ML20056G208
| ML20056G208 | |
| Person / Time | |
|---|---|
| Site: | 05200002 |
| Issue date: | 08/19/1993 |
| From: | Mike Franovich Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9309020247 | |
| Download: ML20056G208 (45) | |
Text
.- . _ __. __ _ _. . . _ _ _ _ _ . . __. ___ _ _ _ ,
pm REGg,
/ t UNITED STATES
[* .. ' Y , . j NUCLEAR REGULATORY COMMISSION - l
, ~! WASHINGTON. D.C. 20555-0001 i
%; v / August 19, 1993 f
Docket No.52-002 [
r APPLICANT: ABB-Combustion Engineering, Inc. (ABB-CE) l PROJECT:- CE System 80+
SUBJECT:
PUBLIC MEETING OF AUGUST 16, 1993, TO DISCUSS CE SYSTEM 80+ .
PROTECTION AGAINST CONTAINMENT BYPASS DURING A STEAM GENERATOR !
TUBE RUPTURE (SGTR) l On August 16, 1993, a public meeting was held at the U.S. Nuclear Regulatory l Commission (NRC) offices in Rockville, Maryland, between representatives of ;
ABB-CE and the NRC. Enclosure 1 provides a list of attendees. Enclosure 2 is :'
the material presented by ABB-CE. The purpose of the meeting was to discuss ~
l potential design alternatives for the CE System 80+ design to prevent SGTR !
- l. containment bypass (draft safety evaluation report Open Item 15.3.8-1). ,
Potential Desian Modifications i
ABB-CE discussed the possibility of installing nitrogen-16 (N-16) monitors in !
the main steamlines in conjunction with automatic primary depressurization i through pressurizer auxiliary sprays. The new control system under evaluation could interface with the turbine bypass and control system and possibly l isolate the faulted steam generator (no feedwater or emergency feedwater).
l
'The current CE System 80+ SGTR strategy is a departure from operating CE
! plants, since feed of a System 80+ faulted steam generator (SG) is continued during the event. ,
Under this design alternative, the new control system could receive an l ,, actuation signal from the N-16 monitors coincident with another signal such as low-pressurizer pressure.
i The staff also noted potential cascade impacts to the emergency procedure l- guidelines, technical specifications, etc., due to new design features and a l revised SGTR coping strategy. Specifically, a new task analysis with the new i indications and controls would need to be performed if ABB-CE were to return to an emergency operations strategy of isolating the faulted SG.
Results of Preliminary Evaluations ABB-CE presented several case studies of various design alternatives to determine the time to main steam safety valve (MSSV) lift. Six cases were studied assuming multiple tube. ruptures (5 tubes). Enclosure 2 contains the transient analyses and results for various design alternatives. The six cases assumed no operator action and included a baseline case (current design) and design alternatives such as automatic pressurizer spray, automatic pressurizer vent, and automatic isolation of the faulted SG using an N-16 signal.
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9309020247 95o819 2-~
PDR ADOCK 0520 bN MY$ EY
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2 August 19, 1993 i
The staff expressed concerns that the multiple tube rupture assumption may not be bounding for a single SGiR. The staff noted that injection of all four .
safety injection pumps for a single SGTR may reduce the time for the pressur- l izer to go solid and negate primary pressure control' from the pressurizer i auxiliary spray. Under low reactor coolant system activity levels, operators !
might be faced with diagnosing the SGTR with a high-pressurizer level indica-i tion and low secondary _ activity.
t The results of the ABB-CE preliminary evaluation indicate that the use of the l- N-16 monitors (or other sensing devices) to lower the turbine bypass setting, isolate the faulted steam generator, and initiate pressurizer auxiliary spray could prevent a challenge to the SG safeties for a 5 tube SGTR. ,
The following commitments were made during the meeting:
(1) ABB-CE will run the. base-case evaluation (without operator action) for a i single tube SGTR. !
(2) In parallel with the work above, ABB-CE will evaluate the engineering ',
l required to install a control system that would achieve the desired L objective of preventing MSSV lift.
! (3) ABB-CE will evaluate the potential negative impacts of such a control ,
system (when the system operates and when it should not operate) so the i l installation of the new system does not introduce substantial new chal-
-lenges. l l (4) For low-power operations, . CE will evaluate the potential use of noble
- gas monitors since N-16 prowetion is negligible.
ABB-CE indicated they will respond within two weeks and have discussions with the Reactor Systems Branch during the interim as results become available.
(Original signed by)
, Michael X. Franovich, Project Manager Standardization Project Directorate l Associate Directorate for Advanced Reactors l and License Renewal Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosures:
See next page i DISTRIBUTION:
See next page
- SEE PREVIOUS CONCURRENCE i
'$ /
OFC: LA:PDST:ADAR SC:SRXB:DSSA PM . . AR SC:PDST:ADAR l NAME: PShe 6/ G MRubin* MX 11 'o ich:tz DATE: 08// 91 08/18/93 08/19/93 TEssig%p 03//l/93 0FFICIAL RECOR COPY: DOCUMENT NAME: MSUM0816.HXF
. ._ ._ . _ , . . - ._.._ __ ,._.- .._-_._4
ABB-Combustion Engineering, Inc. Docket No.52-002 cc: Mr. C. B. Brinkman, Acting Director Nuclear Systems Licensing ABB-Combustion Engineering, Inc.
1000 Prospect Hill Road Windsor, Connecticut 06095-0500 Mr. C. B. Brinkman, Manager Washington Nuclear Operations ABB-Combustion Engineering, Inc.
12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Stan Ritterbusch Nuclear Systems Licensing ABB-Combustion Engineering, Inc.
1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 Mr. Sterling Franks .
U.S. Department of Energy NE-42 Washington, D.C. 20585 Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.
Washington, D.C. 20503 Mr. Raymond Ng 1776 Eye Street, N.W.
Suite 300 Washington, D.C. 20006
,_ , Joseph R. Egan, Esquire Shaw, Pittman, PottS & Trowbridge 2300 N Street, N.W.
Washington, D.C. 20037-1128 Mr. Regis A. Matzie, Vice President Nuclear Systems Development ABB-Combustion Engineering, Inc.
1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 L
. l l
August 19, 1993 DISTRIBUTION w/ enclosures:
Docket File PDST R/F DCrutchfield WTravers PDR MFranovich RPerch, 8H7 PShea SMagruder TEssig DISTRIBUTION w/o enclosures:
i TMurley/FMiraglia,12G18 RBorchardt JMoore, 15B18 EJordan, MNBB3701 WRussell, 12G18 RJones, 8E23 MRubin, 8E23 SSun, 8E23 GGrant, 17G21 DDiec, 8E23 TKenyon JStrosnider, 7D4 NSaltos, 10E4 AEl-Bassioni, 10E4 AThadani, BE2 WBeckner, 10E4 RPalla, 10E4 ACRS (11) BLiaw, 7026 TWambach MMiller, 8F21
- 1 i
i l
i I
1 ABB-CE SYSTE.%180+
Reactor Systems afecting August 16,1993 Rockville, 51aryland NAME ORGANIZATION M. Rubin NRC/DSSA/SRXB M. Franovich NRR/PDST S. B. Sun NRC/NRR/SRXB A. El-Bassioni NRC/NRR/DSSA M. Miller NRC/DSSA/SRXB W. Beckner NRC/DSSA/SPSB J. Strosnider NRC/DE/EMCB B. D. Liaw NRC/NRR/DE R. Jones NRC/NRR/DSSA/SRXB .
T. Murley NRC/NRR T. Wambach NRC/NRR/ADAR/PDST A. Thadani NRC/NRR W. Russell NRC/NRR R. W. Borchardt NRC/NRR/ADAR/PDST R. Palla NRC/NRR/DSSA/SPSB l N. Saltos NRC/NRR/DSSA/SPSB J. Longo ABB-CE S. Ritterbusch ABB-CE F. L. Carpentino ABB-CE T. Rudek ABB-CE i R. A. Matzie ABB-CE
.. . C.Lewe NUS I
i Enclosure 1 v ,
. __ . - _ _ _ - _ _ _ _ - _ _1
)
o i
SGTR... Containment Bypass Meeting August 16, 1993 ABB-CE's Performance Evaluation of Potential Methods of Mitigation of ,
Multiple Steam Generator Tube Ruptures I
1 l
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Enclosure 2
i PARAMETERS AFFECTING CONTAINMENT BYPASS RESULTS (ARISING THROUGH SGTR) i
. NUMBER OF TUBES RUPTURED :
MAIN STEAM ISOLATION SYSTEM PRESSURIZER AUXILIARY SPRAY SYSTEM f
REACTOR COOLANT GAS VENT SYSTEM !
ATMOSPHERIC DUMP VALVE SYSTEM
~ ~
HIGH PRESSURE SAFETY INJECTION SYSTEM TURBINE BYPASS CONTROL SYSTEM MAIN STEAM SAFETY VALVES SYSTEM b
.,,,-,,,--.-,,_.?.:.,..-,-,.., -
~
t MULTIPLE SGTR EVALUATION W/P0TENTIAL DESIGN CHANGES FIVE RUPTURED TUBES
' AUTO SIAS & AUTO AUTO MANUAL TBCS & PZR PZR AUTO HPSI CASE # MSIS SPRAY VENT ADY SHUT 0FF RESULTS 1 YES NO NO NO NO MSSV 0 1000 SEC ,
(REF) 2 YES YES N0 NO NO MSSV 0 1200 SEC 3 YES N0 YES NO NO MSSV 0 1200 SEC 4 YES N0 YES NO YES MSSV 0 1300 SEC
, 5 YES NO N0 YES NO INCREASED LEAK FLOW
- (
E
a MULTIPLE SSTR EVALUATION W/ POTENTIAL _ DESIGN CHANGES FIVE RUPTURED TUBES N-16 AUTO N-16 AUTO TERMINATE AUTO ISOLATE AFW TO SIAS & RUPTURED SG RUPTURED SG CASE # TBCS RESULTS 6 YES YES YES MSSV 0 900 SEC i
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j CASE 1
~
SEQUENCE TUBE RUPTURE OF( 5EVENTSTUBES IN ONE FORSTEAM A MULTIPLE GENERATOR, S TUBES IN OTHER STEAM GENERATOR)
Setnoint ,
Event Time (sec1 Tube Rupture Occurs 0.0 --
Tsat Trip Signal Generated 154 ---
Turbine Trip 155 1835 Pressurizer Pressure Reaches Safety Injection Actuation ,
165 Signal Analysis Setpoint, psia Pressurizer Drains 181 98% WR Steam Generator reaches MSIS High SG Level Serpoint 1030 1200 ,
Main Steam Isolation Valves Close / Main Steam Safety 1040 Valves Lift, psia (Pressurizer never fills to 100%)
i Case #1... Baseline Case #2... Auto Pzr Spray Case #3... Auto Pzr Vent Case 14... Auto Pzr Vent w/ HPSI Shutoff Case #5... Auto ADVs r
Case #6... Auto Isolation of Ruptured SG I
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CASE 2 SEQUENCE OF EVENTS FOR A MULTIPLE STEAM GENERATOR TUBE RUPTURE ( 5 TUBES IN ONE STEAM GENERATOR, NO TUBES IN OTHER STEAM GENERATOR) ;
l i
Time (sec) Event Setnoint l 0.0 Tube Rupture Occurs --- !
154 Tsat Trip Signal Generated ---
155 Turbine Trip ---
165 Pressurizer Pressure Reaches Safety Injection Actuation 1835 1 Signal Analysis Setpoint, psia ,
l 181 Pressurizer Drains l 460 Pressurizer Fills to 100% --
)
1170 Steam Generator reaches MSIS High SG Level Setpoint 98% WR l 1180 Main Steam Isolation Valves Close / Main Steam Safety 1200 Valves Lift, psia Case #1... Baseline Case #2... Auto Pzr Spray Case #3... Auto Pzr Vent 3 l
Case #4... Auto Pzr Vent w/ HPSI Shutoff Case #5...Autg ADVa__
Case #6... Auto Isolation I of Ruptured SG
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CASE 3 SEQUENCE OF EVENTS FOR A MULTIPLE STEAM GENERATOR TUBE RUPTURE ( 5 TUBES IN ONE STEAM GENERATOR, NO TUBES IN OTHER STEAM GENERATOR)
Event Setnoint Time 6ec) 0.0 Tube Rupture Occurs 154 Tsat Trip Signal Generated l l
155 Turbine Trip ---
Pressurizer Pressure Reaches Safety injection Actuation 1835 165 Signal Analysis Setpoint, psia 191 Pressurizer Drains 1240 Steam Generator reaches MSIS High SG Level Setpoint 98% WR 1250 Main Steam Isolation Valves Close / Main Steam Safety 1200 Valves Lift, psia 1300 Pressurizer Fills to 100% ---
Case #1... Baseline Case #2... Auto Pzr Spray l l
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Case #3... Auto Pzr Vent i
Case #4... Auto Pzr Vent i w/ HPSI Shutoff ; {
Case #5... Auto ADVs _
Case #6... Auto Isolation of Ruptured SG o ,
3 SYSTEM 80+ MULTIPLE SGTR S TUDES IN ONE SG - PRESSURIZER VENT ON SIAS 2500
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CASE 4 SEQUENCE OF EVENTS FOR A MULTIPLE STEAM GENERATOR TUBE RUPTURE ( 5 TUBES IN ONE STEAM GENERATOR, NO TUBES IN OTHER STEAM GENERATOR)
Event Setpoint Time (sec) 0.0 Tube Rupture Occurs ---
154 Tsat Trip Signal Generated --
155 Turbine Trip -
165 Pressurizer Pressure Reaches Safety Injection Actuation 1835 Signal Analysis Setpoint, psia 191 Pressurizer Drains -
- 1280 Steam Generator reaches MSIS High SG 1.evel Setpoint 98% WR 1290 Main Steam Isolation Valves Close / Main Steam Safety 1200 Valves Lift, psia 1300 Pressurizer Fills to 100% -
i I
Case #1... Baseline Case #2... Auto Pzr Spray Case #3... Auto Pzr Vent Case #4... Auto Pzr Vent w/ HPSI Shutoff Case #5... Auto'~7EDVs -
Case #6... Auto Isolation of Ruptured SG 3 l
4 e
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l CASE 5 SEQUENCE OF EVENTS FOR A MULTIPLE STEAM GENERATOR TUBE RUPTURE ( 5 TUBES IN ONE STEAM GENERATOR, NO TUBES IN OTHER STEAM GENERATOR) i 1
Time (sec) Event Setpoint 0.0 Tube Rupture Occurs ---
154 Tsat Trip Signal Generated ---
155 Turbine Trip ---
l 165 Pressurizer Prcssure Reaches Safety Injection Actuation 1835 Signal Analysis Setpoint, psia 181 Pressurizer Drains ---
- Steam Generator reaches MSIS High SG I.evel Setpoint 98% WR
-- Main Steam Isolation Valves Close / Main Steam Safety 1200 Valves Lift, psia 4640 Pressurizer Fills to 100% ---
l l
Case #1... Baseline Case #2... Auto Pzr Spray Case #3... Auto Pzr Vent I
Case #4... Auto Pzr Vent , ,
w/ HPSI Shutoff !
)
Case #5. . . Aute ADVs - _
1 Case #6... Auto Isolation ,
of Ruptured SG I
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. 1 CASE 6 l SEQUENCE OF EVENTS FOR A MULTIPLE STEAM GENERATOR l TUBE RUPTURE ( 5 TUBES IN ONE STEAM GENERATOR, NO TUBES IN OTHER STEAM GENERATOR)
Time (sec) Event Setnoint 0.0 Tube Rupture Occurs -
154 Tsat Trip Signal Generated --
155 Turbine Trip ---
165 Pressurizer Pressure Reaches Safety Injection Actuation IS35 Signal Analysis Setpoint, psia ,
191 Pressurizer Drains --
~
880 Steam Generator reaches MSIS High SG Level Setpoint 98% WR 890 Main Steam Isolation Valves Close / Main Steam Safety 1200 Valves Lift, psia
> 3600 Pressurizer Fills to 100% ---
Case #1... Baseline Case #2... Auto P r Spray Case #3... Auto P:r Vent l
Case #4... Auto P r Vent w/ HPSI Shutoff Case #5... Auto ADVs Case #6... Auto Isolation of Ruptured SG i l
i
i SYSTEM 80+ MULTIPLE SGTR S TUBES - N16 AUTO ISOLATE AFFECTED SG .
2500 2000 .
m -_
S.1500 -
B 13
$ 1000 -
D e
500 -
0 0 2 4 6 8 10 12 lI.
Thousands TIME (SEC) i a.. .
c.
SYSTEM 80+ MULTIPLE SGTR S TUDES - N16 AUTO ISOLATE AFFEcrED so .
90 80 -
70 -
60 -
LT Im 50 -
t13 d 40 tt j 30 s
- 20 l
10 -
J 0 r +
f 0 2 4 6 8 10 12 Thousands J .
TIME (SEC) i i
e I
1 SYSTEM 80+ MULTIPLE SGTR S TUBES - N16 AUTO ISOLATE AFFECTED SG .
2500 2000 -
E e
@ 1500 0
$ I
> w n4 W n m %%v s
f1000 8
hi e
O 500 - 1.
0 I. 2 4 6 8 I O 10 12 Thousands TIME (SEC) l i
-_9 .
i SYSTEM 80+ MULTIPLE SGTR S TUBES - N16 AUTO ISOLATE AFFECTED SG 2500 2000 -
G
- 3. m Q1500 O 1000 d
- m
$ 500 -
0 l,l I 2 4 6 8 10 12 O
l! Thousands TIME (SEC) i il t
E c.
SYSTEM 80+ MULTIPLE SGTR S TUI3ES - N16 AUTO ISOLATE AFFECTED SG .
2500 i.
+
$ 1500 -
8 6
1000 -
o i d 500 y -
5 . _ _ _ . .. .. ..
1
--500 '
l l[ 0 2 4 6 8 10 12
! Thousands TIME (SEC) 1 g l
4
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