[Federal Register Volume 59, Number 229 (Wednesday, November 30, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-29484]


[[Page Unknown]]

[Federal Register: November 30, 1994]


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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-213]

 

Connecticut Yankee Atomic Power Co.; Haddam Neck Plant 
Environmental Assessment and Finding of No Significant Impact

    The U.S. Nuclear Regulatory Commission (the Commission) is 
considering issuance of an amendment to Facility Operating License No. 
DPR-61, issued to Connecticut Yankee Atomic Power Company (CYAPCO, the 
licensee), for operation of the Haddam Neck Plant, located in Middlesex 
County, Connecticut.

Environmental Assessment

Identification of the Proposed Action

    The proposed amendment would revise the Haddam Neck Technical 
Specification (TS) Table 3.3-2, ``Engineered Safety Features Actuation 
System Instrumentation,'' Table 3.3-3, ``Engineered Safety Features 
Actuation System Instrumentation Trip Setpoints,'' and Table 4.3-2, 
``Engineered Safety Features Actuation System Instrumentation 
Surveillance Requirements,'' and their associated Bases sections, to 
reflect the addition of permissive interlocks on the core deluge system 
motor-operated valves. The proposed action is in accordance with the 
licensee's amendment request dated August 4, 1994.

The Need for the Proposed Action

    CYAPCO is planning to install permissive interlocks on the core 
deluge valves SI-MOV-871A and B. The permissive interlocks will serve 
to block the opening of these valves until the reactor coolant pressure 
(RCS) has decreased below a specified setpoint. This modification is 
necessary to ensure that should an inadvertent safety injection 
actuation signal (SIAS) occur, the low pressure safety injection (LPSI) 
isolation valves would not open and expose the LPSI system piping, 
which has a design rating of 600 psi, to the normal operating pressure 
of the RCS, which is approximately 2000 psi. To assure the operability 
of the new permissive interlocks the licensee has proposed adding 
various components of the interlock system to the TS. In addition, the 
Bases section will be modified to include a discussion on the 
functioning of the core deluge motor-operated valves and their control 
circuitry.

Environmental Impacts of the Proposed Action

    In the present design a large break LOCA will generate a safety 
injection signal which will open the core deluge valves SI-MOV-871A and 
B to provide borated water to the reactor vessel. The new design will 
install redundant open permissive interlocks in the core deluge valve 
control circuitry to prevent opening of these valves on a SIAS until 
the RCS pressure falls below 1135 psig. This permissive interlock 
system has been included in the TS to assure its operability. The 
Commission has completed its evaluation of the proposed modifications 
and the associated TS changes and concludes that the modifications and 
TS changes will decrease the possibility of an intersystem loss-of-
coolant-accident (LOCA) without compromising the previously performed 
LOCA analysis. The RPS control cabinets were previously evaluated and 
approved by the NRC. The proposed changes to the RPS TS as result of 
the new interlocks are similar to previous RPS TS analog-to-digital 
changes.
    The proposed TS change will not increase the probability or 
consequences of accidents, no changes are being made in the types of 
any effluents that may be released offsite, and there is no significant 
increase in the allowable individual or cumulative occupational 
radiation exposure. Accordingly, the Commission concludes that there 
are no significant radiological environmental impacts associated with 
this proposed TS amendment.
    With regard to potential nonradiological impacts, the proposed 
amendment does involve features located entirely within the restricted 
area as defined in 10 CFR part 20. It does not affect nonradiological 
plant effluents and has no other environmental impact. Accordingly, the 
Commission concludes that there are no significant nonradiological 
environmental impacts associated with the proposed amendment.

Alternatives to the Proposed Action

    Since the Commission has concluded there is no measurable 
environmental impact associated with the proposed amendment, any 
alternatives with equal or greater environmental impact need not be 
evaluated. The principal alternative to the amendment would be to deny 
the amendment request. Such action would not enhance the protection of 
the environment and would result in unjustified cost to the licensee.

Alternative Use of Resources

    This action does not involve the use of resources not considered 
previously in the Final Environmental Statement for the Haddam Neck 
Plant.

Agencies and Persons Consulted

    The NRC staff consulted with the Connecticut State official 
regarding the environmental impact of the proposed action. The State 
official had no comments.

Finding of No Significant Impact

    Based upon the environmental assessment, the Commission concludes 
that the proposed action will not have a significant effect on the 
quality of the human environment. Accordingly, the Commission has 
determined not to prepare an environmental impact statement for the 
proposed amendment.
    For further details with respect to this proposed action, see the 
licensee's letter dated August 4, 1994, which is available for public 
inspection at the Commission's Public Document Room, the Gelman 
Building, 2120 L Street, NW., Washington, DC, and at the local public 
document room located at the Russell Library, 123 Broad Street, 
Middletown CT 06547.

    Dated at Rockville, Maryland, this 21st day of November 1994.

    For the Nuclear Regulatory Commission.
Phillip F. McKee,
Director, Project Directorate I-4, Division of Reactor Projects--I/II, 
Office of Nuclear Reactor Regulation.
[FR Doc. 94-29484 Filed 11-29-94; 8:45 am]
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