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Category:Letter type:L
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2024-01-24
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Text
Perry Nuclear Power Plant
~
to Center Road Perry. Ohio 44081 RrstEnergy Nuclear Operating Company Vito A. Ksminskas 440-280-5382 Vice President Fax: 440-280-8029 December 17, 2012 L-12-447 10 CFR 50.46 A TIN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Perry Nuclear Power Plant, Unit No.1 Docket No. 50-440, License No. NPF-58 Report of Changes Pursuant to 10 CFR 50.46 On November 29,2012, Global Nuclear Fuel- Americas, LLC (GNF) issued a change in the evaluation model regarding the. emergency core cooling system (ECCS) -loss of coolant accident (LOCA) methodology used for the Perry Nuclear Power Plant (PNPP).
Pursuant to 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," FirstEnergy Nuclear Operating Company (FENOC) is notifying the Nuclear Regulatory Commission (NRC) of this change.
The change is associated with* a change in ECCS-LOCA analysis -- from the GESTR*
LOCA to utilization of the PRIME fuel properties. The estimated result is the PNPP post LOCA peak cladding temperature (PCT) has increased by 20 degrees Fahrenheit (OF).
The attachment contains a summary of the 10 CFR 50.46 changes and errors, including the most recent change, applicable to the GE14 fuel in use at PNPP. The summation of the absolute values of these changes and errors results in a value that meets the definition of a significant change as defined by 10 CFR 50.46(a)(3)(i). Therefore, pursuant to 10 CFR 50.46(a)(3)(ii), NRC notification of the recent error is required within 30 days.
As a result of incorporating this change and previously reported changes and errors, the .
PNPP PCT is 15700F and continues to satisfy the 10 CFR 50.46(b)(1) criteria of PCT not to exceed 22000F .
Perry Nuclear Power Plant, Unit No.1 L-12-447 Page 2 The impact on the ECCS evaluation model does not result in any challenge to the 10 CFR 50.46(b) acceptance criteria. This change has been evaluated and there are no other known errors or changes to be evaluated at this time. The overall evaluation model is considered acceptable; therefore, a reanalysis is not required.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager-Fleet Licensing, at (330) 315-6810.
Sincerely, VJa.
Vito A. Kaminskas
Attachment:
Perry Nuclear Power Plant 10 CFR 50.46 Changes and Errors cc: NRC Region III Administrator NRC Resident Inspector NRC Project Manager
Attachment L-12-447 Perry Nuclear Power Plant 10 CFR 50.46 Changes and Errors Page 1 of 1 Vendor Summary of Change/Error licensing Basis Peak Licensee Report of Notification Clad Temperature (PCT) Notification Number Impact (Accession No.)
2001-02 Impact of SAFER' pressure PCT impact for GE 14 ML020710641 rate inconsistency error. fuel is +5 degree Fahrenheit (OF).
2002-01 Impact of SAFER core spray PCT impact for GE14 ML030710170 injection elevation error. fuel is +15°F.
2002-02 Impact of SAFER bulk water PCT impact for GE 14 ML030710170 level error. fuel is OaF.
2002-04 Impact of SAFER04 PCT Impact for GE14 ML030710170 computer platform change. fuel is OaF 2002-05 Impact of error in WEVOL2 PCT impact for GE14 ML030710170 calculation of downcomer free fuel is OaF.
volume.
2003-01 Impact of SAFER levell PCT impact for GE14 ML040710502 volume table error. fuel is +5°F.
2003-03 Impact of SAFER initial steam PCT Impact for GE14 ML040710502 separator pressure drop fuel is OaF.
error.
2003-05 Impact of postulated PCT impact for GE14 ML040710502 post-LOCA3 hydrogen-oxygen fuel Is OaF.
recombination.
2006-01 Impact of top peaked power PCT impact for GE14 ML062490520 shape for small break LOCA fuel Is OaF. ML070390113 analysis.
2011-02 Impact of database error for PCT impact for GE 14 ML112290919 heat deposition for fuel is +25°F.
10X10 fuel bundles.
2011-03 Impact of updated formulation PCT impact for GE14 ML112290919 gamma heat deposition to fuel is -40oF.
channel wall for 10X10 fuel bundles.
2012-01 Impact of change in fuel PCT impact for GE14 This submittal properties from GESTR fuel is +20oF.
to PRIME )
TOTAL Summation of the absolute 110°F values of the changes/errors.
Notes: 1. SAFER - Name of the code developed by General Electric Company which calculates long term reactor vessel inventory and peak cladding temperature for LOCA and loss of inventory events.
- 2. WEVOL - Name of a code that is used to calculate the weight and volume inputs for jet pump plant SAFER analyses.
- 3. LOCA - Loss of coolant accident.
