ML20030D629
| ML20030D629 | |
| Person / Time | |
|---|---|
| Issue date: | 09/02/1981 |
| From: | NRC COMMISSION (OCM) |
| To: | |
| Shared Package | |
| ML20030D627 | List: |
| References | |
| REF-10CFR9.7 NUDOCS 8109140064 | |
| Download: ML20030D629 (28) | |
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PLANFORPRIORITIZATIONANDRESQLUTIONOFGENERICITEMS COMillSS10ll BRIEFING SEPTEMBER 2, 1981 l
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PLAN FOR PRIORITIZATION AND RESOLUTION OF GENERIC ITEMS
>,3 k: kOMMISSIONORIEFING I
I.
BACKGROUND I
II.
SCOPE'0F GENERIC SAFETY ISSUES UNRESOLVED SAFETY ISSUES (USI)
TMI ACTION PLAN TASKS OTNER GENERIC ISSUES III.
SOURCES OF flew SAFETY ISSUES IV.
PLAN FOR PRIORITIZING SAFETY ISSUE 5 V.
EXAMPLES OF PRIORITIZING VI.
CURRENT AND PLANNED STAFF ASSESSMENTS I
p.
' i. E. MURLEY SEPTEMBER 2, 1981 se
PLAN FOR IDENTIFYING AND PRI RITIZING SAFETY ISSUES
- 4 THIS IS A METHOD FOR
- '
V/
(1)
IDENTIFYING NEW SAFETY ISSUES 1
(2)
DECIDING 110W TO ALLOCATE STAFF RESOUfCES TO RESOLVE SAFETY ISSUES (3)
TRACKING ALL SAFETY ISSUES AND F10NITORING PROGRESS 0
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- W e
.s MAJOR NRR ACTIVITIES q
ACTIVITY
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TRACKING SYSTEM METil0D OF CONTROL CASEWORK BEVILL REPORT SRP r
0PERATING REACTOR ISSUES TMI-ITEMS 0RLAS COMMISSION APPROVAL (NUREG 0737)
NON-IMI ITEMS ORLAS MANAGEMENT CONTROL, DST REVIEW.
SYSTEMATIC EVALUATION PROGRAM NUREG Oll85 BEING DEVELOPED (ACRS 8 COMMISSION REVIEW)
UNRESOLVED SAFETY ISSUES NUREG 0606 COMMISSION APPROVAL., REPORT TO CONGRESS GENERIC SAFETY ISSUES TMI ITEMS APTS DST REVIEW NON-TMI ITEMS GITS DST REVIEW a..
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Ul: RESOLVED SAFETY !sSilES t
"A MATTER AFFECTING A NU.MBER OF HUCLEAR POWER PLANTS TilAT POSES IMPORTANT GUESTIONS CONCERNING Tile ADEQ k 0F. EXISTING SAFETY REQUIREMENTS FOR WHICH A FINAL RESOLUTION ilAS NOT YET BEEN DEVELOPED AND TilAT INVOLVES CONDITIONS NOT LIKElY TO BE ACCEPTABLE OVER Tile LIFETIME OF Tile PLANTS AFFECTS."
i DESIGilATED BY COMMISSION, BAS $D ON RECOMMENDA,TIONS OF STAFF AND ACRS.
STATUS REPORTED TO C014GRESS IN ANNUAL REPORTS (IN ACCORDANCE WITil SECTION 210 ENERGY REORGANIZATION ACT)
STATUS UPDATED QUARTERLY FOR' MANAGEMENT IN " AQUA BOOK" - NOREG-0606 26 USIS DESIGNATED TilUS FAR 22 DESIGNATED IN FY 1978 lj DESIGNATED IN FY 1980 AS OF AUGUST 15,.1981:
1 RESOLVED AND IMPLEMEllTATION COMPLETE 10 TECilNICALLY RESOLVED AND BEING IMPLEMENTED 15 RESOLUTION UNDER DEVELOPMENT 5 0F THESE SCllEDULED FOR COMPLETION IN FY'1982 il 0F Tilf ~ SCllEDULED FOR COMPLETI0fl IN FY 1983
' ~
11 0F THESE ScilEDULED FOR COMPLETION IN FY 198'l 2 0F THESE' SCHEDULED FOR COMPLETION IN FY 1905
GENERIC ISSUES A.
TMI ACTION PLAN GENERIC ITEMS
--NRRRESPONSIBLEFORD$kLOPINGTECilNICALPOSITIONSANDIMPLEMENTINGGENERIC ISSUES IDEllTIFIED IN ACTION PLAN AS RESULT OF Tile TMI ACCIDENT
-- 135 APPROVED FOR IMPLEMENTATION IN FY 1981
-- APPROXIMATELY 90 ISSUES STILL REQUIRE DEVELOPMENT I
-- MOST WORK WILL FOCUS ON PRidRITY l ITEMS IN FY 1982
-- MOST WORK ON PRIORITY 2 & 3 ITEMS DEFERRED TO FY 1983
-- STATUS UPDATED QUARTERLY IN ACTIort. PLAN TRACKING SYSTEM (APTS)
B.
OTHER GENERIC ISSUES
-- CATEGORIES A, B, C AND D GENERIC ISSUES IDEN IFIED BY Tile NRR STAFF IN 1977 AND DOCUMENTED IN HUREG-0410
-- STATUS MILL BE REPORTED IN THE GENERIC ISSUES TRACKING SYSTEM (GITS) TO BE UPDATED QUARTERLY
-- Tile EFFORT TO ESTABLISil A PRIORITY RANKING 'F,0R ALL SAFETY ISSUES REPORTED IN GITS HAS'BEEN INITIATED.
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- _ - _ = _. -
G5NERIC ISSUs BREAKDOWN c4
'O USIS 35 I
SAFETY ISSUES 52 I
ENVIRONMENTAL ISSUES 17' LICENSING IMPROVEMENT. ITEMS 38 TOTAL lil2 I
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STATUS 'OF GENERIC SAFETY ISSUES 60
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50 ~
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RESOLVED 40 -
i, ACTIVE 20 e
'I 10 - -
INACTIVE
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. JULY JANUARY i
1981 1981 t
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CURRENT STATUS ~0F GE.NERic SAFETY ISSUES
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15 ACTIVE INACTIVE 16 i
TECHNICALLY RESOLVED 19 IMPLEMENTATION COMPLETE 10 6
IMPLEMENTATION IN PROGRESS 3
IMPLEMENTATION Il0T STARTED s
SUPERCEDED 2
TOTAL 52 9
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-s DEVELOPMENT AilD IMPLEMENTATION OF REGULATORY REQUIREMENTS t,f IDENTIFICATION
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DEVELOP POSITIONS l.
-IIEW CONCERNS I
PRIORITIZE AND 2.
CURRENT ISSUES IMPLEMENTATION PLANS 3
APPROVED REQUIREMENTS i
Y I
PREPARr OBTAIN ISSUE VERIFY FORMAL
- PUBLic,
. APP'OVED 4
IMPLEMENTATION
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R CHANGE ACRS DOCUMENTS COMMENTS REQUIREMENTS BY AUDIT J
- t 4
- 4
..g EXAMPLES OF' SOURCE OF REQUIREMENT REGULATIP',S TMIACTONPid STAFF REVIEWS SEP REVIEW I
ACRS ISSUES AE0D ISSUES-IE BULLETINS llCENSING AND APPEAL BOARD ISSUES INTERVENOR ISSUES IREP, NREP AND OTHER PRA ANALYSES RESEARCH RESULTS REG. GUIDES E
OPERATING EXPERIENCE 9
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EXAMPLES OF PROPOSED HEW REQUIREMENT "PRESENTLYTHEREISNORE,0p'EMENTTODOASCRAMTESTJUSTPRIORTORODWITH-R DRAWAL IN THE APPROACS TO d'RITICALITY...NRC SHOULD ESTABLISH A REQUIREMENT
~
THATJUSTPRIORTOANAPPROACHTOCRITICAL,LICENSEESWITHDRAWORPARTIALLY WITHDRAW AND THEN SCRAM SOME RODS BEFORE EACH APPROACH."
"(ADDITIONAL)TE3TSSHOULDBEPERFURMEDAfSACONFIRMATIONTHATTHEELECTRICAL FEATURES WORK...ALL COMBINATIONS OF COINCIDENCE FEATURES OF EACH TRIP SIGNAL
~
SHOULD BE CHECKED ALONG WITH CONFIRMATION THAT FOR PWRS THE TRIP BREAKERS OPEN TO INTERRUPT CURRENT TO ROD HOLDING COILS AND FOR BWRS THAT SCRAM VALVES OPERATE."
BENEFIT - INCREASED ASSURANCE THAT' SYSTEM NOT DEFEATED DURING SHUTDOWN COST
- DELAY STARTUP SEVERAL HOURS MAY INCREASE WEAR-0UT AND FAILURE RATES I
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- _. -. - _ = - _ --
PRIORITIZATION METHOD 9
c.i PRIORITIES WILL B,E'geSTABLISHED BY MANAGEMENT USING TECHNICAL JUDGMENT AND AUGMENTED BY PROBABILISTIC RISK' ANALYSIS METHODS WHERE APPROPRIATE
-- URGENT SAFETY ISSUES AND AE0D RECOMMENDATIONS WILL CONTINUE TO t
RECEIVE PRIORITY ATTENTION (FOLLOW-ON ACTIONS WILL BE PRIORITIZED)
APPROVED USIS AND OPERATING REACTOR ACTIONS WILL'NOT BE REEVALUATED e
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PRA METHOD FOR EVALUATING PRIORITIES r;
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PRIORITY SCORE ~
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C0sTs I
WEIGHTED RIsx REDUCTION IF PROPOSED UEW tIEIGHT. SAFETY BEllEFIT
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RE UIREMENT IS IMPLEMENTED Costs HRC STAFF COSTS AND ESTIMATED PLANT CAPITAL, OPERATING AND SHUTDOWN COSTS TO IMPLEMENT NEW REau! REM 5NT t
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EXAMPLES OF PRIORITY ANALYSES
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NUMBER flRC' COST PER MANAGEMENT REACTORS COST LICENSEE PRIORITY SCORE SCORE o ay
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5 BORON DILUTION 43
'$73K
$200K 3 x 103 4 x 10 (2 x 102 -+ 5 x 10'l).
I 2
BWR FUEL 2 11
$ 9K
$ 0.3K 3 x 102 5 x 10 NISLOADING I
(3 X 101 + 2 x 10 )
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RESULTSOFPRIORITYNNAi.YSES l{!Gil
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9WR SCRAM TIR DUMP PWR RCP SEAL LEAKAGE PWR DIESEL GENERATOR RELIABILITY MEDIUM DAvlS-BESSE Aux. FEED PUMP BORON DILUTION DURING SiluTD0wN Low BWR FUEL MISLOADIN'G PWR RTD TIME RESPONSE S-G TuaE RUPTURE DETECTORS 9
4.
9
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._ _ _ - -..-_ = _ -.
l 1
CURRENT ACTIVITIES ON PRIORITIZING SAFETY ISSUET i4
'O A-30 ADEQUACY OF SAFETY-RELATED DC POWER SUPPLIES B-53 L0no DREAK SWITCH B-54 ICE CONDENSER CONTAINMENTS B-55 TARGET ROCK SAFETY RELIEF VALVES C-9 RllR llEAT EXCilANGER IUBE FAILURES D-1 ADVISABILITY OF SEISMIC SCRAM i
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FUTURE PLANS 9
FY 1982 1.
COMPLETE CURRENT COMPILATION OF ALL GENERIC ISSUES - INCLUDES Tile GENERIC
' ISSUES TRACKING SYSTEM d.GITS) AND NUREG-0660.
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2.
ADD RECEllTLY IDENTIFIED ITEMS SUCil AS PRESSURIZED TllERMAL SHOCK AND BWR SCRAM DISCllARGE VOLUME.
3.
SCREEN ITEMS TO IDENTIFY SAFETY ISOfEp T11AT Sil0ULD BE PRIORITIZED FIRST.
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ESTABLISil RELATIVE PRIORITIES OF Ti1E MORE IMPORTANT ISSUES SELECTED ABOVE AND INITIATE WORK ON Til0SE OF HIGHEST PRIORITY, RESOURCES PERMITTING.
5.
Delete OLDER ISSUES TilAT APPEAR TO HAVE LITTLE REAL SAFETY SIGNIFICANCE.
~
6.
PRIORITIZE NEW ISSUES, AS TilEY'ARE IDENTIFIED.
FY 1983 1.
CONTINUE TO ESTABLISH RELATIVE PRIORITIES; MAINTAIN ISSUES ON MASTER PRIORITY LIST.
2.
ALLOCATE RESOURCES TO RESOLVE ISSUES IN ACCORDANCE WITH PRIORITIESJ CONTINUE TO
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INITIATE WORK ON GENERIC SAFETY IS$UES OF MOST IMPORTANCE.
3.
PRIORITIZE NEW ISSUES, AS TilEY ARE IDENTIFIED..
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ISSUES FROM NUREG-0410 (JANUARY 1978)
BRANCH TASK NO.
TITLE GIB A-1 (USI)
WATER HAMMER GIB A-2 (USI)
ASYMMETRIC BLOWDOWN LOADS ON THE REACTOR 1
VESSEL 4
l GIB A-3 (USI)
W STEAM GENERATOR TUBE INTEGRITY GIB
.A-4 (USI)
CE STEAM GENERATOR TUBE INTEGRITY GIB A-5 (USI)
B&WSTEAMGENERATOR,JUBEINTEGRITY
~
GIB A-6 (USI)
MARK I SHORT TERM PROGRAM
/
GIB A-7 (USI)
MARK I LONG TERM PROGRAM i
1 GIB A-8 (USI)
MARK II PROGRAM GIB A-9 (USI)
ATWS i
GIB.
A-10 (USI)
BWR N0ZZLE CRAC' KING GIB A-11 (USI)
REACTOR VESSEL MATERIALS TOUGHNESS GIB 2(M 2 '(USI)
FRACTURE TOUGHNESS OF STEAM GENERATOR AND a'
COOLANT PUMP SUPPORTS MEB A-1,3 SNUB 5ERS i
MTEB A-14 FLAW DETECTION CE'B A-15 CHEMICAL DECONTAMINATION l
CPB A-16 STEAM EFFECTS ON BWR CORE SPRAY DISTRIBUTION RRAB A-17 (USI)
SYSTEMS INTERACTION IN NUCLEAR POWER PLANTS
, -18 (+B-16)
PIPE RUPTURE DESIGN CRITERIA -
MEB A
ICSB A-19 DIGITAL COMPUTER PROTECTION SYSTEMS EEB A-20 IMPACTS OF COAL FUEL CYCLE CSB A-21 MAIN STEF.MLINE BREAK INSIDE CONTAINMENT
~
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BRANCH TASK NO.
TITLE CSB A-22 MAIN STEAMLINE BREAK OUTSIDE CONTAINMENT CSB A-23 CONTAINMENT LEAK TESTING GIB A-24(bSI)
QUALIFICATION OF CLASS IE SAFETY RELATED EQUIPMENT PSB A-25 NON-SAFETY LOADS ON CLASS IE POWER SOURCES
~
GIB A-26(USI)
REACTOR VESSEL PRESSURE TRANSIENT PROTECTION (OVERPRESSURE)
CPB A-27 RELOAD APPLICATION GUIDE EEB A-28 INCREASE IN SPENT FUEL. STORAGE CAPACI SSPB A-29 DESIGN FEATURES TO CONTROL SABOTAGE
'PSB A-30 ADEQUACY OF SAFETY RELATED DC POWER SUPPLIES GIB A-31 (USI)
RHR SHUTDOWN REQUIREMENTS SEB A-32 EVALUATION OF OVERALL EFFECTS OF MISSILES AEB A-33 NEPA REVIEWS OF ACCIDENT RISKS ICSB A-34 INSTRUMEN" FOR MONITORING RADIATION AND PROCESS VI) TABLES DURING ACCIDENT $I K
A. i PSB A235 ADEQUACY OF OFFSITE POWER SYSTEMS GIB A-56(USI)
CONTROL OF HEAVY LOADS NEAR SPENT FUEL SEB A-37 TURBINE MISSILES SEB A-38 TORNADO MISSILES GIB A-39 DETERMINATION OF SAFETY RELIEF VALVE (SRV)
POOL DYNAMIC LOADS AND TEMPERATURE LIMITS FOR BWR CONTAINMENTS GIB
_.A-40 (USI)
SEISMIC DESIGN CRITERIA - SHORT TERM PROGRAM EQB A-4' SEISMIC DESIGN CRITERIA - LONG TERM PROGRAM GIB A-42 (USI)
PIPE CRACKS IN BWRs
BRANCH TASK NO.
TITLE GIB A-43 (USI)
CONTAINMENT EMERGENCY SUMP RELIABILITY GIB/RES A-44 (USI)
STATION BLACKOUT GIB -
A-45 SHUTDOWN DECAY HEAT REMOVAL GIB A-46 SEISMIC QUALIFICATION OF EQUIPMENT IN OPERATING PLANTS
~
GIB A-47 SAFETY IMPLICATIONS OF CONTROL SYSTEMS GIB A-4B '
HYDROGEN CONTROL
~
i EEB B-1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS.
[
UFB B-2-(+B-45)
FORECASTING ELECTRICITY DEMAND BY STATE IN THE UNITED STATES ON AN ANNUAL BASIS i
s RSB B-3 EVENT CATEGORIZATION
- ^
RSB B-4 ECCS RELIABILITY J
SEB-B-5 DUCTILITY OF TWO-WAY SLABS AND SHELLS AND BUCKLING BEHAVIOR OF STEEL CONTAINMENT MEB ~
A6 LOADS,' LOAD COMBINATIONS, STRESS CIMITS
-N1 I
SECONDARY ACCIDENT CONSEQUENCE MODELING B?
. AEB RSB 8-B LOCKING 06T OF ECCS' POWER OPERATED VALVES (ALSOICSB,PTG) 4 PSB B-9 ELECTRICAL CABLE PENETRATION OF CONTAINMENT CSB B-10 BEHAVIOR OF BWR MARK III CONTAINMENT CSB B-ll SUBCOMPARTMENT STANDARC PROBLEMS CONTAINMENT COOLING REQUIREMENTS (NON-LOCA)
CSB B-12 CSB B-13 MARVIKEN TEST DATA EVALUATIONS B-14 STUDY OF HYDROGEN MIXING CAPABILITY IN CON-TAINMENT. POST-LOCA (INCLUDED AS PART OF A-48)
CSB B-15 CONTEMPT COMPUTER CODE MAINTENANCE
BRANCH TASK NO.
TITLE B-16 PROTECTION AGAINST POSTULATED PIPING h,'URES IN FLUID SYSTEMS OUTSIDE CONTAINMENT (INCLUDED UNDER A-18)
B-17 CRITERIA FOR SAF:ETY-RELATED OPERATOR ACHONS B-1B VORTEX SUPPRESSION REQUIREMENTS FOR CONTAIN-MENT SUMPS (INCLUDED IN A-43)
CPB B-19 THERMAL-HYDRAULIC STABILITY RSB B-20 STANDARD PROBLEM ANALYSIS CPB B-21 CORE PHYSICS l
uPB B-22 LWR FUEL
/
CPB B-23 LMFBR FUEL GIB B-24 SEISMIC QUALIFICATION OF ELECTRICAL AND-MECHANICAL -COMPONENTS (INCLUDED UNDER A-46)
MEB B-25 PIPING BENCHMARK PROBLEMS i
MEB
'B-26 CONTAINMENT PENETRATIONS MEB B-27 IMPLEMENTATION AND USE OF SUBSECTION NF
.,D.
HGEB BV28 RADIONUCLIDE/ SEDIMENT TRANSPORT PROGRAM 1
HGEB B,29 EFFECTIVENESS OF ULTIMATE HEAT SINKS, HGEB B-30 DESIGN BASIS FLOODS AND PROBABILITY HGEB' B-31 DAM FAILURE MODEL HGEB B-32 ICE EFFECTS ON SAFETY RELATED WATER SUPPLIES RAB B-33 DOSE ASSESSMENT METHODOLOGY RAB B-34 OCCUPATIONAL RADIATION EXPOSURE REDUCTION ETSB B-35 CONFIRMATION OF APPENDIX I MODELS FOR
" CALCULATIONS OF RELEASES OF RADIOACTIVE MATERIALS IN GASECUS AND LIQUID EFFLUENTS FROM LIGHT-WA7ER-C00 LED POWER REACTORS" L
BRANCH TASK NO.
TITLE ETSB B-36 DEVELOP DESIGN, TESTING AND MAINTENANCE CRITERIA FOR ATMOSPHERE CLEANUP SYSTEM AIR FILTRATION AND ADSORPTION UNITS FOR ENGINEERED-SAFETY-FEATURE SYSTEMS AND FOR NORMAL VENTILATION SYSTEMS EEB B-37 CHEMICAL DISCHARGES TO RECEIVING WATERS EEB B-38 RECONNAISSANCE LEVEL INVESTIGATIONS EEB B-39 TRANSMISSION LINES EEB
.B-40 EFFECTS OF POWER PLANT ENTRAINMENT ON PLANKTON EEB B-41 IMPACTS ON FISHERIES,,,
l SAB B-42 SOCIOECONOMIC ENVIRONMENTAL IMPACTS I
i EEB B-43 YALUE OF AERIAL PHOTOGRAPHS FOR SITE EVALUATION i
UFB B-44 FORECASTS OF GENERATING COSTS OF COAL AND 1
NUCLEAR PLANTS i
B-45 NEED FOR POWER - ENERGY CONSERVATION (INCLUDED i
UNDERB-2)
B-46 COSTS OF ALTERNATIVES IN ENVIRONMENTAL DESIGN MTEB
[(' -17 INSERVICE INSPECTION' CRITERIA FOR SUPPORTS 4
U AND BOLTING OF CLASS 1, 2, 3 AND MC COMPONENTS MTEB B-48 BWR CRD MECHANICAL FAILURE (COLLET' HOUSING)
MTEB B-49 INSERVICE INSPECTION CRITERIA FOR CONTAINMENT SEB B-50 REQUIREMENTS FOR POST-0BE INSPECTION (ALSO MEB) i MEB B-51 ASSESSMENT OF INELASTIC ANALYSIS TECHNIQUES B-52 FUEL ASSEMBLY SEISMIC AND LOCA RESPONSES (INCLUDED UNDER A-2)
PSB B-53 LOAD BREAK SAFETY SWITCH CSB B-54 ICE CONDENSER CONTAINMENTS MEB B-55 IMPROVED ' RELIABILITY OF TARGET-ROCK SAFETY-RELIEF VALVES PSB B-56 DIESEL RELIABILITY h
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BRANCH TASK NO.
TITLE B-57 STATION BLACKOUT (CHANGED TO A-44)
RES B-58 PASSIVE MECHANICAL FAILURES (OVERLAPS TASK C-11); (ALSO RRAB)
RSB B-59 REVIEW OF (N-1) LOOP OPERATION IN BWRs AND PWRs RES B-60 LOOSE PARTS MONITORING SYSTEMS.
SEP B-61 ALLOWABLE ECCS EQ'JIPMENT OUTAGE PERIODS (ALSO PAS /RES & RRAB)
CPB B-62 REEXAMINATION OF TEC}iNICAL BASES FOR ESTABLISHING SLs, LSSSs, ETC.
f MEB B-63 ISOLATION OF LOW PRESSURE SYSTEMS CONNECTED TO RCPB i
CEB B-64 DECOMMISSIONING OF REACTORS (A.LSO UFB)
AEB B-65 IODINE SPIKING (ALSO AEB)
AEB
.B-66 CONTROL ROOM INFILTRATION MEASUREMENTS ETSB B-67 EFFLUEET AND PROCESS MONITORING INSTRUMENTATION i
~
w),68
'23 PUMP OVERSPEED DURING A LOCA RSB s
TMI-AP B-69 ECCS LEAKAGE EXCONTAINMENT (SUPERSEDED BY
~
SEVERAL TMI-AP ITEMS, III.D.1.1 THRU* III.P.1.4)
PSB B-70 POWER GRID FREQUENCY DEGRADATION AND EFFECT ON PRIMARY COOLANT PUMPS TMI-AP B-71 INCIDENT MANAGEMENT (SUPERSEDED BY SEVERAL TMI-AP ITEMS, III.A.3, III.B, III.C) a RAB B-72 DEVELOPMENT OF MODELS FOR ASSESSING RISK OF HEALTH EFFECTS AND LIFE SHORTENING FROM URANIUM AND COAL FUEL CYCLES 4
MEB B-73 (+C-12)
MONITORING FOR EXCESSIVE VIBRATION INSIDE THE l
s
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r BRANCH TASK NO.
TITLE EQB C-1 ASSURANCE OF CONTINUOUS LONG TERM CAPABILITY OF HERMETIC SEALS ON INSTRUMENTATION AND ELECTRIC EQUIPMENT (fLSO ICSB, QAB).
CSB C-2 STUDY OF CONTAINMENT DEPRESSURIZATION BY IN-ADVERTENT SPRAY OPERATION TO DETERMINE ACEQUACY OF CONTAINMENT EXTERNAL DESIGN PRESSURE C-3 INSULATION USAGE WITHIN CONTAINMENT (CHANGED TOA-43)
RSB C-4 STATISTICAL METHODS FOR ECCS ANALYSES CPB
~C-5 DECAY HEAT UPDATE CPB C-6 LOCA HEAT SOURCES *
/
MTEB C-7 PWR SYSTEM PIPING ASB C-8 MAIN STEAM LINE LEAKAGE CONTROL SYSTEM ASB C-9 RHR HEAT EXCHANGER TUBT. FAILURES (ALSOfEB/
PAWLICKI)
AEB C-10 EFFECTIVE OPERATION OF CONTAINMENT SPRAYS IN A LOCA (ALSO ASS) 1 RES C-11 ASSESSMENT OF FAILURE AND RELIABILITY OF PUMPS
'.k; AND VALVES (ALSO RRAB) f k
C-12 PRIMARY SYSTEM VIBRATION ASSESSMENT (INCLUDED-IN B-73)
GIB C-13 NON-RANDOM FAILURES (INCLUDED IN A-9, A-17, A-30, A-44 AND B-56)
HGEB C-14 STORM SUP.GE MODEL FOR COASTAL SITES ETSB C-15 NUREG REPORT FOR LIQUID TANK FAILURE' ANALYSIS EEB C-16 ASSESSMENT OF AGRICULTURAL LAND IN RELATION TO
, POWER PLANT SITING AND COOLING SYSTEM SELECTION ETSB C-17 INTERIM ACCEPTANCE CRITERIA FOR SOLIDIFICATI'ON AGENTS FOR RADI0 ACTIVE SOLID WASTES RSB D-1 ADVISABILITY OF A SEISMIC SCRAM i
i
BRANCH TASK NO.
TITLE RSB D-2 EMERGENCY CORE COOLING SYSTEM CAPABILITY ~
FOR FUTURE PLANTS (INCLUDED IN RES IMPROVED SAFETY RESEARCH PROGRAM)
CPB D-3 CONTROL ROD DROP ACCIDENT (BWRs)
NEW STAFF ISSUES SINCE NUREG 0410 ICSB 1
RELIABILITY OF VENTILATION MONITORING EQUIPMENT ICSB 2
PROTECTIVE DEVICE RELIABILITY ICSB 3
INSTRUMENTATION SET.-POINT DRIFT QAB 4
END-OF-LIFE MAINTENANCE CRITERIA QAB 5
DESIGN CHECK AND AUDIT OF BALANCE-OF-PLANT EQUIPMENT
~
CPB 6
BWR CONTROL ROD WORTH 6
I MEB 7
(INCLUDES C-2 PLUS OTHEP. CONCERNS) (ALSO EQB)
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RSB 8
INADVERTENT ACTUATION OF SAFETY INJECTION (ALSO OLB)
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j RSB 9'
REEVALUATION OF REACTOR COOLANT PUMP TRIP CRITERIA 4
CSB 10 SURVEILLANCE AND MAINTENANCE OF TIP ISOLATION.
VALVES AND SQUIB CHAP.GES
~
MEB 11 TURBINE DISK CRACKING MTEB 12 BWR JET PUMP INTEGRITY RSB 13 SMALL BREAK LOCA FROM EXTENDED OVERHEATING OF PRE 3SURIZER HEATERS MTEB 14 PWR PIPE CRACKS (OVERLAPS C-7)
MTEB 15 RADIATION EFFECTS ON REACTOR VESSEL SUPPORTS PSB 16 LOSSOFdFFSITEPOWERSUBSEQUENTTOALOCA GIB 17 PRESSURIZED THERMAL SH0CK SPEB 18 RCP SEAL LEAKAGE
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BRANCH TASK NO.
TITLE AE0B ISSUES
'RSB 19 STEAM LINE BREAK WITH CONSEQUENTIAL SMALL LOCA ICSB 20 SAFETY IMPLICATIONS OF NON SAFETY I&C POWER 4
SUPPLY BUS (I&E BULLETIN 79-27) 4 J
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