February 7, 2008 James J. Sheppard, President and Chief Executive Officer STP Nuclear Operating Company P.O. Box 289 Wadsworth, Texas 77483 SUBJECT: SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION - NRC

RADIATION SAFETY TEAM INSPECTION REPORT 05000498/2008006 AND 05000499/2008006

Dear Mr. Sheppard: On January 17, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your South Texas Project Electric Generating Station, Units 1 and 2. The enclosed Radiation Safety Team inspection report documents the inspection findings which were discussed with Mr. Ken Coates, Plant General Manager, and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission’s 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 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 This inspection report documents one NRC-Identified, noncited violation of very low safety significance (Green). If you contest this noncited violation or its significance, 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 76011-4005; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington DC 20555-001; and the NRC Resident Inspector at the South Texas, Units 1 and 2.

UNITED STATES

NUCLEAR REGULATORY COMMISSIONR E GI ON I V

611 RYAN PLAZA DRIV E, SUITE 400ARLINGTON, TEXAS 76011-4005

STP Nuclear Operating Company

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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 NRC’s 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/ Michael P. Shannon, Chief Plant Support Branch Division of Reactor Safety Dockets: 50-498 50-499 Licenses: NPF-76 NPF-80 Enclosure: NRC Inspection Report 05000498/2008006 and 05000499/2008006 w/Attachment: Supplemental Information cc w/enclosure: E. D. Halpin Site Vice President STP Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483 Ken Coates Plant General Manager STP Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483 S. M. Head, Manager, Licensing STP Nuclear Operating Company P.O. Box 289, Mail Code: N5014 Wadsworth, TX 77483

STP Nuclear Operating Company - 3 -

C. T. Bowman General Manager, Oversight STP Nuclear Operating Company P.O. Box 289 Wadsworth, TX 77483 Marilyn Kistler Sr. Staff Specialist, Licensing STP Nuclear Operating Company P.O. Box 289, Mail Code 5014 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 J. J. Nesrsta/R. K. Temple/ E. Alercon/Kevin Pollo City Public Service Board P.O. Box 1771 San Antonio, TX 78296 Jon C. Wood Cox Smith Matthews 112 E. Pecan, Suite 1800 San Antonio, TX 78205 Steve Winn/Christine Jacobs/ A. H. Gutterman, Esq. Morgan, Lewis & Bockius 1111 Pennsylvania Avenue NW Washington, DC 20004 Director, Division of Compliance & Inspection Bureau of Radiation Control Texas Department of State Health Services 1100 West 49th Street Austin, TX 78756 Brian Almon Public Utility Commission William B. Travis Building P.O. Box 13326 1701 North Congress Avenue Austin, TX 78701-3326

STP Nuclear Operating Company - 4 -

Environmental and Natural Resources Policy Director P.O. Box 12428 Austin, TX 78711-3189 Judge, Matagorda County Matagorda County Courthouse 1700 Seventh Street Bay City, TX 77414 Anthony Jones, Chief Inspector Texas Department of Licensing and Regulation Boiler Program P.O. Box 12157 Austin, TX 78711 Susan M. Jablonski Office of Permitting, Remediation and Registration Texas Commission on Environmental Quality MC-122, P.O. Box 13087 Austin, TX 78711-3087 Ted Enos 4200 South Hulen Suite 422 Fort Worth, TX 76109 Eddy Daniels/Marty Ryan NRG Energy, Inc. 211 Carnegie Center Princeton, NJ 08540 INPO Records Center 700 Galleria Parkway Atlanta, GA 30339-3064 Lisa R. Hammond, Chief Technological Hazards Branch National Preparedness Division FEMA Region VI 800 N. Loop 288 Denton, TX 76209

STP Nuclear Operating Company - 5 -

Electronic distribution by RIV: Regional Administrator (EEC) DRP Director (DDC) DRS Director (RJC1) DRS Deputy Director (ACC) Senior Resident Inspector (JLD5) Branch Chief, DRP/A (CEJ1) Senior Project Engineer, DRP/A (TRF) Team Leader, DRP/TSS (CJP) RITS Coordinator (MSH3) DRS STA (DAP) D. Pelton, OEDO RIV Coordinator (DLP) ROPreports STP Site Secretary (HLW1) Sunsi Review Completed: Yes ADAMS: ■ Yes □ No Initials: mps ■ Publicly Available □ Non-Publicly Available □ Sensitive ■ Non-Sensitive RIV:DRS/PSB PSB PSB PSB C:PSB LCCarsonII GLGuerra DCGraves BDBaca DLStearns /RA/ /RA/ /RA/ /RA/ /RA/ 1/28/08 2/6/08 1/29/08 2/5/08 1/28/08 C:PSB C:DRP/A C:PSB MPShannon CEJohnson MPShannon /RA/ /RA/ /RA/ 2/7/08 2/7/08 2/7/08 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

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U.S. NUCLEAR REGULATORY COMMISSION REGION IV

Dockets: 50-498, 50-499 Licenses: NPF-76, NPF-80 Report No: 05000498/2006008 and 05000499/2006008 Licensee: STP Nuclear Operating Company Facility: South Texas Project Electric Generating Station, Units 1 and 2 Location: FM 521 - 8 miles west of Wadsworth,

Wadsworth, Texas 77483 Dates: January 14 - 17, 2008 Inspectors: L. C. Carson II, Senior Health Physicist - Team Leader

B. D. Baca, Health Physicist D. C. Graves, Health Physicist G. L. Guerra, Health Physicist, CHP D. L. Stearns, Health Physicist

Approved By: Michael P. Shannon, Chief

Plant Support Branch Division of Reactor Safety

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SUMMARY OF FINDINGS IR 05000498/2008006, 05000499/2008006; 01/14/08 – 01/17/08; South Texas Project Electric Generating Station; Access Control for Radiologically Significant Areas, Radiation Monitoring Instrumentation and Protective Equipment; Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems; and Radiological Environmental Monitoring Program and Radioactive Material Control Program The report covered a 1-week period of inspection on site by a team of five region-based health physics inspectors. Based upon the results of the inspection, the team identified one NRC-Identified violation of very low safety significance (Green). 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 (OS)

• Green. The team identified a noncited violation of 10 CFR 20.1902(a) because the licensee failed to conspicuously post a radiation area in the radwaste storage yard with a sign or signs bearing the radiation symbol and the words "Caution, Radiation Area." The licensee had posted radiation area signs only at the entrances to the outdoor radwaste storage yard, instead of a discrete radiation area within the yard. The outdoor radwaste storage yard is a large area that, with the exception of this one area, had radiation levels measuring less than 2 millirem per hour. However, the general area dose rate in the unposted discrete radiation area was as high as 10 millirems per hour. As corrective action, the licensee posted the discrete areas. Additional corrective action is still being evaluated under Condition Report 08-0887.

The finding was greater than minor because it was associated with one of the cornerstone attributes (exposure control and monitoring) and the finding affected the Occupational Radiation Safety cornerstone objective, in that, workers could receive unexpected radiation dose. Using the Occupational Radiation Safety Significance Determination Process, the team determined that the finding was of very low safety significance because it did not involve: (1) ALARA planning and controls, (2) an overexposure, (3) a substantial potential for overexposure, or (4) an impaired ability to assess dose. Also, this finding had a cross-cutting aspect in the area of human performance related to the component of decision making because management did not adopt conservative assumptions in implementing regulatory requirements to decrease the

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likelihood of radiation workers receiving unintended dose (H1.b)(Section 2OS1).

B. Licensee-Identified Violations

None

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Report Details 2. RADIATION SAFETY

Cornerstones: Occupational Radiation Safety [OS] and Public Radiation Safety [PS]

2OS1 Access Control To Radiologically Significant Areas (71121.01) a. Inspection Scope

This area was inspected to assess the licensee's performance in implementing physical and administrative controls for airborne radioactivity areas, radiation areas, high radiation areas, and worker adherence to these controls. The team used the requirements in 10 CFR Part 20, the technical specifications, and the licensee's procedures required by technical specifications as criteria for determining compliance. During the inspection, the team interviewed the radiation protection manager, radiation protection supervisors, and radiation workers. The team performed independent radiation dose rate measurements and reviewed the following item:

• Controls (surveys, posting, and barricades) of radiation areas

The team completed one of the required 21 samples.

b. Findings

Introduction. A Green noncited violation of 10 CFR 20.1902(a) was identified for the failure to conspicuously post a discrete radiation area in the radwaste storage yard with a sign or signs bearing the radiation symbol and the words "Caution, Radiation Area."

Description. On January 16, 2008, the team identified an unposted radiation area in walkways while touring the Unit-1 radwaste storage yard. The general area dose rate in the discrete area of concern measured as high as 10 mrem per hour. The licensee had posted radiation area signs only at the entrances to the outdoor radwaste storage yard, instead of at the discrete radiation area within the radwaste facility. The radwaste storage yard was a large area that, with the exception of this one area, had general area radiation levels measuring less than 2 millirem per hour.

Analysis. The team reviewed the applicable guidance in NUREG/CR-5569, Revision 1, Health Physics Positions 036, "Posting of Entrances to a Large Room or Building as a Radiation Area," and 066, "Guidance for Posting Radiation Areas." Because the radwaste storage yard was a large area and most of it was not a radiation area, the team concluded that posting only the entrances to the area, rather than the discrete area, was not sufficient to inform radiation workers of radiological hazards in their work areas.

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The failure to post the discrete radiation area is a performance deficiency. The finding was greater than minor because it was associated with one of the cornerstone attributes (exposure control and monitoring) and the finding affected the Occupational Radiation Safety cornerstone objective, in that, workers could receive unexpected radiation dose. Using the Occupational Radiation Safety Significance Determination Process, the team determined that the finding was of very low safety significance because it did not involve: (1) ALARA planning and controls, (2) an overexposure, (3) a substantial potential for overexposure, or (4) an impaired ability to assess dose. Also, this finding had a cross-cutting aspect in the area of human performance related to the component of decision making because management did not adopt conservative assumptions in implementing regulatory requirements to decrease the likelihood of radiation workers receiving unintended dose.

Enforcement. Part 20.1003 of Title 10 of the Code of Federal Regulations defines a radiation area as an area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 5 millirem in an hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates. Part 20.1902(a) of Title 10 of the Code of Federal Regulations states that the licensee shall post each radiation area with a conspicuous sign or signs bearing the radiation symbol and the words "Caution, Radiation Area." However, on January 16, 2008, the team identified a discrete radiation area in the radwaste storage yard that was not conspicuously posted. As corrective action, the licensee posted the discrete areas. Additional corrective action is still being evaluated. Because the failure to conspicuously post the radiation area was determined to be of low safety significance and entered into the licensee's corrective action program as Condition Report CR 08-0887, this violation is being treated as an noncited consistent with Section VI.A of the NRC Enforcement Policy: NCV 05000498/2008006-01, Failure to Conspicuously Post a Radiation Area.

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 (SCBA) to workers. The team used the requirements in 10 CFR Part 20 and the licensee’s 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

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• 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

• Licensee event reports, audits and self-assessments

• 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 licensee’s capability for refilling and transporting SCBA air bottles to

and from the control room and operations support center during emergency conditions, status of SCBA staged and ready for use in the plant and associated surveillance records, and personnel qualification and training

• Qualification documentation for onsite personnel designated to perform

maintenance on the vendor-designated vital components, and the vital component maintenance records for SCBA units

The inspection team completed nine of the required nine samples. 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

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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 (ODCM), 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;

• Changes to the liquid or gaseous radioactive waste system design,

procedures, or operation as described in the Updated Final Safety Analysis Report;

• Changes to the ODCM 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 QA 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;

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• 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 (HEPA and charcoal filtration) including the methodology to determine the stack and vent flow rates;

• The identification of non-radioactive systems that have become

contaminated; • 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 characteristics used in the ODCM and effluent dose calculations including a selection of monthly, quarterly, and annual dose calculations;

• The land-use census;

• The implementation of the voluntary NEI/Industry Ground Water

Protection Initiative (GPI); • Records of abnormal gaseous or liquid discharges 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;

• Routine groundwater monitoring results;

• Self-assessments, audits, and licensee event reports; • 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 licensee’s program of problem identification and resolution, including:

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• 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.

The inspection team completed three of the required three samples. 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

• Licensee event reports, special reports, audits, state agency reports, self-assessments and corrective action reports performed since the last inspection

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The inspection team completed six of the required six samples. 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 licensee’s 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 licensee’s 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

• Selected air sampling and thermoluminescence dosimeter monitoring

stations

• Collection and preparation of environmental samples

• Operability, calibration, and maintenance of meteorological instruments

• Each event documented in the Annual Environmental Monitoring Report which involved a missed sample, inoperable sampler, lost thermoluminescence dosimeter, or anomalous measurement

• Significant changes 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

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• 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

• Licensee event reports, special reports, audits, self-assessments and

corrective action reports performed since the last inspection The inspection team completed ten of the required ten samples. 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 licensee’s 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 No findings of significance were identified.

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4OA6 Management Meetings Exit Meeting Summary

On January 17, 2008, the team presented the inspection results to Mr. K. Coates, Plant General Manager, 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

A-1 Attachment

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT Licensee personnel A. Barnett, Instrumentation/Monitoring System Engineer T. Bowman, General Manager Oversight W. Bullard, Manager, Health Physics K. Coates, Plant General Manager L. Earls, Instrumentation Health Physicist T. Frawley, Manager, Plant Protection R. Gangluff, Manager, Chemistry, Environmental and Health Physics M. Ghrist, System Engineer C. Grantom, Manager, PRA E. Hardcastle, Technician, Radiation Protection S. Head, Manager, Licensing R. Jones, Metrology Specialist J. Mertink, Manager, Operations H. Murray, Manager, Maintenance M. Murray, Manager, Systems Engineering A. Passafuma, Technician, Radiation Protection G. Powell, Manager, Site Engineering K. Reynolds, Chemist R. Savage, Engineer Licensing Staff Specialist D. Scoggins, Supervisor, Metrology Laboratory J. Sepulveda, Supervisor, Radiation Protection D. Sherwood, Supervisor, Radiation Protection T. Sullivan, Senior Material Shipper, Radiation Protection M. Tomek, Supervisor, Radiation Protection D. Towler, Manager Quality G. Williams, REMP / Dosimetry Health Physicist, Radiation Protection NRC J. Dixon, Senior Resident Inspector

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Opened and Closed During this Inspection 05000498/2008006-01 NCV Failure to Conspicuously Post a

Radiation Area. (Section 2OS1) Previous Items Closed NONE

A-2 Attachment

Previous Items Discussed NONE

LIST OF DOCUMENTS REVIEWED Section 2OS1: Access Control To Radiologically Significant Areas Procedures 0PGP03-ZR-0050 Radiation Protection Program, Revision 8 0PGP03-ZR-0051 Radiological Access and Work Controls, Revision 21 0PRP04-ZR-0004 Release of Materials From Radiologically Controlled Areas,

Revision 13 0PRP04-ZR-0015 Radiological Posting and Warning Devices, Revision 22 Section 2OS3: Radiation Monitoring Instrumentation and Protective Equipment Procedures 0PRP02-ZR-0006 TLD Issue and Collection, Revision 7 0PGP03-ZR-0054 Respiratory Protection Program, Revision 12 0PRP06-ZR-0002 Respiratory Protection Equipment Issue and Return, Revision 16 0PRP06-ZR-0005 Maintenance, Inspection, and Storage of Respiratory Protection

Equipment, Revision 10 0PRP06-ZR-0008 Air Quality Evaluation for Compressors or Pressurized Gas

Cylinders, Revision 3 0PSP05-RA-8010B MAB Unit Vent Wide Range Gas Monitor Calibration

(RT-8010B), Revision 9 0PSP05-RA-8038 Liquid Waste processing System No. 1 Monitor Calibration

(RT-8038), Revision 8 0PSP05-WL-4078 Plant Liquid Waste Discharge Flow Calibration (F-4078)

Revision 3 0PTP04-ZC-0043 Calibration of Radiological Meters and Ion Chambers, Revision 12 0PTP04-ZC-0049 Calibration of Geiger Counters and Micro R/Hr Meters, Revision 1 0PRP02-ZR-0011 Calibration of WBC System, Revision 3 0PMP08-RA-0052 Primary Calibration Gas Detectors (RD-52), Revision 0 0PSP02-RA-8033 Control Room/EAB Ventilation Radiation Monitor DCOT,

Revision 8 0PSP05-RA-8050 RCB High Range Area Monitor Calibration, Revision 6 Calibration Records 0PRP02-ZR-0011 Calibration of WBC System Accuscan 7/19/06 0PRP02-ZR-0011 Calibration of WBC System Accuscan 8/22/05 0PRP02-ZR-0011 Calibration of WBC System Quicky 8/22/05

A-3 Attachment

0PRP02-ZR-0011 Calibration of WBC System Quicky 7/8/06 0PRP02-ZR-0011 Calibration of WBC System Accuscan 7/11/07 0PRP02-ZR-0011 Calibration of WBC System Quicky 7/11/07 0PSP05-RA-8010B MAB Unit Vent Wide Range Gas Monitor Calibration

(RT-8010B), Revision 9 9/25/07 0PSP05-RA-8050 Unit 2 RCB High Range Area Monitor Calibration 10/4/05 0PSP05-RA-8050 Unit 2 RCB High Range Area Monitor Calibration 4/16/07 0PMP08-RA-0052 Primary Calibration Gas Detectors (RD-52) 9/17/07 0PSP05-RA-8012 Unit 2 RCB Purge isolation Radiation Monitor Calibration 2/8/06 0PSP05-RA-8012 Unit 2 RCB Purge isolation Radiation Monitor Calibration 10/18/07 0PSP05-RA-8035 Unit 1 Spent Fuel Pool Exhaust Radiation Monitor Calibration

8/24/05 0PSP05-RA-8033 Unit 2 Control Room/EAB Ventilation Radiation Monitor

Calibration 8/24/05 0PSP05-RA-8033 Unit 2 Control Room/EAB Ventilation Radiation Monitor

Calibration 8/20/07 0PSP05-RA-8033 Unit 2 Control Room/EAB Ventilation Radiation Monitor

Calibration 5/30/07 0PSP05-RA-8038 Unit 1 Liquid Waste processing System No. 1 Monitor Calibration

(RT-8038) 2/19/07 0PSP05-RA-8035 Unit 1 Spent Fuel Pool Exhaust Radiation Monitor Calibration

9/11/07 EQ ID 155-00127-001 Small Article Monitor Calibration S/N 214 3/9/07 EQ ID 155-00095-002 Portal Monitor Calibration (PM-7) S/N 259 11/14/07 Condition Reports 06-1582 06-5338 06-7168 06-7899 07-1107 07-1954 07-3112 07-5426 07-7425 07-11864 07-15115 08-1030 Audits and Self Assessments NUPIC Audit No. 19518, General Atomics Electronics Systems Inc., February 17, 2006 NUPIC Audit No. PA-06-13, December 12, 2006 Quality Monitoring Report (MN-06-0-15150) Quality Monitoring Report (MN-06-0-16367) Quality Monitoring Report (MN-06-0-20209) Quality Audit Report 06-01, RC, Radiological Controls/Radwaste/REMP Program,

March 21, 2006 Miscellaneous Whole Body Counter Radioactive Source Certificate Listing of SCBA Certified and Qualified Personnel, January 8, 2008 Air Quality Records for breathing air compressors, November 15, 2007 General Employee Training - Respiratory Protection January 15, 2008

A-4 Attachment

Section 2PS1: Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems Procedures 0PCP07-ZS-0010 Waste Monitor Tank Sampling, Revision 2 0PCP07-ZS-0016 Continuous Atmospheric Monitors, Revision 30 0PCP09-ZR-0004 Determination of Radionuclides by Gamma Spectroscopy,

Revision 19 0PEP05-ZH-0010 MAB, RCB, and TSC HVAC Adsorbent Test, Revision 9 0PEP05-ZH-0012 EOF Air Cleaning Unit, Revision 2 0POP02-WL-0005 Waste Monitor Tank Operations, Revision 16 0POP02-WL-0100 Liquid Waste Release, Revision 11 0PSP07-VE-0002 Gaseous Effluent Sampling and Analysis, Revision 11 0PSP07-WL-LDP1 Liquid Effluent Permit, Revision 11 0PSP11-HF-0001 FHB Exhaust Filter Airflow Capacity Test, Revision 8 0PSP11-ZH-0008 CRE and FHB HVAC In-Place HEPA Filter Leak Test, Revision 13 0PSP11-ZH-0009 EAB and FHB HVAC In-Place Adsorbent Leak Test, Revision 19 Condition Reports 06-03826 06-07821 06-07966 06-16854 07-01954 07-02353 07-05326 07-06747 07-10254 07-10275 07-10986 07-11044 07-11152 07-11219 07-11864 Audits and Surveillance Quality Audit Report 06-01 (RC), Radiological Controls/Radwaste/REMP Program Release Permits Gas: 143 Unit 1 Unit Vent March 2006

173 Unit 2 Unit Vent October 2006 180 Unit 1 Unit Vent February 2007 208 Unit 2 Unit Vent August 2007

Liquid: 885 Unit 2 Waste Monitor Tank 2E March 1, 2006 960 Unit 1 Waste Monitor Tank 1F August 31, 2006

991 Unit 1 Waste Monitor Tank 1E October 26, 2006 1085 Unit 2 Waste Monitor Tank 2F April 20, 2007 1165 Unit 2 Waste Monitor Tank 2F January 15, 2008

Release permits with liquid effluent monitor inoperable: Liquid: 1004 Unit 2 Waste Monitor Tank 2D November 11, 2006

1005 Unit 2 Waste Monitor Tank 2D November 11, 2006 1111 Unit 2 Waste Monitor Tank 2D July 4, 2007

A-5 Attachment

Other Documents Offsite Dose Calculation Manual, Revision 15 4th Quarter Measurement Assurance Program Sample Results 2006 1st Quarter Measurement Assurance Program Sample Results 2007 3rd Quarter Measurement Assurance Program Sample Results 2007 2006 Environmental Operating Report 2006 Radioactive Effluent Release Report Section 2PS2: Radioactive Material Processing and Transportation Corrective Action Documents (Condition Reports) 06-04604 06-04179 06-13709 06-13769 06-16863 07-02044 07-02901 07-03169 07-04006 07-07568 07-07778 07-08672 07-10857 07-15915 07-16986 Audits and Self-Assessments Quality Monitoring Reports MN-06-1-19794 MN-06-1-19796 MN-06-1-20066 MN-06-1-20086 MN-06-1-20327 MN-06-2-16945 MN-07-0-21746 MN-07-1-22634 MN-07-0-27671 Procedures 0PGP03-ZO-0017 Radioactive Waste Process Control Program, Revision 5 0PRP03-ZR-0002 Radioactive Waste Shipments, Revision 18 0PRP03-ZR-0012 Processing, Tracking and Loading of Spent Radioactive Filters

Revision 6 0PRP03-ZR-0011 Shipment of Radioactive Material, Revision 14 0PRP03-ZR-0001 Determination of Radioactive Material Curie Content,

Reportability, DOT Sub-Type and Waste Classification Revision 8 0PRP03-ZR-0009 10CFR61 Sampling and Analysis Program, Revision 7 0PRP03-ZR-0010 Dry Active Waste Program, Revision 113 Section 2PS3: Radiological Environmental Monitoring Program and Radioactive Material Control Program Corrective Action Documents (Condition Reports) 03-16708 06-01056 06-03826 06-10548 06-11370 06-11394 06-12527 06-12869 06-14434 06-14639 06-14706 06-14779 06-15217 07-03236 07-03246 07-05356 07-06747 07-09083

A-6 Attachment

Calibration Records HPGe Detector #1: EAR1-0 (08/31/06, 02/24/05); COMP-0 (01/30/06, 10/13/05) HPGe Detector #2: WAT4-0 (02/23/06); FILT-0 (10/05/05) HPGe Detector #4: FLES-0 (01/31/06, 02/23/05); BIO1-0 (01/31/06, 03/01/05); and CART-0 (01/25/06, 10/14/05) Liquid Scintillation and Tennelec beta/alpha counter Radeco air flow calibrators: 400-00136-005 (08/22/07) and 400-00136-006 (01/02/08) Procedures 0PGP03-ZR-0039 Radiological Environmental Monitoring Program, Revision 14 0PGP03-ZR-0050 Radiation Protection Program, Revision 9 0PGP03-ZR-0053 Radioactive Material Control Program, Revision 13 0PRP10-ZL-0023 REMP Interlaboratory Comparison Program, Revision 10 0PRP10-ZL-0029 NEI/NIST Measurement Assurance Program, Revision 1 0PRP10-ZL-0030 Interlaboratory Radioassay Measurement Assurance Program,

Revision 1 0PRP10-ZO-0002 Operation and Calibration of the Tennelec Counter System,

Revision 6 0PRP10-ZO-0003 Operation and Calibration of the Radiological Laboratory’s

Gamma Counting System, Revision 14 0PRP10-ZO-0004 Operation and Calibration of the Liquid Scintillation Systems,

Revision 8 0PRP10-ZU-0007 Environmental TLD Monitoring, Revision 10 0PRP10-ZU-0030 REMP Sample Collection, Revision 5 Miscellaneous 2005 and 2006 South Texas Project Annual Environmental Operating Report 2005, 2006, and 2007 1st, 2nd, and 3rd Quarters STPNOC MAP Report Packages Environmental Air Sample Log Sheet for 01/08-15/08 Gamma Detector Source Check Graphs Gamma System Stability Tests (Daily Quality Control) REMP Instrument Maintenance Logs RL Instrument Maintenance Logs