IR 05000322/1986007

Insp Rept 50-322/86-07 on 860505-09.No Violations Noted. Major Areas Inspected:Organization & Staffing,Qa Audits, Internal & External Exposure Control & Status of Previously Identified Items

ML20198R035
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	06/02/1986
From:	Cioffi J, Dragoun T, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20198Q989	List: IR 05000322/1986007 ML20198Q984
References
50-322-86-07, 50-322-86-7, NUDOCS 8606090439
Download: ML20198R035 (8)

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) U.S. NUCLEAR REGULATORY COMMISSION

] REGION I

Report N /86-07

Docket N li a

License N NPF-36 Priority -

Category C l

j Licensee: Long Island Lighting Company 1 P. O. Box 618

{ Wading River, New York 11792

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Facility Name: Shoreham Nuclear Power Station

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j Inspection At: Wading River, New York

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Inspection Conducted: May 5-9, 1986

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Inspectors: /m / d J. Cioffi iation S ialist date

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T'. Drago

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adiation Specialist s&>be dats

Approved by

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! M. Shanbaki, Chief, Fac(11 ties date Radiation Protection Section

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I Inspection Summary: Inspection on May 5-9, 1986 (Report No. 50-322/86-07)

Areas Inspected: Routine unannounced radiological controls inspection of the following areas: organization and staffing, QA audits, internal and external

, exposure control, and status of previously identified item '

Results: No violations were identifie !

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8606090439 860602

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DETAILS 1.0 Persons Contacted During the course of this routine inspection, the following personnel were contacted or interviewed:

1.1 Licensee Personnel J. Notaro, Director of Safety and Compliance

• J. Scalice, Operations Manager and Assistant Plant Manager E. Cubeta, Instrument Services Foreman

• N. DiMascio, Health Physics Engineer M. Donegan, Radiological Support Supervisor

• Glazier, QCD Section Head

• Grunseich, Operational Compliance Engineer

• Refacey, Compliance Engineer

• Seaman, QC Division Manager

• J. Schmitt, Rad. Con. Division Manager

• D. Smith, Compliance Engineer W. Telfer, HP Shift Technician R. Thompson, Dosimetry Foreman B. Whitmer, Control Point Foreman

• Attended the exit meeting on May 9, 1986

1.2 NRC Personnel J. Berry, Senior Resident Inspector C. Warren, Resident Inspector 2.0 Puipose The purpose of this routine inspection was to review the licensee's radiation protection program with respect to the following elements:

Status of Previously Identified Items

Organiza'. ion and Staffing

QC Audits

External Exposure Control

Internal Exposure Control L-

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3.0 Status of Previously Identified Items 3.1 (0 pen) Follow-up Item (83-19-04) Licensee to ensure that process and effluent monitors collect representative samples. The licensee will complete an engineering evaluation of sample line losses and publish the results by June 20, 198 .2 (Closed) Follow-up Item (85-38-01) The Plateau Summary Report dated December 10, 1985, section 2.3 (0 pen Test Exceptions) was revised to explain the four test exception .3 (0 pen) Follow-up Item (85-38-02) Complete startup testing of offgas syste Testing of system inleakage is complete. The hydrogen recombiner and radiological performance will be tested during 20*J to 100% power ascensio .4 (Closed) Follow-up Item (85-38-03) Upgrade High Radiation area controls. Procedure WI-005, Revision 0, issued in January 1986 provides for control of keys to locked high radiation exclusion area .5 (Closed) Follow-up Item (85-38-04) TIP access upgrades. Procedure SP 62.065.02, " Traversing Incore Probe Room Access Controls," was issued in January 198 .6 (Closed) Follow-up Item (85-38-05) Upgrade drywell access. Procedure 62.063.01 issued in February 1986 improves the HP access controls for drywell entries during fuel movement and TIP operation .7 (Closed) Follow-up Item (85-38-06) Improve skin exposure monitoring in beta radiation fields. Work Instruction #003 was revised to specify wearing the personnel dosimeter in the PC clothing breast pocke .8 (Closed) Follow-up Item (85-38-07) Frovide eye protection in beta radiation fields. Procedure 12.012.01, " Radiation Work Permit," was revised to include instructions to HP technicians to specify use of goggles for eye protection in beta field .9 (Closed) Follow-up Item (85-38-08) HP personnel should remain current with respect to procedure changes. Work Instruction #010 issued in November 1985 requires the HP Engineer to identify important procedure revisions and ensure that HP staff personnel review the revisio .10 (Closed) Follow-up Item (85-04-14) Calibrate low volume air sampler Selected battery operated air pumps were calibrated with high back pressure silver zeolite cartridges by an offsite vendo Special rotometer scales reading in fractional CFM were attached to each unit.

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3.11 (Closed) Follow-up Item (85-26-01) Review Radwaste Operator retrain-ing program. A two-week comprehensive course was presented by vendors in December 198 .0 Organization and Staffing The organization and staffing within the Health Physics Section was reviewed with respect to criteria contained in:

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Technical Specification 6.3, Unit 3taff Qualifications

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Technical Specification 6.5.2.8, Audits

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ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel

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Regulatory Guide 1.8, Personnel Selection and Training

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Station Procedure No. 61.001.01, " Health Physics Program - Policy and Objectives"

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Station Procedure No. 12.002.01, " Organization and Administration"

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Station Procedure No. 61.040.01, " Health Physics Technician Selection, Training and Qualification Program" The licensee's performance relative to these criteria was determined from a review of job description and personnel resumes and interviews with the Health Physics enginee Within the scope of this review, no violations were identifie The inspector determined that the positions for Supervisor - Technical Support and Radiological Engineer were vacant. There are two individuals filling the roles of four foreman position The Supervi2or - Radiological Controls position is filled by a contractor. Although some understaffing is indicated, there is adequate supervisory oversight due to the low level of work activity and low radiation levels. An audit of the Health Physics Section was completed in March 1986 by the Quality Assurance Departmen (Audit No QC-86-03). The inspector noted that this audit was thorough and comprehensiv .0 Quality Assurance Audits The licensee is required to perform audits of the radiological safety program as described in Technical Specification 6.5 - Review and Audit and 10 CFR 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants. As a result of an internal evalu-ation of the Auditing Program in early 1985 :nd NRC identified problems in the Radiochemistry program, the licensee reorganized and restructured the QA function beginning in mid-1985. The licensee embarked on an b

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aggressive performance oriented auditing. program as described in a letter to the NRC dated April 18, 1986. The inspector determined the status of these improvements by discussions with the Quality Control Division Manager and his staff, an interview with the Director of Safety and Compliance, reviews of the training department audit report, audit schedules and selected surveillance report forms. Licensee strengths were noted as follows:

Specific corporate goals and milestones for 1986 include establishment of performance based audits, evaluation of trends and identification of precursors, and enhanced technical training for the auditing staf This new approach represents a significant departure from the previous compliance-based auditing program and is in tune with recent innovations for quality assurance program Auditing staff personnel were provided training in health physics concepts by contractors (Impell and Bartlett). Experienced consultants are used as team members during audits to provide additional technical depth. These efforts improve the effectiveness of audits of the HP program The audit of the training program was commendable for its scope and dept The extensive findings were also analyzed by the licensee to identify the major programmatic weaknesses in the training progra ,

6.0 External Exoosure Controls The licensee's program for controlling external exposures was reviewed against criteria contained in:

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10 CFR 20.101,102, 202, 203, 401, 407, 408, and 409;

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Technical Specification 6.11, " Radiation Protection Program";

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Regulatory Guide 8.7, " Occupational Radiation Exposure Records Systems"; and

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ANSI N13.11 - 1983, " Personnel Dosimetry Performance - Criteria for Testing."

The licensee's performance related to the above criteria was determined by:

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review of personnel monitoring procedures;

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discussions with dosimetry personnel and control point technicians;

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review of dosimetry records and quality control performance data;

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observations of dosimetry use during plant tours; and

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observation of the use of the source and calibration set-uo for direct reading dosimeter calibrations and QC performance checks on TLDs.

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Within the scope of this review, the following was noted:

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The licensee identified the limitations of the presently used two chip TLD system for personnel monitoring at the site and purchased a four chip Panasonic dosimetry system for personnel monitoring before the plant begins commercial operation. The licensee plans to have the Panasonic system in place by the end of 198 Through a quality control check of the vendor dosimetry system used at Shoreham, the licensee identified a problem of increasing under-estimates of dose by the vendor's TLD results. This QC check enabled the licensee to inform the vendor of the negative bias on their TLD results and initiate corrective actions by the vendor. Due to the success of identifying this bias, the licensee instituted a formal quality control procedure which is used routinely to assure the adequate assessment of doses reported by the vendor TLD No violations or deviations were identified in this revie .0 Internal Exposure Controls The licensee's program for controlling internal exposures and assessing the adequacy of their internal exposure controls was reviewed against criteria contained in:

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10 CFR 20.103;

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Technical Specification 6.11, " Radiation Protection Program";

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ANSI N343 - 1978, " Internal Dosimetry for Mixed Fission and Activation Products";

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Regulatory Guide 8.15, " Respiratory Protection Programs";

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NUREG 0041, " Manual of Respiratory Protection Against Airborne Radioactive Materials";

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ANSI N13.1 - 1969, " Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities."

7.1 Air Sampling Program The licensee's performance in air sampling related to the above criteria was determined by:

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review of procedures for calibration and use of air sampling equipment, and a review of the licensce's procedure for implementing the air sampling program;

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discussions with licensee personnel;

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observation of the air sampiing equipment during plant tours and available to the licensee; and

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observation of the calibration of a Radeco variable speed air sampling pump.

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Within the scope of this review, the following was identified:

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The inspector observed that the licensee did not calibrate the Radeco variable flow air samplers for the lower ranges of use (2 cubic feet per minute). Furthermore, rotameters on the air sample pumps were not related to true air flow by means of a calibration graph for each instrumen The inspector discussed these findings with the licensee. The licensee stated that the procedure for calibrating air sampling pumps would be revised to clarify the calibration procedure and include generating a calibration curve for each air sampling pump. The licensee will also calibrate the rotameters on the pumps for the range of flows used to sample air. This item will remain open and be reviewed in a future inspectio (86-07-01)

7.2 Whole Body Counting Program The licensee's performance in whole body counting and in vivo assessment of radioactive uptakes related to the criteria in section 7.0 was determined by:

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review of the applicable procedures;

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discussions with licensee personnel;

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review of calibration data and daily performance checks;

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review of whole body count data for three workers; and

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demonstration of the calibration set-up for the five geometries used by the licensee on the whole body counte There were no violations or deviations identified in this revie However, the inspector observed that the licensee did not properly use and trend daily background and efficiency data to ensure that the whole body counting system was performing properl The inspector discussed the appropriate use of quality control charts with the licensee. The licensee stated that quality control charts for daily

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background and efficiency would be initiated and maintained to track the performance of the whole body counter, as a quality assurance method specified in ANSI N343 - 1978. This item will remain open and be reviewed in a future inspection. (86-07-02)

7.3 Respiratory Protection Program The licensee's performance in respiratory protection rel3ted to the criteria contained in section 7.0 was determined by:

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a review of the applicable procedures;

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review of equipment used in the respiratory protection program, including masks and related components and accessories; fit-booth, and mask maintenance equipment; and storage facilities for respirators and parts; and

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discussions with licensee personnel.

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Within the scope of this review, no violations or deviations were i

identified. The licensee's program contained the essential elements for adequate respiratory protection in accordance with regulatory l requirements, j 8.0 Exit Interview

The inmector met with licensee personnel denoted in section 1.1 at the

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cenclu:1tn of the inspection on May 9, 1986. The scope and findings of

! the inspe: tion were discussed at that time.

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