ML22046A028

From kanterella
Jump to navigation Jump to search

Gns Gesellschaft Fur Nuklear-Service Mbh, 10 CFR72 Application of Castor geo69 Dry Storage System, Technical Meeting
ML22046A028
Person / Time
Site: 07201052
Issue date: 02/07/2022
From:
GNS Gesellschaft fur Nuklear-Service mbH
To:
Office of Nuclear Material Safety and Safeguards
References
Download: ML22046A028 (96)
v • d • e


Text

Non-Proprietary Version 10 CFR72 Application of CASTOR geo69 Dry Storage System G N S G es e 11 sch a ft f u r N u k I ea r-S e r vice m b H Technical Meeting

@ GNS

Agenda - Public Part Project Overview Scope and Intention of Part 72 Application

  • Applicable Regulations and Guidelines Comparison with German Storage Regulations
  • Status of Application

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 2

Project Overview

  • GNS aims to obtain approvals for its Tran sport and storage cask CASTOR geo69 10 CFR 71 Application on 01/14/2021 Docket: 71-9383 10 CFR 72 Application on 06/07/2021 Docket: 72-1052 Quality Assurance Program (QAP)

QAP Description Application on 07/10/2020 Docket: 71-0967 Taking into account both, the requirements according to 10 CFR Part 71, Subpart H and 10 C F R Pa rt 7 2, S u b pa rt G Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Tech n ica I Meeting / 10 CF R 72 CASTOR geo 69 DSS/ 3

Scope and Intention of Part 72 Application Approval of the DSS for SNF without any connection to a specific storage facility Definition of a generic storage environment Derivation of boundary conditions for DSS evaluation Specification of requirements for storage facilities

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Me eting/ 10 CFR 72 CASTOR !!> geo69 DSS/ 4

Applicable Regulations and Guidelines Approval of the CASTOR geo69 DSS under 10 C FR 7 2 S u b pa rt L - A p p r ova I of Sp e n t Fu e I Storage Casks RG 3.61 + Periodic Review conducted 1n July 2019 NU REG 2215 With exception of chapters only applicable for specific licenses (SL) of ISFSI Applicable referenced Guidelines Proprietary Inform ation withheld pe r 10 CFR 2.390 Non-Proprietary Version l"-"!',,kCU.., >0-.-(:...,_>JroatC~IIOt."tll)>>f'Aff1'l-UCl:l

!i.U at.:Ql)JJU:Mon~ ~Oil TID. l!\\0t.PL,uu.r STOf.A(;t. Of Sff.h'T Nut."U:.AI. ' UU.. IIIUJ L..l:.VU.

UDIOACTIVEWASTl:. Ah"'DJ.F.AnllA..aru:reooaura OIANCUSSC'W4Sll:

PART 72-LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE

~

~

Tlll'vp,:oo,,,.

=--

12.)~

Tl.lO~po.-:lll:&

~a-uc.-~Fo,m,.... ~

Tl IIIFil-,ol"a,,pli,;*- f,w.,<<,flc....__

REGULATORY GUIDE Off'IC:I o, 1IIIJCI..IAlt lllf.GlU.TOflTM:MNICH

........ftlll'W'-UI 11-ca..-.

.,.,..,,.,.,f'OMl,I.T,,,_OON'fWlff

,mATDf'ICM.s.vwf'YIAM..,..~l"ClllA WOffl'\\aOft~~

n 111:::_

7:UOl'llbl-.!

~.S.NR 1u.c.-

,._._,.l't,pl,..J*F-Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities Final Report

........,.~~JOZO o.~* A;rt102!)

OlfaolfUlut"Mlllffla'~tnd~

Technical Meet ing / 10 CF R 72 CASTO R111 geo69 DSS/ 5

Applicable Regulations and Guidelines Applic.ability Normal Design Event Conditions Off-Normal Design Event Conditions Scope for Certificate of Compliance and Soecific License Reviews Ambient Temperature:

(1) Maximum (2) Minimum Loading:

(1) Wet or dry Storage and Handling (e_g _, loading, transfer) Orientation:

(1) Vertical or Horizontal Maximum Lift Height Maximum Cladding Temperature 1 % Fuel Rod Rupture Solar lnsolation Temperature Variation Beyond Normal 10% Fuel Rod Failure Combined with Off-Normal Temperatures Failure of One of the Confinement Boundaries Partial Air Flow Blockage Human Error Out-of-Tolerance Equipment Performance Equipment Failure Instrumentation Failure Faulty Instrumentation Calibration

@GNS Proprietary Information withhe ld per 10 CFR 2.390 Non-Proprietary Version Applicability Scope for Certificate of Compliance and Specific License Reviews Design-Basis End Drop:

Accident Design (1) Lift height (or maximum Events and acceleration)

Conditions Side Drop:

(1) Lift Height (or Maximum Acceleration)

Tipover:

(1) Acceleration (if applicable)

Fire:

(1) Duration (2) Temperature Complete Air Flow Blockage Explosive Overpressure Design-Basis Flood Natural Phenomena Design Events and Earthquake Conditions Tornado Burial Under Debris Lightning Other potentially relevant events identified in 10 CFR Part 72 {see SRP Section 3.5-2-5), as annlicable (according to NUREG-2215)

Techn ical Meeting/ 10 CFR 72 CASTOR geo69 D55/ 6

Comparison with German Storage Regulations

  • Storage of Spent Nuclear Fuel in either 12 Onsite intermediate storage facilities attheNPPor 2 Central intermediate storage facilities (Ahaus/ Gorleben)
  • No separate Coe for Dry Storage Systems DSS are included in licenses for relevant storage facilities esundesamtfu rd ieSicherheitdernuklearenEnt1orgung Separate regulatory authorities in each federal state No generally applicable requirements regarding evaluation Storage System related evaluations are individually commissioned by the licensee of the respective storage facility GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technica l Meeting/ 10 CFR 72 CASTORfl geo69 D55/ 7

r-- --

Status of Part 72 Application Application:

Request for supplemental information:

06/07/2021 10/18/2021 Existing Ii n k age to th e Pa rt 71 a p p Ii cat i o n o n I y a 11 ow s s u b seq u e n t e v a I u at i o n by N RC GNS intends to separate the Part 72 SAR from the Part 71 SAR during revision.

Unspecified storage environment results in the need of further evaluations of the DSS main topic of today's meeting Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version I

-th Observations tal information w1 Request for supplem~STOR geo69 storage cask Model No. No.

N 72 1052 Docket o.

-on needed by the staff in 1 information (RSI) iden~fies mtorma~1cate of compliance for the This request '.or ~upplemt:e review of the application for a c;~~21 (AgencyNide Document connection with its a~~ep :9 spent ruel pack.ages, dated Ju~~78)_ The U.S. Nuclear Regulato Model No. CASTOR ~~~ system Accession No. M~11!! guidance in NUREG-2215, Acces~ a~d l\\l(t~~6::taff reviewed the application u~ny~tems and Facilities."

comm1ss1on f

Spent Fuel ory storage "Standard Review Plan or

- listed by technical disc1p\\me of rev1e~1.

The requested information is Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 8

End of Public part

(@)GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo 69 DSS/ 9

Agenda - Closed Part

  • Background and schedule requirements DSS and CLU Definition and description of configurations Handling operations
  • Concepts of safety evaluations Concept for CLU Current concept for DSS Alternative concept for DSS
  • Safety evaluations to be performed resulting from concepts and RSI Organized by specialty department:

Structural, thermal, shielding & radiation protection, criticality, containment and material evaluations, operation procedures, acceptance criteria and maintenance program

(@)GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 10

Agenda - Closed Part Background and schedule requirements DSS and CLU Definition and description of configurations Handling operations Concepts of safety evaluations Concept for CLU Current concept for DSS Alternative co~cept for DSS Safety evaluations to be performed resulting from concepts and RSI 0 r g a n i zed by spec i a It y d e pa rt m e n t :

Structural, thermal, shielding & radiation protection, criticality, containment and material evaluations, operation procedures, acceptance criteria and maintenance program Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 D55/ 11

Background and Schedule Requirements

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 12

Agenda - Closed Part Background and schedule requirements DSS and CLU Definition and description of configurations Handling operations Concepts of safety evaluations Concept for CLU Current concept for DSS Alternative concept for DSS Safety evaluations to be performed resulting from concepts and RSI Organized by specialty department:

Structural, thermal, shielding & radiation protection, criticality, containment and material evaluations, operation procedures, acceptance criteria and maintenance program

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 13

Configuration of DSS CASTOR geo69 storage cask Cask incl. lid system Canister incl. lid system Basket Protection cover incl. cable conduit GNS Pro prietary Information withhe ld pe r 10 CF R 2.390 Non-Proprietary Version

~

Protection cover Storage cask Technical Meeting/ 10 CFR 72 CASTOR geo69 D55/ 14

@GNS uration of DSS Proprietary lnform.atlon withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 15

Intended Handling Operations with the storage cask at nuclear facilities Horizontal delivery of the storage cask at N PP 11 At truck lock inside reactor facility Tilting between horizontal and vertical position (load attachment to trunnions by crane}

Open/closure and dispatch of cask lid system (installing pressure switch}

Accepting transfer cask, transfer lock and canister transshipment 11 Vertical onsite transfer between reactor and storage facility Inside building of storage facility (Installing pressure switch, if not already done, dispatch of cask lid system)

Vertical transfer to/from storage position, e.g. by crane using trunnions (Dis-}connecting pressure switch to monitoring system of storage facility Placing/removing protection cover (incl. cable conduit} on top of cask Maintenance operations during long-term storage

@GNS Proprietary Inform atlon withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 16

Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 17

Agenda - Closed Part

  • Background and schedule requirements 055 and CLU Definition and description of configurations Handling operations Concepts of safety evaluations Concept for CLU Current concept for DSS Alternative concept for DSS 11 Safety eva I uatio ns to be performed resulting from concepts and RSI Organized by specialty department:

Structural, thermal, shielding & radiation protection, criticality, containment and material evaluations, operation procedures, acceptance criteria and maintenance program

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 19

Intended Handling Operations with CLU components inside the reactor facility

  • Any CLU handling provided exclusively inside NPP facility
  • Loading of FA into canister positioned inside transfer cask on ground of SNF pool Crane transfer of transfer cask out of pool on trunnions
  • Crane transfer of transfer cask to the truck lock
  • Mounting transfer lock on storage cask
  • Positioning transfer cask on top of transfer lock 0 pen ing and closure of bottom lid
  • Lowering canister into storage cask
  • Removal of CLU components

@GNS Proprietary Info rmation withheld per 10 CFR 2.390 Non-Proprietary Version J

Technical Meeting / 10 CFR 72 CASTO R geo69 DSS/ 18

Concept of Safety Evaluations - CLU Compliance with safety objectives ensured by NPP building Normal conditions:

Solar insolation Snow & ice Max. lift height (single failure proof crane)

Off-norm a I conditions:

Off-normal ambient temperatures

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Accident conditions:

Transfer cask drops (s in gle failure proof crane, etc)

Transfer cask tipover (anchoring to the building)

Fire (no combustible mate rials)

Explosive Overpressure (no combustible mate rials)

Natural phenomena:

Flood Tornado wind & missiles Burial under debris (closed, non -collapsing DSF building)

Lightning Technical Meeting/ 10 CF R 72 CASTOR geo69 DSS/ 20

Concept of Safety Evaluations - CLU Compliance with safety objectives ensured by CLU Normal conditions:

Ambient temperatures (usage for T < 0°C not permitted, T max (pool water)< S0 °C, T max (reactor hall)< 35°C)

Loading, Handling Max. lift height (single failure proof trunnions) 1%fuelrodrupture Cladding Temperature Off-normal conditions:

Off-normal ambient temperatures Small release of radioactive material (due to contamination of canister or transfer cask during underwater loading)

Human error, equipment or instrumentation failure, misalignment, loss of power for a limited duration, Unintended mechanical loads GNS Proprieta ry Info rmation withhe ld per 10 CFR 2.39 0 Non-Proprietary Version Techn ical Meeting/ 10 CFR 72 CASTOR~ geo69 D55/ 21

Concept of Safety Evaluations - CLU Compliance with safety objectives ensured by CLU Normal conditions:

Ambient temperatures (usage for T < 0°C not perm itted, T max (pool water)< 50°(, T max (reactor hall)< 35°()

Loading, Handling Max. lift height (single failure proof trunnions) 1% fuel rod rupture Cladding Temperature Off-norm a I conditions:

""'a\\

\\-t'ot"

Off-normal ambient tempe~ ~~o\\

0 Small release of rad~,t"Be~

ter~~ec;Se (due to contam i~ tit O!an ist<<,\\°~~ r cask during underwater loading)

Hum~~, _eg ui~~'dr iru_t_PJ_mentation failure, misalignm~

\\\\)8 of ~,~'I,~~ a limited duration, Uninte~

a m~~"'iai i oads acco

(@) GNS Proprietary Info rmation withheld per 10 CFR 2.390 Non-Proprietary Version Technica l Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 22

Discussion

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 23

Agenda - Closed Part

  • Background and schedule requirements DSS and CLU Definition and description of configurations Handling operations Concepts of safety evaluations Concept for CLU Current concept for DSS Alternative concept for DSS Safety eva I uatio ns to be performed resulting from concepts and RSI 0 rga n ized by specialty de pa rtm e nt:

Structural, thermal, shielding & radiation protection, criticality, containment and material evaluations, operation procedures, acceptance criteria and maintenance program

@GNS Proprietary Inform atlon withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 24

Current Concept of Safety Evaluations - DSS Compliance with Safety objectives ensured by DSF (building)

Normal conditions:

Solar insolation Snow & ice Max. lift height (single failure proo f crane)

Off-norm al conditions:

n.a.

GNS Proprieta ry Informat ion withhe ld per 10 CFR 2.390 Non-Proprietary Version Accident conditions:

Cask end and side drops (single failure proof crane)

Tipover (excess ively high seismic loads excluded)

Blockage of ventilation openings of storage building Natural phenomena:

Flood Tornado wind & missiles Burial under debris (closed, non -collapsing DSF bu ilding)

Lightning Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 25

Current Concept of Safety Evaluations - DSS Compliance with Safety objectives ensured by DSS Normal conditions:

Ambienttemperatures Storage, Hand Ii ng, 0 rie ntatio n Loading Max. lift height (single failure proof trunnions) 1%fuelrodrupture Cladding Temperature Off-normal conditions:

Off-normal ambient temperatures Off-normal pressure (10% fuel rod ruptur.

with release of 100% fill and 15% fission gase Pressure switch alert Human error, equipment or ins r entation failure, misalignment, lossofpowerfora limited duration, Unintended mechanical loads GNS Proprietary Informa tion withheld per 10 CFR 2.390 Non-Proprietary Version Accident conditions:

Fire~ 5 min and ~ 800°C (max. 200 liters transporter fuel)

Explosive overpressure Tipover (out of balance with no initial velocity bounded by cask end and side drop)

Cask end and side drops (single failure proof trunnions)

Natural phenomena:

Ea rt h quake Technical Meet ing/ 10 CFR 72 CASTOR geo69 DSS/ 26

Current Concept of Safety Evaluations - DSS DSS without connection to any specific storage facility

  • Postulating a generic storage facility Curren t application assumes that the DSS will be housed in the building of a fictitious, non -

existent storage environment Definition of boundary conditions for DSS safety evaluation Design of the DSS

  • Safety evaluations Inclusion of restrictions in the CoC "DSS may only be operated in storage facilities that ensure... "

GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting / 10 CFR 72 CASTO R* geo 69 DSS/ 27

Discussion

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 28

Agenda - Closed Part 11 Background and schedule requirements DSS and CLU Definition and description of configurations Handling operations 11 Concepts of safety eva I u atio n s Concept for CLU Current concept for DSS Alternative concept for DSS Safety evaluations to be performed resulting from concepts and RSI Organized by specialty department:

Structural, thermal, shielding & radiation protection, criticality, containment and material evaluations, operation procedures, acceptance criteria and maintenance program

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 29

Alternative Concept of Safety Evaluations - DSS 11 If current evaluation concept is not accepted by N RC...

Alternative approach by GNS:

Free-field storage of DSS:

@GNS DSS extended by a storage frame anchored on reinforced concrete foundation Fully comprehensive safety evaluations...

according to NUREG-2215, Section 3.5.2.4 Norm al off-norm a I accident conditions natural phenomena

... without taking credit of any installations of the storage facility (building, pad, etc.) are to be performed.

Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 30

Extended configuration of DSS CASTOR geo69 storage cask Cask incl. lid system Canister incl. lid system Basket Protection cover Incl. cable conduit

  • Storage frame GNS extends the current DSS design Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Protection cover Storage cask Storage frame (example)

Technica l Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 31

Alternative Concept of Safety Evaluations - DSS Compliance with Safety objectives ensured by DSF Normal conditions:

M ax. Ii ft h e i g ht (single failure proof crane)

Off-n arm a I conditions:

n.a.

(@) GNS Proprietary Inform al ien withheld per 10 CFR 2.390 Non-Proprietary Version Accident conditions:

Caskdrops (excluded by single failure proof crane)

Natural phenomena:

n.a.

Techn ical Meeting/ 10 CFR 72 CASTOR 111 geo69 DSS/ 32

Alternative Concept of Safety Evaluations - DSS Compliance with Safety objectives ensured by DSS Normal conditions:

Amb ient tern peratures Solar insolation Snow & ice Loading, Handling Transport, Stora Max. lift height (single fa ilure proof trunni 1% fuel rod rupture Cladding temperature Off-n arm al conditions:

Off-normal ambient temperatures Off-normal pressure (10% fuel rod ruptur.

with release of 100% fill and 15% fission gase Pressure switch alert Human error, equipment or ins r misalignment, loss of power for a limited duration, Unintended mechanical loads Proprietary Information withheld pe r 10 CFR 2.390 Non-Proprietary Version Accident conditions:

Fire~Sminand~800°C (max. 200 lite rs transporter fuel)

Explosive overpressure (max. 200 liters transporter fuel)

Tipover (excluded by storage frame)

Cask drops (exc luded by single failure proof trunn ions)

Natural phenomena:

Lightning Flood Earthquake Burial under debris (e.g. by mud flow)

Tornado wind & missiles Te chnical Meet ing/ 10 CFR 72 CASTOR ge o69 055/ 33

Concept of Safety Evaluations - Onsite Transfer Compliance with safety objectives ensured by storage cask Normal conditions:

Ambient temperatures Solar insolation Transfer Max. lift height (single failure proo f trunnions) 1% fuel rod rupture Cladding Temperature Off-normal conditions:

Off-normal ambient temperatures Off-no rm a I pressure (10% fuel rod rup ture with release of 100% fill and 15% fission gases)

Human error, misalignment, Unintended mechanical loads

(@) GNS Proprietary Informa tion withhe ld per 10 CFR 2.390 Non-Proprietary Version Accident conditions:

Fire ~ 5 min and ~ 800°C (max. 200 liters transporter fuel)

Explosive overpressure (max. 200 liters transporter fuel)

Tipover and drop from vehicle Natural phenomena:

Lightning Ea rt h q u a k e Tornado wind & missiles Technical Meeting / 10 CFR 72 CASTOR geo69 DSS/ 34

Discussion Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 35

Agenda - Closed Part Background and schedule requirements DSS and CLU Definition and description of configurations Handling operations Concepts of safety evaluations Concept for CLU Current concept for DSS Alternative concept for DSS Safety evaluations to be performed resulting from concepts and RSI 0 rga n ized by specialty de pa rtm e nt:

Structural, thermal, shielding & radiation protection, criticality, containment and material evaluations, operation procedures, acceptance criteria and maintenance program

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 36

Safety evaluations Structu ra I eva I u ation Thermal evaluation Shielding & radiation protection evaluation Criticality evaluation Containment evaluation Material evaluation Operation procedures Acceptance criteria and maintenance program

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 37

Safety evaluations Structu ra I eva I u atio n

  • Thermal evaluation Shielding & radiation protection evaluation Criticality evaluation Containment evaluation Material evaluation 11 Operation procedures Acceptance criteria and maintenance program

@GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 38

Structural evaluation - Safety Evaluations - DSS NCS Dead weight Handling Normal pressure Normal environmental temperatures Snow and ice loading off-NCS Temperatures beyond normal Off-normal pressure

@GNS Proprietary Inform a lion withheld per 10 CFR 2.390 Non-Proprietary Version

  • ACS Cask drop Tipover (DSS & onsite-transfer)

Fire Explosive overpressure Natural phenomena Tornado winds and missiles Flood (only DSS)

Earthquake Lightning Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 39

Structural evaluation - Safety Evaluations - CLU NCS:

Dead Weight Handling Environmental Temperatures off-NCS:

Temperatures beyond Normal Off-normal Pressure Human error during handling (e.g. slight collision of CLU with service platform)

Equipment failure (e.g. failure of electric cylinder in transfer lock)

@GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 40

Structural evaluation - RSI-St-1: Storage Frame Storage frame is not part of the current application!

Structural evaluation Determines maximum loads resulting from a design basis earthquake that the storage cask can withstand At sites where stronger earthquakes may occur, a storage frame is to be used. It must then be designed according to the requirements of the storage facility and the storage cask, and corresponding evaluations must be carried out.

Thermal evaluations Conservatively, a generic storage frame is assumed to demonstrate that even then no temperatures limits are exceeded.

  • In case of free field storage, storage frames as ITS component will be designed to increase the stability of the casks in the event of a tornado or earthquake.

Either removal or consequently consideration in the entire SAR Rev. 1 depending on the chosen safety evaluation concept.

@GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 41

Structural evaluation - RSI-St-2: ACS & natural phenomena Subject already discussed before.

  • Current concept:

Cask are placed in a storage facility hall without any particular assessment GNS requests CoC with restrictions on instead of specifications of a storage facility hall 11 Alternative concept In case of free field storage all relevant accidents and natural phenomena and their impacts on the casks' performance and safety functions will be assessed.

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 42

r Safety evaluations 11 St r u ct u ra I e v a I u at i o n

  • Thermal evaluation Shielding & radiation protection evaluation
  • Criticality evaluation Containment evaluation Material evaluation Operation procedures
  • Acceptance criteria and maintenance program

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 43

Thermal evaluation - Safety Evaluations - DSS 111 N CS & off-NC S:

Current concept:

Ambient temperature Alternative concept:

Ambient temperatures covered by 10 CFR 71: "cold (-40°C}" and "warm {38°C}"

lnsolation according to 10 CFR 71.71 (full values, not averaged over 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s}

Current and alternative concept:

@GNS Cask standing in an array of casks of the same type with the same heat power; thereby the heat emission by thermal radiation is reduced accordingly Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 44

Thermal evaluation - Safety Evaluations - DSS

  • ACS Current and alternative concept: Fire~ 5 min and~ 800°C (max. 200 liters transporter fuel)

Alternative concept: Tipover Natural phenomena Alternative concept: Burial under debris, flood Tr a n s i e n t h eat-u p u n d e r ad i a bat i c co n d it i o n s ( o u t e r cask s u rf a c e)

Designating the time remaining for countermeasures until the limit temperatures are reached.

Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 45

Thermal evaluation - Safety Evaluations - CLU

  • NCS:

Temperatures during short term operations

  • off-NCS:

Off-normal ambient temperatures combined with 10 % fuel rod failure Ev a I u at i o n s of sh o rt i n t e r r u pt i o n s d u ring o p e ratio n s

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 46 J

Thermal evaluation - RSI-Th-1: short-term, off-normal conditions and ACS 111 Requested additional thermal conditions will be analyzed as follows and provided in Rev. 1 of the SAR:

a.

the unloading condition,

b.

blockage of storage hall ventilation openings obsolete in case of free field storage (alternative concept}

c.

fire while the canister is within the transfer cask, obsolete, fire is not a credible accident for transfer cask handled exclusively in reactor facility

d.

burial under debris, Transient heat-up under adiabatic conditions (outer cask surface} (alternative concept}

e.

tip-over (e.g., thermal effects due to horizontal cask orientation) (alternative concept}

f.

effect(s) of a collapsed storage hall that encloses the CASTOR storage system.

obsolete in case of free field storage (alternative concept}

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 47

Thermal evaluation - RSI-Th-2: Failed Fuel Rods at maximum decay heat

  • Thermal analyses that demonstrate the effect of failed fuel rods at the maximum design decay heat value will be provided in Rev. 1 of the SAR

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 48

Thermal evaluation - RSI-Th-3: Thermal Model Validation Rev. 1 of the SAR will provide the validation reports

@GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 49

Thermal evaluation - RSI-Th-4P: Effective Thermal Properties of FA Rev. 1 of the SAR will provide the calculation methods and results for determining effective thermal properties of the FA

@GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 50

Thermal evaluation - Obs-Th-1: Surface Treatments - cask & transfer cask Thermal evaluations assume certain thermal properties for e.g. emissivity of transfer casks or storage casks I.e., thermal designs of DSS and CLU makes certain demands on the thermal properties of the materials used, to be specified in a fabrication specification Inner and outer surfaces the cask body and the transfer cask are to be coated to provide defined thermal specifications as required by thermal evaluation.

Qualified products shall be used (typically used for transport and storage casks are e.g.

In Rev. 1 of the SAR a qualification report for possibly used coatings will be provided.

Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 51

Thermal evaluation - Obs-Th-2: Vapor and Helium Pressure 11 Pressure during vacuum drying Canister and Cask:

11 At this pressure level, the heat conductivity is not dependent on the pressure so that the heat removal is not affected

  • At a reduced pressure of-in case of a vacuum equipment failure, the heat conductivity is still not dependent on the pressure The helium pressure is discussed in the chapters about the containment evaluation and operating procedures Canister:

Cask:

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 52

Thermal evaluation - Obs-Th-3: Input and Output Files of Thermal Analyses

  • The input and output files of the bounding thermal analyses will be provided.

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 53

Thermal evaluation - Obs-Th-4P: Ambient Temperature

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 54

Safety evaluations St r u ct u ra I e v a I u at ion Thermal evaluation

  • Shielding & radiation protection evaluation Criticality evaluation Containment evaluation Material evaluation Operation procedures Acceptance criteria and maintenance program

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 55

Shielding & radiation protection evaluation - Safety Evaluations - DSS NCS:

Shielding evaluations are performed for both generic building and open-air storage Ambient temperature - "cold" and "warm" casks are considered Instead of 1 % fuel rupture a covering scenario of 3 % fuel rupture is considered Occupational exposure (cask dispatch, storage site)

Occupational exposure (preparation of D55 for storage) off-NCS:

The only relevant scenario to be considered is 10 % fuel rupture For high burn up fuel a credit of an additional 20 a cooling has been taken for the rupture scenario only (according to NUREG-2224: rupture due to storage)

Evaluations of short interruptions during operations ACS and Natural Phenomena regarding shielding result in:

Loss of moderator - very conservative assumption, considered in SAR 100 % fuel damage - considered in SAR

@GNS Proprietary Inform atlon withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 56

Shielding & radiation protection evaluation - Safety Evaluations - CLU II NCS:

Near-field evaluation of the CLU during loading, dispatch, transshipment, etc.

Annual dose at the site boundary off-NCS:

Consequences of the equipment failure or/and human error:

No influence on the CLU shielding capabilities Annual dose at the site boundary with 10 % fuel rupture No increase of the dose rates is expected due to the axially homogeneous shielding design

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 57

Shielding & radiation protection evaluation - RSI-Sh-1: Drawings - Storage cask For design parts lists and drawings the SAR storage refers to the transport application.

G NS intends to resolve references to the SAR (transport) in the Rev. 1 of the SAR (storage)

Thus, in Rev. 1 of the SAR, all relevant design parts lists and drawings will be included in the Appendix to Chapter 1.

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 58

Shielding & radiation protection evaluation - RSI-Sh-2: Drawings - Basket For design parts lists and drawings the SAR storage refers to the transport application.

  • G NS intends to resolve references to the SAR (transport) in the Rev. 1 of the SAR (storage)

Thus, in Rev. 1 of the SAR, all relevant design parts lists and drawings will be included.

Rev. 1 of the SAR will provide a material qualification report for the basket material

@_)GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 59

Shielding & radiation protection evaluation - RSI-Sh-3:

Off-normal, accident and natural phenomena conditions on the CLU Subject already discussed before.

CLU exclusively handled with SN F inside the reactor facility.

Only normal and off-normal conditions to be considered during handling.

  • Accident and natural phenomena conditions are not credible conditions.

Rev. 1 of the SAR will provide the requested evaluations for off-normal conditions

@)GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 60

Shielding & radiation protection evaluation - RSI-Sh-4:

Acceptance & maintenance tests, acceptance criteria Rev. 1 of the SAR will provide further information regarding acceptance tests and criteria of the components in basket plates moderator rods and plates targeting the shielding and criticality safety functions mate ria I qualification reports far the basket material the moderator material L

Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 61

Shielding & radiation protection evaluation - RSI-Sh-SP:

Occupational dose assessment Rev. 1 of the SAR will provide an assessment of the occupational dose during the preparation of the storage cask for long-term interim dry storage the set-up of the CASTOR geo69 DSS at the storage facility

(@)GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 62

Shielding & radiation protection evaluation - RSI-Sh-6P:

Description of Basket Material In Rev. 1 of the SAR, a sufficient description of the basket material added to Chapter 1 will be For design parts lists and drawings the SAR storage refers to the transport application.

GNS intends to resolve references to the SAR (transport) in the Rev. 1 of the SAR (storage)

Thus, in Rev. 1 of the SAR, all relevant design parts lists and drawings will be included.

  • Rev. 1 of the SAR will provide a material qualification report for the basket material

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 63

Shielding & radiation protection evaluation - Obs-Sh-1: Operating Procedures 11 GNS intends to resolve references to the SAR (transport) in the Rev.1 of the SAR (storage) 11 In Rev. 1 of the SAR all operating procedures will be provided in Chapter 9 In Rev. 1 of the SAR Section 9.3 will be reviewed with regard to completeness and supplemented if necessary

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 64

Shielding & radiation protection evaluation - Obs-Sh-2P:

Normalized burnup profiles

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 65

Shielding & radiation protection evaluation - Obs-Sh-3P:

Specifications of Contents

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 66

Safety evaluations 11 St r u ct u ra I e v a I u at ion Thermal evaluation Shielding & radiation protection evaluation Criticality evaluation Containment evaluation Material evaluation Operation procedures Acceptance criteria and maintenance program

@GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 67

Criticality evaluation - Safety Evaluations - DSS Evaluated configurations within the criticality safety analysis:

infinite array of flooded storage casks infinite array of dry storage casks single, fully reflected storage cask N CS, off-N CS and ACS:

The evaluated configurations are bounding.

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 D55/ 68

Criticality evaluation - Safety Evaluations - CLU Evaluated configurations within the criticality safety analysis:

single, fully reflected transfer cask Normal conditions during handling The evaluated case is bounding.

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 69

Safety evaluations Structu ra I eva I u atio n Thermal evaluation Shielding & radiation protection evaluation Criticality evaluation Containment evaluation Material evaluation Operation procedures Acceptance criteria and maintenance program

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR-geo69 DSS/ 70

Containment evaluation - Safety Evaluations - DSS NCS:

No dedicated activity release and corresponding dose calculations (acc. to NUREG-2215) since structural evaluation states that containment remains leak tight acc. to ANSI N 14.5 (design leakage rate< 10-7 ref*cm 3/s)

Activity mobilization inside the canister Pressurization of Containment Vessel off-N CS:

In analogy to NCS, but with adjusted failure and release fractions taken into account.

ACS In analogy to NCS, but with adjusted failure and release fractions for ACS Fire and ACS impact (acc. to NUREG-2224) taken into account.

If applicable, adjustments as a result of e.g. changed temperatures inside of cask and/or canister.

Natural phenomena If applicable, adjustments as a result of e.g. changed temperatures inside of cask and/or canister.

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Tech n ica I Meeting/ 10 CF R 72 CASTOR gee 69 DSS/ 71

Containment evaluation - Safety Evaluations - CLU The components of the CLU (especially the transfer cask) provide no containment function for the SNF. The canister as primary containment for the fuel is not part of the CLU and is evaluated within the DSS containment evaluation.

(@)GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CF R 72 CASTOR geo 69 DSS/ 72

Containment evaluation - Obs-Co-1:

Pressure Switch and Pressure Monitoring System Use of pressure switches is established in Germany (and also in other European countries)

  • Pressure switches are usually commercially purchased and provided by the storage facility
  • In Rev.1 of the SAR Section 1.2 will be supplemented by detailed information (description, functionality, performance specifications and operational requirements) of The pressure switch The pressure monitoring system Corrective actions in case of an pressure switch alert Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting / 10 CF R 72 CASTOR geo69 D55/ 73

Safety evaluations St r u ct u ra I e v a I u at ion Thermal evaluation Shielding & radiation protection evaluation

  • Criticality evaluation Containment evaluation Material evaluation Operation procedures Acceptance criteria and maintenance program

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Tech n ica I Meeting/ 10 CFR 72 CASTOR geo 69 DSS/ 74

Materials evaluation - RSI-MA-1: Basket Material Qualification

@GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Tech n ica I Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 75

Materials evaluation - RSI-MA-1: Basket Material Qualification

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 76

Materials evaluation - RSI-MA-1: Basket Material Acceptance Tests

@GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 77

Materials evaluation - RSI-MA-1: Basket Material Acceptance Tests

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 78

Materials evaluation - RSI-MA-2: FA Alloys The fuel rod cladding is made of Zircaloy-2. Internal water rods and channels as well as outer channels are made of Zircaloy-2 and Zircaloy-4.

In Rev. 1 of the SAR Table 2.1-1 is adjusted accordingly

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Tech n ica I Meeting / 10 CF R 72 CASTOR geo69 DSS/ 79

Materials evaluation - Obs-Ma-1: Technical Drawings - Storage cask For design parts lists and drawings the SAR storage refers to the transport application.

GNS intends to resolve references to the SAR (transport) in the Rev. 1 of the SAR (storage)

Thus, in Rev. 1 of the SAR, all relevant design parts lists and drawings will be included in the Appendix to Chapter 1.

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 80

Materials evaluation - Obs-Ma-2: Classification of Fuel Assemblies Intact (undamaged) fuel assembly means a fuel assembly without known or suspected cladding defects greater than pinhole leaks and hairline cracks, and which can be handled by norm al means. Pa rtia I fuel assemblies, that is fue I assemblies from which fuel rods are missing, shall not be classified as intact fuel assemblies unless dummy fuel rods are used to displace an amount of water greater than or equal to that displaced by the original fuel rod (s).

SAR assumes that the fuel rod failure for different storage conditions from NU REG 2224 are valid for intact (undamaged) fuel rods only. Higher fuel rod failure rates which had to be assumed for damaged fuel are not covered at least for normal and off-normal conditions of storage.

The statement regarding fuel qualification based on requirements for criticality safety, decay heat removal, radiological protection, and structural integrity might be misleading.

SAR Section 8.4.1 describes procedures to ensure that only intact (undamaged) fuel assemblies are loaded.

@GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 D55/ 81

Materials evaluation - Obs-Ma-3: Procurement of Cast Iron Cask Body

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 82

Safety evaluations

  • St r u ct u ra I e v a I u at ion Thermal evaluation Shielding & radiation protection evaluation Criticality evaluation Containment evaluation Material evaluation Operation procedures Acceptance criteria and maintenance program

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 D55/ 83

Operating Procedures - RSI-Op-1: (Un-)Loading Procedures

  • G NS intends to resolve references to the SAR (transport) in the Rev. 1 of the SAR (storage)

Thus, in Rev. 1 of the SAR, loading and unloading procedures will be supplemented to Chapter 10 Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 D55/ 84

Safety evaluations St r u ct u ra I e v a I u at i o n Thermal evaluation Shielding & radiation protection evaluation Criticality evaluation Containment evaluation Material evaluation 11 Operation procedures Acceptance criteria and maintenance program Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 85

Acceptance Criteria and Maintenance Program - RSI-Ac-1:

Pressure & leakage tests of confinement boundaries

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 86

Acceptance Criteria and Maintenance Program - RSI-Ac-1:

Pressure & leakage tests of confinement boundaries

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 87

Acceptance Criteria and Maintenance Program - RSI-Ac-1:

Pressure & leakage tests of confinement boundaries

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 88

Acceptance Criteria and Maintenance Program - RSI-Ac-1:

Acceptance Leakage Test - Cask Body

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 89

Acceptance Criteria and Maintenance Program - RSI-Ac-1:

Acceptance Leakage Test - Cask Body

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 90

Acceptance Criteria and Maintenance Program - RSI-Ac-1:

Acceptance Leakage Test - Cask Body

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 91

Acceptance Criteria and Maintenance Program - RSI-Ac-1:

Acceptance Leakage Test - Cask Bo_dy

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 92

Safety evaluations St r u ct u ra I e v a I u at ion Thermal evaluation Shielding & radiation protection evaluation Criticality evaluation Containment evaluation Material evaluation Operation procedures Acceptance criteria and maintenance program

@)GNS Proprietary Inform alien withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 93

Agenda - Closed Part

  • Background and schedule requirements DSS and CLU Definition and description of configurations Handling operations
  • Concepts of safety evaluations Concept for CLU Current concept for DSS Alternative concept for DSS
  • Safety evaluations to be performed resulting from concepts and RSI 0 rga n ized by specialty de pa rtm e nt:

Structural, thermal, shielding & radiation protection, criticality, containment and material evaluations, operation procedures, acceptance criteria and maintenance program

@GNS Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Technical Meeting/ 10 CFR 72 CASTOR geo69 DSS/ 94

Further Topics?

Proprietary Information withheld per 10 CFR 2.390 Non-Proprietary Version Tech n ica I Meeting / 10 CF R 72 CASTOR geo 69 DSS/ 95

L Non-Proprietary Version 10 CFR72 Application of CASTOR geo69 Dry Storage System G N S G es e II s c h a ft f u r N u k I ea r-S e r vice m b H Technical Meeting

@ GNS

Retrieved from "https://kanterella.com/w/index.php?title=ML22046A028&oldid=3801401"