ML20195J593
| ML20195J593 | |
| Person / Time | |
|---|---|
| Issue date: | 09/15/1978 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| References | |
| NUREG-0435, NUREG-0435-V01-N03, NUREG-435, NUREG-435-V1-N3, NUDOCS 8812020281 | |
| Download: ML20195J593 (51) | |
Text
NUREG - 0435 Dat.
df b3/15/78 0FFICE OF NUCLEAR
' REGULATORY RESEARCH w
I
~
9 *R'Co s '+
STATUS kik y;$
SUMMARY
's,,,,,/
REPORT l
RESEARCH RESULTS UTILIZATION
.;y
r
(
i l
f I
i I
i i
i t
6 eA l
W 4A u
W O
l me W
b l
w>
b
>4 6
o f
u e6 4
eie D
og d
)
w w
W L
I W
o z
A M
l T
o=
t
- e i
a e en 2
D
> k W
Q es W
W D
to l
R 71 X
C CA u
W W u
w M
ee k
b O
K 1 o
w a
u o gr' 4
da **
W 4d d
be 4
A W
4 en W
em e f e
Q e
W ar ed b
G eiie-w f
w W
.K.
w o
et
> E w
- u W
- w p
4A ed et to De W
tt
.4 en ed 4
W o
4 u 6
(
3 l
A
.4 I"
f
.O* w e.
w M
D L hea l
J 4
W to E
W an
- e
.e w
b Q
d 4
3 4
b W
O E O *= E
(
E
- w a t
3 e = w p@
u ** O e-I n m ed 4.
U Q
W W
Ju w
M M
e
- te O E w
- 4 i
t
- 4 fd f4 4=
e O.
e.
- hj O$
L i
b l
d i
O E
l
- tt 4 O
- I 4
u.
p si i
P f
i w
W G
4 4
E E
e4 ME Z
W W
WETO O
402K 24 ha44QW OW kW QOW W
Wa Gm O
@@Z
@M 00 em6We >>em
@mEE *AQWWQDM O
O ON M
OE@
W 3
WWEM Z>>WQdC@
D e
DMONEupE 240WE eO
@Wm40kM404 Ukn
@k E
WwwEM4wNW E
AM M4 Q
WA WWWMMe@OW 3
H EOQuemEWWMZ U Wh *>
1 ECW6WWaEOQhem
- W MZ WOMO vuk3@much u
(WAD CM MUWEMWA mW EO 4>w Ww WW QD@
@4
>O O
I WWWW *EAW W
WOM kW5 W20W i
i w
em>Ze>AZW3 wZ
( v.
34rb Q
WWWW@
4>THUCOM WW s
.J W k2Q W6 kW W
>E
- @O C4 O
3UGwE MWpW2
@3EZ WW
>@wWO 404 ZupM MO 4 WOW m
i HD M44MwEMWup>D4 E
MM m
20 EWMDAOrw E
OMO W4
@>>E Z
@WWW M1 kWE2WW D WWUC E4 M4 t
uw z wwwwWeutwoAw uwdM w
CD WOW WM>>4WouOu NW M
@2 OW k E W W O U C E fL W 6 NW w>
6 *AM mM EZ
>4EN>MbwEkZWAW 4
6hDu Wew 4>
246 3' MOMMA > WO e Quem ANO O*w WMWU 4
4 m
W W3a EeO
@E
>EWWD*7.CO Ok O D>M kwom LM W>ZOEmuWww(k2
>WW EwwD
- A ekokWW WM EW4 DO dowk WOW 4@
WWW 40 QUDO E WEZ NUQ CW NZ E
M *EWu we>O du M
we*
pe
@w OkMW w(APwdOW kmq 30 MW U
a 3
kud ZE e ME4r a 4 W OppZs Ws2 l
- Emmek
- W AMED W
- O wpD kMp WW W kW600 E>W uC>
O M4W 4
4 QE OwwwEXWmWmuW W
UO WWEW OE4 M
W4MWMk3WZ AMmZ W4w OwMMZ UN WMMu M*Irw W@u 3A
>4u u
g
> C F,8 0020 Ou 4>
ME3
>WWW@
j M
wM4D km AEdwo OOO4m u A4 W4 wwkwWpM MW E
O Ma@M>
W te O p W e **
W>
own
==
- Z sm4>w O
434hWL4@
4 We O
Wh B @
A@
EW mWEN>kM*OEp@
Ow 3 CEW On WDa4MwWp4w wO@
wwW WWauw 0
.P M
h6OhwCEEwAkDh>
>Mu EkMON E
M6 4
3OMQwwwkW@( E 4>4 4
64 M
4Q 4
Op>OQ&4AWDW A
@23 e 3
a N
a END M
4WOD W
- 2 u@wMO M
M2
@wuk
- 2 TOA wW WW4 4WM k
wO e Qu%@WOOVW Zw WWE Wuk34 3
+
MM w
Wa>>McMErudW uwa M
W l
MEWWM4EwZWQE4@
MM
@602I E
&Q@@
0343WM4 W
WmW 8h>
Q M
DM Nu wMWDe QHWkZ wDZ MO O
r
@Ma
>4 WC>@Q M@OV
@u > OEE O r
wwg 4W Wh>EMWWeW>
DEZwQ W
i 4
wM i wwZM w Nuonu WWO meM>M o
EZZ Mhmun k
I D e *;*
A4>@OE4MW4 4 *
@DJ WEU KWW@KI 6wW M4 kO4W4 4
WOsw 3
W a.a m ODwW434Oh>
e n W m.u a
mW v>
v e w u r, et 4
W
= a 36 QA
- EEM Z..d MAhws O
Q
%=
w 3HO v'RwuCMEsD
@OGk e m. >ee
> E D
u WJ4W2 4A@
- WM A
WO@
47%4@N
@upWO
@Me W2Ohb W
MEW 440
- uhweM4Wk e
Q4MO e
wN>w@
WMu Ei hwwOkkwwuwA wE
- O erM C44 m A M M u o 4 W w M p A MOh we M
l wh>
Mao
&&A>
CQwMd h >. w WZEWZ w
eUNT 46w A
em wdhap D
. M o u w W r d w A E A [, e Ej kWu I
wuE mOQm o
O aud M
2h TwrwzZuM4 4404 wwD MuwM6 Z
j EGA h%44*>uC>>&
v 4@2 3@Q v
Qu na W
WW@ wow ZuMz D
O W we2dwh 004>W EZA Ow O2 O
>22 FW4wMe@
WeaMkO OMD AZWAC l
O kOW ww>m
@wwudA>O4 O
@>>@M E
C OM ME OMEZMw 2@E 002 WO4WW W
l r
e6DOw*
EwO 4 MkD
[
hQ w W W W V
Ap@
EZK W
uOw
>W Me OM G
L muMOM>= COW "CO.
-23
@zA@M C
E WWW M
=EM mu e4h 4kr>
WsA4
@ww MMOMk u
@OM 614 W Z M O W
O O
M@M 4
Mw.*
vs A4 2AOwwW>WW@
wWM
@@A40 W
TEC WOh30WFM@ZZZZW WW WWAEM w
l pe '%
h-WpukWNQWMe>4 (AE kW440 4
f I
2 1HD5ASI DE IMEARI DE RIL11 DE IHE RESHLAIDEI tRDGEli INCREASED TECH BASIS STANDARD STANDARD LICENSEE UNDERSTANDING LICENSING RECO-REG.
TECH STD.
FORMAT &
REVIEW INSPEC.
REPORTING RIls OF PHENOMENON REVIEW LATIOy GUIDE $
SPEC 1 DEVELOP.
COMTENT PLAH PROGRAM REQULREMENT t
YES 2
SCME POSSIBLE YES POSS.
3 YES 4
YES YES S
YES 6
SOME 7
YES 85 YES POSSIBLE PDSS.
POSS.
POSS.
95 YES POSSIBLE POSS.
POSS.
POSS.
10 YES YES 11 POSd.
POSSIBLE 12 YES YES 13 YES YES YES YES YES YES 14 YES YES YES YES YEt 15 YES YES YES 16 YES YES 17 YES YES 18 POSS.
POSSIBLE 19 POSS.
20 YES YES YES YES YES
~~21 YES POSSIELE 23 POSSIBLE POSS.
POSS.
POSS.
24 POSSIBLE POSS.
POSS.
POSS.
25 SOME
"!26 YES YES 27m
1llli 3
E L
U R
S C
C 3
E 0
G N
I G
N A
H C
R O
F N
A L
F N
O I
T C
)A S
R EN SC U
L YA BV O
S DR E
EP Y
WP EA I
VN EO RI S
GS NI IM E P.
BD S
C E
Y Y
8
= =
8 9
0 t
2 3
4
= 8 2 2 3
3 3
3 3
l
4 2.1 LIST OF ISSUED pit's RESEARCH INFORM 7. TION LETTERS ISSUED BY RES TO DATE ARE LISTED BELOW IN TABLE 2.1 TOGETHER WITH THE DATE OF ISSUE. ASSOCIATED F.ESEARCH PROGRAM ELEMENT AND PROGRAM MANAGER.
DATE PIL N9.
F80E NO.
ISSUED RESEARCH INF0DMATION LETTER TITLE RES PROG'AM ELEMENT PROJECT MANAgeg 1
7 3/19/74 ORNL V-5 INTERMEDIATE VESSEL TEST RESULTS PRIMARY SYS INTEG.
C. SERPAN 2
3 5/20/74 SEISM 0 TECTONIC MAP OF THE EASTERN UNITED SITE SAFETY J. HARBOUR STATES 3
9 3/7/74 ORNL V-7 INTERMEDIATE VESSEL TEST RESULTS PRIMARY SYS INTEG.
C. SERPAN 4
10 9/10/74 MAP SH0! JING RECENCY OF FAULTING IN COASTAL SITE SAFETY J. HARBOUR SOUTHERN CALIFORNIA 5
11 6/2d/76 CONFIRMATORY PRESSURE VESSEL TEST UNDER PRIMARY SYS INTEG.
C. SERPAN PNEUMATIC LOADING 6
12 10/12/76 A CRITIQUE OF THE BOARD-HALL MODEL FUR THERMAL FAST BREEDER REACTOR R WRIGHT DETONATIONS IN THE UO2-NA SYSTEM 7
t3 3/25/76 THE SIMMFR CORE r0R ANALYSIS OF HYPOTHETICAL FAST BREEDER REACTOR R. CURTIS CORE DISRUPTIVE ACCIDENTS IN LMFPC'S 3
14 1/31/77 DECAY HEAT DATA APPLICABLE TO LOCA EVALUATION FUEL BEHAVIOR R. DISALVO 9
15 3/14/77 HIGH TEMPERATURE OXIDATION OF ZIRCALOY FUEL FUEL BEHAVIOR M. PICKLESIMER CLADDING IN STEAM 10 16 2/25/77 PRESSURE VESSEL FAILDRE PROBABILITY PREDICTION RISK ASSESSMENT W. VESELY (OCIAVIA CODE)
PRIMARY SYS INTEG.
11 17 9/15/77 IEEE NUCLEAM RELIABILITY DATA MANUAL RISK ASSESSMENT J. JOHNSON
~2 13 6/16/77 MODIF' CATIONS T7 PRESSURE VESSEL FAILURE PISK ASSESSMENT W.
VESELY PROBAsILITY PREDICTIGN (OCIAVIA CODE)
PRIMARY SYS INTEG.
13 19 11/11/77 RESIDUAL STRESSES IN WELDS PRIMARY SYS INTEG.
C. SERPAN 14 20 11/9/77 PHYSICAL SEPARATION CRITERIA FDP ELECTRICAL SYSTEMS ENG.
R. FEIT CABLE TRAYS (HORIZONTAL OPEN SPACC CONFIG.)
15 22 12/1/77 CHARACTERIZATION OF Ek2 FEEDWATER N0ZZLE PRIMARY SYS INTEG.
C. SERFAN CORNER CRACKS 16 23 12/t/77 WARM PRESTRESSING PRIMARY SYS INTEG.
C.
SERPAN 17 24 5/05/78 FCRER BURST FACILITY (PBF) SINGLk ROD-POWER FUEL PEHAVIOR R. VAN HOUTEN COOLING ttISMATCH (PCM) YEST RESULTS 15 25 11/9/77 FRANTIC COM.* UTER CODE RISK ASSESSMENT F.
GOLDBERG 04
5 DATE PIL NO.
PAGE.ND, JSSUED RESEARCH TWFORMATION LEVTER_TXTL(_
RES PROGPAM ELEMENT PRCJECT MANAGER t?
20 t/31/78 30 METHODOLOG's ASSESSMENT RISK ASSESSMENT J. PITTMAN 2c 27 t/24/73 A STUDY OF PHYSICAL PROTECTION EQUIPMENT SAFrGUARDS E.
RICHARD 21 28 3/24/73 CRITICAL REVIEW GF SODiLM HYDROXIDE AEROSOL RISK ASSESSMENT M.
CULLINCFORD T0XICITY 23 29 4/10/75 "EASI" ADVERSARY SEQUENCE EVALUATION MODEL SAFEGUARDS R. ROBINSON
{CCMPUTER GRAPHICS VERSION) 24 30 4/10/75 "FESEM" ADVERSARY SEQUENCE EVALUATION SAFEGUARDS R. ROBINSON MODEL 25 31 3/21/78 FRAP-33 FUEL BEHAVIOR G. MARINO 26 32 4/27/15 TPE IMPACT OF CFFTH9RE NUCLEAR GENERATING FUEL CYCLE SAFETY D.
BARNA ST ATI0t:5 ON RECREATIONAL BEHAVIOR AT ADJACENT AND ENVIRONMENTAL COASTAL SITES.
EFFECTS 27 33 6/02/78
' BEACON / MOD 2" CODE DEVELOPMENT S.
FABIC 23 34 5/09/78 "hELT/ CONCRETE INTERACTIONS" FAST BREEDER. REACTOR R.
DISALJD 29 35 6/07/78 "FUEL ROD AN ALYSIS COMPUTER CODE:
FRAP-T3" FUEL BEHAVIOR H.
SCOTT 30 36 6/28/73 PHASE 1 FINAL RFFORI. "BARRIER PENETRATION SAFEGUARDS R. ZIMMERMAN DATA BASE"; 0F STUGY. "ASSISTANCE-PHYSICAL PROTECTION ASSESSMENTS" 31 37 7/10/78 ASSAY OF STANDARD REFERENCE MATERIAL (SRM)950 SAFEGUARDS R. SHEPARD 32 35 8/3/73 IMPROVEMENTS IN THE AEROSOL BEHAVIOR CODE FOR FAST BREEDFR J.
LARKINS PADIOLOGICAL ASSESSMENTS Gr LMFER'S REACTOR 33 39 8/3/78 PLUTONIUM ACCIDENT CONTAINER PROGRAM RESEARCH, FUFL CYCLE SAFETY W.
LAHS DESIGN AND DEVELOPMENT.
AND ENVIRONMENTAL EFFECTS 34 40 3/3/76 NUCLEAR DECAY DATA FOR RADIONUCLIDES DCCURRING FUEL CYCLE SAFITY J. FOULKE IN ROUTINE RELEASES FROM NUCLEAR FUEL CYCLE AND ENVIRGNMENTAL FACILITIES EFFESTS 05
+
6 2,2 P9TENTIAL APPLICA5fLITY OF RESE APf"1.. RESUL.WH TH1EEATORY PPOCESS COMMEMTS ARE OFFERED FROM RES AND FROM COGNIZANT USEP CFFICES ON THE NATURE OF THE REPORTED RESULTS AND THEIR POTENTIAL (OR ACTUAL) APPLICABILITY TO ANY PART OF Tl!E REGULA1 CRY PROCESS. INCLUDING:
A) TECHNILAL DATA SUPPC"TING LICENSING REVIEWS CP REGULAICRY JUDGMENT, 5) EVALUATION CODES. C) INFORMATION APPLICABLE TO REGULATORY GUIDES OR STANDARDS, AND G) INFORMATI0H SUPPORTING JUDGMENTS REGARDING REGl'L A T CRY POL ICY.
06
7 PROGRAM Off1CE CC"nENTS ON PO!ENTIAL bT1t!2ftICh_L5[3ALUE OF RESEARCH RESULTS IN THE REGULATORY PROCESS R't 8:
1 DATE ISSUED:
3/19/74 RES PR0qEEN ELEMENT: PRIMARY SYSTEM INTEGRITY E11_TJ1L$1 GRNL V-5 INTERMEDIATE VESSEL TEST RESOLTS {c2hl HSST PROGRAM) iECNSORING OFFICE (1): RES RRQ:
1-23 f2SSEL INTEGRITY EE1EARCH PROJECT MGR:
C. SERPAN RES CCr?ENT1: EXPERIMENTAL EVIDENCE THAT A "SAFE" FAIiURE NODE (LEAK-BEFORE-BREAK) FOR REACTOR PRESSURE VESSELS MAY EXIST, WAS REPORTED FOR THE FIRST i!ME.
TESIS ON THF. V-S INTERMEDIATE VESSEL AT ORNL DEMONSTRATED THAT A LEAK OCCURRED INSTEAD OF A FRACTURE BREAK WHEN THE VESSEt WSS HEATED TO 190 F AMD PRESSURIZED TO 26,600 PSI.
FULTHER ANALYTICAL STUDY TO GENERALIZE THIS RESULT IS UNDER/AY.
USER DISCUSSION POSITIO.i COMMISSION ACRS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS
'_Q11_R I t ACTIVIiIES R EVILH HELD COMPLETED HELD HELD ISSUED IMPLEMENTED OFFICE RESPONSIBLE......... NRR/bD NRR SCHEDULED CCMPLETION DATE.. --
UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED N/A ACTUAL COMPLETION DATE.....
05/21/78 N/A ER_C0r"ENTS ON 09/09/77, 03./21/73, B. QRjMES DElf31SE APPLICATLQN T O R EG')1 Alp R Y PROC (1}: THE RESULTS OF THIS TEST ADDED TO THE STAFF'S UNDERSTANDING OF FRACTURES ORIGINATING AT FLAWS IN N0ZZLE CORNERS OF HEAVY SECTION STEEL VESSELS.
IF LEAK-BEFORE-BREAK COULD BE DEMONSTRATED UNDER ALL REASONASLY CONCEIVABLE CONDITIONS AND CIRCUMSTANCES, IT WOULD DEMONSTRATE THAT CURRENT LICENSING POSITIONS ARE VERY CONSIRVATIVE.
RE1CE15E.* PACT OF RESQLT1: WHILE ADD;NG TO CUR UNDERSTANDING OF VESSEL FAILURE MODES, THERE HAS BEEN N3 DEFINITIVE IMPACI ON LICENSING AT THIS TIME.
sEEE_ENT S/R EEEEKS : THE OPINIONS EXPRESSED IN THE RTL REGARDING LEt.K-BEFORE-BREAK ARE ENCOURAGING BUT HEED FURIHER SUBSTANTIATION BEFORE CURRENT LICENSING POSITIONS CAN BE RELAXED.
SD CCt3ENTS ON n9/13/73, P RaNDatt THIS PROGRAM HAS GENERATED SUSSIANTIAL DATA USED IN PREDICTING IRRADIATION EMBRITTLEMENT AND MARGINS TO FAILURE OF REACTOR PRFSSURE VESSELS WHEN FLAWS ARE PAESENT, CONSIDERING MATERIAL PROPERTICS AND LOADINGS.
THIS PROGRAM HAS PROVIDED INPUT TO NRC REQUIREMENTS FOR FRACTURE TOUGHNESS OF PRESSURE VESSEL MATERIALS DESCRIBED IN APPENJIX G TO 10 CFR S3 AND CCNTRIBUTED LA1A USED IN
'HE ASME Core WHICH WAS INCORPORATED INTO APPENDIY G.
IT HJ.S ALSO PROVIDED PART OF THE DATA PASE USED IN REGULATORY CUIDE 1.99 CONCERNING THE EFFECT OF COP /ER IMPURITIES CH SENSITIVITY OF STEEL TO IRRADIATICN AND IS EXPECTED 10 PROVIDE A SUBSTANTIAL INPUT FOR FUTURE REVISIONS TO REGULATORY GUIDE 1.99.
07
8 PPDGRAM OFSICE COMMENTS ON POTENTIAL UTILIZATION OR vaLUE OF RESEARCH RESULTS IN THE PEGULATORY PROCESS PfL 8:
2 DATE ISSUED:
S/20/74 RE3 P90GR AM Elf t"FHT:
SITE SAFETY QIL TITLE: SEISMO TECTONIC MAP OF THE EASTERN UNITED STATES SPONSOFING OFFICEfS): RES ERG: 3-2 GEOLOGY t SEISNIC CHARACTERISTICS RESEARCH PROJECT MGR:
J. HARBOUR P E5_Gh f EN TX RIL 2 REPORT $ A COMPILATION OF E.1R?HQUAKE FAULT DA'A FOR THE EASTERN UNITED STATE!.
THESE DATA ARE USED BY LICENSE APPLTCANTS IN PREPARATION OF MATERIAL FOR PRELIMINARY SAFETY ANALYSIS REPORTS.
USER DISCUSSION POSITION COMMISSION ACRS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS POST RIL ACTIV H1El RE V_Jf14
.H_EJ S0*'P L E T E Q H_E_L D HELD ISSUED IMPLEMENTED OFFICE RESPONSIBLE......... NRR/SD NRR SCHEDULED CC'"PLETION D%TE.. --
t:MSCHED UNICHED UNSCHED UNSCHED (INSCHED 1974 ACTUAL CCMPLETICN DATE.....
9/27/77 1974 ficR_C3 r ENTS ON 09/27/77.
R.
PENTSE:
DIMERE APP L IGH0f8 10 P1QVL 41CWY PPf]Q$3:
THIS RESEARCH DEVELOPED LIMITED SEISMOTECTDNIC PROVINCES MAPPING OF INE EASTERN UNTIED SIA!ES AI:1ED AY IMPLEMENTING APPENDIX A R2QUIRENENT! FCE DEIERMINING SEISMIC DESIGN FOR NUCLEAR FACILITIES.
DE1[P_ME_JMP ACT OF RE3VU3: THE RESEAPCM ADDED VERY LITTLE TO'JUR KNnWLEDGE OF EARTHQUAKE PROCESSES IN THE EAST ERN UNITED ST AIES L:HICH CD'JLD BE USED TO IMPLEMENT APPENDIX A REQUIREMENTS.
G ZfNT5/_PE[APKS: CURRENT EARTHQUAKE MONITORING AND TELTGNIC STUDIES EHOULD BE SYNTHESIZED TO DEVELOP AN APPLICABLE SEISM 0 TECTONIC MAP.
1D__C CCEN T S__flN 09/15/7b G.
RIVEN 4 art (
THIS SIUDY IS PRESENILY USED AS GUIDANCE IN ASSESSING TECTONIC PROVINCES AND SEISMICITY IN LICENSING CASE REVIEWS IN THE EASTERN UNITED STATES.
THIS STUDY, AS WELL AS ONSOING STUDIES, WILL EVENTUALLY BE USED TO OFFER GUIDAdCE ON A REGIONAL B ASIS TitROUGH REGULATORY GUIDES.
08
9 PPOGQAM OEFICE COMMENTS ON POIENT11L_*J.ILIZATION O' VALUE OF RESEARCN RESULTS IN VHE REGULATORY PROCESS DIt s:
3 DATE ISSUED:
8/7/74 RES PM004 AM FLDjf 4T_:
PRIMARY SYSTEM INTEGRITY PIL TITLE:
ort.L V-7 INTERMEDIATE VES3EL TEST RESULIS inEt.L HSST PROGRAM)
SPONSORING OFFICE (5):
RES EpQ:
1-20 VESSEi INTEGRITY RESEARCH PROJECT MGR:
C. SERPAN RE1_CQ5"ENT1: ADDITIGNAL EXPERIMENTAL FVIDENCE IS DEMONSTRATED THAT A "SAFE" FAILURE MODE FOR REACTOR PRESSURE VES$tLS MAY EXIST. NAMELY. "LEAK-BEFDP2-3REAK".
THESE RESULTS SUPPORT EARLIER RESULTS REPORTED IN RIL 81.
IN THIS TEST. THE FLOW WAS 13-INCHES LUNG AND 5-INCHES CEEP IN THE 6-INCH THICK PRESSURE VESSEL MALL.
THE VESSEL WAS ABLE TO SUSTAIN IWICE THE DESIGN LOA 9 PRIOR 70 PEN 1RA) ION OF THE FLOW THROUGH THE REMAINING THIN LIGAMENT OF VESSEL MATERIAL.
THIS RESEARCH CONTRIBUfES TO OUR UND.'P".TANDING OF VESSEL FAILURE MODE.
THIS INCREASED UNDERSTANDING SUPPORTS THE NRR STAFF IN ITS REVIEW EF70RTS.
USER DISCUSSION PGsII!O;;
COMMISSICH ACR$
PRESS OFFICE MFETING PAFE7 BRIEFING BRIEFING RELEASE RESULTS EpST RIL ACTIVITIES Elvish HEL D C0716 L ET ED HELD HELD ISSUED IMPLEMENTED OFFICE RESFONSIBLE......... NRR/SD NRR SCHEDULED CCMPLETION DATE.. --
UNSCHED UNSCHED UNSchED UNSCHED UNSCHED N/A ACTUAL CCMPLETION DATE.... 9/9/77 N/A NUP Cp55[NTS ON 09/09/77, D,
EISEN3ME D E $(EllE A P P L I C A_i_! QN TQ Rf Gy(AJ ORY PPQCESS: THE TEST RESUI TS HAVE BEEN USEFUL IN ESTIMATING THE MARGIN OF SAFETY. IN TERMS OF FLAW SIZE. FOR A L AkGE FL AW IN A HEAVY SECTION STEEL VESSEL TESTED AT UFPER SHELF TEMPERATURES. WHILE CRACK ADVANCEMENT THRD.'GH THE REMAINING WALL LIGAMENT WAS IN THE STABLE TEARING MOD;. PRODUCING A LEAK. AND PRESSURE TO CAUSE LEAKAGE WAS MORE THAN ! MICE THE VESSEL DESIGN PRESSURE, THESE RESULTS MAY HAVE BEEN INSUCCD BY THE SPECIAL EFFECTS OF THE TEST GECNETRY.
DESCELD E_Ju! AC T OF RESULTS: NHILE ADDtHO TO OUR UMDERSTANDING OF VESSEL FAILURE MODES. THERE HAS BEEN NO DEFINIIIVE IMPACI CN LICENSING t.T THIS IIME.
C9"MENTS/ REMARKS:
THE OPINIONS EXPRESSF) IN THE RIL REGARDING LEAK-BEFORE-BREAK ARE STILL SPECULATIVE.
SD C0"_2ENT3_cN 09/15/JLS., e. eANCALL IHIS PROGRAM HAS GENERATED 30BSIANTIAL DATA U3ED IN PREDICTING IRRADIAlION EMBRITTLEMENT AND MARGINS TO FAILURE OF REACTOR PRESSURE VESSELS WHEN FLAWS ARE PREStNT. CONSIDERING MATERIAL PROPERTIES AND LOADINGS.
THIS PROGRAM PAS PROVIDED INPUT TO NRC REQUIREMENTS FOR FRACTURE TOUGHNESS OF FRESSURE VESSEL MATERIALS DESCRIBED IM fPPENDIX G TO 10 CFR 50 AND CONTRIBUTED DATA USED IN THE ASME CODE WHICH WAS INCORPORATED INTO kPPENDIX G.
IT HAS ALSO PROVIDED PART OF THE DATA BASE USED IN REGULATORY GUISE Y.99 CONCERNING THE E."FECT OF COPPER IMPL* CITIES OM SENSITIVITY OF STEEL TO 1RRADIATION AND IS EXPECTED TO FROVIDE A SUBSTANTIAL INPUT FOR FUTURE REVISIONS TO REGULATORY GUIDE I.99.
09
l
\\ i 10 5>c0 GRAM 06FICE CO M ENTS ON P O T E N ! DDffRT('IT I ON OR VALOF Q7 RESE. ARCH RESutJJ IN THE REGULATORY PROCESS RIL a:
4 DATE ISSUED:
9/10/74 eJS P90GDAM E Rf1Nf' SITE SAFETY pit TITLE: MAP SHDMING RECENCY OF FAULTING IN COASTAL SCUTHERN CALIFORNIA SPONSQL*!*((. O FFICE(S ) : RES EEQ: 3-2 GEOLOGY
- SEIsh!C CHARACTERISTICS RESEARrH PROJECT MGR:
J. HARBOUR
@E}_CQ m ENT): RIL 4 COVERED FAULTING IN COASTAL SOU T H err 4 CALIFORHIA AND IS REFERRED TO dY HRR WHEN CONSIDERING l
SEISMIC SAFETY QUESTIONS REGAREING PLANTS IN THE AREA COVERED.
USER DISCUSSION PGSITION COMMISSION ACRS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RES:ILTS D$T_RILa[TIUTlfj EEVE y HELD __
[OMP(fTE2 HELD HELD ISSUED IMPLEMENTED OFFICE RESPCNSIBLE......... NER/SD NRR SCHEDULED C0MPLETICN DATE.. --
UNSCHED UNSCHED UNSchED UNSCHED UNSCHED 1975 ACTUAL COMPLETION DATE.....
9/27/77 1975 1
N_EP_(PE (NTS QN 09/27/77.
R.
DENISE Pt31EI RE A PF L I{a TJ UN TO RECH AIQRY PR1GE31: TO BE USED IN SELECTING SITES FOR NUCLEAR FACILITIES AND T
FOR REGIONAL INPUT 10 STAFF REVIEW OF Nt CLEAR FACILITY APPLICATIONS.
PE5CRJ E_IUP A CT QF Pf$Q W : WORK PROVIbED NEW KNOWLEDGE OF THE DISTRIBUTION OF ACTIV2 FAUETS IN COASIAL CALIFORNIA. HAS FROVIDED INPUT TO OUR REVIEU OF DIABLO CANYON AND OTHER SITES.
COMMENTS /PEMARFS: WORK HAS LARGELY BEEN COMPLETED. NO EXTENSION IS ANTICIPATED.
Sp_f9_NENTS CN 09/13/78, G.
RIVdNJ_ ARK THE OBJECT CF 1HIS SIUCY UAS 10 PRODUCE DATA DESCRIBING THE RELATIONSHIP BETWEEN EARTHQUAKE MAGNITUDES AND DIMENSIONS OF FAULT DISPLACEMENT. THIS STUDY, ALONG WITH OTHERS. IS USED AS Gb! DANCE IN ASSESSING "CAPABLE FAULTS" IN LICENSING REVIEUS. RIL 54 PROVIDED A MAP WHICH UDPATED INFORMATION ON FAULTING IN COASTAL SOUTHERN CALIFORNIA.
i l
l l
10
11 P&OGoaM OFFICE COMMENTS ON P0fLNTIAL UTILIZATION CR VALUE OF RESEARCH RESUlis IN THE REGULATORY PROCESS RIL 2:
S DATE ISSUED:
6/23/74 RES PROGPAM ELEMENT: PRIMARY SYSTEM INTEGRITY RTL TITLE: CONFIRMATORY PRESSURF VESSEL TEST UNDER PNEi;MATIC LCADING (ORNL HSST PROGRAM)
SPONSORING OFFICE (S):
RES ERS:
1-20 VESSEL INTEGRITY RESEADCH PROJECT MGR:
C.
SERPAN p(1_(f5][NT1: RIt'S 1 35 5 REPCRTED TH5 RESULTS FRar1 THE HEAVf SECTION STEEL TECHNOLOGY PROGRAM WHICH SHOWED THAT THE ANALYTICAL METHODS FOR PFEDICTING FLAW INITIATION AMD CRACK ARREST IN REACTOR PRESSURE VESSELS HAVE BEEN uELL VALIDATED.
THESE VALIOATED ANALYTaCAL METMODS (LINEAR ELASTIC FRACTURE MECHANICS AND ELASTIC-PLASTIC FRACTURE MECHANICS) ALLOW A PREDICTION OF THOSE CONDITIONS bHDER WHICH FLAWS IN PRESSURE VESSEL STEELS CAN CAUSE FAILURE OF THE VESSEL.
THIS PROVIDES THE NRR. STAFF WITH A NEW TECHNIQUE FOR SETTING SAFE LIMITS FOR NORMAL QPERATION AND FOR ABNORMAL AND ACCCIDENT SITUATIONS TO REDUCE THE LIKELIHOOD OF PRESSURE VESSEL FAILURE.
USER DISCUSSION POSITION CbMMISSION ACRS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS POST RIL ACTIVITIES RivifR HELD COMPLETED net D HELD ISSUED IMPLEMENTED OFFICE RESPONSIBLE......... SRR/SD NRR SCHEDULED COMPLETION DATE.. --
UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL CCMPLETION DATE.....
12/16/77 1976 NPR CQ5 RENTS QN 12/16/77.
J.
KNICHT:
E11C81BE APPLICAljpN TO REGUL A T037 PRC(E15: THE INTERMEDIATE TEST VESSELS, ITV-7 AND ITV-7A UNDER SUSTAINED LOADING DEMONSIRAIED THAT BOI8 I"t VES5ELS RESPONDED 10 PNEUMATIC LUADING ESSENTIALLY AS THEY HAD TO HYDRAULIC LOADING.
EARLIER EXPERIENCE OF A RA.'ID CRACK EXTENSION IN THE GAS FIPE LINE WAS INHIBITING THE ACRS CCMMITTEE ABOUT THE RESULTS OF ITV-1EST UNDER dYDRAULIC LOADING.
HENCE. THE PHEUMATIC LOAD TEST WAS SUGGESTED.
RESCRJ)f IPPACT OF RESULTS:
fMESE TES'S SHOW THAT ThZ VFSSELS UNDER SUSTAINED LOADING BEHAVED SIMILARLY TO HYDRAULIC LOADING. AND THE RESULTS ARE APPLICABLE TO TSE EVALUATION OF THE BEHAVIOR OF EEACTOR PRESSURE VESSELS UNDER SUSTAINED LOAD.
THE TW9 VESSEL TESTS THAT 2UPTURED. WITHSTOOD PRESSURE 2.15 TO 2.75 TIMES DESIGN PRESSUPE.
THE TEST FRESSURES WERE ABOVE ASME B 4 P V CODE A;LOWABLT FOR FAULTED CONDITIONS.
COPMENTS/ REMARKS: TESTS DEMONSTRATE THE LEAK WITHOUf BURI).
12_CC'"1ENTS ON 0 9/13/ZL P. R AN((A([1 THIS PROGRAM HAS OENERATED SUBSTANTIAL DATA USED IN FREDICTING IRRADIATION EMBRITTLEMENT AND MARGINS TO FAILURE OF Ri4CTOR PRESSURE VESSELS WHEN FLAWS ARE PRESENT. CONSIDERING MATERIAL PROPERTIES AND LO ADINGS.
THIS PROGRAM HAS PROVIDED INPUT TO HRC REQUIREMENTS FOR FRACTURE TOUGHNESS OF PRESSURE VESSEL MATERIALS DESCRIBED IN APPENDIX G TO to CfR 50 AND CONTRIBUTED DATA USED IN THE ASME CODE WNICH WAS INCORPORATED IN10 APPENDIX G.
IT HAS ALSO PROVIDED PtRT OF THE DATA BASE USED IN REGULAT0kr GUIDE 1.99 CONCERNING THE EFFECT OF COPPER IMPURITIES ON SENSITIVITY OF STEEL TO IRRADIATICN AND IS EXPECTED TO PROVIDE A SUBSTANTIAL INPUT FOR FUTURE REVISIONS
'O REGULATORY GUIDE 1.99.
kl
12 PROGR AM OFFICE COMMENTS ON FOT E.4fI AL UilL IZ AT ION OR VA10E ff RESEARCH RESULTS IN THE REGULATORY PROCESS Jit 4:
6 DATE ISSUED:
10/12/76 RLS PROGRAM FLEMENT: FAST BREEDER REACTORS
..L PIL TITLE: A CRITIQUE OF THE BOARD-HALL MODEL FOR THERMAL DETONATIONS IN THE UO2-NA
' STEM SPCMSORING OFFICE (S): NRR RPJ:
2-6 ACCIDENT ENERGETICS E ? ARCH PROJECT MGR:
R. WRIGHT PE}_COE"*fM_I5* THIS CRITIQUE OF THE BOARD-MALL THEORY F08' THERMAL EXPLDSIONS I' A URANIUM OA 'E-SODIUM SYSTEM REIhf0RCED THE BELIEF THAT SUCH DE10 NATIONS ARC OF LOW PR03 ABILITY, THE CRITIQUE HAS BEEN Us ' AS AN AID IN t
ANSWERING ACRS CCNCERNS ABOUT THE POSSaBILI TY 06 ENERGETIC F7EL-C00L A'ti IN)ERACTIONS IN ADVAN*.
REACTORS AND WAS EMPLOYED IN SUPPORTING NRR'S PCSIT!9N IN THE EVALUATION GF THC PRELIMINARY SAFETY ANALYSIS Al' ORT FOR THE CLINCH RIVER BREEDER REACTOR.
USER DISCUSSION POSITION COMMISSION ACRS PRESS OFFICE MEETING PAFER BRIEFING BRIEFING RELEASE RESULTS EPST RIL AC_T_1YLT111 REVIEW HELD COMPLETED HELD HELD ISSUED LMPLEMENTED OFFICE RESPONSIBLE......... NRR NRR SCHECULED (CMPLETIDM DATE.. --
UNSCHEG UNSCHED UNSCHED UNSCHED UNSCHED 1977 l
ACTUAL COMPLETION DATE....
9/9/77 1977
!L3_Cpt**fMTS ON 09/09/77. W. GAfCIR:
M} G[pg rPPLISATION TO REGULATORY PRQGhi$' ESTIMATES OF THERMAL DETONATION ENERGIES ARE DIRECTLY RELEVANT IN LICENSING CECISIONS RELATED TO CONTAINMENT REQUIREMENTS FOR LNFBR. PARTICULARLY KINETIC ENERGY RELEASE. SYSTEM DAMAGE AND RADIO ACTIVITY RELEASES. THF RIL TRANSMITTED A CRITIQUE CF THE BOARD AND HALL (UKAEA) THEORY FOR THERMAL EXPLOSIONS IN THE UO2-50DIUM SY5 TEM.
THIS INDEPENDIN! THEORETICAL ASSESSMENT IS USEFUL IM REINFORCING THE CURRENT NRR BELIEF THAT SUCH DETONATIONS ARE OF LOW PR03 ABILITY AND THAT FURTHER EXPERIMENTAL EFFORT IS REQUIRED.
DESCRIBE IMPACT OF R $f W : THE RESULTS 0F THE CRITIGUE ARF MINIMAL IN THIS OH-GOING ifCHNOLOGICAL EXPLORATION.
EXCEPI AS NOTED ABOVE IN REINFORCING THE IDENTIFIED PRECEPfIONS AND NEED FOR EXPERIMENTS. SUCH WORK, INDEPENDENT ASSESSMENTS OF IDENTIFIED AND PDTENTIAL SIGNIFICANT SAFETY ISSUES. SHOULD CONTINUE.
COM"ENTS/REMARES: INE INITIAL EFFORT OF AN EXPERIMENTAL At*G ANALYTICAL EVALUATION OF THE BOARD AND HALL MODEL OF IHERMAL EXPLOSIONS WAS UNDERTAKEN BY DPM AT THE REQUES) D t-THE ACRS (ACRS REQUEST DATED JULY 9.
1975 FOR BOARD AND HALL REVIEW). NOTE DPM RESPONSE TO THIS REQUEST IN A LETTER FROM R. P.
DENISE TO M.
LIBARKIN. ACRS, DATED OCTOBER 24. 1975.
THE PHENOMENON IS APPLICABLE IN THE ONGOING REVIEW OF THE FFTF REACTOR.
NRR HAS BEEN IN CONTINUING CONTACT WITH RES STAFF ON THE RESEARCH PROGRAMS PERTAINING TO INVESTIGAT7.ONS ON THE BOARD AND HALL EFFECT. AND THE GENERAL SUBJECT OF lHERMAL EXPLOSIONS. AND MAINTAINS COGNIZANCE OF SUCH WORK IN THE U.S. AND OTHER COUNTRIES.
b 12
13 PF0GR A7 0FFICE COMMENTS ON PO I EN T I A L UTTL IZ A T ION CR VALUE Of RESEARCH RESULTS IN THE REGULATORY PROCESS PIL 9:
7 DATE ISSUED:
3/25/76 RES PROGRAM ELEMENT: FAST EREEDER REACTORS RIL TITLE: THE SIMNER CODE FOR ANALYSIS OF HYPOTHETICAL CORE DI!RUPTIVE ACCIDENTS IN.1FBR'S SPCNSORING OFFICE (S): NRR ERQ:
2-14 SIMMER CODE RESEARCH PROJECT MGR:
R. CURTIS RIS J05 RENTS: THE SIMMER CODE IS DESICNED TO PRECTCT THE MbrION OF FAST REACTCR CORES DURING POTEN11AL CORE DISRUPTIVE ACCIDENTS. A TRIAL VE2SION OF THIS CODE WAS MADE AVAILABLE TO NkC'S LICENSING STAFF AND HAS SUPPORrCD SRC BRANCH POSITIONS ON li;2 ANALYSIS OF CCRE DISRUF TIVE ACCIDENTS FOR CLINCH RIVER BREEDER REACTOR LICENSING CJNSIDERATIONS. SIMNER IS RECOGNI2ED a5 AN IM?ORTANT FIRST STEP IN THE DEVELOPMENT OF A MECHANISTIC CODE CAPABLE OF DESCRIBING PHENONENA NEFCED TO ASSESS CORE DISRUPTIVE ACCIDENTS IN LIQbID METAL FAST BREEDER REACTORS.
I USER DISCUSSION POSITION COMMISSION ACRS PRESS l
i 0FFICE MEETING PAFER BRIEFING BRIEFING RELEASE RESULTS PQS L P LL_ A CTIVIllEl REVIEW HELD T
OFFICE EE5FONSI3tE......... NRR
$_0j1P_L{ T_FJ UJL D HELD ISSUER _
LMPL EMEN T ED NRR SCHECULED CCMPLETION DATE.
UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED 1976 ACTUAL CCMPLETION DATE.....
9/9/77 1976 NM CCMNT$ 04 09/09/77. W.
GAMMIL(1 ELSCRIPE APELICallgN 10 RlEs1ATORY PROCESS: THE SUBJECT RIL ANNOUNCEP THE AVAILA31LITY OF THE SIMMER-1 CODE.
THE SIMMER-t CODE 15 RECOGNIZED BY NRR AS AN IMPORTANT FIRST STEP IN THE DEVELOPMENT OF A MECHANISTIC CODE CAPABLE OF DESCRIBING RECRITICALITY, TRANSITION PFASE PHENOMENA. AND WUkK ENERGY PARTITION, ALL "ITAL TO ASSESSING CGRE DISRUPTIVE ACCIDENTS IN LMFBRS.
CESCEllE_1tPACT OF P($Q(T}: InERE IS NO INPACT SINCE RESULTS USING THE SIMMER-1 CODE ARE NOT SUFFICIENTLY SU351ANIIATED IO BE USED DIRECTLY IN THE LICENSING DECISIONS FOR LMFBR'S.
IT IS ANTICIPATED THAT FURTHER CODE DEVELCPMENT. AND THE PERFORMANCE OF EXPERIMCHTS WHICH CONFIRM THE COMPUTATIONAL MODELS. WILL YIELD A TOOL WHICH UILL PE USEFUL IN REACHING SIGNIFtCANT LICENSING DECISIONS.
00EEENilLEEneE55: NRR VIERS THE SIMMER PROGRAM AS AN IMPORTANT LONG TERM EFFORT TO DESCRIBE THERMAL AND MECHANICAL CCRE DI5RUPIION ACCIDENT SECUENCES. NRR ALSO SLES NEAR-TERM BENEFIT IN USING SIMMER TO BETTER UNDERSTAND KEY PH E N 0!!EN A. AND THE INTEGRATICN OF THESE PHENOMENA INTO AN A0CCIDENT SEQUENCE. SIMMER AL50 HAS THE BENEFIT OF BEING LARGELY INDEPENDENT OF ERDA SPONSORED WORK.
NRR HAS BEEN IN CGHSTANT COMMUNICATION WITH ARSR AND HAD INITIATED A SMALL T.A.
EFFORT WHICH MAKES USE OF SIMMER.
NPR STAFF HAVE ATTENDED SIMMER WORKSHOPS AND BRIFFINGS OM 9s14-15/76. 4/?9/77 AND 7/21-22/77.
NRR CORRESPONDENCE RELATED TO SIMMER AND SIMMER-RELATED WORK CONDUCTED BY RSR:
1.
TO SAUL LEVINE. RES FROM S. RUSCHE. NRR. "LMFBP SAFETY RESEARCM FPOGRAM PLAN". 3?tS/77.
2.
TO L.
S. RUBENSTEIN FROM R. P. DENISE. "DEGREE OF SUPPORT FOR RESEARCH PROGRAMS FOR ADVANCED REACTORS",
7/6/77 (CC. TO C. KELBER).
3.
TO E. G. CASE FROM R. P.
DENISE. "NER COMMENTS TO ACRS ON ARSR PROGRAM". 7/15.77.
4.
TO SAUL LEVINE, RES. FROM E. CASE. NRR. "RES INFORMATION ON THE UNDERSTANDING OF CDA ENERGETICS IN LMFBR'5".
13
14 PPOGDAM OFFICE CO--ENTS On ForENTIAL UTILIZATION OP_VALUE OF RE11. ARCH RESULTS IN THE REGULATCRY FROCESS AIL s:
3 DATE ISSQip:
t/3t/77 RES PROGPjyl ELEMENT: FUEL BEHAVIOR PIL TITLE: DECAY HEAT DATA APPLICABLE TO LOCA EVALUATION SPONS0efNG OFFICE 111:
RES REQ:
1-11 DECAY HEAT RESEARCH PROJECT MGR:
R. DISALVO RE1_CCf"ENTS: RECENT CALCULATIONS AND EXPERIMENTS WERE PERFORMED 10 DETERMINE A BEST ESTIMATE OF THE VALUE OF THE RESIDUAL (DECAY) HEAT GENERATED IN NUCLEAR FUEL AFTER SNUTDCWN.
THE VALUE CHOSEN FOR RESIDUAL HEAT RATE PLAYS A VERY IMPCRTANT PART IN PREDICilNG THE PERFORMANCE OF ECC SYSTEMS. RESULTS INDICATE THAT THE DECAY HEAT RATE CURREATLY USED HAS A 27% MARGIN OVER THE NEWLY DETERMINED VALUE.
THIS INDICATES A SIGNIFICANT CONSERVATISM IN CURRENT LICENSING BASES AND THEY ARE NOW BEING REEXAMINED.
RIL*S 3 A ? ARE BOTH UNDER REVIEW BY NRR FOR POSSIBLE INCLUSION IN A M3DIFICATION TO THE EMERGENCY CORE CCOLING SYSTEMS (ECCS) RULE PROVIDED IN APPENDIX K OF 10 CFR 50.
THESE RIL*S REPORTED ON COMPLETED PESEARCH PROJECTS IN FISSION PRODUCT DECAY HEAT AND ZIRCALOY OXIDATION RHICH RESULTED IN DAT4 BASES AND CORRELATIONS WHICH INDICATE THAT THOSE IN CURRENT USE IN THE ECCS RULE ARE HIGHLY CONSERVAT'VE.
A COMNISSION PAPER WAS PREPARED (SECY 77-368) ON JULY 1 1977. PRE;ENT STAFF PROGRESS ON A PROPOSED ACTION PLAN REGARDING POSSIBLE MODIFICATION TO THE ECCS RULE.
TPF COMMISSION PAPER (SECY 78-25) PRESENTING THE PROPOSED ACTION PLAN WAS FREPARED ON JANUARY 13. 1973.
USER DISCUSSION PCSITION COMMISSICH ACRS PRESS OFFICE MFETING PAPER BRIEFING BRIEFIN3 RELEASE RESULTS Mil _Rll_A_QTIVJ U11 REVIEW hitD COMPLETED MLD HELD 111EED_
I"PLEMENTED OFFICE RESPONSIBLE......... hP.R.SD NRR NRR.SD.RES NRR.SD.RES NRR SCHEDULER,CCM?LETICN DATE.. --
UNSCHED DEFERRED 9/0/77 1978 ACTUAL CCMPLETICN DATE.....
G3/21/78 9/10/77 7/26/77 9/9/77 MER_CCEMENT3_rN 09/19/77, 0?/21/73, D.
RQSS:
DE1CR151_APPLICAIION.1Q_EliULATORY PRp([lj:
1 NEW DATA IS BEING CONSIDERED AS PARTIAL BASIS FOR MODIFICATION OF PRESENI ECCS PULE ( 10 CFO 50.46 AND APPENDTX K).
PROPGSED OPTION 3 FGR RULE CHANGE INCLUDE ACCEPTABILITY OF NEW DECAY HEAT DATA IN ECCS LICENSING CALCULATIONS.
2.
NEW DATA WILL BE INCCRP09ATED IN ";EST ESIIMATE" ANALYSIS CODES. THESE CODES ARE INTENDED TO BE USED IN PRDBABILISTIC ASSESSMENT'JF SAFETY M.*RGTNS.
p111PJ11_JMP ACT OF RESQLT$:
1 NEW DATA CCNFIRMS MARGINS ALLOTTED IN PRESENT ECCS RULE ARE CONSERVATIVE.
2.
IF ACCEPTED FCR USE IN LOCA LICENS1hG CALCULATIONS, VENDORS COULD USE ADDITIONAL MARGIN IN DESIGN.
(I.E.,
INCREASE PEAK KW/FT. ETC.).
C0r"ENTILEEMAR$$: THE CCMMISSION APPROVED THE PROFDSED ACilUN PLAN TO MODIFY APPENDIX K (SECY 73-26).
NRR AND RES ARE PREPARING A REQUEST TO SD TO INITIATE RULEMAKING TO MODIFY APPENDIX K.
1p_Q 0"{NJ } Rjl 9 / 01/ 7 7, V. PANCJffy:,
IHESE SIUDIES F ROVICE INFOR::AT ION NECESSARY TO ASSESS THE DEGREE CF CONSERVATISM OF THE DECAY HEAT A?SUMPTIONS IN 10 CFR 50 APPENDIX K (ECCS EVALUATION MODELS).
14
15 P90ceAM OFFILE_CCtNENTS 09 POTEN*iAL UTILIZATION 02 VALUE OF RESEARCH RESULTS IN THE REGULATORY PROCESS DIts:
9 JATE 151212:
3/14/77 RES P70 GRAM ELEMENT: FUEL BEHAVIOR PIl TITLE: HIGH TEMPERATURE OXIDATION OF ZIRCALOY FUEL CLADDING IN STEAM
$PONSCPING OCFICE(S):
RES RRE: 1-3 ZIRCALOY CLADDING RfSEARCH PROJECT MGR:
M.
L. PICKLESIMER
?E$_CQ55ENT}: THE REPORTED RESULTS IMPROVE OUR UNDERSTANLANG OF THE 3EHAVIOR OF ZIRCALOY FUEL CLADDING IN AN E N V I R 0 t.M E N T REPRESENTED BY A LOSS OF COCL 4HT ACCIDENT (LOCA).
THrY INDICATE THAT THERE WOULD BE SIGNIFICANTLY LESS DEPTH OF EM3RITTLEMENT IN THE FUEL CLADDING WALL, CALCULATED FOR ANY POSTULATED LOCA AND MORE WALL MATERIAL WILL BE LEFT WHICH IS CAPABLE OF SUSTAINING LOADS LATER IN THE SECUENCE OF SUCH AN ACCIDENT. THIS INFORMATIJN TOGETHER WITH DATA CN THE RATE CF GRCUTH OF OXIDE AND OXYGEN - STABILIZED LAYERS IN CLADDING. PROVIDES A MORE SCIENTIFIC BASE PCR ESTABLISHING FUEL CLAD EMBRITTLEMENT CRITERIA FOR EMIRGENCY CORE COOLING SYSTEM ACCEPTANCE.
THESE RESULTS -
CCNFIRM THAT THERE IS A DEGREE OF CONSERVATISM IN THE EVALUATIUt! MODEL BEING USED BY THE REGULATORY STAFF FOR CALCULATING THE OXIDATION OF ZIRCALOY DURING A POSTULATED LOCA.
THIS INFORMATION IS BEING CONSIDERED AS A PARTIAL BASIS FCR MODIFICtTION OF THE PRESEMI ECCS RUL E (10CFP $0. APPENDIX K).
RIt'S 8 1 9 ARE BOTH UNDER CONSIDERATICN BY NRR FOR POSSIBLE INCLUSIGN IN A MJDIFICATION T9 THE EMERGENCY CORE COOLING SYSTEMS (ECCS)
RULE FROVIDED IN APPENDIX K OF 10 CFR 50.
THESE "It'S REPORTED ON COMPLETED RESEARCH PROJCCTS IN FISSION FR00UCT DECAY HEAT AND ZIRCALOY OXIDATICM WHICH RESULTED IN CATA BASES AND CORRELATIONS WHICH INDICATE THAT THOSE IN CURRENT USE IN THE ECCS RULE ARC HIGHLY CONSERVATIVE. A COMMISSION PAPER WAS PREPARED (SECY 7/-368)
ON JULY 1.
1977. PRESENT STAFF PROGRESS ON A PROPOSED ACTION PLAN REGARDING POSSIBLE MODIFICATION TO THE ECCS RULE. AND THE CCMMISSICN PAPER (SECY 73-26) PRFSENTING TUE PROPOSED ACTION PL AN WAS PREPARED ON JANUARY 12. 1978.
R11 39 HAS BEEN REVIEWE7 BY NRR. NPSS. IE. AND SD.
THIS MATERIAL WAS INCLUDED IN THE 3RIEFING OF THE ACRS FUlt COMMI!TEr. BY NRR IM SEPTEMBER, 1977, CONCERNING A POSSIBLE REVISION OF APPENDIX K 10 CFR 50.
THE ACRS DISCOURAGEb A kEVISION OF THE ECCS RULE AT THIS TIME.
USER DISCUSSIOP POSITION COMMISSION ACRS PRESS OFFICE MEETING
? APER BRIEFING BRIEFING RELEASE RESULTG E 0 tJ _ FI L 41 T F T.Tl f i ELVEM HELD COMPLETED HELD HELD ISSUED JMPLEMENTED C ICE RES.Ct4SIELE......... 14RR/SD NRR NRR SCHEDJLED COMFLETION DATE..
UNSCHED DEFERRED 9/0/77 UNSCHED UNSCHED 1978 ACTUAL CCMfLETION DA E..
.. 9/23/77 9/10/77 1973 N
99/2.'"l5 d 3/1/?O D. POSS:
JP_C C"* ENILO N QLiCEIS1_AFPLICATipN IQ FEQQLA10PJ PR_Q(ES1*
1 DEW DATA MAY BE CONSIDERED AS PARTIAL BASIS FOR MJDIFICATICNS OF PRESENI ECCS RUL E ( 19 CFR 50. A?PENDIX K).
2.
NEW DATA MAY BE USEL IN "BEST ESTIMtTF" CODES.
THESE CODES ARE INTENDED TO BE USED IN PROBAEILISTIC ASSiSSMENTS OF SAFETY MARCINS.
PE1CEIRE_J5EJCT OF 3ESULTS:
1 NEW DATA CDFFIRMS MARGIN ALLOTTED IN PRESENT ECCS RULE IS C" SERVAIIVE.
2.
IF ACCEPTED FOR USE IN LCCA LICENSItiG CALCULATIONS. VENDORS COULD USE ADDITIONAL MARGIN IN CESIGN (I.E.,
INCREASE PEAK KW/FT).
l CCP91NTS/FigASy3: THE COMMISSION AFPROVED THE PROPOSED ACTION PLAN TO MODIFY tPPENDIX K (SECY 78-26).
tWR AND RES ARE PREPARING A REQUEST TO SD TO INITTATE RULEMAKING TO MODIFY APPENDIX K.
SD_fC5"_E515 p 09/1L/Z5. V.
PANCn %1 IHIS FROJECI PROVIDE 5 DATA CN IHE AMUUN1 OF METAL-WATER REACi!ON AND HYLA0 GEN GAS GENERATION FOLLOWING A LOCA AND AIDS IN THE DEVELOFMENT OF REVISICNS TO REGUIATORY GUIDE 1.7 AND IN ASSESSING THE CONSERVATISM 0F ASSUMPTIONS IN 13 CFR 50 APPENDIX K.
15
16 PGOSDAP C F F IC E CO*"EN T S ON POTENTIAL UIILIZATION OR VALUE_pF PESEARCH RESUt ts IN THE REGULATORY PROCESS PIL s:
1C DATE ISSUED:
2/25/77 RFS PROCPAM ELEMENT: RISK ASSESSMENT / PRIMARY SYSTEMS INTEGRITY DIt TITLE: PRESSURE VESSEL FAILURE PROBABILITY PREDICTION (OCTAVIA CODE)
SPnNSODING OFFICE (S): RES EPG:
1-20 VESSEL IHfEGRITY RESEARCH PROJECT MGR:
W. VESELY R11_COE31NTS: OCIAVIA IS A COMPUTER CODE FUR PREDICTING FAILURE FROBABILITIES IN REACTOR PRESSURE VESSELS AS A FUNCTICN OF TEMPERATURE 5 AND PRESSURES THAT MIGHT OCCUR DURING STARTUP AND SHUTDOWN OPERATIONS.
EFFECTS OF MATERIAL PEOPERTIES AND CPERATING ACE WERE ALSO INCLUDED. THE RESULTS INDICATED THAT EXISTING SAFETY MARGINS COULD BE SIGNIFICANTLY RE00CED WITH CCNTINUED AGING (RESULTING IN RADIATION EMBRITTLEMENT) 0F THE REACTOR VESSEL.
IF THE RATE OF OCCURRENCE OF OVERPRESSURE EVENTS CONTIhUES TO BE SIMILAR TO THAT PREVIGGSLY OBSERVED. FURTHER IMPEDVEMENTS IN THE CODE ARE REPORTED ON IN RIL 12.
THESE RESULTS WERE USED BY NRR DURING THIS PAST YEAR IN REVIEWING THE PRCEABILITY OF FAILURE OF REACTUR PRESSURE VESSELS DUE TO SUCH EVENTS AND TO GIVE GUIDANCE ON PLANT IMFROVEMENTS TMAT MAY BE NEEDED.
THEY MAY ALSO BECCME THE BASIS FOR REVISING REGULATORY GUIDES OR STANDARDS.
USER DISCUSSION POSITION CCMMISSION ACRS PRESS OFFICE MEETING PAPER 3RIEFING BRIEFING RELEASE RESULTS EM T_ PILA C TIV LT I E1 REVIEW HELD
[T 1FTED HELD HELD ISSUED IMPLEMENTED m
CFFICE EESPONSIBLE......... NRR/SD NRR SCHECULED CCMPLETION DATE.. --
UNSCHED UNSCHED UNSCHED UNSCHED UNSCPED 1977 ACTUAL CONPLETION DATE.....
9/9/77 1977 N?R C# ~ENTS_CM_09/09/77, B.
GHIPES:
Ci tk? I E h_![P (((3]J pN TO WEQ21ATORY PR0_[E13: THE OCTAVIA COMPUTER CODE HAS BEEN USED TO EVALUATE THE PROBABILITY OF REACICR VESSEL FAILURE ikCM OVERPRESSURE TRANSIEN;S WHICH CAN OCCUR DURING PWR OPERATION.
THE RESULTS OF THE ANALYSES INCICATED THAT EXISTING SAFETY MARGINS COULD EE SIGNIFICANTLY REDUCEL WITH CONTINUED NEUTRON IRRADIATION OF THE REACTCR VESSEL IF THE HISTORICAL FREQUENC( OF OVERFRESSURE EVENTS CONTINUED.
LESCEITE_lEfALI_QF 'ESULIS:
THE ANALYSES ENAEttD NRR TO CONFIRfl. IN A MORE RIGOROUS. QUANTITATIVE MANHER, INITIAL LICENSING DECISICNS TO REDUCE THE FREQL'ENCY AND MAXIMUM PRESSURE OF THE TRANSIENTS. THESE DECISIONS RESULTED IN MODIFICATIONS TO OPERATING PROCEDURES FOR RECUCING lHE FREQUENCY OF TRANSIENTS AND THE INSTALLATION JF PHYSICAL CEVICES TO LIMIT PRESSURES IN OPERATING PLANTS TO THOSE SPECIFIED BY THE PRESSURE-TEMPERATURE LIMITATIONS IN THE TECHNICAL SFECIFICATIONS.
g rmE N T S / P E'" A r(1: NCNE 1]LC 7"E N TMy 0 9 /13 / 7 h P. m ga((1 IHIS FFCGRAM HAS GENERAIED SUBSIANTIAL DATA USED TN PREDICTING IRRADIATION EMBRITTLEMENT AND MARGINS TO FAI;URE OF REALTOR FRESSURE VESSELS WHEN FLAWS ARE PRESENT, CONSIDERING MATERIAL PROPERTIES AND LOADINGS.
THIS PROCRAM HAS PROVIDED INPdi TO NRC REQUIREMENTS FOR FRACTURE TOUGHNESS OF PRESSURE VESSEL MATERIALS DESCRIBED IN APPENDIX G TO 10 CFR S0 AND CONTRIBUTED DATA USED IN THE ASME CODE RHICH WAS INCORPORATED INTO APPENDIX G.
IT HAS ALSO PROVIDED P RT OF THE DATA BASE USED IN REGULATORY GUIDE 1.99 CONCERNING THE EFFECT OF COPPER IMPURITIES ON SENSITIVITY
~~ OF STEEL TO IRRADI ATICN AND IS EXPECTED TO PRO'eICE A SUBSTAN!I AL INPUT FOR FUTURE REVISIONS TO REGULATCRY GUIDE 1.99.
l 16
17 PP0Gaa9 0F F ICE COMMENT S ON POTENilAL UTitl2ATION OR VALUE OF RESEAPCH RESULTS IN THE REGULATORY PROCESS SIL 9:
11 DATE IS$HQ:
9/15/77 RES PROGRAM ELEMENT: RISK ASSESSMENT Elt. TITLE: ICEE NUCLEAR RELIABILITY DATA MANUAL SPONSgING_QFFICE(S): RES 8_P_Q : NONE RESEAPCH PP0_*ECT f43:
J.
JOHNSON E E5_(CE E'4 T_$ ' A FAILURE RATE DATA MANUAL WAS DEVELOPED WHICH CAN BE USED IN RISK AND RELIABILITY ANALYSIS OF REACICP. SYSTEMS.
THE MANUAL CONTAINS FAILURE RATES AND FAILURE MODE INFORMATION FOR OVER 1.000 ELECTRICAL.
ELECTRCNIC U4D SENSING COMPONENTS UJED I'4 NUCLEAR PCUER PLANTS.
A METHOD IS CIVEN FOR COLLECTING AND PRESENTING RELIABILITY DATA FOR QUANTIT ATIVE RELI ABILITY A'iD AVAIL ABILITY EVALUATIONS OF S AFETY-REL ATED NUCLEAR PL ANT SYSTEMS.
UNCERTAINTY BCUNDS ARE ALSO GIVEN FOR EACH ESTIMATE OF A COMPONENT FAILURE RATE.
THIS WORK IS PART OF A CCNTINUING EFFCRT TO ESTABLISH AN IN1ERIM DATA BASE FOR USE IN MEETING NRC NEEDS IN THE ELECTRICAL AND ELECTRONIC AREA UNTIL SIGNIFICANT CPERATING DATA 0'4 COMPCNCNTS USED IN THE NUCLEAR INDUSTRY BECOME AVAILABLE USER DISCUSSION POSITION COMMISSION ACRS PRESS OFFICF MEETING PAPER BRIEFING BRIEFING RELEASE RESulTS
- 0 S T_9_IL_A C Tiv_I Tlfi EEVIE4 HEt 3 COMPLET Q HELD HELD ISSUED IMPLEMENTED
_OFFICE RESPONSIBLE......... hER NRR SCHEDULED CCMPLETION DATE.. --
UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED 4/30/78 ACTUAL CCMPLETION DATE.....
10/25/77
- iDe CO N NTS3 lN 1?/ZS/77, I.
TERE $G :
CE5G211E SPPLI(aliqN 10 PECd!LAIC f PRQCfSF TiiE SUP. JECT RIL ANNQUNCED THE AVAILABILITY OF A FAILURE RATE DATA MANUAL.
THIS DAIA SUFFLEMESIS OTHER SOURCES OF RELIABILITY DATA SUCH AS THE REACTOR SAFE *iY STUDY.
SUCH DATA ARE BEING USED IN RELIABILITY STUDIES THAT SUPPORT OR PROVIDE THE EASES FOR LICENSING REQUIREMENTS.
EE3M llL IMU Cl_QF R [gtQ: THE FIRST STUDIES USING THIS DATA HAVE NOT YET BEE 4 COMFLETED AND THEREFORE THE IMPACT C AM40 3 YEI EE DEIERMINED.
CaZ ENTS/DEM3D53: THIS DAT A MANUAL."RO'! ICES THE STRUCTURE FOR INCORPORATING :<EW OR REVISED DAT A AS IT BEr0MES AVAILABLE.
THE MANUAL NOW CONTAINS UND!FFERENTIATED HARD AND SOFT DATA WH RH IS A SERICUS IMPEDIMEi4T TG (HE APPLICATION OF THIS DATA.
ThEREFORE CodTINUING WORK IS RE'JUIAED TO IMCREASE THE CONTENT OF HARD DATA BY INCORPCRATING THE DATA DEVELOPED 1HROUGH SUCH PROGRAMS AS NPRDS.
l l
l 17
18
~
FRosn N OFFICE C0 m ENTS ON P O T E ** T I 2 L ul i t j 4AJ1Q2LEP VALUE OF RESE*RCH RESULTS IN THE REGULATORY PROCESS P,lL_s :
12 DATE ISSUED:
6/16/77 RES PROGRAM ELEMENJ: RISK ASSESSMENT / PRIMARY SYSTEMS INTEGRITY PIL TITLE: MODIFICATICNS TO PRES $URE VESSEL FAILURE PROBABILITY PREDICTION (OCTAVIA CODE)
$PONSOPING CFFICE(S): RES M9: NONE RESEARCH PROJEtT MGR:
W. VESELY
@ E 5__C G"'_*LN LS : MODIFICATIONS IN THE OCTAVIA COMPUTER CODE REPORTED IN RIL 810 WERE MADE.
THESE MODIFICATIONS ISCLUDE A CAPABILITY TO HANDLE RESIDUAL STRESS IN A REACTOR PRESSURE VESSEL WHICH CAN EITHER BE CO:4STANT, OR VARY WITH FLAW SIZE; THE CCDE USER CAN IMPOSE AN UPPER BOUND ON THE VESSEL TOUGHNESS AND THE CODE HAS THE CAPABILITY TO HANOLE UNCERTAINTIES IN THE TOUGHNESS. USING THE MODIFIED OCTAVIA CODE. THE MEDIAN FAILURE PROBABILITY FOR THE SURRY REACTOR PRESSURE VESSEL MAS CALCULATED TO BE S X 10-7 PER VESSEL YEAR FOR AN CPERATING TEMPERATUPE OF 110 DEGREES C AND THE CURRENT AGE OF APPROXIMATELY 2.5 YEARS.
THE FAILURE PROBABILITY INCREASE % TO 3 X 10-5 PER VESSEL YEAR AFTER 40 YEARS.
USER DISCUSSION POSITION COMMISSION ACRS PRF.S$
l OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS
(
E_Q$T_11(J C M ILIE}
PEV_lEW F E L D __ _
LQMPLETED HELD HELD ISSUED P1PLEMENTED OF f ICE RESPC:4SIBLL......... hRRrSD NRR SCHEDULED CCMFLETION DATE.. 3/16/77 UN*CHED UNSCHED UNSCHED UNSCHED UNSCHED 19?/
ACTUAL CCMPLETION DATE.....
9/23/77 1977 N'?_COE5N13RMU /_11duEll.1N "ll:
i RESie I M E U F(IC1.f lf_N T O ? F GU! A T f Q.f RQ.(ESS :
(SEE RIL clo)
U W _1? L I N A.CI 0F RESULTS: (SEE RIL 410)
C 7 "LNTS/e'r utS:
IHIS IS A MODIFICATIGN OF RESULTS TRANSFERRED Bi RIL 810, 02-25-77.
5.D_C CO 5 NELON _N/ 21/ 7 3, P.
R AMR( - SEE CO:*.MENTS FOR RIL 810.R RIL 810.
THIS PRC^rR Af! H AS GtretRAltD SUSSI ANTI AL DATA USED IN PREDICTING IRRADTATION Ef'BRITTLEMENT AND MARGINS TO FAILURE OF RE ACTOR PRESSURE VESSELS IJ;;EN FL AWS ARE PRESE!!T. CONSIDERING MATERIAL PROPERTIES AND LOADINGS.
THIS PRCGPCM HAS PROVIDED INPUI TO NRC REQUIREMENTS FOR FRACTURE TOUGHNESS OF FRESSURE VESSEL MATERIALS DESCRISED IN APPENDIY G TO 10 CFR SO AND CONTRIBUTED DATA USED IN THE ASME COCE UHICH WAS INCORPORATED INTO APPcNDIX G.
IT HAS ALSO PROVIDED PART OF THE DATA BASE USED IN REGULATORY GUIDE 1.99 CONCERMING THE EFFECT OF COPPER IMPURITIES ON SENSITIVITY OF STEEL TO IRRADIATICM AND IS EXPECTED TO Pa0 VIDE A SUBSTANTIAL INPUT FOR FUTURE REVISIONS TO RECULATORY GUIDE 1.97.
18
19 P(Q;# AM CFFICE CD-~ENTS ON P0YEMTIAL UTILI7AMO N OP VALUE OF RESEARCH RESULTS IN THE REGULATORY PROCESS PJL 8:
13 DATE ISSUED:
11/?t/77 RES PRCG'AM ELEMENT: PRIMARY SYSTEMS INTEGRITY FIL T I T L F. : RESICUAL STRESSES IN WELDS MN30t:IE CFFICE(5): RES P RJ :
?-20 VESSEL INTEGRITY RESEARCH PROJECT MGR:
C. SERPA.4 SE)_( C ENTS A VERIFIED MODEL IS PRESENTED FCR PREprCTING RESIDUAL STRESSES RESULTING FRCM THE WELDING OF FIFES, AND lHE ESTIMATION OF RESIDUAL STRESSES RESULTING FRCM WELD REPAIRS OF REACTOR PRESSURE VESSELS.
THE MCDEL CAN BE USED IN THE LICENSI*:G PROCESS TO AID IH THE EVALUATION OF CRACKING THAT HAS CCCURRED IN GIRTH-BUTT WEL OS IN PIPING.
IT SHOULD ALSO PROVE TO Bt USFFOL IN ANY SAFETY EVALUATION OF PROPOSED REPAIRS BY WELD BUILDUP IN THE COFNER REGIONS OF PRESSURE VESSEt N0ZZiES AFTER CRACKS HAVE BEEN REr:0VED, AND IN VESSEL WELD REPAIRS.
USER DISCUSSION
- 'OSITION CC"MISSION ACES PRESS CFIICE MEETING PAPER ERIEFiNG BRIEFING RELEASE RESULTS PO S TjJ.t XTJV T U FJ P.EV E ED COMPLETED HELD HELD ISSUED IMPLEMENTED GFflCE RES10NSIBLE......... N R ?> S D SCHE 00i23 CCMPLETION DATE.. 3/31/73 UNSHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL CC"PLETICN DATE.....
08/14/73 NPD C0 "ENT3_CN__p?/14/75 d _fSJ M T:
EMIRryF g rqa r !PN ig_g gy(AJ p y rROCE51.:.
THE AXISOL CODE COULD BE USED AS AF AID IN EVALUATING RESIDUAL SIRLSSES IN FLUED HEAD-PEUCLSS PIFE WtLLS OF CONTAINMENT PENETRATION ASSEMBLIES AND GIRTH BUTT WELDS IN PIPING.
IT SHOUL D AL SO PROVE USEFUL AS AN AID IN DEVLOPING THE NFCESSARY DECISIONAL INFORMATION IN ANY SAFETY EVALUATON CF PRCFCSED WELD REPAIRS.
THE CCMPUTER CODE AVISOL COULD EVENTUALLY BE USED AS A DCSIGN TOOL BY BOTH GOVERNMENT AND ISOUS!Rf, 19 It:FROVE WELDING TECHNIQUES AND PROCEDURES.
THE RESULTS OF THIS PROGRAM SHOULn BE BROUGHT TO THE ATTLhlION OF VARICUS ASME GROUPS ENGAGED IN PREPARING CCDES AND STANDARDS ON WELDED FABRICATION AND INSPECTION PROCECUEES.
THORCUGH DISCUSSION AND EVALU; TION SY SUCh GROUPS AND CCNSIDERABLE TRIAL USE BY INDUSTRY IS NECESSARY PEFbRE F UL L APPLICATICN CF THE CODE IN THE LICENSINu PROCESS WOULD BE APPROPRIATE.
THE INABILITY OF Tite CODE TO TAKE INTO ACCO';NT THE EFFECTS OF PCSI- :FLD HE AT 1RfATMENT, AT THIS TIME. IS A DRAMSACK IN UTILIZING THE CODE IN lHE LICENSINO PRCCESS.
1D _ C"--r N T S_S N ft ? 13 / 7 ?,_junp u IHIS PRCGeAM HAS GENEEATED SUSSTANTIAL DAT7.tJSED IN PREDICTING IRRADIATION EMBRITTLEMENT AND MARGINS TO FAILURE OF REACICR FRESSURE VESSELS WHEN FLAWS ARE PRESENT, CONSIDERIr4G MATFRIAL FRCPERTIES AN" *CADINGS.
THIS PROCRAM HAS FPOVIDED INPUT TO NRC REQUIREMENTS FOR FRACTUTE TOUGHNESS OF rRE55URE 'FSSEL f?ATERIALS DESCRIBED IN APFEMDIX G TO 10 CFR 50 AND CONTRIBUTEJ DATA USED IN THE ASME CCOE IJHICH WAS INC0FFCRATED INTO APPENDIX G.
IT HAS ALSO PROVIDED PART OF THE DATA BASE USED IN REGULATORY GUIDE 1.97 CONCERNING IME Et-F ECT OF C0FPER IMPURITIES ON SENSITIVITY OF STEEL TJ IRRADIATICN AND IS EXPECTED 'O PROVICE A SUBSTANTIAL INPUT FOR FUTURE REJISIONS TO REGULATORY GUIDE 1.99.
I 19 t
i
20 PecG=19 cFFICE CC"9ENTS ON FOTENTIAt UTILIZATION 07 vatVE OF RESEARCH R ESL TS IN THF REGULATORY PROCESS PIL 5:
14 DATE ISSUE 9:
11/9/77 RES PEOGDAM ELEMENT: SYSTEM ENGINEERING DIL TITL(: PHYSICAL SEPARATIC.! CRITERIA FCR ELECTRICAL CABLE TRAYS (HCRIZONTAL OPEN SPACE CONFIGURATION)
SPONSODING CFFICE(5): RES P P,3 : 1-23 ELECTRICAL STDS A PESEARCH PROJECT MOR:
R. FEIT FIRE PROTECTICN fi$_Ctr?J N T3 : THE ADECUACY CF THE REQUIRED SPACING OF ELECTRICAL CABLE TRAYS AT NUCLEAR POWER PLAH!S WAS EXAMINED 10 PREVENT THE SPREAD OF CA3LE FIRES.
RESULTS INDICATE fHAT CURRENTLY USED CRITERIA FCR CA"LE TRAY SEPARATION APPEAR TO BE ADEQUATE FOR ELECTRICALLY-INITIATED FIRES. BUT THAT CHAFGES MAY BE REQUIRED SOR FIRES DUE TO EXTERNAL IGNITICH SCUECES.
THIS WORK IS APPLICABLE TO A VERIFICATION OF REGULATCRY GUIDE 1.75, "PHYSICAL INDEPENDENCE OF ELECTRI. SYSTEMS".
EXPOSt'RE Flk TESTING EMPLOYING EXTERNAL FUEL SOURCES WAS CONDUCTED TO PROVIDE DATA FCR THE DEVELOPMENT OF CURPENT NRC STAFF POSIrio; AS DOCUMENTED IN THE APPENDIX A TO THE BRANCH TECHNICAL POSITION APCSB 9.5-1 "GUIDELINES TDR FIRE PROTECTIGa FOR NUCLEAR POWER PLANTS" AND IN THE CRAFT REGULATORY GUIDE 1.120. "FIRE PRDTECTICN GUIDELINES FOR NUCLEAR POWER PLANTS."
USER DISCUSSION POSITION COMMISSION ACRS PRESS OFFICE MEETING PAPER BRIEFING BPIEFING RELEASE RESULTS P MT__PJ LAC 11VITIE3 52VJiy HFLD COMPLETED HELD HELD ISEUED IMPLEMENTED 3F+ ICE kESecaSIBLE........
NTR.so SCHEDULED CCMPLETION DATE.
1/9/73 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL CCMPLETION DATE.....
04/26/73 S q'""E N TS_ p N 0 4/M/7FJ3/01/ 73, R. TEDESCO:
plicl151 AffG M N_TQlt191 ATOPY F M ESS: THE RIL PROVIDES RESULTS OF A COMPLETED PORTION OF THE NRC RIFE PRCTECTION RESEAPCH FRCGRAT1 CONDUCIED AT THE SANDIA LABORATORIES REGARDING THE EFFECTS OF CABLE TRAY SEPARATION CN THE PEOP GATICM OF ELECTRICALLY INITIATED AND EXPOSURE FIRES.
OESCRISE_1EEACT OF D[3tJ[T3: THE INTRODUCTORY PARAGRAPH OF RIL 314 STATES THAT THE RESULTS OF THE SANDIA tkOCRAM ItaDICA!E THAI "CURRENTLY USED CRITERIA FOR CABLE TRAY SEPARATION APPEAR TO BE ADEQUATE FOR ELECTRICALLY INITIATED FIRES BUT THAT CHANGES MAY BE REQUIRED FCR FIRES DUE TO EXTERNAL IGNITION SOURCES."
RES NOTED IN A CCNVERSATION ON NOVEMBER 11 1977 THAT THE SPECIFIC POINT RAISED IN THAT PARAGRAPH IS DIRECTED TO THE ADECUACY OF SOLE RELIANCE ON THE SEPARATION CRITERIA OT REGULATORY GUIDE 1.75 FOR PROTECTION AGAINST EXPCSURE FIRES.
THE FIRE PROTECTION CRITERIA DEVELOPED BY THE STAFF SINCE THE BROUNS FERRY FIRE HAVE RcCCONIZED THAT RELIANCE SHOULD NOT BE PLACED SOLEL7 01 THE SEPARATION CRITERIA 0F REGULATORY GUIDE 1.75.
OUR STAFF REPORT.
DATED N3VEMBER 9.
1977 CN "THE CUESTION OF WHETHER THE PETITION OF THE UNION OF CONCERNED SCIENTAS!G RAISES MATTERS THAT REQUIRE IMMEDIATE CCMMISSION ACTION." INDICATES THE STAFF POSITION THAT THE IEEE-336 AND THE REGULATCRY GUIDE t.75 SEPARATION GUIDELINt$. AND THE IEEE-333 FIRE RETARDANCY STANDARDS FOR SAFETY CABLES. BY THEMSELVES ARE NOT SUFFICIENT TO PROTECT AGAINST EXPOSURE FIRES.
CCNSEQUENTLY WE REQUIRE LDDITIONAL TIEASURES FOR FIRE PROTECTION SUCM AS: FIRE 3ARRIERS BETWEEN REDUNDANT DIVISION CABLE TDAYS; FTRE RETARDANT COATINGS ON CABLING; AUTCMATIC FIRE DETECTION SYSTEr15; AUTOMATIC FIRE EXTINGUISHING l
SYSTENS: ADMIFISTRATIVE PROCEDURES: AND TRAINING PROGRtMS.
THIS POSITION HAS BEEN HELD BY THE STAFF SINCE l
THE BRC2NS FERRY FIRE AND IS REFLECTED IN CUR STANDARD REVIEW PLAN SECTICN 9.5.1 (BTP 9.5-1). REVISION.
REG. GUIDE 1.120 HAS BEEN ISSUED FCR COMNENT.
THUS. EXPOSURE FIRES ARE RECUIRED TO BE CONSIDERED IN THE FIRE PROTECTION l
FROGRAMS FOR BOTH CPERATING PLANTS AND PLANTS IN THE LICENSING PROCESS.
IT SHOULD BE NOTED THAT THE RIL ACK!;CULEDGES THAT FURTHER TESTING WITH ELECTRICALLY INITIATED CABLE TRAY FIRES UNDER DIFFERENT CGNDITIONS MAY RESULT IN FULLY DEVELOPED FIRES.
WE CONCOCE. AS DOES RIL 314. T f" A T THESE RESEARCH RESULTS CONFIRM THE NEFD FOR PROTECTION MEASURES IN A D DI T Id'? TO THE SEPARATION CRITERIA.
SINCE SUCH MEASURES ARE INCLUDED IN OUR PRESENT CRITERIA UE CCNCLUDE THAT.r.i INFORMATION IN RIL 384 DOES NOT INDICATE THE NECD FOR CHANGES IN OUR FIRE PROTECTION GUIDELINES.
BUT THAT IT CCNFiRMS THE NEED FPR CUR PLANS TO UPDATE REGULATORY GUIDE 1.75.
C C M* E N T S / R EM A C_K S : MCNE 20
SD CCTI4_IS CM 0 ? /13'Eu JIVEC A 8 5 21 G
IHE IESIS HAVE CCNFIR.NED THE VALIDITY OF GUIDELINES IN REGULATCRY GUIDE 1.120 MHICH CALL F02 SEPA24TIING RECUNCANT SAFETY SYSTEM CADLING BY RATED FIRE BARRIERS. THE TESTS HAVE CCNFIRMED THE VALIDITY OF SEPARATICN CRITERIA SPECIFIED IN REGULATCRY GUIDE 1.75 ONLY WITH RESPECT TO FIRES RESULTING FRCM ELECTRICa*. FAILURE WITHIN A CABLE TRAY EUNCIE.
HOMEVER. THEY SHOW THE BASIC DEFICIENCIES OF THE
!EFARATICN REQUIREMENTS WITH RESPECT TO EXPOSURE FIRES CCMMON TO MORE THAN ONE REDUNDANT SYSTEM CAELE RUM.
21
23 P G CGosM CF F IC E C0rrEN TS ON P0fENTI2L UTILIZATION OR VALUE OF RESEARCH RESULTS IN THE REGULATCRY /ROCESS 1
- It 3:
15 D ATE ISSt'ED:
12/t/77 RES PP000AM ELEMENT: PRIMARY SYSTEMS INTEGRITY l
RIL TITLE: CHARACTEPIZATIOM OF BWR FEEDWATER N3ZZLE CORNER CRACKS SPONSORINC JFFICEFS): RES 999: 1-20 VESSEL INTEGRITY RESEARCH PROJECT BGR: C. SERPAN PE5_CCE*ENTS: PRESSURE LO Ai)ING OF CRACKS IN THE INSIDE CORNER OF FEECWATER INTAKE N0ZZLES FOR BOILING WAIER ktACICR C E12 ) PRESSURI VESSELS :: AVE BEEN CHARACTERIZED. THE rHARACTERIZATION ESTABLISHED THE RELATICNSHIP BETWEEN STRESS-GENERATED PRESSURE AND MEASURABLE CRACK PARAMETERS, IN ORDER TO DETERMINE THE GRCWTH OF THE CRACK AND ITS CRITICAL S'ZE.
THESE RESULTS CAN BE USED TO CHECK THE CALCULATIONS, BASED ON INTERNAL PRESSURE, FOR THF SAFEi. ANALYSIS OF BWR FEECWATFR N0ZZLE CORNER CRACKS DURING SUBSECUENT COM3fNED COOLING 1ND UNLOADING.
IT HAS BEEN SHOWN THAT UNDER THE MOST SEVERE CONDITIONS, THE CFACK CAN PENETRATE N3 M1RE THAN 1/3 0F THE PRESSURE VESSEL WALL.
THIS MEANS THAT THE VESSEL WILL AtuAYS BE CAPABLE OF RETAINING EMERGENCY COOLING WATER. THUS KEEPING THE CORE COOL AND PROVIDING FOR A SAFE SHUTCOWN.
THUS. VFSSt i FAILURE IS NOT POSSIBLF FOLLOWING WARM PRESTRESSING UNDER CONDITIONS WHERE COLD EMERGENCY CORE CGOLING WATER IS INJECTED INTO THF HOI PRESSURE VESSEL FOLLOWING A LOSS OF COOLANT ACCIDENT.
i LSER DISCUSSION POSITION CC"MISSION ACRS PRESS CFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS E957_RIL_Af71XtTLES E EElfW HELD.
COMPLETED HELD HELD ISSUED IMPLEMENTED OFFICE RESFGNS13LE......... FRR/5D SCHECULED CCMPLETICN DATE.. 3/31/73 UNSCHED UNSCdED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL CCMPLETION DATE....
2/21/73 NDP CC"MENTS cN cC/2t/;3, B.
GRIMES:
P E1E MEJ P PL]X A T IEN_J Q3 EE! Lf1C P Y P RJ GEM e NRR CONCURS THAT THESE DATA CAN BE USED FOR PARTIAL VERIFICATION OF IHE APFRCXIt. AIL t;EIHODS USED BY GE IN ESf! MATING THE STRESS INTENSITY FACTOR $ APPLICABLE TO FEEDWATER AND CFD N0ZZLE CRACK 5 IN BWR REACTOR VESSELS.
THEY CAN ALSO BE USED FOR WERIFICATION OF MORE SOPHISTICATED METFOCS OF EVALUATION (SUCH AS FINITE ELEMENT ANALYSIS) IF AND WHEN SUCH METHODS ARE DEVELOPED.
DESSELEf_lMPA(J_QF_Pf321T5: WE HAVE MADE A COMPARISON BETWEEN THE GE STRESS INTENSITY CURVE (FIG. 3-26 GF NLOL-21433) ICR THE ONE CASE WHERE A DIR2CT COMPARISON CAN BE MADE -- NAMELY, AT AN A/T RATIO SLIGHTLY GREATER THAN 3.53, AS PROVIDED BY FIG. 7 0F THE PRCGRESS REPORT.
FOR THIS ONE CASE. THERE I5 ALMOST EXACT ACREEMENT BETWEEN THE GE CURVE AND THE VPI TEST RESULT).
THE GE CURVE, WNEN CONVERTED TO NORMALIZED STRESS INTENSITY FACTCRS. WILL ALSO PROCUCE A CURVE (AS A FUNCTION OF A/T RATIO) WHICH IS QUALITATIVELY SIMILAR TO THAT OF FIG. 7 0F VIP REPORT VIP-E-76-25: IN THIS CASE. EXACT CORRESPONDENCE IS NOT TO BE EXPECTED BECAUSE OF THE MATERIAL DIFFERENCE IN THE DIAMETER-TO-THICKNESS RATIOS OF VESSELS INVOLVED. THE CLOSE AGREEMENT SETWEEN THE GE CdRVE AND THE TEST RESULT FOR THE ONE CASE UHERE A VAIID COMPARISON CAN BE MADE FROVID25 ASSURANCE THAT THE STRESS INTENSITY FACTORS USED BY GE IN THEIR EVALU. TION FRE REASONABLE APPROXIMATIONS.
[C5EENL$iPLMEPKS:
-JE ENCOURAGE THE COMPLETION OF THIS WORK add PARTICULARLY THE DEWELOPMENT OF VERIFIED ANALYIICAL METHODS WHICH WILL PROVIDE AN ASSURED MEANS FOR FUTURE CALCULATION OF SIF'S FOR CRACKS IN COMPLEX GEOMETRIES (SUCH AS THROUGH THE USE OF FINITE ELEMENT ANALYSIS).
%D_CGENDJN 09/15/7 k G..RIVENEA'K:
THIS F RCGR AM N AS GENERAT ED SUBS! ANTI AL DAT A USED IN PREDICTING IRRADI ATION EMBRITTLEMENT AND MARGINS TO FAILURE OF REACTOR PRESSURE VESSELS WHEN FLAWS ARE PRESENT, CONSIDERING MATERIAL PROPFRTIES AMD LOADINCS.
THIS PROGRAM HAS PROVIDED INPUT TO hRC REQUIREMENTS FOR FRACTURE TOUGHNESS OF PRESSURE VESSEL MATERIALS DESCRIBED IN APFENDIX G TO to CFR 50 AND CONTRIBUTED DATA USED IN THE ASME CDCE WHICH WAS INCORPORATED INTG APPENDIX G.
IT HAS ALSO PROVICED PART OF THE DATA BASE USED IN REGULATORY GUIDE 1.91 CONCERNING THE EFFECT OF COPPER IMPURITIES ON SENSITIVITY OF STEEL TO IRRADIATION AND IS EXPECTED TO PROVIDE A SUBSTANTIt'. INPUT FOR FUTURE REVISIONS TO REGULATCRY GUIDE 1.99.
22
23 P&COktM OFFICE COM*ENTS CN POTENTIAL UTILIZATION OR VALUE OF PESEARCH RESULTS IN THE REGUL TORY PRdCESS ell _s:
16 DS.TE ISSUED:
t?st/77 RES FROPRAM ELEMENT: PRIMARY SYSTEMS IATEGRC f FIL TITLE WARM PRESTRESSING SPONS0*ING OFFICE (S):
RES REG:
1-20 VESSEL INTEGRITY RESEAPCH PROJECT MGRr C. SERPAN EE5_(D5?ENI): THE EFFECT OF COLD EMERGENCY CORE COOLING WATER ON HOT REACTOR PRESSURE VESSELS WAS CONSIDE;ED. THE RESULTING THERMAL SHOCK COULD. UNDER "WORST CASE" CONDITIONS. LEAD TO THE PREDICTION THAT FLAWS IN THE STEEL FRESSURE bESSEL WOULD EXTEbJ. RESULTS REPORTED HERE PRDVIDE A VERIFICATION OF THE
- WARM PRESTRESSING" EFFECT WHICH CAN PRECLUDE CRACK EXTENSION WHEN IT OTHEFWISE WOULD HAVE BEEN PREDICTED. TO DESCRIBE THIS EFFECT. ONCE A CRACK IS LOADED WHILE THE MATERIAL IS VERY TOUGH. NO RAPID EXiELSICN WILL CCCUR.
USER DISCUSSION POSITION COMMISSION ACRS PRESS OFFICE MEETING PAPER BRIEFING RRIEFING RELEASE RESULTS ECST_EIL_ M 11Y111El RE*21fW HELD
[CMPLETEC
!!f L D MELD ISSUED IMPLEMENTED OFFICE RESPONSIBLE......... NkR'SD SCHECULED COMPLETION DATE.
2/1/75 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL CCMPLETION DATE.,..
2/14/73 tt!R_CCEENTS 10ZL1447_L._f f /2' 75.
P.
CR15ES:
PR. @ 3: IF "WARM PRESTRESSING" AS DESCRIBED IN THE RIL IS OPERATIVE ON HIGH;Y M $ CRJ H LAlT LLC A I LCS_12_ EMU L A T O R Y IRRADIATED REACICR 4EsStL SIEELS. IHIS t1ECHANISM C03tD PROVIDE ADDITIONAL MARGIN IN THE RPV TO ACCOMMODATE ASSOCIA ED WITh ECCS INJECTION DURING A LARGE LOCA.
THERMAL SHOCK BY LIMITING CONCERNS REGARDING THEPMAL SHCCK TO REACTOR VESSELS TO THOSE TRANSIENTS THAT PEICPlF1_JMP4CT C E_Ei39LIS :
INVOLVE REPRESSURIZATION OF THE VESSEL. VENDOR ANALYSES AND NRC EVALUATIONS WLULD dE SIMPLIFIED.
IT WOULD ALSO PK0 VIDE AT LEAST A PARTIAL ANSWER TO THE CUESTIONS POSED IN REG. GUIDE 1.2. "THERMAL SHOCK TO REACTOR VESSEL."
CC"ri?I3dEEEAPES: NRn HAS DISCUSSED THE TECHNICAL ASPECTS COVERED BY THIS RIL WITH RES PERSONNEL. RESEARCH REGARDING WARM PRESTRESSING IS STILL UNDERWAY. ESPECIALLY ITS RELEVANCE TO CYLINDR' CAL VESSEL UALLS. WHILE IT A TO BE A PRCMISING PHENOMENON FOR LIMITING CRACK EXTENSION DURING A THERMAL SHOCK. THE DATA ARE STILL INSUFFICIENT TO SE USED AS A 5 ASIS FOR LICENSING DECISIONS. A DETAILED TECHNICAL EVALUATION OF THE RESEARCH DESCRIBED IN THE RIL AND THE NRR ASSESSMENT OF ITS RANGE OF APPLICABILITY WILL BE COMPLE!ED FOLLOWING RECEIPT OF MORE SUBSTANTIAL DATA.
1D_ R I"iE*jl3_CN O9/'3/7 h _f,_fIYf y ai p th15 FROGRAM HAS CEhtRAIED SUSSIANTIAL DATA USED IN PREDICTING IRRADIATION EMBRITTLEMENT AND MARGINS TO FAILURE OF REACTCR PRESSURE VESSELS WHEN FLAWS ARE PRESENT. CONSIDERING MATERIAL PROPERTIES AND LOADINGS.
TMIS PROGRAM HAS PROVIDED INPdT TO MRC REQUIREMENTS FOR FRACTURE TOUGHNESS OF PRESSURE VESSEL MATERIALS DESCRIBED IN APPENDIX G TO 10 CFR 50 AND CONTRIBbfED DATA USED IN THE ASME CCCE WFICH MAS INCORPORATED IN10 APPENDIX G.
AT HAS ALSO PROVIDED PART OF THE DATA 2ASE USED IN REGULATORY GUICE 1.99 CONCERNING YHE EFFECT OF COPPER IMPURITIES ON SENSITIVITY OF STEEL TO IRRiDIA!ICN AND IS EXPECTED TO PRCVIDE A SUBSTANTIAL INPUT FOR FUTURE REVISIONS TO REGULATORY CJTDE 1.99.
1 23
24 Fr0G&tM CfFICE CCr?tNTS Os FOTENTIAL UTIL!Zf. TION OR VAlk1_pF *ESEADCH GESULTS IN THE DEGULATORY FPOCESS PJ(,3:
17 DATE 15$C{C:
$/$/73 RES P90GPAM (LEMENT: FUEL BEHAVICR I
Pil TITLE: PCWER EURST FACILITY (PBF) SINGL E ROD-POWER COOLING MISMA TCH iPCM) TEST RESULTS LPQNSORING OFFICE (S):
RES DRG:
!-10 FBF E/PERIMENTAL PESEARCH PROJECT MGR:
R. VAN HOUTEN PP0 GRAMS ef1_C0 5(?_Y3 :
CC"PLETED RESEARCH IS REPCRTED ON SINGLE FUEL ELEMENTS EXPOSED TO POWER-COOLING MISMATCH (PCM) COND IN THE PUWER BURST FACILITY (PBF).
DEP AR TURE-i R OM-NUCL E ATE-BOILING F ATIOS (DMSR'S)THE RESULTS ARE OFFERED FOR USE IN DETERMI.4ING POSSIBLE C DICXIDE FUEL RODS.
FCR ALL CCSMERCIAL PCWER PEACTORS WHICH USE ZIRCALOY-CIAD URANIUM THE RESEARCH PESUL TS SHCM THAT ZIRCALOY FUEL ROD CL ADDING NORMALLY DOES NOT FAIL EVEN WHEN PROLONGED FIL OCCURS AS A CESULT Of INADEOUATE COOLANT FLOM RATES.
THE CLADDING GENERALLY WILL NOT FAIL UhlESS IT BECOMES SO NEAVILY OXIDIZED THAT IT IS BRITTsE AT ROCM TEMPER'.TURE.
SUCH SEVERE ZIRCALOY OXICATION WOULD REQUIRE HIGHER Cl*LOING TEMPERATURES TFAN ARE CURRENTLY PREDICTED FOR ANY LIGHT WATER REACTCR ACCILENTS WHICH RE3 ULT IN A PCM.
WHETHER RELATED TO A LCSS OF COOLANT FLCW OR TO AN INCREASE IN FUEL ROD POWER.
USER DISCUS $10r POSITION COMMISSION ACRS PRESS OFFICE MLETING PAPER BRIEFING BRIEFING RELEASE RESULTS PCST_DIL 2CTiyITIES EEglfW PEtD OFFICL RE5fCASIBLE..........hER'SD
[EEELETED HELD HELD ISSUED IMPLEMENTED SCHECULED COMPLETICN DATE. 07/05/73 UN5CHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAi COMPLETICN DATE...
.03/22/78
- d L F""M1.1_CNLI M T/ % _D J f5100
__ptE U ?E_P ELLC W E IO S E D IC" P QCf151-VARIOUS FUEL FAILURE MECHANISMS AND THE CONS' QdENCES OF FAILURES ARE EvuuAIED IN IhE SAIEir ANAL
- SIS OF TRANSIENTS AND ACCIDENTS. DEPARTURE FROM HUCLEATE BCILING (LMB) TS ASSUMED TO FF00CCE FUEL RCD FAI1URE AND IS THE FAILURE CRITERION USED FOR MANY LICENSING ANALYSES. PELLET /LLADDING INTERACTION (PCI) CAN ALSO BE A FUEL FAILURE MECHANISM. FBF FROVIDES THE CAPABILITY fur STUDYING FUEL BEHAVIOR AND FAILURE MECHANISMS UNOER TRANSIENT AND ACCIDENT CONDIl0NS.
__rf5fel5E_l"EACT Cf_PEil I): THE DEMONSTRATED ABILITY OF MOST FUEL RODS TO EXPERIENCE CM3 WITHOUT FAILURE SHOWS THA THE CURRLht LNB CRITERION IS CCNSERVATIVE. REQUESTS F02 LESS CONSERVATIVE FAILURE CRITERIA HAVE BEEN MADE BY THE INOUSTRY.
TURBINE T IP WITHOUT BYPASS (TTWOB? AND STEAM LINE BREAK (SLB) ARE NE.R-LIMITING EVENTS IN WHICH DNB IS FREDICTED TO OCCUR MOMENTARILY YET FAILURE BY THIS MECHANISM MAY NOT OCCUR.
DEFINITION OF A LESS CCNSERVATIVE FAILURE CRITERION FOR THESE EVENTS WOULD RELIEVE THESE LIMITING CONDIT0NS. BASED CN THESE PBF RESSLTS. NRR WILL GIVE SERICUS CCNSIDERATION TO THESE VENDOR REQUESTS: HOWEVER. APPROVAL DF RELAXED FAILURE WIi BE CONTINGENT UPON THE EVALUATION OF OIHER NON-CNB FAILURE MECHANISMS.
70CSEN T5f*EU1cIS : THE SINGLE ROD PCN TEST RESULTS SHOW THAT 'HE CURRENS CNB FAILURE CRITERION IS CONSERVATIVE.
THE WICE RAriCE CF CLADDING TEMPERATURES DURING DNB WHEN TEST PARAMETERS ARE NEARLY THE SAME FREVENT A QUANT ASSESSMENT CF THE MARGIN TO FAILURE.
FURTHERMORE. THE PAWEL CLADDING EM2RITTLEMENT CRITERION HOULD NEED ADDITIONAL FEVIEw *EFORE A QUr.ti!ITATIVE MEASURE OF MARGIN COULD BE USED IN LICEESING MATTERS.
THE PCM TEST SERIES uAs DI11GNED PRIMARILY TO STUDY THE EFFECTS OF CNB.
THERFORE. PELLET / CLADDING INTERACTION
'PCI) DATA FRO:1 THESE EXPERIMENTS WZRE PROBABLY CCMPRCMISED BY THE TEST CCNDITONS. FOR EXAMPLE. FUEL EXPOSURE TIME AT POWER, FUEL PRECCNDIsIONING AND CLADDING TERMPERATURE WERE NOT IDEAL FOR PCI STUDIES.
CONOLUSICNS CN THE SUBJECT OF FUEL FaltbRE PROPAGATION CRAWN FROM THE PCM SERIES MAY BE PREMATURE SINCE VENDOR FUEL RCD PRESSURE CRITERIA HavE BEEN CdANGED. NEW EESIGN CRITERIA. RECENTLY APPROVED BY NRC. ALLOW FCR INTERNAL RC3 PES $URE TO EXCEED THE EXTERNAL SYSiEM PRESSURE DURING M9RMAL OPERATION.IN ADDITION. THE FUEL RCD BEHAVICR CF A sir 4GLE RCD IN A COLD SHRCUO IS NOT TYPICAL OF FUEL RODS IN A MULTIPLE ARRAY.
THE FORTHCCMING BUNDLE TESTS IN PEF SHOULD GIVE nCRE INFORMATCN ABOUT FAILURE PROPAGATICN.
SD C0"*ENTS.
G.
PIJENB2D(?
NO RESPONSE RECEIVED.
25 6 0.0 M a t' CSFICE CC'"LNIS CN POIENTIAL UTILIZAT!0N CR VAIUE OF PESEARCH RESUtis IN THE REGULAIORY F90 CESS l
Flk.5 :
13 DtTE USED:
11/9/77 RES PROGDJM EL EMENT: RISK ASSESSMENT
F.
GOLDEERG Pf$_(ONENTS: THE FRANTIC CO?'PUTER CODE IS USED TO CALCULATE THE UNAVAILABILITY OF ANY SYSTEM MODEL.
COMPREHENSIVE StkvElttAhCE TESTING EVALUATIONS F0e A SYSTEM ARE POISIBLE WITH THE INCURPORATION CF TEST DOWNTIMES. TEST INEFFICIENCIES. AND TEST-CAUSED FAILURES IN THE ANALYSIS OF SYSTEr1 MODELS.
THE FRANTIC CODE HAS POTENTIAL SIGNIFICANT APPLICATICN IN EVALUATING TEC.MNICAL SPECIFICATIONS 2N TESTING AND ALLOWED DOWNTIMES FOR REACTOR SAFETY S Y S T ET.S. THE EVALUATICNS CAN BE OF A GENERIC NATURE, OR CAN SE APPLIED TO SPECIFIC PLANT 5YSTEMS IF APPLICABLE DATA ARE AVAILABLE.
USER DISCUSSICN POSITION COM'11SSI ON ACRS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS EOST>l LAtllU UES EEylEW HELD C C**P L E T E D HELD NEtD ISSUED M EMENTED CFFICE EESPG*eSIBLE.........
NCR/SD NRR SCHECULED CC"2LETION DATE.. 1/7/73 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED 2/1/73 ACTUit CCM?tETION DATE.....
12/6/77 1/15/78 M'_CNESTS C'8 ??/JA M _ U l5EN M :
2LSC?IEE APPLICaf1CN TU FEGULATORY EPQCESS: PREVIOUS COM:1ENTS FROM NRR ARE PRESENTLY UNDER REVISION, iD CC" ENTS, G. RIVEN! PO NO RESPONSE RECEIVED 25
i i
26 FTOGE RM OF FICE CC"ENT S ON FOTENilAt UTILIZATION OR vat 0E OF RESEAPCH PESU1.'S IN THE REGULATORY PROCESS _
RIL 8:
19 DATE ISSUED:
t/31/7C Bfi_l'RJSPr M EL EMEN T : RISK ASSESSMENT FIL TITLE: GO METHODOLOGY ASSESSMENT SPC'sSCPIN_G OFFICE (5 ):
RES ER$
LONE RESEAPCH PROJECT MGR:
J. PITTMAN B ELet"E y T3 : GO PROVIDES A METHOD FOR SYSTEM MODELING AND A COMPUTER CODE TO CALCULATE A PREDICTION OF SYSTEM EELIABILIIY.
THE STUDY DEMDNSTRATES THAT THIS METHOD PRCVI"ES EQUIVALENT RESULTS TO THOSE OBTAINED FROM FAULT TREE ANALYSIS. WH1CH WAS USED IN THE REACTOR SAFETY STUDY.
THE MODEL RESEMBLES THE SYSTEM SCHEMATIC OR PIPIhG DIAGRAM WHICH REDUCES THE BURDEN OF MODELING ALL SYSTEM CCMPONENTS. GO HAS A POTENTIAL SIGNIFICANT USE LS A MEANS OF DETERMINItsG SYSTEM RELIABILITY 07 AS A DIVEPSE METHOL, FOR VERIFYING SYSTEM ANALYSIS PERF0EMED USING FAULT TREE CR SIMIL AR MODELING T EC*'NIQUES.
USER DISCUSSION POSITION C0". MISSION ACR$
PRESS OFFICE MEETING PAPER BRIEFING BRIEF*NG RELEASE RESULTS ECST PIL ACIlvlIJ11 PlV1fy HELD
[f**PL ET ED HELD HELD ISSUED IMPLEMENTED OFFICE FESPC?4sIBLE......... F.RR/SD MSS SCHECULED CCMPLETION DATE.. 3/31/75 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL COMPLETION DATE.....
B P PlC"E*411_C *L_0 $ / 21/ 78. D. POSS: C O*: MENT EXPECTED ON 29 DECEMBER, 1918 CCC:E!415 DUE CEC 2 9, 1973.
S U C"f5'S, G.
RIV EN? A cr.:
NO RESP"NSE RECEIVED.
HATTER: NO RESPONSE RECEIVED.
26
27 i
- 30331" CFFICE CC-"t%IS CN PQiENTIAL UTILIZATION 09 vatOE OF PESEARCH RESULTS IN VME PEGULATu(7 PROCESS DIL s: 2P OATE ISSOf0:
1/24/73 PES PPOGDAM ELEMENT: SAFEGUARDS I
RIL TITLE:
A STUDY OF PHYSICAE PROTECTICN EC'JIPMEN T l
l SPCNS??!NS CrrICE(5): IAE EPf:
4-4 SAFEGUARDS EQUIPMENT EVAL.
PESE8eCH PPOJECT MGR:
E. RICHARD PE5_fC 5(NTS: THE PURPOSE OF Th!$ STUDY WAS TO PRO 7IDE INE NRC INSPECTOR. LICENSING REVIEWER AND FIELD EVALUATOR WIIH Stw AND IMPROVED METF0DS FCR EVALUATING PHYSICAL PROTECTION EQUIPMENT TNAT IS IN USE UR PROPOSED FOR USE AT LICENSED NUCLEAR FACILITIES.
THE FIVE MAJOR PRODUCTS OF THIS STUDY ARE:
T.
A CATALOG OF PHYSICAL FECTECTlUN EQUIPMENT.
2.
A GUIOE FOR EVALUATICM OF PHYSICAL PPOTECTION EQUIPMENT.
3.
A E00< CF REFERENCE MATERIALS (RELEVANT TO THE EQUIPMENT CATALOG AND THE EVALUATION GUIDE).
4.
A SET OF GUIrELINES FCR CEVELCPINO A METHODOLOGY TO MEASURE LEVELS OF EFFECTIVENESS FOR A FIXEC-SITE PHYSI (At PRDTECTION SYSTEM.
5.
A SUMNARY REPCRT. INCLUDING RECCMMENDATIONS FCR FURTHER WORK.
ALL OF THE ABOVE PROCUCTS HAVE BEEN DISTRIEUTED TO THE VARICUS NRC REGIONAL DFF7CES AND ARE PRESENTLY BEING USED BY IW PEC' ORS AS BASIC REFERENCE CCCUNENTS FCR EVALUATING PHYSICAL PROTECTION EQUIPMENT INSTALLED AT LICFNSED HUCLEAR FACILITIES.
DATA IRCM ~HFSE DCCUNENTS WERE ALSO USED IN THE DEVELOPMENT OF A NEW NRC RESULATORY GUILE ON INTERIOR INTEUSION DETECTISN ALAEM SfSTEMS SY THE OFFICE OF STANDARDS DEVELOPMENT. OTHER FEDERAL AGENCIES HAVE PEQUESTED IPE RESULTS CF TH 5 STUDY AS A MEANINOFUL COMPENDIUM 35 AVAILABLE PHYSICAL PROTECTION EQUIPMENT AND EVALUATIO4 EQUIPMENT TECHNICUES.
THE RESUL!S CF THIS STUDY WILL BE USED IN PHASE II 0F THIS SAFEGUARDS RESEARCH PROGRAM AS A SASIS FOR EXP ANDING AND IMPROVING THE DAT A AVAILABLE TO NRC STAFF REGAPDING THE CHARACTERISTICS AND EFFECTIVENESS CF CONSINATICNS CF PHYSICAL PRCTECTION EQUIPMENT. AND THEIR ASSOCIATED ACMINISTRATIVE AND OPERATIONAL PROCEDURES.
THE DIVISION GF PCCUMENT CCNTRCL HAS BEEN REQUESTED TO PRINT THESE REPORTS FOR DISTRIBUTION ONLY TO OTHER AGENCIES AND NRC ST AFF.
USER DISCUSSION POSITICM COMNISSICN ACRS PRESS OFFICE MEETING PAPE' ERIEFING BRIEFING RELEASE RESULTS E05I_ Ell _A[TLEITIII EEEIEy HELD TCMPLETED HELD HELD ISSUED IMPLEMENTED CFf1CL #ESFCNSIBLE......... tJR/hMSS/ --
SD'IIE SCHECULED CON *LET!CN DSTE.. 3/31/73 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UMSCHED ACTUAL CCNPLETION DA1E.....
lLE CCM*EMTS. G. Will: k3 RFSPONSE RECEIVED.
ip y FNTS_QN E /_N d b R.
JC g5:
IHIS r s CGR Art CC%CJCitJ SY IFt MITRE CORPORAi1CN RESULTED IN A MULTI-v0LUME REPORT ON PHYSICAL PROTECTION MtFOWAEE INCLUDING DESCRIPTIONS. *ERFGRNANCE CHARACTERISTICS AND MANUFACTURERS SPECIFICATIONS.
THIS WORK HAS M?TERIALLY ASSISTED IN THE PRFPARATION OF SEVERAL TECHNICAL REPORTS ON SPECIFIC TYPES
"- OF HARrWARE AND HAS PEFMITTED THE CAKCE*LATION OF TWO PLAFNCD REPORTS ON ITEMS THAT WERE ADEQUATELY CCVEEED IN THE MITRE REPCRT.
THE REPORT ALSO it TO BE REVERENCED IN THE DESIGN GUIDANCE REPORT NOW 3EINO PREPARED IN CCNNECTICM WITH THE FUEL CYCL' FACILITY SAFEGUARDS UPGRADE RULE.
$~51_r[5";NT12_f, Pf17tE:
N/A - REPCRTS WFRE REVIEWED. NMSS PLANS TO REFERENCE PARTS OF THESE REPORTS IN A ICn TECCMWS GJIDANCE PACKAGE TO LICENSEES.
5k E_(&MTs 09 C 3 Q1L? b__L-__"_I LLEY 2 i
l
__ ktvItw FeR Ccr.NENT INITIATED C3/22/75.
COMMENTS EXPECTED CN 10/23/7E.
\\
l l
27 1
1 l
i 1
28
- FOG"*M C'flCE C0%:EN15 ON P QJ tN T I t UTILIZATION OR VtiUE OF uESEARCH RESULTS IN THE REGULAIORY P;;0 C ES S
~~
l E11.8: 21 CATE ISSUED:
3/24/73 DES PROGRAN ELEMENT: RISK ASSESSMENY DIL TITLE:
07ITICAL REv!EW OF SCDIUM HYDRLXICE AEROSOL IDXICITY SPO*S0eINO OrrICE(5): RES RES: N0t'E RESEARCH PROJECT MGR:
M.
CULLINGFORD P11_fC5*(1TS: THIS WORK CONSISTED PRIMARILY OF A REVIE4 0F RELLVANi LITERATURE (WITH SOME PRELIMINARY SUPPORTIVE ALAL1515) FtRTAINING TO THC TCXICITY OF SODIUM HYDROXfDE INA0H).
CNE INSIGHT HAS BEEN THAT SCDIUM IN 1HE HYDROXIDE (
FCPM. FCLLCMING AN INCICENT INVOLVING S0DILM Rt' 5 ASE, MAY NOT EXIST IN SUFFICIENT AMOUNTS TO WARRANT FURTHER ATTEwTION.
IN AODITION. THE CHEMIC AL SPECIFS THiT WOULD BE PRESENT IN APPRECIABLE QUANTITIES (NA2CO3) MAY NOT BE JF CONCEPN IN TEPMS CF HEALTH EFFECTS.
THE PRINCIPAL FINDINOS WNIC% SUBSTANTIrTE 'dE ABOVE INSIGHTS ARE:
(A)
FOR PELATIVE PUMICITIES EXCEE9?NC 357, IT APPEARS ! HAT NACH DROPLETS IN THE ATMOSPHERE WILL BC TRANSFCRt!ED TO SCDIUM CARbONAIF DECAHYrRAlf IN LESS THAN A MINUTE IF THE NACH AEROSOL CCNCENTRATICM IS ESS THAN CR ECUAL TO ABOUT ~00 CG/M3.
THIS TRANSFORMATION WILL TAKE LONGER IF THE EELA!IVE HUNIDITY IS LESS THAN $5%.
(B) THE ALE?.LINITY OF A SODIUM CARCDMATE SCtUTION WIli St SUBSTANTIALLY LESS THAN THAT OF A SODIUM fiYCROXIDE SOLUTICN OF THE SAME NORMALITY; THUS. CAR 20NATE AEROSOLS WILL BE LESS HA2APDOUS. PER SCDIUM ATCN. THAM HYOROXIDE AEROS9LS.
(C) THE TRANSFORMATION FPOM THE SOUIL9M HYDROXIDE TO SODTUM CARBONATE DECAHYCRATE INOREASES THE AEROD1 NEMIC DIAMETER OF T"5 AEROSOL SY APPROX 1 ** t ELY 40%.
TFIS INCREASE IN DIAMETER SHIFTS SCME OF THE AERC!DL 0;- CF THE RESPIRASLE RANGE AND THUS LOWERS THE RESPIRABLE FRACTION OF THE AEROSCL.
HYF 3% ICE CR CAR?ONATE PARTICLES ENTERING THE UPPER RESPIRATORY TRACT WILL ABSCRB WATER AND ixCW S0 THE RESPIRAPIE FRACTION WILL DECREASE.
USER DISCUSSION POSIr!ON COMMISSICN ACRS PRE 55 0FFICE NEETING i4PER BLIEFING BRIEFING RELEASE PESULTS EOST_EIL_AC11VITIES
?EV11M NELD (CDPLETED HELD HELD ISSUED IPPLEMENTED OFFICE ALSFC:4SIBLE......... bRR SCHECULED COMPLETICM DATE.. S/29/78 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL CCNFLETICN DATE.....
05/31/75 EP CC-"!N T S C1J i/ 01/ 7h_WJOiLL :
E f 50 Li tt_ A LCLif allD M_lD_E!GT.2 7 0" Y PPOCESli THE REPORT PROVIDES THE LATEST AVAILABLE INFCPMATION ON SODIUM HYD':0XIDE ALEUSOL BEHAVICR AND IIS 10xICOLOS(.
THIS INFCRMATION IS NEEDFD IN OUR REVIEW ON CCNTROL ROOM HABITABILITY AND OFF-SITE CCNSEOUENCES FOLLClING A POSTULATED ACCIDENTIAL RELEASE OF SODIUM FETAL AND SODIUM FIRE.
Ef 5CElf E_LIACl_pF 3E}RTS: THE REPORT FORMS A BASIS FOR CONSIDERING OTHER SPECIES LESS T0XIC AND MORE READILY FORMED THAN SJDIU:1 Ht CROXICE IN CUR REVIEW OF SODIUM HAZARDS.
CON"ENTS/ REM 1055:
AUTHORS RECOMMENCATICNS FOR rJETHER M9RK SHOULD BE CONSIDERED WITH RESPECT TO NRR'S NEEDS.
28
29 Q [VALUE OF RESEacCH RESULTS IN THE GEGulTICRY PDOCESS i
c se-E t F I C E C C -"En !S Cs (Ott,71*L U!ILIZATION PIL s: 23 DsTE TSSUED:
4/10/73 PES PROOPAM FLEMENT: SAFEGUARDS c1L TITLE:
"EASI" ADVERSARY SEOCENCE EVALUATICN MODEL (COMPUTER GRAPHICS VERSICN)
!PCN5-PIN 3 CEFICLill: N"SS PPG:
4-1 EFFECIIVENESS FESEAPCH PROJECT MOR: R ROBINSON EVALUATION RES CC MENTS: FESEAPCH HAS BEEN COMPLETFu 04 CEVELCPIitG A GOAFHICS DISPLAY VERSICN OF A COMPUTER MODEL CALLED ESTI"1![ SF ADVIRSARY SEOUESCE INTER 8CPTION (ftSI). AND PESPONDS TO AN EXPRESSED NEED FCR EVALUATIVE METHODS FOR FIXED-SITE THEFT AND SABOTAGE PREVENTIC" $YSTEMS.
00CUNtMTATICN HAS ALREtDY BEEN MADE AVAILABLE THROUGHOUT NRC CON:ERNING PFCCRAMM:fLE PCCF,ET CALCULA Ce VERSICNS OF THE EASI N00EL.
THE COJECTINE CF THE *ELSI* METHOD IS TD PE',v!CE A USABLE EVALUATION METHOD WHICH CAN SERVE AS EITHER A PHYSICAL PFOTECTICN SYSTEM OESIGN AID CR AS A DECIs;09 AID IN THE LTCENSING AND IN5PECTION PRCCESS. THE EASI GRAPHICS PROGRAM ALLC25 THE USER TD INFU! FACILITY AND AL/LRSARY PATH ATiRIBUTES AT A CD"PUTER GRAPHICS TERMINAL. AND OBTAIN AS OUTPUT A CRT "FERSFECTIVE VIEW" LINE PLOT THE MSTNOD CAN TRtAT R3iu THEFT Ah* SABOTAGE OBJECTIVES BY THREATS OF INSIDERS.
CUTSICERS. AND CCESINATICN5 CF EACH GROUP.
Yur ersm T% CF THE EASI ANALYSIS AEC FXPRESSED IN TERMS OF THE PROBAEILITY THAT THE PHYSICAL PROTECTION SYSTEM CAN RtM ;Na IN TI E TO INTERRUPT AM ADVERSI.?Y ALONG A ?HYSICAL PATH (ACTION SEQUENCE).
TC SUPPLEMFNT THE EASI C AL CL'L A T ICNS, EASI GRAPHICS PF0VIOf5 THE ANALYST WITH A SELECTION CF SIX TWO-DIMENSICNAL AND EIGHi sHREE-DIMENSIONAL PLOYS.
THESE Ft0Ti ALLCW THE USER TO EXAN'"- THE SENS'TIVITIES OF VARIOUS COMPONENTS ALONG THE ADVERSARY'S PATH AND 10 STUCf TFE EFFECT CN THE PRC 43.' I T
,F
.NTERPUPTION Of VARVING THE PERFORMANCE Or THESE CCM70NENTS.
IT IS FECCM"EN0ED THAT THE EASI hETHOD /E US(D BY hMSS AND OTHER OFFICES AS AN ANCILLARY AID IN DEVELOPING PERTCF 2NCE-CRIENTED REGULATICNS OR IN CfrRYING OU! A CCMPREHENSIVE EVALUATION PROGRAM.
USER DISct'SSION PCSITICN COMMISSION ACR$
PRESS OFFICE MEETING PAPEk ERIEFING BRIEFIhG RELEASE R ES'JL T S PC$J R_Il_aCTiviTJ5%
Pr?[LN HELD Cr"Pt E ff D HELD HELD ISSUED IMrLEMENTED ur.t v t aus I E t t......... nMi$
SCHtCJLED CI TL ET ION CATE.. 6/10/73 UNSCHED UNSCHED UNSCHED UNSCHED UNSiHED UNSCHED AC!UIL COMPLETION DATE..
h*ll_f!ZZ13i%,
3.
HSTTER:
N/A - TEST APPLICATIONS ARE BEING CONDUCTED TO DETERMINE USER SUITAB?LITY h6 9 ~~M _M.J_? 'MG 6 s J JM LLC kElitW r C r: COMMLN! INillA1ED ;&'22/73.
CCMMENTS EXPECTF.D ON 13/23/7F.
l 2,0 l
P&OGRAM OH ICE COM"ENVi ON POIENTIAL UflL72ATION OR VALUE OF RESEARCH RESULTS IN THE REGULATORY PROCESS i
TATE ISSUED: 4/10/73 PES PROCRAM ELEMENT: SAFEGUARDS PIL #1 F_ I_L TITLE:
"FESET' AIMERSAPY SECUENCE EVALUATION MODEL
'iL0NSOPIN G_p F F I C E(5 ) : HN55 EPfG:
4-1 EFFECTIVENESS RESEA'CH PROJECT t'GR:
R, ROBINSON EVALUATION c!E5J0P;"lLM : RESEAkCH HAS BEEN COMPLETED ON THE FORCIBLE ENTRY SAFEGUARDS EFFECTIVENESS MODEL (FESEM), IN RESPON5t 10 A NEED FOR EVALUATIVE METHODS FOR TIXED-SITE THEFT AND SABOTAGE FREVENTION SYSTEMS.
THE PURF05: OF TH?S SidDY MAS TO LEbELOP A METHODOLOGY FOR ANALYZING FIXED-SITE SECURITY SYSTEMS AS TO THEIR EFFECTIVENESS AGAINST A FDECIBLE ATTACK BY AN ADVERSARY INTENT ON CREATING Ar* ACT OF SABOTAGE OR THEFT.
THE MODEL Pk1VIDES A FRAMEWORK ICR PEPF0FMING INEXPENSIVE EXPERIMENTS RELATED TO FIXED-SITF SECURITY SYSTEMS. FOR TESTING M TERNATIVE DECISIONS. AND FOR CEV* RMINING THE RELATIVE COST EFFECTIVENESS ASSOCIATED WITH THESE DECISION POLICIES.
c THE RESULTS OF THE FESEM ANALYSIS INELUDE ESTIMATES OF THE PROBABILITY OF SABOTAGE OR THEFT WINS (AND LOSSES) BASED ON ATTACK F0 ICE SIZE, ATTACK MOBILITY. AND TYPE OF ATTACK; COLLECTED STATISTICS ASSOCIATED WITH EACH VARIABLE (E.G,.
NU?"BER OF WINS 3.Y DEFENDERS AND BY f TT ACKEPS FOR SUCCESS /UL SABOTAGE OR THEFT, AL ARM TYPES FOR ALL RUNS, TIME REQUIRED FCR SUCCESSFUt SABOTAGE Ck CCMPLETION OF THEFT, ETC.).
THE PROGRAM IS CURREFTLY AVAILABLE FOR KRC USE VIA AN ACCESS CODE NUMBER TO SANDIA*S COMPUTER. A TRAINING PROGRAM WAS FIVEN IM FEBRUAaY 1978 TO INTERESTED NRC PERSONNEL AND POTENTIAL USERS.
IT IS PECOMMLNDED THAT.'HE FESEM MODEL BE USED AY HMSS AND OTHER OFFICES AS AN ANCILLARY AID IN FORMULATING AEGULATORY REQUIREMENTS. LICENSING. I:"*ECTION AND OTHER MONITORING OPERATIONS.
USER DISCUSSION POSITION COMMISSION ACRS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS E0$L?lLlCT LYIUIS REU14 HELD fd*P L ET ED HELD HELD ISSUED IMPLEMENTED 3f f IC1i R E S F 0 N S I f, L t......... Ni;55/NRR NRR SCHEDULED CCMPLETION DATE.
6/10/78 UNSCHED UNSCHED UNSCHED UNSCHED UNSrHED UNSCHED
%CTUAL COMPLETICN DATE.....
N_MS_)_ CE"'CJ
' LLER - TEST APPLICATIONS ARE BEING CONDUCTLD 10 DETERMINE USER SUITABILITY.
RPf l 0 % CM TS_ y n 2% _ L MR LE3 Rtv1Lu FOR CO llIA1ED 08/22//8.
COMMENTS EXPECTED ON 10/23/78.
~
1D CU'E LNT.5 C L I.
IPE FLSU4TS OF
.rFIR T. R1 Uti15'*3 G
2 WILL wm USED IM DEVELOPMENT OF STANDARDS FOR SAFEGUARDS SYSTEMS LS W 9.( A% f,Y LICENSEES IN DEVELOPING THEIR SYSTEMS AND BY NRC IN EVALUATING THOSE SYSTFMS.
30
31 P A01t!H C& F ICE _00t9EN f 5 UN F0fENTIAL_UfjtIZA110N OR VALUE CG -
ISULIS IN THE REGULATORY FROCESS PIL 8: 25 DATE IS!UED:
3/21/7A PES. PROGRAM ELEMEMf FUEL BEHAVIOR R J L T I '11:
FRAP-53
$P2_NS001NG OFFII_E(S); NRR EP3:
1-12 TUEL CODE RESEARCH PF0 JECT MGRt G. MARINO DEVELOPMENT PE5_ f p** LN T S -
FPAP-53 15 A BEST-ESTIMATE COMPUTEP CGDE TH AT CALCUL ATES THE THERMAL AND MECHANICAL RESPONSE ce4ARActth1SIICS OF A NUCt E AR FUEL ROD OPER ATING UNDER STE ADY-ST ATE POWER CONDITIONS. AND WAS DEVELOPED TO PROVIDE ACCURATE INITIAL VALUES OF FUCL-ROD PARAMETERS FOR INPUT INTO TRANSIENT ANALYSES CODES SUCH AS FRAP-T AND RELAP.
IT IS CAPABtE Or SUP? LYING THE HOT-STATE VALUES OF SUCH QUARTITIES AS:
1 STORED ENEeGY 2.
RACIAL TEMFERATURE DISTRIBUTIONS AT GIVEN AXIAL LOCATIONS 3.
TOTAL FISSION GAS RELEASE 4.
RSD 'NTERNAL CAS PRESSURE AND COMPOSITICM 5
CLAD DEFORMATION 6.
AMOUNT OF PELIET-CLAD INTERACTION (PCI) 7.
FUEL DEFORMATION (SWELLING. DENSIFICATICd, REL OC AT ION, AND THERMAL EXPANSION) 8.
FUEL-CLAD GAP SIZE AND GAP CONDUCTANCE 9.
CLAD-CCFELSION AND HYDRIDING.
ALL CT THESE CUANTITIES ARE STRONGLY DEPENDE%T UFON THE OPERATING HISTORY OF THE ROD AND EACH WILL HAVE A LARGE EFFECT 09 THE FREDICTED AND MEASURED RESPONSE OF A FUEL RCD CURING A TRANSIENs'.
7HE CODE. THEREFORE, HAS BEEN DESIGNEC TO FROVIDE THELE AND OTHER QUANTITIES FOR ANY GIVEN POWER HISTORY AS INITIAL CONDITIONS TO THE TRANSIENT CODES.
THE VERIFICATION OF THE FRAP-53 CODE HAD TW3.?AJOR 03JECTI%ES:
(1) (O CETERMINE THE CODE PERFORMANCE IN PREDICTING THE AVAILALLE. CUALIFIED, EXFERIMENTAL DATA, AN3 (2) TO IDENTIFY THOSE AREAS TdAT REQUIRE MORE SOPHISTICATED MDDELING OR MORL EXPERIMENTAL UATA.
THE CODE PEPF0FMaNCE 2ND DAT A MERE ANALYZED USING ST2TISTICAL METHODS.
- THUS, ALL OF THE MAJOR F ESFONSE VARI ABLES ARE PRESENTED ALONG WITH THEIR CORRESPONDING STANDARD ERROR BOUNDS.
THE VERIFICA'10N PROCEDU2E USED INFORNATION FROM OVER 700 SCEL RODS CONTAINING A WIDE RANGE DF OPERATING AND DESIGN PARAMETERS USER DISCUSSION POSITION COMMISSION ACWS PRESS OFFICE MEE?ING PAPER BRIEFING BRI E FINP-RELEASE RESULTS i 95T_ ELL FCT LVITjf1 RE11EW ELLD COMPLETED HELD HELD ISSUED IMPLEMENTED Off!CL RL560NSILLE......... NkR/hD SCHEDUL E D COMFI E T ION DATE.. S/21/73 UNSCHED UNSCHED UNSCHED UNSCNED UNSCHED UNSCHED ACTUAL COMPLETION DATE.... --
_.JP' _COTEN15_0!L9 5/22rl5,_D. POSSI P! SC klf L_flilli41HS_J 0_1100L licit _E RECESS! STEADY-STATE FUEL PERF0FMAN;E CODES ARE REVIEWED BY NRR AS PART OF LOCA AND U1HER ACCIT*E N T ANALYSIS.
Hkk USLS AH INDEPENDiNT NRC-DEVELOPED CODE FsR AUDIT PURP05ES IN THESE REVIEWS.
Pf 5 C P LEE _ !O[$ C.l_0f_F F.5PL T S : NO niRECT IMPACT.
NRR USES THE GAPCON SERIES OF CODES IN AUDIT WORK AS IT HAS DONE SINCE BLFutt f R AF -5 WAS DLVt L OPED.
NRR HAS NO PLANS TO USE FRAP-S IN THIS CAPACITY.
Cp:MFNTSf(r,M3gtS: THE FRAP-S CODE W35 DE/ ELOPED LY RES TO INIeIALI25 VARIOUS ANALYSIS CODES.
RES AND NRR HAVE RECOGN12LD IHL DUPLICATE GAFCON AND FRAP-S CDDE TFFORTS AND HAVE CONSOLIDATED THESE EFFORTS INTO A HYBRID CODE FRAPCON.
TR APCON WIll CONTAIN SOME ELEMT.N15 FROM FRAP-53, BUT FAAP-S DEVELOPMENT WILL BE DISCONTINUED.
S D C C D**1N T $, R. PIVEDPANK - NO PESP095E RECEIVED.
31 1
i
P-$
Cat W
e4 et I
.J W
>=
2W
.4
.J J
W W@
=( 2 U er
> Z
>J W
oft at O
Cg W
@ CL T O Z r3 M
.J W Z 6
23W D
HZ M
W
)>
- a4
> >=
Cg UUU W
M Q >= D 6.J @ Z U
M 4
2 at W
m3 @
>= W at O O.J Z 4 W
m3 O
W6Q Q
Q:
- 4@W
>=
at O 6
M m3 O QZ W'
e0 O ut CK ZUMO 6
.J Q
t=
Q
.J W
>=
I J a3 U O O me H >=
W e4 M
at
- W tt.J DL Z
- 6 W
Z >= W *C
>= >
EM WOD OW
@W G
QW M&=WUQ J
et Cr W Z *= 0 3Q pE W
AEZ Z42MW 4
et O
O r*
>= 3 JW Z
ZO46 CW.4 W.J L 4.D O
6M QC W
- D.J U
6 is.J O W D O CL Q O
Z U Z@
> CL Ca' W
@ CL 6
UU CL J W
W n
>4 Z
Z OW WE IZ Z
6@
Z.J Z 4 W CL E
k w
et if 6 2>
Car M 1D OMQZ O *4 O >
Z Z O
Q at Z@
@W M
V U re W
O W E W >= >= Z 63
>MbQ
>= CL Q 4
CE O
M =C 6O Z Cr >= Z
>QZZ O
M
=(
>=
C et
>= Z O Z.
O
>e at ZWW6@
C*
"D U
CaC O Z46 W.
Q E A Z >=
O *4 >=
J l
at E
Q W CL U
=C Z Q
@Q W
MWM@
EOZUO N
M J Q >= 0
>= > U.e W
-J W
e4
- a E
> = > =
>= kJ
@ at W Z
MMe
>= # U 6 >=
D C
>g*=
tr >=
ZE
@WD Ul 0
Q >=
Ch Z
O@U
- E>=
W.4 0 Mi WW>Q
@ es
>=
4.aJ Z
ag 6
QW C( @ et
.J>=
Cg W @
l Z
>U Z W @UZ cr aC ZU E W CL A
- 4 Cg M I D QClu D >= # >e W U L'
Z.
at 4 ** J C CW >
6WZ et Z CL CK W
> 0 U
7 Cg W H 6 CL >= U + 6 2 >= @ aC I
>4 CL 3A @#
W>W at M>6 W
C=
W >
- a Lad af
@.*L ^
306 0
>= Q Z s'.J 4 W 6 N @
mm 6
4 W
Z W at U O
et Z
O
@ >= M W J a= U O O W Z
aC Z
L=
JTw CL @ @
M W
Z et O Z 6 CK M
W W
Z4 CW
>=
6 Z
O W W W Cet a4 %
m Ca H
@WQ CL' O @
@WQ U1
>= D Q O W W G O @ J W
- e CW MLZ
- 4 b=
Car >=.J
@ l Z Q me Z > M **Z aC
.J
.J 3O 4
W CL M U CK W t 7 M
>NWMOWGM J
U et M
WQ
-J E asa "I i 3
- at b J O >= > M M U 24
> Z Z Z **
OMQ Q >= 7 A U *t @ >= 0 U Q
>= *L a4 =( uJ D Z W @ LaJ 4 @ W OU@
i.aJ
>e MZ
.4 w CE ZW4
>= >= m2 O
- 9..aCL 4 T
J
>=
> LaJ L G Z
e4 Cg N @ m3 *C @
6 W
4 d sa ZZ 6 O Ca' O
Cr " J >= m3 o e O M me O O T
D W
- E Cr =L @
OZW 6e O OO@
W *= Q Z U
6 Cr Z =J
- ( Z 6
>= 3
@Z Q
CL >= >4 et WZ M@
Ch' U
et at W >= 6 O C
@M Wl Y
Cr ZCgW>@Z at W
H Z
.4 O
Z 6 CL M6 II J > D Q >4 O >= W Z O uJ
>=
CE U
>= O 0W MC KWQ U
U m3 O W E O O W **
7 at we M Dy>
>= W 6 pg
,J Z
>= g.3 W CL >= U >=
haJ W
Z CL 6**
Z CD J M > =E OCatufI M e a=s D
- O M st Y
E Q
I E W 4t
- 1. M
@ >= W U m3 Il 1 D
@ LL > @ CK 6 at.J D W
D **
ZW O U me.J O>00@WO6
- =
6 J
>e Wu Z f *a W Q.J U Z Cf CE >e O
@ W **
O W
Z UU EQ U >* Z Eg
>= >e D m e O Z CL Z @== W @
Q O **
I W ba M
m3 7 O
W@O
@ O uJ >= D W
E M
>= CK
- C > Q W et Z
W 53 W ** O *=e CW >= et > W D
at O
Od
.J > b=
0 >=
Q Cr >= @ Z ** *t @ *3 =E
.J Ch at
== Z OZ J sa @
sa @ D M
W LaJ et.J > @ E 6W at O
>= NO UC 6 et W at O >= CE J Kl
- Z.J =E M
J ll>
O sV a) J
>= W m3 he dJ CL U1 UO WZW *ZU CL eA W U@
4OM D Z aC
@6E
> at tw > J ** @ @ ke D Y
Cu O
CK Z Ca:E ma >=
O at O 4 :r O W *C Q C.a knJ W Z
O Z
a ZO LL Ca.
A CL U l D D ela Ca:DZQ MZ
- O M Ca*
6
>= >= >= =C W W $* Cg C Q 2
W
>=
Ca
> = >
^
>=
- W
@ LL X @ Z v= Z O W > Ca O
Cs
- (
CL CE et
> m3 0
> = > *
- OW JWZU
=C
- m CE O-
>= w Z at c4 J Z
WOD CZZN ls' W
CL @
>e W
Q
>* W Z>@
U O O **
Z
."L E * * >=
3' W m3 **
ZU * > = W eWUMZ N
W
- ) O
>e @ e e
@O Q
- = Z W A= Car @
>=
O 4
X@@
>= 0 Q
@Z WI at CV
>= *
.J @ *C.id
.J
=e oW Cr =J Z DM I1 QO * ** @ CL at ** U 4
- I @.d *C Z > Z M CW mm Cs O p=
Ca' Z C+.
D U et U>Q U
a O
.o W J WrO @ De*Z 6 @>=
JD
=t
>= *C 4WZ + >= @ Q ou W W l Z
@pe 6 O m2 at CL >=
D W
>6 J
QW 8'==**e Q
>= Cr C3 E I ID L et 6 D =E > 6 O W Ca. 4 J
e3 O WZ 4 > CW W Z Z et
(
O Z CL Q O U > aC Z at N
D Ch W wUW@
we >* 3
.J W et U
=E b
N P WO 4>4 OO MMMMUmb6ZZE N
6 CE 6 W Z 4 >=
m3 CLlw >=
@ >= Q M *C O t
(*= re @ CV
- E CK 2
N w
, 6 Ca' u >= =4 CE O
43 N u
- aJ Cr O *E W>
U
>*>=@
W *T)
NN
> >{2 2 M D @ Z W >= @ 6 W
G W
et et T Z > *t W Uw
%b
- ca ew **
O**>=0.J4 O
.1 W.J Z
U we U Q Cp N 7 C4== U @
ZUZW3M 6
Ca' O >= I 4 3
=D W w.> N N %
Ca M O *.* >= Z >= re et 6
et D UW>
Q W>=
@ 6 hAa'% @
oL > Y W
> CK CW > >=
2" 6
Z W =4 mm **
W.J M D O Q l.C @ E3 et Z O Q Cs O
O
>W 3
CE a.a >=
Z W.J >= a W4 3
E die. Z C O O Z W >= 0 6= 6 et sa *( as M>=
+ *
- 6aM>
Z > j> 0 U @ >=
D 6
Cr JO U
WO4 Z N Cat Z% >= D WW=*
- e. l O Cr D
- O L1861 OM eW CL 3
=
O@W SN ZI O
7 Q ' * *" bJ
.es J >=
- > =
- e Q M o m.aM t W M :.
=OZ 4.
N W
M
>=
WW ren Z@u U 6 Z >=
U 4M ** Z 2* e t ZWW eQW
% **J N rla w w J N
ZQ@
Cale =C
> = >
i.
W es
=
4 e
- e4 > +
W Z Ca
+ >=
WCQ C
o C.
n W a.
vE u w 74 v
et.
C
@E >= &a Q ** Car > D W OQ
% %.ad >= 6 J I E =J
.J d
4 w
anJ **
JWJQ bad -d V 64 4ad M d e u me O *4 Cy V re D " L.J hl beJ Z
D >= D CL >=
>%d >= Y RalZ @
3 14 O d'h =s 7l=v ) Q @ > I p.go >* @ Cq't rO O HWUI U
W v
> = >
@ woe Cr 6 McWO w
I M
.J W.3 3 at W.4 O me eg.J **
a u
e L W
Cn:
Z@
ll> $# C *=
C.M U mt ! E
+G u.
u V Z@>
>=@>
e
'? E J l d e Z # M C. h O @ T a-o O
O
@lM Z *e Z.4 ha.J >=
>= Q U J Lenaet**T Q Q Z O6*4:=
- "p*=J U
C.uJ
- UM k 146 N C.
- " N ed 2 O.I b ' IC l1 op O
71 Cr @ Cs at
> b..J
=t i @
E 7 j
- Ca. Si wJ U *= N1
=L N
68
- c 6M
=E W > **
W 7 *-e p.aJ Q O dJ 7 J C='
O W Cr @ J A'
.J
>1
) 5.!
W *= at >
- 1 SQ AT W U
$ tie O CE C.. O C44 Z
- L W ea3 i
t--
(L 1 **
@ D CL Z 7 e= *C
- 4 a
S M i~ *L
=a >1 4 > W Z l c.
- >=
ca DO Wr, W
E O *-
Ch w D J O r.a== W CW "* cv C..J Z 6.a 2 od 85 e-VJ VA Cr >= 3 7
- .J Z @
lU Q *t L.A L *
- d W % u== W
[^ i
- C lL Z
l.aJ Cs W O
> t*= W D Me o 3 Z Wo w CL a E
.J
.J c,
o@ W *= 4 C
-W vm. I >
taaJ=0WmMZwa tw C.,
Et. t Z >= W M ZDZ Q: U U Ca O== Z Ca. ea Ca et.J 6 Ut'I i
Ch Cm, o Cu er
>= 4 e1 W H s.a >=
6 U @ -t gi x
l 33
_ PROGRAM OFFICE COMMENTS ON POTENTIAL UTILIZATION OR VALUE OF PESEAPCM RESULTS IN THE DEGULATORY PROCESS P.It 8*
27 DATE ISSUED: 6/2/78 RES PROGRAM ELEMEMI: CODE DEVELOPMENT Q1L TITLEt "BEACON / MOD 2" SPONSORING OFF7CE(Sir RES 1P9:
1-15 CONTAINMENT CODE RESEARCH PROJECT MGRt S. FABIC P[1_(Q[O[NT32 THIS RIL TRtNSMITS THE BEACON / MOD 2 COMPUTER CODE MANUAL, DESCRIBES ITS FIELD OF APPLICATION AND DISCUSSES THE CGDE'S STRENGTHS AND LIMITATI0MS. BEACON / MOD 2 IS AN ADVANCED, BEST ESTIMATE CODE INTENDED FOR EVALUATION OF SHCPT-TERM THEPMOHYDRAULIC CONDITIJNS WITHIN "DRY" (FULL PRESSURE) MULTICOMPARTMENT CONTAIMMENTS, OR WITHIN CERTAIN REGIONS OF THE "PPES$URE SUPPRESSION" DRYWELL.
THIS RESEARCH WAS INITIATED TO PROVIDE IMPORTANT MODELING IMPROVEMENTS FOR BEST E5TIMATE ANALYSIS OF THESE CONTAINMENT SYSTEMS.
BEACON / MOD 2 UFFERS CONSICER AB*_ E ADV ANTAGES OVER THE EXISTING CONT AINMENT CODES FOR BEST ESTIMATE EVALUATION OF HYCRAULIC LOADS IN MULTICOMPARTMENT PWR TYPE CONTAINMENTS.
IT IS PARTICULARLY SUITABLE FOR EVALUATION OF THE REACTOR CAVITY LOADS (FOR POSTULATED BPEAKS BETWEEN THE REACTOR 'ESSEL AND THE BIOLOGICAL SHIELD) IN BOTH PWR AND BWR CONTAINMENTS.
THE CODE HAS ALSD SHOWN A CAPABILITY TO DESCRIBE THE EV0luTION OF A TWO-THASE (FLASHING) JET AND THE RESULTING PRESSURE LOADS ON THE IMFACTED BARRIER.
IT IS RECOGNIZED THAT THE CODE MUST BE M0kE EXTENSIVELY TESTED AGAINST EXPERIMENTAL DATA.
NEVERTHELESS. THE BEACON / MOD 2 IS RECOMMENDED FOR CALCULATIONS OF THE REACTOR CAVITY LOADS, FOR BOTH PWR AND BWR INSTALLATIONS, AND FOR EVALUATION OF JET IMPACT LOADS.
USER DISCUSSION POSITION COMMISSION ACRS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS E051_RIL_fCTIVIIIES REVIEW HELD CCMPLETED HELD HELD ISSUED IMPLEMENI[g 0FLICE RESPGNSIBLE......... NRR SCHEDULED COMPLET]ON DATE.. 6/10/73 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL COMPLETION DATE.....
NDR COMMENTS.
R.
TEDESCor RESPONSE EXPECTED ON 10/13/78 33
34 PROG &AM OFFICE CO*"LNf5 ON POIENiiAL UTILIZ3 TION OR valyl _DF_fESEADCH RESULTS IN THE REOUL ATORY FROCESS PIL_f: 23 DATE ISSUEJ: S/9/78 RIL PPOGRAM ELEMENT: FUEL BEHAVIOR ELL _ TITLE "MELT / CONCRETE INTERACTIONS" iPp33DE1HG_Off]IEfS): RES RP9:
1-13 FUEL MELT RESEARCH PROJECT MQR:
R. DISALVC RIS_COTrENI): THIS RIL DESCRIBES THE INTER-1 CODE FOR CALCULATING THE EFFECTS OF INTERACTION BETWEEN MOLTEN MATEKIALS AND CONCRETE AND THE EXPERIMENTAL DATA BASE FROM WHICH IT WAS DEVELOPED. THIS WORK HAS RESULTED IN AN IMPROVED MODEL BASED ON EXPERIMENTS WITH PROTOTYPICAL MATERIALS.
IN SEPARATE EFFECTS EXPERIMENTS. MONOLITHIC SPECIMENS OF CONCRETE WERE SUBJECTED TO CONTROLLFD THERMAL FLUX 55 IN ORDER TO MEASURE RATES CF E:.051CN.
EROSICM IS LINEAR WITH TIME FOR A GIVEN HEAT FLUX, AFTER CORRECTION FOR THERMAL LOSSES THROUCHCUT REFLECTION AND RADIATION.
THE DOMINANT MODE OF EROSION IS QUI 2 SCENT MELTING OF THE CEMFNT (I.E..
THE BINDING MATERIAL), WITH NO DIFFEENCES OBSERVED BY VARYING THE COMPCSITION OF THE AGGREGATE MATERIAL. THESE DATh ARE NECESSARY TO INTERPRET EROSION RATES OBSERVED IN INTEGRAL EXPERIMENTS.
AS A RESULT OF THE INTEGRAL EXPERIMENTS, IN WHCH PROTOTYPICAL MOLTEN MATERI ALS C0i87 ACT CONCRETE, THE FOLLOWING CONCLUSIONS WERE DRAWN:
- EROSION OF CONCRETE IS THERMALLY DOMINATED. WITH INSIGNIFICANT CONTRIBUTIONS FROM FiCHANICAL AND CHEMICAL EFFECTS.
- THE PRINCIPAL MECHANISM OF EROSION IS MELTING OF THE BIHLING MATERIAL, WITH NO SIGNIFICANT QUALITATIVE DIFFERENCES CAUSED BY CHANGI'4G THE CGNPOSITIPN OF THE AGGREGATE.
- THE COMPOSITION OF THE CJNCREIE DETERMINES THE COMPOSITION AND MASSES OF GASES RELEASED AT THE INTERFACE OF THE MELT AND CONCRETE.
- TURBULENCE AND ESSENTIALIY ISOTHERMAL CONDITIONS ARE INDUCED IN THE MELT BY THE PASSAGE OF LECOMPOSITION GASES.
- H"0ROGEN AND CARBON MUNOXIDE ARE AMONG THE GASES EVOLVED FROM THE SURFACE OF THE MELT AND THEY BURN U"0N COWTACTING AIR.
THIS INDICATES THAT THE H2O AND C0Z RELEASED FROM THE DECOMPOSING CONCRETE ARE REDUCED CHEMICALLY, MOST LIKELY BY OXIDIZING TFE METALLIC CONSTITUENTS OF THE MELT.
THE EXPERIMENTS HAVE CULMINATED IN AN ANALYTICAL MODEL (INTER-1) 0F THE MELT /CONCRErE INTERACTION WHICH CAN HELP EXTEND THEIR RANGE OF APPLICABILITY.
WtILE DIRECT EXTPAPOLATION OF THE DATA TO PROTGTfPICAL CONDITIONS MJST ALWAYS BE MADE CAUIIOUSLY, ENDUCH CONF!DENCE Has BEEN DEVELOPED 50 THAT NO FUNDAMENTAL DICFERENCES IN BEHAVIOR ARE ANTICIPATED iN SCALING TO FULL-12ZE SYSTErb 7ESERVATIONS EXIST REGARDING THE APPLICATION CF INTE4-1 TO PREDICT SUCH VARIA3LES AS THE TIME OF CONTAINMENT MEtTIHROUGH OR OVERPRESSUplZATION. THE MODEL CAN BEST BE UTILIZED IN ITS CURRENT FORM TO ESTIMATE THE RELATIVE SIGNIFICANCE OF VARIATIONS IN PARAMETERS SUCH A5 MATERIALS. PROPERTIES AND COMPOSITIONS, INTERFACE HEAT TRANSFER COEFFICIENTS, GECMETRY, ETC.
THE PRIMARY SIGNIFICANCE OF THE WORK DESCRIBED IS THE IMPROVED UNDERSTANDING OF PHYSICAL PHENOMENA.
RES RECOGNIZES THAT THE RESUL TS A2E UNLIKELY TO HAVE SIGNIFICANT NEAR-TEPM IMPACT ON CURRENT LICEN%ING PROCEC'JRES.
IT SHOULD, HOWEVER,
~~ PROVIDE ADDITIGNAL BACKGROUND INFORMATION USEFUL IN ANALYZING REGULATORY ISSUES INVOLVING ACCIDENTS 3EY3ND DESISN EASIS REVENTS.
USER DISCUSSION POSITION COMMISSION ACRS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS PM LPlLA CTIVURS REV H W tiiL D COMPLETED HELD HELP 15jiUED IMPLEMENTED OFIICE RESFONSIBLL......... NRR/SD SCHEDULED COMPLETION DATE.. 08/30/78 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHE?
UNSCHED
~2 ACTUAL CGMPLETION DATE.....
NRP_CDM*iNTS, Wm OA"M_lLL:
RESPONSE EXPECTED ON 10/13/78 SD COTMENTS.
G.
R!vEN3ApK: RESPONSE EXPECTED ON 10/13/78.
34
35 P90GRKH'0F FICE CCP9ENVS CN POVENTIAL UTILIEATION 04 VALUE OF RES2 ARCH RESULTS IN THE REGU(A107.Y F90 CESS ELL _12 29 DATE ISSUED: 5/7/78 RES PROGRAM ELEMENT: FUEL BEHAVIOR RXL TITLE:
"FUEL ROD ANALYSIS COMPUTER CODE FRAP-T3" SPONSCRING OFFICE (S): RFS DPL:
1-12 FUEL CODE RESEARCH PROJECT MGR:
H. SCOTT DEVELOPMENT EE5_LO55EMIS: THIS RIL TRANSMITS THE RESULTS OF COMPLETED RESEARCH TO PREPARF
- THIRD MODIFICATION OF THE CGMPUTEf. CODE FRAP-T (FUEL ROD ANALYSIS PROGRAM - TRANSIENT).
FRAP-T IS A Ff
'ER CODS BEING DEVELOPED TO PREDICT THE TRANSIENT REPONSE OF A L WP. FUEL ROD DURING POSTULATED ACCIDENTS
' ?J w 's
OLANT ACCIDENTS. POWER COOLING MISMATCH ACCIDENTS, REACTIVITY INITIATED ACCIDENTS. GR INLET FLOW r.ctuc1
.llDFe=5 FRAP-T IS ALSD BEING DEVELOPED TO PERFDRM THE CALCUL ATIONS NEEDED FOR PL ANNING AND ANALYZING Pf 4ER ",tR3C T A O U.
f L42 LOSS OF FLUID TEST EXPERIMENTS.
IN FRAP-73. THE COUPLED EFFECTS OF MECHANICAL. THERMAL. INTERNAL GAS AND tb TEK' 7i < JPEL 5Y M A*DfiNSE ON THE BEHAVIOR OF THE
/
FUEL ROD ARE CONSIDERED. GIVEN APPROPRIATE COOLANT CONDITION AND POWER HIS,'*~5
. < AP-i> 4, AN C(LCUL ATE ROD BEH AVIOR FOR A WIDE VARIETY OF OFF-NORMAL SITUATIONS AND POSTULATED ACCIDENT CONDITIO<
EW7 07 Nei PCMER TRANSIENIS. FLOW COASTDOWN. LOAD LOSS OR COOLANT DEPRESSURIZATON).
IN THE CONTEXT OF LWR SYSTEM TRANSIENTS FRAP IS WELL SUITED TO TO BE USED AS A COMPONENf CADE TO DESCRIBE FINE DETAIt" OF FUEL ROD BEHAVIOR.
F"RTHERMDRE. SENSITIVITY STUDIES WITH FRAP WILL FACILITATE LEFINITION OF THE SIMPLEST ACCEPTAP.E FUEL DESCRIPTION IN SYSTEMS CODES.
USER DISCUSSION POSITION COMMISSIOM ACRS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS E051_PJ1_A CJJVJ TLES EEVI(W HELD COMPLETEQ FELD H EL D ISSUED IMPLEMENTED O F F I C E R E S F' O N S I B L E......... NRR/SD SCHEDULED COMPLETION DATE.. 08/30/78 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL COMPLETION DATE.....
ERR _CD55ENTS ON 07/3J/78. J. V0GLEWEDE:
DESCPJDf_APFLICA1LON_TO PEGULATORY PROQ[11: TRANSIENT FUEL PERFORMANCE CODES ARE REVIEWED BY NRR AS PART Of LOCA AND OINER ACCIDENT ANALYSES.
NRR USES INDEPENDENT NRC-DEVELC'ED CODES FOR AUDIT PURR 0SES IN THESE REVIEWS.
DESCEJ EE_JMP A C T OF_EE$Ull):
FRAP-T3 IS ONE VERSION OF THE FRAP TRANSIENT FUEL PERFORMANCE CODE.
BECAUSE THIS IS ONLY AN INTERIM VERSION OF A BEST-ESTIMATE CODE. IT HAS NOT BEEN ADAPTED FOR LICENSING APPLICATIONS.
IN THE FUTURE. NRR PLANS TD USE THE WATER REACTOR ANALYSIS PACKAGE (WRAP) WHICH WILL INCLUDE A MORE CURRENT VERSION OF FRAP-T THAT INCORPORATES CONSERVATIVE MODIFICATIONS.
IN PRESENT AUDIT WCRK. NRR USES THE WATER PEACTOR EVALUATION MODEL (WREM) SERIES OF CODES WHICH D3ES NOT INCLUDE FRAP-T3.
(Q(([NT1LEEMARKS: THE NEED FOR A M0kc DETAILED TRANSIENT FUEL BEHAVIOR CODE IN LICENSING APPLICATIONS HAS LONG PEEN RECOGNIZED BY NRR.
IT IS EXPFCTED THAT A MORE CURRENT VERSION OF THE FRAP-T CODE SERIES WILL BE ADAPTED FOR LICENSING APPLICATIONS.
ALTHOUCH CONSERVATIVE MODIFICATIONS WILL BE REQUIRED. THIS CODE WILL CONTAIN MANY OF THE ELEMENTS NOW IN FRAP-T3.
SD COPMENTS, G.
RIVENBAPK: RESPONSE EXPECTED ON 10/13/78 l
35
36 P90GPAM OFFICE CC9MENTS ON POIENTIAL UTILIZATION OR VALUE OF RESEaRCH RESULTS IN THE PEGULATORY PROCESS m _t:
30 DATE ISSUED: 6/23/78 RES PROGRAM ELEMENT 2 SAFEGUARDS PIL TITLE: PHASE I FINAL REPORT. "BARRIER PENETRATION DATA BASE":
OF S'UDY "ASSISTANCE-PHYSICAL PROTECTILM ASSESSMENTS" T
SPONSORING OFFICE (S): NRR ggg: NONE
.R11EARCH PROJECT MGR:
J. MILLER R ELCOMMENIS : THE REPORTED RESULTS PROVIDED:
(1) A CLASSIFICATION OF BARRIERS IN TERMS OF THE PENETRATION TIME FOR SELECIED CCUNTERMEASURES WHICH AN ADVERSARY MIGHT USE TO OVERCOME THE BARRIER. AhD (2) PROCEDURES TO BE FOLLOWED IN TESTING REACTOR SITES FOR COMPLIANCE FOR 10 CFR 73,55.
TH"' REACTOR SAFEGUARDS REGULATION.
USER DISCUSSION POSITTON CONMISSION ACRS PRESS 0FFICE MEETING PAFER ERIEFING BRIECING RELEASE RESULTS P_Q1J_pIL_AC TJ_VIIIES EEVIEW HELD COMPLETED
[fLL D FFL D 1.151:,p__
IMPLEMENTED OFFICE ELSPONSIBLE......... hRR SCHEDULED COMPLFTION DATE.. 08/28/78 UNSCHED UNSCHED UNSCHED UNSCHED UNICHED UNSCHED ACTUAL COMPLETI0d DATE.....
M R_C0ZENJ$_pN J fj0] $,
J. MI,[({gi Di1GRJ R E APPLIC AIJON TQ_6LfilLATOPY PPQCISS: AS STATED IN THE RIt, THE BARRIER PENETRATION DATA BASE IS AVAILAELE AS A SUFFLLMENTAL DAIA SOURCE FOR USE IN THE EVALUATION OF LICENSEE FACILITY SAFEGUARD PROGRAMS.
THE DATA PROVIDES A STANDARDIZED BASE OF BARRIER DELAY TIMES AGAINST VARIOUS ADVERSARY COUNTERMEASURES FROM CURRENTLY AVAILABLE LITERATURE.
THIS DATA WILL PROVIDE FOR MORE RELIABLE AND CONSISTENT EVALUATION Or SAFEGUARD PROGRAMS BY BOTH THE NRR STAFF AND LICENSEE STAFFS.
DfftC"Iff_Jt*P A C T OF T E19tJjil THIS COMPILATION OF DATA IS USEFUL r0R THE DESIGN OF PHYSICAL SECURITY SYSTEMS By THE LICENSEES, #.5 WELL AS IN THE EVALUmTION OF THE EFFECTIVENESS OF SUCH SYSTEMS BY NRR.
ALTHOUGH THE RESULTS OF THIS PROGRAM WERE NOT AVAILABLE DURING THE DESIGN PHASE OF THE CURRENT UPGRADING OF PH(SICAL SECURITY AT NUCLEAR PCWER PLANTS, THIS DATA BASE WILL PROVIDE USEFUL DATA FOR FUTURE APPLICATIONS.
}
1 1
)
36
37_
PFOGkAM 05FICE COMMENTS ON POTENilAt 41XLJ2ATICH OR VAluE OF RESEARCH RESutVS IN i.EE REEULAT01Y PROCES2 PIL 3: 31 DAIE ISSUED: 07/10/7Q PES PROGPAM ELEMENT: SAFEGUARDS RIL TITLE:
"ASSAY OF STANDARD REFERENCE MATERIAL (SRM) 950B" SPONSOPING OFFICE (S): SD PSS:
4-5 MEASUREMENTS A RESEALCH PROJECT MGR:
R. SHEPARD STANDARDS RE1_C.DM5E N T S : THIS RIL TRANSMITS THE RESULTS CF A COMPLETED PHASE OF RESEARCH ON THE ASSAY DETERMINATON OF URANIUM IN STANDARD REFERENCE MATERIAL (SRM) 9505. IN RESPONSE TO A NEED TO IMPROVE THE QUALITY OF MEASUREMENTS MADE CN SPECIAL NUCLEAR MATERIAL FOR CONTROL AND ACCCUNIING PURPOSES.
THE PURPOSE OF THE WORK WAS TO DEVELOP AND CERTIFY A URANIUM CXICE (U305) ASSAY STANDARD TO REPLACE THE VIRTUALLY DEPtETED SRM 950A. USED IN NONDESTRUCTIVE ASSAYS.
THE RESEARCH RESULTS INDICATE THAT THE NEWLY DEVELOPED SRM 9205 CALIBRATION STANDARD HAS A CERTIFIED VALUE OF 99.97 4/- 0.02 PERCENT URANIUM OXIDF (U303).
THESE RESULTS ARE EXPECTED TO IMPROVE THE STANDARDIZATION AND CALIBRATION CAPABILITY OF BOTH NRC FIELD INSPECTORS AND THE NUCLE 1R INDUSTRY AS A WHOLE: THEY ARE EXPECTED TD HAVE A SIGNIFICANT NEAR-TERM IMPACT ON CURRENT SD GUIDES THA1 WILL ADDRESS THE IMPLEMENTATION OF 10 CFR 70.57. LICENSEES MEASUREMENT CONTROL PLANS.
USER DISCUSSION POSITION COMMISSION ACPS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS EDS L_RJ L_pg TJ VJ TJIS EEvlIW HELD COMPLETED HELD HELD ISSUED IMPLEMENTED UfEICE RESPONSIBLL......... NMSS/NPR NRR SCHEDULED C0"PLETION DATE.. 05/30/78 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL COMPLETION DATE.....
NMSS COMMENTS.
3.
HATTER - TEST APPLICATIONS ARE BEING CONDUCTED TO DETERMINE USER SUITABILITY.
NRR COMMENTS W.
GAMMILL - RESPONSE EXPECTED ON 10/10/73.
37
PPJGR AM Of FICE COPMENTS CN POTENilAL UTILIZATION OR VALUE OF PESEARCH PESULTS IN THE PEGULAV01Y PROCESS gll_e: 32 DATE ISSUED: 08/03/78 RES PROGPA9 ELEMENT: FAST EREEDER REACTORS PIL TITLE:
IMPROVEME6TS IN THE AEROSOL BEHAVIOR CODE FOR RADIOLOGICAL ASSESSMENTS OF LMFBRS.
iPQN3fPINS OFFICE (S): RES PEG:
2-7 AEROSOL MODELING PESEAPCH PPOJECT MANAGER:
J. LARKINS AND PROPERTIES RE5_C05?EN13: THIS MEMORANDUM TRANSMITS THE RESULTS OF COMPLETED RESEARCH ON THE MEASUREMENT OF SODIUM OXIDE AEROSOL PROPERTIES. SODIUM OXIDE IS THE KEY AEROSOL CONSTITUENT IN POSTULATED SEVERE LMFBR ACCIDENTS.
FOR THE MOST SEVERE POSTULATED LMFBR ACCIDENT SCENARIOS (HCDA AND CORE MELT), SODIUM-0XIDE AEROSOL REPRESENTS Th~
HIGHEST AIFBORNE MASS CONCENTRATIONS IN THE CONTAIN9ENT VESSEt AND IS EXPECTED TO DOMINATE AND GOVERN THE BEHAVIOR OF THE FUEL AND FISSION PRODUCT AEP050L.
THEREFORE. AS A FIRST STEP IN IMPROVING THE AEROSOL BEHAVIOR CODE, HAARM-2.
SEPAFATE EFFECTS WORK WAS CARRIED OUT CN SODIUM-0XIDE AEROSOL.
THE RESULTS OF THESE SEPARATE EFFECTS MEASUREMENTS HAVE BEEN INCORPORATED INTO THE MODELS OF THE AEROSOL BEHAVIOR CODE HAAPM-2. AND TOGETHER WITH SCME ADDITIONAL IMPROVEMENTS USED TO GENERATE A NEW VERSION CALLED HAARM-3.
ThE IMPRCVED MODELS IN HAARM-3 PROVIDE A MORE PEALISTIC DESCRIPTION OF PARTICLE CHARACTERISTICS AND THEREBY ALLOW IMPROVED ESTIMATES OF SODIUM-0XIDE AEROSOL BEHAVIOR DURING A POSTULATED HCDA.
THE HAARM CODE IS USED BY NRR FOR LMFBR SITE RADIOLOGICAL CONSEQUthCE ASSESSMENT.
USER DISCUSSION POSITION COMMISSION ACRS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS P051_RIL_ACTly[TI13 REVILM HELD COMPLETED HELD HELD ISSUED IMPLEMENTED OFFICE RLSPONSIBLE......... HaR SCHEDULED LCMPLETION DATE.
09/15/78 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL COMPLETION DATE....
NRR COMMENTS, W.
GAM 9ILL - RESPONSE EXPECTED ON 10/23/78.
38
39 PROGRAM OF FICE CCPME4V5 ON POVENilat Of1LIZAVION GP VALUE OF REsf4RCH RESULis IN THE REGULATORY FROCESS RIL 8:
33 DATE ISSUED: C8/03/78 RES PRn0 RAM ELEMENT: FUEL CYCLE SAFETY AND ENVIRONMENTAL EFFECTS RIL TITLE: PLUTONIUM ACCIDENT CONTAINER PROGRAM - RESEARCH, DESIGN AND DEVELOPMENT.
SPONSORING OFFICE (11: NMSS RES: 5-11 PLUTONIUM CONTAINER RESEARCH PPOJECT MGR2 E. LAHS CERTIFICITION E El_CDTMEtiT3 : RESULTS ARE PEFORTED ON THE DESIGN, DEVELOPMENT AND TEST OF THE PAT-1 PLUTONIUM PACKAGE THAT MEETS THE NEC QUALIFICATION CRITERIA PUBLISHED IN NUREG-0360 "QUALIFICATION CRITERIA TO CERTIFY A PACKAGE FOR AIR TRANSPORT OF PLUTONIUM."
USER DISCUSSION POSITION COMMISSION ACRS PRESS OFFICE MEETING PAPER BRIEFING BRIEFING RELEASE RESULTS PD}J_RIL_sqllVJIJIS EEVIEW HEL D COMPLETED HELD HELP ISSUED IMPLEMENTED OFFICE RESFON51BLE......... hRR SCHEDULED COMPLETION DATE., 09/15/78 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL COMPtETION DATE.....
NRR COMMENTS, k.
GAMMILL - RESPONSE EXPECTED ON 10/03/78.
l 3D
00 ekOGoaM 0FFICE COMME;415 ON P01ENTIAL UTILIZAfl0N CR vaLUE OF RESEARCH RESULTS IN THE REGULATORY PROCESS RIL 8:
34 DATE ISSUED: 05/03/78 RES PROGRAM ELEMENT: FUEL CvCLE SAFETY AND ENVIRONMENTAL EFFECTS RIL TITLE: NUCLEAR DECAY DATA FOR RADICHUCLIDES OCCURRING IN ROUTINE RELEASES FROM NUCLEAR FUEL CYCLE FACILITIES.
$PONSORING OFFICE (5): NRR PES:
5-24 RADI0 BIOLOGY AND DOSIMETRY RESEARCH PROJECT MGR:
J. FOULKE BES_C0trENI$
THIS IS A TABULATION OF NUCLEAR DECAY DATA FOR 240 RADIONUCLIDES WHICH MIGHT BE EXPECTED TO OCCUR IN RoulINE RLLEASES OF EFFLUENTS FRCM NUCLEAR FUEL CYCLE PACILITIES. THIS CAN BE USED BY NRR AS A BASIS FOR ESTIMATION OF RADIATION EXPOSURE TO MAN.
USER DISCUSSION POSITION COMMISSION ACRS PRESS OFFICE NEETING PAPER BRIEFING
- BRIEFING RELEASE RESULTS E05I_P1L_AcfivlILES REVIEW HELD COMPLETED HELD HELD ISSUED IMPLEMENTED 2
OFFICE RLSPONSIBLE......... NRR SCHEDULED COMPLETION DATE.. 09/30/78 UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED UNSCHED ACTUAL COMPLETION DATE.....
NDP COMMENTS, W.
GAM 91LL - RESPONSE EXPECTED ON 10/03/78
(
01 3.0 PROJECTEA NEAQ-TERM RESEARCH I N F RQM A T IS,N LETTERS (TARGET DAVE 3 ACE FISCAL YEAOS)
TEMP.
Mt:1. SUBJECT / TITLE /IFPACT TARGET DATE
_R R G e AND HaME RRG CHAIRMAN
.-1 RELAP 4 MOD 6.
EXTENDS BEST ESTIMATE QTR 1 79 1-16 REFERENCE SYSTEM CODE
- 5. FABIC g,-'
ANALYSIS OF BWR LOCA THRU THE REFLOOD.
3 T-2 MARC STRUCTJRAL ANALY315 PR3 GRAMS.
Q T P,4*. 79 5-19 TRkNSPDPTATION SAFETY W.
LAHL 6/'"
i IHSTRUCTIONS ON THE CAPABILITIES ?ND USE STRUCTURAL ANALYSIS 0F THE MARC PROGRAM HAVE BEEN AND WILL AGAIN BE PELSENsED TN A 5 DAY COURSE TAUGHT BY THE MARC ANALYSIS CORP. STAFF.
T-4 EMERGENCY PiANNING QTR 1 79 6-1 EMERGENCY PLANNING R.
BLOND T-5 INSTITUTIONAL RACWASTE CHARACTERIZATIONS. QTK 1 79 NONE C. BARTLETT L'
RIL WILL BE A REPORT WHICH WILL PRESENT DATA ON SOURCE CHARACTERISTICS AND VOLUMES OF L0W LEVEL WASTE GENERATED IN THE MEDICAL ACADEMIC USES OF RADI0 ISOTOPES. DATA WILL BE USED IN ESTABLISHING STANDARDS FOR P ACK AGING AND DISPOSAL OF LOW LEVEL WASTES.
T-7 EVALUATION OF f!NERAL ATOMIC CODES.
QTR 1 79 2-12 GAS CGOLED REACTOR R. SCHAM3ERGER 41e=4 d3
(*
(V *8 78/
PROVIDES LICENSING WITH BETTER BASIS FOR RESPONSE TO GAC EVALUATIONS OF FCRT ST.
VRAIN (FSV).
T-v REVISION OF NUCLEAR SAFETY GUIDE TID QTR 1 79 NONE D. SQLBERG L'
7016.
THE NUCLEAR SAFETY GUIDE P9ESENTS DATA AND METHODS FOR EVALUATION OF NUCLfAR CRITICALITY FOR A WIDE RANGE OF SYSTEM GEUMETRIES AND MATERIALS.
THE SECOND UPDATE INCCRPORATES MORE RECENT DATA SOURCES AND IMPROVED ANALYSIS METHODS ALLOWING BROADER APPLICATION THAN IN PREVIOUS VERSIONS.
T-3 RELEASE BRENDA.
PROVIDES A GUICK RUNNIN"-
QTR 1 79 2-13 FAST REACTOR SYSTEMS CODES P. M. WOOD 6'.
INDEPENDENT ANALYSIS OF SYSTEM TRANSIENTS.
AND ACCIDENT ANALYSIS T-6 PRELIMINARY REPORT ON WASTE MANAGEMENT QTR 1 79 6-5 HIGH LEVEL WASTE 150L.iTION
- 1. C. CULLINGFORD RISK ASSESSMENT METHODOLOGY DEVELOPMENT
~~T-8 PROMPT BURST ENERGETICS 8 FUEL EGUATION-QTR 1 79 2-6 ACCIDENT ENERGETICS R.13. WRIGHT k
d'3 J I d 4f=A 0F-STATE.
ANALYSIS OF HCDA DAMAGE POTENTIAL 41
PROJECTED CEAQ-TERM QESEARCH INFROMfTICM LETTEQS (CONTINUED) 42 TEMP.
NU"B SUBJECT / TITLE / IMPACT TAPGET DATE PPG 8 AND NiME PRG CHAIRMAN m
T-11 P90CEDUPES FOR 0;TEFMINING CYCLIC QTR 1,
79 3-2 GEO(OGY S SEISMIC CHAR.
J. HARBOUR C"
TRIAXIAL STRENGTH OF SANDS AND CLAY.
SUFPORTS tICENSING REVIEW, T-12 12NTRRADIATED CRACK ARREST.
ADDS CON-QTR t,
79 t-2C VESSEL INTEGRITY C. SERPAN FIELNCE TO LOWER BOUND KIR CURVE.
T-13 SUPER iYSTEM CODE (LOOP).
PEPMITS QTR 1,
79 2-13 FAST REACTOR SYSTEMS CODES P. M. WOOD *
INDEFENDEh! ANALYSIS OF SYSTEMS AND ANALYSIS TRAN5!ENTS.
T-16 SEN5ff!VITY TEST 5 OF AERIAL PHOTOCRAPHIC QTR}P,79 5-22-AERI AL REM 9f E SENSING TECH.
D. BARNA TECHNICUES. DETERMINE THE EFFECTIVENESS CF REMOTE CENSING TECHNIQUES FOR DETECTING VEGETATIVE STRESS IN THE VICINITY OF OPER-ATING SALT WATER COOLING TOWEES.
ESTABLISH SENSITIVITY BY CDPRELATING THE RESULTS OF AERIAL PHOTOGRAPHY WITH CROUND BASED MONI-TOPING PROGR AMS AND WITH THE PPEDICTIONS OF DRIFT DISPERSION MODEt5.
DEVELOP a RECOMMEND APPLIED RFMOTE SENSING PROGRAt15 THAT COULD BE USED ROUTINELY TO REPLACE ALL OR PART OF THE IIELD SURVEYS CLRRENTLY BEING USED TO MONITOR n
VEGETATIVE STRESS AROUND COOLING TCWERS.
(,[bE$avv+/
T-15 ASSES 5 MENT OF AGRICULTURAL LAND IN QTR 2, 79 5-21-50CIDECONOMIC IMPACT 5 er-F*PNA T-16 SIMMER-II RELEASED. REASSESSMENT OF WORK QTR$1. 79 2-14-SIMMER CODE R. CURTIS 4'
f ENERGY TO BE ACCOMMODATED IN HDCA.
T-17 BUILDING WAKE DIFFUSION MODELS. COMPARES QTR 4,
79 6-6-LWP RISK ASSESSMENT J. MURPHY FIELD AND WIND TUNNEL MODELS TO VERIFY LICENSING DATA BASE.
T-18 FISSION GAS PELEASE MODEL VERIFIED. ADDS QTR t,
79 1-9-FI55I0M PRODUCT PELEASE W.
JOHNSTON TRANSIENT FISSION GAS RELEASE QUANTI-FICATION TO FRAP-T ENHANCING ACCIDENT CALCULATIONS.
T-19 INITIAL IN-PILE CCRE MELT RETENTION TESTS. QTR 1,
79 2-2-POST ACCIDENT HEAT REMOVAL R. W. WRIGHT 4/'
~~
QTRAf,79 T-20 GENERIC PE<IEW OF THE IMPACT OF CONSERVA-5-21-50CICECONOMIC IMPACTS
,D.
0 ;; N A-g,~
TION, RATE STRUCTURE & LOAD MANAGEMENT
[
ALT [RN#TIVES 04 THE NEED FOR POWER.
(],
tv /
PREPARE A REFERENCE DOCUMENT WHICH PEVIEWS S SYNTHESIZE 5 RECENT EVIDENCE 8 EVALUATES FUTURE PROSPECTS REGARDING THE IMPACT OF ALTERNATIVE ENERGY CONSERVATION PROGRAMS, RATE STRUCTURE DESIGNS, LOAD flANAGiMENT STRATEGIES, AND CO-GENERATION SYSTEM 5 ON THE NEED FOR FCWER.
l s
l l
~.-,..
43 P'0JECTED NE47-TERM QESEARCH INFDPMATION LETTE75 (CONTICUED)
TEMP.
HM51. SUBJECT / TITLE / IMPACT TARGET DATE RPG e AND NaME RRG CHAIRMAN T-21 L AND USE AND L AND VALUE CHANGES OVER TIME QTR$1,79 5-21-SDC10 ECONOMIC IMPACTS De-FRRNA L__-
O AT NUCLEAR PLANTS.
EXAMINE A DOCUMENT THE SHIFT 5 IN LAND USE THAT 700K PLACE
([. '
OVER TIME, FROM PRE-INSTALLATICH TO THE PRESENT, IN THE VICINITY OF THREE HUCLEAR ELECTRIC GENEPATING PLANTS.
DETERMINE, BUTH SEPARATELY AND JOINTLY, THE NET EFFECTS OF A NUCLEAR PLANI DN REAL PROPERTY VALUES.
DETEEMINE REAL PPOPERTY VALUE CHAhGES IN THE VICINITY OF SEVERAL PROPOSED NUCLE AR GENER ATING PL ANTS WHFRE THE SITE 5 HAVE BEEN ACQUIRED BUT THE FACILITIES NOT YET CONSTRUCTED.
T-22 CABLE COATING MATERI AL TESTS.
CONFIRMS QTR 1,
79 t-23-ELECTRICAL STANDARDS AND R. FEIT DESIGH5 IN CURRENILY OPERATING PLANTS AND FIRE PRGTECTION PORTIONS cr REG GUIDE 1.120.
T-23 RADIATION (SOURCE TERM) SIMULATOR TESTS.
QTR 1,
79 1-25 QUALIFICATION, TESTING, R. FEIT EVALUATION T-24 VALIDATION OF SIMMER NEUTkONICS. PEFMITS QTR7,79 2-11 CRITICAL EXPERIMENTS P. M. WOOD l'
GREATER CONFIDENCE IN MARGIN AVAILABLE IN HCDA ANALYSIS.
T-25 WRAP EM/BW2 - INCORPORATES INTEGRATED QTR 1,
79 NONE NOME AND AUTOMATED IMPROVEMENTS INTO A LICENSING CODE PACKAGE.
T-26 IE APPLICATION OF WASH-1400 METHODOLOGY EARLY 79 6-6 LWR RISK ASSESSMENT J. MURPHY T-27 COERA-DF-ANALYSIS.
PROVIDES NRR WITH QTR 2, 79 t-64-ADVANCED SYSTEM CODF N. ZUBER INDEPENDENT EVALUATION OF LHI PERFORMANCE DURING LOCA.
T-28 CORE MELTDOWN SENSITIVITY STUDY QTR 2, 79 6-6 LWR RISK ASSESSMENT J. MU7PHY T-29 CONSEQUENCE MODEL (INDIVIDUAL SITE QTR 2, 79 6-2 CONSEQUENCE MODELING R. BLOND ASSESSMCNT, FINAL MODEL UPD4TE. CRAC j
USERS MANUAL. AND COMPARISON TO SAFETY
~~
PEVIEW METHODS IN 10 CFR 140) 7-30 LOW FLOOD RATE CORRELATION. MAY REMJVE QTR 2, 79 t-5 REFLOOD HEAT TRANSFER E. H. DAVIDSON TFE CURRENT RESTRICTION IN APPENDIX K OF STEAM COOLING BELOW t INCH /SEC AND REPLACE WITH CCRRELATION.
T-31 PHYSICAL SEPARATION CRITERIA (HORIZ.
QTR 2, 79 t-23 ELECTRICAL STD5 A FIRE PROT. R. FEIT l
CLOSED SPACE).
CONEIRMS PORTIONS OF REG. GUIDE 1.73.
43
=
00 PPDAECVED NEAQ-VEDM RESEARCN INF00MATIRO LETTEQS (CONTINUED)
TEMP.
$p51. SUBJECT / TITLE / IMPACT TAPGET DATE RPG 8 AND NAME PPG CHAIRMAN 7-32 FIELD VALIDATE ELECTROCHEMICAL TEST.
QTR 2, 79 t-12 CORRDSION J. MU$CARA UPDATES PEG. GUIDE TO PRECLUDE SENSITIZED STAINLESS STEEL IN SERVICES.
T-33 CODE RECOMMENDATIONS FOR MULTIPLE INTER-QTR 2.
79 t-20 VESSEL INTEGRITY P.
ALBRECHT ACTING N0ZZLES.
?ROVIDES NEW DESIGN FULES FOR SUCH AS SAFETY INJECTION N0ZZlES.
T-34 ENVIRONMENTAL IODINE SPECIES BEHAVIOR.
QTR 2, 79 S-16 AQUATIC RADIONUCLIDES, P. R. REED STUDY THE PHYSICAL A BIOLCSICAL TRAN5PCRT RADI0 ECOLOGY OF CHEMICAL F0rMS TO RADI0 IODINES RELEASED TO T H E ENV I P ONM".t4 T FROM AN OPERATING NUCLEAR STATION.
DETERMINE THE INFLUENCE OF MET DEPOSITION (9AIN OR DEW) FCR METEOROLOGICAL MODELS A THE 10 PINE-AIR-ORASS-MILK PATHVAY3.
PERFCRM LA30PATORY TESTS TO DETLRMINE IF METHYIUDIDE IS DEPOSITtD ON GRASS UNDER WET DEPOSITION CONDITIONS.
DETEFMINE ENVIRONMENTAL PATOMAYS OF TRITIUM AND CARBON-14 RELE ASED FROM NUCL EAR ST A TIONS.
T-35 MONITCRING OF RADICIODINE FRCM CONTAINMENT QTR 2, 79 S-19 TERRESTRIAL RADI0 ECOLOGY F.
SWANBERG ACCIDENTS.
TO DETEFMINE THE PRACTICALITY OF USING AVAILA5LE CIVIL DE. TENSE INSTRU-MENTS TO ASSESS PUBLIC NEALYN IMPACTS OF AN ACCICENTAL RELF*3E OF RADI0 IODINE FROM NUCLEAR STATIONS.
TO ASSESS INSTRUMENTA-TION CAPABil~fIES (PARTICLE CCLLECTION EFFICIENCV, PARTICULATE CONTRIBUTICNS, AND IP.STRUMENT RELIABILITV) CY EVALUATING A *DPTABLE FIEtD RADIDIODINE COLLECTION SYSTEM AND A DETECTION SYSTEM USING A CDV-700 GM SURVEY INSTRUMENT.
T-36 REACTOR RADWASTE.
FOUR REPORTS WILL QTR 2, 79 S-8 REACTOR EFFLUENT CONTROL D. SOLBERG SUMMARIZE 3 YRS. OPERATING EXPERIENCE AND WASTE TREATMENT SYSTEMS IN USE DF EVAPORATION, FILTRATION AND ION EXCHANGE EQUIPMENT AND SCLID WASTE
~~
MANAGEMENT SYSTEM! IN mUCLEAR POWER PLANTS.
DATA WILL RE USED IN LICENSING EVALUATIONS OF APPLICANTS' EFFLUENT CONTROL SYSTEMS DESIGNS.
T-37 LICUID PATH QTR 2, 79 6-6 LWR RISK ASSESSMENT J. MURPHY 44
45 PPOJECTED NEA7-TECM CESEARCH TNFORMA[JON LETTECS (CCHTINUED)
TEMP.
N ')M B.
SUll[fi/TITLEeIMPACT TARGET DATE RRG e AND NaME ppg CHAIRMAN T-38 REWET COPRELATICN. MAY REMOVE APPF.NDIX K QTR 2. 79 1-3 PWR-BDHT E. H. DAVIDSON RuSTRICTIONS ON 'RETUPN CF NUCLEATE 1-4 BWR-BDHT E. H.
DAVIDSON BOILING' WITH A C0FRELATION.
T-39 ASSESSMENT OF SOURCES OF DOCUMENTATIONAL QTR 2. 79 5-23 OCCUPATIONAL EXPOSURE J.
FOULFE RADIATION EXPOSURE AT NUCLEAR POWER AND PROTECTION PLANTS.
IDENTIFY EkPOSURE REDUCTION TECH-NIQUES AND RECOMMEND DESIGN FEATURES TO KEEP OCCUPATIONAL EXPOSURES AS LOW AS R E ASCN.:BLY ACHIEVABLE. TO BE USED IN ASSESSING THE EFFECTIVENESS OF REGULATORY GUIDE 8.8.
T-40 LOCA-FCCS THERMAL SHOCK ANALY%IS OF THIS QTR 2. 79 C. SERPAN ACCIDENT CLASS INCLUDING EFFECTS OF WARM PRESCPEENING.
T-41 PROGRAM OUTLINE FOR HUMAN FACTORS QTR 2.
79 NONE NONE TRAINING - PF0 VIDE RECOMMENDATIONS TO IE REGAFDING INSPECTION 8 INVESTIGAIION.
T-42 TRANSIENT CHF COFFELATION. NO CHANGE QTR 3.
79 1-3 PWR-BDHT E. H. DAVIDSON IN APPENDIX K BUT MAY REPLACE CUERENT 1-4 ADVANCED SYSTEM CODE E.
H.
DAVIDSON CORRELATION, T-43 LWR LOCA iPAC RELEASED. PROVIDES NRE WITH QTR 3, 79 1-14 ADVANCED SYSTEM CODE N. ZUBER ADVANCED EWR AND FWR COOLANT SYSTEMS CODE TO ESiABLISH MARGINS OF SAFETY.
- -44 VERIFY PELAP 4 MOD 6.
VERIFIES PWR LEST QTR 3, 79 1-17 CODE APPRAISAL L. S. TONG
? STIMATE ANALYSIS THRU RErLOOD.
T-45 MECHANICAL PROPERTIES EEPORT.
PROVIDES QIR 3. 79 1-8 ZIRCALOY CLADDING M. L. PICKLESIMER INDEPENDENTLY VEPIFIED IFKADIATED ZIFCALOY DATA FOR USE TM LICENSING CALCULATIONS.
T-46 SOURCE TERM CORRELATION. CCHFIRMS QIR 3. 79 1-13 FUEL MELT W.
JUHMSTON CONSERVATISM OF FEG. GUIDE ASSUMPTIONS FOR ACCIDENT ANALYSIS.
'T-47 VERIFY FRAPCON - PROVIDES NRR WITH BE QTR 3.
79 1-12 FUEL CODE DEVELOPMENT G. MARING AND EM CAPABILITY TO ANALYZE STEADY STATE FUEL BEHAVIOR.
T-48 8XS TRANSIENT CHF TESTS CCMPLETE. SUPPORT QTR 3. 79 1-4 BWR-BDHT E. H.
DAVIDSUN EXISTING CORRELATION OR FECCMMEND A NEW CORRELATION.
45 l
d 4
Z O
Z W
4 W
L Z
W Z
k W
4 a
Z Z
N M
W A
W 4
4 O
U M
4 w
M W
3 A
7 A
W X
3 W
m M
u m
u V
O D
W e
N e
4 W
6 N
6 9
W en h
O e
Z g
e u
e e
e c
e 4
9 Z
ff M
Z U
3 4
a Q
W Q
D Z
Z 4
d W
M W
W W
Z Z
D Q
Q O
W O
O w
W E
U C
(*
4 A
W L
Q Z
0 W
Q X
E Z
M w
Q e
W M
W 4
M W
O V
W C
W U
W W
O W
O W
4 W
W Q
P Z
wZ Z
W W
OZ Z
40 Z
W W
W E
MD M
Q UM M
Q E
4 MM W
M>
O E
4 Z
Z 4.=
w U
wu >
w y
M A
1 O
L'8 W
Z kW W
W 4
j M
Q DW 4
UM 4
w m
Z Up WO E W
Z 4
4 UO W
6 sk M
W D
C O
E OE WA E
W U
U r-m A
A W
D M
e d
MW W
D N
6 O
NQ N
e NE M
Z N
e d
Z A
6 Z s
i IM t
O e
e i
e N
a og
>6 N
Z e
e i
Z 1
U fc W
C W
d' e
P P
P P
P P
P P
P Q
N N
N W
h h
h h
b b
We W
M M
M M
M M
4 4
f E
O u
a w
w w
W u
w w
w w
w W
4 O
O O
O O
O O
O W
O Ip 4
0 0
WZ W
Z Z
Z
@W mM E
WO D
I C
M 00 M
l
- WMew 6
ew w
WZ Q>
W Z
l C
4Z>
O V
ZQ O
ZD Q
ww WW 46m l
W k>u 60 UQ WO 6
M W
UD aQ4 OU ECO b
D * >
qw UU w>
00 403 OZ W
kWW@>
mW M
O 4
WWW Es AO O
OOwWZW 3
WW WM M4 4Au
<* t 4
- w U eZO k@>WZ wN O
U MM>@
ZWW FMEW ww
$4 WO WO wd>
>>Wa men Os
<@O@WU QW WE UW MZ4 s
W WAZ M
j WU
>4 M@
QM ZZ ME ADOQ eko l
OD kWM Mk NZ MM W@
MEWO WOC (OM kw?*OwQ OW W
OM ZZ
- k E
@ZZ w &
W4m>@4 k>
OW Z
w MW@
wk>
M4 6WA WD U
6 m
M W>
www Qw2
@Q k@
k 04w@
A>
+ w
@Z
>Z M@
OwMM WD.
EDU Ew>
> w kwW D U OWWWWW Z
W QW WW =
3C>EMO eW WW Q
OE NEW 4
w
>.t h
WUW UEW ZZ owe W44 e>mz wZe O
MM Z>
>Q imM M +
F>WOWU Q
Q D@
>M L>M
> Z
- OMMO OMZ
@40 l
O 00A2E4 MW 680 3 QW W4 WOW
@@4@
QwAM W
W
@w2 -
4 MwwMZW AO
@Z>
Q Ep OEU v'
W MM4e
>ZO 4
Z AWOO A
HAkwCW O
WM@
WM Z
Und QQWO mud 202 a
l' O
4%
W>
WZ WD
@O ZEA EMUZ 4
M MUO@
ZM M
D
@wMk@
>M wZh MC MU
- MM 4>O4
- E.. M b (UM eMe>
s b
- WW>Op ZE W3>
k W
OZZ
@gma W
M 4
Q
>@@kZ M
M td wmm W3
>L.Q 4QQ WWOU pu >
- mW>
UQww w
@iW O O W Z 2 W
4 WW wC4 WO V6 Q
M Uw UZWW ZeQ OD WA a>M m2 4
O kau O
w
- 4>Zw ZM4 W W (a rt M
OM NZM M
We>
Zew 34 I
40 4W44 QM Z
ACW i
l UOZ4MHO 40 mWM WW 4Z AEO
@ =EW 44 U
O
= =4
>4EO ww@
Q wp NOZ eas WZ>M Eed Zs U
s O
UZ Am OMM@QDM w
Z ww WEZ E*M wMW@
MWW WUZ W
B U
HQH4Wh>
WQN "4W M
&@W WD@
4@Z
>Ep@
ZO*C MW@3
>4WA>4 ZM D@
D@Q (Z
E>>
WMWM OMEM
@O@W WOM e 30W QD4 EZ AM wwM L
W uw Z M w 1. >
U44>
ZZ4Z
@gGr
'W woA Ow2 Z@
MOV EQU W4WU wwC4 MUZ4 44 6 OWsOWOL Wuw ZMO C4 40U WZM ZZOW W4Wp WW>k EZ>O QWW3mVO 3Ok H3w Um 644 34w eMek
>LO@
mhCW PUm>
As P
O e
N M
e h
W l
En<
c, e
e e
e e
e e
l i
i i
i e
i i
i W q >.
rz I
l l
l
i.
4 M
WE Z 2.
Z w
M U
OO O
W O
Z CE
@ a9 e
(3 Z
W at Z
W QO Q
- tC M
J E
O k
W m3 MM M
ed Z
he O
>=
3 D
6 W
so Z
U Z
O W
O M
W 4 at
=C I*
- E M
W O
aC Z
m3 W
m3
>=
e's QQ
.J Q
=(
J A
W
>=
Z Z
W so CK W
.J Z
53 V
O at D
es D
M e
- D U
D e
"1 Z
N 3
L' ZZ m3 J.
O Q
d N
Em
. W Cif
- I E
Z
.J Ch 3
")
Z "i
M E
WW Q
Z Z
W O
d p
M
>e d
+
+
4 M
W W
W
>=
Q W
Q O
k W
Z Q
A W
Q O
.,J O
.J k
W O
U
=E U
- E Z
O U
w CK Cr et Z
>=
0 D
3*
D CK at U
Z E
l e
>=
W
>=
>=
a re W
.J U
U
>=
U
>=
W Q
t=*
st W
D D
.J W
Q d
>=
Cr CK W
O a4 M
>=
H
>=
Q d
- E Q
.J 4
W W
W W
O O
W W
U W
.J Q
U Cr Z
.J W
Q A
E.a
- J a
W W
w >=
0 J
W g
E 2
E Z
U Z
W at ZZ Q
O
- 1 O
U et O
O 2.
O W
QQ O
U U
.J Z
M Q
J W
at CE 7*
W CQ m3 O
e et W
>=
Z W
M M
E O
e i a
e*
U Q
"E EL D
Q JD M
E WW 6
et E
Q O
E 6
2 at
=
at
- 4 3 W
O W
- e at 4,
ff EB W
W
-d M A m3 g
M N
O M
4 4
>=
N W
6 0
M w
P4 P@
Mf sh
- =
N 03 e=
2 CE I
I I
i 1
eW i e e
i i
e i
1
==
e=
e-M Cr
>g e=
e N
Np
= *
e=
N Z
U fr W
as W
at g
g g
O O
Q N
r=
N N
N N
N N
N g3 m) e3 e3 m3 W
G
>=
=
W d
f f
e W
4 4
4 4
w e=
T O
t.
tv Cr w
w w
w Cr w
W w at ne at er at W
es
>=
>=
>=
>=
>=
>=
>=
>= >=
>=
>=
>=
>=
>=
t-O O
O O
O O
O O O O
O O
O O
I
(' '
WOO Z
- E UWZ O
O W
W as U re A
Z ZM C
d A ht >=
2
- Q Eg W M Cs O LaJ Ed EOW O
6 6 O>
O sg du 32 Q
CK Z
- k M Q
Z O
at M E d
6 **
Z6 O4 W
- O ZM W =
M W
4
.J>=>=
Q D
W W
k CL 6 &*
> ** W U@
'J
>=
WZ CK WUW Z
eo U
U m'
- I e4 O
Z >=
ei W Z*
Cr seJ CK O ZO Of W E W
MW e4
>= A
>=*)
W D CL E W I*
- E N O Cr O re
.J O
Ch @ O A
@ Cg
.J
.d O
- 1 UE Cd
>3 62UZ
>=
W MM O
W W
e4 A
- U WQ O
D CE e o CJ.J Z O Z **
- et Q
U30 Q
ma >
W mf M UZ Em
- O ak at M M O >=
QU O
at M
- W
=t CE W.J Z =C 4
+6
>= 6 Z Z WeV@
WD E
.J O A Cr Z d
&E M
QW W
Z et O
O
@M CE W re OJ WA2 W
M e
> >* >= Q QZ O
WeU W
QQM
=C
.d E C6 0 6WX ZQ.
I^ Z OE 6E e4 O
>O we =E MW
> >=
Q6
.J WW WW D
CL D M e CE W Z
- Q Zw M3
.c u u J Cr e
C e >=
Z<
Z e se hr W
- 1>>=
Z >= Cic I*
WD C
U et et D @
W W
A A2 OW Q@
=
O VO
>2X ag b
.J D WE O at O E O Cs CE.J Ca J
CE U W M
g og 6W
- CE O A 6 we we W
- W
>= W W
.A WO
>cQ M
- > =
CE O CK d AW atMZ6
.J e4 4
WWCK O
Eg CE Z
W CE
+M Z M *=
N
>e W >< Z WW 6 >= LW Z
> 0 sQ O ** Z CW Z Q 54 W >=
U CO6 as D Z p@WU Q
@WO we et > Q ss W CE d W W ** WD
>6 4
WW>
CK O W
- .d af O OJ 2 -d V e
W 4 e4
>= 2 CL ** A
@.J d MO Md at at Z O.d CL Ca.J
>W7 2 et Cr >=
EW e4 CL W
ZE U A1 W
CE M W>0 8
W w
Cs E OE O U Cr Cr D
Cs E
- O O ea M
@6:
M
- *1 6 =t O O JW O
>OZ O Q >= ** *
- O V Cg J W *e Z
W l>'
WW E
O -
@ m3
>= 0 Z W
W
+>
e
\\
- E Q e4 4 2 ad e
Cg 6
> = >
CE Q <
NM
. - D6e >=
Cu C Q he eO Cg O QL W
6 Wo*.
.J d I* >=
I >* Z 0 W >=
WM@@M 6 O **
et 2 C6 hl
.J W m3 WZ Z **
W.d i "I WOD O
to M M W >= 2 W Cs aUD U
WOZ W 0 O==
l>
W
> = > = = =
.J CE M W WW=
Z>ZZZ d >= >
OZ ZMU M
W6M Z >= >= 0 O EO I" Z U et 2
>=
>= Q WQ v'
u >=
at W 98W OZJ OO Cr Cg M Q O.J Z **
W W at.J CE O e4
\\
2 at e-*
O W I*
e : >e
.J 7", E E E EW4 O==
6 aC Q Cr Z MD
@W>
JO w>4
>=0>=
' A "> U esU>W Cg J e=
W :C w at =7. t CE >
IUW U
NWW OO UUU
> = =
QU
>* =C U
O CE U L ** W Ct
>= o.e
- 4 Cr we CE
= d # =C W af U ** U M
">A WW U ** W
>=M
' e4
> CK Q L =a C. W at CE E CE M c3 D + o o es we at #
e4 Q 6 et I*
A Q Eg Wd@
M>=
e=
6 at
- "*j >= 0 W@UD 6 et
.J O 3 >= D W =4
>e
>= M.J X Z *C 0
CK d Cr Z ** ** C6 >=
s1
.J z w >=
Z o 3A = CW U Z o eoQ x.J e Cr A
>e O
>W MMI m **
O*Q Cr E e 24 WOO 2WDW
>= =a
>etWOW DOU M =C OWW W
N ** 6 0Z ZZW EM IM3 WOW 61 EUw M @ U (*
b > Cd O
- >= 0 6>
DDZ WW W 3 *E
> U a=
A e
O e
N
>'l 4
P.
e3 e
o
==
N Er e e
e a
a
~
e.
e.
W Z1 e i
a e
i e
a a
e i
e t
i a
>= T 3 >=
>=
>=
>=
>=
>=
>=
>= >
>=
>=
- =
>=
>=
l l'
l l
l l1
]i l
8<
N A
N T
M G
O H
P N
T N
C N
R Y
I O
C S
A C
E A
E H
A T
I N
P I
R P
M P
T T
T H
B H
R B
B R
R R
I I
I C
A O
E A
L E
A U
E E
E 5
F J
S F
A S
F M
F F
F E
G M
P O
P L
5 W
C 5
R C
W J
R R
R N
)
D E
D D
U N
N N
D A
A I
E N
G T
D A
5 S
N 8
N O
D D
I 4
O C
E T
R R
T C
C N
A A
S
(
M Y
E Y
Y N
E D
D E
E T
D T
T A
M N
N T
S L
T I
O I
I L
S A
A R
A S
R C
R R
L S
T T
N E
S Y
G G
G I
E S
S O
T I
S E
T E
E E
S I
T A
T N
T T
V S
LN LH T
E E
R E
T N
E N
N R
M P
C L
I M
I I
U CI CI C
A P
N E
N S
K IT IT I
N N
A E
M L
I L
L S
S RC RC F
O R
E A
E E
EC I
TE TE IN I
D E
E L
S T
S S
SI R
N D
F E
5 N
S S
A O
E U
E O
E E
OS R
LR LR UT M
C R
F V
C V
V NO W
EF EF QA
?
e N
L U
O 7
6 3
0 5
0 0
8G 3E 3E 5L E
F G
1 1
1 2
1 2
2 2A 6
2R 2R 2A N
N P
I I
- I
- V O
I P
1 1
1 1
1 1
1 1D 6
1 F 1F 1E N
N C
R E
A T
E A
0 0
0 0
0 0
0 0
0 0
0 0
0 S
D 8
8 3
8 8
3 3
8 8
8 8
8 8
E P
T E
1 1
1 1
1 1
1 1
1 1
1 1
2 M
G r
R R
R R
R R
R R
R R
R R
R E
A T
T T
T T
T T
T T
T T
T T
T T
Q A
Q Q
Q Q
Q Q
2 C
Q Q
Q Q
T R
A SD EN A
D E
S DA N
DT S
I N
NES E
SN VE G
D GSE M
NN SI S
OG I
E CAT Aa HW PA I
E RN LG S.
T E
E GO T
ST C
H TI D
.RE C
SSL P
E J
NNI IM TO FC R
LTE ANA RA O
OIW T
FVAO C
F L
C GT OET H
OL P
I N
OOET FC
)
.A IDNE NN CCN C
TE P
T5D E
RT L
.S T
ENAF IE IE I
CR A1L I
SPSE E -
A EE EI ROLS OE T
I A
N EN L
R N
E L
N EhO E
O RI RcW V
I 3I N
EI C
E N UY At FVC NU U A A
T SS 0TH O
UWNI LTA T%
i LCRN OQ CT
. V A
EE CAT C
Q OL IAl S
KM EAUF ME LCNS E
U TS LI EYIP TEF N
C*
SCSU R
AAIN L
S L
S C ER S
NBCA U
G TI RT ESEF TEW MEI E
V O
A FRN U
E PA P
FOO CS9Y
- OI E5
- E DAD AII T
CA S
RT P
NCS set.
M OA I
A I
DOEi5 V
A FR VI RVLA GE DACT S
E CD NPP5T RSR EP Rc UOA E
.R OM N T
N e
RER H
FE G
S IG E
THA 7E A
ON UIE P
Uc 5RVT S
L TP D
CC N
Y N
E E
OEH E
N I
S L
I T
T M DO Y
.V L
AC IS I
ANC OC TSISP RE T
EEN R
.Y" LR4 MNNO H E
.T 5
OOC S N
D EA T
EIC M
INTN I
N SE IFO PELF'E REL DON EII I
O O
5R
/
H A
4C IIT1N E
I M
1E Y r.H T
G O
BSI5I EC5 ES EEA CDATI V
C ARAS 0
T 3P C
E FN!
PL AOTDT TIE OSS T5U TEPIT OTI UEUA N
C G
O l
C C U R. F E
RUL LPLE I
E N
A IE0 A
BLNLA AVV RET A
L AOCI PP ASAL T
T I
TD f RSR La OFAPO POR DRN DRA 2
EIH EW RXUXL PPU YPE POV ERCMI MNO VIVE X
E G
AN 1
VFT RF PEOET UPC H(M UFE RPAIL IIT EDEE E
D A
DA PB 3
4 5
6 7
8 9
0 1
2 3
4 5
MM 7
7 7
7 7
7 7
8 8
2 8
3 8
EU TN T
T T
T T
T T
T T
T T
T T
~
7 ll ll l
C9 PROJECTED NEA7-TECM RESEAPCN INFO "ATION LETTJP5 (C00TINUED)
TEMP.
EM5E. Sf)PJECT/ TITLE / IMPACT TA*CET DAT_E PPG # AND NAME RPO CMAIRMAN T-86 INCORPORATE IMPROVED UT IN CODE.
IMPROVED QTR 2. 8) 1-21 NON-DESTRUCTIVE EXAMINATION J. MUSCARA CCNFIDENCE IN EVALUATION OF FLOW SIG-NIFIOANCE FROM ACCUPATE FLOW SHAPE AND SIZE.
T-87 VALIDATE ACOUSTICS EMISSICM FtAW C07 RELA-QTR 2. 80 1-21 NON-DESTRUCTIVE EXAMINATION J. MUSCARA TICN.
VALICATES THE DETECTION.
IDENTIFICATICH & ELIMINATION OF FLAW 5 DUP!NG WELDING - LATER EVALUATION NOT NEEDED.
T-88 COMMIX CODE (TWO-PHASE).
REASSESSMENT QTR 2. 80 2-13 FAST REACTOR SYSTEMS CODES P.M. WOOD OF COOLABILITY OF SUBA55EMBLY UNDER AND ACCIDENT ANALYSIS NATURAL CONVECTICN.
T-89 CREEP FATIGUE INTERACTION TESTS AND QTR 2. 80 2-3 PRIMARY SYSTEM INTEGRITY T.
J. WALKER C000.
VERIFIES DESIGN PULES FOR LONG T EEN PRIruRY SYSTEM INTEGRITY.
T-9d CONTAINMENT PRE 55UPE PULSE ANALYSIS QTR 2. 80 2-12 GAS COOLED REACTOR R.
D. SCHAMBERGER MC1M005.
CONCL U5!ONS MAY EF FECT THE LICENSING F051 TION ON DEPRESSURIZATION ACCIDENIS.
T-91 FRAGILITY LIMITS FOR ELECTRICAL E9UIPMENT. QTR 3. 80 3-19 PLANT STRUCTURES J.
RICHARDSON MAY BE BASIS TOR REG. GUIDE OR EFFECT DESIGN CRITEPIA.
T-92 8X8 BUNDLE TESTS.
CONFIRMS ABILITY QTR 3. 80 1-8 ZIRCALOY CLADDING M.
L. PICKLESIMER 70 LIMIT rFCPA0AeION AND MAINTAIN C00LABLE GEOMETRY.
T-93
- YCLIC CRACK GFDWTH RATE EVALUATIJN.
OTR 4 80 1-20 VESSEL INTEGRITf C. SERPAN t:FW CURVE FOR ASMC XI CRACK GPOWTH RATE.
T-94 RErCMMEND CPTIMIZED PIPING SYSTEM QTR 4, 80 1-20 VESSEL INTEGRITY P. ALBRECHT CL31GN.
GUIDELTWE5 FOR SAFER PIPING SV5ffMS.
T-95 SM s t l CLUSTER TESTS.
CONFIRMS ABILITY QTR 4 80 1-10 P4F EXPERIMENTAL PROGRAMS R.
VAN HOUTEN 10 LIMIT PF0PAGATION AND MAINTAIN C00 TABLE Gt0 METRY.
T-96 SAFE 1Y RELATFD OrtRATOR ACTING CRITERIA.
QTR '. 80 1-24 HUMAN ENGINEERING W. 5. FARMER MAY IMPACT ENGINEERED SAFETY SYSTEM 5 T-97 UR At4IUM OXICE AEF050L TESTS (NSPP).
RE-QTR 4. 80 2-9-LARGE AFR050L TRANSPORT M. SILBERBERG ASSESSMENT OF AEE050* TRAN5 PORT RELATED TESTS MARGINS IN EVALUATION MODEL FOR SITING.
u,-
w.
i l
4 l
DISTTilBUTION ogg,c, No.of Copees Emecistsve Dweetor for Operassons 5
Office of Nasclear Rescsee Reps 4ations 31 Office of Nasclear " ; " ^__i Reneerch 25 Office of Nasciesr Rhetorial Setety and Solopsards 31 Ofsees of scandenis en i+-- _ ;
25 I
Office of :.. :::- and Enforconsent 25 t
l Office of "-. _ ^ ased Proyani Analyses 10 l
l l
!-.. -, -.. - -..-.. - - - ~__,-.
-,.m_.__.-
- _ _,___.__ -,,_ _ _._ _ _.. _._ _,-._ _ ___ ___.__ _=_.___._ ____ _
r l
uNif to s-ovts NUCLEAR RE CVLATOMY CCVVISSION W ASHINGTON,0. C. 20S%l yogT Aot Amn r att P AIO u 6 NWCLE AR NEGUL Atomy Of f eCI AL SVilNE15 couuissiom L_ Q PE N ALT Y F OR PmlV ATE USE.$300 J
l r
I I