ML20008F818
| ML20008F818 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/30/1981 |
| From: | Trimble D ARKANSAS POWER & LIGHT CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| 2R-0481-10, 2R-481-10, NUDOCS 8105120100 | |
| Download: ML20008F818 (2) | |
Text
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t3 ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK ARKANSAS 72203 (5011371-4000 April 30, 1981 e-0 JI-1C 2R-0481-10 S
IU1Y']
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'11 Director of Nuclear Reactor Regulation Q %s, %
ATTN:
Robert A. Clark, Chief y
(3./
3 Operating Reactors Branch #3 Division of Licensing g
s V. S. Nuclear Regulatory Comm.
Washington, D.C.
20555
SUBJECT:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Infomation Regarding ANO-2 Reload Report (File: 2-1510)
Gentlemen:
AP&L would like to submit the attached infomation as requested by telephone by your Mr. Dale Powers regarding our Unit 2 reload repo rt.
Very truly yours, haua e.t/1 David C. Trimble Manager, Licensing DCT:1p Attachment 8105120le P
MEMBEA MOOLE SOUTH tJTILITIES SYSTEM
. ra ATTACHMENT 1.
BURNUP DATA
- a. E0C1 Core Average 12,500 MWD /MTU
- b. E0C2 Peak Assembly, Batch 'B' Fuel 25,200 MWD /MTU
- c. EOC1 Batch Averages 13,500 MWD /MTU
- Batch 1A
=
14,100 MWD /MTU
- Batch B
=
9,700 MWD /MTU
- Batch C
=
- d. E0C2 Batch Averages 21,000 MWD /MTU
- Batch 1A
=
24,500 MWD /MTU
- Batch B
=
21,600 MWD /HTU
- Batch C
=
9,700 MWD /MTU
- Batch D
=
13,500 MWD /MTU
- Batch D*
=
2.
FUEL PIN AXIAL GROWTH A calculation was performed using the method described in CENPD-198 Supplement up to the fluence limitation given in the SER for that document. The method recommended in the June 22,1976 SER on CENPD-198 was used for incremental fluences beyond that limit.
For the maximum predicted E0C2 fluence, the results of this calculation showed no inter-ference between the fuel rods and the upper end fitting.
Preliminary review of shoulder gap (fuel rod / upper end fitting clearance) closure data from the E0C1 examination of characterized fuel assemblies has shown that less than one-half of the available gap has been closed. Since these assemblies have accumulated over 1/2 of the burnup for any assembly to be used in Cycle 2, and since gap closure rate decreases with burnup, these data provide qualitative evidence that the gap is sufficiently 'large to preclude interference during Cycle 2.
3.
NRC FISSION GAS ENHANCEMENT FACTOR f
The NRC fission gas enhancement factor-is used consistently in all of the CE fission gas analysis for ANO-2 Cycle 2.
We hope that this supplemental information will aid the NRC review of the ANO-2 Cycle 2 reload.
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