ML13281A530

Meeting Slide for FENOC - NRC Pre-Submittal Meeting Request for Licensing Action

ML13281A530
Person / Time
Site:	Perry
Issue date:	10/15/2013
From:	FirstEnergy Nuclear Operating Co
To:	Ellen Brown Plant Licensing Branch III
Brown E
References
Download: ML13281A530 (15)

Text

FENOC - NRC Pre-Submittal Meeting Request for Licensing Action October 15, 2013 Perry Nuclear Power Plant

FENOC Representatives Doug Reeves, Director - Site Engineering Robb Borland, Director - Nuclear Fuel & Analysis Ben Huck, Manager - Design Engineering Tom Lentz, Manager - Fleet Licensing Paul Gilles, Supervisor - Core Design Phil Lashley, Supervisor - Fleet Licensing Al Widmer, Nuclear Engineering Analysis Brad Ferrell, Licensing Engineer Nicole Schlichting, Core Design Engineer Tom Tomlinson, Project Manager Marvin Morris, Enercon 2

Requested Licensing Action Proposed Licensing Action Scope Full implementation of alternative accident source term (AST) for PNPP design basis accident analyses, using RADTRAD and GNF2 fuel source term Updated Safety Analysis Report (USAR) changes included for NRC review/approval One Technical Specification change (I-131)

Requested for spring 2015 refueling outage 3

Current Design Basis Accident Analysis Amendment 103 (March 1999) was a pilot plant application of an alternative AST for a Loss Of Coolant Accident (LOCA)

Amendment 112 (June 2000 power uprate) looked at four of the design basis events, and scaled prior dose calculation results in order to bound the uprate Amendment 122 (March 2003) analyzed the Fuel Handling Accident using an alternative AST and RADTRAD 4

Regulatory Requirement Governing Submittal 10 CFR 50.59 requires reviews of changes including items such as departures from a method of evaluation previously used in the safety analyses 10 CFR 50.67(b)(1) requires licensees who seek to revise their current accident source term in design basis radiological consequence analyses to apply for a license amendment per 10 CFR 50.90, including an evaluation of the consequences of applicable design basis accidents previously analyzed in the safety analysis report 5

LOCA Calculation Polestar Applied Technology methodology is replaced with RADTRAD Current core source term is updated for GNF2 Expanded guidance in Regulatory Guide 1.183 is used 6

LOCA Calculation Results Current Revised Acceptance Location Analysis Analysis Criteria (rem TEDE) (rem TEDE) (rem TEDE)

EAB 21.2 21.2 25 LPZ 10.1 6.5 25 Control Room 4.3 2.8 5 7

LOCA Dose Calculation Key Input Changes Isotopes Gap Release Pressure Reduction at 24 Hours Control Room Filtration Aerosol Removal in Containment Dose Conversion Factors Containment Spray Initiation 8

Control Rod Drop Accident Calculation Revised calculation uses Regulatory Guide 1.183 Revised calculation uses RADTRAD TID 14844 source term is updated to GNF2 source term Current TID 14844 whole body and thyroid doses converted to a TEDE dose for comparison purposes on next slide 9

CRDA Calculation Results Converted TEDE Revised Acceptance Location Dose (rem) Analysis Criteria (rem TEDE) (rem TEDE)

EAB 0.07206 0.161 6.3 LPZ 0.3896 0.162 6.3 Control Room Not Previously 0.263 5 Required 10

Main Steam Line Break Calculation Current TID 14844 source term is updated to Regulatory Guide 1.183 source term Revised calculation uses Regulatory Guide 1.183 Revised calculation uses RADTRAD Current TID 14844 whole body and thyroid dose converted to TEDE dose for comparison 11

MSLB OC Calculation Results (4 Ci/g)

Converted TEDE Revised Acceptance Location Dose (rem) Analysis Criteria (rem TEDE) (rem TEDE)

EAB 3.597 1.17 25 LPZ 0.458 0.131 25 Control Room Not Previously 0.622 5 Required 12

Dose Calculation Results Summary All revised calculations conform to the methodology in Regulatory Guide 1.183, including the use of RADTRAD All calculated doses meet Regulatory Guide 1.183 acceptance criteria No calculated doses increase by more than 10% of the margin to the regulatory limit 13

Regulatory Evaluation 10 CFR 50.90 application submitted in accordance with 10 CFR 50.59 and 10 CFR 50.67 No significant hazards No change to the site Environmental Plan No impact on the environment 14

Requested Licensing Action Next Steps:

Submittal planned for November 2013 NRC review requested to support spring 2015 refueling outage 15