ML13190A316

Units 1 and 2, Oconee, Units 1, 2, and 3, Capability to Perform Multi-Unit Dose Assessment Capability

ML13190A316
Person / Time
Site:	Oconee, Mcguire, Catawba, McGuire
Issue date:	06/26/2013
From:	Annacone M J Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13190A316 (3)

Text

DUKE Michae J. Annacone 526 South Church Street ENERGY, Charlotte, NC 28202 Mailing Address: Mail Code EC07H / P.O. Box 1006 Charlotte, NC 28201-1006 980-373-2544 704-382-6056 fax June 26, 2013 1 0CFR50.4 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Catawba Nuclear Station (CNS), Units 1 and 2 Docket Numbers 50-413 and 50-414 Renewed License Numbers NPF-35 and NPF-52 McGuire Nuclear Station (MNS), Units 1 and 2 Docket Numbers 50-369 and 50-370 Renewed License Numbers NPF-9 and NPF-17 Oconee Nuclear Station (ONS), Units 1, 2, and 3 Docket Numbers 50-269, 50-270, and 50-287 Renewed License Numbers DPR-38, DPR-47, and DPR-55

Subject:

Duke Energy Carolinas, LLC, Capability to Perform Multi-Unit Dose Assessment Capability

Reference:

1. Nuclear Energy Institute (NEI) Letter, Commitment for Implementation of Multi-Unit Dose Assessment Capability;.

Pollock to Wiggins; dated March 14, 2013 (ADAMS Accession Number ML13073A522)

2. NRC Letter, Industry Implementation of Multi-Unit Dose Assessment Capability, Wiggins to Pollock; dated February 27, 2013 (ADAMS Accession Number ML13029A632)

In accordance with Reference 1, Duke Energy Carolinas, LLC, hereby provides the following information concerning the capability to perform offsite dose assessment during an event involving multiple release points (e.g., releases from reactor containments and spent fuel pools)at the Catawba, McGuire, and Oconee Nuclear Stations: 1. Summary of current capability to perform multi-unit/multi-source dose assessment.

In the event of a multi-source or multi.-unit release accident, dose assessors would take the following actions: Qualified dose assessors responding to the onsite Technical Support Center (TSC) and the offsite Emergency Operations Facility (EOF) located in Charlotte, North Carolina, initiate dose assessment functions within 75 minutes of a declared emergency.

Radioactive releases are modeled using the computer software program Raddose V and procedure SH/0/B/2005/001, Emergency Response Offsite Dose Projections.

U. S. Nuclear Regulatory Commission June 26, 2013 Page 2 The components of the Raddose V program used by dose assessors allows for evaluating up to five concurrent release pathways for each calculated step. For each release pathway, one out of ten accident types can be specified, including a loss of coolant accident (LOCA), steam generator tube rupture, LOCA outside containment, and a fuel handling accident.Each accident type can model accident spectrums associated with normal reactor coolant, fuel gap releases or core melt. Raddose V can also model other onsite radiation monitors including unit vent low, high, and high-high range monitors concurrently.

Other onsite units can be also modeled using a direct isotopic sample entry (pCi/ml) or release rate, if known (Ci/sec).The Raddose V program determines source term and calculates projected offsite dose to the public on a per unit basis. Therefore, in order to perform multi-unit dose assessments, the Raddose V program must be run from more than one computer workstation and the results summed together.

Currently, the Raddose V program is installed on multiple computer workstations located within each station's TSC and the EOF.2. Anticipated schedule to establish multi-unit/multi-source dose assessment capability on an interim and/or permanent basis if required.Duke Energy has the capability to perform multi-unit/multi-source dose assessments.

Notwithstanding, procedural enhancements have been identified that, when implemented, will strengthen that capability.

The identified procedural enhancements are expected to be implemented by December 31, 2014.3. A description of the administrative process that will be used to track completion of key actions (e.g., commitment tracking or corrective action program and tracking identifiers).

No key actions or milestones were identified.

The procedural enhancements identified in response to Item 2, however, will be tracked within the corrective action program as Problem Investigation Program (PIP) G-13-0585.

This letter does not contain any new or revised regulatory commitments.

Any actions discussed in this letter should be considered intended or planned enhancement actions.Should you have any questions concerning the content of this letter, please contact Michael Austin, at 980-373-4134 (michaelaustin@duke-energy.com).

Sincerely, Michael J. Annacone, Vice President

-Organizational Effectiveness

&Regulatory Affairs U. S. Nuclear Regulatory Commission June 26, 2013 Page 3 xc: V.M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 John Boska, Project Manager (ONS)U.S. Nuclear Regulatory Commission One White Flint North, Mailstop O-8G9A 11555 Rockville Pike Rockville, MD 20852-2738 J.S. Kim, Project Manager (MNS and CNS)U.S. Nuclear Regulatory Commission One White Flint North, Mailstop O-8C2A 11555 Rockville Pike Rockville, MD 20852-2738 E. L. Crowe NRC Senior Resident Inspector Oconee Nuclear Station J. Zeiler NRC Senior Resident Inspector McGuire Nuclear Station G. A. Hutto, III NRC Senior Resident Inspector Catawba Nuclear Station Justin Folkwein American Nuclear Insurers 95 Glastonbury Blvd., Suite 300 Glastonbury, CT 06033-4453 Ms. Sue Perkins-Grew, NEI Nuclear Energy Institute 1201 F St., NW, Suite 1100 Washington, DC 20004-1218