IR 05000413/1985017

Insp Repts 50-413/85-17 & 50-414/85-14 on 850429-0503.No Violation or Deviation Noted.Major Areas Inspected:Liquid & Gaseous Radwaste Mgt

ML20127M055
Person / Time
Site:	Catawba
Issue date:	05/13/1985
From:	Montgomery D, Stoddart P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20127M054	List: IR 05000413/1985017 ML20127M050
References
50-413-85-17, 50-414-85-14, NUDOCS 8507010078
Download: ML20127M055 (9)

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p% fig UNITED STATES g 'o NUCLEAR REGULATORY COMMISSION REGION 88

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p 101 MARIETTA STREET, g j

• 2 ATLANTA, GEORGI A 30323

%,*****/ gay 151985 Report Nos.: 50-413/85-17 and 50-414/85-14 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos'.: 50-413 and 50-414 License Nos.: NPF-35 and CPPR-117

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Facility Name: Catawba 1 and 2 Inspection Cond edgpril29-May3,1985 Inspector: d[ry / N P. ModHiiFt Date Signed Approved by: . lh. / e/Acu S/M/SI Danfel'M Montqpmery,t}Section Chief Date Signed Emergency Preparednes's and Radiological Protection Branch Division of Radiation Safety and Safeguards SUMMARY Scope: This routine, unannounced inspection entailed 36 inspector-hours on site in the areas of liquid and gaseous radwaste managemen Results: No violations or deviations were identifie PDR 0 ADOCK 05000413 PDR

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, REPORT DETAILS Persons Contacted Licensee Employees

• J. W. Hampton, Station Manager

• J. W. Cox, Superintendent, Technical Services A. Duckworth,' Coordinator, Radwaste Chemistry R. H. Charest, Station Chemist

• W. P. Deal, Station Health Physicist

• P. G. LeRoy, Licensing Engineer R. A. Amos, Completion Engineer

• G. T. Mode, Coordinator, Support Functions C. V. Wray, Health Physics Supervisor, Counting Room T. L. Titchenal, Support Engineering Staff M. Hutcheson, Test Engineer

• P. N. McNamara, Health Physicist R. E. DeShazo, Shift Supervisor, Health Physics

• C. L. Hartzell, Compliance Engineer A. Bhatnagar, Test Engineer M. Seagle, Technical Associate, Training G. G. Barrett, Training Supervisor Other Organizations T. L. Bohart, Consultant, Performance Engineering NRC Resident Inspector

• P. H. Skinner, Senior Resident Inspector

• P. K. VanDoorn, Senior Resident Inspector

• Attended exit interview Exit Interview The inspection scope and findings were summarized on May 3, 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 inspector during this inspectio . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Audits and Appraisals (80721, 84723, 84724)

Technical Specification 6.5.2.9 requires audits of the radiological environmental monitoring program at least once each 12 months, of the Offsite Dose Calculational Manual (0DCM) and implementing procedures at

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least once each 24 months, and of the Process Control Program (PCP) and implementing procedures at least once each 24 month Technical Specification 6.5.2.9.n requires audits of analytical quality control, licensee contractors, and of service vendors once each 12 month The inspector reviewed QA audit NP-85-2(CN), dated February 14, 1985, covering administrative services and maintenance activitie The report included an audit of the CDCM. The inspector also reviewed QA audit NP-84-17(CN), dated October 30, 1984. The report included audits of analytical laboratory quality control, the ALARA program, measuring and test equipment, radioactive waste process control program, and the radiological environmental monitoring program. A licensee representative informed the inspector that an audit of the radiological environmental monitoring program had begun on April 15, 1985, but had not been completed as of the dates of the inspectio No violations or deviations were identifie . Changes to Equipment'and Procedures (84723, 84724)

Technical Specification 6.15 requires that major changes to radioactive liquid and gaseous radwaste treatment systems shall be reported to the Commission in the Semi-Annual Radiological Effluent Release Report for the period in which the safety evaluation was reviewed. Since Unit 1 was not made critical until January 1985, the first semi-annual report period had not been completed as of the dates of the inspection. Through inspection of the liquid and gaseous radwaste facilities for Units 1 and 2, review of

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procedures and discussion with licensee personnel, the inspector determined that no major changes had been made since the previous inspection (September 1984), or since Unit I criticality was achieved January 9, 198 Technical Specification 6.8.1 requires the licensee to establish, implement,

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and maintain written procedures. The inspector reviewed the following i procedures which had been issued or revised since the previous inspection.

l All procedures listed below had been reviewed and approved by the l appropriate plant management, as provided in the specification.

l HP/0/B/1004/04: Radioactive Liquid Waste Release, February 12, 1985 HP/0/B/1001/02: Sample Preparation for Counting Room Equipment, January 5, 1985 l HP/0/B/1001/14: Preparation and Counting of Composite Samples, April 22,

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1985 HP/0/B/3314/13: Radiation Monitoring System (EMF) Particulate Activity Monitor Channel Calibration, March 4, 1985 PT/0/A/4450/02: Generic Filter Performance Test Instruction, December 7, 1984 PT/0/A/4450/018: Control Room Area Outside Air Pressure Filter Trains, December 7, 1984

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PT/0/A/4450/17: Safety Related Filter Run Time Monitoring, February 26, 1985 ID/0/8/4000/01: Performance Calibration of Halogen Monitor, January 7, 1985 No violations or deviations were identifie . Semi-Annual and Annual Reports (84723, 84724)

Technical Specification 6,9,1,6 requires the licensee to submit an Annual Radiological Environmental Report. Technical Specification 6.9.1.7 requires the licensee to submit a Semi-Annual Radiological Effluent Release Repor Since the Technical Specifications became effective on January 9,1985, at the time criticality was first achieved on Unit 1, the initial reporting periods for both of the above-listed reports had not been completed as of the dates of the inspection; therefore, no reports had been required or submitted at the time of the inspectio No violations or deviations were identifie . Radioactive Liouid Wastes and Liquid Effluent Treatment Systems (Unit 1 -

84723, Unit 2 - 84523)

Technical Specification 3.11.1.1 establishes limits for concentrations of radioactive materials in liquid effluent The inspector reviewed selected liquid effluent release permits for the period of January 1, 1985, through April 15, 1985, and determined that the calculated release concentrations at the point of discharge were less than the limits of the Technical Specificatio Technical Specification 3.11.1.3 requires that the liquid radwaste system be operable and requires the appropriate portions of the liquid radwaste system to be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to liquid effluents from the site, when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any orga The inspector reviewed selected liquid effluent release permits for the period January 1,1985, through April 15, 1985. The inspector verified, by calculation using the manual methods described in the ODCM, that the calculated doses had not exceeded the specified limits during the period January 15, 1985, through April 15, 1985. It was noted, however, that the licensee had elected to use the liquid radwaste system for the entire period to minimize the radioactivity content of affluent Technical Specification 3.11.1.2 requires the licensee to limit the dose or dose commitment to an individual from radioactive materials in liquid effluent releases to:

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5 During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any orga The inspector reviewed the ODCM and corresponding implementing procedures as well as selected release permits and dose calculation records to meet the requirements of Technical Specification 3.11.1.2. Dose calculation records 4 indicated that the specified limits had not been exceede Technical Specification 6.10.2 requires that records of gaseous and liquid radioactive material released to the environs shall be retained for the duration of the Unit Operating Licens 'The inspector verified from selected records of liquid and gaseous effluent releases made during the period of January 1, 1985, through April 15, 1985, that the records reqyired by Technical Specification 6.10.2 were retained in terms of frequency and conten The liquid radwaste treatment system was designed as a shared system and will be used for both Units 1 and At the time of the inspection, the system was being operated using only the ion exchange demineralizers and filters. Expended resins were sluiced to a holding tank, pending transfer to a contractor mobile facility where, periodically, the resins will be sluiced to a shipping cask for dewatering prior to shipment to an offsite disposal facility. The contractor has the capability for solidification of resins or other wastes in concrete for shipment to the offsite disposal facilit No violations or deviations were identifie . Radwaste Gaseous Wastes and Gaseous Effluent Treatment Systems (Unit 1 -

84724, Unit 2 - 84524)

Technical Specification 3.11.2.1 requires that the dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to: For noble gases: less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and For radioiodines and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half-lives greater than eight days: less than or equal to 1500 mrem /yr to any orga The inspector reviewed selected logs and records for the period of January 1, 1985, through April 15, 1985, and determined that the calculated dose rate was within the limits of the Technical Specificatio Technical Specification 3.11.2.2 requires that the air dose due to noble gases released in gaseous effluents from each reactor unit, to areas at or beyond the site boundary, shall be limited to:

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l During any calendar quarter: less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and During any calendar year: less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

l The inspector reviewed selected logs and records for the period January 15, 1985, through April 15, 1985, and determined that the calculated noble gas air dose was within the limits of the Technical Specificatio Technical Specification 3.11.2.3 requires that the dose to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from each reactor unit to areas at or beyond the site boundary shall be limited to: During any calendar quarter: less than or equal to 7.5 mrems to any organ, and

' During any calendar year: less than or equal to 15 mrems to any orga The inspector reviewed selected logs and records for the period January 1, 1985, through April 15, 1985, and determined that the calculated dose was within the limits of the Technical Specificatio Technical Specification 3.11.2.4 requires that the waste gas holdup system and the ventilation exhaust treatment systems shall be operable and that appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases from each reactor unit, to areas at or beyond the site boundary would exceed either: .2 mrad to air from gamma radiation, or .4 mrad to air from beta radiation, or .3 mrem to any organ of a member of the publi The inspector reviewed selected records and logs of gaseous effluent releases for the period of January 1, 1985, through April 15, 1985, and determined that the projected doses due to gaseous effluent releases from plant ventilation exhaust, were within the prescribed limits. In the period from January 1,1985, through the dates of the inspection, no releases had been made from the waste gas holdup system; therefore, the inspector was unable to review waste gas holdup system release permit Technical Specification 3.11.2.6 requires that the quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 97,000 curies of noble gases (considered as Xe-133).

The inspector reviewed selected records and logs of gaseous concentrations in gaseous storage tanks for the period January 1,1985, through April 15,

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1985, and determined that the maximum quantity of radioactivity in each tank had been a small fraction of the prescribed limi In the inspector's review of compliance with Technical Specifications, the inspector reviewed the ODCM and relevant implementing procedures for determining projected offsite doses resulting from gaseous effluent releases. The inspector also reviewed selected procedural records of the calculation of projected offsite doses and verified certain of the licensee's determinations by calculation, using the manual methods described in the ODCM and implementing procedure No violations or deviations were identifie . Operation and Testing of Air Cleaning Filtration and Adsorption Systems (Unit 1 - 84724, Unit 2 - 84524)

Technical Specifications 3/4.6.1.8, 3/4.7.6, 3/4.7.7, 3/4.9.4.2, and 3/4.9.11 provide reqpirements for system operability, testing of charcoal adsorber sample retention efficiency for methyl iodide, and for in place leak testing of HEPA filter and charcoal adsorption sections of Engineered Safety Feature (ESF) filtration system ESF filtration and adsorption systems at Catawba include the Annulus Ventilation System, Control Room Area Ventilation System, Auxiliary Building Filtered Exhaust System, and Fuel Handling Ventilation Exhaust System. The Containment Purge Ventilation System is a non-ESF syste The inspector reviewed selected records and logs of the operability of ESF and non-ESF filtration and adsorption systems, of HEPA filter and charcoal adsorber leak tests, and of charcoal sample methyl iodide retention efficiency tests. The Unit 1 systems were all operational at the time of the inspectio The Unit 2 Auxiliary Building Filtered Exhaust System was also operational because it served a portion of the shared Auxiliary Buildin The inspector examined the Unit 2 ESF and non-ESF filtration and adsorption systems as part of the preoperational inspection program. The inspector noted that the licensee inspection organization had identified excessive gaps or spaces between components of the bulk-load charcoal adsorber structure. The gaps or spaces were such as to permit the possible loss of charcoal fines or small fragments of charcoal. Similar gaps or spaces had been identified in the Unit 1 ESF systems and had been corrected by seal welding. A licensee representative indicated that a similar technique would be used to correct the Unit 2 adsorber structures. The inspector will review the licensee's corrective actions in a subsequent inspectio (Inspector Followup Item 50-414/85-14-02, Review Actions to Correct Excessive Spacing in Charcoal Adsorber Cells of ESF Air Treatment Systems).

No violations or deviations were identifie _

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10. - Effluent Radiological Monitoring Instrumentation (Unit 1 - 84723 and 84724, Unit 2 - 84523 and 84524)

Technical Specifications 3.3.3.10 and 3.3.3.11 require that effluent radioactivity monitors shown in Table 3.3-12 (for liquid effluents) and Table 3.3-13 (for gaseous effluents) shall be operable with their alarm / trip setpoints within the specified limits, as determined in accordance with the Offsite Dose Calculation Manual (0DCM).

The inspector reviewed appropriate sections of the licensee's ODCM and corresponding implementing procedures for determining and adjusting alarm / trip setpoints. The inspector also reviewed selected release permits for instrumentation setpoints and verified that the bases for the setpoints were understood by affected operators and technician Technical Specification Tables 4.3-8 and 4.3-9 provide surveillance requirements for liquid and gaseous effluent monitor The inspector reviewed selected logs and records and verified that the required channel calibration and channel functional surveillance tests had been performed at the prescribed interval Table Notations (2) and (3) of Technical Specification Tables 4.3-8 and 4.3-9 require that channel calibration of liquid and gaseous effluent monitors be made to appropriate reference standards that have been obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards (NBS).

The inspector reviewed selected source procurement documents and verified that calibration standards had been obtained from a supplier participating in measurement assurance activities with the NB No violations or deviations were identifie . Technical Training and Qualification of Unit Staff (92706)

Technical Specification 6.3.1 requires each member of the unit staff to meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Health Physicist who is to meet or exceed the qualifications of Regulatory Guide 1.8, September 197 Technical Specification 6.4.1 provides for the maintenance of a staff retraining and replacement program to meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971, Appendix A of 10 CFR 55, and Enclosure 1 of the March 28, 1985 NRC letter to all licensee The inspector reviewed selected training material and training files for process chemistry technicians and radwaste chemistry technician The review included Section 10.8, Chemistry Training Programs, Nuclear, of the Training Program Plan. System training for the Post-Accident Sampling System (PASS) was also reviewed, n

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No violations or deviations were identifie . Inspector Followup (92701)

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(Closed - Unit 1) LER 84-19, Continuous Sampling of Unit i Vent Disable Licensee took appropriate action to prevent a recurrence by locking open the inlet and outlet valves to the vent sampling pump.

l (Closed - Unit 1) LER 84-13, Turbine Building Sump / Steam Generator Water Sample Radiation Monitors Inoperabl Licensee took appropriate administrative action by revising procedures and operations round sheets to minimize the potential for a recurrenc No violations or deviations were identifie .

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