ML20099L036

Evaluation of Acceptability of Reactor Vessel Head Lift Rig,Reactor Vessel Internals Lift Rig,Load Cell & Load Cell Linkage to Requirements of NUREG-0612

ML20099L036
Person / Time
Site:	Millstone
Issue date:	09/30/1984
From:	Sandner H WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20099L020	List: B11406, Forwards WCAP 10669, Evaluation of Acceptability of Reactor Head Lift Rig,Reactor Vessel Internals Lift Rig,Load Cell & Load Cell Linkage to Requirements of NUREG-0612 & Rev 1 to Control of Heavy Loads ML20099L036 ML20099L053
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR WCAP-10669, NUDOCS 8503200449
Download: ML20099L036 (190)

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WCAP'10669 WESTINGHOUSE CLASS 3 Although information contained in this report is nonproprietary, no distribution shall be made outside Westinghouse or its-licensees without the customer's approval.

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 0612 for NORTHEAST UTILITY SERVICE COMPANY MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 SEPTEMBER, 1984 o

H. H. SANDNER, P. E.

Approved': e - /;u

/ A. E Mafshall, P.E. Ma W V Component Handling Equipment WESTINGHOUSE ELECTRIC CORPORATION Nuclear Energy Systems

, P.O. Box 355 Pittsburgh, PA 15230 8503200449 850314 '

PDR ADOCK 05000423 A pop 80798:1b'-083184

ABSTRACT 3

An evaluation of the Millstone Nuclear Power Station, Unit No. 3 reactor vessel head and internal lift rigs, load cell and load cell linkage was performed 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 marufacture 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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80798:1b-083184 til L.

TABLE OF CONTENTS 3

. Section Title Page ABSTRACT tii

1. INTRODUCTION 1-1 1.1 Background 1-1

2. COMPONENT DESCRIPTION 2-1 2.1 Reactor Vessel Head Lift Rig 2-1 2.2 Reactor Vessel Internals Lift Rig 2-1 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 e

80798:1b-083184 v

3 LIST OF ILLUSTRATIONS

- Figure Title Page 2-1 Reactor Vessel Head Lift Rig 2-3 2-2 Reactor Vessel Internals Lift Rig 2-4 e

80798:1b-083184 vii

ATTACHMENTS A

A. Comparison of ANSI N14.6-1978 Requirements fcr 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 Northeast Utility Service Company, Millstone Nuclear Power Station, Unit No. 3.

8. Stress Report - Reactor Vessel Head Lift Rig, Reactor Vessel Internals Lift Rig, Load Cell and Load Cell Linkage for Northeast Utility Service Company, Millstone Nuclear Power Station, Unit No. 3.

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80798:1b-08h184 jx

,c REFERENCES

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

2. ANSI N14.6-1978 Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds or More for Nuclear Material

3. Westinghouse Drawing 1212E27 Loop Lifting Rig - Head, General

' Assembly

4. Westinghouse Drawing 1464E23 Loop Reactor Plant Internals Lifting Rig General Assembly

5. Manual of Steel Construction, Seventh Edition, American Institute of Steel Construction.

, 6. Westinghouse Drawing 1216E70 - Head and Internals Lifting Rig Load Cell Linkage Assembly.

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SECTION 1 3

INTRODUCTION The Nuclear Regulatory Commission (NRC) issued i;UREG 0612 " Control of Heavy Lead at Nuclear Power Plants"Illin 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 Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds or More for Nuclear Materials.(2) . In' general, ANSI N14.6 contains detailed requirements for the design, fabrication, testing, maintenance, and quality assurance of special lifting devices. The Millstone Nuclear Power Station, Unit No. 3 lifting devices which can be categorized as special lifting devices and which are contained in the scope of this report are:

1. Reactor vessel head lift rig

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2. Reactor vessel internals lift e,ig

3. Load cell and 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 lif t rig, the reactor vessel internals lif t rig, load cell and load cell linkage were designed and built for the Millstone Nuclear

• Power Station, Unit No. 3 circa 1979-80. These devices were designed to the requirements that the resulting stress in the load carrying members when 80798:1b-083184 1-1

4 subjected to the total combined lifting weight should not exceed the allowable stresses specified in the AISC[5] code. Also, a 125 percent load test was required on both devices followed by appropriate non-destructive testing.

'These items were not classified as nuclear safety components and 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.

80798:1b-083184 1-2

SECTION 2 COMPONENT DESCRIPTION 2.1 REACTOR VESSEL HEAD LIFT RIG The reactor vessel head lift rig (3) (Figure 2-1) is a three-legged carbon steel structure, approximately 48 feet high and 16 feet in diameter, weighing approximately 16,000 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 legs, clevis, and pins which are a part of the support for the seismic platform meet the requirements of the ASME Boiler and Pressure Vessel Code,Section III, Subsection NF Class I Supports. The tripod assembly is attached to the three vertical legs and is used when installing and removing the reactor vessel head. During plant operation, the sling assembly is removed and the three vertical legs and platform assembly remain attached to the reactor vessel head.

2.2 REACTOR VESSEL INTERNALS LIFT RIG The internals lifting rigI43 (Figure 2-2) is a three-legged carbon and stainless steel structure, approximately 30 feet high and 14 feet in diameter weighing approximately 21,000 pounds. It is used to handle the upper and lower reactor vessel internals packages. It is attached to the main crane hook for all lifting, lowering and traversing 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 storage stand.

The reactor vessel internals lift rig attaches to the internals package by means of three rotolock studs which engage three rotolock inserts located in the internals flange. These rotolock studs are manually operated from the 80798:1b-083184 2-1

internals lift rig platform using a handling tool which is an integral part of the rig.- The studs are normally spring retracted upward and are depressed to engage the inserts. Rotating the mechanism locks it in both positions.

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. The unit is a load sensing clevis type, rated at 350,000 pounds.

This load cell is a part of the load cell linkage which is an assembly of pins, plates, and bolts that connect the polar crane main hook to the lifting blocks of both the reactor vessel head and the internal lift rigs.

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CLEVIS PIN (LOAD SENSING)

REMOVA8LE PIN SIDE PLATE v LIFTING BLOCK

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ci LUG LIFTING LEG y Ne,7, g '

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CLEVIS PIN j

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/ mg _ s CLEVIS d

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CLEVIS PIN e Y

REACTOR o VESSEL s HEAD y Figure 2-1. Reactor Vessel Head Lif t Rig 80798:1b-083184 2-3

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LIFTING BLOCK i

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,,,,,,,-.e 3 LING ROD ARM CLEVIS

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3 ROD HOUSING GUIDE SLEEVE ENGAGING SCREW Figure 2-2. Reactor Vessel Internals Lift Rig 80798:Ib-083184 2-4

SECTION 3 SCOPE OF EVALUATION The evaluation of these lifting devices consists mainly of three parts:

1. A detailed review of the' ANSI N14.6 requirements

2. Preparation of a stress report-

3. Recommendations to demonstrate compliance with NUREG 0612, Section 5.1.1(4).

Discussion of these items follows.

3.1 REVIEW OF 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

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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 Attachment B to this report.

80798:1b-083184 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 EVALUATIONS ,

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 preparation of a stress report in accordance with Section 3.2 and preparation of a critical items list in accordance with

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Section 3.1.2. The stress report is Attachment 8 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 i and welds, the materials of these items, and the applied non-destructive volumetric and surface inspections that were performed. (Details of these non-destructive processes and acceptance standards are available at L Westinghouse should they be needed.)

i A detailed item by item comparison of all the requirements of ANSI N14.6 and those used for the desigt., manufacture and inspection of these lifting devices I is contained as Table 2-1 of Attachment A. The comparison shows that these  !

devices meet the intent of the ANSI document for design, fabricatien and quality control. However, they do not meet the requirements of ANSI N14.6 for i periodic maintenance, proof and functional testing. Thus, a tabulation of those ANSI N14.6 requirements that are incompatible with these lifting devices was prepared and is Appendix B to Attachment A. Included in Appendix B to Attachment A are 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 devices

. 80798:1b-083184 4-1

F r

performed in accordance with the criteria of ANSI N14.6. A discussion is included which responds to the NRC qualifying conditions of NUREG 0612. All of the tensile and shear stresses with the exception of the tensile stresses in the rod housing (item 15) and the guide sleeve (item 16) meet the design T criteria of Section 3.2.1.1 of ANSI N14.6, requiring application of stress design factors of three and five with the accompanying allowable stress limits of yield and ultimate strength, respectively. In addition, all of the tensile ,

and shear stresses meet the requirements of the AISC(5) code.

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 least amount of perturbation to the refueling sequence. These recommendations do not involve any equipment changes.

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n SECTION 5 CONCLUSIONS The following conclusions are apparent as a result of this eviluation:

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 #or stress limits associated with certain stress design factors for most tensile and shear stresses are adequately satisfied.

3. These devices are not in strict compliance only with the ANSI N14.6 requirements for acceptance testing, maintenance and verification of continuing compliance. Recommendations are included to identify actions that should enable these devices to be considered in compliance with the intent of ANSI N14.6.

4. The applicaticn of the ANSI N14.6 criteria for stress design factor of 3

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and 5 are only for shear and tensile loading conditions. Other loading conditions are to be* analyzed to other appropriate criteria.

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80798:1b-083184 5-1 L

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 most important in demonstrating the continued reliability of these devices. They consist of suggestions and proposed responses to identify compliance to the NRC and future considerations.

6.1 Recommend that no changes be made to the reactor vessel internals lif t rig

^

.should the stresses, discussed in Attachment B, be considered excessive by

-others because:

a. The design weight used in the stress calculations is based on the weight of the icwer internals. The lower internals are only removed when a periodic inservice inspection of the vessel is required (once/10 years).

b. Prior to removal of the lower internals, all fuel is removed. Thus the concern for handling over fuel is non-existent in this particular Case.

c. Normal use of the rig is for moving the upper internals which weigh less than one-half of the lower internals. The design weight is based on lifting the lower internals. Thus all the stresses could be reduced by approximately 50 percent and considered well within the ANSI N14.6 criteria for stress design factors.

6.2 Review plant operating procedures to include consideration of ANSI N14.6 Sections 5.1.3 through 5.1.8. These sections include requirements for:

scheduled periodic testing; special identification and marking; maintenance, repair, testing and use. Westinghouse remarks on addressing these sections are listed in Attachment A, Appendix B, Items 5, 6, and 7.

'80798:1b-083184 6-1

t 6.3 A proposed response to the requirement of ANSI N14.6, Section 5.2.1, l 5

requiring an initial acceptance load test prior to use equal to 150 percent of the maximum load is that the 125 percent of maximum load test ,

that was performed be accepted in lieu of the 150 percent load test. I 6.4 A proposed response to ANSI N14.6 Section 5.3 which requires, annually, j either a 150 percent maximum load test or dimensional, visual and  ;

j non-destructive testing of major load carrying welds and critical areas l

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

a. Reactor Vessel Head Lift Rig. 1 Prior to use and after reassembly of the spreader assembly, lifting

( lug, and upper lifting legs to the upper portion of the lift rig, ,

( visually check all welds. Raise the vessel head slightly above its  ;

support (maximum of 6 inches) and hold for 10 minutes. Visually inspect the sling block lugs to the lifting block welds, and spreader i lug to spreader arm weld. If no problems are apparent, continue to lift, monitoring the load cell readout at all times.  ;

b. Reactor Vessel Internals Lif t Rig i Prior to use, visually inspect the rig components and welds while on ,

the storage stand for signs of cracks or deformation. Check all bolted joints to ensure that they are tight and secure. After l l connection to the upper or lower internals, raise the assembly i slightly off its support (a maximum of 6 inches) and hold for 10 ,

minutes. Visually inspect the sling block lugs to the lifting block

welds. If no problems are apparent, continue to lift, monitoring the load cell readout at all times.

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80798:1b-083184 6-2

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. The above actions do not include a non-destructive test of these welds because:

a. Access to the welds for surface examination is difficult. These rigs are in containment and some contamination is present.

b. All tensile and shear stresses in the welds are within the allowable stress.

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

d. To perform non-destructive tests would requiro:

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

(2) Performance of either magnetic particle inspection or liquid penetrant inspection and (3) Repainting after 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 16 feet diameter by 50 feet high) and the results of dimensional checking would always be questionable. Other checks on critical load path parts such as pins, are also not included since an examination of these items would require disassembly of the special lift devices.

6.5 Recommend.that a periodic non-destructive surface examination of critical welds and/or parts be performed once every ten years as part of an inservice inspection outage.

80798:1b-083184 6-3

WESTINGHOUSE CLASS 3 ,

. Although information contained in this report ATTACHMENT A >

is nonproprietary, no distribution shall be to made outside Westinghouse or its licensees WCAP-10669 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 the Load Cell Linkage  ;

for Northeast Utility Service Company Millstone Nuclear Power Station, Unit No. 3

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September 1984 H. H. Sandner, P.E.

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Approved am b 14

. R. Marshall, P.E., Mand

. Component Handling Equipment

. ABSTRACT 1

. The requirements used in the original design, fabrication ~, testing, mainteaance and quality assurance were compared to the ANSI N14.6-1978 requirements for the Millstone Nuclear Power Station, Unit No. 3 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 taculation of ANSI N14.6 requirements that are, at present, incompatible with the Millstone Nuclear Power Station, Unit No. 3 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 Background 2-1 2.2 Component Description 2-2 2.2.1 Reactor Vessel Head Lift Rig 2-2 2.2.2 Reactor Vessel Internals Lift Rig 2-2 2.2.3 Load Cell and Load Cell Linkage 2-3 3 DISCUSSION 3-1 ,

4 CONCLUSIONS 4-1 APPENDIX A - CRITICAL ITEMS LIST PER ANSI N14.6-1978 A-1 APPENDIX B - TABULATION OF ANSI N14.6-1978 REQUIREMENTS B-1 INCOMPATIBLE WITH THE MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 SPECIAL LIFTING DEVICES i

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8079B:1b-083184 v

.- LIST OF ILLUSTRATIONS

, Figure -

Title Page A-1 Reactor Vessel Head Lift Rig A-5 A-2 Reactor Vessel-Internals Lift Rig, A-9 Load Cell and Linkage t

80798:1b-083184 vii

LIST OF -TABLES

, Table Title Page 2-1 Comparison of the Requirements of ANSI N14.6 2-4 and Millstone Nuclear Power Station, Unit No. 3 Special Lift Devices A-1 Reactor Vessel Head Lift Rig, Critical Items A-3 List of Parts per ANSI N14.6-1978 A-2 Reactor Vessel Head Lift Rig, Critical Items A-4 List of Welds per ANSI N14.6-1978 A-3 Reactor Vessel Internals Lift Rig, Critical A-6 Items List of Parts per ANSI N14.6-1978 A-4 Reactor Vessel Internals Lift Rig Load Cell A-8 and Load Cell Linkage, Critical Items List of Welds per ANSI N14.6-1978 1

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REFERENCES

. , 1. Westinghouse Drawing 1212E27 Loop Lifting Rig - Head, General Assembly.

2. Westinghouse Drawing 1464E23 Loop Reactor Plant Internals Lifting Rig General Assembly.

3. Manual of Steel Construction, Seventh Edition, American Institute of Steel Construction.

4. Westinghouse Drawing 1216E70 - Head and Internals Lifting Rig Load Cell r Linkage Assembly.

A 4

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SECTION 1 i

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 Lifting 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 lifting 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 rr.actv vessel head lift rig, the reactor vessel internals lift rig, load cell, and the load cell linkage.

This comparison is listed in Table 2-1.

2.1 BACKGROUND

The reactor vessel head and internals lifting rigt. were designed and built for the Millstone Nuclear Power Station, Unit No. 3, circa 1979-80. These devices were designed to the requirement that the resulting stress in the load carrying members, when subjected to the total combined lif ting weight, should not exceed the allowable stresses specified in the AISC I33 code. Also, a 125 percent load test was required on both devices, followed by appropriate non-destructive testing. Westinghouse also required non-destructive tests and inspections on critical load path parts and welds both as raw material and as finished items. These requirements of design, manufacturing and quality assurance were identified on detailed manufacturing drawing and purchasing

. documents.

80798:1b-083184 2-1

1 Westinghouse also issued field assembly and operating instructions, where

~

. applicable.

3

. 2.2.. COMPONENT DESCRIPTION 2.2.1 Reactor Vessel Head Lift Rig  ;

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The reactor vessel head lift rig Ill is a three-legged carbon steel structure, approximately 48 feet high and 16 feet in diameter, weighing approximately 15,000 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 legs, clevis, and pins which are a part of the support for the seismic

[

platform meet the requirements of the ASME Boiler and Pressure Vessel Code,Section III, subsection NF Class I supports. 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 vessel head. [

[ 2.2.2 Reactor Vessel Internals Lift Rig l

The reactor vessel internals lift rig (2) is a three-legged carbon and stainless steel structure, approximately 30 feet high and 14 feet in diameter  !

weighing approximately 21,000 pounds. It is used to handle the upper and f lower reactor vessel internals packages. It is attached to the main crane j 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 ,

storage stand.

80798:1b-083184 2-2  !

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~ __ ___ _

The reactor vessel internals lift rig attaches to the internals package by means of three retolock studs which engage three rotolock inserts located in the internals flange. These rotolock studs are manually operated from the internals rig platform using a handling tool which is an integral part of the rig. The studs are normally spring retracted upward and are depressed to engage the inserts. Rotating the mechanism locks it in both positions.

2.2.3 Load Cell and Load Cell Linkage The load cell is used to monitor the load during lifting and lowering the reactor vessel head or internals to ensure no excessive loadings are occurring. The unit is a load sensing device type, rated at 350,000 pounds.

This load cell is a part of the load cell linkage which is an assembly of pins, plates, and bolts that connect the polar crane main hook to the lifting blocks of both the reactor vessel head and internals lift rigs.

80798:1b-083184 2-3

TABLE 2-1 COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 AND NILLSTONE NO. 3 SPECIAL LIFT DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement- Actual Special Lift Device Requirements Section 1 Sco and Definitions - These sections These sections are definitive, and not 1.1 ine the scope of the document and requirements.

to include pertinent definitions of 1.3 specific items 2

3 Design A. No design specification was written con-3.1 Designer's Responsibilities - This section cerning these specific requirements.

3.1.1 contains requirements for preparing However, assembly and detailed manu-to a design specification and its' contents, facturing drawings and purchasing

'," stress reports; repair procedures; limi- documents contain the following 3.1.4

• tations on use with respect to environ- requirements:

mental conditions; marking and nameplate '

information; and critical items list. (1) Naterial specification for all the critical load path items to ASIN, ASNE specifications or special listed 4

requirements.

l (2) All welding, weld procedures and l

welds to be in accordance with ASME f

Boiler and Pressure Vessel Code -

l Section IX.

(3) Special non-destructive testing for specific critical load path items to be performed to written and approved procedures in accordance with ASTN or specified requirements 80798:1b-090584 .. -- - - . __ __ _

1ABLE 2-1 (cont)

COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 AND MILLSTONE NO. 3 SPECIAL LIFT DEVICES

ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section (4) All coatings to be performed to 1

strict compliance with specified ,

j requirements.

(5) Letters of compliance for materials and specifications were required for verification with original specifi-cations.

B. A stress report was not originally j required but has been prepared.

C. Repair procedures were not identified.

D. No limitations were identified as to

the use of these devices under adverse environments.

E. The Internals Lift Rig and Load Cell linkage have nameplates attached which include pertinent information.

F. Critical item lists have been prepared for each device that identify load carrying members and welds of these special lifting devices.

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TABLE 2-1 (cont)-

COMPARIS0N OF THE REQUIREMENTS OF ANSI N14.6 AND MILLSTONE NO. 3 SPECIAL LIFT DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section '

3.2 Design Criteria 1..These devices were originally 3.2.1 Stress Design Factors - These sections designed to the requiremer.t 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 tively for maximum shear and tensile exceed the allowable stresses specified stresses; high strength material stress in the AISC code. A stress report-design factors; special pins; wire rope has been generated which addresses the and slings to meet ANSI D30.9-1971; and capability of these rigs to meet the drop-weight tests and Charpy impact test ANSI design stress factors.

requirements

? 2. High strength materials are used in

• some of these devices (mostly for pins, load cell). 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 previous analyses and the resulting stresses were acceptable.

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

4. For the Head Lifting Rig, the material for the clevis pin, the lifting leg, and the clevis meets the Charpy V-notch requirements per ASME Boiler and Pressure Vessel Code,Section III subsection NF 2300.

80798:lb-083184

L '

TABLE 2-1 (cont)

COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 AND MILLSTONE NO. 3 SPECIAL LIFT DEVICES l

J ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device RequirementsSection I 3.3 Design Considerations - These sections Decontamination was not specifically.

3.3.1 contain considerations for; materials of addressed. Locking plates, pins, etc.

i to construction, lamellar tearing; decontam- are used throughout these special 3.3.8 ination effects; remote engagement provi- lifting devices. Remote actuation is sions; equal load distribution; lock only used when engaging the internals l devices; position indication of remote lift rig with the internals and position

actuators; retrieval of device if disen- indication is provided from the operatinq gaged; and nameplates. platform.

.I 3.4 Design Considerations to Minimize Decontam- Decontamination was not specifically

m 3.4.1 ination Efforts in Special Lifting Device addressed. However, the design and i L to Use - These sections contain fabrication, manufacture included many of these 1 3.4.6 welding, finishes, joint and machining items, i.e. lock devices, pins, etc.

j requirements to permit ease in decontamination.

. 3.5 Coatings - These sections contain provi- The requirements for coating carbon l 3.5.1 sions for ensuring proper methods are used steel surfaces are contained in a to in coating carbon steel surfaces and for Westinghouse process specification 3.5.10 ensuring non-contamination of stainless referenced on the assembly and detail i

steel items, drawings when applicable. These speci- l i fications require a proven procedure, I proper cleaning, preparation, applica-tion and final inspection of the coat-i ing. These requirements meet the intent 4

of 3.5.1 through 3.5.8. No provisions

]

were included in these designs for 4 ensuring non-contamination of stainless

' steel items.  ;

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TABLE 2-1 (cont)

COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 AND MILLSTONE NO. 3 SPECIAL LIFT DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements j Section 3.6 Lubricants - These sections contain On the head lifting rig, threaded con-3.6.1 requirements for special lubricants to nections and 63 finishes are coated with to minimize contamination and degradation of Fel/ pro N-1000 as indicated on the 3.6.3 the lubricant and contacted surfaces drawings. On the internals lift device, or water pools threaded connections are coated with neolube. On the load cell linkage, l

j silicone grease is used where applicable as indicated on the drawings.

2 I 4 Fabrication A formal quality assurance program for the 4.1 Fabricators Responsibilities -These manufacturer was specifically required.

lj 4.1.1 sections contain specific requirements All the minufacturers welding pro-to for proper quality assurance, document cedures and non-destructive testing pro-n, jo 4.1.12 control, deviation control, procedure cedures were reviewed by Westi.nghouse prior l

control, material identification to use. All critical lead carrying members and certificate of compliance, require certificates of. compliance for

{

i material requirements. Westinghouse per-formed certain checks and inspections during '

various steps of manufacturing. Final West-i inghouse review includes visual, dimen-sional, procedural, cleanliness, personnel qualification, etc. and issuance of a quality release to ensure conformance with drawing requirements.

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. _ _ ~, . . _ _ . _ _ _ . _ . _ . _ . . . _ _ _ _ _ _ . _ . _ , _ _ _ _ . _ _ _ _ _ _ _

TABLE 2-1 (cont)

COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 AND MILLSTONE NO. 3 SPECIAL LIFT DEVICES ANSI'N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section 4.2 Inspectors Responsibilities -These Westinghouse Quality Assurance personnel 4.2.1 sections contain requirements for performed some in process and final to a non-supplier inspector. inspections similar to those identified 4.2.5 in these sections, and icsued a Quality Release. (Also see comments to Section 4.1 above) 4.3 Fabrication Considerations -These General good manufacturing processes 4.3.1 sections contain special requirements were followed in the manufacture 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.

m 5 Acceptance Testing Maintenance, Both the Reactor Vessel Head and Internals and Assurance of Continued Lift Rigs were proof tested upon comple-Compliance Owner's Responsibilities - tion with a load of approximately 1.25 5.1 Sections 5.1.1 and 5.1.2 require the times the design weight. Upon the comple-5.1.1 owner to verify that the special tion of the test, all parts, particularly to lifting devices meet the performance welds, were visually inspected for cracks 5.1.8 criteria of the design specification or obvious deformation. Critical welds by reviewing records and witness were magnetic partical inspected. In of testing. addition, the Westinghouse Quality Release verifies that the criteria for letters of compliance for materials and specifications required by the Westinghouse drawings and purchasing documents was satisfied.

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

- . _ . - . . - . , _ ~ .._,.,m. .,.,.,....,.,,.,,_..___..,,,,..,..--__,,.-.-_,,_,,,,_,.,m., -

_.,in-,- - . + , - ....,.,4.._...c.-..m.__,_.-.---v,.v-.

TABLE 2-1 (cont)

COMPARISON OF REQUIRENENTS OF THE ANSI N14.6 AND MILLSTONE NO. 3 SFECIAL LIFT DEVICES i

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

! Section 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.

Sections 5.1.5, 5.1.5.1 and 5.1.5.2 It is obvious from their designs that these require special identification and rigs are special lifting devices and can only marking to prevent misuse. be used for their intended purpose. The rigs are identified as indicated in Section E., page 2-5.

Sections 5.1.6, 5.1.7 and 5.1.8 require Operating instructions and maintenance n>

the owner to provide written documenta- instructions should be reviewed to assure

2. tion on the maintenance, repair, testing that they contain the requirements to c) and use of these rigs. address maintenance logs, repair and testing history, damage incidents etc.

80798:1b-083184 _

TABLE 2-1 (cont)

COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 AND MILLSTONE NO. 3 SPECIAL LIFT DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section 5.2 Acceptance Testing and Testing to Verify The head and internals lifting rigs were load and Continuing Compliance - These paragraphs tested as indicated in Section 5. The require-5.3 require the rigs to be initially tested ment for 150 percent load testing, or dimen-5.2.1 at 150 percent maximum load followed by sional checking and non-destructive testing is to non-destructive testing of critical load not practical due to the space limitations and 5.2.3 bearing parts and welds and also annual cleanliness requirements in containment. In and 150 percent load tests or annual lieu of these requirements, written procedures 5.3.1 non-destructive tests and examinations; should be developed requiring the special lift-to qualification of replacement parts, ing devices to be attached to their respectiva '

5.3.8 loads, lifted a maximum of six inches, and held for ten minutes prior to use at each refueling. A visual inspection of critical

?) welds and parts should follow. Further note

that with the use of the load cell for the head and internals, lifting and lowering is monitored at all times. Replacement parts should be in accordance with the original or equivalent requirements.

4 4

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

- _ ~ - _ .

TABLE 2-1 (cont)

COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 AND' NILLSTONE NO.~3 SPECIAL LIFT DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section 5.4 Naintenance and Repair - This section Maintenance and repair procedures should

5.4.1 requires any maintenance and repair to be contain, as much as possible, require-to performed in accordance with original .ments that were used in the original 5.4.2 requirements and no repairs are permitted fabrication. The critical items list will contain the original type of non-destructive 4

l for bolts, studs and nuts.

4 testing. Weld repairs should be performed in i accordance with the requirements identified in l NF-4000 and NF-5000 (Fabrication and

! Examination) of the ASME Boiler and Pressure Vessel Code Section III, Division, 1, Subsection NF.

f

;) If pins, bolts or other fasteners need i

repairs, they should be replaced, in lieu of repair in accordance with the original or equivalent requirements for material and non-destructive testing.

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TABLE 2-1.(cont)

COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 AND MILLSTONE NO. 3 SPECIAL LIFT DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device _ Requirements Section 5.5 Non-destructive Testing Procedures, Liquid penetrant, magnetic particle, 5.5.1 Personnel Qualifications, and Acceptance ultrasonic and radiograph inspections to Criteria - This section requires non- were performed on identified items.

. 5.5.2 destructive testing to be performed in These were in accordance with ASTN speci-accordance with the requirements of the fications, Westinghouse process specifi-ASNE Boiler and Pressure Vessel Code cations or as noted on detailed drawings and provide similar results to the requirement 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 can be m 6.2 requirements for items handling critical demonstrated and therefore this section 1 6.3 loads.

~

is not applicable to these devices.

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 contain equivalent requirements. A stress report has been prepared for these devices. 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 require-ments. A 125 percent load test was performed on both the head and internals lift rigs followed by the appropriate non-destructive testing.

It is anticipated that 100 percent load test, performed on each device, at each refueling, followed by a visual check of critical welds would be sufficient to demonstrate compliance. This may require modification of the Millstone Nuclear Power Station, Unit No. 3 operating and maintenance procedures.

Upon completion of the field assembly of the internals lift rig, prior to using, the assembly procedure calls for a visual inspection of all bolted joints on the rig and a visual inspection for cracks or distortions, particularly,in the area of the welds. Upon completion of the field assembly of the reactor vessel head Ifiting rig, the assembly procedure calls for a 100 percent load test (lifting of the assembled head), with a visual inspection for any signs of distortion. ,

80798:1b-083184 3-1

SECTION 4 CONCLUSIONS

' The review of the ANSI N14.6 requirements and comparison with the origina'l '

Westinghouse requirements has shown that these items are generally in agreement for the design, fabrication and quality assurance of the lifting devices. However, the lifting devices are not in strict compliance with the ANSI N14.6 raquirements 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 product and this product was designed, fabricated, assembled and inspected in accordance with internal Westinghouse requirements. In general, Westinghouse requirements meet the intent of ANSI N14.6 but not all the specific detailed requirements.

i 8079B:1b-082984 4-1

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 specification 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 lifting 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 lift rig, the reactor vessel internals lift rig and the load cell and load cell linkage. These tables include the material identification, and the applicable volumetric and surface inspections that were performed in the fabrication of these special lifting devices. In some instances, non-destructive testing was not specified since the material selection and strength result in very low tensile stresses and thus, non-destructive testing was not justified.

80798:1b-083184 A-1

The material selection for all critical lead 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 items. Westinghouse required all welding, welders, and weld procedures to be in accordance with ASME Boiler and Pressure Vessel Code Section IX for all welds. Westinghouse required a certificate, or letter 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 issued quality releases for the internals and head lifting rigs.

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80798:1b-083184 A-2

TABLE A-1 REACTOR VESSEL HEAD LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE CRITICAL ITEMS LIST OF PARTS PER ANSI N14.6-1978 Non-destructive Testing Item (a) Description Material Material Finished 1 Lifting Block ASTM A350 Ultrasonic Magnetic GR. LF Particle 2,7 Lug ASTM A516 Ultrasonic Magnetic Grade 70 Magnetic Particle Particle (item 2 only) 3,6 Clevis Pin ASTM A434 Ultrasonic Magnetic AISI 4340 Particle Steel Class BD 4,10 Clevis ASTM A668 Ultrasonic Magnetic Forging and Particle Class L

, AISI 4340 5,9 Lifting Leg ASTM A434 Ultrasonic Magnetic

. Class BC Particle AISI 4340 11 Clevis Pin ASTM A564 Ultrasonic Magnetic (load sensing) Type XM12 Particle 12 Side Plates ASTM 533 Ultrasonic --

Type B Class 1 13 Removable Pin ASTM A564 Ultrasonic Liquid Type 630 Penetrant (a)See figure A-1 I

8079B:1b-083184 A-3

r TABLE A-2 REACTOR VESSEL HEAD LIFT RIG, LOAD CELL, AND LOAD CELL LINKAGE CRITICAL ITEMS LIST OF WELDS PER ANSI N14.6-1978 Non-destructive Testing Item Description Root Pass Final ,

i 1,2 Lugs to. Lifting Block . Magnetic Magnetic ,

(Full Penetration) Particle Particle Radiograph 7,8 Spreader Arm Magnetic Magnetic Lug to Spreader Arm ' Particle Particle (fillet) l i

80798:1b-083184 A-4

CLEVIS PIN (LOAD SENSING) h REMOVABLE PIN h

.h SIDE PLATE - LIFTING BLOCK @

@ LIFTING LEG

&f~ @ g %fy, t

/ '

CLEVIS @

1. s

/ z/ NN g/g, b

@ CLEVIS PIN %g, /[ [ p posmON 3

]L' ARM @

I

@ LUG

['p

'. 'N I s N%

%s h LIFTING LEG

/ '

~

TYPICAL CRDM T

, . - "I

/' ng_ b l

h CLEVIS a

ql \

h CLEVISPIN

[SSEL

" a. s HEAD ,/

Figure A-1. Reactor Vessel Head Lift Rig 80798:1b-083184 A-5

'l TABLE A-3

' REACTOR VESSEL INTERNALS LIFT RIG <

CRITICAL ITEMS LIST OF PARTS-

. PER ANSI'N14.6-1978 t  ;

Non-destructive Testing i Item")- I Description Material Material Finished 1 Lifting Block ASTM A350 Ultrasonic Magnetic l Grade LF 2 Partical >

2' Lifting Block ASTM A516 . Ultrasonic. Magnetic Lug Grade 70 Magnetic Partical Particle 3,7 Clovis Pin ASTM A564, Ultrasonic Liquid  ;

-Grade 70 Penetrant  ;

Precipitation  !

Hardening SST Age treated 9 t 1150* F/4 hrs. i Air cooled RC 28-31 4,6 Clovis

• ASTM A471 Ultrasonic Magnetic Class 3 Particle  !

Steel Forging  ;

5 Sling Rod ASTM A434 U1trasonic Magnetic Class BC Particle l AISI 4340 or  !

-(ASTMA588) 8,11 Spread Lug ASTM A516 Ultrasonic

Leg Lug GR 70 STL Particle [

Plate Magnetic ,

Normalized l .

l 12 Leg Channels ASTM A36 CS, HR Visual l L ,

13' Mounting Block ASTM A350 LFI Ultrasonic Forging Steel Magnetic Particle j

i L (a)See figure A-2 i.

)

l~ i i  !

! 80798:1b-083184 A-6 i

TABLE A-3 (cont)

REACTOR VESSEL INTERNALS LIFT RIG CRITICAL ITEMS LIST OF PARTS PER ANSI N14.6-1978 Non-destructive Testing Item (a) Description Material Material Finished 14,15 Load Nuts ASTM A276, Ultrasonic Rod Housing Type 304 SST, Hot Rolled, Condition A 16 Guide Sleeve ASTM A276, Ultrasonic Liquid Type 304 SST, Penetrant Hot Rolled, Annealed

& Pickled, Condition A 17 Rotolock Stud ASTM A564, Ultrasonic Liquid Type 630, Penetrant 17-4 pH Steel 1100*F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (a) See figure A-2 80798:1b-083184 A-7

TABLE A-4 REACTOR VESSEL INTERNALS LIFT RIG CRITICAL ITEMS LIST OF WELDS PER ANSI N14.6-1978 Non-destructive Testing Item Description Root Pass Final 1,2 Lugs to Lifting Block Magnetic Magnetic (Full Penetration) Particle Particle Radiograph 8,9 Lug to Spreader Block Magnetic Magnetic (Full Penetration) Particle Particle 11,12 Leg Lug to Channel Leg Magnetic Magnetic (fillet) Particle Particle 12,13 Mounting Block to Magnetic Magnetic Channel Leg Particle Particle (fillet) 8079B:1b-083184 A-8

UFTING BLOCK h lug @

S} ,

,. ^

h CLEVIS PIN ,

/ O hCLEVIS  %,

I f .o k P I c _ ___ D b(lhl5 j q T

,, le SLING RODh b ^"" N L g( CLEVISh

~

7g LUG '~h CLEVIS PIN h

} '

FE  ;

I iLEG lug @

l CHANNELh y

.i ,. . ,l

[S l

I / [

/E ,

4 r i

k ig b h LOAD NUT

@ MOUNTING 8 LOCK r

y h ROD HOUSING l

h GUIDE SLEEVE h ENGAGING SCREW Figure A-2. Reactor Vessel Internals Lif t Rig i

8079B:1b-083184 A-9

{-

E

, APPENDIX B TABULATION OF ANSI N14.6-1978 REQUIREMENTS INCOMPATIBLE WITH THE MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 LIFTING DEVICES

1. GENERAL The comparison of the various ANSI N14.6 requirements and those of these lifting devices has shown that these devices are not in strict compliance with 4 all the ANSI N14.6 requirements. Listed below is a tabulation of those sections of ANSI N14.6 considered most important in demonstrating the continued load handling reliability of these special lifting devices.

Associated Westinghouse remarks are also listed and could be used as suggested actions and/or responses to demonstrate compliance to the NRC.

la. Requirement:

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

lb. Remarks:

Any repair to these special lifting devices is considered to be in the form of welding. Should pins, bolts or other fasteners need repair, they should be replaced, in lieu of repair, in accordance with the original or equivalent requirements for material and non-destructive testing. Weld repairs should be performed in accordance with the requirements identified in NF-4000 and NF-5000 (Fabrication and Examination) of the ASME Boiler and Pressure Vessel Code,Section III, Division 1 Subsection NF.

2a. Requirement:

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

- factors.

80798:1b-083184 B-1

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 characteristics. However, in lieu of a different stress design factor, the stress design factors listed in 3.2.1 of 3 and 5 were used in the analysis and the resulting stresses are considered acceptable.

3a. Requirement:

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

3b. Remarks:

Fracture toughness requirements were not identified for all the material used in these special lifting devices. However, the material selection was based on its fracture toughness characteristics.

4a. Requirement:

Para. 5.1 lists Owner Responsibilities and 5.1.2 requires the owner to verify that the special lifting devices meet the performance criteria of the design specification by records and witness of testing. t 4b. Remarks: ,

There wasn't any design specification for these rigs. A 125 percent load test followed by the appropriate nondestructive testing was performed. In addition, the Westinghouse Quality Release, may be considered an acceptable alternate to verify that the criteria for the letters of compliance for materials and specifications required by Westinghouse drawings and purchasing document were satisfied. [

80798:1b-083184 B-2

p 5a. Requirement:

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

5b. 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.

6a. 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. '

6b. Remarks:

Operating instructions and maintenance instructions should be reviewed to assure that they contain the requirements to address maintenance logs, repair and testing history, damage incidents and other items mentioned in-these paragraphs.

7a. 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 i- bearing parts and welds.

b. Remarks:

^

^

-Both the reactor vessel head and internals lifting rigs and . load cell were proof tested upon completion with a load of approximately 1.25 s- times the design weight. Upon completion of the test, all parts,

particularly welds, were visually inspected for cracks or obvious deformation and critical welds were magnetic partical inspected. In addition the Westinghouse Quality Release verified that the criteria

.. for letters of compliance for materials and specifications required by the Westinghouse drawings and purchasing documents were satisfied.

L-f t

80798:1b-083184 8-3 l)-

r 8a. Requirement:

Para 5.2.2 requires replacesant parts to be individually qualified and tested.

8b. Remarks Replacement parts, should they be required, should be made of identical (or equivalent) material and inspections as originally required. Only pins, bolt and nuts are considered replacement parts for the reactor vessel head and internal lift rigs.

9a. Requirement:

Para 5.3 requires testing to verify continuing compliance ar.d annual 150 percent load tests or annual non-destructive tests.and examinations to be performed.

9b. Remarks These special lifting devices are used during plant refueling which is epprcximately once per year. During plant operation these special lifting devices are inaccessable since they are permanently installed and/or remain in the containment. They cannot be removed from the containment unless they are disassembled and no known purposes exist for disassembly. Load testing to 150 percent of the total weight before each use would require special fixtures and is impractical to perform. Crane capacity could also be limiting. It is suggested that written procedures be developed requiring the special lifting devices to be attached to their respective loads, lifted a maximum of six inches, and held for ten minutes prior to use at each refueling.

A visual inspection of critical welds and parts should follow.

Further note that witn the use of the load cell for the head and internals lif t rig, all lif ting and lowering is monitored at all times.

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80798:1b-083184 B-4

,-,,r-.- - - - - - - - - _ _ ___.__

2.

SUMMARY

The ANSI requirements for periodic checking and functional load testing appear to be most difficult to demonstrate compliance. It is almost impractical to perform the 150 percent load test prior to each use. It is suggested 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.

80798:1b-083184 B-5

, WESTINGHOUSE CLASS 3 Although information contained in this report is nonproprietary, no distribution shall be made outside Westinghouse or its ATTACHMENT B to licensees without the customer's approval WCAP-10669 STRESS REPORT REACTOR VESSEL HEAD LIFT RIG, R!: ACTOR VESSEL INTERNALS LIFT RIG AND THE LOAD CELL LINKAGE FOR NORTHEAST UTILITY SERVICE COMPANY MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 September 1984 H. H. Sandner, P.E.

Approv d: m:4%

J . M sha N , P.E., Manah r omponent Handling Equipment N I

80798:1b-083184 l

L

ABSTRACT A stress analysis of the Millstone Nuclear Power Station, Unit No. 3 reactor

~ vessel head and internal lift rigs load cell and load cell linkage was performed to determine the acceptability of these devices to meet the design requirements of ANSI N14.6.

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8079B:1b 083184 iii

l's ACKNOWLEDGMENT Acknowledgment is hereby made to the following individuals who contributed to

~ the structural analysis presented in this report.

F. C. Peduzzi J. W. Richard R. M. Blaushild I

Y A

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IV 80798:1b-083184 t

i TABLE OF CONTENTS Section Title Page ABSTRACT lii 1 INTRODUCTION 1-1 1.1 Background 1-1 2 COMPONENT DESCRIPTION 2-1 2.1 Reactor Vessel Head Lift Rig 2-1 2.2 Reactor Vessel Internals Lift Rig 2-1 2.3 Load Cell and Load Cell Linkage 2-2 3 DESIGN 3 ASIS 3-1 3.1 Design Criteria 3-1 3.2 Design Weights 3-1 4 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 5-2 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 l

l 80798:1b-083184 v

F -

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LIST OF ILLUSTRATIONS Figure Title Page 5-1 Reactor Vessel Head Lif t Rig 5-12 5-2 Reactor Vessel Internals Lift Rig, Load Cell and Linkage 5-23 l*

l 80798:1b-083184 vii

LIST OF TABLES Table Title Page 4-1 Reactor Vessel Head Lift Rig Material and Material Properties 4-2 4-2 Reactor Vessel Internals Lift Rig, load Cell and Load Cell Linkage Material and Material Properties 4-3 5-1 Summary of Results - Reactor Vessel Head Lift Rig 5-3 5-2 Summary of Results - Reactor Vessel Internals Lift Rig, Load Cell and Load Cell Linkage 5-13 i

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80798:1b-083184 ix i -

REFERENCES

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

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

3. Westinghouse Drawing 1212E27 Loop Lifting Rig - Head, General Assembly.

4. Westinghouse Drawing 1464E23-4-Loop Reactor Plant Internals Lifting Rig General Assembly.

l

5. Manual of Steel Construction, Seventh Edition, American Institute of Steel

, Construction.

6. Westinghouse Drawing - 1216E70 - Head and Internals Lifting Rig Load Cell Linkage Assembly.

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80798:1b-083184 xi l

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SECTION 1 INTRODUCTION  !

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 l

requirements for. assuring safe and reliable operation for the handling of heavy loads. In the containment building, NUREG 0612 requires special lifting devices to meet the requirements of ANSI N14.6-1978 "American National Standard for Special Lifting Devices for Shipping Containers Weighing 10,000 +

Pounds or More for Nuclear Materials".[2] In general, ANSI N14.6 contains detailed requirements for the design, fabrication, testing, maintenance and quality assurance of special lifting devices. '

I This report contains the stress analyssis performed on the Millstone Nuclear Power Station, Unit No. 3 reactor vessel head lift rig, reactor vessel internals lift rig and the load cell and load cell linkage to determine the acceptability of these devices to meet these requirements.

i

1.1 BACKGROUND

i The reactor vessel head lift rig, the reactor vessel internals lifting rig and I load cell and load cell linkage, were designed and built for the Millstone Nuclear Power Station, Unit No. 3, circa 1979-1980. These devices were designed to the requirements that the resulting stress in the load carrying

! members when subjected to the total combined lifting weight should not exceed the allowable stresses specified in the AISC(5) code. Also a 125 percent

load test was required on both devices, followed by appropriate non-destructive i testing. These items were not classified as nuclear safety components and ,

l thus requirements for formal documentation of design requirements and stress l

reports were not applicable. Thus, stress reports and design specifications l

. were not formally documented. Westinghouse defined the design, fabrication and; quality assurance requirements on detailed manufacturing drawings and

• purchasa order documents. Westinghouse also issued field assembly and operating instructions, where applicable. ,

l 83798:1b-083184 1-1 f

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SECTION 2 COMPONENT DESCRIPTION 2.1 REACTC2 VESSEL HEAD LIFT RIG The reactor vessel head lift rig (3) is a three-legged carbon steel structure, approximately 48 feet high and 16 feet in diameter, weighing approximately 15,000 pounds. It is used to handle the assembled reactor vessel head.

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

The' leg, clevises, and pins which are a part of the support for the seismic platform,' meet the requirements of the ASME Boiler and Pressure Vessel Code,Section III, Subsection NF Class I supports. 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 vessel head.

2.2. REACTOR VESSEL INTERNALS LIFT RIG The reactor vessel internals lift rig I43 is a three-legged carbon and stainless steel structure, approximately 30 feet high and 14 feet in diameter weighing approximately 21',000 pounds. It is used to handle the upper and lower reactor vessel internals packages. It is attached to the main crane hook for all lif ting, 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 storage stand.

The reactor vessel internals lift rig attaches to the internals packaga by

, . means of three rotolock studs which engage three rotolock inserts located in 9

80798:1b-083184 2-1

the internals flange. These rotolock studs are manually operated from the internals lift rig platform using a handling tool which is an integral part of the rig. The studs are normally spring retracted upward and are depressed to engage the inserts. Rotating the mechanism locks it in both positions.

.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. The unit shall be a load sensing clevis type rated at 350,000 pounds. This load cell is a part of the load cell linkage which is an  :

1 assembly of pins, plates, and bolts that connect the polar crane main hook to the lifting blocks of both the reactor vessel head and internais lift rig. [

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80798:1b-083184 2-2 ,

r SECTION 3 .

DESIGN BASIS _

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3.1 DESIGN CRITERIA l

NUREG 0612, paragraph 5.1.1(4) states that special lifting devices should satisfy the guidelines of ANSI N14.6. Further, NUREG 0612,5.1.1(4) states:

"In addition, the stress design factor stated in Section 3.2.1.1 of ANSI N14.6 should be based on the combined maximum static and dynamic loads that could be imparted on the handling device based on characteristics of the crane which will be used. This is in lieu of the guideline in Section 3.2.1.1 of ANSI N14.6 which bases the stress design factor on only the weight (static load) of the load and of the intervening components of the special handling device".

It can be inferred from this paragraph that the stress design factors specified 'in Section 3.2.1.1 of ANSI N14.6 (3 and 5) are not all inclusive.

Also, it' can be inferred that the static load should be increased by ar. amount based on the crane dynamics characteristics.

The dynamic characteristics of the crane would be based on the main hook and associated wire ropes holding the hook. Most main containment cranes use

!. sixteen (16) or more wire ropes to handle the load. Should the crane hook suddenly stop during the lifting or lowering of a load, a shock load could be transmitted to the connected device. Because of the elasticity of the sixteen or more wire ropes, we consider the dynamic factor for a typical containment crane to be not much larger than 1.0.

To provide flexibility on stress Jesign factor, the summary table lists the stresses with stress design factors of 1, 3 and 5. Thus, any stress design factor may be easily applied to satisfy any concerns.

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

80798:1b-083184 3-1

3.2.1 Reactor Vessel Head Lift Rig, Load Cell, and Lead Cell Linkage The design weight is 336,218 pounds which is the total weight of the assembled head and the lifting device.

3.2.2 Reactor Vessel Internals Lift Rig The design weight for the lower internals including the internals lifting rig is 300,000 pounds.

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l 80798:1b-083184 3-2

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

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80796:1b-083184 4-1

TABLE 4-1 REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE MATERIAL AND MATERIAL PROPERTIES Yield Ultimate Strength Strength Item (*) Descripcion Material S y (ksi) S ult (ksi) 1 Lifting Block ASTM A350 36 70 2,7 Lug ASTM A516 38 70 Grade 70 3,6 Clovis Pin ASTM A434 110 140 AISI 4340 Steel Class 80 4,10 Clovis ASTM A668 Forging and 85 110 Class L AISI 4340 5,9 Lifting Leg ASTM A434 Class BC 85 110 AISI 4340 8 Arm ASTM A106 35 60 11 Clovis Pin ASTM A564, Type XM12 105 135 (load sensing) 12 Side Plates ASTM A533, Type B 50 80 Class 1 13 Removable Pin ASTM A564, Type 630 105 135 (a) See figure 5-1, 80798:1b-0'3184 8 4-2

. TABLE 4-2 REACTOR VESSEL INTERNALS LIFT RIG MATERIAL .

AND MATERIAL PROPERTIES Yield Ultimate Strength Strength ItemI "I Description Material S y (ksi) S ult (ksi) 1 Lifting Block ASTM A350, Grade LF 2 36 70 2 Lifting Block Lug ASTM A516, Grade 70 38 70-90 3,7 Clovis Pin ASTM A564, Grade 70 105 135 Precipitation Hardening SST, Age Treated 1150*F/

4 hrs. Air Cooled RC 28-31 4,6 Clovis ASTM A471, Class 3 95 110 Steel Forging 5 Sling Rod ASTM A434, Class BC 85/(46) 110/(67)

AISI 4340 or (ASTM A588) 8,11 Spreader Leg Lug ASTM A516, GR 70 STL 38 70-90 Plate Normalized 9,13 Spreader and ASTM A350, LFI 30 60 Mounting Block Forging Steel 10 Spreader Arm ASTM A500, Grade B 46 58 12 Leg Channels ASTM A36, CS, HR 36 58-80 14,15 Load Nuts ASTM A276, Type 304, SST 30 75 Rod Housing Hot Rolled, Cond. A 16 Guide Sleeve ASTM A276, Type 304, 30 75 SST, Hot Rolled, Annealed and pickled, Condition A

, 17 Rotolock Stud ASTM A564, Type 630 115 140 17-4 PH Steel 1100*F for 4 hrs. l (a) See figure 5-2.

80798:1b-083184 4-3

~

SECTION 5

SUMMARY

OF RESULTS Tables 5-1 and 5-2 summarize the stresses on each of the parts which make up the reactor vessel head, load cell and load cell linkage and the internals lift rig. All of the tensile and shear stresses with the exception'of the tensile stresses in the rod housing (item 15) and the guide sleeve (item 16),

meet the design criteria of Section 3.2.1.1 of ANSI N14.6, requiring application of stress design factors of three and five with accompanying allowable stress limits of yield and ultimate strength, respectively. In additicn, all of the tensile and shear stresses meet the requirement of not exceeding the allowables of the AISC(5) code.

5.1 DISCUSSION OF RESULTS 5.1.1 Application of ANSI N14.6 Criteria 8 Both the reactor vessel head and internals lift rig were originally designed to the requirement that all resulting stresses in the load carrying members, when subjected to the total combined lifting weight, should not exceed the allowable stresses specified in the AISC(5) code.

The design criteria of section 3.2.1.1 of ANSI N14.6, requiring application of stress design factors of three and five with the accompanying allowable stresses, are to be used for evaluating load bearing members of a special lifting device when subjected to loading conditions resulting in shear or tensile stresses. Application of these design load factors to other loading conditions is not addressed in ANSI N14.6. However, these two stress design factors have been used to determine the stresses of the load carrying members when subject to other loading conditions, viz, bending, bearing. This is an extremely conservative approach and in several instances the resulting stresses exceed the accompanying allowable stress limit. .

l 80798:1b-083184 5-1 l

m.

5.2 CONCLUSION

S a) Bearina Stresses'- For the internals lifting rig, several of the parts do not' meet this criteria. However, since they are localized stresses, they can, if necessary. be considered under Section 3.2.1.2, which states that the stress _ design factors of Section 3.2.1.1 are not intended to apply to situations where high . local stresses are relieved by slight yielding. None of the bearing stresses reach the yield stress, and in fact, all of the bearing stresses meet the design criteria of the AISC(5] code.

-b) Bendina Stresses - The removable pin and the load sensing clevis pin in the load cell linkage do not meet the Section 3.2.1.1 SW criteria. However, a very conservative approach was used to calculate the bending stress in pins, as shown in the reactor vessel head lifting rig calculations. In addition, this is a local fiber stress. Even if the fiber stresses reached anywhere near the yield stress, the rest of the pin cross-section could assume the additional load. The shear stress in the pin is extremely low and well within the Section 3.2.1.1 criteria. Again, Section 3.2.1.2 applies if necessary.

The bending stress meets the AISC(5) code criteria, c) Combined Stresses - The combined tensile stress from bending and tension, in the lower. sling rod clevis (item 6), and the leg lug (item 11) of the internals lift rig exceed the Section 3.2.1.1 criteria. As indicated above, bending is not a uniform stress, but is at a maximum at the outermost fiber.

Bending contributes to the major portion of the stress shown in the table, o and, as a result, the tensile stress without the bending is extremely low and well within the Section 3.2.1.1 criteria. The combined stresses also meet the AISC code criteria.

d) Tensile Stresses - The rod housing (item 15) and the guide sleeve (item 16) do not meet the 3W criteria of ANSI N14.6 when analyzed for tension i

at the thread relief. However these items do meet the AISC allowable tensile

! stress criteria of 0.6 times the yield strength and this is considered I

acceptable from a design standpoint.

8079B:1b-083184 5-2

l TABLE 5-1

SUMMARY

OF:RESULTS REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE i

Calculated Stresses (ksi) Material Allowable Item (a) Part Name Value (ksi) '

No. And Naterial Designation W(b) 3W SW Sy(c) g ult i

I 1 Lifting Block Tension 9 6.515" Dia. Hole 4.4 13.2 22.0 36 70 ASTM A350 Bearing 9 6.515" Dia. Hole 6.9 - 20.7 34.5 Grade LF2 Shear 9 6.515" Dia. Hole 4.4 13.2 22.0 u, Tension 9 Lug Supports 7.2 21.6 36.0 -

O Cross-Section 2 Lug Tension 9 4.015" Dia. Hole 4.8 14.4 24.0 38 70 ASTM A516 Bearing 9 4.015" Dia. Hole 8.3 24.9- 41.5 Grade 70 Shear 9 4.015" Dia. Hole 4.8 14.4 24.0 Tension 9 Lug Root 7.7 23:1 38.5 Shear 9 Lug Root ,

2.4 7.2 12.0 (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S,is the yield strength of the material (ksi)

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

TABLE 5-1 (cont)

Sul#4ARY OF RESULTS-REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE Calculated Stresses (ksi) Material Allowable-ItemI *) Part Name Value (ksi)

And Material Designation W IDI 3W SW Sy(c) 3

., No. ult Position 1 110 140

3 Clevis Pin ASTM A434 Shear 5.3 15.9 26.5 AISI 4340 Bearing 8.3 24.9- 41.5 Bending 25.9 77.7 129.5 Steel Class BD us 1.

Position 2 Shear 5.3 15.9 26.5 Bearing 8.6 25.8 43.0 l

Bending -

26.6 79.8 133.0 (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi)

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

__ _ $0798:lb-083184 -- - . - . --.

TABLE 5-1 (cont)

SUNNARY OF RESULTS-REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE ,

Calculated Stresses (ksi) Naterial Allowable Item {a) Part Name Value (ksi)

No. And Material Designation W(b) 3W SW Sy(c) 3 ult Position 3 Shear 4.8 14.4 24.0 Bearing 7.7 23.1 38.5 Bending 24.0 72.0 120.0 l 4 Clevis Position 1 ASTM A668 Tension 9 4.005" Dia. Hole 5.3 15.9 26.5 85 110 Forging & Bearing 9 4.005" Dia. Hole 6.9 20.7 34.5 Class L Tension 9 Thread Relief 2.1 6.3 10.5 i AISI 4340 Shear 9 4.005" Dia. Hole 5.3 15.9 26.5 Steel Thread Shear 2.5 7.5 12.5

! (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S,is the yield strength of the material (ksi) ,

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

TABLE 5-1 (cont)

SUMMARY

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

No. And Material Designation W IDI 3W SW Sy(c) 3 ult Position 2 Tension 9 4.005" Dia. Hole 5.4 16.2 27.0 85 110 Bearing 9 4.005" Dia. Hole 7.1 21.3 35.5 T Tension 9 Thread Relief 2.1 6.3 10.5 Shear 9 4.005" Dia. Hole 5.5 16.5 27.5 Thread Shear 2.5 -7.5 12.5 (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S jis the yield strength of'the material (ksi)

(d) S ult is the ultimate strength of the material (ksi) 80798:lb-083184 - - - - _ _ _ . _ _ _

TABLE 5-1 (cont)

SUMMARY

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

No. And Material Designation W(b) 3W SW Sy(c) j ult Position 3 Tension 9 4.005" Dia. Hole 4.9 14.7 24.5 85 110 Bearing 9 4.005" Dia. Hole 6.4 19.2 32.0 Tension 9 Thread Relief 1.9 5.7 9.5 j]

Shear 9 4.005" Dia. Hole 4.9 14.7 .

24.5 Thread Shear 2.3 6.9 11.5 5 Lifting Leg Tension 9 Threads 7.5 22.5 37.5 85 110 ASTM A434 Thread Shear 2.5 7.5 12.5 Class BC AISI 4340 Steel (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi)

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

TABLE 5-1 (cont)

SUMMARY

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

No. And Material Designation W(b) 3W SW Sy(c) S ult 6 Clevis Pin Shear 4.4 13.2 22.0 110 140 ASTM A434 Bearing 6.8 20.4 34.0 AISI 4340 Bending 22.3 66.9 111.5 Steel m

do Class BD i

7 Lug Tension 9 Upper Hole 4.9 14.7 24.5 38 70 ASTM A516 Shear @ Upper Hole 4.9 14.7 24.5 Grade 70 Tension 9 Lower Hole 4.0 12.0 20.0 .

Shear 9 Lower Hole 4.4 13.2 22.0 Shear 9 Weld 2.4 7.2 12.0 (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lif ting device (c) S yis the yield strength of the material (ksi)

(d) S ult is the ultimate strength of the material (ksi) 8079B:lb-083184

1 TABLE 5-1 (cont)1 SlM4ARY OF RESULTS REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE-Calculated Stresses (ksi) Material Allowable Item (a) Part Name Value (ksi)

No. And Material Designation W(b) 3W SW Sy(c) S ult t

8 Arm Compressive Stress 2.6 7.8 13.0 35 60 ASTM A106 Shear 9 Weld 2.4 7.2 12.0 18("I Grade B ui Seamless a

9 Lifting Leg Thread Shear 2.3 6.9 11.5 85 110 ASTM A434 Tension 9 Thread 6.8 20.4 34.0 Class BC AISI 4340 Turned, Ground

& Polished (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi)

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

(e) Stress limit for fillet weld from ASME Boiler and Pressur Vessel Code,Section III, Division 1 -

Subsection NF 1980 Edition, Table NF-3292 1-1, page 43.

s TABLE-5-1 (cont)

St##4ARY OF RESULTS REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE-Calculated Stresses (ksi) Material Allowable item (a) Part Name Value (ksi) f No. And Material Designation W IDI 3W SW .Sy(c) 3 ult 10 Clevis Tension 9 3.947" Dia. Hole 4.2 12.6 21.0 85 110 ASTM A668 Bearing 9 3.947" Dia. Hole 5.6 16.8 28.0 Forging Shear 9 3.947" Dia. Hole 4.2 12.6 21.0 Grade L. Tension 9 Thread Relief 1.6 4.8 8.0 AISI 4340 Thread Shear 2.0 6.0 10.0 o Steel Clevis Pin Bearing 9 Midspan Section 7.8 23.4 39.0 105 131 11 (Load Sensing) Bearing 9 End Sections 7.8 23.4 39.0 ASTM A564 Shear 4.7 14.1 23.5 Type XM12 Bending 26.6 79.8 133.0 (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S,is the yield strength of the material-(ksi)

(d) S ult is the ultimate strength of the material,(ksi)

._ ,_, _ 80798:lb-083184 ---- -- . . _ - . _, . _ , . __ _ _ . _ _

-TABLE 5-1 (cont)

SUMMARY

OF RESULTS REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE Calculated Stresses (ksi) Material Allowable Item (a) Part Name Value (kni)

No. And Material Designation W(b) 3W SW Sy(c) 3 ult 12 Side Plates Tension 9 7.5 Dia. Hole 5.0 15.0 25.0 50 80 ASTM A533 Bearing 9 7.5 Dia. Hole 7.8 23.4 39.0 Type B, Class 1 Bearing 9 6.520 Dia. Hole 7.2 21.6 36.0 Shear Tear-out 9 6.52

• Dia. Hole 4.4 13.2 22.0 Shear Tear-out 9 7.5 Dia. Hole 5.0 15.0 25.0 13 Removable Pin Shear 5.6 16.8 28.0 105 135 ASTM A564 Bearing 9 Midspan 6.9 20.7 34.5 Type 630 Bearing Ends 7.2 21.6 36.0 Bending 28.3 84.9 141.5 (a) See figure 5-1 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi)

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

CLEVIS PIN (LOAD SENSING) @

)) REMOVABLE PIN h h SID'E PLATE LIFTING BLOCK '@

m lug @

@ LIFTING LEG

(  %,7, CLEVIS @

/s ,\

\ \ /,

• "-";_?% / jd / J -

y ARM @

@ LUG p i

k M

@ LIFTING LEG

/ '

~

TYPICAL CRDM f

/

\ - e- ds

@ CLEVIS j h CLEVISPIN g "I4 " )

Figure 5-1. Reactor Vessel Head Lift Rig 8079B:1b-083184 5-12

TABLE 5-2

SUMMARY

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

Designation W(b) 3W SW Sy IC) S No. And Material ult Tensile Stress 9 6.515 3.9 11.7 19.5 36 70 1 Lifting Block ASTM A350 Dia. Hole Grade LF2 Bearing Stress 9 6.515 5.7 17.1 28.5 Dia. Hole Shear Tear-out 9 6.515 3.9 11.7 19.5 Dia. Hole Tensile Stress 9 Central 6.0 18.0 30.0 Cylinder i

(a) See figure 5-2 for location of item number and section i (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi)

(d) S ult is the ultimate strength of the material (ksi) grom -_ . _ _ _ _ - . _

TABLE 5-2 (cont)

SUMMARY

OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG Calculated Stresses (ksi) Material Allowable 1- Item (a) Part Name Value (ksi)

No. And Material Designation W(b) 3W SW Sy IC) S ult 2 Lifting Block Tensile Stress 9 4.015 4.7 14.1 23.5 38 70 Lug ASTM A516 Dia. Hole Grade 70 Bearing Stress 9 4.015 7.8 23.4 39.0 Dia. Hole Tension 9 Lug Root 6.7 20.1 33.5

! Shear Tear-out 9 4.015 4.7 14.1 23.5 Dia. Hole Shear 9 Lug Root 2.0 6.0 10.0 (a) See figure 5-2 for location of item number and section .

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

(d) S ult is the ultimate strength of the material (ksi) l l

80798:lb-083184

TABLE 5-2 (cont)

SIM4ARY OF RESULTS REACTOR VESSEL' INTERNALS LIFT RIG Calculated Stresses (ksi) Material Allowable Item (a) Part Name Value (ksi)

No. And Material Designation W(b) 3W SW Sy(c) g ult 3 Clevis Pin Shear 5.0 15.0 25.0 105 l'35 ASTM A564 Bearing on Lifting Block Lug 7.9 23.7 39.5 Type 630 Bending 23.9 71.7 119.5 17-4 pH H1150 Bearing on Clevis Lugs 6.5 19.5 32.5 4 Clevis Tension 9 4.018 Dia. Hole 5.2 15.6 26.0 95 110 ASTM A471 Bearing 9 4.018 Dia. Hole 6.5 19.5 32.5 Class 3 Shear Tear-out 9 4.018 5.2 15.6 26.0 Steel forging Dia. Hole Thread Shear 5.2 15.6 26.0 (a) See figure 5-2 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S,is the yield strength of the material (ksi)

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

TABLE 5-2 (cont)

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SlM4ARY OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG Calculated Stresses (ksi) Material Allowable ItemI "I Part Name Value (ksi)

And Material. Designation W(b) 3W SW Sy(~c) g No. ult 5 Sling Rod Thread Shear 5.2 15.6 26.0 85 110 ASTM A434 Tension 9 Thread Relief 12.0 36.0 60.0 Class BC Tension @ Thread 11.3 33.9 56.5 ui AISI 4340 5

6 Lower Sling Bearing 27.6 82.8 138.0 95 110 Rod Clevis Tension 9 4.018 Dia. Hole 31.3 93.9 156.5 ASTM A471 Thread Shear 4.3 12.9 21.5 Class 3

Steel Forging i

(a) See figure 5-2 for location of item number and section l

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

(d) S ult is the ultimate strength of the material (ksi) 80798:Ib-090584 -

TABLE 5-2 (cont)

St#etARY OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG Calculated Stresses (ksi) Material Allowable ItemI "I Part Name Value (ksi)

No. And Material Designation W IDI 3W SW Sy(c) g ult 7 Clevis Pin ,

Bearing 27.6 82.8 138.0 105 135 ASTM A564 Shear 6.8 20.4 34.0

Type 630 Bending 12.4 37.2 62.0 h 17-4 pH H 1150 8 Spreader Lug Combined Stresses, Bending 10.3 30.9 51.5 38 70 ASTM A516 and Tensile GR 70 STL Plate Normalized or Bearing Stress 15.4 46.2 77.0 l

l ASTM A537 Gr. A I

(a) See figure 5-2 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi)

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

TABLE 5-2 (cont)

SIM4ARY OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG-Calculated Stresses (ksi) Naterial Allowable Item (a) Part Name Value (kuli No. And Material Designation W(b) 3W SW Sy(c) g ult 9 Spreader Block Bearing from Arm 4.1 12.3 20.5 30 60 ASTN A350 LFI l Forging Steel 10 Spreader Arm Nominal Compression Stres.s 4.1 12.3 20.5 F,= 23.0I '}

t

ASTN A500 GR B l

(a) See figure 5-2 for location of item number and section (b) W is the total static weight of the component and the lif ting device l (c) S,is the yield strength of the material (ksi) l (d) S ult is the ultimate strength of the material (ksi)

(e) F, = allowable compression stress to prevent buckling in absence of bending moment f

8079B:1b-083184

TABLE 5-2 (cont)

SIDWARY OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG Calculated Stresses (ksi) Naterial Allowable ItemI "I Part Name Value -

(ksi)

No. And Material Designation W(b) 3g 5W Sy(c) g ult 11 Leg Lug Combined Stress Bending & 14.9 44.7 74.5 38 70 ASTM A516 Tensile 9 4.015 Dia. Hole Grade 70 Bearing 25.4 76.2 127.0 m Steel, Weld Stresses 4.1 12.3 20.5 21(f)

• Normalized 12 Leg Channels Tensile 2.5 7.5 12.5 36 58 ASTM A36 CS, HR Forging Steel (a) See figure 5-2 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S,is the yield strength of the material (ksi) '

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

(f) Stress limit for fillet welds from ASME Boiler and Pressure Vessel Code,Section III, Division 1 -

Subsection NF 1980 Edition, Table NF-3292.1-1, page 43.

TABLE 5-2 (cont)

SUNNARY OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG

-Material Allowable Calculated. Stresses (ksi)

ItemI *I Part Name Value (kui)

No. And Naterial Designation W(b) 3W SW Sy(c) g ult

?

13 Mounting Block Bearing to Load Nut 14.1 42.3 70.5 30 60 I ASTM A350 LF1 Shear in Welds 6.1 18.3 30.5 18 III

$ 14 Load Nut Bearing to Mounting Block 14.1 42.3 70.5 30 75 ASTN A276 Thread Shear 5.4 16.2 27.0 i

Type 304 i

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

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

(f) Stress limit for fillet welds from ASME Boiler and Pressure Vessel Code,Section III, Division 1 -

Subsection NF 1980 Edition, Table NF-3292.1-1, page 43.

80790:1b-083184

TABLE 5-2 (cont)

SUMMARY

Of RESULTS REACTOR VESSEL INTERNALS LIFT RIG Calculated Stresses (ksi) Material Allowable ItemI ") Part Name Value (ksi)

No. And Material Designation W(b) 3W SW Sy(c) 3 ult 15 Rod Housing Tension 9 Thread Relief 11.2 33.6 56.0 30 75 ASTM A276 Thread Shear on Upper 6.4 19.2 32.0 Type 304 Threads y' Lower Threads Shear 5.1 15.3 25.5

'3 16 Guide Sleeve Thread Shear 5.1 15.3 25.5 30 75 ASTM A276 Tension 9 Thread Relief 12.0 36.0 60.0 Type 304 SST Bearing to Stud 14.6 43.8 73.0 (a) See figure 5-2 for location of item number and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi)

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

TABLE 5-2 (cont)

SUNNARY OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG Calculated Stresses (ksi) Naterial Allowable Item (a) Part Name Value (ksi)

No. And Material Designation W(b) 3W SW Sy(c) g i ult 17 Rotolock Stud Tensile Stress 9 Cross- 19.6 58.8 98.0 115 140 ASTM A564 Section Type 630 Combined Shear Stress on 24.0 72.0 120.0 T 17-4 pH H 1100 Land Root

' O Bearing on Land Surfaces 18.9 56.7 94.5 Bearing on Stud Head 14.6 43.8 73.0 (a) See figure 5-2 for location of item number and section I (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) l 80798:lb-083184

, LIFTING BLOCK h

, LUG @

, I a

hCLEVIS PIN ,

~

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h ROD HOUSING h GUIDE SLEEVE h ENGAGING SCREW Figure 5-2. Reactor Vessel Internals Lift Rig 80798:1b-082984 5-23

APPENDIX A DETAILED STRESS ANALYSIS - REACTOR VESSEL HEAD LIFT RIG This appendix provides the detailed stress analysis for the Millstone reactor vessel head lift rig in accordance with the requirements of ANSI N14.6.

Accentance criteria used in evaluating the calculated stresses are based on the material properties given in section 4.

80798:1b-091184 A-1

SKETCHSHEET ststeNoMoust toau 54202

, 5.0. PROJECT PAGE NKVJ-188 Millstone, Unit 3 1 w 40 7iTLE CALCULATIONS NO.

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

This appendix provides the detailed stress analysis for the Millstone reactor i vessel internals lift rig, load cell and linkage, in accordance with the requirements of ANSI N14.6. Acceptance criteria used in evaluating the  ;

calculated stresses are based on the material properties given in section 4.

l l

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s.o. PAoJECT PAGE NKVJ-188 Millstone, Unit 3 1 ,31 YITLE C A LCuL AT I oNs No. I R.V. Head Lift Rig, Load Cell & Linkage Assy Analysis poc Auf noe 4 o ATE CMECREo SV & oATE F. C. Peduzzi $ ,d,$ h ; gjgy puseost Ano assutts:

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l. The purpose of this analysis is to determine the acceptability of this rig to the requirements of ANSI N14.6.

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

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.C.Peduzzi REVISION NO. DATE D ESCR I PT ION SY assutt ons naroats. LatTras on natuceano AI O

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i

TsTLE PAGE j R.V. Head Lift Rio Stress Analysis 2. On 31 PROJECT AUTHOR DATE CME'O. gy ATE CME'O. S V OATE NEU Q[.$0Eumiqitt blo@:_*- L__-91 N {

s.O. CA6C.=0. 0 0~ 8' * "o - ***u'  !

NKVJ-188 . REE HEAD LIFTT.N(a rib M5EMOLY D w n t a1 2 E t 'r 1 IFTINO BLOCK i'

~

O2 v tuo CLayzs PIM 5 r= m>= 2 _o i I'

otbtTZON $

4 OLI.VIf3 amermana

- 5 omerre=2 ptlbETr0N 3 f prrzom 3 I

o T )

LUG TT/ T3 8 ARM j

r, , . i l 1 st2smze. otarroam I i

-a LIMNb LT.E  ;

i CLEvXS @ $

REkt. TOR vs.n tt 6- 6 c,LEWh Prw e

wuno i I

t AuTMOR OATS CME *0. SV OATE CME *D. sv OATE Rev. Rev.

NO. DATE WSSTINOMOUSE PORM 883130 t

- ~ - _ - _ _ -

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION

. I TITLE PAGE R.V. Head Lift Rig Stress Analysis 3 0, 31 l PROJECT AUTHOR OATE CM K'O. B y ATE CM K*0. S V DATU

~

NEU 6f i.odu ul_ T/TY  %) hl . GROUP S.o. CALC.No. Ud SE NO.

, NKVJ-188 l . REE l

HEAD 4 T.NTERNALS LISTIN(e RI(a LO AD CELL

{ Cr.NEMSE AMENELY j i MAIN C.R$t4E. HOOK

~%

ie 4

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l I g i T., LING BLOC 6 E.uPPLIED wr.TH INTERNALL f HEAD LI FTIN E. RIM SLIN(.s E. LOC.K AN ALY5.r.5 IMuuctD IN Ht AD AND IMTtRN Au tryT TNIc ANatstri'.

Wib'6HT = GREATER. OF IMnRNALS OR HEAD LT.FT RI(s DEEE6N wEI6HT5 = %i, t,5 !b O

ngy, ngy, AUTMOR DATE CH K'D. S Y DATE CM K*D. S V DATE NO. DATE WESTIMOMOUSS PORM SS2130

WESTINGHUUSE NUCLEAR TECHNOLOGY DIVISION TayLE PAGE R.V. Head Lift Rig Stress Analysis 4 On 31 yTE CME'O. BY DATE NEU Nf foAnm2 TM4 0LEtO mar.

k_Al u D oROue s.O. CALC. mO'. U) 6 NKVJ-188 REE WElGHT OF ASSEM 6LY ( LIFT RtG WElOHTS', POUNDS R.V. HE AD 165,(50 Stubs, NUTS (Whs HMS 3 57,150 CRDM's'.

FVLL LENGTH 70j 050 C A P P ED L ATC.H ttou SINGS 2,900  :

l rod Position INoicATOR 11,750 .

i Coit STACKS COOLING StiROUD 5,250- l DUMMY C.ANs 1,000  !

LlFT R lt, t s)l154 STUD TENS 10NER HOIST 900 S E 15 Mlc, P L ATFO R M II, i oo f (

C ONTINC,ENT ATTM ti MEMTS i 5, o o o *  :

TO S EISMit P L ATFO R M HEhD INSULkT10M 1,7o0 l C.o NT IN G E NC.t ES 12; I co. ,

ToThL .3 6l,175 i

i I-ng y, ngy, AuTMOR OATE CME *0. SY OATE CM E'O.SY DATE NO. DATE t

115SSTINOMOuSS fores 083130 h

i WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION

(

TITLE PAGE R.V. Head Lift Rig Stress Analysis E On 31 AuTMOR DATE CM K'D. SY PROJECT GATE CME"D. SV DATE s.O.

NEU h.& To b l_TRY CALC.=0. g WMf

• LE =0.

M GROue NKVJ-188 REE C.Cl%TANTS OhED THROU(shout TH E.

CALC.UL ATT.ONS CX :- 03 4., upy 516 law % kn* b ver4ie,)

A. 25,142* km DWG n 12 E 2'7 W

• Wofh& of head esambly plus -ig auembly

'T7 1 V= 3 b 1,n 5 Pounds M Y' MWdh A sb hp Tc.o> o<.

A

-Y 3b),!75 l T

w= -

3 c.o 3 2,3, n.2. =

131 3 99( ib tw -

T/.

e e

a n 9

9

,gy, pg y, AUTHOR OATE CME *D. s v DATE CH K*D. s v DATE NO. DATE WESTINOMOUSE FORM E43130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE ,

R.V. Head Lift Rig Stress Analysis lo on 31 PROJECT AUTHOR OATE CH E* 0. Y OATE CME'O. SY DATE NEU 3 f -9 h '. 7/T 4 htdK* caou' 8.0. CALC. =0. UO 9

• ac-NKVJ-188 REE LIF TING BLOCK A S.SE M BLY 1 2 t1AT'L -

1.IFTLNto BLOC.K3 I.r.2. . As rM Asso c.RN>E LF 2.

LOG IT 2. - A 5T M ASN GR ADE '70

- b3 a.t. C h E. 7 O \ % E LEc TRODn ET.WT. 940 "

s--- 5.19r,',p

. hV g

i s.tst.tsa i e. .01,2.on a 43*12*cawEs g__y l '

tom = Eusm)

A A I I t 9 7' " "

l 6. sis 2.cas 4

+- ,

....,E

, P Lht 4 1

?

IP B+ *g ,

ILOO 1.os 40'51 $ k $52*

l 7.002. r1 l 7tpt .tc  ;

1r l _ . .

e ==.) .uot.n. 4 ' 4 "

S-2.0lc.eF W 9 h of M syneemd et 120* - 8.com.os P l (t. u s. raoTwito sNb VInw)

AUTHOR DATE CME'O.SY OATE CH E*0. S Y DATE REV. REv.

NO. DATE WSSTINOMOUSS PORM 882130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R.V. Head Lift Rig Stress Analysis ~/ On 31 PROJECT AUTHCR OATE CME'D. ATE CH K'O. SV OATE Sf.f obl up- TR9 NEU cQ v

8.o. cAoc. No. efAE Ho= - oRoue NKVJ-188 i . REE 1.II: TING BLOLK.(1)

TEN SI.LE e. A- A- TE N 5r.LE. e B- B w =. 3 6 I, O S \b W = 3 b l l'? 5 \b i

(-

P/A t Ot ' 9/At P = W/2. P =. W Ai -(s.u 'TXa.m) .(.or8 Ae Tr(B.OO')*/4

.M

= 43.B'1R = 50.2 (o 5 in' f t- W/(,2 = 40,B'd f t

.fe - 44I9 p: k i = 7I75 w / so.245 p_t BE ARIN G E A-A W - % Il?S s lb

- .(, P / Au c

. 1 P = W. yico-,

• 2*

Ac = c1 J _ . . -- E.4.

c. sis ( s. s7 -24))

+- N'"'"

- 52.E6 M "*

s.so i.-

t W/s2.56 - 4 f' , 6%71- _:

,4 (7.oo+s.so)/2 T = 4.2s' 7

t SHEAR. 4.ea, -out TEMSION t G-C VJ= 3 61,0 5 Ik T= l31, H l Ib

^

D -f,- P/2'A, [3 - P/A, l P=w P = T/2.

A - 40.8r/ a N-(s.so 'fX4.co)

= \3.97 @

( f. - W/(2a

= 9919 40.%7) t m; i (i.T/(2 87eo= n.9-0 pc l REV. REV. AUTHOR DATE CM E'O. S V OATE CM K"D. S Y QATE NO. DATE ,

WESTINOMOUSE PORM 882130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION  !

1

. i 7 TLa PAoE (

R.V. Head Lift Rig Stress Analysis I or 31 PROJECT AUTMom oATE oATE CME *o.Sy OATE NEU Mf.inAmd Tff4 CME *o.gvM v_41 g_ _ _ _ _

s.o. cAcc. Mo. us pa Mo. onoue NKVJ-188 - REE i

BEA RIN C, T= . G4991 4 c,,,,. . G,25 A  :

f - P/Au P - T- I = bhYl?. l i

Ac - d .P -

4.co (u.s)*/12.  !

= 4.ois(4.co) -

%31.0 in 4 l

= lG.oG W 36 - Mc./r um l

r. ur f,f =- T/it..ot. g = _

u. sir. m:

i S H E AR - we -..t E-i P/A. t " " " P  !

T= ' I n,9 9 t . A P Tsk x -nV"I t.sswl  !

v' E/1bv k

• bh P=T = 4.00 ( 1.co +s.so) j A -(s.so- M4.co) - sO i#  !

= .i 3.9 '1 R .?f- Tscwa/so l S ' f, - 1I M pu S, , . T/(2 4ntn = 13.57) at Ss+ q - uss 7: ,

l SERR e., Luc Recsr i STResse.se, Luc. woor T= L31 Mil *; m= 2s. 82' [

l T= 131 991 3 \b fv - 9/Av (

Bendij n.iomen+ about P= Tcom poink D: ccw e Av- bb- 50id l l

x- as.)42' 4, - Tcoa. /s o  ;

l X.= /75 tanM fv - 1903 ~t X- 0. 357 0 in  !

M - Tr.o,x (63-X)

M= u9,3 69 i.- b i new. -

new. AuTMon oats cMso.sv oats cms o.sv oAra I

l No. oats .

, j WESTINGMoVSE PoRM 933130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R.V. Head Lift Rig Stress Analysis 9 On 31 PROJECT AUTHOR OATE CM K'O. S y g I DATE CM E* D. S V OATL S.O .

NEU E f foM n nl T/T4 CALC.N .

Old E N

@ LEND. GROUP NKVJ-183 REE CLEvr5 . PIN MNT'L A STM A - 454 (AISI 4 3 4 O LTEEL C,LAu ab 140,000 MI MIN ttwatt sTRet%TH Est wT 458 y ,,g.is m.-, route

-e e ut f .Wi s - i6uM(,, AB l /

p 3*395,*p,$ ,

Q.

L11.**p

• 'r i_ _v, _

m "8 + .Ob f,Cr1 u 43* t t,* q p ,

Gb 0'*

~

1811.98  ;

. , i

• TIF

.e 2.15 $45 =>==

TvP

% 0 13.(s1. REF KEEPER PLATE.h AltE l.Q31.0"2. THIf.K  ;

I l

e REV. AUTHOR DATE CME *D.SV DATE CM E*D. S V DATE R E V.

NO. DATE l WESTINOMOUSE PORM 953130

{

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R.V. Head Lift Rig Stress Analysis 10 On 31 PaomCT AuTwon OATu CME 0.SV ATE CME *D. SV DATE  !

NEU  %.l*.10Anu a ins ru)RL L - = _ eaoue

. .o . CA6C. ao. go ya no.- i NKVJ-188 REE -

PIN ts useD 70 (QNNt(T THE SW NI. OtCLM, rHz s S A M t.

% THL LISTSNLv Ltte (POb1TEON 1) a kIFTENie kLb1D %MttADER AkMBLY Ann .DREAost IVitmoLy w vutTzcAk LZarrm,Lnt.farrAw.5).

(pbberION SNEA2.) R T.131,9s( w  ;

w . % I,ILT

• mrzou @  !

S,- P/Av Q d4 2.ws(2.**-4 =s)) 9.3%B W l A,= 'w d'/4 Pz . (wts')/2 bo,196 *

- Tr (3.as)Y4 A.edg- S.995(2.SS)* 4s.501 [Y '

12.ssso in 2 p . (Wh)= t io;M i n postTrONS h h P- T ke L 40 f kg* 7 ' '" 7 7#

po>rrxou @ P' Y BEMDING,

@ fy , n o s- me 9 3 2.

@ p, . L: T . v d*

9 T 0 2.

y[.brS+3+s% ._

As VA BEARIN G I

% 'M It l l f,. P/Am H C iak P

hP/2 PostTroN@

A= d P-3.*5(ss-itad 9.rStb'POhrT20Nh P, T/2 W 4%

• a - 2.so-2(.oss) - 2.4i e Q . a 9.- 3. sos (4.co) is.ssOd  ! - 4.co - 4.0o a:-

P, - T- 131,iiI

• d - 3.995 - 29'5 ,A

{; .JC_ 27 p.4 .T311 7' 3 =[4.st+2(.oss)-4ce}h= 0.2l55 s poszrzoN h ,

PI *' #

4 31 -.

A-as 2 s(244-2( s)-33 sst. S, i. I (2.4T +.23s + x)m(2.9 sf Pz r/2.= %'i% * = T(.19490)

q. 4 .s.,42. asp i..-=oi a -uuo p a T. m.,99 i w

.'u 1031M (u.{WO

• a.,h, on pAsE 31 REV. RE V. AUTMoM OATE CME *D. SY DATE CME *0. S V DATE No. oATE wasTimonouse pones statso

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE .

R.V. Head Lift Rig Stress Analysis Il OF 31

. PROJE CT AUTHOR DATE CHE*D.SV I ATE CM K*D. S V DATU NEU @ f. PM n y,' 7/TV /}(2)h*, l_w S.O. CALC.NO. Op (/LE NO. GROUP

- NKVJ-188 REE POSITION a= 2. 4 4 - 2. h -(.045) s.as -

= 2.35 A J- s. a e da 1 995 - twu g = h.so +1(.o4s)-3.BB /2 = 0.sssi P- T = l 31;% l .h k-P(i)(1+3+ $),$r 2

.n.scr..m a+) %,e T(.i s 3 6,s)

6. u,,ss7 m ,-

TosITION h a= 2. 4 4 - 2(.o4s) = 2.s rA 3 ses sss e d = 3 995 = 1%4 4 g - [4.so 42(.oes)-3.ss] /2- e.ssse P- W/3 = 110,312. W

$3-T(.199M)

$s s "L 4 ;OHI yQ e

ggy, g g y, AUTHOR DATE CHK*D.SV QATE CM E*0. S V DATE NO. DATE ,

WSSTINGHOUSE FORM SS2130

I WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE -

i R.V. Head Lift Rig Stress Analysis 12. on 31 '

l PaoJECT AUTMon DATE CMn'o.av g oATE CM n'o. S V oATE l' NEU 5f Tod..u; T/rY W Re- L esta mo. onove s.o. CAi.C. Mo. og NKVJ-188 REE r

CLEVT.5 M AT' L ... ASTM A Gr.B vonterwG t c,thss t, A rdr. 4 34 0 STE E L {

14rMIMuM YZELD STRENWTH..BS.OOO Phl.

i EST. WT 340 an i 6-- 9 6w ,

l fsomt.06d -!

o e i j ys.co-4uu -2s l  ;. t W30t .It I it ' d B li F 3 i _'  :- i- , , ..d.

J /

run J.11 /4 j /j/

P' ats

• skaled $ Mm ,

,'.;1 L

_s. sos.es $ wau g

h A1 n.sa.m F rs 1 i 4 I$ r 1 - 4,cos3 ',g 4 l N,,l l 4  ;

1 f l

' F _

" .ees 2.ent a 43*.21*w p l

rTm 250I m  : y m 4.sg 2.os s 2.44 g ITot 4.s02 03 >

RH 1T 0"2. AT nottom 0F trwTIMw Lat.

LM 1T 01 A1- 'TO P 05 LISTINb l.E(n

~7.00 MIN WD EM(e%tMtW T' (assh tin.r2 r vr.tw s-s)  :

l l

l I

l l

nev. new. Aufwon oATE CMn'o.av OATE CMn o.sv oats l Mo. oAva l l westimoMouse ponu seatso i . -. -. _.- . . . - .

I WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION  !

TITLE PAGE

- R.V. Head Lift Rig Stress Analysis 13 OP 31 PROJECT AUTHOR DATE CME o.av ATE CMED.SV OATE NEU Mf.9al. ult /TV iktD 9_1 2 1 grove s.O. cAi.e. =0; oo pa =0.

NKVJ-188 REE T= '3 7, 9 9 I VI-3 b l; n s TEN srON e. A - A BEAs.INC,4 A-A 4e = P / A* .Q- P/A,.

At w, = z.so - (9-4mos)h-m' e P = T/2 - %,9 9 6 16 G.242in' Ac= d.9 4.cos = (2.so - 2 Loes)

( Ac = 9,ros2. ikt ,

@ Ac-aJ s 4.cos = (2.44 -2(.o+s)

A42= 2.4u( 9-4.cos)h-oes' = 9,412 R

= G.0 92. rnt P-T/2.* bb,49b b

@ A c.= d 3 - 4 COT * (7 4 +-1(.045$

= 9A 12. m'

= s. h, es. vn c.Ou=u.x rat lb hsus OLOr.w. io ras. umm ui.. P=.$*bo116 3 e P -T/4 - 33,19r \_b . 4, - (T/2 )/s.t.s2 zviml ss mia, se ceasei.e vm. 4, - L T E9 7

move, armen. tu, to mi. 5,PRtAptM, kg= W[7 1)!9.4l2 o 6 S' p

=>>w as.v... Ics- ,

@ R= T/4 - 3 3,197 lb b. (W/2)/2./9.912.

nwo To comwtc.r rn vn'arn fe.s

• _ L ;3 9 fo Pi mi, mas.y to 7mt we4a anrrn<,

Lts(wmene.)...

@ P=W

• 30,09% lb e 4 -(T/4)/G.241

. ss16 me

@ f,- (T/4)/so92

- S '1 ST m

, , @ fg = W/3 / C,.092 /4'

, . 4 941 m

j

~

Rev. Rev. AuvMOR DATs cM E o. av oats CME o. av oats e NO. DATE l WESTINOMOUSS PORM 883130 l

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i

TITLE PAGE j

.R.V. Head Lift Rig Stress Analysis i4 on 31  ;

PROJEC T AuTMOR DATE CME *O ATE CME *D. sv OATE  !

e.O.

NEU $.C, $abud il19 cAs.C. no. (/0

&ll)evRi A oROuP l

r(f.E no:

NKVJ-188 REE l

T. in,91t",w- %ii n5 * -

TEMLION G. B- B @ 4v,' (Th N (M*2)  !

g, . s s u - 7:

G fv

• F/2) + (2 = c.032) l

%= P/A, tv- 9 T7 vi g ry.-(why3(2 =c.o,0 gxp p- T = in,991 ik tv- Ym r<  :

A - 9.co(un)-w(unf/4

- G 4. i t.o u

@ P- W/3 = twi392. I b 1HREAD SHEAR, (

A - 64.it.o ie ' .

f- y P/Av '

Gxt fi T/c,4.it.o Ay- Tr D r J / 3.,,,,  :

%on ft = mi D,w D, - n  !

@ 06- N/0 /c 4. it.o A p 6a - s.oois l h iJ% -i n.- ww a ,p.,e.s - 4 ga - 4.s374 ik t

SHE AR - 4.ur -out

) = 7. oo A

.T,,- P/2A,, Av- ,r (4.an-) 7.oo/2.

b ~

- 52,1962 e:: - -: \

} me p - T l q) P = T-/2.= 6bM% lb A,,- 53.19 J [

A,p 2.so (9.co-4ms)-oet .

@ P- W/3 l G.2 42i ' * -

A ' 5 3.1 3'*d- '

@ P- T/2.= W 4% i M 2.w (3.co-Iceey2 .ms' gg) .[y . T/53.19  !

= G os2iR T, - 1 s on -

@ P- (w/s)/2 6o,i96 @ f, -(w/3')/sa.is '  ;

4 c.os2 0 5,- ,. .w3 7:

RE Y. Re v. AUTMOR DATE C H E*0. SV OATE CME *0. S Y OATE NO. DATE WWESTINOMOUSS PORM OS2130 f

G

,,,w-. . - , - , - , - - - - - - - - - - , - . - - , - . - - - - . - - - - - - - - -

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE

• PAGE R.V. Head Lift Rig Stress Analysis 15 OP 31 PROJECT AUTHOR OATE CH K'D. Y ATE CMK'D. S Y DATE NEU & .(_*. 9.0 ) u 4 T R Y b40 Saove s.O. cA6C.a0. UD P'E ao.

NKVJ-188 REE LINTINCs LEG $

M A7'L ALTM - A 4 34 C.LA55 BC ALM 4 240 STtEL.

TURwtD,teEOuMO,l POLDHE.D. MCMIMVM VIELD STRtNb1H B(000 E.5T LAST ~770 8 I I 400 MDt FutL7HD l (TYp) i j S.00- 4UN -2 A -ty, b

!: ?is.W.*44 11 f.,961.04 e

A A 1 i - 4 l l C.OO- 40N- 2A- L. W.

i

• 4 ' k 7.oo m2w Two swou.tmmt (m :s aw. mu2%

\

l l l 1

l l

l O

i O

ggy, pgy, AUTHOR DATE CHK'D.SY DATE CHK*D. SY DATU NO. DATE WESTINGMOUSS PORM 942130

l WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION ,

I TITLE *

1. AGE R.V. Head Lift Rig Stress Analysis _

i6 op 31  !

PROJECT AUTHOR OATE CMK'O. e v TE CME'O.ev OATE s.O.

NEU h.C indn 4 T/87 catc.No. (7/

fw) M gE MO; amove NKVJ-188 REE l

l THREAD SMEAR TgM>rox4 e, A- A j

. l 1 - P/Av 4 - 9/A* l P-T - i n,39 l th i A, n % =J h 4.- pp ss of A.su.s.T.(m.o)

. . n,ms=wxm b p, W .t 4.,4% Ag J.( b - c.97434)'

Macd1 uri$Ad m 4hness (l%o) hembret4hiends D= bas w.jor ch.m b-Q megeedie==ke h = howihar of 4Ws ywsh w- n~w .* + as As DA =[Q L

, w[s2 A*t W~ 4 bp -(s oo - Sb4936) 4 n.%%*

= 4.83H. A A, T(4.svm) = 7.co/2 P= T = 131,19l ik 53.19 9

( -T/N - y g4 mt

%- T/ss.e '

. 1. 5 0 0 m ggy, gg y, AUTMOR OATE CME'O. SY DATE CMK'O. S Y DATE NO. OATE WESTINOMOUSS PORM 983130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R.V. Head Lift Rig Stress Analysis I 7 oP 31 PROJECT AUTMCA OATE CM K'O. av TE CHE* o. a v OATE e

NEU $.C .fh' 7/g4 CALC. NO.

(ke MM J~

GROUP s.O. QQ Pgt NO.

, NKVJ-188 REE Ct.EVIS PIN 6

MATL AST M A 434 AnI 4 34O STEEL , CLAW 0D,

! 44000 PM. PcNIMUM TENhnE STRENhTH EsT wr 50*

q ..--- w k .m,2.nw

[33,4.g4

-- - F ,__

. , 9.B& t.03 -q I TE M S O N P A G, E 4 N 6 R KE D wi tTit A N A S TE RI S K *e DO NOT CoNTRIB uTE To THE LOAD ON TttE Clevis PIN @,

THERE FORE THE LohD ON THE PIN IS WJ = 319,3 50 lb.

3 O

m E v. nav. AuTMon oATE CMno.sv oATE CMn o. sv oArd NO. DATE WESTINOMOUSE PORM SS2130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE ' AGE R.V. Head Lift Rig Stress Analysis l7 on 31 PROJECT AuTPdN' OATE CM E'O J. Y pATE CME'O.BV OATE NEU $.C.$aAnal TM Qu/YE d ~ AlltY _

s.O. CA6C. MO. ua rile wO. saOu*

NKVJ-188 REE ,

~~

~

, % s ?. . ca sa SHEAR  ?[- Id+s+ M h3 f,- P/A,  %. .e u.a u A = nd'/4

= w(3.959)'/4 l b- 5(N$ + ."5

• b W

= 12.I'7 3 % * - I(. 2.0 3 6'l )

P. (w/3V2. Ih- nin M

.fv = L43TO osi T

BEARIN Cs '

fu = P/A A,,= [2.50 - 2(.oess.h' l P, - lWh)/? . s3,n5n j Ag-[4.oo33.orr=g5.94g2 . P, = (W/3) = lo6@SO h 6

                 ' r to i o -,-

(1 ,

                      -         e 46a .        6M
                     ,          y                                                                        ,

1 l BENDIt%  : 1 a - 2.so - 2. (, oes) - 2.41 i

j. 4.006 3 = [4.5o d(ms)-4m3/2

              = .O.2 95 A d = 3. 937 m P= (W/3) = 1 Ch b50 h                             ,

AE V. REV, AuTMOR OATO CME'O. S v OATE CME *D. S Y OATE NO. DATE 4WSETIM4 MOUSE POned 583130 l l l

                                                                                          .______._i

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITi,5 PAGE R.V. Head Lift Rig Stress Analysis l9 on 31 PROJE CT AUTHOA DATE CM K'O. S V CHK'O. SV OATE NEU  %.(.blaul Mi grLE yoRX1]hgATE D S.o. , CALC.No. UO mo. caour NKVJ-188 REE 4-1:009 SPReAor sit Asstmet.y 78 M AT'L :

                               @        ARM           AbTM A10(* GFACE E 5EAMLES
                                @       LU 6           ASTM ASW C,RAct 90 WeLod          P. 70 IB E LECTRODeh EST. WT             2800"                                                                            3 8

7 (.00inas sr.Hao Prpe t.s at*) s $  ;

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                    \                                                   ,             i                               t e4%   tr.                                  81. cot 4 ube
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                           \     .

o$,'~' YIh ,. S s, p*.t %7

                             \.   ..

t sW , ,,,,,,,- rumw

                             /+[r[v l

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                                                              +                                 a p         4.*n.o2                        7daf gN               As2.i2     3.n c.%
                                                                  -6                ,,
                                                          / 1 an. ,

m..p,g -,,.- gg y, ggy, AUTHoA DATE CM K'D. S V OATE CH K'D. S V DATE NO. DATE WESTINGHOUSE POMat 842130

                                       .               . . _ _ .                    __._.._.m     _    . m. _. ._ .            _          . . - . . _ _ . _ . _ . . . . _ _ _ _ _ .              _ _ _ . . _
                                                                                                                                                                                                                   ?

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION  ! TITLE ' AGE R.V. Head Lift Rig Stress Analysis lo on 31  ! PROJECT AuTMOR DATE CME *D.gy TE CME *0. S V OATE  ; NEU h.C..faAnel T/74 w)M~,l.2- - i

                                      ,  n.O.                                  CALC. mo.            vo                 pt =o.-                            oRove                                                     j NKVJ-188                                                                                                                      REE                                 i I

LUG,, yg .  :

                                                                                                                       ..  '.K wh %                          aM                                                s    l A             T=InHilb                      O M CI         Sed. 6 hen s-d&}                                                        '

u  ; t  !

l. ., 'a -

FORCES ON  :  ! b m% ~5

                                                                    ~! * *k, -6
                                                                                       \                              set ARMAnun/, -[k .

k. b '

f, K - t iP [

                                                                  \<          /                                                 R

• axad forea.

7

m as = 3-3.v. R cd3r - K/2. i EE tv. v R .= KA7.aM)  !

Y w= 361 DF lb 3

• 5% 503 /(25 % 4  !

R = n;Ln 1 i

                                                                                = hn E

k ,

km m a %= .T , b 'O  !

                                                  % @= Ku

• Sb 3503  !

S. O *  ! k9 K- n; w n. l T -kan u E*

                                                                          - m so -x                                                                                                                               i t

t (ao.w.- u . ..w) - l

                                                         & 4~pr a.                                                                                                                                                i RE V.      RS V.                      AUTMOR                       DAYS CM E'D.SY                OATE CME'O. S V                                        04TE           k NO.        DATE                                                                                                                                                        [

wesTimoMoves pores Geniso ( i  ;

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R.V. Head Lift Rig Stress Analysis 2. I OP 31 l PROJECT AUTHOR DATE CH E'O. S V gT CH E*D. S V DATO'

• NEU  %.C. M ua; i m Mi $ h &DATE CALC. NO. Wd GROUP 5.0.

gtE NC. NKVJ-188 REE l Tuw sti.e. star.:,s e umawan - 12o;3 9 2./D.%a'-

                                                               *- son m    '

1

            ~ { = P/A P - T = 131,13 l

• A i- (s.som- 4.co) s.se,

                     -   27.Ic,i,,s                              SHEAR e towen Hott.

f, - IT1, t il /n.ic,

                & - 4797 m ,-                                    fy -     P/2Av r.orm,vakkg A, = (5.s - 4'F13.SB)'13.5 P= W/3

• 110;341 Sma wse.u,,mam .

                                                                 .fy     110,312. /(24 is.ss) i, - PA                                         fv 2. 9433               pi P- T- 132,19 l

• A, - (s.so 'O sis 13.se e L = l32,911./(un.ss) STatss e wn.o 4 . $ T97.at

                                                                          /
                                                                               %p s

TEftSILE STRtw G. LowLR HOLE [a ,,M...

• I/ SIN O

     ^'D

• f , P/A, 6 m.,u weae,od.(. % )

G

• P: Wl3 = 3bl,I75 /3

. I10,311 lb J. pe+ of pcK4r of und 26 . g or ads E n5H A, =M1n.s4 3)lt.O 2b: mm5r 9dd A  %- sA9

           ,.         1As=M.8nn)s.s              .
            .- 3.; . AgAiW='6(a.sms)u                            O- 30* ,i.,A 3cr                   c.s 4tw f , % n'? - $#=ll.G7                                 b= 4

, A 0-d M =(sit.M)2.se 25.7sA* a=8 REV. RE V. AUTHOR DATE CHE'O. S V DATE CM E*D. S V OATE NO. DATE WESTINGHOUSS PORM 882130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION PAGE TITLE R.V. Head Lift Rig Stress Analysis ~22 on 31 AUTHOR DATE cM E'o. av ATE CME *o. S V OATE PROJECT NEU $.(* 40A,, c 164 (stD Qi> s.o. aaou' cai.c. no. VO~ t'n ad. NKVJ-188 REE 9b 1 a + b.' 3

         ..      k = 1.02. 9 J       =(a+b) K 121t (1.019)
              - 3 8.79 4 hee, b. 3+ .
                 .50 n .701 = . 3EM A As 2she x.2 sir
                    . ta:r t ss R= anM form A Snk

• 31;b13 ,k l

i

                'FV *NbJ                                          !      !

Ev = 1 ~5 7o os.i o*TE cun o.sv oaTE RE v. Rav. Aviaca r 571 N/v

 " '        ""                                                                    L.                                      ..

WESTINOMOUSE PORM SS2130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE I R.V. Head Lift Rig Stress Analysis 23 os 31 l PROJECT A TMOR DATE CM E* D. S V ' TE CM K'D. S V DAT 8 g NEU .C.iM T/i'f rd _L lor g) S.o. NKVJ-188 CA(C.wo. ( LE no. ' onouP REE j t BUC,KLING STFE.55 Ed (kJ/rl/G = A @i IN EPREADER ARM F. - m io u d z a s a 3 6 , R.= 6Xial but, in speedar prn.ikJ s w.abw a. ar rn l of. waeporn.nt i

                                        = 31,lo13 Ib                                                                              :

Fa - (1-NA*)F, , K .s(r a=. w .n-ns. h (3 + 1 A _. g)

                                         = .h.% I                                                                                 l for Tip$t:h         &&r-
                                                         - h ] ev.ds, yi.id sw
                                                                                   -when. F) l= 3% - 140.09 A 1

74,33g  ! g e- 2.678for 8.co sc.w so ecg A = g2,9, g = 0.\C) 0 3 0

                                .-    A = 12.'M int                                                                             -

E- l os.'7 in' F3 = 35,000pst R-*j K.!/r MR

                                                   .s(uo.o )h.s,s Fa - 197iss ps;                   .
                                                = 24.3 3 B F 2wsE Cc, = 1 29,00U403                      d=Co p renuW com p Q
                                              - (2nt.     . . .                             m.
                                              -    12 9. M                              k = R /A E  nan /i2,%

K9/r 4. L f.. ,s.s., s ' ~

                                .S  re enc umenon. o.s-ie                                          '

1.3.l.3 Companwow S ngy, ggy, AUTHOR DATE CM E*D. S Y DATE CM E'D. S V DAT NO. DATE WESTINOMOUSE POmed 842130 9

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION j TITLE . #ADE , R.V. Head Lift Rig Stress Analysis l'1 on 31 PROJECT AUTHOR OATE CHE*D. SV TE CME *D. ev OATE NEU  %. C.9aAu d. Tl84 t A13 $!A s.O. CALC.No. (/g plLE NC . OROUP i NKVJ-188 REE l l 1 i

                .LIFTT.NG L.ag,                     (venrn%)                                                           g MT'L Mm A434 c, LAW se                             AIst 4Mo,iuEas>% fasaneo.

PhT WT I 4 9fe8 ,g l ---- . . .. - - . ., g,,o 49%,.,g l T  ! W

            ~

340.':2$ m i

                                                                                  ==1                                              !

I f I- - 24"1.TO 2,Cg, t l l MINImuP1 YrELD STRENWTH -- 85,000 PSZ .  ; MIMZfh8P) TMD EMhMesm4NT-.. '"7.00 EMcMEk k l '7.00 mTu Two spassaden.mtseT- (vraw h- m itac27) l i

                                                                                                                                  ?

t I t i l 5 l i I gg y, pgy, AUTHOR DATE CM E'O. S Y DATE CME *D. s v DATE NO. DATE WGSTINOMOues PORM b130

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

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R.V. Head Lift Rig Stress Analysis 25 OP 31 PROJECT AuTMOm DATE CME *0. S y ATE CME *D. S V DATE 7 a NEU 9,d.MnAwi T/74 /}u)k M S.O. CALC.MO. vg gtE Mo. . OnouP NKVJ-188 REE THREAD SHEAR regum g g.g P/Av= 110,392. W hp.- (W/3) f,- P/Av l l A, n brw = > h. -fr- p.j. ss Or A.su.s.T.(iwe) T u o r. a s m w A m t A b, p3 si or N.,4% A - p( b - c.97434)* Swae ds umGAd v.=o Ahn.as Dmo) fore = bet hOa> D= WA ksoro.~ b-Q = mes.c dew- h = nom hu =4 4 d> y na hs wu kr ok % ends pe 6 h bs 'c, w "n'5: A , T3 ( s. m O4S M ) o.wosn Dp = (S.00 - q ) 17,749cg 1.

~
                    - 4. sam.

AT- T(4.ss%) 7.co/2 P= (W/3) = 11.o ,3% lb

                  = 53.19 iO f+ - P/N -          4 ns mr k - P/s2.:                                                            '
                =

u, La m [ t ngy, ggy, AUTHOR DATE CME *D.SV DATE CH E*D. S V OATE MO. DATE WSSTINOMOUSE PORM 982130

I I WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l TITLE

• PAGE I R.V. Head Lift Rig Stress Analysis .

llo op 31  ; pnomer aurwon oaru enn o.sv p ra enno.sv oara NEU  %.&.9a),,m: Tilli OG)fu A n D s.o. c46c. =o. uo pa nq. caoue NKVJ-188 REE l l CLEvn 10  ; 1 WL 1 ASTM l A GefoB FOR4rH(e CoRADE. L . AIhr 4 ?.40 STEEL. MINIMOM V:tELD STRENwTH BS,000 Pst. l I!tbT b.D: 340" i 4 -, ,"**~,y - O i

                                   ,   .f*rd'                          9*d I- **

• t.- 9.so '

T L.o2 %- 7 s.co- AuN -20

                  ' ;,     ;i t 7              xy                                u sera       ',                    n so     ,

Ni ,

                     ', i i;'

i

                                                      .      N ,:i-                            = =.i1 n.*

N W,t i di j E_. L. r- , l z.s m

                                                             \ D\ \
                                                             \\
                                                                                       ^

i:} K i ysim.% 4 *" ' >

                                                             .N                     ,,gg A

4 A 4 o h A L _.., _ Sq == i

             "                             it                           i   \\         v 7.14-y e .oes !.ots A45*12*19p
                                                 ,3               ,e                                                        '
                                                  \eV 7.00 m que a ww== m a.ur ( % .,. n.n m)

HEAD LUG ygyc ngy st = 400 N. l iTENs ON PAGE 4 M ARKE D WITff AN ASTERISK ** DO . Nor coNTalBurs To TttE LOAD CN TttE C. LEVIS ITEM @ . Trt E RE FOR E T tie LO A D o N Tti E C.LE VIS ) S VV = 319." 50 l b,  ! nev. nev. ^urwon oars can o. av cara cun o.sv oara No. OATE

WESTINGMoWS5 PoRM 85313o I i

WESTINGHOUSE NUCLEAR TECHNOLOGY DIYlSION TITLE PAGE R.V. Head Lift Rig Stress Analysis ~2 1 OF 31 PROJECT AUTHOR OATE CMK*D.av CH K'O. S V OAv a NEU $.(.hadu.ej Tf14 kW &Ja). ,GATE k S.O. CALC.No. (g/ $E NO. GROUP NKVJ-188 REE T= 132,iil * , W= 319,950* TEN SI.O N e. A- A TEN SION G. B-B

                 .fi  -      P/A t                                kP--      P/At P- (*4 }/4                                  (w/3)
                               - w 6 63 '                          A - (S.cox9.so)-v(s.amW(

k ="(smo-3.911[Q2.50)-(. 045)* * (,5.2.4 int

                   = 6.314 in*                                      2{g = (WGG.24
                    .i-li)(i)/6.314                                  3-     i oss           _

f, - 4 m mt ' THREAD SMEAR BEARING E A- A 0,, - P/Ay - f, - P./Ac Ay ,t e,,a# J /2. P-(w/.3)/2 Dpw- 4.837L e t k=dD )= 7.00 a A= 3.947 (2.so- 2(.oes)) As, = 53.19 M

9. 3 I 2. in2 P= (W/3')

L - (i)(t)/s.s n, .Cy 05)/53.19

k. R,l,0 G y; E, m , aoR pi SHE AR - 4.eer-out-

               ~
                  .[,, - ( P) /2A.

P- (w/3)/a A, -(smo-uudXm)$0451

                        - c 3:4 e
                  .f.,_C, -am
                       .           (3Xi)/(2 m:= c sw)

REV. REV. AUTHOR DATE CH K*D. SV DATE CM K'D. S V OATI NO. DATE WESTINGMOUSE FORM SE2130

i WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R.V. Head Lift Rig Stress Analysis l'f on 31 PROJECT AUTMOR OATE CMK'O. By yTE CMK'O. SV OATE l l NEU  % .(, Pe)a Tliti Den $h 1. ~ A fitY S.O . CALC.NO. up pE wo. oROve NKVJ-188 REE i BEARLN& ON HOOK l C t.E.VIS PT.N ll  ! CL.oAD SEN SINC,. ) . C.-. P/Ac  : P=w i MAT'L: be 7.50 (,(s.2') = %.5 d ASTM A 5(e4 TYPE. AM11 ka 'W'/%.S T%- 135, OOC) PEE.

• W( .02 is t)

E=77L9 psz

                , _ '

• n.I m + [k MX BEARIM& QN SIDE PM fc. - P/Ac

                ..__     __   _ _ _ _ _ .._      __  . _.1
                                                        ."+                P - W /2.
            ..    ._.    ._   _ _ . _ . _ .._    ._  .                                            u < 3.sp.3a)
                .                                _ . , 7                  Ac= "l.5o ( 3.1)

_. T 1 23.2s mt - T . . W AliL* 2ns) E W = 3 f.:,1, ll5 l b  : W (.02 \505' ') L= 3 62 m

                        - n us -                                            PIN BENDING,

_  % comuner=. m. tuaan om=>m or 9  % wn. em

   .n g k                " "               3                        Ig -% ((,.tsf .w.s') = 1%.98 O c.. 7.s0/2 = s.?si

_%%m, .pu.us. & < is % I } I *h #ses w{ w/s

           *            *- s. car                                              y,    g
                                     -         - s.ats

[ N li T (us-1.55) = 2.5 W PIN SHEAR fg = Mc./I r uw= 3.'is/uc fr. f,, P/ A,, - Ow/a)/Ay - W (. O? 3'? 3 ) (. '% ( c .sa72 .mf)=5L%' Su u , f, FL PM

       . f,, w/2/39.ss. w(.ot3it.0)

c. 4.7 54 m ng y, gg y, AUTHOR DATE CH E*D. S V DATE CHE*D.SV DATE NO. OATE WSSTINOMOUSS PORM 882130

t WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION j TITLE PAGE R.V. Head Lift Rig Stress Analysis ":L9 On 31 PROJECT AuTMOR DATE CME *D. ey ATE CME'D. S V DATE s.O. NEU

                                                                            &.C..Vodu us TriN CAi.C. MO.             vs-th}L'A -(-

Pies No. oRoue

    ,                                     NKVJ-188                                                                                                                  _ REE WNhroM 4., 1 %. $ 44 c LE SIDE PLATE 5                                 q                                             E = P/A Ps W/2.

A , . (n.se-2.snXu.zs}- u.st? MAT'L: 34.tc.7 e ASTM A 533 wen ( - w /z./x.ua c t.Aw 2. ,so us. m a v.s = w (.o na ts) L. = 9 m m.

                                                   -.                     p.                                                                                            -

r,. k ane > u 4 S, .n mw> susw.-Teu<mr e. M $ watu.

                                                                                                                                   -f, . .pA, . (w/1) 4 A) r-                         ,.
                                                         /r j           V                   w.                           2. %,- (p.so-tsisXs.un)-z(.n.P i                    A           E                                             t. f, 4                           W (. o r38u) uno y- ---

ser

                                                              ---   ----                   t                                                   g,   yqqz                               m T1 y,li G

h'* **w Tu i .u . s. m SNEAlt. TEAR-OUT t, (oS IM HOLL

       ,                                                                                                                           6 - P/2Av -WI2.)X2A)

A ,:(S.5 - T h .co) .'152 /z.

                                                                                                                               - . wh. .soo(.v7s)
                                                                                                                                              = 2.o.9 9 W 6-- sv.so "

b = L.aJ /(54

• 2.C.%'M)

                                                                                                                                              = W . Oli t 39 )
                                                               @                                                                      fu = 4. 4 o b                  Psr.

I I BEAAIN(r lW- G%. 4 HOLIr.,  ; I Q , zs w s. na m s as von w i  ! EEARIN(s. AT ~7d h 4 Ot.E. 9Wana. OP ma. manomeu. pp QON k ss ws sama. m som wt. m wr.oe. es.am, anwea. as son. mwssm. @ one Q - W( . C/96 2 G ) f T984 494. PbM

     ,                                        .ca . wc.ousos3     .,u,                   m b          , ru                                     -

4 RE V. RE V. AUTHOR DATE CM E'D.SY DATE CME *D. SY OATE f NO. DATE wEsTINOMOUSE FOR44 582130 I

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , i t TITLE PAGE I R.V. Head Lift Rig Stress Analysis 30 Os 31 PMOJECT AUTHOR OATE CME *D ev CME *0. a v DATE NEU G.(.kk~i TITH YYUVIN[ ATE onove ~ ( s.o. . CAi.C. mo. oo es'E Mo. . i NKVJ-188 REE B E M t.I M 4 OM 5 3: D E R A T Y.

w. ,=. eaan g = m. .s= j REMOVABLE PIN m om m. m sva m.u m came, waam m. == m. zuwano I.

Peu Asm As(,4,Two c.m (_ - P/A maarmvacme HNtourewr ss., Aminuse P= W /2 i

e use van 4 nets,==uxun.me,comnr. Ac- f 500 ( 4.00 .\a.) i l m v= == i.e. sme n. A 26-32. = 2s.21e

( = w h. h.S.2.t.  ! 1P 1 - w( .o a su,) l E= l a __ _ _ _ _ _ J 1ib i ns. t w, - --- 435 )

             ' -- - '- - - -' ~ ~ '         ~~

T~

             -                                                   St.Ptir.t NW on strut, m                       [
     .                                              f                  .F;. =. P/Ac                             !

p- W  ! IB. 2.5 1 A v. = d b tA 8187 a.( or ) s g.o07 b 8.cz.7 (,( 92) = 51.434 SHEAA .[c- W/5143 l 6- P/Av - W(.oi sot 3) l P=. W /2. -(.- 9, q g g es2. [ Av - (c ss- lau') T4 I

                    - s a.183 c-                                  Bt. Norm 4                                   f E -w/2./ 32.189                                  S. 9.te'7- 2.(..o4 = B.oV7                     ;
                    - N/ ( .o ts 5 3 )                          a- 4 00                                        i G       g , 0,09        en                      y [8.2s -s.cm2(.iq /2 .2nsi                    j P = LJ i

f,,-'W il N(.d'10M S)Ot 4.c ( E* S T,3 9 7 Pu [ i m g y, ngy, AUTHOR OATE CHE*D.sv DATE CH E*D. s v DATE NO. DATE westimoMouse FORu seatso e i

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R.V. Head Lift Rig Stress Analysis 3l on 31 PROJECT AuTMOR OATE CM E'O. S Y TE CME *D.SY QATE

• NEU $.C.V.QEumi1lTt I s.o. afLE mo.

CA6c. no. U0 oRoue NKVJ-188 REE l

            - BENDIN(, STRF.h FORMULA CEqvATION -                                                    .

A h h u M I N Cs FORCES IN tounts t.ut. vo w r At T u s. t.u r. c. s N T s a.s A n o r u t v e n c e. 2. n v a t. C t.NitR. i.uc To Ac T AT Two ig.Acgs % wpN g,wyo rut t.u c. : MJ

aM I4

                                                              % a --e W (g .           '

jm s.m y 3., u-., 2_ ?9v  ; w. -e.u , ,  ; I a= 1 5 % o f orw. AG of cbble.-Ig Waeh A\\k\\ " E Y MM% surfeu.

                                                                                     .9. ga o c L..,.g h                                            sorb.of canke g                        l             g                 P - Soru. u vS o n n
                                                                                               .                  s d- CLiaTrwhe of Ein
                                               >% i Et+ F %-*i i

A t-84 *g%d " weata =

                                         . o       o is - Mc I

4% z.

                                             !                                           c,, a   df c'%
                                                       "'*                       4. m,_ c &

9

                               *\ +i + T"           '!                            (     a          9s y-                       f                           b'\      3 *YI) 32 Tid

• N.a. w. - -..~ ,

momen+ aba occuck wksha.  ! j w .s .mo,.,.a .% - l JWh.k.d ar.% N. L,h avr Ac l ! r

 ,                                          -          - M8hekl'                 *3 g g y,    p g y,             AUTHOR                   DATE CHE*D. S V                DATE CH E'O. S Y            DATE NO.       DATE WESTINGHOUSE FORM SS2130}}