ML19350E527
| ML19350E527 | |
| Person / Time | |
|---|---|
| Issue date: | 03/11/1981 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | |
| Shared Package | |
| ML19350E524 | List: |
| References | |
| ACRS-1842, NUDOCS 8106230230 | |
| Download: ML19350E527 (7) | |
Text
.
.s..
~
EstBFFD ESTFG O
PRIGITY IhSIGMTIM TYP IhSCRIPTI'N 111 5 s L4-2 GLDCA GLCCAWITH LPI LBLOCA GLOCA W1310FF-NOR%L INITIAL
'lA-1 C0t0ITI0'S 15.1/LB-2 IBLOCA/lfiCOER( IBL0rNC0E LTICOER/ WITH HIGi ECAY HEAT LA-2 IBLnCA IBLOCA WIIi DIFEfB C20lT125 FPS 115-1 L9-2/L6-7 TPAGIER
- 10-2TUFSI.E TRIP TRRGIB1T/
ST. LUCIE MB.lPAL CIf0LLATI0t!
C00Un?l EE!T
[9-3+LA-3*
TPRSlEE A'lWS INDUED BY LGS OF FEMAER -
2 TESTS
& pun L2-6 LBLOCA WIli PEPESSUR12ED FLEL LA-4 LBLOCA TEST FOR EPEATA31LITI LA-5 SBLOCA W131 RCPs OEPATIEG @LLOW-m TOL3-6)
L3-3 SBLOCA LD0ED-091 PORV "ACCllM OVdRRIE" lEST La LS-4 TP#SIST R0D WIIiDP#!AL L9-4 TP#SIBE Alls INTHED By LOSS OF 0FFSIE POER LA-6 TPRSIBE LECQHPUJ_5 D BOREN DILUil2!
.LA-7+lA-8 TP#SIENT STEN 1.INE BEA'S (Wili #!D W1310UT 0FFSITE POEfD i
I
- SGEDULE lA-3 IF NEEDED AS A FOLLGi-01 To L9-3
~
810s28o2'30
T REsEARCsPRPNA['Fs[0F1,' TEST'PR0sRdM TEST DESCRIPTION
...)
.'LsRG''
l PRIORITY NOMENCLATURE L-0F-FW, SG DRYOUT, LOCK OPEN PORV, SG REFILL M/H L9{1/L3-3 C00LDOWN ACCIDENTS ST, LUCIE, AND H
L6-7/L9-2 INTERMED, BREAK: ACCUM, LINE, UNC0VERY H
L5-1/L8-2 OPERATIONAL TRANS CONTINGENCY
- M LA-10 D
LB LOCA: PRES, FUEL: L.-0F-0FFSITE: OFFNORM, ICs H
'LA-1/L2-5 INTERMED, BREAK CONTINGENCY
L9-3 S.B. AFTER CODE ASSMENT PROGRESS CONTINGENCY
- M LA-3 ATWS CONTINCENCY*
H LA-3 D
LB LOCA, PRES, FUEL,.L-0F-OFFSITE,. DELAY.ECC'
.H L2-6 N0' TESTS BELOW-
__7LB LOCA, UPPER PLENUM INJ.
H L4-2 S.B. CONFIRM PUMPS ON/0FF RESULTS M
LA-4 l
ANTIC, TRANS ROD w/D L
L6-4 ATWS, L OF 0FFSITE L
L9-4 ANTIC, TRANS: UNCONT, B, DILUTION L
LA-6/L6-6 STEAM LINE BREAK L
LA-7 STEAM LINE BREAK L
LA-8 NOTE:
THE ESTIMATED DATE OF COMPLETION OF ALL TEST' WILL S
PREPLANNED TESTS TO BE RUN ONLY IF REQUIRED, OF THE 4 TESTS, RES ESTIMATES 2 WILL BE NECESSARY.
FM tWE &
~
I
.s n
'/,
LOFT - OPTION 2 (RES REC. PROG. WITil MIN. STAFF SUPPORT DURING STAND-BY)
PROGRAM SUPPORT & EQUIP. MENT (DOLLARS IN MILLIONS)
'82
'83
'84
'85
'86 LOFT PROGRAM TEST OPER. & SUPPORT
$28.2
$19.6 0
0 0
. ANALYSIS & REPORTING 9.6 7.9 2.0 0
0 FUEL PROC. & EXAM.
4.5 1.7 1.2 0
0 ANCILLARY PROJECTS 3.2 4.9 4.1 3.5 3.0 PROJECT CLOSE-0UT 0
5.1 1.0 0
0 TOTAL
$45.5
$39.2
$8.3
$3.5~
$3.0 STAND-BY ACTIVITIES 0
4.5 9.0 4.5 0
DECONTAMINATION &
DECOMMISSIONING 0
0 0
6.5*
3.5" TOTA'L
$45.5
$43.7
$17.3
$14.5
$6.5 g/lFFACILITYREACTIVATED,WOULDCOSTAPP.$24 MOVER 9MOS.
w n1 W
/ 'l
/
l y
Proposed LOFT Test Program in Response to RESISRG Recommendations March 13,1981 A
A Test Targot
. Commitment Date Description i
ID Date Small hot leg break experiment
"* I'"
L3-3/L91 4-15-61 4-22-81 Loss of all foodwater.
Scram on high pressure - delayed l
Raquked test of containment CVleak 6 19-81 7-02-81 Isak Integriff test Simulated turbine trip L6-71L9-2 6-03-21 S-24-81 multiplo failure continuation of L6-7 Intermediate size break (accumulator lino).
L6-1/L8-2 9-25-81 1026-81 Core uncovery at high decay heat level.
10-15-81 11-19-81 F1 conter fuel pressurized l
Replace to 350 pel A2 with F1 through 1241-81 throughit 0582 200% cold leg break at 50 MW to produco the worst probable core j
h L2-s 1 13-s2 2-24 82
,,,i,,,,,y,,,,,,,,,,d,,,,,,,
No fuel damage g
INEL-S-31 108 Y
J m.
w
-+---=r e
w
-aw.--
/
I i
Proposed LOFT Test Program in Response to RESISRG' Recommendations March 13,1981-t i
A A
B B
Proposed Proposed Test Target
~ comm!!mos.i Target commitment 1
ID data date date date Description LA-10 2-24-82 4-14-82 2-24-82 4-14-82 Boron dilution from cold. shutdown I
I L8-3 4-27-82 6-29-82 5-10-82 7-5-82 ATWS-Loss of feedwater iI, L4 0
0 8-07-82 8-9-82 ATWS l
LA-9 7 12-82 6.~82 6-21 82 11-01-82 Smell break intact loop cold leg ECC Injection in downcomer LA-2 0
0 11-22-82 2-07-83 Intermediate break i
i i
8-19-82 11-11-82 12 19-82 3-14-83 Replace F1 with F2 through through through through F2 pressurized bundle
)
9-22-82 12-15-02 1-22-83 4-15-83 l
L2 4 11-12-82 2-14-83 3 14-83 6-15-63 200% cold les break double ended at 50 MW s%
INEL-S-31 107 m
D
/
l l~
,-L e
TABl.E 1, DVERYlEW 0F KEY FINDINGS (it5NRENCIE: USI-Al EVALUATION REPORTS)
I Key Ffndings Overview Study Objective f
Reference Endorsed technical studies contained in Task 4.0 of TAP-A1, reconwended NUR.0-0522. Water Hamer in Staff review of water ha per reviews of experimental data and analytical methods, revisions of REG N9c. ear Fower Plants events, classification of (Juiy1979) problems and reconnendation guldes,etc.
foraction(s).
FWR S.G. feedline water hamer events most damaging.
CAAP-TR-053 (Rev.1)
-l*-
Followup review on water 1.
- . 2.
Flow into void lines, water entrainment in steam line and steam
- j l(ater Hamer Studfes -
!'. i hamer incidents by EG8G.
bubble collapse noted as occurring in safety systems.
.i Judgment made that computer codes for analyzing certain types of I,.
(July 1980) i t4
,.~;
.H,1 * * ' i j
. 3.
,3'i t '*/ ' t,
water hamer events exist, although these codes have not been compared with applicable test data.
4.
Rate of condensation in steam bubble collapse is not easfly determined, and therefore, peak pressure loads from slug inpact is not predictable within current state-of-the-art Water entrainment and vapor bubble collapse can result in poten'tfally.
CAAP-TR-042(Rev.1)
Review and evaluattos, of 1.
actual and potential water.
damaging water hammers.
[.7 Review and Evaluation of
.Y Acttal and Potential Water hamer events (BWR and PWR),
2.
Valve, or flow, instabilities noted as significant problem fn PWR and BWR feedwater systems.
Hamer Events in Nuclear 3.
Recomendations mde for design and operational (including operator Pla ts (September 1979) actions) requirements which would protect nuclear plant against damaging water hanner.
RE-Ji-79-044, A State-of-the-Review current knowledge from 1.
Review of computational methods shows a gap between existing analysts Art Literature Review of experimental and analytical capability and appilcation.
Water Hamer (April 1979) work reported.
2.
Advanced best estimate codes have potential to analyze two-phase watet hamer phenomene.
NUREG/CR-1606, An Evaluation Evaluate potential for 1.
State-of-the-art on condensation heat transfer prevents derivlag a credible scaling criteria.
of Condensation - leduced condensation fnduced water W and CE 5.G. des 19n review resulted in recomendation that each plan Watrr Hanner in Preheat :
ha mer, uttifre 1/8 scale W 2.
l lie reviewed separately and that verification tests be performed,
~
. Steem Generators e
test data.
- (Septenber 1980) f.'
k
~
g q
y
,.y
~'
y
~..
l if TMLE 1 (t:Mitir.ta)
OYE UlIV CF TET Fi n lMG5 (REFEREMCE': U51 Al EVALUATION REPORTS)
-t g
Key Findings Overview Study Objective Results demonstrate applicability of a modified SOLA-PLOOP.
Reference 1.
~ Analysis of rapid (filing hydrodynamics code.Recortnendation made for experimental verifica RE-E-79-C01. An A alysis of volded pfptng systems 2.
Tool fee Preocting tre (Dwa core spray ifne ffiling tool.
i 'I Trams! at Pf r grn efes wasanalyzed).
f Rervlting frw the PJpid Filling of Volded Piping
~
'i Sy* tens (Febrtiary 1979)
Analytical proceedure demonstrated for:~ Sudden check val 1.
- f FE.4-78-013. An Analytical Formulate analytical Simulated BWR core spray line experiencing an instantaneous a.
Prt:edure for Performing procedure to predict b.
structural sequences of valve opening.
Stisctural Analyses of fluid transients in nuclear Nuilear Piping Systems 2.
Findings show significant loads on piping systems Sul fected to fluid pfpfng systems.
Tra isients (February 1979)
Use of K-FIX/ MODI judged inadequate due to treatment of interphase; 1.
RE 4-78-229. An Investigation Investigate steam void heat transfer and mass transfer.
cf the Steam Vold Collapse collapse water hamer Reccmendation made to analyze experimental data with advanced codes 2.
initiating mechanisms.
Ilke TRAC or THERfiIT.
Wa er Hamer Initiating Evsit(February 1919)
RELAPS adapted to model check valve, BWR primary feedwater line 1.
RE %-78-261 (Rev. 2).'An-Analysis tool constructed for transient caiculation performed.
An. lysis Tool for Predicting analyzing fluid transients in Future experimental verification noted as desirable.
2.
Tr. 9sient Hydrodynimics in pfpfng systems having a check valve.
Nuilesr piping Systems Coi taining Swing Check Va ves (September 1979)
Effect of assumed valve opening times (1 versus 5 seconds) has.
1.
EG /CAAP-5733, Supplemental Additional water hamer significant effort. Evaluation of 16 water hansner scenarios judged to Wa er Hamer Analysis and analysis and system review 2.
effort (checkvalveclosure SystemsReview(July 1980) andslugflowinvoidedlines).
unilkely level of occurrence.
s g
sq r
}
1
=
J t
N
.I a
-