ML20215M452

Proposed Tech Specs Re RCS Iodine Activity Limits & Surveillance Requirements

ML20215M452
Person / Time
Site:	Oyster Creek
Issue date:	10/23/1986
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20215M444	List: ML20215M443 ML20215M449 ML20215M452
References
NUDOCS 8610300256
Download: ML20215M452 (6)

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PROPOSED CHANGE 4

RADIOACTIVE EFFLUENTS APPENDIX A TO PROVISIONAL OPERATING LICENSE DPR-16 OYSTER CREEK NUCLEAR GENERATING STATION J

GPd NUCLEAR CORPORATION

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TABLE OF CONTENTS Section 1 Definitions. Page 1.1 Operable 1.0-1 1.2 Operating 1.0-1 1.3 Power Operation 1.0-1 1.4 Startup Mode 1.0-1 1.5 Run Mode 1.0-1 1.6 Shutdown Condition 1.0-1 1.7 Cold Shutdown 1.0-1 1.8 Place in Shutdown Condition 1.0-2 1.9 Place in Cold Shutdown Condition 1.0-2 1.10 Place in Isolated Condition 1.0-2 1.11 Refuel Mode 1.0-2 1.12 Refueling Outage 1.0-2 1.13 Primary Containment Integrity 1.0-2 1.14 Secondary Containment Integrity 1.0-2 1.15 Deleted 1.0-3 1.16 Rated Flux 1.0-3 1.17 Reactor Thermal Power-To-Water 1.0-3 1.18 Protective Instrumentation Logic Definitions 1.0-4 1.19 Instrumentation Surveillance Definitions 1.0-4 1.20 FDSAR 1.0-4 1.21 Core Alteration 1.0-5 1.22 Minimum Critical Power Ratio 1.0-5 1.23 Staggered Test Basis 1.0-5 1.24 Surveillance Requirements 1.0-5 1.25 Fice Suppression Water System 1.0-5 1.26 Fraction of Limiting Power Density (FLPD) 1.0-6 1.27 Maximum Fraction of. Limiting Power Density (MFLPD) 1.0-6 1.28 Fraction of Rated Power (FRP) 1.0-6 1.29 Top of Active Fuel (TAF) 1.0-6 1.30 Process Control Plan 1.0-6 1.31 Augmented Offgas System (A0G) 1.0-6 1.32 Member of the Public 1.0-6 1.23 Offsite Dose Calculation Manual 1.0-6 1.34 Purge 1.0-7 1.35 Exclusion Area 1.0-7 1.36 Reportable Event 1.0-7 1.37 Dose Equivalent I-131 1.0-7 1.38 Hot Shutdown 1.0-7 Section 2 Safety Limits and Limiting Safety System Settings 2.1 Safety Limit - Fuel Cladding Integrity 2.1-1 2.2 Safety Limit - Reactor Coolant System Pressure 2.2-1 2.3 Limiting Safety System Settings 2.2-3 l Section 3 Limiting Conditions for Operation i 3.0 Limiting Conditions for Operation (General) 3.0-1 j 3.1 Protective Instrumentation 3.1-1 3165f

-o 1.0-7 1.34 PURGE PURGE or PURGING is the controlled process of discharging air or gas

. from a confinement and replacing it with air or gas.

1.35 EXCLUSION AREA EXCLUSION AREA is defined in 10 CFR Part 100.3(2). As used in these technical specifications, the Exclusion Area boundary is the perimeter line around the OCNGS beyond which the land is neither owned, leased, nor otherwise subject to control by GPU (ref. ODCM Figure 1-1). The area outside the Exclusion Area is termed 0FFSITE.

1.36 REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

1.37 DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 microcuries per gram which alone would produce the same thyroid dose, if inhaled by an adult, as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluences for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I".

1.38 HOT SHUTDOWN The reactor is at HO'T SHUTDOWN when the mode switch is in the shutdown mode position, there is fuel in the reactor vessel, all operable control rods are fully inserted, and the reactor coolant system maintained at greater than 212*F.

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3.6-1 3.6 Radioactive Effluents ,

Applicability: Applies to the radioactive effluents of the facility.

Objective: 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 CFR part 20.106 and 40 CFR Part 190.10(a).

Specification 3.6.A. Reactor Coolant Radioactivity 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.) I-131.

Limiting Condition for Operation

1. Whenever an isotopic analysis shows reactor coolant activity exceeds 0.2 uCi/ gram DOSE EQUIVALENT (D.E.) I-131, additional analyses shall be done at least 6 times within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or until the specific activity of the primary coolant is restored to within its limit.

2. If the reactor coolant activity is greater than 0.2 uCi/ gram D.E. I-131 but equal to or less than 4 uCi/ gram D.E. 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, be in at least HOT SHUTDOWN with the main steamline isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3. If a sample of the reactor coolant activity is greater than 4 uCi/ gram D.E. I-131, a second sample shall be taken and analyzed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. If the second sample indicates that the reactor coolant activity is greater than 4 uCi/ gram D.E. I-131, be in at least HOT SHUTDOWN with the main steamline isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the second sample indicates that the reactor coolant activity is less than or equal to 4 uCi/ gram D.E. I-131, the statement 3.6.A.2 shall apply.

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4. 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 o an annual basis. The following infort.._.*. ton shall be included: (1) Reactor power history starting 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> prior to the first sample in which the limit was exceeded until after the radiolodine activity is reduced to less than the limit; (2)

Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than the limit. Each result should include date and time ;f sampling and the radioiodine concentrations; (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 radiolodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

3.6.B Liquid Radwaste Treatment Applicability: To liquid radwaste batches before i

discharge as aqueous effluent.

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i 4.6-1  ;

i 4.6 RADIOACTIVE EFFLUENT i- Applicability: Applies to monitoring of gaseous and liquid radioactive effluents of the Station during release of effluents via the monitored pathway (s). Each

Surveillance Requirement applies whenever the corresponding Specification is applicable unless otherwise stated in an indi.vidual Surveillance i Requirement. Surveillance Requirements do not have to be performed on inoperable equipment.

Objective To measure radioactive effluents adequately to verify that radioactive effluents are as low as is reasonable achievable and within the limit of 10 CFR ll Part 20.106.

Specification: 4.6.A Reactor Coolant l Reactor coolant shall be sampled and~

! analyzed at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for i DOSE EQUIVALENT I-131 during RUN MODE,

' STARTUP MODE and HOT SHUTDOWN.

s 4.6.B (See 4.6.I) 4.6.C Radioactive Liquid Storage

1. Liquids contained in the following tanks shall be sampled and analyzed for i radioactivity at least once per 7 days when radioactive liquid is being added to the tank:

a. Waste Surge Tank, HP-T-3;

b. Condensate Storage Tank. '

i- 4.6.D Main Condenser Offgas Treatment i

l 1. Operation of the Offgas System charcoal j absorbers shall be verified by verifying the A0G System bypass valve (V-7-31) alignment or alignment indication closed at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the' main condenser air ejector is operating.

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