ML19296B156
| ML19296B156 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 12/07/1979 |
| From: | NUTECH ENGINEERS, INC. |
| To: | |
| Shared Package | |
| ML19296B150 | List: |
| References | |
| TASK-03-05.A, TASK-3-5.A, TASK-RR NUDOCS 8002200181 | |
| Download: ML19296B156 (36) | |
Text
.
BIG ROCK POINT PIPE BREAK STATUS REPORT SEP TOPIC III-5.A PREPARED FOR C0flSUMERS POWER COMPAliY DECEMBER 7, 1979 g j nutech soo22oo
BIG ROCK P0lf1T PIPE BREAK STATUS REPORT SEP TOPIC III-5.A ITEMS TO BE COVERED e
OVERVIEW e
DESCRIPTION OF APPROACH USED e
STATUS OF ANALYSIS FEEDi!ATER PIPING BREAKS MAlfi STEAM PIPING BREAKS RECIRCULATION PIPING BREAKS e
POTEtlTIAL SOLUTIONS TO CONCERNS e
SUMMARY
nutech CONSUMERS PONER COMPANY December 7, 1979
BIG ROCK P0lflT PIPE BREAK STATUS REPORT SEP TOPIC III-5.A OVERVIEW e
SEP PLANTS TO BE REVIEWED RELATIVE TO CURRENT NRC CRITERIA e
THREE NRC OPTI0lls FOR BREAK SELECTI0tl EECHANISTIC SIMPLIFIED MECHAilISTIC EFFECTS ORIENTED e
TECHillCAL APPROACH DICTATED BY INFORIMTION AVAILABLE e
GENERAL PLANT CONFIGUPATION e
RECIRCULATION PUMP ROOM gllRi?Joi!?,co"P^x' Med
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11utech CONSUMERS POWER COMPA','Y
_3 December 7, 1979
t BIG ROCK P0 lilt PIPE BREAK STATUS REPORT SEP TOPIC III-5 A TECHNICAL APPROACH e
EFFECTS ORIENTED METHOD CHOSEN TO SCOPE PROBLEM e
SIMPLIFIED AtlALYTICAL METHODS USED C0!lSERVATIVE P I t! P O I N T C O I! C E R!; S SAFETY TARGETS DETEPJil ED e
PIPE WHIP f!RC CRITERIA FOLLOWED SII',PLE DYi!AMIC Ai!ALYSIS o
STRUCTURAL IMPACT Af!ALYSIS ENERGY CollSERVATION ELASTIC-PLASTIC ANALYSIS e
JET IMPIt1GEMENT AflSI 176 SIMPLIFIED TECHllIQUES mtech CONSUMERS POWER CUMPANY December 7, 1979
BIG ROCK P0Illi PIPE BREAK STATUS REPORT SEP TOPIC III-5,A STATUS OF RECIRCULATIOll PUMP ROOM PIPIliG BREAK AtlALYSIS e
LARGE NUMBER OF POSTULATED BREAKS C0ilSIDERED 82 RECIRCULATION SYSTEli BREAKS 10 MAlli STEAM SYSTEM EREAKS 8
FEEDUATER SYSTER BREAKS
- 5100 OTHER BREAKS Il1 I" ALLER PIPII!G e
A f! UMBER OF C0tlCERiis IDE;;TIFIED RECIRCULATI0tl PIPli1G BREAKS FEEDWATER PIPIl!G BREAKS nutech CONSUMERS POWER COMPANY December 7, 1979
BIG ROCK P0llii PIPE BREAK STATUS REPORT SEP TOPIC III-5.A STATUS OF RECIRCULATI0tl PUF,P ROOM PIPIIG BREAK At!ALYSIS (cot 4Tinusny e
MAIN STEAM PIPING
[10 SIGNIFICANT PROELE"S IEE TO MAlil STEAM BREAKS FEEDWATER PIPIflG FEElidATER JETS iMY C.;.' SE :;:'_L'RE OF E F.E R G Ei! C Y C 0: 3 Ei; S E.: (E::
. IFII'G FEEDWATER JETS iMY FAIL STEXi DRUM LEVEL INSTRUMEllTATION e
STATUS OF SMALLER PIPI.1G BPE;:-:S PROBLEMS GENERALLY Ei;'/ELr.:EJ BY LARGER PIPE BREAKS nutech CONSUMERS POWER COMPANY December 7, 1979
BIG ROCK POINT PIPE BREAK STATUS REPORT SEP TOPIC III-5.A STATUS OF RECIRCULATION PUMP ROOM PIPING BREAK ANALYSIS (CONTINUED) o RECIRCULATION PIPING HIGH PIPE WHIP VELOCITIES PREDICTED SIMPLE " EFFECTS ORIENTED" APPROACH USED TO DATE IDENTIFIES PROBLEMS WITH FOLLOWING SAFETY RELATED EQUIPMENT ALL STRUCTURAL STEEL TARGETS ALL CABLE TRAYS INSTRUMENT AND CORE SPRAY PIPING OTHER SAFETY RELATED PIPING AND EQUIPMENT STRUCTURAL INTEGRITY OF RECIRCULATION PUMP ROOM WALLS DEMONSTRATED
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BIG ROCK POIllT PIPE BREAK STATUS REPORT StP TOPIC III-5.A STATUS OF RECIRCULATI0tl PUMP ROOM PIPIllG BREAK AtlALYSIS (continued) e LIST OF TARGETS FOR LARGE RECIRCULATIO.'l SYSTEM LOCA's PIPIi!G CORE SPRAY 4-CSS-101 REACTOR VEiiT TO STEAM DRUM 1.5-i:SS-117 MAlf; STEA.'l PIPIrlG 12-MSS-105 FEEDWATER PIPIllG 10-R.5-201 IflSTPUMEfiT lit 1ES REACTOR LEVEL PIPING Af:D TU31!!G STEAM DRUM LEVEL PIPIflG At!D TUBI!;G ELECTRICAL CABLE TRAYS TF13, TF14, TF15, SB06, SE07, SB10, Sell, AtiD SB12 STRUCTURES STEEL AT ELEVATION 597' AtiD 619' RECIRCULATI0fl ROOM WALLS
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CONSUMERS POWER COMPANY December 7, 1979
BIG ROCK POII;T PIPE BREAK STATUS P.EPORT SEP TOPIC III-5 A POTEilTIAL SOLUTI0iiS TO PIPE BREAK CC !CERils e
ISI PLUS LEAK DETECTI0il e
STRUCTURAL CHAilGES e
RER00TIllG OF ESSEliTIAL PIPI:lG A::D RELOCit-TIO:: 0F ESSEilTIAL E]UIF:iEi;T e
l~,ECHA:;ISTIC APPRCACH nutech CONSUMERS POWER COMPANY December 7, 1979
BIG ROCK P0 lilt PIPE BREAK STATUS REPORT SEP TOPIC III-5,A ISI PLUS LEAK DETECTION o
AUGMENTED ISI (ACCELERATED SCHEDULE PLUS IMPROVED TECHilIGUE) e LOCAL ACOUSTIC Ei'.ISSIO!1 LEAK DETECTORS e
FRACTURE MECHAMICS E\\.'ALUATION nutech CONSUhlERS POWER COMPANY December 7, 1979
BIG ROCK POINT PIPE BREAK STATUS REPORT SEP TOPIC III-5.A ISI PLUS LEAK DETECTION e
PR0's UTILIZES HARDWARE AND TECHNOLOGY ALREADY DEMONSTRATED IN NUCLEAR POWER PLAi1T APPLICATIONS PERMITS EARLIER IMPLEMENTATION THAN MAJOR HARDWARE MODIFICATIONS PREVENTATIVE - REDUCES PIPE BREAK PROBA-BILITY RATHER THAN JUST MITIGATIllG C0f1 SEQUENCES NO ADVERSE IMPACT ON i;0RMAL OPERATIO:lAL PIPING SYSTEM STRESSES COST EFFECTIVE - MINIMIZES HARDi.ARE COSTS, PLANT OUTAGE TIME e
CON's UNCERTAINTIES /CONSERVATISFE IN FRACTURE MECHANICS ANALYSIS MAY LEAD TO HIGH INSPECTION FREQUENCIES HIGHLY SENSITIVE LEAK DETECTION SCHEME, MAY RES' LT IN UNNECESSARY PLANT SHUTDOWils J
CONSUMERS POWER COMPANY nutech December /, 1979
BIG ROCK P0Illi PIPE BREAK STATUS REPORT SEP TOPIC III-5,A STRUCTURAL CHANGES e
SEVERAL PIPE WHIP RESTRAlfli CONCEPTS IDENTIFIED STRUT RESTRAlllTS U-BOLT RESTRAINTS STRUCTURAL STEEL RESTRAlilTS o
JET BARRIERS FOR CABLE TRAYS e
PROTECT ECCS RECIRCULATICH STRAI!'lER e
PROTECT CONTAINMENT ISOLATI0ii VALVE nutech "EllPJ?!?9
BIG ROCK P0 lilt PIPE BREAK STATUS REPORT SEP TOPIC III-5.A STRUCTURAL CHANGES (CONTinuso) e PR0's PROVIDE DIRECT PROTECTI0i!
a COII's DIFFICULT DESIGil PROBLEMS DUE TO PIPING CONFIGi RATIO!!
J liiSTALLATI0ii DIFFICULT DUE TO ACCESS P..0BLEMS PADIATI0f! LEVELS WILL RESULT Ill HIGH DOSAGES FOR WORK FORCE MAY I!! CREASE PROBABILITY OF PIPE BREAK DUE TO STRESS RISERS A!;D R DUCED PIPlilG FLEXIBILITY MAY Ii!TERFERE l!ITH !!ORMAL ISI REQUIRES SIGNIFICAili PLA!!T GUTAGE CONSUMERS P0h'ER COMPANY
- nutech December 7, 1979
BIG ROCK Politi PIPE EREAK STATUS REPORT SEP TOPIC III-5.A REROUTING AND RELOCATION e
ROUTE CORE SPRAY PIPIllG OUTSIDE OF RECIRCU-LATION PUNP ROOM TO MAXIMUM EXTEilT POSSIBLE PROTECT PORTION OF CORE SPRAY PIPING IN ROOM o
MOVE ECCS SUCTI0i' STRAIiER o
MOVE SAFEIY RELATED CABLES o
RELOCATE EilTAli'3ENT ISOLATI0i! VALVE nutech CONSUMERS POWER COMPANY December., 1979
BIG ROCK PolilT PIPE BREAK STATUS REPORT SEP TOPIC III-5,A REROUTIllG AIID RELOCATION (conTinusa) e PR0'S MAINTAltlS POSITIVE SHUTDOWil CAPABILITY FOR PLANT LESS DIFFICULT THAN STRUCTURAL CHANGES o
CON'S WILL NOT REDUCE PROBABILITY OF PIPE BREAK WILL RESULT If! HIGH DOSE RATES FOR ',,'ORK FORCE REQUIEES SIGNIFICANT FLA1T GUTAGE 85!""!?SJ?!",c"""
nutech
BIG ROCK POIflT PIPE BREAK STATUS REPORT SEP TOPIC III-5 A MECHANISTIC APPROACH e
PERFORM STRESS ANALYSIS VERIFY LOW STRESS LEVELS Ill PIPING e
SELECT BREAKS ONLY AT TERMINAL ENDS AtlD BRANCHES, IF JUSTIFIED c ""^*' gxig":sfo;;ye Mah
BIG ROCK PolilT PIPE BREAK STATUS REPORT SEP TOPIC III-5.A MECHANISTIC APPROACH (CONTINUED) e PR0'S HIGH LIKELIHOOD THAT STRESSES llILL BE LOW MINIMIZES PLANT MODIFICATIONS CAN BE IMPLEMENTED FASTER THAI! MAJOR PLAi1T MODIFICATI0ils a
C0il'S REOUIRES SEISMIC DESIGil Di.T.. EEliiG GENERATED O!! A!iOTHER SEP TOPIC -
POTEilTIAL TO EXTEND COMPLETI0t! 0F THIS TCPIC i9Y REQUIRE SOME CHA!!GES li! CURREilT I!RC BREAK SELECTIGil CRITERIA nutech CONSUMERS POWER COMPANY December 7, 1979
BIG ROCK P0lflT PIPE BREAK STATUS REPORT SEP TOPIC III-5 A
SUMMARY
e RECIRCULATI0il PUMP ROOM EFFORT COMPLETE e
PIPE BREAK PROTECTI0il IS ilEEDED Iil RECIRCU-LATI0t! PUMP ROOM e
RESOLUTI0i! 0F C0i!CERi;S F 0CEEDIliG WITHlii SEP ?ROGRAfl e
ISI FLUS LEAK DETECTIOi; iiAS EEEli SELECTED AS MOST DESIRABLE SOLUTI0f!
o EVALUATI0i! 0F OTHER AREAS II; SIDE C0iiTAli1 MENT IS C0ilTli!UIiiG s
nutech C0"SUMERS POWER COMPANY December 7, 1979
9 ATTACHMENT 3
BIG ROCK P0 lilt PIPE BREAK STATUS REPORT SEP TOPIC III-5,A AUGMENTED ISI PLUS LEAK DETECTION AS A SOLUTION e
OVERVIEW e
AUGMEllTED ISI ACCELERATED SCHEDULE IMPROVED TECHNIQUE o
LEAK DETECTIO!!
LOCAL ACOUSTIC EMISSI0il SENSORS o
FRACTURE MECHANICS EVALUATI0il CRACK PROPAGATI0il ANALYSIS CRITICAL CRACK SIZE DETER.'!It!ATIO?!
COMSUMERS POWER COMPANY December 7, 1979 r1 Lite 3C Il
BIG ROCK POINT FIPE BREAK STATUS REPORT SEP TOPIC III-5,A
,d 3
OVERVIEW 0F PROPOSED
-t ISI/ LEAK DETECTI0tl APPROACH TO s
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BIG ROCK POIflT PIPE BREAK STATUS REPORT SEP TOPIC III-5.A AUGMENTED ISI e
ACCELERATED SCHEDULE CIRCUMFEREllTIAL PIPE BREAK LOCATIONS ALREADY INCLUDED IN ISI PROGRAM INCREASE EXAMINATIO!! FREQUEllCY TO THAT DETERMIt!ED BY FRACTURE fiECHAtllCS AllALYSIS IMPROVED TECHilICUE*
DUAL ELEMENT, FOCUSED BEA:i SEARCH UllIT s
PROPER TRAtlSDUCER FREQUEilCY SELECTION MAGiiETIC TAPE RECORDIi!G OF UT DATA FOR EVALUATIOil IN MORE FAVORAELE EilVIRON-MENT DEVELOPMEllTAL TECHilIQUES lilV0LVIi!G OTHER SIGi!AL CHARACTERISTICS BESIDES AMPLITUDE
REFERENCE:
NUREG-0531, " Investigation and Evaluation of Stress-Corrosion Cracking in Piping of Light Water Reactor Plants", NRC Pipe Crack Study Group, February, 1979.
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Sensitized BWR Piping g.
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J BIG ROCK POINT PIPE BREAK STATUS REPORT SEP TOPIC III-5.A LEAK DETECTI0tl e
TECHNIQUE i3 ACOUSTIC EMISSION TRANDUCERS LOCATED 3l' f
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AT PIPE BREAK LOCATION (
10 FEET RANGE)
SET ALARiiS FOR ORDER OF MAGNITUDC IllCREASE IN BACKGROU!!D il0ISE LEVEL (INTEGRATED OVER SUSTAli;ED TI:E PERIOD)
DEI':::STRATED TO BE HIGHLY SEi:SITIVE LEAK DETECTOR HISTORY OF NUCLEAR POWER PLAilT APPLI-CATIONS
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I AC0USTIC EiilSSION LEAK DETECT 10tl SYSTEM 7 j DEMONSTRATION TEST AtlD RESULTS
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REFERENCE:
GOPAL, RU, " ACOUSTIC FDNITORING SYSTBIS TO ASSURE Ih'EGRITY OF NUCLEAR POWER PL4TS", FDNITORING STRUCIURAL IhTEGRITY BY ACOUSTIC DlISSION, ASTM STP S71, A>!ERICAN SOCIETY FOR TESTING AND MATERIALS, 197S, PP. 200-220.
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BIG ROCK POIIli PIPE BREAK STATUS REPORT SEP TOPIC III-5,A FRACTURE MECHAflICS EVALUATI0il o
STRESS CORR 0SI0il CRACK PROPAGATI0fl AllALYSIS l
(AUSTENITIC PIPIf1G)
CONSIDERS SUSTAlt!ED PRIi!ARY, SEC0t!DARY AND RESIDUAL STRESSES CORRELATE RATE OF CRACK GR0'lTH WITH SUSTAlllED LEFM STRESS INTEiiSITY FACTOR SIMILAR TO APPROACH USED TO SET liiSPECTI0fl I!!TERVALS FOR DUA;;E ARi:0LD REPLACEMEfiT SAFE-ENDS AND Ii! RECENT EPRI SPCUS0 RED WORK e
CORROSIOil FATIGUE CRACK PROPAGATI0il AilALYSIS (FERRITIC PIPIflG)
C0liSIDERS CYCLIC PRII'ARY AliD SEC0ilDARY STRESSES CORRELATE RATE OF CRACK GROWTH WITH CYCLIC LEFM STRESS II'TEi!SITY FACTOR SIMILAR TO APPROACH USED TO SET Ii;SPECTION INTERVALS Ill BWR FEEDt!ATER [10ZZLES e
CRITICAL CRACK SIZE DETERillilATI0il IlET SECTI0fl COLLAPSE APPROACH FOR DUCTILE MATERIAL (CONFIRMED BY EXPERIMEilT)
APPLY DESIGN SAFETY MARGlilS nutech DETERMIllATION OF LEFM STRESS INTENSITY FACTORS FOR VARI 0llS TilR01]Gil-WALL STRESS DISlRil'Ilfltitl5 IN PIPING o- : Ao + A X + A2X2+AX3 g
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Buchalet and W. 11. Bamford, " Stress IntensRy Factor Solutions for Continuous Surface Flaws In Reactor Pressure Vessels" ASTM-STP-590, 1975.
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1 iluTECH STRESS CORROSION CRACK GROWTH RATE RELATIONS FOR AUSTENITIC STEELS lii BWR ENVIR0i4MEi!T In Reactor Tests in 0.2 pom O, (Dresden 1)
A - SENS. S. S.
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REFERENCE:
EPRI Report NP-1163, "The Influence of Crack Growth Kinetics on the Integrity of Sensitized BWR Piping Welds", dated September, 1979.
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1MP_MG IUIENT-DESIfdL 655!)
EUbU
" U
~
/
.i g- '
0.2 n
El,0 Il 2 c q s:
/_
h tW,
-f- -.
7 0.1
- -s
~~-
Gy;gg g
gg c =-
M@zi; 3
0 1.0 2.0 3.0 4.0 C
TIME., YEARS e-t=
(D
REFERENCE:
Docket No. 50-331, "Duane Arnold Energy Center Recirculation
@2j5 O
Inlet Safe-End Repair Program, Supplement", Iowa Electric Light 4 Power
[j =,
z 7
Company, dated Februacy 22, 1979.
CORROSI0il FATIGUE CRACK GROWTH RATE RELATIONS FOR FERRITIC STEELS Ill IIATER REACTOR EINIR0ilMENTS 10~3 ASME - SECT xi m f b
BEST FIT CURVE ca/dN = 0.0707 m 10'9 K,tf 3.726 UPPER BOUND CURVE ca/dN = 0.3795 a 3o-9 KH 1728
/
of a om j
O
/
ao QQ Q
jaD O O
O
,,s
/j c0 00 3
D3 i
/
la" a %
0 h
5B
=
D E
O oO f
,O O
8 6
1 kP
[
5
/O "O
ic-5
/
o
/CO 3 h3 o h
W DATA O Low a io.15 < R < o :s>
(PWR ENVI C HIGH R (0 63 < R < 0 70) 0' O
g I O 'cw a in - o c5)
GE OATA U
(BWR ENV)
Q HIGH A (R = 0.78)
/
Ga l
^
I o.
/
/
10 2
3 10' 10 10 F.FFECTIVE STRESS INTENSITY F ACTORY (kas MI j
K,ff = Kmas (1 R)O 5, ggfgj, p,0.5
REFERENCE:
GE Report NEDO-21821, "BWR Feedwater Nozzle /Sparger Final Report", June, 1978.
Mutech ANALYTICALLY DERIVED CRACK GRONTH CURVES VET, lD DATA FOR BWR FEEDWATER NOCLES 1.7 OCSERVED CRACK DEPTHS:
d BORE REGION O BLEND R ADIUS h PLANTS WITH PARTIAL FIXES y,$
(WE LDEO SPARGER. INTER.
O FERENCE FIT SPARGERS. OR NINE MILE HIGH FERRITE CLADOING)
POINT BEST ESTi.t ATE a
1.4 AN ALYTIC A L CURVE (BORE REGIOnt 1.3 UPPER BOUND AN ALYTICAL CURVE (BORE REGION) 1.1 OVE RSEAS BWR
=
1.0 -
I
.s 3
C9-I O
C.E -
=
PI LG Rl'.1 b
1 BEST ESil*.' ATE HU TBAY 0.7 ANALYTICA L CURVE O
o*
J (BLE*.D R A0iUS)
I OYSTER CREEK O O6 J
l a.*l L LS TO N E o S r--
MONTiCE llc O O oRESoEN.2
/
@,U^
O QUAD CITIES 1 T ES-2
/
PEACH SOTTOM 2 O o
OoPESsE*; 3 O
v E R '.*O N T 0.3 o2 COOPER h OVE RSE AS 0.1 BWAS BROWNS FERRY.1 PEACH Q
OVERSEAS BOTTOM 3 WAS B R OWNS F E R R Y.2 AT
\\^' CH 1 l I
I I
'^
I I
I I
^ ' '
o v
v v,
0 70 40 60 to 100 120 NUMBER OF STARTUP/ SHUT 00WN CYCLES
REFERENCE:
GE Report NEDO-21821, "BWR Feedwater NO::zle/
bparger Tinal Report", June, 197S.
nutech BIG ROCK P0 lilt PIPE BREAK STATUS REPORT SEP TOPIC III-5.A DETERMINATI0i1 0F CRITICAL FLAW SIZE e
FOR THE DUCTILE MATERIALS USED Ill flUCLEAR POWER PLANT PIPlilG, THE FOLLOWI!!G "STREi;GTH OF fiATERIALS" AP-PROACH HAS BEEM DEM0ilSTRATED* TO PROVIDE A HIGHLY ACCURATE MEAilS OF ESTINATIi!G CRITICAL FLAW SIZE:
ASSUME CRACKS SIMPLY REDUCE LOAD BEARIi!G AREA AllD SECTIOil EODULUS C0ilPUTE PLASTIC LIP.IT LOAD OF Pl?E USIi!G " FLOW STRESS" = (o
+
ut s ), 2 ys DETERMI!;E FLW SIZE FDP '.HCh RE LIMIT LOAD EQUALS ThE SUM OF ALL FR:."7'
- PLIED LOADS (IliCLUDIi;G SEISMIC)
APPLY APPROPRIATE DESIGt! MARGli:S
- REFEREi!CES:
- 1. KA!!illi!Eil, M.F., BROEK, D.,
ET AL, "."ECHAi!ICAL FRACTURE PREDICTI0i1S FOR SEflSITIZED STAliiLESS STEEL PIPIi1G WITH CIRCUMFEREi!TIAL CRACKS," BATTELLE COLUMBUS LABORATORIES, FINAL REPORT TO ELECTRIC POWER RESEARCH IllSTITUTE, EPRI f!P-192.
- 2. " REVIEW Af1D ASSESSMENT OF RESEARCH RELEVANT TO DESIGil ASPECTS OF ilUCLEAR POWER PLAi!T pipit!G SYSTEMS,"
fiUREG-0307, HUCLEAR REGULATORY COMMISS10il, JULY 1977, khhhk nutech