ML14069A552

RP RFI Letter

ML14069A552
Person / Time
Site:	Summer
Issue date:	03/10/2014
From:	Brian Bonser NRC/RGN-II/DRS/PSB1
To:	Gatlin T South Carolina Electric & Gas Co
Linda K. Gruhler 404-997-4633
References
Download: ML14069A552 (10)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 March 10, 2014 Mr. Thomas D. Gatlin Vice President - Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P.O. Box 88 Jenkinsville, SC 29065

SUBJECT:

VIRGIL C. SUMMER POWER STATION, NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Gatlin:

During the weeks of April 7 - 11, 2014, and April 21 - 25, 2014, the U.S. Nuclear Regulatory Commission (NRC) will perform a baseline Radiation Safety Inspection at V.C. Summer Power Station, (NRC Inspection Procedures (IPs) 71124.01, 71124.02, 71124.03, 71124.04, 71124.05, and the Radiation Safety Sections of 71151). In order to minimize the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for documents needed for this activity. It is important that all of these documents are up-to-date and complete, thereby minimizing the number of additional documents requested during the preparation and/or the onsite portions of the inspection. The NRC requests that these documents be provided to the inspectors in CD format on or before April 1, 2014.

We have discussed the schedule for these inspection activities with your staff, and understand that our regulatory contact for this inspection will be Ms. Susan Reese (803-345-4591) of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Ruben Hamilton at 404-997-4672, or the Plant Support Branch 1 Chief, Brian Bonser at 404-997-4653.

This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget under control numbers 3150-0044, 3150-0014, 3150-0011, and 3150-0008. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement, unless the requesting document displays a currently valid Office of Management and Budget control number.

T. Gatlin 2

In accordance with Title 10 of the Code of Federal Regulations (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 Agencywide Documents Access and Management System (ADAMS), accessible from the NRC web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket No. 50-395 License No. NPF-12

Enclosure:

Document Request List cc: Distribution via Listserv

T. Gatlin 2

In accordance with Title 10 of the Code of Federal Regulations (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 Agencywide Documents Access and Management System (ADAMS), accessible from the NRC web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket No. 50-395 License No. NPF-12

Enclosure:

Document Request List cc: Distribution via Listserv DISTRIBUTION:

S. Ninh, RII, SR PE B. Bishop, RII, PE J. Parent, RII, RIDP J. Reece, RII, SRI E. Coffman, RII, RI C. Evans, RII, EICS L. Douglas, RII, EICS RIDSNRRDIRS PUBLIC RidsNrrPMSummer Resource PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE NON-SENSITIVE ADAMS:

Yes ACCESSION NUMBER:

ML14069A552 SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS/PSB1 RII:DRS/PSB1 SIGNATURE RKH1 BRB1 NAME R. Hamilton B. Bonser DATE 3/ 6 /2014 3/ 10 /2014 E-MAIL COPY YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME:

G:\\DRSII\\PSB1\\RFI INFORMATION REQUEST LETTERS\\SUMMER\\SUMMER 2014003 RP RFI LETTER.DOCX

Enclosure DOCUMENT REQUEST LIST Occupational Radiation Safety Cornerstone Licensee:

Virgil C. Summer Power Station Docket Number(s):

50-395 Inspection Dates:

April 7-11, 2014, and April 21-25, 2014 Inspection Procedures:

71124.01 Radiological Hazard Assessment and Exposure Controls 71124.02 Occupational ALARA Planning and Controls 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 71124.04 Occupational Dose Assessment 71124.05 Radiation Monitoring Instrumentation 71151 Performance Indicator Verification Note: Unless specified otherwise, the current version of these documents is expected.

Electronic media is preferred if readily available (The preferred file format is MSWord, or searchable.pdf files on CDROM). Note that the inspectors cannot accept data provided on USB or flash drives due to NRC IT security policies. To the extent possible, please organize the information in the order shown below. Experience has shown that a poorly organized CD leads to a less efficient inspection and places additional burden on licensee staff. If there are questions regarding the documents requested, please do not hesitate to contact the lead inspector.

Documentation for the inspection procedures (IPs) from August 12, 2013, to the present is requested, depending on which procedure is being performed. This reflects the last time particular areas were inspected. 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 inspector will select documents/areas from the list for onsite review.

If you have any questions, please call Ruben Hamilton at 404-997-4672. Thank you in advance for your effort in putting together this material.

Assistance Requested During Onsite Inspection Identification of work activities available during the inspection for inspector observations, including notification of pre-job briefings, notification of diving activities, audio/visual surveillance for remote job coverage Health physics assistance in plant walkdowns assessing access controls (e.g., verifying the posting and locking of entrances to high and very high radiation areas (HRA and VHRA), and spent fuel pool (SFP) controls

2 Health physics assistance in plant walkdowns/job coverage of ongoing activities to assess access controls Discussions with appropriate individuals regarding access controls Miscellaneous

1.

Plant Management, Radiation Protection, and Chemistry organizational charts w/contact numbers.

2.

List of primary contacts for each inspection area with telephone numbers.

3.

Updated Final Safety Analysis Report (UFSAR) Chapter 11, Radioactive Wastes and Radiation Protection.

4.

List of radiation protection procedures that includes title and number.

5.

Outage schedule, including work activities to be conducted during the week(s) of the inspection.

6.

Most recent dry active waste (DAW) 10 CFR Part 61 analytical results.

7.

Corrective Action Program procedure(s).

8.

Procedure(s) for identifying, notification, tracking, and correcting performance indicators (PIs) occurrences.

9.

List of all PIs and copies of associated corrective action reports for Occupational Exposure Control Effectiveness and Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual (RETS/ODCM) Radiological Effluent Occurrences.

10.

Audits and self-assessments performed since August 12, 2013, that encompass the areas of; (1) the As Low As Reasonably Achievable (ALARA) program and implementation; (2) respiratory protection; (3) airborne radioactivity, monitoring and/or mitigation-engineering controls; and (4) radiological monitoring instrumentation (portable, installed, and counting room instruments).

71124.01 - Radiological Hazard Assessment and Exposure Controls

1.

List of active Radiation Work Permits (RWPs), including outage RWPs, with their administrative limits, electronic dosimeter dose rate limit, and dose limit.

2.

Most recent survey of all Locked HRAs and VHRAs (as applicable).

3.

Most recent survey of Independent Spent Fuel Storage Installation (ISFSI) areas.

4.

Procedures related to health physics (HP) controls (e.g., Posting, labeling, surveys, RWPs, contamination control, HRA/LHRA/VHRA control, key control, control of divers, special controls during fuel offload, hot spots, etc.).

5.

Procedures related to release of personnel and materials (e.g., release surveys, decontamination, guidance for alarm followup, etc.).

6.

List of Nationally Tracked Sources and any change-of-ownership transactions.

7.

List of all non-fuel items stored in spent fuel pool.

8.

All self-assessments and audits covering HP controls since August 12, 2013.

9.

List of condition reports (CRs) related to HP controls where the cause was listed as human performance (radworker error) or human performance (HP technician error) issued since August 12, 2013. This should be a list of corrective action documents containing a CR number and brief description, not full CRs.

10.

All CRs related to Nationally Tracked Sources since August 12, 2013.

3 71124.02 - ALARA Planning and Controls

1.

Site and corporate procedures associated with maintaining site dose ALARA, including those involving ALARA work activities. These procedures should include:

ALARA program implementation, including ALARA committee activities and ALARA planning, briefing, and reviews RWP preparation and worker compliance Processes used to estimate and track work activity specific exposures Making changes to dose estimates during task performance Work controls Engineering controls Exposure mitigation requirements

2.

Most recent annual ALARA report and most recent refueling outage report.

3.

Annual ALARA goals for 2013 and 2014, and the methodology utilized to make the projections.

4.

ALARA Committee activity summaries (e.g., meeting minutes) discussing activities associated with the upcoming refueling outage.

5.

Outline of the source term reduction strategy. Information should include:

Historic trends and current status of plant source term Factors that affect the source term Activities employed to reduce the source term Specific sources identified for reduction actions Source term reduction evaluation Results achieved since August 12, 2013

6.

List of corrective action reports generated since August 12, 2013, related to the ALARA program, including the following:

ALARA planning Post-job review identified problems Radiation worker practices Occurrences where the collective exposure was greater than intended dose determined to be ALARA for the individual work activities

7.

List of personnel monitored for radiation exposure that shows the total effective dose equivalent (TEDE) to date for each person. If possible, sort individuals by work group.

(Please do not provide any records which contain personally identifiable information such as social security number and name on the CD).

8.

Available for onsite review during the inspection:

ALARA planning packages for jobs to be performed during the outage Temporary shielding requests generated for the outage 71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

1.

Site and corporate procedures/manuals associated with airborne radiation monitoring instrumentation and respiratory protection. Procedures/manuals should include:

Operation, calibration, and maintenance of air sampling instrumentation, including set-point determination (e.g., low-vols, high vols, goosenecks, AMS 4s, etc.)

Calibration and maintenance of portable instruments

4 Actions to be taken when air sampling instrumentation is found to be significantly out of tolerance/calibration Issuance and use of respiratory protective equipment (emphasis on self-contained breathing apparatus (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

2.

Two most recent HEPA filter DOP and charcoal test results, or the following ventilation systems:

Main Control Room Auxiliary Ventilation Exhaust

3.

Two most recent calibrations for the following Continuous Air Monitoring (CAM) equipment:

RM-A1 Control Room Ventilation RM-A10 Spent Fuel Area

4.

Records of certification of air quality for equipment used to provide breathing air for air-supplied respirators and SCBA bottles (air compressors and bottled breathing air) since August 12, 2013.

5.

List of corrective action reports generated since August 12, 2013, involving radiation monitoring and protective equipment deficiencies, including the following:

Continuous air monitors Respiratory protection equipment and program implementation

6.

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 71124.04: Occupational Dose Assessment

1.

Provide Procedures/Guidance Documents for external dose monitoring (i.e., dosimetry issuance and use). The documents should include:

Guidance for multi-badging; monitoring in steep/highly variable dose rate gradients Personnel contamination events; storage/care of personal dosimeters; use of electronic dosimeters including evaluation of any biases identified relative to Thermoluminescent Dosimeter (TLD) monitoring Internal dose assessment (i.e., both in vivo and in vitro bioassay and air sampling capabilities). The documents should include guidance for calibration/quality control (QC) and use of whole body counter (WBC); release of contaminated individuals, use of passive monitoring as screening method for evaluations, and special in vitro sample collection and analysis, and actions for declared pregnant workers

2.

National Voluntary Laboratory Accreditation Program (NVLAP) accreditation documentation for current dosimetry used by the site.

3.

List of all positive WBC, in vitro, or air sampling analyses which resulted in an assigned committed effective dose equivalent (CEDE) equal to or exceeding 10 millirem since August 12, 2013. [Note: Only a listing should be provided for use by the inspectors to select a sample of issues for in-depth review during the onsite inspection].

5

4.

List of all personnel contamination events, dispersed contamination/discrete particles, identified since August 12, 2013. [Note: Only a listing should be provided for use by the inspectors to select a sample of issues for in-depth review during the onsite inspection].

5.

Copies of all audits, self-assessments, and/or reviews related to internal or external dosimetry issues generated since August 12, 2013. The documents provided should include any reviews/evaluations conducted of vendor facilities (e.g., corporate or outside vendor/ or corporate calibration facilities).

6.

Provide a list of CR documents generated since August 12, 2013, for internal or external dosimetry issues/events. [Note: Only titles and a summary statement should be provided for use by the inspectors to select a sample of issues for in-depth review].

71124.05 - Radiation Monitoring Instrumentation

1.

Procedures/Guidance Documents for:

use of portable instrument calibrators (e.g., Shepherd calibrator) calibration and functional test/source checks of portable radiation detection instrumentation calibration and functional tests of small article monitor (SAM), personnel contamination monitor (PCM), portal monitor (PM), whole body counting (WBC) equipment; and continuous air monitors (CAMs) determination of set-points for Area Radiation Monitor (ARM), CAM, PCM, personnel monitor (PM), and SAM equipment collection and analysis of high-range, post-accident effluent samples QA program for count room instruments (e.g., laboratory inter-comparison data)

2.

The last two calibration records for the following monitors:

RM-A3 Main Plant Vent Exhaust RM-L5 - Liquid Waste Disposal RM-A9 - Steam Generator Blowdown RM-G19 A, B, C - Main Steam Lines RM-A14 - Containment High Range Purge Exhaust Radiation Monitor RM-G18 - Containment High Range Area Monitor WBC systems in Dosimetry

3.

The last two surveillances performed on the Post-accident Sampling System, as applicable.

4.

The last two test record of the instrument calibrator (Shepherd validation testing/dose rate curves).

5.

List of the portable instruments currently in service and available for use. Several will be selected for onsite review of the calibration records.

6.

List of the following radiation monitors currently in service. Several will be selected for onsite review of the calibration records.

Portal Monitors used in Dosimetry for Passive Monitoring SAMs at radiological controlled area (RCA) exit point Whole Body Contamination Monitors at RCA exit point Portal Monitors at RCA exit point Countroom High-purity Germanium and liquid scintillation systems

7.

Documentation for the radioactive sources used to calibrate the above requested monitors showing traceability to a national standard (National Institute of Standards and Technology (NIST)) and traceability to the primary calibration, as applicable.

6

8.

Chart or procedure listing any Emergency Action Level (EAL) value associated with installed or portable radiation monitoring instrument indication(s).

9.

Copies of all audits, self-assessments, and/or reviews of area and personnel monitoring equipment, and portable radiation survey instruments generated since August 12, 2013.

The records should include any reviews conducted of vendor facilities (e.g., outside calibration laboratories) as applicable.

10.

List of CRs generated since August 12, 2013, related to portable instruments, effluent and area monitors, CAMs, RCA release point monitors, WBCs, and count room instruments. This should be a list of corrective action documents containing a CR number and brief description, not full CRs.

71151 - Performance Indicator Verification

1.

Site procedures/manuals for gathering and reporting performance indicator (PI) data.

2.

Monthly/Quarterly PI reports since August 12, 2013, and copies of associated condition reports for any RETS/ODCM Radiological Effluent occurrences.

3.

End of calendar year (CY) 2013 liquid and gaseous effluent release permits that specify the monthly, quarterly, and annual curies released by isotope, and associated public dose assessments.

4.

List of all corrective action documents since August 12, 2013, using keywords such as:

HRA, LHRA, VHRA, unintended dose, unlocked door, etc.

5.

List of all electronic dosimeter (ED) dose rate alarms and ED dose alarms since August 12, 2013.

6.

List of all corrective action reports generated since August 12, 2013, using keywords abnormal/ unmonitored effluent release, etc.

LIST OF ACRONYMS ALARA As Low As Reasonably Achievable ARM Area Radiation Monitor CAM Continuous Air Monitoring CEDE Committed Effective Dose Equivalent CR Condition Report DAW Dry Active Waste EAL Emergency Action Level ED Electronic Dosimeter HP Health Physics HRA High Radiation Areas IP Inspection Procedure ISFSI Independent Spent Fuel Storage Installations NIST National Institute of Standards and Technology NVLP National Voluntary Laboratory Accreditation Program PCM Personnel Contaminate Monitor PM Personnel Monitor QC Quality Control

7 RCA Radiological Controlled Area RETS/ODCM Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual RWP Radiation Work Permit SAM Small Article Monitor SCBA Self-contained Breathing Apparatus SFP Spent Fuel Pool TEDE Total Effective Dost Equivalent TLD Thermoluminescent Dosimeter UFSAR Updated Final Safety Analysis Report VHRA Very High Radiation Areas WBC Whole Body Count Inspector Contact Information:

Ruben Hamilton 404-997-4672 ruben.hamilton@nrc.gov Mailing Address U.S. Nuclear Regulatory Commission, Region II ATTN: Ruben Hamilton 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303