ML20235U934
| ML20235U934 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 09/13/1988 |
| From: | Randles M LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20235S178 | List: |
| References | |
| PROC-880913, NUDOCS 8903090437 | |
| Download: ML20235U934 (51) | |
Text
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- Effcetiva D:to: 9/13/88 f
SOLID WASTE PROCESS CONTROL PROGRAM FOR SHOREHAM NUCLEAR POWER STATION - UNIT 1 REVISION 5 LONG ISLAND LIGHTING COMPANY
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Docket No. 50-322 August 12, 1988 A Prepared by: iOl(f ku k( ('k Date: ' feh -
Nuclear ngineering Department
8' Reviewed by:-
Date:
ROC Chairman Approved by. Date: 9-8 @
Plant Manag(er/ ~
E00NTR0llED 8903090437 890228 PDR ADDCK 05000322 R PDR ,
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.-_ ,_ ,___. _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _
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TABLE OF CONTENTS '
PAGE#
i 1.0 Purpose 1 !
2.0 Radioactive Waste Sources. 1 .I 2.1' Evaporator Bottoms 2 2.2. Floor Drain Filter 2 3 2.3. Radwaste Filter 3 .'
1 2.4 Spent Resin Tank 4 2.5 Cartridge' Filters 4 2.6 Trash Compactor 4 2.7 Mobile Filter and/or Demineralized 4' 3.0 Radioactive Waste Streams 5 4.0~ In-House Solidification System. 6
. 5.0' In-House Dewatering 7 I . . .
'6.0- Mobile Solidification, Dewatering, Filtration 7 and Demineralization Services
-'7 . 0 Solidification Process Control Parameter Determination 8 '!
8.0 Solidification and Dewatering Process Control ,.,
8
,, 8.1 Sampling and Analysis 8 8.2 Conditioning 9 8.3- Batch Test Solidification 9' 8.4 Waste Classification 10 8.5 Container Control 11 8.6 . Decontamination 11 ,
8.7 Changes to the Process Control Program 11 !
8.8 Records and Inventory Control 12 9.0 Responsibilities 12 10.0 . References 13 10.1 LILCO Operating Procedures 13 10.2 Mobile Services Contractor Documents 14 10.3 General References 15 Appendix A Solidification Record Sheet 17 Appendix B Dewatering Record Sheet 21 FIGURE 1 Solid Radwaste System 23 i
OM% - _ _ - - - -
i1 Page 1 of 23 1.0 PURPOSE The Shoreham Nuclear Power Station (SNPS) Process Control Program (PCP) describes the administrative and process controls which provide reasonable assurance of a consistent quality radioactive waste product which is acceptable for shipment and burial. Implementation of this PCP will:
o Provide assurance that waste types produced at SNPS will be classified satisfactorily in accordance with the requirements of 10CFR61.
o Provide assurance that the requirements of 10CFR61 and specific disposal site criteria for Class A unstable waste to be solidified are met by the use of a mobile solidification system supplied by a qualified contractor. When additional sample solidification data becomes available, this PCP will be modified to demonstrate the qualification of the in-house solidification system that may be used,
- in addition to a mobile solidification system supplied by a qualified y contractor, for processing of Class A unstable waste.
o Provide assurance that the waste form stability requirements of 10CFR61
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for Class B and C wastes are met. This will,be accomplished through the use of a mobile solidification system supplied by a qualified contractor or use of approved High Integrity Containers (HICs). Until such time as the contractor's Topical Report has been app, roved by the NRC, qualification will be based on the contractor's past record of producing acceptable BWR waste packages for waste streams similst to those produced at SNPS. The contractor's Process Control Programs are referenced in the " Mobile Service Contractor Documents" Section of this document. SNPS management shall ensure that the contractor's waste ;
processing operations are performed in accordance with urocedures.
o Provide assurance that dewatered Class A, B or C waste products meet the applicable burial site criteria for free standing water when the in-house or contractor's dewatering equipment and procedures are used.
o Provide assurance that the processing and packaging of solid radioactive wastes meet the requirements of federal and state regulations and disposal site criteria.
o Ensure that the quality assurance requirements delineated in 10 CFR 71.101, 71.103 and 71.105 are met for both in-house and mobile contractor processing.
2.0 RADIOACTIVE WASTE SOURCES Low-level radioactive wastes are produced as a result of routine plant operation and maintenance of plant systems. The major contributing ,
sources of radioactive waste are listed below: !
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Page 2 of 23 2.1 EVAPORATOR BOTTOMS g 2.1.1 Waste Evaporator
,The waste Evaporator receives high conductivity waste.
primarily from the floor drains.
The design concentration of the Waste Evaporator is an 18 weight percent concentrate of dissolved and-suspended solids.
2.1.2 Regenerant Evaporator 'l i
The Regenerant Evaporator receives primarily liquid chemical. 1 wastes produced by the acid / caustic regeneration of the -
condensate demineralized resins.- ,
[P'
.The waste is collected, neutralized, and sampled in the Regenerant Liquid and. Evaporator Feed Tanks,.and then pumped to the Regenerant Evaporator for concentration to's 25
, weight percent mixture of sodium sulfate and other dissolved and suspended solids.
2.1.3 Bottoms Transfer y iEach evaporator:is a forced circulation design with a reboiler providing process heat and an overhead entrainment separator and rectifying column which minimizes liquid droplets in the vapor. When the desired solid content has been reached. the concentrated evaporator bottoms are cooled and sent to the Evaporator Bottoms Tank'or directly to the Evaporator Bottoms Metering Pump for solidification according to the contractor's procedure F458-P-002,
" Operating Procedures for Mobile In-Container Solidification of Sodium Sulfate Slurries."
In order to provide maximum flexibility, each evaporator can be used as a back-up for the other.
l 2.2 FLOOR DRAIN FILTER The filter is a horizontal traveling screen, precoat type, designed for air drying and air-aided discharge of the cake (without backflushing) into a shipping container for further dewatering. The waste may contain filter media such as diatomaceous earth or a powdered resin / fiber blend type material.
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The floor drain, filter can be used to process the following combined liquid radwaste streams:
o Reactor Bldg Floor Drains
.o Turbine Bldg. Floor Drains o Radwaste Bldg. Floor Drains o Machine Shop Floor Drains o Sample Tank Area Floor Drains o Turbine Bldg. Decon Area Floor. Drains o Condensate Demin. System Waste Sump Pump Disch. and URC Backwash.
o Cond. Storage and Transfer System overflow Sump Pumps discharge.
o Laundry Drains Tank Class ~A, B and C waste which is dewatered using in-house equipment.is processed according to-SP R3.710.02, " Dewatering of Spent Radwaste Media". -
Waste which is dewatered by the contractor's mobile equipment will be processed according to his procedures.-(see " REFERENCES" Section). .
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2.3 RADWASTE FILTER
_ . The Radwaste Filter is used to process the following combined liquid radwaste streams:
o Low conductivity equipment drains s o Reactor Bldg. Equip. Drains,.drywell equip. drains,'Radwaste Bldg
,, equip'. ' drains, and Turbine Bldg equip. drains .
o Solid Waste System dewatering tank decanted liquid o RW filters displacement and prefiltration liquid o Decanted liquid from the Phase Separator and the Spent Resin Tank o Blowdown from the reactor water cleanup and residual heat removal systems o Blowdown from the Fuel Pool Cooling and Clean-up System o Ultrasonic Resin Cleaner Backwash The radwaste filter units are each composed of stacked horizontal filter discs assembled on an axially located hollow shaft. After l draining the filter vessel and air-drying the filter cake, the i filter assembly is spun to remove the filter cake from the filter discs and discharged directly into a waste shipping container for dewatering and disposal.
The waste resulting from the filters may contain diatomaceous earth, Ecodex or similar powdered resin / fiber blend' material. If Class A, B or C waste is being dewatered using in-house equipment, it is
(. processed according to SP R3.710.02 " Dewatering of Spent Radwaste Media". All classes of waste may also be dewatered by the contractor using procedures referenced in the " REFERENCES" Section.
F Page 4 of 23 2.4 SPENT RESIN TANK (SRT)
The Spent Resin Tank accepts resin / filter media (via the Phase Separator Tanks) from the reactor water cleanup (RWCU) filter demineralizers, the sludge from the backwash storage tank of.the Fuel Pool Clean-up etched-disc type filter, in addition to spent .;
bead resin from the condensate domineralizers, the fuel pool demineralizers, and the radwaste domineralizers. The resin is allowed to settle before excess water is decanted to the waste collector tanks.
Mixed powdered and bead. resin in the SRT can be transferred directly into a' HIC from the SRT for dewatering by the~in-house equipment or the contractors' Mobile unit using the procedures in the '
" REFERENCES" section of this PCP. Condensate domineralizer. resin-
. may also be reused by transfer into a mobile filtration /deminer-alization unit, described in Section 2.7.
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2.5 CARTRIDGE FILTERS.
The Laundry Drain System and the Control Rod Drive System use a l-cartridge type filter for processing. . These' cartridges may be immobilized in a cement mixture which includes _ evaporator bottoms concentrates or spent resins. These may also be compagted as Dry Active Waste (DAW) using SP R3.075.01 (provided the filter cartridge is dry)'. Liners that contain solid objects are specifically identified. Liquid effluent from filtration of the laundry drains is not recovered.
2.6 TRASH COMPACTOR The drum compactor is used to compress low level dry waste such as rags, paper, shoe covers, floor sweepings, dry filters, HEPA filters, strainers and plastic gloves into 55 gallon steel drums for shipment offsite.. Compaction force is rated at 18,000 lbs for an approximate 4:1 compaction ratio.
A box compactor will be installed which compresses waste into 96 cu.
ft. metal boxes. This is a self-contained unit with its own HEPA filtering system. The compaction force is rated at 60,000 lbs.
I 2.7 HOBILE FILTER AND/OR DEMINERALIZED ]
l The mobile filter and/or demineralized may be used to process the I waste streams.normally treated by the floor drain filter or the )
radwaste filters (refer to sections 2.2 and 2.3 above). The i filtration and/or demineralization media used may include carbon-based media, oil-block media, bead resins, and also condensate dominera11:er resins from the Spent Resin Tank. After use, the filtration and/or demineralization medium is transferred to
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4 Page 5 of 23 a waste container for in-house dewatering in accordance with SPR3.710.02, " Dewatering of Spent Radwaste Media", or mobile dewatering or mobile solidification in accordance with contractor's procedures listed in the " REFERENCES" Section.
3.0 RADIOACTIVE WASTE STREAMS 3.1 EVAPORATOR BOTTOMS CONCENTRATES This may be a mixture of :
3.1.1 Chemical regeneration concentrates from the Regenerant Evaporator process.
3.1.2 Floor Drain concentrates from the Waste Evaporator process.
3.2 SPENT RESIN TANK WASTE This might be a mixture of the following:
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___ . 3.2.1 Condensate Demineralized Resins .
3.2.2 Radwaste Demineralized Resins 3.2.3 Fuel Pool Demineralized Resins 3.2.4 Phase Separator Resin 3.2.5 Vacco Filter Backwash Sludges 3.3 FUNDA FILTER GENERATED WASTE 3.4 FLOOR DRAIN FILTER GENERATED WASTE 3.5 DRY ACTIVE WASTE (DAW) 3.5.1 Compactible 3.5.2 Non-Compactible 3.6 FILTER CARTRIDGES 3.6.1 HEPA Filters 3.6.2 Laundry Drain Filter Cartridges 3.6.3 CRD Filter Cartridges
Page 6 of 23 3.7 RADI0 ACTIVELY CONTAMINATED LIQUIDS AND SOLIDS
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Due to varying burial site regulations, each will be handled on a case by case basis in accordance with the burial site criteria and federal regulations.
3.7.1 Organics (including oils) j 3.7.2 Charcoal (Filters, Charcoal Beds) 3.8 MOBILE. FILTER AND/OR DEMINERALIZED WASTE i
. This may include the following: 1
-3.8.1 Carbon-Based Media 3.8.2 Oil-Block Media
'3.8.3 Bead Resins )
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_ , 3.8.4 Condensate Demineralized Resins from the Spent Resin Tank i
NOTE: Items 3.8.1 and 3.8.2 can only be used if found acceptable !
under 3.7 and the 1% oil test has been demonst, rated ;
successfully on those media. !
4.0 IN-HOUSE SOLIDIFICATION SYSTEM SNPS has a permanently installed Atcor radioactive waste solidification system which, when additional test data is available, may be used to package either radioactive evaporator bottoms or resins / sludges for disposal as Class A waste. Until that time, all wastes for solidification will be transferred to the contractor's mobile equipment.
The following is a description of the in-house system. Waste and cement flows are fixed by preset metering pumps using flow rates recommended by Atcor and verified by full scale testing. Flows are also monitored by tachometers installed on the control panel. The resin / sludge is processed from the Waste Dewatering Tank and evaporator bottoms are processed from the evaporator bottoms system or directly from the evaporators.
Cement and evaporator bottoms or resin / sludge are introduced into the mixer feeder unit for through mixing and discharge into a container. The small-volume continuous mixer limits the surface contact of the wet cement and also limits the quantity of wet cement in the system at any time. A !
manual handerank is provided to permit emptying the mixer / feeder by the )
operator in case of power loss or equipment malfunction.
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.I Flush water connections are provided inside the mixer / feeder to remove cement residue.
Safety features include:
o An interlock to prevent filling unless the pipe is properly inserted into the container fill opening.
o An ultrasonic level sensor, and a timer to monitor waste level in the container to prevent overflowing. Cement-bearing flush water cannot be discharged unless a receptacle is in place.
o Failure to initiate a flush sequence within 20 minutes after filling stops prompts an alarm.
When operational the system will be operated according to SP 23.713.01,
(- " Solid Radwaste System." A simplified functional diagram appears in f- Figure 1.
5.0 IN-HOUSE DEWATERING As an' alternative to solidification, Class A, B, and C dewaterable waste may be dewatered in High Integrity Containers (HIC). Non high integrity containers can be used for Class A waste. All of these contpiners are equipped with internal filters to which a pump may be attached. Pumping
.. continues until burial site criteria for free standing non corrosive liquid are met as described in SP R3.710.02.
Dewatering is conducted in accordance with plant procedure SP R3.710.02,
" Dewatering of Spent Radwaste Media," to assure a consistently acceptable product.
6.0 MOBILE SOLIDIFICATION, DEWATERING, FILTRATION AND DEMINERALIZATION SERVICES 6.1 Wastes to be solidified must be transferred to the mobile solidification / dewatering equipment which is provided and operated by a qualified contractor. . Class A, B or C dewatered wastes may be ,
processed by the mobile services contractor or the in-house l l devatering system at the discretion of the Radwaste Engineer. Class i A solidified wastes may be processed by the contractor or by the 1 I in-house solidification system after qualification is completed.
The mobile filtration and demineralization system may be operated by either contractor or properly trained SNPS Radwaste Operators.
6.2 The " Mobile Services Contractor Documents" in the References Section have been used to prepare Station Procedures for use by the mobile services contractor and SNPS personnel to ensure that waste products ,
meet all requirements for shipment and burial offsite. !
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6.3 Provisions have been made for the mobile solidification, filtration and demineralization equipment to be installed on Elevation.195 6" of the Radwaste Building which is a Seismic Category I Structure.
This equipment will be installed and utilized as required. Spills. l are contained by installing the equipment:in areas where sloping floors will carry liquids to floor drain sumps. The building-ventilation system provides for filtering of particulate airborne contamination and monitoring of radiation before it enters the station vent.
7.0 SOLIDIFICATION PROCESS CONTROL PARAMETER DETERMINATION When additional samples have been tested *for solidification, this section will'contain a summary of qualification test results for the in-house solidification system. During the interim, the in-house system will not be used to solidify waste for shipment offsite.
8.0 SOLIDIFICATION AND DEWATERING PRODUCT CONTROL 8.1- SAMPLING AND ANALYSIS 8.1.1- ' Samples shall be obtained and analyzed according to SP 72.002.18. "Radwaste Sampling for. Disposal," prior to each solidification or dewatering operation and SPgR4.014.01, "Radwaste Sample Solidification Test,"' prior to solidification.
8.1.1.1 Sampling for Solidification
- 1. The waste tank to be sampled shall be recirculated for a minimum of three tank volumes prior.to sampling, unless the tank had been on recirculation continuously since it began filling.
- 2. An exception to the above is the Waste Dewatering Tank which is equipped with an agitator rather than a recirculating pump.
Agitation is continued for at least 25 minutes prior to sampling.
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- 3. The waste tank sampled shall remain isolated and in recirculation or agitation, as applicable, until the solidification process is started. If it becomes necessary to add material to the tank being processed, a new batch number will be initiated and a new sample will be taken after an appropriate mixing time, i
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Page 9 of 23 4.' Test solidification will be performed according.
to the schedule described in the " Batch Test
-Solidification" Section.
- 5. Solidification sampling requirements apply to all. waste,.whether.it is being processed by permanently installed equipment or by the-contractor's mobile equipment.
8.1.1.2 Sampling for Dewatering
'Funda. Spent Resin Tank and flat bed filter wastes must be sampled from the liner. These will not be mixed prior-to sampling.
. 8.1.2 The following applies to both Dewatering and Solidification.
- 1. Samples will be analyzed for pH and gamma emitters.
- 2. Oil content will be verified to be less than 1% by volume
, prior to shipment. -
- 3. The analysis number will be added to the Solidification or Dewatering Record Sheet which is prepared for each vaste container'(liner or HIC).
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8.2 CONDITIONING 8.2.1 Waste conditioning for solidification is required when any
'of the following conditions exist:
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- 1. The pH is outside of the acceptable range'according to the contractor's PCP.
- 2. Liquid content of the batch is above or below the acceptable envelope for solidification as indicated in the Contractor's PCP in the " REFERENCES" Section documents.
8.2.2 pH shall be determined on the decanted liquid from each '
container which has been dewatered. If pH is less than 4 or greater than 11 it will be determined on a case-by-case basis if any further action is required prior to shipment.
8.3 BATCH TEST SOLIDIFICATION 8.3.1 Test solidification shall be performed according to the following schedule:
k-fi? l Page 10 of 23
- 1. One sample initially from each type of wet waste, and then from every tenth batch of each type of wet waste.
,, NOTE: Batch is defined asithe total-volume of waste contained in a waste mixing tank that has been prepared for solidification.
- 2. When sample analyses fall outside the acceptable envelope established by the mobile services contractor, indicating a changeLin the waste type.
w 8.3.2 ' If.any test specimen fails ,to solidify. the solidification .
of the batch under test shall'be deferred until such time as
' additional test specimens can be obtained, alternative.
solidification parameters can be determined, and a ,
i, subsequent test verifies solidification. Solidification of
-the batch may then be performed using the alternative i },' solidification parameters determined.
Representative samples shall be obtained and tested from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate solidification. The process control program shall be modified as required to assure solid N ication of subsequent. batches of waste. The contractor shall modify
.- 'his own PCP as necessary to accommodate unusual waste
!. streams.
l-8.3.3 The test specimen shall be judged to have solidified successfully if, when its container has been removed, it remains a free standing monolith with no visible free liquid.
8.3.4 If a cement and water mixture (without waste) is used to solidify miscellaneous objects, this mixture will be tested for solidification prior to use.
8.4 WASTE CLASSIFICATION 8.4.1 In compliance with 10 CFR 20.311, wastes are classified as Class A, B or C, or greater than Class C, based on the presence of particular radionuclides and their activities as specified in 10 CFR 61.55. Plant procedures SP R1'.001.02, "10CFR61 Compliance Program", and SP R2.713.06,
" Calculations for Radweste Curie Content" or SP R3.713.02 "RADMAN Computer Program" provide the methodology for this determination as used at SNPS.
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f Page 11 of 23 8.4.2 Waste streams will be sampled based.upon the Branch Technical Position requirements (or more frequently, if plant parameters indicate a change in waste characteristics) and analyzed for fission and activation' products, including transuranic. Scaling factors developed from these complete analyses will be used with gamma spectra from each batch of waste to' infer the concentrations of non-gamma emitting radionuclides.
8.4.3 During initial plant operation when th'e results of actual analyses are not yet available, radionuclides concentrations will be used in accordance with "RADMAN - Data Base Anal'ysis Report".
8.4.4 The curie content of waste streams (such as trash) for which representative sampling is difficult may be inferred based on gamma. analysis of representative smears and external dose f
rate measurement (SP R2.713.06 or SP R3.713.02).
8.5 CONTAINER CONTROL
! 8.5.1 A quality assurance program shall be established to inspect the container to be used for dewatering (and solidification) using SP R2.713.30, "Radwaste Container Control".
8.5.2 < This program shall assure that prior to use, the containers to be used for dewatering are intact and free of any visual damage that would prevent the dewatering of waste to required limits.
8.6 DECONTAMINATION 9 Prior to shipment, containers will be swiped for removable contamination and examined for general condition. Decontamination will be conducted as necessary to meet shipping requirements.
8.7 CHANGES TO THE PROCESS CONTROL PROGRAM Any changes to the Solid Waste Process Control Program for the Shoreham Nuclear Power Station shall be reviewed and found acceptable by the Review of Operations Committee and approved by the Plant Manager and reported to the NRC in the Semiannual Radioactive Effluent Release Report.
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Page 12 of 23 8.8 RECORDS AND INVENTORY CONTROL i- 8.8.1 Solidification
- 1. A Solidification Record Sheet (Appendix A) shall be completed for each liner filled for solidification.
- 2. If more than one liner results from a batch, then the initial. liners will not be shipped until all liners for-that batch have verified solidification. Those liners will be identified by a common analysis number.
8.8.2 Devatering Radiochemistry Analysis Sheet and Post Dewatering Survey Sheet (see Appendix B and Appendices 12.4 and 12.5 of SP R3.710.02) shall be completed for each container filled-f.
with dewatered waste.
8.8.3 Solidification and Dewatering
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- 1. The Solidification or Dewatering Record Sheets and the attached isotopic analysis shall be forwarded to the Radwaste Engineer for retention until such pine as the liner identified on the Record Sheet is shipped for final
< disposition.
- 2. When the identified liner is shipped and then verified received, the Solidification or Dewatering Record Sheets and other documents concerning the shipment shall be forwarded to SR2 for permanent record storage.
9.0 RESPONSIBILITIES The following outlines departmental responsibilities and interfaces to implement and support all activities associated with the SNPS PCP.
NOTE: All service contractor procedures implementing the PCP which will be used at SNPS, prior to their utilization and implementation, must be approved by the Review of Operations Committee as per SNPS Tech. Spec.
6.8.1.h.
9.1 NOC Policy 25 (Management of Low Level Radioactive Waste) identifies the following departments as having direct responsibilities for the implementation, maintenance, licensing and regulatory interface of the SNPS PCP. ,
9.1.1 Nuclear Engineering Department, as also described in NED 1.02.
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Page 13 of 23 9.1.2 Shoreham Operation Department, as also described in SP RI.001.01.
9.1.3 Nuclear Operations Support Department.
9.1.4 Quality Assurance Department (QA) as described in the QA Manual, Section 1.
9.1.5 Nuclear Review Board (NRB) as also described in the " Charter of the Shoreham Nuclear Power Review Board".
See NOC Policy 25 for more details.
9.2 Procedure NED 6.04, " Change Control", in conjunction with the NOSD
- 6. " Control of License Documents" shall be used to review, approve,
, , control and disposition proposed changes and revisions to the SNPS PCP.
9.3 NED is responsible for preparing and maintaining the PCP current per NED Procedures 6.04 and 6.01.
9.4 The Review of Operations Committee (ROC) is responsible to review and find acceptable any changes to this program and the associated implementing procedures. 3
.. 9.5 The Plaht Manager's approval shall be obtained for every PCP l
revision.
9.6 ROC and Plant Manager approval signatures shall be indicated on the cover page of the PCP.
9.7 PCP implementation is accomplished through station procedures and is the responsibility of the Radiological Controls and Operations Divisions.
10.0 REFERENCES
10.1 LILCO OPERATING PROCEDURES 10.1.1 SP 23.710.01, Low Conductivity Liquid Radwaste 10.1.2 SP R3.710.02, Dewatering of Spent Radwaste Media 1 10.1.3 SP 23.711.01, High Conductivity Liquid Radwaste 10.1.4 SP 23.712.01, Regenerant Chemical Liquid Radwaste 10.1.5 SP 23.713.01, Solid Radwaste System 10.1.6 SP 23.718.01, Liquid Radwaste Spent Resin 10.1.7 SP 23.719.01, Liquid Radwaste Evaporator Bottoms 10.1.8 SP R2.713.06, Calculations of Radwaste Curie Content 10.1.9 SP R2.713.24, Sampling, Treatment and Disposal of Radioactive Waste Oil 9
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Page 14 of 23 10.1.10'SP R2.713.30 Radvaste Container Control t.
10.1.11 SP R2.713.35, Storage of Packaged Radwaste Liners and DAW I
10.1.12 SP R4.014.01,'Radwaste Sample Solidification Test 10.1.13 SP 72.002.18 Radwaste Sampling for Disposal 10.1.14 SP R3.713.02, RADMAN Computer Program 10.1.15 SP R3.075.01, sorting, Compaction and Handling of Contaminated Waste 10.1.16 SP R1.020.01,-Liquid Radwaste Process Control 10.1.17 SP R1.001.01, Radwaste Program - Policy and Objectives l 10.1.18 SP RI.001.02, 10CFR61 Compliance Program l }
10.2 MOBILE SERVICES CONTRACTOR DOCUMENTS i
'h 10.2.1 STD-R-05-007, Topical Report, Cement Solidified Wastes to 'l Meet the Stability Requirements of 10CFR61, Westinghouse Hittman Nuclear, Inc. {
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10.2.2 F458-P-001, Process Control Program for.the In-Container Solidification of 20-25 Weight Percent Sodium Sulfate !
Slurries
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10.2.3 F458-P-002, Operating Procedure for Mobile In-Container Solidification of Sodium Sulfate Slurries 3
10.2.4 F458-P-003, Procers control Program for Incontainer I
... i Solidification of Bead Resin - Powered Resin Mix ;
10.2.5 F458-P-004, Dewatering Powdered Resin Slurries in Mittman HN-100 Steel Liners with a Three Layer' Flexible Underdrain Assembly to Less Than 1/2% Drainable Liquid i 10.2.6 F458-P-005 Devatering Bead Resins Mixed with Powered Resin in Mittman HN-100 Steel Linert. with a Three Layer Flexible i Underdrain Assembly to Less Than 1/2% Drainable Liquid 10.2.7 F458-igd 6,DewateringPowderedResinSlurriesinHittman i RADLOK - 100 Container with a Three Layer Flexible Underdrain Assembly to Less Than 1% Drainable Liquid i 10.2.8 F458-P-007,DewatgingBeadResinMixedwithPowderedResin I in Hittman RADLOK - 100 Containers with a Three Layer Flexible Underdrain Assembly to Less Than 1% Drainable Liquid i
10.2.9 F458-P-008. Process Control Program for Incontainer i Solidification of Powdered Resin !
10.2.10 F458-P-009, Process control Program for the Incontainer Solidification of Radwaste Filter Cake. (50 weight percent l powdered resin - 50 weight percent Diatomaceous Earth) '
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10.2.11 F458-P-010, Operating Procedure for Mobile Incontainer Solidification of Mixed Bead Resin - Powdered Resin Slurry (Maximum 28 weight percent powdered resin) 10.2.12 F458-P-011. Operating Procedure for Mobile Incontainer Solidification of Powdered Resin Slurry 10.2.13 F458-P-012, Operating Procedure for Mobile Incontainer Solidification of 50% Powdered Resin /50% Diatomaceous Earth Filter Sludge 10.2.14 F458-P-014, Dewatering Filter Sludge Cakes in Hittman HN-100 Steel Liners with a Three L'ayer Flexible Underdrain Assembly
.to Less Than 1/2% Drainable Liquid 10.2.15 STD-P-05-025, Process Control Program for.Incontainer Solidification of Sodium Sulfate Slurries Containing Mixed f.
Solids, Hittman Nuclear l
i 10.2.16 STD-P-05-014, Sodium Sulfate Solidification 10.2.17 Operating Procedure 10-1, Liquid Waste Filtration Operation of Duratek/BFRT 3
,. 10.3 GENERAL' REFERENCES 10.3.1 NRC Standard Review Plan 11.4 " Solid Waste Management Systems" (NUREG-0800) 10.3.2 NRC Branch Technical Position ETSB 11-3, " Design Guidance for Solid Waste Management Systems Installed in Light-Water-Cooled Nuclear Power Reactor Plants", July 1981 ~
10.3.3 Code of Federal Regulations, Title 10. Part 61, " Licensing Requirements for Land Disposal for Radioactive Waste" 10.3.4 Code of Federal Regulations Title 49, " Transportation" 10.3.5 South Carolina Department of Health and Environmental Control, Radioactive Material License No. 097, as amended.
10.3.6 NRC Special Nuclear Material License No. 12-13536-01, as amended, for Barnwell SC 10.3.7 State of Washington Radioactive Materials License
- WN-IO19-2, as amended, for Richland, Washington.
Page 16 of 23 10.3.8 NRC Special Nuclear Material License No. 16-19204-01, as amended for Richland, Washington.
10.3.9 ANSI /ANS-55.1/1979 American National Standard for Solid Radioactive Waste Processing System for Light Water Cooled Reactor Plants.
10.3.10 AIF/NESP-027, Methodologies for Classification of Low-Level Radioactive Wastes form Nuclear Power Plants. Impell Corporation, January 1984.
10.3.11 NRC Low-Level Waste Licensing Branch, Final Waste Classification and Waste Form Technical Position Papers May 11, 1983 10.3.12 RADMAN-Data Base Analysis Report - Shoreham Nuclear Power Station - Waste Management Group Inc., August, 1985 10.3.13 QA Manual App. K, " Packaging and Transport of Radioactive Material".
S e
l l
l e
l 4
___.__-__m .
1
)
Page 17 of 23 5 i
i Appendix A Page 1 of 4 SOLIDIFICATION RECORD' SHEET PART I Sampling and Pre-Solidification Analysis vigt sg ,
%gh
- 1. Type of Waste 'w;
- 2. Waste tank placed on recire.
, 'Date/ Time
. 3. Waste Tank sampled analysis IDI Date/ Time
- 4. Waste Stream pH
- 5. Oil Content % by volume
- 6. Isotopic Analysis Attached Check
- 7. Estimated Curie content (SP R2.713.06) pei/cc
~'
- 8. Test Solidification Required Yes No
- 9. Acceptable Test Solidification performed (if required)
Initials
- 13. The above waste tank has been analyzed and is acceptable for solidification.
i
\
Radiochemistry Engineer Date or designee l
__m _______-
Page 18 of 23 Appendix A Page 2 of 4 SOLIDIFICATION RECORD SHEET PART II System Preparation and Processing (Use Part iia. if vendor supplied system is used)
- 1. Container and- (SP R2.713.30).
Type ID#
- 2. Container Properly Positioned Under Fill Pipe Check
- 3. Fill Flange Properly Mated to Container Check
- 4. Sufficient Cement Available Check
~~~~ '
- 5. Waste Dewatering Tank Level inches Evap. Bottoms Tank Level inches 6, Authorization to commence process 3
~~
Radwaste Supervisor Date
- 7. Time process started
- 8. Time process stopped
- 9. Tachometer reading (Metering Pump)
- 10. Waste Dewatering Tank Level inches
- 11. Evap. Bottoms Tank Level inches
- 12. Process Completed Operator Date Time
- 13. Waste class: A B C
.14. Liner Check for free standing water Initials Date/ Time
- 15. Liner Capped Date Time
- 16. Container Weight lbs.
l l
Page 19 of 23 )
i Appendix A Page 3 of 4 SOLIDIFICATION RECORD SHEET PART iia Contractor System Preparation and Processing
- 1. Container ID Number Type
- 2. Applicable connections made to liner for transferring waste and cement to liner Initials
- 3. Connections made to liner for mixing contents, if applicable i Initials-
- 4. Process parameters
___ . Waste to be added to liner . cf Cement to be added to liner cf Water to be added to liner cf s
- 5. Authorization to commence processing
~
Radwaste Supervision
- Date Time .
- 6. Time processing started
- 7. Time processing stopped
- 8. Waste Class Class A Class B Class C
- 9. Container checked for free standing water Initials Time /Date
- 10. Liner capped Date Time
- 11. Liner Weight lbs.
t.
I -Page 20 of 23 Appendix A.
Page 4 of 4 SOLIDIFICATION RECORD SHEET-PART III Filled Liner Data
'1. Filler Liner Radiation Levels
- a. Contact Dose Rate 1 Meter Dose Rate-mR/hr mR/hr
- b. Smearable Activity
~ 4 Quadrants 1 dpm/100 cm XI dpm/100 cm2 .,%, _
(Use actual 2 dpm/100 cm 3b 2 dpm/100 cm =>c number) 3 dpm/100 cm LB3 -dpa/100 cm ess 4 dpm/100 cm 32f4 dpa/100 cm
- c. Liner decon performed Yes/No 2
- d. Smearable activity after decon (if performed). .dpa/100cm
,. e. Liner ready for shipping or transfer to storage Health Physics Supervision Date Time
- 2. Storage Location Radwaste Supervision
" e
I l
Page 21 of-23 Appendix B
( .Page 1 of 2 DEWATERING RECORD SHEET RADIOCHEMISTRY ANALYSIS SHEET
- 1. Type of Waste
- 2. Waste Tank (or Liner) Sampled Analysis ID# I Date/ Time
- 3. pH of Decant
% by volume
- 4. Oil Content
- 5. Isotopic Analysis of filter media and or bead resin attached Check
- 6. The above waste tank / container has been sampled and found to contain the isotopes and properties as indicated on the attached data sheets. s Radiochemistry Supervision Date-
- . Page 22 of 23 Appendix B Page 2 of 2 DEWATERING RECORD SHEET POST DEWATERING SURVEY SHEET
- 1. Container and.
Type ID#
- 2. Container Radiation Levels
- a. Contact Dose Rate mR/hr 1 Meter Dose Rate mR/hr
- b. Smearable Activity f'
4 Quadrants (Use actual 2 1 dpm/100 cm2 158 1 dpa/100 cm2 'A g 2 dpm/100 cm dps/100 cm "*'
2
- ,(
2 number) 3 dpm/100 cm2 3> 2( 3 dpm/100 cm'*"' 2 4 dpm/100 cm 1L2( 4 dpm/100 cm =*s
- c. Container Descon Performed )
Yes/No 2
- d. Smearable activity after washdown/decon dep/100cm
- e. Liner ready for shipping or transfer to storage !
Health Physics Supervision Date Time I l
- 3. Waste Class A B C Initials
- 4. Storage Location Radwaste Supervision l
l l
L _ . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
-_ --._.- - _ _ _ - - - - - - ~ - - - - - - - - - - - - --- -
~
, Page 23 of 23 1
- SILD UENT FILTER :
. TIGURE1 SOLID RADVASTE SYSTEM R ;
. PRR$t SEPARATOR $ , .l F
, CEMEN1 ,
r $1DRRGE !
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futL PDOL DEMINE ARLl2ERS .i rS g r. -
p
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==
FUfL P00L FILTER BRCKWASH y
' SRT BRTCH NIER r d L SIN BLOWER 1
4 r CalEMICAL DECRWT10
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PUMP MDBILE BRUM $0LIDlilCATl0H $ HIPPING COMPACTOR q p ,P CORIRINER RADtilRSTE $Rkfi#NG - .
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=====8 h 50Ll0ll'ICRifGN
t f'fLCO Document No. 4170002 Eff. Date 9//f/ff Rev. No. 11 Prepared By Date Reviewed By Date Paus- vinter L,bl G " " 're APPROVALS Title / Dept. Signature
/ Date
&aEuAk4sLBnAlw l4 W ) AkNsW B/7.42 Rkc%wM / 9JP.5 'C$b".WJ- 5/3b/Ny r
l TITLE OF DOCUMENT: SHOREHAM NUCLEAR POWEP. STATION - UNIT .1
, OFFSITE DOSE CALCULATION MANUAL l
'f UNCDE0LLED 1
n
SNPS-1 ODCM 1
)
LIST OF FIGURES I
Figure Title )
2.1-1 Detector RE-13, Efficiency vs. Camma Energy 2.1-2 Detector RE-79, Efficiency vs. Camma Energy 2.1-3 Detector RE-23A, Efficiency vs. Camma Energy 2.1-4 Detector RS-23B, Efficiency vs. Camma Energy 2.2-1 Detector RE-42, Efficiency vs. Average Beta Energy 2.2-2 Linearity Response Curve for Detector RE-42
. 2.2-3 Detectors RE-65A,B, Generic Efficiency vs. Average Beta Energy 2.2-4 Generic Linearity Response Curve for Detectors RE-65A.B 2.2-5 Detectors RE-12A,B, Efficiency vs. Camma Energy
___ , 2.2-6 Generic Linearity Response Curve for Detector RE-12A,B 3.1-1 Site Boundary for Liquid Effluents 3.1-2 ?
Liquid Radwaste System Model
~~'
3.3-1 Gaseous Effluent Model l 3.6-1 Ventilation Exhaust Treatment System 5-1 Onsite Sampling Locations - Radiological Environmental Monitoring Program 5-2 Offsite Sampling Locations - Radiological
(
Environmental Monitoring Program 1 1
f BN1-11600.02-92 viii Revision 11 - August 1988 i
- l. .
y OFFSITE DOSE CALCULATION MANUAL.
_ List of Effective Fates Page, Table (T),
Revision L or Figure (F)
Number EP-1:
-EP-2 11 L 11 iii thru iv 3
-v thru vii- 3 viii 4 1-1 2.1-1 8 2.1-2 10 2.1-3 2 2.1-4 8 2.1-5 8 2.1-6 thru 2.1-7 8 F2.1-1 thru F2.1 8 2.2-1 3
?
2.2-2 thru 2.2-5 1 2.2-6 thru 2.2-8 3 T2.2-1 6
. F2.2-1 10 F2.2-2 thru F2.2-4 3 F2.2-5 thru F2.2-6 1 3.0-1 7 3.1-1 to ?
~~
3.1-2 ' 8 3.1-3 thru 3.1-5 8 3.1-6 8'
~T3.1-1 1 T3.1-2 3 F3.1-1 3 F3.1-2 1-3.2-1 11 3.3-1 2 3.3-2 thru 3.3-4 4 3.3-5 thru 3.3-8 3 3~.3-8 9 F3.3-1 10 3.4-1 10 3.4-2 4 3.4-3 thru 3.4-5 3 T3.4-1 9 3.5-1 1 3.5-2 4 -
3.5-3 thru 3.5-6 10 3.5-7 thru 3.5-9 3 3.5-10 10 3.5-11 4 3.5-12 thru 3.5-13 9 10 EP-1 Revision 11 - August 1988
OFFSITE DOSE CALCULATION MANUAL List of TJfective Pages (Cont'd.)
Page, Table (T).
or Figure (F) Revision Number T3.5-1, p. 1/3 10 T3.5-1, pp. 2/3 and 3/3 1 T3.5-2 1
T3.5-3 1
T3.5-4 1
T3.5-5 T3.5-6 3 1
T3.5-7 ,
1 T3.5-8 i' 10 T3.5-9 3
T3.5-10 T3.5-11 3 i 3
T3.5-12 l p 3 T3.5-13~
3 T3.5-14 3
T3.5-15 3
T3.5-16
- 3 73.5-17 4 3.6-1 1
F3.6-1 1 3.7-1 2 "
g 4-1 ,
8
.- 4-2 thru 4-3 4 T4-1 10, 1 T4-2 4 5-1 10 T5-1, p. 1/5 10 75-1, pp. 2/5 thru 3/5 4 T5-1, p. 4/5 1
L TS-1, p. 5/5 4
T5-2 10 75-3 10 T5-4 j 10 T5-5 10 75-1 10 l FS-2 10 6-1 3 A-1 8
B-1 3 '
l D-2 Revision 11 - August 1988
'.1 l
.-. l l
I FLODR M AIN.
m FLOOR M AIN COLLECTOR TANK. -
pgg7gg 3 r IEll!LE 0,'
FILTER /DEMIN.
-+- <*8' l'>
3 ,
I CIRCULATING I
I NAIER SYSTEM
_ NASTE _ b T 15_ ~
Dl!CHARBE EVAFORATOR NASTETANK
~ "
l!y [g da
h +
i
. 4 5 ,
? d L l ,
I I '
fI NA$it RADWASTE RECOVERY i / }
r CDLLICTOR DEMIN!RAll!ER/ + SAMFLE TANK FILTER gggi> ; L
+' 1 /
YARD P!FING MAIN SUMP
~
EVAPORAf0R RESIDUAL HEAT REMOVAL (RNR) 28 SEPVICE NATER DISCHARBE F
^
REAC10E PU!LDINS SALT WATER Y
DRAIN TANK (RSSWDT) h RE79 TO DIFFUSER Y
FISURE 3.1-2 L19UID RADWASTE SYSTEM MODEL SHORIHAM NUCLEAR POWER STAilDN - llNii !
DDCM - RIVISION !!, AUBUST 1998
. SNPS-1 ODCM 3.2 OPERATION OF LIQUID WASTE TREATMENT SUBSYSTEMS The dose projection analysis will be performed using the methodology described in Section 3.1 with the exception that the calculated doses will be compared with the limits specified in RETS Section 3.11.1.3.
The liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system doses shall due to thebe used liquid to reduce releases of radioactivity when the projected effluent i to UNRESTRICTED AREAS would exceed 0.06 arem to the total body or 0.2 arem to any organs in a 31-day period.
A model of . the liquid radwaste treatment subsystems is shown on Figure 3.1-2.
Although the RHR Service Water Discharge, RBSWDT, and yard piping drain sump systems are not part of the ' radwaste treatment subsystems, they are included in Figure 3.1-2 because they represent locations of potentially radioactive dis-charges.
?
f 1
BN1-11600.02-92 3.2-1 Revision 11 - August 1988
. . . _ _ - _ _ _ _ . . ......e_._m e. .
4170002
"" Document No.
Ef f. Date /0/31/Rg Rev. No. 12 Date Reviewed By Date Prepared By p a .s Kuy x in toints 17amard AM widt APPROVALS Sianafure / Date Title / Dept.
2, A l~,b L } N a s //$ semr lh1' -
) 2 $ 344s/b /ol/WPR btAlb&
Wauw> $f }'$3naNavs $$n !& AW,TL- Wdue //
7
/ / / / y'~
//
v TITLE OF DOCUMENT; SHOREHAM NUCLEAR POWER STATION 5- UNIT I 0FFSITE DOSE CALCULATION MANUAL I
i 1 f
l l csm a - - - - -
i 0FFSITE DOSE CALCULATION MANUAL List of Effective Pages Page, Table (T), Revision i or Figure (F) Number EP-1 12 EP-2 12 1 3 111 thru iv 3 v thru vii 4 viii 11 1-1 8 2.1-1 10 2.1-2 2 2.1-3 8 2.1-4 8 2.1-5. . 8
. 2.1-6 thru 2.1-7 8 F2.1-1 thru F2.1-4 3 y 2.2-1 1 2.2-2 thru 2.2-5 3 2.2-6 thru 2.2-8 6 T2.2-1 10 F2.2-1 .
3 F2.2-2 thru F2.2-4 1 F2.2-5 thru F2.2-6 7 3.0-1 10 g 3.1-1 8
'~'
3.1-2 <
8 3.1-3 thru 3.1-5 8 3.1-6 1 T3.1-1 3 T3.1-2 3 F3.1-1 1 F3.1-2 11 3.2-1 2 3.3-1 4 3.3-2 thru 3.3-4 3 3.3-5 9 3.3-6 thru 3.3-8 12 F3.3-1 10 3.4-1 4 3.4-2 3 3.4-3 9 3.4-4 and 3.4-5 12 T3.4-1 1 3.5-1 4 3.5-0 10 3.5-3 thru 3.5-6 3 3.5-7 12 3.5-8 10 3.5-9 12 3.5-10 4 EP-1 Revision 12 - October 1988
i l
j 1
0FFSITE DOSE CALCULATION MANUAL List'of Effective Pages-(Cont'd.)
l Page Table.(T), Revision or Figure (F) Number 3.5-11 9 3.5-12 thru 3.5-13 12 T3.5-1, p. 1/3 10 j T3.5-1, pp. 2/3 and 3/3 1 T3.5-2 1 T3.5-3 1 T3.5-4 1 T3.5-5 3 T3.5-6 1 T3.5-7 1 T3.5-8 12
. T3.5-9 3
- T3.5-10 3 I T3.5-11 3 T3.5-12 3 T3.5-13 3
_ , T3.5-14. 3 T3.5-15 3 T3.5-16 3 T3.5-17 4 3.6-1 1 y F3.6-1 1
... 3.7-1 2 4-1 8 4-2 thru 4-3 4 T4-1 12 ,
T4-7 12 l 5-1 10 T5-1, ;. 1/5 10 T5-1, pp. 2/5 thru 3/5 4 T5-1, p. 4/5 1 TS-1, p. 5/5 4 T5-2 10 T5-3 10 T5-4 10 T5-5 12 F5-1 10 F5-2 12 6-1 3 A-1 8 B-1 3 EP-2 Revision 12 - October 1988
S SNPS-1 ODCM V
g
=
1.73E+08 cc/sec (3.66E+05 cfs), station ventilation exhaust duct ventilation exhaust flow rate, V =
5,70E+05 cc/sec (1200 cfa), air removal pump ashaust duct ventila-2 tion exhaust flow rate, V =
5.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation 3
exhaust flow rate, y/Q 1 =
1 ng term dispersion factor due to release via the station ventila- !
tion exhaust point; refer to Table 4-1, cells Al and A3,..
=
X /Q 2 short term dispersion factor due to air removal pump release via the station ventilation exhaust point; refer to Table 4-1, cells Al and AS, X /Q3* 8h It term dispersion f actor due to containment drywell purge vis -
the station ventilation exhaust point; refer to Table 4-1, cells A1:
and A7,
?
0.70 = shielding factor that accounts for dose reduction due to shielding from residential structures.
3.3.2.2 Noble Cas Skin Dose Rate
=
DS, X/Qy * .{ [K,g *(Cgy
- V7 -C12
- 2 -C g3
- V )]y 3
,, +N2 (X!S2 *(IKsi *C g) + V3 *X0 3 *kI si *Cg3) (arem/yr) .
During periods of no intermittent releases such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the following: .
DS, =
Vy
- X/Q y *{[K,g*Cgy) (arem/yd If main condenser air removal is performed by the mechanical vacuum pump and the sampling is performed at the Station Vent, the following equation should be used:
= Vy
- y/Q 2
- DS, IEd*Cgy) (mrem /yr) where: <
D S, = skin dose rate from all radionuclides released (arem/yr),
BN1-11600.02-92 3.3-6 Revision 12 - October 1988
7
, SNPS-1 ODCM K
'A
= the skin dose factor due to beta and gamma. emissions for each identified noble gas . radionuclides (arem/yr per pCi/m8 ) from Table 2.2-1,
~C II
=
the station ventilation exhaust duct release concentration of radionuclides, i, (pCi/cc) (from isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor),
C 12
= the air removal pump ventilation exhaust duct release concentration of radionuclides,'i, (pCi/cc) (from the isotopic analyses' performed on the gaseous sample taken from the air removal pump discharge monitor),
C 13
= the containment drywell purge ventilation exhaust concentration of radionuclides,- i, (pC1/cc) obtained from a sample taken during a i filtered release or from the c'ntainment o drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter
. (The concentration is obtained from the isotopic analyses performed '
. on the gaseous sample taken.),
?
v 3
= 1.73E+08 cc/sec (3.66E+05 cfm), station ventilation exhaust duct ventilation exhaust flow rate, v = 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct ventila-2 tion exhaust flow rate, j i
V 3
= 5.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation exhaust flow rate,
= long term dispersion factor due to release via the station ventila-X/Q 3 tion exhaust point; refer to Table 4-1, cells Al and A3, X/Q 2 = short term dispersion factor due to air removal pump release via the
. station ventilation exhaust point; refer to Table 4-1, cells Al and A5, X/Q3 = short term dispersion factor due to containment drywell purge via the station ventilation exhaust point; refer to Table 4-1, cells Al and A7.
3.3.2.3 Organ Dose Rate (Particulate Releases)
D,3
=
{[106
- R,
- P
- x/Q * (C11 v-C1 12 Y2.- C13v13
+v* 2
[106,g, ,p ij
- X/42*C12 3
+V 3
[106
- R,
- P g
- X/Q3 *Cg3] (aren/yd During periods of no intermittent releases, such as no main condenser air removal pump operation and no containment drywell purge, the above formula reduces to the following:
D,3
=
v1 * { 106*R *P g3
- x /Q1*C11 (arem/yr)
- _ - - --- - .. - - - - b
4 2
SNPS-1 ODCM
^
If. main condenser air removal is performed by the' mechanical vacuum pump and the sampling is performed'at the Station Vent, the following equation should be used:
6 D
g
=
10 .
- Vy
- R,* X/Q2
- ij *Cgy) (arem/yr) where:
D,)
= total dose rate to organ, j , arem/yr.
P = the inhalation dose conversion factor, for radionuclides other than ij noble gases, i, and organ, j, in arem per pCi from Table.3.5-3.
The dose factor P is based on the critical individual organ for theChildgroup,d$ichismostrestrictive. . Inhalation dose factors for other age groups are givenLin Tables.3.5-1, 3.5-2,-and 3.5-4.
R, = ' inhalation rate (m*/yr), from Table 3.5-5.
E C g3 = the station ventilation exhaust duct release concentration of radionuclides,1, (uC1/cc) (from the Dotopic analyses performed on the filter paper and charcoal cartriage taken from the station ventilation exhaust monitor),
C 12
= the air removal pump ventilation exhaust duct release concentration of radionuclides, i, (uCi/cc) (from the isotopic analyses performed on the fodine and particulate filters taken frondhe air removal pump discharge monitor),
C 13
= the containment drywell purge ventilation exhaust' concentration of radionuclides,1, (uC1/cc) obtained from the iodine and particulate filters during a filtered release or from the containment drywell atmosphere monitor with the purge lines bypassing the primary .
j containment purge filter (The concentration is obtained from the isotopic analyses performed on the iodine and particulate filters.),
V = 1.70E+08 cc/sec (3.60E+05 cfa), station ventilation exhaust duct j 3
ventilation exhaust flow rate, V
2
= 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct ventila-tion exhaust flow rate, V
3
= 5.70E+05 cc/sec (1200 cfs), containment drywell purge ventilation
! exhaust flow rate, long term dispersion factor due to releases via the station ventila-X /Q3= tion exhaust point; refer to Table 4-1, cells A2 and A4, X /Q 2 = short term dispersion factor due to condenser air removal pump release via the station ventilation exhaust point; refer to Table
'4-1, cells A2 and A6, X /Q 3 = short term dispersion factor due to containment drywell purge via the station ventilation exhaust point; refer to Table 4-1, cells A2 and AB.
SNPS-l"0DCM.
C g3 : = .the containment drywell purge ~ ventilation exhaust concentration' ~
of radionuclides, ' 1, : (uci/cc) .'obtained from ' a - sample 1 takanu
~during a ' filtered release ~ or from the containment drywell - )
atmosphere monitor withi the purge lines bypassing the ' primary; containment : purge f11ter (The concentration E is 'obtained ' from i the isotopic. analyses performedion the gaseous sample taken.), '
V.g. =: l'.73E+08 ' ec/sec (3.66E+05 cfa), station ~ ventilation exhaust duct ventilation exhaust flow rate.
V 2
=
5.70E+05 cc/sec (1200 cfa), ' sir' removal pump exhaust duct. .,
ventilation exhaust flow rate, j i
.V 3
=
5.70E+05 cc/sec (1200 efs), containment drywell purge ventila- ;
tion exhaust flow rate, ~'
= long term dispersion' factor due to release via . the station X/Q g~
ventilation exhaust point; refer to Table 4-1, cells B1 and B3, j
X/Q 2 = short term dispersion. factor'due to condenser.' air removal pump release via the station ventilation exhaust . point; refer to Table 4-1, cells.B1 and B5, X/Q3 - = short term dispersion factor due to containment dryvell purge release - via the station ventilation exhaust release point; refer to Table 4-1, cells B1 and B7.
3.4.2.2 Noble Gas Beta Air Dose
.The general equation is:
D 3
s
=
3.17E-08
- X/Qy * { - [N g * (C. gy V ty-C12 2 *2 -C g3 V3 t3 3 ))
+ 3.17E-08
- X/Q 2 *Y 2 * "L I"i *C12 3
+ 3.17E-08
- X/Q 3 *V3*t3 *{[N g *Cg3) (arad)
During periods of no intermittent releases, such as no main condenser air removal pump operation and no containment drywell purge, the above formula reduces to the following:
D B
s
,= 3.17E-08
- X/Qy*Vy *ty *{[N g *Cgy) (mrad)
If the main condenser air removal is performed by the mechanical vacuum pump and the sampling is performed at the Station Vent, the following equation should be used*
I D
B s
= .
-08
- Vy*t2* N2* I i*Cgy) (arad) i BN1-11600.02-92 3.4-4 Revision 12 - October 1988
.. : I SNPS-1 ODCM j
- x. u
. where:
D '= beta air dose from all radionuclides released .(arad),
B
] i L N- =
the air. dose factor due to beta emissions for each g
identified noble gas radionuclides.(arad/yr per uC1/m*) )
from Table 3.4-1, 3.17E-08 =
the inverse of' number of' seconds in a year,
- , t g
=-
7.88E+06 see for quarterly. dose calculation,.
= 3.15E+07 sec for yearly dose calculation, t
2
=
release Period (sec) for condenser-air removal pump, t
3
=
release period (sec) for containment drywell. purge exhaust,
, C gy =. th station ventilation exhaust duct release concentration of radionuclides, .1, :(uCi/cc) (from the isotopic analyses 3 performed on the gaseous sample taken'from the station ventilation exh'aust monitor),
Cd2
= the air removal pump ventilation exhaust duct release concentration of radionuclides,1. (uCi/cc) (from the isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor),
C 13
= the containment drywell purge ventilation exhaust concen-
, tration,of radionuclides, i,-(uCi/ce) obtained from a sample taken during a filtered release or from the con-tainment drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter (The concentration is obtained from the isotopic analyses performed on the gaseous sample taken.),
V 3
= 1.73E+08 cc/sec (3.66E+05 cfm), station ventilation-exhaust duct ventilation exhaust' flow rate, V
2
= 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct ventilation exhaust flow rate, V
3
= '5.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation exhaust flow rate, y/Q 3 = long term dispersion factor due to release via the station ventilation exhaust point; refer to Table 4-1, cells B1 l and B3, i y/Q 7 = short term dispersion factor due to condenser air removal pump release via the station ventilation exhaust point; refer to Table 4-1, cells B1 and B5, 2/Q3 = short term dispersion factor due to containment drywell purge release via the station ventilation exhaust point; refer to Table 4-1, cells B1 and B7.
_ _m m mm mm. --- ~ __ __ - - -
i SNPS-1 ODCM
= ingestion rate of leafy vegetables by individual in age
. group a (from Table E-5 of the Guide, maximum individual). )
[kg/yr]
3 = concentration factor for uptake of radionuclides i from iv soil by edible . parts of crops [(pci/kg)(wat weight)/-
(pCi/kg) (dry soil)) (Ref.: Reg. Guide 1.109. Table E-1 and included on Table 3.5-6)
DF1 = dose conversion factor for nuclide i to organ j of kja individual in age group a due to ingestion of contaminated food [ mrem /pci ingested) (from Tables E-11 through E-14 of the Guide)
DFI =
DFIg ), for Carbon-M C14da ,
DFI =
. F C14 fi'# ** "~ 10 ('" ***I " 3' * *I * **}
I f * # *#'*I"*
E3 i H = absolute humidity of the atmosphere at the location of
. interest [g/m ]8 (See Table 3.5-7)
(x/Q)** = concentration dispersion factor (Sector - Average model) for the period of release (nearest garden and nearest residence) [sec/ms j ,
.- (D/Q)
= particulate deposition rate (nearest garden and nearest residence) [1/m2 )
3.5.1.6 Infant Thyroid Dose Due to Ingestion of Goat Milk and Inhalation Infant thyroid dose equation:
= D inh , pailk D thy.inf thy inf thy inf where:
psilk milk , milk thy,inf (pthy,inf) part (pthy,inf) iodines milk , milk
+
(Dthy,inf) C14 (pthy.inf) H3 E
D ,g ,f
=
(X/Q) " T' 3.17 x 10 Rinf part+1 i DFA i , thy,inf BN1-11600.02-112 3.5-7 Revision 12 - October 1988
f ,'
SNPS-1 ODCM L
AEi = Ai.+ 0.0021 [hr-I] (see pgs 1.109-4 and 1.109-69)
- s g,-2j g (,,e) . (ofq) t,' (average transport time of activity from the f&ed into the milk - and to the receptor); data listed in Table 4-2
- f .(fraction of the year that animals graze on pIsture based on survey data); data listed in Table 4-2
- f w$en(fraction the animalofgrazes daily feed that isbased on pasture pasture on grass survey data); data listed in Table 4-2 Il (D* thy inf) iodines
= infant thyroid dose due to ingestion of milk contam-
, inated with radio-iodines [arem/hr) (Ref.: Reg. Guide
/* Eqs. C-5, C-7, C-10, C-11, and C-13 for milk; similar te the infant thyroid dose due to the ingestion of particulate given - above, with the exception of a different multiplying factor and r = 1.0)
(D* thy,inf)C14
= infant thyroid dose due to ingestion of milk contam-insted with C14 [ mrem /hr) (Ref.: Reg. Guide 1.109, .
Eqs. C-8, C-10, C-11 and C-13 for silk, with p (the ratio of the total annual release ' time to the total annual time during which photosynthesis occurs) = 1, and. t - f and f as given above for the particub,ates3,
- I
= infant thyroid dose due to ingestion of milk contam-(D* thy,inf)H3 insted with tritium [arem/hr) (Ref.: Reg. Guide 1.109 Eqs. C-9, C-10, C-11, and C-13 for milk, with ef , f , and f, as given above for the particulstes)
Rgg = infant breathing rate [m /yr] 8 (from Table E-5 of the Guide, for maximum individual)
DFA i, thy,inf
= dose conversion factor for nuclide i to the infant thyroid due to inhelation [arem/pCi inhaled] (from Table E-10 of the Guide)
DFI i, thy,inf
= dose conversion factor for nuclide i to the infant thyroid due to ingestion [arem/pci ingested] (from Table E-14 of the Guide)
DFI C14, thy,inf
" " 1, thy,inf
- I " I # **I*'""
H3, thy,inf 1 thy,inf
_ _ _ _ _ _ _ _ _ ___ - __ _ _ _ _m
i ~l t
SNPS-1 ODCM Note: . For short term releases such as from condenser air removal pump or containment drywell pur6e P for C-14 must be adjusted.(see note in Tables g3 3.5-15, 3.5-16 and 3.5-17).
R, = inhalation rate (m s/yr) from Table 3.5-5, P = the dose conversion factor for radionuclides, other than noble Id gases,1, and organ j, for the leafy vegetables, stored vegetables, and contaminated ground pathways in 8m (ares /yr per uCi/sec) respec-tively, from Table 3.5-9 and goat milk from Table 3.5-11.
The dose factors P P organforthechilb$g,ro0hU,arebasedonthecriticalindividual since this group is most restrictive, t
g
= 7.88E+06 see for quarterly dose calculation
= 3.15E+07 see for yearly dose calculation, p t 2
= rele888 Period (sec) for condenser air removal pump, t
3
= release period (sec) for containment drywell purge exhaust,
- . C il
- * * ****' " "*"*I **I " ** ""** """ I* **** * "**"****I " *I radionuclides, i, (uci/ce) (from the isotopic analyses performed on the iodine and filter cartridge taken from the station ventilation exhaust monitor),
C i2
= the pir removal pump ventilation exhaust duct role se concentration of radionuclides,1, -(uCi/cc) (from the isotopic analyses performed on the iodine'and particulate filters taken from the air removal pump discharge monitor),-
C g3 = the containment drywell purge ventilation exhaust concentration of radionuclides, i, (uCi/cc) obtained from the iodine and particulate filters during a filtered release or from the containment drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter (The concentration is obtained from the isotopic analyees performed on'the iodine and particulate filters.),
V, = 1.73E+08 cc/sec (3.66E+05 cfa), station ventilation exhaust duct ventilation exhaust flow rate, v
2
= 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct ventilation exhaust flow rate, V
3
= 5.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation i exhaust flow rate,
= long term dispersion factor due to releases via the station ventila-
)( /Q 3 tion exhaust point; refer to Table 4-1, cells C1 and C3,
)(/Q 2 = short term dispersion factor due to condenser air removal pump release via the station ventilation exhaust point; refer to Table 4-1, cells C1 and C5. l l
_ . _ _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ I
1 SNPS-1 ODCM X /Q3 = short term dispersion factor due to containment drywell purge via the station ventilation exhaust point; refer to Table 4-1, cells C1 ,
and C7, '
= long term deposition factor due to releases via the station D/Q 3 ventilation exhaust point; refer to Table 4-1, cells C1 and C9, .
l D/Q 2 = short term deposition factor due to condenser air removal pump releases via the station ventilation exhaust point; refer to Table 4-1, cells C1 and C11, D/Q3= short term deposition factor due to containment drywell purge exhaust via the station ventilation exhaust point; refer to Table 4-1, cells C1 and C13, ,
3.17E-08 = inverse of 3.15E+07 sec/yr, and NOTE:
f If ti,e land _use census (see Table 3.5-8) changes, the critical location; location where an individual would be exposed to the highest dose, must be i.e., the reevaluated using Equation 3.5.2-1 for each of the following locations:
- 1. nearest residence,
- 2. nearest vegetable garden, and
- 3. nearest milk cow or goat.
?
..,. P used in Equatibn 3.5.2-1 will include the values in Tables 3.5-10 through 37N14,ifthosepathwaysexist.
At each location, the following pathways must be considered and dose (dose rates) reevaluated it any actual pathway exists:
- 1. inhalation,
- 2. leafy vegetables (fresh),
- 3. stored vegetables,
- 4. goat's or cow's milk (if both exist choose the one resulting in the higher dose), and
- 5. deposition on ground.
Since a person will always be present, pathways 1 and 5 must always be evaluated.
Once the location of the critical individual is determined and found to be other than the one listed in Table 4-1 (cell C1), the values of 7/Q and D/Q st the updated critical location must be used.
BN1-11600.02-112 3.5-13 Revision 12 - October 1988
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$NPS-1 ODCM TABLE 4-2 GENERAL SITE SPECIFIC DATA PARAMETER YALUE Elevation of upper-level met. instruments 33 ft above ground level Elevation of upper-lev'el met. instruments ( } 150 ft above ground level Temperature sensor separation 117 feet Release height for station vent 249 ft above MSL Station grade elevation. 20 ft above MSL Reactor building height 65 m Reactor building cross-sectional area 2600 m8 Station vent equivalent diameter 2.664 m Maximum effective plume height allowed , 400 m Height of inversion layer aloft 600 m Maximum plume vertical standard deviation a, = 1000 m**
Fraction of the year that animals graze on pasture f = 1.0 p
Fraction of daily feed that is pasture grass when f = 0.50 the animal grazes on pasture Average transport time of activity from the feed tf = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> into the milk and to the receptor Onsite 10 M meteorological tower Gifsite 400 ft meteorological tower BN1-11600-112 1 of 1 Revision 12 - October 1988
I *
\
SNPS-1 ODCM TABLE 5-5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
INGESTION MONITORING STATIONS Functional Designation Location Code (NUREG-0473) (Shoreham REMP) Location Description la 13B1 Goat Farm 1.90 Mi. W Ia2* 10F1 Goat Farm, 9.2 Mi. SSW 8G2 Dairy (Cow), 10.8 Mi. SSE r
Ib1 3C1 Fish and Invertebrates, Outfall I Area, 2.9 Mi NE Ib2 14C1 Fish and Invertebrates, Outfall
- . Area 2.1 Mi. WNW Ib3 13G2 Fish and Invertebrates, Background, 13.2 Mi. W 5
Ic1 ,
BB1 Local Farm, 1.2 Mi. SSE Ic2 SC2 Local Farm 2.8 Mi. E Ic3 12H1 Background Farm, 26 Mi. WSW
- Samples will be obtained from one of the locations listed as available. Priority will be given to the first of the two locations listed. If samples are unavail-able from that location, substitution will be made from the second location listed.
BN1-11600.02-112 1 of 1 Revision 12 - October 1988
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Date issued 9/20/88 Review of Operations Committee Meeting s
- % ctanding: L. Lewin, Chairman H. Randles, Guest
- H. Pierson, Guest
- H. Potkin, Member
- D. Smith, Guest P. Kwaschyn, Alt.
L. Somma, Alt. 2. Sacks, Guest * '
H. Case, Member R. DeRocher, Guest P. Zlatuiski, Secretary J. Stroh, Guest
- E. Dean Alt. II. Amirmokri, Guest
- J. Martin, Guest J. Jeffries, Guest C. Losnedahl, Alt. H. Donegan, Alt.
H. Buring, Member R. Wiemann, Alt.
G. Inch, C.E. H. Beer, Guest
- H. Tucker, Alt. l H:eting Called to Order by the Chairman -
D:te 8/30/88 fTine 10:35 A.H.
H2eting 88-068
~~ Approval of Previous Hinutes a F Minutes of Heetings88-063 and 88-064 were approved'
. - hw Items v
88-068-001 Reviewed License Document Change Request TS88-006. Based upon a presentation by H. Pierson, NOSD, this request has been reviewed in accordance with 10CFR50.59 and ROC has l determined that there are no unreviewed safety questions.
This was approved. Ites Closed 88-068-002 ROC reviewed Revision 11 to the Offsite Dose Calculation Manus 1 and approved this revision which adds the mobile filter demineraliser. Based upon a presentation by H.
Boer, NED, this manual has been reviewed in accordance with 10CFR50.59 and ROC has determined that there are no unreviewed safety questions. This was approved. - Item closed 88-068-003 Reviewed Solid Waste Process Control Program, Revision 5.
Based upon a presentation by H. Randles, NED, this has been reviewed in accordance with 10CFR50.59 and ROC has determined that there are no unreviewed safety questions.
This was approved. Ites 01-sed 0 Attended Part Time eu,F
88-068-026 Reviewed Station Procedure SP 12.070.01, SPCN No.' 88-1385, Initiation Review and Disposition of LILCO Deficiency ,
L Reports (LDR). Based upon a presentation by D. Smith, )
Plant Engineer, this procedure has been reviewed in accordance with 10CFR50.59 and ROC has determined that there are no unreviewed safety questions. This procedure was approved for station use. Item Closed l
I l
Mutina Adjourned by Chairman {
Tire: 2:06 P.M.
~
A 7AC(hec ' >
(pprovalOfMinutes ROC Chairm4n /
SR2-1065.102-6.020
. N' v
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_ _ _ _ _ _ _ - _ _ - - - _ - _ - . . _ - - - - _ -