ML081630509
| ML081630509 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/11/2008 |
| From: | Brian Bonser NRC/RGN-II/DRS/PSB1 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| References | |
| Download: ML081630509 (12) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II SAM NUNN ATLANTA FEDERAL CENTER 61 FORSYTH STREET, SW, SUITE 23T85 ATLANTA, GEORGIA 30303-8931 June 11, 2008 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060
SUBJECT:
SURRY NUCLEAR POWER STATION, NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Christian:
During the period of July 28 through August 1, 2008, the NRC will perform the baseline Public Radiation Safety Inspection at the Surry Nuclear Power Station, (NRC Inspection Procedures 71121.01, 71121.03, 71122.01, 71122.03, Radiation Safety Sections of 71151, and 60855.1).
Experience has shown that this inspection is resource intensive both for the NRC inspectors and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection. It is important that all of these documents are up to date and complete, in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection. The inspection team leader has cancelled the pre-inspection visit scheduled for June 23-25, 2008 based in part on your historical performance in this area. The material requested should be provided to the resident inspector for forwarding to the inspection team by July 1, 2008.
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Paul Kershner of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Ruben K. Hamilton at (404) 562-4672.
2 In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/ reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely, Joel Munday /RA/ for:
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37
Enclosure:
Occupational Radiation Protection Inspection Document Request (cc: w\encl - See Page 3)
June 11, 2008 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060
SUBJECT:
SURRY NUCLEAR POWER STATION, NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Christian:
During the period of July 28 through August 1, 2008, the NRC will perform the baseline Public Radiation Safety Inspection at the Surry Nuclear Power Station, (NRC Inspection Procedures 71121.01, 71121.03, 71122.01, 71122.03, Radiation Safety Sections of 71151, and 60855.1).
Experience has shown that this inspection is resource intensive both for the NRC inspectors and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection. It is important that all of these documents are up to date and complete, in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection. The inspection team leader has cancelled the pre-inspection visit scheduled for June 23-25, 2008 based in part on your historical performance in this area. The material requested should be provided to the resident inspector for forwarding to the inspection team by July 1, 2008.
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Paul Kershner of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Ruben K. Hamilton at (404) 562-4672.
OFFICE RII:DRS RII:DRS SIGNATURE /RA/ Joel Munday/RA/for NAME Ruben Hamilton Brian Bonser DATE 06/10/2008 06/11/2008 6/ /2008 6/ /2008 6/ /2008 6/ /2008 6/ /2008 E-MAIL COPY? YES NO YES NO YES YES NO YES NO YES NO YES NO VEPCO 3 cc w/encl: Millstone Power Station Chris L. Funderburk Electronic Mail Distribution Director Nuclear Licensing and Operations Support Attorney General Virginia Electric and Power Company Supreme Court Building Electronic Mail Distribution 900 East Main Street Richmond, VA 23219 Donald E. Jernigan Site Vice President Senior Resident Inspector Surry Power Station Virginia Electric and Power Company Virginia Electric & Power Company Surry Power Station Electronic Mail Distribution U.S. NRC 5850 Hog Island Rd Virginia State Corporation Commission Surry, VA 23883 Division of Energy Regulation P.O. Box 1197 Michael M. Cline Richmond, VA 23209 Director Virginia Department of Emergency Services Lillian M. Cuoco, Esq. Management Senior Counsel Electronic Mail Distribution Dominion Resources Services, Inc.
VEPCO 4 Letter to David A. Christian from Alan J. Blamey dated Date of Letter
SUBJECT:
SURRY POWER STATION - NRC INTEGRATED INSPECTION REPORT 05000280/2008 AND 05000281/2008 Distribution w/encl:
RIDSNRRDIRS PUBLIC S. P. Lingam, NRR (PM: NA, SUR)
Pre-Inspection Document Request Public Radiation Safety Cornerstone Licensee: Surry Nuclear Power Station Docket Number(s): 50-280, 50-281 Inspection Dates: No (bagman), July 28- August 1, 2008 Inspection Procedures Scheduled:
71122.01 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems
[11/09/07]
71122.03 Radiological Environmental Monitoring Program (REMP) and Radioactive Material Control Program [8/4/06]
71121.01 Access Control to Radiologically Significant Areas [11/09/07]
71121.03 Radiation Monitoring Instrumentation and Protective Equipment 71151 Performance Indicator Verification [11/9/07]
60855 Operation of an ISFSI (RP aspects) [11/9/07]
The most recent inspection completed for the listed inspection procedures is listed to the right of the procedure titles inside brackets []. We request documentation from the date of the previous inspection to the present.
We would prefer as much of the information as possible in electronic form. An index to the CD contents is also helpful. For those items requesting a list of documents/areas, the inspectors will select documents/areas from the list for on-site review.
If you have any questions, please call Ruben Hamilton at 404-562-4672. Thank you in advance for all your effort in putting together this material.
Assistance Requested During On-Site Inspection G Introductions to, and discussions with, licensee personnel who will be assisting with the inspection G Plant familiarization tour for those unfamiliar with the plant G Health physics and security assistance with walk-down of ISFSI G Identification of work activities during the inspection for inspector observations, including notification of pre-job briefings.
G Advance notification of any liquid or gaseous effluent releases, including the associated pre-release sampling, analysis, and permit generation.
G Health physics assistance in plant walk-downs assessing access controls, e.g. verifying the posting and locking of entrances to HDR-HRA and VHRA, and spent fuel pool controls.
G Assistance in plant walk-downs of the liquid and gaseous effluent systems and associated radiation monitors.
G Assistance in plant walk-downs of radiation monitors, including ARMs, CAMs, whole body counters, and personnel contamination monitors, etc.
G Assistance with walk-down of meteorological equipment.
G Assistance with observations of REMP sample collection and processing.
Enclosure
2 General Information Request G Telephone numbers of contacts G Plant, Radiation Protection, and Chemistry organizational charts G Electronic copy of applicable chapters of UFSAR (e.g. radiation protection program, effluents and environmental monitoring programs, radiation monitoring system, etc.)
G Latest revision of the Offsite Dose Calculation Manual (ODCM)
G List of radiation protection and chemistry (i.e. effluents) procedures G Most recent DAW 10 CFR Part 61 analytical results.
G Corrective Action Program procedures G Procedure(s) for identifying, notification, tracking, and correcting PI occurrences G List of all Performance Indicators (PIs) and copies of associated corrective action reports for Occupational Exposure Control Effectiveness and RETS/ODCM Radiological Effluent Occurrences G Audits and self-assessments performed since the last inspection that encompass the areas of (1) radiation protection, (2) access controls, (3) effluent treatment and monitoring program (including chemistry and count room), (4) radiological environmental monitoring program, (5) meteorological monitoring program, (5) radioactive material control, (6) radiation measurement instrumentation program (fixed and portable), and (7) respiratory protection program.
60855 Operation of an ISFSI G Procedures associated with the ISFSI facility. Procedures should include:
< Radiological surveys, postings, and radiation control barricades
< Environmental monitoring (including TLDs)
< Loading of casks
< Routine activities G Radiation surveys of the ISFSI since the last inspection. [ Since 5/18/07]
G ALARA reviews and planning and associated RWPs for cask loading activities G Environmental monitoring results (e.g. TLDs)
G Radiological records for the loading of casks since the last inspection G Records of contamination incidents since the last inspection. [Since 5/18/07]
G List of corrective action reports related to the ISFSI with respect to radiation protection (i.e. access controls, ALARA, contamination, radiation levels, etc.) since the last inspection. [Since 5/18/07]
71121.01 Access Controls to Radiologically Significant Areas G Site and corporate procedures associated with the access control program. Procedures should include:
< Radiological surveys, postings, and radiation control barricades
< Security and control of high radiation sources/objects stored in pools
< Radiation Work Permits
< Radiological Job-Coverage
< Controlling access to High Radiation Areas (HRAs), High Dose Rate High Radiation Areas (HDR-HRAs), and Very High Radiation Areas (VHRAs)
< Key controls for all high radiation areas
< Radioactive material control, including contamination and hot particles Enclosure
3
< Dosimetry monitoring (electronic dosimeters, multi-badging, etc.)
< Calculations of internal exposures G List of the 10 most exposure significant work areas within radiation areas, high radiation areas (<1R/hr), or airborne radioactivity areas in the plant. This may include areas with low dose rates but high collective dose. Identify any high radiation areas with significant dose rate gradients (factor of 5 or more), including underwater diving activities.
G List or map of HRAs, LHRAs, HDR-HRAs (>25 rem in one hour @ 30 cm), and VHRAs.
Include areas with the potential to become a HRA during routine operations or outages.
G Internal dose assessments, including calculations, for any internal exposures greater that 50 mrem CEDE since the last inspection.
G List of corrective action reports generated since the last inspection related to access controls, including the following:
< Access controls, including high radiation area radiological incidents
< Radiological events caused by radiation worker errors
< Radiological events caused by radiation protection technician errors G Available for onsite review during the inspection:
< RWPs for the top five dose rate areas or tasks; RWPs for airborne activity areas.
< Elevation maps with most recent operating and outage radiation survey levels.
71122.03: Radiological Environmental Monitoring Program (REMP) and Radioactive Material Control Program G Site and corporate procedures associated with the REMP program, meteorological monitoring, and radioactive material control program. These procedures should include:
< Environmental sampling methodology for each matrix (e.g. TLD, ground and surface water, milk, vegetation, sediment, etc.) including sample collection, preparation, and analysis
< Calibration and maintenance of sampling equipment
< Calibration and QC activities for sample counting instruments
< Calibration, maintenance, and routine surveillance of meteorological instruments
< Control, survey and release of individuals and materials from the RCA
< Response to alarms at RCA and/or protected area exits
< Calibration, maintenance, and use of small article monitors, tool monitors, etc.
G Two most recent Annual Environmental Monitoring Reports [2006 and 2007]
G Calibration and maintenance records for air samplers and composite water samplers.
G Calibration records for environmental sample counting instruments, including control charts and LLD determination OR audits of quality control program of vendor laboratory used to analyze REMP samples, as appropriate.
G Interlaboratory comparison program results for the past two years (in-house laboratory or vendor laboratory). For in-house counting lab, quality control evaluation of results.
G Calibration/surveillance/maintenance records for the meteorological instruments since the last inspection.
G List of small article monitors, tool monitors, etc. and their locations (calibration records for select instruments will be requested by the inspectors after reviewing the list).
G G List of corrective action reports generated since the last inspection related to the REMP and Radioactive Material Control program, including the following:
< REMP program, including sampling and sample analysis Enclosure
4
< Meteorological monitoring program, including sensor problems, tower unavailability and data transmission/display discrepancies
< Radioactive material control 71122.01 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems G Site and corporate procedures/manuals associated with the radioactive effluents treatment and monitoring program. Procedures/manuals should include:
< Calibration and routine surveillance procedures for the effluent monitors listed below, including set-point determination.
< HP/Chemistry/Operations procedures for liquid and gaseous effluent sampling, analysis, and release, including release permit generation
< Calibration and use of the effluent sample counting laboratory instruments (gamma spectroscopy, liquid scintillation, gas proportional)
< Counting laboratory QC activities, including daily/weekly calibration checks, control charts, and interlaboratory comparison performance
< Surveillance activities on air treatment systems, including charcoal and HEPA filter testing
< Calculation of projected doses to members of the public from effluent releases G Two most recent Annual Radioactive Effluents Release Reports.
G Two most recent calibrations for the following effluent monitors, including flow meter calibrations:
< Containment Vent Monitor Unit 1
< Condenser Off-gas monitor Unit 1
< Plant Main Vent/ Stack Monitor
< Plant Liquid Effluent Monitor
< Turbine Building Sump Monitor G List of time periods during which the above listed effluent monitors were out of service since the last inspection.
G Most recent liquid and gaseous continuous release permits and most recent liquid and gaseous batch release permits (4 total).
G Two most recent surveillances of the air cleanup system for the routine main plant Airborne effluent release pathway including flow rate determination and HEPA/charcoal efficiency determinations.
G Interlaboratory comparison program results for effluent sample counting laboratory since the last inspection.
G List of corrective action reports generated since the last inspection related to effluent monitoring equipment, effluent treatment systems, and air cleanup systems.
G Available for onsite review by inspector during inspection:
< Plant drawings sufficient to permit the inspector to walk-down the liquid and gaseous effluent processing systems and effluent/process radiation monitors to verify current system configuration/operation agrees with the descriptions contained in the UFSAR and ODCM.
< List/description of modifications and design changes, including procedural or operational changes, made to effluent treatment, monitoring, or sampling systems or to plant ventilation systems since the last inspection.
Enclosure
5 71121.03 Radiation Monitoring Instrumentation and Protective Equipment G Site and corporate procedures/manuals associated with radiation monitoring instrumentation and respiratory protection. Procedures/manuals should include:
< Operation, calibration, and maintenance of ARM, CAM, portal monitor (PM),
personnel contamination monitor (PCM), and tool monitors, including set-point determination
< Operation and calibration of Whole Body Counter (WBC) equipment
< Issuance/operation of portable survey instruments
< Calibration and maintenance of portable instruments (e.g. ion chambers, friskers, teletectors, rem-ball)
< Actions to be taken when portable instrument found to be significantly out of tolerance/calibration
< Issuance and use of respiratory protective equipment (emphasis on SCBA and air-supplied equipment)
< Training, including fit-testing, for use of SCBA and supplied-air systems
< SCBA maintenance activities, including vital components (i.e. regulators)
< Determination/verification of Grade D air for SCBA G If PASS capabilities have been modified through license amendment, provide a copy of the amendment and applicable SER G Two most recent surveillances of PASS equipment (or equivalent equipment as approved by license amendment)
G Two most recent calibrations for the following ARM/CAM equipment for Unit 1:
< Control Room Area Radiation Monitor
< Spent Fuel Pool Area Radiation Monitor
< Letdown or RHR System Area Radiation Monitor
< Spent Fuel Pool Ventilation Monitor/CAM
< Auxiliary Building Air Monitor
< Containment Air Monitor G Two most recent calibrations for PCMs and PMs located at the RCA exit.
G Most recent calibration of WBC and copy of the analysis library.
G Records of certification of air quality for equipment used to provide breathing air for air-supplied respirators and SCBA bottles since the last inspection.
G List of corrective action reports generated since the last inspection involving radiation monitoring and protective equipment deficiencies, including the following:
< Area radiation monitors and continuous air monitors
< Portable instrumentation, PCM, PM, and WBC monitoring equipment
< Respiratory protection equipment and program implementation.
G Available for onsite review by inspector during inspection:
< Inventory, inspection, and maintenance records for SCBA equipment
< Training records, including fit-testing, for SCBA-qualified individuals
< Training records/certification for individuals qualified to perform maintenance on vital components (e.g. regulators) on SCBA