ML072970889

From kanterella
Jump to navigation Jump to search
Meeting with Portland General Electric Company Regarding Response to the First Request for Additional Information for the Trojan Independent Spent Fuel Storage Installation Application
ML072970889
Person / Time
Site: Trojan  File:Portland General Electric icon.png
Issue date: 03/21/1997
From: Reid D
NRC/NMSS/SFPO
To: Kane W
NRC/NMSS/SFPO
References
NUDOCS 9703260004
Download: ML072970889 (48)
v • d • e


Text

72-47

%Lfto REGo UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 21, 1997 C

MEMORANDUM TO:

William F. Kane, Deputy Director Spent Fuel Project Office, NMSS FROM:

Dennis G. Reid, Project Manager Spent Fuel Licensing Section Spent Fuel Projec:t Office, NMSS

SUBJECT:

MEETING WITH PORTLAND GENERAL ELECTRIC COMPANY REGARDING RESPONSE TO. THE FIRST REQUEST FOR ADDITIONAL INFORMATION FOR THE TROJAN INDEPENDENT SPENT FUEL STORAGE INSTALLATION APPLICATION On February 26. 1997, a management and technical exchange meeting was held between representatives of Portland General Electric Company (PGE) and its associated contractor and the U.S. Nuclear Regulatory Commission to discuss PGE's application to construct and operate an independent spent fuel storage installation (ISFSI) at its Trojan facility. Attachment 1 is an attendance list. is a copy of the slides presented by PGE.

The meeting was noticed on February 10, 1997.

The discussions included the application review process, but focused primarily on technical issues that resulted from PGE's response to the NRC request for additional information (RAI) issued to PGE on November 25. 1996.

The technical issues discussed included:

basket coatings, pad design, transfer station seismic structural analysis, basket decelerations under drop conditions for 10 CFR Part 72, criticality, fuel cladding temperature limits, the fuel debris program, and ISFSI operating procedures. Other licensing topics discussed were site construction, component fabrication and related quality assurance controls at PGE's, vendors, and interfaces between 10 CFR Parts 50, 71, and 72.

The staff noted that the licensee still needs to address a number of technical issues for the.staff to perform its, license review. For example, the basket coating is yet to be defined, the transfer station drop analysis was incomplete, no calculations were furnished for the transfer station's foundation, and the safety significance of the transfer station's pad has not been defined.

The staff raised concerns regarding PGE's design of the concrete storage pad.

Specifically, the method used to develop the design basis drop accident was unclear, and the drop weight could not be corroborated by the technical staff, even when using PGE's information.

Also, the staff questioned PGE's approach of using probabilistic methods for analyzing the tornado missile impact on the transfer station.

PDR ADDCK 05000344 NRC FILE CENTER CRPY I

w.

POR X

W. Kane an office policy may be needed. In light of these discoveries, PGE's construction schedule may be impacted.

The current schedule states that the concrete pad lay-out will commence !in mid-March 1997 and be poured by the end of April 1997.

PGE plans to respond to the issues discussed during the meeting. A representative from Oregon's Office of Energy attended the meeting.

A member of the public attended the non-proprietary portion of this meeting.

Proprietary information was discussed at the technical exchange portion of this meeting, however, no proprietary information was disseminated. No regulatory decisions were requested or made.

Docket 72-17 Attachments:

1.

2.

Attendance List PGE Slides Distribution:

Dockets 72-17 SFPO R/F EEaston WReamer, OGC w/o attachments (50-344)

NRC File Center SGagner,OPA JJankovich VEverett, RIV PUBLIC PEng LPittiglio SMirsky, SAIC NMSS R/F SShankman MMasnik, NRR NRC Attendees rI9FC SFPO SFPO SAT SFPO IC I

I 4

I ZZ..

4 I

I DReid I VThQ'

'e '

EJLeeds v I

eJ 97

-, I '~/ 1 197 1 I3j~D 97 1

L '

LUVK OFFICIAL REC LUVL' K & tLNLLUUK N - mU bur ORD COPY G:\\TROJAN\\PGESUMRY.NTG 3/21/97

dd

ATTENDANCE LIST MEETING BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PORTLAND GENERAL ELECTRIC COMPANY FEBRUARY 26, 1997 ORGANIZATION NAME Charles J. Haughney Susan F. Shankman Fritz Sturz Dennis G. Reid Lawrence E. Kokajko Michael Franovich David Tang Steve Hogsett Thomas Matula Donald E. Carlson K. C. Leu C. G. Interrante Lee Thomas Mike Masnik H. Ray Pate Dan Gildon Mike Lackey Stephen Quennoz Ted Bushnell Chris Dieterle L. R. Walker Jay Rollo Bill McConnaghy David Williamson John Stokley Steve Mirsky Roy Karimi Adam Bless Robert E. Sweeney NRC/NMSS/SFPO NRC/NMSS/SFPO NRC/NMSS/SFPO NRC/NMSS/SFPO NRC/NMSS/SFPO NRC/NMSS/SFPO NRC/NMSS/SFPO NRC/NMSS/SFPO NRC/NMSS/SFPO NRC/NMSS/SFPO NRC/NMSS/SFPO NRC/NMSS/SFPO NRC/NRR/PDND NRC/NRR/PDND PGE PGE PGE PGE PGE PGE PGE Sierra Nuclear Sierra Nuclear SAIC SAIC SAIC SAIC Oregon Office of Energy IBEX ATTACHMENT 1

-~

TROJAN ISFSI APPLICATION NRC m-PGE MANAGEMENT MEETING FEBRUARY 26, 1997

AGENDA TITLE:

NRC Management Meeting for the Trojan ISFSI Application Opening:

Dennis Reid, NRC Project Manager, Trojan ISFSI Charles Haughney, Acting Director, SFPO Eric Leeds, Section Chief; SFPO Project Overview: Stephen Quennoz, Trojan Site Executive Project Schedule:

Michael Lackey, General Manager, Engineering and Decommissioning 0

a Site Constructi.on and Component Fabrication Preoperational Inspections and Testing Licensing Activities Communication:

Ray Pate, Manager Licensing, Compliance and Commitment Management S

S S

10 CFR 50, 72, and 71 Interfaces Review Process PGE-NRC Expectations ISFSI Safety Analysis Report Revisions Status of State ISFSI Review Technical Topics:

Dan Gildow, Manager Decommissioning Planning 0

0 0

S S

0 Basket Coatings Pad Design Transfer Station (including Seismic Structural Analysis)

Basket Deceleration Under Drop Conditions for Part 72 Criticality Fuel Cladding Temperature Limits (Methodology/Assumptions)

Fuel Debris Program Procedures for Cask Loading ISFSI Operating Procedures

AP TROJAN NUCLEAR PLANT Independent Spent Fuel Storage Installation Project Overview Stephen M. Quennoz Trojan Site Executive

I.-.

[e i

Trojan Decommissioning Schedule

/ /2015 2016 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2017 2018 2019 Permanent Shutdown D-Plan Submittal NIOftsIA~ok Ap...-.va of D-Plan Large Component Removal Project Reactor Vessel Removal Project ISFSI Loading Full Scale Dismantlement Final Radiation Survey Non-Contaminated Building Demolition I

I I

I II II II I

IIIIIIIIIIIII III II I

I I I

I I

I I

~I AI

~I a

I IIIIIIIII

. I I

I I

I I

I I

I I

I I

l I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I 1=

I I

I I

I I

I I

a S

I I

IIIIII I

I I

i I

I I

I I

I I

III I

I I

II i

I I

. I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I a

I I

I I

I a

I I

I I

I I

I I

f ISFSI PROJECT IMPACT OF DELAY

  • DELAYS FULL SCALE DISMANTLEMENT PERIOD

. Potential loss of key personnel

. Current LLRW disposal site rate agreement expires in 2001

  • EXTENDED WET STORAGE PERIOD

. Adds > $6 Million annually to estimated costs

e-

'4 ISFSI PROJECT HISTORY

  • STORAGE ONLY SYSTEM INCORPORATED INTO INITIAL DECOMMISSIONING STRATEGY AND INITIAL COST ESTIMATE
  • DISCUSSIONS WITH NRC INDICATED DECOMMISSIONING OF SPENT FUEL POOL WOULD REQUIRE A TRANSPORTABLE SYSTEM
  • BEGAN PREPARATION OF A BID SPECIFICATION 03/01/94
  • ISSUED BID SPECIFICATION 09/29/94
  • AWARDED CONTRACT TO SIERRA NUCLEAR 06/05/95
  • SNC SUBMITTED IOCFR71 APPLICATION 12/20/95
  • PGE SUBMITTED 10CFR72 APPLICATION 03/28196

ISFSI PROJECT OBJECTIVES

  • SAFELY STORE TROJAN SPENT NUCLEAR FUEL

. Intact Fuel with control components

  • Failed Fuel
  • Fuel Debris
  • FACILITATE DECOMMISSIONING
  • ALIGN WITH DOE FUEL STRATEGY (MPC BASED)
  • MINIMIZE TROJAN SPENT FUEL POOL MAINTENANCE COSTS
  • PREPARE SPENT FUEL FOR EVENTUAL DOE ACCEPTANCE

r, 0

f v

A-

"I ISFSI PROJECT DESCRIPTION

  • SNC TRANSTORTM SYSTEM
  • 24 assembly storage basket with double seal-welded stainless steel shell
  • Steel-lined thick walled concrete vertical storage casks
  • IOCFR72 SITE SPECIFIC LICENSE FOR STORAGE
  • DESIGNED TO BE COMPLETELY INDEPENDENT OF SPENT FUEL POOL ONCE LOADED
  • Off normal overpack

. Transfer station

  • IOCFR71 LICENSED TRANSTORTm SHIPPING CASK FOR EVENTUAL OFF-SITE TRANSPORT

no Du 0

o0 O

h -'

THE VENTILATED STORAGE CASK THE SEALED BASKET (PATENT PENDING)

THE TRANSFER CASK TranStorT"I SYSTE:.M COMPONENTS

S I I k

I PGE ROLE IN ISFSI DESIGN FABRICATION AND CONSTRUCTION

  • PGE REVIEWED AND APPROVED SNC QA PROGRAM
  • PGE PERFORMS QA AUDITS, SURVEILLANCES, AND QC INSPECTIONS OF SNC, SNC SUBVENDORS AND FABRICATORS
  • PGE REQUIRED VALIDATION PACKAGES FOR ALL SNC CALCULATIONS
  • PGE REVIEWED AND CONCURRED WITH ALL CALCULATIONS AND DESIGN DOCUMENTS
  • PGE VALIDATED ISFSI SAFETY ANALYSIS REPORT (SAR)
  • PGE REPRESENTATIVE ON-SITE AT SNC OFFICE
  • PGE DEVELOPING ALL PROGRAMS AND PROCEDURES FOR TESTING, LOADING AND OPERATING THE ISFSI
  • PGE MANAGING PAD CONSTRUCTION AND SECURITY SYSTEM INSTALLATION
  • PGE RESPONSIBLE FOR BASKET LOADING AND HANDLING OPERATIONS

.W-f PROJECT SCHEDULE Michael B. Lackey General Manager Engineering and Decommissioning

2 1 LU



7i ':%J i-

i. 1 " i nt J.

if4-;1Af:4t 1:44A fA iiiJ:4i:ii

L:1 1 6LL 4LLLLU t

I __

Grao Ing A Leveling 1 I3 P id Constructlb Roadbulk O

IJUAPR97 SlteIRoads bIg

,,rsr I14MAY97 e,,,

Z l

l l

l l

.I

-. ~::::,

II0

afvmtm, 1

I I

i 1

11

._w_...._

.- I.-.....

'97 30SEP97 16JUN97 Security 3yste Installs I

, u r I - F e n c e I n s t a l_

8ecuri Fenee Instalt tion & Test Mon 22APR97 Select Fatn Icaor & Order Miateral - Bask s 08JUL97 07APR96 I Fabricate - Ba skets C o crt* C as a r c t o 29APR97 Select Fat s*car & Orde Mateni

- CC I jnems 14JUL97 04SEP97 Fabrcate.

Liers 29JUL97 3Select Fat ricator & Orde, Material - CC 09SEP97 09JUN98 S

Construction 4 Yt Concrete Ca ks Tra f, E quI

.lt::,.

O1APR97 Selectk Fabrlia or & Order Ma eral TC I TC Y >ke 22APR97 Select Fablca

& Order ateril - TS 21MAY97 18SEP97 Fa n-TC 03JUN97 07JUL97 la

-TS 24JUN97 22SEP97 lbrcate-TC Yke 08JUL97 27AUG97 Construct Tr nsfer Station

4.

§ w Ft

'7 ISFSI pi Deed n4et 14NOV98A 02SEP97 t

gf

_ ~-

IBJAN97A 27MAR97 FE Crne M tIntenance and Inspections 02APR97 17APR97 Fuel Bldg. Cra we Load TestLad Cekrtfat 24JUL97 t8SEP97 Instal impg t ULr plete Fueld Prep 2WiAN97A IOMAR97 F eF Inspec Ion ftack i l.n~a

&S SPP orCeau I2WUN9r 10JUN97 Sing SF Rack Rer wal 0iUN97' ItJt!Ln7 SPF Floo Cleanup (Vaccum) 16MAY97 23UL97 Spent el Filter Pnm ssIng

_ _ 02SEP97-1SF I Specialists Q altifled & S d

03SEP97 30OCT97 PC p TraIning 23SEP97 30OCT97 onduct PreOp resting 05JAN98 Commence Fuel Lod OSOuFd

i /

P..

LL Li LU

§l ss l Bs f l\\}l slA ll l

r lubmital to 4RC Revlei NRC

- Prepare 29MAR98A 27N0V9MA 20NOV98A 27NOV9A 02DEC98A 24DEC96A I13FE897A Ir n -

St Round Secu O

App Res tAI rov pot btan In lot En ito NV Revis O

erlm Appr wironmento IC 1st Rou ed SAR Su val I Report id RAI Emitted 01DEC97 Pa 0

72 ULnms Received InNC-PadCyA

.NC -Patt T1 Approv 30MAY96A Sut mIttal to NV IC 16JAN97A O A 237 sevslon S bmittal L5APR97 A

pprovaoPart 50 CA-237 Put50 I'~ ea t'Load.

LCA-24)':-'_

S1BJAN97A P rt60L GA-2401ssi ed 01APR97 pproval Part 50 LC A-240 23OCT96A Submft Il to NRC 27NOV9eA Sub mIt evise ISAR (LC -239)

.31 MAR97

_pproval 0t LCA-239 u-1106

F

e-L-

V k

_.#._0.,

Sbtil Flnisk

=

i=i

-=

g Sa I

J I

D I J I

, lI M I

JlA.

I 0 I N l o J I FJ I A

_._IA:_3____

LJ.

II.

.t. iL.L.LLLi 'LL.L JJi U+/-L lL I.t.l0l Part 50 Partial Sib Re eas (R0374)

I00CT96A-Submit Sur Rel or to NRC 27NoV98A Sur epot kpproval Part 50 Exdude ISFSI F frt,(LCA-242)

_ 2FEB97 Part I 0 LCA-242 ssued

_ 1DEC97" Ap attl of P rt LCA

°>

Baskt Fbonkf IOMAR97 Id ntlfy Rema Ining Basbi Technic Issues 11MAR97 21APR97 R solve Rem Ining Basi et Techn I Issues CTnerc Case Fbricatin 17MARE9 Id ent Rem Ining CC T Yoe Tech i sues 18MAR97 1MAR97 Re Rmal nng Ln r Tech I

sst es 710UM 1

IntIAy7Rem RMingeCee Tech Is nsTP 17JUN97 128UL97 R

solve Rem gning TCas Tech lst es Trarnfer E qpj~xfwoM Fbon

!er 17FEB97-

  • Ident fyRemaini ig TC & TQ Yoke Tec h Isues 18FEB97 131MAR97 llResc IvaRemai Ing Techh Isues -TC fk IS8FEB97 IO0MAR97 llResc vRemaln ng Tech Is sues -TC I

0OMAR97 *ll Identify Remsning Trani 'or Station rech Isue 1 1MAR97~

121APR97 l

Rt sove RemMning Tran 10erStatior TechhIsu t

AK A&

a, I

CC COMMUNICATIONSi Ray Pate Manager Licensing, Compliance and Commitment Management

t

F ffk I

ISFSI INTERFACE Successful ISFSI Licensing PART 50 PART 72 PART 71

I I

PART 50

  • LICENSE CHANGES ADDRESS REQUIREMENTS FOR SAFELY LOADING SPENT NUCLEAR FUEL AND TRANSFERRING IT TO THE ISFSI

. LCA

  • LCA

. LCA

. LCA 237 239 240 242 CASK LOADING SFP DEBRIS PREOPERATIONAL TESTING ISFSI FOOTPRINT

i :

AO i-9 PART 50 PROCEDURES

  • INTERFACING PART 50172 PROCEDURES
  • CERTIFIED FUEL HANDLERS TRAINING PROGRAM
  • FUEL TRANSFER &

REFUELING EQUIPMENT CHECKLIST

. FUEL MOVEMENT PREPARATION

  • SFP BRIDGE CRANE OPERATING INSTRUCTION
  • SPENT FUEL ASSEMBLY HANDLING TOOL OPERATING INSTRUCTION

. ISFSI FUEL LOADING PLAN SEQUENCE

  • OFF-NORMAL AND ACCIDENT CONDITIONS e FUEL HANDLING EMERGENCY PROCEDURES

. CASK DROP IN THE FUEL BUILDING o PRESSURIZED LINE RUPTURE

  • VACUUM DRYING TIME EXCEEDING ADMINISTRATIVE LIMITS
  • VACUUM DRYING SYSTEM

-I-I f I je if V

V k

I PART 72

  • SITE SPECIFIC LICENSE UNDER PART 72
  • OPERATIONAL CONTROLS ARE DEFINED IN ISFSI PROGRAMS AND PROCEDURES

.fi e i

p PART 72 PROGRAMS AND PROCEDURES m

  • PROGRAMS o RADIATION PROTECTION
  • ENVIRONMENTAL AND EFFLUENT MONITORING
  • FIRE PROTECTION
  • TRAINING
  • SECURITY PLAN
  • CASK HANDLING AND STORAGE
  • STRUCTURAL INSPECTION
  • PROCEDURES

. PHYSICAL SECURITY

  • RADIOLOGICAL EMERGENCY
  • FIRE PROTECTION
  • MODIFICATION CONTROL

. TRAINING

  • OPERATION AND SURVEILLANCE

. WASTE CLASSIFICATION, LOADING SEQUENCE AND INVENTORY

. OFF-NORMAL AND ACCIDENT

. MATERIAL ACCOUNTING RADIATION PROTECTION

ZV I "I I

PART 71

  • PART 71 TRANSTORTm BASKET WILL BE USED AT TROJAN FOR PART 72 STORAGE
  • SNC MUST SUCCESSFULLY OBTAIN CERTIFICATE OF COMPLIANCE FOR THE PART 71 TRANSTORm SYSTEM
  • ASSURES PGE OF EVENTUAL TRANSPORTATION TO U.S. DOE HIGH LEVEL WASTE FACILITY

N ii ISFSI SAFETY ANALYSIS REPORT REVISIONS

  • DESIGN REVIEWS
  • Revisions as a Result of Part 72 Regulatory Review

. Revisions as a Result of Transtorm Part 71 Regulatory Review

  • FABRICATION

a f

I

'v I

REVIEW PROCESS PGE AND NRC EXPECTATIONS

  • ISFSI PROJECT IS PGE'S MOST IMPORTANT DECOMMISSIONING PRIORITY PE HkAS A D S AwH iCmH%.m FACILITATES PROMPT RESPONSE TO NRC QUESTIONS AND CONCERNS
  • PGE SUPPORTS COMMUNICATION WITH REVIEWERS REGARDING TECHNICAL ISSUES
  • NRC SUPPORT OF PROJECT MILESTONES

1 X

STATE ISFSI REVIEW

  • PROCESS
  • Purpose
  • Capacity and Safety Standards

. Alternative Spent Nuclear Fuel Storage

  • Other than SFP Requires Rule Change
  • ISFSI 11 Subsections concerning areas of Design, Cask, Radiation and Effluent Monitoring, etc.
  • Report Requirements
  • CURRENT STATUS

II--

J-i ISFSI TECHNICAL TOPICS Daniel C. Gildow Manager Decommissioning Planning ISFSI Project Manager

BASKET COATINGS I

  • BACKGROUND
  • SELECTiON

. 3 Coatings

  • PGE QA Oversight
  • TEST SCHEDULE

. Boric Acid Immersion Scoping Test (Room Temp) Complete

  • Radiation Tolerance Test Complete

. High Temperature Qualification Test 03/14/97

. Boric Acid Immersion Test (Elevated Temp) 04111/97

  • INCORPORATED INTO DESIGN 06101197

lk v

v

(

I IF A

D ISFSI PAD DESIGNl

  • FOUNuAITiON' RUC
  • ACCESS ROAD
  • DESIGNED TO WITHSTAND SME (0.38g)
  • PGE QAlQC OVERSIGHT OF CONSTRUCTION

A-v I..

I

-in------.

H----

, I". _, _

1 H - --- t Few-.-

I I. 1

_w I i.'

I I 00000 00000

/I -,

FtEC'PtC*q M" Isrst Si 00000 00000 00000 L!

ACCESS FENCE ISFSI L

CONTROL POINT AUXILIARY BUILDING CONTAIN WSH WAREHOUSE z

0 crU M m

1+/-.

CONTROL BUILDING

if o

  • I.

TRANSFER STATION DESIGN omI

  • BACKGROUND
  • PURPOSE -- PROVIDES TDALI00MM fAOuf I F% 1%;rLF %aplO
  • IMPORTANT TO SAFET
  • STEEL FRAME STRUCT'

. ASTM A36 Framing

  • ANCHORS
  • SLIDING COLLAR HORIZONTAL SUPPORT FOR

REMOVABLE SIDE

-COLLAR STOPS SLOING COLLAR TRANSFER CASK

","TRANSFER CASK TRANSFER CASK--,,,,,,

CASK

Ez V

,1.-

\\-d TRANSFER STATION SEISMIC STRUCTURAL ANALYSIS

  • SEISMIC EVENT (038g SME)
  • HORIZONTAL FORCES (0.5g FOR TRANSFER CASK AND FRAMING)

.,1. I

  • AISC STEEL CONSTRUCTION MANUAL

(k

(

TRANSFER STATION MISSILE IMPACT ANALYSIS

  • ERIN ENGINEERING
  • MISSILES
  • RESULTS I

i ^.

BASKET DECELERATION FOR DROP CONDITIONS

  • METHODOLOGY - EPRI NP-7551
  • TARGET HARDNESS
  • LIMITING DECELERATIONS

. i V RESULTS AND CONCLUSIONS

  • DROP LOADS
  • Concrete Cask 28.2g
  • Shipping Cask 58.7g
  • BASKET END DROP LIMIT 124g

( - -

I CRITICALITY

  • WET BASKET LOADING (PART 50)
  • Part 50 LCA-237

. New Trojan Specific Calculation

. No Credit Taken For 2000 PPM Borated Water

  • DRY STORAGE PERIOD (PART 72)

Trojan Specific Calculation

. Criticality Controlled by Geometry (Ken <41)

  • No Credit Taken for Boral

. No Long Term Efficacy Program Required

  • TRANSPORTATION (PART 71)
  • SNC Part 71 Submittal

. Generic Calculation captures Trojan Fuel

  • Boral Credited for Criticality Control
  • Functionality of Boral

1pIk a

'-7 FUEL CLAD TEMPERATURE LIMIT CALCULATION

  • DESIGN THERMAL LOAD
  • TROJAN ADMIN LIMIT
  • METHODOLOGY o PNL 6364
  • 40 GWD/IMTU, 5 Year Cooled
  • 705 Degrees F 26 kW 24 kW

I i

a lwo~

a A(

Iti FAILED FUELIFUEL DEBRIS PROGRAM

  • BACKGROUND e LCA 239
  • COMPONENTS
  • Failed Fuel Can
  • Process Can
  • Process Can Capsule
  • PACKAGING INTERFACE

MED04 INCONEL FILITR MEEA:

INCONEL ODTAIL 6 PROCESS CAN (IAtEq:rA STAINLrSS SrEEL)

'la4 Ili*

SPENT FUEL TOOL INTERrACE

  • 6 50' MAX O.0
  • 8 OO I.0 WELD JOINT SHIELD PLUG TO SHELL 7.27-FTi l

PROCESS CAN l

SHIELD PLUG, STAINLESS

/fiSTEEL WTH SCHRADER PURCE h

AND BACKFlLL PORT VALVE 16D.0' MAX 1.3.D0 8.75'

.LJ P RO0CE SS L

CAN CAPSULE WI'" s OLa

...C

i.. I CASK LOADING PROCEDURES

  • IMPACT LIMITERS/SAFE LOAD PATH
  • OPERATIONS IN THE CASK LOAD PIT
  • Load Fuel As5embhies
  • Place Shield Lid
  • OPERATIONS IN THE CASK WASH PIT
  • Draining

. Drying

  • Backfilling
  • Welding
  • BASKET TRANSFER TO CONCRETE CASK
  • STARTUP TEST
  • MOVE CONCRETE CASK TO PAD

^

^ j SPAC1 1

1 0 l 3 X 3'-3' L- -

c:13)'I CASK WAS PIT I

I il3X13 I-I i3 h 1X C

,EL 72'-S0 1

- L EL.93c-O EL.67'-P 7 rnHOISTWAY JiJt Q

PRTN

~O TPaIRCS~

(iC)ASK LOAD

(/1i FUEL POOL FIGURE WITHHELD UNDER 10 CFR 2.390

ISFSI OPERATING PROCEDURES

  • CASK MOVEMENTS ON PAD
  • BASKET TRANSFER o

To Ovellrpll ackr

  • To Overpack
  • SURVEILLANCES/INSPECTIONS

1 ki+F - m B]iidL jnind (V, ;!240 mph)

A Wood'Plank B 6" Sch 40 pipe C 1" Steel rod D Utility poie E 12" Sck 40 pipe F Automobile 114.40 2K6 3.8 1122 748 3982 3.62"xl 1.38"xl2.0' 6.61"oxl5.03' 1ox3.12' 13.50"ox35.04' 12.60"oxl5.03' 16.41'x6.56'x4.27 Vm mm) 190.24 32.80 26.24 85.28 22.%

134.48 Vertical velocities shall be taken as 70% of the postulated horizontal velocities. Except for missile C above mch sdall be assumed to have the same velocity in all directions. Missiles A, B, C, and E we to be cmidered at all elevations and missiles D and F at elevations up to 30 feet above grade level.

Trojan Missiles (V, = 200 MW

1) Wood Plank 128#
2) 3" Sch 40 pe 75.
3) Automobile 4N0W (G 25' above pade) 4"x12"x12.0' 3.50"oxl O.0' 293.33 ft/sec 110.00

/sOc 58.67 RNsec

-7 

7 Az 7-25'rW14) 2 r. ---- 

22

_C; MMM7 Askkfr-47ew17lM1'J -

  • OrT/O I-:-o ".KAW,
2EcgMo~ef5 I

Sy.

, JX -TAR

-. 75f57Z.

-ZZ574e0

_

Retrieved from "https://kanterella.com/w/index.php?title=ML072970889&oldid=5339367"