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Category:Letter type:L
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2024-01-24
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Text
FENOC Perry Nuclear Power Plant P.O. Box97 10 Center Road r~ ..r- m , /-.
- rs- Perry, Ohio 44081 FirstEnergy Nuclear Operating Company y Frank Payne 440-280-5382 Vice President November 19, 2019 L-19-269 10 CFR 50.46 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Report of ECCS Model Changes and Errors Pursuant to 10 CFR 50.46 On October 29, 2019, Global Nuclear Fuel - Americas, LLC provided a notification to FirstEnergy Nuclear Operating Company that identified an error in an acceptable evaluation model regarding the emergency core cooling system (ECCS) - loss of coolant accident (LOCA) analyses 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 the error.
The driving differential pressure for forward and backward bypass leakage is limited with an upper and lower limit in the SAFER code. The limits are implemented correctly on all but one of the nine leakage paths. The error occurred with the lower limit for the control rod guide tube to control rod drive housing interface backward leakage path.
A SAFER version correcting the lower limit on differential pressure for bypass leakage issue confirmed the software code error had no impact on the ECCS LOCA event evaluations. Therefore, the effect on peak cladding temperature is reported as 0°F.
The error and the impact of the error was reported for both the GE14 and GNF2 fuel-types. In Operating Cycle 17, PNPP had a mixed core of GE14 and GNF2 fuel. During the refueling outage that ended in April 2019, PNPP went to a complete core of GNF2 fuel.
The attachment contains a summary of the 10 CFR 50.46 changes and errors, including the most recent change, applicable to the GE14 fuel that had been used at PNPP. The summation of the absolute values of these changes and errors results in a value that
Perry Nuclear Power Plant L-19-269 Page 2 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, relative to the GE14 fuel. Although there is the same effect on the PCT for GNF2 fuel, NRC notification is not required, since the summation of absolute values of the changes and errors applicable to GNF2 fuel does not meet the definition of a significant change.
As a result of this error, along with previously reported changes and errors, the PNPP PCT for GE14 fuel remains 1555°F and continues to satisfy the 10 CFR 50.46(b)(1) criteria of PCT not to exceed 2200°F. Since PNPP no longer uses GEM fuel, a reanalysis is not warranted, and no other action is required.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Acting Manager - Nuclear Licensing and Regulatory Affairs, at (330) 315-6808.
Si Fra
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-19-269 Perry Nuclear Power Plant 10 CFR 50.46 Changes and Errors Page 1 of 2 Vendor Summary of Change/Error Licensing Basis Peak Licensee Report of Notification Cladding Temperature Notification Number (PCT) Impact (Accession No.)
2001-02 Impact of SAFER1 pressure PCT impact for GE14 ML020710641 rate inconsistency error. fuel is +5°F.
2002-01 Impact of SAFER core spray PCT impact for GE14 ML030710170 injection elevation error. fuelis+15°F.
2002-02 Impact of SAFER bulk water PCT impact for GE 14 ML030710170 level error. fuel is 0°F.
2002-04 Impact of SAFER04 PCT impact for GE14 ML030710170 computer platform change. fuel is 0°F 2002-05 Impact of error in WEVOL2 PCT impact for GE 14 ML030710170 calculation of downcomer free fuel is 0°F.
volume.
2003-01 Impact of SAFER level/ PCT impact for GE 14 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 0°F.
error.
2003-05 Impact of postulated PCT impact for GE14 ML040710502 post-LOCA3 hydrogen-oxygen fuel is 0°F.
recombination.
2006-01 Impact of top peaked power PCT impact for GE 14 ML062490520 shape for small break LOCA fuel is 0°F. 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 -40°F.
channel wall for 10X10 fuel bundles.
2012-01 Impact of change in fuel PCT impact for GE 14 ML12353A320 properties from GESTR fuel is +20°F.
to PRIME
Attachment L-19-269 Page 2 of 2 Perry Nuclear Power Plant 10 CFR 50.46 Changes and Errors (Continued)
Vendor Summary of Change/Error Licensing Basis Peak Licensee Report of Notification Cladding Temperature Notification Number (PCT) Impact (Accession No.)
2014-01 Impact of use of a new PCT impact for GE14 ML14170A178 version of SAFER04A. fuel is 0°F 2014-02 Impact of system mass PCT impact for GE14 ML14170A178 divergence error. fuel is 0°F 2014-03 Impact of minimum delta PCT impact for GE14 ML14170A178 pressure error. fuelis-15°F.
2014-04 Impact of counter current flow PCT impact for GE14 ML14170A178 limitation (CCFL) error. fuel is 0°F 2017-02 Impact of fuel rod plenum PCT impact for GE14 ML17233A279 temperature update. fuel is 0°F 2019-05 Impact of lower control rod PCT impact for GE14 This submittal drive housing interface fuel is 0°F backward leakage path TOTAL Summation of the absolute 125°F values of the changes/errors.
Notes: 1. SAFER - Name of the code developed by General Electric Company that 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.
