ML17076A141

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Notification of Inspection Request for Information
ML17076A141
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/16/2017
From: Brian Bonser
NRC/RGN-II/DRS/PSB1
To: Lane N
Virginia Electric & Power Co (VEPCO)
References
Download: ML17076A141 (7)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 March 16, 2016 Mr. N. Larry Lane Site Vice President Surry Power Station Virginia Electric & Power Company 5570 Hog Island Road Surry, VA 23883-0315

SUBJECT:

SURRY POWER STATION, NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Lane:

During the week of May 15 - May 19, 2017, the Nuclear Regulatory Commission (NRC) will perform a baseline Radiation Safety Inspection at Surry Power Station, (NRC Inspection Procedures 71124.01 and 71124.08). 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/DVD format on or before May 5, 2017.

We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Terri Cuthriell (Terri.S.Cuthriell@dom.com) of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Robert Kellner at (404) 997-4508, 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 3150-0008, 3150-0011, 3150-0014, 3150-0044, 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.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public inspections, exemptions, requests for withholding, of the NRCs Agency Rules of Practice and Procedure, 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

L. Lane 2

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. 50-280, 50-281 License No. DPR-32, DPR-37

Enclosure:

Pre-Inspection Document Request cc: Distribution via Listserv

L. Lane 3

SUBJECT:

SURRY POWER STATION, NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION Distribution:

A. Masters, RII, DRP BC S. Ninh, RII, SR PE B. Bishop, RII, PE E. Andrews, Acting SRI C. Jones, RII, RI PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE NON-SENSITIVE ADAMS:

Yes ACCESSION NUMBER:_________________________

SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE RXK3 VIA EMAIL BRB1 NAME RKELLNER BBONSER DATE 3/15 /2017 3/16/2017 E-MAIL COPY?

YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME:

G:\\DRSII\\PSB1\\RFI INFORMATION REQUEST LETTERS\\SURRY\\2017\\SUR_ 2017002_PSB1_DOC REQUEST_DRAFT.DOCX

Pre-Inspection Document Request Occupational and Public Radiation Safety Cornerstones Inspection Dates:

May 15 - May 19, 2017 Documents Due by:

May 5, 2017 Licensee:

Surry Power Station Docket Number(s):

05000280 and 05000281 Inspection Procedures (IPs): IP 71124.01 Radiological Hazard Assessment and Exposure Controls IP 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage 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 inspection procedure 71124.01 is requested from December 1, 2016 to the present, and from October 1, 2015 to the present for inspection procedure 71124.08, unless otherwise noted. This reflects the last time these 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 on-site review.

If you have any questions, please call Robert Kellner at (404) 997-4508. Thank you in advance for your effort in putting together this material.

Miscellaneous

1.

List of primary site contact(s) for each inspection area including name(s) and telephone numbers.

2.

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

3.

List of radiation protection procedures, including title and number.

4.

Corrective Action Program (CAP) procedure(s).

2 71124.01 - Radiological Hazard Assessment and Exposure Controls (Last Inspected November 2016)

1.

List of current on-line and planned outage Radiation Work Permits (RWPs), including their administrative limits, electronic dosimeter dose rate limit, and dose limit.

2.

List of locations, or plant maps indicating the location, of all LHRAs and VHRAs. Include areas with the potential to become a LHRA during routine operations or outages.

3.

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

4.

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.).

5.

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

6.

List of Nationally Tracked Sources, change of owner ship and copies of any National Source Tracking System (NSTS) transaction documentation (e.g., annual reconciliation).

7.

Most recent sealed source inventory record.

8.

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

9.

All self-assessments and audits covering HP controls since December 1, 2016.

10. List of CAP nonconformance reports (AR, CR, NCR, etc.) related to HP controls (e.g.

keyword searches for radworker error, HP technician error, posting issues, HRA/LHRA/VHRA issues, survey problems, etc.) issued since December 1, 2016. This should include CAP nonconformance reports where the cause was listed as human performance. This should be a list of corrective action documents containing an (AR, CR, NCR, etc.) number and brief description, not full documents.

11. All CAP nonconformance reports (AR, CR, NCR, etc.) related to Nationally Tracked Sources since December 1, 2016.

71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation (Last Inspected October 2015)

1.

All procedures/guidance documents describing licensee compliance with 10 CFR Parts 20, 61, and 71, and 49 CFR Parts 170-189. Procedures/manuals should include:

Solid and liquid radwaste processing procedures.

Procedure(s) for transferring radioactive waste resin and sludge discharges into shipping/disposal containers.

Waste stream mixing and/or sampling procedures, including: (1) waste concentration averaging; (2) use of scaling factors and calculations used to account for difficult-to-measure radionuclides; and (3) ensuring waste stream composition data accounts for changing operational parameters.

Shipping/transportation procedures.

Cask loading and closure procedures (licensee and vendor) applicable to last three cask transports.

List of Radioactive Material (RAM) storage areas, including satellite RCAs.

Monitoring impact of long-term storage (e.g. build-up of gases produced by waste decomposition, chemical reactions, container deformation, loss of container integrity, rerelease of free-flowing water).

Process Control Program (PCP).

3

2.

Liquid and solid radwaste system diagrams and detailed system descriptions (e.g.,

information that might be contained in curricula for training new system engineers)

3.

List of all shipments made since September 1, 2015 (shipping logs)

4.

List, and documentation, of any changes made to the radioactive waste processing systems (liquid and solid) and/or the PCP since September 2015, and associated 10 CFR Part 50.59 documentation, as appropriate.

5.

List of all abandoned solid and liquid radwaste processing equipment

6.

Last two 10 CFR Part 61 analyses for each waste stream (DAW, resins, filters, etc.),

including quality assurance data (e.g., in-house vs. vendor lab comparisons, current results vs. database)

7.

Copies of applicable transport cask Certificate of Compliance for the last three transport cask shipments.

8.

Most recent self-assessment or audit of Shipping/radwaste processing and RAM storage programs.

9.

List of CAP nonconformance reports (AR, CR, NCR, etc.) related to involving radioactive waste and radioactive material processing and/or transportation (e.g. keyword searches for RAM, shipping, radwaste, Part 61, etc.) issued since September 1, 2015. [This should be a searchable list of corrective action documents containing a number and brief description, not full CRs.]

10. Available for onsite review during the inspection:

Site drawing(s) showing the location of all stored radioactive materials and all stored radioactive waste.

Plant drawings sufficient to permit the inspector to walk-down the liquid and solid radioactive waste processing systems to verify current system configuration/ operation agree with the descriptions contained in the UFSAR and in the PCP.

Documentation describing the status of any radioactive waste process equipment that is not operational and/or is abandoned in place.

Information concerning the sites waste disposal volume and waste reduction program.

Training and qualification records for personnel responsible for radioactive waste 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.

Assistance Requested During On-Site Inspection Identification of work activities available during the inspection for inspector observations, including notification of pre-job briefings, notification of risk significant work activities, and audio/visual surveillance for remote job coverage Health physics assistance in plant walk-downs assessing access controls, e.g.

verifying the posting and locking of entrances to high and very high radiation areas (HRA and VHRA), and SFP controls.

Health physics assistance in plant walk-downs/job coverage of ongoing activities to assess access controls Inspector Contact Information:

Robert Kellner Sr. Health Physicist US NRC Region II (404) 997-4508 robert.kellner@nrc.gov Mailing Address:

U.S. Nuclear Regulatory Commission Region II ATTN: Mr. Robert Kellner 245 Peachtree Center Ave., N.E, Suite 1200 Atlanta, GA 30303

4 LIST OF ACROYNMS CAP Corrective Action Program DAW Dry Active Waste HRA High Radiation Area LHRA Locked High Radiation Area NSTS National Source Tracking System PCP Process Control Program RAM Radioactive Material RWP Radiation Work Permit UFSAR Updated Final Safety Analysis Report VHRA Very High Radiation Area