ML20004G074
| ML20004G074 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/23/1981 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612 TAC-07972, TAC-7972, NUDOCS 8106290119 | |
| Download: ML20004G074 (25) | |
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'Af M um 4se-cooo 435 Siam Avenue I"$"#' June 23, 1981 Director of Nuclear Reactor Regulation /I . g. -
United States Nuclear Regulatory Commission g/ ..
/[ ff Attn: Mr. Steven A. Varga, Chief C Operating Reactors Branch No. 1 ,2 &
Division of Licensing
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' Washington, DC 20555 "'8. kl,,Og [g/
- s Refereace: Beaver Valley Power Station, Unit No. 1 ^ &x ,
Docket No. 50-334 / g f ; ,9 \" Control of Heavy Loads - NUREG-0612 Car.tlemen: Attached for your review are the itemized responses for Section 2.1 as requested by your letter dated Dece.nber 22, 1980. We wish to point out that the safe load paths defined to date have not taken into account any analysis which are being performed on the integrity of the structures to withstand load drops. We have assumed for the initial response, that a dropped load penetrates one floor elevation. The safe load pachs may be revised f n the second required submittal of information to take into account further information in this area. We will proceed wit.h implementation of any required changes or modifications deemei necessary as a result of the reviews being performed. At this time, we expect to complete the changes within the two years specified in your letter. Very truly yours, J. . Carey Vice President, Nuclear cc: Mr. D. A. Beckman, Resident Inspector U.S. Nuclear Regulatory Commission Beaver Valley Power Station Q33 Shippingport, PA 15077 f
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U.S. Nuclear Regulatory Commission c/o Document Management Branch
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Washington, DC 20555
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JP I 8106290_( @ , -
y. DUQUESNE LIGHT COMDANY Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Control of Heavy Loads - NUREG-0612 Attachment A
.2.1.1 Report the results of your review of. plant arrangements to identify all overhead handling systems from which a load drop may result in damage to any system required for plant shutdown 7
-or decay heat removal (taking no credit for any interlocks, technical specifications, operating procedures or detailed -
structural analysis). RESPONSE APPLICABLE OVERHEAD LOAD HANDLING SYSTEMS
' Mark No. Identification- Location CR-1 Polar Crane Reactor Containment CR-9 7.5 Ton Monorail System Auxiliary Building CR-15 Fuel Cask Crane Fuol Building CR-17 Screenwell Crane Intake Structure CR-19 PCA Shop Crane Service Building CR-20 10 Ton Monorail System Auxiliary Building CR-21 6 Ton Monotail System Auxiliary Building CR-23 10 Ton Monorail System Auxiliary Building CR-24A&B 6 Ton Monorail System Auxiliary Building-CR-27 Moveable Platform & Hoists Fuel Building 2.1.2 Justify the exclusion of any overhead handling system from the above category by verifying that there is sufficient physical separation from any load-impact point and any safety-related component to permit a determination by inspection that no heavy load drop can result in damage to any system or component required for plant shutdown or decay heat ramoval.
RESPONSE NONAPFLICABLE OVERHEAD LOAD HANDLING SYSTEMS
, Mark No. Identification and Reason CR-2 Turbine room crane - This crane is located inside the turbine building which does not contain any safety related equipment or systems.
Therefore, a load drop from this crane would not result in damage to any system required for plant shutdown or decay heat removal. CR-5 Refueling Manipulator Crane - This crane is located inside the Reactor Conrainment. The maximum load this crane will lift is a fuel element with its handling tool. This by definition (NUREG-0612) is not classified as a " heavy load". A load drop associated with this crane was addressed in a detsiled study entitled
" Fuel Handling Accident Evaluation" dated October'31, 1977.
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Beaver Valley Power Station, Unit No. 1
-Controi of Heavy Loads - NUREG-0612 Attachr.ent A Page 2
'CR-8 Solid Waste Handling Crane - This crane is located inside the Solid Waste Building which does not contain any safety related equipment or systems. Therefore, a load drop from this crane would not result in damage to any system required for plant shutdown or decay heat 7 removal.
CR*;6 Neutron Detector Carriage - This crane is located inside the Reactor Containment and is not used to lift any " heavy loads" as defined in NUREG-0612. CR-18 Clean Shop crane - This crane is located in the Service Bui' ding in an area where a load drop would not result in damage to any system required for plant shutdown or decay heat removal. CR-22 7.5 Ton Monorail Holst - This crane is located inside the Auxiliary Building and is used for the gaseous waste and primarf drains transfer systems. A load drop from this crane would not result in damage to any system required for plant shutdown or decay heat removal.
.CR-25 10 Ton Monorail Holst - This crane is used for the Boron Recovery system in the Auxiliary Building and does not operate in an area where a load drop could result in damages to any system required for plant shutdown or decay heat removal.
2.1.3.a Drawings or sketches sufficient to clearly identify the location of safe load paths, spent fuel and safety-related equipment. RESPONSE Safe load travel paths hava been defined which will minimize adverse effects of a load drop for those handling systems identified in Table 1. These safe load paths are shown in Figures 2 through 5. There is no figure to show a safe load path for CR-19 because it is used to handle equipment throughout the PCA shop and there is no preferential load path. Thus, the safe load path is the entire area accessible by the crane. Figures lA and IB are plan views of the containment structure (Elevations 767' 10" and 738' 10") showing locations of various safety related equipment, piping and systems required for plant shutdown or decay heat removal, as well as various heavy loads. These figures may be used in conjunction with written procedures to define safe load psths for any undefined heavy load movement inside the containment. Figures 2A through F show the safe load path for all heavy loads which have been-determined for the polar crane (CR-1). E
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' Beaver Valley Power Station, Unit Nc. 1
. Control of Heavy Loads.- NUREG-0612 Attachment A Page 3 Figures 2A, B and C depict the safe load paths for the dismantling and laydown necessary.for Refueling Operations. Figure 2A shows the safe load path.for the installation of the removable slabs (Item Nc. 6) from'their storage locations abovs the RV head storage stand (Item No. 5) including the temporary remcval.
and replacement of the manipuistor crane rail and grating 7 (from area by Item No. 5 to Item No. 16). Figure 2B shows the ' safe load path for the sevement of the CRDM ventilation ring - duct (Itum No. 15) and the CRDM shield (Item No. 5) to the removal of the RV internals lifting rig tripod (Item No. ' 5) from its storage position to its temporary position south of steam gen.rator RC-E-1C. 4 The tripod is then moved into position over the core and then with the RV internals placed back in the storage stand. Also shown on Figure 2C is the movement of the RV head, lower internals (Item No. 14) and stud tensionec handling frame (Item No. 15). Figures 2D, E and F depict varicus other heavy loads located within the containment which could possibly be lifted by the polar crane (CR-1) and their safe load paths. Figure 2D shows the path to be used for reactor coolant pump (s) removal. Figure 2E shows removal path for the containment recirculation g spray coolers and residual heat removal heat exchangers. Figure 2F shows the location of various heavy loads (Elevation 738' 1G") to be lifted by CR-1. Figures 3, 4 and 5 are plan views of the fuel and decontamination building, intake structure and auxiliary building showing the location of safety related equipment an.d piping and safe load paths used when handling heavy loads within these structures. 2.1.3.b 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 Maintenance administrative procedures are being revised to - include the general guidance and evaluation requirements contained in NURIG-0612. Implementing procedures will require compliance with NUREG-0612 using the load paths defined in the attached figures. Deviation from these procedures requires field changes which are' reviewed and approved in accordance l with existing administrative procedures.
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t Beaver Valley Power Station, Unit No. 1 . 1
. Control of Heavy Loads - NUREG-0612 Attachment A Page 4 2.1.3.c A tabulation of heavy-loads to be handled by each crane which includes thr load identification, load weight, its designated lifting device and verification that _the handling of such loadLis. governed by a written procedure containing, as a cinimum, the information identified in NUREG-0612, Section 5.1.1(2). ,
RESPONSE -The attached Table 1 which is consistent with the loads identified in Table 3-1 of NUREG-0612 provides this information. - Existing maintenance procedures generally follow the guidance of NUREG-0612. Trigger statements will be added to existing procedures requiring an evaluation to the requirements of NUREG-0612 before making the lift. New procedures generated .i will incorporate the guidance of NUREG-0612. 1.1.3.d Verification that lifting devices identifed in 2.1.3-c, 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 equivalency in terms of load-handling reliability. RESPONSE The designs of the head lifting device and the internals lifting rig were reviewed with respect to the above listed criteria. These criteria were not available at the time the devices were designed and the lifting devices were built to the current industrial standards using good engineering practices. Additionally, the following specific items were found to either
- comply or substantially comply with the new criteria. They were designed to lift five times the weight of the designed load without exceeding the ultimate strength of the material.
They were welded according to Section IX of the ASME code, and they were load tested to 125% of the design lift load weight. 2.1.3.e Verification that ANSI B30.2-1976, Chapter 2-2, has been invoked with respect to crane inspection, testing and maintenance. Where any exception is taken to this standard, sufficient information should be provided to demonstrate the equivaler.cy of proposed alternatives. RESPONSE Preventative maintenance procedures are being reviewed for compliance to ANSI B30.2-1976 and will be revised as necessary. Contractors are presently used to perform crane inspections and testing. Purchase orders will be revised to require inspectors to be qualified and inspections conducted'in accordance with ANSI B30.2-1976. 8 8
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B2 aver Vallcy Pov:r St: tion, Unit No. 1 Control of Hesvy Loads - NUREG-0612 Attachment A
.Page 5 2.1.3.f Verification that crene design complies with the guideline of CMAA Specification 70 and Chapter 2-1 of ANSI B30.2-1976, including the demonstration of equivalency of actual design l' requirements for instances where specific compliance with these standards is not provided.
RESPONSE CMAA Specification 70 and ANSI B30.2-1976 apply to cranes CR-1, 13, 17, 19 and 27. ' Cranes CR-15 and CR-27 have been designed , to comply with CMAA 70. Cranes CR-1, CR-17 and CR-19 were designed to comply with EOCI Specification 61 which was superceeded by CMAA 70. The
. differences between these two-specifications which impact the evaluation of the safe handling of heavy loads are addressed below with respect to the significant cranes.
a) CMAA 70 requires the hoist rope safety factor be calculated oa the combined weight of the bottom block assembly and the rated load. This requirement is met by all of the above listed cranes except CR-19 which will be administratively limited to a 13.9 ton load to meet this safety requirement while the remainder of this study is in progress, b) CMAA 70 requires ASTM-A36 structual steel; all of the above cranes are built of this material. c) Though the specification requirements differ, the stress requirements of CMAA 70 for bridge girders, end trucks' and trolly frames are met by the cranes. ANSI B30.2-1976 adds the additional requirement applicable to safe heavy load handling that crane hooks have latches if practical in that application. This requirement is met by the above listed cranes. 2.1.3.g Exceptions, if any, taken to ANSI B30.2-1976 with respect to operator training, qualification and conduct. RESPONS,E Training is in accordance with ANSI B30.2-1976. 1
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FIGURE: 3A
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$Q _ teu FIGURE: SC nl p PL AN EL 735'- 6 BEAVER VALLEY POWER STATION - UNIT 1 t
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- CONTROL OF HEAVY LOADS l AUXILIARY BUILDING EL 735'-6* [
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. TABLB 1 .
IIEAVY LOADS . Load Crane capacity Weight - Mark No. (Tons) Heavy Load Identification (Tons) Lifting Device CR-1 Bridge-200 Tons Reactor Vessel llead & Attachments 117.3* Vessel Head Lifting Device Trolley No. 1-130/15 Tons Trolley No. 2-130 Reactor Vessel Internals Packsje 64.8* Internal Lif ting Rig Reactor Core Barrel Assembly 124 Reactor Coolant Pump - Motor 41.1 RCP-Motor Handling Fixture l<eactor Vessel Seal Ring- .5 4 segments (each) Recirculation Spray Coolers 7.4 Recirculation Spray Pump Motor 1.2 CRDM Missle Shield 38.6 Ventilation Supply Ducting (To CRDM) 3.0 Ventilation Ring Duct (To CRDM) 5.0 Ventilation Fans 3.1 Stud Carriers (Full) 3.8 Residual lleat Removal Exchanger 12.5 Residual lleat Removal Pump-Motor 1.5 Regenerative lieat Exchangers 3.1 - Polar Cranes-Bottom Block & Ilook '5. 4 , e~~ .- *e
- 1. -
't TABLE I
- IIEAVI LOADS ,
Load Crane Capacity weight Mark No. (Tons) lleavy Ioad Identification (Tons) Lifting Device R. C. Operating Floor Ren.ovable 14.9 Plugs (20)- Heaviest Plug CR-9 7 1/2 Tons lias no Specified Imads CR-15 125 Tons Spent Fuel Shipping Cask 21.5 CR-17 15 Tons River Water Pumps 6.5 River Water Motc s 2.7 Raw Water Pumps 9.3 itaw Water Motors 3.8 1 Elect. Fire Pump 3.0 Elect. Fire Pump Motor 2.0 i Diesel Fire Pump 3.0 Diesel Engine 1.9 Ilydro-Pneumatic Tank 1.2 Removable Covers (largest) 4.3 Unit 2 Serv. Water Pumps & Motors 13.8 Traveling Water Screens (heaviest 10.4 sect.) Stoplogs 10
TABLE 1 iiEAVY LOACS . Ioad Crane Capacity Weight Mark No. (Tons) lleavy Ioad Identification (Tons) Lifting Dcvice CR-19 15 Tons Itas no specified loads CR-20 10 Tons Charging Pumps - Pump 3.8 Charging Pumpa - Motor 2.0 cubicle Covers (largest) 5 CR-21 6 Tons Component Cooling Water Pump 1.5 Component Cooling Water Motor 1.7 CR-23 in Tons Seal Water lleat Exchanger 1.1 Fon Regener.=tive Heat Exchanger 4.3 1 Deborating Demineralizer 1.0 Cesium Removal Ion Exchanger 1.0 Fuel Pool Ion Exchanger 1.0-Removable Covers (largest) 8.5 CR-24A 6 Tons Each Removable Covers 3.0 24B CR-27 5 Tons Each New Fuel Shipping Containir.ent 2.5 (fully loaded) Failed Fuel Assy Storage Can (Full) 1.5 NOTE: Where no lifting device is listed, there is no specific lifting device for this item.
- Indicates Lifting Device weight included
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_ . _ _ _ _ _ _}}