[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]
BILLING CODE 7590-01-M