IR 05000261/1982013

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IE Insp Rept 50-261/82-13 on 820419-23.No Noncompliance Noted.Major Areas Inspected:Training,Respiratory Protection Air Sampling Program,Exposure Controls,Personnel Qualifications & Licensee Action on Previous Insp Findings
ML20053E250
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 05/12/1982
From: Albright R, Barr K, Franklin L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20053E247 List:
References
50-261-82-13, NUDOCS 8206070730
Download: ML20053E250 (6)


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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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E I4EGION 11

o 101 MARIETTA ST N.W., SUITE 3100 ATLANTA, GEORGIA 30303

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MAY 171982 Report No. 50-261/82-13 Licensee:

Carolina Power and Light Company 411 Fayetteville Street Raleigh, North Carolina 27602 Facility Name:

H. B. Robinson Docket No. 50-261 License No. DPR-23 Inspection at H. B. Robinson site near Hartsville, South Carolina

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2,,, Mb Inspectors:

c L. A. Franklin'

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5 6 -S -V Date Signed 6-6'/.2.

it. H. Albrigit Date Signed Approved by:

b AMOM F-I ~4 -2 M if K. Barr, Sectipn Chief j

Date Signed Technical Inspection Branch Division of Engineering and Technical Programs SUMMARY

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Inspection on April 19-23, 1982 Areas Inspected

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This routine, unannounced inspection involved 74 iaspector-hours on site in the areas of training, respiratory protection, air sampling program, exposure controls, personnel qualifications, and licensee action on previous inspection l

findings.

Results

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Of the six areas inspected, no violations or deviations were identified.

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8206070730 820517 PDR ADOCK 00000261

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REPORT DETAILS

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1.

Persons Contacted Licensee Employees

  • R. B. Starkey, Jr., Plant General Manager
  • D. S. Crocker, Manager, Environmental and Radiation Control i
  • C. L. Wright, Specialist, Regulatory Compliance
  • W. L. MacCready, Radiation Control Supervisor i
  • K. Traegde, Health Physics Engineer W. T. Ritchie, Radiation Control Foreman

D. Boan, Radiation Control Foreman H. McManus, Training Assistant

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  • F. Gilman, Senior Specialist, Regulatory Compliance
  • W. Webster, Manager, Radiation Control and Chemistry Support i

Other licensee employees contacted included two mechanics and six office personnel.

NRC Resident Inspector

  • S. Weise
  • Attended exit interview l

2.

Exit Interview

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The inspection scope and findings were summarized on April 23, 1982,'with those persons indicated in paragraph 1 above.

The plant general manager acknowledged the inspectors concerns.

3.

Licensee Action on Previous Inspection Findings (Closed) Violation 81-07-36 - This item concerned the movement of contami-

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.nated sediment from the settling pond in the plant Radiation Control Area (RCA) to an ash pond outside the RCA but still on property owned by the

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licensee.

The licensee completed a safety evaluation for the contaminated material in the ash pond and concluded that there is no expected impact to the health and safety of the public. The licensee is conducting hydro-

logical studies of several areas on their property, including the settling ponds. These studies will determine flow and sediment characteristics of

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the settling ponds. The ash ponds are in the environmental sampling program and are included in the environmental report. The inspector had no further i-questions.

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4.

Unresolved Items Unresolved items were not identified during this inspection.

5.

Licensee Action on Previous Inspector Identified Items

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IFI 81-07-02 This item concerned inadequate record and documentation practices in the area of radiological records. The licensee has provided training to personnel who generate records in order to ensure that these personnel make corrections to records in a proper manner when required. Surveys are now recorded on maps and make it easy to determine the radiological conditions of the surveyed area. The inspectors reviewed-several types of records and found them to be in good order. The inspector had no further questions.

(Closed) IFI 81-07-04 This item concerned a lack of job specific health physics training for workers at H. B. Robinson.

The inspector received health physics training for. the steam generator work in progress.

This training was given by the training department and appeared adequate.

The licensee has also developed additional training for HP personnel who cover the steam generator work as well as mock-up training for personnel involved in the steam generator work.

Other mock-up training was developed for cutting out a RHR valve which had an extremely high radiation reading. The inspector had no further questions.

(Closed) IFI 81-07-05 This item' concerned documentation of escort training given to permanent plant personnel. The licensee no longer gives separate escort training to permanently badged personnel. The inspector has received the radiation worker training required to get a permanent plant badge and the steam generator health physics training required for personnel to enter i

the containment vessel.

The inspector concluded that personnel received sufficient training so that separate escort training is not required. The inspector had no further questions.

(Closed) 81-07-16 This item concerned calibration of the CAM's.'

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licensee experienced frequent maintenance problems with the CAM's.and has j

now taken all but the stack monitor out of service. The licensee intends to

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purchase replacement CAM's during the next fiscal year. The inspector had

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no further questions.

(Closed) 81-07-42 This item concerned protective clothing being in bad

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repair and being in an area that flooded when it rained. The roof over this area has been repaired and a check of the clothing available indicated that the clothing was in good condition. The inspector had no further questions.

(Closed) 81-20-01 This item concerned functional tests, counting geometry and establishment of dead time limits for use of the GeLi system.

The inspector reviewed procedure changes which satisfactorily addressed the concerns. The inspector had no further question.

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t (Closed) 82-01-01 This item concerned a monthly survey instrument inventory which a licensee procedure required to be completed within the first week of i

each month. The procedure has been revised to require the inventory to be completed during the month.

A licensee representative stated that the inventory is performed as early as possible during the month. Since-this-was only a backup to other licensee controls for survey instruments the inspector had no further questions.

(Closed) 82-01-02 This item concerned the 'recertification frequency of a new model of self contained breathing apparatus in use at this facility. The licensee contacted the manufacturer for this information and has a letter in

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their file to this effect. The inspector had no further questions.

(Closed) 82-01-03 This item concerned the need to provide documentation that personnel entering a high radiation area are provided a dose rate instrument

or an HP escort. Instrument check-out logs, personnel interviews and direct observation of personnel entering high radiation areas indicate that the I

licensee is meeting technical specifications requirements.

The inspector had no further questions.

6.

Training a.

The inspector selectively reviewed the training records of radiation control personnel and maintenance personnel.

These records included j

basic radiation safety training, retraining, and respiratory protection training.

The records appeared to be in good order and the training appears adequate to cover the requirements of 10 CFR 19 and Appendix A to Regulatory Guide 8.13 concerning exposure to radiation during pregnancies.

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The inspector was required to attend the course mandatory for steam

generator workers. The duration of the course was approximately one hour and a test was given at the conclusion.

Emphasis was placed on procedures, dosimetry, exposure levels, and the fact that health physics personnel were in charge during this work. The course was informative and well presented.

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7.

Respiratory Protection Program

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a.

By review of records, observation by the inspector, and discussions

with licensee representatives the inspector evaluated the respiratory-protection program for compliance with 10 CFR 20.103, Regulatory Guide 8.15, NUREG 0041, and plant procedures. Technical Specification 6.11 requires that procedures for personnel radiation protection be j

consistent with the requirement of 10 CFR 20 and be maintained and adhered to for all operations invovling personnel radiation exposure.

Records of air samples, bioassays, MPC-hours, medical evaluations, training, and respirator maintenance and fit tests were selectively reviewed and appeared, to be adequate.

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8.

Air Sampling Program t

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The facility. air sampling program was reviewed. The licensee requires air samples for all RWP's. The air sampling frequency for each RWP varies with

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the probability. of an airborne contamination problem. The number of air samples taken during the refueling outage appear adequate.

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The facility has experienced continuous maintenance problems with inplant

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continuous air monitors (CAM). Plant management decided that the CAM's were not dependable and removed all CAM's from service except the stack flow CAM.

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A licensee representative stated that replacement CAM's are in the proposed budget for 1983. The inspector questioned the adequacy of the facility air sampling program during normal operation because 1) the number of RWP's issued during normal operation and therefore the number of required air samples are significantly reduced when compared to the outage situation, 2) routine air sampling is on a weekly basis, and 3) the facility does not

put low-volume air samplers in various plant areas to add confidence in their air sampling program.

The inspector stated that this area would be

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reviewed during a future inspection (82-13-01).

9.

Records i

During the inspection the inspectors reviewed several types of records. A

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poor documentation practice was noted regarding RWP 186. The RWP contained

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a note, " Rewritten for Clarification."

The original of the RWP was apparently destroyed. The inspector stated that the original record should be maintained.

This area will be reviewed in a future inspection

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(82-13-02).

10.

Tour of Radiation Control Area The inspector toured the turbine building, auxiliary building, containment vessel and outside areas.

During tours, the inspectors. reviewed the

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licensee's posting and control of radiation areas, high radiation areas, airborne radioactivity areas, contamination areas, radioactive material areas, and the labeling of radioactive material.

No violations or

deviations were observed.

During the containment vessel tour, the inspector observed decon of a

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reactor coolant pump shaf t and the X-ray inspection of a reactor coolant pump bowl.

Health physics coverage and controls for these jobs appeared adequate.

11.

Personnel Qualifications l

Technical Specification 6.3.1 states that the qualifications of each member

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of the facility staff shall meet or exceed ANSI 18.1-1971.

An inspector i

reviewed the resumes of various personnel on the radiation control staff and found that all personnel appear to meet or exceed the qualifications requirements of ANSI 18.1-1971.

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Exposure Controls l

The inspector reviewed licensee radiation work permits currently in effect.

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Survey records that were pertinent to-these radiation work permits were also examined and appeared adequate.

The inspectors reviewed the exposure

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records of selected personnel on these RWP's and found that one worker had

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the potential for an overexposure which is currently under investigation.

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Information available-at the time of the inspection indicated that the'TLD exposure may not be accurate. However, the incident is under investigation

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i and the licensee expects to make a conclusion as to the individual's exposure in the near future and submit 'a final report to this region for evaluation. NRC-Form 4's were properly completed for the above individual

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and other selected personnel who the licensee allows to exceed 1250

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mrem / quarter.

The inspector, during the review of RWP's and survey data, noted that the licensee makes adequate use of multiple whole body and extremity dosimetry.

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