ML17229A565

Summary of 971125 Meeting W/Florida Power & Light Co Re Plans to Request NRC Approval of License Amend to Allow Credit for Soluble Boron in Unit 2 SFP in Order to Increase Pool Storage Capacity.List of Attendees & Handouts Encl

ML17229A565
Person / Time
Site:	Saint Lucie
Issue date:	12/16/1997
From:	Wiens L NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9801050224
Download: ML17229A565 (30)

Text

December 16 997 LICENSEE:

FACILITY:

SUBJECT:

Florida Power and Light Company St. Lucie, Unit 2

SUMMARY

OF HEfTING ON NOVEMBER 25.

1997, REGARDING PROPOSEO USE OF SPENT FUEL POOL SOLUBLE BORON CREDIT - ST.

LUCIE UNIT 2 On November 25,

1997, representatives of the Florida Power and Light Company (FPL), licensee for St. Lucie Plant, Unit 2, met with members of the Nuclear Regulatory Commission (NRC) staff to discuss plans to request NRC approval of a license amendment to allow credit for soluble boron in the Unit 2 spent fuel pool (SFP) in order to increase the pool storage capacity.

The FPL representatives provided a summary of the methods to be used to support the license change

request, including SFP cooling and criticality analyses, analysis of potential dilution paths.

and postulated accident review.

Included in the presentation was a description of the existing SFP storage racks and intertacing systems and the licensee's conclusions concerning SFP structural loads.

The presentation concluded with a review of the licensee's schedule for submittal and implementation.

Enclosure 1 is an attendance list for the meeting.

Enclosure 2 includes copies of the meeting handouts.

griy~ennsl q@n>eodr project"3anager Project Directorate II-3 Division of Reactor Projects

- I/II Office of Nuclear Reactor Regulation Docket No. 50-389

Enclosures:

l.

Attendance List 2.

Handouts cc:

See next page DOCUMENT NAME:

G:MEETGSUM.BIO To receive a copy of this document, indicate in tho box: "C I Copy without snachment/enclosure E

~ Copy with attachment/enclosure "ff" ~ No co OFFICE PDII-3/PM PDI I-3/LA PDI 1-3 NAME LWIens:rrsr BCIa ton FHebdon 12/ t

/97 12/

/97 DATE 12/If'97 OFFICIAL RECORD COPY 980i050224 97i2ih PDR ADQCK 05000389 P

PDR IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII,IIIIIII

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++*++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 December 16, 1997 LICENSEE:

FACILITY:

SUBJECT:

Florida Power and Light Company St. Lucie, Unit 2

SUMMARY

OF MEETING ON NOVEMBER 25,

1997, REGARDING PROPOSED USE OF SPENT FUEL POOL SOLUBLE BORON CREDIT - ST.

LUCIE UNIT 2 On November 25, 1997, representatives of the Florida Power and Light Company (FPL), licensee for St. Lucie Plant, Unit 2. met with members of the Nuclear Regulatory Commission (NRC) staff to discuss plans to request NRC approval of a license amendment to allow credit for soluble boron in the Unit 2 spent fuel pool (SFP) in order to incr ease the pool storage capacity.

The FPL representatives provided a summary of the methods to be used to support the license change

request, including SFP cooling and criticality analyses.

analysis of potential dilution paths, and postulated accident review.

Included in the presentation was a description of the existing SFP storage racks and interfacing systems and the licensee's conclusions concerning SFP structural loads'he presentation concluded with a review of the licensee's schedule for submittal and implementation.

Enclosure 1 is an attendance list for the meeting.

Enclosure 2 includes copies of the meeting handouts.

L. A. Wiens, Senior Project Manager Project Directorate II-3 Division ot Reactor Projects

- I/II Office of Nuclear Reactor Regulation Docket No. 50-389

Enclosures:

l.

Attendance List 2.

Handouts cc:

See next page

in mm r

~HARD PY Docket File.

PUBLIC

'T.;L'uolte-'~I" Reading File OGC ACRS

~L.- Wiens-- "

J.

Johnson, RII E-M~I S.

Collins/F. Miraglia R.

Zimmerman B.

Boger F.

Hebdon L.

Wiens B.

Clayton T.

Martin (e-mail to SLM3)

L.

Kopp D.

Jackson C.

Gratton B.

McCabe

~

~

l I

+'j Florida Power and Light Company ST.

LUCIE PLANT Senior Resident Inspector St.

Lucie Plant U.S. Nuclear Regulatory Commission 7585 S.

Hwy AIA Jensen

Beach, Florida 34957 Joe Hyers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida. 32399-2100

. H. S.

Ross, Attorney Florida Power

& Light Company P.O.

Box 14000 Juno

Beach, FL 33408-0420 John T. Butler, Esquire

Steel, Hector and Davis 4000 Southeast Financial Center

Miami, Fl orida 33131-2398 Hr. Douglas Anderson County Administrator St.

Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Hr. Bill Passetti Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.

Tallahassee, Florida 32399-0700 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 61 Forsyth Street, SW., Suite 23T85

Atlanta, GA 30303-3415 H. N. Paduano, Manager Licensing E Special Programs Florida Power and Light Company P.O.

Box 14000 Juno

Beach, Florida 33408-0420 J.

A. Stall, Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen

Beach, Florida 34957 J. Scarola Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen

Beach, Florida 34957 Hr. Kerry Landis U.S. Nuclear Regulatory Commission 61 Forsyth Street, SW., Suite 23T85 Atlanta, Georgia 30303-3415 Mr. T. F. Plunkett President - Nuclear Division Florida Power and Light Company P.O.

Box 14000 Juno

Beach, Florida 33408-0420 E. J.

Weinkam Licensing Manager St.

Lucie Nuclear Plant 6351 South Ocean Drive Jensen

Beach, Florida 34957

MEETING ATTENDEES ST.

LUCIE UNIT 2 SFP BORON CREDIT MEETING November 25, 1997 Larry Kopp Diane Jackson Chris Gratton Len Wiens Ed Weinkam Claude Villard Pete Sharp ORGANIZATION NRC/NRR/SRXB NRC/NRR/SPLB NRC/NRR/SPLB NRC/NRR/PDII-3 FPL FPL FPL Enclosure 1

FLORIDA POWER 8 LIGHTCO.

ST. LUCIE UNIT 2 PROPOSED USE OF SPENT FUEL POOL SOLUBLE BORON CREDIT Sung "mu

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Meeting with NRC November 25, 1997

AGENDA Discuss reasons for FPL's license amendment submittal Summarize the methods used and results obtained by FPL to support license amendment request Review the following items:

Spent fuel pool (SFP) storage racks and interfacing systems SFP cooling analysis performed for increased storage capacity Criticality analysis of proposed new storage configuration Analysis of potential SFP dilution paths Conclusions concerning SFP structural loads Postulated accident review

~

Review timetable for submittal and implementation

REASON FOR FPL'S PROPOSED LICENSE AMENDMENT

~

To request credit for soluble boron at St. Lucie Unit 2 SFP to increase storage capacity Unit 2 is FPL's limiting unit for spent fuel storage capacity (692 irradiated assemblies currently in storage)

~

To extend full core offload capability until 2007

BENEFITS OF DELAYINGNEED FOR DRY STORAGE

~

Permit Multi-Purpose Canister technology to mature prior to design selection

~

Avoid use of store-only containers

~

More time allowed for potential DOE interim storage site

SCOPE OF LICENSE AMENDMENTSUBMITTAL FPL will propose modification of the Unit 2 Technical Specifications DESIGN FEATURES section as follows:

Section 5.6.1 - CRITICALITY:

~

Add requirements for fuel pool k,when flooded with unborated water and water containing 520 ppm boron

~

Revise text describing Region I and Region II of the spent fuel storage racks Section 5.6.3 - CAPACITY:

~

Revise the maximum storage capacity from 1076 to 1360 fuel assemblies Figure 5.6-1 initial enrichment vs. burnu re uirements for stora e of fuel assemblies

~in re ion ii:

~

Remove existing figure and replace with new Figure 5.6-1a through 5.6-1e, titled; REQUIRED FUEL ASSEMBLY BURNUP vs INITIALENRICHMENT and DECAY TIME, for the various subregions of Region I and Region II

ANALYSISSCOPE Engineering Package supporting this license amendment request considers:

~

SFP heat loads with increased storage capacity

~

Reanalysis of SFP reactivity for normal storage and accident conditions

~

Effects of additional capacity on SFP structural and seismic analyses of record (AOR)

~

Identification of SFP dilution pathways and dilution times.

Analysis examined the potential for challenging the 0.95 k,<<design limit

~

Effects of additional capacity on fuel handling and cask drop AOR

DESCRIPTION OF THE ST. LUCIE UNIT 2 SPENT FUEL POOL

~

L-shaped concrete tank lined with welded stainless steel plate

~

SFP has no drains

~

SFP equipped with leak detection capability

~

Fuel Handling Building and SFP structure designed as seismic Class I

~

Connected to cask loading area and the trarisfer canal via removable bulkheads

~

Redundant level and temperature instrumentation and control room annunciation powered from separate diesel backed Motor Control Centers

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DESCRIPTION OF SPENT FUEL STORAGE RACKS Unit 2 SFP has 1584 total storage cells:

~

Licensed to use 1076 cells

~

Designed as Seismic Class I

~

Two storage regions; nominal 8.965" cell pitch

~

12" minimum distance from storage racks to fuel pool liner walls

~

Racks are unpoisoned stainless steel with no non-structural neutron absorber.

Region I cells contain a stainless steel L-insert

~

Storage racks extend -1'bove stored fuel to limit interaction with hypothetical dropped assembly

FUEL POOL COOLING 8c PURIFICATION SYSTEMS

~

Fuel pool cooling system has seismic Class l piping; cooling loops are separate from puriTication system Two complete cooling trains; can be cross connected Manual loading of cooling train to EDG following loss of offsite power (LOOP)

No heat exchanger tube leaks during service lifetime

~

Purification system uses filters, strainers and ion exchangers One train with split duty; spent fuel pool 8 RWT ion exchanger resin bed changed -every 18 months 10

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FUEL POOL COOLING ANALYSIS

~

Used ANSI/ANS-5.1-1979 decay heat methodology

~

Used conservative thermal performance and assembly burnup input

~

Considered effects of 24-month fuel cycles

~

Benchmarked SFP cooling model to actual plant conditions

~

Performed bounding full core offload analysis for increased capacity'erformed bounding analysis of fuel shuffle-type refueling (96 assembly offload) 12

ANALYSIS RESULTS

~

Model conservatively represented actual SFP conditions (plus 7 'F)

~

Model conservative (by greater than 4 'F) with respect to existing AOR

~

Full core offload case (1517 total assemblies):

less than 155 'F with 2 cooling pumps operating; less than 171 'F with 1 pump operating

~

Fuel shuffle results:

139.8 'F with one SFP cooling train available; 130.8 'F with one heat exchanger out of service

~

The analysis demonstrates that fuel cladding integrity is maintained following a loss of SFP cooling

CRITICALITYANALYSIS

~

Analysis performed by ABB-CE consistent with Westinghouse Owners Group methodology as approved by NRC

~

Used DIT and PC version of SCALE-4.3 code

~

Benchmarked to PNL and 8 8 W critical experiments

~

SFP retains two region format

~

Used conservative initial neutron source distribution

~

Analyses conservatively based on "value-added" fuel pellet design 14

CRITICALITYANALYSIS(continued)

~

Biases and uncertainties applied consistent with approved methodology

~

Region I retains more than full core offload capability (276 assemblies)

~

Fuel arranged in U-shaped rings interspersed with vacant rows

~

Analysis addresses fresh fuel of up to 5 w/o U-235

~

Region II cell utilization increases to 95.4% from 75%

15

CRITICALITYANALYSIS (continued)

~

Region II has two subregions

~

Credit actinide decay

~

Considers Gd shims for initial fuel enrichments >4.5 w/o U-235

~

Accident analyses evaluated total loss of SFP cooling and three types of fuel assembly misloads 16

CRITICALITYANALYSIS RESULTS (Including biases and 2'ncertainties)

At 0 ppm boron:

k,ff 0.99801 At 350 ppm boron:

k,<< = 0.94797 Reactivity equivalencing effects require an additional 170 ppm boron

~

Allowance for postulated accidents requires 746 ppm boron:

hk for loss of fuel pool cooling = +0.66%.

hk for limiting misload = +10.16%

~

Total boron requirements

= 1266 ppm Boron requirements less than current St. Lucie Unit 2 Technical Specification requirements 17

ANALYSISOF SFP DILUTIONPATHWAYS

~

Performed analysis consistent with SER guidance

~

Six plausible dilution pathways identified

~

Pathway flow rates and makeup sources identified

~

Dilution times & required water volumes calculated based on a 1200 ppm dilution (1720 to 520 ppm) 18

0

~

i.

DILUTIONANALYSIS RESULTS

~

Greater than 358,000 gallons required to dilute SFP to k,ft 0.95 2.39 X Primary Water Tank volume Assuming makeup available, minimum dilution time for credible pathway is 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />

~

Only random pipe break event provides SFP dilution during LOOP

~

SFP level & temperature instrumentation available following a LOOP

~

SFP makeup and letdown pathways administratively controlled (locked closed valves)

~

SFP boron procedurally maintained between 1800 and 1950 ppm

~

Dilution to k,<< = 0.95 is not a credible event at Unit 2 19

FUEL POOL STRUCTURAL EVALUATiON EVALUATION:

~

Additional stored assembly weight necessitated review of AOR

~

SFP cooling analysis required revision of T, for racks

~

Storage rack stress levels examined for higher temperatures RESULTS:

~

Existing structural AOR considered the presence of consolidated fuel in each storage location

~

Storage rack stress levels under both normal and faulted conditions remain within acceptable limits at the increased temperature

~

Rack response to seismic event remains bounded by existing AOR 20

POSTULATED ACCIDENT REVIEW

~

Reviewed fuel assembly drop and cask drop accidents

~

Considered effect of "value-added" fuel pellet

~

Process review indicates accident probability not increased by capacity expansion

~

Nothing about expanded SFP capacity increases accident consequences

~

Use of "value added" pellet does not increase accident consequences for cask drop or fuel handling accidents

SUMMARY

AND CONCLUSION The analytical basis for the proposed license amendment to increase spent fuel pool storage capacity at St. Lucie Unit 2 through credit for soluble boron is sound and thoroughly supported 22

IMPLEMENTATIONPLANS

~

FPL to submit license amendment request no later than December 31, 1997

~

Approval of this license amendment requested by October, 1998

~

Implementation will require the removal of most cell blocking devices and the repositioning of -800 fuel assemblies

~

Development of the implementation documentation for this license amendment planned to begin -August, 1998

~

Cell block removal and fuel repositioning would begin in 1999 23