ML19253C980: Difference between revisions
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ATTACHMENT II SAFETY EVALUATION RELATED TO SPIRAL LOADING / UNLOADING OF THE REACTOR CORE POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 December | ATTACHMENT II SAFETY EVALUATION RELATED TO SPIRAL LOADING / UNLOADING OF THE REACTOR CORE POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 December 6, 1979 154\\ | ||
D\\A 7912120 t[f / | |||
I. Description of the Modification The Technical Specification changes will provide for spiral loading / unloading of the core, permit reloading without the require-ment that all control rods be inserted in the core, and redefine SRM operability during spiral reload / offload operations. | I. | ||
II. Impact of Chance The proposed changes will not reduce the shutdown margin bclow that provided for the complete core. The redefinition of SRM operability will not reduce the adequacy of the SRM's for reactivity monitoring. | Description of the Modification The Technical Specification changes will provide for spiral loading / unloading of the core, permit reloading without the require-ment that all control rods be inserted in the core, and redefine SRM operability during spiral reload / offload operations. | ||
III. Conclusion The incorporation of this modification: a) will not increase the probability nor the consequences of an accident or mal-funtion of equipment important to safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specificatio | II. | ||
Impact of Chance The proposed changes will not reduce the shutdown margin bclow that provided for the complete core. | |||
The redefinition of SRM operability will not reduce the adequacy of the SRM's for reactivity monitoring. | |||
III. Conclusion The incorporation of this modification: | |||
a) will not increase the probability nor the consequences of an accident or mal-funtion of equipment important to safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specificatio | |||
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Latest revision as of 08:01, 4 January 2025
| ML19253C980 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/06/1979 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML19253C977 | List: |
| References | |
| NUDOCS 7912120461 | |
| Download: ML19253C980 (2) | |
Text
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ATTACHMENT II SAFETY EVALUATION RELATED TO SPIRAL LOADING / UNLOADING OF THE REACTOR CORE POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 December 6, 1979 154\\
D\\A 7912120 t[f /
I.
Description of the Modification The Technical Specification changes will provide for spiral loading / unloading of the core, permit reloading without the require-ment that all control rods be inserted in the core, and redefine SRM operability during spiral reload / offload operations.
II.
Impact of Chance The proposed changes will not reduce the shutdown margin bclow that provided for the complete core.
The redefinition of SRM operability will not reduce the adequacy of the SRM's for reactivity monitoring.
III. Conclusion The incorporation of this modification:
a) will not increase the probability nor the consequences of an accident or mal-funtion of equipment important to safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specificatio
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