IR 05000302/1993001

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Insp Rept 50-302/93-01 on 930104-08.No Violations Noted. Major Areas Inspected:Licensee RP Program Including self- Assessments,Changes to Program,Outage Planning & Preparation & Training & Qualifications
ML20127K304
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 01/14/1993
From: Rankin W, Testa E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20127K269 List:
References
50-302-93-01, 50-302-93-1, NUDOCS 9301260091
Download: ML20127K304 (5)


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    $AN 1 L 7333 Report No.: 50-302/( -01-Licensee: Florida Power Corporation 3201 34th-Street, South St. Petersburg, FL 33733 Docket No.: 50-302    License No.: DPR-72 Facility Name: Crystal River 3 Inspection Conducted: January 4-8, 1993 Inspector: [Nb  ~

O - [[ ///3/2.$ E. D. Testa . Date Signed Approved byg/)3 $ n h M W. H. Rankin, Chief D //II Q3 Dat6 Sighed

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Facilities Radiation Protection Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards-SUMMARY Scope: This routine, unannounced inspection of the licensee's radiation protection (RP) program involved the review of RP activities including: self . assessments, changes.to.the program,-outage planning and preparation, training-and qualifications, external exposure control, control of radioactive materials, and contamination surveys / monitoring and maintaining occupational exposure As Low As. Reasonably Achievable (ALARA).

Results:

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Based on interviews with licensee management, supervisors, personnel from station departments, and records review, the inspector found the RP program lto- , be adequately' managed. The-licensee's program for occupational radiatio safety was functioning to protect the health-and safety of the wcrkers and general public. RP technician technical knowledge was identified as a program ' strength.

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b-REPORT DETAILS-

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l .- ' Persons Contacted Licensee Employees

 *J. Alberdi , Manager, Nuclear Plant Operations-
 *P. Beard, Jr., Senior Vice President, Nuclear _ Operation
 *G. Cadwell, Quality Programs
 *E. Froats, Manager, Nuclear Compliance, FPC Compliance
 *R. _ Fuller, Senior Nuclear Licensing Engineer,- FPC Licensing
 *S. Garry, Corporation H. P., FPC/SNS-
 *G. Halnon, Manager, Nuclear Plant and Technical Support
 *S. Hickle, Director, Nuclear _ Plant Operations

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 *S. Johnson, Manager, Chemistry and Radiation-Protection J. Kessler M.D., Site Medical Doctor
 * Marshall, Manager, Nuclear Plant Operations
 *R. McLaughlin, Nuclear Regulatory Specialist

'. *W. Rossfeld, Manager, Site Nuclear Services K. Spilios, Physicians Assistant ,

 *R. Widell, Director, Nuclear Operations Site Support
 *D. Wilder, Radiation Protection Manager 0ther licensee employees contacted during the: inspection included technicians, maintenance personnel, and ' administrative personne Nuclear Regulatory Commission
 *P. Holmes-Ray, Senior Resident. Inspector
 * Hunt, Reactor Inspector
 *H. Miller,-Reactor Inspector
 *G. Wiseman,-Reactor Inspector
Changes (83750)

I -The inspector reviewed the licensee's RP program to determine if any major changes had occurred since the last inspection in the in organization, facilities,- _ equipment, program, procedures, or personnel . , The former Manager, Quality Programs was named Manager, Chemistry and - l Radiation Protection in October 1992._The inspector determined that the ' program continues to be well managed.

! No violations or deviations were identified.

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3.- _ Facility Tours-(83750)__ l -- During-the onsite inspection, the inspector toured selected areas of the containment,' Auxiliary Building, instrument calibration facility, tool-

 . storage area, Fuel Handling Building, yard storage, and berm are __
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The inspector observed facility operations and selected work activitie to evaluate the implementation and effectiveness of the-licensee's RP: program. -The inspector observed that all inspected survey meters and continuous air monitors in use within the RCA were observed to be operable, calibrated, and source checked in accordance with licensee-procedure No violations or deviations were identifie . As low As Reasonably Achievable (ALARA) (83750) ' 10 CFR 20.l(c) states that persons engaged in activities under licenses issued by the NRC should make every reasonable effort to maintain' radiation exposures ALAR The inspector reviewed and discussed with licensee representatives the-ALARA program implementation and initiatives and the planning for the mid-cycle outage. The licensee appears to be aggresively controlling routine doses and planning to control the upcoming mid-cycle outage dose No violations or deviations were identifie . Internal Exposure Control (83750) 10 CFR 20.103(a)(1) states that no licensee shall possess, use, or: transfer licensed material in such a manner as to permit any individual in a restricted area to inhale a quantity of radioactive material in any period of one calendar quarter greater than the. quantity which would result from inhalation _for 40 hours per week for 13 weeks .at uniform concentrations of radioactive material in air specified in Appendix B, Table 1, Column CFR 20.103(a)(3)-requires, in part, that the licensee, as-appropriate, use measurements of radioactivity in the body, measurements of radioactivity excreted from-the body, or any combination of:such measurements as may be necessary for timely detection and assessment-of individual intakes of radioactivity by exposed individual CFR-20.103(c)(2) permits a licensee to maintain and implement a respiratory protection program that includes, at- a minimum: air-sampling to identify the hazard; surveys _;and_ bioassays;to evaluate th actual exposures; written procedures to select,' fit and maintain-respirators; written procedures regarding the supervision and training _ of personnel :nd issuance of. records; and determination by a physician prior to the use of respirators, that the-individual is= physically able

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The inspector toured the onsite medical facility and . discussed, respirator medical examinations and the general employee health profile at the site. No unexpected revelations were observe No violations or deviations'were-identifie ' 6. Surveys, Monitoring, and Control of Radioactive-Material and Contamination (83750) 10 CFR 20.201(b) and 20.401 requires that surveys must be performed and records maintained of such surveys necessary to show compliance with regulatory limit _ CFR 20.203(f) requires each container of licensed radioactive material to bear-a durable,- clearly visible label identifying the content _ l During the facility tour, the inspector independen" verified radiation and/or contamination levels in radwaste storage areas, tool storage areas, the Fuel Handling Building, and the Intermediate Building. The inspector noted that all containers, raaterials, and areas were properly labeled, posted, and/or safeguarded in accordance with radiation hazards present. The licensee promptly placed radtape on some drain lines which may have contained potentially contaminated water.

., No violations or deviations were identified, 7. External Exposure Control and Personnel Dosimetry (83750) 10 CFR 20.202 requires each licensee to supply appropriate monitoring equipment to specific individuals and requires the use of such equipment. During tours of the plant, the inspector observed workers g wearing appropriate personnel monitoring device CFR 20.408(b) requires that when an individual terminates employment-with the licensee, or an individual assigned to work' in_ a licensee's facility but not employed by the licensee completes _ the work assignment, the licensee furnish- the NRC a report of the individual's exposure to radiation and radioactive material incurred during the period of employment or work assignment, containing information recorded by the licensee pursuant to-10 CFR 20.401(a). 10 CFR 20.401(a) requires each-licensee to maintain records showing the radiation exposure of all

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individuals for whom personnel monitoring is required under 10 CFR 20.202 of the- regulations. Such records shall be kept _on Form-- NRC-5 or equivalen The inspector-selectively reviewed 1992 and historical termination letters--for individuals and found no problems or inaccuracies with'the hard-copy records or the microfiche records examine No violations or deviations were identified.

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4 Radwaste Processing and Transportation (86750) 10 CFR 71.5 (a) requires each licensee who transfers licensed material outside of the confines of its plant or other place of use, or who delivers licensed material to a carrier for transport, shall comply with the applicable requirements of the regulations appropriate tt the mode of transport of the Department of Transportation (DOT) in 49 FR, Parts 170 through 18 Pursuant to these requirements, the inspector reviewed the licensee's activities affiliated with Radioactive Waste Shipment 93-01 on January 6, 1993, to determine whether the licensee effectively packages, stores, and ships radioactive solid material _ The inspector observed the pre-job planning meeting, the loading of a radioactive material shipment (Shipment No. 93-01) and the post job critique and the associated activities to evaluate the effectiveness of training, activities and attitudes of personnel, adequacy of procedures, etc. The shipment was a High Integrity Container (H.I.C.) containing dewatered primary bead resins. The H.I.C weighed approximately 5550 pounds and contained approximately 500 Curies in the 120 cubic foot volume. The work proceeded well; each member of the work detail handled their responsibilities in an efficient, professional manne The technicians took a radiation survey at the surface of the truck cask (model no. 8-120) and blocked and braced it to assure compliance with regulatory requirements. Placarding of the vehicle was reviewed by the technicians af ter loading had been complete The inspector reviewed the final survey records of the shipment and concluded that the survey was properly done and well-documente Placarding was done in accordance with 00T regulation _ The inspector selectively reviewed historical records of radwaste shipments and Licensee Event Reports (LERs). No inaccuracies or omissions were note No violations or deviations were identifie . Exit Meeting At the conclusion of the inspection of January 8,1993, an exit eeeting was held with those licensee representatives indicated in Paragraph 1 of this repor The inspector summarized the scope and findings of the inspection and indicated that no apparent violations or deviations were ' identified. The licensee did not indicate that any of the information provided to the inspector during the inspection was proprietary in natur No dissenting comments were received from the licensee. }}