ML20148H511
| ML20148H511 | |
| Person / Time | |
|---|---|
| Issue date: | 06/04/1997 |
| From: | Wang E NRC (Affiliation Not Assigned) |
| To: | Matthews D NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9706100302 | |
| Download: ML20148H511 (47) | |
Text
{{#Wiki_filter:_ l{ June 4, 1997 MEMORANDUM T0: David B. Matthews, Chief g Generic Issues and Environmental l Projects Branch Division of Reactor Program Management t Office of Nuclear Reactor Regulation FROM: Egan Y. Wang, Reactor System Engineer Original Signed By: i Generic Issues and Environmental Projects Branch i Division of Reactor Program Management l Office of Nuclear Reactor Regulation
SUBJECT:
MEETING
SUMMARY
OF MAY 6, 1997, REGARDING THE METHODOLOGY t 0F OPTIMIZING EXISTING SPENT FUEL MANAGEMENT AND l-ENCAPSULATION OF SPENT FUEL FOR DRY STORAGE. On May 6, 1997, representatives of Siemens Power Corporation (SPC) met with representatives of the Nuclear Regulatory Commission (NRC) in Rockville, MD. The purpose of this meeting was for SPC to present approaches to: 1) expedite the current discharge rate of spent fuel from spent fuel pools to dry storage i casks, and 2) be more flexible in the storage and handling' spent fuel assemblies in independent spent fuel storage installation, monitored retrievable storage, and the final repository by an early encapsulation of individual spent fuel assemblies in the fuel pool prior to dry cask loading. l The NRC staff indicated that such methodologies appeared to be technically sound. However, the staff stated that more details would be necessary to determine if an early encapsulation of damaged fuel assemblies would make the bundles equivalent to undamaged fuel assemblies with respect to dry storage, or would allow loading such assemblies' into dry casks. The staff indicated that given sufficient resources, the NRC would review the approaches for plant specific applications. A portion of the material presented is proprietary. : List of Attendees. : Non-proprietary Slides rg Attachments: As stated cc w/atts: Mr. H. D. Curet, Manager Product Licensing / Siemens Power Corporation I 2101 Horn Rapids Road P. O. Box 130 hkggg Richland, WA 99352-0130 9706100302 970604 PDR TOPRP EMVEXXN C PDR M d page Document name: 970506MT. SUM y g,4 g e m 0FC PGEB8() SC:PGEB C:hiEk f NAME EWangIsw FAkstulewicz DMabiN's I ews qg ,DATE 05/df97 -05/ /9J0002/41 Oh/97 \\ y W
l l e-i 1. Sa 8: tog. 'g g UNITED STATES } NUCLEAR REGULATORY COMMISSION - 2 WASHINGTON, D.C. 20606 4001 June 4, 1997 [ MEMORANDUM TO: David B. Matthews, Chief _- Generic Issues and Environmental Projects' Branch l Division of Reactor Program Management l Office of Nuclear Reactor Regulation FROM: Egan Y. Wang, Reactor System Engineer-l Generic Issues and Environmental Projects Branch l Division of Reactor Program Management Office of Nuclear Reactor Regulation l
SUBJECT:
MEETING
SUMMARY
OF MAY 6, 1997, REGARDING THE dETH000 LOGY l OF OPTIMIZING EXISTING SPENT FUEL MANAGEMENT AND-ENCAPSULATION OF SPENT FUEL FOR DRY STORAGE. On May 6, 1997, representatives of Siemens Power Corporation (SPC) met with l representatives of the Nuclear Regulatory Commission (NRC) in Rockville, MD. The purpose of this meeting was for SPC to present approaches to: 1) expedite the current discharge rate of spent fuel from spent fuel pools to dry storage . casks, and 2) be more flexible in the storage and handling spent fuel assemblies in independent spent fuel storage installation, monitored retrievable storage, and the final repository by an early encapsulation'of l individual spent fuel assemblies in the fuel pool prior to dry cask loading. l The NRC staff-indicated that such methodologies appeared to be technically l sound. However, the staff stated that more details would be necessary to l determine if an early encapsulation of damaged fuel assemblies would make the bundles equivalent to undamaged fuel assemblies with respect to dry storage, or would allow loading such assemblies into dry casks. The staff indicated that given sufficient resources, the NRC would review the approaches for plant specific applications. A~ portion of the material presented is proprietary. Attachment I: List of Attendees : Non-proprietary Slides Attachments: As stated ' I cc w/atts: Mr. H. D. Curet, Manager Product Licensing i Siemens Power Corporation 2101 Horn Rapids Road.: P. O. Box 130 Richland, WA 99352-0130 7
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I l DISTRIBUTION: Mtg. Summary of May 6 Meeting with Siemens Power i Corporation Dated June 4, 1997 HARD COPY ' Central File Public PGEB r/f E. Wang OGC ACRS E-MAIL F. Miraglia A. Thadani R. Zimmerman G. Holahan T. Martin M. Slosson D. Matthews F. Akstclewicz G. Hubbard C. Withee C.-Gratton L. Kopp F. Sturz 6 e yO, nh U g I
1 4 NRC/SIENENS POWER CORPORATION NEETING ON OPTINIZATION EXISTING SPENT FUEL AND ENCAPSULATION LIST OF ATTENDEES Nay 6, 1997 N8liE ORGANIZATION Dannert, Volker Siemens Curet, D. H. Siemens Sturz, Fritz NRC/SFP0 Withee, Carl NRC/SFP0 i Carlson, Don NRC/SFP0 Hubbard, George NRC/SPLB l Gratton, Chris NRC/SPLB Kopp, Larry NRC/SRXB Crawford, Sidney Public Wells, Alan Waste Package Design Wang, Egan NRC/PGEB i i i ATTACHMENT 1 4 k
SIEMENS s SAFIR Mission Support our customers newngggyv to achieve cost-effective inten,m storage of fuel assemblies taking into account all relevant e economic, technical, and licensing conditions using a comprehensive and broad field know-how e in nuclear technology i 05/1 o
t SIEMENS New developments in the front end have significant consequences for spent fuel management L 5-F 55 Mwd /kg Each additional year = ExamDie: l of average Cooling time ? Decay Heat requires about 50 4-(kWperFA) i l rack positions in the pool j l (German PWR 1300) r 3-1A J j i j i i l t f j- --{ l l 2-l -- q l l t i I j l l 1_ 45 mwd /kg pjt 5 dears l . _ l _. j. j l i-v
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[ 4 1 1 l 1 I I I O 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 i Decay Time (years) i t 05/1997 2 i
r SIEMENS l Mid-to Long-term Management of the Storage Pool of a Plant is an Important issue l ) Number of FA in the storage pool 900 l l 800 700 i lill .nu Fuel ss s ready for cask loadin 200 Fuel assemblies not ready for cask loading (or to be inserted again into the core) inuuuuuuuuuni 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 05/1 o i
SIEMENS Cost-Effective Interim Storage Requires Cask Design and Cask License Adapted to Fuel Assembly Properties q Cask License Technical Design r [ l Fuel Rod Integrity Heat Load Capacity Subcn.ticality Shielding l h i 1 i I I f a k i P f i i osn N Yr 4
o 1 i SIEMENS Existing Cask Licenses are Based Upon Conservative Assumptions for the Fuel Loaded l Cask License -Technical. Design i ) Fuel Rod integrity Heat Load Capacity i i Subcriticality I Shield.ing f i t i O O b O g E S. 3 BE E I F c m a e8 E E S _.c >f x .M8 8,_ 8 E Eb E TE t C 00 0 3 OO M 3 G) Cw Q1 o m zw 0 1H l k 05/19 7 5 i l \\
SIEMENS Technical Margins of the Cask Cannot be Used Due to Licensing Limiting Licensing Concepts Cask License Techn.ical Design i Fuel Rod Integrity i Heat Load Capacity Subcriticality i Shielding i j ? 8 FA z 8 2 Propert. es i a) i g E m 3 Be e r F c m a e8 E MR _c x
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SIEMENS i Existing Licenses Prevent the Use of the Technical Margins of the Cask Existing Advanced licenses As a' result,- licenses are set limits the heat load able to use Heat load for each capacity can the whole cask capacity fuel assembly not be used capacity FAWrgy _.. _. = -=..._:n 7_ .l.i i.J::N.3 i ,.g cn -- m E T TE_. "J ( -- r ^ I ~. ~. 7, ^ '.'Z ~ ,g, ~.._.. Mi _ __5 @= -- x--' -] pw 2 =.19 _... l c. . _= :mD A {lQ@]5E;/Mk!Rh;((j f Frame Conditions V i 05/1 7 7 ,w
l t f SIEMENS Individual Cask Loading-Patterns Create l Technical and Economic Potential L l Cask Loading-Pattern i 4 A in-Cask Cladding Behavior l Cask Shielding Temperature During j Calculations Distribution Storage Pen _od j y Source Terms, Fuel Rod Design j n Source Terms Calculations with l and Decay Heat Actual Power Histories i I in-Core Fuel Management 05/1 7 o
SIEMENS Analyzed realistic power histories h 1 l l i f k t f i t BVAND/Bk 05/1997 - No. 9
l l SIEMENS 4 Effects of realistic power histories on total decay L heat l i i ? e i ( i 05/199 0 I L m m
SIEMENS Effects of burn up variation on total decay heat i i i 1 a i 05/19
l SIEMENS Heat Dissipation Calculations for Spent Fuel Transport and Storage Casks l Calculational method: 3-dimensional calculation, if necessary Codes: l ANSYS { HYDRA (only for parameter-studies) f Comment: i Thermal hydraulics only applied if experimental data and calculated results show sufficient coincidence 05/1N o 4 1 .m
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- SIEMENS i Temperature profiles can be calculated for a cask on the basis of realistic power histories i-i f i ouieTai 5 t i
SIEMENS Fuel Rod Cladding Behavior Analysis for Spent Fuel Transport and Storage Casks i I e l r t t 05/1997 0 I
SIEMENS Cladding temperature is a <ey variable for dry storage. Cladding temperature in C ^ during dry storage Maximum reference y 400 ( l temperaturefor loaded l CASTOR V/19: 370 *C 350-300-Temperature profile 1 7 ~ 200 4 6 8 10 0 2 Time in years E9 i 2
O SIEMENS The self-consistant statistical analysis of cladding strain j provides additional margins. Frequency on the basis of 10,304 computations Quantiles Licensed limit f r 95 %/95 % CASTOR V/19 l [ 95 %/99 % Deterministic calculation m r Additional margin l ~ through statistical analysis i i i i 0.00 0.50 1.00 1.50 2.00 2.50 3.00 3.50 i Total equivalent strain in % for temperature profile 1 j En% f
SIEMENS Shielding Calculations for Spent Fuel Transport and Storage Casks Calculational method: Sn-method (method of discrete ordinates) Codes: ANISN (1d Sn-Code) i DOT 4.2 (2d Sn-Code) j I TORT (3d Sn-Code) Cross section libraries: EURLIB4 (100n + 20y groups) based on ENDF/B4 i EURLIB6 (175n groups) based on ENDF/B6 l Alternative method: l ? Monte Carlo method, MCNP-Code l i 05/199 1 l r l
SIEMENS SAFIR: Dienstleistungen f0r die Brennelemententsorgung F i L i i h i f f h t 05/19 I i
T SIEMENS l CASTOR lla: Radial distribution of the dose rate parallel to the l 0 -axis in a distance.of 6 cm (between two fins) i [ t I i [ = i [ - ~,. - .,-.----~,+--g- -.sww ,e. g4 wow--.c>tw-w,ww,.,9-yw,,w---<,.c.-- y v.,.- - - r-. gw,-#.
SIEMENS Conceptual Approach for Licensing: " Frame Specification" for Individual Cask Loading Patterns i 05/19 3
SIEMENS 1 The Frame Specification for in-Core Fuel Management Can Serve as a Model for an Advanced Cask License i I l i i l I f 05/19 i
SIEMENS i To Use Existing Margins the Cask Design Must Match to License and Cask Loading Pattern l Cask License Technical Design i Fuel Rod Integrity [ Heat Load Capacity Subcriti f Shielding ~ Propert.ies i I The use of the technical margin of the cask design and optimized cask l l loading patterns are feasible with a frame specification i I 05/199 5 t 1
SIEMENS Benefits O Front-end and back-end planning can be coordinated better O The technical margins of the casks can be used by optimized cask-loading patterns O Leads to more flexibility and cost-savings O Increased safety by earlier discharge of spent fuel from the pool to the passively cooled dry casks 05/19 6
t SIEMENS j Early Encapsulation Contributes Toward Further Development of Dry Storage i 1 L i 1 r l [ j i i r t' l ~ lilli 1 l i osnsE T E t i
SIEMENS Early Encapsulation Fuel Assemblies Prepared in the i Spent Fuel Pool for Emplacement in a Repository 1 t I f i V V xo Al: Capsule O V "3 b G i 2 m III Ii i,:;+,4-.:,' - ;o :: , u m a.c. -d k + lN.~ ^r , :'N S -.f' _ w.
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( i 2 ) g i s 3 0 w u 13 5 % $Ni ' WC-1 l [ L ) 6 A % h li s L i ' s, n1 ii Overpack t o System i V u Reactor Core Spent Fuel Pool Dual-Purpose bv._M I Cask r i t 8VAND/8k [ 05/1997 - No.18 j F I J
SIEMENS The Capsules can be Reloaded into Overpacks - I Without the Need to Handle the Fuel Itself I b_'g.s a y .u mes.,,3w, as gw a s-m WMDMNLNWJ ' Loading Station r3 3 Repository kb J& + O (full) O i )( Transport ^ ~ o a v Shielding i l f \\ 1I II I h j l( O O O I v I.-_ pack Capsule Ah O (T 3 v (I j l l Dual-Purpose Repository O s (empty) Cask Over V esn E T IE i
~ f mmus Major Design Considerations for the Fuel Assembly Encapsulation Unit i i O A standard capsule design concept is suitable for use with { various types of fuel assemblies l 4 O Allows use of standard casks i O Encapsulation unit is mobile and can be employed in LWR plants i O Method of fuel assembly handling similar to that already practiced l 4 1 O Retrievability of fuel assemblies during the entire encapsulation process O The objective is to prepare a complete load of encapsulated fuel assemblies for one cask within one week j marm i
b SIEMENS Capsule Design Boundary Conditions 1 t t i r t L f i 5 1 05/1997 - No. 21 l
SIEMENS Example: PWR-capsule (Type 16x16 /18x18) 05/199
SIEMENS PWR-capsule (type 16x16 /18x18} 1 L ? i 1 05/199
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SIEMENS ~ L The Individual Steps of the Encapsulation Process e O ) 05/199 4
l SIEMENS Insert Capsule into the Spent Fuel Pool and into (1/s) the Encapsulation Unit t e I 05/199 i
SIEMENS Insert Capsule into the Spent Fuel Pool and into the (2/s) Encapsulation Unit l l-E i [ t 03/199 P . - ---.~ 2-
SIEMENS Insert Capsule into the Spent Fuel Pool and into the (3/6) Encapsulation Unit i i I l o I esnA?M
SIEMENS I insert Capsule Into the Spent Fuel Pool and into the (4/s) Encapsulation Unit i t h y 05/199 1
SIEMENS Insert Capsule into the Spent Fuel Pool and into the (s/s) i Encapsulation Unit a 6 i i L h h i 05/199 i
SIEMENS Insert Capsule into the Spent Fuel Pool and into the (e/s) Encapsulation Unit e 0$/199
SIEMENS Remove Fuel Assembly From Fuel Storage Rack (1/3) and Dry O 05/199
6 SIEMENS Remove and Dry Fuel Assembly From Fuel Storage (2/3) Rack e 05/199 No
t SIEMENS Remove and Dry Fuel Assembly From Fuel Storage (3/3) Rack L [ t i i i t , - - _ - _ - - - - - - - - - - - - - - -. - - - - -. - - - ~ - - -. _ - - - - - - - - - -. - - - -
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,g.o-4 , SIEMENS i nsert Fuel Assembly into Capsule na) r i \\ s s 9, ?
SIEMENS 6 Insert Fuel Assembly Into Capsule (2/2) t e 7 4 i 05/1
SIEMENS (1/3) l Seal Capsule and Adjust Internal Pressure 1 ? I l l t I h 05ff99 i f
SIEMENS (2/3) Seal Capsule and Adjust Internal Pressure k e [ r 05n99
SIEMENS r (3/3) Seal Capsule and Adjust Internal Pressure i [ t t t e e s. e, n ~.<e r-w
SIEMENS Perform Helium Leak Test on the Capsule (1/2) O 6 b I i osnSPA"5 L I
SIEMENS Perform Helium Leak Test on the Capsule (2/2) e 5 I i l I i t i osn E M j
SIEMENS Insert Capsule into the Second Transfer Position (1n) O P P esnA1*L*Tl
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SIEMENS Summary O SAFIR: Siemens would submit methodology to the NRC for approval to: > load spent fuel more flexibly in existing licensed dry casks > support new licenses for dry casks O Early Encapsulation: > Short term: failed fuel or fuel to be canistered in general > Long term: to meet final repository requirements more easily O Safety: > Expedited transition from active to passive storage of spent fuel 05/199 3 - -}}