ML20205L842
| ML20205L842 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/31/1999 |
| From: | Curet H, Haun J, Mcburney D SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| Shared Package | |
| ML20205L820 | List: |
| References | |
| EMF-96-125, EMF-96-125-R02, EMF-96-125-R2, NUDOCS 9904140317 | |
| Download: ML20205L842 (400) | |
Text
. !
SIEMENS i'
EMF-96-125 Revision 2 I
i l
l LaSalle Unit 2 Cycle 8
! Reload Analysis I
l l
l I
I March 1999 6k nem ann e em
, %x ;D' l Siemens Power Corporation kg Nuclear Division
ISSUED IN SPC ON.UNE DOCUMENTSYSTEM Siemens Power Corporation DATE: Od6/97 EMF-96-125 Revision 2
~
LaSalle Un1t 2 Cycle 8 Reload Analysis Prepared:
' L%
J. ti'Haun, Engineer
! 3 //t./j $
f Date BVfR Neutronics Prepared: u rd hh Y LCM M. McBurney, Engineer \ Date BWR Safety Analysis Concurred: 3//5'/9er H. D. Curet, Manager Date Product Licensing 2_ 2, uru Approved:%D 0,_ , f 3-/r-9 9 M. (harrft, 'Mangger / Date BWR Safety Analysis Approved: k O. C. Brown, Ma/p/geW
[o O c. 8 7
'Date a[ff BWR Neutronics Approve 3 M W S//1[f7 Dafe /
~
7.'kl. Howe, Manager Product Mechanical Engineering-
~ Approved: W A h $$ Marck'1999 D[J. Denver, Manager .
Date Customer Projects
.gdh/pa);
Customer Disclaimer .
a.
r important Notice Regarding Contents and Use of This Document Please Read Carefully Siemens Power Corporation's warranties and representations concerning the subject matter of this document are those set forth in the agreement between Siemens Power Corporation and the Customer pursubnt to which this document is issued.
Accordingly, except as otherwise expressly provided in such agreement, acting neither Siemens Power Corporation nor any person on its behalf:
a.
makes any warranty or representation, express or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this document, or that the use of any information, apparatus, method or process disclosed in this document will not infringe privately owned rights; or b.
assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process disclosed in this document.
The information contained herein is for the sole use of the Customer.
In order to avoid impairment of rights of Siemens Power Corporation in patents or inventions which may be included in the information contained in this document, the recipient, by its acceptance of this document, agrees not to publish or make public use (in the patent use of the term) of such information until so authorized in writing by Siemens Power Corporation or until after six (6) months following termination or expiration of the -
aforesaid Agreement and any extension thereof, unless expressly provided in the Agreement. No rights or licenses in or to any patents are' implied by the furnishing of this document.
s 4.
J
I EMF-96-125 i LaSa!!e Unit 2 Cycle 8 Revision 2 l Reload Analysis Page i l 1
)
Nature of Changes Paragraph item or Page(s) Description and Justification 1,
General Comment. The report has been revised to i.nclude analysis results and licensing limits for an updated core loading and cycle depletion, updated ATRIUM
- 9B* additive constants and additive constant uncertainties, updated gap conductance values and changes to some of the operating parameters including reduced pressure operation. Mid cycle MCPR analysis results and operating limits are also included. in addition, the report has been revised to be consistent with the current SPC report format. Due to the I number and extensive nature of the changes made in this report relative to the previous revision, the changes are not individually identified and no .
change bars are presented. ;
l l
i (a) ATRIUM is a. trademark of Siemens.
Siemens Power Corporation- _ .
~
j
EMF 96-125 LaSalle Unit 2 Cycle 8 Revision 2
- Reload Analysis Page ii Contents
- 1. Introduetion...................................................................................................1-1
- 2. Fu el M e c h a nic al D e sig n An alysis .... . . .... . . . . .. .. ... . . . . . .. ... .. .. . ........ ... ..... ... . .. . ...... .. . .. 2- 1
- 3. Th e rm al- H yd raulic D esig n Analysis ....... ..... ...... . . . . . .. . ... .. ... ...... ... . . .......... ... ..... ... . 3 - 1 3.2. H yd raulic C ha ra et e riz ation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . 3 1 3.2.1 H yd ra ulic C om p atibility. . . . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3- 1 3.2.3 Fu el Centerfin e Temperature .. .. ......... . . .. . ... .... .. ... ... ....... .. ........ . . 3- 1 3.2.5 BypassFlow.................................,........................................31 3.3 MCPR Fuel Cladding Integrity Safety Limit (SLMCPR) ............................... 3-1 3.3.1 Coolant Thermodynamic Condition ................................. ......... 3-1 3.3.2 Design Basis Radial Power Distribution...................................... 3 1 3.3.3 Design Basis Local Power Distribution....................................... 3 2
- 4. N u clea r D e sig n An alysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. . . 4- 1 4.1 Fuel Bundle Nuclear Design Analysis ................................................ ..... 4-1 4.2 C o re N u cie a r D e sig n Analysis ... .. .. . . .... . . . . . . . .. .. ... .. . .. ... .... . ..... ... . ........ ... . . . 4-2 4.2.1 C o r e C o n fi g u ra t io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . 4-2 l 4.2.2 C o re R e a ctivit y C ha ra ct eristic s . .. .. . .. .... . . . . . . .. ... ... . ... ..... . . ..... .. . ... 4-2 l 4.2.4 l C o re H yd ro d yna mic S t a bility . . .... . . . . .. . ... . . . .. . ... .. . ..... .... .. . . ...... ... . . 4-2
- 5. Anticipated Operational O ccurrences ............................ .................................... 5- 1 l 5.1 Analysis of Plant Transients at Rated Conditions...................................... 5-1 5.1.1 12.000 mwd /MTU Cycle Exposure ........ .................... .............. 5-1 l 1
5.1.2 E O C Lic ensing E x p o su re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1 -3 l
t 5.2 Analysis f o r Red u ced Flo w Operation .. .. . . . . . . . ..... .. .............. .. ................ . .. 5-2 5.3 Analysis for Reduced Power Operation .................................................. 5 2 l 5.4 A S M E O verp res su riz a tion A nalysis .... . . .. . .. . . .. . .. .. . . . . . .... . .. .. . . . . . . .. .. .. ... . .. . . . 5 2 5.5 C o nt r al R od Wit h d ra wal E rro r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .
5.6 F u el L o a d in g E r r o r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3 5.7 Determin ation of Thermat Margins ..... ... . . . ..... .... ..... ............ ..... . . . . . .... . . .. . . . 5 3 1
i I
- 6. Po st u l at e d A c cid e nt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I. . . . . . .
6.1 L o s s - o f- C o ol a n t A c cid e nt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i l
6.1.1 B re a k Lo c atio n S pe ctru m.. . .. . ... ... . . .. . . ... . ... . ... .... . ...... .... .. . ..... .. .. . 6- 1 1
1 6.1.2 B re a k Siz e S pe ctru m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... ... . .. .. .... . .. . . 6- 1 6.1.3 M A P LH G R An al y s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 - i 6.2 C o nt r ol Rod Drop Ac cid ent . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .. . .. .. .. . ..... . ... . . 6- 1 6.3 S pe nt Fu el C as k D rop A c cid ent ...... . .. . . ... . . ...... . ..... . . ...... .. . .. . . .. .. ... . . . ... ..... . 6-2
- 7. Te c hni c al S p e cifi c atio n s . . .. . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .. . . . . . . . .. .. . . . . ... .. . .. . . .. . . . . . . . . 7- 1 7.1 Limitin g S af e t y S yst em S ettin g s .... ... .. . .. . . . .... . ...... . .... .. ... .. . ... ...... ........... . 7- 1 7.1.1 l MCPR Fuel Cladding Integrity Safety Limit................................. 7-1 1 7.1.2 Steam Dome Pressure Safety Limit............................ .............. 7-1 i
l i
I i 1 l
! Siemens Tower Corocration - -- - - - - - - -
EMF 96-125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page iii 7.2 Limitin g C on ditions f or Opera tion . .. .... . . . . . . . .. .. .. . .. . . . .. . . .. . .... . .. ... .. . ... .... . . . <..... . ... . 7- 1 7.2.1 Average Planar Linear Heat Generation Rate...... ....................... 7-1 7.2.2 Minim u m Critic al Pow er R a tio . .. .. .. .... .. . ... . . .. . .. ... . . . . . . . . . . . . ......... .. 7- 1 j 7.2.3 Lin e a r H e at G e n e ration R a t e .. .... . . .. . . .. . .. ... . . ...... . . . ... .... . .. . ........ . . 7-2 {
i i
- 8. M e t h od olo g y R e f eren c e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8- 1 9.
A d diti c nal R e f e r e n c es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1 Tables Table 1.1 EO D a n d E O O S Opera tin g Condition s .. . .. .. . . .. . . .... .. . .. . ... . ... .... . .... . . .. ... . ... 1 -2 Table 4.1 N e ut ro nic D e sig n Valu e s . . .. . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .... .. 4-4 Table 5.1 12,000 mwd /MTU Base Case and EOOS MCPR, Limits and LHGRFAC, Multipliers for TSSS Insertion Times................................... 5-4 Table 5.2 EOC Base Case and EOOS MCPR, Limits and LHGRFAC, Multipliers f o r TS S S In s ertion Tim e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Table 5.3 Coastdown Operation Base Case and EOOS MCPR, Limits and LHGRFAC, Multiviers for TSSS insertion Times................................... 5 8 Table 5.4 FFTR/Coastdown Operation Base Case and EOOS MCPR, Limits and LHGRFAC, Multipliers for TSSS Insertion Times ................................. 5-10 Table 5.5 Base Case MCPR, Limits and LHGRFAC, Multipliers for NSS I n s e rt i o n Ti m es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Figures Figure 3.1 Radial Power Distribution for SLMCP Determination .......................... 3-3 Figure 3.2 LaSalle Unit 2 Cycle 8 Safety Limit Local Peaking Factors SPC A9 3 81 B-13 GZ7-80M With Channel Bow ..................................... 3-4 Figure 3.3 LaSalle Unit 2 Cycle 8 Safety Limit Local Peaking Factors SPCA9-384B-11 GZ6-80M With Channel Bow ..................................... 3-5 Figure 4.1 LaSalle Unit 2 Cycle 8 403L-13G7 Enrichment Distribution................... 4-5 Figure 4.2 LaSalle Unit 2 Cycle 8 430L-11 G7 Enrichment Distribution ................... 4-6 Figure 4.3 LaSalle Unit 2 Cycle 8 406L 11G6 Enrichment Distribution................... 4-7 Figure 4.4 LaSalle Unit 2 Cycle 8 434L 10G6 Enrichment Distribution................... 4-8 Figure 4.6 LaSalle Unit 2 ATRIUM-9B SPCA9-381B.13GZ7-80M A s s e m b l y D e si g n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 - 9 Figure 4.6 LaSalle Unit 2 ATRIUM-9B SPCA9 3848-11GZ6-80M A s s e m bly D e s i g n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4- 1 1 Figure 4.7 LaSalle Unit 2 Cycle 8 Reference Loading Map (One-Quarter of S ymm et ric al C o re Loa din g ) . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4- 13 Figure 5.1 Flow Dependent MCPR Limits for Manual Flow Control Mode.............. 5-13 Figure 5.2 Flow Dependent LHGR Multipliers for ATRIUM 9B Fuel....................... 5-14 Figure 5.3 12,000 mwd /MTU Base Case Power Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times ........................................... 5-15 Siemens Power Corporation
EMF-96-125 i Revision 2 t.eSalle Unit 2 Cycle 8 Page iv Relobd Analysis L
4 Figure 5.4 12,000 mwd /MTU Base Case Power Dependent 4CPR Limits for G E 9 Fuel - TS S S Ins ertion Tim es . .. .. .. . . .. . . . ... ..... .. . . . . .. . .... .... .. . . .... . ...... 5 Figure 5.5 EOC Base Case Power Dependent MCPR Limits for ATRIUM-9B Fu el - TS S S In s e rtion Tim e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .
Figure 5.6 EOC Base Case Power Dependent MCPR Limits for GE9 Fu el - TS S S In s ertion Tim e s . . . . . . . . . . . . .. ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Figure 5.7 12,000 mwd /MTU Base Case Power Dependent MCPR Limits for 0
ATRIU M 9 B Fu el - N S S Ins e rtion Times ................ ............................ 5- 19 f 12,000 mwd /MTU Base Case Power Dependent MCPR Limits for l Figure 5.8 G E 9 Fu el - N S S Ins e rtio n Tim e s .. ...... ... ..... ..... ......... .... . . .... ... .. ..... ..... 5-2 0 Figure 5.9 EOC Base Case Power Dependent MCPR Limits for ATRIUM-9B l
F u el - N S S Ins e rtion Tim es . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . 5 - 21 i Figure 5.10 EOC Base Case Power Dependent MCPR Limits for GE9
' Fu el - N S S Ins e rtion Tim es . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . ..
Figure 5.11 Starting Control Rod Pattern for Control Rod Withdrawal Analysis ....... 5-23 g
n Figure 7.1 Protection Against Power Transient LHGR Limit for ATRIUM-98 Fuel..... 7-4 r
u .
l l
4 r
i
r EMF-96-125 -
LaSa!!e Unit 2 Cycle 8 Revision 2 Reload Analysis Page v Nomenclature 4
AOO abnormal operational occurrence APRM average power range monitor BOC beginning of cycle CPR critical power ratio CRWE control rod withdrawal error DR decay ratio EFPH effective full power hour EOC end of cycle EOD extended operating domain EOFP end of full power -
EOOS equipment out of service ELLA extended load line limit area FFTR final feedwater temperature reduction FHOOS feedwater heater out of service FWCF feedwater controller failure ICF increased core flow LFWH loss of feedwater heater LHGR linear heat generation rate LHGRFAC LHGR multiplier LPRM local power range monitor LRNB load rejection no bypass MAPLHGR maximum average planar linear heat generation rate MCPR minimum critical power ratio MSIV main steam isolation valvo MWR metal water reaction NSS nominal scram speed OLMCPR operating limit minimum critical power ratio PAPT protection against power transient PCT peak clad temperature RPT _ recirulation pump trip RVOOS relief valve out of service SLMCPR ~ .saf etylim it m ii t cal power rat i o n mum cr ii SLO single-loop operation SPC Siemens Power Corporation SRVOOS- safety / relief valve out of service
.- N # O
3/ .
~t
/
EMF 96-125:
LaSalle Uni: 2 Cycle if . Revision 2
. Reload Analysis Page vi TBVOOS . turbine bypass valves out of service TCV . turbine control valve TIP traversing in-core probe TIPOOS traversing in-core probe out of service TSSS technical specification scram speed UFSAR updated final safety analysis report ACPR change in critical power ratio
+
4 N
e
' Siemene'Pnwar Onennepinn- .
EMF 96-125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 1-1
- 1. Introduction This report provides the results of the analysis performed by Siemens Power Corporation (SPC) as part of the reload analysis in support of the Cycle 8 reload for LaSalle Unit 2. This report is intended to be used in conjunction with the SPC topical Report XN NF 19(P){A), Volume 4, Revision 1, Application of the ENC Methodology to BWR Reloads, which describes the analyses performed in support of this reload, identifies the methodology used for those analyses, and provides a generic reference list. Section numbers in this report are the same as corresponding section numbers in XN-NF 19(P)(A), Volume 4, Revision 1. Methodology used in this report which supersedes XN-NF-80-19(P)(A), Volume 4, Revision 1, is referenced in Section 8.0. The NRC Technical Limitations presented in the methodology documents, including the documents referenced in Section 8.0, have been satisfied by these analyses.
Analyses performed by Commonwealth Edison Company (Comed) are described elsewhere.
This document alone does not necessarily id.entify the limiting events or the appropriate operating limits for Cycle 8. The limiting events and operating limits must be determined in conjunction with results from Comed analyses.
The Cycle 8 core consists of a total of 764 fuel assemblies, including 256 unirradiated ATRIUM
- 9B"' assemblies and 508 irradiated GE9 assemblies. The reference core configuration is described in Section 4.2.
The design'and safety analyses reported in this document were based on the design and operational assumptions in effect for LaSalle Unit 2 during the previous operating cycle.
The efft ts of channel bow are explicitly accounted for in the safety limit analysis. The extended operating domain (EOD) and equipment out of service (EOOS) conditions presentud in Table ',.1 are supported.
Analyses were performed to support mid-cycle and end of-cycle (EOC) operating limits.
The mid-cycle limits (12,000 mwd /MTU) support operation from BOC to a Cycle 8 exposure of 12,000 mwd /MTU. The EOC limits support operation from 12,000 mwd /MTU to end of cycle.
ATRIUM i: a trademark of Siemens.
4 Siemens Power Corporation
EMF-96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 12 Table 1.1 EOD and EOOS Operating Conditions Extended Operating Domain (EOD) Conditions increased Core Flow Coastdown Final Feedwater Temperature Reduction (FFTR)
- Combined FFTR/Coastdown Equipment Out of Service (EOOS) Conditions'd Feedwater Heaters Out of Service (FHOOS)
Single Loop Operation (SLO)- Recirculation Loop Out of Service Turbine Bypass Valves Out of Service {TBVOOS)
Recirculation Purtp Trip Out of Service (No RPT)
Turbine Control Valve (TCV) Slow Closure and/or No RPT Safety Relief Valve Out of Service (SRVOOS)
Up to 2 TIP Machine (s) Out of Service (or the equivalent number of TIP channels)
Up to 50% of the LPRMs Out of Service TCV Slow Closure, FHOOS and/or No RPT
'd EOOS conditions are supported for EOD conditions as well as the staridard operating domain.
Each EOOS condition combined with 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of
. TIP channels) and/or up to_50% of the LPRMs out of service is supported.
4 Siemens Power Carporation
EMF-96-125 LaSalle Uni 2 Cycle 8 Revision 2 Reload Analysis Page 2-1
- 2. Fuel Mechanical Design Analysis Applicable SPC Fuel Design Reports References 9.1 and 9.2 To assure that the power history for the ATRIUM 98 fuel to be irradiated during Cycle 8 of LaSalle Unit 2 is bounded by the assumed power history in the fuel mechanical design analysis, LHGR operating limits have been specified in Section 7.2.3. In addition, LHGR limits for Anticipated Operational Occurrences have been specified in Reference 9.1 and are presented in Section 7.2.3 as Figure 7.1.
.f
> Siemens Power Corporation
' EMF 96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis . Page 31
- 3. Thermal-Hydraulic Design Analysis 3.2 Hydraulic Characterization 3.2.1 Hydraulic Compatibility Component hydraulic resistances for the fuel types in the LaSalle Unit 2 Cycle 8 core have been determined in single phase flow tests of full-scale assemblies. The hydraulic demand curves for SPC ATRIUM 9B and GE9 fuelin the LaSalle Unit 2 core are provided in -
Reference 9.1, Figure 5.2.
3.2.3 Fuel Centerline Temperature Applicable Report '
ATRIUM 98 Reference 9.1, Figure 3.2 3.2.5 Bypass Flow Calculated Bypass Flow 14.4 Mlb/hr - Reference 9.3 at 100%P/100%F (includes water channel flow)
/
3.3 MCPR Fuel Cladding Integrity Safety Limit (SLMCPR)
Two-Loop Operation 1.08 Reference 9.3 Single-Loop Operation 1.09 3.3.1 Coolant Thermodynamic Condition Thermal Power (at SLMCPR) 4749 MWt FeerJwater Flow Rate (at SLMCPR) 20.4 Mibm/hr Core Exit Pressure (at Rated Conditions) 1031 psia Feedwater Tempereture 420 F 3.3.2 Design Basis Radial Power Distribution Figure 3.1 shows the radial power distribution used in the MCPR Fuel Cladding integrity Safety Limit analysis.
Includes the effects of channel bow, up to 2 TIPOOS (or the equivalent number of TIP .
channels), a 2000 EFPH LPRM calibration interval, and up to 50% of the LPRMs out of service.
Siemens Power Corporation
- EMF 96125
' LaSalle Unit 2 Cycle 8 ~'
Revision 2.
- Reload Analysis ' Page 3-2 3.3.3 Desion Basis Local Power Distribution Figures 3.2 and 3.3 show the local power peaking factors used in the MCPR Fuel Cladding integrity Safety Limit analysis.
-SPCA9 3818-13GZ7-80M ' Figure 3.2 SPCA9 384B-11GZ6-80M Figure 3.3 d
4-t - ,
Siemens Pov7r Corporation . ,, . _ .. . .
EMF 96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 3 3 100 , , , , , , , ,
75 -
~
m D
E m -
o % -
c -
o -. -
.o - -
E 25 - - - -
1 _
4 l _
f 0 '
.0 .1 2 3 .4 3 .6 .7 .8 .9 1.0 1.1 1.2 13 1.4 13 1.6 Radial Dower Peaking
{
I i
I Figure 3.1 Radial Power .~;stribution I
i for SLMCPR Determination e
4 e
4 i
e 4
t 6
Siemens Power Corporation
EMF 96-125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 3-4 Control Rod Corner o
t 1.110 1.138 1.129 1.086 1.148 1.070 1.096 1.094 1.057 r
o 1 1.138 0.884 1.053 1.022 0.773 0.995 0.770' 1.018 1.071 R
0 1.129 1.053 1.029 1.087 1.108 1.062 0.964 0.749 1.052 d
C 1.086 1.022 1.087 0.795 0.948 1.012 Internal r
1.148 0.773 1.108 Water 1.067 c.727 ?072 L- "..
1.070 0.995 1.062 Channel 1.032 0.958 1.008 1.096 0.770 0.964 0.795 1.0G7 1.032 0.732 0.971 1.040 1.094 1.018 0.749 0.948 0.727 0.958 0.971 0.808 1.041 1.057 1.071 1.052 1.012 1.072 1.008 1.040 1.041 1.011 FiJte 3.2 LaSalle Unit 2 Cycle 8 Safety Limit Local Peaking Factors SPCAS 381B 13GZ7-80M With Channel Bow i
Siemens Power Corporation
EMF 96-125 LaSalle Uni: 2 Cycle 8 -
Revision 2 Reload Analysis Page 3-5 Controf Rod Corner o
n t 1.072 1.103 1.095 1.056 1.123 1.047 1.075 1.070 1.026 r
o i 1.103 0.908 1.029 1.003 0.807 0.994 1.007 0.874 1.048 R
0 1.095 1.029 1.006 1.065 1.094 1.055 0.982 0.989 1.036 d
C 1.056 1.003 1.065 Internal 0.848 0.961 0.996 r
1.123 0.807 1.094 Water 1.067 0.765 1.055 1.047 0.994 1.055 Channel 1.025 0.949 0.986 1.075 1.007 0.982 0.848 1.067 1.025 0.763 0.960 1.014 1.070 0.874 0.989 0.961 0.765 0.949 0.960 0.836 1.013 1.026 1.048 1.036 0.996 1 055 0.986 1.014 1.013 0.979 Figure 3.3 LaSalle Unit 2 Cycle 8 Safety Limit Local Peaking Factors SPCA9-384B 11GZ6-80M With Channel Bow Siemens Power Corporation
EMF-96125 '
LaSalle Unit 2 Cycle 8 -
Revision 2.
Reload Analysis Page 41
- 4. Nuclear Design Analysis
- 4.1 FuelBundle Nuclear Design Analysis Assembly Average Enrichment (ATRIUM-9B fuel)
SPCA9-3818-13GZ7-80M 3.81 wt%
SPCA9 3848-11GZ6 80M 3.84 wt%
Radial Enrichment Distribution SPCA9-403L 13G7 Figure 4.1 SPCA9-430L-11 G7 Figure 4.2 SPCA9-406L-11 G6 Figure 4.3 SPCA9-434L-10G6 Figure 4.4.
Axial Enrichment Distribution Figures 4.5 and 4.6 Burnable Absorber Distribution Figures 4.5 and /.6 Non Fueled Rods Figures 4.1-4.4 Neutronic Design Parameters . Table 4.1 Fuel Storage LaSalle New Fuel Storage Vault Reference 9.4 The LSB-1 Reloari Batch fuel designs meet the fuel design limitations defined in Table 71 of Seference 9.4 and therefore can be safely stored in the vault.
LaSalle Unit 1 Spen 1. Fuel Storage Pool (BORAL Racks) Reference 9.5 The LSB-1 Reload Batch fuel designs meet the fuel design limitations defined in Table 2.1 of Reference 9.5 and therefore can be safely stored in the pool.
LaSalle Unit 2 Spent Fuel Storage Pool Reference 9.6 The LSB-1 Reload Batch fuel designs can be safely stored as long as the fuel assembly reactivity limitations defined in Reference 9.6 are met.
< Comed has responsibility to confirm that fuel meets reactivity limitations. >
1 r
I.
?6 Siemens PEwer Corporation
EMF-96-125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 4-2 4.2 Core Nuclear Design Analysis 4.2.1 Core Configuration Figure 4.7 Core Exposure at EOC7, mwd /MTU 26,383 (nominal ~value)
Core Exposure at BOC8, mwd /MTU . 14,154 (from nominal EOC7)
Core Exposure at EOC8, mwd /MTU 27,822 (licensing basis)
NOTE: Analyses in this report are applicable to a core exposure of 27,822 mwd /MTU.
< Cycle 8 short window exposure to be determined by Comed. >
4.2.2 Core Reactivity Characteristics
< This data is to be furnished by Comed. >
4.2.4 Core Hydrodynamic Stability Reference 8.5 The results of STAIF calculations for several points along the current exclusion region boundary on the power / flow map for a flow runback from normal operation are shown below. These calculated decay ratios are for demonstrating and tracking rek.tive core stability behavior from cycle to cycle. The Cycle 8 design basis control rod step-through projection was used to establish expected core depletion conditions. For each power / flow point, decay ratios were calculated at multiple cycle exposures to determine the highest expected decay ratio throughout the cycle. Similar calculations were made for the Cycle 7 core, (comprised entirely of GE fuel assemblies). These calculations show that the limiting Cycle 8 decay ratios (values shown in bold) are either bounded by the Cycle 7 values or show no significant chanse. It is concluded that for nominal operating conditions, Cycle 8 will exhibit stability behavior that is similar to or bounded by the Cycle 7 core.
x Clemene Anwee ('ernnrptinn
J i EMF 96-125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 4 3 LSB Cycle 8 Decay Ratio Results (ADR)
Power / Flow Case Global Decay Ratio Regional Decay Ratio 70/45'*' O.77 (-0.34) 1.13 (0.07) 61/45 O.54 (-0.18) 0.79(0.07) 31/2 6.6 O.71 (0.03) 0.59 (0.20)
For reactor operation unde conditions of power coastdown, single-loop operation, final feedwater temperature reduction (FFTR), and/or operation with feedwater heaters out of service, etc., it is possible that higher decay ratios could be achieved than are shown for normal operation. *ihe comparisons above should be considered ),with the BWROG interim Corrective Actions (ICA) to establish administrative r ia 'egion boundaries for Cycle 8 operation.
DRey - DRey, valees are shown in ( ).
APRM rod block line at 45% flow.
'
- 100% xenon rod line at 45% flow.
- '* 70% xenon rod line at natural circulation.
Siemens Power Corporation
EMF 96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 4-4 Table 4.1 Neutronic Design Values Number of Fuel Assemblies 764 Rated Thermal Power, MWt 3323 Rated Core Flow, Mibm/hr 108.5 Core inlet Subcooling, Btu /lbm 18.0 -
Moderator Temperature, "F 549 Channel Thickness, inch 0.080 Fuel Assembly Pitch, inch 6.0 Wide Water Gap Thickness, inch *' O.281 Narrow Water Gap Thickness, inch"' O.28 Control Rod Data *'
Absorber Material BC4 Total Blade Support Span, inch
- 1.580 Blade Thickness, inch 0.260 Blade Face-to-Face Internal Dimension, inch 0.200 Absorber Rod OD, inch 0.188 Absorber Rod ID, inch 0.138 Percentage B.C, %TD 70
"' The water gap thicknesses presented are based on 80-mil channels for ATRIUM-9B fuel.
"' ' The control rod data represents original equipment control blades at LaSalle and were used in the neutronic calculations.
4 Siemens Power Corporation ; _ - _ _ _ __ - - - _ -
EMF 96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 4-5 Control Rod Corner i
n 1 2 3 3 4 3 3- 2 1 t 2.720 3.530 3.940 3.940 4.530 3.940 3.940 3.530 2.720 r
0 2 G 4 4 G 4 G 6 2 I
3.530 3.690 4.530 4.530 3.690 4.530 3.690 4.190 3.530 3 4- 4 4 4 4 4 G 3 l 3.940 4.530 4.530 4.530 4.530 4.530 4.530 3.690 3.940 C 3 4 4 G 4 3 o 3.940 4.530 4.530 Internal 3.690 4.530 3.940 r
n 3 G 4 # 6 4 e 4.530 3.690 4.530 Water 4.530 3.690 4.530 3 4 4 Channel 4 4 3 3.940 4.530 4.530 4.530 4.530 3.940 3 G 4 G 4 4 G 4 3 3.940 3.690 4.530 3.690 4.530 4.530 3.690 4.530 3.940 2 6 G 4 G 4 4 G 2 3.530 4.190 3.690 4.530 3.690 4.530 4.530 3.690 3.530 1 2 3 3 4 3 3 2 1 2.720 3.530 3.940 3.940 4.530 3.940 3.940 3.530 2.720 1 Rods ( 4) -
2.720 wt% U-235 2 Rods ( 8) -
3.530 wt% U 235 3 Rods -(16) --
3.940 wt% U 235 4 Rods (29) --
4.530 wt% U-235 G Rods (13) -
3.690 wt% U-235 + 7.00 wt% Gd203 6 Rods ( 2) -
4.190 wt% U 235 Figure 4.1 LaSalle Unit 2 Cycle 8 403L-13G7 Enrichment Distribution Siemens Power Corporation
EMF 96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 4 6 Controf Rod Corner o
n 1 2 3 3 4 3 3 2 1 ,
t 2.720' 3.780 4.190 4.190 4.780 4.190 4.190 3.780 2.720 r
0 2 G 4 4 G 4 3 G 2 I
3.780 4.190 4.780 4.780 4.190 4.780 4.190 4.190 3.780 3 4 4 4 4 4 4 3 3 d
4.190 4.780 4.780 4.780 4.780 4.780 4.780 4.190 4.190 C 3 4 4 G 4 3 o 4.190 4.780 4.780 Internal 4.190 4.780 4.190 r
n 4 G 4 4 G 4-e 4.780 4.190 4.780 g
4.780 4.190 4.780 3 4 4 Channel 4 4 3 4.190 4.780 4.780 4.780 4.780 4.190 3 3 4 G 4 4 G 4 3 4.190 4.190 4.780 4.190 4.780 4.780 4.190 4.780 4.190 2 G 3 4 G 4 4 G 2 3.780 4.190 4.190 4.780 ,.190 4.780 4.780 4.190 3.780 1 2 3 3 4 3 3 2 1 2.720 3.780 4.190 4.190 4.780 4.190 4.190 3.780 ~2.720 1 Rods ( 4) ---
2.720 wt% U 235 2 Rods ( 8) --
3.780 wt% U 235 3 Rods (20) --
4.190 wt% U 235 4 Rods (29) -
4.780 wt% U-235 G Rods (11) --
4.190 wt% U 235 + 7.00 wt% Gd203 Figure 4.2 LaSalle Unit 2 Cycle 8 430L 11G7 Enrichment Distribution
, 4
' Siemona Power Corporation -
EMF 96-125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis.
Page 4-7 Controf Rod Corner o
n 1 2 3 3 4 3 3 2 1 t
2.720 3.530 3.940 3.940 4.530 3.940 3.940 3.530 2.720 r
0 2 G 4 4 G 4 4 G I 2 3.530 3.690 4.530 4.530 3.690 4.530 4.530 3.690 3.530 3 4 4 4 4 4 4 4 3 h 3.940 4.530 4.530 4.530 4.530 4.530 4.530 4.530 3.940 C 3 4 4 G 4 3 o 3.940 4.530 4.530 Internal 3.690 4.530 3.940 r
n 4 G 4 4 Water G 4 e 4.530 3.690 4.530 4.530 3.690 4.530 3 4 4 4 Channel 4 3 3.940 4.530 4.530 4.530 4.530 3.940 3 4 4 G' 4 4 G 4 3 3.940 4.530 4.530 3.690 4.530 4.530 3.690 4.530 3.940 2* G 4 4 G 4 4 G 2 3.530 3.690 4.530 4.530 3.690 4.530 4.530 3.690 3.530 1 2 3 3 4 3 3 2 1 2.720 3.530 3.940 3.940 4.530 3.940 3.940 3.530 2.720 1 Rods ( 4) -
2.720 wt% U 235 2 Rods ( 8) --
3.530 wt% U-235 3 Rods (16) --
3.940 wt% U 235 -
4 Rods (33) -
4.530 wt% U 235 G Rods (11) --
3.690 wt% U 235 + 6.00 wt% Gd203 Figure 4.3 LaSalle Unit 2 Cycle B 406L 11G6 Enrichment Distribution Siemens Power Corporation
i 4
EMF-96-125 LaSalle Unit'2 Cycle 8 Revision 2 Reload Analysis Page 4 8 Conte of Rod Corner o
g ,
n 1 ' 2 3 3 4 3 3 2 -1 i
t 2.720 3.780 4.190 4.190 4.780 4.190 4.190 3.780 2.720 r
0 2 G 4 4 , G 4 4 G 2 I
3.780 4.190 4.780 4.780 4.190 4.780 4.780 4.190 , 3.780 3 4 4 4 4 4 4 '4 3 4.190 4.780 4.780 4.780 4.780 4.780 4.780 4.780 4.190 C 3 4 4 G '4 3 o 4.190 4.780 4.780 Internal 4.190 4.780 4.190 r i n 4 G 4 4 6 4 e 4.780 4.190 4.780 Water '
4.780 4.190 4.780 l l
3 4 4 Channel 4 4 3 4.190 4.780 4.780 4.780 4.780 4.190 s
3 4 4 G 4 4 4 4 3 4.190 4.780 4.780 4.190 4.780 4.780 4.780 4.780 4.190 2 G 4 4 G 4 4 G 2 3.780 4.190 4.780 4.780 4.190 4.780 4.780 4.190 3.780 1 2 3 3 4 3 3 2 1 2.720 3.780 4.190 4.190 4.780 4.190 4.190 3.780 2.720 1 Rods ( 4) --
2.720' wt% U-235 2 Rods ( 8) --
3.'780 wt% U-235 '
3 Rods (16) -
4.190 wt% U 235 4 Rods (34) -
4.780 wt% U 235 G Rods (10) --
4.190 wt% U-235 + 6.00 wt% Gd203 Figure 4.4 LaSalle Unit 2 Cycle 8
.. 434L-10G6 Enrichment Distribution a
' Siemens Power Corporation..
l
~ EMF 96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 4 9 1 2 3 3 4 3 3 2 1 SPCA9-0.72L-0GO.0 2 G1 4 -4 G1 4 G2 G3 2 3 4 4^ 4 4 4 4. G2 3 3 4 4 W W'W G1 4 3 4 G1 4 .W W W 4 G1 4 ..
SPCA9-4.03L 13G7.0 3 4 4 W W W 4 4 3 3 G2 4 G1 4 4 G1 4 3 2 G3 G2 4 G1 4 4 G1 2 1 2 3 3 4 3 3 2 1 Fuel Rod No.
Type Rods 1 4 SPC A9-4.'30L-11 G7.0 2 8 3 16 4 29 G1 9 G2 4 G3 2 SPCA9-0.72L-0GO.0 Figure 4.5 LaSalle Unit 2 ATRIUM-9B SPCA9 381B-13GZ7-80M Assembly Design l
' Siemens Power Corporatiori:.
EMF-96-125 1.aSalle Unit 2 Cycle 8 Revision 2 Reload Analysis . Page 410 SPCA9 3818-13GZ7-80M 1 2 3 4 G1 G2 G3 A A A A A A A B C E G I I F D F H J F J A A A A A A A A 0.72 wt% U-235 B 2.72 wt% U-235 C 3.53 wt% U-235 D 3.78 wt% U-235 E 3.94 wt% U-235 F 4.19 wt% U-235 G 4.53 wt% U 235 H ' 4.78 wt% U-235 1 3.69 wt% U-235 + 7.00 wt% Gd303 J 4.19 wt% U-235 + 7.00 wt% Gd203 Figure 4.5 LaSalle Unit 2 ATRIUM 9B SPCA9-381B-13GZ7-80M Assembly Design (Continued)
^
Siemens Power Corporation
EMF 96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis ~ Page 4 1 2 3 '3 4 3 3 2 '1 SPCA9-0.72L-0GO.0 2- G1 4 4 G1 4 4 G1 2 3 4 4 4 4 4 ~4 4 3 3 4 4 'W W W G1 4 3 SPCA9-4.06L-11 G 6.0 4 G1 4 W W W 4 G1 4 3 4 4 W W W 4 4 3 3 4 4 G1 4 4 G2 4 3 2 G1 4 4 G1 4 4 G1 2 1 2 3 3 4 3 3 2 1 Fuel Rod No.
Type Rods SPCA9-4.34L 10G6.0 1 4 2 8 3 16 4 33 G1 10 G2 1 SPCA9-0.72L-0GO.0 Figure 4.6 LaSalle Unit 2 ATRIUM 9B '
SPCA9-384B-11GZ6 80M Assembly Design J
- . Siemens Power Corporation
EMF 96125 -
LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 412, SPCA9 3848-11GZ6-80M 1 2 3 4 G1 G2 A A A A A A B C E G I i ,
u.
D F H J H A A A A A A A O.72 wt% U 235 B 2.72 wt% U 235 C 3.53 wt% U-235 D 3.78 wt% U-235 E 3.94 wt% U 235 F 4.19 wt% U 235 G 4.53 wt% U 235 H 4.78 wt% U-235 1 3.69 wt% U-235 + 6.00 wt% Gd202 J 4.19 wt% U-235 + 6.00 wt% Gd203 Figure 4.6 LaSalle Unit 2 ATRIUM 9B SPCA9 384B 11GZ6-80M Assembly Design
- (Continued)
' %mene Power Cornorntion .
EMF 96-125
{ LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 4-13 i l
1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 1 12 2 14 13 13 1 14 12 13 2 14 13 13 2 10 2 2 14 13 14 2 15 2 14 1 15 13 14 15 1 10 3 14 13 14 2 15 13 15 2 14 1 14 15 1 15 11 4 13 14 2 12 12 14 1 13 13 13 15 12 13 -12 10 5 13 2 15 12 12 2 14 13 13 15 14 13 13 12 10 6 1 15 13 14 2 15 12 15 2 14 13 14 15 12 10 7 14 2 15 1 14 12 15 13 15 1 15 15 1 12 10 8 12 14 2 13 13 15 13 12 2 14 14 1 1 10 9 13 1 14 13 13 2 15 2 13 15 1 1 10 10 2 15 1 13 15 14 1 14 15 13 10 10 10 11 14'13 14 15 14 13 15 14 1 10 10 12 13 14 15 12 13 14 15 1 1 10 13 13 15 1 13 13 15 1 1 10 10 14 2 1 15 12 12 12 12 10 15 10 10 11 10 10 10 10 Fuel Number Bundle Cycle Type of Assemblies Description Loaded 1 96 G E 9 B-P8 CWB322-1 1 GZ-100M-150-C E CO 7 2 80 GE98 P8CWB320-9GZ-100M-150-CECO 7 10 93 GE9B-P8CWB302-9GZ-100.M-150-T 5 11 8 GE9B-P8CWB300-9GZ-100M-150-T 5 12 80 GE9B-P8CWB313 9GZ-100M 150-CECO 6 13 151 GE9B-P8CWB316-9GZ-100M-150-CECO 6 14 128 SPC A9-381 B-13GZ7-80M 8 15 128 SPC A9-384B-11 GZ6-80M 8 Figure 4.7 LaSalle Unit 2 Cycle 8 Reference Loading Map (One-Quarter of Symmetrical Core Loading)
Siemens Power Corporation
EMF 96-125 -
LaSalle' Unit 2 Cycle 8f Revision.2 Reload Analysis ! Page 51
- 5. Anticipated Operational Occurrences Applicable Generic Transient Analysis Report' Reference 9.7 5,1 Analysis of Plant Transients at Rated Conditions- Reference 9.3 Limiting Transients: Load Rejection No Bypass (LRNB)'
Feedwater Controller Failure (FWCF)
Loss of Feedwater Heating (LFWH) 5.1.1 12,000 mwd /MTU Cycle Exposure Peak Peak Peak Lower
. Neutron Heat Plenum Scram Flux Flux Pressure' ACPR' Transient Speed (% Rated) (% Rated) (psig) ATRIUM-9B/GE9 LRN B TSSS 323.4 119.2 1194 0.27 / 0.30 FWC F TSSS 255.4 117.7 1160 0.24 / O.27 LRN B NSS 268.4 114.8 1186 0.23 / O.28 LFWHS' "' "'
5.1.2 EOC Licensing Exposure Peak Peak Peak l 'wer Neutron Heat Plenum Scram Flux Flux Pressure ACPR Transient Speed (% Rated) (% Rated) (psig) ATRIUM-98/GE9 LRN B TSSS 389.9 124.1 1194 0.31 / O.32 FWC F TSSS 310.1 121.6 1167 0.27 / 0.30 LRN B NSS 356.4 120.3 1193 0.28 / O.31 l
FWC F NSS 278.7 118.8 1160 0.25 / O.28 LFWH*' "' "'- S' "'
Based on 100%P/105%F conditions.
S' This data to be furnished by Comed. - -
i Siemens Power Corporation L_____ -
I
, EMF 96-125 j LaSalle Unit 2 Cycle 8 Revision 2 ;
Reload Analysis Page 5-2 I
^
5.2 Analysis for Reduced Flow Operation Reference 9.3 Limiting Transient: Recirculation Flow increase Transient MCPR, Manual Flow Control ' ATRIUM-9B and GE9 Fuel _ Figure 5.1 LHGRFAC, - ATRIUM 98 Fuel Figure 5.2 MAPFAC, - GE9 Fuel '*'
MCPR, and LHGRFAC, results are applicable at all Cycle 8 exposures and in all EOD, EOOS and combined EOD/EOOS scenarios presented in Table 1.1.
5.3 Analysis for Reduced Power Operation Reference 9.3 Limiting Transient: Load Rejection No Bypass (LRNB)
Feedwater Controller Failure (FWCF)
MCPR, Base Case Operation Tables 5.1, 5.2 and 5.5, Figures 5.3-5.10 LHGRFAC, Base Case Operation *' Tables 5.1, 5.2 and 5.5 MCPR, EOD, EOOS and EOD/EOOS Conditions Tables 5.1-5.4 LHGRFAC, EOD, EOOS and EOD/EOOS Conditions *' Tables 5.1-5.4 MAPFAC, - All Operating Conditions *' <To be furnished by Comed.)
5.4 ASME Overpressurization Analysis Reference 9.3 Limiting Event MSIV Closure Worst Single Failure Valve Position Scram Maximum Vessel Pressure (Lower Plenum) 1310 psig Maximum Steam Dome Pressure 1280 psig 5.5 Control Rod Withdrawal Error Starting Control Pattern for Analysis Figure 5.11
< This data is to be furnished by Comed. >
'*' This data to be furnished by Comed.
" LHGRFAC, values presented are applicable te SPC fuel. GE MAPFAC, lirrJts will continue to be applied to GE9 fuel at off rated power.
% mens Power Cornoration
l
! )
EMF 96-125 l LaSalle Unit 2 Cycle 8 Revision 2 i
i Reload Analysis Page 5 3 f,
5.6 FuelLoading Error i
The fuel loading error, including fuel mislocation and misorientation, is classified as an
, accident. By demonstrating the fuelloading error meets the more stringent Anticipated Operational Occurrence (AOO) requirements, the offsite dose requirement is assured to be
. met. Because the events listed below result in a ACPR value that is less than that of the limiting transient, the AOO requirements and hence the off-site cose requirements are met for the fuelloading error. For LaSalle Unit 2 Cycle 8, the fresh SPf: ATRIUM-9B fuelis the limiting fuel for loading errors.
Therefore, the values reported below for the fresh SPC ATRIUM-0B fuel bound all fuel types found in the core. !
)
Event ACPR Mislocated Bundle 0.17 Misoriented Bundle 0.18 For the fuelloading error, the fresh reload .'uel complies with the SPC 1 % plastic strain criteria via conformance to SPC transient LHGR limits.
5.7 Determination of ThermalMargins l l
The results of the analyses presented in Sections 5.1-5.3 are used for the determination of the operating limit. Section 5.1 provides the results of analyses at rated conditions.
Section 5.2 provides for the determination of the MCPR and LHGR limits r. reduced flow (MCPR,, Figure 5.1; LHGRFACs, Figure 5.2 ). Section 5.3 provides for the determination of the MCPR and LHGR limits at conditions of reduced power (Figures 5.3-5.10, Tables 5.1-5.5). Limits are presented for base case operation and the EOD, EOOS and combined EOD/EOOS scenarios presented in Table 1.1. The results presented are based on the analyses performed by SPC. As indicated above, the final Cycle 8 MCPR operating limits need to be established in conjunction with the results from Comed analysts.
Siemens Power Corporation _ _ ___ _ _ _ _ _ _ _ _
i I EMF-96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 5-4 Table 5.1 12,000 mwd /MTU Base Case and EOOS MCPR, Limits and LHGRFAC, Multipliers for TSSS insertion Times
ATRIUM-9B Fuel GE9 Fuel EOOS/EOD Power Condition (% Rated) MCPR, LHGRFAC, MCPR, Base Case Operation 0 2.60 0.75 2.60 .
25 2.10 0.75 2.10 25 1.90 0.75 1.90 60 1,46 1.00 1.47 100 1.35 1.00 1.39 Feedwater Heaters 0 2.70 0.65 2.70 Out of Service 25 2.20 0.65 2.20 (FHOOS) 25 2.20 0.65 2.20 60 1.52 0.96 1.52 100 1.35 1.00 1.39 Single-Loop O 2.47 0.40 2.47 Operation 25 2.47 0.40 2.47 25 2.47 0.40 2.47 60 2.47 0.40 2.47 100 2.47 0.40 2.47 Turbine Bypass 0 2.60 0.75 2.60' Valves Out of 25 2.10 0.75 2.10 Service (TBVOOS) 25 2.00 0.75 2.00 60 1.54 0.96 1.55 100 1.39 1.00 1.40
"' Limits support operation with any combirtatien of one SRVOOS, up to 2 TIPOOp (or the equivalent number of TIP channels), un to a 13*F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% Cf the LPRMs out of service in the standard, ICF and ELLLA regions of the power / flow map.
_ - __ _ __ ____ __ __i h-A-e G o h -- - + 8 - a __ _ _ _ _ _ ____________
i EMF 96-125
, LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 5 5 Table 5.1 12,000 mwd /MTU Base Case and EOOS MCPR, Limits and LHGRFAC, Multipliers for TSSS Insertion Times"'
(Continued)
ATRIUM-98 Fuel GE9 Fuel EOOS/EOD Power Condition (% Rated) MCPR, LHGRFAC, MCPR, Recirculation Pump 0 2.60 0.75 2.60 Trip Out of Service 25 2.10 0.75 2.10 (No RPT) 25 1.90 0.75 1.90 60 1.49 0.96 1.50 100 1.42 1.00 1.44 Turbine Control O 2.80 0.60 2.80 Valve (TCV) Slow 25 2.30 0.60 2.30 Closure and/or 25 2.30 0.60 2.30 No RPT 60 1.52 0.96 1.53 100 1.42 1.00 1.45 TCV Sluw Closure / O 2.80 0.60 2.80 FHOOS and/or 25 2.30 0.60 2.30 No RPT 25 2.30 0.60 2.30 60 1.55 0.92 1.55 100 1.42 0.98 1.45 Limits support operation with any combination of one SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 13'F reduction in feedwater temperature (except
.. and ELLLA regions of the power / flow map.
t I Siemens Power Corporation
. EMF 96125 Revision 2 LaSalle Unit 2 Cycle 8 Page 5-6 Reload Analysis Table 5.2 EOC Base Case and EOOS MCPR, Limits and LHGRFAC, Multipliers for TSSS Insertion Times" ATRIUM-98 Fuel GE9 Fuel EOOS/EOD Power Condition MCPR, LHGRFAC, MCPR,
(% Rated)
Base Case Operation 0 2.60 0.75 2.60 .
25 2.10 0.75 2.10 25 1.90 0.75 1.90 60 1.46 1.00 1.47 100 1.39 1.00 1.40 0 2.70 0.65 2.70 Feedwater Heaters 25 2.20 0.65 2.20 Out of Service 25 2.20 0.65 2.20 (FHOOS) 60 1.52 0.96 1.52 100 1.39 1.00 1.40 Single-Loop 0 2.47 0.40 2.47 Operation 25 2.47 0.40 2.47 25 2.47 0.40 2.47 60 2.47 0.40 2.47 100 2.47 0.40 2.47 Turbine Bypass 0 2.60 0.75 2.60 Valves Out of 25 2.10- 0.75 2.10 25 2.00 0.75 2.00 Service (TBVOOS) 60 1.54 0.96 1.55 100 1.42 1.00 1A3 S' Limits support operation with any combination of one SRVOOS, 'up to 2 TIPOOS (or the equivalent number of TIP char.nels), up to a 13*F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF and ELLLA' regions of the power / flow map.
EMF 96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 5 7 i
Table 5.2 EOC Base Case and EOOS MCPR, Limits and LHGRFAC, Multipliers for TSSS insertion Times"'
(Continued)
ATRIUM-9B Fuel GE9 Fuel EOOS/EOD Power Condition (% Rated) MCPR, LHGRFAC, MCPR, Recirculation Pump 0 2.60 0.75 2.60 Trip Out of Service 25 2.10 0.75 2.10 (No RPT) 25 1.90 0.75 1.90 60 1.50 0.96 .1.50 100 1.46 1.00 1.48 Turbine Control 0 2.80 0.60 2.80 Valve (TCV) Slow 25 2.30 0.60 2.30 Closure and/or 25 2.30 0.60 2.30 No RPT 60 1.54 0.96 1.54 100 1.48 1.00 1.48 TCV Slow Closure / 0 2.80 0.60 2.80 FHOOS and/or 25 2.30 0.60 2.30 No RPT 25 2.30 0.60 2.30 60 1.55 0.92 1.55 100 1.48 0.94 1.48 Limits support operation with any combination of one SRVOOS, up to 2 TIPOOS (or the equivalent number of YlP channels), up to a 13'F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard,ICF and ELLLA regions of the power / flow map.
Siemens Power Corporation
EMF 96125 Revision 2 LaSalle Unit 2 Cycle 8 Page 5-8 Reload Analysis Table 5.3 Coastdown Operation Base Case and EDOS MCPR, Limits and LHGRFAC, Multipliers 8cr TSSS Insertion Times
O 2.60 0.75 2.60 Coastdown Base 25 2.10 0.75 2.10 Case Operation 25 2.00 0.75 2.00 60 1.47 0.96 1.47 100 1.41 0.97 1.42 0 2.47 0.40 2.47 Coastdown With 25 2.47 0.40 2.47 Single-Loop 25 2.47 0.40 2.47 Operation 60 2.47 0.40 2.47 100 2.47 0.40 2.47 0 2.60 0.75 2.60 Coastdown With 25 2.10 0.7.5 2.10 TBVOOS 25 2.00 0.75 2.00 60 1.55 0.95 1.56 100 1.43 0.97 1.44
)
'" Limits support operation with any combination of one SRVOOS', up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 13*F reduction in feedwater te..iperature, and up to 50% of the LPRMs out of service in the standard, ICF and ELLLA regions of the power / flow map.
- a
EMF 96-125 LaSalle Unit 2 Cycle 8 Revision 2 -
Reload Analysis Page 5-9 Table 5.3 Coastdown Operation Base Case and EOOS MCPR, Limits-and LHGRFAC, Multipliers for TSSS insertion Times'd (Continued)
' ATRIUM 9B Fuel GE9 Fuel EOOS/EOD Power Condition (% rated) MCPR, LHGRFAC, MCPR, Coastdown With O 2.60 0.75 2.60 No RPT 25 2.10 0.75 2.10 25 2.00 0.75 2.00 60 1.62 0.87 1.62 100 1.48 0.87 1.49 Coastdown With 0 2.80 0.60 2.80 TCV Slow Closure 25 2.30 0.60 2.30 and/or No RPT 25 2.30 0.60 2.30 60 1.65 0.87 1.65 100 1.51 0.87 1.51
'd Limits support operation with any combination of one SRVOOS, up to 2 TIPOOS (or the egoivalent number.of TIP channels), up to a 13'F reduction in feedws.ter temperature, and up to 50% of the LPRMs out of service in the standard, ICF and ELLLA regions of the power / flow map.
Siemens Power Corporation
EMF-96-125 Revision 2 LaSalle Unit 2 Cycle 8 Page 5-10 Reload Analysis Table 5.4 FFTRICoastdown Operation Base Case and EOOS MCPR, Limits and LHGRFAC, Multipliers for TSSS Insertion Times"'
ATRIUM-98 Fuel GE9 Fuel EOOS/EOD Power MCPR, LHGRFAC, MCPR, Condition (% rated) 0 2.70 0.65 2.70 FFTR/Coastdown Base Case Operation 25 2.20 0.65 2.20 25- 2.20 0.65 2.20 60 1.52 0.09 1.52 100 1.41 0.97 1.42 0 2.47 0.40 2.47 FFTR/Coastdown 25 2.47 0.40 2.47 With Single-Loop 25 2.47 0.40 2.47 Operation 60 2.47 0.40 2.47 100 2.47 0.40 2.47 0 2.70 0.65 2.70 FFTR/Coastdown 25 2.20 0.65 2 20 With TBVOOS 25 2.20 0.65 2.20 60 1.55 0.95 1.56 100 1.43 0.97 1.44
"' Limits support operation with any combination of one SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels) and up to 50% of the LPRMs out of service in the standard,
~
ICF and ELLLA regions of the power / flew map.
L
l .;
EMF-96-125 l
LaSalle Unit 2 Cycle 8 Revision 2 l Reload Analysis Page 511 i
Table 5.4 FFTR/Coastdown Operation Base Case and EOOS MCPR, Limits and LHGRFAC, Multipliers for TSSS Insertion Times
(Continued) '\
ATRIUM 9B Fuel GE9 Fuel -
EOOS/EOD Power I Condition (% rated) MCPR, LHGRFAC, MCPR, FFTR/Coastdown 0 2.70 0.65 2.70 l
Witn No RPT 25 2.20 0.65 2.20 25 2.20 0.65 2.20 60 1.62 0.87 1.62 100 1.48 0.87 1.49 FFTR/Coastdown 0 2.80 0.60 2.80 l With TCV Slow 25 2.30 0.60' 2.30 Closure and/or 25 2.30 0.60 2.30 No RPT 60 1.65 0.87 1.65 100 1.51 0.87 1.57 i i
'" Limits support operation with any combination of ont, SRVOOS, up to 2 TIPOOS (or the ;
equivalent number of TIP channels) and up to 50% of the LPRMs out of service in the standard, ICF and ELLLA regions of the power / flow map.
Siemens Power Corporation '
EMF-96-125 Revision 2 LaSalle Unit 2 Cycle 8 Page 5-12 Reload Analysis Table 5.5 Base Case MCPR, Limits and LHGRFAC, Multipliers for NSS Insertion Times"'
ATRIUM-98 Fuel GE9 Power Exposure MCPR, LHGRFAC, MCPR,
(% Rated) 0 2.60 0.80 2.60 12,000 mwd /MTU 25 2.10 0.80 2.10 25 1.90 0.80 1.90 60 1.43 1.00 1.44 100 1.31 1.00 1.36 0 2.60 0.80 2.60 EOC 25 2.10 0.80 2.10 25 1.90 0.80 1.90 60 1.45 1.00 1.46 100 1.36 1.00 1.39
"' Limits support operation with any combination of one SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 13*F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF and ELLLA regions of the power / flow map. .
l l-l:
l EMF-96125 LaSalle Unii 2' Cycle 8 Revision 2 Reload Analysis Page 5-13 e
l l 1.8 1y .........................., ATRUMB
,,,,, g 1.6 - N, 1.5 - -
.4 ' t g3 1.2 11<
.u 1 .
0 10 20 30 4 $0 60 70 80 90 100 110 kmdRed)
Flow (% rated) ATRIUM-98 GE9 O 1.64 1.70 30 1.64 1.70 102.5 1.08 1.08 105 1.08 .1.08 Figure 5.1 Flow Dependent MCPR Limits for Manual Flow Control Mode le Siemens Power Corporation
EMF 96125
"-vision 2 LaSAlle Unit 2 Cycle 8 Page 514 Reload Analysis L1 1-0.9 -
25 t$
g 0.s-5 0.7 -
0.6 -
0.5 '
0 1O $0 IO IO NO 60 IO 8'O NO - 1do 110 Percent of Roted Flow Flow (% rated) LHGRFAC, O O.69 30 0.69 76 1,00 1,00 105 Figure 5.2 Flow Dependent LHGR Multipliers for ATRIUM 9B Fuel
k EMF 96-125 LaSalle Unit 2 Cycle 8. Revision 2 Reload Analysis Page 5-15
- 2.15 2.65 -
235 -
2.45 -
2.35 -
2.25 -
2.15 -
-2.05 :
1.95 -
1.t5 -
1.75 -
1.65 -
155 -
1A5-1.35 -
, 1.25 -
- 1.15 0
l 10 20 30 40 50 60 70 80 90 100 110 i
- t Core Power (% of Rated)
I
'1 Power (% rated) MCPR, Limit 1
o 2.60 25 2.10 25 1.90 80- 1.46 100 , 1.35 Figure 5.3 12,000 mwd /MTU Base Case Power Dependent
- MCPR Limits for ATRIUM 98 Fuel - TSSS Insertion Times 8iemens Power Corporation -
[ . . . . . . .
. EMF-96125
. Revision 2 LaSalle Unit 2 Cycle 8 Page 5 Reload Analysis 175 2.65 -
255-245 -
225-225-115 -
2.05 -
195 -
125-175-1.65-1.55 -
1.45-125-1.25 -
0 10 20 30 40 50 60 70 M M @ 8 Cae Poe(%dRaed)
Power (% rated) MCPR, Limit 0 2.60 25 ' 2.10 25 1.90 60 1 47 '
100 1.39 ;
Figure 5.4.12,000 mwd /MTU Base Case Power Dependent MCPR Limits for GE9 Fuel- TSSS Insertion Times
),-
.- =. *_ _ _ . > * ,
EMF 96-125 LaSalle Unit 2 Cycle 8 Revision 2 Flefoad Annivsis Page 517 2.75 2 65-2.55
\
2 45-2M-225-2.15 -
2.05 -
1.95 -
115<
1.75-1.65 -
1.55 -
1.45 -
1.35 -
1.25 1.15 0 10 20 30 40 50 60 70 80 90 100 110 Core Peer (%dRated)
Power (% rated) MCPR, Limit 0 2.60 25 2.10 25 1.90 60 1.46 100 1.39 Figure 5.5 EOC Base Case Power Dependent MCPR Limits for ATRIUM-98 Fuel- TSSS Insertion Times L Siemens Power Corporation
EMF 96125 taSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 518.
2.75
'2E 2.55 -
2A5-21 2.25 -
2.15 -
\
2E 1.95 -
1.85 -
1.75 -
1.65-1E 1A5-1.35 -
- 1.25 -
1.15 20 30 40 50 60 70 80 90 100 110 0 10 Cat Pons (%of Reed)
Power (% rated) MCPR, Limit O 2.60 25 2.10
-25 1.90 60 1.47-100 1.40 Figure 5.6. EOC Base Case Power Depei; dent MCPR Limits for GE9 Fuel - TSSS insertion Times -
I-
- u. La. .
- L ,. n . . . ? . ..
a:
EMF-96-125 LaSalle Unit 2 Cycle 8. . Revision 2 Reload Analysis Page 5-19 2.15 2E -
2.55 -
~ 2.45 -
22-2.26 -
2.15 - -
2.05 -
1 95 - -
t05 -
115-t65 -
1.55 -
145 -
12-1.25 -
1.15 0 10 20 30 40 50 80 70 80 90 100 110 Core Power (% of Rated)
Power (% rated) 'MCPR, O 2.60 25 2.10 25 1.90 60' 1.43 .-
100- 1.31 Figure.5.7.12,000 mwd /MTU Base Case Power Dependent MCPR
.. Limits for ATRIUM 9B Fuel - NSS lasertion Times I
'j ~
Siemens Power Corporation . .c .
EMF-96-125
- Revision 7 Lass 11e Unit 2 Cycle 8 Page 5-20 Reioad Analysis 215 2 45 -
2.55 -
2.45 -
2.35 -
225-2.15 -
2.05 -
1.95 -
1h5-1.75-115-1.55 -
1.45 -
~
1.35 -
125 -
1.15 60 70 80 90 1J0 110 0 10 20 30 40 50 Cae Power (% dRated)
Power (% rated) MCPR, O 2.60 25 2.10 25 1.90 60 1.44 100 1.36 Fig'ure 5.8 12,000 mwd /MTU Base Case Power Dependent MCPR Limits for GE9 Fuel - NSS Insertion Time:; -
-....n.....c.......,..
EMF 96-125-LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Pace 5 21 2.75 2 65 -
2.55-2A5-235-2.25 -
2.15 -
2.05 -
1.95 -
1.65 -
115-1.65 -
1.55 -
1.15 0 10 20 30 40 50 60 70 80 90 100 110-CorePower(% of Raed)
Power (% rated) MCPR, 0 2.60 25 2.10 25 1,90 60 '- 1,45 100 1.36 Figure 5.9 EOC Base Case Power Dependent MCPR Limits for ATRIUM 9B Fuel - NSS insertion Times -
Siemens Power Corporation.
EMF-96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 5 22-175 2.65 >
1 55 -
2.45-235-2.25-115-2.05 -
195 -
185-175-165 -
155< ,
145-135-1.25 -
115 30 40 50 60 70 80 90 100 110 0 10 20 Core Power (% of Reed)
Power (% rated) MCPR, 0 2.60 25 2.10 25 1 90 60 1.46 100 1,39 Figure 5.10 EOC Base Case Power Dependent MCPR Limits for GE9 F Jet - NSS Insertion Times ci. .. , n-... . r -. . _..i. ( __
EMF-96-125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis - : Page 5 23
.f R
i
< This data is to be furnished by Comed. >
4 1
i Figure 5.11 Starting Control Rod Pattern for Control Red Withdrawal Analysis {
i a
i Siemens Power Corporation - I
EMF 96125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 61
- 6. Postulated Accidents 6.1 Loss-of-Coolant Accident 6.1.1 Break Location Spectrum Reference 9.8 6.1.2 Break Size Spectrum Reference 9.8 6.1.3 MAPLHGR Analyses Reference 9.9 The MAPLHGR limits presented in Reference 9.9 are valid for LaSalle Unit 2 ATRIUM 9B (LSB-1) fuel for Cycle 8 operation.
Limiting Break: 1.1 ft8 Break Recirculation Pump Discharge Line High Pressure Core Spray Diesel Generator Single Failure Considering all exposures, the peak clad temperature and peak local metal-water reaction for ATRIUM-98 fuel for Cycle 8 are reported below.
Maximum PCT Peak Local Metal-Water Reaction
(*F) (%)
ATRIUM-9B Fuel 1807 0.72 The peak core wide metal water reaction is < 0.16%. '
i' 6.2 ControlRodDrop Accident LaSalle Unit 2 is a Banked Position Withdrawal Sequence (BPWS) plant, in order to ' allow the site the option of shutting down the reactor by inserting control rods using a simplified control rod sequence, a control rod drop accident analysis was performed for the simplified 1
sequence as defined in Attachment 3 of Reference 9.11. The analysis determined that the .
l simplified sequence meets the Technical Specification limit of 280 cal /g for a control rod drop accident. A 0.32%Ak adder is included in the analysis to account for possible rod mis-positioning errors.
I
. Dropped control Rod Worth without 0.32%Ak adder, %Ak 1.112' t
Dropped control Rod Worth with 0.32%Ak adder, %Ak 1.432 Doppler Coefficient, (%Ak/k)/'F -10E-6 EOC Effective Delayed Neutron Fraction 0.0053 Siemens Power Corporation .
- l
ETAF 96125 -
Revision 2, LaSalle Unl: 2 Cycle 8, Reload Analysis .
Page 6 2
'?
Effective Delayed Neutron Fraction used -0.0045-Four Bundle Local Peaking Factor 1.362 Max. Deposited Fuel Rod Enthalpy with 0.32%Ak adder, (cal /g) 244.4 Number of Rods Greater than 170 cal /g with 0.32%Ak adder 590 Note that the limit on maximum deposited enthalpy is 280 cal /g and the limit on the number of rods grater than 170 cal /gm (failed rods)is 770.
6.3 Spent Fuel Cask Drop Accident The radiological consequences of a spent fuel cask drop accident have been evaluated for SPC ATRIUM fuel designs in conformance with the analysis described in the LSCS UFSAR Section 15.7.5. The analysis is assumed to occur 360 days following shutdown of the reactor, and it is assumed that all 32 fuel assemblies in the cask completely fail as a' result of the accident.
Because the accident is assumed not to occur sooner than 360 days following shutdown of the reactor, the source term for the accident will be very low due to fission product decay. Hence, the commensurate radiological whole-body and thyroid doses will be very low. The results of this analysis demonstrate that spent fuel cask drop accidents involving
. SPC ATRIUM fuel will not exceed the established radiological whole body and thyroid dose limits which are a small fracticn of the 10 CFR 100 limits for radiological exposures.
6 f
'k I
F 3 'S SImes om e bMneebw f at he 4 estimes -
\
EMF.96125 LaSalle Unit 2 Cycle 8 Revision 2 '
Reload Analysis Page 71
- 7. Technical Specifications 7.1 Limiting Safety System Settings .
7.1.1 MCPR Fuel Cladding Integrity Safety Limit '
MCPR Safety Limit (all fuel) - two-loop operation 1.08"'
MCPR Safety Limit (all fuel) - single-loop operation 1.09*
7.1.2 Steam Dome Pressure Safety Limit .
Pressure Safety Limit 1325 psig 7.2 Umiting Conditions for Operation 7.2.1 Average Planar Linear Heat Generation Rate Reference 9.9 ATRIUM-98 Fuel GE9 Fuel MAPLHGR Limits MAPLHGR Limits Average Planar Exposure MAPLHGR (GWd/MTU) - (kW/ft) < To be furnished by Comed. >
0.0 13.5
. 20.0 13.5 61.1 9.39 7.2.2 Minimum Critical Power Ratio Rated Conditions MCPR Limit" -
Flow Dependent MCPR Limits:
Manual Flow Control Figure 5.1
- ~ Includes the effects of channel bow, up to 2 TIPOOS (or the equivalent number of TIP channels), a 2000 EFPH LPRM calibration interval and up to 50% of the LPRMs out of service.
" . This data is to be furnished by Comed.
a ,
Siemens Power Corporation -
EMF-96-125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 7 2 Power Dependent MCPR Limits:
Base Case Operation - TSSS Insertion Times Figures 5.3-5.6 Base Case Operation - NSS Insertion Times Figures 5.7-5.10 EOD, EOOS and Combined EOD/EOOS Tables 5.1-5.4 Operation 7.2.3 Linear Heat Generation Rate Reference 9.1 ATRIUM 9B Fuel GE9 Fuel Steady State LHGR Limits Steady State LHGR Limits Average Planar Exposure LHGR (GWd/MTU) (kW/ft) < To be furnished by Comed. >
0.0 14.4 15.0 14.4 61.1 8.32 The protection against power transient (PAPT) linear heat generation rate curve for ATRIUM-9B fuel is identified in Reference 9.1 and is presented here as Figure 7.1 for convenience. LHGRFAC, and LHGRFAC, multipliers are applied directly to the steady state LHGR limits at reduced power, reduced flow and/or EOD/EOOS conditions to ensure the PAPT LHGR limits are not violated during an AOO. Comparison of the Cycle 8 nodal power histories for the rated power pressurization transients with the approved bounding curves to show compliance with the 1% strain criteria for GE9 fuelis discussed in Reference 9.10.
LHGRFAC Multipliers for Off Rated Conditions - ATRIUM-9B Fuel:
i LHGRFAC, Figure 5.2
- LHGRFAC,. Tables 5.1-5.5 i
i b wm.n. Anwer Onennra, inn
EMF-96-125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 7-3 :
-1
- MAPFAC Multipliers for Off Rated Conditions - GE9 Fuel:
MAPFAC, < To be furnished by Comed. >
MAPFAC, < To be furnished by Comed. >
I 4
3 r.
-I t
~
q Siemens Power Corporation -~
I EMF-96125 f LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 7 4
-I 11 20 (0,19.4) (15.19.4) f 18 -
i 16-14 -
(61.1.11.2) l'
$10-5 8- l 6-4-
2-0 5 1O 1!i IO ' d5 $0 $5 4'O 4S $0 $ NO $ 70 Average Planar Exposure, GWct/MTU Figure 7.1 Protection Against Power Transient LHGR Limit for ATRIUM-98 Fuel l
o l
1
- : ~ m . m . ,,, . . _ r . .. . . .; .
EMF-96-125 LaSalle Unit 2 Cycle 8 Revision 2 Reload Analysis Page 81
- 8. Methodology References See XN-NF 80-19(P)(A), Volume 4, Revision 1 for a complete bibliography.
8.1 ANF 913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2,3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.
8.2 ANF-524(P)(A) Revision 2 and Supplement 1, Revision 2, ANF Cr/t/caiPower Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
l 8.3 ANF-1125(P)(A) and ANF-1125(P)(A) Supplement 1, ANFB CriticalPower Corre'ation, Advanced Nuclear Fuels Corporation, April 1990.
8.4 XN NF-8019(P)(A) Volume 1 Supplement 3, Supplement 3 Appendix F, and Supplement 4, Advanced Nuclear Fuels Methodology for Boiling Water heactors:
Benchmark Results for CASMO-3G/MICROBURN-B Calculation Methodology, Advanced Nuclear Fuels Corporation, November 1990.
8.5 EMF-CC-074(P)(A) Volume 1, STAIF- A Computer Program for BWR Stability Analysis in the Frequency Domain, and Volume 2, STAiF- A Computer Program for BWR Stability Analysis in the Frequency Domain - Code Qualification Report, Siemens Power Corporation, July 1994.
A Siemens Power Corporation -
j LaSalle Unit 2 Cycle 8 EMF 96-125 Revision 2 Reload Analysis Page 9-1 l 9. Additional References 9.1 EMF-96-122(P) iatest revision, FuelDesign Rsport for LaSaHe 2, Cycle 8 A TRIUM"-
9B Fuel Assemblies, Siemens Power Corporation.
l 9.2 ANF-89-014(P)(A) Revision and Supplements 1 and 2, Advanced Nuclear fuels Corporation Generic MechanicalDesign for Advanced Nuclear Fuels 9x9-IX and 9x9 9X BWR Reload fuel, Advanced Nuclear Fuels Corporation, October 1991.
9.3 EMF 96-124(P) Revision 3. LaSaHe Unit 2 Cycle 8 Plant Transient Analysis, Siemens Power Col "ation, March 1999. '
9.4 EMF 95-134(P), Cmicality Safety Analysis for A TRIUM"-98 Fuel, LaSaHe Units 1 and 2 New FuelStorage Vault, Siemens Power Corporation, December 1995.
9.5 EMF-96117(P), Criticality Safety Analysis for A TRIUM"-98 Fuel, LaSalle Unit 1 Spent Fuel Storage Pool (BORAL Rack), Siemens Power Corporation, April 1996.
9.6 EMF-95-088(P), Criticality Safety Analysis for A TRIUM"-9B Fuel, LaSaHe Unit 2 Spent FuelStorage Pool (Boraflex f.ack), Siemens Power Corporation, February 1996.
9.7 XN-NF-79 71(P)(A) Revision 2 Supplements 1, 2 and 3, Exxon Nuclear Plant l
Transient Methodology for Boiling Water Rehctors, Exxon Nuclear Company, March '
1986, 9.8 EMF 2174(P), LOCA Breck Spectrurn Analysis for LaSalle Units 1 and 2, Siemens Power Corporation, March 1999.
9.9 EMF-2175(P), LaSalle LOCA-ECCS Analysis MAPLHGR Limits for A TRIUM"-9B !
Fuel, Siemens Power Corporation, March 1999.
9.10 Letter, D. E. Garber (SPC) to R. J. Chin (Comed), "LaSalle Unit 2 Cycle 8 Mechanical Limits for GE9 Fuel," D5G:99:066, March 2,1999.
9.11 Letter, James E. Nevling (Comed) to D. E. Garber (SPC), "SPC Neutronic Licensing Analyses for LaSalle Unit 2 Cycle 8," February 3,1999.
4 Siemens Power Corop_ ration __ _ _ _ __ ._ ___ ____ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ - _ - - -
i EMF 96-125 l- - 1.aSalle Unit 2 Cycle 8' Revision 2
- Reload Analysis -
1 i
l Distribution i .i Garber, 38 (15)
D. E.
i I
Notification List
'. (e-mail notification) .
. O. C. Brown
- D. G. Carr
- M. E. Garrett K. H. Harsche i K. D. Hartley J. M. Haun D. B. McBurney R. R. Schnepp S. A. Tylinski J. A. White A. W. Will P. D. Wimpy i
e l
Siemens Power Corporation
Administrative Technical Requirements - Appendix B L2C8 Reload Transient Analysis Results Attachment 3 .
LaSalle Unit 2 Cycle 8 Plant Transient Analysis (Excerpts) p- LCSalle Unit 2 Cycle 8 ., March 1999
' s DEG:99:078 Attachment Page A 1 Nonproprietary Summary of EMF-96-124(P) Revision 3 Table 3.1 LaSalle Unit 2 Plant C6nditions at Rated Power and Flow Reactor Thermal Power 3323 MWt Total Core Flow 108.5 Mlbm/hr Core Active Flow 94.1 Mibm/hr Core Bypass Flow
- 14.4 Mlbm/hr Core inlet Enthalpy 524.1 Btu /lbm Vessel Pressures Steam Dome 1001 psia Core Exit (upper plenum) 1012 psia Lower Plenum 1037 psia Turbine Pressure 955 psia Feedwater/ Steam Flow 14.32 Mlbm/hr Feedwater Enthalpy 400.9 Btu /lbm Recirculating Pump Flow (per pump) 15.83 Mlbm/hr Core Average Gap Coefficient (EOC) 1158 Btu /hr-ft r.ep Includes water channel flow.
C. m.
n e
DEG:99:078 Attachment
.Page A-2 Table 3.3 12,000 mwd /MTU Base Case LRNB Treasient Results Peak Peak' ATRIUM *-9B
- ATRIUM 9B GE9 Neutron Flux Heat Flux Power / Flow _.
ACPR . LHGRFAC, ACPR (% rated) (% rated)
TSSSInsertion Times 100/105 0.266 1.001 0.300 323.43 119.24 100/100 0.258 1.000 0.282 312.26 119.25 100/87 0.254 1.031 0.270 330.75- 118.94 80/105 0.277 1.029 0.299 270.40 95.21 80/54.5 0.209 1.109 0.203 193.51 88.91 60/105 0.269 1.071 0.291- 195.43 70.14' 60/45.2 0.205 1.131 0.188 138.01 66.53 40/105 0.226 1.133 0.244 98.83 45.04 25/105 0.163 1.222 0.181 42.26 26.64 NSSInsertion Times 100/105 0.224 1.074 0.271 268.36 114.78 80/105 0.240- 1.005 0.273 236.06 92.16
. ATRIUM is a trademark of Siemens.
k
DEG:99:078 Attachment Page A-3 Table 3.4 EOC Base Case LRNB Transient Results Peak Peak ATRIUM 9B ATRIUM 9B GE9 Neutron Flux Heat Flux Power / Flow ACPR LHGRFAC, ACPR (% rated) (% rated)
TSSSInsertion Times 100/105 0.301 1.000 0.317 389.88 124.14 100/100 0.296 1.000 0.311 408.37 124.47 100/87 0.296 1.000 0.319 401.28 124.72 80/105 0.303 1.012 0.319 291.43 98.21 80/54.5 0.315 1.036 0.313 263.07 95.22 60/105 0.285 1.052 0.303 222.00 71.91 60/45.2 0.321 1.057 0.294 184.77 70.99 40/105 0.226* 1.126 0.244' 98.83* '45.04' 25/105 0.163* 1.220 0.181* 42.26* 26.64*
NSS /nsertion Times 100/105 0.272 1.000 0.303 356.44 120.28 100/100 0.265 1.000 0.289 371.58 120.23
'100/87 0.250 1.017 0.270 354.00 120.14 80/105 0.278 1.025 0.294 262.97 95.79 80/54.5 0.208 1.090 0.210 196.79 89.62 60/105 0.269 1.061 0.287 209.31- 70.74 60/45.2 0.245 1.102 0.213 145.72 67.61 40/105 0.212 1.131 0.231 105.18 45.31 25/105 0.137 1.222 0.164 43.21 26.72 The analysis results presented are from an earlier cycle exposure. The ACPR and LHGRFAC,results are conservatively used to establish the thermallimits.
i
DEG:99:078 Attachment -
Page A-4 Table 3.5 12,000 mwd /MTU Base Case FWCF Transient Results Peak Peak ATRIUM 9B ATRIUM-98 GE9 Neutron Flux Heat Flux Power / Flow ACPR LHGRFAC, ACPR (% rated) (% rated)
TSSSInsertion Times 100/105 0.238 1.081 0.268 255.41 117.71 100/100 0.230 1.085 0.256 240.19 117.30 100/87 0.210 1.097 0.218 219.14 115.81 80/105 0.284 1.061 0.296 222.29 97.09 80/54.5 0.129 1.183 0.123 126.16 87.05 60/105 0.357 1.018 0.367 170.85 76.37 60/45.2 0.130 1.195 0.119 91.55 65.61 40/105 0.495 0.948 0.489 109.43 56.30 25/105 0.753* 0.821' O.759' 56.05* 40.57' NSSInsertion Times 80/105 0.250 1.087 0.272 195.20 94.38 60/105 0.331 1.033 0.339 156.28 74.95 40/105 0.476 0.955 0.471 104.13 55.81 25/105 0.725 0.832 0.684 68.48 41.49
- ' The analysis results presented are from an earlier cycle exposure. The ACPR and LHGilFAC,results are conservatively used to establish the thermal limits.
DEG:99:078 Attachment Page A-5 Table 3.6 EOC Base Case FWCF Transient Results Peak Peak ATRIUM 9B ATRIUM 9B GE9 Neutron Flux Heat Flux .
Power / Flow ACPR . LHGRFAC,_ ACPR (% ratad) -(% rated).
TSSS /nsertion Times 100/105 0.268 1.066 0.294 310.14 121.56 100/100 0.262 1.067 0.283 293.99 121.50 100/87 0.248 1.073 0.263 267.48 120.52 80/105 0.305 1.051 0.316 262.46 99.69 80/54.5 0.217 1.135 0.216 163.28 91.25 60/105 0.358 1.021 0.367 193.36 77.58 60/45.2 0.219 1.148 0.207 117.66 68.57 40/105 0.495* 0.948* 0.489* 109.43* 56.30*
25/105 0.753' O.821' O.759' 56.05* 40.57' NSSInsertion Times 100/105 0.244 1.082 0.277 278.66 118.76 100/100 0.237 1.086 0.266 262.44. 118.41 100/87 0.210 1.098 0.227 233.56 116.66 80/105 0.286 1.062 0.297 245.02 98.01 80/54.5 0.141 1.179 0.139 129.40 87.49 60/105 0.345 1.027 0.355 185.90 76.78 60/45.2 0.152 1.183 0.145 99.03 66.29
'40/105 0.476* 0.955' O 471* 104.13' 55.81*
25/105 0.725* 0.832' O.684* 68.48' : 41.49 * .
~
. The analysis results presented are from an earlier cycle exposure. The ACPR and LHG'RFAC,results 4 "are conservatively used to establish the thermal limits.
DEG:99:078 Attachment Page A-6 Table 3.8 Flow Dependent MCPR Results Core Flow
(% rated) ATRIUM-9B GE9 30 1.598 1.566 40 1.510 1.475 50 1.447 1.413 60 1.382 1.352 70 1.314 1.290 80 1.242 1.228 90 1.167 1.162 100 1.097 1.096' 102.5 1.0S0 1.080 105 1.080 1.080
^t
1
'- 4 4
l DEG:99:078 ' Attachment Page A-7 eoon CORE POWER
- - KAT
- - - .FLtR CORE FLOW _ , , , , . .
U STEAM FLOW acon-FEED TLOW ,
8 y room.
m L
o z
d '
_ ,g g ,, . - - - ( .--
3
..g .. ,_,
i I
3 l e
y-A '/
L b 1D 20- 3D 4D SD 6B TIME, SEC0 FOS Figure 3.1 12,000 mwd /MTU Load Rejection No Bypass at 100/105 TSSS Key Parameters 4
)
g
> a. , , -;
, .I, ,j'
DEG:99:078. ! Attachment Page A-8 ND .
E' W
M "" 1 3
Y 8
E
- s4D-S 5
4 3
329 -
d 8
W MA , . . , ,
D 1D 2D 10 49 SD SD TNE SECONDS
- Figure 3.2 12,000 mwd /MTU Load Rejection No Bypass at 100/105 - TSSS Vessel Water Level M z
.,\c
~ DEG:99:078 - Attachment
.Page A-9 12 cob tisos-4 5
a
$ 1100.o-W a
taJ 8
O taso.o-
'*8 . . . . .
.o 1A - ' 2.o 3.o 44 54- $4 TK, SECONDS Figure 3.3 12,000 mwd /MTU Load Rejection No Bypass at 100/105 ;- TSSS Doma Pressure f:'
DEG:99:078 Attachment Page A 10 -
400 0 CORE POWER
__E_^I_F_ LUX,__,.
CORE FLOW STEAM FLOW FEED FLOW 8
Q 20a0- 1 m J b
w m
100.0 y M %,_
m ~
' ' --'1-- %
f==~K~ -~y'GQ34 v'
I I /
D' I \ l
\bl A la 2.0 3.0 4.0 10
^
TNE, SEC0f05
~
Figure'3.4 EOC Load Rejection No Bypass at 100/105 - TSSS Key Parameters 4
i.
1 .
~ DEG:99:078 . Attachment .
Page A-11 anD 0
5.
N 5"
E 8
E 3 349 -
5 8
5 Q
R g 32D-D 1D 2D 39 4D $9 TIME, SECONDS Figure 3.5 EOC Load Rejection No Bypass at 100/105 .TSSS Vessel Water Level-
. .- i _
(
.c.
. DEG:99:078 - Attachment
. ;- Page A-12.
1200.0 1150.0 -
(
ih 0.
O
$ 11004-W 0.
Y O
O 1050.0 -
10004. , , , ,
A , IA 2.0 3D 40 5A TNE, SECONDS Figure 3,6 EOC Load Rejection No Bypass at 100/105 - TSSS Dome Pressure .
e l'
L DEG:99:078 Attachment Page A 300A CORE POWER
-_HE3]JLUL,,
as04 CORE FLOW STEAM FLOW FEED FLOW 200A -
8 4
0: 150A -
~ '
b l 'T
- .M.
5 300.0 _
m --. --- ;-- _ _ s. .s
~
. hlb.
Ii
%Y. s 504 -A.>'t-s,
's,i 1
l
,I-h.\ s l 1 3
i I
~508 , , , ,
A 10 10A 110 204 210 THE, SECONDS Figure 3.7 12,000 mwd /MTU Feedwater Controller Failure at 100/105 - TSSS Key Parameters k
,- 4 4
4 i e ,
i
7-DEG:99:078 Attachment -
'Page A-14 sus
@ so-H s
k y som-O E
4LD-s 5
q <0s-it d
M y a0-308 D LO 10D 15.0 20D 210 TNE, SECONDS -
Figure 3.8 -12,000 mwd /MTU Feedwater Controller Failure
-at 100/105 - TSSS Vessel Water Level 4
a
DEG:99:078 Attachment Page A-15 i
l l
l l 1150.0 l l
11210- )
l f 1100.0-us CL hi af 10710- ,
W i
- o. ;
$ i o 1 o ioso.o- j i
i i
i 10210-10040 _ , , , ,
a 50 10.0 15.0 204 210 TNE. SEC0tOS Figure 3.9 12,000 mwd /MTU Feedwater Controller Fallure at 100/105 - TSSS Dome Pressure I
DEG:99:078 Attachment Page A-16; econ CORE POWER
..TM J.M ... .
CORE FLOW_
~
STEAM FLOW FEli) FLOW" ~
8 y soon-m o
n ..
6 O -a-'--~~-
n 20 - - -
N.\
5 1
. ifs fx. -
1 I\ M, .
,, xw ~
.o .
. ,I jo ~ -
ll l
-20 , , , , i A 4h 8.0 12h '16A 20.0 ~ 24D TNE. SECONDS 4
Figure 3.10 EOC Feedwater Controller Failure at 100/105 - TSSS' Key Parameters 4
, o LSEG:99:078 ; ' Attachment '
Page A-17 4 -
no O
5 N
n eu-W 8
Z su-a 6
4 a au-bl 0
M i . . . .
D 4D SD 122 fu % 34b TNE, SECONDS Figure 3.11' EOC Feedwater Controller Failure at 100/105 - TSSS Vessel Water Level .
h .'
=
- ' i. _ _r. , -}
, u-DEG:99:078 .: Attachment ;
Page A s 1180D 11240-4 15
- a. -
=
l A 42 60 12D 16D 3Db 24b TedE, SEC0f05.
Figure 3.12 EOC Feedwater Controller Failure at 100/105 - TSSS Dome Pressure ~
s s-,
~
,h- -
3
- 4
r-DEG:99:078 - Attachment
, Page A 19 '
t 25 tu. . vos e FWCF 24
_m 2.M .-
2.5 -
1 15 in.-
12 -
kin.- ,
15' i.e .
ie .
'gg.. , 5 (n.- .
e s l
1 15 0 10 3 '3 e 10 to N 10 to 100 110 Core Power $si Ashd) .
Power (% rated) MCPR, Limit O 2.60 25 2.10 25 1.90 60 1.46
'100 1.35 Figure 3.16 12,000 mwd /MTU Base Case Power Dependent MCPR
, Limits for ATRIUM-98 Fuel - TSSS Insertion Times a- .
i-I /
t
- DEG:99:078 , ' Attachment Page A 20
.1 2H !-
as a w-
-0u08 '
22 1 ns .. 4 ris --
su.
1M.-
f,.. s 1 75 1H--
8 1H -
1 46 ,
135 <
- 8 e
1 25 s e 1 15 0 10 20 30 40 50 R 70 # E 100 110 Core Poww $of Rand)
Power (% rated) MCPR, Limit 0 2.60 25 2.10
- 25 1.90 60 1.47' 100 1.39 Figure '3.17 12,000 mwd /MTU Base Case Power Dependent MCPR Limits for GE9 Fuel - TSSS Insertion Times 4- ( ,f L
DEG:99:078 ' Attachment Page A-21 f
sn 2N..
e uns-ts. e fuer
-cucen rs.-
15 2 15 -
am.-
gie.-
te.- -
e in.
te..
12 .
I 1 45 .
is.-
in..
til e to a z a e a n o a se is Coe Peuer(% of Reed)
Power (% rated) MCPR, Limit .
0 '2.60 25 2.10 25 -1.90 60 1.43 100 1.31 Figure 3.18 12,000 mwd /MTU Base Case Power Dependent MCPR Limits for ATRIUM 98 Fuel - NSS insertion Times
.. .. .a
--t'.
3 DEG:99io78 Attachment Page A-22
?2n tm. , u,a
~ 22
_oten gg-, t 2g..
1 25
- 2 15 -
tm.
12 .
is..
(n.. E in.
1 55 - 8 16 -
1 35 -- 3 1 25 --
1 15 0 10 3 10 40 2 9 70 80 90 100 110 Com Pew $ elAmed)
Power (% rated) MCPR, Limit O 2.60 25 2.10 25 1.90 60 1.44 100, 1.36 y" ; Figure 3.19 12,000 mwd /MTU Base Case Power Dependent MCPR Limits for GE9 Fuel- NSS insertion Times 4
9
8.
m DEG:99:078: ' Attachment 1 Page A-23 2 15 2 05
. uns 2 56 .
e FWCF
_.cucPR 2 46 22 -
1 25 -
2 15 LM. )
5 .
h s in- ,,
1.76 .
1 85 -
iss .
1 45 a
in.- ]
i.n .- .
1 15 0 10 N N 40 50 00 15 N 00 100 110 Cat Pomerl% af Rated)
Power (% rated) MCPR, Limit 0- 2.60 25 2.10 25 1.90 60 1.46 100 1.39
- Figure 3.20. EOC Base Case Power Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times
+ ..
1
DEG:99:078 Attach' ment Puge'_A-24 2 75 2M- ,
am 2n. - ou m 2 45 -
2 35 -
In,.
2 15--
Ei .
i
!.N '
1 75--
1M--
e i.e -
1 45-. ,
os .
8 j 8 8 i.25 .
1 15
' " 8 8 a a a n a a in ii, Care Pour (% of Reed)
Power (% rated) MCPR, Limit 0 2.60 25 2.10 25 1,90 60 1.47 100 1,40 Figure 3.21 EOC Base Case Power Dependent MCPR Limits for GE9 Fuel - TSSS Insertion Times l
i t - o i'
s DEG:99:078 - Attachment Page A-25.
to 2 16 .
, use 24 . -
,g 2.2 <.
23 2 15 .
2m..
15 kin.
l.75 .
is..
1s. e is.
ts.. e 9
. * . m us , ,
11$
0 10 20 30 40 50 to 70 80 to 850 110 c p menn.e Power (% rated) MCPR, Limit 0 2.60 25 2.10 25 1.90 60 '1.45
-100- 1.36 Figure 3.22 EOC Base Case Power Dependent MCPR Limits for ATRIUM-98 Fuel - NSS insertion Times 4
4
DEG:99:078 Attachment Page A-26 m
a~
a .
'N
, m1 24-. l-D3 a..
a..
15
{
2m-.
15 .
)
l is.-
ts ~
1 l
- . a m .
in -
o e a m ,1 m e a a e a in Ca**Ar(% dred .
Power (% rated) MCPR, Limit 0 2.60 25 2.10 25 1.90 60 1,46-
-100 1.39 Figure 3.23 EOC Base Case Power Dependent MCPR Limits for GEL iuol - NSS Int,ertion Times '
..____U-___________.m__. _ _ . _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ . _ I. - _ _ _ _ _ _ _ _ _ _
DEG:99:078 Attachment -
Page A se e use is..
sN
- ura n -
13 -
a tn -
g
- e e e lim-. :
I .
9 00 --
9 80 ea 0 to 3 30 40 2 to N 10 10 600 110 w*eMW Power (% rated) LHGRFAC, O O.75 -
25 0.75 i 25 0.'75 60 1.00 100 1.00 l l
l Figure 3.24 12,000 mwd /MTU Base Case Power Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times ,
1 l
. l l
i mad !.
f DEG:99:078 Attachment Page A-28 15 e use a twer tm, -uore.e 1 10 .
s 1 00 .
- 8 e
em 8 10 .
em 0 10 2 30 40 2 N 70 80 90 100 110 Cae Pons (5 of RsW)
Power (% rated) LHGRFAC, O 0.80 25 0.80:
25 0.80 60 1.00 100 1.00 Figure 3.25.12,000 mwd /MTU Base Casa Power Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times -
DEG:99:078 Attachment Page A-29 '
L30 4 UDE e' FWCF 1.20 -LHGRFQ a
1.10 -
t00 :
k e 0
e 0.00 0 70 0 60 9 10 20 30 40 2 80 70 10 90 106 110 '
Com Poww(% of Raed)
Power (% rated) LHGRFAC, O O.75 25 0.75 25 0.75 60 1.00 100- 1.00 Figure 3.26 EOC Base Case Power Dependent LHGR Multipliers for ATRIUM 98 Fuel - TSSS Insertion Times
DEG:39:078 - Attachment
. Page A 30
.12 -
e uns e e rwcr m' -uonc, e
e 1.10
, 'g e a a . ,
1.00 - 0-9 s ,.
$m.
0 e
0 00 0 70 0.80 0 20 40 to 80 . 100 Com Pouw(E of Raisd)
Power (% rated) LHGRFAC, O 0.80 25 0.80 25 0.80 60 1.00 100 1.00 Figure 3.27_ EOC Base Case Power Dependent LHG,R Multipliers for ATRIUM-98 Fuel - NSS insertion Times 4
e
DEG:99:078 Attachment Page A 31 Table 4.1 Coastdown Operation Transient Results ATRIUM-9B GE9 Power / Flow Event (% rated /% rated) ACPR LHGRFAC, ACPR LRNB 100/105 0.322 0.978 0.334 LRNB 80/105 0.338 0.955 0.353 ~
LRNB 60/105 0.342 0.971 0.335 LRNB 40/105 0.317 0.961 0.300 LRNB 25/105 0.167 1.150 0.162 FWCF 100/105 0.278 1.063 0.291 FWCF 80/105 0.304 1.056 0.311 FWCF 60/105 0.363 1.030 0.359 FWCF 40/105 0.460 1.050 0.452 FWCF 25/105 0.753 0.995 0.837
DEG:99:078 Attachment Page A 32 Table 4.2 FFTR/Coastdown Operation Transient Results ATRIUM GE9 Power / Flow Event (% rated /% rated) ACPR. LHGRFAC, ACPR-LRNB 100/105 0.272 1.029 0.285 LRNB 80/105 0.266 1.034 0.277 LRNB 60/105 0.288 1.013 0.263 LRNB 40/105 0.246 1.020 0.219 LRNB 25/105 0.121 1.200 0.120 FWCF 100/105 0.283 1.066 0.294 FWCF 80/105 0.318 1.053 0.326 FWCF 60/105 0.387 1.039 0.385 FWCF 40/105 0.571 1.180 0.533 FWCF 25/105 1.006 0.883 1.032 l_
DEG:99:078 Attachment -
Page A 33 I to tm~ , we a no 24 .
_m .
13 .
t5 .
115 <.
15 .
t%<-
f,. .
1.3 -
t#'
t.E .. ,
1 45 -.
g e ,
12 . 8 is. .
t15 0 10 2 N & M R N N N 1N 110 rme=,menme .
Power (% rated) MCPR, Limit O 2.60 25 2.10 25 2.00 60 1.47 100 1.41 Figure 4.1 - Coastdown Power Dependent MCPR Limits for ATRIUM-98 Fuel
- DEG G9:078 Attachment Page A-34
)'
t.30 e use a AUCF 1JO. -U"JFACp 1.10
, e s
1.90 ,
5 -
I s e0 en om 0 10 20 30 40 W 80 70 80 90 100 110 c r .rs.inae Power (% rated) LHGRFAC,
. 0 0.75 25 0.75 25 0.75 60 0.96 100 0.97 Figure 4.2 Coastdown Power Dependent LHGR Multipliers for ATRIUM-98 Fuel
.e .
I' I a...
DEG:90:078 Attachment -
Page A-35 s.
In
.gg. k\ e von 14 -
g sWCF
~
254-1 25 1 15 --
2 06 1 95 -
hiss,.
vs 1%.
1.55 .
18-' g .
- 8 tz..
us .
1 15 0 10 20 30 40 W to 70 N to 100 110 Ces Pont(% alRase Power (% rated) MCPR, Limit O 2.60 25 2.10 25 2.00 60 1.47 100 1.42 Figure 4.3 Coastdown Power Dependent MCPR Limits for GE9 Fuel
DEG:99:078 Attachment Page A-36 tm US -
,y gg \ s FWCF
-aucen ns.-
2 45 .
U6 -
23 -
2 fl .
2%<
t.M .-
1a..
136 .
in.- a 1.M ..
se.
s us .
- I 13<
1 15 9 Id 20 30 40 50 to 79 to to 100 110 Cate Powetl% c(Ratail)
Power (% rated) MCPR, Limit O 2.70 25 2.20
- 25 2.20 60 1.52 100 1.41 Figure 4.4' Combined FFTR/Coastdown Power Dependent
- MCPf1 Limits for ATRIUM-98 Fuel
DEG:99:078 Attachment Page A-37
'14
. Lee
- u. '"
-uneco
- n. .
e 1.1 <
s s. - ..
21, ' '
j 0,.
08<
01-06 0 10 20 30 40 $0 80 70 80 to 100 110
, c re ,n.enewe Power (% rated) LHGRFAC, O 0.65 25 0.65 25 0.65 60 0.96 100 _ O.97_
Figure 4.5 Combined FFTR/Coastdown Power Dependent.
LHGR Multipliers for ATRIUM-98 Fuel 4
e
DEG:99:078 Attachment Page A-38
,2m 2n .
2 65 .
a FWCF 2M- -00dCPR 2 45 1 35 2 25 2 15 2 05--
ki.e.
15 -
1.54-1.05 .
1 55 8
1 45 --
u5 .
e 12 1.15 0 10 20 30 40 50 60 70 80 to 100 110 c F m .fn wi Power (% rated) MCPR, Limit O 2.70 25 2.20 25 2.20 60 1.52 100 1.42 Figure 4.6 Combined FFTRICoastdown Power Dependent MCPR Limits for GE9 Fuel
DEG:99:078.- Attachment Page A-39 Table 5.1 12,000 mwd /MTU Feedwater Heater Out of Service Analysis Results ATRIUM-98 GE9 Power / Flow Event (% rated /% rated) ACPR LHGRFAC, ACPR FWCF 100/105 0.252 '1.069 0.284 FWCF 80/105 0.319 1.024 0.327 FWCF 60/105 0.418 0.971 .O.420 FWCF 40/105 0.617 0.875 0.592 FWCF 25/105 1.025' O.712* 1.007'
- ' The analysis results presented are from an earlier cycle exposure.' The ACPR and LHGRFAC,results'
. are conservatively used to establish the thermallimits.
, s
DEG:99:078 Attachment -
Page A-40 Table 5.2 EOC Feedwater Heater Out of Service Analysis Results ATRIUM-98 GE9 Power / Flow Event ACPR LHGRFAC, ACPR J%reted/% rated)
FWCF 100/105 0.276 1.062 0.301 FWCF 80/105 0.328 1.036 0.336 FWCF 60/105 0.418' O.971* O.420' FWCF 40/105 0.617' O.875* 0.592*
FWCF 25/105 1.025* 0.712* 1.007*
- iThe analysis results presented are from ar$ earlier cycle exposure. The ACPR and LHGRFAC,results -
are conservatively used to establish the thermal limits.
DEG:99:078 Attachment
' Page A' Table 5.3 Abnormal Recirculation Loop Startup Analysis Results ATRIUM-9B Power / Flow FCV
(% rated /% rated) Position - ACPR' LHGRFAC, . .
35/47 15% open 1.31 0.450_.
35/47 27% open 1.37 0.429 ACFR results for ATRIUM-98 fuel are conservatively applicable for GE9 fuel.
DEG:99:078 Attachment -
Page A Table 5.4 12,000 mwd /MTU Turbine Bypass Valves Out of Service Analysis Results ATRIUM-9B GE9 Power / Flow Event (% rated /% rated) ACPR LHGRFAC, ACPR FWCF 100/105 0.302 1.000 0.316 FWCF 80/105 0.355 0.998 0.369 FWCF 60/105 0.431 0.967 0.441 FWCF 40/105 0.577 0.903 0.563 FWCF 25/105 0.837 0.793 0.795*
The analysis results presented are from an earlier cycle exposure. The ACPR and LHGRFAC,results.'
are conservatively used to establish the thermal limits.
DEG:99:078' . Attachment Page A 43 c.
Table 5.5 EOC Turbine Bypass Valves Out of Service Analysis Results ATRIUM-9B GE9 Power / Flow Event (% rated /% rated) ACPR LHGRFAC, ACPR 1
FWCF 100/105 0.333 1.004 0.347' FWCF 80/105 0.377 0.991 0.391 FWCF 60/105 0.435 0.967* .0.445 FWCF 40/105 0.577* 0.903* O.563*
FWCF 25/105 0.837' O.793* 0.795*
I*'- The analysis results presented are from an earlier cycle exposure. The ACPR and LHGRFAC,results are conservatively used to establish the thermal limits.
DEG:99:078 . Attachment Page A-44 Table 5.6 12,000 mwd /MTU Recirculation Pump Trip Out of Service Analysis Results ATRIUM-98 GE9 Power / Flow Event (% rated /% rated) -ACPR _
!.HGRFAC, ACPR LRNB 100/105 0.335 1.000 0,357 LRNB 100/100 0.326 1.000 0.347 LRNB 100/87 0.293 1.000 0.313 LRNB 80/105 0.333 1.000 0.356 LRNB 60/105 0.318 0.994 0.340 LRNB 40/105 0.260 1.059 0.279 LRNB 25/105 0.161 1.164 0.186 FWCF 100/105 0.292 1.000 0.311 FWCF 80/105 0.329 0.994 0.343 FWCF 60/105 0.388 0.965 0.397 ,
FWCF 40/105 0.505 0.912 0.496 FWCF 25/105 0.728 0.806 0.721' The analysis resul's presented are from an earlier cycle exposure. The ACPR and LHGRFAC,,results are conservatively used to establish the thermal limits.
' DEG:99:078 Attachment Page A-45 Table 5.7 EOC Recirculation Pump Trip Out of Service Analysis Results ATRIUM-9B GE9 Power / Flow Event (% rated /% rated! ACPR LHGRFAC, ACPR .
Lr ! .B 100/105 0.377 1.000 0.394 LRNB 100/87 0.351 1.C00 0.365
'LRNB 80/105 'O.368 1.000 0.385 LRNB 60/105 0.345 0.978 0.362 LRNB 40/105 0.273 1.054 0.209 LRNB 25/105 0.182 1.122 0.194 FWCF 100/105 0.326 1.000 0.340 '
' FWCF -80/105 0.357 0.981 0.370 FWCF 60/105 0.401 0.964 0.410 FWCF 40/105 0.505* O.912' O.496*
FWCF 25/105 0.728' O.806* 0.721*
- ; The ana)ysis results presented are from an earlie'r cycle exposure. The ACPR and LHGRFAC,results -
are conservatively used to establish the thermal limits.
~
DEG:99:078 Attachment Page A-46 Table 5.8 12,000 mwd /MTU Turbine Control Valve Slow Closure Analysis Results ATRIUM-9B GE9 Slow Valve (s) Power / Flow Event Characteristics (% rated /% rated) ACPR LHGRFAC, ACPR s
LRNB 1 TCV Closing at 2.0 sec 100/105* O.330 1.000 0.358 LRNB 1 TCV Closing at 2.7 see 100/105* 0.312 1.000 0.339 LRNB 1 TCV Closing at 2.0 sec 100/100* O.333 1.000 0.362 LRNB 1 TCV Closing at 2.0 sec 100/87* 0.338 1.000 0.357 LRNB 1 TCV Closing at 2.0 sec 80/105* O.376 1.000 0.393 LRNB 1 TCV Closing at 2.0 sec 60/105* 0.363 0.976 0.378 LRNB 1 TCV Closing at 2.0 sec 40/105** 0.798 0.773 0.749 ' *
- LRNB 1 TCV Closing at 2.0 sec 25/105** 1.003 * *
- 0.706 0.975 "
- Scram initiated by high neutron flux.
Scram initiated by hig,h dome pressure.
- *
- The analysis results presented are from an earlier cycle exposure. The ACPR and LHGRFAC,results are conservatively used to establish the thermal limits.
a DEG:99:078 Attachment Page A-47 Table 5.9 EOC Turbine Control Valve Slow Closure Analysis Results' ATRIUM GE9 Slow Valve (s) Power / Flow Event Characteristics (% rated /% rated) ACPR LHGRFAC, ACPR LRNB 1 TCV Closing at 2.0 see 100/105* O.387 1.000 0.382 LRNB 1 TCV Closing at 2.7 sec 100/105* O.395 1.000 0.391 LRNB 2 TCVs Closing at 7.75 sec 100/105* O.184 1.045 0.223 LRNB 1 TCV Closing at 2.0 see 100/100* 0.361 1.000 0.368 LRNB 1 TCV Closing at 2.0 see 100/87* 0.363 1.000 0.389 LRNB 1 TCV Closing at 2.7 see 100/87* 0.341 1.000 0.369 LRNB 1 TCV Closing at 2.0 sec 80/105* O.387 1.000 0.393 '
LRNB 2 TCVs Closing at 7.75 sec 80/105* 0.249 1.028 0.264 LRNB 2 TCVs Closing at 7.75 sec 60/105* 0.322** 1.026 0.375**
LRNB 1 TCV Closing at 2.0 sec 60/105* 0.381 0.968 0.380 LRNB- 1 TCV Closing at 2.0 sec 40/105 "
- O.798 " 0.773 " O.749 '
LRNB 1 TCV Closing at 2.0 sec 25/105 '
- 1.003** O.706** 0.975 '
LRNB w/ 1 TCV Closing at 2.7 see 100/105* O.316 0.948 0.324 FHOOS Scram initiated by high neutron flux.
The analysis results presented are from an earlier cycle exposure. The ACPR and LHGRFAC, results are conservatively used to ettablish the thermallimits.
- " Scram initiated by high dome pressure. .,
DEG:99:078 Attachment Page A-48 f
Table 5.10 12,000 mwd /MTU Recirculation Pump Trip and Feedwater Heater Out of Service Analysis Results ATRIUM-9B GE9 Power / Flow Event (% rated /% rated) ACPR LHGRFAC, ACPR LRNB 100/105 0.278 0.985 0.325 FWCF 100/105 0.294 1.004 0.322 FWCF 80/105 0.355 0.969 0.365 FWCF 60/105 0.442 0.928 0.442 FWCF 40/105 0.620 0.847 0.590 FWCF 25/105 0.984* 0.709 0.971*
! The analysis results presented are from an earlier cycle expos'y J. The ACPR and LHGRFAC,results are conservatively used to establish the thermal limits.'
s DEG:99:078 Attachment Page A-49 Table 5.11 EOC Recirculation Pump Trip and Feedwater Heater
~
Out of Service Analysis Results '-
' ATRIUM-9B - GE9 Power / Flow Event (% rated /% rated) ACPR LHGRFAC, ACPR LRNB 100/105 0.311 0.942 0.333 FWCF 100/105 - 0.325 0.994 0.333 FWCF 80/105 0.374 0.969 0.382 FWCF 60/105 0.446 0.928' O.450 FWCF 40/105 0.620' O.847' O.590*
FWCF 25/105 0.984* 0.709' O.971*
~
- - The" analysis results' presented are from an earlier cycle exposure. The ACPR and LHGRFAC,results
! are conservatively used to establish the thermal ilmits. -]
4
DEG:995078 Attachment Page A 50 ts 235 -
e FWCF ts.- _a ts.
te-ts..
23 .
1 15 -.
ts~
1 96 1 16 7
in.-
e 1 85--
1.55 -.
s 1 45 s
12--
12-1 15 C 10 20 30 4 S N M N 90 1m 110 Core Power (%of Rand)
Power (% rated) MCPR, Limit 0 2.70 25 2.20 25 2.20 60 1.52 100 1.35 Figure 5.1-12,000 mwd /MTU Feedwater Heaters Out of Service Power.-
Dependent MCPR Limits for ATRIUM-9B Fuel
. DEG:99:078 Attachment Page A tM a FWJ
-UMACp 1.20 I 10 -
E e
1Jo.
$o-0t e
0 10 O F0 -
0 80 0 10 20 30 40 W 90 70 W N 100 110 Cue Power (Yiof Asted)
Power (% rated) LHGRFAC, O 0.65 25 0.65 25 0.65 60 0.96 100 1.00 Figure 5.2 12,000 mwd /MTU Feedwater Heaters Out of Service Power Dependent LHGR Multipliers for ATRIUM-98 Fuel
. DEG:99:078 Attachment Page A 52 2 05 2 75 25 .
-00CPR 1 55 -
2 45 .
2.35 15 -
2 15 2 05 1H.
1M.>
1 75 .
8 gg.,
1 56 1 45 -
a 8
1 35 in.
1 15 0 10 20 30 40 50 80 70 00 10 100 110 Com Power (%cf RMed)
Power (% rated) MCPR, Umit O 2.70 25 2.20 25 2.20 60 1.52 100 1.39 Figure 5.3 12,000 mwd /MTU Feedwater Heaters Out of Service Power Dependent MCPR Limits for GE9 Fuel 4
4 7
DEG:99:078, ' Attachment Page A-53 2 85 .y.
24-a FW7 20$ -00CPR 22--
2e-25--
23~
2 15 -
a 2m--
12--
1 15 14 .
s 1664.
15e 16--
12-. 8 13-.
1 15
- c. m a a e a e a e e in 12 -
CsePour(%ofRaed)
Power (% rated) MCPR, Limit O 2.70 25 2.20 25 2.20
-60 1.52 100 1.39
' Figure 5.4 EOC Feedwater Heaters Out of Service Power Dependent MCPR Limits for ATRIUM-9B Fuel' L
,A
DEG:99:078 Attachment Page A-54 i, , 1.30
'I" u0 <
-LHGRFACp 1.10 <
s l e
, ./
kO 90 <
0 80 <
0 70 -
1 0 50 0.50 0 10 20 30 40 50 80 70 80 to 100 110 Cove Power (% of Rated)
Power (% rated) LHGRFAC,
( 0 0.65 25 0.65 25 0.65 60 0.96 100 1.00 f
Figure 5.5 EOC Fredwater Heaters Out of Service Power Dependent LHGR Multipliers for ATRIUM 98 Fuel
.. DEG:99:078 ' Attachment Page A 55 tm ,
1%.-
a mr la- -- auon LE te~
13 .
ta-.
1 15 15 -
him.-
tE l.5 -
1%
12-16--
1s.-
12 1 15 0 10 20 30 - 40 m to N N W 1H 110 c %.sans.e Power (% rated) MCPR, Limit 0 2.70
.25- 2.20' 25 2.20 60 '1.52 100 1.40 Figure 5.6 EOC Feedwater Heaters Out of Service Power Dependent
.MCPR Limits for GE9 Fuel y..
i
_* . ' .i._.
DEG:99:078 Attachment Page A-66
, au -.
re. .
A 22 14<-
Ill ,-
tM.
15 12 s.n -.
1M<
12<
4 mtmenum to.. _ga 12 52 .
1.15 0 10 20 30 40 2 60 70 80 N 100 110 Cm Pewu5 WRes4 Figure 5.7 AbnormalIdle Recirculation Loop Startng.
Power Dependent MCPR Limits for ATRIUM-9B Fuei i
h tc ~
DEG:99:078 Attachment Page A-57 0$
4 MeLasp
-LMG RFACp 0.7 <
04 k .5 0 <
1 A
04 03 0.2 .
0 10 20 30 40 50 to 70 80 to 100 - 110 Com Power l% of Reed)
Figure 5.8 - Abnormal Idle Recirculation Loop Startup Power Dependent LHGR Multipliers for ATRIUM-9B Fuel
DEG:99:078 , - Attar
- ment Page A-58 '-
tu 2n.. a 4-2 35 -
ts.
2 15 2m.
IM.
1%.
1 75 1 85 tis 16-a mwnnu tz.
-oween 1 25 1 15 0 10 20 30 4 50 60 70 80 M 150 110 Coe Pouer{% alnated)
V Figure 5.9 ' Abnormal Idle Recirculation Loop Startup .
Power Dependent MCPR Limits for GE9 Fuel s .
W
..G..
DEG:99:078 Attachment -
Page A-59 tn te.
2 15 te.
gin. ,
is.
1 75 1m. E t 55 1 45 .
g 12 1254 til 0 10 2 N 40 50 N 70 00 10 100 110 Com Penw(%sf Rohd)
Power (% rated) MCPR, Limit O 2.60 25 2.10 25 2.00 60 1.54 100 1.39 Figure 5.10 12,000 mwd /MTU Turbine Bypass Valves Out of Service Power Dependent MCPR Limits for ATRIUM-9B Fuel .
.e '
F DEG:99:078 ' Attachment Page A-60 1 30 m rw -
-DGRFACp u0 1.10 .
1.00 < g 0 90 -
E o so.- ,
0 70 Osa 0 10 20 30 40 50 00 70 10 90 100 110
, ememenernme ,
Power (% rated) _
LHGRFAC, O 0.75 25 0.75 25 0.75 60 ~
0.96 100 1,00 Figure 5.11 12,000 mwd /MTU Turbine Bypass Valves Out of Service Power Dependent LHGR Multipliers for ATRIUM-98 Fuel e
DEGi99:078 Attachment '
Page A-61.
tR tm.
is, -oucm 2 45 tm.
1z..
1.15 ~
iss 1R<-
is..
sn.
1m. a 1 56 -
i .s- e 1.35 -
12<
l.15 0 to 20 30 40 H 10 70 lo to 100 110 Core Power l%of Rated)
Power (% rated) M-CPR, Limits O 2.60 25 2.10 25 2.00 l 60 1.55
- 100- 1.40 -1 Figure 5.12 .12,000 mwd /MTU Turbine Bypass Valves Out of Service -
Power Dependent MCPR Limits for GE9 Fuel
(
l; f
DEG:99:078 Attachment -
= Page A 62 vs t.
te-sW 15 -cup
- 16 .
13 -
th-1 16 -
2E.
14 a
t.m ..
1.15 --
5m. ,
t56 -
t6--
11 12 1.15 0 to 20 30 40 50 to N 80 80 100 - - 110 CsePoser(% afihm$
Power (% rated) MCPR, Limit O 2.60 25 2.10 25 2.00-60 1.54 100 1.42 Figure 5.13 EOC Turbine Bypass Valves Out of Service Power Dependent MCPR Limits for ATRIUM-98 Fuel 4
4
DEG:99:078 Attachment Page A-63 1.30 a fiNCF -
11 -u(AFACp 1.10 -
1 00 1,0 0 .
0 80 - g 0 10 0.50 0 10 20 30 40 50 00 70 80 90 100 110 Cove Power (%otRaisd)
Power (% rated) LHGRFAC, 0 0.75 25 0.75-25 0.75 60 0.96 100 1.00 Figure 5.14 EOC Turbine Bypass Valves Out of Service Power Deperident LHGR Multipliers for ATRIUM 9B Fuel
.i-
DEG:99:078 : Attachment Page A-64 in n- , no
~
2.5 -
24 -
12 13 .
I 16 .-
1.5 -
gin..
1 85 1n--
tN.- s O
in.
e ie..
1.36 -
1.3 1.15 0 10 20 30 W M 00 70 to to 100 110 CesPew $ WAm4 L
- Power (% rated) MCPR, Limit O 2.60 25 2.10 -i 25 2.00 60 1.55 100 1.43 I
Figure 5.15 EOC Turbine Bypass Valves Out of Service Power Dependent , .
- MCPR Limits for GE9 Fuel ',
i I
1 r . . . . ... . - -- . . . . - .ii,, -
- . . -..i . . . .
~,
DEG:99:078 Attachment Page A-65 2n 1 55
,g 2 55
-00CPR 2 45 2 35 2 25 1 15 2m..
1 95 -
1 05 .
s 1n--
1 65 -
1.55 -.
1 45 -
, ,5 .
in .
1 15 0 to 20 30 40 W 80 70 80 90 C "
ca. P=., n n.=di Power (% rated) MCPR, Limit O 2.60 25 2.10 25 1.90 60 .1.49 100 1.42 Figure 5.16 12,000 mwd /MTU Recirculation Pump Trip Out of Service Power Dependent MCPR Limits for ATRIUM-98 Fuel
DEG:99:078 Attachment -
Page A tm e ve a eWCF -
-unesco no e
1.10 <
e f.00 <
- e g
k.. .
g CM<
0.n -
0 60 e is a a a a e n a e in tio Com Paus(% of Asted)
Power (% rated) LHGRFAC, O 0.75 25 0.75 25 0.75 60 0.96 100 1.00 Figure 5.17 12,000 mwd /MTU Recirculation Pump Trip Out of Service Power Dependent LHGR Multipliers for ATRIUM-9B Fuel
, - ,. i.,.,,.,.. -
e .
g _ ,.l i . ..,..g g , , , _ , , _ _ _ _ . ,[
1 DEG:99:078 Attachment Page A 2n 1 85 e ues 2 56
,g te..
-mcPR 25 23 -
1 15 2 05 15 -
15 -
e (n..
in.-
1 55 -
s ie.-
33 . .
1 25 1 15 0 10 20 30 C 50 to M 80 10 100 110 c r.c p n.=e .
Power (% rated) MCPR, Limit O 2.60 25 2.10 25 1.90 60 1.50 100 1.44 ;
Figure 5.18 12,000 mwd /MTU Recirculation Pump Trip Out of Service Power Dependent MCPR Limits for GE9 Fuel I'
DEG:99:078 Attachment Page A-68 2n 2 65
,g gg., a NCF
-0LICPR 1 45 -
gg..
1 25 .
1 15 -
1 05--
giw.
1 85 s
115 165 -
t55 <-
1 45-- e ul .
in +
11$
0 10 20 30 C 50 to 70 80 to 100 110 Com Pour (% WRded)
Power (% rated) MCPR, Limit
. 0 2.60 25 2.10 25 1.90 60 1,50 100 1.46 Figure 5.19 EOC Recirculation Pump Trip Out of Service Power -
Dependent MCPR Limits for ATRIUM-98 Fuel h
e'
DEG:99:078 '
-~
Attachment -
Page A-69 1.30
- UDS 1 20 8 FWCF
-UeWACp 1 10 -
e 1.004 e t
.0 0.. .
4 70 0 00 0 10 20 3D 40 50 50 70 e 80 to 100 110 c p mwn e Power (% rated) LHGRFAC, 0 0.75-25 0,75 25 0.75 60 0.96 100 1,00'
~ Figure 5.20' EOC Recirculation Pump Trip Out of Service Power Dependent LHGR Multipliers for ATRIUM-9B Fuel h
a a
l DEG:99:078 , Attachment
- Page A 70
-A 2n 25 .
gs,
\- e FWCF
-ouan 24,.
gg..
13<
2 15 224-gte.-
is.-
e in.-
in<
8 t!i6 1 45
', 8. g.
tis 13 .
1 15 0 to 3 to 40 g 30 70 10 E 100 1'.0 cm w manme Power (% rated) MCPR, Limit 0 2.60 25 2.10 25 1.90 60 1.50 100 1.48' Figure 5.21 EOC Recirculat;on Pump Trip Out of Service Power Dependent MCPR Limit: for GE9 Fuel
DEG:99:078 Attachme-
= Page A 71 t -
zu ik--
2M<- 0 UBSweNoWI a RUCrneNoNT
_oucen 1 56 --
2 4$ <-
15, 2 25 t il e gl., ..
in<-
IN'-
14<
1 05 1H.
1 45 '. l e tz. ..
1s.- .
1 15 0 to 20 30 40 - 53 60 4 10 90 100 110 Cose Poss (%sf Rand)
Power (% rated) MCPR, Limit 0 2.80 25 2.30 .
25 2.30-60 1.52 100- 1.42 Figure 5.22 12,000 mwd /MTU Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out of Service Power Dependent MCPR Limits for ATRIUM-9B Fuel
~
e
3 L
DEG:99$078 Attachment Pa9e A-72 in .
. swicy
. uven.wt a FWCF ho RPt UO .. _gg 1.10 -
in. . a 90s..
0.. .
0%,.
- SM 02 0 10 N 3C # M N 70 M N 100 110 Cas Poss(5 elRated)
Power (% rated) LHGRFAC, 0 0.60 25 0.60 25' O.60 60 0.96 100 1.00 Figure 5.23 12,000 mwd /MTU Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out of Service Power Dependent LHGR Multipliers for ATRIUM-98 Fuel-4 M- t u
DEG:99:078 . Attachment
. Page A tm 2m -
, wxy
- use empi in..
e FWCFichbrT is.-
_m 22 14 2.36 -
25 1 15 -
2g.. e ,
iz<.
1 85 .
1 75 ..
1 15 8
1.E ..
! e.
]
1 35 .
12s 1 15 0 10 20 30 # 50 W 70 to to 100 til Can Powerinof bed)
Power (% rated) MCPR, Limit 0 2.80-25 2.30 25- 2.30 60 1.53 100 .1.45 Figure 5.24 12,000 mwd /MTU Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out of Service Power Dependent MCPR Limits for GE9 Fuel 4
DEG:99:078 Attachment Page A-74 In 25 . swa g,, ,. . unemes a FWCF k WT is~ _._oucen 2 16 -
in.
15-1 25 -
itt --
g,,,
tm~
15-1 75 te.
1%
8.
in.
l l 1,. . ,
t2s . '
til 8 10 20 2 40 2 M 70 80 90 100 110 ComPoeflL of Rsed)
Power (% rated) MCPR, Limit O 2.80 25 2.30 25 2.30 60 1.54 100 1.48 Figure 5.25 ' EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out of Service Powei Dependent MCPR Limits .
for ATRIUM-9B Fuel
- y
'I r
DEG:99:078 '- Attachment
- Page A 75 -
im e swicy
. sa. e une
. FWCF
-usum
+
1.10 i
- e .
sa- e QN.
OM.
On-
- ON.
OM 8 10 20 30 40 W IO . 70 N N 100 110 Com Power lE of Rated)
Power (% rated) LHGRFAC, O O.60 25 0.60 25 0.60 60 0.96 100 1.00 t
Figure 5.26 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out of Service Power Dependent LHGR Multipliers for ATRIUM-9B Fuel-
- E __i______________ _________._._____m
DEG:99:078 : ttachment -
Page A-76 25 te" e smicy 23 e uusmet a FWCF h FT 2H' -00NlPR 2 56 2 45 1%~
1 25--
2 15 -
g, e LM.
tu.- ,
1 75 -
ie5 1 55 -
1 45--
E l
u5 .
+
in..
1 15 6 to 20 30 40 50 60 70 N 90 1# 110 -
Coe Pomwl% of Amed) 4 Power (% rated) MCPR, Limit -
0 2.80 25 2.30 25 2.30 60 1.55 100 1.48 Figure 5.27 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out of Service Power Dependent MCPR Limits for GE9 Fuel 1
.I s
DEG:99:078 ' Attachment Page ~A 2M 2m.. e s=1cv e unemorf.anFHoos 1 75 -
e FWCFNoriaanFHool 2m..
- ou m 2 15 -
2 45 -
2 36 -
1254-2154-
, 8 g2n<.
IM.-
1..
% 1.75 -
e 1 45 --
155 <. ,
1 45 '- e l 15 1.5 All 0 10 20 30 40 10 60 70 to 90 100 110 Ces Power $ sihebd) .
Power (% rated) - MCPR, Limit '
O 2.80 25 2.30 25 2.30 60- 1.55 100 1,42 Figure 5.28 12,000 mwd /MTU. Turbine Control' Valve Slow Closure and/or Recirculation Pump Trip and Feedwater Heaters Out of Service
' Power Dependent MCPR Limits for ATRIUM-9B Fuel 0 e
("~
e b 3 _$
l
i DEG:99:078 Attachment Page A 78 1 30 e SlowlCV -
ja, e UUSNo&TalhFH006 e FWCF No RPfulth FH006
_ucaru0 1 10 -
tm. e s
- s 0 00 -
$ e 0 00 -
e 0.m .
e 0 00 0.50 0 to 20 X, 40 50 00 70 80 50 100 110 Cove Power (%of Rated)
Power (% rated) LHGRFAC, 0 0.60' 25 0.60 25 0.60 60 0.92 100 0.98 Figure 5.29. 12,000 mwd /MTU Turbine Control Valve Slow Closure
.and/or Recirculation Pump Trip and Feedwater Heaters Out of Service Power Dependent LHGR Multipliers for ATRIUM-98 Fuel 4
ee
_ . . . . _ . . . . . ...:. . . . . ..___..___i_____, ________________,_,_____i_
DEG:99:078 Attachment Page A-79 tm 1 05 e $w1CV
, une =wt.eFu00s a FWCFhoRPTunFH006 2N. -0LICPR 1s..
2 45 .
1 35 -
- 2 25 -
2 15 -
a g2m..
tu.-
1 85 -
U6 .
8 1 65 is..
1 45 - e l u5 -
125 .
1 15 0 10 20 30 40 60 to M 80 90 100 110 cm.p pane Power (% rated) MCPR, Limit O 2.80 25 2.30 25 2.30 60 1.55 100 1.45 Figure 5.30.12,000 mwd /MTU Turbine Control Valve Slow Closure and/or Recirculation Pump Trip and Feedwater Heaters Out of Service Power Dependent MCPR Limits for GE9 Fuel
DEG:99:078 . Attachmeri, Page A-80
- ts 1s- , gg zz. x s neurs ,
. taememmxs a fW7PtMulhmII is . - aumt 24 -
25 .
22--
25--
25- O ts..
is .
tz-.
E ts..
ts.- ,
8 0 14 .
13 .
to .
15 o e z z e e e a e e a te ro.r.,m aw Power (% rated) MCPR, Limit O 2.80 25 2.30 25 2.30 60 1.55 100 1.48 Figure 5.31 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip and Feedwater Heaters Out of Service Power Dependent MCPR Limits for ATRIUM-9B Fuel
I DEG:99:078 Attachment Page A tm
. sis. icy I SlowTOVunhFH005 in. e UINO NoflPTudhFH005 e FWCFNefFTumbFH006
-usnFwo 1 10 in. s e
- e. x e
0.90 --
.g a 8 00 On-
- C ao l
02 9 to 20 W 40 H 80 70 80 80 100 110 Cue Power (% of Rate (
Power (% rated) LHGRFAC, 0 0.60 25 0.60 25 0.60 60 0.92 100 0.94 Figure 5.32 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip and Feedwater Heaters Out of Service Power Dependent LHGR Multipliers for ATRIUM-9B Fuel-E.___m.___._____
DEG:99:078 Attachment ,
Page A-82 j b ZE g
- f ~
p 22 -
e SanTW 25 .
x Sa=TWAR005
, sammenas e nommenaz 25 -
- (UlGR 26 -
23 .
2s.
\ 25-25 -
a 12-is.- ,
13 -
ss..
15' s __ __
8 te.- 8 a.. .
g..
15 e a m m e s e a e e a tio ca.P= m dams:
Power (% rated) MCPR, Limits I
O 2.80 25 2.30 25 2.30 60 1.55 l 100 1.48 l 1
l Figure 5.33 EOC Turbine Control Valve Slow Closure and/or Recirculation -
Pump Trip and Feedwater Heaters Out of Service Power Dependent MCPR Limits for GE9 Fuel
r DEG:99:078 Attachment Page A-83 Table 6.1 Coastdown Turbine Bypass Valves Out of Service Analysis Results ATRIUM-9B GE9 Power / Flow Event (% rated /% rated) ACPR LHGRFAC, 'ACPR FWCF 100/105 0.347 0.984 'O.357 FWCF 80/105 0.390 0.984 0.401 FWCF 60/105 0.447 0.962 0.452 FWCF 40/105 0.560 0.959 0.557 FWCF 25/105 0.753 0.958 0.837 f
___A_Mh._____U___m__m ' ' ' " * ' ' -
1'
DEG:99:078 Attachment .
Page A 84 t
Table 6.2 Coastdown Recirculation Pump Trip Out of Service Analysis Results ATRIUM-9B GE9-Power / Flow Event' (% rated /% rated) ACPR LHGRFAC, ACPR-LRNB- 100/105 0.396 0.877 0.407 LRNB 80/105 0.459 0.900 0.452 LRNB 60/105 0.461 0.895 0.464 LRNB 40/105 0.424 0.876 0.402 LRNB 25/105 0.281 1.020 0.261 FWCF 100/105 0.339 0.978 0.349 FWCF 80/105 0.381 0.977 0.397 FWCF 60/105 0.451 0.958 0.457 FWCF 40/105 0.507 0.987 0.500 FVVCF 25/105 0.753 0.970 0.837 )
.i l
e
DEG:99:078 Attachment Page A-85 Table 6.3 Coastdown Slow Turbine Control Valve Closure Analysis Results ATRIUM-9B GE9 Slow Valve (s) Power / Flow Event Characteristics (% rated /% rated) ACPR LHGRFAC, ACPR.
LRNB 1 TCV Closing at 2.0 sec 100/105' O.424 0.908 0.413 LRNB 1 TCV Closing at 2.7 see 100/105' O.430 0.903 0.420 LRNB 1 TCV Closing at 2.0 sec 80/105' O.481 0.925 0.475*
LRNB 1 TCV Closing at 2.0 sec 60/105* 0.479 0.933 0.463 LRNB 1 TCV Closing at 2.0 sec 40/105 ' 0.844 0,827 0.817 LRNB 1 TCV Closing at 2.0 sec 25/105 ' 1.167 0.733 0.955 Scram initiated by high neutron flux. -
- Scram initlated by high dome pressure.
'*A....w
r DEG:99:078 Attachment
. Page A-86 Table 6.4 Combined FFTR/Coastdown Turbine Bypass Valves Out of Service Analysis Results ATRIUM-9B GE9 Power / Flow Event (% rated /% rated) ACPR LHGRFAC, _ ACPR FWCF 100/105 0.343 1.014 0.348 FWCF 80/105 0.383 1.003 0.392 FWCF 60/105 0.450 0.983 0.454 FWCF 40/105 0.598 1.076 0.560 FWCF 25/105 1.006 0.883 1.032 4
DEG:99:078 - Attachment .
Page A Table 6.5 Combined FFTR/Coastdown Operation With Recirculation Pump Trip Out of Service Analysis Results ATRIUM-9B GE9 Power / Flow .
Event (% rated /% rated) ACPR LHGRFAC, ACPR-LRNB 100/105 0.357 0.920 0.341 LRNB 80/105 0.439 0.936 0.439 LRNB 60/105 0.447 0.928 0.406 LRNB 40/105 0.328 0.929 0.285 LRNB 25/105 0.233 1.059 0.207 FWCF 100/105 0.340 0.972 0.345' FWCF 80/105 0.405 0.972 ' O.413 FWCF 60/105 0.461 0.962 0.463-FWCF 40/105 0.579 0.942 0.540 FWCF 25/105 1.006 0.883 1.032 f
4 9
DEG:99:078 Attachment Page A-88 Table 6.6 Combined FFTR/Coastdown Slow Turbine Control Valve Closure Analysis Results ATRIUM-9B GE9 Slow Valve (s) Power / Flow Event Characteristics (% rated /% rated) 'ACPR LHGRFAC, ACPR LRNB 1 TCV Closing at 2.0 sec 100/105* 0.389 0.948 0.377 LRNB 1 TCV Closing at 2.7 see 100/105* .O.380 0.957 0.368 LRNB 1 TCV Closing at 2.0 sec 80/105* 0.435 0.962 0.429 LRNB 1 TCV Closing at 2.0 sec 60/105* 0.426 0.957 0.405 LRNB 1 TCV Closing at 2.0 sec 40/105 " 0.822 0.803 0.759 LRNB 1 TCV Closing at 2.0 sec 25/105 " 1.097 0.758 0.968 t
Saram initiated by high neutron flux.
'. Scram initiated by high dome pressure.
DEG:99:078. Attachment -
Page A-89 2.75 2 65 , gwcy 2s. \ -0L" te.
22-2 25 -
2 15 -
2 05 .
1.95 1.75 --
1.65 ,
1.55 .
to.
1 15 12 t il 0 to 20 30 40 50 60 70 M 90 100 110 Com Power (%of Rand)
Power (% rated) MCPR, Limits O 2.60 25 2.10 25 2.00 60 1.55 100 1.43
. Figure 6.1 Coastdown Operation With Turbine Bypass Valves Out of Service Power Dependent MCPR Limits for ATRIUM-9B Fuel
DEG:99:078 Attachment Page A-90 1.30 m rwcr
-vown 12 1 10 1 00-e a n G
I cio 0 00 -
0 70 -
0 00 0 20 40 80 80 100 tE ,
Core Power $ elRand)
Power (% rated) LHGRFAC, O O.75 25 0.75 25 0.75 60 0.95 100 0.97 Figure 6.2 Coastdown Operation With Turbine Bypass Valves Out of Service Power Dependent LHGR Multipliers for ATRIUM-98 Fuel'
.t-
DEG:99:078 Attachment .
Page A-91 2n ,
2 85 s FVdCF
~
2.M ..
26 -
'an..
22 ~
215 <
tM.
g,00 ,
i a5 1.75 1M. ,
1.55 ,
18 33, 13 1.15 0 to 20 30 40 50 50 70 00 00 100 tto c P ron.g Power (% rated) MCPR, Limit O 2.60-25 2.10 25 2.00 60 1.56 100 1.44
~
Figure 6.3 Coastdown' Operation With Turbine Bypass Valves Out of
- Service Power Dependent MCPR Limits for GE9 Fuel .
J 9
DEG:99:078 Attachment Page A 92 2n 1 65
,g 255 ~
8N
-ouem 1 45 -
1 35 -
1 25 -
215 ~
20$ r 1 95 -
,5 ,
tn..
1 65 -
~
1 55 a
1 45 .
1 35 '
1 25
- 15 0 10 20 30 /> $0 60 M 80 90 100 110 7
ro. p== rw nme Power (% rated) MCPR, Limit O 2.60 25 2.10 25 2.00 60 1.62 100- 1.48 Figure 6.4 Coastdown Operation With Recirculation Pump Trip Out of Service Power Dependent MCPR Limits for ATRIUM-9B Fuel
DEG:99:078 Attachment Page A-93 ics e use u0 -usvAc, a s E
8.M ..
ON< ,
0 6$ <
Q
$0m.
Or, 010 0.65 -
0 60 0 10 3 # 40 W 60 70 60 90 100 110 Ces Power (% of Rded)
Power (% rated) LHGRFAC 9
.0 0.75 25 0.75 25 0.75 60 0.87 100 0.87 Figure 6.5 Coastdown Operation With Recirculation Pump Trip Out of Service Power Dependent LHGR Multipliers for ATRIUM-9B Fuel Y __ _l
1 DEG:99:078 -Attachment Page A tn gg..
. Los 2.55 ,y me..
-ouon 23 .
ta.-
2 15 -
15<.
1.E .-
in -
1.n .-
16 5
15<- g 12 .
t 26 -.
1.15 Il to 20 30 40 M to 70 to 90 100 110 caer rsenne Power (% rated) MCPR, Limit 0 2.60 25 2.10 25 2.00 60 1.62 a 100 1.49 Figure 6.6 ~ Coastdown Operation With Recirculation Pump Trip Out of )
Service Power Dependent MCPR Limits for GE9 Fuel
DEG:99:078 Attachment Page A-95 20s - - - -
2n. , ,, a in<-
- U** * *1 e FWCFNoFT 2 85 -
_,y tu--
24s-.
US <.
us -
e 21$ ..
g:0s~
1 85 .
as .
us us .
3 us -
Ils--
1.18 0 10 20 30 40 so 80 70 00 to 100 110 Core Power (%of hhd}
Power (% rated) MCPR, Limit 0 2.80 25 2.30 25 2.30 60 1.65 100 1.51 Figure 6.7 Coastdown Operation With Turbine Control Valve Slow Closure and/or No RPT Power Dependent MCPR Limits-for ATRIUM 9B Fuel if.
DEG:99:078 . Attachment Page A-96 1m
. n-Tev 12--
' N*E 5 wem
-van @
to--
12 ,
" 8 E e
on-- , , 8 e -
02 -
am--
02 as e e a a e e e a e e a in
. cae w r4 dame Power (% rated) LHGRFAC, 0 0.60 25 0.60 25 0.60 60 0.87
, 100 0.87 Figure' 6.8 Coastdown Operation With Turbine Control Valve Slow Closure and/or No RPT Power Dependent LHGR Multipliers for ATRIUM-9B Fuel m -
DEG:99:078 Attachment Page A 25 15 e SW1CV 6 UUS No flPT 1 75' 3 FWCF No RPT in -00CPR 15 -
f 2454 15 -
25 .
til .-
.gis. .
s .
t85 <.
1 75 .
1H4.
12 3 $
1 45 g
15 .
a 15 .
1 15 :
0 10 20 30 # 50 60 70 M to 100 110 rm Peeryame Power (% rated) MCPR, Limit -
0 2.80 25 2.30 25 2.30 60 1.65 100 1.51 Figure 6.9 Coastdown Operation With Turbine Control Valve Slow Closure and/or No RPT Power Dependent MCPR Limits for GE9 Fue!
W
DEG:99:078 Attachment Page A-98 '-
' 25 '
'25 s FWCF 2g.,
t14
- 24 2.2 1 25 -
215 <
ig.
< 15<
15 tM-15-1 56 --
ie.
- 15-1 25 --
1 15 o to a a e a e n a a e m Core Power (sof Reed)
Power (% rated) MCPR, Limit O 2.70 25 2.20 25 2.20 60 1.55 100 1.43 Figure 6.10 ' Combined FFTR/Coastdown Operation With Turbine Bypass Valvas Out of Service Power Dependent MCPR Limits for ATRIUM-98 Fuel 4
DEG:99:078 Attachment Page A-99 tM e ma 1JO<
110 <
e I
l 1 00 e-e ^
G l am.
e QN<
t an-8 40 0 10 - N 30 40 so a 70 W to 100 110 c r nan e Power (% rated) LHGRFAC, O O.65 25 0.65 25 0.65 60 0.95 100 0.97 Figure 6.11 Combined FFTR/Coastdown Operation With Turbine Bypass
- Valves Out of Service Power Dependent LHGR Multipliers
, for ATRIUM-9B Fuel
'y-
i
. DEG:99:078 Attachment -
Page A 100 to 23 s FWCF su. _m 12-24<-
22-
. 22 <
215 <-
2m.
LV in.-
1.5 -
1.N < s 12- g 1 45 -
1M.,
12<-
1.15 0 to 20 m 40 50 W 70 N N 100 110 Core Power (% of Ratal)
Power (% rated) MCPR, Limit 0 2 70 25 2.20 25 2.20 60 1.56 100 1.44 Figure 6.12 ' Combined FFTR/Coastdown Operation With Turbine Bypass Valves Out'of Service Power Dependent MCPR Limits for GE9 Fuel
DEG:99.078 Attachment Page A-101 le 1 75 --
2 85 a FWCF
_oucn 2 55 2 45 12 -
125 2 15 1 05 hins.
1 85 .
1 75 165 l. 5 iss .- g 1 45 i N g
us e
1 25--
1 15 0 10 20 30 40 50 80 70 80 90 100 110 ComPoner(% WReed)
Power (% rated) MCPR, Limit O 2.70 25 2.20 25 2.20 60 1,62 100 1.48 Figure 6.13 Combined FFTR/Coastdown Operation With Recirculation Pump Trip Out of Service Power Dependent MCPR Limits
. for ATRIUM-9B Fuel
DEG:99:078 Attachment Page A-102 1.M e um a m::F
-owAce 1.10 e
1N.
g F g e ,
em.
e 0 80 0704-9 60 0 10 20 N 40 60 80 70 80 H 100 110 Cat Power (% WRae4 Power (% rated) LHGRFAC, O O.65 25 0.65 25 0.65 60 0.87 100 0.87 Figure 6.14 Combined FFTR/Coastdown Operation With Recirculation Pump Trip Out of Service Power Dependent LHGR Multipliers for ATRIUM-96 Fuel
DEG:99:078 - Attachment Page A-103 2E 2n.
. tme te.
e FWCF 22-- _g 24-25-.
1 25 ,
2 15 -
e 1 05 him..
1m..
1 75 -
1 85 1E-- ,
- 8 14 e
tz..
125 <
1 15 0 2 20 N # 50 82 70 i go @ 110 Core Power $of flatd)
Power (% rated) MCPR, Limit O 2.70 25 2.20 25 '2.20 60 1.62 100 1,49 Figure 6.15 Combined FFTR/Coastdown Operation With Recirculation Pump Trip Out of Service Power Dependent MCPR Limits for GE9 Fuel
r DEG:99:078 Attachment -
Page A-104 ans ,
an . se.r.y in..
s FWCF lio M 1 55 -
-0LifCPR 26 .
2 35--
1 25~
2 15 .
2 05 1.H <
1 85 --
1 76 -.
1 85-- 8 1.65 .
in..
, l 1 35
+
125 <
1 15 0 10 20 30 40 60 00 70 m M 100 110 Cow Power l%of Rand)
Power (% rated) MCPR, Limit O 2.80 25 2.30 25 2.30 60 1.65 100 1.51 Figure 6.16 Combined FFTR/Coastdown Operation With Turbine Control ,
Valve Slow Closure and/or No RPT Power Dependent MCPR Limits- '
for ATRIUM 98 Fuel
q l
- DEG:99:078 Attachment l Page A-105 12 e Slow %V gy, e LNS No RPT-3 FWCF NoIFT
-LHGEACp 11 l'
B I g i e +
$19 I
O.. .
e 0.1 66 05 O to 20 30 40 50 to 70 80 to 150 110 Cove Power (%of Asted)
Power (% rated). LHGRFAC, O O.60 25 0.60 25 0.60 60- 0.87 100 0.87-
_ Figure 6.17 Combined FFTR/Coastdown Operation.With Turbine Control.
Valve Slow Closure and/or No RPT Power Dependent LHGR Multipliers for ATRIUM-9B Fuel o
DEG:99:078 Attachment
' Page A-106 2 95 2 85 e 8;cwIC)f 2 75 ' e UU$ ho RPT 25 s FWCFleRPT
~
ggi 2 45 -
2N<
2 25 -
1 15 -
1 05 -
8 1 95 -
1 85 e 1 75 -
1 65 -
1 55 .
s 1 45 .
g f
sni.
13<-
1 15 0 10 20 30 40 50 M 70 80 90 100 110 Core Power {%of Rand}
Power (% rated) MCPR Limit O 2.80 25 2.30 25 2.30 60 1.65 100 1.51 Figure 6.18 Combined FFTR/Coastdown Operation With Turbine Control Valve Slow Closure and/or No RPT Power Dependent MCPR Limits for GE9 Fuel -
i
'pr i 'T gi i
DEG:99:078 Attachment Page A-107 Table 7.1 ASME Overpressurization Analysis Results 102%P/105%F Peak Peak- Maximum Vessel Maximum Dome Neutron Heat Pressure Pressure Event Flux Flux Lower Plenum (psig) .
(% rated) (% rated) (psig)
MSIV 355.1 133.1 1309.7 1280.0 TCV 648.1 142.6 .1308.7 1277.0 TSV 648.3 142.6 1309.1 1277.8' i
1 a
l u .-u a - --. La- .s.
DEG:99:078 . Attachment -
Page A-108 soob ,
CORE POWER EAT FLUX-CORE FLOW STEAM FLOW 300.0 -
FEED FLOW .
v j rood-n:
o y ,--..
g ,, .....e...-.-... ,,..
- ---...,,, ' - = . m ..-
o, t [
\l\[s]VV'I
-'#8 . . . . .
Tme (Seconds)
Figure 7.1 Overpressurization Event at 102/105-MSIV Closure Key Parameters 4
ig ii
)
' DEG:99:078 : Attachment Page A 109 -
.p s7.0 36.0 --
o 4'
N j 35.0-s I
$ un-8 i
j 33A-a t
o 32A-T s,a -
aan I# IS 34 4!D 5!0 - 64 '
Time (Seconds)
Figure 7.2 Overpressurization Event at 102/105-
- MSIV Closure Vessel Water Level.
. er h
I b
E _ 3:99:078 Attachment Page A-110 1350A 1300A-7 S 12som-5
?
a troom-I.
E e 115o4-I o
a l
11004 I
- D , , , , ,
D 1h 2D 32 4D LD Sb Time (Seconds)
Figure 7.3 -Overpressurization Event at 102/105-MSIV Closure Lower Plenum Pressure
- ,s a
-~ _ _ _ _ . _ . . . . _ _ _ _ . . _ _ .____..._..__________m._. . _ _ _ _ _ . _ _
- DEG
- 99:078 . Attachment .
Page A-111-13004 w
\
1250A-g 1200A-m o
, 11$0A -
at 0 1100.0 -
1050.0-
' s . a , ,
A 'IA 10 ' ). 3A 44 SJ 64 Time (Seconds)
Figure 7.4 Overpressurization Event at 102/105-.
. MSI/ Closure Dome Pressure
+
9 4
')-
. 2. .... m.......au. i.... .. -- -. .-
DEG:99:078 Attachment Page A 117, zooom SRV BANK 1
...SRV BANK.2 . -
tsoo.o-7 s
1
, icoo.o- , . , , . _ , . -- ,
if // [
> 'l i Di !!
t:
lI lII i!
sooh- g:
!i n!l .
II 1j fj i
i 'I D ' .
A lb 2.0 3.0 44 5.0 6.0 Trne(Seconds)
Figure 7.5 Overpressurization Event at 102/105-MSIV Closure Safety / Relief Valve Flow P.atas
_'t
+
- DEG:99:078 Attachment .
Page A 113 '
m CORE POWER' E AT FLUX CORE FLOW I STEAM FLOW
"' ~
FEli) FLOW ]
m I j m-a:
o c
8 t m-n.
.<.___~~.,g.,,-
~~..
f --- _- =J,aws.g.~
~
I l
f~x - %-
)
D-
\j' sp'
-m . . . . .
A 1D 2D 3D 4D SD SD Tme (Seconds) .
Figure 7.6 Overpressurization Event at 102/105-TSV Closure Key Parameters
=
C
DEG:99:078 - ' Attachment Page A-114' no
?
t
$"8 1-s E
d340-1 5
a t
li 3:
j 324-MS i i i i i A th 2.0 3D 4D ' 54 - 6.0 Trne (Seconds)
Figure 7,7, Overpressurization Event at 102/105-TSV Closure Vessel Water Level f- ,
DEG:99:078 Attachment
. Page A 115 1WD 1204- w 7
's a nus-I
.ao-i
> vus.
E a
snoon. .
4 1080s a gg A 0 ' sa Time ( conds) s Figure 7.8 Overpressurization Event at 102/105-TSV Closure Lower Pier.:im Pressure f
4
DEG:99:078 ' Attachment Page A~. 116 1300D
\ w 12so.o-t 9 ro0D-
~m o
e b
- issob-E o.
e E
o O 1 003-1050 2 -
5 5 5 5 5 b 1D 2D 3h 4D SD SD Time (Seconds)
Figure 7.9 Overpressurization Event at 102/105-TSV Closure Dome Pressure e
9 9
4
(
- DEG:99:078 Attachment -
Page A-117 accoD SRV BANK 1 SR ,B, ,2 ,
1 10ooD- -m_'.- ---,:.----.
'P~
\- . -
2 s.-
/l\t/\/
5 th N\
s ::
sub-(l u
I :l ,,
\*
!. l li' 8 ,
!!I D 12 .4 3.o 4D SD sD Time (Seconds)
Figure 7.10 : Overpressurization Event at 102/105-TSV Closure Safety / Relief Valve Flow Rates Y~
> m _