ML20246K558
| ML20246K558 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/03/1989 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20246K549 | List: |
| References | |
| PROC-890303, NUDOCS 8909050507 | |
| Download: ML20246K558 (34) | |
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LIMERICK GENERATING STATION I UNITS 1 AND 2 !
PHILADELPHIA ELECTRIC COMPANY I
l-SOLID RADWASTE SYSTEM .
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APPROVAL: "[
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PLANT MANAC4R PORC MEETING: 89-OR$ DATE: $[g /gg
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1.0 PURPOSE This program provides guidance and boundary conditions for preparation of specific procedures for processing, sampling, E analysis, packaging and shipment of solid radwaste in I accordance with State and Federal Regulatory requirements.
2.0 SCOPE
! This program is applicable to the Limerick Generating Station solid radwaste processing system. ,
I 1.
3.0 REFERENCES
3.1 49'CFR Parts 170 through 178 1 3.2 10 CFR Parts 20, 50, 61 and 71 b 3.3 Standard Review Plan 11.4, Rev. 2, including Branch Technical Position ETSB 11-3, Rev. 2 3.4 Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification l
3.5 Low Level Waste Licensing Branch Technical Position on Waste l Form !
3.6 Limerick Generating Station Technical Specification 3/4.11.3 i
3.7 South Carolina Department of Health and Environmental Control Radioactive Material License No. 097 3.8 Barnwell Waste Management Facility Site Disposal Criteria l l 3.9 State of Washington Radioactive Materials License No. WN-1019-2 3.10 Chem Nuclear Systems Inc. Topical Report RDS-1000 l Radioactive Waste Dewatering System RDS-25506-01-NP-A 3.11 Stock Equipment Co. Topical Report Quick Dry Process for I
Dewatering Bead Resin and Filter Sludge, SRS-003-P Rev. O.
3.12 Nuclear Pacific Inc. Topical Report for Dewatering System
.TP-02-P-A Rev. 1.
l 3s
-ll Rev. 8 Page 3 of 15 tc TJG/KJC/dsl l
3.13 Westinghouse-Hittman Nuclear, Inc. Topical Report STD-R l 011P-A, Mobile-Incontainer Dewatering and Solidification L
System, l- .
4.0 GENERAL Plant Technical Specification 3/4.11.3 requires the Solid l Radwaste Processing System to be used in accordance with a j Process Control Program to meet transportation and disposal i site requirements. l It is the intent of the Process Control Program to provide
! reasonable assurance of meeting the regulations and to
} demonstrate compliance with 10CFR61 by:
l Defining the various waste streams Establishing a set of process parameters that affect solidification and developing operational controls for l
those parameters.
Implementing a Waste Classification System in accordance with 10CFR61 and applicable Regulatory Guidance. i Providing an appropriate Quality Control Program as required by 10CFR20.311 4.1 REVIEW, APPROVAL, CHANGES
'4.1.1 Changes to the Process Control Program shall be reviewed and approved by the Plant Operations Review Committee in accordance with Technical Specifications 6.5.1 and 6.13.
4.1.2 Changes shall be submitted to the Nuclear Regulatory Commission in the Semi-Annual Radioactive Effluent
! Release Report for the period in which the change was made in accordance with Technical' Specification 6.13.
4.1.3 Changes to resin dewatering implementing procedures or systems shall require verification that the free standing water content of the packaged product is
. within the limits established by regulatory limits via ST-0-RRR-733-0.
4D
LGS - PCP l Rev. 8 Page 4 of 15 TJG/KJC/dsl 4.2 USE OF VENDOR SERVICES
,4.2.1 Vendor services may be used to solidify or dewater any radioactive waste stream provided the services are performed with an acceptable. Process Control Program in accordance with A-99, Cont: ol of the Radwaste Process Control Program.
l 4.2.2 For Vendor dewatering described in Section 5.2 and 5.3 the Chem Nuclear Rapid Dewatering System RDS-1000 may be. utilized. A description of the Chem Nuclear equipment and process method may be found in Topical l Report RDS-25506-01-NP-A previously submitted to the NRC.
l 4.2.3 For Vendor dewatering described in Section 5.2 and 5.3 the LN Technologies / Stock Equipment Co. Quick Dry Process may be utilized. A description of the LN Technologies / Stock Equipment Co. equipment and process method may be found in Topical Report SRS-003-P Rev. O, previously submitted to the NRC.
l 4.2.4 For Vendor dewatering described in Sections 5.2 and 5.3, the Pacific Nuclear Systems dewatering equipment may be utilized. A description of the Pacific Nuclear equipment and process method may be found in Topical Report TP-02-P-A Rev. 1, previously submitted to the NRC.
4.2.5 For Vendor dewatering described in Sections 5.2 and 5.3, the Westinghouse-Hittman Nuclear dewatering equipment may be utilized. A description of the L
Westinghouse-Hittman equipment and process method may be found in Topical Report, STD-R-05-OllP-A, previously submitted to the NRC.
l 5.0 IMPLEMENTATION The Process Control Program shall be implemented by the use of approved plant procedures which provide the step-by-step direction for the operation of the process systems and shipment of waste to a licensed burial site. A list of plant procedures which implement the Process Control Program is given in Table 6.1.
I 41
o
,j LGS - PCP G yl Rev.-8 s Page 5 of 15 .!
TJG/KJC/dsl 5.1 WASTE STREAMS I
5 .1.1' CONDENSATE FILTER / DEMINERALIZED SLUDGE The contaminated waste product. generated.by the l backwash of the condensate filter demineralizers i Lconsisting of. contaminated powdered ion exchange resins at varying degrees of. exhaustion, fibrous I filter media, carbon overlay material, and small l concentrations of various solids, activated and non - )
activated corrosion products.
5.1.2 ' WASTE SLUDGE
.The contaminated waste product generated ~by the backwash of the liquid radwaste and. fuel pool filters and demineralizers consisting of contaminated powdered ion exchange resinsiand bead resins at varying degrees of exnaustion, fibrous filter media, carbon overlay material and small concentrations'of various solids and corrosion products; 5.1.3' REACTOR WATER CLEANUP FILTER / DEMINERALIZED SLUDGE A contaminated waste product generated by the backwash of the Reactor Water Cleanup filter demineralizers consisting of contaminated powdered ion exchange resins at varying degrees of exhaustion, fibrous filter media, and small concentrations of various solids and corrosion products.
5.1.4 DRY ACTIVE WASTE Dry wastes consists of air filters, miscellaneous paper, rags, etc., from contaminated areas;
- h. contaminated clothing, tools, and equipment parts that cannot be effectively decontaminated; and solid laboratory wastes.
5.1.5 OILS / SLUDGES-WET RADIOACTIVE WASTES Oils consist of non-reclaimable contaminated oils and grease of various grades both synthetic or otherwise in free form or containing various amounts of solid
, material. Sludge consists of sump dewatering sludges, filter solids, strainer solids and other wet solids too large to be handled by conventional dewatering techniques.
l 42
- : .g LGS.- PCP f $. [j! Rev. 8
. Page 6 of 15-
,4 m .TJG/KJC/ds1 7
5.2- PROCESS DESCRIPTION 5.2.1 CONDENSATE FILTER / DEMINERALIZED SLUDGE , ,
if I -a.- 'Each condensate filter / demineralized. backwash'
/ consists of approximately 9,000.. gallons.of-slurry
'l : with approximately'350 lbs (dry wt.)' spent resins u- and? crud.
H -
- b. Successive backwashes are collected and allowed to settle in a Condensate Phase Separator.' As the' sludge l settles, clarified' liquid is decanted.
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- c. For-centrifuge dewatering of the settled sludge,
& the phase separator is isolated when L approximately 240 cubic feet of sludge has
. accumulated.
- d. LFor vendor dewatering of'the settled. sludge, the-phase separator:is. isolated when approximately 360: cubic feet of sludge has accumulated.
l.
L e. The settled sludge is allowed'to decay in preparation for dewatering while further backwashes are routed to alternate phase r separators.
- f. The phase separator. contents are recirculated for a minimum of 30 minutes to mix contents of the vessel, resulting in a homogenous resin slurry.
(For centrifuge devatering the mixture is approximately 5% dry wt. concentration. For Vendor dewatering the mixture is approximately 7%
dry wt. concentration).
- g. The solids slurry is then fed to a centrifuge or d '
the External Processing Station for dewatering as appropriate.
5.2.2 WASTE SLUDGE l a. Each backwash from a radwaste or fuel pool filter L demineralized consists of approximately 1,500 j gallons of slurry, with approximately 60 lbs. i (dry wt.) spent resins and-crud (may contain l charcoal overlay). .j h.
l
- b. Each backwash from a radwaste demineralized consists of approximately 1,500 gallons of slurry, with an average of 2,125 lbs. (dry wt.) !
spent resins (may contain charcoal overlay).
),
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LGS - PCP y l Rev. 8 1 Page 7 of 15 L
TJG/KJC/ds1
- c. Successive backwashes from radwaste filter demineralizers, radwaste demineralizers, and fuel pool filter /deminerali'zers are collected in the Waste Sludge Tank until approximately 12,000
. gallons of liquid is accumulated.
- d. The Waste Sludge Tank contents-are recirculated for a minimum of 45 minutes to mix contents of the vessel, resulting in a homogeneous resin slurry ranging from 0.5 to 6% (dry wt.) total solids.
During normal operation the Waste Sludge Tank contains only the radwaste and fuel pool filter demineralized backwashes which result in a 0.5%
(dry wt.) total solids concentration. Periodic radwaste demineralized backwashes will increase the solids level to approximately 3% (dry wt.)
for one bed or 6%(dry wt.) for two beds.
- e. The solids slurry is fed to a centrifuge for dewatering or to the External Processing Station for vendor services processing.
- f. Waste Sludge Tank contents may also be sent to a l condensate phase separator for processing in accordance with Section 5.2.1.
5.2.3 REACTOR WATER CLEANUP FILTER / DEMINERALIZED SLUDGE
- a. F' + RWCU filter / demineralized backwash consists
- o. . approximately 1,100 gallons of slurry with approximately 48 lb. (dry wt.) spent resins and crud.
- b. Successive backwashes are collected and allowed to settle in a phase separator. As the sludge settles the clarified liquid is decanted.
- c. For centrifuge dewatering of the settled sludge, the phase separator is isolated when approximately 140 cubic feet of sludge has accumulated.
- d. For vendor dewatering of the settled sludge, the phase separator is isolated when approximately 190 cubic feet of sludge has accumulated.
- e. The settled sludge is allowed to decay in preparation for dewatering while further backwashes are routed to alternate phase separators.
dd
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l Rev. 8 Page 8 of 15 TJG/KJC/ds1
. f. The phase separator contents are recirculated for l a minimum of 30 minutes to mix contents of the L vessel, resulting in a homogenous resin slurry.
(For centrifuge dewatering the mixture is approximately-51 dry wt. concentration. For '
l l Vender dewatering the mixture is approximately 7%
dry wt. concentration).
l g. The solids slurry is then fed to a centrifuge or the External Processing Station for dewatering as appropriate.
5.2.4 Resin sludges from different waste streams may be mixed to optimize packaging.
5.2.5 OILS / SLUDGES
- a. Sludges and oils generatea during operation and maintenance are collected in containers in appropriate approved areas throughout the plant.
The filled and labeled containers are sealed and moved to a controlled-access enclosed area for temporary storage.
l b. Oils and sludges can be solidified in appropriate l containers by vendor supplied equipment in accordance with approved vendor process control procedures.
- c. Certain wet wastes may be allowed to dry and be .
treated as dry active .aste. ,
5.3 DEWATERING PROCESS CONTROL 5.3.1 Centrifuge Resin Sludge Desatering -
- a. The 0.5-6% solids slurries discussed in Section 5.2 are fed to a centrifuge at a controlled flow rate for dewatering.
- b. Operating variables such as centrifuge pond setting, bearing temperatures, equipment vibration, and differential torque are monitored to ensure optimum centrifuge operation and compliance with the free standing water criteria.
l c. The centrifuged resin is packaged in appropriately selected liners or High Integrity Containers (HIC). Process system level probes extending into the liners or HICs ensure that void spaces within the container are minimized to the extent practical. ,
45
LGS - PCP l Rev. 8 Page 9 of 15 -
L TJG/KJC/ds1 '
1 l 5.3.2 Vendor Resin Sludge Dewatering
- a. The 7% solids slurries discussed in Section 5.2 a're fed unthrottled to Vendor dewatering systems at approximately 30 gpm. ,
- b. Vendor dewatering operating variables such as waste type, process time, pump suction pressure, blower inlet pressure, ambient temperature and percent relative humidity are moritored to ensure optimum operation and compliance with the free standing water criteria for burial. ,
- c. Vendor dewatered resin is packaged in appropriately selected liners or High Integrity Containers (HIC). Process system level probes and/or video cameras mounted within the fill head
, ensure the liner or HIC is filled without undue void spaces to the maximum extent practical.
5.4 10CFR61 IMPLEMENTATION 5.4.1 WASTE CLASSIFICATION
- a. For dewatered resin, waste classification shall be based upon dose-to-curie calculation and the use of scaling factors for hard to measure isotopes. After each container fill, appropriate dose rates are obtained and inputted into Radman.
A detailed analysis is performed on an annual ,
basis by an independent commercial laboratory to ' -
e f identify isotopic abundances and scaling factors
( via ST-0-RRR-731-0, ST-0-RRR-732-0.
- b. For dry active waste (DAW), waste classification shall be based upon isotopic analysis and the use of scaling factors for Reactor Water along with DAW dose-to-curie conversion.
- c. For oils / sludges, waste classification shall be based upon isotopic analysis and the use of scaling factors for hard to measure isotopes. A detailed analysis is performed on each batch to be processed and packaged.
- d. A computerized waste classification and shipping l program, RADMAN, is used to determine waste classification from the isotopic analysis and l scaling factors. Manual methods may be used if
) the computer system is not available.
l
,l Rev. 8 Page 10 of 15 t TJG/KJC/dsl 5.4.2 WASTE STABILITY
- a. MINIMUM STABILITY REQUIREMENTS ,
- 1. Waste at Limerick Generating Station is ,
packaged in metal containers (drums, boxes, liners) or High Integrity Containers. In no case shall radioactive waste be packaged in cardboard or fiberboard boxes for burial.
- 2. Dewatered resin is sampled as a minimum annually to verify that the free standing water content of the packaged product is within the limits established by applicable regulatory limits via ST-0-RRR-733-0. In addition to the annual verification, the free 's standing water is determined whenever process changes occur that may significantly alter system dewatering performance.
3, To prevent accumulation of radiolyticdily '
generated combustible gas in greater than Type A radioactive waste packages containing water and/or organic subttances, one or more of the following measures are taken:
The container is equipped with a vent to prevent accumulation of such gas.
A determination by calculation, test, or measurement is performed to ensure that hydrogen generation is limited to a molar -
quantity that would be no more than 5% by volume of the secondary container gas void at STP over a period of time that is twice the expected shipment time.
The cask cavity will be inerted.
- 4. Experience has demonstrated that' utility waste streams do not contain or generate ~
toxic gas, vapors, or fumes and do not i contain hazardous, biological, pathogenic, or infectious materials.
)
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R3v. 8 i'
, Page 11 of'15 TJG/KJC/dsl'
- b. WASTE STABILITY
-1. Dewatered resin required to be stabilized is packaged in High Integrity Containers :(HIC) f, y
that have been certified to meet the stability requirements of 10CFR61.56(b). The HICs are handled and' stored in a-manner such i that their ability to provide stabilization is not compromised. The chemical and physical properties of the resin in no way compromises the. Integrity of the container.
h 2. All reasonable efforts are made to eliminate unnecessary void spaces within the waste
,_ packages.
5.4.3 LABELLING I
I Each package of waste shall be clearly labelled to
-identify waste classification.
5.4.4 SHIPMENT-MANIFESTS Each. waste shipment shall be accompanied by a shipping manifest giving a physical description of the waste, the volume, the radionuclides identity and quantity, the total radioactivity, the principal chemical form, and waste class.
5.4.5 QUALITY CONTROL PROGRAM l l
- a. The quality control program consists of required I use of plant procedures which implement the Process Control Program and requirements of the Corporate Quality Assurance Program. Audits by ,
.~ personnel independent of the activities are j performed and reviewed by appropriate management .;
personnel,
- b. In addition, the Process Control Program and implementing procedures are audited once per 24 months by the Puclear Review Board in accordance h with Plant Technical Specification 6.5.2.
~
g 5; 5 ADMINISTRATIVE CONTROL V !
f- -
5.5.1 Processing of solid radioactive waste shall be !
performed by properly trained and qualified operating .
- personnel. j L 4a ;
LGS - PCP l Rov. 8 Page 12 of 15 TJG/KJC/ds1 5.5.2 Processing of radioactive waste shall be performed in accordance with approved Operating and/or Radwaste procedures.
f 5.5.3. Procedures for processing, containerization, and I transport of waste shall ensure that specific DOT, NRC, and burial site requirements are satisfied.
l 5.5.4 Changes to implementing procedures are reviewed to ensure continued compliance with the Process Control
- Program.
t 5.5.5 Records of all data, tests, analysis results, and records of training, inspection, and audits are maintained in accordance with' plant QA procedures for record retention.
6.0 ATTACHMENTS, TABLES, FIGURES 6.1 Table 6.1 Process Control Program Implementing Procedures.
6.2 Figure 6.1 Solid Radwaste Management System Process Flow l
Diagram.
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h LGS.- PCP l Rav. 8 Page"13 of 15
{ TJG/KJC/dsl ATTACHMENT 6.1
.- Process Control Program Implementing Procedures A-99 Control of the Radwaste Process Control Program RW-100 Administration of the Radioactive Material and Radwaste Packaging and. Transportation Program RW-101- Administration of Packaged Radioactive Waste l RW-103 Isotopic' Determination of Packaged Radioactive Material RW-106 Review of Vendor Topical Report for Waste Proce'ssing l RW-130 Administrative Controls for RADMAN
- l RW-132 User's Guide to RADMAN f l RW-222 Shipment of Radioactive Waste to Barnwell l RW-223 Shipment of Radioactive Waste to Richland RW-230' Core: Sample of Liners and HIC's p RW-420 External Processing Station Resin Transfer and Dewatering Using Pacific Muclear Containers and Equipment S66.8.B RWCU. Phase Separator Decanting S66.8.C. Centrifuging RWCU Phase Separators
- S66.8.F Centrifuging Waste Sludge Tank i
S67.8.A Operating the Resin Pill Stations S 6 7 . 8 '. A Equipment Alignment for Operation of a Solid Radwaste (COL) Centrifuge S67.8.B Condensate Phase Separator Decanting LS67.8.G Centrifuging Condensate Phase Separators
. l'S67.0.A External Processing of RWCU Phase Separators l S67.0.B External Processing of Condensate Phase Separators l S67.0.C External Processing of Waste Sludge Tank L
50
I LGS - PCP l Rev. 8 Page 14 of 15 TJG/KJC/dsl ST-0-E R-731-0 Periodic Sampling and Analysis Program for the l
Determination of Abundance Factors ST-0-RRR-732-0 Periodic Deter'mination and Update of Abundance i Factors for Gamma Emitting Isotopes .
ST-0-RRR-733-0 Sampling and Analysis of Dewatered Resins for the Determination of Free Standing Liquid l
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WFM/CBA/ del PHILADELPHIA ELECTRIC COMPANY
-LIMERICK GENERATING STATION .
L SURVEILLANCE TEST' .
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7[,28 ((
ST-O'-RRR-990-0: DETERMINATION OF MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS..
TastLSpecification: 6.15~ ~ -OR- Initiating Event: 1. Reason Tost Frequency: 6 Months 2. MRF No.
! Test Results:
Section A. All Steps Completed SATISFACTORILY >
Performed By:(Sign - Time /Date) 'M -0D0/$+S1 Reviewed By: (Sign - Time /Date) mu% o
&/rf$ /I m,/8[9[69
(;
Section B. One or More Steps / Test Results UNSATISf'ACTORY Performed By:(Sign /Date/ Time)
Reviewed By:(Sign /Date) i
- NOTIFICATION
Person Notified: (Supervision)
Notified By:(Sign Date) i l
l
- Time Notified:
f ADDITIONAL ACTION / TEST COMMENTS:
If any entry is made in Additional Action / Test Comments !
Section, person making initial entry sign here.
(Sign - Time /Date) 44 C- 7 - Odf8 o .
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Paga 2 of 5 i WFM/CBA/ds1 l
1.0 PURPOSE To. determine what constitutes a Major Change to i Radioactive Waste Treatment Systems as required in plant Technical Specifications, Section 6.15.
AND in Surveillance Test ST-0-107-992-0, Semi-Annual Radioactive Effluent Releas~e Report.
2.0 REFERENCES
2.1 Limerick Technical Specifications, Section 6.15, Major Changes to Radioactive Waste Treatment Systems.
f 2.2 Peach Bottom Technical Specification, Section 6.18, Major Changes to Radioactive Waste Treatment Systems.
2.3 Surveillance Test ST-0-107-992-0, Semi-Annual Radioactive Effluent Release Report.
I 3.0 TEST EOUIPMENT None l
l 4.0 PRECAUTIONS AND LIMITATIONS I 4.1 The responsible system engineer (s) for systems 61, 62, 63, 64, 66, 67, 69, and 70 need to be involved in the implementation of this procedure.
l 5.0 PREREQUISITES f
None 6.0 PROCEDURE IT IS THE RESPONSIBILITY 0F THE PERSON OR PERSONS PERFORMING THIS TEST TO ENSURE ALL BLANKS AND DATA SHEETS ARE CORRECTLY AND COMPLETELY FILLED IN.
1 i
54
)
.. _ _ _ _ _ - ..i
w wa;w=uAvce, tuy. w P292 3 of 5 WFM/CBA/d31 6.1 Review all modifications implemented during the period described in ST-0-107-992-0 to determine if any major
- changes to radioactive waste treatment systems have been
{ made which need to be reported in the Semi-Annual
) Radioactive Effluent Release Report. Major changes shall include the following:
f 6.1.1 Changes in process equipment, components, structures and effluent monitoring instrumentation from those described in the Final Safety Analysis f~ Report (FSAR) and evaluated in the NRC Staff's Safety Evaluation Report (SER).
) 6.1.2 Changes in the design of radwaste treatment 3 i systems that significantly alter the {'
characteristics and/or quantities of effluents released from those previously considered in the FSAR and SER.
i 6.1.3 Changes in system design which invalidate the f
} accident analysis as described in the SER.
6.1.4 Changes in system design that result in a !
significant increase in occupational exposure of j operating personnel.
i 6.1.5 Changes in system design which require a change to
! the PCP (Process Control Program).
i 6.2 ALL modifications implemented during the period specified
) in ST-0-107-992-0 have been reviewed by the responsible test engineer:
j TEST ENGINEER, SYSTEM 61 i)Mb () i TEST ENGINEER, SYSTEM 62 T)PN) NYi*)
TEST ENGINEER, System 63 DPM 9 Nd( * )
l TEST ENGINEER, SYSTEM 64 3 M D/M[d(*)
TEST ENGINEER, SYSTEM 66 bo (*)
l TEST ENGINEER, SYSTEM 67 ufM1 h (*)
TEST ENGINEER, SYSTEM 69 Efd ()
TEST ENGINEER, SYSTEM 70 b9 *)
6.3 E no major changes to radioactive waste treatment systems have been implemented during the period specified in .
) THEN go to section 7.0 ( rer'arn to normal) .
55
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4 H ~Pags 4'of:S T< <
WPM /CBA/dsl L'
E 6142 IFEany majorfchanges.to radioactive wasta-treatment' systems have been implement?:d during the period specified in.ST-0-107-992-0,.
THEN prepare a di'scussion of the change gp' ~~' AND include this discussion in the ADDITIONAL ACTION / TEST ,
' COMMENTS section. This. discussion shall contain the ' ,.
'following:
I
, 6.4.1 A summary of the' evaluation that led to the determination'that the change.could be made in
.,; accordance with'10CFR 50.59.
'b.'.2-4 Sufficient detailed information to totally support the reason for the change without the benefit of-additional or supplemental information.
p-6.4.3. A. detailed. description of the equipment,
-components, and processes involved and the interf aces -with other.. plant systems.
6.4.4 An evaluation of the change which shows the predicted releases of radioactive materials.in
-liquid and: gaseous effluents and/or quantity of F ' solid waste that differ from these previously b
. predicted in the license application and smendments thereto.
6.4. 5. An evaluation of the change which shows the expected maximum exposures to individual in the UNRESTRICTED AREA and to the general population J
tuat-diffct from those previously estimated in the 1icense application and amendments thereto.
6.4.6- A comparison of the predicted releases of ~
radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made.
6.4.7 An estimate of the exposu.e to plant operating personnel as a result of the change.
6.4.8 Documentation of the fact that the change was reviewed and found acceptable by the PORC.
s .
56
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.w. , w ave ,o avve w p' ?~ .
.Pega 5 of~S' WFM/CBA/ds1 V .
T 7;0- RETURN TO NORMAL:
T 7)l', '
Notify! responsible coordinator for Surveillance Test A ST-0-107-992-0, OR Technical Support Health' Physicist of the results of l
Hii's Major. Changes to Radioactive Waste Treatment Systems 4 ';l< Determination ll k AND provide them with-the description of any major i N ,- changes,--if'appli' cable. "
8.0 ' ACCEPTANCE! CRITERIA.
1 i 8.1. All steps marked with asterisk (*) completed. 1 i
..8.2- Review.of major modifications has-been performed
- AND a discussion ~of major changes to radioactive waste 1 f: *reatments' systems is attached (where applicable). l 843. Coordi,nator'for ST-0-107-992-0 ,
L R O_R: Technical Support Health Physicist has been notified of j tes_t. completion.
I f' NOTEi At test. completion, ensure cover sheet is correctly and
) completely filled in.
NOTE: .If any entry is made in this section, sign /date cover -j
["
i ' sheet under Additional Action / Test Comments.
ADDITIONAL ACTION / TEST COMMENTS: @ W 6. l. f 4F Td75 P/oc6Wf-t f2omes bocamewm,oJ sF " can ne.1 id syso
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- ~_ _~ = c. v _o _=,.- _ 0.:. O*Cr:. __' r..'1*. _.7 r :.. _ ON
- 2. YES Is a chance to the Technical Specifica:icns required?
NO If YES, an a==endmen: to the Technical Specifi:2tiens (c is recuired to be suh=itted to NES for amereval.
- 2. %
Asthe cf a resultf=11cwinc cf thececur? prcpesed chanc.e, test, or exteri=en: na.v anv. .
1 .
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- a. YIS Increase the pr:bability of ce urrence or the c=nsequences of an acciden: er NO r.alfunction of equip.ent i=portant to safety as evaluated in the FSAR. *
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DESGIEE EASIS FOR DE~r= NATION: '
ffAll5 CN $ 'ID y1+E fRocEsS 'CodTh L. (f.d%s A-bb82SSES AES' d gu,y.y cagcgg.ifth led 0%IGES A#b A * P ~ 'A # # f^*##" '"'d~~E' NA WhSTE EVAW4= nod . '7PE55 CA.4NES Wtbl. McY idCAEASE THE f%rAgiu;y of;
. eccMRf2' .dCC o A TV5 Cod 5EQJEnc&S. eF Ad Acctb247~ oA MAU;udcnad er f a00 fMEdT tmlc'RY&n/*r 'ov SA+6YY, 5MBb oW Ad Et/ALWPns& Mb A6 VIED aF F5kR. SEcnod it.sf .
- b. YES Create the possibility of an accident er
'malfu?2ction of a different tyce than any
-~h evaluated previously in the FSAR. ~ '
DESGISE EASES FOR DET.r e.MINATION:
'11f6 CHAD &SS 10 'tY 6 NBC6SS C W W.DI (AtGfJt4n Nil.L Hbl~ CAE.EE 'rH S
. fos 3tSIW7Y of UdEMM.WrEh ACCibEd7S of /WKfdWCD*AS 5BSEb ad A /GV'E'd
,of= FSAA S'5 cT7W 15,7. z. , THE, CMnG65 CodCEAftdG VE/M BEN 4'rT.AldG l ARE CoMSISTEdf" WsTH- THE VEMbcd'S (RocESS ce M cL. @oG/Am A.5 .
$nPWAT6b sd FSAA SEc3& //.Y.2.2.'7. .
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- _ = _ - - _ . = . . . _ _
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Revis1:n 1 Shee- 2 cf'2 b<
a % . ,. c. YES Reduce the margih-of safs:7 as' defined in the basis'fer any Tech.. Spec.
DESCRI3E SASES TOR.DETEv.INATION:
M CH>>(CES 9 .Tlff fNCESS CUTA*& $A0GdAm Wttu Mor"
( lggpocg ' 'Ny mAA4W of i'AFETYj BASEb ^ od A REf*M cf ry G .;Sfec.. 'SR5ti fV.II.5-1
-If any of othe abcVe questiens are answered YES, an unreviewed safety ques:icn exists and NES approval is required l .' 4. YFS'.
Is the prepesed change, test or ecuin=ent ne icncer E .l , N
'in greement'with what is described 'in the TSAR or l asscciated with an ICAR~ change?
g cg/Ggs ~m ~7pg (DCBSS cMt. /2'oGKAnt wEdg m&CE jd
);c.u spkfCE yliTit A-99 krb Do NoT' CWR.tc7 Wm+ FSM p- DE5cAtm%f.% :A9 ARE f- AS5cci;qqp pni7t AN 7=SMKlCHHv66***
;FASEb eil n /EMid SP FSAA SECWd H.4 ,
ll If yes, a ecpy of the 'PORC~. packages must'be submitted te the3 i
'l ~ Nuclear Supper: Licensing See:icn by the preparer for 10CFR50.59-deportability.
/
Preparec py Date
- 5. -PORC APPROVAL:
(NOT APPLICABLE IF PORC APPROVAL FORM IS DSED). p' . F , .
.(a) Sta. Supt. : (g) I&C Eng. ':
.(b) Assist. Sta. Supt.: (h) Reac Eng. :
(c) Tech.'Eng. : (i) Shift Supt.: (d) Ops. Eng. : (j) Reg. Eng. : (e) Maint. Eng. : (k) : (f) Sr. E.P. ,
- (1) :
' DIRECTIONS TO' ADMIN. STAFF:
~-~ TRANSMIT TO NR3 FOR: INFO REVII'd APPROVAL .
. , _ _ FILE (to NRMS)-
~OTEER:
~
59
- _y3 -
grgumexr 2-l_ ST- o-AKK - 990 - 0 AbbmWK AcmdlY&sr &M ff.DC&vdBE S75f 6.V . biscu.csiod 6,1, l SEE MMCHrHEAT' / - SAf67-}' Svgt/#no) 442- TW6 (A6CES5' W i- fA'o W was pgvices n At>p4ss /ESW SuifA' cWcgdrzw.s cms, w incubs Abbman vgwbegs in ws "use op W/stboA SES. VICES SEcried, Adb 10 tacwb6 A- J soPrWA$E PDGM w cM4dGE Fo2 WASrE svauknod. G.!l3 $0 E#fMEM, %poggd75 og fArc6Sstr u/E#6 OyVdG6b AS A f B S di- Y OF ~77h 5 1"Cf A&d/C/DN ~ s1SMM c%fAndG fMc64dAE.S WE 5ggd AgasEb t -o BGREcT' fCP CH*dG66 i
- f. y.t) ruz PEditied ro 77tE PhcGTS ce,acoz. fA>ewAm wou for BESULY t d A u%fGE 70 TW5 PAssicrEb
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6.g 7. -rn ouven1y op wiencnvcm m a won ey 7Hc soub p.4wamc syrrem ma Mor ! ( CH1WGE AS A- /ESd7 DF 'nhs P/ocess cos w.'ot. f 5S' * $8, & 7'C W 4 i.. Aldm8EA cP cdD ES IMdblEb Sy tHE saub \ i ! RJbWASTE 5ytr6m Wiu- psr c//-MdGE. fa CH&GE l tM EXfoiu% v fthWY ofEA+ridG PEASos/Sc WIU - ' occoK ks p SEMr op- nHS cimwGs.
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g-w,1 y u N hifR;vicion 5 LIMERICX GENERATING STATION y /, M fEFFECTIVEDATE PORC APPROVAL FORM . i OA Acoreval Not Recuired Pago 1 of 1 CRE [ DOCUMENT (TITLE, OR PROC f & REV.): J. A - fc / A v, wer/2-,, 883078610
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- 2. REASON FOR SUBMITTAL / CHANGE: W /?#. 7 /
tge%o2 de /e?>,/4, r
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l[l NEW PROCEDURE l_~l TEMPORARY CHANGE TO APPR'D PROC. I j l [ PROCEDURE REVISION REVIEW OF TEMP CHANGE ONLY ;
~
-l_l PORTIONS OF PROC. REVIEWED & l~l TEMPORARY CHANGE TO APPR'D PRCC. *'
REVIEW OF TEMP CHANGE AND SUGGESTED CHANGES INDICATED PERMANENT PROC REVISION . l[ENTIREPROC. REVIEWED & h' SUGGESTED CHANGES IJDICATED l__l PROCEDURE CANCELLATION / SUPERSEDURE (Periodic v ' ewA-2 Y /b>) by i: Revl. ewer Resp. Staff Engr. Approval ' l
. Sub PORC l l[lPORCMeeting l~l/C ~3~ CE//Ci [] PORC Walkaround Reporting Resp. -
f: Date: PORC' REV'D& APP'D PORC REV'D& APP'D PORC REV'D& APP *D
~
pEVIEWER INITIAL 1DATE. REVIEWER INITIALiDATE REVIEWER INITIALiDATE , (UPT-OPS ) 2 (( SUPT-M/IC: MAINT ENG, JUPT-TECH. A SUPT-OP , REG ENG
- g;]T-PLT TECH ENG l
SFT SUPT Ntd 2-k Y'h Opica r AG W wr2- $$ Y'9 - k f/k/b .,<$ rl y'lh9 T ; i \
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1 NOTIFICATION / TRAINING: Procedure Sections
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[l Imm:c:1 Notif l[l Requal Trng l_l Intern Train l_It'Not Req. Resp ,vac's
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Groups:..._l...Oper l_ l_l HP .._l.. l_ Chem l_;,,,l-- -- - . Tech Staff l_l Other involved . _
-Comments Sugg. comp 1. date or, event: ::
. _ . i-
- OMMENTS/ CORRECTIVE ACTION
- : I
.'. i 7, ii
] Approved with' comments / changes on attached document f,:'.
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IlENTS/ CORRECTIVE ACTION .I EN & CHECKED /DATE MANAGER APPROVAL /DATE Coon to NRB for ' Approval t
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Info b.; elIN OR PREPARER , ~
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- - - _ _ _ _ _ _ _ _ - - - _ - _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ __ _ _ _ - _ _ J
V. f 0.D.C.M., Revision 7-1 The O'.D.C.M.:was revised'to include new sampling station'in h ' response to LGS LER 89-30. .One TLD control station (18Gl-C) has
- i. 'been included in-revision 7. Fish and food product sampling stations,' inadvertently omitted in'the previous. revision, have now-
!. been incorporated. A copy of the affected pages and documentation
'of:POHC approval,'isjincluded within. ..j
.l L
f , ! I ); r. L l l l p l l a r
p r j., 3 ,OFFSITE; DOSE CALCULATION MANDAL: h; _
, Revision;7~
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LIMERICK: GENERATING ~ STATION- 'i UNITS;.1 AND'2 PHILADELPHIA ELECTRIC COMPANY Docket Nos. 50-352i,f 50-353 0 PORC' Approval: > [7
<g Manag'er Radiation Control and Chemistry j
'Section Approval:. /.
1 g Dirptor i LGS Health Physics N'8en," M l
. Representative: 44
/
Radiation. Control',and Chemistry 47 , , f .
- Rapresenta tive : ' e /' . '/ev Y
j. b _i________ -. --
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t 8 APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - SAMPLE TYPE, LOCATION, AND ANALYSIS )~ i o G5 ! l
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' s SSSSSW O n s
- .I D o sssssessssssssssssssessssss eeeeel eeee A i ceeeeeeeel eeeeee R t lllllilllll'allllllllillllll a iiiiimiiiiiiiiiiiiiimiiiiii mmmmm c o mmmmmmmmmmmmmm mmmmmm - l 61664.58.15225955936266 050402204203502403011033500
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55W 5 \ I. ) FIGURE B 1 ENVIRONMENTAL SAMPLING LOCATIONS ~ ON SITE OR NEAR THE l' ' LIMERICK GENERATING STATION i ENGR 464 HP W DATE ih*'4
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REV 70 _ - - _ - - -}}