ML13247A708
| ML13247A708 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/04/2013 |
| From: | Brian Bonser NRC/RGN-II/DRS/PSB1 |
| To: | Heacock D Virginia Electric & Power Co (VEPCO) |
| Linda K. Gruhler | |
| References | |
| Download: ML13247A708 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 September 4, 2013 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Dominion Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
SURRY NUCLEAR STATION, NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION 05000280 AND 05000281
Dear Mr. Heacock:
From October 21 through October 25, 2013, the U.S. Nuclear Regulatory Commission (NRC) will perform the baseline Occupational Radiation Safety Inspection at the Surry Nuclear Station for NRC Inspection Procedures 71124.01 and 71124.08. Experience has shown that this inspection is resource intensive for both the NRC inspectors and your staff. 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 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.
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Jennifer Pollard of your organization, at (757) 365-2848, and that the material be available for review by October 11, 2013. If there are any questions about this inspection or the material requested, please contact the lead inspector, Ruben Hamilton at (404) 997-4672.
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 3150-0011, 3150-0014, and 3150-0135. 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.
D. Heacock 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), which is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA by Adam Nielsen Acting For/
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37
Enclosure:
Pre-Inspection Document List cc: Distribution via Listserv
D. Heacock 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), which is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA by Adam Nielsen Acting For/
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37
Enclosure:
Pre-Inspection Document List cc: Distribution via Listserv DISTRIBUTION:
C. Evans, RII, EICS L. Douglas, RII, EICS RIDSNRRDIRS PUBLIC RidsNrrPMSurry Resource PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE NON-SENSITIVE ADAMS: Yes ACCESSION NUMBER: ML13247A708 SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS/PSB1 RII:DRS/PSB1 SIGNATURE RKH1 ADN for BRB1 NAME R. Hamilton B. Bonser DATE 9/ 4 /2013 9/ 4 /2013 E-MAIL COPY YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: G:\DRSII\PSB1\RFI INFORMATION REQUEST LETTERS\SURRY\SURRY PSB1 RP 2013-005 DOC REQ LTR_COMMENTS (2).DOCX
Licensee: Surry Power Station Docket Numbers: 50-280 and 50-281 Inspection Dates: October 21 - 25, 2013 Procedure: 71124.01 Radiological Hazard Assessment and Exposure Controls 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation Note: The current version of these documents is expected unless specified otherwise.
Electronic media is preferred if readily available (The preferred file format is Word, WordPerfect, 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. Please organize the information as it is arranged below to the extent possible. Experience has shown that a well organized CD leads to a more efficient inspection and lessens additional burden on licensee staff. During the inspection, the inspectors may request additional documents. If the licensee wishes to use an electronic document service such as CERTRAC or a Shareware portal, the inspectors will try to accommodate for the documentation requested onsite. The initial documents should not require an internet connection to be reviewed.
Documents requested are referenced to last inspection date for that particular module.
If you have any questions, please call Ruben Hamilton at (404) 997-4672. Thank you in advance for your efforts in putting together this material.
General Information Needed
- Contact Phone Numbers for:
- a. Radiation Protection contacts
- b. Chemistry contacts
- Procedure for issuing Nuclear Condition Reports (CR) and assessing issues for risk significance and follow-up actions/ Corrective action program procedure.
- Updated Final Safety Analysis Report Chapters 11, Effluents/Radwaste; and Chapter 12 Radiation Protection.
- Current Part 61 Analysis Results for Dry Active Waste (DAW).
- Plant Management, Radiation Protection, and Chemistry organizational charts with contact numbers.
- Outage schedule of major activities (Gantt chart if available).
- Audits and self-assessments performed since the last inspection that encompasses the areas of (1) radiation protection, (2) access controls, (3) solid radioactive waste processing, and (4) shipping and transportation of radioactive material.
Enclosure
2 71124.01 Radiological Hazard Assessment and Exposure Controls (Last Inspected 5/18/12)
- List of outage RWPs.
- Plant maps of all Locked HRAs and VHRAs. Include areas with the potential to become a LHRA during routine operations or outages.
- Procedures related to 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.).
- 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 gradients (factor of five or more), including underwater diving activities.
- Procedures related to release of personnel and materials (e.g., release surveys, decontamination, guidance for alarm follow up, etc.).
- List of Nationally Tracked Sources and any change-of-ownership transactions.
- List of all non-fuel items stored in spent fuel pool.
- All self-assessments or audits covering HP controls since May 18, 2012, (if none, then provide the most recent)
- List of CRs related to HP controls where the cause was listed as human performance (radworker error) or human performance (HP technician error) issued since May 18, 2012. This should be a list of corrective action documents containing a CR number and brief description, not full CRs.
- All CRs related to Nationally Tracked Sources since May 18, 2012.
71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation (Last Inspected 10/14/2011)
- Site and corporate procedures associated with radioactive waste processing and handling, storage, and transportation of radioactive material (RAM), including:
- b. Waste stream mixing, sampling, concentration averaging, and use of scaling factors
- c. Monitoring impact of long-term storage (e.g., build-up of gases produced by waste decomposition, chemical reactions, container deformation, loss of container integrity, and re-release of free-flowing water)
- d. Transferring of resin and/or sludge into shipping/disposal containers; dewatering and waste stabilization
- e. Preparing packages and documentation for shipping radioactive materials
- Copies of applicable transport cask Certificate of Compliance for the last three transport cask shipments.
- List of changes to the radioactive waste processing systems since October 14, 2011, and copies of the associated 50.59 screening documentation.
3
- Log of radioactive material shipments (LSA I, II, IIII; SCO I, II, Type A, or Type B) since October 14, 2011. (The inspectors will select 3-5 packages to review in detail.)
- List of radioactive waste streams characterized for Part 61 (e.g., DAW, filters, resins, etc.)
- List of condition reports generated since October 14, 2011, related to radioactive solid waste processing and packaging, handling, storage, and shipping of radioactive materials.
- Available for onsite review during the inspection:
- a. Site drawing(s) showing the location of all stored radioactive materials and all stored radioactive waste.
- b. Plant drawings sufficient to permit the inspector to walkdown the liquid and solid radioactive waste processing systems to verify that the current system configuration and operation agree with the descriptions contained in the UFSAR and in the PCP.
- c. Documentation describing the status of any radioactive waste process equipment that is not operational and/or is abandoned in place.
- d. Information concerning the sites waste disposal volume and waste reduction program.
- e. Training curriculum and primary lesson plans for qualifying persons, including vendors, for radwaste processing, packaging, and making shipments of radioactive materials and radioactive waste, as specified by 49 CFR 172.