ML20205C798

Requests That ACRS Review of FY88 Proposed Presidential Budget Be Conducted in Closed Session Under Exemption 9(B)

ML20205C798
Person / Time
Issue date:	11/12/1986
From:	Marcus G NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	Fraley R Advisory Committee on Reactor Safeguards
Shared Package
ML20205C720	List: ML20205C715 ML20205C798
References
ACRS-2479, NUDOCS 8703300264
Download: ML20205C798 (46)

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NOV 12 1936 MEMORANDUM FOR:

R. F. Fraley, Executive Director, Advisory Committee on Reactor Safeguards FROM:

Gail H. Marcus, Deputy Director, Division of Regulatory Applications, Office of Nuclear Regulatory Research

SUBJECT:

REQUEST TO CLOSE ACRS MEETINGS ON RES FY 1988 BUDGET In response to information regarding the ACRS review of the RES FY 1988 proposed Presidential budget, we are requesting the review be conducted in closed session.

We request that the session be closed under Exemption 9(B).

Premature disclosure of the possible curtailment or elimination of any contract could result in an inability to retain key personnel and thereby frustrate the Commission's ability to implement the affected programs effectively.

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Gail H. Marcus, Deputy Director Division of Regulatory Applications Office of Nuclear Regulatory Research 8703300264 861224 PDR ACRS 247c7 PDR

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REVISED:

12/4/86

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PRESENTATION SCHEDULE ACRS SUBCOMMITTEE MEETING ON THE SAFETY RESEARCH PROGRAM DECEMBER 10, 1986 ROOM 1046, 1717 H STREET, N.W.

WASHINGTON, D.C.

ACRS CONTACT: Sam Duraiswamy 202-634-3267 NOTE:

Presentation Time should not exceed 50% of the Total Time allocated for a specific item. The remaining 50% of the time is reserved for the Subcommittee questions and answers.

TOTAL PRESENTATION ITEM PRESENTER TIME ACTUAL TIME I.

EXECUTIVE SESSION 15 min 8:30 - 8:45am II.

RES PRESENTATION a.

Introduction Eric Beckjord 15 min 8:45 - 9:00am b.

Budget Overview Gail Marcus 20 min 9:00 - 9:20am c.

Program Changes and Priorities

• Engineering Guy Arlotto 30 min 9:20 - 9:50am Safety

• Reactor System Billf4crris 45 min 9:50 - 10:35am Safety

• • • BREAK ***

15 min 10:35 - 10:50am

• Regulatory Karl Galler 30 min 10:50 - 11:20am Applications, and Radiation Protection / Health Effects d.

Status of NAS Eric Beckjord 30 min 11:20 - 11:50am Report e.

Program Gaps Denny Ross 30 min 11:50 - 12:20pm

• • • LUNCH ***

60 min 12:20 - 1:20pm A rrac8 next" 6

B.I

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O Safety Research Program December 10, 1986

- Presentation Schedule -

TOTAL PRESENTATION ITEM PRESENTER TIME ACTUAL TIME III. NRR PRESENTATION Karl Kniel/

30 min 1:20 - 1:50pm Tom King a.

Areas Where NRR Differs with RES on the Proposed Research and Budget b.

Technical Assist-ance Program Activities in NRR IV. NMSS PRESENTATION Phil Justus/

30 min 1:50 - 2:20pm John Greeves a.

Areas Where NMSS Differs with RES on the Proposed Research and Budget b.

Technical Assist-ance Program Activities in NMSS V.

SUBCOMMITTEE REMARKS 10 min 2:20 - 2:30pm

• • • ADJ0 URN ***

2:30pm

/3 2L

Safety Research Program -

December 10, 1986 LIST OF DOCUMENTS SUBMITTED TO THE SUBCCMMITTEE DECEMBER 10, 1986 SAFETY RESEARCH PROGRAM MEETING 1.

Tentative Presentation Schedule.

2.

Memorandum from R. Gustave to S. Duraiswamy related to FY 1988-1989 Budget Table, dated October 15, 1986.

3.

Portion of the " BLUE B00X" dealing with the Commission's Budget request to the OMB for the FY 19ES NRC Safety Research Program.

4.

Information presented to OMB by RES on September 9, 1986.

5.

Program Support Budget Estimates, (FIN level budaet information),

dated November 12, 1986.

6.

ACRS report to the Commission transmitting comments on the NPC Safety Research Program and budget for FY 1988, dated June 11, 1986.

7.

ACRS report to the Congress on the FY 1987 NRC Safety Research Program, dated February 19, 1986, 8.

RES responses to ACRS recommendations contained in the June 11, 1986 report to the Commission on the NPC Safety Research Program Budget for FY 1988 dated July 28, 1986.

9.

Memorandum from E. Beckjord to R. Scroggins related to " MINIMUM" Research Program, dated October 7, 1986,

10. Memorandum from D. Ross to RES Staff concerning, "RES Goals For The Next Year," dated September 3, 1986.

11. Memorandum from E. Beckford to R. Scroggins related to "RES FY 1987 Budget Reduction," dated October 2, 1986.

12. Presentation Materials submitted to the Subcommittee during the meeting.

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NUCLEAR REGULATORY RESEARCH 12/09/86 FY 1988 (DOLLARS IN MILLIONS)

FY 87 FY 88 REACTOR SYSTEM SAFETY

$ 44.9

$ 49,9 THERMAL HYDPAULIC TRANSIENTS 15,5 21,4 WESTINGHOUSE /CE ISSUES 7.9 9.6 B&W ISSUES 5.9 9.9 GE ISSUES 1.7 1.9 SEVERE ACCIDENTS 17,7 18,6 FISSION PRODUCT BEHAVIOR 4.5 4.6 CONTAINMENT LOADING 13.2 14.0 RISK 8 RELIABILITY 11,6 9,9 RISK METHODOLOGY 3.0 4.3 RISK APPLICATIONS 2.8 2.1 SEVERE ACCIDENT RISK ASSESS 4.3 2.0 OPERATIONAL RELIABILITY 1.5 1.0 SAFETY ISSUE RESOLUTION 0

0.5 ENGINEERING SAFETY 42,8 42.3 MATERIALS AGING 19.2 17.0 REACTOR PRESSURE VESSEL SAFETY 8.1 7.6 PIPING 5.3 3.7 NONDESTRUCTIVE EXAMINATION 2.8 3.0 CHEMICAL EFFECTS 3.0 2.7 PLANT SAFETY 23.6 25.3 PLANT AGING 8.1 10.0 SEISMIC 11.2 11.7 CONTAINMENT INTEGRITY 4.3 3.6 WASTE MANAGEMENT 5,8 9.0 HIGH LEVEL WASTE 3.2 5.0 LOW LEVEL WASTE 2.6 4.0 REGULATORY APPLICATIONS 2.3 2.4 REGULATION DEVELOPMENT 1.2 2.0 RESEARCH APPLICATIONS 1.1 0.4 TOTAL

$ 95.8

$103.6 ArmNatur D O'l

12/09/86 NUCLEAR REGULATORY RESEARCH FY 1988 (DOLLARS IN MILLIONS)

FY 1988 OMB DECISION UNIT 6/10/86 SUBMISSION REACTOR SYSTEM SAFETY

$ 45,1

$ 49,9 THERMAL HYDRAULICS 16,7 21,4 SEVERE ACCIDENTS 18,4 18,6 RISK & RELIABILITY 10,0 9,9 ENGINEERING SAFETY 43,1 42,3 MATERIALS AGING 17,8 17,0 PLANT SAFETY 25.3 25.3 WASTE MANAGEMENT 9,0 9,0 HIGH LEVEL WASTE 5,0 5,0 L0w LEVEL WASTE 4.0 4.0 REGULATORY APPLICATIONS 2,4 2,4 REGULATION DEVELOPMENT 2.0 2,0 RESEARCH APPLICATIONS 0,4 0,4 TOTAL

$ 99,6

$103,6 1/

1/ BRG ADDED $5,5 TO PROGRAM ($5.0 ADDED FOR THERMAL HYDRAULICS (CEC); $0,5 ADDED FOR ADVANCED REACTORS) AND SUBSEQUENTALLY REDUCED RES BY $1.5 FOR CONSOLIDATION, FY 1988 OMB MARK - $380 MILLION; NO SPECIFIC CUTS BY OFFICE HAVE BEEN ASSIGNED, B-2

1?/08/86 NUCLEAR REGULATORY RESEARCH FY 1988 BUDGET (DOLLARS IN MILLIONS)

CATEGORY FY 1987 FY 1988 ANALYSIS

$ 22,0

$ 23.1 PREVENTION 58.1 64.4 MITIGATION 15,7 16,1

~

TOTAL

$ 95.8

$103,6 ANALYSIS INCLUDES TECHNICAL ASSISTANCE IN SUPPORT OF STANDARDS ACTIVITIES SUCH AS SECTION XI, OCCUPATIONAL PROTECTION & HEALTH EFFECTS, CODE DEVELOPMENT AND VERIFICATION, AND REGULATORY

SUPPORT, MITIGATION INCLUDES THE CONTAINMENT PROGRAM, THE ACCIDENT EVALUATION PROGRAM, AND A SMALL PART OF SURVIVABILITY IN SEVERE ACCIDENTS, PREVENTION INCLUDES REACTOR VESSELS, PIPING, STEAM GENERATORS, NONDESTRUCTIVE EXAMINATION, SEISMIC, EQUIPMENT QUALIFICATION, WASTE MANAGEMENT, THERMAL HYDRAULICS, RISK, AND THE REST OF THE SURVIVABILITY IN SEVERE ACCIDENTS, B-4 D -3

OUTSTANDING RESEARCH ISSUES o

ACRS AND NRR CONCERNS ARE BEING ADDRESSED o

STUDIES UNDERWAY TO IDENTIFY ADDITIONAL RESEARCH FEEDS i

EXAMPLES:

- ELECTRICAL EQUIPMENT QUALIFICATION SCOPING STUDY

- FIRE PROTECTION SCOPING STUDY l

o CONTRACTS AND OTHER ACTIVITIES PLANNED OR UNDERWAY IN SEVERAL KEY AREAS.

EXAMPLES:

- MIST FOLLOW ON (N0 FULL POWER TESTS)

- WATER HAMMER - MIT GRANT, CREARE CONTRACT

- BLEED AND FEED TESTS IN ROSA-IV 1)-df B-5

O FY 1988 PROPOSED 10% CUTS 12/09/86 OMB'

AMT AMT

_Ef_0_

_fJJL REMAIN 0

REACTOR SYSTEM SAFETY 16.2 1!Ld 1E5.d THEPPAL HYDRAULIC TRANSIENTS 21,d 2.Al 132$

TECHNICAL SUPPORT TO JAERI 0.5 0.5 0

PLANT ANALYZER 0.5 0.5 0

SG TUBE RUPTURE 0.1 0.1 0

TRAC APPLICATION To 2D/3D 2.5 0.5 2.0 2D/3D INSTRUMENTS SUPPORT 0.5 0.5 0

SEVERE ACCIDENTS IIA 6 1.a.E 1h21 NRU (CANADIAN REACTOR) TEST PROGRAM 1.8 1.2 0.6 QP ACRR MELT PROGRESSION EXPERIMENTS (1.3)

(1.2)

(0,1)

HIGH TEMPERATURE F.P. EXPERIMENTS 0.4 0.2 0.2 TMI-2 FUEL EXAM 0.3 0.3 0

TRAP / MELT VALIDATION 0.2 0.2 0

RISK AND RELIABILITY RESEARCH

$23 Q22 32S RMIEP FOLLOW-ON STUDIES 0.3 0.3 0

NUCLEAR POWER SAFETY REPORTING SYSTEM 0.5 0.5 0

RELIABILITY ISSUES 2.05 0.05 2.0 CONSEQUENCE ISSUES 2.05 0.05 2.0 ENGINEERING SAFETY

$42.3 LL.1.I.tQ MATERIALS AGING 1[d 12E 1E.a.2 HYDROGEN ADDITION EFFECTS 0.3 0.3 0 WELDED 8 WELD REPAIRED STAINLESS STEEL 0.2 0.2 0 NDE 8 MATERIALS INTEGRATION 0.5 0.5 0 REACTOR VESSEL INTEGRATION 0.8 0.8 0 PLANT SAFETY 2E.a.E 2.a.1 22.tE RESIDUAL LIFETIME EVALUATION 0.5 0.3 0.2 INDEPTH ENG. STUDIES OF COMP / SYSTEMS 0.5 0.5 0 P! PING l!FE EXTENSION 0.3 0.1 0.2 STD. PROBLEMS FOR STRUCTURAL COMPUTER CODES 0.2 0.2 0 DAMS AND EMBANKMENTS 0.5 0.5 0 NONLINEAR BEHAVIOR OF CONCRETE STRUCTURES 0.2 0.2 0 SEISMIC PIPING TESTS 0.7 0.7 0 WASTE MANAGEMENT 22Q 129 120 HIGH LEVEL WASTE E29 921 Sal GROUNDWATER DATING / GEOCHEMICAL ANALOGUES 0.3 0.3 0 FOR MODEL VALIDATION low LEVEL WASTE I20 E2Z 121 ROLE OF ORGANIC COMPLEXANTS AND MICRO-0.3 0.3 0 PARTICULATES IN CONTAMINANT TRANSPORT CHARACTER!ZATION OF RETARDATION MECHANISMS 0.4 0.4 0 IN SOILS D-5 TOTAL BRf2

t OFFICE OF PUCLEAR REGULATORY RESEAPO! DIVISION OF FNGIEERING SAFETY PROPOSED CUTS IN ANTICIPATION OF A 10% REDUCTION TO THE FY ]988 BUDGET 0FCISION UNIT PLANPED

AMT, AMT.

ACCOPP. FIN TITLE CllT RENIN ENGINEFRit0 SAFEIY MATERIALS A6841 ItYDROGEN ADDITION EFFECTS $300K 0 AGING B2449 WFLDED E WELD-REPAIRED STAINLFSS STEEL 250K 0 {B2907 NDE a MATERIALS INTEGPATION 500K 0), (D1615 PEACTOR VESSEL INTEGPATION 750K 0) PLANT D1728 RESIDUAL LIFETIME EVALUATION 280K 2M SAFETY yD1731 INDEPTH ENGR. STUDIES OF COMP / SYSTEMS 545K 0 i (D.173? P: PING LIFE FXTENSION 75K ??SK; A3242 Sm.PPOBLFMS FOR STPUCT. COMPUTER CODES 200K 0 D1724 PAMS AND EMBANKMENTS 500V 0 A32P NONLINEAR BEHAVIOR OF CONCRETE STRUCTURES 200K 0 l B3052 SEISMIC PIPING TESTS 700K 0 WASTF MANACH FNT til-LEVEL IBD GROUNDWATER DATING /GE0 CHEM. ANALOGUES 270K 0 j WASTE LOW-LEVEL B6007 ROLF OF ORGANIC ffMLEXANT R MICROPARTICULATES 300K 0 )h D6608 RETARDATION TCHANISMS IN Snits 350K 0

DIVISION OF ENGINEERING SAFETY CONTRIEllTIONS OF RECENT RESFARCll MATERIALS AGING 0 Tile SFf0ND PRESSURIZED TilEPMAL S110CK TEST AND A SERIFS OF WIDF PLATE CRACK ARPFST TESTS Sl!0WED THE ABILITY OF LOP CilARPY UPPER-SHELF MATERIAL TO PFSIST CATASTP0PilIC FAllllPF, AND TilVS HELPED VALIDATF THE PTS RULE. o CDPROSION TESTS, AND VALIPATION TESTS ON IN-SERVICE CRACKED PIPFS SUPP0PTFD Tile BASIS FOR NUREG-0313, PEV. 2, ON ACCEPTABLF MATERIALS AND PROCESSFS TO REMEDY BWR PIPE CPACKS, o A LAFGE SERIES OF PIPE TESTS PROVIDED Tilf BASIS FOR Tile ASME-XI IPP-3640 AND 3620 Pl!LES FOR FLAWED STAINLFSS AND CARBON STEEL PIPF, RESPECTIVELY, AS WEll. AS FOR THE ACCEPTAPCE CRITERIA FOR THE GDC-4 RULE CilANGF. o PROVIDED Tile TECilNICAL BASIS FOR ASPF-XI CODE CASES FOR NDE SYSTEM QUALIFICATION IN Tile ARFA 0F PIPING AND PERSONNEL TRAINING. O PPOVIDFD TFCilNICAL BASIS AND COMPl.FTED ALL REVIEWS FOR THF FINAL RULE ON 6 DECOMftiSSIONING, NOW BEING READIFD FOR FD0 AND COMMISSIOP APPROVAL. -J CI-3

DIVISION OF ENGINFFRING SAFETY CONTRIBilTIONS OF RECENT RESFARCll PLANT SAFETY o COMPLETED MAINE YANVEE SEISMIC MARGIN REVIEW WHICH WILL AfD IN RESOLUTION OF THE ISSUE OF GROUND MOTION GREATER TilAN DFSIGN BASIS AT MAINF YANKFF. O COMPLFTED DRAFT PEVISION OF GDC-4 (APPLICATION OF LEAK-BEF0PE-BREAK TECliN01.0GY) TilAT WILL AVERT WOPKER RADIATION FXPOSilPES (10,000s 0F MAN-RFMS) AND PROVIDE COST SAVIPGS OF $100 MILLIONS. o COMPLETED SEISM 0 TECTONIC RESEARCil IN NEW MADRID PFGION (DESCRIBED IN RIt. #1116) WilICH CONFIPMFD LICFNSING ASSUMPTION OF A CAPABLE STRUCTURE CAUSING THE 1811-12 NFW MADRID EART110UAKES. 6 da CI-4 l

DIVISION OF EPGINEERING SAFETY CONTRIBUTIONS OF PECENT RESEARCll HIGil-LEVEL WASTE o IDENTIFIED GE0 HYDROLOGY TECHNIQUE FOR CHARACTERIZING FRACTURES, MFASURING INFILTRATION AND PERCOLATION, AND MFASURING PERMEABILITY OF UNSATURATED FRACTilRED l ROCK (NilREG/CR-!655). i l o DFMONSTRATED THAT DOE NEEDS TO DFVFLOP THERM 0DYNAPIC GF0 CHEMISTRY DATA FDP i PADIONLICLIDES AT PEPOSITORY TEMPERATURES (T >25*C) (NilREG /CR-liS82). LOW-LFVEL WASTE l 0 DEVELOPED BASIS F0P EVALUATING FNGINEERED FEATURES OF SFVFRAL FN!!AFCEMENTS/ ALTEPNATIVES TO SHALLOW LAND PIIRIAL AND ASSESSED THETP RFLATIVE IPPORTANCF TO SAFETY (NUREG/CR l:701). i o DEVELOPED SITF CHAPACTEPIZATION PLAN FOR PREDICTING RAD 10FilCLTDE TI!ANSPORT AT A LOW-LFVFL WASTE SITE BASED ON ITMITED FIELD MFASilRFPENTS. RESULTS OF A TRIAL ST jh Tilf AECL CIIALK RIVER FACILITY SHOWED GOOD CORRELATION BETWFFN PRFDICTFD TPANSPORT ld AND ACTUAL RADIONitCLIDE MOVFMENT AT THF SITE. CI-5

~ THERMAL-HYDRAULICS l 1 0 TOP PRIORITY IS THE EVALUATION OF SAFETY IMPLICATIONS OF COMPLEX OPERATIONAL TRANSIENTS IN B&W DESIGNED REACTORS INCLUDING: TESTS AT MIST IN ALLIANCE, OHIO, AND THE CONTINUING EXPEPIMENTAL CAPABILITY AT INEL TO IMPROVE COMPUTER CODE MODELING OF B8W TRANSIENTS. ANALYSIS OF OPERATOR RESPONSE TO LIKELY B&W PLANT TRANSIENTS INCLUDING THOSE COMPLICATED BY MULTIPLE EQUIPMENT FAILURES. O PROPOSED REVISION OF APPENDIX K WOULD ALLOW REALISTIC BEST ESTIMATE EVALUATIONS OF ECCS PERFORMANCE AND UNCERTAINTY ANALYSES AS AN ALTERNATIVE TO CURRENT RESTRICTIVE EVALUATION MODELS. O EXPERIMENTAL PROGRAMS IN COOPERATION WITH INDUSTRY AND FOREIGN PARTNERS (?D/3D, ROSA IV, MIST) WILL PPOVIDE DATA TO SUPPORT IMPLEMENTATION OF REv! SED APPENDIX K AND TO SUPPORT VALIDATION OF NRC COMPUTER CODES, TRAC AND RELAP, AND EVALUATE INDUSTRY CODES FOR ADE00ACY IN ACCIDENT ANALYSIS. O THE PRINCIPAL CODE VALIDATION EFFORT IS THE INTERNATIONAL CODE ASSESSMENT PROGRAM (ICAP) INVOLVING 14 FOREIGN PARTNERS. O RESEAPCH GOALS ALSO INCLUDE: 6 - CONTINUING EXPERIMENTAL CAPABILITY. ($ - SUPPORT TO BNL FOR BWR ANALYSIS CAPABILITY. - CONTINUED SUPPORT TO UNIVERSITIES. CII-2

IMPACT OF A 107. PUDGET CIIT - DRSS THFPMAL HYDRAULICS O REDUCE DATA ANALYSIS ON ROSA IV TESTS ON STEAM GENERATOR TURE RUPTURF, STFAMLIFE BREAKS AND OPERATIONAL TRANSIEPTS 0 REDUCE SUPPORT TO 2D/3D PROGRAM IN ANALYSIS OF ECCS TESTS AND OUR CAPABILITY TO PESPOND TO POSSIBLE PECURRING INSTPUMENT PROBLEMS 0 ELIMINATE SG TUBE RUPTURE TEST DATA ANALYSIS O ELIMINATE MUCLEAR PLANT DATA BANK PROGRAM SEVERE ACCIDENTS O REDUCE IN-PILE TESTING IN NRU AND ACRR TO QUANTIFY F.P. RELEASE, HYDROGFN GFNFRATION AND CORE MELT PROGRESSION O REDUCE HIGH TEMPERATURE FISSION PRODUCT DEPOSITION AND REVAPORIZATION EXPERIMENTS O ELIMINATE NRC PARTICIPATION IN TMI-2 FUEL EXAMINATION LEAVING RESPONS!RILITY WITH DOE 4 ELIMINATE TRAP-MFLT CODE VALIDATION ON TRANSPOPT AND DEPOSITION OF AEROSOL IN RCS n b CII-5

4 \\ IMPACT OF A 10% BUDGET CUT - DRSS (CowT'D.) RISK AND RELIABILITY, RESEARCH l o ELIMINATE RMIEP FOLLOW-ON STUDIES TO ANALYZE CONTROL SYSTEM FAILURE AND SEISMICALLY INDUCED FIPE EFFECTS IN PISK ASSESSMENT o ELIMINATE SUPPORT OF NUCLEAR POWER SAFETY RFPORTING SYSTFM (A THIPD PARTY HUMAN PELIABILITY DATA REPOPTING SYSTFM) O REDUCE EFFOPTS TO FACTOR THE EXTENS!vE DATA BASE GENERATED FOR NUREG 1150 INTO APLLICATIONS OF CONSEQUENCE AND RELIABILITY ANALYSES l l LN CII-6

RISK AND RELIABILITY ANALYSIS O PUBLICATION OF DRAFT NUREG-ll50 IN JANUARY 1987 WILL PROVIDE TECHNICAL BASIS FOR: IMPLEMENTATION OF SAFETY 60AL POLICY IMPLEMENTATION OF SEVERE ACCIDENT POLICY STATEMENT UPDATES OF SOURCE TERMS TO SUPPORT REVISION TO REGULATORY REQUIREMENTS SUCH AS THOSE ON EMERGENCY PREPAREDNESS, SITING, EQUIPMENT DUALIFICATION O POSSIBLE SUPPLEMENTARY SAFETY GOALS ARE BEING EVALUATED INCLUDING: CONTAINMENT PERFORMANCE DESIGN OBJECTIVES THE GOAL THAT PPOBASILITY OF LARGE RELEASE BE LESS THAN 10-6 PER REACTOR YEAR O APPLICATIONS OF PROBABILISTIC RISK ASSESSMENT TO THE REGULATORY PROCESS ARE BEING DEVELOPED: PERSONAL COMPUTER BASED SYSTEMS (PRISM AND SARA) TO USE PRAS IN PLANT INSPECTIONS AND COST BENEFIT EVALUATIONS OF GENERIC REOUIREMENTS RISK BASED PERFORMANCE INDICATORS USE OF PRA IN ESTABLISHING TECHNICAL SPECIFICATIONS O IMPROVED METHODS FOR PERFORMING PRAS ARE BEING DEVELOPED IN THE FOLLOWING AREAS: HUMAN RELIABILITY MODELING AND DATA f3 COMMON CAUSE FAILURE QUANTIFICATION EXTERNAL EVENTS (FIRES, FLOODS, SEISMIC) {- CII-4

ACCIDENT EVALUATION O THIS RESEARCH PROVIDES: l CAPABILITY TO EVALUATE FISSION PRODUCT RELEASE AND TRANSPORT DURING SEVERE ACCIDENTS. QUANTIFICATION OF THERMAL AND PRESSUPE LOADINGS ON CONTAINMENT. SUPPORT TO ESTIMATION OF RISK IN NUREG-1150. SUPPORT TO IMPLEMENTATION OF SEVERE ACCIDENT POLICY STATEMENT AND THE SAFETY GOALS. O SPECIFIC SEVERE ACCIDENT ISSUES TARGETED FOR RESOLUTION ARE: DIRECT CONTAINMENT HEATING FROM HIGH PRESSURE CORE MELT EJECTION. CONTAINMENT LOADINGS FROM HYDROGEN COMBUSTION. REVAPORIZATION OF PREVIOUSLY DEPOSITED FISSION PRODUCTS. EFFECT OF CHEMICAL FORM OF IODINE ON SOURCE TERMS. NATURAL CIRCULATION OF COOLANT DURING CORE DEGRADATION. MODELING OF IN-VESSEL PROGRESSION OF CORE MELTING. EX-VESSEL INTERACTION OF MOLTEN CORE WITH CONCRETE. STEAM EXPLOSIONS. O RESEARCH GOALS ALSO INCLUDE: VALIDATION OF SOURCE TERM COMPUTER CODES. SUPPORT TO REVIEW OF ADVANCED LMR AND HTGR DESIGNS. CONTINUED SUPPORT TO UNIVERSITIES. O THIS RESEARCH IS BEING CONDUCTED IN COOPERATION WITH A NUMBER OF FOREIGN PARTNEps, EPRT, g) AND DOE AND INCLUDES ANALYSIS OF THE TMI CORF AND ACCIDENT. a4 CII-3

\\ l REGillATORY APPLICATIONS PROGRAM 1 FY88 ($K) o EMERGENCY PLANNING 400 o REVISION OF SITING REntJIREMENTS 400 o VAltlE-IMPACT METHODS FOR OTilEP TilAN NPP'S 700 0 SAFETY EFFECTIVENESS OF REGilLATIONS AND REG 11LATORY RE0tilREMENTS 500 o PEER REVIEW 0F PESEARCil PROGRAMS 100 $2,100 I 6 CIII-3 i

r RADI ATION PROTECTION AND llEALTil EFFECTS PROGRAM 1 FY88($K) FINALIZATION & IMPLEMENTATION OF 10 CFR 20 $150 RADIATION EXPOSilRE INFO REPOPTING SYS (REIRS) 100 BNL ALAP.A CENTER 50 $300 NOTE: N0 HEALTil EFFECTS RESEARCil 6 L CIII-4

i CH. ? PRINCIPLES OF NUCLEAR SAFETY RESEAPCH THE THREE MAJOR CUESTIONS: WHO SECULD FUND t!UCLEAR SAFETY RESEARCll? WHO Sl!0ULD SET THE RESEAPCil AGENDA? WHO S1100LD CONDilCT THE RESEARCil? O b D-2

t ~ IPPLICATIONS FOR DECISIONMAKING .t l CATEGOPY 1: RESEARCH ON CURRENT REACT 0PS TliAT IS AIMED DIRECTLY AT IMPROVING REGULATOPY DECISIONS CATECOPY 2: RESEARCH ON CURRENT PEACTOPS WHERE THE RESEARCH HAS SAFETY IMPLICATIONS EUT IS NOT I DIRECTLY IN SUPPORT OF RE6ULATORY DECISIONS CATEGORY 3: RESEARCH ON FUTURE REACTORS i [ O i 5 D-3

r h I GENERAL REf111REMENTS FOR THE DESIGN OF GOVERNMENT RESEARCH PP0 GRAMS l TO SUPPORT BASIC OP EXPLOPATORY RESEARCH i TO ENSURE AGENCY COPPETENCE TO ENSURE AN ADEQUATE NATIONAL POOL OF TRAINED SCIENTISTS AND ENGINEEPS i l t l b l L 8 D-4 1 ,,---,e ,r- - -. - + - -,-. - - - - +,, - - w. --e .. ~.. --.,-v -- - -.. - - - - -. - - -- ~ ~ - -. -,

l j WHO SHOULD CONDUCT NUCLEAR SAFETY RESEARCH i GOVERNMENT INDUSTPY i CONTRACT RESEARCH COMMUNITY, INCLUDING UNIVERSITIES AN INTERNATIONAL COOPERATIVE ARRANGEMENT l ALL COMBINATIONS OF THE ABOVE 1 ATTAINING BALANCE IN ALLOCATING RESEARCH DOLLAPS 1 .W 0-5 0 s

I 1 TAI 1LE 3 ELEMENTS OF A FUTURE AGENDA 0F NUCLEAR SAFETY RESEARCH CURRENT PLAPT DESIGNS EEHAVIOR OF MATERIALS IN NUCLEAR POWEP PLANT ENVIRONMENTS DECOMMISSIONING EXTENDED FUEL CYCLE HUMAN FACTOPS, INSTRUMENTATION AFD CONTROL, AND OPERATIONS NONDESTRUCTIVE TESTING AND EXAMINATION PLANT AGING (LICENSE EXTENSION) POLICY RESEARCH 00ALITY ASSURANCE /0UALITY CONTROL. PEEVALUATING EXISTING REGULATIONS PELIABILITY OF PLANT COMPONENTS AND PLANT SYSTEMS SAFETY ANALYSIS PETHODOLOGY AND APPLICATION SEISMOLOGY, S0ll MECHANICS, AND STRUCTURAL RESPONSE.TO SEISMIC EVENTS SEVEPE ACCIDENTS THERMAL HYDRAULICS FUTURE PLANT DESIGNS D b D-6

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L + v' L ~ 4 ~ I ' CONTRACTING FOR SAFETY RESEARCH -CREATE AIR COMPETETIVE SYSTErl FOR ALLOCATING RESEARCil. s /, -DEVELOP PROCEi',URES T0:F.AKE CONTRACTIFG AT OTHER ORGANIZATIONS _THAN NATIONAL LABS AN EASILY -?O.'AILABLE OPTION ~- k -NPC SHOULD CONDUCT CAPEFUL ANflYSIS OF COSTS IWD' BENEFITS OF OPT.10NS FOR CONSOLIDATING WOPK ~ Al NATIONAL LABC ~ -NRC SHOULD REQUEST EXPANDED GRANT AUTl!0RIT,Y WHICH SHOULD THEN BE FULLY USED. ~ I t l 1 l I N ls D-8

APEAS WilERE RESEARCH llAS BEEN TERMINATED, OR SIGFIFICANTLY REDUCED IN Tile LAST FEW YEARS HEALTH EFFECTS 8 RADIATION PROTECTION 110 MAN FACTORS ATMOSPilERIC (METEOROLOGY HYDROLOGY) FIRE PPOTECTIOP INSTPUMENTATION & CONTROL ELECTRICAL E0 FUEL CYCLE I SAFEGUARDS - SAPOTAGE h N 9 i ~ E-2

UNFUNDED PROJECTS - AGING & DEGRADATION IN 5'PP WELD RFPAIR OF STAINLESS STEEL 5 PROPOSED IN FY87 - NOT DONE DUE TO BUDGET CllTS; 1 IlYDR0 GEN ADDITION EFFECTS PROPOSED (AND IN, AT SUBMITTED LEVEL) FOR FY88 - MATERIALS INTEGRATION CENTER BUT CUT IN FY 88 10% PEDUCTION FIRE PROTECTION 1 ELFCTRICAL EQUIPMENT OllALIFICATION i PRESTRESSED CONCRETE CONTAINMENT-CAPABILITY PRESSURE STRUCTURAL AGING N0DillAR CAST IRON SillPPING CASKS PTSE EFFECTS OF CLADDING ON PTS l 63 l VT E-3

~ UNFUNDED PP0JECTS - THERMAL-ilYDRAllLICS ADEQUATE FUNDING FOR NEW INTEGRAL TEST FACILITY FOR B8W SIMULATION GENERAL UPGRADING IN 14E AREA 0F CONTINUED EXPERIMENTAL CAPABILITY CONDENSATION HEAT TRANSFER (UNIVERSITY PROJECTS) i CODE ANALYSIS OF SEVERAL ROSA-IV TESTS REQUESTED BY NRC IN ODDER TO PROVIDE DATA FOR CODE ASSESSMENT PLANT DATA FOR NPP DATA BANK QUALIFYING EXPERIMENTAL DATA FOR ECCS RULE REVISION 'l Eh i M E-4

ilNFUNDED PROJECTS - SEVERE ACCIDENTS FUNDING SHORTFALL IS BEING REVISITED - BUT INCLUDES WORK IN THESE 8 AREAS: 1 AREA 0F UNCERTAINTY NATURAL CIRCULATION IN REACTOR COOLANT SYSTEM 2. CORE MELT PROGRESSION AND HYDROGEN GENERATION 3. STEAM EXPLOSIONS II. IIIGil-PRESSURE MELT EJECTION 5. CORE-CONCRETE INTERACTIONS 6. IlYDROGEN COMBUSTION 7. 10 DINE CHEMICAL 8. FISSION PRODUCT REEVAPORIZATION i ) N i sa E-5

UNFUNDED PROJECTS - RISK 8 REllABILITY l CONTROL SYSTEM REllABILITY RESEARCil IlUMAN REll ABILITY ANALYSIS - SOME BEING DONE; NEED MORE IlUMAN FACTORS EXTERNAL EVENTS - SOME BEING DONE; NEED MORE 6 b D E-6

UNFilNDED PROJECTS - WASTE DISPOSAL - IIIGH LEVEL STUDIES OF Tile EFFECT OF MINERAL VARI ATION IN ll0ST ROCK ON llLW OVERPACK COPPOSION STl1 DIES OF llYDROGEN EMBRITTLEMENT OF HEAT-AFFECTED WELD ZONES OF IILW OVERPACKS RESEAPCil INTO REPOSITORY BEHAVIOR UNDER OFF-NORMAL CONDITIONS (SAFETY MARGIN STUDY) ANALYSIS OF COUPLED TilERMAL llYDRAULIC-GEOCilEMICAL P11ENOMENA IN llLW REPOSITORIES SEISMIC AND GE0TECl8MICAL RESEARCil RELATFD TO REPOSITORY DESIGN (Fl!NDED IN 88) 6 i N E-7 i D

S E E V V A I T l l A H K E N C R C R R T O N E A N F A T E E M L S M E R A E S T O R S S F R E E A R O T W S W E F S L S P A L A W A W L L I G E L A R L N C S E N A O T E I V W A P I E O M S S R L L R A I C L O D W O F E Y O F R T W T L E S L I 8 E P A L L I E W l i T R R B S O N O I T N F O F T C O I A E M T S P J S R A E M O T E N U O Q C T l R l I P O M I E A N G D H C T N l i E C R N C I D T U O E R N E O C T E U R S E E F T D D N N S G N I U N R A G D I W N N K L S E A R E E O F I S W O G T Y E I A A N T S L O A E Y F I R F D R O T T O A A S T S T Z T I G N N S N A E E R N EM C C M E I I E P T R P F N O C O O B I L A T L L N N E R I E S G E V A N V E E H O E O I S B D C M D T ,hO l

l UNFUNDED PROJECTS - MISCELLANE00S ~ VALUE/ IMPACT ASSISTANCE FOR PULEMAKING IN OTHER OFFICES i i SIGNIFICANT NEEDED RADIATION PROTECTION AND llEALTH EFFECTS RESEARCil RADIATION EXPOSURE INFORMATION REPORTING SYSTEM (REIRS) HAS BEEN GREATLY CURTAILED l 1 ] l f M E-9

GENERAL COtt*ENTS MATERIAL REVIEWED CONSISTED OF PACKAGE PRESEf1TED TO ACRS IN 5/86 Af1D 6/86, A NOVEMBER 12,1986 FIN LIST, AND DRAFT PRESENTATION PATERIAL FOR DECEMBER 10,1986 PRESENTATION TO ACRS. FURTHER NRR REVIEW WILL CONTIrlUE AS SPECIFIC RES IM'LEMEffrATION PLANS ARE DEVELOPED. PROPOSED RES FUf0ING PLANS FOR FY88 APPEAR TO COVER PAJOR NRRflEEDS. SCOPE NO FUNDING LEVELS OF RES PROGRAMS APPEAR GENERALLY ACCEPTABLE. SOME SPECIFIC CONSIDERATI0flS FOLLOW. NRR POSITION ON PROPOSED CUTS TO ACC0ft10DATE A 10% REDUCTIOf1 IN FY88 HAS NOT BEEN ESTABLISHED DUE TO TIME CONSTRAlt(TS. 3 -32/

SPECIFIC CONSIDERATIONS IN REVIEW OF THE FY88 RES BUDGET THE FOLLOWIf!G ITEMS SHOULD BE NOTED: NO FY88 FUf0 LNG IS IDENTIFIED TO REStPE RESEARCH WORK Ill THE AREAS OF FIRE PROTECTION, EQUIPMENT QUALIFICATION OR HYDROGEN GENERATION IF THE RESULTS OF STUDIES IN FYS7 IFOICATE SUCH WORK IS NEEDED. IT IS NOT APPARENT THAT ALL CODE MAlifTENANCE ACTIVITIES, REQUESTED BY NRR Ili THEIR MEMCRANDUM OF SEPTEMBER 23,1986, ARE FUt0ED Ill THE FY88 RES BUDGET. FURTHER FOLLOWUP ON THIS CONCERN IS PLANNED. D -33

O OmER CONCERNS A PROPOSED PRIORITIZATION OF RES PROGRAMS HAS NOT BEEN PROVIDED TO NRR FOR REVIEW AND APPROVAL, ORIGINAL TARGET DATE WAS JULY 1, 1986 SLIPPED TO OCTOBER 1986 NKR CONTINUES TO CONSIDER PRIORITIZATION OF RES PROGRAMS VERY IMPORTANT FOR: ESTABLISHING AN AGREED UPON BASELINE FOR FlITURE CHANGES HELPING TO QUANTIFY THE IMPORTANCE OF THE VARIOUS PROGRAMS &-34k

9 NRR REQUESTED If! A SEPTEMBER 22, 1986 PEliORAt0UM TO PES THAT NKR BE GIVEN THE OPPORTUNITY TO CONCUR ON FUTURE INTERNATIONAL AGREEMENTS (OR EXTENSION OF EXISTING AGREEMENTS) FOR COOPERATIVE WORK. THIS REQUEST WAS MADE TO HELP ENSURE THAT FUTURE AGREEMEKrS: ADDRESS AREAS OF REGULATORY CONCEPJ4 ARE NOT SO bit 0!NG AS TO FORCE THE DEFERRAL OF OTHER HIGH PRIORITY WORK IN THE TIME OF TIGHT BUDGETS l-AV0PABLE RES RESPONSE RECEIVED OCTOBER 1,1986. SPECIFIC PLANS FOR C00RDINATICf; 0F THIS ISSUE BY RES AND NRR ARE EXPECTED TO RESOLVE THIS CONCERff. D-3C

TECHNIC AL ASsisrAuc e Proc, nan sa Msg. NRR FY87 APPROVED FIN PLAN Decision Unit Approved Budget Operating Reactors $13,132,000 Systematic Safety Eval. 200,000 of OR's Operator Licensing $ 2,267,000 License Reviews $ 4,635,000 Safety Technology $ 6,879,000 TMI-2 Cleanup 245,000 TOTAL $27,358,000 D-36 N

i t. l 'd ' RESEARCH AND TECHNICAL ASSISTANCE -RELATIONSHIP 0 i t.. RES TA UNDERSTANDING PHENOMENA LICENSING QUESTIONS LONG-TERM RESULTS SHORT-TERM RESULTS GENERIC OR SITE-SPECIFIC GENERIC t l t t Il ! 4 f t t l' g 4 g it, 'i b l ,~ 6 a t .1

I e TECHNICAL ASSISTANCE PROGRAM ACTIVITIES HIGH-LEVEL WASTE CONTRACTS i fcchnical Assistance Technical Methodology Confirmatory %rca Expertise Development Data Gathering i iydrqlogy 60% 40% hochemistry 50% 20% 30% 3eology/ Geologic Stability 80% 20% as'te, package 50% 30% 20% Msign/ Rock Mechanics 80% 20% )artormance f Ashdspment 30% 70% ]u,ality Assurance 100% .1 censing Support 80% 20% l I W m i' 'g

- 0 1 i { i 1 i DIVISICN OF WASTE f'ANAGETEIT .i LCW LEEL WASTE USER f!EED STATEiET FOCUS OF RESEARCH ECRK: 1.- SCLRCE TER1 E/ALUATICNS i l 2. STUDIES CF LLW ALTERNATIVES 'f 3. LESSCNS LEAFfE FRCX EXIST!f'G SITES k i l j i i i 5 4 4 4 4 i i D -3 0 J ~,-.--.-

-_ -- -._._-.~ o o" i PESEARCH C0hTRACT EUDGET I $K FYE6 FY 87 FY88 4 SOURCETEPf1 750 1,120 1,200 i ALTEFFATIVES 275 619 997 F LESSOfG LEAFFED 100 470 SCO PEPT-0PFAf!CE ASSESSIDT 020 425 1,000 1,545 2,634 3,997 I k i f D-40

,o. 3-s -6 J I e A J 4 LCW-LEVEL PASTE TECHNICAL ASSISTANCE BLT;GET $K FY 87 FYCf LLFFPAA 1,540 1,100 l GTHER REGl'LATC8Y ACTIC.N 260 ICO CASEWORK 290 870 LOW-LE'EL WASTE TOTAL 2,C70 2,070 .i i

• ESTIFATES h

a l r i <.0-m . ~.... _ _ _ _ _ _ _ _ - _, _.. -,, _ _ _ _ _ _ _. _ - _.,

o gs-LCW LEVEL !cSTE TECHNICAL ASSISTANCE FF0JECTS FIN Fo TITLE CCf!TPACTOR LLFWPPA LICENSING REVIE'/ CAPABILITY. A6188 LLW DATA BASE EE'ELOPiBiT-EPICOR EGM B2483 DEF. OF SOLLTE TPAfiS FEO'ANISBS FNL E2405 PEFF0FFANCE ASSESS: bit FFL ALTEFNATI'ES A3176 PEV. OF CRITERIA FCR FATERIALS ENL B2484 EhVIEGtFE.TAL FONITCP!fG EAIItLLE D1071 TA - DEV. ENG. CRITERIA A 0 RECS CCE DATA BASE A61CO CCM TN DATA BASE - DISPOSAL PECCFDS EG8G E6599 LLRW RECCFDS O!EM NUCLEAR B7CCO LLE'd RECCPDS USE Oil!ER REGULATOPY ACTICNS TED BICHAZAFICl>S WASTE TED CAS&,CRK A3175 ANALYSIS FCR SPECIAL 't.'ASTE FF0ELEFS ENL A3174 [EV. CF LLW FCFM CRITERIA DL D -42}}