ML20073H920

Proposed Tech Specs 3.6,3.15 & 4.15,eliminating Requirement to Monitor Liquid Radwaste Effluent Line W/Radiation Monitor & Recognizing Batch Releases W/Double Sampling as Primary Means of Controlling Releases Via Pathway

ML20073H920
Person / Time
Site:	Oyster Creek
Issue date:	04/29/1991
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20073H883	List: ML20073H880 ML20073H912 ML20073H920
References
NUDOCS 9105070309
Download: ML20073H920 (9)

Text

?. e, 3.6 Radioactive Effluen1A Aeoli cabilit y : Applies to the radioactive effluents of the facility.

Obiectives To assure that radioactive material is not released to the environment in an uncontrolled manner and to assure that the radioactive concentrations of any material released is kept as low as is reasonably achievable and, in any event, within the limits of 10 CPR part 20.106 and i 40 CPR Part 190.10(a).

Specification 3.6.A. Reactor Coolant Radicactivity The specific activity of the primary coolant except during REFUEL MODE shall be limited to: Less than or equal to 0.2 microcuries per gram DOSE EQUIVALENT (D.E.) 1-131.

Limiting condition f or Operation

1. Whenever an isotopic analysis shows reactor coolant activity exceeds 0.2 uCi/ gram DOSE EQUIVALENT (D.E.) 1-131, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Additional analyses shall be done at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until the specific activity of the primary ceolant is restored to within its limit.

2. If the reactor coolant activity is greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than 4.0 microcuries per gram D.E. 1-131, be in at least SHUTDOWN CONDITION within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 3

3. Annual Reporting Requirement The results of specific activity analyses in which the reactor coolant exceeded the limits of Specification 3.6.A shall be reported on an annual basis. The following information shall be includeds.(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior 1 to the first sample in which the limit was exceeded until after the radiciodine activity is reduced to less than the limit; (2) Results of th6 last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after radiciodine activity was reduced to loss than the limit. Each result should include dato and tLme of sampling and the radiciodine coa.contrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded until after the radiciodine activity is reduced to less than the limit; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcurice per gram as a function of time for the duration of the specific activity above the steady-state level; and (t)

The time duration when the specific activity of the primary coolant exceeded the radiolodine limit.

OYSTER CREEK 3.6-la Amendment No.: 48, 108, 126 h 0 gOCK o9 910429 05000219 P

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4. With the reactor modo switch in Run or Startup position, with:

1. Thermal power changed by more than 15% of rated thermal power in one hour *, or

2. The off-gas level, at the SJAE, increased by more than 10,000 microcuries per second in one hour during steady state operation at release rates less than 75,000 microcuries per second, or

3. The off-gas level, at the SJAE, increased by more than 15%

in one hour during steady state operation at release rates greater than 75,000 microcuries per second, take sample and analyze at least one sample, between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the change in thermal power or off-gas level and at least once per four hours thereafter, until the specific activity of the primary coolant is restored to within limits.

3.6.B Llauld Radwaste Treatment an3 Discharae Applicability: To liquid radwaste batches for discharge as aqueous effluent.

1. Any untreated batch of liquid radwaste shall be treated (in appropriate liquid radwaste treatment equipment) before discharge as aqueous effluent when the radioactivity concentration, exclusive of tritium and dissolved noble gases, in the batch exceeds 0.001 ci/ml.

2. When radioactive 11guid waste is discharged without treatment and in excess of the above limit, in lieu of any other report, prepare and submit to the commission within 30 days pursuant to specification 6.9.3 a special Report that includes the following information.

a. Identification of any inoperable equipment or subsystems, and the reason for the inoperability.

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and a

c. Summary description of action (s) taken to prevent a recurrence.

• If there are consecutive thermal power changes by more than 15% per hour, take sample and analyze at least gng sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> .

following the change and at least once per four hours thereafter, until i the specific activity of the primary coolant is restored to within limits.

1 OYSTER CREEK 3.6-1b Amendment No.: 49, 108, 126 l

3. Specifications 3.0. A and 3.0.B do not apply.

l 4.- Liquid radwaste discharges may occur provided thats

a. At least two independent batch samples shall be taken, one prior to discharge and one near the completion of discharge. These samples shall be analyzed in accordance with specification 4.6.I.1.

b. Prior to discharge, qualified personnel shall determine an acceptable release rate and establish proper dischargo valving. Other qualified personnel shall indeper.dently verify that the release rate and discharge valv'.ng are acceptable.

3.6.C Radioactive Lieuid Storace Applicability: Applies at all times to specitled outdoor tanks used to store radioactive liquids.

1. The quantity of radioactive material, excluding tritium, noble gases, and radionuclides having half-lives shorter than three days, contained in any of the following outdoor tanks shall not exceed 10.0 curies:

a. Waste Surge Tank, HP-T-3

b. condensate Storage Tank

2. In the event the quantity of radioactive material in any of the tanks named exceeds 10.0 curies, begin treatment as soon as reasonably achievable, continue it until the total quantity of radioactive material in the tank is 10 euries or less, and deveribe the reason for exceeding the limit in the next semi-annual Effluent Release Report.

3. Specifications 3.0.A and 3.0.B do not apply.

3.6.D condensor offoas Treatment Applicability: Whenever the main condenser air ejector system is in operation except during startup or shutdown with reactor power less than 40 percent of rated. In addition, the Augmented offgas System need not be in operation during end of cycle coast-down periods when the system can no longer function due to low offgas f l o' t.

OYSTER CREEK 3.6-2 Amendment No.: 49, 108

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Th3 LCO ctetement permitting pow 3r operation to continus for limited time periods with the primary coolant's specific activity greater than 0.2 microcuries per gram DOSE EQUIVALENT I I-131, but less than or equal to 4.0 microcuries per gram DOSF j EQUIVALENT I-131, accommodates possible iodine spiking l

phenoruenon which may occur following changes in thermal power. The reporting of cumulative operating time with greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 .

I will allow sufficient time for Commission to evaluate the circumstances. i Information obtained on iodine spiking will be used to asess ,

the parameters associated with spiking phenomens. A reduction I in frequency of isotopic analysis following power changes may I be permissible if justified by the data obtained.

The surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

3.6.D This specification implements the requirements of 10 CTH

$0.36a related to opsration of radioactive waste treatment equipment to keep radioactive niatorial in ef fluents to unrestricted areas as low as reasonably achievable.

Radioactive liquid wastes generated at the OCNGS are controlled on a batch basia with each batch processed by a method appropriate for the quality and concentration of material present. Below 0.001 uci/m1, it is not cost-beneficial to treat a batch of aqueous waste for the purpose of reducing potential t adiation exposure of f site.

Hence specification 3.6.B implements 10 CrR Part 50 Appendix I provisions for cost-beneficial treatment of radioactive liquid waste before release in effluent. Each batch of radioactive liquid waste is sampled and analyzed for radioacivity before release to the discharge canal so that an appropriste discharge rate can be determined, accounting for dilution by condenser cooling water and/or canal flow.

The method of double sampling and independent verification of release rate and valve alignment is adequate to ensure liquid radwaste batch discharges are in compliance with the concentration limits of 10 CFR 20 in the discharge canal at the Route 9 bridge.

OYSTER CREEK 3.6-7b- Amendment No.: 49, 100, 106

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4. Wh n icon than ths minimum number of radioactivo goesous monitoring instrumentation channelt are OPERADLE, take the ACTION shown in Table i 3.15.2. Make every reasonable effort to restore the instrument to '

OPERADLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

D. The Provisions of Specifications 3.0.A, 3.0.D, and 6.9.2 are not applicable.

Unmio A. The radioactive liquid ef fluent instrumentation is provided to n.cnitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The use of this instrumentation is consistent with the requirements of General Design criteria 60 and 64 of Appendix A to 10 CFR Part 50. A radioactivity monitor on the liquid effluent line from the Turbine Building Sump No. 1-5 initiates a trip to stop the effluent discharge pump when the trip setpoint is exceeded. The reactor service water system discharge line radioactivity monitor initiates an alarm in the reactor control room when the alarm setpoint is exceeded. A method for double sampling and independent verification of release rate and valve alignment is used in lieu of a radiation monitor for batch releases via the liquid cadwaste effluent line.

The alarm / trip setpoint for each of these instruments is calculated and adjusted in accordance with the methodology and parameters in the ODCH to ensure that'the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.106.

D. The radioactive gaseouw effluent instrumentation le provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during releases of gaseous effluents. The alarm / trip setpoint for each of the noble gas monitors is calculated and adjusted in accordance with the methodology and parameters in the ODCH to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.106. The instrumentation in Table 3.15.2 also includen provisions for monitoring hydrogen below the explosive level in the offgan system downstream from the recombiner. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50. The offgan hydrogen monitor and the radioactive gas monitors for the condenser air ejector offgas, the stack effluent, and the offgar building exhaust ventilation have alarms which report in the reactor control room. The offgas hydrogen monitor initiates a bypass of the Augmented Otfgas System in the event the setpoint is exceeded.

The Stack and the_ Turbine Building exhaust ventilation _ effluent air are monitored by a radioactive gaseous effluent monitoring system. It can measure the gross concentration of redioactive noble gases. A grab sample of the effluent air will be taken at least once per month and analyzed for the principal noble gas radionuclides (Reference Table 4.6.2).

The grose gamma activity concentration of noble gas in Stack effluent is-displayed in the reactor control room. That channel also causes an alarm OYSTER CREEK 3.15-2 Amendment No.: 108 y--tgr w wr,w ww ww w-wwrwy-y--wr-y - Ay r--*--- u- -t-i- q .i y -- +1PM8"- 9-U-F-

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TABLE 3.15.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum" Instrument Channels Applicability Action Operable

1. GROSS RADIOACTIVITY MONITORS

a. (Deleted)

b. Reactor dullding Service Water System Effluent Line 1 b 112

c. Turbine Building Sump I;o. 1-5 1 b 114

2. FLOW MEASUREMENT DEVICES

a. Liquid Radwante Effluent Line 1 b 113 OYSTER CREEK 3.15-4 Amendment No.: 100 i

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Table 3.15.1 Notations

a. Instrument.channele shall be OPERABLE and in service as indicated except that a channel may be taken out-of-service for the purpose of a check, calibration, test, or maintenance without declaring the channel to be inoperable.

b. During releases via this pathway.

ACTION 112 With no channel OPERABLE, effluent releases via this pathway may continue provided that, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the re' ease, grab samples are collected and analyzedforgrossradioactigity(betaorgamma) at a limit of detection of at leset 10' microcuries/ml.

ACTION 113 With no channel OPERABLE effluent releases via the affected pathway may continue provided the flow is estimated with the pump curve or change in tank level, at least once per batch during a release.

ACTION 114 With no channel operable effluent may be released provided that before initiating a release:

1. A sample le taken and analyzed in accordance with

. Specification 4.6.I.l.

2. Qualified personnel determine and independently verify the acceptable release rate.

OYSTER CREEK 3.15-5 Amendment No.: 108 t_________ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ________

TABLE 4.15.1 2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ,,

O g Channel

-p Channel Source Channel Functional Surveillance N Instrument Check Check C~libration Test Required" a

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M X l. Gross Radioactivity Monitors

a. [ Deleted]

b. Reactor Building Service Water f

System Effluent Line D M R Q* b

c. Turbine Building Sum No. 1-5 D M R Q* b

2. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line h D N.A. R Q b u.

I ta N

@ Leoend S = once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, D = once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, W = once per 7 days,

@ M = once per 31 days, Q = once per 92 days, SA = once per 184 days,

@ R = once per 18 months, S/U = before each reactor startup, P = completed before each release, N.A. = Not Applicable.

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a Instrumentation chall be-OPERABLE and in service except that a channel may -!

be taken out of service forfthe purpose of a-check,-calfbration, test or maintenance without declaring it to be inoperable.

.b. During releases via this pathway. }

c. This notation not used.

d.

:This notation not used.

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-e. The CHANNEL FUNCTIONAL TEST shall.also demonstrate that control room alarm annunciation occurs if any of the following conditions exists

1. Instrument indicates measured levels above the alarm setpoint.

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2. Instrument indicates a downscale failure,

3. Instrument controls not set in operate mode.

4. Instrument electrical power loss. -f

f. The CHANNEL CALIBRATION shall be performed according to established station. calibration procedures.

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g. This notation not used.

h. A CHANNEL-CHECK ehall consist of verifying indication of flow during.

effluent. release.. A CHANNEL CHECK shall be made at least once during any day on which a-release is made.

.l. The CHANNEL FUNCTIONAL TEST shall also demonstrate that-Control Room alarm-annunciator occurs if any of the following conditions exists

1. Instrument indicates measured levolu above the alarm setpoint.

2. Instrument indicates a downocale failure. ,

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a OYSTER GREEK 4.15-3 Amendment No.: '108 Y

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