ML13281A530
| ML13281A530 | |
| Person / Time | |
|---|---|
| Site: | Perry  (NPF-058) |
| 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
2 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
3 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
4 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
5 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
6 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
7 LOCA Calculation Results Location Current Analysis (rem TEDE)
Acceptance Criteria (rem TEDE)
EAB 21.2 21.2 25 LPZ 10.1 6.5 25 Control Room 4.3 2.8 5
8 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
9 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
10 CRDA Calculation Results Location Converted TEDE Dose (rem)
Acceptance Criteria (rem TEDE)
EAB 0.07206 0.161 6.3 LPZ 0.3896 0.162 6.3 Control Room Not Previously Required 0.263 5
11 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
12 MSLB OC Calculation Results (4 Ci/g)
Location Converted TEDE Dose (rem)
Acceptance Criteria (rem TEDE)
EAB 3.597 1.17 25 LPZ 0.458 0.131 25 Control Room Not Previously Required 0.622 5
13 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
14 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
15 Requested Licensing Action Next Steps:
Submittal planned for November 2013
NRC review requested to support spring 2015 refueling outage