ML19350E190
| ML19350E190 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 05/26/1981 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19350E189 | List: |
| References | |
| NUDOCS 8106170124 | |
| Download: ML19350E190 (34) | |
Text
.
ENCLOSURE 2
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il R C fl E E T I Il G HAFllIUil ilAY26,1901 A G E il D A
- 1. IllTRODUCTION/ PURPOSE
- 2. TECHtllCALDISCUSSICtl A) OVERVIBl 0F SUBSTITUTI0tl PLAtl B) PRICR EXPERIBlCE C) OVERVIEW OF W RCCS IMSIsl u) DESIGl I'CDS/CCMPARISOff WIE [GIliCD
-312/4.12 PtAnTS
- XL PLANTS i E) I'ATERIALS i F) PHYSICS L
j G) SAFETY EVALUATIm ItPACT
- 3. LICSS!flG/kTIWS
- 4. C0tJCLUSION/[CTI0ts l
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I 81061 7 0 YbA i
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1 HAFNIUM CONTROL ROD ASSEMBLY DESIGN .
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H A F il I U M ' A B S O R'B E R M A T E-R I'A L ~ SUBSTITUTION 0BJECTIVE: REPtKE AGINCD WIE FAFNIW STATUS: FAFNIW ItGRG)UCED IN 1980 I (1 P L E f1 E N T A T I O fl : FAF?HW SHIPfeUS ST/RT LATE 1981
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H A F il I U i1 APPLICABILITY 11CCA ALTEPRATIVE PLAr4T DESIGft STAWS fu-flF 17 x 17 312/412 CCTPLETE 17x17 XL PROPOSED 16x16 212 CCf4PLETE 15x15 312/412 FUTURE 14x14 ?17 FUTURE HFTIPS 312/412 C0f1PLETE tri EqC 17x17 7 ih'BRID XL C0fPLETE 0
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t l Hainium Control Rod Assembly i Development Schedule Overview Preliminary Decision Intermediate
} Design to Design i Review Delay Review Final I y y Program Reinstated y y y Design
! Des,ign v/nuss///A---------------------Tf////u////////A Review j
i Testing vus/gruuuruus/A------------- M g ,,,,,,,
l NRC l
Approval
- Materials Report SubniittalY y
" "O Lead Plant SAR Y Amendment RCCA Prototype V
! Y/ H H H A l Production V Ship 1st j yppp/A Production 1
l iiiliiiIiiiliiiIiiiiiiiiiiiiiiiliiil i
1974 1975 1976 1977 1978 1979 1980 1981 1982 i
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- 1 Hafnium Production Process Outline ,
Zircon Sand r
ZrO 2 Hf0 2 Extraction Process -
v v Zirconium Metal Hafnium Metal Reduction Reduction and Purification
! v v Zirconium Metal Hafnium Metal Products Fabrication Products Fabrication e
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Commercia0 Emperiertee 30
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N J A' \ \ CORE A HAD A F U L L.
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- \ :. COMPLEMENT l
YA\<EE 10.WE T ULL CORE COMPLEMENT
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FOR 3 YEARS. WO .
CRUC I FORM CONTROL RODS
/ IN CORE SINCE :.972 .
- S -
- 33. \ G 30 R ~~ T ULL CORE COMPLEMENT 4
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Hafnium RCCA Rodlet Design For 212, 312, 412 Plants-n
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Plenum 4" t
a Hafnium Replaces 142" Ag-In-Cd u
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l Design Objective i ,
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- Replace AGINCD with Hafnitim l
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- Minimize changes to already proven design l -
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Standard RCCA Configuration GisiiiiiB
- ; p Spring g , ,
t Spider Body S ,
h/h kh 0p.:!]l c L: 0,3 @
Spring Retainerm - --
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.88 Travel N a
.362 Dia.- -* -
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1.25 Dia. _ _ _
l 150.574 a
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142.00 Absorber ,
Length
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e Cladded Absorber Concept Preferred Over Unciadded
- One for one absorber material change
- f.
- Retain proven features of design:
- S. ST structure and joints Wear interfaces e Manufacturing flexibility (same parts?
- Facilitate licensing I {' }
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i 312/41217 X 17 RCCA Design Features j .
! All Ag All Hf f' Absorber O.D. (inch)
Absorber
.341 .341
- Length:(inch) Ag or Hf 142 142 l
l Clad I.D. (inch) .344 .344
!. Clad O.D. (inch) .381 .381 Giad Material 304 S.S. 304 S.S. ,
i Rodlet Spring Material 302 S.S. 302 S.S.
SpiderSprings Single Double Nested 4
e Nested Spider Spring rg f3
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\ ._ J 0-, Inner Spring w
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Outer Spring 8
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l 312/41217 X 17 RCCA De' signs l Performance Comparison l
l All Ag All Hf l .
RCCA Wt. (Ibs.) 149 180
{ Drive Rod Wt. (Ibs.) 136 136 Overall Wt. (Ibs.) 285 316 Calculated N-1 '
Rod Worth (%A/>)
STD Fuel 5.71 5.76 OFA Fuel 6.15 6.20
- 4 s
1 i
i Key Differences t
Key Differences from AalNCD Design Hesult i
- Greater Weight
- Change rodlet spring (shipping)
- Use nested spider spring
- Use appropriate drive shaf* coupling i
- Faster drop time -
i' i
! Reactivity Worth / Depletion
- Better than AalNCD l Lower Coef. Therm. Exp.
- Larger hot clearances l Lower Thermal Conductivity
- Higher absorber temperature 4
(melting temp. higher also)
- Cause of Potential Absorber
- HF Volume Change due to hydriding:
i Dimensional Change AalNCD Volume change due to irradiation l Both within same design limits Greater Stiffness
- No measurable change in wear performance
- Corrosion Resistance
- Better than AalNCD j 4
't l
Conclusion:
Design margin is unchanged or improved
9 Design Verification / Testing
! Verification Item
- Reactivity Worth
- Computer Codes l
- 1974 Critical Experiment
- Drop Time
- Previous D-Loop Tests
! (with less weight)
!
- Scram Loads
- Analytical Models Bas'ed on i D-Loop and Bench Test Data 1
i
- CRDM Stepping Loads,
- Previous D&M-Laop Tests Drive Line Wear, Vibration at Comparable Conditions
- Loads within Original Design Basis l
- Coupling / Joints
- Fatigue Tests at '
j Representative Loads t
l 0 Rodlet Integrity.
- Previous Tests and Operating Experience
- Cladded HF Autoclave Tests i
1
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PROPOSED XL HAFNIUti RCCA KEY DIFFERENCES XL- 312/IG2 ABSMBER LENGTH (IN.) 158.87 1412.00 R C C A Wr. (LBS) 200 180 OVERAU WT (LBS) 3ld 316 SPIDERSPRINGTRAVEL(IN) 1.05 0.88 Patsr SPRITS PRELCAD SalVSTED Fm WT.'
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Key Material Differences -
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' ' i i HF AGINCD i
- -Coefficient of Thermal 3.3 x 10 6 12.5 x 10 6 Expan.s. ipr) (IN/IN/ F).
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! Thermal Conductivity, , 0.213 at 620 F .902 at 600'F l (Watts /GM/ C) ; r .;
Density,(GM/CC) ... ' 13.36 10.17 1
i Modulus of Elasticity (PSI) 13.8 x 106 at 700 F 9.7 x 108 at 600 F i .
! Melting Point ( C) 2,222 800
- Strength (PSI,0.2 YS) > 30,000 ~ 7,000 -
1
} Resistance to Corrosion < 10 > 200 (MG/DM2 IN 200 Days) -
l 1 . .. i j Dimensional Stability ' i Sus' c eptible!t o . . l Susceptible to Irradiation
- Hydriding Swelling -
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@ NFD and Naval Specification l
! Chemistry Comparison
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! .. . Naval @NFD -
Spec Spec Remarks -
j i i l Interstitial (PPM, MAX) 525 1,510 Difference Affects (0,N,H) Weldability and Formability 1
Iron (PPM) 200-500 750 Negligible impact
! Total Metallic (PPM, MAX) 1,530 2,000 Negligible Impact l
Other than ZR ZR (% MAX) 4.5 4.5 Same HF (% MIN) 95.3 95.3 Same C;;' ' , ,,
$ $ 3i l' -
4
l MATERIALS TESTS AND OPERATING EXPERIENCE OTHER THAN NFD NAVAL REACTORS EXPERIENCE SHIPPINGPORT ATR ETR OPERATING EXPERIEi;CE IN PWR'S NFD TESTING CLADDED HAFNIUM AUTOCLAVE TEST
, STAINLESS STEEL-HAFNIUM CHEMICAL COMPATIBILITY i
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r PHYSICS CONSIDERATIONS CONTROL R0D WOPTH HAFNIUM AND AG-IN-CD HAVE NEARLY IDENTICAL ROD WORTHS AT OPERATING CONDITIONS E DESIGN.
CRITICAL EXPERIMENT DATA AND ANALYTICAL-ESTIMATES INDICATE WORTH EQUIVALENCE AT OPERATING CONDITIONS.
METHODOLOGY EMPLOYED TO GENERATE HF GROUP CONSTANTS AND HF ROD WORTHS IS DESCRIBED IN WCAP-9217(P), 9218 (NP)
"RESULTS OF CONTROL ROD WORTH PROGRAM".
HF METHODOLOGY IS IDENTICAL TO AG-IN-CD METHODOLOGY.
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PHYSICS CONSIDERATIONS CRITICAL EXPERIMENT DATA SOURCE HAFNIUM COLD WORTH RELATIVE TO AG-IN-CD BNWL CRITICALS (1974) 2.2% LESS ANDERSON AND THEILACKER, NEUTRON ABSORBER MATERIALS FOR REACTOR CONTROL Sl.0% LESS VALENTINE (BETTIS) $2.5% LESS (SOME DIFFERENCE IN R0D GE0METRIES)
HARTLEY AND BAYARD (BETTIS) 1.2% LESS NOTE:
- 1) ABOVE COMPARISONS WERE MADE AT COLD TEMPERATURES (S68*F)
- 2) DIFFERENCES BETWEEN HF AND AG-IN-CD HZP ROD WORTHS WILL BE SMALLER THAN INDICATED ABOVE DUE TO THE HARDER NEUTRON SPECTRUM AT OPERATING TEMPERATURES.
- 3) BETTIS PERSONNEL INDICATE THAT HF IS WORTH SLIGHTLY MORE THAN AG-IN-CD AT OPERATING' TEMPERATURES.
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PHYSICS CONSIDERATIONS CONTROL ROD WORTH CALCULATIONS TYPICAL CALCULATED ROD WORTHS FOR A 4-LOOP, 12 FT CORE, HZP, E0L, EQUILIBRIUM CYCLE, STANDARD 17X17 FUEL ROD WORTH (%ao)
N N-1 AG-IN-CD 6.95 5,70 HAFNIUM 7,00 5,74 N-1 R0D WORTH IS USED TO CALCULATE SHUTDOWN MARGIN HF N-1 R0D WORTHS WILL BE REDUCED BY 10% FOR SHUTDOWN MARGIN CALCULATIONS HAFNIUM AND AG-IN-CD WILL ALSO HAVE NEARLY IDENTICAL WORTHS IN 14 FT CORES AND OPTIMIZED FUEL CORES l
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~
PHYSICS CONSIDERATIONS GROUP CONSTANTS AND SPECTRUM EFFECTS COMPARISON OF HF AND AG-IN-CD GROUP CONSTANTS CONSTANT RATIO (HF/AG-IN-CD)
D1 1.03 El 1.16 ER 0.92 2
D 1.22 g2 ,
0.72 INCREASED RESONANCE ABSORPTION IN HF COMPENSATES FOR DECREASED THERMAL ABSORPTION INC . EASE .IN 01 /0 2WITH INCREASE IN TEMPERATURE RESULTS IN HF WORTH INCREASE RELATIVE TO AG-IN-CD (TYPICAL VALUES: 01 /0 2 COLD = 4.6, 0 /0 1 2 HOT = 5.8 )
l CORE AVERAGE 10 /0 2 IS NEGLIGIBLY CHANGED DUE TO PRESENCE OF HF:
01/02 (HZP, ARI)
HAFNIUM 6.14 AG-IN-CD 6.18 .
NO IMPACT ON CORE KINETICS e -- .- -- .- , . . - - , . . , - , - . , , , , - . . , - _ . . . , . . - - . . - - . - - , , - , . - - - - - . - , . . , - - - . , . - - - . . . , - - , , . . , . , - - - . . , ,
.3 l
. LIFETIME CONSIDERATIONS CONTROL ROD DEPLETION IS NORMALLY NOT A PROBLEM SINCE PLANTS ARE USUALLY OPERATED WITH AR0 HAFNIUM DEPLETES SLOWER THAN AG-IN-CD OVER A LARGE FLUENCE PANGE DUE TO:
- 1) TRANSMUTATION OF HF ISOTOPES
- 2) QUICK BURNUP OF CD-113 IN AG-IN-CD EVEN WITH DAILY LOAD FOLLOW, WORTH DEPLETION IS NOT A PROBLEM SINCE < 10% OF CONTROL RODS SEE SIGNIFICANT FLUENCE l
I f
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SAFEIY EVAUJATICN IMPACT REACTIVITY 10RTH l
NO PEACTIVITY lGTH F91ALTY (ESSENTIALLY SA N WORTH)
NO SIGNIFICANT EFFECT CN SAR-T6E ACCIDENTS RCCA DROP TIE i
PARlILN RCCA HEAVIER TPAN M-IN-CD FASTER DROP TIE PEEFICIAL TO ALL SAR-TYPE ACCIIHITS l
l l
l CCNCLUSICNS: SAFETY REQUIFSINTS AE ET ETAL TO CR EETTER WN M-IN-CD l
LICENSIfE ACTIG S PRIOR #0 OJRRBE PAFNIlN APPROVALS PATERIALS TOPICAL GOP-9.U9) APP 90lX SLBITTED OCTGER,1980
- COP #DE PEAK FSAR #EDEIT II4 SLB1IIIw J#BRY,1981
- SNUFPS FSAR fEVISION 2 SUEMIllw FEBRJARY,1981 OTHER SPECIFIC PLANT FSAR #SDERS IN PROGRESS COWDE PEF #0 St0PPS SERS iN PREPARATION
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CONCUJSIWS BASED UPW TE MATERIAL ECPANICAL, NJCLEAR, #lD SAETY EVALUATImS FRESENTED, IT CAN E CWCUJED TFAT THE DIECT SUBSTITUTIm E FAFNIUM FOR AG-IN-CD INTO THE FRESENT TESTItG0JSE RCCA DESIC44S SATISFIES ALLPERTINENT RF0W#lCE AND SAFETY EQJIREPENTS AS DOCLPENED IN EGULAT0kT CUIE 1.70 #1D THE ST#GRD FE/IEW PLANS.
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MEETING SuicMRY ihSTRIBUTION Docket File G. Lear NRC POR Local PDR 5. Pawlicki NSIC V. Senaraya J~ TERA:".?' Z. Rosztoczy LB!T 3'R$ading W. Haass
!!. Denton D. Muller E. Ccsc R. Ballard D. Eisenhu: W. Regan R. Purp'. a R. Mattson B. J. Y:ungblood P. Check A. Schwencer F. Miraglia 0. Parr J. Miller F. Rosa G. Lainas W. Butler R. Volicer W. Kreger J. P. Knight R. licuston R. Bosnak T. Murphy F. Schauer L. Rubenstein R. E. Jackson T. Speis Project Manager D. Sells W. Johnston Attorney, OELD - see cottom or page. J. Stolz J. Lee S. Hanauer O gg .f OIE (3) W. Cannill 2 Sg ACRS (16)
R. Tecesco T. Murley T. S(.hroeder 8
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O. Skovholt M. trnst.
01
- J U ti 1 0 19 8 I
- I NRC Particinants: , R. Bacr " sm*
p>estm( -7
- J. Voglewede C. Berlinger
- MTokar. K, Kniel TChan - G. Knighton
- BJYoungblood
'y A. Thadani
- ADromerick D. Tandi
- MDunenfeld . J. Kramer D. Vassallo
. P. Collins D. Ziemann E. Adensam bcc: A ' Comanche Peak PM - SBurwell S.pplicant Texas & Service List Callaway PM - RAuluck -*
Comanche Peak Wolf Creek PM - GEdison Callaway
- Lawyers: .
Wolf Creek ,
Comanche Peak - Rothschild/ Turk / Gray Callaway - Lessy/McGurren S. Texas ' leg'ar/::cdsdx/[Laddsecrre Ai:
Wolf Creek - Vogler
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., - - . . - . . .- . . - . . .