ML20151R713

Rev 1 to Evaluation of Acceptability of Reactor Vessel Head Lift Rig,Reactor Vessel Internals Lift Rig,Load Cell & Load Cell Linkage to Requirements of NUREG-0612 for Indiana & Michigan Electric Co,Dc Cook 1 & 2

ML20151R713
Person / Time
Site:	Cook
Issue date:	03/31/1985
From:	John Marshall, Sandner H WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML17334A943	List: ML20151R713
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR WCAP-10230, WCAP-10230-R01, WCAP-10230-R1, NUDOCS 8602060201
Download: ML20151R713 (168)

Text

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i WESTINGHOUSE CLASS 3 WCAP-10230 Rev 1 Although information contained in this report is nonproprietary, no distribution shall be made outside Westinghouse or its ~.

licensees without the customer's approval.

4 EVALUATION OF THE ACCEPTABILITY OF THE REACTOR VESSEL HEAD LIFT RIG, REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL, AND LOAD CELL LINKAGE TO THE REQUIREMENTS OF NUREG 0512 for INDIANA AND MICHIGAN ELECTRIC COMPANY l

DONALD C. COOK NO. 1 AND NO. 2 i

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! MARCH, 1985 H. H. SANDNER, P. E.

Approved : .__/_m-4 J. i. Marshall, P. E.' Manager

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Component Handling Equipment WESTINGHOUSE ELECTRIC CORPORATION Nuclear Energy Systems P.O. Box 355

• Pittsburgh, PA 15230

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ABSTRACT An evaluation of the Donald C. Cook No. I and No. 2 reactor vessel head and internal lift rigs, lead cell, and load cell linkage was performed

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to determine 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 demonstrate compliance with the intent of NUREG 0612 and ANSI N14.6.

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8435B:1b-020485 iii

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ATTACHMENTS Comparison of ANSI N14.6-1978 Requirements for Special Lifting l A.

Devices and the Requirements for the Reactor Vessel Head Lift Rig, Reactor Vessel Internals Lif t Rig, Load Cell, and Load Cell Linkage for Indiana and Michigan Electric Company Donald C. Cook No. I and No. 2.

B. Stress Report - Reactor Vessel Head lift Rig, Reactor Vessel Inter-nals Lift Rig, Load Cell, and Lead Cell Linkage for Indiana and Michigan Electric Company Donald C. Cook No.1 and No. 2.

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TABLE OF CONTENTS Section- Title . Page

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ABSTRACT iii

1. INTRODUCTION 1-1 1.1 Background 1-1

2. COMPONENT DESCRIPTION 2-1 f f

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

3. SCOPE OF EVALUATION 3-1 3.1 Study of ANSI N14.6-1978 3-1 3.2 Stress Report 3-1 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 Recommendations 4-2

5. CONCLUSIONS 5-1

6. RECOMMENDATIONS 6-1 1 8435B:1b-O'0485 2 v

LIST OF ILLUSTRATIONS o Figure Title Page

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2-1 Reacter Vessel Head lift Rig 2-3 2-2 Reacter Vessel Internals Lif t Rig 2-4 f

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REFERENCES

1. George, H., Control of Heavy Loads at Nuclear Power Plants Reso-lution 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. Westinghouse Drawing 113E529 - 4 Loop Head Lifting Rig General Assembly

4. Westinghouse Drawing 113E479 - 4 Loop-Plants lif ting Rig Internals -

General Assembly 4

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SECTION 1 INTRODUCTION

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The Nuclear Regulatory Commission (NRC) issued NUREG 0612 " Control of Heavy Load at Nuclear Power Plants"Ill in 1980 to address the control of heavy loads to prevent 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 handling 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 "American National Standard for Specia' Lifting Devices for Shipping Containers Weighing 10,000 Pounds or More for Nuclear Materials".I 3 In general, ANSI N14.6 contains detailed requirements for the design, fabrication, testing, maintenance, and quality assurance of special lifting devices. The Donald C. Cock lifting devices which can be categorized as soecial lifting devices and which are cortained in the scope of this report are:

1. Reactor vessel head lift rig

2. Reactor vessel internals lift rig

3. Load cell

4. Load cell linkage This report contains the evaluation performed on these lifting devices to determine the acceptability of these devices to meet the above requirements.

1.1 BACKGROUND

The reactor vessel head lift rig, the reactor vessel internals lift rig, load cell, and load cell linkage were designed and built for the Donald C. Cook Nuclear Power Plant circa 1969-71. Westinghouse used the design 8435B:1b-020485 1-1

criteria that the resulting stress in the load carrying members, when subjected to the total combined lifting weight, should not exceed one fifth-(1/5) of the ultimate strength of the material. These items we're not classified as nuclear safety components and requirements for formal documentatien 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 instructions for the reactor vessel head lift rig which included an 4 initial load test followed by non-destructive surface examination of critical welds.

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1 SECTION 2 COMPONENT DESCRIPTION 2.1 REACTOR VESSEL HEAD LIFT QIG The reacter vessel head lif t rig [3] (Figure 2-1) is a three-legged carbon steel structure, approximately 39 feet high ant' 14 feet in dia-l 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 permanently 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 I

operation, the sling assembly is removed and the three vertical legs and platform assembly remain attached to the reactor vessel head.

2.2 REACTOR VESSEL INTERNALS Lift RIG The internals lifting rigI 3 (Figure 2-2) is a three . legged ca'rbon and ,

j stainless steel structure, approximately 31 feet high and 14 feet in

! diameter weighing approximately 14,750 pounds. It is used to handle tne upper and lower reactor vessel internals packages. It is attached to the main crane hook for all lif ting, 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

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rig is stored on the upper internals storage stand.

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 manipulator crane walkway using a handling tool which is essentially a long wrench. The screas -

are normally spring retracted upward and are depressed to engage the  ;

tapped holes by the weight of the handling tool.

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2.3 LOAD CELL AND LOAD CELL LINKAGE The load cell is used to monitor the load during lifting and lowering the reactor vessel head or internals to ensure no excessive loadings are occurring. It is installed between the load cell linkage and the lift-ing device. The load cell is a strain gage (tension) type, rated at 400,000 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 main hook to the lead cell.

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SECTION 3 SCOPE OF EVALUATION The evaluation of these lifting devices consists mainly of thrbe 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 A detailed comparison was made of the information contained in ANSI N14.6 with the information that was used to design, manufacture, inspect and test these special lifting devices. The detailed comparison is provided in three parts:

1. Overall item by item comparison of requirements

2. Preparation of a critical item list per ANSI N14.6 Section 3.1.2, and

3. Preparation of a list of nonconforming items.

This detailed analysis is contained in Attachment A to this report.

3.2 PREPARATION OF A STRESS REPORT 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 criteria are specified for this analysis. The stress report is Attach-ment B to this report.

8435B:Ib-020485 3-1

3.3 RECOMMENDED ACTIONS An obvious result from the previous evaluations is a list of items that can be performed to demonstrate to the NRC that these special lifting

, devices are in compliance with the guidelines of ANSI N14.6 and NUREG 0612 Section 5.1.1(4). These recommendations are identified in Section 6.

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SECTION 4 DISCUSSION OF EVALVATIONS 4.1 STUDY OF ANSI N14.6-1978 A review of ANSI N14.6 identifies certain analyses to be performed and 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 prepared per Section 3.1.2 and is contained in Appendix A to Attachment A. This list identifies the critical load path parts and welds, the materials of these items, and the applied non-destructive volumetric and surface inspections that were performed. (Details of these non-destructive procerses and acceptance standards are available at Westinghouse shoulc they be needed.)

A detailed item by item comparison of all the requirements of ANSI N14.6 and those used for the design, manufacture and inspection cf these lift-ing devices is contained as Table 2-1 of Attachment A. The comparison shows that these devices meet the intent of the ANSI document for design, fabrication and quality control. However, they do not meet the require-ments of ANSI N14.6 for periodic maintenance, proof and functional testing. Thus, a tabulation of those ANSI N14.6 requirements that are incompatible with these lif ting devices was prepared and is Appendix B to Attachment A. Included in Appendix B to Attachment A are recommended actions that may be used to demonstrate acceptability to the NRC.

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. Attachment B is the stress report for these 8435B:1b-020485 4-1

A devices performed in accordance with the criteria of ANSI N14.6.

discussion is included which responds to the NRC qualifying conditions of NUREG 0612.

All of the tensile and shear stresses with the exception of three specific items meet the design criteria of Section 3.2.1.1 fof

, 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. .

4.3 RECOMMENDATIONS The recommendations identified in Section 6 require a review of plant maintenance and operating instructions to ensure that they contain information relative to the identification, maintenance and periodic testing required by ANSI N14.6. The extent of the periodic testing is

) also. addressed and the recommendations identify procedures which are intended to fully meet the intent of NUREG 0612 and ANSI N14.6 with the '

These recom-i least amount of perturbation to the refueling sequence.

mendaticns do not involve any equipment changes unless stricter com-pliance becomes necessary, and then a change to the sling blocks is recommended.

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i SECTICN 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 except as indicated in Section 4.2.

3. These devices are not in strict compliance 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 compliance 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 leading conditions. Other loading conditions are to be analyzed to other appropriate criteria.

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SECTION 6 RECOMMENDATIONS The following recommendations address the areas of ANSI N14.6'which are

incompatible with the present lifting devices and which are considered l most important in demonstrating the continued reliability of these i

devices. They consist of suggestions and proposed responses to identify

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compliance to the NRC and future considerations, 6.1 Review plant operating procedures to include consideration of ANSI N14.6 Sections 5.1.3 through 5.1.8. These sections inclu::e requirements for: scheduled periodic testing; special identifi-cation 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 lead is as follows:

The Westinghouse site assembly inst.uctions required the following for the head lift rig after initial assembly: Raising the rig, assembled to its respective attachment, slightly above the supporting surface and let it be free hanging for one-half hour.

During this time, visually inspect for signs of distress or ,

l distortion. Lowering the rig to its support and performing non-destructive surface inspections of critical welds.

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 folicws. (Since the 150 percent load test is very impractical, the approach identified in the following recommendation is to perform a minimum of non-destructive testing.)

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a. Reactor Vessel Head Lift Rig:

i Prior to use and af ter reassembly of the spreader assembly, lifting lug and upper lifting legs to the upper portion of the f lif t rig, visually check all welds. Raise the vessel head slightly above its support and hold for 10 minutes. During this time, visually inspect the sling block top lug to top plate weld, side lugs to support pipe welds, and spreader lug to I spreader arm weld. If no problems are apparent, continue to I

lift, monitoring the load cell readout at all times.

I b. Reactor Vessel Internals Lift Rig Prior to use, visually inspect the rig components and welds 1 while on the storage stand for signs of cracks or deformation.

Check all bolted joints to ensure that they are tight and secure. Af ter connection to the upper or lower internals, raise j the assembly slightly off its suppcrt and hold for 10 minutes.

l During this time, visually inspect the sling block tcp lug to su; port plate weld, and sice lugs to support pipe welds. If no problems are acparent, continue to lif t, monitoring the load I cell readout at all times.

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! The above actions do not include a non-destructive test of these r

welds because:

a. Access to the welds for surface examination is difficult.

i - These rigs are in containment and some contamination is t present.

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b. Most tensile and shear stresses in the welds are within the l allowabia stress. -

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c. The items that are welded remain assembled and cannot be misused for any other lift other than their intended 4 function. l

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d. To perform non-destructive tests would require:

(1) Removal of paint around the area to be examined which is contaminated.

-(2) Performance of either magnetic particle inspection or i

liquid penetrant inspection and (3) Repainting af ter testing is completed.

(4) Cleanup of contaminated items.

Performing non-destructive tests on these welds every refueling would increase the critical path refueling time.

Dimensional checking is not included since these structures are large (about 14 feet diameter by 40 feet high) and the results of dimensional checking would always be questionable. Other checks en critical load path parts such as pins, are also not included since an examination of these items wculd require disassembly of the i

special lift devices.

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6.4 Recommend that a periodic non destructive surface en. amination of critical welds and/or parts be performed once every ten years as part of an inservice inspectie r outage.

l 6.5 Recommend that the head and internals lif t rig sdng block be changed to a forged block with welded side lugs to roduce the numcer of welds and eliminate any concern, if any, of lamellar tearing, should the NRC require yearly surface inspection of welds and plates.

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j 6.6 Recommend that no changes be made to the reactor. vessel internals

' lif t rig should the stresses, discussed in Attachment 8, be

considered 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 4

removed when a periodic inservice inspection of the vessel is required (once/10 years).

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i b. Prior to removal of the Ic er internals, all fuel is removed.

l Thus the concern for handling over fuel is non-existent in this J particular case,

c. Ncrmal use of the rig is for moving the upper internals which i

weigh less than one-half cf the lower internals. The' design weight is based on lif ting the lower internals. Thus all the l stresses could be reduced by approximately 50 percent and J

j eensidered well within the ANSI N14.6 criteria fer stre.s design factors.

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WESTINGHOUSE CLASS 3 ATTACHMENT A to WCAP-10230 Rev 1 Although information contained in this report .

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is nonproprietary, no distribution shall be made outside Westinghouse or its licensees without the customer's approval.

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, and Load Cell Linkage for Indiana and Michigan Electric Company Donald C. Cook No. I and No. 2 March, 1985 H. H. Sandner, P.E.

Approved mby Marshall, P. E., Manager Component Handling Equipment 84358:1b/020485

ABSTRACT i

The requirements used in the original design, fabrication, testing, maintenance and quality assurance were compared to the ANSI N14.6-1978 l ^

requirements for the Donald C. Cook reactor vessel head and internals lift rig, load cell, and load cell linkage. A critical items list per ANSI N14.6 section 3.1.2 has been prepared and a tabulation of ANSI N14.6 requirements that are, at present, incompatible with the Donald C. Cook lifting devices has been prepared.

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TABLE OF CONTENTS Section Title Page ABSTRACT iii 1 PURPOSE 1-1 2 INTRODUCTION 2-1 2-1

2.1 Background

! 2.2 Component Description 2-2 l

2.2.1 Reactor Vessel Head Lift Rig 2-2 2.2.2 Reactor Vessel Internals Lift Rig 2-2 f

2.2.3 Lead Cell and Load Cell Linkage 2-3 3 DISCUSSION 3-1 I

4 CONCLUSIONS 4-1 APPENDIX A - CRITICAL ITEMS LIST PER ANSI N14.6-1978 A-1 1

i APPENDIX B - TABULATION OF ANSI N14.6-1978 REQUIREMENTS B-1 INCOMPATIBLE WITH THE DONALD C. COOK SPECIAL LIFTING DEVICES l

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LIST OF ILLUSTRATIONS Figure Title ,

Page A-1 Reactor Vessel Head Lift Rig A-5

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A-2 Reactor Vessel Internals Lif t Rig A-9 8435B:1b-020485 vii

LIST OF TABLES Table Title Page 2-1 Comparison of the Requirements of ANSI N14.6 2-4 and Donald C. Cook Special Lifting Devices A-1 Reactor Vessel Head lif t Rig, Critical Items A-3 l

List of Parts per ANSI N14.6-1978 1

A-2 Reactor Vessel Head Lift Rig, Critical items A-4 l List of Welds per ANSI N14.6-1978 A-3 Reactor Vessel Internals Lift Rig, Lead Cell A-6 and Lead Cell Linkage, Critical Items List of Parts per ANSI N14.6-1978 A-4 Reactor Vessel Internals Lift Rig, Load Cell A-8 and Lead Cell Linkage, Critical items List 1

i of Welds per ANSI N14.6-1978 l

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REFERENCES

1. Westinghouse Drawing 113E529 4-Loop Head Lifting Rig Gener.al Assembly I

2. Westinghouse Drawing 113E479 4-Loop Plants Lifting Rig Internals -

General Assembly l

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SECTION 1 PURPOSE The purpose of this report is to compare the requirements of the special lifting rigs used to lift the reactor vessel head, and reactor vessel upper and lower . internals, with the requirements . contained in ANSI N14.6 for special lifting devices.

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SECTION 2 INTRODUCTION ANSI N14.6-1978 "American National Standard for Special Lif ting Devices for Shipping Containers Weighing 10,000 Pounds or More for Nuclear Materials" contains detailed requirements for the design, fabrication, testing, maintenance and quality assurance of special lif ting devices.

NUREG 0612 " Control of Heavy Load at Nuclear Power Plants", paragraph 5.1.1(4), specifies that special lifting devices should satisfy the guidelines of ANSI N14.6-1978. Subsequently the Nuclear Regulatory Commission (NRC) has requested operating plants to demonstrate compliance with NUREG 0612. To demonstrate compliance with this document, a detailed comparison of the original design, fabrication, testing, maintenance 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 design and manufacture the reactor vessel head lift rig, the reactor vessel internals lift rig, load cell, and load cell linkage. This comparison is listed in Table 2-1.

2.1 BACKGROUND

The reactor vessel head and internals lifting rigs were designed and built for the Donald C. Cook Nuclear Power Plant, circa 1969-71.

Westinghouse used the design criteria that the resulting stress in the load carrying members, when subjected to the total combined lif ting weight, should not exceed one fif th (1/5) of the ultimate strength of the material. Westinghouse also required non-destructive tests and inspections on all critical load path parts and welds both as raw material anc as finished items. These requirements of design, manufacturing and quality assurance were identified on detailed manufacturing drawing and purchasing documents.

8435B:1b-020485 2-1

Westinghouse also issued field assembly and operating instructions, where applicable.

2 2.2 COMPONENT DESCRIPTION 2.2.1 Reactor Vessel Head Lift Rig 4

The reactor vessel head lift rig II3 is a three-legged carbon steel j structure, approximately 39 feet high and 14 feet in diameter, weighing approximately 25,000 pounds. It is used to handle the assembled reactor vessel head.

,e The three vertical legs and control rod drive mechanism (CRDM) platform j

assembly are permanently attached to the reactor vessel head lifting i lugs. The tripod sling assembly is attached to the three 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 platform assembly remain attached to the reactor 3

vessel head.

2.2.2 Reactor Vessel Internals lift Rig The reactor vessel internals lift rig [2] is a three-legged carbon and stainless steel structure, approximately 31 feet high and 14 feet in diameter weighing approximately 14,750 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 operations. A load cell linkage is connected between the main crane hook and the rig to monitor loads during all operations. When not in use,therigisstoredontheupperjpternalsstoragestand.

The rig attaches to the internals packages by means of three engaging j

serens which are serewed into tapped holes in the internals flanges.

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i 8435B:1b-020485 2-2 l

These screws are manually operated from the manipulator crane walt.way using a handling tool which is essentially a long wrench. The screws are normally spring retracted upward and are depressed to engage the tapped holes by the weight of the handling tool.

2.2.3 Load Cell and Load Cell Linkage l

The load cell is used to monitor the load during lifting and-lowering the reactor vessel head or internals to ensure no excessive loadings are occurring. It is installed between the load cell linkage and the lifting device. The load cell is a strain gage (tension) type, rated at 400,000 pounds, built by W. C. Oillon 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.

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I I TABLE 2-1 COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 AND f

l DONALD C. COOK SPECIAL LIFTING DEVICES 1

r ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements j Section I

1 Scope and Definitions - These sections These sections are definitive, and not  ;

requirements.

1.1 BdTine the scope of the document and to include pertinent definitions of j

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-1 7 to a design specification and its' contents, facturing drawings and purchasing

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• 3.1.4 stress reports; repair procedures; limi- documents contain the following 1 tations on use with respect to environ- requirements:

I mental conditions; marking and nameplate j information; and critical items list. (1) Material specification for most of the 1

critical load path items to ASTM, ASME j specifications or special listed i requirements.

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(2) All welding, weld procedures and welds 4 to be in accordance with ASME Boiler and i Pressure Vessel Code - Section IX.

I j (3) Special non-destructive testing for i specific critical load path items.to be .

{ performed to written and approved procedures I in accordance with ASTM or specified requirements

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i s

l 8435B:1b-020485 1

j

TABLE 2-1 (cont)

COMPARISDN OF THE REQUIREMENTS OF ANSI N14.6 AND DONALD C. COOK SPECIAL LIFTING DEVICEd ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section (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 specifications.

B. A stress report was not originally required but has been prepared and is Attachment B.

[ C. Repair proced'ures were not identified.

D. No limitations were identified as to the use of these devices under adverse environments.

E. Markings and nameplate information was not addressed.

F. Critical item lists have been prepared for each device and are identified as Appendix A to this Attachment A.

84358:lb-020485

-- . . - _ _ - _ . - - - - .- -- - -= . _ - . . - . - .- - -- . _- . . _ .

8 TABLE 2-1 (cont) j COMPARISDN OF THE REQUIREMENTS OF ANSI N14.6 AND o DONALD C. COOK SPECIAL LIFTING DEVICES

ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements l Section i

l

, 3.2 Design Criteria 1. These devices were originally 3.2.1 5 tress Design Factors - These sections designed to the requirement that the

! to contain requirements for the use of stress resulting stress in the load carrying 3.2.6 design factors of 3 and 5 for allowable members, when subjected to the total stresses of yield and ultimate respec- combined lifting weight, should not j tively for maximum shear and tensile exceed one fifth (1/5) of the ultimate stresses; high strength material stress strength of the material. A stress design factors; special pins; wire rope report (Attachment B) has been gener-i and slings to meet ANSI B30.9-1971; and ated which addresses the capability j drop weight tests and Charpy impact test of these rigs to meet the ANSI design

' [ requirements stress factors.

2. High strength materials are used in some

of these devices (mostly for pins, i loadcell). Although the fracture toughness was not determined, the material was selected based on it's fracture toughness characteristics. However, the stress design factors of ANSI N14.6 Section 3.2.1 of 3 and 5 were used in the analysis and the resulting stresses are acceptable.

{ 3. Where necessary, the weight of pins was considered for handling. ,

I

)

I 4

)

8435B:lb-020485 i

TABLE 2-1 (cont)

COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 ANO DONALD C. COOK SPECIAL IIFTING DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section

4. Drop weight and Charpy impact tests were not required nor performed except for the upper and lower clevisis of the internals lift rig. The applicable material specification for these items is an ASME specification which require Charpy tests.

3.3 Design Considerations - These sections Decontamination was not specifically y 3.3.1 contain considerations for; materials of addressed. Lamellar tearing was L to construction, lamellar tearing; decontam- considered in the' design of the reactor 3.3.8 ination effects; remote engagement provi- vessel and internals lift rig sling sions; equal load distribution; lock blocks by requiring non-destructive devices; position indication of remote tests (ultrasonic, magnetic particle and actuators; retrieval of device if disen- radiograph) of the base material and gaged; and nameplates. assembly welds. Locking plates, pins, etc. are used throughout these special lifting devices.

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. ,,

84358:lb-020485

TABLE 2-1 (cont)

COMPARISON Of THE REQUIRENENTS Of ANSI N14.6 AND ,

DONALD C. COOK SPECIAL LIFilNG DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section .

I 3.4 Design Considerations to Minimize Decontam- Decontamination was not specifically i 3.4.1 ination Efforts in Special Lifting Device addressed. However, the design and i to Use - These sections contain fabrication, manufacture included many of these 3.4.6 weTding. finishes, joint and machining items, i.e. lock devices, pins, etc.

requirements to permit ease in l decontamination.

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 l to coating carbon steel surfaces and for Westinghouse process specification l O' 3.5.10 ensuring non-contamination of stainless referenced on the assembly and detail l

• steel items. drawings. This specification requires a proven  !

procedure, proper cleaning, preparation, t application and final inspection of the coating. These requirements 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 noncontaminating 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 identif:ed. However, neolube to minimize contamination and degradation of is recommended for use with the engaging 3.6.3 the lubricant and contacted surfaces screws in the internals lift device or water pools which are under water and silicone grease for the load cell pins which ,

are out of water. L 84358:1b-020485 ,

i

TABLE 2-1 (cont)

COMPARISON OF THE REQUIREMENfS OF ANSI N14.6 AND DONALD C. COOK SPECIAL LIFilNG DEVICES Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements ANSI N14.6 Section 4 Fabrication A formal quality assurance program for the Fabricators Responsibilities -These manufacturer was not specifically required.

4.1 However, all the manufacturers welding pro-4.1.1 sections contain specific requirements for proper quality assurance, document cedures and non-destructive testing pro-to control. deviation control, procedure cedures were reviewed by Westinghouse prior 4.1.12 control, material identification to use. All critical load carrying members and certificate of compliance. require letters of compliance for material requirements. Westinghouse performed certain checks and inspections during various steps of manufacturing. Final Westinghouse review 7' includes visual, dimensional, procedural,

• cleanliness, personnel qualification, etc. and in some instances is uance of a quality release to ensure conformance with drawing requirements.

4.2 Inspectors Responsibilities -These Westinghouse Quality Assurance personnel 4.2.1 sections contain requirements for performed inprocess and final to a non-supplier inspector. inspections simila.r to those identified 4.2.5 in these sections. (Also see comments to Section 4.1 above) 4.3 Fabrication Considerations -These General good manufacturing processes ,

4.3.1 sections contain speciai requirements were followed in the manufacture for ease in decontamination or control of these devices. However, the to 4.3.3 of corrosion. information defined in these sections was not specifically addressed.

84358:Ib-020485

TABLE 2-1 (cont)

COMPMISON Of IllE REfXilREMENIS Of ANSI N14.6 AND DONALD C. COOK SPECIAL LIFTING DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section 5 Acceptance Testing Maintenance. There wasn't any design 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 o-ner 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. Although

', proof and functional testing was not required, c' after initial assembly on site, the critical welds of the reactor vessel head lifting rig was visually, and magnetic particle inspected after lifting its respective attachment and holding for one-half hour.

Section 5.1.3 requires periodic functional Maintenance and inspection procedures testing should be revised to include a visual check of critical welds and parts during lifting to ccmply with this requirement for functional testing.

Section 5.1.4 requires operating procedure Operating instructions for the reactor vessel internals lift rig were furnished to the utility and operating procedures were prepared and are used.

84358:lb-020485

l TABLE 2-1 (cont) i COMPARISON OF THE REQUIREMENTS Of ANSI N14.6 AND 1 DONALD C. COOK SPECIAL LIFTING DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section 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. cavices and can only be used for their intended <

l purpose. Specific identification of the rig can be made by marking, with stencils, the rig name j

l and rated capacity, preferably on the spreader assembly.

1 Sections 5.1.6, 5.1.7 and 5.1.8 require Operating instructions and maintenance the owner to provide written documenta- instructions should be reviewed to y

1. tion on the maintenance, repair, testing assure that they contain the require-

-- and use of these rigs. ments to address maintenance logs, repair and testing history, damage incidents etc.

5.2 Acceptance Testing and Testing to Verify The head lift rig was load tested after and Continuing Compliance - Ihese paragraphs field assembly. It is suggested that a 5.3 require the rigs to be initially tested check of critical welds and parts be l 5.2.1 at 150% maximum load followed by included in the maintenance procedures for to non-destructive testing of critical load both the head and internals lifting devices.

5.2.3 bearing parts and welds and also annual Preferably, a visual check during initial and 150% load tests oc annual non-destructive lift should be acceptable. Further note 5.3.1 tests and examinations; qualification of that with the use of the load cell for,the to replacement parts. head and internals, lifting and lowering is monitored at all times. However,the load cell.

5.3.8 cannot exceed the rated load by 20% without i

being inaccurate. This would preclude monitoring of a 150% load test with the present equipment. Replacement parts should be in accordance with the original or equivalent requirements.

84358:lb-020485

TABLE 2-1 (cont)

COMP 4RISON Of THE REQUIREMENTS OF ANSI N14.6 AND 4 DONALD C. COOK SPECIAL LIFTING DEVICES I

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 criginal ments that were used in the original 5.4.2 requirements and no repairs are permitted fabrication. The critical items list of for bolts, studs 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.

7' 5.5 Non-destructive Testing Procedures, Liquid penetrant, magnetic particle, K 5.5.1 Fersonnel 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 Westing-accordance with the requirements of the house process specifications or as noted ASME Boiler and Pressure Vessel Code on detailed drawings and provide similar results to the requirenent of the ASME Code.

6 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.

8435B:lb-020485

I L

t SECTION 3 DISCUSSION The reactor vessel head and internals lift rigs, load cell, and load cell linkage 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 centain equivalent requirements. A stress report has been prepared for these devices and the design criteria is considered satisfied. These devices, for the most part, were manufactured under Westinghouse surveillance with identified hold points, procedure review and personnel qualification which adequately meet these related ANSI requirements. Acceptance testing as defined in ANSI N14.6 was not performed, but an initial 100 percent load test was conducted on the head lif t rig followed by non-destructive testing of critical welds. The load cell was calibrated in tension at its capacity of 400,000 pounds.

It is anticipated that a 100 percent load test, performed on each device, followed by a visual check of critical welds would be sufficient to demonstrate compliance. This may require modification of Donald C. Cook operating and maintenance procedures.

8435B:1b-020485 3-1

SECTION 4 CONCLUSIONS The review of the ANSI N14.6 requirements and comparison with the original Westinghouse requirements has shown that these items are generally in agreement for the design, fabrication and quality assurance l of the lifting devices. However, the lifting devices are not in strict compliance with the ANSI N14.6 requirements for acceptance testing, maintenance and verification of continuing compliance. These specific ,

requirements that are incompatible with the lifting devices are discussed in Appendix B with suggested actions. Westinghouse's objective was to provide a quality prodect and this product was designed, fabricated, assembled and inspected in accordance with internal Westinghouse requirements. In general, Westinghouse requirements meet the intent of ANSI N14.5 but not all- the specific detailed regt.irements.

i t

t I'

r l l l i 8435B:1b-020485 4-1 l

1 APPENDIX A CRITICAL ITEMS LIST PER ANSI N14.6-1978

1. GENERAL Section 3.1.2 of ANSI N14.6-1978 specifies that the design specificatien shall include a critical items list, which identifies critical components and defines their critical characteristics for material, fabrication, non-destructive testing and quality assurance.

" Critical items list" is further defined in ANSI N14.6, Section 2 as:

" critical items list. A list that specifies the items of a special lif ting device and their essential characteristics for which specified quality requirements shall apply in the design, fabrication, utilization, and maintenance of the device."

Load carrying members and welds of these special lifting devices are considered to be the critical items.

Tables A-1, A-2, A-3, and A-4 are the critical items list of parts and welds for the reactor vessel head lif t rig, the reactor vessel internals lift rig, load cell and load cell linkage, respectively. These tables include the material identification, and the applicable volumetric and surf ace inspections that were performed in the fabrication of these special lifting devices. In some instances, nor.-destructive testing was not specified since the material selection and strength resu't in very low tensile stresses and thus, non-destructive testing was not justified.

The material selection for most critical load path items was made to ASTM, ASME or special material requirements. The material requirements were supplemented by Westinghouse imposed non-destructive testing, and/or special heat treating requirements for almost all of the critical 8435B:1b-020485 A-1

items. Westinghouse required all welding, welders, and weld procedures to be in accordance with ASME Boiler and Pressure Vessel Code Section IX for carbon steel welds. Westinghouse required a certificate, or 1etter of compliance that the materials and processes used by the manufacturer were in accordance with the purchase order and drawing requirements.

Westinghouse also performed final inspections on these devices and in some instances issued quality releases for the internals and head lifting rigs.

84358:1b 0204B5 A2

TABLE A-1 REACTOR VESSEL HEAD LIFT RIG CRITICAL ITEMS LIST OF PARTS

~

PER ANSI N14.6-1978 ltem(a) Description Material Non-destructive Testing Material Finished 1.5,9, 4",5" and 6" ASTM A304 Ultrasenic Magnetic 12,16 dia pins A!S! 4340, Particle and ASTM A434 3 Class BD 2,3 Sling Block ASTM A516 Ultrasenic Top Lugs Grade 70 Magnetic Tcp Plate Particle Side Lugs 6,8, Clevis ASTM A105 Ultrasenic Magnetic 13,15 Grade 1 or 2 Particle or ASTM A508 Class 1 or 2 7,14 Sling Lift- ASTM A306 Ultrasenic Magnetic ing Legs, Grade 80 Particle Lifting Leg 10 Spreader Lug ASTM ASIS Ultrasonic Magnetic Grade 70 Particle (a)See figure A-1 8435B:1b 020485 A-3

TABLE A-2 REACTOR VESSEL HEAD LIFT RIG CRITICAL ITEMS LIST OF WELDS ,

PER'ANS! N14.6-1978 t  !

Item Weld Non-destructive Testing Description Root Pass Final 2,3 Sling Block Magnetic Ultrasonic Top Lugs to Particle Magnetic Particle Top Plate (Full Penetration)

Side LJgs to Magnetic Radiograph Support Pipe Particle Magnetic Farticle (Full Penetration) 9,10 Spreade- Iog in Magnetic Magnetic Spreader Arm Particle Particle Weld (fillet) 84358:1b 020485 A-4

@ TOP LUG ,, 4" DI A PIN h

~

@ SIDE LUG p 5" DIA PIN 4lJL ,

'O h SLING BLOCK BODY

@ CLEVIS i h SLING LIFTING LEG ,,

h CLEVIS h LUG -fy; CLEVIS h

. ! \\sm ' w, h 5"DIA PIN W,, y ARM h

\  %)/ \

~ i, f r % _w.,m s ' v . . -

h LIFTING LEG g

TYPICAL CMDM % , ,

, - m 1

/, -'

I, _ . . - 3

\ t U

~ ~~

h CLEVIS s ( ,

~~ "'- ), .

h 4" DI A F IN ,' Q U g pf [:

' '4, gf,($ l' MEACTOM m % ,

VtsstL " n ,., " " " ' ,c" HEAD Figure A 1. Reactor Vessel Head Lift Rig 84358:1b 020485 A5

TABLE A-3 REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE .

f CRITICAL ITEMS LIST OF PARTS PER ANS! N14.6-1978 Item (a) Description Material Non-destructive Testing i

Material Finished 1

5 Lead Cell 17-4 pH Stain- Ultrasonic Liquid less Steel, Penetrant Condition H-1100 2 Lead Cell ASTM ASIS Ultrasonic Linkage Grade 70 Side Plates 4,6 Adaptors A!SI d340 Ultrasonic Magnetic

< Particle i

1,3,7, 7-1/2" Dia. ASTM A434 Ultrasonic Magnetic 3

12 Hook Pin Class BD Particle 6" Dia. Adapter A!S! 4340 Pin 6" Dia. Removable i Pin 4" Dia. Clovis Pin 16 4" Dia. Clevis Bolt ASTM A434 Ultrasonic

, Class BD AISI 4340

< 13,15 Clovis SA 508 Class 2 Ultrasonic Magnetic Particle 14 Sling Leg A!SI 1117 Hot Rolled AISI 1020 Cold Rolled (a)See figure A 2 s

84358:1b 020485 A6

TABLE t.-3 (cont)

REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CLLL LINKAGE CRITICAL ITEMS LIST OF PARTS PER ANSI N14.61978 Item (a) Description Material Non destructive Testing Material Finished 24,26 Adapter ASTM A276 Guide Sleeve Type 304 Condition A 25 Outer Tube ASTM A312 Type 304 Seamless 27 Engaging ASTM A564 Ultrasonic Liquid Screw Grade 630, Penetrant Cond, 1100 8,10,11 Top Lug ASTM A515 Magnetic Support Plate Grade 70 Particle Side Lug CLT l'Itrasonic 20 Spacer ASTM ASBS Grade A or B 21,22 Leg Channel ASTM A 36 Brace Plate 23 Leg Support AISI 8620 Ultrasonic Block Magnetic Particle (a) See figure A 2 84350:1b 020485 A7

TABLE A-4 REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE '

CRITICAL ITEMS LIST OF WELDS l PER ANS! N14.6-1978 Item Weld Non-destructive Testing Description Root Pass Final 8,10 Sling Bleck Top Lugs to Support Magnetic Particle Ultrasonic Plate Magnetic Particle (Full Penetration) 9,11 Side Lugs to Radiograph Support Pipe Mag etic Particle (Full Penetration) 20 Spacer Magnetic Particle Visual to Leg Weld Magnetic Particle (ic; and Bottem)

(Full Penetration) 15 Torcue fute Adapter to Outer Liquid Penetrant Liasid Peretrant Tute (Full Pene-tration) f 21,22. Brace Plate and Magnetic Particle Visual 23 Leg Support Block Magnetic Particle to Leg held (fillet) 8435B;1b 020485 A8

71/2 DIA HOOK PIN @

k SIDE PLAIE @

6"DIA ADAP10H PIN @

@ UPPER ADAPTOR BOTTOM ADAPTOR @

@ LOADCELL

],s 6"DIA REMOVABLE PIN @

h TOP LUG SUPPOHT PLATE @

@ SIDE LUG 1{};

\ SUPPORT PIPE @

@ 4" DI A CLEVIS PIN NSLINGLtc @

@ UPPER CLEVIS /

yE ,",

" f 4 ACLEVIS @

@ SPACER ,

NYfl- 4 END PLATE h l

h SPREADER \

, , oy LEGCHANNELS @

LEO l t i' ASSEMBLY p H {! ,

I

@ BACKING i  !

U$

p BLOCK "4 '

{ ll i I, b { b,[

yd?'24 23 g l l - 2t>

l .. .

cj e b I L' ; f/-- 26 p-- 27 N s<fj'/

i

[' [ ** ..b)

/\eh, RING GIRDER s *

+ /

d /

y ADAPTOR @

k A' / OUTER TUHE @

@ eMAct PLAtt

@ LEO SUPPORT NLOCK #

Figure A 2. Reactor Vessel Internals Lift Rig 84359:1b 020485 A9

APPENDIX B TABULATION OF ANSI N14.6-1978 REQUIREMENTS INCOMPATIBLE WITH THE DONALD C. C00K LIFTING DEVICES

1. GENERAL The comparison of the various ANSI N14.6 requirements and those of these lifting devices has sho n that these devices are not in strict ceroliance with all the ANSI N14.6 requirements. Listed belca is a tabulation cf those sections of ANSI N14.6 considered most important in demonstrating l

the continued load handling reliability of these special lifting devices. Associated Westinghouse remarks are also listed and could be l

used as suggested actions and/cr resperses to detonstrate co pliance to the NRC.

la. Require ent:

Para. 3.1.4 - reavires the designer to indicate permissible repair procedures and acceptance criteria for the repair.

Ib. Remarks:

Any repair to these special lifting devices is considered to be

! in the form of welding. Should pins, bolts or other f asteners 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 performed in accordance with the requirements identified in NF-4000 and NF-5000 (Fabrication and Enamination) of the A$vE Boiler and Pressure Vessel Code, Section 111, Division 1 Subsection NF.

2a. Requirement:

Para. 3.2.1.1 - requires the design, when using materials with yield str6ngths above 80 percent of their ultimate strengths, to be based on the material's fracture toughness and not the listed design factors.

8435B:1b 020485 B-1

l 2b. Remarks:

High strength materials are used in these devices. Although the fracture toughness was not determined, the material was selected based on it's fracture toughness characteristici.

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 l acceptable.

3a. Requirement:

Para. 3.2.6 requires material for load-bearing members to be subjected to drop-weight or Charpy impact tests.

30. Remarks:

Fracture toughness requirements were not identified for the l material used in these special lifting devices except for the j upper and loner clevisis of the internals lift rig. The applicable specification for these items is an ASME specifi-l l cation which requires Charpy tests. However, all material selection was based on its fracture toughness characteristics.

da. Requirement:

Para. 3.3.6 requires an indication that an actuating mechanism is engaged.

1 4t. Remarks:

The reactor vessel internals lif t rig employs a long handled tool to engage the rig and the internals. The tool depresses a spring loaded tube and turns the engaging screw into the inter-nals. No specific position indication is identified, escept l

' for scribe marks on the tool, and the visual difference in the top of the spring loaded tube is considered sufficient indica-tion that the internals are engaged.

8435B:1b-020485 B-2 I

i Sa, Requirement:

Para. 4.1.6 requires a formal quality assurance program for the manufacturer and para. 4.1.7 requires certification and identi-

~

fication of materials.

Sb. Remarks:

A formal quality assurance program for the manufacturer was not required for all items. However, the manufacturers welding procedures and non-destructive testing procedures were revieaed by Westinghouse prior to use. Most of the critical load carrying members require letters of compliance for material requirements. Westinghouse performed certain checks and inspections during various steps of manufacturing. Final Westinghouse review includes visual, cimensional, procedural, cleanliness, personnel qualification, etc. and, in most cases, issuance of a quality release to ensure conformance with drawing requirements.

6a. Requirement:

Para. 5.1 lists owner Responsibilities and 5.1.2 requires the owner to verify that the special lif ting devices meet the performance criteria of the design specification by records and witness of testing.

6b. Remarks:

There wasn't any design specification for-these rigs. Load testing was performed on the reactor vessel nead lift rig at field assembly. This was a 100 percent load test and non-destructive testing was conducted on critical welds following the test. However, the Westinghouse Quality Release, when used, may be considered an acceptable alternate 8435B:1b-020485 B-3

4 i

to verify that the criteria for letters of compliance for materials and specifications required by the Westinghouse drawings and purchasing document were satisfied. -

7a. Requirement:

Para. 5.1.3 requires periodic functional testing and a system te indicate continued reliable performance.

i 7b. Remarks:

Maintenance and inspection procedures should include a visual check of critical welds and parts during lifting to comply with this requirement for functional testing. P Ba. Requirement:

Para. 5.1.5, 5.1.5.1 and 5.1.5.2 require special identification 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 I

and parts are not interchangeable. Specific identification of the rig can be made by marking with stencils, the rig name and rated capacity, preferably on the spreader assembly.

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:

Operating instructions and maintenance instructions should be reviewed to assure that they contain the requirements to

,8435B:1b-020485 B-4

- - - . . . - ~ _ _ - - - - . - -. - _ _ _ _ - - -. --

O address maintenance legs, repair and testing history, damage

• incidents and other items mentiened 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 l The head lift rig was load tested and inspected at assembly tc aporoximately 100 percent of the load folloaed by ncn-destructive testing of critical welds.

11a. Requirement:

Para 5.2.2 requires replacement parts to be individually cualified and tested.

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 lif t rigs.

12a. Requirement:

Para 5.3 requires testing to verify continuing compliance and annual 150 percent load tests or annual non-destructive tests i

and examinations to be performed.

12b. Remarks These special lifting devices are used during plant refueling which is approximately once per year. During plant operation 8435B:1b-020485 B-5

4 these special lif ting devices are inaccessable since they are permanently installed and/or remain in the containment. They cannot be removed from the containment unless they are disas-,

sembled and no known purposes exist for disassembly. Loid testing to 150 percent of the total weight before each use l would require special fixtures and is impractical to perform.

Crane capacity could also be limiting. It is suggested that a check (visual) of critical welds and parts be conducted at initial lift prior to moving to full lift and movement for both devices. Further note that with the use of the load cell for the head and internals lif t rigs, all lif ting and lowering is I

monitored at all times.

2.

SUMMARY

The requirements for periodic checking and functional load testing appear to be the ANSI N14.6 requirements that are most difficult to demonstrate compliance. It is almost impractical to perform the 150 percent load test prior to each use. It is suggebied that the proposal to the NRC include a 100 percent load test to be performed with a minimum of non-destructive testing, (visual-only) in the critical parts and welds.

8435B:1b-020485 B-6

l WESTINGHOUSE CLASS 3 l

Although information centained in this report ATTACHMENT B to is nonproprietary, no distribution shall WCAP-10230 be made outside Westinghouse or its Rev.-1 licensees without the customer's approval.

STRESS REPORT REACTOR VESSEL HEAD LITT RIG, REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL, AND LOAD CELL LINKAGE FOR INDIANA AND MICHIGAN ELECTRIC COMPANY DONALD C. COOK NO.1 AND NO. 2 March,1985 H. A. Sandner, P.E.

Approved- <- ~

J . Marshall, P. E., Ma' nager Component Handling Engineering 8475B:1b-020485

s ABSTRACT A stress analysis of the Donald C. Cook reactor vessel head and internal lif t rigs, ',oad cell, and load cell linkage was performed to determine ihe 6cceptability of these devices to meet the design requirements of ANSI N14,6.

8475B:1b-020485 iii

ACKNOWLEDGMENT Acknowledgment is hereby made to the following individuals who contributed to the structural analysis presented in this report. -

J. W. Richard, P.E.

F. Peduzzi 8475B:1b-021185 iv

TABLE OF CONTENTS 1

I Section Title Page ASS!otCT 'ii 1 INTRODUCTION 1-1 1.1 Background 1-1 2 COMPONENT DESCRIPTION 2-1 2.1 Reactor Vessel Head Lift Rig 1 2.2 Reactor Vessel Internals Lift Rig 2-1 2.3 Load Cell and Lead Cell Linkage 2-2 3 DESIGN BASIS 3-1 3.1 Design Criteria 3-1 3.2 Design Weights 3-2 d

MATERIALS 4-1 4.1 Material Description 4-1 5

SUMMARY

OF RESULTS 5-1 5.1 Discussion of Results 5-1 5.2 Conclusion 5-5 APPENDIX 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 8475B:1b-020485 v

LIST OF ILLUSTRATIONS Figure Title Page o

S-1 Reacter Vessel Head Lift Rig 5-11 5-2 Reactor Vessel Internals Lift Rig, Lead Cell and Linkage 5-19 84758:1b-020485 vii

LIST OF TABLES Table Title Page 4-1 Reacter Vessel Head Lift Rig Material and Material Properties 4-2

• 4-2 Reactor Vessel Internals Lift Rig, Load Cell and Lead Cell Linkage Material and Material Properties 4-3 5-1 Summary of Results - Reactor Vessel Head Lift Rig 5-6 5-2 Summary of Results - Reacter Vessel Internals Lift Rig, Load Cell and Lead Cell Linkage 5-12 8475B:1b-021185 in

REFERENCES

1. George, H., Control of Heavy Leads at Nuclear Power Plants Resolution of Generic Technical Activity A-36, NUREG 0612, July,1980,

2. ANSI N14.6-1978, "Special Lif ting Devices for Shipping Containers Weighing 10,000 Pounds (4500kg) or More for Nuclear Material," American National Standards Institute, New York, 1978.

3. Westinghouse Drawing 113E529 - 4 Loop Head Lifting Rig General Assembly

4. Westinghouse Drawing 113E479 - 4 Loop Plants - Lifting Rig Internals General Assembly

5. Lin, C. W., " Approximate Evaluation of Dynamic Lead Factors for Certain Types of Load Factors for Certain Types of Loading," ASME Paper 70-WA/NE-2.

6. Biggs, J. M., Introduction to Structural Dynamics, McGraw-Hill, New York, 1964.

7. Gwinn, Jr., J. T., "Stop Over-Designing for Impact Loads," Machine Design,-

33, pp. 105-113 (1961).

Timoshenko, S., Strength of Materials, Part 1. Elementary Theory and 8.

Problems, D. Van Nostrand Company, Inc. Third Edition April 1955, pp.

263-279.

9. ASME Boiler and Pressure Vessel Code,Section III, Division 1, " Nuclear Power Plant Components," American Society of Mechanical Engineers, Nea York, 1980.

10. Manual of Steel Construction, Seventh Edition, American Institute of Steel Construction, New York, 1973.

84759:1b-021185 xi

SECTION 1 INTRODUCTION The Nuclear Regulatory Commissien (NRC) issued NUREG 0612 "Contrc 1 of Heavy Lead at Nuclear Power Plants"Ill in 1980 to address the control of heavy loads to prevent and mitigate the c~onsequences of postulated accidental lead drops. NUREG 0612 imposes 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 lif ting devices to meet the requiremants of ANSI N14.6-1978 "American National Standard for Special Lifting Devices for Shipping Containers Weighing 1C,000 Pounds or More for Nuclear Materials";I 3 In general, ANSI N14.6 contains detailed requirements for the design, fabrication, testing, maintenance and quality assurance of special lifting devices. The NRC has requested operating plants to demonstrate compliance with these requirements.

This. report contains the stress analysis performed on the Donald C. Ceck reacter vessel head lift rig, reactor vessel internals lift rig, load cell, load cell, and linkage to determine the acceptability of these devices to reet these requirements.

1.1 BACKGROUND

The reactor vessel head lif t rig, the reactor vess'el internals lif ting rig, load cell, and load cell linkage, were designed and built for the Donald C. Cook Nuclear Poaer Plant, circa 1969-1971. At that time, the general design criteria was that the resulting stress in the load carrying members, when subjected to the total combined lifting weight, should 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 formal 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.

8475B:1b-020485 1-1

i I

i SECTION 2 COMPONENT DESCRIPTION 2.1 REACTOR VESSEL HEAD LIFT RIG-The reactor vessel head lift rig I33 is a three legged carbon steel-structure, approximately 39 feet high and 14 feet in diameter, weighing approximately 25,000 pounds. It is used to handie the assembled reacter vessel head. [

The three vertical legs and control rod drive mechanism (CRDM) platform assembly are permanently attached to the reactor vessel Fead lifting lugs.  ;

The tripod sling assembly is attached to the three vertical legs and is used [

wnen installing and removing the reacter vessel head. During plant operations, the sling assembly is removed and the three vertical legs and platform assembly remain attached to the re ctor vessel head.

2.2 REACTOR VESSEL INTERNALS LIFT RIG The reactor vessel internals lift rig I43 is a three-legged carbon and l stainless steel structure, approximately 31 feet high and 14 feet in diameter weighing approximately 14,750 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 operations. 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 i 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 manipulator crane walkway using a handling tool which is essentially a long wrench. The screws are normally spring retracted upward and are depressed to engage the tapped holes by the weight of the handling tool.

8475B:1b-021185 2-1  ;

t

. . .. - = .. . _ - - . _ .. - .. _ . . ___ __ . _ - _ - ... -. . -

2.3 LOAD CELL AND LOAD CELL LINKAGE 4

The load cell is used to monitor the load during lif ting and lowering the reactor vessel head or internals to ensure no excessive loadings are ~

occurring. It is installed between the load cell linkage and the lifting device. The load cell is a strain gage (tension) type, rated at 400,000 pounds, built by W. C. Dillon 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.

L 4

1 l

'l i

i i

8475B:1b-020485 2-2 i

- - - . . . . . ~ . , - . _ . _ , , . . - , - . , , , . , , - ____.n,, . _ - - - , _ _ . ,,_n,,,,,,_ - , , - . - . . ,-- -- ,. , _ ,

l i

SECTION 3 DESIGN 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 ccmbined 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 4 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".

l it can be inferred from this paragraph that the stress design factors ,

i specified in Section 3.2.1.1 of ANSI N14.6 (3 and 5) are not all inclusive.

4 Also, it can be inferred that the specified ANSI N14.6 stress design factors should be increased by an amount based on the trane dynamic characteristics.

The dynamic characteristics of the crane would be based on the main hook anc associated wire ropes holding the hook. Most main containment cranes use sixteen (16) or more wire ropes to hancle the load. Should the trane book

! suddenly stop during the lifting or lowering of a load, a shock load could be transmitted to the connected device. Because of the elasticity of the sixteen

( or more wire ropes, the dynamic factor for a typical containment crane is not nuch larger than 1.0. The maximum design factor that is recommended by most design texts [5,6,7] 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

3 (weight) < Yield Strength  !

5 (weight) < Ultimate Strength

The factor of 3 specified, certainly, includes consideration of suddenly applied loads for. cases where the dynamic impact factor may be as high as l 2.0. Thus, we feel that the use of the design criteria in ANS! N14.6 satisfies the NUREG requirement.

1 8475B:1b-021185 3-1 i

To provide flexibility on stress design factor, the analysis of the devices was performed with stress design factors of 1, 3 and 5. Thus, any stress c'esign factor may be easily applied to satisfy any concerns. , )

1 i

3.2 DESIGN WEIGHTS The following design weights were used in the analysis of the lif ting devices:

I 3.2.1 Reactor Vessel Head lift Rig The design weight is 320,000 pounds which is the total weight of the reactor vessel head, its attachment and the lif t rig.

3.2.2 Reactor Vessel Internals Lif t Rig, Load Cell, and Load Cell Linkage ,

(a) The design weight for the internals lif t rig is 339,500 pcunds which 3

is the total weight of the lifting device and the lower internals.

(b) The design weight is 333,500 pounds for the load cell and load cell linkage since it is used in lifting the lower internals.

l l

4 1

1 j 8475B:1b-020485 3-2

I SECTION 4 MATERIALS 4.1 MATERIAL DESCRIPTION The materials and material properties for the ceactor vessel head lift rig, the reactor vessel internals lift rig, lead cell, and load cell linkage are listed in Tables 4-1, 4-2 and 4-3.

8475B:1b-021185 4-1

4 TABLE 4-1 i REACTOR VESSEL HEAD LIFT RIG MATERIAL AND MATERIAL PROPERTIES i

j -'

Yield Ultimate 1 ~

Strength Strength Item (a) Description Material S y (ksi) b ult (ksi) >

)

! 1 6" Dia. Removable Pin ASTM A304 120 135 AISI 4340

]

1 5,9,.12 5" Dia. Pins ASTM A434 105 135 <

16 4" Dia. Pins Class BD l

2,4 Top Lugs, Side Lugs ASTM A516 38 70 Support Plate GR70, O&T 1

3 Sling Block Body ASTM A106 30 48

)

6,9,13 Clevis ASTM A105 36 70 15 Grade 1 or 2 i

or ASTM A508 <

Class 1 or 2 ) ,

l 7,14 Sling Lifting Leg, ASTM A306 35 70 Lifting Leg Grade 70 t

11 Spreadar Arm ASTM A106 35 60 Grade B j 10 Spreader Lug ASTM A516 38 70  !

i Grade 70 '

O&T

i i

i (a) See figure 5-1.

I l

8475B:1b-020485 4-2

TABLE 4-2 REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE MATERIAL AND MATERIAL PROPERTIES Yield Ultimate Strength Strength Item (a) Description Material S S y (ksi) ult (ksi) 2 Side Plate ASTM A515 38 70 Grade 70, Q&T

! 1,3,7, 7-1/2" Dia. Hook Pin, ASTM A434 100 130 l 12 6" Dia. Adaptor Pin, Class BD 105 135 i AISI 4340 l

6" Dia. Removable Pin 105 135 4" Dia. Clevis Pin 110 140 4,6 Load Cell AISI 4340 O&T 120 135 Adaptors 5 Lead Cell 17-4 pH s/s 115 140 ccndition H1100 8,10,11 Tcp Lug, ASTM A515 38 70 i

Support Plate GR 70 O&T.

Side Lug 9 Support Pipe ASTM A106 35 60 i 13,15 'Jpper Clevis, ASME SA 508 50 80 Lower Clevis Class 2 Q&T 14 Sling Leg AISI 1117 HR 45 or 71 or or 32 60 AISI 1020 CR l

16 Clevis Bolt ASTM A434 105 135 Class BD AISI 4340 17 Spreader Leg ASTM A36 36 58 (a) See figure 5-2.

8475B:1b-020485 4-3

. __. _ _ . . . _ . . - - _ . . _ _ . . . _ _ . _ _ _ _ _ _ _ _ . _ - . . - ~ _ __ _ _. - - _ _

1 i

i TABLE 4-2 (cont)

REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE MATERIAL'AND MATERIAL PROPERTIES ,

Yield Ultimate i

! Strength Strength ItemI '} Description Material S y (ksi) b ult (ksi) i i

t 18 Backing Block ASTM A276 i Type 304 30 75 ,

Cond. A ,

i-i 19 End Plate ASTM A36 36 58

! 20 Spacer ASTM A588 50 70 Grade A or B 21,22 Leg Channel ASTM A36 36 58  ;

i Brace Plate

) 23 Leg Support Block AISI 8620 40 65 25 Outer Tube ASTM A312 30 75 r Type 304 l

i 24,26 Adaptor, Guide Sleeve ASTM A276 30 75 Type 304 Cond. A 1

j 27 Engaging Screw ASTM A564 115 140

< Grade 630

Cond. 1100 i

i (a) See figure 5-2.

i i 8475B:1b-020485 4-4 i

1

• l l

1 SECTION 5

SUMMARY

OF RESULTS Tables 5-1, and 5-2, sunnarize the stresses on each of the parts which make up the reactor vessel head and internals lif t rig, load cell, and load cell linkage respectively. All of the tensile and shear stresses except for three specific items meet the design criteria of section 3.2.1.1 of ANSI N14.6, reauiring application of stress design factors of three and five with the acccmpanying allo able stress limits of yield and ultimate strength, respectively. Application of the ANSI N14.6 criteria to structural members subject to compression bearing, or corrbined loads result in some stresses exceeding this criteria. However, when using more appropriate criteria, the resulting stresses are acceptable.

5.1 DISCUSSION OF RESULTS 5.1.1 Application of ANSI N14.6 Criteria The design criteria of section 3.2.1.1 of ANSI'N14.6, requiring applicatien cf stress design f actors of three and five with the accompanying allcaable stresses, are to be used for evaluating load bearing members of a special lif ting device when subjected to loading conditions resulting in shear or tensile stresses. Application of these design load factors te ether loading conditions is not addressed in ANSI N14.6. However, these twc stress design facters have been used to determine the stresses of the load carrying nen.bers when subject to other loading conditions, viz. bearing, buckling. This is an extremely conservative approach and in some cases the resulting stresses esteed the accompanying allowable stress limit.

Structural elements loaded in compression are analyzed by the empirical equations of the ASME and/or AISC rules. Allowable stresses for compressien members are based on the estimate that the upper limit of elastic buckling failure is defined by an average column stress equal to one-half of the yield stress. These equations do not determine the limiting stresses of members in 84758:1b-021185 5-1

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 determining factor in the structural member's acceptability. l TimoshenkoIO) 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 larger than the nominal design load and thus, these members are considered acceptable.

5.1.2 Structures Loaded in Bearing The parts of the reactor vessel internals lif t rig that do not meet the ANSI N14.6 criteria (3 and/or 5) when analyzed for bearing stresses are the (2) side plate, and (26) guide sleeve. .However, these items do meet the AISC allowable bearing stress criterion of 0.9 yield strength and thus are considered acceptable.

5.1.3 Parts Exceeding the 3W and/or 5W Criterion The side plate (item 2) of the internals lift rig does not meet the ANSI N14.6 criteria of either 3W or 5W when analyzed for shear stresses. The 3W stress (44,700 psi) exceeds the allowable yield stress (38,000 psi), and the SW stress (74,500 psi) exceeds the allowable ultimate stress (70,000 psi).

Hcwever, this item does meet the AISC allowable shear stress criterion of 0.4 yield strength and this is considered acceptable.

The sling leg (item 14) does not meet the 3W criterion when analyzed for tension at the thread. The 3W stress (33,600 psi) esceeds the allowable yield stress (32,000 psi). However, this item meets the AISC allowable tensile stress criterion of 0.6 yield strength and this is considered acceptable.

The outer tube (item 25) does not meet the 3W criterion when analyzed for tension at the thread relief. The 3W stress (34,200 psi) slightly enceeds the allenable yield stress (30.000 psi). Again this item meets the AISC allowable tensile stress criterion of 0.6 yield strength and is considered acceptable.

8475B:1b-022085 5-2

The base plate (22) and leg support block (23) fillet weld stress exceeds the l allowable weld stress from the ASME Boiler and Pressure Vessel Code at the SW  !

condition. However, this stress meets the ANSI criteria and is actually less than the yield stress at the SW condition and is considered acceptable. t 5.1.4 Structures Loaded in Compression l l  :

The spreader assembly of the reactor vessel internals lift rig does not meet '

the SW criterion of ANSI N14.6 when analyzed for axial compression loadings I and comparing to the allowable stresses of the AISC code (instead of the l l corresponding yield strength and ultimate strength of the (3W and SW I criterion). If we were to use the corresponding yield strength and ultimate [

strength acceptance criteria for the 3W and SW leading conditions, the  :

structure would be adequate. Hoaover, it is well known that care should be taken when addressing members in compression to ensure elastic stability.  !

Thus, structures loaded in compression are analyzed by the empirical equatiens of the I9) ASME Boiler and Pressure Vessel Code Section III, Appendix XVII or the AISC (10] Part 5 rules.

If we were designing a new structure, the material and member size would be  ;

changed to ensure these allowable stresses would be satisfied for all loacirg  !

conditions. However, these calculatiens are being applied to an existing f structure and since these conditions are not satisfied then the ultimate load carrying capability must be determined. [

The column under consideration is relatively short ( = 29.8). Timoshenko(8) {

l states that experiments show that short columns buckle when the compressive strength reaches the material yield point. (The horizontal line on the figure I I

i below).

i I

l i l

i t

8475B:1b-021485 5-3 I l

l r

YlELD POINT I

EULER CURVE I J E = 30 X 106 psi l

N I E I M I N l l u i c

I 5 l l

I I

e 29.8 f/r -80 COLUMN BUCKLING Therefcre the total stress P

• y must be less than or equal to the material yield stress.

for the case cf the internals lift rig spreader;

4600 psi OTctal

i which is less tnan the material yield strength ($,)

Then to find the ultimate column load, let man * $y *

• E$i Then tre masinum column load is the ratio of 36,000

• eaa#* total

• W ' 7*0 84759:1b-021185 5-4

Thus the ultimate column load is 7.8 times the nominal value.

The internals lift rig spreader members are considered acceptable for this condition of axial compression.

5.2 CONCLUSION

Application of the ANSI N14.6 criteria of (3 and 5) to these special lifting devices mostly results in acceptable stress limits for tensile and shear stresses. Application of this criteria to all structural members sucject to other types of loadings tend to result in oversimplified conservatism and with some stresses exceeding the accompanying alloaable limits. Hoaever, when using the more aopropriate criteria for those cases not addressed by the ASI N14.6 criteria the stresses are within the appropriate alloaable limits.

Further, these calculations are being applied to an existing structure and if we were designing a new structure, the materials and member si:es would be changed to ensure these limits would be satisfied for all loading conditic".s.

8475B:1b-021185 5-5

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4 I

i 4

TABLE 5-1 SIMMARY Of RESULTS l

li REACTOR VESSEL HEAD LIFT RIG 1

Calculated Stresses (ksi) Material Allowable

{ Item IdI Part Name Value $ (ksi)  :

? No. And Material Designation 1

W(b) 3W SW 5 Ic) S IdI y uit 1 6" Dia. Shear 5.7 17.1 28.5 120 135 l Removable Pin Bearing: i i ASTM A304 On Load Cell Linkage 8.6 25.8 43.0 AISI 4340 On Sling Block Top Lug 9.0 27.0 45.0 Bending 23.9 71.7 119.5 l  !

1 2 Upper Sling Tensile at Weld 4.5 13.5 22.5 38 70 '

Block Lug Bearing on Removable Pin 9.0 27.0 45.0 I

T* ASTM ASIS Tensile Stress at 6" Dia. Hole 9.0 27.0 45.0

l. .

Grade 70 Q&T Shear Tear-out 9.0 27.0 45.0 j 3 Sling Block Tension 3.5 10.5 17.5 30 48 t Body l ASTM Al%

1 l 4 Sling Block Bearing 9 5" Dia Pin Hole 5.9 17.7 29.5 38 70 l Side Lug Tension 9 5" Dia. Pin Hole 5.9 17.7 29.5 ASTM A515 Shear Tear-out 5.9 17.7 29.5 i GR 70 0&T Vertical Shear Weld 2.2 6.6 11.0 Max. Tension 9 Weld 7.2 21.6 36.0 i

l (a) See Figure 5-1 for location of item numbers and section  !

(b) W is the total static weight of the component and the lifting device j (c) S is the yield strength of the material (ksi)  !

(d) Sy is the ultimate strength of the material (ksi)

]; ult  ;

I I i j 84758:lb-021185  !

_ _ . _ _ _ ~ . _ _ . _ . . . _ . _ . _ _ _ _ _ __.__

TABLE 5-1 (Cont)

SUMMARY

Of RESULTS REACTOR VESSEL HEAD Lift RIG Calculated Stresses (ksi) Material Allowable item (a) Part Name Value (ksi)

No. And Material Designation (d)

W(b) 3W SW Sy (c) 3 ult 5 5" Dia. Shear 3.0 9.0 15.0 105 135 Upper Sling Bearing On Sling Block 5.9 17.7 29.5 Leg Pin Lug ASTM A434 Bearing on Upper Sling Leg 6.3 18.9 31.5 CLBD with Min. Clevis Tempering 9 Bending 10.5 31.5 52.5 1100*F 6 Upper Sling Thread Shear 2.2 6.6 11.0 36 70 Leg Clevis Pearing 6.3 18.9 31.5 ASTM A105 Tension W Pin 6.0 18.0 30.0 L Shear Tear-out 6.0 18.0 30.0 GR 1 or 2 Alt. ASTM A508 Tension THD Relief 2.5 7.5 12.5 Class 1 or 2 7 Sling lifting Thread Shear 2.2 6.6 11.0 35 70 Leg ASTM A306 Tension 9 Thread 6.6 19.8 33.0 Gr. 70 excd.

By Bessemer Process

~

(a) See Figure 5-1 for location of item numbers 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)

(d) S ult is the ultimate strength of the material (ksi) 8475B:lb-021185

TABLE 5-1 (Cont)

SUMMARY

OF RESULTS REACTOR VESSEL HEAD LIFT RIG Calculated Stresses (ksi) Material Allowable Item (a) Part Name Value (ksi)

No. And Material Designation W IbI 3W SW Sy (c) 3 (d) uit 8 Lower Sling Thread Shear 2.2 6.6 11.0 36 70 Leg Clevis Bearing on Pin 6.3 18.9 31.5 ASTM A105 Tension 0 Pin 6.0 18.0 30.0 Gr. 1 or 2 Shear Tear-out 6.0 18.0 30.0 or: ASTM A508 Tension 0 Thread Relief 2.5 7.5 12.5 Class 1 or 2 1

9 5" Dia. Shear 3.0 9.0 15.0 105 135

{l Lower Sling Bearing on Spreader Lug 5.9 17.7 29.5 Leg Pin Bearing on Clevis 6.3 18.9 31.5 ASTM A434 Bending 10.5 31.5 52.5 Cibd with Min.

Tempering of 1100*F 10 Spreader Lug Tension 0 Pin 6.0 18.0 30.0 38 70 ASTM A516 Shear Tear-out 6.0 18.0 30.0 Grade 70 O&T Bearing 5.9 17.7 29.5 (a) See Figure 5-1 for location of item numbers 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) -

] (d) S ult is the ultimate strength of the material (ksi) i 1

I 84758:1b-021185

TABLE 5-1 (Cont)

SUMMARY

OF RESULTS REACTOR VESSEL HEAD LIFT RIG Calculated Stresses (ksi) Material Allowable item (a) Part Name Value- (ksi)

No. And Material Designation Ic) Id)

W(bI 3W SW S S y uit Nominal Compressive 2.1 6.3 10.5 35 60 11 Spreader Arm ASTM A106 Stress Fd Ie) = 19.5 Gr. 8 Seamless Weld Shear 1.9 5.7 9.5 Normalized Upper Lifting Shear 2.7 8.1 13.5 105 135 12 Leg Pin Bearing on Lug 5.4 16.2 27.0 ASTM A434 Clbd Bearing on Clevis 5.8 17.4 29.0 m 9.6 28.8 48.0 with min Temp. Bending a 9 1100*F 13 Upper Lifting Thread Shear 2.0 6.0 10.0 36 70 Leg Clevis Bearing 5.8 17.4 29.0 ASTM A105 Tension 0 Hole 5.5 16.5 27.5 Gr. I or 2 Q&T Shear Tear-out 5.5 16.5 27.5 or Class 1 or 2 Tension 9 Thread Relief 2.3 6.9 11.5 (a) See Figure 5-1 for location of item numbers 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) ,,

(d) Syu is the ultimate strength of the material (ksi)

(e) F,l$s the compressive buckling strength of the material (ksi) 8475B:Ib-021185

TABLE 5-1 (Cont)

SUMMARY

OF RESULTS REACTOR VESSEL HEAD LIFT RIG I

Calculated Stresses (ksi) Material Allowable item Id) Part Name Value (ksi)

No. And Material Designation g(b) 3W SW Sy (c) 3 (d) uit 14 Lift leg Thread Shear 2.0 6.0 10.0 35 70 ASTM A306 Gr 70 Tension 9 Thread 6.0 18.0 30.0 Excd Steel By Bessemer Proc.

15 Lower Lifting Thread Shear 2.0 6.0 10.0 36 70 Leg Clevis Bearing 7.3 21.9 36.5 ASTM A105 Tension 9 Hole 4.5 13.5 22.5 Y' Gr 1 or 2 0&T Shear Tear-out 4.5 13.5 22.5 5 or ASTM A508 Tension 9 Thread Relief 2.3 6.9 11.5 Class 1 or 2 16 4" Dia. Lower Shear 4.4 13.2 22.0 105 135 Lifting Leg Pin Bearing on Lug 6.8 20.4 34.0 ASTM A434 Bearing On Clevis 7.3 21.9 36.5 C1bd with Min. Bending 19.6 58.8 98.0 Temp. 9 1100*F (a) See Figure 5-1 for location of item numbers and section (b) W is the total static weight of the component rad the lif ting device (c) S is the yield strength of the material (ksi) ,,

(d) S ult is tLe ultimate strength of the material (ksi) 8475B:1b-021185

l r,-

h TOP LUG ,, 6" DIA PIN h h SIDE LUG gjh r 5"DIA PIN h;

@ SLING BLOCK BODY ' Sj @

h CLEVIS i h SLING LIFTING LEG /,

'\ 5" DI A PIN h h CLEVIS /

h LUG M rCLEVIS h h 5" DIA PIN

\ ARM h

- a/ ,

Mu%

\  %- wM h LIFTING LEG T ..

4 TYPICAL CRDM% , h

~

y' my , _ _- # s h CLEVIS - N *

/ o h 4" DI A PIN -

REACTOR m o e f' VESSEL o o

,c o HEAD ' ' c' Figure 5-1. Reactor Vessel Head Lift Rig 8475B:1b-020485 5-11

. . _ . _ _ _ _ - _ _ . _ . _ _ _ _ , ._- - _ . _ _ _ -_ __ - - - - - _ . . _ ~ . __ _. _

\

TABLE 5-2

SUMMARY

Of RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE

! Calculated Stresses (ksi) Material Allowable.

l Item Id) Part Name Value (ksi) i No. And Material Designation i W(b) 3W SW S IcI S Id)

y ult i

1 Hook Pin Shear 3.9 11.7 19.5 100 130 ASTM A434 Bearing (Hook) 5.5 16.5 27.5 Class BD Bearing (Side Plate) 11.6 34.8 58.0 AISI 4340 Bending 12.8 38.4 64.0 2 Side Plate Tension 9 7 1/2" Dia. hole 11.6 34.8 58.0 38 70 i ASTM A515 Bearing 9 6" Dia. hole 14~5

. 43.5 72.5 GR70 Q&T Shear lear-out 0 6" Dia. hole 14.9 44.7 74.5

}* G 3 Adaptor Pin Shear 6.0 18.0 30.0 105 135 l ASTM A434 Bearing (Adaptor) 6.9 20.7 34.5 1

Class BD Bearing (Side Plate) 14.5 43.5 72.5 AISI 4340 Bending 25.1 75.3 125.5 4 Upper Adaptor Tension 9 Pin Hole 15.7 47.1 78.5 120 135

' AISI 4340 Bearing 9 Pin Hole 6.8 20.4 34.0 Q&T Tension 9 Thread Relief 6.0 18.0 30.0 ~

1hread Shear 14.6 43.8 73.0 Shear Tear-out 7.2 21.6 36.0 l

}

(a) See Figure 5-2 for location of item numbers and section .

(b) W is the total static weight of the component and the lifting device 1

(c) is the yie:d strength of the material (ksi) t (d) S[lt S is the ultimate strength of the material (ksi) i 1

l 8475B:1b-021185 i

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 (d)

W(b) 3W SW Sy (cI S uit 5 Load Cell Tension 9 Thread 25.4 76.2 127.0 115 140 17-4 pH Thread Shear 14.6 43.8 73.0 s/s Cond H-1100 6 Lower Adaptor Tension 9 Pin Hole 16.9 50.7 84.5 120 135 AISI 4340 Bearing 9 Pin Hole 9.0 27.0 45.0 ui Q&T Tension 9 Thread Relief 7.9 23.7 39.5 Thread Shear 14.6 43.8 73.0 Shear Tear out 9.2 27.6 46.0 7 Removable Pin Shear 6.0 18.0 30.0 105 135 ASTM A434 Bearing on Adaptor 9.1 27.3 45.5 Class BD Bearing on Top Lug 9.4 28.2 47.0 AISI 4340 Bending 25.3 75.9 126.5 8 Top Lug Tension 9 Hole 9.5 28.5 47.5 38 70 ASTM A515 Bearing 9 Hole 9.4 28.2 47.0 Gr. 70 Tension 9 Base 4.7 14.1 23.5 Q&T Shear Tear-out 9.5 28.5 47.5 (a) See Figure 5-2 for location of item numbers 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)

(d) Syult is the ultimate strength of the material (ksi) 8475B:1b-021185 ,

TABtE 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 W(b) 3W H

SW S Ic) S Id) y ult 9 Support Pipe Tension 3.8 11.4 19.0 35 60 ASTM A106 Steel 10 Support Plate Tension 0.9 2.7 4.5 38 70 ASTM A515

, Gr. 70 0&T b 11 Side Lug Tension 9 Hole 5.3 15.9 26.5 38 70 ASTM A588 Combined Stress 9 Weld 7.1 21.3 35.5 Gr. 70 0&T Shear 9 Weld 2.4 7.2 12.0 Bearing 9 Hole 7.8 23.4 39.0 12 Clevis Pin Shear 5.0 15.0 25.0 110 '140 ASTM A434 Bearing On Pin 7.9 23.7 39.5 Class BL Bearing on Side Lug 7.8 23.4 39.0 AISI 4340 St Bending 20.0 60.0 100.0 (a) See Figure 5-2 for location of item numbers 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) ,,

(d) Sy is the ultimate strength of the material (ksi) ult 84758:1b-021185

-'*b-- e..,.-,____. __ _ _ _

TABLE 5 2 (Cont)

SUMMARY

OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses ('ksi) Material Allowable Value (ksi)

Item I8) Part Name No. And Material Designation Ic) S Id}

W(b) 3W SW S y uit 8.0 24.0 40.0 50 80 13 Upper Clevis - Tension 9 Pin Hole Bearing 9 Pin Hole 7.9 23.7 39.5 SA-508 C1 2 10.2 17.0 Thread Shear 3.4 0&T 24.0 40.0 Tear-out Shear 8.0 3.4 10.2 17.0 32 60 14 Sling Leg Thread Shear Tension 9 Thread 11.2 33.6 56.0 1018 Cold u,

Rolled

1. 3.4 10.2 17.0 50 80 -

• 15 Lower Clevis Thread Shear l' Combined Stress 8.0 24.0 40.0 SA-508 C1 2 24.0 40.0 8.0 0&T 5.8 17.4 29.0 105 135 .

16 Clevis Bolt Shear  !

Bearing 7.8 23.4 39.0 ASTM A434 Class BD AISI 4340 l l

(a) See figure 5-2 for 1ccation of item numbers 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)

(d) S[yg is the ultimate strength of the material (ksi) s 84758:lb-022085

. _ _ _ _ - . _ . _ _ _ _ _ _ _ _ _ _ _ _ . ~ _ _ .._ _ - _ __ . . . _ . _ _ _ _ _ _ - _ _ _ _ _ _ _ .._ _ ___ _ _ _ _ .

i TABLE 5-2 (Cont)

SUMMARY

Of RESULTS REACTOR VESSEL INTERNALS Lift RIG, LOAD CELL AND LOAD CELL LINKAGE 1

i Calculated Stresses (ksi) Material Allowable l Item I8 Part Name Value (ksi)

No. And Material Designation .

Ss) i I W(b) 3W ' SW c

3 (d) y uit I

17 Spreader Leg Compression 4.6 13.8 23.0 Fa = 19.8 I9)

ASTM A36 Bearing on Backing Block 6.8 20.4 34.0 36 58

, 18 Backing Block Tension 5.7 17.1 28.1 30' 75 ASTM A276 Bearing 6.8 20.4 34.0 Type 304 m Cond. A 1

l

• 19 End Plate Bearing 4.6 13.8 23.0 36 58 3

ASTM A36 20 Spacer Bearing 7.8 23.4 39.0 50 70 ASTM A588 Tension 7.8 23.4 39.0 Grade A or B Shear in Weld 2.0 6.0 10.0 18.0(h) i i

(

(a) See Figure 5-2 for location of item numbers and section l

(b) W is the total static weight of the component and the lifting device (c) S is the yield strength of the material (ksi)

) (d) is the ultimate strength of the material (ksi)

(g) S{jlsthecompressivebucklingstrengthofthematerial(ksi)

F ..

! (h) Stress limit for fillet weld from ASME Boiler & Pressure Vessel Code, Section 111, Division 1-Subsection NF 1980 Edition, Table NF-3292.1-1, page 50 j

l 8475B:1b-022085

TABLE 5-2 (Cont)

SUMMARY

OF RESULTS REACTOR VESSEL INTERNALS LIFT WIG, LOAD CELL AND LOAD CELL LINKAGE Material A'10wable Calculated Stresses (ksi) Value (ksi) item (a) Part Name And Material Designation b) y g No.

51.5 36 58 10.3 30.9 21 Channel Tension 9 Cross-section ASTM A36 28.5 36 58 5.7 17.1 22 Brace Plate Shear (weld) 18 Ih}

ASTM A36 17.1 28.5 65 Shear (weld) 5.7 40(h) 18

$ 23 Leg Support 6.7 20.1 33.5 '

- " Block Thread Shear AISI 862.

8.1 13.5 30 75 Thread Shear 9 4.5" Dia. Thd 2.7 24 Adaptor 9.9 29.' 49.5 ASTM A276 Tension 9 4 1/2" Dia. Thd Type 304 H.R. & Pick.

Cond. A.

(a) See Figure 5-2 for location of item numbers and section ,

(b)

W is the total static weight of the component and the lifting device .

(c) S is isthe yield strength of the material (ksi) the ultimate strength of the material (ksi)

(d) Sult (h)

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 84758:1b-021185

l l

1 i

f TABLE 5-2 (Cont) i

SUMMARY

Of RESULIS

! REACTOR VESSEL INTERNALS LIFT RIG, l LOAD CELL AND LOAD CELL LINKAGE l

! Calculated Stresses (ksi) Material Allowable

! ItemI *I Part Name Value (ksi)

! No. And Material Designation i W(b) 3W SW S IcI S IdI

! y uit '

i i

4 25 Outer Tube Thread Shear 9 5.5" Dia. Thd 6.7 20.1 33.5 30 75 i ASTM A312 Tension 9 Thd Relief 11.4 34.2 57.0 I Type 304 -

l Sels. Cf. &  : '

l Ht. Tr.

l Y' 26 Guide Sleeve Bearing On Engaging Screw 20.2 60.6 101.0 30 75

{ 5; ASTM A276 Thread Shear 6.7 20.1 33.5 Type 304 ,

Hot Rolled & '

Pickled.

Cond. A i i

27 Engaging Screw Bearing on Guide Sleeve 20.2 60.6 101.0 115 140 ASTM A564 Tension 9 Thread Relief 15.0 45.0 75.0 i Grade 630 Thread Shear 7.8 23.4 39.0  !

Cond. 1100 l

i (a) See Figure 5-2 for location of item numbers and section (b) W :s the total static weight of the component and the lifting device i (c) S,is the yield strength of the material (ksi) ,,

j (d) S u't is the ultimate strencth of the material (ksi) i 1

i l I

j 8475B:1b-021185 i

1 71/2 DIA HOOK PIN @

SIDE PLATE @

h UPPER ADAPTOR 6" DIA ADAPTOR PIN @

l h LOADCELL BOTTOM ADAPTOR @

@ TOP LUG 6" DIA REMOVABLE PIN h l

SUPPORT PLATE h h SIDE LUG h 4" DIA CLEVIS PIN

/ d SUPPORT PIPE h SLING LEG h I

h UPPER CLEVIS p

/ 4" DIA CLEVIS h EV S j h SPACER END PLATE h

! \ p LEG h SPREADER CHANNELS h LEG ASSEMBLY

((

h BACKING

"" . R [d.d2;,

> JG y i g 2s

• ^

[ j g i 9 6s

/

y RING GIRDER n;f# ,

/

1. ] /

ADAPTOR h 6

/ OUTER TUBE h U

r

@ BRACE PLATE h LEG SUPPORT BLOCK Figure 5-2. Reactor Vessel Internals Lift Rig, Load Cell, and Linkage 8475B:1b-020485 5-19

t j

i 1 i APPENDIX A DETAILED STRESS ANALYSIS - REACTOR VESSEL INTERNALS LIFT RIG ,

ThisappendixprovidesthedetailedstressanalysisfortheDonal[fC. Cook

. reactor vessel head lift rig in acccrdance with the requirements of ANSI 4 j N14.6. Acceptance criteria used in evaluating the calculated stresses are I based on the material properties given in section 4.

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i 1 i SKETCH $HEET

, etst ems = oust toew S4202 ,.

5 a- ..c a c , ,, , ,

ABKP-188 Donald C. Cook Units I and !! '

1 ,., 30

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J. Urb.an

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1. The purpose of this analysis is to detemine the acceptability of i 3

l this rig to the requirements of ANSI N14.6. ,

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2. The results show that all stresses are within the allowable stresses.

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A WESTINGHOUSE NUCLEAR TECHNOLOGY CIVISION

' AGE 18 T L E Reactor Vessel Head lift Rig t o, 30 s a gJE CT Av1 06 Daft gsa DAfk CM A D S

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. v.e c i avi-pa u*it c- a . . vart e-~u..

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(,a so c,a o s ABKP-188 CHE D ES IC, N W E I C3 ti T W '.'J t.t U S E C THRoucH0JT

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t= rudh,ik c sk.olaMn= svs. wiads.

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WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION T*,LE P.GE Reactor Vessel Head lift Rig y a, 30

'. a c.t L T .V,M M LATE CMM O Bv 4]A,L CMA D95

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9= forte. eeNngon as:4 m bipik. .. GE ARING STRESS . __

. . . _ . d =..diaen.tse o f p in, ini . _

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.__ . a.=_ t.qut_of h. n'q 3A _ _ _ . . . . . TNNER .

on .ca e u.r_w. apis. _. _. . A5 ct.9 - (. ma. X4.n 1

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= ( . 3 "/. E) ins .

sur b.o dn. _ __ - ._

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L. . tet.Lu.mp .L_ _ _ _ j w .(,.o2c 9 L 1 . _

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_ _ _ . = - ..! + .2(a + g)___ _ _ _ _ _ . . _ _ _ _ _ _ _ . . . .

- O U T E R. _ _ _ _ . .__ _

_ P_ . .W ' . A= .u0,0001 ..

k 2.ad= 2( 2.98)(s.990

_ d a m 9 a 2._.,_in. . ._ .

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l WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION TITLE

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so cg No .gt e w s c o.

CH,t ABKP-188 BENDINC STRE55*

k=(P/2 )( h + c) + M)yk b ( W }/2.*(2.38 /2+c,ms

+ 'e. L 3 /4 )=32/(1r(Astfl

. - W ( c.079B1) k- G.3.93R m,

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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TIT L?

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- BE NDI N G STREhh FOR MUL A DE MVAT. ION -

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i WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TtT Lt 8 AGE Reactor Vessel Head Lift Rig ,

e, 30 PROJECT AyT* 'R DAT& CMg Q sv QAll OMgQg, gayg AEP/AftP /ky sy k, l'$ ., g % Q,.]*

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c;ctw.sto ( rt.metato w ,

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q A,* (n.* -c..cnXi.Wz BEARING

• Sc. A;A f, = W/2./2./ s.9%

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dw.u on W . n, % aW pik @ .

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= W ( . O t 9 019 )

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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l

Tif Lt

• AGE l Reactor Vessel Head Lift Rig q o, 33

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!

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• A epr , g % p, @ c.... . .,.3 e E - bh*/G = 3.99 *lt.W/4

• 95.20Zmi b w (o.ots u s) G,.... T( .ou slB). w( on40)

4. = 5969 m. 6.' OI70 m

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WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION tiig( 'AGI Reactor Vessel Head 1.ift Rig jo o, 30

. exct .vt-c o.v. c- o .. , oats c-s a . . o.t.

TJ Atr/AnF 4 a #A ,Vn L P1 cy ~o oaov-rf ~a CHE UPPER. St.T.N Ce t t. r.. S H E APL STRESS.

PIN 5 n e u m . e n u .sao w u a R - P / 2. A ,.

m -tm o nm r P= . % 4 2. w m ,.am .~a A,- ed%

g- ->- g A, Tr( 4.990)W 3 ,- -

a- " Ay= 19.5 5 4 in'

~ -

. i _

. . ft *- ( . 34 47.W ) 4' 15.'.5 6 )

• W ( O.DO 9211)

. - . ,I " l . . .,, . .

fv =

2C)RO pst

-- - . e r%

Mir -

- ;m @ ru m P. b .ac.agonnmWA BE.ARING STRESb.

.d =._ diam.n.se of pih r io . _ _ _ . .. __ . . _ . _ . ' . _ _

4._13sh_LI.m3.we4 . _. ft - P/ A ,,_ _ .._

.te *_nt.4J~ P= . 34 42. W . . _ _ _ . . _

a_ l.rph_.O nh.2A __. _.. T N N E R. . .

en .d de. =E w he_ b d3 sh._ Av ci.9 - 0 m has _.1

__ _9._ gap.bA m b.nh3  !: * ( _l9. 86 h' surfas.o,in. Sc.=__Lw4_'1Vd/(19.% 1. _

L

• htalarMys.JS+.h4 = w _(_O.oiE 3).t 1 _

pai,e E= 59M m.

- L.2(a y)

__ O U.T E R__. _ . . .

P - T a M 2W_168.J .'. A=_2 ad=."2(.t._B'S )(4 9R0)

_.cQ_1ar/AnoA. = (_12.% 3_hn? .

._)., s_ z3.9 8_ s 4..=_L%mM/_(J8.Huu

' a,p.es p.ss..w

_ =

= WLaat9n2.6) .

_S _. m-.g ._ '

. 4. ._C.,312. m.____ _

a u t e.o m omit C-a o e , pate c-a o e, oate

.. o batt v.ssis.c-C,wst a PORY'87130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l

tit ti s ct Reactor Ve!,sel Head lift Rig if c. 33

.aoa ct .vt- c.t e c- a .. com o .. c.,.

! AEP/ AMP h - 6,h Al 1 ,Q /,/j ,12[goit -~ -

u, ov.

! so ya 4.0~

ABKP.183 c.{so CHE BE N DT.N C= sT RE55' 6-(W2 )( % +g + S 4ap 4 (.um)/z'().? s/2 +.zu

                          + 3.% /4)'32/(v(4y:o)$
                           = vv (0.0 2 2'lff) h \ O. 4 'Mo m.

_. . . . . .._q. . ._. . . . . _ - - . . _. . _ _ . . . . _ _ _ _ _ _ _ _ _ _ _ . . . _ _ = _ . _ . . _ _ . _ . ....

         =                                                              _-               -      _ _ _ _ . _ _ . _ _ . _ . . . . _ _ . .                                   . . .                   . ..
         .1_teu Arr.m_DEArvEO CM.P(.foi                                                            _               _ _ . _ _ _ _ _ . . . . .                            _ . . -                  _ . . .
          .._ .Uhth_W ORhT_- C.Mt                                                        _                      -
                .DD4EN MMIN Cm--                              .__                        _      . . . _ _ . _ . . _ _ . . . _ _ _ - . . _ _ . _ - - - _ -
     ,n                 ,,,,                         .v,-o-                          o fi c-               c ..                                o.ie c-o.,                                           o.t.
     *.i.               Dft o t %f *eG-c vSt 8 098.' &$213o

WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION Tit (t eagg Reactor Vessel Head lift Rig  : il c, 30

   .aus.ct                                       Avi- e                            cast       c~.a..                                                 c-        o ..                                                                                 c.t.

AEP/AttP h x t,,h b 1,Q/,/j,.2[gouit unou-so cA o so - 9 <.o-ABKP.183 CHE BE N DT.N Ca STRE55' k=(W2 )( h. + g +4I )wk k= (.ww)/2 * (). S/2 +.2n

                         + 2.% /4)'32/(1r(4yo)$
                           = w (0.0 2 2'79) k = 10. 4 93 (o Ma: .

_ . . _ _ _ . _ _ _ _ _ _ _ . = _ _ . _ _ . _ _ . _ . . . . .

                                                                                                   ...__==                     . _ _ _ _ . _ . . . .                                                                                          . . _ . . .

_1 EquATroet_DEnryEQ CH.P (f oi .- _ _ . _ _ _ _ . . . . . . _ . . - _._

           .__.uhT.n_WORhT_.                           -

c.M - - _ _ . . _ _ . _ . . . _ _ . . _ _ __ DIMENMCMINCs _ ..._ __.__ _. _._ .. _ . _ . _ . . _ . _ . Avipum DAtt can L et cafe Cum o av patt ogy agy 0418 WLSti*eQMLwSt8099SL2130 e

1

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 'l                     '
                         .                 .'. WESTINGHOUSE  ,                       NUCLE AR TECHNO.   -

OGY DIVISION y e , l

    ',,,tr                                                                                                                g                              40.                             l Reactor t'essel Head 1.if t Rig                                                                        ,,                                      12  c. 30
    .aoa c i                                                                              .*,i    cm..                                   o* u    ;-o..                   o.,.            j AEP/ AMP                            .q$p\    1   .            .v %!,                    4 A'1,Lg'[y3
    ,o                                            c.sy so                                         su so                                          oae -

ASKP-188 CHE i UPPER. S LINC, LEG g "THRE AD SHE AR CLEVIS T s. wat a ::, . e a.a ::; w t M Al 'L ; :m e. A.:. sc o, we u ING ASTM - A - 105 G,1

• O R. ? Lt S P QQLNLHtD i RMPM10 WIT * [y
• h s= IT N2. )

k A A (Nm3N e cunst . l o *'d r -.s. 6 A sT. ASTM - A tog <.,sm a ca 2, -r v a W \/ .w wc 7 a \ i QuNWs0 t MMato W3T H t*

                                                                                                                                              \ hl
                                                                                                                                       ~

MA C.AM.c4 Oc 4 ? L uT' . 2 0 *v* PSI Ii i tP - 5.m.4uN 19 -hH

                          *-             6. 0 3 7.D i

12. 0 3 lt, $ 7 1

8 N i

                                                                                              . _-                                             s.o,<4 i       T                Al iL                       .h              5.049 I

8, - - - - - a^ _ _ __ - . - e 9 ' ( s.oio 6.00b 4 V g 1 03 l.9'I i- f'.D M P - ,, t, i  : 8.13 . l ,,,, , , s. . s i v ..

                                                                   ~

U il i.. 6 .. . v.iif.6m. va'e t

     .,i         nati                                                                                                                          i

_ . . _.. 4----- -

     .,..t.*t.**,vit     aom'.'t y1Jo

l WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION v., u ..c. Reactor Vessel Head lift Rig l3 e. 30 P d asi ci av "s m Catt CaA D tv 0416  ;"A ee' cait AEP/Af'P M w b $3 3 g 'A / '[f's 3O CA NO ' 48A t '.0 G R C Q. CHE ABKP-188 UPPER SLING LEG SHE AR Tt. AR-cut CLEVr_s m u.u. m see o- a i x fy (P/2)/2 Av d Wl R1 GEA PJ.MG srREM )'l 2-[, wsbearij hw 6 % .p w ,,, II 5 ems sh h oub bwig ska w t.n vpp4e stig n.g Av*Yi k bmp vis pis caWioA f,,, w (.. ot99 2. 6 ),. - G . P/4 '4 A+ f+ fy . W (o.otsw ) (- (o 312. , nt  : ' ( =-( - 4 0 c 2 = TEMuoN t 4( A-A. . TEM SION e. M -

                                                                                             " THREAD ret.IE F Lh                bl                  .

f, . 5.m- - - - - - ---- d "%.m.u P/Ag I@ m a-*[ p - W C,2 G 4 7. ) A+-bh-TrdV4

                                        .734         P/A,                           f.h             , 7.99(as$-Tt(s.os*?/4 P - W (.w 4 2. )                                              A6,169             u,=

Ae a20.wX4.w 55F ) q (. m )' 4 aW (.*" )/% i es w (, .00189% )

                                          % = n 9.'i R O                                       ft =         ~2.5~2.5            est 4 = W(,%41 )/(19.'Kf7 )

w (o.ois w'i) .

                                       ?t ~ cooOA                     m W u av                Nft    C% D D'             M '8 m.,       ngy                  av1Hym             Date
                            *. 3      Daft
                            .'.tStiNLaQw%t fOmv t,g3i30

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION tif Lt

                                                                                                                                              .aGf Reactor Vessel Head Lift Rig                                                                                                   jy   o, 30

• Host C 7 avi (N. DAti CMa O 6v Da16  ; M a. O 5' CaTE so A Ei'/ A'? hikh J' N3 4 f Ag #/ft .

ca Ko SG T caov. AE G-188 CHE SLING THRE AD SHEAR LEG 6.p/A, M Al'l ! Ay Dr a )/2. rei. = s.co -4vs-:8 r-r t u o ASTM - A 3Ofo GR. 9 O Opw = Dm. .'e*c51/n Exc.D STEEL M ADE BY Dr%

• ii.00 WSn/4 5 4.51%

G Eh t.M E R. P P.OC

4. s two3ce c.bame.kr-c f cs k eno A 4 % ect n

W s nom ber of %*ab

                                                                  ,,                pu%

7 iw (Pu ava9 7 t>wt.)

                                                          ,                                 2 i                                            Ae 53,D2 W i         l P = W (. w 42. )

fy- W l.%42 )/53.\92 l  ! '

                                                                                                                   = W(o.oocerfi n'
                                                                         ,                &=                                 21 9 1              m THREAD TENSION w                   .

4 .P/N y .4 =w x) %g y =ch As Y4 ( Dm,, ,991$f

                                                                                              , %(s .m2/4)'.19.969p

( = W ( %4 2 )/n.%9 1

                                                                                                              .w I

l i E ' e(o.020so n sto O PE ) 6 < I  !

                                 ~

s.co.4u% 1P l Zy ,, n mui v uni c -. o n . on,e caTijcn o av pave t

     .u s t . .c - :, v . s . :. . v i: mo

s 9 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION

                                                                                                                                                    ' AGE TIT LE Reactor Vessel Head Lift Rig                                                                               )7       0,  30
                               *ROJE CT                                   AVTMO                  DATE CM A O Sv               g DATL CMK O Bv                    LATE AEP/AftP                        _.k phb'/g f; [ M y f SC                                         CALQ NO '                    p E NO                                 GADv'
                   ~

b' CHE ABKP-188 l LOWER SLIN6 LEG g THRE AD 5 HErhR Ct.EVIS Tt -u- s-en _. --t N k) 'l. * ~~. *** *., A E 2 ". C * - E ,, 7 , *a ASTM - A- 105 G R. 2. c R 2. Lt , c  ; QQLNCAD ( h.m9UuQ wna .,e L. . " .)/2. ) M% (NtouN c.witur .30% ' t~

                                                                                                                                                                   \

A CT. - ASTM - A SOlh C.N 1 C8.2- rv = W ( s0. 00 G ~o C 3 i QuNuso I nmMuo wzTH , MA C.Aiscq c-ouTt.ur . 30%, v l' 9 I F5: i tP o l- e 5.Q.4UN -2 0 -LH e - 7.9'18.01 % gg,m ' I g, p ' i L N- & 5.094 7 %T ik h 5.c4Mg

                                                                                              #        h                I       i A+

f . _ _ _t^ -- - T -

                                       .                                            5.01 O ses +

V _, z.e 5 l.9'7 em P _ ,,3 , - , 8.33 Daft CMA'O tv OAff CMn O sv OAtt pf y sty AUTMon NO DATI t a $ i t ** G M O US E F O R 4* ? l 213 0

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION YIT L {

• ACE Reactor Vessel Head Lift Rig , 1, c, 30 P ROJE CT AUTHOR CATE CmCa av g DATE Can O B' OATE 20 I k 3 L NMu 5C CA 50 GAOVP G. E N O WEk 5.LLN4 leg $p =,,A E. T R R -CUT CLEVIS Ne eu. 7e ut n-a i i I f, (P/2)/2 Av

                                                                  /

Ah _ i EE A P LNG ErRES.5 The becr r. h ,' y-" Ii

w. - is h e. 4_

f LEL t E

                                                                                                                       $ '{

U S M C. aSL hhe. Cub hetg s h en t% Av = V4 Ag bm pi. woe pN mer sis le[ , cakMoa k : W (, . -

                                           ^- e ),,

f, A E/4 lAt

• t k= b ' 1 fv - W ( .oss% . )

P .I [p = ( = /~n 004 *=. TEMSION Q, LEC A- A TE M SI ON Ct. H *-._. THREAD RELIE F A ' suo7 --. - - - J-- dSi y { , p/4 rg 7 p w ( , a 42- ) m ^-8 . _, ( . 6 - ndy4 4 = P/A, Rh 2 tM(aa$-7t(s.ouf/4 P= W(.a42.) k

                                                                                = 4. jpg, p As a(i.99X r

4.w #? ) fy - W (.wu )/%.169

                 -4(.or.f                                                         = W (,. coq 689 )

Ag = l3.909 0 f+ = 252M pst fg = W(.mt )/(19.909 )

               - W (.0iS %r; )

kt' G004 Pu ,, A u f p u se OAft C M *L D g, DATg twA y av Daft i DATI

   $* iNGwOutt # C"* 15213U

WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION TIYLE

• AGE Reactor Vessel Head Lift Rig 17 o, 30 P ROJE CT AUTM DATE CMM D Bt C " m, D D' CATL AEP/ AMP MTpA b EM j.[f.g/,wf'[CATL h GRNP

                                                                                                                             ~

S O. CALM NO. f ILEXO w ABKP 188 CHE LMER st rNCe L.EG g S H E AR, STRESS PIN meu As.TM A-434 ceno wrm { P / 2. A , m m mt m, on n oo= , p. , w 4 2. w Y.." A,- Trd%

                    %             *-- T                      ._
                                                                   %                                      A,- M 4 990)W Av- is.s s 6 in z

__5 d f = (.2e uw ) jp_. n.:s- ) t  ; .

    ..                                                                      "                                         = W (O.CC3 L i ?.)
                           ._, 1 l

fy = 13SO e u.

                   # y .                                        wm
                                                                   ' QLi nw .

_ .-.= . .a _ . _ . _ __ __ _. _ T..__% . ac

                                                                    . . m_.
                   .2=_forw acAsg on_au mW y,th.                                                      GE ARING STRESS                                         ._ _

d =_ diam.he_of pnr in __._. __ -

                                                                                               ..j_ .                                  .          .         _ . . . .
                    .E _1.ngth.=E k arin p er                                      . _ _ .              f - P/Aw_ _                         .. .             . _ . . .

ntueur_6a u s _.. P = . 2542. w .. . a.=_t.cph_oE.hearig surb __ _._._;.. . T_N N ER .

                           -- o n . d d i o E s k r_ bo d p k                                     ;    . Av             cl.9 - U.no h9i 1 a =_pp.b.b n 6.ciny

.- = ( 19.B 10 )ins sur6 gin. $ =_(a s3LW)/(l*>.Biol .

L

• h+aLaw.Estigt.h of ___ '

_ z_WL O.) 638 31_ ._ _.. py *

T_ - C 5BB3 m.t _

1t 2(ag) _ _ _ _ _ . _ _ _ _ _ _ _ . _ . _ . _ _ . __OUTEFL.. ._ __ _ P -T.= .3642w tt .'._ _ A =_2.a4= 20:es. X4.wo) _d A % c _._ _ in _ = ( lB,%S hn' _ . ._ EN _ . c_ k _ k*(_,1691_W)[_b6.N3.). .__ _ag__1._B5 . S = _ggx2so__3.._ u l = . W(so1937Jo A l t ? . re. ___. ) . pgy pgy AUTMON DATE CMK'D BT DATE CM A D ev DATE NO DATE WLSTINGMOUSE F Omv $5213D

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION 11LE 8.Ct Reactor Vessel Head Lift Rig [f o, 30

  . .s , . . t ,
                                    ...q-           .,a,  c... o o ,      r,c . c . . .- i , u .         v.,,
 .: a AEP/AfP             hhuMV93               J, k - M,j '/93                        -
    ~                              ctjc uo                46 6 r o               caoua            -

ASKP-188 CHE BE N DT.N Cs ST RES5* fg=(P/2 )( h + g +4I )[d3 O ( w0/2'( i.es /2 +.no

                      + ? ,9'? /4 )'32/(v(4 99)')
                       - W( . 012 S O )

f d- 1.'z 4 9 fc Psr . toumm Dep,rvto OM P('g)

 ..,.              ...             .ui-o-          o.1. c-<o     ,     c.1     c-~o..                  o.1.

i' . " j0 1r 9

  .. r . . ;.. a st .o...::. m o

l WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION PAGE TITLE i Reactor Vessel Head Lift Rig l 'J o, 30 AUT R CME D Sv DATL C*s D ev DATE 6R4 L Mp P ROJE C T f/ AEP/AtP d 'DATE hb GMOUP r S 0. C C NO F(kE % SHEAR TtAt. cur SPREADER : LUG Q Pmatt To seu n-a G P AA, T e A v = !i At

                                     'f,

• 6 = f, = W (,0\S 3 i3 )

G= G Q'a vc s.eu g

                                                ,4.94
                         ./           '

4 [ <.' . . i; ' - - ',-i 4$(3, T:E ARIN G w be a r iq s4.eu 6 h. u . o s 4 ,- w to. , st. g M4- .- k gpis A w bean g d m

                                                          ~"            '

(, w (0.0109i )

r. o ' E= SBBS ya 4.34 vwh M AT'L *. ASTM - Asif.

GRADE 90 QUENt.HEDl Ttt*PLtto WITH M AA CARBON toNTF.NT .MYo TEM sION e set A- A { = P/At. Pm.. . T = . %4 2.W As * [4.94 N-5,c4(3.M )

                          = b.M4 A

[t *W * *( Dl8M .lW/I>39b) Pu A= G O ') 1 DATE CME'O sv DATE AUTwom DATE CHE'O SV

    #Fv       #EV.

NO oaf f V*i STINGHOutt F O R*

• 5'2130

WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION TTLE PAGE Reactor vessel Head Lift Rig 20 o, 30 r; $h dh, ffc, Aie non c, AvT-o oaTE c-< o . c- oav oATE AEP/ AMP h obly3 sc cg ~0 . g sw - c0-SPREADER ARM NOMIN AL, C.OMPRE L'Jv t . ST R E n T. N s, p R E A c r a. ARM M AT 'L : A ST M - A I Ofe GR.B, EE AMLEtt ( NOR M ALI E E D i 2 P ces 30* = K k[N '

                                                    /               f )

P

                                                                                          =   K/2 /c05,30" W +.im?/.8%o2/2
         \. ' ' . ^ sf#"/        .
                                                    ,4                                   = w (o.oB4G 6) 11 nto*        '

w ,. - .

                  ,          f %' 7 FOA       FR 0.00          %H 20 letb \                  %      ,Iv            /,. * * . ;                P3 Pl. (MNtd H43GK,, $*td, 99- 155) ss u o                                    /   . . , ,
                                       .e-                 /.. .         2....      Ag- 11.% M
                           \

5;i32 [t. {2%so '. . I s tos.7 m *

                             \ llq / /                    y .;. -

S = 2. 4. 51 in'

              ,              .        ,    /                                             r       2.sn a rs
              ,                       y          *= teo usm Pm.

P,. w" .- f+ - p/At

        ~                                                                                 *
           ,                          , g ,,ggg 9 W ( . OB%B') /ti.%

W(.Cor. 6 %) k q f_* t 21?_4 PSI-m o w s o u. m m u m m s.ni u , g- 7 ,,, n,. ( Ane. manyw) O/  : xS 5 > I O' " - ' - " "~

                                                                               ~J .wI 40.16e k .s %A.ii) r      2.89ai.
           ** i7

, , Av7MOR DATE CMCO ev DaTEICHA o av DaTE

• S

.       Da70 v.at*t% ~CUSC80A. 15213D

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l TITLE ' AGE Reactor Vessel Head Lift Rig g) e, 30 ano;EcT Av7Mc c4TE cMK o av oATt cMoo e, care AEP/ AMP hg(hkg f.M 7 5 O. C A, L Q Pw o . F l ua7 P.O.' GROUP ASKP-188 L/ CHE SPREADEN ARM gg SME ADEP ARM '.'.T.D

                                                                         ' T t'.2RVAT!vtLN Whiu +- y W' -

i ni w . o ts a gr- ( , K 1/r= (.O 140.4/LS9S AND J M "'-..*..n A.n. 29.'?20S A .P. ,o sa ccutiv.r so wnr

 ,                             J                                          A.L %L Cat.:.15 1 RiMM C., * \                                            'T . NTT :4 s *T e       K.'.' ;;s a 7

• t~.'.. h 7 .; ,

N F7 Ict E,= 3su ^' ' N " #: 'n * * '- 2.TF 2.9,000,00'$ y, 7AN.7.3 %'." T at M to a > gg,oog . m w as WL TW 62 A. ,

                                                                                   .           _t                       ,e e . x,
                          =

12.9.888 ' '

                                                                                            -     R                ./
                                                                            ,- - ,8 y-                 _
                                                                            ',_i_.,

cme: k Wr < Cs e Mc 94, o, = o llowdbit c.ow pms iv s R cubid.a radiU3 s @.D. + 2.tY2. 3.% 4 W.abuni oS t.h b urau ,%Lm.u ui n = [7.szv + 1(.saf, h = 9.ms A = g mom.m%ik1/c)/c.c. J 7:a in E = 0 - R/2 ) Fs

• TTR ( l /5t',9 4.1)

(.%ds A- % A*) - 40.69 % h = ss,ooo .ry = P/Av. . A= 2 3.220'A /127.BB8 A, = T.J.9o7, ww E a 13

                      = ,2.2.% %                                               ,,,ihw P       W (O.08 4 8)Ik Fa -     B ,4 6 B est.                                 A, . 40. css (. sox.no,). l'i.~ns,J 6 - w (ACD58142)

. -v' \B% PLI p, gg7 AUTMom DATE CHK D BY DATE CMK'D s v DATE NO DATE MSi rNGMoust 8 0549 S52130

a WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TIT L E PAGE Reactor Vessel Head Lift Rig 2 L o, 30 emosecT Avr-e oAva c-a o ev oATE c-a o.e, care s o. AEP/AttP MMdD c g rJo. - (fesa iR h g caova V PPER LIFTING LEG q S H E AR, STRESS PIN neu Ana - Au+ c.wo wna S - P/2A, mnnnnem er n ocfe P - W/2 _. s ,. - = - A,= wd% l + - > -

                       ,- i
                           , *3                s-      +-

A 9( 4.c)9o )*/4 Av= 19:sr G m- 2 d fs=(.W/2 ) @ !9.E) 2 t  ; - _

                                                                                                                                              = W(C.OoBE2.2)
                            ;l     "
                                                "l                   ..u   .y                                                        fv     -

2927 m um%

               .A.                                  ..                g gg g _                  . - . . . . .                                                                                                                         .

_ _ . . ._. .. . _ 3 ___._%_ _ _ 9tm _9=.forw. ac.Mngon_ammW 3L GE ARING STRES5 ___. ..

                 .d .=. diam tse of piny in .._ ..                                             _ _ _ . _                                                                                                               ~~
 . _ . _ _ J_ _1 SthM_kach suem                                                                                - _ _ f,. - P/A w ._ . _ . _ _ __ _ _
 . . . . _ . .; .. atc a,_ w >sn-                                                                                          _ . P = W/3                                                  _                   . . _ .

_ ___ a :T.N N ER

                          ._t. 3 w .of..b u n h 2 A ..                                         . . . . . . . . . .                                                                                                                   .

__ on s. W e. # w k , k e d p h ._ _

                                                                                                                           .. Ar ct.9 -(A9900M 1

_. _ _ p .. p p_ktu a ba dn y __.._

                                                                                                                                      ..

• U9,%10)in?

_ ______sark gd . - ._

                                                                                                                    ._._.f<.,X_ LWl3_..)/(4.% 10) _ .

___.L *_ tem at.ikiq+.h of _ _ __ _ _ pia _.Ic* ! =5384 .WLOlb82fol_ m_ .__ . . _ _.

                               .L+. 2(a.+g)

OLIT E. FL ___ _ . ... P - W/3 . . _ IL . . _ _ . _ _Aw=_2 ad= 2.LLM.)L4.990) __d , m. 990 - ' in, . =L.lL10_hn'- _.)$L.9 7 _t __ (.=_LwI.3 )l(.LS.% > 1. __ Q RS ... $ = W10.Q1 AoJ'i.).__._ _.p . _A 2 a o___m ._ w . _ _ _ _ _ _A = S V 1 "1 re __. _ _ _ AUTMom DATE CMa'D ev DATE CMED.av DATE

,,y                  ,gy NO                   DATE

• tSTINGHOUSE 8 0mv 552130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE

• AGE l Reactor Vessel Head lift Rig 72, ~

e, 30 PROJECT AUTHO DATE CMn'D Sv g DATE cMn O sy puTg s o. AEP/At1P cAcc no. Y - b gew ry g j d M oRou, U CHE ABKP-188 BEN DT.NCs STRES5* E =(P/2 X h. + g + M) d3 4 ( w/3 )/as(i.s5 /2+,2so

                              + 3.9 7 /4)'32/(1r(pc)$
                                     =

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e

          +         EQu ATIcw(_ocpy.y e.Ct_QM_P.Q.L                                                 _                                                                  __.. ..__. __ _ _

DATE CMK'O S V DATE AUTMOM OATE CMK'D SV REV AE V. NO DATf V.LSTINGHOUSE F OMV L52130

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pin, i Peactor Vessel Head lift Rig jq o, 30 m n .1 avi p oi16 c- o e , , cast :-m o .

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   ~

ASTM - A- 105 GR :L c a 7. LE G c QutNuso ( wmpuuo w:m E = (% n 2/i i MAK CAttacN @uTtu- .10 3 A t.T. ALTM - A SOB C 'u a C8 7- W . / 7 ' k:l @ l' CrGN'JG I it%MnO w:I H MA C. Ate c w c.c u t u ? . 2 O y= 2 C C; 5 es: t P* a,

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                           . - a. >.em , _ .-.,

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1 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l TITLE pact l Reactor Vessel Head Lift Rig y 5 c,, 33 PAOJL CT AUTMQ CHE D bv DAlk CMn QSv CATE s o AEP/AfiP d d ,DATE 7L IL Q /M,,,(

• r .6 Gaoca l

CA(c No ASKP-188 lg' CHE l UPPER LIFTINb LE4 gy,9 R TiAR-cyT CLEVI.s NM *

• u - B - - + -

i rf fy (P/2)/2 Av 1 BE Alu.MG S.T. REs.5  ;

                                                                            - ['l lg                   I{

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                              &Nm "-           -
                                                       'i          THREAD RELIEF mu-    - - - ._ _ .M..-

f . T@ stu-a b ,m . , P: W(t P/ A g/3 ) k - bh - ndV4

              .f+ =           P/A,/3 dh                 3 W CB36)- M m *f/4 P= W(l                      )             ?

• O.169 - M Ag = 40 99X 4.39 - T ) i f+ - W ( I/3 }/% M

_j.,,,(.cxf =. W (.007 220 ) N = t 9. 409 0 f+ = ?__ 3 \ O P2 4'+ - W( ill )/(19.4M

                     =

w (o.019199 ) Er ' s M 94 m DATE CMK D BY DATE CMn'D Sv DATE REV av7 MON r4 E V NO DATE ) NiST *.GMOUSE 5 OHV "52130

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                                                                        &ll $f

• ROJE C T OATE CHK D
• OAft can O ev cATE so AEP/ AMP \)([ G u h %

cAsd so b '-

                                  ' -'                       #j t N O '                 c. a o v e ABKP-188                                                                                 CHE 1

LIFT 19 THRE AD SHEAR LEG fy = P/Av Ay = Dp.sTrJ / 2. M AT'L rea. a s.co - 4vs-2x wnuo ASTM - A 306 GR.9O DA = D , . GM951/n EXC.D 5 TEEL M ADE B't Dr%

• 5.00 .W9s2/4 4. 51.S3%

BE.% E M E R. P R O C., 4. 2 YhojoechamAr-of c O rna.1 4ha d, h h 7. nombe.r of %wath

                                                 ..            per- O
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                                                 . ....                   Ay. 53.\9. s. '

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                                                                            'M
                                                                         , % ( s . m ss/4 f 19.qr,9 O E+= W ( \/3                ) /I't.%4 I      l
                                                                            =  W (ChotB7 5 9 )

l E* 4 Ca h 0 3 PSE I i I i s.co- 4um f4; v RE v AUTMON DATE C"A D 8* OATE CmacO ev oaTg

• OATE

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i WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION YtTLE ' AGE Reactor Vessel Head Lift Rig 2 7 nr 30 aRoncT AUTwo oATE cnco av cavo sv cart AEP/At4P 1) kh f.Pl,j.,ggTt,d . S 0. C A(C. NO F il4. ,6 GROUP ABKP-188 CHE LOWER. LIFTTr* LF G THREAD 5 HEAR CLEVIS T*t. watAc s*.tn. =. -t M A'l L F SAM t. As won. :~r tr7- M 3 ASTM - A- 105 G R. 1. C R ?. LE C, . P QutNtHtD ( wmpuuo wrTa -fy = ($u Tr Jh.) MAK CAtt00N couttu1.30% act. Am- Asoa c.m aca.2. fy = W (.03(ozy? ) o m motwwnno wzis MA cannou c.cuTuc . 30% - y= 2005 es:

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• Cy 'NO p t 'N'O GRQy*

LoWERtmrNotsc,g shen T;. A . -cur l CLEVT-S NW u t- ro te n - a _4 f, (P/2)/2 A, . A 4 EE A Pl.NG STRES5 Mv' F'

                                                                                                                 .m v           .f              i 9

The bCartr% Ebbb th Of- $ - --

,e m e.

as w oub. wi - sw e, e u m;S w A, = % 1A 6 p .. . 3 pr.s e,ww.o:, O w (o.onsi ) ,, R . PA % E.

6. W (,oH:"7 )

b 7 33 i ' nt ( =4 - u r;g m. TEMSION t LEc. A-A TE N SI ON c. d4 THREAD R E. LIE F

k.

• 3m- - - -- - --- ' "

f, . P/ A g T@ m a-* (, m,... s P: w( t/3 )

                                                                        ,_._,            - 6h - TrdV 4

{P-- WP/A, ( \/3 ) dh (2 'G9(a.5}-w(s.oWY

                                                                                        = %. /

A* 40.wx en 3422)

                        - 4 (.cx.f

(-w(69M l/3 )/%./(o9

                                                                                         =. w L o o 9 2 2. 0 )

N = 23,5'7B e f+ = 7 3iO em Q3. W ( l13 )/(23 578)

                      =

W ( . Ol'1 i3 '? ) ft* Y 5 24 P4 l

  ,,           ,,,                     .  ,-op                    o... C-,..                       o. . C-o..                             o...
  '.3          DATE

..ti?

• L a O L S E F O R'.* ", 52130

_.a -& ----c. - -. ., - -

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION T6TLE

      .m ou c T Reactor Vessel Head Lift Rig                                                                                           . AGE a vT - a                          c,* T a      c-Eo.e,                              y9   o,    30 D    c~n o s.

so AEP/ AMP Azuogo% 3 ig u _ gja% att o.16 cy no sve so caova

                                                              .                                                                                  CHE LOWER. LGTrN6 Le.G PIN                                                              S H E AR STREEE MAT"L- ASTM- A 4,5 4 CLGO WLTH hy =. P/?_ A.

MIN TTMPE RING t_e itey"

                                                  '                                                                   P=
                                                                  - % w6                                             A, s .3   333; W 7t-d;/
               "[TT 4

A, = n (3.932. )W Av- 12..) t3 in'

          -                                                                              l T ~~                                       -~
                                                                                 -- d t                      ;                                      fy = (w / 3 ')/h 12.M3 )

be I " " l vs (o.007 20) Ev = 4 3 9 2. 95.I l

             .[ -- ,, 4 l
                                                           % _~ - _ ' m v ue.

E6 P 6 .c.ung on assmW ,th. y BE ARING STRESS d = diam.tse of p in, in. -

               .9                                                    '

1 5th of b u cin3 -.ur k . f,.- P/A, ef c...au- b.av .in. P = W/3 a - 1 3o, of 5..-i em.s.iae. # <U.q su h T_N N ER .

                                                                       , hadpie .
                                                                           '                                       Av - 4.9 - (.2.9n X               4     )

S = cpp behm karin3 = ( 15.~n B hs surg,.% A _ .. Sc = ( W/3 )/(15 % L Matat ac.Evtl.5+.h of .. o.O'2.5 t O pi gA . . _ . _ . E=,w-(OPi/ _ C, mr.

                                                 .f+ 2(a +g ) _. .                     .

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4.= - ( W/3 )/09.ssa') o

s. 2ps. , w. . _ . f, w9 (n.onsi) m.

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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION T.T L E 8 AGE Reactor Vessel Head Lift Rig . 3 p o, 30 ..ox C1 Av1-0 C-<=, c < o. . . oArt AEP/ AMP I sgre j ( pg , Qg o.1. - 5 O. CA NO. $L No G R O u' BE N DT N Cs STRE55' k=(W2 )( % + g + M)y 2 h (.nrQ/2 * ( l.S$/2 +,245 l

                     +     4.0 /4 )*32/(1r(3.932f)    .
                       - W (. oCol10) f=5          19, 'S 9 0 pet.
     *        .tou Anm M Anno                        P( k AUTMom               DATE CMM C S Y       D AT E j CMK'D. B T        DATE pgy              ngy NO               DATE                                                                j WISTING =CUSE F omu 152130

APPENDIX B DETAILED STRESS ANALYSIS - REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LINKAGE

 .This appendix provides the detailed stress analysis for the Donald C. Cook 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 prcperties given in section 4.

8475B:1b-020485 B-1

SKETCH SHEET

     =csti=G oust rosu 54202 s.o.                                                  Peostct                                        .ast            ]

ABKP-188 Donald C. Cook Units I and II 1 y 46 ' itTLE lc..cv6. tic =s go. R. V. Internals Lift Rig, load Cell & Linkage PDC- ' l 61 o a o it ic ic.E. ., .;.t ..

          "J. S. Urban                       _                ) U!       J. Richard             Mg,j_ '/ / '
      .s..o E ..     .t.ec,..

rq g

1. Thepurposehthisanalysisistodeterminetheacceptabilityof this rig to the requirements of ANSI N14.6.

2. The results show that all stresses are within the allowable stresses.

                                                   #Mr     .. .       b l
                                                    .........u. g

_v.

                                           ; JOSEPH W. RICHARD ,;
 )
                                                      .... ... g.4,y eso oc7167(
                                                                        /

qw h# wwR M h REVISION NO.

                                    //ll8'                                                               '

e By lwo DATE O ESCR I PT 10% l 9

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              "'oc" I
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                                                                                                               -    25 k

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             @ SRACE PLATE                                     U           (*p i          Lw              ENGAGING SCREW @

h LEG SUPPORT BLOCK

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                                                                                                     ' AGE TITLE Reactor Vessel Internals lift Rig                                              3   os 46 ca?g I                                                                  DATE CME'O av        DA14'C M E O. s v PMOJECT                   AV}

m f

                                                 . 1d%J WtAbtM I

AEP/ AMP / GROUP SO C(y C No. No. CHE i ABKP 188 _ CMG & s! alEIG l-4 T5 : wE\C.WT OY LOWE6 \ NT ERN ALS = 32 5,000 LB , i-I. NTE EN ALS Ll FTt NG R tt, = H,500 LB 3 3 9, 500 LB The abcoe weig his were obtained f rom Don Weah n's e e' p e e Leii e c n umb'ee MP -n - 19 4 ( MMENC.LNTORE . A = aw a , tW- "Tha. wormneJo.Auw cC C = d u%nw bm < ear- ttferm or var a s of f\um 4 esh b,i defwel od- 1L As it.okJnok cl ch a h , 9 mg A. v =a. as P4 k = 6 cA g s, % , psi le W. o.heve. hi'r. Wk fe, bearig s h ,p.,; 4.h6 r> w h wwong of 3 4 - 4.mib sw , p.; t.b. J,erms am <hN Eya s,La r- Aw, pi w 6 4% c.o D<.o\a.h k

                          .T.~ me w ofww h ,m*                                sw Mada..                                 ,

K^oh A.4..h s E. j2,t 59 LB. b

• podar Mmin'w3tb li 'g * \\b IMd M m o m4w:t , A -Ib b

Y*k(g.wcreI N bN ik 3 Orw k)

• l3 %

3 9,90(,e W = dauf t,g u b#

                              <= 6a A 5% A -a b 4. **3
                                                    , n .       -

No f Oa f [ /g ) I WESTINGMOwSE F OmW552130' h

WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION

• AGE TITLE Reactor Vessel Internals Lift Rig lf or 46 emoJtCT AUTM m Dalt CMA'O ev DATE CMn'D. t v Daft 4tdd3 h kA '!U

                                                                                             ^

AEP/ AMP b sp6E No. omove s o. . Cp No ABKP-188 CHE I LOA D CELL LINK AGE ASSEMBLYi ' ow r--i' I ' HOOK i i E P AC,t.R i i w 2 - L _ _ _i nn

• HOOK PIN 1 3

1- ,g s1ct atm t 2 r N N rn

y- AC APTOR PIN 3 c x ts l

                                             'p(              UPPERADAPTOR 4 LOAD CEL     .5 yy

_A wwta mo8 Pron 6 b +_ [_ ,

                                        +W i                                      ,

V 16 CME D Sv OATS CMA0.ev DATE arv sty

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                                                                                               ..a o a om.

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   ~
                                                                                 .    ,  ,                     Av = 44.ca4                                   ins
                                =                    t                         ;                                 f. = ( w                                 3 4 44.ce4))
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W

                                                  "          "1                                                 6-                           3851 nr               -

e . ,

                                                                              -s SE ARINC, STRES5

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                   .                      .c           6.4,, ,A                                                      P ='W a = 1.qw arf h q A                                                                        ~ ~~ T N N ER                                   .

em Ja .F mh b.d 3 ,ie,. A C. . d S = OA% X 9.23 ) g - ap p b= h == h r,h3 = ( Cain )e ' i

 ~

wr6,, A S, . ( w )/( cot.% ) L .ta w s g o,.f = w (.o.ou.21s) p.k ,4 fc = 5504 ist

                                            -  J + 2(a q)

OUTER P- W IL.h~5tDW. A c - t ad 2( i.96 )(9.4911 d = 1snaAsst. k ~

                                                                                                                                          =(29.h*)v
                     >- t.23                                x                                                      (-(                         w )/(19.w' ) j a - z.ov i.,<.                         $

w C o.osdos) s e.oS w ft= l1,SGO est L . i u 9 /is 93 ou 3 paTE CMK D ev OATE AY E CMn D a v REV mEV f // [Oa

           ~*        l            *f/         I$7          N           lb/WLlNi     ' '

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                                                                                 ^

AEP/ AMP A NOkW GmowP 5O CQ NO ABKP-188 CHE _ t411(.ELLANELOuh C.AU ukATIOM1 - I BEN DINCs ETEEM. 2 3 = L .) - 2 a - ?. sym.ui Awo

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                 . w (o.c2 ?rs)
             -4, 12,810 rsr l

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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE YtTLE Reactor Vessel Internals lift Rig '7 e5 46 AuT R DATE CMnC ev D CME DO' Cait PR OJt c T AEP/ AMP b $3 FR HATEGaowP - s o. CQCNo *GL (6 CHE l ABKP-188

                                 - hL:.N, %TRen pcnMu.A Of M VAM ON~~                                                                                             -

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                                                                                                                              .t. w:9s .c 6%                        _

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                                          .f-% h %h h .$d                             hi"FS b = M C.

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               / o'n AM dAU0$ Ai ihr                                                                     nwPDi.er R{V
        ,. 6,, , ~ o o m . . . Q . . m , -                                                          a

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                                                                                                                                                                                        ' ACE T4T L E Reactor Vessel Internals lift Riq                                                                                                                                      T es 46 CATE CME O ev                                       DATE CME D B'                                      DATE
             **0.tCT                                            avT OR                                                                        f AEP/ AMP                                  .
                                                                                               %J              4, #Mm S_

det No . Gmove 5O $C NO CHE ABKP-188 i SIDE. PLATE g TEMu.ene.nc. A-A . 6 - P/ As P = w/2. M AT'L t MTM- Ast5 GR.90 As - (i4.w-,.sa2) i.w outNcuto At4o rtmtuuo . = 14.5'1W

                                          .                                                                                          ft s W( 0.034 3) uu,                        y                                                  n
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                                         +                                     -+-.                                     umm mm ~ m mna, soa                           Pzu                                                                           j fc a W (0,04 2.57) s.96 TestM fc' l t4 , 4 5 3 PSI.

o

                                                                   +

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W $339,5OO # A. =(t1%- ts.cs- u.cnh ) t.v. 4 w(.o H 3 B 6.1 ' f, = m , s e , em

                                                                            , in                                                                                                                                DATE O          CME'O ev                                 ATE CMn D sv AUT F(s         mtv
                  = i       c u ll7/er                                       .
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                .. . s e M C v ,. . . . . ... , m g

l WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION PAGE TITLE 9 os 46 Reactor Vessel Internals lift Ri9 O *a i k Can D sv CAft can o sv carg AUT LML% p*Lspnj hg emOJE CT - noiw GRO# No 5 O CALW NO CHE ABKP-188 S H E AR, STRESS ADAPTcR PIN 3 ,

                    , ,. m - w 4 c a w = =
                                                                                                   .                             E C P/2A xm 43,o sm u                                                              p. w n-                                                A,- wd%

t'L- *--> g J L- g A, Ws.992 )% Av = 28.09 in' I

                                        =

L a v 5 ( W ') M28.tS 9

                                                                                                      "                           h = w ( 0.Ot '1'7 3) l
                                                                      ,      o       a i                                           fv = ca19 p r.
                                  ."c T                   "i                                      -xec
                                                                                        , s       pn

( 3 b *sti on a%L , BE ARING STRES5 d = diam.kse p in, in.. S - ley * .4 W irs' , surf = 4 - P/A c of c aar 64,,,A P=W T.N N ER a.-1 3 w of % A em n,Ws. # mk, % ,A. Ac- a 9 -(s.$$2 X s.2 3 '. s

                                                                                                                                               =    ( 49.314 lin 9

cppi=4 m banh5 )/(6389 ) sur b o,in.

                                                                                                                                     .E -=w{ o.o?.o2.5) (W L w .i m e i                                ns     .f Ic= G s o,5                         mr pk A .

3

                                                                  =          J + 2(a +g)

OUTER P- W ik.* 3D,soolb A c- 2.aa 2( i.s c Xs.992.

                                                                                                                                                  =('A3.43 hn*                        '

d = 5.cocJr.ut.. A ~ )/(2.349 .

                                   .) = t.27 /8.2 3 A                                                                                     k =(w(Wo.o
                                                                                                                                                  =                 A 2 5'1) a - 2.oo2.o 4 h                                                                                        fc = H,453 9 . c.c a                                         w L = ti. 9 / c 3 . A .

N/ S'c ll7/ff hh{ ?fhfgb kJ}Y"f Vd ; 5 T iN.eaCv5E FCav 152130'

WESTINGHOUSE N'JCLEAR TECHNOLOGY DIVISION PAGE TITLE Reactor Vessel Internals Lift Rig lO or 46 cM= o a v Data . m on C t avgi ca omit cM og s g g o,.r t AEP/ AMP /}M Q i d J VM hlf dJ QE NO GmovP $ 0 CGC ho CHE ABKP-188 Mrw.cu.ANtu BEN DT.NC STRESE* 23 = L- J. 2(4) - 2. EN bh= ' fg(#2)( bg + 4J )h 23. n.99-e.u- 2.(i.w) - 2 (.?a) S = o.ca ' {= { W )/2.*(1,96/2 +9ct,

            + .B.2.5 /4 ) = 32/(1r(5,nr.)',
            = W(c.o93OO)                                                                            l Sb   . 2s,0 5 5 at O

Aff CMAO ev DATE a Gi D E C a* K D S v mgv CO mg vl l **' tb y ESTINGMOUSE F OmW LS2133 (lht %

                                 ~     "

k*$kWh

                                               ~"

f5

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION

                                                                                                                                                                                           ' AGE TITLE Reactor Vessel Internals                                          lift Rio                                                                          Il       es 46                          l
                                                                              .vi        a                          omia        c~o..                                        oats c-oe,                                 c.T.          i
                             ..osic?                                                                                                                          gj l

AEP/ AMP & '/ R3 4.k d - Gmova s o. qajc ho gt hb l ABKP-188 CHE

 !                                       LOWER. ADAPTO R, 4/                         r                                        ~4 - as AND uppgtt, p@APK3t,                                                                                                             4 l

DWh 108D058 hcl mo Ho2. sr k

                                                                                                                                                     ;                          h           :

M AT'U A:::17 434O BCDY AREA

     .                                                            clU4NC.MEQ AND Tt.MRRtQ                                            kg = 2 AQ., + TTh!6f/4 * .ha taLD: 12c, coo N                                                                              c.os cm - A/s wtz.m. I35,000 PE.                                                                                            6 = i B'- A' p,y                                                                 A*54 B" D
                                     "'ug A, 11 b2 - a' + W(W)-

N gj cm en s. a/b { ' At . .t A re c m ai. A o m Pr e n.

                                                                                                                              .                      . . su l                                   st g g. g~ ^. "

w ou, , . A. b = 9.94

                                                                                                                                                       . s i. i,.

3,.ss e s , b N, (L

   -                                                                                                                  l               S'oe. u 7 n.rt h o MPlcR.

3 ' 0" h , m;M4(munaem.)

                                                                                                             . sN- a.s                                     b* 9 99
                                                            , J.8g    ,

b x= 5 4.1 L *

                                                                    .                                                                               A, 'n. t s #

t~

                                            ?
                                                                                                !\

E4 --

.@n l

4 1 ((li-i ll i 1" i Am

                                  'O       l          OA E/ ff                                         pg y
                                                                                                                        /,        ,

j

                                  . . 1,           ..o v, . . c . . . m o                                       f i

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TIT L E

                                                                                                ' AGE Reactor Vessel Internals Lift Rig                                                    l 2. o. 46
   .aassci                               avi ca             caTE c-a o av       sj  oave cao.-                oava AEF/ AMP                              Q      '/

93 h so cucNo ya No- Gaove ABKP-188 CHE 1.CwER. ADAProR 4/6 Am* =C"cu(#**n) ~ AND UPPER ADN 37.5 2. ' ' I4 w ( 0,024G E) 6 W= 339,500# TunsrLE. sige.n e, A-A

b. 9048 m

                 . A =i Af- A%

up a. A = 71.13 - G.o21(B.?3) Trautz sra,sw a a-a um== A 59.9- 4.023(ra.23) f i= P/As f, - P/A,, P- w A .A,-ve'/4 d, % , 4.3t - 4 . W (0.0 %38) Ai_. m2-r(uiy4.sc. 54

                                                ._                        A(        57.s>-n(uy,= o.=

Eo, = ' 15 0 4 b pu. P=w - (, - V (0.04 9 83) 4_ = w (o.oi %s7') , L -, W 9tT 'm R ., . - 6 00 5 m , SM. w (o.onzc) BEATCNGSW.n& A4 (w= 7@g 7 ' m G,= P/Ac P= W L = 6.o23('s.n) -

                                     - as. raw
                     . L ,,,,,,         W C o. c z o t 7 )

k vm.s..i h 8 N-Pi

                                                  ?

J s'o av DaTE ogw mEv a/ y

                                                             //y>'fNkA58           Al Y$

f O l7 y, ! h". E ST NG ** Q vS L 8 0 m v S S213D

WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION PAGE TITLE Reactor Vessel Internals Lift Rig 1_3 es 46 CATL CNg D sv QATE Cwm C. g v gayg PROJE CT A T ragR AEP/AF.P AMAf CM NO.

                                                                     %1          Tk h

8 y NO' d /A - Gac J' 5 O. l CHE I ASKP-188 4/g -- My = P/2Av .

 -                    LOWER ADawreR AMD uPPD, ADePTON                                             c.c m var:w w , u.r b nr. m Ansa w Tu onem-usrzos Dtnt.t.TLY Anovf. THt. AEL sHEAA,                                  sea en tw            o emn THREAD A, s (s.98- ( cts /2.b.7.3 )

f,- P/A, = 18.49 % ' A, Tr D =J /2. , = w. u m ao -m n m. N fnmasi mescom ==. we'a, wastra op m macaw 9 5to,

• E ,ses.
• 4 4 - Bri-2 5 .bns act ss. 2. ( 4.S'1* -(f 23h.) f ~ ~

                                                                                        =    3.574b,im n Drem.=4.1(oBB

{ .M.a 3.95 .3 9 = 3.5G. L tm w*w m. wou. $ = (=.c2 3, so uT m Temen nr. Ava T-(4.L86)3.st./2. '

• 2.3.51 m' 2. ( 4 9't*-4 c23/zi)\ = 9.90%

m s tmo or B.7.1 L. P= W A, .M.9tflX s.98-( cu/2.3 f,= W (Q.04190)

                             .k=l'{,% $ m P- V C,,,,- w/(2 2s.4r0 4v' o,,u = W ( O.02:30)

SHEAB. TEAR-QUT L,.. 7231 m I C .t, ., = w/(2. m.49+) W~ 4, _ - w ( o.o29 04) rucen. 9180cc. 1 A A D TL CME O.av DATE PEv REv. / l A

? (

O' ' WEST 6**GHov$E F Opv S52130

WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION PAGE TaTLE Reactor Vessel Internals lift Rig 14 os 46

 .a cat cT                       aut ca          omia cMoo            v fjg c t e  c-to    .
                                                                                                  ^

p.T. SO AEP/ AMP c NO. 1 dd/83 G, 8 M SLE NO. GROUP ABKP-188 CHE 1

                                                                                                               ~

LOAD MLL '""'* * *- ^-^ 5 . ( =P/As MAT'L: l9-4 ph gs P=W two a neo- r== r..e * ~osom ,x =c1 a= u, , a-a ST1tt.a Aa t h, = 11.3483 : A t gw 4 - w / i u r. e 3 4 w (o.o'74Bo) ( __ 4 25,395 MI

                                                                     'THRE AD SHE AR THE Tm AD sucAsi,rta. LTatsi n wt.s,Amt Nwos1rit AoApro%

tA tA fv= w (O.04?.90) Pqc =;

                                                                            't', %5 e sr 4 4 - B N -7. A W'

w = 339,500 LG T ' ev .Tt CMCD.Bv o.Tt mEV RE V

                       !                     1 [                           d V

WsSTINGMOUSE cmw E12133

WESTINGHOdSE NUCLEAR TECHNOLOGY DIVISION

                                                                                                              *act Ta1LE Reactor Vessel Internals lift Rig                                                               16 es 46carg AUT    m            DATE Ca n'O. a v                         DATC Cat C s e
       'mOJE CT                                                                        f
     .          AEP/ AMP                    1         $3 j) 8 M ,,27                                Gmove ULE NO l

5 O. M C. NO' CHE ! ASKP-188 4 BLOC,K ASEEMBLY 8 ' -

                                                                                                                              ~

i

                                                                                                            /

h6. un hge. 4. identf) ' b lor.4 ben of ses Gom cvh , w[--],L t i L i so

                                                                                                           ~

m Q *;p f, -

                                                                                                                      .2     i l

g'd'~9A\g'7 E.

                                                                                                    \. .-

( TOP LU6 atmovAME Pu w a ~.

x. n Vdyr .c @9

                                                                                                     +

1 F 8+ 2 8 m +5

                                                      "                           i!,           M
                                    @m                 a     D.       (#/ M".//h,)

umet unt N y/

                                                              @             \                          g D '-

g\ \ N ' 2

                                -. w,                                            i__                            , :

D k gn be nATE

                                          /f_                                                      ATE  CMEO.Bv              DaTE Au Da E CaE'O ev pfv NO    f af v.
                             /

O AT E l[ S{ ,

                                                         / $'f                           g      h f v           i./

resTisonoust conv ssasaO

WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION PAGE Ytf LE Reactor Vessel Internals Lift Rig l,b os 46 A 1* R DAIL CME C ev OATL GMn'D Sv C. A T E

   .moJECT AEP/ W                                 A             '/93      6R'/             3                  -

so ctf~o vi ~o c ov-W= 3 39.500 LG REMOVABLE PIN r7 SHEAR STRESS - f, - (P/2.)/A. A, = ir d2/4 mwn iii.o = v(s.nt)Y4 mn Asm A434 m ac 2.8.199 int A m 4s4o (P/2) W/2. R . w/ (2. za.m)

                                                         -                                 W ( .ot 7 731~)

g,.

        ~                    ~

S=G010 psz . ( - .c. .- .

                                                            .,g                          BEARING SrFE55 n.n                        :

8 PIN To St.cr.r, Ant.Many

                                                                                      &= (P/a)/A gP.w                                               A =d+.= 3 (5.992) 19.9 8 a
                                                                                        . P= w
        *m9                               /b.~' " "*""                                {c. W /(2.n.sg)
                      -- - -                    --                                    k-W(.017B15)
                                                 -  -Pm                               (, 9993                    m      ^

I I PLN 't c ADAproR , [ <, E= P/A Wz 'l P- w 8- - h]IEbelEl A.= dt'5.992(413)=37.53 A'

                                                                                      -fc. = W ( .02.C.98 8)
                                                                               .-     fc. " - --c;O9 5 Pu
                      - t31 a H. swm.
                                            --            ,c TE  CME D Sv               TE  CME D.Sv           Daft U"                                                  /b                    M4        (
       . . . . _ , . . . . . , _                                            v

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TITLE Reactor Vessel Internals lift Rig 17 os 46gayg AUT OR DATE CMa' O. b y QATE CME O ev

          'ROJECT AEP/ AMP                      cl! d u N3'              4k             4 G M ov'>

S O. (fwC NO.' F p NO' CHE ABKP-188 l. W BENDING STRESS

    !                         P-W a - 3. A                        '

J = (e.13 i ..

                      .        gu(L4cs-ku)As.ca1CA

__ d.- tr. M 1 A __ ( [g= k+3+ T

                               -vxtM3a.                     s.swa

• 3a /1r/d* ' *J '

A- w(.om s) # . v:--

                                 *            ,          Wl                         .
                                      *- -~ .,- .,

MMAM%NM4 j WE 3214LL,U5ES Cr4 % ANQ AL.L. sesquCNT" PINhIS. DERIVED m ms Fo.wwrnc. PA6E.;

                                -9HCq~

ATE CMu o av OATE A Y D TE CME'D V AEV RfV h kjdf ((

                ~*    l   **l     . SS                             / Vl U
                                                                              $dU t.EST.N3M Cust s o Rv 152130         .

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TafLE 8 AGE Reactor Vessel Internals lift Rig 17 os 46 PROJECT AUTi O A CATE Cwn o av OATE cwn o. av OATg AEP/ AMP h%A we ~o. 1 43 D. Q Iml 4 caova s o. yt ~o.

                ..                                 __              g I O 9 LV C,                                             f 4. 5 kJ (. o. 01To7) i
                                           %-                        Pt = 9519 PSI
                                   ,_ ishL_            9/L
                                             .43%        o R     ' disf h                --
                                                                        'B E A l lW G (A. A - A
   ~

h 3. _ _ . _d

         +

4 4 _ _ __ _

                                                                 . .. . . Tite b E A R \ NG STRESS is. T HE S AME h5 THE OUTER bEAMWG
                                               . . _                  STRESS OF THE AEMOVABLE                         .

b L 4

                                                .. dL 4
                                                                    . tin D                         ..         . __

i < , 11.0L 51 %  %- Ell f c. e w( .02.7%15) _ ._ MAT 8L Ce = 9443 iSI ^ hbTH h 515 C A 'l D QuENC.RE D ( TEM 9ERED TENSlow (RwtLO B-3 f t # (i b.YAt = w( 2.&t. W = 33%500 ** At " it.% ( 3.00) : 35.TT F+ = w L o.o 113 35) T E wstO N @ 4 - 4 , , P+ 973I f t = (Pil)/kt S MEhR. F OR TE AR- Otfr P-w ev = ( 9/O la A v5 w 19 A v A t = 3 (11.9 6 - L.ory ) 1gv = 3 (\\.9 6 - b.013)= IITll An'

                     =-

n.il1 in 1 ft* wlo.01%O n

                                 ~

pt = 9523 PSI I A cwn o ev Daft DATL nsv r a vi

       -        oA,.

hk MESTeNPovSE F ony 552130 dv,Tw % % okitc wnuad4r \cun D ev

WESTINGHOUSE NUCLE AR TECHNOLOGY DIVISION m ot or 46 19 Reactor Vessel avi Internals lift Ri9 uit6 c~s o e, c,soav oars d dJ 'kJ %kki M L,g oatt naoact AEP/ AMP on E '.o GRovP C16L C too

     ,o
                                                                '                                        CHE ABKP-188                                                                  _
                                                                             \gm 13=>,soo LB.

g Tte m et m.

              . s u p pe n t P w e.4

• SUPPORT PIPE. o' .

4. P/A6= W /At 5* At - M.W MAT'L M= ( cossmv

 ~

Support prpt &= 9 $ L\ pst MTM AIOts'

                                                             .             TENhION T.N PT_PF                          _

suPPOR1' PLATE. asm asis g f e , p / 4 - w )/ A GE l* A = T/4(d/-d?

                                       ,P    n,        ;

• T/4 ( 17.9 M' .iWM) 5%o 5 in'

                                                                                =

g 9 LATE ,se.m. l .

                                                           ;p 5 ' W( 0 01I"O ft : 31;il PSI peu s k'                              Y
                                                   ~

r

                  !      1 1        is.s w 4
                    =                t10e }           =l
                    )                 D.9 y

m .,. _ ,..o.. ,,,,,o s

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TIT L E PAGE Reactor Vessel Internals Lift Rio 7 0 or 46 PRC4ECT AUT OR DATE CHK'D Sv g DATE CMK'D SV CATE 50 AEP/ AMP

                                      %C NO
                                                         ' (bYL                       19 W MENO                         GROUP
                                                                                                                            ^

ABKP-188 CHE CALC.ULATION OF TENSION T N SLINC, LEG j EL (h'B*) REMem kr. PzN 'g I e s==. I UPPTR PIN p g, g' ,' ,I -4 T l MI'NG LEG Q , , l , a

• s

                             , ', r f                                           .   ;           1r
                      . , a'6,                       ,             .        .--
                                                                                    - -. W: 359, coo
                           #                                          I

( LMtR P27t ,# .

                                                    .l     . . . .

V 8.WEZWT OP tOvvCL ENitu6&d 4 h WT,

  ' e' * *> .,         ..                        '

_. _T.ymm zu straw t.u. b S(, f.3  ; ... . __ . ._ A* Of."

                                                                                               .            D FQRt4 f.MRWD Ev watActs,
         '         "                                                                       L = mmwmo ponct thRnc d                                                                           SV A LEr. = w /3 8:4 _                            sih m =. C/t- 72. G3 /D4.00
                                                                                                 % =. 29.2 (.*

A* RIt. q, To tovat rzu g = Bt fe3 i B= Pa6 ( vo uma ezu 4 = 14.2.09 T c.o s x - L = , 43 Ts W ( 3En) d= (A-B) + "T2, G3 ' T= 3% w L= Fnom c.6.utta os uPPtR FJN T o o ~ m . o f t.o u s a. n ~ T i -t.an A =. K /(.w/3) L= nc.soi, g , w (tama> u.m m~--,> >

                                                                                        = _K = , ) 5 O2 W
                                                                             \ 4

[ l El $) / Q . h'

  .E., - . .         .O.- EE,,,.                                                      o

I l

                              . WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
      ,,,e                                                                                                 i..e.                    1 Reactor Vessel Internals lift Rig                                                           i 21 o e, m 46 c.,c l

oaie com o o Ta c ,

      ..an c,                         a v i .,

AEP/ AMP __

                                           )        Ahib%7 Ipt        J4

• No. caove 1 s o. ca{y No.

CHE AEKP-188 , j 4 - T/ A = .3*w /At ~ ST_DE LUG Q (9.9s(1) - 4.on] + 1.%

                                                                                 %=            2.3. 3 I iO MAT'L                                                                -Q -      . wsw/23.31 AST M A sis GR 10                                                =     w ( .o15 7 0)

Q UENCHE0 ( f 4= s33 o esi  ! ,, TEM 9ERED COMBINED 5.TRUS Q. WELD sinw.ar msnN t k " K /A t= .isoiW /At o 9 Ag. u.m (1.9s) =. 4 7. 5 2. ( ,a $ R F F Q = . iso 2.w /c.s2. = W (.cos t u) j 7% h

• 10 73 to j f2h Bt.N DIN (.s g ti H f,.Mc./2.=Cy)b.013-(4.H)/I \T j oyms g t 3.3s , n.w'/i2 = SG H .d N 7v 4. w( .om3c0 o'
• L4 \,,  % = cot 4 bei PudtTSA?!W gomgINED TIMd W ,

h v Y  % 5.03 -4m 4.99 I+4 A b= M1b

                  . f                                                EHtAR
           \Ii' h
           "' '-P Nr vu. ==

• c= Awm E - (w/s)/ Av N . n.w v.9s) = 47.57 l f, = w /s/c.st ,

TENSI.ON G WOLE. , w (,oog oig) j W=339, pod (= zrs/ Pi s

                *TMt. AJtt A WI LL (oNitkvA Jt'-Y EL up.N h ints. musicum                                 -

_ _ __._. - / O1!T A3 MLD ?CA HORJ VOkaTAL T01hCD 3EbSENb M M D l %. M hl, M ' Q4 O IIMb g uNgt h Atruh,* W[ MON = 7 6 /hN so / "'D o* / /7/ff 5.- WESTsNGMoust FOmv 562130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION pact TITit Reactor Vessel Internals Lift Rig ~12 o. 46

 ,aon ct                         avv- =           omia c-co e,         ,y   o*Te c-co ..                        o it AEP/ AMP              h      hAlihu YB3     f]. R/M1 ut awo.                   caove c y .o.

so CA.EVIS PIN p . b e W e.oo y _ i

                                                     <=    .                          . _ _ .

ts

                                                                                               .- a                     <

4.oen

                                                                                ~                   '~

N AT'Lt ASTM A 4 34 C.LGBD A:1I 434O STEEL J L-ia +-, sr_

                                                               ~                        '

p ls 1 g%ML4 *(sco-20a) .

                 . b O                                3.500

• 4 QN C,= 2 A e

                                   % PIM                 (* h9                           i 2.is 2.n     Nh

( . mp_ X- W=.339 sOO # sawm jr row.m.iorn. Invaa.ms.s E,= P/2Av P=T 3as A, . TrdV4

                                                                        .v(3.w.)v4
                                                                        . rz.sa e
                                                           .E, . ~ .3 64W/(23 n.51) f , - ( . ,, w w w                                        ,

py . f 4 56I N f A B [ v.E ST a%-OU$a 8 Ca ss bS2133

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION

                                                                                              ' AGE TIT L E Reactor Vessel        Internals lift Rio                                 23    O, 46
           .                             aut                 oats c-vo .           omis e-s o ..          ooit O;s cT AEP/AMD              ,     Arn_b $3          $N                  Gmoup 5 O                           CM NO!                   8MENO CHE ABKP-188 C. LEVIS PIN                      11            BEND INC, STRESS 9 = T = . E.6 w a = 1.9 7 BEAR lWC,      STRE SS                        _t = 3. 9 7 2

3d == 3.934 M.04- 3.97') /2 = o.c3 PIN T O C LE V t.5 Fc.=(?11)/Ac Pb = (M(% +p@e s (.P /1) = T/1 = ( .3 < c v Il') Fb =( .x.i s/Mt.it/1&.03t 3A1/0 Ac = 4t = 3.%9 (l.3%) t 311 ( tr

• 3.3W )

( = l.it in' Pb=w( e s5r) f c. = .v.c, w I n t711) _

                                                                    %=       p o "/       PE F t = vv ( . o tu y _ )                                                .

Pc5 7 S r 'o ' vc. PIN To SIDE 1.uc, ft:P/Ac P = T = ; ne.s Ac' d 6 = 3.9% (3,9T)

                                = ts.9T in'                  .

i S c. = . 3c.. v / ts.tib 9 t. = w (.ou at ) Se /(= W I. er =

                 'Y /
                 -.         UYc//9/pr t.E f.T NGaQuSE F Omv 652130'
                                                    'h jkli[NS$&lt&'~~""

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION YtTLE PAGE Reactor Vessel Internals Lift Ri9 ~2'i oF 46

  = a c,n c i                avva a             o*Tt c==o.e,                         o4TE   c-n o a v           caTe AEP/ AMP                3 1 d '/03 t) A Mg
  $0                         CA $ No                  F$E No.                               Gaove ABKP-188                                                                                ~CHE SLIN6 LEC3 Abbi.MBLY -                                                         UPPE R
                                                              -- h-C.LEvn O                    ,
      ,                                                                   1 I

CQ) LE

                    ,                     .                             j LG I

c?d3  ; - LOWIR s ll ; 2 n, ( LEVL LU_ d T e 1

                                  '   '^

a aT cum- ov te cwn o.sv oaTE N3 l A E/ 7f$ u j [ , YY$ WESTINGHOUSE FOau g$2130

l WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l ' AGE TtTL. l Reactor Vessel Internals lif t Rig C-. o e, 26 e, 46 o.1 f eawaci avi- a omia can o .. AEP/ AMP M.. CAR _b 43 4 k h_gjjp cfet - s o uc ~o. ega e c,now. CHE ABKP-188 ' UPP ER c.LE.VI.s }3 -

                                                                                                                                                       ~                            ~

4.ou g W .... ..

                                                                                      . &    A+                                          9A              -                  ----

MAT'u p-5% c,L 1 qu=.= = m ---- ___

     .                                   WELD Kooo M wa. no, coo am. .

I 4.j =. M.9 sO i OM TENSt0N Q A-A j i . A

• D.19-9.013)(1.9T) ~ T~ ~ I' l

pV y

                                                - 7.7 s6 in'                                  =
                                                                                                                               '!        p.cn gi                                     [f.1 g

5"  :' P = TI1 = 3u. W / 2. >

                                                                                                              -                 n        ]                  m
                                                                                                                                                                                     !L-'.

f s = . n C W t 1, 1 5 6 1 2. ft* w/(.o2.2f95- ) b%

                                                     ~                                                                                  "                  **~""

p +_ = 60ro PSI b THREAD SH E AR, bEhKINC, G A- A (su. sum L.am mvm n arm) b = w ( . o oe z ) . BEAM 4 STRESS @ A-h wu . P LEVlov.5 LY C, ALCVL AT ED FV= 3# 3I 95I puRINC. C.LEVl3 PIN AN AL,1515 EC.

• w ( o Lit't ) T E AA- OUT S HE AIL Fv ' N )/'1AV (.h 6 W/[2)/(1f Ec - 3M'_ psi L( ~/. 9 ') - 1. 0T5') /9
• l.9 7 ]
• W(. c21# '

Fv ' _80 81]H .. 0 - C a1t CME'D ev D&Ti au 0 t CHE'O ev mty

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                                                                                        ' AGE Ti* L E Reactor Vessel Internals Lift Rig                                               2 L-   os 46
  *p3.ECT                   AUTM R              DATE CMK'O Sv            DATE C M K o. s v            OATE sc AEP/ AMP              ~

cucNo ddh k b'd '

                                                        *(/E No                Gaove ABKP-188                                                                         CHE SLING LEG                 y                               a y'                                 l l                                 ,

n' ' ' A

l. 4A i

t%TU t 3 I 8 l1,00m l ua> *ene niN i 1 [ s A-a,n

                 . tom c.a.n m iD                                              I
                                                                                      }
                                                                              ,       s ar

(- uJ =. 339,500 4 TREA6 5HEhRt. A-A Q fy - P/A. A v - tr D , w .1/2.

      .        m       . A; .     - roc a.a S u to. p s-to D4 - 3.83B i                                                    ,

w use M i t - ga w s*tm venetuvssmame ) ) , I I J- c.o u ' A ,.ir b.us W o/2 w.n p , l l P = T = .m w 4 **** *'*/ I I Fv=.wu w/%,17 , s tv = w (,o<o,v ) p, _ sur - psr. _ Ll i ,

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                                                                                                                                                     )

TITLE Reactor Vessel Internals lift Rig *17 c, 46 .

      'ROJECT                       AV        A             Daft CME ~D av                                   OAft cms'o se                 catt AEP/ AMP o.

M $3 L. [ *

e. so da oV, j

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1 SLtt% LsG g * ,

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TE.N5T LE STRE55 Si - P/A, c., A - A inom. wa a n's u m on s t

• w m.teuwmu wwemsn'ss6e  !

ru; A- watw mnen. n.ogos A . ( nw. Le 9/11090T ,

                           . P = r:            3c.c. w f ema A = , .5u. w / ll,0105 f t <m x = w ( .ono v )
                             #4 mr=                v ze #     T*.r.                            .

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     *RQJELT                    AUTM'R                DATE CME ~D Sv                                    DATE CME'D Sv                     DATE AEP/ AMP          Ab 12,b S3 kN' so                         cA\k. No.                     pt No                                                omour ABKP-188                                                                                                      CHE i

towet ctavrs 15 ruum zu caun w., k= F/Ae Ths. Lewur. c Lwn' F= T/2 tzmuwcas m int sArm. At W E V @ E Sk\ O # WLE T"

                                                                               %= (w-d)t THAT TMI. M@tE NAE                                                                  ._A wace soTH Lue .r Twwao                                  .
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( 2, t. s. er _ 33C) 3QQJS

                                                    "                            f * [7 * ( 'II'b [ N W
                                                          ~

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• N I
• 0 2 MI* O\

mwrten:. p, s o "- oc p v = w ( , or o /_L _.) - p v = 3 </3 r Phr. . s

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                                                                                             'aGt TITLE        ,

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      *=oa ci

b. iib 3 >$ iti 4 f AEP/ AMP aue mo. yE 80 a ou.

   -sa.

1 LowtA C.LE'%5 15 S HER TE M OUT ev = @ luv

                           = ( 1* WlO h T AV                                                                             g Av s D ,%-9.on3 lit i.W f v

• W ( .ous sol ,

                                   $ O / 2,-

f %f S

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 ..oa c, Reactor Vessel Internals lift Riq                                                                   30 ee 46
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 .o                                cy so                                   vi ~o                     c.ov.
                                                                                          ~ t !' -

CLEVIS BotT 4 , qug

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oe ,. 1 . ..___ f f ',j:/})y* __ g___ , gy 4.eco.*s e e gg - .,u,2 4,g

• gg-3-- , -

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( v. , E Q7 MAT'L : , A.5TM A4 34 CLA% EO A 111 4 34 O STET L

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                      .f, . P/2A

• T/2 A, A, '% .tt, ,

w at Ope %

• uur erme, or 1 , 1 pen. A 4.a0 0 4tm.1A 7 y ba 3,fe%33k T = . M4. W fve p.w w//1 p ft/g gl',93y a W ( 0/ '7 0 G I )

ya _ O$Y $ <!,

                                                          //qf cws            c agy         ag y      / j         .6                            ate            p,              il Cwm O es             Daft
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION

                                                                                                            *.GE 7t761 Reactor Vessel Internals lift Rig                                                                3l or 46 o.n c-o..                 o .u c-   o..         c.,.
   ..ox c, AEP/ AMP
                                    .v,     -

U LMLA yb Gaov-so uc o ytwo

                      '         -                                                                                    ~

16 CA.E v r.5 B O L T - BE AhlNCs, STR,ESS . r a o d ~ l dQ " .

                    - - - ,   t, '  __

l ( ., F The beating 5 tress 15 % f Ssme s s th*T Calculated f or the , 5 P9(er-c,hanneL (lo/1.1) k 2 ( .ozifN W . 7781, P2. S c. = , D.it C M. D . , DATS a t it Cas b S. afy

        ?o l ~~ //7)K $vfA0 Al v
                                                                   ,_bD[ uf,44ebler'               '

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• AGE Reactor Vessel Internals Lift Rig 3 2. o, 46

   *ROJE C T                     Aw1M R         DATE CMg D g y                    CATE CME D S

• CATE 6O AEP/ AMP As d $3 /k k M *gi t' N'O GRovP GC NO ABKP-188 CHE e SPREADER ASSEM BLY e N

V2 SPREMER LP.G A h

                                      -               .. g           .

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          /    oatt/[/ Mf                  -/f                            Al v.E nt s*.GMQwlt t Cav (S2133 I                                                                  .

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• AGE ToTLE l Reactor Vessel Internals Lift Ri9 B os 46 l *mOJt CT AvtMom Dalk CMED ev OATL CMn C av Datt

! AEP/ AMP ,-b (Abb @k - Gnova 5 O. M NO- 8h E NO ABKP-188 CHE SPRE W R M ATL

• ASTM - A 36 _

LEG AMEMBt.Y h

                                           %@#M D

• s=

A [*** * * -[h y g-g- m, -

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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE Pacg Reactor Vessel Internals lift Rig 34 os 46

                                  .mOJLCT                                                           AUT*C                                                      OATE Cma c ev                                         OATE Can o ev                                               cars AED/ AMP                                                                        d. '/g3                       G.R                                     fl                                          -

5O GnovP CA[ NO QE NO ABKF-188 CHE

                                                                                                                                            .. .                .                        CQM PRELION IM Lgs . ,,                                                               ~

SonEADER. L.EG race. Twi. Arsc s= e me 1. l'1 -

                                                                                                                                                                                                                                                                                            )

AMEM G LY wa-vak via ta , , s-ir, sac i.r. i.s ,

                                                                                                                                                                                  $ = Agtm6 staus psms rmo ru ua = 339.500 LB                                                                                           w - - m .. a m e.

IMr. NCWCN AL CDf"Phub T.VE N* &#*etuun. Law weom.70m. hMW ZN THE $PRCADEN ]s 3DPIN 6 t N w,M Z.L . . . .. .  !"

• tun or%)h Co. c.v a a3 gr4 ,

4 - K /2% e. m, . m,Tm.s,,

                                                         -s            x         r                . .<m m , - , ut                                                                              * :sieco =2.,/                                       woi.

kKe N

• MJhTmgM 4EtLD 'JT'RLD .

w .."f II .. c.com,, m .

a. sw amezo oevsatan. nans.

{ m a ..s is. m m. cm -

                                                                                                                                                                                                      - u mm. -

A*g 3 50 in i .

                                    ,                    ( y aan = *i nr m e m sTi n a.                                                                                                        Cc..(2#E/F)\                         y p 1- 5h l th ED-                                                                                                                       =(2n* 29,ocz:, coo /sc,oco)\

a i 2Gn.1C u..ytr..< c . f 1 L. - (_. so y M s. .,,, .s a .

4. w( .omrn ,. ...,,.,.~,.~ue e,

• Ei - 1 A'D,/(bb -i A9 f~ ms ,ss. . s. 8 ouievq 3

s y rc kStu- > c.c n

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• 5"L S In * . Fa - r2.*r* E/(n*(y/r.)')

1 1 . n. #,um

                                                --                             -             e-                             In 3.09 in .                              . . . . -
                                                    .                    . . .           .,,                              Sua 13.1 ir9                                     . jak k* 2. l                                                ' K o l.1 cf _. .                                              N                          rw                     .m in                     pe ,,n           p_s.at                                         '.

Facm ' test smansat an s.siaty maatts H

                                               .                                          1                                     i..tnin                                      J . 31- 4 v                               u. s e, n      1 h .o % 1 : i..lf A                                                          D T4 CHK'O S v                                         ATE C ME D. t v                                          DATE eg y                         ag y NO                            0"II /             [I                ,
                                                                                                                                         *t                  /)                                   N
                                  .          ,T               .-    ,...m. ,,,,,,                                                                                          v
 . - _   . . - . . , _ _ . _ _ . - _ , _ _ _ _ . _ , _ .                                     ,.            _ , _ _ _ _ . _ . . , _ _ . .                          . _ . ,             . - - _ .      _.--.___m_          . . _ . . - - . ,_ ~ , , - _ _ - . _ _ . - - . .

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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TsTLE Reactor Vessel Internals lif t Riq 36 or 46cave AUTH R QATE CMn D sv g OATE CHK o av

     *ROJLCT AEP/ AMP                        d $3       Nd m's 4 F ig Nb '

Gaov*

   . so                         caGc. No.

CHE ABKP-188 Ai* 15.10 /11b 10 ' 1990 St AE ADER LEC, " ASS E MSL1 As* 31.10/11b.10* .Vt10 c.cm pre sslon (c) (cent) Es. = 10.1 % 9st , Fas' \(f 41 t3I These gsso m e, the (cLv,mns act IPlh* I = I cc + d' At toy etber . Tbt to<,$ est unbraced d= dist a nct beiween ,xis tenph .about hxi s 7-7 is 90 01 we= 0.65 * ( P y 5-13r- AI5c passing Wrough ctetroid H and b ook ) cLn d desired Axis

                                                       .d. *- M 0 01
         +

r=,T1y

         =* Icc a r).y As                                                                              -

t.11f 5.5e - 4.lo ) ln  % e4 /r 2.9.74/ c<.= n.L.Ic (K e a Ir)lC c

• 2A 7 6 / iu.gO

( , d l.1T/t t .T14 : 9.169 in he

• 5.5 o in t

                                                                              .1% O I 3 9.1o1 t (9.14995.5D                 Fa3= R953P5I 3
                      =  139. h tSI                      *Kc.is b te a 5 1.1 Tot n e full For two channels                        length as %f tnd is belied h               a n d ( tens e.rv si;vely) ma y ddleet 13 = 2.bt.b4 in                         s\;3hi) i f loose . The c as e o f th<.

r 3 ** fibt.b1/1l5.50) onbexed Itn$1 h h as K .t.T a g it is M.Ct M in wcLa cA t u c 9 ate. t and so K d. lex ' 1.l h3 3d [6N '

                           = LS , t 0                     would def orm in the mede.          ,

K e.q, f r y = 1.1 (73.nl [ 9.94 t= .5 Theocci; cal

                            = 3 t.9 0                                                                        '

Am.k5 recommnde:1 F o r b oth htte , Kale (C < .

                   % 0, Fa =[.l-\ A'3Fy/G +k A -i A9 tuntWM 6E Atwee STRESS S A hE AS FOR. THE 6 ACKlWC, F 3= 36,0009si bloc.K5     h'. fes vJ I .0 2'o7 e.)

F c. = c82 e E

                                                                                      '~    
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                                                           \S BEMtNG bAC. KING BLOC.K h CHANNEL S 5.50 in '

MAT'L: - ASTM A '2 '7 ( , "TNP" 304 h conta# A cp ~~ tL-[7-2/l.5LM C F. C.ON D A. = 3,;35in i l P=KfL: ,,sOg w / 2 THE BOLT HOLES ARE. , ,gy, w SLOTTE D SO TH AT T HE BACKIN(a BLOC.Kk RESTST

• f s = f / A t oNige.T 1H1E INWARD FORCE, K. -

_g,y]3,33y) ( . w (,,1,,,5) S WT 4 Sc: t 8 % . PsT 3 ga _. J l i.Soskan t.5 J < a LKo C.oM PRESS 10N IN BLOCK Y ,, s * ,,. .

                     #,        '.                                            Pt*K/'A*.ifozW11 ls i    i
                                                                                 =- .onst VJ At = 1.5 x 3.0 : 4.5 ins 9,.          I L B u l e tt.9 %

l 1 ma eirL 8 Ch 7FL.TMg p t #.o7gi 9.E

                               '                                                 - e .., m )

i

                      - 94     p- ,3 53                                                                                                               e ll I

I i I i C+ = N 5' PST e # 3

                                     .,, , ' 7 JL                                      'l VJ= 3 39500LB                        .

I CMK'D ev ATE CME'D St oaf t

     ?I          "';<th/gC A

WAST AGMov$6 F C,mv 552130 Salt d ( VkuRsuist/ des i kATE '

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION 8 AGE TITLL Reactor Vessel Internals Lif t Rig 37 C. 46 OAft c oe n O e v OATE

              *mOJECT                         AUT"                 OATE CME D tv           l AEP/AMD cal #. h0.

4-Ukk $t4,NoMUL s N GROW l ,5C CHE ABKP-188 3 ASTM - A 3 Co l' 1 I I....- .. . c. IO i O* l I rwo hTv. Ih

                                         , (% .
                        ' %AceNE L -

BEARIN 6 oncasmauomo CunPATE,(httsott2MM b P/A . A c.

• A c H A N N!!L T S.IO ln 9 = K/1 = ,/sor. N [2.

S c. = .rcOc

• w 1/S.So /

                                          =    w(. costs)
                  +

4e= qu5r est

                                    ~

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• n oJE C T AvM^ DATE CME'O ev DATE Can'D ev cat.

so AEP/ AMP C

                                           <d ev o.
                                                   -s $3         4.MM'[n g61 Ao Gmove     -

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A AUTmG DATL CMK D v AT CME D sv DaTt rg y agy ' O OI {f /y ( f -

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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE pact Reactor Vessel Internals lift Rig 33 c. 46

     *RUJk CT                  A T w" A                  DATE CML D Sv                          DAT6   ;an C e v                 cAfg AEP/ AMP                    Jd h                   r1 OMd[t3 oo-                               -
   - - o-cuc~                            e"o                                                   ,

W = 339,5 00# SPACER, { C.HANNEL @m . . - .

                                                               .\.          MN= -4                                                   ~

v m ,. ,

                                                                                                                  / ..en 4 MAT'L                                                          L A,                                       ,3(

SPAC ER - ASTM AEBB l

                                                                                                       %g      /     a GRADt.h AmB                                     -

b ^]g g i 3 5 tuwN e.t - m m- n , sac *# g ,Tx 1, w n 9,soo w. - s.1 ssf REAIChito %TRth '*****=w-7HL adt. A t. 2a wr. y wto _! Ec. = P / A e ( w 9 . ., P = Tn. = (.wl/4W h = d t = 3 9%D.ceb7.m.' -Iv - P/A, P = (w/s)

                &c = (w~ AXw h.m)                                         A ,. . g.ce (i r, q zy n .. w ,y. g a
                     = w (. . oz.tE)                                                 r . 5 b . o T i n2 __.

pc. __ 7 7 s z Tv= W( o 00 51'f 3) __ L-2.01i m. 2F m% A w ot'.T C,.AhL 37 73 Asiaeso twat A u. St ett. ALT o w 9 M L '.p u t.

                                                                                                                                    ~
                                                                         "T ru 'KON             t.,      B-S                        l
                                     ,                                       6 = P/As                                               !

P= w/2, N 6 7. L,,J It s. sob i t.o in' ,, i' W( 030303 ) t ,

                                                                           ++.\018% psT                                             l l

mgv 7 rpm ATE CMa O Sv att Cum D ev Daft R(v

                       /'              {            W   ll )

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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TIT L E Reactor Vessel Internals lift Rig 40 os 46 PROJE C T av7M DATE CMK'c 8v 0 TE CME'C Sv OATE s o. AEP/ AMP MAlub $3 t/ta C Att7 e.o. A-k %o M'/5J Gaove ABKP-188 CHE i SPenRi@0AVEL 20/a . 1

                                                                                                      -       l Te.nudJ A -4 T w 9 6 w c_ h a n r d W d W W k.
               "P PS* '                 byrT                                                          . ..
                                      ,fwa                                                            -

( e t. i

                                  *r 'F la.s g wc4 /k- s --d 1 4

L 4 = P/% 9% = Th. AM - (B-M4~0X1)

                              = 1.9 5 9 'i #

r .v.u w ft - .nu w/11 usy ,

                          =(..no,.w n= _        ,e n         V-?

ev OAft CME D.sv DATE

                                      $v)J L ibaTE( CMuN' n                  a          -

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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE 8 AGE Reactor Vessel Internals Lift Rig 9l os 46 avt- oast c~s o av c- o e, ca3

           .aosi c s AEP/ AMP 1 d %p                    r} k h g M,g cast 5 O                                     Ca    NO                              yLL NO                                          GROU' ABKP-188                                                                                                                     CHE

) i

                                                                                                         %RZAD lbHEAR.                                     E._

W S38,500 lb . we , mao wm a wt LEG SUPPORT BLO(x 2. AND BRME, ViATE. 3 , - t u , e s e n. v s t aca m fy- WM 19 879) MAT'L t.cc, supponT- atoc.c Ass ar.20 ERALL PLATE  : e A-3t. [v :. b N 9 p2 WELO E H E. AR, L V N "' " *

                                                             &Q                                TW w a w m o (.it) an=.:nw

(

                                   -Q                                                         w t n u ta m u u. _ n a tNtr.

_ _,, M% NLCe&gu. (C 4tv,,7 QN Tug JJ

• C. t.,

jI j JCp u t e U n i N 0N W r. f m 1 4 gik < M G M) MOESTHAN Fu l.4. 8 g

                                                     .                -   -                    > = u . m T o ,a s. n a a.. n m CQNNLC.TZCN. 30 TML SH4.hR.

l 450.m smw to m .mx -u y ** m =- =

                                   \ M                                                                                   5:5P.

Av-(m%sols.o =4 MM,L

                                                                ' s ."
                ,.              /                                            1                                                  .'m by .L.

N ,

• 19,79Ce t#

sh Ov W (O.01G % In f s t v.z. n-

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NO f Oatt /

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G R O vP 5O CQ NO. ABKP-188 CHE v =. 3 39 SOO LB . ADA9 TOR ( 2. S.5-4 rM RE AD SHE.AR c. 5.5 4w OUTER. T US E. f P/Adw/s)/A, m 'u r i hPTtR- hTM A-7.% d,9 j-%[, w n.304 = ,-y ; - 4cr p.ou.to ( 9:tutic n I' " w o - =r,o sseaun cure.70tst- ASTM A-3t?. .)= flo* .n) .s2 = P = 2.co TYPE 304 ~ A. , tr % .0/2. sm.s.c.r.twr.Tn. 4w = 4s.s ..(,4su/4 c,4 is:./n. s.u%2. ( A,= Tr(s.n%t)(t.cn)/2.= 16.% 9 dNW F f,- w (,oi3a'19)

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J. s.uc h-Eths h@  %***(~'") A, t(cAs94)s.3s h.= 41.9.9%' d w p M se .fy - W/(15 41.B9) D I $ 'T N f, . w( o. con 58) 6  ; - wast cutLtust: / .30-3 4w-28 f'1 - 170I W EM.160

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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGk TITLE Reactor Vessel Internals lift Ri9 44 c' 46 enOJE C T Awfa R A DATE Cat O SV .DATE Can'D sv cATE AEP/ AMP 1R,L dVB3 &#ic/ J G a ov' - S O C No F e dI N O ABKP-188 CHE s ADAPTOl% t- - QUTER. TutE. . i TEN SION e. THREAD RELIFF rem man aer, ,e s4:n, t*u [ fe.00 %*t Leo %ht PTPL M% %

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C.C. OF (4.(s 25 in . P/N4Wh)/N - - -4 e

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r  % (a,'-a?) 4 %( c r.ts'-s.sW)

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f, W ( o.03369) , f t.=. 11,54% m. nuncu eevtamo t Faw main mier., ew ta Tm. N a AstA on A 4\*l4H-IA t HattAD r.s Ag = LE.4E.2. M

                                                                                                                                                                                                                                                                       .fi - P/Ae = (W/3)/A t As= A3        %al                                                                         .
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              *MOJE C T                       Reactor Vessel Internals lift Rig                                                                         PAG [              ~]

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m. mac % sxue,s et w itu T% t 4VT.Dt Mstvt MD ens %3A.

MAT'L : ASTM A ?_'76 TYPE 304 satw n tawwto a n~t c.w%:N4 WttW LELT 04. HOT ROLLED ( Prt.tED COND.A. [c = W (0.059 61) se_,I 4 s.so .

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t i k 2  !  % l 1t rHREAD S4 EAR en f,14 ' ~ l ** & = P/A, @/3)/A, A,= D,wtS /2

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ma v Av. s.nm.wp.sco)/2. 16.7 9 s -w-w vnsao t, w /n.w.w o , s.sco - or,es2/4

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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TIT L E '.GE Reactor Vessel Internals Lift Rig  !{ (, or 46

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ABKP-188 CHE L u : 1 3 9.iSOOLB ENGAG:tNG gr7 BE ARING G, B-B - SC,REW ,

                                                                                                                    -Ic. P/A, MAT'L: A5TM A- sco4                                                                 P-(W/3)

GRADEre30 Ac= (d,' - cll) */4 CONO II00 *(Tr/4)( ( 4.%-2(m)f-(s.'17 + 2 (. i4))*

                                                                                                                         = 5.59.1 m' fc= w/(u s.s92.)

N Sc w (o.o s9r.1) . at

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l'R6 Ic= RO,23B Pir ( aL.-- ,- ". i s.ei TENSIt.E e. THREAD RELIEF Is- P/A+ P-w/3

                                                                                                   '                 A        % A f,ocs.5) 't.5 m

y _m 4 fg = W/(2*MM S w(0.OHZZ)

L4%C e 6,r_3,ou z.iis no na a = 1 Si O ) 3 m. 1-u6 EAD

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                                                -u.o _                                                               E       P/Av =(W/3)/Av i

i Ob A, %Tt J /2 = 343n w 2.,s/2. f, - w (c.oz.uz.)

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