ML14296A689

Summary of September 18, 2014, Meeting with Firstenergy Nuclear Operating Company to Discuss Alternative Source Term Implementation as a Result of Fuel Change

ML14296A689
Person / Time
Site:	Perry
Issue date:	11/10/2014
From:	Ellen Brown Plant Licensing Branch III
To:	FirstEnergy Nuclear Operating Co
Eva Brown, NRR/DORL 415-2315
References
Download: ML14296A689 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 10, 2014 LICENSEE: FirstEnergy Nuclear Operating Company FACILITY: Perry Nuclear Power Plant, Unit 1

SUMMARY

OF SEPTEMBER 18, 2014, MEETING WITH FIRSTENERGY NUCLEAR OPERATING COMPANY TO DISCUSS ALTERNATIVE SOURCE TERM IMPLEMENTATION AS A RESULT OF FUEL CHANGE On September 18, 2014, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a Category 1 public meeting with FirstEnergy Nuclear Operating Company (FENOC, the licensee) at NRC Headquarters, 11555 Rockville Pike, One White Flint North, Rockville, Maryland. The purpose of the meeting was to discuss changes to the previously approved full implementation of alternative source term (AST) to reflect a change from General Electric-14 to Global Nuclear Fuel-2 at Perry Nuclear Power Plant, Unit 1 (Perry). The enclosure contains a list of attendees.

BACKGROUND In a letter dated December 6, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13343A013), FENOC submitted a revision of the Perry Updated Safety Analysis Report to reflect updated radiological calculations performed using an AST and a modification of the definition of DOSE EQUIVALENT IODINE-131 in the technical specifications. The NRC staff issued discussion topics in support of this meeting which can be found at ADAMS Accession No. ML14246A201).

DISCUSSION The first discussion topic was related to the how the shine dose from the control room emergency recirculation filter system was evaluated as a contributor to the control room loss-of-coolant-accident dose consequence analysis. The licensee discussed that RADTRAD

[Radionuclide Transport and Removal and Dose Estimation) and MicroShield© methodologies were used to determine the shine dose. Additionally some of the assumed conservatisms were listed.

The second discussion topic was related to the calculation of dispersion factors used in the Technical Support Center (TSC) dose consequence analysis. Section 1.3.1 of Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," mentions the potential application of AST to emergency response facilities (ERFs) consistent with NUREG 0737, "Clarification of TMI [Three Mile Island] Action Plan Requirements." This NUREG, as supplemented, indicates that the licensee is to ensure that the radiological dose to individuals within ERFs be limited to 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident. The licensee indicated that the no information was submitted related to the TSC as the analyses performed in the 1980s were not revised. The licensee indicated that if the dose in the TSC approached unacceptable

limits, licensee staff could be relocated to a facility offsite over 10 miles away. The licensee indicated that the location of this alternate TSC excludes it from the need for further evaluation related to the dose consequences to TSC staff. The NRC staff requested that the licensee provide information related to the licensee's TSC analyses on the docket.

The third discussion topic was related to addressing the basis for the use of one set of control room dispersion factors for all release points evaluated in the AST accident dose consequence evaluations. The licensee described the method used as well as additional testing that was performed to refine the analysis. It was indicated that the use of one set of dispersion factors was submitted and reviewed by the NRC staff in the late 1990's. The licensee offered to provide any needed information to support confirmation of the NRC staff's approval. The NRC staff indicated that a review of the past approval would be performed and additional questions asked if necessary.

No members of the public were in attendance, and no feedback forms were received. No commitments or regulatory decisions were made by the NRC staff during the meeting.

Sincerely, IRA/

Eva A. Brown, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-440

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv

Participants U.S. Nuclear Regulatory Commission (NRC)

Public Meeting with FirstEnergy Nuclear Operating Company Regarding Updated Alternative Source Term John Parillo Jason White Eva Brown FirstEnergy Nuclear Operating Company Tom Lentz Phil Lashley Albert Widmer Rob Moreland Thom Thomlinson Paul Gilles Bradley Ferrell Marvin Morris Mark Dewall Enclosure

ML14296A689 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME EBrown SRohrer TTate DATE 10/28/14 10/28 /14 11/10/14