Text

Rev 5 to Chapter 12 of Zion Annex Odcm
	ML20216G135
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	09/23/1999
From:	; COMMONWEALTH EDISON CO.
To:	;
References
	PROC-990923, NUDOCS 9909280429
	Download: ML20216G135 (59)
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7-s September 23,1999 X244 ALL Document Control Desk Director of Nuclear Reactor Regulation ,

U.S. Nuclear Regulatory Commission i Mail Station PI-137 Washington, DC 20555 l

l Attached is a revision to the Offsite Dose Calculation Manual (ODCM), Zion Annex, Chapter 12. Please update your manual as follows:

Remove: Insert:

Zion, Chapter 12, Revision 4 Zion, Chapter 12, Revision 5, dated August,1999 i

Please sign below indicating your receipt of this manual update.

RETURN TO:

Outside Comed inside Comed Comed Procedure Clerk Procedure Clerk Central File 1400 Opus Place - 4th floor Downers Grove -4 Downers Grove, IL 60515 ACKNOWLEDGEMENT -

Signature Date i

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Description of ODCM Changes for OSR/014/99 i

l Pace Chance Descrintion/Brief Justification of Chance 12-4 Added a suney frequency of annually to Table 12.1-1. As prescribed in the ODCM a radiation monitor has a calibration frequency of annually. This table provides the guidance / definition for the " annual" requirement.

12-10 On item 2., added Aux Building to the title " Aux Building Effluent Ventilation" to differentiate these monitors from the new Fuel Building ventilation monitors.

i 12-10 Eliminated ORE-0014 as a required noble gas monitor. The monitor is not described in the DSAR, it is redundant to the Vent Stack SPING gas monitoring, and with isolation of fuel building ventilation from aux building ;

ventilation there is no longer a source of noble gas for the aux building. l l

12-10 Added the new radiation monitors (ORT-PR30A&B-partic and gas) for the p new fuel building ventilation system. The channel operability and inoperable V requirements were maintained the same as for the basic vent stack SPING '

partic, and noble gas channels. Also included a footnote (3) that establishes applict.bility concurrent with initial operation of the fuel building exhaust fans. This allows the change to be in place when the release path risk is realized.

12-13 Added the new radiation monitors to Table 12.2-4 with appropriate l sun eillance requirements.

12-21 The LLD requirement for Fe-59 was removed from Table 12.3-1. This radionuclide is only generated during an operating mode (fission), based on its half-life and time since shutdown, this nuclide cannot exist at Zion The only potential source of neutrons would be the insignificant flux froi i the two 4 Pu-Be sources in the spent fuel pool and the spent fuel itself. Thr ,e neutron sources cannot produce measurable amounts of activity.

12-26 Added fuel building ventilation as a continuous release path. With isolation of the fuel building ventilation from aux ventilation, the fuel building becomes its own continuous release pathway. Sampling and analyses requirements were maintained as with the current continuous release path requirements.

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12-27 The LLD requirement for Fe-59 was removed from Table 12.4-1. This

~( radionuclide is only generated during an operating mode (fission), based on its half-life and time since shutdown, this nuclide cannot exist at Zion. The only potential source of neutrons would be the insignificant flux from the two Pu-Be sources in the . spent fuel pool and the spent fuel itself. These neutron sources cannot produce measurable amounts of activity.

12-42 The LLD requirements for Fe-59.1-131, and Ba/La-140 were eliminated from Table 12.5-3, These radionuclides are only generated during an operating mode (fission), based on their half-lives and time since shutdmvn, these nuclides cannot exist at 7 ion. The only potential source of neutrons would be the insignificant flux fr e 'he two Pu-Be sources in the spent fuel pool and the spent fuel itself. Qese neutron sources cannot produce measurable amounts of activity. Eliminating these isotopes reduces the number of geometries and count times required.

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i ZION Revision 5 August 1999 O

SPECIAL NOTE The requirernents of the Technical Specifications shall take precedence over this chapter, should any differences occur.

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ZION Revision 5 August 1999 CHAPTER 12 REVISION 5 O

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ZION Rsvision 5 August 1999 CHAPTER 12 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE 12.1 DEFINITIONS 12-1 12.2 INSTRUMENTATION

1. Radioactive Liquid Plant Monitoring Instrumentation 12-5

2. Radioactive Plant Monitoring instrumentation 12-9 12.3 LIQUID EFFLUENTS

1. Concentration 12-16

2. Dose 12-22

3. Liquid Radwaste Treatment System 12-24 12.4 GASEOUS EFFLUENTS

1. Dose Rate 12-25

2. Dose - Noble Gases 12-28

3. Dose - l-131,1-133, Tritium, and Radioactive Material in Particulate Form 12-30

4. Gaseous Effluent Treatment System ' 12-32 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i

1. Monitoring Program 12-33 l

2. Land Use Census 12-45 3.

l Intertaboratory Comparison Program 12-46 l l

12.6 PROCESS CONTROL PROGRAM (PCP)

1. PCP Program Requirement 12-47

2. Changes to the PCP 12-47 12.7 REPORTING REQUIREMENTS

1. Annual Radiological Environmental Operating Report 12-48

2. Annual Radioactive Effluent Release Report 12-49

3. Offsite Dose Calculation Manual (ODCM) 12-51

4. Major Changes to Liquid and Gaseous Effluent Treatment Systems 12-52 D

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r-i ZION Rsvision 5 August 1999 CHAPTER 12 k

RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

LIST OF TABLES PAGE 12.1-1 Surveillance Frequency Notations 12-4 12.2-1 Radioactive Liquid Plant Monitoring instrumentation 12-6 12.2-2 Radioactive Liquid Plant Monitoring instrumentation Surveillance 12-8 12.2-3 Radioactive Plant Monitoring instrumentation 12-10 12.2-4 Radioactive Plant Monitoring instrumentation Surveillance 12-13 12.3 1 Allowable Concentration of Dis Jolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Effluents 12-18 12.3-2 Radioactive Liquid Effluent Sampling and Analysis Surveillance 12-19

-12.4-1 Radioactive Gaseous Effluent Sampling and Analysis Program 12-26 12.5-1 Radiological Environmental Monitoring Program 12-36 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-41 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-42

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- ZION Rsvision 5 August 1999 12.1. DEFINITIONS v 12.1.1 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.

12.1.2 A CHANNEL CAllBRATION, shall be the adjustment, as necessary, of the channel such that it responds with the necessary range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors (where possible),

alarm interlock and/or tnp functions and shallinclude the CHANNEL FUNCTIONAL TEST. The CHANNEL CAllBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

12.1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shallinclude, 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.

12.1.4 A CHANNEL FUNCTIONAL CHECK shall be:

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a. Instruments-The injection of a simulated signol(s)into the channel as close to the primary sensor (s) as practicable to verify OPERABILITY, including all channel outputs, as appropriate.

b. Logics The application of input signals, or the operation of relays or switch contacts, in all the combinations required to produce the required decision outputs including the operation of all ACTUATION DEVICES. Where d practicable, the test shallinclude the operation of the ACTUATED EQUIPMENT as well (i.e. pumps will be started. valves operated, etc.).

1 12.1.5 A COMPOSITE SAMPLE is one in which the quantity of liquid sample 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 12.1.6 A CONTINUOUS RELEASE is the discharge ofliquid or gaseous wastes of a nondiscrete volume (e.g. from a volume or system that has an input flow during the release). l 12.1.7 A CONTINUOUS SAMPLING FREOUENCY is uninterrupted sampling with the exception of sampling interruptions of short duration for routine activities (e.g. filter replacements).

12.1.8 DOSE EQUIVALENT l-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of l-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 ill of TfD-14844, " Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109 Rev.1, dated October,1977. This definition is not used in the defueled condition. Decay has eliminated all concerns related to radioactive iodine.

12.1.9 MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose.

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e ZION Revision 5 August 1999 12.1.10 OCCUPATIONAL DOSE means the dose received by an individualin the course of O) i

~# employment in which the individual's assigned duties involve exposure to radiation and/or radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.

12.1.11 OPERABLE - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are requirea for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

12.1.12 OPERATING is defined as performing the intended function in the intended manner.

12.1.13 The OPERATING CYCLE shall be the interval between the end of one major refueling outage and the end of the next subsequent major refueling outage per unit.

12.1,14 An OPERATIONAL MODE (i.e., Mode) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1 of the Technical Specifications, when fuel assemblies are present in the reactor vessel. This definition is not applicable in a permanently defueled condition.

12.1.15 The PROCESS CONTROL PROGRAM (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 fD d 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.

12.1.16 PURGE OR PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner, that replacement air or gas is required to punfy the confinement.

12.1.17 RATED THERMAL POWER shall be a total steady state reactor core heat transfer rate to the reactor coolant of 3250 MWL 12.1.18 The REACTOR PRESSURE shall be in the pressure in the steam space of the pressurizer.

12.1.19 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee.

12.1.20 SOLIDIFICATION shall be the conversion of radioactive liquid, resin and sludge wastes from liquid systems into a form that meets shipping and burial site requirements.

12.1.21 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

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-i ZION Revision 5 August 1999 r 12.1.22- SURVEILLANCE shall be those parts of the sections which presenbe remedial measures Q] required under designated conditions, activities required to demonstrate instrument operability, and activities performed to ensure applicable offsite dose limits are not exceeded.

12.1.23 The SURVEILLANCE FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 12.1-1.

12.1.24 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

12.1.25 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee.

12.1.26 GASEOUS EFFLUENT TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive materialin particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any affect on noble gas effluents. The iodine removal function is no longer used in the defueled condition.

12.1.27 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a venting process.

12.1.28 WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off-gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total 4 V radioactivity prior to release to the environment. This system is no longer used and usefulin the defueled condition. f j

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e ZION Revision 5 August 1999 l hA TABLE 12.1-1 SURVEILLANCE FREQUENCY NOTATIONS 4

NOTATION FREQUENCY

S (Shiftly) ~ At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D (Daily) At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W (Weekly) At least once per 7 days M (Monthly) At least once per 31 days O (Quarterly) At least once per 92 days SA- (Semiannually) At least once per 184 days A' (Annually) At least once per 366 days l R At least once per 18 months S/U (Startup) Prior to reactor startup P (Prior) Complete prior to start of release EFPM At least once per effective full power month N/A Not Applicable

. Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. These frequency notations do not apply to the Radiological Environmental Monitoring Program as described in Section 12.5.

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ZION Revision 5 August 1999 6'

12.2 INSTRUMENTATION

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12.2.1 Radioactive Liquid Plant Monitoring instrumentation Operability Reauirements 12.2.1.A The radioactive liquid plant monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE AND. the radioactive liquid effluent monitoring instrumentation channels sha:1 have their alarm / trip setpoints set to ensure that the limits of Section 12 3.1.A are met.

- Apolicability: As indicated in Table 12.2-3.

Action

. 1, With a radicactive liquid effluent monitoring instrument channel trip setpoint less conservative than the value necessary to prevent violating the limits of Section 12.3.1.A, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

2. With one or more radioactive liauid plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement delineated in Table 12.2-1.

Surveillance Reauirements

'_12.2.1.B.1 - The liquid effluent monitor setpoints shall be determined in accordance with procedures O as desenbed in the ODCM.

LV 12.2.1.B.2 Each radioactive liquid plant monitoring instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CHECK, SOURCE CHECK CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-2.

Bases 12.2.1.C The radioactive liquid plant monitoring instrumentation is provided to indicate abnormal radiological conditions within the plant. AND.

1 The radioactive liquid effluent instrumentation is provided to monitor and control, as

' applicable, the release of radioactive materials in liquid effluents. The alarm / trip setpoints

' for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of RETS. The i OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10CFR Part 50.

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ZION Revision 5 August 1999

,e % TABLE 12.2-1 Id RADIOACTIVE LIOUID PLANT MONITORING INSTRUMENTATION (Cont'd)

SURVEILLANCE 1 With one af the LDT monitors inoperable, all LDT releases shall be made through the OPERABLE monitored pathway. If both monitors are inoperable, effluent releases from the tank may continue for up to 14 days, provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed. in accordance with Section 12.3.1.B.1, and

2. At least two technically qualified members of the facility staff independently verify the release-rate calculations and discharge flow path valving; Otherwise, suspend release of radioactive effluents via this pathway.

SURVEILLANCE 2 With the number of channels OPERABLE less the minimum number required, effluent releases via this pathway may continue, provided that at least once per day grab samples are analyzed for gross radioactivity (beta / gamma or isotopic) at a lower limit of detection (LLD) as specified in Table 12.3-2. Restore the channei to operable status within 30 days or conduct a station review to determine a plan of action to restore the channel to operable status.

V SURVEILLANCE 3 With the number of channels OPERABLE less than the minimum number required, effluent releases via this pathway may continue, for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used to estimate flow.

SURVEILLANCE 4 With the number of channels OPERABLE less than the minimum required, obtain and analyze a component cooling sample once per day. If the monitor is not returned to service within 30 days, conduct a station review to determine a plan of !

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ZION Rrvision 5 l August 1999 j 12.2.2 Radioactive Plant Monitoring instrumentation

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Operability Reauirements l

12.2.2.A The radioactive plant monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE, AND, the radioactive gaseous effluent monitonng instrumentation shall have their l alarm / trip setpoints set in accordance with the method presenbed in the ODCM to ensure that the limits of Section 12.4.1.A are met.

Applicability: As indicated in Table 12.2-3.

Action j

1. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Section, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channelinoperable.

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2. With one or more radioactive plant monitoring instrumentation channels inoperable, l initiate the SURVElLLANCE requirement as delineated in Table 12.2-3.

Surveillance Reauirements 12.2.2.B.1 The effluent monitor setpoints shall be determined in accordance with procedures as desenbed in the ODCM.

(' 12.2.2.B.2 Each radioactive plant monitoring instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.24 Bases 12.2.2.C . The radioactive plant monitonng instrumentation is provided to indicate abnormal radiological conditions within the plant. AND, The radioactive gaseous effluent instrumentation is provided to monitor, record and control, as applicable, the release of radioactive materials in gaseous effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10CFR Part 20.

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, ZION Rsvision 5 August 1999 TABLE 12 2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS ' APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE CONDITION

1. Effluent Containment Purae or Vent

' A. Particulate Monitor -

1. 1R-PR40A (Channel 1) 1 6',72 Venting or Purging

2. 2R-PR40A (Channel 1) 1 6',72 Venting or Purging

2. Aux Buildina Effluent Ventilation l

A. Gas Activity Monitor

1. 1R-PR49E (Channel 5) i 10 All Times

2. 2R-PR49E (Channel 5) 1 10 All Times B. Particulate Monitor

1. 1R-PR49A (Channel 1) -1 11 All Times

2. - 2R-PR49A (Channel 1) 1 11 All Times C. Flow Rate Monitor

1. 1LP-084 1 8 Supply or Exhaust Fans j Operating I 2, 2LP-084 ~1- 8 Supply or Exhaust Fans l Operating j

3. Fuel Buildina Monitorina A. Gas Activity Monitor

1. ORT-PR30A 1 10 All Times 8 i B. Particulate Monitor

1. ORT-PR30B 1 11 All Times 8 I C. Area Monitoring

1. ORT-AR03 1 12 When fuelis present

2. ORE 0005 1 14 When fuelis present >

3. ORT-AR13 1 13 When fuel building crane is operated in bypass mode

' During VENTING '

8 During PURGING 8 Concurrent with initial operation of fuel building ventilation exhaust fans. l V

zi2r5 doc ~ 12-10

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ZION Rr, vision 5 August 1'999

. TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION (Cont'd)

MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE CONDITION

4. Emeraency Monitonna A. Control Room Process

1. ORIA-PR29A (Channel 1) 1 9 All Times

2. ORIA-PR29E (Channel 5) 1- 9 All Times

3. ORIA-PR29G (Channel 7) 1 9 All Times B. Technical Support Center Process

1. ORIA-PR32A (Channel 1) 1 9 All Times

-2 ORIA-PR32E (Channel 5) ' 1 9 All Times

3. ORIA-PR32G (Channel 7) 1 9 All Times C. Control Room Area

1. ORE 0001 1 15 All Times 0

4 D. Technical Support Center Area 1.

2.

ORE-AR31 ORE-AR32 1 1 15-15 All Times All Times

3. ORE-AR33 1 15 . All Times E. Ventilation

1. .1RIA-PR49 (Channel 7) 1- 9 All Times

2. - 2RIA-PR49 (Channel 7) 1 9 All Times

3. 1RIA-PR49 (Channel 9) 1 9 All Times -

4. . 2RIA-PR49 (Channel 9) 1 9 All Times

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zi2r5 doc 12-11 i

.' ZION Revision 5 A,ugust 1999

/m TABLE 12.2-3 s

RADIOACTIVE PLANT MONITORING INSTRUMENTATION (Cont'd)

TABLE NOTATIONS SURVEILLANCE 6 - With the number of channels OPERABLE less than the minimum number required, effluent releases via this pathway may continue for up to 30 days provided grab samples are obtained and analyzed for gross activity at least once per day.

SURVEILLANCE 7 - With the number of channels OPERABLE less than the minimum number required, and no redundant monitor OPERABLE in this flow path, immediately suspend PURGING of radioactive effluents via this pathway.

SURVEILLANCE 8 - With the number of OPERABLE channels less than the minimum number required, efiluent releases via this pathway may continue provided the effluent flow rate is estimated at least once per day while release is in progress.

SURVEILLANCE 9 - With the number of channels OPERABLE less than the minimum number required, restore the inoperable monitor to OPERABLE status within 30 days or establish an alternate means of monitoring the parameter.

SURVEILLANCE 10 - With the number of OPERABLE channels less than the minimum number required, restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent p)

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releases via this pathway may continue provided grab samples are obtained and analyzed for gross activity at least once per day.

SURVEILLANCE 11 - With the number of OPERABLE channels less than the minimum number required, restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent release via this pathway may continue provided grab samples are continuously collected as required in Table 12.4-1.

SURVEILLANCE 12- With the number of channels OPERABLE less than the minimum required, stop all movement of fuel within the spent fuel pool and crane operation with loads over the spent fuel pool AND perform area surveys of the monitored area at least once per day.

SURVEILLANCE 13 With the number of channels OPERABLE less than the minimum required, stop operation of overhead crane in bypass after placing loads in safe condition.

SURVEILLANCE 14 Perform area surveys of the monitored area at least once per day.

SURVEILLANCE 15 Establish an attemate means of monitoring with alarm capabilities OR perform area survey of the monitored area at least once per day, s.,

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ZION Revision 5 August 1999 g] Table 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE (Cont'd)

TABLE NOTATIONS (1) CHANNEL CAllBRATION shallinclude performance of a CHANNEL FUNCTIONAL TEST.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation occurs; and that Control Room alarm annunciation occurs if any of the following conditions exist (if the capability is installed):

a) Instrument indicates measured levels above the alarrn setpoint.

b) Circuit failure.

c) Instrument indicates a downscale failure.

d) instrument controls not set in " operate" mode.

(3) Daily during operations of overhead crane in bypass mode.

(4) Daily during fuel handling operations or load handling operations in or above the spent fuel pool.

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zi2r5 doc 12-15

r s ZION Rtvision 5 August 1999

.-g 12.3 LlQUID EFFLUENTS

12.3.1 Concentration Ooerability Reauirements 12.3.1.A.11 The concentration of radioactive material released from the site to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-

' 20.2402, for radionuclides other than dissolved or entrained noble gases. Fce dissolved or entrained noble gases, the concentrations shall be limited to the values listed in Table 12.3-1.

12.3.1.A.2 During the release of radioactive liquid wastes, the combination of dilution water flow and waste water discharge flow shall be established to ensure the discharge concentration limits of 12.3.1.A.1. are not exceeded.

Applicability: At all times.

Action

1. ~ With the concentration of radioactive materials released from the site to UNRESTRICTED AREAS exceeding the limits specified in Section 12.3.1.A.1.

immediately decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits.

Surveillance Reauirements 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by campling and analysis in accordance with Table 12.3-2. The results of pre-release analysns shall be used with the calculational methods in the ODCM to assure that the concentraN at the point of release is maintained within the limits of Section 12.3.1.A.1.

12.3.1.B.2 Post-release analyses of samples composited from BATCH RELEASES shall be performed in accordance with Table 12.3-2. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1.

' 12.3.1.B.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by. collection and analysis of samples in accordance with Table 12.3-2.

The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1. )

'12.3.1. B.4 Appropriate discharge and dilutions flows for each batch radioactive liquid release shall be determined with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A 1.

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' zi2r5 doc - 12-16 I

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=* ZION Revision 5 August 1999

~

Bases 12.31.C This Section 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 ten (10) times the concentration levels specified in Appendix B. Table 2, Column 2 to 10CFR 20.1001-20.2402.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section ll.A design objectives of Appendix l,10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10CFR20.1301.

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O zt2r5. doc 12-17 i

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i ZION Revision 5 August 1999 f^3 TABLE 12 3-1

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ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID EFFLUENTS NUCLIDE A(uCi/ml)*

Kr-85m 2 X 10' Kr-85 5 X 10d Kr-87 '

4 X 10-5 Kr-88 9 X 10'5 l

Ar-41 7 X 10-5 Xe-131m 7 X 10d Xe-133m 5 X 104 !

Xe-133 6 X 10d l

[ \ Xe-135m 2 X 10d V

Xe-135 2 X 10d

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.

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RJ zi2rs. doc 12-18

, ZION Revision 5 August 1999 TABLE 12 3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE MINIMUM ANALYSIS LOWER LIMIT OF LIQUID RELEASE SAMPLING FREQUENCY TYPE OF DETECTION (LLD)

TYPE FREQUENCY ACTIVITY ANALYSIS (pCi/ml)(a.e)

A. Lake Discharge Prior to Each Release Prior to Each Principal Gamma SE-7 Tank (c) - Release Emitters (e)

P M Dissolved and 1 E-5 One Batch /M(c) Entrained Gases (Gamma Emitters)

P M Tritium 1 E-5 Each Batch (c) Composite (b)

Gross Alpha 1 E-7 P Q Sr-89, Sr-90 SE-8 Each Batch (c) Composite (b)

Fe-55 1 E-6 B. Turbine Building Continuous During W Principal Gamma SE-7 Fire Sump (f) Release (d) Emitters (e)

Dissolved and 1 E-5

'L Entrained Gases (Gamma Emitters)

Continuous (d) M Tritium 1 E-5 Composite (b)

Grcss Alpha 1 E-7 Continuous (d) Q Sr-89, Sr-90 SE-8 Composite (b)

Fe-55 1 E-6 C. Waste Neutralizing Prior to each Release Prior to each Release Principal Gamma SE-7 1 Tank Emitters (e)

P M Tritium 1 E-5 Each Batch (c) Composite (b)

Gross Alpha 1 E-7

%4 zi2r5 doc 12-19

. ZION Rsvision 5 August 1999 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd)

TABLE NOTATIONS

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD = 4 66 s A + E

V + 2.22 + Y + exp (-Aat)

Where:

LLD is the lower limit of detection as defined above in picocuries (pCi) per unit mass or volume, sois the square root of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

A is the number of gamma rays emitted per disintegration for gamma ray radionuclide analysis (A = 1.0) for gross alpha, strontium, and tritium measurement.

E is the counting efficiency (as counts per gamma),

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, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental sample).

l The value of soused in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples.

Typical values of E, V, Y, and At shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within 1 one FWHM (Full Width at Half Maximum) energy band about the ene,rgy of the gamma ray peak used for the quantitative analysis for that radionuclide.

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r12r5 doc 12-20 l

U ZION Revision 5 August 1999 m TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd)

TABLE NOTATIONS For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using observed ratios with those radionuclides which are measurable.

b. A COMPOSITE SAMPLE is one in which the quantity of liquid sampled 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.

1) To be representative of the quantities and concentrations of radioactive matenals in liquid effluents, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

2) The weekly and monthly Proportional Composite samples are not required provided that (1) the analysis required for each of these composite samples has been run on each batch discharged, and (2) a monthly record of radionuclides discharged (isotope and quantity)is maintained.

O c, 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.

d. A CONTINUOUS RELEASE is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of system that has an input flow during the continuous release.

e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54 Co-58, Co-60. Zn-65, Mo-99 Cs-134, Cs-137, Ce-141, and Ce-144. This l list does not mean that only these nuchdes are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations,

f. If the fire sump composite sampler is inoperable, grab samples shall be taken from the turbine building fire sump once per day O

V zi2r5 doc 12-21

. ZION Revision 5 August 1999 12.3.2 Dose

(~

() Operability Reauirements

. 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC above background from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited:

1. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

2. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

Applicability: At all times.

Action

1. With the calculated dose from the release of radioactive materials in liquid i effluents exceeding twice the limits specified in Section 12.3.2.A, 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 I 25 mrem to the total body or any organ (except thyroid, which is limited to less ;

than or equal to 75 mrem) over 12 consecutive months. Demonstrate that l radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the l

g 40CFR Part 190 and 40CFR Part 141 Standard, otherwise obtain a variance from '

t <

the Commission to permit releases which exceed the 40CFR Part 141 or 190 Standard. The radiation exposure analysis shall use methods prescribed in the ODCM.

' Surveillance Reauirements

' 12.3.2. B Cumulative dose contnbutions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodologies and parameters of the ODCM at least once per 31 days.

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-q-zi2r54oc 12-22

ZION Revision 5 August 1999

,s Bases 1(b} 12.3.2.C This Section is provided to implement the requirements of Sections ll.A. Ill.A and IV. A of Appendix I,10CFR Part 50. The limiting Condition of Operation implements the guides set forth in Section ll.A of Appendix 1. The ACTION 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 liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies, which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are excess of the requirements of 40CFR 141. The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix l 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 dose due to the actual release rate of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109; Calculation of Annual Doses to Man from Routine Releases of Radioactive Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix 1, Revision 1, October 1977 and Regulatory Guides 1.113," Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977.

This Section applies to the release of liquid effluents from each unit at the site. For shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing the system.

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zi2r5. doc'. 12-23 l

. ZION R:: vision 5 August 1999

,-) 12.3.3 Liquid Radwaste Treatment System Operability Rec iments 12.3.3. A The Liquid Radwaste Treatment System shall be OPERABLE

and appropriate portions of the system shall be used to reduce the radioactive materials in liquid effluents prior to discharge when the projected doses due to :iquid effluent, from each unit, to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F 1) would exceed 0.06 mrem to the total body or 0.20 to any organ in a 31-day period.

The liquid Radwaste Treatment System shall be considered OPERABLE, if liquid waste can be held up and/or discharged within applicable limits.

ADDlicability: At all times.

Action With the Liquid Radwaste Treatment System inoperable for more than 30 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, return the system to OPERABLE status and place the appropriate portions of the system in use.

Surveillance Reauirements 12.3.3.B Doses due to liquid releases from the site to UNRESTRICTED AREAS, shall be projected at least once per 31 days in accordance with the methodologies and parameters of the 3 ODCM when the Liquid Radwaste Treatment System is not being fully utilized.

[O Bases 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that the 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 Section implements the requirements of 10CFR Part 50.36a, General Design Criterion of Appendix A to 10CFR Part 50 and the design objective given in Section ll.D of Appendix I to 10CFR Part 50.

The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment Systern were specified as a 2% fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10CFR Part 50, for liquid effluents.

J zi2r5 doc 12-24

ZION RIvision 5 August 1999 12.4 GASEOUS EFFLUENTS g.

\j 12.4.1 Dose Rate Operatina Reauirements 12.4.1. A The dose rate due to radioactive matenals released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1), shall be limited to the following:

1. For noble gases: Less than or equa! to 500 mrem /yr to the whole body and less than or equal to 3000 mrem /yr to the skin, and

2. For lodine-131, lodine-133, tntium and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.

Applicability: At all times.

Action With a release exceeding the above limits, immediately reduce the release rate to within 3 the above limits.

Surveillance Reauirements f

12.4.1.B.1 The dose rate due to radioactive matenals in gaseous effluents shall be determined to be within the prescribed limits in accordance with the methods and procedures of the ODCM.

[dD 12.4.1.B.2 The dose rate due to radioactive materials, other than noble gases in gaseous effluents shall be determined to be within the presenbed limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4-1.

Bases 12.4.1.C This Section is provided to ensure that the dose at or beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR Part 20.1301. 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 SITE BOUNDARY to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release-rate limits also restrict, at all times, the corresponding organ dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year. For purposes of calculating dose resulting from airborne releases, the stack is considered a ground-level release.

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z12r5 doc 12-25

ZION Revision 5 August 1999 TABL E 12.41 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF GASEOUS RELEASE SAMPLING LOWER LIMIT OF ANALYSIS ACTIVITY TYPE FREQUENCY FREQUENCY ANALYSIS DETECTION (LLD)

(pCi/cc)(f)

A. Deleted B.- Containment Vent Prior to Each Release Prior to Each Noble Gases 1 E-4 and Purge Release Principal Gamma Emitters (d)

Tritium 1E-6 C. Continuous Grab (b) Monthly Noble Gases 1 E-4 Principal Gamma Aux Building Emitters (d)

Ventilation Stack for both (2) units A_nd Tritium 1 E-6 Continuous (b)(h) Weekly (c) Particulate 1 E-11 Fuel Building Principal Gamma (j% Ventilation m Emitters (e)

Composite Quarterly Sr-89 Particulate 1 E-11 Sr-90 Particulate 1 E-11 Gross Alpha 1 E-11 Continuous (g)(h) N.A. Noble Gases, 1 E-6 Noble Gas Monitor am mlnitial applicability concurrent with initial operation of fuel building ventilation exhaust fans.

O zi2r5 doc 12-26

, ZION Rsvision 5 August 1999 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd)

TABLE NOTATIONS

a. - Deleted

b. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period in Section 12.4.1.

c. The particulate filter (s) shall be saved for a quarterly composite analysis for Sr-89 and Sr-90.

d. For gaseous emissions, 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.

Other peaks 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 at the LLD level for that nuclide.

e. For particulate emissions, the principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, l Ce-141, and Ce-144. Other peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an p actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses f i shall not be reported as being at the LLD level for that nuclide.

V

f. The LLD is defined in Notation a of Table 12.3-2.

g. Refer to Table 12.2-3 for required actions when the noble gas monitor is not in service.

h. Sampling interruptions of short duration for routine activities, e.g. filter replacement, do not ;

constitute a deviation from the requirements for continuous sampling.

V zt 2r5. doc - 12-27

. ZION Rsvision 5 l August 1999 p 12.4.2 Dose - Noble Gases Operability Reauirements 12.4.2.A The air dose due to noble gases released in gaseous effluents from each unit to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1, During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and

2. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

Apolicability: At all times Action

1. With the calculated air dose from gaseous effluents exceeding the above limits, define the corrective action (s) to be taken to ensure that future releases are in compliance with Section 12.4.2.A.

2. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding twice the limits of Section 12.4.2.A:

a. Limit subsequent releases such that the dose or dose Q

V 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 the thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months.

b. Prepare an analysis which demonstrates that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluents pathways and direct radiation) are less than the 40 CFR Part 190 Standard.

Surveillance Reauirements 12.4.2.8 . Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodologies and parameters of the ODCM at least once every 31 days. 1 l

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W. l b) l zi2r5 doc 12 28 0

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. i ZION Revision 5 August 1999 Bases 12.4.2.C This Section implements the requirements of Sections ll.B, Ill.A and IV.A of Appendix 1, 10CFR Part 50. The Operability Requirements implement the guides set forth in Section 11.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix ! to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section til.A of Appendix I that conformance with the guides of Appendix 1 is to be shown by calculation procedures based on modefs and data such that the actual exposure of an individual through the appropriate pathways is unkkely to be substantially underestimated.

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212r5. doc 12-29

, ZION Ravision 5 August 1999 12.4.3 Dose - l-131,1-133, Tritium, and Radioactive Material in Particulate Form

'(3 Operability Reouirements 12.4.3. A The dose to a MEMBER OF THE PUBLIC from I-131, l-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and

2. During any calendar year: Less than or equal to 15 mrem to any organ.

Applicability: At all times.

Action With the calculated dose from the release of lodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding twice the limits of Section 12.4.3.A:

1. Limit subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources to less than or equal to 25 mrem to the total body or organ (except the thyroid which is limited to less than or equal to 75 mrem) over 12 consecutive months.

2. Prepare an analysis which demonstrates that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 Standard. Otherwise, request a variance from the Commission to permit release which exceeds the 40CFR Part 190 Standard. The radiation exposure analysis shall use the methods prescribed in the ODCM.

Surveillance Reouirements 12.4.3.3 Cumulative dose contribution for the current calendar quarter and current calendar year for I-131,1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodologies and parameters in the ODCM at least once per 31 days.

p V

' zi2r5. doc 12-30 l

, ZION Revision 5 August 1999 i Bases

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() 12.4.3.C This Section implements the requirersents c' Sections ll.C. Ill.A and IV. A of Appendix 1, 10CFR Part 50. The Operability Requirements are the guides set forth in Section ll.C of Appendix 1. The ACTION 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 materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculation methods specified in the Surveillance Requirements implement the requirements in Section ill A of Appendix 1 that conformance with the guides of Appendix I is to be shown by caiculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The release-rate specifications for radioiodines, radioactive material in particulate form and radioiodines other than noble gases are dependent on the existing radionuclide pathways to man, at or beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airbome radionuclides, 2) disposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man.

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zi2r5 doc 12-31

. ZION R: vision 5 August 1999 12.4.4 Gaseous Effluent Treatment System

- Qperability Reouirements 12.4.4 A The GASEOUS EFFLUENT TREATMENT SYSTEM shall be OPERABLE

and appropriate portions of these systems shall be used to reduce radioactive materials in gaseous effluents when the projected doses in 31 days due to gaseous effluent releases.

from each unit, to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) would exceed:

1

1. 0.2 mrad to air from gamma radiation, or

2. 0.4 mrad to air from beta radiation, or

3. 0.3 mrem to any organ.

The installed GASEOUS EFFLUENT TREATMENT SYSTEM shall be considered OPERA'BLE by meetings Section 12.4.1,12.4.2 and/or 12.4.3, as applicable.

Applicability: At all times.

Action: With the Gaseous Effluer.t Treatment System inoperable for more than 30 days I or with radioactive gaseous waste being discharged without treatmer.t and in excess of the above lirnits, return the system to OPERABLE status and place the appropriate portions of the system in use. '

Surveillance Reouirements '

12.4.4.B Doses due to gaseous releases from each unit to areas at or beyond the SITE g BOUNDARY shall be projected at least once per 31 days in accordance with ;

the methodologies and parameters in the ODCM when the Gaseous Effluent Treatment Systems are not being fully utilized.

Bases 12.4.4.C The OPERABILITY of the GASEOUS EFFLUENT TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment pnor to release to the environment.

The requirement that the appropriate portions of this system be used when specified provides reasonable assurance that the relcases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This section implements the requirement of 10CFR50.36a, General Design Criterion 60 of Appendix A to 10CFR50 and the design objective given in Section ll.D of Appendix i to 10CFR50. The specified !

limits governing the use of appropriate portions of the Gaseous Effluent Treatment System were specified as a 2% fraction cf the dose design objectives set forth in Section ll.B and ll.C of Appendix 1,10CFR50, for gaseous effluents.

O V

zi2r5 doc 12-32

p ZION Rsvision 5 August 1999 I

A 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitoring Program Operabihty Reauirements

' 12.5.1. A - The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.

Acolicabiktv: At al! times.

Action

1. With the Radiological Environmental Monitonng Program not being conducted as specified in Table 12.51, prepare and submit to the Commission, in the Annual Radiologicol Environmental Operating Report, a description of the reasons for not conducting a program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of sampling equipment, if a person who participates in the program goes out of j business or no longer can provide sample, or contractor omission which is '

corrected as soon as discovered. if the equipment malfunctions, corrective j actions shall be completed as soon as practical. If a person / business supplying 1 samples goes out of business, a replacement supplier shall be found as soon as l possible. All deviations from the sampling schedule shall be described in the Annual Radiological Environmental Operating Report.

2. With the level of radioactivity as a result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.6-2 when averaged over any calendar quarter, prepare and submit 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 reduce radioactive effluents so that the potential annual dose

to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3.

When more than one of the radionuclides in Table 12.5.2 are detected in the

. sampling medium, this report shall be submitted if.

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concentration (1) + concentration (2) + . > 1.0 reporting level (1) reporting level (2) i When radionuclides other than those in Table 12.5-2 are detected and are the ;

result of plant effluents, this report shall be submitted if the potential annual dose ;

to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than I the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; I' however, in such a event, the condition shall be reported and describeo in the Annual Radiological Environmental Operating Report.

The methodology and parameters used to estimate the potential dose to a MEMBER OF THE PUBLIC l X shall be indicated in the report

'i j V

Z12r5 doc 12-33

i-ZION Rsvision 5 August 1999

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3. If the sample type or sampling location (s) required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the pathway ofinterest and/or spccific locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the program.

Prepare and submit a controlled version of the ODCM within 180 days including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location (s) for obtaining samples.

Surveillance Reauirements 12.5.1.B.1 The Radiological Environmental Monitoring samples shall be collected from the locations specified in the ODCM and analyzed pursuant to Table 12.5-1 and the detection capabilities required by Table 12.5-3.

Bases 12.5.1.C .The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This O

V monitoring program implementsSection IV.B.2 of Appendix 1 to 100.:R50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable 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. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least 3 years of commercial operation.

Fotbwing this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an efter the fact limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual. HASL-300 (revised annually), Currie, LA., " Limits for Qualitative Detection and Quantitative Determination-Application to Radiochemistry

Anal Chem 40, 586-93 (1968), and Gartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

o z12r$. doc 12-34

. ZION Rsvision 5 August 1999

/ Interoretations L) 12.5.1.0 Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 10 kilometers (6.2 miles)." Drinking water supply is defined as water taken from river, lakes, or reservoirs (not well water) which is used for dnnking. Since Lake Michigan has no designated downstream or upstream direction, two drinking water locations (one northlone south) within 10 kilometers shall be sampled as annking water indicator locations, and two other locations (one north /one south) beyond 10 kilometers shall be sampled as control locations.

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z

ZION Rsvision 5 August 1999 TA!LE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) l This table contains lower limits of detection for analyses beyond the requirements of i Table 12.5-1. This table does not imply that only these nuclides are to be detected and reported; other peaks which are measurable and identifiable in the analyses required by Table 12.5-1 shall be reported in the Annual Radiolcgical Environmental Operat.ng Report.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide l 4.13.

(3) The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of i falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation, the

' LLD is defined as follows:

4.66 S, + 3/t, LLD = ----------------------

(E) (V) (2.22) (Y) (exp (-Aat))

4.66 S.

LLD -

(E)(V) (2.22) (Y)(exp (-AAt))

Where: 4.66 S, n 3/t, LLD = the "a priori" Lower Limit of Detection (picoeuries per unit mass or volume),

s, = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts per minute),

4 Total Counts ts E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (secd),

to = counting time of the background or blank (minutes), and zi2rs. doc 12-43

n

ZION

, Revision 5 August 1999 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS at = the elapsed time between sample collection, or end of the sampic collection period, and the time of counting (sec).

Typical values of E, V Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

(4) If no drinking water pathway exists, the value of 15 pCi/l may be used.

(5) A value of 0.5 pCi/l shall be used when the animals are on pasture (May through October) and a value of 5 pCill shall be used at all other times (November through April).

-(6) This LLD applies only when the analytical separation and counting procedure are specific for this radionuclide,

b. (7) This is the minimum required LLD, h'owever, environmental samples analyzed off-site will be required to use 200 pCi/l.

i p)-

L zi2r5. doc 12 44

r.

ZION Revision 5 August 1999 12.5.2 LAND USE CENSUS Operability Recuirements i 12.5.2.A A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 I

mi) the location, in each of the following meteorological sectors, A, J, K, L, M. N, P, O, and R, of the nearest milk animal, the nearest residence", and an enumeration of livestock.

For dose calculation, a garden will be assumed at the nearest residence.

Apolicability: At all times.

Action:

With a Land Use Census identifying location (s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in Chapter 11 of the ODCM Station Annexes. The sampling location (s), excluding the control location, having the lowest calculated dose or dose commitment (s), 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. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change in sampling locations.

The nearest industrial facility shall also be documented if closer than the nearest residence.

Surveillance Recuirements 12.5.2. B The Land Use Census shall be conducted during the growing season, between June 1 and October 1, at least once per calendar year using that information that will provide the best resuLs, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authonties. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.

Bases 12.5.2.C This specificatm is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified anJ that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 of Appendix 1 to 10 CFR Part 50.

An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations.

O zt2r5 doc 12-45

1

. ZION Rzvision 5 August 1999 12.5.3 INTERLABORATORY COMPARISON PROGRAM

(~]

\d Operability Reavirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an interlaboratory comparison program that correspond to samples required by Table 12.5.1.

ADolicability: At all times.

Actiori:

1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Comrnission in the Annual Radiological Environmental Operating Report.

Surveillance Reauirements 12.5.3.8 A summary of the results obtained as part of the above required interlaboratory comparison program shall be included in the Annual Radie.agical Environmental Operating Report.

Bases 12.5.3.C The requirement for participation in an interlaboratory comparison program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the

,s results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

N]

s

,f N/l 212r5. doc 12-46

j ZION R: vision 5 August 1999 12.6 PROCESS CONTROL PROGRAM (PCP)

/

12.6.1 PCP Proaram Reauirements v

Contains the requirements and methodology for the c arrent formulas, sampling, analyses, tests, and determinations performed to ensure the prc cessing and packaging of solid radioactive wastes based on actual or simulated wet solid wastes is accomplished in compliance with:

e 10CFR Pans 20,61, and 71 e State Regulations e Burial Site Requirements Other Requirements Governing the Shipping and Buria: of Radioactive Waste 12.6.2 Chances to the PCP Changes to the PCP include those changes that affect the process or methodology, by which wastes are solidified, packaged to meet burial site form requirements, classified, or dewatered.

12.6.2.1. Shall be documented and records of reviews performed shall be retained, and Shall contain sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and Shall contain a determination that the change will maintain the overall (p) conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations, and Shall become effective after review and acceptance by the Onsite Review and Investigative Function and the approval of the Decommissioning Plant Manager.

7.-

zi2r5 doc

$7 47

r

, , , - ZION Rnvision 5 August 1999 12.7 REPORTING REQUIREMENTS O 12.7.1 Annual Radioloaical Environmental Operatina Report

L.)

Routine Annual Radiological Environmental Operating Report covering the operation of the Unit (s) during the previous calendar year shall be submitted according to Technical Specification 6.6.1.C. The Annual Radiological Environmental Operating Report shall include summaries. Interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including, as found appropnate, a comparison of preoperational studies with operational controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the Chapter 11 of the ODCM Station Annexes, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons (

for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, and discussion for all deviations from the sampling schedule of Table

)

(A)

" 11.1-1; a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample 1

l j

measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents; discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; results of the Land Use Census required by Section 12.5.2, and the results of licensee participation in an interlaboratory comparison program and the corrective actions being taken if the specified program is not being performed as required -

by Section 12.5.3.

t The Annual Radiological Environmental Operat;ng Report shall also include an annual summary of hourly meteorological data collected over the applicable year. This annual j

summary may be either in the form of an hour-by-hour listing on magnetic tape of wind '

speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the I licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

A single submittal may be made for a multiple unit station.

V zi2:5 doc 12 4g

, .

ZION Rzvision 5 August 1999 O

-Q' The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This report shall also include an assessment of radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from pnmary effluent pathways and direct radiation, for the previous calendar year, The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM and in compliance with 10 CFR 20 and 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation."

12.7.2 Annual Radioactive Effluent Release Report ** l The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21," Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Matenalin Liquid and Gaseous Effluent from Light-Water.

Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Annual Radioactive Effluent Release Report shallinclude a list and description of unplanned releases of radioactive materialin liquid effluents from the site to UNRESTRICTED AREAS and of unplanned releases of radioactive material in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY during the reporting period.

/G The Annual Radioactive Effluent Release Report shallinclude any changes made during the Q reporting period to the Process Control Program as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.7.4.

The Annual Radioactive Effluent Release Report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11 or 3.12, respectively.

12.7.2.1 Exceptions to Regulatory Guide 1.21 Reporting Requirements:

a. All references to " semiannual" are not applicable. The report will be submitted according to Technical Specifications.

b. Hourly meteorological data is recorded for all periods throughout the year, and quarterly summaries will be reported. Separate mnteorological data for periods of batch releases are not required to be included.

c. Total body and significant organ doses to the maximally exposed individual from receiving-water-related exposure pathways will be provided. Associated population dose is not required to be included.

V 212r5 doc 12 49

i

, . * ' ZION Rsvision 5 '

August 1999

d. Organ doses to the maximally exposed individualin unrestricted areas from p radioactive iodine and radioactive matenal in particulate form from all exposure Q pathways will be provided. Associated population dose is not required to be included. l

e. Total body doses to the maximally exposed individual in unrestricted areas from direct radiation from the facility should be included in the report. Associated population dose is not required to be included.

I

f. Total body doses to the population and average doses to individuals in the i population from all receiving-water-related pathways are not required to be included. l 1

g. Total body doses to the population and average doses to individuals in the ;

population from gaseous effluents to a distance of 50 miles from the site and beyond ,

will not be included. !

i

" A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

1 i

[

%J zi2r5. doc .

12 50

ZION Rsvision 5 August 1999 12.7.3 Offsite Dose Calculation Manual (ODCM) 12.7.3.1 Changes to the ODCM;

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.5.2. This documentation shall contain: l

1. Sufficient Information to support the change together with the appropnate analyses or evaluations justifying tne change (s); and j

1

2. A determination that the change will maintain the level of radioactive

{

effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 1 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

3. Documentation of the fact that the change has been reviewed and found acceptable by the Onsite Review Function.

b. 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.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concerent with the Annual Radioactive Effluent Release Report for the period of the report in whit.h 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 shallindicate the date (e.g.,

O. month / year) the change was implemented.

O zi2r5 doc 1 12-51

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( / , ZION Rsvision 5 August 1999 12.7.4 Maior Chancesjo liquid and Gaseous Effluent Treatment Systems *"

O Licensee-initiated major changes to the Effluent Treatment Systems (liquid and gaseous):

a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the penod in which the evaluation was reviewed by the Onsite Review and Investigative Function. The discussion of auch change shall contain:

1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplementalinformation;

3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.

4) An evaluation of the change which shows the predicted releases of radioactive materiais in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto;

5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC and to the general population that differ from those previously estimated in the License application and amendments thereto;

6) A comparison of the predicted releases of radioactive materials, in liquid and p gaseous effluents, to the actual releases for the period prior to when the changes are to be made:

7) An estimate of the exposure to plant operating personnel as a result of the change; and

8) Documentation of the fact that the change was reviewed and found acceptable by the Onsite Review and investigative Function.

b. Shall become effective upon review and acceptance by the Onsite Review and investigative Function.

-"* Licensees may choose to submit the information called for in this standard as part of the annual FSAR update.

l I

f%

O 212r5. doc 12-52

ML20216G135

Text

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