ML20127J612

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Summary of 921217 Meeting W/Licensee to Discuss Fuel Pool Reracking
ML20127J612
Person / Time
Site: Maine Yankee
Issue date: 01/15/1993
From: Trottier E
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TAC-M85218, NUDOCS 9301250190
Download: ML20127J612 (25)
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UN11 ED ST ATES NUCLE AR REGUL ATORY COMMISSION f

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January 15, 1993

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Docket flo. 50-309 LICEf?SEE: Maine Yankee Atomic Power Company FACillTY:

Maine Yankee Atomic Power Station

SUBJECT:

SUMMARY

OF MEETll1G HELD Off DECEMBER 17, 1992 10 DISCUSS FUEL POOL RERACKif(G (TAC fl0. M85218)

The licensee plans to submit a request to amend their Technical Specifications to allow a third reracking of the fuel pool.

The meeting was requested by the licensee to discuss criticality, thermo-hydraulic and radiological analyses that will accompany the amendment application, currently scheduled for mid-January 1993.

This was the third pre amendment submittal meeting between the licensee and staff.

During introductory remarks, the licensee's Vice President of Engineering and Licensing noted that this reracking will allow full core offload at expiration of the a rrent (original) operating license.

it was also noted that the licensee's goal is NRC's consideration and issuance of this reracking amendment under the terms of no significant hazards determination, as provided for in 10 CFR 50.91 and 50.92.

Toward that end, the licensee stressed that every significant analysis, computer code, piece of equipment, procedure, manufacturing process, and method of installation and removal has been previously approved by the staff for fuel pool reracking at other f acilities.

lhe licensee's manager for each of the disciplines discussed at the meeting (criticality, thermo-hydraulics and radiological) made a presentation.

Presenters identified previous staff acceptance of significant methods, analyses and equipment.

The manager of the radiological discipline noted that the amendment will request an increase to a 6-day waiting period between reactcr shutdown and fuel movement.

(The current limit is 3 days.)

1he staff questioned the licensee on the proposed reracking hoist; possible fuel assembly rerack location errors; contingency plans for core emergency off-load during rerack; fuel pool cooling water inlet, exit and saturation temperaturn assumptions and margin; and the current licensing basis weight percent fuel enrichment.

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9301250190 930115 PDR ADOCK 05000309

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' January 15, 1993 As stated above, the licensee plans to submit their reracking amendment application in mid-January 1993, with completion requested by December 1993.

This schedule will allow material procurement to support fabrication, which is scheduled to begin in July 1994.

Installation is scheduled for Summer, 1995.

/s/

E. H. Trottier, Project Manager Project Directorate I-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Enclosures:

1.

List of attendees 2.

Meeting Handout cc w/ enclosures:

See next page DHIRIILULION wLenc1osures:

^ Docket File 50-309 NRC & Local PDRs PDI-3 Reading J. Linville, RI DISTRIBUTION w/o enclosure 21 T. Murley/f. Miraglia J. Partlow S. Varga J. Calvo W. Butler E. Trottier T. Clark OGC E. Jordan S. Jones N. Wagner L. Kopp V. Beaston ACRS (10)

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NAME TCQ ET h @ mw WButler W f//k/93 0 /f 993 l /t 93 DATE 0FflCIAL RECORD COPY flLENAME: A:\\MY85218. HTS I

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.s January 15, 1993 As stated above, the licensee plans to submit their reracking amendment application in mid-January 1993, with completion requested by December 1993.

This schedule will-allow material procurement to support fabrication, which-is scheduled to begin in July 1994.

Insta)Ation is scheduled for Summer, 1995.

E. H. Trott-ler, Project Manager-Project Directorate I-3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Enclosures:

.t.

List of attendees 2.

Meeting Handout cc w/ enclosures:

See next page v

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Maine Yankee Atomic Power Company Maine Yankee Atomic Power Station CC:

Mr. Charles. B. Brinkman Mr. James R. Hebert, Manager Manager - Washington Nuclear Nuclear Engineering and Licensing Operations Maine Yankee Atomic Power Company Combustion Engineering, Inc.

83 Edison Drive 12300 Twinbrook Parkway, Suite 330 Augusta, Maine 04336 Rockville, Maryland 20852 Mr. Robert W. Blackmore John A. Ritsher, Esquire Plant Manager-Ropes & Gray Maine Yankee Atomic Power Company One International Place P.O. Box 408 Boston, Massachusetts 02110-2624 Wiscasset, Maine 04578-Mr. Uldis Vanags Mr. G. D. Whittier, Vice President State Nuclear Safety Advisor Licensing and Engineering State Planning Office Maine Yankee Atomic Power Company State House Station #38 83 Edison Drive Augusta, Maine 04333 Augusta, Maine 04336 Mr. P. L. Anderson, Project Manager Mr. Patrick J. Dostie Yankee Atomic Electric Company State of Maine Nuclear Safety 580 Main Street

_ Inspector Bolton, Massachusetts 01740-1398 Maine Yankee Atomic Power Company P, 0. Box 408 Regional Administrator, Region I Wiscasset, Maine 04578 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. Charles D. Frizzle, President King of Prussia, Pennsylvania 19406 Maine Yankee Atomic Power Company 83 Edison Drive First Selectman of Wiscasset Augusta, Maine 04336 Municipal Building U.S. Route 1 Wiscasset, Maine 04578 Mr. Charles S. Marschall Senior Resident inspector Maine Yankee Atomic Power Station U.S. Nuclear Regulatory Commission P. O. Box E Wiscasset, Maine 04578

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MAINE YANKEE SPENT FUEL POOL RERACKING PROJELT SAFETY ANALYSIS INTRODUCTION MEETING DECEMBER 17. 1992 NAME ORGANIZATION Bob Jordan Maine Yankee Ed Trottier NRR - Project Manager (MY)

Steve Van Volkinburg Yankee Atomic Peter Anderson Yankee Atomic G. D. Whittier Maine Yankee K. R. Rousseau Yankee Atomic P. A. Bergeron Yankee Atomic R. 5. Bradbury Stone & Webster Steven R. Jones NRR/SPLB Norman Wagner NRR/SPlB Larry Kopp NRR/SRX8 Marshall D. Murphy Maine Yankee Mary Ann Lynch Maine Yankee Virgil Beaston NRR/PRPB l

James J. Raleigh STS Inc.

R. J. Cacciapouti Yankee Atomic l

J. S. Cranston BRAND l-l

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"*"*I MAINF; YANKEE ArrnAt R

safety analysis philosophy ami Ley concepts of the A viY A v spent fuel storage racks, proposed for use at Maine COMPANY v"-

  • To identify the work performed to date and the schedule for future activities leading to a license

"'"d**"' 'abminat SPENT FUEL POOL RERACKING PROJECT

  • To obtata Staff opinions and ideas on license amendment submittal AGENDA l lRERACKING GUIDELINES: -l
  • Pt'RPOSE
  • R. P. Jorden (MY)
  • Use Design Concepts and Technologies Previously
  • PROJECT SC11EDULE. R. P. JarJan [MY}

Re*wed by the NRC

  • CRITICALITY AN ALYSES
  • R. A Canispousl[YAEC) -
  • Use Analysis Methodologies and 1.Jmits Previously
  • T11ERM AL.llYDRA0!JC ANALYSE 3. K. R. Rous

.u ReWwed by ee h7C US CI

  • Maintalo Current Operational Practices at Plant
  • RADIOLOGICAL AN ALYSES R. B. Bradbury [SWEC)
  • Previde Storage Capacity to Reach the Fad of the
  • QUESTIONS & ANSWTRS R. P. Jorden [MY)
  • No Signi6 cant Huard Consideration

-....... - - ~.

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H lPROJECTSCliEDULE l l CRITICALITY ANALYSISj l-Design Introduction Meeting. 10/15/92

. Methodology Safety Analysis Summary hfecting. 12/17/92

  • Region I & 2 Analyses License AmendmentSubmittal.1/93
  • hiedenical Uncertainty Analysis
  • Acdd'"' ^"*I 53' 7

Fabrication Phase - 7/94 5/95

  • *ddi'i "*3 ^"*I "'

I Installation Phase - 5/95 9/95 Disposal Phase &95.&96

[ ANALYSIS METHODOLOGYn-l REGIONTANALYSIS l

  • KF.NO-Va

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  • Pool at 68* F cAssto-3
  • PDQ-7
  • Fresh Fuel e ltenchmarked
  • Used in Pmions Submittals
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%EGION 2 ANALYSIS -l SIECTIANICAL UNCERTAINTY ANALYSIS ~ :'l

  • Pool at 68* F
  • No Creda for Boroa
  • Burned Fuel Cell Wsil Dkkness
  • Azial Effects
  • Bc,rs)= Areal Density (Minimum]
  • Funden of Buruup
  • Borar* Length, Width and ThicL1wss
  • Function of Emkhment "I

' Analyse

  • Actual Cell
  • Fuel EmMment
  • Virtual Cell

[ ACCIDENT ANALYSIS; l l ADDITIONAL ANALYSES l

  • Dropped Assembly
  • Assembly at Side of Ruk
  • Eccentric Posilloa e Assembly at Comer of Rack
  • Effects of Pool Temperature
  • Anume
  • Region 1/Regica 2 Interface
  • Fresh Amembly
  • Berna Credited w

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4 TIIERMAL-EIYDRAULIC ANALYSES = 1

~E pUMMARY

  • CRITICALITY ANALYSES l
  • Prenotation Objecthes
  • Methods Cornistent with Previous Submittals

. Yaraee Spent Fuel PtwJ Analysis Experience

  • Region 1 Accepts Fruh Fuel
  • Thennal-hydraulic Analysis Approach
  • Region 2 Accepts Bunnd fuel
  • Spent Fuel Pool Cooling SystenVDecay lint Lead
  • Accident Canditiorm Analyzed
  • IJmiting Stocage Cell
  • Fuel Pin Coung
  • Loss of Forced Cooling
  • hmmary/ Conclusions TIIEIGIAI IIYDRAULIC ANALYSIS 1 SFP COOLING SYSTEM / DECAY IIEAT LO AD s

-APPROACII -

L (Pst 1]E

  • Speas Feel Pool Cooitng System /Dway lleet Loed
  • Objective.5FP Coding System Analysas
  • Adequery of SFP Coolins System foe Expanded Capacity
  • SpenFeel Poal Cooltan System Capability
  • Methed-SFP Coolias System Analysts
  • IJmiting Cell Analysie
  • Decay beat load.1JBl$ eelt hxselons
  • Spent Fuel Poni Layout
  • 06 loal rmis mainsains conditions < eysaem design
  • Rock Thermal-hydraulle Design Characteristics
  • F4
  • pin Cooling Analysis
  • On-lamst ennartas
  • t.im6 sing Leeel F mel Fia Condition,
  • Normal coes os.had { gf3 ew,1
  • tone of Focad Cedtag
  • I"38 '"' 'U'3**d
  • Spent Fuel Paul Respee. Loss of Cooling Samarbs

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SI'P COOLING SYSTEM / DECAY HEAT LOAD l LIMITING CELL [Part 1)-. l

- [Part 2}i

  • Objectives.1Jmiting Cell
  • Poot byout and Design Sufficient to prevent laeal beilles a Key Assumptiarm SFP Cooling System Analysis

. Dua trspe cooled [ Region 1)

  • Decay heat calculations. BTP ASB 9 2

. Method. Limitins Cell

  • Projected conditions thruegh final off load

. IdentW the ihnhine eilt resto.

  • Melllenkins celts. 2D RETRAN Model
  • Results SFP Cooling System Analysis
  • Lhuins feet att thennal+ydr =lle ew.didons

' 5FP Cooling System operated within design

  • Ents tempereaure conditions
  • Boutulary conditions for the pin cooling analysis
  • Void haetion
  • Conlant flow este i -

lI+1MITING CELL [Part 21/J.

l LIMITING CELI;[Part3hl Key Assumptions. Umiting Ceu Results Umiting Cell

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  • Flow patterim in the SFP an 3 D
  • M "U 0"
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  • 2 D model credits spacing bdween th* rack aml
  • Region 1 and Region 2 rack design -

the pool wad for downcomer Gow

  • Cornervatin assembly radial peaking factor
  • Adequacy of flux trap cooling path
  • Pool bulk tempersten design conditions
  • Impact of partially blocked cells
  • Boundary conditions for lor.al pin cooling analysis
  • Pool bulk volume
  • weG mixed
  • Downcomer/eeu inlet temperatun at bulk temperature e

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[ FUEL PIN COOL,1NG [l' art 2lc j

[ FUEL PIN COOLING {1%rt 11 - l

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  • Objective Fuel 14n Co=Jhg
  • st.st mee hear e aduethm/vaa**etian
  • Adequate canding for the limiting fuel plo

. con r,mi, bx.i pin r ta.1 p..ndas f ad*e e AW shapes

  • No localised boiling in the limiting cdl a Chopped ensine [BOCl
  • Method. Fuel lin Cooling e nes tEOC)
  • ltEf RAN boundary conditioem from lindung nil

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. steds. Fuel ria Caollag

  • Determine limiting fuel pin temperatures e P, h fuel p6a surfees tempermure 1,OSS OF FORCED COOL ING (Part 1]:- l LOSS OFFORCED COOLING [Part 21 l
  • Objetlives
  • Partial Loss of Conting
  • Whods

= Normal [UJ) con off load sunati,

  • Partial Less of Cooling
  • Peak temperatun < cooling system dnign tempe retute

. If est balauce

  • Full core off-loed scenario e Complete Loss of Cooling No bulk bollks in pad
  • Tiene to bulk gnwd boilhg
  • Complete Less of Contint
  • Maximum build randmakeup requinment
  • Suffklent time to establish ehernate cooling, of
  • Sumelent makeup avaBable

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  • Key Assumptions
  • Lms of Forted Cooling
  • Conservative pool initial heat load
  • Stethods Comistent with Previonshbmittals
  • Silnimum pel initiallevel
  • Onniew of Analysis Approach a Resulta = loss of Forced Cooling
  • SFP cooling system adequacy
  • Partial loss of coding
  • Peak system temperature
  • Poollayout and rack des 6gn provide local cooling

.Comi ete lost of c= ling

  • Addren loss of cooling s<enaries J
  • Minimum time to bulk bdling
  • Puoi twantf rase / makeup requirements

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lRADIOLOGICA1, ANAL,YSES l lRADIOI,0GICAL ANALYSES'[Part 21? - l

  • POSTt'LATF.D ITEL IIANDLING ACCIDENTS
  • LIMmNG CASE ACCIDENTSCENARIO
  • Dropped Fuel Assembly
  • Fuel Asumbiks Remain Un.wgd
  • All Fuel Rode la Dropped Assembly Fail on impaci
  • A11 Noble Genes & Halogens in Gap Released so Feel a Fuel Handling Procedures a el Equipment Puni Unchanged
  • Dropped Fu.i Ammbly Recentty D&hersed from Care end Fully Bvened
  • Source Term Unchanged
  • Release to Atmosphere it.rench Fuel Buildins Ventilauan Syntan

[lI ADIOLOGICAL ANALYSES [Part3) :l

  • CONClf510N
  • Reracking does not affect existing postulated Questions & Answers scrident consequences.
  • Doses at the site boundary and control recen for current licerming bests rernain valid.

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CLOSURE

  • NEUTRON ABSORBER CHANNEL REGION 2 CONFIGURATION g.

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YANKEE SPENT FUEL POOL ANALYSIS EXPERIENCE o

PREVIOUS SUDM11TALS USING YANKEE METHODS f.hfgg}l$$$'$5!3i@$$3g*[y$[j D$f

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SERil3E@RENCEmp Maine Yankee increase in stomge capacity.

Amendment No. 70 to Maine (50-300)

Limited fuel consolidation.

Yankee Technical Specifications Vermont Yankee increase in storage capacity.

Amendment No.104 to Vermon' (50-271)

Yankee Technical Specifications Yankee Rowe increase in stosage capacity Amendment No. 75 to Yankee

( 50-29) using double tiered rack Rowe Technical Specifications desi n.

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THERMAL-HYDRAULIC METHODS CONSISTENT WITH PREVIOUS SUBM11TALS o

APPROAClf CONSISTENT WITH NRC POSITION PAPER "OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications",

issued April 14,1978 (later amended on January 18,1979)

MAINE YANKEE Scent Fuel Poc! Flow Pattems[Umitira Locations g' "WPMFm"mmmmmmstanWPJMEM"xm"BFEMW3mS]

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)O00000 0000000 0000000 0000000 0000000 0000000 0000000 0000000 0000000 OOAOOO OOOAOO OOAOOO OOOA OO OOVOOO OOO VOO OOVOOO OOOVOO 0000000 0000000 0000000 0000000 0000000 0000000 000000C OQ_OOOOO i

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