IR 05000413/1989026

Insp Repts 50-413/89-26 & 50-414/89-26 on 890821-24.No Violations or Deviations Noted.One Unresolved Item Identified.Major Areas Inspected:Organization & Mgt Controls & Maintaining Radiation Exposures ALARA

ML20248B756
Person / Time
Site:	Catawba
Issue date:	09/20/1989
From:	Collins T, Potter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20248B748	List: IR 05000413/1989026 ML20248B743
References
50-413-89-26, 50-414-89-26, NUDOCS 8910030278
Download: ML20248B756 (6)

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pQ rec UNITED STATES

1. oq'o NUCLEAR REGULATORY COMMISSION f

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n REGION 11 101 MARILTTA STREET, g j

• 5 g ATLANTA, GEORGI A 30323

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Report Nos.: 50-413/89-26 and 50-414/89-26 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: E0-413 and 50-414 License Nos.: NPF-35 and NPF-5?

Facility Name: Catawba 1 and 2 Inspection Conduc^ed: A ust 21-24, 1989 Inspector:

T. R. Collins-cus //6 Date' 51gned Approved by: I/I-J. P. Potter, Chi ~ef //

h f/7e//f Date Signe Facilities Radiation Protection Section Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards SUMMARY Scope:

This routine, and special unannounced insoection was conducted to eninate the licensee's radiation protection program. The review included: licensee organization and management controls; maintaining occupational exposures as low as reasonably achievable (ALARA); control of radioactive materials and surveys; internal and external exposure control; and licensee action on previously identified inspection findings. During this inspection, the inspector was accompanied by three Soviet Union Nuclear Regulatory Comission (SUNRC)

personnel who wished to become familiar with the United States Nuclear Regulatory Comission (USNRC) radiological inspection program. A significant portion of this inspection involved accompaniments and translations with the three SUNRC visitor Results:

No violations or deviations were identifie One unresolved item was identified in the area of adequate corrective actions to prevent unlocked or unsecured high radiation area doors. The licensee's ALARA program appeared to be adequate as indicated by their lower than national average collective dose total <330278 890920 FDR ADOCK 05000413 o PDC

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REPORT. DETAILS Persons Contacted Licensee Employees

• H. Barron, Superintendent Operations C. Couch, Health Physics Supervisor G. Courtney,' Supervising Scientist P. Deal,' Station Health Physicis '

• J. Forbes, Manager, Technical Services

• R. Glover, Technical Services, Compliance

• V. King, Compliance Engineer

• T. Owen, Station Manager ,

• L. Schlise, General Supervisor, Health Physics Other licensee employees contacted during this inspection included  !

technicians, maintenance personnel,-and office personne United States Nuclear Regulatory Commission

• Lesser, Resident Inspector

• Order, Senior Resident Inspector

• M. Shymlock, Section Chief, Division of Reactor Projects Soviet Union Nuclear Regulatory Commission

l A. Davidov, Physicist A. Kordyuk, Deputy Regional Administrator V. Stovboun, Inspector

• Attended exit interview Occupational Exposure, Shipping and Transportation (83750)

i Organization and Management Controls 2 The licensee was required by Technical Specification (TS) 6.2 to implement the plant organization specified in Table 6.2.2-1. The responsibilities, authorities, and other management controls were further outlined in Chapters 12 and 13 of the' Final Safety Analysis i Report (FSAR). TS 6.2.3 specifies the members of ~the Catawba Safety l Review Group (CSRG) and outlined its. functions and authoritie Regulatory Guide 8.8 specifies certain functions and responsibilities i to be assigned to the Radiation Protection Manager (Station Health Physicist) and radiation protection responsibilities to be assigned to line managemen :

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The inspector reviewed recent changes to the plant organization, to determine their effect on plant radiological controls, by examining the resulting changes to administrative procedures and position descriptions and by discussing the changes with the Acting Station Health Physicis The inspector discussed with operations maintenance and radiation protection personnel, the type, methods of, and degree of interaction between plant groups. The inspector discussed with the Acting Station Health Physicist and selected radiation protection personnel, how often they toured they plant, radiation control areas (RCAs), and reviewed documentation of these tours. It was determined that an adequate number of tours had been mad No violations or deviations were identifie b. Staffing i TS 6.2.2 specifies minimum plant staffin FSAR Chapters 12 and 13 I also outline further details on staffing. The inspector discussed the authorized staffing level vs. actual on-board staffing with the Acting Station Health Physicis The inspector examined shift

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staffing for the period of August 21 to August 23, 1989, to determine if it met the minimum criteria for radiation protectio The .

inspector also determined that the licensee uses sufficient contract I health physics (HP) technicians to support refueling and maintenance )

outage J No violations or deviations were identifie c. Control of Radioactive Materials and Contamination, Surveys and Monitoring

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The licensee is required by 10 CFR 20.201(b) and 20.401 to perform surveys to show compliance with regulatory limits and to maintain records of such surveys. Chapter 12 of the FSAR outlines radiation survey methods and instrumentation and TS 6.8 requires the licensee to follow their written procedure Catawba radiological control procedures further outline survey methods and frequencie The inspector observed, during plant tours, surveys being performed by the radiation protection staf The inspector reviewed selected i Radiation Work Permits (RWPs) during the inspection to determine if adequate controls were specified. The inspector discussed the RWP controls and monitoring with the assigned radiation protection technicians and selected worker The inspector performed independent radiation level surveys and found them to be consistent with licensee measurement During plant tours, the inspector observed radiation level and contamination survey results outside selected cubicle The inspector performed independent radiation level surveys of selected

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l areas and observed satisfactory comparison with licensee survey results. The inspector reviewed selected survey records for the month of August 1989, and discussed with licensee representatives the methods used to disseminate survey results. The inspector also noted that only approximately 10 percent of the RCA was controlled as ,

contaminated. The licensee's goal for 1989 is to reduce the amount 1 of contaminated area to less than 8,000 square feet (ft2) which is '

equivalent to approximately 5 percent. The licensee's total RCA, excluding fuel pools and containments, is approximately 162,500 ft2, ,

No violations or deviations were identifie High Radiation Areas 10 CFR 20.203(2)- requires that each entrance or access point to a high radiation area be maintained locked except during periods when j access to the areas is required, with positive control . over each 1 entr The inspector was informed by the NRC Senior Resident Inspector'(SRI)

that a Notice of Violation (NOV) was . issued in NRC Inspection Report No. 50-413 and 50-414/89-16 on July 25, 1989, for failure to lock a high radiation area. At the time of this inspector's observations (August 21-24,1989), the licensee's response to the NOV had not been received by the NRC Region II Office. However, since the NOV was issued, the licensee has identified two or three occasions _where they have found high radiation area doors- unlocked. The licensee's investigation of the root causes of these events revealed that mechanical failure of door closers, latching mechanisms, and personnel error were the root causes for these events. The inspector discussed this issue with licensee representatives and the NRC ,

Resident Inspectors. The inspector determined after consultation !

with the NRC resident inspectors, that since the licensee's  !

correttive action had not been completed to preclude further events 1 af this nature, the NRC Resident Inspectors would review this issue when the licensee's corrective action is received.- The inspector _

informed licensee management representatives that subsequent !

violations could be issued if adequate corrective actions are not j taken to prevent unlocked high v adiation areas. The inspector also '

informed licensee management representatives that this issue would be i considered an unresolved item (URI) pending corrective actions taken 1 to prevent unsecured and unlocked high radiation areas (URI:50-413, !

414/89-26-01).  ;

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e. External Exposure Controls The licensee is required by 10 CFR 20.101(b)(3) to determine an individuals accumulated occupational dose to the whole body on an NRC

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Form 4 or equivalent record prior to exceed the limits of 10 CFR 20.101(a) permitting

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the individual The inspector to selectively

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reviewed occupational exposure histories for individuals who exceeded !

the values in 10 CFR 20.101(a) for the period of January 1989 to l

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August 198 The exposure histories were being completed and maintained as required by 10 CFR 20.102.

i 10 CFR 20.101 specifies the applicable radiation dose standards. The inspector reviewed the computer printouts (NRC Form 5 equivalent) for the period of January to August 1989, and verified that the radiation doses recorded for plant personnel were well within the quarterly limitsof10CFR20.101(a).

No violations or deviations were identifie As low As Reasonably Achievable (ALARA) Program 10 CFR 20.1(c) states that persons engaged in activities under I licenses issued by the NRC should make every reasonable effort to maintain radiation exposure ALARA. The recommended elements of an ALARA program are contained in Regulatory Guide 8.8, Information Relevant to Ensuring that Occupational Radiation Exposure at Nuclear Power Stations will be ALAR The inspector discussed the ALARA goals and objectives for 1989 with licensee representatives and reviewed the person-rem estimates and results. The licensee's goal for 1988 was 551 person-rem. The actual collective exposure for 1988 was 556, which is well below the national average for a two unit Pressurized Water Reactor (PWR).

The licensee has established a goal of 474 person-rem for 1989, of

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which 305 person-rem has been expended through July 1989. The inspector determined by review that :n:. licensee's ALARA program i

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appeared to be adequate, as indicated by their lower than national average person-rem total No violations or deviations were identifie . Licensee Actions on Previously Identified Inspector Findings (92701)

(Closed) IFI 50-413, 414/89-11-0 This item concerned the licensee's i method for controlling calibrated pressure gauges utilized with supplied air respirators to ensure that sufficient flow could be maintained. The inspector determined by review that the licensee has identified by numerical sequence each pressurt gauge in the Mine Safety and Appliance (MSA) air manifold box to verify and control calibration frequencies of pressure gauges when they are due for calibratio The inspector had no further question . Exit Interview The inspection scope and results were summarized on August 24, 1989, with those persons indicated in Paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection results listed abov The licensee acknowledged the inspection findings and took no

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exception Licensee management was informed of the status of the '

inspector followup ite:a discussed in Paragraph 3. The licensee did not identify as proprietary any of the material provided to or reviewed by the ,

inspector during the inspectio {

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Item Number Description and Reference f

50-413, 414/89-26-01 URI - Adequate corrective actions to prevent unlocked or unsecured high radiation doors (Paragraph 2.d).

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