ML20063B238
| ML20063B238 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/21/1994 |
| From: | Benes G COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20063B233 | List: |
| References | |
| NUDOCS 9401280090 | |
| Download: ML20063B238 (4) | |
Text
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4 4
ATTACIIMENT TECIINICAL SPECIFICATION BASES CIIANGES FOR LASALLE UNITS 1 AND 2
SUMMARY
OF PROPOSED CHANGES FOR LASALLE UNIT 1 B 3/4 2-6 Reference for applicable LaSalle LOCA Analysis updated, Reference for GE LOCA model updated, References moved to end of page t
P
POWER DISTRIBUTION SYSTEMS BASES
"!P!""" CP! TIC ^' n0YEo onin (e-+ 4mg) 4 ferences:
1.
General Electric Company Analytical Model for Loss-of-coolant AnalvsisinAccordancewith10CFR50,AppendixK,@E0E-205CE D*
f g & g$Et /926)
NEGO-20566Ah 2.
" Qualification of the One-Dimensional Core Transient Model for_ -
Boiling Water Reactors," General Electric Company Licensing Topical Report NEDO-24154 Vols. I and II and NEDE-24154 Vol. III as sup-plemented by letter dated September 5, 1980, from R._H. Buchholz (GE) to P. 5. Check (NRC)..
I 3.
"LaSalle County Statio its 1 and 2 SAFER /GESTR-LOCA Loss of-Coolant Accident Analv General Electric Company Reco ;
fEDC-?l51M, 00:e r 199 g g g gg/> Cdok /99 4.
" General Electric Standard Application for Reactor Fuel,"
~
NEDE-24011-P-A, (latest approved revision).
5.
" Extended Operating Domain and Equipment Out-o.f-Service for LaSalle County Nuclear Station Units 1 and 2," NEDC-31455, November 1987.
3/4.2.4 LINEAR HEAT GENERATION RATE The specification assures that the LINEAR HEAT GENERATION RATE (LHGR) in
~
any rod is less than the design linear heat generation even if fuel pellet densification is postulated.
The power spike penalty specified is based on the analysis presented in Section 3.2.1 of the GE topical report NEDM-10735 Supplement 6, and assumes a linearly increasing variation in axial gaps between core bottom and top and assures with a 95% confidence that no more f
than one fuel rod exceeds the design LINEAR HEAT GENERATION RATE due to power.
spiking.
LA SALLE UNIT 1 B 3/4 2-6 Amendment No. 70
SUMMARY
OF PROPOSED CIIANGES FOR LASALLE UNIT 2 L
i B 3/4 2 6 Reference for applicable LaSalle LOCA Analysis updated, Reference for GE LOCA model updated, References moved to end of page i
l
POWER DISTRIBUTION SYSTEMS BASE 5 MINI +tUM CRii1LAL t'UwtiR RAIIC (Conlinut:d) eferences:
1.
General Electric Company Analytical Model for Loss of-Coolant-Malvsis in Accordance with 10 CFR 50. Anoendix KQE40%6,
[ Hove ~ber1N Q qgf}
gfk 2.
" Qualification of the One-Dimensional Core Transient Model fo Boiling Water Reactors" General Electric Co. Licensing Topical Report NEDO 24154 Vols. I and II and NEDE-24154 Vol. III as sup-plemented by letter dated September 5, 1980, from R. H. Buchholz (GE) to P. 5. Check (NRC).
1 3.
"LaSalle County Station Units I nd 2 SAFER /GESTR - LOCA Loss-nf-Enn h a+ accident Analy
, General ElectMr En Do - +
go:-n51cr,am u -.
proc-3225ge,cdober IW3, 4.
" General Electric Standard Application for Reactor Fuel",
NEDE-24011-P-A, (latest approved revision).
5.
" Extended Operating Domain and Equipment Out-of-Service for LaSalle County Nuclear Station Units 1 and 2", NEDC-31455, November 1987.
3/4.2.4 LINEAR HEAT GENERATION RATE g
The specification assures that the LINEAR HEAT GENERATION RATE (LHGR) in any rod is less than the design linear heat generation even if fuel pellet densification is postulated.
The power sp'ike penalty specified is based on the analysis presented in Section 3.2.1 of the GE topical report NEDM-10735 Supplement 6, and assumes a linearly increasing variation in axial gaps between core bottom and top and assures with a 95% confidence that no more than one fuel rod exceeds the design LINEAR HEAT GENERATION RATE due to power spiking.
g LA SALLE - UNIT 2 B 3/4 2-6 Amendment No.54 l
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