ML20212G695

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Slides from Usdot 971105 Meeting Entitled, SNEC Large Component Removal Project
ML20212G695
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 11/05/1997
From:
NRC
To:
References
NUDOCS 9711070046
Download: ML20212G695 (91)
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{{#Wiki_filter:. 'es iljj SNEC Large Component 's" Removal Project USDOT Meeting 5 November,1997 c;;;;; -iEE g, C ms

i SNEC Large Component Removal Project

  • Agenda

- Introduction - G. A. Kuehn, Jr. - Project Overview - R. D. Holmes - Characterization Methodology - B. Brosey - Characterization Results - K. Tuite - Component Preparation, Certification & Slipment - L. Brown /S. Chen i j - Transportation - L. Brown j - Summary Remarks - G. A. Kuehn, Jr.

SNEC Large Component Removal Project 4 G. A. Kuehn, Jr. - Iritroductory Remarks

SNEC Large Component Removal Project Project Overview - R. D. Holmes - What and where is "SNEC" Brief History of the Facility Current facility conditions ~ - What does the project consist of - Who makes up our team 8

SNEC Large Component Removal Project What/Where is "SNEC" - SNEC = Saxton Nuclear Experimental Corporation Wholly owned by GPU Inc. GPU Nuclear, part of GPU Inc., operates the Three Mile Island, Oyster Creek and SNEC Nuclear Facilities - The SNEC Facility Located midway between Pittsburgh and Harrisburg, Pa. About 20 miles north of the Pa; Turnpike l

SNEC Large Component Removal Project Brief history of the SNEC facility - 23.5 Mwt PWR operated from 1962 to 1972 - Served as a demonstration facility for new technologies in commercial nuclear power - Facility was shut down in may 1972 at the successful completion of these programs - All nuclear fuel was removed from the site - The facility was placed in "SAFSTOR" until 1986

SNEC Large Component Removal Project Current facility conditions - All nuclear fuel removed from the site - Phased decommissioning started in 1986 All structures except the Containment Vessel (CV) have been demolished Characterization of the facility complete Preparatory activities in support of final site decommissioning are complete Awaiting NRC approval to proceed Objective is free release of the site mid 2000 L____

SNEC Large Component Removal Project Larae Component Removal Project - Remove, prepare, ship and dispose of the three large NSSS components located in the CV Reactor Vessel Pressurizer Steam Generator - All three components will be trucked to a rail siding and shipped by rail to the Chem Nuclear facility in Barnwell, SC for disposal - Scheduled to ship fall 1998 to support mid 2000 completion date

SNEC Large Component Removal Project All three components are small and robust compared with a commercial size PWR - Reack /essel - Pressurizer - Steam Generator

SNEC Large Component Removal Project The Team - GPU Nuclear is the licensee Overall control and responsibility - Raytheon Nuclear Inc. Prime contractor for removal, package certification and shipping - WMG Inc. - Support of package certification, waste classification and sh.ielding analysis - F. W. Hake Inc. - Rigging and transportation - Chem-Nuclear Inc. - Disposal

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\\ l l l RV Characterization Methods l i e RV activation analysis by TLG services, inc. Confirmation measurements (TLD's i etc.) i Exterior structural samples o Sample of internal contamination i \\

i I i SNEC RV Activation Analysis \\ t e TLG performed activation analysis using: A series of one-dimensional neutron l transport calculations coupled with point j neutron activation analysis Used "ANISN" & "ORIGEN2" codes obtained from ORNL's Radiation Shielding i information Center (RSIC)-

Activation Analysis Comparisons e Activation analysis results were compared to: RV external and internal TLD string data Radiological instrument measurements Concrete core bore samples external to the RV Stainless steel samples external to the RV o-

RV Activation Analysis Results o Conclusions RV internal & external TLD measurements i are in very good agreement with predicted values Sample result comparisons with calculated results are reasonable t

SNEC RV Internal Contamination e RV internal contamination levels were estimated by sampling surface contamination from the RV lower internals area, and I e Collecting a sample of material from the safety injection line between the installed check valve & the RV .=

Characterization of SNEC Steam Generator & Pressurizer e Methodology included: Identification, collection and analysis of appropriate sample materials Removal of asbestos coverings outside of both components Decontamination of high levels of surface contamination on S/G near cold leg manway Radiation shielding code (Microshield? modeling based on best available survey data

4r Characterization of SNEC Steam Generator & Pressurizer o Currently analyzing additional representative samples and survey information Collected TLD measurements internal to PZR Collected 100 cm2 smears from inside PZR Collected 100 cm2 smears from inside the ~ S/G lower man ~way area (divider plate, bowl, & tube sheet, and tubes)

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Characterization of SNEC S/G (10 CFR 61 Type Independent Analysis) e Three independent sample results ubed to define internals Cold leg primary side smear from divider plate Secondary side scrape sample from behind manway Materials from SI system to represent hot leg side o Current effort is to fine tune surface contaminants i

Characterization of SNEC S/G Location of Primary Sic;e Smear Analyzed by B&W 1G;_,.-?h 6 ,_n1 y 7

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Characterization of SNEC S/G Location of Secondary Side Smear Ana yzed by J B&W SNEC Steam Generator gwsk Q /,. v ny gyp- _ni,w /, is s - / ~ ~ .(, q__,-, g, / gyp ;l _3 .- y -g p + L <(x, y _C f J l c c 64l [ [, s T-sm. _ -t ,R(% - 7 -Jc -t [, p. r - h%M ) Min a:w,<-->~>>--wK w zy,; M m y4N &z A--w Ja b~ 14 s s s a u u y u S/G Secondary Side Manway '/ Cover

Characterization of SNEC Large Components - Conclusions e Characterization effort was J extensive and included: . Benchmarking of the RV activation analysis . Extensive sampling & surveys of the three large components . Independent analysis of samples (10 CFR 61) l J

Characterization of SNEC Large Components-Conclusions e The curie calculations for the SNEC Facility large components are conservative, but reasonable

SNEC LARGE COMPONENT REMOVAL PROJECT CHARACTERIZATION AND CLASSIFICATION K. Tuite \\NMG, Inc.

SNEC LARGE COMPONENT REMOVAL PROJECT Reactor Vessel and Internals Characterization . ANISN/ORIGEN2 Analyses to Quantify Activation Products . Swipes of internal Surface - independent Lab Part 61 Radiochemical Analysis to Quantify Surface Contaminants Radiation Surveys of Exterior and Interior to Benchmark Activation Analysis Results \\

= SNEC LARGE COMPONENT REMOVAL PROJECT Intact Vessel / Internals Results (as of 8/98) . Total Activity 1280 Curies Surface Contaminants - 10 Curies - Activated Vessel / Internals - 1270 Curies . Maximum Unshielded Radiation Levels (calc.) Contact 8400 mrem /hr 2 meter 970 mrem /hr 3 meter 660 mrem /hr

SNEC LARGE COMPONENT REMOVAL PROJECT Intact Vessel / Internals DOT Classification Classification Results (Intact Vessel / internals) LSA-II Sum of A /g Fractions - 3.9 % 2 LSA-Ill Sum of A /g Fractions - 0.2% 2 Internal Components Each Internal Component Meets LSA-Ill A /g Limits 2 Worst Case Component is the Core Baffle LSA-Ill Sum of A /g Fractions - 5.4% 2

SNEC LARGE COMPONENT REMOVAL PROJECT Intact Vessel / Internals Part 61 Classification . Classification Results Table 1 Sum of Class C Fractions - 0.19 Table 2 Sum of Class C Fractions - 0.02 . Worst Case Component Exceeds Table 1 Class C Limits Due to Conservative Contamination Estimate. (Meets Concentration Averaging BTP and is Therefore Class C Waste)

SNEC LARGE COMPONENT REMOVAL PROJECT Intact Vessel / Internals Shipping Classification . DOT Class - Greater Than Type A Quantity of LSA-Ill Material . Reportable Quantity Of Radioactive Material . Ship as IP-2 Package

SNEC LARGE COMPONENT REMOVAL PROJECT Intact Vessel / Internals . Activation Products - 1270 Curies Intrinsic to Reactor Vessel and Internals Component Metals Shielded by Exterior Grout and Package Walls

SNEC LARGE COMPONENT REMOVAL PROJECT Intact Vessel / Internals . Surface Contaminants - 10 Curies Fixed on Internal Surfaces with Grout Double Containment from Enclosed Reactor Vessel and Package L_______

SNEC LARGE COMPONENT REMOVAL PROJECT Steam Generator Characterization Empirical Data . Part 61 Independent Lab Radiochemical Analysis (Three Samples) . Swipes of Channel Head Bowl, Divider Plate, Tube in Tube Sheet, and Tube Sheet - MCA/GeLi Analysis . Radiation Surveys of Exterior and Interior

SNEC LARGE COMPONENT REMOVAL PROJECT Steam Generator Surface Areas (Primary Side) Area cm2 Percent Tube Bundle 1.7E+6 97 Tube Sheet 1.0E+4 0.6 Channel Head Bowl 2.8E+4 1.6 Divider Plate 1.5E+4 0.9 Total 1.8E+6 100 E

SNEC LARGE COMPONENT REMOVAL PROJECT Steam Generator Results (as of 8/98) . Activity - 1.22 Curies Inaccessible Surface Contamination Levels Maximum at Tube Sheet 4.0 uCi/cm2 2 Tube Bundle (97% Area)- 0.7 uCi/cm . Maximum Radiation Levels Contact 15 mrem /hr Side 30 mrem /hr Bottom

SNEC LARGE COMPONENT REMOVAL PROJECT Steam Generator Shipping Classification . DOT C! ass - Greater Than Type A Quantity of SCO-Il Material . Reportable Quantity Of Radioactive Material . Ship as IP-2 Package

SNEC LARGE COMPONENT REMOVAL PROJECT Pressurizer Characterization Empirical Data . Part 61 Independent Lab Radiochemical Analysis (SG Assumec: Representative) . Swipes of Interior Wall and Heater Surface - MCA/GeLi Analysis (10 CFR 61 pending) . Radiation Surveys of Exterior and Interior

SNEC LARGE COMPONENT REMOVAL PROJECT Pressurizer Surface Areas i I Area cm2 Percent Interior Shell 1.3E+5 84.4 Heater Bundle 1.3E+4 8.3 Spray Flange 1.2E+4 7.3 Total 1.6E+5 100 L__-

SNEC LARGE COMPONENT REMOVAL PROJECT Pressurizer Results (as of 8/98) . Activity - 0.70 Curies . Inaccessible Surface Contamination Level 4.7 uCi/cm2 (Avg) . Maximum Radiation Level on Contact-15 mrem /hr

SNEC LARGE COMPONENT REMOVAL PROJECT Pressurizer 9 Shipping Classification ~ DOT Class - Greater Than Type A Quantity of SCO-il Material Reportable Quantity Of Radioactive Material a . Ship as IP-2 Package Y

Component Preparation, Certification and Shipment L. Brown /S. Chen Raytheon Nuclear

COATING OF VESSEL EXTERIOR SURFACES e Coatings of surfaces will be applied in the RCA to encapsulate surface i contaminates l e Cdatings will meet the requirements of l ASTM-D5064 i o Coatings have a proven history in industry l l

PLACING REACTOR INTO SHIELD CANISTER i e The lower section of the shield canister will be placed on crane mats e Reactor vessel will be lowered into lower canister section supported by reactor support ring e Canister will be affixed to the reactor support ring by welding, or with hold down clips e The lower canister will be grouted

PLACING THE REACTOR INTO SHIELD CANISTER e The lifting trunnions will be cut off e The upper canister will be placed and welded e The upper canister will be grouted e

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METHODS OF TRANSPORT TO RAll SIDING STM. GENERATOR & PRESSURIZER e Heavy duty Tractor trailer with 7 to 8 axles e Maximum package size 21'x9'x9' Steam Generator / Pressurizer e Steam Generator Estimated Weight 70,000 lbs. o Pressurizer Estimated Weight 40,000 lbs.

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m REACTOR VESSEL TIE DOWN SYSTEM e RV package will be supported by two saddles 24" wide. o On each saddle there will be 4-wire rope slings each 1.25" in diameter, each having a capacity of 15-tons. e The main shipping skid will be constructed of W-14x120 wide flange beams. g

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4*-1" DECK HEIGHT ABOVE RAll IS MEASURED AT CENTER OF CARBODY. INCLUDING CAMBER.WITH A LOAD EQUAL TO 501 OF LOAO LIMIT UNIFORMLY DISTRIBUTED OVER FULL LENGTH OF LOADING DECK. = 73*-4" OVER PULLING FACES 15" E.O.C. 88'-8" LENGTH OVER STRIKERS COLLAPSIBLE HANDBRAKES (2) 55'-O" OECK 36"DIA +b+ 6 1/2= 10*8" 3 6 1/2x12 1" DECK COLLAPSED r t 2, _10.. 3 HAND BRAKE F l YNNN/NA / PLATE L, .y l lt .n .e . ; l --- -- p y -{ L- -r-g m SIDE MOUNTED LEVER 26 TYPE HANDBRAKE (2) 15" E.O.C. HAS 4.-1" DECK HEIGHT BLOCK OUT CAPABILITY 5'-10"

= 5'-10" (BOTH ENDS) FOR BOLSTER LOADS (NOT ON CARS 131040-131046) CARS OTTX 131025-1J1034 WERE ORIGINALLY EQUlPPED WITH VERTICAL WHEEL HANOBRAKES MOUNTED CN COLLAPSIBLE STANCHIONS. MAX 1 MUM WEIGHT OF PARTIAL LENGTH LOADS CARS ARE BEING CONVERTED TO SIDE MOUNT LEVER TYPE HAN08 RAKES. CARS OTTX LOAD LENGTH (FT) (b) LOAD (1000 LBS) (P) 131035-13:046 EQUIPPED WITH SIDE MOUNT LEVER TYPE HAN0 BRAKES. 0 315.0% 2 319.0 33IO NT LihN$NCHT CAR NUMBERS QTTX 131025-131039 CAR SERIES to 6 8 343.5 131025-131024 393.400 132.600 131 35-131039 394.400 131.600 (([ (hMMN[ I 6 131040-1J104s 394.500 131.500 I4 3 AVERAGE 1 394.000 i 132.000 195 lON, 55 FOOT DECK 38.0 18 394.0 FLAT CAR 19 & OVER 395.0 CLASS DSH55 % MAX. CONCENTRATED LOAD CENTER OF CRAVITY - EMPTY = 33.3"ATR D-7225-E CLEARANCE PROFILE WITHIN AAR PLATE "C" DATE:05-18--93

STEAM GENERATOR AND PRESSURIZER TIE DOWN e Vessels will be supported by two saddles 10" wide. &On each saddle there will be 2-wire rope slings each 1" in diameter each having a capacity of 10-tons. e The main shipping skid will be constructed of W-10 wide flange beams. ~

STEAM GENERATOR AND PRESSURIZER TIE DOWN e End blocking beams will be attached to the shipping skid e The shipping skid will be attached to the rail car with welded hold down clips

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TIE DOWN REQUIREMENTS AND REGULATIONS Truck Transport: e ANSI-N-14.2 (Draft) Design Loads Longitudinal 1.6 G Lateral 1.5 G Vertical 1.5 G

TIE DOWN REQUIREMENTS AND REGULATIONS Rail Transport: AAR-Section 1 Open Top Rules Design Loads Longitudinal 3.0 G Lateral 2.0 G Vertical 2.0 G

TRANSFER TO RAll CARS e Rail siding will be graded and compacted to allow the rail car and transporter to be on equal elevations e The rail car will be cribbed to stabilize e Timber cribbing will be placed between transporter and rail car o Rolling plates will be placed on ~ rail car deck and f:imber cribbing

TRANSFER TO RAll CAR e Skid and canister will be jacked up using (4) 50 ton hydraulic jacks on designed in lugs e Rolling plates will be placed on transporter and aligned with rail car plates e Pipe rollers of 4.5" OD will be placed under cradle

,,em,.. TRANSFER TO RAll CARS e Cradle and canister will be winched on to the rail car e Hydraulic jacks will be reinstalled to remove the rollers and the cradle will be lowered to the rail car and tie downs clips installed

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TRANSPORT TO RAll SIDING e Exit SNEC site on to Rt. 913 east through Saxton e Right on to state Rt. 26 North e Rt. 26 north to Huntingdon, PA. e Right onto Ridge Rd. rail siding is 1/2 mile on right. e The Route is estimated to be twenty seven miles.

KEY FACTORS TO ROUTE SELECTION e Only one long-span bridge along route, and the bridge is relatively new. e There are no steep grades along route o There are no sharp corners along route o Rail siding has been used for heavy loads in excess of 100 tons e There are ample staging areas along route

TRANSPORTATION SAFETY FEATURES ROAD TRANSPORT e Speed Limited to 5 MPH e Transporter has continuous leveling capability o Transporter has been conservatively sized providing reduced wheel loading e Transporter length will spread load out on bridges. o Backup tractor will travel with move p.

TRANSPORTATION SAFETY FEATURES RAIL TRANSPORT e Rail car loading 60% of rated capacity e Dedicated train with GPUN rider's and escorts to assure proper handling e Shipment aspects will be in accordance with a Transportation Plan which meets all applicable requirements, agreed to by GPUN & the railroads

---~ TRANSPORTATION TO BARNWELL BY RAIL Conrail: e Shipment will be by Conrail from Huntingdon, PA to Effingham, ILL. Illinois Central Railroad: o Shipment will be by Illinois Central Railroad from Effingham ILL. to Barnwell, SC

TRANSPORTATION TO BARNWELL BY RAll Conrail: e Shipment will be by Conrail from Huntingdon, PA to Hagerstown, MD CSX: o Shipment will be by CSX from Hagerstown, MD to Barnwell, SC A}}

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