ML20082M231

From kanterella
Jump to navigation Jump to search
Semiannual Radioactive Effluent Release Rept - 910101-0630
ML20082M231
Person / Time
Site: Waterford Entergy icon.png
Issue date: 06/30/1991
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20082M216 List:
References
NUDOCS 9109050096
Download: ML20082M231 (34)
v • d • e


Text

{{#Wiki_filter:. i Semiannual Radioactive Effluent Releasr Heport January 1, 1991 - June 30, 1991 Waterford 3 Entergy Operat ions, Inic. W350897tlP 9109050096 910829 gDR ADOCK 05000382 eos

f TAllLE OF CONTENTS I 1.0 SCOPE l t 2.0 SUPPLLMENTAL INFORMATION j t 2.1 Regulatory Limits l 2.2 Maximum Permissible Concentrations l 2.3 Average Energy f 2.4 Measurements and Approximations of Total Radioactivity i 2.5 11atch lieleases - 2.6 Unplanned Releases 3.0 GASEOUS EIT1,UENTS l t -l 4.0 LIQUID EFFLUENTS l 1 5.0 SOLID WASTES' 6.0- METEOROLOGICAL DATA

7.0 ASSESSMENT

OF DOSES 8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program 8.2 Changes to the 9ffsite Dose Calculation Manual 8.3 Unavailability of REMP Milk Sampling 8.4 Report. of Technical Specification Required Instrument inoperability 8.5 Activity Released via Secondary Pathways 8.6 Additional Information 9.0 TABLES 10.0 ATTACl!MENTS L W35089711P 1 l . ~. - _ ~...,.. _. _... _.,. ~, -., _.. ~...., -... _ _.. _,, _, _..-..,.._,.....m

l 1.0 SCOPE i ? This Semiannual Radioactive Elfluent Release Report is submitted as required by Waterford 3's Technical Specification 6.9.1.8. It covers the e period from January 1, 1991 through June 30, 1991. Information in this l t report _ is presented in the f ormat outlined in Appendix B of Regulatory i t Guide 1.21. I i i The information contained in this report includes: i ) (1) A runnary of the quantities of radioactive 11guld and gaseous ef fluents { and solid wastes released f rom the plant during th'e reporting period; f t (2) A discussion regarding radioactive gaseous effluents released from identified and monitored secondary release paths during the reporting l period; and, .i (3) An explanation of why certain inst rumentation _was not restored to I operable status within the time specified in the ACTION statement, as i per Waterford 3 Technical Specifications 3.3.3.10 and 3/4.3.3.11. } The summary of meteorological data and results from the assessment of radioactive doses due to the release of liquid and gaseous radioactive 3 effluents will be included in the Semiannual Radioactive Effluent Release Report to be submitted within 60 days af ter January 1, 1992. i i l t t I t W350897HP 2 I ... -...- m. ,,___-..._-_-...__--._._,.__.J

._.. ~... _ _ _...._ _.__ _._ _ _ _ _. ~. _ _ _.. _ _ __ _ _,_ 2.0 SUPPL.DIENTAL INF010!AT10N 4 2,1 Regulatory 1.imit s The Technical Specification limits applicable to the release of . radioactive material in liquid and gaseous effluents are described in the following sections. 2.1.1 Fission and Activation cases (Noble Gases) The dose rate uue to radioactive noble gases released in gaseous ef fluents from the site to areas at and beyon1 the site boundary shall be limited to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin. The air dose due to nobic gases released in gaseous effluents from the site to arets at or beyond the site boundary shall be limited to the following: a. During any calendar quarter: 1.ess than or equal to 5 mrad for ganuna radiation and leas than or equal to 10 mrad for beta radiation and, b. During any calendar year: Less than or equel to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation. l 2.1.2 Jodines; Particulates, llalf 1.ives > 8 Days; and Tritium-l The dose rate due to lodine-l?1 and 133, tritium, and all l l radionuclides in particulate ferm with half' lives greater than eight (8) days, released in gaseous offluents from the site to' areas at and beyond the site boundary, shall be limited to less than or equal to 1500 mrem /yr to any organ, l t W35089711P 3 1 1. v,_m.. -.-.w.~,-.,. ,.,,.~, .m~,.. - ~..,-.. -.-.-..,--,. _. ---.,,.

_____._m__.___..-_.__-_._ i r h The dose to a member of the public f rom Iodine 131 and 133, l' tritium, and all radionuclides in particulate form wi'.h half lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall b'c limited to the following: a. During any calendar que.rter: Less than or equal to 7.5 f mrem to any organ and, b. During any calendar year: Less than or equal to 15 mrem to any organ. 2.1.3 Liquid Effluents The concentration of radioactive material tu'a "I in liquid g effluents to unrestricted areas shall be limited to the f f concentrations specified in 10 CFR Part 20, Appendix D, Table i II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/mi total activity. I The dose or dose commitment to a member of the public f rom l radioactive materials in liquid effluente released to unre-f stricted areas shall be limited to the following: ) During any calendar quarter to less than or equal to 1.5 f a. mrem to the total body and less than or equal to 5 mrem f to any organ, and i b. During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to t -any organ, t i l l l I i f W35089711P 4 . ~

1 2,1.4 Uranium Fuel Cycle Sources l [ The dose or dose commitment to any member of the public due [ t to release: of radioactivity and radiation irom uranium fuel i cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, t which shall be limited-to less than or equal to 75 mrem) over 12 consecutive months. f i 2.2 Maximum Permissible Concentrations [ -i

2. 2.1 - Fission and Activation Gases; Iodines; and Particu'ates, llalf i

Lives > 8 Days e L t For gaseous' effluents, maximum permissible concentrations are j not directly used in release rate calculations since the appl'icable limits are expressed in terms of dose rate at the site boundary. I 2.2.2 Liquid Effluents } i The maximum permissible concentration (MPC) values specified A I in 10 CFR Part 20, Appendix B, Table II, Column 2 are used as I the permissible concentrations of liquid radioactive. ef fluents l -at the unrestricted area boundary. A value of 2.0E-4 pCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents. i l i F 2.3 Average Energy i l F l Average energy is not applicable t.o Waterford 3's Radiological [ L Effluent Technical Specifications. E-Bars are not required _to be f calculated from effluent release data. i b r r W35089711P 5 [

) 2.4 Heasurement s atul_ Aynroximat ions of Total Radioactivity i The quantification of radioactivity in liquid and gaseous effluents was accomplished by performing the sampling and radiological-analysis ) of offluents in accordance with the requirements of Tables 4.11-1 and ) 4.11-2 of the Waterford 3's Technical Specifications. i 2.4.1 Fission and Activation Gases (Noble Gases) 5 For continuous releases, a gas grab sample was analyzed l monthly for noble gases. Each week a Gas Hatio (GR) was calculated according to the following equation: i GR = Average Weekly _ Nolle Gas Moni_ tor Heading f _ Monitor Reading During Noble Gas Sampling The monthly sample analysis and weekly Gas Hatio were then used to determine noble gases discharged continuously for the previous week. For gas decay tank and containment purge batch releases, a gas grab sample was analyzed prior to release to determine noble gas concentrations in the batch, in all cases the total-radioactivity in gaseous effluents was determined from measured concentrations of each radionuclide present and the total volume discharged. 2.4.2 lodines and particulates lodines and particulates discharged were sampled using a i continuous sampler which contained a charcoal cartridge and a i-particulate filter. Each week the charcoal cartridge and l_ particulate filter were analyzed for gamma emitt!crs using 4 j gamma spectroscopy. The determined radionuclide concentrations i and effluent volume discharged were used to calculate the i previous week's activity released. t !f-4 4-1 W35089711p 6

The particulate sampics were composited and analyzed quarterly f or Sr-89 and Sr-90 by a contract laborat ory (Teledyne Isotopes). Particulate gross alpha activity was measured weekly using alpha scintillation counting techniques. The detennined activities were used to estimate ef fluent concentrations in subsequent releases until the next t.cheduled analysis was performed. Grab sampics of continuous and batch releases were analyzed monthly f or t ritium. The determined concentrat lonn were used to estimate tritium activity in subsequent releases until the next scheduled analysis was performed. 2.4.3-Liquid Ef fluent s For continuous releases, samples were collected weekly and analyzed using gamma spectroscopy. The measured concentra-tions were used to determine radionuclide concentrations in-the previous week's releases. For batch releases, gamma analysis was performed on the sample prior to release. For both continuous and batch releases, composite samples were analyzed quarterly by a contract laboratory (Teledyne Isotopes) for Sr-89, Sr-90, and Fe-55. Samples were composited 8 and analyzed monthly for tritium and gross alpha using liquid scintillation and gas flow proportional counting techniques, respectively. For radionuclides measured in the composite samples, the measured concentrations in the composite samples -from the previous month or quarter were used to estimate released quantities of these isotopes in liquid effluents during the current month or quarter. The total radioactivity in liquid effluent releases was determined f rom the measured and estimated concentrations of each radionuclide present and the total volume of the effluent discharged. W350897HP 7

..__3 [ 1 ? I 2.5 ljatch Releases I l The summarization of information for gaseous and liquid batch releases is included in Table 1. t 2.6 1]nplanned Releases l [ I On riarch 22, 1991 at 0$11, an unplanned release of radioactivity } occurred-during Steam Generator ventilation operations inside the -l t Reactor Containment Building. At no time were any Technical Specification limits exceeded. I Description of_ Event: On March 22, 1991 a' 0511, both Plant Stack radiation monitor gas i t channels went % high alarm and isolated Containment Purge. Plant l conditiot.. at the time of the event were: Reactor shut down, refueling l outage //4 in progress, primary coolant system drained to mid-loop l level, Steau Generator #1 manways being removed for maintenance, Containment Purge running with limit stops removed. A ventilation blower with installed high efficiency filters had been connected to f one of the Steam Generator manways and the discharge ducting routed i i to the suction of the Containment Purge exhaust duct. The ventilation unit connected to the Steam Generator was started and, af ter approximately 30 seconds, the Plant Stack radiation monitor 6 gas channel went into high alarm and automatically terminated Containment Purge. The highest value observed for the Plant Stack l gas channel was 1.4E-3 pCi/ce, which then decreased rapidly due to f the termination of Containment Purge. The duration of the release [ was approximately 30 seconds, in which a maximum of 3.03 Ci of Xe-133 was released. Potential Reportable Event 91-016 documents this event. I I r I i i ) W35089711P 8 l i'

L i i e Cause of Event [ r Ilecause a continuous release permit was in place to account for i radioactive gas released f rom containment through the Plant Stacx, a f gas sample from the Steam Generator was not obtained prior to the discharge. The Plant Stack high alarm setpoint is used to ensure I that releases do not exceed Technical Specification limits. This ) setpoint is conservatively based on the noble gas nuclide mix that I would be released f rom the reactor coolant system during full power operations. When the gas has aged somewhat, as was the case in this event, the Plant Stack radiation monitor high alarm setpoint is lower than necessary and will alarm at noble gas levels well below j Technical Specification limits. l 5 i Because venting the-Steam Generators had not isolated Cont-ainment f Pu rt, during past outages, the Plant Stack radiation monitor high l alarm setpoint was not adjusted upward to account for the actual I nuclide mix. As a result, a high alarm was received, isolating f Containment Purge, even though no Technical Specification limit was exceeded. i -l, Corrective Action: I Immediate corrective actions included securing the ventilation unit I connected to the Steam Generator #1, evacuating unnecessary personnel j from inside containment, and obtaining a Plant Stack r.oble gas grab sample. The Plant Stack noble gas grab sample contained 7.626E-6 pCi/cc Xe-133. Because the Emergency Plan Implementing Instruction j l-uses a valid Plant Stack reading of > 1.10E-3 pCi/cc as an i 1 indication of an Unusual Event, the event was declared on March 22,- t 1991 at 0544. f m- ? i I r W35089711P 9 L

t E

r

.. - ~.. I I [orrective Action (cont'd): - A' subsequent evaluation of the Plant Stack release rate was performed using the maximum monitor readings and actual nuclide mix during this event. The calculations indicated that the instantanenus dose rates due to noble gases were 326.6 mrem / year for the total body and 771.4 mrem / year for the skin. These dose rates are within the - limitations of 500 mrem / year for the total body and 3000 mrem / year f or the skin. The total doses due to the release of 3.03 Ci of Xe-133 were calculated to be 3.106E-4 mrem for the total body, 7.373E-4 mrem for the skin, 3.730E-4 mrad gamma airdose, and 1.109E-3 mrad beta I airdose. Thus, no Technical Specification limits were-exceeded. Before commencing further venting of Steam Generator #1, a greb sample was obtained from the discharge of the ventilation unit connected to Steam Generator #1. The sample contained-!.92E-2 pCi/cc noble gas, mainly Xe-133. Based on this sample, the Plaut Stack nobic gas high alarm setpoint was adjusted upra-ds. As an - added precaution, the large ventilation unit (2000 cht) connected to - Steam Generator #1 was replaced with a smaller one (250 cim) Actions Taken to Prevent Recurrence: An act. ion. plan was established to run the small ventilation unit for brief intervals while observing the. Plant Stack radiation monitors for rapidly increasing activity. If the result s were satisf actory, then continuous operation would commence. Ventilation of Steam Generator #1 proceeded and Plant. Stack activity was within the expected value. The 250 cfm unit was ran for an hour and then switched to the 2000 cfm unit. No further problems were encountered. In' future maintenance outages, ventilation of the Steam Generators will be done in a method similar_ to the plan initiated during recovery from this event. IIcalth Physics procedure HP-002-222 will be revised to include precautions for venting operations on the primary side of the Steam Cencrators. Venting the reactor vessel j head should be performed prior to opening the Steam Generator manways. W350897HP. 10 ,,-,~...m. _,,.,m- __--.. _,,, _ -... _ _..,.. -. _. _... _ ~ . ~ ~ . - ~

3.0 G AS EOU_S__.EI_T_I.U_ENT S The quantities of radioactive material released in gaseous effluents are summarized in Tables lA, 18, and IC. Note that there were no elevated releases, since all Waterf ord 3's releases are c onstdered to be at ground level. The estimated total error in % is based upon several statistical uncertainties due to sample counting, cificiency, volume, etc. 4.0 LIQUID EFTLUENTS The quantities of radicartive material released in liquid ef fluents are summarized in Tables 2A and 211. The estimated total error in % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc. 5.0 SOLID WASTES The summary of radioactive solid wastes shipped offsite for disposal is listed Table 3. The estimated total error in % is based upon soveral statistical uncertainties due to sample counting, efficiency, volume, etc. 6.0 METEOROLOGICAL DATA The summary of the hourly meteorological data for this repor t ing period will be included on the Semiannual Effluent Release lleport to be submitted within 60 days a f t er January 1, 1992.

7.0 ASSESSMENT

OF DOSFS l The summary of doses due to gaseous and liquid effluents for this reporting period will be included in the Semiannual Effluent Release Report to be submitted within 60 days after January 1, 1992. l 1 W35089711P 11

8.0 RELATED INFORMATION 8.1 Changes to the Procecs Control Program Changes made to the Process Control Program are included in of this report. 6 8.2 Changes to the Offsite Dose Calculation Manual There were no changes to the Offsite Dose Calculation Manual for the period this report covers. Changes, in accordance with NRC Generic Letter 89-01, to Radiological Effluent Technical Specifications and-the Offsite Dose Calculation Manual were approved by the Nucle 3r Regulatory Commission, but have not been implemented at this time. - 8.3 Unavailability of REMP Milk Samples Due to the unavailability of three milk sampling locations within five kilometers'of the plant, Broad Leaf sampling is performed in accordance with Technical Specification Table 3.12-1, Milk is collected, when available, from the control location and three identified sampling locations as indicated in Vaterford 3 Offsite Dose Calculation Manual, Table 2 and Table 3. 8.4 Report of Technical Specification Required Instrument inope rability Technical Specifications 3.3.3.10 and 3.3.3.11 require the reporting, in the Semi-annual Radioactive Effluent Release Report, of why designated inoperable instrumentation was not restored to operability within the time specified in the ACTION statement. During the g reporting period, ti,ere was one case when instrumentation was not r" stored to operability within the time specified by Technical Specifications. This case is described in the foll: wing saction, W350897HP 12

8.4.1 Mo n.i t o ry Waste Gas lloldup System Noble Gas Activity Monitor Tiige_ Re!pp i ejl_ by lechni c a l Speci f i c a t ions _t o Rest ore !!!'.e rab i l i t y; 30 days l'e riod o f I n op_e_ r a b i_1_i _t yj. 03/28/91 to 05/10/91 (43 days) Cause of luoperability: The Gaseous Waste Management (GWM) syntem effluent radiation monitor was declared out of service due to the inability of the samp}e }>tlNp to starl U}noll C omme n c i ll g a discharge, US a result of incorrect steps in procedure OP-007-003. Gperations declared the GWM radiation monitor out of service on March 28, 1091 at 0400. E!'a 5 P!Lf!P_e r a b i l i t y Not _ lje s t o red Wi t h i n. A l l ot t ei_J i me. l Operations department. initiated change !!8 t o procedure op-007-003 to correct the problem in the procedure. Due to the increased work load during Refueling Outage v4 (March 16, 1991 to May 27, 1991), the procedure change implementation was delayed. There was no need to perfcrm any additional Gas Decay Tank releases after April 1, 1991, therefore, the procedure ctange was not implemented within 30 days. Potential Reportable Event 91-027 documents this event. A functional test was satisfactorily completed and the GWM tadiation monitor was declared operable on May lb, 1991 at 0852. W35089711P 13

I f 8.5_ Activity Released via Secondary pathways i Secondary-release paths previously identified and discussed in-t previous semi-r.nnual' effluent release reports were continuouslyi { monitored for radicactivity. The areas monitored were: (1) the llot Machine Shop Exhaust (All-35), (2) Decontamination Shop Exhaust [ t ( All-34), (3) the RAB }!&V Equipment Room Ventilation System Exhaust I (E-41A and E-41B),-and (4) the Switchgear/ Cable Vault Area Ventilation System.(All-25). Continuous sampling for these areas is maintained in { order to demonstrate the operability of installed treatment systems - a and to verify the integrity of barriers separating primary and secondary i i

-ventilation systems.

Sampling for these areas was limited to ) continuous particulate and iodine sampling and. monthly grab noble gas sampling. The activity teleased via these secondary pathways resulted -} from routine operations and remained below significant levels ( $ 1% ) of annual Technical Specification liinits). No corrective actions are 1 -required. Release data will be it i4ded on the report t.o be' submitted -l within 60-days after January 1,-1992 for these aceas. l v 8.6-Additional-Information l t -f 8.611 Reactor Coolant System E-bar -{ t The most recent Reactor Coolant System E-fiar calculation l yielded results of 1.4649 MeV/ Disintegration-from a sample obt.ained on December 7,-1990. Reactor Coolant Syste.m E-Bar j is supplied for info -' Lion only and.is not used for effluent l dose calculations, l i 1 t ? I + I i W35089711P 14 f + , - -.~ - - -,. - -. ~.. - - ~ . - -. ~. - - - - -,.,,... ~... -, - .-,=,-n

i = 1 J 8- { 9.0 TABLES 1' Batch Release Summary 1A Semiannual Summation of all Releases by Quarter - All - Airborne - [ Effluents i I IB-Semiennual Airborne Continuous Elevated and Ground Level Releases IC- % miannual Airborne Batch Elevated and Ground Level Releases I 2A Semiannual Summation of All Releases by Quarter - All Liquid I Effluents 2 11. Semiannual Liqu d Sontinuous and 3atch Releases t t i 3-Solid Waste Shipped Offsite for Disposal 4 Not Used (Reserved for rteteorological Data) p I G.'O ATTACH? TENTS i-4 1 Changes to the Process Control Program t i W35089711P 15

~, .. ~ -- P r i TABLE 1 i (1 of 1) t i REPORT CATEGORY

BATCH RELEASE

SUMMARY

RELEASE P0lNT

ALL TYPE Or RELEASE
BATCH LIDJID AO GASEQUS PERIOD START TIME 0:00 HRS = 12:00AM JANUARY 1 4343:59 HRS =11:59PMJUNE3d,1991 PERIOD EM) TlHE 1991

( LIQUID RELEASES NUMBER OF RELEASES 115 TOTAL TIME FOR ALL RELEASES : 28894,0 MINUTES MAXIMUM TIME FOR A RELEASE : 315.0 MINUTES AVERAGE TIME FOR A RELEASE : 251.3 MINUTES NINIMUM TIME FOR A RELEASE : 113.0 MINUTES AVERAGE STREAM FLOW 649273.2 GPM GASEOUS RELEACES NLf18ER OF RELEASES 7 TOTAL TIME FOR ALL RELEASES : 3217.0 MINUTES MAXIMUM TIME FOR A RELEASE : 630.0 MINUTES AVERAGE TIME FOR A RELEASE : 458.6 MINUTES-MINIMUM TIME FOR A RELEASE : 202.0 MINUTES I I i l W350897]IP 16 l

TABLE 1A (1 of 1) REPORT CATEGORY

SEM1 ANNUAL S!JMMATION OF ALL RELEASES BY 094RTER TYPE OF ACTIVITY
ALL AIP90RNC EFFLUENTS REPORi!NG PERIOD
QUARTER t 1 AND OLM TER 4 2 UHli
00ARTER 1 :0UAPTER 2 :EST. TOTAL:
HOURS
HOURS
ERROR % :

TYPE OF EFFLUENT 1 2160 :2161-4344 : A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE
CURIES
2.12E 03 : 2.68E 01 : 1.50E 01:
2. AVERAGE RELEASE RATE FOR PERIOD :UCl/SEC
2.73E 02 : 3.41E 00 :
3. PERCENT OF APPLICABLE LIMIT N/A N/A B. RADIO!ODINES 1 TOTAL 100lHE-131
CURIES
1.53E-0) : 7.24E.04 : 1.50E 01:
2. AVERAGE RELEASE RATE r0R PER100 :UCl/SEC
1.97E-04 : 9.21E.05 :
3. PERCENT OF APPLICABLE Linii N/A N/A C. PARTIC'JLATES
1. PARTICULATES(HALF-LIVES)B DAYS) : CURIES
5.06E.05 : 9.88E-05 : 1.50E 01:
2. AVERAGE RELEASE RATE FOR PER100 :UCl/SEC
6.51E.06 : 1.26E-05 :
3. PERCENT OF ADPLICAGLE LIMIT N/A N/A
4. GROSS ALPHA FAD 10 ACTIVITY
CURIES
7.39E-Of : 3.94E-06 :

D. TRITIUM

2. AVERAGE RELEASE F< ATE FOR PER100 :UCl/SEC
3.18E 00 2.10E 00 :
3. PERCENT OF APPLICABLE LlHIT N/A N/A W3 0097HP 17

k TABLE IB -(1 of 1) i i REPORT CATEGORY

SEMIANNUAL AIR 90RNE CONTINU0US ELEVATED AND GR0'J4D
LEVEL RELEASES. TOTALS FOR EACH NUCLIDE RELEASED.

TYPE OF ACTIVITY

FISSION GASES, 100lNES AND PARTICULATES REPORTING PERIOD
QUAR 1ER41ANDQUARTE442 i

1

ELEVATED RELEASES : GROUND RELEASES :

i )

UNIT
0UARTER 1 :00ARTER 2 :00ARTER 1 :00ARTER 2 :
HOURS
HOURS
HOLRS
HOURS HUCLIDE 1 2160 :2161-4344 :

1-2160 :2161-4344 : + j FISS10N GASES f KR-85M

CURIES : 0.00E 01 0.00E.01 : 9.36E-01 : 0.00E-01 :

XE-131M

CURIES : 0.00E-01 : 0.00E-01 : 1.44E 01 : 0.00E-01 :

i XE.133M

CURIES : 0.00E.01 : 0,00E.01 : 1.67E 01 : 0,00E.01 :

XE.133

CURIES : 0.00E-01 : 0.00E.01 : 1.68E 03 : 2.47E 01 :

XE-135

CURIES : 0.00E.01 : 0.00E.01 : 1.24E 01 : 9.10E-01 :

AR-4;

CURIES : 0.00E.01 : 0.00E-01 : 8.6BE-01 : 0.00E-01 :

TOTAL FOR PERIOD

CURIES : 0.00E-01 : 0.00E-01 : 1.92E 03 : 2.56E 01 :

100lNES-i 1 131

CURIES : 0.00E-01 : 0.00E.01 : 1.53E-03 : 7.03E 04 :

l-133

CURIES : 0.00E.01 : 0,00E.01 : 3.42E-05 0.00E.01 :

TOTAL FOR PERIOD

CURlES : 0.00E.01 : 0.00E-01 : 1.57E-03 : 7.03E-04 :

i i PARTICULATES I H : CURIES : 0.00E.01 : 0.00E-01 : 2.42E 01 : 1.65E 01 : l CR-51

CURIES : 0.00E-01 : 0.00E.01 : 0,00E-01 : 0.95E.06 :

MN-54

CURIES : 0.00E-01 : 0.00E.01 : 0.00E-01 : 5.64E-07 :

i CO-50

CURlES : 0.00E.01 : 0.00E-01 : 2.24E-06 : 4.93E.05 :

i CD-60

CURIES : 0.00E-01 : 0.00E.01 2 0.00E-01 : 2.69E-06 :

i l ZR-95

CURIES : 0.00E-01 : 0.00E.01 : 0.00E-01 : 1.39E.06 :

1 l NB-95

CtWlES : 0.00E-01 : 0.00E-01 : 0.00E.01 : 3.96E-06 :

i RU-103

CURIES : 0.00E-01 : 0.00E.01 : 0.00E-01 : 6.90E-07 :

) l CS-134

CURIES : 0.00E-01 : 0.00E.01 : 1.35E.06 : 1.48E.06 :

) CS-137

CURIES : 0.00E.01 : 0.00E-01 : 2.15E-06 : 1.67E-06 :

G ALPHA

CURIES : 0.00E-01 0,00E.01 : 7.39E-06 :-3.84E-06 l

BR-02

CURIES : 0.00E-01 : 0.00E.01 : 4.49E 05 : 2.01E-05 :

1 TOTAL FOR PER100

CURIES : 0.00E-01 : 0.00E-01 : 2,42E 01 : 1.65E 01 :

l ? I l I i i t i 4 W35089710P 18

TABLE IC (1 of 1) REPORT CATEGORY

SEMIANNLAL AIR 90R4E BATCH ELEVATED AND GROUND
LEVEL PELEASES. TOTALS FOR EACH NU(llDE RELEASED.

TYPE OF ACTIUlTY

FISSION GASES, 10 DINES AND PARTICtLA1ES REPORTlHG PERl00
QUARTERI1ANDDUARTE442
ELEVATED RELEASES : GROUND RELEASES :
(NIT
00ARTER 1 :0UARTER 2 :0UARTER 1 :0UARTER 2 :
HOURS
HOURS IHJURS
HOURS NUCLIDE 1-2160 :2161 4344 :

1-2160 :2161-4344 : FISSION GASE9 FR-85M

CURIES : 0.00E.01 : 0.00E-01 : 2.45E-01 : 0.00E-01 :

VR-05

CURIES : 0.00E-01 : 0.00E-01 : 3.32E-01 : 0.00E-01 :

KR.87

CUPIES : 0.00E-01 : 0.00E-01 : 1.2BE-01 : 0.00E-01 :

KR.88

CURIES : 0.00E-01 : 0.00E 01 : 1.82E-01 : 0.00E-01 :

XE-131M

CURIES : 0.00E-01 : 0.00E-01 : 2.52E 00 : 0.00E-01 :

XE.133M

CURIES : 0.00E-01 : 0.00E-01 : 1.76E 00 : 0.00E-01 :

XE-133

CURIES : 0.00E-01 : 0.00E-01 : 1.03E 02 : 1.15E 00 :

XE-135M

CURIES : 0.00E.01 : 0.00F 01 : 4.11E-01 : 0.00E-01 :

XE-135

CURIES : 0.00E-01 : 0.00E-01 : 3.81E 00 0.00E-01 :

AR.41

CURlES : 0.00E-01 : 0.00E-01 : 5.96E.01 0.00E-01 :

TOTAL FOR PERIOD

CURIES t 0.00E-01 : 0.00E-01 : 1.93E 02 : 1.15E 00 :

10 DINES 1-131

CURIES : 0.00E-01 : 0,00E-01 : 0.00E-01 : 2.13E-05 :

PARTICULATES H. )

CUPIES 0.00E-01 : 0.00E-01 : 4.73E-01 : 6.07E-03 :

CO-58

CURIES : 0.00E-01 : 0.00E-01 : 0.00E.01 : 3.93E 00 :

i TOTAL FOR PER100

CURIES : 0.00E-01 : 0.00E 01 : 4.73C 01 : 6.09E-03 :

l l W350597HP 19

l l TABII 2A l (1 of 1) REPORT CATEGORY

SEMIAWJAL SUMhATION OF ALL RELEASES BY QUARTER TYPE OF ACTlulTY
ALL L10VID EFFLUENTS REPORTING PERIOD
QUARTER 4 1 AND QUARTER 4 2 UHli
0UARTER 1 :QU$ TER 2 :EST. TOTAL:
tt]URS
HOURS
ERROR %

TYPE OF EFTLUENT 1-2160 :2161-4344 : A. FISSION AND ACTIVAT10H PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)
CURIES
1.3BE-01 : 5.93E-01 : 1.50E 01:
2. AVERAGE DILUTED CONCENTRATIDH DURING PERIOD
UCl/ML
3.67E.09 : 1.78E.08 :
3. PERCENT OF APPLICABLE LlHIT 4

N/A N/A B. TRITIUM

1. TOTAL RELEASE
CURIES
1.28E 02 3.47E 01 : 1,50E 01:
2. AVERAGE DlLUTED CONCENTRATION DURING PERIOD
UC1/ML
3.40E.06 : 1.04E.06 :
3. PERCENT OF APPLICABLE LIMIT 4

N/A N/A C. DISSDLVED AND ENTRAINED GASES 1, TOTAL PELEASE

CURIES
1.32E 01 : 5.23E.02 : 1.50E 01:
2. AVERAGE DILUTED CONCENTRATIDN DURING PERIOD
UC1/ML

, 3.51E-07 : 1.57E-09 :

3. PERCENT OF APPLICABLE LIMIT N/A N/A D. GROSS ALPHA RADIDACTIVITY
1. TOTAL RELEASE
CURIES
2.16E.06 0.00E-01 : 1.50E 01:

E. WASTE VOL RELEASED (PRE-DILUTION) : GAL

7.07E 05 : 9.22E 05 1.50E 01:

F. VOLUME OF DlLUTIDN UATER USED

GAL
0.96E 09 8.80E 09 1.50E 01:

1 W35089711P 20

t i TABLE 2B (1 of 2) REPORT CATEGORY

SEMIAN4JAL LIQUID CONilRJOUS AND BATCH RELEASES
TOTALS FOR EACH HJCL10E RELEASED.

TYPE OF ACTIVITY

ALL RADIONUCLIDES REPOR11NG PERIOD
QUARTER 4 1 AND QUARTER 4 2
CONTlHUQUS RELEASES :

BATCH RELEASES : t UHli

00ARTER 1 :0UARTER 2 :OlJARTER 1 :00ARTER 2 :
HOURS
H0lRS
HOURS
HOURS NUCLIDE 1-2160 :2161-4344 :

1-2160 :2161-4344 : ALL NUCLIDES H-3

CURIES : 2.48E-04 : 1.35E-03 : 1.20E 02 : 3.47E 01 :

NA-24

CURIES : 0.00E-01 : 0.00E-01 : 3.H E-05 : 7.05E-04 :

CR-51

CWIES : 0.00E-01 : 0.00E-01 : 5.33E-03 : 4.36E-02 :

lH-54

CURIES : 0.00E-01 : 0.00E-01 : 8.5BE.04 : 6.58E-03 :

FE-%

CURIES : 0.00E-01 : 0.00E-01 : 1.25E-02 : 1.69E-02 :

FE.59

CURIES : 0.00E-01 : 0.00E-01 : 1.02E-03 3.44E-03 :

C0-58

CURlES : 0.00E.01 : 7.92E-05 : 4.95E-02 : 1.77E-01 :

CD-60

CURIES : 0.00E-01 : 0.00E-01 : 7.00E-03 : 3.10E-02 :

SR-89

CURIES : 0.00E-01 : 0.00E-01 : 9.20E-05 : 1.97E-04 :

SR-92

CURIES : 0.00E-01 : 0.00E-01 : 9.09E-05 : 2.31E-04 :

ZR-95

CURIES : 0.00E-01 : 0.00E-01 : 1.03E-03 : 1.40E-02 :

2R-97

CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.51E-04 :

HB-95

CURIES : 0.00E-01 : 0.00E.01 : 1.76E-03 : 2.34E-02 :

MD-99

CURIES : 0.00E-01 : 0.00E-01 : 1.9BE-03 : 0.00E-01 :

TC-99M

CURIES : 0.00E-01 : 0.00E-01 : 3.43E-04 : 1.32E-05 :

RU-10)

CURIES : 0.00E-01 : 0.00E-01 : 2.95E.04 : 8.18E-04 :

RU-106

CURIES : 0.00E-01 : 0.00E-01 : 6.20E.04 : 7.02E-04 :

AG-110M

CURIES : 0.00E-01 : 0.00E-01 : 4.73E-04 : 6.02E-03 :

TE-132

CURlES : 0.00E-01 : 0.00E-01 4.30E-03 : 6.5BE.04 :

1-131

CURIES : 1.04E.05 : 7.76E-06 : 5.06E.03 : 9.35E-03 :

1-132

CURIE 5 : 0.00E-01 : 0.00E-01 : 7.7BE-03 : 1.16E-03 :

1-133

CURIES : 0.00E-01 : 0.00E-01 : 1.01E-04 : 0.00E-01 :

CS-134

CURIES : 0.00E.01 : 1.77E-05 : 9.92E-03 : 4.37E-02 :

CS-136

CUP!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.66E-03 :

CS-137 CURIES : 0.00E-01 : 3.3BE.05 : 1.63E-02 : 5.27E-02 : BA-139

CURIES : 0.00E-01 : 0.00E.01 : 4.2BE.03 : 0.00E-01 :

BA-140

CURIES. 0.00E-01 : 0.00E-01 : 1.2SE-04 : 0.00E-01 :

LA-140

CURIES : 0.00E-01 : 0.00E.01 : 2.15E-03 : 1.39E-03 :

W350897HP 21

TABLE 2B l (2 of 2) 1 1 REPORT CATEGORY f SEM14WL L10VID CONTit00US AND BATCH RELEASES 1 10TALS FOR EACH NUCLIDE RELEASED. TYPE OF ACTIVITY

ALL RAD 10HlEL10ES REPORilNG PERIOD
QUARTER 6 1 AND M RTER I 2
  • CON 11NUQUS RELEASES :

BATCH RELEASES : UHli

00ARTER 1 :0UARTER 2 200ARTER 1 10UARTER 2 :
HOURS
HOURS
HOURS
HOURS NUCLIDE 1 2160 :2161-4344 :

1 2160 :2161-4344 : ALL NUCLl0ES CONTlHUED CE-141

CURIES : 0.00E-01 : 0.00E-01 : 5.66E-05 : 1.BBE-04 :

CE-144

CURIES : 0.00E-01 : 0.00E-01 : 0.0eE-01 : 1.16E-03 :

W-187

CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-O! : 4.21E-04 :

KR-05

CURIES : 0.00E-01 : 0.00E-01 1 3.75E-02 : 1.38E-03 :

XE-132M

CURIES : 0.00E-01 : 0.00E-01 : 1.0$E-01 : 1.06E-02 :

XE-133M CURLES : 0.00E-01 : 0.00E-01 : 7.42E-02 : 0.00E-01 : XE-133

CUR lES : 0.00E-01 : 0.00E-01 : 1.30E 01 : 4.00E-02 :

XE-135

CURlES : 0,00E-01 : 0.00E.01 : 4,51E-03 2 3.33E-04 :

AR-41

CURIES : 0.00E-01 : 0.00E-01 9.26E-05 : 1.22E-05 :

SR-90

CURIES : 0.00E.01 : 0.00E-01 : 1.17E-05 : 2.71E-05 :

G ALPHA

CURIES : 0.00E-01 : 0.00E-01 : 2.16E-06 : 0.00E-01 :

C0-57

CURIES : 0.00E-01 : 0.00E-01 : 4.56E-05 : 6.33E-04 :

58-124

CURIES : 0,00E-01 : 0.00E-01 : 3.39E-04 : 2.38E-02 :

SN-113

CLRIES : 0.00E-01 : 0.00E-01 3.85E-04 : 3.62E-03 :

NB-97

CURIES : 0.00E-01 : 0.00E-01 : 7.12E-04 : 1.58E-03 :

SB-122

CURIES : 0.00E-01 : 0.00E-01 : 2.46E-05 2.31E-04 :

58-125

CURIES : 0.00E-01 : 0.00E-01 1 3.06E-03 : 1.26E-01 :

SB-126

CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.82E-04 TOTAL FOR PERIOD
CURIES : 2.50E-04 : 1.49E-03 : 1.42E 02 3.53E 01 :

.... = =................................................................... W350897HP 22

TABLE 3 (1 of 8) SOLID WASTE SHIPPED 01T31TE FOR DISPOSAL DURING PERIOD 1/1/91 THRU 6/30/91 WASTE CONTAINER VASTE TOTAL TYPE VOLUrlE (ft3) VOLUtlE (m ) ACTIVITY (Ci) ERROR 3

  • Non Compacted Dry 1040 647.89 1.32E+0 kl 125%

Active Waste Shipped to Scientific Ecology Group for volume 11.36 ceduction Burial Volume

  • Non Compacted Dry 1040 176.6 1.33E-1 kl 125%

Active Waste Shipped to Allied Technologies Group for Volume Reduction Waste volumes shipped for volume reduction do not reflect final burial waste volumes, unless stated.

  • 1 Activity determined by estimations.
  • 2 Activity determined by measurements.

W350897HP 23 --.___________-_____--_____u

-.._..____._..._m_ TABLE 3 (2 of.8) SOLID WASTE SHIPPED OITSITE FOR DISPOSAL DURING PERIOD 6/1/91 THRU 6/30/91 WnSTE_ CONTAINER WASTE TOTAL 3 a TY"E VOLUME (ft ) VOLUME (m ) ACTIVITY (Ci) ERROR I _j [ Resin Waste 158.1 4.47 1.87E+2

  • 2 125%

Management Dewatered 120.3 3.40 5.34E+1

  • 2 i25%

Resin in a High i Integrity Container Liquid Waste 181.7 5.14 4.93E+0

  • 2 125%

Management Dewatered Resin-in a Carbon Steel Liner l-Waste volumes shipped for volume reduction do not reflect final burial-waste volumes, unless stated. l

  • 1

. Activity determined by estimations.

  • 2 Activity determined by measurements.

W350897HP 24

TAltLE 3 (3 of 8) SOLID WASTE SillPPED OITSITE FOR DISPOSAL DURING PERIOD 1/1/91 TllRU 6/30/91 WASTE CONTAINER WASTE TOTAL 3 TYPE VOLUML (ft3) VOLUrlE (m ) ACTIVITY (Ci) ERROR

  • Mechanical Filters 100.1 2.05 8.63E+1
  • 2 125%

Dewatered Shipped to Allied Technologies Group Waste volumes shipped for volume reduction do not reflect final burial waste volumes, unless stated.

  • 1 Activity determined by estimations.
  • 2 Activity determined by measurements.

I W35089711P 25

TABLE 3 (4 of 8) SOLID W/.STE SilIPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/91 THRU 6/30/91 WASTE TYPE NUCLIDE NAME % ABUNDANCE CURIES Non Compacted Mn-54 2.74 9.53E-4 Dry Active Waste Fe-55 33.63 1.17E-2 Shipped to Scientific Co-58 9.37 3.26E-3 Ecology Group for C -60 8.76 5.05E-3 Volume Reduction Ni-03 14.79 5.14E-3 Cs-134 11.12 3.87E-3 Cs-137 19.40 6.74E-3 Non-Compacted Mn-54 3.96 5.63E-7 Dry Active Waste Fe-55 6.41 9.11E-7 Shipped to Scientific Co-58 34.59 4.91E-6 Ecology Group for Co-60 5.09 7.23E-7 Volume Reduction Ni-63 2.05 2.91E-7 CS-134 11.98 1.70E-6 Cs-137 18.40 2.62E-6 Ce-144 16.59 2.3bE-6 l I W35089711P 26 s

TABLE 3 (5 of 8) SOLID WASTE SillPPED OFFSITE I'OR DISPOSAL DURING PERIOD 1/1/91 THRU 6/30/91 WASTE TYPE NUCLIDE NAME % ABUNDANCE CURIES Non Compacted Mn-54 4.42 4.41E-2 Dry Active Waste Fe-55 18.69 1.86E-1 Shipped to Scientific Co-58 38.32 3.83E-1 Ecology Group for Co-60 5.72 5.71E-2 Volume Reduction Ni-63 8.05 8.49E-2 Cs-134 9.21 9.20E-2 Cs-137 14.47 1.44E-1 l -: l' Non-Compacted Mn-54 4.42 1.47E-2 Dry _ Active Waste-Fe-55 18.69 6.24E-2 Shipped to Allied Co-58 38.32 1.27E-1 f Technologies Group for Co-60 5.72 1.91E-2 Volume Reduction Ni-63 8.05 2.68E-2 CS-134 9.21 3.07E-2 Cs-137 14.47 4.83E-2 l l W3508971[P 27 1

TABLE 3 (6 of 8) SOLID WASTE SillPPED OFFSITE FOR DISPOSAL DURING PERIOD 1/1/91 TllRU 6/30/91 WASTE TYPE NUCLIDE NAME t AEUNDANCE CURIES Resin Waste Mn-54 2.16 4.03E+0 Management Resin Fe-55 3.40 6.35E+0 Dewaterd in a Co-58 33.30 6.22E+1 liigh Intergrity Co-60 4.37 8.17E+0 Container Ni-63 17.00 3.17E+1 Cs-134 14.00 2.61E+1 Cs-137 25.20 4.71E+1 Resin Waste Mn-54 2.16 1.15E+0 Management Resin Fe-55 3.40 1.81E+0 Dewatered in a Co-58 33.30 1.77E+1 High Integrity Co-60 4.37 2.33E+0 Container Ni-63 17.00 9.07E+0 CS-134 14.00 7.47E+0 Cs-137 25.20 1.34E+1 W35089711P 28

I t TABLE 3 l r (7 of 8) l l SOLID WASTE SillPPED OFFSITE FOR DISPOSAL' .f DURING PERIOD 1/1/91 TIIRU 6/30/91 i i f WASTE TYPE NUCLIDE NAME % ABUNDANCE CURIES 4 r Liquid Waste Mn-54 5.29 2.60E-1 Management Resin Fe-55 8.60 4.23E-1 I Dewaterd in a-Co-58 46.20 2.27E+0 Carbon Steel Liner Co-60 6.80 3.35E-1 Ni-63 2.74 1.35E-1 Cs-134 11.30 5.57E-1 Cs-137 17.40 8,57E-1 Mechanical Filters Mn-54 5.29 4.56E+0 Dewatered and Sent-Fe-55 8.60 7.42E+0 to Allied Technologies Co-58 46 20 3.98E+1 Group Co-60 6.80 5.86E+0-Ni-63 2.74 2.36E+0 CS-134 11.30 9.75E+0 Cs-137 17.40-1.50E+1 .W350897HP 29

4 i TABLE 3 l (8 of 8) l' i SOLID WASTE SillPPED OFFSITE FOR DISPOSAL j; DURING. PERIOD 6/1/91 THRU.6/30/91 4 i' r i f _ NUMBER OF SilIPMENTS-MODE OF TRANSPORTATION DESTINATION I -- 16 TPUCK 9-Oak Ridge, TN j 3-Barnwell, SC j 4-Richland, WA WASTE.

  1. OF TVPE OF CLASS SHIPMENTS TYPE CONTAINER

' MODE DESTINATION A 13 LSA Strong-tight Truck 9-Oak Ridge, TN LSA Strong-tight Truck 2-Richland, WA Type A Carbon Steel Liner Truck 1-Barnwell, SC LSA Carbon Steel I.iner-Truck 1-Richland, WA B__ 2 Type A Poly-HIC Truck 2-Barnwell, SC Limited 1-Limited Strong-tight-Truck 1-Richland, WA Quantity Quantity W35089711P - 30

TABII 4-(1 of-1) NOT USED (Reserved for Meterological Data) y r-t W3508971[P 31

. _ _...- _ _.... _. _.. _. _. _ _.. _., _. - _ _. _ ~... _. _ _.. _. _. ~.. - _ _ _ ATTACilMENT-1 (104 pages) h i Changes to the Process Control Program - W3508971[P - 32

i l This attacitment contains changes to the Process Control Program which were not' addressed in previous Semi-annual Radioactive Release Reports. Copies of the Process Control Program procedures af fected-by the changes are included in this attachment. Below is a listing of changes to the Process Control Program by date: April 29, 1985 Deleted non-applicable vendor procedures April 27, 1987 Changed vendor-for easte processing from NUS Process Services to LN Technologics Corporation October 13, 1987 Included Aquaset and Petroset media for solidification. Added reference _ to vendor procedures. March 29, 1989 Deleted vendor procedures that are not currently being used to process radioactive wastes at Waterford 3. Deleted Corporate QA Manager responsibilities. Added core samples for determining waste class. a b l l W350897HP 33 i _. I I z.- --- - ~

3 WATERFORD 3 SES PLANT OPERATING MANUAL E POWER & LIGHT LOUlBIANA NNkeidU POM VOLLME 20 RW-1-210 REVISION 0 POM SECTION i LP&(. W-3 RECORDS UNCONT RO'_ LED COPY DO NOT USE 44 ANY SAFETY-kELATED TESTING, MAIPTENANCE, OR OPERAT Or6AL ACTIVITY ' M in ADMINISTRATIVE PROCEDURE PROCESS CONTROL PROGRMt . O ~ . O PORC Heating 50.. # T*//i i Reviewed: M[2 PORC (2>airasa Approved: i Plant Managar-Wuclear . Approval Date Effective Date i

v IETIIB CCITE1 EII2:2 (Change 1) N C72 RW*l-210 - Process Cont rol Program (Rev.0) PCRC IIv!IV no FCIC has rettsved this 1tas and datarzined that a safety evaluation was peric1Haed (as applicable), that an unrevised saf ary questian dess not exist (as syylicable), that a chsaga to the T*"1 Specifications is not required, sad that unr1==v saf ecy is/vss not advarsely aff ected. CI:3Z1 'N 07 ,FCRC EIZECL PC1C EE%IE1 _TCR ATFICTAL DA:Z ggt:32 SI 3AT:3t1 TT.S I to ///7 1 rin ant N_ f 1 .. rams v Superintendent (f [ (t)j9[9 s d st1an trotaction J I l ,trintaakant "R / Ufl4 SY EY M Y-f /J,$9lt*y L' g Tashais 21 Sayyert Superissandest f" AssistastFlasK f ye arer NEO ea i o - __ '_ f fY m Itaus 54.' / Datas V/- / - F V _ FC1C Eastlag No. / / m nie itas is redad far syprovsit @ TER O so This itas requires $2C/EIO revi m prist to impi b etsst O tz: Q so ~ ~ o 12 yss, ensure doctmentactos supporting review is artached. This itas requires QA revim prior to implaasst.asiast O ris E =o-CA tr?!IV taviewed by 2A:1 Carycrata QA nanagar PLUT MAFACTI-M.IA1 AFYROVAL (REFER 7"O EV.M 6, g) Cosansats: NA n$ IN DATE N f 9 84 / Apperved by Plant Mangst-duclear t*rl-1-0:3, Revt:1:n 5.1 (1 of 1)

VATIETOR'D 3 SES PLANT OPIRAT3G EANUAL Chack B e sato. CHANGE /RIVISION/DEIITION REQUIST I,~42 l lPORC-S/C b c ess C o d rol b_~e4rn m Procedars No, Etd-l.210 Titis k Effective Data (if different from approval data) Cowpleta A. B. and C l A. Change No. 1 D}lParmanent l~lDeviation Expiration Data B. Revision No. O C. Deletion l,'1 YIS %)NO DESCRIPTION OF CHAK2 OR RIVISION b ro]Cr. +o nne.Nt (d ie nt et en ce, in re e retkr Seekiod, aan Anette% 0;dornoec r e Ce retue 'm S, A d d S A I. I l- 'n RIASON FOR CIANat. EIVISIQW. OR MTYTION bhadee Yu Dnnra d e enl e r eors 'i d re he_ce.0c_t s eed 60 .n as t% ce A '* 4 <> <ecer re h reoce.'a S. A,a s. st. il. i 6 m ~~ REQUIRID SIGNATURIS ~ CRIGIIAICR 2 An. n DATE ///QfR(/ sATtTT EE7 u v g l c Does this change, revision, or deletion: 1. Change the facility as described in the T5 ART T13 50 X 2. Changs the procedures as described in the T5 arf YE3 _ 50 X 3. Conduct tests /supertasata not described in the TSART TIS N0 1 4. Raquire a change to the Technical Specifications? TIS 50 Y If the answer to any of the above is res, complete and attach a 10CTR50.59 Safe Evaluationg ) j j SATITT hm ruhm DATE /1/ / Q / 27Y TEGNICAL RIVIIW NA 94 DATE //'/ef/O GROUP EEAD EIVIIV 604- - *# DATE

  1. //1[tV TIMPORARY APPROVAL * ($R0)

DATE TIMPCRARY APPROVAL

  • DAIX
  • Temporary approval must be followed by Plant Manager /APB N - Nuclear approval within 14 days.

CNT-1-003 Revision 8 63 _.7 (1 of 1) 1

b I RIVIEW Cain SErtT IN-1-210 - Process Cont rol Program (Rev. 0) RIVIEW CP: l PORC PIVT W The PCRC has reviewed this iten and deter:ined that a safety evaluation was perforced (as applicatie), that an unreviewed safety questien does not exist (as applicable), that a change to the Technical Specifications is not required, and that nuclear safety is/vas not adversely affected, j CRDER RICot003DD j CT PORC V.IMBER PCR0 EER FOR A.PPROVAL DATI F.IVIW SIGNATG I YES l ho u i dent //-8'd [ l Operations

  1. -I M l

Superintendent ,) W O % } ,/ F.aciation Protection l Superintecdent geg n[fkf I Plact Quality 'ff[$ Md */ u l l T Manager [ je, g / i to Tenh.ical Suppert i e 4, 3 Superintandent +v c l Assistant Plant / / l .f !h g I h esser I g /hk,[h % w W I lfl3s) I;EC Ch* * ** m i ?:RC Meeting No. fr4f-//7 lten No. 4/ Dater //- &-W l j & ~his ite: is recc= ended f or approva17 Yt5 ONO l g l'-f f y ( This ite: requires 4Ref!"AC review prict to 1:ple:entatient h TIS O wo ( jO if yes, ensure docu entati:n supporting reviev is attached. l i This itt: requires QA review prior to imple:entation? O Yts a so l CA FIVIW i I

  • > l Reviewed by 14 / A DATE 14 / ft l

l l Corporate QA' hanager i i f P!.JLNT WJSACEF 'CT!. EAR APPPOVAI. (REFER. 70 E 4'./2./) l i 4*f [ j Cementas p l i f Approved by 4 /A DATE 14 /h. Plant r.an'gd f-:iu cle a r l I 15 1 l n*T-1-004, Revision 5.1 (1 cf 1)

h WATERTORD 3 St.S PIAWT OPERATING MANUAL Check Block Below , NEW PROCEDURE REQUEST @PON l~lPORC S/C PROCEDURENO.M-lgoRIV .O PROCEDURE TIPE StL m !n s krk b ee. TITLEirvee;A (64cr4 Eciv, eam ETTECTIVE DATE (IT APPLICARLE) ALTTHOR _ L. R. 8 Im oQ EIPIRATION DATE (IT APPLICABM ) DESCRIPTIONOTPROCEDUREM,cceiks m eh e A nba b be u ed in deoebnior LliiCac4ina Ao.ad 'riod ion vih d e Alo M thit nJJiod imMewedhide O Dn c_ ed u_r eA i l \\ REASON FOR PROCEDURE 9pw.iic, O Or Ok l n't c oc e 'b M v \\n o AITTHORIZED BT dhb/M DATE " 4 4 4 SATET7 REVIEW El'A' "*8' " ""*l**' N Does this procedure: Assist Plant Manager-Nuclest(PORC-5/C) 0 1. Change the fact'ity as described in the TSART TIS , N0 t/ 2. Change the procedures as described in the TSAR 7 YES 50 o-3. Conduct tests /experiaants not described in the TSART TES NO / 4 Require a change to the Technical Specifications? TIS NO / g If say question 1 through 4 has been answered YES, complete and attach a 10CIlt50.59 SAIITT EVALUATION. f a SATETT REVII n 11 reAn (Mhs /// / 7 ~ Sigiaturei Kathor i Data TECHNICAL REVIEW A-d_.- fM ~ Signature, TeNiical Reviewer - ' Date (b1di nNw CRn wDum, Signatur6 Group Kalid Data Applicable Conditians (Temporary Procedures only): UNT 1-003 Revision 8.6 (1 of 1) 4J. s m

d. 7,y: n, . ra v Administrative Procedure RW-1 210 Revision 0 Process control Program TABLE OF CONTINTS 1.0 PURPOSE 2.0 RETERU CES 3.0 DETINITIONS 4.0 RESPONS15ILITIES T 5.0 PROCEDURE v 5.1 Proarsa Description 5.2 Solidification Process Parassters tn 5.3 Administra;ive Controls 5.4 Weste Character 1:stion and Classifiestino 5.5 Quality Assurance C. 6.0 ATTACIDGXTS LIST OF ETPECTIVE PhCE5 Title 1svision 0 1-11 Eevision 0 0 h.dy. & I, 3, I o Cw.ge 4. gg tt-gi 44 1

Administrative Frocedure Process Control Program RW-t-210 Revision 0 1.0 PURPOSE 1.1 The purpose of Waterford Steam Electri (Waterford 3) Process Control c Station - Unit Number 3 program which provides reasonable assuraProgram (PCP) is to describe the ation of various radioactive " vet vast nce of the couplete solidift-and evaporator bottoms are accordance es" including resin slurries Transportation (DOT). Nuclear Regulat with applicable Departaent of Itcensed burial facilities acceptance c iory Commission (KRC), Stats and shipment to an approved burial siter teria for packaging and m will be achieved through teplementation ofCompliance with these criteria 9 Waterford 3 and vendor supplied prothe PCP and related 10 cedures. 2.0 MRFRCES \\ i 2.1 Waterford 3 Documents n 2.1.1 FSAR Chapter 16, Technical Specificati O' on 3/4 11.3 2.1. 2 FSAR Chapter 16. Technical Specificati ca 6 13.2 2.1. 3 PSAR Chapter 11.4, Solid Weste Mana gement System 2.1.4 PSAF. Chapter 13.4, Review and Audit 2.1.5 PSAR Chapter 13.2. Training 2.1.6 FSAR Chapter 13.5, Plant Procedures 2.1.7 Nuclear Operations Quality Assuranc /5 Chapter 6 a Manual, Section 2, 2 V. * ,w

Administrative Procedure RW-1-210 Process Control Program Esvistoa 0 i VendorCor[ troll,'dDocuments 2.2 chgqa i l*$.$3*O378 e 2.2.1 i>;.>0;7;. NUS Process Services Corporation, Topical Report 801 on Radvaste Solidification Systes, Rev. O Il l% Bi 2.2.2 TR002. NUS Process Services Corporation. Topical Report on 10CTR61 Qualified Radioactive Veste Forms May 1984 2.2.3 4313-01354-OlP Chem-Wuclear Systess Inc.. Topical Report on Mobile Cement solidification Systes, Rev. 2 4 CNSI-VFg-0J-NP,10CPR61. Waste Form Certification-Coment. 2.2.4 y Chen-#eodoor Systes Inc., November 30, leg 3 gg,gg,q cust bW.salis-ci P e

  • y C"1 2.2.5 C:::: ::: '::'0 ^: ?, Chen-nucisar system, Inc., Devatorins Topical. December 23, 1983 gg. 6 64 t")

1 2.2.6 RN-R1109, Westinghouse Rittaan Wuclear, Inc., Topical Report on 54dveste Solidification System (Cament), Rev. 4 p 2.2.7 STD-E-05-005, Westinghouss Rittman Nuclear, Inc., Topical Report on Cement Eolidified Wastes to Meet the Stability Requirsments of 10CT161. Esv. 0 2.2.8 STD-A-03-008, Westinghouse Rittman Weelser, Inc., Topical Report for Rittman RADLCE Righ 1stegrity Containers, tav. 0 2.2.9 F1-013. Process Control Program for Dewstering Liner with EUS PSC Internals, NUS Procese Services Corp. 2.2.10 STD-P-05-003, Hittatu Wyclear Development Corp., Process Control Program for lacontainar Solidification of 10 of 14 Weight Percent Boric Acid, Rev. 1 3

g. .___.w _ _ _.. ~... _ _., _. _. ~, _. _. _ _ _ _ _.. _ Administistive Freesduro gW-1-210 Process Control Prt'stsa R*violon 0 4 2.2.!! '7-P-05-004, Hittman Nuclear Development Corp., Process Control Prcgram for Incontainer Solidification of Bead Resin, Rey. I 2.2.12 Hittaan Nuclear Development Corp., gTD-P-03-005, Rittman Nuclear Development Corp., Devotering Hittman Radlock Cont iners with Plexible Underdrains to Lees D en 11 Drainable Liquid, Rev. 2 2.2.13 57V-P-04-002, Dewstering ten Exchange Resin and Activated N Charcoal P11ter Media to 0.52

  • T 2.2.14 WHG 102.*P-A, Waste Man &g-eer:t Group, RADMAN Tropical Report g

2.3 Other Documento O 2.3.1 10CPR61, Licensing Requirements for Land Disposal of 34dio-ective Weste CP 2.?.2 - 10CPE20.3tl, Transf er for disposal and manif este C

2. 3. 3 10CPR71.91, Records 3.0 DrrtNITION NOKE 4.0 RESPONSIBILITIES l

4.1 Plant Manager-Nuclear 4.1.1 The Plant Manager-Wuclear has ov&rall administvative control responsibilittee for the Process Control Program at Waterford-3. He la responsible for ensuring the following: 4

_A i e + Adstnistrative Procedute EV-1-210 Process Control Progras Revtalon 0 4.1.1.1 The pterstation teview and approval of the Procese Control Program procedures pertaining to the procese. Ing and packaging, of radioactive seteriale, and for the operation and pointenance of redweste systemet 4.1.1.2 'that plant pereotinel adhere to the procedural requite-mente of thle prograel 4.1.1.1 That plant interdepartmental responsibilttles effect-ing the Procese control Program are clearly established 03 and sceosplished; v 4.1 1.4 That perernnel receive appropriate training and are to qualtfled for their respective dutteet g 4.1.1.5 Procurement of materiste end supplies required for toplementation and maintenance of the Procese Control Program: tb 4.1.1.6 w oration and maintenance of radveste systessi O 6.1.1.7 Inspection of Radweste activities; and 4.1.1.8 Adequate staffing and sufficient resources for efftetent and economic operation of the Process Control Prostaa. 4.2 Eadiation Protection Superintendent 4.2.1 The Radietton Protection Superintandant to responsible for the overall effective aansgement of the plant Process Control Program. The Radiation Protection Superintendent ensures that changes are inittsted to The Process Control Program procedures when necesasty and that appropriate Itealth rhysico support to provided. 5

t Adatuistrative Procedure RW-l-210 Precess Control Program Revision 0 4.3 Plant Redwaste Entir.ser-Nuclest 4.3.1 The Plant Radweste Fngineet who reports to the Radiation Pretection Superintendent holde key responsibilitter for implementation of the Process Centrol Progree such as 4.3.1.1 Data collection, trend analysis, long-ters planning, and problea solving for the plant Process Centrol Prograal m 4.3.1.2 Meneging radwoote solidification, dewatering and y packaging; tn

4. 3.1. 3 Preparitig procedures for solidification. dewatering and packaging; n
4. 3.1. 4 Interfacing with other groups se necesesty to enalyse and resolve problems relating to the Process Control e

program such as the design of Radvaste Systeem and Equipment O 4.3.1.5 Preparing periodic reports summarising the Process Control Program. 4.4 Operations Superintendent 4.4.1 The Operatione Superintendent is responsible for the effective operations of perv.anent plant radweste systees and will coordinate raivast: activities with the radvaste department. y 6

.. - - - ~,. ~,, -. g_..- Ad31nistrative Procedure tv.1-210 Frocess Cent rol Program R3 vision 0 4.5 Cheristry Engineer-Nuclear 4.5.1 The Chemistry Engineer-Nuclear is responsible for interfacing with the Redweste Ingf neer on items or problems relating to radweste processes and chemistry controle or chemical reactions and performing cheetcal and radiocheetcal analyses of easples of radioactive waste or materiale. 4.6 Plant Quality Manager O 4.6.1 The Plant Quality Manager is responsible for the review of i in plant Process Control Progree procedures to ensure QA Frostem in requirements are taplemented and for the performance of activity surveillance. C 4.7 Nuclear Services Haneger e i ) ~ 4.7.1 The Nuclear Services Manager is responsible for providing the (b following services 4.7.1.1 State-of-the-art technical advies, support, and g assistance as required: 4.7.1.2 Licensing and regulatory compliance supporti and 4.7.1.3 Appraising the Waterford=3 Process Control Progras and recommending improvements. 4.7.2 The Nuclear Services staff interfacee directly with the plant staff in providing these services. I 7

Moinlettative Procedure gW.I.210 process control Progras Itovieton 0 4.8 Corporate Quality Assurance Manager 4.8.1 The Corporate Quality Assurance Manager is responalble for assemains the itplesientatten and ef f ectiveness of the gustity assurance aspects of the Process Control Program through regular audits and selective monitoring of setivities. 5.0 l'ImcrDt'R F. 5.1 Program Descriptinn in 5.1.1 golidification System Descriptions Vaterf ord 3 utilites vendor supplied pottable solidification th equipment for radioactive veste solidification. References o 2.2.1 through 2.2.13 provide a general description of respec-tive vender solidification processes and process control r3 featuress Reference 2.2.16 describes the method which will be utt11:ed to cloself y vestes in accordance with 10CF1613 and ~ ? Ref erence 2.1.1 thtough 2.l.7 are Waterf ord 3 documente which either taplement or describe activities which provide reason-able eseurance that vestes are solidified or devatored to o accordance with all appitcable reguistione and critetta. 5.1.2 Bources of Vaterford 3 Solidi!! cation feeds: The solidification systen vill be used to process resino, evaporator bottoms and boric acid concentrates. Durtrig resta solidification, vendor equipment will be connected to both the Resin Waste Management Systee outlet and devoterlag inlet to allow for the transfer of teein and the devotering of the liner. Vendor equipment will be connected to the Solid weste Management System outlet when evaporatos bottens from the radweste evaporotor and boric seid concentrates f rom the Boron Management System evaporator are to be solidified. 8 w.. 3,.

1 l Ad31niettative Procedure W.I.210 l Frocess Control Program Revision 0 I j 5.2 Solidification Process Parameters: 5.2.1 Solidification fornulas and solidification process parametste l are incorporated it to the applicable vendor piocess control program. No exceptions or deviations f ree vendor supplied prockdures or topical reports are anticipated. The formules i ste used to calculate the ratio of waste. cement, water and other reagents tequired to achieve an acceptable solidified product. Corpetibility requirentnts of the weste stresa with respect to the solidification s,edia are described in the l N vendor process controle program. Waste streme pataseters are l to adjusted as recessary to meet these requiremente. I (A 5.2.2 Test,solidificatione are performed on vaste etteam samples to verify vendor calculated solidification formulso. Plant i l procedures describe the frequency for perf orming test so!!. O difications and establish the acceptance criteria for the test solidifications in accordance with Technical Specificatios = 3/4 11.3. l 9 -______________.____-_-_._______________.-_____.______J

Ad intettative Procedure 3W.I.210 Frocess Control Progres Rwiston 0 5.3 Admintettative Controlo 5.3.1 Administrative controle utill ed to insure compilance with eppplicable state and federal reguistions and burial site etitoria are detsited in the radioactive vaste solidification surveillance procedure (s). These implementing document (s) for radioactive vaste entidification and devotering describes the requiremente which must be met prior to processing radio-active vaste, se well as the condition of the solidified or devetered weste. Test solidificatione, full scale estcula-gvy tiene and operation of the solidification equipment are perforwed by vendor personnel. Dewstering operatione vill be ,n retformed by vendor personnel or by quellfied Flont etaff. In Flant staff provides Itealth rhysics and Quality Assurance O coverage, operates plant radioactive weste systems, cellsets vaste stress east es and performa isotopic analyses. Copies l o of all taferenced documente are available on ette for ese by personnel engaged in solidification activittee. CP S.3.2 Changes to thte Process Control Progree shall be desct1 bed in tl.a tesi+ annual r4dioactive Ef fluent Ralsase Report for the O period in which the change le nede, t,o accordance with Techn!- cal $pecificetten 6.13.2. S.4 Waste Characterisation and Claselfication S.4.1 Weste Classifiestion $.4.1.1 Solidified wa:'ee are claestfied in accordasce with the requirements of 10CFR61.55, as implemented kT ' Ch*9* 1 ref erence 2.2N and plaat waste classification and A6 characterisation procedure (s). 88* fi'N ' i 10

Admiriistrative Procedure kWal-210 Frecess Control progree Revision 0 $.1'.6.2 Annual analysis will be perforted on the usate streans to determine the tectopic abundance of gaana emaitting f ootopes in the streams, scaling factore for the non-gamma emait t irig and tranovrante conet t-tuents will be developed from this annuel analysis. The activity of each radionutilde in the solidilled waste will be determined by a calculational method eeploying the percent abundance ano scaling f actors with a does to curie conversion f actor se described in reference 2.2.14 97 to S.4.2 Weste Characteristice in $.4.2.1 Solidified usetes will meet the charactoriettre of 10CFR61.56(a) and (b). Vaste containess will be labelled to identify the weste class. m $.6.2.2 The maulteeting requiremente of IDCFR20.311 are ~~ en tuplemented and records are meint41ned in accordance with IDCFR71.91. C3 5.5 Quality Assurance 5.5.1 Quality Assurance related activities for the Radioactive Waste Program are impleoented as described in the Nuclear Operatione Quality Assurance Manuel (Raforence 2.1.7). These activities provide verification that the solidified wastes meet applicable state and federsi restletions and burial ette criteria.

6.0 ATTACRMrwTs

NONE 11

4 Ch anges ade To S U)- ?!? to o U*fCA L 0Pvi sh fsd,&M ut, h n = - - _ s t as esse O Rev. d.-- 1 I I 1 l l 1:.: MSG r'n.----,,2-- mW '

. ~.... _ _. - . ~ _. _ I E37135 CUfEI. SG IT + q (Chotige 1) ggyggy 073 RW-1-210 - Procese Cont rol Program (Rev.0) i P7M UTIZ3

n. row u.r.rt-w au iu..a 4u.mu.4 au..ac..y.nzme

,.re,.a (as appl.taakia), that as unr.rimmd safscy qu.st.us does not esist (as applicabla), that a change to the T=hi as! Sp--"4 =*d-= La set required, and that

==*1==* saf ety is/ ens met eivenely affestad, i 00I1 .wrrmammtwn or , ronc viassa. peac usussa roa mw n. uzz trnza sta n n u ru l so 1

    • .rYszm4:

kkhw / //[f[V )'MLM / p/yJ9 openstans e s., state 4=t i-W n. ua-u.en u / '</nfer / up ue.a.a m l T q RW ,/r(C-r-,Ps. - spir /ey n. tammaust serpen s.,.esssmedess usu.sans r4 iq i y W M ** 4 90 $ ranc u.asas m. / E ' tsaus u; / neu: //- /*F-W ,,,.T$14 isas is r - d for appewealf @ III CW C TIS %W e-IkLa itas rogstrom $3c/NRc rwtaar ystet se ti!- - - staaf r.:r. ns a v,.nu,mu.u m Tkts stan reguirse 4 retts, rak.or as $myt-=====t Q Yts @ 50_ m A)M uzx A%+- n,vs a n

c. - %m ft.AIT H&KM21-*qK2. EAR ArraLu (,KEFER *TD CV,LL/)

g d, ca Lai Approved W badwM' DA:I NI / 19 N runs hanger-valur i 4 e

  • WA1TIIT1RD 3 SI3 PLANT OPERATING t1AhtLL Check Block Balev l~l P0ft ( lPORC 5/C b r ess (o ph rol b[c;rnin CRANGTJEmJICW/DELLTION REQUEST Precedure No.,3W - l 2 40 Title Effective Data (tf different f ross approval date)

Cosplete A. B. and C A. Change io. l @?ermanent l[lDevis t. ion Empiration Date 3. Revision No. O C. Deletion ([l tT.5 @NO DESCRIM0f 0F CRAN 01 C2 TITI$!ON g etence, < a reMe rcoer s erItat h Urmoc.r_ +u em nkle ni N o.05 hnere)A 0;,Jornoer-veCercuer 's S, V n d 5.4.1., i ii s \\ l i te HArcif TUR CIVCt._ imSIW, OR UTT. MON Chnor.g h nnnen A id ecco s 'ia rebecuer s eed.60 ~ e ndh 01cter~1 N c '~ n n e c' t~ e C e c e at e M.L A,o) M. J. i i g 4 n. 1-m GL11 ll It') W ou rg i 7 n EAluf Emtv Doss this cisage, rweistos, or deleties: 1. Chaage the facility se described La the T&Atf II3 E0,X 2. Change the procedarss as described La the IIART I!J

80. X 3.

Conduct tests /expertmaats not described La the T8 ART TLS 30 4 j R4 quire a change to tu Techaical Specificat.ioast TIS 30 i If the sasver to any of the above is yes, carglete and att.tch a 100/130.59 SafayEvaluationg j j EAn Tf REVir b m As m

  • rxn.es DAIE

// / / Q /17Y l TICINICAL IIVIIV N A M <. DATE //'/M/O l Gt0CF EIAD tgVIEW (du% =

  • y CATE

///M[tr l TIL*FORAIT AFTt0 VAL * (510) tiLTE TDIPQRAIT APYROVAL* DATI

  • Temporary approval innst be followed try Plast tis.aager/APti-f a Nuclear approval wit. kin 1

14 days. UNT 1-003 f.svision 8 63 AAtacht 6.7 (1 of 1)

Lemisistrative Procedure RW-1-210 Fracess Control Progrs* 3*vist:00 i TABLE OF CONTUTS 1.0 FURPOSE i l 2.0 RETER D CES 3.0 DETU ITIOWS 4.0 EEsFOKI!BILITIES M 5.0 FEDCEDURI i le 5.1 Fregram Description in 5.2 Solidtfication Process Parameters !.3 Aeninistrative Controla O S.4 waste Characterisettaa sa.d Classification 5.5 Quality Assurance . m I 1 6.0 ATTACIDGXTS h ~~ o LIST OF trF3crITE IAGES j Title Ber$ sten 0 l !=)1 , heristas 0 G hage, s. I,3,to Cuqa.$. gg.. i 4t? ti-M i l 1

_ e. ~ l l Adminiscretivo Pt9e #rfr W-1-210 Proc m Control trrgraa Levision 0 l l i l 2.2 M der Centrdised p eusents b *il PS.$8 0870 I 2.2 1 i,,, y, u,, trU8 Process Services Corporation, Topical Report 891 on Pedysste solidiftestica Systes, new. O Il li M 2 3,2 Tis 00L K05 revcase is ntess Catforation. Topical Report on 10CT1614 alified hdtoactten Winste Forms, Hey 1984 2.2.3 431901354-01F Chew-blear Systsee lac., Topir.at Report on Mobile Caceat $4 1dification Systes, Sev. 2 W M 2.2.6 CBB1jFg4J47,10CTR&1, hte Pota Certifissties-Comset, lA Ch m-peetowe systee lac, November 30, 19C3 tt.it.q O 2.2., cut!.bW.filig.cl.P -,g-..r ,,.t , m., -t.ro. C;71 Toptral, December p,1983 n.g gg i I 2.2.6 15-11109, ke.ap.e' vee tittman hlaar, tas., Tepisal Soport ~ on Radwast - Solidifiesties syetas (Coment), now. 4 i f o J.2.7 STD-E-0$4CS, liestin8 ouse Rittaen himar, tas., Tot aal b t Report on Coment Solidified unetae am Meet tas Stability Esquirements of 10CFR41, lev, 0 2.2.8 STD-t-03-004, ifestinghouse Bittmas maalmar, tea., Topical Report for Rittman RADLDE Rigin tategrity h*=hes, Ber. 0 2.2.9 T1-013 Procese control Program for Deessaring Liner with NUS PSC !atermais. NUS Freceos Sesvissa Corp, 2.2.10 sto-F-05-005, Rittmas pealear 5evatar===* Corp., Preseos Control Progren for taccatateer Solidtttastims of 10 of 14 lietsht Percent Boric Acid, Rev.1 )

A6s.ta10ttitiv3 FT Cf FVel-210 Frec:ee Control Fregram Revisten 0 3.3 Administre)19eControle S.3.1 Adainistrative controle utilised to insure ccepli.ance with applicable state and federal regulations aad burial ette criterte are detailed in the radioecties veste eolidification surveillance procedure (s). These implemetting document (s) for radioactive waste solidification and dwatering ducribes the requirements which must be met prior to processtag radio-active waste, se voll as the condition of the oo11dified or devotered waste. Test polidifications, full scale calcula-O tions and operation of the solidification equipeant are ^ perforwed by vender pereunnel. Dewstering operatione vill be M performed by vendor personnel er by goalified Flant staff. O Flast staff provides Baalth rhystes and Quality Aaestsnos coretage, operatu plast radioactive waeve eyetemas, collecta vaste streme samples and performs teeteric analypes. Copies n of all referemced documente are available on ette for use by personnel engsgod in ectidification activittee. ~ S.3.2 Changes to this Peptue Contiel Progen shall be described in O ti osai-annual Radioactive Ef flusst tale Laport for the l i period in which the change is ende, la cecordance with Teshni-cal Specification 6.13.2. 3.4 Waste Charactertsstion and Clasoffic.atice 5.4.1 Waste C1seeification S.4.1.1 Solidified waste.e are claaeffled in accordance with i l the requireaneets of 10Cf341.Sh n impleaseted by ! Cqe i reference 1.2N and plant we4te elsestrication asa N characterisetion procedure (s). 83* fi'M 10

t Papa Swm.10adn CBPY A attac/wl Pap Aaa-fie.c.a. &AM and Eu-- 12cw Pap amwM-1)& : n/20hv c4.* / p.u. _ 0 1 o 99. t.

d Administistive Freceduse BW.I.2g0 l't oce ss Cent rol l' rest am Loviejon o TAllLE Or Coh'TrRTS 1.0 ITRI'OS T l 2.0 FITTRI:NCf.$ ) 3.0 DIi!N!110N6 l 4.0 !J6 POK 51 Bit.111 r8 N 5.0 PRocr. DURE $.1 Pregime Description in 5.2 Solidification Process rarametste o $.3 Adn'ntattative Controle $.4 Waste Character 1:stion and Classification 5.5 Quality Asaurence 6.0 ATTACRMD(TS ~ m 1

o LIST OF ETTrrTIVE TMts Title Levision 0 1-11 Revision 0

? I 1 i

^ Administrativs Frecedere $W-t 210 Process Cor, trot Progran Esvisicn 0 2.2 Vendor Controlled Documente l 2.2.1 PS*5.1-0178 Nt's riccese Services Corporation, Topical Report on.Rodwa6te Solidification Systes, Rev. 0 j 2.2.2 Tk002, NU$ Process services Corporation. Topical Report on 10CFF61 Qualified Radioactive Waste Forse May 1984 2.2.3 4313-01354-Otr Chem-hueleet Systems Inc.. Topical Report on Hobile Cement solidification System, Rev. 2 M e 2.2.4 CNS!*WF-C-01-NP,10Cn61 Wsete Form Certification-Coment, in neo-Nueirar System Inc., No" ember M,1983 O 2.2.5 CN81-DN-illl8-Cl-P, Chee Nuclear Systes, Inc., Dewatering Topical, Deces,ber 23, 1983 O 2.2.6 NN-Ril09. Westinghouse Hittman Nuclear, Inc., Topical Report ~ Cp on Radvaste Solidification System (Cement), Rev. 4 2.2.7 STD-R-05-005, Westinghouse Hitsma:6 puclear. Inc., Topical Report on Coment solidified Wastes to Mest the Stability Requiremente of 10Cn61, Rev. 0 2.2.8 STD-R-03-008, Westin6 od*e Rittman Nuclaar, lac., Topic.a1 h Report for liittman RfDLOK High Inte8 tit) Containers, Rev. 0 2.2.9 FI-013. Process Control Program for Devotering Liner with arD6 PgC Internals NUS Procese Setvites Corp. I 2.2.10 i STD-P-05-003. Hittman Nuclear Development Corp., Process Control Program for incentainer Solidification of 10 of 14 Weight Percent Boric Acid, Rey. I l I l r

a. -

RW-1-!!O ' Administrative Procedure Reviolon 0 l'rocese Control Fregram 1 5.3 Adelniettative lontrola 5.3.1 Admintattative controle utilited to insure complistice with applicable state and f ederal regulattene and burial site etiteria are detailed in the radioactive weste solidification surveill'ance procedure (s). These loplementing document (s) for radioactive vaste solidtitration and dewetering describes the requitenants which emot be set prior to proceselog radio. active weste, as well as the condition of the solidtfied or dewatered voete. 1est solidifications, full scale celeula-T tiene and operation of the solidification equipment ste

  • O performed by vendor personnel. Dewatering operettone vill be performed by vendor perennuel or by qualified Flant staf f.

Ln Flant staf f provides Hesith rhyette and Quality Assurance O coverage, opetetes plant radioactive vaste erstema, collects weste stream semples and perlotsie tootopic analyses. Copies of all referenced docusente are evallable on alte for use by O petoonnel engaged in solidification activittee. ~ Ch 5.3.2 Changes to thle Procese Control program shall be described in = the seat-annual Radioactive Effluent Release Report for the o pettod in which the change to mode, in accordance with Techat. cal 6pecification 6.13.2. $.6 Weste Chetsetettsstion and Claeef fication 5.6.1 Weste Claestfication 5.4.1.1 Bolid1(led wastes are classifted in accordance with the tequiremente of 10CTR61.55, as implemented by reference 2.2.9 and plant weste closelficotton and charactettsetion procedure (s). 10

  • s n}}
Retrieved from "https://kanterella.com/w/index.php?title=ML20082M231&oldid=4370892"