ML19290A483
| ML19290A483 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/22/1974 |
| From: | John Miller METROPOLITAN EDISON CO. |
| To: | |
| References | |
| NUDOCS 7911070659 | |
| Download: ML19290A483 (5) | |
Text
AEC DI$ _ ' 3t'TICN FOR PA?T 50 DOCKET MATE
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(TDiPORARY FCPM)
CONTROL NO:
12.'3 FILE: O' FROM:
DATE OF DCC DATE REC'D LTR MEMO RPT OTFER "etropolitan Edison Coneany Read in:;, Penn. 19603
'tr. J.G. 5 filler 2-22-74 2-25-74 X
TO:
ENT LOCAL PDR M
D.R. Knuth 1
CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DCCKET NO:
- cc<
1 50-289 DESCRIPTION:
ENCLOSUPIS:
Ltr furn final report on the requirenents in FIGURES:
re:',ard to the revision of the Specific Heat LOCA LI?!ITED l'AXD'U!! ALLONABLE LINEAR Curve for UO ? fuel.....trans the following...
HFAT RATE.
SPECIFIC HEAT Of UO2 PLANT NAME:
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(l. q~ '7 Dr. D. R. Knuth, Director 3
Directorate of Regulatory Operations
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c0 United States Atomic Energy Commission h h
.Y fib.'2 51974 w Washington, D. C.
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Subject:
Three Mile Island Nuclear Station Unit 1
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Docket No. 50-289
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s Revised Specific Heat
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Dear Dr. Knuth:
This is a final report pursuant to the 10 CFR 50.55(e) reporting require-ments in regard to the revision of the Specific Heat Curve for UO fuel.
On January 21, 1974, you were notified that Babcock & Wilcox Company was revising the specific heat curve for CO fuel as utill:ed in some of its trans-2 ient computer codes for plant safety analyses. This revision was expected to increase the values for specific heat at elevated temperatures. A new specific heat curve has now been issued, following appropriate quality assurance and approval steps, and incorporated into the af fected transient codes. The new specific heat curve is attached.
The safety implications of higher values of specific heat were investi-gated by re-running the various transients. The slower transients were unaf-fccted. The more rapid transients were investigated with the following results:
ROD EJECTION TRM;SIENT The DNBR was not noticeably affected. The maximum cladding temperature decreased by 70 F to 100 F, and the maximum fuel temperature decreased by 200 F to 300 F.
LOCKED ROTOR TRANSIENT The DN3R was not noticeably affected. The maximum cladding temperature increased by 5 F to 15 F and the fuel temperature fell off at a slower tate.
The overall effect of this change is insignificant.
FOUR-PUMP COASTDCWN TRANSIENT The increased specific heat values had no significant effect on this transient.
1559 336
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Dr. D. R. Knuth Page 2 Febr nry 22.1?74 r_ c c.e 4
,..a, n,.1 A j o.
v-e The only significant impact the specific hest revisisn nas on safety limits is the icwering of sone pertions of the allcwable linear heat rate by up to 0.65 KW/ft.
"his LCCA derived curve determines the allowsble linear heat rate as a functicn cf ele-vation in the core for which the Interim Acceptance Criteria are met.
Revised LOCA limits were determined h's repesting the Oconee 2 calculations becsuse these analyses are representative of the 177 fuel assembly plants.
The allowable heat rate curve on Ccenee 2 is lower by 0.65 Ci/ft at H =
six f:ct elevation, but is unchanged at the ten fsot elevati:
The revised LCCA limit curve is attached.
P. u=e't La v *t
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The initial stored energy in the core is increased by less thaa one million Stu's; calculation of the Reactor 3uilding Pressure sb vs no change.
A re-analysis of Three :iile Island Unit 1 cperating margins with respect to the revised LCCA limit curve was performed b1ced on the procedures level:pei in 3A'd-1C078.
This analysis shcws that the revised LCCA limit would have been violated assuming the licensed design conditions early in life.
Based :n Ocenee 1 and 2 oreraticn, however, these design conditions are known to be conservative ard an actual violation vculd have required the simultanecus existence of several
" worst case" uncertainties.
In order to ensure that Three ? tile Islar.d Unit 1 operates within the revised LOCA li.vit and to more accurately reflect the cper-ating characteristics of Cconee 1 ani 2 experience to date, propcsed revisicr.s for the Three Mile Islan1 Unit 1 Technical Specifi;sticns wi'.1 be submitted to the Directorate of Licensing during the week of March 4, 197k.
Very truly ycur.s,-
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G. Miller Vice President brh/kg A.,
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Mr. A. Giambusco, Deputy Director for L
Reactor Projects, Washington, D.C Mr. J. ?. O'Reilly, Directorate of Regulatory Operations, King of Prussia, Pa.
Mr.
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THREE MILE Ist ';;D U:!IT 1 LOCA LIMITED MAXI.T. ALLOWABLE LINEAR HEAT RATE
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