ML20207K071
| ML20207K071 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/18/1986 |
| From: | Kuzo G, Stoddart P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20207K043 | List: |
| References | |
| 50-413-86-23, 50-414-86-25, NUDOCS 8607290329 | |
| Download: ML20207K071 (8) | |
See also: IR 05000413/1986023
Text
{{#Wiki_filter:. _ _ _ _ m . . . . UNITED STATES Ceco [[pO . 'o NUCLEAR REGULATORY COMMISSION REGION 88 p $ ,. j 101 MARIETTA STREET.N.W. 2 ATLANTA. GEORGI A 30323
, %,*****/ JUN 2 6 BBS Report Nos.: 50-413/86-23 and 50-414/86-25 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 ' Docket Nos.: 50-413 and 50-414 License Nos.: NPF-35 and NPF-48 Facility Name: Catawba 1 and 2 Inspection Cond ted g June 2-5, 1986 ' Inspector: 9 s . Id ' G.~B. Tuz' ' Date Signed M 7E Approved by: 7 , P. GT Steddart? Acting Section Chief Date Signed j Division of Radiation Safety and Safeguards SUMMARY Scope: This routine, unannounced inspection involved review of liquid and gaseous radwaste systems; liquid and gaseous effluent sampling, analysis, and monitoring; and review of inspector followup items. Results: One violation was identified - Failure to follow procedures for gamma spectroscopy measurements of gaseous effluent process samples. ! i DR ADO K O PD a . . - . - . - - . _ , .
- . -_ _ _ _ _ _ _ _ _ - . , 2 , REPORT DETAILS 1. Persons Contacted Licensee Employees
- J. W. Hampton, Plant Manager
- J. W. Cox, Technical Services Superintendent
- W. P. Deal, Station Health Physicist
- C. k. Wray, Health Physics Supervisor
- B. M. Chundriik, Health Physicist
- C. S. Gregory, Maintenance, I&E Superintendent
- A. S. Bhatnagar, Performance
- C. L. Hartzell, Licensing and Project Engineer
- F. P. Schiffley, Licensing Engineer
- P. N. McNamara, Health Physicist
T. Robinson, I&E Engineer B. Wrayfield, I&E Specialist W. Green, Engineer Other licensee employees contacted included engineers, technicians, operators, and office personnel. NRC Resident Inspectors
- P. K. VanDoorn
- M. Lesser
- Attended exit interview
2. Exit Interview The inspection scope and findings were summarized on June 5,1986, with those persons indicated in Paragraph 1 above. The inspector discussed the following inspector followup items: inclusion of background limits and sensitivity requirements in EMF calibration procedures (Paragraph 6.c.) and review of design changes to EMF-50 to ensure proper operability (Paragraph 7.d.). One potential violation concerning failure to follow established procedures for gamma spectroscopy analyses of gaseous effluent process samples was discussed (Paragraph 6.b.). Licensee representatives acknowledged the inspector's comments. The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection. 3. Licensee Action on Previous Enforcement Matters (50-413/85-50-02, 50-414/85-60-02) VIO: Failure to have Adequate Procedures to Implement QA Program. The inspector discussed changes to the radioanalytical QC program and reviewed selected inter-detector comparison _ _ , _ _.
. . 3 data. The inspector noted that the high "between detector" variability noted in a previous inspection (IE Report No. 50-413/85-50, 50-414/85-60) has been reduced. This item is considered closed. . 4. Unresolved Items Unresolved items were not identified during the inspection. 5. Audits (84723,84724) a. Technical Specification (TS) 6.5.2.9 states that audits of unit activities shall be performed under the cognizance of the Nuclear Safety Review Board (NSRB) encompassing: the conformance of unit operation to provisions contained within the technical specifications and applicable license conditions at least once per 12 months; the radiological environmental monitoring and the results thereof at least once per 12 months; the Offsite Dose Calculation Manual and implementing procedures at least once per 24 months; and the performance of activities required by the Quality Assurance Program for l effluent and environmental monitoring at least once per 12 months. The inspector reviewed the following audit reports: QA Audit NP-85-8(CN) Technical Services and Operations Activities, April 15 - May 1, 1985. QA Audit NP-85-18(CN) Technical Services and Administrative Services Activities, September 16 - October 2, 1985. QA Audit NP-86-3(CN) Performance Group, January 20 - February 5, 1986. QA Audit NP-86-8(CN) Health Physics and Environmental Group Activities, April 1-25, 1986. The inspector noted that the licensee audits verified compliance with the applicable Technical Specifications, ANSI standards, station and corporate procedures, and 10 CFR regulations. The licensee audits did not identify any areas of concern in the areas reviewed during this inspection. No violations or deviations were identified. 6; Procedures (84723, 84724) a. Technical Specification 6.8.1 states that written procedures shall be established, implemented and maintained covering the applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978, "Offsite Dose Calculation Manual Implementation," and in the Quality Assurance Program for effluent and environmental monitoring. 4
. . . _ _ _ ... . . . . _ _ _. . _ _ _ _ _ . ,- ~ . j 4
B (1) OP/0/A/6500/18- Operating Procedure for the Release of a Waste
Gas Decay Tank (2) OP/0/B/1001/16: Operation and Calibration: ORTEC ADCAM GAMMA Analysis System, May 8, 1986. ! (3) HP/0/B/1001/12: Technical Specifications Gaseous Waste Sampling
and Analysis, Rev. 11, December 3, 1985. (4) HP/0/B/1000/03: Correlation of EMF's, June 14, 1984. i ! (5) HP/0/B/1001/19: Counting Room Intrastation/Interstation Cross Check Program
3 ] (6) TP/1/B/2600/15: Process and Effluent Monitor Test, July 17, 1985. _ (7) IP/0/B/3314/14: Radiation Monitoring System Iodine Activity, ! 1 EMF 37 & 40, 2 EMF 37 & 40, May 10,1984. I (8) IP/0/B/3314/13: Radiation Monitoring System (EMF) Particulate
j Activity Monitor Channel Calibration 1 EMF 35, 1 EMF 38, 2 EMF 35, i 2 EMF 38, March 4, 1985. j (9) IP/0/B/3314/11: Radiation Monitoring System Dual Range Gamma i Activity Monitors, May 8, 1984. (10) IP/0/8/3314/09: Radiation Monitoring Systen: Dual Range Beta Channel Calibration, May 4, 1984. i f The inspector discussed results of the procedure review with cognizant j licensee representatives as detailed in Paragraphs 6.b and 6.c. ! b. The inspector discussed with cognizant licensee representatives the ! gamma spectroscopy analysis of liquid and gaseous process samples. The ,
inspector noted that HP/0/B/1001/16, " Operation and Calibration: ORTEC ' ' ADCAM GAMMA Analysis System," stated that a count rate is acceptable if j detector dead-time is less than 10%. The procedure further specified that if detector dead time was greater than 10%, the sample was to be 3 , counted at a higher ' level or was to be diluted. Following review of i . gaseous waste release reports (Paragraph 7), the inspector noted that - l the 10% dead-time limit had been exceeded on numerous occasions from January 1986, through May - 1986. The inspector pointed out that as dead-time increases for the gamma spectroscopy system, non-conservative inaccuracies increase for analytical measurements. The inspector informed licensee representatives that the failure to adhere to- the- gamma spectroscopy analysis procedures for process gas analyses was a potential violation (50-413/86-23-01, 50-414/86-25-01).
c. The inspector discussed effluent monitor calibration - and set point determination procedures with cognizant' lice.nsee representatives. The , ' inspector noted that the ' sensitivity of the effluent monitors was I .. . - . . . . . . . .
- . 5 affected by background radiation levels. Approved procedures for l monitor calibratica and set point determination required technicians to record background radiation levels; however, the procedures did not provide details to ensure instrument sensitivity limits were met. Licensee representatives stated that cognizant licensee individuals were aware of the limits and were consulted during monitor calibrations and set point determinations. Licensee representatives agreed to provide more detail in the procedures regarding this item. The inspector informed licensee representatives that this issue would be reviewed during a subsequent inspection (50-413/86-23-02, 50-414/86-86-25-02). Violation (50-413/85-23-01, 50-414/85-25-01) Failure to follow procedures for gamma spectroscopy analyses of gas effluent process samples. Open Item (50-413/86-23-02, 50-414/86-25-02) Improved detail regarding background and sensitivity limits of effluent monitors. 7. Review of Records, Logs and Reports (84723, 84725) a. The inspector reviewed selected portions of the following records and logs: (1) Safety Related Filter Run Time Monitoring, 1985. (2) Radiciodine Penetration and Retention Test Reports - Control Room Area (VC) System, 1985-1986. (3) EMF-36(L) Unit Vent Noble Gas Monitor 1984-1985 (a) Analog Channel Operational Test (b) Instrument Calibration Sheet (4) EMF-35(L) Unit Vent Particulate Monitor, 1985 (a) Flow Calibration - (b) Channel Calibration (5) EMF-49, 1985 (a) Flow Calibration (b) Channel Calibration (6) EMF-50, 1984-1986 (a) Channel Calibration (b) Flow Calibration (7) Liquid Waste Release (LWR)/ Gaseous Waste Release (GWR) Log Book 1985-1986 s . .-
. - 6 (8) Unit Vent Unknown Noble Gas Activity Work Sheet, 1985 (9) LWR Records, January-May 1986 (10) WGR Records January-May 1986, for Containment Purge (VP), Containment Air Release and Addition System (VG) and Waste Gas Decay Tanks for the following analyses: (a) Noble Gas Grab Sample (b) Charcoal Cartridge (c) Particulate Filter (11) 1985 Semiannual Effluent Release Reports Results of the record review are discussed in Paragraphs 7.b, 7.c and 7.d, below. b. Technical Specification 6.9.1.7 states that Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The inspector reviewed and discussed the 1985 Semiannual Radioactive Effluent Release Reports with cognizant licensee representatives. There were no reports of abnormal releases. Dose estimates from the uranium fuel cycle at Catawba Nuclear Station were estimated to be 0.88 mrem and 2.2 mrem, total body and GI-LLI (maximum organ) respectively. The Semiannual Effluent Release report for 1986 was not available for review at the time of the inspection. c. The inspector discussed gaseous waste release reports with cognizant licensee representatives. The inspector noted that for noble gas analyses using the marinelli beaker, procedural dead timo limits were exceeded on several occasions but that dead-time limits were not exceeded for any other analyses. Licensee representatives informed the inspector that the gas marinelli geometry was calibrated only for one sample to detector distance and thus the sample could not be analyzed . at increased distances from the detector surface. The inspector informed licensee representatives that when the problem of exceeding the dead-time limit was first observed, study should have been conducted to evaluate the effect of increased dead-time on the accuracy of gaseous effluent process samples. The failure to follow the procedural limits and to conduct a proper evaluation of exceeding the specified dead-time limits resulted in the violation noted in j Paragraph 6.b. d. The inspector discussed EMF-50, Waste Gas Decay Tank monitor calibrations with cognizant licensee representatives. Licensee representatives informed the inspector that selected concerns regarding monitor operability had been identified and documented in Intrastation Letter CN-215.10, dated May 27, 1986. These concerns included
- - 7 nonrepresentative sampling, inleakage from multiple gas sources into the common discharge header, aspiration and backflow of water into the instrumentation, inadequate position of the waste gas control valve, and pressure effects regarding setpoint methodology. The inspector noted that operability of this system was deferred from Unit 1 to the Unit 2 FSAR commitments. The inspector noted that prior to any WGDT release, EMF-50 must be operable. Licensee representatives stated that corrective actions regarding this monitor are being evaluated. The inspector informed licensee representatives that this item will be reviewed during a subsequent inspection (50-413/86-23-03, 50-414/86-25-03). Open (50-413/86-23-03, 50-414/86-25-03) Review of WGDT noble gas monitor (EMF-50) operability. No violations or deviations were identified. 8. Verification of Effluent Monitor Operability (84724, 84725) The inspector toured the control room with cognizant licensee represent- atives and verified readouts of all operable effluent process monitors. The inspector verified by direct inspection operability of the Liquid Waste (EMF-49) and the Unit 1 Vent (EMF-35, -36, -37) effluent monitors. All areas were clean and equipment appeared to be properly maintained. No violations or deviations were identified. 9. Inspector Followup Items (92701) a. (50-413/85-50-01, 50-414/85-60-01): IFI Review of Radiological Effluent Measurement QA Procedures for Changes to Ensure Adequate Measurement Capability. The inspector discussed changes to the Quality Assurance (QA) Program for radioanalytical measurements. Changes included improved review and trending of selected quality control data, and the development of a single procedure outlining the Catawba Nuclear Station Intrastation and Interstation cross check programs. This item is considered closed. b. (50-413/85-50-03, 50-414/85-60-03): IFI Review of Licensee's Evaluation of Alpha / Beta & Beta / Gamma Effluent Measurements. The inspector discussed this issue with cognizant licensee representatives and noted that corrective actions were in progress. The licensee had initiated a program (1) to define and evaluate drift problems associated with the detectors, (2) to correct any identified > deficiencies in equipment electronics and detector counting gas, and (3) to define quality control (QC) charts using both the instrument and counting standard deviations. Licensee actions regarding this item were detailed in a memorandum, " Meeting Regarding Instability of Tennelec LB-5100 Efficiency," dated January 30, 1986. Th;s item is , considered closed. - _ _ -- . _ j
. . . . 8 c. (50-413/85-50-04, 50-414/85-60-04) IFI Review 6f Licensee's Fe-55 Analysis of NRC Spiked Samples. The inspector confirmed that the i licensee had received the spiked sample from the NRC contract laboratory. Analyses had not been completed at the time of the inspection but licensee representatives stated that results would be provided to the NRC Region II Office by July 31, 1986. This item is considered closed. . I ! i 4 % .. l i , 4 '
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