ML032170529: Difference between revisions
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Perry Nuclear Power Plant t0 Center Road FirstEnergy Nuclear Operating Company | FENOC Perry Nuclear Power Plant | ||
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t0 Center Road FirstEnergy Nuclear Operating Company Perry, Ohio 44081 W~~~~llarn R. | |||
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~~~~~~~~~~~~~~~~~~~~~440-280 5579 IWillam R. KandaFa 402089 Vice President - Nuclear Fax: 440-280-8029 July 23, 2003 PY-CEI/NRR-2722L United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Perry Nuclear Power Plant Docket No. 50-440 Withdrawal Of License Amendment Request Regarding Revision of the Minimum Critical Power Ratio (MCPR) Safety Limit Ladies and Gentlemen: | |||
This letter requests the withdrawal of Nuclear Regulatory Commission (NRC) review and approval of a previously submitted license amendment request dated January 30, 2003 (Letter PY-CEI/NRR-2665L). The license amendment request involved a proposed modification to the existing Minimum Critical Power Ratio (MCPR) Safety Limit contained in Technical Specification 2.1.1.2. Specifically, the change modified the MCPR Safety Limit values, as calculated by Global Nuclear Fuel (GNF), by decreasing the limits for both the two recirculation loop and the single recirculation loop operation. | This letter requests the withdrawal of Nuclear Regulatory Commission (NRC) review and approval of a previously submitted license amendment request dated January 30, 2003 (Letter PY-CEI/NRR-2665L). The license amendment request involved a proposed modification to the existing Minimum Critical Power Ratio (MCPR) Safety Limit contained in Technical Specification 2.1.1.2. Specifically, the change modified the MCPR Safety Limit values, as calculated by Global Nuclear Fuel (GNF), by decreasing the limits for both the two recirculation loop and the single recirculation loop operation. | ||
The change resulted from the core reload analysis performed for the PNPP Fuel Cycle 10. | The change resulted from the core reload analysis performed for the PNPP Fuel Cycle 10. | ||
As a component of the reload licensing methodology used by the Perry Nuclear Power Plant (PNPP), ["General Electric Standard Application for Reactor Fuel" (GESTAR II)], the as-loaded core is required to be compared to the reference core. The need for this evaluation is due to the assumptions made as to the core end state which are used in the development of the reference core. This ensures that the calculations performed to develop the reference core are applicable to the as-loaded core. This evaluation has been completed. As a result, the values associated with the MCPR Safety Limits have changed from those values proposed in the aforementioned license amendment request. Since the current PNPP MCPR Safety Limits are more conservative than the proposed revised values, initial Fuel Cycle 10 operation will be based upon the current Technical Specification MCPR Safety Limit values. Therefore, the proposed license amendment is not needed at this time. | As a component of the reload licensing methodology used by the Perry Nuclear Power Plant (PNPP), ["General Electric Standard Application for Reactor Fuel" (GESTAR II)], the as-loaded core is required to be compared to the reference core. The need for this evaluation is due to the assumptions made as to the core end state which are used in the development of the reference core. This ensures that the calculations performed to develop the reference core are applicable to the as-loaded core. This evaluation has been completed. As a result, the values associated with the MCPR Safety Limits have changed from those values proposed in the aforementioned license amendment request. Since the current PNPP MCPR Safety Limits are more conservative than the proposed revised values, initial Fuel Cycle 10 operation will be based upon the current Technical Specification MCPR Safety Limit values. Therefore, the proposed license amendment is not needed at this time. | ||
DD | |||
PY-CEI/NRR-2722L July 23, 2003 Page 2 of 2 If you have questions or require additional information, please contact Mr. Vernon K. Higaki, Manager - Regulatory Affairs, at (440) 280-5294. | PY-CEI/NRR-2722L July 23, 2003 Page 2 of 2 If you have questions or require additional information, please contact Mr. Vernon K. Higaki, Manager - Regulatory Affairs, at (440) 280-5294. | ||
Very truly yours, for William R. Kanda cc: | Very truly yours, for William R. Kanda cc: | ||
NRC Project Manager NRC Resident Inspector NRC Region IIl State of Ohio}} | |||
Latest revision as of 08:19, 16 January 2025
| ML032170529 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 07/23/2003 |
| From: | Kanda W FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PY-CEI/NRR-2722L | |
| Download: ML032170529 (2) | |
Text
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4.
FENOC Perry Nuclear Power Plant
_eft%
t0 Center Road FirstEnergy Nuclear Operating Company Perry, Ohio 44081 W~~~~llarn R.
Fonda
~~~~~~~~~~~~~~~~~~~~~440-280 5579 IWillam R. KandaFa 402089 Vice President - Nuclear Fax: 440-280-8029 July 23, 2003 PY-CEI/NRR-2722L United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Perry Nuclear Power Plant Docket No. 50-440 Withdrawal Of License Amendment Request Regarding Revision of the Minimum Critical Power Ratio (MCPR) Safety Limit Ladies and Gentlemen:
This letter requests the withdrawal of Nuclear Regulatory Commission (NRC) review and approval of a previously submitted license amendment request dated January 30, 2003 (Letter PY-CEI/NRR-2665L). The license amendment request involved a proposed modification to the existing Minimum Critical Power Ratio (MCPR) Safety Limit contained in Technical Specification 2.1.1.2. Specifically, the change modified the MCPR Safety Limit values, as calculated by Global Nuclear Fuel (GNF), by decreasing the limits for both the two recirculation loop and the single recirculation loop operation.
The change resulted from the core reload analysis performed for the PNPP Fuel Cycle 10.
As a component of the reload licensing methodology used by the Perry Nuclear Power Plant (PNPP), ["General Electric Standard Application for Reactor Fuel" (GESTAR II)], the as-loaded core is required to be compared to the reference core. The need for this evaluation is due to the assumptions made as to the core end state which are used in the development of the reference core. This ensures that the calculations performed to develop the reference core are applicable to the as-loaded core. This evaluation has been completed. As a result, the values associated with the MCPR Safety Limits have changed from those values proposed in the aforementioned license amendment request. Since the current PNPP MCPR Safety Limits are more conservative than the proposed revised values, initial Fuel Cycle 10 operation will be based upon the current Technical Specification MCPR Safety Limit values. Therefore, the proposed license amendment is not needed at this time.
PY-CEI/NRR-2722L July 23, 2003 Page 2 of 2 If you have questions or require additional information, please contact Mr. Vernon K. Higaki, Manager - Regulatory Affairs, at (440) 280-5294.
Very truly yours, for William R. Kanda cc:
NRC Project Manager NRC Resident Inspector NRC Region IIl State of Ohio