ML17255A449

Forwards Response to Requests for Addl Info Re Special Lifting Devices Used for Control of Heavy Loads (Ref NUREG-0612)

ML17255A449
Person / Time
Site:	Ginna
Issue date:	10/12/1983
From:	Maier J PACIFIC GAS & ELECTRIC CO.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NUDOCS 8310180193
Download: ML17255A449 (36)

Text

REGULATORY FORMATION,DISTRIBUTION'S EM (BIDS)

AOJESSION NBR;8310180193 OOC ~ DATE 83/10/12 NOTARIZED:., NO DOCKET

.FAGIL'.,50 244 Robert" Emmet,,~Gonna Nuclear ~Plantr 'Unit.ir 'Rochester G

05000244

'AUTH~NAME'UTHOR AFFILIATION MAIERrJ,E, (Pacific 'Gas', Electric:.Co, "RECIPeNAME~

RECIPIENT AFFILIATION

~ORUTCHFIELD~D ~

Oper ating -Reactor s Branch.'5

SUBJECT:

.For wards.r.esponset;to r equests for,"addi,-info r e,especial lifting~devices used foi contr ol of heavy loads

,(ref NUREG 0612').

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TITLE':

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USI A 36 Control of He'avy Load Near 'Spent",Fuel NUREG~06 NOTES;NRR/Ol/SEP 1cy,,

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zaire'nzuzz Zzui sssxztzu ROCHESTER GAS AND ELECTRIC CORPORATION

~ 89 EAST AVENUE, ROCHESTER, N.Y. I4649 JOHN E, MAILER Vice President TELEPHONE AREA COOE Tld 546-2700 October 12, 1983 Director of Nuclear Reactor Regulation Attention:

Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.

5 U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Control of Heavy Loads R. E.

Ginna Nuclear Power Plant Docket No.

50-244

Dear Mr. Crutchfield:

This letter is in response to requests from members of the NRC Staff for additional information regarding special lifting devices at Ginna.

The attachment to this letter provides the requested information.

Very truly yours, Jo n E. Maier Attachment 83iOi80193 83iOi2 PDR ADOCK 05000244 P

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SECTION 1.0

SUMMARY

the The following pages list additional information regarding Special Lifting Devices at R.

E. Ginna Nuclear Power Plant.

Reactor Internals Lift Rig Normal use of this rig is or lzftz.ng the upper internals at refueling.

The upper internals package and lifting fixture weighs approximately 26 tons.

This same lifting device is also used to lift the lower internals package which weighs approximately 100 tons, including the lifting rig.

The lower internals liftis not, considered critical because the fuel is removed.

The lower internals pick; which has been successfully performed, most recently in 1979, can be considered an adequate load test for the upper internals lift.

2)

Reactor Coolant Pump Motor Sling Attached to this report rs a sketch of thrs lzftrng device (Figure 1);

a list of material properties (Table 1), weld examinations done during fabrication (Table 2),

and the summary of stress results (Tables 3 and 4).

Also attached are certain explanations of the stress calculations.

It can be seen from the sketch that this device is basically a spreader bar and is a very simple lifting assembly.

The stress design margins are within ANSI N14.6 criteria as shown in the stress results.

The welds on the rig underwent non-destructive examination during fabrication as listed in the information provided and again during our Spring 1983 outage under our continued compliance program.

This lifting sling is used in containment where it is not feasible to be load tested due to physical space and load requirements.

It cannot be removed from containment in one piece, unless the equipment hatch fixture is removed.

Load testing outside containment would require decontamination.

Based on the evaluation results, the simplicity of the

device, the fact that the device has lifted 100% of its rated load, and the existence of a continued compliance inspection program RGEE believes that a load test is both unnecessary and impractical.

3)

Reactor Vessel Head Lift,Ri Attached to this report is a sketch of this lxfting device (Figure 2),

a list of material properties (Table 5), weld examinations done during fabrication (Table 6),

and the summary of stress results (Table 7).

P

As shown and listed in the attachments, there are three (3) sets of critical welds which were examined during construction and which are encompassed in the existing continued compliance inspection program.

During our Spring 1983 outage, the link lug to sling assembly link welds were examined with the remaining weld inspections scheduled for the Spring 1984 outage.

It can be seen from Table 7 that the stress levels for liftrig components are well within ANSI N14.6 Guidelines.

Because of the size and configuration of the lifting rig, final fabrication was completed inside containment It is physically impossible to get, it outside of containment in one piece.

It is also, because of limited space,and the load requirements, impractical to perform a rated load test in excess of 100%.

The rig has been tested to 1008.

Based on the evaluation results which show substantial margins of safety in the lifting device design, the existence of a continued compliance inspection

program, and the devices proven capability to lift 100% of its design load RGSE believes that this lifting rig adequately satisfies the guidelines of ANSI N14.6.

A load test is neither warranted nor practical.

1 f

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SECTION 2.0 SPECIAL'IFTING DEVICE'EVALUATIONRESULTS 1)

This section provides additional information such as sketches, material lists, weld examination requirements and stress level results for the Reactor Coolant Pump Motor Sling and the Reactor Vessel Head Lift Rig.

In some cases, explan-ations are provided for certain stress calculations.

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SIIIICIILB TURNBUSNf S Q

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TABLE PEACTOP.

COOLANT PUMP MOTOR LIFT SLING MATERIALS AND MATERIAL PROPERTIES (a)

Item

. Description

~

Material Yield Strength y(ksi)

U1 timate Strength ult(ksi) 1 2

Side plates ASTM 212 Grade A

Spreader (pipe)

ASTM A 106 G~ade B

36 60 58

)See figure 1

~

TABLE 2

ACTOR COOLANT PUMP MOTOR LIFT G

CRITICAL ITEMS LIST OF PARTS AND WELDS PER ANSI N14.6-1978 Item(a)

Non-destructive Testing Description Material

., Material Finished 8

9.

Spreader Side Plate Master Link Sling Assembly Shackle Turnbuckle Eye Hook ASTM A106 Grade B

ASTM A106 Grade B

Alloy Steel Forging Improved Plow Steel Grade Alloy Steel Forging Alloy Steel Forging Alloy Steel Forging Radi ograph hag neti c Particle on Melds Only

~a)See figure 1

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TABLE 4

'tiYiPARISON OF DESIGN LOADS AND RATED LOAD VAL'UES OF THE hON-DESIGNED ITEMS OF THE R.C.

PUMP MOTOR LIFT SLING l

Loads (Pounds)(

)

Safety Factor(4)

'o.(?)

Item.

Design Rated(1)

Load

~ Value Proof(

)

Ultimate(

~ Load Load "

~

Sling 81,000 Shackle 27",000 Master Link -81,000 L

160,000 81,000 70,000 320,000 g4,000(5) 154,000 544,000

'.4:1 405,000 420,0GO Turnbuck 1 e 27,000 37,000.

74,000

.185,000 5:1 Hook 27,000 38,750 77,500 131,750 3.4:1 NOTES:

(1)

RATED LOAD VALUE - The maximum recommended load that.should be exerted on the item.

The following terms are also used for the term Ratea Load:

"SWL", "Safe Working Load", "Working Load", "Working Load Limit", and the "Resultant Safe Working Load." All rated load

values, are for in-line pull with respect to the.centerline of the item.

(2)

PROOF LOAD - The average force to which an item may be subjected before visual permanent deformation occurs or a force that is applied in the performance of a proof test.

(3)

ULTIMATE LOAD The average load or force at which item fails or no

'onger supports a load.

(4)

SAFETY FACTOR - An industry. term denoting theoretical reserve capability.

Usually computed by'ividing the 'catalog stated ultimate load by the catalog stated working load limit and generally expressed as a ratio, for example 5 to l.

TABLE 4

(Cont)

(5) This. information is as stated on Mestinghouse drawing AEO SK 618J644 TXK Sub 5 as follows:

"Safe workin~ load of this sling assembly is 81,000 lb and a safe factor of 5:1.'atalog information is not

'pp1 icable.

r (6) The rated load value, proof load, ultimate load and safety factor information was obtained from the following vendor catalogs:

a.

S.G. Taylor Chain Co., Inc., Bulletin AS-67 Alloy Steel Chain Assemblies, Attachments for items 5 and 9.

b.

Pennsylvania Sling Co. for item 6.

c.

Crosby Group, 950 General

Catalog, June 1981 for items 7 and 8.

(7) Refer to figure 1 for identification of items.

1

Structures Loaded in Compression and Bending The spreader assemblies

'of the reactor vessel internals lift rig and the reactor coolant pump motor lift sling do not meet the ANSI N14.6 criteria of 5W when analyzed for axial compression loadings and comparing to the allowable stresses of the AISC code (instead of the corresponding ultimate strength of the 5W criterion). If we were to use the corresponding ultimate strenth acceptance criteria for the 5W loading conditions, the structure would be adequate.

However, it is well known that care should be taken when addressing members in compression to ensure elastic stability'hus, structures 'lqaded in compression are analyzed by the empirical equations of the(>>

ASME Boiler and Pressure Vessel Code Section III, Appendix XVII or the AISC(2) Part 5 rules.

If we were designing a new structure, the material and member size would be changed to ensure these allowable stresses would be satisfied for all loading conditions.

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

The column under consideration is relatively short (kl/r=45.2).

Timoshenko (3) states that experiments show that short columns buckle when the compressive strength reaches the material yield point.

(The horizontal line on the, figure below).

CO CO LU tC (0

uI-CCD YIELDPOINT E = 30 X 106 PSI l

l 1

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I EULER CURVE 2/r 45.2 COLUMN BUCKLING 80 10

There fore the total stress o

=

P A

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

For the case of the internals liftrig spreader:

<Total =

P

=

4531 psi A

which is less than the material yield strength (Sy)

Then to find the ultimate column load, let omax

= Sy = 36,000 psi Then the maximum column load is the ration of max/ototal Thus the ultimate column load is 7.9 times the nominal value The internals liftrig spreader members are considered acceptable for this condition of axial compression.

Similarl

, the ultimate load for the reactor coolant um motor lift sling is 6.7 times the nominal value and also considered acce table.

Rated Load Values of the Reactor Coolant Pum Motor Lift Slin Since most of the components that comprise the reactor coolant pump motor sling are pre-engineered components, application of the criteria of section 3.2.1.1 of ANSI N14.6 to these components is not appropriate.

Therefore, Table 4 has been prepared from catalog information and list the various load conditions.

Noting that the safety factors are based on the ratio of the ultimate strength of the material to the rated load value, the sling is acceptable for five times the design load.

REFERENCES 1)

ASME Boiler and Pressure Vessel

Code,Section III, Division I, Nuclear Power Plant Components, American Society of Mechanical Engineers, New York, 1980 2)

Manual of Steel Construction, Seventh Edition, American Institute of Steel Construction, New York, 1973 3)

Timoshen'ko, S.,

Stren th of Materials, Part 1, Elementar Theory and Problems, D. Van Nostrand Company, Inc.,

The.rd Edxtxon, April, 1955, pp.

263-279.

12

Q3 6.5/8" DIA. BOTTOM PIN Q4 SLING ASSEMBLY LINK Q6 4" DIA.CLEVIS PIN Qo Qo 6-5/8" DIA.HOOK PIN Ql LIFTINGPLATE Q2 LINKLUG Q5 UPPER CLEVIS Q7 ARM Q8 BOTTOM CLEVIS Q9 Qll SUPPORT LUG 4" DIA CLEVIS PIN Q10

, RING GIRDER Q12 LEG Q13 CLEVIS PLATE Q14 3" DIA. CLEVIS PIN 015 Figure 2 Reactor Vessel Head Lift Rig

I A

TABLE 5

'REACTOR VESSEL HEAD LIFT RIG MATERIAL AND MATERIAL PROPERTIES Yield Ultimate Item" Description Material Sy (ksi) ult.(ksi)

-Strength.

Strength 1,3,6,.

10,15 2,11, 14 4,5,7 9

12 13 6-5/8" Dia.

Hook Pin 6-5/8" Dia. Bottom Pin 4." Dia. Clevis Pin 4" Dia. Bottom Clevis Pin.'"

Diameter,Pin Lifting Plate Support Lug.

'levis Plate Sling Assembly Link Link Lug Upper Clevis Bottom Clevis

Arm, Ring Girder, Leg ASTM A434 C1ass,BD ASTM:A51 4..or.

VSS Tl ASTM.A237 Class'A ASTM A306 Gr-70 ASTM A285 GR.

C'STM A36 (A 501) 100 105 90 36 50

~

30 36 130 135 100 70

.80 70

'55 58

)See figure 2

TABLE 6

REACTOR VESSEL HEAD LIFT RIG CRITICAL ITEMS LIST OF HELDS PER ANSI N14.6-1978 Item(

)

Weld Non-destructive Testing Description Root Pass, Final 4,5 11,12 14

. Link Lugs to Link (full penetrat'ion)

Ring Girder to Support Lug (fillet)

Clevis Plate to Leg

.(fi 1 1 et)

Magnetic Particle Radiograph

=Magneti.c Particle Magnetic Particle L ~

Magnetic Particle-(a)

See figure 2

1

TABLE !7 SUNARY. OF RESULTS REACTOR VESSEL HEAD LIFT RIG Calculated Stresses (ksi)

Material Al 1 owabl e Item(a)

No.

Part Name And Matelial Designation Mb'alue 3W S (c)

S (d)

~ Suit 6 5/8" Dia.

Hook Pin ASTM A 434 Class BD Bending Shear

.Bearing 11.7 2.8 5.0 35.1

~

8.4 15.0 58.5 14.0 25.0 100 130 Lifting Plate ASTM A 514 or USS Tl Tension Shear Bearing 4.3 4.3 4.9 12.9 12.9 14.7

21. 5 21.5 24.5 90 100 6 5/8" Dia. Bottom Pin Bending ASIA A 434 Shear Class BD Bearing 11.7 2.8 5.0

'5.1 8.4 15.0 58.5 14.0 25.0

'00 130 (a)

See figure 2

for location'of item numbers and section (b)

M is the total.static weight of the component and the lifting device (c)

S is the yield. strength of the material (ksi)

(d)

Slt is the ultimate*strength of the material (ksi).

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TABLE 7

(cont)

SUlOARY OF RESULTS-REACTOR VESSEL HEAD LIFT RIG Calculated Stresses (ksi)

Material Allowable Ite'm" No.

Part Name And Materi.al 4" Dia.

Clevis Pin ASTM A 434 Class BD Designation Bending Shear Bearing W

b'1 2 ~ 8 5.0 Value 3W 33 '

8 '

15 '

5W 56 '

14.0 25.0 S (c)

/

105 ksi (d) ult

'1 35 Upper Clevis ASSAM A 237 Class A

Tension 9 Hole Shear 9 Hole Bearing 9 Hole 2 ~ 9 2'

4.5 8 ~ 7 8.7

13. 5

14. 5 14.5 22 '

50 80 Arm ASlM A 306 Gr.

70 Thread Tension Tension 9 Full Section Thread Shear 6 ~2.

5 '

2 '

18 ~ 6 16 '

8 ~ 7 31 '

27.0 14.5 35 70 8 ~ 1 Turnbuckle C-1035 69.4 167.8 (a)

See figure 2

for location of item numbers. and section (b)

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

S is the yield strength of the material (ksi.)

(d)

Sl> is the ultimate strength of the material (ksi)

(e)

Des'n load (maximum applied load)

(f)

Safe working load (contains 5:l safety.factor)

l 4

1

TABLE 7~ (cont)

SblihARY UF RESULTS REACTOR VESSEL HEAD LIFT RIG No.

Part Name And Naterial Calculated Stresses (ksi)

Designation Value 'W c) 0 ult materi al Allovable (ksi Bottom Clevis ASTl1 A 237 Class A

Stresses are the same as Item 7.

Same as Item 7

Same as Item 7

':Same as Item'7:

i 50 10-4" Dia.

Stresses are the same as 105 135 Bottom Clevis Pin Item 6 except for:

ASTN A 434 Bearing Class BD 5.0 15.0

'25;0 Support Lug ASThl A 514 or USS Tl Tension 9 Hole Shear 8 Hole Beat ing 8 Hole 3.3 3.3 5.1 9.9 9.9

'l5. 3 16.5 38

16. 5

25. 5 70 (a),

See figure 2 for location of item numbers and section (b)

N is the total static weight of the component and the lifting device (c')

S is the yield strength of the material (ksi)

(d)

Suit.is the ultimate strength of the material (ksi)

L

TABLE

'7.'cont)

SDtihARY OF RESULTS

. REACTOR VESSEL HEAD LIFT RIG q )q,(I A'o.

Part Name And Material Calculated Stresses (ksi)

Designation Value c

.I ult Materi al Allowable ksi N12 Ring Girder ASTM A 285 GR.

C Total Shear Maximum Bending Maximum Tensile Stress Ring Girder to Support Wela 1.'6 1.0 2.1 1.6 4,8 3.0 6.3 4.8 8.0 5.0

10. 5 8.0 3O 18(g) 13 Leg ASTM A 36

{A-501)

Clevis Plate ASTM A 515 GR.

70 QIIT Tension Weld.

Tension Shear Bearing 5.3 2o3 3.5 3.6 6.6

15. 9 6.9

10. 5

10. 5 19.8

'26. 5 17.5 17.5

33. 0 36=

18(')

38

'58 70 (a)

See figure 2

for location of. item.numbers and section (b) 0 i s the total stati c wei ght of the component and the 1 ifting devi ce (c)

S is the yield strength of the material (ksi)

(d)

Suit is the ultimate strength of:the material (ksi)

(g)

Stress limit for fillet weld from ASIDE Boiler, Im Pressure.

Vessel Code,.Section III, Division 1-Subsection NF 1980 Edition, Table t<F - 3292..1-1

.page 50

TABLE 7

(cont)

SUMMARY

UF RESULTS REACTOR VESSEL HEAU LIFT kl6 Calculated Stresses (ksi)

Material Allowable Item(')

Ho.

Part.hame And Material Vesignation Value

'3W 'W s

ksi 3" Diameter Pin ASTN A 434 Class BD Bending Shear Bearing 14.3 3.7 8.8

42. 9

.11.1

~

26.4 "71.5 18.5 44.0 110 140 (a)

See figure 2: for location of item numbers and section (b)

W is the total static weight of. the component and the liftinjdevice (c)

S is the yield strength of the material (ksi)

(d), Suit i.s the ultimate strength of the material'ksi)

k a.

C j

1