IR 05000458/1985082
| ML20151Z029 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 01/09/1986 |
| From: | Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20151Z014 | List: |
| References | |
| 50-458-85-82, IEB-80-10, NUDOCS 8602130268 | |
| Download: ML20151Z029 (9) | |
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'3 APPENDIX B
.U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-458/85-82 License: NPF-40 Docket': 50-458 Licensbe:
Gulf States Utilities (GSU)
P. O. Box 2951 Beaumont, Texas 77704 Facility Name:
River Bend Station (RBS)
. Inspection At:
River Bend Station, St. Francisville, Louisiana Inspection Conducted: December 16-20, 1985 Inspector:
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R.~E. Baer, Radiatiog Specialist
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Dats Facilities Radiological Protection Section Approved:
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h Blaine Murray, Chie Facilities Dfite'
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Radiological Pr ction Section Inspect! ion Summary Inspection Conducted December 16-20, 1985 (Report 50-458/85-82)
Areas Inspected: Routine, unannounced inspection of the licensee's radioactive waste management control, training and qualifications, radwaste startup, and operation of the liquid, gaseous, and solid waste systems. The inspection.
-involved 39 inspector-hours onsite by one NRC inspector.
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Resulty: Within the areas inspected, one violation was identified (failure to perform an adequate calibration, paragraph 7).
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~2-DETAILS 1.
Persons Contacted GSU
- J. C. Deddens, Vice President,l River Bend Nuclear Group
- T. F. Plunket, Plant Manager
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T. P. Anthony, Senior Mechanical Engineer.
- E.' M.~ Cargill, Jr., Supervisor, Radiological Programs
- J. V. Conner, Supervisor, Environmental Services J. W. Cook, Licensing Engineer
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- T. C. Croose, Manager, Quality Assurance-(QA)
- R. G. Easlick,- Radwaste Supervisor W. F. Eisele, Jr., Health.Physici st
- C.
L. Fantacci, Radiation Protection Supervisor J. Galloway, Jr'.,
Instrument and Control (I&C) Technician
- D. R. Gipson, Assistant Plant Manager
- E. R. Grant, Supervisor, Nuclear Licensing
- B.
R. Hall, Plant Service Supervisor D. E. Jacobsen, System Engineer
- G. R. Kimmell, Supervisor, Operations QA
- A. D. Kowalczuk, Assistant Plant Manager-Maintenance J. M. McGhee, Radwaste Foreman
- C. L. Nash, Chemistry Supervisor
- E. R. Oswood, QA Engineer
- C. A. Rohrmann, Technical Training Coordinator D. R. Suggs,-I&C Foreman H. D. Snowder, Radiation Protection Specialist
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R. N. Taylor, QA Engineer L. R. Thompson, I&C Supervisor-Others.
D. K. Garner, Solidification Technician, Chem-Nuclear J. K. Neubauer, I&C Technician, NORCO R. G. Odden, Test Engineer, NUS Corporation D. D. Chamberlain, NRC Resident Inspector The NRC inspector also interviewed several other licensee and contractor employees.
- Denotes those individuals present during the exit meeting on December 20, 198.
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-3-2.
Licensee Action on Previously Identified Inspection Findings (Closed) Open Item (458/8414-05):
Effluent Release Procedures - This item involved the lack of an approved effluent release procedure.
The licensee had developed and implemented Station Procedures ADM-0054, " Radioactive Liquid Effluent Batch Discharges," and CSP-0110, " Control of Plant Liquid Radioactive Discharges," which included the radioactive liquid effluent i
discharge permit.
This item (458/8414-05) is considered closed.
(Closed) Open Item (458/8414-08): Air Cleaning Systems - This item involved the lack of "as-built" ALARA review, completion of preoperational tests, and development of an in place testing program.
The licensee had completed an ALARA design review of the off gas and ventilation systems, completed Preoperational Tests 1-SST-17, " Field Testing of Cat I Charcoal Filter Units," and 1-SST-18, " Field Testing of Cat II Charcoal Filter Units," which included the in place testing procedures.
This item (458/8414-08) is considered closed.
3.
Inspector Observations The'following are observations the NRC inspector discussed with the licensee during the exit interview on December 20, 1985.
These observations are neither violations nor unresolved items.
These items were recommended for licensee consideration for program improvement but they have no specific regulatory requirement.
The licensee stated that the items would receive further review, a.
10 CFR 71.101 Quality Assurance Program - The licensee had not submitted a QA program to the NRC's Office of Nuclear Material Safety and Safeguards (NMSS) for approval to ship radioactive materials in quantities greater than Type A.
See paragraph 8 for additional details.
b.
Use of NRC Approved Shipping Casks - The licensee had not applieri to NMSS for approval to use NRC certified casks for the shipment of radioactive materials.
See paragraph 8 for additional details, c.
Storm Drain and Sewage System Effluent Samples - The licensee had not developed and implemented a sampling / analysis schedule for the storm drains and sewage system effluent: as recommended in Inspection and Enforcement (IE)Bulletin 80-10.
See paragraph 6 for additional details.
d.
Radioactive Waste Management Policy Statement - The licensee had not issued a radioactive waste management policy statement as described in Station Procedure ADM-0038.
See paragraph 4 for additional details.
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-4-e.
Process and Area Radiation Monitor Procedures - The licensee had not developed procedures for the calibration or functional testing, or defined the frequency for performance of these actions for the radiation monitors not identified in the Technical Specifications (TS).
See paragraph 7 for details, f.
Waste Classification - 10 CFR 61.55 - The licensee had not established a sampling frequency, identified waste streams to be sampled, nor selected a qualified vendor to perform analysis of the waste stream samples to classify solid radioactive waste in accordance with 10 CFR Part 61.55.
See paragraph 8 for additional details.
g.
Segregation of Waste - The licensee had not established a policy nor implemented a monitoring / segregation program for waste material collected within the radiologically controlled area (RCA) of the plant.
See paragraph 8 for additional details.
4.
Radioactive Waste Organization and Management Controls The NRC inspector examined the licensee's onsite organization regarding radioactive waste management to determine compliance with commitments in the Final Safety Analysis Report (FSAR), Chapters 13.1 and 13.4, requirements of RBS TS, Sections 6.2.2 and 6.5, and the recommendations of Regulatory Guide (RG) 4.15.
The NRC inspector discussed with licensee reg.resentatives the status of the GSU Radioactive Waste Management Policy Statement (RWMPS).
The licensee stated that the RWMPS had not been issued because of some minor changes that needed to be addressed. No date was available when the RWMPS would be issued.
The NRC inspector noted that the licensee had replaced one radwaste nuclear equipment operator (RNEO) since the last radwaste management
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inspection.
The licensee representatives indicated that it will require 3 to 6 months to qualify a RNE0 to where he would be capable to perform RNE0 functions without direct supervision.
The licensee is presently using qualified RNE0s on overtime to maintain system operation.
No violations or deviations were identified.
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5.
Radwaste Training and Qualificationt The NRC inspector reviewed the licensee's radwaste training program and
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individual qualifications to determine compliance with FSAR commitments, l
TS, Section 6.4, and 10 CFR Part 19.12 requirements.
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g e-5-The NRC inspector reviewed the qualifications and training for RNE0 personnel. The NRC inspector discussed with licensee representatives the status of the RNE0 training course.
The licensee stated that the RNE0 training course was presently being revised and scheduled to be conducted starting the week of January 6, 1936.
The licensee also stated that additional nuclear equipment operators would be included in this training class and should provide additional depth for radwaste operations.
No violations or deviations were identified.
6.
Radwaste Startup The NRC inspector reviewed lic.nsee records and sampling schedule to determine compliance with TS,' Sections 3/4.4.4 and 3/4.4.5.
The NRC inspector reviewed selected records of liquid and gaseous samples taken from the reactor coolant system and main plant exhaust vent system.
All analysis indicated systems were being maintained within the limits required by TS.
The NRC inspector discussed with licensee representatives whether the radiological results obtained by sample laboratory analysis were compared to readings being recorded by process or effluent radioactivity monitors. The licensee stated that radioactivity concentrations were too low to accurately correlate these data.
The NRC inspector discussed with licensee representatives the collection and analysis of samples from nonradioactive systems and resulting potential for unmonitored, uncontrolled release of radioactivity to the environment.
The licensee stated that approved procedures were not in place addressing the frequency and analysis of samples from the storm drains and sewage system effluents.
The licensee indicated work would begin to establish the necessary procedures and sampling.
No violations or deviations were identified.
7.
Radiation Monitoring Systems - Process and Effluent Monitoring The NRC inspector reviewed the calibration of selected process and effluent monitors to determine compliance with TS, Sections 3/4.3.7, 3.3.7.5, 3.3.7.10, 3.3.7.11, and 6.8.4.n, and commitments in FSAR Chapters 11.5 and 12.3.
The NRC inspector determined that the licensee had developed and implemented procedures for calibration and functional testing on the 19 radiation detection elements identified in the TS.
The licensee had not developed procedures '.vhich specifically addressed the remaining 75 radiation detection elements but was using generic test procedures referred to as G-CALs,1-G-CAL-03, " Low Range Area Radiation Monitor
' Calibration," Revision 7, March 13, 1985, 1-G-CAL-04, " Ion Chamber Area
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-6-Radiation' Monitor Calibration'," Revision 2, May 16, 1985, 1-G-CAL-05,
" Portable Continuous Air Radiation Monitor Calibration," Revision 2, June 19, 1985, 1-G-CAL-06, " Particulate and Gas Process Radiation Monitor
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Calibration," Revision 4, September 24, 1985, 1-G-CAL-07, " Liquid Process Radiation Monitor Calibration," Revision 1, April 25, 1985, and 1-G-CAL-09,
" Gas Process Radiation Monitor Calibration," Revision 3, April 30, 1985.
The NRC inspector reviewed the above G-CAL procedures and noted that they did not address functional checks, calibration or functional tesc frequencies. Also, it was not possible to determine if the monitors were being calibrated on each decade over the full range.
The NRC inspector determined the licensee had performed the last calibration of the containment high range monitors in accordance with Station Operating Procedure STP-511-4249, "RMS-Primary Containment Area Radiation Monitor 18 Month CHCAL (IRMS*RE16A)," Revision 1, July 10,1985, on August 21, 1985, which included a radiological calibration at 1.64 and 9.50 R/hr and electronic calibrations at 1E+0, 1E+2, 1E+4, IE+6, and IE+8 R/hr.
TS, Section 4.3.7.5, requires an electronic calibration of the monitors, for all decade ranges above 10 R/hr.
The NRC inspector informed the licensee that the failure to perform electronic calibrations on each decade above 10 R/hr is an apparent violation of TS (8582-01).
8.
Solid Radwaste Management System The NRC inspector reviewed the solid radwaste system to determine compliance with FSAR, Chapter 11.4 commitments, TS, Sections 6.8.1, 6.13.2, and 6.15.1, and 10 CFR Part 61 requirements.
The NRC inspector determined that the licensee did not have an approved QA program that meets the requirements of 10 CFR Part 71. The NRC inspector
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discussed with licensee representatives the necessity to submit their QA program to the NRC for approval prior to offering for transport certain packages.
The NRC inspector also determined that the licensee had not applied to the NRC for permission to use certain Type A or Type B shipping casks.
The NRC inspector discussed the need to apply for use of these packages.and to be placed on the registered users list for selected packages. The licensee stated they would submit their QA program and register as users for casks with the NRC.
The NRC inspector discussed with licensee representatives the status of surveillance for process streams to determine waste classification as required by 10 CFR Part 61.55.
The licensee stated that they had not develcyed a program to determine what waste streams would be sampled nor selecwd a vendor to perform the analyses. The licensee was presently
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-7-using scaling factors as determined in " Methodologies'for Classification of Low-Level Radioactive Waste from Nuclear Power Plants," Atomic Industrial Forum. The NRC inspector noted that the NRC's branch' technical position on radioactive waste classification' recommended that waste
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streams be ' sampled on an annual basis for Class B and C waste and
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biannually for Class A dry active waste (DAW).
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The NRC inspector noted that the licensee had been accumulating all DAW in plastic bags or uncompressed steel drums.
This included quantities.of
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potentially clean waste.
The NRC inspector. discussed with licensee representatives the desirability to segregate this waste material.before an unacceptable quantity was accumulated. The licensee stated that a 1 segregation facility was to be completed at which time the waste would be separated and radioactive waste compacted and packaged for shipment.
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No violations or deviations were identified.
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9.
Liquid Radioactive Waste System The NRC inspector reviewed the licensee's liquid radioactive waste program to determine compliance with TS, Sections 3/4.1.5, 3.3.7.10, 3/4.4.4, 3/4.4.5, 6.9.1.8, 6.14, and 6.15.1, FSAR, Chapters 11.2 and 11.5 commitments, and_IE Bulletin 80-10.
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The NRC inspector verified that the temporary line from valve A0V115
(discharge from floor drain collector subsystem) to va:ve A0V257, (liquid waste discharge valve), and to the circulating water blowdown discharge
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line for release to the environment had been removed as required prior to the release of effluents which contained detectable quantities of radioactivity.
- The NRC inspector discussed with licensee representatives the status of the filter /demineralizer trains.
The licensee stated that the
"B" train
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walnut filter system has not been able to run for longer than a couple of hours.
The licensee had removed the walnut filter media and reloaded with fresh walnut shells and experienced some difficulties. The licensee
stated that the radwaste task force consisting of personnel from radwaste, nuclear plant engineering, and technical staff engineering had been
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reestablished to resolve various radwaste problems which included the l
walnut filter. Other areas to be reviewed by the task force will include E
finishing station transfer of systems, correct deficiencies, deferred equipment, DAW segregation facilities, compaction, and long term storage.
No violations or deviations were identified.
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-8-10.
Gaseous Radioactive Waste System The NRC inspector reviewed the licensee's gaseous waste management system to determine compliance with TS, Sections 3.3.7.11, 3.6.5.4, 3.6.5.6, 3/4.6.6, 3/4.7.2, 6.9.1.8, and 6.15.1 requirements, FSAR, Sections 9.4.11.3 and 11.5 commitments.
The NRC inspector reviewed Preoperational Test Procedure 1-SST-17, " Field Testing of CAT-I Charcoal Filter Units," Revision 0, April 12,1985, and approved by the Joint Test Group (JTG) on September 27, 1985.
This test included the standby gas treatment, fuel building, and control room filter trains. The licensee had included the vendor test procedures as part of the test package.
The NRC inspector also reviewed STP-257-3601,
"In-Service Testing of Standby Gas Treatment Filtration System," Revision 1, June 30, 1985, which included the laboratory retest of the charcoal which was found acceptable with ANSI Standard N509-1980.
The NRC inspector discussed with licensee representatives the status of correlation between gaseous effluent radioactivity monitors and laboratory radiochemistry results. The licensee stated that the radioactivity concentrations in gaseous effluents are still too low to arrive at meaningful results.
No violations or deviations were identified.
11. Audits The NRC inspector reviewed audits performed by the licensee of the radwaste management system to determine compliance with TS, Section 6.5.3.8.
The NRC inspector reviewed audits GSU-RWMP-85/04, conducted during the period April 17-25, 1985, and the followup audit,_ GSU-RWMP-85/07, conducted during the period July 15-23, 1985.
The NRC inspector noted that all items identified in the audits had been satisfactorily resolved. ALARA concerns had been assigned ALARA committee action item numbers, and are being resolved. Engineering evaluation and assistance requests had been initiated where needed.
The NRC inspector also reviewed Operational QA Reports OSR2 85-06-10,
" Radioactive Waste Management," dated June 7, 1985, performed to verify the controlling / handling of radioactive waste materials and OSR2 85-12-18,
" Observe Radwaste Shipment," dated December 10, 1985, for two liners containing resins shipped to a burial site.
No violations or deviations were identified.
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-9-12. Exit Interview The NRC inspector met with licensee representatives identified in paragraph I and the senior resident inspector at the conclusion of the inspection on December 20, 1985. The NRC inspector summarized the scope and findings of this inspection, including the observations identified in paragraph 3.
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