IR 05000338/1985006

Insp Repts 50-338/85-06 & 50-339/85-06 on 850311-14.No Violation or Deviation Noted.Major Areas Inspected: Organization & Mgt Controls,Training & Qualifications, External Exposure Control & ALARA

ML20127J527
Person / Time
Site:	North Anna
Issue date:	04/04/1985
From:	Jenkins G, Peery W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20127J515	List: IR 05000338/1985006 ML20127J511
References
50-338-85-06, 50-338-85-6, 50-339-85-06, 50-339-85-6, NUDOCS 8505210488
Download: ML20127J527 (6)

Text

UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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APR 0 81985-Report'Nos.: 50-338/85-06 and 50-339/85-06 Licenseet Virginia Electric and Power Company Richmond, VA 23261 Docket.Nos.: 50-338 and 50-339 License Nos.: NPF-4 and NPF-7 Facility Name: North Anna 1 and 2

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Inspection Conducted: March 11-14, 1985-Inspectors: W Xf W.W.Peerg Dats Signed

' Accompanying Perso . ' Lee

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. Approved by:, s

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G.'R- Jeh ~ns? Section Chief Date Signed Divisio f Radiation Safety and Safeguards SUMMARY Scope: This routine, unannounced inspection ' entailed 54 inspector-hours on site in the areas of organization and management controls, training and qualifi-cations, external exposure control and ALAR Results: No violations or deviations were identified, f

8505210488 850400 PDR ADOCK 05000338 G PDR

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REPORT DETAILS Persons Contacted

. Licensee Employees

• E. W. Harrel, Station Manager

• M. L. Bowling, Assistant Station Manager R. Infinger, Superintendent of Operations

• D. Wagner, Health Physicist, Corporate

• A..H. Stafford, Supervisor, Health Physics

• F. Termine11a, Supervisor, Quality _ Control S. B. Eisenhart, Licensing Coordinator

• M. Pinion,-Engineering Supervisor J. O'Connel, Assistant Health Physics Supervisor A. Kozak, Operations Instructor

. J. Breeden, Training Specialist

• T. Johnson, Quality Assurance

• A. Hogg, Quality Assurance-Other licensee employees contacted included engineers, technicians, and office personne NRC Resident Inspector

• M. W. Branch

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• Attended exit interview Exit Interview The inspection scope and findings were summarized on March 14, 1985, with those persons indicated in paragraph 1 above. The licensee did not identify as proprietary any of the materials provided to or reviewed by the-inspectors during this inspectio . Licensee Action on Previous Enforcement Matters (Closed) Violation (388, 339/84-40-02) Unmonitored Release of Radioactive Liquid. The inspector reviewed the corrective actions initiated by the licensee in accordance with his letter to the NRC dated December 26, 1984, and concluded that the actions taken should be adequate to preclud recurrence of the violatio . Organization and Management Controls (83722)

. Technical Specification 6.2 described the licensee's organization. Detailed responsibilities and lines of authority were specified in the plant radiation protection pla a

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The' inspector reviewed changes made to the. licensee's organization, staffing

levels and . lines of authority as they related ~to' radiation protection and radioactive material control and verified that the changes.had not' adversely

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affacted .the Itcensee.'s ' ability. to control: radiation exposureslor radio-

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. active material. f Through t discussions with Health . Physics personnel- and

' othe_r groups, it wasL . determined .that the Radiation Protection ~ Manager

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Japparently has adequate responsibility, authority ~and management support to ensure an effective radiation protection program. 'The inspector reviewed

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' training- and . organizational documentation with Radiation Protection Management and supervision and determined that the licensee 'has 'been very successful _ in _ maintaining -a high degree of stability of personnel in the radiation protection progra .No violations or deviations.were identifie ,

5 .' ' Training ~and Qualifications (83723)

a'. Basic Radiation Protection Training

.The licensee was required by 10 CFR- 19.12 to provide basic radiation protection 1 training to ~ workers. Regulatory Guides 8.27, 8.29, and

8.13, outline : topics that should be included in such ' trainin The inspector discussed the initial and refresher general ' employee radiation' protection training -(GET) with~ the Training Supervis_or and

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rev_iewed lesson plan's -to -determine what changes had been made in GET ~ -

training 'and the scope of these changes. An . inspector attended GET ' '

train.ing . sessions for' selected topics' where the program had been

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changedc The inspector reviewed the GET training records for ~ selected workers to determine if records reflected adequate completion' of ~ GET

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initial and refresher training, Radiation Protection. Technician Qualification The inspector.. reviewed' the program for qualification of contract :

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radiation' protection technicians. The inspector discussed .with:

Radiation : Protection Management ~ the technicians' previous' experienc'e

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and training to ' determine if- it was comprehensive or. if 'it had been limited to ' selected tasks. The inspector also discussed the training and qualification program the licensee had provided, what limits had been- placed on their activities, and controls that should be established for one task they were qualified to perfor Radiation Protection Foreman Qualifications Technical Specification 6.3.1 required radiation protection staff to have four years experience in their specialty. The inspector i

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' discussed with ' Radiation: Protection Supervision the radiation protection' training and experience and selected duties and 7* responsibilities of.the. respective position ' ' - Radiation Protection Manager Qualifications

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. Technical Specification 6.3.1 required that -the individual filling

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the. position of Radiation Protection Supervisor meet the qualifi-cations for_a Radiation Protection Manager.specified'in Regulatory

- Guide 1.8. The inspector discussed with the Radiation Protection Supervisor his training and experienc No violations or deviations were identifie _

4 External Occupational Dose Control and Personal Dosimetry (83724)

During ' plan t tours, the -inspector checked the security of the locks at several locked high radiation areas _ and observed posting of survey-results and the use of controls specified on applicable radiation work permits (RWPs).

- a? "Use of' Dosimeters and Controls The licensee was required by 10 CFR 20.202, 20.201(b), 20.101,

. 20.102, 20.104, 20.402, 20.403, 20.405, 19.13, 20.407, and 20.408 L to maintain worker's doses below specified levels and keep records of and make reports of dose The licensee was required by 10 CFR 20.203 -and Technical Specification 6.12 to post and control access - to plant area During observation of work in the plant, the inspector observed the wearing of TLDs and pocket dosimeters by

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V mworker The inspector discussed the assignment and use of dostmeters with radiation protection technicians. During plant tours,

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the inspector observed the posting of areas and observed measurements of dose 'to assure proper postin The inspector reviewed recent

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changes ^to plant procedures regarding the use of TLDs and dosimeter t

" Processing of Dosimeters

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The inspector discussed with the Dosimetry Supervisor the flow of the TLD badge from its return by a worker through the recording of information (dose) from the readout on the worker's dose record, to determine areas where information could possibly be mishandle . The inspector observed the results of the most recent National i

Voluntary Laboratory Accreditation Program (NVLAP) tests and audit t, ;

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4 Dosimetry Results Due to unplanned outages of both units at North Anna, the licensee experienced man-rem overruns in excess of projected exposures. The initial exposure estimate was 773 man-rem for

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calendar year 1984, however, the actual collective exposures of 1918' man-rem was a factor of 2.48 higher than the initial estimat Barring unforeseen outages, the licensee anticipated a marked de-crease in man-rem for the calendar year 1985. For example, as of March 10, 1985,-the initial estimate was 42 man rem and the actual exposures totaled 19 man-re No violation or deviations >were identifie i 7. Maintaining Occupational Doses ALARA (83728)

10 CFR 20.1(c) specified that licensees should implement programs to keep

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workers' doses As Low As Reasonably Achievable (ALARA). FSAR Chapter 12 also contains licensee commitments regarding worker ALARA action Worker and Supervisor Actions

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The inspector discussed dose control measures with radiation pro-

.tection personnel and with maintenance and operations supervisors to determine their degree of involvement in dose reduction. The inspector also discussed actions to set dose goals for tasks, methods used to reduce doses, and techniques used to monitor performance against goal ALARA Procedure Changes The inspector reviewed recent changes to administrative procedures that implemented the elements of ALARA. The inspector discussed these changes with radiation protection personne ALARA Reviews The inspector reviewed the ALARA review documentation for activities during 1984 and through March l1985 and discussed resulting actions with radiation protection personnel.

' ALARA Reports The inspector reviewe$ the ALARA Outage Report for the 1984 outages and discussed ' the -results with the Radiation Protection Manage The summary of tasks estimate for 1984 was 773 man-rem The total cumulative dose for 1984.was 1918 man-rems, due to unplanned outages of both unit No violations or deviations were identifie ,

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8. . Inspector Followup (92701)

.:(Closed)UnresolvedItem(338,339/84-40-01) Failure to Make Exit Whole Body Count. The inspector reviewed the actions taken by the licensee to assure that exit whole body counts are. performed and concluded that the actions should be effective in assuring that the whole body counts are performe .

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