IR 05000269/1982029

IE Insp Repts 50-269/82-29,50-270/82-29 & 50-287/82-29 on 820712-16.No Noncompliance Noted.Major Areas Inspected: Radiation Protection,Shipment of Radioactive Matl,Personnel Dosimetry,Portable Instrument Calibr & Review of LERs

ML20062J464
Person / Time
Site:	Oconee
Issue date:	07/23/1982
From:	Barr K, Collins T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20062J427	List: IR 05000269/1982029 ML20062J424
References
50-269-82-29, 50-270-82-29, 50-287-82-29, NUDOCS 8208160375
Download: ML20062J464 (6)

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[ 4'f, UNITED STATES 8 NUCLEAR REGULATORY COMMISSION g a REGION ll _

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

Report No. 50-269/82-29, 50-270/82-29, and 50-287/82-29 Licensee: Duke Power Company P. O. Box 2178 Charlotte, NC 28242 Facility Name: Oconee Nuclear Station Docket Nos. 50-269, 50-270, and 50-287 License Nos. DPR-38, DPR-47, and DPR-55 Inspection at Oconee Nuclear Station near Seneca, South Carolina Inspector: a # #L T'.'R. Collin /Date ' Signed Approved by: ~ m 7 9/86 ~

K. P/ Barr, ection Chief '/Dat( Signed Technical Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on July 12-16, 1982 Areas Inspected This routine, unannounced inspection involved 33 inspector-hours on site in the areas of radiation protection, shipment of radioactive material, personnel dosimetry, portable instrument calibrations, respiratory protection program, contamination of primary demineralizer water header, health physics controls of Unit 3 refueling outage, posting, labeling and control, and review of licensee event report Results Of the nine areas inspected, no violations or deviations were identified in nine area PDR ADOCK 05000269 G PDR

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REPORT DETAILS Persons Contacted Licensee Employees

• J. Ed Smith, Station Manager

• T. B. Owen, Superintendent of Technical Services

• J. N. Pope, Superintendent of Operations

• C. T. 'Iongue, Station Health Physicist C. L. Harlin, Projects and Training Coordinator

• D. L. Davidson, Associate Health Physicist J. A. Long, Support Functions Coordinator B. A. Murphree, Health Physics Administrative Supervisor S. E. Spear, Health Physics Supervisor J. E. Owens, Health Physics Supervisor J. J. Sevic, Station Biologist

• L. Benge, Associate Chemist D. P. Rochester, Station Chemist R. Brown, Chemistry Coordinator

• T. C. Matthews, Technical Specialist

• R. C. Adams, Inspection and Enforcement Engineer

• J. J. McCool, Quality Assurance Representative

• R. P. Rogers, Licensing Engineer Other licensee employees contacted included four technicians, three security force members, and two office personnel .

Other Organizations Rad Services, In Numanco NRC Resident Inspector

• T. Orders

• D. P. Falconer

• Attended exit interview Exit Interview The inspection scope and findings were summarized on July 16, 1982, with those persons indicated in paragraph 1 above. The inspector discussed the cross contamination of the primary demineralizer water header in the Auxiliary Building with licensee management. The station manager acknowl-edged the inspector's concerns of the demineralizer water system. The inspector informed licensee management that this incident would be left as an unresolved item pending further evaluation (see paragraph 15).

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3. Licensee Action on Previous Inspection Findings Not inspecte . Unresolved Items Unrecolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. New unresolved items identified during this inspection are discussed in paragraph 1 . Inspector Follow-up Items (Closed) 79-33-01 (INF) Liquid Release in Excess of 10 CFR 20 Values. The inspector discussed this with a licensee representative and concluded that the sewage treatment sump was inside the restricted area but outside the radiation controlled area and that routine patrols by security personnel were being performed. The inspector had no further question (0 pen) 80-BU-10 (IFI) Contamination of Non-Radioactive Syste The inspector discussed this with licensee personnel and stated that IE Bulletin 80-10 requires that if a non-radioactive system becomes contaminated, a 10 CFR 50.59 Safety Evaluation will be performed if the system is consioered necessary for continued operation. The 10 CFR 50.59 Safety Evaluation must consider the level of contamination (i .e. , concentration and total curie inventory) and any potential releases (either routine or accident) of radioactivity to the environmen The relationship of such releases to the radioactive effluent limits of 10 CFR 20 and the facility's Technical Specifications and to the environmental radiation dose limits of 40 CFR 190 must also be evaluated. The record of the Sifety Evaluation must set forth the basis and criteria on which the determination was made. The inspector stated that this evaluation would be insp(cted upon the next routine inspectio . Licensee Event Reports (LER's)

Reportable Occurrance R0-287/82-05 (Closed) Spent Fuel Pool Ventilation Fans not operable during movement of fuel . The inspector reviewed the licensee's corrective action which incorporated a revision to prevent the movement of fuel, stating specifically what equipment should be tagged when the Spent Fuel Pool Fans or associated circuits are tagged out. The inspector con-cluded this appeared to be adequate and had no further question Reportable Occurrence R0-269/82-21 (Closed) Proper valve line up for release of Laundry and Hot Shower Tank's (LHST's). The inspector reviewed the licensee's corrective action which incorporated revision to all appropriate procedures to specify proper valve line ups for the release of LHST's. The inspector concluded this appeared to be adequate and had no further question < a

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f 7. Posting, Labeling and Control The inspector reviewed the licensee's posting, and control of radiation areas, high radiation areas, airborne radioactivity areas, contamination areas, radioactive materials areas, and the labeling of radioactive material during tours of the Auxiliary Building, Reactor Building, and Turbine Building. No discrepancies were observe The inspector also performed independent surveys of Radiation Control Zones (RCZ's) to determine proper labeling and posting of RCZ's. The inspector concluded that posting, labeling and control appeared to be adequate and had no further question . Notification and Reports The inspector reviewed the licensee's records to determine if radiation exposure data had been provided to terminated employees as required by 10 CFR 19.13(d). The inspector reviewed the first quarter of 1982 terminated employees and verified that each employee had been sent a letter regarding his radiation exposure history. The inspector had no further question The inspector discussed with a licensee representative the reporting requirements of 10 CFR 20.402, 403, 405, and 408 and reviewed plant records. No deviations were identifie . Surveys The inspector selectively reviewed records of radiation, contamination and airborne radioactivity surveys performed in July 1982, of the Unit 3 Reactor -

Building (Containment) and discussed the survey results with licensee repre-sentatives and observed the work in several active work areas to verify that the licensee was following the regulatory requirements of 10 CFR 20.103, 201(b) and 401(b). The inspector concluded that proper surveys were being performed and had no further question . Respiratory Protection Program The inspector reviewed and discussed the licensee's respiratory protection program with licensee representatives on issuance of respirators, MPC-hour

, controls, inspection of respirators, training of personnel and respiratory

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medical qualificatio The inspector concluded upon his review that the respiratory protection program appeared to be adequate and had no further

question . Posting of Notices 10 CFR 19.11 requires, in part, that each licensee post current copies of

10 CFR 19 and 10 CFR 20 or, if posting of the documents is not practicable, j the licensee may post a notice which describes the document and states where

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it may be examined. 10 CFR 19.11 further requires that copies of any Notice

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of Violation involving radiological working conditions be conspicuously posted within two working days af ter receipt of the documents from the Commission. The inspector observed the posting of notices required by 10 CFR 19.11 and had no further question . Shipment of Radioactive Material On July 15, 1982, the inspector observed a radioactive waste shipment, number ONS-82-276, being loaded for shipment to Chem Nuclear Systems, In (CNSI) for buria The waste shipment was low specific activity (LSA)

compacted waste involving 47 55 gallon drums and three wooden boxes. The inspector concluded after his review of the Radioactive Shipment Record (RSR) and independent radiation surveys of the shipping vehicle and packages that the radioactive waste shipment appeared to meet 10 CFR 71 and 40 CFR Department of Transportation (DOT) requirement . Instruments and Equipment The inspector observed a variety of radiological instruments (portable survey instruments, portal monitors, personnel friskers) in use and avail-able for use. The inspector checked calibration stickers, performed battery checks for selected portable instruments in operating plant and response checked selected portable instruments for proper operation. The inspector discussed the radiation survey instrument calibration program with licensee representatives. The inspector had no further question . Personnel Frisking The inspector observed workers in the change room performing personnel frisking of themselves after exiting the Unit 3 containment RC The inspector concluded after his review and observations that the workers were adequately frisking themselves using the proper technique The inspector had no further question . Contamination of the Primary Demineralized Water Header On July 9, 1982, two personnel, upon exiting the Radiation Control Area, determined they were contaminated. Health Physics was contacted and it was determined that the demineralized water hose and portable demineralizer where the two personnel were working were contaminate Further surveys revealed that approximately 200 square feet of ground near the Unit 3 Reactor Building were also contaminated. Health Physics personnel set up an adequate Radiation Control Zone (RCZ) around this area until the soil and gravel could be removed. The licensee removed approximately 4800 lbs. of soil and gravel in nine 55 gallon drums and stored it for future radioactive waste shipment for burial. The licensee determined the cause of the con-tamination to be from the primary demineralized water (DW) header near the CNSI mobile solidification syste The licensee immediately tagged all valves associated with the DW system, " closed" restricting use of D V

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Additionally, the licensee began flushing the demineralized water lines to remove the radioactivit However, this flushing will take some time to remove the entire residual remaining in the DW System. The licensee also has revised all appropriate procedures to begin sampling DW System on a periodic frequenc The inspector concluded the licensee's corrective action was adequate and that further investigation to determine the cause of the contaminated primary DW header should continue until the actual cause has been identified. The inspector informed licensee management that this incident would remain as an unresolved item pending final evaluation and determination of the cause of the contaminated DW System (269/270/287-82-29-01).

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