs safely and in accordance with regulatory requirements. The material covered the basic principles of radiation safety and how these principles are applied to operations and proce-dures at the plant to maintain radiation exposure to a minimu _J

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4 The inspector also attended the respiratory protection training session presented by the licensee. It appeared that the training was adequate to meet the requirements of 10 CFR 20 and was sufficient for indi-viduals who attended the training to know the proper procedures to use respiratory protection equipment and the precautionary measures that are necessary. A test was also given at the end of training session prior to a physical examination by the plant physician and fitting by the training instructo The inspector examined the records of the training provided for the radiation protection technician It appeared that the technician training has been continuous and comprehensive for 1982. The inspector had no further question . Air Sampling Air samples are collected at the plant depending upon the location and nature of the work being performed. Air sampling is controlled through the radiation work permit system and the weekly routine requirement An examination of several records showed that airborne concentrations of radioactive material ranged from fractions of a percent to approvimately three percent of MPC. This included special work where respiratory pro-tection equipmemt was require No violations or deviations were identi-fie . Whole Body Counting Licensee representatives explained their whole body counting procedure The inspector verified that the daily energy and alignment checks were performed and that daily empty chair background determinations were mad Verification was made that the semiannual detector drif t measurements were made and that the results were within 25 percent of the calibration valu An examination of the body counter records showed no significant results which would be indicative of any internal deposition of radioactive materials in the body. The inspector had no further question . Plant Tour During the inspection, the inspector toured the plant accompanied by a licensee representativ External radiation measurements were taken at various location Radiation readings obtained by the inspector were consistent with those determined by the license The inspector observed that areas were properly posted, roped of f, tagged, and locked as appro-priat Radiation frisker equipment was available at the various check point Bags and containers of contaminated equipment and waste were properly tagged and labelled. No violations were identified.

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10. Release of Contaminated Materials From the RCA On May 3, 1982, the 11< .see discovered a contaminated compressed gas cylinder cart in the tu- 'ne building. The strap for securing the cylinder was contaminated to 40,10 dpm/100 cm2 which resulted in an individual contaminating his hands. Surveys did not reveal other contamination and an investigation did not determine how or wnen the material was removed from the radiation controlled area (RCA). A report of the incident was made to site management soliciting their support to help maintain the radioactive material control program to prevent a recurrence. The inspector had no further question J