ML20195J579
| 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) | |
Text
- ____
NUREG-0435' A $$ OF: 52/01/78 I ,
l OFF!CE OF NUCLEAR l REGULATORY RESEARCH l
/,o='A STATUS l [ j
SUMMARY
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/ REPORT j RESEARCH RESULTS UTILIZATION 88120~20277 780201 O 35 PDR e
IaBLE_DE_CONIENIS_
EAGE_N01 DESCRIE1103 1 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 AECHw' uRK. A RIL MAY COVER MATERI AL DEVELOPED FRDM MORE 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: C. FITZGER ALD I
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2.C__ELLEARElf 13ECE5AIIEG_LLIIE&i_iEIL!il 2.1__L151_CL_15LUE3_EILii WESEAtCH INFORMATION LETTER 5 1550E0 BY RES TO DATE ARE LISTED BELOW I# TABLE 2.1.
YUGETHER WITH THE DATE OF ISSUE, A 553CI AT E D RE SE AR CH PROGRAM ELEMENT AND PROGRAM
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CATE ESQLEAE_MA3AGER EELEaEEU_INICE5AIIDS_LLIIER_IIILL EE1_EEQGRA5_ ELE"Eh1 EALE_30. EIL_33. .151UEJ_
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- 4 9/10/74 MAP SHORING RECFNCY OF FAULTING IN CCASTAL 50uTHIRN CALIFORNIA PRIMARY SYS INTEG. E.K. LYNN 9 5 6/29/76 CONFIRMATORY PRE 55USE VESSFL TEST UNDER PNEUM & TIC LOADING FAST 3REEDER RfACTOR R. WRIGHT 10 6 10/12/TA A CRITIQUE OF THE BOARD-HALL MODEL FOR THERMAL DETONATION 5 IN THE 902-NA SYSTE" FAST BREEDER REACTOR R. CURTIS 11 7 C/25/76 THE SIMMER CORE FOR ANALYSIS OF HYPOTHETICAL CORE DISRUPTIVE ACCIDENTS IN LMFBR'S FUEL BEHAVIOR R. DISALVO 12 8 1/11/77 DECAY HEAT DAff. APPLICABLE TO LOCA EVALUATION FUEL BCHAVIOP M. FICKLE 5fMER 13 9 5/14/7' HIGH TEaPERATURE OAIDATION OF ZIRCALOY FUEL CLACDING IN STEAM RISK ASSESSMENT W. VESCLY 14 10 2/25/17 PRESSURE VESSEL FAILURE PROBASILITY PREDICTION
.00TAv!A C00E3 RISK A55E55 MENT J. JOH450N IS 11 9/15/T7 IEFC NUCLEAR RELI ARILITY D AT A MANUAL RISK A55E55 MENT W. VESELY 16 12 6/16/7' M OC I F I C A T I ONS TO PRES 5URE VESSEL F AILURE PRU6A91LITY PRE 0!CTION IOCT Avl 4 CODEI PRIMARY SYS INTEG. E . K. LYNN 17 11 11/11/77 RES/ DUAL STRESSES IN mELOS SYSTEMS ENG. R. FEIT 18 14 13/9/77 PHYSICAL SEPARATION CRITERIA FOR ELECTRICAL CABLE TRAYS IHORIZONTAL OPEN $ PACE CONFIG.)
PRIMARY SYSTEMS E. K. LYNN 19 15 12/1/17 CHARACTER!lATION OF swr FEEDWATER NOZZLE CORNER CRACKS PRIMARY SYSTEMS E. K. LYNN 20 16 12/1/77 WARM PRESTRESSING RI5K ASSESSMENT F. GOLOBERG 21 18 11/9/77 FR ANT IC COMPUTER CODE Alin ASSESSMENT J. PITMAN 22 14 1/31/T* GO METHODOLOGY ASSESSMENT SAFEGUARDS E. RICHARD 11 20 1/24/78 & STU3Y OF PHYSIC AL PdOTE CTION E QUIPMENT J
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1.Z__EDIE311AL&EELICABIL11LDE_EEsEARCti_EEsutis T 9 THE REGUL&lDRY PROCE11 COMNECTS C3E OFFECED FOOM #ES CND FCOM COCNIZAOT USE2 G FICES ON THE CSTURE OF THE REPORTED RE5utT5 AND 2 HEIR POTENTIAL IOR ACTUALI APPf,ICABILITY TO ANY PART OF THE REGULATORY PROCESS, INCLUDING 2 Al TECHNICAL DATA SUPPORT ING LICENSING R EVIEWS OR REGULATORY JUDCMC!4T. 88 EVALUATION CODES. C3 INFORMATION APPLICABLE TO REGULATORY GUIDES OR STANDAPDS, AND Of INFORPATION SUPPORTING JUDGMFNTS REGARDING REGULATORY POLICY.
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_ . . PR3LRA5_DELILE_C35EL315.05_EQ1LS11AL_UIIL11A11D!LDE MALUE OF RESEARCH RESULT 3 IN THE_ELGUL&lDEY PROCE15 E11_ft 5 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 HF1 D CQIIELETED tif s 0 liturn M EEgEg1ED ED51_EIL_ACI1Y11115 EEVIEW _ UF 1 B 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 00p4ITTEE A80GT THE RE5utT5 OF ITv-TEST UNDER HYDRAULIC LOADING. 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
HYDR AULIC LOADI%. AND fHE RE5JLTS ARE APPLICA8LL TO THE EVALUATION OF THE SEHAVIOR OF REACTOR PRES 5URE VESSELS UNDE R SU5T AINED LOAD. 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 UPPE R SHELF OF YOUGHNE55 ARE CLOSELY REL ATED TO RATIO U/T (CRACK OEPTH/THICRNESSI.
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___E330E15_LLLALL.L3EELSIL_in'_UIbI1CL_UIILII&I1C3_DE_V ALUL_CL.EL5LOECti_ELSUL11_l'Ji_lul_ELLULAICR Y PROCESS EIL_t! T C&ls.111ULD: 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 -- -- -- -- --
?.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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EILf 9 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 __ ull D liiULD_ 15EIFMrNILD l OFFICT RESPON51etE......... NER -- --
NRP -- --
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
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 . EDBELLIED isELD
- I f) l' auld. 15eLESElllED OFFICE RESPON58etE......... NRR -- -- - -- -
terr SCHEDULED ComPLETI0's DATE.. -- UNSCHED Use5CPfD U'e5CHED UNSCHED U43CHE3 1'3 F T l' ACTUAL Comet E T ION DA T E... .. UNet - - -- -- - 1977 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. 0 _SII__E._1&MDALL_D*11_El21212 -
RESULTS ',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 cSTOS FORM PARTICLES 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 APPENDIX R RECUIREMENTS.
I2-FUEL BEHAVIOR W. V. JOHNSTON !,
TSI FISSION GAS RELE ASE MODEL VERIFIED. 4D05 l QTR 4 78 9-FISSION PRODUCT RELEASE R. DISALVO 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.
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E80 JEEIED _N EAR:IEER _RES?.AECtLIN ECEEA IIDN_LEIIER3 TEMP. ERG _ CHAIRMAN MUES. 1USJECIIIIILEZIBEACI laEGEI_DAIE REC _1_AND_NAME 27-POST ACCIDENT HEAT REMOVAL R. W. WRIGHT T54 INITIAL IN-PILE CORE MELT RETENTION TESTS. CTR 4, 78 ASSESSMENT OF CONTAIN"ENT INTEGRITY.
PROMPT BURST ENERGETICS C FUEL ECUATION- CTR 4, 78 29-THERMAL-MECHANICAL INTERACTION R. W. WRIGHT T55 OF-STATE. ANALYSIS OF HCOA DAMAGE POTENTIAL.
8x8 TRANSIENT CHF TESTS COMPLETE. SUPPORT QTR 4, TO 4-0WR-80HT E. H. DAVIDSON T56 EXISTING CORRELATION OR REC 0mHEND A f:E W CORRELATION.
QTR 4, 78 20-VE55EL INTEGRITY E. K. LYNN T66 ANNE AL ING TEST. PROVIDES B ACKGROUND TO EV ALU ATE ANNE AL IN', PROPOS ALS AND DEF INE RULES AND LIMI TS FOR AN,4E AL I NG.
QTk 4, 78 20-VE55EL INTEGRITY E. K . LYNN T67 GYCLIC CRACK GROWTH EVALUATION. NEW CURVE FOR ASME II CRACK GR0wtH RATE.
OTR 4, 78 22-CORR 0510N J. MUSC AR A T68 FIELO VALIDATE ELECTRnCHEMICAL TEST.
UPOATC5 REG. GUIOE TO PRECLUDE SENSITIZE 0 STAINLESS STEEL IN SEPVICES.
QTR 4 78 20-VE55EL INTSGRITY E.K. LYNN T69 CODE RECOMMENDATIONS FOR MULTIPLE INTER-ACTING N0ZZLES. PROVIDES NEW OEstGN RULES FOR SUCH A5 5AFSTY INJECTION No!!L E S .
CTR 4, 78 NONE NONE T152 PROGR AM OUTL INE FOR HUMAN FACTORS TRAINING - PROV10E RECOMMENDATIONS TO IE REGARDING INSPECTION C INVESTIGATION.
CTR 4, 78 343- AQUATIC TRANSPORT C FATE P. R. REED T136 ENV IRONMENT AL IODINE SPECIES HEHAVIOR.
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.
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SUES. SuSJEC1/IIILEZIEEACI LASGil_DAIE REG 1_AUD_BAEE REL_CHAIREAN T137 MONITORINS OF RADIODINE FROM CONTAINMENT QTR 4, 78 ACCIDENTS. 874-TERRESTRIAL RADI0 ECOLOGY P. R. REED 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 l GENERIC REVIEW OF THE IMPACT OF CONSERVA- QTR 4 ?8 STS-50CIDECONOMIC IMPACTS TION, RATE STRUCTURE C LOAD MAMiGFMENT D. BARNA 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 AT NUCLEAR PLANTS. E V AMINE & DOCUMENT D. BARNA 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 RELATION TO POWER PLANT SsTING AND STS-SOCIOECONOMIC IMPACTS D. BARNA 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
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!fut2. Sun.lECILIIILElit!EACI 876-0CCUPATIONAL EXPOSURES J. FOULKE TI41 DOSE TO CONSTRUCTION WORKERS AT OPERATING QTR 4, 78 AND PROTECTION REACTOR SITES. PRov10E VALUES FOR THE 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.
QTR 4, 78 876-0CCUPATIONAL EXPOSURES J. FOULKE TI42 ASSESSMENT OF SOURCES OF DOCUMENTATIONAL AND PROTECTION RADIATION EXPO 5URE AT NUCLEAR POWER '
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 f
GUIDE 8.8.
W. LAHS l QTR 4, TS 853-TRANEPORTATION SAFETY l T144 PUO2 - 002 LEAKAGE C00 RELATIONS. THIS 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 78 NONE D. SOLBERG l CTR 4, TI47 REACTOR RA0dASTE. FUUR REPCRTS WILL ,'
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.
LATE 78 62-tWR RISK 455E55MEPT J. MURPHY T127 LIQUID PATHmAY REASSESSMENT FOR BdR CONTAINMENT 5, CTR I, 79 15-CONTAINMENT CODE 5. F ABIC TS9 CHAMP [8 AND !!. 1 PROVIDES AIR AND STEAM VENTfNG ANALYSIS l CAPABILITY-INCLUCES MARK I, II AND III SYSTEMS.
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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.
T38 l 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 $IMMER NEUTRONIC5. PERMIT 5 QTR 1. 79 33-CRITICAL EXPERIMENTS P. M. WOOD GREATER CCNFIOLNCE IN MARGIN AWAILABLE IN HC D A ANALY515.
T73 FSV DESICN 5A515 TRAN51ENIS. DEPEN 05 UPGN QTR 1. 79 38-GCR ACCIDENT DELINEATION P. M. h000 THE RESULTS 06TAINEO. AND ANALYSIS 31.
ES0JECIED_NEa&:IEE5_RESEABLtLI ECE5111CM_LEllE85 TEMP. RRG CMalaEAN IAEGEl_DAIE EEG_1_ASD NAME 32"S. SUDJELILIIILEllM2&CI 7 *, NONE NONE wkAP EM/8WR - INr,ORPOR A T E S INTEGRATED QTR 1, T12R AND AUTOMATED IMPROVE *ENTS INTO A LICENSING CODE PACKAGC.
QTP. 2, 79 20-VE55EL INTEGRIY E.K. LYNN T44 WELD REPAIR INTEGRITY. PROVIDES B ACK-GROUNO TO PERMIT OR DrNY VESSEL WELO REPAIRS.
N. ZUBER PR0vtDES ttCEN>tNO QTR 2, 79 14-ADVANCED SYSTEM CODE T74 THOR 1 (bel RELEASED.
wtTH A FAST RUNNING Br$T ESTIMATE CODE FOR SENSITIVITY STUO!FS.
23-ELECTRICAL STOS C FIRE PROT. R. FEIT TO FORM CTR 2. T9 T75 CONDUIT C BARRIER CUlr.E LINES.
BASIS FOR N:w GUIDES.
CTR 2, 79 28-PRIMARY SYSTEM INTEGRITY T. J. WALKER T76 FAILURE nN ALYSI S MET HODS FOR CCLt LINERS.
ASSES $ MENT OF CONTAIN"ENT INTEGRITY UNDEx ACCIDENT LOADS.
CTR 2, 79 3-PWR-80HT E. H. DAVIDSON TRANSIENT CHF CORR E L A T IOf4. NO CHANGE E. H. DAVIDSON T82 4-PWR-BDHT IN APPENDIK % BUT MAY REPLACE CURRENT CORRELATICN.
3, 79 20-VE55EL INTEGRITY E. L. LYNN QTR T43 THERMAL SHOCK AND STEAM LJNE 6REAK ANALYSIS. PROVIDE 5 A LICD458NO PROCEOURE FOR THERMAL 5 HOCK A'4ALYSIS, MAY RESULT IN I
TECH. SPEC. CH A:4GE S.
N. ZUBER l 14-ADVANCED SYSTEM C00F T60 lwr LOCA TRAC RELEA$iD. PROwlDES NRR WITH QTR 3, 79 l l
ADVANCED BwR AND PWR CGOLANT SYSTLMS 5000 I TO ESTABLISH MARGINS OF SAF CTY.
GTR 3, 79 17-VERIFICATION L. 5. TONG I63 VERIFY RELAP 4 MOD 6. VERIFIE S PMR 8EST ESTIM ATE AN ALYSIS THRtf REFLC00 W. V. JOHNSTON 3, 79 12-FUEt. SEHAVIGR VERIFY FRAP T4. ADDS TO ERAP T3; Al QTR l T6+ l PR2LIMINARY CAPABILi'Y FOR MULTI-ROU GEOMETRY AND B) CAPA6II I TY TO EVALUATE {
STATISTICAL VARIATIONS IN MOCELS.
QTR 3, 79 15-CONTAINMENT CODE
- 5. F ABIC TFT BEACCN MOD 5. INTEGRATES SEVERAL PACKAGES IN BEACGr4 INCLUDING PSS POOL OYNAMIC5, ICE CONDENSER, AND H2 CONCEN-TRATION ANALYS15.
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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.
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ASSESSMENT OF FUEL FAILURE L OC A T I ON Or HCCA ANALYSIS.
M. SILBERBERG AEROSOL MODEL QTR 4, 79 25-AEROSCL RELEASE C TRANSPORT TR9 MIX AEROSOL TESTS.
VAL 10ATICN.
4, 79 3-PWR-BDHT E.H. DAVIDSON QTR E. H. DAVIOSON T9] POST LMF HEAT TRANSFde CORRELATION 4-EWR-BDHT VLRIFICATION COMPLETE. SUP/GRT5 OR RFPLACED CURRENT COR4FLATIONS.
79 5-REFLCOD HEAT TRANSFER E.H. DAVIDSON QTR 4, T91 17 X lT RffiOOO FEAT TRANSFER CORRELA-TION VERIFIFO. MAY RrQUIAE NEw SEC T ION OF APPE40!X K TO ADORC55 THIS GEOMCTRY.
79 20-VE55EL INTEGRIYY E. 4 LYNN QTR 4 TICS RECCMMEND OPTIMIZED PIPIN- SYSTEM CESIGN. GUIDELINES FOR SAf tR PIP.NS SYSTEMS.
8-2;RCALOY CLAD 0!NG M.L. PICKLESIMER MAY R/PLACF Q!R 1. 80 ToS EM8RITTLEMENT CRITERIA.
K.
l EXISTING CRITEPIA IN APPEN0tX 80 14-ADVANCED SYSTEM CODE N ZUBER T94 THOR 1 (Emi RELfASED. PROVIDES LICENSING CIR 1.
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L. 5. TONG GIVE5 CONfICEN;E THRU QTR 1, 80 17-VE R I F IC A T ION Toi VER!iY TRAC-2.
COMPARISON WITH LOFT. GERMA4 AND JAPANJ5E TEST DATA.
L. 5. TONG CON- CTR 1, 60 17-VERIFICATION T96 VERIFY HEAT TRANSFE R COR7EL ATION.
FICENCE IM THE CORRELATION 15 INCREASED THRU COMPARIS0N wlTH WORIO WIDE IEST DATA.
16-REFERENCE SYSTEM FODE 5. FAbtC USE CONVENIENT QTR 1, 80 T97 RELAP 4 MCD 7.
PWR LOC A CODE i3-FUEL MELT R. DISALVO QTR 1. 80 .
T100 PROSABILITY AND CGNSEOUE NCE S OF STEA4 I ERPLO5 IONS. POS$1BLY WILL PRCVIDE A I QUANTITATIVE PREDICTION OF STEAM I ERPLOSIGNS MOSTLY APPLICAdLE TO FLOAT ING PL ANT S.
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T102 UPDATE KIR CURVE-CRACF ARREST. BASIS QTR I. 80 20-VE55EL INTEGRITY FOR SEVERE ACCICENT ANALYSIS ARREST E. K . LYNN EVALUATION.
T104 REACTOR PRESSURE VE5SEL SURVEILLANCE QTR 1. 80 PROCEDURE. PROVICES BACKGRGUND TO 20-VE55EL INTEGRITY E. K. LYNN ACCURATELY EVALUATE SURVEILLANCE EMBRITTLEMENT ANC FLUENCE SAFC LIFETIMES.
Y10T IM"RCVED LOOS E PAR TS MONI TORING. PROVIDES QTR 1. 80 INPUT TO REG. GUIDE REQUIREM2NT CHANGE AND 69-NO!5E SURVE:LLANCE AND W. FARHER TO LICEN51NG REVIEh. DIOGNOSTICS T109 EVALJATE METHOD TO CALCULATE COASTAL QTR 1. CO I DISPER5!CN. MAY IMPAC T CN LICtNSING 62-LWR RISK ASSESSMENT J. MURPHY 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 CON *IoENCE IN EVALUATION OF FLOW SIG- 21-NON-DESTRUCTIVE EXAMINATION J. MUSC AR A NIFICANCE FROM ACCURATE FLOk SHAPE AND SIZE.
Y1C6 l VAL TION.ID AT E ACDUST ICS EMISSION t L AW CORRELA- QTR 2. 80 VALIDATES THE DETECTICN. 21-NON-PFSTRUCTIVE EXAMINATION J. MUSCAR A 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 CF CCOLABILITY CF SUSA55EMBLY UNDER P. M. WOOD NATURAL CONVECTION. ANALYSIS T111 CREEP FATIGUE INTERALTION TESTS AND OTR 2. 80 CODE. 28-PRIMARY SYSTEM INTEGRITY T. J. WALKER VERIFIES GESIGN RULES FOR LONG !
TERM PRIMARY SYSTEM INTEGRITY.
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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.
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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.
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