Federal Register / Vol. 60, No. 40 / Wednesday, March 1, 1995 / Notices 11151

are contained in a Safety Evaluation

dated February 14, 1995.

Attorney for licensee: Michael I.

Miller, Esquire; Sidley and Austin, One

First National Plaza, Chicago, Illinois

60690.

Local Public Document Room

location: Public Library of Illinois

Valley Community College, Rural Route

No. 1, Oglesby, Illinois 61348.

NRC Project Director: Robert A. Capra.

Dated at Rockville, Maryland, this 21st day

of February 1995.

For the Nuclear Regulatory Commission.

John N. Hannon,

Acting Director, Division of Reactor Projects—

III/IV, Office of Nuclear Reactor Regulation.

[FR Doc. 95–4870 Filed 2–28–95; 8:45 am]

BILLING CODE 7590–01–P

[Docket Nos. 50–245, 50–336, 50–423]

Northeast Utilities; Issuance of

Director’s Decision Under 10 CFR

2.206

[Millstone Nuclear Power Station]

[License Nos. DPR–21, DPR–65, NPF–49]

Notice is hereby given that the Acting

Director, Office of Enforcement, has

issued a decision concerning the

Petitions filed by Ms. Carmela V. Marien

and Ms. Marianne W. Nericcio on

August 21, 1993. The Petitions

requested that the NRC initiate an

investigation and accelerated

enforcement action against Northeast

Utilities (Licensee) for willful violation

of the employee protection provisions of

10 CFR 50.7.

After due consideration of Petitioner’s

assertions, the Acting Director, Office of

Enforcement, has denied the Petitions.

The reasons for the denial are explained

in the ‘‘Director’s Decision under 10

CFR 2.206’’ (DD–95–04) which is

available for public inspection in the

Commission’s Public Document Room

at 2120 L Street NW., Washington, DC

20555.

A copy of this decision will be filed

with the Secretary for the Commission’s

review in accordance with 10 CFR

2.206. As provided by this regulation,

the decision will constitute the final

action of the Commission 25 days after

the date of issuance of the decision

unless the Commission on its own

motion institutes a review of the

decision within that time.

Dated at Rockville, Maryland this 22nd day

of February 1994.

For the Nuclear Regulatory Commission.

Joseph R. Gray,

Acting Director, Office of Enforcement.

[FR Doc. 95–4978 Filed 2–28–95; 8:45 am]

BILLING CODE 7590–01–M

[Docket No. 50–219]

GPU Nuclear Corporation; Notice of

Issuance of Amendment to Facility

Operating License

The U.S. Nuclear Regulatory

Commission (Commission) has issued

Amendment No. 177 to Facility

Operating License No. NPF–16 issued to

GPU Nuclear Corporation (the licensee),

which revised the Technical

Specifications for operation of the

Oyster Creek Nuclear Generating Station

located in Ocean County, New Jersey.

The amendment is effective as of the

date of issuance, to be implemented

within 60 days of issuance.

The amendment revises Technical

Specification 2.3.D to change the

setpoints ‘‘Reactor High Pressure, Relief

Valve Initiation’’ by increasing the

setpoint value by 15 psig for each of the

Electromatic Relief Valves in the

Automatic Depressurization System.

The application for the amendment

complies with the standards and

requirements of the Atomic Energy Act

of 1954, as amended (the Act), and the

Commission’s rules and regulations.

The Commission has made appropriate

findings as required by the Act and the

Commission’s rules and regulations in

10 CFR Chapter I, which are set forth in

the license amendment.

Notice of Consideration of Issuance of

Amendment and Opportunity for

Hearing in connection with this action

was published in the Federal Register

on July 5, 1994 (59 FR 34453). No

request for a hearing or petition for

leave to intervene was filed following

this notice.

The Commission has prepared an

Environmental Assessment related to

the action and has determined not to

prepare an environmental impact

statement. Based upon the

environmental assessment, the

Commission has concluded that the

issuance of the amendment will not

have a significant effect on the quality

of the human environment (60 FR 9056).

For further details with respects to the

action see (1) The application for

amendment dated June 15, 1994, as

supplemented September 23, and

November 23, 1994, (2) Amendment No.

177 to License No. DPR–16, (3) the

Commission’s related Safety Evaluation,

and (4) the Commission’s

Environmental Assessment. All of these

items are 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 Ocean County Library, Reference

Department, 101 Washington Street,

Toms River, NJ 08753.

Dated at Rockville, Maryland, this 21st day

of February 1995.

For the Nuclear Regulatory Commission.

Alexander W. Dromerick, Sr.

Project Manager, Project Directorate I–4,

Division of Reactor Projects—I/II, Office of

Nuclear Reactor Regulation.

[FR Doc. 95–4977 Filed 2–28–95; 8:45 am]

BILLING CODE 7590–01–M

[Docket No. 50–483]

Union Electric Company;

Consideration of Issuance of

Amendment to Facility Operating

License, Proposed No Significant

Hazards Consideration Determination,

and Opportunity for Hearing

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of an amendment

to Facility Operating License No. NPF–

30, issued to Union Electric Company

(the licensee), for operation of the

Callaway plant, located in Callaway

County, Missouri.

The proposed amendment would

modify Technical Specification (TS)

Section 3/4.9.1 to establish

administrative controls to address a

possible boron dilution event directly

from the reactor makeup water (RMW)

system. An unreviewed safety question

was involved with the use of RMW to

rinse items removed from the refueling

pool and to spray down the refueling

pool walls during the pool drain

evolution. The use of RMW in prior

refueling outages during these Mode 6

activities raised the possibility of a

different type of accident than any

previously evaluated in the Callaway

Final Safety Analysis Report (FSAR).

FSAR Section 15.4.6.2 currently states

that administrative controls during

Mode 6, i.e., closing and locking

dilution source manual valves, preclude

an inadvertent dilution of the boron

concentration of the primary system.

Since these valve closures do not

preclude the potential dilution scenario

described above, different procedural

controls are required to ensure that LCO

3.9.1 boron concentration limit of 2000

ppm is met.

NRC Generic Letter 85–05,

‘‘Inadvertent Boron Dilution Events,’’

January 1985, and NSAC–183, ‘‘Risk of

PWR Inadvertent Criticality During

Shutdown and Refueling,’’ dated

December 1992, documents the

technical justification for determining

that boron dilution events are selflimiting. Based on the analyses

provided in these documents, the staff’s

acceptance criteria remains valid for the

different boron dilution transient (i.e.,

that gradual boron dilution events are