Text

Spent Fuel Pool Ventilation Exhaust Sys Study
	ML19344A920
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	08/22/1980
From:	Hogg C, Vance J; BECHTEL GROUP, INC., BECHTEL POWER CORP.
To:	;
Shared Package
ML19344A919	List: ML19344A918; ML19344A920; ML19344A921;
References
	REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR NUDOCS 8008220589
	Download: ML19344A920 (50)
	v • d • e

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e e-9 4 SPENT FUEL POOL VENTILATION

[ EXHAUST SYSTEM STUDY Prepared for Pennsylvania Power & Light Company Susquehanna steam Electric Station Units 1 and 2, Job No. 8856 j Prepared by Bechtel Power Corporation San Francisco, California v ( By (( $ VI. hw f Approved by / C [ Ads -i February, 1975 [Q

I. INTRODUCTION / Spent fuel pool ventilation exhaust systems have been provided on past nuclear power plants to aid in the control of airborne contamination from the pool area. These systems typically provide exhaust intake locations at or near the water level of the pool, which take a fraction of the total air exhausted from the air volume above the refueling floor. The intent was to capture as large a fraction as possible of radio-2 active airborne contamination at the release point and exhaust it from the building, before it was dispersed in the refueling floor air space. Investigations of these past designs coupled with surveys of operating plants have indicated that the spent fuel pool ventilation exhaust systems were not as effective in controlling airborne contamination as originally expected. Some plants contacted in the survey, however, indicated that even though they could not make a statement regarding the system effectiveness they would not eliminate the system from the plant. In order to make an assessment of the actual effectiveness of a spent fuel pool ventilation exhaust system, Penn-sylvania Power & Light has requested that Bechtel conduct a study at an operating BWR plant. A 550 MWe BWR, was ( selected for the study because they were entering into a refueling outage and would potentially be experiencing high airborne iodine levels. In this study, smoke bomb tests and airborne I-131 measure-ments were made to identify the air flow patterns on the refueling floor and the capture effectiveness of the fuel pool ventilation exhaust system. Recommendations for a improved design of the refueling floor ventilation system to minimize airborne contamination are included for '~' future plant designs. f'

II.

SUMMARY

AND RECOMMENDATIONS / The pool ventilation exhaust system studied demonstrated a low effectiveness for capturing all the airborne con-tamination (I-131) released from the pools. Smoke bomb tests showed that the pool exhaust system captured essenti-ally all the air in a space extending about 18" vertically over the top of the handrails at the side of the pool and 4' to 5' horizontally from the exhaust openings. Air ris-ing from the pools, because of thermal bouyancy or entrained air flowing into the pool area over the top of the handrails, which is outside this zone was not captured by the pool ex-haust system. The smela bomb tests and the airborne I-131 measurements made on the refueling floor indicated the following general air flow pattern. Warm air (80-82*F) which is supplied 15 feet above the operating flocr, by virtue of its buoyancy, tends to rise to the top of the reactor building. The air cools and flows down the walls and across the floor to the exhaust openings at the pool level and the floor level. This cold air also mixes with the supply air. Any thermal currents from the pools ascend aad mix with the supply air at the top of the reactor building. The turbu-lence and mixing in the refueling floor air space causes rapid dispersion of any contaminant released in the build-ing. This is shown by Figure 1. I The measured airborne iodine concentrations were generally higher on the north side of the reactor building because most of the exhaust ducts are located there. The supply side of the building was normally less by a factor of 2 than the measurements on the exhaust side. The measurements adjacent to the reactor cavity pool showed concentrations comparable to the supply side (Zone 3) concentrations, with the exception of two spikes which occured during the dryer g,, transfer and the cavity flooding. The spike concentrations at the reactor cavity were probably due to recirculation patterns in close prox!.mity to the pool caused by the air flow over the handrails. The iodine concentrations on the refueling bridge were comparable to the concentrations in the exhaust area of the building. Plant operating personnel indicated that reducing the pool water temperature substantially reduced the airborne iodine problem. This effect will be investigated later to determine the temperature dependence of iodine releases from water surfaces. f'

It is recommended that the pool ventilation exhaust /*' systems be deleted from future plant designs. It is further recommended that the refueling floor ventilation system be designed with elevated exhaust intakes, pre-ferably on the wall nearest the pools, and supply openings on the opposite wall at floor level. An optimum design would be to supply air on both sides of the pool at floor level and exhaust at the top of the reactor building over the top of the pools. It is recognized that this latter arrangement could have interference problems in routing large ducts past the reactor building crane to the reactor building exhaust. This design could result in a improved air exhaust flow. D 1 I

III. DISCUSSION OF. AIRBORNE PROBLEM' / In nuclear plants the refueling operations and the storage of spent fuel is usually done under water in pools which have surfaces exposed to the air space above the pools. Because of this direct path, radioactivity will be released to the air space above the pool. The activity released may be categorized into one of the following four groups: noble gases, particulates, tritium and iodines. Noble gases may be evolved from failed fuel pins or from the reactor watar. = Particulates are generally released from surfaces, such as the pool walls, which have dried after being in contr.ct with the pool water which contains soluble and inscluble radioactive materials. Tritium, which is in the reactor coolant and pool water, may be released from the pool due i to evaporation of triated water. The iodines contained in the reactor water and pool water exhibit a degree of volatility depending on the pH and temperature of the water and the chemical nature of the iodine. N, In operating plants to date noble gases and tritium have not been a significant source of activity in the air space above the pools. Particulates have generally been con-trolled by maintaining pool wall surfaces in a wetted condition. Iodines, on the other hand, caused an airborne problem at the plants during their last refueling outage The iodine levels exceeded MPC values and protective f equipment (face masks) were required to continue the operations. The magnitude of the airborne iodine level is a function primarily of the ventilation system desiga - r the temperature of the pools and iodine concentration in the water. a 4 4

IV. DESCRIPTION OF VENTILATION SYSTEM The airflow diagram of the refueling floor ventilation ( system is shown on drawing M-157. Drawings M-519, M-520 and M-528 show the supply and exhaust ducts for the pool exhaust and refueling floor ventilation systems. Approxi-mately 32,000 cfm of air are supplied 15 feet above the floor on all four sides of the refueling floor. The pool exhaust system exhausts approximately 18,000 cfm and the remaining 14,000 cfm are exhausted by the refueling floor The refueling floor exhausts are located exhaust system. at floor elevation on the north and east walls of the building. The system was designed for 10 air changes per hour for the lower 15 feet of the refueling floor. During the test, the supply ducts on the north side of the reactor building were shut down. The pool exhaust system was designed to operate in any one of seven different operating modes by selection of mode switche's on a local control panel. The different modes position dampers in the ducts from the three pools and j changes the exhaust air flow rate distribution from the pools. Some of the modes were not available for the tests because of plant policy and one of the modes co.uld not be maintained because of imbalances in the system causing the supply fans to trip. It was judged that the difference in modes would have negligible impact on the airborne iodine levels measured during the test because of the general f flow patterns observed during the. smoke tests. f The refueling floor air volume is approximately 500,000 cubic feet. The equipment hatch, the two stairwells and the elevator were covered with plastic sheeting to minimize airflow between other portions of the reactor building. The walls of the refueling floor level are insulated steel siding. The outside temperatures varied from -15'F to 10*F during the testing period. Plastic i sheeting had been taped to the handrails surrounding the pools preventing air from flowing directly across the floor and into the pool level exhaust system. f' I e

V. STUDY APPROACH I The purpose of this study was to determine the effective-ness of the pool exhaust system. Airborne concentrations of 1-131 were measured during the various steps in the refueling operation from vessel head and dryer / separator removal through fuel transfer to the spent fuel pool, to track absolute levels of iodine during these operations. Iodine airborne measurements were made at various locations on the refueling floor to determine the extent of the dis - 1 persion and to characterize the air flow patterns in this area. Iodine sample locations are shown in Figure 2. Smoke bomb tests were utilized to identify the flow patterns and determine capture distances from the pool exhaust open-ings. A chemical smoke gun was used to verify the capture distances observed in the smoke tests and eliminate the question of heat content in the smoke plume. Photographs were taken of the smoke bomb tests for inclusion herein. Three air samplers were used for the iodine measurements. The samplers were located at various places on the refuel-ing floor and operated simultaneously. Thirty minute air samples were collected on Cesco "B" charcoal cartridges. The cartridges were counted for 10 minutes on a Ge-Li detec-tor using a ten minute decay time, f %e f

VI. TEST RESULTS / A. General 1. Air flow measurements were made on the pool exhaust and reactor buildings ducts to verify the design air flow requirements. An anemometer and an Alan 6r Velometer were used to take the measure-ments. The measured exhaust flows were within the range of the design air flows. 2. During the test the following conditions were prevalent: H & V Mode Exhaust from fuel pool, reactor cavity and reactor building only. T supply air 80 - 82*F T fuel pool 68*F T reactor cavity 78*F T exhaust air 68*F 3. Smoke bomb locations are shown in Figure 3. ( B. Smoke Test 1. Test 1 One smoke bomb (3 minutes in duration) was located south of the reactor cavity approximately six feet from floor level as shown in pictures 1-1, 1-2 and 1-3. These pictures show the smoke rising vertically until the smoke reaches the supply duct elevation. At this point, the smoke turned north towards the reactor cavity (See picture 1-3). The supply air is hotter than the pool and ambient air temperature giving an upward motion to the air, noted by the fact that the air is not driven toward the cavity but continues to rise. Since the supply air is not flowing down to the cavity then the air that is supplied to the fuel pool floor most come from the recirculation of the air in the reactor building. This is shown in Figure 1. Recirculated air will be in contact with the cold walls bringing the air down against the floor and towards the pool. This ) action was demonstrated by the next set of test pictures. l f i we+ we

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2. Test 2 / The conditions during this test were as des-cribed above with the reactor cavity water level two feat below the pool skimmers. A smoke bomb was 10cated on the southwest corner of the reactor cavity at floor level as shown in picture 2-1. Note that during the tests the railings were covered by plastic sheets. Pictures 2-1 and 2-2 show the smoke being pulled over the railing towards the pool exhaust ducts and spreading to the middle of the reactor cavity. Picture 2-3 is the opposite side picture taken about the same time as picture 2-2. Pictures 2-4, 2-5 and 2-6 show the exhaust ducts capturing approximately 20% of the smoke with the remaining 80% escaping to the center of the pool. The exhaust ducts on the opposite wall of the reactor cavity were providing very little smoke capture. The cooler air exhaust flow which is flowing across the floor was apparently partially entraining N, warmer air enroute to the exhaust ducts as the air stream moved up over the top of the handrails. The air being swept to the reactor cavity is the re-circulated cold air and not the main supply air. Since air is being recirculated we would expect iodine to be well spread over the operating deck which was demonstrated by the iodine samples measured and described in Section C below. The air that was I not captured by the pool exhaust ducts, due to the thermal driving force from the pool and entrained air, rises to the top of the reactor building and is recirculated. This is clearly demonstrated by pic-tures 2-7, 2-8, 2-9 and 2-10. About 3 minutes after the smoke bomb had burned out, the pool is almost cleared with most of the smoke rising to the tcp of the reactor building, as shown by picture 2-11. (\\

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3. Test 3 In order to determine the effectiveness of the f pool exhaust ducts, test 3 was performed. The fuel pool was used because most of the pool exhaust is from these ducts. Picture 3-1 shows a smoke bomb held within four feet of the exhaust duct results in the capture of 100% of the smoke. As the smoke source is moved towards the area of the fuel pool where no exhaust ducts are located the smoke starts to rise and a smaller fraction of smoke is captured.- This is demonstrated by pictures 3-2 and 3-3. When the smoke is approximately six feet from the exhaust duct, very_little smoke is being pulled to the pool exhaust ducts. Most of the smoke is escaping and rising vertically to the top of the reactor building. This is shown in pictures 3-4 and 3-5. Picture 3-6 shows the smoke source being moved back to the exhaust duct within capture range. This test demonstrated that the expected capture of the pool exhaust ducts with a face air velocity of 630 ft/ min is less than six feet. s, I T ~g-b 7 i w

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i 4. 'lest 4 / This test was performed to demonstrate the effectiveness of the exhaust ducts located on the northeast side of the fuel pool. This corner of the fuel pool has two exhaust ducts on the north j side and six on the east side (two are part of the skimmers). Since this area has most of the exhaust ducts the effectiveness of the pool exhaust system should be increased. Pictures 4-1, 4-2 and 4-3 show e most of the smoke being captured by the exhaust duct with very little smoke escaping. The effectiveness of the exhaust is limited to a distence of less than j six feet as seen by test 3, therefore the iodine re-i leased from the center of a fuel pool is not being captured, but rises to the top of the reactor building l as seen in picture test series 2 and 3. W I s-t

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5. Test 5 The smoke bomb was placed on the southwest t corner of the fuel pool in order to determine the effectiveness of the pool exhaust and the reactor building exhaust on the northeast side. Picture series 1 showed the smoke flowing in a general northeast direction. Picture series 5 shows the smoke close to floor level at the release point and starting to rise some ten feet away from the release point. The pool exhaust ducts are pulling the smoke towards the plastic covered railing but picture 5-2 shows the majority of the air being exhausted from the pool exhaust rather than the reactor building exhaust. Picture 5-3 shows the smoke is split with part going towards the pool exhaust and the rest rising in air currents from the supply air. The split in smoke appears to be 50-50, as seen in picture 5-4. Note that the pool temperature s,, was approximately 68'F during this test. This test demonstrates again that the air being provided to the pool exhaust is from the floor

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7. Test 7 f The smoke bomb was placed on the northwest corner of the dryer-separator pool as seen in picture 7-1. The north wall supply ducts were closed off as can be noted by the plastic covering the supply duct in picture 7-1. The smoke is rising and flowing directly east. There are two exhaust ducts in this area but these ducts are behind the shield plugs. Picture 7-2 shows no flow toward the supply ducts. In picture 7-3 the smoke is heading towards the reactor cavity and rising. The supply ducts on the west wall were still in operation pro-viding the driving force for the smoke. Picture 7-4 shows a small pull towards the exhaust duct but the majority of the smoke is flowing to the top of the reactor building. Picture 7-4 moved the smoke bomb closer to the exhaust duct at the north center of the reactor cavity. A definite flow to the reactor building exhaust can be seen. This indicates that the air pattern on the north side of the fuel pool is not being recir-culated but is being captured. e $I f' i

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9. General Observation Test Results The, smoke not directly captured by the reac-t tor building and pool exhausts rose to the t.op of tha reactor building. The smoke bombs acle generally 3 minutes in duration and within a minute of the end of the burn, the smoke was widely dispersed. This can be generally seen by pictures 9-1, 9-2 and 9-3. The smoke in the top of the reactor building remained about ten minutes after which time the smoke could not be visually detected. This is generally indicative of the large air movement, i.e., turbulence, in the top of the reactor building. It also indicates that i about 6 air changes per hour were taking place above the supply duct elevation. This air moves to the sides of the reactor building and is cooled by the reactor building sidings (outside air temperature ranged from -15 to 10'F). The cold air then flows to the reactor floor where it is picked up by the pool exhaust. N-t v T

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l C. Iodine Measurements In this test three air samplers were used located in various places on the refueling floor. The locations are shown in Figure 2. The air samplers normally operated for 30 minutes in each location and then were counted for ten minutes. The results are plotted in Figure 4 for the five zones in the re-fueling floor. The five zones and the sample test points are shown in Figure 2. Table 1 shows the measured iodine levels for each sample point. The results generally followed the~ air pattern shown by the smoke tests. 1. Zone 1 The highest iodine levels are recorded here except for selected incidents in Zone 2. The reason for the higher iodine level in this zone is because the air flow is generally towards this area. The air flow pattern for the north g, side of the cavity that is shown in Figure 1 is shown by the iodine levels measured in Zone 1. l 2. Zone 2 During steady state conditions the iodine levels are below the levels in Zone 1. Any large increases in iodine released from the reactor cavity, such as removing the dryer or filling the cavity, caused a peak in the iodine level in Zone 2 to occur. The reason is because there is a direct recirculation of the air from l the pool, as shown in Figure 1. The air from } the pool is entrained by the mixture of cold recirculated air and the supply air. After the increase in iodine levels, the iodine is spread over the refueling floor. This is seen by the iodine levels in Zone 3. 3. Zone 3 This area measured the iodine levels on the south side of the refueling floor. If the pool exhaust ventilation system was performing ef-fectively then the iodine levels in Zone 3 should be substantially less than Zones 1 and 2. As can be seen by Figure 4, Zone 3 is only a factor of 2 less than Zone 1. This indicates that the airborne iodine is fairly well spread over the refueling floor by means of the re-circulated air as seen in Figure 1. l

l 4. Zone 4 The general iodine level wa comparable to Zones 2 and 3 with the exception c2 the spikes due to cavity flooding or dryer removal. Of interest in this area were the measurements on the refueling bridge. As seen in Figure there is not a substantial change for medsured iodine level in Zones 2 and 3. 5. Zone 5 This zone generally snowed the spread of con-I tamination in the reactor building. I I 6. General During the above tests one air sample was taken while the smoke bombs were set off. In picture 10-1 the three particulate pre-filter which were removed from the Cesco Cartridges pre-filter are shown. The location of each sampler was as follows: I No. 1 - south of reactor cavity a. b. No. 2 - north side of reactor cavity No. 3 - south side of reactor building c. As seen in picture 10-1 the amount of dust particles collected on the pre-filters was indica-tive et the smoke concentrations which g-nerally supported the air flow patterns demonstrated by the iodine measurements. a 1 v I i 1 i i i I

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D. Chemical Smoke Gun Tests Because the smoke bombs used in these tests were of the burning type there was some concern that the thermal content of the smoke plume may be biasing the test results. To eliminate this con-cern a hand-held chemical smoke Sun was used to I conduct a series of tests near the fuel pool l water surface. Photographs were not taken at this series of tests as it was judged that the smoke plume density and size were rot sufficient to obtain adequate photographs. The sraoke gun tests confirmed the results of the smoke bonb tests. The chemical i smoke which was released at the pool surface.ithin 5 feet of the exhaust opening was captured. At further distances smoke was not captured but was rising to the top of the reactor building. V L l l s-t \\

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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 nozzle (red spot in the southwest corner). ~ ~ ~ ~ ' ~ 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 the 1atched. 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 new 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 rocking pin in to lock the shaft in the upper (unlatched) position. 9. Slowly ' raise the handling tool and verify that the tool is m unlatched. (zg; 10 Repeat steps B.3. through B.9. until the fue1~ transfer evolution is complete. .~ ~ r: ' ' ~. ~~ ~ - - ~ c. ,3---.. 't' i_. 3---- y, z.....: - ~,-.'.. ..,,5 c : c ~:-- ~ ~

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h.AlClGHBa2.5 McAvy conos =crtard General Eectric Conrany .. mE NMM dM ~' - b - - +-:- August 4, 1978 CinItzAw&Lt Victor Stello, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 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, / C. Goodwin, Jr. Assistant Vice President Thermal Plant Operation and Maintenance CG/WSO:mm Enclosures c: 223f)()24 0 0 0 0 m

ENCLOSURE Response to Question _V). 1 A diagram illust ut the physical relationship between the reactor core, the fuel transfer canal, .te spint fuel storage pool, and the setdown, receiving, and storage areas for heavy loads moved on the refueling floor is enclosed as. Response to Question No. 2 s 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 perfo rmed. The drop of the heaviest load to be carried by the Fuel Building crane from the maximum height to which it can be carried is discussed in the 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 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 movement envelope,

Page Two ENCLOSURE the cask would be carried no closer to the pool than about 8'-6" and then 4 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. e 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 11 feet from the spent fuel pool at its closest point. The probability of a heavy objec*. 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 t* 1 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. Respons; 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. i )

TABLE 1 ITEMS WillCil MAY BE CARRIED OVER Tile REACTOR CORE DURING REFUELING Item Item _ Drop lieight No. . Description Crane Used Weight (Pounds) (Feet) Length (Feet) Handling Frequency-1.- 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 Happing Fixture Manipulator 100 pounds 13 4' 1/ year 5. Fuel Assembly Manipulator 1,750 pounds 14 13' 350/ year i

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 Itsm 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 Handl!ng Tool a Burnable Poison SF 800 33 12 100 - 1s t 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 48 1/yr-3 yr Channel Spacing 1/10 yr Tool 7 Rod Cluster SF 1200 12 65 Control Change Tool ) 8 Radiation Specimen SF 600 1 1/yr-3 yr Transfer Basket 1/10 yr 4 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 l Scand 14 Push Arm FB 350 17 48 1/10 yr 15 Spent Side Stand FB 150 4 I,8 1/10 yr

IABLE 2 Page 2 of 2 Items Which May Be Carried Over or In the Spent Fuel Fool Max. Drop Approx Item Weight Length Height to Handling Item No. Description Crane Used (lbs) (ft) Top of Racks (ft) Frecuency New Fuel Elevator Parts: 16 Elevator Assembly F3 660 14 48 1/10 yr 17 Track F3 450 38 48 1/10 7 18 3 racket FB 125 2 48 1/10 yr Miscellaneous: 19 Underwater Light FB 100 30 26 1/vr Poles j r/1. lA3 i

mu3 Items Which May Be Handled Within 10 Ft of the Edge of the Spent Fuel Pool Max Drop Height to Closest Approx. Item Weight Length Top of Dist. Handling Item No. Description Crane Used (lbs) (ft) Racks (ft) To Pool Frequency A New Fuel Assembly SF 1620 14 25 3 65/yr B New Fuel Assembly 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 ? 1, 10 Stand & 15 yr H New Fuel Shipping FB 8000 _ 25 6 1/yr Containers (Full) MRG/jr/1.lA5

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,I I iI I or AN d g g 3? r,.W.. f g PLANT AA8tANCEi.atNT CIACR AM or urs :r.% w mace u..so asesum *a sen.sc re es se_ r4.s.a =ts;;;La ne:r,usten Js i.sQs M4:C. 2 *4 h ha.4Mfm FIGU'It 9.110 FVEL CA!K WOVinstNT (NVELOPE Amend 54RC 3 (october DT3) L<-----__ - --e- __m._ -~ % m- __x_ m __ m ,m
ATTAGMENT 2 PORTLAND GENERAL ELECTRIC COMPANY g ~~ TROJAN NU t . ) TA- - ) ' ' ~ ~ May 9, 1978< W SAFETY-PJLAT D Revision 6 FUEL IIANDLING PROCEDURE FHP-1 SITE REMOVAL OF NEW FUEL ASSEMBLIES FROM SHIPPING CONTAINERS, FUEL INSPECTIONS, AND HANDLING OF SHIPPING CONTAINERS APPROVED BY DATE /o[78 / PURPOSE This procedure establishes guidelines for site removal of new fuel assemblies from shipping containers and initial receipt inspection of ner 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.it Operating Manual. 5. FHP-5-4, Transfer of Fuel Assemblies. B. Enclosures Form FH-1, Fuel Receiving Record. II. PRECAlTTIONS A. Observe the precautions and limitations of Reference A.I. B. Care must be exercised in lifting and moving the shipping container at all times. The container shall be moved at a slow speed, kept as IcVel as possible, and not permitted to contact barriers of any kird. C. The new fuel room should be cleaned before new fuel storage and rack bottom locations checked to be free of obstructions. FHP-1 Page 1 ef 13 l Revision 6
D. A fuel assembly may only be lifted when it is in the vertical position. Horizontal 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 fuel 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 acccrdance 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. A Radiation Work Permit shall be issued to cover the l fuel receipt work. It should require cotton gloves to be used when touching the fuel directly. J. When installing fuel into the New Fuel Storage Pit, a rope barrier should be erected around the hole for personnel safety when pit is 4 unattended. K. Avoid transferring new fuel (or other heavy loads) over irradiated fuel. l III. SPECIAL_ EQUIPMEhT A. 1/2" drive socket set with deep sockets, small adjustable wrench, 7/16" and 3/4" combination box /open end wrenches. I B. A 2S00 lb. spring scale. C. A four legged steel sling equipped with shackles with a rated capacity exceeding 7,000 pounds. 4 D. New fuel handling tool and short sling (nylon or steel). l 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 i constructed. f FHP Page 2 of 13 Revision 6
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, concerning container indentification (Operations group representative) and radiation levels (Operations group or Radiation Protection representative). Inspect the Westinghouse fuel i 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 i in a stable level position for fuel unloading (the container should be orientated with the valve cover end toward the south and about th ce feet from the SFP north edge). C. Perfom 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. Tnis 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 removed. Record whether a differential pressure existed on form FH-1. ~ E '. Loosen-the fastener hardware between the container shell halves after pressure has equalized. between the. container and atmosphere. If the container is equipped with bolts,~ simply unfasten. If the 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 container cover. Break and remove the seals through the container flange. = .- u : a :: : - - " + ::: 3r c " F. Raise the cover to allow room for a radiation detector probe. Press [ the gasket seal te its position on the bottom 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 -~-- group representative). When the radiation check is completed satis Ectorily, set the cover on wood cribbing. .t. r- - G. Inspect the inside.of the container and supply the information specified in the Container Inspection-Internal Section of form FH-1 and note any abnormalities in the Remarks section, r 1.f-"If.either-of the 'two shock overload 'acceleratometers (ball and e.rr. tspring) are-tripped, the assemblies may have received an acceler-ntion in excess of design limitations. Report this condition tes :to:the Reactor Engineer. ~
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r 2ad::.If any..desiccantsbags-have ruptured, remove them from the container. ' L i 01, E ui. J:.'.. :. H. Remove the ball lock pin securing the lateral lock tubes at the aft O r. end rof' the sshock ' mount eframer: It:will be necessary tio-lift the c: ~r:- :. - PHP-I Page 3'of 13 Revision 6
internals to permit telescoping the lock tubes into their housing. This may be accomplished by using the lifting fixtures provided on (_,,, each pillow block and a double lifting sling. l I. Concurrent with the outrigger and the lock :ube manipulations, the following. may take place. 1. Remove 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. 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 supgr*: frame in the hori:ontal position. For orientation purposes, the left and right fuel assemblies shall be determined when viewing ,; ' the container from the top end. 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 contain'er assembly. Lock in place using hardware prcvided. Adjust the pads
,3 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.
~ After having uncovered the new fuel storage rack intended locations, l K. attach the crane to the lifting-eye at the forward end of the fuel ^assembly support frame using a steel shack ~1'e and short (approximately T six foot)' sling having a minimum rated capacity of-3000 lbs. l ^ L. Plvoi. the-~ support frame slow'ly' to 'the vertical position. C'oordinate crane movement in the4 vertical direction with crane movement in the horizontal in steps small enough to maintain vertical alignment of the cable- ~~2m' ~~
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M. While holding support ' frame 'in the vertical position, install the supports and secure. Remove the crane from the lifting eye only when ~ the uprighted support frame is secure. Inspect the uncovered portion of the container internals for damage. 7" " - ~~~:" - .c n. :..: :. :..... : ~ N. Exposei th'e top' ehd of 'the' fuel assembly no::le in preparation for engagement of the new fuel handling tool. If the exposed components were not ' examined; earlier,- they may' be examined at this-time; or aft'er- - the assembly is placed in the new fuel storage rack.- -i. l.. la c-
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~ 0. Assemble the new fuel handling tool and the lifting sling onto the Q spent fuel crane hook, and position the tool above the exposed fuel Q assembly nozzle. Note that the bridge must be driven north until 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. - Q. Maintaining a taut cable on the assembly, finish loosening and swing open all but the top and ottom clamping frames. R. Loosen and open the bottom clamping frame, and then loosen and open the top clamping frame. Swing back all clamping frames so as not to 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. Particular attention should be l paid to the container flange and the clamping frames for hori: ental movements and the top closure assemblies for vertical movements. Carefully proceed with removal. T. Inspect the fuel assembly protective cover, !f 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 abnormalities on the new Fuel Inspection section of Fom FH-1 (Operations or Engineering representative). U. Remove the polyethylene bag and perform a visual inspection of the entire bundle, providing the infomation specified on Fom 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 AMSI number (LM) on fom FH-1. At the locations where the outside surface of the protective bag was damaged, if damage has occuned, inspect for indications of penetratien through the bag. If penetration is all the way through the bag, infom 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 l 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. V. Proceed with the placement of the fuel sssembly in the fuel storage racks. Care must be exercised when mwg and aligning the fuel assembly for placement in the fue! storage racks. Continue fuel inspection during lowering and replace the polyethylene bag by l 4 FHP-1 Page 5 of 13 Revision 6
putting the bag in the appropriate fuel storage rack and pulling the i bag up as the fuel assembly is slowly lowered into the rack. Fold eO the top of the bag closed. W. Record the fuel rack position of the fuel assembly on the Fuel Receiving Record, Form Fil-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.
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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 determ'.e 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 twc top closure assemblies must be partially closed to clear the container sides. Secure by the locking pins after shackle removal. O CC. Loosen 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 in order 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 lower x1 to within one-half inch of the bottom and each stud che 'ked ' i finger to ensure that one is not cocked with the weight of the it. As in unfastening, each Camloc stud can be fastened by ...ag through 90 with a wrench. 1 l GG. Remove the Department of Transportation (DOT) radioactive shipment / label and attach the empty label on the side of container. Reverse (g] address label. Flip-1 Page 6 of 13 Revision 6
HH. Repeat steps A through GG until all new fuel assemblies in a given h[?N shipment have been removed from their respective containers and stored 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 thimble 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. Record 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. .-- ~ rrr. r
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l TROJAN NUCLEAR POWER PIANT FUEL RECEIVING RECORD - CONTAINER REPORT Container Shipping Information: Shipment No. Shipment Date Container No. Container Seal No. and Verified Date Radiation Information: Radiation Level on Surface Inside 2 Contact ar/hr Contamination dpm/100cm Verified Container Inspection External: Va m 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 l Container Return Inspection: Clamps and Bolts Secure 0;; Stabilizing Bars in Place 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 As.embly LM No. Fuel Insert, Type, ID Intended Storage Location ( / ) Verified New Fuel Inspection Fuel Assembly ID Free of Obvious Burrs, Scratches, Foreign Matter (exclude l oval machine marks Free of Obvious Rod Bowing or Grid Defomation l 17 x 17 Array, Free of Obvious Endplate Misalignment l Insert Free of Obvious Bowing, Burrs, Foreign Matter [ Insert Moves Freely without Binding Weight of Assembly Plus Insert Plus Tool Remarks: Verified l Receipt Inspection by of PGE Date Witnessed by of Westinghouse (if available) Date Form Fil-1 FHP-1 Page 8 of 13 Oc-edS119 Tit 3
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ATTACHMENT 2 PORTLAND GENERAL ELECTRIC COMPANY O,/ ""^" Sen'E R 0 _ ~.). _ C 03 Y w_ , /.\\_ November 21, M - ). ) J g Revision 2 SAFETY-RELATED F EL HANDLING PROCEDURE FHP-5-4 TRANSFER OF FUEL ASSEMBLIES APPROVED BY S# DATE O 7[ f 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. 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, Burnable Poison Rod Assembly Handling Tool Operating Instructions. II. PRECAUTIONS A. Observe the,..ecautions and limitations of Reference A. B. If the applicable Trojan iechnical Specifications of section 3/4.9, Refueling Operations, are.not met, refueling shall cease until the l specified limits are met; no operations which may increase the reactivity of the core shall be made, hh FHP-5-4 Page 1 of 5 l Gl Revision 2 l
W C. The status of each fuel assembly location and insert type will be maintained by use of the refueling sequence checkoff and Fuel Status /'~%g Board. Should any discrepancy between the checkoff, status board, i ],) and actual fuel location occur, the refueling operation will cease s until the discrepancy is restored. _D. Precautionary measures established by Chemical and Radiation Protection personnel must be strictly followed. 4E. 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. l 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 at the conveyor car frame location on the reactor side using ) the thimble plug handling tcol attached to the auxiliary crane 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 \\ ['T accordingly. /v) Fl!P-5-4 Page 2 of 5 i Revision 2
B. Transfer of Fuel Assemblie,s 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. Insth11 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 fuel assembly to the reactor side in accordance with Reference E. Update the status board to indicate the new location. ins' tall a thimble plug if required and remove the fuel assembly l /,) 6. from the fuel transfer system conveyor car frame using the manipulator x-/ 'drane in accordance with Reference B. h. R5kositionthemanipulatoferane.overthecoretothelocation specified in the refueling procedure. Lower the fuel assembly into the core.and unlatch the manipulator crane in accordance with Reference.S. ; Update the status board to indicate the new location. C. TransEEr 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 16 accordance'with References B and D. Update the status. board.to. indicate.the.new. location. D. Transf5rofFuel ssembliss' from the Spent Fuel Pooi~to'the Reactor Core: 1. fEsiti66the' spent" fuel'poolbriugecraneoverthefuelassembly ppecified in the refueling procedure and attach.the spent fuci sssembly handling to61 in accordance with Reference C (for initial core. loading must first.open pol ethylene bag and then remove O; bag when assembly out of rack). . FHP-5'-4 Page 3 of 5 i Revision 2
2. Lift the fuel assembly out of the spent fuel rack and transfer it to the fuel transfer syste,m conveyor car frame in accordance '~'s with Reference F. Update the status board to indicate the new location. 3. Perform steps B.5 through B.7 to transfer the fuel assembly to the reactor core. -E. Transfer of Fuel Assemblies from the Spent Fuel Pool to the RCC 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 taansfer system conveyor car frame using the manipulator crane in accordance with Ref-erence B. D' 5. Reposition the manipulator crane over the RCC change fixture, 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 Reference B. Update the status board to indicate the new location. 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 3 assembly to the. manipulator crane and withdraw the fuel assembly from the core. .e FHP-5-4 Page 4 of 5 f][T Revision 2 J
2. Reposition the manipulator crane over the Fuel Transfer System conveyor car frame, lower the fuel assembly into the frame and [1 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. 5 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 po.ol. m ( Q_,/ ~ q_.._ , a:. -.. -::=.. ~ ..e:.- ne.s ;- t, r.....-._. CTW v. ~.. ;-....:~. .a. ir:- : GGB FHP-5-4 Page 5 of 5. P Revision 2
ATTACHMENT 2 PORTLAND GENERAL ELECTRIC COMPANY TR(kiAhNUhEhh ~~}{ ~" November 1,19W 0 7 '! 3 Nk h. BED W Revision 2 J o A FUEL HANDLING PROCEDURE FHP-6-12 SPENT FUEL POOL BRIDGE CRANE OPERATING INSTRUCTIONS / f[t [ 7.,7 APPROVED BY DATE PURPOSE This 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. The 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 crane 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. FHP-6-12 Page 1 of 2 Revision 2
III. INSTRUCTIONS A. Position the spent fuel pool bridge crane 4.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. NOTE: Whenever raising or lowering a fuel element in the fuel rack or conveyor car frame (upender), the hoist should be operated in slow speed to reduce the possibility of damage in case of (3,/ 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 NOPTE: to the fuel elevator, do not carry the assembly over irradiated fuel rack locations. Move along the transfer canal centerline area. . GGB FilP-6-12 Page 2 of 2 Revision 2
ATTACHMENT 2 PORTLAND GENERAL E1FfLDC3MP.L10 L ) C0'3Y y l' y ) [33A"""'3 ~' TROJAN NUCLEAR PL >n,,.> November 11, 1977
ggg, Revision 2 FUEL HANDLING PROCEDURE FHP-6-14 NEW FUEL HANDLING TOOL OPERATING INSTRUCTIONS
~ //!/ Y[ 7 7 APPROVED BY DATE / / PURPOSE 1his procedure institutes a standard for use of the new fuel handling tool. I. REFERENCES A. Drawing MIS (3)-49-1, New Fuel Assembly Handling Tool B. FHP-14, Limitations and Precautions for Handling Fuel Elements [VQ 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 tovi 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. The 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. SPECI AL EQUIPMENT A. Load cell to monitor fuel element / handling tool load (0-2000 lb range minimum) for use in loading assemblics into new Fuel Storage room with fuel building crane. I ;- s) i/ FHP-6-14 Page 1 of 3 Revision 2 4-.--4
B. One Clevis and bolt to connect the handling tool and load cell to the refueling building bridge crane (25 ton hook). l l < ); 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 fue element from the container frame and inspect in accordance with Reference D. O: 6. When the inspection is complete, relocate the fuel element in the 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. FHP-6-14 Page 2 of 3 Revision 2}}

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