IR 05000395/1986020
| ML20214N053 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/18/1986 |
| From: | Dan Collins, Harris J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20214N043 | List: |
| References | |
| 50-395-86-20, NUDOCS 8612030521 | |
| Download: ML20214N053 (10) | |
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NOV 211986 Report No.: 50-395/86-20 Licensee: South Carolina Electric and Gas Company Columbia, SC 29218 Docket No.:
50-395 License No.:
NPF-12 Facility Name: Summer'
i Inspection Conducted: ~0ct'ober 20-24, 1986 Inspec or:
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J. D1, Harris Date Signed
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Accompanying Personnel:
R.c R. Marston
Approved 'by: YM9No f' hllut4 II-Il ~ 9 (*
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D. M.iCollins, Chief.
Date Signed Emergency' Preparedness and Radiological Protection Branch
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Division of. Radiation Safety and Safeguards SUMMARY Scope: This routine, unannounced inspection was conducted in the areas of liquid and gaseous radwaste management, environmental programs, and the post accident sampling system.
Results: No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- 0. S. Bradham, Director, Nuclear Plant Operations
- W. R. Baehr, Manager, Corporate Health Physics and Environmental Programs
- W. F. Bacon, Associate Manager, Chemistry
- J. W. Cox, Associate Manager, Health Physics L. F. Faltus, Acting Plant Chemist / Chemistry Supervisor
- J. Sowell, Count Room Supervisor
- J. Proper, QA Supervisor, Operations
- E. H. Rollins, Corporate Health Physicist V. Prawdzik, Instrument and Control Coordinator D. Bergen, Maintenance Engineer
- M. D. Blue, Regulatory Compliance Engineer A. Monroe, Regulatory Compliance Engineer
- G. Parsons, ISEG Engineer P. J. Krawczyk, Chemistry Specialist Other licensee employees contacted included technicians and office personnel.
Nuclear Regulatory Commission
- R. Prevatte, Senior Resident Inspector
- P. Hopkins, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on October 24, 1986, 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 inspection.
3.
Licensee Action on Previous Enforcement Matters (Closed) Violation 50-395/85-19-01, Failure to Meet Technical Specification LLD Requirements for Xe-138.
l The inspector reviewed Procedure HPP-808, Sample Analysis.
The procedure specifies a maximum of 45 minutes from the midpoint of the sampling interval and sample analysis.
This would allow the required LLDs to be met.
During the inspector's review of gaseous release permits, no deviation from the sampling procedure was noted.
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4.
Audits and Appraisals (80721, 84723, 84724)
Technical Specification 6.5.2.8 requires audits of the radiological environmental monitoring program at least once per 12 months; the Offsite Dose Calculation Manual (0DCM) and implementing procedures at least once each 24 months; and the Process Control Program (PCP) and implementing procedures at least once each 24 months. The licensee conducted additional corporate and internal audits as part of the overall plant QA/QC program.
The inspector reviewed the following audits and appraisals:
II-5-85-R, Radioactive Waste, March 4-19,1985; II-5-86-R, Radwaste, March 5-14 and March 24 - April 4, 1986; II-25-85-L, Station Radiation Control, October 16-23, 1985; II-26-85-M, Environmental Monitoring, October 28 -
November 14, 1985.
Licensee representatives stated that the 1986 Station Radiation Control and Environmental Monitoring audits had been completed, but had not yet been published.
The Offsite Dose Calculation Manual was audited by the Corporate Health Physics staff in the fourth quarter of 1984 and reported in January 1985, and audited in the third quarter of 1986 and reported in October 1986, both under File Number 22.270.
The Process Control Program was audited by the Corporate Health Physics staff during the fourth quarter of 1983 and the fourth quarter of 1985, and reported in January 1984 (File 22.350) and January 1986 (File 22.280), respectively.
In addition, several short surveillance audits were reviewed for 1985 and 1986.
The audits appeared to be comprehensive and to meet the Technical Specification requirements.
No violations or deviations were identified.
5.
Changes to Equipment and Procedures (84723, 84724)
Technical Specification 6.15.1.1 requires that major changes to radioactive liquid and gaseous waste treatment systems shall be reported to the Commission in the Monthly Operating Report for the period in which the evaluation was reviewed by the Plant Safety Review Committee.
Technical Specification 6.8.1 requires the licensee to establish, implement, and maintain written procedures.
Licensee representatives stated that no changes had been made in organization or equipment pertaining to the radwaste program since the last inspection.
The inspector reviewed the following procedures which had been issued or revised since the previous inspection.
All procedures had been reviewed and approved by appropriate plant management, as provided in the specification.
Health Physics Procedures:
HPP-303, Airborne Activity Sampling Techniques and Procedures, Rev. 3, September 5, 1985
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HPP-707, Health Physics Actions and Surveillance for Unplanned Releases, Rev. 3, September 30, 1986 HPP-709, Release of Radioactive Gaseous Effluents, Rev. 3A, August 28, 1986 HPP-710, Release of Radioactive Liquid Effluent, Rev. 4B, August 28, 1986 HPP-808, Sample Analysis, Rev. 78, April 24,1986 HPP-810, Sampling of Radioactive Gases and Liquids, Rev. 6C, April 24, 1986 HPP-812, Operation and Calibration of the ND-66/HP-9845 Ge(Li)
Spectroscopy System, Rev. 2, June 26, 1986 HPP-813, Quality Control of the ND-66/HP-9845 Ge(Li) Spectroscopy System, Rev. 38, June 30, 1986 HPP-814, Non Routine Gas and Liquid Sampling, Rev. 4. July 26,1985 HPP 817, Quality Control of Sampling and Sample Analysis Methods, Rev. 3, April 1,1985 HPP-823, Analysis of Emergency Samples, Rev. 0, June 24, 1986 HPP-904, Use of the Radiation Monitoring System (RMS), Rev. 48, August 21, 1986 l
HPP-916, Computer Program Control, Rev. 3, April 4, 1986 i
HPP-917, Computer Program Testing, Rev. 3, April 4, 1986 l
l HPP-920, Post Accident Reactor Building Atmospheric Sampling, Rev. 4,
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January 11, 1986 l
l Chemistry Procedures:
CP-163, Post Accident Hydrogen Analysis, Rev. 0, July 2, 1986 l
CP-164, Post Accident Gas and Liquid Isotopic Analysis, Rev. 1, June 19, 1985 d
CP-165, Post Accident Chloride Analysis, Rev. 1, July 14, 1986 CP-301, 15 Minute Degassed Gross Activity Determination (Specific Activity;, Rev. 3, November 14, 1985 CP-614, Reactor Coolant Chemistry Control, Rev. 6, December 3, 1985
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CP-903, Operation of the Nuclear Sample System Under Normal and Post Accident Conditions, Rev. 6A, April 23, 1985 CP-906, Post Accident Sample System Preventative Maintenance and Sample Comparison Program, Rev. 2A, July 17, 1986 Station Operating Procedures:
50P-108, Liquid Waste Processing System, Rev. 14, May 24, 1985 S0P-109, Spent Resin Removal and Replacement, Rev. 6, January 7,1986 S0P-114, Reactor Building Ventilation System, Rev. 11, January 3, 1986
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SOP-119, Waste Gas Processing, Rev. 11, January 15, 1986 S0P-406, Engineered Safety Features, Rev. 4, April 4,1985 SOP-502, Auxiliary and Fuel Handling Building Ventilation System, Rev. 4, July 14, 1986 S0P-505, Control Building Ventilation System, Rev. 4, January 3, 1986 Surveillance Test Procedures:
STP-554.002, Control Room Emergency Air Cleanup System Performance Test, Rev. 0A, December 9, 1985 STP-554.004, Auxiliary Building Exhaust HEPA and HECA Filter Test Plenums (XAA-40A and 40B), Rev. O, September 13, 1985 STP-555.002, Spent Fuel Pool Ventilation System Performance Test, Rev. 1 December 18, 1985 STP-555.003, Reactor Building Purge Exhaust HEPA and HECA Filter Test, Rev. O September 12, 1985 In addition, the inspector reviewed 32 STPs in the Series STP-360.031 through STP-360.088.
These procedures provided for calibration and/or operational test of gaseous and liquid radiation monitors and flow rate indicators.
No violations or deviations were identified.
6.
Semi-Annual and Annual Reports (80721, 84723, 84724)
Technical Specification 6.9.1.6 requires the licensee to submit an Annual Radiological Environmental Report.
The inspector reviewed the Annual Radiological Environmental Reports for calendar years 1984 and 1985.
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Technical Specification 6.9.1.8 requires the licensee to submit a Semi-Annual Radiological Effluent Release Report.
The inspector reviewed reports for January - June 1985, July - December 1985, and January - June 1986.
No technical discrepancies or trends were identified and the reports were consistent with the guidance of Regulatory Guide 1.21.
On the basis of the Semi-Annual Effluent Release Reports discussed above and the inspector's review of selected liquid and gaseous effluent release permits, the inspector concluded that plant effluents were within 10 CFR Part 50, Appendix I design objectives, and were ALARA (As Low As Reasonably Achievable).
No violations or deviations were identified.
7.
Radioactive Liquid Waste and Liquid Effluent Treatment Systems (84723)
Technical Specification 3.11.1.1 establishes limits for concentrations of radioactive materials in liquid effluents.
The inspector reviewed selected liquid effluent release permits for the period January 6 to October 4,1986, and determined that the calculated release concentrations were less than the limits of the Technical Specifications.
A review of the Semi-Annual Effluent Release Reports for calendar year 1985 and January - June 1986, indicated that release concentrations were less than the release limits.
Technical Specification 3.11.1.2 requires the licensee to limit the dose or.
dose cocnitment to an individual from radioactive materials in liquid effluent releases to:
a.
During any calendar quarter:
less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and b.
During any calendar year:
less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ.
The inspector reviewed the ODCM and corresponding implementing procedures as well as selected release permits and dose calculation records.
The inspector also reviewed the Semi-Annual Effluent Release Reports for calendar year 1985 and January - June 1986.
Dose calculation records and reports indicated that the specified limits had not been excee<jed.
i The inspector verified from selected records of liquid effluent releases that the records required by Technical Specification 6.10 were maintained in
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terms of frequency and content.
No violations or deviations were identified.
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8.
Radioactive Gaseous Waste and Gaseous Effluent Treatment Systems (84724)
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:
a.
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 b.
For radiciodines 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 organ.
The inspector reviewed selected records for the period from January 1986 through October 1986 and determined that the calculated dose rate was within the limits of the Technical Specification.
l Technical Specification 3.11.2.2 requires that the air dose due to noble gases released in gaseous effluents to areas at or beyond the site boundary shall be limited to:
a.
During any calendar quarter:
less than or equal to 5 mrads for gamma
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radiation and less than or equal to 10 mrads for beta radiation, and b.
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.
The inspector reviewed selected records for the period of January 1986 through October 1986 and determined that the calculated noble gas air dose was within the Technical Specification limits.
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 to areas at or beyond the site boundary shall be limited to:
a.
During any calendar quarter:
less than or equal to 7.5 mrems in any organ and, b.
During any calendar year:
less than or equal to 15 mrems in any organ.
The inspector reviewed selected records for the period of January through June 1986 and determined that the calculated dose was within the Technical Specification limits.
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 160,000 curies of noble gases (considered as Xe-133).
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The inspector reviewed selected records of gaseous concentrations in gaseous storage tanks for the period of January through October 1986 and determined that the maximum quantity of radioactivity in each tank had been less than the specified limit.
The inspector verified from selected records of gaseous effluent releases made during the period from January to October 1986, that the records required by Technical Specification 6.10 were maintained in terms of frequency and content.
The inspector also reviewed the Semi-Annual Radiological Effluent Release Reports for January - June 1985, July - December 1985, and January - June 1986.
No violations or deviations were identified.
9.
Testing of Air Cleaning Filtration Systems (84724)
Technical Specifications 3/4.7.6 and 3/4.9.11 list the requirements for the Control Room Normal and Emergency Air Handling System and the Spent Fuel Pool Ventilation System, respectively.
The inspector reviewed the results of leak testing of associated HEPA filters and charcoal absorber banks performed since the last inspection.
The inspector verified that the surveillance requirements were met.
No violations or deviations were identified.
10. Post Accident Sampling Systems (PASS) (84723, 84724)
Technical Specification 6.8.4.d requires the licensee to have the capability of sampling and analyzing plant fluids and gases in the event of an accident.
The inspector toured a section of the PASS control system and discussed its operational history over the past year with cognizant licensee personnel.
The system exhibited low maintenance problems and the licensee considered the overall reliability to be high.
The licensee had a check testing program, including a stock of key replacement parts.
The inspector reviewed routine logs from July 1985 to October 1986 and noted that checks on systems such as the nitrogen gas supply, gas section leak tightness, visual inspections of remotely operated valves and PASS hood spray functional test were conducted as specified in the appropriate procedures.
Chemical reagents were changed out on a prescribed schedule and reactor coolant and stripped gas isotopic comparison were performed as required by procedure and showea adequate agreement between the normal sampling system and the PASS system.
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No violations or deviations were identified.
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1 11. Effluent Radiological Monitoring and Analysis Instrumentation (84723, 84724)
Technical Specification Table 4.3-8 provides surveillance requirements for liquid effluent radioactivity monitors.
The inspector reviewed selected records and verified that the required channel calibration and channel functional surveillance tests had been performed at the prescribed intervals.
Technical Specification Table 4.3-9 provides surveillance requirements for gaseous effluent radioactivity monitors.
The inspector reviewed selected records and verified that the required channel calibration and channel functional surveillance tests had been performed at the specific intervals.
Health Physics Procedure HPP-812, Operation and Calibration of the-ND-66/HP-9845 Ge(Li) Spectroscopy System, prescribes calibration methods and frequencies for the count systems used to analyze effluent gas and liquid samples, charcoal and silver zeolite cartridges, and particulate samples.
Five detector systems were used, three for Health Physics samples and two for Chemistry samples.
The inspector reviewed selected records for these systems for calendar years 1985 and 1986 to date which indicated that calibrations were performed in
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accordance with the procedure.
Health Physics Procedure HPP-813, Quality Control of the ND-66/HP-9845 Ge(Li) Spectroscopy System, specifies the daily Quality Control checks which
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are to be used to check the counting systems.
The inspector reviewed selected Quality Control records for the systems for the months of July and August 1986, which indicated the checks were performed in accordance with the procedure.
No violations or deviations were identified.
12.
Inspector Followup (92701)
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(Closed) Inspector Followup Item (IFI) 50-395/85-05-01, Precedures to be Provided for Preparation of Stripped Gas Samples from Reactor Coolant (PASS)
and for Gamma Spectrographic Analysis of Stripped Gas Samples.
The inspector reviewed Procedure CP-164, Post Accident Gas and Liquid Isotopic Analysis.
This procedure, with the necessary references, provided adequate direction to obtain and analyze stripped gas from the PASS system sampling point.
(Closed) IFI 50-395/85-19-02, Evaluation of Systematic Bias for Gamma Spectroscopy Analysis of Particulate Filters.
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The inspector reviewed an evaluation performed using 57mm and 47mm particulate filter standards.
An intercomparison with the known values and values obtained at the licensee's environmental laboratory showed agreement.
(Closed) IFI 50-395/85-19-03, Review Results of Spi'.ed Sample Results for H-3, Fe-55, SR-89, and SR-90 Analysis.
The inspector reviewed licensee's results for spiked samples provided to
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them in March 1985 and May 1986.
The licensee was in disagreement for H-3 l
in the March 1985 spiked samples but agreement for the other measurements.
(Closed) IFI 50-395/86-IN-42, IE Information Notice 86-42, Improper Maintenance of Radiation Monitoring Systems.
The inspector discussed the notice with cognizant personnel in relation to current maintenance practices within the plant.
The licensee's program calls for independent verification that radiation monitors are returned to the proper operating conditions. This program should help prevent the types of problems discussed in the notice.
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(Closed)LER 50-395/85-LER-12, Liquid Radwaste Computer Program.
From August 1984 to April 1985, an incorrect constant was used to determine the trip setpoints for Liquid Radwaste monitors.
This was caused by human error.
The inspector reviewed the licensee corrective actions and
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l evaluations of releases made during this period. This review indicat.ed that no Technical Specification limits were exceeded during this period.
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licensee has instituted improved computer program verification procedures and this deficiency was corrected as of July 1985.
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