ML19289F892
| ML19289F892 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/31/1979 |
| From: | Budnitz R NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| References | |
| BE-790531, NUDOCS 7906210044 | |
| Download: ML19289F892 (14) | |
Text
fGQ PRESENTATION OF DR. ROBERT J. BUDNITZ BEFORE TiiE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS MAY 31, 1979 ge-sao S
7 9 0 62 3 coqq eve usP 241 160 gaws 71-17 1
IDENTIFIED RESEARCH NEEDS (TMI-2)
CATEGORY e
TRANSIENT & SMALL LOCA EVENTS e
ENHANCED OPEPATOR CAPABILITY e
PLANT RESPONSE UNDER ACCIDENT CONDITIONS e
POST MORTEM EXAMINATION & PLANT REC 0VERY e
IMPROVED RISK ASSESSMENT o
IMPROVED REACTOR SAFETY (OTHER) k u?
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IDENTIFIED RESEARCil NEEDS TRANSIENT AND SMALL LOCA EVENTS e
THERMAL 1 HYDRAULIC EXPERIMENTS CONCERNING CORE & PRIMARY COOLANT SYSTEM BEHAVIOR (PWR'S & BWR'S) FOR NATURAL CIRCULATION, TRANSIENTS & SMALL LOCA'S o
C00 LABILITY OF SEVERELY DAMAGED CORES e
RELEASE & TRANSPORT OF FISSION PRODUCTS FROM SEVERELY DAMAGED FUEL e
IMPROVED BEST ESTIMATE TRANSIENT AND SMALL LOCA CODES
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TRANSIENTS & Sf1ALL LOCA EVENTS PROPOSED PROJECTS - FY 1980 SUPPLEMENT e
UPGRADE SEMISCALE TO STUDY PWR TRANSIENTS
- $3.0M 2.2 UPGRADE TLTA TO STUDY BWR TRANSIENTS & SMALL LOCA'S o
o SEPARATE EFFECTS THERMAL-HYDRAULIC TESTS 1.3 (NAT. CIRC, BUNDLE UNC0VERY, ETC.)
1.0 e
ACCELERATE St1ALL BREAK TESTS IN '_ OFT 0.4 o
C00 LABILITY OF SEVERELY DAfiAGED CORES 1.6 o
BEHAVIOR OF CORES BOILING DRY 0.4 o
FISSION PRODUCT RELEASE & TRANSPORT CODES 1.7 e
ACCELERATE TRANSIENT & SMALL LOCA CODES e
ANALYSIS OF PWR/BWR TRANSIENTS 1.4 e
ESTABLISH OPERATING REACTOR DATA BANK FOR ANALYSIS
- 0.4
$13.4 241 163
IDENTIFIED RESEARCH NEEDS ENilANCED OPERATOR CAPABILITY IMPROVED DATA DISPLAY & DIAGNOSTIC SYSTEMS e
STilDIES & TESTS OF ADDITIONAL IN-VESSEL & PLANT INSTRUMENTATION STUDIES TO DEFINE IMPROVED STATUS MONITORING e
ENHANCED DATA TRANSMISSION CAPABILITY FOR OUTSIDE ASSISTANCE o
IMPROVED REQUIREMENTS FOR OPERATOR TRAINING SIMULATORS e
2
ENHANCED OPERATOR CAPABILITY PROPOSED PROJECTS - FY 1980 SUPPLEMENT e
DEVELOP INSTRUMENTATION NEEDS (INC. FLUID LEVEL & FAILED FUEL DETECTION)
- $0.2M 1.0 e
TEST PROPOSED INSTRUMENTS 0.4 o
DEFINE ENHANCED DATA TRANSMISSION REQUIREMENTS 0.1 o
REVIEW ACCIDENT RESPONSE PROCEDURES o
ACCELERATE STUDIES AND TESTING OF IMPROVED DATA 1.0 DISPLAY & DIAGNOSTIC SYSTEMS s
STUDIES TO DEFINE IMPROVED STATUS / MONITORING 0.3 FOR ESF & SUPPORTING SERVICES e
IMPROVED RE0. FOR OPERATOR TRAINING SIMULATORS 0.3
$3.3M 241 165
IDENTIFIED RESEARCH NEEDS PLANT RESPONSE UNDER ACCIDENT CONDITIONS e
PRIf1ARY COOLANT CHEMISTRY FOLLOWING FUEL FAILURE HYDROGEN EVOLUTION 8 BEHAVIOR Ift PRIMARY SYSTEM 8 CONTAINt1ENT o
BEHAVIOR OF PLANT SAFETY COMPONENTS UtiDER ACCIDENT ENVIRONfENT e
DEVELOP TESTING REQUIREMENTS FOR CRITICAL PLANT EQUIPMENT e
e PLANT STRUCTURAL RESPONSE m
L PLANT RESPONSE UNDER ACCIDENT CONDITIONS PROPOSED PROJECTS - FY 1980 SilPPLEMENT COOLANT CHEt11STRY AFTER FUEL FAILURE
- $0.5M e
0.6 HYDROGEN BEHAVIOR IN COOLANT & CONTAINMENT e
EFFECTS OF HYDROGEN EXPLOSIONS ON PRIMARY VESSEL 0.3 o
0.2 EFFECTS OF HYDROGEN EXPLOSIONS ON CONTAINMENT o
0.1 HYDROGEN EMBRITTLEMENT OF PRIMARY SYSTEM MATERIALS o
0.6 REACTOR VESSEL SHOCK AT HIGH PRESSURE o
0.5 CONTAINMENT INTEGRITY UNDER FUEL MELT CONDITIONS o
0.5 o
RELIEF VALVE TESTING REQUIREMENTS 0.5 o
PUT1P & VALVE OPERABILITY DURING ACCIDENTS 0.5 DAMAGE ASSESSMENT OF PLANT STRUCTURES e
BENCHMAPKS FOR STRUCTURAL & PIPING SYSTEM o
0.3 ANALYSIS CODES
$5.19 241 167
IDENTIFIED RESEARCH NEEDS POST MORTEM EXAMINATION & PLANT RECOVERY e
EXAMINATION OF TMI CORE DATA ON FISSION PRODUCT CHEt11STRY, TRANSPORT 8 PLATE 0VT e
OPERABILITY OF SAFETY EQUIPflENT AT TMI e
ESTABLISH CRITERIA FOR REQUALIFICATION OF SAFETY EQUIPMENT e
m
POST MORTEM EXAMINATION & PLANT REC 0VERY PROPOSED PROJECTS - FY 1980 SUPPLEMENT e
EXAMINATION OF TMI CORE AT TAN
- $1.0M o
OBTAIN FISSION PRODUCT CHEMISTRY, TRANSPORT 0.6 R, D' AiEOUT DATA 0.5 o
POST MORTEM OF TMI SAFETY RELATED EQUIP.
e ESTABLISH EQUIPMENT REQUALIFICATION 0.2 CRITERIA e
DEVELOP IMPROVED QUALIFICATION TESTING 0.2 METHODS 0.2 e
EVALUATE RISK IMPLICATIONS DECONTAMINATION ALTERNATIVES
$2.7M 241 169
IDENTIFIED RESEARCH NEEDS IMPROVED RISK ASSESSMENT e
DEFINITION OF ACCIDENT SEQUENCES LEADING TO SEVERE CORE DAMAGE e
RE-EXAMINATION OF ROLE OF HUf1AN ERROP. IN RISK AflALYSIS e
HUMAN ERROR RATE ANALYSIS e
OPERATIONAL FAILURE DATA ANALYSIS e
LONG-TERM RELIABILITY OF REACTOR SYSTEMS DURING ACCIDENTS M
IDENTIFIED RESEARCH NEEDS IMPROVED REACTOR SAFETY (OTHER) e ALTERNATE CONTAINMENT CONCEPTS ALTERNATE DECAY HEAT REMOVAL o
e ALTERNATE ECCS e
EMERGENCY RESPONSE PLANNING ro f
IMPROVED VALUE/ IMPACT METHODS e
C
If1 PROVED REACTOR SAFETY * (OTHER)
PROPOSED PROJECTS - FY 1980 SUPPLEMENT o
VENTED CONTAINMENT CONCEPT INVESTIGATIONS
- $0.3M o
OTHER C0tiTAINMENT CONCEPTS 0.2 e
ALTERNATE DECAY HEAT REMOVAL 0,3 e
ALTERNATE ECC SYSTEMS 0.3 e
SCOPING STUDIES OF OTHER CONCEPTS TO IMPROVE REACTOR SAFETY
-0A 0.2 o
IMPROVED VALUE/ IMPACT METHODOLOGY e
EVALUATE NRC & LICENSEE EMERGENCY 0.2 RESPONSE PLANNING 0.1 e
ASSESSMENT OF EMERGENCY RESPONSE PREPAREDNESS e
ASSESSMENT OF EMERGENCY IMPACT ON SAFEGUARDS 0.2 PERFORMANCE
$2.2M STUDIES RELATED TO IMPROVING OPERATOR.-RESPONSE'TO ACCIDENTS ARE INCLUDED IN CATEGORY ON
" ENHANCED OPERATOR CAPABILITY" 241 172 r --
IMPROVED RISK ASSESSMENT PROPOSED PROJECTS - FY 1980 SUPPLEMENT e
SITE SPECIFIC ACCIDENT CONSEQUENCE ASSESS.
- $0.4M ANALYSIS OF ACCIDENTS LEADING TO SEVERE e
0.3 CORE DAMAGE 0.3 POTENTIAL OPEPATOR/ MAINTENANCE ACTIONS e
0.2 e
HUMAN ACCIDENT INITIATION 0.2 e
HUMAN ERROR IMPACTS ON RISK 0.1 e
HUMAN ERROR RATE ANALYSIS 0.3 HUMAN ERROR DATA ANALYSIS FROM SIMULATORS o
o RELIABILITY MODELING OF LONG-TERM SYSTEM 0.2 OPERATION 0.1 ALGORITHM DEV. FOR HUMAN ERROR ANALYSIS o
0.3 o
OPERATIONAL FAILURE DATA ANALYSIS
$2.4M 241 173