IR 05000416/2009009

IR 05000416-09-009; on 08/17/2009 - 08/21/2009; Grand Gulf Nuclear Station; Radiation Safety Team Inspection

ML092740225
Person / Time
Site:	Grand Gulf
Issue date:	09/30/2009
From:	Greg Werner NRC/RGN-IV/DRS/PSB-2
To:	Douet J Entergy Operations
References
FOIA/PA-2010-0209 IR-09-009
Download: ML092740225 (21)

Text

September 30, 2009

SUBJECT:

GRAND GULF NUCLEAR STATION - NRC RADIATION SAFETY TEAM INSPECTION REPORT 05000416/2009009

Dear Mr. Douet:

On August 21, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Grand Gulf Nuclear Station. The enclosed report documents the inspection findings, which were discussed at the conclusion of the inspection with you and other 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

Grand Gulf Nuclear Station

- 2 -

Docket: 50-416 License: NPF-29

Enclosure:

NRC Inspection Report 05000416/2009009 w/Attachment: Supplemental Information

REGION IV==

Dockets:

50-416

Licenses:

NPF-29

Report:

05000416/2009009

Licensee:

Entergy Operations, Inc

Facility:

Grand Gulf Nuclear Station

Location:

Waterloo Road Port Gibson, Mississippi 39150

Dates:

Inspectors:

August 17 through 21, 2009

Louis C. Carson II, Senior Health Physicist and Team Leader Larry T. Ricketson, P.E., Senior Health Physicist Donald L. Stearns, Health Physicist G. Michael Vasquez, Health Physicist

Accompanied By:

Approved By:

Casey C. Alldredge, Health Physicist (NSPDP)

Gregory E. Werner, Chief Plant Support Branch 2 Division of Reactor Safety

- 2 -

Enclosure SUMMARY OF FINDINGS

IR 05000416/2009007; 08/17/2009 - 08/21/2007; Grand Gulf Nuclear Station; 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

- 3 -

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;

- 4 -

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 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;

- 5 -

Enclosure

• Changes, if any, to the liquid or gaseous radioactive waste system design, procedures, or operation as described in the Updated Final Safety Analysis Report;

• Changes, if any, to the Office of Dose Calculation Manual made by the licensee since the last inspection;

• The annual effluent release reports since the previous inspection;

• The correlation between the effluent doses and the environmental monitoring results.

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 nonsafety 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 nonradioactive 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;

• A selection of monthly, quarterly, and annual dose calculations;

• 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

- 6 -

Enclosure notifications, and assessments and reporting of abnormal discharges in the Annual Radiological Effluent Release Report;

• Effluent sampling records.

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.

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;

• Radiochemical sample analysis results for radioactive waste streams and use of scaling factors and calculations to account for difficult-to-measure radionuclides;

- 7 -

Enclosure

Shipment packaging, surveying, labeling, marking, placarding, vehicle checking, driver instructing, and disposal manifesting;

• Shipping records for nonexcepted 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.

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;

- 8 -

Enclosure

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.

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:

- 9 -

Enclosure

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.

40A5 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;

- 10 -

Enclosure

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.

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. The licensee had addressed most of the audit findings. However, according to the Entergy self-assessment, the licensee needs to upgrade its site specific hydrogeological evaluations to better define groundwater flow characteristics and gradients. The inspection team found the licensee had not performed a new hydrogeologic study to determine the predominant ground water flow characteristics and gradient.

The licensee initiated Condition Report GGN-2009-01611 on March 26, 2009, to address the corporate audit findings.

4OA6 Management Meetings

Exit Meeting Summary

On September 21, 2009, the team presented the inspection results to R. Douet, 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

KEY POINTS OF CONTACT

D. Barfield, Director, Engineering R. Benson, Supervisor, Radioactive Waste E. Blush, Radiochemist R. Brevily, Health Physicist/Chemistry Specialist M. Causey, Maintenance Rule Engineer D. Coulter, Licensing Specialist R. Douet, Vice President, Operations A. Fox, Systems Engineer, System Engineering J. Hagood, Senior Health Physicist, Radiation Protection D. Jackson, Health Physicist/Chemistry Specialist M. Krupa, Director, Nuclear Safety and Assurance M. Larson, Senior Licensing Specialist M. Larson, Senior Licensing Specialist J. Lassetter, Supervisor, Chemistry C. Mason, Quality Assurance Auditor J. McClure, Radiochemist S. Osborn, Licensing C. Perino, Licensing Manager P. Rescheske, Senior Licensing Specialist F. Rosser, Supervisor, Radiation Protection R. Scarbrough, Superintendent, Chemistry P. Stokes, Radiation Protection Specialist W. Trichell, Radiation Protection Manager J. Watts, Radiation Protection Specialist M. Withrow, Supervisor, Reactor Engineering E. Wright, ALARA Specialist, Radiation Protection

NRC

R. Smith, Senior 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-121 Radioactive Material Control

EN-RP-143 Source Control

EN-RP-303 Source Checking of Radiation Protection Instrumentation

EN-RP-306 Calibration and Operation of the Eberline PM-7

EN-RP-307 Operation and Calibration of the Eberline Personnel Contamination Monitors

EN-RP-308 Operation and Calibration of Gamma Scintillation Tool Monitors

EN-RP-501 Respiratory Protection Program

EN-RP-502 Inspection and Maintenance of Respiratory Protection Equipment

EN-RP-503 Selection, Issue, and Use of Respiratory Equipment

EN-RP-504 Breathing Air

EN-RP-301 Radiation Protection Instrument Control

08-S-10-02 Calibration of Portable Area Radiation Monitors,

08-S-07-83 Operation and Calibration of the ND-9000 Whole Body Counter

08-S-10-04 Calibration of Portable Dose Rate Instrument

06-IC-1D21-R-1002 Containment/Drywell High Range Area Radiation Monitor, 105 06-IC-1D17-A-0013 GE Radioactive Gaseous Effluent Monitor 105 06-IC-SD17-A-1024 Liquid Radwaste Effluents Radiation Monitor Calibration, 102 06-IC-SG17-R-1001 Liquid Radwaste Effluent Flow Calibration 100 07-S-53-D21-1 Area Radiation Monitors Loop Calibration

06-1C-SD17-A-1026 Accident Range Monitor AXM-1 Calibration 107

A1-3 Attachment EFFLUENT MONITOR CALIBRATIONS

CHANNEL NO. MONITOR DESCRIPTION WORK ORDER PACKAGE DATE D17-A-1023 Component Cooling Water System Radiation Monitor 51675031 03/12/2009 D17-A-1026-02 Offgas & Radwaste Vent Radiation Monitor (AXM-1)

51803346 07/01/2009 D17-A-1026-03 Fuel Handling Area Vent Radiation Monitor 51699148 05/28/2009 D17-A-1026-04 Turbine Building Vent Monitor 51646847 08/27/2009

AREA MONITOR CALIBRATIONS

CHANNEL NO.

MONITOR DESCRIPTION WORK ORDER PACKAGE DATE D21-R-1001 Control Room Range Radiation Monitor 5169789 04/14/2009 D21-R-1002-B Containment/Drywell High Range Radiation Monitor 5169522 08/17/2009 D21-R-1003-A Fuel Pool Sweep Radiation Monitor 0011885501 5/09/2008 D21-K-0605 TIP Mechanism Radiation Monitor 00118857-01 5/09/2008

RADIATION PROTECTION INSTRUMENTATION CALIBRATIONS

IDENTIFICATION NO.

INSTRUMENT TYPE CALIBRATION TYPE 5097-073 AMP-100 Area Radiation Monitor 08/29/2007 CHP-ARM101 AMP-100 Area Radiation Monitor 04/13/2009 HP-DR-481 RO-20 Dose Rate Meter 08/19/2009 96-9508 Whole Body Counter 08/13/2009

CONDITION REPORTS (CR)

GGN-2007-04587 GGN-2007-04899 GGN-2007-05188 GGN-2007-05500 GGN-2007-05531 GGN-2007-05767 GGN-2007-05768 GGN-2007-05919 GGN-2008-00276 GGN-2008-00803 GGN-2008-01529 GGN-2008-02364 GGN-2008-03325 GGN-2008-03663 GGN-2008-04936 GGN-2008-05602 GGN-2008-06156 GGN-2008-07078 GGN-2009-00047 HQN-2009-00193 HQN-2009-00253 HQN-2009-00749 GGN-2009-02449 GGN-2009-02615 GGN-2009-02918

MISCELLANEOUS DOCUMENTS

Radiation Source Verification Log 10/17/2009 Model 89 400 Curie Cs-137 Source Calibration 05/12/2008

A1-4 Attachment Section 2PS1: Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems (IP71122.01)

PROCEDURES NUMBER TITLE REVISION 06-CH-1000-M-0049 Effluent Dose Calculations 104 06-CH-SG17-P-0041 Radwaste Release Pre-Release Analysis 106 06-CH-SG17-O-0045 Radwaste Release Post-Release Calculations 102 06-CH-1000-M-0059 31-Day Dose Projection 102 06-CH-iD17-W-0017 Gaseous Release Points Iodine, Tritium and Particulates 106 06-ME-1T48-R-0005 In-Place Testing of Standby Gas Treatment Filtration System 105 06-ME-1Z51-R-0006 In-Place Testing of Control Room Emergency Filtration System 107

AUDITS, SELF-ASSESSMENTS, AND SURVEILLANCES NUMBER TITLE DATE GLO-2008-0009 Chemistry Assessment for Public Radiation Performance Indicator (PR01)

February, 08 GLO-2009-00062 Radiological Effluent Technical Specifications (RETS)

/Radiological Environmental Monitoring Program (REMP)

June, 09

CONDITION REPORTS (CR)

GGN-2007-04587 GGN-2007-04652 GGN-2007-04843 GGN-2007-05746 GGN-2007-05768 GGN-2008-00318 GGN-2008-00502 GGN-2008-01248 GGN-2008-01529 GGN-2008-02855 GGN-2008-03325 CGN-2008-03929 GGN-2008-01410 GGN-2008-04198 CGN-2008-06268 CGN-2008-06275 GGN-2008-06571 CGN-2008-06888 CGN-2009-00047

RELEASE PERMITS NUMBER TITLE DATE 2008061 Gaseous Release, Turbine Building 7/15/08 2008130 Gaseous Release, Fuel Handling Area 12/19/08 2008244 Gaseous Release, Turbine Building 9/28/08 2009014 Liquid Release, EDST-A 2/12/09 2009057 Liquid Release, FDST-A 3/10/09

A1-5 Attachment

MISCELLANEOUS NUMBER TITLE REVISION /

DATE 51548166-01 Biannual Land Use Census 5/12/08 51687534-01 Surveillance Procedure, In-Place Testing of Standby Gas Treatment Filtration System 8/06/09 51797847-01 Surveillance Procedure, In-Place Testing of Standby Gas Treatment Filtration System 6/16/09 Radiation Protection Standards and Expectations Rev 44 2008 Annual Radioactive Effluent Release Report 2007 Annual Radioactive Effluent Release Report

Section 2PS2: Radioactive Material Processing and Transportation (IP71122.02)

PROCEDURES NUMBER TITLE REVISION /

DATE EN-RW-102 Radioactive Shipping Procedure

EN-RW-104 Scaling Factors

01-S-08-22 Operating Guidelines for the Use of Polyethylene High Integrity Containers

08-S-06-71 Sampling Procedures for Waste Classification

08-S-07-76 Cask Handling for the 10-142 Cask

AUDITS, SELF-ASSESSMENTS, AND SURVEILLANCES NUMBER TITLE DATE QA-15-2007-GGNS-1/

QA-14-2007-GGNS-2 Radwaste/Radiation Protection Quality Assurance Audit Report 10/22/07 -

2/22/08 LO # GLO-2009-0059 2009-RP Focused Assessment Radioactive Material Processing and Transportation May 18 - 21, 2009

NUCLEAR PROCUREMENT ISSUES COMMITTEE AUDITS NUMBER TITLE DATE 20127 WMG, Inc.

7/21/09 -7/25/08

CONDITION REPORTS

GGN-2007-05274 GGN-2008-00023 GGN-2008-1003 GGN-2008-06174

A1-6 Attachment

RADIOACTIVE MATERIAL SHIPMENTS NUMBER TITLE REVISION /

DATE 2007-0901 LSA-II - Waste Class B 9/04/07 2007-0902 Type B Package - Waste Class C 9/27/07 2007-1005 Type B Package - Waste Class C 10/11/07 2007-1008 Type B Package - Waste Class C 10/22/07 2007-1015 Type B Package - Waste Class C 10/30/07

MISCELLANEOUS TITLE DATE Waste Stream Sampling Analysis 2007 Waste Stream Sampling Analysis 2008 Radioactive Waste Packaging, Shipping and Disposal Training 2008 Radwaste Shipper Qualifications

Section 2PS3: Radiological Environmental Monitoring Program and Radioactive Material Control Program (IP71122.03)

CONDITION REPORTS (CR)

GGN-2007-04618 GGN-2007-05197 GGN-2007-05696 GGN-2008-00201 GGN-2008-00611 GGN-2008-00854 GGN-2008-02513 GGN-2008-02613 GGN-2008-02653 GGN-2008-02836 GGN-2008-02934 GGN-2008-04377 GGN-2008-04897 GGN-2008-04936 GGN-2008-05052 GGN-2009-01447 GGN-2009-01581 HQN-2007-00894 HQN-2008-00097 HQN-2008-00191 HQN-2008-00552 HQN-2008-00954 HQN-2009-00431

PROCEDURES

NUMBER TITLE REVISION 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, SELF-ASSESSMENTS, AND SURVEILLANCES NUMBER TITLE DATE GLO-2008-0009 Chemistry Assessment for Public Radiation Performance Indicator (PR01)

February, 08 GLO-2009-00062 Radiological Effluent Technical Specifications (RETS)

/Radiological Environmental Monitoring Program (REMP)

June, 09

A1-7 Attachment 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 /

DATE EN-CY-109 Sampling and Analysis of Groundwater Monitoring Wells

EN-CY-111 Radiological Ground Water Monitoring Program

EN-RP-113 Response to Contaminated Spills/Leaks

AUDITS, SELF-ASSESSMENTS, AND SURVEILLANCES NUMBER TITLE REVISION /

DATE HQNL0-2008-00008 CA-1 Fleet Self Assessment of the Ground Water Protection Initiative 8/25/08

CONDITION REPORTS

HQN-2006-00062 GGN-2009-01611

MISCELLANEOUS NUMBER TITLE REVISION /

DATE Entergy Nuclear Communications Plan for Groundwater Monitoring for Tritium and Other Unplanned Releases 7/25/06