ML19344A921
| ML19344A921 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 08/04/1978 |
| From: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| To: | Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19344A919 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR TAC-07716, TAC-7716, NUDOCS 8008220590 | |
| Download: ML19344A921 (30) | |
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August 4, 1978 e
Victor Stello, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation United States Nuclear Regulatory Comission Washington, D. C. 20555
Dear Sir:
Enclosed is the Portland General Electric Company's response to your request for information dated May 17, 1978, regarding the control of heavy loads near spent fuel.
Sincerely, jf
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C. Goodwin, Jr.
Assistant Vice President Thermal Plant Operation and Maintenance CG/WSO:n Enclosures c:
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ENCLOSURE Response to Question No. 1 A diagram illustrating the physical relationship between the reactor core, the fuel transfer canal, the spent fuel storage pool, and the setdown, receiving, and storage areas for heavy loads moved on the refueling floor is enclosed as.
RysponsetoQuestionNo. 2 t
Spent fuel and fuel handling tools are handled on a normal periodic basis in or over the spent fuel pool by the spent fuel bridge crane.
Infrequently, the mechanical stops may be removed from the Fuel Building bridge crane rails to allow use of the Fuel Building crane to transport items such as fuel transfer canal equipment over or around the pool.
Table 1 shows items which may be carried over the reactor core during refueling. Table 2 shows items which may be carried over or in the pool.
Table 3 shows items which may be carried within ten feet of the pool.
Response to Question No. 3 The type of spent fuel casks that could be used at Trojan are the NLI-1/2 truck cask and the NLI-10/24 rail cask. The NLI-10/24 cask is 204-1/2 inches long by 96 inches in OD and has an unloaded weight of approximately 160,000 pounds.
The NLI-1/2 cask is 195-1/4 inches long by 41-1/8 inches in OD and has an unloaded weight of approximately 46,000 pounds.
Response to Question Nos. 4 and 6 To the best of our knowledge, no analyses for the dropping of heavy loads such as the spent fuel cask directly into the spent fuel pool have been performed.
The drop of the heaviest load to be carried by the Fuel Building i
crane from the maximum height to which it can be carried is discussed in the l
FSAR, Page 9.1-5.
The fuel pool is designed so that the impact of this load onto the operating floor or into the cask loading pit would not cause leakage l
which would uncover the fuel.
Response to Question No. 5 This question is not applicable to the Trojan Nuclear Plant since there is no equipment required for safe shutdown of the plant over which heavy loads will be moved near the spent fuel storage pool, and which is required to operate during the time such fuel is moved.
Response to Question No. 7 The' capacity of the spent fuel bridge crane which operates over the pool is about 2000 pounds. Heavy loads (such as the fuel cask) are handled by the Fuel' Building bridge crane. Mechanical stops are provided on the Fuel Building bridge crane rails.
They consist of welded steel plates bolted to the crane rail girder.
The crane has energy absorbing bumpers along with limit switches which cut off power to the trolley so that the crane does not hit the stops while under power.
The stops are placed so that the Fuel Building bridge crane hook can be placed no closer than six feet from the edge of the pool. As shown on~the attached diagram of the fuel cask =ovement envelcpe,
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i' Page Two ENCLOSURE the cask would be carried no closer to the pool than about 8'-6" and then only over the cask loading pit.
This reduces the probability of the cask tipping into the pool if dropped onto the Fuel Building operating floor.
The Fuel Building bridge crane hoist has dual independent brakes which are automatically applied on loss of power.
In order for the fuel cask to be dropped into the spent fuel pool, three independent concurrent events would have to occur.
The three failures are:
1.
Limit switches and mechanical stops must fail.
2.
A mechanical device of the crane must fail, e.g., the crane hook.
3.
Administrative procedure control must be violated.
)
Heavy equipment that is moved through the Containment equipment hatch will be transported along a set of rails that run parallel to the hatch center-line. The nearest rail is.ll feet from the spent fuel pool at its closest point. The probability of a heavy object entering the pool during movements through the equipment hatch is very low due to this distance together with the normal industrial precautions that are taken when handling heavy loads.
Response to Question No. 8 The fuel handling procedures contained in the Trojan Plant Operating Manual for the movement of heavy loads over the reactor core during refueling and the spent fuel storage pool are enclosed as Attachment 2.
Response to Question No. 9 The Portland General Electric Company has taken no exceptions to the provisions specified in Regulatory Guide 1.13, Revision 1, and has implemented the Guide at the Trojan Nuclear Plant by including the specified requirements in design criteria and design analysis.
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TABLE 1 ITEMS WHICil MAY BE CARRIED OVER Tile REACTOR CORE DURING REFUELING a..
Item Item Drop Ileight No.
Description Crane Used Weight (Pounds)
(Feet)
Length (Feet) llandling Frequency L.
Upper Internals Load Polar Replace Internals 27 14'x14'x30' 1/ year 256,000 pounds Pick Up Internals 14,500 pounds 2.
Inservice Inspection Tool Polar 9,000 pounds 27 14'x30' 1/40 month 3.
Irradiation Specimen Tool Polar 250 pounds 15 47' 1/10 year and. Capsule 4.
Core TV Mapping Fixture Manipulator 100 pounds 13 4'
1/ year l
5.
Fuel Assembly Manipulator
',750 pounds 14 13' 350/ year
IABLE 2 Page 1 of 2 Items Which May Be Carried Over or In the Spent Fuel Pool Max. Drop Approx.
Item Weight Length Height to Handling Item No.
Description Crane Used (lbs)
(ft)
Top of Racks (ft)
Frequency 1
Spent Fuel Assembly SF 1620 14 1
100/yr 2
Spent Fuel Assembly SF 356 33 14 350/yr Handling Tool 3
Spent Fuel Assembly SF 1976 46 1
100/yr with Handling Tool 4
Burnable Poison SF 800 33 12 100 - 1st yr Rod Assembly 65 - 2nd yr Handling Tool 5
Rod Cluster SF 290 29 16 Less than Control Assembly 65/yr Plug Tool 6
Fuel Assembly FB 500 4P, 1/yr-3 yr Channel Spacing-1/10 yr Tool 7
Rod Cluster SF 1200 12 65 Concrol Change Tool 8
Radiation Specimen SF 600 1
1/yr-3 yr Transfer Basket 1/10 yr Fuel Transfer Equipment Parts:
9 Spent Fuel Pit FB 700 17 48 1/10 yr Span 10 Lifting Arm FB 650 15 48 1/10 yr 11 Car Conveyor FB 600 15 48 1/10 yr 12 Fuel Container FB 600 14 48 1/10 yr 13 Chain Support FB 300 15 48 1/10 yr Stand 14 Fush Arm FB 350 17 48 1/10 yr 15 Spent Side Stand FB 150 4
48 1/10 yr
TABLE 2 Page 2 of 2 Items Which May Be Carried Over or In the Spent Fuel Pool Max. Drop Approx Item Weight Length Height to Eandling Description Crane Used Mbs)
(fc)
Too of Racks (ft)
Frecuency It n No.
New Fuel Elevator Parts:
16 Elevator Assembly FB 660 14 48 1/10 yr 17 Track FB 450 38 48 1/10 yr 18 Bracket FB 125 2
48 1/10 yr Miscellaneous:
19 Underwater Light FB 100 30 26 1/yr Poles jr/1.lA3
e IABLE 3 Items Which May Be Handled Within 10 Ft of the Edge of the Spent Fuel Pool Max Drop Height to Closesi Approx.
Item Weight Length Top of Dist.
Handling Itom No.
Des criptic ',
Crane Used (1bs)
(ft)
Racks (ft) To Pool Frequency A
New Fuel Assembly SF 1620 14 25 3
65/yr B
New Fuel Assechly SF 85 25 3
65/yr Handle Tool C
New Fuel Assembly SF 1705 25 3
65/yr with Handling Tool D
Spent Fuel Shipping FB 200,000 25 6
20/yr Cask E
Radiation Specimen FB 7,000 25 6
1 @ 1, 10 Shipping Cask
& 15 yr F
Rod Cluster Control SF 170 25 3
31/yr Assembly G
Fuel Inspection FB 2000 25 5
1 9 1, 10 Stand
& 15 yr H
New Fuel Shipping FB 8000 25 6
1/yr Containers (Full)
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e a._ e * " l l l pe _.__6- __4' i p > AN a? ri.e a'.. f .u-i i ?.s us.a seems ma amavam u'.e4 amsws *s suLsene ca 9a FIGURE 6.1-10 PLANT AR8tMCEut'eT 01ACAAas 08' t.as's :P suiL lumonwt Je uns &s.6::im p 'is P-m - FVEL CA$K WOVEk(NT ENVf Ll718 Amendment 5 (October 1973) l L ' --- --_ C ~_u .u- _n _m NITACHMENT 2 PORTLAND GENERAL ELECTRIC COMPANY g ~~ TROJAN NU t .11 A.. -] Hay 9,19W N O T' ^~ SAFETY-REl.AT D Revision 6 e FUEL !!ANDLING PROCEDURE FHP-1 SITE RE10 VAL OF NEW FUEL ASSEMBLIES FROM SHIPPING CONTAINERS, FUEL INSPECTIONS, AND IIANDLING OF SHIPPING CONTAINERS a APPROVED BY M DATE /o[78 / j PURPOSE This procedure establishes guidelines for site removal of new fuel assemblies from shipping containers and initial receipt inspection of new fuel assemblies. I. REFERENCES A. ~ Documents and Manuals 1. FHP-14, Limitations and Precautions for Handling Fuel Elements. 2. FHP-11, Special Nuclear Material Safeguards and Accountability. 3. PHP-13, Fuel Handling Emergency Procedures. - 4. Radiation Protection Manual, Volume 10, Pla.tt Operating Manual. l S. FHP-S-4, Transfer of Fuel Assemblies. B. Enclosures Form FH-1, Fuel Receiving Record. II. PRECAtTTIONS A. Observe the precautions and limit /1tions of Reference A.I. B. Care must be exercised in liftig and moving the shipping container at all times. The container shall be moved at a slow speed, kept as level as possible, and not permitted to contact barriers of any kind. C. The new fuel room should he cleaned before new fuel storage and rack bottom locations checked to be free of obstructions. O FHP-1 Page 1 of 13 Revision 6 D. A fuel assembly may only be lifted when it is in the vertical position. V] / Iforizontal handling of a fuel assembly is prohibited except as speci-fled in Reference A.1. E. After fuel assemblies and core components are removed from their shipping container for site storage, precautions must be taken with respect to cleanliness and atmosphere control to assure that the assemblies are maintained in the same condition as they were when they were shipped. If a polyethylene wrapper is enclosed and must be removed, it should be stored in a clean place. Clean cotton or rubber gloves shall then be worn by personnel handling the assemblies. If any subsequent cleaning is required, use clean, acetone-dampened, lint-free cloths, followed with demineralized water wipe. l F. Keep the shipping container base in a level position throughout the unloading operation. G. The fuel building bridge crane, the spent faal bridge crane, and new l fuel handling tool have been demonstrated to be operable. H. Prior to fuel unloading and transfer, Form R-T1 Fuel Transfer Authori-zation, and Form R-T3, Fuel Transfer Record must be prepared in accordance with Reference A.2. I. Instructions and precautions established in the Radiation Protection manual and Reference I.A.4 concerning the receipt of new fuel shall be followed. \\ Radiation Work Permit shall be issued to cover the O' fuel receipt work. It should require cotton gloves to be used when touching the fuel directly. J. When installing fuc1 into the New Fuel Storage Pit, a rope barrier should be erected around the hole for personnel safety when pit is unattended. Avoid transferring new fuel (or other heavy loads) over irradiated fuel. l K. III. SPECIAL EQUIP?EhT A. 1/2" drive socket set with deep sockets, small adjustable wrench, 7/16" and 3/4" combination box /open end wrenches. B. A 2500 lb. spring scale. C. A four legged steel sling equipped with shackles with a rated capacity exceeding 7,000 pounds. D. New fuel handling tool and short sling (nylon or steel). E. Radiation monitoring equipment as specified 'by the Radiation Protec-l tion Supervisor, F. A movable scaffold assembly with a work platform at 10-feet should be p( constructed, s FHP Page 2 of 13 Revision 6 l IV. INSTRUCTIONS A. When the new fuel shipment arrives, make a preliminary container inspection and provide the information specified on form FH-1, Fuel Receiving Record, concerni.ng container indentification (Operations group representative) and radiation levels (Operations group or Radiation Protection representative). Inspect the Westinghouse fuel quality assurance release forms accompanying the shipment. B. Hove the shipping container to the new fuel unloading area using the 7,000 pound rated sling and the fuel building bridge crane. Place it in a stable level position for fuel unloading (the container should be orientated wi:h the valve cover end toward the south and about three feet from the SFP north edge). C. Perform a detailed external inspection of the container and note any dents, scrapes, or abnormalities on form FH-1. D. Remove the two wingnuts and the round cover plate over the air valve on the end of the container. This end will be referred to as the aft-end. Equalize pressure between the container and atmosphere by pressing er removing the air valve stem, and reinsert stem if renoved. Record whether a differential pressure existed on form FH-1. ~ E. Loosen-the fastener hardware between the container shell halves after pressure has equali:ed between the container and atmosphere. If the container is equipped with bolts, simply unfasten. If tne container has 1/4 turn Camloc fasteners, unlock by turning 90 ' CCW with a wrench. 0 Camloc studs should be lifted from their receptacles by hand before raising the containec cover. Break and remove the seals through the container flange.
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s h: Mrn = = - F. Raise the cover to allow room for a radiation detector probe. Press l the gasket seal te its position on the bottcm container half if it has lifted off its: seat. Perform a container internals Radiation Survey and record data on form FH-1 (Radiation Protection or Operations n.. -~-- group representative). When the radiation check is completed saHs Ect'orily, set the cover on wood cribbing. ~ .7 u-.... G. Inspect the inside of the container and supply the information specified in the Container Inspection-Internal Section of form FH-1 and note ary W.ormalities in the Remarks section. 1.f-If.either of the '.two shock overicad acceleratometers (ball and c:< tspring'j are tripped, the assemblies may have received an acceler-ation in excess of design limitations. Report this condition Sc. -to:the Reactor Engineer. -"--'e.c.. T 24.d::.If any. desiccant bags-have ruptured, remove them from the container. li 01..~ Z.
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~ H. Remove the ball lock pin securing the lateral lock tubes at the aft O r. end-of the-shock mount ~ frame.. It:will be necessary tio-lift the - e~ n-FHP-I Page 3'of 13 Revision 6 internals to permit telescoping the lock tubes into their housing. 4 p, This may be accomplished by using the lifting fixtures provided on ~' each pillow block and a double lifting sling. l l I. Concurrent with the outrigger and the lock tube manipulations, the following may take place. I 1. Reove the sling and shackles and then loosen the swing bolt clamps of the shock mount frame and swing the clamps free of the fuel assembly support frame. e l 2. Back the hold down pad screws on the top closure assemblies all the way off. Remove the ball lock pins securing the ton closure assemblies and swing the top closure assemblies open as far as possible. Record the fuel assembly number and the core component number on the fuel receiving records. The top of the components should be inspected visually at this time, with the support frame in the horizontal position. For orientation purposes, the left and right fuel assemblies shall be determined when viewing { ~ the container from the top end. f 3. Break, but do not loosen, each of the clamping bracket nuts except those on the top and bottom brackets. Do not open the clamps at this time. J. Extend'the outrigger ~ membeis located on' the:outside 'of'the container assembly. Lock in place using hardware provided. Adjust the pads @C as' required to obtain-firm contact-with the floor, but do not attempt to level the container with these members. They are only for stabilization. K. After having uncovered the new fuel storage rack intended locations, l attach the crane to the lifting eye at the forward end of the fuel m'ssembly support frame using a steel shack 1'e and short' (approximately six foot) ' sling having a minimum rated capacity of 3000 lbs. l ~ L. Plvbt the support frame slow'ly" to 'the vertical positibn. Coordinate crane movement in the-vertical direction with crane movement in the horizontal in steps small enough to maintain vertical alignment of the cabler
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' r -- ' ~ ~ ' M. While holding support frame 'in the' vertical position, install the l ~ supports and secure. Remove the crane from the lifting eye only when ~ the uprighted support frame 'is secure. Inspect the uncovered portion of the"c~ontainer internals for damage. ~ r - :' "2= N. Expose th'e top' en'd ofthe fuel assembly no::le in preparation for engagement of the new-fuel handling tool. If the exposed components were no't ' examined: earlier, they may be examined att this-time'- or aft'er- --. the assembly is placed in the new fuel storage rack. l.. i.e c & :- -c:.. a.u.- ;c e :.. r: ef ti.c r' M. :.' ' n : e: c.---- H.:~ 4 FilP-1 Page 4 of 13 Revision 6 T'
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,c----- i 0. Assemble the new fuel handling tool and the lifting sling onto the I y' spent fuel crane hook, and position the tool above the exposed fuel i assembly nozzle. Note that the bridge must be driven north until j almost contacting the outrigger 45 support brace. P. Guide the new fuel handling tool into the exposed nozzle. When the tool is locked in position, take up the slack in the lifting cable. Do not lift excessively. l i' Q. Maintaining a taut cable on the assembly, finish loosening and swing open all but the top and bottom clamping frames. 4 R. I.oosen and open the bottom clamping frame, and then loosen and open l the top clamping frame. Swing back all clamping frames so as not to 1 interfere with the removal of the fuel assembly. S. The fuel assembly may now be removed horizontally out the side of the shipping container. Care must be exercised to avoid potential obstruc-tions and not moving over the SFP. I' rticular attention should be l paid to the contains. flange'and the : lamping frames for horizontal movements and the top closure assemblies for vertical movements. Carefully proceed with removal. T. Inspect the fuel assembly protective cover, 3f present, for evidence of damage from flying debris, bumping or fluid saturation, making note of the position where such damage is located with respect to the assembly. Record any abnormalitics on the new Fuel Inspection section of Form FH-1 (Operations or Engineering representative). U. Remove the polyethylene bag and perform a visual inspection of the entire bundle, providing the information specified on Form FH-1. The fuel inspection is primarily intended to catch damage to the assembly during shipment. The checks on rod bowing, grid deformation, endplate alignment (twist), etc., are made by comparing characteristics relative differences. Generally speaking, for damage to be significant, it would at least have to be oovious to a visual inspection in which one item is significantly different from another comparable item. Record the MISI number (LM) on form FH-1. At the locations where the outside surface of the protective bag was damaged, if damage has occurred, inspect for indications of penetration through the bag. If penetration is all the way through the bag, inform the Reactor Engineer. Otherwise, prepare the fuel assembly for storage. For dry storage in the new fuel racks, the polyethylene bag will be replaced, and a hole i cut in the bottom of the bag to permit drainage should any water accumulate in the bag, if required. Store the fuel assemblies l with the assembly alignment hole (M-hole) orientated toward the southwest in the new fuel storage racks. 1 4 V. Proceed with the placement of the fuel assembly in the fuel storage racks. Care must be exercised when moving and aligning the fuel assembly for placement in the fuel storage racks.
- Continue fuel inspection during lowering and replace the polyethylene bag by l
FHP-1 Page 5 of 13 Revision 6 putting the bag in the appropriate fuel storage rack and pulling the [V_') bag up as the fuel assembly is slowly lowered into the rack. Fold the top of the bag closed. W. Record the fuel rack position of the fuel assembly on the Fuel Receiving Record, Form FH-1 (Engineering representative) and status board. l Review the fuel QA inspection and release forms accompanying the fuel delivery to insure the vendor's inspection results are satisfactory. Sign off vendor QA release forms if acceptible and send forms to the Reactor Engineer. X. Close the fuel assembly clamping frames on the container for the position in which unloading was just completed. Y. Repeat steps N through X above for unloading the second fuel assembly from the container. After the second element is seated, use the 2500 lb. spring scale to determine the relative weight of each fuel assembly. Z. Attach the crane to the shipping container support frame lifting eye and remove the slack from the cable. AA. Remove the locking pins securing the supports to the support frame. Move the supports to their storage position and secure them. BB. Carefully pivot support frame from a vertical to a horizontal rest position in container frame. Before reaching the horizontal position, the two top closure assemblies must be partially closed to clear the container sides. Secure by the locking pins after shackle removal. v CC. I,oosen the screws on the lock tube support pad brackets. Retract the lock tubes lifting the internals as before if necessary. Fasten the lock tubes in the retracted position by installing the lock pin. DD. Engage and tighten the swing-bolt clamps iv ' Mer to clamp the fuel assembly support frame to the shock mount frame. EE. Return outrigger members to their storage position and install the locking pins. Account for all hardware which may have dropped or been taken from the container. FF. Install the container cover making sure that it is oriented the same as when it was taken off. The fact that each container half is serialized at the aft end will aid in ensuring proper orientation of the lid upon installation. When installing the lid, make sure that the gasket is properly seated. Containers equipped with 1/4 turn Camloc fasteners should have the cover lowered to within one-half inch of the bottom and each stud checked by finger to ensure that one is not cocked with the weight of the lid on it. As in unfastening, each Camloc stud can be fastened by turning through 90 with a wrench. GG. Remove the Department of Transportation (' DOT) radioactive shipment (] label and attach the empty label on the side of container. Reverse Q address label. FilP-1 Page 6 of 13 l Revision 6 HH. Repeat steps A through GG until all new fuel assemblies in a given {ms3 shipment have been removed from their respective containers and stored sli/ in the fuel storage racks. II. Proceed with an inspection of the fuel assembly inserts if applicable. If the fuel assembly contains a control rod assembly, use the RCCA handling tool to withdraw it a few inches from the assembly. If the fuel assembly contains a burnable poison assembly or a source assembly, + use a nylon strap looped over the assembly hold down bar to withdraw it a few inches from the assembly. If the fuel assembly contains a thimbic plugging device, remove it by hand. Inspect the visible portion of the component. The component movement should be free and unrestricted (RCAA lift drag about 170 lbs). Reposition the component and remove the handling tool. Place thimble plugging device with the ID toward the southwest. Recerd deviations on the New Fuel Record,
- Form FH-1 (Operations group representative or Engineering representa-tive).
For fuel receipt with burnable poison inserts verify that the insert hold-down bar is positioned with the identification number located at the reference hold corner of the fuel assembly on all _ inserted assemblies. i - - - rr :
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D GGB FHP-1 Page 7 of 13 R.evision 6 TROJAN NUCLEAR POWER PIANT FUEL RECEIVING RECORD - CONTAINER REPORT j Container Shipping Information: Shipment No. Shipment Date Container No. Container Seal No. and Verified Date Radiation Information: r Radfation Level on Surface Inside 2 Contact ar/hr Contamination dpm/100cm t Verified Container Inspection External: Vacuum or l Labels, Markings OK Seals on Container YES NO Pressurized YES NO Signs of Damage Explain: Verified Container Inspection Internal: Shock Indicators OK Desiccant Material OK Protective Wrappers OK Bolts and Clamps OK Cleanliness OK Explain: Verified Container Return Inspection: Clamps and Bolts Secure 0;* Stabilizing Bars in Pla::e OK Desiccant OK Label Address Reversed Empty Label On Explain: Verified Container Contents: (when facing end opposite maneplate, top end) Left Right Fuel Assembly ID Fuel Asrembly LH No. Fuel Insert, Type, ID Intended Storage Location ( / ) Verified New Fuel Inspection l Fuel Assembly ID Free of Obvious Burrs, Scratches, Foreign Matter (exclude l oval.nachine marks Free of Obvious Rod Bowing or Grid Deformation l 17 x 17 Array, Free of Obvious Endplate Misalignment l Insert Free of Obvious Bowing, Burrs, Foreign Matter l Insert Moves Freely without Binding [ Weight of Assembly Plus Insert Plus Tool Remarks: Verified Receipt Inspection by of PGE Date Witnessed by of Westinghouse (if available) Date Form FH-1 FHP-1 Page 8 of 13. Rev6sion.6 . -.... _. ~.. . -. - - -r0*a... -...., c.&, n. .. $....-.. --*l ,ar.=., r-se. a... } ^.,-..-..I,r.,2,' ),._. g.. .t=*-.*.....,:,y;: \\(ga. b *.g? X: ~~=4 e'.y m. :S.~N <.:. [;.. . f:*-m.** lW?'$:,*.l,q.i.y.) q) u. 1 n. .q;.
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.:/_,,,.. ,a u l t i FHP-1 Page 13 of 13 Revision 6 ATTACHMENT 2 PORTLAND GENERAL ELECTRIC COMPANY (D '"o3^" 3 80 0 7 R 0 _ _ E ) C03Y November 21, 3}k~~f) Revision 2 SAFETY-RELATED FbEL HANDLING PROCEDURE FHP-5-4 TRANSFER OF FUEL ASSEMBLIES APPROVED BY DATE M 2L 7[ l I PURPOSE This procedure outlines the steps necessary for fuel transfer during a refueling evolution. I. REFERENCES A. FHP-14, Limitations and Precautions for Handling Fuel Elements. B. FHP-6-1, Manipulator Crane Operating Instructions. C. FHP-6-S, Spent Fuel Assembly Handling Tool Operating Instructions. D. FHP-6-8, RCC Change Fixture Operating Instructions. E. FHP-6-10, Fuel Transfer System Operating Instructions. F. FHP-6-12, Spent Fuel Pool Bridge Crane Operating Instructions. l G. FHP-6-13, New Fuel Elevator Operating Instructions. H. FHP-6-14, New Fuel Handling Tool Operating Instructions. I. FHP-6-4, Thimble Plug Handling Tool Operating Instructions. J. FHP-6-9, Barnable Poison Rod Assembly Handling Tool Operating Instructions. II. PRECAUTIONS A. Observe the precautions and limitations of Reference A. B. If the applicable Trojan Technical Specificationr of section 3/4.9, Refueling Operaticns, are.not met, refueling shall cease until the specified limits are met; no operations which may increase the reactivity of the core shall be made. O-FHP-5-4 Page 1 cf 5 Revision 2 C. The status of each fuel assembly location and insert type will be maintained by use of the refueling sequence checkoff and Fuel Status ({)),/ / N; Board. Should any discrepancy between the checkoff, status board, and actual fuel location occur, the refueling operation will cease until the discrepancy is restored. D. Precautionary measures established by Chemical and Radiation Protection personnel must be strictly followed. jE. Boron concentration in the refueling water shall be maintained between 2000 ppm and 2150 ppm. F. Care must be exercised in monitoring for radiation hazards when handling the tools and equipment withdrawn from the refueling water. G. Do not move new fuel over irradiated fuel stored in the SFP racks unless using spent fuel tool. Move fuel to elevator via transfer canal centerline when using New Fuel tool. III. INSTRUCTIONS A. General 1. Rod Cluster Control (RCC) assembly transfers, will be made in the RCC change lixture in accordance with Reference D. 2. Thimble plug transfers will be made at the RCC change fixture or gg at the conveyor car frame location on the reactor side using ,) the thimble plug handling tool attached to the auxiliary crane ty hoist on the manipulator in accordance with Ref2rence I. 3. Burnable poison rods in discharged spent fuel assemblies will be left in the discharged spent fuel assemblies and returned to the fuel reprocessor with the spent fuel. Burnable poison rods will be removed from the partially spent fuel assemblies on the spent fuel pool side and the fuel assemblies will be replaced in the core with a thimble plug or RCC assembly as assembly insert. / Burnable poison rods removed shall be stored in the Burnable Poison Storage Rack inserts or discharged spent fuel assemblies l in the spent fuel pool in accordance with Reference 5. NOTE: All burnable poison rods will be removed from the core ~ during the first refueling. 4. This procedure outlines the steps necessary to transfer fuel assemblies from one location to another. The sequence of transfers and location changes required will be specified in the specific core loading procedure issued for each refueling. 5. Each fuel assembly location change should be noted on the refueling sequence checkoff and the fuel status board should be updated I ['.[/ / T accordingly. / FilP-5-4 Page 2 of 5 Revision 2 B. Transfer of Fuel Assemblies from the New Fuel Storage Area to the Reactor Core: 1. Open the polyethylene wrapper if present to expose the top of l the fuel assembly and attach the new fuel handling tool in accordance with Reference H. Inst'all by hand a new thimble plug if available and required for this assembly core location. .~ 2. Lift-the element out of the storage rack using the spent fuel . pool bridge crane, remove the bag if present and transfer it to the new fuel elevator via the transfer canal centerline (see precaution G). Remove the new fuel handling tool and lower the fuel assembly in accordance with Reference G. Update the status beard to indicate the new location. 3. Attach the spent fuel assembly handling tool in accordance with . Reference C to the spent fuel bridge hoist. l 4. Lift the fuel assembly out of the new fuel elevator and transfer it to the fuel transfer system conveyor car frame in accordance ~~ with Reference F. Remove the spent fuel assembly handling tool. Install a thimble plug if required for this assembly with the thimble plug tool here or in containment. Update the status board to indicate the.new location. 5. Transfer the fsel assembly to the reactor side in accordance with Reference E. Update the status board to indicate the new location. OS kns' tall'a thimble plug if required and remove the fuel assembly l 6. from the fuel transfer system conveyor car frame using the manipulator Erane in accordance'with Reference B. h. N[ositionthemanipulat6fcrane.~6vbrthecoretothelocation specified in the refueling. procedure. Lower the fuel assembly int 6 the' core and unlatch the manipulator crane in accordance with 8eference.B.. Update the status board to indicate the new location. C. TransE6r of Fuel Assemblies ~from the New Fuel Storage Area to the RCC Change Fixture: 1. Perform steps B.1 through B.6. to transfer the fuel assembly to the reactor side and~ attach the manipulator crane. 2. Reposition the manipulator crane over the RCC change fixture, lower the fuel assembly into place and unlatch the manipulator crane is accordance with References B and D. Update the status. board.to.icdicate.the new. location. D. TransNEofFue1 ~ ssembli6s from the Spent Fuel Pool ho'the Reactor Core: f'siti66 the' spent'fue1 ~ pool bridge crane over the fuel assembly 1. o ppecified in the refueling procedure and attach.the spent fuel assembly handling t6ol. in' accordance with Reference C (for initial core.. loading must first.open polpethylene'~ bag and then remove bag when assembly out of rack). FHP-5'-4 Page 3 of 5 Revision 2 2. Lift the fuel assembly out of the spent fuel rack and transfer it to the fuel transfer system conveyor car frame in accordance with Reference F. Update the status board to indicate the new n location. v 3. Perform steps B.5 through B.7 to transfer the fuel assembly to the reactor core. e _E. Transfer of Fuel Assemblies from the Spent Fuel Pool to the RCC E Change Fixture: 1. Position the spent-fuel pool bridge crane over the fuel assembly specified in the refueling procedure and attach the spent fuel assembly handling tool in accordance with Reference C. 2. Lift the fuel assembly out of the spent fuel rack and transfer it to the fuel transfer system conveyor car frame in accordance with Reference F. Update the status board to indicate the new location. 3. Remove the spent fuel assembly handling tool and transfer the . fuel assembly to the reactor side in accordance with Reference E. Update the status board to indicate the new location. 4. Remove the fuel assembly from the fuel tiansfer system conveyor ~ car frame using the manipulator crane in accordance with Ref-erence B. () ~ Reposition the manipulator crane over the RCC change fixture, 5. lower the fuel assembly into place and unlatch the manipulator crane in accordance with References B and D. Update the status ~ board to indicate the new position. F. Transfer of Fuel Issemblies from the RCC Change Fixture to the Reactor Core: -1._ Position the manipulator crane over the RCC change fixture and -latch the fuel assembly in accordance with Reference B. 2. Reposition the manipulator crane over the core to the location .specified in the refueling procedure, lower the fuel assembly into position and unlatch the fuel assembly in accordance with Update the status board to indicate the new location. Referenca B. G. Transfer of Fuel Assemblies from the Reactor Core to the Spent Fuel Pool:. 1. Following the _ instructions of Reference B, position the manipulator urane over the-fuel-assembly to be removed, latch the fuel
- assembly to the. manipulator crane and withdraw the fuel assembly 3,
from the core. g FHP-5-4 Page 4 of 5 (* Revision 2 v -.--_,_~--m.,. 2. Reposition the manipulator crane over the Fuel Transfer System conveyor car frame, lower the fuel assembly into the frame and / TX unlatch the assembly in accordance with Reference B. Update (;}j the status board to indicate the new location. 3. Transfer the fuel element to the spent fuel pool side in accordance with Reference E. Update the status board to indicate the new location. 4 '. Position the spent fuer pool bridge crane over the conveyor car frame, attach the spent fuel assembly handling tool and withdraw the fuel assembly in accordance with References C and F. 5. Transfer the fuel assembly to the spent fuel rack specified in the refueling procedure, lower the assembly into the rack and unlatch it in accordance with References C and F. Update the status board to indicate the new location. H. Transfer of Fuel Assemblies from the RCC Change Fixture to the Spent Fuel Pool: 1. Position the manipulator crane over the RCC change fixture and latch the fuel assembly in accordance with Reference B. 2. Perform steps G.2 through G.5 to complete the transfer to the spent., fuel pool. n. ( .... ~. ~ -~ - ~~ ~ . ~. ~ _~ ~ [ -. s E.1.
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1. .e... f. ~ fr:- :. :::.. GGB FHP-5-4 Page 5.of 5. Revision 2 ATTACHMENT 2 PORTLAND GENERAL ELECTRIC COMPANY TROJANNUhEh 'l([] ' ~" ^- - November 1,19W 0 7 c 3 kk-Y AfED Revision 2 FUEL HANDLING PROCEDURE FHP-6-12 SPENT FUEL POOL BRIDGE CRANE OPERATING INSTRUCTIONS //[L.[7,7 APPROVED BY DATE PURPOSE Ris procedure institutes a standard for operation of the spent fuel pool bridge crane. I. REFERENCES A. Spent Fuel Pool T.idge Crane Instruction Manual M1-28 II. PRECAUTIONS A. He hoist upper limit switch is a protective device and should not be intentionally used as a stopping device, but should be checked without a load. B. The hoist should not be used for side pulls. Ensure the cable is verti-cal before starting a lift. C. Visually check the hoisting cable for excessive wear, broken wires, kinking, or twisting prior to use. D. Verify no obstructions exist on bridge rails. E. All loads should be landed prior to leaving the cran unattended. F. Remove the Spent Fuel Pool railing to allow unlimited motion to North direction on rails. G. Operations should be conducted as smoothly as possible to prevent swinging of the fuel element. H. The bridge and hoist are interlocked to prevent simultaneous operation. I. Do not transport new fuel assemblies over irradiated fuel assemblies unless the spent fuel tool is being used. FH P-6-12 Page 1 of 2 Revision 2 III. INSTRUCTIONS O". A. Position the spent fuel pool bridge crane M.C.C. B-35 breaker 3515 to "0N". The breaker is located on the west pool side. B. Check hoist upper limit switch stop with no load at beginning of first refueling operation. 'C. Move the spent fuel pool bridge crane to the required predetermined loca-tion as follows: 1. Position the bridge by depressing either the "NORT11" or " SOUTH" push-button at the local pendent pushbutton station. Partially depress the button for slow speed; fully depress the button for fast speed. A J0G mode is also available to position bridge when hoist is not fully up. 2. Position the trolley by manual operation of the trolley hand chain. 3. Position the hoist by depressing either the "UP" or "DOWN" pushbutton at the local pendent pushbutton station. Partially depress the button for slow speed; fully depress the button for fast speed. ~~ Whenever raising or lowering a fuel element in the fuel rack NOTE: or conveyor car frame (upender), the hoist should be operated /l?N in slow speed to reduce the possibility of damage in case of (;11 interference or misalignment. D. The spent fuel pool bridge crane may be used to transport fuel assemblies from the new fuel racks, the spent fuel racks, the new fuel elevator and the fuel transfer system conveyor car frame. ~ When transferring new fuel from the New Fuel storage racks NOTE: to the fuel elevator, do not carry the assembly over irradiated fuel rack locations. Move along the transfer canal centerline area. ~. O,.GGB FilP-6-12 Page 2 of 2 Revision 2 x ATTACHMENT 2 PORTLAND GENERAL ELFfLDC3MP.L10 y 1 C 0 '3 Y TROJAN NUCLEAR PL iT0.. {~~L an, .,a November 11, 1977 SAFETY-RELATED Revision 2 4 FUEL HANDLING PROCEDURE FHP-6-14 NEW FUEL HANDLING TOOL OPERATING INSTRUCTIONS APPROVED BY DATE // / 77 / / PURPOSE nis procedure institutes a standard for use of the new fuel handling tool. I. REFERENCES l A. Drawing M1S(3)-49-1, New Fuel Assembly Handling Tool l B. FHP-14, Limitations and Precautions for Handling Fuel Elements / C. FHP-1, Site Removal of.New Fuel Assemblies from Shipping Containers and (> Handling of Shipping Containers II. PRECAUTIONS A. Observe the limitations and precautions of Reference B. B. Ensure the handling tool is resting firmly on the fuel element before attempting to latch or unlatch the handling tool. C. Whenever raising or lowering a fuel element in the new fuel storage rack, monitor the load cell for any indication of interference or misalignment. D. Occasional lubrication of the handling tool with silicon grease or neolube may be required to prevent galling and provide smooth oper-ation. He tool should be inspected for burrs and galling and the mechanism demonstrated to operate freely prior to use. E. Do not transfer a new fuel assembly over irradiated fuel rack locations. III. SPECIAL EQUIPMENT A. Load cell to monitor fuel element / handling tool load (0-2000 lb range minimum) for use in loading assemblies into new Fuel Storage j g room with fuel building crane. i; (- FHP-6-14 Page 1 of 3 Revision 2 B. One Clevis and bolt to connect the handling tool and load cell to the refueling building bridge crane (25 ton hook). l {d IV. INSTRUCTIONS A., Initial inspection and storage of new fuel. 1. Connect the load cell and handling tool to the refueling building bridge crane. Check that the latching shaft is in the upper (unlatched) position. 2. With the fuel element in the vertical position, lower the handling tool onto the fuel element. Ensure the tool is positioned so the pins of the tool align with the corresponding holes in the top of the fuel element no::le (Red spot in the south west quadrant). ~ 3. With the handling tool resting solidly on the fuel element, pull out on the locking pin and lower the latching shaft to the bottom (latched) position. 4. Push in on the locking pin to lock the latching shaft in latched position. Screw in the safety screw. 5. Take up the cable slack, unfasten the fuei element from the container frame and inspect in accordance with Reference D. h) 6. When the inspection is complete, relocate the fuel element in the C. desired new fuel storage rack (spent fuel storage rack for initial fuel loading). Observe the precautions and limitations of Reference B. 7. Lower the crane hook until the spring scale reads 0 to ensure the handling tool is resting solidly on the fuel element. 8. Unscrew the safety screw and pull out on the locking pin and raise the latching shaft to the upper (unlatched) position. 9. Push the locking pin in to lock the shaft in the upper position. 10. Slowly raise the handling tool and monitor the load cell to ensure the tool has properly unlatched. 11. Repeat steps A.2. through A.10. until the new fuel has been trans-ferred to the desired location. B. Transfer of new fuel from the new fuel storage racks to the new fuel elevator. 1. Connect the handling. tool to the spent fuel pool bridge crane. Do not install spring scale. Check that the latching shaft is l in the upper (unlatched) position. (D i V FHP-6-14 Page 2 of 3 Revision 2 m 2. Lower the handling tool over the desired fuel element and lower it onto the element. Ensure the tool is positioned so the pins of the tool align with the corresponding holes in the top of the fuel element no::le (red spot in the southwest corner). ' With the handling tool resting solidly on the fuel element, pull 3. out on the locking pin and lower the latching shaft to the bottom (latched) position. 4. Push in on the locking pin to lock the latching shaft in the latched position. Screw in the safety screw. 5. Slowly raise the fuel element out of the new fuel storage rack and transfer it to the new fuel elevator rack by moving along the transfer canal; do not carry the r.ew fuel over irradiated fuel rack locations. 6. Lower the crane hook until the handling tool is resting solidly on the fuel element. 7. Unscrew the safety screw and pull out on the locking pin and raise the latching shaft to the upper (unlatched) position. 8. Push the locking pin in to lock the shaft in the upper (unlatched) position. 9. Slowly raise the handling tool and verify that the tool is unlatched. O,.. 10. Repeat steps B.3. through~ B.9. until the fue1~ transfer evolution is complete. ~ r..
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