RA-13-012, Capability to Perform Multi-Unit Dose Assessment

Capability to Perform Multi-Unit Dose Assessment

ML13190A313
Person / Time
Site:	Harris, Brunswick, Crystal River, Robinson
Issue date:	06/26/2013
From:	Annacone M Carolina Power & Light Co, Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-13-012
Download: ML13190A313 (4)

Text

DUKE ENERGY, Michael 526 SouthJ. Annacone Church Charlotte, NC 28202 Street Mailing Address:

Mail Code EC07H / P.O. Box 1006 Charlotte, NC 28201-1006 980-373-2544 704-382-6056 fax Serial: RA-13-012 June 26, 2013 10 CFR 50.4 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Brunswick Steam Electric Plant, Unit Numbers 1 and 2 Docket Numbers 50-325 AND 50-324/Renewed License Numbers DPR-71 AND DPR-62 Crystal River Unit 3 Nuclear Generating Plant Docket Number 50-302/License Number DPR-72 Shearon Harris Nuclear Power Plant, Unit Number 1 Docket Number 50-400/Renewed License Number NPF-63 H. B. Robinson Steam Electric Plant, Unit Number 2 Docket Number 50-261/Renewed License Number DPR-23

Subject:

Carolina Power & Light Company (CP&L) and Florida Power Corporation (FPC)

Capability to Perform Multi-Unit Dose Assessment

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)

3. Duke Energy Letter, Crystal River Unit 3 Certification of permanent cessation of power operations and that fuel has been permanently removed from the reactor, J. A. Franke to U.S. NRC, Dated 2/20/13, Serial No. 3F0213-07 (ADAMS Accession Number ML13056A005)

In accordance with Reference 1, this letter, from Duke Energy Progress, Inc., formally known as Carolina Power & Light Company, and Duke Energy Florida, Inc., formally known as Florida Power Corporation, hereby provides the following information concerning the capability to perform offsite dose assessment during an event involving multiple release pathways (e.g.,

releases from reactor containments and spent fuel pools) at the Brunswick, Crystal River, Shearon Harris, and H. B. Robinson 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 at the Brunswick, Crystal River, Shearon Harris, and H. B. Robinson Nuclear Stations would take the following actions:

United States Nuclear Regulatory Commission RA-1 3-012 Page 2 Qualified dose assessors at each nuclear station perform individual dose assessment calculations using Nuclear Regulatory Commission (NRC) dose assessment model RASCAL (Radiological Assessment and Consequence Analysis), Version 3.0.5. The program does not have the capability to perform simultaneous multiple release point calculations. During a multiple release point event, individual dose assessment results are manually summed to determine total offsite dose to the public.

2. Anticipated schedule to establish multi-unit/multi-source dose assessment capability on an interim and/or permanent basis if required.

Manual summation of dose assessment results provides an interim capability and will continue to be performed until implementation of a multi-unit/multi-source software code.

Brunswick, Shearon Harris, and H. B. Robinson will compile design data supporting modeling with a multi-source/multiple release pathway software code such as Raddose V or multi-source/multiple release point modeling capable version of Unified RASCAL Interface (URI), test the new program, develop relevant procedures, perform training, and complete implementation 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).

Duke Energy will identify and track key actions through the corrective action program (CAP) as Action Request (AR) 610491.

On February 20, 2013, Duke Energy Florida, Inc. certified to the NRC the permanent removal of fuel from the Crystal River Unit 3 reactor vessel. Therefore, Duke Energy has no plans to establish multi-unit/multi-source dose assessment capability at the Crystal River nuclear station.

This letter contains one new voluntary regulatory commitment for Brunswick, Shearon Harris, and H.B. Robinson Nuclear Stations. That voluntary regulatory commitment is identified in . Any other 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 (michaeL austin@duke-energy.corn).

Sincerely, ichael J. Annacone, Vice President - Organizational Effectiveness &

Regulatory Affairs Enclosure

1. Table of New Voluntary Regulatory Commitments

United States Nuclear Regulatory Commission RA-13-012 Page 3 cc: USNRC Region II,Regional Administrator USNRC Region I, Regional Administrator USNRC Resident Inspector - BSEP, Unit Nos. 1 and 2 USNRC Resident Inspector - SHNPP, Unit No. 1 USNRC Resident Inspector - HBRSEP, Unit No. 2 S. T. Hammann (NRC Region I, DNMS/DB)

C. Gratton, NRR Project Manager - BSEP, Unit Nos. 1 and 2: CR-3 A. T. Billoch-Col6n, NRR Project Manager - SHNPP, Unit No. 1; HBRSEP, Unit No. 2 D. H. Jaffe, NRR/JLD/PMB, NRC Ms. Sue Perkins-Grew, NEI

RA-13-012 Enclosure Enclosure 1 Table of New Voluntary Regulatory Commitments Below is a table of actions that are described within this document and considered voluntary regulatory commitments. Any other statements in this document are provided for information purposes and are not considered to be regulatory commitments.

Commitment Action Request Scheduled Number Completion Date 1 Brunswick, Shearon Harris, and H. B. Robinson 610491 December 31, 2014 will compile design data supporting modeling with a multi-source/multiple release pathway software code such as Raddose V or multi-source/multiple release point modeling capable version of Unified RASCAL Interface (URI), test the new program, develop relevant procedures, perform training, and complete implementation by December 31, 2014.