ML19322A601
| ML19322A601 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/14/1973 |
| From: | Thies A DUKE POWER CO. |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7911210679 | |
| Download: ML19322A601 (5) | |
Text
AEC DIC; BUTIO?! FOR PART 50 DOCET !GTI.
AL (T7/APORARY FOPJ.)
CONTROL NO:
317e FIIZ FROM:
DATE OF DOC:
DATE REC'D LTR IGMO RPI Or. E.t Duke Power Company Ch.arlcpte, H. C.
28201 a
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5-lh-73 5-15-73 X
TO ORIG CC OniER SENI AEC PD3 x
SENI LOCAL PLa y
Mr. Cir.:nbusso 1 signed CIASS:
gm0P IliFO IliPUT lio CYS REC'D DOC;;ET liO:
40 50-269 DESCRIPTIO i:
E;;CLoSgaES:
Ltr furnishing info re BAW Topical Report ta Fuel,Densification....... W/ Attached Tables -
Fuel Rod Dimensional Data & Dimensional Data Used in TAFY3 Fuel. Temperature Calculations.
Do Not Rem 6Fii pgyp gg33 Oconee Unit 1 FOR ACTION /IN70RMATION 5-15-73 AB BUTLER (L)
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W/ Copies W/ Copies W/ Copies W/ Copies GOLLER(L)
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W/ Copies W/ Copies W/ Copies W/ Copics KNIEL(L)
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cy ng POCKETED May 14, 1973 II
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Q MAY151973 >
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REGULATORY S
h Mr. Angelo Giambusso h
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1 4
Deputy Director for Reactor Project 6 e
8 Directorate of Licensing
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/C-a U. S. Atomic Energy Commission
,, g' t l' Washington, D. C.
20545 g
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<T N Re: Oconee Nuclear Station
/
l)N Unit 1 ui i
Docket No. 50-269
Dear Mr. Giambusso:
The analyses for Oconee Nuclear Station Unit 1 fuel with potential fuel densification effects are presented in Babcock & Wilcox Topical Reports BAW-10054, Rev. 1, " Fuel Densification Report," and BAW-1387, Rev. 1, "Oconee 1 Fuel Densification Report," which were filed with the Atomic Energy Comunission on May 1,1973 and April 13, 1973, respectively.
As a result of.the meeting with the AEC/ DOL staff on May 8, 1973, Duke Power Company and Babcock & Wilcox agreed to reevaluate the linear heat generation rates for center line fuel melt and for stored energy and resultant RW/ft limit associated with fuel clad temperature criterion using the following assumptions, 1.
Gap conductance as calculated by the TAFY code (BAW-10044) should i
be reduced by 25 percent from the beginning of life value and not further decreased with core life.
2.
A cladding ID of 0.3773 inches should be used.
I 3.
A sorbed gas content of 0.01 cc/gm should be used.
l l
4.
No credit should be taken for fuel restructuring.
All other inputs to the TAFY calculation are as presented in BAW-1387, Rev. 1.
For comparison, the attached table shows the parameters used in BAW-1387, Rev.1 and the as-built parameters which were presented at the May 8, 1973 meeting.
The results of B&W's analyses yield a 20.1 KW/ft fuel melt limit and a 18.65 KW/ft loss-of-coolant accident limit which corresponds to a fuel 3
.(
,176
Hr. Angelo Giambusso Page 2 Hay 14, 1973 clad temperature of 2300 F.
Discussions are rarrently proceeding among members of your staff, Duke, and B&W to revf.ac the Technical Specifications to provide appropriate limits for fur'. densification effects. We trust that these discussions will be succe=,sfully completed on May 15, 1973.
Therefore, the results of the above analyses; your conclusions on clad collapse documented in R. E. DeYoung's letter of April 23, 1973 to Babcock & Wilcox; and appropriately revised technical specifications will support the conclusion that the Oconee 1 reactor can be safely operated at a power icvel of 2568 Nt.
Consequently, we request that the power restriction of 1926 W e be rescinded.
Sincerely, A.c.Thhs A. C. Thies ACT:vr Attachment l
l
(
I J
FUEL ECD DDG:NSIONAL DATA
^""
Nominal Spec Value & Tolerance Mean Standard Sa:ple l
Deviation Size I
ruEL Diameter, in.
0.370 I 0.005 0.36998 0.0002 14272.
Density
- gm/cc 0.935 1 0.015 0.93558 0.00445 l
12755.
Sorbed Gas, cc/gm j 0.02 U.T.L.
0.0102 0.000957 7C.
Surface Roughness,,
RHR 63.0 U.T.L.
50.121 6.976 7406.
l 143.966 0.3253 i
783.
Stack Length, in.
144.0 I 0.75 CMD j
l I
580.
0.D.,
in.
O.430 I 0.002 0.4294 0.00042 g
i I.D.,
in.
0.377
- 0.002 0.37725 l
0.00054 580.
1 t
l i
I.D. Surface j
^
580 i
Roughness, RRR j
63.0 U.T.L.
I 16.743 i
3.383 l
I
'g
'i:
GAP, in.
0.007 in.
l 0.00727 0.000574 580.
8 2
i i
i
- BACK FILL i
NOT AVAILABLE' ---------
! PRESSURE 375'..I 25. psia t
( ------------li i
- Geometrical densities based on fuel pellet weight, length,diameteranddishdimensions.]
t The backfill pressure tolerance is met on 100% of the fuel rods using a go-no-go technique.
9
DDiENSIONAL DATA USED IN TAFY3 FUEL TEMPERATURE CALCULATIOUS BAW-1387 (Rev. 1) Values Proposed As-Built Values flotes PARAMETER FUEL Fuel Density Undensified w/o-20 93.558% T.D.
93.558% T.D.
This number is the mean as-built value.
Undensi*fied w-2o
, 92.668% T.D.
, 92.668% T.D.
Densified 96.5% T.D.
96.5% T.D.
Fuel Diameter Undensified 0.36998 0.36998 Densified
- 0.36523 0.36523 Sorbed Gas 0.02 cc/gm (UIL) 0.01 cc/gm (MEAN)
Surface Roughness 70 micro inchea RilR 50 micro inches RIIR (MEMI)
Stack Length Undensified 143.966 143.966 This number is the mean as-built value.
Densified 141.848 141.848 This number was obtained_by densifying from the sea s-:
built value.
CLAD Gap Undensified 0.00842 (max. stat.)
0.00727 (MEAN)
Method of calculation on attached sheet.
Densified 0.01278 (max. stat.)
0.01202 (MEAN)
These values were derived from calculated Clad I.D.
and dennifIcd lic11. t.Ita-meter.
.