B13065, Application for Amend to License DPR-61,changing Tech Spec Tables 7.2-1 & 8.2-1 to Identify Which Radiation Monitors Required to Be Operable.Fee Paid

Application for Amend to License DPR-61,changing Tech Spec Tables 7.2-1 & 8.2-1 to Identify Which Radiation Monitors Required to Be Operable.Fee Paid

ML20206B679
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	11/07/1988
From:	Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20206B683	List: B13065, Application for Amend to License DPR-61,changing Tech Spec Tables 7.2-1 & 8.2-1 to Identify Which Radiation Monitors Required to Be Operable.Fee Paid ML20206B685
References
B13065, NUDOCS 8811150532
Download: ML20206B679 (3)

Text

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H ARTFORD. CONNECTICUT 06141-0270 L L J [ZlC,',(([, (203) 665-5000 November 7, 1988 Docket _.No. 50-213 B13065 Re: 10CFR50.90 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Haddam Neck Plant Proposed Revision to Technical Specifications Radioactive Liouid Effluent Monitorina Instrumentation Pursuant to 10CFR50.90, Connecticut Yankee Atomic Power Company (CYAPCO) hereby proposes amending its operating license, DPR-61, by incorporating the changes identified in Attachment I into the Technical Specifications of the Haddam Neck Plant.

Specifically, the proposed changes to Tables 7.2-1 and 8.2-1 identify which radiation monitors are required to be operable.

The radiation monitor on the waste and recycle test tank discharge line is identified as R-22. Waste test tank effluent is routed through the liquid waste discharge flow control valve, WD-FRCV-1003. A portion of the effluent is routed past R-22 and then rejoins the main service water discharge header to the river. A flow measuring device downstream of the detector is used to adjust the flowrate past the detector. High activity will automatically close WD-FRCV-1003 to prevent the discharge of liquid waste with higher than expected activity.

The radiation monitors on the steam generator blowdown lines are identified as R-16A and B. A continuous sample of steam generator shell-side water, extracted from all four blowdown lines, is cooled by steam generator sample coolers, mixed together in a common header and analyzed by each monitor for unusual activity. The sample passes in front of the detector and is then directed to the steam generator blowdown tank. Modifications to install automatic termination of bbwdown upon high activity are scheduled to be implemented during the 1990 refueling outage.

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U.S. Nuclear Regulatory Comission B13065/Page 2 November 7, 1988 The radiation monitor on the service water effluent line is identified as R 18. A sample pump sends a small service water sample to a fixed volume holdup tank near the detector. The sample stream then rejoins the main service water discharge. A flow measuring device downstream of the detector is used to adjust the flowrate )ast the ' detector. Action Statement number three to Table 7.2-1 is being c1anged from "effluent releases" to "service water discharge" to clarify any potential ambiguity in allowable release.

The proposed changes are intended as clarification only. There is no change in the requirements nor the intent of the Technical Specification.

CYAPCO has reviewed the proposed changes in accordance with 10CFR50.92 and has concluded that they do not involve a significant hazards consideration in that the changes would not:

1. Involve a significant increase in the probability or consequences of an accident previously analyzed. The proposed changes are intended for clarification only and in no way change the intent of the Technical Specifications.

2. Create the possibility of a new or different kind of accident from any previously analyzed. Since there are no changes in the way the plant is operated, the potential for an unanalyzed accident is not created. The proposed changes are purely editorial and have no affect on plant operation.

3 Involve a significant reduction in a margin of safety. The proposed changes clarify which radiation monitors are required to be operabic and have no affect on the way the plant is operated. Since the proposed changes do not affect the consequences of any accident previously analyzed, there is no reduction in the margin of safety.

Moreover, the Commission has provided guidance concerning the application of standards in 10CFR50.92 by providing certain examples (March 6,1986, FR7751) of amendments that are considered not likely to involve a significant hazards consideration. The proposed changes are enveloped by Example (1), a purely administrative change to technical specifications, correction of an error, or a change in nomenclature. The changes proposed herein are intended to clarify which radiation monitors are required to be operable as well as clarify any ambiguity concerning allowable release.

Based upon the information contained in this submittal and the environmental assessment for the Haddam Neck Plant, there are no significant radiological or nonradiological impacts associated with the proposed action, and the proposed license amendment will not have a significant effect on the quality of the human environment.

The Haddam Neck Nuclear Review Board has reviewed and approved the attached proposed revisions and has concurred with the above determinations.

U.S. Nuclear Regulatory Commission i B13065/Page 3 November 7, 1988 l.

In accordance with 10CFR50.91(b), we are providing the State of Connecticut  :

with a copy of this proposed amendment.  ;

Pursuant to the requirements of 10CFR170.12(c), enclosed with this amendment I request is the application fee of $150.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY f/)k ut./

E. J. Mroczka ,7 i Senio,r Vice President l

cc: W. T. Russell, Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant  !

J. T. Shediosky Senior Resident Inspector, Haddam Neck Plant  !

STATE OF CONNECTICUT  !

ss. Berlin i COUNTY OF HARTFORD

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Then personally appeared before me, E. J. Mroczka, who being duly sworn, did state that he is Senior Vice President of Connecticut Yankee Atomic Power Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein, and that the statements contained in said information are true and correct to the best of his knowledge and belief. ,

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