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Research Results Utilization Status Summary Report.Data as of February 1,1978.(Buff Book)
	ML20195J579
Person / Time
Issue date:	02/01/1978
From:	; NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	;
References
	NUREG-0435, NUREG-0435-V01-N01, NUREG-435, NUREG-435-V1-N1, NUDOCS 8812020277
	Download: ML20195J579 (38)
	v • d • e

- _.. -. _ - - - _ - -.. - -

NUREG-0435' A $$ OF: 52/01/78 I

l OFF!CE OF NUCLEAR l

REGULATORY RESEARCH l

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1.0 I N T RODUC T I O'4 3

2.0 RESEARCH INFORMATION LETTERS (RIL'S) AND SCHEDULING POST RIL ACTIVITIES 3

2.1 I.IST 0" ISSUED RTL'S 4

2.2 POTENTTAL APPLICABILITY OF RESEARCH RESULTS IN THE REGULATORY PROCESS 24 3.0 PROJECTED NEAR TERM RESEARCH INFORMATION LETTERS

l 1.0__191RD02C110N THIS REPORT 04 "RESEARCH RESULTS UTILIZATION" PROVIDES STATUS AND CONIROL INFORN ATION COECERMING THC UT ILIZ ATION OF RESEARCH RE5utTS IN THE REGULATORY POLICIES AND PRACTICES OF THF NRC.

P.LSE&&Eli_IMLDEBAIIDM_LEILL15 -- IRIL*5) ARE PREPARED dY RES TO TR ANSMIT RESEARot RESULT 5 TO NRC USER OFFICES UFON COMPLETION OF A SUBSTANTIAL, CDHERENT AND RE A504 Arty COMPLE TE BODY OF FXPERIMENTAL AND/OR ANALYTIC AL RESE AECH ' uRK.

A RIL MAY COVER MATERI AL DEVELOPED FRDM MORE w

TH AN ONE RESE ARCH PROJECT. THE USER / PROGRAM OFFICEISI IN THE NRC REVIEW THE I NFORM AT ION CONT AI NED IN THE RIL AND CONSIDER ITS UTILIZAIION IN THE REGUL ATORY PROCESS. SFCTION 2.0 OF THIS REPORT LIST 5 THE RIL*5 ISSUED TO DATE. TDGETHER WITH AN :DENTIFICATION OF THE Rf5E ARCH PROGR AM MANAGER AND THE RESE ARCH PROGR AM ELEMENT WHICH GENERATED THE RIL.

THE POTENTIAL APPLICA81LITY OF EACH RIL TO THE REGULATORY PROCESS IS ALSO IDENTIFIED HERE. AND COM#ENTS FROM THE COGNIZANT RES AND USER OFFICE ST AFF ARE SUMMARIZED WHICH REL ATE TO THE E PECTED IMPACT OF THE REPDRTED RIt's ON THE RE GUL ATORY PROCE SS.

WHrRE DEEMED APPROPRIATE BY MUTUAL AGREEMENT BETWEEN RES AND OTHER INVOLWED SRDGRAM OFFICES A *051TIO7 PAPER MAY BE PREPARED TO INFORM THE COMMI1$104 ABOUT THE P9TENTIAL APPLICATION OF RESEARCH RESULTS. BRIESINGS MAY BE CONDUCTED FOR THE COMMISSION.

THE ADVISORY COMMITTEE ON REACTOR SAFEGUARD 5 IACR$1 04 OTHER APPROPRIATE GROUPS. PRESS RELEASES MAY AL50 SE MADE. A5 APPRGPRIATE.

THESE EVENTS ARE SCHEDULED AND TRACKED IN THIS SECTION.

A LISTING OF ALL RIL'S THAT "AY BE GENERATED IN THE NE AR FUTURE 12 OR 3 YEAR $5 IS PRESENTED IN SECTION 3.0 THE SUBJECT. TITLE. IMPACT. TARGET DATE. AND RESEARCH REVIEW GR OUP NURSER. TITLE AND CHAIRMAN ARE SHOWN FOR ESCH RIL.

f RES 15 RESPONSIBLE FOR DISTRIBUTING EACH NEW RIL TO COGNIZANT OFFICES AS THEY ARE I55UED.

RES AND OTHER COGNIZANT PROGWAM OFFICES ARE O8 LIGATED TO COLLECT. REVIEW. AND FORWARD APPR OP R I A T E INFORMATION RELATING TO RILS AND ASSOCI ATED FOLLOW-UP ACTIONS TO MPA.

MPA Is RESPONSIBLE FOR REFLICTING NEW INFORMATION IN THIS PUBLICATION AND PRODUCTION AND DISTRIBUTION OF THIS PURLICATION 04 A DUARTERLY SCHEDULE.

ALL COMMENTS SHOULD BE FORmARDED IN WRITING TO:

DIRECTOR. MPA MAIL STOP 12105 MN88 ATIN:

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DalL_115ULD1 6/28/T6 W _EROGRAm FirpE31 PRIMARY SYSTEM INTEGRITY EIL_111LE: CONFIRMATG4Y PRES $URE WESSEL TEST UNDER PNEUMATIC LOADING. IORNL H55T F ROGR AMI 1ED313313G_CLEICE111 RES REG 820-vE55EL INTEGRITY BESEAECH PROJECT MLE:

E.F.trw EL1_L335E311 RIL*5 Is 3 C *> REPORTED THE RESULTS FRCM THE HEAVY SECTION STEEL TECHNOLOGY PROGRAM WHIC*4 5HOWED THAT THE ANALYTICAL ME THODS FOR PREDICTING FL AW INITIATION AND CRACK hAREST IN REACTOR PRESSURE WESSELS HAVE PEiN WELL VALIDATED.

THESE WALIDATED ANAlff! CAL MCTHOC'S ELINrAR ELASTIC FRACTURE MECHANICS AND ELASTIC-PLASTIC FR ACTURE MECHANIC 53 ALLOW A PhEDICTION OF THOSE CONDITIONi UNDER WHICH FLAWS IN PRES 5URE WESSEL STEEL 5 CAN CAUSE F AILURE OF THE vf 55EL.

THIS PR3 TIDES THE NRR STAFF WITH A NEW TECHNICUE FOR SETTING SAFE LIMIT 5 FOR neORMAL OPERATION AND FOR ABNORai.L AND ACCCIDENT SITUATIONS TO REDUCE TM1 LIKELIHOOD OF PRE 55URE WESSLE F AILURE.

USER DISC *d 5 ION POSITION COPMISSION ACRS PRESS OFFICE MEETI%

PAPER BAIEFING BRIEFING RELEASE RESULT 5 ED51_EIL_ACI1Y11115 EEVIEW HF1 D CQIIELETED UF 1 B tif s 0 liturn M EEgEg1ED OF F ICE R ESPONS I BL E......... N R R "fRR SCHEDULED COMPLETION LATE.. --

UNSCHED UNSCHED UNSCHED UNSCHED Ufe5CHED UNSCHED ACTUAI COMPLETION DATE..... UNK 1976 CD98LM15_LROHJWER_RI1_J._EX1031_Dau_12Z1&LII -

DELL EIAL_AEELICA11DM.1D_1LG ULAIDEI_ERQCE55 : THE INTERMEDIATE YEST WES>ELS. IYW-T Aas0 ITv-TA uneDER SU5TAINED LOADIE DEMONSTRATED THAT FOTH THE VE55LL5 RESPONOED TO PseEUMATIC LDADING ESSENTI ALLY A5 THEY HAD TO HYDRAULIC i

LOADING. EARLIER EXPERIENCE OF A R APID CR ACK E XTENSION IN THE GAS PIPE LIseE WAS INHIBITING THE ACRs 1

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HENCE. THE PNEUMATIC LOAD TEST WA5 SUM ESTED.

4 DL5011EE_15EAC1 DE_EE5LiL15: THESE TESTS SHOW THAT THE WESSELS UNDER SUSTAINED LOADING SEHAVED SIMIL ARLY TO 3

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THE TWO VE5SEL TEST 5 THAT RUPTURED, WITHSTOOD PRES 5URE 2.15 TO 2.75 TIMES DESIGN PRES $URE.

T HE f t 51r PRESSURE 5 WERE ABOWE A5ME 8 C P W CODE ALLOW 48tE FOR F AULTED CONDITIONS.

CDm!E311LELBARE$s TEST 5 DEMONSTRATE THE LEAK WITHOUT FURST.

CDenLMTi f RD8_$D_EIL_E,_EAbD ALL DgL.Q2/21/13 -

THIS TEST RESUL T AND THE ONE ON v-T IRIL 838 ARE U5EFUL IN SHDRING TriAT SURST STRAIN IN FAILURES 04 THE l

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8/25/76 ELS.EEDCEAE_LLLEL3It F ST BREEDER REACTORS EIL_IIILL: THE SIw*Em CODE Fca ANatv515 Or HvPOTHETIC AL CORE DI5RU8 *lWC ACCIDENTS IN LMFER*5 f*.353E13G_CELILL111:

NRR Edi:

86P-5tP rR CcDE FL5LAECu_EEDJELI enE R. CURTIS EL1_03*EL31$1 THE SIP"fR CU^E IS Or51GNrp to PRc0ICT THE Mofl04 OF FAST REACTOR CORES DURING POTENTIAL CCRE DISRUPTIVE ACCIDENTS.

A TPIAL VERSION OF THIS CSOE WA5 MADE AVAILABLE TO NRC'$ LICENSING STAFF AND HAS SUPPORIED NRL 88ANCH P0 5 f T I G.4 5 GN IHE ANAlv5i5 OF CORE DISRUP!IVE ACCIDENIS FOR CL INCH RIVER BREEDER RE AC TOR LICf451NG CON 51CTRATILN5.

51PmFR 15 diCOGNIIED A5 AN IPFORTANT FIR 5' STEP IN THE DEVELOPPENT OF A MECHANISTIC CUDE *APABtt OF DESCRIBING PHENGMEN6 NffDtD TO ASSESS CPRE DI5RUPi!VE ACCIDENf5 1N LIQUID METAL FAST BREEDER RFACIOR$.

USE R 015CU551DN POSIT!ON 00PMI5510N ACR5 PRESS OfrgCE PEETING PAPER nRIErlec BRIEFING RELEASE RE SUL T 5 EDil_RIL ACIIVIIILL

'EMILu ULLD LQ"ELLIED uLLD urto li1ULD.

IEELL5L3ILD Of f !CE RtSPONSIBIE......... NRR NRR

?.CHr 7JLE D COMPL E T ION tsATE.. --

UNSCHED UNSCHED UNSCHED UN5CHED UNSCHED 1976 AC T uat COMPLETION CATE.....

uNE 1976 LSE504I5_LEC5_ HEE _dII_E._0L3151/I. 5EL11_U31_3I2LII -

CLLC31BL AffLIC111C3_IC_&LSULAICEY_EERCL51:

THE SUBJECT RIL ANNOUNCED THE AVAILABILITY C5 THE $1PMER-1 CODE.

THE SJa9TR-I CODE 15 RECOGNif19 Sy Nem 45 AN I* PORT ANT F IRST STEP IN THE DEVELOPMENT OF A PECHANISTIC CODE CAPABLE OF Cf50RIBINO RECRITICALITV. TRANSITION PHASE PHENOMENA, AND WORK ENERGY P AR T I T I ON, ALL VITAL TO ASSESSING CORE D I 5' UP I I VE ACCIDENTS IN LMFBMS.

CELLBIBL_1Ef&LI_UL.EL1CLIL:

THE*E 15 NO IPPACT SINCE RESULT 5 USING THE SI* DER-I CODE ARE NOT SUFFICIENTLY SUBS T ANII AT ED TO BE USE D Df NECTLY IN THE LICENSIN; DECISIONS F OR LPFER'5.

IT 2 5 ANTICIPATED THAT FURTHER CODE DEVELOPMENT, AND THE P[RF C9 PANCF OF EAPERIMENT5 WHICH CONF IRM THE COMPUTATIONAL PDDEL5 WILL VIELD A TOOL WHICH WILL BE USEFUL IN REACHING SIGNIFICANT LICENSI.JO DECISIONS.

LD55L315/EL5&ECL: Ndd VIEWS IHE S I'mE R PROGRAM A5 AN IPPO4fANT L DN; TERM EFFORT TO DESCRIBE THERMAL AND MECHANICAL CORE DI5RUPTION ACCIDENT 55CUENCES.

NRR ALSO SEES NE AR-TERM nENfFIT IN USING SIMMER TO BETTEP UNDERSTAND REY PHENCMENA, AND THE INIcGRATION OF THESE PHE N0'E N A INIO AN ACCCIDENT SE QUE NC E. SIMPER ALSO HAS THE SENEFIT CF BEING I i*Gk LV I NCE PENDENT OF ECDA SPONSORED kORR.

NRR HA5 BEEN IN CONSTANI COMPUNICATICN WITH AR5R AND HAD INiilATED A S*ALL T.A.

EFFORT WHt0H MAKE5 USE OF $1MMER.

NRR STAFF HAVE ATTENDED SIMMER WORRSHOPS AND BRIEFINGS ON 9/14-15/76 4/19/77 AND 7/21-22/71.

NRR CURRESPONDENCE REL ATED 10 SIPPE R AND SIMMER-REL ATED WORK CONCUCTED BY R$R:

I.

TO $AUL Lfv!NE, RES FROM B.

RUSCHE. NRR, "imFBR SAFETY Rf5EAPCH PROGRAM PLAN *, 3/15/77.

i. TO L.

5. KU9ENSTEIN FR"9 R.

P. DENI5C. "DEGREE Or SUPPORT F OR RESEARCH PROGR AM5 FOR ADVANCED REACTOR 5".

1/6/77 4CC. TO C. MELBEpl.

I 3.

TO E. G. CASE FROM R.

P.

DENISE, *NRR COPMENTS TO ACR5 DN AR5R PROGRAP", 7/15/7T.

4 l0 SAut LEWINE. RES. F804 E. CASE. 444 "RES INFORMATION ON THE UNDERSTANDING OF CDA ENERCPTICS IN LMF84'5".

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DalL_li1ULD2 3/I4/FF EL5_EECGER5_LLL"LSI: EUIEL BEHAVIOR EIL_111LL: HIGH TEMPE R ATUR E DEID A TIUM CF ZIRC ALGY FUEL CL ADDING IN STTAM LECMLOE13G_CLLILL1513 RES EE3* SS-IIRCAt0Y CLADDING EL1L&ECH_EEQJLLl_ ELE:

M. L. PICRLESIMER EL1_C3*ELSI5: THE RE POR TE D #F $ut i5 IM6 ROVE 00R UNDERSIANDING GF THE BEHAVIOR OF ZIRCALOY FUEL CLADDIMG IN AN TNVIR3N*ENT REPRESENTED MY A LOS5 0F COOLANT ACCIDENT ILOCAI.

THEY INDICATE ? HAT THERE WOULD SE SIGNIFICANTLY LESS DEPTH OF EwCRITTLEMENT IN THE FUEL CLACDING Wall. CALCUL ATED FOR ANY POSTUt ATED LOCA AND *0RE W ALL MATERI AL WILL BE LEFT WHICH IS CAPAP.LE OF SUSTAININS LOADS L ATER IN THE SECUENCE OF SUCH AN ACCIDENT. THIS INFORMATION TOGETHER WITH D AT A 04 THE RATE Of GROWTH OF 04tDE A43 ORYGEN - STABILIlED LAYERS IN CLADDING. PEDVIDE5 A MORE SCIENTIFIC BASE FOR ES I ABLISHING F UE L C(AD f*HRITTLEMENT CRITERIA FOR E ME R GE NCY CORE COOLING SYSTEM ACCEPTANCE.

THESE RESULTS CONF #M THAT THERF 15 A OfGRFE OF C ON SE R V A T I SM IN IHE EVALUATION MODEL BE14G USED BY THE REGULATORY STAFF FOR C AL CUL AT ING THE 0x tD A TION OF ZIRCALOY D UR I NG A POSTULATED LOCA.

THIS INFORMATION IS BEING CONSIDERED AS A PARTIAL BASIS FOR MODIFICATION OF THE PRESENT ECCS RULC IIDCFR 50. APPENDIE KI.

Rit's 8 C9 ARF BOTH UNDER CONSIDEpaTION BY NRR FOR P0 5'. t B L E INCLUSION IN A MDDIFICATION TO THE EMERGENCY CORE COOLING SYSTEMS IECCS)

PUL E Pp0V!7ED IN APPENDIX R OF ID CFR 50.

THESE R!L'S Rf PORTED ON COMPL ETED Rose ARCH PROJECT 5 IN FI5510N PRODUCT D E C.U HEAT AND f!RCAt0V OEIDATION WHICH RESULIED IN DATA BASES AND CORREL ATIONS WHICH INDIC ATE THAT THOSE IN CURDENT USF IN THE ECC5 PULE ARE HIGHLY C ON SE R V A T I VE. A COMMISSION PAPER WAS PREPARED ISECY 77-3685 ON JUL Y I.

19 F F.

PRESENT STAFF PP.0GRESS ON A PROPOSED ACTION PLAN REGARDING POSSIBLE MDOIFICATION TO THE ECCS

UL E.

AND THE C0"MISSION PAPfR (SECY F9-26) PR E SENTING THE TRCPOSED ACTICN PLAN WA5 PREPARED ON JANutRY IB. 1978 RIt s9 HA% BEEN REw!EWED BY NRR, NM55, IE. AND SD.

THIS MA7FLIAL WAS INCLUDED IN THE BR IE FI NG Cr THE ACR 5 FULL CUwMITTEE BY NRR IN SEPTEM9ER. 1977 CONCERNING A POSSIBLE REVISION OF APPCNDIX R l

IO CFR 50.

THE ACR5 DISCOURAGED A R[ VISION CF THE ECCS RULE AT THIS TIME.

tf 5ER DISCUSSION POSITION CO* MISSION ACR$

PRESS "FFICE

EETING PAPER BRIEFING BRIEFING RE LE ASE

ESULTS ED51_EIL_ AC11Y111LS

!LY1LW uiLD CCSELLIED utto l

OFFICT RESPON51etE......... NER NRP ull D liiULD_

15EIFMrNILD kR9 l

' E HE DUL E D COMP L E T I ON DA T E.. --

uN SCHt 9 DEFERRED 9/0/77 UNSCHED UN5CHED 1973 i

ACTUAL CCMPL E T I ON Da T E..... UNE 9/10/T7 1978 1

LDEELNL5_LEC5_3EE_ EEL _D..ED55_D%L_2l23/11 -

L LiC E LB L_A EELital101_ID _ELG UL&l0EI_EECLL512 1.

nee DATA MAY BE CONSIGERED AS PACT I AL BASIS FOR MODI FIC ATIONS OF PRESENT (CCS ROLE II0 CFR 50. s'PENDIX RI.

1.

NEW DATA MAY BE USE D IN "PEST E57! MATE" COIFS THESE CODES ARE INTENDED TO BE USED IN

fOBASILISTIC A55E55 MENT 5 UF SAFETY M AR GI NS,

CELC215L_1EEACI_CL_ELLUL11 1.

NE m DAT A CONFIRMS MARGIN ALLOTT ED IN PRESENT E005 RULE I5 r045ERvATIVE.

2.

IF ACCEPTED FOR USE 11 LOCA LICENSING CALCULATIONS. VENDOR 5 CO9LD USE ADDITIONAL MARGIN IN DESIGN II.E..

INCREASE PEAK KW/Fil.

CC55Lh15/EL"LELL: CPTION FOR CHANGINS PRESENT ECC5 ROLF NA5 DISCDURAGED BY ACRS.

INITIATION OF RULE CH ANGE M95T BE DECIDED Bf THE COMMISSION.

CCE"L115_LE05_5D_tt1_f._EA301 LEA _D M 2222411 -

IF PROPOSE D PL AN F OR EEC5 RULE CH Ara;E IS APPRevE D BY THE COMMISSION. 50. IN COORDINATION WITH NRR AND RES.

WILL IMPLE ME NT THE AULE CHANGE PpOCE55.

l 13 l

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~ PED;E65_DELICE LDetE011.D3_EDIE511&L_U11L11A11DfLD&_MALUL.0a RL5EARLtLEFw M fa TMF REr.uLAIDE.V PaarF u EIL_ft to D&IE 151ULDt 2/25/FT ali_ERCf.E&B_ELEBLMis 415st ASSESSMENT / PRIMARY SYSTEMS INTEGRITY 11L_111LE: PRE 55URE WE55EL F AILURE P?OSA8te.1TV PAEDICTIO8e LEC319El%_DLLILL111 RES REGs s20-4C55EL INTEGRITV REiLARCH ?ROJFtf NCE:

w. WESELY EL1_LDaggE315: OCTAVIA I5 A CDmPUTER CODE FOR PREQICTING F AILURE PR0f" (ILITIES IN RE ACTOR PRESSURE WESSELS AS A FUNCT ION 0F TEPPEtt.TURES AND PRT554RE S TH AT MIGHT OCCUP DURING ST AR's P AteO SHUTDOWN OPER ATIO885. USECTS OF MAT [RI AL PROPERTIES AND OPER ATI% nGE wHERE ALSO INCLUCEO. THE RESULT 5 INDICATED THAT ExtSTI M 5AFETY MARGIses COULD SE SIGNIF ICANTLY REDUCED WI TH C0setINuro AGIE g AE5ULTi% IN RADI Af f 04 sp8tRITTLE*!ENT S OF THE REACTOR VE5SEL.

tF CHE RATE OF OCCU*RENCE OF OVERPJE55URE EVENTS CopeTINUE5 TO BE SIMIL AR TO THAT PREVIOUSLY OBSERVED. FURTHER TMPROVEMENTS IN THE C0JE ARE REPORTED e, iN RiL it.

THtSE RESULT 5 ERE USEo BY NRR oURi.ec THt5,AST YEA. IN

EVIEWI E THE PROBABILITY OF FAILURE OF RE ACTOR PREISURE WESSEL5 DUE TO SUCH EVENTS Asso To CtvE GUIDAseCE ON PLANT IMPR0vf MENTS THAT M AY *E NEECED. THEY MAY ALSO SEComE THE BASIS FOR REVISI'et REGUL ATORY GUIDES OR STANDARDS.

USER DISCU55 ? ON POSITIO8e COMMI55IO88 AC F.5 PRESS OFFI"E MEETIpeG PAPER BRIEFIE BRIEFI80G RELEASE RESULTS EDil 11L._ALIIV111LL REM 1Ed tiELD.

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15eLESElllED terr OFFICE RESPON58etE......... NRR UNSCHED Use5CPfD U'e5CHED UNSCHED U43CHE3 1'3 F T l

SCHEDULED ComPLETI0's DATE..

1977 ACTUAL Comet E T ION DA T E..... UNet LDet!E311_LEDH_N'LE_EII_L EllistiUI_DW1..hl2LII -

D LLL E1B L_AEELI C1110k _2 A115 L'L11 DE I.E30CLil THE OCT Avia CeMPUTER CODE HA5 BEtte USED TO EVALUATE THE PROSA81LtTV OF REACTOR Vf55EL FAILURE F#5)* OVERPRE'.,5URE TR A'e$t ENT5 WHICH CAN OCCUR DURIR? PwR 07ER AT40ne. TrE RESU".75 OF THE AN AL YSE Y. INDICATED THAT EXfifl % SAFEff MARGIPe5 000LD SC SIGNIFsCANTLY REDUCFD WITH costiterJED dEUTRON IRR ADI AT IO*e OF THE.uaCTOR WESSEL IF THE HI!TutICAC FREDUENCY OF OVEpr*RE550RE EVE 88TS Coset tseUED.

DL50EIAE_1EEAC1_DL_RL5tlL112 THE A884Lf 5E S E NABLE0 NRR TO CONFIRM. 14 f MOR E R I E-OR005, cuase T ' T A T i v E M A'e8eE R, INITIAL LICENilesG DEC15104 10 REDUCE TPE F REQUEteCY AND MARImum PRES 5URE of EHE TRANSIENTS. THESE DECISIDee5 RE58'LTED IN POOIFICATIONS TO OPER AT ING PROCEDURES FOR RE DUCI% THE FRE QUE NCY OF TR AN5IENTS AseO THE IMT ALL ATIOpe CF P:fYSICAL DEVICES To limit PRE 554sJE5 IN OPIRAIING T1ApeTS TO TH05C SPCCIFIED BY THE PRES 5URE-TEMPERATURE LIMITATIONS IN THE TECHNIC AL SPECIFIC AT 1045.

LD5!!L3114EEE&EL1 NC 1E EDEEL311_LECB_1. _SII__E._1&MDALL_D*11_El21212 -

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',0 DATE SEEM TU BL A% I 4 CMPLFTE PROPADILITY A8eALYS!5 BUT REPRESENT A U5ETUL PRODUCl FOR ANALYZI M ACCIDENT C0f.08 T1045 WHEWE NO REfew!RiJ SAFETY PARGIN5 HAVE BEEN EST ABLISHED.

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NueB. 193JEEIZIIILEllEEACI I&RGET DAIE REG _i_AND_NAEE REG EBalREAN T134 ASSESTOS IN COOLING T0nERS. OSTAIN INFO OTR 3 78 873-CHFMICAL T0XICITY OF P. R. REED ON THE EXISTENCE OF A58EST05 IN COOLING AQUATIC EFFLUENT TOWER WATERS.

DETERMINE THE TYPES AND C04CENTRATIONS OF Aso STOS FORM PARTICLES c

IN COOLING TodER MAKE-UP DATER RECIR-CULATING WATER, AND BLOWDOW1 AT SELECTED SITES USING NATURAL D* AFT OR MECHANICAL CRAFT CCOLING T0hERS.

TI43 INFORMATION REPORT ON THE SAFETY ANALYSIS CTR 3 T8 NONE OF THE PU AIR TRANSFGETabcE CONTAINER.

W. LAHS THIS REPOtt WILL PROVIDE A COMPENDIUM OF ALL ANALYSIS AND TESTING PERFORMED TO SUPPORT ON NRC SAR ON THE PAT CONTAINER.

INFORMATION FROM THE HRAFT CF THIS REPORT IS CURRENTLY BEING SUFO AS THE BASIS FOR THE NRC 5AR.

STRUC TU* AL. HE AT TRANSFER.

CONTAINMENT. S H I EL D I NP., CRITICALITY.

OPERATING PROCEDORES, ACCEPTANCE E MAINTEN-ANCE. AND CUALITY CONTROL IINCLUDING A COMPLETE SET OF CR AWINGS AND SPECIFIC ATIONSI SECTIONS ARE INCLUDE 0.

T47 REWET CORRELATION. MAY REMOVE APPENDIX K QTR 4, 78 3-P WR-B DHT E. H. DAVIOSON RESTRICTIONS ON 'RE Tu9N CF NUCLEATE 4-BWR-BDHT BOILING

WITH & CORRiLATION.

E. H. DAVIDSON T48 eUILDING WAKE DIFFUSION MODELS. COMPARES QTR 4 T8 62-LWR RISE ASSESSMENT J. MURPHY FIELD AND WIND TUNNEL FODELS TO VERIFY

{

LICENSING DATA 845E.

l TSD SEST ESTIMATE GAP CONDUCT ANCE.

TO CONFIRM QTR 4, 78 I2-FUEL BEHAVIOR W. V. JOHNSTON APPENDIX R RECUIREMENTS.

TSI FISSION GAS RELE ASE MODEL VERIFIED. 4D05 QTR 4 78 9-FISSION PRODUCT RELEASE R. DISALVO l

TRANSIENT FISSICN GAS RELEASE CUANTI-FICaTION TO FRAP-T ENHANCING ACCIDENT 1

CALCOLATIONS.

l T52 PHYSIC AL SEPARATION CitTERIA IHORIZ.

QTR 4 78 23-ELECTRICAL STDS C FIRE Pr.0T.

R. FEIT CLOSED $ PACE).

CONFI9MS PORTIONS OF REG. GUIDE I.7S.

N i

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E80 JEEIED _N EAR:IEER _RES?.AECtLIN ECEEA IIDN_LEIIER3 TEMP.

MUES. 1USJECIIIIILEZIBEACI laEGEI_DAIE REC _1_AND_NAME ERG _ CHAIRMAN T54 INITIAL IN-PILE CORE MELT RETENTION TESTS. CTR 4, 78 27-POST ACCIDENT HEAT REMOVAL R.

W.

WRIGHT ASSESSMENT OF CONTAIN"ENT INTEGRITY.

T55 PROMPT BURST ENERGETICS C FUEL ECUATION-CTR 4,

78 29-THERMAL-MECHANICAL INTERACTION R. W. WRIGHT OF-STATE.

ANALYSIS OF HCOA DAMAGE POTENTIAL.

T56 8x8 TRANSIENT CHF TESTS COMPLETE. SUPPORT QTR 4, TO 4-0WR-80HT E. H. DAVIDSON EXISTING CORRELATION OR REC 0mHEND A f:E W CORRELATION.

T66 ANNE AL ING TEST.

PROVIDES B ACKGROUND TO QTR 4,

78 20-VE55EL INTEGRITY E. K.

LYNN EV ALU ATE ANNE AL IN', PROPOS ALS AND DEF INE RULES AND LIMI TS FOR AN,4E AL I NG.

T67 GYCLIC CRACK GROWTH EVALUATION. NEW QTk 4,

78 20-VE55EL INTEGRITY E. K. LYNN CURVE FOR ASME II CRACK GR0wtH RATE.

T68 FIELO VALIDATE ELECTRnCHEMICAL TEST.

OTR 4,

78 22-CORR 0510N J. MUSC AR A UPOATC5 REG. GUIOE TO PRECLUDE SENSITIZE 0 STAINLESS STEEL IN SEPVICES.

T69 CODE RECOMMENDATIONS FOR MULTIPLE INTER-QTR 4 78 20-VE55EL INTSGRITY E.K. LYNN ACTING N0ZZLES. PROVIDES NEW OEstGN RULES FOR SUCH A5 5AFSTY INJECTION No!!L E S.

T152 PROGR AM OUTL INE FOR HUMAN FACTORS CTR 4,

78 NONE NONE TRAINING - PROV10E RECOMMENDATIONS TO IE REGARDING INSPECTION C INVESTIGATION.

T136 ENV IRONMENT AL IODINE SPECIES HEHAVIOR.

CTR 4,

78 343-AQUATIC TRANSPORT C FATE P. R. REED STUDY THE PHYSICAL C P10 LOGICAL TRANSPORT OF CHEMICAL FORMS TO R ADIO100INES RELE A5F0 TO THE ENVIRONMENT FRnM AN OPERATING NUCLE AR ST AT ION.

OETERMINE THE INFLUENCE OF WET DEPOSITION IRAIN OR DEW) FOR METEOROLOGICAL MODELS C THE IODINE-AIR-i GRASS-MILK PATHWAYS.

PERFORM LABORATORY

(

TESTS TO DETERMINE IF METHYI0010E 15 DEPOSITED ON GRASS Ur40ER wE T DEPOSITION CONDITIONS. DETERMINE ENVIRONMENTAL PATPhAYS OF TRITIUM A*tD CARBON-14 RELEASED FROM NUCLEAR STATIC:45.

M 1

E&QJECLEDJiEAE-IEE5_EESEAEEILANECP2AIICtLLElIfBi TEMP.

SUES. SuSJEC1/IIILEZIEEACI LASGil_DAIE REG 1_AUD_BAEE REL_CHAIREAN T137 MONITORINS OF RADIODINE FROM CONTAINMENT QTR 4,

78 874-TERRESTRIAL RADI0 ECOLOGY P. R.

REED ACCIDENTS.

TO DETERMINE THE PRACTICALITY OF USING AVAILABLE CIVIL DEFENSE INSTRU-MENTS TO ASSESS PUSLIC HE4LTH IMPACTS OF AN ACCIDENTAL RELEASL OF RADIO!ODINE FROM NUCLEAR STATIONS.

TO ASSESS INSTRUMENTA-TIGN CAPABILITIES IPARTICLE COLLECTION EFFICIENCY, PARTICULATE CONTRIBUTIONS.

AND INSTRUMENT REL I ABILITY) OY EVALUATING A PORT ABLE FIELD RADInIODINE COLLECTION SYSTEM AND A DETECTION SYSTEM USING A COV-700 GM SURVEY INSTRUMENT.

I I

T138 GENERIC REVIEW OF THE IMPACT OF CONSERVA-QTR 4 ?8 STS-50CIDECONOMIC IMPACTS D. BARNA l

TION, RATE STRUCTURE C LOAD MAMiGFMENT ALTERNATIVES GN THE NrED FOR POWER.

PREPARE A REFERENCE DOCUMENT WHfCH REVIEWS C SYNTHESIZE 5 RECENT Ev!OENCE C EVALUATES FUTURE PROSPECTS REGARDING THE I"PAC T OF ALTERNATIVE ENERGY CONSERVATION PROGRAMS, RATE STRUCTURE OESIGN5. LOAD MANAGEMENT STRATEGIF S, AND CO-GENER A TION SYSIEMS ON THE NEED FOR POWER.

T131 LAND USE AND LAND VALUE CHANGES OVER TIME QTR 4 78 sT5-SOCIUECONOMIC IMPACTS D. BARNA AT NUCLEAR PLANTS.

E V AMINE & DOCUMENT THE SHIFT 5 IN LAND USE THAT TOOK PALCE l

OVER TIME. FROM PRE-INSTALLATION TO TNE PRESENT. IN THE VICINITY OF THREE NUCLEAR ELECTRIC GENERATING PL ANTS.

D E T E RM I edE.

BOTH SEPARATELY A6D JnINTLY, THE NET EFFECTS OF A NUCLEAR PLANT CN REAL PROPERTY VALUES.

DETERMINE REat PROPERTY VALUE CHANGES IN THE VICINITY CF SEVERAL PROPOSED NUCLEAR GENERATING PLANIS WHERE THE SITES HAVE BEEN ACCUIRED BUT THE FACILITIES NOT YET CONSTRUCTED.

T140 ASSESSMENT OF AGRICULTURAL LAND IN QTR 4, 78 STS-SOCIOECONOMIC IMPACTS D. BARNA RELATION TO POWER PLANT SsTING AND COOLINO SYSTEM SELECTION. A METHO-DOLOGY FOR NET ENERGY ANALYSIS AS A CUPNTITATIVE MEAN5 FO' ASSESSING NATURAL RESOURCES AND LAND USE.

IN PARTICULAR.

THE STUDY w!LL 8E BASED ON ENERGY GUALITY AND FLOW AND WILL BE DESIGNED TO AID IN MAKING LAND USE OECISIONS WHICH INVOLVE CHOICE OF SITES AND ALTERNATE MODES FOR COOLING SYSTEMS.

D

T EE0JECIED NFAR-YFRM RESEARCU_ANFORMAl20N tFTTEPS TEMP.

!fut2. Sun.lECILIIILElit!EACI IAEGLI_DAIE REG _ LAND _5AEE REG _ClialEEAN TI41 DOSE TO CONSTRUCTION WORKERS AT OPERATING QTR 4, 78 876-0CCUPATIONAL EXPOSURES J. FOULKE REACTOR SITES. PRov10E VALUES FOR THE AND PROTECTION RADIATION 00SES RECEIVED BY CONSTRUCTION WORKERS AT OPERATING LEACTOR SITES.

TO BE USED IN ENVIRONMENTAL STATEMENT FOR CONSTRUCTION OF REACTORS ADJACENT TO j

OPERATING UNITS.

TI42 ASSESSMENT OF SOURCES OF DOCUMENTATIONAL QTR 4, 78 876-0CCUPATIONAL EXPOSURES J. FOULKE RADIATION EXPO 5URE AT NUCLEAR POWER AND PROTECTION PLANTS.

IDENTIFY EXPO 5URE REDUCTION TECH-NIQUE5 AND RECOMMEND DESION FEATURES TO KEEP OCCUPATIONAL EXPOSURES At LOW AS REASONABLY ACHIEVABLE. TO BE USED IN A55ESSING THE EFFECTIVENESS OF REGULATORY GUIDE 8.8.

f l

T144 PUO2 - 002 LEAKAGE C00 RELATIONS. THIS QTR 4,

TS 853-TRANEPORTATION SAFETY W.

LAHS l

REPORT WILL SUPMARIZE THE EXPERIMENTAL RESULTS INVOLVING THE LEAKAGE OF PUO2 THROUGH SMALL URIFICES AND CAPILLARIES.

PARAMETERS BEING INVESTIGATED INCLUDE, DRIVING FORCE PRE 55Udr TEMPERATURE, l

ORIF ICC CR CAPILLARY GEOMETRY WITH j

RESPECT TO THE PUO2 POWDER AND VIBRATION.

I CORRELATION WITH MEASURED GAS LEAKAGE i

RATES AND URANIUM SURROGATE LEAKAGE WILL BE EPPHASIZED.

i TI47 REACTOR RA0dASTE.

FUUR REPCRTS WILL CTR 4,

78 NONE D.

SOLBERG l

SUMMAR'2E 3 YRS. OPERATING EXPERIENCE IN O'. OF EVAPORATION, IILTRATION AND ION cKCHANOE Euu!PMENT AN9 SOLID WASTE MA' AGEMENT SYSTEMS IN NUCLEAR POWER j

PL -NT S.

DATA WILL BE USED IN LICENSING I

EVALUATIONS OF APPLICANT 5' EFFLUENT CONTROL SYSTEMS DE5!GNS.

T127 LIQUID PATHmAY REASSESSMENT LATE 78 62-tWR RISK 455E55MEPT J. MURPHY TS9 CHAMP [8 AND !!.

FOR BdR CONTAINMENT 5, CTR I, 79 15-CONTAINMENT CODE

5. F ABIC 1

PROVIDES AIR AND STEAM VENTfNG ANALYSIS l

CAPABILITY-INCLUCES MARK I, II AND III SYSTEMS.

i l

l

EaQJECIED_ SEAR:IES5_ELSEARCU_13ECE"aIIC5_LEILEB1 TEMP.

32E3.

'4 JECJ.4111LilISEACI IAEGEI_DAIE ESG_1_AND_NAEE REG CUALSHAN lol SOLA-FLX RELEASED. P49VIOp5 N10 wlTH A QTR 1.

79 14-ADVANCEO 5YSTEM CODE N.

ZUBER C O D L-TO CONDUCT INDEPrNDENT AUDIT GF

{

VENDOR etowD0wN LOAJ CALCutATIUN5.

T62 SENSITIv!TV 510c!ES. DETERMINES QTR 1.

T9 14-ADVANC50 SYSTEM CODE N.

ZUBER SENSITIVITY OF THE CCPRA ANALYSi5 PERFORME0.

l T38 TRAN5FER OF SE VE 2 AL SCR SAFFTV CODES.

CTR 1.

79 38-GCR ALCIDENT DELINEATION P.

M.

WOOD PERMIT 5 INDEPENDENT NoC A*44LV5IS OF SAFETY AND ANALYSIS PRC2LEMS IN FSV.

T53 URANIUM OXIDE A2R050s TESTE INSPPl.

RE-QTR L.

79 25-AER050L RELEASE C TR*N5 PORT M. SILBERBERG ASSES 5 MENT OF AEtOSOL TRANSPORT RELATED MARGINS IN EVALUATICN MOOst FOR SIIING.

T70 CABLE COATINO MATERIAL TEST 5.

CONFIRMS CTR 1 79 23-ELECTRICAL STDS C FIRE PROT.

R. FEIT DESIGNS IN CUR 1ENTLY PPERATING PLANTS AND PORYIONS 0F REG GUIDE t.120.

T71 RADIATION (LouRCE TER*) SIMULATOR TEST 5.

QTR 1 79 23-ELECTRICAL STOS C FIRE PROT.

R. F EIT l

CONFIRMS PORTIONS OF OLG GUIDE 1.89.

1 772 VALIDATION OF $IMMER NEUTRONIC5. PERMIT 5 QTR 1.

79 33-CRITICAL EXPERIMENTS P. M. WOOD GREATER CCNFIOLNCE IN MARGIN AWAILABLE IN HC D A ANALY515.

T73 FSV DESICN 5A515 TRAN51ENIS.

DEPEN 05 UPGN QTR 1.

79 38-GCR ACCIDENT DELINEATION P. M. h000 THE RESULTS 06TAINEO.

AND ANALYSIS 31.

ES0JECIED_NEa&:IEE5_RESEABLtLI ECE5111CM_LEllE85 RRG CMalaEAN TEMP.

IAEGEl_DAIE EEG_1_ASD NAME 32"S.

SUDJELILIIILEllM2&CI NONE T12R wkAP EM/8WR - INr,ORPOR A T E S INTEGRATED QTR 1,

7 *,

NONE AND AUTOMATED IMPROVE *ENTS INTO A LICENSING CODE PACKAGC.

T44 WELD REPAIR INTEGRITY. PROVIDES B ACK-QTP. 2, 79 20-VE55EL INTEGRIY E.K. LYNN GROUNO TO PERMIT OR DrNY VESSEL WELO REPAIRS.

T74 THOR 1 (bel RELEASED.

PR0vtDES ttCEN>tNO QTR 2, 79 14-ADVANCED SYSTEM CODE N.

ZUBER wtTH A FAST RUNNING Br$T ESTIMATE CODE FOR SENSITIVITY STUO!FS.

T75 CONDUIT C BARRIER CUlr.E LINES.

TO FORM CTR 2.

T9 23-ELECTRICAL STOS C FIRE PROT.

R. FEIT BASIS FOR N:w GUIDES.

T76 FAILURE nN ALYSI S MET HODS FOR CCLt LINERS.

CTR 2, 79 28-PRIMARY SYSTEM INTEGRITY T. J. WALKER ASSES $ MENT OF CONTAIN"ENT INTEGRITY UNDEx ACCIDENT LOADS.

E. H. DAVIDSON T82 TRANSIENT CHF CORR E L A T IOf4.

NO CHANGE CTR 2, 79 3-PWR-80HT E. H. DAVIDSON 4-PWR-BDHT IN APPENDIK % BUT MAY REPLACE CURRENT CORRELATICN.

T43 THERMAL SHOCK AND STEAM LJNE 6REAK QTR 3,

79 20-VE55EL INTEGRITY E. L. LYNN ANALYSIS.

PROVIDE 5 A LICD458NO PROCEOURE FOR THERMAL 5 HOCK A'4ALYSIS, MAY RESULT IN TECH. SPEC. CH A:4GE S.

I T60 lwr LOCA TRAC RELEA$iD. PROwlDES NRR WITH QTR 3, 79 14-ADVANCED SYSTEM C00F N.

ZUBER l

l ADVANCED BwR AND PWR CGOLANT SYSTLMS 5000 l

TO ESTABLISH MARGINS OF SAF CTY.

I I63 VERIFY RELAP 4 MOD 6.

VERIFIE S PMR 8EST GTR 3, 79 17-VERIFICATION L. 5. TONG ESTIM ATE AN ALYSIS THRtf REFLC00 W. V.

JOHNSTON T6+

VERIFY FRAP T4.

ADDS TO ERAP T3; Al QTR 3,

79 12-FUEt. SEHAVIGR l

PR2LIMINARY CAPABILi'Y FOR MULTI-ROU l

GEOMETRY AND B) CAPA6II I TY TO EVALUATE

{

STATISTICAL VARIATIONS IN MOCELS.

5. F ABIC TFT BEACCN MOD 5.

INTEGRATES SEVERAL QTR 3, 79 15-CONTAINMENT CODE PACKAGES IN BEACGr4 INCLUDING PSS POOL OYNAMIC5, ICE CONDENSER, AND H2 CONCEN-TRATION ANALYS15.

eN q

R&2JECIED_$EAh IEEM_EEXEAGEU_INECEEAIIDS_LE11EES TEMP.

SUES. SU3JELIIIIILEZIEEACI IAEGEI_DA1E BEG _f_AND_MA5E REG _EualE5AN TTR HYDROEL 1STIC EFFEC TS SIUDIE S.

FOR P55 QTR 3.

79 I5-CONTAINMENT CODE

5. FABIC IPRE55U2E SUPP9E55 ION SYSTEM $l CCNTAIN-MENTS TT9 M E C H AN I C AL PROPERTIES REFORT.

PROVIDES QTR 3.

T9 S-Z1RCALOY CLAODING M. L. PICKLESIMER i

INDEPENDENTLY WERIFIED IRRACIATED l

ZIRCALOY OATA FCR U$i IN LICENSING CALCULATIONS.

TS)

TRANSIENT ECC SYPAS$ CORRELATICN.

MAY QTR 3 79 6-ECC BYPASS A.

SERK!Z CHANGE APPENDIX K FROM USE CF "fND OF BYPAS5" MODEL %NC NO #CC *RICR TO E08 TO NEW CCRRELATICN.

TF4 UNI-ECC5 TESTS.

PROWIDES NRR 8ACIS FOR QTR 3.

79 2-5EMISCALE W.

W.

BIXBY UHI LICENSING 0ECISIONS AND MAY REQUIRE NEW SECTION I:4 APPENDI4 K.

T:36 SOURCE TELM CORRELATION. CCNFIRMS QTR 3 79 13-FbEL MELT R. DISALVO CONSERVATISM OF REG. c.UICE ASSUMPTIONS FOR ACCIDENT ANALV5IS.

Y130 VERIFY FRAPCON - PRCv!OES NRR WITH 8E QTH 1 79 12-FUEL BEHAVIOR W. V. JOHNSTON AND EM CAPABILITY TO ANALYZE STEADY l

$? ATE FUEL BEHAVIOR.

l Ti21 WRAP EM/PWR - INCORPORATES INTEGRATED OTR 3, T9 NONE NONE AND AUTOMAIED IMPRDWEMENTS INTO A LICENSING CODE PACKAGE.

T80 MELTOOWN RELEASE COR1rtgygog, cogrgppS gyg 4,

79

13. FUEL MELT R. DISALVO l

CONSERVATISM OF REG. GUIDE A550M*TIONS FOR ACCICENT ANALY5li.

Tal INTERFACE SHEAR T R A'4 5F E R TEST.

MAY INPACT QTR 4 T9 55-ENVIRON. STRUCTURAL DESIGN J. HARSOUR SEI5MIC DESIGN REau!REMENTS F01 REINFCRCED CCNCRETE CONTAINM2NTS. OR CGNFIRM EXISTING REQUIREMENTS.

l l

T85 ATW5 TRAC VERSION.

PROVIDE 5 ADVANCEO QTR 4 79 14-ADVANCED SYSTEM CODE N. ZUBER CAPABILITY TO ANALYZE ATWS IN LWR *5.

T87 EVALUATE NEED FOR DIAGONAL RE8NFORCING QTR 4 79 55-ENVIRON. STRUCTURAL DESIGN J, HAR8OUR l

SARS.

MAY IMPACT SEISMIC DESIGN l

RECUIREMENTS FOR REINFORCED C040 RETE i

CONTAIN*ENTS. CR CCNFIRh EFISTING REQUIREMENTS.

M l

l l

1

eacatc1to_staa:ttse_at5tasas_1seceeAticettt11tas IAEGEI_ Dale EEG_f_ASD_5A5e EBE_ChalEMAN TEMP.

TJ52. SualtCIIIIILEl15Ea01 R. CURTIS TBS LOS AL AMOS FUEL MODE:. RELE ASED.

RE-QTk 4 T9 60-51MMER CODE ASSESSMENT OF FUEL FAILURE L OC A T I ON Or HCCA ANALYSIS.

TR9 MIX AEROSOL TESTS.

AEROSOL MODEL QTR 4,

79 25-AEROSCL RELEASE C TRANSPORT M. SILBERBERG VAL 10ATICN.

E.H. DAVIDSON T9]

POST LMF HEAT TRANSFde CORRELATION QTR 4,

79 3-PWR-BDHT 4-EWR-BDHT E. H. DAVIOSON VLRIFICATION COMPLETE.

SUP/GRT5 OR RFPLACED CURRENT COR4FLATIONS.

T91 17 X lT RffiOOO FEAT TRANSFER CORRELA-QTR 4,

79 5-REFLCOD HEAT TRANSFER E.H. DAVIDSON TION VERIFIFO.

MAY RrQUIAE NEw SEC T ION OF APPE40!X K TO ADORC55 THIS GEOMCTRY.

TICS RECCMMEND OPTIMIZED PIPIN-SYSTEM QTR 4 79 20-VE55EL INTEGRIYY E. 4 LYNN CESIGN. GUIDELINES FOR SAf tR PIP.NS SYSTEMS.

M.L.

PICKLESIMER ToS EM8RITTLEMENT CRITERIA.

MAY R/PLACF Q!R 1.

80 8-2;RCALOY CLAD 0!NG l

EXISTING CRITEPIA IN APPEN0tX K.

T94 THOR 1 (Emi RELfASED.

PROVIDES LICENSING CIR 1.

80 14-ADVANCED SYSTEM CODE N ZUBER WITH ADVANCED EwALUATICN MGLEL COD" FOR AUDIT CALCULATIONS.

L. 5. TONG Toi VER!iY TRAC-2.

GIVE5 CONfICEN;E THRU QTR 1,

80 17-VE R I F IC A T ION COMPARISON WITH LOFT. GERMA4 AND JAPANJ5E TEST DATA.

L. 5. TONG T96 VERIFY HEAT TRANSFE R COR7EL ATION.

CON-CTR 1, 60 17-VERIFICATION FICENCE IM THE CORRELATION 15 INCREASED THRU COMPARIS0N wlTH WORIO WIDE IEST DATA.

T97 RELAP 4 MCD 7.

USE CONVENIENT QTR 1,

80 16-REFERENCE SYSTEM FODE

5. FAbtC PWR LOC A CODE R. DISALVO T100 PROSABILITY AND CGNSEOUE NCE S OF STEA4 QTR

1. 80 i3-FUEL MELT I

ERPLO5 IONS.

POS$1BLY WILL PRCVIDE A I

QUANTITATIVE PREDICTION OF STEAM I

ERPLOSIGNS MOSTLY APPLICAdLE TO FLOAT ING PL ANT S.

M

EECJELIEC_ SEAS IEEti_RESEAREU_INECEf!AIION iFYTig$

TEMP.

NUES. SUSJEEli1IILEf1SEAEl IAEGEI_DAIE BEG 1_AND_NAEE REG _EBAIEHAS T101 UPDATF KIR CUR VE-OUC T I LC SHELF TOUGHNESS.

CTR 1 80 20-VE55EL INTEGRITY E.K. LYNN PROVIDES 9 ASIS FOR HEAT UP - COOLDOWN CURVE 5 IN OPER ATING PL AN TS.

T102 UPDATE KIR CURVE-CRACF ARREST.

BASIS QTR I.

80 20-VE55EL INTEGRITY E. K. LYNN FOR SEVERE ACCICENT ANALYSIS ARREST EVALUATION.

T104 REACTOR PRESSURE VE5SEL SURVEILLANCE QTR 1.

80 20-VE55EL INTEGRITY E.

K.

LYNN PROCEDURE. PROVICES BACKGRGUND TO ACCURATELY EVALUATE SURVEILLANCE EMBRITTLEMENT ANC FLUENCE SAFC LIFETIMES.

Y10T IM"RCVED LOOS E PAR TS MONI TORING.

PROVIDES QTR

1. 80 69-NO!5E SURVE:LLANCE AND W. FARHER INPUT TO REG. GUIDE REQUIREM2NT CHANGE AND TO LICEN51NG REVIEh.

DIOGNOSTICS T109 EVALJATE METHOD TO CALCULATE COASTAL QTR

1. CO 62-LWR RISK ASSESSMENT J. MURPHY I

DISPER5!CN. MAY IMPAC T CN LICtNSING EVALUATION OF CLOSE-IN ACCICENTAL RELEASE CGNCENTRATIONS.

T59 DATm BASE.

INCCRPORATES REACTOR DESIGN QTR 2 80 NONE AND OPERAT!NG CATA 6ASES IN RELAP S.

NONE T105 INCCRPORATE IMPROVED UT IN CODE.

IMPROVE 0 QTR 2 80 21-NON-DESTRUCTIVE EXAMINATION J. MUSC AR A CON *IoENCE IN EVALUATION OF FLOW SIG-NIFICANCE FROM ACCURATE FLOk SHAPE AND SIZE.

Y1C6 l

VAL ID AT E ACDUST ICS EMISSION t L AW CORRELA-QTR 2. 80 21-NON-PFSTRUCTIVE EXAMINATION J. MUSCAR A TION.

VALIDATES THE DETECTICN.

IDENTIFICATION C ELIMINATION 05 FLAWS DURING WELDING - L ATER EVALUATION NOT NECDED.

l j

T110 COMMIX CCCE ITwG-PHA5FI.

RCA55E55 MENT QTR 2.

80 32-5YSTEMS CODES AND ACCIDENT P. M.

WOOD CF CCOLABILITY CF SUSA55EMBLY UNDER NATURAL CONVECTION.

ANALYSIS T111 CREEP FATIGUE INTERALTION TESTS AND OTR 2. 80 28-PRIMARY SYSTEM INTEGRITY T. J. WALKER CODE.

VERIFIES GESIGN RULES FOR LONG TERM PRIMARY SYSTEM INTEGRITY.

1 35 J

. - _.. ~

l i

21DJECIED_ SEA &:lER5JLEiEARUMEDSB&IlOM LETTER 1 TEMP.

nub 5.

SUBJECirTITLE/lHEACI 1&RGEl_ DALE RRC p AND MAME R&G_CH&lRB&B Til2 CONTAINMENT PRES 5URE PULSE ANALYSIS QTR 2. 80 36-GCR STRUCTURAL R. D. SCH AM8ERGER METHODS. CONCLUSIONS MAY EFFECT THE LICENSING POSITION OM DEPRE55URilAT10N ACCIDENTS.

i T91 8X 8 SUNDLE TESTS. CONFIRMS 481LITY QTR 3, 80 8-ZIRCALOY CLADDI4G M. L. PICKLE 51MER I

TO LIMIT PROPAGATION AND MAINTAIN l

COOLABLE GEOMETRY.

E i

T98 SMALL CLUSTER T[5TS. CONFIRMS ASILITY QTR 4, 80 10-PBF EXPERIMENTAL PROGRAMS R. V AN HOUTEN TO LIMIT PROPAGATION AND MatNTAIN C00LABLE GEOMET9t.

a T108 SAFETY RELATED OPERATOR ACTING CRITERIA.

QTR 4, 80 24-HUMAN ENGINEERING W. 5. FARMER

^,

maw IMPACT ENGINEERED SAFETY SYSTEMS AUTOMATION.

J i

i, 36 e

sua e0vesuusse=T retmsvines cepeu. a,7s 32e-wrta: a. s

uWtTEo STATES F

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i l

NUCLEam REGULATOR Y COMMISSION WASHINGTON, D. C 20$55 post Aos Ano e aas raio U S NUCLE AR RE GUL ATORY O>FICI AL SUSINESS CowMillioN PEN ALTY FOR PRIV ATE USE, $300 L

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ML20195J579

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Text

SUMMARY

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ML20195J579

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SUMMARY

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