ML17308A452

Forwards Response to NRC Bulletin 87-002,Suppl 2 Re Fastener Testing to Determine Conformance W/Applicable Matl Specs, Consisting of Primary Suppliers,Secondary Suppliers & non-safety Suppliers Lists

ML17308A452
Person / Time
Site:	Saint Lucie
Issue date:	07/25/1988
From:	Conway W FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
IEB-87-002, IEB-87-2, L-88-311, NUDOCS 8808020230
Download: ML17308A452 (177)

Text

ACCEIZRATED DISTRIBUTION DEMONSTRA.'EON SYSTEM REGULATE INFORMATION DISTRZBUTIO~STEM (RIDS)

'ACCESSION NBR:8808020230 DOC.DATE: 88/07/25 NOTARIZED: YES DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION CONNAY,W.F. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Des

SUBJECT:

Forwards response to NRC Bulletin 87-002,Suppls 1 & 2 re R fastener testing to determine conformance w/applicable matl.

DISTRIBUTION CODE: IE57D TITLE: 87-02 &

COPIES RECEIVED:LTR 87-02 Supplement, Fastener L ENCL ~ SIZE: C3 Testing to Determine Conformance w/g NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 NRR ROSSFT 1 1 PD2-2 PD 1 1 TOURIGNYFE 1 1 INTERNAL: AEOD/DOA 1 1 AEOD/DSP 1 1 AEOD/DSP/TPAB 1 1 NRR/DEST/ADE 8H 1 1 NRR/DEST/ADS 7E NRR/DOEA/EAB 11 NRR/DOEA/GCB NRR/PMAS/ILRB12 ll 1 1

1 1

1 1

NRR/DRIS/VIB 9D NUDOCS-ABSTRACT 1

2 1

1 2

1 OI 1 1 RECgg32&'2 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL EG&G BARNES F B 1 1 LPDR 1 1 NRC PDR 1 1 NSIC 1 1

C P. O. X 14000, JUNO BEACH, FL 33408.0420

~, I QlllK 2 5 1988 L-88-311 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 NRC Bulletin No. 87-02 Supplement 1 and 2 Fastener Testing to Determine Conformance with A licable Material S ecifications By Supplement 1 and 2 of the subject Bulletin, the NRC staff requested licensees to, 1) provide a list of suppliers and manufacturers from which safety related ferrous fasteners 1/4 inch in diameter or gxeater may have been purchased within the past 10 years, and 2) provide similar information for non-safety related fastener suppliers. The review should be on a best effort basis of possible suppliers.

Enclosed is the Florida Power & Light Company (FPL) xesponse to Supplement 2. of the Bulletin. The information included is as follows: ) Prima Su liers List Those suppliers which were included on the FPL Quality Assurance Approved Suppliers List, and whose scope included supplying fasteners. ) Seconda Su liers List Those suppliers which were on the FPL Quality Assurance Approved Suppliers List and may have supplied fasteners as spare replacement parts or with their products. ) Non-Safet Su liers List Those suppliers which were generally used to provide non-safety related fasteners to the St. Lucie site. Zn addition, the suppliers listed in Enclosure 1 may also be used to provide non-safety related fasteners.

GRM. FT 8808020230 880725 PDR ADDCK 05000335 8 PNU an FPL Group company if)

USNRC Page 2 L-88-311 The attached information is provided pursuant to Section 182a of the Atomic Energy Act of 1954, as amended.

information is required on this topic, please contact us.

If further Very truly yours, W. F. Con~@-

Senior Vice President - Nuclear WFC/GRM/cm enclosure cc: Dr. J. Nelson Grace, Regional Administrator, Region II, Resident Inspector, USNRC'enior St. Lucie Plant USNRC, GRM. FT

STATE OF FLORIDA )

) ss.

COUNTY OF PALM BEACH )

~W.F.C dd dd dl,dd d That he is Senior Vice President- Nuclear of Florida Power & Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.

!+

PZ ~ ~re,l~y W..~onway Subscribed and sworn to before me this

~5 day of NOTARY PUBLIC, in and for th ounty of Palm Beach, State of Florida

~gg+ foMd. Stata Of ROOdO i 19M E p s J ne iAY C mm ss

'ffay fafa lafwaacad laao g~ gfaa My Commission expires:

8808020230 Enclosure 1 Primary Suppliers List GRM. FT

0 ENCLOSURE 3.

In preparation of this list FPL has included the suppliers and manufacturers listed on the Quality Assurance Approved Suppliers List with the following product descriptions:

PRODUCT DESCRIPTION Bolting Materials Anchor Boltings Fasteners GRM. FT

t P'AGE 1 t FLORIDA PORE'R & 'LIGHT COMPANY RESPONSE TO NRG BULLETIN NO. 87-82, SUPPLEMENT 2 PRIMARY SUPPLIERS A PRIMARY SUPPLIER IS DEFINED AS A SUPPLIER FROM WHOM DIRECT PROCUREMENT OF FASTENERS GOULD HAVE TAKEN PLACE.

SUPPLIER NAME AND ORIGINAL ADDRESS NEM ADDRESS ASME ASTM A & 8 ENGINEERIN6 CO. II, ING. YES YES 4648 E. LA PALMA AVE.

ANAHEIM, CA ACIMET MANUFACTURING CO YES YES 1718 GLARKSTONE RD CLEVELAND, OH ACTION BOLT & NUT CO NO YES PO BOX 12156 212 NEWSMAN RD LAKE PARK, FL ACTION BOLT & TOOL GO. NO YES PO BOX 12156 212 NEWMAN RD E PARKi FL P PRODUCTS NO YES CORP'UB.

OF AMP ING.

448 H. SMEDESFORD RD. PION BOX 1776 BERMYN, PA PAOLI, PA AMP SPECIAL INDUSTRIES NO YES DIV. OF AMP 1NG.

448 M. SHEDESFORD RD. P.O. BOX 1776 BERHYN, PA PAOLI, PA AMPCO METAL DIVISION YES YES AMPCO-PITTSBURGH CORP.

1745 SOUTH 38TH ST.

MILWAUKEE, 'Ml ANCHOR DARLING INDUSTRIES INC. YES YES MAMBOLD RD. P.O. BOX 388 1888 NORTH PENN RD.

KULPSVILLE, PA HATFIELD, PA APPLE INDUSTRIAL SUPPLY GO. NO YES 5988 ORANGE AVE. RTE 68 FT. PIERCE, FL

PAGE 2

'"" '-"""'"'FL'ORIDA'POMER'&'L1GHT'COHPANY' "

~ ~

TO NRC BULLETIN NO. 87-82, SUPPLENENT

-'ESPONSE 2

PRIMARY SUPPLIERS A PRIHARY SUPPLIER IS DEFINED AS A SUPPL1ER FRON MHON DIRECT PROCURENENT OF FASTENERS COULD HAVE TAKEN PLACE.

SUPPLIER NAME AND ORIGINAL ADDRESS NEM ADDRESS ASIDE ASTN 8 & G MANUFACTURING CO. YES YES 3867 UNIONVILLE PIKE HATF IELD, PA BABCOCK & 'MILCOX YES YES UTILITY NUCLEAR POMER GENERATION 01V ~

3315 OLD FORREST RD, PO BOX 1268 LYNCHBURG> VA r ~ P: '

BABCOCK & MILCOX YES NO 3117 000 FELLOMS RD LYNCHBURGH> VA r

BARR SUPPLY CO YES YES

'MEST FRONTAGE RD I-55 & RT 6 CHANNOHON> IL ARR-SAUNDERS, INC. YES YES JOLIET DIVISION NEST FRONTAGE.RD I-55 & RT 6 CHANNOHON> IL BASIC ENGINEERS YES YES JOHNSTON INDUSTRIAL *PK> BLDG 425 JOHNSTON> PA BERGEN PATERSON PIPESUPPORT CORP. YES YES ELM ST.

LACONIA, NH BETHLEHEM STEEL CORP NO YES ONE CUNBERLAND ST LEBANON> PA BREDA FUCINE S.P.A. NO YES MILANO MORKS VIALE SARCA> 336 LAND, ITALY, N/A

PAGE 3

'FLORI'D'A POWER & LIGHT BULLETIN NO. 87-82, COMPANY'ESPONSE TO NRG SUPPLENENT 2 PRINARY SUPPL1ERS A PRItiARY SUPPLIER IS DEFINED AS A SUPPLIER FROH WHOH DIRECl PROGURENENT OF FASTENERS GOULD HAVE TAKEN PLACE.

SUPPLIER NAME AND ORIGINAL ADDRESS NEW ADDRESS , ASIDE ASTN CAPITAL PIPE & STEEL GO. YES YES DIV OF FAS INT'L 1NG 4281 ORANGE ST PEARLAND, TX CAPITOL PIPE & STEEL GO YES YES DIV OF FAS INT'L INC 381 CITY LINE AVE BALA GYNWYD. PA

• r,e >'\C..

CAPITOL PIPE & STEEL GO YES DIV OF FAS INT'L INC 8288 HENDERSON RD CHARLOTTE, NG CAPITOL PIPE & STEEL PRODUCTS GO. YES DIV. OF BOWLINE CORP.

81 CITY LINE AVE A CYNWYD, PA APITOL PIPE &. STEEL PRODUCTS CO. YES YES DIV. OF BOWLINE CORP.

8288 HENDERSON RD CHARLOTTE'C CARDINAL INDUSTRIAL PRODUCTS CORP YES YES 3873 'WEST OQUENDO LAS VE6ASi NV CHICAGO TUBE & IRON GO YES YES 2531 WEST 48 ST CHICAGO'L COGNE SOGIETA NATIONALE YES VIA PARAVERA 16 AOSTA 11188 ITALY, ITY CONNERCIAL FASTENERS CORP YES YES 241 LAFAYETTE ST 18-35 38TH ST.

NEW YORK, NY LON6 IS. CITY, NY

P'AGE 4

~ g

"'LORIDA POMER &'LIGHT COHPANY RESPONSE TO NRG BULLETlN NO. 87-82, SUPPLEMENT 2 PRIMARY SUPPLIERS A PRINARY SUPPLIER IS DEFINED AS A SUPPLlER FROM MHON DIRECT PROCUREMENT OF FASTENERS GOULD HAVE TAKEN PLAGE.

f SUPPLIER NANE AND ORIGINAL ADDRESS NEM ADDRESS ASNE ASTH CONSOLIDATED POMER SUPPLY YES DIV. OF CONSOLIDATED PIPE & SUPPLY GO., ING.

7586 E. INDEPENDENCE BLVD,STE118 1285 HILLTOP CHARLOTTE, NC 8 I RNIN6HAN, AL DUBOSE STEEL INC YES YES HMY 24 ROSEBORO, NG

'~

• iy. v y>, y y>'s q, ~ e v, ' q~'8so,*a>r> v.r}q . ~ S ~ y at, ~ ~ ~~ y i "i,r>'< i.i.";;(i>i~ ~", '~ ., As'E>, g,g .' . "r ~, ~ )

ENERGY STEEL & SUPPLY CO ~ YES YES 2685 LAPEER RD. 2715 PALDAN DR PONTIAC'I AUBURN HILLS, NI EN6INEERS & FABRICATORS CO. YES YES 3581 M. 11 ST.

OUSTON, TX.

RICO PRODUCTS, INC. NO YES 34688 SOLON RD.

SOLON'H FLORIDA BOLT & NUT CO NO 825 NM SIXTH AVE FT LAUDERDALE'L FLORIDA BOLT & NUT GO NO YES 2915 HILLSBORO RD

'M PALM BCH, FL FLORIDA STEEL CORPORATION YES NO NISCELLANEOUS & ORNAMENTAL NETALS DIV 2788 FIFTH AVE TANPAp FL GRINNELL CORP YES YES 268 MEST EXCHANGE ST.

PROVIDENCE, RI

PAGE 5

~

' " " ' 'LORIO'A POMER & LIGHT"COMPANY'ESPONSE TO NRC BULLETIN NO. 87-82, SUPPLEMENT 2 PRIMARY SUPPLIERS A PRIMARY SUPPLIER IS DEFINED AS A SUPPLIER FROM WHO'IRECT PROCUREMENT OF FASTENERS COULD HAVE TAKEN PLACE.

SUPPLIER NAME AND ORIGINAL ADDRESS NEM ADDRESS ASIDE ASTN HARDMARE SPECIALTY CO. INC. NO YES 48-75 36 ST LONG ISLAND CITY> NY HILTI FASTENING SYSTEHS, INC. NO 88 GREEN BRIAR CIRCLE CHESAPEAKE. VA HILTI INC. NO YES FASTENIN6 SYSTENS 5813 N ANDRE'MS 'MAY

~

FT. LAUDERDALE. FL HILTI INDUSTRIES NO YES 5484 S. 122 EAST AV. PO BX 21148 TULSA, OK INC.

ILTI INDUSTRIES'N'OUTHWESTERN NO YES REGIONAL HEADQUARTERS 2588 PARK CENTRAL BLVD.

DECATUR> GA HILTI, NO YES FASTENING SYSTEMS 1535 N.W. 79 AVE.

NIANI, FL HOKE INC YES YES ONE TENAK1LL PARK CRESSKILL, NJ HOUSE OF THREADS NO YES 665 NOKENA OR MIAMI SPRINGS'L HOUSE OF THREADS NO YES 2181 S DIVISION AVE ORLANDO, FL

"'7

PAGE 6

'L, ~ W FLORIDA POME'R 8 L'IGHT COMPANY RESPONSE TO NRC BULLETIN NO. 87-82, SUPPLENENT 2 PRIMARY SUPPLIERS A PRIHARY SUPPLIER IS DEFINED AS A SUPPLIER FROt1 MHOH DIRECT PROCUREMENT OF FASTENERS COULD HAVE TAKEN PLACE.

SUPPLIER NAME ANO ORIGINAL ADDRESS NEM ADDRESS ASIDE ASTN HOUSE OF THREADS NO YES 1913 FLAGLER ST TANPA, FL HOUSE OF THREADS NO YES PO BOX 12255 JACKSONVILLE, FL r ~r '." + r *'- ~ ~ ) 'ri; 'rt 4 '~A g

'r'd '

~ g~ >Hi(r' '

p g'" "-8, -., I, w", rp ~,rr',.f,,>',; r err rrr .w'Lr ~ ',, i,','Cp' r'wr . +' ' ~ "" ~

INC YES

'UB YES 2146 FLINTSTONE OR TUCKERS GA INDUSTRIAL SALES 4 NANUFACTURING CO NO YES NUCLEAR COMPONENTS OIV 2715 MEST 15 ST E, PA T GRINNELL YES YES INDUSTRIAL PIPING INC OLO ROUTE 421 KERNERSVILLE, NC ITT GRINNELL YES NO PO BOX 4719 645 NORTHSIOE OR NM ATLANTA'A ITT 6RINNELL CORP YES YES PIPE HAN6ER DIVISION 621 NE DANA AVE MARRENi OH ITT GRINNELL CORP YES 1431 NOREHEAO ST CHARLOTTE, NC ITT GRINNELL CORP'374 NO YES CLINTON ST.

BUFFALO, NY

PAGE

'F'LORIDA'POMER 8 LIGHT CONPANY'-

TO NRC BULLETIN NO. 87-82, SUPPLEMENT e

RESPONSE 2 PRINARY SUPPLIERS A PRIMARY SUPPLIER IS DEFINED AS A SUPPLlfR FROM WHO'IRECT PROCUREHENT OF FASTENERS COULD HAVE TAKEN PLACE.

SUPPLIER NANE ANO ORIGINAL ADDRESS NEM ADDRESS ASIDE ASTH ITT GRINNELL CORP. NO YES ENGINEEREO PIPING PRODUCTS GROUP RT. 128 K OTTER POND ROAD PRINCETON, KY ITT HARPER YES YES 8288 LEHIGH AVE NORTON GROVE, IL

.i ITT PHILLIPS YES DRILL DIVISION PO BOX 364 HMY 12 & LIBERTY TR MICHIGAN CITY, IN JAMES C. 'WHITE CO, NO YES 511 HALTON RD i ~ PO BOX 5495 GREENSVILLE> SC OSEPH DYSON YES PO BOX 228 53 FREEDOM RD.

PAINESVILLEi OH JOSEPH DYSON R SONS 1NC NO YES DEPENDABLE DIV 33228 LAKELAND BLVD EAST LAKE, OH KILBOURN ENGINEERING CO YES YES 9226 WEST FLAGG AVE MILWAUKEEp WI KSN FASTENING SYSTEMS NO YES OIV. OF ONARK INDUSTRIES 381 NEM ALBANY RO.

HOORESTOMN, NJ LAKE ERIE SCREM CORP YES YES 13881 ATHENS AVE CLEVELAND, OH

PAGE 8 FLORIDA'POWER & LIGHT BULLETIN NO. 87-82, GOHPANY'ESPONSE TO NRC SUPPLENENT 2 PR IHARY- SUPPLIERS PLACEBO A PRIHARY SUPPLIER IS DEFINED AS A SUPPLIER FROH MHON DIRECT PROCUREHENT OF FASTENERS COULD HAVE TAKEN SUPPLIER NANE ANO ORIGINAL ADDRESS NEM ADDRESS ASIDE ASTH LOUIS P. CANUSO, INC. NO YES CEDAR & SPRUCE STS,, PO BOX 378 DEPTFORD, NJ MCCULLOCH INDUSTRIES INC & NO YES HILTI FASTENERS OIV

'ES 1888 FREEMAY BLVD HINNEAPOLIS, HN "k >'0 '>> >>, l';cC '>'> ~ "~ ~ .'> se>>'>s p'p g >>>>4 '

">> <l>> wl(>>

.'~I>Py 4. >p, '>, (' > g" >>>>>,'>>><>> .,4 '>'P >,: ~ w HC JUNKIN CORP YES l1CJUNKIN RO.

NITRO'V HEREOITH CORPORATION YES YES 468 HILLSIDE AVE.

HILLS I OE J NJ ETAL GOODS CO. YES 6211 CEDAR SPRINGS OR.

DALLAS, TX HIDLAND PIPE & SUPPLY CO YES NO 2869 SOUTH 61 CT CICERO, IL NODULUS CORPORATION NO YES 1888 NODULUS RO MT PLEASANT, PA NATIONAL VALVE & HANUFACTURING CO. YES YES JOHNSTON INDUSTRIAL PK, BLDG 425 JOHNSTON, PA l NOVA HACHINE PRODUCTS 18685 SHELDON ROAD HIODLEBURGH HEIGHTS, OH CORP. NO YES

I ~

PAGE 9 f ~

, fr,,

FLORIDA'OMER R'LIGHT COHPANY" '-

1

\ I f ~

RESPONSE TO NRC .BULLETIN NO. 87-82, SUPPLEMENT 2 PRIMARY SUPPLIERS A PRIMARY SUPPLIER IS DEFINED AS A SUPPLIER FROM WHO'IRECT PROCURENENT OF FASTENERS COULD HAVE TAKEN PLACE.

SUPPLIER NANE AND ORIGINAL ADDRESS NEW ADDRESS ASME ASTN NPS INDUSTRIES, INC. YES YES ONE HARNON PLAZA SECAUCUS, NJ NPS INDUSTRIES'NC. YES YES 2758 S,M. MOODY ST.

PORTLAND, OR

,W<<gfff ~,", ~ ' '<<q '<< figiPi q

~ \'fbi V q ~ I,,",( i'V ",;if.. j'f')<I, -'pi i, '~i ~i 'I',i if~i yi P+ ., f tg.';jP f'~I:yP: ffifI','II'If~if I g (~>>' i~i P I'ig eiq ..; f . ' i, ' =, ~

~

NPS INDUSTRIES, INC. YES YES 18428 NETRIC BlVD.

AUST IN, TX PBI INDUSTRIES YES YES STEEL SERVICE CENTER OIV 4188 LAKE PARK RO NGSTOMNJ OH ENNISULAR SUPPLY CO NO YES PO BOX 428865 2247 N'W 17 AVE NIAHI, FL PHILLIPS DRILL CO., INC. NO YES DRILL DIVISION PO BOX 364 HMY 12 & LIBERTY TR HICHIGAN CITY, IN PIPE SHIELDS INC YES YES 151 N AUTUMN 1881 ALDRIOGE RO.

SAN JOSEi,CA VACAVILLEi CA POMER 8 ENGINEERED PRODUCTS CO., INC. YES YES 151 R 157 HELEN ST.

'SOUTH PLAINFIELD, NJ POWER PIPING COMPANY YES NO 829 BEAVER AVE PITTSBURGH'A

I ~

PAGE 18

RESPONSE

~ h FLORIDA- POWER &'IGHT-'COMPANY TO NRG BULLETIN NO. 87-82, SUPPLEMENT

" 2 PRIMARY SUPPLIERS A PRIMARY SUPPLIER IS DEFINED AS A SUPPLIER FROM WHOM DIRECT PROCUREMENT OF FASTENERS COULD HAVE TAKEN PLACE.

SUPPLIER NAME AND ORIGINAL ADDRESS NEW ADDRESS ASME ASTM PRESSURE VESSEL - NUCLEAR STEELS> YES YES IN'68 HILLSIDE AVE.

HILLSIDE, NJ PULLMAN POWER PRODUCTS YES NO 2688 REACH RD.

P.O. BOX 3388. REACH RD.

WILLIAMSPORT> PA 4t> ~ /,,P'>'>eq RUSSELL BURDSALL

~ +w '> '>w 4,C'M a &PA

& WARD Ww "In '~,y CORP,

">~',0,'E ~l> >'()i $ qw> > yp

' >4' '

5 tk ~ ~ I'l> 6 pent I', >, m .

NO

>0 " ~

YES 5825 WEST 73 ST CHICAGO> IL SOUTHEASTERN BOLT & SCREW YES 183716 AVE WEST B I RMINGHAM> AL OUTHEASTERN BOLT & SCREW NO YES ATLANTIC BOLT & SCREW DIV 1769 EDMOND RD CAYCE> SC SOUTHERN BOLT & FASTENER CORP YES YES 381 MONTGOMERY ST SHREVEPORT,, LA STANDARD PIPE & SUPPLY CO ~ YES NO 2688 KAULTON RD TUSCALOOSA> AL STANDARD PIPE & SUPPLY CO .ING YES NO 26TH & JANE STS PITTSBUR6H, PA TEXAS BOLT COMPANY YES P.OS BOX 1211 HOUSTON> TX

0

~ ~

PASE, 11

' 'FL'ORIDA'POWER &"'L'16HT 'GOHPANY RESPONSE TO NRC BULLETIN NO. 87-82, SUPPLEMENT 2 PRINARY SUPPLIERS A PRIMARY SUPPLIER IS DEFINED AS A SUPPLIER FRON WHO'IRECT PROCUREMENT OF FASTENERS GOULD HAVE TAKEN PLAGE.

SUPPLIER NAME AND ORIGINAL ADDRESS NEM ADDRESS ASME ASTH IN'.

TIOGA PIPE SUPPLY CO., ING. YES 2458 MHEATSHEAF LANE PHILADELPHIA, PA TRM NELSON DIVISION YES TOLEDO AVE R 28 ST WEST RIDGE RD.

LORAIN> OH ELYRIAi OH

~; 0'~,(,,aol't,l~th P a,~hg) <,, 4% 4&<th'CgPgy,"%L'g>'I;W+<t',4,~ /~WE w p)~ ~p. gt l yV, g 9+,' 'J /',~ ah w,g x: ~ = P5~

TUBECO, YES YES 123 VARICK AVE.

BROOKLYN'Y TYLER-DAMSON SUPPLY CO. NO YES 1248 SOUTH JOPLIN ULSA, OK NION PUHP GOHPANY YES YES 87 CAPITOL AVE. S.M.

BATTLE GREEK, NI UNISTRUT CORP NO DIV OF SYLVANIA CORP 4118 S MAYNE RD WAYNE > Nl UNISTRUT DIVERSIFIED PRODUCTS GO. YES

'IV OF SYLVANIA CORP NO 4118 S MAYNE RD WAYNE'I UNISTRUT FLORIDA NO YES 2648 N. E. FIFTH AVE.

POMPANO BEACH, FL VELAN VALVE CORP. YES YES GRISMALD INDUSTRIAL PARK AVE. C ILLI STON, VT

PAGE 12 FLORIDA POMER & LI6HT COHPANY RESPONSE TO NRG BULLETIN NO. 87-82, SUPPLEMENT 2 PRIHARY SUPPLIERS A PRINARY SUPPLIER IS DEFINED AS A SUPPLIER FROM MHOt1 DIRECT PROCUREMENT OF FASTENERS COULD HAVE TAKEN PLACE.

SUPPLIER NANE AND ORIGINAL ADDRESS NEM ADDRESS ASME ASTH VELAN, YES NO IN'LANT 2

558 HCARTHUR ST.

ST. LAURENT, QUEBEC, CAN VITCO NUCLEAR PRODUCTS, YES YES IN'445 HAMANN PKMY MILLOUGHBYi OH MESTINGHOUSE ELECTRIC CORP. YES NUCLEAR GONPONENTS DIV.

SCENIC HIGHMAY, U. S. 90 PENSACOLA, FL MILLIAM H. ORR, ING. NO YES NORTH BRADDOGK AVE ~

- AT ITTSBURGHi PA END PF

Enclosure 2 Secondary Suppliers List GRM. FT

ENCLOSURE 2 In preparation of this list FPL has included the suppliers and manufacturers listed on the Quality Assurance Approved Suppliers List with the following product descriptions:

PRODUCT DESCRIPTION Actuators Heat Exchangers Instrument Valves Penetration Assemblies.

Tanks Valves & Parts Vessels Component Supports Fluid Conditioning Devices (Strainers)

Hydraulic Shock Arrestors Mechanical. Shock Arrestors Pipe Hangers Pumps Turbines Cable Tray & Fittings Diesel Generators Electrical Motors Relays Service Doors Control Rod Drive Mechanisms GRM. FT

PABE 1

'i ~ i

~ )

F'LOR'IDAPOWER '&16HT 'COMPANY RESPONSE TO NRC BULLETlN NO.87-82i SUPPLEMENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER 1S DEFINED AS A SUPPL1ER FROM WHOM DIRECT PROCUREMENT OF FASTENERS NORMALLY WOULD NOT HAVE OCCURRED BUT'WHO COULD HAVE BEEN USED'O OBTA1N FASTENERS AS SPARE PARTS' SUPPLIER NAME AND ORIBINAL ADDRESS NEW ADDRESS ASME ASTM AEROFIN CORPORATION NO YES

. 4621 MURRAY PLACE LYNGHBUR6, VA ALFAB, 1NC. NO YES HWY 84 E BYPASS ENTERPRISE, AL

.".> ~,>6 j'>~>>>>,>e>> ~ >>>,'>> .,(>4>'>'V

~ >i>> }, K." > i),',,C> fi ~,> ~ >> lp( )> ~ } >,,'> v>>><>'I,';> ~ >g> ~ y"' >>>>,'> '>>'>>>>>, rg p>. ~

>I >> '. i vy >' ~ >" ~ '>>>> ' a.-

ALLIS CHALMERS YES YES VALVE DIVISION LINCOLN R HARTLEY, PO BOX M93 YORK, PA ALOYCOJ ING. YES ALOYCO PLANT 488 W. ELIZABETH AVE.

DEN, ND PROOFS MERACE CORP NO YES 1865 FLORAL AVE UNlON. N J AMERACE CORP. "A6ASTAT" NO CONTROL OIV.

1888 HICKORY ST.

6RAFTON, 'WI AMERICAN AIR FILTER CO. YES NO 2888 TAMM ST.

BROWNSVILLE, TH AMERICAN AIR FILTER CO., INC. NO YES 6ENERAL OFFICE 215 CENTRAL AVENUE LOUISVILLE, KY, AMERICAN STANDARD YES YES HEAT TRANSFER OIV 175 STANDARD PKWY.

FFALO, NY

t PAGE 2

'"'FLORIDA POWER & L1GHT COMPANY g

> ~

RESPONSE TO NRC BULLETIN NO. 87-82, SUPPLEMENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS OEFlNEO AS A SUPPLIER FROM WHOM DIRECT PROCUREMENT OF FASTENERS NORMALLY WOULD NOT HAVE OCCURRED BUT WHO COULD HAVE BEEN USED TO OBTA1N FASTENERS AS SPARE PARTS.

SUPPLIER NAME AND ORIGINAL ADDRESS ' 'EW ADDRESS ASME ASTM AMETEK YES NO STRAZA OIV1SION 798 GREEN FIELD OR ~, PO BOX 666 EL CAJON, CA AMETEKi 1NC. NO YES 2233 STATE RD CORNWELL HEIGHTS, PA BENSALEM> PA AMF CUNO YES NO 488 RESEARCH PKWY MERIDENr CT ANCHOR/DARLING MFG CO YES

~ 781 F1RST ST ILLIAMSPORTi PA NDERSON GREENWOOD R CO YES YES PO BOX 1897 5425 SOUTH RICE AVE.

BELLAIREi TX HOUSTON, TX APEX TECHNOLOGIES INC. NO YES SOUTHERN OIV ~

2536 COUNTRYSIDE BLVD.

CLEARWATER'L ARMCO STEEL NO YES NATIONAL SUPPLY CO PO BOX DRAWER H HWY I-35 GAINESVILLE, TX ASEA BROWN BOVERI NO YES SWITCHGEAR PRODUCTS 01V.

281 H1CKMAN DR.

SANFORD, FL ATLAS INDUSTRIAL MANUFACTURING CO YES NO 81 SOMERSET PALCE CLIFTON, NJ

PAGE 3 i

'" FLORIDA'POMER: R'-Ll'GHT GONPANY' "i"' ' ~"

RESPONSE TO NRC BULLETIN NO. 87-82, SUPPLEMENT 2 SECONDARY SUPPL1ERS A SECONDARY SUPPLIER 1S DEFINED AS A SUPPLIER FROM MHOM DIRECT PROCUREMENT OF FASTENERS NORNALLY MOULD NOT HAVE OCCURRED BUT MHO COULD HAVE'EEN USED'TO OBTAlN FASTENERS AS SPARE PARTS.

SUPPLIER NAME AND ORIGINAL ADDRESS NEW ADDRESS ASME ASTN ATWOOO & MORRILL CO. ING. YES YES 285 CANAL ST.

SALEN, MA AUTOMATIC SPRINKLER CORP.'F AMERICA YES PIPE FABR1GATION FACILITY 282 E. MEAOOMLAKE PKMY SMAINSBORO, GA

" "C> ii; ~ 'rC>+>'~,,>q>ply'>s>>~~' 4m>V i i>>> c"., >,>A ii '~>~~'i >>w>,"C> t L' ',, >" i(> ~

ii) i'i i C>> i > g>, .i>,>A 5'",44 "i >, *','>> i,C>> ' i'i...

AUTONATIC SMITCH'CO NO YES 58-56 HANOVER RD FLORHAN PARK, NJ B F SHAM YES OLO LAURENS AIRPORT LAURENS, SC I F YES NO 1688 DIVISlON RD MEST MARM1CK, Rl B-LINE SYSTEMS INC NO YES 589 M NONROE ST HIGHLAND, IL BABCOCK R MILCOX YES NO GALT ONTARIO, GAN i

BABCOCK R WILCOX YES 28 S VAN BUREN AVE BARBERTON> OH BASGO YES OIV. ANERICAN PRECISION INDUSTRY 2777 MALDEN AVE ~

UFFALO> NY

4 PAGE 4 FLORIDA POMER- & L'IGHT" COMPANY "

RESPONSE TO NRC BULLETIN NO. 87-82, SUPPLEMENT 2 SECONDARY SUPPLIERS A SFCONDARY SUPPLIER IS OEF1NED AS A SUPPLIER FRON MHOH 01RECT PROCUREMENT OF FASTENERS NORNALLY WOULD NOT HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS.

SUPPLIER NAHE ANO ORIGlNAL'DDRESS NEM ADDRESS ASIDE ASTH BBC BROMN BOVER1 NO YES SM1TCHGEAR PRODUCTS 01V.

281 HICKNAN OR.

SANFORD, FL BERGEN PATTERSON NO YES ROUTE 24 HEST, P. BOX 426 HOULTONi AL BERGEN PIPE SUPPORT CORP YES NO ST HMY 7 & ANDERSON AVE WOOORIDGEJ NJ BETHLEHEN STEEL CORP. YES BUFFALO TANK OIV.

349 HIGHMAY AVE KSONVILLE, FL INGHAM INTERNATIONAL INC. YES YES 2888 N M FRONT AVE PORTLAND, OR 8 INGHAM-MILLANETTE YES YES 2888 N M FRONT AVE PORTLAND'R BORG-'WARNER FLUID CONTROLS YES YES BORG-'WARNER CORP 7588 TYRON AVE VAN NUYS. CA BROOKS INSTRUHENT DlV. YES YES EHERSON ELECTRIC CO.

487 M. VINE ST.

HATF IELD> PA BROWN BOVERI ELECTRIC, INC. NO YES 4371 COUNTY LINE RO ~

CHALFONT, PA

PA6E 5

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-FLORIDA POMER & LI'GHT COMPANY '". I~

RESPONSE TO NRC BULLETIN NO. 87-82, SUPPLEMENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPL1ER FROM MHON DIRECT PROCUREHENT Of FASTENERS NORMALLY MOULD NOT HAVE OCCURRED BUT MHO GOULD HAVE BEEN USED TO OBTA1N FASTENERS AS SPARE PARTS'UPPLIER NAME ANO ORIGINAL ADDRESS NEW ADDRESS ASNE ASTN BUFFALO TANK DIV1510N YES YES BETHLHEN STEEL CORP 5349 HIGHWAY AVE JACKSONVILLE, FL BM/IP INTERNATIONAL INC. YES YES PUNP 01V. LOS ANGELES OPS.

2388 E VERNON AVE LOS AN6ELES, GA r .r- rr l <J r,, '4h, $ '" r'g,lt/~(rj;gQ$(

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PUMP DIVISION 2388 E VERNON AVE LOS ANGELES, CA VERNON'A C-E POWER SYSTEMS YES YES NEWINGTON SITE 0 BOX 638 OLD DOVER RO. PO BOX 638-INGTONi NH PORTSNOUTH, NH CANADIAN WORCESTER CONTROLS, YES. YES PRODUCTS DIV. LTD'UCLEAR 28 HID-DONINION ACRES 8CARBOROUGH, ONTARIO, GAN GBl SERVICES, ING. YES YES 5888 TENTH ST B I RNINGHAH, AL CHICAGO BRIDGE & IRON CO YES YES 5888 TENTH ST B I RNINGHANi AL GA'ES GINCORP INC. NO YES 899 W HMY 96 SHOREVIEM, HN CIRCLE SEAL CONTROLS YES BRUNSMIGK CORP TEGHNET1GS OIV PO BOX 3666 1111 N BROOKHURST ST AHEIN(

PAGE 6 ~

4 ~

'."FtORIDA'OMER &LIGHT CONPANY.

RESPONSE TO NRC BULLETlN NO. 87-82, SUPPLEMENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFlNED AS A SUPPLlER FRON MHON DIRECT PROCUREMENT OF FASTENERS NORNALLY MOULD NOT HAVE OCCURRED BUT WHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PAR1'S.

SUPPL'IER NANE AND ORIGINAL ADDRESS NEM ADDRESS ASME ASlN COMBUSTION ENGINEERING YES YES PF AVERY Dlv PO BOX 638 OLO DOVER RO. PO BOX 638 NEMINGTON, NH PORTSMOUTH, jan% NH CONBUST ION ENGINEERING YES NUCLEAR CONPONENT NFG.

911 M. NAIN ST CHATTANOOGA, TN

~ r<< iW r'Ci ~ .qr'V,<<i<<*; . r j ',b";,"'r err>'<<p 0 p'X <<C i'<<><< '<<<<jr",p "<<rrlr<<'( y<< l '<<<<ran j g fAr<<r <<gf $ "r '~l,r",,<<t p'<< ~ <<<<) r; gyr rrr: ' a" ' ' <<~ r ~

CONBUSTlON ENGINEE RING . YES . YES NUCLEAR PRODUCTS NFG INDUSTRIAL PARK 1888 PROSPECT HILL RO EAST WINDSOR, CT MINOSOR, CT CONBUST10N ENGINEERING> INC. YES YES POMER-SYSTEMS GROUP - CHATTANOOGA NUCLEAR OPER.

11 W. MAIN ST TTANOOGA, TN ONAX BUFFALO CORP YES YES 2388 WALDEN AVE BUFFALO, NY CHEEKTOMAGA, NY CONAX CORP YES YES 2388 WALDEN AVE BUFFALOS NY CHEEKTOWAGA> NY CONTROL CONPONENTS INC YES YES OIV OF BABCOCK & 'MILCOX 2567 SE MAIN ST 22591 AVENlDA EMPRESA IRVINE, CA RANCHO SANTA MARGARITA, CA CONTROL COMPONENTS, INC. YES YES DIV. OF INl, LTO 2567 SE MAIN ST 22591 AVENIDA ENPRESA IRVINE, CA RANCHO SANTA NARGARITA, CA CONTROMATICS DIVISION 222 ROBERTS ST E HARTFORD, CT

I PAGE 7'

'I

"'FLOR1DAPOWER'& LlGHT'"COMPANY" ' " "

~

I '

RESPONSE TO NRC BULLETIN NO. 87-82, SUPPLEMENT 2 SECONDARY SUPPLIERS' SECONDARY SUPPLIER IS DEFINED AS A SUPPL1ER FROM WHOM 01RECT

. PROCUREMENT OF, FASTENERS NORMALLY WOULD NOT HAVE OCCURRED BUT WHO COULD HAVE 'BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS.

SUPPLIER NAME AND ORIGINAL ADDRESS NEW ADDRESS ASME ASTM COOPER 1NDUSTRIES NO YES FLOW CONTROL 01V.

16588 S MAlN ST MISSOURI CITY, TX COPES VULCAN YES YES PO BOX 577 LAKE ClTY, PA

.',<<, J>! J<< ...Ii~,,><'~"'>> CJJ "0".,'><<g >~@II. I <<l II,'<<><<'>"I>>J J>>','h>V>,y qg>, r;; JP '~'q~>l>g>f'~'"',J> "'I>>'J'>>, <<J."I m",,bV > ~ >> 'J. ><<y'<<W .">>>i ~ W '. ';,">'. >-', -,', <<, t; ~ >' > J CORNER & LADA CO.J INC. YES YES 1341 ELMWOOD AVE.

CRANSTONJ RI CRANE ALOYCOJ INC. YES YES 12 EAST DEVONWOOD AVE.

ROMEOVILLEJ IL RANE CO YES YES CHEMICAL PUMP DIVISION 175 TITUS AVE WARRINGTON INO PK WARRINGTON, PA

~

CRANE COMPANY NO YES 283 HAMPSHlRE ST.

INOlAN ORCHARD, MA CRANE PACKING CO. NO YES 6488 OAKTON ST.

MORTON GROVE, IL CROSBY VALVE YES YES 43 KENDRICK ST WRENTHAMJ MA CROSBY VALVE & GAGE CO. YES 43 KENDRICK ST WRENTHAMJ MA

PAGE

'FLORIDA POWERR L'IGHT"CONPANY RESPONSE TO NRG BULLETlN NO. 87-82, SUPPLEMENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLIER FRON WHOM DIRECT PROCUREMENT OF FASTENERS NORNALLY MOULD NOT HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS.

SUPPLIER NANE ANO ORIGlNAL ADDRESS NEW ADDRESS ASIDE ASTN CVI CORP YES A PENMALT CORP 188 LYNAN COURT PO BOX 2138 HILLI ARD, OH GOLUNBUS, OH OIETERIGH STANDARD CORP ~ YES YES SUB OF DOVER CORP.

5681 NORTH 71 ST, BOULDER, GO p

~ > g'>'>>,> f> ~ <>> >v C ~ f')4 >, ~ >'); >>> gY ~ y>qg '>>>>> f>>g> ~ >>>>,>>9, ',' >

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DIETERICH STANDARDS YES YES 5681 NORTH 71 ST.

BOULDER, GO DIVISION OF ALLIS CHALMERS CORP. YES GLEAN AIR DIV.

15 CENTRAL AVENUE ISVILLE, KY RAGON VALVES INC YES YES PO BOX 489 f

13457 XGELS IOR OR NORWALK, CA DRESSER INDUSTRIES YES YES HWY 71 NORTH ALEXANDRIA, LA DRESSER INDUSTRIES, ING. YES YES DRESSER VALVE AND CONTROL OIV.

HMY 71 NORTH ALEXANDRIA, LA DRESSER PUMP DIVISION NO YES DRESSER INDUSTRIES'NC.

5318 TONEYTOWN PIKE TONEYTOMNp NO DUNCAN EDWARD GO NO YES PO BOX 14838 597 S ANDREMS AVE T LAUDERDALE, FL

I

~

PABE 9 FL'ORIDA" POMER -!L LIGHT GONPANY RESPONSE TO NRG BULLET1N NO. 87-82'UPPLEMENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLIER FRON WHOM DIRECT PROGUREHENT OF FASTENERS NORHALLY MOULD NOT HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTA1N FASTENERS AS SPARE PARTS.

SUPPLIER NAME AND ORIGINAL ADDRESS NEW ADDRESS ASIDE ASTH EGODYNE NRH NO YES 687 1ST STp S.M.

HAS S ILLON, OH EDERER CRANE NO 2925 F1RST AVE. SO.

SEATTLE'A

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ELECTRO SMITCH CORP NO 167 KING AVE MEYHOUTH. HA ENGINEERED PRODUCTS DIV. YES 248 FALL ST SENECA FALLS, NY SCO CORPORATION NO INDUSTRIAL SERVICE CENTER 6415 EAST GORVFTTE LOS ANGELES'A FISGHER & PORTER GO NO YES 112 E COUNTY LINE RD MARNINSTERi PA FISHER CONTROL CO YES YES 285 SOUTH CENTER ST HARSHALLTOMN, 1A FISHER CONTROLS INT'L YES YES CONTROL SYSTEMS DlV IN'lNAL 285 SOUTH CENTER ST MARSHALLTOMNi IA FISHER SERVICE GO NO 757 GLEASON RD.

COLUMBIA, SG

0 WAGE ~ 18

'"' FL'ORID'A"'POMER'-'8 'LIGHT COMPANY RESPONSE TO NRC BULLETIN NO. 87-82( SUPPLEMENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLIER FRON -MHON DIRECT PROCUREHENT OF FASTENERS NORMALLY MOULD NOT HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS.

SUPPLIER NAME AND ORIGINAL ADDRESS NEM ADDRESS ASIDE ASTN FOSTER MHEELER YES NO ENERGY CORP PO BOX 38 BLVD' MOUNTAINTOP, PA G ~ HE BETTlS CORP. NO 7831 GRANO , PO BOX 14689 HOUSTON, TX GARRETT PNEUMATIC NO YES SYSTENS DIVISION 111 SOUTH 34 ST., PO BOX 5217 PHOENIX( AZ GARRETT PNEUNATIC YES SYSTEMS DIVISION 88 MARNER RO.

PE, AZ GCA PAR SYSTENS CORP, NO 3468 LEXINGTON AVE. N.

ST. PAUL, NN GENERAL ELECTRIC YES NO LARGE MOTOR OIV ONE RIVER RD BLDG 48 RH 488 SCHENECTEDY( NY GENERAL ELECTRIC CO. NO YES ENERGY R PROCESS OIV.

518 AGENCY RD.

'MEST BURLINGTON, IA GENERAL ELECTRIC CORP YES YES NUCLEAR ENERGY BUSINESS OPERATIONS 175 CURTNER AVE.

SAN JOSE, CA GENERAL ELECTRIC CORP NO INDUSTRIAL CONTROLS DEPT PO BOX 489 BANE, NC

'PAGE 11 t ~ t / '

" ' FLORIDA'. POMER' "LIGHT COMPANY" RESPONSE TO NRC BULLETIN NO. 87-82, SUPPLENENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS OEF1NEO AS A SUPPLIER FROM WHOA DIRECT PROCUREMENT OF FASTENERS NORMALLY MOULD NOT HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE .PARTS.

SUPPLIER NANE ANO ORIGINAL ADDRESS NEM ADDRESS ASNE ASTH GENERAL ELECTRIC CORP. NO YES NOTOR OIV.

2155 S ~ FIRST ST.

SAN JOSE, CA GINPEL CORPORATION YES 258 N MOOOBOURNE RO

~ ~

LANGHORNE, PA

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i 6" <<, '>t ~ >>t', >> '+ Z>> >>"' t>>it ", 4 '>>O ">> g '*<<4 " * >~ t, ~ GIRARD DEVELOPMENT INC. NO YES PRO. BOX 172 2536 KNIGHTMOOO ST. RANCHO COROOVA, CA GOULD 1NC YES NO ITE SMITCHGEAR 01V 71 COUNTY LINE RO LFONT, PA GOULD INC YES NO VALVE & FITTIN6S 01V 6388 M HOMARD ST NILESI IL 60ULD PUMPS INC YES YES 248 FALL ST SENECA FALLS, NY GPE CONTROLS YES YES OIV1S ION OF VAPOR CORP 6511 OAKTON ST. NORTON GROVE, IL GRANAOA VALVE & FITT1NG CO. NO 4858 N.M. THIRD ST. FT. LAUDERDALE. FL 6RAY TOOL CONPANY YES'ES 7135 ARONORE ST HOUSTON'X C>> + ~ . ' i~p> t<< ., ><<<<tt<<o ~ <<<">><<I'<<<<<<>><<>>t>><<>>>>>,'\tl la i Ptt~:> t<<><<> >>><<<< PAGE 12 FL'ORIOA POWER 8'IGHTONPANY: "" NRG BULLET1N NO. 87-82, SUPPLEMENT ESPONSE.TO 2 SECONDARY SUPPL1ERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLIER FRON WHO'1RECT PROCURENENT OF FASTENERS NORNALLY MOULD NOT HAVE OCCURRED BUT MHO GOULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS. SUPPLIER NAME ANO OR161NAL ADDRESS NFM ADDRESS 'ASNE AS1N 6REER HYDRAULICS ING YES YES 6588 E SLAUSON AVE CONllERCEi CA CITY OF CONVERGE, CA 6TE SYLVANIA NO YES 2588 58TH ST HAMPTON'A 6UFALLOY INC YES YES 4738 OARIEN ST HOUSTON, TX 6UYON ALLOYS ING YES YES 3488 R06ERDALE RO USTON, TX I'UYON ALLOYS INC YES YES 958 S FOURTH ST HARRISON, NJ HANNEL-DAHL CONOFLOM DIV. YES NO ITT 6RINNELL VALVE CO., IN'75 POST RD WARWICK; RI HAROEE HAINTENANCE & STEEL FABRIGATORS, 1NC. NO YES PLANT CITY INOUSTR1AL PK. 'YDNEY RO., PO DRAMER 1788 PLANT CITY'L HAYWARD TYLER PUMP CO YES YES 88 INDUSTRIAL PKMY, PO BOX 492 BURLIN6TONi VT HENRY PRATT GO'. YES YES 481 S. HI6HLANO AVE. 988 SOUTH DEPOT AVE. AURORA, IL DIXON, IL ~ L I 'PAGE '3 ' I' "FLORID'A POWER &'LIGHT BULLETlN NO. 87-82, COHPANY'ESPONSE .TO. NRC SUPPLEMENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLIER FROM WHO'IRECT PROCUREMENT OF FASTENERS NORMALLY WOULD NOT HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTA1.N FASTENERS AS SPARE PARTS. SUPPLIER NANE AND ORIG1NAL ADDRESS NEW ADDRESS ASIDE ASTN HENRY VOGT HACH CO YES 1888 WEST ORVSBY AVE LOUI SVILLEi KY HUSKY BURNDY, 1NC. NO YES HUSKY PRODUCTS DIV. 7485 INDUSTRIAL RD. FLORENCE, KY ~ ~',a ~ 'i +C 6 )r 'hetb'~ r +4> i0 + j '" ',)i'1 "r<'qW>> +~48> ~h)⪙ )>0 S,F>i s, W'(' e'y ~ s )S5 ) r, ) to+ ( +I %' Etr +P+ pa 'ES ~ ~ . INGERSOLL RAND YES CANERON PUHP DIV1510N 942 HEtiORIAL PKWY PHILLlPSBURG, NJ ITE IMPERIAL CORP 'ES NO CONTROL 8 SYSTEM 01V. BOX 386 TNINSTER, HD ITT CONOFLOW NO YES ROUTE 78 ST, GEORGE, SC ITT ENGINEERED VALVES YES YES UNIT OF ITT FLUID TECH CORP 33 CENTERV1LLE RD. LANCASTER, PA ITT GRINNELL YES .DIA-FLO DIVISION 33 CENTERVlLLE RD. LANCASTER'A ITT GRINNELL YES NO SPECIALTY VALVE GROUP 225 N. FRONT ST. WRIGHTSVILLE, PA ITT HATCHEL-DAHL YES . NO 175 POST RD MARWICK, RI e PAGE 'b.'LOR'IOA POMER & LI6HT GOHPANY '. RESPONSE TO NRC BULLET1N NO. 87-82> SUPPLEMENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLIER FRON WHOM DIRECT PROCURENENT OF FASTENERS NORMALLY WOULD NOT HAVE OCGURRED BUT MHO GOULD HAVE BEEN USED TO,OBTAlN FASTENERS AS SPARE PARTS. SUPPLIER NAHE AND OR161NAL ADDRESS NEW ADDRESS ASIDE ASIA ITT STANDARD YES YES HEAT TRANSFER DIV ~ 175 STANDARD PKWY ~ BUFFALO, NY J E LONER6AN GO YES NO PO BOX 6167 PHILADELPHIA, PA >> >>>a'>' I >>,>>>>'>>>; $ >>f >>,p> ~; yl )P>>> ia > l ~,) >P>>a>>>>>> $>>>>>>4'I j>>>> > >>>>>+>>\>>1Np",Z>>>'>>>>>>>. P/lb'>>>>4>>l>>('> ",i >>>> g>> S>> g" l; ">> l' 4 '>>>5 J H SLITHER & CO NO YES PO BOX 47438 ATLANTA> 6A JAMESBURY CORP YES YES TMO (2) LOCATlONS BOMOITCH OR - 648 LINCOLN ST EMSBURY - WORCESTER> NA JERBUSON 6ABE & VALVE CO. NO YES 15 ADAMS ST. BURL IN6TON, NA JOHNSTON PUMP YES YES 1775 E ALLEN AVE 6LENOORA> CA JOHNSTON PUNP CONPANY YES YES NUCLEAR SERV1GE CENTER 2681 EAST 34 ST. 'HATTAN006A, TN JOSEPH OAT CORP. YES YES 2588 BROADMAY CAMDEN, NJ JULIUS NOCK & SONS, ING. NO YES 777 RUTLANO RO ~ BROOKLYN, NY . PAGE . 15 'LORIDA"POMER 8 LIGHT GOHPANY RESPONSE.TO NRG BULLETIN NO.. 87-82 .SUPPLEHENT 2 SECONDARY SUPPL1ERS A SECONDARY SUPPLlER IS OEFlNEO AS A SUPPLIER FRON MHON DIRECT PROCUREMENT OF FASTENERS NORMALLY MOULD NOT HAVE OCCURRED BUT MHO GOULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS SUPPLIER NAME AND ORIGINAI ADDRESS NEM ADDRESS ASNE ASTN JUNO INDUSTRIES ING NO YES PO BOX 5877 4628 S FLORIDA AVE LAKELAND, FL JUNO 1NOUSTRIES 1NC NO YES 1368 SM 12 AVE PONPANO BGH, FL KEROTEST HANUFACTURING CO. YES YES 2525 LlBERTY AVE. PITTSBURGH, PA KUNKLE VALVE NO YES .8222 BLUFFTON RO ~ ~ MAYNEi IN LAKESIDE BRIDGE 8 STEEL GO. YES YES 5388 N. 33 ST HILMAUKEE, 'Ml LANGO INDUSTRIES INC YES NO 1532 NORTH JOHNSON EL CAJON, GA LEAR SIEGLER INC YES NO 2848 E OYER RO SANTA ANA, GA LESLIE CONPANY YES NO 481 JEFFERSON RD PARS IPPANY, NJ LIHITORQUE CORP. NO YES 5114 MOODALL RO. I PO BOX 11318 LYNCHBURG, VA 0 'PAGE 16 j -""FLORIDA 'POMER &"LIGHT COMPANY"" RESPONSE TO NRC BULLET1N NO. 87-82, SUPPLENENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLIER FRON WHO'IRECT PROCUREHENT OF FASTENERS NORMALLY MOULD NOT HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS, SUPPLIER NANE ANO OR1G1NAL ADDRESS NEM ADDRESS ASNE ASTH LITTON INDUSTRIAL PRODUCTS, 1NC, YES YES 222 ROBERTS ST E HARTFORD, CT N & H POWER PIP1NG NO PO BOX 2417 958 SM 12 AVE. POMPANOS FL N.P. HUSKY NO YES GREER ROAD 284 PIEDMONT HMY HAULDINi SC GREENVILLE p SC NAGNETROL INTERNATIONAL YES YES OIV OF SCHAUB CORP 88 BELMONT RD NERS GROVE. IL CARLO COIL NUCLEAR COOLING INC. NO YES 6868 HWY, PP HIGH RIDGE p HO HASONEILAN DIVISION YES YES NCGRAW EDISON CO. 85 BODEWELL ST. AVON> HA NASONEILAN DRESSER YES 'DRESSER VALVES & CONTROL DIV.,DRESS 1NOUSTRY INC 85 BODEWELL ST ~ AVON, tiA MASONEILAN 1NTERNATIONAL YES YES 63 NAHATAN ST NORWOOD, NA NASONEILAN 1NTERNATIONAL INC. YES NO NONTEBELLO OPERATIONS 1848 S. VAIL AVE. NTEBELLOp CA PAGE '7 FLORIDA'POWER &"L'iGHT BULLETlN NO. 87-82, COMPANY'ESPONSE TO NRC SUPPLEMENT 2 e A SECONDARY SECONDARY SUPPLIERS SUPPLlER IS OEFlNED AS A SUPPLIER FROM WHOM DIRECT PROCUREMENT OF FASTENERS NORMALLY WOULD NOT HAVE OCCURRED BUT WHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS. SUPPLIER NAME AND ORIGINAL ADDRESS NEW ADDRESS ASME ASTM MCGRAW-EDISON CO YES YES REGULATOR OPERATIONS, MASONElLAN OIV. 63 NAHATAN ST NORWOOD, MA METAL BELLOWS CORP. YES WESTERN OIV. 28977 KNAPP ST. 288 SClENCE OR. ~ CHATSWORTH, CA ( ~ (,(g MlLLER FLUID ~ (( ~ ~ 4j'l("(((,,10(,'('(~ ~$ 1)(((44((( POWER ~ ~ ~ MOORPARKi CA PA~A((w(1(4(,,gi'(I'('gi g*(((I'((t(' '(=(('( NO YES DIV. OF TEMPLETON KENOY COMPANY 4488 HIGHLAND PARKWAY SMYRNA, GA MlLLER FLUID POWER NO YES 888 N. YORK RO. BENSENVlLLE. IL LNE ASSOClATES NO YES PO BOX 13518 483 FAIRLANE AVE. ORLANDO, FL MISSION DRILLING P ROOUCT 5 0 I V. NO TRW ENERGY PRODUCTS GROUP 8768 CLAY RO HOUSTON, TX MODERN POWER & PROCESS PIPlNG NO YES PO BOX 776 5'224 RlVEREOGE OR TITUSVILLE, FL MORRISON KNUDSEN CO., INC. YES YES POWER SYSTEMS DIV. 1488 VANCE ST. ROCKY MOUNT, NC MUESCO CONTROLS,'NC. NO YES 5458 OLD SPANISH TR, PO BX 14239 HOUSTON'X 0 0 'PAGE '18 ~ 4 ~ FLORIDA-POMER &'l&HT CONPANY RESPONSE TO NRC BULLETlN NO. 87-82, .SUPPLEHENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLIER FRON WHO'IRECT PROCUREMENT OF FASTENERS NORHALLY MOULD NOT HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS. SUPPLIER NANE AND ORIGINAL ADDRESS NEM ADDRESS ASME ASTN f NASH ENGINE RING CO NO YES 318 WILSON AVE NORMALK, CT NL INDUSTRIES YES NO FOOT OF MEST ST MILMINGTONi OE NUCLEAR VALVE DIVISION YES YES BORG-MARNER CORP 7588 TYRON AVE VAN NUYS, CA NUPRO INC NO YES 4888 E 345 ST MILLOUGHBYi OH S CORPORATlON NO YES SOUTHERN Dlv. 2536 COUNTRYSIDE BLVD. CLEAR'MATER, FL OVERBEKE-KAIN NO YES 28985 AURORA RD CLEVELAND'H OVERLY MANUFACTURING CO. NO YES 574 W. OTTERNAN ST. GREENSBURG. PA PAC1FIC SCIENTIFIC INC YES YES 1346 SOUTH STATE COLLEGE BLVD ANAHE IN, CA PACIFIC VALVES INC YES 3281 MALNUT AVE LONG BEACH, CA 'PAGE 19 t A SECONDARY

RESPONSE

"" FLORIDA TO NRC

.POWER SUPPLIER IS DEFlNED AS R

A "LIGHT CONPANY BULLETlN NO. 87-82> SUPPLENENT SECONDARY SUPPLlERS SUPPLlfR 2

FRON WHON DIRECT PROCURENENT OF, FASTENERS NORNALLY WOULD NOT HAVE OCCURRED BUT WHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS.

SUPPL1ER NANE AND ORlG1NAL ADDRESS NEW ADDRESS ASNE ASlN PACIFIC VALVESJ 1NC. YES YES NARK CONTROLS CORP.

3281 WALNUT AVE LONG BEACH, CA PAUL NUNROE ENERTECH NO 2958 BIRCH ST ~ P.O. BOX 5988 BREA, CA ORANGE, CA PERRY OCEANOGRAPHICS> 1NC ~ NO YES 275 W. TENTH ST. P.O.BOX 18297 RIVIERA BEACH, FL PITTSBURGH DES NOINES CORP. NO YES 3488 GRANO AVE. NEVILLE 1S.

PITTSBURGH, PA SI SEAL 1NT'S GNGH NO YES SEALANT NANUFACTURING SUNDERHUES ESCH 38 AHAUS GERNANY NA 04422>

POWELL THE WILLIAN CO YES YES PLANT <<I 2583 SPR1NG GROVE AVE C INC INNAT1, OH POWELL, THE WILLIAN CO. YES YES PLANT <<2 3233 COLERAIN AVE.

CINCINNATI, OH PROCESS EQUIPNENT CO 1NC YES NO 71 FOREST ST BROCKTON> NA PROTECTIVE NATERIALS CO NO YES FOLLY HILL RD SEABROOK, NH

'PAGE 28 ~ ~

FLORIDA 'POWER "8 L'IGHT COMPANY TO NRG BULLETlN NO. 87-82, SUPPLEMENT 2

'ESPONSE SECONDARY SUPPLIERS A SECONDARY SUPPLIER 1S OEFlNED AS A SUPPLIER FROM WHOM 01REGT PROCUREMENT OF FASTENERS NORMALLY WOULD NOT HAVE OCCURRED BUT WHO COULD HAVE BEEN USED TO OBTA1N FASTENERS AS SPARE PARTS.

SUPPLlER NAME ANO ORIGlNAL ADDRESS NEW ADDRESS ASME ASTM PULLMAN CONSTRUCTION 1NOUSTRIES INC. NO YES 1488 EAST 97 PLAGE CHICAGO> IL PULLMAN SHEET METALS CO. NO YES 1488 EAST 97 PLAGE CHICAGO, 1L t

R P ADAMS YES NO 225 E PARK OR BUFFALO, NY R V HARTY GO 1NC NO YES DIV 'OF DOOR-MAN MFG CO 585 E TEN MILE RD YAL OAK, Ml LPH A. HILLER NO YES 951 KILLARNEY OR.

PITTSBUR6H, PA REACTOR CONTROLS, INC. (RCI) YES NO SOUTHEAST SERVICES DIVISION 6643-8 42 TERRACE NORTH WEST PALM BEACH'L RECO 1NDUSTRIES, INC ~ YES PO BOX 25189 RICHMOND, VA RECO SOUTH CAROLINA INC. NO YES 1788 FRINK ST.

CAYCEi SC REL1ANCE ELECTRIC GO NO YES STATE ROAD 187 MADISON, IN

'PAGE 21

'I FLORIDA'OWER:E LIGHT CONPANY -"

RESPONSE TO NRC BULLETIN NO. 87-82, SUPPLEMENT 2 SECONDARY SUPPL1ERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLIER FRON WHON DIRECT PROCUREHENT OF FASTENERS NORMALLY MOULD NOT HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTA1N FASTENERS AS SPARE PARTS.

SUPPLIER NAHE ANO ORIG1NAL ADDRESS NEM ADDRESS ASIDE ASlN RICHMOND ENGINEER1NG YES YES PO BOX 25189 RICHMOND, VA ROCKMELL INTERNAT10NAL YES YES FLO'W CONTROL OIVIS10N 198 S SAUNDERS ST RALEIGH, NC 1

ROCKMELL INTERNATIONAL YES YES PO BOX 581 SULPHUR SPRINGSI TX ROSENOUNT 1NC NO YES PO BOX 35129 HINNEAPOL I S, NN EDEN PRAIRIE, HN TORK CONTROLS, INC. NO YES 19 JET VIEW DR.

ROCHESTER, NY ROYAL INDUSTRIALS YES NO 2848 E DYER RO SANTA ANAi CA SCHUTTE R KOERTING NO YES 2233 STATE RO CORNWELL HEIGHTS, PA BENSALEN, PA SELANCO INC NO LARGO INDUSTRIES 181 SWING RD GREENSBORO, NC SIEMENS - ALLIS'NC. NO YES LARGE ROTAT1NG APPARATUS DIV.

78TH ST. & GREENFIELD AVE, MEST ALLIS'I

'PAGE 22 <<

"'"*' '" FLORIDA POWER & LlGHT COHPANY TO NRG BULLETIN NO. 87-82, SUPPLEMENT ESPONSE 2

SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLIER FROM WHOM DlREGT PROCUREMENT OF FASTENERS NORMALLY MOULD NOl HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS.

SUPPLIER NAME ANO ORIGINAL ADDRESS NEW ADDRESS ASIDE ASTH S I EVENS-ALLI S, INC. NO YES HEDIUN NOTOR & GENERATOR OIV.

4628 FOREST AVE.

NORWOOD, OH SORGEL TRANSFORMERS YES YES

'O DIV OF SQUARE D GO 838 WEST NATIONAL AVE I NILWAUKEE, Ml

.i'<<: << '4'"<<ri,g" ~ <<' ~ i'p iq" ~<<<,",,>y" r '>ji<'~<<'>>'>":c <<>i'>> u< ~ ~<<ii" '<<<<<<q<<<,ii'< ...i ~'g ) >',;6 <<,.<<<< ~ ', i >~<<>> ", ".; <<r;%.,';

SOUTHERN'FLUID CONTROLS CORP, YES 4491 N.E. SIXTH TERRACE FT. LAUDERDALE, FL SOUTHERN SMA6ELOK GO NO YES 189 CITATION GT B I RHINGHAl1, AL UTHERN TOOL COHPANY YES DIV. OF SCIENTIFIC ATLANTA P.O. BOX 2248 HWY 78 MEST ANNIS TON, AL SOUTHWEST FABRICATING & MELDING CO.i INC. YES NO 7525 SHERHAN ST.

HOUSTON> TX SOUTHWESTERN ENGINEERIN6 GO NO 6111 E BANOINI BLVD LOS ANGELES, GA SPECIALTY MAINTENANCE & CONSTRUCTION CO. NO 4338 DRANE FIELD RD.

LAKELAND, FL STATIC-0-RING NO YES PRESSURE SNITCH GO 11785 BLAGKBOB GO OLATHE, KS

'PAGE 23 'I

" "~ 'LORIDA POWER R LI:GHT'COHPANY" ". " ~ ~ ~ s RESPONSE TO NRC BULLETIN NO. 87-82, SUPPLEMEN1 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER 1S OEFlNED AS A SUPPLIER FRON WHOM DIRECT PROCUREHENT OF FASTENERS NORMALLY WOULD NOT HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTAlN FASTENERS AS S'PARE PARTS.

SUPPLIER NAHE A'NO ORIGlNAL ADDRESS NEM ADDRESS ASIDE ASTN STEARNS-ROGER MFRS. INC. YES HANUFACTURING OIVISlON 688 'HEST BATES AVE ENGLEMOOD, CO STEARNS-ROGERS HFRS.> INC. YES YES 4588 CHERRY CREEK DR. 788 SOUTH ASH ST, GLENDALE, CA DENVER, CO 4ili i r~ ~ ', 1 ~;>a ~

~ t A4q )qg ate, i"i'r a 'P' >g-, g ~$

'a'4 g ',<, 4 aqua> i g" 4."~+'- j ~

~ se

~ s, ~o P ' ) >'~'4, (',( ~,-Ps y a -i r ~

STEARNS-ROGERS, INC. YES NO P.O. BOX 5888 788 ASH ST.

DENVER> CO STEWART STEVENSON NO YES PO BOX 1637 4516 HARRISBURG BLVD USTON, TX STEM CONPONENTS INC NO YES 383 FIRST ST N COCOA BCH> FL TARGET ROCK CORP NO YES 1966 E BROAOHOLLOM RD E FARMINGOALE, NY TAYLOR DEVlCES, NO YES IN'88 MICHIGAN AVE NORTH TONAMANDA, NY TEC VALVE COMPANY NO YES PO BOX 1159 JOHNSON RD.

'CONROE> TX TECHNO CORPORATION NO YES 2789 M. 18TH ST.

ERIE> PA

PAGE 24

~ " "

FtORIDA POMER R'I6HT 'CONPANY RESPONSE TO NRC BULLETIN NO. 87-82, SUPPLENENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLIER FROM WHOM DIRECT PROCUREMENT OF. FASTENERS NORMALLY MOULD NOT HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS.

SUPPLIER NAHE AND ORI6INAL ADDRESS NEM ADDRESS ASHE ASTH TECO NFG.i NO F.H. 528 IN'725 EAST ALVIN'X TELEDYNE BROMN EN6INEERIN6 YES NO CUHNINGS RESEARCH PK 388 SPARKMAN OR SM HUNTSVlLLE, AL 4)A ~ ) 0 ( ) ' 9 ) t)A ~ ~ ) )<<<<+I f) v~" )fit ) P) ' - vc 9r ) ~

TELEDYNE BROWN ENGINEERING NO 23 SECOND ST SW DECATUR, AL TELEDYNE FARRIS ENGINEERIN6 YES YES 481 COHHERCIAL AVE 488 COHHERCIAL AVE PALASADES PARKi NJ PALISADES PARKI NJ LEFLEX INC. NO YES DEFENSE AEROSPACE OIV.

CHURCH RO.

NORTH WALES> PA TERRY CORP'O NO YES BOX 1288 P.O. BOX 555 HARTFORD, CT WINDSOR> CT TERRY STEAN TURBINE NO YES PO BOX 1288 PRO. BOX 555 HARTFORD, CT MINDSOR, CT TEXAS PIPE BENDING CO. YES NO 2588 OLD GALVESTON RD.

HOUSTON, TX THE WILLIAM POWELL CO. YES PLANT 42 3233 COLERAIN AVE.

CINCINNATI, OH

'PAGE 25

~

RESPONSE

" 'l'ORIDA ~ ~

POWE'R "K LIGHT 'GOMPANY"-

TO NRG BULLETIN NO. 87-02, SUPPLEMENT 2 P

SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFlNED AS A SUPPLlER FROM MHOM DIRECT PROCURENENT OF FASTENERS NORNALLY MOULD NOT HAVE OCCURRED BUT MHO GOULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS'

\

SUPPLIER NAME AND ORIG1NAL ADDRESS NEW ADDRESS ASNE ASlN TRM MISS10N MFG CO YES NO 8760 CLAY RO HOUSTON'X TUBE TURNS GO. YES NO OIV. OF GHENETRON CORP.

2900 SOUTH BROADMAY LOUISVILLE,

.-, .r j r g. q =

r e f W.i KY Vg g I' ~ ~ 4rrr:,~'+ (0'"prrrrgi<. ir- '4', r,'i)C 'p r'JY", *~'r TUBE TURNS GO ~ YES NO DIV OF GHENETRON CORP,

~

PO BOX 987, 718 S. 28 STREET LOUISVILLE, KY TURA MACHINE CORP, NO YES FOLCROFT IND. PKi HORNE DR.

FOLGROFT. PA ITED ENGINEERS &

CONTRACTORS'N'TEARNS YES YES ROGER OIV.

4580 CHERRY GREEK OR. 700,SOUlH ASH ST.

GLENDALE, GA DENVER, GO VALCOR ENGlNEERING CORP. YES YES T'WO LAMRENCE RO, SPRINGFIELD > NJ VALCOR EN61NEERIN6 CORP. YES NO 365 GARNE61E AVE.

KENILWORTH'J VALTEK. IN'O YES BOX 2200, NOUNTAIN SPRIN6S PK SPRINGFIELD'T SPRINGY ILLEi UT VAN LINDA IRON WORKS NO YES 3787 BOUTMELL ROAD LAKE WORTHY FL

rPAGE 26" t I S

'.FLORIDA-POMER R LIGHT COMPANY RESPONSE TO NRC BULLETlN NO. 87-82, SUPPLEMENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS DEFINED AS A SUPPLlER FRON WHOM DIRECT PROCUREMENT OF FASTENERS NORNALLY MOULD N01 HAVE OCCURRED BUT MHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS.

SUPPLIER NAHE AND ORIGINAL ADDRESS NEM ADDRESS ASNE ASTt1 VAPOR CORPORATION YES YES GPE CONTROLS Dlv.

6511 OAKTON ST ~

NORTON GROVE, IL VELAN ENGINEERING YES YES 2125 MARD AVE NONTREALi CAN

~

VELAN, INC.

qg '> Vx ~ ~ ~ (arqv ~q'~" ~$ ','a@A. '" p y l jr' '(et~! p ag '

>p e h >( 0 pk< ', g ~c. I tag 4 'h ' ', ') YES YES 2125 MARO AVE MONTREAL, CAN MALWORTH CONPANY YES NO HUFF AVE GREENSBURGp PA LMORTH VALVE CO. YES YES ALOYCO PLANT 1488 M. ELIZABETH AVE.

LINDEN, NJ MESTERN REG10NAL INT'L. INC. NO YES 16366 VALLEY BLVD.

CITY OF INDUSTRY, CA MESTINGHOUSE CORP YES NO ELECTRO-MECHANICAL OIV CHESMICK AVE CHES MICK, PA.

MEST1NGHOUSE CORP YES NO TAMPA DIVISION PO BOX 19218 TAMPA, FL MESTINGHOUSE ELECTRIC CORP NO YES NUCLEAR FUEL OIV BLUFF RO COLUMBIA, SC

"PA6E 27 1

t FLORIDA POWER & LIGHT 'COMPANY TO NRC BULLETlN NO. 87-82, SUPPLEMENT 2 e

'ESPONSE SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS.DEF1NED AS A SUPPLIER FRON WHOM DIRECT PROCUREMENT OF FASTENERS NORMALLY MOULD NOT HAVE OCCURRED BUT WHO COULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS SUPPLIER NANE AND ORIGlNAL ADDRESS NEM ADDRESS ASIDE ASTN MESTINGHOUSE ELECTRIC CORP NO YES RELAY INSTRUNENT 01V.

95 ORANGE ST.

NEMARK, NJ WESTINGHOUSE SMI T CH6 EAR NO YES 788 BRADOOCK AVE E PITTSBURGH, PA WHITEY VALVE CO NO YES 318 BISHOP RO HI6HLAND HEIGHTS> OH MKN VALVE DIVISION NO YES AFC INDUSTRIES INC 16588 S HAIN ST SOURI CITY p TX ODWARO GOVERNOR CO. YES FN61NE & TURBINE CONTROLS 1888 EAST DRAKE RO.

FT. COLLINS i CO WORTH1NGTON 6ROUP YES YES NCGRAM EDISON CO.

481 MORTHINGTON AVE HARRISON, NJ WORTHINGTON PUHP NO YES 5318 TONEYTOMN PIKE TONEYTOMNr MO MORTHINGTON PUHP CORP YES YES ENGINEERED PUMP OIV 481 WORTHlNGTON AVE HARRISON, NJ XONOX CORP. YES NO TUFFLINE OIV.

4444 COOPER RO.

C INC INNATI, OH

'8 ~,

I A <<

'PAGE

, ( ~

~

~

p

' (,(

OME R 'K L'I GHT COMPANY

~

FLOR I OA'

~

RESPONSE TO NRG BULLETIN NO 87-82 SUPPL'EMENT 2 SECONDARY SUPPLIERS A SECONDARY SUPPLIER IS OEFlNEO AS A SUPPLIER FROM MHOM DIRECT PROCUREMENT OF FASTENERS NORMALLY MOULD NOT HAVE OCCURRED BUT WHO GOULD HAVE BEEN USED TO OBTAIN FASTENERS AS SPARE PARTS.

I SUPPLIER NAME ANO ORIGINAl. ADDRESS NEM ADDRESS ASME ASTM YARMAY YES YES NORRISTOMN 8 NARGlSSA RDS.

BLUE BELL, PA YORK ELECTRO PANEL CONTROL COMPANY'NG. NO PO BX 1782, YORK COUNTY INO PARK YORK, PA s<v, .g+,(( 1',, (( ~

(

v~/'p~

YUBA HEAT TRANSFER CORP qf';(,.rpg,, y <<j~<'('r 'p'( ~((~'~jp(', (<<gg'(" .~ (A;: 'Io . <<(P js",.i qg "r ty'.p'~ g,-'l, '

~ (( ." g.,"'( <<(,,('r (

YES

( ~

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• . ~, ~ ..', (r y: ~

PO BOX 3158 TULSA, OK ZURN INDUSTRIES YES NO MATER 8 MASTE TREATMENT OlVISlON 3885 PITTSBURGH AVE IE, PA P O F L I $

Enclosure 3 Non-Safety Suppliers List

Page 1 of 2 FPL provides the following list of suppliers generally used to provide non-safety related fasteners at the St. Lucie Site. The information was compiled by purchase order and material and supply information available on computer for fastener purchases.

Additionally, all suppliers listed on Enclosure 1 of this response may have supplied fasteners for non-safety applications.

This list is not all inclusive as procedures do not require procurement information traceability for non-safety related fasteners. Certified Material Test Reports or Manufacturers Certificates..of.-,Compliance., are,not.,required for ordering non-safety related fasteners. Information concerning sub-tier suppliers or manufacturers is not generally available for fasteners purchased as non-safety related.

GRM. FT

Page 2 of 2 Action Bolt & Tool Company 212 Newman Road P. 0. Box 12156 Lake Park, FL 33403-0156 Duncan Edward P. 0. Box 14038 Ft. Lauderdale, FL 33302-0000 Florida Bolt & Nut Company 825, N. W.,Sixth Avenue Ft. Lauderdale, FL 33311 Bert Lowe Supply Company P. 0. Box 11517 Tampa, FL 33680-0000 Service Industrial Supply Company, Inc.

4252 Westroads Drive P. O. Box 3126 West Palm Beach, FL 33402-0000 GRM. FT

b) Liner and Liner Anchors The acceptance criteria for the liner and liner anchors is in accordance with the requirements specified in Paragraph CC-3720 and CC-3730 of ACI-ASME Section III, Division 2, Subsection CC and can be summarized as follows:

i) Liner The strain in the liner induced by thermal loads and the deformation of the pool structures is limited to the allowables presented in Table CC-3720-1 of,ACI-ASME Section III Code. Load Combinations (a) and (b) presented in Section 4.4.1.2 of this report are considered as Service Load category and (c) and (d) as Factored Load category as these terms are used in that table.

ii) Liner Anchors The displacement of the liner anchors induced by thermal loads and deformation of the pool structures is limited to the allowable presented in Table CC-3730-1 of ACI-ASME Section III Code. Load Combinations (a) and (b) presented in Section 4.4.1.2 of this report are considered as Normal Load category, (c) as Extreme Environmental Load category and (d) as Abnormal Load category as these terms are used in that table.

4.6.1.2

~ ~ ~ Material Properties The following material properties were used in the analysis of the spent fuel pool structure:

a) Concrete (f'c 5,200 psi)

Young's modulus Ec = 3.85 x 106 psi Poisson's ratio Vc 0.17 Thermal Expansion coeff O!c ~ 5.5 x 10 6 1/oF b) Rebar Steel Young's modulus Es 29 x 106 psi Poisson's ratio Vs 0.30 Thermal Expansion coeff O! s = 6.5 x 10 6 1/oF Yield Strength 40, 000 psi c) Liner Plate Young's modulus E ~ 28.8 x 10 psi Poisson's ratio fp ~ 0.3 Thermal Expansion coeff o. p = 6.5 x 10 6 1/oF Yield Strength ~ 27,500 psi 4.6.1.3 Results a) Spent Fuel Pool Floor For the nonlinear analysis of the selected loading cases (Section 4.4.1.2), the maximum stress results in the concrete and rebars are summarized in Table 4-2.

4-21 0077L/0011L

II

~ CI ~

Cf r o

It is observed that the stresses in wall reinforcement are significantly affected by those loading combinations which include temperature effects. It is further observed that loading case v, which has the largest temperature gradients, has the worst'ffect on concrete compressive stresses for both mat and wall locations. Also, the average reinforcement stress for locations is greatest for this loading case while the mat rebar stress at the cask storage area is greatest for loading case vi.

The safety factor (SP) is defined as ultimate stress divided by maximum actual stress including load factors. The safety factors for the maximum stress are also presented in Table 4-2.

The smallest safety factors for the reinforcement tension and concrete compression are 1.10 and 3.65, respectively, which resulted from loading case v, while the smallest safety factor for concrete shear is 1.05 resulting from loading case vi. This clearly indicates that the shear stress in the concrete is the governing component. The critical location of this shear stress is at the cask storage area of the mat, since the thickness of the mat is the smallest (5 feet) here.

Liner and Anchorage The critical loading case for the liner evaluation was loading case v which produced maximum compressive stress in the liner plate. This compressive stress was due to temperature and the deformation of mat. The buckling analysis result indicated that the liner plate would not buckle, due to the stability effect of the hydrostatic pressure.

Two loading conditions were considered necessary in the liner anchor evaluation; one was the strain-induced load which produced the unbalanced in-plane force at the edge of the pool area, and the other was the horizontal seismic load transmitted through the friction between the rack support and the liner.

This horizontal seismic load was assumed to the uniformly distributed at the liner anchors. A maximum friction coefficient of 0.8 was used in calculating this horizontal force. In the liner anchor analysis, the load-deflection relationship for the liner anchor subjected to the liner in-plane force, which is usually obtained from actual test data, is required. Since there were no test data available for the actual anchor size of W8 x 24, the load-deflection test. data for a lesser strength anchor angle 3 x 2 x 1/4 were used in this analysis. This is considered to be a conservative approach.

The results of the liner and liner anchor evaluation are summarized in Table '4-3. The minimum safety factors for liner and liner anchor are 5.20 and 1.33 respectively. It should be noted that the actual safety factor for the liner anchor would be greater than 1.33 if the load-deflection data for the actual anchor size of W8 x 24 were used.

4-22 0077L/0011L

CI r

r A

c) Poundation Stability and Soil Bearing A detailed soil bearing evaluation was performed. The soil stresses were obtained at each mat corner and compared to the allowable value.

The results for the critical loading case are summarized in Table 4-4. The minimum safety factor for soil bearing for this loading condition is 1.0.

Stability calculations were performed for overturning and sliding. The results for the critical loading case are summarized in Table 4-5. The minimum safety factors for overturning and sliding for this loading condition are 4.59 and 3.10 respectively.

4.6.2 Structural Acceptance Criteria for S ent Puel Stora e Racks 4.6.2.1 Criteria There are two sets of criteria to be satisfied by the rack modules:

a. Kinematic Criterion This criterion seeks to ensure that the rack is a physically stable structure. St Lucie racks are designed to sustain certain intermack impact at designated locations in the rack modules. Therefore, physical stability of the rack is considered along with the localized inter-rack impacts.

Localized permanent deformation of the module is permissible, so long as the subcriticality of the stored fuel array is not violated.

b. Stress Limits The stress limits of the ASME Code, Section III, Subsection NP, 1983 Edition up to and including Summer 1984 Addenda are used since this code provides the most appropriate and consistent set of limits for various stress types and various loading conditions.

4.6.2.2 Stress Limits for Specified Conditions The following stress limits are derived from the guidelines of the ASME Code,Section III, Subsection NP, in conjunction with the material properties data of Subsection 4. 6.2.3.

4-23 0077L/0011L

~ 4 4.6.2.2.1 Normal and Upset Conditions (Level A or Level B Service Limits)

Allowable stress in tension on a net section = Ft = 0.6 Sy or (0.6) (23,150) = 13,890 psi (rack material) is equivalent to primary membrane stresses Ft = (.6) (23,150) = 13,890 psi (upper part of support feet)

(.6) (101,040) = 60,600 psi (lower part of support feet)

b. On the gross section, allowable stress in shear is:

Fv .4 Sy

(.4) (23,150) = 9,260 psi (main rack body)

(.4) (23,150) = 9,260 psi (upper part of support feet)

(.4) (101,040) = 40,400 psi (lower part of support feet)

C~ Allowable stress in compression, Fa:

(1 1/2A C ) Sy 5

3

+ 3G!

8Cc 8C 3 2 w2 Z 1/2 where G! kl/r and Cc =

S kl/r for the main rack body is based on the full height and cross section of the honeycomb region. Substituting numbers, we obtain, for both support leg and honeycomb region:

Fa ~ 13,890 psi (main rack body)

Fa ~ 13,890 psi (upper part of support feet) 60,600 psi (lower part of support feet) d~ Maximum allowable bending stress at the outermost fiber due to flexure about one plane of symmetry:

Fb ~ 0.60 Sy 13,890 psi (rack only) 13,890 psi (upper part of support feet)

~ 60,600 psi (lower part of support feet)

e. Combined flexure and compression:

+

Cmx Dx Fbx fbx

+

Cmy Dy Fby fby

( 1 0077L/0011L 4-24 Revision 1

where:

~ Direct compressive stress in the section fbx Maximum flexural stress about xmxis fby ~ Maximum flexural stress about ymxis Cmx Cmy

~ 0 ~ 85 fa D

F'ex fa Dy =1 F'

where:

12~2 E F'ex, ey klbx,y 2 23 rbx~y lb and rb indicate unbraced length and radius of gyration about the concurrent plane (x or y) and the subscripts x,y reflect the particular axis of bending.

f. Combined flexure and compression (or tension):

fa fbx 0.6sy Fbx

+

fby Fby

( 1.0 The above requirement should be met for both the direct tension and compression case.

4.6.2 .2 .2 Faulted Condition (Level D Service limits)

Paragraph F-1370 (Section III, Appendix F)(2 ), states that the limits for the Level D condition are the minimum of 1 2 (S /Ft) or (0.7Su/Ft) times the corresponding limits for Level A condition. Since 1.2 Sy is less than 0 7 Su for the rack material, and for the upper part of the support feet, the multiplying factor for the limits is 2.0 for the SSE condition for the upper section. The factor is 1.62 for the lower section under SSE conditions.

Instead of tabulating the results of these six different stresses as dimensioned values, they are presented in a dimensionless form. These somalled stress factors are defined as the ratio of the actual developed tress to its specified limiting value. Hith this definition, the limiting alue of each stress factor is 1. 0 for OBE and 2 .0 or 1.62 for the SSE condition.

0077L/0011L 4-25 Revision 1

4.6.2.3

~ ~ ~ Material Properties The dat a on the physical properties of the rack and support materials, obtained from the ASME Boiler & Pressure Vessel Code, Section III, appendices, and supplier's catalog, are listed in Tables 4-8 and 4-9. The reference design temperature for evaluation of material properties is 200oF.

4.6.2.4 Results for Rack Analysis Figures 4-12 through 4-14 show the pool slab motion in horizontal x, horizontal y and vertical directions. This motion is for the SSE.

Results are abstracted in Table 4-10 for modules B2, Hl and Gl (Figure 2-1).

A complete synopsis of the analysis of these modules subject to the SSE earthquake motions is presented in a summary Table 4-10 which gives the bounding values of stress factors Ri (i ~ 1,2,3,4,5,6). The stress factors are defined as:

Ratio of direct tensile or compressive stress on a net section to its allowable value (note support feet only support compression)

R2 Ratio of gross shear on a net section to its allowable value R3 Ratio of maximum bending stress due to bending about the x-axis to its allowable value for the section R4 ~ Ratio of maximum bending stress due to bending about the ymxis to its allowable value Combined flexure and compressive factor (as defined in 4.6.2.2.le)

R6 Combined flexure and tension (or compression) factor (as defined in 4.6.2.2.1f)

As stated before, the allowable value of R (i = 1,2,3 4,5 6) is 1 for the OBE condition, exce t for the lour section o t e support where the factor is 1.62 , and 2 for the SSE.

The dynamic analysis gives the maximax (maximum in time and in space) values of the stress factors at critical locations in the rack module. Since these maximax values are subject to minor (under 5X) variation if the input data (viz., rack baseplate height, cell inside dimension) is perturbed within the range of manufacturing tolerances, the bounding values, instead of the actual values, are presented in Table 4-10. The terms in Table 4-10 have the following meaning:

a b

implies implies implies Ri Ri ((( 1,0 1,5 c

d implies Ri Ri ( 1.75.0 2

0077L/0011L 4-26 Revision 1

0 0 ~

~ ~

4 g

l1 4

It is found that the results corresponding to SSE are most critical when compared with the corresponding allowable limits. The results given herein are for the SSE. The maximum stress factors (Ri) are below the limiting value for the SSE condition for all sections. It is noted that the critical load factors reported for the support feet are all for the upper segment of the foot and are to be compared with the limiting value of 2 .0.

Analyses have been carried out to show that significant margins of safety exist against local deformation of the fuel storage cell due to rattling impact of fuel assemblies and against local overstress of impact bars due to inter-rack impact.

Analyses have also been carried out for the OBE condition to demonstrate that the stress factors are below 1.0. Results obtained for all rack sizes and shapes are enveloped by the data presented herein. Overturning has also been considered for the cases where racks are adjacent to open areas.

4.6.3 Fuel Handling Crane Uplift Anal sis An analysis was performed to demonstrate that the rack can withstand an uplift load of 4,000 pounds produced by a jammed fuel assembly. This load, which exceeds the capacity of the fuel handling crane, can be applied to any point of the fuel rack without violating the criticality or structural acceptance criteria. Resulting stresses are within acceptable stress limits, and there is no change in rack geometry of a magnitude which causes the criticality acceptance criterion to be violated.

4.6.4 Im ct Anal ses 4.6.4.1 Impact Loading Between Fuel Assembly and Cell Wall The local stress in a cell wall is estimated from peak impact loads obtained from the dynamic simulations. Plastic analysis is used to obtain the limiting impact load that can be tolerated. Including a safety margin of 2.0, the total limiting load for the number of cells is over 5.5 times the actual maximax (maximum in time and space) value.

4.6.4.2 Impacts between Adjacent Racks All of the dynamic analyses assume, conservatively, that adjacent racks move completely out of phase. Thus, the highest potential for inter-rack impact is achieved. Based on the dynamic loads obtained in the gap elements simulating adjacent racks, we can study rack integrity in the vicinity of the impact point. The use of framing material around the top of the rack allows the rack to withstand impact loads totaling lx106 lbs applied along any edge of the rack at any instant of time reaching the fully yielded state above the active fuel region. The actual total rack-tomack impact loads along any rack edge do not exceed 500,000 lbs, and thus, impacts between racks can be accommodated without violating rack integrity. It is found that pool walls are sufficiently far away from the racks such that pool wall-tomack impact does not occur.

4.6.5 Weld Stresses The critical weld locations under seismic loading are at the connection of the rack to the baseplate and in the support leg welds. For the rack welds, the allowable weld stress is the ASME Code value of 27,300 psi for fillet welds and 42,000 psi for groove welds (Table NF-3324.5(a)-1, Subsection NF, with reference to Section III, Appendix F).

0077L/0011L 4-27 Revision 1

I ~

0

For the support legs, the allowable weld stress is governed by the levels outlined in Section 4.6.2 (see NF-3324.5 for partial penetration welds).

Held stresses due to heating of an isolated hot cell are also computed. The assumption used is that a single cell is heated over its entire length to a temperature above the value associated with all surrounding cells. No thermal gradient in the vertical direction is assumed so that the results are conservative. Using the temperatures associated with this unit, the skip welds along the entire cell length do not exceed the allowable value for a thermal loading condition.

4.6.6 Summary of Mechanical Analyses The mathematical model constructed to determine the impact velocity of falling objects is based on several conservative assumptions, such as:

The virtual mass (see Refs 8-10 for further material on the subject) of the body is conservatively assumed to be equal to its displaced fluid mass. Evidence in the literature(>>),

indicates that the virtual mass can be many times higher.

2 ~ The minimum frontal area is used for evaluating the drag coefficient.

3~ The drag coefficients utilized in the analysis are the lower bound values reported in the literature(12>. In particular, at the beginning of the fall when the velocity of the body is small, the corresponding Reynolds number is low, resulting in a large drag coefficient.

4~ ihe fa11dug bodies are assumed to be ~rd id for the purposes of impact stress calculation on the rack. The solution of the immersed body motion problem is found analytically. 'Jhe impact velocity thus computed is used to determine the maximum stress generated due to stress wave propagation.

With this model, the following analyses are performed:

a. Dropped Fuel Accident I A fuel assembly (weight is conservatively analyzed as 1500 pounds with control rod assembly) is dropped from 36 inches above the module and impacts the base (actual height is 36 1/2 inches; 1/2 inch difference between analysis and actual is considered insignificant). The final velocity of the dropped fuel assembly (just prior to impact) is calculated and, thus, the total energy at impact is known. To study baseplate integrity, it is assumed that this energy is all directed toward punching of the baseplate in shear and thus transformed into work done by the supporting shear stresses. It is determined that shearing deformation of the baseplate is less than the thickness of the baseplate so that we conclude that local piercing of the baseplate will not occur. Direct impact with the pool liner does not occur. The subcriticality of the adjacent fuel assemblies is not violated.

0077L/0011L 4-28 Revision 1

'1 ll e ~

b. Dropped Fuel Accident II One fuel assembly drops from 36 (actual maximum distance is 36 1/2 inches; 1/2 half inch difference between actual and analysis is deemed insignificant.) inches above the rack and hits the top of the rack. Permanent deformation of the rack is found to be limited to the top region such that the rack crossmectional geometry at the level of the top of the active fuel (and below) is not altered. The region of local permanent deformation does not extend below 6 inches from the rack top. An energy balance approach is used here to obtain the results.

c. Jammed Fuel Handling Equipment A 4000-pound uplift force is applied at the top of the rack at the "weakest" storage location; the force is assumed to be applied on one wall of the storage cell boundary as an upward shear force. The plastic deformation is found to be limited to the region well above the top of the active fuel.

These analyses prove that the rack modules are engineered to provide maximum safety against all postulated abnormal and accident conditions.

4.6.7 Definition of Terms Used in Section 4 Sl, S2, S3, S4 Support designations Pi Absolute degree-of-freedom number i Relative degreemf-freedom number i Coefficient of friction Pool floor slab displacement time history in the i-th direction x,y coordinates Horizontal direction z coordinate Vertical direction KI Impact spring between fuel assemblies and cell Linear component of friction spring Compression load in a support foot Rotational spring provided by the pool slab Subscript i When used 1

with U or X indicated direction indicates x-direction, i = 2 indicates (i ~

yMirection, i~ 3 indicates z-direction)

[M] Mass Matrix (generic notation)

Generalized coordinate vector Axial Spring of Support leg locations 0077L/0011L 4-29 Revision 1

4.6.8 Lateral Rack Movement Lateral motion of the rack modules under seismic conditions could potentially alter the spacing between rack modules. However, girdle bars on the modules prevent closing the spacing to less than 1.50 inches, which is greater than the normal flux-trap water-gap in the Region 1 reference design. Region 2 storage cells do not use a flux-trap and the reactivity is insensitive to the spacing between modules. Furthermore, soluble poison would assure that a reactivity less than the design limitation is maintained under all conditions.

4.7 MATERIALS, QUALITY CONTROL, AND SPECIAL CONSTRUCTION TECHNIQUES 4.7.1 Construction Materials Construction materials will conform to the requirements of the ASME Boiler and Pressure Vessel Code, Section III, Subsection NF. All the materials used in the construction are compatible with the storage pool environment and will not contaminate the fuel assemblies or the pool water. The plates, sheets, strips, bars and structural shapes used for rack construction are Type 304L stainless steel.

4.7.2 Neutron Absorbin Material The neutron absorbing material, Boraflex, used in the St Lucie spent fuel rack construction is manufactured by Bisco and fabricated to the safety-related nuclear criteria of 10 CFR 50, Appendix B. Boraflex is a silicone-based polymer containing fine particles of boron carbide in a homogeneous, stable matrix. The specification for the handling and installation of the poison material requires that it will not be installed in a stretched condition. The specification precludes the use of adhesives in the attachment of the boraflex to the rack cell walls. FPL will require that the manufacturing process avoid techniques which could pinch the boraflex. The design of the racks requires that additional lengths of boraflex, i.e. greater than the active length of a fuel assembly, be installed to account for anticipated shrinkage of the boraflex.

4.7.3 Qualit Assurance The design, procurement, and fabrication of the new high density spent fuel storage racks comply with the pertinent Quality Assurance requirements of Appendix B to 10 CFR 50 as implemented through: FPL's Topical Quality Assurance Report FPL-NQA-100A[9]; the Joseph Oat Quality Assurance Plan as described in their QA Manual; the Holtec's Nuclear Quality Assurance plan as described in their QA Manual; and the Ebasco Quality Assurance Program for Nuclear Plants, ETR-1001. All have been approved by the NRC.

4.7.4 Construction Techniques 4.7.4.1 Administrative Controls During Manufacturing and Installation The St. Lucie Unit I new spent fuel storage racks will be manufactured at the Joseph Oat Corp., Camden, New Jersey. This facility is a modern high-quality shop with extensive experience in forming, machining, welding> and assembling nuclear-grade equipment. Forming and welding equipment are specifically designed for fuel rack fabrication and all welders are qualified in accordance with ASME Code Section IX.

4-30 0077L/0011L

C C

II 0

I

To avoid damage to the stored spent fuel during rack replacement, all work on the racks in the spent fuel pool area will be performed using written and approved procedures. These procedures will preclude the movement of the fuel racks over the stored spent fuel assemblies.

Radiation exposures during the removal of the old racks from the pool will be controlled by procedure. For anticipated radiation doses see Table 5-5.

Water levels will be maintained to afford adequate shielding from the direct radiation of the spent fuel. Prior to rack replacement, the cleanup system will be operated to reduce the activity of the pool water to as low a level as can be practically achieved.

4. 7.4.2 Procedure 4.7.4.2.1 Preinstallation The following sequence of preinstallation events is anticipated for the spent fuel storage rack replacement for Unit I.

a. Design and fabricate new spent fuel storage racks.

b. Prepare modification procedure.

c. Fabricate and test all special tooling.

d. Receive and inspect new spent fuel storage racks.

4.7.4.2.

~ ~ ~ ~ 2 Installation The final configuration of the 17 new rack modules in the spent fuel pool is shown in Figure 2-1. The installation of these racks will be accomplished in accordance with the following considerations and guidelines:

A temporary construction crane will be installed and operated in the spent fuel pool area to move new and existing rack modules within the spent fuel pool.

At no time will this temporary crane carry a rack module directly over another module which contains stored spent fuel.

The temporary construction crane and all rack modules will be installed and/or removed from the spent fuel pool area with the fuel cask crane.

All load handling operations in the spent fuel pool area will be conducted in accordance with the criteria of Section 5.1.1 of NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants".

Spent fuel relocations within the pool will be performed as required to maintain separation between the stored fuel and the rerack operations.

4-31 0077L/0011L

0 I

0 p

1 I'

4.8 TESTING AND IN-SERVICE SURVEILLANCE

.8.1 Program Intent A sampling program to verify the integrity of the neutron absorber material employed in the high density fuel racks in the St Lucie fuel pool environment is described in the following paragraphs.

The program is conducted in a manner which allows access to the representative absorber material samples without disrupting the integrity of the entire fuel storage system. The program is tailored to evaluate the material in normal use mode and to forecast future changes using the data base developed.

4.8.2 Description of Specimens The absorber material used in the surveillance program, henceforth referred to as "poison", is representative of the Boraflex material used within the storage system. It is of the same composition, produced by the same method, and certified to the same cxiteria as the production lot poison. The sample coupon is of a thickness similar to the poison used within the storage system and not less than 5 by 15 inches on a side. Figure 4-19 shows a typical coupon. Each poison specimen is encased in a stainless steel jacket of an austenitic stainless steel alloy identical to that used in the storage system, formed so as to encase the poison material and fix it in a position and with tolerances similar to the design used for the storage system. The jacket is closed by tack welding in such a manner as to retain its form throughout the test period and still allow rapid and easy opening without causing mechanical damage to the poison specimen contained within.

e jacket permits wetting and venting of the specimen similar to the actual rack nvironment.

4.8.3 Specimen Evaluation After the removal of the jacketed poison specimen from the cell at a designated time, a careful evaluation of that specimen will be made to determine its actual condition as well as its apparent durability for continued function. Immediately after the removal, the specimen and jacket section will be visually examined for any effects of environmental exposure. Specific attention will be directed to the examination of the stainless steel jacket for any evidence of physical degradation. Functional evaluation of the poison material will be accomplished by the following measurements:

o A neutron radiograph of the poison specimen aids in the determination of the maintenance of uniformity of the boron distribution.

Neutron attenuation measurements will allow evaluation of the continued nuclear effectiveness of the poison. Consideration will be given in the analysis of the attenuation measurements to the level of accuracy of such measurements, as indicated by the degree of repeatability normally observed by the testing agency.

A measurement of the hardness of the poison material will establish the continuance of physical and structural durability. The hardness acceptability criterion requires that the specimen hardness will not be less than hardness listed in the qualifying test document for laboratory test specimen irradiated to 10 rads. The actual hardness measurement will be made after the specimen has been withdrawn from the pool and allowed to air dry for not less than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to allow for a meaningful correlation with the pre-irradiated sample.

0077L/0011L 4-32 Revision 1

I ~

A 1

Measurement of the length, the width, and the average thickness and comparison with the pre-exposure data will indicate dimensional stability within the variation range reported in the Boraflex laboratory test reports.

In the event of any observed deterioration of the coupon that could affect the poison function, an immediate inspection of the "poison panels" in the rack will be performed. The NRC will be advised immediately indicates degradation of the poison material.

if the inspection

4.9 REFERENCES

FOR SECTION 4 Nuclear Regulatory Commission, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants", NUREG-0800, Revision 1, July 1981.

2~ ASME Boiler 6 Pressure Vessel Code,Section III, Subsection NF (1983 Edition up to and including Summer 1984 Addenda).

3. USNRC Regulatory Guide 1.29, "Seismic Design Classification," Rev 3, 1978.

4~ "Friction Coefficients of Water Lubricated Stainless Steels for a Spent Fuel Rack Facility," Prof. Ernest Rabinowicz, MIT, a report for Boston Edison Company, 1976.

5~ USNRC Regulatory Guide 1.92, "Combining Modal Responses and Spatial Components in Seismic Response Analysis," Rev 1, February 1976.

"The Component Element Method in Dynamics with Application to Earthquake and Vehicle Engineering," S Levy and J P D Wilkinson, McGraw Hill, 1976.

7~ "Dynamics of Structures," R W Clough and J Penzien, McGraw Hill (1975).

8. "Mechanical Design of Heat Exchangers and Pressure Vessel Components,"

I Chapter 16, K P Singh and A Soler, Arcturus Publishers,. Inc., 1984.

9. R J Fritz, "The Effects of Liquids on the Dynamic Motions of Immersed Solids," Journal of Engineering for Industry, Trans. of the ASME, February 1972, pp 167-172.

10. "Dynamic Coupling in a Closely Spaced Two-Body System Vibrating in I

Liquid Medium: The Case of Fuel Racks," K P Singh and A Soler, 3rd International Conference on Nuclear Power Safety, Keswick, England, May 1982.

"Flow Induced Vibration," R D Blevens, VonNostrand (1977).

12. "Fluid Mechanics," M C Potter and J F Foss, Ronald Press, p. 459 (1975).

13. St Lucie Plant Unit I, Updated Final Safety Analysis Report, Docket No 50-335.

4-33 0077L/0011L

e J1

, I

Table 4-1 BORAFLEX EXPERIENCE FOR HIGH DENSITY RACKS Plant NRC Site Type Docket No.

Point Beach 1 & 2 50-226 & 301 Nine Mile Point 1 50-220 Oconee 1 & 2 50-269 & 270 Prairie Island 1 & 2 50-282 & 306 Calvert Cliffs 2 50-318 Quad Cities 1 & 2 50-254 & 265 Watts Bar 1 & 2 50-390 & 391 Waterford 3 50-382 Fermi 2 50-341 H B Robinson 2 50-261 River Bend 1 BWR 50-458 Rancho Seco 1 50-312 Nine Mile Point 2 BWR 50-410 Shearon Harris 1 50-400 Millstone 3 50-423 Grand Gulf 1 50-416 Oyster Creek BWR 50-219 V C Summer 50-395 Diablo Canyon 1 & 2 50-275 & 323 Byron Units 1 & 2 50-454 & 455 4-34 0077L/0011L

TABLE 4-2 MAXIMUM STRESS

SUMMARY

(UNIT ~ LBS PER SQUARE INCH (PSI))

Loading Maximum Stress Maximum Compression Stress Maximum Shear Stress Case (See of Rebar of Concrete of Concrete Section SF WALL SP MAT SF WALL SP MAT SP WALL 4.4.1.2) 19,937 1.81 8,'610 4'.18 -616 6.46 -338 11.77 83 1.48 65 1.90 8 elmt 8 elmt 8 elmt 8 elmt 8 elmt 8 elmt 81 206 81 156 81 156 14,979 2.40 23,549 1.53 -938 4.24 -903 4.41 115 1.07 114 1.08 8 elmt 8 elmt 8 elmt 8 elmt 8 elmt 8 elmt 3 184 9 266 5 280 14,333 2.51 18,646 1.93 -653 6.09 653 6.10 107 l. 15 115 1.07 8 elmt 8 elmt I elmt 8 elmt 8 elmt 8 eimt 5 130 9 266 5 190 I

4) lv 18,153 1.98 18,743 1.92 -701 5. 67 -444 8.96 80 1.54 40 3.07 8 elmt 8 elmt 8 elmt I elmt 8 elmt 8 elmt 5 288 5 136 5 288 20,403 1.76 32,715 1.10 1056 3.77 -1090 3.65 66 1.86 117 1.05 8 elmt 8 elmt 8 elmt 8 elmt 8 elmt 8 elmt 79 234 9 266 5 288 vi 23,375 1.54 25,486 1.41 -1049 3.79 -722 5.51 117 1.05 78 1.58 8 elmt 8 elmt 8 elmt 8 elmt 8 elmt 8 elmt 25 184 9 266 25 280 vii 20,800 1'.73 12,742 2.83 -576 6.91 -524 7.59 76 1.62 55 2.24 I elmt I elmt 8 elmt 8 elmt 8 elmt 8 elmt 5 204 5 102 9 102

1. Ultimate Rebar Stress Fa 36,000 psi.

2. Ultimate Concrete Compressive Stress P ~ 3,978 psi

3. Ultimate Concrete Shear Stress Pv 125 psi

4. SP Safety Fa'ctor (See Section 4.6.1.3)

l I TABLE 4-3 STRESS/STRAIN

SUMMARY

POR LINER AND ANCHORS Stress or Porce Strain or Dis 1 Actual Allowable SF Actual Allowable SF Remark Liner -11.1 No Buckling -3.847x10 " -2.0x10 5.20 Constraint-ksi due to in/in in/in Induced Load hydrostatic pressure.

Liner Evaluation not required 0.025 in 0.0625 in 2.5 Constraint-Anchor by Code. Induced Load 1.525 2.03 1.33 Evaluation not required Horizontal kips/in kips/in by Code. Seismic Load (N-S)

NOTE: Actual stress and strain are based on Pactored (abnormal)

Load condition and allowables are based on Service (normal)

Load condition where these terms are as defined in Paragraph CC-3220 of ACI-ASME Section III Division 2.

4-36 0077L/0011L

o TABLE 4-4 SOIL BEARING STRESSES (KSF)

Corner Location D + L + SSE N-E 4.1 S-E 1.7 N-W 12. 0 S-W 7.9 NOTE: Allowable soil bearing stress is 12.0 KSF 4-37 0077L/0011L

P V l TABLE 4-5 STABILITY SAFETY FACTORS Earthquake Overturning Sliding Loading Type D + L + SSE D + L + SSE SSE(N-S) + Vert. Up 7. 82 3.10 SSE(E-W) + Vert. Up 4. 59 3.31 4-38 0077L/0011L

Table 4W DEGREES OF FREEDOM Displacement Rotation Location ux uy uz Oy (Node) pl p2 p3 q4 q6 Point 1" is assumed fixed to base at X~, y>, Z=O Point 2 is assumed attached to rigid rack at the top most point.

p7 p8 Pi - qi (t) + Ui(t)

Other p9, pl0 Rattling pll, p12 Node points 3*, 4*, 5*

Masses pl3, p14 p15, p16 0077L/0011L 4-39 Revision 1

0 Table 4-7 NUMBERING SYSTEM FOR GAP ELEMENTS AND FRICTION ELEMENTS I. Nonlinear Sprin s (Gap Elements) (64 total)

Number Node Location Descri tion Support Sl Z compression only element Support S2 Z compression only element Support S3 Z compression only element Support S4 Z compression only element 2 ~2* X rack/fuel assembly impact element 2 ~2* X rack/fuel assembly"impact element 2,2* Y rack/fuel assembly impact element 2* Y rack/fuel assembly impact element 9-24 Other rattling masses 25<4 Bottom cross-section Inter~ack impact elements of rack (around edge) 45%4 Top cross-section Inter mack impact elements of rack (around edge) Inter mack impact elements II. Friction Elements (16 total) umber Node Location Descri tion 1 Support Sl X direction friction 2 Support Sl Y direction friction 3 Support S2 X direction friction 4 Support S2 Y direction friction 5 Support S3 X direction friction 6 Support S3 Y direction friction 7 Support S4 X direction friction 8 Support S4 Y direction friction 9 Sl X Slab moment 10 Sl Y Slab moment ll 12 S2 S2 X

Y Slab Slab moment moment 13 S3 X Slab moment 14 S3 Y Slab moment 15 S4 X Slab moment 16 S4 Y Slab moment 0077 L/001 1L 4<0 Revision 1

Table 4W RACK MATERIAL DATA Young' Yield Ultimate Modulus Strength Strength Material E (psi) Sy (psi) Su (psi) 304L Stainless 27.9 x 106 23,150 65,000 Steel ASME Section III Table Table Table I-3 Reference 1%.0 I-2 .2 ~ 2 0077L/0011L 4-41 Revision 1

I

~

Table 4H AIUUSTABLE HEIGHT SUPPORT MATERIAL DATA (Reference Temperature = 150oF)

Young's Yield Ultimate Modulus x 106 Strength Strength Material (psi) ksi ksi Upper part 27.9 23.15 65 (Female)

SA-240-304L Lower Part 27. 9 101. 04 140 (Male)

SA&64 %30 (age hardened to 1100oF) 0077L/0011L 4<2 Revision 1

TABLE 4-10 BOUNDING VALUES FOR STRESS FACTORS Stress Factors*

Rl R2 R3 R4 R5 R6 Run No. (Upper values for rack base lower values for upper part of the support feet)

SSE a a

.8, full a a Module B2 SSE a a a

/l ~ .2, full a a a Module B2 SSE a a a a p, .8, 10 cells a a a a loaded Module B2

• The terms a, b, c and d imply the stress factors Ri (i 1, 2 ... 6) are bounded by the following limiting values:

a: 1.0 b: 1.5 c: 1.75 d~ 2 0077L/0011L 4<3 Revision 1

c ~ 1 TABLE 4-10 (Cont'd)

BOUNDING VALUES FOR STRESS FACTORS Stress Factors*

Rl R2 R3 R4 Rg R6 Run No. (Upper values for rack base lower values for upper part of the support feet)

SSE a a a a

.8, a a a a Module Hl full SSE a a a P~.8 a a a Module Hl Positive x&alf loaded SSE a a a a a

.2, a a a a a Module Hl Positive x-half loaded 0077L/0011L 4-44 Revision 1

0 TABLE 4-10 (Cont'd) e BOUNDING VALUES FOR SZKSS FACTORS Stress Factors~

Rl R2 R3 R4 R5 R6 Run No. (Upper values for rack base lower values for upper part of the support feet)

SSE a a a a a a p, .2, 10 cells a a a a a a loaded Module B2 SSE a a a a p, .8, Positive a a a a x&alf loaded Module B2 SSE a a a a a JL .2, Positive a a a a a x&alf loaded Module B2 SSE a a a a

.8, Full a a c c Module Gl 0077L/0011L 4-45 Revision 1

0 TABLE 4-10 (Cont'd)

BOUNDING VALUES FOR S'IRESS FACTORS Stress Factors*

Rl R2 R3 R4 Rg R6 Run No. (Upper values for rack base lower values for upper part of the support feet)

SSE a a a a a

/g= o2 a a a a a Module Gl Full SSE a a a

.2 a c c Module Gl Positive x half loaded SSE a a a a a

.2, Module Gl a a a a a Positive x half loaded SSE a a a a

.2 a a a a Module Gl 10 Cells loaded 0077L/0011L Revision 1

'll e

4.335" + .015" Cl

+I LA CO CO

.08R" FLORIDA POWER & LIGHT COMPANY

. ST. LUCIE PLANT UNIT 1 CHANNEL ELEMENT REGIONS 1 &2 (2 FOR SQUARE CELL)

FIGURE 4-0

SQUARE TUBE (FROM 2 FORMED CHANNELS) 8.650" + .032" SQ.

COVER SHEET

.020" + .003" NEUTRON ABSORBER SHEET FLORIDA POSER 5 LIGHT COMPANY ST. LUCIE PLANT UNIT 1 COMPOSITE BOX ASSEMBLY REGION 1 FIGURE 4-2

.080" FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT 1 GAP ELEMENT- REGION 1 FIGURE 4-3

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I I BASE Pl.ATE 3/4" THK.

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CO GUSSET PLAT lO lO 5 1/2" 4 UNC CLASS 1A 9" DIA.

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2 1 /2" D(A. IFLOW HOLES 60 DEG. APAR REVISION I FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT 1 ADJUSTABLE SUPPORT FIGURE 4.6

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FLORIDA POWER 5 LIGHT COMPANY ST. LUCIE PLANT UNIT 1 3 x 3 TYPICALARRAY REGION 1 FIGURE'4-7/

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'WEST WALL SOUTH WALL MAT ll 0

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~ C/l ~~

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g 1 2 TYP. FRICTION ELEMENT REVISION 1 F LOR IDA POWER 5 LIGHT COMPANY ST. LUCIE PLANT UNIT 1 SCHEMATIC MODEL FOR DYNRACK FIGURE 4-16

TYPICAL TOP IMPACT ELEMENT RACK STRUCTURE TYP. BOTTOM IMPACT ELEMENT FLORIDA POWER 5 LIGHT COMPANY ST. LUCIE PLANT UNIT 1 RACK-TO.RACK IMPACT SPRINGS FIGURE 4-16

CELL WALL MASS i XB j%

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/ FUEL ASSEMBLY/CELL IMPACT SPRING

//

/

YB

/

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FLORIDA POWER 5 LIGHT COMPANY ST. LUCIE PLANT UNIT 1 IMPACT SPRING ARRANGEMENT AT NODE I FIGURE 4-47

K GAP ELEMENTS TO SIMULATE INTER. RACK IMPACTS (4 FOR 2 - D MOTION 20 FOR 3 - D MOTION) .

RACK CENTROID (ASSUMED AT H/2)

RIGID RACK BASEPLATE Kf gR KR Kf REVISION 1 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT 1 SPRING MASS SIMULATION FOR TWO-DIMENSIONALMOTION FIGlfAE 4-18

TACK WELD

~

~ I

~ ,075" THK. FILLER FOR REGION

.031" THK. FILLER 1

(is

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FOR REGION 2 p ~~ (304 L S.S.T) 16 3/4" o+

NEUTRON ABSORBER 3/8"

.080" THK.

S.S. - 304L.

REVISION I FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT 1 TEST COUPON AGURE 4-19

5.0 COST/BENEFIT AND ENVIRONMENTAL ASSESSMENT 5.1 COST/BENEFIT AND THERMAL ASSESSMENT The cost/benefit of the chosen reracking alteration is demonstrated in the following sections.

5.1.1 Need for Increased Storage Capacit

a. FPL currently has no contractual arrangements with any fuel reprocessing facilities.

FPL executed three contracts with the Department of Energy (DOE) on June 16, 1983 pursuant to the Nuclear Waste Policy Act of 1982, but the disposal facilities are not expected to be available for spent fuel any earlier than 2003.

b. Table 5-1 includes a proposed refueling schedule for St. Lucie Unit 1 and the expected number of fuel assemblies that will be transferred into the spent fuel pool at each refueling until the total existing capacity is reached and it becomes impossible to conduct a full refueling past cycle 9-10 shutdown in 1991. At present the licensed capacity of Unit 1 is 728 storage cells. All calculations in the table for loss of full core reserve (FCR) are based on the number of licensed total cells in the pool. The table is then continued assuming the installation of 1706 replacement cells and loss of full core reserve is projected in the year 2009.

c. The St. Lucie Unit 1 spent fuel pool is expected to contain 529 spent fuel assemblies at the time of reracking.

d. Adoption of this proposed spent fuel storage expansion would not necessarily extend the time period that spent fuel assemblies would be stored on site. Spent fuel will be sent offsite for final disposition under existing legislation, but the government facility is not expected to be available until after 2003.

e. The estimated date when the spent fuel pool will be filled with the proposed increase in storage capacity is provided in Table 5-1. In addition to the fuel assemblies, six storage locations are occupied by non-fuel equipment (e.g. dummy fuel assembly, trash basket, etc.).

5.1.2 Estimated Costs Total construction cost associated with the proposed modification is 8 million dollars. This figure includes the cost of designing and fabricating the spent fuel racks; engineering costs; and installation and support costs at the site.

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5.1.3 Consideration of Alternatives

a. There are no operational commercial reprocessing facilities available for FPL's needs in the United States, nor are there expected to be'ny in the foreseeable future.

b. At the present time, there are no existing available independent spent fuel storage facilities. While plans are being formulated by DOE for construction of a spent fuel repository per the Nuclear Waste Policy Act of 1982, this facility is not expected to be available to accept spent fuel any earlier than 2003.

c. At present, FPL has no license to transship fuel between facilities.

St. Lucie Unit 1 lost full core reserve capacity upon startup of cycle 7 in 1987. Permanent transfer of St. Lucie Unit 1 spent fuel to other facilities would only compound storage problems there and is not,a viable option.

d. Estimates for costs of replacement power were calculated based on the last official rate of return. The assumption was made that the unit could be operated without maintaining full core reserve, thus cycle 09-10 in 1990 would be the last refueling possible with existing storage capacity. Table 5-2 indicates the average yearly fuel cost increases for St. Lucie Unit 1 after three years of shutdown. Plant shutdown would place a heavy financial burden on Florida residents within FPL's service area and cannot be justified.

5.~ 1.4

~ Resources Committed Reracking of the spent'uel pools will not result in any irreversible and irretrievable commitments of water, land, and air resources. The land area now used for the spent fuel pools will be used more efficiently by safely increasing the density of fuel storage.

The materials used for new rack fabrication are discussed in Section 4.7.1.

These materials are not expected to significantly foreclose alternatives available with respect to any other licensing actions designed to improve the possible shortage of spent fuel storage capacity.

5.1.5 Thermal Impact on the Environment Section 3.2 considered the following: the additional heat load and the anticipated maximum temperature of water in the SFP that would result from the proposed expansion, the resulting increase in evaporation rates, the additional heat load on component and/or plant cooling water systems, and whether there will be any significant increase in the amount of heat released to the environment. As discussed in Section 3.2, the proposed increase in storage capacity will result in an insignificant impact on the environment.

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5.2 RADIOLOGICAL EVALUATION 5.2.1 Solid Radwaste Currently, resins are generated by the SFP purification system. Current frequency of resin change out is approximately once per year. No significant increase in volume of solid radioactive wastes is expected due to the new racks. It is estimated that a minimal amount of additional resins will be generated by the spent fuel pool cleanup system during reracking. The most recent isotopic analysis of the spent fuel pool resin is present in Table 5-7.

Operating plant experience with high density fuel storage has not indicated any noticeable increase in the solid radioactive wastes generated by the increased fuel storage capability.

5.2.2 Gaseous Releases Table 5-3 summarizes the PHB Gaseous releases in 1985 and 1986. No significant increases are expected as a result of the reracking.

5.2.3 Personnel Ex osure The range of values for recent (October 1985 refueling) gamma isotopic analyses of spent fuel pool water is shown on Table 5-4.

b. Operating experience shows dose rates of less than 10 mrem/hour either at the edge or above the center of the spent fuel pools regardless of the quantity of fuel stored. This is not expected to change with the proposed reracking because radiation levels above the pool are due primarily to radioactivity in the water, which experience shows to return to a level of equilibrium.

Stored spent fuel is so well shielded by the water above the fuel that dose rates at the top of the pool from this source are negligible.

c~ There have been negligible concentrations of airborne radioactivity from the spent fuel pools. Operating plant experience with dense fuel storage has shown no noticeable increases in airborne radioactivity above the spent fuel pool or at the site boundary. Recent spent fuel pool airborne radioactivity is depicted in Table 5-8. No significant increases are expected from more dense storage.

dO As stated in Section 5.2.1, reracking and utilization of the new racks will result in no significant increase in the radwaste generated by the spent fuel pool cleanup system. This is because operating experience has shown that with high density storage racks, there is no significant increase in the radioactivity levels in the spent fuel pool water, and no significant increase in the annual man-rem due to the increased fuel storage, including the changing of spent fuel pool cooling system resins and filters.

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e. Most of the corrosion products "crud" associated with spent fuel storage is released soon after fuel is removed from the reactor. Once fuel is placed into the pool storage positions, additional crud contribution is minimal.

The highest possible water level is maintained in the spent fuel pool to keep exposure as low as reasonably achievable. Should crud buildup ever be detected on the spent fuel pool walls around the pool edge, it could easily be washed down.

There is no access underneath the spent fuel pool. During normal operation, the radiation dose rate around the outside of the pool could increase locally up to .53 mrem per hour should freshly di.scharged fuel be located in the cells adjacent to the pool liner. This dose rate will decrease to below .25 mrem per hour after approximately 25 days. The depth of the water above the fuel is sufficient so there will be no measurable increase in dose rates above the pool due to radiate.on emitted directly from the fuel.

Operating experience has shown a negligible increase in man-rem due to the increased fuel storage with high density racks. Therefore, a negligible increase in the annual man~em is expected at St. Lucie as a result of the increased storage capacity of the spent fuel pools with the higher density storage racks.

The existing St. Lucie or Turkey Point health physics program did not have to be modified as a result of the previous increase in storage of spent fuel. It is not anticipated that the health physics program will need to be modified for this increase in storage capability.

5.2.4 Radiation Protection Durin Re-Rack Activities 5.2.4.1 General Description of Protective Measures The radiation protection aspects of the spent fuel pool modification are the responsibility of the Plant Health Physicist, who is assisted by his staff, with the support of the Corporate Health Physicist and his staff. Gamma radiation levels in the pool area are constantly monitored by the station Area Radiation Monitoring System, which has a high level alarm feature.

Additionally, periodic radiation and contamination surveys are conducted in work areas as necessary. Hhere there is a potential for significant airborne radionuclide concentrations, continuous air samplers can be used in addition to periodic grab sampling . Personnel working in radiologically controlled areas will wear protective clothing and when required by work area conditions respiratory protective equipment, as required by the applicable Radiation Work Permit (RWP). Personnel monitoring equipment is assigned to and worn by all personnel in the work area. At a minimum, this equipment consists of a thermoluminescent dosimeter (TLD) and self-reading pocket dosimeter.

Additional personnel monitoring equipment, such as extremity badges, are utilized as required.

Contamination control measures are used to protect persons from internal 0 exposures to radioactive material and to prevent the spread of contamination.

Work, personnel traffic, and the movement of material and equipment in and out of the area are controlled so as to minimize contamination problems. Material 5-4 0078L/0011L

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and equipment will be monitored and appropriately decontaminated and/or wrapped prior to removal from the spent fuel pool area. The station radiation protection staff will closely monitor and control all aspects of the work so that personnel exposures, both internal and external, are maintained as low as reasonably achievable (ALARA).

Water levels in the spent fuel pool will be maintained to provide adequate shielding from the direct radiation of the spent fuel. Prior to rack replacement, the spent fuel pool cleanup system will be operated to reduce the activity of the pool water to as low a level as can be practically achieved.

5.2 .4.2 Anticipated Exposures During Reracking Table 5-5 is a summary of expected exposures for each phase of the Unit 1 reracking operation. Xhese estimates are made based on the proposed installation plan, including fuel transfers, the use of long&andled tools, and the onsite decontamination cleanup and packaging of the old storage racks. Also, current pool radioactivity levels were conservatively increased in calculating these exposures. %he total occupational exposure for the Unit 1 reracking operation is conservatively estimated to be between 10 and 15 person mern. See Table 5-5.

5.2.5 Rack Disposal

%he spent fuel storage rack modules that will be removed from the spent fuel pool weigh between 30,000 and 42,000 pounds each. %he total weight of these racks is approximately 222 tons and the racks occupy a total uncompacted e volume of approximately 11,900 ft3. ihey will be cleaned of loose contamination, packaged and shipped to a licensed radioactive waste processing facility.

Shipping containers will meet the requirements of DOT regulations pertaining to radioactive waste shipments, including limitations with respect to the waste surface dose and radionuclide activity distribution. Shipping containers will be certified to meet all requirements for a strong tight package. The maximum weight of a loaded shipping container will be in accordance with the American Association of State Highway and Transportation Officials (AASHTO). Trucks and drivers used for rack and waste transportation will have all permits and qualifications required by the Federal DOT and the DOT for each State through which the truck will pass.

At the waste processing facility, the racks will be decontaminated to the maximum extent possible. Remaining portions of the racks and contaminated waste generated from decontamination will be buried at a licensed radioactive waste burial site. In preparing non-decontaminable waste for shipment and subsequent burial, volume reduction methodologies will be employed such as compaction, combining metallic materials with "soft waste" to minimize void space, and super compaction where feasible.

0078L/0011L Revision 1

5. 3 ACCIDENT EVALUATION 5 .3.1 S ent Fuel Handling Accidents 5.3.1.1 Fuel Assembly Drop Analysis For a drop on top of the rack, the fuel assembly will come to rest horizontally on top of the rack with a minimum separation distance from the fuel of more than 12 inches, sufficient to preclude neutron coupling. Maximum expected deformation under seismic or accident conditions will not reduce the minimum spacing between the dropped assembly and the stored fuel assemblies to less than 12 inches. Consequently, fuel assembly drop accidents will not result in a significant increase in reactivity due to the separation distance. Furthermore, soluble boron in the pool water would substantially reduce the reactivity and assure that the true reactivity is always less than the limiting value for any conceivable dropped fuel accident.

As discussed in Section 4.1.2.2, the proposed spent fuel pool modifications will not increase the radiological consequences of fuel handling accidents previously evaluated in Section 9.1.4.3 of the St Lucie Unit 1 Updated FSAR<2).

5.3.1.2 Cask Drop Analysis t

5.3.1.2.1 Cask Handling As discussed in Subsection 9.1.4.3 of the St Lucie Unit 1 Updated FSAR~

limit switches prevent movement of the cask beyond the spent fuel cask storage area in the northeast corner of the fuel pool; prevent interference of the cask crane bridge, trolley, and hoist with fuel racks or building structures; and restrict vertical lift of the cask to an elevation sufficient to gain entry to the Fuel Handling Building. The rerack program does not alter the cask handling procedures described in Updated FSAR Section 9.1. The cask handling crane meets the design and operational requirements of Sanction 5.1.1 of NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants"< i.

5.3.1.2.2 Radiological Consequences For the calculation of radiological consequences potentially resulting from a cask drop accident, two cases were evaluated regarding the number of fuel assemblies that are assumed to suffer a loss of integrity:

Case I: One-third of a core is placed in the spent fuel pool each year during refueling for the next 23 years, until the pool is filled. The number of assemblies damaged is equal to the number offloaded during a normal refueling plus the remainder of the pool filled with discharged assemblies from previous refuelings.

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Case II: One-third of a core is placed in the spent fuel pool each year during refueling for the next 20 years. Following the 21st year of operation, the entire core is removed from the reactor and placed into the pool, which fills the pool. The number of assemblies damaged is equal to a full-core offload plus the remainder of the pool filled with discharged assemblies from previous refuelings.

The model for calculating the thyroid and whole-body exclusion area boundary doses incorporates the conservative assumptions speciff,e$ in Standard Review Plan (SRP) Section 15. 7. 5 and Regulatory Guide 1.25~ with the exception that a 1.0 Radial Peaking Factor (RPF) is utilized. An RPF of 1.65 as specified in Regulatory Guide 1.25 is intended to represent the highest burnup fuel assembly. awhile this value may be appropriate for the analysis of a postulated accident involving a single assembly, it is grossly overconservative when applied to an analysis of a normal refueling batch or a full core whose fuel assemblies have various exposure histories. An RPF of 1.0 has been selected as being more representative for the off-load of one or more regions from the coze and has been applied to each assembly in the present analysis. The use of a 1.0 RPF for the calculation of cask drop radiological consequencyy has been previously submitted to the NRC for FPL's St. Lucie Unit 1 plant.<o)

The core inventory used in the analysis of the dropped spent fuel cask is given by the St. Lucie Unit 1 Updated FSAR Table 15.4.1-1c. As indicated in the St. Lucie Unit 1 Updated FSAR Table 15.4.1-4 and the St. Lucie Unit 1 Updated FSAR Subsection 2.3.4.3, the 0-2 hour exclusion area boundary (EAB) X/9 value of 8.55 x 10 5 sec/m3 is used for the analysis. The results of the analysis demonstrate that by retaining the required decay time of spent fuel in the pool to be the minimum times imposed in Technical Specification 3.9.14 prior to moving a spent fuel cask into the spent fuel pool, the'potential offsite doses are less than 10 percent of 10 CFR Part 100 limits even if all the assemblies in a full pool are damaged and no credit is taken for filtration. For a decay time in the spent fuel pool of either 1180 hours0.0137 days <br />0.328 hours <br />0.00195 weeks <br />4.4899e-4 months <br /> (Case I described above) or a decay time of 1490 hours0.0172 days <br />0.414 hours <br />0.00246 weeks <br />5.66945e-4 months <br /> (Case II), the EAB thyroid dose, which is governing, is approximately 15 rem. The SRP 15. 7.5 acceptance criterion for these analyses (25 percent of 10 CFR 100) is 75 rem.

The whole-body doses calculated for Case I and Case II for the corresponding decay times are less than 0.1 rem, compared to the SRP 15. 7. 5 acceptance criterion of 6 rem. Accordingly, the Technical Specification 3. 9.14 decay time requirements prior to cask handling operations are acceptable. This is conservative, since not all spent fuel storage modules located in the pool are susceptible to impact from any single cask drop. Thus, the proposed spent fuel pool modifications do not increase the radiological consequences of the cask drop accident previously evaluated.

5.3.1.2.3 Overhead Cranes Except for the area described in Section 5.3.1.2.1, the spent fuel cask crane is not capable of traveling over or into the vicinity of the spent fuel pool.

A complete cask crane component description, cask handling description, and cask crane design evaluation are provided in Updated FSAR Section 9.1 and will not be affected as a result of the rerack program.

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5.3.1.2.4 Acceptability The accident aspects of review establish acceptability with respect to Sections 5.3.1.2.1 and 5.3.1.2.2 of this report.

Technical Specification requirements for spent fuel decay time prior to moving a spent fuel cask into the spent fuel pool containing freshly-discharged fuel assemblies result in potential offsite doses less than 10 percent of 10 CFR Part 100 limits should a dropped cask strike the stored fuel assemblies.

5.3.1.3 Abnormal Location of a Fuel Assembly The abnormal location of a fresh unirradiated fuel assembly of 4. 5X enrichment could, in the absence of soluble poison, result in exceeding the design reactivity limitation (keff of 0.95). This could occur if the assembly were to be either positioned outside and adjacent to a storage rack module or inadvertently loaded into a Region 2 storage cell, with the latter condition producing the larger positive reactivity increment. Soluble poison, however, is present in the spent fuel pool water (for which credit is permitted under these conditions) and would maintain the reactivity substantially less than the design limitation.

The largest reactivity increase occurs for accidentally placing a new fuel assembly into a Region 2 storage cell with all other cells fully loaded.

Under this condition, the presence of 500 ppm soluble boron assures that the infinite multiplication factor would not exceed the design basis reactivity.

With the normal concentration of soluble poison present (1720 ppm boron), k is normally less than 0.80 and will not be critical even if Region 2 were to be fully loaded with fresh fuel of 4.5X enrichment. Administrative procedures will be used to confirm and assure the continued presence of soluble poison in the spent fuel pool water.

5.3.1.4 New Fuel Storage in Region 2 In a confirming calculation, it was determined that a checkerboard storage pattern in Region 2 would allow new fuel assemblies of 4.5X enrichment to be safely accommodated without exceeding the limiting 0.95 keff value. In this checkerboard loading pattern, the fuel assemblies are located on a diagonal array with alternate storage cells empty of any fuel.

The Monte Carlo calculation (AMPX-KENO) resulted in a k of 0.8084 + 0.0085.

With a one sided K-factor( ) for 95X probability at a 95X confidence level and a 5 k of 0.0125 for uncertainties (Table 3-1 for Region 2), the maximum k c is 0.857, which is substantially less than the 0.95 limiting value. Thus, Region 2 may be safely used for the temporary storage of new fuel assemblies provided the storage configuration is restricted to the checkerboard pattern with alternate storage locations empty of fuel.

Technical Specification 3.9.14 requires decay time for freshly discharged fuel prior to movement of the cask into the pool. As a result, with the increased storage capacity, the radiological consequences of a cask drop are less than 10 percent of the requirements of 10 CFR Part 100.

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5.3.3 Loads Over Spent Fuel Administrative procedures and Tech Spec 3.9.7 limits the maximum weight of loads that may be transported over spent fuel.

5.3.4 Temperature and Hater Densit Effects The moderator temperature coefficient of reactivity in both regions is negative; a moderator temperature of 4oC, with a water density of 1.0 g/cm 3 , was assumed for the reference designs, which assures that the true reactivity will always be lower, regardless of temperature.

Temperature effects on reactivity have been calculated 'and the results are shown in Table 5-6. Introducing voids in the water internal to the storage cell (to simulate boiling) decreased reactivity. Since, at saturation temperature, there is no significant thermal driving force, voids due to boiling will not occur in the outer (flux-trap) water region of Region l.

5.3.5 Conclusions Since the spent fuel cask will not be handled over or in the vicinity of spent fuel as discussed in Section 5.3.1.2.1, the proposed modification does not result in a significant increase in the probability of the cask drop accident previously evaluated in the St Lucie Updated FSAR or Safety Evaluation Report(9>. Furthermore, as shown in Section 5.3.1.2.2, by requiring a minimum decay time for spent fuel prior to moving a spent fuel cask into the spent fuel pool, the potential offsite doses are less than 10 percent of 10 CFR Part 100 limits should a dropped cask strike the stored fuel assemblies.

The proposed spent fuel pool modifications do not increase the radiological consequences of a cask drop accident previously evaluated.

Since there will be a negligible change in radiological conditions due to the increased storage capacity of the spent fuel pool, no change is anticipated in the radiation protection program. In addition, the environmental consequences of a postulated fuel handling accident in the spent fuel pool, described in Updated FSAR Section 15.0, remain unchanged. Therefore, there will be no change or i~pact to any previous determinations of the Final Environment statement (8 . Based on the foregoing, the proposed amendments will not significantly affect the quality of the human environment; therefore, under 10 CFR 51, issuance of a negative declaration is appropriate.

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5.4 REFERENCES

FOR SECTION 5

1. PROMOD III Computer Code, Version 22.8, Energy Management Associates.

2. St Lucie Plant Unit 1, Updated Final Safety Analysis Report, Docket No. 50-335.

3. Nuclear Regulatory Commission, "Control of Heavy Loads at Nuclear Power Plants", NUREG-0612, July 1980.

4. Nuclear Regulatory Commission, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, NUREG-0800, Revision 1, July 1981.

5. Nuclear Regulatory Commission, "Assumption Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors," Regulatory Guide 1.25, March 1972.

6. St Lucie Plant Unit 1, Final Safety Analysis Report, Section 9.1, Docket No. 50-335.

7. St Lucie PLant - Unit 1, Technical Specifications, Facility Operating License DPR-67.

8. NUREG 0575, "Final Environmental Impact Statement on Handling and Storage of Spent Light Water Power Reactor Fuel," Vol 1-3 USNRC August 1979.

9. St Lucie Plant Unit 1, Safety Evaluation Report. Licenses DPR-Docket Nos. 50-335.

10. St Lucie Plant Unit 1, Final Environmental Statement, Docket No.

50-335.

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TABLE 5-1 NUCLEAR FUEL DISCHARGE INFORMATION ST LUCIE UNIT 1 Cumulative Total Number of of Spent Fuel Cycle Shutdown Assemblies Assemblies No Dates Discharged in the pool 01 3/28/78 , 60 60 02 3/31/79 68 128 03 3/15/8O 88 216 04 9/9/81 64 280 05 2/26/83 92 372 06 10/21/85 73(1) 445 07 2/7/87 84 529<<

728 CURRENTLY INSTALLED/USABLE CELLS ACTUAL CYCLE INFORMATION THROUGH CYCLE SEVEN, PROJECTED THEREAFTER 08 10/8/88 72 601 09 3/16/90 80 681 10 10/1/91 64 745 11 3/15/93 68 813 12 10/1/94 64 877 13 3/15/96 68 945 14 1O/1/97 64 1009 15 3/15/99 68 1077 16 10/1/2000 64 1141 17 3/15/O2 68 1209 18 10/1/03 64 1273 19 3/15/05 68 1341 20 1O/1/O6 64 1405 21 3/15/08 68 1473 22 10/1/09 64 1537(2) 23 3/15/10<* 68 1605 24 10/1/11 64 1669 25 3/15/13 68 1737 26 1O/1/14 64 1801 END OF LIFE 3/1/16 217 Final Offload 2018

> FULL CORE RESERVE (FCR) LOST AT 511 CELLS WITH CURRENT RACKS'ERACK REQUIRED TO REGAIN FCR

• • CURRENT END OF LIFE = 7/1/2010, CURRENT APPLICATION PENDING TO EXTEND LIFE TO MARCH 1, 2016 (1) INCLUDES FUEL ASSEMBLY H406 WHICH WAS PART OF A RECONSTITUTION.

(2) FCR LOST AT 1489 CELLS WITH POISONED RERACK (ASSUMES 1706 AVAILABLE STORAGE LOCATIONS) 5-11 0078L/0011L

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TABLE 5-2 ANNUAL PUEL SAVINGS ATTRIBUTED TO ST. LUCIE UNIT NO. 1 Cumulative Nominal Net Cumulative Present Value Present Value Energy Production Re lacement Cost Cost 1986 Dollars 1986 Dollars Year (GWa) ( 000) ( ee) ($ 000) ($ 000) ($ 000) 1992 7147 5147,771 20. 68 $ 147,771 $ 70,977 4 70s977 1993 5879 $ 147,621 25. 11 $ 295,392 $ 62,748 5133,725 1994 5894 $ 1759783 29.82 4471,175 $ 66,123 4199,848 NOTE: Discount Rate 13.0X St. Lucie 1 assumed to be out of service all year(s)

TABLE 5-3 GASEOUS RELEASES FROM FUEL HANDLING BUILDING 1985 Radionuclide Curies Xe-133 64.9 Xe-135 9.9 I-131 2.74 E-4 Kr-85m 1.0 Kr-87 7.94 E-l Kr-88 1.5 1986 Radionuclide Curies Xe-133 20.1 Xe-135 7.5 I-131 1.45 E-4 Kr-85m 1.0 Kr-87 1.3 Kr 88 1.3 I-133 9.88 E-5 5-13 0078L/0011L

I TABLE 5-4 GAMMA ISOTOPIC ANALYSIS SPENT FUEL POOL WATER RADIONUCLIDE ACTIVITY Co-58 4.90 E-4 p,Ci/ml Co-60 6.70 E-4 /lCi/ml Cs-134 5.80 E-4 P Ci/ml Cs-137 9.32 E-4 PCS/ml Ek-3 7.70 E-2 PCi/ml 5-14 0078L/0011L

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TABLE 5-5 ANTICIPATED DOSES DURING RERACKING Project Dose (man-rem)

Spent Fuel Movement 0.5 Install Rack Removal Crane 0.1 and Remove Crane Decontaminate Racks Underwater 2.5 and Remove from Pool Decontamination of Racks in 2.0 Cask Washdown Bldg and Crate for Shipment Install New Racks 2.5 Repair Equipment 0.5 Measurement of New Racks and 1.0 Dummy Assembly Testing Health Physics Coverage and Surveys 2.0 General Entry and Inspection 1.0 Fuel Pool Floor Vacuum and 2.0 Filter Disposal TOTAL 14.1 5-15 0078L/0011L

TABLE 5-6 EFFECT OF TEMPERATURE AND VOID ON CALCULATED REACTIVITY OF STORAGE RACK Case Incremental Reactivity Change, 5k Region 1 Region 2 4'C Reference Reference 2O'C -0. 0014 -0.0009 SO'C -0. 0054 -0. 0032 80oc -0.0109 -0. 0062 12O'C -0.0216 -0. 0117 120o + 20X void -0.0767 -0.0446 5-16 0078L/0011L

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TABLE 5-7 SPENT FUEL POOL PURIFICATION SYSTEM RADIONUCLIDE ANALYSIS REPORT RESIN ACTIVITY RADIONUCLIDE ACTIVITY NON-TRANSURANIC p,Ci/cm Co-58 56. 93 Cs-137 23. 25 Cs-134 17. 06 Co-60 6. 63 I-131 3.37 Cs-136 1.09 Mn-54 0.44 C-14 6.63E-3 Tc-99 1.63E-4 I-129 1.95E-6 H-3 7.6E-2 Sr-90 3.95E-3 Ni-63 1.39 Fe-55 9.68E-2 TRANS URANIC nci/gm Pu-239, 240 1.39E-5 Pu-241 2 '2E-3 Cm-242 9.28E-6 TRU<< 3.71E-5 Resin Volume ~ 35 ft or 0.991 m

+ Other alpha-emitting transuranic nuclides with half-lives greater than 5 years.

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TABLE 5-8 SPENT FUEL POOL AIRBORNE ACTIVITY RADIONUCLIDE ANALYSIS REPORT CONCENTRATION RADIONUGLIDE p Ci/ml Ag-110m <<3.0E-ll Ar-41 <<9.5E-11 Ba-139 <<1.2E-10 Ba-140 <<7.8E-11 Ba-141 <<8.5E-11 Ce-139 <<2.5E-ll Ce-144 <<1.5E-10 Ce-141 <<3.6E-ll Co-57 <<1.7E-11 Co-58 <<3.6E-11 Co-60 << 4.4E-ll Cr-51 << 2.0E-10 Cs-134 <<2.7E-ll Cs-137 <<3.7E-11 Cs-138 << 2.8E-11 Fe-59 <<4.0E-11 I-131 1.0E-9 I-132 <<3.7E-11 I-133 << 2.0E-11 I-134 <<2.7E-ll I-135 <<8.0E-ll Kr-85 <<5.2E-9 Kr-85m <<2.7E-ll Kr-87 <<4.3E-11 La-140 <<2.0E-11 La-142 <<9.9E-ll Mn-54 <<2.5E-ll Mo-99 <<1.4E-10 Nb-95 <<2.4E-ll Nb-97 <<3.4E-ll Lower level of Detection and was not detected in the sample.

I-131 and Xe-133 were detected in the sample. Fuel movement and fuel reconstitution was in progress during the sample collection. These are normally not detected and their lower levels of detection are I-131 = 3.0E-ll pCi/ml and Xe-133 = 9.0E-ll PCi/ml.

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TABLE 5-8 (Cont'd)

SPENT FUEL POOL AIRBORNE ACTIVITY RADIONUCLIDE ANALYSIS REPORT CONCENTRATION RADIONUGLIDE PCi/ml Np-239 <<6.4E-ll Rb-88 <<1.9E-10 Rb-89 <<6.7E-11 Ru-103 <<2.4E-ll Ru-106 <<1.8E-10 Sb-124 <<2.6E-11 Sb-125 <<5.5E-ll Sn-113 <<1.7E-ll Sr-85 <<2.3E-11 Sr-91 <<7.1E-11 Sr-92 <<1.7E-ll Te-99m <<2.2E-11 Te-132 <<2.3E-ll Xe-131m <<1.1E-9 Xe-133 3.4E-10 Xe-133m <<2.0E-10 Xe-135 <<1.3E-10 Xe-138 <<1.0E-10 Y-88 <<2.3E-ll Y-91m <<3.7E-11 Zr-65 <<5.4E-11 Zr-95 <<3.9E-ll Zr-97 <<1.9E-11 Lower level of Detection and was not detected in the sample.

I-131 and Xe-133 were detected in the sample. Fuel movement and fuel reconstitution was in progress during the sample collection. These are normally not detected and their lower levels of detection are I-131= 3.0E-ll pCi/ml and Xe-133 = 9.0E-ll p,Ci/ml.

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