ML20069C377
| ML20069C377 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/31/1982 |
| From: | Leduc R, Sandner H WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML17345B008 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 5885B:1-120382, WCAP-10168, NUDOCS 8303170516 | |
| Download: ML20069C377 (195) | |
Text
WESTINGHOUSE CLASS 3 3
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6 EVALUATION OF THE ACCEPTABILITY OF THE REACTOR VESSEL HEAD LIFT RIG, REACTOR VESSEL INTERNALS l
LIFT RIG, LOAD CELL, LOAD CELL LINKAGE AND REACTOR COOLANT PUMP MOTOR LIFT SLING j
TO THE REQUIREENTS OF NUREG 0612 for FLORIDA POWER AND LIGHT COMoANY TURKEY POINT UNITS 3 AND 4 y
DECEMBER, 1982 L
H. H. SANDNER, P. E.
Approved:
e R. [ Leduc, P. E., Manager Component Handling Equipment WESTINGHOUSE ELECTRIC CORPORATION Nuclear Energy Systems P.O. Box 355 Pittsburgh, PA 15230 8303170516 830315 PDR ADOCK 05000250 P
PDR i
5885B:1/120382
ABSTRACT I'
An evaluation of the Turkey Point Units 3 and 4 reactor vessel head and internal lift rigs, load cell, load cell linkage and reactor coolant pump motor lif t sling was performed to detenmine the acceptability of these devices to meet the requirements of NUREG 0612.
The evaluation consists of:
(1) a comparison report of the ANSI N14.6 requirements and the requirements used in the design and= manufacture of these devices; (2) a stress report in accordance with the design criteria of ANSI N14.6; and (3) a list of recommendations to enable these devices to i
demonstrate compliance with the intent of NUREG 0612 and ANSI N14.6.
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[ABLE OF CONTENTS i
Section Title Page s
ABSTRACT iii 1.
INTRODUCTION 1 -1 f
1.1 Backg round -
1-2 2.
COMPONENT DESCRIPTION 2-1 2.1 Reactor Vessel Head Lift Rig 2-1 2.2 Reactor Vessel Internals lift Rig 2-1 2.3 Load Cell and Load Cell Linkage 2-2 2.4 Reactor Coolant Pump Hotor Lift Sling 2 _
3.
SCOPE OF EVALUATION ~
3-1 ~
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t 3-1 3.1 Study of ANSI N14.6-1978
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3-1 3.2 Stress Report 3.3 Recommendations 3-2 4.
DISCUSSION OF EVALUATIONS 4-1 4.1 Study of ANSI N14.6-1978 4-1 4.2 Stress Report 4-1 4.3 Recom:nendations 4-2 5.
CONCLUSIONS S-1 6.
RECOMMENDATIONS 6-1
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LIST OF ILLUSTRATIONS Figure Title Page 2-1 Reactor Vessel Head Lifting Rig 2-3 2-2 Reactor Vessel Internals Lifting Rig 2-4 2-3 Reactor Coolant Pump Motor Lift Sling 2-5 k
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1 ATTACHMENTS A.
Comparison of ANSI N14.6-1978 Requirements for Special Lifting Devices and the Requirements for the Reactor Vessel Head Lift Rig, Reactor Vessel Internals Lift Rig, Load Cell, Load Cell Linkage and Reactor Coolant Pump J4otor Lift Sling for Florida Power and Light Company, Turkey Point Units 3 and 4.
B.
Stress Report - Reactor Vessel Head Lift Rig, Reactor Vessel Inter-nals Lift Rig, Load Cell, Load Cell Linkage and Reactor Coolant Puup i
Motor Lift Sling for Florida Power and Light Company, Turkey Point Units 3 and 4.
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REFERENCES 1.
George, H., Control of Heavy Loads at Nuclear Power Plants Resolution of Generic Technical Activity A-36, NUREG 0612, July, 1980.
2.
ANSI N14.6-1978 Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds or More for Nuclear Material 3.
ANSI B 30.9-1971.
Slings, American National Standards Institute, New York, 1971 4.
Westinghouse Drawing 685J249, Head Lifting Rig General Assembly 5.
Westinghouse Drawing 685J291, Turkey Point Units 3 and 4 Internals Lifting Rig General. Assembly 6.
Westinghouse Drawing AED-SK-618J644TXK, Handling Sling Spreader for -
tiotor SV-4M-Al Pump General Assembly
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ATTACINENT A to WCAP-10168 COMPARISON OF ANSI N14.6-1978 REQUIREMENTS FOR l
SPECIAL LIFTING DEVICES AND THE REQUIREMENTS FOR THE REACTOR VESSEL HEAD LIFT RIG, REACTOR YESSEL INTERNALS LIFT RIG, LOAD CELL, LOAD CELL LINKAGE AND REACTOR COOLANT PUMP l
MOTOR LIFT SLING FOR FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 l
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December 1982 H. H. Sandner, P.E.
l Approved f.J. Leduc,P.E., Manager Coapanent Handling Equipment s
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e ABSTRACT The requirements used in the original design, fabrication, testing, maintenance and quality assurance were compared to the ANSI N14.6-1978 requirements for the Turkey Point Units 3 and 4 reactor vessel head and internals lift rig, load cell, load cell linkage and reactor coolant pump motor lift sling.
critical items list per section 3.1.2 has been prepared and a tabulation of ANSI N14.6 requirements that are, at present, incompatible with the Turkey Point Units 3 and 4 lifting devices has been prepared.
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TABLE OF CONTENTS Section Titl e Page ABSTRACT 111 l
1 PURPOSE 1-1 2
INTRODUCTION 2-1
2.1 Background
2-1
- 2. 2 Component Description 2-2 2.2.1 Reactor Vessel Head Lift Rig 2-2 2.2.2 Reactor Yessel Internals Lift Rig 2-2 2.2.3 Load Cell and Load Cell Linkage 2-3 2.2.4 Reactor Coolant Pump Motor Lift Sling 2-3 3
DISCUSSION 3-1 4
CONCLUSION 4-1, t
APPENDIX A - CRITICAL ITEMS LIST PER ANSI N14.6-1978 A-1 APPENDIX B - TABULATION OF ANSI N14.6-1978 REQUIREMENTS B-1 INCOMPATIBLE WITH THE TURKEY POINT SPECIAL LIFTING DEVICES 4
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LIST OF ILLUSTRATIONS Figure Title Page A-1 Reactor Vessel Head Lift Rig A-5 A-2 Reactor Yessel Internals Lift Rig, A-10 Load Cell and Linkage i
A-3 Reactor Coolant Pump Motor Lift Sling A-12 l
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5888B:1/122882 vii
LIST OF TABLES I
Table Title Page 2-1 Comparison of the Requirements of ANSI N14.6 2-4 and Turkey Point Special Lifting Devices A-1 Reactor Vessel Head Lift Rig, Critical Items A-3 List of Parts per ANSI N14.6-1978 A-2 Reactor Vessel Head Lift Rig, Critical Items A-4 List of Welds per ANSI N14.6-1978 A-3 Reactor Vessel Internals Lift Rig, Load Cell A-6 and Load Cell Linkage, Critical Items List of Parts per ANSI N14.6-1978 A-4 Reactor Yessel Internals Lift R.ig, Load Cell A-9 and Load Cell linkage, Criticals Items List of Welds per ANSI N14.6-1978 L
A-5 Reactor Coolant Pump Motor Lift' Rig, Critical A-ll Items List of Parts and Welds per ANSI N14.6-1978 B-1 Bill of Material for the Non-Designed Items of B-7 i
the Reactor Coolant Pump Motor Lift Sling I
5888B:l/122882 ix l
E' REFERENCES 1.
Westinghouse Drawing 685J249, Head Lifting Rig General Assembly 2.
Westinghouse Drawing 685J291, Turkey Point-Units 3 and 4 Internals Lifting Rig General Assembly 3.
Westinghouse Drawing AED-SK-618J644TXK Handling Sling Spreader for Motor SV-4M-Al Pump General Assembly i
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5383B:1/122182 xi
SECTION 1 PURPOSE The purpose of this report is to compare the requirements of the special lifting rigs used to lift the reactor ve'sel head, reactor vessel upper s
and lower internals, and the reactor coolant pump motor with the requirements contained isi Al4SI N14.6 for special lifting devices.
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SECTION 1 INTRODUCTION The Nuclear Regulatory Commission (NRC) issued NUREG 0612 " Control of Heavy Load at Nuclear Power Plants"bl in 1980 to address the control of heavy loads to preven,t and mitigate the consequences of postulated accidental load drops.
NUREG 0612 imposes various training, design, inspection and procedural requirements for assuring safe and reliable operation for the hand'ing of heavy loads.
In the containment building, NUREG 0612 Section 5.1.1(4) requires special lifting devices to meet the requirements of ANSI N14.6-1978 "Anerican National Standard for Special Lifting Devices for Sh p ing Containers Weighing 10,000 Pounds or More for Nuclear Materials" In general, ANSI N14.6 contains detailed requirements for the design, fabrication, testing, maintenance, and quality assurance of special lifting devices.
In addition, ANSI N14.6 required that when wire rope or chain is used in the design of a special lifting device, the wire rope or chain shall be in conformance with ANSI B30.9-1971 "Anerican National Standard Safety Standard for Slings. "E33 -
The Turkey Point lifting devices which c~an be categorized as special lifting devices and which are contained in the gcope of this report aret_
1.
Reactor vessel head lift rig 2.
Reactor vessel inte'rnals lift rig 3.
Load cell 4.
Load cell linkage I
5.
Reactor coolant pump motor lift sling.
i This report contains the evaluation performed on these lifting devices to determine the acceptability of these devices to meet the above requirements.
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1.1 BACKGROUND
The reactor vessel head lift rig, the reactor vessel internals lift rig, i
load cell, load cell linkage and reactor coolant pump motor lift sling f
were designed and built for the Turkey Point Units 3 and 4 circa 1967-68.
The actual design criteria is unknown for the lifting devices.
It appears that for the head lift rig, internals lift rig,
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load cell, load cell linkage and the reactor coolent puiap motor lift sling that in most cases the design criteria used was that the resulting stress in the load carrying members, when subjected to the total com-bined lif ting weight, does not exceed one fifth (1/5) of the ultimate strength of the material.
These items were not classified as nuclear j
safety components and requirements for fonnal documentation of design j
requirements and stress reports were not applicable. Thus, stress I
reports and desigr specifications were not formally documented.
Westinghouse defined the design, fabrication and quality assurance requirements on detailed manufacturing drawings and purchase order docu-
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ments.
Westinghouse also issued field assembly any operating instruc-tions, where applicable.
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i SECTION 2 COMPONENT DESCRIPTION r
2.1 REACTOR VESSEL HEAD LIFT RIG l
The rea: tor vessel head lift rigE43 (Figure 2-1) is a three legged carbon steel structure, approximately 35 feet high and 14 feet in dia-meter, weighing approximately 25,000 pounds.
It is used to handle the assembled reactor vessel head.
The three vertical legs and Control Rod Drive Mechanism (CRDM) platform assembly are pennanently attached to the reactor vessel head lifting lugs.
The tripod assembly is attached to the three vertical legs and is used when installing and removing the reactor vessel head. During plant operation, the sling assembly is removed and the three vertical legs and platfonn assembly remain attached to the reactor vessel head.
2.2 REACTOR YESSEL INTERNkLS LIFI RIG The internals lifting rig [5] (Figure 2-2) is a -three-legged carbon and.
L stainless steel structure, approximately 29 feet high and 12 feet in diameter weighing approximately 13,000 pounds.
It is used to handle the upper and lower reactor vessel internals packages.
It is attached to the main crane hook for all' lifting, lowering and traversing opera-tions.
A load cell linkage is connected between the main crane hook and tne rig to monitor loads during all operations.
When not in use, the rig is stored on the upper internals storage stand.
The rig attaches to the internals packages by means of three engaging screds which are screwed into tapped holes in the internals flanges.
These screws are manually operated from the spreader assembly using the l
integral tools.
The screws are nonnally spring retracted upward and are l
depressed to engage the tapped holes.
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l' 2.3 LOAD CELL AND LOAD CELL LINKAGE l
The load cell is used to monitor the load during lifting and lowering the reactor vessel internals to ensure no ' excessive loadings are f
occurri ng.
It is installed between the load cell linkage and the lif ting device.
The load cell is a strain gage (tension) type, rated at 300,000 pounds and built by W. C. Dillon and Co.
The load cell linkage' is an assembly of pins, plates and bolts which connect the polar crane i
main hook to the load cell.
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2.4 REACTOR COOLANT PUMP MOTOR LIFT SLING The reactor coolant pump motor lift sling (Figure 2-3) consists of f
a six (6) foot triangular carbon steel spreader assembly weighing l
approximately one thousand (1,000) pounds.
It has wire rope slings, f
i shackles and turnbuckles attached which fom a three point lif t assembly.
It is used to handle the reactor coolant pump motor.
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g 71/2" DI AMETER PIN 8" DIAMETER PINN
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LINKLUG SIDE PLATE
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UPPER CLEVl3
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4" DI AMETER UPPER CLEVIS PIN ARM
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CLEvi$
j 4" DI AMETER PIN
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SUPPORT lug N-
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RING GIRDER
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LEG
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CLEVl3 PLATE S1/2" DI AMETER PIN Q#
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Figure 2-1.
Reactdr Vessel ifead Lifting Rig 58858:l/120382 2-3
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(HOOK)p N
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(UPPER) ADAPTOR (UPPER ADAPTOR) PIN TENSION CELL TOP LUG (LOWER) ADAPTO Nqr (REMOVA8LE) PtN (UPPER SLING LEG) PIN r
SLfNG LEG 0
BLOCK t;
(LOWER SLING LEG) PIN p
N (GE9 N
SPREADER
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J p
P NUT f(LEG) OUTER TU8E (LEG)
ADAPTOR
5 (LEG) LEVELING SLEEVE D
COUPLING w
(SUPPORT RING) /
LEVELING SLEEVE
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(SUPPORT RING) OUTER TUBE GUIDE SLEEVE ENGAGING SCREW Figure 2-2.
Reactor Vessel Internals Lifting Rig 58858:l/120382 2-4 i
MASTER LING y
ASSEMBLY
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SPREgggR SHACKLE 4 ~ TunngUCKLE I
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SLING Hoog 5
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I Figure 2-3.
Reactor Coolant Pump liotor Lift Sling I'
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SECTION 3 SCOPE OF EVALUATION The evaluation of these lifting devices consists mainly of three parts:
1.
A detailed review of the ANSI N14.6 requirements 2.
Preparation of a stress report 3.
Recommendations to demonstrate compliance with NUREG 0612, Section 5.1.1(4).
Discussion of these items follows.
3.1 REVIEW 0F ANSI N14.6-1978 i
A detailed comparison was made of the infomation contained in ANSI N14.6 with the infonnation that was used to design, manufacture, inspect and test these special lifting devices.' The detailed comparison' is provided in three parts:
A 1.
Overall item by item comparison of requirements 1
2.
Preparation of a critical item list per ANSI N14.6 Section 3.1. 2, and 3.
Preparation of a list of nonconfoming items.
This detailed analysis is contained in Attachment A to this report.
i 3.2 PREPARATION OF A STRESS REPORT 1
Section 3.1.3 of ANSI N14.6 and NUREG 0612 Section 5.1.1(4) require a stress report to be prepared.
Special loads and allowable stress cri-i teria are specified for this ana. lysis.. The stress report is Attachment 8 to this report.
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4 3.3 RECOMlENDED ACTIONS i
An obvious result from the previous evaluations is a list of items that can be perfonned to demonstrate to the NRC that these special lifting i
devices are in compliance with the guidelines of ANSI N14.6 and NUREG 0612 Section 5.1.1{4).
These recomendations are identified in i
Section 6.
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SECTION 4 l,
DISCUSSION OF EVALUATIONS I l 4.1 STUDY OF ANSI N14.6-1978 l
l A review of ANSI N14.6 identifies certain analyses to be performed and j
certain identifications "that are required to be made to demonstrate compliance with this document.
These are a preparation of a stress report in accordance with Section 3.2 and a preparation of a critical items list in accordance with Section 3.1.2.
The stress report is Attachment B to this report.
The critical items list has been pre-pamd per Section 3.1.2 and is contained in Appendix A to Attachment A.
This list identifies the critical 13ad path parts and welds, the mater-ials of these items, and the applied non-destructive volumetric and 3
surface inspections that were perfonaed.
(Details of these non-destruc-l tive processes and acceptance standards am available at Westinghouse l
should they be needed.)
l A detailed item by item comparison of all the requirements of ANSI N14,6 i
and those used for the design, manufacture and inspection of these lifting devices is contained as Table 2-1 of Aftachment A.
The compari-
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son shows that these devices meet the intent of the ANSI document for i
design, fabrication and quality control.
However, they do not meet the requirements of ANSI N14.6 for periodic maintenance, proof and func-i tional testing.
Thus, a tabulation of those ANSI N14.6 requirements that are incompatible with these lifting devices was prepared and is Appendix B to Attachment A.
Included in Appendix B to Attachment A are recomended actions that may be used to demonstrate acceptability to the NRC.
i 4.2 STRESS REPORT As part of the invoking of the ANSI N14.6 document, the NRC requested utilities to demonstrate their compliance with the stress criteria with some qualifying conditions.
At1!ac~hme'nt B is the stress report for these devices perfonned in accordance with the criteria of ANSI N14.6. A 5885B:1/122082 4-1 l
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I discussion is included which responds to the NRC qualifying conditions of NUREG 0612.
All of the tensile and shear stresses with the exception
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of the tensile stress at the minimum section of the internals engaging l
screw, item 23, meet the design criteria of Section 3.2.1.1 of ANSI N14.6, requiring application of stress design factors of three and five with the accompanying allowable stress limits of yield and ultimate strength, respectively.
In the engaging screw, the tensile stress t
I slightly exceeds the criteria that three times the calculated stress 3
must be less than the yield stress.
However, the conservative cciterion l
that five times the calculated stress must be less than the ultimate is met.
Application of Section 3.2.1.1 of ANSI N14.6 criteria to pins subject to l
bending, structural members subject to buckling and bending loads, and various parts subject to bearing loads, result in some stresses exceed-ing this criteria.
However, when using more appropriate criteria, the resulting stresses are acceptable.
4.3 RECOMMENDATIONS
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The recommendations identified in Section 6 requi6re a review of the existing Turkey Point maintenance and operating instructions to ensure that they contain infonaation relative to the identification, mainten-ance and periodic testing required by ANSI N14.6.
The extent of the periodic testing is also addressed and the reconnendations identify i
procedures which are intended to fully meet the intent of NUREG Util2 and ANSI N14.6 with the least amount of perturbation to the refueling i
l sequence.
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SECTION 5 CONCLUSIONS The following conclusions are apparent as a result of this evaluation:
1.
The ANSI N14.6 requirements for design, fabrication and quality assurance are generally in agreement with those used for these special lift devices.
2.
The ANSI N14.6 criteria for stress limits associated with certain stress design factors for tensile and shear stresses are adequately satisfied with the exception noted in Section 4.2.
3.
These devices are not in strict compliance only with the ANSI N14.6 requirements for acceptance testing, maintenance and verification of continuing compliance.
Recommendations are included to identify actions that should enable these devices to be considered in compli-ance with the intent of ANSI N14.6.
4.
The application of the ANSI N14.6 criteria for stress design factor of 3 and 5 are only for shear and tensile 1,oading conditions.
Other loading conditions are to be analyzed to other appropriate criteria.
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SECTION 6 RECOMMENDATIONS g
I The following recommendations address the areas of ANSI N14.6 which are I
incompatible with the present lifting devices and which are considered most important in demonstrating the continued reliability of these devices.
They consist of suggestions and proposed responses to identify l'
compliance to the NRC and future considerations.
6.1 Review the existing operating procedures to include consideration of ANSI N14.6 Sections 5.1.3 through 5.1.8.
These sections include requirements for:
scheduled periodic testing; special identifica-4 I
tion and marking; maintenance, repair, testing and use. Westing-house remarks on addressing these sections are listed in Attachment A, Appendix B, Items 7, 8, and 9.
6.2 A proposed response to the requirement of ANSI N14.6 Section 5.2.1 requiring an initial acceptance load test prior to use equal to 150 percent of the maximum load is as follows:
5 The head lift rig was load tested and inspqcted at assembly to approximately 100 percent of the load.
The' internals lift rig and the R.C. pump motor lift sling were not required to be load tested.
6.3 A proposed response to ANSI N14.6 Section 5.3 which requires, annually, either a 150 percent maximum load test or dimensional, visual and non-destructive testing of major load carrying welds and critical areas follows.
(Since the 150 percent load test is very impractical, the approach identified in the following recommendation is to perfonn a minimum of non-destructive testing.)
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a.
Reactor Vessel Head Lift Rig:
Prior to use and after reassembly of the head lifting rig sling assembly to the platfona assembly, visually check the clevis to leg fillet welds at the bottom end of the legs and the support lug to ring girder fillet welds on the platfom.
Raise the vessel head slightly above its support and hold for 10 ninutes.
During this time, continue to visually inspect these welds.
If no problems are apparent, continue to lift.
b.
Reactor Vessel Internals Lift Rig Prior to use, visually inspect the rig components and welds while on the storage stand for signs of cracks or defonaation.
Check all bolted joints to ensure that they are tight and secure.
After connection to the upper or lower internals, raise the assembly slightly off its support and hold for 10 minutes.
If no problems are apparent, continue to. lift, raonitoring the load cell readout at all ti'mes.
c.
Reactor Coolant Pump Motor Lift Sling L
Prior to use, visually inspect the rig components and welds for signs of cracks, defomation, kinks, or frayed ends.
Check all bolted joints to ensure that they are tight and secure.
After connection to the pump motor, raise the assembly slightly off l
l its support and hold for 10 minutes.
During this tiue visually j
check the spreader welds.
If no problems are apparent, continue f
to lift.
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The above actions do not include a non-destructive test of these welds because:
a.
Access to the welds for surface examination is difficult.
These rigs are in containment and some contamination is present.
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b.
All tensile and shear stmsses in Lthe welds are well within the allowable stress with the exception of the internals engaging screw.
c.
The items that are welded remain assembled and cannot be misused for any other lift other than their intended func-tion.
d.
To perfonn non-destructive tests would require:
i (1) Removal of paint around the area to be examined which is contaminated.
(2) Perfonaance of either magnetic particle inspection or -
liquid penetrant inspection and 3
(3) Repainting af ter testing is completed.
(4) Cleanup of contaminated items. *
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Perfonning non-destructive tests on these welds every refueling
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I would increase the critical path refueling ' time.
f Dimensional checking is. not included since these structums are
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large (about 14 ft. dia. by 35 ft. high) and the results of dimen-sional checking would always be questionable.
Other checks on critical load path parts such as pins, are also not included since l
an examination of these items would require disassembly cf the-I special lift devices.
6.4 Recommend that a periodic non-destructive surface exainination of critical welds and/or parts be perfonned once eve 7 ten years as part of an inservice inspection outage.
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i 6.5 Recotxnend that a modification be made to the load cell to be adapt-l able to both the head and internals lift rig. Thus, monitoring of l
these loads during movement can be accomplished at all times.
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6.6 Recominend that no changes be made to the reactor vessel internals lif t rig should the stresses, discussed in Attachment B, be con-sidered excessive by others because:
a.
The design weight used in the stress calculations is based on the weight of the lower internals. The lower internals are only removed when a periodic inservice inspection of the vessel is required (once/10 years).
b.
Prior to. removal of the lower internals, all fuel is removed.
Thus the concern for handling over fuel is non-existant in this particular case.
c.
Nonnal use of the rig is for moving the upper internals, which weigh less than 1/2 of the lower internal's.
The design weight is based on lifting the lower internals gThus all the stresses j
could be reduced by approximately 50 perc'ent and considered well within the ANSI N14.6 criteria for stress design factors.
6.7 Recommended that the internals lift rig sling block be changed to a forged block with welded side lugs to reduce the number of welds, should the NRC require yearly surface inspection of welds.
6.8 Recommended that plates be added to the sides of the spreader (item
- 14) to reinforce it.
Plates should be of sufficient size to satisfy the emperical equations for structures loaded in combined compres-l sion and bending, as described in the ASME Boiler and Pressure l
Vessel Code Section III, Appendix XVII.
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SECTION 2 INTRODUCTION l
i ANSI N14.6-1978 "American National Standard for Special Lifting Devices for Shipping Containers t!cighing 10,000 Pounds or More for Nuclear Materials" contains detailed requiremerits for the design, fabrication, testing, maintenance and quality assurance of special lifting devices.
NUREG 0612 " Control of Heavy Load at Nuclear Power Plants", paragraph 5.1.l(4), specifies that special lifting devices should satisfy the guidelines of ANSI N14.G-1978.
Subsequently the Nuclear Regulatory Coinmission (NRC) has requested operating plants to demonstrate coupli-ance with NUREG 0612. To demonstrate compliance with this document, a detailed comparison of the original design, fabrication, testing, main-tenance and quality assurance requirements with those of ANSI N14.6 is necessary.
Thus, the ANSI N14.6 document has been reviewed in detail and compared to the requirements used to desigr1 and manufacty're the reactor vessel head lift rig, the reactor vessel internals lift rig, load cell, load _
cell linkage and the reactor coolant pump motor lift sling. This o
comparison is listed in Table 2-1.
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2.1 BACKGROUND
The reactor vessel head lift rig, the reactor vessel internals lift rig, I
load cell, load cell linkage and reactor coolant pump motor lift sling were designed and built for the Turkey Point Units 3 and 4, circa l
1967-63. The actual design criteria is unknown for the lifting devices.
It appears that for the head lift rig, internals l'ift rig, load cell, load cell linkage and the reactor coolant pump motor lift sling that in most cases the design criteria used was that the resulting stress in the load carrying members, when subjected to the total combined lifting weight, does not exceed one fifth (1/5) of the ultimate strength of the material. Westinghouse also required non-destructive tests and inspections on most critical ' load path parts and welds both as i
58883:l/122182 2-1
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raw material and as finished items.
These requirements of design, manufacturing and quality assurance were identified on detailed manufacturingdrawingandpurchasingdo5uments.
Westinghouse also issued field assembly and operating instructions, where applicable.
2.2 COMPONE!1T DESCRIPTION 2.2.1 Reactor Vessel Head Lift Rig EI3
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The reactor vessel head lift rig is a three legged carbon steel structure, approximately 35 feet high and 14 feet in diameter, weighing j
I approximately 25,000 pounds.
It is used to handle the assembled reactor vessel head.
The three vertical legs and control rod drive mech.anism (CRDM) platform assembly are permanently attached to the reactor Wer,sel head lifting lugs.
The tripod sling assembly is attach'ed to the three vertical legs -
'I and is used when installing and removing the reactor vessel head.
During plant operations, the sling assembly is reincved and the three vertical legs and platform assembly remain attached to the reactor j
vessel head.
i-2.2.2 Reactor Vessel Internals Lift Rig i
The reactor vessel internals lift rig [2] is a three-legged carbon and stainless steel ~ ct. ;ture, approximately 29 feet high and 12 feet in diameter we p, ;, groximately 13,000 pounds.
It is used to handle' the upper and Iv.er., *.or vessel internals packages.
It is attached to the main crane hook for all lifting, lowering and traversing opera-tions. A load cell linkage is connected between the main crane hook and the rig to monitor loads during all operations. 'Uhen not in use, the rig is stored on the upper interna.ls storage stand.
t 58833:l/i22182 2-2 l
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i The rig attaches to the internals packages by means of three engaging screws which are screwed into tapped holes in the internals flanges.
These screws are manually operated from the spreader assembly using the integral tools.
The screws are nonnally spring retracted upward and are depressed to engage the tapped holes.
2.2.3 Load Cell and Load Cell Linkage The load cell is used to monitor the load during lifting and lowering the reactor vessel internals to ensure no excessive loadings are occurri ng.
It is installed between the load cell linkage and the lifting device.
The load cell is a strain gage (tension) type, rated at 300,000 pounds, built by W. C. Uillon and Co. The load cell linkage is an assembly of pins, plates and bolts which connect the polar crane main hook to the load cell.
2.2.4 Reactor Coolant Pump Motor Lift Sling b
The reactor coolant puup motor li t sling consists of a six (6) foot triangular carbon steel spreader assembly ' weighing approximately one thousand (1,000) pounds.
It 4_ wire rope slings, shackles and
~
turnbuckles attached which fona a three point lift assembly.
It is used it to handle the reactor coolant pump motor.
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l 58888:1/120682 2-3
w TABLE 2-1 h
COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 AND 3
TURKEY POINT SPECIAL LIFT DEVICES
{
a
)
J N
ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section 1
Scope and Definitions - These sections These sections are definitive, and not 1.1 define the scope of the document and requirements.
to include pertinent definitions of 1.3 specific items 2
3 Design A. No design specification was written con-3.1 Designer's Responsibilities - This section cerning these specific requirements.
3.1.1 contains requirements for preparing However, assembly and detailed manu-to a design specification and its' contents,.
facturing drawings and purchasing 3.1.4 stress reports; repair procedures; limi documents contain the following l
tations on use with respect to environ-requirements:
mental conditions; marking and nameplate information; and critical items list.
(1) Material specification for all of the critical load path items to ASTM, ASME specifications or special requirements listed.
. p.
(2) All welding, weld procedures and welds to be in accordance with ASME Boiler and Pressure Vessel Code -
Section IX or Westinghouse specifications (3) Special non-destructive testing for specific critical load path items to be performed to written ana approved procedures in accordance with ASTM or specified requirements
TABLE 2-1 (cont) f, COMPARISON OF THE REQUIREMENT OF ANSI N14.6 AND TURKEY POINT SPECIAL LIFT DEVICES 8?
E3 ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Sectioh (4) All coatings to be performed to strict compliance with specified requirements.
(5) Letters of compliance for materials and specifications were required for verification with original specifi-cations.
n3 i
6, B. A stress report was not originally required but has been prepared and is Attachment B.
C. Repair procedures were not identified.
D. No limitations were identified as to
'P the use of these devices unaer adverse environments.
E. Markings and nameplate information was not addressed except for the reactor coolant pump motor lifting which identifies MAXCAPACITY & TOOL (Drawing)
Number.
F. Critical iteailists have been prepared for each device ano are identified as Appendix A to this Attachnent A.
h3 TABLE 2-1 (cont) co 88 CUMPARISON UF THE REQUIRLMENT OF ANSI N14.6 AND
-k TURKEY POINT SPECIAL LIFT DEVICES G
m ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section 3.2 Design Criteria
- 1. The actual design criteria is 3.2.1 Stress Design Factors - These sections unknown for the lifting devices.
It to contain requirements for the use of stress appears that for the head lifting rig, 3.2.6 design factors of 3 and 5 for allowable internals lift rig, load cell, and the stresses of yield and ultimate respec-reactor coolant pump motor lift sling tively for maximum shear and tensile that in most cases the design criteria stresses; high strength material stress used was that the resulting stress in design factors; special pins; wire rope the load carrying members', when sub-and slings to meet ANSI b30.9-1971; ano jected to the total combined lifting drop-weight tests and Charpy impact test weight, ooes not exceed one fifth of
?)
requirements the ultimate strength of the mater-m i
ial. A stress report (Attachment B) has been generated which addresses the capability of these rigs to meet the ANSI design stress factors.
- 2. High strength materials are useo in some of these oevices (mostly for pins). Although the fracture r
toughness was not ceterminea, the material was selected based on it's tracture toughness characteristics.
However, the stress design factors of AN51 kl4.6 Section 3.2.1 of 3 ana 5 were useo in the analysis and the resulting stresses are acceptable.
- 3. Where necessary, the weight of pins was considered for hanaling.
i'
u, 88 TABLE 2-1 (cont) cu y,
COMPARISON OF THE REQUIREMENT OF ANSI N14.6 AND 2
TURKEY POINT SPECIAL LIFT DEVICES E$$
"3 ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lif t Device Requirements Section
- 4. Wire rope is used only in the design of the R.C. pump motor li f t sling.
However, the wire rope is of a special design and thus this device is considered a special lift device.
- 5. Drop weight and Charpy impact tests were not required nor performed.
3.3 Design Considerations - These sections.
Decontamination was not specifically 93 3.3.1 contain considerations for; materials of addressed.
Lamellar tearing was-not to construction, lamellar tearing; decontam-considered but the designs of these 3.3.8 '
sions; equal loao distribution; lock type of joint deterioration.
Even ination effects; remote engagement provi-devices are not susceptible to this devices; position indication of remote distribution of the load is evident actuators; retrieval of device if disen-from these designs.
Locking plates, gaged; and naneplates.
pins, etc. are used throu special lifting devices. ghout these Remote actuation is only used when engaging the internals lift rig with the internals, however, no position indication of engagement was provided.
However, all these items were considered and the designs reflect these requirements.
3.4 Design Considerations to Minimize Decontam-Decontamination was not specifically 3.4.1 ination Ettorts in Special Lif ting Device addressed.
However, the oesign and to Use - These sections contain fabrication, manufacture included many of these 3.4.6 welding, finishes, joint and machining items, i.e. lock devices, pins, etc.
requirements to permit ease in decontamination.
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TABLE 2-1 (cont)
-5 COMPARISON OF THE REQUIREMENT OF ANSI N14.6 AND
]
TURKEY POINT SPECIAL LIFT DEVICES Sm N
ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section 3.5 Coatings - These sections contain provisions The requirements for coating carbon 3.5.1 for ensuring proper methods are used in steel surfaces are contained in a to coating carbon steel surfaces and for 3.5.10 ensuring non-contamination of stainless.
Westinghouse process specification referenced on the assembly and detail steel items.
~
drawings except for the reactor coolant pump motor lift sling.
(The coating requirements for the reactor coolant pump motor lift sling are contained in purchasing documents and require proper
?
preparation and application of an epoxy paint.) This specification requires a proven procedure, proper cleaning, preparation, application and final in-spection of the coating.
These require-ments meet the intent of 3.5.1 through 3.5.8.
No provisions were included in these designs for consideration of decontamination materials or the use of non-contaminating contact materials for use in stainless steel parts.
3.6 Lubricants - These sections contain No specific lubrication requirements 3.6.1 requirements for special lubricants to have been identified.
However, neolube to minimize c6ntamination and degradation of is recommended for use with the engaging 3.6.3 the lubricant and contactea surfaces screws in the internals lif t device or water pools which are under water and silicone grease for the load cell pins which are out of water.
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4 g
TABLE 2-1 (cont) i COMPARISON OF THE REQUlkEMENT OF ANSI N14.6 AND TURKEY POINT SPECIAL LITT DEVICES El cn O
ANSI N14.6 Description of ANSI N14.6 Requirement-Actual Special Lift Device Requirements Section i
4 Fabrication A formal quality assurance program for the 4.1 Fabricators Responsibilities -These manufacturer was not required.
- However, 4.1.1 sections contain specific requirements all the manufacturers welding procedures to for proper quality assurance, document and non-destructive testing procedures 4.1.12 control, deviation control, procedure were reviewed by Westinghouse prior to control, material identification use. All critical load carrying members and certificate of compliance.
require letters of compliance for matcrial requirements. Westinghouse performed certain checks and inspections during ma various steps of manufacturing.
Final Westinghouse review includes visual, dimensional, procedural, cleanliness, personnel qualification, etc. and issuance of a quality release
- to ensure conformance with drawing requirements.
7 4.2 Inspectors Responsibilities -These Westinghouse Quality Assurance personnel 4.2.1 sections contain requirements for performed some inprocess and final to a non-supplier inspector.
inspections similar to those identified 4.2.5 in these sections.
(Also see consnents to Section 4.1 above) 4.3 Fabrication Considerations -These General good manufacturing processes 4.3.1 sections contain special requirements were followed in the manufacture to for case in decontamination or control of these devices.
However, the 4.3.3 of corrosion.
information defineo in these sections was not specifically addressed.
s' These remarks are not applicable to the Reactor Coolant Pump Motor Lift Sling
u, 88 TABLE 2-1 (cont) m CP COMPARISON OF REQUIREMENT OF THE ANSI N14.6 AND 23 TURKEY POINT SPECIAL LIFT DEVICES E$,
om ANSI,N14.6 Description of ANSI N14.6 Requirement Actual Special Lif t Device Requirements N
Section 5
Acceptance Testing haintenance, There wasn't any aesign specification and Assurance of Continued for these rigs and functional load Compliance Owner's Responsibilities -
testing was not originally required, 5.1 Sections 5.1.1 and 5.1.2 require the or performed.
- However, the Westinghouse 5.1.1 owner to verify that the special Quality Release may be considered an to lifting devices meet the performance acceptable alternate to verify that 5.1. 8 criteria of the design specification the criteria for letters of compliance by reviewing records and witness for materials and specifications of testing.
required by the Westinghouse drawings
?
and purchasing documents was satisfied.
3 2;
- Although proof and functional testing was not required, the site assembly instructions require, after initial assembly on site, the following for the reactor vessel head lif ting:
Raising the rig, assembled to it's
,p respective attachment, slightly above the supporting surface to be free hang-ing for one-hal f hour.
Lowering the rig to its support and performing visual inspection and the appropriate nonde-structive testing.
l These remarks are not applicable to the Reactor Coolant Pump Motor Lift Sling l
l 1
' ~ ~ ~ " ' - ~ ~ ~ ^ - ' - ~
=-
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TABLE 2-1 (cont) q' E
C0ffARIS0N OF THE REQUIREMENT OF ANSI N14.6 AND
^
C TURKEY P0lNT SPECIAL LIFT DEVILES
- G 8
E ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lif t Device Requirements Sec ti~on Section 5.1.3 requires periodic functional Since uaintenance and. inspection proce-testing dures are written, if these procedures do not contain this requirement, then these procedures should be revised to l
include a visual check of critical welds i
and parts during lifting to comply with this requirement for functional testing.
Section 5.1.4 require operating procedure Operating instructions for the reactor 1
m vessel internals lift rig were furnished
]
3 to the utility and operating procedures were prepared and are used.
Sections' 5.1.5, 5.1.5.1 and 5.1.5.2 require It is obvious from their designs special identification and marking to that these rigs are special lifting prevent misuse.
devices and can only be used for their
'I intended purpose.
Specific identifi-cation of the rig can be made by mark-ing, with stencils, the rig name and rated capacity, preferably on the spreader assembly.
Sections 5.1.6, 5.1.7 and 5.1.8 require Since operating instructions and the owner to provice written documenta-maintenance instructions have been i
tion on the maintenance, repair, testing written by the owner, these should i
and use of these rigs.
be revieweo to assure that they contain the requirements to address maintenance logs, repair and testing history, damage e*
incidents etc.
I
FJ TABLE 2-1 (cont) en$
COMPARISON OF THE REQUIREMENT OF ANSI N14.6 AND C
TURKEY POINI SPECIAL LIFT DEVICES C
2 ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section 5.2 Acceptance lesting and Testing to Verify Tne head lift rig was load tested at and Continuing Compliance - Ihese paragraphs field as'sembiy. it is suggested that a 5.3 require the rigs to be initially tested check of critical welds anc parts be 5.2.1 at 150 percent maximum load tollowec by -
incluceo in the maintenance proceoures to non-destructive testing of critical load for all three oevices. Preferably, 5.2.3 bearing parts anc welds ano also annual since these oevices have been in use at and 150 percent loaa tests.or annual non-least once per year for nyer ten years, 5.3.1 aestructive tests ano examinations; that a visual check during initial litt to qualification of replacement parts.
when possible should be acceptable.
5.3.8 Further note that with the use of the mi i
loaa cell for the internals, lifting and lowering is monitoreo at all times.
liowever, the loaa cell, which is used to monitor the internal lift rig loaas at all times, cannot exceed the rated loao by 20 percent without being inaccurate.
This would preclude monitoring of a load
,' test with the present equipment.
r Replacement parts should be in accord-ance with the original or equivalent requirements.
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TABLE 2-1 (cont) co COMPARISON OF THE REQUIREhENT OF ANSI N14.6 AND k
TURKEY POINT SPECIAL LIFT DEVICES
&8$
ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section 5.4 Maintenance and Repair - This section Maintenance and repair procedure should 5.4.1 requires any maintenance and repair to be contain, as much as possible, require-to performed in accordance with original nients that were used in the original 5.4.2 requirements and no repairs are permitted fabrication.
The critical items list of for bolts, stuos and nuts.
Appendix A contains the original type of non-destructive testing.
The procedure should also define bolts, studs and nuts as non-repairable items.
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5.5 Non-destructive Testing Procedures, Liquid penetrant, magnetic particle, L
5.5.1 Personnel Qualifications, and Acceptance ultrasonic and radiograph inspections to.
Criteria - This section requires non-were performed on identified items.
5.5.2 destructive testing to be performed in These were in accordance with ASTM accordance with the requirements of the specifications, the ASME Code, and ASME Boiler and Pressure Yessel Code Westinghouse process specifications or as noted on detailed drawings and pro-
- P vide similar results to the requirement of the ASME Code.
5 Special Lifting Devices for Critical It is assumed that compliance with 6.1 Loads - These sections contain special NUREG 0612, Section 5.1 has been 6.2 requirements for items handling critical demonstrated and therefore this section 6.3
- loads, is not applicable to these devices.
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l SECTION 3 DISCUSSION The reactor vessel head and internals lift rigs, load cell, load cell linkage and reactor coolant pump motor lift sling generally meet the intent of the ANSI N14.6 requirements for design and manufacture.
However, they are not in strict compliance with the ANSI N14.6 requirements for acceptance testing, maintenance and verification of continuing compliance.
Although no specific design specification was written, the assembly and detailed manufacturing drawings and purchase order documents contain equivalent requirements.
A stress report has been prepared for these devices and the design criteria is considered satisfied.
These devices, l
for the most part, were manufactured under Westinghouse surveillance with identified hold points, procedure review and personnel qualifica-tion which adequately meet these related ANSI requirements. Acceptance testing was not performed.
However, an initial jift test was conducted,
for the head lift rig followed by the appropriate non-destructive testing following site assembly. Although the reactor coolant pump L
motor lift sling is called a sling, it is not afstandard catalog item.
Thus, it cannot be considered to be reviewed in accordance with the requirements of ANSI B30.9-1971.
It is anticipated that a 100 percent load test, performed on each j
device, folicwed by a visual check of critical welds would be sufficient to demonstrate compliance. This may require modification of existing Turkey Point operating and maintenance procedures.
t 5888B:1/122882 3-1
SECTION 4 CONCLUSIONS The review of the ANSI N14.6 requirements and comparison with the origi-nal Westinghouse requirements has shown that these items are generally in agreement for the design, fabrication and quality assurance of the lif ting devices.
However, the lifting devices are not in strict compli-ance with the ANSI N14.6 requirements for acceptance testing, mainte-nan;e and verification of continuing compliance.
These specific requirements that are incompatible with the lifting devices are dis-cussed in Appendix B with suggested actions. Westinghouse's objective was to provide a quality product and this product was designed, fabri-cated, assembled and inspected in accordance with internal Westinghouse
[
requirements.
In general, Westinghouse requirements meet the intent of l
A1451 1114.6 but not all the specific detailed requirements.
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l 5888B:l/120682 4-1 I
APPENDlX A CRITICAL ITER 4S LIST PER ANSI N14.6-1978 4
1.
GENERAL F
t' Section 3.1.2 of ANSI.N14.6-1978 specifies that the design specification shall include a critical items list, which identifies critical compo-nents and defines their critical characteristics for material, fabrica-tion, non-destructive testing and quality assurance.
" Critical items list" is further defined in ANSI N14.6, Section 2 as:
I' L
" critical items list.
A list that specifies the items of a special lifting device and their essential characteristics for which specified quality requirements shall apply in the 4
design, fabrication, utilization, and maintenance of the device."
l Load carrying members and welds of these special lifting devices are
~
considered to be the critical items.
i y
Tables A-1, A-2, A-3, A-4, and A-5 are the critical items list of parts and welds for the reactor vessel head lift rig, the reactor vessel internals lift rig, load cell and load cell linkage, and the reactor coolant pump motor lift sling respectively.
These tables include the material identification, and the applicable volumetric and surface inspections that were perfonned in the fabrication of these special lifting devices.
In some instances, non-destructive testing was not specified since the material selection and strength result in very low tensile stresses and thus, non-destructive testing was not justified.
The material selection for critical load path items was made to ASTM, i
ASME or special material requirements.
However, the non-designed iteus l
of the reactor coolant pump motor lift sling were selected based on i
l l
l 58888:1/120682.
A-1 I
c t
1 their load carrying capacities.
The material requirenients were supple-l I
mented by Westinghouse imposed non-destructive testing, and/or special 1
i heat treating requirements for almost all of the critical items.
I Westinghouse required all welding, welders, and weld procedures to be in accordance with ASME Boiler and Pressure Vessel Code Section IX or l
Westinghouse specifications. Westinghouse required certificates, or j
letters of compliance that the materials and processes used by the manu-i f acturer were in accordance with the purchase order and drawing require-ments.. Westinghouse also perfonmed final inspection on these devices and issued quality releases for the internals and head lifting rigs.
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I-i S8883:l/120682 A-2
TABLE A-1 REACTOR VESSEL HEAD LIFT RIG CRITICAL ITB4S LIST OF PARTS PER ANSI N14.6-1978 f
Item (a)
Description Material Non-destructive Testing Material Finished 1,7,10,13 Pins ~
ASTM A434 U1 trasonic Magnetic 14 Class 80 Particle 2
Clevis Plate ASTM ASIS Ultrasonic Grade 70 Magnetic Particle 3
Leg ASTM A36 4
Ring Girder ASTM A285 Grade C 5
Support Lug ASTM A515 Ultrasonic Grade 70 Magnetic l
Particle
~
6,9 Clevi s ASTM A237 Ultrasonic Magnetic Class A Pa rticle' 8
Arm ASTM A306 Ul trasonic Magnetic Grade 70 Pa rticle l
11,12 Sling Assembly ASTM A105 Ultrasonic Magnetic Link and Lug Class 2 Particle l
15 Lifting Plate ASTM A514 Ul trasonic Magnetic I
Particle i
l (a)See figum A-1 l
l 58888:.1/120682 A-3
f TABLE A-2 l
REACTOR VESSEL HEA0 LIFT RIG
}
l CRITICAL ITEMS LIST OF WELOS I
PER ANSI N14.6-1978 i
Item (a)
Weld llon-destructive Testing Description Root Pass Final l
2,3 Clevis Plate to Leg Vi sual Magnetic (fillet)
Particle i
i' 4,5 Ring Girder to Support Lug (fillet) 14agnetic Particle 11,12 Link Lugs to Link Radiograph (full penetration) 11agnetic Particle l
(a)See figure ' A-1.
l 6
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58888:1/120682 A-4 L
h 8" DIAMETER PIN
' ' DIAMETER PIN h sioE PLATE h 8
LINK LUG @
/
LINK
,\\
UPPER CLEVIS @
h 4" D METER UPPER p
o ARMh
\\
Clevis @
/
g 4" DI AMETER PIN h
^
o h SUPPORT LUG N
I#
(
l\\/
VRING GIROER h ad/,
N %
x&
i i
N I
LEGh
~~
- /
u i
ll CLEVl3PLATEh qq n~otAuErEnpuuh a,
e)
NrJ SS Figure A-1.
Reactor Vessel Head Lift Rig i
58888:1/120682.
A-5
TABLE A-3 REACTOR VESSEL INTERdALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE CRITICAL ITEMS LIST OF PARTS PER ANSI N14.6-1978 Item (a)
D?scription Material Non-destructive Testing Material Finished 5
1, Hook Pin ASTM A434 Ultrasonic Magnetic Class BD Particle 3
Upper Adapter Pin 7
Removable Pin 2
Side Plate ASTM A515 Magnetic Grade 70 or Particle ASTM A516 Grade 70 8
Top Lugs
~~
12 Sling Leg L
10 Side Lugs 4
Upper Adapter ASTM AS40 Ultrasonic Magnetic Grade B24 Particle or Liquid Penetrant 6
Lower Adapter 5
Tension Cell 17-4 pH Ultrasonic Liquid H-1100 Penetrant 9
Block SA-105 Class 1 or 2 Ultrasonic Magnetic or Particle SA-266 Class 1 or 2 or SA-508 Class 1 or 2 (a)See figure A-2 I
i 58883:1/122182 A-6 6
TABLE A-3 (Cont)
REACTOR YESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE CRITICAL ITEMS LIST OF PARTS PER ANSI N14.6-1978 Itera(a)
Description Material Non-destructive Testing liaterial Finished 11 Upper Sling ASTM A276 Leg Pin Type 304, Center Ground Condition A 13 Lower Sling Leg Pin 14A Spacer Block SA-105 Class 1 or 2 Ultrasonic Magnetic or Particle SA-266 Class 1 or 2 or SA-508 Class 1 or 42 148,C,D Spreader ASTM A515 Grade 70 k
~
Assembly or ASTM A516 Grade 70 15 Nut ASTM A276 Type 304 HR and PKLD, Condition A 18 Leg Leveling ASTM A276 Sleeve Type 304 HR and PKLD, Condition A 20 Supporting Ring ASTM A276 Leveling Sleeve Type 304 HR and PKLD, Condition A l
22 Guide Sleeve ASTM A276 Type 304 HR and PKLD, Condition A (a)See figure A-2 5888B:1/120682 A-7
t i
6 TABLE A-3 (Cont) l REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND L0A0 CELL LINKAGE CRITICAL ITO4S LIST OF PARTS
-l PER ANSI N14.6-1978 Iteta(a)
Description Material Non-destructive Testing Material Finished 16 Leg Adapter ASTM A276' Type 304 HR and PKLD, Condition A i
23 Engaging Screw ASTM A276 Type 304 HR and PsLD, Condition A 19 Coupling ASTM A312 l
Type 30_4 21 Support Ring ASTM A312 Outer Tube Type 304
- Seamless, 4
~__
Cold Finish, HT TR i
17 Leg Outer ASTM A312 Tube Type 304
- Seamless, Cold Finish, HT TR (a)See figure A-2 l
I;-
i 5888B:l/1'20682 A-8
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TABLE A-4 REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE CRITICAL ITEMS LIST OF WELDS PER ANSI N14.6-1978 Item (a)
Weld Non-destructive Testing Description Root Pass Final 8,9 Top Lugs to Sling Block Magnetic Particle Magnetic Particle j
(full penetration) 9,10 Side Lugs to Sling Block Magnetic Particle Magnetic. Particle (full penetraton) 14 Spreader Assembly Visual Magnetic Particle (fillet) 16,17 Leg Outer Tube to Leg Liquid Penetrant Liquid Penetrant Adapter (full penetration) 17,18 Leg Outer Tube to Leg.,
LiquidPe,detrant Liquid Penetrant Leveling Sleeve i
(full penetration) 21,22 Support Ring Outer Tube Liquid Pet'netrar,t Liquid Penetra'nt to Guide Sleeve (full penetration)
(a)See figure A-2.
5888B:1/122182.
A-9
\\,
I t
t
. /(HOOK) PIN h SiOE PLATE h (UPPER ADAPTOR) PIN h h TENSION CELL
,U N
top LUG h h (LOWER) ADAPTOR (REMOVABLE) PIN h r
h (UPPER SLING LEG) PIN O
I
@ SioE lug _
[,
S"
@ BLOCx j'id e
(LOWER SLING LEG) PIN h
{
f j
C r
h
\\
\\
$PREADER N
s.'s
- s i
h NUT f(LEG) OUTER TUBE h
@ ADAPTOft (tEGi 5
c (LEG) LEVELING SLEEVE h i}.
I h COUPLING
'i Ne j
h (SUPPORT RING) /
LEVELING SLEEVE I
25:
(SUPPORT RING) OUTER TUBE h l
GU10E SLEEVE h ENGAGING SCREW h Figure A-2.
Reactor Vessel Internals Lift Rig 58883:1/120682 A-10
TABLE A-5 REACTOR COOLANT PUMP MOTOR LIFT RIG CRITICAL ITEMS LIST OF PARTS AND WEL0S PER ANSI N14.6-1978 Item (a')
Descri ption Material Non-destructive Testing Material Finished 1
Spreader ASTM A106 Grade B Magnetic Particle on Welds Only 2
Side Plate ASTM A106 Grade B 5
Master Link Alloy Steel Forging Radiograph 6
Sling Improved Plow Steel t
Assembly Grade 7
Shackle Alloy Steel Forging 8
Turnbuckle Alloy Steel Forging i
9 Eye Hook Alloy Steel Forging (a)See figure A-3 4
i
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l i
5888B:l/120682 A-11
,, 1
(
MASTER LINK Il h SLING ASSEMBLY l!
I i
\\
1 h
"U" BOLTS
,r i
h SPREADER I.
h SHACKLE b
E y
r h TURNBUCKLE
),
t.
as, l
h SIDE PLATES
~
l h ELING HOOK i
I Figure A-3.
Reactor Cooldnt Pum4 i40 tor Lift Sling i
i I
58888:l/120682 A-12
z APPENDIX 8 TA30LATION OF ANSI N14.6-1978 REQUIREMENf3 INCOMPATIBLE WITH THE TURKEY POINT LIFTING DEVICES 1.
GENERAL f.
The comparison of the various ANSI N14.6 requirements and thosd of these lifting devices has shown that these devices are not in strict compli-ance with all the ANSI N14.6 requirements.-
Listed below is a tabulation of those sections of ANSI N14.6 considered most important in demonstra-ting the continued load handling reliability of these special lifting devices. Associated Westinghouse remarks are also listed and could be used as suggested actions and/or responses to demonstrate coupliance to the NRC.
l a.
Requirement:
Para. 3.1.4 - requires the designer to indicate pemissible h
repair procedures and acceptance criteria for the repair.
a l b.
Remarks:
Any repair to these special lifting davices is considered 'to b'e in the fom of welding.
Should pins, bolts or other fasteners need repair, they should be replaced, in lieu of repair, in accordance with the original or equivalent requirements for material and non-destructive testing. Weld repairs should be perfomed in accordance with the requirements identified in NF-4000 and NF-5000 (Fabrication and Examaination) of the ASME Boiler and Pressure Vessel Code,Section III, Division,1 Sub-section NF.
2a.
Requirement:
Para. 3.2.1.1 - requires the ~ design, when using materials with l
yield strengths above 80 pen:ent of their ultimate strengths, I
i 5888B:1/120682 B-1
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to be based on the material's fracture toughness and not the listed design factors.
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2b. ' ' Remark s:
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,f' High strength materials are used in these devices.
Al though the fracture toughness was not determined, the material was selected based on it's fracture toughness characteristics.
i However, in lieu of a different stress design factor, the stress design factors listed in 3.2.1 of 3 and 5 were used in the analysis and the resulting stresses are considered acceptable.
f 3a.
Requirement:
Para. 3.2.6 requires material for load-bearing members to be subjected to drop-weight or Charpy impact tests.
3b.
Remarks:
Fracture toughness requirements were notfidentified for the material used in these special lifting devices.
However, the
't-material selection was based on its fract' re toughness u
4
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characteristics.
- 4a.
Requirement:
Para. 3.3.6 requires an indication that an actuating mechanism is engaged.
4b.
Remarks:
The reactor vessel internals lift rig employs a long handled tool to engage the rig and the internals.
The tool depresses a I
spring loaded tube and turns the engaging screw into the inter-nal s.
Although no specific position indication is identified, j
the visual difference in the top of the spring loaded tube is considered sufficient indication that the internals are engaged.
5888B:1/120682 B-2
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Requirement:
Para. 4.1.6 requires a formal quality assurance prograu for the manufacturer and para 4.1.7 requires certification and identi-fication of materials.
Sb.
Remarks:
J' A fonnal quality assurance program for the manufacturer was not required.
However,1the manufacturers welding procedures and non-destructive testing procedures were reviewed by Westing-house prior to use.
All critical load carrying members require letters of compliance for material requirements.
Westinghouse perfonaed certain checks and inspections during various steps of manufacturing.
Final Westinghouse review includes visual, dimensional, procedural, cleanliness, personnel qualification, etc. and issuance of a quality release to ensure conformance with drawing requirements.
No information that a quality release was issued for the reactor coolant pump motor lift sling has been found, although Westinghouse performed the final inspection.
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6a.
Requi reaent:
L Para. 5.1 lists Owner Responsibilities and 5.1.2 requires the owner to verify that the special lifting devices meet the perfonnance criteria of the design specification hy records and i
witness of testing.
l 6b.
Remarks:
There wasn't any design specification for these rigs and load j
testing was not originally required or performed.
However, the Westinghouse Quality Release may be considered an acceptable alternate to verify that the criteria for letters of compliance for materials and specifications required by the Westinghouse drawings and purchasing document were satisfied. Although I
L 5888B:.1/120682 B-3
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proof and functional testing was not required, the site assem-bly instructions require, after initial assembly on site, the following for the reactor vessel head lifting:
)
Raising the rig, assembled to it's respective attachment, slightly above the supporting surface to be free handing for one-half hour.
Lowering the rig to its support and perfonaing i
visual inspection'and the appropriate nondestructive testing.
No other checks of welds and/or dimensions after assembly was required of the other special lifting devices.
7a.
Requirement:
Para. 5.1.3 requires periodic functional testing and a system f
to indicate continued reliable perfonaance.
7b.
Remarks:
Since maintenance and inspection procedures are available if these procedures do not contain this requirement, then these procedures should be revised to include ji visual check of critical welds and parts when possible during lifting to comply _
l with this requirement for functional testing.
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t 8a.
Requirement:
Para. 5.1.5, 5.1.5.1 and 5.1.5.2 require special identification j
and marking to prevent misuse.
8b.
Remarks:
It is obvious, from their designs, that these rigs are specific.
lifting devices and can only be used for-their intended purpose and parts are not intert:hangeable.
Specific identification of l
the rig can be made by marking with stencils, the rig name and rated capacity, preferably on the spreader assembly, t
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I 58888:1/120682 B-4
9a.
Requirement:
Para. 5.1.6, 5.1.7 and 5.1.8 require the owner to provide written documentation on the maintenance, repair, testing and use of these rigs.
9b.
Remarks:
Since operating instructions and maintenance instructions have been written by the owner, these should be reviewed to assure that they contain the requirements to address maintenance logs, repair and testing history, damage incidents and other iteus mentioned in these paragraphs.
10a. Requirement:
Para 5.2.1 requires the rigs to be initially tested at 150 percent maximum load followed by non-destructive testing of critical load bearing parts and welds.
10b. Remarks The head lift rig was 16ad tested and' inspected at assembly to ^
approximately 100 pen:ent of the load! The internals lift rig and the R.C. pump motor lif t sling wepe not required to be loa'd tested.
I lla. Requirement:
Para 5.2.2 requires replacement parts to be individually quali-fied and tested.
j lib. Remarks Replacement parts, should they be required, should be made of identical (or equivalent) material and inspections as origi-nally required.
Only pins, bolt and nuts are considered replacement parts for the reactor vessel head and internal lift ri gs.
Some of the items comprising the reactor coolant pump motor lif t sling are catalog items and should they need replacement should be as identified in table B-1.
58888:1/120682 B-5 i
12a. Requirement:
l Para 5.3 requires testing to verify continuing compliance and annual 150 percent load tests or annual non-destructive tests and examinations to be perfonned.
12b. Remarks j
These special lifting devices are used during plant refueling which is approximately once per year. During plant operation these special lifting devices are inaccessable since they are pennanently installed and/or remain in the containment.
They cannot be removed from the containment unless they are disas-sembled and no known pumoses exist for disassembly. Load testing to 150 percent of the total weight before each use would require special fixtures and is impractical to perfona.
Crane ca'pacity could also be limiting.
It is suggested that a j
check (visual) of critical welds and parts be conducted at initial lift when possible prior to moving to full lift and
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movement for all three devi_ces.
Preferagly, since these devices have.been in use at least once per year for over ten years, that a visual check during initial lift would be acceptable.
Further note that with the Ise of the load cell
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for the internals lift rig, all lifting and lowering is monitored at all times.
2.
SUittARY The requirements for periodic checking and functional load testing f:
appear to be the ANSI N14.6 requirements that are most difficult to demonstrate compliance.
It is almost impractical to perfona t'he 150 i:
l-pen ent load test prior to each use.
It is suggested that the proposal to the NRC include a 100 pen:ent load test, similar to the original check-out test to be perfonaed with a minimum of nondestructive testing, (visual-only) in the critical parts and welds.
4 5888B:l /120682 B-6
TABLE B-1 BILL OF MATERIALS FOR THE NON-DESIGNED ITEMS OF THE REACTOR COOLANT PUMP MOTOR LIFT SLING Description Rated (6)
Load Value i
No. Il )
Item Orawing(2)
Catalog (7)
(Pounds) 3 "U" Bolts 7/8" "U" Bolts +
(5) "U" Bolts - G-450 Cable Saddle 1-1/2" Dia. Wire 7/8" Dia. "U" Bolt Wire Rope Clips 5
Alloy Oblong 2-3/4" x 9" x 18" (3) 2-3/4" x 9" x 16" 211,500 Link 6
Sling 1-1/2" x 11'4"
(4) 81,000(2)
Assembly (Total inc. turn-1-1/2" x 11'4" 6 x 37 buckle, shackle, Improved Plowsteel etc. ) 6 x 37 I.W.R.C. 3 Bridle improved plow Sling with Mechanical I.W.R.C. 3 Bridle Connections Sling (7'6" sling length only incl.
eye) 7 Shackle Anchor Safety (5) 2" Size 70,000 Shackle G-213 or S-213 l
8 Turnbuckle 2" x 6" Jaw & Eye (5) G-227 Jaw & Eye 37,000 j
Turnbuckle Turnbuckle 2" Dia. thd., 24" i
l take-up Class 8 i
9 Sling Hook TAYC0 A-73
'(3) Sling Hook 38,750 No. A-73 1" Dia.
Chain with 2-1/2" Dia. Eye NOTES:
(1)
See figure A-3 for identification of item numbers (2) Description is from Westinghdus'e drdwing AED SK 618J644 TXK SUB 5 l
l 5888B:1/120682 B-7 l
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i (3) Taylor Chain Co., Inc., Alloy Steel Chain Assemblies, Attachments, I
Revised 4/80 (4) Pennsylvania Sling Co.
l (5) Crosby Group, 950 General Catalog, June 1981.
1 I
(6) Rated load value: The maximum recommended load that should be exerted on the item.
The following terms are also used for the tena Rated Load:
"SWL", " Safe Working Load", " Working Load Limit", and the
" Resultant Safe Working Load".
All rated load values are for in-line pull with respect to the centerline of the item.
Information is from catalogs identified in (3), (4), (5).
(7) Ordaring Information Sling assembly per Westinghouse Drawing AE0 SK 618J644 TXK, SUB 5 composed of the items in table B-1 including the following requirements:
a.
The safe working load of this sling assembly is 81,000 lb. and a safety factor of 5:l".
b.
Perform lift test at assembly of 121,500 pounds (61 tons),
c.
The master link is to be magnetic particle inspected after load test to the requirements of ASME Boiler & Pressure Vessel Code.
Section V Article 7.
Acceptance standards are to ba to ASME d&PV Code Section III Subsection NF 5341.
Radiograph. inspection may be substituted for magnetic particle inspection to ASME B&PV Code Section V, Article 2 with acceptance standard to ASME B&PV Code 4
Subsection NF 5320.
d.
A certification is required for load testing, non-destructive testing and material used in this assembly.
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58888:l/120682 B-8
WESTINGHOUSE CLASS 3 ATTACHMENT B to WCAP-10168 STRESS REPORT REACTOR VESSEL HEAD LIFT RIG REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL, LOAD CELL LINKAGE AND REACTOR COOLANT PUMP MOTOR LIFT SLING FOR FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND. 4 December, 1982 H. H. Sandner, P.E.
Approved:
=,
4-R. J. Leduc, P. E., Manager Component Handling Equipment l
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5887B:1/122882 f
ABSTRACT A stress analysis of the Turkey Point-Units 3 and 4 reactor vessel head and internal lift rigs, load cell, load cell linkage and reactor coolant pump motor lift sling was perfonned to detenaine the acceptability of these devices to meet the design requirements of ANSI N14.6.
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ACKNOWLEDGMENT
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Acknowledgment is hereby made to the following individuals who contrib-uted to the structural analysis presented in this report.
I J. M. Matusz, P.E.
J. W. Richard, P.E.
M. F. Hankinson, P.E.
F. C. Peduzzi J. Urban i
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i-I 5887B il/120682 jy
TABLE OF CONTENTS Section Title Page ABSTRACT iii 1
INTRODUCTION 1-1
1.1 Background
1-1 2
COMPONENT DESCRIPTION 2-1 2.1 Reactor Vessel Head Lift Rig 2-1 2.2 Reactor Vessel Internals Lift Rig 2-1 l
2.3 Load Cell and Load Cell Linkage 2-2 2.4 Reactor Coolant Pump Motor Lift Sling 2-2 3
DESIGN BASIS 3-1 3.1 Design Criteria 3-1 3.2 Design Weights 3-2 E
4 MATERIALS 4-1 4.1 Material Description 4 5
SUMMARY
OF RESULTS 5-1 5.1 Discussion of Results 5-1 5.2 Conclusion 5-6 AP?ENDIX A DETAILED STRESS ANALYSIS - REACTOR VESSEL HEAD LIFT RIG A-1 APPENDIX B DETAILED STRESS ANALYSIS - REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LINKAGE B-1 APPENDIX C DETAILED STRESS ANALYSIS - REACTOR COOLANT PUMP MOTOR. LIFT SLING C-1 y
5887B:1/010433
LIST OF ILLUSTRATIONS l
Figure Title Page 5-1 Reactor Vessel Head Lifting Rig 5-11 5-2 Reactor Vessel Internals Lifting Rig 5-20 5-3 Reactor Coolant Pump Motor Lift Sling 5-22 4
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i vii 5887B:1/010683
I LTST OF TABLES
. Table Title Page 4-1 Reactor Vessel Head Lift Rig Naterial Properties 4-2 4-2 Reactor Vessel Internals Lift Rig, Load Cell and Load Cell Linkage 14aterial Properties 4-3 4-3 Reactor Coolant Pump liotor Lift Sling 14aterial Properties 4-5 l
5-1 Suisnary of Results - Reactor Vessel Head Lift Rig 5-7 5-2 Sumary if Results - Rdactor Ve.ssel Internals Lift Rig, load Cell and Load Cell Linkage 4
5-12 5-3 Sunnary of Results - Reactor Coolant Pump liotor Lift Sling 5-21
]
5-4 Comparison of Design Loads and Rated
[
Load Values of the Non-Designed Items of the R.C. Pump liotor Lift Sling 5-23 l
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58878:l/010483 ix
!c.
i REFERENCES 1.
George, H., Control of Heavy Loads at Nuclear Power Plants Resolution of Generic Technical Activity A-36, HUREG 0612, July, 1980.
2.
ANSI N14.6-1978, "Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500kg) or More for Nuclear Material,"
American National Standards Institute, New York,1978.
3.
ANSI B-30.9-1971, " Slings," American National Standards Institute, New York, 1971.
4.
Westinghouse Drawing 685J249 - Head Lifting Rig General Assembly 5.
Westinghouse Drawing 685J291, Turkey Point Units 3 and 4 - Internals Lifting Rig General Assembly l
g 6.
Westinghouse Drawing AED-SK-618J644TXK - Handling Sling Spreader for Motor SV-4M-Al Pump General Assembly 4
7.
Lin, C.
W., " Approximate Evaluation of Dynamic Load Factors for Certain Types of Load Factors for Certain Types of Loading," ASME l
Paper 70-WA/NE-2.
i 8.
Biggs, J. M., Introduction to Structural Dynamics, McGraw-Hill, New l
York, 1964.
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5887B:1/122882 xi l
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9.
Gwinn, Jr., J. T., "Stop Over-Designing for Impact Loads," Machine Design, 33, pp.105-113 (1961).
1
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- 10. ASME Boiler and Pressum Yessel Code,Section III, Division 1,
" Nuclear Power Plant Components'," American Society of Mechanical Engineers, New York, 1980.
l l
- 11. Manual of Steel Construction, Seventh Edition, American Institute of Steel Construction, New York,1973,
- 12. Timoshenko, S., Strength of Materials, Part 1, Elementary Theory and Problems, D. Van Nostrand Company, Inc. Third Edition April 1955, pp. 263-279.
- 13. Fastening and Joining, 4th Edition, Machine Design,1967.
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58878:1/120'682 xii
SECTION 1 INTRODUCTION The Nuclear Regulatory Coranission (NRC) issued NUREG 0612 " Control of Heavy Load at Nuclear Power Plants"U3 in 1980 to address the control of heavy loads to prevent and mitigate the consequences of postulated accidental load drops. HUREG 0612 iinposes various training, design, inspection and procedural requirements for assuring safe and reliable operation for the handling of heavy loads.
In the containment building, NUREG 0612 requires special lifting devices to meet the requirements of ANSI N14.6-1978 "American National Standard for Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds or More for Nuclear Materials".[2] In general, ANSI N14.6 contains detailed requirements for the design, fabrication, testing, taaintenance and quality assurance
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of special lifting devices.
In addition, ANSI NI4.6 requires that when wire rope or chain is used in the design of a lifting device, the wire rope or chain shall be in conformance with ANSI B30.9-1971 "American NationalStandardSafetyStandardforSlings".k33 The NRC has requested. operating plants to demonstrate compliance with these requirements.
o This report contains.the stress analysis perforiaed on the Turkey Point reactor vessel headlift rig, reactor vessel internals lift rig, load cell, load cell linkage and reactor coolant pump motor lift sling to determine the acceptability of these devices to meet these requirements.
1.1 BACKGROUND
i The reactor vessel head lift rig, the internals lifting rig, load cell, I
l load cell linkage, and reactor coolant pump motor lift sling were I
designed and built for the Turkey Point Units 3 and 4, circa 1967-68.
The actual design criteria is unknown for the lifting devices.
It appears that for the head lift rig, internals lift rig, load cell, cell linkage and the reactor coolant puinp motor lift that in inost cases the l
l 5837B:1/122887 1-1
design criteria used was that the resulting stress in the load members, when subjected to the total combined lifting weight, does not exceed one fifth (1/5) of the ultimate strength of the material. These items were not classified as nuclear safety components and thus requirements for fonnal documentation of design requirements and stress reports were not applicable.
Thus, stress reports and design specifications were not formally documented. Westinghouse defined the design, fabrication and quality assurance requirements on detailed manufacturing drawings and purchase order documents. Westinghouse also issued field assembly and operating instructions, where applicable.
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5887B:1/122882 1-2
r SECTIOi 2 COMPONENT DESCRIPTION 2.1 REACTOR VESSEL HEAD LIFT RIG E43 The reactor vessel head lift rig is a three legged carbon steel structure, approximately 35' feet high and 14 feet in diameter, weighing approximately 25,000 pounds.
It is used to handle the assembled reactor vessel head.
The thme vertical legs and control rod drive mechanism (CRDH) platfona asserably are pennanently attached to the mactor vessel head lifting lugs.
The tripod sling assembly is attached to the thme vertical legs and is used when installing and removing the reactor vessel head.
During plant operations, the sling assembly is removed and the three vertical legs and platfonn assembly remain attached to the reactor vessel head.
2.2 REACTOR VESSEL INTERNALS LIFT rig b
The reactor vessel internals lift rig is a threk-legged carbon and stainless steel structure, approximately 29 feet high and 12 feet in diameter weighing approximately 13,000 pounds.
It is used to handle the upper and lower reactor vessel. internals packages.
It is attached to the main crane hook for all lifting, lowering and traversing opera-tions.
A load cell linkage is connected between the main crane hook and the rig to monitor loads during all operations.
When not in use, the rig is stored on the upper internals storage stand.
The rig attaches to the internals packages by means of three engaging screws which are screwed into tapped holes in the internals flanges.
These screws are manually operated from the spreader assembly using the internal tools.
The screws are nonaally spring retracted upward and are i
depressed to engage the tapped holes.
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58878:l/120682 2-1
i 2.3 LOAD CELL AND LOAD CELL LINKAGE i
The load cell is used to monitor the load during lifting and lowering the reactor vessel internals to ensure no excessive loadings are occur-ri ng.
It is installed between the load cell linkage and the lifting device.
The load cell is a s, train gage (tension) type, rated at 300,000 pounds, built by W. C. Dillon and Co. The load cell linkage is an assem-bly of pins, plates and bolts which connect the polar crane main hook to the load cell.
2.4 REACTOR COOLANT PUMP MOTOR LIFT SLING b
The reactor coolant pump motor lift sling consists of a six (5) foot triangular carbon steel spreader assembly weighing approximately one thousand (1000) pounds.
It has wire rope slings, shackles and turn-buckles attached which form a three point lift assembly.
It is used to handle the reactor coolant pump uotor.
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58878:l/120682 2-2 l
SECTION 3 DESIGr4 BASIS 3.1 DESIGN CRITERIA NUREG 0612, paragraph 5.1.1(4) states that special lifting devices should satisfy the guidelines of ANSI N14.6.
Further, NUREG 0612, 5.1.1(4) states:
"In addition, the stress design factor stated in Section 3.2.1.1 of ANSI N14.6 should be based on the combined maximum static and dynamic loads that could be imparted on the handling device based on characteristics of the crane which will be used.
This is in lieu of the guideline in Section 3.2.1.1 of ANSI N14.6 which bases the stress design factor on only the weight (static load) of the load and of the intervening components of the special handling device".
It can be inferred from this paragraph that the stress design factors specified in Section 3.2.1.1 of ANSI N14.6 (3 and 5) am not all inclu-si ve. Also, it can be inferred that the specified Ar4SI tJ14.6 stmss design factors should be increased 69 an amount ba' sed on the crane dy-namic charact' eristics.
The dynamic characteristics of the crane would
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be based on the main hook and associated wire ropes holding the hook.
1 Most main containment cranes use sixteen (16) or more wire ropes to handle the load.
Should'the crane hook suddenly stop during the lifting or lowering of a load, a shock load could be transmitted to the con-l nected device.
Because of the elasticity of the sixteen or more wire ropes, the dynamic factor for a typical containment crane is not much larger than 1.0.
The maximum design factor that is recomended by most design texts is a factor of 2 for loads that are suddenly applied.
The stress design factors required in Section 3.2.1.1 of ANSI N14.6 are:
l 3 (weight) < Yield Strength i
5 (weight) < Ultimate Strength l
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i, The factor of 3 specified, certainly, includes consideration of suddenly applied loads for cases where the dynamic impact factor may be as high as 2.0.
Thus, we feel that the use of the design criteria in At4SI N14.6 satisfies the NUREG requirement.
To provide flexibility on stress design factor, the summary tables list the stresses with stress design factors of 1, 3 and 5.
Thus, any stress design factor may be easily applied to satisy any concerns.
{
3.2 DESIGN WEIGHTS 1
The following design weights were used in the analysis of the lifting devices:
i 3.2.1 Reactor Vessel Head Lift Rig (A) Design Weight for Lower Clevis and Pin (Items 14 and 15) is 263,000 pounds
[
j' (B) Design Weight for rest of Lift Rig is 278,000 pounds 3.2.2 Reactor Vessel Inte.rnals Lift Rig, load Cell, and Load Cell Linkage The design weight is 260,000 pounds which is the total weight of the lif ting device and the lower internals.
3.2.3 Reactor Coolant Pump Motor Lift Sling i
The design weight is 81,000 pounds which is larger than the total weight of the lif ting device and the reactor coolant pump notor.
It is the safe working load identified on the assembly drawing.
5887B:1/120682 3-2
SECTION 4 l%TERIALS i'
4.1 t%TERIAL DESCRIPTION The materials and mat,erial properties for the reactor vessel head lift l
rig, the reactor vessel internals lift rig, load cell, load cell linkage and reactor coolant pump motor lift sling are listed in Tables 4-1, 4-2 and 4-3.
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TABLE 4-1 REACTOR COOLANT HEAD LIFT RIG 1%TERIAL AND IMTERIAL PROPERTIES Yield Ultimate Strength Strength Item (a)
Description Materials Sy (ksi)
Sult (ksi) 1 3 1/2" Diameter Pin ASTH A434 110 140 7
4" Dia. Bottom Clevis Pin Class BD 110 140 10 4" Dia. Upper Clevis Pin 105 135 13 7 1/2" Dia. Pin 100 130 14 8" Dia. Pin 100 130 2,5,15 Side Plate ASTM A515 or 38 70 Support Lug GR70 3
Leg ASTM A36 36 58 4
Ring Girder ASTM A285 30 55 GR. C s
6,9 Upper. Clevis ASTM A237 50 80 Clevis CL A 8
Arm ASTM A306 35 70 Gr. 70 11, 12 Clevis Plate Link ASTM A 105 36 70 Link Lug CL 2 (a)See figure 5-1 58878:1/0104'83 4-2
i TASLE 4-2 REACTOR VESSEL INTERNALS LIFT RIG MATERIAL AND MATERIAL PROPERTIES
'[
Yield.
Uitimate Strength Strength Item (a)
Description Materials Sy (ksi)
Sult (ksi) 1 Hook Pin ASTM A434 100 130 CL BD 3
Upper Adaptor Pin ASTM A434 105 135 CL BD 7
Removable Pin 11 Upper Sling Leg Pin ASTM A 276 30 75 Type 304 Center Ground Cond. A 13 Lower Sling Leg Pin
[
2 Side Plate
' ASTM A-515 38 70 Gr. 70 or k ASTM A-516 38 70 Gr. 70 8-Top Lugs 10 Side Leg 12 Sling Leg 14,B,C,D Spreader Assembly i
4 Upper Adaptor ASTM A-540 120 135 l
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Gr. B-24 j
6 Lower Adaptor 5
Tension Cell 17-4 pH H1100 115 140 (a)See figure 5-2 5887B:1/122882 4-3 l
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TABLE 4-2 (Cont)
REACTOR VESSEL INTERNALS LIFT RIG MATERIAL AND MATERIAL PROPErtTIES l
Yield Ultimate Strength Strength Item (a)
Description Materials Sy (ksi)
Sult (ksi) 9 Block SA-105 CL 1 or 2 3G 70 or SA-266 CL 1 or 2 30 60 or SA-508 CL 1 or 2 35 70 14A Spacer Block 15 NUT ASTM A-276 38 82 Type 304 HR+PXLD, Cond. A 18 Leg Leveling Sleeve 20 Support Ring Leveling Sleeve N
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l 22 Guide Sleever 16 Leg Adaptor ASTM A276 43.9 86.5 Type 304 HR+FXLD, Cond. A 23 Engaging Screen ASTM A276 3G.8 80.9 HR+PXLD, Cond. A 19 Coupling ASTM A312, 30 75 Type 304 17 Leg Outer Tube ASTM A312 38.0 83.4 Type 304 Seamless, Cold Fanish and Heat i
Treat i
l 21 Support Ring Outer Tube
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(a)See figure 5-2 I
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TABLE 4-3 f
REACTOR COOLANT PUMP HOTOR LIFT SLING MATERIALS AND
-l iMTERIAL PROPERTIES Yield Ultimate Strength Strength Itera(a)
Description Materials Sy (ksi)
Sult'(ksi) 1 Spreader (pipe)
ASTM A106 35 60 Grade B o
2 Side plates-ASTM 212 36 58 Grade A (a)See figure 5-3 i
5387B:1/122882 4-5
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SECTION 5
SUMMARY
OF RESULTS Tables 5-1, 5-2, and 5-3 summarize the stresses on each of the parts which make up the reactor vessel head and internals lift rig, load cell, load cell linkage and reactor coolant pump motor lift sling, respectively. All of the tensile and shear stresses, with the exception of the tensile stress at the minimum section of the internals lifting rig engaging screw, item (23), meet the design criteria of section 3.2.1.1 of ANSI N14.6, requiring application of stress design factors of three and five with the accompanying allowable stress limits of yield l
and ultimate strength, respectively. Application of the ANSI N14.6 criteria to pins subject to bending, structural members subject to l
buckling and bending loads, and various parts subject to bearing loads result in some stresses exceeding this criteria.
However, when using more appropriate criteria, the resulting stresses are acceptable.
i 5.1 DISCUSSION OF RESULTS 1
5.1.1 App 1'ication of ANSI N14.6 Criteria 4
1 The design criteria of section 3.2.1.1 of ANSI N14.6, requiring applica-tion of stress design factors of three and five with the accompanying allowable stresses, are to be used for evaluating load bearing members of a special lifting device when subjected to loading conditions resulting in shear or tensile stresses.
Application of these design l
load factors to other loading conditions is not addressed in ANSI l
N14. 6.
However, these two stress design factors have been used to f
determine the stresses of the load carrying members when subject to other loading conditions, viz. bearing, bending, buckling.
This is an extremely conservative approach and in some cases the resulting stresses exceed the accompanying allowable stress ifmit.
In the internals lift rig engaging screw (item 23) the tensile stress slightly exceeds the criteria that.three times the calculated stress
(
must be less than the yield stress. However, the conservative criteria l
l 5887B:1/122882 5-1 L
e that five times the calculated stress must be less than the ultimate is met and thus the engaging screw is considered acceptable.
For items 11,13,15, 22 and 23 of the internals lifting rig, the bearing stress exceed the criteria that three times the calculated I
stress must be less than the yield stress. However, all the bearing I
stresses meet the conservative criteria that five times the calculated stress must be less than the ultimate stress and thus the parts are considered acceptable for bearing.
The bending stresses in the internals lifting rig pins (items 3, 7,11 l
and 13) were calculated using the conservative approach shown in the Machine Design Fastening and Joining Issue.
This approach, coupled with the use of the ANSI 14.6 stress factor for this condition, results in 3
bending stresses' exceeding the allowables. However, the acceptance criterion for pin design is shear stresses and the results of all shear stress calculations are below acceptable limits., The bending stress calculations are included for reference.
{
The bending stress in the internals lifting rig s, pacer blocks (item..
14-A) does not meet the criteria of section 3.2.I.1.
However, this is a -
local fiber stress.
Even if the fiber stress reached the yield stress, and it doesn't, the rest of the cross-section could assume the additional load. This localized stress can be considered under section 3.2.1.2 which states that the stress design factors of 3.2.1.1 are not intended to apply to situations where high load stresses are relieved by slight yielding. The shear stress in the block is extremely low and i
well within the section 3.2.1.1 criteria.
l Structural elements loaded in compression and bending are analyzed by the empirical equations of the ASME and AISC rules.
Buckling stresses are expressed as the ratios of actual stresses to the allowable stresses with the acceptable ratio being < 1.0.
These equations do not deter-mine the limiting stresses of members in buckling but indicate whether or not the calculated stress is or is not within the allowable values.
Instead, the ultimate load carrying capability of the member is the 58878:1/122882 5-2
D 2]
determining factor in the structural member's acceptability.
Timoshenko notes that the ultimate load for short struts is equal to the material yield point. Calculation of the ultimate load results in this load being 1.3 times the nominal design load and thus, these members are considered acceptable.
5.1.2 Pin Bending Several of the internal lifting rig pins do not meet the ANSI N14.6 criteria (3 and 5) when analyzed for bending stresses.
In calculating the bending stresses in pins, it is assumed that loads from the outside lugs are linerally distributed and from the inside eye are uniformly distributed along the pin.
Further, the assumption is made that span to diameter ratios are large enough such that the assumptions inherent to simple beam theory are valid (Neither condition is met, however, by the actual joint geometry).
Pin deflections and local yielding of the pin, lugs, and eye cause the loads to be non-uniform and their' centroids to ' shift towards the inter-faces between the lugs and eye, i.e., the shear planes in the pins.
This concentration of load near the shear planes reduces the effective '--
j bending arms at which loads are applied thereby reducing the bending moment.
The calculated bending stresses are thus over estimated and are tabu-lated for reference.
Shear stresses in the pins are the governing para-meter for pin strength. Using shear stresses as the criteria for pin design results in all pins meeting three times the calculated stress being less than the yield stress and the ' ANSI criteria of 5 times the I
calculated stress being less than the ultimate stress.
Thus all the l
above pins are considered acceptable.
5.1. 3 Structures Loaded in Compression and Bending The spreader assemblies of the reactor. vessel internals lift rig and the reactor coolant pump motor lift sling do not meet all the ANSI N14.6 criteria (3W and SW) when analyzed for combined axial compression and 5887B:1/122882 5-3
F l
bending (buckling) or bendirg loadings.
Structures loaded in combined compression and bending are analyzed by the empirical equations of the D0] ASME Boiler and Pressure Vessel Code Section III, Appendix XVII.
(Sace as the AISC UI) Part 5 rules).
Ratios less than 1.0 indicate the calculated stress is within the allowable values; greater than 1.0,' the stress is greater than the allowables.
When comparing the spreader arm to the above criteria, the acceptable i
ratio < l.0 is not satisfied.
However, these empirical equations do not identify the maximum stress for this loading condition.
When the ratio is >l.0, these equations identify an unacceptable design l'
condition.
If we were designing a new structure, the material and member size would be changed to ensure these ratios would be satisfied for all loading conditions.
However, these calculations are being applied to an existing structure and since these conditions are not satisfied then the ultimate load carrying capability !nust be determined.
1 The column under consideration is relatively shorh (
= 44.12).
D2] states that experiments show that short columns buckle Timoshenko when the compressive strength reaches the material yield' point.
(The..
horizontal line on the figure below).
~
I i
YlELD POINT EULER CURVE 6
l E = 30 X 10 psi I
8 i
E I
N l.
d I
e I-l 2
l O
I I
44.12 I
1 2/r
~80 COLUMN BUCKLING 5887B:1/122882 5-4
Therefore the total stress a=f+f=DirectStress+BendingStress must be less than or equal to the material yield stress.
Since the column is loaded eccentrically (i.e., M is proportional to P, so the two could be equivalently replaced with a load P displaced from the column centerline by a distance e) as the column bends the effective lever arm of the load increases. For this condition i
P Pe P
n.
o = g + 7-secant pg,y For this particular column (internals lift rig spreader) hy the expression secant is essentially 1.0 for even 5 time'5 the nominal ' load and the equation reverts to 4
i P,
Pe P
M a=A,T,K,7 For the case of the internals lift rig spreader; f=25,135 psi h=3290 psi and Then the total stress is:
total = 3290 + 25,135 = 28,425 psi' which is less than the material yield strength (Sy) 58878:1/120682 5-5
1 i
Then to find the ultimate column load, let o
- b
= 38,000 psi max y
]
Then the maximum column load is the ratio of j
= 38,000 = 1.337 max /ctotal 28,425 o
Thus the ultimate column load is 1.3 times the nominal value, t
The internals lift rig spreader members are considered acceptable for this condition of combined stresses for axial compression and bending.
Similarly, the ultimate load for the reactor coolant pump motor lift sling is 3.7 times the nominal value and also considered acceptable.
5.1. 4 Rated Load Values of the Reactor Coolant Pump Motor Lift Sling Since most of the components that comprise the reactor coolant pump
~
motor lift sling are non-designed components appl { cation of the criteria of section 3.2.1.1 of ANSI N14.6 to these components arc not appropri-ate. Therefore, Table 5-4 has been prepared from catalog information and list the various load conditions. Noting thah the safety factors
~
are based on the ratio of the ultimate strength of the material to the rated load value, the sling is acceptable for five times the design load.
5.2 CONCLUSION
Application of the ANSI N14.6 criteria of (3 and 5) to these special lifting devices results in acceptable stress limits for tensile and shear stresses with the exception of the internals lifting rig engaging screw. Application of this criteria to all structural members subject to other types of loadings tend to result in oversimplified conservatism and with some stresses exceeding the accompanying allowable limits.
However, when using the more appropriate criteria for those cases not i
addressed by the ANSI N14.6 criteria the stresses are within the appropriate allowable limits.
i i
5887B:1/120682 5-6
TABLE 5-1
SUMMARY
OF RESULTS REACTOR VESSEL HEAD LIFT RIG Calculated Stresses (ksi)
Material Aliowable Item (a)
Part Name value (ksil No.
And Material Designation Wtb) 3W SW S tc)
Sgto; y
1 3-1/2" dia. pin Shear 4.8 14.4 24.0 110 140 ASTM A434 Bearing on Head Clevis 8.8 26.4 44.0 Class BD Bearing on Clevis Plate 8.3 24.9 41.5 Bending 17.0 51.0 85.0 2
' Clevis Plate Shear Tear-Out at Pin Hole i
4.1 12.3 20.5 38 70
' ASTM A515 Bearing on Pin 8.3 24.9 41.5 Grade 70 Q&T Tension at Pin Hole 4.1 12.3 20.5 5
3 Leg Fillet Weld on Clevis weld allowable = 18(e)
ASTM A36 Plate to Leg - Shear 4.0 12.0 20.0 7,
Tension 7.8 23.4 39.0 36 58 4
Ring Girder Total Shear 2.4 7.2 12.0 30 55 ASTM A285 GRC Combined Tensile 3.5 10.5 17.5 Firebox Weld of Ring Girder to Support Lug 2.4 7.2 12.0 (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d) S it is the ultimate strength of the material (ks'i)
S$ress limit for fillet weld from ASME Boiler and Pressure Vessel Code,Section III Division 1 - Subsection NF (e) 1980 Edition, Table NF-3292 1-1, page 43 5887B:1/010483
- - ~ _ _
TABLE 5-1 (cont).
SUMMARY
OF RESULTS REACTGR VESSEL HEAD LIFT RIG Calculated Stresses (ksi)
Material Allowable Item (a)
Part Name Value
.. (ksi)
No.
And Material Designation WlDJ 3W SW S tcJ Sult' #
y 5
Support Lug Tension at Pin Hole 5.8 17.4' 29.0 38 70
. ASTM A515 GR70 Shear-Tear-Out at Pin Hole 5.0 15.0 25.0 Normalized Bearing on Pin 7.5 22.5 37.5 and Tempered 6
Clevis Thread Shear 3.4 10.2 17.0 50 80 ASTM A237 Bearing on Pin 6.7 20.1 33.5 Class A Shear Tear-Out at Pin llole 4.3 12.9 21.5 Tension at Pin Hole 4.3 12.9 21.5 Tension at Thd. Relief 2.1 6.3 10.5 u,
7 4" Dia Pin.
-Shear 4.1 12.3 20.5 10 5 135 ASTM A434 Class BD Bearing on Support Lug 7.5 22.5 37.5 Min. Tempering Bearing on Lower Clevis 6.7 20.1 33.5 Temp. = 1100*F Bending 14.3 42.9 71.5
.r.
8 Arm Thread Shear 3.4 10.2 17.0 35 70 ASTM A306 Thread Tension 9.2 27.6 46.0 GR 70 (a) See figure 5-1 for location of item number and 'section (b) W is the total static weight of the component and the lif ting device (c) S is the yield strength of the material (ksi) y (d) Sult is the ultimate strength of the material (ksi)-
t' 5887B:1/010483
-m
TABLE 5-1 (cont)
SUMMARY
OF RESULTS REACTOR VESSEL HEAD LIFT RIG Calculated Stresses (ksi)
Material A.'lowable Item (a)
Part Name Value
_. (ksi)
No.
And Material Designation WlDJ 3W SW S tcJ
$ j (c) y 9
Upper Clevis Thread Shear 3.4 10.2 17.0 50 80 Bearing on Pin 6.7 20.1 33.5 Shear Tear-Out at Pin Hole 4.3 12.9 21.5 Tension at Pin Hole 4.3 12.9 21.5 Tension at Thd. Relief 2.1 6.3 10.5 10
.4" Dia Upper Clevis Shear 4.1 12.3 20.5 105 135 Pin Bearing on Link Lug 7.3 21.9 36.5 ASTM A434 Class BD Bearing on Upper Clevis 6.7 20.1 33.5 Min. Tempering Bending 14.1 42.3 70.5
' Temp. = 1100*F u,
e 11 Link Bearing on liook Pin
.r.
, 4.3 12.9 21.5 36 70 a
A105 Tension at Pin ilole
~4.0 12.0 20.0 Class 2 Shear Tear-Out at Pin iloie 4.0 12.0 20.0 Tension at Cylindrical Section 5.3 15.9 26.5 (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S is the yield strength of the material (ksi) y (d) Sult is the ultimate strength of the material (ksi)
I' 5887B':l/010483
TABLE 5-1 (cont)
SlNMARY OF RESULTS REACTOR VESSEL HEAD LIFT RIG Calculated Stresses (ksi)
Material Allowable Item (a)
Part Name
'la l ue (ksi)
No.
And Material Designation WlDI 3W SW S tc)
SultW#
y 12 Link Lug Tension at Pin Hole 4.9 14.7 24.5 36 70 A105 Shear Tear-Out at Pin Hole 4.9 14.7 24.5 Class 2 Bearing at Pin Hole 7.3 21.9 36.5 Shear at Root of Lug 1.6 4.8 8.0 Combined Tension at Lug Root 3.7 11.1 18.5 13 7-1/2" Dia. Pin Shear 3.2 9.6 15.0 100 130 ASTM A434 Bearing on Hook 4.6 13.8 23.0 Class BD Bearing on Side Plate 6.2 18.6 31.0 Bending 10.7 32.1 53.5 T
i G
14 8" Dia. Pin Shear 2.8 8.4 14.0 100 130
' ASTM A434 Bearing on Link 4.3 12.9 21.5 Class BD Bearing on Side Plate 5.8 17.4 29.0 Bending 8.8 26.4 44.0
.r.
15 Side Plate Bearing at 7-1/2" Hole 6.2 18.6 31.0 90 100 ASTM A514 Tension at 8" Hole 5.5 16.5 27.5 Shear Tear-Out at 8" Hole 5.5 16.5 27.5 (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S is the yield strength of the material (ksi) y (d) Sult is the ultimate strength of the material (ksi) i' 5337B:1/010483
@ a~ OfAuereR Puu Q 7-'!2~ OtAuETeR een @
SIDE PLATE h h
U E CLE
\\
@ CLEVISPIN 4" DI AMETER UPPE W
ARMh CLEVish g
j 4" DIAMETER PIN h 1
i o
\\
h SUPPORT LUG
(\\
N y
RING GIRDER h
/
f $t
- IW i
s LEGh CLEVIS PLATE h 1/2" DI AMETER PIN h
)
4 si
\\
\\
Se
$S Figure 5-1.
Reactor Vessel Head Lifting Rig 58878:l/120682 5-11
TABLE 5-2
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)
Material Allowable Item (a)
Part Name Value
.. (ksi)
No.
And Material Designation WlDJ 3W SW S tc1 Sult
- I y
1 1
(Hook) Pin Shear 3.0 9.0 15.0 100 130 ASTM A434 Bearing on Hook 4.4 13.2 22.0 Class BD Bearing on Side Plates 10.1 30.3 50.5 AISI 4340 Bending 9.3 27.9 46.5 Hot Rolled
'and Quenched &
Tempered 2
Side Plate Tension at 7.515 Dia. Hole 10.1 30.3 50.5 ASTM A515 ASTM A515 GR 70 Bearing at 7.515 Dia. Hole 10.1 30.3 50.5 38 70 T
or Shear Tear-out at 7.515 10.1 30.3 50.5 g
. ASTM A516 GR 70 Dia. Hole ASTM A516
.Q&T Tension at 4.385 Dia. Hole
'9.2 27.6 46.0 38 70 Shear Tear-out at 4.385 9.2 27.6 46,0 Dia. Hole Bearing at 4.385 Dia. Hole 10.6 31.8 53.0 3
(Upper Adaptor)
Shear 8.8 26.4 44.0 105 135 Pin Bearing on (Upper) Adapter
- 946 28.8 48.0 ASTM A434, Class Bearing on Side Plate 10.6 31.8 53.0 BD, AISI 4340 Bending 42.4 127.2 212.0 Hot Rolled and Q&T (a) See figure 5-2 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S is the yield strength ~of the material (ksi) y (d) Suit is the ultimate strength of the material (ksi) s' 5887B:1/010483
TABLE 5-2 (cont)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)
Material Allowable Item (a)
Part Name Value
.. (kri)
No.
And Material Designation Wtbj 3W SW S tcJ Sult y
4 (Upper) Adaptor Tension at 4.387 Dia. Hole 10.6 31.8 53.0 12 0 135 ASTM AS40 Bearing at 4.387 Dia. Hole 9.5 28.5 47.5 Grade B-24 Tension at Thread Relief 7.0 21.0 35.0 Thread Shear 11.2 33.6 56.0 Shear Tear-out at 4.387 9.1 27.3 45.5 Dia. Hole 5
Tension Cell Tension at Threads 19.4 58.2 97.0 115 140 y
17-4 pH ss H-1100*
Thread Shear 11.2 33.6 56.0 C
6 (Lower) Adaptor Tension at 4.387 Dia. Hole 10.6 31.8 53.0 120 135 Bearing at 4.387 Dia. Hole 9.5 28.5 47.5 Tension at Thread Relief 7.0 21.0 35.0 Thread Shear O
' *1 1.'2 33.6 56.0 Shear Tear-out at 4.387 9.1 27.3 45.5 Dia. Hole 7
(Removable) Pin Shear 8.8 26.4 44.0 105 135 ASTM A434 Class Bearing on Lower Adaptor 9.6 28.8 48.0 BD, AISI 4340, Bearing on Top Lugs 10.0 30.0 50.0 Hot Rolled, Q&T Bending 42.4 127.2 212.0 (a) See figure 5-2 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S is the yield strength of the material (ksi) y (d) Sult is the ultimate strength of the material (ksi) 5837B:l/010483 a
TABLE 5-2 (cont)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)
Material Allowable Item (a)
Part Name Value (ksi)
No.
And Material Designation Wlb) 3W SW S (c)
Sul tIdl y
8 Top Lugs Bearing on Pin 10.0 30.0 50.0 ASTM A515 ASTM A515 GR 70 Tension at Pin Hole 9.8 29.4 49.0 38 70 or ASMT A516 GR 70 Shear Tear-out at Pin Hole 9.8 29.4 49.0 ASTM A516 Q&T Tension at Weld 4.9 14.7 24.5 38 70 9
Block Tension in Block 1.5 4.5 7.5 SA 105 u,
SA 105 CL 1 or 2 36 70 or ASTM A266 CL 1 ASTM A266 CL1 30 60 CL 2 35 70 or SA 508 CL 1 or 2 SA 508 CL 2 35 70 CL 2 50 80 10 Side Lug Tension at Pin Hole 5.6 16.8 28.0 ASTM A515 ASTM A515 GR 70 Shear Tear-out at Pin Hole 5.6 16.8 28.0 38 70 or Bearing on Pin 9.1 27.3 45.5 ASTM A516 GR 70 Shear at Lug Root Weld 1.9 5.7 9.5 ASTM A516 Q&T CL 2 Combined Bending and Tension 5.2 16.5 26.0 38 70 at Lug Root Weld (a) See figure 5-2 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S is the yield strength of the material (ksi) y (d) Sul t is the ultimate strength of the material (Lsi) 58878:l/010683
~
/
TABLE 5-2 (cont) l
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE 1
Calculated Stresses (ksi)
Material Allo <.shle Item (a)
Part Name Value (ksil No.
And Material Designation W(b) 3W SW S tc) g (d) y 11 (Upper Sling-Leg)
Shear 7.5 22.5 37.5 30 75 Pin ASTM A276 Bearing on Sling Leg 11.8 35.4 59.0 Type 304 Cent.
Bearing on Side Lug 9.1 27.3 45.5 Grd. Cond. A Bending 28.8 86.4 144.0 i
12 Sling Leg Bearing on Pins 11.8 35.4 59.0 ASTM ASIS u,
ASTM A515, GR 70 Tension in Leg 5.9 17.7 29.5 38 70 L
or Tension at Pin Hole 12.0 36.0 60.0 ASTM A516 ASTM A516, GR 70 Shear Tear-out at Pin Hole 12.0 36.0 60.0 38 70 13 (Lower Sling Leg)
Shear 7.5 22.5 37.5 30 75 Pin ASTM A276 Bearing on Sling Leg.
, 11.8 35.4 59.0
+
Type 304 Bearing on Spreader 6.1 18.3 30.5 Cent. Grd. Cond. A Bending 35.3 105.9 176.5 (a) See fisure 5-2 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S is the yield str ngth of the material (ksi) y (d) Sult is the ultimate strength of the material (ksi) i' 58878:1/010683
TABLE 5-2 (cont)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)
Material Allowable Item (a)
Part Name Value (ksi)
I #
WlDJ 3W SW S tc)
Sult No.
And Material Designation y
~
14 SPREADER SA 105 36 90 14-A Spacer Block Bending 16.3 48.9 81.5 ASTM A266 SA 105 CL 1 or 2 Shear 3.4 10.2 17.0 30 CL1 60 CLI Q&T, or Bearing 6.1 18.3 30.5 35 CL2 70 CL2 ASTM A266 SA508 CL 1 or 2 35 CL1 70 CL2 or 50 CL2 80 CL2 2;
'SA 508 CL 1 or 2 Q&T 14-B, Spreader Nominal Compression 3.3 9.9 16.5 38 70
< l.0(9)
Rag C, D Assembly
. Buckling 1.2 NA NA 18 ASTM A515 GR 70 Welds (max. shear stress) 11.1 33.3 55.5 of ASTM A516 GR 70 (a) See figure 5-2 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S is the yield strength of the material (ksi) y (d) Sul t is the ultimate strength of the material (ksi)
( f) Stress limit for fillet weld from ASME Boiler & Pressure Vessel Code,Section III, Division 1 -
Subsection NF 1980 Edition, Table NF - 3292.1-1 page 50 (g) Stress limit ratio's for buckling from ASME Boiler & Pressure Vessel Code,Section III, Division 1, Appendices, Article XVII-2215,1980 Ed.
)
l 5887B:1/010683
TABLE 5-2 (cont)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS L1FT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)
Material Allowable Item (a)
Part Name Value
.. (ksi)
I No.
And Material Designation W(DJ 3W SW S tCJ Sult "#
t y
i 15 NUT Thread Shear 11.9 35.7 59.5 38(e) 82(e)
ASTM A276 Bearing on Spacer 14.5 43.5 72.5 Type 304 Block HR & PKLD. Cond. A 16 (Leg)
Thread Shear 11.9 35.7 59.5 43.9(e) 86.5(e)
' Adaptor Tension at Threads 10.2 30.6 51.0 ASTM A276 V'
. Type 304 0
.HR & PKLD. ' Cond. A 17 (Leg)
Tension 10.3 30.9 51.5 38.0(e) 83.4(e)
Outer Tube i
ASTM A312 Type 304 Sli.S CF and HT TR.
18 (Leg)
Tension at 6.60 Dia.
3.2 9.6 16.0 30 75 Leveling Sleeve Thread Shear 4.0 12.0 20.0 ASTM A276 Type 304 ilR & PKLD. Cond. A.
j (a) See figure 5-2 for location of item number and seqtion (b) W is the total static weight of the component and the lifting device (c) S is the yield strength of the material (ksi) y (d) Sult is the ultimate strength of the material (ksi)
(e) These are actual S and Sult taken from the material certification y
5887B:1/010483
TABLE 5-Z (cont)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)
Material Allowable Item (a)
Part Name value (ksi)
No.
And Material Designation Wlb) 3W SW S tc) s ltidl y
u 19 Coupling Thread Shear 4.0 12.0 20.0 30 75 ASTM A312 Tension at Thread Relief 4.5 13.5 22.5 Type 304 SMLS CF & HT Tr.
20 (Support Ring)
Thread Shear on 7.000-8UN 4.0 12.0 20.0 30 75 Leveling Sleeve Thread yi ASTM A276 Tension at THD. Relief 5.6 16.8 28.0 g
Type 304 Thread Shear on 5.500-12VN 4.9 14.7 24.5 HR & PLKD. Cond. A.
Thread 21 (Support Ring)
Thread Shear 4.9 14.7 24.5 30 75 Outer Tube
' Tension at Thd. Relief 8.4 25.2 42.0 ASTM A312 Tension at Weld 6.5 19.5
'32.5 Type 304 SH.S CF & HTTR
-b (a) See figure 5-2 for location of item nu:nber and section (b) W is the total static weight of'the component and the lifting device (c) S is the yield strength of the material (ksi) y (d) Sult is the ultimate strength of the material (ksi) t' 5837B:l/010483
---~ - - - - - - -
TABLE 5-2 (cont)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)
Material Allowable Item (a)
Part Name Value
.. (ksi)
No.
And Material Designation WlDJ 3W SW S tCJ Sult' #
y 22 Guide Sleeve Bearing on Engaging Screw 13.6 40.8 68.0 30 75 ASTM A276 Nominal Compression Below 8.3 24.9 41.5 Type 304 Engaging Screw HR & PKLD. Cond. A 23
- Engaging Screw Bearing on Guide Sleeve
- 13.6 40.8 68.0 36.8(8 80.9(e)
ASTM A276 Tension at Minimum Section 13.5 40.5 67.5 Type 304 Thread Shear 5.1 15.3 25.5 m
b (a) See figure 5-2 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S is the yield strength of the material (ksi) y (d) S (e) Thilt is the ultimate strength of the material (lfti) ese are actual S and Sult taken from the material certification y
i i*
5887B:1/010483
-nm+
+
(HOOK) PIN h SIDE PLATE h
\\/
(UPPER ADAPTOR) PIN h ~
h TENSION CELL
,U
- h TOP LUG h h (LOWER) ADAPTOR pr (REMOVABLE) PIN h '
r h (UPPER SLING LEG) PIN p
h SIDE LUG hBLOCK g
l
- h (LOWER SLING LEG) PIN h h
N SPREADER i-
.31 V, &
i (LEG) OUTER TUBE h h (LEG)
ADAPTOR,,
(LEG) LEVELING SLEEVE h
~~
E m
h COUPLING h (SUPPORT RING) /
LEVELING SLEEVE Jaisi (SUPPORT RING) OUTER TUBE h l
GUIDE SLEEVE h ENGAGING SCREW h Figure 5-2 Reactor Vhssel'Ihternals Lifting Rig i
I 5887B:1/120682 5-20 l
L
9 TABLE 5-3
SUMMARY
OF RESULTS REACTOR COOLANT PUMP MOTOR LIFT RIG Calculated Stresses (ksi)
Material Allowable I tem (a)
Part Name Value (ksi) l No.
And Material Designation W(b) 3W SW 5,(c) 3ult 1
Spreader Compressive Buckli.ng 5.2 15.4 25.7 F I'I = 19.35 ksi Stress on Tube-to-Tube Weld 2.9 8.6 14.3 35 60 Stress on Tube-to-Plate Weld 7.1 21.3 35.5' 2
Plate Tension 1.9 5.6 9.3 36 58 9'S (a) See Figure 5-3 for location of item number and section (b) W is tne total static weight of the component anIthe lifting device
~
(c) S is the yield strength of the material (ksi) y (d)- S is the ultimate strength of the material (ksi) ul t (e) F is the compressive buckling strength of the material (ksi) c i'
5887B:1/120682
i 1
8 MASTER LINK @
h SLING ASSEMBLY I
"U" BOLTS h SPREADER i
h SHACKLE b
Os C h TURNBUCKLE t
)
h
._J L-h SIDE PLATES 4
h SLING HOOK E
R l
' Figure 5-3.
Reactor' Coolant Pump Motor Lift Sling 3
58878:1/120682 5-22 I
TABLE 5-4 COMPARIS0N OF DESIGN LOADS AND RATED LOAD VALUES OF THE NON-DESIGNED ITEMS OF THE R.C. PUMP MOTOR LIFT SLING Safety Loads (Pounds)(6)
FactorI4)
RatedII)
Load
' Proof (2)
Ultimate (3)
No.I7)
Item Design Value Load Load 5
Master Link 81,000 160,000 320,000 544,000 3.4:1 6
Sling 81,000 81,000(5) 94,000(5) 405,000 5:1(5) 7 Shackle 27,000 70,000 154,000 420,000 6:1 8
Turnbuckle 27,000 37,000 74,0 185,000 5:1 9
Hook 27,000 38,750 77,500 131,750 3.4:1 NOTES:
(1) RATED LOAD VALUE - The maximum recommended load that should be exerted on the item. The following terms are also used for the term Rated Load:
"SWL", " Safe Working Load", " Working Load", " Working Load Limit", and the " Resultant Safe Working Load." All rated load values, are for in-line pull with respect to the centerline of the item.
(2) PROOF LOAD - The average force to which an item may be subjected j'
before visual permanent deformation occurs or a force that is l
applied in the performance of a proof test.
l (3) ULTIMATE LOAD - The average load or force at which item fails or no l
longer supports a load.
(4) SAFETY FACTOR - An industry term denoting theoretical reserve capability.
Usually computed by dividing the catalog stated ultimate load by the catalog stated working load limit and generally expressed as a ratio, for example 5 to 1.
5887B:1/120682 5-23
TABLE 5-4 (Cont)
(5) This information is as stated on Westinghouse drawing AED SK 618J644 TXK Sub 5 as follows:
" Safe working load of this sling assembly is 81,000 lb and a safe factor of 5:1." Catalog information is not applicable.
(6) The rated load value, proof load, ultimate load and safety factor information was obtained from the following vendor catalogs:
a.
S.G. Taylor Chain Co., Inc., Bulletin AS-67 Alloy Steel Chain Assemblies, Attachments for items 5 and 9.
b.
Pennsylvania Sling Co. for item 6.
c.
Crosby Group, 950 General Catalog, June 1981 for items 7 and 8.
(7) Refer to figure 5-3 for identification of items.
5
~
4 l
I 58878:l/120682 5-24
{
I1 APPENDIX A DETAILED STRESS ANALYSIS - REACTOR VESSEL HEAD LIFT RIG This appendix provides the detailed stress analysis for the Turkey Point Units 3 and 4 Reactor Vessel Head Lift Rig,in accordance with the requirements of ANSI N14.6. Acceptance criteria used in eJaluating'the calculated stresses are based on the material properties given in section 5.
1 9
L 1
5887B:1/120682 A-1
(
SKETCH SHEET etsfinchiust retz 54202 i
5.0.
PROJECT PAGE I
FJIP-93447 Turkey Point Units 3 and 4 1
26 y
1 YLE CALCULATsONS No.
R. V. Head Lift Rio Assembly PDC -
.uf oR a cats u] l A.
/.
8?
J. Richard
- .tCaco av a oAYc
(,. hg j<_bpfp[
J. Urban /
m Ptarost AhoResutTs[
rT
'Y 1.
The purpose of this analysis is to detennine the acceptability of this rig to the requirements of ANSI N14.6.
2.
The results show that all stresses are within the allowable stresses.
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DATE WESTINGHOUSE FORM 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TIT L E pggg I..
I-lE A D LIFT P.T_(r 3
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T-W / 3 /c.os 2.s.co' T=
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K= HOPJEONTAL c.0mPONENT OF T
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K /(W/3)
K = tans
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= i.an RS.00'
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i WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l
TITLE PAGE HEAD LIF T R E (3-
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(HE AO C. LEVI 5 PIN)
Av = ndW= tv(3.m)2/4 = 9.G3s9J fv-w/3/2./9.63e W (. O n 2.9 8 )
MATL-
=
A bT M b M 3 9 c.L A bh B D fv=
M 8 O 9 PM.
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= W (. 02.9 9 3 )
- a. u ~ ~ e, o m sor m G = B 3 2 o at of cAustA Booy,Iu.
BENDIN(:r STRESS a = uuto & awttuu wu% oy Eb = IG P(,g +3 e k )/(trd 5) out not a, com atov,2w
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$=ene wrwtw outu.wu e,m.
- IG*(W/3)+(Y t.as + $ )
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3.00 %
l 8 = 't.1 '5 - 1 (. o O = l,s 9 4
. 265 L I
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AUTHOR DATE CHK'D. BY DATE CH K'O. B Y DATE RO, DATE WESTINGHOUSE FORM 552130
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t f - W/3/ll 9 t
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i
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- 11.33460 V_
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WESTINGHOUSE NUCLEAR TECliNOLOGY DIVISION 1
TITLE
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.. DATE REV.
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NO DATE WEST 1NGHOUSE FORV 55213D
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
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FPL AUTHLOLr r,H K'D. 8 Yw n 2 h DATE CH K'D. S V DATE CA p D.
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P/Av (W - 4/)
P = K =, iss%W 38.sss4 2.C.so)] w
=[,)5599 W/2]
- pi,194 Ay 3
(_ ime - m.7s]/2.
I.1024 W sk-\\b 39.935 + [ '""a*"*- 2Qb),
ss.ies e
-M_ =
1 Pa(t - s e) fv
.15544 h/ /53.185 w(.oow29
-m
-1(. swr""f")
=
+ h) - Y4&)
i V*
.bl~2.Pu_
~
= -2.0957W I A-lb TO TIA L SHtAR
_ i 9 = fv + (v m,;n T
h= ' $
= 15.25 A 9
Wk h l(ol'7 t 8I2 A b e b -2.(.w) = l u E A 2919 b; =
39.m s
v
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e p g.n,y, w.%
G 2 N D r M (o iTR8.5
&h.-+
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= % 9 3 s = 18.2s' - 3 M.%5
- 17.2 c,'
c, - i s.ss y,
p E - 3es 0o ik' P
b*
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=
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AUTHOR QATE CH K'D. S Y DATE CH K'D. B Y DATE i
REV.
REV.
NO.
DATE f
WESTINGHOUSE FORM $52130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
(
H E AD LIFT R tGr
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CAE O.
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> 4 --H RINGr GIRDERS M Axt mo rn T t NJLt.
- TRtSj Y[-f f v' 3.r.ws -b
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-39.ns.5,O 6.CLS 39.9is +.so
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+
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= 14.249A l
a =
9.ezwo = n.zs ia i 2'I M K
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=. Ess9W ( tush 4.o@
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= %I(3.15 %) A-)b g
l Bb* + Gbdh d3 b"
Jf 32 a.a i
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.DATE CH K'D. 8 V DATE CH K'D. B Y DATE RE V.
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION I
I TITLE
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=
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=
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=
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=
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AUTHOR DATE CH K*D. 8 v DATE CM K'D. B Y DATE R E v.
R E V.
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TlTLE PAGE
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HEAD LIl T RI.tr n
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O G=
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c 4: N.
TmR-oor
- e. PrN w3.E 4
' * ~
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fv m
P - T=. 3&78 W M = '1.00-* (5-5.o0/2. ))+ 2.
I i
- 1.5C * ( G -500h.)
.a L
.x P.%.
,gqgt A4 l 0.29 8 (R '
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- \\/J (.O\\'79 45) '
fv H @ 8 9 Ps.
- 1. 00 -a'7 l
l m P;
L 5 O Ef_ AR_TMb ON PIN 1
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h'3Rm p.ta -z t L i - 1:_ mp t.Rt D
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{c =
9 9 92. PSI T E N5 TOM t PIN - HO LL f;_
P/A i l
P.
T
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AUTMOR QATE CH K'O. B v DATE CH K*D. s v DATE REV.
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NO DATE WESTINGHOUSE FORM 552130
i WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i
PAGE
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DATE WESTINGHOUSE FORM 55213D
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
(
HEAD LIFT RIC7 15 o, m PROJECT AUTHO DATE CH K'O. B Y 7 ATE CH K'D. S Y DATE Jk. %'
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)
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2.7 s a l
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=
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- ". F fy n,t
=
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+
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/
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- -s = N p, w (,3(og g )
{ - P/A, A = bh -Tid 27q t
P =.3G' 7 B
- 7.8'7 + 7.B7 -n + 4t/rl/4 A= ~2.co(L.00s 2)- 2(9.02)
Li B.8%2
=
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- 23.9i e pg w (, oo7sz.4) 4 w (.wis)/23.9i
- w (, ois 3a3 )
&=.
2092.
92 H 2 '7 Co 5
AUTHOR DATE CH K"D. B Y DATE C H K'D. B Y DATE R E V.
RE V.
NO.
DATE WESTINGHOUSE FORM $52130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION H E Tw.'u LT_F T KI_C r li O, z; b.
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~
wmr we A, = Trd%
Av - TP h.0025 )b W ----*
PA k
+. 3 3,
a z
4 Av = 12. S B 2. in' o
fy = { J(dB W ) /(2.+ 17.5E )
d t.
=. W (.o\\9ro\\ M y
fv H O M est l
l
=
m
--i.ewn C LE N T-.
op,
.pg P,j P/2 P= be. ec.un3 on asuu lb.
BE,ARINC, STRESS l
yi
^
d - diarnCter of pcn,in.
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.fc = P/AS c f c.c. a.c r b e a
,in.
P =. 397 % W v
a = impw of bca iq.s o c L.c.
T_N N E R ens s.iac ef O Ao bCd ps.
A9 = a.9 = (.w.m X 3.W )
3 9 = pp txAweCn wrin3
=(t3.(c49lin s
se decc.yn.
(, (.u98w')/(13 G6)
L
-toiei aak i.9.x of 2 VJ(,02.WO P^#
k." 7M51 P3 i
_P + 2(a + 9 )
OUTER P== %73 w T s.
Ac = z aa= 2( tm )(una i
d = q.co2s in.
= ( is.290 hn2 J = 5.41 ih. z i(2)4i.sO-z(.ous)
-f
= (,3fd7B'W)/( \\715 3 )
t
= w(,02s oco) a " L 91 fa n.co
.(.ous)
.fc =
G (o 8 r7 n2,
- o. 2,s 9 =[7.M - 20 00) +2(.ows)- 3 913 /2.
=
AUTMOR DATE CH K'D. B Y DATE CH K'D. S Y DATE REV.
REV.
NO.
DATE WESTINGHOUSE FORM 552GD
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION 4
i I
y
,,.3 H E Ais LIFT TRIGr g
f.
,RoaC1 AU1 L k4 ATE w# ale,*L%A1E C-s o. B.
Com o.8, oA1E FPL h
u S O.
CA t'. O. '
$L E NO..
GROUP FJIP-32947 CHE LOWER.C.LEvn PI N g
~
Ll" DIA PM B NDrN 6.5TRE55 (2)
M=f(i.a+s44f)
.Q = u tz I = 3 d"/foH l
t =-
d/2.
=UP( b +3
- k ))/(Tid )
b*
Tcl R4
+
I 16(.2U1B\\N)/tr/4.001s'
- 4
=
( '$' 4. m + T )
j
= w (. os i s33)
O M,3 2 9 wu t
l ACAFimD PROM j
l FKW_ NI% AND JOINTN 6,
1 l
9D Ed, A m 5%RENLt. %LLut OF, MM hlN1 CELI 6M, Bt4TC,t4 P03CIStidh PAGE 1ry t
(
REV.
RE V.
AUTHOR
,OATE CH K*D. BY DATE C M K'D. BY DATE l
NO.
DATE
(
WESTINGHOUSE FORM 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION H EAD LIF T MGr I$'
o,2 c,
~
R DATE CH K'D. S Y CM K'O. S Y DATE l
AUTdHaA%s mwAJ/,L4.ffATE
,ROJECT FPL
)c
- p. ~o.
,tE ~o:
- cRou, S.o.
s ARM rHREAD SHEAR (LEG).
O Q.P/Av Av 4uttrJ/2.
MAT'L *.
FCR Ass EmmessiL ME AD AsrM A - 3CVe.,
G R70 4u, = D,u,,
. 6 4 S52 /n 4%=(4.OO).fo4952At )
-( s.s37c ) S.
QO,, = m ajor cA 'amde.c of ederneS thee.ad h = nu ber of threach /A "P
.$=S Q Q & <3egsmet
. = 5.oo nc., ( r.coe,-a) l l
rnenes. Av = ( 30. tM i ) R t
i P-WC. 3678 )
l l
[v = W(.012201 h+_
l 4 =
3 3 9 2 est i
x TwntAo Tamrow y
f, =. p/A.
i t
m uwwe.y wama mm At = 9 ( D,, c. 9ws/n?
l l
= h ( x.o
.vns/s )'-n.ou 4 l
..f w (.mB )/ C 1Los3 )
l i
l l
=
w (,o331 % )
O..
c3 2 2. G i
m i
4.00-4 um-g) Pn. % um. or neuw %W "p
m i
I l
AUTHOR DATE CHK'D.BY DATE CH K'D. B Y DATE REV.
REV.
NO.
DATE WESTINGHOUSE FORM 552130 i
4 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE P A G,E,, u,
(-
HEAD LT.FT rcer i
PROJECT AUTMO DATE CHK E CH K'O. BY DATE FPL n/qt. a'O. S Vz!t
~
S 0.
C NO.'
LE Nd.
GROUP T JIP-9349"7 GHE 4"4UPPE R CLEVIS.
SHEAPs STRESS PIN
- u pssm m 34 c. e uo f, - P/2 A, mtNImom Tt MPtRINu MP: llOO F_
P =. 3 G"/ B W
~ '7
'- u " *
- A, = Trd%
g m
Av = Tr R.
2s)%
a y
3, e
z Av = (2.sez in z
a f, = (.3 a 8w) /(2., i2.sen )
-d t.
= k) (.ol40iM 1"
l fy HOCo3 eu
=
m,
-e s
s 8
P= be. ec.un3 on amu,1b.
BE ARING STRESS y
d = diameter of p in, in.
4
.b ten e of scorin3 urrec.
-fc = P/A5 er c.ceur boa
,m.
P=..% W v
a = t=w3w of beans serL.c T_N N E R one. s 'de cf OA bedpin.
Ac = a S = (.s.mts Xs so )
= ( I4.C09 lin S = cp p be. h n hacA3 s
ser 6. g n.
R = (.%7skD/(i9 m9)
L
+0w eak i=mp of w(.oze 2e)
=
pA pa
[c= 72c33 m
_b 2(a y )
OUTER P - r=.3eisk> is.
AS-z ad-2( t.9i )(s.mo d =9.0025 in.
= ( t s.2 90 )ins
( = (.3 con Bul)/( IS.290 )
.P = 3. 5 0 is a = 1. 91.
(n = 2 00 - u.ms0
= u)(.02.4 0 G) 0.230
.fc =
g(o a 7 eq g
g = [9.m - 2(2.m),u.oe)-s.so3/2 c
=
AuTMOR DATE CM K'O. 8 Y DATE CH K'O. B Y OATE R E V.
R E V.
i NO.
DATE WESTINGMOUSE FORM 552130
Y WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION I
TITLE PAGE 7..
H E AD LI.F T RT_( r g et o,_,
j PROJECT AUTMOR M <%. t,1,tA J Ng DATE CM K'O. S v ATE CH K'D. S V DATE i
FPL N
5.0.
CAL.
d.
F(/ E NO.
GROUP FJIP- %447 C H E_
Q" D.tA UFPtR. CLtVIS PI N gg B$NDrN6 STRE55 W M = f(I a+ S + 4 f) fs = Mc /.t I=nd%9 t, =-
d /2.
.fs = i(ia +g f)(1)(?)
(
=ise(3a4c+A1
)/(Trai)
+
3
= is(,wsw)/vr/s.ots '
4 1
3 (q4. m '?)
w(.osom t )
=
Q=
M,ts 6 l
l l
l' l
ACAPTED PROM l
MW_NINb AND JCENIN 6, 1
Mb
(, a pa rg at ur t. nt e,, op M.e..nc ctix ew, tuctu pustr.mn P
PAGE ?. 9 REV.
REV.
AUTMOR OATE CH K'D. B Y DATE CH K'O. S Y DATE
(
NO.
DATE l
WESTINGMOUSE FORM 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TIT LE PAGE OF exc7
. THldCE o A/A,p>
o.Te c
K.o...
Te c _. o...
oATE FPL h
u cAg so.-
que so.
caour s o.
ll iz 8 So 4 I
LIF t.1_ N G LIN K
/ w[
a2s n
=
TG' l
rbLtup
)
I 1
- I, 8 '* 4 c.rw tucr I
3 g.
m. ta s nt s tr sma n mt.
1 s n er,s
% % rusu a t AnrN>
T r
. v.rn _.
j sre rou me. eorTon
-[c,= W (. 015509 ')
- ;5-l fc. -
'-i 6 \\ 2.
em l
TE N5.I ON '. PIN HOLE
, m....
-@y jO
~
.p2 W
,-x N = [8,25(1)- 8.030]4 8.15 l
M AT't.
- 2 (,otis)I l
6>T m a - t 05 c.' A
= Co9. O3 in
-Q = W /G9.03
= W( o19480 LI N K AUTHOR REV REv.
,OATE CH K'D. 8 Y DATE CH K*D..Y DATE l
NO DATE W L SilNGHJuSE F ORM $$2130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION p
TITLE PAGE i
20 Or2G DAlk CH e('O. B Y C H K "D. B y DATE l
P ROJE C T AUTHhOw A t. cMML)All i
)
S O.
CA C' N O.'
WLE NO. ~
~
GROUP FJ rP-93447 chb sLIN6 [bsg)_y.
LIN K.
't m
0 ru g L;5 SHE.AF TtAR-Our t* P.IN fy = P/2Av I
W n.co Ay = (B.25
- $N* 8.ts
.045'
[
r.m v
= 3H.515 v
fy - w/2./ 39.513 T
w(,oiqqB'7)
"* 4 u.os
=
hv' M O 2. 7 P>r.
}
T EN'SIONI G. PIN -HOLE.
k= 9/A TEN'>IdN 1 CNLIM DRn. A t t
secrraw P =iT-. 3&7 B W 1
A(* 's.co(2)- w.c2.] + 1.5a ft =.
p/At P=W
- a o. 9 s ic-Au = % C e.is)'
.r =. s wis w /20.93 w(. o n s 73 )
s 2. i <o s ie
=
=
fe -- W/ s2.16 s
-f+ =
H B BS m:
= w (. ois i e )
R =
5 3 2 9 e>r setan rc" % r e mn-sott-
.[v = P/2%= T/2Ae.3yrsw/(2A,)
Ave (5 00-T X3.30) = 1casR
.fy = 3(47 8w /2./ toms W (, O\\ 75r73 )
=
A =
H_B a s est LIN K LUCr-g.
AUTHOR DATE CH K'O. B Y DATE CH K'O. B y DATL R E V.
REV.
NO DATE WESTINGHOUSE FORM 552130 i
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
'^ '
('
l lE AD LI FT RIGr 21 o, E CHK'DJ. YdATE C H K'O. B Y DATE DATE FPL AUTAHOdh. (2/et PMQJECT b
s o.
cC NO F @_ E N O.
GROUP F JIP-9344 7 CHE R - Mc./I E
LI.N K L U Gr I = bh'/12 - 350 (n.007/12.
= 1933.0 i#
EE AM N (:r CL PIN -HOLE C,. h.OO/2 = 8.50 k M - (w/5). Cit.oe-8.is/2.')
rnr. usart* stata ts va t
- M ( 4 - s.oo')
wt as,sc t~~tr eemrne
=- W (2.32B')
,ls5Yfw(1.so) mtss oc r ut uents. cttvr> ern W O.7 88 0 )
fc = W (.02G2.4) 5s = W (t.ed)(s.so')/ \\953 fc =.
72._99 est
= w(.ot 05S2 )
b*
- 2. 3 'id PSI
,5HtAR e THL FULL-FtNt.TRNTON ut.LD f
F 4~ b l
t so '
1 g
= r72c, +29n l-3 G4 B psr _
l fy P/Av f+_g,o
=
P= W/3 Av =.b h = n.co( 3.so')
ss.EiO fy, w/ 3 /59.5
'w (.oor ect)
=
i l
Fv=
\\se7 est t
%,s.
i FROti 1ENJON AND T!.Et4DTN (:r
?=
P/At l
iP=K=,tSS44W A = bh.17.ools.so) s9.s ic tfi
.issm/ /s9.5 r
w (. 00 2.(oll)'
=
A-
'7 2 C est AUTHOM OATE CH K'D. B Y DATE CHCO.BY DATE REV.
RE V.
l No DATE W ESTINGHOUSE F ORY 55213D t
1 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE L
HEAD LIFT Rh 22 n,
c-CH K'O. B Y DATE CM K'O. B y DATE PROJECT AUTMOR DATE FPL A M, IV,t. /),o pgdy C y eO.
p E ~ 0.
oRQU, C, H E.
s.O.
I'
'i:JIP-9 344 "?
WDIA SHEAPs STRESE g
PIN maru Asm A 9 34 ciass ao f, -=
P / 2. A,
P=w A,, = Trd%
~ '
C' 4
7%.%
Av = Td 3.%95 )%
Av = 49.120 in' c.
f, = (
W
') /(2.+ 99.Ro) d
=
= w(.ou s33)
I fv 1
315\\
P u.
=
r a._,
.e
- ps p
s P= Ec. acWnS on ammbhi.
BE ARING STRESS lb d = diarnder of p cn, in.
.c i
0 impser s a r i n 3 u r k C.
.fc = P/Aq cf c.ced.cr body ',sn.
P=W a = hwpb cf beariq 3erkt.
TNNER anm s.tae. a ou s=a,~
A, = a S = 0 99s )( e
)
3
= ( 59.9b lins S = pp beAwun bearih3 ser 6,im.
& = ( Nu
')/( s9.96 ')
w (.ot w 7B)
I L
. tow eakimpss
=
pii pA e=
H (o %
psr l
= J + 2(a + 9 )
OUTER l
P=w 16.
A. = z aa= 2( 3.m x u93 d = 7.8 9 5 cn.
= ( 4 4.9'7 ') ins
(=( 'W
)/( 4 9.9"? ')
J = 8_
is
= W (.oz224) a =.3.0 0 cw
.fc =
G l 8 3 es.
9 = c.i e ns
= 6%.3 7 5 - 2(3.co) - 8 ] h AUTHOR DATE CH K'O. B Y DATE CH K'O. B Y DATE j
REV.
REV.
l NO.
DATE WESTINGHOUSE FORM 552130 l
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TeTLE PAGE
(.
HE AD LIFT R I (7 23 o, _,
PROJECT FPL AUTdMQA %1.
t DATE CM K'D. B y TE CM K'O. S V DATE 1
S 0.
CALC NO FILE NO.
GROUP T 3IP-93W 7 C H E_
7%" DIA PI N
\\3 B NDrN6 STRESS W M = ll I. a + S + 4.0)
O = Mc /I
.I = v d %9 t, =
d /2.
[b " 5 (b e + 3
- h.9 d) 5E
=KoP(3 a4g +
)/(Tra )
a g'
= 16W( Y+ 01975* 4)/Thd
.L
= w (.os es s')
& = L OD 20 eu l
l i
N ADAFil.D FROM
?N.W_NING ant JOININ 6,
l MD fed, n. m esaur.t. xv.c.
op.
Lf to.Ac. s c r e e n, a t a.t4 p u s t.r t e.
\\-
PAGC 19 AUTMOR
.DATE CM K'D. S V DATE CH K*D.BY DATE A E v.
R E V.
NO DATF t
W ESTINGMOUSE F ORM 55213D l
t
4 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE I
HEAD LIFT RIC7 2K 0,
l PROJECT AUTHhOJ-d h pups &g DATE CH K'D. S V ATL C H K'O. 8 v DATE FPL i
C Ae. ~ c.-
u.E ~o.
- oRou,
~
S o.
B* DI A q
S H E AR, STRES.E PIN mru m m ss3s cass20 f, = P / 2. A,
P=W
~ ""N A, = Ted%
w
-.. ~.3 a
Av = M s.000)%
z 3 -,.-
a Ay= 50;2"7 in' fy =( W
) /(2.+ 50.re )
d t.
=
= w(.co399 7) l fy I
- 2. "7 Co S e st
=
~_
-m
%m P= fose..cun3 on asamu,16.
BE.ARINC> STRESS y
+
d - diam.ter of p in, in.
S=1.n3th of heerin3 :.urfeC.
-fc = P/Ac of c.cace boay,in.
P=W a = lewph of beariq s e r b.t.
T_N N E R l
ene. slae ei oA, bCd gs -
A9 =. a.9 = (. eso X e.oe )
3
=(
69 4B )in l
9: c3 ap bcAwecn bearih-3 t
ser b u,cn.
Sc = ( w
)/(Gs sa )
L * -Lo%I ad.h 1.$thof
= W(.ossso9)
-fc.=
H 3 \\ 2.
PI psi ia 3
A 2(a + 9 )
OUTER l
P-w is.
A5 = z ad= 2(s.co )(s.m )
d = 9.000 in.
=(4S.0
)ins P = 8.0 6 s,e.15-2.(.090
(=(
w
)/( Hs o
)
a = 3.00 rw
= W (.02.0 S O
.fc. = 5"791n=
0.1575 rn 9 =6<.2 u-m.co. - s.*M
~
AUTMOR DATE CM K'O. S Y DATE CH N*O. S Y DATE REV.
REV.
NO.
DATE WESTINGHOUSE FORM 552130 1
I WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
_'(
e.
H E 4.L LI FT F<I. Or
'Ei o, a PROJECT AUTHQ[ b A M w n d i!E DATE CH K'D. s v DATE C M K'O. S V DATE FPL N
5 O.
CA N'O.
FQ.E NO' GROUP PJIP-n447 C H E.
B" DfN I
PI N g
B NDrN6 STRE55(2)
M=UIa4 S 4 4 J) s
.fs = Me /r 1=vd%9 t, =-
d /2.
f = i(ia +p %.9)(881) 3 g
=va(%ug +k 1 )/Ge) tew ($?..ss,s + SE/w/&ml
=
w (.os t s G) ts
B77 9 m
ADAPTI.D FROM FRTE NIN,'u AND JOINTN 6,
MD fed, A mssatNtt nun, op -
MM "1M1 CCC 6N, BM7vil PO3(ILHdh E
PAGC 2. 9 AUTHOR DATE CH K*D.BY DATE C H K*D. 8 Y DATE R E V.
R E V.
NQ DATE WESTINGHOUSE FORM 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION 787LE PAGE HEAD LUT RIC r 2.co or 2 G, F9L Auf MC %.
.s v 2 4, DATE OATE CH K"D. av C H K'D. 8 5 DATE PROJECT 9
CAq ~or pE ~o.
- oRou, s o.
F JIP-93947 C_,H E_
SIDE 15 NON G 8 030 @ "
PLATE.
{=
P/A t P = W/2 A = u..so 3.o0 - 8.oso (3 00) t
- ( 8.s(o - B.030) =.so
_[.
[
= 2 5.lH 5 tnt f = W/2. / 2s.lys 4
i
= W(.Ot9 E95')
- ie.so -
g 15 I
f=
5528 t
Pu
(_l!-
e.cso 4
/
samrs,em-oar e. e.o=o 4 la'i j
HOLE
{
u,,4
~
C. = F/2.As e.n ?
so w F = W/2 3.co -.
c'e' e m '
g,
. o _. q 1 a g.
M AT'l_:
-("''4*.50 ASTM A514
- 12. 3 % '-
fy = N/2)/2 /12.5%
R U SST-1 W (. Ol9 '3 85)
=
l ELARIN6 8 7,515 $
552.8 ra THL rnAKIme GtARINe STRb) y=
IS THt. 5 Afht Ad THE. CArrLR.
Et.ARINCr Sibb ON TH L HOOK, PIN G.= w(. oz2_2.s )
l E=Gl83 est l
l 1
AUTHOR DATE CH K'O. 8 4 DATE CH K *D. B Y DATE l
REV.
R E v.
NO DATE l
l WESTINGHCUSE FORM 55213D l
t
f APPENDIX B DETAILED STRESS ANALYSIS - REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LINKAGE This appendix provides the detailed stress analysis for the Turkey Point Units 3 and 4 reactor vessel internals lift rig, load cell and linkage, in accordance with the requirements of ANSI N14.6. Acceptance criteria used in evaluating the calculated stresses are based on the material properties given in section 5.
1 1
1
~
c
^
I 58878:1/120682 Bl
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TITLE M
(-
T N TER N ALS L \\FTINC R\\G
'l Or PHOJECT AUTH DATE CHK'D SV g
OATk CH K'D. S V DATE V9 L l V \\. b L:
.hb1 VU RjM S o, ALC NO.
GLE NO.
GROUP V J IP -93497 C HE IMOOKIPIN h
%/gj SIDE PLATE h h (UPPERI ADAPTOR (UPPER ADAPTORlPIN h h TENSION CELL OWER) ADAMOR fREMDVABLE) PIN h h (UPPER SLING LEGI PIN f
SLING LEG h h SIDE LUG
(
l h8 LOCK
/
c ILOWER SLING LEGIPIN h l$
\\
SPREADER h s
t a.
\\
I a.
j?
k p LEG) OUTER TUBE h f
ADAPTOR ELEGILEVELING SLEEVE h f
h COUPLING s
h ISUPPORT RINGl LEVELING SLE EVE 9
(SUPPORT RINGlOUTER TUBE h p GuiOE SLEEVE h v
h ENG AGING SCREW I
AUTHOR D' ATE CH K"D. 8 4 DATE C H K'D. B Y DATE REv.
REV.
NO DATE W ESTaNGHO JSE FORM 55213D I
SKETCH SHEET etsfisswcust romu 54202
$.0, PROJECT Past i
FJIP-93447 Turkey Point Units 3 and 4 1
39 or TITLL CALCULATIONS NO.
R. V. Internals J,ift Rig, Load Cell & Linkage PDC -
ALTHCR & D AT E CuttstD tv & CAT Il[f' J. Urban
)
bk J. Matusz lA4 PLnPC5E AND RESULTs:
L 1.
The purpose of this analysis is to detennine the acceptability of this rig to the requirements of ANSI N14.6.
2.
The results show that all stresses are within.the allowable stresses with the exception of the internals lifting rig engaging screw.
/+
+
/o, arctstrato 0
Ofi anerrssienst as
! JOHN M. MATUSZ
.f
,~.n e e, or i
No.14370-E M"
L M \\/h Ikf' Original Issue J. Urban l
l l
BY DESCRIPTION DATE REVISION NO.
REIULTING REP (RTS, LETT(#$ On utuon AND A
i WESTINGHOUSE NUCLEAR TECHNOLOGY DIV!SION TITLE PAGt
_._L NTE FsNAL5 LT FTIN( r RT._C7 3
0,39 R
DATE FrL AU bTHh n'et.
~
DATE CH K'D. B Y DATE P ROJE CT C3K'D. 8 vm WLJ%rtirt S O.
C A@ NO.-
FILE No.
/
GROUP F 3I P-92 W7 C_, H E.
DESIQrN
'WE.E C-r HT NOM EN Ct.NT U RE. -
LIFT Ps.T.Gr (EST) 13 000 3
LOWERS I.N TERNW 5 2 %,00 0 C,CNTIN G ENCIf_E II, 0 0 0 tes.16 N WEI6HT, W,= 2(oO, 0 0 O
$. L I. N C r L E.Gr AN Gl.E.
r p,
i M *\\~, sanu us e, e v.sacu,)
\\
i 4
\\s y
(N.:.umntr sdwo;r y
COLUMN INM.TIVE.)
j
\\re c.t rotw~e.
7'7.10 6 sz.973=39.779o co s cx =
em 0LI N6 L E 6 'T E.N.' ION F OFe.E,T, AND SPRE ADEF. C.OMPRE5 HIVE FOR( E, K T
r, a su,,. gt,
-, =
r Teosm-w/3
' j g
T= W/3/rmwmf
/
T= w (.9039') m.,../
K v.. n s w/3 Dh d * (wt?)
t,*r A b t.or,vs K = W /5
- ta n 39.')Pi g
k=.(2314N AU T H L1H DATL CHA'O B4 DATE CH K'O. B Y DATE gg y gg y MS DATf V.E STINGNOUSE F ORM $52130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE 39 i
~L NTE R N AsLE LIFTIN ( 7 ct3 C-r H
0-PROJE CT AUTMOR DATL C
K'O. B Y DATL CH K'O. B Y DATE FPL bd%
, w A t/ft 5.0.
C A Ld Jf.O.
FiiE NO.
GROUP F J r P-934 4 9 CHE.
1 h
SLING ASSEMRY l
(HOOK)PI N e
h(UPPER ADAPTCR)PJN p
[
(UPPE R) A D APTCF.,
I.
J' TE N.sI ON C.E LL h(LONEPd ADAFroFs
'O' (s.w.ovaatt) r.ts@
70F LU b
-(HIDE ) LV (7 (UPER, 5LIN6 x
LE 6-) PIN ELIN6 LEG l-BLOC.K h '
(tower EdI.NSrL56)ICN
,0, C/
AUTHOR DATE CH K*D. 8 4 DATE CH K'O. S Y DATE REV.
RE V.
NO DATE V.ESTINGHOUSE F ORV 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE F
INTERNALS L1 FT7%
R16 5
o,59 PRDJECT DATE 4
FPL AUT bHOd Mt DATE CHKD.8v DATE ChK'D.8vw w w % s/t' S.O.
CAL O.
FILE NO.
~
GROUP FJ I P-9344'7 C 4-l E_
(HOOK)
SHEAPs STRESS PIN mvu Astm Aym t.tm eo f, = P / 2. A.
Any 4 340 HGT FurD Q 4 T,
P=w A, = Trd%
e=~
%-.* 3 > ~,.k Av = Tr.n.q.ss )%
3-z Av = H 3.450 in' a
ViIJ '
c.
f, = ( w
) /(2.+ 9mo )
a w c.ot ia sO m
"I fy 2c378 e s z.
1
=
-n, srae-
-~
I P= be. ec.un3 on aamW lh.
BE ARINC, STRESS yi a = ai.-.u, a c
e f
- i. n 3 s w o f h e a r i n 3. u r f e e.4-P/A, l
of c.cn4.se body,in.
P= W a = 1.wpw of bean, surge.
TNNER on sta._oroa,wea gs.
Av = a.9 =G9ss X e
)
3 g : pp beriwee.n bar In3
= ( 5 9. W ins sur b o,im.
&=( w
)/(ss.ew) w (. om % 7) l L
e ei ac Ev i.5 +.xof
=
pi pa
[c.=
H d59 m
J + 2(a +9 )
OUTE A, = z aa= R P=W
- 16. = 260,000 ts.
2C i. n X u ss )
l d = 7.9 55 an.
=( 2sa9 hns
(=(
w
)/( 2T. M )
A3 B is.
a =
- 1. '73 m J (n
= w (.o M 77)
.fc. = l O,O B O n:c.
.390 in h.
9 =02.m-20.n)- s4/2 REV.
REV.
AUTHOR DATE CH K"D.SY DATE CH K'D.BY DATE NO.
DATE WESTINGHOUSE FORM $52130 i
vvcsi sNuMUUbt: NUCLEAH TECHNOLOGY DIVISION s
TITLE PAGE ENTERNAlb LIT:TI% PJtv 6
39 0,
PROJECT FPL AUhTH4M%
DATE DATE C H K'D. S V DATE kM r.'D. 8 YMWVTAlt/1' I
S.O.
C NO.
FILE NO.
GAOUP NIP-93 4 4 9 CHE (H OOK)
PI N 1_
BENDEN6 STRE55 W
-%khk8.+.{+k.M)
.r = Me tr sI=vd%4 L =-
d /2.
a +3 + $ lkv4M b=
}
=lGPC:$a4gtk}
)dTr33)
~A U bs)F @.ho d )$r.+
~
~
4
~1
,.es y
=.W(,0358 5 )
l f#
b bd\\
PE b
l i
ADAPTED PROM FWr.NI% AND JOININ(:7, MD Ed, A RWhNC.L. Thut OF MAc.wint on.rew, atercu puace PACsE 19 AUTHOR OATE CH K'O. B Y DATE CM K'D. B y DATE R E V.
REV.
NO.
DATE WESTINGMOUSE F OstM 552133
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE
(
I NTE RN ALL LT F T3.M6 RIGr
'7 o,39 DATE CH K'O. 8 v DATk CH K'O. 8 v DATE AU ITH b l k % %4 n/n P ROJC CT FFL o
CQNO.
F4CE NO.
~
GROUP S O.
F J I P-92. H H r/
CHE BEARINCs AT I.StSC) HOLE ist omnta w r3 Tat sAnn As j
g SIDE F L INT E.
,4 t outtA utAntNb CN T H E Hoo k.
928 (arrn os.)
M AT'L : Amo NSIS GR9O fc = W (. O 3 9 "1"I )
crs ASTM TN-SIL-GR 70 Q (T.
-fc-iO,OBO ru C. AR D ON ton L M T ~7 0 TA T. LEW
{
1%
n n*
ser Ars n u-os m,.sc 4 sett fy=
P /2 Av t,f' u?M
,fr i.,3
/
P = W/2 l
Ave (s.w-7. sis)/2 i.73 G.9 90 "V
fy - w /2 /2. / Co.440 l
f
-f v =
W (.03 88 2 )
10,093 pu.
-fv
^
i
=-
TEN $ ION AF H.%5 $ hot E.
+
p aux--
P/N =(w/2)/A
_.L (
Q -(8.so-M.3ss')(i.io) +
i uss Nm
'[.--uo s.ss a 4
( w.estz)-9.3ss%.,s3-is.m e fe - W/2/m.t71 = W( 03 52.B')
e T E. N LI C N AT l.51"., & H OLE
.fp = 9 { ) N Psr.
SHEAR 7 EAR-Our AT 9.1959%
fe = P / A e
.fv = P/2 Av = (W/2.) /2Av l
l P = W/2.
N ~ (q.sa-9.3ss/z h t. w.
~
A e - (s. % - 7. s is)( i. 93 )
+ (sso-a.3ss)a.to)/2 - 7.osss j
= 12. 8 e c i a fy - w/2./2/7.ogss = w(.owzs -
f.e - W / 2. /12. B B O
.fv = 9 M4 m
= w(. 0 3 8 8 2. )
f =
10,0 9 3 t
esz.
sesunu xx s.we 4 suG_
g_ Bt AltI NG,m.S MSAm t Ab w ovT4.R.. v e n e. A n l
2 vtuarse on t.
lt
-fc.= W(.osoGr ) = \\O i 5 12 o
r.1 AUTHOH ATE CHVD,84 DATE CHK'D 8 v DATE lit V HI V NO DAII W ESTINGe40VSE F ORM $5:13D
Wt:SilNUHOUSE NUCLEAR TECHNOLOGY OlVISION i
l
~"
INTE RN AL5 LI PT1Nb RIG 7 O, 2S PROJECT O ATh'CFK'D BY DATE CH K'O. B Y DATE FPL AUTbMvfA.2% W W E.J1.hs S O.
CAQ NO.
F'LE NO.
GROUP
^
~
FJIP-9344 9 G H E.
(UPPER. ADAPTOR) b SHEAFy STRE55
~
,.,~ pI N myu Asm A-m cw s no,os 6 = P/2 A, P=W srsr mo sonottcomnowtwne
^ -
v ote a o-,or.
. A, = TrdV4 A,= w(H w5)%
g
.' - > t,_ g e
A v = w. s 2. s in' m-f, = (
w
)/g+ta.stc)
~
a o
L.
= w(.o nn) a "I
fy 1
9 7 co")
est
=
m _,
L
, _ -~ s Y
/
2.
2 SIDE PLMO ME, s pMr A PL ATE..
P= force.
6.bn3 en asamu,16.
BE ARING STRESS y
d =l diam.tcr of p ig in..
?
1
.9=lenSth of hearin3 surb
.fc - P/As t
ef c.cn4.cr b=ay,in.
P=w I
a = im3eiM bearim sur6 T_N N E R i
one. sjde. ef cA bedpin.
Av = a S = (9.ws X c>.u )
l
' S = cpp phn wrA
= (2 7.069 )in s
4 se rfdco, in.
[c, = (
N/s/
)/(7.7.059 )
f L
weiacue. temp of
= w (. 0309 4 )
l --
pi eq fc= 9 (o O $ m.
j~
l 1
A 2(a +9 )
OUTER l-P.= W A, = z ad= 2( 2.s3 ')(ms )
d = 9.3 4 5 i,,c,in.
= ( 2 9.5 9 )ins E, = (
W
)/( 2 H.e - )
' P = Co.23s,s
.1 '
/-
ih.
s c
W C. OH O(cG) a = 2. 8 3 s,,
(w.
=
in
. [c, = \\ O. 5 ~l 2 esz.
94 12.5 tt2,l'-4 me, - 2 O -61) -(,[4 d /2.
il' 2
7 A UTMOS '
DATE CMK'D. B Y DATE CHK'D. B Y DATE REV.
a E V.
NO.
DATE
~
I lWESTIM.>ttOL:SE FORM 552130
/
I WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
^
TIT LE PAGE T NTE R N A L5 LI F T_TN 6 TC16 9
OF 3 c) i PROJECT AUTHOR DATE CH K*O. e V OATE CH K'O. S V DATE FPL
%A1A% %@c/rs S.O.
CAL O.
FILE NO.
GROUP 1: JIP-93447 CHE (UPPER ADAPTOR)
Pr N 3
BENDrN6 STRE55 @)
M==cY s p.+ b;+ k A) b -
.fr Mc /r I=vd%9 t,=.
d /2.
[h =
& +3 + k Td
=If5P('h G4'g + k }
)NTi33)
= w(t@4'4.ns M)An-4 1
~
l 4.295 )
5 w (.mso3)
=
Q H2.3B 8 Pu t
l l
l l
ADAMED PROM FMTEMI% AND JQ.ENIN(:r,
MD t.d, A manNr.t shut OF tWMNE CELE 6N, MNTCM Pu3L2Muh
?
PNaE 19 AUTHOR DATE CH K'O. S Y DATE CM K'O. s v DATE REv.
R E v.
NO.
DATE WESTINGMOUSE FORM 552130 I
~
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION J
PAGE TITLE I NTE R. N AL5 LI i- ) _L MG RT_6 10 O, 59 i
P R O.'E CT AUT DATE C
'O. B Y DATE C H K'O. B Y DATE F PL A %s M WJNt/t t-I
)
FILE NO.
GROUP S.O.
CALJ.NO.
1=JT P-9394 9 CHE 6
(UPPER AND LOW R) q BODY AREA ADAPTOR i
a A* = IT b'- a2 + m b' 'f-M-*;
1940s M AT'L: ASTM A-590 MtCC W H E RE.
e-2 8, vtci.o,,, = 120, coo nt tos x =
a / b -+ x = M.&
%Nmt mia n.5,000 psi aP i
1 D43N h.= 4.M B m,-
m h
']
a= G.n m, m
Ah',,
b= 8.w e,,
r
(,
(2).y)y-za s';-sn-u m
d, s,,. g, g 7, r" k - 3.' m m.,
m t,1 g:
,39 m.
m e
y
- i tr 7'. g D
9.38hs m
i A
V Ct=4. %
m 1
P= W -
Ib EP OH9t4-2a Tao 1s t, < D T g
c.
- i l
s!
c-1 st-st l
?;--y
,1 (. s.c39 P-u.u )'
E 3
(c.412.
in s
1 4-
=.
l
'l D =
't. 3 9 '?
A
'.s-c C>D s-l l0 AUTHOR DATE CH K*D. S Y DATE CH K'D. S Y DATE l
REV.
REV.
NO.
D' ATE WESTINGHOUSE FORM 55213D I
i
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE 39 IMTERN AL5 L2 FT It46:r RIc r 11 0,
PROJECT AUTM OATE CH K*D. SY DATE CH K*D. B Y CATE
% % vt & t/n FPL S.O.
C AG. N O.
FIT.E NO.
GROUP 4
l F JIP -93 4 Lt 9 GkO C H E.
G THREAD
.5 HEAR (UPPER. AND LOVjER).
q
( = P / Ay = W/Ay ADAPTO R Ay = n bpe a /2.
j= k-m TEt%ILE STRESS c., A-A
= ( 333. 2 )- (. 39 )
4= P/A-
= 3. 5 8 2. '.
in t
P=W D a = E
.6 99E2. /N p
(9.w s 8 ) in.
A=Aa-AwA
=
t Av = (zs.so s )in 6-(D asi.e3.3 )-(8.nT)(u2) fy = W /Ay t
61 =
= W (,041l1
)
t
= 2 4.602. in f = W /At E=u,209 t
m.
= w (,o9o(os ) ~
'Ev*
\\ O,5 (o 9 Psr SHE AR TEAR -QUT ?_.
g
%=
P/EAv BEARING STRt.55t XA Ay =(h - D/1) 8
~.
~
ft =
P/Ae
= (Lt.9 B - us?/2.)d4.3) 2 19.24 5 in -
P=W
=
A i aD
' P.e = w c-(Ga3 X s.287 )
fy = w /(2Av) 2 '7. 3 3 in'-
= w (,osst oo )
fc = W./Ac fv =
9 ) 2.(o
=
i
. W (. 0%59.)
f=
9 513 em t
- u
) = carrtsc5 As s u.
TENSI.LE STRESS e. B'-B w karx o,-mE h =
P /At = W /As i
caow-w.now V
A+ = A - n dV4 cruerm saavs a
= (51.933)-9 (4.31 ),
A>tts 4
37.34 ins
=
t
&a =.w C. oz co 9 8
)
e 9 tes em c
AUTHOR DATE CH K*D. S Y DATE CH K*D. s Y DATE R E V.
REV.
NO.
DATE WESTINGHOUSE FORM SS2130
..~...
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TITLE
[*
INTE R N AL5 L2 FTIN6 RIC, 12 oF 3 9 DATE Cw %'D. B y DATE C H K'D. O y DATE AUTHOFp b b %
P R OJE C T bt h
I S \\W L1/to M
FPL FIL - NO.
d GROUP d.
s o.
CAL Q d.
FJT P-43 449 C_4-1E.
"5" TENSION Q LL 5
7HE W R E.AD httAA D THE.
Sa m t-- 6 THAT C4 7 %t. AD AI'ERS M A T 'L. -
(yggm yAnes) t,-s es u a iico fs =. w (.00i0 fv -
i\\,2.09 m
tP I
(
i 4P 4A-s-LA T E Nb10N AT 7 H rw AD5 i
-f P/A
= w/A
=
t t
t
~
FRCM PI Mkh H AND U OOK it t. B-13 s.uw mas A - As - n.nel J
-f = W l.O1960) t i
-f
=
19f4 H 3 e=
g t
AUTHOR CATE CM K' D BY DATE CH K'D. B y DATE REV REV.
NO DATE WESTINGHOUSE FORM 552130 t
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE i
INTP RNALS LTFTI N C-r RIC-r 13 O,33 P ROJE CT AUTM R QATE CH K*D. B y DATE C H K'O. B Y DATE FPL A%
h ttv & z./r-5.0.
C NO.
FILE NO.
L/
GROUP FJIP-934 4 7 G H E.
(RE MOVABLE.)
7 SHEAPs STRE SS, PIN M AT'i.: ASTM A43's c_,8 h B D y
v AT.SI H390 Hor ROLLED, Q(T P=w
&" ^ =
A, =. Trd%
w
- a Av=Trfo95 )%
~
a
~3 A v - H. s 2. s in '
c FIN --
c.
fv =( w'
)/(D mms) a
= w (.. o 3 3 7 2 ')
I' I
fv 8 7 Co l est
=
ra -,
_w m
, 'otr lL 2
- e P = 6 e c u n 3 o n a m m u,1b.
Bli ARING STRESS y
d - diarneter of p cn, in.
.0=len$th of hearin3 surfecc.
-fc y.P/As of.c.ca6e b=ay,in..
P-W-a = lewph of hearim sce6 TNNER m.s.camc;Da,%ag-Av = a.9 = (s.9sx o.23 )
S = pp u+m, we,m3
= (2,. o c,9 ) ins se r6, im.
.Pc = (w
)/(noes)
I L
+o%i acth i. nee.h of
=WLo 369 H )
pth si
[c.=
9 GoK pu-3
_9 + 2(a + 9 )
=
l OUTER l
P=W 16.
A, = z a& 2(2.98 Xs.ws )
c1 = 4. 3 4 5,' in.
= (as. e% )ins
-f, = ( W
)/(1s.B % )
.P = g 2.2,.:
is t
l a = 2.,98e in
" \\Al(. 03 8 62.)
l1 9 = o.o,s ~. rm fc. = 10,OH \\
er.
l.-
= (c.s ao-c.2 2 ')/2 AUTHOR DATE CH K'O. S Y DATE CM K*D. B Y DATE REV.
R E.V.
NO.
DATE WESTINGHOUSC FORM 552130 l
t
1 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION g
76TLE PAGE INTE R.N A th LIF Tl N 6 R 1 (7 l4 0,3 S l
DATE CM K'O. sv OATE CM K'O. B Y DATE l
PROJECT AUTHhR A n/n
%1 th,t /n FPL h
S.O.
CQ. NO.
FILE NO.
- GROUP, FJIP-9344 9 CW (REMOVABLE)
Pr N g
1 BENDING STRE55(2)
Qib 5. B +.p k..$ )
.Q = w tr I=vd%4 c =
d /2.
- 6. i(sa +p OXtXe)
- 3
-lGP(%ag+h.0
)/(Trd )
8 l
= 16 + w * (2.98/3 4.on s 4
G.u/4 ) /,r / 9.39s 2
+
W (. l c,3 0 3 )
=
6 = _ H 2.,3 B 8 m
ADAPIT.D PROM
%TENI% AND JOENIN(v,
9D Ed, A etantNtt zwus oF MMRIN7. OEW(sN, BNICN Pu312kHulk PA4 E 2. ')
AUTHOR DATE CM K'O. BY DATE C M K'O. B Y DATE REV.
REV.
NO.
DATE WESTINGHOUSE FORM 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TIT LE
.{
I NT E.R N INL5 LT F TIN (y G I. @
t$ m 3 9 DA(E CH K*D. SY DAIL C H K* D. tl Y DATE Hog PROJE CT AU FPL RhwkGk,1- % u[L i2/p.
5 O.
CA $ NO.'
Fit E bO.
GROUP FJIP-934 4 7 CHE g
TENSION RT PrN-HOLE TOP LU 65 1r n m m r* To nu,ue m w %
L ogso / FIM sMOVD MAT'u AnM A sis eR 7 0,on,
( = P/A uTM A-si6, en.no o f T. cmoN P = W/2.
(,,0NTENT ro EE. LELS TH AN h_
ht = (8.9G -S.1B3X2.96,52.)
o.z o A M
- (L 96 -5.m )(. 5 2.)
M.335 @ M O.
.'M
= \\ 5
- M 3 m'-
I ip S.CM m. 52. OuP C,'GCRL l
.[3 = W /?_ /13.293 14 f*-
+F E
R/S w(. o s 'w i )
=
Ee -
9 7 7 c) esr i,'
f m.n: -
2 A rg;;;m
.swJgtcwd.-ovrwPm ROLE.
-[v=
P/2Av
'ND E
3 P - W/2 c
lh k Ay = [(8.96-M.iss)'2.9s.n}
l
^
(
- (9.3G-5.0$.51)] /2.
V 2 A, = 13.2.33 M i
.fy = W/2 /2 /Av w (.osw )
m i
6.9 H
.f =
gga y SI D E. " Awewe f cos us me oN tut,s T~t.N SI O N AT W E LD P/At EEAFJ N & O N PIN -f = 3P = W/2 i w eearene srwes.s zs rse. A = 8.%
- 2.96 : 2(c.'70W l
SAM E. m 7H E OUTE R G E ARIN er t f = W/2/2(o.70 statss os rse atmovaetE 4 ero(trtm 7) = W (.ot s '7 2(,) F. = w (. o 3 862 ) Cy = q g (o 3 m c t
- i ft=
\\ O, O '4 i nr AUTHOR OATE CH K'O. 6 v DATE CHK*D.BY DATE REV. REV. NO. DATE W ESTINGHOUSE C ORM $$213D t
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION I l' PAGE TIT LE 39 INTE RNALL LIFTI N Qr RIer Vo 0, DATE CH K D. B v OATE PROJECT AUTHCP DATE C FPL fMA % hK'D. By& n/n j S O. CA D NO F I L'E N O, V GROUP FJIP-93449 C, H E. H:.N SI O N IN Bloc.q j 9 .Q = P/Ag = W / A1. BLOC.K AND S I. D E LUGS 10 Atmm. 7, (, 3 % So = (92) ~ L = 2 c. co19,;.. GLCc K: sAcsc L.,Lu L sA(d 2 E> u av, ww e.to t.1 ot:. p% corcue To F~'_g \\ --- g h = n.O'? L e w. w. m r,v u s - u m -a,6 T. ,q'w 1 4 n tu s ci a cis.n56ps. out..cA a:n c.wnnr n s t. 1 i.:. t ttw w% c.i e w [ *- m upE Lu(3 Ann Asir 6c'70 crz asTrw.ggr. n ud'T me. a t v. we.- a To. o. % aa M i A ^ * ;- H.33 - v.95 - 7.% Aa- 'I h L d'i NG.G39(U CM 307.2 s m s mv. = [ ] - k * "* h% = h - M.S s - 8. ) 3 A i +(a ' p. Lu,m.: 11% (2ms) = 9.38 % r .t p,6, t ~ F ~ Au,g,.s = ('iXB.r3)(9.3ss)- 39,w.3 A - 3 A,uu ](s.oY; 4 s= e m-g A%,.,' t t =IN(4 M j 4 -Q =. w/ /1 Ti.'o T -.m - * * -- d " d 6 'w/ (.00 5 5 G 6 ) M', *k hh = "l' 1 ,e = \\HH7 m
- 3. m ~,
3=\\~17 $,) 4.K' %% t h H.G 9 t,: s us' s t a C C T w i.<. sw _. TENS ~ON AT HOLE J6 9 [ t P = T4 cos oc - (4) T / ?f -',@ Ny\\3 x= 28.W,
- T =.405 B W t
/_____. c. N+ p.ss h)-s.s.s],i.w 9.m 9a N,.' y fe =.%saw /us. -n 9 l w(.oass ) = 4-SGOO = BLOCK O s, / AU7 MOM OATE CHCO 8% OATE CHK'O. 8 Y DATE A E V-A E V. NO DATE WESTINGHOUSE,ORM 552130 e
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE TNTE RN ALS LIFTJ N6 RI& 17 0,.3 9 i P ROJE CT AUTH 3 OATE H K'O. B Y OATE C H K'O. B Y DATE '%t. W4/1/v. i F PL S.O. CA NO, ' FILE NO. GROUP FJIP - 92 4 4 7 Cf-lE V C.OMBINED TENSION AND f gg BENDr.M Gr AT F. P. LotLD 5I.DE. L U(:r Tgusons .f+= P/A+ sME AR ~nEAR-OUT AT EN H3LE. E = '$si 39.M9 )/2. -fv = P/2 Av At= ti.9e+ i.98 = 2 3.w2u P= T/2. =.405BW/2 4 - T+(s4 29. nv)/2 /2 3.202. Ay = (3. 94 - 3.025/2 )
- 1.w
= T (. oi n 9i) =.sossw(.omg = 4 "t O 9 e = W (.00%988 ) -fv =.Hoso W/2 /2 /4.'?oc> -f = 12 97 PE t = NA/ (.07.15 4 ) fv = 5 to 0 0 Psr M %WOM MMCIMLr' -fd d M G / I ; c = 5, ]._ \\.,n.,c %; bh*/I2. BE AFs1 N (7 ON PI. N rst et ARIwe sTatu ts Tse c, 5 h / 2. .}_ M:b ,h sAmt As Tut currcA nENuNe F =(w/3)/2. une.s on rae uncc. w~e-uemu (uts n ) J = M.t3 A -Q = W (.039 9 2. ) Q(w/3/2)+s.e@'( t.9% u.s<>/12) S079 f es2 w (. 01M BB 30 = t h;. 387O vsr SHEAR A T Y.P. weto .fy = P/Av c.omGINED-P- (w/3 )/2. E m,, = b
- ft A,=11.90+i.9s w (.otsees +.cns9sa )
= W (,0l 9 B71) = 2 3.2 0 2. e = -fy-w /3 /2. /23. 2 02. .Q*= 5\\66 nr .f v - W (. 00'718 5 ) i fy \\ P (o 8 =. a est l AEV. REv. AUTHOR DATE CH K'O. S Y DATE CH K*D. B Y DATE l NO DATE I WES TINGHOUSE F ORN4 5' 2130 s l f
f WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l pacg TITLE 13 I.N i t R. N AL5 LT FTI N L7 T*I C r I@ OF CH K' OATE CHK'O. BY DATE PROJECT AUTMOp OATE T PL h04 d d Ve 9 NO.Bd.it/f u S.O. C A Q N'O. FICE NO. / GAOUP 1 DIP-93449 CHE_ S H E AR STRESS. (U PPE R. SLIN6-LE6-lPI N MM-'Lc MTM A, 27G 7 N pt. 30 4 [y P/P_A .= V ct ur. Gr o. to s c. A. P = T=.4 059 W s %WG LEG A, =. y d% -. 7', _;._ g Ay = Tr( 2.995 )N Av = 7.04 50 in t pg _ fv = (.9058 Nr/ ) /(2_+7.0-iTO) ~~ d L. = W(.02sBoo) 1" 9 fv 9 4 8 @, P SI. = r a._, -e s p g P= fone. ecun3 on aucmti;,16. BE,ARING, STRESS ~ d = ciiarnCter of p in, in. f len$th ef bcan'n3 urfke. -fc, = P/Av er ca a te b a y.cn. P = TN905 B W a = lergw of wus... m? cc. T_N N E R en_cac =:=u's=a g-Av = a.9 = 0 995 X t 9s ) 3 = ( 9. 9 2st )ins S = pp sme wr.,03 surrec:,,in. Sc = (.sossw )/(s.91st ) ~ L +o ui ac s
- i. ~ th of
= w (.04 5 4 '7) [c. = \\\\B?._2.- Psr pi gA J + 2(a + g ) = OUTER P =T=w(.ecsa)is. A,= z aa= 2C is4 )(:.99n = { l 1 G l )in2 d = 2. 9 SS s. E=(wt405S)/Cli'ai- ) P = 2.98 m a = t.99~ = w(03491) iw fc. = S079 n.
- 0. 0s s
9 =L2.OB-2. 9h')/2 = j AUTHOH DATE CM K'O BY DATE CHK'O. SY OATE REV. R E V. NO. DATE WESTINGMOUSE FO AM 55:130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i-TITLE PAGE l s Ab TFTIN6 RI6 A o,3 9 i P R OJE CT AUTHOR DATE Q K'O. B y DATE CH K* D. S V DATE FPL %4a A '% huvC nhs S.O. CA No. FILE NO. GROUP FJI P-92 'l 4 7 C_.4-1E. (U PPE Ps SLIN6-LE 6-) PI N f( BENDrN6 STRE55(2) M==' $ $. S t. 3 ~ + k l ) t .q = Mc /r I = 7 d%4 t= d /2. $ dhvM [b, i =lfdPOha.4a +$ + k } )/(Trda; + " 16(.H05 W)* ( '@ +.os, 2.9e/9)/(In2.mj' c = W (. // 0 9 2 ) & = 28,8 37 m I ADAPTT.D PROM FMTENIt% AND JOrNIN 0:r, @ Ed, A a t % n N tt. w u s C F [' M AC-MNO. DEM'bM g RNM PU31.15HtD L' PAGE '2. 9 REV. REV. AUTHOR O, ATE CH K'O. B Y DATE CH K'D. 8 Y QATE NO. DATE WESTINGHOUSE FCRM 552130 I
l WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION I. PAGE TITLE INTERNAL 5 LI PTI N b R T_6 20 0.39 PHOJECT AUT HOR DATE CHK D. BY D,ATL CHCD.BV OATL FFL M& %s 1 Rut @VP S.O. C A[ NO. FICE NO. GROUP FK P -93 449 CHE BE ARIN6 ON PIN E I i TriE EEARIN(y 5:JRE% IS THE SAME SLI N Gr LEcr 12 As.mc tumen,atuzwt,auvet s.ns-i.ee-Frss(zrsmo me a) t%Tb -fc = W (.0% 54 7 ) A6TM A-s 15 GR '70 CR, f= l }, Q 2. ~2, Pr t I NTM A-si6 G rs '1o, Q ( T. Git < O 30 Yo TEN 5I ON ~I N LE. Cs ..= u~n 6 = P /At = T/As =.<fosm/N. . A_. pmTso As 2.98 + 5.96 = 17 3 2 cue 13 I, fe=. 't053W /i?.3:0 :W (.07 7.77 ) (= 910 m ,3.ou 4 wau(2) ~ TENSION AT FTN - HOLE v,q -[i - P/A+ = T/Ag =.4053 W /A.; k ik+ A -i( s.92-z.75, + 2.96 2 8. 6's /- i 3 Ac = .+ h =.40ssw/8.srs w(.0%oe,) 2 ' -k - \\\\ 98\\ Tu sec A-A i por twcr stw% ruct + <,n Ae 3.-u et or b 3 us.ctc SHE M TtAR-OUT AT PIN-H O' ' .[9 = P/2Av =T/2 Av: ws W/2 Av Ay e (s..ss-3.ots) 4 :.se /2. s 4.". 33 s.c-fy =. /058W /2/u.u.0D W(.0'G9) i fv = ll1 9 31 nr i l l [ ~Lse +- l 0) m Ab5UvCN& b*a p ponT c.0 L J M N Is NOT ACTIVE. A U T H O F4 pATE CH K'O. S V DATE CHKD.ev OA1E REV. REV. NO DATE WESTINGHOUSE FORM 55213D f
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION f I NTE RN AL5 L2 F TIN 6 RIer f5 O,39 C H K'O. S Y O TE CM K'O. 8 v OATE PROJECT AUTHOA DATE F PL M4tz/e. 3 mwM n S.O. CA h NO. Fif.E NO. ~ GROUP rJIP - 9344c/ CHE (. LOW E R l3 S H E AR STRESS mNe-treAPIN mru mm ezw m. sos -P, = P / 2. A, t wr.
- c. t c.
c.oNo. h. P = T= 4 058 w s --- - 7 .s e w u e A, = 77d% g P, A, = Tg:2,99s)% / Av = 7.o95 0 in' a e.m -a [v = (.9058 w) /(2.+7.0450 ) d t. 7 = w ( 02 BBO ) La, I" I fv 1 M 8 6 PST. = I e m e,, 5%e. how 4 L:a em t, WEuonEwT g 08 !.PGnCttA h%>WGLY P= fone. ec.unS on asamu,is. Bq ARINC, STRESS y d = diarneter of pin,in. h.r P/Av Av.lenSth of hdeing wrfecc.. c... orwate boa 3,in. P'= T =. 4osB W a = kwpb of beana 3erL.c. TNNER one. s.iac. ef O.k/bedgm. Av = a.9 = (. zcas x 2. 93 ) =(e.9tst)in s S = c p p w +. ee n w e r cn 3 se rface.y in. S,. = (.M 058#)/( B.92 SI ) L +0iei ac.tive. knp of = w (..o4 5 M ?) pA pA ( = M i P_N 2. Psr J + 2(a +9 ) OUTER P = T=.yossw 16. A,- z aa= 2(2.m )b.es ) d - 2.9 s.s (n. = ( (7.ws t )ins f = (VOFBW )/(l741I ) P = 2. 99 ih.:. t W (.O '2.3 2. B ) a = 2,9l thc.9m(.uNSs3 [c. = (c O 53 t> sz. 9=.o5 re 2 (5.0 S - :1,98i/7-v. AUTHOH DATE CM K'O. B Y DATE CH K'O. SV DATE AEV. R EV. NO. DATE WESTINGHOUSE FORM 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE .m' I NTE R N ALS LI1:TI N Gr RICr 22.O,3S DATE CH K'D. B Y DATE OATE 3K'O.ByNv4 n/n FPL AU bMd Wo. PHOJECT C AQ. NO." FILE NO. GROUP S.O. FJIP-91447 CHE (LOWER S LIN G-LEC7- ) PI N l3 BENDING STRE55(2) M. w=":b(- 5. a +. 3: + k }) .fs = M e. f r I=vd%4 t, = d /2. {b
- A*
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q + 4 4 = b y W +,TD58 * ? ~~ ( 2.9i /3 +.05 + 2.93/4)/ ( TT +. 2.995 ) 3 6 = w (.i3s7.8 ) b= 35,303m k ADAPTED PROM F.STENI% AND JQrNIN 6, 9D fed, A am nNtt. wu op mar.mnt on.rew, MNtu Pusttwut's PAfaE 19 AUTHOR CATE CHK'D.BY DATE C H K'O. B Y DATE REV. REV. NO. DATE WESTINGHOUSE FORM 552130
r-WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i PAGE TIT L E T N ~ E RI,..T _'_ LIFTT N C7 R T_. C r-2 3 or.I 9 .( ' PROJECT AUTHO DATE CHK*D.BY DATE CH K*D. BY DATE FPL /huja_% 9 wmE /1/I' i \\ s o. Ca tt)N6. rice No. GADue F J I P -934'19 C, H E SPRE ADER AS5EMBLYh SPAC.ER BLOCN A e s.491l 16 % - 9' E 1 euxear am. l (.T'YP) ' 62 ,,X s b' N \\Y F tve b.= p o j i 3 ICE PLATE. i,, i t-1L.0% I A / .-;y.n m .n y M'tP i. T I i nur i J 20.97 .n.- + 4.98 1 4 ,i t c..s s /- u .50 tar s 9 gg 4S ,' h .51 I-L S 'L x gP-vf t .- g.co s.E,
- 7. B 7
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION T11 LE PAGE l 1 3 N T E R. N A LL L_ E r: T T N 's R. I (. r N n,,. C3 PROJECT AUTH DATE CH K'D.BY DATE CH K'O. B Y DATE FPL 't ypg/gr 9 pI wR,z,,,, GROUP S.O. CAQ.NO. F II.E N O. FJ I. P-93 4 4 "I C H F-ca Aprc8. s, s.tc.rz on i.4, es e c-n COMPAMSON OF SPRE ADE R. St.wo t.a.b su c a t cno TO GO - WA ARM STRE.EEE E TO AISC. COthPRLMION A M C, BENDI N 6 ?% W. a C, RITE RI A sHALL Et PtoPonTroNEo to s.ATnr* "THC SPRC A?E R AG.!41. AR.F. THE FOt LOWING Rt Q,.)I RE ME NT5 : x)G..itLTto TD Elf 4ET NLT A N D ha (bt bmy (h t V b,3 Fa * (i p*= ) F>. * ' Fey,' N fA A' COMPREh1 ION s L',i, si. 3 IF- -+l " ^ S %q /.tr.;,
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- EtIT TON AIiG 3
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TIT LE ] I NTE RN AL5 LIFTT N 6 RE ( r 25 O,3 c) DATE CH K* O. BY DATE DATE $K'D.BYmvSEn/g1 FPL AUTMp*A th PROJECT S O. CA . NO. FILE NO. il GPOUP PJ I P-9244'? CHE comPARn.ow on s.PasotR Awvm uu,as vun cat.,o et F1Rm s.TRt MEb TO. RI h L. Rt'ATrvu.s LoNu aun F tsunLL, Aun 5.o GRI. IER T. A TMittutt IntAPAcu. o( t%,RTINw eN 'INFlutrJGM. M,OMt.MT K THEM.T.3 3 DETE R MININ 6 -fd K x=. O. B O (cau b) I.M T &h PO9J doktTAL. PLAu fr, Tv%. -E = K/At =. 2 319 W/A. 3 t 1wat.n. e n abut ~ cr uo, sur A
- 2. +. 50 + G.oo 4 2 v.73 + 8.00 n+ o e. eso % m ustm, Aus i
4 44. 3 3 *.18 [2. ROT ATT_. THE.,HtottT:cAu k GAtut. A = I B.2 9 M x.s 2.0. Tut. nne nuou rn up o t .Pa .2als W/t8.29 m At.u s ts W(. O l 2. (o b'5 ) ky 2.1 4 = fa = 3, 2. c3 O r d r. n e r i c. m ~ s t-r# c z.= oc t,3 tarIon bh [l2. i von A a tf.T A N e tt. Ig =i h h / 3(o I. = I s + 1t, l 2 S rea A t ra r e.N r-L E CETE R. M I NI N L-r Fa aw, c I,_x 4 2 (. is + s.co'/12.) - 4 ((G.co 4.so'/12' 4.so(wo 2 secTrow i.s. i. 3 4 er Tr s m: w N L,- C' 18 +.2S /3% +. 33*g o,.E p 8 + C = T 2,r2 e. / F 1 -x = l'5 \\.3 0 i# t y x Y = (2m ' 30,oM, coa /1S,000 ' r3-x = 1 I,., / A - i29.93 = Q3i.30 /18.29% t nt e mr~2s e K 0 /r-r.x = 2.G 7 9 A s .9 = c, i. G 9 fs etrenMrN04e k/s. (pop s-ise) L.y = 2. (. s 0+ 400'/i2) Tot 2 wav. (Nu x3 m.t., wo + ? ( 8.co(.7sf/11 +.1s(a.oi 3.#-,,{ +4(.u+.uYA4 'f(3.co-T/) l nue ce m n w e ram ry, m. ciuT a l COLUMN, Re mTIVity C.t0y.. TD T HL k -y
- l 5 9. @ (U i
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- -wa r.
= *1% / 24' 3: w o u m) Awo wouto noo xt. ro; acm Am Kl h- <. k styret tun.vATutt ff.%C12. 1 h3d So EqusT2om s-1,5-1 so ra AT j C,ovenNs ( page_ 5-16) Gm=.6 .4 on + y, '73 ,4, wszu tven, u tess 3 Fe = {1 iN )F /(h4-5) f,.c .,9 7 y WHERt N - (kJ/r)/ k N, = t B.u t /l29.83 DeTsRMIwrm er f3 I , im E9 = ( = 'Y(9.52) = 92s,o ms-m M c. / L.s N - u s.l w / 12 4.o 3 0 y 1s34'7 M. . ', Fa,= A I, 9 3 4 r. I. o S.0 / 2. - 4A l F3) = 2 9, 8(a vu (- 92.s,ota m / I 51.3 0 Fa Fac = Fs, ( = 2 5, t 55 ec h = / 9, 86 2 et DETE RMI NIN (7 - Fb. DETLRVnINING IF 4 /Fa zs Fe =..GoF7 (pep c-n) cuoua,is =. 60 w 2.e. coo 6 /fa A 3,290 /i9,242. R = 2 2,800 m .{a /Fa -,I(oSTo// (.l5 DET E RN NT N 6 F[, .'. h t. FIALT St r C s ( Q J U3 C,N3 FJ = 12 m ' E./n /(K 9/r P } F s (pop 5-n) GOVERN An t (.,% = 126 3.0,andh> /21/ l8 W2* nar a t ot ncm,r oto. F6 = H 55, i 9 9, AUTHOR DATE C H K
- D. B Y DATE CHK'O.BY DATE REV.
REV. NO. DATE WESTINGHOUSE FORM 552130 t.
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- ROJE CT AUTMO DATE CHK'D. 8Y DATE CH K'O. 8 Y DATE FPL 1
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- 22,900 l
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- REV, REV.
NO, DATE WESTINGHOUSE FORM $5213D I
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TITLE _'I NTE RN ALh, L_I FT I N & RI. 6 23 o,3 S PROJECT AUTHER DATE CH K'D. Bv DATE CH K' O. B Y OATE FPL Jd')4& nh % lu m /2/4 t-FILE NO. GROUP CgC.'NO. CHE s o.FJI P-914 C 5 HEAPS SPRE ADER WAGR tur u: tmm c.a.on
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- REV, NO.
DATE WESTINGHOUSE FORM 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION c,, I PAGE TITLE ) INTERNAL 5 LIFTTNtr RI(r 2_01 OF 3 3 DATE CHK*D.BY DATE DATE $K'D. BY FFL AUTMHOd% P R OJE CT ws# g//t FILE NO. GROUP CALytwo. S.O.FJtP-93447 C.H E SPREADER WELDS WELO Gr E O MET R3:E5 C.O AD5 ON SPRFADER ARM SPACER ELOCK TO trDE gg -s _, c I PLATES .? s. H h l,%O'O W I j'(,T A 93 A E L 1. T k /' ',;': / n.vw' 9 9 1, 30 g ,~ f 5.95 m g 5.98 - 1. 0 % = 2. 9 0 9 N EACK-OP PLATE TO LIDE PL ATE,\\ yw I T i G.9% 53-4E AR L3 Aq.EAM (V) f 4 4> b i s -Ytb d 93 8 j PCMENT DI AL,rt AM P L ATE b TO ETDE PLATE 5 !M) y- /'. / c-I w(9.52) &_gg _ / [;' .' j /* ,..,' [ l I 0 ) p J d' / 0.ss ,.::hd, ', I. .L x kd9P! AUTHOR .OATE CH K'O. B Y DATE C H K'O. B Y DATE REV. REV. NO. DATE WESTINGMCUSE FORM 55213D
D WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE [ I NTE R NIA L5 LIF TIN (:r RI tr 30 OF 3c) DATE CM K'D. B Y DATE P ROJECT AUT OR DATE ChK'D. B yWiWW/2// t FPL lt/st-S.O. C AW. NO. FILE NO. GROUP FJIP-93 4 4 '7 CHE W E LD STRE55 DUE TO SH E AR. c.oMhtDtA. SPAtu b'OLN LO ADe D BY EHEAR.VORCr. K /,/l O a / g /A 4 = P/Av K/A,A, = 3 m,s i As. 4(.u w.s. m ) 2 4.09 int = (v = K/2%.09 . 2 3)H'W/2 4.09 -(.OO 9GolW fv= 2MS7 e I 4 4 AUTHOR DATE CMK*D. S Y DATE CH K'D. B Y DATE REV. c' E V. NO, DATE WESTINGHOUSE FORM 55213D r
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TlT L E PAGE OF = P ROJE CT AUTH R DATE CHK*D. BY DATE CH K* D. B Y DATE FPL A %t 9 wnt&rz/t 2 S.O. C AW N D. FILE NO. GROUP FJIP-93tm CHE WELD ETREE CUE j AP/l2 i ,s TO T W I W I N E *' k '.389o(i.H50)/IR ,Q G B2hg C CNSI DE rs S Q A L E F. Gtt%% = to Aor o G'r c o s tt Y\\ VJ p,.= (9.go'f +3,qcP) = \\O.MO9 i
- H1Hlf
' '"3V i me%mmmm ^ T war,m.a ntw s cewur zuw:.t em:w [y ! {t ; ;,h V ~ ~ k = 4 $0'eStu 6.is9 s ic40 0 y l 'l ((o9I'2in" b s.s5* I 4 J = 9.s 2 --+; = )g = 5 61% kO.9'7[/12. % o, t,nove 2 O Co.4 in ' V = W /3 = Pl W/3 + 9.32 = 825,067 in lb ,=rwu a -tw t me %xms ) q1 =. ((10.98s -3.B o7)* &. 3.99. : us5 ctwitt cs swaTi er wrto ts too p : Jg,= 4(2o:,.9) - 9(s.uls,)gsss)2-j racm : m..mTar c5 m we6o tocar h-11 [Q%n* y = G.98 / 2. = 3.9 9 A,f = s.seh=2.A d - l (o9.I ?.+ 1 il O.1 :. l'2.7 9. 5 2 / X = E k 3 [ A; (mm e ~ A, - 1.nso (, aa s.7cn ) =.us' .fv = Mr/J sJ 87_S,c67(d /1279.5 x,= 0 i, = A. '2.o,97 f.1'a =.707) = s.t.3 %t GtJ4 8t .x , o.' x2 20.97 /2 - lo.HBS A rro, e t m rr can e t m t e r mtw = H Ty pE. 1 t.o t s.05, % T'v pir. 7. v.re tos Dots Nor %ny In vt ~2 crtstTrow so r4 ( 3.99 + (2o.97-9.so7Y)"' T = 9(. sal (o) + 9 (s.cnkimes) 2 it.70 A 9 ( 38 % 4 s.ess) = i X = 9. so 7. A f,, = (,W.Bui.90) '7 p h [ [ ns,-n ~x,~~~ l J - Jo + Ae = ~ms, l j, r, was % w ca et b y # qiu A3 c.C A u>c M 4. O c. (s e e u c te met. c u %ettA *r os spotti j [ f gen;t.) of & egoop te.:<3m oc n oc~t mm.m o CW t & bs AUTHOR DATE CH K'D.SY DATE CH K'O. SY DATE REV. REV. NO. DATE WESTINGHOUSE FORM 552130 l
WESTINGHOUSE NUCLEAR TECHNOLOGY-DIVISION TITLE PAGE I.NTE r. N ALi LT F TI N LT RI (: r .32 o,39 R DATE CH K'D. B Y DATE CH K*D. B Y DATE i PROJECT AUThHA rgt. 9MwA n/fs i FPL y S.O. C A Q. NO. FILE NO. GROUP j FJIP-924 47 C.RE i \\A/E LD S.T R E3.' DUE I.-a s TO SHEAR F LOW g_. _ em+g y. n _A. I B** THE WELDS ALdo sie, SrcocaONty = _Zf srntsst s eaz To s amrs F LOW @ .t.__ 3 03 o* .-s),p.--.- f, = \\/ay /14. 2 L.3 )+ acis) 7 /12 Y= earns 0 Nedi[c I shc.r on kram '+ 2 (.73) P,*/12. C Mit o & + ire.uS - 3.O(o ( 7.od,2/l'2. f
- 3. = tv.,o w d o i
b acanu d ua.L e. pn, -( fo 4 M(.75)-2.oi)( 3.o1)'/I 2. j whm h 6 se_,61 = I 77.2 8ina a - Brea of v.d 5, 1.wra Pic % 2 M A 'AIS-2.-1 v f u nc~ s.w m ac,La i,;- q(.7s) t.s o im. = o 3r *R a = 2 (.7 5)(.50) .7s w .-d h cfeA-C y f ar_a ttwM mr, of ) b y 3,s +.30/2 =. 2.7 s% o e-m wm .(,_,. (w/3) *. is ms /tu.i7 /t.so M src 8-A \\/ = w/3 - W(.cos is 8 ) a-e V: W/3 \\,3 4 ire c.- o \\/ = Q fy, = w/2 +.7s + 3.7s /n7.u/i.so
- I.* y
.7_ L - w(.cozs2.s ) ez., .c co* 7'/R f .o = 9 l 7 esr 4 m :- + 2.(.,s X 3'/11)
- m. m wm e re. :s
~ _s, - _, ) L-so. - W M / l ?_ F = fv t F.s - 2.01/2. a /6 3 i ~In-S = 1 2 1.1lih" Fea-13 7 (o lbAL El(2 l.nl.,m)) = 3,W5 c= G = I2) 7,['l.'po.,e(.ssy.m]=12BO+: l tc. t:, n,n m o r.1.u.- i-i U I4GL LA M C, W t LCJ t'4 c m ytJCATION I PLGt 2. co -2 AUTHOR DATE CHK D.BY DATE CHK'O. B Y DATE REV. REV. NO. DATE l WESTINGHOUSE FORM 552130 l
r WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION IT8TLE PAGE 1 I NTE RN AL5 LI1:TI N LT RT 6 33 OF J S R DATE CH K'b. e Y DATE C H K'D. S V DATE F PL AUTbHdfb. 3 givda/f1. P ROJE CT S O. CA Q. NO. FILE NO. GROUP COM BININ C.:r ( ** %"- 1lf 0%u srREM,ES IN WE L D.5 Tat sTxmt > r~ +cmr wims A Rt. W %IDiTWD SkAR, STRibbu i ANaO M W L.n GL % 0 C>t O ALtADrAIIhu.4 AT rHE. E N D Q A "I H( $ PRtApt rt Evi $v% (3,,g+ fy(%aggeu = '7, s 4s e 2 't 9 7 = b' lgOH2 y AT sEc A-x c k=G % m j 4. m o<9 (> 4t 4 A. F LOW) i V(TLuZhTIN W c = (2.w + [ie.9d" 4.309]'),' r= 7.531. fvSwrmwg = 'd M h PbI f l Gs - Y8 % + M.17+ 3 24s j -(t lI,O 9 D F5I = (1) SCE SVWC H PAVw 13. f l AUTHOR OATE CHK'D S V DATE CH K'D. 8 Y DATE REV. REV NO DATE WESTINGHOOSE FORM 552130 l l
7 ) WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION + .\\- 1-TITLE PAGE I_N 1 t _ R N /hL5 LI F TI N Cr RT ry 3 g c, 3 9 R DATE CH K'D. By DATE CH K*D. UV OATE p' AUT hH % 3 1u n, 4 A // 1 PROJECT FPL S O. CAL 4.NO. F RE NO. V GROUP F J T_ P-9 5447 G H E t [ s r m ....'s_.- m NUT .d' i (LEQr) ADAPTOR-SPEEADI R l n (tecAouraajuea i
- i.
t F I $ - II' (LE6 LEVELIN M SLEEVE. / GOU PLI N(:r 4 O (.iuPPORT RIN(2)LEVELIN(:r IVFPoC L4* LT SLEE VE @(sueecrsr nrwe) l 7- - ouran rust l l-a.. u =ce r - rs1 8 e j' l d h C7UIDE ELE EN E_ l / s } i / r y T r a TT. R N N.E W/ s i / AUTHOR DATE CHA'O BT DATE CHK'D. B Y DATE REV. REV. NO. DATE WESTINGHOUSE FORY 557130
p WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION Ti1LE PAGE i INTE R N ALS LIFTIN Gr RIer 35 OF39 H K'O. B y DATE CHK'D. B Y DATE P R OJE C T AUTH H DATE FPL % (%Cn/f t. 5 O. CALM.NO. FILE NO. V GROUP F J IP-9344 7 C H E_ AvA tr(3.91BBXl.B)/2 -9(S9) NU1 15 = 7 ?_ s 9 i ' .C'y = w/ 3 / ?.25 9 t1 A T b - W (. 04 3 9 2. ) ASTM A-27fo, TY PE 304, f= 1i,939 PET. v H. R. 4 PK LD. COND. A EEARIN tr ON S PACER. BLOCK (ITEM ) y,33 4 e /^,"m w=%t fc=. P / Ae =(Wh)/Ac ,.3,. W'! k M 'i" Ac =li(9.98-ava/Ts)* fra 9.OG'-J is!,p f.2<.-E.3 cog g 3,99%t t i 4 ae:ves fc - w /3 / s.99 4 ca -nae c 4 m 34_3
- w (.oss6t)
Ec = 14, H 5 9 es.t 4 P g y TH FS. A D SHEAK' -fk P/Av =(w/3)/Av F s Tr De 3/2-4An Dg-D3 . cow ss2/n = 4. coo.ms 2 /8 =- 3.9 i 8 8 ik An= A e.2%.so =.o78 i AUTHOR DATE CH K'O. S V DATE CHK'D BY DATE REV. REV. i NO DATE V.ESTINGMOUSE F ORM 552130 i ,,I
.n lD y. y 4m ,l _ I WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i 4r ll i P A G L' IN I t.RN A Lg L.I_ FTI N 6 rsICr g3 L.3 S TITLE DATE CHK'D.B* DATE j P ROJE CT AUTHOR -A DATE CbK'D. Byn i d, vf _e' FPL %,duAtu % ) FICE NO. V' GROUP / 5.0 C A LjfC/40. e FJ IP-93447 a. GRE. gg '[ MAT'L: { ( LE c. ) LEVE LIN tr SLE E VE - MTM A-2.% Tyrr. KH g OUTER TVEE sn< exto.c.one n. j ASM M E LY 8 CE OU ER TVEE - AsaM A 3)2. 79rt 304 re. ap ggmus c r Awo aT. . _> f t o0,,+. 6 t AD APTOR - As TM A-?.%, T't i:E. 3.09 y - -I r ~ H. R. ( P K t o. < omo A.
== l 9 CC3. Bur 4 -2 A (,. ( trG) ;. (LE G) ADAPTOR. gg i g g AouTes (G M .__ 3 % 4 TH RE AD S HEAR ' o .5AM E Ab yon TH E nut (ITE M I6 ) M.N r i Py= W (.0W9 2. Y i EC E = \\\\, % 9_ nr 3 ~ _ - %
- [
-l 'RNS. ION AT THREADS i fg = P/At = (W/3) / At I i hn, s.co m,, 4 = 3 (D.,c,ng3/nf_ @cd l etT>nt 1 3 py i [.(s.zo.9m/s)'-2.'o 55. s.%o 6 = w/3/ 8990- w (.039 31 ) Q'Q 4 - 1 0,2 2.I wu h l ggyd (LEG) OUTE Ps TUEE. i l l 7'"' O i:NsION
- 1' fe = t>/ Ag =(w / 3) / A +
{ im .C 64= 8.H O W (v eos tv u d w u c c e c e i h ~ 'l 6 W/3/B.90 = v>( 033' gy o 1Q,3\\F1 rg p c.Go & pg __+ / ,a a tMt% - i t ( GM F - I l LLttyt I LEVELIN Cr SLEEVE (lc3] 273 ] {,j 34 s b TENE. TON AT (s.Co O C I. A eco _ y g., t,J*, h e P/N = (w/O / A e ) = 2'7.0 5 y= 3 ( G.GO - 3.Op LEVE LINC7 SLEEVE THREO sugar, S, t W/~6 / 27.05 - W (,o[2 32 3) 7tiRcAD SHEAR n Twu.m. As von T s.e. E 3204 esr-C,OVPLt.N G-(,I. TEM ) 3= .fv= M/ (.015335 )= 3 9 O N AUTHOR O. ATE CHK*C BY DATE C H *J D. B Y DATE REV. REV. NO DATE WESTINGHOUSE FORM 55213D 1
V WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION T4TLE PAGE i I.NTE R N ALS LIFTIN Gr RT_ Cr 390,39 DATE CH K'D. B Y DATE DATE C AUT HdC Ai )#.A Wu-hK'D. B Yni tdu/fu P R OJE CT FPL S O. CA @.NO. FILE NO. GROUP F JI P-9344 7 C H E. (SUPPORT RT N Gr) y COU PLT NGr \\9 LEVE LIN6 St.EEVE 9.cz s4 M AT'L : k (ti ASTM A 29(o TYPE 304 f., m ]d)*,,, %) H R t P K L D. COND A. erem orN
- 2. coo Tuc.
.._ -..o i rwn OL cr TMrs.L 7096 c4 ow t M.* ss et (.wm raon I l ,.oec bs.n swwmiotv owq ) 1 I h i l /A Tt E.37 $ -l/ g 9 rw o ntstre ( M j h 7.cc0 - bun -23 #' s.s2-n vu 2 A. [L"s'l,j't 2.* s Ove; M AT 'L. TH(E AD SHE AR ON 7.O'O CJN Th D. ASTM A 312. T Y P E 3 OH s ve.a. A:. w te 1.nc u v a a..i.e. 5,M LS GF ( H T T R. (ITtm l9 ) fv = W(.0\\ t32 5) '3989 -fv = cu THRf:AD s H E A R. TENiJON AT THD RELIE F fy = P/Ay -(W./O/Ay 6: F /N = (,w/z)/A t A -% ( 5.37 - 3.022):is.ssu 2 Av = Tr Dp _1/2. t D = q . co4 9s 2. /n fe w/s/ts.sas = w(.o2 t 53 ') e
- 7.000.(otf 952/8 = G.919 A 6 = 5 5 9 '3 est Ay n(G.919)(7.00)/2 : 21.7 H THREAD LREAR ON 5.500-QLN-i80nL 4'v = W/3/2.t.79 W (.otsus) p,.
pfg,,(w f3)f g fv - ~S987 A,.,r q.pf2. m Dp = El.G652/n = S.500.W95 /'t. TE N5.I O N & TMEAD Rrutp f5 = F/N = (w/5)/Ae f = 2.se.2 s.is = 2.o% A B/d5'-1042)- l 9.2,79# Ae n (s.s..msz/n.)(7.co)/2 = n,gna b ' )(/3/19.779 : Wl.00290) 4 t*W .fv' = w/ 3/17.G22 : W(,oE9ie,) 4= W495 P:s G H 918 p: AUTHOR ,DATE CH K'D. B Y CATE CH K'D. B Y DATE REV. R E V. NO DATE WESTINGH USE F ORM SS2130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION I i hLE PAGE } PROJE CT AUTH DATE T NTE R N ALS LIFT _TN Gr RICr 39 D, 59 DATE CH A'U. H D DATL FPL A n/st. ChN'D.svt a4LAt 50. C AJ. N O. F dE NO. 4/ GROUP F JTP-93WF/ CeH E i ($FFORT FJNG)OJTERTUEE gg TENSION AT THD. RELIEF .fi = P/A - (w/3') /At Aso t A =[% C wozs'-s.ss') GrUI DE. ELE EVE 22 l0.279iL'- i MAT't. (suerorsT arne) oorraTuee f = W/3/10,27 9 l i W(. O 12M 3) ALTM A 3t'd. Tf Fr SOM St1LS C,P t HT. TR. = f GUI DE SLE EVE-k= 6 L\\ 3 2. PSI AST M A '?.% h F E 1CH H R I F%D.(IN D A, { j_ _ r "* - '~ * -" T ENSION AT W EL.D I !/'i?nT# (, P/A =.(w/3 )/ At E.,,.3 i A =.utsosurt= 13.33 ia 4.: c e, =,- i i s se r 26 m:2xa [ G ~ w/3A3.33= W(.02501) s ~ TURI")*~' ~ f+ ' &_5 02 esz ~ s 1 sewo' .h,,) G.dIDE SLE EVE. s \\ v,w ne e <t /[ . s ,-.m. ei i M 5 1." M $ 3.) EE Nu.NL, ON EN6N !Nd. (J r w / / .;;. - P/Ac =. (w/3 '; / Au A< = Ufi.9 e-u.:nf- [m.,,0*, f. 3 5 6 6 i? { 1 c .(= W/3ho.3583 W(. o S 2 4 2. ) = bi3,c29o m Nryi1NAL conFh JON GELOW E N 6 A 6-I N ( r SC.R E W (SVPPORT RIN6) OUTER TUEE y fe= F/Ae.- (w/3 )/ Au Ae[(e.is3. cxsf-z. fos 2 3% lo. sos.. rsseAc ssaArs ~,-.ene ~ ~c.v. -e n enu,-e n, = w/3/1o.509 - w.osm.,,j s - o,. . T,H. c. m,-c os m,.z o ). i-P 1 %ne rus o.a.c cnre 5O Sf ) ( = \\^/ (. Of S 9 f fo) : L-l 813 Psr = t AU1HOH DATE CH A'O B4 DATE CHCD.si DATE l REV. REV. NO. DATE WESTINGHCUSE FORM 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TIT E t PAGE 1 T_N TE.R N A LS LIF i.t.Ner RI.Gr 29 o,23 PHOJE CT FPL AUNTHea A ry t. % mgf.jf R DATE CH K'O. S V DATE CH K'D. B Y DATE g z s o. CALC No F M.E No. V GaouP l F J I P-9'399 7 G H t_ BEARINCT ON GUIDE SLEEVE 23 EN & AGIN6 SLREW Tut utAaruw u nr_ss s - t SAME Ab THE P.E. ARINb $TREkh M AT'L-en Tse euteE auve (tun 22) ASTM A-2.76 T'vps. 304 fc = W (. O s 2 M'2. ) H R 4 PK LD. C ON D A, fc, = I 3, b 2. O MI undron xt niurnum uctron f
- P/At =(w/3')/ A t
t A = % ( 2.8(o) = fo.9 2 4 0 [ i t f fg= w/ 3/ G.424 s W(.os i B 9) = . co,5 ( - l 3, H 91 1 "'"" ' vs:. 1 i Tb RE AD SHEAR
- .9a 4 fy =
P/Av = (W/3 ) /Av Av = iT D.S/2. r D = Ds . w9s2/n e 3.2so, Gs 9s:/4 3.OB E = i 1664 ) 3.9 6 ik i j k A y-Tr.(3.os w h 3.s B /2 L' 'i 1
- 16. 9 7 8 th'
= fy = w/3 / lG.B 7 8 L u so - 40eu.-2 s = W(. Oi9 7 50) [ -fv = 5135 est AUTHOR O' ATE CH K'D B4 DATE CH K*D. By DATE Rt V Rt V NO DATF WE STINGHOUSE F ORM 55213D
- )
i APPENDIX C DETAILED STRESS ANALYSIS - REACTOR COOLANT PUMP MOTOR LIFT RIG This appendix provides the detailed stress analysis for the Turkey Point Units 3 and 4 reactor coolant pump motor lift sling, in accordance with. the requirements of ANSI N14.6. Acceptance criteria used in evaluating the calculated stresses are based on the material properties given in section 5. .L 5887B:1/122882 C-1 I
r- - i SKETCH SHEET etstenswowst FCIw S4202 S'C' .A0 JECT . AGE FJIP-93447 Turkey Point Units 3 and 4 1 20 y CALCULATIONS h0. R. C. Pump Motor Lift Sling PDC-
- b'"C* g [ g 4 L 1_
/ CntCato ev & catt <^ J. M. Matusz hl44 % /2/s2-M. F. Iankinson ,o.,0,E A0.E m,,, i i 1. The purpose of this analysis is to determine the acceptability of this sling to the requirements of ANSI N14.6. 2. The results show that all stresses are acceptable. "A h+ .tcisitat'. O, sw\\,,,as10-E 4 / N f) c M 'v syd ' MM / [k l l 1 l l l Original Issue M. Hankinson l l REVISION NO. DATE DESCRIPfl0N BY 4tsgLT thG ACPCA?$. LETTras os utuonANDA l l l l l
i WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION 1 1 PAGE TITLE 1-05 20 R. C. Pump Motor lift Slina PROJE CT AUTHOR DATE CH K'D. B v DATk CMA'C.89 DATE FPL/FLA ///. [ 7 d d + " M i-9L44V d %I'-[T" S O. CALC.NO. FILL NO. GROUP V FJIP-93447 CHE MASTER LINK @ @ SLING ASSEMBLY "U" BOLTS f I i i @ SPREADER ASSEMBLY l l @ SHACKLE ' } B j c f @ TURNBUCKLE gg E /t b t e _ ATES s, l @ SLING HOOK i 8 i l 1 i l AUTMOR DATE, CH K'O. e v DATE CM A'O. S v OATE REV RE V. NO. DATE WESTINGMOUSE F ORM $5213D
m WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TITLE R. C. Pump Motor Lift Slina 3 or 20 P ROJ[ G T AUTMOR DATE CHK'O ev DATE CH K'O. g Y DATE T. OMwY 3 W M/t/f5' FPL/FLA S O. CALG NO. FILE NO. GROUP FJIP-93447 CHE i De.Styrn Wtl hi f or ((.E. Mot or $ ( g ny weight of Motor - 6 4 000 +e n,ooo (bs. 3 Wetg ht of Sling Assembly - _ t, o oc lb s. 13,0 0 0 lbs. i Pius to*io f or contingeocte.s 7 30 o lbs. 10, 300 lb s us e. TI,000 lb s. Which is rated lif t of Sitng { 1 Eor design Wtt9 ht-l l l i l I ( I i AUTHOR DATE CH K'O.SV DATE CH K'D. B Y DATE REV. RE V. NO. DATE WESTINGHOUSE FORM 552130
i i WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TITLE 9 Or 20 R. C. Pump Motor Lift Slino AUTMOR DATE CH K'D.BY DATE C H K' O. B 4 QATE -ROJE C T W-Mndi "Ma 9 Uw WM iL/ Sv FPL/FLA fa L E N O. GROUP 8 CALC NO. 5O. CHE FJIP-93447 I Establish TenstoE Velve. In l Tripod Section of wire % ope Tmax 3 A l 8 I 8 4' = s* f K.:M \\ / q'f we$ect l End l konserv.I n.15 .i ,9 i bied Lt + wetght of RlG = $1,000 ( b s. t w: wi% no information to the controty, assurne toad is i i a pproximat ely c. entered,i.e. P = Tension in e.ach verticat ro pe = T ~ = $1,000 lb s. / 3 = 17,000 t b 5, e = c.os-' ! 91.15-L\\ =. c.os ' [ 30 s = 43. b fo* (M5 t9.15/ . (5 %.15 ) Tm= E l 5 \\n e = rimoo t.b 9 03 = 31.109 tbs. AUTHOM DATE CH K'D 8Y DATE C H K'D. B Y DATE
- REV, REV.
NO. DATE WESTINGMOUSE F ORM 552130
r WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TIT LE 5 OF 20 R. C. Puro Motor lif t Slino P ROJE C T AUTMOR DATE CH K'D. S V DATE C H K 0, 3 % DATE FPL /Fl.A W//7/a d - 'VA 9 W6 IMTA-V 5 O, CALC.NO. FILE NO. GROUP CHE FJIP-93447 S PRE ADER A SSN. PH v k/ A y x' N M O I I PH 9% "g E H dortiontal forLt on,6 endtf (S ee. page 4) = Tm c o s e = 3%Io9cos ('G.bbi = 1% V3 tb l L et Fc. = compresstve force. in s pendec 7_ F x'= o : 2.(.7 60 Fc - P H = 0 f F c. = to 43 = lb,335 lb 2(.f 60 i For Lt" S cH '10 PlPE o 0 = 'i 500 wall =.137 " 3 I D = 'i. 5 0 0 .237 X 1 " 'i.0 >_ b " A = A KE A = "/'t ( 9.5 - 't.01@) : 3.n 9 d 1 l AUT MOR DATE CH K'O.SY DATE CH K'O. B Y DATE R E v. REV. NO. DATE WESTINGHOUSE F ORM $52130
U i WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION I PAL.L TIT LE R. C. Pump Motor Lift Sling b OF 20 PROJECT AUTHOR D TE CH K'D. B Y DATE CH K'O. B v DATE FPL/FLA W /.-7. h / C ' / L- %tAA A J Nf6 50. CALC NO. FRE ho. G ROUP V ll FJIP-93447 CHE I, l The. c.ompte ssive stre ss is &c. I =. S t 9 b p s i l f c. = tLuc ib t 3.179 in For ASTM A tob Glb f: N ie. l d st r. = 35 K si y fu : ultim 5-t r. : 60 K5 i Chec.K compressive q{lowa ble. Q From 4tst co0E S EC, t.5. l.3 4 i c c. = 3 Tri t U siq1611 h9xioboc0 I I F) 35 000 ps t l 3 l = l'G, 79 .k. = 71.43 in I bend = _E._-( d 4-d7 ) = _H.h.soo 4 _ 4.016$ = 7.1T2. In1 64 cs i 1 l f= KAD. oF GNR. = 11M =
- 1. 510 A
3 17.4 AUTMOR DATE CM K'O. B y DATE CM K'D. B Y DATE A REE NO DATE WESTINGHOUSE FORM 552130
r-WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TIT LE 7 05 20 R. C. Pump Motor lif t 511r.Q AUT HOR DATE CM K'O. Bv DATE CM K'D. B ' DATE i %. 044 =, YA 9kkF 4 8YY" PROJE CT FPL/FLA CALC.NO. FILE NO. GROUP 5 O. CHE FJIP-93447 e For ideal f u<a e.nas, K .s This Sy mmtiric Cn5E p ro bably approaches K=.5 j l i Vst K =. b5 f or conservativis w1 11., =. 65 l ll.40 = 3o.7 5 4 Cc. r 1.510 1 i ~ l t i I k Y I ( l i l AUTMOR DATE CMK*D. 8 Y CATE C H K'D. B v DATE l REV. R E V. NO, DATE WESTINGMOUSE FORM 552130
I WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
- AGE TIT L E R. C. Pump Motor Lift Slina T
OF 20 PROJECT AUTMOR DATE CH K'D. B Y DATE CM K'D. B T DATE FPL/FLA WW4:4_ ' Yt S M4 di t/f '- S O. CALC.NO. FILE No. b/ GROUP CHE _ FJIP-93447 t s in ce LL /_ c.c_. r I Fg = Max C.omp, st cess (v u lt? VY = t-s c ,ce 5_ p T ( t 0 /r?._[t E/ r9 i 3 TCc. 7 dc, I { l - A n.7c;f y y = h ,1m1G-5 .5 4 3. (30 7 0._ h o.1G -? 3 T tri.ti 7 (m.19Y i. i
- Li-.0179 Fy
_5. +.og t . con 3 i I .0159 Fy =.5s3 Fy =.533(.35 Ksi) l.755 i M.35 Ksi j f c. 4 Fa I I AUTHOR DATE CHK'O BY DATE C M K 0. 8 4 OATE REV. RE V. NO. DATE f WESTINGHOUSE FORM 552130 g 1
WESTINGHOUSE NUCLWh;t VEC@@LTdMf7L@%$cMJ ~ DAGE Ti1 L E R. C. Pump Motor lift Slino q 05 20 P R OJE CT AUTHOR OATE K'D. B Y DATE CHK*D.8v DATE FPL/FLA @ (2Ar -,4. /VA. g % d,)2-/p g S 0. CALC.NO. FILE NO. V ' GROUP FJIP-93447 CHE A naty t.c competsdive SitC55 on Tube to Tubt Weld x/ i so- / 1 b;9'11(pa3e 5) The length of weld will be \\tngth of a half f.llipSE. t ( projtc.tiop Cf ID of~ p'ipd N 6
- a-N 5
9.5 oo L b ' b = 1.1 5 l \\ / N. / / l_ l l 4=.L' s ~=S.So in: a.b = 125 =.'533 2. Si n 1 0" a+b 6.15 1 From hacks handbook,7 TH ED. Pages 1 -t% L = Length of perinn+.'Itr of half - Cllip50- _.y1 t Tu a +b) k 1 = Vit n oa soXt oYt0 * ' 5 '" AUTHOR DATE CM K*D. 8 v DATE CM K'D. 8 V DATE R E V. REV. NO DATE WESTINGMOUSE FORM 552130 I t
F WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TITLE R. C. Pump Motor lift Slino 10 OF 20 PROJE CT AUTMOR DATE 'H K'D. B y DATE CHK*O. S v OATE FPL/FLA 'At[78u-4, /V/t-- /JVM vh M / Y T b 5 O. CALC,NO. FILE NO. GROUP CHE FJIP-93447 The throat area of the wela is!
- 1. 7 5 9 i n' 4 t = (10.91 )( il o h(. 37)
= The compressive force en the Weld Fc : lb 33 5 ( s tn 3o") = Tl b7 lb s. l %e c.o mpressive stress o n the wcld E c. : 11.h1 =
- 2. S 61 p si 2.359 in'
) Fe = Max atiowable sitess ( A tsc,7 AE0, Table 1.5.3) .c = Same as base m e ta l .LOFy .b o b5ooo) = 1t ooo =- f cc Fc i C. heck. Plate t o Tube. Weld v N 14: %5.cn = S;196 / 2530' u = y,3o N s 4 1.S 3T t 1a = s.\\% ) b 1 i 1b = 9.s i f b = 1.15 AUTHOR DATE CH K*D. BY DATE CH K*D. B y DATE I f REV. REV. NO DATE ) WESTINGHOUSE F ORM 552130
1 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TIT LE R. C. Pumo Motor lift Sling ff OF 20 PROJECT AUT MOR DAIE CM K'Q, B y DATE (,M g 0, g y DATE FPL/FLA A Ih*4--- 'V v h4td /kf" 7 5 O. CALC.NO. FILE NO. GROUP CHE FJIP-93447 m = 1. H 7 - 1.1 <: =, o 37 L.59Y t 1.15 L= f erimiter of E1\\ipse 1T (1.59Y t 1.15) K = n ( 4.T97)(1. co k) = 15.1% in s-b: l is.1%M.7 00(. 31) = 3.4 % f i nt I Fc = ( Po3e. 5) C.om p re ss i ve. t'occ.e "en W e Id .i t9349 lb = l Fc : tempressive. Stress on w e id i 7o99 psi 7 n 92 m = t 3.9 7 f in .L,o L3Sooo p si) = vooo gs, ok i: L Note 4t we assume d on pq3e 3 %qt the, fubt. -to- +ube. t.omp: ession wouid be. taken by the tub e - to-tube we td. h en if th;s force. went th rough the. 4 ub t Fo plate. w e ld the max st ress wovia be : AUTMOR DATE CM M'O. B y JATE CH K'D. B Y DATE
- pgy, pg y, NO.
DATE WESTINGHOUSE FORM 55213D m
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TaTLE R. C. Pump Motor Lif t Sling l 2. o, 20 PROJECT AUT MOC OATE K'O. S V DATE CMCD.BY DATE FPL/FLA ~B/. % d #a 4144 uuMh-/fk s o. CAtc.~o. ertE uo. oRovP i FJIP-93447 CHE Shearing s+ cess T= 1.Lk1 ( Pa g e 10) l Si4 in' ( hit of tube to Pl.. wtld) E 4095 pst c.4 7y =.1(35000) = igooo Ti 0 - 7094 I h f+9095* 1.
- 1. i
-3547 r 59l7 [ = = - 7%9 157o ps, h 3 r i,1 <.bo Ey = si,000 ps; og g,,3,3 The force. tepn3 o slide the O-bolts is the, t dif ferenc.e between the rop itnsions. ( No c-redit for f riction) This forc.e will also put the pinte in te ns io n. AUTMOR CATE CH K'D.8v DATE CH K'O. B y DATE NO.
- DATE, WESTINGHOUSE FORM 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION F PAGE TsTLE R. C. Pump Motor lif t Sling 1 3 Or 20
- R OJE C T A U T ** O R DATE CH K'D, S V DATE CM K'O. 8 v DATE N'b.b5 deWZ-S tuvM/ L/fv
/ FPL/FLA CALC.NO ffLE NO. V GROUP 5 O. CHE FJIP-93447 S(DE PLATE Te.nstle, strength of Pigte,-( Assume tdtn by top bolts) F v 6 = 39,109 - u, o co = rt, t os i b. [ 39 109 3 A= bi'xt
- 6. 6 0 int
= 7T: Tensile Stress = Esft j-A " u,ooo l 1963 p si = nio9 lb =, b.s o i n '
- t From A1sc Rui es, allowable. stre ss for members with beits holes is A577 i
CA =.ss x 30,00o = n,soo p si l FT c e4.. Ox i t l l AUTHOR DATE CH K'O.BY DATE CN K"D.8Y DATE m E V. REV. NO DATE WESTtNGMOUSE F ORM 55213D I
I' WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION k i PACE \\ I TITLE R. C. Pump Potor Lift Slino 19 or 20 PROJE CT AUTHOR DATE C K* D. B y DATE CH K'D. S v DATE V JMi&Mi L/f V 4 EMJ%f A / FPL/FLA 5 O. CALC NO FtLE NO. GROUP I CHE FJIP-93447 l \\ The, foDowing items gre bought from sitn3 Suppittrs per the referteted drawing. Stress C4\\culations are not performed since. materiot requirements are, i for most LTtmS, Unkn0WO. 1 The attached bili of Matettals desc.ribes these l t stems with the. Available information and lists design I h loads togethte 'Anib ihe catato 3 d (or drain 3 f, .t i rated loads. i i i i l i 4 AUTHOR DATE CHK'O BY DATE C H K'D. B v DATE RE V. AEV. NO DATE WESTINGHOUSE FORM 552130
r WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION d PAGE TIT L E R. C. Pump Motor lift Slina 15 or 20 PROJECT A U T *= c a DATE CH K'O. 8 v sOATE CHE"D.B' DATE l FPL/FLA W (h ,4_ 'Y/i 3M4 d /L/f1 5 O. CALC NO. FILE NO. GROUP FJIP-93447 CHE z W in C g a o y 3 h h t O E l @ <D ~ qy= U.1 O $ y M e4 p-Q i a>a w 3 d[ 3 c 0 o o G v$ c o o o W G p C o o o O * =f t 3 O o' g' ~ H-s va r-- ,o af. J > v Z esM8 ,M M f & = w o'. y V
- lr-J-
p in a U f = a s m .9 ~J - O _ _3 y 1 -I s (,. 3 e.c V 3-i 42*g O h 0 C ad n f o o 5 g "o a-a e (H G.D9 o?,., LA V l 0 o 41 e y V ao V Jo V =- g C .g t g 2 d h eo e ,s e n o dd O.' t 5 E h Q W ) a c' e3 v$ V32 J *c y ': h h-8 .<ar - ) C +- U ."C V
- :O 5
t OP
- d-3
'J m -o = o.+- g. e e e, -j$ "o ij ~_ 5.3 # tLFe5; a, e n(
- y._E A &_ _+ 2 2m E
E, s uz.v = r e x x o ) '~9 p-S 5 1~ 7 ':> 9""" a
- < g W
M -4d d O 7 dJ =5 w d p- =o 8 S w e g en C e r+ a v c o Z W 2 O c-o)
- 5 5
5 W g Cw o c f c2 t O 2 _p E o T a c V.b d 4 0 c 2 C .C. 3 e o C a Z sn m l-3 = 1 2 ts. s r-t c O en '2 sL AUTHOR DATE CH K'D. S V DATE CH K'D. B Y DATE R E V. R E V. NO DATE WESTINGHOUSE FORM 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION f PAGE TIT L E R. C. Pump Motor Lift Slina i 6 or 20 i PROJECT AUTHON DATE CH K*D. B Y DATE C H K'D. S V DATE FPL/FLA WeX7du.-, "//L 9 144 /2-/f2, ) 50. CALC NO. MLE NO. V GROUP l FJIP-93447 CHE G z a o d Jcz o 4 3 0 0" a v f Of o Q re o a oW f N <0 <s"3E r/)- eJ>g
- m O
4 z B m 5 -4N Y .g h . E _c d OC o 3 o," s ~ 7 C4 o LJ .c ggm-Q J Q 'C s
- x c l.s g
ra a !; r I o o 2 t a r l .e w '3 l 2 O cC d J d J pa ul W A C Y O r d c u-o oz, o W O _t 3 r c a e U a y 8 - c0 { ac Z l p d O 4 e o O O Z +- C pl r Z d 5-c~ o o 2 u-AUTHOR DATE CH K'D. S V DATE CH K'D. B Y CATE R E V. REV. a NO DATE f WESTINGHOUSE FORM 552130 i.
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION I i i PAGE TaTLE R. C. Pump Motor lift Slina l7 OF 20 PROJE CT AUTHOR DATE CMK'O. sv DATE CH K'D. 8 v DATE FPL/FLA 'NT% d = "/2 h l44 dit/f t / S O. CALC.NO. FILE NO. V GROUP FJIP-93447 CHE LIOT:G : T A B LE I (1) See pag e ?_ for tdeniification of item no.85 6.) D e sc ri ption is f rom W estir.S ouse d to.wincj h AE0 SK 6lf J 644 TXtt SUB 3 (3) Actual purchase order c, hang ed link to li " t 9 )( 16. (9) S.G.Tay tor tha;n Co, lnc., Bulletin As-Vi alloy steel chain ass emblies, attachments. 1 ~ P' nnsylvanig Sting Co. [ (5) e 1 l (6) Crosby Group, 350 General C atalog j une. LUl J lm Rate.d. load value The maximum rec.owimended load that should be eXected enthe tttm. The following terms cut also used f or the ierm I R,at e d L o ad. " 5 wl", "Sxte wo r kin $. oad ", t
- 5afe,
wo rk; ng L oad Limit"j an d ihe. " & e suttant Working Logd " Att caied load valufs are for e in-line pull with respect to the. Ctnierlin ef th e itt m. In f o r m dion is f ro rn c.at alogs i d e n t i f ie d in l'O,(5) ;( 0. (D in formation from c.qtalogs may not b e, identical 'o thai Which l's INStA LLE D. WOtuSVB.'R, THis sufoAmAng/ M A L L. TMAT-is AVAILASt4.AWD if R GF4GSGVTP DVf. I AUTHOR ,DATE CH K'D. S Y DATE CH K*D.8Y DATE RE v. REV NO DATE WESTINGMOUSE FORM 55213D -)
7. WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE UTLE R. C. Pump Motor Lift Slina lf or 20 PROJECT AUTHOR DATE K'D. s y OATE CH K'O. S V DATE FPL /FLA W 774r--4, '28' n MWMAAL/fv s o. CALC.No File ND. U GROUP CHE FJIP-93447 woTF %', C.ontinu ed (9) Inf or medion from the note 1 drawing states! saf e worki63 oad of ibis slin9 assernbly l Th t \\S Tl,000 lb and a saft1y factor of 5', (" 6 AUTHOR DATE CH K*D Bv DATE CH K'D. B Y DATE REV. REV. NO. DATE g WESTINGHOUSE FORM 552130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TITLE )q or 20 1 R. C. Pumo Motor Lift Slina CHK'D.SV DATE [ ATE AUTHOR DATE CM K'D.av PROJECT 'M/M- /2g g, g4 sfg p FPL/FLA \\/ ' Grove F tLE No. CALC.No. s o. CHE FJIP-93447 Tht. Cated loads of att ittms are grenitt thar. the design loads. Cat 4lcg tnf ormation on-thE S ling IS S petgal Sting, c utstiona ble, Stnct iht desseU t$ 4 Howtvet, reviewin3 +we. eewc.o son 3 coato3 c.circa is,5) shows that f or 3 l eg s, l if t angle cf 45 b X F7, i A. Dia. 3 I
- 5 / 0,400 fouv05.
bridlt Siin3 ) iht Sqfe, Wothing LOAD 5 g (Lglest ca.talog information (tm) States th e 5.W. L. CnMnt.oG l's l4,000 pounds.) tiowever, this. (Sling rating enay. not be f or the special monufaciured sting described on the W drawin3 The W drawing states ihat the l S.W.L. for the Sting is Tl,000 tb with a saf ety factor b wiih a ptoof ie st of 41 +on 5 (9%,000 pcunds) of 5 '. i at assembly. For compacison the ANSI 6 5o.3 -R11 sting 5 3 table 7-for 3 te3 bridte stinS 3 bx31 IwRc3 11" Die, AUTHOR DATE CH K'D. s v DATE C H K* D. 8 v OATE PEV. REV. i NO CATE WE fMINGMOUSE F ORM 552130 m
r q PAGE TaTLE R. C. Pump Motor lift Slina 70 or 20 NOJECT AviMOR DATE CM K'D. B Y DATE CMg'O By DATE FPL/FLA TMMas Trt. )M4VMk idD-i C ALC. NO. FME NO. V GROUP S O. CHE FJIP-93447 45 degree, nngit wit.h nitchanical Splic t rgii gg is 37 ton (.7 9,000 pcund). The, proef lead (, Section u.3.1) 15 twict the Single leg vertitgj capac't y vJhich IS (Tabit 0 17 tons (39,000 pounds). This table. 4 valve, t indicates that Yht Sik Ag5 are. O t t e. i? to b l e, I .i AUTHOR QAT{ Q.M K D. S V DATE C M K 'D. s v DATE REV. REV. NO. DATE WESTINGHOUSE FORM 552130 -}}