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| issue date = 08/21/2007
| issue date = 08/21/2007
| title = IR 05000458-07-010; 07/09/2007 - 07/13/07; River Bend Station; Access Control to Radiologically Significant Areas; Radiation Safety Team
| title = IR 05000458-07-010; 07/09/2007 - 07/13/07; River Bend Station; Access Control to Radiologically Significant Areas; Radiation Safety Team
| author name = Shannon M P
| author name = Shannon M
| author affiliation = NRC/RGN-IV/DRS/PSB
| author affiliation = NRC/RGN-IV/DRS/PSB
| addressee name = Venable J E
| addressee name = Venable J
| addressee affiliation = Entergy Operations, Inc
| addressee affiliation = Entergy Operations, Inc
| docket = 05000458
| docket = 05000458
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:ust 21, 2007
[[Issue date::August 21, 2007]]


Joseph E. VenableSenior Vice President, Operations Entergy Operations, Inc.
==SUBJECT:==
RIVER BEND STATION - NRC RADIATION SAFETY TEAM INSPECTION REPORT 05000458/2007010


River Bend Station 5485 US Highway 61N St. Francisville, LA 70775
==Dear Mr. Venable:==
On July 13, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your River Bend 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.


SUBJECT: RIVER BEND STATION - NRC RADIATION SAFETY TEAM INSPECTIONREPORT 05000458/2007010
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.
 
==Dear Mr. Venable:==
On July 13, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection atyour River Bend 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 inspection examined activities conducted under your license as they relate to safety andcompliance 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
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:
*Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems
* Radiation Monitoring Instrumentation
*Radioactive Material Processing and Transportation  
* Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems
*Radiological Environmental Monitoring Program and Radioactive Material ControlProgram This inspection report documents one NRC-identified finding of very low safety significance(Green). However, because the finding was of very low safety significance and it was entered into your corrective action program, the NRC is treating this finding as a noncited violation consistent with Section VI.A of the NRC Enforcement Policy. If you contest the noncited violation in this report, 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 River Bend Station facility.
* Radioactive Material Processing and Transportation
* Radiological Environmental Monitoring Program and Radioactive Material Control Program This inspection report documents one NRC-identified finding of very low safety significance (Green). However, because the finding was of very low safety significance and it was entered into your corrective action program, the NRC is treating this finding as a noncited violation consistent with Section VI.A of the NRC Enforcement Policy. If you contest the noncited violation in this report, 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 River Bend Station facility.


Entergy Operations, Inc.-2-In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, itsenclosure, 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).
Entergy Operations, Inc. -2-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 Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


Sincerely,/RA/Michael P. Shannon, ChiefPlant Support Branch Division of Reactor SafetyDockets: 50-458Licenses: NPF-47
Sincerely,
/RA/
Michael P. Shannon, Chief Plant Support Branch Division of Reactor Safety Dockets: 50-458 Licenses: NPF-47


===Enclosure:===
===Enclosure:===
NRC Inspection Report 05000458/2007010
NRC Inspection Report 05000458/2007010 w/attachment: Supplemental Information


===w/attachment:===
REGION IV==
Supplemental Information cc:Executive Vice President and Chief Operating Officer Entergy Operations, Inc.
Docket: 50-458 License: NPF-47 Report: 05000458/2007010 Licensee: Entergy Operations, Inc.


P.O. Box 31995 Jackson, MS 39286-1995Vice President Operations Support Entergy Operations, Inc.
Facility: River Bend Station Location: 5485 U.S. Highway 61 St. Francisville, Louisiana Dates: July 9 - 13, 2007 Inspectors: Larry Ricketson, P.E., Senior Health Physicist, Plant Support Branch Louis C. Carson II, Senior Health Physicist, Plant Support Bernadette Baca, Health Physicist, Plant Support Branch Gilbert L. Guerra, C.H.P., Health Physicist, Plant Support Branch Donald L. Stearns, Health Physicist, Plant Support Branch Accompanied By: David C. Graves, Health Physicist, Plant Support Branch Approved By: Michael P. Shannon, Chief Plant Support Branch Division of Reactor Safety-1-  Enclosure


P.O. Box 31995 Jackson, MS 39286-1995General ManagerPlant Operations Entergy Operations, Inc.
=SUMMARY OF FINDINGS=
 
IR 05000458/2007010; 07/09/2007 - 07/13/07; River Bend Station; Access Control To
River Bend Station 5485 US Highway 61N St. Francisville, LA 70775Director, Nuclear Safety & LicensingEntergy Operations, Inc.
 
1340 Echelon Parkway Jackson, MS 39213-8298Manager, LicensingEntergy Operations, Inc.River Bend Station 5485 US Highway 61N St. Francisville, LA 70775The Honorable Charles C. Foti, Jr.Attorney General Department of Justice State of Louisiana P.O. Box 94095 Baton Rouge, LA 70804-9005H. Anne Plettinger3456 Villa Rose Drive Baton Rouge, LA 70806Bert Babers, PresidentWest Feliciana Parish Police Jury P.O. Box 1921 St. Francisville, LA 70775Richard Penrod, Senior Environmental Scientist, State Liaison Officer Office of Environmental Services Entergy Operations, Inc.-3-Northwestern State University Russell Hall, Room 201 Natchitoches, LA 71497Brian AlmonPublic Utility Commission William B. Travis Building P.O. Box 13326 1701 North Congress Avenue Austin, TX 78701-3326Jim CallowayPublic Utility Commission of Texas 1701 N. Congress Avenue Austin, TX 78711-3326Lisa R. Hammond, ChiefTechnological Hazards Branch National Preparedness Division FEMA Region VI 800 N. Loop 288 Denton, TX 76209 Entergy Operations, Inc.-4-Electronic distribution by RIV:Regional Administrator (BSM1)DRP Director (ATH)DRS Director (RJC1)DRS Deputy Director (WBJ)Senior Resident Inspector (MOM)Branch Chief, DRP/C (MCH2)Senior Project Engineer, DRP/C (WCW)Team Leader, DRP/TSS (CJP)RITS Coordinator (MSH3)DRS STA (DAP)M. Kunowski, OEDO RIV Coordinator (MAK3)D. Pelton, OEDO RIV Coordinator (DLP1)ROPreports RBS Site Secretary (LGD)SUNSI Review Completed: LTR ADAMS: G Yes G No Initials: LTR O Publicly Available G Non-Publicly Available G Sensitive O Non-SensitiveRIV:PSB\SHPPSB\HPPSB\HPPSB\HPPSB\SHPLTRicketson:BDBacaGLGuerraDLStearnsLCCarsonII/RA//RA//RA//RA//RA/08/07/0708/21/0708/21/0708/15/0708/07/07C:PSBDRP/CC:PSBMPShannonMCHayMPShannon/RA/WCWalker for/RA/08/17/0708/21/0708/21/07OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax Enclosure-1-U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket:50-458License:NPF-47 Report:05000458/2007010 Licensee:Entergy Operations, Inc.
 
Facility:River Bend Station Location:5485 U.S. Highway 61St. Francisville, LouisianaDates:July 9 - 13, 2007 Inspectors:Larry Ricketson, P.E., Senior Health Physicist, Plant Support Branch Louis C. Carson II, Senior Health Physicist, Plant Support Bernadette Baca, Health Physicist, Plant Support Branch Gilbert L. Guerra, C.H.P., Health Physicist, Plant Support Branch Donald L. Stearns, Health Physicist, Plant Support BranchAccompanied By:David C. Graves, Health Physicist, Plant Support BranchApproved By:Michael P. Shannon, ChiefPlant Support Branch Division of Reactor Safety Enclosure-2-


=SUMMARY OF FINDINGS=
Radiologically Significant Areas; Radiation Safety Team The report covered a 5-day period of inspection on site by a team of five region-based inspectors. A finding of very low safety significance (Green) was identified. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using IMC 0609,
IR 05000458/2007010; 07/09/2007 - 07/13/07; River Bend Station; Access Control ToRadiologically Significant Areas; Radiation Safety TeamThe report covered a 5-day period of inspection on site by a team of five region-basedinspectors. A finding of very low safety significance (Green) was identified. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using IMC 0609,
Significance Determination Process. Findings for which the Significance Determination Process 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.
"Significance Determination Process". Findings for which the Significance Determination Process 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===
===NRC-Identified and Self-Revealing Findings===
Line 63: Line 58:
===Cornerstone: Occupational Radiation Safety===
===Cornerstone: Occupational Radiation Safety===
: '''Green.'''
: '''Green.'''
The team identified a noncited violation of 10 CFR 20.1902(a) becausethe licensee failed to post radiation areas in the radwaste building with a conspicuous sign or signs bearing the radiation symbol and the words "Caution,Radiation Area."  The licensee posted radiation area signs only at the entrances to the different elevations of the building, instead of at the discrete radiation areas, even though most of the radwaste building was not a radiation area.
The team identified a noncited violation of 10 CFR 20.1902(a) because the licensee failed to post radiation areas in the radwaste building with a conspicuous sign or signs bearing the radiation symbol and the words Caution,
Radiation Area. The licensee posted radiation area signs only at the entrances to the different elevations of the building, instead of at the discrete radiation areas, even though most of the radwaste building was not a radiation area.


Dose rates in unposted radiation areas were as high as 15 millirems per hour.
Dose rates in unposted radiation areas were as high as 15 millirems per hour.


As corrective action, the licensee posted the discrete areas. Additional corrective action is still being evaluated.The finding was greater than minor because it was associated with one of thecornerstone attributes (exposure control and monitoring) and the finding affected the Occupational Radiation Safety cornerstone objective, in that, uninformed workers could unknowingly accrue additional 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 and component of work control because the licensee did not coordinate work activities by incorporating actions to address the need to keep personnel apprised of plant conditions that may affect work activities. (H3.b)(Section 2OS1)
As corrective action, the licensee posted the discrete areas. Additional corrective action is still being evaluated.
 
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, uninformed workers could unknowingly accrue additional 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 and component of work control because the licensee did not coordinate work activities by incorporating actions to address the need to keep personnel apprised of plant conditions that may affect work activities. (H3.b)(Section 2OS1)


===B.Licensee Identified Violations===
===Licensee Identified Violations===


None Enclosure-3-
None


=REPORT DETAILS=
=REPORT DETAILS=
2.RADIATION SAFETY Cornerstones: Occupational Radiation Safety [OS] and Public Radiation Safety [PS]2OS1Access Control To Radiologically Significant Areas (71121.01)
 
==RADIATION SAFETY==
Cornerstones: Occupational Radiation Safety [OS] and Public Radiation Safety [PS] 2OS1 Access Control To Radiologically Significant Areas (71121.01)


====a. Inspection Scope====
====a. Inspection Scope====
This area was inspected to assess the licensee's performance in implementing physicaland 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 bytechnical specifications as criteria for determining compliance. During the inspection, theteam 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 1 of the required 21 samples.
This area was inspected to assess the licensees 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 licensees 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 1 of the required 21 samples.


====b. Findings====
====b. Findings====


=====Introduction.=====
=====Introduction.=====
A Green noncited violation of 10 CFR 20.1902(a) was identified for thefailure to post radiation areas in the radwaste building with a conspicuous sign or signs bearing the radiation symbol and the words "Caution, Radiation Area."Description. While making observations in the radwaste building on July 10, 2007, theteam identified localized radiation areas in walkways in front of high radiation area and locked high radiation area doors which were not posted as radiation areas. The general area dose rates in front of Door RW106-G2 and RW65-G8 were 6 mrem/hr and 15 mrem/hr, respectively. The only radiation area signs to warn workers prior to entering the radiation areas were at the entrances to the different elevations of the radwaste building. The radwaste building is a large area and according to the licensee's surveys, only a small part of the total area had dose rates exceeding 5 millirems per hour.  
A Green noncited violation of 10 CFR 20.1902(a) was identified for the failure to post radiation areas in the radwaste building with a conspicuous sign or signs bearing the radiation symbol and the words Caution, Radiation Area.
 
=====Description.=====
While making observations in the radwaste building on July 10, 2007, the team identified localized radiation areas in walkways in front of high radiation area and locked high radiation area doors which were not posted as radiation areas. The general area dose rates in front of Door RW106-G2 and RW65-G8 were 6 mrem/hr and 15 mrem/hr, respectively. The only radiation area signs to warn workers prior to entering the radiation areas were at the entrances to the different elevations of the radwaste building. The radwaste building is a large area and according to the licensees surveys, only a small part of the total area had dose rates exceeding 5 millirems per hour.


=====Analysis.=====
=====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 area was large and very little of it was a radiation area, the team concluded that posting only the entrances to the area, rather than the discrete areas, was not sufficient to inform radiation workers of radiological hazards in their work areas. The failure to post a radiation area is a performance deficiency. The finding was greaterthan 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, uninformed workers could unknowingly accrue additional  
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 area was large and very little of it was a radiation area, the team concluded that posting only the entrances to the area, rather than the discrete areas, was not sufficient to inform radiation workers of radiological hazards in their work areas.
-4-radiation dose. Because the finding involved the potential for unplanned, unintended doseresulting from conditions that were contrary to NRC regulations, the finding was evaluated 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:
 
The failure to post a 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, uninformed workers could unknowingly accrue additional
 
radiation dose. Because the finding involved the potential for unplanned, unintended dose resulting from conditions that were contrary to NRC regulations, the finding was evaluated 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,
: (1) ALARA planning and controls,
: (2) an overexposure,
: (2) an overexposure,
Line 92: Line 99:
: (4) an impaired ability to assess dose. Also, this finding had a cross-cutting aspect in the area of human performance and component of work control because the licensee did not coordinate work activities by incorporating actions to address the need to keep personnel apprised of plant conditions that may affect work activities.
: (4) an impaired ability to assess dose. Also, this finding had a cross-cutting aspect in the area of human performance and component of work control because the licensee did not coordinate work activities by incorporating actions to address the need to keep personnel apprised of plant conditions that may affect work activities.


(H3.b)Enforcement. Part 20.1003 of Title 10 of the Code of Federal Regulations defines aradiation area as an area, accessible to individuals, in which radiation levels could result inan 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.
    (H3.b)
 
=====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 July 10, 2007, the team identified radiation areas in the radwaste building that were 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 radiation areas was determined to be of low safety significance and was entered into the licensees corrective action program as Condition Report CR-RB-2007-03038, this violation is being treated as an noncited consistent with Section VI.A of the NRC Enforcement Policy:
NCV 05000458/2007010-01, Failure to Conspicuously Post a Radiation Area.


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 July 10, 2007, the team identified radiation areas in the radwaste building that were 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 radiation areas was determined to be of low safety significance and was entered into the licensee's corrective action program as Condition Report CR-RB-2007-03038, this violation is being treated as an noncited consistent with Section VI.A of the NRC Enforcement Policy:
2OS3 Radiation Monitoring Instrumentation and Protective Equipment (71121.03)
NCV 05000458/2007010-01, Failure to Conspicuously Post a Radiation Area. 2OS3Radiation Monitoring Instrumentation and Protective Equipment (71121.03)


====a. Inspection Scope====
====a. Inspection Scope====
This area was inspected to determine the accuracy and operability of radiation monitoringinstruments 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 highradiation areas and post-accident monitors used for remote emergency
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 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
assessment *Calibration of portable radiation detection instrumentation, electronic alarmingdosimetry, and continuous air monitors used for job coverage *Calibration of whole body counting equipment and radiation detection instrumentsutilized for personnel and material release from the radiologically controlled area *Self-assessments, audits, and licensee event reports  
* Calibration of portable radiation detection instrumentation, electronic alarming dosimetry, and continuous air monitors used for job coverage
-5-*Corrective action program reports since the last inspection*Licensee action in cases of repetitive deficiencies or significant individualdeficiencies*Calibration expiration and source response check currency on radiation detectioninstruments staged for use *The licensee's capability for refilling and transporting SCBA air bottles to and fromthe 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 performmaintenance on the vendor-designated vital components, and the vital component maintenance records for SCBA units The team completed nine of the required nine samples.
* Calibration of whole body counting equipment and radiation detection instruments utilized for personnel and material release from the radiologically controlled area
* Self-assessments, audits, and licensee event reports
* 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 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 team completed nine of the required nine samples.


====b. Findings====
====b. Findings====
No findings of significance were identified.2PS1Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems (71122.01)
No findings of significance were identified.
2PS1 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems (71122.01)


====a. Inspection Scope====
====a. Inspection Scope====
This area was inspected to ensure that the gaseous and liquid effluent processingsystems are maintained so that radiological releases are properly mitigated, monitored, and evaluated with respect to public exposure. The team used the requirements in 10 CFR Part 20, 10 CFR Part 50 Appendices A and I, the Offsite Dose Calculation Manual, and the licensee's procedures required by technical specifications as criteria fordetermining compliance. The team interviewed licensee personnel and reviewed: *Radiological effluent release reports since the last inspection, changes to theOffsite Dose Calculation Manual, radiation monitor setpoint calculation methodology, anomalous sampling results, effluent radiological occurrence performance indicator incidents, program for identifying contaminated spills and leakage and the licensee's process for control and assessment, self-assessments, audits, and licensee event reports*Gaseous and liquid release system component configurations
This area was inspected to ensure that the gaseous and liquid effluent processing systems are maintained so that radiological releases are properly mitigated, monitored, and evaluated with respect to public exposure. The team used the requirements in 10 CFR Part 20, 10 CFR Part 50 Appendices A and I, 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:
*Routine processing, sample collection, sample analysis, and release of radioactiveliquid and gaseous effluent
* Radiological effluent release reports since the last inspection, changes to the Offsite Dose Calculation Manual, radiation monitor setpoint calculation methodology, anomalous sampling results, effluent radiological occurrence performance indicator incidents, program for identifying contaminated spills and leakage and the licensee's process for control and assessment, self-assessments, audits, and licensee event reports
-6-*The licensee's understanding of the location and construction of undergroundpipes and tanks and storage pools that contain radioactive contaminated liquids; the technical bases for onsite monitoring, the licensee's capabilities of detecting spills or leaks and identifying groundwater radiological contamination both on siteand beyond the owner-controlled area*Changes made by the licensee to the Offsite Dose Calculation Manual, the liquidor gaseous radioactive waste system design, procedures, or operation since the last inspection*Monthly, quarterly, and annual dose calculations
* Gaseous and liquid release system component configurations
*Surveillance test results involving air cleaning systems and stack or vent flow rates
* Routine processing, sample collection, sample analysis, and release of radioactive liquid and gaseous effluent
*Instrument calibrations of discharge effluent radiation monitors and flowmeasurement devices, effluent monitoring system modifications, effluent radiation monitor alarm setpoint values, and counting room instrumentation calibration and quality control *Interlaboratory comparison program results
* The licensee's understanding of the location and construction of underground pipes and tanks and storage pools that contain radioactive contaminated liquids; the technical bases for onsite monitoring, the licensee's capabilities of detecting spills or leaks and identifying groundwater radiological contamination both on site and beyond the owner-controlled area
*Licensee event reports, special reports, audits, self-assessments and correctiveaction reports performed since the last inspectionEither because the conditions did not exist or an event had not occurred, no opportunitieswere available to review the following items:*Abnormal releases The team completed 11 of the required 11 samples.
* Changes made by the licensee to the Offsite Dose Calculation Manual, the liquid or gaseous radioactive waste system design, procedures, or operation since the last inspection
* Monthly, quarterly, and annual dose calculations
* Surveillance test results involving air cleaning systems and stack or vent flow rates
* Instrument calibrations of discharge effluent radiation monitors and flow measurement devices, effluent monitoring system modifications, effluent radiation monitor alarm setpoint values, and counting room instrumentation calibration and quality control
* Interlaboratory comparison program results
* Licensee event reports, special reports, audits, self-assessments and corrective action reports performed since the last inspection Either because the conditions did not exist or an event had not occurred, no opportunities were available to review the following items:
* Abnormal releases The team completed 11 of the required 11 samples.


====b. Findings====
====b. Findings====
No findings of significance were identified.2PS2Radioactive Material Processing and Transportation (71122.02)
No findings of significance were identified.
2PS2 Radioactive Material Processing and Transportation (71122.02)


====a. Inspection Scope====
====a. Inspection Scope====
This area was inspected to verify that the licensee's radioactive material processing andtransportation 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 releasereports, and the scope of the licensee's audit program  
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 171-180. The team interviewed licensee personnel and reviewed:
-7-*Liquid and solid radioactive waste processing systems configurations, the statusand 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 ofscaling factors and calculations to account for difficult-to-measure radionuclides *Shipping records for non-excepted package shipments
* The radioactive waste system description, recent radiological effluent release reports, and the scope of the licensees audit program
*Licensee event reports, special reports, audits, state agency reports,self-assessments and corrective action reports performed since the last inspection Either because the conditions did not exist or an event had not occurred, no opportunitieswere available to review the following items:*Shipment packaging, surveying, labeling, marking, placarding, vehicle checking,driver instructing, and disposal manifestingThe team completed six of the required six samples.
* 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
* 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 Either because the conditions did not exist or an event had not occurred, no opportunities were available to review the following items:
* Shipment packaging, surveying, labeling, marking, placarding, vehicle checking, driver instructing, and disposal manifesting The team completed six of the required six samples.


====b. Findings====
====b. Findings====
No findings of significance were identified.2PS3Radiological Environmental Monitoring Program (REMP) and Radioactive Material ControlProgram (71122.03)
No findings of significance were identified.
 
2PS3 Radiological Environmental Monitoring Program (REMP) and Radioactive Material Control Program (71122.03)


====a. Inspection Scope====
====a. Inspection Scope====
This area was inspected to ensure that the REMP verifies the impact of radioactiveeffluent 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  
This area was inspected to ensure that the REMP 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
*Selected air sampling and thermoluminescence dosimeter monitoring stations  
* Annual environmental monitoring reports and licensee event reports
*Collection and preparation of environmental samples
* Selected air sampling and thermoluminescence dosimeter monitoring stations
*Operability, calibration, and maintenance of meteorological instruments  
* Collection and preparation of environmental samples
-8-*Each event documented in the Annual Environmental Monitoring Report whichinvolved a missed sample, inoperable sampler, lost thermoluminescence dosimeter, or anomalous measurement*Significant changes made by the licensee to the Offsite Dose Calculation Manualas 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 leavingthe radiological controlled 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*Licensee event reports, special reports, audits, self-assessments and correctiveaction reports performed since the last inspectionThe team completed 10 of the required 10 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 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
* Licensee event reports, special reports, audits, self-assessments and corrective action reports performed since the last inspection The team completed 10 of the required 10 samples.


====b. Findings====
====b. Findings====
No findings of significance were identified.4.OTHER ACTIVITIES4OA2Problem Identification and Resolution
No findings of significance were identified.
 
==OTHER ACTIVITIES==
{{a|4OA2}}
==4OA2 Problem Identification and Resolution==


====a. Inspection Scope====
====a. Inspection Scope====
The team evaluated the effectiveness of the licensee's problem identification andresolution process with respect to the following inspection areas:*Radiation Monitoring Instrumentation (Section 2OS3)
The team evaluated the effectiveness of the licensees problem identification and resolution process with respect to the following inspection areas:
*Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems (Section 2PS1)*Radioactive Material Processing and Transportation (Section 2PS2)  
* Radiation Monitoring Instrumentation (Section 2OS3)
-9-*Radiological Environmental Monitoring Program and Radioactive Material ControlProgram (Section 2PS3)
* 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====
====b. Findings and Observations====
No findings of significance were identified.4OA6Management MeetingsExit Meeting SummaryOn July 13, 2007, the team presented the inspection results to Mr. J. Venable, Senior VicePresident, Operations, and other members of the staff, who acknowledged the findings.
No findings of significance were identified.
{{a|4OA6}}
==4OA6 Management Meetings==
 
===Exit Meeting Summary===
 
On July 13, 2007, the team presented the inspection results to Mr. J. Venable, Senior Vice President, Operations, and other members of the staff, who acknowledged the findings.
 
The team confirmed that proprietary information was not provided or examined during the inspection.


The team confirmed that proprietary information was not provided or examined during the inspection.ATTACHMENT:
ATTACHMENT:  


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL INFORMATION=
Line 171: Line 223:
: [[contact::M. Miller]], Resident Inspector
: [[contact::M. Miller]], Resident Inspector
: [[contact::D. Bollock]], Project Engineer
: [[contact::D. Bollock]], Project Engineer
==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED==
==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED==
Opened NoneOpened and Closed During this Inspection05000458/2007010-01NCVFailure to Failure to Conspicuously Post Radiation Areas (Section 2OS1)
AttachmentA-2
==LIST OF DOCUMENTS REVIEWED==
Section 2OS1: Access Controls to Radiologically Significant Areas (71121.01) Condition ReportsCR-RBS-2007-03028CR-RBS-2007-03038ProceduresEN-RP-108, "Radiation Protection Posting," Revision 4
: SurveysSurvey
: RBS-0707-0110 7/11/07Survey
: RBS-0707-0102 7/11/07
: Survey
: RBS-0707-0100 7/11/07
: Survey
: RBS-0706-0138 6/8/07
: Survey
: RBS-0705-0280 5/20/07
: Survey
: RBS-0705-0012 5/1/07
: Survey
: RBS-0705-0011 5/1/07


==Section 2OS3: Radiation Monitoring Instrumentation and Protective EquipmentProceduresADM-0045, System Management and Utilization of the==
===Opened===
: DRMS, Revision 5ARP-RMS-DSPL230, DRMS
: RM-11 CRT Alarm Response
: EN-RP-301, Radiation Protection Instrument Control, Revision 0
: EN-RP-303, Source Checking of Radiation Protection Instrumentation, Revision 8
: RP-304, Operation of Counting Equipment, Revision 2
: EN-RP-306, Operation and Calibration of the Eberline
: PM-7, Revision 0
: EN-RP-307, Operation and Calibration of the Personal Contamination Monitors, Revision 0
: EN-RP-308, Operation and Calibration of the Gamma Scintillation Tool Monitors, Revision 0
: RHP-0106, Calibration of the Canberra Fastscan and Accuscan II Whole Body Counters,Revision 2RPP-0034, Operation of the General Atomics Digital Radiation Monitoring System CRT,Revision 8
: AttachmentA-3RPP-0036, Calibration of DRMS Area Monitors and Determination of Alert and High AlarmSetpoints, Revision 5ACondition ReportsCR-RBS-04294
: Audit and AssessmentsQA-14-2007-RBS-1, Quality Assurance Audit of Radiation Protection, April 20, 2007LO#2007-00068, "Radiation Protection Program, April 2-6, 2007Calibration RecordsCalibration of the Canberra Accuscan II Whole Body Counting System at River Bend Station,System #96-5818, March 17, 2006Calibration of the Canberra Accuscan II Whole Body Counting System at River Bend Station,System #96-5818, March 14, 2007Calibration of the Canberra Fastscan Whole Body Counting System at River Bend Station,System #96-9762, March 17, 2006Calibration of the Canberra Fastscan Whole Body Counting System at River Bend Station,System #96-9762, March 14,
: 20072006 B2.28CALDAT-00761:
: AMP-100, February 6,
: 20072007 B2.28CALDAT-00433: R0-7, January 17, 2007
: 2007 B2.28CALDAT-00618: R0-7, February 1, 2007
: 2007 B2.28CALDAT-00806:
: SAC-4, January 30, 2007
: 2007 B2.28CALDAT-01141:
: BC-4, February 7, 2007
: 2007 B2.28CALDAT-01775:
: RO-20, March 6, 2007


==Section 2PS1: Radioactive Gaseous and Liquid Effluent Treatment and MonitoringSystemsProceduresCOP-0046, "Sampling Gaseous Effluents Via the Wide Range Gas Monitors," Revision 11COP-0050, "Grab Sampling Gaseous Streams," Revision 8==
None Opened and Closed During this Inspection
: RSP-0008, "Offsite Dose Calculation Manual (ODCM)," Revision 13
: 05000458/2007010-01              NCV              Failure to Failure to Conspicuously Post Radiation Areas (Section 2OS1)
: EN-MA-105, Control of Measuring and Test Equipment, Revision 2
Attachment
: MCP-4201, DRMS Low Range Area Monitor Calibration, Revision 4
: AttachmentA-4MCP-4203, DRMS High Range Calibration Area Monitor Calibration, Revision 4CMCP-4206,
: DRMS-Particulate and Gas Monitor Calibration, Revision 3B
: STP-511-4201, Main Steam Line Radiation High High Channel Calibration and Logic SystemFunctional Test, Revision 16STP-511-4214,
: RMS-Main Plant Exhaust Duct Noble Gas Activity Channel CalibrationRMS-RE125, Revision 9STP-511-4249,
: RMS-Primary Containment Area Radiation Monitor Channel CalibrationRMS-RE16A, Revision 301STP-511-4280,
: RMS-Liquid Radwaste Effluent Line Radiation Monitor Channel Functional TestRMS-RE107, Revision 9FSTP-511-4515,
: RMS-Main Plant Exhaust Duct Noble Gas Activity Channel CalibrationRMS-RE126, Revision 6DSTP-511-4580,
: RMS-Liquid Radwaste Effluent Line Radiation Monitor Channel Functional TestRMS-RE107, Revision 8 Work Orders, Calibration Records and Surveillance Test ResultsW.O.-0116572,
: MCP-4201, DRMS Low Range Area Monitor Calibration, RE-204
: W.O.-0116572,
: MCP-4201, DRMS Low Range Area Monitor Calibration, RE-149
: W.O.-50688322,
: STP-511-4515,
: RMS-Main Plant Exhaust Duct Noble Gas Activity ChannelCalibration
: RMS-RE126W.O.-50990918,
: STP-511-4214,RMS-Main Plant Exhaust Duct Noble Gas Activity ChannelCalibration RMS-RE125
: W.O.-50992632,
: STP-511-4201, Main Steam Line Radiation High High Channel Calibration andLogic System Functional TestW.O.-51000668.
: MCP-4201, DRMS Low Range Area Monitor Calibration,
: RE-126W.O.-51013232,
: STP-511-4249,
: RMS-Primary Containment Area Radiation Monitor ChannelCalibration
: RMS-RE16AWO-51014558,
: STP-511-4580, Liquid Radwaste Effluent Line Radiation Monitor ChannelFunctional Test
: RMS-RE-107W.O.-51039002,
: STP-511-4201, Main Steam Line Radiation High High Channel Calibration andLogic System Functional Test AttachmentA-5WO-51097711,
: STP-511-4580,
: RMS-Liquid Radwaste Effluent Line Radiation Monitor ChannelFunctional Test
: RMS-RE107Corrective Action DocumentsCR-RBS-2003-02084,
: CR-RBS-2004-00362,
: CR-RBS-2004-01219,
: CR-RBS-2005-01485,CR-RBS-2006-00038,
: CR-RBS-2006-00085,
: CR-RBS-2006-00125, CR-RBS-2006-00147,
: CR-RBS-2006-00539,
: CR-RBS-2006-00634,
: CR-RBS-2006-00918, CR-RBS-2006-01498,
: CR-RBS-2006-02291,
: CR-RBS-2006-02299,
: CR-RBS-2006-02316, CR-RBS-2006-02459,
: CR-RBS-2006-02547,
: CR-RBS-2006-03707,
: CR-RBS-2007-00550, CR-RBS-2007-01620,
: CR-RBS-2007-CR-RBS-2007-03034Audits and AssessmentsQA-6-2005-RBS-1, Quality Assurance Audit of Effluents and Environmental Monitoring,September 11, 2005QA-2006-2-RBS-1, Quality Assurance Audit of Chemistry, December 13, 2006
: Release PermitsRadioactive Liquid Effluent Discharge Permit 2006086Radioactive Liquid Effluent Discharge Permit 2006108
: Radioactive Liquid Effluent Discharge Permit 2007032
: Radioactive Liquid Effluent Discharge Permit 2007042
: Gamma Spectrum
: 070710002 Main Plant Charcoal Canister Gamma Spectrum
: 070710003 Main Plant Particulate Filter Gamma Spectrum
: 070710004 Fuel Building Charcoal Canister Gamma Spectrum
: 070710005 Fuel Building Particulate Filter Gamma Spectrum
: 070710014 Radwaste Building Charcoal Canister Gamma Spectrum
: 070710015 Radwaste Building Particulate FilterMiscellaneousSite Hydrogeologic Assessment for River Bend Station, January
: 20072005 River Bend Station Annual Radioactive Effluent Release Report
: 2006 River Bend Station Annual Radioactive Effluent Release Report Groundwater Protection and Monitoring, Entergy Nuclear Fleet, Revision 1, April 16, 2007
: Results of Radiochemistry Cross Check Program 3
rd Quarter 2005Results of Radiochemistry Cross Check Program 3
rd Quarter 2006
: AttachmentA-6


==Section 2PS2: Radioactive Material Processing and TransportationCondition ReportsCR-ECH-2005-00594CR-RBS-2005-03943CR-ECH-2005-00595==
==LIST OF DOCUMENTS REVIEWED==
: CR-RBS-2005-04027
: CR-ECH-2005-00606 CR-RBS-2005-04038
: CR-ECH-2006-00087 CR-RBS-2005-04044
: CR-ECH-2006-00174 CR-RBS-2006-00913
: CR-ECH-2007-00013 CR-RBS-2006-02996
: CR-ECH-2007-00089 CR-RBS-2006-03729
: CR-ECH-2007-00097 CR-RBS-2006-04568
: LO-OPX-2006-00279 CR-RBS-2007-00489
: LO-OPX-2005-00357 CR-RBS-2007-00499
: LO-OPX-2006-00369 CR-RBS-2007-01234
: CR-RBS-2007-02197
: AssessmentsQA-15-2005-ENS-1 Radwaste Quality Assurance Audit Report
: QS-2006-RBS-003Radiation Protection 2005 QA Audit Follow-upTraining Lesson PlansRLP-RPCT-SHIPRadiation Protection Technician DOT Hazmat/Radioactive MaterialShipping ProceduresEN-RW-101Radioactive Waste Management Rev. 1EN-RW-102Radioactive Shipping Procedure Rev. 4
: EN-RW-103Radioactive Waste Tracking Procedure Rev. 1
: EN-RW-104Scaling Factors Rev. 2
: EN-RW-105Process Control Program Rev. 0
: EN-RW-106Integrated Transportation Security Plan Rev. 0
: EN-EV-106Waste Management Program Rev. 0
: ENS-EV-114Hazardous Materials Packaging and Shipping Rev. 2
: RWS-0304Radioactive Waste Handling and Control Rev. 15Shipment RecordsRBS-2006-040RBS-2006-048
: RBS-2006-70
: RBS-2007-04
: RBS-2007-36
: RBS-2007-39
: AttachmentA-7


==Section 2PS3: Radiological Environmental Monitoring Program (REMP) And RadioactiveMaterial Control ProgramAuditsLO-RBS-2007-00068Condition ReportsCR-ECH-2006-00030,==
: CR-ECH-2006-00062,
: CR-ECH-2007-00072,
: CR-ECH-2007-00251,CR-RBS-2005-04049,
: CR-RBS-2006-00302,
: CR-RBS-2006-01124,
: CR-RBS-2006-02358,
: CR-RBS-2006-03037,
: CR-RBS-2006-04233,
: CR-RBS-2007-00917,
: CR-RBS-2007-01016,
: CR-RBS-2007-01550,
: CR-RBS-2007-02171,
: LO-ELO-2006-00129ProceduresEN-CY-102Laboratory Analytical Quality Control, Revision 1EN-CY-109Sampling and Analysis of Groundwater Monitoring Wells, Revision 0
: EN-EV-116Radiological Environmental Analytical Services, Revision 2EN-RP-100Radworker Expectations, Revision 0
: EN-RP-103Access Control, Revision 2
: EN-RP-121Radioactive Material Control, Revision 0
: EN-RP-121Radioactive Material Control, Revision 1
: EN-RP-143Source Control, Revision 1
: EN-RP-304Operation of Counting Equipment, Revision 2
: ESP-8-005Assessment of the Reliability of Results of the Radiological Environmental
: Monitoring Program, Revision 10ESP-8-021Sampling Water for Radiological Environmental Monitoring, Revision 12
: ESP-8-022Monitoring of Sanitary and Storm Sewers for Radioactivity, Revision 9
: ESP-8-023Sampling of Airborne Radioiodine and Particulates for Radiological Monitoring,Revision 14
: ESP-8-028Deployment and Retrieval of Environmental Thermoluminescence Dosimeters,Revision 12ESP-8-032Analysis of Gross Alpha and Gross Beta activity on Particulate Filters, Revision 10
: ESP-8-034Gamma Dose Estimation from Environmental Thermoluminescence Dosimeters,Revision 9ESP-8-036Gamma Isotopic Analysis for the Environmental Samples, Revision 10
: ESP-8-037Preparation of Environmental Samples for Gamma Isotopic Analysis, Revision 9
: ESP-8-043Calibration and Instrument Performance Assessment of the Packard Model 2700Liquid Scintillation Analyzer, Revision 9ESP-8-050Conduct of the Radiological Environmental Monitoring Program (REMP), Revision
: 13ESP-8-051Land Use Census, Revision 8
: ESP-8-052Interlaboratory Comparison Program for Radiological Environmental Monitoring,Revision 9ESP-8-054Calibration of the Environmental Gamma Ray Spectroscopy System, Revision 11
: ESP-8-066Operations of the Canberra Model S5XLB Low Background Counting System,Revision 0
: AttachmentA-8RHP-03640CFR190 Dose Determination, Revision 00ARPP-005Management of Radiological Postings, Revision 26
: RPP-006Performance of Radiological Surveys, Revision 21
: RPP-118Calibration and Maintenance of Portable Radiological Air Samplers, Revision 3
: RSP-008Offsite Dose Calculation Manual, Revision 13
: RSP-216Radioactive Source Control, Revision 7Miscellaneous2005 and 2006 River Bend Station Annual Radiological Environmental Operating Reports2005 and 2006 Radioactive Effluent Release Report
: 2005 and 2006 River Bend Station Interlaboratory Comparison Results Calibration Records for Environmental Gamma Spectroscopy Detectors 1, 2, 4, and 5
: Calibration Records for Environmental Air Samplers 0042, 0236, 1081, and 1286
: Daily Source Check Records for Contamination Monitors Environmental Counting Instrument Quality Control Records for Serial Numbers
: 103867,
: 4953367,
: 8841116,
: 8841128, 10943415
: Groundwater Protection and Monitoring, Entergy Nuclear Fleet Project Plan, Revision 1
}}
}}

Latest revision as of 08:22, 22 December 2019

IR 05000458-07-010; 07/09/2007 - 07/13/07; River Bend Station; Access Control to Radiologically Significant Areas; Radiation Safety Team
ML072340080
Person / Time
Site: River Bend Entergy icon.png
Issue date: 08/21/2007
From: Shannon M
Plant Support Branch Region IV
To: Venable J
Entergy Operations
References
IR-07-010
Download: ML072340080 (21)
v • d • e


Text

ust 21, 2007

SUBJECT:

RIVER BEND STATION - NRC RADIATION SAFETY TEAM INSPECTION REPORT 05000458/2007010

Dear Mr. Venable:

On July 13, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your River Bend 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 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 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 finding of very low safety significance (Green). However, because the finding was of very low safety significance and it was entered into your corrective action program, the NRC is treating this finding as a noncited violation consistent with Section VI.A of the NRC Enforcement Policy. If you contest the noncited violation in this report, 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 River Bend Station facility.

Entergy Operations, Inc. -2-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 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: 50-458 Licenses: NPF-47

Enclosure:

NRC Inspection Report 05000458/2007010 w/attachment: Supplemental Information

REGION IV==

Docket: 50-458 License: NPF-47 Report: 05000458/2007010 Licensee: Entergy Operations, Inc.

Facility: River Bend Station Location: 5485 U.S. Highway 61 St. Francisville, Louisiana Dates: July 9 - 13, 2007 Inspectors: Larry Ricketson, P.E., Senior Health Physicist, Plant Support Branch Louis C. Carson II, Senior Health Physicist, Plant Support Bernadette Baca, Health Physicist, Plant Support Branch Gilbert L. Guerra, C.H.P., Health Physicist, Plant Support Branch Donald L. Stearns, Health Physicist, Plant Support Branch Accompanied By: David C. Graves, Health Physicist, Plant Support Branch Approved By: Michael P. Shannon, Chief Plant Support Branch Division of Reactor Safety-1- Enclosure

SUMMARY OF FINDINGS

IR 05000458/2007010; 07/09/2007 - 07/13/07; River Bend Station; Access Control To

Radiologically Significant Areas; Radiation Safety Team The report covered a 5-day period of inspection on site by a team of five region-based inspectors. A finding of very low safety significance (Green) was identified. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using IMC 0609,

Significance Determination Process. Findings for which the Significance Determination Process 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.

NRC-Identified and Self-Revealing Findings

Cornerstone: Occupational Radiation Safety

Green.

The team identified a noncited violation of 10 CFR 20.1902(a) because the licensee failed to post radiation areas in the radwaste building with a conspicuous sign or signs bearing the radiation symbol and the words Caution,

Radiation Area. The licensee posted radiation area signs only at the entrances to the different elevations of the building, instead of at the discrete radiation areas, even though most of the radwaste building was not a radiation area.

Dose rates in unposted radiation areas were as high as 15 millirems per hour.

As corrective action, the licensee posted the discrete areas. Additional corrective action is still being evaluated.

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, uninformed workers could unknowingly accrue additional 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 and component of work control because the licensee did not coordinate work activities by incorporating actions to address the need to keep personnel apprised of plant conditions that may affect work activities. (H3.b)(Section 2OS1)

Licensee Identified Violations

None

REPORT DETAILS

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 licensees 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 licensees 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 1 of the required 21 samples.

b. Findings

Introduction.

A Green noncited violation of 10 CFR 20.1902(a) was identified for the failure to post radiation areas in the radwaste building with a conspicuous sign or signs bearing the radiation symbol and the words Caution, Radiation Area.

Description.

While making observations in the radwaste building on July 10, 2007, the team identified localized radiation areas in walkways in front of high radiation area and locked high radiation area doors which were not posted as radiation areas. The general area dose rates in front of Door RW106-G2 and RW65-G8 were 6 mrem/hr and 15 mrem/hr, respectively. The only radiation area signs to warn workers prior to entering the radiation areas were at the entrances to the different elevations of the radwaste building. The radwaste building is a large area and according to the licensees surveys, only a small part of the total area had dose rates exceeding 5 millirems 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 area was large and very little of it was a radiation area, the team concluded that posting only the entrances to the area, rather than the discrete areas, was not sufficient to inform radiation workers of radiological hazards in their work areas.

The failure to post a 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, uninformed workers could unknowingly accrue additional

radiation dose. Because the finding involved the potential for unplanned, unintended dose resulting from conditions that were contrary to NRC regulations, the finding was evaluated 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 and component of work control because the licensee did not coordinate work activities by incorporating actions to address the need to keep personnel apprised of plant conditions that may affect work activities.

(H3.b)

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 July 10, 2007, the team identified radiation areas in the radwaste building that were 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 radiation areas was determined to be of low safety significance and was entered into the licensees corrective action program as Condition Report CR-RB-2007-03038, this violation is being treated as an noncited consistent with Section VI.A of the NRC Enforcement Policy:

NCV 05000458/2007010-01, 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 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
  • Self-assessments, audits, and licensee event reports
  • 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 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 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 ensure that the gaseous and liquid effluent processing systems are maintained so that radiological releases are properly mitigated, monitored, and evaluated with respect to public exposure. The team used the requirements in 10 CFR Part 20, 10 CFR Part 50 Appendices A and I, 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:

  • Radiological effluent release reports since the last inspection, changes to the Offsite Dose Calculation Manual, radiation monitor setpoint calculation methodology, anomalous sampling results, effluent radiological occurrence performance indicator incidents, program for identifying contaminated spills and leakage and the licensee's process for control and assessment, self-assessments, audits, and licensee event reports
  • Gaseous and liquid release system component configurations
  • Routine processing, sample collection, sample analysis, and release of radioactive liquid and gaseous effluent
  • The licensee's understanding of the location and construction of underground pipes and tanks and storage pools that contain radioactive contaminated liquids; the technical bases for onsite monitoring, the licensee's capabilities of detecting spills or leaks and identifying groundwater radiological contamination both on site and beyond the owner-controlled area
  • Changes made by the licensee to the Offsite Dose Calculation Manual, the liquid or gaseous radioactive waste system design, procedures, or operation since the last inspection
  • Monthly, quarterly, and annual dose calculations
  • Surveillance test results involving air cleaning systems and stack or vent flow rates
  • Instrument calibrations of discharge effluent radiation monitors and flow measurement devices, effluent monitoring system modifications, effluent radiation monitor alarm setpoint values, and counting room instrumentation calibration and quality control
  • Interlaboratory comparison program results
  • Licensee event reports, special reports, audits, self-assessments and corrective action reports performed since the last inspection Either because the conditions did not exist or an event had not occurred, no opportunities were available to review the following items:
  • Abnormal releases The team completed 11 of the required 11 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 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 171-180. The team interviewed licensee personnel and reviewed:

  • The radioactive waste system description, recent radiological effluent release reports, and the scope of the licensees 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
  • 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 Either because the conditions did not exist or an event had not occurred, no opportunities were available to review the following items:
  • Shipment packaging, surveying, labeling, marking, placarding, vehicle checking, driver instructing, and disposal manifesting The team completed six of the required six samples.

b. Findings

No findings of significance were identified.

2PS3 Radiological Environmental Monitoring Program (REMP) and Radioactive Material Control Program (71122.03)

a. Inspection Scope

This area was inspected to ensure that the REMP 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
  • 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 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
  • Licensee event reports, special reports, audits, self-assessments and corrective action reports performed since the last inspection The team completed 10 of the required 10 samples.

b. Findings

No findings of significance were identified.

OTHER ACTIVITIES

4OA2 Problem Identification and Resolution

a. Inspection Scope

The team evaluated the effectiveness of the licensees problem identification and resolution process with respect to the following inspection areas:

  • Radiation Monitoring Instrumentation (Section 2OS3)
  • Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems (Section 2PS1)
  • Radioactive Material Processing and Transportation (Section 2PS2)
  • Radiological Environmental Monitoring Program and Radioactive Material Control Program (Section 2PS3)

b. Findings and Observations

No findings of significance were identified.

4OA6 Management Meetings

Exit Meeting Summary

On July 13, 2007, the team presented the inspection results to Mr. J. Venable, Senior Vice President, Operations, and other members of the staff, who acknowledged the findings.

The team confirmed that proprietary information was not provided or examined during the inspection.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

R. Albert, Supervisor, Health Physics
R. Anthony, Supervisor, Health Physics
T. Baccus, Senior Health Physicist, Radiation Protection
B. Biggs, Technical Specialist, Licensing
T. Griffiths, Measuring & Test Equipment Supervisor
D. Heath, Supervisor, Health Physics (Radwaste/Shipping)
R. Heath, Supervisor, Chemistry
B. Houston, Manager, Radiation Protection
K. Huffstatler, Technical Specialist, Licensing
J. Hurley, Supervisor, Health Physics
M. Laiche, Senior Health Physicist, Radiation Protection
B. Michura, Master Nuclear Environmental Technician, Chemistry
B. Olinde, Superintendent, Instruments and Calibration
M. Reeves, Studsvik Transportation Representative
D. Sandlin, Engineer, Systems Engineering
W. Spell, Senior Environmental Specialist, Chemistry
S. Zabaski, Senior Health Physics/Chemistry Specialist, Chemistry
M. Vierra, Technical Specialist, Health Physics

NRC

M. Miller, Resident Inspector
D. Bollock, Project Engineer

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened

None Opened and Closed During this Inspection

05000458/2007010-01 NCV Failure to Failure to Conspicuously Post Radiation Areas (Section 2OS1)

Attachment

LIST OF DOCUMENTS REVIEWED

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