IR 05000458/2003009
| ML032580294 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 09/12/2003 |
| From: | Troy Pruett Plant Support Branch Region IV |
| To: | Hinnenkamp P Entergy Operations |
| References | |
| IR-03-009 | |
| Download: ML032580294 (20) | |
Text
September 12, 2003
SUBJECT:
RIVER BEND STATION - NRC RADIATION SAFETY TEAM INSPECTION REPORT 05000458/2003-09
Dear Mr. Hinnenkamp:
On August 22, 2003, the NRC completed the onsite portion of the radiation safety team inspection at your River Bend Station. The enclosed report documents the inspection findings which were discussed on August 22, 2003, with yourself and other members of your staff.
This inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The team reviewed selected procedures and records, observed activities, and interviewed personnel. Specifically, the team evaluated the inspectable areas within the Radiation Protection Strategic Performance Area that are scheduled for review every two years. These areas are:
Radiation Monitoring Instrumentation
Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems
Radioactive Material Processing and Transportation
Radiological Environmental Monitoring Program and Radioactive Material Control Program This inspection report documents one NRC identified finding and one self-revealing finding of very low safety significance (Green). However, because of their very low safety significance and because the findings were entered into your corrective action program, the NRC is treating these findings as noncited violations (NCVs) consistent with Section V1.A of the NRC Enforcement Policy. Additionally, a licensee-identified violation which was determined to be of very low safety significance is listed in Section 4OA7 in this report. If you contest the violations or significance of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to the Regional Administrator, U.S. Nuclear Regulatory Commission, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011; the Director, Office of Enforcement, U.S. Nuclear
Entergy Operations, Inc.
-2-Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the River Bend Station facility.
In accordance with 10 CFR 2.790 of the NRCs "Rules of Practice," a copy of this letter, its enclosure, and your response will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
//RA//
Troy W. Pruett, Chief Plant Support Branch Division of Reactor Safety Docket: 50-458 License: NPF-47
Enclosure:
NRC Inspection Report 050000458/2003-09
REGION IV==
Docket:
50-458 License:
NPF-47 Report No.:
50-458/03-09 Licensee:
Entergy Operations, Inc.
Facility:
River Bend Station Location:
5485 U.S. Highway 61 St. Francisville, Louisiana Dates:
August 18-22, 2003 Inspectors:
Accompanied:
D. R. Carter, Health Physicist, Plant Support - Team Leader B. D. Baca, Health Physicist, Plant Support L. T. Ricketson, P.E., Senior Health Physicist, Plant Support M. P. Shannon, Senior Health Physicist, Plant Support B.K. Tharakan, Health Physicist, Plant Support Approved By:
T. W. Pruett, Chief, Plant Support Branch ATTACHMENT:
Supplemental Information
SUMMARY OF FINDINGS River Bend Station NRC Inspection Report 05000458/2003-09 IR 05000458/2003-09; 08/18 - 22/2003; River Bend Station; Radioactive Material Processing and Transportation; Radioactive Material Control Program; Radiation Safety Team Inspection The report covered a one week period of inspection on site by a team of four region-based health physics inspectors. Two findings of very low safety significance (Green) were identified.
The significance of most findings is indicated by their color (Green, White, Yellow, Red) using IMC 0609, Significance Determination Process, (SDP). Findings for which the SDP does not apply may be Green or be assigned a severity level after NRC management review. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
A.
NRC-Identified and Self-Revealing Findings Cornerstone: Occupational Radiation Safety
Green. The team identified a non-cited violation of Technical Specification 5.4.1a because the licensee failed to post a radiological hazard (hot spot). Station Procedure RP-109, Hot Spot Program, Revision 0, Step 5.2.1, required that hot spots are identified with a hot spot tag to alert workers of the hazard. However, on August 19, 2003, the team identified a hot spot on an accessible drain line from the radwaste sample sink reading 200 millirem per hour on contact and 50 millirem per hour at one foot from the source. The licensee performed a survey 11 days earlier that identified the radiation levels, however, the technician and the survey reviewer failed to tag the hot spot to warn workers of the hazard.
The finding was more than minor because it was associated with the Occupational Radiation Safety cornerstone attribute (Program and Process) and affected the associated cornerstone objective. The finding involved the potential for a workers unplanned or unintended dose resulting from actions contrary to procedures. When processed through the Occupational Radiation Safety Significance Determination Process the team determined that the finding had very low safety significance because the finding did not involve as low as is reasonably achievable (ALARA) planning or work controls, no individual received an overexposure or a substantial potential for overexposure, and the ability to assess dose was not compromised. (Section 2PS2)
Cornerstone: Public Radiation Safety
Green. A self-revealing non-cited violation of Technical Specification 5.4.1a was reviewed by the team because the licensee did not prevent the release of detectable licensed radioactive material from the controlled access area. Specifically, Section 5.1.1 of Procedure RSP-213, Control and Handling of Radioactive Materials, Revision 16, stated, in part, that material can be unconditionally released from the controlled access area if there is no detectable loose surface and fixed contamination above background radiation levels. However, on March 31, 2003, the licensee failed to evaluate an item, against their procedural criteria, prior to it being unconditionally released from the
-2-controlled access area and subsequently released from the protected area. Fixed contamination levels were as high as 1,000 corrected counts per minute per probe area.
The finding was more than minor because it was associated with the Public Radiation Safety cornerstone attribute (Program and Process) and affected the associated cornerstone objective. The finding involved an occurrence in the radioactive material control program that was contrary to licensee procedures. When processed through the Public Radiation Safety Significance Determination Process, the team determined the finding had very low safety significance because the public exposure associated with the item was less than 5 millirem and there were not more than 5 occurrences.
(Section 2PS3).
B.
Licensee Identified Violation A violation of very low safety significance (Green) which was identified by the licensee was reviewed by the team. Corrective actions taken or planned by the licensee have been entered into the licensees corrective action program. This violation and corrective action tracking number is listed in Section 4OA7.
Report Details 2.
RADIATION SAFETY Cornerstone: Occupational Radiation Safety [OS]
2OS3 Radiation Monitoring Instrumentation (71121.03)
a.
Inspection Scope This area was inspected to determine the accuracy and operability of radiation monitoring instruments used for the protection of occupational workers and the adequacy of the program to provide self-contained breathing apparatus (SCBA) to personnel entering unknown atmospheres. The team conducted an in-office review of the licensees annual reports and self-assessments, and corrective action documents.
Onsite, the team interviewed cognizant licensee personnel and compared the following items with regulatory and procedural requirements:
Calibration, operability, and alarm setpoints of selected area radiation monitors (RMS-RE140, RMS-RE141, and RMS-RE193) and emergency assessment instrumentation (RMS-RE16A, RMS-RE16B, and RMS-RE21B)
Calibration and operability of portable radiation detection instrumentation used for job coverage of high radiation area and contaminated area work, whole body counters, and personnel contamination monitors (BC-4, PCM-1B, PM-7, SAC-4, and tool contamination monitor)
Calibration expiration and source response check currency on selected portable radiation detection instruments staged for use (AMP-100, AMS-4, ASP-1, and WR telepole), to include the observation of instrument source response checks (L-144 and RSO-50E)
The status of SCBAs staged and ready for use in the plant and associated surveillance and maintenance records
The licensees capability for refilling and transporting SCBA air bottles to and from the control room and operations support center during emergency conditions
Training and qualifications of personnel who may use SCBAs during an emergency (control room operators and emergency response personnel),
perform maintenance and repair of SCBAs, and refill air bottles
Periodic air cylinder hydrostatic testing results
Audits, surveillances, and self-assessments related to the radiation monitoring instrumentation and self-contained breathing apparatus programs performed since the last inspection
-2-
Summary of corrective action documents written since the last inspection and selected documents related to radiation monitoring instruments, self-contained breathing apparatus equipment, repetitive, and significant individual deficiencies Because of the lack of opportunity or the lack of occurrence, the team did not observe instrument calibrations.
b.
Findings No findings of significance were identified.
2PS1 Radioactive Gaseous And Liquid Effluent Treatment And Monitoring Systems (71122.01)
a.
Inspection Scope This area was inspected to ensure that the gaseous and liquid effluent processing systems were maintained so that radiological releases were properly mitigated, monitored, and evaluated with respect to public exposure. The team conducted an in-office review of the licensees annual reports and self-assessments, and corrective action documents. Onsite, the team examined procedures and representative records, walked down the major components of the gaseous and liquid release systems, and interviewed cognizant personnel. The following items were reviewed and compared with regulatory requirements and commitments in the Updated Safety Analysis Report:
2001 and 2002 Radiological Effluent Release Reports
Changes to the Offsite Dose Calculation Manual and to the radioactive waste system design and operation.
- Selected radioactive liquid waste release permits and associated projected doses to members of the public.
- Projected dose calculations to members of the public associated with continuous gaseous effluent releases
Monthly, quarterly, and annual dose calculations
Air cleaning system surveillance test results
Surveillance test results for the stack and vent flow rates
Records of instrument calibrations performed since the last inspection for effluent radiation monitors and flow measurements devices at each point of discharge
Calibration records of counting room instrumentation associated with effluent monitoring and release activities
-3-
Quality control records for the counting room instruments
Interlaboratory comparison program and results
Audits and self-assessments related to the radioactive effluent treatment and monitoring program and the licensees ability to meet the Radiological Effluent Technical Specification/Offsite Dose Calculation Manual requirements
Summary of corrective action documents written since the last inspection and selected documents related to the radioactive effluent treatment and monitoring program, and the engineered-safety-feature air cleaning systems Because of the lack of opportunity or the lack of occurrence, the team did not review the sampling of the liquid or gaseous radioactive effluents by licensee personnel, anomalous results which would have been reported in the radiological effluent release reports, and performance indicator incidents. Previously, a potential unmonitored release from the condensate storage tank was reviewed and documented in Inspection Report 50-458/02-07, Section 3.3.
b.
Findings No findings of significance were identified.
2PS2 Radioactive Material Processing and Transportation (71122.02)
a.
Inspection Scope The team conducted an in-office review of the licensees annual reports and self-assessments, and corrective action documents. Onsite, the team interviewed radiation workers and radiation protection personnel involved in radioactive material processing and transportation activities and walked down the liquid and solid radioactive waste processing systems to verify that the current system configuration and operation agreed with the descriptions contained in the Updated Safety Analysis Report and in the Process Control Program. The team also reviewed radioactive waste processing equipment that was not operational or abandoned in place for material condition, potential unmonitored release pathways, and unnecessary personnel exposure.
The team observed the packaging and shipment of a container of liquid radioactive waste resin (shipment 2003-099) made during the inspection to verify that the licensees transportation program complied with Department of Transportation regulations contained in 49 CFR Parts 170-189. In addition, the team reviewed the licensees overall transportation program to ensure that it complied with the requirements of 10 CFR Parts 20, 61, and 71 and Department of Transportation regulations. The following items were reviewed and compared with regulatory requirements:
The adequacy of any changes made to the radioactive waste processing systems since the last inspection
-4-
Waste stream determination and sampling procedures
Radioactive waste transfer and sampling procedures and waste classification methodology
Radio-chemical sample analysis results and changes to operational parameters affecting the results for each of the licensees radioactive waste streams
Scaling factors and calculations used to account for difficult-to-measure radionuclides
10 CFR Part 20, Appendix G, quality assurance program
Applicable transport cask Certificates of Compliance
Transferee licenses
Procedures for cask loading and closure
Training of personnel responsible for the conduct of radioactive waste processing and radioactive material shipment preparation activities
Documentation for five non-excepted package shipments which demonstrated shipment packaging, surveying, labeling, marking, placarding, vehicle checks, emergency instructions, disposal manifest, shipping papers provided to the driver, and licensee verification of shipment readiness
Audits and self-assessments related to the radioactive material and transportation programs performed since the last inspection
Summary of corrective action documents written since the last inspection and selected documents involving the radioactive material and shipping programs, and repetitive and significant individual deficiencies.
b.
Findings
Introduction. A Green non-cited violation was identified by the team for the failure to post a radiological hazard (hot spot) in accordance with a Technical Specification required procedure.
Description. On August 19, 2003, during a tour of the 106 foot elevation of the radwaste building, the team identified elevated radiation levels on an accessible drain pipe from the radwaste sample sink that was not tagged as a hot spot. Health Physics personnel verified contact radiation levels of 200 millirem per hour and 50 millirem per hour at one foot. From discussion with radiation protection personnel the inspector noted that the licensee had performed a survey 11 days earlier that indicated contact dose rates on the pipe of 310 millirem per hour with a one foot reading of 32 millirem per hour; however, the technician and the survey reviewer failed to tag the hot spot to warn workers of the hazard.
-5-Analysis. The team determined that the licensees failure to properly tag a radiological hazard is a performance deficiency. The finding was more than minor because it was associated with the Occupational Radiation Safety Cornerstone attribute (program and process) and affected the cornerstone objective to ensure the adequate protection of a workers health and safety from exposure to radiation. The finding involved the potential for a workers unplanned or unintended dose resulting from actions contrary to procedures. When processed through the Occupational Radiation Safety Significance Determination Process the finding was determined to be of very low safety significance (Green) because the finding did not involve ALARA planning or work controls, no individual received an overexposure or a substantial potential for overexposure, and the ability to assess dose was not compromised.
Enforcement. Technical Specification 5.4.1.a requires written procedures be established, implemented, and maintained covering the activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Appendix A, Section 7, references procedures for control of radioactivity and limiting personnel exposure. Station Procedure RP-107, Radiation Protection Glossary, Revision 2, Step 3.63, defined a hot spot as an area of a valve, pipe or drain which have contact radiation levels greater than 100 millirem per hour and 4 times the one foot reading.
Station Procedure RP-109, Hot Spot Program, Revision 0, Step 5.2.1, stated in part, that hot spots are identified with a hot spot tag to alert workers of the hazard.
However, on August 19, 2003, the licensee did not post a hot spot to alert workers of the radiological hazard as required by procedure. Because the failure to identify a radiological hazard was of very low safety significance and has been entered into the corrective action program as Condition Report CR-RBS-2003-2955, this violation is being treated as a noncited violation, consistent with Section VI.A of the NRC Enforcement Policy: NCV 50-458/0309-01, Failure to post a radiological hazard.
2PS3 Radiological Environmental Monitoring Program and Radioactive Material Control Program (71122.03)
a.
Inspection Scope The team conducted an in-office review of the licensees annual reports and self-assessments, and corrective action documents. Onsite, the team interviewed members of the licensees staff responsible for implementing the radiological environmental, meteorological monitoring, and radioactive material control programs.
The team observed the following activities and equipment with respect to the Final Safety Analysis Report (FSAR), Offsite Dose Calculation Manual (ODCM), Technical Requirements Manual, and Technical Specification requirements:
Preparation of airborne particulate, and charcoal samples for analysis
Meteorological primary and back-up instrumentation at the meteorological tower and data displays in the control room and emergency operation facility
The survey of materials for release from the controlled access area The following items were reviewed and compared with the FSAR, ODCM, and regulatory requirements to determine whether the licensee had an adequate program
-6-to verify the impact of radioactive effluent releases to the environment and to ensure that the licensees surveys and controls were adequate to prevent the inadvertent release of licensed materials into the public domain:
Implementing procedures for the radiological environmental monitoring program
Environmental sample analytical results
Two environmental air sampling stations (AP1 and AQS2, located in Emergency Planning Sectors P and Q, respectively ) and four thermoluminescent dosimetry stations (TA1, TP1, TQS1, and TQS2 located in Emergency Planning Sectors A, P, Q and Q, respectively) specified in the Offsite Dose Calculation Manual
Calibration and maintenance records of selected environmental air sampling equipment
Calibration, maintenance, and quality control records of environmental sample analytical instrumentation
2001 and 2002 land use census results and changes to the radiological environmental monitoring program (no changes where identified)
2001 and 2002 Annual Radiological Environmental Operating Report
The environmental laboratorys performance in the interlaboratory comparison program
Implementing procedures for the meteorological monitoring program
Meteorological instrument operability, reliability, and annual meteorological data recovery
Procedures, methods, and instruments used to survey, control, and release materials from the controlled access area
- Calibration procedures and records for instruments used to perform radiological surveys prior to material release
Detection sensitivities and counting parameters of radiation survey instruments used for the release of potentially contaminated materials from the controlled access area
Criteria used for the unrestricted release of potentially contaminated material from the controlled access area
Audits and self-assessments related to the radiological environmental, meteorological monitoring, and radioactive material control programs performed since the last inspection
-7-
Summary of corrective action documents written since the last inspection and selected documents involving radiological environmental monitoring, meteorological monitoring, and release of radioactive material programs.
Because of the lack of opportunity, the team did not observe the collection of environmental media.
b.
Findings Introduction. The team reviewed the circumstances related to a self-revealing non-cited violation for the failure to control radioactive material in accordance with a Technical Specification required procedure.
Description. On March 31, 2003, the licensee was notified by Tri-Tool Incorporated of Houston, Texas that two pieces of clam shell equipment used on the Leading Edge Flow Meter project was sent to Tri-Tools shop. Tri-Tools personnel surveyed the items and found fixed contamination levels as high as 450 corrected counts per minute per probe area. Surveys conducted by the licensee on April 1, 2003, determined that fixed contamination levels were as high as 1,000 corrected counts per minute per probe area. (The licensee identified three additional examples in which detectable licensed radioactive material was not properly controlled. These examples are discussed in Section 4OA7.)
Analysis. The team determined that the licensees failure to control radioactive material in accordance with a Technical Specification required procedure is a performance deficiency. The finding is greater than minor because it is associated with the Public Radiation Safety Cornerstone attribute (program and process) and affected the cornerstone objective to protect public health and safety from exposure to radioactive materials released into the public domain. The finding involved an occurrence in the radioactive material control program that was contrary to licensee procedures. This isssue was evaluated using the Public Radiation Safety Significance Determination Process and was determined to be a finding of very low safety significance (Green) because public exposure associated with each item was less than 5 millirem and there were not more than 5 occurrences.
Enforcement. Technical Specification 5.4.1.a requires written procedures be established, implemented, and maintained covering the activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Appendix A, Section 7, references procedures for control of radioactivity. Section 5.1.1 of Procedure RSP-213, Control and Handling of Radioactive Materials, Revision 16, stated, in part, that material can be unconditionally released from the controlled access area if there is no detectable loose surface and fixed contamination above the background radiation levels for the particular counting system. However, on March 31, 2003, the licensee failed to evaluate an item that was unconditionally released from the controlled access area, against its procedural criteria, and subsequently released radioactive material from the protected area. Because the release of radioactive material was of very low safety significance and has been entered into the corrective action program as Condition Report CR-RBS-2003-1540,
-8-this violation is being treated as a noncited violation, consistent with Section VI.A of the NRC Enforcement Policy: NCV 50-458/0309-02, Failure to control radioactive material.
4.
OTHER ACTIVITIES 4OA2 Problem Identification and Resolution Annual Sample Review a.
Inspection Scope The team evaluated the effectiveness of the licensees problem identification and resolution process with respect to the following inspection areas:
Radiation Monitoring Instrumentation (Section 2OS3)
Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems (Section 2PS1)
Radioactive Material Processing and Transportation (Section 2PS2)
Radiological Environmental Monitoring Program and Radioactive Material Control Program (Section 2PS3)
b.
Findings and Observations No findings of significance were identified.
4OA6 Management Meetings Exit Meeting Summary On August 22, 2003, the team presented the inspection results to Mr. P. Hinnenkamp, Vice-President, Operations, and other members of his staff who acknowledged the findings. The team confirmed that proprietary information was not provided or examined during the inspection.
4OA7 Licensee-Identified Violations The following findings of very low safety significance were identified by the licensee as violations of NRC requirements which meet the criteria of Section VI of the NRC Enforcement Policy, NUREG-1600, for being dispositioned as NCVs.
Technical Specification 5.4.1.a requires written procedures be established, implemented, and maintained covering control of radioactivity. Section 5.1.1 of Procedure RSP-213, Control and Handling of Radioactive Materials, Revision 16, stated, in part, that material can be unconditionally released from the controlled access area if there is no detectable loose surface and fixed contamination above background radiation levels. On November 1 and 9, 2002, and April 10, 2003, the licensee identified a total of three examples in which detectable licensee radioactive material was found outside the controlled access area. These events are described in the licensees corrective action program as Condition Reports (CR)-RBS-2002-1714,
-9-CR-RBS-2002-1769 and CR-RBS-2003-1779, respectively. Because public exposure associated with each item was less than 5 millirem and there were not more than 5 occurrences, this violation is of very low significance.
PARTIAL LIST OF PERSONS CONTACTED Licensee R. Biggs, Coordinator, Licensing C. Fantacci, Technical Specialist, Radiation Protection D. Heath, Supervisor, Radiation Protection P. Hinnenkamp, Vice-President, Operations V. Huffstatler, Supervisor, Radiation Protection K. Huffstatler, Technical Specialist, Licensing J. Leavines, Manager, Licensing G. Morrison, Senior HP/Chem Specialist, Radiation Protection B. Olinde, Manager, I&C P. Page, Supervisor, Radiation Protection J. Parker, Engineer, Digital Radiation Monitoring System W. Spell, Senior Environmental Specialist, Chemistry T. Trepanier, General Manager, Plant Operations NRC M. Miller, Resident Inspector LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Opened NONE Opened and Closed During this Inspection 05000458/2003009-01 NCV Failure to post a radiological hazard (Section 2PS2)05000458/2003009-02 NCV Failure to control radioactive material (Section 2PS3)
Previous Items Closed NONE LIST OF DOCUMENTS REVIEWED Quality Assurance Documents:
QA-6-2001-RBS-1 Quality Assurance Audit of Effluent and Environmental Monitoring QA-2-2001-RBS-1 Quality Assurance Audit of Chemistry, Effluents, and Environmental QA-15-2001-RBS-1 Audit of Radwaste QA-14-2001-RBS-1 Audit of Radiation Protection Program QA-14-2003-RBS-1 Audit of Radiation Protection Program QS-2001-RBS-023 Surveillance of Audit QA-15-2000-RBS-1 QS-2003-RBS-009 RF-11 Radiation Protection Surveillance
-2-QS-2002-RBS-011 Surveillance of Audit QA-2-2001-RBS-1 LO-RLO-2001-00004 Assessment of Radiation Protection (2000)
LO-RLO-2001-00011 Assessment of Radiation Protection Radioactive Waste (RP-07)
LO-RLO-2003-00107 Assessment of Radioactive Material Control RPG-M-2002-034 Review of the Whole Body Count Libraries Inspection Procedure 71121.03 Condition Reports CR-RBS-2002-1244, CR-RBS-2002-1363, CR-RBS-2003-0234, CR-RBS-2003-0378, CR-RBS-2003-0615, CR-RBS-2003-1189, CR-RBS-2003-1507, CR-RBS-003-2334, CR-RBS-2003-2617, CR-RBS-2003-2748, CR-RBS-2003-2863 Procedures 08-S-10-03 Calibration of Portable Area Radiation Monitors: Non-safety Relate, Revision 2 08-S-10-04 Calibration of Portable Dose Rate Instruments: Non-safety Related, Revision 2 08-S-10-06 Calibration of Extendable Dose Rate Instruments: Non-safety Related, Revision 2 08-S-10-08 Calibration of Portable Count Rate Instruments: Non-safety Related, Revision 1 08-S-10-11 Calibration of Portable Scalers, Revision 2 MCP-4201 DRMS Low Range Area Monitor Calibration, Revision 3J RHP-0105 Operation of the Canberra Accuscan II and Fastscan Whole Body Counters, Revision 5 RHP-0106 Calibration of the Canberra Fastscan Whole Body Counter, Revision 1 RP-104 Personnel Contamination Events, Revision 3 RP-202 Personnel Monitoring, Revision 1 RP-203 Dose Assessment, Revision 2 RP-30 Source Checking of Radiation Protection Instrumentation, Revision 2 RP-304 Operation of Counting Equipment, Revision 1 RP-306 Operation and Calibration of the Eberline PM-7, Revision 0 RP-307 Operation and Calibration of Eberline Personnel Contamination Monitors (PCM),
Revision 2 RP-308 Operation of Gamma Scintillation Tool Monitors, Revision 1 RP-310 Operation and Initial Setup of the Eberline AMS-4 Continuous Air Monitor, Revision 0 RPP-0074 Refilling SCBA Cylinders, Revision 8 RSP-0201 Respiratory Protection Program for River Bend Station, Revision 9A STP-511-4202 RMS-Primary Containment Purge Isolation Radiation-High Activity Monitor Channel Calibration Test and LSFT (RMS-RE21B), Revision 13 STP-511-4249 RMS-Primary Containment Area Radiation Monitor, Channel Calibration RMS-RE16A, Revision 9A STP-511-4250 RMS-Primary Containment Area Radiation Monitor, Channel Calibration RMS-RE16B, Revision 9 Inspection Procedure 71122.01 Condition Reports CR-RBS-2001-0310, CR-RBS-2001-0975, CR-RBS-2003-2290, CR-RBS-2003-2432, CR-RBS-2003-2493, CR-RBS-2003-2529, and CR-RBS-2003-2722
-3-Calibration Data Effluent Release and Flow Rate Instrumentation MAI 353369, MAI 355309, MAI 357659, MAI 363095, MAI 365724, MAI 367333, MAI 372163 Effluent Radiation Monitors and Flow Measurements Device Calibrations RMS-FE126, RMS-FE5A, RMS-FE6A, RMS-RE126, RMS-RE5A, RMS-RE6A, RMS-RE107 Procedures CSP-0110 Radioactive Liquid Effluent Batch Discharge, Revision 16 RP-304 Operation of Counting Equipment, Revision 1 RPP-0027 Gaseous Effluents Monitor Setpoints Determination, Revision 3A RPP-0102 Dose Calculations from Gaseous Effluents, Revision 6A STP-511-4205 SCIS/RMS Fuel Building Ventilation Exhaust Radiation - High Channel Calibration Test RMS-RE5A, Revision 7F STP-511-4215 RMS-Main Plant Exhaust Duct Noble Gas Activity Channel Calibration RMS-RE-126, Revision 8 STP-511-4216 RMS-Radwaste Building Ventilation Exhaust Duct Noble Gas Activity Monitor Channel Calibration RMS-RE6A, Revision 7B STP-511-4231 RMS-Main Plant Exhaust Duct Monitoring System Effluent System Flow Rate Monitor Channel Calibration RMS-FE126, Revision 6B STP-511-4233 Fuel Building Exhaust Duct Monitoring System Flow Rate Monitor Channel Calibration RMS-FE5A, Revision 5C STP-511-4239 RMS-Radwaste Building Ventilation Exhaust Duct Monitoring System Flow Rate Monitor Channel Calibration RMS-FE6A, Revision 5A STP-511-4280 RMS-Liquid Radwaste Effluent Line Radiation Monitor Channel Calibration RMS-RE107, Revision 9C Radioactive liquid waste release permits 2003-164 2003-175 2003-176 Inspection Procedure 71122.02 Condition Reports CR-RBS-2000-1016, CR-RBS-2000-1826, CR-RBS-2000-1827, CR-RBS-2000-1232, CR-RBS-2000-1165, CR-RBS-2001-0585, CR-RBS-2001-1473, CR-RBS-2001-1496, CR-RBS-2001-1566, CR-RBS-2002-2041, and CR-RBS-2003-0904, Procedures RW-101 Radioactive Waste Management, Revision 0 RW-102 Radioactive Shipping Procedure, Revision 1 RW-105 Process Control Program, Revision 1 RP-109 Hot Spot Program, Revision 0
-4-RWS-336 Set-Up and Operation of the RDS-1000 Dewatering Unit, Revision 8 Shipment Packages 2001-012, 2002-011, 2002-016, 2002-024, 2003-075 Inspection Procedure 71122.03 Condition Reports Radiological Environmental Monitoring Program CR-RBS-2001-00329, CR-RBS-2001-00334, CR-RBS-2001-00976, CR-RBS-2001-00977, CR-RBS-2001-00983, CR-RBS-2001-00984, and CR-RBS-2003-01877 Release of Radioactive Material CR-RBS-2002-00747, CR-RBS-2002-01079, CR-RBS-2002-01714, CR-RBS-2002-01769, CR-RBS-2002-01895, and CR-RBS-2002-01943, Meteorological Monitoring CR-RBS-2001-00481, CR-RBS-2001-00573 and CR-RBS-2002-01793 Procedures Radiological Environmental Monitoring Program ESP-8-001 Organization and Responsibilities of RBS Environmental Services Group, Revision 8 ESP-8-005 Assessment of the Reliability of Results of the Radiological Environmental Monitoring Program, Revision 9 ESP-8-023 Sampling of Airborne Radioiodine and Particulates for Radiological Environmental Monitoring, Revision 13 ESP-8-050 Conduct of the Radiological Environmental Monitoring Program, Revision 12 Meteorological Monitoring ESP-8-012 Routine Performance Checks of Meteorological Monitoring Equipment, Revision 13 Calibration Data Radiological Environmental Monitoring Program Air Sample Pump Serial Number 0235, Dated February 27, 2003 Air Sample Pump Serial Number 0512, Dated February 27, 2003