|
|---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20248F3341989-03-31031 March 1989
Design Certification Licensing Review Basis
ML20246M1121988-12-31031 December 1988
Vol Viii to Resolution of Outstanding Nuclear Fission Product Aerosol Transport & Deposition Issues Wbs 3.4.2
ML20151G1141988-07-15015 July 1988
Design Certification Licensing Review Bases
LD-88-049, Flow Distribution & Tube Vibration:Evaluation of Sys 80 Steam Generator Tube Lane/Economizer Corner Region1988-07-0101 July 1988
Flow Distribution & Tube Vibration:Evaluation of Sys 80 Steam Generator Tube Lane/Economizer Corner Region
LD-88-015, Nonproprietary Base Line Level 1 PRA for Sys 80R NSSS Design1988-01-31031 January 1988
Nonproprietary Base Line Level 1 PRA for Sys 80R NSSS Design
ML20235G9941987-09-30030 September 1987
Response to NRC Evaluation of CEN-315 for Sys 80R
ML20234D7241987-07-0101 July 1987
Draft Sys 80R Design Certification Licensing Basis Agreement
ML20137H1491985-06-28028 June 1985
Amend 10 to C-E Std Sar.W/Two Oversize Figures
ML20101B4791984-11-30030 November 1984
Summary Rept on Design Basis of Shutdown Cooling Sys Relief Valves for CESSAR Sys 80
ML20101B4931984-11-30030 November 1984
Summary of Rept on Operability of Shutdown Cooling Sys Relief Valves for Palo Verde Units 1,2 & 3
ML20087G6341984-02-29029 February 1984
Amend 9 to C-E Std SAR
ML20024E3921983-08-31031 August 1983
Nonproprietary Info on Sys 80 Bypass Flow.
ML20076D2681983-08-31031 August 1983
Encl 2-NP to LD-83-010,Rev 1, Statistical Combination of Uncertainties Part III - Uncertainty Analysis of Limiting Conditions for Operation C-E Sys 80 Nsss
ML20023B9501983-04-30030 April 1983
Nonproprietary Response to NRC Questions on CESSAR-F Statistical Combination of Uncertainties in Thermal Margin Analysis for Sys 80, (SER Item 7)
ML20073D8791983-04-30030 April 1983
Nonproprietary Response to NRC 830131 Questions Re Sys 80 Core Protection Calculators & Reactor Power Cutback Sys
ML20073Q3041983-04-30030 April 1983
Nonproprietary Version of, CESSAR Fuel & Control Element Assembly Design Evaluation Summary Rept
ML20069L7871983-04-30030 April 1983
Sys 80 CESSAR Fsar,Responses to Questions on Steam Line Break Method
LD-83-020, Nonproprietary Response to NRC Questions for CESSAR-F Statistical Combination of Uncertainty in Thermal Margin Analysis for Sys 801983-03-31031 March 1983
Nonproprietary Response to NRC Questions for CESSAR-F Statistical Combination of Uncertainty in Thermal Margin Analysis for Sys 80
ML20079N3581983-01-31031 January 1983
Nonproprietary Statistical Combination of Uncertainties Part Ii,Uncertainty Analysis of Limiting Safety Sys Settings C-E Sys 80 Nsss,Part II
ML20079N3761983-01-31031 January 1983
Nonproprietary Statistical Combination of Uncertainties Part Iii,Uncertainty Analysis of Limiting Conditions for Operation C-E Sys 80 Nsss,Part III
ML20027C3381982-09-30030 September 1982
Statistical Combination of Uncertainties,Part II, Uncertainty Analysis of Limiting Safety Sys Settings for C-E Sys 80 Nsss.
ML20027C3411982-09-30030 September 1982
Statistical Combination of Uncertainties,Part III, Uncertainty Analysis of Limiting Conditions for Operation for C-E Sys 80 Nsss.
ML20063M1831982-09-0808 September 1982
Natural Circulation Cooldown of C-E Sys 80 Nsss
ML20063A4771982-08-31031 August 1982
Long-Term Iodine Control in Reactor Containment Bldgs Using C-E Iodine Removal Sys
ML20050A9351982-03-31031 March 1982
Nonproprietary Safety Evaluation of Reactor Power Cutback Sys.
ML20050A9361982-03-31031 March 1982
Nonproprietary Cpc/Ceac Software Mods for Sys 80.
ML20041D7751982-03-0404 March 1982
Review of Depressurization & Decay Heat Removal Capabilities for C-E Sys 80 NSSS
ML20040E1211982-01-31031 January 1982
Response to Round One Question 440.40 on Cessar Fsar. Nonproprietary Version
1989-03-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20042E9171990-04-30030 April 1990
Amend G to C-E SAR Design Certification
ML20011D5171989-12-15015 December 1989
Amend F to C-E Std SAR - Design Certification (CESSAR-DC).
ML19324B6831989-10-31031 October 1989
QA Program:Description of Nuclear Power Businesses QA Program, Rev 5
NUREG-0852, Sser Supporting Vendor Responses to Confirmatory Issue 2, Steam Generator Tube Rupture. Calculated Radiological Consequences of Postulated Steam Generator Tube Rupture Accident Meets 10CFR100.11 Dose Ref Values1989-08-0404 August 1989
Sser Supporting Vendor Responses to Confirmatory Issue 2, Steam Generator Tube Rupture. Calculated Radiological Consequences of Postulated Steam Generator Tube Rupture Accident Meets 10CFR100.11 Dose Ref Values
NUREG-1044, Sser Supporting Vendor Responses to Confirmatory Item 1, Shutdown Cooling Sys1989-08-0404 August 1989
Sser Supporting Vendor Responses to Confirmatory Item 1, Shutdown Cooling Sys
ML20246A2321989-04-28028 April 1989
Sser Re CESSAR Sys 80 Concerning Steam Generator Tube Vibration
ML20248F3341989-03-31031 March 1989
Design Certification Licensing Review Basis
ML20248B0021989-03-30030 March 1989
App 3A, Discussion of Finite Difference Analysis for Analysis of Pipe Whip, to CESSAR Sys 80+ Std Design
ML20247H4531989-03-30030 March 1989
App 15C, Analysis Methods for Steam Line Breaks, to CESSAR Sys 80+ Std Design
ML20247H4701989-03-30030 March 1989
Chapter 16, Tech Specs, to CESSAR Sys 80+ Std Design
ML20247H4781989-03-30030 March 1989
Chapter 17, QA Program, to CESSAR Sys 80+ Std Design
ML20247J0591989-03-30030 March 1989
Chapter 18, Human Factors Engineering, to CESSAR Sys 80+ Std Design
ML20247G9891989-03-30030 March 1989
App 5C, Structural Evaluation of Feedwater Line Break for Steam Generator Internals, to CESSAR Sys 80+ Std Design
ML20248C3801989-03-30030 March 1989
App 3.11A, Environ Qualification for Structures & Components, to CESSAR Sys 80+ Std Design
ML20248C3921989-03-30030 March 1989
App 3.11B, Identification & Location of Mechanical & Electrical Safety-Related Sys Components, to CESSAR Sys 80+ Std Design
ML20247H2911989-03-30030 March 1989
Chapter 7, Instrumentation & Controls, to CESSAR Sys 80+ Std Design
ML20247H0331989-03-30030 March 1989
Chapter 6, Esfs, to CESSAR Sys 80+ Std Design.W/One Oversize Encl
ML20247H4431989-03-30030 March 1989
App 15B, Methods for Analysis of Loss of Feedwater Inventory Events, to CESSAR Sys 80+ Sys Design
ML20247H4271989-03-30030 March 1989
App 15A, Loss of Primary Coolant Flow Methodology Description, to CESSAR Sys 80+ Std Design
ML20247H4171989-03-30030 March 1989
Chapter 15, Accident Analyses, to CESSAR Sys 80+ Std Design
ML20247H4031989-03-30030 March 1989
Chapter 14, Initial Test Program, to CESSAR Sys 80+ Std Design
ML20247H3971989-03-30030 March 1989
Chapter 13, Conduct of Operators, to CESSAR Sys 80+ Std Design
ML20247H3941989-03-30030 March 1989
Chapter 12, Radiation Protection, to CESSAR Sys 80+ Std Desing
ML20247H3601989-03-30030 March 1989
App 11A, Core Residence Times, to CESSAR Sys 80+ Std Design
ML20247H3531989-03-30030 March 1989
Chapter 11, Radwaste Mgt, to CESSAR Sys 80+ Std Design
ML20247H3361989-03-30030 March 1989
Chapter 10, Steam & Power Conversion Sys, to CESSAR Sys 80+ Std Design.W/One Oversize Encl
ML20247H3161989-03-30030 March 1989
Chapter 9, Auxiliary Sys, to CESSAR Sys 80+ Std Design. W/Four Oversize Encls
ML20247H3081989-03-30030 March 1989
Chapter 8, Electric Power, to CESSAR Sys 80+ Std Design
ML20247G9831989-03-30030 March 1989
App 5B, Structural Evaluation of Steam Line Break for Steam Generator Internals, to CESSAR Sys 80+ Std Design
ML20247G6661989-03-30030 March 1989
Chapter 1, Introduction & General Plant Description, to CESSAR Sys 80+ Std Design.W/One Oversize Encl
ML20247G6781989-03-30030 March 1989
Chapter 2, Site Envelope Characteristics, to CESSAR Sys 80+ Std Design
ML20247G7141989-03-30030 March 1989
Chapter 3, Design of Structures,Components,Equipment & Sys, to CESSAR Sys 80+ Std Design
ML20247G8511989-03-30030 March 1989
Chapter 4, Reactor, to CESSAR Sys 80+ Std Design
ML20247G8621989-03-30030 March 1989
App 4A Sys 80 Reactor Flow Model Test Program, to CESSAR Sys 80+ Std Design
ML20247G8681989-03-30030 March 1989
App 4B, Hot Loop Flow Testing of Sys 80 Fuel & Control Element Assembly Components, to CESSAR 80+ Std Design
ML20247G9131989-03-30030 March 1989
Chapter 5, RCS & Connected Sys, to CESSAR Sys 80+ Std Design.W/Two Oversize Encls
ML20247G9281989-03-30030 March 1989
App 5A, Overpressure Protection for C-E Sys 80 Pwrs, to CESSAR Sys 80+ Std Design
ML20246M1121988-12-31031 December 1988
Vol Viii to Resolution of Outstanding Nuclear Fission Product Aerosol Transport & Deposition Issues Wbs 3.4.2
ML20206C7791988-09-30030 September 1988
QA Program
ML20151G1141988-07-15015 July 1988
Design Certification Licensing Review Bases
LD-88-049, Flow Distribution & Tube Vibration:Evaluation of Sys 80 Steam Generator Tube Lane/Economizer Corner Region1988-07-0101 July 1988
Flow Distribution & Tube Vibration:Evaluation of Sys 80 Steam Generator Tube Lane/Economizer Corner Region
ML20150B8181988-06-30030 June 1988
Amend C to CESSAR-DC
ML20151H8191988-04-11011 April 1988
CESSAR-DC Submittal Group B - Revs to Chapters 1,4,5 & 9
LD-88-015, Nonproprietary Base Line Level 1 PRA for Sys 80R NSSS Design1988-01-31031 January 1988
Nonproprietary Base Line Level 1 PRA for Sys 80R NSSS Design
LD-88-005, Draft C-E Sys 80+TM Std Design, Design Certification Licensing Review Bases.Response to NRC Comments on Licensing Document Encl1988-01-18018 January 1988
Draft C-E Sys 80+TM Std Design, Design Certification Licensing Review Bases.Response to NRC Comments on Licensing Document Encl
ML20234C6451987-12-31031 December 1987
Safety Evaluation Report Related to the Final Design of the Standard Nuclear Steam Supply Reference System.Cessar System 80.Docket No. 50-470.(Combustion Engineering,Incorporated)
ML20235G9941987-09-30030 September 1987
Response to NRC Evaluation of CEN-315 for Sys 80R
ML20236W0531987-09-11011 September 1987
Amend 12 to CESSAR-F
ML20234D7241987-07-0101 July 1987
Draft Sys 80R Design Certification Licensing Basis Agreement
ML20137H1491985-06-28028 June 1985
Amend 10 to C-E Std Sar.W/Two Oversize Figures
1990-04-30
[Table view] |
Text
,
e ENCLOSURE 1-NP to LD-83-068 INFORMATION ON SYSTEM 80 BYPASS FLOW AUGUST,'i983-i-
(
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! 8308100332 830803 l
DR ADOCK 05000470 PDR I
..y LEGAL NOTICE -
This report was prepared as an account of work sponsored by Combustion Engineering Inc. Neither Combustion Engineering nor any person acting on its behalf:
A.
Makes any warranty or representation, express or implied including the warranties of fitness for a particular purpcse or merchantability, with respect to the accuracy, completeness, or usefullness of the information contained in this. report, or-that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rightst or B. Assumes any liability with respect to the use of, or for damages resuiting from the use of, any information.
apparatus, method or process disclosed in this report.
O k
e-
INFORMATION ON SYSTEM 80 BYPASS FLOWS
- 1. Introduction
~
The System 80 design contains five different types of guide tubes, each type
, , having different flow resistance networks and, therefore, different bypass flow rates. The flow networks and flow resistances are presented in detail in this report.
Also presented in this report is a comparison of bypass flow rates between the System 80, 2570 MWth and 3410 MWth class designs.
2.- Types of Guide Tubes The System 80 reactor design contains five different kinds of guide tubes.
They are:
1 .. center guide tubes containing in-core instrumentation
- 2. empty center guide tubes
- 3. corner guide tubes containing control rods (CEA's)
- 4. corner guide tubes in non-CEA locations
- 5. corner guide tubes in CEA locations but containing no control rods At the present time the inventory of these five types of guide tubes in the reactor is as follows:
- 1. instrumented center guide tubes: 61
- 2. empty center guide tubes: 180
- 3. rodded corner guide tubes: 740
- 4. corner guide tubes in non-CEA locations: 160
- 5. unrodded corner guide tubes in CEA locations: 64 Total 1205
- 3. Driving Heads The driving heads for the five categories of guide tubes are listed in the following Table. The subscripts coincide with the numbered guide tube stations shown in Figure 1.
h
, --n , er , . , - -
- - . , . , , - . - - - . - - , - , - . , - - - - - n. -- ,, , , ,, , ,- .,_,-c-,----,
TABLE OF DRIVING HEADS Type of Guide Tube pin-Pout Numerical Value (psi)
^
- 1. instrumented center GT P6
- 2. empty center GT P6
- 3. rodded corner GT P8
- 4. corner GT in non-CEA location P6
- 5. unrodded corner GT P4-P8 in CEA location -
- 4. Flow Networks The overall geometry of the five categories of' guide tubes is exhibited in Figure 2. The inlet and exit positions of the flow are indicated by wiggly arrows. Next to each flow network a sketch of the applicable guide tube geometry is added to help interpret the network components. For each bra every flow network the pressure loss coefficient is shown in the form K/Agch of ,
which can be interpreted as the pressure loss coefficient per unit square area. The K values are based on empirical information from published literature. For convenience, the pressure at the flow inlet is always designated as O psi.
- _ - - _-- --~ -- ---,,-.,n._,_. , - - . , - . . . , -. - . , . , , .p-.,_,. , - - - ,,.-----,.--n-.,,.-.-e m.,,, a - , ,, . _ , -,-,-, 7
~
4.1 Instrumented Center Guide Tube
~
lO &W g
3:9
.h LEF f
Jh >@
l Q,
p
, The GT bypass flow in the above flow network is represented by the term (Wj -W2
). The numerical solution of the network equations yields
, (W-W)=(
7 2 lbm/sec The total bypass flow for the 61 instrumented center GT's then becomes:
1 2 IN'W)cenkf[Ck - ~
1
4.2 Empty Center Guide Tubes
. . ,. . . . . +@
- ^& !
z r
?
/ *"
j .EF t
i m i~
/ / // ////
The GT bypass flow in the above flow network is represented by the term W).
The numerical solution of the network equations yields W j=r -
jlbm/sec The total bypass flow for the 180 empty center GT's then becomes: -
lbn/hr W =
4.3 Rodded Corner Guide Tubes
.m r .
I' o
d63SP
%\ \\' r ngg /
j TIE TOSE 1
l IDMM (gg OEF
{"'I t,s j
LEF
~
\\\\'\\ Ass
~
The GT bypass flow in the above flow network is represented by the term W7 .
l The numerical solution of the network equations yields
{ W) ={ lbm/sec l'
The total bypass flow for the 740 rodded corner GT's then becomes:
W 1bm/hr fyggggGT* . _
l i
l I
4.4 Empty Corner Guide Tubes in Non-CEA Positions
'l///$,///// ,
U EF
~
l GT k
.@ < v
//// /// // .
l The GT bypass flow in the above flow network is represented by the term W. The l numerical solution of the network equations yields:
1 . -
W= . ..
lbm/sec The total bypass flow- for the 160 empty corner GT's then becomes:
-' W lbm/hr er GT = ,.
corEy emp - '
I
e I
4.5 Empty Corner Guide Tubes in CEA Locations l.
h\W( R\\\\\ V
' ' TIE Tupe I I J l mmw xx m xs O n
= g uer J
GT
. LEf 4 . Im
////s //
The GT bypass flow in the above flow network is represented by W). The numerical solution of the network equations yields:
W j =[ lbm/sec
, The total bypass flow for the 64 empty corner GT's then becomes:
N lbm/hr corerGT"f empEy -
y
- For simplicity, the same values as for th$ redded case was used. The difference between rodded and unrodded case is negligible.
- 5. Operating Condition (Nominal Design Flow Rate) 6 Vessel mass flow rate: 154x10 lbm/hr
- 6. Summary of Results of Guide Tube Bypass Flow Rates No. of GT's Category of GT Driving p 0/QD (psi) (1bm/hr). %
61 Center GT w/ICI 180 Center GT w/o ICI 740 Corner GT, rodded 160 Corner GT, unrodded non-CEA pas.
64 Corner GT, unrodded CEA pos.
1205 TOTAL _
i l
l l
l
( -
, COMPARISON OF BYPASS FLOW RATES IN PERCENT OF DESIGN FLOW RATE SYSTEM 80 2570 3410 3817
- Bypass Flcw Path MWth MWth MWth Outlet Nozzles 0.4 0,6 1.0*
Core Shroud 0.7 0.6 0.3**
(a) seams in shroud 0.4 0.3 0.0**
(b) cylinder holes 0.3 0.3 0.3 Alignment Keys 0.4*** 0.1 0.4 Guide Tubes 1.7+ 0.8+ 0.7+E (a) center guide tubes 0.2 0.2 (b) corner guide tubes 1.5 0.6 0 0.4. 3 ><
TOTAL 3.2 2.1 2.4
- 2570 MWth and 3410 MWth design bypass flows are based on as-built nozzle gaps. System 80 outlet nozzle bypass flows are larger because of larger outlet nozzle diameter inherent. in the design and calculations are based on maximum drawing allowed nozzle gap dimensions. .
- Welded construction in System 80 has eliminated bypass flow through seams in core shroud.
- The bypass flow through alignment keys reported in 2570 MWth class reactor FSAR wasThis keyways. calculated for a flow area ig larger- (9.6area in ) agsociated than for 3410 with an early MWth (2.4 in desigg)for the and System 80 (6.8 in ) designs.
. + Guide tube bypass flows show a decreasing trend due to use of smaller guide tube flow holes for- the later reactor designs.
> # The final best estimate guide tube flow rate has increased from 0.6% shown in CESSAR to the 0.7% shown here as a result of incorporating latest design changes. The design value for total bypass flow remains at 3.0% for System y
~
e -.
,. , , , . --.a. _ , .7-, - - -,,n ... ., , , e- - . - -, , . , . --e n ., -. - .,,-,
GUIDE TUBE STATIONS e
b e
4 E sg I t
\
J .a w c> '
]\ s
~
i wiur-
.
__ - k;T(
'7 6
\
. 5 s < \
\ \
\ 4
\
\ \
\ \
\ i \
\ } \
\ n ) \ *
\ \
\ \
\ '
5
_i 4
\
s _ . y. __
1 -
- i_ . - _
s - _. 3
\ '- t N
_ _ _ _4 s s s FIGURE 1.
e
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f.t OSVOE HE AD 12EG10M '<
y I
Q GrG REGrlOM
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W{ WALIGMNEui j s
%)
s s s
}b INLE t-f s "bOL40C0HER
. , ,,..r UG G "Pt.A cr j
......,.m......_., N1l 7
/'lE N6 _. M02'tLE F0EL AL.tGuNEUT HATE -Is m ap.2 x u y 1 s ss ss C u- -
,\,, .
y ,
'Ik'com D. [ (, EEACTc7.
coeune
- *Y b'ft t 4ECCE G N / / ,
e $
g GutDE l s s
-UN3 L j
Nd CC26sWouc l fs euuct.uS.
s h T s
- 4 i ,
1
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.I FIGURE 2
INITIAL DESIGN GUIDE TUBE FLOW HOLE DIMENSIONS
- s GUIDE TUBE LOCATION NUMBER OF H0LES DIMENSLON(INCHES)
Center Guide Tube 1 Corner Guide Tube 2 1
I
) ..
- These values were used in the initial calculation of best estimate core bypass flow which resulted in the 4.0% value quoted in Revision No. 4 of CESSAR-F.
e er --- - -
9.-%y. . - - - - -
,--.,.e-1 --.e- oy r- - ,y- ---y- - - - - , , - - - , . - - - , - - , - - - - ,a---- - ---..