ML20150D675

Application for Amend to License DPR-61,revising Tech Specs That Provide Limiting Conditions for Operation & Surveillance Requirements in Response to Generic Ltr 83-37. Fee Paid

ML20150D675
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/01/1988
From:	Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20150D677	List: A06214, Proposed Tech Specs,Providing Limiting Conditions for Operation Per Generic Ltr 83-37 ML20150D675
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.B.3, TASK-2.E.1.1, TASK-2.F.2, TASK-3.D.3.4, TASK-TM A06214, A6214, GL-83-37, TAC-54393, TAC-54538, NUDOCS 8807140101
Download: ML20150D675 (3)

Text

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NORTHEAST UTILITIES cenerai ottices . seicen street. seriin. connecticut t j ,

03) 5 July 1, 1988 q 19t No. 50-213 Roc A06214 Re: 10CFR50.90 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

Reference:

(1) F. M. Akstulewicz letter to J. F. Opeka, Outstanding Technical Specification Issues, dated November 13, 1986.

Gentlemen:

Haddam Neck Plant Proposed Changes to Technical Specifications Generic Letter 83 NUREG-0737 (TAC Nos. 54538, 54393)

Pursuant to 10CFR50.90, Connecticut Yankee Atomic Power Company (CYAPC0) hereby proposes to amend its Operating License, DPR-61, by incorporating the attached changes into the Technical Specifications for the Haddam Nack Plant.

Specifically, the proposed changos included in Attachment (1) to this letter, consist of new Technical Specifications and revisions to the existing Techni-cal Specifications that provide limiting conditions for operation (LC0) and surveillance requirements in response to Generic Letter 83-37, as applicable to the Haddam Neck Plant (Reference (1)). Below is a listing of items that are addressed in this submittal. The item numbers to the right represent the TMI NUREG-0737 topic numbers associated with each Technical Specification changes.

o Reactor Coolant System Vents (II.B.1) o Post Accident Sampling (11.8.3) o Long Term Auxiliary Feedwater System (II.E.1.1) o Noble Gas Effluent Monitors (II.F.1.1) o Sampling and Analysis of Plant Effluents (II.F.1.2) o Containment High-range Radiation Monitor (II.F.1.3i o

Containment Pressure Monitor (II.F.1.4) o Containment Water Level Monitor (II.F.1.5) o Containment Hydrogen Monitor (II.F.1.6) o Instrumentation for Inadequate Core Cooling (II.F.2) o Control Room Habitability (III.D 3.4)

Attachment 2 provides a discussion on each of the above items, how they compare to the model specifications recommended by Generic Letter 83-37 and why CYAPC0's proposed changes are from the model justified. Two additional proposed changes to Technical Specification Table 3.9.2 :.escribed in Attachment 2 are not directly related to Generic Letter 83-37 and ar 8807140101 880701 PDR ADOCK 05000213 O N A( 8g6 P PDC 0 4

i U.S. Nuclear Regulatory Commission A06214/Page 2 July 1,1988 editorial in nature. As such they do not involve a significant hazards W consideration.

CYAPC0 has reviewed the proposed changes in accordance with 10CFR50.92 and has determined that they involve no significant hazards considerations. The basis of the determination is discussed in Attachment 2.

rioreover, 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 changes proposed herein are enveloped by example (ii), a change that constitutes an additional limitation, restrittion or control not previously included in the Technical Specifications. These proposed changes would add LCOs and surveillance requirements for the post accident monitoring instrumentation and systems. This will help ensure the operability and reliability of instrumentation and systems that monitor the course of an accident.

With respect to the proposed changes to Technical Specification Table 3.9-2, our review of the given examples in 51FR7751, March 6, 1986, of amendments that are considered not likely to involve a significant hazards consideration has determined that example (i), a purely administrative change to the Techni-cal Specifications is applicable. The proposed changes to Technical Specifi-cation Table 3.9-2 are editorial in nature.

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

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 request is the application fee of $150.00.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY

1. 6 &a/

L.Wjtiroczka 9 Seni6r Vice President l

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1 U.S. Nuclear Regulatory Commission A06214/Page 3 July 1, 1988 cc: W. T. Russell, Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plunt J. T. Shedlosky, Senior Resident Inspector, Haddam Neck Fiant Kevin McCarthy Director of Radiation Control Unit Department of Environmental Protection Hartford, Connecticut 06116 STATE OF CONNECTICUT)

) ss. Berlin COUNTY OF HARTFORD )

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 Licensee herein, and that the statements contained in said infor,aation are true and correct to the best of his knowledge and belief.

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Not'ary Public