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Category:Letter type:L
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L-21-280, 10 CFR 50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirements2022-01-0505 January 2022
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10 CFR 50.55a Requests Number VR-10 and VR-11, Inservice Valve Testing
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Submittal of Revision 22 to Updated Safety Analysis Report (Supplement Letter)
2024-01-24
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Category:Licensee 30-Day Written Event Report
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Text
FENOC Perry Nuclear Power Station
^^ 10 Center Road FirstEnergy Nuclear Operating Company Perry, Ohio 44081 Mark B. Bezilla 440-280-5382 Vice President Fax. 440-280-8029 August 17, 2011 L-11-246 10 CFR 50.46 ATTN: 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 July 20, 2011, Global Nuclear Fuel -Americas, LLC issued two error notifications 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 these errors.
The attachment contains a summary of the 10 CFR 50.46 changes and errors, including the two most recent errors, applicable to the GE14 fuel in use at PNPP. The summation of the absolute values of theses 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 two recent errors is required within 30 days.
One error is associated with the input coefficients used to direct the deposition of gamma energy produced by the fuel, determining whether it would heat the fuel rod, fuel cladding, fuel channel, or control rod structural materials. This resulted in an overprediction of the heat deposited in the fuel channel (post-scram) and an underprediction of the heat deposited in the fuel. Evaluations have been performed and a bounding effect on peak clad temperature (PCT) has been determined. For PNPP, the PCT increases by 25 degrees Fahrenheit (°F).
The second error is associated with the assumptions on the distribution of gamma heating pre-LOCA. The contribution from gamma heating to the fuel channel was minimized. For simplification, the energy was assumed to be deposited in the fuel rods prior to the LOCA, and then adjusted such that the correct heat deposition
Perry Nuclear Power Plant, Unit No. 1 L-11-246 Page 2 was applied after the scram. Not accounting for this power generation outside of the fuel rod tended to suppress the hot bundle power required to meet the initial operating planar linear heat generation rate. Further, there is a small effect on the initial conditions for the balance of the core as these are set in relation to the hot bundle condition. The energy distribution during the pre-scram phase was updated with the appropriate energy distribution. For PNPP, the PCT decreases by 40°F.
As a result of incorporating these, and previously reported changes and errors, the PNPP PCT is 1550°F and continues to satisfy the 10 CFR 50.46(b)(1) criteria of PCT not to exceed 2200°F.
Evaluation of the two aforementioned errors indicate continued compliance with the 10 CFR 50.46(b) acceptance criteria. The evaluation also accounted for the uncertainties in the analysis methods and inputs indicated in 10 CFR 50.46(a)(1)(i).
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) 761-6071.
Sincerely, Mark B. Bezilla
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-11-246 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 SAFER1 pressure PCT impact for GEM ML020710641 rate inconsistency error. fuel is +5 degree Fahrenheit (° F).
2002-01 Impact of SAFER core spray PCT impact for GEM ML030710170 injection elevation error. fuel is+15° F.
2002-02 Impact of SAFER bulk water PCT impact for GEM ML030710170 level error. fuel is 0° F.
2002-04 Impact of SAFER04 PCT impact for GEM ML030710170 computer platform change. fuel is 0° F 2002-05 Impact of error in WEVOL2 PCT impact for GEM ML030710170 calculation of downcomer free fuel is 0° F.
volume.
2003-01 Impact of SAFER level/ PCT impact for GEM ML040710502 volume table error. fuel is +5° F.
2003-03 Impact of SAFER initial steam PCT impact for GEM ML040710502 separator pressure drop fuel is 0° F.
error.
2003-05 Impact of postulated PCT impact for GEM ML040710502 post-LOCA3 hydrogen-oxygen fuel is 0° F.
recombination.
2006-01 Impact of top peaked power PCT impact for GEM ML062490520 shape for small break LOCA fuel is 0° F. ML070390113 analysis.
2011-02 Impact of database error for PCT impact for GEM This submittal.
heat deposition for fuel is +25° F.
10X10 fuel bundles.
2011-03 Impact of updated formulation PCT impact for GEM This submittal.
gamma heat deposition to' fuel is -40° F.
channel wall for 10X10 fuel bundles.
TOTAL Summation of the absolute 90° 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.
