IR 05000346/1986029

Insp Rept 50-346/86-29 on 861022-24.No Violation or Deviation Noted.Major Areas Inspected:Gaseous & Liquid Radioactive Programs,Including Effluent Releases,Records & Repts of Effluents

ML20213F288
Person / Time
Site:	Davis Besse
Issue date:	11/06/1986
From:	Hueter L, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20213F285	List: IR 05000346/1986029 ML20213F284
References
50-346-86-29, NUDOCS 8611140129
Download: ML20213F288 (6)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-346/86029(DRSS)

Docket No. 50-346 License No. NPF-3 Licensee: Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, OH 43652 Facility Name: Davis-Besse Nuclear Power Station (DBNPS)

Inspection At: DBNPS, Oak Harbor, Ohio

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Inspection Conducted: October 22-24, 1986 Inspector: Hu Date

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Approved By: M. C. Schumacher, Chief /'

Radiological Effluents and Date Chemistry Section Inspection Summary Inspection on October 22-24, 1986 (Report No. 50-346/86029(DRSS))

Areas Inspected: Routine, unannounced inspection of gaseous and liquid radioactive programs including: effluent releases; records and reports of effluents; effluent control instrumentation; procedures for controlling releases; reactor coolant chemistry and activity; gaseous effluent filtration, and audit Results: No violations or deviations were identifie )

861114o129 861107 6 PDR ADOCK 0500

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DETAILS 1. Pi rsons Contacted C. Arbac, Systems Engineer L. Bonker, Health Physics Specialist

• R. Cook, Acting Compliance Supervisor - NLD

• R. Dielman, Environmental Monitoring

• D. Erickson, Chemistry and Health Physics Assessment Manager B. Geddes, Senior Quality Assurance Auditor J. Hart, Associate Nuclear Technologist M. Horne, Health Physics Superintendent W. Mills, Plant Process Systems W. Perchiazzi, Senior Assistant Nuclear Engineer B. Randall, Operations

• R. Scott, Chemistry Superintendent i

• J. Scott-Wasilk, Nuclear Health and Safety Director

• B. Smith, Environmental Monitoring L. Storz, Plant Manager

• P. Byron, NRC Senior Resident Inspector

• D. Kosloff, NRC Resident Inspector

, The inspector also contacted other members of the chemistry and health l physics, I&C, and engineering staf * Denotes those present at the exit meetin . Licensee Action on Previous Findings (0 pen) Open Item (346/84-30-02): Stack sample return line. As noted in Inspection Report No. 346/86021, the licensee stated they would resolve by December 1, 1986, a matter concerning the stack sample stream that does not reourn to the source, but instead is released from the side of the Turbine Building. Licensee personnel stated they had performed a test to address a concern that returning the sample line to the stack might significantly reduce the sample flow rat The test was performed with flexible tubing and reportedly showed that returning the sample line to the stack would result in a small improvement in sample flow rat Therefore, the licensee has just issued Facility Change Request FCR-860362, a permanent type modification, involving return of the stack sample stream to its source, the vent stack. The licensee anticipates completion of this modification by December 1, 1986.

. 3. Organization and Staffing Significant organizational and staffing changes have occurred in the Chemistry and Health Physics (C & HP) Group since the last radwaste inspecticn in November 1984. The staff has remained quite stable except for several testers (technicians) who left to seek other employment during a strike. Most of the staffing changes i aolve . new employees to fill a i

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number of new positions in both supervisory and non-supervisory levels resulting largely from the organizational changes which occurred with the recent separation (October 1, 1986) of chemistry and health physics programs. Each discipline now has its own dedicated testers. The organizational changes are intended to expand and improve the C & HP programs. The licensee is working to fill the new positions quickly and had made five offers during the week of October 12-18, 1986, to experienced testers. The General Supervisor of C & HP position has been elevated to the General Superintendent of C & HP position. Both the Chemistry Supervisor and the Health Physics Supervisor positions have been elevated to Chemistry Superintendent and Health Physics Superintendent positions, respectivel New positions of General Foreman have been established in both Chemistry and Health Physic A new section has been established titled C & HP assessment. The C & HP assessment Manager, an experienced, qualified manager hired from the outside, reports directly to the C & HP General Superintendent but has direct access to the plant manager. Four nuclear technologist (three positions currently vacant), a dosimetry records clerk, a senior nuclear engineer; an associate technologist and a health physics specialist all work in C & HP assessment section. All are new positions except for the health physics specialist positions which was transferred from one of the other section No violations or deviations were identifie . Training and Qualification Effectiveness The significantly increased staffing described in the preceding section is intended to improve the program in large part by providing not only a new rather comprehensive training program but the extra manpower needed to carry out the work of those being traine The training program, being carried out in-house by the training department, is designed to lead to INPO accreditation (INPO onsite visit expected by end of 1986) and is designed to involve about 20 percent annually of each assistant testers work hours and about 10-15 percent of the work hours of each tester and higher position. The training will include health physics fundamentals, selected plant systems training, water treatment, chemistry and radiochemistry, liquid and solid radioactive waste handling, radioactive waste shipments, procedures, and a " Qual Card" program. Personnel interviewed during the inspection were knowledgeable of applicable procedures and assigned responsibilitie No violations or deviations were identifie . Gaseous Radioactive Waste The inspector reviewed the licensee's gaseous radwaste management progra The effluent records and semiannual effluent reports were selectively reviewed for last half of 1984 through the first half of 198 . _ _ _ -. - . _ . _ . . . - _ _ _ _ - - - - - - _ _ ,-- -

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d In review of gaseous effluert records and semiannual effluent reports, it was noted that although the licensee collects and has samples analyzed for Sr-89 and 90, this data is not reported in the semiannual effluent report owing to the activity being less than the lower limit of detection (LLD). The same situation exists for Sr-89 and 90 in liquid effluent samples. This matter was discussed with licensee personnel who agreed to record, in future semiannual effluent reports, similar results using both the LLD value and the "less than" symbol, to show that the analysis had been performe This matter will be reviewed during a future inspection and is considered an open ite (0 pen Item 346/86029-01)

i The licensee's gaseous effluents have been very low with noble gas releases totaling about 500 curies in 1984, about 118 curies in 1985, and no measurable noble gas activity in the first half of 198 The licensee has had no unplanned gaseous releases during the review period. The reactor has been shut down since early June 1985 and, therefore, noble gas releases have been minimal since that time. The licensee plans to resume operation in the next few weeks. The licensee has had good fuel cladding integrity which contributed to low noble gas release rates and low dose equivalent I-131 concentrations in reactor coolant when the plant was operatin The RETS Technical Specifications and Offsite Dose Calculation Manual (ODCM) were successfully implemented in late 1985. Release rates in terms of dose have remained less than one percent of technical specification limits for gaseous effluent No violations or deviations were identifie . Liquid Radioactive Waste The inspector reviewed the licensee's liquid radwaste management progra The effluent records and semiannual effluent reports were selectively reviewed for the last half of 1984 through the first half of 198 The licensee liquid effluents (excluding tritium) have been very low, totaling about 1.9 E-1 curies annually in both 1984 and 1985 and about 1.2 E-2 curies during the first half of 1986. The licensee has also had no unplanned liquid releases during the review perio The lengthy shutdown since early June 1985 has contributed to the low levels released in 1986. As noted in Section 5, although the licensee collects and has liquid effluent samples analyzed for Sr-89 and 90, this data is not reported in the semiannual effluent report owing to the activity being less than the LLD. This matter is the subject of an open item as described in Section Except during the last half of 1985, release rates in terms of dose have also remained less than one percent of technical specifications limits

for liquid effluents during the review period. During the fourth quarter of 1985, the total body dose reached about ten percent of the quarterly limit due to Cs-137 in liquid effluents.

i No violations or deviations were identifie ~

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7. Calibrations and Setpoints of Gaseous and Liquid Effluent Monitors The inspector reviewed calibration records for the nonnal range noble gas channel for both Kaman monitors on the station vent. The vendor conducted a type calibration of a model detector with NBS traceable Xe-133 and Kr-85 gas concentrations. To correlate the response of the licensee's detector to the gaseous calibration, both detectors were exposed to NBS traceable solid transfer sources of three different activities and adjustments made to achieve comparable responses. A transfer source is used to make one point solid source calibrations at technical specification required frequencies. At the time of the last radwaste inspection, it was noted that although the transfer source provides traceability to a gaseous calibration, no known gas activity had been introduced into the detector to determine its response to fluid source In response, the monitor was calibrated in early 1985 using plant gases collected from a waste gas decay tank and also gases collected from containment. The determined efficiencies compared favorably with the vendor supplied calibration curve The licensee is working with the vendor of the Kaman monitors on some modifications to improve operability / reliability of the monitor The inspector also reviewed calibration records for four liquid effluent monitors, two on the miscellanecus radwaste line and two on the clean radwaste line. No problems were identified in review of calibration data for the monitors. All four monitors had been calibrated at the frequencies specified in the technical specification The inspector reviewed the setpoint determinations for both the gaseous and liquid monitors described above as well at the containment purge monitor and the waste gas decay tank monitor and found that the setpoints were in all cases established in accordance with the setpoint criteria specified in the ODC No violations or deviations were identifie . Reactor Coolant Chemistry A review of reactor coolant chemistry and specific activity data for 1985 and 1986 to date showed that dissolved oxygen, chloride, fluoride, dose equivalent I-131 and 100/E parameters have remained well within applicable limits. Shortly before the shutdown in early June 1985, the dose equivalent I-131 concentration was 1.3 E-2 sci / gram (limit is 1.0 sci / gram).

Fluoride concentration has always been less then 0.02 ppm (steady-state limit of .15 ppm and transient limit of 1.5 ppm); chloride remains below 0.10 ppm when the purification demineralizers are not in service and below 0.05 ppm when the demineralizers are in service (steady-state limit of 0.15 ppm and transient limit of 1.50 ppm). Dissolved oxygen concentration remains below .005 ppm (steady-state limit of 0.10 ppm and transient limit of 1.00 ppm).

No violations or deviations were identified.

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. HEPA Filter and Charcoal Absorber Systems Three ventilation systems have HEPA filters and charcoal absorbers subject to technical specification requirements. These systems are the hydrogen purge system for containment, both trains of control room ventilation and both trains of shield building emergency ventilation. A review of licensee

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records showed that in November and December of 1984, all three systems were tested end met the technical specification criteria of equal to or greater than 99 percent removal of both 00P by HEPA filters and halogenated hydrocarbon refrigerant test gas by charcoal absorbers when tested in place. Also, samples of activated carbon were removed and laboratory tested and showed less than one percent methyl iodide penetration (technical specification criteria). These tests are required at least once per 18 months in specified modes of operation but not in cold shutdown mode which the licensee has been in since June 1985. The licensee is currently in the process of performing these tests in anticipation of resuming reactor operation in a few weeks. Tests are expected to be completed in about a week. Both trains of control room HEPA filters and charcoal absorbers had been satisfactorily tested in place on October 17, 1986. Both trains of shield building emergency ventilation HEPA filters and charcoal absorbers were tested in place on October 16, 1986. However, the charcoal absorber did not quite meet test criteria for Train 2 (98 plus percent vs 99 percent criteris). The licensee is in the process of replacing this charcoal absorber which will be followed by reperforming in place testing. Remaining in place testing and laboratory testing results of the current testing program will be reviewed during a future inspectio No violations or deviations were identifie Audits The inspector reviewed QA Audit No. 1543 conducted April 21 through May 2, 1986. The purpose of this audit was to verify implementation of Amendment 86 to the Technical Specifications which incorporated the RETS Technical Specifications. Satisfactory corrective action appears to have been taken by the licensee regarding all three audit finding No violations or deviations were identifie . Open Items Open items are matters which have been discussed with the licensee, which will be reviewed further by the inspector, and which involves some action on the part of the NRC or licensee or both. An open item disclosed during the inspection is discussed in Section . Exit Meeting The inspector met with licensee representatives (denoted in Section 1)

at the conclusion of the inspection on October 24, 1986. The inspector summarized the scope and findings on the inspection. The inspector also

, discussed the likely information content of the inspection report with

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regard to documents or processes reviewed by the inspector during the inspection. The licensee identified no such documents / processes as proprietar . . . . - . - - . - __.- - . .__ _

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