IR 05000382/2009007
| ML091050491 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/15/2009 |
| From: | Greg Werner NRC/RGN-IV/DRS/PSB-2 |
| To: | Kowalewski J Entergy Operations |
| References | |
| FOIA/PA-2010-0209 IR-09-007 | |
| Download: ML091050491 (21) | |
Text
April 15, 2009
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - NRC RADIATION SAFETY TEAM INSPECTION REPORT 05000382/2009007
Dear Mr. Kowalewski:
On March 6, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Waterford Steam Electric Station, Unit 3. The enclosed report documents the inspection findings, which were discussed at the conclusion of the inspection with you and members of your staff.
The team reviewed selected procedures and records, observed activities, and interviewed personnel. Specifically, the team evaluated the inspection 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
Based on the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) 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 website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Gregory E. Werner, Chief
Plant Support Branch 2
Division of Reactor Safety UNITED STATES NUCLEAR REGULATORY COMMISSION R E GI ON I V 612 EAST LAMAR BLVD, SUITE 400 ARLINGTON, TEXAS 76011-4125
Entergy Operations, Inc.
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Docket: 50-382 License: NPF-38
Enclosure:
NRC Inspection Report 05000382/2009007 w/attachment: Supplemental Information
REGION IV==
Dockets:
50-382
Licenses:
Report:
Licensee:
Entergy Operations, Inc
Facility:
Waterford Steam Electric Station, Unit 3
Location:
Hwy. 18 Killona, Louisiana
Dates:
Inspectors:
March 2 through 6, 2009
L. C. Carson II, Senior Health Physicist and Team Leader L. T. Ricketson, P.E., Senior Health Physicist D. C. Graves, Health Physicist D. L. Stearns, Health Physicist
Accompanied By:
Approved By:
N. A. Greene, Health Physicist
Gregory E. Werner, Chief Plant Support Branch 2 Division of Reactor Safety
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Enclosure SUMMARY OF FINDINGS
IR 05000382/2009007; 03/02/2007 - 03/06/2007; Waterford Steam Electric Station, Unit 3; Radiation Safety Team Inspection
The report covered a one-week period of onsite inspections by a team of four region-based health physics inspectors. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.
A.
NRC-Identified and Self-Revealing Findings
No findings of significance were identified.
B.
Licensee-Identified Violations
None
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Enclosure Report Details
2.
RADIATION SAFETY
Cornerstones: Occupational Radiation Safety [OS] and Public Radiation Safety
[PS]
2OS3 Radiation Monitoring Instrumentation and Protective Equipment (71121.03)
a.
Inspection Scope
This area was inspected to determine the accuracy and operability of radiation monitoring instruments that are used for the protection of occupational workers and the adequacy of the program to provide self-contained breathing apparatus to workers. The team used the requirements in 10 CFR Part 20 and the licensees procedures required by technical specifications as criteria for determining compliance. The team interviewed licensee personnel and reviewed:
- Calibration of area radiation monitors associated with transient high and very high radiation areas and post-accident monitors used for remote emergency assessment;
- Calibration of portable radiation detection instrumentation, electronic alarming dosimetry, and continuous air monitors used for job coverage;
- Calibration of whole body counting equipment and radiation detection instruments utilized for personnel and material release from the radiologically controlled area;
- Audits and self-assessments; licensee event reports or special reports, if any were required since the previous inspection;
- Corrective action program reports since the last inspection;
- Licensee action in cases of repetitive deficiencies or significant individual deficiencies;
- Calibration expiration and source response check currency on radiation detection instruments staged for use;
- The licensees capability for refilling and transporting self-contained breathing apparatus air bottles to and from the control room and operations support center during emergency conditions, status of self-contained breathing apparatus staged and ready for use in the plant and associated surveillance records, and personnel qualification and training;
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Enclosure
Qualification documentation for onsite personnel designated to perform maintenance on the vendor-designated vital components, and the vital component maintenance records for self-contained breathing apparatus units;
Either because the conditions did not exist or an event had not occurred, no opportunities were available to review the following items:
- Licensee event reports or special reports
Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of nine of the required nine samples, as defined in Inspection Procedure 71121.03-05.
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: (1) ensure that the gaseous and liquid effluent processing systems are maintained so that radiological discharges are properly mitigated, monitored, and evaluated with respect to public exposure; (2) ensure that abnormal radioactive gaseous or liquid discharges and conditions, when effluent radiation monitors are out-of-service, are controlled in accordance with the applicable regulatory requirements and licensee procedures; (3) verify that the licensee=s quality control program ensures that the radioactive effluent sampling and analysis requirements are satisfied so that discharges of radioactive materials are adequately quantified and evaluated; and (4) verify the adequacy of public dose projections resulting from radioactive effluent discharges. The team used the requirements in: 10 CFR Part 20; 10 CFR Part 50, Appendices A and I; 40 CFR Part 190; the Offsite Dose Calculation Manual; and licensee procedures required by the Technical Specifications as criteria for determining compliance.
The team conducted an in-office inspection and reviewed:
- Appropriate program documents, procedures and evaluations related to the radiological effluent controls program listed in the attachment to this report;
- The implementation of the Radiological Effluent Controls Program requirements as described in Radiological Effluent Technical Specifications;
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Enclosure
- Changes, if any, to the liquid or gaseous radioactive waste system design, procedures, or operation as described in the Final Safety Analysis Report;
- Changes, if any, to the Offsite Dose Calculation Manual made by the licensee since the last inspection;
- Effluent monitoring instrumentation documentation to ensure adequate methods and monitoring of effluents;
- The program for identifying, assessing, and controlling contaminated spills and leaks;
- The annual effluent release reports and the correlation to the environmental monitoring results;
- The results from quality assurance audits.
The team conducted an onsite inspection which included interviewing cognizant licensee personnel, performing walkdowns of facilities and equipment, and observing licensee activities to review:
- The gaseous and liquid discharge system configuration;
- Selected point of discharge effluent radiation monitoring systems and flow measurement devices;
- The observation of selected portions of the routine processing and discharge of radioactive gaseous and liquid effluent (sample collection and analysis) including a selection of radioactive gaseous and liquid waste effluent discharge permits;
- Effluent discharges made with inoperable (declared out-of-service) effluent radiation monitors including the projected doses to members of the public;
- Surveillance test results on non-safety related ventilation and gaseous discharge systems (high efficiency particulate air and charcoal filtration) including the methodology to determine the stack and vent flow rates;
- The identification of non-radioactive systems that have become contaminated, if applicable;
- Effluent monitoring instrument (installed and counting room) maintenance, quality control, and calibration;
- The methods used to determine the isotopes in the plant source term, meteorological dispersion and deposition factors, and hydrogeologic
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Enclosure characteristics used in the Offsite Dose Calculation Manual and effluent dose calculations including a selection of monthly, quarterly, and annual dose calculations;
- The land-use census;
- Records of abnormal gaseous or liquid discharges, if any, including the evaluation and analysis of events involving spills or discharges, dose assessments to members of the public, required (or voluntary) offsite notifications, and assessments and reporting of abnormal discharges in the Annual Radiological Effluent Release Report;
- Evaluations of discharges from onsite surface water bodies, if any;
- Routine groundwater monitoring results;
- Audits and self-assessments; licensee event reports or special reports, if any were required since the previous inspection;
- The results of the inter-laboratory comparison program;
- Effluent sampling records;
- The calibration of post-accident effluent monitoring instrumentation and expected accident source.
The team reviewed the licensees program of problem identification and resolution, including:
- Placement of problems identified through audits, self assessments, and monitoring results into the corrective action program and adequacy of immediate and long term corrective actions;
- Problem identification and resolution follow-up activities;
- Identification of repetitive deficiencies or significant individual deficiencies in problem identification and resolution identified by the licensee=s self-assessment activities.
Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of three of the required three samples, as defined in Inspection Procedure 71122.01-05.
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Enclosure
b.
Findings
No findings of significance were identified.
2PS2 Radioactive Material Processing and Transportation (71122.02)
a.
Inspection Scope
This area was inspected to verify that the licensee=s radioactive material processing and transportation program complies with the requirements of 10 CFR Parts 20, 61, and 71 and Department of Transportation regulations contained in 49 CFR Parts 171-180. The team interviewed licensee personnel and reviewed:
- The radioactive waste system description, recent radiological effluent release reports, and the scope of the licensee=s audit program;
- Liquid and solid radioactive waste processing systems configurations, the status and control of any radioactive waste process equipment that is not operational or is abandoned in place, changes made to the radioactive waste processing systems since the last inspection, and current processes for transferring radioactive waste resin and sludge discharges;
- Radio-chemical sample analysis results for radioactive waste streams and use of scaling factors and calculations to account for difficult-to-measure radionuclides;
- Shipment packaging, surveying, labeling, marking, placarding, vehicle checking, driver instructing, and disposal manifesting;
- Shipping records for non-excepted package shipments;
- Audits and self-assessments, licensee event reports, special reports, audits, and state agency reports, if any were required since the previous inspection.
Either because the conditions did not exist or an event had not occurred, no opportunities were available to review the following items:
- Licensee event reports or special reports
Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of six of the required six samples, as defined in Inspection Procedure 71122.02-05.
b.
Findings
No findings of significance were identified.
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Enclosure
2PS3 Radiological Environmental Monitoring Program and Radioactive Material Control Program (71122.03)
a.
Inspection Scope
This area was inspected to ensure that the radiological environmental monitoring program verifies the impact of radioactive effluent releases to the environment and sufficiently validates the integrity of the radioactive gaseous and liquid effluent release program; and that the licensees surveys and controls are adequate to prevent the inadvertent release of licensed materials into the public domain. The team used the requirements in 10 CFR Part 20, Appendix I of 10 CFR Part 50, the Offsite Dose Calculation Manual, and the licensees procedures required by technical specifications as criteria for determining compliance. The team interviewed licensee personnel and reviewed:
- Annual environmental monitoring reports and licensee event reports, if any were required since the previous inspection;
- Selected air sampling and thermoluminescence dosimeter monitoring stations;
- Collection and preparation of environmental samples;
- Operability, calibration, and maintenance of meteorological instruments;
- Each event, if any, documented in the Annual Environmental Monitoring Report which involved a missed sample, inoperable sampler, lost thermoluminescence dosimeter, or anomalous measurement;
- Significant changes, if any, made by the licensee to the Offsite Dose Calculation Manual as the result of changes to the land census or sampler station modifications since the last inspection;
- Calibration and maintenance records for air samplers, composite water samplers, and environmental sample radiation measurement instrumentation, quality control program, interlaboratory comparison program results, and vendor audits;
- Locations where the licensee monitors potentially contaminated material leaving the radiological controlled area [or controlled access area] and the methods used for control, survey, and release from these areas;
- Type of radiation monitoring instrumentation used to monitor items released, survey and release criteria of potentially contaminated material, radiation detection sensitivities, procedural guidance, and material release records;
- Audits, self-assessments, corrective action documents and licensee event reports or special reports, if any were required, since the previous inspection.
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Enclosure
Either because the conditions did not exist or an event had not occurred, no opportunities were available to review the following items:
- Licensee event reports or special reports
Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of ten of the required ten samples, as defined in Inspection Procedure 71122.03-05.
b.
Findings
No findings of significance were identified.
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.
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Enclosure
4OA5 Other Activities
.1 (Closed) Temporary Instruction 2515/173, Review of the Implementation of the Industry Groundwater Protection Voluntary Initiative
a.
Inspection Scope
An NRC assessment was performed of the licensees groundwater protection program to determine whether the licensee implemented the voluntary Industry Groundwater Protection Initiative, dated August 2007 (Nuclear Energy Institute 07-07, ADAMS Accession Number ML072610036). Inspectors interviewed personnel, performed walk-downs of selected areas, and reviewed the following items:
- Records of the site characterization of geology and hydrology;
- Evaluations of systems, structures, and or components that contain or could contain licensed material and evaluations of work practices that involve licensed material for which there is a credible mechanism for the licensed material to reach the groundwater;
- Implementation of an onsite groundwater monitoring program to monitor for potential licensed radioactive leakage into groundwater;
- Procedures for the decision making process for potential remediation of leaks and spills, including consideration of the long term decommissioning impacts;
- Records of leaks and spills recorded, if any, in the licensees decommissioning files in accordance with 10 CFR 50.75(g);
- Licensee briefings of local and state officials on the licensees groundwater protection initiative;
- Protocols for notification to the local and state officials, and to the NRC regarding detection of leaks and spills;
- Protocols and/or procedures for thirty day reports if an onsite groundwater sample exceeds the criteria in the radiological environmental monitoring program;
- Groundwater monitoring results as reported in the annual effluent and/or environmental monitoring report;
- Licensee and industry assessments of implementation of the groundwater protection initiative.
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Enclosure
b.
Findings No findings of significance were identified. Implementation of the Industry Groundwater Protection Initiative is voluntary. Under the final Initiative, each site was to have developed an effective, technically sound groundwater protection program by August 2008. The licensees corporate office completed the Entergy Fleet self-assessment of the Initiative on August 25, 2008. According to the Entergy Fleet self-assessment, the licensee had not met the objectives established in Nuclear Energy Institute 07-07 Groundwater Protection Initiative for the Waterford 3 site. The team also found that the licensee had not fully implemented the Groundwater Protection Initiative and had not conducted its own site self-assessment of the initiative implementation. According to the Entergy Fleet self-assessment Waterford 3 had not implemented the following aspects of the Groundwater Protection Initiative:
An overall groundwater monitoring program and plan had not been implemented.
- The site-specific hydrogeological evaluation that was conducted in January 2007 needed to be upgraded to reflect groundwater flow characteristics.
- The risk assessment and leak detection program for systems, structures, and components needed to be updated regarding potential for onsite contamination and leaks to groundwater (i.e., monitoring and sentinel wells);.
A remediation protocol to prevent migration of licensed material off-site and to minimize decommissioning aspects had not been established.
As of a result of this team inspection, Waterford 3 issued Condition Report WF3-2009-01021 to perform a line-by-line review of the Nuclear Energy Institute Groundwater Protection Initiative and Entergy Fleet self-assessment.
4OA6 Management Meetings
Exit Meeting Summary
On March 6, 2009, the team presented the inspection results to Mr. J. Kowalewski, 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.
ATTACHMENT: SUPPLEMENTAL INFORMATION
A1-1 Attachment
SUPPLEMENTAL INFORMATION
J. Brawley, ALARA Supervisor, Radiation Protection A. Buford, Engineer, System Engineering K. Cook, Acting General Manager Plant Operations L. Dauzat, Supervisor, Radiation Protection A. Dubois, Environmental Specialist D. Dufrene; Technician, Radiation Protection J. Hornsby, Superintendent, Chemistry J. Kowalewski, Vice President, Operations S. Landry, Specialist, Radwaste Material Control J. Lewis, Manager, Emergency Preparedness M. Louque, Environmental Specialist, Chemistry M. Mason, Engineer, Licensing C. Miller, Lead Supervisor, Radiation Protection D. Miller, Supervisor, Radwaste/Radioactive Material Control R. Murillo, Manager, Licensing K. Nichols, Director, Engineering B. Piluti, Manager, Radiation Protection R. Prejean, Senior Specialist, Chemistry C. Pramono; System Engineer, Radiation Monitoring System S. Ramzy; Specialist, Radiation Protection J. Ridge, Manager, Quality Assurance J. Wilbur, System Engineer, Systems Engineering C. Zeringue, Superintendent, Chemistry NRC
D. Overland, Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened and Closed During this Inspection None
Previous Items Closed None
Previous Items Discussed None
A1-2 Attachment LIST OF DOCUMENTS REVIEWED
Section 2OS3: Radiation Monitoring Instrumentation and Protective Equipment (IP71121.03)
Audits and Self-assessments
2007 Respiratory Protection Focused Self Assessment December, 2007
Procedures NUMBER TITLE REVISION EN-RP-301 Radiation Protection Instrument Control Revision 2 EN-RP-302 Operation of Radiation Protection Instrumentation Revision 1 EN-RP-303 Source Checking of Radiation Protection Instrumentation Revision 2 EN-RP-306 Calibration and Operation of the Eberline PM-7 Revision 2 EN-RP-307 Operation and Calibration of the Eberline Personnel Contamination Monitors Revision 1 EN-RP-308 Operation and Calibration of Gamma Scintillation Tool Monitors Revision 2 HP-002-450 Calibration and QA of the Whole Body Counting System Revision 17 EN-RP-501 Respiratory Protection Program Revision 3 EN-RP-502 Inspection and Maintenance of Respiratory Protection Equipment Revision 4 EN-RP-504 Breathing Air Revision 2 RPP-0074 Refilling SCBA Cylinders Revision 11
Effluent Monitor Calibrations
Channel No.
Monitor Description Work Order Package Date PRMIR0100-1 Plant Vent Stack Radiation Monitor 51209490-01 4/23/2008 PRMIR0110 Plant Vent Stack High Range Radiation Monitor 51205693-01 1/21/2008 PRMIR0100-2 Plant Vent Stack Radiation Monitor 51201752-01 1/15/2008 PRMIR0647 Waste Condensate and Laundry Waste Discharge Monitor 5151024-01 9/22/2008
Area Monitor Calibrations
Channel No.
Monitor Description Work Order Package Date ARMIR5400-A Containment High Range Radiation Monitor 0011885501 5/09/2008 ARMIR5400-B Containment High Range Radiation Monitor 00118857-01 5/09/2008
A1-3 Attachment Radiation Protection Instrumentation Calibrations
Identification No.
Instrument Type Calibration Date Westside Access Whole Body Counter 8/14/2008 Dosimetry Office Whole Body Counter 1/22/2009 HP-DS-064 Tool Monitor 7/08/2008 HP-DS-065 Tool Monitor 2/27/2008 HP-DS-068 Tool Monitor 7/08/2008 HP-DS-075 Personnel Contamination Monitor 7/09/2008 HP-DS-034 Personnel Contamination Monitor 8/18/2008 HP-DS-034 Personnel Contamination Monitor 8/18/2008 HP-DS-067 PM-7 3/24/2008 HP-DS-056 PM-7 7/30/2008 HP-DS-057 PM-7 3/27/2008
Corrective Action Documents
WF3-2007-00650 WF3-2007-01321 WF3-2007-01626 WF3-2007-01658 WF3-2007-01974 WF3-2007-02238 WF3-2007-02317 WF3-2007-02466 WF3-2007-02505 WF3-2007-02609 WF3-2007-03180 WF3-2007-03293 WF3-2007-03343 WF3-2007-03707 WF3-2007-04463 WF3-2008-00003 WF3-2008-00351 WF3-2008-00462 WF3-2008-00757 WF3-2008-01162 WF3-2008-01312 WF3-2008-01323 WF3-2008-02572 WF3-2008-02681 WF3-2008-03021 WF3-2008-03179 WF3-2008-04870 WF3-2009-00003 WF3-2009-00130 WF3-2009-00196 WF3-2009-00244 WF3-2009-00957
Miscellaneous Documents
Instrument Failure Review Date Instrument Response Check Failure Review for RSO5 #8163 4/4/2008 Instrument Response Check Failure Review for RSO50E #HP-DR-45 4/4/2008 Instrument Response Check Failure Review for RSO50E #11669 4/4/2008
Breathing Air Quality Certificate of Analysis
Lot Number:
Date of Test Cascade System 43P0423501 8/23/2004 Cascade System AC00S301AB 10/28/2005 Compressed Air System, Main Control Room EBA 1/29/2009 Compressed Air System, Station Air 5212 1/29/2009 Compressed Air System, Electric Blast Yard 1/29/2009
A1-4 Attachment
Section 2PS1: Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems (IP71122.01)
Audits and Self-assessments
NUMBER TITLE QA-2-2007-2F3-1/
QA-6-2007-WF3-1 Chemistry/Effluents and Environmental Monitoring
Procedures NUMBER TITLE REVISION CE-003-509 Routine Filter Replacement and Grab Sampling on PIG Monitors and WRGMs 301 CE-003-512 Liquid Radioactive Waste Release Permit (Manual)
CE-003-513 Gaseous Radioactive Waste Release Permit (Manual)
301 CE-003-516 Calculation and Adjustment of Radiation Monitoring Setpoints
EN-CY-102 Laboratory Analytical Quality Control
Effluent Release Reports
NUMBER TITLE
GB2008-0001 Containment Purge Exhaust
GC2008-0010 Condenser Evacuation System Exhaust
LB2008-0035 Waste Condensate Tank B
Corrective Action Documents
WF3-2007-2799 WF3-2007-3454 WF3-2007-3697 WF3-2007-3698 WF3-2008-0405 WF3-2008-5093
Miscellaneous
2007 Annual Radioactive Effluent Release Report 2006 Annual Radioactive Effluent Release Report 2008 Quarterly Offsite Laboratory Analysis Reports Daily Quality Control Check - Counting room detectors 4 and 5
A1-5 Attachment Section 2PS2: Radioactive Material Processing and Transportation (IP71122.02)
Procedures NUMBER TITLE REVISION EN-RP-121
Radioactive Material Control
Radioactive Waste Management
Radioactive Shipping Procedure
Scaling Factors
RW-002-310
Storage of Radioactive Waste
Radioactive Waste Shipments
2007-1001 2007-1008 2007-1012 2008-1004 2008-3001
Corrective Action Documents
WF3-2007-00569 WF3-2007-03329 WF3-2007-04105 WF3-2007-04441 WF3-2008-01597 WF3-2008-02892 WF3-2008-04422 WF3-2009-00295 HQN-2007-00978 LO-WTHQN-200800104
Audits and Self-assessments
NUMBER TITLE QA-15-2007-WF3-1/
Effluent and Environmental Monitoring Programs QA-14-2007-WF3-2
Section 2PS3: Radiological Environmental Monitoring Program and Radioactive Material Control Program (IP71122.03)
Corrective Action Documents
WF3-2007-1495 WF3-2007-1698 WF3-2007-1809 WF3-2007-2002 WF3-2007-02299 WF3-2007-2970 WF3-2007-3317 WF3-2008-1383 WF3-2008-2709 WF3-2008-4214 WF3-2007-4727
Procedures
NUMBER TITLE REVISION UNT-005-014 Offsite Dose Calculation Manual
CE-003-522 Meteorological Data Collection and Processing
CE-003-523 Meteorological Monitoring Program
CE-003-525 REMP Evaluations and Reports
CE-003-526 Collection and Preparation of REMP Liquid Samples
CE-003-527 Collection and Preparation of Milk Samples
CE-003-528 Collection of Sediment Samples
CE-003-529 Collection of Vegetation Samples
A1-6 Attachment
Procedures
NUMBER TITLE REVISION CE-003-531 Collection and Preparation of REMP Air Samples
EN-CY-102 Laboratory Analytical Quality Control
EN-EV-116 Radiological Environmental Analytical Services
EN-RP-108 Radiation Protection Posting
EN-RP-121 Radioactive Material Control
EN-RP-143 Source Control
Audits and Self-assessments
NUMBER TITLE QA-2-2007-WF3-1/
Effluent and Environmental Monitoring Programs QA-6-2007-WF3-1
Miscellaneous Documents
2007 Radioactive Effluent Release Report 2007 and 2008 Interlaboratory Comparison Results 2008 Calibration Records for Environmental Air Samplers 2006 and 2007 Annual Radiological Environmental Monitoring Reports 2008 Land Use Census Data
Section 4OA5 Temporary Instruction 2515/173
Procedures NUMBER TITLE REVISION EN-CY-108 Monitoring of Nonradioactive Systems
EN-CY-109 Sampling and Analysis of Groundwater Monitoring Wells
EN-CY-113 Response to Contaminated Spill/Leaks
EN-DC-343 Buried Piping and Tanks inspection and Monitoring Program
Corrective Action Documents
HQN-2007-00677 HQNLO-2008-0048 RBS-2009-00780 HQN-2008-01055 HQN-2009-0113 WF3-2009-01021
Miscellaneous Documents
Nuclear Energy Institute 07-07 Industry Groundwater Protection Initiative - Final Guidance Document Site Hydrologic Assessment in Support of Entergy GPI: Waterford 3 Steam Electric Station, dated January 2007