ML20154F492

Amend 126 to License DPR-16,revising Requirement on Max Radioiodine Concentration Allowed in Reactor Coolant

ML20154F492
Person / Time
Site:	Oyster Creek
Issue date:	09/12/1988
From:	Stolz J Office of Nuclear Reactor Regulation
To:	GPU Nuclear Corp, Jersey Central Power & Light Co
Shared Package
ML20154F495	List: ML20154F492 ML20154F500
References
DPR-16-A-126 NUDOCS 8809200020
Download: ML20154F492 (10)

Text

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UNITED STATES

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NL7 LEAR REGULATORY COMMISSION t

y WASHINGTON. D. C. 20656 1

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GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER 8 LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENOMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 126 License No. DPR-16 1.

The Nuclear Regulatory Comission (the Comissien) has founo that:

A.

The application for amendment by GPU Nuclear Corporation, et al.,

(the licensee), dated October 23, 1986 as supplemented April 5, 1988, j

complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rulos and regulations set forth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

'There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in con:pliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Provisional Operating License No. DPR-16 is hereby amended to read as follows:

(2) Technical Spccifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.126, are hereby incorporated 'in the licenre. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be implemented within 60 days.

FOR THE FUCLEAR REGULATORY COMMISSION

/1 ohn F. Stol i ector Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specificatic;.s Date of Issuance: S"Ptember 12, 1988

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ATTACRMENT TO LICENSE AMENDMENf NO.126 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCK,ET NO. 50-219 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Ir. sert i

Page i Page i Page 1.0-7 Page 1.0-7

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Page 3.6-1 Page 3.6-la Page 3.6-1b Page 3.6-7 Page 3.6-7a Page 3.6-7b Page 4.6.1 P.;e 4.6.1 i

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 1.0-2 1.8 Place in Shutdown Condition 1.0-2 1.9 Place in Cold Shutdown Condition 1.0-2 1.10 Place in Isolated Cond'ition 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 Themal Power-To-Water 1.0-3 1.18 Protective Instrumentation Logic Definitions 1.0-3 1.19 Instrumentation Surveillance Definitions 1.0-4 1.20 FDSAR 1.0-4

1. 21 Core Alteration 1.0-4 1.22 Minimum Critical Power Ratio 1.0-4 1.23 Staggered Test Basis 1.0-4 1.24 Surveillance Requirements 1.0-5 1.25 Fire Suppression Water System 1.0-5 1.26 Fraction of Limiting Power Density (FLPD) 1.0-5 1.27 Maximum Fraction of Limiting Power Density (MFLPD) 1.0-5 1.28 Fraction of Rated Power kRP) 1.0-5 1.29 Top of Active Fuel (TAF) 1.0-5 1.30 Reportable Event 1.0-5 1. 31 Identified Leakage 1.0-6 1.32 Unidentified Leakage 1.0-6 1.33 Process Control Plan 1.0-6 1.34 Augmented Offgas System (A0G) 1.0-6 1.35 Member of the Public 1.0-6 1.36 Offsite Dose Calculation Manual 1.0-6 1.37 Purge 1.0-6 1.38 Exclusion Area 1.0-6 1.39 Dose Equivalent I-131 1.0-7 l

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 Section 3 Limiting Conditions for Operation 3.0 Limiting Conditions for Operation (General)

3. 0-1 3.1 Protective Instrumentation 3.1 -1 OYSTER CREEK i

Amendnent No. : f4, #4', 77,19ff,126

1.39 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 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".

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A en ment.

6 OYSTER CREEK 1.0-7

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, 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 coolant is restored to within its limit.

2.

If the reactor coolant activity is greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 i

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. I-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.

Annual Reporting Requirment 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 infonnation shall be included:

(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 to the first sample in which the limit was exceeded until after the radiotodine activity is reduced to less than the limit; (2) Results of the last isotopic analysis for radioiodine perfonned prior to exceeding the limit, results of analysis while OYSTER CREEX 3.6-la knendment No.: W M6' 126

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4 limit was exceeded and results of one analysis after radiofodine activity was reduced to less than the limit.

Each result should include date and time of sampling and the radiofodine 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 radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-stato level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiof odine limit.

4.

With the reactor mode switch in Run or Startup position, with:

1.

Thennal 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

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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,

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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 themal 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 Liquid Radwaste Treatment Applicability: To liquid radwaste batches before discharge as aqueous effluent.

If there are consecutive themal power changes by more th'an 155 per hour, 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 and at least once per four hours thereafter, until the specific activity of the primary coolant is restored to within limits.

0YSTER CREEX 3.6-lb Amendnent h. : F, 308',126

Basis:

3.6.A 10CFR100, as implemented by SRP Section 15.6.4, requires that the radiological consequences of failure of a main steam line outside containment be limited to small fractions of the exposure guidelines of 10CFR100. During Systematic Evaluation Program (SEP) f.,r Oyster Creek, an irdependent assessment of the radiological consequences of a main steam line failure outside containment (SEP Topic XY-18) was perfonned by the NRC staff.

The assessment detennined that if the existing Oyster Creek Technical Specification limit for primary coolant iodine acti:ity (8.0 uCi total fodine per gram) is used, the potential offsite doses would exceed the applicable dose limit. The staff recomended that Oyster Creek maintain the primary coolant radiciodine activity within the General Electric Standard Technical Specification (NUREG-0123) limit (0.2 uCi/ gram DOSE EQUIVALENT I-131), which would meet the acceptance criteria.

However, the Staff's analyses for Oyster Creek i

showed that small-line failures are more limiting than the main steam line failure.

10CFR100, as implemented by SRP Section 15.6.2, requires that the radiological consequences of failure of small lines carrying primary coolant outside containment be limited to small fractions of the exposure guidelines of 10CFR100. During the evaluation of SEP Topic XY-16 "Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Outside Containment" the Staff detennined that Oyster Creek does not comply with current acceptance criteria. The Staff recomended that the General Electric Standard Technical Specification (NUREG-0123) limit (0.2 uCi/ gram DOSE EQUIVALENT I-131) for reactor coolant radiciodine activity be adopted in order to ensure that the radiological consequences to the environment from a failure of small lines are acceptably low.

0YSTER CREEK 3.6-7a Anendment No.: g, 10ff,126 53649

The LCO statement permitting power operation to continue for limited time periods with the primary' coolant's specific activity greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131, but less than or equal to 4.0 microcuries per gram DOSE EQtlIVALENT I-131, acconnodates possible iodine spiding phenomenon 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 will allow sufficient time for Commission to evaluate the circumstances.

Information obtained on todine spiking will be used to assess the parameters associated with spiking phenomena.

A reduction in frequency of isotopic analysis following power changes may be permissible

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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 i

sufficient time to take corrective action.

3.6.B This specification implements the requirements of 10 CFR 50.364 related to operation of radioactive waste treatment equipment to keep radioactive material in effluents to unrestricted areas as low ar. reasonably achievable.

Radioactive liquid wastes generated at the OCNGS are controlled on a batch basis with each batch processed by a method appropriate fo" the quality and concentration of material present.

Below 0.001 uCi/ml, it is not cost-beneficial to treat a batch of aqueous waste for the purpose of reducir;g potential radiation exposure offsite.

Hence specification 3.6.B implements 10 CFR 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 radioactivity before release to the discharge canal so that an appropriate discharge rate can be determined, accounting for dilution by condenser cooling water and/or canal flow.

0YSTER CREEK 3.6-7b Amendment No.:

49', 10s, 126 l

53649

4.6 RADIOACTIVE EFFLUENT 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 individual Surveillance Requi rement.

Surveillance Requirements do not have to be perfonned 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 Part 20.106.

Spect fication:

A.

Reactor Coolant 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 DOSE EQUIVALENT I-131 during RUN MODE, STARTUP MODE and SHUTDOWN CONDITION.

B.

(See 4.6.1)

C.

Radioactive Liquid Storage 1.

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

s

. aste Surge Tank, HP-T-3; W

a.

b.

Condensate Storage Tank.

D.

Main Condenser Offgas Treatment 1.

Operation of the Offgas System charcoal 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, i

E.

Main Condenser Offgas Radioactivity l

U The gross radioactivity in fission gases discharged from the main condenser air ejector shall be measured by

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sampling and analyzing the gases.

l a.

at least once per month, and b.

When the reactor is operatin at more than 40 percent of rated power, with 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> after an increase in the fission gas release via the air l

ejector of more than 50 pr n.ent, as indicated by e

the Condenser Air Ejector Offgas Radioactivity i

Monitor after factoring out increase (s) due to change (s) in the thennal power level.

OYSTER CREEK 4.6-1 Amendment No.: % 126 I

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