ML20203C047
| ML20203C047 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/09/1997 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9712150212 | |
| Download: ML20203C047 (6) | |
Text
.
Dave Morey Southern Nuclear
=
. %ce Prevdent Operating Company FarteyProject -
. P.O. Box 1295 r
- Birmingham. Alabama 35201 '
Te! 205 992.5131 4
SOUTHERN COMPANY Deconber 9,1997 Docket Nos.: 50-348 50-364 U.S. Nuclear Regulatory Commission ATI'N: Document Control Desk Washington, DC 20555 Joseph M. Fa -ley Nuclear Plant Egliological Analyses Ladies and Gentlemen:
As a result of several recently approved or submitted technical specification amendments, multiple radiological analyses have been performed in the analysis of several design basis accidents. Specifically, the Fuel Handling Accident (FHA), Loss of Coolant Accident (LOCA), and the Steam Line ' Break (SLB) analyses results have been submitted for NRC review in support of: spray additive tank deletion (SAT Deletion, Amendments 128 and 118 for Units I and 2 respectively); steam generator tube support plate voltage-based repair criteria (ARC, Amendments 132 and 124 for Units 1 and 2); power uprate (Uprate, SNC letter dated Febmary 14,1997); and filtration systems and radiation monitoring instrumentation (Filters, SNC letter dated June 30,1997).
The enclosed tables provide a comparison of the analyses major inputs associated with each of these referenced amendments and submittals, including the current FS AR analyses inputs.
Other analyses and inputs submitted in support of the power uprate are not affected by multiple submittals and, therefore, should be reviewed as provided in the power uprate submittal and RAI responses.
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9712150212 971209 PDR ADOCK 05000348 P
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- U.S. Nuclear Regulatory Commission -
Page 2 -
i If there are any questions, please advise.
Respectfully submitted,-
SOUTHERN NUCLEAR OPERATING COMPANY h
34/M Dave Morey.
REMkit: COMPARE. DOC
Enclosure:
Comparison Tables 1,2,3, and 4 cc: Mr. S. D. Ebneter, Region II Administrator Mr. J. I. Zimmerman, NRR Project Manager
.Mr. T. M. Ross, Plant Sr. Resident Inspector T
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ENCLOSURE Comparicon Tables 1. 2. 3. and 4
Enclosure Table 1 FUELllANDLING ACCIDENT f.illus i
in Aux. Bidt Current FSAR ljpnts Power level (MWt) 2821 2831 283I Peaking Factor 1.65 1.7 1.7 lodine form (%)("
NA )
99.75/0.25 99.75/0.25 C
Gap fraction 0.1 '
O.1")
0.1 "'
0 Pool DF" 100")
133/1 133/l Filter clTiciency (%)"8 95"'
90/70 90/30 la CDRiainment Powcr level (MWt) 2766 2831 283i Peaking Factor 1.4 1.7 1.7 C
lodine form (%)("
NA '
99.75/0.25 99.75/0.25 Gap fraction 0.1"'
O.1")
0.1"'
Pool DF" 100")
133/1 133/1 Filter efficiency (%)'"
70")
90/30 NA Isolation Time (sec)
NA NA 45 Purge Flow (cfm)
NA 1.1 x 48,500 1.1 x 48,500 NOTES:
1.
Elemental iodind Organic iodine.
2.
All forms of iodine treated equally.
3.
Except Kr.5 = 0.3.
Except l u = 0.12 and Kris = 0.3.
4.
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' Enclosure-it-Table 3
' LOSS OF COOLANT ACCIDE TI' S.A.T Deletion UPnts E!!1cn Current FSAB A
Power level.
2826 2831 2831 2831-lodine form (%)'"
91/4/5
- 95.5/2/2.5 95.5/2/2.5 95.5/2/2.5 o
NaOli TSP TSP TSP Containment Sp) ray-Aw o (hr' 25.5 1.4 1,4.
1.4 Platcout.
50 %
Time dependent Time dependent Time Dependent Aw,,.i (hr) :
Instantaneous 12.5 12.5 12.5
-ECCS leakage (2)
Source Realistic gap
$0 % core 50% core 50% core Flow (3) 20 x Table 6.3 8 Same as S AT Same as SAT Flashing (%)
I 10 10 10 I
Filter (%)(0 Nonc
- 95/95/95 95/95/95 90/30/90 Control Room (4)
Volume (if) 69,000 114.000 114,000 114,000 Inicak (cfm).
Unfiltered 10 10 to 10 Pressurization Flow (cfm) 300 450 450 450 Filter (%)
99 99 99-99 Recirculation Flow (cfm) 3000 2700 2700 2700-Fiher (%)
- 95
- 95 95 95 NOTES:
. 1.
Elemental / organic /particulatc.
2.
Original A/E cvaluation from FSAR Section 15.4.1.10.
3.
Assumed to be fmm FSAR Table 6.3-8.
4.
No ECCS leakage contribution included.
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Enclosure Table 3 MAIN STEAM LINE BREAK Current FSAR ABC Upr;tts Power level 2766 2831 2831 Equilibrium 1 RCS
~3.8 v.15("
0.5 1pCi del n /gm) SG
-0 0.1 0.1 i
i RCS I Spike a)
NA 9 pCi del u /gm 30 pCi del n /gm i
i b)
NA 0.15 pCi del n /gm
.0.5 pCi del n /gm i
i appearance x 500 appearance x 500 Dose Cony. Factor R.G.1.109 ICRP 30 ICRP 30 SG Partition
- 0.1/0.I 1.0/0.I 1.0/0.I Steam Releases &
FSAR Table FS/.R Table brate RAI #1 Feedwater flow 15.4 23 15.4 23("
Primary-secondary I gpm 23.8 gpm "'
150 gal / day / SG leakage NOTES:
1.
Originally submitted as 0.5 and subsequently reduced to 0.15 due to higher than expected leakage.
2.
3.
The secondary side iodine inventory modeled for the ARC SER bounds the secondary side inventory (steam plus feedwater) analyzed for power uprate.
4.
Accident induced leak in addition to 150 gal / day / intact SG.
Table 4 CONTROL ROD EJECrlON*
Current FS AR -
Unra.)tg Power level (MWt) 2821 2831 Steam release Mass (Ib) 55,000 426,000 Duration t :c)*
220 98 RCS leakage Rate I gpm 150 gal / day / SG Duration (sec)*
700 2500 NOTES:
1.
Inchided to clarify RCS and s cam release modeling.
2.
Time for ster n release is coe,crvatively short to maximize blondown rate. Time for RCS release via steam must be continued be ond the steam release duration until the RCS leak stops.
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