ML17249A817
| ML17249A817 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/29/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | White L ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| NUDOCS 8004100316 | |
| Download: ML17249A817 (5) | |
Text
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Docket Ho. 50-244
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Dear Hr. White:
Hr. Leon D. 1lhite, Jr.
Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, Hew York 14649 During the last several years, data have begun to indicate that the fission gas release rate from LMR fuel pellets is increased (enhanced) with burnup.
ttany of the current fuel performance analyses do not consider the impact of burnup-enhanced release on safety.
Sy letters dated November 23, 1976, the HRC staff requested all LMR licensees to assess the higher fission gas release for fuel burnups above 20,000 Megawatt-day per metric ton (tll~D/t).
Also, by HRC staff letter dated January 18, 1978, all U. S.
LNR fuel suppliers were requested to revise their fuel performance analyses to include the enhance-ment of fission gas release at higher burnups.
All responses to the Hovember 23, 1976 letters have been reviewed.
Me have concluded that no immediate licensing action is required for operating reactors.
This conclusion is valid for typical reported LWR fuel bundle and batch burnups.
Any extension of these burnups or other factors which significant'ly affect fission gas release, LOCA PCT or fuel rod internal pressure is outside the scope of the conc 1u s ione Westinghouse was the only fuel supplier calculating that the increased release would cause internal fuel rod pressure to exceed coolant system pressure.
The-staff has approved revised design criteria which allow internal rod pressures greater than system pressure.
The staff is also completing the review of a Hestinghouse revised fuel performance code.
The staff, in evaluating reloads, has been requesting licensees using llestinghouse fuel to quantify the burnup when the newly approved design criteria will be violated.
In the reloads evaluated thus far, there appears to be significant burnup margin to the nelly approved design criteria to compensate for modifications which may result from the staff rev of the Westinghouse revised fuel performance code.
The responses concerning Conhustion Engineering (CE) and Exxon PHR fuel bundles demonstrated that neither was there an adverse effect on ECCS evaluations nor did the internal fuel rod pressure exceed system pressure.
Therefore, no immediate licensing action is necessary on CE or Exxon fueled PRRs.
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SURNAME DATEP..
NRC FORM 318 {9 76) NRCM 0240 AU S. GOVERNMENT'RINTINGOFFICE: 1979'289'369
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t'fr. Leon D. White, Jr.
Inasmuch as you and/or the staff viill be evaluating all future reloads against fuel vendors'evised tuel performance codes which provide for increase in fission gas release at hfgher burnups, ue consider this a satfsfactory resolution of this concern.
Sincerely, cc:
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'OV.S. GOVER ENT PRINTING OFFICE: 1979.289 389
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'Mr. Leon D. White, Or.
February 29, 1980 CC Harry H. Voigt, Esquire
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P.'0.
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