ML20138J498

Fort St Vrain Nuclear Generating Station Heavy Load Analysis Phase I

ML20138J498
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/15/1985
From:	SARGENT & LUNDY, INC.
To:
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR TAC-11025, TAC-52230, TAC-56302, NUDOCS 8510290366
Download: ML20138J498 (58)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION i

HEAVY LOAD ANALYSIS REPORT PHASE I IlO i

kh0MO366 851015 ADOCK 05000267 p

PDR PREPARED l

BY 1

SARGENT & LUNDY O

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OCTOBER 15, 1985 E

t e Monorail with Electric Hoist Building 16 l and Trolley i RB = Reactor Building i TB = Turbine Building i i { i l J a [ ( d TABLE 2.1.2-2 CRANE /HolST EXCLUSIONS BY INSPECIION FOR HEAVY IDAD DAMACE lu SHUTDOWN MODEl, EQUIPMD4T OR ACTUAL IDADS LESS THAN ONE 1DN RATED IfCATION LABEL ID NO. DESCRIIPTION IDAD CAPACITY ELEVATION COMENTS C3 C-7215 Reactor Building Truck Bay 20 tone 4791 R8 No shutdown equipment Crane C5 C-7214 Helium Circulator Turntable 2 tone 4740 R8 No shutdown equipment Jib Crane C8, C9 C-7207 Cas Waste Compressor 6 tons 4740 RB No shutdown equipment. Manual Holst and Trolley C10 C-7209 Helium Transfer Compressor I ton 4740 RB No shutdown equipment. Trolley Cl4 C-7208 Strontium Monitor Cask 4 tone 4829 R8 Cask is not used, hoist handles Electric Hoist and Trolley loads less than 3/4 ton. Electric hoist will be dersted to 3/4 ton y CIS G-7206 Reactor Outlet Coolant I ton 4829 RB Monorail only. Hoist will be derated a 1herm> couple Monorail to 3/4 ton C19 C-7210 Cooling Water Filter and 1.5 tons 4849 R8 Hoist lifts hinged covers on tanks Demineraliser Tanks Trolley and filters each less than 3/4 ton. and Monorail System Hoist will be derated to 3/4 ton. C21 C-7502 Machine Shop Electric Hoist 5 tons 4791 TB No shutdown equipment. and Trolley C22 C-7506 Service Water Return Pumps I con 4791 T8 Hoist will be derated to 3/4 ton. Manual Chain Hoist and Trolley C24 C-7504 Service Air Compressors 4 tons 4791 TB No shutdown equipment Manual Chain Hoist and Trolley C25 C-7505 Instrument Air compressor I A 4 tons 4791 TB No shutdown equipment Trolley C26 G-7505S Instrument Air Compressor IB 4 tons 4791 TB Mo shutdown equipment. Trolley j RB = Reactor Building TB = Turbine Building i ._m.._. _ _. _ _. ~. i l i 4 TABLE 2.1.2-2 (Cont'd) 1 4 j RATED LIX'ATION 't LABEL ID ND. DESCRIPTION IDAD CAPACITY ELEVATION 00000ENTS 1 2 n' C31 C-4201 Service Water Suction Screen 3 tons 4788 No shutdown equipment. Trolley and Hoist Outdoors Holst will be derated to 3/4 ton 1 C32 Mobile Nydraulic Crane, Outdoors Not a fixed overhead handling Jib Capacity no of f set t 3 te-s system i j Outriggers Estended, Jib Not Engaged 14 tone 1 C33 Condenser Water Box Monorails 6 tone 4791 TB No shutdown equipment each C34 Machine Shop, Building 15, I ton _ Remote No shutdown equipment Monorail with Electric Hoist Building and Trolley a C35 Welding Shop. Building 16, 2 tone Remote No shutdown equipment Monorail with Manual Hoist Building i and Trolley C36 Turbine Building Sump 8 tons 4791 Tb Ilo shutdown equipment u

• Pump Monorail a

C38 A-Frame Trolley and Hoist 1/2 ton 488I RB Trolley is rated at I con and will be derated to 3/4 ton l i t i, l i 5 RB = Reactor Building I TB = Turbine Building i 1 I 1 Fort St. Vrain /s\\ V 2.1.3 Compliance of Containment and Spent Fuel Area Heavy-Load-Handling Systems with NUREG-0612, Section 5.1.1 Guidelines With respect to the design and operation of heavy-load-handling systems in the containment and the spent-fuel-pool area and those load-handling systems identified in 2.1.1 above, provide your evaluation concerning compliance with the guidelines of NUREG-0612, Section 5.1.1. The following specific information should be included in your reply: 2.1.3 a) Drawings or sketches sufficient to clearly identify the location of safe load paths, spent fuel, and safety-related equipment. RE SPONSE Figures 2.1.3-1, 2.1.3-4 through 2.1.3-12 identify the hook coverage areas of FSV handling systems, including those that O's have been evaluated against the guidelines of NUREG-0612 (listed in Table 2.1.3-1). Safe load paths for the monorail / hoist systems listed in Table 2.1.3-1 are in effect defined as the hook coverage of the monorails as shown in these figures. With regard to the Reactor Building and Turbine Building over-head cranes, no prescriptive safe load paths have yet been defined. An exclusion area has been defined for the Reactor Building crane, in that no load movements are permitted over the prestressed concrete reactor vessel (PCRV) during reactor operation. As a result of the Phase II analyses and evaluations (see Phase II report), a better understanding is now available lO l 2-10 l Fort St. Vrain O 4 as to the location of shutdown equipment relative to the Reactor i l Building and Turbine Building cranes. Based on this infor-l mation, PSC is evaluating the need for more de'finitive safe load paths for these two overhead handling systems. Such safe load paths, if found to be necessary, will be appropriately I incorporated into plant load handling procedures. 2 l f i O i j I l l l l l l l O 2-11 l l ll t Fort St. Vrain O 2.1.3 b) Heavy Load Procedures and Change Process A discussion of measures taken to ensure that load-handling operations remain within safe load paths, including procedures, if any, for deviation from these paths.

RESPONSE

Table 2.1.3-1 lists loads for cranes or hoists not excluded in response 2.1.2, the crane or hoist making the lift, the load weight, the lifting device being used and the procedures for load movement.

The Fort St. Vrain Nuclear Generating Station Maintenance Procedures MP-104 series are used in the load handling operation of the reactor building overhead cranes

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and the turbine building overhead crane.

Some loads are governed by a specific procedure, for example:

Fuel Handling Procedure Work Packet-22 (FH PWP-22 ) governs the fuel handling operations.

Any deviation from these specific operational procedures or safe load paths will require a written alternative approved plan.

Any future heavy loads will use either currently approved procedures or will have load-handling pro-cedures developed to ensure safe load-handling operations.

l 2-12

Fort St. Vrain O

The reactor building overhead crane, G-7201, is an electric overhead traveling bridge crane with a rated capacity of 170/50 tons for the main hook and 17.5 tons for the auxiliary hook.

It is controlled by an operator on the refueling floor using a pendant pushbutton control panel.

Figure 2.1.3-1 shows the hook coverage areas on the refueling floor and the monorail in the turbine building for the reactor plant air handling equip-ment hoist.

Major heavy loads such as the fuel handling machine (FHM),

auxiliary transfer cask (ATC), three isolation valves (two reactor isolation valves (RIV) and fuel storage isolation valve),

)

and spent fuel cask have specific laydown areas.

However, the singular unique features of each outage or modification generate unique requirements for the movement and' location of other heavy loads within the limited space of crane hook coverage.

Requiring permanent floor markings would either generate a confusing multiplicity of floor markings or place unrealistic constraints on work operations.

Furthermore, ALARA considerations of the work performed on the refueling floor may at times require placing opaque paper with taped borders on the floor to prevent the spread of potential radioactive contamination, thus reducing the usefulness of permanent floor markings.

Other ALARA considerations for a specific modification may also

[

impose unique requirements on the movement and location s

of equipment.. During reactor operation, no movement of crane 2-13 l

Fort St. Vrain (3

%1 1

load lifts is permitted over the prestressed concrete reactor vessel (PCRV).

Thus, it is not feasible to mark per-manent load paths and laydown areas on the fl6or, nor would it contribute to the health and safety of the plant personnel or the public.

The reactor building overhead crane is operated in accordance with written approved Procedure MP 104-1 and written approved work packages.

The turbine building overhead crane, G-7501, is an electric overhead traveling bridge crane with a rated capacity of 65/15 tons.

Figure 2.1.3-10 shows the hook coverage of the 65-ton main hook and the 15-ton auxiliary hook.

The turbine building

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operating floor is used for the occasional laydown of equip-ment requiring temporary internal storage and for turbine generator parts laydown during the periodic maintenance outage with the reactor shut down.

Operation of the turbine building overhead crane is in accordance with written approved proce-dure MP 104-4.

Deviations from approved procedures require written approval in accordance with established procedures.

l 2-14 l

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

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i Fort St. Vrain i

Figure 2.1.3-13 shows the monorail / hoist / trolley coverage i

l outside the reactor / turbine buildings.

The mobile hydraulic l

crane is also shown.

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Fort St. Vrain O

2.1.3 c)

Heavy Load List A tabulation of heavy loads to be handled by each crane which includes the load identifi-cation, load weight, its designated lifting i

device, and verification that the handling of such load is governed by a written procedure containing, as a minimum, the information identified in NUREG-0612, Section 5.1.1. (2).

RESPONSE

The attached Table 2.1.3-1 lists the cranes / hoists and the heavy loads normally handled by each overhead handling system.

It also indicates the written procedures that govern the handling

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of each crane load combination.

MP-104 series Fort St. Vrain Nuclear Generating Station Maintenance Procedures apply generally to loads handled by the reactor building overhead cranes and the turbine building overhead crane.

These procedures address the items in NUREG-0612, Subsection 5.1.1. (2) and will be updated based on the results of this. heavy loads analysis.

In addition, procedures will be developed to cover the hoists and loads listed in Table 2.1.3-1.

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V TABLE 2.1.3-1 IDADS OF CRANES AND HolSTS C-1 C-7201 Reactor Building Overhead Crane 170/50/17% Tons 4881'-8" Reactor Building 4

LIFTING RIC/

LOAD ID DESCRIPTION IDAD DEVICE PROCEDURE C000 TENTS H-1301 Fuel Handling Machine 165.5 tons Lifting Mushroom MP-104-1 and Snubber Control FHPWP-22 System H-1602 Auxijiary Transfer Casit 66.5 tons Lifting Mushroom MP-104-1 and Snubber Control FHPWP-22 Systes T-2302 Helius Purification Stings MP-104-1 Equipment H-1605 Control Rod Storage 10 tons Slings MP-104-1 Well Shielding Adapter H-1501 Fuel Shipping Cask Yl tons Scissor Lifting MP-104-1 For each opent fuel cask shipment, Rig FSAR 9.1.2.2.4 a special work package is prepared FHPWP-22 and approved in accordance with established procedures. Deviations y

require written approval in accordance u

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with established approvat procedures.

M-1305 Fuel Loading Port 8,588 lbs Stings MP-104-1

.n Cover Plate 2,355 lbs Slings MP-104-I g

C-2101, Helius Circulator 15 tons Slings, with be.se MP-104-1 2,3,4 each or cradle MP-21-15 i

T-2101 Helium Circulator with 40 tons Slings MP-104-1 Lower Cask, Isolation HP-21-15 Ball Valve, and Pipe 3

Container H-1302 Reactor Isolation Valve 15 tous Slings MP-104-I l

H-1303 Reactor Isolation Valve 15 tons Slings MP-104-I H-1402 Fuel Storage Isolation 15 tons Slings MP-104-1 Valve l

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TABli 2.1.1-1 (Con t 'd )

C-l C-720I Reactor Building Overhead Crane 170/50/17\\ Tons 4881'-8" Reactor Buit. ling (Cont'd)

LIFTIIIC RIC/

IAAD ID g RIPTION IDAD DEVICE PROCEDURE CosetENTS Peripheral Shielding Deck Plates I

2 plates 2600 the each Slings MP-104-1 2 plates 5450 lbs each Stings MP-IO4-1 2 plates 5500 lbs each Stings MP-104-I a

2 plates 5600 lbs each Stings MP-104-1 2 plates 6000 lbs each Slings MP-IO4-1 i

Hold Down Plates, PCRV Top I plate 3000 lbs Stings MP-104-1 I plate 4570 lbs Slings MP-104-1 I

n I plate 4850 lbs Slings MP-104-1 (n

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I plate 5I00 the Slings MP-104-1 i

H 2 plates 5810 lbs each Stings MP-104-1 E

F I plate 6290 the Slings MP-104-1 i

2 plates 6340 lbs each Slings MP-104-1 I plate 6600 lbs Stings MP-104-1 i

Annular Shield Plates, PCRV Top 2 plates 2500 lbs each Slings MP-104-1 12 plates 2650 lbs each Slings MP-IO4-1 L

2 plates 1850 lbs cach Slings MP-104-1 4

I plate 1200 lbs Slings MP-104-1 1 plate 1350 lbs Slings MP-104-1 2

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C-1 G-7201 Reactor Building Overhead Crane 170/50/17\\ Tons 4881'-8" Reactnr Building (Caint 'd )

LIFTING RIC/

LOAD ID DESCRIPTION IDAD DEVICE PROCEDURE COMMENTS Hot Service Facility 35 tuas Stings MP-10 '*- l Removable Cover Slab (2) each i

Hot Service Facility 20,820 lbs Slings MP-104-1 Plug Shield Spent Fuel Cell Cover 22 tons Stings MP-104-1 Plug (9) each Regeneration Pit Cover Removable Slabs (1) 34 tons Slings MP-104-1 (2) 17 tons each Slings MP-104-1 Misce!!aneous Loads Varies Slings MP-104-1 C-2 C-750I Turbine Building overhead Crane 65/15 Tons 4829'-0" Turbine Building

'=3 Turbine Rotor - HP 44,852 lbs Beam 158D979 Slings MP-104-4 0

- LP 98,410 lbs Beam 158D979, Slings MP-104-4 m

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M Cenerator Rotor 102,000 lbs Beam 158D979, Slings MP-104-4 e

Turbine Upper LP Inner Shell 18,130 lbs Slings MP-104-4 LP-inner Casing 67,280 lbs Slings MP-104-4 IP-inner Shell 8,000 lbs Slings MP-IO4-4 HP-inner Shell 42,000 lbs Stirgs MP-104-4 HP-outer Casing 114,656 lbs Slings MP-104-4 Turbine Front Appearance 4,000 lbs Stings MP-104-4 Lagging Turbine Front Standard Cap 4,000 lbs Stings MP-104-4 HP-LP Turbine Appearance 4,000 lbs Slings MP-104-4 Lagging LP Hood Upper End 30,230 lbs Stings MP-104-4 LP Diaphragas (10) 6,000 lbs Slings MP-104-4 cach (2) 9,000 lbs Slings MP-104-4 each Diaphrages (9) 9,000 lbs Slings MP-104-4 each Crossover Pipe 30,680 lbs Slings MP-104-4

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C-4 C-7205 Bearing Water Pump Holst 1.5 Tons 4740'-6" Reactor Building i

LIFTING RIC/

ICAD ID DESCRIPTION IDAD DEVICE PROCEDUKE COMMENTS P-2102, 2S, Bearing Water Pumps IC,lD,lF P-2107 Head and Bowls 2346 the each Slings Motor 965 lbs each Slings Barrel 1115 lbs each Stings C-6 C-7205 Bearing Water Pump Hoist 2 Tons 4740'-6" Reactor Building P-2101, IS Bearing Water Pumps IA,lB,lE P-2106 Head and Bowls 2346 lbs each Stings Motor 965 lbs each Slings Barret 1815 lbs each Stings C - Bearing Water Make-Up Pump Hoist 3 Tons 4771'-0" Reactor Building P-2105 Bearing Water Make-Up g

Pump 3100 lbs Slings O

Motor 1400 lbs Slings rr if D3 ha r'

C-11 C-72tl Waste Filters and Demineralizers Manual Hoist and Trolley 4 Tons 4791'-0" Reactor Building F-6301, IS Cas Waste Filters 700 lbs each Slings 3

F-6304, AS Waste cas Pre-Filters 125 lba each Stings Shield Blocks (2) 1.7 tons each Stings.

(2) 2 tons each

, Stings (2) 2.7 tons each Slings (1) 3 tons Slings (2) 4 tons each Slings i

C-16,- 17,- 18 C-7212 Hydrogen Cetter Area Trolley and Hoist 1 Tons 4854'-0" Reactor Building I

t E-2307 Hydrogen Removal Slings Economizer A-2309,95 Hydrogen Cetter Unit Cover 216 lbs Slinge F-2301,2 Purified Helium 1,100 lbs Stings Filter 14.18 cach C-2301,lS Puri fied Helium Slings Compressor IA,lB ij Removable Stabs (8)

I ton each Slings

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D' TABli 2.l.3-1 (Cont'd)

C-20 C-1601 Hot Service Facility Hoist 5 Tons 4864'-0" Reactor Building LIFTING RIC/

IDAD ID DESCRll410N IDAD DEVICE PROCEDURE C00 STENTS C-2101 to Helium Circulator Parts varies Slings t

MP21-15 C-2104 Control Rod and Orificing 4900 lbs Stings MPl2-6 Assembly C-23 C-7503 Conde % ate Pumps Electric Hoist and Trolley 5 Tons 4791'-0" Turbine Building P-3104 Condensate Pump IA Pump Casing 10,100 lbs assembled weight.

Motor 6400 lbs Slings Disassembled weight of components is less than 10,000 lbs P-3105 Condensate Pump 18 Motor 6400 the Slings Pump Casing 10,l00 lbs assembled weight.

Disassembled weight of components is less than 10,000 lbs Mo P-3106 Condensate Pump IC 3300 lbs Stings S

Motor 1180 lbs Slings to u

d P-3106S Condensate Pump ID 3300 lbs Stings 4

N Motor 1180 lbs Stings 3

C-28 C-7213 Reactor Plant Air Handling Equipment Electric Paist and Trolley 2 Tons 4885'-0" Turbine Building i

S-7301, 15 Compressor 3600 lbs each Slings Evaporator IA 3250 lbs Slings C-29 Circulating Water Pump Electric Hoist and Trolley 5 Tons 4788'-0" Outdoors 3

P-4101,2, Pump Upper Casing 8,820 lbs each Stings Rotor 5,200 lbs each Stings P-4103,4 Pump 4,500 lbs each Stings Motor 2,085 lbs each Stings Base plate 1,300 lbs each Stings C-30 C-7203 PCRV Safety Valve Tank Head Trolley 8 Tons 4816'-0" Reactor Building T-1201 PCRV Safety Valve Tank Cover 13,200 lbs Chains

i Fort St. Vrain OV 2.1.3 d)

Lifting Rigs / Devices Verification that lifting devices identified in 2.1.3c, above, comply with the requirements of ANSI N14.6-1978, or ANSI B30.9-1971 as appropriate.

For lifting devices where these standards, as supplemented by NUREG-0612, Section 5.1.1(4) or 5.1.1(5), are not met, describe any proposed alternatives and demonstrate their equiva-1ency in terms of loadhandling reliability.

RE SPONSE With regard to special lif ting devices, there are four identified in Response 2.1.3c that are used to handle heavy loads.

These special lifting devices are listed in Table 2.1.3-2.

i ANSI N14.6-1978 was written for special lifting devices for shipping containers for nuclear materials.

The devices described above were designed and fabricated prior to a decision by the NRC to apply this standard to other types of special lifting devices.

Accordingly, ANSI N14.6-1978 was not specifically applied in the design and fabrication of these devices.

The detailed comparison of the devices to ANSI N14.6 was limited to Sections 3.2.1 and 5 of the standard.

ANSI N14.6 - Section 3.2.1 Section 3.2 of ANSI N14.6-1978 establishes design criteria for special lifting devices.

Generally, special lifting devices r'

satisfy the guidelines of ANSI N14.6-1978, as shown in Table 2.1.3-2.

l 2-23

Fort St. Vrain The calculations are based on the published minimum vield strength and published minimum ultimate strength.

Beam 158D979, which is used for lifting the generatot and turbine rotors, is the only special lifting device that does not comply with ANSI N14.6-1978.

A modification is planned to bring this lif ting beam into com-pliance with the above requirements.

ANSI N14.6 - Section 5 ANSI N14.6-1978 is intended to cover lifting rigs that are used on a frequent basis (potentially 50 to 100 times in a year),

and such lifting rigs would be subjected to potential abuse in transportat-ion between sites as well as harsh environments during transportation.

The lifting devices identified above for Fort St. Vrain are typically used less frequently than the lifting rigs for which ANSI N14.6-1976 was intended.

A program for inspection, testing, and maintenance of the devices will be incorporated in load handling procedures that meets the provisions of ANSI N14.6-1978, Section 5 with some exceptions based on the low frequency at which these devices are used.

To ensure against improper use, the special lifting devices will 3

be used only in the controlled environment of the reactor and l

2-24 f

Fort St. Vrain

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turbine buildings.

Procedures will exclude their use with any loads other than those intended, except for special test loads as required.

I ANSI B30.9-1971 - Slings With respect to lifting devices not specially designed (i.e.,

slings),"the criteria of ANSI B30.9 apply.

Therefore, to assure i

that slings are appropriately used and maintained, load handling 4

)

procedures are being developed which will require:

a.

The use of ANSI B30.9 and NUREG-0612 Section 5.1.l(5) criteria for sling selection and rigging techniques; 1

b.

A preventive maintenance procedure specifying periodic inspec-tions of slings; 2

a c.

A visual inspection of slings for damage prior to caking a lift; 4

d.

A preventive maintenance procedure that includes tagging requirements to identify:

sling rating, applicetion, last eximination, and expiration date of examination; and e.

Sling selection, use, and marking will be based on rated l

loads which include the sum of both maximum static and dynamic t

loads.

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Table 2.1.3-3 lists lifting devices used for the reactor building t

refueling floor, and the turbine building operating floor cranes.

f 2-25 i

Fort St. Vrain Generally, these lif ting devices comply with ANSI B30.9-1971 standards, except for the following loads with their weight:

1 HP outer casing (57.4 tons) j-r LP inner casing (33.7 tons)

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LP rotor (49.3 tons)

Crossover pipe (15.4 tons) i 1

PSC is planning modifications to bring these lifting devices into compliance with the requirements of ANSI B30.9-1971.

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Fort S t. Vrain TABLE 2.1.3-2 SPECIAL LIFTING DEVICES SAFETY FACTORS MEET ANSI N14.6-1978 AND NUREG-0612 SECTION 5.1.1 ( 4 )

Cradle for Lifting Yes Helium Circulator (15 tons)

Beam for Lifting Yes Helium Circulator (15 tons)

Shipping Cask Lifting Yes Apparatus (23 tons)

Beam 158D979 for Lifting No Turbine LP Rotor (49.3 tons)

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Fort S t. Vrain i

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TABLE 2.1.3-3 LIFTING DEVICES A.

REACTOR BUILDING REFUELING FLOOR CRANE SAFETY FACTOR MEETS ANSI B30.9-1971 AND l

LIFTING NUREG-0612, ITEM DEVICE SECTION 5.1.1. (5) 1)

HSF Removable Slab Wire Rope Yes (35 tons) 2)

Regeneration Pit Wire Rope Yes Removable Slabs (34 tons, 17 tons, 17 tons) 3)

Isolation Valve Wire Rope Yes (15 tons each) H-1302, H-1303, H-1402 4)

Shielding Adapter Wire Rope Yes (10 tons) H-1605

()

5)

Helium _ Circulator, Wire Rope Yes Isolation Valve, Shield Cask, and Pipe Container (All Together, 40 tons) T-2101 B.

TURBINE BUILDING OPERATING FLOOR C9ANE 1)

HP Outer Casing Wire Rope No (57.4 tons) 2)

1. 1 HP Inner Shell (21 tons)

Wire Rope Yes 3)

LP Hood, Upper End Wire Rope Yes (15.2 tons) 4)

LP Inner Casing Wire Rope No (33.7 tons) 5)

LP Upper Inner Wire Rope Yes Shell (9.1 tons) 6)

Turbine Rotor-HP (22.5 tons)

Wire Rope Yes 7)

Turbine Rotor-LP Wire Rope No (49.3 tons) 8)

Crossover Pipe Wire Rope No (15.4 tons) 2-28

Fcrt Ft. Vrain O

2.1.3 e)

Crane Inspection, Testino, and Maintenance verification that ANSI B30.2-1976, Chapter 2-2, has been invoked with respect to crane inspec-tion, testing, and maintenance.

Where any exception is taken to this standard, sufficient information should be provided to demonstrate the equivalency of proposed alternatives.

RE SPONSE The inspection, testing, and maintenance of overhead bridge cranes at Fort St. Vrain Nuclear Generating Station (FSV) generally comply with Chapter 2-2 of ANSI B30.2-1976.

FSV Procedures MP-104-1, MP-104-2, and MP-104-5 through MP-104-9

}

provide the guidelines and J

eptance criteria for the annual, semiannual, monthly, and daily operational maintenance, inspection, and testing for the reactor building overhead crane and the turbine building overhead crane.

FSV procedure MP-104-12 provides the guidelines for preoperation inspection and oper-ation of the reactor building truck bay crane, G-7215, l

in accordance with ANSI B30.2-1976.

l These procedures were written using ANSI B30.2-1976 and manufacturers' Overhead Crane Manual guidelines.

PSC will develop procedures to inspect and maintain monorails and hoists.

IlO 2-29 i

Fort St. Vrain

/%

U 2.1.3 f)

Crane Design Verification that crane design complies with the guide-lines of CMAA Specification 70 and Chapter 2-1 of ANSI B30.2-1976, including the demonstration of equivalency of actual design requirements for instances where specific compliance with these standards is not provided.

RESPONSE

The turbine building overhead 65/15 ton crane meets CMAA 70 speci-fications and ANSI B30.2-1976 design standards for Class A service, as determined by Whiting Corporation in their report of April 18, 1985, except for the following instances:

1.

The girder web stiffener is not located per CMAA specification; and

()

2.

The_ moment of inertia of the girder web stiffener is less than required by CMAA 70.

Although these specific CMAA 70 criteria are not met, the girder 1

I has been reviewed assuming no longitudinal stiffener and the factor of safety against buckling of the girder web due to the SSE load is 1.46.

Alternately, using the tension field action l

l l

provisions of AISC the factor of safety is 5.4.

An adequate factor of safety against buckling exists; thus, the design of i

l the turbine building crane girder is considered acceptable.

2-30

Fort St. Vrain O

The reactor building overhead 170/50/17.5 ton crane meets ANSI B30.2-1976 and was reviewed for conformance with CMAA 70 speci-fications as indicated in PSC's letter to the'NRC dated December 14, 1981.

The trolley beams and supports of the following overhead handling systems were evaluated based on as-built measurements and found to meet ANSI B30.11-1980, Section 11.1.3.2.

C4 Bearing Water Pumps Monorail C6 Bearing Water Pumps Monorail Cl2 Bearing Water Makeup Pump Monorail C13 Waste Filters and Demineralizer Tanks Monorail-i C16 )

C17 )

Helium Purification Equipment Monorails l

C18 )

C23 Condensate Pumps Monorail C28 Reactor Plant Air Handling Equipment Monorail C29 Circulating Water Pumps Monorail C30 PCRV Safety Valve Tank Head Monorail The Hot Service Facility Hoist Monorail (C20) was not evaluated because it was not possible to obtain as built measurements due to contamination of the hot service facility.

However, in Phase II, load drop analyses were performed for the hot service facility j

hoist and the consequences were determined to be acceptable.

l l

2-31

i Fort St. Vrain O

2.1.3 g)

Crane Operator Training, Qualifications, and Conduct Exceptions if any, taken to ANSI B30.2-1976 vith respect to operator training, qualification, and co. duct.

RE SPONSE Fort St. Vrain Nuclear Generating Station requirements for crane operator training, qualifications, and conduct generally comply with Chapter 2-3 of ANSI B30.2-1976.

Station procedure MP-104 provides overhead crane operator training qualifications guidelines.

The crane operator training / qualification program requires medical examination verification and oral and written examination on crane operation, as described in Station

()

Procedures MP-104A and MP-104B.

PSC will develop appropriate procedures for operator training and qual 5fication for the hoists in Table 2.1.3-1.

I i

O i

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