ML17309A896
| ML17309A896 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/11/1997 |
| From: | CHEM-NUCLEAR SYSTEMS, INC. |
| To: | |
| Shared Package | |
| ML17229A389 | List: |
| References | |
| ST-257, ST-257-R, ST-257-R00, NUDOCS 9706270134 | |
| Download: ML17309A896 (27) | |
Text
CHEM-NUCLEAR SYSTEMS, INC.
140 STONERIDGE DRIVE COLUMBIA, S.C.
29210 DESIGN DOCUMENT COVER SHEET DOCUMENT ID NUMBER:
ST-257 PROJECT NUMBER'6621 REVISION NUMBER:
0 SECURITY STATUS'ROPRIETARY NON-PROPRIETARY x
PERIOD:
Life of the Pro ect +
1 ear TITLE:
Structural Evaluation of the St. Lucie S.G. Packa e
Non-Pro rieta PREPARED BY:
DATE:
6/10/97 TITLE:
Princi al En ineer REVIEWED BY:
DATE:
TITLE:
Senior Pro'ect En ineer REVISION NOTES:
Received 8 Document ated From:
Verification to Index By:
Storage Shelf Location; DOC T CONTROL lo Date;4 d
e To:
'K-5'ate:
9706270%34 9706%'UP PDR ADOCK 05000335 P
CHEM-NUCLEAR SYSTEMS, INC.
140 STONERIDGE DRIVE COLUMBIA, S.C.
29210 DESIGN DOCUMENT REVIEW CHECKLIST Design Package Identification No ST-257 Date 6/10/97 Revision No.
ITEM YES N/A 1.A Design Inputs such as design bases, regulatory requirements,
- codes, and standards are identified and documented.
1.8 Effect of design package on compliance with the Safety Analysis Report or Certificate of Compliance identified and documented.
2.
Revision numbers correct on the list of drawings?
3.
Assumptions reasonable?
4:
Appropriate analysis method used?
5.
Correct values used from drawings?
6.
Answers and units correct?
7.
Summary of results matches calculations?
8.
Material properties properly taken from credible references?
9, Figures match design drawings?
10.
Computer input complete and properly identified?
11.
Documentation of all hand calculations attached?
12.
Meeting minutes of the Design Review?
'ot Applicable, Explain 1.8 - This design package willbe submitted to obtain exemption for the Saint Lucie Steam Generator Package as it provides equivalent safety to that of DOT IP-2 Packages.
2, 5 Through 8, 10,11 - Details are part of the Proprietary Document and are included in the Design Package ST-255.
12 - No design review meeting is needed.
Independent Reviewer
Title Structural Evaluation ofthe St. Lucie S.G Packa e(Non-Pro rieiarv Version Cole. No.
ST-257 Rev.
0 Sheet l
of l0 Introduction Florida Power & Light (FPAL) Company will be replacing the steam generators at their St. Lucie Unit 1 facility.
The old steam generators (OSGs) will be transported to Barnwell South Carolina for disposal.
The steam generators will be transported under DOT exemption as alternatively packaged radioactive material that provide equivalent safety to that of DOT IP-2 packages.
These IP-2 packages are required by 49 CFR 173.411 to meet the general requirements of 49 CFR 173.410 and must prevent loss or dispersal ofradioactive contents or significant increases in the external radiation dose rates when subjected to the tests prescribed in 49 CFR 173.465 (c) and (d), namely, 1-foot drop and compression tests.
The 1-foot drop test requires that the package be dropped in the most vulnerable orientation so that the maximum damage is caused.
The special procedures used to handle the steam generators during transportation provide significant increases in safety over uncontrolled shipments, and provide controls to prevent the steam generators from being dropped in an arbitrary orientation.
From the time the packages are ready for shipment to the time they arrive in the burial trench they are permanently tied to a pair of saddles.
Each saddle is bolted to a massive frame which, in turn, is secured to a self propelled modular transporter (see Figure 1 for a
. schematic of the tie-down). The steam generators are raised and lowered on the cribbing using these &ames.
During this operation the assembly is raised by only a few inches above the support points.
Therefore, the only probable drop that could occur is a drop of the assembly by a few inches over the cribbing-pile.
Because of the Qexibility of the support-kame and the cribbing pile involved in this drop, such a drop willhave a minor effect on the steam generator.
A much more severe drop has been postulated for analyzing the steam generator for the compliance with the regulatory requirement.
In this scenario, the steam generator is dropped on a rigid surface from a height of 1-foot in the orientation it is transported.
Since the diameter of the primary side of the steam generators is smaller than that ofthe secondary-side, such a drop would result in an initial impact on the secondary side and-a second impact (slap-down) on the primary side of these generators.
It should be noted that for the transportation, the steam generators are rotated in such'a way that all their protrusions are well above an imaginary horizontal plane drawn at the bottom ofthe steam generator (Figures 2 and 3). Table 1 lists all the protrusions and their circumferential orientation from a vertical plane pointing downwards.
Thus, for the postulated 1-foot drop, none of the protrusions on the steam generator would impact the rigid surface.
The protrusion closest to the impact point are, (1) the secondary manway, and, (2) the primary inlet nozzle.
The lowest point of the secondary manway is 4.52" above the horizontal plane (see Figure 4) and that of the primary inlet nozzle is 2.68" above the horizontal plane (see Figure 5).
The analysis performed to comply the regulatory requirement of 1-foot drop ofthe package on an unyielding surface shows that due to such a drop,
e
Title Structural Evaluation ofthe St. Lucie S.G Packa e
on-Pro rietarv Version Cele. No.
ST-257 Rev.
0 Sheet 2
of 10 (1)
The stresses in the package do not exceed the allowable stresses.
The allowable stresses are established based on NRC Regulatory Guide 7.6.
Accordingly, the extreme fiber stress on the shell does not exceed the ultimate strength of the material and the average stress over the cross-section does not exceed 70% of the Ultimate strength of the material.
(2)
Due to the deceleration experienced by the package during the drop, all the caps and plugs of the nozzles maintain their sealing.
The stresses in the caps and plug welds are limited to the AISC allowable values.
(3)
The deformation of the package would not be sufficient to'cause any of the protrusions to impact the unyielding surface.
The compression test, which is required to simulate the loding on the package when they are stacked on top of another, is not applicable for the shipment of the steam generators because the generators would be shipped separately and no other component is stacked on top ofthese generators during the shipment.
Anal sis Methodolo Figure 6 shows the scenario used in the drop analysis of the steam generator package.
The lowest point of the package, i.e.,
the secondary shell, is located 1 foot above the unyielding surface. The package is assumed to be horizontal in order that the primary shell is located farthest from the surface (conservative).
The package is dropped &om this orientation.
The first impact takes place on the secondary shell. Subsequently, because of the location ofthe center ofgravity in the primary end ofthe steam generator, the primary side rotates about the transition cone edge and a slap-down takes place.
The analyses cover both the primary and secondary impacts.
The analysis is performed using ANSYS finite element computer program.
The steam generator is modeled by two-dimensional beam elements that appropriately represent the area and the moment of inertia of the steam generator along its length.
The unyielding surface is modeled by rigid surfaces that are capable of reacting only the compressive load.
The local Qexibility of the steam generator shell is included in the model and 5%
structural damping is used in the analyses.
The model is analyzed using the linear transient (time-history) option ofANSYS program.
The displacem'ent, velocity, acceleration and reaction force time-history at each node of the model are obtained for the initial and secondary impact ofthe steam generator with the rigid surface.
The maximum acceleration is established Rom the largest acceleration of these time-histories.
The largest deformation at an appropriate node is used to establish whether the protrusions nearest to the rigid surface would come in contact with it or not.
The largest reaction forces in the in the primary and secondary shells are used in separate linear finite element models to obtain the stresses in the steam generator.
The largest
Title Structural Evaluation ofthe St. Lucie S G Packa e
on-Pro rietarv Version Calc. No.
ST-257 Rev.
0 Sheet 3
of l0 acceleration value is used with the mass of the caps and plugs to evaluate the weld stresses.
Although it is shown that none of the protrusions would make a contact with the rigid surface, the protrusions closest to the rigid surface (primary outlet nozzle and secondary manway) are analyzed for the stresses under the maximum reaction force obtained from the beam finite element model, described in the above paragraph.
Results The results ofthe analysis show that the'stresses in the steam generator under l-foot drop on a rigid unyielding surface, are within the allowable values, the cap and plug welds maintain their integrity, and the deformation at the point of impacts is such that none of the protrusions make a contact with the rigid surface.
Title Structural Evaluation ofthe St. Lucie S.G. Packa e
on-Pro rietarv Version)
Calc. No.
ST-257 Rev.
0 Sheet 4
of 10 Table 1 - Location ofthe Protrusions on the St. Lucie Steam Generators Protrusion Circumferntial Location &om the Bottom (Degrees)
Primary Inlet Nozzle
-52 Primary Outlet Nozzle No.1 Primary Outlet Nozzle No.2 83 173 Handhole No. 1 Handhole No.2 128
-142 Primary Manway No.1 Primary Manway No.2 128
-119.5 Feedwater Nozzle Secondary Manway No.1 128 Secondary Manway No.2 Steam Outlet Nozzle
-142 90 Support Skirt Bottom Blow-DownNozzle 90
.-142
Title Structural Evaluation ofthe St. Lucie S.G. Packa e
on-Pro rietarv Version)
Cale. No.
ST-257 Rev.
0 Sheet 5
of 10 i.O 0
0 Cfl 0
(
L 0
IL al I0 Q.
Vl00 l
0
'0 Cl ca Q.0 Q.
0 C
0 0
Figure 1 - St. Lucie Steam Generators - Tie-Down Schematic Diagram
Title Structural Evaluation ofthe St. Lucie S.G. Packa e
i on-Pro rietarv Versions Cala. No.
ST-257 Rav.
0 Sheet 6
of 10 Figure 2-St. Lucie Steam Generators - Isometric View
Title Structural Evaluation ofthe St. Lucie S.G Packa e
'on-pro rietarv Version Calc. No.
ST-257 Rev.
0 -'heet 7
of 10 Seeanaary Manway I
Hananote Pr mary Outlet ceo n a h a Ie Prirncry Manway
<eedwater Nozzle Primary inlet 38 i
/
Primary Monway Primary Outlet Secondary Monwoy Horizontal Plane Primary Side Horizontal Plone Secondary Side Figure 3-Orientation of Steam Generator Protrusions
Title Structural Evaluation ofthe St. Lucie S.G. Packa e
i on-Pro rietarv Version Cale. Ne.
ST-257 Rev.
0 Sheet 8
of 10 Figure 4-Lowest Protrusion on the Secondary Side
Title Structural Evaluatiori ofthe St. Lucie S,G. Packa e
i on-Pro rietarv Version Calc. No.
ST-257 Rev.
0 Sheet 9
of 10 2.68" Figure 5-Location ofthe Primary Inlet Nozzle above the Rigid Surface
Title Structural Evaluation ofthe St. Lucie S.G. Packa e CNon-Pro rietarv Version)
Calc. No.
ST-257 Rev.
0 Sheet 10 of 10
~ ~~ ~~
Figure 6-Steam Generator 1-Foot Drop Scenarios I
Steam Generatot'ransportation General Arrangement Drawings C-110-B-4662-003 Sheet 1; "St. Lucie Unit 1 Steam Generator Cable Tie-Down," Chem-Nuclear Systems, Inc.
C-110-B-4662-004 Sheets 1 to 3; "St. Lucie Unit 1 Steam Generator General Assembly,"
Chem-Nuclear Systems, Inc.
CABLE ASSY. -1 749 CABLE ASSY. -2 82 1/2 R.
REF.
119 7/8 R.
REF.
189.751-156.028 80.75 COMBINED C.GI+-
1.7 I47 1/2 REF.
141 1/8 REF.
CABLE ASSY. -I CABLE ASSY. -2 55.1 I8 7
CTR TRL.
0' 0' 0''
0 0'
111 I/8 FIEF.
LAYOUT CABLE LENGTH CTR. CRDL. SUPP.
LENGTH OF CABLE ASSY. RT" 202 CTR. CRDL. SUPP.
164~
7 8
FORGED SHACKLE.
1 3/4 NOM. SIZE, 25 TON WLL IS-213 6
8 TURNBUCKLE, 2 1/2 X 24 JAW 84'YE. HG-227-81032457 5
8 WIRE ROPE, I 3/8 OIA. IWRC. EIPS X LENGTH AS REO'0 4
16 THIMBLE FOR 1 3/8" DIA. WIRE ROPE 3
16 SWAGE FITTING FOR 1 3/8" DIA. WIRE ROPE 2
4 CABLE ASSEMBLY CROSBY OR EO.
CABLE ASSEMBLY 1 8c 2 LENGTH OF CABLE ASSY.; REQ'D.
1 4
CABLE ASSEMBLY ITEM OTY DESCRIPTION BILL OF MATERIALS SPEC.
ASSY.-1:
619 7/8 (16
+ 53 7/8") = 550" (45'-10")
ASSY.-2:
491 7/8" (16" + 53 7/8") ~ 422" (35'-2")
GENERAL NOTES:
USE 2 1/2 X 24, JAW Cc EYE TURNBUCKLE, ONE (1)
EACH END OF CABLE ASSY.
LENGTH FULLY EXTENDED: 75.8" LENGTH FULLY CLOSED: 51.8 MAX. LENGTH OF TRAVEL: 24" FIELD ADJUSTMENT: 16" PROPRIETARY NON-PROPRIETARY FSCM No. 54643 IHIS DRAWING IS THE PROPERTY OF CH[.MNUCLEAR SYSTEMS IT IS LOANEO UPON 'IHE CONDITION 1HAT IT IS NOI TO BE REPRODUCED.
COPIEO OR LOANEO TO OTFiERS WITHOUT WRITTEN PERMISSION Of CHEM-NUCLEAR SYSTEMS AND IS TO BE RETURNED UPON REOUEST, DRAWN BY CHECK B
R.
BREHEN
/6/gp ENGINEER g
DO NOT SCALE PRINT DIMENSIONS ARE IN INCHES UNLESS NOTED PROJECT No.
57906 FILE ID.
08900100 REVIEWERS OF ORIGINAL (REV. 0)
CHEMNUCLEAR SYSTEMS SIZE ST.
LUCiE UNIT STEAM GENERATOR CABLE TIEDOWN DRAWING NUMBER REV EI C-110-B-46621-003 0
SCALE I/IOO WI N / A SHEET I
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HX. NUT, 1 3/4 -5 UNC., FLAT AND SPLIT WASHER Ig 8
HX. HD BOLT, I 3/4 -5 UNC X 3 LG.
A/R HX. NUT, 1/2"-13 UNC.. FLAT AND SPLIT WASHER COMML A325 COMML 16 A/R HX. HD. BOLT, I/2"-13 UNC X 3" LG.
15 A/R CLAMP PLATE, 14 I
SHEAR KEY BLOCKING BEAM ASSEMBLY 13 A/R SHIELD PLATES (LOWER FRAME) 12 A/R SHIELD PLATES (UPPER FRAME) 11 24 LUG PLATES 10 48
- SHACKLE, 1 3/4" DIA. STOCK, 25 TON WLL - G-213-1018277 9
24 JAW AND JAW TURN BUCKLE. 2 X 24 81033054 A325 OWG. C-110-D-46976-100 DWG. C-110-D-46621-015 DWG. C-110-0-46621-014 OWG. C-110-0-46976-100 DWG. C-110-D-46976-500 CROSBY OR EO.
8 CABLE TIE DOWN 1
PRIMARY CRADLE ASSEMBLY SECONDARY CRADLE ASSEMBLY 1
PERSONNAL BARRIER MAIN SUPPORT FRAME (BASE SECTION) 2 CRADLE SUPPORT BEAM 3
1 PERSONNAL BARRIER END SUPPORT FRAME (BASE SECTION) 2 1
PERSONNAL BARRIER FRAME (MID. SECTION) 1 PERSONNAL BARRIER FRAME (UPPER)
SECTION)
ITEM OTY DESCRIPTION BILL OF MATERIALS OWG. C- 'I 10-0-46621-003 OWG. C-110-0-46621-013 OWG. C-110-D-46621-012 DWG. C-110-0-46621-009 OWG. C-110-0-46621-009 8
OWG. C-I 10-0-46621-006 OWG. C-110-0-46621-007 OWG. C-I 10-0-4662 1-005 SPEC.
AtID / OR PARI tto.
DO NOT SCALE PRINT PROPRIETARY gOg PROPRIETARY DIMENSIONS ARE IN INCHES UNLESS NOTED PROJECT No.
57906 FILE ID.
08910100 THIS DRAWING IS THE PROPERTY OF CHEM-NUCLEAR SYSTEMS IT IS LOANED UPON 1HE CONDITION THAT l1 IS NOI TO BE REPRODUCED.
COPIEO OR LOANEO TO OTHERS WITHOUT WRITTEN PERMISSIOti Of CHEM-NUCLEAR SYSTEMS ANO IS TO BE RETURNED UPON REOVESI.
DRAWN BY CHE Y
ENGINEER R.
BREHEN 6/97
</~/rt 4/c/tg FSCM Np 54643 REVIEWERS OF ORIGINAL (REv.'0)
CHEMNUCLEAR SYSTEMS ST.
LUCIE UNIT 1
STEAM GENERATOR GENERAL ASSEMBLY SQE DRAWitlO IIUVBEP RLv C-110-B-46621-004 Q
SCALE I/100 W:
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3.00 REF.
15 Q16Q17 12 B
12
~28 l 8 8 REF.
26'-2 ~ REF.
70 1/4 0'
0' 0
0 0
0 0'
5 6
16'-10 13 8 7
4 CTR. OF TRAILER 29'-10 1/4 SIDE VIEW 19 Q18 B
VIEW BB ARS'tI EC APmr'Vze CARD 4'-2 6'-4" REF.
45'4-6" CRIBBING 16'-2" BY OTHERS 33'- IO 1/2" 48'BARGE)
VIEW AA (SHT. 3 oF 3) 9Q0 11 PROPRIETARY NON-PROPRIETARY FSCIvI No. 54643 THIS 'ORAWING IS THE PROPERTY OF CHEM-NUCLEAR SYSTEMS IT 6 LOAAEO UPON THE CONOITION THAT IT IS NOT TO B.
REPROOUCEO.
COPIEO OR LOANEO TO OTHERS WITHOUT WRITTEN PERMISSION OF CHEh1-NUCLEAR SYSTEMS ANO IS,TO BE RETURNEO UPON REOUEST.
DO NOT SCALE PRINT:
DIMENSIONS ARE IN INCHES UNLESS NOTED PROJECT No.
57906 FiLE iO.
08910200 REVIEWERS OF ORIGINAL (REV. 0)
ST.
LUCIE UNIT 1
STEAM GENERATOR GENERAL ASSEMBLY DRAWN BY R.
BREHEN CHEC
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(X) TO CTR. OF TRAILER 200'-0 LENGTH OF'ARGE I~LW.
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CTR. LINE 6
REF BARGE/TRAILER 33'-1 0 1/2 24'-0 16 -11 1/4" 5'-3" 10'-9 1/4" 1 -1 1/2 TYP.
CTR.
LINE TRAILER 7'-7 1/4" 5'-3 5'-3 1/2 BARGE DECK PLAN VIEW PROPRIETARY DO NOT SCALE PRINT CHEMNUCLEAR SYSTEMS NON-PROPRIETARY DIMENSIONS ARE IN LNCHES UNLESS NPTEO PR(DIECT No.
57906 FILE ID.
08910300 THIS DRAWING IS THE PROPERTY Of CHEM-NUCLEAR SYSTEMS IT IS LOANEO UPON THE CONDITION THAT IT IS NOT TO BE REPRODVCEO.
COPIEO OR LOANEO TO OTHERS WITHOUT WRITTEN PERMISSION Of CHEM-NUCLEAR SYSTEMS AND IS 10 BE RETURNED UPON REOVEST.
DRAWN BY R.
BREHEN CHECKED Y
r ENGINEER
/1 4/97 C/C/t7 FSCM gp 54.6/3 REVIEWERS OF ORIGINAL (REV.,O)
SIZE ST.
LUCIE UNIT 1
STEAM GENERATOR GENERAL ASSEMBLY ORAWlNG tIUAIBER lhwz7oI5 -G REV B C-110-B-46621-004 0
SCALE I/I00 vn u / A suEET 5
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