IR 05000458/1986034
| ML20215D618 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 12/02/1986 |
| From: | Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20215D587 | List: |
| References | |
| 50-458-86-34, NUDOCS 8612160423 | |
| Download: ML20215D618 (7) | |
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APPENDIX U.S. NUCLEAR REGULATORY COP #iISSION
REGION IV
NRC Inspection Report:
50-458/86-34 License:
NPF-47 Docket:
50-458 Licensee: Gulf States Utilities (GSU)
P.O. Box 220 St. Francisville, Louisiana 70775 Facility Name:
River Bend Station (RBS)
Inspection At:
RBS, St. Francisville, Louisiana Inspection Conducted: October 27 through 31, 1986 Inspector:
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R. E. Baer, Radiation Specialist, Facilities Date '
Radiological Protection Section Approved:
(NY) Lit <Z4/
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BlaineMurray, Chief,FpcilitiesRadiological Date Protection Section Inspection Summary Inspection Conducted October 27-31, 1986 (Report 50-458/86-34)
Areas Inspected:
Routine, unannounced inspection of the licensee's radiation protection program during a maintenance outage.
Results: Within the areas inspected, no violations or deviations were identified.
8612160423 e61202 PDR ADOCK 05000458 G
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-2-DETAILS 1.
Persons Contacted GSU
- J. E. Booker, Manager,. River Bend Oversight t
- T. F. Plunkett, Plant Manager
- D. L. Andrews, Training
- L.
Broussard, Nuclear Communications Specialist W. T. Bullard, Radiation Protection Foreman
- J. G. Cadwallader, Supervisor Emergency Planning
- E. M. Cargill, Supervisor, Radiological Programs
'G. R. Collett, Radiation Protection Specialist
- J. W. Cook, Lead Environmental Analysis
- T. C. Crouse, Manager, Qualtiy Assurance (QA)
J. D. Davis, Senior QA Engineer R. G. Easlick, Radwaste Supervisor W. F. Eisele, Radiological Health Supervisor C. L. Fantacci, Radiological Engineering Supervisor A. O. Fredier, Assistant Operations Supervisor
- P. E. Freehill, Outage Manager
- D. R. Gipson, Assistant Plant Manager-0perations
- E. R. Grant, Director Licensing W. C. Hardy, Radiation Protection Supervisor E. L. Hensley, Radiation Protection Foreman
- K. C. Hodges, Supervisor, Quality Engineering
- R. E. Horn, Nuclear Training Coordinator
- R. K. Jobe, Emergency Planning A. D. Kowalczuk, Assistant Plant Manager-Maintenance P. A. Lefort, Radiation Protection Technician
- J. H. McQuirter, Licensing C. L. Nash, Chemistry Supervisor
- V. J. Normand Jr., Supervisor, Administrative Services
- W. H. Odell, Manager, Administration
- E. R. Oswood, Senior QA Engineer
- S. E. Perron, Communications T. R. Sloan, Radiation Protection Foreman (Acting)
- R. B. Stafford, Director, Operational QA L. R. Thompson, Instrumentation and Control Supervisor M. A. Vierra, ALARA Coordinator
- M. G. Walton, Technical Assistant A. D. Wells, Radioation Protection Foreman
- C.
Wells, Public Affairs i
- D.
Wells, Licensing Analysis
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- D. D. Chamberlain, Senior Resident Inspector, NRC
- J. P. Davis, General Physics Corporation M. L. Davis, ALARA Coordinator, Stone & Webster
- B. R.: Hall, Assistant Superintendent Quality Control, Stone & Webster
- W. B. Jones, Resident Inspector, NRC
- N. M. Terc, Emergency Specialist, NRC E. M. Raiguel, Site Coordinator, Hydro-Nuclear Services The NRC inspector also interviewed several other licensee and contractor employees.
- Denotes those individuals present during the exit interview on October 31, 1986 2.
Licensee Action on Previously Identified Inspection Findings:
(Closed) Violation (458/8582-01):
Failure to Properly Calibrate the Containment High Range Radiation Monitor - This item involved the lack of a calibration for all range decades above 10 R/hr on the'RMS-Primary Containment Area Radiation Monitors.
The licensee had revised the affected calibration procedures for the primary containment area and primary drywell area radiation monitors on March 7,1986, and completed a calibration of these affected monitors during the period March 23-30, 1986.
This item (458/8582-01) is considered closed.
(Closed) Violation (458/8622-01):
Disposal of Low-Level Radioactive Waste - This item involved the transfer of a low-level radioactive waste liner with detectable free standing liquid.
The licensee had implemented a quality control program and verified that the next 29 liners containing solidified spent resins in cement did not contain detectable quantities of free standing liquid.
This item (458/8622-01) is considered closed.
(0 pen) Deviation (458/8622-02):
Solid Radioactive Waste System - This item involved the lact of equipment being installed and operated as specified in Section 11.4 of the Final Safety Analysis Report (FSAR).
The lic*nsee had completed installation of the dry active waste compactor, but had not started the installation of the sample collection system.
This itep (458/8622-02) remains open.
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(0 pen) Open Iten (458/8414-07):
Radiation Monitoring Systems - Process and Effluent Monitors - This item involved the lack of calibration of liquid radioactivity monitors with NBS traceable liquid radioactive
standards and daseous radioactivity monitors with NBS traceable gaseous radioa;tive standards and verification that radiation monitors are viewing
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a representative portion of the liquid, particulate, and gaseous effluent
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streams'.
The licensee had not completed the calibrations of all the gaseous and liquid radiation monitors and the representative sampling verification had not been verified.
This item (458/8414-07) remains open.
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Advance Planning and Preparation-The NRC. inspector reviewed the planning and preparations the licensee had made to support the outage...The licensee had a. sufficient quantity of
- protective clothing available and was shipping the worn clothing to the laundry twice a week.
The licensee had a. sufficient quantity of' temporary shielding material, respiratory protection equipment, and instrumentation available for the outage.
The NRC inspector attended selected daily 7:30.a.m., 3:30 p.m., and 11:00 p.m. scheduling meetings where current: problems and upcoming events-were discussed.
It was noted that.all departments, including radiation protection operations personnel. associated with the outage, were represented.
No violations or deviations were identiified.
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Staffing
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The' NRC inspector reviewed the licensee's functional organization regarding the radiation protection program to determine compliance with technical specification (TS).Section 6.'2 and.for agreement with
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commitments-in the FSAR,- Sections 12 and 13.
The licensee had increased the radiation protection staff with nine additional. contract technicians.. The licensee had 20 senior-grade contractor technicians in addition to the licensee's 18 technicians available to support normal plant operations.
The NRC inspector discussed with licensee representatives what appeared to be a minimal number of technicians available to support the outage.
The licensee acknowledged that there had been more work scheduled than orginally anticipated for the outage and occasionally work had to be delayed because of the. lack of radiation protection personnel to adequately cover the work. The NRC inspector verified by observation and discussions with construction, maintenance, and radiation protection personnel that work requiring radiation protection coverage was not performed without the proper
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No violations or deviations were identified.
5.
Training and Qualifications-The NRC inspector reviewed the training and qualifications for the contractor senior level radiation protection technicians to determine agreement with FSAR, Section 13, commitments and the requirements of TS Section 6.3 and 10 CFR Part 19.12.
No violations or deviations were identified.
6.
ALARA The NRC inspector reviewed the licensee's ALARA program for agreement with the recommendations of Regulatory Guides (RG) 8.8 and 8.1 _
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-5-The licensee's ALARA program consisted of an ALARA coordinator, a vendor supplied ALARA coordinator, and a radiation protection technician.
The ALARA group had become involved approximately one month prior to the start of the outage and had set a goal of 20 person-rem for the 29 day outage.
The licensee had expended approximately 22 person-rem as recorded by direct reading dosimeters as of October 31, 1986.
The licensee expected to exceed both the length of time the outage would take and the person-rem expended, due to increased work on the reactor water cleanup (RWCU) heat exchangers and main stea isolaLSn valves.
The NRC inspector raviewed the memorandum RPG-M-86-374, which details the mockup training for RWCU heat exchanger work, and viewed selected portions of the mockup training that was in progress during the inspection period.
The NRC inspector also' reviewed procedure RSP-0009, "ALARA Program Implementation," Revision 0, October 17, 1986, which defines the responsibilities for station personnel and the methodology the licensee had implemented for job preplanning, ALARA review checklist, pre-job training, briefings, and post-job reviews.
The NRC inspector observed an ALARA committee meeting which discussed the draft procedures for the RWCU heat exchanger work.
The ALARA committee and ALARA coordinator appeared to be effective and the licensee was supportive of their work.
The NRC inspector discussed with licensee representatives the possibility of sending the ALARA coordinator to a formal class of instruction on effective ALARA programs.
No violations or deviations were identified.
7.
External Exposure Control The NRC inspector reviewed the licensee's program for external exposure control for compliance with 10 CFR Parts 20.101, 20.102, 20.104, 20.202, 20.403, 20.405, and 20.408.
l The licensee had established administrative radiation exposure limits in procedures RBNP-024, " Radiation Protection Plan," and RSP-0203, " Personnel
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l Monitoring," of 1000 millirem per calendar quarter.
The licensee had not exceeded the administrative limits on any employee during the outage.
The licensee routinely tracked the radiation exposure received by the week, month, quarter, year, and lifetime.
Updates of the radiation exposure tracking were performed daily based on direct reading dosimeter results l
and monthly based on thermoluminescent dosimetry (TLD) results.
The NRC
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inspector noted that the highest radiation exposure recorded for the current calendar quarter was 450 millirem on October 30, 1986.
The licensee had implementated procedure RPP-0065, "Use of Multiple
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Dosimetry Devices," for the issuance of multiple or extremity TLD's.
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-6-o licensee had issued multiple TLD's for work involving valve packing where high beta radiation exposures were expected.
No violations or deviations were identified.
8.
Internal Exposure Control The NRC inspector reviewed the licensee's internal exposure control program for compliance with 10 CFR Part 20.103.
The licensee had procedures for the tracking of radiation exposures resulting from the exposure to airborne radioactivity.
The licensee had not exposed any individual to a concentration of airborne radioactivity in excess of the limits specified in Appendix B of 10 CFR Part 20.
The NRC inspector reviewed the licensee's respiratory protection program, airborne radioactivity surveys, and whole body counting / bioassay program.
The licensee had obtained a fast scan whole body counting system which was used to monitor personnel prior to the performance of any work in the radiologically controlled area and upon completion of their work assignment.
No violations or deviations were identified.
9.
Radioactive and Contaminated Material Controls and Radiological Surveys The NRC inspector reviewed the licensee's program for control of radioactive and contaminated material and radiological surveys against the requirements of 10 CFR Parts 19.12, 20.201, 20.203, 20.205, 20.207, 20.301, and 20.401.
The NRC inspector reviewed radiation and contamination survey records and evaluated the licensee's surveys against independent surveys performed by the NRC inspector.
It was noted that the licensee was routinely performing beta radiation measurements during radiation area surveys.
The licensee performed a daily response check of the radiation survey instrumentation for both beta and gamma radiation.
The NRC inspector commented to licensee representatives about the presence of craft tool boxes in contaminated areas, which was not consistent with the waste reduction policy.
These boxes and all the contents would have to be decontaminated and surveyed prior to removal from the area even if the contents were not used.
The NRC inspector noted that the licensee had not established any " hot" tool storage areas within the radiologically controlled area (RCA).
The NRC inspector inspected the radiological control points for surveying and releasing material and personnel from the RCA.
The NRC inspector discussed with licensee representatives the congestion that takes place around the monitoring tables when personnel are removing items from the RCA.
The licensee agreed to review this area.
No violations or deviations were identifie,
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Posting, Labeling, and Worker Control The NRC inspector reviewed the licensee's program for control of workers and posting and labeling of radioactive material and radiation areas for compliance with the requirements of 10 CFR Parts 19.12, 20.203, 20.205, 20.207, and 20.301. The NRC inspector also reviewed the licensee's actions taken in regard to NRC inspection and enforcement (I&E)Bulletin 78-08, " Radiation Levels from Fuel Element Transfer Tubes."
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The NRC inspector verified that the licensee had properly posted radioactive material locations, radiation areas, and high radiation areas, and that radioactive waste materials were being properly packaged and taken to the radioactive material storage areas in a timely manner.
The NRC inspector discussed with licensee representatives the requirements of I&E Bulletin 78-08, which includes a review of the shielding design of plant areas adjacent to the fuel transfer tube to identify potential high radiation areas.
The licensee stated they had reviewed the shielding design and plan to perform detailed surveys during the first refueling outage scheduled in 1987.
No potential shielding design deficiencies had been noted.
No violations or deviations were identified.
11.
Licensee Event Reports The N(C inspector reviewed Licensee Event Report (LER)86-046 submitted on September 26, 1986, regarding a missed technical specification action on the fuel building radiation monitor.
The licensee had revised procedure COP-0046, " Sampling Gaseous Effluents Via the Wide Range Gas Monitor,"
Revision 4, and required all chemistry personnel to review the procedure.
The chemistry group also issut J two laboratory standing orders, 86-0006,
" Effluent Monitoring," and 86-0008, " Sampling Gaseous Effluents for Particulates and Iodine in the Portable Sampling Pumps when the Wide Range Gas Monitors are Inoperable." It appears that the actions taken by the licensee should preclude the recurrence of this condition.
LER 86-046 is considered closed.
12.
Exit Interview The NRC inspector met with licensee representatives and the NRC resident inspector identified in paragraph 1 of this report at the conclusion of the inspection of October 31, 1986.
The NRC inspector summarized the inspection findings.