ML19317G508
| ML19317G508 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/11/1977 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Rodgers J FLORIDA POWER CORP. |
| Shared Package | |
| ML19317G509 | List: |
| References | |
| NUDOCS 8003180796 | |
| Download: ML19317G508 (3) | |
Text
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Docket file ELD NRC PDR IE (3)
FEB 11197%ocal POR R. Reid LWR 1 File C. Nelson D. B. Vassallo D. Eisenhut F. J. Williams K. Goller Docket No. 50-302 J. Stolz ACRS (16)
J. Angelo J. Miller 4
E. Hylton
.B. Stello i
e eman K. Goller,.>f Florida Power Corporation ATTN:
J. T. Rodgers J. Knight SS Assistant Vice President R. Tedesco bcc: J.R. Buchanan, NSIC sad Nuclear Project Manager H. Denton
.T. B. Abernathy, TIC P. O. Box 14042 y, 4, - goo p, St. Petersburg, Florida 33733 R. H. Yo11mer
/ 'M'. L.' Ernst -
./* ' W. P.;Gammill Cent 1emen:
o.
RE: FISSIO?! GAS. RELEASES FROPt FUEL' PELLETS (CRYSTAL RIVER UNIT 2 WUCLEAR GENERATING PLANT)
- R, * *,,
The NRC staff has recently f4t410ed information which indicates that fission pas releases free.fvel pellets with high burnup may be under-predicted by the. current-industry models for fission gas release.
As a result,. actual end-of-life fuel rod pressure may be higher than that which was considered in the safety analysis for your facility.
Although this situation does not lead us to suspect that fuel design limits have been or are currently being exceeded at your facility, the potential may exist for such an occurrence in the future as higher fuel burnups are reached. Consequently, you are requested to evaluate the effects of increased fission gas releases on the safety analysis for your facility in accordance with the schedule specified below.
If the estimated 'date on which any fuel rod in your facility will reach a local exposure (burnup) of 20,000 Megawatt-days per metric -
ton of Uranium (HWD/tu) is sooner than June 1,1977, provide the following infomation within 30 days of receipt of this letter.
(!f this estimated date is later than June 1,1977, your response may be submitted within 90 days of receipt of this letter).
The estimated date on which any fuel rod in your facility will a.
reach a local exposure (burnup) of 20,000 Hegawatt-days per netric ton of Uranium (tND/tu).
- b.. Us'ng the correction technique described in the attached enclosure, c.odify the fission gas release model in the thermal performance code for the fuel in your facility and calculate the fission gas release, fuel rod pressure, fuel k
temperature, etc. for burnups up to and including the g
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Florida Power Corporation FEB 11 1977
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target peak-rod burnup. Provide a comparison of the results of your calculations with those obtained using the uncorrected fission gas release model.
c.
Describe the inpact (if any) of larger fission gas releases on the LOCA analysis and other safety analyses for your facility.
d.
If internal fuel rod pressures, as calculated using the above-mentioned fission gas release correction, are predicted to exceed the nominal system pressure for your facility, provide the date that this is anticipated to occur and discuss the impitcations of operating under both nomal and accident conditions with fuel cladding tensile stresses.
We have advised all U. S. fuel manufacturers by separate correspondence that this infomation request is being sent to ifcensees of operating power reactors.
In our letter to the fuel manufacturers, we have indicated that bounding calculations for appropriate plant groupings would,be acceptable.
This request for generic infomation was approved by GAO under a blanket clearance number B-180225 (R0072); this clearance expires July 31, 1977. Three signed. originals and 40 copies of your response will be required..
Sincerely, Original Signed b[
Jolm F.Stols John F. Stolz, Chief Light Water Reactors Branch No.1 Division of Project Nanagement
Enclosure:
Burnup-Dependent Correction for Fission Gas Release Models cc w/ enclosure:
See next page
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4w FEB Il 1977 Florida Power Corporation e cc: Mr. S. A. Brandimore Vice President and General Counsel
- P c-0.-Box-14042 -- - -
St. Petersburg, Florida 33733 I
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