ML19224B782
| ML19224B782 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/10/1979 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-SM-0115, ACRS-SM-115, NUDOCS 7906220322 | |
| Download: ML19224B782 (23) | |
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A C R S S n - o ll5 b2'f/f FRALEY/ car 5/10/79 RECE VED PRV05EDASSIGtMNTSANDPRIORITIESi83U50
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T:lE It', PLICATION 5 Of THE TMI-2 ACCIDENT t.' S. P;'in r.'.a rrn cr vj
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Arrangement of Primary System 2.
Perfomance of Pressure Relief-Safety Valves 3.
RHR System 4.
Isolation of Containment 5.
Design of Auxiliary Building 6.
Design of Radwaste Transfer System 7.
Containment Design 8.
Additional Instrumentation S.
Design of ECCS and Residual !! eat P,emoval Systems 10.
Maintenance QA
- 11. Operator Training 12.
Picnt lunagement Structure
- 13. Control Room Hu:un Engineering 14.
Transient Analysis
- 15. Specifics of TMI-2 Accident 16.
Energency Planning 17.
Design Criteria / Contingency Design Measures
- 18. Administration / Regulation 19.
Reactor Safety Research 20.
Siting Policy and Practices 21.
Electrical Power Supplies oGb.
2i' 7906220T4?2
g PRIORITY DEFINITION A-A report provided to the ACRS within 3 months B - A report should be providcd to the ACRS by 12/19/79 f
'uld be provided to the ACR3 ASAP con-C - A report sistent with uevelopments in the field.
Note: The report to the ACRS should not be a status report but should include specific recommendations for resolution of the item and a specific schedule for impleraenta tion.
Consideration should be given to the priorities for plants in operation, under construction, being designed.
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TOPIC: Arrangtment of Primary System Spec _ific Tasks a.
relative elevation of reactor PV, steam generator, and pressurizer b.
loop seal in pressurizer surge line c.
problems associated with caridy-cane and vertical vs.
horizontal U-tubes in PWR steara generators d.
Remotely Operated vent valves on high points in system Assigranen+
Subcommittee on Plant Arrangements:
BENDER, Ebersole, Lawrcski, })kt[, Plesset, Ray, LEtheringto_/
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Priority A (as related to existing plants which may require special operator training, instrumentEtion, etc. to understand / control the thermal-hydraulic characteristics and performance during transients, accidents, etc.
B (matters related to plants under construction)
C (matters related to the design of the next generation of nuclear plants) 254 333 4
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a
- 2) TOPIC:
Performance of Pressure Relief-Safety Valves Specifi_c Tasks a.
qualified for severe service (e.g., release of steam / water mix.tures) b.
reliability of operation valve stem position indication (see Topic 8c) c.
Assiennent Subconnittee on Metal Comp.onents:
S H Eh'M0'I s Bender, Etherington, Okrent Priority A (Task a)
B (Task b)
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- 3) TOPIC:
RHR System Spycific tasks a.
how long will it run without maintenance, etc.
b.
provisions for maintenance (e.g., shielding, lubrication c.
provisions ta handle radioactive leakage (e.g., contain-nent/ confinement Assi_pnment Subcomnittee on '!11-2 Implications:
OKRENT, Carbon, Mark, Plesset, Siess, Kerr Priority B (Tasks a, b, and c) 2bk
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. i f, ) TOPIC:
Isolation of Containment Specific Tash a.
basis for isolation (e.g., rad alana, high press, etc.)
b.
Class A/ Class B isolation Assignmcot Subcon.mittee on Tl:1-2 Implications:
OKREf1T, Carbon, fbrk, Plesset, Sicss, Kerr
- Priority, A(Taska)
G (Task b) h 4
254 336
- 5) TOPIC:
Design of Auxiliary Building Sfe_Ci.fi_C. Ta e,ks_
a.
containment vs. confinement b.
Replaccaent of radioactive graphite filters Assign 3rd.
Subcc.Tmittee on TllI-2 Ir.:Plications:
OKREj.T_, Carbon, fiack, Plesset, Siess, Kerr
- Priority, B/C W ""
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G) TOPIC:
Design of Pad',laste transfer System S_pecific tn s a.
Isolation on high rad levels b.
I'3x. pressure / capacity of pumps vs. storage tank design
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Assignment Subcommittee on Maste !!anagcment:
l'0ELLER, C'.(L a, Kerr, Lawroski, liark. fiathis, Plesset f
l Priority A(Taska)
B (Task b)
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254 339
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- 7) TOPI C,:
Containment Design Specific Tasts a.
ability to withstand flooding.
b.
Remote containment flooding adequate shielding to penait continued neari>y c.
activities (e.g., hook-up emergency equipment, replace depleted equipment, take samples, operate nearby plants, etc.
and recovery cperctinns) d) ability to contain all postulated accident e) vented containment As s igr. men t :
Sulcommittee on TMI-2 Implications:
OKRENT, Carbo.1, Mark, Plesset, Siess, Kerr s
Priority
/s = item a and b C = item c C
item d and e s
254 3389
c.
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a
- 8) TOPIC: Additional Instr
. tion Specific Items a.
Containment wTter level b.
prompt nonitoring of primary coolant c.
position indication on relief / safety valves d.
core level sensors (e.g. fast / slo <, neutron ratios anc h-rayintensities,waterleveldpindicator,etc.)
e.
flow indication in all -PCS legs for normal and abnormal (e.g., natural circulation) conditions f.
other instruments to follow the course of an accident g.
status indication / interlocking of all safety systems h.
core outlet +hcrrocouples 1.
instrur..entation to detect boiling Assignment Subcommittee on Power and Electrical Systems KERR, Ebersole,.
this, Okrent, Ray Priority.
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254 3?q9
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- 9) TOPIC:
Design of ECCS and Residual iteat Removal Systems Specific Tasks a.
high pressure vs. low pressure r
Assignment:
Subcommittee on TMI-2 Implications:
OKREfiT, Carbon, Mar, Plesset, fiess, Kerr Priority B
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- 10) TOPIC: !bintenance QA Specific Tasks a.
Securing and realignment of systems for maintainence testing F
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Assignment:
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Subcccaittee on Reactor Operations:
ETHERIt'GTO ', Ebersole, l'athis, Okrent, Ray a
h Priority A
m 254 341
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- 11) TOPIC: Operator Training Specific Tasks c.
abnormal as well as normal and anticipated events b.
initial qualification (e.g., grade needed to qualify) and requalification c.
Educational or experience level required practice / procedures for infrequent but expected operations (e.g., shift to natural
- circulation) c.
How does one station / utility ccmpare to others f.
Authority / provisions to delay / override safety functions (e.g., secure HPSI)
Assignment Subcommittee on Reactor Operations:
ETHERI!:GTON, Ebersole, Mathis, Moeller, Okrent, Ray Priority A (Items a, b, and c}+ -
)
B (Items d and c)
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254 3d
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- 12) TOPIC:
Plant Management Structure
,S_ge_c_i fi c Ta s ks a.
engineering / operations interface b.
evaluation and resolution of LER's (e.g., i.ow much backfit and retraining is do7e) c.
should operating shift include a Senior Operator in the control room at all times Assignment Subco=nittee cn Reactor Operations ETiiERII;GTON, Ebersole, Mathis, Ray, Okrent, Moeller Priority B
s 254 3All'Y
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- 13) TOPIC:
Control Room liuman Engineering Sp_e_cific Tasks a.
need for systcm mimics b.
better aids such as steam tables, A T indications, one-line diagrams, startup and operating checklists, technical data books, complete set of drawings, etc.
c.
better display of important monitors, alarms d.
use of computer assist to operator short term - ?
long term - monitor status / position of important components / valves Assignment Subcommittee on Reactor Operations:
ETl!ERINGTON, Ebersole, Mathis, Moeller, Okrent, Ray Priority A (Tasks a and b)
B (Tasks c and e)
C(Taskd) s 25A 3466 r
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- 14) TOPIC-Transient Analysis Specific Tasks analysis of very small break accidents a.
b.
Scenarios of accidents that include operating procedures as actually written with inclusion of operator errors, faultyequipment[instrumentperformance,etc.
c) Analy,is of accident scenarios including core dainage, interaction of primary (secondary) systems d) Natural circulation for normal and abnormal condit'cns e) Anticipatory trip on secondary plant signals Assignment ECCS Subcommittee:
PLESSET, Ebersole, Ethcrington, Okrent F'riority A (Tasks a and d)
A/B (Task b) 3 (Task c) 254 346 s
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- 15) TOPIC:
Specifics of TMI-2 Accident Specific Tasks a.
complete chronology for first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> b.
status of TMI-2 c.
recovery of TMI-2 d.
Proposed changes in TMI-2 (assuming c is successful) e.
specific features of TMI-2 design which contributed to the accident (e.g., inventory of once through steam generators, interaction of primary / secondary system, performance of ICS, design of auxiliary feed system, arrangement of primary system (e.g., candy-cane, surge lineloopseal),etc.)
Assignment Tasks a, b, and d = Subccmmittee on TMI-2:
ETHERI!lGTO.'!, Bender, Kerr, Lawroski, Moeller, Okrent, Siess Task c = Subcommittee on Radiological Effects and Site Evaluation revised as noted:
MOELLER, Lawreski, Okrent,bhewmon, Etherington, Kerr]
9 NkMs Prior 1ty A (Tasks a and b)<
d L )
B (Task c)
C(issk[)
254 3461 7.-
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- 16) _TOPI C :
Emergency Planning Specific Tasks _
a.
e;aergency p.otedures (e.g., are state plans adequate) b.
technical competence of emergency team (e.g., utility rcle/liRC role / vendor role) c.
connunications (e.g. ac.ong phnt-tech, support team -
f!RC - state cuthorities) d.
standby ercergency equipu nt e.
offsite monitoring f.
provisions for incident evaluatien (e.g., storage cnd recovery of vital data)
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Assigr.nent:
Subco:=1ittee on Rad. Effects and Site Evaluation:
linELLEP., Dlbrf le, Lattroski, Ok; cnt, Ray, Lliathis/
s Priority A/B (Tasks a, b, c) e d' '
C (Taskdir>edL b 254
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- 17) TOPI C_: Design Criteria / Contingency Design fteasures Sp_ecific Tasks a.
freq'lency of challenges of safety system b.
single failure criteria c.
use of shared facilities d.
environmental qualification of non-safety grade but S
vital process and auxiliary equipment.
d.
station blackout f.
adequacy of D.C. power supplies g.
system interactions h.
water ham.Ter i.
provisions to preclude sabotage j.
Other generic items applicable to operating reactors, reactors under construction, being designed k.
Other design features to reduce the probability cf accidents (e.g., plant simolification, improved materials, separation of control and safety systems 1.
other design features to reduce the consequences of accidents (e.g., improved separation of barriers) m.
do standardized plants inhibit safety improvements n.
ATWS o.
environmental qualification of safety system controls, cooling water, etc.
A sienment:
l Subcommittee on Tril-2 Implications:
pD!Ef1T, Carbon, liark, Plesset, Siens, Kerr P i o ri ty_
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- 10) T0 fir.: Administration /Reculation Specific Ja s ks regulatory process (scope of NRC review) a.
b.
ACRS role c.
role of.;RC inspectors d.
operator training and qualificatior.
e.
evaluation and application of operating experience f.
dcoth of knowledge in NRC staff (e.g., chemistry, hardware, plantbehavior,other) 9 liRC responsibilities /procec'ures during emergencies h.
NRC-state relationr for emergencies 1.
use of probabilistic vs. deterministic criteria / evaluation (consider multiple human errors, etc.)
Assignment ACRS Procedures Subcommittee CARB0", Pender, Kerr, Lawroski, isceller, Okrent, Plesset, Siess Pri~orities B
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- 19) TOPIC:
Reactor Safety Research e
Synecific Tu t' a.
H /02 generation under accident conditions 2
b.
added c:,phasis on small/very small breaks WI-2 recovery ogsle. be%c.c c.
d.
Improved s-fety systems (e.g., vented containment)
Assign:ent Subcc:r;nituee on Reactor Safety Rei, arch:
OKRENT, Bender, Etherington, Kerr, Mark, Moeller,
'lesset, Sheunon Priarity A(Taska)
B (Tasks b, c, and d)
CB nw.
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- 26) TOPIC: Siting policy and practices Syecific Tasks a.
use of distance vs. engineering safety features b.
ability to evacuate, practice evacuations, etc.
hydrological conditions taking into account core melt c.
As sign:r.ent Su!'cen.:aittee en Radiation Effects and Site Evaluation
[';0ELLER, Ebersole, Lawroski, Okrent Priority C
254 352.
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- 21) TOPIC:
Electrical Power Supplies Specific Tasks adequacy of offsite po'.ier supplies (e.g., reliability, a.
thennai adequacy, diversity) b.
stability following an accident (e.g., loss of major nuclear generating station) energency power to pressurizer hcaters c.
Assionment Subccamittee on Power and Electrical Systems =
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KERR, Ebersole, liark, !1athis, C,[(rb
, Ray Priority B (Tasks a and b)
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