IR 05000416/2003009

IR 05000416-03-009, on 11/10/03 - 11/13/03, Grand Gulf Unit 1, Radiation Safety Team

ML033560293
Person / Time
Site:	Grand Gulf
Issue date:	12/18/2003
From:	Troy Pruett Plant Support Branch Region IV
To:	Gerald Williams Entergy Operations
References
IR-03-009
Download: ML033560293 (18)

Text

ber 18, 2003

SUBJECT:

GRAND GULF NUCLEAR STATION - NRC RADIATION SAFETY TEAM INSPECTION REPORT 05000416/2003009

Dear Mr. Williams:

On November 13, 2003, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Grand Gulf Nuclear Station. The enclosed Radiation Safety Team inspection report documents the inspection findings, which were discussed at the conclusion of the inspection with you and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

The team reviewed selected procedures and records, observed activities, and interviewed personnel. Specifically, the team evaluated the inspectable areas within the Radiation Protection Strategic Performance Area that are scheduled for review every two years. These areas are:

• Radiation Monitoring Instrumentation

• Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems

• Radioactive Material Processing and Transportation

• Radiological Environmental Monitoring Program and Radioactive Material Control Program Based on the results of this inspection, no findings of significance were identified.

In accordance with 10 CFR 2.790 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 Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Entergy Operations, Inc. -2-Should you have any questions concerning this inspection, we will be pleased to discuss them with you.

Sincerely,

//RA//

Troy W. Pruett, Chief Plant Support Branch Division of Reactor Safety Docket: 50-416 License: NPF-29

Enclosure:

Inspection Report 05000416/2003009 w/Attachment: Supplemental Information

REGION IV==

Docket: 50-416 License No.: NPF-29 Report No.: 05000416/2003009 Licensee: Entergy Operations, Inc.

Facility: Grand Gulf Nuclear Station (GGNS)

Location: Waterloo Road Port Gibson, Mississippi 39150 Dates: November 10-13, 2003 Inspectors: Larry T. Ricketson, P.E., Senior Health Physicist Michael P. Shannon, Senior Health Physicist Bernadette D. Baca, Health Physicist Daniel R. Carter, Health Physicist Accompanying Binesh K. Tharakan, Health Physicist, Plant Support Inspector:

Approved By: Troy W. Pruett, Chief Plant Support Branch Division of Reactor Safety Enclosure

SUMMARY OF FINDINGS

IR 05000416/2003-009; 11/10/03 - 11/13/03; Grand Gulf Nuclear Station; Radiation Safety

Team.

The report covered a one week period of inspection on site by a team of four region-based health physics inspectors. No findings of significance were identified.

REPORT DETAILS

RADIATION SAFETY

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

[PS] 2OS3 Radiation Monitoring Instrumentation (71121.03)

a. Inspection Scope

This area was inspected to determine the accuracy and operability of radiation monitoring instruments used for the protection of occupational workers and the adequacy of the program to provide self-contained breathing apparatus (SCBA) to personnel entering unknown atmospheres. The team conducted an in-office review of the licensees applicable audits, self-assessments, and corrective action documents related to the radiation monitoring instrumentation and SCBA programs. On site, the team interviewed cognizant licensee personnel and compared the following items with regulatory and procedural requirements and commitments in the Updated Final Safety Analysis Report:

• Calibration, operability, and alarm setpoint of selected area radiation monitors and emergency assessment instrumentation (control room ventilation radiation monitor and containment building post-accident monitor)

• Calibration and operability of portable radiation detection instrumentation used for job coverage of high radiation area work, whole-body counters, and personnel contamination monitors

• Calibration expiration and source response check currency on portable radiation detection instruments staged for use

• The status of self-contained breathing apparatuses staged and ready for use in the plant and associated surveillance and maintenance records

• 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

• Training and qualifications of personnel who may use self-contained breathing apparatus during an emergency (control room operators and emergency response personnel), perform maintenance and repair of self-contained breathing apparatus, and refill air bottles

• Periodic air cylinder hydrostatic testing results

• Licensee self-assessments and audits related to the radiation monitoring instrumentation and self-contained breathing apparatuses

• Summary of corrective action documents written since the last inspection and selected documents related to radiation monitoring instruments, self-contained breathing apparatus equipment, repetitive, and significant individual deficiencies The team completed all nine of the required samples in this inspection area.

b. Findings

No findings of significance were identified.

2PS1 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems (71122.01)

a. Inspection Scope

This area was inspected to ensure that the gaseous and liquid effluent processing systems were maintained so that radiological releases were properly mitigated, monitored, and evaluated with respect to public exposure. The team conducted an in-office review of the licensees annual reports, self-assessments, and corrective action documents. On site, the team examined procedures and representative records; walked down the major components of the radwaste, fuel handling area, containment, and turbine building gaseous and the liquid effluent release systems; and interviewed cognizant personnel. The team observed sample preparation, collection, and analysis of gaseous effluent from the fuel handling area exhaust and the offgas post-treatment monitor for compliance with procedural and regulatory requirements. Additionally, the following items were reviewed and compared with regulatory requirements and commitments in the Updated Final Safety Analysis Report:

• 2001 and 2002 Annual Radioactive Effluent Release Report

• Changes made in 2001 and 2002 to the Offsite Dose Calculation Manual and to the radioactive waste system design and operation

• Unplanned, monitored releases reported in the 2001 Radiological Effluent Release Report

• Effluent radiological occurrence performance indicator incidents (no occurrences during the inspection period)

• Effluent radiation monitor alarm setpoint values and calculation methodology

• Selected radioactive liquid waste and gaseous release permits and associated projected doses to members of the public

• Compensatory sampling and radiological analyses conducted for unmonitored releases and when effluent monitors were declared out-of-service

• Monthly, quarterly, and annual dose calculations

• Air cleaning system surveillance test results for the Control Room Ventilation and Fuel Handling Building Systems.

• Surveillance test results for vent flow rates

• Records of calibrations performed since the last inspection for the containment, fuel handing, and turbine building gaseous effluent radiation monitor and flow measurement devices

• Records of instrument calibrations performed since the last inspection for the liquid effluent radiation monitor

• Calibration records of counting room instrumentation associated with effluent monitoring and release activities

• Chemistry Department and Vendor interlaboratory comparison program and results

• Quality control records for the counting room instruments

• Audits and self-assessments related to the radioactive effluent treatment and monitoring program and the licensees ability to meet the Radiological Effluent Technical Specification/Offsite Dose Calculation Manual requirements

• Summary of corrective action documents written since the last inspection and selected documents related to the radioactive effluent treatment and monitoring program, the engineered-safety-feature air cleaning systems, repetitive, and significant individual deficiencies The team completed all ten of the required samples in this inspection area.

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 licensees 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 170-189. The team conducted an in-office review of the licensees annual reports, self-assessments, and corrective action documents. On site, the team interviewed radiation workers and radiation protection personnel involved in radioactive material processing and transportation activities and walked down the liquid and solid radioactive waste processing systems to verify that the current system configuration and operation agreed with the descriptions contained in the Updated Final Safety Analysis Report and in the Process Control Program. The team reviewed radioactive waste processing equipment that was not operational or abandoned in place for material condition, potential unmonitored release pathways, and unnecessary personnel exposure. Additionally, the following items were reviewed and compared with regulatory requirements:

• Waste stream determination and sampling procedures

• Radioactive waste transfer and sampling procedures and waste classification methodology

• Radio-chemical sample analysis results and changes to operational parameters affecting the results for each of the licensees radioactive waste streams

• Scaling factors and calculations used to account for difficult-to-measure radionuclides

• 10 CFR Part 20, Appendix G, quality assurance program

• Transport cask Certificates of Compliance (9208 and 9233)

• Transferee licenses (R-I2005-K01, R-24003-D05, and R-73013-F91)

• Procedures for cask loading and closure

• Training of personnel responsible for the conduct of radioactive waste processing and radioactive material shipment preparation activities

• Documentation for five non-excepted package shipments that demonstrated shipment packaging, surveying, labeling, marking, placarding, vehicle checks, emergency instructions, disposal manifest, shipping papers provided to the driver, and licensee verification of shipment readiness

• Changes to the radioactive waste processing systems since the last inspection (No changes were identified.)

• Audits and self-assessments related to the radioactive material and transportation programs performed since the last inspection

• Summary of corrective action documents written since the last inspection and selected documents involving the radioactive material and shipping programs, and repetitive and significant individual deficiencies No shipments of radioactive materials were conducted during the inspection. The team completed all six of the required samples in this inspection area.

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 determine whether the licensee had an adequate program to verify the impact of radioactive effluent releases to the environment and to ensure that the licensees surveys and controls were adequate to prevent the inadvertent release of licensed materials into the public domain. The team conducted an in-office review of the licensees applicable audits, self-assessments, and corrective action documents related to the radiological environmental monitoring program and the radioactive material control program. On site, the team interviewed members of the licensees staff responsible for implementing the radiological environmental, meteorological monitoring, and radioactive material control programs. The team observed the following activities and equipment with respect to the Technical Requirements Manual (TRM), Offsite Dose Calculation Manual (ODCM), Technical Specifications (TS), and regulatory requirements:

• Collection and preparation for shipment of airborne particulate, charcoal, and water samples for analysis at an off-site contract laboratory

• Meteorological instrumentation at the primary and back-up meteorological towers and data displays in the control room

• The survey of materials for release from the controlled access area

• Implementing procedures for the radiological environmental monitoring program

• Environmental sample analytical results

• Two environmental air sampling stations (AS-1 and AS-7, located in Emergency Planning Sectors G and H, respectively ) and six thermoluminescent dosimetry stations (M-07, M-60, M-22, M-21, M-16, and M-10 located in Emergency Planning Sectors G, G, G, J, A, and A, respectively) specified in the TRM

• Calibration and maintenance records for environmental air sampling equipment

• Calibration, maintenance, and quality control records for environmental sample measurement instrumentation

• 2001 land use census results and changes to the radiological environmental monitoring program (no changes where identified)

• 2001 and 2002 Annual Radiological Environmental Operating Report (GNRO-2003/00013 and GNRO-2002/00034, respectively)

• The contractor environmental laboratorys performance in the inter-laboratory comparison program

• Implementing procedures for the meteorological monitoring program

• Meteorological instrument operability, reliability, and annual meteorological data recovery

• Procedures, methods, and instruments used to survey, control, and release materials from the controlled access area

• Calibration procedures and records for instruments used to perform radiological surveys prior to material release

• Detection sensitivities and counting parameters of radiation survey instruments used for the release of potentially contaminated materials from the controlled access area

• Criteria used for the unrestricted release of potentially contaminated material from the controlled access area

• Audits and self-assessments related to the radiological environmental monitoring program and the radioactive material control program

• Summary of corrective action documents written since the last inspection and selected documents involving radiological environmental monitoring, meteorological monitoring, and release of radioactive material programs.

The team completed all ten of the required samples in this inspection area.

c. Findings

No findings of significance were identified.

4OA2 Problem Identification and Resolution

Sections 2OS3, 2PS1, 2PS2, and 2PS3 evaluated the effectiveness of the licensee's problem identification and resolution processes in the respective inspectable areas.

No findings of significance were identified.

4OA6 Management Meetings

Exit Meeting Summary

On November 13, 2003, the team presented the inspection results to Mr. G. Williams, Site Vice President, and other members of his staff who acknowledged the findings.

One proprietary document was reviewed by the team during the inspection but was not copied or retained.

ATTACHMENT

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

R. Benson, Supervisor, Radwaste

D. Cotton, Supervisor, Health Physics Operations

J. Hagood, Senior Health Physicist, Radiation Protection Department

M. Hurley, Meteorological Systems Engineer

D. Jackson, Health Physics/Chemistry Support Coordinator, Chemistry Department

J. Lassetter, Effluents Supervisor, Chemistry Department

F. Rosser, Supervisor, Health Physics

R. Shaw, Environmental Specialist, Chemistry

P.Stokes, Senior Specialist, Health Physics/Chemistry

R.Tolbert, Senior Specialist, Health Physics/Chemistry

J. Watts, Senior Specialist, Health Physics/Chemistry

R. Wilson, Superintendent, Radiation Protection

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened

NONE Opened and Closed During this Inspection NONE Previous Items

Closed

NONE Previous Items

Discussed

NONE