ML20215M449

Application for Amend to License DPR-16,consisting of Tech Spec Change Request 148,revising Sections 3.6 & 4.6 Re RCS Iodine Activity Limits & Surveillance Requirements

ML20215M449
Person / Time
Site:	Oyster Creek
Issue date:	10/23/1986
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20215M444	List: ML20215M443 ML20215M449 ML20215M452
References
NUDOCS 8610300254
Download: ML20215M449 (3)

Text

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0YSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 148 DOCKET NO. 50-219 Applicant submits by this Technical Specification Change Request No. 148, to the Oyster Creek Nuclear Generating Station Technical Specifications.

By: TV :_ ^ f2- -

P8Ee M dler Vice President and Director Oyster Creek Sworn to and subscribed to before me this 673 day of ( , 1986.

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/ NOTARY 0F,-NEW J % EY

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CAROL A. SCARPINATO NOTARY PUBLIC Of NEW JERSEY My Commissian Expires feb.27,1991 K$hb0f}

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OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET No. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 148 Pursuant to 10 CFR 50.91, an analysis concerning significant hazards considerations is provided below:

1. Sections to be changed:

Table of Contents, 1.37 and 1.38, sections: 3.6 and 4.6.

2. Extent of changes:

To incorporate radioiodine limits in reactor coolant system and appropriate limiting conditions for operation as shown in Standard Technical Specifications for General Electric Boiling Water Reactors (NUREG-0123) reporting requirement for radioiodine spiking as shown in NRC Generic Letter 85-19, " Reporting Requirement on Primary Coolant Iodine Spikes" and provide definitions for DOSE EQUIVALENT I-131 and HOT SHUTDOWN.

3. Discussion:

On October 22, 1984 GPUN submitted Technical Specification Change Request (TSCR) No. 69, Revision 1, " Radiological Effluent Environmental Technical Specifications". The TSCR No. 69, Revision 1 proposed changes to sections 3.6 and 4.6 concerning reactor coolant system (RCS) radiciodine activity limits and surveillance requirements. These changes were proposed following discussions with the NRC staf f during the integrated assessment of the Systematic Evaluation Program (SEP) for Topic XV-16, " Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Outside Containment".

Subsequently, the staff requested re-submittal of the proposed changes for RCS radioactivity limits by providing definition for DOSE EQUIVALENT Iodine I-131, limits for non-iodine radioactivity in RCS and annual reporting requirement for radioiodine spiking as shown in Standard Technical Specifications for General Electric Boiling Water Reactors (NUREG-0123) and NRC Generic Letter 85-19, " Reporting Requirement on Primary Coolant Iodine Spikes". The staff also requested changes to Limiting Condition for Operation (also given in NUREG-0123).

TSCR 148, therefore has been prepared in response to the request by the staff described above and includes the information requested with exceptions of non-iodine radioactivity limits and a part of the Limiting Conditions (i.e., sampling requirement following changes in thermal power or off-gas level). These exceptions are being evaluated by GPUN and will be incorporated at a future date. Meanwhile, GPUN Specification No. 1302-28-001 " Technical Specification, Water Quality, Oyster Creek Nuclear Generating Station" addresses limit and monitoring 3202f

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requirements for-non-iodine radioactive effluent at the plant stack in order to assure that radioactive Waterial 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.

This change request provides definitions, limiting conditions for operation, surveillance and annual reporting requirement- to incorporate Standard Technical Specifications for General Electric Boiling Water Reactors (NUREG-0123) and NRC Generic Letter 85-19,

" Reporting Requirement on Primary Coolant Iodine Spikes". We have determined that this change request involves no significant hazards considerations in that operation of the Oyster Creek Plant in

, accordance with the proposed amendment will not:

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1. Involve a'significant increase in the probability of an accident previously evaluated, because the primary coolant activity is not an initiator of an accident. Also, the proposed change will not

increase the consequences of an accident, because the proposed change, a reduction of the primary coolant activity limit, will not result in increased amount of radioactive release for design basis accidents previously evaluated; or

2. Create the probability of a new or different kind of accident from any accident previously evaluated because a bounding design basis accident associated with changes in the primary coolant activity level was already evaluated and reported in FSAR (i.e., Control Rod Drop Accident); or 4

3. Involve a significant reduction in a margin of safety because more restrictive limit for the primary coolant radio-iodine activity will increase a margin of safety.

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