05000333/LER-1979-060-03, /030-0:on 790904,reactivity Required to Demonstrate Shutdown Margin Was Found to Be Larger than Value Used During Demonstration at Beginning of Current Fuel Cycle

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/030-0:on 790904,reactivity Required to Demonstrate Shutdown Margin Was Found to Be Larger than Value Used During Demonstration at Beginning of Current Fuel Cycle
ML19209B268
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 10/03/1979
From: W. Verne Childs
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19209B267 List:
References
LER-79-060-03L, LER-79-60-3L, NUDOCS 7910090422
Download: ML19209B268 (2)


LER-1979-060, /030-0:on 790904,reactivity Required to Demonstrate Shutdown Margin Was Found to Be Larger than Value Used During Demonstration at Beginning of Current Fuel Cycle
Event date:
Report date:
3331979060R03 - NRC Website

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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FlTZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 79-060/03L-0 Page 1

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While conducting a normal startup and during management review of updated fuel parameters received frora the fuel vendor, a change in the magnitude of the temperature co-e f # ' ci en t of react i vi ty was noted. The shut down margin demon-stration performed following the 1978 Refueling used the temperature co-ef ficien-of reactivity value of minus 0.58 (E-5) f/F compared to an updated value of minus2.3(E-5)Sh/F. Review of the shut down margin demonstration utilizing this new temperature co ef ficient revealed that the reactivity insertion re-quired to denonstrate the shut down margin was approximately 0.05% Ak larger.

'than the value actually used during the demonstration performed at the beginning of the current fuel cycle.

Recalculation, based on the new value of temperature co-ef' cient of re-activity and the data from the in sequence critical for this startup, show that the shut down margin capability at the beginning of the cycle was greater than 1.0% compared to the value of R+.38% requi red by the Technical-Speci fications Appendi x A, Paragraph 4. 3. A. I.

Based on this finding, the event did not represent any significant hazard to the public health and safety.

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