Text

Rev 1.1 to Chapter 12, Radioactive Effluent Technical Stds of Dresden ODCM
	ML20085M617
Person / Time
Site:	Dresden
Issue date:	07/31/1994
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML17180B253	List: ML17180B252; ML17180B254; ML20085M617;
References
	PROC-940731-01, PROC-940731-1, NUDOCS 9506290284
	Download: ML20085M617 (66)
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{{#Wiki_filter:- _- DRESDEN L Revtion 1.1 'Y, July 1994

1. ;

~. + b.: la L 'l CHAPTER 12.0 t-L SPECIAL NOTE s-Until the Unit 2 & 3 Radiological Effluent Technical Specifications have been approved by the. Nuclear Regulatory Commission, the requirements of the Technical Specifications shall take precedence over this chapter, should any differences occur. i -~ .I i . i 124 9506290204 950616 PDR ADOCK 0500 7 .P

i' b F0llM0M0ffDU "Tne'd DR8SDEN ANNEX INDEX - E&g.E REVISION 'PAGE REVISION i CHAPTER 12 12 - l 1.1 12 - 46 1.1 l ^ .12 - li 1.1 12 - 47 1.1 12 - ill 1.1 12 - 48 - 1.1 12 - iv 1.1 12 - 49 1.1 12 - v 1.1 12 - 50 1.1 12 1.1 12 - 51 1.1 ' 2 - 1.1 12 - 52 1.1 12 - 3 1.1 12 - 53 1.1 12 - 4 . 1.1 12 - 5 1.1' '12 - 6 1.1 12 - 7' 1.1 12 - 8 ' 1.1 12 - 9 1.1 12 - 10 1.1 12 - 11 1.1 12'- 12 1.1 12 - 13 1.1 12 - 14 1.1 12 - 15 1.1 12 - 16. 1.1 12 - 17 1.1 12 - 18 1.1 12 - 19 1.1 12 - 20 1.1 j 12 - 21 1.1 12 - 22 1.1 12 - 23 .1.1 i 24 1.1 l 12 1.1 12 - 26 1.1 i 12 - 27 1.1 12 - 28 1.1 ' 12 - 29 1.1 12 - 30 1.1 12 - 31 1.1 i ' 12 - 32 1.1 12 - 33~ 1.1 12 - 34 1.1 12 - 35 1.1 12 - 36 1.1 12 - 37 1.1 12 - 38 1.1 12 - 39 1.1 12 - 40 1.1 12 - 41 1.1 I 12 - 42 1.1 12 - 43 1.1 12 - 44 1.1 .12 - 45 1.1 ~l 12-li r 5

I D F011NF0M AT10 LO RY """o"" "29A V 1P p p n;} pe> ~ % .,1 y g 4. 3 CHAPTER 12" 1, RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) TABLE OF CONTENTS l PAG.E F-12.1. DEFINITIONS 12 ; u 12.2. INSTRUMENTATION 12-5 . A. Radioactive Uquid Effluent Monitoring Instrumentation - 12-5 } 1. Operability 12-5 l 2. Surveillance 12-5 h B. Radioactive Gaseous Effluent Monitoring instrumentation 12-5 1 L 1. Operability 12-5 c 2. Surveillance 12-6 C, Uquid and Gaseous Effluent 12-18 i instrumentation Bases l 12.3 UQUID EFFLUENTS - 12-19 A. Liquid Effluents Limits and Reporting Operability 12-19 ~ 1.- ConcentrtOn in Onrestricted Areas 12-19 I 2. Dose frr a i., quid Effluents 12-19 i 3. Dose rrob J ons 12, 4. Liquic htNetive Waste Treatment System - 12-21

5.. System Operability and Plant Operations -

12-21 i B. Uquid Effluents Surveillance. 12-21 [ 1. Concentration in Unrestricted Areas. 12-21 l 2. Dose from Liquid Effluents. 12-22 3. Dose Projections 12-22 C. Liquid Effluents Bases 12-27 i 12.4 GASEOUS EFFLUENTS 12-29 A. Gaseous Effluents Limits and Reporting Operability 12-29 1. Dose Rate 12-29 2. Noble Gas Dose 12-29 l 3. lodine-131, lodine-133, Tritium and Particulates Dose 12-30 i 4. Off Gas Treatment 12-31 5. Main Condenser Air Ejector 12-32 6. System Operability and Plant Operations 12-32 j B. Gaseous Effluents Surveillance ~ 12-33 l 1. Dose Rate 12-33 2. Noble Gas Dose 12-33 3. lodine-131, lodine-133, Tritium and Particulates ] Dose - 12-33 4. Off-Gas Treatment 12-33 5. Noble Gases at the Main Condenser Air Ejector ' 12-34 C.. Gaseous Effluents Bases 12-38 2-i 12-lil

).-.

~ ~ .l 13 ??3? cl.6t 7 pp'5 y " DRESDEN',4 =l ], Revision 1.1 - v.. FOR HFORMATION ONLY ~ CHAPTER 12' 'i y.. RADIOACTIVE EFFLUENT TECHNICAL STANDARDS i b -(RETS)? i [ - TABLE OF CONTENTS i p CONTINUED ! P.8.GE 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1240 A. Radiological Environmental Monitoring Program 1240l B. ~ Radiological Environmental Monitoring Program. Surveillance 12-41 { C. Radiological Environmental Monitoring Program - 1 Bases 1248 j 12.6 RECORDKEEPING AND REPORTING '1249' -1. Station Operating Records 1249 I 2. Reports ; 1249 1. ' Radioactive Effluent Release Report

1249, 2.

Annual Radiological Environmental l Operating Report 1249 3. Non-Routine Environmental Reports 12-51. 3. Offsite Dose Calculation Manual (ODCM) - 12-51 4. Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) 12-52 i i le " 3 .4 .j l j 4 124v

f l m 1 n 'q DRESDEN. R:vi: ion 1.1 1 CHAPTER 12 - RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) UST OF TABLES. i F ? NUlWIBER IIILE E89.E .l 12.1 Surveillance Frequency Notation 12-4 ~ 2 12.2 Radioactive Uquid Emuent Monitoring I Instrumentation 12-7. i .I 12.2 Radioactive Uquid Effluent Monitoring Instrumentation Surveillance Requirements 12-9' i 1 12.2-3 Radioactive. Gaseous Effluent Monitoring Instrumentation 12-12' \\ 12.2-4 ~ Radioactive Gaseous Effluent Monitoring - l Instrumentation Surveillance Requirements .12-15 + 'i

1 12.3-1

- Allowable Concentration of Dissolved . or Entrained Noble Gases Released from the Site to Unrestricted Areas in Uquid Waste ' 12-23 12.3-2 Radioactive Liquid Waste Sampling and Analysis Program 12-24 i i 12.4-1 Radioactive Gaseous Waste Sampling and Analysis ' I Program 12-35 '- g 12.5 Radiological Environmental Monitoring Program .12-43 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples - 12-44 j t 12.6-1 Practical Lower Umits of Detection (LLD) for Standard Radiological Environmental Monitoring i Program 12-45 J t t l I I I ) 12-v i i I

l a J 994 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12.1 DEFINITIONS 1. Channel Functional Test (Radiation Monitor) - Shall be the injection of a simulated signalinto the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions. 2. Dose Eauivalent 1-131 - That concentration of 1131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132,1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table 111 of TID -14844,

Calculation of Distance Factors for Power and Test Reactor Sites".

3. Hot Standby - Hot standby means operation with the reactor critical, system pressure less than 600 psig, the main steam isolation valves closed. 4. Immedate -Immediate means that the required action will be initiated as soon as practicable considering the safe operation of the unit and the importance of the required action. l S. Instrument Calibration ' An instrument calibration means the adjustment of an instrument signal output so that it corresponds, within acceptable range and accuracy, to a known value(s) of the parameter which the instrument monitors. Calibration shall encompass the entire instrument, including actuation, alarm, or trip. 6. Instrument Check - An instrument check is qualitative determination of acceptable operability by observation ofinstrument behavior during operation. This determination shallinclude, where possible, comparison of the instrument with other independent instruments measuring the same variable. 7. Instrument Functional Test - An instrument functional test means the injection of a simulated signalinto the instrument primary sensor to v6rify the proper instrument response alarm and/or initiating action. 8. Member of the Public - an individualin a controlled or unrestricted area. However, an individualis not a member of the public during any period in which the individual receives an occupational dose. 9. Mode - The reactor mode is that which is established by the mode-selector-switch. 10. The Offsite Dose Calculation Manual f0DCM) shall contain the methodology and parameters used in the calculation of offsite doses regulating from radioactive gaseous and liquid effluents,in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM 12-1

m-r 10 M ORMAT01D M oaesoe" - 12.1 DEFINITIONS (Cont'd) shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs described in Section 12.5 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports ' required by Sections 12.6.2.2.1 and 12.6.2.1. 11. Operable - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, a normal and an emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s). 12. Operatina - Operating means that a system, subsystem, train, component or device is performing its intended function in its required manner. 13. Operatina Cvele -Interval between the end of one refueing outage and the end of the subsequent refueling outage. 14. The Process Control Proaram (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. 15. Rated Thermal Power - Rated thermal power means a steady-state power level of 2527 thermal megawatts.. 16. Reactor Power Operation - Reactor power operation is any operation with the mode switch in the "Startup/ Hot Standby" or "Run" position with the reactor critical and above 1% rated thermal power. 1. Startup/ Hot Standby Mode -in this mode, the reactor protection scram trips, initiated by condenser low vacuum and main steamline isolation valve closure, and by-passed when reactor pressure is less than 600 psig; the low pressure main steamline isolation valve closure trip is bypassed, the reactor protection system is energized with IRM neutron-monitoring system trips and control rod withdrawalinterlocks in service. 2. Run Mode -In this mode, the reactor protection is energized with APRM protection and RBM interlocks in service. l i l { 1 12'-2 i

y, a += e ~ uly 12.1 DEFINITIONS (Cont'd) 17. Reactor Vessel Pressure - Unless otherwise indicated, reactor vessel pressures listed in the RETS are those measured by the reactor vessel steam space detector. 18. Refuelino Outaae - Refueling outage is the period of time between the shutdown of the unit prior to a refueling and the startup of the plant subsequent to that refueling. For the purpose of designating frequency of testing and surveillance, a refueling outage i shall mean a regularly scheduled refueling outage; however, where such outages occur within 8 months of the completion of the previous refueling outage, the required surveillance testing need not be performed until the next regularly scheduled outage. 19. Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the rhutdown mode position and no core alterations are being performed. When the mode switch is placed in the shutdown position a reactor scram is initiated, power to the centrol rod drives is removed, and the reactor protection system trip systems are de-energized. 1. Hot Shutdown means conditions as above with reactor coolant temperature greater than 212'F. 2. Cold Shutdown means conditions as above with reactor coolant temperature equal to or less'than 212* F. 20. Source Check - The qualitative assessment of instrument response when the sensor is exposed to a radioactive source. 21. Surveillance Interval-Each surveillance requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the surveillance interval. 1 22. Definitions Related to Estimatina Dose to the Pubic Usina the ODCM Computer Proaram: 1. Actual-Refers to using known release data to project the dose to the public for the previous month. These data are stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12. 2. Projected - Refers to using known release data from the previous month or estimated release data to forecast a future dose to the public. These data are NOT incorporated into the database. \\ 12-3

y: [y DRESDEN R^ vision 1.1, .[ 'gigg[gyl[Q Q Q p3 -l,il Un Hr1l U.] U Ll. July 1994 : < R -[J l TABLE 12.'1-1 SURVEILt.ANCE FREQUENCY NOTATION 1 l NOTATION - FREQUENCY .? S At least once per 8 hours - l D At least once' per 24 hours 'I T At least once per 72 hours W At least oncept 7 days M At least once per 31 days Q At least once per 92 days SA At least once per 184 days f A At least once per 366 days 6 R At least once per refuel outage S/U Prior to each reactor'startup i N.A. Not applicable E At least once per 550. days (Units 2 & 3) and 18 months for Unit 1 j 12-4

F L Y.is,L L. U f DRESDEN Revision 1.1 I July 1994 12.2. INSTRUMENTATION A. Radioactive Licuid Effluent instrementation

1. Radioactive Liauld Effluent instrumentation Operability 1.

The effluent monitoring instrumentation shown in Table 12.2-1 shall be operable with alarm trip setpoints set to insure that the limits of Section 12.3.A are not ~ exceeded. The alarm setpoints shall be determined in accordance with the ODCM. 2. With a radioactive liquid effluent monitoring instrument alarm / trip setpoint less conservative than required, without delay suspend the release of radioactive liquid effluents monitored by the affected instrument, or declare the instrument Inoperable, or change the setpoint so it is acceptably conservative. 3. With one or more radioactive liquid effluent monitoring instruments inoperable, take the action shown in Table 12.2-1. Return the instrument to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. This is in lieu of an LER. 4. In the event operability requirements and associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specifications, provide a 30-day written report to the NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operational mode.

2. Radioactive Liouid Effluent Instrumentation Surveillance 1.

Each radioactive liquid effluent monitoring instrument shown in Table 12.2-2' shall be demonstrated operable by performance of the given source check, instrument check, calibration, and functional test operations at the frequencies shown in Table 12.2-2.

8. Radioactive Gaseous Effluent Instrumentation

1. Radioactive Gaseous Effluent Instrumentation Operability 1.

The effluent monitoring instrumentation shown in Table 12.2-3 shall be operable with alarm / trip setpoints set to ensure that the limits of Section 12.4.A are not exceeded. The alarm / trip setpoints shall be determined in accordance with the ODCM. 2. With a radioactive gaseous effluent monitoring instruments alarm / trip set point less conservative than required, without delay suspend the release of radioactive gaseous effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative. 1215

j I i. DRESDEN- - Revision 1.1 - . July 1994 - s. r 12.2.B.1.; - Radioactive Gaseous Effluent instrumentation Operability (Cont'd). 3. With one or more radioactive gaseous effluent monitoring. instruments inoperable, take the action shown in Table 12.2-3. ~ Retum the instrument to operable status - ? within 30 days and, if unsuccessful, explain in the next Radioactive Effluent - . Release Report'why the inoperability was not corrected in a timely manner. This'- is in lieu of an LER. 4. .The unit 2/3 plant chimney gas sampling system may be out of service for,48 hours for the purpose of servicing the high range noble gas monitor as long as the? following conditions are satisfied:

1. Both units are at steady state conditions with the recombiners and charcoal' absorbers in service for the operating unit (s).

t ' =

2. The dose rate in unrestricted areas must bs shown by calculation to be less F

than the limits of 12.4.A assuming the charcoal absorbers are bypassed on. both units. 3. Both offgas monitors on Unit 2 and Unit 3 must be operational and the monitor . reading correlated to the chimney release rate based on the conservative assumption of both units' charcoal absorbers being bypassed. p 4. If the provisions of 12.4.A.1.1,12.4.A.1.2, or 12.4.A.1.3 cannot be met, an : orderly load reduction of'the unit (s) shall be initiated immediately. 5. In the event operability requirements and associated action requirements'cannot - be satisfied because of circumstances in excess of those addressed in this Section, provide a 30-day written report to the NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operation mode.'

2. Radioactive Gaseous Effluent instrumentation Surveillance Each radioactive gaseous radiation monitoring instrument in Table 12.2-4 shall be demonstrated operable by performance of the given source check, instrument.

check,' calibration, and functional test operations at the frequency shown in Table - 12.2-4. ey 4 12-6

i g y DRESDEN-Revision 1.1 ) hill TABLE 12.2-1 RADIOACTIVE LlOUID EFFLUENT MONITORING INSTRUMENTATION { UNIT 1 Minimum Total Channels No. of instrument Operable Channels Action 1. Service Water Effluent 1 1 10 Gross Activity Monitor 2. Discharge Canal 1 1 12 Sampler ACTIONS ACTION 10 - With less than the minimum number of operable channels, releases via this pathway may continue, provided that at least once per 24 hours grab samples are collected and analyzed for beta or gamma activity at an LLD ofless than or equal to 10 pCl/ml. ACTION 12 - Operability is verified prior to performing and once a day during planned discharge. k s b 12-7

p n I July 1994 DRESDEN-Revtisn 1.1 ~ 1 TABLE 12.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION UNITS 2 & 3 l i L Minimum Total Channels ' No. of instrument Operable Channels - Action i i 1. Service Water Effluent i 1 10 Gross Activity Monitor 2. Liquid Radwaste Effluent 1 1 11 Gross Activity Monitor .] .t ACTIONS [ ACTION 10 - With less than the minimum number of operable channels, releases via this pathway f may continue, provided that at least once per 12 hours grab samples are collected and analyzed for beta or garama activity at an LLD of less than or equal to 10~7 l uCi/ml. t ACTION 11 - With less than a minimum number of operable channels, effluent releases via this pathway may continue, provided that prior to initiating a release, at least 2 independent samples are analyzed, and at least 2 members of the facility staff l independently verify the release calculation and discharge vaMng. Otherwise, suspend release of radioactive effluent via this pathwap, I i [ [ t I i l 1 ? e I 12-8 [ t u

u 'i -[U DRESDEN' ~ Revision 1.1 July 1994 -k TABLE 12.2-2 i ' RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS [ UNIT 1 i i Functional Calibration Instrument Source . instrument . Test - (b)(f) Check (f) Check i 1. Service Water Effluent Gross Q (a,f.e) E(c) D E i Activity Monitor i 2. Discharge Canal (g) i Sampler ,. P M' 12-9

l; ~ !)

h 9

TABLE 12.2 RADIOACTIVE LIQUID EFFLUENT MONITORING - INSTRUMENTATION SURVEILLANCE REQUIREMENTS : UNITS 2 & 3 1 Functional Calibration ' tr.strument ' Source instrument Test (s)(f) (b)(f) Check (f) Check 1. Liquid Radwaste Effluent Gross. Q(e) E(c). D E(d) Activity Monitor 2. Service Water Effluent Gross O(e) E(c) D. E Activity Monitor 4 9 1 O 12-10

O 1f a DRESDEN R;vhi::n 1.1 July 1994 TABLE 12.2-2 (Cont'd) RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS (a) The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where appEcable. 1. Instrument indicated levels above the alarm setpoint. 2. Circuit failure. 3. Instrument indicates a downscale failure. 4. Instrument controls not set in OPERATE mode. (b) Calibration shallinclude performance of a functional test. (c) Calibration shallinclude performance of a source check. (d) Source check shall consist of observing instrument response during a discharge. (e) Functional tests may be performed by using trip check and test circuitry associated with the monitor chassis. (f) Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or are tripped. Calibration is not required to be performed more than once every 18 months. ] (g) Operability is verified prior to performing discharge and once a day during planned discharge. 1 9 12'11

g...

.y 4 yq 'DRESDEN; - Rivisin 1,1L = ' l[dn.g gggggy p pj gg y3 [18.U. n Uni,lU,it UllL g. luly 1994 : s- .i TABLE 12.2-3 ~ + 'i RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION t UNIT 1 i Minimum Total ' Apriicable-- l Channels ' No. of -. ; Operational l f' instrument' Operable Channels' Modes' '- Action .I t 28 [ 1. Main Chimney SPING Noble Gas 1-3' Monitors

2. ' Main Chimney Particulate 1

1 27 l Samplers j 3. Main Chimney lodine Samplers 1 1 27- ~* l l ~! -i r ( l e 5 .] + -] 1 , y 12-12 9 a w ~ m yw-e, w

g-N DRESDEN Revision 1.1 L July 1994 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION UNITS 2 & 3 1 Minimum Total Applicable Channels No. of Operational instrument Operable Channels Modes Action 1. Main Chimney Noble Gas /SPING/ 1 3 20 GE Low Range Activity Monitor 2. Main Chimney SPING Noble Gas 1 1 26 Monitors Mid, Hi Range 3. Main Chimney lodine Sampler 1 1 22 4. Main Chimney Particulate Sampler 1 1 22 5. Main Chimney Flow Rate Monitor 1 1 21 6. Main Chimney Sampler Flow Rate 1 1 21 Monitor 7. Reactor Building Vent Exhaust 1 2 24 Duct Radiation Monitor 8. Reactor Building Vent SPING 1 1 25 Noble Gas Monitor Low, Mid, High Range 9. Reactor Building Vent Flow 1 1 21 Rate Monitor

10. Reactor Building Vent Sampler 1

1 21 Flow Rate Monitor

11. Reactor Building Vent lodine 1

1 22 Sampler )

12. Reactor Building Vent 1

1 22 Particulate Sampler J i 12-13

DRESDEN R:vi:lin 1.1 July 1994 TABLE 12.2-3 (Cont'd) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ACTIONS AND TABLE NOTATIONS ACTION 20 - With less than the minimum channels operable, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once every 8 hours and analyzed for noble gas within 24 hours. in addition, restore the inoperable equipment to operable status within 7 days, or prepare and submit a report to the commission within the next 30 days outlining the plans, actions taken and procedures to be used to provide for the loss of sampling capability. ACTION 21 - With the number of operable channels less than the minimum required, effluent releases via this pathway may continue provided that the flow rate is estimated at least once per 4 hours. ACTION 22 - With less than the minimum channels operable, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment, as required in Table 12.4-1. ACTION 24 - With less than the minimum channels operable, immediately suspend release of radioactive effluents via this pathway. ACTION 25 - With less than the minimum channels operable, effluent releases via this pathway may continue provided that the minimum number of operable channels for the - Reactor Building Vent Exhaust Duct Radiation Monitor are operable. ACTION 26- -With less than the minimum channels operable, effluent releases via this pathway may continue provided the low range monitor is operable and on scale. Restore the inoperable equipment to operable' status within 21 days, or prepare and submit a report to the commission pursuant to Technical Specification 6.6.B (Section 6.6.A in Upgraded Technical Specifications) within the next 30 days outlining the plans, actions taken and procedures to be used to provide for the loss of sampling capability of the system. ACTION 27-The main chimney SPING monitor may be out-of-service for calibration and maintenance provided that particulate and iodine samples are taken and analyzed. The samples sha!! be collected using alternate filter holders and pumps connected to the main chimney sample stream. ACTION 28 - With less than the minimum channels operable, effluent releases via this pathway may continue provided daily noble gas samples are taken and analyzed daily. Restore the inoperable equipment to operable status within 30 days. If service can not be returned, document equipment availability difficulties within the Radioactive Effluent Release Report for the period including actions taken in response to the equiprnent and procedures used to provide for the loss of sampling capability of the system.

At all times 12-14

7-t g . DRESDEN.- Revision 1.1 = July 1994 . TABLE 12.2-4 : RADIOACTIVE GASEOUS EFFLUENT MONITORING. INSTRUMENTATION SURVEILLANCE REQUIREMENTS -y UNIT 1 i i' l Applicable l Functional ~ Calibration Instrument. Source - Operational instrument - Test (a)(e) (b) Check Check Modes - j 1. Main Chimney SPING Q E D M i Noble Gas Monitor Low Range i -I l f 1 I l I i l l 12-15

y3 p p1 g*= lp p kJg DRESDEN R' vision 1.1 -.3 hgdidfds4 [d[ $ [, July 1994 -[ g g TABLE 12.2-4 g RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS UNITS 2 & 3 l Applicable Functional Calibration Instrument Source Operational Instrument Test (a)(e) (b)(e) Check (e) Check Modes 1. Main Chimney Noble Q E D M Gas Activity Monitor 2. Main Chimney SPING Q E D M Noble Gas Monitor Lo, Mid, High Range 3. Main Chimney N.A. N.A. D(c) N.A. Particulate and lodine Sarnpler 4. Main Chimney Flow Q E D N.A. Rate Monitor 5. Main Chimney Sampler Q(d) E D N.A. Flow Rate Monitor 6. Reactor Bldg Vent Q E D -Q Exhaust Duct Radiation Monitor 7. Reactor Bldg Vent O E D M SPING Noble Gas Monitor Lo, Mid, High Range 8. Reactor Bldg Vent Q E D N.A. Flow Rate Monitor 9. Reactor Bldg Sampler Q(d) E D N.A. Flow Rate Monitor 1 10. Reactor Bldg Vent N.A. N.A. D(c) N.A. Particulate and i lodine Sampler 1 l 12-16

r: 1 DRESDEN Revision 1.1 July 1994 I TABLE 12.2-4 (Cont'd) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS (a) The instrument Functional Test shall also demonstrate that control room alarm annunciation occurs,if any of the following conditions exist, where appicable. 1. Instrument indicates levels above the alarm setpoint. 2. Circuit failure. 3. Instrument indicates a downscale failure. 4. Instrument controls not set in OPERATE mode. (b) Calibration shallinclude performance of a functional test. (c) Instrumenttheck to verify operability of sampler; that the sampler is in place and functioning properly. (d) Functional test shall be performed on local switches providing low flow alarm. (e) Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or are tripped. Calibration is not required to be performed more than once every 18 months. 1 At all times. 12'17

fp l I h.: i Rgvisien k.1 N' s ! DRESDEN- ~ ? July 19941 L12.2.CIliauid And Gaseous Effluents instrumentation Bases s . 1., The radioactive liquid and gaseous effluent instrumentation is provided to : 1-monitor the release of radioactive materiais in liquid and gaseous effluents. j during releases. The alarm setpoints for the instruments are provided to ensure ~ that the alarms will occur prior to exceeding the limits of RETS - 3-5 s I l-.. ? e f I f I I I i f l L + Li t t 4. s e 12-18 t

h /kQ 7 y .g L ia I N ~"** '~ DRESDEN::: ' "Re'visiori1.1 July 1994-g c12,3? UQUID EFFLUENTS ' 12.3.A? Uauld Effluent's Umits and Reportina Operability i g -1.> ' Conce,a,Jen in Unrestricted Areas ' 1 + '~ J J iThe concentration of radioactive material released from the site to unrestricted - P areas (at or beyond the site boundary, Dresden Station ODCM Annex,. . Appendix F, Figure F-1) shall be Emited to the concentrations specified in ' l Appendix B, Table 2; Column 2 to 10CFR20.1001-20.2402t with the Table 12.3-1 values for. noble gases. F With the concentration of radioactive material released from the site to'- unrestricted areas exceeding the above Bmits, without delay decrease the. l release rate of radioactive ' materials and/or increase the dilution flow rate to n ,.] ' restore the concentration to within the above Emits. I-l 2. Dose from Liould Effluents i - The dose or dose commitment above' background to a member of the public L from radioactive materials in liquid effluents released to unrestricted areas (at or ] beyond the site boundary) from the site shall be limited to the following: 1; 4 1. During any Calendar. Quarter: nn (1)- Less than or equal to 3 mrem to the whole body. -(2) Less than or equal to 10 mrem to any organ.-

2. '

During any Calendar Year: (1) Less than or equal to 6 mrem to the whole body. (2) Less than or equal to 20 mrem.to any organ.. -l 3. With the calculated dose from the release of radioactive materials in - t7 liquid effluents exceeding any of the above limits, prepare and submit to. Li the Commission within 30 days a Special Report which identifies the ' cause(s) and defines the corrective actions taken and the proposed ' actions to be taken to ensure that future releases are in compEance - with Sections 12.3.A.2.1 and 12.3.A.2.2. This is in lieu of a Licensee { Event Report. i L I s 'I 2Upon technical specification approval, ten (10) times the l Appendix B value may be used to determine the maximum instantaneous liquid release, ( 12-19 [ b .~.

F01aF01K0LDE a i;q,'d oaesoe" 12.3.A - Liouid Effluents Limits and Peoortina Operability . (Cont'd) n 4.

With the calculated dose from the release of radioactive materials in Equid effluents exceeding the limits of Sections 12.3.A.2.1 or 12.3.A.2.2. prepare and submit a Special Report to the Commission :

-within 30 days and limit the subsequent releases such that the dose or dose commitment to a member of the public from all uranium fuel cycle , sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is imited to less than or equal to 75 mrom) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent - pathways and direct radiation) are less than the 40 CFR Part 190 - Standard. Otherwise obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use' methods. i prescribed in the ODCM.' This report is in lieu of a Licensee Event . Report. S. When the projected annual whole body or any internal organ dose l computed at the nearest downstream community water system is equal j to or exceeds 2 mrem from all radioactive materials released in liquid ; effluents from the Station, prepare and submit a Special Report within 30 days to the operator of the community water system. ' The report is '] prepared to assist the operator in meeting the requirements of 40 CFR Part 141, EPA Primary Drinking Water Standards. A copy of this report j will be sent to the NRC. This is in Eeu of a Licensee Event Report. 3. Dose Proiections l At all times during processing prior to ducharge to the environs, process and control equipment provided to reduce the amount or concentration of radioactive materials shall be operated when the projected dose due to liquid effluent l L releases to unrestricted areas (Dresden Station ODCM Annex, Appendix F, i Figure F-1), when averaged over 31 days, exceeds 0.13 mrem to the total body .j or 0.42 mrem to any organ. I i I l 2 12-20

M[ 9 ~ f W1' y d f ~ DRESDEN: Revisiob 1.1' . July 1994 4 in3.A1 - Liauid Effluents' Limits and'R=Ndirm OoerW(Cont'd): s (( 4.', f Llauld Radioactive Waste Treatment Svutom ?!f liquid waste has'to be or is being discharged without treatment as required ' . above, prepare and submit to the Commesion with 30 days, a report whichi ' includes the following information. 1, Identification of the defecewe egiapment. 2.- . Cause of the defect in the egiapment. 3. Action (s) taken to restore the equipment to an operating status. 4. Length of time the above requsements were not satisfied.

5. >

Volume and curie content of the waste discharged which was not > processed by the appropriate equipment but which required processing. ' 6. Action (s) taken to prevent a recurrence of equipment failures. This is in lieu of a Licensee Event Report. 5. System Operability and Plant Ooerations in the event a limit and/or associated acten requirements identified in Sections 12.3.A and 12.3.B cannot be satisfied because of circumstances in excess of - i those addressed in this Section, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operational mode. ~ - 12.3.B g (lggid Effluents Surveillance 1. Concentration in Unrestricted Areas The concentration of radioactive materialin unrestricted areas'shall be determined to be within the prescribed limits by obtaini_ng representative samples in accordance with the sampling and analysis program specified in _ Table 12.3-2. The sample analysis resubs_will be used with the calculational. methods in the ODCM to determine that the concentrations are within the limits.' of Section 12.3.A.1, 12-21

y. r~ ..s 1yj; j 1DRESDEN Revisiin 1.1 ^

y

.. July 1994 ' a 4 s 12.3.8 ' Liauld Effluents Surveillance (Cont'd) _

2. '

Dose from Liouid Effluents . The dose contribution' from measured quantebes of radioactive material shall be j ~ determined by calculation at least once per 31 days and cumulative summation '{ of these total body and organ' dosed shall be maintained for each calendar - 1 ' quarter. j . Doses computed at the nearest commuaity water system will consider only tho' I drinking water pathway and shall be projected using the methods prescribed in { ODCM, at least once per 92 days. 3. Dose Proiections Doses due to liquid releases to unrestricted areas (at or beyond the site boundary) shall be projected at least once per 31 days in accordance with the. l ODCM. [ t t f ?! f \\ i 5 e 9 12-22 L

m a<

m '?

~

i u_ ' i A: ? t_t. /DRESDEN

Revision 1.1

' ~~ . July 1994( = " l-j j i a TABLE 12.3 '-

'j

ALLOWABLE CONCENTRATION OF DISSOLVED -

{ ? ?.-- . OR ENTRAINED NOBLE GASES RELEASED FROM. z; ' ' ~ THE SITE TO UNRESTRICTED AREAS.: 'l - IN LIQUID WASTE i 'l m^.; NUCLIDE ACluci/mir - Kr-85m : 2 x 10 s d Kr-85 l5x10d l Kr 4 x 10 ) 4 Kr-88 9 x 10

j 8

Ar-41 7 x 10 j 4 Xe-131m ' 7 x 10 ) d Xe-133m 5 x 10 - d ' Xe-133 ' 6 x 10d t Xe-135m 2 x 10d 't Xe-135 ' 2 x110 - d -i - r Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion-- -in water, and R = 0.01 rem / week, density = 1.0 g/cc and Pw/Pt = 1.0. j !la i .e \\' 12-23

l i J 994 TABLE 12.3-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM UNIT 1 LOWER LIMIT OF TYPE OF ACTIVITY DETECTION LIQUID RELEASE SAMPLING MINIMUM ANALYSIS ANALYSIS (LLD)") (pCi/ml) TYPE FREQUENCY (6) FPEQUENCY(6) A. Service M M l-131 1x10* Water Releases M M g,rincipal Gamma Emitters 5x10'7 (4) (Grab Sample) M M Dissolved & Entrained 1x10-5 (Grab Sample) Gases

Gamma Emmitters*

' M M H-3 1x10-5 (Grab Sample) (Composite) Gross Alpha 1x10-7 O Q Sr-89, St-90 5x10* (Grab Sample) Fe-55 (Gamma Emitters) 1x10* LOWER LIMIT OF TYPE OF ACTIVITY DETECTION LIQUID RELEASE SAMPLING MINIMUM ANALYSIS ANALYSIS (LLD)") (pCi/mi) TYPE FREQUENCY (6) FREQUENCY (6) 1 B. Above Ground T T g,rincipal Gamma Emitters 5x10 Uquid Storage Tanks (7) Dissolved & Entrained 1x10~5 Gases

Gamma Emmitters*

i 6 12-24

7 ,i DRESDEN Revision 1 1t A TABLE 12.3-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM UNITS 2 & 3 l LOWER LIMIT OF TYPE OF ACTIVITY DETECTION LIQUID RELEASE SAMPLING MINIMUM ANALYSIS ANALYSIS (LLD)"3 (pCi/ml) TYPE FREQUENCY (6) FREQUENCY (6) A. Batch Prior to Prior to Principal Gamma 5x10 Release Each Batch Each Batch Emitters

1x10*

Tanks 1-131 Prior to M Gross Alpha 1x10-7 Each Batch Composite

H-3 1x104 Prior to Q

Fe-55 1x10* Each Batch Composite

Sr-89, Sr-90 5x104 Prior to M

Dissolved Entrained 1x104 One Batch /M Gases "'(Gamma Emmitters) B. Plant MA Mm l-131 1x104 Continuous (Grab Sample) () MA MA grincipal Gamma Emitters 5x10 (Grab Sample) MA MS Dissolved & Entrained 1x104 (Grab Sample) Gases") Gamma Emmitters" Mm MA H-3 1x10* (Grab Sample) Gross Alpha 1x10' QA QA St-89, Sr-90 5x104 (Grab Sample) Fe-55 (Gamma Emitters) 1x10* LOWER LIMIT OF TYPE OF ACTIVITY DETECTION LIQUID RELEASE . SAMPLING MINIMUM ANALYSIS ANALYSIS (LLD)") (pCi/mi) TYPE FREQUENCY (6) FREQUENCY (6) C. Above Ground T T grincipal Gamma Emitters 5x10-7 Liquid Storage Tanks (7) Dissolved & Entrained 1x10* Gases" s Gamma Emmitters* l 12-25

DRESDEN Revision 1.1 I TABLE 12.3-2 (Cont'd) TABLE NOTATION j 1. The LLD is defined in the ODCM. l 2. A composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. 3. If the alarm setpoint of the service water effluent monitor as determined in the ODCM is exceeded, the frequency of analysis shall be increased to daily until the condition no longer exists. 4. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the release. 5. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. Other peaks which are measurable and identificble by gamma ray spectrometry together with the above nuclides, shall be also identified and reported when the actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level fo'r that nuclide. 6. The dissolved and entrained gases (gamma emitters) for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138. Other dissolved and entrained gases (gamma emitters) which are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide. 7. A sample (s) from: Unit 1: Each of the above-grade liquid waste tanks, Units 2 & 3: The Waste Sample Tanks, Floor Drain Sample Tanks and the Waste Surge Tanks, shall be taken, analyzed, and recorded every 72 hours, if no additions to a tank have been made since the last sample, the tank need not be sampled until the next addition. i i f 12-26

i DRESDEN Revision 1.1 July 1994 12.3.C LIQUID EFFLUENTS BASES 1. Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402. 2. EQ2.0 This specification is provided to implement the requirements of Sections ll.A. Ill.A and IV.A of Appendix 1,10 CFR Part 50. The operational requirements implements the guides set forth in Section ll.A of Appendix 1. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releases of radioactive materialin liquid effluents will be kept *as low as reasonably achievable". The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix i be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be - consistent with the methodology provided in Regulatory Guide 1.109, " Calculation nf-Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR'Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.113," Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose ofimplementing Appendix I", April 1977. NUREG-0113 provides methods for dose calculations consistent with Reg Guide 1.109 and 1.113. 3. Liouid Waste Treatment The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, GeneralDesign Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section 11.D of Appendix I to 10 CFR Part 50. 1 J i 12-27

i DRESDEN . Revi: ion 1.1 -- July 1994 '12 3 C ' LIQUID EFFLUENTS BASES (Continued) 4. Mechanical Vacuum Pumo The purpose of isolating the mechanical vacuum Ene is to Emit rebase' of activity from the main condensor, During an accident, fission products would be transported from ' the reactor through the main steam Ene to the main condenser. -The fission product radioactivity would be sensed by the main steamEne radioactivity monitors which initiate' j . isolation. I 9 4 9 I 12-28

DRESDEN Revision 1.1 July 1994 12.4 GASEOUS EFFLUENTS A. Gaseous Effluents Umits and Reportina Operability l 1. Dose Rate The dose rate in unrestricted areas at or beyond the site boundary (Dresden Station ODCM Annex, Appendix F Figure F-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following. 1. For Noble Gases: (1) Less than a dose rate of 500 mrem / year to the whole body. (2) Less than a dose rate of 3000 mrem / year to the skin. 2. For iodine-131, for lodine-133, tritium and for all radionuclides in particulate form with half-lives greater than 8 days, less than a dose rate of 1500 mrem / year. 3. If the dose rates exceed the above limits, without delay decrease the release rates to bring the dose rates within the limits, and provide notification to the Commission (per 10 CFR Part 20.2203). 2. Moble Gas Dose The air dose in unrestricted areas at or beyond the site boundary due to noble gases released in gaseous effluents from the unit shall be limited to the following: 1. For Gamma Radiation 4 (1) Less than or equal to 5 mrad during any calendar quarter. (2) Less than or equal to 10 mrad during any calendar year. 2. For Beta Radiation (1) Less than or equal to 10 mrad during any calendar quarter. (2) Less than or equal to 20 mrad during any calendar year. 3. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and subtrst to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to ensure that future releases are in compliance with Sections 12.4.A.2.1 an.1 12.4.A.2.2. This is in lieu of a Ucensee Event Report. l 12-29

W i E J'0R!!N0ElAIl01D R 1 6 DRESDEN Revision 1.1 July 1994 f l 12.4.A Gaseous Effluents Limits and Reportina Oper=h%r (Cont'd)'- 1 73 4. With the calculated air dose from radioactive noble gases in gaseous j < effluents exceeding the limits of Sections 12.4.A.2.1 or 12.4.A.2.2,' prepare and submit a Special Report to the Commission within 30 days and limit the i i . subsequent releases such that the doses or dose commitment to a member l 6 of the pubuc from all uranium fuel cycle sources is limited to less than or j equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrom) over 12 consecutive months. This ( Special Report shallinclude an analysis which demonstrates that radiation-exposures to all members of the public from all uranium fuel cycle sourc,es '

(including all effluent pathways and direct radiation) are less than 40 CFR Part 190 Standard. Otherwise, obtain a variance from the. Commission to.

j permit releases which exceed the 40CFR Part 190 Standard. The radiation. exposure analysis contained in the Special Report shall use the methods, 1 prM.cribed in the ODCM. This report is in lieu of a Licensee Event Report.' 3. lodine # 31. lodine-133. Tritium. and Particulate Dose. t The dcse to a member of the public in unrestricted areas at or beyond the site - I boundary from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the unit i . shall be limited to the following. Less than or equal t~ 7.5 mrom to any organ during any calendar quarter. 51. o q 2. Less than or equal to 15 mrem to any organ during any calendar year. l 3. ' With the calculated dose from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in i gaseous effluents exceeding any of the above limits, prepare and submit to j the Commission within 30 days, a Special Report which identifies the .f cause(s) for exceeding the limit and defines the corrective actions taken to ensure that future releases are in compliance with Section 12.4.A.3.1'and - 12.4.A.3.2. This is in lieu of a Licensee Event Report. 4. With the calculated dose from the release'of iodine-131, iodine-133, tritium, J and all radionuclides in particulate form with half-lives greater than 8 days in - ll gaseous effluents exceeding the Ernits of Sections 12.4.A.3.1. or 2j 12.4.A.3.2.; prepare and submit a Special Report to the Commission within 30 days and limit subsequent releases such that the dose or dose commitment to a. i'i 4 L l 2 l 12-30

t. u u 9 L I 12.4.A ; Gaseous Effluents Limits and Reportina OneW5N (Cont'd) a member of the public from aH uranium fuel sources is Emited to less than or-i g' ' equal to 25 mrom to the total body or organ (except the thyroid, which is '. ' limited to less than or equal to 75 mrom) over 12 consecutive months. This. j Special Report shallinclude an analysis which demonstrates that radiation -l exposures to all members of the public from all uranium fuel cycle sources. l

(including all effluent pathways and direct radiation) are less than the 40 -

CFR.Part 190 Standard. Othenusse; obtain a variance from the 1 Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use the methods prescribed in the ODCM. This report is in Neu of a; Licensee Event Report. m :i U 4. Off-Gas Treatment. L At aH times during processing for discharge to the environs, proc'ess and ' l 1. control equipment provided to reduce the amount of concentration of 1 radioactive materials shall be operated.~ 2. . The above specification shaN not apply for the Off-Gas Charcoal Adsorber - ] Beds below 30 percent of rated thermal power. j[ 3. The recombiner shall be operable whenver the reactor is operating at a pressure greater than 900 psig. i 4. The recombiner may be inoperable for 48 hours. y ? 5. With either the recombiners inoperable, or all charcoal beds by-passed for i more than 7 days in a calendar quarter while operating above 30 percent of l the rated thermal power, prepare and submit to the Commission within 30 i days a Special Report which mciudes the following information.- a. Identification of the defective equipment.' ) b. Cause of the defect in the equipment, Action (s) taken to restore the equipment to an operatin' g status, c. d. . Length of time the above requirements were not satisfied. e. Volume and curie content of the waste discharged which' was not ~ processed by the inoperable equipment but which required ! processing. t 12-31

P: g[ 1 JL DRESDEN Revision 1.1 July 1994 12.4.A Gaseous Effluents Limits and Reportina Operability (Cont'd) f. Action (s) taken to prevent a recurrence of equipment failures. This is in lieu of a Licensee Event Report.

5. -

Main Condenser Air Elector The release rate of the sum of the activities from the noble gases measured at the main condenser air ejector shall be limited to 100 microcuries/sec per MWt (after 30 minutes decay) at all times. With the release rate of the sum of the activities from noble gases at the main condenser air ejector exceeding 100 microcuries/sec per MWt (after 30 minutes decay), restore the release rate to within its limits within 72 hours, or be in at least HOT STANDBY within the next 12 hours. 6. System Operrbility and Plant Operati_o.ns in the event a limit and/or associated action requirements identified in Sections 12.4.A and 12.4.B cannot be satisfied because of circumstances in excess of those addressed in this Section, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operational mode. 1 j 4 s i 12-32 ) i

1 3. g l ' 12.4.B Gaseous Emuents Surveillance l -1. Dose Rate ~ i t., The dose rates due to radioactive materials released in gaseous emuents from the ' 1 . site shall be determined to be within the prescribed Emits by' obtaining ' l wx representative samples in accordance with the sampEng and analysis program.. specified in Table 12.41. The dose rates are calculated using methods prescribed, in the ODCM. l ( - 2. Noble Gas Dose .i The air dose due to releases of radioactive noble gases in gaseous emuents shall' ,j be determined to be within the prescribed limits by obtaining representative samples in'accordance with the sampling and analysis program specified in Sections A and1 B of Table 12.4-1:~ The allocation of emuents between units having shared emuent ' l control system and the air doses are determined using methods prescribed in the 'ODCM at least once ever 31 days. _i 3. lodine-131. lodine-133. Tritium and Par +ieu!ste Dose 'l

I 6

The dose to a member of the public due to releases of iodine-131, iodine-133, tritium, and all radionucEdes in particulate form with half-Eves greater than 8 days ' . shall be determined to be within the prescribed Emits by obtaining representative ( ' ci samples in accordance with'the sampEng and analysis program specified in Table. 12.4 1. For radionuclides not determined in each batch or weekly composite, the dose - contribution to the current calendar quarter cumulative summation may be estimated -- .I by assuming an average monthly concentration based on the previous monthly or [ quarterly composite analyses.' However, fer reporting purposes, the calculated dose ' contributions shall be based on the actual composite analyses when possible. p i The allocation of effluents between units having shared effluent control systems and ' [ the doses are determined using the methods prescribed in the ODCM st least once every 31' days.' L h 4. Off-Gas Treatment Doses due to treated gases released to unrestricted areas at or beyond the site ) boundary shall be projected at least once per 31 days in accordance with the .i 'ODCM. / f I

l i

t 12-33 6 e ,,,..-.-y w ,. - - - - ~

p = lj DRESDEN R;visi:n 1.1 July 1994 . = 12.4.B Gaseous Effluents Surveillance - Continued 5. ' Noble Gases at the Main Condenser Air Elector 1 The radioactivity release rate of noble gases at (near) the outlet of the main condenser air ejector shall be' continuously monitored. The release rate of the sum of the activities from noble gases from the main condenser air ejector shall be L determined to be within the limits of 12.4.A at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the recombiner outlet, or at the air ejector outlet if the recombiner is by-passed. 1. At least once per 31 days. 2. Within 4 hours following an increase, as indicated by the main condenser i air ejector noble gas activity monitor, or greater than 50%, after factoring out increases due to changes in thermal power level and off-gas flow, in the nominal steady -state fission gas release from the primary coolant. i b j i 1 4 4 s 12-34

.h 11 . DRESDEN Revision 1,1 July 1994 ) Table 12.4 ' j RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM - ) l. . UNIT 1 i i LOWER LIMIT OF GASEOUS SAMPLING MINIMUM TYPE OF DETECTION (LLD)N RELEASE FREQUENCY. ANALYSIS. ACTMTY _ (pCl/ml)- l TYPE FREQUENCY ANALYSIS t A. Main Principal Gamma 1x10 f d Chimney M E d ers

M (Grab Sample)

Tritium 1x10 4 Noble Gases M 1s104 M"* b131 1x10* (Continuous) lodine Sample I-133 1x10 " 4 .i Mm M" Principal Gamma Particulate 1x10'" . i (Continuous) Eminers

Samplem O

O Sr-89, Sr-90 1x10'u (Continuous) Gr ss Alpha Part cu te Sample I J l l l - i k 12:35

I l 99 ( Table 12.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM UNITS 2 & 3 i LOWER LIMIT GASEOUS SAMPLING MINIMUM TYPE OF ACTIVITY OF RELEASE FREQUENCY ANALYSIS ANALYSIS DETECTION TYPE FREQUENCY (LLD)m (pCl/ml) A. Main -i ""'Y d m Principal 1x10 O'* Idg (Giab ample) M t Vent Stack B. All W" l-131 1x10-52 nunu usg3 Release lodine Sample I-133 1x10 " 4 Types as wm Principal Gamma l Listed Continuous") Edem* 1x10* Particulate Sample nA (1-131, others) above Q Sr-89 1x10'" Continuous") Composite Particulate Sample Sr-90 1x10'" i Continuous") Gross Alpha 1x10'" Com osite Particulate Sample n nuous* NoNe Gas Monitor Now Mses 1x10* hi ney D. Reactor Bldg. Vent Continuous") Noble Gas Monitor Noble Gases 1x10d Stack 42 i l-131 1x10 Continuous") I 40 Process lodine Sample l-133 1x10 Exhaust Sampler ge) Principal Gamma Emitters

1x10'"

Particulate Sample (1-131, others) WS l-131 1x10 : 4 Continuous )s AC lodine Sample I-133 1x10 ' 4 Exhaust 's Sampler gei Principal Gamma Emitters

1 x10'"

Particulate Sample (I-131, others) 12-36

~ f g DRESDEN Revision 1.1 July 1994 TABLE 12.4-1 (Cont'd) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION 1. The lower limit of detection (LLD) is defined in the ODCM. 2. Sampling and analyses shall also be performed following shutdown, startup, or a thermal power. change exceeding 20 percent of rated thermal power in 1 hour unless (1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. 3. Samples shall be changed at least once per 7 days and the analyses completed within 48 hours after removal from the sampler. Sampling shall also be performed within 24 hours following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal power in one hour. This requirement does not apply if 1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 5, and 2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of

3. When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10.

4. The ratio of sample flow rate to the sampled stream flow rate shall be known. 5. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions, and Mn-54, Fe-59, Co-60,2n-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. Other peaks which are measurable and identifiable by gamma ray spectrometry, together with the above nucides, shall be also identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for the nuclide. 6. Analysis frequency shall be increased to 1/ week if release rates exceed 1% of any applicable I limit referenced in the ODCM, when added to Units 2 and 3 airborne effluents. j i 4 i 12-37 ~

h' 2 m DRESDEN- 'R isi:n 1 4 12.4.C Gaseous Effluents Bases - '1. I Gaseous Effluents - Dose : This.Section is provided to ensure tha't the dose at the unrestricted area boundary from

gaseous effluents from the units on site will be within the' annual dose limits of -

10CFR20 for unrestricted areas.- These limits provide reasonable assurance that. radioactive material discharged in gaseous ofnuents will not result in the exposure of an individualin an unrestricted area to annual average concentrations exceeding the Emits specified in Appendix B, Table 2 of 10CFR20.1001-2402. The release rate limits ' restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to 500 mrom/ year to the total body or to less than or equal to 3000 mrem / year to the skin.. These release rate Emits also restrict, at all times, the corresponding thyroid dose rate above background via the*1nhalation pathway to less than or equal to 1500 mrem / year. a For purposes of calculation doses resulting from airborne releases, the main chimney is considered to be an elevated release point and the reactor building vent stack is considered to be a mixed mode release point. 2. Dose. Noble Gases ^ This Section is provided to implement the requwements of Sections 11.B, lli.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements implement the guides set forth in Section 11.3 of Appendix l.- The statements provide the required operating flexibility and at the same time implement the guides set forth in' Section IV.A of Appendix i to assure that the releases of radioactive materialin gaseous effluents will be kept "as low as is reasonably achievable.", The surveillance requirements implement - the requirements in Section Ill.A of Appendix 1 that conformance with the guides of j Appendix I is to be shown by calculational procedures based on models and data such - that the actual exposure of an individual through the' appropriate pathways is unukely to j be substantially underestimated. The dose calculations estabEshed in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents : -l for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix l," Revision 1 October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric { - Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water. -( Cooled Reactors," Revision 1. July.1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. 1 i 3 12-38 1 -,.-i

"s. .s } 4 ?" 2."' p DRESDEN ' Revision ~1.1 ~ July 1994 12.4.C Gaseous Effluents Bases (Cont'd)i ,= 4 ,1 ~ ' 3. Dose: Radiciodines. Radioactive Materialin ParhMe Form and Radionuclides Other, than Noble Gases This Section is provided to implement the requirements $f Sections ll.C, Ill.A and IV.A - of Appendix 1,10 CFR Part 50. The OperabiNty Requirements are the guides set forth in.' Section ll.C of Appendix 1. The statements provide the required operating flexibiNty and -

)

at the same time implement the guides set forth in Section TV.A of Appendix 1 to. assure, I that the releases of radioactive materials in gaseous effluents will be kept "as low as. j reasonably achievable." The ODCM calculatenal methods specified in the surveillance ~ requirements implement the requirements in Section Ill.A'of Appendix l that. -i ' conformance with the guides of Appendix I be shown by calculational procedures based - on models and data such that the actual exposure of an individual through appropriate - j pathways is unEkely to be substantiauy undereselmsted..The ODCM calculational methods approved by,NRC for calculating the doses due to the actual release rates of : the subject materials are required to be consistent with the methodology provided in i Regulatory Guide 1.109.(" Calculation of Annual Doses to Man from Routine Releases : of Reactor Effluents for the Purpose of Evalualme CompEance with 10 CFR Part 50, Appendix 1", Revision 1, October.1977 and Regulatory Guide 1.111; " Methods for - i Estimating Atmospheric Transport and Despemion of Gaseous Effluents in Routine-. Releases from I ight-Water-Cooled Reactors," Revision 1, July 1977.(These equations : also provide for determining the actual doses based upon the historical average i atmospheric conditions. The release rate limits for radiciodines, radioactive materialin particulate form and radionucEdes other than noble gases are dependent.on the existing . radionuclide pathways to man, in the unrestricted area. The pathways which _were examined in the development of these Emits were: 1) individualinhalation of airborne : radionucEdes,2) deposition of radionucRdes onto green leafy vegetation with subsequent consumption by man and 3) deposition onto grassy areas where milk-animals graze with consumption of the rnilk by man. 4. Gaseous Waste Treatment ' 1 The operability of the gaseous waste treatment which reduces amounts or' concentrations of radioactive materials ensures that the system will be available for use ~i whenever gaseous effluents require treatment prior to release to the environment. The' requirement that the appropriate portions of this system be operable when specified j provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "a8 low as reasonably achievable". This specification implements -l the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 1 10 CFR Part 50, and design objective Section ll.D of Appendix 1 to 10 CFR Part 50. j l I 4 12-39 i -.u - +. --a. ~.--.. - - ~. - ~,

~. 4n [ n k E n u g 1 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l A. ' Radiolooical Environmental Monitorina Prooram .] i 4 1. The Radiological Environmental Monitoring Program given in Table 12.5-1 shall l 1 'Lb be conducted except as specified below. i 2. With the Radiological Environmental Monitadng Program not being conducted J as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the l reasons for not conducting the program as required and the plans for preventing. a recurrence.' Deviations are permitted from the required sampEng schedule if specimens are unobtainable due to hazardous conditions, seasonal - . unavailability, contractor omission which is corrected as soon as discovered,. malfunction of sampling equipment, or if a person who participates in the l program goes out of business; if the equipment malfunctions, corrective actions shan be completed as soon as practical. If a person supplying samples goes j out of business, a replacement suppEer will be found as soon as possible.. All deviations from the sampling schedule shou be describe in the Annual Report. 3. When the level of radioactivity in an environmental sampling medium at one or j more of the locations specified in the Table 12.5-1 exceeds the Emits of the - Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a - Special Report which includes an evaluation of any release conditions,. j . environmental factors or other aspects which caused the Emits of the Table 12.5-2 to be exceeded. This report is not required if the measured level of I radioactivity was not the result of plant emuents; however in such an event the 'l condition shall be reported and described in the Annual. Radiological ] Environmental Operating Report.' 4. With milk samples unavailable from one or more of the sample locations. -l required by Table 12.5-1, identify locations for obtaining replacement samples - and add them to the Radiological Environmental Monitoring Program within 30 days;. The locations from which samples were unavailable may then be deleted. from the monitoring program. In Neu of Licensee Event Report, identify the j cause of the unavailabikty of samples and identify the new location (s) for ' obtaining replacement samples in the Annual Radiological Environmental .1' Operating Report and also include.in the report a revised figure (s) and table reflecting the new location (s). -i 1 'i ) y ~h j J, l 4., j i i 12-40 I L i 6

-_-_7 i DRESDEN-Revision 1,1 ' July 1994 k 12.5.A Badioloaical Environmental Monitorina Proaram (Cont'd) - ' 5. ~ A census of nearest residences and of animals producing milk for human , consumption shall be conducted annually (during the grazing season for-F . animals) to determine their location and number with respect to the site. The - nearest residence in each of the 16 meteorological sectors shall also be - determined within a distance of five miles. The census shall be conducted j - under the following conditions: ^l 1. Withm a 2-mile radius from the plant site, enumeration of animals and. i l nearest residences by a door-to-door or equivalent counting technique. -l 2. .Within a 5-mile radius, enumeration of animals by using referenced information from country agricultural agents or other reliable sources. L i, 6. With a land use census identifying location (s) of animals which yield (s) L, calculated dose or dose commitment greater than the values currently being - calculated in Section 12.4.A.3, the new location (s) shall be added to the Radiological Environmental Monitoring Program within 30 days, if possible. The sampling location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was~ conducted. - 7. Radiological analyses shall be performed on samples representative of those in : Table 12.5-1, supplied as a part of the Interlaboratory Comparison Program -I which has been approved by the NRC. 8. With analyses not being performed as required, report the corrective actions. taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. 9. System Operability and Plant Operations-In the event a limit and/or associated action requirements identified in Sections ~ 12.5.A and 12.5.B cannot be satisfied because of circumstances in excess of i those addressed in these Sections, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into any operational mode. B. Radioloaical Environmental Monitorina Surv#ance ' 1. The radiological environmental monitoring samples shall be collected pursuant to Table 12.5-1 from the locations specified in the ODCM and shall be analyzed pursuant to the requirements of Table 12.5-3. I - 12-41

e [0E([Eb bl[l$[0[] O N RESDEN Re on 1 12.5.B Radiolooical Environmental Monitorina Surveillance (Cont'd) 2. The results of analyses performed on radiological environmental monitoring samples shall be summarized in the Annual Radiological Environmental Operating Report. 3. The land use census shall be conducted at least once per twcNe months between the dates of June 1 and October 1 by a door-to-dooraurvey, aerial survey, road survey, or by consulting local agriculture authorities. 4. The results of the land use census sha!! be included in the Annual Radiological Environmental Operating Report. 5. The results of the analyses performed as part of the required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report. The analyses shall be done in accordance with ODCM Table 11-1. i l 12-42

ye~ t t * " q " 1 Q"" ^ " O M i, I,I DRESDEN Revision 1.0 bdNNMi Ukdf I s January 1994 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MINIMUM NUMBER EXPOSURE PATHWAY OF SAMPLES AND SAMPLING AND TYPE AND AND/OR SAMPLE SAMPLE COLLECTION FREQUENCY OF LOCATIONS

FREQUENCY ANALYSIS 1.

AIRBORNE A. Particulates 17 locations Continuous operation of Gross beta and gamma sampler for a week isotopic as specified in ODCM Table 11-1. B. Radiolodine 17 locations Continuous operation of I-131 as specified in sampler for two weeks ODCM Table 11-1. 2. DIRECT 42 locations (Minimum Quarterly RADIATION of two TLDs per packet) 3. WATERBORNE ' A. Surface Water 2 locations M'onthly composite of Gamma Isotopic weekly collected samples analysis of each composite sample B. Sediment 1 downstream location Annually Gamma Isotopic in receiving body of analysis of each sample water C. Plant CooEng Water intake, Discharge Vyeekly Composite Gross Beta analysis of each sample 4. INGESTION A. Milk 2 locations At least once weekly when I 131 analysis of each animals are on pasture; at sample least once per month at other times B. Fish 1 location in receiving SemiannuaHy Gamma isotopic 1 body of water analysis on edible portions

Sample locations are described in ODCM Chapter 11.

\\ 12-43

' -~ p ~ p'. 4, s. DRESDEN

Revision 1.0

=. -~ January 1994 g ~

llC3 -

hi ' Table 12.5-2 m REPORTING LEVELS FOR RADIOACTIVITY O~ CONCENTRATIONS IN ENVIRONMENTAL SAMPLES .L' "..D:a.

I -

d . C3 FOOD' ANALYSIS. WATER AIRBORNE PARTICULATE FISH MILK. PRODUCTS Q (pCi/I) OR GASES (pCi/m') (pCi/Kg, wet) (pCi/1) (pCi/Kg, wet) ' .g D W H 2 X 10*. (see Note 1) 8 Mn-54 1 X 10 3 X 10' 2 Fe-59 4 X 10 1 X 10' Co-58 1 X 10' 3 X 10* Co-60 3 X 10' 2 X 10 Zn-65 3 X 10' 2 X 10' Zr-Nt>MS - ' 4 X 10 2 2 1-131 2 - 0.9 3 1 X 10 Cs-134 30 10 1 X 10' 60 2 X 10' Cs-137 50 '20 1 X 10' 70 2 X 10' 2 2 Ba-La-140 2 X 10 3 x 10 Note: 1) For drinking water samples. This is 40 CFR Part 141 value. 12-44 ..-~. . -. _.... -... - - -,..... - -.,. -. -. -. ~. -,.... - -. -.--.~..-.-.:-- -,.:-,-. - - -.... -...

-DRESDEN . Revision 1.0 . January 1994 ' Table 12.5 "Tt PRACTICAL LOWER LIMITS OF DETECTION (LLD) FOR STANDARD 'C3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM N QQ (LLD)* O c2 g3-SAMPLE MEDIA ANALYSIS (4.66o) UNITS ((] X:.;;s - r-3 3 Airborne

Particulate
Gross Beta
0.01 pCi/m'(C)

-CJ vms Gamma Isotopic 0.01 pCi/m'(C) jd Airborne I-131 lodine-131 0.10 pCi/m'(C) Milk /Public Water 1-131 SW pCi/1 Cs-134 10 pCi/1 Cs-137 10(C) pCi/l Tritium 200 pCi/1 Gross Beta" 5 pCi/1 Gemme isotopic 20 pCi/1/nuclide Sediment Gross Beta" 2 pCi/g dry Gamma Isotopic 0.2 - pCi/g dry Fish Tissue I-133-Thyroid 0.1 pCi/g wet Cs-134,137 ' O.1 ' pCi/g wet - Gross Beta

1.0 pCi/g wet Gamma Isotopic 0.2 pCi/g wet Note:

A. 0.5 pCi/I on milk samples collected during the pasture season. B. Reference to Cs-137 C. 5.0 pCi/1 on milk samples (Notes continued next two pages) "-45

p p qg DRESDEN Revision 1,1 .,[ t ) b' EU U d ty "Udttml py q =p } July 1994 Table 12.5-3 (Cont'd) PRACTICAL LOWER LIMITS OF DETECTION (LLD) FOR STANDARD - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ~ TABLE NOTATION D. The LLD is the smallest concentration of radioactive materialin a sample that will be detected with 95 percent probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation) 4.66 (S) LLD = (A)-(E)-(V)-(2.22) (V)-(exp (-Aat))-(t) Where: LLD is the "A priori" tower limit of detection for a blank sample or background analysis as defined above (as pCi per unit mass or volume). S, is the square root of the background count or of a blank sample count; is the estimated - standard error of a background count or a blank sample count as appropriate (in units of counts). E is the counting efficiency (as counts per disintegration). A is the number of gamma rays omitted per disintegration for gamma ray radionuclide analysis (A = 1.0 for gross alpha and tritium measurements). V is the sample size (in units of mass or volume). 2.22 is the number of disintegrations per minute per picocurie. Y is the fractional radiochemical yield when applicable (otherwise Y=1.0). A is the radioactive decay constant for the particular radionuclide (in units of reciprocal minutes). At is the elapsed time between the midpoint of sample collection and the start time of counting. (t = 0.0 for environmental samples and for gross alpha measurements). t is the duration of the count (in units of minutes). The value of "S," used in the. calculation.of the LLD for a. detection system shall be based on an actual observed background count or a blank sample count (as appropriate) rather than on an unverified theoretically predicted value. Typical values of "E", "V", "Y", "t" and "at" shall be used in the calculation. ?., a 12-46

r= 4 ! !t et DRESD'N-Revision 1.1~ w L. a E v.. July 1994 g Table 12.5-3 (Cont'd).- ~ PRACTICAL LOWER LIMITS OF DETECTION (LLD) FOR STANDARD z RADIOLOGICAL ENVIRONMENT L MONITORING PROGRAM TABLE NOTATIONS For gamma ray radionuclide analyses the background counts are determined from the total counts in the channels which are within plus or minus one FWHM (Full Width at Half Maximum)' of the gamma ray photopeak energy normany used for the quantitative analysis for that' radionuclide.- Typical values of the FWHM shall be used in the calculation. The LLD for all measurements is defined as an "A priori"(before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular sample measurement. E. ' Other radionuclides which are measurable and identifiable by gamma ray spectrometry, together with the nuclides indicated in Table 12.5-3, shall also be identified and reported when an. actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall - not be reported as being present at the LLD level for that nuclide. 4 .a i 1247 -l

Q > ;qpf[ f i... ' ' gn I y 9 i ' 112.5.C Radioloaldal Environmental Monitorina Proaram Bases 1. Monitonna Proaram 1 The radiological environmental monitoring program required by this Section provides rnessurements of radiation and of radioactive materials in those exposure pathways and , for those radionuclides, which lead to the highest potential radiation exposures 'of-individuals resulting from the station operation. This monitoring program thereby ~ . supplements the radiological effluent monitoring program by verifying that the measurab' concentrations of radioactive materials and levels of radiation are not higher-c than expt;ted on the basis of the effluent measurements and modeing of the environmental exposure pathways.' Program changes may be initiated based on operational experience. The detection capabiNties required by Table 12.5-3 are state-of-the-art for routine. environmental measurements in industrial laboratories..The specified lower Emits of. detection for 1-131 in water, milk and other food products correspond to approximately one-quarter of the Appendix 1 to 10 CFR Past 50 design objective dose-equivalent of 15 mrem / year for atmospheric releases and 10 mremfyear for liquid releases to the most sensitive organ and individual; They are based on the assumptions given in Regulatory; Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor : Effluents for the Purpo'se of Evaluating Compliance with 10 CFR Part 50, Appendix I"r October 1977, except the change for an infant consuming 330 liter / year of drinking water instead of 510 liters / year. e 2. Land Use Census ~ This Section 's provided to ensure that changes in the use of unrestricted areas are. i ~ identified and that modifications to the monitoring program are made if required by the. results of this census. This census satisfies the requirements of Section IV.B.3 of. -{ Appendix l to 10 CFR Part 50. 3. Interlaboratory Comparison Proaram. The requirement for participation in the Interlaboratory Comparison Program is provided l .to ensure that independent checks on the precision and accuracy of the measurements ) of radioactive materialin environmental sample matrices are performed as part of the ' quahty assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. >I 9 i 1 i W 12-48 -) a.:

, r e - 8 3 77 ""J 9 ' N [ 7 j YadI DRESDEN Revision 1.1 iO h' had W h l y July 1994 ) 12.6 RECORDKEEPING AND REPORTING 1 1. Station Operatina Recogg 1 1. Records and/or logs relative to the fo!!owing items shall be kept in a manner convenient for teview and shall be retained for at least five years. 1. Records and periodic checks. inspection and/or calibrations performed to verify the surveillance regurements (See the applicable surveillance in the Instrumentation, Liquid Effluents, Gaseous Effluents, and Radiological Environmental Monitoring Sections) are being met. All equipment failing to meet surveiBance requirements and the corrective action taken shall be recorded. 2. Records of radioactive shipments. 2. Records and/or logs relative to the fo3owing items shall be recorded in a manner convenient for review and shat be retained for the life of the plant. 1. Records of off-site environmental monitoring surveys. 2. Records of radioactivity in Equid and gaseous wastes released to the environment. 3. Records of reviews performed for changes made to the ODCM. 2. Reports 1. Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted to the Commission according to the Technical Specifications. The report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR Part 50.36a and Section IV.B.1 of Appendix 1 to 10 CFR Part 50. 2. Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted according to Technical Specifications. The report shallinclude summaries, interpretations, l and analysis of trends of the results of the Radiological Environmental l M,onitoring Program for the reporting period. Thu rnaterial provided shall be consistent with the objectives in (1) t% ODCM and (2) Sections IV.B.2., IV.B.3, and IV.C of Appendix 1 to 10 CFR t' art 50. A detailed listing of the requirement i of the report is given below: 12-49

. ~ T \\ g p'/ p ~v 3

j Ig

~ g qM y.- n..; 112.6.2 Egggs. Continued - d W V34

r

. Results of environmental sampling summarized on a quarterly basis ~- 1x following the format of Regulatory Guide 4.8 Table'1 (December.1975);. 1 4 . (individual sample results will be retained at the station);.

l.:

. In the event that some resu'ts are not available for inclusion with the j report, the report shall be sutmtled noting and explaining the reasons .i for the missing results. ' Summanos, interpretations, and analysis of. l trends of the results are to be provided.- (b) An assessment of the monitoring res0lts and radiation dose via the ' principal pathways of exposure resulting from plant emissions of ; radioactivity including the maximum noble gas gamma and beta air- ~ doses in the unrestricted area.. The assessment of radiation doses 1 shall be perfonned in accordance with the ODCM. ] (c) . Results of the census to determine the locations of animals producing { milk for human consumption, and the pasture season feeding practices i at dairies in the monitoring program.' .l 1 (d) The reason for the omission if the nearest dairy to the station is not in i the monitoring program. i ? (e) An annual summary'of meteorological conditions concurrent with the - 'l releases of gaseous effluents in the form of joint requency distributions ( of wind speed, wind direction, and atmospheric stability, l 4 (f) The results of the interlaboratory comparison program described in 1i Section 12.5.A.7. (g) The results of the 40 CFR Part 190 uranium fuel cycle dose analysis for. each calendar year.' ~ n (h) A summary of the monitoring program, including maps showing. j sampling locations and tables giving distance and direction of sampling locations from the station. 1 3. Non-Routine Environmental Report i y l (a) - If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting level given in Table 12.5-2 and if the radioactivity ~ q ' is attributable to plant operation, a written report shall be submitted to j the Regional Administrator of NRC Regional Office, with a copy of the i Director, Office of. Nuclear Reactor Regulation; within 30 days from the - l and of the quarter. When more than one of the radionuclides in Table

{

12.5-2 are detected in the medium, the reporting level shall have been exceeded if SC/(RL),is equal to or greater than 1 where C is the concentration of the i* radionuclide in the medium and RL is the - reporting level of radionu' elide i. f 12-50

I ggh [ g g QtIfigy Q TU b 5 ME U !}L $ hIlUId U[g!. ~ 1 DRESDEN Revision 1.1 July 1994 12.6.2 Reports - Continued (b) If radionuclides other than'those in Table 12.5-2 are detected and are due to plant effluents, a reporting levelis exceeded if the potential - annual dose to an individualis equal to or greater than the design objective doses of 10 CFR Part 50, Appendix 1. (c) This report Wilinclude an evaluation of any release conditions, environment.1 factors, or other aspects necessary to explain the. anomalous affect. 12.6.3 Offsite Dose Calculation Manual f0DCM). i 1. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquideffluent monitoring Alarm / Trip setpoints and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monsonng Programs required by Technical Specification Sections 3.2.F. 3.2.G 3.8.A. 3.8.B and 3.8.E and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications Sections 6.6.C.1 and 6.6.C.2 (Upgraded Technical Specifications. l-6.9.A.3 and 6.9.A.4). Methodologies and calculational procedures acceptable to the Commission are contained in NUREG-0133. The ODCM shall be subject to review and approval by the Commission prior to initialimplementation. 2. Changes to the ODCM: (1) Shall be documented and records of reviews performed shall be retained as required by Specification 6.5.B (Upgraded Technical Specification 6.10.B). This documentation shall contain: (a) SLfficient information to support the change together with appocriate analyses or evaluations justifying the change (s); and (b) ' A deterrnination that the change will maintain the level of radioactive effluent control required by.10 CFR Part 20.1302,40 CFR Part 190,10 CFR Part 50.36a, and Appendix ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or set point calculations. (2) Shall be effective after review and acceptance by the Onsite Review & Investigative Function and the approval of the Station Manager, on the date specified by the Onsite Review and Investigative Function. k 12-51

p l N< m h1 .DRESDEN Rv on g a. 12.6.3: Offsite Dose Calculation Manual (ODCM)-(Cont'd) (3)- Shall be submitted to the Commission in the form of a complete, legible.! copy of the entire ODCM as a part of or concurrent with the j 1 Semiannual Radioactive Effluent Release Report for the period of the" i l report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected. l pages, clearly indicating the area of the page that was changed, and. shall indicate the date (e.g., month / year) the change was implemented. t 1 12.6.4. Maior Channes to Radioactive Waste Treatment Systems (Llouid and Geseous) NOTE: This information may 'be submitted as part of the annual FSAR update.: ~ i 1. Licensee initiated major changes to the radioactive waste systems may be made provided. The change is reported in the Monthly Operating Report for the period in which - the evaluation was reviewed by the On-Site Review and Investigative Function. l The discussion of each change shall contain: (1) ' A summary of the evaluation that led to the determination that the I change could be made in accordance with 10 CFR Part 50.59; - (2) Sufficient detailed information to support the reason for the change; 6 (3). A detailed description of the equipment, components l and process g involved and the interfaces with other plant systems;_ 'i (4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from l those previously predicted in the license application and amendments;. . (5) ~ A comparison of the predicted releases of radioactive materials in liquid ' 1 and gaseous effluerits to the actual releases for the period in which the changes were made; (6) An estimate of the exposure to plant operating personnel as a result of . the change; and. 1 1 (7) Documentation of the fact that the' change' was reviewed and found acceptable by the On-Site Review and investigative Function. 2. The change shall become effective upon review and acceptance by the On-Site-Review and investigative Function. 1 s 12-52 g l l.

= -~ CATEGORY 3 ou o7-42 1 Ravrszou o 4 v" y Mi. DRESISM NUCLEAR POWER STATION PROCE28 CONTROL PROGRAM-p,; 'Requirementes Technical. specifications, Section 6.9, Process Control Program ) .

TECH SPECS 6 13,. Process Control Progras18

) ' I E1li4F0E1AT10MU i i ) I Special Controls / Reviews: 1. Revisions to this procedure sust he Onsite-reviewed. 2.- Revisions to this procedure must be reviewed by the Radweste coordinator. !-l l L. Ferrell originator J. She11an l Department Procedure Writer M. Nikota/R. Papach Technical moviewer/veritter t - ) T. Nauman-l Authorisation-32 factive Date l j l -i i 1 of 9 l 'w y 7-T -r

-y w

e p) av e

CATEGORY 3 DAP 07-42 REVISION O j DREIDI:N NUCLEAR POWER STATION PROCE'S CONTROL Ph0 GRAM 1 \\ A. GLDIKt y i The purpose of the Dresden Nuclinar Power Atation (DNPE) Process Centrol Program (*CP) is to establish the process parameters which will provide a reasonabis assurance t. hat all Iow-Level Radioactive Waste (LLRW) processed at Dresden station will meet or exceed any and all acceptance criteria for processing, packaging, onsite storage, and shipment of LLRN to Licensed Burial Facilities. These criteria include all Department of Transportation (DOT), Nuclear Regulatory Commission (NRC), State, and Licensed Burial Pacilities' rules and regulations for the processing, packaging, on-site storage, and shipping of LLRW. Although Stock squipment Company Cement solidification system was installed during 1979, DNPS currently uses commercial, Vendor - Euyplied Processing Systems for the processing of the primary liquid LLRN streams generated by the station. Commonwealth Edison requires that all vendors used to process liquid LLRW at DNPS must meet all applicable Commonosalth Edison Co. pality standards and shall have submitted a Prccess Systen Topical Report to the NRC. Furthermore, the vendor solidification / stabilization media must be approved by the Licensed Burial sites. B. USER REFEFENCES: f 1. Technical specificacions, Units 1, 2, & 3. Section 1.0 Definition of Process Control / Program.eTECK s. SPECS 1.0, Definition of Process Control Program

b.

Section 6.9, Procesa Control Program.

TECH SPECS 6.13, Process Control Program
2.

Procedures. a. DAP 02-27, Integrated Reporting Process IRP. b. DAP 10-01, Onsite Review and Investigative Function / Plant Operations Review Committee (PORC). c. DAP 10-02, 10CFR50.59 Review Screenings and Safety Evaluations. d. DOP 2000 Series, Radwasto operating Procedures. m. Vendor Procedures. 2 of 9 )

CATEGORY:3 pYI}' dg,s @7 ( RAP 07 'S ' L gli - [ REV2SION O B. 3. Commonwealth Edison Progree for Implementation of 10 CFR Part 61 'h and 10 CFR Part 20.311 Dated December 22, 1983. 4. Cosmonwealth Edison Quality Resurance Manual. 5. 10 CFR Part 20.311, Transfer for Disposal and Manifests.. 6. 10 CFR Part 61, Licensing Requirements for the Land Disposal of Radiosotive Waste. 7. 10 CFR Part 71, Packaging and Transportation of Radioactive Material. 8. 49 CFR Part 173, General Requirements for shipments and Packaging. C. ERY DEFINITIQMS: HQ25 i The following definition of the PCP is from Tech Specs 1.0 Definition of Process Control /Frogram.

TECH SPECS 1.0, Definition of Process Control Program
1.

PROCESS GurERAL PROGRAM iPCPh - shall contain the current formulas, sampling, analysis, test and determination to be made to ensure that processing and packaging of actual or simulated wet solid wastes will be accompiinhed in such a way to assure i compliance with 10 CFR Parts 20, 61, and 71, State Regulations, ( burial ground requirements, and other requirements governing the j disposal of solid radivactive wasta. 2. EGLIBIFICEFIBK - Liquid Wasta processed to either a stable or unstable free standing sonolith. D. SUPPLEMENTA NONE. E. POLICI 1. Records of license reviews performed for changen made to the PCP program shall be maintained for the life of the plant. 2. The PCP shall be approved by the conuniseien prior to implementation. 3. All waste streams shall be classified per 10 CFR 61.55 and meet l the waste characteristics per 10 CFR part 61.56. 4. station and Vendor Procedures shall be followed to comply with this PCP. 3 of 9 I

\\ CATEGORY 3 NAP 07-42 .0kthf 0{f ) asas + Steps E.5 and E.6 are required by Tech specs 6.9, Process control l Program.

TECH SPscs 6.13, Procese Control Prograst*

L. - E. 3. Changes to the PCP shall be documented. This documentation shall contains Sufficient information to support the change together with a. the appropriate analyses of evaluations justifying the change (s), and l b. A determination that the change will maintain the overall i conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations. 6. Changes shall become effective after review and acceptance by the On-site Review Function, and the approval of the Station Manager per DAP 10-01, Onsite Review and Investigative Function / Plant operations Review committee (PORC). i 7. Because all solidificatiore is performed by vendors, the Vender Process control Procedures contain the formulas, sampling, analysis, test and determination required to be made to ensure that processing and packaging of waste is accomplished to assure compliance with the required regulations. l 8. If any of the PCP criteria are not satisfied, resulting in a defective product, then the shipment of the defective product shall be suspended until a root cause determination has been identified per DAP 02-27, Integrated Reporting Process IRP. 9. Major Changes to Radioactive Waste Treatment Systems may be made provided that the change.,is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by the On-site Review Function. The discussion of each change shall contains a. (1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CPR 50.59, per DAP 10-02, 10CPR50.59 Review screenings and Safety Evaluations; (2) sufficient detailed information to support the reason for the changes 4 of 9

CATEGORY 3 -ohr o7-42 E3 OM11tT011 E.Y ,E.. 9. a. (3) .A detailed description of the equipment, componente, and process involved and the interfaces with other plant systems; (4) An evaluation of the change which shows the predicted quantity of solid waste that differ from those previously predicted in the License application and amendeontes (5) A comparison of the predicted quantity of radioactive materiale in solid waste to the actual quantity for the period in which the changes vers.mados (6) An estimate of the exposure to plant operating personnel as a result of the change; and (7) Documentation of the fact that the change was reviewed and found acceptable by the On-Site Review Function. b. The change shall become effective upon review and acceptance j by the On-Site Review Function. The changes may be made by submitting this information as c. part of the annual RUPSAR update. d. All references to the stock solidification system have been deleted from the PCF, as Dresden presently uses a Vendor Solidification Process only. The stock Solidification system never functioned as intended and because of changing regulations on the solidification PCF, the use of Contract' vendor services proved to be more cost effective over using the stock system. F. PROCEDURE 1. VENDOR PROCESS SYSTENf$1: DNPs currently uses m cial, Vendor supplied, processing 4. r systone for the processing of the primary liquid LIJtw I streams generated by the Station. b. commonwealth Edison requires that all Vendors used to process liquid LLRN at DNPS must east all applicable Commonwealth Edison Co. quality standards and shall have j submitted a Process System Topical Report to the NRC. 1 Furthermore, the vendor solidification /stabilisation media must be approved by the Licensed surial sites. 5 of 9 ) i t

p a.n2 x .s a a a +-- - CATEGORY.'3-g} g[hy Dam o a _n .. -..... s rs... Liquid radwaste processing consists of dowatering, a. solidification, vendor supplied filter / process system, or an evaporative process to treat the following waste stremess' spent resin, concentrated ligulds, sludges, filter media, filter cartridges and oil, b. Spent ion-exchange resin is collected in the spent Rosin Tank prior to processing for disposal. (1) Spent resin may originate from any one of the following systemes e-Condensate. Fuel Pool. Reactor Water clean Up. e Floor Drain Processing system. l t Ra6 waste Equipment Drain Processing systema. e (2) Rosine are allowed to settle in the spent Resin Tank i and then are diecharged to the vendor Processing System via a resin water giurry, i (3) vendor resin beds are also used for decontamination of plant systems such as the Spent Fuel Poc1, RNcu, and i SDC. These resins are then handled by the Vendor Processing system. l l c. CONCENTRATED WASTES: In general, various drains and sump discharges are collected in Floor Drain Collector Tank and/or waste collector Tank for weste treatment. .i (1) Water from these tanks can be sent through a filter or domineraliser prior to being sent to the Max Recycle System where it is concentrated ~utilising-the Max t necycle Concentrator or Vendor supplied processing systems. i (2) The Max Recycle Concentrator boils off the water into a distillate and a concentrate. The distillate is eent to waste systees for filtration,'dominera11sation and plant re-use 93 discharged to the river. The concentrates are periodically discharged to the vendor ( processing system for waste treateent. i 1 6 of 9

- pf))j}]'h[j h[ CATEGORY-.' 3 one o7-42. REVISIOst 0 F. 2. d. i ?l FILTER ELUDGBS: Filtering devices using precoat media are used at DNPS in a variety of process streams. f (1) These devices are used primarily for the removal of auspended solide from the liquid waste streams. t (2) The precoat material from these devices are routinely { removed from the filter vessel and discharged to a Filter sludge Tank. (3) Periodically, the filter sludge is. discharged to the { ~ Vendor Processing System for waste treatment. e. LUBRICANTS AND/OR OILS: Various lubricants and oils become contaminated as a-consequence of normal operating and maintenance activities. These contaminated lubricants / oils i are processed for treatment on an as needed basis using a l

Vendor, f.

FILTER CARTRIDGES: Various f11ter cartridges are dried and ~ placed into a High Integrity Container (e) (NIC) for disposal or are encapsulated in an In-Situ Liner for waste I processing. g. ACTIVATED HARDWhRE: Activated Hardware is stored in the-i spent Fuel Pools. I 3 (1) The waste includes itama euch as:- Control Rods, Fuel Channels, and Nuclear Instrumentation. (2) These items are processed periodically using remote i underwater handling equipment provided by a Vendor. (3) The waste is then put into a liner for shipment and/or j t storage. i 3. DRY ACTIVE WASTE thmute t Dry Active Waste such as paper,. wood, plastic, cardboard, hoses, cloth and metals, etc. become contaminated as a consequence of j normal operating and maintenance activities. a. DAW is collected, surveyed and sorted for compatible and non-compatible wastes. i b. Contaminated compatible waste is packaged in containers to c f acilitate on-site pre-compaction and/or off-site super- } compaction or incineration. Contaminated Non-compatible DAN is sorted to provide an I c. efficient handling method for waste treatment. l I 7 of 9 i i ,_4 e w

CATEGORY 3 Dnp'o7-da a m.., m-mq --o _ F. 3. .d. In addition, Dhw ' items are surveyed for release when applicabis. '4. s costnaaY WARTE STREAMSt Periodically, wastes are generated from such sources as decontaminations, tank cleanings, sump cleanings, dried sewage Treatment Plant Weste, waste oil and other waste from cleanup of inadvertent contaminations. Wastes generated in this manner are sampled on a batch a. . basis. ~ b. i Appropriate formulas for rationing solidification agent to i waste are developed on small bench samples, or if the consistency of the waste is known, from established, j formulas. I secondary waste streams such as Dhw (Dry Active waste) and c. activated hardware are packaged and handled as a case by 1 case bases. samples of the above waste streams are obtained I and analysed by DNPs personnel per approved procedures. 5. I.t[fP4CTIQM1 All shipping containers are inspected for compliance with DOT, station, On-site storage, and/or. burial site { requirements prior to use. .i a. When applicable, containers of Concentrated Waste, spent l Mesin and sludges, are inspected for quality of ] solidification and/or dowatering requirements. b. Dewatering requirements for the station /Surial site is <2% } free standing water. ? (1) If free standing water or poor solidification is observed, then samples of the particular series of i batches is taken for root cause determination. t (2) Additional samples may be taken, as warranted, to J ensure free standing water'and solidification requirements are maintained. Process parameters in'use during the production of these c. containers will be investigated and corrective actions taken j as warranted. 6. SHIPMEalT All wastes shipped off site are packaged in DUI i approved shipping containers. I All transport vehicles must meet the appropriate DOT and NRC .l a. requirements prior to loading. l b. Packages are inspected and shipments (vehicles) are inspected for compliance with DOT, NRC and Burial Site criteries prior to leaving the site. s of 9

' CATEGORY 3 Day o7-42 s fi G. PISCUSSIDE NONE. W. WRITER'S BEFERENCES: 1. NRC Branch Technical Position on Waste Forin. 2. NURaG 0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants - October 1978. 3. Dresden Final Safety Analysis Report, 11.4, Solid Maste Management System. l l 9 of 9

7 FOR 11F0NA0010D l f ^ l [ QUAD CITIES F DPR-29' ],

6. 9 PROCESS CONTROL PROGRAM (PCP).

l A. The PCP shall contain the sampling, analysis, and formulation } determination by which solidification of radioactive wastes from liquid systems is assured. 8. The PCP shall be approved by the Commission prior to implementation. C. Licensee initiated changes may be made to the PCP provided the change: 1. Shall be submitted to the Commission in the Semi-Annual Radioactive Effluent Release Report for the period in which the change was made and shall contain: Sufficiently detailed information to support the change; a. b. A determination that the change d'id not reduce the'overall-conformance of the solidified waste product to existing criteria for solid wastes; and c. Documentation that the change has been reviewed and found-acceptable by the onsite review function. 2. Shall become effective upon review and acceptance by the onsite review function. V f-, 6.9-1 Amendment No. 114

c: QUAD CITIES Revision 1.0 o January 1994 g t, This page reserved for GENERIC QUAD CITIES ANNEX INDEX CHAPTER 12.0 All pages in Chapter 12.0 are designated REVISION 1.0 SPECIAL NOTE Until removal of the Radiological Effluent Technical Specifications has been approved by the Nuclear Regulatory Commission, the requirements of the Technical Specifications shall take precedence over this chapter, should any differences occur. 12-i yy v3 Y f[ g

p . ;^, . QUAD CITIES: Revision 1.0 : ~ January 1994 p, $l ~, g: hf RAGE REVISION R&gg REVISION .j p .j J "12'- i' 1.0 12 - 46 1.0 12:- 11 -1.0-12 -47

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k.% - 9 1

n. -QUAD CITIES Revision 1.0 ) I, I January 1994 L { 0s Ei O CHAPTER 12 . RADIOACTIVE EFFLUENT TECHNICAL STANDARDS ~ (RETS) TABLE OF CONTENTS 12.1 DEFINITIONS-12-1 12.2-INSTRUMENTATION 12-6 1. Radioactive Liquid Effluent p Instrumentation Operability 12-6 2. Radioactive Gaseous Effluent Instrumentation Operability 12-8 12.3 LIQUID EFFLUENTS 12-16 1. Concentration 12-16 2. Dose 12-16 3. Liquid Radioactive Waste Treatment System 12-19 4. Liquid Radioactivt Waste Treatment 12-19 5. Systems Operability and Plant Operations 12-20 12.4 GASEOUS EFFLUENTS 12-26 1. Dose Rate 12-26 2. Noble Gas Dose 12-27 3. Iodine-131, Iodine-133 and Particulates Dose 12-29 4. Off-Gas Treatment 12-31. 5. . Systems Operability and Plant Operations 12-32 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-37 1. Radiological' Environmental Monitoring. Program 12-37 2. Land Use Census 12-39 3. Nearest Residente & Milk Animal Census 12-39 4. Interlaboratory Comparison Program 12-40 5. Systems Operability-and Plant Operations 12-40 Radiological Environmental 6. Monitoring Program Bases 12-46 12.6 REcoRDKEEPING AND REPORTING 12-47 1. Station Operating Records 12-47 1. Radioactive Effluent Release Report 12-47 2. Annual Meteorological and Environmental Radioactivity Monitoring Report 12-47 3. Changes to the ODCM 12-49 4. Major Changes to Radioactive' Waste Treatment Systems (Liquid and GaseousE2-50 h f -' 1 L 12-iii e l, _ _ _ _ _ _ ~.. - - - -

r QUAD CITIES-Revision 1.0 V January 1994 . }, t ] r CEAPTER 12- ' J. -RADIOACTIVE EFFLUENT TECENICAL' STANDARDS.. (RETS) LIST OF TABLES -0 m TITLEPAGE 12.2-1 Radioactive Liquid Effluent Monitoring ' Instrumentation 12-9 12.2-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 12-10 12.2-3 Radioactive Gaseous Effluent Monitoring Instrumentation 12-11 12.2-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements .12-13. 12.3-1 Allowable Concentration of Dissolved or Entrained Noble Gases Release from the Site to Unrestricted Areas in Liquid Waste 12-21 12.3-2* 12.3-3 Radioactive Liquid Waste Sampling and Analysis 4 Program 12-22 12.4-1 Radioactive Gaseous Waste Sampling and Analysis Program ~ 12-33 12.5-1 Radiological Environmental Monitoring Program 12-41 12.5-2 Reporting Levels for. Radioactivity Concentrations In Environmental Samples 12-42 12.5-3 Practical Lower Limits of Detection (LLD) 12-43

'At present, there is no Table 12.3-2 in this. chapter.

12-iv

QUAD CITIES Revieion 1.0 January 1994 12. l '- Definitions 12.1.1 channel calibration - A Channel Calibration shall be the adjustment, as necessary, of the Channel output such that it responds with the necessary range and accuracy to known values of the parameter which the Channel monitors. The Channel. Calibration ^shall encompass the entire Channel including.the sensor and alarm and/or trip functions, and shall include the Channel Functional Test. The Channel Calibration may be perfomed by any series of sequential, overlapping or total Channel steps such that'the entire Channel is calibrated. 12.1.2 channel check - A Channel Check shal'1 be the qualitative assessment of Channel behavior during operation by observation. This determination-shall include, where possible, comparison of the Channel indication and/or status with other indications and/or status derived from independent instrument Channels measuring the same parameter. 12.1.3 Channel Function Test - A Channel Functional Test shall be: a. Analog Channels - the injection of a. simulated signal into the Channel as close to the sensor as practicable to verify Operability including alarm and/or trip functions and Channel failure trips. b. Bistable Channels - the injection of a simulated signal into the sensor to verify Operability including alarm and/or trip functions. The Channel Functional Test may be performed by any series of sequential, overlapping or total Channel steps such that the entire Channel is tested. 12.1.4 Dose Ecuivalent I-131 - Dose Equivalent I-131 is that. concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose. conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors For Power and Test Reactor Sites." 12.1.5 Hot Standbv - Hot standby means operation with the reactor critical, system pressure less than 1060 psig, the main steam isolation valves closed, and thermal i power not exceeding 15%. 12.1.6 Immediate - Immediate means that the required action will be initiated as soon as practicable considering 1 the safe operation of the unit and the importance of j the required action. i 12-1

y. QUAD CITIES Revieion 1.0-1 3 4 r y January 1994 l d 12.1.7 Member (s) of the Public - Members of the Public means an individual in a controlled or unrestricted area. However,-an. individual is not a member of the public during any period in which the individual receives an occupational dose. 12.1.8 Modes switch Interlock - A reactor mode switch selects the proper interlocking for the operating or shutdown condition of the plant. Following are the reactor mode switch positions and interlocks provided: 1. Shutdown - In this position, a reactor scram is initiated, power to the control rod drives is removed, and the reactor protection trip systems have been deenergized for 10 seconds prior-to permissive for manual reset. 2. Refuel - In this position, interlocks are established so that one control rod only may be withdrawn when flax amplifiers are set at the proper sensitivity level and the refueling crane is not over the reactor. Also the trips from the turbine control valves, turbine stop valves, main steam isolation valves, and condenser vacuum are bypassed. If the refueling crane is over the. reactor, all rods must be fully inserted and none can be withdrawn. 3. S2hrtun/ Hot Standhv - In this position, the reactor protection scram trips, initiated by condenser low vacuum and main steamline isolation valve closure, are bypassed, the low pressure main steamline isolation valve closure trip is bypassed, and the reactor protection system is energized, with IRM and APRM neutron monitoring system trips and control rod withdrawal interlocks in service. 4. Hun - In this position, the reactor system pressure is at or above 825 psig and the reactor protection system is energized with the APRM protection and RBM interlocks in service (excluding the 15% high flux scram). 12.1.9 Offsite Dose Calculation Manual (ODCM) - The Offsite i Dose Calculation Manual shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Sections 12-5 and (2) descriptions of the information that chould be included in the Radioactive Effluent Release Reports and in the Annual Radiological Environmental Operating Reports required by Sections 12.6.2.1 and 12.6.2.2. 12-2

-,-i-- y AD CITIES Revi:: ion 1.0 L L January 1994 12.1.10 ooerable - Ocerability - A system, subsystem, train, component, or device shall be Operable or have Operability when it is capable of performing its specified function (s). Implicit in this definition' shall be the assumption that is necessary attendant instrumentation, controls, normal and energency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system,. subsystem, train, component or device'to perform its function (s) are also capable of performing their related support function (s). 12.1.11 oneratina - Operating means that a system, subsystem, train, component or device is performing its intended functions in its required manner. 12.1.12 Oneratina cycle - Operating Cycle is the interval between the end of one Refueling Outage for a particular unit and the end of the next subsequent Refueling Outage for the same unit. 12.1.13 Process Control Procram (PCP) - The. Process Control Program shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated. processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. 12.1.14 Protective Instrumentation Definitions - Protective instrumentation definitions are as follows: a. Channel - A Channel is an arrangement of a sensor and associated. components used to evaluate plant variables and produce discrete outputs used in logic. A Channel terminates and loses its identity where individual Channel outputs are combined in a logic. b. Trin Svstem - A Trip System means an arrangement of instrument Channel trip signals and auxiliary equipment required to initiate action to accomplish a protective trip function. A Trip System may require one or more instrument Channel trip signals related to one or more plant parameters in order to initiate Trip System action. Initiation of Protective Action may require the tripping of a single Trip System or the coincident tripping of two Trip Systems. Protective Action - An action initiated by the c. protection system when a limit is reached. A Protective Action can be at the Channel or system level. 12-3

y QUAD CITIES Revician 1.0 January 1994 gh0$$hb &k-d. . Protective Function - A system protective action which results form the Protective Action of the Channels monitoring a particular plant condition. 12.1.15 Rated Thermal Power - Rated Thermal Power means a steady-state power level of 2511 thermal megawatts. - 12.1.16 Reactor Power Oneration - Reactor Power Operation is any operation with the mode switch in the Startup/ Hot Standby or Run position with the reactor critical and above 1% Rated Thermal Power. 12.1.17 Reactor Vessel Pressure - Reactor Vessel Pressures listed in the Technical Specifications, unless otherwise indicated, are those measured by the reactor vessel steam space. detector. 12.1.18 Refuelino Outace - Refueling Outage is the period of time between the shutdown of the unit prior to a refueling and startup of the plant subsequent to that refueling. For the purpose of designating frequency of testing and surveillance, a Refueling Outage shall mean a regularly scheduled Refueling Outage; however, where such outages occur _within 8 months of the completion of the previous Refueling Outage, the required surveillance testing need not be performed -until the next regularly scheduled outage. 12.1.19 Source check - Source Check is the qualitative assessment of instrument response when the sensor is exposed to a radioactive source. 12.1.20 Definitions Related to Estimatina Dose to the Public Usina the Annendix I Comnuter Procram: a. Actual - Refers to using known release dat'a to project the dose to the public for the previous month. This data is stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12. b. Proiected - Refers to using known release data from the previous month or estimated release data to forecast a future dose to the public. This data is HQI incorporated into the database. 12-4 l e -t

QUAD CITIES Revician 1.0 _ January 1994 I-( l This page is intentionally left blank. l l l i r [ 4 i 12-5

m.. P. QUAD CITIES Revision 1.0-nG,MTgg i '-' ~ .12.2 INSTRUMENTATION 12.2.1.B Radioactive Licuid Effluent Tnstrumentation 12 2.1.A Radioactive Licuid Surveillance Effluent Instrumentation Onerability Anolicabilitv: Applies t'o'the' periodic Acolicability: Applies to measurements'of j radioactive radioactive effluents'from effluents. the plant. Each radioactive liquid effluent monitoring instrument shown in The effluent monitoring Table 12.2-2 shall be inr:rumentation shown in Table demonstrated operable by 12,;.1 shall be operable'with performance of the given source al.irm setpoints set to ensure check, instrument check, the the limits of Section 12.3 calibration, and functional test are not exceeded. The alarm operations at the frequencies i set.7oints shall be determined in shown in Table 12.2-2. sceordance with Section 10.2. 1. With a radioactive liquid effluent monitoring instrument alarm / trip setpoint less conservative than required, without delay l suspend the release of radioactive liquid effluents i monitored by the affected / instrument, or declare the ' instrument inoperable, or change the setpoint so it is i acceptably conservative. 2. With one or more radioactive liquid effluent monitoring instruments inoperable, take j the action shown in Table 12.2-1. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. 1 l 12-6

QUAD CITIES Revision 1.0 7-,.,. . January 1994 i ~ FORU!FORMAll0W DNI.Y l .[12.2.1.A Radioactive'Liouid 12.2.1.B Radioactive Liauid L Effluent Tnstrumentation Effluent Tnstrumentation Onerability Surveillance t ~ 3.- In.the~ event a limiting -condition for operation and. associated action i requirements cannot be satisfied because of 1 -circumstances'in excess of those addressed in the specifications, provide a' 30-day written' report to the i NRC and no changes are -required in the operational 1 condition of the plant, and this does not prevent the plant from entry,into an operational ~ mode, r i .i. -i i I i t f O i r r P t 12-7 m.

_ _~ QUAD CITIES Revision 1.0 : ay e { ) ~ January.1994 1 'd

i. '

i - 12. 2. 2. A-Radioactive nameous-12.2.2.B Radioactive Gameous .I

Effluent Instrumentation Effluent-Inntrumentation.

\\C Onerability Surveillance I LThe effluent monitoring Each radioactive gaseous ' instrumentation shown in Table radiation monitoring instrument 12.2-3 shall be operable with in Table 12.2-4 shall be i alarm / trip setpoints set to. demonstrated-operable by . cnsure.that the limits of Section performance of the given source l 12.'4 are not exceeded. The check, instrument check, alarm / trip setpoints shall be calibration, and functional test detarmined in accordance with the operations at the frequency Section 10.1. shown in Table 12.2-4. l s 1. With a-radioactive gaseous effluent monitoring Linstrument alarm / trip set- [ point less conservative than i required, without delay. suspend the release of radioactive gaseous effluents monitored by the affected i instrument, or declare the instrument inoperable, or ' change the setpoint so it is -acceptably conservative. 2. With one or more radioactive . gaseous effluent monitoring /~ instruments inoperable, take the action shown in Table. 12. 2 - 3. - Exert best efforts i ) to return the instrument to operable status within 30 days and, if unsuccessful, explain in:the next~ Semi-Annual Radioactive Effluent Release Report why i the inoperability was not i corrected in a timely manner. This is in lieu of an LER. 3. In the event a limiting j condition for-operation and associated action i requirements cannot be satisfied because of circumstances in excess of those addressed in the specifications, provide a 30-day written report to the NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode. 12-8 1

[

QUAD, CITIES' Revision 1.0

~ January 1994 p L. TABLE 12.2 ! RADIOACTIVE LIQUID EFFLUENT' MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Functional Source lh Instrument check (1) Calibrat ion (1 ) ( 3 ) Test (1) (2 ) check (1) Liquid Radwaste Effluent - D R Q-(7) (6) . Gross Activity Monitor Service Water Effluent-D 'R Q (7) R Gross Activity Monitor. ' Liquid Radwaste Effluent (4) R NA NA Flow Rate Monitor Notes '(1) D = once per 24 hours M.= once per^31 days l 0 = once per 92 days R = once per 18 months. P S = once per 6 months 1 (2) The Instrument Functional Test shall also demonstrate that control j room alarm annunciation occurs, if any of the following conditions exist, where applicable, lI" Instrument indicates levels above the. alarm setpoints, a. b. Circuit failure, c. Instrument indicates a downscale failure. d. Instrument controls not set in OPERATE mode. (3) Calibration shall include performance.of a functional test. (4) Instrument Check to verify' flow during periods of release. (5) Calibration shall include performance of a source check. (6) Source check shall. consist of observing instrument response during a discharge. l (7)- Functional test may be performed by using trip check and test circuitry associated with the monitor chassis. b 12-10

1 l QUAD CITIES Revision 1.0 ) \\ t TABLE 12.2-1 I 1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum No. of Operable Total No. Channels of Channels Parameter Actionm 1 1 Service Water A Effluent Gross Activity Monitor 1 1 Liquid Radwaste C Effluent Flow Rate Monitor 1 1 Liquid Radwaste B Effluent Gross Activity Monitor j Notes Action A: With less than the minimum number of operable channels, releases via this pathway may continue, provided that at least once per 12 hours grab samples are collected and analyzed for beta or gamma activity at an LLD of less than or equal to 104 uCi/ml. Action B: With less than the minimum number of operable channels, effluent releases via this pathway may continue, provided that prior to initiating.a release, at least 2 independent i samples are analyzed in accordance with Section 12.3.A.1, and at least 2 members of the facility staff independently l verify the release calculation and discharge valving. Otherwise, suspend release of radioactive effluents via this pathway. Action C: With less than the minimum number of operable channels, releases via this pathway may continue, provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be utilized to estimate flow. i 12-9 T-T

QUAD CITIES Revision 1.0 Jmnuay 1994 1kti J x TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum No. i of Operable Total No. ChannelsG) of channels Parameter Action 93 1 2 SJAE Radiation Monitors D l 1 2' Main Chimney Noble A e Gas Activity Monitor 1 1 Main Chimney Iodine C I Sampler 1 1 Main Chimney C Particulate Sampler 1 1 Reactor Bldg. Vent B Sampler Flow Rate Monitor 1 1 Reactor Bldg. Vent C Iodine Sampler i 1 1 Reactor Bldg. Vent C i Particulate Sampler i 1 1 Main Chimney Sampler B Flow Rate Monitor i 1 1 Main Chimney Flow B Rate Monitor 1 2 Reactor Bldg. Vent E Noble Gas Monitor l 1 1 Main Chimney F High Range Noble Gas Monitor Notes (1) For SJAE monitors, applicable during SJAE operation. For other instrumentation, applicable at all times. l (2) Action A: With the number of operable channels less than the I minimum requirement, effluent releases via this pathway may continue, provided grab samples are taken at least once per 8 hour shift and these samples are analyzed within 24 hours. 12-11

QUAD CITIES Revision 1.0 MV January 1994 yAQ Mf f i M" , y< n-1 s c, [e. ' TABLE 12.2-3 (Con't) l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION - Action B: With the number rf operable channels less than the minimum required, effluent releases via this pathway may continue provided that the flow rate is estimated at least once per 4 hours. Action C: With less than the minimum channels operable, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling. equipment, as required in Table 12.4-1. Action D: With less than the minimum channels operable, gases from the main condenser off gas system may be released to the environment for up to 72 hours provided at least one chimney monitor is operable; otherwise, be in hot stand-by in 12 hours. Action E: With less than the minimum channels operable, immediately suspend release of radioactive effluents via this pathway. Action F: With less than the minimum channels operable, initiate the preplanned alternate method of monitoring the appropriate parameter (s) within 72 hours, and: (1) either restore the inoperable channel (s) to operable status within 7 days of the event, or ~ (2) prepare and submit a Special Report to the Commission within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status, i 4 1 1 i .i 12-12

QUAD CITIES Revision l'.0-J January 1994 I TABLE 12.2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE-REQUIREMENTS Instrument' Calibra-Functional SourceL Instrument Mode (2) check (1) t ion (1) ( 4 ) Test (1) (3 ) Checkf1) ~ Main Chimney Noble Gas. B D R Q-M Activity Monitor- ' Main Chimney Sampler B D R O '1 NA l ? low Rate Monitor Reactor Bldg. Vent Sampler B D R Q1 NA Flow Rate Monitor Main Chimney Flow Rate B D R Q NA Monitor Reactor Bldg Vent B D R Q Q Activity Monitor j ~ SJAE' A D R Q R Main Chimney Iodine and B Dl58 NA NA NA Particulate Sampler l Reactor Bldg. Vent Iodine B Dl51 NA NA NA and Particulate Sampler j Main Chimney High Range B D(51 8 0 l Noble Gas Monitor I' Notes (1) D= once per 24 hours M= once per 31 days Q= once per 92 days R= once per 18 months (2) A= during SJAE operation B= at all times (3) The' Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable: I a. Instrument indicates levels above the alarm setpoint b. Circuit failure c. Instrument indicates a downscale failure d. Instrument controls not set in OPERATE mode 12-13

_r l', -QUAD CITIES-Revi9 ion 1.0 January 1994 Jh) 3 '( 's -(^ TABLE 12.2-4.: (cont 'd) j .. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE ~ REQUIREMENTS (4)- Calibration shall. include' performance of-a functional test. '(5) Instrument check to verify operability of the instrument; that the instrument is in place and functioning _ properly. j '(6) Functional test shall be performed on local switches providing low flow 'l alarm. j 1 i l l i i i k 3 4 1 12-14 _a

[l .~ \\ ~ ' [' .QUADTCITIES Revision 1.0. 7 ' January 1994 l 4 lh k 12.2.C' LIOUID AND GASEOUS' EFFLUENTS INSTRUMENTATION BASES r l ?1. The radioactive liquid and gaseous effluent instrumentation'is- _provided to monitor.the release of radioactive materials in -liquid and gaseous effluents during releases. The alarm-setpoints for.the' instruments are provided to ensure that the alarms will occur prior.to exceeding.the limits-of RETS and 10 CFR 20. a i ? ? I t t P i e ) f ? .Ii l t ) - i ~) 12-15 i i a- -~

QUAD CITIES Revision 1.0 16 Januazy 1994 i pgg WORBM,, Fs

l

- 12 '. 3. A Licuid Effluents Limits 12.3.B Liauid Effluents add Renortina Surveillance I .1. The concentration of radioactive material released 1. The concentration of form the site to unrestricted radioactive material in l areas (at or beyond the site unrestricted areas shall be j boundary, see Quad Cities determined to be within the Station ODCM Annex, Appendix prescribed limits by. F, Figure F-1) shall be obtaining the representative limited to the concentrations samples in accordance with specified in 10-CFR Part 20, the sampling and analysis i Appendix B, Table 11, Column program specified.in Table l 2 with the Table 12.3-1 12.3-3. The sample analysis I. values representing the MPC's results will be used with i for noble gases. the calculational methods in the ODCM to determine that j With the concentration of the concentrations are radioactive material released within the limits of from the site to unrestricted Specification 12.3.A.l. E areas exceeding the above limits, without delay j decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the l con.;entration to within the a j above limits. A 2.

a. The dose contributions 2.

The dose or dose commitment from measured quantities l above background to a member of radioactive material of the public from shall be determined by radioactive materials in calculation at least once i liquid effluents released to per 31 days and a unrestricted areas (at or cumulative sufmnation of l beyond the site boundary) these total body.and I from the site shall be organ doses shall be limited to the following: maintained for each I a. During any calendar quarter: (1) Less than or equal to 3 mrem to tla whole body. (2) Less than or equal to 10 mrem to any organ. i 12-16

~ i QUAD J,ES pli Revision 1.0 - i 'S .12. 3. Ai Liouid Effluents Limits 12.3.B Lionid Effluents add Renortina Surveillance i I 3' b. During any calendar year: i

b. Doses computed at the (1)

Less:than or equal nearest community water to 6 mrem to the system will consider only [ whole' body. the drinking water t . pathway and shall be (2) Less than.or equal projected using the e to 20 mrem to cny methods prescribed in the-organ. ODCM at least once per 92 ~ days. c. With the calculated dose from the release of radioactive materials in-liquid effluents. exceeding'any of the above limits, prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit (s) i and defines the l corrective actions taken and the proposed actions to be taken to ensure that future releases.are in compliance with 12.3.A.2.a & b. This is. j 8 in lieu of a Licensee Event Report. 1 d. With.the calculated dose from the release of radioactive materials in [ liquid effluents exceeding the limits of Specification 12.3.A.2.a. I or 12.3.A.2.b., prepare I and submit-a Special .i Report to the Commission within 30 days and limit .j the subsequent releases .i such that the dose or dose commitment to a member of the public from l 12-17 I .r. d

+ g g g $ h B "F ^Y' QUAD CITY Revision NO w.

12. 3. A.-

Liould Effluent s L4mits il2.3.B Liould Effluents l 4 ~ mid'Recortina-Surveillance i all uranium fuel cycle l 1- - sources'is limited to. less than or. equal'to 25 mrem to the; total body or . any organ,(except thyroid, which is limited, to less than or equal to-t 75 mrem):over 12 consecutive-months. This Special Report shall include an analysis which demonstrates that l radiation exposures to a all members of the public from.all uranium fuel-cycle sources (including all_ effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise obtain a variance from i the Commission to permit releases which exceed the 40 CFR Part 190 Standard. ~ e The radiation exposure 7 analysis contained in the Special Report shall use I methods prescribed in the ODCM. This report is in lieu of a Licensee Event I Report. 3. e. With the projected annual j whole body or any internal organ dose computed at the nearest downstream community I water system is equal to or exceeds 2 mrem from I all radioactive materials released in liquid d effluents from the I Station, prepare and submit a Special Report within 30 days to-the operator of the community. .i water system. I t [ 12-18 i i b e r v ,m-iw- .-a 4

" QUAD CITIES: Revision 1.0 N 12.3.A Licuid Ef fluents Limi ts - 12.3.B Lionid Effluents 11Dd Reportina Surveillance-The report is' prepared to assist the-operator in meeting the requirements of 40 CFR 141: EPA Primary Drinking. Water Standards. A copy of this report will be'sent to.the NRC. This is in lieu of a Licensee Event p Report. .3. At all times during 3. Liquid Waste. Treatment processing prior to discharge L -.to the environs, process and a Doses due to liquid control equipment provided to releases to unrestricted reduce the amount or areas (at or beyond the concentration of radioactive site boundary) shall be materials shall be' operated projected at least once c Lwhen the projected dose due per 31 days in accordance .to liquid effluent releases-with ODCM. 'to unrestricted areas (see 2 Figure 12.5-1), when averaged over 31 days, exceeds 0.13 mrem to the total body or i 0.42 mrem to any organ. 4. If liquid waste has to be or is being discharged without treatment as required above, i prepare and submit to the Commission within 30 days, a report'which includes the following information: i l a. Identification of the defective. equipment. i b. Cause of the defective equipment. c. Action (s) taken to restore the equipment to an operating status. i I ..d. Length of time the above requirements were not satisfied. t I 12-19 h.c,. _..4

QUAD CITIES - Revician 1.0 ~ ,; } f 3' - 12. 3.' A

Liould Effluents IImits b

gnd Reportina

5.

In the event-a limited' and/or' associated action-requirements identifiedi in Sections 12.3.A and 12.3.B-cannot be . satisfied because-of' < circumstances in excess of those addressed ~in this Section,,no changes -are-required in'the operational condition of the plant, and this does not prevent the plant from entry into an - operational mode. 3 4 4 12-20

.c. g ;.r 3..:, QUADJCITIES-Revision-1.0 I January.1994 .l =

1..E P

'L A S 3. ' ;I n' 5,. i i .f TABLE 12.3-1~- AT T.OWABLE CONCENTRATION OF DTESOLVED QB ENTRAINED NOBLE GASEE FFT.FASED FROM THE - .. SITE TO UNRESTRICTED AREAS IN LIOUID WASTE l i NUCLIDE . ACfuci/ml)* i i Kr-85m. 2x10-* 'j i Kr-85L 5x10-4

l l

Kr-87 4x10 !n Kr-88 9x10-5 Ar'41 7x10-5 ~ Xe-131m 7x10-8 j .i a Xe-133m 5x10-* -j Xe-133 6x10-4 Xe-135m 2x10-8 l Xe-135 2x10-8 -i 1 -i 1 Computed from Equ'ation 20 of ICRP' Publication2-(1959), ) adjusted for infinite cloud submersion'in water, and R = 0.01 rem / week,' density = 1.0 g/cc abd Pw/Pt ='1.0. y 12-21 t ,v + m r- ,-r.r. = w d

QUAD CITIES Revision 1.0 1-B January 1994 -(M,L g g gA M. c' TABLE 12.3-3 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF LOWER LIMIT OF TYPE FREQUENCY FREQUENCY ACTIVITY DETECTION ANALYSIS (LLD) (uci/ml) A. Prior to Each Prior to Each Principal Gamma 5 x10-' Batch Batch Dnitte rs' I-131 1 x10-' Prior to Each M, Gross Alpha 1x10-' Bat *h Wacter Re3'.tse Tanks Batch Composite

Prior to Each Q

Fe-55 1x10-' Batch Composite

Sr-89, Sr-90 5 x 10-'

Prior to One M Dissolved & 1x10-8 Batch /M Entrained Gases' (Gamma Emitters) B. M' (Grab Sample) M* I-131 1x10-' Pls..t Continuous Principle Gamma 5x10-' Re]enseu Emitters' Dissolved and 1x10-5 Entrained Gases' (Gamma Emitters) H-3 1x10-' Gross Alpha 1x10-' O' (Grab Sample) Q* Sr-89, Sr-90 5x10' Fe-55 1x10-* 12-22

i m QUAD' CITIES-Revisim3 1.0-T~ 1 I January 1994 f z.gt M B n g..

i TABLE 12-3-3 (Continued)

RADIQACTIVE' LIQUID WASTE SAMPLING' f AND ANALYSIS PROGRAM } TABLE NOTATION 'I a.- The LLD is defined in Notation A of Table 11-3. b. A composite sample is one.in'which the quantity of. liquid samples ^ 'is' proportional to the quantity of liquid waste discharged and in-which the method of sampling enployed results in a specimen which is representative of the liquids released. c. If the alarm.setpoint of the service water effluent monitor as determined in the ODCM is exceeded, the frequency of analysis shall be increased to daily until the condition.no longer exists. d. A batch release is'the discharge of liquid wastes.of a discrete l volume. Prior to sampling for analyses, each batch.shall be isolated then thoroughly mixed to assure representative sampling. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system.that has an input flow during the release. The principal gamma emitters for which the LLD specification e. applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Csl37, Ce-141, and Ce-144. other peaks which are measurable and identifiable by gamma. ray i spectrometry together with the above nuclides, shall be also j identified and reported when the actual analysis is performed on a sample. Nuclides which are below the.LLD for the analyses shall not be reported as being present at the LLD level for that-nuclide. 1 f. The dissolved and entrained gases (gamma emitters) for which the LLD specification applies axclusively are the following j radionuclides: Kr-87, Kr-28 Xe-133, Xe-133m, Xe-135, and Xo-138. i Other dissolved and entrained gases (gamma emitters) which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide. -l i l 1 12-23

c = QUAD CITIES ReviCion 1.0 January 1994 k! 4 12.3.C^ LTOUID EFFLUENTS BASEM Ib i 1. Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402. The concentration limit for noble gases was converted to an i equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2. 2. Dose This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Ltmiting Condition for operation' implements the guides set forth in Section II.A of Appendix I. The statements provide the required operating flexibility and at the same time Lxplement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculations in the ODCM inplement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that w the actual. exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive naterials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Conpliance with 10 CFR Part 50, Appendix I*, Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluencs from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977._ NUREG-0113 provides methods for dose calculations consistent with Reg Guide 1.109 and 1.113. 12-24 1

^ r QUAD CITIES Revision 1.0' i January 1994 ,g ggg@NWp 12.3.C-LTOUID EFFLUENTS BASE 9 fCONT.1 3. Liquid Waste Treatment The operability of the liquid radwaste treatment system ensures that this system will.be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". -This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section 11.D of Appendix I to 10 CFR Part 50. i e l I i 12-25

QUAD CITIES Revision 1.0 January 1994 i

pt t.gggf0 Rial @g 12.'4. caseous Effluents

?l2.4.A. caseous Effluents Limits 12.4.B caseous Effluents and Renortino surveillance t .1. The dose' rate in' unrestricted 1. The' dose rates due to areas (at or beyond'the site radioactive materials boundary, see Quad Cities released in gaseous Station ODCM Annex, Appendix effluents.from the site i F, Figure F-1) due to shall be determined to be -radioactive materials within the prescribed limits released in gaseous effluents-by obtaining representative i from'the site shall be samples in accordance with. limited to the following: the sampling and analysis program specified in Table a. For Noble Gases: 12.4-1. The dose rates are calculated using methods = (1) Less than 500 prescribed-in the off-Site mrem / year to the Dose Calculation Manual whole body. (ODCM). (2) Less than 3000 mrem / year to the skin. b. For iodine-131, for iodine 133, and for all radionuclides in particulate form with half-lives greater than 8 days less than 1500 mrem / year. { l l -i 1 12-26

g> .] . QUAD-CITIES-Revision 1.0 ~ January 1994 ii r 1 12. 4 '. A j -- cassous Effluents Limits '12.4.B cameous Effluents and Renortiner - Surveillance I L. - 'c. If-the dose rates exceed the.above limits, without i delay' decrease the . release rates.to bring [ [O the dose rates within the limits, and to provide -prompt notification to the Commission (12.6.2.1) 2. The air dose in unrestricted 2. The' air dose due to releases. .i areas (at or beyond the site of radioactive noble gases boundary) due to Noble Gases

in gaseous effluents shall j

released in gaseous effluents. be determined to be within from the unit shall be the prescribed limits by. limited to the following: obtaining representative i samples in accordance with the sampling and analysis .a. ~ For gamma radiation: program specified in sections A.and B of Table (1) Less than or equal 12.4-1. The allocation of [ to 5. mrad-during effluents between units any calendar-having shared effluent quarter. control systems and the air doses are determined using (2) Less than or equal methods prescribed in.the to 10 mrad during ODCM'at least-once every 31 any calendar year. days. b. For Beta radiation: 5 ? (1) Less than or equal to 10 mrad during any calendar quarter. (2) Less than or equal to 20 mrad _during I any calendar year. j k i 12-27

o v I 4 QUAD CITIES Revisiors 1.0 - 1 b. 1-Of January 1994 ]QMNf0b D - 12.4.A. Gaseous'Effluenes Li mi t s ' 12.' 4. B cameous Effluents i and Renortina su rveill ance i - 2 ;. c. 'With the calculated' air. dose from radioactive noble. gases in gaseous effluents exceeding any of the above limits, prepare and submit to the

Commission within 30 E-days, a Special Report

^ which identifies the cause(s) for exceeding the limit (s) and detines the corrective actions to be taken to ensure that-future releases are in compliance with 12.4.A.2.a & b. This is in lieu of a Licensee Event Report. d. With the calculated air dose from radioactive noble gases in gaseous i effluents exceeding the limits of Specification l 12. 4. A.- 2. a. or. p3 12.4.A.2.b.,' prepare and l submit a special' Report to the. Commission within-30 days and' limit the l subsequent releases such that the doses or dose committment to a member of the public from all uranium fuel cycle sources'is limited to less than or equal to 25 mrem to the. total. body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 l consecutive months. This I special. Report'shall include an analysis which demonstrates that I radiation exposure to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct i 12-28 i

w. . QUAD CITIES Revision 1.0 I m7 January-1994 i (li - -12,4,A - cameous' Effluents Limits' 12.4.B cameous Effluents and Recortina -Surveillance [- - radiation)Lare less than r the 40 CFR Part 90 l Standard. ' Otherwise,' - obtain a variance from H the: Commission to permit } releases which-exceed the = 140 CFR Part 190 Standard. The radiation exposure ' analysis contained in the Special~ Report shall use the methods prescribed in the ODCM. This report is in lieu of a Licensee i Event Report. 3. 'The dose to a member of the 3. The' dose to a member of the public in unrestricted areas public due to' releases of. (at or beyond the site iodine-131,' iodine-133, boundary) from iodine-131, tritium, and'all iodine-133,. tritium, and all radionuclides in' particulate-radionuclides in particulate form with half-lives greater form with half-lives greater than 8 days shall be than 0 days in gaseous determined to be within tne efflusnts released from the prescribed limits by . unit shall be limited to the obtaining representative following: samples in accordance with the sampling. and analysis program specified in Table 12.4-1. i For radionuclides not determined in each batch or i weekly composite, the dose i contribution to the current calendar quarter cumulative summation may be estimated . by assuming an ave *: age monthly concentration based on the previous monthlyfor quarterly composite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual composite analyses when possible. The allocation of effluents between units having shared i effluent control systems and the doses are determined using the methods prescribed j in the ODCM at least once i every 31 days. i 12-29

I-QUAD CITIES. Revicion 1.0 : 4 A E-l 112.4.A.~ l fias.aou s ' rf f inant s iAmits I 12.4.B caseous Effluents D. and Renortina surveillance 3- 'a. Less than or equal to.7.5- .mrom to any organ during !any calendar quarter. b. .Less than'or equal to 15 4 mram to any organ during any calendar year. c. With the calculated dose -from the release of iodinel31, iodine-133,- tritium, and all i radionuclides in particulate form with halflives greater than 8 days in gaseous effluents exceeding any of the above limits,. prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken and the A l proposed' actions to be taken to ensure that future releases are'in compliance with -12.4.A.3.a & 12.4.A.3.b. This is in lieu of a Licensee Event Report. d. With the calculated dose from the release of iodinel31,. iodine-133, r tritium, and all radionuclides in-particulate form with half-lives greater than 8 days in gaseous effluents 'i exceeding the limits'of Section 12.4.A.3a. or 12.4.A.3b, prepare'and submit a Special Report to.the commission within .l l

30. days and limit l

subsequent releases such 's that the dose or dose commitment to'a member of { the public from I 4 l 12-30 - / l. . m

p.; .3 j ~ P W -QUAD-CITIES-Revision 1.0 l E - '. January 1994- 'I }(!' yg 12;4 A.' .causous vffluants rimits 12.4.B camaons Effluents - f,' ana menortiner. surveillance all uranium--fuel cycla' sources'is limited to ? less-than or equal to 25 ' r+. 4 mrom to the total body.or. organ (except.the-thyroid, which is. limited to less than.or equal to 75 mrem)~over 12 consecutive months. This Special Report'shall. { include an analysis which ' demonstrates that' radiation exposures to -i all members of the public _from all uranium fuel cycle sources ' including. j all effluent pathways.and i direct. radiation) are less than the 40 CFR Part i 190 Standard. Otherwise, t obtain a variance from the Commission to permit releases which' exceed the 40 CFR Part'190 Standard. The radiation exposure l analysis contained in the ~! Special Report shall,use the methods prescribed in i the ODCM. This report is in lieu of a Licensee Event Report. i 4. Off-gas System 4. Off-gas System a. At all times during Doses due to treated. gases l processing for discharge released to unrestricted j to the environs, process areas at or beyond the. site i and control equipment. boundary shall be. projected provided to reduce the at least once per'31' days.in-amount or concentration 'accordance with the'ODCM. of radioative materials j shall be operated, r t .b. The above specification {j shall not apply for the Off-Gas Charcoal Adsorber l Beds below 30 percent'of rated thermal power. .) i' 4 12-31

R ' QUAD CITIES Revician'1;0-January 1994. -[ } h hkpegT16fundEL{MME NA ~ 12.4.A. cameous Effluents' Limits' k., and Renortina i. 5.. .The release. rate of the 5. The radioactivity rate of sum of the activities noble gases at (near).the from the noble gases-outlet-of the main condenser 3 measured at the main air ejector shall be. condenser air ejector continuously monitored in I shall be~ limited to less accordance with than or equal to 100-Specification 12.2.2.A. The microcuries/see per MWt release rate of the sum'off i (after 30 minutes decay) the activities-from nolble at all' times. LWith the gases from.the main release rate of the sum condenser air. ejector shall of the activities from be determined to be within noble gases at the main the limits of Specification condenser air ejector 12.4.A.5 at the following i exceeding 100-frequencies by performing an microcuries/sec per MWt isotope analysis of a (after 30 minutes. decay), representative sample of restore, the release rate-gases taken at the ~ to within its. limits recombiner outlet, or at'the within 72 hours, or be in air ejector outlet:if the. ') at least HOT STANDBY recombiner is bypassed, within the next 12 hours. a. At least once per 31 days. b. Within 4 hours following an .? f increase, as indicated by l the main condenser air ejector noble gas activity monitor, of greater than 50%, after factoring out increases due to changes in thermal power level and off-gas flow, in the nominal steady-state fission gas release from the primary coolant. 6. In the event a limit and/or associated action requirement-identified in Sections 12.4.A and i 12.4.B cannot be i satisfied because of I circumstances-in excess of those addressed in this Section, no changes are required in the i operational condition of the plant, and this does not prevent the plant - from entry into an l _ operational mode. I i 12-32 ] l' j y e..

e. -

j' JQUAD. CITIES 4 Revision 1.0_ January 1994' I ~ Ik a 1;i;: , TABLE 12.4-1 .j RADIOACTIVE CAEROUE WAETE EAMPLTNG AND'ANALYETE PROGRAM l MINIMUM LOWER-LIMIT.'OF OASEOUS RELEASE- -SAMPLING ANALYSIS' TYPE OF ' DETECTION 'l TYPE FREQUENCY FREOUENCY ACTIVITY ANALYSIS - .-( LLD ) '(uCi/ml) + .A. - riain Chimney .. Grab Sample Emitters' - l M-M6 Principal Gamma, 11x10** Reactor Bldg. 'ent~ Stack M Tritium 1x10-*

I i

B. 11 Release Continuous (d'). . W I-131-1x10-" 3i 'ypes as Listed Charcoal-i 'n A Above Sample I-133 1x10*" Continuous (d)- W Principal Gamma + Particulate Emitters *... 1x10-" Sample (I-131, others) i i Continuous-(d) Q SR 1x10-" - Composite-Particulate SR-90 1x10-" ' Sample Continuous (d) M Gross Alpha 1x10*" Composite Particulate Sample C. Main Chimney Continuous-(d) Noble Gas. Noble Cases 1x10 Monitor-D. keactor Bldg. Continuous (d) Noble Gas Noble Cases 1x10 Vent' Stack Monitor f l 12-33 l J i l g

7 " QUAD CITIES Revision 1.0 ,o January 1994' ig %e., g a@Mhk c s. TABLE 12.4-1 (Continued) tam R NOTATION [ f a. The lower limit of detection,(LLD).is defined in table notation A. of Table 12.5-3. b. Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20 percent of rated thermal . power in 1 hour unless. (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) ~ the noble gas activity monitor shows that ef fluent ' i activity has not increased by more than a factor of 3. -c. Samples shall be changed at least once per 7' days and the analyses completed within 48 hours after removal from the sampler.. Sampling 1 shall also be performed within 24 hours following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal .{ power in one hour. This requirement does not apply if (1) analysis-shows'that the DOSE EQUIVALENT I-131 concentration in the primary, coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10. i d. The ratio of sample flow rate to the sampled stream flow rate shall be known. i The principal gamma emitters for which the LLD specification applies e. T : j exclusively are the following radionuclides: Kr-87, Kr-88,'Xe-133, i Xe-133m, Xe-135,'and Xe-138 for gaseous emissions, and Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Ce141, and Ce-144 for [ particulate emissions. Other. peaks which are meartrable and identifiable by gamma ray spectrometry, together.with the above i nuclides, shall be also identified and reported when an actual analysis j is performed on.a sample. Nuclides which are below the LLD for the. analyses shall not be reported as being present at the LLD level for l that nuclide. l E i t f f i i a i 12-34 l ~

QUAD CITIES Revision 1.0 fanuary 1994 pgg[01h%hp u, 1 12.4.C. GASEOUS EFFLURifPS BASES 1. Gaseous Effluents Dose This specification is provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from the units on the site will be within the annual dose limits of 10CFR20. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10CFR20. The specified release rate limits restrict, at all times, the corresponding gamma and-beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to 500 mrem / year to the total body or to not less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background via the inhalation pathway to not less than or equal to 1500 mrem / year. For purposes of calculating doses resulting from airborne releases the main chimney is considered to be an elevated release point, and the reactor vent stack is considered to be a mixed mode release point. 2. Dose, Noble Gases This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The bimiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents wil1~be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from bight-Water Cooled Reactors", Revision 1, July 1977. The ODCM equations provide for determining the air doses at the unrestricted boundary based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. 12-35 L.

1 QUAD CITn Revision 1;0 c g gBWAJ,BE " - ~ ' * ~ . 12.4.C' dAREOUR EFFTUENTE HARRn front.) de - j - t 3. . Dose, Radioiodines, Radioactive Material in Particulate F'orm and-i Radionuclides'other than Noble Gases t 1 This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of. Appendix I,.10 CFR Part 50. The f Limiting Conditions for Operation are the guides set forth-in I Section II.C of Appendix I. The statements provide the required i operating flexibility and'at the same time implement the guides set i forth in Section IV.A'of Appendix.I to assure that the releases of radioactive materials'in gaseous effluents will be'kept "as low as-is reasonable achievable." The ODCM' calculational methods specified in the surveillance requirements implements the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based' on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods approved by NRC for i calculating the doses-due to the actual release rates of the subject materials are required to be consi' stent with the methodology provided in Regulatory Guide 1.109, Calculation of. Annual Doses to Man from Routine Releases of Reactor Effluents for .the Purpose of Evaluating Compliance with 10 CFR.Part 50,- Appendix I", Revision l', October 1977 and. Regulatory Guide 1.111, " Methods-for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases.from Light-Water-Cooled Reactors," Revision 1 July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate-specifications for radiolodines, _ radioactive material in particulate form and 4-radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these specifications were: 1)-individual inhalation of airborne i radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man.and 3) deposition i onto grassy areas where milk animals graze with consumption of the milk by man. e i t i k i l e i i t l- + t 12-36 i t e b e - ~. - -n-r- w

. ~.,. .t cg -_ ,n 1 E. ..Retrision 1.0 l QUAD CITIES. . Jarn2ary 1994 .l IL pr (12.5 ElWIRONMENTAL MONITORING H i l2. 5'. A LEnvirnn=antal Monitorina 12.5.B. Environmanen1 Monitet1DE. Proaram surveillgggg 1.c The environmental 1. The radiological environmental monitoring program given in monitoring samples shall be .. Table 12.5-1 shall be collected pursuant to-Table-1 conducted except as: 12.5-l'from the locations. l specified below. specified in the ODCM, and shall be analyzed pursuant to the requirements of Table 12.5-3. '2. 'With the radiological. 2. The resultslof anal'yses . environmental monitoring' performed on radiological program not being conducted environmental monitoring l .as specified in Table samples shall be summarized-in l 12.5-1, prepare and submit the Annual Radiological l to the Commission, in the Environmental-Operating Report. i ~ Annual Radiological Operating Report, a l description of the reasons for hot conducting the program as required and the plans for preventing a recurrence. Deviations are i permitted from the required sampling schedule if specimens are unobtainable due to hazardous 6 conditions, seasonal unavailability, contractor omission which is corrected ) as soon as discovered. malfunction of sampling i equipment, oc if a person j who participates in the program goes out of 't business. If the equipment ti malfunctions, corrective actions shall be completed -l as soon as practical. If a j person supplying samples goes out of business, a l replacement will be found as soon as possible. All l deviations from the- 'l sampling schedule shall be [ described in the annual-report. sj l 12.5-A-Environmental Monitorina 212gIAm 3. With the level of radioactivity in an environmental sampling medium at one or more of the i 'l 12-37

= QUAD. CITIES; .Revicico 1-0 ^ m .. January 1994- [, ,, thi locations specified in the ODCM '. exceeding the limits of Table h-f..:.,' 12.5-2 when averaged over any 4 ' calendar quarter, prepare and isubmit to the Commiasion within 30 days from the end of tho affected-calendar quarter, a -Special Report which includes an evaluation of any release conditions, environmental' -factors or other aspects which j H Lcaused the limits of Table .12.5-2 to be exceeded. This L report:is.not requited if the measured level of radioactivity 'was not the result of plant + effluents; however,'in such an event'the condition shall be. ] reported and described in the Annual Radiological Environmental Operating Report. '12.5 B. Egyj rnnment al - Moni tori na l surveillance -) 3. The land use census shall be conducted.at least once per: twelve months between the dates of June 1 and October.1 by a .) door-to-door survey, aerial-l survey, road survey, or by 1 consulting local agriculture i authorities. ) l l .. l 12-38 I

.~-. 41 QUAD CI IESI;:. - . Revision 1.0 ,9 r ( JM,d January 1994 il n {$ W..e l ,ls.'.A Environmental Mnnitorina 12.5.B. Environmantal Monitorina l Ptnaram surveillance ~; Jo. . With milk samples. unavailable 4. 'The-results of the land use l from one or more'of the sample census shall be included in the locations required by Table Annual Radiological [ 12.5-1, identify locations for Environmental: Operating Report. obtaining replacement samples-r and add them to the radiological 1 environmental monitoring program within 30 days. The locations from which samples were unavailable may then be deleted-l 'from the monitoring program. In j lieu of a Licensee Event Report, identify the cause of the inavailability of samples and _ '4; identify the new location (s) for j obtaining replacement samples in t the Annual Radiological Environmental Operating report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s). j 5. A census of nearest residences of animals producing milk for I human consumption shall be 5. The results of the analyses conducted annually (during the performed as part of the grazing season for' animals) to required crosscheck program determine their location and shall be included in the Annual number with respect to the site. Radiological Environmental The nearest residence in each of Operating Report. The analyses the 16 meteorological sectors shall be done in accordance i 'shall also be determined within with Section 5.3.1 and Chapter 'a distance of five miles. The 11. i census shall be conducted under the following conditions: i a. Within a 2-mile radius from j the plant site, enumeration of animals and nearest residences by a door-to-door or equivalent counting technique. + i l 1 12.5.1 Environmantal Mnnitorina 12 5.B. Environmental Monitori na. . ] i Prnaram Eurveillance L Within a 5-mile radius, I enumeration of animals by using I referenced information from county agricultural agentslor-other reliable sources. 6. n.th a land use census identifying 1 > cat ion ( s ) of animals which 12-39

l .~ QUAD CITIES J Re g g @,M,oC,fl Wu W i a= vision 1.0 r = 1m yield (s)an ODCM calculated dose'or dose commitment greater than the /alues currently being calculated 2n Specification 12.4.A.3, the new location (s ) shall be added to the radiological environmental monitoring program with 30 days, if possible. The sampling location, having the i lowest calculated dose or dose commitment (via the same exposure a pathway) may be deleted from this taonitoring program after October 31 a. the year in which this land use sensus was conducted. 1 7. widiological analyses shall be performed on samples representative

i those in Table 12.5-1, supplied i

r. a part of the Interlaboratory E

i mparison Program which has been s ."sproved by the NRC. 8. With analyses not being per-lormed as required, report the c.orrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. 9. In the event a limit and/or associated actions requirements identified in Sections 12.5.A and 12.5.B cannot be satisified because of circumstances in exess of those addressed in these sections, no I changes are required in the operational condition of the plant, and this does not prevent the plant trom entry into an opetational mode. i I 1 l i I h l 12-40 l

q r[ f Q AD' CITIES Revision 1.0 7 January 1994 p 1 b ( r + r TABLE 12.5-1 RADYOLOCICAL EPNTRONMENTAL MONTTORINC PROGRAM ~ iExporure Pathway Minimum Number of Samples Sampling and Col- -Type and-Frequency' i 'and/or %mnlo and namnle Locationn* 1ection F r acnie nr-v ' of Ana1vsis ~ li ' AIRBORNE-I 1

m. -Particulates 16 locations Continuous opera-Gross beta and:

tion of sampler gamma Isotopic as for a week specified'in OCCM. b. Radioiodine 16 locations-Continuous. opera-I-131 as speci-tion of sampler fled in ODCM.' for two weeks-2. -DIRECT RADIATION Forty Locations Quarterly (Minimum of two .TLDs per packet) 3. WATERBOR11E ' b a. Public Water 2' Locations Monthly composite Gamma Isotopic of weekly collec-

analysis of each.

ted samples composite sample b. Gediment i downstream location Annually Gamma Isotopic'. f in receiving body of analysis of each water sample . i [ c. Plant Cooling-Intake, Discharge Weekly composite Gross Beta analy-t Water sis.of each sample 4. IfJGLSTIOf1 - I i a. Milk 2 Locations At least once I-131 analysis'of l weekly when ani-each sample i animals are on pasture; at least once per month at ~ other. times. t b.-Fish 1 location in receiv-Semi-annually . Gamma Isotopic ing body of water analysis on-edible portions: I

Sample locations are described in'the ODCM

- [ i 1 12-41 l x i e

II L QUAD CITIES Revision 1.0 3 January 1994 FOR 30lMAT!DiHMV .4 :, TABLE 12.5-2 REPORTING LEVFY9 FOR RADIOACTIVTTY CONCFMTRATION9 TN E?NTRONMEPPI'AL 9 AM PT.F4 Reporting Levels - Analy2. Water Airborne Particulate Fish Milk Food Products or Gases (pCi/m') (pCi/Kg, wet) (PCi/1) (PCi/Kg, wet) H-3 2 x 10* (a) 8 Mn-54 1 x 10 3 x 10' 2 Fs-59 4 x 10 1 x 10' ' Co-58 1 x 10' 3 x 10' Co-60 3 x 10'. 1 x 10' Zn-65 3 x 10' 2 x 10' 8 Zr-Nb-95 4 x 10 I-131 2 0.9 3 1 x 10 8 Cs-134 30 10 1 x 10' 60 1 x 10 2 Cs-137 50 20 1 x 10' 70 2 x 10' Ba-La-140 2 x 10' 3 x 10' a) for drinking water samples. This is 40 CFR Part 141 value. l l 1 l i l I 12-42

3 l -l -QUAD CITIES.

Revision 1.0 January 1994

.t. A 1I = (, t .3 TABLE'12.5-3 I -[ PRACTICAL LOWER LTMYTS OF' DETECTION ( LY.fi) ( 1FOR RTANDARD ENVTRONMENTAL RADIOLOOTCAL MONTTODTNO PROGRAM i .l ~I 'Sampie Medla Analysis LLD"" Units ' s. 6 6 Gl l i ' Airborne ~" Particulate" Gross Beta + 0.01 '. pCi /m2 I Gamma Isotopic 0.01 pCi/m 2 i .Airterne I-131 Iodine 131 0.10 pCi/m l 2 . Milk /Public Water I-131 5 ". pCi/1-- Cs-134 10 pCi/l Cs-137 10 A pCi/1 Tritium 200 pCi/1 Gross Beta + 5 pCi/1 Gamma Isotopic 20: pCi/1/nuclide-Sediment ' Gross Beta '+ 2 pCi/g dry Gamma Isotopic 0.2 pCi/g dry. ' Fish Tissue 'I-131 Thyroid '0.1 pCi/g wet ~ Cs-134, 137 0.1 pCi/g wet-Gross Beta + 1.0 pCi/g wet ~ Gamma Isotopic 0.2 pCi/g wet '.0.5 pCi/1 on milk samples collected during the pasture ~ season. 6 Referenced to C3-137 A '5.0 pci/l on milk samples 12-43

QUAD CITIES Revision 1.0 s .gggiB. ~ ~ 1"4 [ i TABLE 12.5-3 (Continued) PRACTICAL LOWER LIMITS OF DETECTION (LLD) .FOR STANDARD ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM TABLE NOTATION A. The LLD is the smallest concentration of radioactive material in the sample that will be detected with 95 percent probability with only 5% probability of falsely concluding that a blank observation' represents a "real" sequal. For a particular measurement system (which may include radiochemical separation) i .c l 4.66.s. LLD = ------------------- -------------------- - AEV 2.22 Y exp (-A A t) 't Where: LLD is the "a priori" lower limit of detection for a blank sample or background analysis as defined above (as pCi per unit mass or volume). j s is the square root of the background count or of a blank (T n sample count; is the estimated standard error of a background ~ i count or a blank sample count as appropriate (in units of l counts). E is the counting efficiency (as counts per disintegration). l A is the number of gamma rays emit'ted per disintegration for gamma ray radionuclide analysis (A=1.0 for gross alpha and l tritium measurements). l V is the sample size (in units of mass or volume). 2.22 is the number of disintegrations per minute per picocurie. Y is the fractional radio-chemical yield when applicable (otherwise Y = 1.0). A is the radiocctive decay constant for the particular radionuclide (in units of reciprocal minutes). 1 is the elapsed time between the midpoint of sample collection at and the start time of counting. (At = 0.0 for environmental samples and for gross alpha measurements), t is the duration of the count (in units of minutes). ( 12-44 l s

1 1 QUAD CITIES' Revision 1.0 l 1 January 1994 2 g g R Q N Wr c TABLE 12.5-3 (Continued) PRACTICAL LOWER LIMITS OF DETECTION (LLD) FOR STANDARD ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM TABLE NOTATION The value of "s " used in che calculation of the LLD for a detection system shall be based on an actual observed background count or a blank sample count (as appropriate) rather than on an unverified theoretically predicted value. Typical values of "E", "V", "Y", "t", and "At" shall be used in the calculation. For gamma ray radionuclide analyses the background counts are l determined from the total counts in the channels which are within plus or minus one FWHM (Full Width at Half Maximum) of the gamma ray photopeak energy normally used for the quantitative analysis for that radionuclide. Typical values of the FWHM shall be used in the calculation. The LLD for all measurements is defined as an "A priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular sample measurement. B. Other radionuclides which are measureable and identifiable by gamma-ray spectrometry, together with the nuclides indicated in l Table 12,5-2, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the i LLD level for that nuclide. 6 I 12-45 i = s

' QUAD CITIES Revision'1.0 January 1994-lgGW. l g (- 12.5.C' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

1. Monitoring' Program l>

The radiological' monitoring program required by.this l specification provides measurements of radiation and of E radioactive materials in those exposure pathways and for those radionuclides, which lead to.the. highest potential radiation-exposures of individuals resulting'from the' station operation. [ This monitoring program thereby. supplements the radiological l effluent monitoring program by verifyi.lg that the measurable l-concentrations of radioactive materials and levels of radiation-are not higher than expected on the basis of the effluent-measurements and modeling'of the environmental exposure pathways.. Program changes may be initiated based on operational experience. The detection capabilities required by Table 12.5-3 are state-of-the-art for routine environmental measurements in-industrial laboratories. The specified Icwer limits of detection for-I-131'in wateri milk and other food products correspond to approximately one-quarter of the' Appendix I to 10' l CFR Part 50 design objective dose-equivalent of 15 mrem / year l for atmospheric-releases and 10 mrem / year for liquid releases' l to the most sensitive organ and individual. They are based on 'O the assumptions given in Regulatory! Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor i Effluents for the Purpose of' Evaluating Compliance ~with 10.CFR l Part 50, Appendix I",. October 1977, except the change for an infant consuming 330 liter / year of drznking water instead of 510 liters / year. l 2. Land Use Census This specification is provided~to ensure that changes infthe use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results I of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. 3. Interlaboratory Comparison Program l The requirement for participation in the interlaboratory i comparison crosscheck program is provided to ensure that l independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. L 1 12-46 4 l'.- j l

2: s QUAD CITIES N! Revision ~ 1.0 ~ ~ N Jarn2ary 1994' N. 'Results of all environmental measurements summarized in' b a. the' format of the Regulatory Guide 4.8 Table'l-(December'1975). (Individual. sample results will be retained at.the Station). In the= event that some results are not available for inclusion with the report,.the report shall be submitted noting and explaining the reasons for missing results. Summaries, interpretations, and analysis of trends of the results e are to be provided. b. JAn assessment of the monitoring results and radiation' dose via the principal pathways of exposure resulting from plant emissions of radioactivity including the maximum noble gas gamma.and beta air. doses in the-unrestricted area. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (ODCM). c. Results of the census to determine the locations of nearest residences and of nearby ani. producing milk for human consumption (Table 12.5-1), d. The reason for the emission if the nearest dairy to the station is not in.the monitoring program (Table 12.5-1). e. An annual summary of meteorological conditions-concurrent with the releases of gaseous effluents in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. f. The results of the Interlaboratory Comparison Program described in Section 12.5.C.3. g. The results of the 40 CFR 190 uranium fuel cycle dose analysis for each calendar year. h. A summary of the monitoring program,. including maps showing sampling locations and tables giving distance and direction of sampling locations from the. Station.

3. If a confirmed measured radionuclide concentration in'an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting level given in Table 12.5-2 and if the radioactivity is attributable to

.]- plant operation, a written report shall be submitted to the Administrator of the NRC Regional. Office, with a copy to the Director, Office of Nuclear Reactor Regulation, within 30 days from the end of the quarter. 12-48

7 Redisionl'.0' i ~ -QUAD CITIES g. D g. --. 4 ' t .12.6 RECORD-KFFDING AND REPORTINGI

f l

-12.6.1 Plant' Operating Records A.. Records and/or logs relative to the following items shall be kept in a manner convenient. for: review and shall be ~! retained for at least 5 years: 1. Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements (see Section 6.4 of the Technical Specifications) are being met (all equipment failing to meet surveillance requirements and the corrective i action taken shall be recorded) 2. Records of radioactive shipments; f B. Records and/or logs relative to the following items shall j be recorded-in a manner convenient for review and shall ~ be retained for the life of the plant:

1. Records of offsite environmental monitoring surveys;-

2. Records of radioactivity in ligpid and gaseous wastes released to the environment; .t. 4. Records of reviews performed for changes made'to the Offsite Dose Calculation Manual. i 12.6.2 Reports 1. Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit during the previous'12 months of operation shall be submitted prior to April-l'of each year.. The report'shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to.10 CFR Part 50. 2. Annual Radiological Environmental Operating Report An annual report'containing the data taken in the standard radiological monitoring program (Table 12.5-1)' shall.be submitted prior to May 1 of-each year. The content of the report shall include: 12-47 b e

E - I -QUAD CITIESi y Revician 1.0 QQhhd L .u. m b. A determination that the change will maintain es the level of radioactive effluent' control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability L of effluent, dose, or setpoint calculations. 2. Shall become effective after review and acceptance by the Onsite Review and Investigative Function and the approval of the Plant Manager on the date specified by the Onsite Review and Investigative Function. 3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made' effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was-changed, and shall indicate the date (e.g., month / year) the change was implemented. 12.6.2.4 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (LIQUID AND GASEOUS) A. Licensee initiated major changes to the radioactive waste systems may be made provided: i.

1. The change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by the onsite review function.

The discussion of each change shall contain: L a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; b. Sufficient detailed information to support the reason for the change; c. A detailed description of the equipment, components, and process involved and the interfaces with other plant systems; d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents'and (or quantity of solid waste that differ from those previously predicted in the license application and amendments); m 12-50

QUAD CITIES- . Revision 1.0 \\ [ a. 'When more than one of the radionuclides in Table 12.5-2 are detected in the medium, the reporting level shall i have been exceeded if I _.Ct_ 2 1 R.L.: I where C, is the average quarterly concentration of the i" radionuclide in the medium and RL is. the reporting level of radionuclide i. b. If radionuclides other than those in Table 12.5-2 are detected and are due to plant effluents,.a reporting level is exceeded if the potential annual dose to an individual is equal-to or greater than the design objective doses of 10 CFR 50, Appendix 1. c. This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous effect. 12.6.2.3 OFFSITE DOSE CALCULATION MANUAL (ODCM) 12.6.2.3.A. The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the-calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the '(-- calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring-Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs described in section 12.5 and (2) descriptions of'the information that should be included in the. Semi-annual Radioactive Effluent Release Reports and in the Annual Radiological Environmental Operating Reports required by sections 12.6.2.1 and 12.6.2.2. The ODCM shall be subject to review and approval by the Commission prior to implementation. 12.6.2.3.B. Changes to the ODCM

1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.5.B.14.

This documentation shall contain: a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 12-49

=;3, W Y.-, _ ~ ,{ . QUAD CITIES.. p

Revision 1.0-x ~

egg &$ f e.- A' comparison of the predicted releases of radioactive materials in. liquid and gaseous effluents'and in solid-i waste to the actual releases for.the perird in which-the changes were-made; f. .-An estimate of the exposure to plant operating personnel as a result of the change;.and -g.- Documentation of.the fact that the change was reviewed.' I and found acceptable by the onsite review. function. -l

2. The change shall become effective'upon review and acceptance by onsite review function.

j ' l E a 4 I .h. .i i I l l l l 12-51 l

g :p BYiCOM ED s-l4-7-96. 14:51':. COMMONWEALTH EDISO W 20.1 -l 'l 3 yn. .w Jk i QUAD-CITIES STATION L ~ r; b PROCESS CONTROL PROGRAM i h I I FOR-t PROCESSING OF RADI0 ACTIVE NET MASTE i o REVISION 11 'l ) i i SEPTDRER 1993 i I i i 01530/0229Z j y. o.s o 4 D ( 6 7 - f g f f o.

f. -

JkCV BYtCOM ED 44 7-DG.s 14:51 : COMMWEALTH EDISOW

2 FOR11FDM ALO10M i

1.

1 The purpose of this Process Control Program (PCP) is to insure that the Radwaste System is used as appilcable to process all low level radioactive wet wastes soitdtfled or dewatered at Quad-Cities lluclear Power Station. The Process Control Program shall contain the current formulas, samp1tng, analyses, test, and determinations to be made to ensure that processing and packaging.of solid radioactive waste based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,- 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal and shipping g solid _radtoactive waste. Ifthe, provisions.of..this_ProcessContro1~Progfamarenoi ~ 3 satisfied the station will suspend shipments of the defectively processed ( or defectively packaged waste.rThis~ program ~E6ve7i~the'in-plant cement,.; y y ' vendor coment7 vendor.dowatering and vendor encapsulating systems. Het ) wastes at Quad-cities Station consist of filter media (powdered resta and fiber), bead resin, sump sludges, tank residuos, and higher activity cartridge filters. When expended, these vastes are transferred to vartogs storage tanks or storage containers and in some cases these wastes are transferred directly into a burial container for processing. Vendor processing of the waste is normally done with the waste container in either a transportation cask or a process shleid which offers the advantage of reduced radiation exposure to personnel l'nvolved in performing the necessary package handling operations. In some cases where radiation exposure would be minimal, processing of the waste is done with the container placed on an unshleided flatbed trailer. l 01530/0229Z '

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-7 II.. IW-PLANT CDENT SQL,ID ESTE SYSTEM 3 . [t $t

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A.. Description (In-plant cement solid waste system'1s limited to use for Class A unstable waste forms only) 1 The resin slurry is transferred to one of two centrifuges for dewatering. The centrifuges have a capacity of 25 gpe.. The_ solids are separated from the water and drop into a. hopper associated with. each centrifuge. The water;is routed'back to a storage tank. Each hopper has~ a 40 cubic foot capacity. At the bottom of the hopper there is a hopper discharge valve. This is a remotely operated, air operated, fall closed valve. Connected to the hopper I discharge valve is the sludge chute and the drum feed valve. The sludge chute is 8 inches in diameter and 6 feet 5 inches long, with a l capacity of 2.2 cubic feet. The drum feed valve is also remotely j operated, air operated, and fall-closed. The hopper discharge valve i and the drum feed valve are interlocked to prevent both valves from being open simultaneously. l Cement is added to'a' drum fromthe' coment silo. The cement sllo i has a capacity of 620 cubic feet. Cement is fed through_ a rotary feeder down a transfer tube through the mixer head, into the drum. The mixer goes into the drum and forms a seal to prevent dispersion of cement dust or spillage during mixing. The alxer has two speeds, l 100 rpm and 200 rps, that are programmed into the six cycle. i Drums are capped at the load-out conveyor area before loading into a shipping vehicle. A cap is set in place and a seal ring is snapped over it. A thread,ed bolt is used to tighten the seal ring. Drum storage consists of three conveyor lines, with room for 25 drums on each.line. Drums stored on the storage lines are removed and either shipped, stored in storage bins located in the radwaste facility, or stored in the Interin Radweste Storage facility. 4 01530/0229Z 4

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14552': ' C04fMON0'EALTH EDl SOW i# 4, ..je j 4 3 3*" g 3. Omaration of tha' In-Plant Emment Solid Manta Synta= In order-to insure' solidification of spent resins with'no free f%- uator,~ tests were conducted at Quad-Clties-Station using unspent resin.. Fresh resins were elsed up in the proportions!that would be- .. 1 expected to be normally processed. These resins were then put into'a-drum and the drum was' processed through the cement system. The drum ~ uas capped as normal and allowed to set in storage for 24 hours. 1 After 24 hours, the drum was cut open lengthwise and inspected. The results of the inspection resulted.in a change of the proportions of. water and cement untti the final product was solid and free of-water. A series of drums were processed using spent resins, and the drums were visually inspected for no free water prior to shipping. I No free water was observed. Based on these tests, specific station procedures were written to assure that solidified barrels produced by the in-plant cement system fall within the test results. Since all of the barrels made on the.In-plant system are classified'as Class A. unstable, per 10 CFR 61, no additional testing outside of the Initial { station tests'are required. The general procedure that is followed to process spent resins is described below. Specific plant operating procedures are followed j i by the operator.- 1. The empty drum is covered with a plastic bag and taped in place to prevent external contamination, i 2. A half of a bag of dry cement is added to the empty drum. 3. The empty drums are loaded on a conveyor. i 4. One empty drum from the conveyor is loaded on a transfer cart (remote operation). l 5. The transfer cart is advanced to the selected hopper station l (remote operation). 01530/0229Z i

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The drum is filled with resins.ts a prescribed level (remoto h operation). The resin is transferred from the hopper to the QM D drum through the sludge chute. The disch'arge valve on the A I[ sludge chute 15 a manually operated remote valve. The operator views the drum through a mirror and fills the drum to between the first and second roll hoop from the top of the drum. r<ca // Although this method of adding resin to the drum is not precise, f it can be controlled to a high degree. If an operator determines that the quantity of resins varies from the prescribed level, he can compensate with water and/or cement. 7. Mater is added (remote operation). Normally 16-20 gallons of water are added to each drum. This amount can be varted if necessary for complete solidification. The amount of water required is selected, and a flow integrator gives the inlet valve a closed signal when that amount is delivered. 8. The drum is transferred to the mixing station (remote 1 operation). 9. The cement tin F l's" set.' ~~ 10. The mixer cycle (remote operation) is started. The mixer lowers into the drum and forms a tight seal. The mixer will begin to rotate at slow speed. The air slide blower and dust collector are started. The cement feeder and vibrators start and cement is matered to the drum. The mixer increases to fast speed. The cement feeder stops and the alt slide blower and dust collector .i stop. When the mixer coegletes the cycle, the RPM meter vill start to decrease. At this point, the mixer control switch is moved from AUTO to FAST and the mixer is given an additional 5 4 minutes on fast speed. The switch is then returned to AUTO, and the atxer cycle is complete. 01530/0229Z.

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11. The drum is traosferred to the inspection statien (remote c -

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12. The atmed drum contact radtation reading are logged and the j

. [se contents of the drum are observed. If it is determined that .[? more cement is required, the drum is returned to the mixer and gm[ N[ additional cement is added. When the mix is satisfactory, the c%g drum is transferred to the drum storage lines. j

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'T. C. Verification of In-Plant cament System Solidification Each solidified drum is verified to be vold of free water prior to shipping or storage. The drum is transferred from the storage ) lines to the load-out conveyor. At this point, each drum is visually j inspected to verify it is vold of free water and the contents j solidified. The protective plastic bag is removed, and the drum is capped. The drum is then surveyed for smearable contamination and dose rate. The drum is then loaded into the shipping vehicle'or j placed in storage. If a drum is found to contain free water, dry cement will be added to solidify the fres water or the drum will be.recyclet.through,... the mixing line as required. The drum will not be shipped with more than 0.5 percent freestanding water. I + 4 1 01530/0229Z ?RCV BY:COM ED: 2 4-OG -;-14:54. COMMON %E LTil EDISNW '

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j III. VElm0R SUPPLIED SOLIDIFICATION SYSTEM F0,1B!FM. 20s 0lRY e ~ A.. Description Contractor solidification services are uttilzed at the Station for wastes which are required to be classified as stable waste per 10 CFR 61 and/or burial site licenses. Additionally, in certain circumstances, contractor mvices say also be used to process wastes, which are not required to be stable per 10CFR61 and/or burial site licenses. The contractor must have procedures or other support documents as necessary to produce a waste. form which meets a11 the requirements of 10CFR61 and appilcable burial site criteria. ' A copy of the vendor's procedures (which states station interface requirements), and other support documents are submitted to an l on-site review prior to use to assure compatability with Station Systems, procedures, and Technical Specifications.. Specific station procedures are then developed from this vendor Information and-approved prior to use. j l Normally, a batching tank is utilfred to collect the radwaste to j be solidified. The tank can; be filled from any of the following: 1. Condensate Phase Separators. 2. Cleanup Phase Separators. 3. Spent Resin Tanks. 4. Haste Sludge Tank. After the tank is filled with radwaste, a decant pump is used to remove water from the top of the settled sludge. When the decanting operation is completed, the tank contains about 1.900 gallons of sludge. The mixing tank can be operated on recirculation to allow a tank sample to be taken for analysis and sample solidification tests as ] required. 01530/0229Z -

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!a certain cases, fcr example,teastes resulting from chemical' l decontaminations, the waste is sent directly to a liner in which the 7 / solidification will take place. In this case a sample is taken out of the liner after it has been properly alxed prior to adding l solidification chemicals. The recipe for solidification will be determined based on a successful solldtftcation demonstration using the sample taken from the liner. 3 A temperature monitor in the liner is used to note the maximum temperature during the exothers. After sufficient cooling the liner is prepared for shipment or storage. 5. Doeration of the Vendor Solldtftcation System A Inner is prepared for use by' installing a thermocouple and tubing for level indication. The fill head is placed over the liner and locked in-place. The radwaste is added to the liner. The alxing tank, if used, ) is first mixed for about 10 minutes. The proper amount of radwaste is delivered by a radwaste pump or slurried from portable processing equipment. Mieste flow to the41ner is monltored by a TV camera. The radwaste pipe lines and waste transfer hose to the fill head are then flushed. After the radwaste has been put into the liner the process is completed by the contractor. The contractor adds cement and additives in accordance with their approved PCP. After final mixing i the temperature is monitored and the maximum temperature is noted. 1 When the solidified liner has suffletently cooled, the contractor and Station personnel visually inspect the product and verify that it is an acceptable product. The Itner is then covered with a lid, secured, surveyed and shipped or stored in the Interim Radwaste Storage Facility. 01530/0229Z _

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9 44.'~ Verification'ofVendortunelledSolidificationSystem verification of solidification filat involves saapitag the y

radweste prior to solldtftcation in order to determine'the proper-j

proporttons of.the ingredients that will produce an acceptable I

product. A representative laboratory sample.of waste is taken. In aecordance with the vendor's PCP program, small, scaled-down amounts + of cement and additives are added in the proper quantitles. Based on an acceptable lab sample solidification, scale-up factors are developed for the full scale solidification. The full scale solidification will not be done until.a satisfactory lab sample solidification has been verifled. A visual inspection of each liner is performed by both the vendor and station personnel prior to Installing the ild. The visual. inspection further verifles that the product is acceptable per the contractors PCP. If the visual inspection does' not verify solidification, the contractor wt11 be required to provide the station an acceptable resolution. 4 gy, m A. Description Contractor dewatering services may be utilfred at the Station in lieu of solidification for stable waste forms as directed by station i operating personnel. Additionally. -In certain circumstances, contractor dewatering may also be used to process wastes which are L not required to be stable per 10CFR61 and/or burial site licenses, The contractor must have procedures or other support documents to ) produce a waste form which meets all the requirements of 10CFR61 and i the applicable burial site criteria. A copy of the vendor's L t i '01530/0229Z '

IltCS "BY : COM. ED '- . 4M 7-95 j 5 4:50 : CXWMONCIiALT11 EDISON-. - . :010 1 4 procedures (which states station-Interface requirements) and other ' support documents are submitted to an onisite review prior to use to j A assure compatability_wlth Station Systems, procedures, and Technical ] 5pecifications. Specific station procedures are then developed from. gh this vendor.Information and approved prior to.use. ' [5h 1 f,.3 Normally a mixing tank is utillzed to collect.the radweste to be N dewatered. The tank can be filled from any of the following:

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Condensate Phase Separators w. 2. Cleanup Phase Separators -t 3.- Spent Resin Tanks. 4. Haste Sludge Tank After the tank is filled with radwaste, a decant pump is used to remove water from the top of the settled sludge. When the decanting operation is completed, the tant contains about 1,900 gallons of sludge. The atxing tank can be operated on recirculation in order to allow a tank sample to be taken for analysts if required. In certatn-cases when It is not possible or~ desirable to"UsetNd ofxtris' tanC " ' for example, wastes resulting from chemical decontaminations, waste from spent Resin tanks, waste from sump cleaning or waste from portable process equipment. This waste is sent directly to a Nigh Integrity Container (NIC) or steel liner, as required, in which the I dewatering wl11 take place. 8. Onoration of the Vendor Dewaterina system A High Integrity Container (HIC) or steel liners, as required, is prepared for use by installing a thermocouple, tf not already Installed, and Inspecting dewatering elements and thermocouple leads. If Installed. The fill head 1s-placed over the HIC or steel liner, as required, and secured in-place. l L 01530/02291. .m ..m..

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11' The cixing tank, if uttitzed, is first clxed for approximately-m 10 minutes. The proper amount of radwaste is delivered to the llIC or

/. steel IIner using the installed radwaste pump, portable waste pumps-i or with air pressure for decontamination system equipment and ) portable processing equipment. Maste flow to the HIC is monitored by -) -l a TV camera. The radwaste p1pe lines and waste transfer hose used 1 for the waste transfer to the-fill head are flushed after each .(Ch I transfer.. j After the radwaste has been put_into the HIC or steel liner, the balance of the dowatering process is completed by the contractor.. The contractor dewaters in accordance with their approved procedures or other support documents until the~' acceptance criteria is met. When the process is complete, the contractor and Station personnel verify that each HIC is an acceptable product and samples are taken from the HIC. The HIC is then covered with a lid, secured, surveyed and shipped or stored in the Interim Radwaste Storage Facility. C. Verif teattan of Vendor Sunn11sd Dewaterina System i Verification of'an~ acceptable dewatered product.1s I ell'neated.in _. d the contractors procedures. The acceptance criteria is dependent upon the type of dewatering system used and the material dowatered. V. VEllDOR EllCAPSULATION OF MASTE A. Descrtntion Contractor encapsulation services may be utlilred by the Station for cartridge filters and other wastes which are required to be classified as stable waste per 10CFR61 and/or burial site licenses. The contractor must have procedures or other support documents as necessary to produce a waste form which meets all the requirements of 10CFR61 and the applicable burial site criterla. Vendor procedures W 01530/0229Z....

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-k used to prepare specific Station procedures which are submitted te an on-stte review prior to use to assure compatibility with station g systees procedures and Technical Speciffcations.- g, vendor Encannulation New ~

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A liner is prepared by the vendor which has a propoured botton W l ([)a l and partial sides. The item to be encapsulated is placed inside the j prepour and the remaining portion of the liner is filled with a I ^ stable formula of cement. When the encapsulation has sufficiently cooled -the contractor and Station _ personnel visually inspect the product and verify that it i i is an acceptable product. The liner is then covered wtth a Ild, secured, surveyed and shipped or stored in the Interim Radwaste Storage Facility. C. vertrication of Vendor Encannulation I To verify encapsulation, a visual inspection of each liner is performed prior to installing the lid. The visual inspection verifles that the product meets to acceptance criteria of.the contractors procedures If the-liner ~1s*not an acceptab1(' product, the vendor will be required by the station to provide an acceptable resolution. 4 VI. HIGH INTEGRITY CONTAIMER USAGE High Integrity container (IIIC's) are used at the Station for packaging higher activity cartridge filters and other various approved i waste packaging. The vendor which supplies the MIC must provide the i Station with a copy of the certificate of Compilance for the. HIC which i details specific limitations on use of the HIC. l l l J i 01530/0229Z.-

m-7-- gg ;; q 'VII. MASTE CLAS$1FICATION Station wastes wt11 be classified as Class A. Class 8. or Class C to . determine the acceptability for near-surface disposal and for the purpose of segregation at the disposal stte. The waste class will be based on the concentration of certain radionuclides in the waste as outlined in 10CFR61.55.. RadionucIlde concentrations ulli be determined based on the volume or . weight of the final waste form as discussed in Section C.2 of the Branch Technical Position Paper on Haste Classification. Of the four suggested methods for determining radionuclide concentration, the one most commonly used is' the direct measurement of individual radionuclides (gasuna emitters) and the use of scaling factors to determine the radionuclide concentration of difficult to measure redlonuclides (normally non-gamma emitters). The use of the other suggested methods; material accountability, classification by source or gross radloactivity measurements may occur If the situation best fits the i use of that methodology. Approvad Statlon.. procedures. ara..used..in.the.. determination of. radionuclide concentration for difficult to measure nuclides (normally non-gamma emitters) and for the classification of radioactive waste for near-surface burial. VII. SHIPMElli MANIFEST Each shipment of radioactive waste to a Itcensed land disposal facility will be accompanied by a shipment manifest as required by 10CFR20,311(b) and 10CFR20.311(c). The manifest will contain the name, address, and telephone number of the waste generator. The manifest will also include the name, address, and telephone number or the name and EPA hazardous waste identification number of the. person transporting the waste to the land disposal facilit}. 01530/0229Z e

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)% The maalfest will also indicate to the extent practicablo: a r> physteal'desertption of the waste;.the volume; radionuelIde identity and e h quantity; the. total radioactivity; and the pr1ncipal cheafcat fore. 'The I-g solidification ager,t, If applicable, will be Identified. -[t[ Naste containing more than 0.11, chelating agents by. weight will be re identified and the weight percentage of the chelating agent estimated. Maste classification, Class A, 5, or C, will be clearly indicated on the A manifest. The total quantity of the radionuclides N-3, C-14, Tc-99,-and i s 1-129 will be shown on the manifest. Each manifest will include a certification by the waste generator l t that the transported materials are properly classified, described, packaged, marked, and labeled, and are in proper condition for ,i transportation according to the applicable regulations of the Department of Transportation and the NRC. A representative of-the Station will sign and date the manifest. Approved Station procedures are used for the preparation of burtal site radioactive shfpping manifests. The Station will maintain a manifest recordkeeping and tracking system that meets the requirements of 10CFR20.311(d). IX. ADMINISTRATIVE CDNTil0LS A. Trainina lii A training program will exist to ensure that waste processing will be performed according to Station procedures and in accordance l with the requirements of the Station PCP. An Individual's training record wl11 be maintained for audit and Inspection. The processing and shipment of radioactive material will be performed by quallfted and trained personnel. I l 01530/0229Z 1 t - ~ ~ ~ ~ ~

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5. Record totantion Records of processing data, test and analysis results, documents, results of training, inspections and audits will be - retained in accordance with company quality verification requirements for record retention. Records of reviews performed for changes made ) to the PCP shall be retained for the duration of the Unit Operating License. l C. Documentation control Licensee initiated changes may be made to the PCP provided that the change: 1. Is documented and records of reytews performed shall be retained for the duration of the Unit Operating License. This documentation shall contain: a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b. A determination that the change will maintain the overall conforsence of the soHtHfted waste - product to existing requirements of Federal, State, or other appilcable regulations. Changes to the PCP shall become effective after review and acceptance by the Onsite Review function and the approval of the Plant Manager. Changes to the PCP shall be submitted to the Commission in the Semi-Annual Radioactive Effluent Release Report for the period in which the changes were made. 01530/0229Z - [

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14 59 : CONISK)NMEALTil ED1S0%. : s#10 '/ Radicactive waste that 'does not fall t:lthin previous waste k processing expertence will be evaluated and.llf necessary, included ti. in the PCP prior to final processing and disposal. D. . Quality control j Licensee procedures ensure that a vendor processing radioactive l SC, waste, for burial, adhere to their procedures and that an acceptable l product that meets regulatory requirements and burial site criteria results. This procedure addresses the requirement to assess the i impact of changes in a vendor's PCP or the Station s PCP and requires a 10CFR50.59 safety evaluation for any changes in the vendor's PCP. E. Major channes to Radioactive Waste Treahment svstems Major changes to the Solid Radioactive Waste Treatment Systems j may be made provided: 1. The change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by the On-site Review Function. The discussion of each change shall-contain: l a. A summary of the evaluation that led to the determination f that the change could be made in accordance with 10 CFR 50.59. b. Sufficient detailed information to support the reason for the change. c. A detailed description of the equipment, components, and process involved and the interfaces with other plant systems. 1 J d. An evaluation of the change which shows the predicted quantity of solid waste that differs from that previously predicted in the Itcense appilcation and amendments. \\ 01530/0229Z '

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-l e. A comparison of the predicted v31ume of radioactive solid waste to the actual volume for the period in which the %,4 changes were made. /s ) f. An estimate of the exposure to plant operating personnel as a result of the change. g. Documentation of the fact that the change was reviewed and Q:? g** found acceptable by the On-site Review Function. f dM 2. The change shall become effective upon review and acceptance by the On-Site Review Function. [ [ I A ) ( i 1 i 01530/0229Z, _}}

ML20085M617

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