ML20080S796
| ML20080S796 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/30/1983 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML18155A230 | List: |
| References | |
| PROC-830930-01, NUDOCS 8310180502 | |
| Download: ML20080S796 (218) | |
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PROCESS CONTROL PROGRAM POINT BEACH NUCLEAR PLANT l
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. September 30, 1783 l
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e PDR ADOCK8310180502 P
05000266 831007 PDR s
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A. INTRODUCTION Point Beach Nuclear Plant's Process Control Program contains the current -
formula, sampling, analyses, tests and determinations to be made which will ensure that the processing and packaging of solid radioactive wastes will be accomplished in such a way as to assure compliance with all State and Federal regulations (including 10 CFR 20 and 10 CFR 71) governing the disposal of radioactive waste.
B. PROCESS CONTROL PROGRAM C0hTENTS The PCP consists of plant procedures pertaining to radioactive waste processing and handling including Chemistry & Health Physics Radioactive Radwaste Handling (RDW's) procedures, Operations' Operating Procedures (OP's), Operating Instructions (OI's) and Refueling Procedures (RP's).
The specific procedures comprising the PCP (showing procedure number, title and type) are listed in Section D.
C. PCP PROCEDURE R2 VIEW All procedures comprising the Point Beach Process Control Program shall be approved and reviewed in accordance with Section 15.6.8 of the plant Technical Specifications.
D. LIST OF PCP PROCEDURES Number Name M OP-9A Liquid Waste Process System Operation Major OP-9B Solid Wate Processing Major OI-8 Waste Solidification Minor 01-16 Blowdowa Evaporator Operation Minor OI-19 Spent Fuel Pit Demineralizcr Resin Flush-U6 Minor 01-20 Resin Transfer Cask and Resin Storage Tank-Til2 Minor 01-21 Mixed Bed (H0H) Demineralizer Resin Flush IU1A(B) and 2UlA(B) Minor 01-22 Changing Primary Coolant Micron Filters Minor OI-22A Changing Reactor Cor,lant Filter (F1) Minor OI-22B Changing Seal Water Return Filter (F2) Minor OI-22C Changing Spent Fuel Pit Filter (F6) Minor
- OI-22D Changing Seal Water Injection Filters (F39A&B) Minor OI-22E Changing Letdown Gas Stripper Filters (F60A&B) Minor OI-22F Changing Boric Acid Filters (F3) Minor OI-22G Changing Boric Acid Feed Filters 1F8 (2F8) Minor
- OI-22H Changing Boric Acid Concentrates Filters IF5A(B) and 2F5A(B) Minor OI-24 Evaporator Feed Ion Exchanger Resin Flush IU12A (B&C) & 2U12A Minor
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4 Number }iane m T
01-26 Deborating Demineralizer Resin Flush IU2A(B)
-and 2U2A(B) Minor OI-27 Cation Bed Demineralizer Resin Flush IU9 & 2U9 Minor 01-28 Condensate Demineralizer Resin Flush U3A(B&C) Minor 0I-29 Waste Polishing Demineralizer Resin Flush T108A(B) Minor 0I-67 Operation of the AMF Waste Evaporator and Waste Condensate System Minor RP-5B NLI-1/2 Spent Fuel Shipping Cask Handling and Unloading Major RDW l.1 Control and Accountability of Radioactive Materials NNSR RDW 2.1 Radioactive Material Handling Responsibilities NNSR RDW 3.1 Radioactive Waste Disposal Minor RDW 3.2 Disposal of Radioactive Weste in 55 Gallon Drums Minor RDW 3.3 Procedure to Absorb Oil with Hi Dri for Shipment to Richland, Washington, Burial Site Minor RDW 3.4 Xylene-Base Scintillation Fluid Packaging and Disposal Minor RDW 3.5 Steam Generator Sludge Lance Filter Disposal Minor i 2DW 3.6 Preparation of Radwaste Liners for Filling Storage and Shipment Minor RDW 3.7 Preparing HEPA Type Filters for Shipment Minor hDW 4.1 Receipt of Radioactive Material Minor RDW 5.) Radioactive Material Shipments - General Minor RDW 5.2 Shipment of Limited Quantities of Radioactive Materials 49 CFR 173.391 Minor RDW 5.3 Shipment of Low Specific Activity Radioactive Materials 49 CFR 173.392 Minor PIW 5.4 Shipment of Radioactive Material in Type "A",
Type "B" and Large Quantitiec 47 C;'2 173.395 Minor RDW 5.5 Shipment of Empty Spent Fuel Casks and Spent Fuel Minor RDW 5.6 Marking and Labeling Requirements for Shipments of Radioactive Material Packages Minor Vehicle Loading, Surveys and Placarding
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RDW 5.7 Procedures for Shipments of Radioactive Material Minor l
l RDW 5.8 Shipment Scheduling and Shipping Paper Preparation for Radioactive Material Shipments Minor
,, RDW 5.9 Documentation of Radioactive Material Shipping Package Inspection, Certification and l Safety Analysis Minor l RDW 5.10 Selecting Packages for Radioactive Material l
Shipments Minor i
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OP-9A MAJOR 7
Revision 8 01-12-81 LIQUID WASTE PROCESS SYSTEM OPERATION 1.0 PURPOSE This procedure describes the operation of the waste disposal system.
It is divided into the following sections:
1 911 - Processing of Waste Liquid 9A2 - Discharge of Condensate 2.0 PRECAUTIONS AND LIMITATIONS 2.1 All liquid discharges from the plant must be in accordance with
- the requirements of the Technical Specifications and other applica-ble regulatory requirements. To insure compliance, no poten-tially radioactive liquids are to be discharged except in strict compliance with a properly authorized " Permit for Discharge of Radioactive Waste".
2.2 Do not exceed 1 pCi/ml in bottoms concentration.
2.3 Wisconsin state law prohibits discharge of chemical drain tanks directly to the lake. Therefore, all discharges from this tank must be processed through an evaporator.
i 3.0 INITIAL CONDITIONS 3.1 Auxiliary steam and condensate system in operation.
3.2 Auxiliary building exhaust system in operation.
3.3 Component cooling system in operation.
4.0 PROCEDURE 4.1 The waste holdup tank is to be kept on recirculation thorugh
', the outlet filter of the waste evaporator feed pump anytime the evaporators are secured and the level in the waste holdup tank is above five percent.
4.2 The normal method of processing will be to process all water through either the waste evaporator or the blowdown evaporator.
Bypassing the evaporators is allowed only with the concurrence l of the Chemistry and Health Physics Group.
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l OP-9A s Page 2 4.3 When processing is required,~ secure recirculating the waste holdup tank and line up the waste evaporator feed pump to the specified evaporator.
4.3.1 When the waste evaporator is to be place in operation on the waste holdup tank the waste evaporator feed pump should be lined up in auto-start, allowing the pump to start and stop based on the feed tank level, and the feed rate to the
! evaporator adjusted to 2-4 gun.
4.3.2 When the blowdown ev.aporator is used for processing the waste holdt.p tank the waste evaporator feed pump should be lined up in manual and the feed rate will be controlled by adjusting the setpoint of the flow controller. If the blowdown evaporator goes high the setpoint will be adjusted down reducing the feed
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rate by the evaporator level control.
4.4 Start up the selected evaporator per the --nit instructions and process.
4.4.1 The waste evaporator distillate will be lined up to a waste condensate tank. When this waste condensate tank is at 90% it will he pumped to the other waste condensate tank via the polishing demineralizer de-signated for waste cleanup.
4.4.2 The blowdown evaporator distillate shall normally be lined up to waste distillate tank "A". When the "A" waste distillate tank reaches 80%, place the blowdown evaporator in reject. Shut the "A" waste distillate tank inlet valve (BE-72). Put the "A" waste distillate tank on local recire for 30 minutes and have Chemistry draw a sample. If acceptable (Reference Chemistry Standing Order CID-26, Revision 0) transfer "A" waste distillate tank through the polishing demineralizer designated for waste cleanup to the "B" waste distillate
- tank. If unacceptable for transfer, drain it te the waste holdup tank. Following the emptying of the "A" waste distillate tank, reopen its inlet valve (BE-72) and take the blowdown evaporator out of reject if it is making good water. If the evaporator's source is steam generator blowdown, following the recire and acceptability, the transfer will be through the demineralizer designated for processing blowdown.
4.5 Maintain chemistry control of the evaporator systems per in- .
sturctions from the Chemistry and Health Physics Group.
4.6 Upon completion of processing, return the system to its shut-down lineup.
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OP-9A Page 3 l 9A2 - DISCHARGE OF CONDENSATE 2.0 PRECAUTIONS AND LIMITATIONS 2.1 All liquid discharges from the plant must be in accordance with the requirements of the Technical Specifications and other applicable regulatory requirements. To insure compliance, no potentially radioactive liquids are to be discharge except in strict compliance with a properly authorized " Permit for Dis-charge of Radioactive Waste.
2.2 Do not discharge at a rate greater than that allowed by the permit.
3.0 . INITIAL CONDITIONS 3.1 One or more main circulating pumps in operation.
3.2 Service water system in operation lined up to the operating 3
circulating water pump discharge flume that is not in an ice
(' melt mode of operation. However, if the non-ice melt circu-( lating water system is out of service, the discharge of the service water system can be lined up to the ice melt unit.
4.0 PROCEDURE 4.1 Isolate the tank to be discharged and recirculate with one pump at the rate of 5 min /100 gallon of condensate for the waste condensate tank,.and 15 min /1000 gallon for the monitor tank, I or vaste distillate tank.
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< NOTE- WHEN WASTE DISTILLATE TANK "A" IS TRANSFERRED TO WASTE DISTILLATE TANK "B" VIA A POLISHING DEMINERALIZER, THE 15 MIN /1000 GALLON RECIRCULATION FOR SAMPLING MAY BE f WAIVED PROVIDED CHEMISTRY OBTAINS A SAMPLE WITHIN TWO I , HOURS FOLLOWING COMPLETION OF THE TRANSFER.
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4.2 Notify Cnemistry and Health Physics Group for sampling and analysis after recirculating the proper length of time.
4.3 Upcn receipt of a completed " Permit for Discharge of Radioactive Waste", comumence discharging at a rate not to exceed the rate specified by the release permit. Note level, time of commencing release, and discharge rate.
4.4 Upon completion of release, note the date and time and sign the release. Restore the system to normal and deliver the completed release permit to the Duty Shift Supervisor.
.4.5 Reinstall lock on discharge valve.
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OP-98 MAJOR Revision 12 04-13-82 SOLID WASTE PROCESSING 1.0 PURPOSE This procedure combines the Operations and Chemistry & Health Physics activities connected with drumming radioactive waste.
Use 55-gallon drums and solidification liners for packaging liquid and solid radioactive waste. Both depleted resin and liquid waste, usually evaporator bottoms, are considered solid waste when solidified. Solid wastes usually consist of both compressible and noncompressible scraps.
Filters should be treated essentially as noncompressible waste.
2.0 PRECAUTIONS AND LIMITATIONS 2.3 All solid waste shipped off-site must be accounted for as to weight, physical contents, and radioactive contente. To accomplish this each drum must be accurately identified as to physical contents by the person processing the drum. Identification of solidified liquid waste is made by the waste permit number assigned to the specific quantity of liquid and/or high level solids.
2.2 Prior to drumming any liquid, a representative sample shall be collected and analyzed to determine its radioactive content. In addition, prior to.having any high level waste (>100 mR/hr contact) encased in cement the Chemistry & Health Physics Group shall be notified. The origin and approximate amount of waste to be processed shall be included on Waste Permit Form, CHP-16.
I 2.3 In no case may liquids be shipped off-site for disposal as waste.
All liquids must be solidified or absorbed prior to closing the drums or liners for shipment.
2.4 Personnel shall wear appropriate protective clothing and dosimetry devices during processing operations.
'2*. 5 Caution should be exercised to prevent splashing of liquids onto personnel, the floor or adjacent drums.
2.6 When baling compressible wastes, caution shall be exercised to prevent entry of noncompressible items into the baler as they may damage the drum or baler.
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OP-9B l Page 2 l
2.7 Containers filled by the Atccr system should be covered with plastic to avoid contamination on the outer surfaces.
2.8 Personnel shall be aware of radiation exposure rates and adhere to the a h inistrative exposure limits and procedures set forth in the Health Physics procedures manual. A radiation vork permit is required for work in the drumming station except for short duration or monitored activities.
, 2.9 Do not allow the boric acid evaporator feed tank or the waste evaporator feed tank to go below five in:hes during the drumm:,ng operation or feed pump may cavitate. Blowdown evaporator bottoms pump P134 is automatically shut off by PI-SHLW-37 upon low level.
2.10 The contents of each container must be kept up to date by the person performing the operation of log entry on the auxiliary building log.
If relief crew personnel are performing the work, notify the auxiliary building auxiliary operator for necessary log entries.
4 2.11 Do not add hot liquid (>150'F) to drums with cement in them.
2.12 Measure radiation levels of filled drums. Inform Health Physics if contact readings are above 100 mR/hr. High level drums should be stored in a shielded area.
3.0 INITIAL CONDITIONS FOR EVAPORATOR DRUMMING 3.1 Preparation- for drumming the blowdown evaporator should be made in accordance with 0I-16.
3.2 A sample of waste must be delivered to the Chemistry Group for analysis, a waste permit number obtained, and CHP-16 initiated. The sample should be drawn and analyzed before transfer to the Atcor i system. The permit number and CHP-16 form may be taken care of after the evaporator is pumped to the Atcor system. Also, Heelth Physics must be notified prior to commencing any drumming action.
4.0 WASTE PERMIT FCRM (CHP-16) 4.1 The person filling a waste container should call control to request a waste permit number for it.
4.1.1 Relay the following information to the Duty Shift Supervisor l
or a person designated by him:
- a. Waste origin e
- b. Type of material
- c. If resin, the demineralizer bed numbers it was taken from. '
- d. Quantity of material 4
- e. Type of container
- f. Size of container
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OP-9B Page 3 i
4.1.2 Write the waste permit number in large letters on top of the container with a wasterproof marker.
4.2 Upon receiving the request for a waste permit number, the Duty Shift Supervisor or his designate should issue the number and initiate a Waste Permit Form, CHP-16.
4.2.1 Obtain a waste permit number from the serialized list found in control.
4.2.2 Initiate the waste permit by entering the information from Step 4.1.1 above.
4.2.3 Update the waste permit log in control. For resins and liquids, cubic feet or gallons should be recorded along with the origin of the waste.
4.2.4 If liquids or resins are being processe'd, arrange to have a representative sample taken to Chemistry. Check off the sampling portion of the Waste Permit worm, CM"-16. If possible, the sample should be taken acd analyzed before waste is transferred to the Atcor system.
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{( 4.2.5 Forward the waste permit form to the Nuclear Plant Engineer - Radwaste for further processing.
5.0 DRUMMING PROCEDURES 5.1 Drunning Miscellaneous Scrap (Noncompressible) 5.1.1 Noncompressible items should be placed in a drum such that the lid will fit properly and the maximum of scrap can be accommodated with it.
l 5.1.2 Delay drumming wet items until the water is evaporated. If i this is not practical, layer the items in enough cement to absorb all the water.
'- 5.1.3 When the drum is full, ensure that the lid gasket is in place and not damaged, place the lid on, and tighten.
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! 5.1.4 Attach two " Caution - Radioactive Material" labels on opposite sides of the drum.
l 5.1.5 Weigh and seal the drum. Write the weight in large numbers on the drum top with a waterproof marker.
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Page 4 5.1.6 Obtain a waste permit number as described in Section 4.0.
. 5.1.7 Enter the required information on a drum processing tag in waterproof ink. A Sharpie pen is ruitable. Attach the tag
< to the drum lid. If no tag is available, write the information on the drum top.
5.1.8 Perform a radiation survey of the drum. If it is i100 mR/hr contact, move it to a shielded storage area. If <100 mR/hr, move it to the assigned staging area. Inform Health Physics of ine location and rad level of the drum so that it can be processed for disposal.
5.2 Baling Compressible Waste L 5.2.1 Clear debris from baler vent screen. Turn on baler vent fan
- unit located on wall above baler and assure the area radiation monitor is operating.
5.2.2 Place drum on sliding shelf in baler.
- 5.2.3 Check the waste and remove noncompressible items.
5.2.4 If baling' compressible waste in a plastic bag, place end of bag over drum and cut a hole in the bottom of the bag.
5.2.5 If any of the waste is wet put a layer of dry cement about l
3" thick in the drum before compacting. After the ram is I
raised put in another 3" layer of cement.
i 5.2.6 Place the bag in the drum. Use caution when pushing bag into the drum so contamination will not blow out and contaminate the person or the area.
5.2.7 Push the drum into the baler, close the baler door and operate the compactor.
5.2.8 Continue Steps 5.2.3 through 5.2.7 until the drum is full.
. 5.2.9 When the drum is full, ensure that the lid gasket is in place and not damaged, place the lid on, and tighten.
5.2.10 Label, seal, identify, move and survey the drum as in Steps 5.1.4 through 5.1.8.
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' OP-9B v Page 5 i
5.3 Drumming Liquid Waste Using Drum Roller J
5.3.1 Pump all evaporator bottoms to holding system in the drusuning station. Identify contents with a written note and allow to cool below 100*F.
NOTE: ADDING HOT LIQUID TO CEMENT WILL CAUSE A LARGE PRESSURE BUILDUP IN THE DRUMS.
5.3.2 When draining is complete and the evaporator has been refilled with diluted solution, recirc the drumming loop to prevent possible plugging.
5.3.3 Obtain a representative sample of the liquid drawn, i preferably before the liquid is transferred to the Atcor system. Contact the Duty Shift Supervisor for a waste i permit number. This number should be used to identify both the sa:sple and drum used to solidify the waste. Forward the ,
identified samole to Chemistry for analysis. (See section 6.0 for sample logging a:J identification.)
NOTE: THE DUTY SHIFT SUPERVISOR SHOULD,THEN BEGIN PRO-
[. CESSING THE WASTE PERMIT (CHP-16) AS DESCRIBED
(. IN STEP 4.2.
5.3.4 Prepare drums for filling with liquids:
- a. Place two scrap boards or other rigid material of the correct diagonal length into each empty drum.
- b. Empty five bags of cement into each drum. Remove
- any loose cement from the drum.
5.3.5 Establish a stepoff pad at each drum fill room entrance.
5.3.6 Agitate the liquid to be drummed to ensure the resuspension of any settled solids, then fill the prepared drum with about 25 gallons of liquid utilizing a bottom filling probe. l
'* (55-gallon drum is 1.74 gallons per inch.) The volume of waste should be transmitted to the Duty Shift Supervisor for waste permit information.
5.3.7 Attach a lid to the drum after veriff ng i the sealing surfaces are clean and the proper seal is in place.
5.3.8 Place the drum on the drum roller and roll for a minimum of 45 minutes.
OP-9B Page 6 J
5.3.9 Ensure that any ces;ent on the outside of the drum is removed before it can harden. Wash with clean water or soap.
i NOTE: ANY FILM THAT IS CrN THE OUTSIDE OF THE D8tUM MAY SMEAR LOW IF THE FILM IS DRY, BUT MOISTURE IN THE FORM OF EAIN OR D8N WILL CAUSE ANY FIXED CONTAMINATION TO BE TRANSFERABLE.
5.3.10 Attach a drum processing tag and complete the applicable sections. Ensure the waste permit number noted in Step 4.1 i is put on the tag.
5.3.11 Attach two " Caution - Radioactive Materialr." stickers on opposite sides of the drum.
i 5.3.12 Perform a rad survey of the drum and move it to a storage location. Do not remove the lid at this time.
NOTE: IF DRUM RADIATION LEVELS ARE 2:100 mR/hr CONTACT IT SHOULD BE STORED IN A SHIELED AREA. NOTIFY HEALTH PHYSICS OF THE LOCATION AND RADIATION LEVEL OF THE DRUM.
g-( 5.3.13 After the drum has set up for a least eight hours, remove the lid and sprinkle dry cement into any standing water until all moisture is absorbed. Leave the lid off for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5.3.14 Add dry noncompressible scrap if available. If this is done inform the Nuclear Plant Engineer - Radwaste by note with permit number and description of added waste. ,
5.3.15 Prior to sealing the drum, verify there is no residual moisture. In either case, sprinkle additional cement dust on top to absorb any moisture that might condense inside the i drum.
1 5.3.16 Clean the sealing surfaces, verify the gasket is not damaged, and secure a lid en the drum. Survey the drums and decon accordingly.
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5.3.17 Weigh and seal the drum. (Drum handling tool weighs 160 pounds.) Write the weight in large numbers on the drum lid with a waterproof marker.
5.3.18 Obtain a vaste permit number as described in Section 4.0.
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l 5.3.19 Enter the required information on a drum processing tag in I waterproof ink. A Sharpie pen is suitable. Attach the tag to the drum lid. If no tag is available, write information on the drum lid with waterproof ink.
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5.3.20 Move the drum to the staging area as described in Step 5.1.8. If drum radiation levels are it100 mR/hr, sto e it in a shielded area and inform Health Physics.
5.3.21 Decon the drumming room and remove the stepoff pads.
5.4 Drumming of Steam Generator Blowdown Filters 5.4.1 A station shall be maintained at each unit's steam generator blowdown filter area. This station will include three 55-gallon drums. One to store new filters in. One to store concrete in. One to be used for processing used filters.
Maintenance and cleanliness of these stations is the operating crews responsibility.
5.4.2 Each time a new drum is placed into service to accept used filters, a waste permit number will be assigned to the drum by the Duty Shift Supervisor and transcribed onto the drum by the auxilary building operator. The Duty Shii't Supervisor will then fill out a Waste Permit Form, CHP-16, and forward to the Nuclear Plant Engineer - Radwaste.
5 4.3 Place two " Caution - Radioactive Material" labels 180' apart
{(( on the mid-section of the drum.
5.4.4 Each filter disposed of in the drum will be entered on the auxiliary building log for ledger maintenance by the Operations Office. This is by unit in the appropriate log entry. The waste permit number of the drum must be entered on the log each time / shift an addition is made.
NOTE: IF FOR ANY REASON THE DRUM BECOMES A RADIATION HAZARD, NOTIFY HEALTH PHYSICS OR DUTY SHIFT SUPERVISOR FOR CORRECTIVE ACTION.
5.4.5 As a layer of filters is formed, dry concrete should be sprinkled into the drum for moisture absorption and layering.
! 5.4.6 Upon filling a drum, assure adequate concrete has been added for necessary moisture absorption. Place lid on drum and tighten.
5.4.7 Remove filled drum to the staging area as described in Step 5.1.8.
5.4.8 Replace with empty drum and proceed as described in- ,
Steps 5.4.2 through 5.4.6.
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OP-9B Page 8 5.5 Processing Sludge Lance Filters 5.5.1 Refer to procedure HP 11.5 for details on processing sludge lance filters.
5.6 Processing of uther Miscellaneous Filters 5.6.1 Two stations for receiving used filters are the pill box on El. 46' of the primary auxiliary building and behind the shield wall in the drumming area. Solidification liners will usually be used as receptacles in these areas.
Blowdown evaporator bottoms filters should be disposed of in the drumming area receptacle. This liner should be identified in a unique manner in such a way that the auxiliary operator can quickly and from a distance identify it. Use of tape, paint, markers, etc., is acceptable.
Other miscellaneous filters including reactor coolant seal injection, letdown, waste feed, boric acid filters should be disposed of in the receptacle housed in the pill box.
5.6.2 Obtain a waste permit number from the Duty Shift Supervisor.
5.6.3 Write the waste permit number on the liner or drum.
5.6.4 Place two " Caution - Radioactive Material" labels 180* apart on the liner or drum.
5.6.5 Liners used to collect filters should be covered with plastic sheeting.
l 5.6.6 Before a liner is used to collect filters, put four bags of dry cement in its bottom. If a drum is used, put half a bag of cement in the bottom.
5.6.7 After each filter is added, sprinkle enough cement on it to absorb any water present.
5.6.8 When a layer of filters has formed, add enough cement to cover them with about one inch of cement.
5.6.9 All filters put into the liner in the drumming area (blowdown evaporator bottoms filters) should be noted in the appropriate place on the auxiliary building log each time per shift. The waste permit number should be entered on the log associated with the liner. The waste permit number should be posted just outside the rhield wall for the liner in use.
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OP-9B Page 9
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5.6.10 The record for filters put into the pill box station will be the auxiliary building log for waste feed filters or the operating instruction for the other individual filters. The waste permit number should be posted on the exterior pill box wall for the liner in use.
5.6.11 When either the liner gets full (not usually the case) or a partial liner is desired for solidification, an empty will be returned to the stations. At this time a waste permit number must be obtained from the Duty Shift Supervisor and assigned to the empty liner. The Duty Shift Supervisor will then send the initiated waste permit form to the Nuclear Plant Engineer - Radwaste.
5.7 Use of Package +s Other Than Drums or Liners 5.7.1 Containers other than drums or liners may be used to collect radwaste.
5.7.2 Contact the Nuclear Plant Engineer - Radwaste for details
. regarding alternative containers. See also procedure HP 11.2, Appendix J.
( 6.0 WASTE SAMPLING 6.1 All resins and liquids to be processed as radwaste should be sampled by the Operations Group.
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6.2 Samples should be taken and analyzed before waste is transferred to
' the Atcor system.
6.3 Issue a waste permit number for the waste material. If more than one container is used to ship it, additional waste permit numbers will be issued for each container.
6.4 Draw the sample. One liter of liquid or ten grams of resin.
6.5 Decon the sample container.
'6. 6 Clearly identify the sample container with the waste permit number of the bulk material. Also identify the type of material, for example,
" Resin" or " Bottoms".
l I 6.7 Place a " Caution - Radioactive Material" label on the sample.
6.8 Measure the radiation level of the sample. Attach a hot-spot tag if l
measured >100 mR/hr.
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Page 10 6.9 Deliver the sample to Chemistry.
6.9.1 Complete a Sample Identification Tag, CHP-26, and log sample in non-routine sample analysis log book. The log book and CHP-26 forms are found in the cart next to the counting room in the Chemistry Lab.
6.9.2 Attach the CHP-26 tag to the sample container.
6.9.3 Put the sample in the lead " pig" in the lab.
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1 OI-8 MINOR Revision 2 08-20-81 POINT BEACH NUCLEAR PLANT OPERATING INT.,TRUCTION NO. 8 WASTE SOLIDIFICATION 1.0 PURPOSE To provide instructions for the proper operation of the waste solidification system.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 The vaste and the processed waste should be treated as highly radioactive and contaminated. Proper Health Physics procedures (ALARA) must be observed.
2.2 Detailed cleanir-g of the mixer / feeder and fill pipe assembly upon process completic,n is absolutely necessary to prevent equipment malfunction in subsequent processing evolutions.
3.0 INITIAL CONDITIONS 3.1 Insure sufficient cement is available in cement silo to complete the l batch and that there is no " rat hole" in the cement. Cycle air j blaster to fluidize and level out cement.
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NOTE: BIN VIBRATOR MUST BE OPERATING TO ENABLE AIR BLASTER TO OPERATE. MOVING THE CONTROL SWITCH FROM OFF TO ON CAUSES ONE BLAST EVOLUTION. IF MORE THAN ONE BLAST.IS REQUIRED FOR LEVELING THE CEMENT, RECYCLE THE CONTROL SWITCH FROM ON TO OFF TO ON AGAIN.
3.2 Insure waste conditioning and sampling is complete prior to processing.
3.3 Procure a radiation work permit and insure the waste permit numbers
- are properly affixed to the liners to be processed into.
3.4 Insure all breakers on motor control center supplying the Atcor package are shut. Waste tank heater breaker should be left open
-unless waste conditioning require heater usage.
3.5 Insure ma mixer feedar drive unit, discharge valve and splatter shield assembly have been tested for operability prior to processing.
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CI-8 Page 2 3.6 Insure reactor makeup water / demineralized water pressure is available at 60-80 psig.
3.7 Insure that all personnel are evacuated from the unshielded waste processing area.
3.8 -Insure waste tank agitator is operating.
3.9 Insure pcVer is supplied to waste tank and liner level sonic probes.
f 4.0 WASTE CONDITIONING NOTE: Processing of evaporator concentrates and solid radioactive wastes (resins and sludges) for solidification is similar except in waste condi-tioning. For evaporator concentrates, this material is pumped into the waste tank, T110, and maintained at temperatures <90*F for subsequent mixing with cement. In contrast, spent resin is fed into the waste tank, T110, as slurry. To maximize the amount of solid radioactive waste material contained in the final cemented waste product, it is necessary to remove the excess liquid in the spent resin slurry.
l l- It-is most important to note that properly conditioned spent resin (that is, solid waste with the correct amount of liquid for subsequent mixing with dry cement) is that condition in which the spent resin material is just barely covered with liquid. The level indicator within the waste tank aides in identifying this condition. With excess water removed, the level indication is that of the solid material in the waste tank. Addition i
I of water will fill the void space within the settled spent resin material and the level will remain constant as observed on the waste tank level indicator on the control panel. As the liquid begins to cover the settled solids, the waste tank level indicator begins to show a level increase. ;
Water addition is then terminated.
4.1 Insure waste temperature <90*F (this does not apply if freeze point of waste is >90*F). If cooling of waste is required:
4.1.1 Run agitator 4.1.2 Line up air sparge to weste tank 4.2 Adjust the moisture content of the spent resin slurry as follows (agitator secured):
4.2.1 Secure air sparging.
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4.2.2 Open ADV-2, A0V-3, A0V-4, A0V-5, A0V-6 and A0V-12.
4.2.3 Open manual valves WS-39 and WS-38.
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OI-8 Page 3 4.2.4 Check all other valves on the control panel shut.
4.2.5 Start the waste feed pump and continue dewatering until the level in the waste tank ceases to decrease indicating that the free water level is below the solid surface.
4.2.6 Secure the waste feed pump and shut A0V-2, A0V-3, A0V-4, A0V-5, A0V-6 and A0V-12. Shut manual valves WS-38 and WS-39.
4,2.7 Open A0V-15 and cycle A0V-2, A0V-3 and A0V-4 to backwash screens. Open A0V-5 ur.:il level in waste tank just starts to rise. Secure all reactor makeup water additions.
4.3 Add chemicals to waste tank if required.
5.0 RADIOACTIVE MATERIAL ACCOUNTABILITY 5.1 If an empty liner or drum is to be filled, obtain a waste permit number from the control room.
5.2 If a partially filled liner from a previous evolution will have waste added to it, call control to update the vaste permit.
5.3 Three items should be recorded as the liner or drum is filled:
5.3.1 Waste feed pump speed (%)
5.3.2 Cement feed speed (cfm) l 5.3.3 Running time (min.) (Running time is the time the waste feed pump is pumping waste into the liner or drum.)
5.4 Forward the above information and the waste permit for the full liner to the Nuclear Plant Engineer - Radwaste.
6.0 AUTOMATIC MODE - SOLIDIFCATION PROCESSING 6.1 Turn the POWER ON selector switch to the on position (on the main control panel).
6.2 Load an empty liner onto the transfer cart.
NOTE: THE FILL PIPE SHOULD BE IN THE DISCONNECT POSITION (DETECTED BY LIMIT SWITCH) TO PERMIT FURTHER LINER POSITIONING. IF THE SWITCH IS NOT ACTUATED, THE LINER TRANSFER CART CANNOT BE ELECTRICALLY MOVED. +
6.3 Press the FILL STATION pushbutton on the main control panel and the liner will be positioned under the fill pipe.
4 OI-8 Page 4 6.4 Press the fill pipe connect pushbutton on the main control panel.
6.5 Place the INTERLOCK ON-OFF selector switch to the on position. Throw the MANUAL-OFF-AUTO selector switch to the auto position.
6.6 Select the waste feed ptmp speed which is determined by waste being processed (Position 1 is for concentrates; Position 2 is for resin).
NOTE: INTERLOCKS PREVENT ANY FURTHER AUTOMATIC SEQUENCING UIILESS -
- 1. FILL PIPE CONNECTED AND LINER IN PLACE RED PILOT LIGHTS ARE LIT.
- 2. RADIATION LEVEL ACCEPTED RED PILOT IS LIT. '(PUSH BLACK BUTTON) 6.7 Press the MIX / FEED START pushbutton and immediately observe the red
- mix / feed phase sta-t pushbutton indication light, and the mix / feed phase red running light will be lit, and the following equipment will be energized
6.7.1 The mixer / feeder will start.
1 6.7.2 The mixer / feeder discharge valve will open.
6.7.3 The cement conveyor will start.
6.7.4 The cement feeder will start.
6.7.5 The cement bin vibrator will start.
6.7.6 The waste feed pump suction from waste tank will open.
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6.7.7 The waste feed pump discharge valve will open.
6.7.8 The waste feed pump will start.
6.7.9 Ihe pump seal water valve will open.
C.8 Continue processing until the liner level controller senses a full level and terminates the process.
6.9 Immediately select MANUAL control and select the OFF position on the interlock control switch. Reopen the mixer / feeder outlet valve and empty the mixer feeder.
6.10 When mixer feeder is empty (*15 seconds), reclose the mixer / feeder oulet valve and add flush water to the mixer feeder to keep residual I
cement in mixer feeder fluid (*15 seconds). Insure mixer / feeder continues to rotate.
OI-8
' Page 5 6.11 Go to disconnect on the fill pipe, move the transfer cart to the loading station, and transfer the liner behind the shield wall.
-6.12 Return to Step 6.2 of this procedure and continue until the waste process is terminated by the no materials sensor on the waste tank
. discharge pipe.
j NOTE: AT APPROXIMATELY 30% LEVEL THE WASTE TANK SONIC LEVEL SYSTEM BACOMES ERPhTIC AND SHOULD BE TURNED OFF.
APPROXIMATE PROCESS TIMES CAN BE CALCULATED BY USING THE TANK LEVEL (%) VERSUS TANK VOLUME (GALLONS) GRAPH.
FEED RATES ARE APPROXIMATELY 5 GPM FOR CONCENTRATES, AND APPROXIMATELY 10 GPM FOR RESIN.
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6.13 Flush the waste tank, waste tank filters and lines from the waste l
tank to the mixer / feeder.
6.14 Repeat Steps 6.9, 6.10 and 6.11 of this procedure.
l 6.15 Transfer flush liner to the transfer vehicle and the transfer vehicle to the fill station, press the FILL PIPE CONNECT pushbutton and flush
- the mixer feeder several times into the liner. What residual is remaining in the mixer / feeder will have to be hand flushed after ,
Health Physics determines area radiation levels, etc. Return the flush liner to its position behind the shield wall.
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6.16 Wash down the mixer / feeder area and secure power to the control panel.
7.0 SPENT RESIN SLURRY EMERGENCY RETURN PROCEDURE If this operation is required and the mix / feed phase has been interrupted, the mixer / feeder must be flushea prior to initiating the following:
7.1 Place the POWER SELECTOR switch in the ON position.
7.2 Place the MANUAL-AUTO selector switch in MANUAL position.
,'I . 3 Place the INTERLOCK ON-OFF selector switch in the OFF position.
7.4 Water must be added in excess to obtain a thin slurry to facilitate return pumping. It is desirable to add suffi ient water to obtain equal volume of solids and liquid in the slurry. If dewatering has i
previously been accomplished, add reactor makeup or domineralized water per normal operating instruction to obtain equal volumes, if possible, of resin and excess water. The agitator start pushbutton should be pressed to insure homogenization of the resin / water slurry during this operation:
,A OR l
If the waste has not been dewatered, simply press the agitator start l
pushbutton to maintain the homogeneous resin / water mixture.
OI-8 Page 6 1
7.5 In manual mode open the following valves sequentially:
i 7.5.1 Emergency waste return pump suction valve, WS-16 7.5.2 Emergency resin return valve, WS-17 7.5.3 Ascertain that spent resin storage tank, T112, is properly connected. Open WS-34 and WS-37.
7.5.4 Reactor makeup wa~er inlet valve, WS-A0V-15 7.5.5 Waste tank outlet line flush valve, WS-A0V-6 7.6 Press the WASTE TANK DISCHARGE VALVE open and the EMERGENCY WASTE RETURN PUMP start pushbuttons.
1 7.7 After 10-15 seconds, close the reactor makeup water inlet valve,
. WS-A0V-15, and waste tank outlet line flush valve, WS-A0V-6. Initial opening of these valves, prior to resin transfer, provides a sluicing effect which makes pumping easier.
. 7.8 Monitor the transfer of waste from the waste tank by observing the decrease of waste volume using the waste tank level indicator.
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7.9 Upon completion of the transfer, place the MANUAL / AUTO SELECTOR in MANUAL and perform a waste tank flush, and return all systems and controls to the OFF position. Fluth all lines contacted by resin during the transfer operation.
8.0 EVAPORATOR CONCENTRATES EMPRGENCY RETURN PROCEDURE USING EMERGENCY WASTE
! RETURN PUMP The following relates to processing evaporato: concentrates from the waste tank with the the waste feeder inoperable. If this operation is required and the mix / feed phase has been interrupted, the mixer must be flushed prior to initiating the following.
8.1 Place the POWER SELECTOR switch in the ON position.
'8. 2 Place the MANUAL AUTO selector switch in the MANUAL position.
8.3 Place the INTERLOCK ON-OFF selector switch in the OFF position.
8.4 Press the AGITATOR START pushbutton.
8.5 Open WS-16, WS-18 and WS-39. Also select the return path and manually open required valves.
l \ 8.6 Assure that the proper flow path for the evaporator concentrates is cleared open to accept the transfer of waste, and that the tank or drian can accept the req' tired volume.
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L OI-8 Page 7 8.7 Press the WAST 72 TANK DISCHARGE VALVE OPEN and the EMERGENCY WASTE RETURN PUMP START pushbuttons.
8.8 Monitor the transfer of waste from the waste tank by observing the ,
discharge pressure being in the condition signifying flow. ;
9.0 MIXER / FEEDER EMERGENCY OPERATION A handcrank is provided for manual operation of the mixer / feeder. Use of i.he handcrank will facilitate gross remeval of cement from the mixer /
feeder. Handcranking must be immediately followed by flushing. The operator will be required to manually crank the mixer before and during flushing. Further, the operator will be required to operate the valve pushbuttons and controls on the system control panel.
9.1 Emergency operation and manual cranking of the mixer / feeder must be #
performed whenever:
9.1.1 The liner fill level indicator on the main control panel ceases to indicate a steady and normal increase in liner volume during the filling operation. This situation can be
. caused by mixer / feeder motor failure or drive failure.
9.1.2 The motor red on or green off pilot light goes out. This can be caused by a seizure in mixer / feeder motor or drive assembly. The pilot lights will go out whenever the motor overload circuit is tripped at the motor control center).
9.1.3 Should either of the above conditions occur, immediately press the system shutdown emergency stop pushbutton.
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9.1.4 Should there be a complete loss of electrical power to the solidification system while processing waste, manual cranking of the mixer / feeder is required to remove cemented waste from within the unit. Flushing to remove residual cement from the walls of the mixer / feeder will have to be done by manually opening the mixer feeder flush valve and manually opening the mixer feeder discharge valve. In that case, it is recommended that the mixer / feeder top inspection I
cover be removed immediately after manual cranking for inspection, and an outside clean water supply line (such as a hose) be brought in to flush out the mixer / feeder, if need be.
9.2 To commence manual removal of cement from the mixer / feeder the i control panel operator must:
9.2.1 Place the MANUAL-AUTO selector switch in the MANUAL position.
9.2.2 Place the INTERLOCK ON-OFF switch to the OFF position.
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OI-8 Pcge 8 9.2.3 Place the LINER FILL LEVEL INDICATOR switch to the ON position (if not previously engaged).
9.2.4 Open the mixer / feeder discharge valve.
9.2.5 Open mixer / feeder breaker at motor control center.
NOTE: FLUSH WATER WILL BE DISCHARGED INTO THE CONTAINER ALREADY IN PLACE FROM SECTION 3.3. THERE MUST BE A SUFFICIENT RESERVE VOLUME IN THE CONTAINER TO RECEIVE THE FLUSH WATER.
9.3 The operator at the mixer / feeder location must:
9.3.1 Push the "T" handled shaft in to disengage drive unit.
9.3.2 Begin manual cranking of the mixer by turning the crank handle in the clockwise direction until cement ceaties to be discharged for the unit. Cranking should be perfoi1ned for several minutes.
9.3.3 After cranking, the operator should open the mixer / feeder flush valve.
s 9.4 Crank the unit for 30 seconds. This time period allows approximately 25 gallons of flush water to clean out the mixer.
NOTE: VISUALLY MONITORING THE LINER FILL L'iVEL INDICATOR ON THE CONTROL PANEL SHOULD PREVENT OVERFILLING THE CONTAINER WITH FLUSH WATER SHOULD THE 30 SECONDS FLUSH TIME PERIOD BE INADVERTENTLY EXTENDED.
9.5 When the flush cycle is ccapleted, stop cranking and return the flush valve to the closed position.
9.6 Prior to returning de mixer to its normal operating condition, it is recommended that the unit be inspected internally for loose, unflushed cemented waste and solidified waste adhering to the mixer internals. The unit cover must be disassembled and removed to
, perform the aforementioned inspection. A separate outside flush water line may be required to wash out the mixer internals.
9.7 After the unit has been adequately cleaned cut, replace and secure the inspection cover. The mixer is now ready to continue normal operation.
10.0 CEMENT BIN LOADING 10.1 Turn the POWER ON selector switch to the START position.
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l 01-8 Page 9 10.2 Place the MAIJUAL-OFF-AUTO selector switch in CAPS position.
I 10.3 Place the INTERLOCK ON-OFF selector switch in the OFF position. j 10.4 Remove dus t cover from inlet connection on cement fill station (cement fill inlet panel).
10.5 Connect truck inlet hose to the inlet connection of the cement fill station. When the inlet hose is connected a limit switch is depressed which enstgizes the following:
10.5.1 Cement bin high level alarm circuit 10.5.2 Dust collector flexing cycles 10.5.3 Truck connected light goes on at the control panel 10.6 Start loading process (controlled fra cement truck).
NOTE: OBSERVE DUST COLLECTOR DIFFERENTIAL PRESSURE GAUGE READING.
THE DUST COLLECTOR SHOULD STABILIZE ITSELF BEIWEEN A PRESSURE OF 0.5 INCHES AND 4 INCHES W.G. IF PRESSURE RISES DURING OPERATION AND DOES NOT STABILIZE, REFER TO N, THE MAINTENANCE MANUAL FOR CORRECTIVE ACTION.
CAUTION: NEVER ALLOW PRESSURE DROP ACROSS BAGS TO EXCEED 17 INCHES W.G. MAXIhllM.
10.7 After about five minutes of filling, press the BIN VIBRATOR START button on the main panel. Allow the bid vibrator to run for five seconds and then press the BIN VIBRATOR STOP button.
10.8 Repeat Step 10.7 every five minutes. The five second action of the bin vibrator levels off the cement so that the full capacity of the tank may be utilized for cement storage.
10.9 When a high level in the cement bin is reached, the alarm horn on the i
cement fill station will sound. To silence this alarm, press alarm
- silence button and disconnect the inlet hose. All items enegized in Stsp 10.5 will be deactivated. -
- NOTE: THIS ALARM IS ASSOCIATED WITH THE CEMENT BIN FILLING l
ONLY.
l 10.10 Replace dust cover on inlet connection.
NOTE: THERE ARE TWO SEPARATE ALARM HORNS. ONE ON THE MAIN SOLIDIFICATION CONTROL PANEL ASSOCIATED WITH THE ANNUNICATOR, AND ONE ON THE CEMENT l FILL STATION ASSOCIATED WITH THE CEMENT BIN HIGH LEVEL.
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t OI-16 MINOR Revision 4 03-10-81 POINT BEACH NUCLEAR PLANT OPERATING INSTRUCTION NO. 16 BLOWDOWN EVAPORATOR OPERATION 1.0 PURPOSE To outline the operational modes'of the blowdown evaporator.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 The unit can be' shut down rapidly in emergency by closing the steam supply pressure control valve PCV-SA1. Rapid cooldown is available by opening the overhead condenser pressure control valve PRCK-LW5.
2.2 Steam supply can he taken from either unit but not both. Safety injection trip valves SA-9 and SA-10 are interlocked to prevent
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opening both valves at the same time. Opening the closed valve closes the valve previcusly open.
f 2.3 Steam supply condensate returns should be to the unit supplying steam. ,
2.4 Nor.nal distillate discharge is to the "A" waste distillate tank. The "B" waste distillate tank is maintained as clean and only receives water which has passed through the polishing demineralizers. ,
2.5 During waste processing operations, FCV-LW1 will be approximately 7 %
open with a clean feed filter. As the filter plugs, the flow control valve will open to maintain the desired flow. Change the fe-d filter when the valve position exceeds 90% open.
2.6 Steam pressure control valve PCV-SA1 should not be used for isolation except for emergency shutdown. Cooldown with the valve fully closed causes severe binding.
'2 . 7 The unit performs best if started on recirculating, then shifted to outside feed after several hours of operation.
. l 2.8 Monitor evaporator bottoms temperature continuously during shutdown to insure boron solubility.
2.9 Antifoam will be added to the evaporator at the discretion of the Duty Shif t Supervisor when foaming it evident in the drumming loop sample. Additions will usually be made in one liter increments and given at least 30 minutes for reaction.
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01-16 Pege 2 3.0 PROCEDURE 3.1 Perfer:;; initial valve linaup per CL-9F and applicable sections of component cooling, service water and condensate valve checklists.
3.1.1 Etter will not be admitted to the waste distillate tanks (BE-71 & 72 shut) until samples with high clarity, low conductance and minimal olfactory stimulation have been received from drain valves BE-106 & 106A.
3.2 Insure ts:::perature recorder TR-LW20 is in op? ration.
3.3 Line up evaporator feed from either the waste holdup tank or blowdown surge tank.
3.4 Perform the following a.utomatic valve lineup:
r""ACK-LW1 Waste feed control Manual / Shut LIC-LW2 Not used -----------
,LRC-LW3 Evaporator /reboiler level control Manual / Shut PRCK-LW5 Overhead condenser pressure control Manual /50% Open LIC-Lk8 Waste distillate accumulator level Auto /60% Level control Setpoint NOTE: THE CONDUCTIVITY INDICATOR MUST BE ENERGIZED (SWITCH OR SIDE) FOR DISTILLATE LEVEL CONTROL VALVE OPERATION. OPERATION OF 73E
- DISTILLATE REJECT VALVE LW-8A REQUIRES ADDITIONALLY THAT A HIGH CONDUCflVITY SIGNAL BE PRESENT. IF THE CONDUCTIVITY IS HIGHER THAN THE METER INDICATION (PEGGED UPSCALE), LEAVE THE METER SELECTOR IN -
ZERO AND REDUCE THE HIGH CONDUCTIVITY SETPOINT (LEFT KNOB TO ZERO)
FOR REJECT VALVE OPERATION.
FCV-L*d15 Waste distillate discharge overboard Manual / Shut LIC-LW19 Blowdown surge tank level control Manual / Shut l' Condensate receiver vacuum drag Auto l LIC-CA7 LIC-CA3 Condensate receiver pump discharge Auto
- TV-UJ51 Service water supply open TV-LW62 Service water return open ,
TV-LW63 Component cooling water supply Open TV-LW64 Component cooling water return Open ILCV-CA3 Auxiliary condensate pump discharge'. ,.
2LCV-CA3 Auxiliary condensate pump discharge J,Sameas ILCV-CA2 Condensate vacuum drag . steam
- l 2LCV-CAO Condensate vacuum drag __) (supply 3.5 Insure the distillate accumulator level is greater than 20% and start distillate pump P132 for seal water.
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01-16 Page 3 s
3.6 Establish a level in the evaporator.
3.6.1 Use the filling sources as outlined in Step 3.12 to fill to approximately 25" as indicated on level recorder LRC-LW3.
3.7 Start the evaporator circulating pump P133.
I 3.8 Place the radweste steam pressure reducing station in operation.
3.8.1 Insure the steam pressure control valve PCV-SA1 is approximately 10% open. Slowly open RS-3 to the pressure reducing station. At approximately 50 psig, null the auto and manual signals for controller PCV-SA1 and shift the controller to automatic. Open RS-3 fully.
i 3.9 Commence a slow heatup of the evaporator.
NOTE: IF THE REBOILER SHELL SIDE IS COMPLETELY FLOODED WITH ,
CONDENSATE, REDUCING THIS LEVEL SLOWLY AFTER ADMITTING STEAM j IS ONE OF THE BEST MEANS OF CONTROLLING THE HEATUP RATE. j i
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3.9.1 Open all evaporator and evaporator distillate section vents. ;
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A 3.9.2 Slowly open the evaporator steam supply i'soletion valve .
RS-15 and/or RS-21. Observe the precsure cctrol of PCV-SA1 ,
and the evaporator pressure /tamoerature.
3.9.3 Control evaporator pressure via the heatup rate by limiting direct steam ab ission or the reboiler condensata level decrease. Until all the noncondensable gases have been removed by heating and venting, evaporator pressure can not be controlhd by overhead condenser service water flows. .
l 3.10 Line up to vacuum drag the condensate drains to the main condenser of l the steam supplying smit and operate the auxiliary condensate pump '
P137 as necessary.
l 3.11 With the evaporater now heating up to normal operating temperature and pressure, perform the following steps as conditions dictate.
3.11.1 Set overhead condenser pressure controller PRCK-LW5 to ;
10 psig. As overhead condenser pressure reacher 9 psig, shift the controller to auto. After pressure has !'
stabilized, increase the setpoint on PRCK-LWS to 15 psig in small increments.
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3.11.2 When evaporator level reaches 20" null the reboiler level controller LRC-LW3 and shift to auto at that setpoint.
01-16 Page 4 3.12 Establish Feed <
l 3.12.1 Waste Holdup Tank
- a. Line up the waste evaporator feed pump P20 through the discharge filter via BE-115.
- b. Start the waste evaporator feed pump and establish feed flow to the evaporator by manual operation of feed flow controller FCV-LW1.
- c. When evaporator level indicates approximately 20",
adjust FCV-LW1 to the desired flow rate and set the controller automatic setpoint to that value and shift to auto, 3.12.2 Steam Generator Blowdown
- a. Shut both steam generator blow 4cwn throttle valvas and have the control room shut the blowdown tank outlet valve.
[ b. Open the blowdowr surge tank feed valve, BE-1 or BE-2.
N _.
- c. Open the blowdown surge tank booster pump diccharge valves, BE-11 and BE-12, and start one blowdown surge tank booster pump.
- d. Throttle open the steam generator blcwdoun valves equally or as directed by control until the desired evaporator feed rate is attained by manual operation of LIC-LW19 while maintaining the blowdown surge tank at 50% level.
- e. After the desired feed rate has been establishe6, shift the blowdown surge tank level controller LIC-LW19 to auto at a 50% level setpoint.
,, 3.12.3 Waste Distillate Tank Recirculation
- a. Open the blowdown surge tank booster pump discharge valves, BE-11 and BE-12, and start one blowdoun booster pump.
- b. Throttle open the "A" waste distillate tank drain, BE-114, until the desired evaporator feed rate is attained by manual operation of LIC-LW19 while maintaining the blowdown surge tank at 50% level.
- c. After the desired flow rate has been established, shift the blowdown surge tank level controller LIC-LW19 to auto at a 50% level setpoint.
OI-16 Page 5 3.13 Open BE-39 and establish reflux at approximately 30 gun for waste processing or approximately 15 gun on blowdown and recirculation.
3.14 Close the vent. Vent periodically and anytime the overhead condenser teraperature decreases below the saturation temperature for the evaporator operation pressure. Place the evaporator drusuning loop in cperation.
3.14.1 Verify operation of three heat tiacing circuits by operation of the test switch on the drumening area heat tracing panel.
3.14.2 Start the bottoms cooler circulating pump P136 and energize the bottoms cooler preheater at a setpoint of 160*F.
3.14.3 When the component cooling temperature for the bottoms cooler has stabilized, start the bottoms pump P134.
Interlocks and setpoints associated with the druauning loop are ss follows:
P134 bottoms pump start requires greater than 150'F on bottoms cooler component cooling outlet temperature switch TIO LW44 and distillate pump P132 operating and suction
%. pressure greater than 2 psig on DISL-LW37. Starting P134 from MCC-B45 bypasses the temperature requirement.
BE-HCV-LW18 drumming valve opening requires less than 170*F on bottoms cooler outlet temperature switch TIS-LW43.
3.15 During ar.y evaporator operation, add a mixture of Calgon deposit inhibitor CL-14 and water such that the amount of full strength Calgora added is equal to one gallon of Calgon per day for every eight '
gallons per minute boiling rate. Boiling rate equals reflux flow plus output flow. The Calgon mixture addition pump flow rate can be varied but is normally set at 20%. Less than a 20% setting produces erratic delivery. ,
4.0 EVAPORATOR SHUTDOWN _
4.1 Normal Shutdown 4.1.1 Secure reflux valve BE-39.
4.1.2 Secure steam rupply.
- a. If letdown gas strippers are operating, shut the evapcrator steam supply valve RS-15. During freezing weather, shut valve RS-21 versus RS-15 to ensure the piping in the facade does not freeze.
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OI-16 Page 6
- b. If letdown gas strippers are not operating, shut the steam pressure reducing station isolation valves RS-3 and open pressure reducing valve PCV-SA1 to approxi-mately 10% in manual to prevent valve binding during cooldown.
4.1.3 Securf2 feed and isolate as per CL-9F.
4.1.4 Place distillate accumulator level controller LW-8 in manual and shut L6'-8.
4.1.5 Place evaporator /reboiler let'al cor, troller LRC-LW3 in canual and shut LW-3.
4.1.6 Stop and pull out P137 cuxiliary condensate pump and close CA-2 and Cl-3. ,
4.1.7 Close vaste distillate tank fill valves BE-71 and BE-72.
4.2 Drumming Shutdem g- 4.2.1 Bypass circulating pump P133 evaporator low level trip.
- 4.2.2 Secure feeding the evaporator and boil down to the desired level or concentration.
4.2.3 Secure steam to prevent further bottoms concentration.
4.2.4 Drum out the evaporator bottoms per OP-9B.
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l 34 WElGHT OF SORIC ACIO (H 360g) SOLUBLE PER SATURATfD 50LuTION WElGHT V5. SATURATION TEMPERATURE (* F) 30
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BORIC ACID SOLUBILITY FIGURE 1 G
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Reviewed By OI-19 MINOR Record Updated Revision 4 02-24-78 .
POINT BEACH NUCIZAR plt.NT OPERATING INSTRUCTION NO.19 SPENT FUEL PIT DEMINERALIZER FESS FLUSH U6 1.0 PURPOSE To sluice the resin out of the spent fuel pit domineralizer (U6) .
2.0 PRECAUTIONS AND LIMITATIONS 2.1 Health Physics monitoring on the 26' level and 8' level of the auxiliary building.
2.2 No unauthorized work near the sluice line during the evolution.
2.3 Resin storage tank T112 relief valve is set at 150 psig. Monitor the cask continuously during flushing operation. Do not exceed 125 psig on resin storage tank pressure gauge, h
i 2.4 Line up monitor tank pump to reactor makeup water header, throttle
\. pump recire valve to maintain 125 psig on the reactor makeup water header.
2.5 If resin storage tank T112 pressure increases to 125 psig and holds, back flushing of the resin retention element on the vent line may be required.
3.0 INITIAL CONDITIONS i
3.1 Verify the following:
3.1.1 Camlock female cap installed on the resin storage tank T112 outlet line with padlock installed.
3.1.2 Camlock female cap installed on the resin storage tank
', T112 rinse line (center penetration) with padlock installed.
3.1.3 Resin storage tank T112 discharge valve shut (WS-34) l and padlock installed.
\
OI-19 1 Page 2 3.2 Perform the following valve lineup Initials WL-1680 Spent resin to task Open WL-1681 RMW to cask outlet Shut WL-169 7 Cask vent Open WL-1662 Service air to cask Shut SF-8043 Inlet (U6) Shut SF-901 Outlet (U6) Shut SF-795 Alt. (U6) inlet from P33 Shut SF-75 RA DH (UC) vent Shut SF-798B DH (U6) drain Shut SF-799 Resin fill tank to U6 Shut 3.3 Health Physics perform a survey of ion exchanger to be dumped to get initial readings.
4.0 PROCEDURE _
4.1 Preesurize the reactor makeup water header.
4.2 Open valve St-800 (spent resin to cask) on U6.
CAUTION: CONTAMINATED RESIN WILL FALL BY GRAVITY
,.... INTO THE RESIN DUMP LINE.
4.3 Commence flush by cracking open valve SF-802 allowing RMW to enter U6. Vary the flow using this valve as required to flush the resin into the cask. Monitor cask pressure. Do not exceed 125 psig at cask liner.
CAUTION: THE RESIN RETENTION ELEMENT ON THE VENT LINE IS LOCATED AT THE TOP OF THE CASK PROVIDING
- A MINIMUM AIR SPACE. USE CAUTION WHEN FLUSHING WITH HIGH FIDW RATES TO PREVENT OVERPRESSURIZA-TION AND LIFTING THE TANK INTERNAL RELIEF VALVE.
4.4 Continue flushing until Chemistry deusrmines the U6
( resin bed to be empty. Then close valve SF-802 (RMW to U6) and SF-800 (resin dump valve) , lock SF-800.
! 4.5 Survey all resin flush lines to check for any stray resin by comparing to initial re& dings. Flush any lines re-quiring it.
4.5.1 At 1U12C (south evaporator feed domineralizer) open BS-1167A to flush residual resin out of south dump header. Do not exceed 125 paig on resin cask liner. Than shut and lock BS-1167A.
l t
i l
01-19 Page 3
?
4.6 Perform the following valve lineup:
WL-1680 Spent resin to cask Shut WL-1697 Cask vent Open 4.7 Recharge the demineralizer per Chemistry requirernents and record.
Volume ft3 Iot #
4.8 Place the IUGi system in the condition required by the Duty Shift Supervisor.
Time /Date Chemistry Supervisor Operations Supervisor 0
9
\
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_j d Unit E Borde Acid Unit 1 Beric Acid , ,
t- Evaporater Cubicle Evapor.,ter Cubicle" "
t 1. A A 2
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Unit 2 Boric .3.cid f"'Initnorter 1 Boric.Acidi.
Cubicle
-- S.Evaccrater Cubicle Passr ceway to L'assageway l to. 1:o. 3 Fipenny No. 2 Pipaway ?>
s
)
/ RESIN CASK Unit 2 ECin1EG E Unit 1 NONREGEN HEX Cubicle HEX Cubicle , ' .l. .. ,b .
I L E/ ID l >L-l'.?.6 5 ' ,.S H 0 T TiJ
.~
V: ' :_
S H \ ELD ~ ~
_\l Noto:
If the resin beinrr durned is routed to the resin cask via the South dur.p header F. contact reodinc or the ilorth header After should be t; ken d:raninr in the sed un incre' ovsrhead of the 1: orth passe-eway before dunning.
contact readinc at this sar.e locaE.n is indic .tive that the north he : der .
also needs flunhine due to resin carryint!: on cast enc!:.
If dur.ninc via 1. orth header take contact re Adinc on South header es lained above.
\.
t -- c a u i. . .
Rivicw3d By 01-20 MINOR Record Updated .
Revision 11 01-21-82 POINT BEACH NUCLEAR PLANT OPERATING INSTRUCTICN No. 20 RESIN TRANSFER CASK AND RESIN STORAGE TANK - T112 1.0 PURPOSE The purpose of this operating instruction is to provide instructions to accomplish the following jobs related to the handling of spent resin:
1.1 Dewatering and disconnecting the resin storage tank T112 from resin transfer line.
1.2 Transfer of storage tank (T112) and cask from short line to transfer stand.
1.3 Transfer of resin from storage tank T112 to waste tank T110.
1.4 Transfer of storage tank (T112) and cask from transfer stand to the
, . . -s short line.
\q.
l.5 Connecting the resin storage tank T112 to resin transfer lines.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 The resin storage tank T112 and transfer cask should be treated as highly radioactive and contaminated. Perform a health physics survey prior to any work to determine radiation and contamination levels.
2.2 The maximum design pressure of the resin storage tank T112 is l 150 psig. Do not exceed this pressure. Note that the code safety is
' set at 150 psig and relieves into the transfer cask.
2.3 Insure cask liner pressure is reading zero psig prior to disconnecting flexible fi3.1 and vent connections.
2.4 Do not transport the resin transfer cask over the spent fuel pit.
Observe posted regulation.
2.5 Use only appropriate wire rope slings and shackles. Note the transfer cask weighs 21 ton and the storage tank full weighs approximately 3 ton for a total of 24 ton.
l
l 0I-20 '
Page 2 2.6 The storage tank outlet line protrudes from the bottom of the cask approximately six to eight inches. Exercise extreme caution when lifting off or setting down the cask to prevent damage.
2.7 Insure t. hat the resin transfer duct fans are operable during freezing
' weather, and never leave water and/or a resin water mixture in the transfer line or dewater rinse line.
3.0 INITIAL CONDITIONS Initials 3.1 Obtain a radiation work permit.
3.2 Obtain a red tag series in preparation for disconnecting the resin storage tank as follows: (Install as required)
WL-1680 Resin storage tank T112 fill Shut WL-1681 RMUW flushing water to resin storage tank T112 Shut WL-1697 Resin storage tank T112 vent Shut Service air regulator outlet isolation valve Shut 4.0 PROCEDURE 4.1 Dewater and discennect the spent resin cask per Attachment "A".
4.2 Move resin storage tank T112 with cask from short line l
(El. 8') to transfer stand (El. 67'), Attachment "B".
4.3 Transfer of resin from storage tank T112 to waste tank T110, Attachment "C". ,
4.4 Nove resin storage tank T112 with cask from the transfer stand (El. 67') to the short line (El. 8'),
Attachment "D".
4.5 Connecting the resin storage tank T112 to the demineralizers resin dump line, Attachment "E'.
ls ,
.--_.m , _ . , _ _ - - . - , . - - . _ ~ . , . - . . . , _ _ , _ . _ , - , . . - , . . . , _ . . - - ,
01-20 Page 3 ATTACHMENT "A" DJWATERING AND DISCONNECTING RESIN STORAGE TANK T112 ;
4.1 PROCEDURE Initials 4.1.1 Shut and red tag resin storage fill valve WL-1680, and reactor makeup water flush valve WL-1681.
4.1.2 Check open resin storage tank vent valve WL-1697.
4.1.3 Check service air regulator isolated, then open service air valve WL-1682 and connect the air hose (located r above the cask). _
4.1.4 open the service air regulator inlet and adjust the regulator setting to 25 psig, then open die regulator outlet valve. Watch the resin storage tank pressure gauge closely. (Relief set at 150 psig)
NOTE: UNDER' NORMAL DEWATERING CONDITIONS PRESSURE WILL
- SLOWLY INCREASE UNTIL AIR PRESSURE IS SUFFICIENT TO START MOVING WATER FROM LINER TO WASTE HOLDUP TANK WHICH AT THIS TIME A SHALL DROP IN PRESSURE WILL BE NOTED AS TH5 CASKS STARTS DEWATERING.
AFTER AMPLE TIME, CHECK TO SEE IF DEWATERING IS COMPLETE BY SHUTTING AIR REGULATOR INLET VALVE AND OBSERVE LINER PRESSURE GO TO IIRO PSIG WITH-IN A FEW MINUTES. DE'JATERIN", REMOVES WATER IN THE UPPER SECTION OF THE CASK ONLY, THE VENT RESIN RETENTION ELEMENT IS LOCATED APPROXIMATELY ONE FOOT FROM THE TOP OF THE TANK.
l 4.1.5 Once it has been determined thdt the liner has dewatered, shut the service air regulator isolation valves and red tag the outlet valve shut. Shut service air valve l
WL-1682 ar.d disconnect the air hose jumper at the connection near WL-1682 only.
I 4.1.6 When the liner pressure gauge indicates zero psig, f shut and red tag liner vent valve WL-1697. __
4.1.7 Disconnect the flexible fill and vent hose. Install canlock male caps on the flex hose and female caps on the resin storage tank connections.
\ Date Operations Supervisor .
I r
OI-20 Page 4
< ATTACHMENT "B" TRANSFER FROM SHORT LINE TO STAND 4.2 PROCEDUP.E Initials 4.2.1 Check the following items on the storage tank and cask prior to aaovement.
WS-34 Storage tank outlet valve Locked Shut Storage tank oulet Capped and Locked Storage tank vent Capped Storage tank fill capped Storage tank rinse Capped and Locked 4.2.2 Hove short line trolley and cask to the lifting location. ,
4.2.3 Rig the 1" x 30' wire rope slings to the PAB large hook and cask shackles.
CAUTION: WATCH RIGGING CLOSELY, DO 120T CROSS SLINGS IN ANY FASHION.
4.2.4 Check all closure bolts installed and 8-b ton shackles installed.
4.2.5 Remove the north section of handrail of the transfer stand (El. 67').
. 4.2.6 Pick up the resin storage tank T112 and cask frorc the short line and move to the transfer stand.
CAUTION: THE TANK OUTLET LINE PROTRUDES FROM THE BOTTOM OF THE CASK, INSURE THAT PROPER ALIGNMENTS ARE MADE WITH RIGGING PRIOR TO LIFTING OR SETTING DOWN.
'4.2.7 Set the resin storage tank T112 and cask on the transfer stand. Install one (1) bolt in the earth-quake restraints.
4.2.8 Install the north section of handrail of the transfer stand (El. 67').
Date Operations Supervisor
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0I-20 Page 5 ATTACHMENT "C" RESIN TRANSFER FROM STORAGE TANK T112 TO WASTE TANK T110 4.3 PROCEDURE Initials 4.3.1 Energize the Atcor solidification system control panel (key switch on) and turn on the resin transfer line duct fans, verify flow in the duct. (Allow at i least 30 minutes for the duct to warm up.) _
4.3.2 Insure that the waste tank T110 is empty by either of the following metnads:
Open tank manway and visually check the tank or check the remote level indication (LI-1101). Preferably use both methods if radiation levels in the tank compartment allow the visual inspection.
l 4.3.3 Check electrical controls as follows:
(Auto-off-Manual) switch in Manual Interlock switch in Interlocks on All valves indicating Shut Waste tank low level alarm Energized All motor control center breakers Closed 4.3.4 Open WS-A0V-14 waste tank T110 resin inlet valve.
4.3.5 Record waste tank (T110) room radiation level.
RI-1102 mR i 4.3.6 Survey the transfer cask openings and record radiation levels:
' Fill connection mR Vent connection mR Rinse connection mR outlet connection mR 4.3.7 Unlock the storage tank (T112) outlet line canlock cap. Using a plastic bag, remove cap, carefully collecting any liquid or resin. Monitor operation with rad-detector.
- . . . - , - ~ . - , , , . . . - . . . . - - , , , . - . _n -- - - - - - , . _ , .,,_....-~_,,..-,-,...---__._.,,_,__.._.,n.-.,,,m.,,-.,-,,,.,.. , , - _ . - . - . , - - , . , , ~ .
01-20 Page 6 Initials 4.3.8 Connect the tank outlet line to the flexible hose and lockwire the canlock connector in the attached position.
4.3.9 Remove canlock caps from the storage tank (T112) fill and vent connections.
CAUTION: RELEASE CAPS SLOWLY. STAY CLEAR ABOVE CAPS.
- 4.3.10 Connect the tank vent line to PI-1120 vent hose rig l and lockwire the canlock connector in the attached I position (see Figure 1). _ l 4.3.11 Connect the tank. fill line to the reactor makeup watar/
l dewater hose rig and lockwire the camlock connector in the attached position (see Figure 1).
1 I 4.3.12 Connect service air jumper to PI-1120 vent hose rig
- (see Figure 1). .
4.3.13 Slowly pressurize the resin storage tank to full ;
service air pressure (approximately 95-105 psig). 1 Check fittings on tank continuously, while pressurizing, for leaks.
4.3.14 Sustion an operator at the Atcor panel to observe the changes in waste tank levels and radiation levels during the transfer and rinse operation. Use FM radio comununication if available.
4.3.15 When the storage tank (T112) is fully pressurized, shut WS-37.
t ,
l 4.3.16 Unlock and open the storage tank (T112) outlet valve WS-34. Observe PI-1120 pressure rapidly decreasing and waste tank T110 level increasing (LI-1101).
i NOTE: THE TRANSFER SHOULD REQUIRE APPROXIMATELY
. 8-12 MINUTES. THE ATCOR PANEL OPERATOR SHOULD HEAR AIR VENTING IN THE WASTE TANK ROOM WHEN ;
THE TRANSFER IS COMPLETE.
1 I
NOTE: APrK0XIMATELY 1-2 CUBIC FEED OF RESIN WILL '
REMAIN IN THE TANK FOLLOWING THE ABOVE STEP.
THE REMAINING RESIN IN THE TANK AMD TRANSFER LINE WILL BE RINSED OUT.
s
, . , , _ . _ . . ._4,_.~ _ . _ . . . . - , _ . , . _ . . _ _ . _ . . . _ _ . _ . _ , , . . . _ _ _ _ _ . _ , . . _ _ _ _ . . . _ _ _ . . . _ . . . , . . . . - . _ _ . _ . _ . _ - .
0I-20 Page 7 Initials 4.3.17 Line up the waste feeder pump P141 to dewater the waste tank T110. Use this water to rinse the storage tank T112 and transfer line back to the waste tank T110 (closed loop). (Reference Atcor Dwg. 2175-D-01)
WS-A0V-2 Dewater valve Open WS-A0V-3 Dewater valve Open WS-AOV-4 Dewater valve Open WS-A0V-5 Dewater valve Open WS-A0V-6 P141 dewater suction Open WS-AOV-12 P141 dewater discharge Open WS-A0V-8 Storage tank rinse Open WS-36 Storage tank rinse Open WS-41 DI/RMW supply Open WS-18 P142 discharge Shut WS-39 Dewater to floor drain Shut ,
WS-35 RMW rinse Shut Check PI-1121 pre 5sure more than 20 psig. Seal water for P141 and record, check WS-41 open. psig 4.3.18 Start P141 and observe PI-1118 pump discharge pressure 15-30 psig. Check rinse hose at storage tank for flow noise, or throttle WS-36 to verify that flow has been established by observing P141 discharge pressure increase. Do not leave WS-36 throttled. __
4.3.19 Continue the closed loop dewater rinse cycle until the storage tank radiation levels stabilize.
i (Minimum 20 minutes). Record radiation levels.
Fill connection mR Vent connection mR Rinse connection mP.
Outlet connection mR 4.3.20 Secure P141.
4.3.21 This step will blowdown the water in the dawater rinse line and the resin transfer line, WS-34 Storage tank T112 outlet Shut WS-AOV-11 P141 discharge flush open WS-36 Storage tank rinse Shut
\
OI-20 Page 8 .
Initials Pressurize the storage tank to approximately 15 psig using service air. When pressurized, open WS-36 and blowdown the dewater rinse line to the waste tank by back flowing through the dewatering screens.
Shut WS-36.
Repressurize the storage tank to 15 psig and open WS-34, blowing down the resin transfer line and depressurizing the storage tank.
4.3.22 Disconnect the service air jumper hose used for pressurizing the storage tank and open WS-37 allowing the tank to totally vent to atmosphere.
4.3.23 Return all solidifcation system control valves to the shut position (green board at panel). >
4.3.24 Snut and lock WS-34 storage tank outlet valve.
4.3.25 Using a plastic bag to collect any liquid or resin, disconnect the resin transfer line from the stcrage tank. Install the male camlock cap in the resin transfer line and the female camlock cap on the storage tank outlet line and lock this cap.
4.3.26 Check storage tank (T112) pressure at zero psig (PI-1320), then disconnect the hose rigs from the fill and vent connections. Bag the hose connections and store on the handrall. Install the female camlock caps on the fill and vent connections. Shut WS-37.
4.3.2? Secure the resin transfer line duct fans.
l Comments; t
d e t
I i
f Date i
operations Supervisor l
l l
l
01-20 Page 9 ATTACHMENT "D" MOVE STORAGE TANK AND CASK FROM TRANSFER STAND TO THE SHORT LINE 4.4 PROCEDURE Initials 4.4.1 Check the following items on the storage tank and cask priar to movement.
WS-34 Storage tank outlet valve Locked Shut Storage tank outlet Capped and Locked ,
Storage tank vent Capped Storage tank fill Capped _
Storage tank rinse Capped and Locked _
Check all closure bolts installed and 8-\ ton shackles available. _ _ _
Remove any bolts from the earthquake restraints.
4.4.2 Rig the 1" x 30' wire rope slings to the PAB large hook and the cask 8-\ ton shackles.
CAUTION: WATCH RIGGING CLOSELY. DO NOT CROSS SLINGS IN ANY FASHION.
4.4.1 Remove the north section of handrail of the transfer stand (El. 67').
4.4.4 Pick the resin storage tank T112 with cask from the transfer stand and move t( the short line. ,
CAUTION: THE TANK OUTLET LINE PROTRUDES FROM THE BOTTOM OF THE CASK. INSURE THAT PROPER ALIGNMENTS ATE MADE WITH RIGGING PRIOR TO LIFTING OR SLTTING DOWN.
4.4.5 Install the north section of handrail of the transfer stand (El. 67').
4.4.6 Nove short line and cask to fill location. Check mark on track and souti.cest wheel aligned (green tape).
Date Operations Supervisor
l 01-20 i
Page 10 -
ATTACHMENT "E" CONNECTING THE RESIN STORAGE TANK T112 TO THE DEMINERALIZERS RESIN DUMP LINE 4.5 PROCEDUR2 Initials 4.5.1 Check the short line in the normal hookup position.
4.5.2 Remove the female camlock caps from the storage tank fill and vent connection and the male camlock plugs from the fill and vent lines, being careful to collect any liquid or resin in bags when removing these plugs.
4.5.3 Ccnnect the flexible fill and vent hose to the tank and lockwire the camlock connectors in the attached position.
4.5.4 Clear the disconnected red tags and obtain the connected red tag series as follows:
WL-1697 Storage tank vent Open C..
- WL-1681 RMUW flush Shut Shut Service air regulator outlet Rail trolley breaker Open 4.5.5 Check shut WL-1680.
4.5.6 Notify the Duty Shift Supervisor that connection is complete.
l l
Date
~ ~ ~ ~ ~ -
Operations Sup erisvr i'
l
OI-20 t Page 31 ATTACHMENT "F" RESIN TRANSFER FROM STORAGE TANK T112 TO SHIPPING LINER ON TRUCK VIA ATCOR BYPASS LINE 4.6 PROCEDURE Initials CAUTION: THIS PROCEDURE CAN BE V.MD ONLY WITH AN OPEN TOPFED SHIPPING LINER.
4.6.1 Energize the Atcor solidification system control panel (key switch on) and turn on the resin transfer line duct fans, verify flow in the duct. (Allow at least 30 minutes for the duct to warm up.)
4.6.2 Check electrical controls as follows:
(Auto-off-Manual) switch in Manual Interlock switch in Interlocks On All valves indicating Shut Waste tank low level alarm Energized All motor control center breakers closed 7-k 4.6.3 Shut WS-A0V-14 and WS-17.
4.6.4 Remove spool piece downstream A0V-14 to the Atcor tank T110 and connect resin bypass line to A0V-14 flange.
4.6.5 Connect resin dump hose (or insert into truck liner, tie down if necessary).
4.6.6 Ccnnect dewater pump to truck liner dewater connection.
Use 1" noncollapsible hose and canlock fitting to insure l
no air inleakage.
(
) 4.6.7 Place mirror / stand on cask to provide for viewing from low radiation area. (Mirror normally located in waste gas compressor room.)
4.6.8 Connect the tank outlet line to the flexible hose and lockwire the canlock connector in the attached position.
4.6.9 Remove canlock caps from transfer cask T112 vent and rinse lines.
CAUTION: RELEASE CAPS SLOWLY. STAY CLEAR FROM ABOVE CAPS WHEN LOOSENING CAPS.
4.6.10 Connect the tank vent line to PI-1120 vent hose rig and lockwire the canlock connector in the attached position (see Figure 2).
01-20 e Page 12 Initials 4.6.11 Connect tank rinse line to the reactor makeup water /
dewater hose rig and lockwire the camlock in the attached position (see Figure 2).
4.6.12 Connect service air jumper to PI-1120 vent hose rig (see Figure 2).
4.6.13 Position perscanel with FM radios at:
- a. Resin transfer cask T112, El. 66'
- b. Atcor panel at WS-A0V-14 control switch
- c. Auxiliary building truck access at truck liner.
4.6.14 Position Health Physics personnel for monitoring.
4.6.15 Slowly pressurize the resin storage tank to full service air pressure (approximately 95-105 psig).
Check fittings on tank continuously, while pressurizing, for leaks.
4.6.16 When the storage tank (T112) is fully pressurized, shut WS-37.
4.6.17 Open WS-A0V-14.
CAUTION: SHOULD ANY PROBLEMS BE ENCOUNTERED DURING TRANSFER, IMMEDIATELY SHUT WS-A0V-14 AND WS-34 AS SHOWN ON FIGURE 2. EMERGENCY FLUSH CONNECTIONS ARE PROVIDED. FLUSH THE HOSE FREE OF RESIN USING THE FLUSH CONNECTION DOWNSTRfAM OF W3-A0V-14 IMMEDIATELY UPON CESSATION OF ANY RESIN TRANSFER.
4.6.18 Unlock and open the storage tank (T112) outlet valve WS-34. Observe PI-1120 pressure rapidly decreasing and level in shipping liner increasing.
- - NOTE: THE TRANFER SHOULD REQUIRE APPROXIMATELY 8-12 MINUTES. THE OPERATOR SHOULD HEAR AIR VENTING IN THE SHIPPING LINER WiiEN THE TRANSFER IS COMPLETE.
NOTE: MONITOR THE TRANSFER OF RESIN. IT MAY BE NECESSARY TO MAINTAIN OR INCREASE THE PRESSURE IN T112 TO i
KEEP A GOOD FLOW GOING OR A RESIN PLUG UP MAY RESULT. I HOWEVER, AIR ADDITION SHOULD BE KEPT TO A MINIMUM IO LIMIT THE AMOUNT TO BE VENTED.
NOTE: APPROXIMATELY 1-2 CUBIC FEET OF RESIN WILL REMAIN IN THE TANK FOLLOWING THE ABOVE STEP. THE REMAINING RESIN IN THE TANK AND TRANSFER LINE WILL BE RINSED OUT.
l 01-20 Page 13 Initials 4.6.19 As water / resin slurry fills liner, dewater as necessary to keep the resin from stac, king.
NOTE: SHOULD LEVEL RISE TOO HIGH IN LINER UITH RESIN STILL TO BE TRANSFERRED, START DEWATER PUMP.
SECURE TRANSFER PER CAUTION STEP 4.6.17 IF NECESSARY UNTIL EXCESS WATER LEVEL CAN BE REMOVED.
4.6.20 When radiation levels at T112 indicate all resin has been transfered and visual inspection of hose indicates no more resin, allow line to flush to truck liner checking piping radiation levels in vicinity of A0V-14 to truck liner.
4.6.21 Allow pressure to decrease to zero. ,
4.6.22 Open WS-35 and flush tank T112 and resin transfer lines while monitoring radiation levels. Limit the amount of -
l water used as this must be dewatered from the shipping l
liner. Shut WS-35 when flushing is completed.
4.6.23 Shut WS-34. Allow line to drain to truck liner.
Provide vent path by use of emergency flush line down-stream WS-34.
l 4.6.24 Shut WS-A0V-14. Remove resin dump line from truck ' '
liner.
4.6.25 Dewater the truck liner as necessary per Chem & HP ,
! requirements.
4.6.26 When dewater is completed, disconnect dewater camlock.
l l CAUTION: THIS WILL BE A HIGH RADIATION AREA.
4.6.27 Cap the liner for shipment.
4.6.26 Disconnect the service air jumper hose used for i pressurizig the storage tank and open WS-37 allowing i '
the tank to totally vent to atmosphere.
i 4.6.29 Retura all solidification system control valves to the shut position (green board at panel).
1 4.6.30 Shut and lock WS-34 storage tank outlet valve.
}
6 I i
01-20
( tage 14 Initials l 4.6.31 Using a plastic bag to collect any liquid or resin, disconnect the resin transfer line from the storage tank. Install the male camlock cap in the resin transfer line and the female canlock cap on the storage tank outlet line and lock this cap.
4.6.32 Check storage tank (T112) pressure at zero psig (PI-1120), then disconnect the hose rigs from the fill and vent connections. Bag the hcst connections and store on the handrail. Install the female camlock caps on the fill and vent connections.
Shut WS-37.
4.6.33 Secure the resin transfer line duct fans.
Comments:
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Date OI-21 MINOR Record Updated Revision 7 05-18-82 MIXED BED (H0H) DEMINERALIZER RESIN FLUSH 1U1A(B) & 2U1A(B) 1.0 PURPOSE To sluice the resin cut of the "A" ("B") mixed bed demineralizer.
2.0 PRECAUTIONS & LIMIT'JIONS 2.1 Health Physics monitoring on El. 26' and El. 8' of the auxiliary building.
2.2 All work activities around area of sluice line, where radiation levt2s will increase, have been tempora,rily terminated.
2.3 Resin :tArege tank T112 relief valve is set at 150 psig. Monitor the cask continuously during flushing operation. Do not exceed 125 psig on resin storage tank pressure gauge.
2.4 Line up monitor tank pump to reactor makeup water heater, throttle pump recirc valve to maintain 125 psig on the reactor makeup water
(- h4cder.
2.5 If resin storage tank T112 pressure increases to 125 psig and holds, -
back flushing of the resin retention element on the vent line may be required.
2.6 The rubidum activity levels in the primary auxiliary building may increase during the spent resin flush if resin bed not off line for sufficient time to allow radioective decay.
3.0 INITIAL CONDITIONS 3.1 Verify the following:
', 3.1.1 Camlock female cap installed on the resin storage tank T112 outlet line with padlock installed.
l 3.1.2 Camlock female cap installed on the resin storage tank T112 rinse line (center penetration) with padlock installed.
I 3.1.3 Resin storage tank T112 discharge valve shut (WS-34) and padlock installed.
l F
- _ . . _ _ _ ._. _ _ - _ , . . _ _ . _ . _ ..- _ . _ _..___.,__,._.__-_--_,__m _ _ . _ . _ . _ _ . . - .
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OI-21 Page 2 3.2 Perform the following valve linepp: Position Initials CV-212(CV-223) "A" ("B") mixed bed inlet . .. S CV-213(CV-224) "A" ("B") mixed bed resin inlet . ........... S CV-214(CV-222) "A" ("B") mixed bed vent ... S CV-216(CV-225) "A" ("B") mixed bed outlet .. S CV-373(CV-377) "A" ("B") mixed bed outlet clrain S WL-1680 Spent resin to resin cask . . . O WL-1681 RMU water to cask outlet ... S WL-1697 Cask outlet . .. ..... .. O WL-1682 Service air to cask . . . . . . S '-
Cask air regulator isolation valve . . . . . . . . . . . . Both Shut RMU water to ion enchanger 0 -
l CV-390A ..
CV-390B RMU water to ion exchanger .. O Record demineralizer he he flushed Unit # Dcmin. #
3.3 Health Physics perform a survey of ion exchanger to be deped to get initial readings.
4.0 PROCEDURE
(
4.1 Pressurize the reactor makeup watet header.
4.2 Open CV-215 (CV-221), "A" ("B") mixed bed resin dump valve.
CAUTION: THIS WILL ALLOW " HOT" RESIN TO FALL BY GRAVITY TOWARDS THE RESIN CASK. RADIATION LEVELS FILL PROBABLY INCREASE.
4.3 open valve CV-374 (CV-376), reactor makeup water to "A"
("B") mixed bed outlet line slowly to a flow rate of about 7-15 gpm while monitoring cack pressure. Do not i
exceed 125 psig at cask liner.
CAUTION: THE RESIN RETENTION ELEMENT ON THE VENT LINE IS LOCATED AT THE TOP OF THE CASK PROVIDING A !
MINIMUM AIR SPACE. USE CAUTION WHILE FLUSHING WITH HIGH FLOW RATES TO PREVENT OVERPRESSURIZA-TION AND LIFTING THE TANK INTERNAL RELIEF VALVE.
4.4 As required by the radiation levels, vary the flow of the reactor raakeup water CV-374 (CV-376) to flush the resin into the cask.
____g
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OI-21 Page 3 Initials 4.5 When Chemistry indicates the mixed bed is empty, shut CV-374 (CV-376) and CV-215 (CV-221), "A" ("B") mixed bed resin dump valve. Lcek CV-215 (CV-221).
Lock #
4.6 Open CV-372 (for Unit 1 or 2 as appropriate) reactor makeup water to spent resin flush line, to flush out the line until Chemistry indicates the resin is all in the cask, then shut and lock CV-372. Lock # l 4.7 If a Unit i demineralizer is being dumped -
4.7.1 At T108A&B (polishir.g deminerlizer), check shut WL-1824 and WL-1823. Open WL-1840 and WL-1825 to flush out residual resin. Do not exceed 125 psig on resin ecsk line. Then shut WL-1840 I and lock shut WL-1825. Lock # l 4.7.2 At 1U12C (south evaporator feed demineralizer),
open BS-1167A to flush residual resin out of the south dump header. Do not exceed 125 psig on resin cask liner. Then lock shut BS-1167A.
Lock #
4.8 If a Unit 2 demineralizer is being dumped -
4.8.1 Between U3A and U3C (evaporator condensate demineralizers), check shut BS-1219, 1BS-1221, BS-1235B and 2BS-1221. Open BS-1218 and BS-1231A to flush residual resin out of north dump header. Do not exceed 125 psig on resin cask line. Then shut BS-1218 and lock shut 1231A. Lock # _
l 4.9 Survey all resin dump lines to check for any stray resin.
4.10 Perform the following valve lineup:
WL-1680 Spent resin to cask . . . . . . . . . S WL-1697 Cask vent . ............. O CV-390A RNU water to ion exchanger . . . . . S CV-390B RMU water to ion exchanger . . . . . S
l l
OI-21 Page 4 Initials 4.11 Recharge the demineralizer per Chemistry requirements and record:
Volume ft3 Lot # ,_
4.12 Place the reactor makeup water supply to the condition as required by the shift Supervisor.
Time /Date Chemistry Supervisor Duty shift Supervisor
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Evaporater Cubicle Evaporater Cubicle x x A 4 i
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Nota: -
If the resin beinz dumped is routed to the resin cask via the South dump header a contact iending of the North header should be taken in the ,
ovarhead of the North passareway before_ dumping. After dumping an incren. sed !
centret reading, at this same location is indicative .that the north hender. !
clso needs flushinr. due to resin carrying on past cask. l' If dumoine via Herth header take contact reading on South header as D ined above, i 1 . w. $* =
m 01-22 MINOR Revision 11 06-14-83 CHANGING PRIMARY COOLANT MICRON FILTERS INFORMATION
- a. Weight of the large gray cask - 3,850 lbs
- b. Weight of shield plug - 3,450 lbs
- c. Weight of the small yellow cask - 1,325 lbs i d. Capacity of the wooden platformed cask dolly - 4,000 lbs 1.0 PURPOSE To provide instructions for changing the following:
1.1 Reactor coolant filter (F1) 1.2 Seal water return filter (F2) 1.3 Seal water injection filters (F39A&B) '
1.4 Spent fuel pit filter (F6) 1.5 Letdown gas stripper filters (F60A&B) 1.6 Boric acid filters (1F3 and 2F3) 1.7 Boric acid feed filters (IF8 and 2F8) 1.8 Boric acid concentrates filters (1F5 and 2FSA&B) 2.0 PRECAUTIONS & LIMITATIONS 2.1 5 radiation work permit ar.d continuous Health Physics coverage is required while changing filters as the filters are highly radioactive.
2.2 Ensure each spent filter tube's inlet and end cap is removed from the filter vessel before installing new filter tubes.
2.3 Ensure the small lead filter removal cask is in a plastic bag with blotting paper prior to transporting cask to prevent spread of contamination.
1
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OI-22 Page 2 1
2.4 The small lead filter removal cask holds only three filter tubes.
2.5 As much work as possible should be performed remotely through the filter access / shield plug opening, to minimize radiation exposure.
3.0 INITIAL CONDITIONS 3.1 Obtain the following items from the storeroom for the applicable filter replacement:
3.1.1 Reactor Coolant Filter (F1)
- a. Lower media - P/N C9060-5018 (4-F-43)
Upper media - P/N C9060-5036 (4-F-54)
- b. I tube lubricant - P/N 3779-1-001
- c. 1 0-ring - P/N 4154-5373 (4-R-62)
- d. Gasket fastners - P/N 911-7857 (12 each plastic holders and metal pins)
- e. Gasket - P/N 911-9817 (gasket set includes upper and lower flat gaskets - upper gasket only is normally replaced. Return lower gasket to
~
ready stores for modification.)
3.1.2 Seal Water Return Filter (F2)
- a. 8 filter tubes - P/N C9627-6366 (4-F-32)
- b. I tube lubricant - P/N 3779-1-001
- c. 1 0-ring - P/N 4154-5373 (4-R-62) 3.1.3 Seal Injection Filters (F39A&B) l
- a. I filter and lifting device assembly - Lot #912-1846
- b. 1 tube lubricant - P/N 3779-1-001
- c. 2 0-rings - P/N A4150-1-006 (4-R-60)
- d. I backup ring - P/N A5040-1-008 (4-2-61) 3.1.4 Spent Fuel Pit Filter (F6) 7 j a. 8 filter tubes - P/N C9627-6366 (4-F-32)
- b. I tube lubricant - P/N 3779-1-001
- c. 1 0-ring - P/N 4154-5373 (4-R-62) 3.1.5 Letdown Gas Stripper Filters (F60A&B[
l l a. 6 filter tubes - P/N C9627-6742 (4-F-31)
- b. 1 tube lubricant - P/N 3779-1-001
- c. 1 flexitalic gasket - P/N 2620-1-052 (4-G-442) l l
I t
01-22 Page 3 3.1.6 Boric Acid Filters (IF3 and 2F3)
- a. 8 filter tubes, P/M N23R30 (4-F-17)
- b. 1 tube lubricant, P/N 3779-1-001 (4-L-36)
- c. 1 gasket set, P/N A2390-5001, C2620-5119, C2720-5140 (4-G-19)
- d. Nylon gasket clips, P/N 7160-5001 (4-F-52) 3.1.7 Boric Acid Feed Filters (1F8 and 2F8)
- a. I filter tube, P/N N15R35V (2-F-17)
- b. I tube lubricant, P/N 3779-1-001
- c. 1 0-ring, P/N 89305-245 (4-R-261)
> 3.1.8 Boric Acid Concentrates Filters (1F5 and 2F5A&B))
- a. 2 filter tube, 911 'i491-1
- *b. I tube lubricant., P/N 3779-1-001
- c. 2 0-ring, 915-4442-2 3.2 Align the system as required by the Duty Shift Supervisor and red tag the filter valves.
3.3 Ensure the demineralized water header is pressurized for flushing the filter vessel with a hose.
3.4 special tools are provided for filter removal from their storage area '
located on Elevation 46' of the auxiliary building.
3.5 Place blotting paper around the filter access shield plug. Also place one piece of blotting paper on the floor next to the filter vessel to set internal plates on.
3.5.1 Unit 2 (F1) only. Place blotting paper for the shield plug and the large cask.
3.5.2 Unit 2 (F1) only. Using the primary auxiliary building crane, pick up the large filter cask and move it to the area for gantry crane pickup, southwest of the shield plug. ;
3.6 Remove the shield plug from the floor using the auxiliary building crane, applicable plug removing jib crane or the gantry.
3.6.1 Unit 2 (F1) only. Remove the shield plug from the floor using the gantry. The gantry is to be positioned in an i
east-west direction and centered over the shield plug. Once l the plug has cleared the floor, move the gantry south (wbeels locked in north-south direction) to the filter cask location. Set down the shield plug, pick up the cask and move the gantry north until it is centered over the filter vessel. Set the cask on blotting paper and rotate two wheels (opposite corners of gantry) 90*, to lock the gantry i in position.
~ . ,,
01-22 Page 4 3.7 Ensure the large filter cask cover is removed prior to transporting used filters and that the cask will accommodate all of the spent filters.
3.8 The small yellow filter cask is utilized for seal injection filter removal.
4.0 PROCEDURE 4.1 Follow the appropriate operating instruction for the filter to be changed.
4.1.1 OI-22A, Changing Reactor Coolant Filter (F1 4.1.2 OI-22B, Changing Seal Water Return Filter (F2) 4.1.3 OI-22C, Changing Spent Fuel Pit Filter (F6) 4.1.4 OI-22D, Changing Seal Uater Injection Filters (F39A&B) 4.1.5 OI-22E, Changing Letdown Gas Stripper Filters (F50A&B) r' 4.1.6 OI-22F, Changing Boric Acid Filters (IF3 & 2F3)
- 4.1.7 OI-22G, Changing Boric Acid Feed Filters (lF8 & 2F8) 4.1.8 OI-22H, Changing Boric Acid Concentrate Filter (lF5 & 2F5A&B)
Reviewed Cy OI-22A MINOR Eecord Updated Revision 3 02-24-78 CHANGING RP.: ACTOR COOLANT FILTER (F1)
Initials INFORMATION: a. Weight of cask - 3,850 pounds
- b. Weight of shield plug - 3,450 pounds
- 1. All initial conditions of OI-22 have been met.
- 2. Open the filter vessel drain valve using the small extension wrench and special valve operating tool.
- 3. Open the filter vessel vent valve using the small extension wrench and special valve operating tool.
- 4. Allow the filter vessel to drain for at least 15 minutes.
- 5. Using the small extension wrench with a 15/16" socket attached, loosen, but do not remove, the vessel closure
.. bolts (12 turns) .
- 6. Using the small extension wrench with the filter vessel cover 4
I handwheel operating tool attached, turn the cover lifting handwheel clockwise to its stop and swing the cover aside.
- 7. Using the sinall extension wrench with the special one inch '
slotted socket attached, loosen the "T" bolts which retain the separator plate and swing the "T" bolts aside.
- 8. Lay blotting paper and plastic as necessary to protect the floor and cask from drippings.
- 9. Move the large filter cask to a location near the portable gantry for Unit 1 only.
- 10. Pick up the large filter cask with the gantry and position it over the filter. Lower the cask until the cask gate is lower than the ceiling of the cubicle, then open the cask gate.
- 11. Thread a rope and "S" hook through the cask.
- 12. From the elevation 46' , lower the rope with attached "S" hook and catch the bail on the separator plate.
- - - - . - . , , . . -, ..w - -- - . , , , , . -
1 OI-22A Page 2 Initials
- 13. Lift the separator plate and attached filter assembly out of the filter room and into the filter cask. Maintain the fil--
ter weight on the lift rope.
- 14. Close the gate. Raise the cask until it clears the floor, cover the bottom of' tne cask with plastic, move the cask west and set it on blotting paper.
- 15. Lift the filter element up by using the rope and hook so that the metal top of the element sits on the lid of the cask.
Clamp the lower filter section with the long handled wedging tool.
- 16. Unscrew the filter assembly from the separator plate by rotating the separator plate counterclockwise.
- 17. Put the lid back on filter cask.
- 18. Put shield plug back into place.
- a. Unit 2 only. Re-align all four wheels in north-south
- direction and lock them.
- b. Unit 2 only. Pick up cask and move to marked spot and set it down. _
- c. Unit 2 only. Move chain fall to east and pick up shield plug. Move gantry to north and put shield plug into place.
- 19. Transfer the filter elements to an " empty" resin liner. _
- 20. Flush the filter vessel with domineralized water to remove
! any dirt left behind.
- 31. Inspect the filter vessel and separator plate for damage.
- 22. Replace the da.naged gaskets or 0-rings. Use silicone grease (Dow Corning #41 or equal) only on the O-rings. Insure the
, flat gaskets and their mating surfaces are free of any grease.
- 23. Apply a light coat of lubricant (Dow Corning #41 or equal) to the O-rings of the new filter and assemble to the separator plate. Tighten tha filter assembly to the separator plate by hand only. The bottom cap should dimple slightly from the coupling rod protruding through the coupling nut.
- 24. Guide the assembled filter into the filter housing.
- 1. - - . - - - - - - . _ _ . . - _ _ , _ _ _ _ , . _ , , . , , _ , , , _ _ _ , , . _ ,__ . _ _ , _ ___ _
r OI-22A Page 3 Initials
- 25. Swing the four (4) "T" bolts into position and tighten evenly.
- 26. Swing the filter vessel cover into position. Turn the hand-wheel counterclockwise until the cover is seated and the linkage sufficiently free so as not to interfere with cover bolt torqueing.
- 27. Clean and lubricate the cover closure bolts.
- 28. Utilizing the diagonal sequence and 25 foot-pound increments, torque the cover closure bolts to 75 foot-pounds.
- 29. Inform the control rocm of your intent to fill and vent the filter vessel.
- 30. Close the drain valve and crack open the filter inlet. When water issues from the vent, close it and check for leaks.
- 31. When the leak check is satisfactory, obtain permission from the Duty Shift Supervisor to clear any red tags and place
_s the filter on the line.
- 32. Clean up the area, check for contamination and replace light bulb in cubicle.
REMARKS:
Performed by o
Duty Shift Supervisor
, - , . - . - , , . --.- .,,.n,,-,-., , , - - - - - - , , , , , - , , . . .-,, , , , - , , , , . ,
Reviewed Zy 01-223 1 MINOR Record Updated Revision 1 02-24-78 CHANGING SEALWATER RETURN FILTER (F2)
Initials
. 1. All initial conditions of 0I-22 have been met.
- 2. Open the vessel drain valve.three (3) turns using the small extension wrench and the special valve opening attachment.
- 3. Open the vessel vent valve three (3) turns using the small extension wrench and the special valve opening attachment.
Allow vessel to drain for approximately 15 minutes.
- 4. Loosen twelve (12) turns but do not remove the vessel closure bolts using the small extension wrench with 15/16" socket attached.
- 5. Using the small extension wrench with special handwheel rotating attachment, turn the cover handwheel clockwise until handwheel stops turning and, cover assembly swings aside.
- 6. Using the small extension wrench with special 1" slotted socket attached, loosen the "T" bolts which retain the separator plate.
-- Swing the "T" bolts aside and remove the separator plate by using the special lifting tool. Set the plate on the floor on blotting paper next to the vessel.
- 7. Place the steel supports across the shield plug opening and place the small lead cask on the supports in line over the
-filter vessel.
- 8. Attach filter tube lifting tool to small cask and lower tool down to pick up a filter tube being sure of which line holds filter and which line releases filter. Seat tool on top of a filter with release line, then pull hold line which grips filter and using same line pull filter gently up into small l
cask. Rotate the indexing mechanism in the cask 90' then l release the filter by pulling the release line and slacking t'he hold line. Repeat above steps to remove each filter tube, checking each filter tube for its top and bottom and caps.
- 9. When the small lead filter cask is full, (3 filter tubes) place it in a plastic bag with blotting paper and transport it to large lead filter storage cask.
- 10. Support it over the large cask, remove plastic bag, and rotate indexing mechanism to allow filters to fall into large cask.
!- l l
- l. .
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OI-22B Page 2 Initials
- 11. Repeat steps 8 through 10 as necessary until all filter tubes have been removed from filter vessel.
- 12. Fluah filter vessel with demineralized water to remove all dirt left behind.
- 13. Inspect filter vessel for damage and insure that all metal end caps f om previous filter tubes have been removed.
- 14. Apply a light coat of lubricant (Dow Carning 41) to 0-rings of new filter tubes and install filter tubes with 0-ring end up.
- 15. Install new O-ring separator plate and position plate over filter tubes pushing down to seat plate onto filter tubes.
- 16. Swing four (4) T-bolts into position and tighten evenly.
- 17. Swing filter vessel cover into position. Turn handwheel counter-clockwise until cover is seated, being careful not to detach handwheel from lead screw.
. 18. Clean and lubricate cover closure bolts. Tighten bolts in diagonal sequence torqueing each bolt to 75 ft/lbs.
- 19. Close drain valve. Fill and vent filter vessel being careful of radioactive gases. Obtain permission from Duty Shift Supervisor to remove red tags.
- 30. Apply system pressure to filter vessel and check for leaks.
Cut in filter and shut bypass.
- 21. Insure shield plug gets installed and area is cleaned up and checked for containment.
l Date UNIT Supervisor Reviewed By
(
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I Reviewed By OI-22C MINOR Record Updated Revision 1 02-24-78 CHANGING SPENT FUEL PIT FILTER (F6) l Initials
' 1. All initial conditions of 01-22 have been met.
- 2. Open the vessel drain valve three (3) turns using the small extension wrench and the special valve opening attachment.
- 3. Open the vessel vent valve three (3) turns using the small extension wrench and the special valve opening attachment.
Allow vessel to drain for approximately 15 ininutes.
- 4. Loosen twelve (12) turns but do not remove the vessel closure bolts using the small extension wrench with 15/16" socket attached.
- 5. Using the small extension wrench with special hardwheel rctating attachment, turn the cover handwheel clockwise until handwheel stops turning and cover assembly swings aside.
- 6. Using tha small extension wrench with special 1" slotted socket attached, loosed the "T" bolts which retain the separator plate.
Swing the "T" bolts aside and remove the separator plate by using the special lifting tool. Set the plate on the floor on blotting paper next to the vessel.
- 7. Place the steel supports across the shield plug opening and i place the small lead cask on the supports in line over the filter vessel.
- 8. Attach filter tube-lifting tool to small cask and lower tool
- down to pick up a illter tube being sure of which line holds filter and which line releases filter. Seat tool on top of a filter with release line, then pull hold line which grips filter and using same line pull filter gently up into small Rotate the indexing mechanism in the cask 90', then
~
cask.
release the filter by pulling the release line and slacking the hold line. Repeat above steps to remove each filter tube, checking each filter tube for its top and bottom end caps.
1
- 9. When the small lead filter cask is full, (3 filter tubes) place'it in a plastic bag with blotting paper and transport ,
- it to large lead filter' storage cask. ,_
- 10. Support it over the large cask, renwe plastic bag and rotata indexing mechanism to allow filter to fall into large cask.
A 11. Repeat steps 8 through 10 as necessary until all filter tubes have been removed from filter vessel. .
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OI-22C !
Page 2.
Initials
- 12. Flush filter vessel with domineralized water to remove all dirt left behind.
- 13. Inspect filter vessel for damage and insure that all metal and caps.from previous filter tubes have been removed.
- 14. Apply a light coat of lubricant (Dow Carning 41) to 0-rings of new filter tubes and install filter tubes with 0-ring end up.
- 15. Install new O-ring in separator plate and position plate over filter tubes pushing down to seat plate onto filter tubes.
- 16. Swing four (4) T-bolts into position and tighten evenly.
- 17. Swing filter vessel cov<,r into position. Turn handwheel counter-clockwise until cover is seated, being carefule not to detach handwheel from lead screw.
- 18. Clean and lubricate cover closure bolt. Tighten bolts in diagonal sequence torqueing each belt to 75 ft/lbs.
l(
C 19. Close drain valve. Fill and vent filter vessel being careful of radioactive gases. Obtain permission from Duty Shift Supervisor to remove red tags.
- 20. Apply system pressure to filter vessel and check for leaks.
Cut in filter and shut bypass.
- 23. Insure shield plug gets installed and area is cleaned up and checked for contamination.
15 ate Unit Supervisor Reviewed By
.a s- a.- _- , ._ _ .g Reviewed By OI-22D MINOR Record Updated Revision 3 01-22-80 POINT BEACH NUCLEAR PLANT OPERATING INSTRUCTION NO. 22D CHANGING SEAL WATER INJECTION FILTERS (F39A&B)
Initials
- 1. All initial conditions of OI-22 have been met.
- 2. Open the filter vessel drain and vent valves and allow the filter to drain for one-half hour.
- 3. Using the large extension wrench and two inch socket, loosen, but do not remove the filter vessel closure bolts (12 turns).
- 4. Using the large extension wrench with the filter vessel cover handwheel operating tool attached, turn the handwheel clockwise to its stop and swing the cover aside.
- 5. Remove the yellow filter cask top plate and open the lower access. (1-1/2" nuts for tight closure, 3/4" square shaft to open or close.)
- 6. Position the cask above the filter access and pass the filter j lifting line through it. Connect a three to four foot piece of j line with a 1/4" "S" hook attached. (Step 10)
- 7. Catch the filter lifting rig with the hook, then maintain a tight line to insure the connection is not lost.
- 8. Lower the cask to a centered position over the filter vessel with the bottom of the cask well into the access opening to j provide as much shielding as possible.
- 9. Raise the filter into the cask and close the cask access.
- 10. , .Release the short length of rope into the cask.
I
- 11. Plastic bag the cask and remove it to the intended filter l depository for disposal of all items in the cask.
- 12. Flush the filter vessel with water to remove any dirt left }
behind. .
- 13. Inspect the filter vessel seal areas for damage.
t
~. . .. _ -- .-. . - - _
l l
OI-22D Page 2 Initials
- 14. Apply a light coating of silicone lubricant (Dow Corning #41 or j equal) to the 0-ring of the new filter. Install the filter and i attached spacer / lifting device by lowering on a line from above.
Guide to a mating with the stub tube. -
- 15. Remove the 0-ring retainer plate from the vesse.1 nead. I
- Inspect the 0-rings for excessive flattening or other damage. (
Replace as necessary. i NOTE: IF 0-RING / BACKUP RING REPLACEMENT IS REQUIRED, PLACE THE NEW 0-RING IN THE 23TAINER PLATE GAOAVE AND CHECK THE FIT. IF THE OUTSIDE DIAMETER OF THE 0-RING !
. CONTACTS THE OUTER EDGE OF THE RETAINER PLATE GROOVE, ;
THE BACKUP RING SHOULD NOT BE USED. ,
- 16. Lubricate the 0-rings. Reattach the 0-ring retainer plate f to the vessel head. (The wide 0-ring groove should be next j to the head.) :
i
- 17. Swing the filter vessel cover into position. Turn the hand- l
(~
wheel counterclockwise until the cover is seated and the l linkage sufficiently free so as not to interfere with cover ;
bolt torqueing. I
- 18. Clean and lubricate the cover closure bolts. !
- 19. Torque the cover closure bolts in a diagonal sequence to i 386 ft/lbs. :
i i 20. Inform the control room of your intent to fill and vent the filter vessel.
- 21. Close the drain valve and crack open the filter inlet. When ,
water issues from the vent, close it and check for leaks. ! i t
i
- 22. When the leak check is satisfactory, obtain permission from ;
i ~the Duty Shift Supervisor to remove any red tags. j
- 23. Install the shield plug, clean up the area, and check for contamination.
q REM &RKS:
1 f
Date Unit ,
Performed By .
j Duty Shift Supervisor
- .: . r .- - .-.- -.-..- .- - - _ ... - -- - . - - - . . - _ . . . . _ . .
- Review:d By OI-22E MINOR Record Updated Revision 1 02-24-78 CHANGING LETDOW GAS STRIPPER FILTERS (F60A & B) 4 Initials 1.' All initial conditions of OI-22 have been met.
2.- ' Attach hose to drain valve and direct to nearest floor drain.
Open drain valve.
- 3. ' Open vent valve and allow filter to drain for .approximately
[ 15 minutes.
- 4. Loosen three (3) turns but do not remove the vessel closure nuts using the small extension wrench with 15/16" socket attached. Swing each nut and bolt assembly aside, free from vessel Cover.
- 5. Using the small extension wrench e.nd the special lifting tool lift hinged cover out of way.
- 6. . Place the steel supports across the shield plug opening and place the small lead cask on the supports in line over the filter vessel.
. .7 . Attach filter tube lifting tool to small cask and lower tool down to pick up a filter tube being sure of which line holds filter and which line releases filter. Seat tool on top of a filter with release line', then pull hold line which grips filter and using same line pull filter gently up into small cask.
Rotate the indexing mechanism in the cask 90', then release the filter by pulling the release line and slacking the hold '
line. Repeat above steps to remove each filter tube, checking each filter tube for its top and bottom end caps. _
- 8. - When the small lead filter cask is full, (3 filter tubes) l place it in a plastic bag with blotting paper and transport it to large lead filter storage cask.
- 9. . Support is over the large cask, resove plastic bag and rotate.
Indexing mechanism to allow filters to fall into large cask.
- 10. Repeat 7 through 9 as necessary until all filter tubes have been removed from filter vessel.
- 11. Flush filter vessel with domineralized water to remove all dirt left behind.
N '
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OI-22E Page 2 Initials
- 12. Inspect filter vessel for damage and insure that all metal end caps from previous filter tubes have been removed.
- 13. Apply a light coat of lubricant (Dow Carning 41) to 0-rings of new filter tubes and install filter tubes with 0-ring end down.
- 14. Install new trexitallic gasket on filter vessel 'lange insuring flange and cover surfaces are clean.
- 15. Swing filter vessel cover into position. Clean and lubricate cover closure bolts. Tighten nuts in diagonal sequence torqueing each nut to 75 ft/lbs.
- 16. Close drain valve. Fill and vent filter vessel being careful of radioactive gases. Obtain permission from Duty Shift Supervisor to remove red tags.
- 17. Apply system pressure to filter vessel and check for leaks.
Align system per Duty Shif t Supervisor.
- 18. Insure shield plug gets installed and area is cleaned up and checked for contamination.
Date Unit
(
( Supervisor j Reviewed By O
1 l
l
Reviewed By OI-22F MINOR Record Updated Revision 0 09-14-78 CHANGING BORIC ACID FILTERS (F3) 1.0 PURPOSE To provide detailed instructions for changing the boric acid filters (F3).
3.0 PRECAUTIONS AND LIMITATIONS In addition to the items mentioned in Section 2.0 of OI-22, note the following:
2.1 The filter vessel ve,t and drain could well be plugged. This proceduo has been written to open the vessel in a full but depressurized condition. Thiiprocedure a.sumes that the radiation exposure does not warrai:t an extensive cleaning ,
operation of the vent and drain piping.
3.0 INITIAL CONDITIONS Initials l
l ,, In addition to the conditions of Section 2.0 and 3.0 of CI-22, f insure the following are met:
3.1 A one-half inch drive reversable impact wrench is available to remove the filter ussel cover bolts.
(15/16" socket) 3.2 Position the large filter cask at the filter area entrance using the manually-operated cask cart.
3.3 Approximately fifteen feet of one-half inch diameter l
rope, knoted for grip, is available to lift the filter
! retention assembly from the vessel (approximately 75 pounds). The easiest hookup and straightest pull can be made using the lifting roop attached to the center of a two foot piece of rope which has hooks attached to each end.
1
! 3.'4 Establish step-off pads well away from the filters at the filter area entrance.
3.5 Usc large plactic bags to double bag the large filter cask interior. l 3.6 Rig a reactor makeup water hose to the filter area.
- s l
l
OI-22F '
Page 2 4.0 PROCEDUPE Initials 4.1 BypsF , then isolate the selected filter.
I 4.2 Monitor the filter vessel pressure on PI-109, filter outlet pressure, and observe a pressure decrease due to cooling as work proceeds.
4.3 Depending on the circuit connections, disconnect or have electricians disconnect the heat tracing circuits involved in removing the vessel cover.
4.4 Use full face respirators as protection against the insulation dust, then remove the cover insulation.
(Two sections, match strk for reinstallation) 4.5 Lay several thicknesses of blotting paper on a plastic backing beside the filter vessel to receive the filter assembly.
4.6 Observe that the filter vessel pressure has decreased by comparing inlet and outlet pressures.
4.7 Operate a boric acid transfer pump and verify no pressure increase in the filter vessel.
4.8 Dress in full plastic protective clothing and remove the vessel cover closure bolts.
4.9 Turn the vessel cover handwheel clockwise to raise and swing the cover aside.
4.10 Using a man above the filter, lift the filter retention assembly and lay it on its side on the blotting paper.
4.11 Remove the individual f 4,lter elements from the asser.bly l hy sliding the r pring ::ap end of the element off the retention plate.
4.12 Retain the spring caps and V-shaped stiffners, bag the filters and place in the filters cask.
4.13 Move the filter retention assembly to the floor drain, then hose them down and inspect gaskets and seal surfaces.
4.14 Replace the gaskets or gasket retention clips as re-quired. Leave the gasket surfaces dry.
_- ,-,.. .,, ,- _ __--. .. - ,.- _ _ _.- ,._ _ -_.... _ _-_,_.- - _ _.__ _ ___._-..., _ .___._.,______ _ _ . ,_._ m - _ _
(
OI-22F Page 3 Initials 4.15 Install the new filter elements in the filter retention assembly using a putty knife to " shoe-horn" the end cap springs onto the bottom plate.
4.16 Clean the filter vessel sealing flanges, wash the bolt holes clean, then hoist the filter assembly into the vessel and replace the vessel cover.
4.17 Clean and lubricate the vessel cover bolts.
4.18 Torque the vessel cover bolts to 75 ft/lbs using a diagonal sequence and 25 ft/lb increments.
4.19 Crack open the filter inlet valve and start a boric acid transfer pump to check for leaks.
4.20 Return the filter lineup to normal and continue recircu-lation for ten minutes to remove air trapped in the filter vessel.
4.21 Transport the used filters to the pill box liner.
4.22 Wash down the boric acid splash area, then reinstall the heat tracing insulation. Utilize full-face respirators as protectica against the insulation dust.
4.23 Reccnnect the heat tracing circuits.
4.24 Decontaminate the area as required.
l I
l l
t e.
O 1
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Reviewed By OI-22G MINOR Record Updated P.evision 0 07-17-80 POINT BEACH NUCLEAR PLANT OPERATING INSTRUCTION NO. 22G CHANGING BORIC ACID FEED FILTERS 1F8 (2F8)
- 1. All initial conditions of 01-22 have been met.
i
- 2. Open vessel drain and vent. Allow vessel to drain for approximately five minutes.
- 3. Loosen four (4) head bolts. Rertove head.
l 4. Manually lift out old element and dispose of at proper location.
Denote location
- 5. Inspect vessel.
[ 6. Apply a light coat of lubricant to new 0-ring, install new filter
(, element, and resecure closure head.
- 7. Close drain. Fill and vint vessel.
- 8. Clear red tags if required and apply system pressure to filter vessel and check for leaks.
Date Unit Supervisor
, Reviewed by 4
m._ . _ , - - . . . - . . _ . , . _ . _ _ , . . , . - _ _ . . . -. - - . _ . - - - _ _ . . . - _ . . , , . - - . . - . . - , _ . . - - -
Reviewed By OI-22H MINOR Record Updated Revision 0 06-22-83 CHANGING BORIC ACID CONCENTRATES FILTERS 1F5&&B (2FS)
- 1. All initial conditions of 01-22 have been met.
- 2. Iools needed
- a. 15/16" wrench and/or socket
- b. 1/2" banding kit
- 3. Flush filters with residual makeup water or demineralized water to concentrates tank until there is a level increase of greater than 20%.
- a. Residual makeup water can be used by filling appropriate boric acid evaporator feed tank and pumping same through filters,
- b. Demineralized water from connection in Unit 2 sample room to inlet pressure gauge on filters.
- 4. Deenergize heat tracing circuits by removing the fuse in heater control box.
NOTE: REMOVAL OF FUSE MIGHT BLOW THE FUSE. CHECK THAT THE FUSE IS GOOD AFTER REPLACING IT.
- 5. Isolate filters inlet and outlet valves.
- 6. Drain filter vessel to floor drain.
- 7. Remove filter vessel insulation and heat tracing.
NOTE: INSULATION AND HEAT TRAC 7NG COMES OFF IN TWO SECTIONS. ;
- 9. Manually lift out old filter and dispose of at proper location.
- 10. Inspect and clean vessel, top flange and seating narface.
- 11. Apply light coat of lubricant to new 0-ring, install new filter element and resecure top flange.
OI-22h .
Page 2
- 12. Close vessel drain valve. Fill, vent and leak test top flange with either feed tank pump discharge pressure or demineralized water header pressure.
- 13. When tested satisfactory, valve in for normal operation. Inform PAB Auxiliary Operator and Control Room of filter status.
NOTE: FLUSH WATER IN BORIC ACID CONCENTRATE TANK SHOULD BE PUMPED BACK TO 2 HOLDUP TANK.
Date Unit Supervisor Reviewen By e .. , , -- . - ,_ , . ._ . .. ,. , ,.,, , , _ ,,,.._____._.,.._._._m. _.
k, IMAGE EVALUATION
(( 4 f4, g 7 v'>: 1Es11AaoE1 cm13) 4)p+p# %y f;8' 1.0 F2UE sfljHE i.i [m llil!n 1.8 1.25 1.4 1.6 4 150mm >
4 6" >
+sk?w,7ze +7/ a4% /$
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$ o k> IMAGE EVAL.UATION g[9 4 pf e + 1es11Amee1 <m133 (([y f,+4,,,
,,9 %,,k?
l.0 F[EnDu' @ Na 1.1 [' IIllE l' l.8 I
l.25 1.4 1.6 4 150mm >
4 6" >
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Reviewed Ey OI-24 MINOR
- Record Updated ,. Revision 5
. 02-24-78
~
POINT BEACH NUCIEAR PLANT OPERATING IFSTRUCTION NO. 24 EVAPORATOR FEED ION EXCHANGER RESIN FLUSH 1U12A, B r, C_ AND 2U12 1.0 PURPOSE To sluice the resin out of the 1U12A, B, C and 2U12 ion exchangers.
2.0 PRECAUTIONS AND LIMITATIONS 2 . l' Health Physics monitoring on the 26' level and 8' level of the auxiliary building.
2.2 No unauthorized vark near the sluice line during the evolution.
2.3 Resin storage tank T112 relief valve is set at 150 psig. Monitor the cask continuously during flushing operation. Do not exceed 125 psig on renin storage tank pressure gauge.
2.4 Line up monitor tank pump to reactor makeup water header, throttle l
pump recire valve to maintain 125 psig on the reactor makeup water header.
~
2.5 If resin storage tank Tll2 pressure increases to 125 psig and holds, back flushing of the resin retention element on the vent line may be' required.
2.6 Do not operate the gas, stripper feed ptunps during this evolution.
3.0 INITIAL CONDITIONS l 3.1 Verify the following:
n 3.1.1 Camlock fema'.a cap installed on the resin storage tank T112 outlet line with padlock installed.
l .
j 3.1.2 Camlock female cap installed on the resin storage tank Til2 rinse line (center penetration) with padlock installed.
3.1.3 Resin storage tank T112 discharge valve shut (WS-34) and padlock instal'.ed.
1
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OI-24 l Page 2 I l
3.2 Perform the following valve lineup on the required ion exchanger:
Record domineralizer to be flushed Initials
' lU12A BS-1190 Inlet Shut 73-1193 Outlet Shut or 1U12B BS-1185 Inlet Shut BS-1196 ,
Outiet Shut or IU12C BS-1165 Inlet Shut BS-ll66 Outlet Shut or 2U12 BS-ll74 Inlet Shut 3S-1164 Outlet Shut WL-1680 Spent resin to cask Open WL-1681 RMW to cask outlet '
Shut WL-1697 Cask vent Open WL-1682 Service air to cask Shut 3.3 Health Physics perform a survey of ion exchanger to be dumped to get initial readings.
g-(_. 4.0 PROCEDURE 4.1 Pressurize the rear tor ndeup water header.
4.2 Open the resin dung valve on the selected ion exchanger.
CAUTION: THIS WILL ALLOW " HOT" RESIN TO FALL EY GRAVITY INTO THE RESIN DUMD LINE.
4.2.1 1U12A 2S-1194 open 4.2.2 1U12B BS-1195 Open 4.2.3 1U12C BS-ll68 Open 4.2.4 2U12 BS-ll84B Open
- 4.3 Crack open reactor makeup water inlet valve to establish reactor makeup water flow into the ion exchanger. Vary the flow as required to flush the resin into the cask.
Monitor cask pressure. Do not exceed 125 psig at cask liner.
f CAUTION: THE RESIN RETENTION ELEMENT ON THE VENT LINE IS LOCATED AT ' DIE TOP OF THE CASK PROVIDING A MINIMUM AIR OPACE. USE CAUTION WHEN FIDSHING WITH HIGH FLOW RATES TO PREVENT OVERPRESSURIZATION AND LIFTING THE TANK INTERNAL RELIEF VALVE.
w w m, ,-- - - - , - ~ . - n_ - - , - - , --, .-,e. - --
- e. , --._a -
- , - - - , , ,-w,, ,w,--
OI-24 Page 3 4.3.1 1U12A BS-1192 Throttled 4.3.2 1U12B BS-1191 Throttled 4.3.3 1U12C BS-1167 Throttled 4.3.4 2U12 BS-1176 Throttled 4.4 When Chemistry indicates the U12 bed is empty, shut
'the reactor rakeup water valve and the resin dump valve, then lock the resin dump valve.
4.5 Survey all resin dump lines to check for any stray resin. Flush out any lines requiring it. _
4.5.1 If a south U12 demineralizer being dunped - at 1U12C, open BS-ll67A to flush residual resin out of south dump header. Do not exceed 125 psig on resin cask liner. Then shut and lock BS-ll67A.
4.5.2 If a north U12 domineralizer being dumped - be-tween U3A and U3C (evaporator condensate demin-eralizer) , check shut BS-1219,1BS-1221, BS-1235D ,
and 2BS-1221. Open BS-1218 and BS-1231A to flush
.- residual resin out of north dump header. Do not exceed 125 psig on resin cawc liner. Then shut them and lock BS-1231A.
4.6 Perform the following valve lineup:
WL-1680 Spent resin to cask Shut WL-1637 Cask vent Open 4.7 Recharge the demineralizer per Chemistry require.aents and record:
3 Volume ft Lot #
4.8 Place the reactor makeup water system to the condition f
l required by the Duty Shift Supervisgr.
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Note:
If the resin beinn: dur. red is routed to the resin cark vie the South dunp header a cortact readine of the !! orth header should After dunpint; be tchen ar. in the incrensed overhead of the 1.~ orth passm eway befor e dunpinr.
contact reidinr at this sar.e location is indicr-tive th .t the nort'c he, der also needs fluckine due to resin carryinr, on past essk.
If der:nine via 1: orth headcr take contact readinc on South hender c.c t-
.lained tbove. ,
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Reviewod Dy OI-26 MINOR Record Updated Revision 5 02-24-78 POINT BEACH NUCLEAR FLANT OPERATING INSTRUCTIOi NO. 26 DEBORATING DEMINERALIZER RESIN FIUSH 1U2A&B AND 2U2A&B 1.0 PURPME To sluice the anWn resin out of the deborating ion exchangers, U2A (U2B) and replace it with new anion resin.
2.0 PRECAUTIONS AND LIMIFATIONS 2.1 Health Physics monitoring on the 26' level and 8' level of the auxiliary building.
2.2 No unauthorized work near the sluice line during the evolution.
2.3 Resin storage tank T112 relief salve is set at 150 psig. Monitor i the cask continuously during flushing operation. Do not exceed 125 psig on resin storage tank pressure gauge-7 .-
l
( 2.4 Line up monitor tank pump to reactor makeup water header, throttle pump recire valve to maintain 125 psig on the reactor makeup water header.
2.5 If resin storage tank T112 pressure increases to 125 psig and holds, back flushing of the resin retention element on the vent line may be required.
3.0 INITIAL iDNDITIONS 3.1 Verify the following:
3.1.1 Camlock female cap installed on the rasin storage tank T112 outlet line with padlock installed.
3.1 2 Camlock ferale cap installed on the resin storage tank Til2 rinse line (center penetration) with padlock installed.
3.1.3 Resin storage tank Til2 discharge valve shut (WS-34) and padlock installed.
x l
- - , - - - , . . _ < - - _ , . . , , - . - - . - . , , - - . , . . . , . - - - .- - - - , - - - - - - - , , - - . - . , - - . --y .., ,
OI-26 Paga 2 3.2 Perform the following valve lineup:
Desired Valve A (B) Name losition Initials CV-227B (226B) Deborating domineralizer inlet Shut CV-227A (226A) Deborating domineralizer inlet Shut CV-237A (2 'A8A) Deborating domineralizer outlet Shut CV-237B (238B) Deborating domineraliter outlet Shut
^
CV-228 NaOH to ion exchangers Shut CV-232 RMU water to ion exchanger inlet Shut CV-230A NaOH to U2A inlet shut CV-230B NaOH to U2A outlet. Shut CV-234A RMU water to U2A oupet Shut _
. CV-234B RMU water to U2D outlet Shut CV-233 red water to U2A & B outlet Shut WL-1680 Spent resin to cask Open WL-1681 PMU water to cask outlet Shut
- WL-1697 Cask vent Open ML-1682 Service air to cask Shut
Isolation valves to cask air regulator Shut CV-390A RMU water to ion exchangers Open CV-390D RMU water to ion exchangers Open I
Record demineralizer(s) to be flushed Unit # r ain#
3.3 Health P$1ysics perform a survey of ion exchanger to be dumped to get initial readings.
4.0 PROCEDURE 4.1 Pressurize the reactor makeup water header.
i 4.2 Open CV-242 (243) , U2A (U2B) resin dump valve.
CAUTION: THIS MILL ALLOW " HOT" RESIN TO FALL BY GRAVITY IETO THE RESIN DUMP LINE. RADIATION LEVELS WILL PROBABLY INCREASE.
4.3 Open CV-234A (234B) , reactor makeup water to ion i exchanger outlet.
4.4 Throttle CV-233 to get back flow through the ion exchanger.
Vsry. the flow as necessary to flush out the resin.
Continue to flush at approximately 7-15 gym while moni-toring cask pzassure. Do not exceed 125 psig.
CAUTION: THE RESIN RETENTION ELEMENT ON THE VENT TJNE IS LOCLTED AT THE TOP Or THE CASK, PRCf7IDING A MINIMUM AIR SPACE. USE CAUTION WHr21 FIUSHING WITH HIGH FLott RATES TO PREVENT OVERPRESSURIZA-TION AND LIFTING TANK INTERVAL RELIEF VALVE.
OI-26 Page 3 b
NCffE IF NECESSARY, FLOW MAY BE DIRECIED TO THE TCP OF THE ION EXQlANGER VIA CV-232 AND CV-230A (230B).
4.5 When Chemit ry indicates the bed is empty, shut CV-233 and CV-234A (234B) , RMU supply and CV-242 (24S resin
~ dung valve. Lock CV-242 (243) 4.6 Flush out all resin du:p lines as necessary to clear the lines of any stray resin. Monitor cask pressure while flushing the following lines.
4.6.1 If a Unit 1 deminer311zer being dumped -
l a. In primary domineralizer valve gallery (NW) open 1CV-372 to flush out residual resin.
Then shut and lock 1CV-372.
. b. At T108A&B (polishing desdneralizer) check shut WL-1824 and WL-1823. Open WL-1840 and WD-1825 to flush out residual resin. Then shut them and lock WD-1825.
- c. At 1U12C (south evaporator feed domineralizer) l - open BS-ll67A to flush residual resin out of south dump header. Then shut and lock BS-1167A.
4.6.2 If a Unit 2 demineralizer being dumped. Between U3A 's U3C (evaporator condensate domineralizer) check shut BS-1219,1BS-1221, BS-1235m & 2BS-1221.
Open BS-1218 and BS-1231A to flush residual resin out of north dump header. Then shut them and lock BS-1231A.
l l 4.7 Perform the following valve lineup:
i WL-1680 Spen?. resin to cask Shut WL-1697 Cask vent Open CV-390A RMU water to ion exchangers Shut
! CV-390B RMU water to ion excflangers Shut _
- 4.8 Recharge the domineralizer per Chemistry requiremnts l and record
Volume ft3 Lot #
.s l
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OI-26 P ge 4 7
4.9 Place the reactor makeup water system to the condition .
required by the Duty Shift Supervisor.
J Time /Date Chemistry Supvr- Operations Supervisor 1
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!@lso needs retdin:
flus':in.e- at thisdue same locaH~Kn tc resin carryingison ind.icntive past cack. that the north hender l
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T Review:d Ky OI-28 MINOR Record Updated Revision 5 02-24-78 POINT BEACH NUCLEAR PLANT 4 OPERATING INSTRUCTICE NO. 28 CONDEt: SATE DEMINERALIZER RESIN FLUSH U3A (U3B) (U3C) 1.0 PURPOSE I
To sluice the resin out of the condensate domineralizer.
2.0 PRECAUTIONS AND LIMITATIONS ,
2.1 Have Health Physics monitor the domineralizer prior to the start of the sluice operation. It should read very low, how-ever, if it is reading high, monitor the 26' level and 8' level.
2.2 Resin storage tank Til2 relief valve is set at 150 psig. Monitor the essk continuously during flushing operation. Do not exceed 125 psig on r.n;in storage tank pressure gauge.
r 2.3 Line up monitor tank punp to reactor makeup water header, throttle pump recire valve to maintain 125 psig on the reactor makeup I(- water header.
2.4 If resin storage tank Tll2 pressure increases to 125 psig and holds,back flushing of the re-in retention element on the vent line may be required.
3.0 INITIAL CONDITIONS 3.1 verify the following:
3.1.1 Camlock female cap installed on the resin storage tank l Til2 outlet line with padlock installed.
3.1.2 Camlock female cap installed on the resin storage tank
, T112 rinse line (center penetration) with padlock
. installed.
l 3.1.3 Resin storage tank Til2 discharge valve shut (WS-34) and padlock installed.
I 1
l l
l
OI-28 Page 2 f .
3.2 Perform the following valve lineup ,Tnitials laS-1273 (2BS-1273) (BS-1201) Condensate domin inlet Shut 1BS-1229 (2BS-1229) (BS-1243) Condensate domin resin fill Shuc 1BS-1228 (2BS-1228) (BS-1274) C,.ndensate demia vent Shut 1BS-1233 (2BS-1233) (BS-1205) Condensate demin outlet Shut W1680 .ipent resin to resin cask Open O l697 Resin cask outlet Ooen b l681 RMU water to resin cask Saut bl682 Service air to cask Shut l Cask a4.r reg. isol. valves Shut RMU water to WHT Shut BS-1219 BS-1215 Regenerate chemicals to demin. Shut 1BS-1223 (2BS-1223) (BS-12 35A) RMU water to top of domin. Shut IBS-1221(2BS-1221) (BS-1235B) RMU water to backflush den.in. Shut BS-1217 RMU to; top of domins Open BS-1218 RMU to backflush demins Open Record domineralizer(s) to be flushed 3.3 Health Physics perform a survey of ion exchanger to be dumpad to get initial readings.
~
4.0 PROCEDURE 4.1 Pressurize the reactor makeup water header.
4.2 Open 1BS-1231 (2BS-1231) (BS-1202) condensate dominera-lizer resin dump line valve.
CAUTION: AT THIS POINT THE RESIN IS FREE TO FALL BY GRAVITY TOWARDS THE RESIN CASK. THE RADIATION LEVEL SHOULD BE LOW, BUT CHECK IT.
4.3 Open valve 1BS-1223 (2BS-1223) (BS-1235A) , reactor makeu,-
water to the condensate domineralizer bed inlet line.
Vary the flow as required to flush the resin to the cask. Do not exceed 125 psig at cask liner.
.=
CAUTION: ME RESIN RETENTION ELEMENT ON THE VENT LINE IS LOCATED AT THE TOP OF IHE CASK PROVIDING A MINIMJM AIR SPACE. USE CAUTION WIEN FLUSHING WITH HIGH FLOW RATES TO PREVENT OVERPRESSURI-ZATIC33 AND LIFTING THE TANK INTERNAL RELIEF VALVE.
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OI-28 Page 3 7
4.4 Vary the flow .. 3 if required because of radiation levels. (FJush time 29 minutes at approximately 10 gpm.)
NOTE: IF 'IEE RESIN IS NOT FLOWING FROM THE DEMINERALIZER PROPERLY, THE FOLLOWING MAY BE ATTEMP'JED.
4.4.1 Shut 1BS-1223 (2BS-1223) (BS-1235A).
4.4.2 Open 1BS-1221 (2BS-1221) (BS-1235B) , demineralizer backflush valves. Vary flow as necesset1 4.4.3 A combination of the above two ways may aid in resin flushing.
4.5 When the demineralizer is empty, secure the reactor makeup water and shut the resin dump valve, then lock resin dump valve.
4.6 At the (U3's) evaporator condensate demineralizers, check the following valves shut - 1BS-1221, 2BS-1221, BS-1235B, BS-1235A, 2BS-1223, and 1BS-1223. Open BS-1231A to flush residual resin out of the north dump header. Do not exceed 125 psig on resin cask liner. Then shut and lock BS-1231A. Shut BS-1218.
4.7 Survey all resin dump lines for radiation. If there is any present, the other resin dump lines from other l demineralizers might have to be flushed.
i 4.8 Perform the following valve lineup to return the resin cask to a normal condition:
WL-1680 Spent resin to resia cask Shut WL-1697 Cask vent Open BS-1217 RMU water to top of drain Shut BS-1218 RMU water backflush Shut A.9 Recharge the demineralzier per Chemistry requirements ,
J
. and record:
Volume ft I4t # i Time /Date Chemistry Supervisor Operations Superv2.sor l'
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Moto If t'.le resin beint.: dunned io routed to the resin cask via the South dump header a cortset readin.e. of the i! orth header should be taken in the cvorhead of the. l. orth passa oway bercre dunninr. .;fter dunninr an incr.ecea contact rendins at this car.e locasion is indientive that the north he~'er also needs flunhinr due to resin carrying on past cack.
If de.ninr via Ucrth header trke contact r<mdinc on South headcr e.s mininnd above. .
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Reviewed By 0I-29 MINOR Record Updated ,
Revision 5 07-17-80 j J
POINT BEACH NUCLEAR PLANT OPERATING INSTRUCTION NO. 29 WASTE POLISHING DEMINERALIZER RESIN FLUSH T108A&B '
1.0 PURPOSE To sluice the resin out of the condensate demineralizer T108A or B.
2.0 PRECAUTIONS'AND LIMITATIONS 2.1 Have Health Physics monitor the demineralizer and piping prior to start of sluice. It should read very low, however, if it is reading high monitor the 26' level and 8' level.
2.2 Resin storage tank T112 relief valve is set at 150 psig. Monitor the cask continuously during flushing operation. Do not exceed 125 psig on resin storage tank pressure gauge.
- k. 2.3 Line up m.:nitor tank pump to reactor makeup water header, throttle pump recirc valve to maintain 125 psig on the reactor makeup water header.
2.4 If resin storage tank T112 pressure increases to 125 psig and .
holds, back flushing of the resin retention element on the vent line may be required.
3.0 INITIAL CONDITIONS 3.1 Verify the following: ,
1
- 3. 3 .1 Camlock female cap installed on the resin storage tank T112 outlet line with padlock installed.
, 3.1.2 Camlock female cap installed on the rcsin storage tank T112 rinse line (center penetration) with padlock installed.
3.1.3 Resin storage tank T112 discharge valve shut (WS-34) and padlock installed. I l
4
)
01-29 Page 2 3.2 Perform the following valve lineup: Initials WL-1809 (1810) "A" ("B") polishing demin inlet Shut l WL-1815 (1.916) "A" ("B") 1olishing demin resin fill Shut WL-1813 (1814) "A" ("B") polishing demin vent Shut WL-1811 (1812) "A" ("B") polishing demin outlet Shut WL-1811A (1812A) "A" ("B") polishing demin outlet (filter bypassed) Shut WL-1680 Spent resin to cask resin Open WL-1681 RMU water to cask outlet Shut WL-1697 Spent resin cask vent Open WL-1682 Service air to cask Shut WL-1823 (1824) RMU water to 108A (108B) outlet Shut WD-1825 RMU water to resin flush line Shut WL-1817 Ion exchanger alternate inlet shut WL-1818 Ion exchanger alternate inlet Shut WL-1821 (1822) "A" ("B") series operation / flushing isolation Shut ICV-390A RMU water to ion exchanger Open 1CV-390B RMU water to ian exchanger Open WL-1841 Polishing demin series operation /
flushing root isolation Open
( Record demineralizer to be flushed 3.3 Health Physics perform a survey of ion exchanger to be dumped to get initial readings.
4.0 PROCEDURE 4.1 Pressurize the reactor makeup water header.
4.2 Open WL-1819 (1820) condensate polishing demineralizer resin dump Jine valve.
CAUTION: AT THIS POINT THE RESIN IS FREE TO FALL BY GRAVITY TOWARDS THE RESIN CASK. THE RADIATION I.EVEL SHOULD BE LOW, BUT CHECK IT.
4.3 Open valve 1821 (1822), reactor makeup water to polishing condensate demineralizer bed inlet line slowly to a flow rate of about 7-15 gpm. Monitor cask pressure while flushing. Do not exceed 125 psig at cask liner.
CAUTION: THE RESIN RETENTION ELEMENT ON THE VENT LINE IS LOCATED AT THE TOP OF THE CASK PROVIDING A MINIMUM LIR SPACE. USE CAUTION WHEN FLUSHING WITH HIGH FLOW RATES TO PREVENT OVERPRESSURIZA-TION AND LIFTING THE TANK INTERNAL RELIEF VALVE.
- ~ - , . . _ . _ , _ - . . . , _ _ . - . _ _ , _ , - . _ , , , . . .
OI-29 Page 3 r
Initials 4.4 Vary the flow rate if required because of radiation levels.
4.5 When the demineralizer is empty, shut 1821 (1822)
(reactor makeup water to demineralizer) and 1819 (1820)
(resin flush line). Then lock resin dump valve 1819 (1820).
4.6 Flush spent resin line (do not exceed 125 psig on resin cask liner).
4.6.1 Open WL-1840 and WD-1825 to flush. Shut WL-1840; shut and lo. 1 WD-1825.
4.6.2 In primary demin valve gallery (NW), open ,
ICV-372 to flush. Shut and lock ICV-372.
4.6.3 At 1U12C (south evaporator feed demineralizer),
open BS-1167A to flush. Shut and lock BS-1167A.
4.7 Survey all resin dump lines for radiation; if there is
[-
any present, flush as necessary.
4.8 Perform the following valve lineup:
WL-1680 Spent resin cask Shut WL-1697 Cask vent Open 1CV-390A RMU water to the demineralizers Shut 10V-390B RMU water to the demineralizers Shut WL-1841 RMU water flushing root isolation Shut 4.9 Recharge the demineralizer per Chemistry requirements and record:
Volume ft3 Lot #
Time /Date Chemistry Supervisor Supt. - Operations
ut i
ggy ~ 6- f M l
~'
93C-: }-
I
%-L'L3ny 1
BS-1218 C
(./ ce-air.7'.' A E .'-
- 1 PJN l'J!1A , V6 lU36 -;;-l lill29 ZU12 s RMW '-'
p ;
L._f XI h-T a t 7
?
1:
r I-In ovnrheid of 6 In eve:rherd of lHX-lla P.tlR 'IEX 2HX-llA "Ei F2X Cubicle. Cubicle.
..- .- --.? ? . . . . ..
Unit 1 3oric Acidi # d Unit 2 Doric Acid Evaporr,ter Cubiclrh ', 3. . ;. .t 2 i iE vaporater Cubicle
^
.,t, .i T l TiosBM 1016 109 iUlh 191B D23.
l
... - _.. .. . \_/
~
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wL $
RMW ic4-372,
'k, IOMM.! %g Ec-$1-; g. g-ion. ,j I
fE:cV 37:.c--u sw 20!A .109 .?))lA. 2ViB ?.Uli I 's 2 4 1, Yt f i f i -'
1 3oric Acil. Unit 2 Beric .'. cia
[' Unit
' porter Cubic 1e i
, vCyarorater Ct.bicle k.assageway to Passnceway to No. 2 Piperay I!o. 3 Fipeway
> o I
d
['RES!N CASK Unit 1 KOI.TtEGEN Unit 2 KChT. GM HEX Cubicle .'...s ..->
HEX Cubicle
^ T F.) 1.EAD *:E6[ '
.S' HOT U!
- - . . . - .. L' .- S H I E L D .. _ :. -
._ . .._V ._ ..___.
Note:
If the recin beins dumad is routed to the resin cask via the South dump header a contact rnndine- of the 1: orth heador should bo t; ken in the overhead of the I.' orth passarcway before dunninr. After dumninc en incrr sec contact, reading at t%is same loi:ation is indic-tive that the north he' der also needs flumin.- due to resin carrying on pact cask.
If dim.nin- vie l'crth hesdcr t9ke contact rreinr- on South header e.s clained cbove, s
\ v c .:. . - rm,
0I-67 MINOR Revision 1
- 02-06-81 00 INT BEACH NUCLEAR PLANT OPERATING INSTRUCTION NO. 67 0FERATION OF THE AMF WASTE EVAPORATOR AND WASTE CONDENSATE SYSTEM 1.0 PURPOSE 1.1 The purpose of this procedure is to standardize the operation of the AMF waste evaporator.
1.2 Detail startup, on-line, operation and shutdown.
2.0 PRECAUTIONS mfd LIMITATIONS 2.1 Use normal precautions as would be exorcised around thermally hot equipment.
2.2 When it is necessary to be in the area of the waste evaporator during a processing event, a 0-500 mrem dosimeter should be worn since it is possible to experience hot spots in the piping, concentrator, etc.
2.3 The concentrated fluid may be very contaminated, therefore, all precautions should be taken to eliminate the possibility of personal contamination. This also makes it imperative to use good house-keeping practices.
2.4 Water should be made only to the "A" waste condensate tank to avoid contaminating the "B" waste condensate tank.
30 INITIAL CONDITIONS 3.1 Steam available for heating the unit.
3.2 Power available Nr operation.
S.3 Rod out level tube for feed tank.
i .
l 3.4 Feed filter and pu p available. This persumes that the bloedown #
evaporator is not being used to process waste.
3.5 Level established in the distillate tank.
I I
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OI-67 7
Page 2 4.0 OPERATION 4.1 Check valve lineup as follows:
[ 4.1.1 Inside Room Feed tank outlet valve Open Feed tank drain Shut Reactor makeup water valves to feed tank pump suction and dis::harge chut .
Seal water to feed tark pump from distillate pump open Drumming loop supply and return Shut Feed tank discharge sample valve Shut Feed line eductor inlet one turn open Concentrator outlet valve Open Feed line eductor inlet pressure gauge isolation Open Distillate tank outlet Open Distillate pump suction drain Shut Distillate eductor inlet Open Distillate eductor inlet pressure gauge isolation Open Dist1ilate tank drain Shut Distillate outlet to waste condensate tanks Shut Hot water pump discharge valve Open Component cooling makeup to hot water expansion tank Shut Temperature centrol valve inlet, outlet and bypass open Trap inlet and outlet open Trap bypass one turn open Isolation valve for vacuum trensmitter Open Line up the feed pump (P20) to pump to the weste feed tank through the feed filter Manual valve to vacuum pump Shut ,
Outside Room 4.1.2 Component cooling supply open' Component cooling return Throttle to 100 gpm Steam supply to backpressure regulating valve open 7ackpressure regulating valve bypass shut Waste condensate to "A" waste condensate tank open
0I-67 !
Page 3 I
/
4.1.3 Control Panel Feed tank heater Auto at 150*F Concentrator level override On Conductivity Off Feed pump (P20) Auto Al breakers on MCC section On Control switch for reflux valve Close control switch fu flush valve close Control switch for level valve close Control switch for eductor valve N/A 4.1.4 C59 Control switch for P20 EVAP 4.2 Start the feed tank, pump 4.3 S. art the. distillate pump.
4.4 Start the hot water pump.
Adjust the feed line eductor inlet valve for 35 psig inlet pressure
(- 4.5 to eductor.
4.6 When vacuum in concentrator is greater than 14" Hg, open the level valve on the control panel.
4.7 When concentrator level is normal, as viewed in the level control chamber window, crack open the steam outlet from the backpressure regulator. Warm up sic,wly to stinimize carryover. l 4.8 After the hot water temperatures have stabilized, Points 2 and 3 on the temperature monitor, check tc.e conductivity by turning on the conductivity cell. Temperature compensating dial should be set for 120*F.
4.9 When the conductivity is less than 80 pahos, open the distillate tank outlet valve to the waste condensate tanks.
NOTE: DURING THE TIME FRECEDING THE OPENING OF THE VALVE IN STEP 4.9, THE DISTILLATE TANK LEVEL MUST BE WATCHED.
DRAIN TANK AS NECESSARY TO PREVENT OVERFLOWING.
4.10 When conductivity is less than 50 pahos, or at the direction of the Duty Shift Supervisor, pump the "A" waste condensate tank back to the waste holdup tank in order to start a processing run.
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OI-67
>- Page 4 NOTES AND GUIDELINES FOR EVALUATION CF THE OPERATION OF THE WASTE EVAPORATOR
- 1. pH should be maintained between 7.0 and 8.0.
- 2. Freeze point of feed tank sample should be done once per shift.
- 3. Keep the Calgon addition pot between one-fourth and three-quarters full.
- 4. Add antifoam solution conservatively. An excess of antifoam solution seems to cause a gummy residue and silicon balls. Antifoam should be added directly to the concentrator by allowing vacuum to suck it in.
- 5. The vacuum should be between 20" and 21" Hg. If vacuum gets to be greater than 21" Hg, the valve at the inlet to the distillate eductor should be throttled to control vacuum between 20" and 21" Hg.
- 6. The valve at the inlet to the feed line eductor should be throttled to maintain 35 psig inlet pressure to the eductor.
- 7. If it becomes necessary to run the evaporator in reject for longer than five minutes, the flush valve controlled from the control panel should bc opened. When the evaporator goes out of the reject mode, close the flush
. valve.
- 8. The evaporator should be checked every two hours to make certain that:
- a. The feed line eductor pressure is 35 psig.
- b. The level is proper and there is activity in the level chamber.
- c. Feed tank level visual agrees with indicated.
- d. Calgon pot level between one-fourth and three quarters full.
- e. Feed filter differential pressure less than 20 psid and <1 R/hr.
- 9. If concentrator high level alarms become frequent, the concentrator float
'v,lve a chamber sensing line to the concentrator is probably becoming plugged. The unit sheuld be shut down and the line flushed to clear it.
OI-67 Page 5 o
t 5.0 WASTE CONDENSATE OPERATION 5.1 Evaporator effluent should always be aligned to the "A" waste condensate tank.
5.2 After filling, the "A" waste condensate tank must be sampled to determine if the contents are suitable for discharge, or must be further cleaned by the polishing demineralizer prior to resampling and discharge, or be rejected to be reprocessed.
5.3 Polishing demineralizer flow should be maintained between 5 and 35 gpa.
5.4 The waste evaporator condensate cooler should be on-line any time the condenente temperature is greater than 130'F.
6.0 TERMINATION OF WASTE EVAPORATOR OPERATION 6.1 Shut the steam outlet valve from tne backpressure regulator.
6.2 When the hot water temparature approaches the concentrator :
g- temperature, secure the hot water pump.
l(m 6.3 Shut the level valve on the control panel.
b.4 Observe an increase in the level in the was*.t feed tank and then open !
the flush valve.
6.5 Allow about three minutes and secure the distillate pump. Vacuum should decrease slowly and then very rapidly.
6.6 When the feed tank level ceases to rise the feed tank pump can be secured.
6.7 Shut the distillate outlet to the waste condensate tank.
5.8 If it is necessary to run the feed tank pump, the distillate pump should also be run to provide seal water for the feed tank pump. In this condition the distillate eductor inlet valve should be throttled to about 5 psid inlet to the eductor. The concentration outlet valve must also be shut at this time.
6.9 Prior to shutting down unit for drumming, process the 18 inches.
Then perform a normal shutdevn.
6.10 After each shutdown, flush the concentrator float chamber.
O b
_ - _ _ . - _ _ _ _ . . . _ ~ _ . _ _ . . _ _ , , . , _ _ . , _ _ , _ - . , . . _ . , _ _ _ . , , _ _ , . . , . . _ , , . _ , _ . . _ _ , _ _ _ , . . . _ , _ _ _ _ . , , , _ _ _ _ . . . _ _ ___.__.,,_,__m , . _ _ _ , . , ,
D:t2 RP-5B Cask No. MAJOR Revision 1
. Fuel No.
DSS 07-25-83 NLI-1/2 SPENT FUEL SHIPPING CASK HANDLINO & UNLOADING 1.0 PURPOSE This procedure outlines the methods for receipt, placement in the spent j fuel pool, unloading of radioactive material, removal from the spent fuel pool, decontamination, and shipment of the NLI-1/2 LWI cask.
2.0 REFERENCES
2.1 Operating Manual, NLI-1/2 Legal Weight Truck (LWT) Spent Nuclear Fuel Shipping Casks
- 2.2 Interface Manual, NLi-1/2 Legal Weight Truck (LWT) Spent Nuclear Fuel Shipping Cask j 2.3 Certificate of Compliance 9010, NLI-1/2 Legal Weight Truck (LWT) Carir 2.4 OI-4, " Spent Fuel Assembly Handling Tool Operating Instructions"
- 2.5 E0P-8D, " Cask Drop Incident" 2.6 PBNP 3.4.5, "Special Structural Limitations on the Lifting of Heavy Loads"
! 2.7 RDW 5.5, " Shipment of Empty Spent Fuel tasks & Spent Fuel" 2.8 RDW 4.1, " Receipt of Radioactive Material" 3.0 PRECAUTIONS & LIMITATIONS 3.1 Auxiliary building crane travel interlocks shall be operable in order to prohibit movement of the shipping cask over the south pool.
3.2 The cask will contain spent fuel when it arrives on site, so care
' should be taken when loosening and removing the cask lid to minimize personnel exposure.
3.3 Use of unborated water over the spent fuel pool for purposes of rinsing off the cask and crane hook / cables is permissible.
3.4 The drumming ares and auxiliary building ventilation system should be operable.
1 l
l
RP-5B Pcge 2 3.5 All loose material associated with this procedure is to be secured with lanyards when in close proximity to the spent fuel pool.
i 3.6 Aurfliary building crane movements are governed by PBNP 3.4.5, "Special Structural Limitations on the Lifting of Heavy Loads."
j 3.7 Do not immerse the cask in wster which has a temperatere of 100*F more or less than that of tne cask surface to prevent thermally i shocking the cask structure.
3.8 The cask surface may not be cleaned with steel wool or any other abrasive material. No polishing of the cask exterior is permitted. ,
l 3.9 The cask trailer is light in weight and fragile. Extreme care must be taken when loading or unloading the cask to prevent damage to the trailer. Place wheel chocks. on transporter when loading and unloading.
3.10 The cask exterior is constructed of one-fourth inch stainless sheet metal and care must be exercised when handling to prevent denting the cask.
3.11 Exercise care when unloading fuel from the cask or installing closure heads to prevent scratching the flange "0" ring seating surfaces.
3.12 Ensure that the cask is vented prior to unbolting the inner closure head.
3.13 SNM safeguards practices required close attention to accurate documentation of those steps which involve the fuel assembly.
3.14 When the closure head is left hanging on the spent fuel pit bridge, l care should be tuercised when moving a fuel assethly near it. An assembly cannot be removed from rows "0" and "P" when the head is hanging from the bridge.
j 3.15 The cask is licensed under permit USA /9010/B( ) F and documentation j relating to shirments should include the number (e.g., bills of l lading and packing lists).
3.16 The cask weight i,s limited to 52,500 pounds.
i 3.17 Extreme care surt be exercised when latching and unlatching the lifting yoka and the cask trunnions to ensure both arms of the yoke are engaged or disengaged, respectively. Moving the lifting yoke with one trunnion engaged could result in tipping the shipping cask over or damaging the lifting yoke.
- 3.10 Extreme care must be exercised when moving fuel in or out of the spent fuel cask so as not to scratch or nick the cask closure head (s) sealing surfaces.
t i
RP-5B Pcge 3
- 3.19 Initial conditions and procedural steps marked with an asterisk (*)
require an Operations Supervisor signoff.
3.20 Initial conditions and procedural steps marked with a plus (+)
tequire a Health Physics Supervisor signoff.
3.21 Initial conditions and procedural steps may be signed off either on the procedure or on the procedure signoff sheet.
4.0 INITIAL CONDITIONS Initials 4.1 The auxiliary building truck access area is clear enough to allow access of the spent fuel cask truck and trailer.
4.2 The decontamination pit is available for use. Debris has been cleared and the drains are operable.
4.3 Equipment laydown areas hrve been designc*ed for the following:
4.3.1 Personnel barriers 4.3.2 Top impact limiter 4.3.3 Bottom impact limiter 4.3.4 Outer closure head 4.4 Crane hook spacers, if required, are available at the truck access area.
4.5 Service air is available to the cask yoke controls and air hoses not hooked up to lifting yoke.
4.6 Two (2) 4" x 4" x 4' wooden blocks, cc rered with polysheet, are in place at the outer closure head laydown area.
4.7 Remove "the west section of the handrailing and walkway l
at the spent fuel pit to allow clearance for transferring the shipping cask between the decon pit and spent fuel l
, pit.
4.8 The spent fuel cask valve board is set up and the i following lines are hooked up to it. (See Figure 1) 1 J
4.8.1 Service air, regulated to 10-30 psig 4.8.2 Demineralized water 4.8.3 Vent to drumming area exhaust 4.8.4 Blowdown to spent fuel pit Jine ,
f RP-5B Pcge 4 Initials
- 4 9 . Anytime fuel is being moved, the following equipment should be operating:
4.9.1 The radiation monitor on the spent fuel pit bridge.
OPS Supvr.
4.9.2 The spent fuel pit area monitor (RE-105 & 135).
OPS Supvr.
4.9.3 The drumming area vent monitor (RE-221).
OPS Supvr.
4.9.4 The radiation monitor located just west of the compactor and south of the decon pit. 1 OPS Supvr. l 4.9.5 The spent fuel pit supply fans (W33A & W33B)
(operable only).
OPS Supvr.
4.10 The lifting yoke has been prepared for msnual operation. ,
4.11 The following equipment is ready:
4.11.1 Auxiliary building truck access
- a. Stainless steel lockwire and lead seals
- b. Chocks for the trailer wheels
- c. Tools .
1" Allen wrench i
2' persuader 15/16" socket - 3/4" drive i
3/4" socket - 3/4" drive j
3/4" drive ratchet 4
1" hex head driver - 1" drive l
3/4" F to 1" M Adapter Torque wrench - 3/4" drive, 0-350 ft/lbs 1-1/4" box-end wrench Lockwire pliers 1-1/4" docket - 1/2" drive 12" crescent wrench
- d. Neolube thread lubricant I
i 4
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RP-5B Page 5 Initials 4.11.2 Decon pit
- a. Stainless steel lockwire and lead seals
- b. 3/4" sheet of plywood for cask bottom
- c. Tools Torque wrench - 3/4" drive, 0-350 ft/ ins Torque wrench - 1/2" drive, 0-100 ft/lbs Torque wrench - 3/8" drive, 0-25 ft/lbs 3/4" drive ratchet 1/2" drive ratchet-3/8" drive ratchet 3/4" socket - 3/4" drive 3/4" breaker bar 8" extension - 3/4" drive 1-1/2" socket - 3/4" drive 3/4" hexdriver - 1/2" drive 3/4" Allen wrench Lockwire pliers 6" Crescent wrench 12" Crescent wrench _
- d. Neolube thread lubricant I
4.12 Floating setdown platform for the cask bottom is in the spent fuel pit.
4.13 Cask spray ring is in the spent fuel pool with demineralized water available to the ring.
4.14 The closure head handling tool is hanging in its storage position on the spent fuel pit bridge.
4.15 inere is some means (either underwater TV or periscope) available to verify the assembly identification number and
. serial number if present.
l 4.16 A radiation work permit has been issued for the shipment .
}
work or Health Physics coverage is available.
- 4.17 The interlocks on the auxiliary building crane have been tested within two weeks prior to the shipment.
OPS Supvr.
)
f 4.18 The NLI-1/2 LWT, Yoke B, interface adapter has been installed on the auxiliary building crane hcok.
)
i
RP-5B Page 6
(
Initials 5.0 UNLOADING PROCEDURE 5.1 Unloading the Cask From the Trailer 5.1.1 Note time of truck arrival at gatehouse.
Date Time
+5.1.2 Radiation surveys of the spent fuel cask and transporter have been made and Health Physics has receipted for shipment in accordance with RDW 4.1.
HP Supvr.
5.1.3 Spot the truck and trailer east of the centerline of the rail tracks. Place wheel chocks on the trailer.
5.1.4 Remove four (4) 5/8" hex head bolts (requires 15/16" hex socket) from the personnel barrier.
With the auxiliary building crane, remove the personnel barrier using the attached sling.
Place the personnel barrier in its designated laydown area.
5.1.5 Attach the top in;act structure sling to the top impact structure and to the auxiliary building 20 ton crane hook. Raise the crane hook until the slack has been removed from the sling. , , ,
5.1.6 Remove the lockwise and four (4) 3/4" hex head bolts (requires 1-1/4" box-end wrench) which att ach the top impact structure to the cask.
Remove the top impact structure and place in the designated laydown area. ___
I 5.1.7 Repeat Steps 5.1.5 & 5.1.6 for the bottom impact structure.
5.1.d Remove the lockwire and two (2) 1-3/8" socket head cap screws (requires 1" hex wrench) from the 7
front cask tie-downs. Store the bolts in the bolt box provided.
a l
RP-5B Page 7 Initials l
5.1.9 Remove the guide brackets (if present) from the lifting yoke. Attach the lifting yoke to the auxiliary building 130 ton hook via the interface adapter.
5.1.10 Move the lifting yoke into position just above the cask trunnions. Lower the yoke and manually engage the trunnions.
- 5.1.11 Place slight tension on the book. Stop the hoist and ascertain that the cask trunnions are fully engaged and that tt,th (2) 1-3/8" tiedown bolts have been removed.
OPS Supvr.
- 5.1.12 Rotate and translate the shipping cask to the vertical position on the transporter, keeping the crane cable as vertical as practicable.
OPS Supvr.
- 5.1.13 Lift the cask from the transportar to the decon pad. Set the cask down into the fixed scaffold on the plywood pad. Inspect the cask for damage.
OPS Supvr.
OPS Supvr.
5.1.15 Wash down the cask surfaces, as required for entry into the spent fuel pool.
5.2 Preparing the Cask for Fuel Assembly Unloading I 5.2.1 Remove the eight (8) outer closure head bolts,
' la socket cap screws (requires 3/4" Allen i wrench).
5.2.2 Using the outer closure head sling, with the 20 ton auxiliary building crane hook, remove the i
outer closure head from the cask.
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RP-5B Prge 8 D
Initials i
5.2.3 Carefully wipe the 0-ring and seal surface on the underside of the outer closure head with a clean, lint-free cloth. Visually examine the exposed surfaces of the 0-ring for defects and replace if necessary.
5.2.4 Set the outer closure head on clean wooden blocks for interim storage in the designated laydown area. Ensure the seal ring does not contact the wooden blocks.
5.2.5 Remove the two caps from the outer cavity drain valved nipples V3 and V4. Each cap is held on with three (3) 3/8" cap screws (requires 5/16" allen wrench).
5.2.6 Inspect both outer cavity drain cap seals and replace the seals if necessary. Store caps and bolts in a protected container.
5.2.7 Remove the two (2) caps from the inner head valved nipples V1 & v2. These caps are each fastened with three 1/2 13 UNC bolts (requires 3/4" socket).
5.2.8 With the caps removed, inspect the metal and plastic seals and replace if necessary. Itore the caps and bolts in a protected container.
5.2.9 Visually examine valved nipples to determine if they are seated properly. If they are not 7
seated properly, replace them.
5.2.10 Check shut vent rig isolation valves V21 & V22.
5.2.11 Attach the vent rig quick disconnect to the cask upper cavity connection VI.
, 5.2.12 Check shut demineralized water rig isolation
- valve V11.
5.2.13 Attach the demineralized water rig quick disconnect to the cask inner cavity bottom connection V2.
- 5.2.14 If requested by Health Physics, take a gas sample from the cask cavity prior to venting the cask. . ,_
OPS Super.
5.2.15 Open V21. The cask is now being vented to the drumming exhaust ventilation filters.
- . - , ,- , .-__,---.----.-.._-.-.-.---,,.--,,c. .-,-_-,.-,--e, , . _ . ~ - . . - . , _ . - , . . , . _ - , . - , , , , - -
DP-5B Page 9 Initials 5.2.16 Ensure demineralized water pressure is available up to V11.
5.2.17 Open V11 and adjust V12 for 3-5 gpm flow to the cask. Fill the cask completely. _
5.2.18 When the cask is full, shut V11 It will take approximately 41 gallons to fin the cask.
5.2.19 Remove the demineralized water rig from the cask inner cavity bottom connection V2.
5.2.20 Replace the shipping bolts (requires 1-1/8" open end wrench) with the two guidepins. Tighten them securely.
5.2.21 Remove twelve (12) 1" hex head bolts (requires 1-1/2" socket) from inner head.
NOTE: LOOSEN ALL BOLTL COMPLETELY PRIOR TO REMOVAL SINCE THE BOT.T3 PROVIDE SOME SHIELDING AGAINST STREAMING FROM THE CASK CAVITY.
5.2.22 Remove the vent rig from the cast upper cavity connection VI.
5 . 2 . 2.i Attach the underwater vent rig quick disconnect to the cask upper ca"4ty connection VI, and open '
the vent valve.
l i 5.2.24 Attach the inner closure head lifting rig to the inner closure head lifting lugs.
NOTE: SIEP 5.2.26 CAN BE DONE ANYTIME AFTER THE SHIPPING CASK HAS BEEN SET DOWN INTO THE DECON PIT.
,- 5.2.25 Attach the closure head cavity drain valve rigs to the outer cavity drain valved nipples V3 & V4. Open both outer cavity drain valves. _
CAUTION: RESIDUAL CONTAMINATED WATER MAY ISSUE FROM THE CLOSURE HEAD CAVITY l DRAINS WHEN THE DRAIN VALVES ARE I OPENED.
5.2.26 Replace the guide brackets on the lifting yoke.
t
RP-5B l Pege 10 l
4 Initials 5.3 Unloading Spent Fuel From The cask i
- 5.3.1 Hanually attach the lifting yoke to the shipping cask trunnions. ~
OPS Supvt
- 5.3.2 Raise the shipping cask to tbs ser.t fuel pit cask loading area. Align the cask over the spray ring and start lowering the cask through the rinse ring. Establish flow through the rinse ring that will wet the cask surface as it is lowered.
OPS Supvr.
NOTE: THE RINSE MAY BE STOPPED AND RESTARTED ANYTIME IMPROVED VISIBILITY, INSPECTIONS, OR MONITORING IS REQUIRED.
5.3.3 Ensure the shipping cask bottom engages the floating setdown platform as it submerge 4.,
5.3.4 Attach the pneumatic control lines to the liiting yoke before the yoke is submerged.
The rinse may have to be interrupted while attaching the control lines.
5.3.5 When the shipping cask and yoke are submerged, stop flow in the rinse ring. Continue lowering the cask to the cask laydown area of the spent fuel pool.
- 5.3.6 When the shipping cask is on the spent fuel pool bottom, disengage the lifting loke from the cask trunnions and lift the yoke clear of the cask.
Move the yoke to a location that will not inter-fere with fuel unloading.
OPS Supvr.
5.3.7 Attach the closure head lifting tool to the spent fuel pit bridge hoist. Attach the tool to the
', cask inner closure head and slowly raise the tool and closur e head. Any air that has not escaped will esespe at this time.
5.3.8 With the inner head attached, store the lifting tool on the bracket provided on the spent fuel pit bridge.
5.3.9 Pick up the spent fuel handling tool on the north side of the bridge and remove the designated spent fuel assembly from the shipping cask.
RP-5B rage 11 Initials
- 5.3.10 Move the designated assembly to the identification station and verify assembly or can identification j number. Identification number verification should be performed by both the Operations Supervisor and the Reactor Engineering Supervisor.
- OPS Supvr.
- 5.3.11 Mo(c the spent fuel assembly to its designated ;
storage location. The fuel assembly identifi-cation number and final storage location will be documented on RE-T2, signed and dated by the Reactor Engineering Supervisor and the Operations Supervisor.
OPS Supvr.
5.3.12 With the closure head handling tool and the spent fuel bridge hoist, replace the inner closure head on the cask.
- 5.3.13 Reposition the auxiliary building crane over the centerline of the shipping cask and align the rinse ring. Engage the shipping cask with the lifting yoke and begin raising the shipping cask.
OPS Supvr.
5.3.14 Start flow through the rinse ring to wash down the cables, block and hook. Raise the cask to the surface of the pool.
NOTE: THE RINSE MAY BE STOPPED AND RESTARTED ANYTIME VISIBILITY, INSPECTIONS, OR MONITORING IS REQUIRED.
NOTE: FLUSHING THE S!iIPPING CASK CLOSURE HEAD CAVITY WITH DEMINERALIZED WATER WILL FACILITATE CASK DECON AFTERWARDS.
5.3.15 When the shipping cask in. completely out of the water, secure demineralized water to the spray ring when it is no longer needed. _
" 3.16
. Let the shipping cask drip dry over the spent fuel pool for 5-10 etinutes.
- 5.3.17 Nove the shipping cask to the decon pad. When the cask is on the decon pad, disengage the lifting yoke from the trunnions and move the lifting yoke out of the way.
OPS Supvr.
. . _ - _ _ _ _ __ _ _ _ .__ _ _ - - - .__ , . - ~ . . _ . . , . . . _ , . - -
RP-5F Pcge 12 Init!nis 5.4 Preparation of the Unloaded Cask For Shipment 5.4.1 Shut both closure head cavity drain valves downstream of valved nipples V3 and V4.
5.4.2 With the 20 ton auxiliary building crane hook, lift off the inner head and raise it to a convenient height for an inspection of the closure head seals.
5.4.3 Inspect the inner closure head seal surfaces and the inner closure head seal ring. Wipe the inner closure head seal surfaces and its ssal ring with a soft, lint-free cloth. Replace the seal ring if there is any indication of damage.
5.4.4 Install the inner closure head.
5.4.5 Remove the inner closure lifting rig from the l inner closure head lifting lugs.
5.4.6 Clean the inner closure head bolts and lubricate them with Neolube.
5.4.7 Install the inner closure head bolts and tighten them to 300 ft/lbs using the following bolt pattern and torquing sequence.
First pass - 100 ft/lbs Second pass - 200 ft/lb:
Third pass - 300 ft/lbs i
8 l l 3 l
/0 n , p .
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g n 9 7 l 2 l
1 I *
/NNEM Cl-OSUME H54p BOLT 776H7EN/NG sEgygg I
l RP-5B Page 13 Initia1_s_
5.4.8 Check shut the demineralized water supply isolation valve V11.
5.4.9 Ccr.nect the demineralized water supply to the inner cavity upper access valved nipple, V1. .,__
5.4.10 Check shut the cask blowdown isolation valve V31.
5.4.11 Attach the blowdown line to the spent fuel pit to the inner cavity lower access valved nipple V2.
5.4.12 Verify blowdown valve lineup to the spent fuel pool with the exception of V31.
5.4.13 open the cask blowdown isolation valve, V31. _
5.4.14 open the demineralized water supply valve V11 and adjust V12 for 5-10 gpm.
5.4.15 Flush the cask with a minimum of 100 gallons of
,f
. demineralized water.
5.4.16 When the flushing is complete, close the demineralized water supply isolation valve V11.
5.4.17 Remove the demineralized wt_er supply line from the cask inner cavity upper access connection V1.
5.4.18 Check the air supply valve, V41, is shut.
5.4.19 Connect the air supply rig to the inner cavity upper access connection, V1.
5.4.20 Adjust the air regulator to 10-30 psig and slowly open V41.
NOTE: WATER MILL BE TCRCED OUT OF THE CASK
.- CAVITY TO THE SPENT FUEL POOL ONCE V41 IS OPEN.
5.4.21 When the cask is blown dry, as indicated by the sound of air blowing by to the spent fuel pool, shut the blowdown valve to the spent fuel pit, V31, and the air supply valve, V41 5.4.22 Disconnect the blowdown line from the shipping cask at valved nipple V2.
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,---- _ ,, -.,. .- -r,
RP-5B Pcge 14 Initials 5.4.23 Check ASut vent rig valves V21 and V22.
5.4.24 Attach the vent rig to valved nipple V2. Slowly open V21 to vent the remaining air and water from the cast.
5.4.25 When the cask inner container is depressurized, shut vent valve V21 and remove the air supply
> rig and vent rig from valved nipples VI and V2, respectively.
5.4.26 Replace the valve covers on the inner head valved nipples VI and V2. Each cover is fastened with three 1/2-13 UNC bolts (requires 3/4" socket).
Torque bolts to 20 ft/lbs.
.5.4.27 Wipe the outer closure head seal surfaces and seal ring with a clean, soft, lint-free cloth.
5.4.28 Inspect the outer head seal ring for damage and replace if necessary.
Ensure that all water has been drained from the f 5.4.29 cask clo'sure head cavity. Open the closure head cavity drain valves attached to valved nipples V3 & V4.
C&UTION: RESIDUAL CONTAMINATED ;'ATER MAY ISSUE FROM THE CLOSURE HEAD CAVITY DRAINS.
5.4.30 When all the water has been drained from the '
closure head cavity, shut the closure head cavity drain valves and disconnect the drain rigs.
5.4.30 Blot excess water from the closure head cavity.
5.4.31 Replace the covers on the closure head cavity
- drain valved nipples V3 & V4. Each cover is fastened with three 3/8" cap screws (requires 5/16" allen wrench). Torque to 7 ft/lbs.
l 1
i
RP-5B !
Prge 15 Initials 5.4.32 Install the outer closure head and torque bolts to 75 ft/lba using the following bolt pattern and torquing sequence.
First pass - 25 ft/lbs Second pass - 50 ft/lbs Third pass - 75 ft/lbs W
L 1 6 -ha f
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8 1
Bow 7;ggrgyz Cf@ufMr.t*
RP-5B Prge 16 Initials
+5.4.33 Cask has been decontaminated to levels specified in RDW 5.5 for shipment of empty spent fuel cask offsite.
HP Supvr.
5.4.34 Check water jacket drain valve cover for secure attachment. ,
5.4.35 Remove the guide brackets from the lifting yoke.
5.4.36 Verify that the trailer is level, side to side.
- 5.4.37 Manually attach the cask lifting yoke to the shipping cark and lift the cask about three feet.
OPF Supvr.
5.4.38 Decontaminate the cask bottom if necessary.
CAUTION: SAFETY BLOCKS SHOULD BE SET UP UNDER THE CASK IF PERSONNEL MUST GO UNDERNEATH CASK FOR DECONTAMINATION EFFORTS OR SURVEYS.
+5.4.39 Cask bottom has been decontaminated to levels specified in RDW 5.5 for shipment of empty spent fuel cask offsite.
HP Supvr.
- 5.4.40 Move the cask over the trailer location. Positicn the cask to engage the cutouts in the bottom end the cask with the rear tie-down. Lower the cask to rest on the front tie-down saddle, moving the cask / trailer as required, to keep the crane cables vertical.
OPS Supvr.
- 5.4.41 With slight tension on the crane cables, verify that front tie-down bolts can be started into their respective holes. Disengage the cask
, lifting yoke and store the yoke in the designated equipnent laydown area if the crane is needed for other evolutions.
OPS Supvr.
RP-5B Pcge 17 .
1 l
Initials 5.4.42 Clean and lubricate the threads of the front tie-down bolts, two 1-3/8" socket head cap screws, with Neolube. Install the bolts and torque to ,
200 ft/lbs (requires la hex driver). Install a lockwire on each bolt.
5.4.43 Install the top and bottom impact structures with four (4) 3/4" hex head bolts each and torque to 50 ft/lbs (requires 1-1/4" socket).
5.4.44 Lockwire adjacent bolts on the impact structure.
5.4.45 With the auxiliary building 20 ton crane hook, install the personnel barrier on the trailer and bolt in place the four (4) 5/8" hex head bolts (requires 15/16" socket).
NOTE: DO NOT SECURE THE CENTER CLAMPS ON EITHER SIDE.
i 5.4.46 Install the personnel barrier access panel if
/ removed.
!(
! 5.5 Release the Truck I +5.5.1 Radiation surveys have been performed and truck and trailer meet the requirements of RDW 5.5 for shipment.
HP Supvr.
5.5.2 Remove the wheel chocks.
f v5.E.3 The Health Physics Supervisor will sign the bill of lading and add:
- a. Time of truck arrival
- b. Cask identification number (if required)
- c. Time truck is released by Operations for shipment
- d. Time truck is ready for actual departure
- e. Retain one copy for WE records.
Ensure that the truck driver receives a copy of I the radioactive material shipment record and a copy of the bill of lading. Verify that the tractor is properly latched to the trailer and have the driver pull out of the truck access area.
HP Supvr.
RP-5B Pcge 18 o
Initials
- 5.5.4 At the time of the departure, notify NFS Plant Shift Supervisor (716/942-3235) or the GE Morris Operation Plant Shift Supervisor (815/942-5590) of the time that the truck tras released. Also notify him of any problems in the handling of the cask.
OPS Supvr.
+5.6 Two copies of the bill of lading will be distributed as follows. One copy goes to Reactor Engineering and one copy remains with the shipment records. If there is a packing list, one copy goes to Reactor Engineering and one copy r* mains with the shipment records. A copy of the radicactive materials shipment record also remains '
with the shipent record.
HP Supvr.
5.7 ' Reactor Engineering Supervisor is to complete the ERDA/NRC Form 741 (Nuclear Material Transportation Report) and mail it to tne NRC and either NFS or GE.
RE Supvr. r M
9
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~
NLI - LFr Cask - Functional Parts Identification
( All Valves and Lines Shown in Same Plane for Convenience) faner davity Upper faaer Cavity 30ttee.
- Access Yalve (VI) Access Vaivo (Y2)
Outer Closure Head
(
Inner Closure '
- :frumaion Read l, l j
- Outer Closure Read
! O-Ring Seal Isser Closure R&ad O-Ring Gasket
/
- Closure Head Cavity
- Drain Valvo (2) -
Water Jacketj, * (Y3) and (V4)
Relief Valve G-(VT) y{g hf ~5 mm i m &% 7,- -1
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as 2'G' ,,!
' @T OK r-2 '.
Water Jac.tet Expansion Tank b,
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i .Jf'T J % Water Jacket Yeat (VS)
Sei Lugs g *
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('"!.'-;,y' Fall and 6
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Draia Valve .. *
(V6) ,fl,},2 t;n%
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Bottom Trumaion m #~ Sockets r
I, - Schematic Sketch - NLI 1/2 LWT Cask
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-y.cwu , - - , . _ . . _ , , , , , _ . . ,
Date RP-5B Cask #
Fuel /Can #
DSS SIGNOFF SHEET FOR RP-5B 4.0 INITIAL CONDITIONS Initials Initials 4.1 *4.9.3 4.2 OPS Supvr.
4.3 *4.9.4 4.4 OPS Supvr.
4.5 *4.9.5 4.6 __
OPS Supvr.
47 -
4.10 4.8.1 4.11.1 4.8.2 _
4.11.2 4.8.3 4.12 4.8.4 ~
4.13
- 4.9.1 4.14 OPS Supvr. 4.15
- 4 . 53 . 2 4.16 OPS Supvr. *4.17
' (' 4.18 OPS Supvr.
5.1 UNLOADING THE CASK FROM TRAILER 5.1.1 *5.1.13 Date Time OPS Supvr.
+5.1.2 *5.1.14 HP Supvr. OPS SupvI.
5.1.3 5.1.15 -
5.1.4 5.1.5 5.1.6 5.1.7 5.1.8 5.1.9 5*.1.10
- 5.1.11 OPS Supvr.
- 5.1.12
! OPS Supvr.
1
i RP-5B, Sign 2ff Page 2 5.2 PREPARING THE CASK T3R FUEL ASSEMBLY UNLOADING Initials Initials 5.2.1 *5 2 14 . .
5.2.2 OPS Supvr.
5.2.3 5.2.15 5.2.16 5.2.4 ~ ~ " "
5.2.5 5.2.17 5.2.6 5.2.18 _ _ _ _ _
5.2.7 5.2.19 5.2.8 5.2.20 5.2.9 5.2.21 5.2.10 5.2.22 5.2.11 5.2.23 5.2.12 5.2.24 :
5.2.13 5.2.25 ;
5.2.25 l 5.3 UNLOADING SPENT FUEL FROM THE CASK
g *5.3.2 5.3.12
_ OPS Supvr. *5.3.13 _
5.3.3 ,
OPS Supvr.
5.3.4 5.3.14 l
5.3.5 5.3.15
- 5.3.6 5.3.'16 l
OPS Supvr. *5.3.17 5.3.7 OPS Supvr.
i 5.3.8
! 5.3.9 l
- 5.3.10 ;
OPS Supvr. t M .
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I RP-5B, Signoff Page 3 5.4 PREPARATION OF THE UNLOADED CASK FOR SHIPMENT Initials Initials 5.4.1 5.4.25 5.4.2 _
5.4.26 5.4.3 5.4.27 5.4.4 5.4.28 5.4.5 5.4.29 5.4.6 5.4.30 5.4.7 5.4.31 5.4.8 5.4.32 5.4.9 +5.4 33 5.4.10 HP Supvr.
5.4.11 5.4.34 5.1.12 5.4.13 5.4.35 5.4.14 5.4.36 5.4.15 5.4.16 *5.4.37 5.4.17 OPS Supvr.
5.4.18 5.4.38 5.4.19 5.4.20 __,
+5.4.39 ,
5.4.21 HP Supvr. j
- 5.4.40 5.4.22 5.4.23 OPS Supvr.
5.4.24 *5.4.41 OPS Supvr. j 5.4.43 i 5.4.44 i 5.4.45 5.4.46 '
s 5.5 RELEASE THE TRUCR
+5.5.1 HP Supvr.
A.5.2 _
+5.5.3 HP Supvr.
- 5.5.4 OPS Supvr.
+5.6 HP Supvr.
5.7 RE Supvr.
RDW l.1 NNSR
-7 Revision 0 03-18-83 CONTROL & ACCOUNTABILITY OF RADIOACTIVE MATERIAL 1.0 SCOPE
- The procedures in the Radioactive Material Handling Manual specify the methods to be us~ed and doc u ~ mentation required for'the receipt,' possession, use, transfer and disposal of radioactive materials.
2.0 RESPONSIBILITY .
2.1 Byproduct and source Material 2.1.1 Health Physics is responsible isr the c'ontrol and account-ability of source material, except neutron sources for use in the reactor core, and solid byproduct material, which is primarily radioactive waste. The group is also responsible for solid, liquid and grseous samples which may be shipped from time to time.
9 2.1.2 Chemistry is responsible for the accountability of liqusd V and gasaous effluents.
2.1.3 Reactor Eugineering is responsible for the control and accountability of neutron sources for use in the reactor core.
I 2.2 Special Nuclear Material Reactor Engineering is responsible for the control and accountability of special nuclear me.terial.
2.3 Incore Detectors I&C is responsible for the control and accountability of incore detectors.
2'4 Receipt & Shipment of Radioactive Material 2.4.1 It 1e the responsibility of Health Physics to assure that thu eceipt and shipment of radioactive materials complies witt applicable regulations and criteria.
2.4.2 It is the responsibility of cognizant supervision to notify the Health Physicist of any anticipated shipment or receipt of radioactive material.
l 3.0 ALARA Radioactive materials will be handled consistent with ALARA principles.
1
RDW 2.1 NNSR O Revision 0 03-18-83 RADIOACTIVE MATERIAL HANDLING RESPONSIBILITIES 1.0 GENERAL Various Federal and State regulations have been established to prevent the loss or disposul~of radioactive material'during' shipment and to' insure the safety of the public, transportation workers, und plant personnel. Due to the complexity of these regulations and the requirements at PBNP, specific procedures have been established covering the various phases of radioactive material handling and shipping. These procedures, which outline the specific requirements of the Federel and State regulations in addition to the in-plant practices are not intended to be as complete as the oriainal do:uments. Therefore, all questions or conflicts should be answered by referring to the specific publications listed in the reference section of this procedure.
2.0 REFERENCES
2.1 10 CFK 71, Packing of Radioactive Material for Transport.
2.2 49 CFR Parts 100 to 199, Transportation.
1.3 10 CFR 20,-Standards for Protection Against Radiation.
2.4 Chem-Nuclear Systems, Inc., Radioactive Material Licenses; and the Barnwell, South Carolina, Burial Ground Site Criteria.
2.5 U.S. Ecology, Inc. Radioactive Material Licenses; and the Richland, Washington, Burial Ground Site Criteria.
2.6 Package Certificates of Compliance (where applicable).
2.7 RDW 4.1, Receipt of Radioactive Materials.
3,8 RDW 5.1, Radioactive Material Shia==nts 2.3 PENP Q& Voltane II, Table IV 3.0 SAFETT PREC&ITfIONS 3.1 observo radiation protection procedures when handling any radioactive material. Refer to the Radiation Protection Manual for applicable procedures.
3.2 Adhere to standard safety practices who lifting heavy packages or using cranes and forklift vehicles.
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RDW 2.1 Imge 2 4.0 RESPONSIBILITIES 4.1 It shall be the re pa==ih414ty of the caaninnt group supervisor to nctify the Superintendent - C4HP or Health Physicist of any 4? nding in-plant processing of radioactive waste or the shipment of any radioactive material.
4.2 The Superintendent - C&HP has overall responsibility for the shipping of all^ radioactive materials and the maintenance of all records.
4.2.1 The Health Physicist is responsible to the Superintendent -
C6HP for maintaining and implementing in-plant procedures for the handliu; and shipping of all radioactive materials.
4.2.2 The Nuclear Plant Engineer or Specialist assigned to radwaste handling, in conjunction with the Health Physics Supervisors, is responsible to the Health Physicist and instigates the developing, revising and implementing of procedures. The Nuclear Plant Engineer or Specialist or Health Physics supervisors, shall be responsible for handling and shipping radicactive materials and shall monitor the receipt, packaging, and =hi.===nt a of all radioactive material <=
~
assure compliance with applicable procedures, regulatims, V) and guidelines.
CSHP Nuclear Plant Specialists /Chamistry I.ab Superr!=a-
~
4.2.3 shall have the same responsibilities described in Section 4.2.2 above when acting as a Health Physics Supervisor.
4.3 It is the responsibility of operations to prepare liners for shipment according to operations procedures and applicable Federal and State ,
regulations.
l i 4.4 It is the responsibility of Health Physics to survey and properly mark and label all radioactive materials prepued for shipment and to survey and placard (if required) the vehicle for =hia===at.
4.5 It is the re=pa==4hility of a CSEP Supervisor or Nuclear Plant
. Engineer or Specialist to review shipping papers for completeness and
. accuracy prior to =hi r t.
4.6 It is the responsibility of Health Physics and Traininr, to train all -
personnel packaging and shipping radioactive materials on the requirements of these procedures and the Federal and State regulaH ans, rules, and guidelines listed in Section 2.0 of this procedure.
h
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RDW 3.1 MINOR
[ Revision 0 03-18-83 RADI0 ACTIVE WASTE DISPOSAL 1.0 SCCP_E The release of all plant radioactive 3ffluents shall be subject to the applicable reetlations specified in 10 CFR 20 and the conditions of the facility license. Shipments of waste for offsite disposal shall be in accordance with applicable NRC and DOT regulations and conditions of the disposal contractor's license.
2.0 REFERENCES
2.1 10 CFR 20, 61, 71 4
2.2 49 CFR 100 to 199 2.3 Chem-Nuclear Systems, Incorporated, Barnwell, South Carolina Disposal Site License and Criteria s 2.4 US Ecology, Incorporated, Richland, Washington, Disposal Site License 3.0 RESPONSIBILITY 3.1 It is the responsibility of C&HP to determine the radioactivity content of plant effluents and solid wastes. ,
l 3.2 It is the responsibility of C&HP to ensure that all controlled radioactive waste discharges are in compliance with 10 CFR 20, and provisions of the facility license.
3.3 C&HP will maintain complete records of radioactive waste releases to the environment and shipments offsite for disposal.
3.4 It is the responsibility of the Duty Shift Supervisor to review the operational aspects of all controlled releases of radioactive effluents and to ensure the proper' lineup of tanks, valves and discharge pumps.
In the case of an uncontrolled and unmonitored release of radioactivity, the Duty Shift Supervisor has the rerponsibility of determining if any adjustments are required in plant operation or equipment. Any uncontrolled or unscheduled release shall be reported to a Duty &
l
~ Call Superintendent.
3.5 It is the responsibility of cognia.mt supervision to notify C&HP of anticipated accumulations of radioactive material that require disposal.
\.
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l RDW 3.1
' Page 2
{
i 3.6 It is the responsibility of cognizant supervision to assure that peacnnel filling packages of solid or solidified wastes obtain a waste permit number for each package.
3.7 It is the responsibility of the Duty Shift Supervisor, or his designate, to initiate the preparation of a Waste Permit Form (CHP-16) for each package of solid or solidified radioactive wastes.
4.0 SOLID RADIOACTIVE WASTE 4.1 Solid radioactive waste containers, properly designated, are located at convenient points throughout the controlled zone.
Containers for compressible scrap should be lined with a plastic bag to prevent the spread of contamination during the transfer from the container to the baler.
4.2 containers should be routinely monitored and radiological hazards posted as cppropriate.
4.3 When full, containers should be emptied or processed for shipment as appropriate.
)(
4.4 Large solid N dioactive waste articles shall be monitored and then wrapped, boxed, or otherwise sealed, if necessary, to confine any contam:. nation before moving or storing as contaminated waste.
4.5 C&HP uill assure that solid waste is properly packaged and shipped to a licensed disposal site.
4.6 Solid waste will have no free standing liquids in the package. Use of absorbent solidification agents or dewatering methods will be used as appropriate.
5.0 LIQUID RADIOACTIVE WASTE 5.1 All normal liquid radioactive wastes are collected by the vaste disposal system and processed as required.
5.2 Prior to disposal of any tank of liquid radioactive waste, a sample of the tenk shall be analyzed. The specific activity (da pCi/ml) shall be determined; isotopic concentrations identified, if necessary, and the required dilution factor calculated.
5.3 If the tank is acceptable for disposal, a permit for radioactive waste discharge will be completed by a C&HP Supervisor or his designated personnel and forwarded to the Duty Shift Supervis 7 who will authorize and carry out the disposal. Radioacti've liquid waste having concentrations in excess of those specified in Appendix B, Table II, 10 CFR 20, after in-plant dilution, will not normally be k approved for discharge from the plant. A release rate in excess of that stipulated by the radioactive waste release permit is not permittad. Any deviation froa the conditions of the release permit shall ne noted on the permit.
^
"A RDW 3.1 Page 3 d d and 5.4 Eny uncontrolled, or unplanned liquid releasei dshall by C&HP. be recor e concentrations and total activity output will be determ ne ill be The Duty Shift Supervisor and the Duty & Call Superintendent w notified promptly.
GASEOUS RADI0 ACTIVE WASTE l 6.0 6.1 All rudioactive gaseous wastes emitted ll be in throudt t d provisions 6.2 The controlled release of all radioactive gaseous of the facility license. ample 6.3 Prior to disposal of any tank of gaseous radioactive waste, a sThe of the tank shall be analyzed. identified, if necessary, will be determined; isotopic concentration I
and the required dilution factor calculated.
dioactive 6.4 If the tank is acceptable for disposal, a pemiti for ra his h waste discharge will be completed by a C&HP S will authorize and carry out the disposal. d d and 6.5 Any uncontrolled, or unplanned gaseous releare determined d t willshall by C6HP. be recor y be concentrations and total activity output will be The Duty Shift Supervisor and the Duty & Gil Superinten en notified promptly.
i N
O I
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l l
RDW 3.2 Page 2 l
3.3.3 No oil, except as provided in procedure RDW 3.3, may be placed in any drum of waste. This prohibition does not exclude objects with minor amounts of oil on them from being placed in a drum.
3.3.4 Personnel shall be aware of radiation exposure rates during drumming operations. When handling potential high radiation level wastes, personnel should be equipped with high range dosimeters, radiation socitors and have a radiation work permit if required.
NOTE: CONTACT HEALTH PHYSICS IF THE BALER AREA MONITOR (VAMP) ALARMS.
4.0 IDENTIFICATION OF CON 1ENTS 4.1 Call the control room for a waste permit number.
4.2 Write the waste permit number on the drum with an indelible marker.
Make the number Et least 1" high.
4.3 Affix a drum processing tag (OPS-14) on the drum head when it is 4 full, using an indelible marker, such as a Sharpie pen. Do not use Flair type pens.
4.4 Enter information on the tag as appropriate, date and initial it.
5.0 NONCOMPRESSIBLE WASTE DRUMMING PROCEDURE l
5.1 Noncompressible waste shipped in 55 gallon drums will be cut up and placed in the drum such that the lid will fit properly and the maximum amount of weste can be accommodated within the drum.
5.2 When the drum is full, inspect the lid and insure
- hat the lid gasket is in place and not damaged. Install lid and tighten.
5.3 Attach two "Catttion Radioactive Material" stickers, 180' apart, at the midsection of the drum.
5.4 Weigh the drum and install a lend seal on the lid retaining ring.
5.5 Affix a drum processing tag (OPS-14) to the tcp~cf the drum and fill in the appropriate information with indelible ink.
l 56 Survey the drum and place li: in the drum storage area.
Postthedrumstoragbareaasappropriatefortheradiationlevelsof the drums.
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i RD'J 3.2 Page 3 6.0 COMPRESSIBLE WASTE DRUMMING PROCEDURE 6.1 Turn on the compactor vent fan and assure that the area radiation monitor is operating.
6.2 Place drum in compactor.
6.3 Place the compressible waste in the drum.
NOTE: 1. WHEN DRUMMING TRASH IN PLASTIC BAGS, CUT A HOLE IN THE BAG TO ALLOW AIR TO EXIT DURING COMPACTING.
- 2. INSURE THAT NONCOMPRESSIBLE ITEMS ARE, REMOVED FROM THE WASTE.
- 3. WHEN BALING WET TRASH, CARE MUST BE TAKEN TO INSURE THAT ALL LIQUIDS ARE ABSORBED. THIS MAY BE ACCOMPLISHED BY OPENING THE BAG AND PLACING THE WET TRASH BETWEEN TWO-INCH LAYERS OF DRY CEMENT.
CAUTION: IF DURING COMPAC'" ION EXCESS LIQUID IS OBSERVED, ADD SUFFICIENT DRY CEMENT TO ABSORB ALL OF THE LIQUID.
y*'
6.4 Adjust drum under compactor ram, close the door and operate compactor.
t 6.5 Continue Pteps 6.3 to 6.4 until the drum is full.
6.6 When the drum is full, remove it from the compactor, install the drum lid and tighten, weigh the drum and affix lead seal.
NOTE: INSURE THAT THE LID GASKET IS IN PLACE.
d.7 Attach two " Caution Radioactive Material" stickers, 180* apart, at the midsection of the drum.
6.8 Affix a drum processing tag (OPS-14) to the top of the drum and fill in the appropriate information.
. NOTE: ALL D.TRIES ARE TO BL MADE WITH WATER RESISTANT INK.
6.9 Survey the drum and p h :e it in the drum storage area. Post the storage area as appropriate.
7.0 SOLIDIFICATION IN DRUMS 7.1 Prior to solidifying liquid or wet waste:
3 7.1.1 Obtain a sample of the waste for isotopic analysis. This g sample should be identified by the waste permit number of the drum (s) being filled. .
7.1.2 Review the burial site criteria and assure that only an approved solidification agent is used.
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RDW 3.2 Page 4
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7.1.3 If cement is used, assure that it is type 1.1.0 masonry cement from Western Lime & cement Company.
7.2 Solidification of wet waste should be done following Steps 7.2.1 to 7.2.13 below.
7.2.1 Begin layering the wet waste between equal layers of dry cement.
NO 2: AS A RULE OF THUMB, 15 TO 20 GALLONS OF LIQUID OR WET WASTE WILL BE ABSORBED BY APPROXIMATELY FIVE BAGS OF CEMENT. THIS QUANTITY OF WASTE AND CEMENT WILL NORMALLY FILL ONE 55 GALLON DRUM.
7.2.2 Record the total volume of both waste and cement placed in the drum on waste permit form CHP-16. (This information is required for calculating drum Curie content.)
7.2.3 Clean all waste and cement residue from the drum lid sealing surfaces and install lid and tighten.
7.2.4 Place two " Caution Radioactive Material" labels 180* apart
[s on the a:.dsection of the drum.
7.2.5 ,Obtain a vaste permit number from the Duty Shift Supervisor.
7.2.6 Attach a drum processing tag (OPS-14) to the top of the drum and enter:
- 6. Waste permit number.
- b. ~ Gallons (volume) of waste, date and initial.
NOTE: USE WATER RESISTANT INK TO MAKE ENTRIES ON DRUM PROCESSING TAG.
7.2.7 Nove the drum to the drum staging area.
CAUTION: A RADIATION SURVEY SHALL BE TAKEN OF EACH DRUM PRIOR TO IT BEING FLACED IN THE DRUM STAGING AREA. SHOULD THE DRUM STAGING AREA BECOME A HIGH RADIATION ARIA, THE AREA SHALL BE POSTED AS l
PER PROCEDURE HP 8.3.
7.2.8 After the drum has set up for at least eight hours, remove the lid and sprinkle dry cement onto any standing water until all moisture is absorbed. Leave the lid off for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
'\ After 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, if no free liquid is observed, clean the lid 7.2.9 sealing sarfaces, install lid and tighten. If free liquid '
is observed, add additional dry cement and allow drum to set for an additional 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Repeat this addition until all free liquid is absorbed. Attach lead seal.
RDW 3.2
- Page 5 7.2.10 Clean the drum, removing any residual dirt, cement or waste residue.
7.2.11 Weigh the drum and record the drum weight on the drum processing tas (OPS-14). Date and initial.
7.2.12 Complete the drum processing tag (OPS-14).
- a. Solids; no,t applicable; date and initial.
- b. Liquid absorbed; date and initial.
- c. Drum sealed; date and initial.
7.2.13 Return drum to staging area for shipment processing.
7.3 Solidification of liquids in druras should be done on the drum roller in accordance with procedure OP-9B.
8.0 DRUMMING BAG FILTERS 8.1 Refer to OP-9B, Solid Waste Processing, to drum filters.
8.2 When filters are added to a drum, notify the Operations 01fice of the number and type put in the drum.
9.0 ACTIVITY CALCULATIONS 9.1 Compressible & Noncompressible Waste
- 9.1.1 Calculate the total activity of the drum using the following formula:
Ci = Wt X mR/hr X 3.4E-06 Where Ci = Total Curies per drum i
! Wt = Weight of drum in pound =
l ..
I mR/hr = Average contact, reading in mR/hr l 9.1.2 Record the total beta-gasuna activity (Curies) in the
! appropriate column of form CHP-43.
NOTE: TRITIUM ANALYSIS IS NOT REQUIRED FOR NONCOMPRESSIBLE OR COMPRESSIBLE WASTE.
~
- 9.1.3 The activity per transport group in the drum should be calculated using the average isotopic percentage.
q
- a. If the total activity is 53 Curies, check the lines j
marked " Type A" and enter the total activity on the waste permit (CHP-16). It is not necessary to calculate the activity of Group III and Group IV separately in this case.
RDW 3.2 Page 6 l
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- b. If the total activity is >3 Curies, calculate the total l activity and the activity in Group III and Group IV.
Enter the results on the appropriate lines of the waste permit, and check off Type "A", Type "B", or Large Quantity as required.
- c. Check off the " Average Isotopic Percentage" box on the waste permit.
9.1.4 Sign the waste permit (CHP16) on the "Calculatzd By" line and return the form to the Health Physics Supervisor.
9.2 Solidified Waste 9.2.1 Obtain the appropriate Special Radiological Analysis form (CHP-24) from Chemistry.
9.2.2 Attach the Radiological Analy;is form to the Waste Permit (CHP-16) and check the "Special Radiological Analysis" box on the waste permit.
9.2.3 Assure that all nuclides are Transport Group III or IV.
Contact the Nuclear Plant Specialist assigned to radwaste if nuclides not in those groups appear on the analys4.s sheet (CHP-24).
9.2.4 Calculate the activity using the following formula:
Formula: A = (C) (V) (lE+06)
Where; A = Total activity in Curies.
C = Total activity concentration of sample in pCi/cc or pCi/ gram.
i V = Volume (ce's or grams) o 'f the liquid or j
wet waste that has been mixed with cement and placed in the drum.
If the tctal activity is <3 Curies, check the lines marked 9.2.5
" Type A" and enter the total on the Waste Permit (CHP-16).
i
! It is not necessary to calculate the activity of Groups III and IV separately in this case.
9.2.6 If total activity >3 Curies, calculate the total and the activity in Groups III and IV. Enter the results
' appropriately and check off the quantity type as required.
9.2.7 Sign the vaste permit form on the " Calculated By" line and g return it to the Health Physics Supervisor.
9.2.8 Enter total activity under the appropriate column of the Waste Operation Report (CHP-43).
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.Page 7
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. , 1 I, 9.3 BagFilterActivit"r) #
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~v 9.3.1- Obtair? the number and' type of' filters in the drum from
-s? Operations'or thel Nuclear Plant Specialist 0 signed to 3
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- y' s ' .9.3.2 CalcuInteactivityuhingTable1below.
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s i[N ACTIVITI0FFi{TERS TA7LE 1 g 4g Activity per Filter s
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4.5 aci x Waste Evaporator Feeds l
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\s . Blowdown Evapor.ntor Bottoms * <
.045 mci
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Stea:n Generator Blowdown
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(Table I assumes 450 grams of sludge per fiiter. Evaporator filters J' ,. .are estimated at 10 pCi/g and steam generator filters at 0.1 pCi/g.)
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- b. V i 9.3.3 Multiply theinumber of filters times the activity per filter l % to find total
- estimated activity.
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L, 10.0 PREPARATION FOR. SHIPMENT ,
c .
10.1. Cbtain .the; Waste Operations Report (CHP-43) .
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l 10.2 At the -drum staginq'arsa, ensure that each drum is marked " Caution j
Radioactive Material" at two places /130* apart) and that the drum s
processing tag / OPS-14) is attached and the appropriate sections are
/
j completed.
(
3 "C&'JTION RADI0 ACTIVE MATERIAL" MARKINGS ARE NOT TO BE USED l' NOTE:
" ON DRUMS TO BE SHIPPED AS " RADIOACTIVE LSA." THESE DRUMS i
MUST BE MARKED,"RADI0 ACTIVE LSA" AND OTHER MARKINGS REMOVED.
_ NOTE: FOR DRUMS NOT M&aKED " RADIOACTIVE LSA," NOTIFY HEALTH PHYSICS SUPERVISOR IF, DRUM WEIGHS MORE THAN 840 POUNDS.
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10.3 Select the waste drdtd.be processed and complete the waste permit
" (CHP-16), drum processing tag (OSP-14) and the waste operation report '
(CHP-43)'as required below. ,
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Enter the wdsia ydrait b!Jmber in the container / permit number k.t 10.3.1 L' [# .
cd1tain of the vaste cperatica ' report (CHP-43) . '
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Using'thecodesatlthstcpofformCHP-43,identifythe J
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'.,1 volUne i coluarc of 'CHP'-43, s s
container and contents and, ent
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10.3.3 Enter the date filled and the initials of the person who filled the drum (from the drum processing tag, OPS-14) in the columns provided in form CHP-43.
10.3.4 Record the drum weight on form CHP-43.
NOTE: DRUMS WEIGHING >840 P0thlDS MUST MEET THE REQUIRE-
- MENTS OF LSA MATERIAL.
10.3.5 Perform a beta-gasur.a survey of the drum. Record the highest
- contact on the bottom, side and top of the drum, average contact and the highest reading at three feet on form CHP-43.
CAUTION: CARE MUST BE USED WHEN TAKING THE ABOVE SURVEYS
- TO ENSURE THAT ACCURATE RESULTS ARE OBTAINED. THE BOTTOM OF THE DRUM MUST ALSO BE SURVEYED.
10.3.6 The drum should be cleaned prior to taking a smear survey.
10.3.7 After the drum is cleaned, perform a smear survey. A sufficient number of smears should be taken to ensure that a
- representative area of the drum is surveyed. Count the smears for beta-gamma and alpha contamination. Record
- /[V
\ results of survey on Form CHP-43.
NOTE: THE POLICY OF PBNP IS TO MAINTAIN CONTAMn!ATION LEVELS AT EQUAL TO OR LESS THAN MDA UNLESS OTHERWISE AUTHORIZED BY A C&HP SUPERVISOR.
10.3.8 Determine the appropriate Department of Transportation (DOT) label for the drum from the following (49 CFR 172.403).
- a. Radioactive White - I Must be affixed to each package measuring 0.5 mR or less per hour at each point on the external surface of the package, provided the package:
. 1. Is not Fissile Class II or III.
- 2. Does not contain a large quantity of radioactive material.
- b. Radioactive Yellow - II I
Must be affixed to each package measuring more than l
0.5 r7. per hour but not more than 50 mk per hour at each point and not exceeding one (1.0) mR per hour at three feet from each point on the external surface of the q" package or for a Fissile Class II package having a transport index of one (1.0) or less.
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RDW 3.2 Page 9
- c. Radioactive Yellow - III Must ba affixed to each package measuring more than 50 mR per hour at each point or exceeds one (1.0) mR per hour at three feet fra tach point on the external surface of the package, or
- 1. Is Fissile Class III ,
- 2. Contains a large quantity of radioactive material
{49 CFR 173.389(b)}
10.3.9 Using indelible ink, such as a sha @ ie pen, complete the DOT label as follows:
- a. Enter the predominate radioisotopes found in the waste. .
- b. Enter the Curie content of the drum.
- c. Enter the transport index number which is:
- 1. The highest radiation dose rate, in mR per aour
/[, at three feet from any accessible external lL' surface of the package.
- 2. For Fissile Class II packages, see 49 CFR.
10.3.10 Attach two completed DOT labels to the midsection of each drum 180' apart.
10.3.11 If the quantity of radioactive material being shipped is a Type "A" quantity contained in a 17H drum, the drum must be marked " USA DOT-7A TYPE A RADIOACTIVE MATERIAL" in \" or higher letters.
10.3.12 Using indelible ink, mark the weight, waste permit number, and 3 foot radiation reading on the drum head in letters at l
. least la high, if possible. The 3 feat reading should be circled.
10.3.13 Using indelible ink, sign off OPS-14 tag on radiological surveys complete lira.
10.3.14 Upon completion, place the drum in the drum staging area for shipment.
10.3.15 Perform a radiation survey of the drum storage area and update postings according to procedures.
10.3.16 Co@ lete the waste permit form (CHP-16) as appropriate.
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RDW 3.3 MINOR Revision 0 03-18-83 1 ,
PROCEDURE TO ABSORB OIL WITH HI DRI FOR SHIPMENT TO RICHLAND, WASHINGTON, BURIAL SITE a
1.0 GENERAL This procedure defines the method to be used to absorb oil for shipment to, the burial site at Richland, Washington.
2.0 DEFINITIONS 2.1 Waste Oil Drum Drums in which waste oil is stored prior to absorption. They are normally identified with an "NR-- " number. These drums are not used for shipping.
2.2 Shippino Drum
- /( Drums into which oil and Hi Dri are layered. These drums should not il' have been used for anything else previously. When full, they will be shipped to the burial site.
i 2.3 Separation Drum Drums used to hold water pumped out of a waste oil drum. These drums are used to provide extra time to get complete water and oil separation prior to pumping water to a control side floor drain.
3.0 REFERENCES
l 3.1 " Absorbents 4 proved for Use in Packaging Radioactive Wastes", undated memorandum from E. Lee Gronemeyer, In-Charge Transportation and Waste l
Management, Department of Social and Health fervices, State of
. Washington.
3.2 49 CFR Parts 100 to 178.
l 3.3 10 CFR Part 71.
l 3.4 U.S. Ecology, Inc. State of Washington Radioactive Materials License WN-1019-2.
3.5 Waste oil Shipping Drum Contents, form CHP-76.
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J RDW 3.3 Page 2 4.0 MATERIALS NEEDED 4.1 Hi Dri in 40 pound bags.
4.2 Two and one-half gallon bucket.
4.3 New 55-gallon drums.
4.4 Four mil (or greater) thick plastic bags large enough to line a 55 gallon drum.
4.E Adhesive tape to seal plastic bag.
4.6 Hand pump and hoses to fit.
4.7 Bottom probe for pump.
4.8 Protective clothing for handling contaminated liquids.
4.9 " Radioactive" markings 5.0 PRECAUTIONS
- /
- i. (\
Handle oil carefully. It is a contaminated liquid.
Also, avoid spilling Hi Dri.
6.0 FILLING THE DRUMS --
6.1 Obtain a waste permit number from the Duty Shift Supervisor.
4 6.2 Check the waste oil drum for water. If four inches or more water is present, use a bottom probe to pump the water to a separation drum.
Avoid carrying oil over to the separation drum; it is better to leave some water behind in the waste oil drum.
6.2.1 Let the separation drum stand long enough to allow any
. entrained oil to separate.
i 6.2.2 Using a bett e probe, pump the water to a control side floor drain. Do not allow any oil into the drain since oil will cause problems in the blowdown evaporator.
6.2.3 Treat any water and oil left in the separation drum as oil.
Absorb it as outlined in the rest of this procedure.
5.3 Line a 55-gallon drum with a plastic bag. This will be the shipping drum. The bag must he at least four mils thick. Thickness should be checked by referring to manufacturer's data or with a micrometer.
6.4~ Four one bag of Hi Dri into the shipping drum.
6.5 Pour one two and one-half gallon pail of oil into the shipping drum.
RDW 3.3 Page 3 6.6 Repeat Steps 6.4 and 6.5 three more times. There will then be four bags of Hi Dri and 10 gallons of oil in the shipping drum.
6.7 Add one more bag of Hi Dri.
6.8 Twist bag shut and seal tightly with tape.
6.9 Place a " Radioactive" marking on the top of the bag.
6.10 See Figure 1 which illustrates the distribution of Hi Cri and oil.
6.11 Place lid on drum and tighten.
6.12 Put two " Radioactive Material" labels 180* degrees apart on the drum.
6.13 Fill out a drum processing tag, form OPS-14 and attach it to the shipping' drum.
6.14 In order to keep track of the activity in each shipping drum, record the following data on form CHP-76.
6.14.1 Waste permit number.
'( ,
. 6.14.2 Waste oil drum number. -
6.14.3 Number of gallons from a waste oil drum put in the shipping drum. If oil is taker. from more than one waste oil drtun, record the gallons taken from each.
NOTE: THE TOTAL NUMBER OF GALLONS OF OIL PUT IN A DRUM i MUST NEVER EXCEED 10 GALLONS.
6.15 Survey the drum and place it in the drum staging area. Post the area L as necessary.
7.0 PREPARING DRUMS FOR SHIPMENT 7.1 Contact the Nuclear Plant Specialist or Engineer assigned to radwaste to establish the hazardous material classification of the shipn;ent.
This will determina which health physics procedure will be used for l processing.
7.2 ufter the shipping drums have been prepared for shipment, place them outside on the pallets along the west side of the No. 2 facade.
7.3 Send completed form CHP-76 to the Nuclear Plant Specialist or Engineer assigned to radwaste.
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RDW 3.3 Page 4 ATTACHEh7 1 CALCULATION OF AMOUNTS OF OIL AND HI DRI TO BE PUT Il A 55-GALLON DRUM
- 1. Oil /Hi Dri Ratio to be Used for Shipping Purposes Testing at Point Beach Nuclear Plant shows that Hi Dri will absorb 77% of its weight in oil.
However, regulations require that a container must be filled with enough Hi Dri to absorb twice the amount of oil present. The oil /Hi Dri ratio used is only half of the actual absorption ability of the Hi Dri.
Weight Oil
= 0.385 Weight Hi Dri The ratio shown above is used for shipping purposes.
- 2. Weight of Hi Dri per Drum l.
( A little over five forty-pound bags of Hi Dri will fill a 55-gallon drum.
Weight Hi Dri per Drum = 200 pounds.
- 3. Weight Oil ?.1. lowed in 200 Pounds of Hi Dri O
200 pounds Hi Dri x lb H br = s. oil ,
- 4. Gallons of oil Allowed in 200 Pounds of Hi Dri L This assuues a specific gravity of 0.9 for oil. This is higher than actual, but allows a safety margin.
1 l 77 lbs. oil g 1 = 10.27 gallon / drum
, drum 0.9 x 8.33 lbs./ gal.
- 5. Amounts of Hi Dri And Oil to be Put in a 55-Gallon Drum The amounts will be stated in terms of bags and pail fulls for convenience.
A bag of Hi Dri is 40 pounds. A pail of oil is 2.5 gallons.
Hi Dri to be placed in drum = 5 bags oil to be placed in drum = 4 pails
\' Note that this allows only 10 gallons of oil in the drum, less than the allowable. This provides another' safety margin.
i FIGURE 1 t
1 Bag 1 Bag + 2 Gal.
1 Bag & 2h Gal.
1 Bag + 2 Gal.
1 Bag + 2 Gal.
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RDW 3.4 MINOR Revision 0 03-18-83 XYLENE-BASED SCINTILLATION FLUID PACKAGING AND DISPOSAL 1.0 GENERAL This procedure defines the method to be used to dispose of xylene-based scintillation fluids. It shall remain in effect no longer than December 31', 1983 (
Reference:
U. S. Ecology Washington License WN-1019-2, paragraph 27b). Scintillation fluids will be packaged for disposc.1 at Richland, Washington, until that time.
2.0 REFERENCES
2.1 " Absorbents Approved for Use in Packaging Radioactive Wastes,"
undated memorandum from E. Lee Grenemeyer, In-Charge Transportation and Uaste Management, Department of Sccial and Health Services, State of Washington.
- 2.2 49 CFR Parts 100 to 178.
," 2.3 10 CFR Part 71.-
!(
2.4 U. S. Ecology State of Washington Radioactive Materials License WN-1019-2.
3.0 PRECAUTIONS 3.1 This procedure applies to xylene based scintillation fluids for shipment to Richland, Washington, only.
3.2 Handle scintillation fluids in s:cordance with procedures for flammable ano aazardous liquids as appropriate.
3.3 Leave the fluid in its original vial.
4.0, REQUIRED SHIPPING MATERIALS l
i 4.1 55-gallon steel drum, DOT specification 17H (49 CFR 178.118, 173.119b, c, d).
t j 4.2 Hi-Dri absorbent, 40 pound bags.
4.3 Plastic bag, 4 mil minimum thickness, large enough to line a 55-gallon drum.
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RDW 3.4 Page 2 4.4 Adhesive tape. .
4.5 " Sharpie" pen and '*3anford" marker, or equivalent indelible ink pens and irarkers 5.0 PACKING THE DRUM 5.1 Line a 55-gallon drum with a larm plastic bag.
5.2 Empty a bag of Hi-Dri into the drum.
5.3 Put 400 counting vials of scintillation fluid on top of the Hi-Dri.
Vials should be left in their cardboard packing box. The caps of the vials shall be upward. The vials should for:n a layer <6" thick.
5.4 Repeat Steps 5.2 and 5.3 two times.
5.5 Put half a bag of Hi-Dri in the drum.
l 5.6 Put 100 vials on top of the Hi-Dri.
5.7 Put the remaining half bag of Hi-Dri over the vials.
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, 5,7.1 The total material in the drum will be 1300 vials and four j bags of Hi-Dri.
5.8 Twist the bag shut and seal it with tape.
5.9 Insure that the drum lid gasket is in place e.nd not damaged. Put the lid en, tighten, and seal.
5.10 Obtain a waste permit number from the control room. Tell the control room the amount of liquid and Hi-Dri that is in the drum.
5.11 Fill out a drum processing tag with weatherproof ink. A " Sharpie" pen is suitable. Affix the tag to the drum top.
5.12 Write the weight on the drum lid in large numbers using weatherproof ink. A "Sanford" marker is suitable. (40 CFR 172.310) 6.0 MARKING AND LABELING 6.1 Stencil the following proper shipping names near the top of the drum.
(49 CFR 172.301)
RADIOACTIVE MATERIAL, LSA, N.O.S. UN-2912 XYLENE, UN-1307 y 6.2 Stencil the following words near the top of the drum. (49 CFR 312) j "THIS END UP" l
. , , - -- . ~ . , - .- .- , . . _ . - ~ . , , - - . , . _ - - , , - . , - - - , - . . . . . . . , - , , . ,
RDW 3.4 Page 3 6.3 Stencil the name and address of Point Beach Nuclear Plant in an appropriate spot. (49 CFR 172.306)
Wisconsin Electric Poder Company 6610 Nuclear Road Two Rivers, WI 54241 6.4 Survey the drum for radiation and contamination levels. Refer to RDW 5.3 for applicable limits.
6.5 Select a radioactive White I, Yellow II, or Yellow III label consistent with the radiation limits measured.
6.6 Place two radioactive labels, properly filled out,180* apart on the midsection of the drum.
6.7 Place a " Flammable Liquid" label next to each radioactive label.
7.0 PLACARDING 7.1 The " Radioactive" placard must be used on the transport vehicle in the following situatione (172.504).
!(-.
\ 7.1.1 Any package on the truck is labeled " Radioactive Yellow III."
7.1.2 The truck is assigned for exclusive use.
7.2 The " Flammable" placard must be used if the total gross weight loaded on the truck is 1,000 pounds or greater. (49 CFR 172.504(c)).
8.0 ACTIVITY CALCULATION 8.1 Obtain the average isotopic distribution of the fluids from chemistry.
8.1.1 If necessary, initiate a Special Radiological Analysis form, CHP-24, for completion by chemictry.
4.2 Assume 16 er liquid per vial and 0.1 pCi/cc activity to calculate I
total activicy.
8.3 If there are 1,300 vials in the drum, the total activity is 2.08E-03 Ci.
9.0 SHIPPING PAPERS Refer to procedure RPW 5.8 for proper shipping paper entries.
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RDW 3.4 Page 4 ATTACHMENT "A" f
1.0 CALCULATION OF HI-DRI NEEDED TO PACKAGE XYLENE-BASED SCINTILLATION FLUID IN ACCORDANCE WITH 49 CFR 173.393(q)(2) 1.1 Hi-Dri absorbency measurement:
150 ml Fluid Absorbency = 178 gr. Hi-Dri 1.2 Volume of fluid in a scintillation vial = 16 ml 1.3 Weight of a bag of Hi-Dri = 40 pounds 1.4 Number of vials that could be absorbed by a bag of Hi-Dri:
150 m1 fluid X 1 #i*l X 454 gr. X 40 pounds = 956 vials 178 gr. Hi-Dri 16 ml lb. bag bag i
1.5 Number of vials per bag allowed by regulation:
- /
956 vfas Xf=478 vf,als 2.0 ESTIMATED ACTIVITY OF SCINTILLATION FLUIDS 2.1 The highest activity fluid is made from reactor coolant samples.
2.2 Unit I reactor coolant activity is 12.0 pCi/cc; Unit 2 reactor coolant activity is 1 3 pCi/cc.
2.3 Unit 1 and Unit 2 are sampled with equal frequency. Thus, the average coolant activity is (2.0 + .3) + 2 = 1.15 pCi/cc.
2.4 Since the coolant is diluted by a factor of 16 to 1, the activity of the scintaillation fluid is 1.15 + 16 = .072 pCi/cc.
2.5 The 0.1 pci/cc figure used to estimate activity is very conservative, especially since the bulk of the fluid is much less active than reactor coolant samples.
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hDW 3.5 MINOR Revision 0 03-18-83 STEAM GENERATOR SLUDGE LANCE FILTER DISPOSAL 1.0 GENERAL To ensure compliance with the numerous regulatory requirements for the packaging, shipment and disposal of radioactive waste, the following procedures will be utilized for disposing of steam generater sludge lance filters.
2.0 REFERENCES
2.1 Title 10, Code of Federal Regulations.
J 2.2 Title 49, Code of Federal Regulati6ns.
2.3 Chem-Nuclear Barnwell Site Disposal Criteria Memo, dated December 8, 1978.
3.0 RESPONSIBILITIES
(' 3.1 Operations Group Responsibilities 3.1.1 Prepare an empty liner and place it at a convenient position by the sludge lance trailer for loading.
3.1.2 Place a sufficient amount of dry cement at the liner location for adding to the liner as tha used filters are loaded.
3.1.3 Dry cement should be covered with plastic to protect it from rain.
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l 3.2 Westinghouse Sludge Lance Crew Responsibilities l 3.2.1 The Westinghouse sludge lance supervisor will ensure that l
his personnel are familiar with ana comply with this procedure.
3.2.2 The Westinghouse sludge lance supervisor will ensure that the sludge lance area is kept reasonably clean and will notify a Health Physics Supervisor of any condition that might result in the spread of radioactive contamiaation.
t 3.3 Health Physics Responsibilities 1
3.3.1 Ensure that all provisions of the radiation work permit are being observed.
( 3.3.2 Periodically monitor the filling of the liner to insure that the provisions of this procedure are complied with.
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RDW 3.5 l Page 2 3.3.3 Obtain the necessary radioactive waste permit and identify i the liner with the permit number.
3.3.4 Put two " Caution Radioactive Material" markings 180' apart on'the liner.
3.3.5 Prepare the liner for shipment.
3.4 Chemistry Responsibilities 3.4.1 Obtain two sludge sczples from each steam generator.
3.4.2 Analyze the samples and forward results to the Nuclear Plant Specialist or Engineer assigned to radwaste.
4.0 SPECIAL PRECAUTIONS 4.1 No paper, plastic bags, cardboard boxes or other miscellaneous trash will be placed in the liner.
4.2 Filters are to be distributed in a manner that will allow maximum utilization of the liner and an even distribution of dry cement.
5.0 PROCEDLTE 5.1 Liner Preparation (Operations) i 5.1.1 Place the liner at the sludge lance trailer in a convenient position for filling. Cover the top of the liner around the opening with plastic to protect against contaminating the 4
liner.
5.1.2 Place a sufficient quantity of dry cement next to the liner.
This cement will be added as the liner is filled.
l 5.2 Liner Filling (Westinghouse) 5.2.1 Put 3 bags of cement in liner.
l l 5.2.2 Filters to be disposed of will be placed into the liner in evenly distributed layers.
5.2.3 Filters should be dewatered to the maximum extent practical before they are put in the liner.
5.2.4 A record of the number of filters from each steam generator put in a liner, and gallons of sludge removed should be kept on CHP-137, Steam Generator Sludge Lance Filter Disposal
( Record. Send the completed form to the Superintendent - C&HP.
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RDW 3.5 Page 3 5.2.5 After a layer of filters is placed in the liner (bottca area of liner covered), dry cement will be sprinkled over them to absorb residual moisture. This will be done after each layer of filters are placed in the liner. This layer of cement shall completely cover the layer of filters.
5.2.6 When the liner is full, cover the top layer of filters with dry cement to a depth of one inch. _. .
5.2.7 After the final layer of dry cement is placed in the liner, the top and sides are to be cleaned. After cleaning is completed, notify Health Physics so that the liner may be surveyed for loose radioactive contamination. No removable external contamination is allowed. Put a lid on the liner, but do not tighten the bolt.
. 5.3 Liner Preparation for Shipment (Health Physics) 5.3.1 Periodically monitor the radiation and removable contamination levels of the liner and insure that filling procedures are being complied with.
,; 5.3.2 Obtain a waste permit (CHP-16) and number from the control room. Label the liner with the waste permit number for future identification.
5.3.3 After the liner is filled and cleaned, perform a radiation and' removable contamination survey. Removable contamination must be less than minimum detectable.
5.3.4 Arrange to have the liner moved to the storage area and complete all necessary preparations for shipping.
5.4 Sludge Analysis (Chemistry) 5.4.1 Obtain two sludge samples from each steam generator.
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One sample near beginning and one near end of sludge lancing sequence.
l 5.4.2 Analyze the sludge for isotopic concentration in pCi/cc of wet sludge.
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5.4.3 Forward results to Nuclear Plant Specialist or Engineer assigned to radwaste.
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RDW 3.6
- MINOR
/ Revision 0 03-18-83 PREPARATION OF RADWASTE LINERS FOR FILLING, STORAGE AND SHIPMENT 1.0 GENERAL Disposable type liners can be used for shipping solidified liquid waste, filters and resin. Their preparation and filling is normally accomplished by operations using procedures outlined in OP-9B and OI-8. This procedure addresses the health physics requirements in preparing the liner for shipment to a burial site. The liners are normally shipped within shipping casks that are approved packages for Type "A", Type "B" or large quantity radio-active materials. Liners must be compatible with the cask they are shipped in as specified by the particular cask certificate of compliance. The specific shipping package used is determined by the quantity of radioactive material and by transport group being shipped. The liners may also be shipped, depending upon external radiation levels and the type and quantity of radioactive material it contains, without an external shipping package.
2.0 REFERENCES
2.1 RDW 5.1, Radioactive Material Shipments.
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2.2 CNSI specific cask handling procedures.
2.3 Nuclear Regulatory Commission certificate of compliance for specific casks.
2.4 OP-9B, Solid Waste Processing.
2.5 OI-8, Waste Solidification.
2.6 Hittman Cask Handling Procedures.
3.0 RADWASTE LINER FILLING AND STORAGE 3.1 Prior to issuing a radiation work permit for placing of radwaste into a liner, Health Physics is to insure that a sample of the waste has been taken for Chemistry Lab analysis. This sample should indicate the waste permit numbers (CHP-16) of the liners into which the waste is placed.
NOTE. BEFORE THE LINER IS e*ILLED, COVER THE LINER WITH PLASTIC.
THIS WILL MAKE DECONNING EASIER.
3.2 After the liner is filled by operations and before it is placed in storage behind the Atcor cubicle shield wall, a thorough radiation g survey is to be taken using form CHP-21 Area 36.
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RDW 3.6 Page 2 l
NOTE: THIS SURVEY IS NOT REQUIRED FOR LINERS WHICH ARE FILLED WHILE CONTAINED WITHIN A SHIPPING PACKAGE (CASK).
3.2.1 Survey each area as indicated on form CHP-21 Area 36 and record results. Insure that the highest radiation level is recorded by location.
3.3 Perform a removable external contamination survey of the liner sufficient smears should be taken so that results will be representative of the total liner area. Record results on form CHP-21 Area 36.
3.3.1 Liner External Contamination Limits Under normal conditions, liners which have external removable contamination in excess of 22,000 dpm/100 cm 2 will be decontaminated to below this limit.
NOTE: LINERS IN EXCESS OF 22,000 DPM/100 CM 2SHALL NOT BE PLACED IN THE UNDERGROUND STORAGE VAULTS UNLESS AUTHORIZED BY A CHEMISTF.Y & HEALTH PHYSICS SUPERVISOR.
S 3.4 Record the following additional information on form CHP-21 Area 36.
3.4.1 Liner serial number 3.4.2 Liner waste permit number 3.4.3 Liner storage location 3.5 When completed, the yellow copy af form CHP-21 Area 36 is ta be sent to the Nuclear Plant Specialist or Engineer assigned to radwaste.
3.6 The Nuclear Plant Specialist or Engineer assigned to radwaste will i inspect the liners for solidirication and verify the absence of free standing liquids. At this time the liner may be placed in the under-ground storage vaults if external contamination levels are less than ,
2
. 22,000 dpa/100 cm ,
4.0 PREPARATION FOR SHIP"ENT 4.1 The Nuclear Plant Specialist or Engineer assigned to radwaste will schedule the liner for shipment to a burial site.
4.2 On arrival of the shipping package (cask):
4.2.1 Complete incoming removable external contamination survey of s vehicle, trailer and cask.
4.2.2 Prepare ridiation work permit for loading liner into cask as l
required.
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- 1DW 3.6 Page 3 4.2.3 Complete the radiation and contamination surveys as required by the specific cask checkoff forms.
4.2.4 .Upon completion of loading, refer to the applicable portions of Radioactive Material Handling Hanual for preparing the shipping package (cask) and vehicle for shipment.
5.0 ACTIVITY CALCULATION FOR CASK CURIE CONTENT .
5.1 Resin samples are analyzed before shipment. Use the analysis to determine the activity per cc.
5.1.1 The volume of resin transferred is obtained from records maintained by the Operations Group.
5.1.2 Multiply the' volume times the activity per volume figure to find the total activity in the liner.
Example: 70 ft.3 of resin is transferred. Chemistry finds the activity to be 10 pCi/cc.
Activity = 70 ft.3 x 28,317 cc/ft.3 x 10 pCi/cc
= 19.82 Ci
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5.2 Evaporator bottoms samples are analyzed before shipment. Obtain the analysis results from Chemistry or the Nuclear Plant Specialist or Engineer assigned to radwaste. .
5.2.1 The volume of evaporator bottoms in a liner can be esti:aated by noting the waste feed speed and running ti:ne of the Atcor system when the liner is filled.
5.2.2 An alternate method of determining the volume of bottoms in the liner is to measure the level drop in the Atcor waste tank.
5.2.3 Conversion factors to be u:2d to ccavert waste feed speed or tank level to volume can be obtained from charts in the
. Atcor cubicle.
5.3 Filter activity is determined by two parameters, number of filters and type of filter.
5.3.1 The number and type of filters are obtaine?. from Operations Group records or the waste permit log maintained by the Nuclear Plant Specialist or Engineer assigned to radwaste.
5.3.2 The estimated activity per filter by filter type is tabulated y below.
RDW 3.6
. Page 4 Table 1 Activity of Filters .
Filter Type Activity per Filter Waste Evaporator Feed 4.5 mci Blowdown Evaporator Bottoms 4.5 mci
- Steam Generator Blowdown .045 aci (Table 1 assumes 450 grams of material per filter.
Evaporator filters estimated at 10 pCi/g, steam generator blowdown filters estimated at 0.1 pci/g.)-
5.3.3 Multiply the number of filters times the activity per filter to find total estimated activity.
i l.
Example: 60 blowdown evaporator filters are in a liner. '
Activity = 60 filters x 4.5 mci / filter E
,f = 270.0 mci l.r .- -
f 5.4 The activity of a mixture of resins, bottoms, and/or filters is icund i by calculating the activity of each component and adding them together.
6.0 ESTIMATING ACTIVITY FROM RADIATION MEASUREMENTS 6.1 For comparison purposes, or if getting a sample of waste i~s inadvisable, activity can be estimated from radiation readings. The measurements may be taken.of a liner either in or out of a shipping cask.
6.2 Take four readings around the middle of the cask or in.er at a distance l
of three feet from the surface. The readings should be equally spaced.
! 6.3 Calculate the average radiaticn level in r.R/ hour at three feet.
6.4 Using Table 2 below, find the :ppropriate multiplier for the container and waste type involved. Casks are identified by their DOT number.
Table 2 Activity Multipliers Container Solidified Waste Dewatered Resin 440 gal. Liner .020 .011 lg l
USA /6601/B Cask 115.1 88.3 l
USA /9111/A Cask -- 46.4 HCS /Q1 A A /1 Psek ?? E 11 1
. . . . _ . _ _ . . _ m __, _ _ - . . . _ , _ _ . _ _ _ _, - - . - . .
RDW 3.6 Page 5 6.5 Multiply the average radiation level at three feet by the multipli r in Table 2 to estimate activity.
Example: Radiation levels around the middle of a 440 gallon liner of solidified evaporatcr bottoms are: 100 mR/hvur, 100 mR/ hour, 150 mR/ hour, 100 mR/ hour (three feet readings).
Average Radiation Level = 112.5 mR/ hour Activity
= 1:2.5 x .020 = 2.25 Ci
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RDW 3.7 MINOR Revision 0 05-18-83 PREPARING HEPA TYPE FILTERS FOR SHIPMENT 1.0 GENERAL The HEPA type filters used in the plant exhaust ventilating fans are normally shipped to the burial ground as " Radioactive - LSA" type waste in plastic -
lined wooden boxes. This' procedure outlines the steps in packaging the filters and praparing the boxes for shipment.
2.0 REFERENCES
2.1 RDW 5.1, Radioactive Material Shipments and related appendices.
2.2 Form CHP-21, Miscellaneous Survey Form.
3.0 PACKAGING PROCEDURE 3.1 Box Preparation 3.1.1 Obtain a wooden filter shipping box from Ready 3 tores and line it carefully and thoroughly with plastic. Leave enough
'[ plastic to fold over the top when the box is full.
3.1.2 Put a second lining of blotting paper in the box.
- a. Use a double thickness of blotting paper for the lining.
- b. Tape or staple the paper in place so that it does not fall out of place.
3.2 Crush the filters in thi compactor and place them in the box in a volume efficient manner.
3.3 When no more filters will fit in the box, add low-level scrap
(<2 mR/hr), either compressible or non-compressible, to brace the filters in the box so that they will not shift during transport.
l 3.4 Put a double thickness of blotting paper over the top of the filters.
Tape it in place.
3.5 Fold the ends of the plastic over the top and tape in place.
3.6 Secure the box lid with nails and band the box using metal banding.
3.7 Weigh the box and record the gross weight on both sides of the box in the upper right corner.
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RDW 3.7 Page 2 3.8 Measure the box and record the length, width and height (including skids) and record this information on both sides of the box in the upper right corner and on form CHP-16, Waste Permit. Measurements should be to the closest half-inch.
3.9 Contact the control room and obtain a waste permit number. Record the permit number on both sides of the box in the upper right corner.
NOTE: USS A WATER RESISTANT MARKER FOR RECORDING THE ABOVE INFORMATION.
3.10 If box will be prepared for shipment the same day it is filled, go to Step 4.0.
3.11 If preparation of the box for shipment is not going to be completed at this time, place " Caution - Radioactive Material" markings on both sides of the box, cover the box with plastic sheeting and store it in the drum staging area in the northwest corner of the truck access. <
4.0 PREPARATION FOR SHIPMENT 4.1 Move the box containing the filters to an area of low background radiation (<1 mR/hr) and perform a beta gamma survey as follows and
,/ record results on form CHPs21, Miscellaneous Survey Form.
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4.1.1 Highest contact 4.1.2 Average contact at middle of box 4.1.3 Highest at three feet 4.1.4 Average around middle at three feet 4.1.5 For purposes of activity calculations, contact and three foot readings must be taken at the center of each side of the box, not including the ends.
4.1.6 Send the completed yellow copy of form CHP-21 to the Nuclear Plant Specialist c,r Engineer av.igned ta radwaste.
4.2 Perform a removable contaminaton survey and record results on form CHP-21, Miscellaneous Survey Form.
4.2.1 Contamination Limits Maximum Permic;sible Level Contaminant dis / min /100 cm 2 Beta Gamma 2,200*
g Alpha 220*
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- The policy at Point Beach Nuclear Plant is to reduce external contamination levels to as low as practicable, Therefore, contamination levels in excess of 10% of those listed above require Health Physics supervisor approval prior to release.
RDW 3.7 Page 3 4.3 Activity Calculation 4.3.1 The formula for calculating activity contained in a wooden box made of 3/4" plywood with dime.nsions 87" long x 30" wide x 25" high is:
- a. Average 3 foot reading (mR/hr) x 2.35E-3(mR/hr/Ci) =
Curies
- b. Average contact reading (mR/hr) x 3.85E-4(mR/hr/Ci) =
Curies 4.3.2 Contact the Nuclear Plant Specialist or Engineer assigned to ra6 waste to determine Curie content of box sizes diffc: rent from Section 4.3.1.
4.3.3 Use the three foot reading to calculate curie content, unless the reading is close to background.
4.3.4 If the three foot reading is within 0.5 mr/hr of background, use the contact reading to calculate activity.
/ 4.4 Confirm that the contents meet the requirements of LSA material
,' (reference procedure RDW 5.3).
4.4.1 Mark " Radioactive - LSA" on tne two long sides of the box.
6.4.2- Remove the " Caution - Radioactive Material" markings if they are present.
4.4.3 If the box does not meet LSA requirements, inform the Nuclear Plant Specialist or Engineer assigned to radwaste.
4.5 Cover the box completely with plastic sheeting and place it in the radwaste storage area outside the west side of Unit 2 facade for shipment.
4.6 Complete the required entries on the following Chemistry & Health Physics forms.
4.6.1 Waste Permit (CHP-16).
4.6.2 Waste Operation Report (CHP-43).
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RDW 4.1 MINOR Revision 0 03-18-83 RECEIPT OF RADIOACTIVE MATERIAL 1.0 GENERAL Packages of radioactive material must be surveyed and checked for proper packaging and 1cbeling by Health Physics when delivered to the PBNP.
Packages that are to be' picked up at the carrier's terminal may ~ require health physics coverage. If a package is found to exceed allowable limits for contamination or radiation, the incident must be immediately reported
)_ to the NRC and the delivering carrier.
2.0 REFERENCES
2.1 10 CFR 20 2.2 10 CFR 71 2.3 49 CFR Parts 100 to 178
,-- 3.0 TIME LIMITS
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1' 3.1 Unless excepted in Section 3.4, packages received at PBNP will be surveyed for external contamination and radiation levels within the folleving time limits:
Time of Receipt Time to Survev During normal working hours 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> outside normal working hours 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> 3.2 Normal working hours are 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> to 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />, winter, and 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> to 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />, summer.
. 3.3 A package is considered " received" when it is taken off the delivering vehicle.
' 3.4 Packages which are excepted from the survey time limit are listed below:
3.4.1 Packages containing r.o more than the exempt quantity specified in the table in Section 3.4.6 below.
3.4.2 Packages containing no more than 10 pCi of radioactive material consisting sole._y of tritium. carbon-14, sulfur-35, or iodine-125.
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RDW 4.1 Page 2 l- f ,
I i 3.4.3 Packages containing radioactive material as gases or in special form.
3.4.4 Packages containing only radioactive material ir. other than l liquid form and not exceeding the Type "A" quantity limit I specified in the table in Section 3.4.6 below.
3.4.5 Packages containing only radionuclides with half-lives of less than 30 days and a total quantity of no more than 100 mci.
3.4.6 Table of Exempt and Type "A" Quantitier
' Exempt Type "A" Quantity Limit Quantity Limit iransport Group (In Millicuries) (In Curies)
? .01 .001 II 0.1 .050 III 1 3 IV 1 20 V 1 20 VI 1 1,000 VII 25,000 1,000 l f( 20 l\
Special Form 1 i
l l 3.5 Packages being held for pickup at a carrier's terminal will be picked l up expeditiously upon notification of its arrival.
4.0 NOTIFICATION OF RADIOLOGICAL VIOLATIONS 4.1 If a package exceeds the following limits, notify the Health Physicist or Superintendent - C&HP.
4.1.1 Package Surface
- a. Removable contamination (the sum of alpha and beta gamma) 22,000 dpm/100 cm2
- b. Radiation level, nonexclusive use vehicle, all.open vehicles 200 mR/ hour
- c. Radiation level, closed trans-port exclusive use vehicle N/A 4.1.2 Three Feet from Package Surface
- a. Radiation level, closed trans-port exclusive use vehicle 1,000 mR/ hour
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- b. Radiation level, non-exclusive use vehicle, all cpen vehicles, 10 mR/ hour except as noted in "c" below.
- c. Radiation level of shipping cask L on exclusive use ooen vehicle. N/A .
r-RDW 4.1 g Page 3 s
4.1.3 Six Feet From Shipping Cask
- a. . Applies only to casks on exclusive use vehicles.
- b. Sides of cask 10 mR/hr
- c. Top and bottom of cG3k. N/A 4.2 The Health Physicist or a plant superintendent, normally the Superintendent - EQ&RS, will notify as soon as practicable the NRC Office of Inspection and Enforcement (after verification of survey results) by telephone and in writing by telegram, mailgram, facsimile, or equivalent. The address and phone number is:
Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road
- Glen Ellyn, Illinois 60137 Telephone: (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) 312/932-25000 4.3 The Health Physicist or a plant superintendent will also notify the
,,( final delivery carrier of the violation by telephone and written telecommunication. This should be done as soon as practical after the NRC notification.
5.0 SAFETY PRECAUTIONS 5.1 The stockman shall not move or handle any package containing radioactive material shipped in a sole use (exclusive use) vehicle until it has been surveyed and released by Health Physics.
5.2 If the package is broken or damaged, detain the carrier untal the package has been surveyed and released by Health Physics.
5.3 Use radiation protection procedures when handling radioactive raterials.
I t 5.4 Adhere to standard safety methods when lifting heavy packages.
6.0 RECEIPT OF PACKAGES 6.1 The package must be surveyed (when required) for external radiation levels and external contamination levels. Smears shall be counted for both beta gamea and alpha contamination. Packages received at PBNP are normally sent in one of three ways; in the mail as limit?d quantities, nor. exclusive use vehicle, and exclusive use vehicle shipments.
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g' 6.2 Packages. expected to arrive at P2NP containing quantities of 4 l
l radioactive material in excess of Type "A" quantities (refer to RDW i 5.1, Section 3.2) will be accepted when offered for delivery at PBNP.
RDW 4.1 Page 4 f
6.3 Receipt of Limited or Exempt Quantities
,. No surveys of limited or exempt quantities of radioactive material are required; however, the package and material should be checked to ensure that they meet the requirements of limited or exempt quantities.
Reference RDW 5.2, Section 3.1.
6.4 Receipt of Radioactive Materials in a Nonexclusive Use Vehicle Monitoring of this type package shall be completed in the required time period previous ~1y stated in this procedure. If radiation levels are found on the external surface of the package (s) in excess of 200 m2/ hour or at three feet from the package (s) in execss of 10 mR/ hour, the Health Physicist shall be notified immediately. Title 49 173.393(i).
The package should also be checked for proper labeling and packaging according to the quantity of radioactive material shipped. A radioactive material receipt (CK!-12) should be completed and the materials inarked or posted as appropriate. The receiver should be instructed as to the proper handling and storage requirements.
6.5 Receipt of Radioactive Materials Shipped in an Exclusive Use Vehicle o(~'
The same procedure as receipt of nonexclusive use vehicle shipments is followed except the vehicle should be surveyed prior to unloading.
External radiation readings should not exceed the limits of exclusive use vehicles. Notify the Health 2hysicist if any reading exceeds these limits. Title 49 173.393(i). Reference RDW 5.7, Sections 6.1 and 6.2.
7.0 RECEIPT OF EQUIPMENT / MATERIALS 7.1 General l The majority of equipeent received at the PBNP is used during extended outages by contractor personnal. It consists of steam generator eddy current, steam generator sludge lance or inservice inspection equipment.
l These shipments are normally shipped in 'an exclusive use vehicle l ,
owned or leased by the contractor.
i 7.2 Procedure 7.2.1 Perform a beta gamma survey of the vehicle prior to unloading.
Ensure the following readings are obtained.
- a. Highest contact reading on vehicle surface (<200 mR/ hour).
- b. Highest reading at six feet from vehicle surface (g
(<10 mR/ hour).
- c. Highest reading in any normally occupied position in s
the vehicle (<2 mR/ hour).
- d. Notify a Health Physics Supervisor if any of the above
! limits are exceeded.
RDW 4.1 7
Page 5 d
7.2.2 After unloading the equipment, each package shall have a beta gamma survey and a contamination survey performed. The smear survey shall be counted for alpha and beta gamma contamination.'C Refer to Section 4 0 above to determific if the package is within acceptable limits. +
7.2.3 Obtain the incoming shipping papers from the driver or contractor representative'.
l 7.2.4 After unloading and prior to release of a vehicle used for exclusive use shipments, the following surveys must be i completed. (Title 49 173.397)
- a. Complets a contamination survey of the empty vehicle.
Removable contamination levels must be iMDA prior to release of the vehicle. Notify a CEP Supervisor if contamination levels in excess of $MDA are found.
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NOTE: CONTAMINATION LEVELS OF >22,000 DPM/100 CM2 REQUIRE IMMEDIATE NOTIFICATION TO THE NUCLEAR #
REGULATORY COMMISSION AND THE CARRIER. NOTIFY e A SUPERVISOR IMMEDIATELY.
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! b. Complete a radiation survey of the empty vehicle. A j vehicle may not be returned to service until the l
radiation dose rat.e at any accessible surface is 0.5 millirem per hour or less.
l l c. When the above conditions have been met, the vehicle may
! be released._
7.2.5 Complete " Radioactive Material Receipt", form CHP-12.
8.0 RECEIPT OF SOURCES 8.1 General Sources received at FBNP may be either liquid or solid sources used
, by CEP. They may be shipped as exempt or limited quantities in the mail or as Type A, B, or large quantities in exclusive or nonexclusive use vehicles.
8.2 Procedure 8.2.1 Notify a Chemistry or Health Physics Supervisor.of the receipt of a source.
8.2.2 Perform both a beta /gansna and contamination survey of the g source container (s). Contact a CEP Supervisor if contamination levels exceed SMDA.
NOTE: CONTAMINATION LEVELS OF >22,000 DPM/100 CM2REQUIRE IMMEDIATE NOTIFICATION TO THE NUCLEAR REGULATORY COMMISSION AND THE CARRIER. NOTIFY A SUPERVISOR IMMEDIATELY.
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8.2.3 If delivery of the source (s) is by exclusive use vehicle shipment, then the requirements of Section 7.2 of this 2
appendix apply.
8.2.4 Complete a " Radioactive Material Receipt", form CHP-12.
8.2.5 Make the appropriate entry in the source inventory and leak
- test record book, based on the amount of activity received.- -
- 8.2.6 Store the source (s) in the health physics source root or any I other designated area.
- 9.0 RECEIPT'OF NEW FUEL i
9.1 General l
New fuel received at PBNP is shipped in an exclusive use vehicle;
- therefore, the vehicle must be surveyed before the vehicle can be l unloaded. The new fuel is shipped as Fissile Class II radioactive
! material.
9.2 Procedure
[
9.2.1 Perform a beta /gansia and contamination survey prior to l unloading the vehicle. Count the smears for beta gamma and l alpha contamination. Contact a C&HP Supervisor if l contamination levels exceed 1MDA.
l NOTE: REFER TO SECTION 4.0 ABOVE TO DETERMINE IF THE PACKAGE IS WITHIN ACCEPTABLE LIMITS.
9.2.2 New' fuel containers are stored at the spent fuel pit or on El. 66' by the waste distillate tanks until they are unloaded.
l 9.2.3 When the containers are opened, the assemblies and the inside of the containers arc smeared. Count the smears for beta / gamma and alpha contamination. A beta / gamma survey is taken of each assembly.
, 9.2.4 After unloading and prior to release of a vehicle used for exclusive use shipments, the fcllowing surveys must be completed. Title 49 173.397 l
- a. Complete a contamination survey of the empty vehicle.
Removable contamination levels must be <MDA.
- b. Complete a radiation survey of the empty vehicle. A vehicle may not be returned to service until the i~ -radiation dose rate at any accessible surface is 0.5 mR/ hour or less.
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- - .- ._ _ _ _ _ _ _ _ . . _ _ , . . ~ - _ , , - _ . _ . _ , _ . _ , _ . , _ . _ _ . _ , _ _ . _ _ . . . - - - _ _ - - _ _ _ -
RDW 4.1
/ Page 7
- c. An " Empty" label is needed if internal contamination of the containers exceeds 2,200 dpm/100 cm2 beta / vama or 2
220 dpm/100 cm alpha contamination. Refer to RDW 5.6, Section 4.4.
- d. When the above conditions have bfon met, the vehicle may be released.
9.2.5 Consplete the " Radioactive Material Receipt", form CHP-12.
- a. The radionuclide entry is UO 2-
- b. Physical and chemical form entries are solid and oxide.
- c. Obtain activity (Curie content) from Reactor Engineering.
9.2.6 Results of the incoming container smear survey should be called to Reactor Engineering.
10.G RECEIPT OF SPENT FUEL CASKS (EMPTY) - EXCLUSIVE USE VEHICLE 10.1 Upon the arrival, obb in the following from the truck driver.
! 10.1.1 The freight bill.
10.1.2 The shipping report.
10.1.3 Copies of the outgoing surveys (their survey).
10.2 Perform a smear survey of the tractor and release if the smears are iMDA.
10.3 Perform a beta / gamma and smear survey of the cask and trailer. Follow the instructions on survey Form CHP-21, Area 31. Contact a C&HP Sugervisor immediately if contamination levels exceed 22,000 dpm/100 cm'.
10.4 Complete CHP-12 as appropriate.
11.0kECEIPTOFSPENTFUELCASKS(LOADED)-EXCLUSIVEUSEVEHICLE 11.1 Upon the arrival, obtain the following from the truck driver.
11.1.1 The freight bill.
11.1.2 The shipping report.
11.1.3 Copies of the outgoing surveys (their surveyi.
\
11.2 Perform a smear survey of the tractor and release if the smears are iMDA.
i RDW 4.1 l Page 8 l
11.3 Perform a beta / gamma, neutron and smear survey of the cask and trailer.
Follow the instructions on survey Form CHP-21, Area 31. Contact a chemistryandHealthPhysicsSugervisorimmediatelyifcontamination levels exceed 22,000 dps/100 cm .
11.4 Complete CHP-12 as appropriate.
11.5 Notify Reactor Engineering of the receipt.
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l-RDW 5.1
.- MINOR Revision 0 03-18-83 RADI0 ACTIVE MATERIAL SHIPMENTS - GENERAL 1.0 GENERAL The various categories of radioactive material shipments have been designated by Federal regulations and it is the intent of this procedure to define those categories routinely rec.aived at or shipped from PBNP. In addition, there is incluced a section on commealy used terms that have specific application to radioactive material shipmente. The information herein is provided as a guide and in no manner is to supersede the intent of the applicable Federal regulations referenced below.
2.0 REFERENCES
2.1 10 CFR 71, Packaging of Radioactive Material for Transport and ,
Transportation of Radioactive Material Under Certain Conditions.
2.2 49 CFR Parts 100 to 199, Transportation.
3.0 CATEGORY OF RADIOACTIVE MATERIAL SHIPMENTS s(-
Each shipment of radioactive material will fall under one of the following categories. Each category has specific requirements for isotopic composition, quantity of radioactive material per package and specific requirements under which it may be transported.
3.1 Type "A" Quantity Ra(ioactive Materials 49 CFR 173.389 and 10 CFR 71 Type "A" quantity radioactive materials means a quantity the aggregate radioactivity of which does not exceed that specified in Table "A" to follow.
3.2 Type "Bd Qttantity Radioactive Materials Type "B" quantity radioactive caterial means a quantity the aggregate radioactivity of which exceeds the quantity limit for Type "A" quantity
- but does not exceed that specified for Type "B" quantity in Table "A" to follow.
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RDW 5.1 Page 2 TABLE "A" Transport Type "A" Quantity Type "B" Quantity Group in Curies in Curies I 0.001 20 II 0.05 .:2 0 III 3 200 IV ~
20 200 i V 20 5,000 VI and VII 1,000 50,000 Special Form 20 5,000 3.3 Large Quantity Radioactive Materials Large quantity radioactive materials means a quantity the aggregate
. radioactivity of which exceeds that specified for Type "B" quantity in Table "A" above.
3.4 Low Specific Activity Radioactive Material
, gs._ .
Low specific activity means any of the following.
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3.4.2 Unirradiated natural or depleted uranium or unirradiated natural thorium.
3.4.3 Tritium oxide in aqueous solutions provided the concentration does not exceed five millicuries per milliliter (5 mci /ml).
3.4.4 Material in which the activity is essentially uniformly distributed and in which the estimated average concentration per gram of contents does not exceed:
- a. 0.0001 mci of Group I radionuclides.
l
. b. 0.005 mci of Group II radionuclides.
- c. 0.3 mci of Groups III or IV radionuclides.
NOTE: THIS MAY INCLUDE, BUT IS NOT LIMITED TO, MATERIALS OF LOW RADIOACTIVITY CONCENTRATION SUCH AS RESIDUES .
OR SOLUTIONS FROM CHEMICAL PROCESSING: WASTES SUCH AS BUILDING RUBBLE, METAL, WOOD, FABRIC SCRAP, GLASSWARE, PAPER AND CARDBOARD; SOLID OR LIQUID PLANT WASTES, SLUDGES, AND M:MES.
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_ - . - _ _ - - . . - - - - _ _ - - _ = - .
RDW 5.1 .
- Page 3 3.4.5 Objects of nonradioactive material externally contaminated vi d radioactive material, provided that the radioactive material is not readily dispersible and the surface con-tamirntion when averaged ovar an area of one square meter does not exceed:
- a. 0.0001 mci (220,000 dpm) per square centimeter of Group I radionuclides, or
- b. 0.001 aci (2,200,000 dpm) per square centimeter of other radionuclides.
3.5 Limited Quantities of Radioactive Materials and Radioactive Devices 40 CFR 173.391 The limited quantity designation is given to quantities of radioactive material in normal form which does not exceed the following:
3.5.1 0.01 mci of Group I radionuclides.
3.5.2 C.1 mci of Group II radionuclides.
1.0 mci of Groups III, IV, V, or VI radionuclides.
3.5.3 3.5.4 2b Curies of Group VII radionuclides.
3.5.5 Tritium oxide in aqueous solution with a concentration not exceeding 0.5 mci per millilitar and with a total activity per package of not more than three Curies.
3.5.6 One mci of radioactive material in special form and not containing more than 15 grams of U-235.
3.6 Fissile radioactive material to be covered in a separate procedure.
4.0 COMMONLY USED TERMS AND DEFINITIONS 4.1 Transport Group Transport group means any one of seven groups into which normal form radionuclides (see 4.3) are classified according to their radiotoxicity and their relative potential hazard in transportation. See table on 49 CFR 173.390.
4.2 Transport Index Transport index means the number placed on a package to designate the degree of control to be exercised by the carrier during transportation.
s The transport index assigned to a package of radioactive materials represents the highest radiation dose rate, in millirem per hour at three feet from any accessible external surface of the package.
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RDW 5.1 Page 4 ,
For determining the transport index for Fissile Class II packages, refer to the Federal Regulations 49 CFR 173.389(2). '
4.3 Normal Form Redioactive Material Normal form radioactive material means those which are not special form radioactive materials. Normal form radioactive materials are grouped into transport groups. (See Section 4.1.)
4.4 Special Form Radioactive Materials
- Special form radioactive materials means those which, if released from a package, might present some direct radiation hazard but would present little hazard due to radiotoxicity and little possibility of contamination. See 49 CFR 173.398 and 173.389(f) for complete information. To qualify as special form, the material must either be in massive solid form or encapsulated and must pass special tests.
1 4.5 Radioactive Material Radioactive material means any material or combination of materials,
,n which cpontaneously emits ionizing radiation, Materials in which the
/t estimated specific activity is not greater than 0.002 pCi per gram of material, and in which the radioactivity is essentially uniformly distributed, are not considered to be radioactive materials for transportation purposes.
4.6 Type "A" Packaging Type "A" packaging means packaging which is designed in accordance with the general packaging requirements of 49 CFR 173.24 and 49 CFR 173.393.
4.7 Type "B" Packaging Type "B" packaging means packaging which meets the Standards for Type "A" packaging and in addition meets the criteria prescribed in 49 CFR 173.398(c). Type "B" packaging must also be specifically licensed by
- the NRC and the NRC must be notified of intent to use particular Type "B" packages per 10 CFR 71.
4.8 Exclusive Use (Sole Use or Full Load)
Exclusive use (sole use or full load) means any shipment:
4.8.1 From a single consignor having the exclusive use of a transport vehicle or of an aircraft, er of a hold or compartment of an inland watercraft, or of a hold
\ compartment, or defined deck area of a seagoing vessel; and 4.8.2 For which all initial, intermediate, and final loading and unloading is carried out by or under the direction of the consignor (shipper), consignee (receiver), or his designated agent. .
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RDW 5.1 Page 5
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l 4.9 Closed Vehicle Transport closed vehicle transport means a vehicle equipped with a securely
- attached exterior enclosure, which during normal transport, restricts the access of unauthorized persons to the cargo space containing the radioactive materials. The enclosure may be either temporary or permanent, may be of the "see-through" type, and must limit eccess
- from top, sides, and ends.
c, 4.10 Open Transport Vehicle A vehicle that does not restrict access to the load; i. e., a flat bed trailer.
3.0 PRECAUTIONS 5.1 Dosimetry
> When handling radioactive materials with radiation levels in excess of 105 Rem / hour, personnel will be issued radiation work permits and medium or high range dosimeters.
[
t' 5.2 Use of survey instruments is recommended in most cases for ALARA purposes and required whenever the movement and handling of radio-active materials can cause a high radiation area to exist (>100 mR/ hour).
l 5.3 Proper industrial safety pracautions must be used when handling heavy j containers and materials or using heavy equipment.
l 6.0 NOTIFICATIONS l 6.1 Notify the consignee of any special loading /unisading instructions prior to the-first shipment.
6.2 Before shipping fissile, Type "B", or large quantities of radioactive l material, notifications to the consignee, NRC, and states through which the shipment will pass must be made in accordance with RDW 5.8, Section 7.0.
6.3 After shipment of fissile, Type "B", or a large quantity of radio-active material, the U.S. Department of Transportation must be notified in accordance with RDW 5.8, Section 7.0.
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RDW 5.2 MINOR Revision 0 03-18-83 SHIPMENT OF LIMITED QUANTITIES OF RADI0 ACTIVE MATERIALS 49 CFR 173.391
~
1.0 GENERAL
, Shipments of limited quantities of radioactive material may be shipped routinely through the mail or by other means provided that the conditions of this procedure are met.
1
2.0 REFERENCES
2.1 49 CFR Parts 100 to 199, Transportation 3.0 SHIPMENT OF LIMITED QUANTITIES JF RADIOACTIVE MATERIAL 3.1 The radioactive materials to be shipped must be classified as " normal form" radioactive meterial and nust not exceed the following quantities.
3.1.1 0.01 mci cf Group I radionuclides.
I(f 3.1.2 0.1 mci of Group II radionucidies.
- a 3.1.3 1.0 sci of Groups III, IV, V, or VI radionuclides.
3.1.4 25 Curies of Group VII radionuclides.
1 3.1.5 Tritium oxide in aqueous solution with a concentration not exceeding 0.5 mci per milliliter and with a total activity per package of not more than three Curies.
3.1.6 A maximum of 1.0 taci of radioactive saterial in "special form" may be shipped as limited quantity.
3.1.7 No more than 15 grams of U-235 may be shipped in any form as limited quantity.
3.2 The above quantities of radioactive material are excepted from specification packaging, marking, and labeling, and are excepted from the general packaging and shipment requirements of 49 CFR 173.393., if l
the following conditions are met.
3.2.1 Must be packaged in strong tight packages such that there will be no leakage of radioactive caterials under conditions normally incident to transportat:.on.
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I RDW 5.2
(~ Page 2 l 3.2.2 The external radiation dose rate at any point en the external surface of the package must not ex9eed G.5 mrem / hour.
3.2.3 There must be no significant removable radioactive surface contamination on the exteriors of the package. (See Table
',' A" . )
ThBLE "A" Maximum Permissible Level Contaminant (dis /m'in)/100 co" Beta gamma. 2200*
Alpha 220*
- The policy at PBNP is to reduce external contamination levels to <MDA. Therefore, contaminction levels in i excess of 10% of those listed above require Health Physics Supervisor approval prior to release.
ff 3.2.4 The outside of the inner container must bear the marking
" Radioactive".
1.0 The shipment of various radioactive devices may also be cade under the
, " limited quantity" designation. For information on this type of shipment refer to 49 CFR 173.391.
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RDW 5.3 MINOR
[ Revision 0 j 03-18-83
, SHI? MENT OF LOW SPECIFIC ACTIVITY RADIOACTIVE MATERIALS 49 CFR 173.392 1.0 GENERAL Shipments of low specific activity radioactive materials (LSA) may be made i under the "exclusi~v e use" or " nonexclusive use" provisions of 49 CFR 173.392.
This procedure will address the requirements for each of these provisions.
2.0 REFERENCES
2.1 10 CPR 71, Packaging of Radioactive Material for Transportation.
2.2 49 CFR Parts 100 to 199, Transportation.
2.3 Specifically 49 CFB 173.392.
2.4 IE Information Notice 80-32, Revision 1, Clarification of Certain Requirements for Exclusive Use Shipments of Radioactive Materials.
( 2.5 File No. HP 2.6, Package Certificate of Compliance.
3.0 EXCLUSIVE USE VEHICLE SHIPMENT OF RADIOACTIVE LSA MATERIAL l
l The following provisions must be fulfilled for each shipment of low l specific activity radioactive material by exclusive use vthicle.
j 3.1 Shipment must meet the requirements for low specific activity radio-active material. See RDW 5.1, Section 3.4.
3.2 LSA radioactive materials which are transported in a transport vehicle (except aircraft) consigned as exclusive use are exempt from speci-fication packaging, marking, and labeling provided the shipment meets the following requirements.
I l
3.2.1 Material must be packaged in strong, tight packages, so that
- 'there will be no leakage of radioactive material under l conditions normally incident to transportation.
3.2.2 Pyrophoric materials (highly flammable, spontanecasly com-l bustible, or water reactive) require special handling and will not be included in shipments from PBNP without the specific approval of the Superintendent - C&HP.
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RDW 5.3
,e Page 2 3.2.3 Packages for shipment to a vaste burial site will contain no free standing liquids. Site licenses require certification of less than 1% or .5% free standing liquids by volume depending on waste form and packaging.
3.2.4 The outside of each package must be stenciled or otherwise marked " Radioactive - LSA".
3.2.5 Packages must not have any significant removable surface contamination (173.392(c)(2)}. See Table "A" below.
TABLE "A" Maximum Permissible Level Cont &dinint dis / min /100 cm' Beta gamma 2200*
Alpha 220*
, *The policy at PBNP is to reduce external contamination f levels to <MDA. Therefore, contamination levels in
-( excess of 10% of.those listed above require Health
, Physics Supervisor approval prior to release.
3.2.6 The radiation dose rate for each package must not exceed the following limits.
" Closed Transport vehicles"
- a. 1000 mrem / hour at three feet from the external surface of the package (closed transport vehicle only).
- b. 200 mrem / hour at any point on the external surface of the vehicle (closed transport vehicle only).
- c. 10 mrem / hour at any point two meters (six feet) from the
- vertical plsnes projected by the outer lateral surface
! . of the vehicle.
1
- d. 2 mrem / hour in any normally occupied position in the vehicle, except that this provision does not apply to private motor carriers.
"Open Transport Vehicles"
- e. 200 mrem / hour at any point on the external surface of the package.
( f. Except for shipping casks, the package transport index (3 foot radiation reading in mR/ hour) must not exceed 10.
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l RDW 5.3
( Page 3 j
- g. Shipping casks may exceed 10 mrem / hour at 3 feet, but must not exceed 10 mR/ hour at two meters (6 feet) from the cask surface. (IE Information Notice 80-32, Revision 1).
- h. 2 mrem / hour in any normally occupied position in the vehicle, except that this provision does not apply to private motor carriers.
3.2.7 Shipment must be loaded by consignor and unloaded by consignee from the transport vehicle in which originally loaded.
3.2.8 There must be no loose radioactive material in the vehicle.
3.2.9 Shipment must be braced so as to prevent leakage or shift of lading under conditions normally incident to transportation.
3.2.10 Th: transport vehicle must be placarded " Radioactive" on all four sides (49 CFR 172.500). .
3.2.11 Specific instructions for maintenance of exclusive use shipment controls (CHP Form 138) must be provided to the
' C~
carrier with the shipping paper information (per RDW 5.8).
4.0 NONEXCLUSIVE USE VEHICLE SHIPMENTS OF RADIOACTIVE LSA MATERIAL
- t. Packages of low specific activity radioactive material shipped under the
" nonexclusive" provisions of 49 CFR 173.392 must meet the following requirements.
- 4.1 Shipment must meet the requirements or low specific activity radio-active material. See RDW 5.1, Section 3.4.
[ 4.2 Package must meet the requirements of 49 CFR 173.335 for radioactive material in normal form (7A specification container).
! '4. 3 Pyrophoric materials require special handling and will not be included in shipments from PBNP without the pecific approval of the l Superintendent - C&HP.
4.4 There must be no significant removable radioactive surface contamina-tion on the exterior of the package. See Section 3.2.5 above.
4.5 Must be packaged so that at any time during normal conditions of transportation the radiation dose rate does not exceed 200 mrem / hour l
at any point on the external surface of the package and the transport index does not exceed 10.
(
4.6 Package must be marked " Radioactive Material LSA, n.o.s." and labeled with the applicable Radioactive White I, Yellow II, or Yellow III 1sbel. See RDW 5.6, Section 4.0.
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RDW 5.3 l r Page 4 5.0 Instructions for completing the necessary shipping papers are contained in RLW 5.8.
6.0 GREA!ER THAN TIPE A QUANTITY OF LSA MATERIAL 6.1 If the total activity of a package of LSA material exceeds the limits for a Type A quantity, check the package Certificate of Compliance to assure that the package is authorized to transport the materiar.
6.2 If the total activity qualifies as a "Large Quantity", make notifications before and after shipment in accordance with RDW 5.8, Section 7.0.
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RDW 5.4 MINOR
,{.
Revision 0 03-18-83 SHIPMENT OF RADIOACTIVE MATERIAL IN TYPE "A", TYPE "B" AND LARGE QUANTITIES 49 CFR 173.395 1.0 GENERAL The shipment of normal form radioactive materials in Type "A", Type "P,", or large quantities may be made provided that the conditions of this procedure are met.
2.0 REFERENCES
2.1 10 CFR 71, Packaging of Radicactive Material for Transportation.
2.2 49 CFR Parts 100 to 199, Transportation.
2.3 Package Certificates of Compliance file HP 2.6.
2.4 IE Information Notice No. 80-32, Revision 1, Clarification of Certain
- Requirements for Exclusive Use Shipments of Radioactive Materials.
l NUREG-0923, Advance Notification of Shipments of Nuclear Waste and 2.5 Spent Fuel.
3.0 SHIPMENT OF RADIOACTIVE MATERIAL IN TYPE "A", TYPE "B", OR LARGE QUANTITIES 3.1 Determine the " quantity" designation of normal form radioactive material to be shipped from the following table.
TABLE "A" Type "A" Type "U' Transportation Quantity Quantity Large Quantity C-roup in Curies in Curies in Curies I 0.001 20 > 20 II 0.05 20 > 20 III 3 200 > 200 IV 20 200 > 200 V 20 5,000 > 5,000 VI and VII 1,000 50,000 >$0,000 Special Form 20(1) 5,000 (1) For Cf-252. The Type "A" quantity limit for special form is two Curies, s 3.2 Shipping Package Selection Refer to procedure RDW 5.10 to select a shipping package.
RDW 5.4
- Page 2 7
3.3 General Packaging and Shipment Requirements In addition to the specific requirements for each type of package (cask) used, the following requirements must be complied with.
3.3.1 The outside of each package must be sealed, which, while intact, will be evidence that the package has not been illicitly opened.
3.3.2 The smallest outside dimension of any package must be four inches or greater.
3.3.3 Internal bracing or cushioning, if required, must be adequate to assure that, under the conditions normally incident to transportation, the distance from the inner containers of radioactive material does not change and the radiation dose rate external to the package does not exceed the transport index number shown on the label.
3.3.4 Inner containers must be positively secured to prevent loss' of contents.
3.3.5 Pyrophoric material 3 require special handling and will not be included in shipr.ents from PBNP without the specific ff__ approval of the Superintendent - C&HP .
3.3.6 Liquid radioactive material in Type "A" quantities must be packaged in or within a leak resistant and corrosion resistant inner container.
3.3.7 Absorbent material must be provided to absorb at least twice the volume of any radioactive liquid centents.
3.3.8 A secondary leak resistant-and corrosio-! resistant container must be provided to t rtain the radioacizve liquids should the inner container fail during shipment.
3.4 There must be no significent removable radioactive surface contamina-tion on the exterior of the package. See Table "B".
TABLE "B" Maximum Permissib33 Level d Contaminant dis / min /lOJ cm Beta gamma 2200*
Alpha 220*
- The policy at PENP is to reduce external contamination levels to <MDA. There fore , contamination levels in i excess of 10% of those listed above require Health Physics Supervisor approval prior to release.
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l RDW 5.4 l Page 2
( j 3.5 The radiation dose rate for each package must not exceed the following limits.
3.5.1 Nonexclusive Use Vehicle Shipments
- a. 200 mrem / hour at any point on the external surface of the package.
The transport index must not exceed 10.
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b.
3.5.2 Exclusive Use Vehicle Shipments - Closed Transport Vehicle
- a. 1000 mrem / hour et three feet from the external surface of the package.
- b. 200 mrem / hour at any point on the external surface of the vehicle, including the bottom.
- c. 10 mrem / hour at any point two meters (six feet) from the vertical planes projected by the outer lateral surface of the vehicle.
d( d. 2 mrem / hour in any normally occupied position in the ,
vehicle, except this provision does not apply to private motor carriers.
3.5.3 Exclusive Use Vehicle Shipments - Open Transport vehicle
- a. Packages other than shipping casks may have maximum radiation levels of 200 mR/ hour contact and 10 mR/ hour at 3 feet.
- b. Shipping casks may have maximum radiation readings of 200 mR/ hour contact and 10 mR/ hour at 2 meters (6 feet) l from the cask surface.
4.0 SHIPMDrr NOTIFICATIONS l
Refer to RDW 5.8, Section 7.0, for notifications required to ship l radioactive materials.
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RDW 5.5 MINOR Revision 0 03-18-83 SHIPMENT OF EMPTY SPENT FUEL CASKS & SPENT FUEL 1.0 GENERAL Empty spent fuel casks shall be received the same as any other radioactive material since all spent fuel casks -are potentially contaminated with radioactive material. Spent fuel shall be shipped similar to cther radio-active material. Procedures are written as guidelines but shall be adhered to as closely as possible.
2.0 REFERENCES
2.1 10 CFR 20.205 2.2 49 CFR Parts 100 through 199 3.0 PRECAUTIONS ON. SPENT FUEL SHIPMENTS 3.1 Loose contamination surveys have been completed before cask is loaded
.- on truck.
3.2 Loose contamination does not exceed 10 ~11 Ci per square centimeter (2200 dpm/100 cm2 ) beta-gamma and 10 12 Ci pe'r square centimeter (220 dpa/100 cm2 ) Alpha.
3 r3 - Final required surveys have been completed after loading.
3.4 The cask contents shall be limited under normal ccnditions of transport that 27 times the neutron dose rate plus 1.4 times the gasuna dose rate will not exceed 100 mrem per hour at three feet from the external surface of the cask.
l l 3.5 The shipping paper description shall include the notation: " Fissile
! Class III Shipment. Personnel Handling and Storing this Shipment must be .tdvised to not Load More Than One Package per Vehicle. In any Loading or Storage Area this Shipment must be Segregated by at Least
. 20 Feet From Other Packages Bearing Radioactive Label."
4.0 SPENT FUEL SHIPMENT The shipment of spent fuel assemblies shall be in accordance with provisions of the facility license and applicable sections of the MRC and Department of Transportation regulations. Prior to the shipment of spent fuel from the plant site, health physics personnel shall survey the truck and spent fuel cask for radiation and contamination levels. Records will be maintained for all shipments of spent fuel.
RDW 5.5 Page 2 g
r 5.0 PROCMDURES FOR SHIPMENT OF EMPTY SPENT FUEL CASK Upon completion of decontamination of the spent fuel cask by operations, Health Physics will survey the cask for shipment.
5.1 With the spent fuel cask in the lowered position in the decon pit, begin taking smears at the top of the cask. Operations personnel will operate the crane and raise the cask as directed. Ensure that the cask is completely dry and free from moisture. At least 50 smears from various locations on the cask will be taken. The smears will then be counted for gross activity on the Nuclear Chicago Counter Scaler and for alpha activity using the porthble alpha counter PACI-SAGA.
5.2 All results are to be recorded on a survey form.
5.3 It is expected that the removable contamination level of the cask should be below 1000_dpm/100 cm 2 beta gamma. Small areas with contamination levels >1000 dpm/100 cm2 but less than 2200 dpm/100 cm 2 beta'ganuna may be accepted for release as determined by a C&HP Supervisor. Areas of greater contamination than that listed above will be decontaminated by Operations and resurveyed by Health Physics.
Allowable shipping limits are outlined under precautions and shall be
. - . adhered to.
( 5.4 Record all results on the survey form.
5.5 After the smear surveys are completed and comply with the loose contamination limits, the C&HP Supervisor will notify Operations that the cask can be loaded.
5.6 Upon completion of loading, operations and Health Physics will wipe down the trailer to remove any contamination that may have been transferred during the loading operation. Health Physics will then smear the trailer for release. All smears will be counted for gross activity using the Nuclear Chicago Counter Scaler and for alpha with the portable. alpha counter PACI-SAGA.
5.7 All results will be recorded on the survey form.
5.8 After the loaded trailer is removed from the truck access area, the
. following surveys will be taken:
5.8.1 Beta gasuna and neutron radiation surveys will be taken at:
- a. Contact of the cask.
- b. Three (3) feet from the cask.
- c. Six (6) feet from the cask.
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The result shall be recorded on the survey form.
e-e--n --m--- - - - - , - _ . _ , _ . _
f-RDW 5.5 '
( Page 3 i
5.8.2 A beta gamma and neutron survey will be taken inside of the l tractor and sleeper and recorded on the survey form.
NOTE: ALL BETA GAMMA PLUS NEUTRON READINGS IN ANY AREA OCCUPIED BY THE DRIVER MUST BE LESS THAN 2 MR/HR.
5.8.3 Upon completion of all surveys, the CEIP Supervisor will complete Radioactive Material Shipment Record, provide the driver with two copies and release the truck from the controlled zone.
5.8.4 'All survey forms and copies of Radioactive Material Shipment i Record will be left in the health physics station before forwarding to the C&HP office.
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RDW 5.6 g MINOR Revision 0 03-1d 33 MARKING AND LABELING REQUIREMENTS FOR SHIPMENTS OF RADI0 ACTIVE MATERIAL PACKAGES 1.0 GENERAL Marking and labeling of radioactive material packages is specified under the Department of Transportation regulations. The following terminology refers to the specific requirements that must be fulfilled prior to shipment.
2.0 REFERENCES
2.1 49 CFR Parts ?.00 to 199, Transportation.
2.2 HPSO 10, Use of Radiation Measurement Instruments io" Radioactive Material Package Surveys.
3.0 MARKING (49 CFR 172.300) 3.1 Each package containing radioactive material for transportation shall
.- be marked with the applicable shipping name from the following list elN unless exception is granted by regulation.
3.1.1 Radioactive Device, n.o.s.
3.1.2 Radioactive Mat % rial, fissile, n.o.s.
3.1.3 Radioactive LSA, n.o.s.
3.1.4 Radioactive Material, n.o.s.
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3.1.5 Radioactive Material, Limited Quantity, n.o.s.
l 3.1.6 Radioactive Material, Special Form, n.o.s.
3.2 All marking must be durable and printed on or affixed to the surface l
t of a package or printed on a label, tag, or sign attached to the package. Marking must be of a sharply contrasting color and must not l
be obscured and must be located away from other marking that could reduce its effectiveness. Abbreviations may not be used unless specifically authorized by this procedure or by 49 CFR.
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RDW 5.6 fr Page 2 3.3 Each package of radioactive material offered for shipment must be marked as follows.
3.3.1 Packages in excess of 110 pounds must have the gross weight marked on the outside.
3.3.2 Packages conforming to Type "A" or Type "B" packaging must be marked with the words " Type A" or " Type B" in letters at least one-half inch in height. In addition, Type "A" packages must be marked " USA DOT 7A" in letters at least one-half inch high.
3.4 Packages of radioactive material that are transported via a non-
). exclusive use vehicle will be marked with the name and address af Point Beach Nuclear Plant or the consignee. Exempt quantities need not meet this requirement (49 CFR 172.306).
3.5 As of July 1, 1983, packages of 110 gallons or less capacity must be marked with the DOT identification number corresponding to the shipping name marktd on the package (49 CFR 172.301).
4 3.5.1 Shipping. names and DOT identification numbers commonly used
/ ; at Point Beach Nuclear Plant are below:
s Radioactive Material, n.o.s. NA 9181 Radioactive Material, LSA, n.o.s. UN 2912 Radioactive Device, n.o.s. UN 2911
- Radioactive Material, Limited Quantity, n.o.s. UN 2910 1
3.5.2 A list of all shipping names and their associated identifica-tion numbers is found in the Hazardous Materials Table, 49 CFR.172.101.
3.5 Limited Quantities Limited quantities of radioactive materials and radioactive devices are not required to have any markings or labels on the outside container.
Refer to RDW 5.2 for details.
4.0 LABELING (49 CFR 172.400) 4.1 Unless excepted from labeling by regulation such as limited quantity or exclusive use vehicle shipments of low specific activity material, each package of radioactive material offered for shipment must be labeled as one of the following.
( 4.1.1 Radioactive White I Label This label will be used for packages meeting the following requirements:
- a. Measures less than 0.5 mrem / hour at any point on the
RDW 5.6 Page 3 g
- b. Does not contain Fissile Class II or III radioactive material.
- c. Does not contain a 'large quantity" of radioactive material.
4.1.2 Radioactive Yellow II This label will be used for packages meeting the following requirements:
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- a. Measures more than 0.5 Elem/ hour but not more than 50 mrem / hour at any point on the surface of the package.
L l b. Does not exceed one mrem / hour at any point three feet from the external surface of the package.
Meets the requirements for Fissile Class II package c.
having a transport index of one or less.
! 4.1.3 Radioactive Yellow III g( This label will be used for packages meeting the following i requirements:
' a. Muasures more than 50 mrem / hour at any point on the surface of the package.
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! b. Exceeds one mrem / hour at any point three feet from the external surface of the package.
- c. . Meets the requirements for Fissile Class III package,
- d. Contains a "large quantity" of radioactive materu l.
4.1.4 Measurement and records of radiation levels should be to the nearest .1 mR/ hour for readings less than 2.0 mR/ hour, to the nearest 1 mR/ hour for readings up to 11 mR/ hour, to the
- nearest 5 mR/ hour up to 55 mR/ hour, and to at most two significant figures above 55 mR/ hour.
4.2 Packages of radioactive material which also meet the definition of an additional hazard class must be labeled to reflect the additional hazard. Refer to 49 CFR 173.2 for hazard, class listing and exceptions.
4.3 The following inforr; tion must be entered on the RADIOACTIVE label chosen in Section 4.1 by printing, using a durable weather resistant marking.
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4.3.1 For mixtures of radionuclides the most restrictive radio-nuclides on the basis of radiotoxicity must be listed as space on the label allows as defined by 49 CFR 173.390. The lower the group number, the more restrictive is the radio-toxicity. Symbols such as co-60, Cs-137 Are authorized.
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RDW 5.6 Page 4
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4.3.2 Number of Curies Enter the total activity of the package in Curies.
4.3.3 Transportation Index Enter the highest dose rate measurement at three feet from the external surface of the package. (Not applicable to l White - I labels.)
t NOTE: ALL ENTRIES ARE TO BE MADE WITH INDELIBLE INK. A " SHARPIE" PEN IS SUITABLE. [49 CFR 172.403(g)]
4.4 Empty Label 4.4.1 Any packaging which has been used for a shipment of radio-active material and which contains internal contamination above the ;evels listed be16w must be labeled with the
" Empty" label (49 CFR 173.29(b).
Contaminant Dis / Min /100 cm 2 l [n l
Beta Gamma 2200 i
( Alpha 220 4.4.2 Radiation at the external surface of the package must not exceed 0.5 millirem per hour. ..
5.0 PLACEMENT OF LABELS on PACKAGE (49 CFR 172.406) 5.1 The following specifies the manner in which labels will be printed or affixed to the surface of the package.
! 5,1.1 Labels must be displayed on at least two sides or two ends of each package of radioactive material.
5.1.2 Vehicle placarding may not be used in lieu of package labeling.
. 5.1.3 One of each of the appropriate labels must be displayed on or near the package closure.
5.1.4 Labels must not be obscured by narkings or attachments.
l 5.1.5 All labels must conform to the specifications given in 49 CFR 172.407.
6.0 OVERPACKS [49 CFR 173.393(r)]
, 6.1 Packages of radioactive matarial transported in an overpack must l , comply with all packaging, marking and labeling requirements as if no overpack was used.
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R5W 5.6 Page 5 g
6.2 The overpack must also be marked and labeled. [49 CFR 173.25]
6.2.1 Markings will include all applicable proper shipping names.
An overpack can have more than one shipping name marked on it.
6.2.2 The overpack ;hould be marked "INSIDE PACKAGES COMPLY WITH PRESCRIBED REGULATIONS."
6.2.3 Overpacks containing only LSA or limited quantities or a mixture of both need not be marked as specified in Section 6.2.2, 6.2.4 The overpack must be labeled as per Section 4.0 above.
However; the label entries are detennined as follows:
- a. The " contents" entry on the label may state " mixed" unless each inside package contains the same radio-nuclide(s).
- b. The number of 1, ries is determined by adding together the Curies of each package in the overpack.
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! c. The transport index is determined by direct measurement of the overpack dose rate at three feet from the surface unless the overpack contains fissile material. .
- d. If the overpack contains fissile material, the transport -
index is determined by adding together the transport indices of the packages contained inside.
6.2.5 The transport index of an overpack is limited by the mode of transport as listed below:
Transport Mode Transport Index Limit Passenger Aircraft 3.0 Cargo Only Aircraft 10.0
. Nonexclusive Use Vehicle 50.0 Exclusive Use Vehicle No Limit 6.2.6 The transport index of a nonexclusive use vehicle is determined by adding the transport indices of all packages on the vehicle. The total may not exceed 50.0. See procedure RDW 5.7 for details.
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RDW 5.7 MINOR Revision 0 03-18-83 VEHICLE LOADING, SURVEYS AND PL& CARDING PROCEDURES FOR SHIPMENTS OF RADIOACTIVE MATERIAL 1.0 GENERAL This procedure provides direction and guidelines for the loading, surveying, and placarding of vehicles carrying radioactive materials either arriving at or departing from PBNP.
2.0 REFERENCES
2.1 49 CFR Parts 100 to 199, Transportation.
2.2 RDW 4.1, Receipt of Radioactive Material 2.3 RDW 5.9, Documentatic. of Shipping Packaggs 2.4 Letter, dated January 22, 1982, from C. W. Fay to H. G. Shealy outlining drum bracing requirements. (Plant File 12.8 SC) 3.0 VEHICLES ARRIVING ONSITE 3.1 Vehicles arriving onsite carrying radioactive material or intended for radioactive material transport, will be surveyed in accordance with RDW 4.1.
3.2 Surveys should be completed and the results reported to the supervisor in charge of loading the vehicle before loading begins.
3.3 Visually inspect the condition of the vehicle tires and wheels,
' flooring, welds and support beams. Report any leaks, cracks, or deterioration to the Health Physics Supervisor or Nuclear Plant Specialist or Engineer assigned to radwaste.
4.0 CARGO LOADING 4.1 Package Inspection 4.1.1 All packages used to transport radioactive material with activity exceeding 2.0E-9 Ci/g (9.1E-1 pCi/lb.) will be inspected by a C&HP Supervisor or a person designated by him.
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RDW 5.7
. /' Page 2 4.1.2 Packages will normally receive two inspections.
- a. The first inspection should be done within five working days of the shipment and will be documented on the
' checkoff of form CHP-7d. This inspection is intended to i be the primary assurance that the package is properly prepared for shipment. .
- b. The second inspection will be a visual check at the time ti,e package is loaded. This will assure that no deteri-oration of the package has occurred since the first inspection. The second inspection will be documented by signing off the bottom of form CHP-78.
If no inspection document is required by procedure RDW c.
i 5.9, form CHP-78 (Package Inspection Checkoff) will not be used. The first inspection requirement is also waived. However, the visual check must be performed. A Health Physics Supervisor or Nuclear Plant Specialist
> (or Engineer) will approve the package for shipment. If it meets the criteria of a strong tight container, it-
- f- may be shipped. In this case, the signature of the Supervisor or Nuclear Plant Specialist (or Engineer) on l(- CHP-11, Radioactive Material Shipment Form, will be evidence that the package was properly inspected.
1 i 4.1.3 Casks will be inspected in accordance with their applicable cask checkoff forms when the vehicle arrives on site.
4.2 Pallet Inspection 4.2.1 If packages are shipped on pallets, the supervisor loading the truck shall assure that:
- a. Package is securely banded or otherwise attached te the l pallet.
! b. The pallet is strong enough to support the' package
. during the trip.
4.2.2 Drums weighting 2 800 lbs., which are destined for the Barnwell, SC, disposal site, must be palletized.
l 4.2.3 Drums weighting between 600 and 800 lbs, which are sent to Barnwell, SC, must be palletized only if they are shipped in a fixed top trailer.
4.2.4 Drums shipped to Richland, WA, need not be palletized.
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4.2.5 A pallet should have two more more drums on it.
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RDW 5.7
- / Page 3 4.2.6 Drums should be banded to the ?allet as fellows
- a. One band over top of each drum.
- b. Two bands around the drums.
4.3 Bracing the Load 4.3.1 Sufficient bracing shall be used to prevent movement of the packagu during conditions normally incident to transport (bouncing, swaying, sliding, etc.).
i 4.3.2 The supervisor in charge of loading should inspect the i bracing before shipment.
4.3.3 Palletized drums should be placed against walls or other secure drums if possible. Drum braces should be used to secure a pallet if the trailer walls and other drums cannot be used to surround it.
4.4 Radiation Surveys During Loadinq When more than one package is to be shipped, and when the packages
' have contact readings in excess of 50 mR/ hour, the truck should be
,i - surveyed as the packages are loaded. If the limits in Section 6.0 below are exceeded, the load should be changed to meet the limits.
4.5 Weight of Load 4.5.1 Check with the carrier to assure that the weight of the packages does not exceed the vehicle's capacity.
- 4.5.2 Authorized weights for casks can be found in file HP 2.6.
4.6 Separation From Other Cargo 4.6.1 Packages of radioactive material bearing a Yellow II or Yellow III label that are transported in a non-exclusive use vehicle should be separated from the rest of the cargo as follows:
- a. At least 7 feet from any personnel area or compartment on the vehicle.
- b. At least 36 feet from any undeveloped film.
4.6.2 If the distances above cannot be met, contact the Nuclear Plant Specialist or Engineer assigned to radwaste and refer to 49 CFR 177.942.
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RDW 5.7 Page 4
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5.0 CONTAMINATION CONTROL 5.1 .Whenever practical, locate vehicles to be loaded outside the controlled zone.
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5.2 For vehicles that are brought into the controlled zone, establish a stepoff pad for the truck. The truck will be treated as a clean ares. As a minimum, all personnel working on the truck surfaces will
, change into clean shoe covers.
5.3 A stepoff pad may also be established for vehicles loaded while located'outside the controlled zone to provide convenient access.
However, except for activities necessary for loading the transport vehicle, all personnel must still enter and leave the controlled zone in the normal manner.
j 6.0 VEHICLE SURVEYS i
61 Closed Transport, Exclusive Use Vehicle
, After the transport vec.icle is leaded and the cargo secured from shifting, the following surveys are required.
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- - c , 6.1.1 Complete a smear survey to check for the presence of l
removable alpha and beta-gamma contamination in those areas
! where contamination is most likely to occur, including cargo L
i access doors and suspect areas as identified by visual
! ; inspections. As a minimum, take two smears on each interior i side of the vehicle, two on the exterior surface of the trailer doors, and two on the off-loading area at the back of the vehicle.
6.1.2 Move the transport vnhicle to the controlled zone barrier L (if inside the controlled zone) and take a removable contamination (smear) survey of all vehicle tires. If Ga vehicle did not enter the controlled zone, tire an ars are
, unnecessary.
Co,ntamination limits are listed in Table "A" below.
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TABLE "A"
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Maximum Permissible Level y Cor.t'asinant dis / min /100 cm 2 Beta Gamma 2200*
^ j Alpha 220*
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- The policy at PLNP is to reduce the removable i
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contamination, levels to less than MDA. Therefore, contamination levels greater thm MDA require l
- approval of a C&HP. Supervisor prior to release.
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RDW 5.7 Page 5
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6.1.3 Complete the following radiation dose rate measurement survey. A sufficient number of measurements should be taken to ensure that the following limit.= are not exceeded:
- a. 2 mrem / hour anywhere in the driver's compartment.
< b. 1000 mrem / hour at three feet from the external surfaca of the package. ,
- c. 200 mrem / hour at any point on the external surface of the vehicle (sides and bottom).
- d. 10 mrem / hour at any point two meters (six feet) from the vertical planes projected by the four sides of the vehicle.
- e. If measured levels are above 50% of the limits, use a second instrument to verify compliance and notify Health Physics supervision concerning the situation.
NOTE: DO NOT ESTIMATE DISTANCES IN PARAGRAPH d ABOVE WHEN DOSE RATE MEASUREMENTS ARE CLOSE i
TO 10 MREM / HOUR. USE A TAPE MEASURE.
t l 6.1.4 on completion of the above survey:
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I 1. Install tamper proof seals on all doors.
- 2. Place RADI0 ACTIVE placards on the rear, sides, and front
! of vehicle. Placards should be securely installed.
(See Section 7.0 below.)
6.2 Open Transport, Exclusive Use Vehicle Shipments 6.2.1 Radioactive material packages being transported in an open type vehicle must meet the following requirements.
- a. Radiation dose rate must not exceed 200 mrem / hour at any point on the external surface of the package.
- b. Except for casks, package transport indes must not exceed 10.0.
- c. Shipping casks may exceed 10 mR/ hour at 3 feet, but must l not exceed 10 mR/ hour at two meters (6 feet) from the sides of the cask.
- d. External removable contamination on the surface of the
( package must meet the following limits.
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RDW 5.7
- - Page 6
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TABLE "A" -
Maximum Permissible Level Contaminant dis /mir/100 cm 3 I
Beta gamma 2200*
Alpha 220*
- e. If package radiation limits exceed 50% of the limits above, resurvey the package with a second instrumer:t to l verify compliance and notify Health Physics supervision concerning the situation.
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- The policy at PBNP is to reduce removable contamination levels to <MDA. Therefore, contamination levels g* tater than MDA require approval of a C&HP Supervisor prior to loading.
6.2.2 Brace the load so that it won't move under conditions normally incident to transport.
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6.2.3 Shipping casks will be surveyed after loading to assure that 6 its radiation and contamination levels are within the limits' specified by Section 6.2.1 above. Be sure to :neasure radiation levels underneath the vehicle. .
6.2.4 Perform a smear survey of the accessible parts of the cargo area floor. If the vehicle was on th controlled side, bring it to the boundary and smear the tires. Removable contamina-tion must meet the limits of Table "A" in Section 6.2.1 l
i above.
l 6.2.5 Perform a radiation survey of the vehicle to veri f that the following limits are not exceeded: ,
i l a. 10 mR/ hour at'any point six feet from the vertical I planes projected by the outside edge of the vehicle.
- b. 2 mR/ hour at any point in the normally occupied portions of the vehicle; i.e., the cab of the truck.
- c. If measured levels are above 50% of the limit, use a second instrument to resurvey the vehicle and notify Health Physics supervision of the situation.
6.3 Nonexclusive Use Vehicle shipments
. 6.3.1 All packages must not exceed the radiation and contamination s
limits of Section 6.2.1 above.
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RDW 5.7 Page 7
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6.3.2 Braca the packages so they will not move during conditions normally incident to transportation.
6.3.3 The number of packages loaded on the vehicle must be limited so that the sum of the transport index numbers of the packages does not exceed 50.
Example: Suppose three packages, each with a transport index~of nine were to be shipped. The sum of the transport index numbsrs is 9 + 9 + 9 = 27.
This is an acceptable load.
6.3.4 The vehicle driver is responsible for assuring that the addition of radioactive materisi packages to his load will not result in a total transport index sum greater than 50.
This is noted on form CHP-138, Carrier / Driver Instructions.
6.3.5 Radioactive material will not be shipped via cciaercial passenger carryjng vehicles, such as a bus or taxi.
6.3.6 Perfor:n a smear survey as follows:
(_ a. If the package has been placed on the clean side and the vehicle has not. entered the controlled zone, no smear survey is necessary.
- b. If the package has not been placed on the clean side and the vehicle has not entered the controlled zone, complete a smear survey of the vehicle as described in Section 6.1.1 above.
- c. If the vehicle has entered the controlled zone, move it
'to the boundary, and complete a smear survey of all I vehicle tires as well as a smear survey of the vehicle as described in Section 6.1.1 above.
- d. Contamination levels must not exceed the limits in
- Table "A" of Section 6.2.1 above.
6.3.7 Perform a radiation survey in accordance with Table "B" below.
TABLE "B" Package Surface Radiation Survey Radiation Measurement Required
< 2.0 mR/ hour None 2 2.0 mR/ hour Survey truck cab to assare level is < 2.0 mR/ hour NOTE: REFER TO SECTION 4.6 ABOVE IF A PACKAGE BEARING A YELLOW II OR YELLOW III LABEL IS BEING SHIPf5.'D.
RDW 5.7 Page 8
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7.0 VEHICLE PLACARDING (49 CFR 172.500)
The following placarding requirements will be adhered to for vehicles
! transporting radioactive materials from the PBNP.
7.1 Vehicles carrying packages with Yellow-III labels or being used under the exclusive use rules normally must be placarded.
l 7.2 The radioactive placard will be placed on each side and each end of the transport vehicle. The front placard may be on the tractor, or trailer, or both, when a semi-trailer truck is used.
7.3 The placard must be securely attached and positioned, if possible, so that water is not directed to it from the wheels of the vehicle.
7.4 The placards must be placed in a readily visible position.
I l 7.5 Large quantity placard
( When a large quantity is to be shipped, the radioactive placard must t
be on a white square background with a black border. Refer to 49 CFR
.- 172.507 and 172.527 for details.
IC 7.6 Exceptions to this procedure w:.Al be on a case-by-case basis as specified by 49 CFR 172.500.
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RDW 5.8 MINOR
{s Revision 0 03-18-83 I
SHIPMENT SCHEDULING AND SHIPPING PAPER PREPARATION I
FOR RADIOACTIVE MATERIAL SHIPMENTS 1.0 GENERAL Radioactive material shipping is subject to many State and Federal '
regulations. Shipping papers are among the items examined for accuracy by carriers, radwaste contractorr, and government inspectors. Improperly prepared shipping papers can result in fines, and if violations are repetitive, even exclusion from burial facilities.
Therefore, it is important to be accurate and complete when preparing the shipping papers.
2.0 PURPOSE
! The purpose of this procedure is to enable a person to accurately and -
i completely prepare shipping papers for radioactive material shipments.
Additionally, this procedure will enable a person to make required telephone notifications and make proper file entr.ies for documentation of
[. the shipment.
3.0 REFERENCES
3.1 Act No. 499, South Carolina Radioactive Waste Transportation and Disposal Act.
3.2 Chem-Nuclear Site Criteria and License for Barnwell Facility.
3.3 U.S. Ecology, Inc., Site Criteria and License for Richland Site.
3.4 Procedures HP 3.1 and RDW 5.1.
3.5 49 CFR Parts 100 to 178.
3.6 State of Washington Section WAC 402-19-500, Preparation of Radioactive Material for Transport.
3.7 Forms CHP-11c and CHP-lld, Radioactive Material Shipment Checkoffs.
3.8 10 CFR 71, Packaging of Radioactive Material for Transport and Transportation of Radioactive Material under Certain Conditions.
3.9 NUREG-0923, Advance Notifications of Shipment of Nuclear Waste and Spent Fuel.
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RDW 5.8
- Page 2 !
t 1 3.10 HPSO 2, Completing Shipping Papers for Radioactive Material Shipments.
3.11 Chem-Nuclear letter dated March 19, 1982, referring to certifications required to use high integrity containers.
, 3.12 Chem-Nuclear letter dated Februar? 12, 1982, referring to resin and filter disposal.
4.0 SHIPMENTS OF LOW LE*JEL WASTE TO U.S. ECOLOGY AT RICHLAND, WASHINGTON 4.1 Transportation will normally be arranged by the Nuclear Plant Specialist or Engineer assigned to radwaste.
4.2 Forms are listed below.
Form Number Form Title CHP-ll Radioactive Material Shiprent Record CHP-11d Radioactive Material Shipment Checkoff for Shipments to U.S. Ecology I
!f CHP-138 Carrier / Driver Instructions for Radioactive 21 Material Shipments CHP-21 Area 35 Radiological Survey CHP-21 Area 36 Radiological Survey for Casks & Liners
U.S. Ecology, Inc. Radioactive Waste Shipment and Disposal Form
U.S. Ecology Inc. Waste Shipment Continuation Sheet CHP-16 Waste Permit Form CHP-156 Large Quantity Radioactive naterial Shipment checkoff CHP-158 Advance Notification of Large Quantity Shipment DSHS RHF-31A Washington State Low Level Radioactive Waste Shipment certification for commercial Generator / Packages and Brokers and Carriers 4.3 Type "B", or Large Quantity
( See Section 7.0 below for notifications required.
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, _ , , , - - - - - - - - y-, , ,-,, - , ,- ,,,,-,,ry,% ,,-e-,. _... , , , , _n,__,m_,,,,_y, _-.. , _- _ _-..v.,- .. , - , , ,,,., _.e., -.
RDW 5.8 I
Page 3 4.4 Forms are to be completed as fully as possible before the shipping date. They must be fully complete before the shipment leaves the plant.
Telephone notifications noted on CHP-lld, Radioactive Material Shipment checkoff, may be completed as soon as practicable after the truck leaves PBNP.
4.5 Distribute copies of the forms as specified by the Radioactive Matericls checkoff Shaet, CHP-11d.
4.6 Telephone notifications are listed below. They should be made as soon as possible after the shipment leaves.
4.6.1 Richland Site - 509/377-2411 Give:
- a. Bill of lading number
- b. Dates of shipment and expected arrival
- c. Quantity e(
- d. Carrier
- e. Tractor and trailer number
- f. Special unloading instructions, if any -
4.6.2 Ready Stores, Point Beach Nuclear Plant Give:
- a. Date
- b. Cubic feet shipped
- c. Destination 4.6.3 Control Room Duty Shift Supervisor, PBNP Give:
- a. Departure time
- b. Cask type, if any s
- c. Contents
RDW 5.8
( Page 4 4.6.4 Weir;h Station, State of Washington Depending on the route the carrier uses, call Spokane (on I-90) phone number 509/266-3366, or Plymouth phone number 509/783-6492. Give:
- a. Arrival time
- b. Carrier
- c. Tractor and trailer number 4.7 File entries are listed below.
4.7.1 File the Waste Permit Form, CHP-16, in file HP 2.4. This form is not a part of the shipping papers.
4.7.2 File the white copy of CHP-21 in file'HP 1.9.
4.7.3 Place applicable copies of the other forms listed in Section 4.2 above into file HP 2.1.1.
- [~ 4.7.4 Enter the date, Point Beach Nuclear Plant bill of lading s nu=her, consignee, volume, activity in Curies, and package type in file HP 2.1.
4 4.7.5 Forward a list of waste permit numbers of the items shipped to the Health Physics Supervisor in the Health Physics -
Station for checkoff on CHP-43, Waste Operations Report, file HP 2.5.
5.0 SHIPMENTS OF LOW LEVEL WASTE TO CHEM-NUCLEAR, BARNE, S0tml CAROLINA 5.1 Scheduling Barnwell Shipments Scheduling shipments to the chem-Nuclear disposal site in Barnwell, South Carolina, normally must be done between one and three months before the date of shipment. Scheduling date deadlines are set by
. Chem-Nuclear and can be obtained from the Naclear Plant Specialist or Engineer assigned to radwaste.
Two things are done to schedule the Wipment. First, ob'tain a volume allocation plan (VAP) number from C:am-Nuclear. Second, arrange for a carrier to transport the load to darnwell, South Carolina.
5.1.2 Obtain the volume allocation plant number from Chem-Nuclear allocations section. The telephone contact number is 803/259-3577.
N 5.1.2 Selection of a carrier can be made t.hrough the Chem-Nuclear dispatcher by calling 803/259-1781. It is not mandatory to select a carrier through Chem-Nuclear. Contact the Nuclear Plant Specialist or Engineer assigned to radwaste for details on otner carriers.
RDW 5.8 Page 5
.g 5.2 Forms Required Listed below are forms required for radwaste shipments to Chem-Nucitar in Barnwell, South Carolina.
Form Number Form Title RHA-PNC or South Carolina Prior Notification and Manifest DHEC 802 RHA-CT or South Carolina Waste Shipment Certification DHEC 803 CHP-ll Radioactive Material Shipment Record CNS-201 Bernwell Management Facility Radioactive Shipment Record CHP-21 Area 35 Radiological Survey
! CHP-21 Area 36 Radiological Survey f[
- y CHP-131 Series Cask Checkoff Sheets CHP-138 Carrier / Driver Instructions for Radioactive Material Shipments CHP-157 Resin and Filter Disposal Checkoff CHP-lle Radioactive Material Shipmen't Checkoff Sheet for Chem-Nuclear Shipments CHP-156 Large Quantity Radioactive Material Shipment l
Checkoff l CHP-158 Advance Notification of Large Quantity Shipment i
Bill of Lading t
. NOTE: 1HE SOUTH CAROLINA PRIOR NOTIFICATION AND MANIFEST, RHA-PNC, MGT ARRIVE AT THE CHEM-NUcTIAR, BARNWELL, SOUTH CAROLINA,
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! 0FFICES THREE DAYS BEFORE THE SHIPPING DATE.
THE SOUTH CAROLINA PRIOR NOTIFICATION AND MANIFEST MUST PE IN THE SCUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL, COLUMBIA, SOUTH CAROLINA, OFFICES THREE DAYS BEFORE <
l J..E LOAD ENTERS SOUTE CAROLINA, BUT NOT MORE THAN 30 DAYS l AHEAD OF TIME.
I. ( HAIL THE FORMS TO THE ABOVE LOCATIONS WELL AHEAD OF TIME i l l SINCE FAILURE TO HEET THESE DEADLINES CAN RESULT IN DELAYS IN WASTE BURIAL OR FINES.
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RDW 5.8 Page 6 5.3 Forms should be filled out as completely as possible before the shipping date. This will allow more time to accurately finish completion of the forms on the actual shipping day.
NOTE: CERTIFICATIONS REQUIRE INSPECTION OF THr LOAD WITHIN 48 HOURS OF THE SHIPMENT. PERFORM THE INSI'CTION, SIGN, AND DATE SUCH FORMS IN THE PRESCRIBE's TIME LIMITS.
5.4 Bill of Lading Occassionally drivers have bills of lading which require attention.
Look over the forms carefully and provide necessary infonmation.
Identify waste material accurately. If the driver has no bill of lading, CHP-11, Radioactive Material Shipment Record, is the bill of lading.
5.5 Distribution Dirl.tibute copies of forms as specified by CHP-11c, Radioactive Material Shipment checkoff for Shipments to Chem-Nuclear. ,
5.6 Telephone Notifications
- .{
Telephone notifications should be made as soon as possible after the
~
truck leaves the site. The calls are listed below.
5.6.1 Barnwell Allocation Section 803/259-3577 Give:
- a. Allocation number I b. Changes and additions to South Carolina Prior l
Notification Form, RNA-PNC, if any 5.6.2 Barnwell Dispatcher 803/259-1781 I Give: "
- a. Trailer number
- b. Cask number, if any l
l c. Departure tiac
! d. Estimated date of arrival l
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I RDW 5.8 Page 7
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5.6.3 South Carolina Bureau of Radiological Health 803/758-7806 or 803/758-7951 Give:
Changes and additions to South Carolina Prior Notification Form, RHA-PNC, if any. Typically, the trailer number and owner must be ut. dated since these items may not be known until the truck arrives. Update other information as necessary.
5.6.4 Ready Stores, PBNP Give:
- a. Date
- b. Cubic feet shipped
- c. Destil.ation 5.6.5 Control Room Duty Shift Supervisor, PBNP Give:
.( <
- a. Departure time
- b. Cask type, if any
- c. Contents 5.7 File Entries 5.7.1 Place waste permit forms, CHP-16, in file HP 2.4. These forms are not part of the shipping papers.
( 5.7.2 File the white copy of CHP-21 in file HP 1.9.
5.7.3 Place the applicable copies of all other forms listed in~
. Section 5.2 above in file HP 2.1.1.
5.7.4 Enter the date, PBNP bill of lading number, consignee, volume, activity in Curies, and package type in file HP 2.1.
5.7.5 Provide a list of waste permit numbers of the items shipped to the Health Physics Supervisor in the Health Physics station for checkoff on form CHP-43, Waste Operations Report, file HP 2.5.
s 5.7.6 Advance notification of a large quantity shipment, if any, should be attached to the shipping papers and put in file HP 2.1.1.
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RDW 5.8 Page 8
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6.0 SHIPMENTS OF RADIOACTIVE MATERIAL TO PLACES OTHER THAN BURIAL SITES (VENDORS, CONTRACTORS, LABORATORIES, ETC.)
6.1 Scheduling the Shipment 6.1.1 Call the consignee to which the shipment will be made to arrange a date.
6.1.2 Contact Ready Stores, PBNP. They will arrange for a carrier.
6.2 Required forms are listed below.
Form Number Form Title CHP-ll Radioactive Material Shipment Record CHP-lle Non-Radwaste Radioactive Material Shipatat Checkoff Sheet CHP-138 Carrier / Driver Instructions for Radioactive Material Shipments CHP-21 Radiological Survey 1
NOTE: A. IF THERE ARE MORE ITEMS THAN CAN BE LISTED ON CHP-11, THE LIST CAN BE CONTINUED ON CHP-11a.
4 B. LIMITED QUANTITIES OF RADIOACTIVE MATERIAL DO NOT REQUIRE CHP-138.
4 6.3 Contact a Health Physics Supervisor to complete the forms.
l 6.4 Distribute copies of forms as specified on CHP-11d.
.6.5 Send the Health Physics copies to the Nuclear Plant Specialist or Engineer assigned to radwaste for review and filing in file HP 2.1.4.
l 7.0 SHIPMENT NOTIFICATIONS i
7.1 Fissile, Type "B", and Large O_uantity Shipment 7.1.1 Prior to each shipment of fissile, Type "B", and large l
quantity radioactive materials, notify the consignee of the date of shipment and expected arrival date (49 CFR 173.22(b)).
l
' a. For shipments to the Barnwell, SC, disposal site, the South Carolina Radioactive Waste Shipment Prior Notifi-cation and Manifest Form (Form No. DHEC 802 or RHA-PNC) v should be used as written notification to Chem-Nuclear.
It should be mailed to Barnwell at least 7 days before the shipping date. It should be sent by registered mail.
l .
- b. For shipments to destinations other than Barnwell, SC, the appropriate information should u_,... be sent by registereda.mail
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RDW 5.8
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7.1.2 Within 90 days following the shipment of fissile, Type "B",
or large quantity radioactive material, notify the Associate Director for Hazardous Materials Regulation, MTB by mail of the shipment. (49 CFR 173.22(c)) The information transmitted shall include-
- a. The shipment route plan and supplements, if any.
- b. A atatement identifying the name and address of the shipper, carrier and consignee.
- c. A copy of the shipping paper.
7.2 Large Quantity Shipments 7.2.1 In addition to notifications required by Section 4.1 above, notification must be made in writing to the office of the governor of each state into or through which the shipment '
will pass and to NRC Region III.
7.2.2 Fill in the information requested on form CHP-158, Advance Notification of Large Quantity Shipment.
7.2.3 The form should be sent by registered mail postmarked at least 7 days before beginning* of the 7-day period in which the shipment is to occur.
7.2.4 Changps tc the shipping schedule may be telephoned to the appropriate governors offices and NRC. Record the names of the individual contacted on form CHP-158.
7.2.5 If the shipment is canceled, a written cancellation notice shall be sent to NRC and the appropriate governor's offices.
7.2.6 Copies of the notifications should be kept with the shipping papers.
7.2.7 A list of state officials to be notified can be found in
, file HP 2.8.
7.3 Alternate Notification Method 7.3.1 A notification required by Section 7.2 or 7.3 above can be j made by messenger provided that it arrives in the appropriate official's office at least 4 days before the 7-day period in which a shipment will occur. A telecopy can be considered a
" messenger."
s 7.4 Filr. Entries Attach copies of advance notifications to the shipping papers for filing.
RDW 5.8 y Page 10 8.0 SCINTILLATION FLUIDS 8.1 In addition to the requirements listed in Sections 1.0 through 7.0 of this procedure, shipments of xylene-based scintillation fluids in liquid fora should include the hazard class, "Flanunable liquid" on the shipping papers. (49 CFR 172.201(a)(4)(ii)).
8.2 Enter the words, " Waste Xylene," and the identification number, l'N-1307, to the proper shipping name on the shipping papers.
8.3 The information required on the shipping papers (49 CFP 172.200) may be entered on a separate sheet to maintain legibility. The sheet should be attached to the other shipping papers.
8.4 li over 1000 pounds of xylene is in a single package, the basic description should be preceded by the letters "RQ".
(49 CFR 172.203(c)(2)).
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c RDW 5.9 MINOR
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Revision 0 03-18 .
DOCUMENTATIGH OF RADIOACTIVE MATERIAL SHIPPING PACKAGE INSPECTION, CERTIFICATION AND SAFETY ANALYSIS 1.0 GENERAL This procedure outlines the documentation requirements for packages used to transport radioactive materials. These documents are in addition to the shipping papers required. Files must be maintained for the documents.
2.0 REFERENCES
2.1 10 CFR Part 71, Packaging Radioactive Material for Transport 2.2 49 CFR Part 173, Shippers - General Requirements for Shipments and Packagings 2.3 File HP 2.6, Package QA Documents 2.4 Mound Facility Report MLM-2228, Packaging Compliance with DOT Spec.
-- ?A. See file HP 2.6.7.
\- 3.0 FILE ENTRIES 3.1 File HP 2.6 will be used to maintain a copy of the certificate of .
compliance er other approval authorizing use of a package. All documents referred to in the license, or other approval, will also be maintair.ed in file HP 2.6.
3.2 User registration letters to NRC, when required, will be filed in HP 2.6.
3.3 Package inspection documents will be maintai. rad with the shipping papers pertaining to the shipment for which the package was used.
These are filed in HP 2.1.1 or 2.1.4, as appropriate.
4.0 REQUIRED DOCUMEN_TS, 4.1 Preliminary determinations of quality a.ssurance and quality control should be performed by the package vendor. An NRC certificate of compliance maintained in file HP 2.6 will be sufficient evidence that the preliminary determinations required prior to the first use of t. .e package have been performed by the package manufacturer.
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RDW 5.9
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l 4.2 The table below lists all the possible radioactive waste quantities authorized for shipment. Eeside each quantity is a notation showing that documentation is required ("yes") or is not required ("no"). A series of numbers indicates which documents are required. The key is at the bottom of the table.
I Package ,
Quantity Packaged Documentation Required Limited quantity No Radioactive device No LSA, not greater than Type "A" quantity, transported in a sole use vehicle No LSA, not transported in a sole use vehicle Yes (1)
LSA, > Type "A" quantity Yes (1, 2, 4, 5)
Type "A" Quantity in a shipping cask Yes (1, 2, 4, 5)
Type "A" Quantity in a drum or liner Yes (1, 3, 4)
Type "B" Quantity Yes (1, 2, 4, 5)
Large Quantity Yes (1, 2, 4, 5)
KEY:
I (1) Routine inspection (2) NRC Certificate of Compliance (3) Vendor certification i (4) Safety Analysis
. (5) User registration letter to the NRC NOTE: FISSILE MATERIALS ARE NOT LISTED. NO FISSILE MATERIAL MAY BE SHIPPED WITHOUT SPECIFIC AUTHORIZATION FROM THE SUPERINTENDENT - C&HP.
4.3 Foreign-made packages and packages intended for international shipment require additional documents. Such packages and shipments are not expected to be used at PBNP. Contact the Nuclear Plant Specialist or Engineer assigned to radwaste for details if necessary.
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RDW 5.9 i' Page 3 f
5.0 DESCRIPTION
OF DOCUMEA'S 5.1 Routine Inspections 5.1.1 Routine inspections of cask packages are performed with the use of cask checkoff forms, the CHP-131 series. These forms are unique in that they are part of the shipping papers and a copy is sent with the shipment.
5.1.2 Routine inspections of other packages are performed, if necessary, using form CHP-78. They are filed with the shipping paper, but no copy is sent with the shipment.
5.1.3 The routine inspection is performed by PBNP personnel. Cask inspections'will be done by operations in the normal course of loading. Other packages will be inspected by Health Physics. ,
5.2 Certificate of Compliance 5.2.1 This document is required for a cask shipment unless exempted by Section 4.2 above. It is issued by~the NRC. It contains the package identification number, a physical description of the package, authorized contents, and other special instructions. The certificate of compliance normally contains references to other documents. All such references must be filed with the certificate.
5.2.2 The certificate of complaince should always be consulted before shipment to verify compliance with its conditions.
5.3 Vendor certification 5.3.1 This is required for Type "A" quantities (DOT Specification 7A). Typically, it is a certification for a 55-gallon drum.
It states that the containers meet the requirements of DOT Spec. 7A. The manufacturer of the package must supply this.
. 5.3.2 In the special case of 55-gallen drums, this requirement is satisfied if the drums are certified as meeting DOT Spec.
17H.
5.3.3 If the manufacturer has marked the container with a USDOT specification marking, this is acceptable as a certification. .
(49 CFR 173.22) s
RDW 5.9 if Paga 4 2
f 5.4 Safety Analysis 5.4.1 A Type "A" package must be provided with a safety analysis by its manufacturer. It must demonstrate that the package complies with the specification set forth in 49 CFR 178.350 (DOT Specification 7A). It must also demonstrate that the package will pass the tests specified in 49 CFR 173.398(b).
The manufacturer is ax2mpted from this requirement if a generic safety analysis for the packaging is already on file at Point Beach Nuclear Plant. Refer to reference 2.4 abovc for generic safety analyses which are applicable to 55 gallon drums.
5.4.2 Packages to be used for shipping greater than Type "A" quantities must be provided with a safety analysis by the manufacturer. This also applies to packages transporting LSA material if the package contains greater then Type "A" quantities. The analysis is more extensive than for a Type "A" package. It must show compliance with the following regulations:
10 CFR 71.31 10 CFR 71 Appendix A 10 CFR 71 Appendix B 49 CFR 173.398(c)
If the package is used for LSA material and is shipped via a
. sole use vehicle, the safety analysis does not need to comply with 10 CFR 71 Appendix B.
5.5 User Registration Letter A package used to transport greater than Type "A" quantities, even if
- the material meets LSA requirements, needs a user registration letter.
The letter informs the Director of Nuclear Material Safety and Safeguards of the intent to use a particular package. See 10 CFR 71.12 for details to be contained in the letter.
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RDW 5.10
/ MINOR Revision 0 03-18-83 SELECTING PACKAGES FOR RADIOACTIVE MATERIAL SHIPMENTS
1.0 REFERENCES
4 1.1 10 CFR Part 71 1.2 49 CFR Parts 100 to 178 1.3 Health Physics file HP 2.6, Package QA Documents 1.4 Radioactive Material Handling Manual 1.5 IE Information Notice 80-32 and 80-32, Revision 1 2.0 DEFINITIONS (49 CFR 171.8) 2.1 Overpack overpack means an enclosure not intended for reuse that is used by a single shipper to consolidate two or more packages for convenience in y handling. This definition does not apply to shielded containers if l-the shielding is required to reduce raddation levels to allowable limits.
For example, suppose four 55-gallon drums each meeting DOT Specifi-cation 7A and each containing a Type "A" quantity of material were to be shipped. The drums could be shipped separately. The drums could also all be put in a large wooden box and shipped even though the-box was not qualified as a Type "A" package. The box is an overpack in i
this case and is not intended or expected to provide containment of the radioactive material. The drums provide the containment.
A truck is never an overpack since it is intended to be reused.
2.2 Package or Outside Package This means a packaging plus its contents.
2.3 Packaging This means the assembly of one or more containers and any other components necessary to assure compliance with the minimum packaging requirements of Federal regulations. It does not include overpacks.
! For example, an empty 55-gallon drum is a " packaging". When the drum
, is filled, it becomes'a " package", assuming that it meets radiation s limits. Loading the drum on a truck does not make the truck a package unless the drum radiation level exceeds 1000 mrem / hour at 3 feet, or it contains more than a Type "A" quantity.
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1 RDt1 5.10 Page 2 f
2.4 Strong Outside Container or Strong Tight container
~
This means the outermost enclosure which provides protection against the unintentional release of its contents under conditions normally incident to transportation. A strong wooden box can fit this definition.
2.5 Liner A liner is a large container intended to be used as an inner containment within a shielded shipping cask.
3.0 QUANTITY LIMITATIONS OF PACKAGINGS 3.1 There are three levels of packages. Listed in order from minimum to maximum capability, they are: strong tight container, Type "A" packages (DOT Specification 7A), and Type "B" packages. J. package can be used at less' than its full capability; i.e., a package authorized for use in transporting Type "A" quantities can be used as a strong tight container. Whenever a shielded shipping cask is used, review its certificate of Compliance to be sure it is properly applied.
4 Refer to file HP 2.6 for the certificate.
.~W.(~ -
- m. 3.2 container construction There are 7 types of containers used at PENP: wooden boxes; 30-gallon steel drums; 17H steel drums, 55-gallon; 83-gallon steel drums; steel liners; polyethylene liners; shielded shipping casks.
3.3 Strong Tight containers 3.3.1 Wooden boxes, 30-gallon steel drums and 83-gallon steel drums may be used as strong tight containers only. Liners and 55 gallon drums may also be used as strong tight -
containers.
3.3.2 A strong tight container may be used to ship only the following quantities of radioactive material: ,
i i
- a. Limited quantity
- b. Radioactive devices
- c. LSA material if less than Type "B" quantity and only when shipped in an exclusive use vehicle.
3.4 Type "A" Quantity Package (DOT Specification 7A) 3.4.1 17H steel drums, 55-gallon size, and steel liners, if certified as a Type "A" package, may be used to meet DOT Specification 7A.
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RDW 5.10
/ Page 3
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3.4.2 In addition to the quantities authorized for a strong tight container, a 17H drum, 55-gallon size, or Type "A" steel liner may also be used to ship the following quantities:
- a. LSA caterial, not greater than Type "A" quntity, shipped in a nonexclusive use vehicle.
- b. Type "A" quantities.
3.5 Shielded Shipping Casks (> Type "A" Packa e) 3.5.1 These packages are licensed by the NRC. Before they can be used to transport radioactive materials, special documentation must be obtained. See procedure RDW 3.9, Radioactive Material Shipping Package Documentation, to determine which documents are required.
3.5.2 Check file HP 2.f., to verify that the documents have been obtained. If the required documents are not on file, the cask may be used only as a strong tight container.
3.5.3 If the required documents specified in procedure RDW 5.9 are 3
on file, a shielded cask is authorized to transport radio-active material quantities listed in Sections 2.3.2 above.
Depending on the limitations of the particular cask Certificate of Compliance, it may also be authorized to transport the following quantities:
- a. Type "A" quantities
- b. LSA material in greater than Type "A" quantities
- c. ~ Type "B" quantities
- d. Large quantities NOTE: ALWAYS CHECK THE CERTIFICATE OF COMPLIANCE BEFORE USING A SHIELDED CASK. DIFFERENT CASKS
. ARE AUTHORIZED TO TRANSPORT DIFFERENT QUANTITIES.
4.0 SELECTING A SHIPPING PACKAGE 4.1 Determine the quantity in Curies of radios.-tive material to be packaged.
4.2 Determine whether the package will be shipped via exclusive use or nonexclusive use vehicle.
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.RDW 5.10
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4.3.1 Radioactive material or devices in gteater than limited I quantities may not be transported in commercial passenger carrying vehicles.
4.3.2 Packages put on vehicles must corform to the radiation and contamination limits specified in RDW 5.7.
4.3.3 Shipping casks have specific criteria for use which vary according to the cask model. Refer to the appropriate Certificate of Compliance in file HP 2.6 for specitic information regarding the cask's package category and acceptable contents.
4.3.4 I,iners for use inside a cask may be either steel or polyethylene. In some cases, such as the CSN 6-75 cask operated by Chem-Nuclear Systems, liner must be a certified Type "A" package. Refer to file HP 2.6, procedure RDW 5.9 and burial site criteria to determine which liner is appropriate for a given case.
4.3.5 Refer to file HP 2 6 and procedure RDW 5.9 to determine if a
' liner is certified as a Type "A" package. -
4.4 If a shipping cask is selected, estimate the dose rate at the cask.
surface e.nd 6 feet from the surface. Contact the Nuclear Plant Specialist or Engineer assigned to radwaste for assistance. If estimated dose rates are above 200 mR/ hour contact or 10 mR/ hour at six feet, select a different cask and make a new radiation level estimate.
4.5 Packagings other than those shown in Table 1 above may be used with approval from the Superintendent - C&HP.
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RDW 5.10 Page 4 4.3 Using the table below, select the proper packaging.
TABLE 1 SHIPPING PACKAGE SELECTION CHART Motor Vehicle Use Acceptabl,e Restrictions Packagings Quantity to be Packaged 4.3.2 below) Packaging Category 4.3.4 be. low)
Limited Quan'tity None Strong, tight container a. wood box Radioactive Device b. 30-gal steel drum
- c. 55 gal steel drum
- d. 83-gal steel drum
- e. steel liner Type "A" Shielded vehicles: Type "A" a. 17H steel drum, exclusive use 55-gal Others: None b. Type "A" steel lines
- c. Liner or drums insid a shipping cask Type "B" Exclusive use Type "B" Liner or drums inside a shipping
[
cask Large Quantity Exclusive Use Type "B" Liner or drums inside a shipping cask LSA material, act None Type "A" a. 17H steel drum, greater than Type 55-gal "A" quantity b. Type "A" steel lineG LSA material, not Exclusive use Strong, tight a. Wood box greater than Type container b. 30-gal steel drum "A" quantity c. 55-gal steel drum
- d. 83-gal steel drum
- e. steel liner
- f. liner or drums inside a shipping cask LSA Material Exclusive Use Variable, See liner or drums greater than Section 4.3.3 inside a shipping Type "A" quantity below cask
. ~ (;
LICENSEE COMMENTS ON
SUMMARY
OF DISCUSSION DURING PLANT VISIT ON RETS QUESTIONS POINT BEACH NUCLEAR PLANT l
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l October 6, 1983 l
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The following are comments on certain items contained in the " Summary of Discussion During Plant-Visit on RETS Questions" as transmitted with Mr. R. A. Clark's letter dated April 25, 1983. The numbering of the comments corresponds with that of the Summary.
Item 19: The component cooling system is a closed system and is monitored as stated. However, since the component cooling system is not a point of effluent release, the monitor is not included in the proposed RETS.
Item 76: These are no permanent, undiked, outdoor liquid storage tanks at Point Beach, and hence there is no need for a related specification. The only temporary liquid storage tanks are those used for sludge lancing. These tanks are provided with a catch tray capable of containing the entire 4,000-gallon volume. Furthermore, the maximum curie content observed during sindge lancing was 1.0E-04 curies. Ignoring the catch tray and assuming no ground absorption and no further dilution by wash water, the batch release of this quantity would result in a peak concentration of only 6.6E-08 pCi/cc at the nearest municipal cater intake. Again, no further specification is required.
By way of hydrological background for the Point Beach site:
(a) The groundwater gradient is toward Lake Michigan and is protected by a relatively impervious clay layer.
(b) The plant is located at the edge of Lake Michigan, 26 feet above mean lake level.
i
, (c) Yard drains discharge to Lake Michigan.
(d) The nearest municipal water supplies are Green Bay '
(thirteen miles north) and Two Rivers (twelve miles south). The minimum calculated dilution factor is j 100, and the minimum transit time is fifty hours.
( . Item 82: As shown in Figure 1-2 of the ODCM, Drumming Area Vent (DAV) releases are not potentially affected by power transients. Hence, there is no need for special attention to the DAV following a power transient.
As a matter of plant practice, the Auxiliary Building Vent (ABV) is sampled whenever a significant upward trend is noted on the monitors. In addition, of course, normal periodic sampling is also done. In consideration of the constant monitoring, periodic sampling, plant practice, and the fact that design objectives are applicable to all releases, no further specification is needed for power transients.
Items 71 and 94: Section IV. A of Appendix I to 10 CFR 50 already provides for actions to be taken in the event quarterly releases exceed one-half the annual design objectives. These actions include the definition and initiation of corrective action. Clearly the operation of liquid and gaseous radwaste systems would be included in such corrective action if appropriate. Hence, an additional specification of operability related to 1/48 of the dose objectives is i unnecessary and would entail and excessive administrative burden without justification. As a matter of historical fact, Point Beach has operated for more than twenty reactor years well below the design objectives of Appendix I.
Additional specifications are not justified.
Item 100: Rupture of a gas decay tank was considered in a bounding analysit presented in Section 14 of the Point Beach FSAR assuming a 1% fuel defect level. The calculated whole body dose was 750 mrem at the highest point along the site boundary. However, this bounding analysis overconservatively assumed collection of all gases during an entire fuel cycle. In reality, the gas decay tanks are sized to accommo-date gases resulting from 45 days of operation. Correcting for this single overconservatism results in a dose of
- approximately 100 mrem, well within the guidelines of the Branch Technical Position. Of course, this still neglects the gaseous waste processing system which provides for substantial decay of the shorter lived isotopes. With
, this redundant system, the actual dose for a tank rupture would be much lower. Since the accident dose calculated
' for the adverse meteorology and maximum design loading of the tanks is so low, additional surveillance would provide no benefit, and a specification is neither needed nor justified.
Item 107c- The next revision to the Point Beach Environmental Manual will contain a statement that gross beta countirg of air particulate samples will not occur sooner than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after removal of the sample. This has always been the practice but was not explicitly documented in the Environ-mental Manual.
Item 107b: The next revision to the Point Beach Environmental Manual will note that at least two TLD chips are to be used per location. This practice is already implemented.
Item 107f: Point Beach will retain an 0.5 pCi/l LLD for I-131 in lieu of the 1.0 pCi/l recommended in NUREG-0472. At the same time, however, a monthly milk sampling frequency wili be retained in lieu of the two-week frequency recommended in NUREG-0472. The technical basis for this position was presented in our July 12, 1976 letter to Mr. B. C. Rusche, then Director of NRC's Office of Reactor Regulation. For convenience, the pertinent portion of that letter is as follows:
1
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1 "For purposec of these _ radiological environmental technical specifications, we have made further calcu-lations using the assumptions contained in Regulatory Guide 1.109.
"The Appendix I design objective of 15 mrem to the infant thyroid would easily be detected since the milk analysis is performed with a detection limit of 0.5 pCi/1. An average concentration of 0.5 pC/l would correspond to a dose of 1.1 mrem for the six-month grazing season.
"A similar demonstration of detectability can be made for " puff" releases. A disappearance of 5.12 days is calculated for the combined processes of weathering and decay. Conservatively assuming that the " puff" always occurs immediately after the monthly sample, the detection limit of 0.5 pCi/l corresponds to a peak concentration of 29.0 pCi/l thirty days earlier at the time of the puff. For six such repeated puffs during the six-month grazing season, the total inte-grated ingestion would be 1,140 pCi, corresponding to a dose of 14.9 mrem. Thus, the Appendix I design objective can be detected even under these unlikely circumstances.
"Since Appendix I objectives can be detected in the milk sampling program even in the extreme case of puffs repeatedly occurring immediately atter the monthly sample is taken, and since sampling is performed in the worst D/Q sector, semimonthly sampling is not
, warranted."
l Item 110b: The Appendix I evaluation for PBNP and the ODCM methodology already assumes milk animals present at the site boundary in the worst D/Q sector. Since this is the most conservative situation possible, a detailed land use census provides no benefit and is not justified. The existing Technical Specifications provide for visual confirmation of conditiens (i.e., principally to verify that milk animals have not moved onto the site), and no further specification is needed.
Item llla, b: Our contractor for environmental sample analysis continues to participate in the Interlaboratory Comparison Program.
The requirement that the contractor continue such participa-tion will be added to the Point Beach Environmental Manual in the next revision.
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Item 118e: Current burial site requirements include identification of principal nuclides. The Point Beach PCP, in RDW 5.8, requires f> completion of burial site forms in the proper manner. In
., addition Health Physics Standing Orders, specifically 4
HPSO-2f requires identificatica 'of . specific nuclides.
, Completion cf fem CHP-24, which entails such identification, is required by both the PCP and HPSO-2. Finally, the new 10,CFR 61 requires the same identification. Because of all these requirements in other. places, no Technical Specification is acessary.
Item 124: The requirement to report major changes to the radioactive waste treatment systems is already addressed in 10 CFR 50.59.
An additional inclusion in Technical Specifications is unnecessary.
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